ML14279A079

Diablo Canyon 2014-08 Draft Operating Test

ML14279A079
Person / Time
Site:	Diablo Canyon
Issue date:	06/20/2014
From:	Vincent Gaddy Operations Branch IV
To:	Pacific Gas & Electric Co
laura hurley
References
50-275/14-OL, 50-323/14-OL
Download: ML14279A079 (402)

Text

N UCLEAR P OWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE M EASURE AUTHOR:L ISAT ORIBIOD ATE:06/20/2014OPERATIONSR EPRESENTATIVE

A BDULK ADIRD ATE:06/20/2014R EV.0 Number: NRCL121-A1 Title: DETERMINE ULTIMATE HEAT SINK TEMPERATURE Examinee: Evaluator: Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments:

References:

STP I-1A, Routine Shift Checks Required by Licenses, Attachment 12.1, Rev. 127 Technical Specifications, DCPP Units 1 & 2 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 2.3, 2.7, 3.4 Job Designation: RO Rev Comments: modified from bank LJACO02R Gen KA / Rating: G2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation. 4.3 Note: This is an admin JPM (RO), intended for the classroom setting.

JPM TITLE: DETERMIN E ULTIMATE HEAT SINK TEMPERATURE JPM NUMBER: NRCL121-A 1 EVALUATOR WORKSHEET Directions:

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

Unit 1 STP I

-1A, MODE 1 Shift Checks, Step 37 (SR 3.7.9.2) Initial Conditions GIVEN: Unit 1 is at 50% power CWP 1-2 out of service for replacement of damaged screens Unit 2 is in day 14 of a refueling outage.

Current plant conditions for the Circ Water and ASW systems are as follows: Component Status Current Ocean Temperature CWP 1-1 In-service TI-311 Out of Calibration CWP 1-2 Cleared TI-328 60.1F ASW Pp 1-1 In-service to CCW HX 1-1 TI-1484 61.4F ASW Pp 1-2 In-STBY TI-1485 60.2F CWP 2-1 Cleared TI-311 60.3F CWP 2-2 Cleared TI-328 60.4F ASW Pp 2-1 In-service to CCW HX 2-1 TI-1484 61.5F ASW Pp 2-2 Cleared TI-1485 60.4 F Initiating Cue: Shift Forman directs you to determine the Ultimate Heat Sink Temperature, using STP I-1A, "Routine Shift Checks Required by Licenses," Attachment 12.1, Step 37.

DO NOT READ TASK STANDARD TO EXAMINEE Task Standard:

Using step 37, determined ocean temperature is 62.1°F and needs to be recorded every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

NRCL121-A1 PAGE 2 OF 5 R EV. 0 JPM TITLE: DETERMIN E ULTIMATE HEAT SINK TEMPERATURE JPM NUMBER: NRCL121-A 1 EVALUATOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure.

1.1 Obtains STP I

-1A, Attachment 12.1.

Sat: ______ Unsat _______

Comment: 2.0B** Determine ocean temperature 2.1 Reads NOTE prior to step 37.a.

2.2 "N/A" checked for step 37.a (Method 1) (TI-311 is Out of Service and CWP 1-2 is not running) 2.3 1BPerformed step 37.b (Method 2), and recorded Pacific Ocean water temperature, 61.4F (TI-1484).**

2.4 2B"N/A" checked for TI-1485, (ASW Pp 1-2 not running).

2.5 3BDetermined

61.4F is the highest available indication. 2.6 4BAdds 0.7 F 2.7 5BRecorded 62.1F as the corrected ocean temperature. **

2.8 Checks "N/A" for step 37.c (Method 3) Sat: ______ Unsat _______

Comment: NRCL121-A1 PAGE 3 OF 5 R EV. 0 JPM TITLE: DETERMIN E ULTIMATE HEAT SINK TEMPERATURE JPM NUMBER: NRCL121-A 1 EVALUATOR WORKSHEET 3. Document monitoring requirements 3.1 Read NOTE prior to step 37.d.

3.2 Checked "N/A" for step 37.d 3.3 Checked step 37.

e.1) t o inform SFM to review SR 3.7.9.2 3.4 Checked step 37.d.2) due to ocean temperature determined to be greater than 62°F but less than 64° F, and that temperatures need to be recorded every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.** 3.5 N/A step 37.f Sat: ______ Unsat _______

Comment:

Stop Time:

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

Follow up Question Documentation

Question: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

Response: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

NRCL121-A1 PAGE 4 OF 5 R EV. 0 69-20232 01/27/14 Page 15 of 26 STP I-1A (UNIT 1) ATTACHMENT 12.1 TITLE: MODE 1 Shift Checklist STP_I-1Au1r27.DOC 06 0515.1508 APPL MODE TECH SPEC

REFERENCE A. CHECK / VERIFICATION FROM CONTROL ROOM PERF 37.Determine the Ultimate Heat Sink (UHS) temperature using one of the following methods:NOTE: Temperature indicators are only available whentheir associated pumps are running.

a.Method 1 - Record Pacific Ocean water temp as readon the following indicators:N/A [ X ] ______ TI-311 (T2400A) (CWP 1-1) _______FN/A [ ] TI-328 (T2401A) (CWP 1-2) _______FN/A [ ] Record the highest of the available indicators. F Instrument Error Correction 1.9 F Add the highest available indicator reading and the Instrument Error Correction. F b.Method 2 - Record Pacific Ocean water temp on thefollowing indicators:N/A [ ] __NRC__ TI-1484 (ASWP 1-1) _61.4__FN/A [ ] TI-1485 (ASWP 1-2) _______FN/A [X ] Record the highest of the available indicators.61.4 F Instrument Error Correction 0.7 F Add the highest available indicator reading and the Instrument Error Correction.62.1°F 1 SR 3.7.9.2 69-20232 01/27/14 Page 16 of 26 STP I-1A (UNIT 1) ATTACHMENT 12.1 TITLE: MODE 1 Shift Checklist STP_I-1Au1r27.DOC 06 0515.1508 APPL MODE TECH SPEC

REFERENCE A. CHECK / VERIFICATION FROM CONTROL ROOM PERF c.Method 3 - If Method 1 and Method 2 are notavailable, M&TE may be used.N/A [X ] ______ Instrument Used: ____________________Cal Due Date: ____________________Reading using M&TE F Uncertainty of M&TE F Add M&TE ocean temp and uncertainty F NOTE: Tech Spec Bases B3.7.9 specifies that the UHS is common to both units. Therefore any required action due to elevated ocean water temp would apply to both units depending on mode requirements. Notify the Unit 2 SFM as required.

d.IF corrected ocean temp is > [60F] AND [62F],THEN perform the following:N/A [ X]

1)Notify SFM to review Tech Spec SR 3.7.9.2.______ 2)Record ocean temp every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

______ e.IF corrected ocean temp is > [62F] AND [64F],THEN perform the following:N/A [ ] 1)Notify SFM to review Tech Spec SR 3.7.9.2.

_NRC_ 2)Record ocean temp every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

_NRC_ f.IF corrected ocean temp is > [64F],THEN place both CCW HXs in service:N/A [ X ] ______ SR 3.7.9.2 (Continued) 1 EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A1 Initial Conditions: GIVEN: Unit 1 is at 50% power CWP 1-2 out of service for replacement of damaged screens Unit 2 is in day 14 of a refueling outage. Current plant conditions for the Circ Water and ASW systems are as follows: Component Status Current Ocean Temperature CWP 1-1 In-service TI-311 Out of Calibration CWP 1-2 Cleared TI-328 60.1F ASW Pp 1-1 In-service to CCW HX 1-1 TI-1484 61.4F ASW Pp 1-2 In-STBY TI-1485 60.2F CWP 2-1 Cleared TI-311 60.3F CWP 2-2 Cleared TI-328 60.4F ASW Pp 2-1 In-service to CCW HX 2-1 TI-1484 61.5F ASW Pp 2-2 Cleared TI-1485 60.4 F Initiating Cue: Shift Forman directs you to determine the Ultimate Heat Sink Temperature, using STP I-1A, "Routine Shift Checks Required by Licenses," Attachment 12.1, Step 37.

NRCL121-A1 PAGE 5 OF 5 R EV. 0 69-20232 01/27/14 Page 15 of 26 STP I-1A (UNIT 1) ATTACHMENT 12.1 TITLE: MODE 1 Shift Checklist STP_I-1Au1r27.DOC 06 0515.1508 APPL MODE TECH SPEC

REFERENCE A. CHECK / VERIFICATION FROM CONTROL ROOM PERF 37.Determine the Ultimate Heat Sink (UHS) temperatur e using one of the following me thods: NOTE: Te mperature indicators are only available whentheir associated pumps are running.a.Method 1 - Record Pacific Ocean water temp as readon the following in dicators: N/A [ ] ______ TI-311 (T2400A) (CWP 1-1) _______ FN/A [ ] TI-328 (T2401A) (CWP 1-2) _______ FN/A [ ] Record the highest of the available indicators. F Instrument Error Correction 1.9 F Add the highest available i ndicator reading and the Instrument Error Correction. F b.Method 2 - Record Pacific Ocean water temp on thefollowing indi cators: N/A [ ] ______ TI-1484 (ASWP 1-1) _______F N/A [ ] TI-1485 (ASWP 1-2) _______F N/A [ ] Record the highest of the available indicators. F Instrument Error Correction 0.7 F Add the highest available i ndicator reading and the Instrument Error Correction.

°F 1 SR 3.7.9.2 69-20232 01/27/14 Page 16 of 26 STP I-1A (UNIT 1) ATTACHMENT 12.1 TITLE: MODE 1 Shift Checklist STP_I-1Au1r27.DOC 06 0515.1508 APPL MODE TECH SPEC

REFERENCE A. CHECK / VERIFICATION FROM CONTROL ROOM PERF c.Method 3 - If Method 1 and Method 2 ar e notavailable, M&TE may be used.N/A [ ] ______ Instrument Used: ____________________Cal Due Date: ____________________ Reading usin g M&TE F Uncertainty of M&TE F Add M&TE ocean temp a nd uncertainty F NOTE: Tech Spec Bases B3.7.9 specifies that the UHS is common to both units. Therefore any required action due to elevated ocean water temp would apply to both units depending on mode requirements. Notify the Unit 2 SFM as required.

d.IF corrected ocean temp is > [60F] AND [62 F],THEN perform the followi ng: N/A [ ] 1)Notify SFM to review Tech Spec SR 3.7.9.2.______ 2)Record ocean temp every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

______ e.IF corrected ocean temp is > [62F] AND [64 F],THEN perform the followi ng: N/A [ ] 1)Notify SFM to review Tech Spec SR 3.7.9.2.______ 2)Record ocean temp every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.______ f.IF corrected ocean temp is > [64 F],THEN place both CCW HXs in service:N/A [ ] ______ SR 3.7.9.2 (Continued) 1 NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: LJACO-02R Title: DETERMINE ULTIMATE HEAT SINK TEMPERATURE Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Rev 4A an EC was performed to change to current rev and step of I-1A approved by the ILT supervisor. Also changed ASW to 61.5 degrees per TIP 20048 act 16.

References:

STP I-1A, Routine Shift Checks Required by Licenses, Attachment 12.1, Step 37 (SR 3.7.9.2), Rev. 121 Technical Specifications, DCPP Units 1 &

2 Alternate Path:

Yes X No Time Critical:

Yes No X Time Allotment:

10 Minutes Critical Steps:

2, 3 Job Designation:

RO Task Number:

G2.1.23 Rating: 4.3 AUTHOR: DAVID RICHARDS / CHARLES HIBBARD DATE: 05/04/11 REVIEWED B Y: JOHN P. LYLE DATE: 05/04/11 TRAINING SUPERVISOR APPROVED B Y: KEN JOHNSTON DATE: 05/05/11 MANAGER - OPERATIONS R EV. 4A JPM TITLE: DETERMINE ULTIMATE HEAT SINK TEMPERATURE JPM NUMBER: LJACO-02R INSTRUCTOR WORKSHEET Directions:

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

STP I-1A, MODE 1 Shift Checks, Step 37 (SR 3.7.9.2) Initial Conditions:

Unit 1 is at 50% power with CWP 1-2 out of service for replacement of damaged screens. Unit 2 is in day 14 of a refueling outage. Current plant conditions for the Circ Water and ASW systems are as follows: Component Status Current Ocean Water Temperature CWP 1-1 In-service TI-311 61F CWP 1-2 Cleared TI-328 61F ASW Pp 1-1 In-service to CCW HX 1-1 TI-1484 61.5F ASW Pp 1-2 In-STBY TI-1485 60F CWP 2-1 Cleared TI-311 61F CWP 2-2 Cleared TI-328 61F ASW Pp 2-1 In-service to CCW HX 2-1 TI-1484 61.5F ASW Pp 2-2 Cleared TI-1485 61F Initiating Cu e: Shift Forman directs you to determine the Ultimate Heat Sink Temperature, using STP I-1A, "Routine Shift Checks Required by Licenses," Attachment 12.1, Step 37.

DO NOT READ TASK STANDARD TO EXAMINEE Task Standard:

Ultimate Heat Sink temperature is determined based on given information and Shift Foreman informed of results.

DOCCONTENT.dll PAGE 2 OF 5 R EV. 4A JPM TITLE: DETERMINE ULTIMATE HEAT SINK TEMPERATURE JPM NUMBER: LJACO-02R INSTRUCTOR WORKSHEET Start Time: StepExpected Operator Actions

1. Obtains correct procedure.

1.1 Obtains STP I-1A, Attachment 12.1. Note: Provide exam copy of STP I-1A, Attachment 12.1, Step 3 7. Step was: Sat: _______ Unsat _______*

2. **Determines UHS temperature using method 1.

2.1 Reads NOTE prior to step 37.a. 2.2 Records the Pacific Ocean water temperature , 61F on TI-311.** 2.3 Checks "N/A" for TI-328, since CWP 1-2 is not running.

2.4 Determines that 61F is the highest available indication, and writes that value on the data sheet.

• • 2.5 Adds 1.9F, and writes 62.9F as the corrected ocean temperature.

Initials step 37.a.** 2.6 Checks "N/A" for methods 2 and 3. Step was: Sat: _______ Unsat _______*

• Denotes an entry required on the JPM cover sheet. **Denotes a Critical Step.

DOCCONTENT.dll PAGE 3 OF 5 R EV. 4A JPM TITLE: DETERMINE ULTIMATE HEAT SINK TEMPERATURE JPM NUMBER: LJACO-02R INSTRUCTOR WORKSHEET StepExpected Operator Actions

3. **Performs steps 33.d and e.

3.1 Reads NOTE prior to step 37.d.

3.2 Informs the Unit 1 SFM that the corrected ocean temperature is greater than the Tech Spec limit of 62F, and that temperatures need to be recorded every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Initials step d.** Note: Unit 2 SFM does not need to be informed since Unit 2 is in a refueling outage (not in Modes 1

-4). 3.3 Checks "N/A" for step 37.e. 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.

DOCCONTENT.dll PAGE 4 OF 5 R EV. 4A EXAMINEE CUE SHEET JPM NUMBER: LJACO-02R Initial Conditions:

Unit 1 is at 50% power with CWP 1-2 out of service for replacement of damaged screens. Unit 2 is in day 14 of a refueling outage. Current plant conditions for the Circ Water and ASW systems are as follows: Component Status Current Ocean Water Temperature CWP 1-1 In-service TI-311 61F CWP 1-2 Cleared TI-328 61F ASW Pp 1-1 In-service to CCW HX 1-1 TI-1484 61.5F ASW Pp 1-2 In-STBY TI-1485 60F CWP 2-1 Cleared TI-311 61F CWP 2-2 Cleared TI-328 61F ASW Pp 2-1 In-service to CCW HX 2-1 TI-1484 61.5F ASW Pp 2-2 Cleared TI-1485 61F Initiating Cue:

Shift Forman directs you to determine the Ultimate Heat Sink Temperature, using STP I-1A, "Routine Shift Checks Required by Licenses," Attachment 12.1, Step 33.

DOCCONTENT.dll PAGE 5 OF 5 R EV. 4A N UCLEAR P OWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE M EASURE AUTHOR:L ISAT ORIBIOD ATE:06/20/2014OPERATIONSR EPRESENTATIVE

A BDULK ADIRD ATE:06/20/2014R EV.0 Number: NRCL121-A2 Title: DETERMINE DILUTION REQUIREMENTS TO RAISE POWER Examinee: Evaluator: Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments:

References:

DCPP Unit 2 Cycle 18 Reactivity Briefing Sheet (263 to 310 EFPD) Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 2.2, 3.3, 4.1, 5.1 Job Designation:

RO or SRO Rev Comments: modified from L081 NRC ADMRO1 Gen KA / Rating: G2.1.25 - Conduct of Operations 3.9 Note: This is an admin JPM (RO), intended for the classroom setting.

JPM TITLE: DETERMINE DILUTION REQUIREMENTS TO RAISE POWER JPM NUMBER: NRCL121-A2 EVALUATOR WORKSHEET Directions:

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

Calculator, Reactivity Briefing Sheet from the Reactivity Handbook Initial Conditions Given: Unit 2 was ramped down due to high vibration on the main turbine.

Unit 2 has been at 80% power for 3 days.

Control Bank D is at 200 steps Initiating Cue:

The Shift Foreman directs you to determine the dilution or boration requirements to raise power to 90% assuming final rod position of 210 steps using the data from the Reactivity Briefing Sheet (from Reactivity Handbook)

DO NOT READ TASK STANDARD TO EXAMINEE Task Standard:

Determined that 928 (+/

- 5 ) gallons of primary water is required for the 10% power increase.

NRCL121-A2 PAGE 2 OF 5 R EV. 0 JPM TITLE: DETERMINE DILUTION REQUIREMENTS TO RAISE POWER JPM NUMBER: NRCL121-A2 EVALUATOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure.

1.1 **********************************

Cue: Provide examinee with reactivity briefing sheet, if not already done.

Sat: ______ Unsat _______

Comment: 2.0B** Calculate reactivity change for 10% change in power 2.1 From graph power coefficient is

-15.47 pcm/% power.

2.2 Record e d (-)154.7 pcm for 10% increase in power.

• • Sat: ______ Unsat _______

Comment: 3.1B** Calculate reactivity change due to change in rod position 3.1 Recorded 45.9 pcm for Control Bank D at 210 steps.

(From graph, A. Control Bank D Integral Rod Worth) 3.2 Recorded 9 8.1 pcm for Control Bank D at 2 00 steps.

(From graph, A. Control Bank D Integral Rod Worth) 3.3 Recorded (+)52.2 pcm for change in rod position.

• • (98.1 - 45.9 ) Sat: ______ Unsat _______

Comment: NRCL121-A2 PAGE 3 OF 5 R EV. 0 JPM TITLE: DETERMINE DILUTION REQUIREMENTS TO RAISE POWER JPM NUMBER: NRCL121-A2 EVALUATOR WORKSHEET 4.2B** Calculate reactivity left after accounting change in rod position.

4.1 Recorded (-)102.5 pcm

)reactivity from change in rods position on total reactivity from change in power.

• • (-154.7 + 52.2) Sat: ______ Unsat _______

Comment: 5.3B** Determines amount of primary water to add Note: The examinee may set up a ratio to get the primary water needed, or may do two steps (determine power change needing dilution, and then dilution for that power change).

5.1 Determined 928 (+/- 5 ) gallons of primary water is required.

(102.5 pcm/15.47 pcm/% = 6.63 % pwr) (6.63% x 140 gal/% =

928 gallons (+/- 5 gallons) ** Note: The critical "part" of the above step is the dilution gallons, as the data can be manipulated several different ways in one or more steps to arrive at the right answer. Sat: ______ Unsat _______

Comment: Stop Time:

Total Time:

(Enter total time on the cover page)

Follow up Question Documentation

Question: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

Response: ___________________________________________________________________

______________________________________________________________________________

NRCL121-A2 PAGE 4 OF 5 R EV. 0 EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A2 Initial Conditions:

Given: Unit 2 was ramped down due to high vibration on the main turbine.

Unit 2 has been at 80% power for 3 days.

Control Bank D is at 200 steps Initiating Cue: The Shift Foreman directs you to determine the dilution or boration requirements to raise power to 90% assuming final rod position of 210 steps using the data from the Reactivity Briefing Sheet (from Reactivity Handbook)

Answer (show work)

NRCL121-A2 PAGE 5 OF 5 R EV. 0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL081LJA_ROA1 Title: DETERMINE DILUTION REQUIREMENTS FOR A POWER INCREASE Examinee:

Evaluator:

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

References:

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

Yes No X Time Critical:

Yes No X Time Allotment:

15 Minutes Critical Steps:

2-6 Job Designation:

RO Task Number:

G2.1.25 Rating: 3.9 JOHN P. LYLE E D HURST AUTHOR: GARY HUTCHISON DATE: 12/10/09 R EV. 1 JPM TITLE: DETERMINE DILUTION REQUIREMENT S FOR A POWER INCREASE JPM NUMBER: NRCL081LJA_ROA1 INSTRUCTOR WORKSHEET Directions:

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

Calculator, Reactivity Briefing Sheet Initial Conditions:

Unit 1 was ramped down due to problems with Govenor valve 4. Unit 1 has been at 90% power for 3 days with Control Bank D at 200 steps. Initiating Cue:

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

Operator determines that 230 (+/- 5 ) gallons of primary water is required. NRCL081LJA_ROA1 rev 1.doc PAGE 2 OF 6 R EV. 1 JPM TITLE: DETERMINE DILUTION REQUIREMENT S FOR A POWER INCREASE JPM NUMBER: NRCL081LJA_ROA1 INSTRUCTOR WORKSHEET Start Time: StepExpected 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 _______*

• Denotes an entry required on the JPM cover sheet. **Denotes a Critical Step.

NRCL081LJA_ROA1 rev 1.doc PAGE 3 OF 6 R EV. 1 JPM TITLE: DETERMINE DILUTION REQUIREMENT S FOR A POWER INCREASE JPM NUMBER: NRCL081LJA_ROA1 INSTRUCTOR WORKSHEET StepExpected 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 (+/- 5 ) 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)*Denotes an entry required on the JPM cover sheet. **Denotes a Critical Step.

NRCL081LJA_ROA1 rev 1.doc PAGE 4 OF 6 R EV. 1 JPM TITLE: DETERMINE DILUTION REQUIREMENT S FOR A POWER INCREASE JPM NUMBER: NRCL081LJA_ROA1 ANSWER K EY Initial Conditions:

Unit 1 was ramped down due to problems with Govenor valve 4. Unit 1 has been at 90% power for 3 days with Control Bank D at 200 steps Initiating Cue:

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

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

NRCL081LJA_ROA1 rev 1.doc PAGE 5 OF 6 R EV. 1 EXAMINEE CUE SHEET JPM NUMBER: NRCL081LJA_ROA1 Initial Conditions:

Unit 1 was ramped down due to problems with Govenor valve 14 . Reactor power is now stabilized at approximately 90% with Control Bank D at 200 steps Initiating Cue:

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

NRCL081LJA_ROA1 rev 1.doc PAGE 6 OF 6 R EV. 1 NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-A 3 Title: PERFORM OUTAGE SAFETY CHECKLIST Examinee: Evaluator:

Print Signature Date Testing Method:

Perform X Simulate Results: Sat Unsat Total Time:

minutes Comments:

References:

AD8.DC55, Outage Safety Scheduling, Attachment 4, pg. 6, Rev. 38 Alternate Path:

Yes No X Time Critical:

Yes No X Time Allotment:

10 minutes Critical Steps:

2.1, 2.2, (3 or 4 & 5) 6, 7, 8 Job Designation:

RO Rev Comments:

Bank: LJAEC

-01R ; previously used in L061C NRC ADM02 Gen KA / Rating:

G 2.2.37 - Ability to determine operability and/or availability of safety related equipment 3.6 Note: This is an admin JPM (RO), intended for the classroom setting.

AUTHOR: LISA TORIBIO/ DATE: OPERATIONS REPRESENTATIVE

ABDUL KADIR/ DATE: R EV. 0 JPM TITLE: PERFORM OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A 3 EVALUATOR WORKSHEET Directions:

No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the

evaluator. The student will be given the initial conditions and initiating cue. The examiner will then ask if any clarifications are needed. The examinee may be given the procedure and told the step with which to begin. Required Materials:

AD8.DC55, Outage Safety Scheduling, Attachment 4, pg. 6, Rev. 38 Technical Specifications (available)

NRCL121-A 3 PAGE 2 OF 9 R EV. 0 JPM TITLE: PERFORM OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A 3 EVALUATOR WORKSHEET Initial Conditions Unit 1 is currently in MODE 6 with Core reload in progress.

Current plant parameters are as follows:

Operable Cleared Offsite power sources Startup power X Aux power X Onsite power sources Diesel Generator 1 X Diesel Generator 2 X Diesel Generator 3 X Vital bus crosstie 4kV & 480v Bus F X 4kV & 480v Bus G X 4kV & 480v Bus H X Onsite distribution sys.

4kV & 480v Bus F X 4kV & 480v Bus G X 4kV & 480v Bus H X Instrument AC Panels PY-11 X PY-11A X PY-12 X PY-13 X PY-13A X PY-14 X Vital DC Power DC Bus 1-1 X DC Bus 1-2 X DC Bus 1-3 X Refueling cavity level 23.4 Feet Initiating Cue:

The Shift Foreman directs you to perform the AD8.DC55, "Outage Safety Scheduling," Att 4, page 6, Mode 6 Outage Safety Checklist for the current plant conditions DO NOT READ TASK STANDARD TO EXAMINEE Task Standard:

Correctly completes AD8.DC55, Att 4, page 6, Mode 6 Outage Safety Checklist for VITAL AC POWER

. NRCL121-A 3 PAGE 3 OF 9 R EV. 0 JPM TITLE: PERFORM OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A 3 EVALUATOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure.

Note: Provide exam copy of AD8.DC55, Att 4, page 6 (page 9 of this JPM). **********************************

Sat: ______ Unsat _______

Comment: 2.0B** Determines status of power to operable vital buses

. 2.1 Determines S/U Power is operable and marks the appropriate "boxes" on Att 4, page 6. **

2.2 Determines that a D/G is operable for 4kV vital bus F (D/G 1

-3) and G (D/G 1

-2) and marks the appropriate "boxes" on Att 4, page 6. **

Sat: ______ Unsat _______

Comment: 3.1B** Determines onsite power supply operability

. Note: Examinee may complete either step 3 (page 7) or both steps 4 and 5 (page 8 of this JPM).

3.1 Determines that D/G 1

-2 and 1-3 are operable and marks the appropriate "boxes" on Att 4, page 6. **

Sat: ______ Unsat _______

Comment: NRCL121-A 3 PAGE 4 OF 9 R EV. 0 JPM TITLE: PERFORM OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A 3 EVALUATOR WORKSHEET Step Expected Operator Actions 4.2B** Determines status of refueling cavity

. 4.1 Determines that refueling cavity level is 23.4 feet ( 23 feet above the vessel flange) and the upper internals are removed (i.e., core onload is in progress) and marks the appropriate "boxes" on Att 4, page 6.

• • 4.2 Determines that S/U power is operable and marks the appropriate "boxes" on Att 4, page 6. Sat: ______ Unsat _______

Comment: 5.3B** Determines Diesel Generator (D/G) Operability 5.1 Determines that one D/G is operable (either D/G 1

-2 or 1-3) and marks appropriate "boxes" on Att 4, page 6.**

5.2 Determines that a different D/G (either D/G 1-3 or 1-2) is either operable or available and marks appropriate "boxes" on Att 4, page 6. **

Sat: ______ Unsat _______

Comment: 6.4B** Determines TS required 4kV and 480V bus operability 6.1 Determines that 4 kV buses F and G, as well as 480V buses F and G, are operable and marks appropriate "boxes" on Att 4, page 6. **

Sat: ______ Unsat _______

Comment: NRCL121-A 3 PAGE 5 OF 9 R EV. 0 JPM TITLE: PERFORM OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A 3 EVALUATOR WORKSHEET Step Expected Operator Actions 7.5B** Determines status of Instrument AC Power Panels. 7.1 Determines that all vital instrument AC power panels are operable and marks appropriate "boxes" on Att 4, page 6. **

Sat: ______ Unsat _______

Comment: 8.6B** Determines status of Vital DC Power 8.1 Determines that all vital DC buses are operable and marks appropriate "boxes" on Att 4, page 6. **

Sat: ______ Unsat _______

Comment: Stop Time:

Total Time:

(Enter total time on the cover page)

Follow up Question Documentation

Question: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

Response: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

NRCL121-A 3 PAGE 6 OF 9 R EV. 0 JPM TITLE: PERFORM OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A 3 EVALUATOR WORKSHEET NRCL121-A 3 PAGE 7 OF 9 R EV. 0 JPM TITLE: PERFORM OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A 3 EVALUATOR WORKSHEET NRCL121-A 3 PAGE 8 OF 9 R EV. 0 E XAMINEE C UE S HEET JPM N UMBER: NRCL121-A3 NRCL121-A3 PAGE 9 OF 9 R EV. 0 Initial Conditions:

Unit 1 is currently in MODE 6 with Core reload in progress. Current plant parameters are as follows:

Operable Cleared Offsite power sources Startup power X Aux power X Onsite power sources Diesel Generator 1 X Diesel Generator 2 X Diesel Generator 3 X Vital bus crosstie 4kV & 480v Bus F X 4kV & 480v Bus G X 4kV & 480v Bus H X Onsite distribution sys. 4kV & 480v Bus F X 4kV & 480v Bus G X 4kV & 480v Bus H X Instrument AC Panels PY-11 X PY-11A X PY-12 X PY-13 X PY-13A X PY-14 X Vital DC Power DC Bus 1-1 X DC Bus 1-2 X DC Bus 1-3 X Refueling cavity level 23.4 Feet Initiating Cue: The Shift Foreman directs you to perform the AD8.DC55, "Outage Safety Scheduling," Att 4, page 6, Mode 6 Outage Safety Checklist for the current plant conditions

Unit 1 Outage Safety Checklist - Mode 6 RCS Level Greater Than or Equal to 111' AD8.DC55 R38 Page 35 of 66 Attachment 4: Page 6 of 7

AD8!DC55u3r38.DOC 1126.1027

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(!-4) 4)4))) 5#$/!&! ,678,7~# 9,678,7~# ,678,7~# :;;);;;);,~# ~# ~#  !$!7~#

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)$E0 (0-NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: LJ A EC-01R Title: PERFORM OUTAGE SAFETY CHECKLIST Examinee:

Evaluator:

Print Signature Date Testing Method:

Perform Simulate Results: Sat Unsat Total Time: minutes Comments: (Note: Any Unsat step requires a numbered comment; use back as needed.)

Page 7 contains a completed copy of AD8.DC55 Att 4, page 6 which is the examiner's key.

Page 8 contains an exam copy of AD8.DC55 Att 4, page 6 for the examinee to complete.

Rev 5A changes AD8.DC55 to current rev approved by ILT Supervisor.

References:

AD8.DC55, Outage Safety Scheduling, Attachment 7.4, Rev. 36 Alternate Path:

Yes No X Time Critical:

Yes No X Time Allotment

10 minutes Critical Steps:

2, 3, 6, 7 (or 2, 4, 5, 6, 7)

Job Designation:

RO Rev Comments/TIPs:

This JPM was rewritten; therefore, no revision bars were used. Incorporated TIP 19743-29. DCPP Task # / Rating: NA NA Gen KA # / Rating

G2.2.37 3.6 AUTHOR: D AVE RICHARDS / CHARLES HIBBARD DATE: 04/28/11 REVIEWED B Y: JOHN P. LYLE DATE: 04/28/11 TRAINING SUPERVISOR APPROVED B Y: ERIK WERNER DATE: 04/28/11 LINE MANAGER R EV. 5A JPM TITLE: PERFORM OUTAGE SAFETY CHECKLIST JPM NUMBER: LJ A EC-01R INSTRUCTOR WORKSHEET Directions:

No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.

The examiner will then ask if any clarifications are needed. If the task is being done in the plant or lab, and after identifying the appropriate procedure for the task, the examinee may be given the procedure and told what step to begin the task at. Required Materials:

Make a copy of Technical Specifications available for reference.

Initial Conditions:

Unit 1 is currently in Mode 6 with Core onload in progress. Current plant parameters are as follows:

Cleared Available Operable Offsite power sources Startup power X NA Aux power NA X Onsite power sources Diesel Generator 1 X Diesel Generator 2 X Diesel Generator 3 X Vital bus crosstie 4kV & 480v Bus F X NA 4kV & 480v Bus G X NA 4kV & 480v Bus H NA X Onsite distribution sys.

4kV & 480v Bus F X NA 4kV & 480v Bus G X NA 4kV & 480v Bus H NA X Instrument AC Panels PY-11 X NA PY-11A X NA PY-12 X NA PY-13 X NA PY-13A X NA PY-14 X NA Refueling cavity level 23.4 Feet Initiating Cue:

The Shift Foreman directs you to perform the AD8.DC55, "Outage Safety Scheduling," Att 4, page 6, Mode 6 Outage Safety Checklist for VITAL AC POWER ONLY, for the current plant conditions.

DOCCONTENT

.DLL PAGE 2 OF 9 R EV. 5A JPM TITLE: PERFORM OUTAGE SAFETY CHECKLIST JPM NUMBER: LJ A EC-01R INSTRUCTOR WORKSHEET NOTE: Do NOT provide the student with the Task Standard.

Task Standard:

Correctly completes AD8.DC55, Att 4, page 6, Mode 6 Outage Safety Checklist for VITAL AC POWER.

• Denotes an entry required on the JPM cover sheet. ** Denotes Critical Step and Sub Steps. DOCCONTENT

.DLL PAGE 3 OF 9 R EV. 5A JPM TITLE: PERFORM OUTAGE SAFETY CHECKLIST JPM NUMBER: LJ A EC-01R INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtains the correct procedure. 1.1 Obtains AD8.DC55, Att 4, page 6, Mode 6 Outage Safety Checklist for VITAL AC POWER. Note: Provide exam copy of AD8.DC55, Att 4, page 6

, on page 8 of this JPM

. Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

• • 2. Determines status of power to operable vital buses.

2.1 Determines S/U Power is operable and marks the appropriate "boxes" on Att 4, page 6.

• • 2.2 Determines that a D/G is available for 4kV vital bus F (D/G 1

-3) and G (D/G 1-2) and marks the appropriate "boxes" on Att 4, page 6. ** Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

Note: Examinee may complete either step 3 or both steps 4 and 5 (see logic in Att 4, page 6

). Note: Examiner's key on page 7 shows completion of steps 2, 3, 6, and 7.

• • 3. Determines onsite power supply operability.

3.1 Determines that D/G 1-2 and 1-3 are operable and marks the appropriate "boxes" on Att 4, page 6. ** Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

• Denotes an entry required on the JPM cover sheet. ** Denotes Critical Step and Sub Steps. DOCCONTENT

.DLL PAGE 4 OF 9 R EV. 5A JPM TITLE: PERFORM OUTAGE SAFETY CHECKLIST JPM NUMBER: LJ A EC-01R INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 4. Determines status of refueling cavity. Note: Examinee may complete either step 4.1 or step 4.2 (see logic in Att 4, pag e 6). 4.1 Determines that refueling cavity level is 23.4 feet ( 23 feet above the vessel flange) and the upper internals are removed (i.e., core onload is in progress) and marks the appropriate "boxes" on Att 4, page 6. ** 4.2 Determines that S/U power is operable and marks the appropriate "boxes" on Att 4, page 6. ** Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

• • 5. Determines D/G operability. 5.1 Determines that one D/G is operable (either D/G 1-2 or 1-3) and marks appropriate "boxes" on Att 4, page 6.

5.2 Determines that a different D/G (either D/G 1-3 or 1-2) is either operable or available and marks appropriate "boxes" on Att 4, page 6. Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

• Denotes an entry required on the JPM cover sheet. ** Denotes Critical Step and Sub Steps. DOCCONTENT

.DLL PAGE 5 OF 9 R EV. 5A JPM TITLE: PERFORM OUTAGE SAFETY CHECKLIST JPM NUMBER: LJ A EC-01R INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 6. Determines TS required 4kV and 480V bus operability.

6.1 Determines that 4 kV buses F and G, as well as 480V buses F and G, are operable and marks appropriate "boxes" on Att 4, page 6. ** Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

Note: The boxes at the bottom of the right hand column of Att 4, page 6 are a continuation of the boxes at the bottom of the left hand column.

Note: Tech Spec 3.8.2 says that only one of these vital buses is required to be operable in Mode 6.

Note: If requested, provide access to Tech Specs. ** 7. Determines status of Instrument AC Power Panels. 7.1 Determines that all vital instrument AC power panels are operable and marks appropriate "boxes" on Att 4, page 6. ** Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

Stop Time:

Total Time:

(Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet. ** Denotes Critical Step and Sub Steps. DOCCONTENT

.DLL PAGE 6 OF 9 R EV. 5A KEY (Steps 2, 3, 6, and 7) x x x x x x x x x x x x x x x x x x DOCCONTENT

.DLL PAGE 7 OF 9 R EV. 5A DOCCONTENT

.DLL PAGE 8 OF 9 R EV. 5A JPM NUMBER: LJ A EC-01R EXAMINEE CUE SHEET Initial Conditions:

Unit 1 is currently in Mode 6 with Core onload in progress. Current plant parameters are as follows:

Cleared Available Operable Offsite power sources Startup power X NA Aux power NA X Onsite power sources Diesel Generator 1 X Diesel Generator 2 X Diesel Generator 3 X Vital bus crosstie 4kV & 480v Bus F X NA 4kV & 480v Bus G X NA 4kV & 480v Bus H NA X Onsite distribution sys.

4kV & 480v Bus F X NA 4kV & 480v Bus G X NA 4kV & 480v Bus H NA X Instrument AC Panels PY-11 X NA PY-11A X NA PY-12 X NA PY-13 X NA PY-13A X NA PY-14 X NA Refueling cavity level 23.4 Feet Initiating Cue:

The Shift Foreman directs you to perform the AD8.DC55, "Outage Safety Scheduling," Att 4, page 6, Mode 6 Outage Safety Checklist for VITAL AC POWER ONLY, for the current plant conditions.

DOCCONTENT

.DLL PAGE 9 OF 9 R EV. 5A N UCLEAR P OWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE M EASURE AUTHOR:L ISAT ORIBIO/D ATE:OPERATIONSR EPRESENTATIVE

A BDULK ADIR/D ATE:R EV.0 Number: NRCL121-A4 Title: REVIEW LIQUID RADWASTE DISCHARGE CHECKLIST Examinee: Evaluator: Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments:

References:

OP G-1:II, Liquid Radwaste System - Discharge of Liquid Radwaste, Rev. 37A CAP A-5, Liquid Radwaste Discharge Management, Rev. 48 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Step(s):

6 Job Designation: RO Rev Comments: modified from L061C NRC ADM04 Gen KA / Rating: 2.3.11 Ability to control radiation releases 3.8

Note: This is an admin JPM (RO), intended for the classroom setting.

JPM TITLE: REVIEW LIQUID RADWASTE DISCHARGE CHECKLI ST JPM NUMBER: NRCL121-A 4 EVALUATOR WORKSHEET Directions:

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

OP G-1:II, Liquid Radwaste System

- Discharge of Liquid Radwaste, Rev.37A Partially completed Section 12 CAP A-5 Completed Attachment 11.1 Parts 1 & 2 Initial Conditions Chemistry has issued a discharge permit for PWR 0

-2 using CAP A

-5 Att. 11.1 parts 1 & 2. OP G

-1:II Section 12 has been partially completed. CCW HX 1

-1 is in service, and both Units are at 100% power Initiating Cue:

Review OP G

-1:II Section 12 Discharge Checklists for accuracy and completeness thru step 12.10. Document any discrepancies noted DO NOT READ TASK STANDARD TO EXAMINEE Task Standard:

1 Technical error identified

Section 12 page 2 (of 8), CCW HX 1

-1 is designated to be used for the release (initial condition), but alignment has been performed for CCW HX 1-2 (SW-1-6 8 is open when SW 6 7 should be open

) NRCL121-A 4 PAGE 2 OF 5 R EV. 0 JPM TITLE: REVIEW LIQUID RADWASTE DISCHARGE CHECKLI ST JPM NUMBER: NRCL121-A 4 EVALUATOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Review step 12.1

- Parts 1 and 2 of discharge permit complete and signed by Chemistry 1.1 Review e d Parts 1 and 2 of CAP A

-5, Attachment 11.1 and determine d parts 1 & 2 are complete and signed by Chemistry Sat: ______ Unsat _______

Comment: 2. Review step 12.2 - Appropriate tank identifie d 2.1 Identifie d that PWR 0

-2 has been correctly circled for discharge Sat: ______ Unsat _______

Comment:

3. Review steps 12.3 (RE-18 adjustment)

& 12.4 (FIT-243 not operable actions) 3.1 Identifie d that RE-18 setpoint doesn't require adjustment 3.2 Identified FIT

-243 is OPERABLE Sat: ______ Unsat _______

Comment: 4. Review step 12.5 - Discharge flowpath aligned to inservice U1 CCW heat exchanger identifie d 4.1 Identified that LWS 436 to U1 CCW , marked as OPEN 4.2 Identified that LWS 43 9 to U 2 CCW , marked as CLOSED Sat: ______ Unsat _______

Comment: NRCL121-A 4 PAGE 3 OF 5 R EV. 0 JPM TITLE: REVIEW LIQUID RADWASTE DISCHARGE CHECKLI ST JPM NUMBER: NRCL121-A 4 EVALUATOR WORKSHEET Step Expected Operator Actions

5. Review steps 12.6 thru 12.9

- valves closed 5.1 Identified that steps 12.6 through 12.9 signed as completed Sat: ______ Unsat _______

Comment: 6.** Review step 12.10

- ASW checklist 6.1 Identified CCW HX 11 should be circled to be used, but that valve alignment was incorrectly done for CCW HX 12. **

Sat: ______ Unsat _______

Comment: Stop Time:

Total Time:

(Enter total time on the cover page)

Follow up Question Documentation

Question: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

Response: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

NRCL121-A 4 PAGE 4 OF 5 R EV. 0 EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A 4 Initial Conditions:

Chemistry has issued a discharge permit for PWR 0

-2 using CAP A

-5 Att. 11.1 parts 1 & 2. OP G

-1:II Section 12 has been partially completed. CCW HX 1

-1 is in service, and both Units are at 100% power Initiating Cue: Review OP G

-1:II Section 12 Discharge Checklists for accuracy and completeness thru step 12.10. Document any discrepancies noted NRCL121-A 4 PAGE 5 OF 5 R EV. 0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCADM061C-A4 Title: Review Liquid Radwaste Discharge Checklist.

Examinee:

Evaluator:

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

g.

References:

OP G-1: II , Liquid Radwaste System - Discharge of Liquid Radwaste, Rev. 35A CAP A-5, Liquid Radwaste Discharge Management, Rev. 41A Alternate Path:

Yes X No Time Critical:

Yes No X Time Allotment:

20 minutes Critical Steps: 4 Job Designation:

S RO K/A: G 2.3.6; Ability to approve release permits.

Rating: 3.8 AUTHOR: GARY HUTCHISON DATE: 08/12/2008 R EV. 1 JPM TITLE: REVIEW LIQUID RADWASTE DISCHARGE CHECKLIST JPM NUMBER: NRCADM 061C-A4 INSTRUCTOR WORKSHEET Directions:

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

OP G-1:II, Liquid Radwaste System - Discharge of Liquid Radwaste, Rev. 35A Completed Attachments 9.1 & 9.5 CAP A-5 Completed Attachment 11.1 Parts 1 & 2. Initial Conditions:

Chemistry has issued a discharge permit for PWR 0-1 using CAP A-5 Att. 11.1 parts 1 & 2. OP G-1:II Attachments 9.1 & 9.5 have been completed. Initiating Cue:

As the Unit 1 Shift Foreman, review OP G-1:II Attachments 9.1 & 9.5 Discharge Checklists for accuracy and completeness. Document any discrepancies noted and determine if the discharge checklist should be approved or not approved based on your review. Task Standard:

2 Technical errors were identified:

Attachment 9.1 page 2, CCW HX 1-2 is circled to be used for the release, but SW-1-67 is opened when SW-1-68 should be opened PWR 0-2 has been aligned for discharge instead of PWR 0-1 Discharge authorization was not approved. NRCADM061C

-A4.DOC Page 2 of 6 R EV. 1 JPM TITLE: REVIEW LIQUID RADWASTE DISCHARGE CHECKLIST JPM NUMBER: NRCADM 061C-A4 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Review checks on page 1 of Attachment 9.1.

1.1 Determines Batch number matches CAP A-5 Att. 11.1 number.

1.2 Identifies that Valve alignment is complete. 1.3 Identifies that independent verification of Valve alignment is complete.

1.4 Identifies that dilution flowrate is adequate.

1.5 Identifies that RE-18 setpoint doesn't require adjustment.

Step was: Sat: ______ Unsat _______*

• • 2. Review Manual Valve Lineup Verification on page 2 of .1 2.1 Determines that CCW HX 12 is to be circled to be used, but that valve alignment is for CCW HX 11.

Step was: Sat: ______ Unsat _______*

• • 3. Review Attachment 9.5 PWR alignment checklist. 3.1 Determines that PWR 0-2 has been aligned for discharge instead of PWR 0-1. Step was: Sat: ______ Unsat _______*

• • 4. Determine if Authorization should be approved.

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

Step was: Sat: ______ Unsat _______*

• Denotes an entry required on the JPM cover sheet. ** Denotes a Critical Step.

NRCADM061C

-A4.DOC Page 3 of 6 R EV. 1 JPM TITLE: REVIEW LIQUID RADWASTE DISCHARGE CHECKLIST JPM NUMBER: NRCADM 061C-A4 INSTRUCTOR WORKSHEET Stop Time:

Total Time:

(Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet. ** Denotes a Critical Step.

NRCADM061C

-A4.DOC Page 4 of 6 R EV. 1 JPM NUMBER: NRCADM 061C-A4 EXAMINEE CUE SHEET Initial Conditions:

Chemistry has issued a discharge permit for PWR 0-1 using CAP A-5 Att. 11.1 parts 1 & 2. OP G-1:II Attachments 9.1 & 9.5 have been completed. Initiating Cue:

As the Unit 1 Shift Foreman, review OP G-1:II Attachments 9.1 & 9.5 Discharge Checklists for accuracy and completeness. Document any discrepancies noted and determine if the discharge checklist should be approved or not approved based on your review.

Technical Errors Identified:

[ ] APPROVE Discharge [ ] DO NOT Approve Discharge

NRCADM061C

-A4.DOC Page 5 of 6 R EV. 1 REVIEW LIQUID RADWASTE DISCHARGE CHECKLIST JPM NUMBER: NRCADM 061C-A4 ATTACHMENT 1, SIMULATOR SETUP The simulator is not needed for the performance of this JPM.

NRCADM061C

-A4.DOC Page 6 of 6 R EV. 1 JPM TITLE: REVIEW LIQUID RADWASTE DISCHARGE CHECKLIST. JPM NUMBER: NRCADM 061C-A4 ANSWER K EY Initial Conditions:

Chemistry has issued a discharge permit for PWR 0-1 using CAP A-5 Att. 11.1 parts 1 & 2. OP G-1:II Attachments 9.1 & 9.5 have been completed. Initiating Cue:

As the Unit 1 Shift Foreman, review OP G-1:II Attachments 9.1 & 9.5 Discharge Checklists for accuracy and completeness. Document any discrepancies noted and determine if the discharge checklist should be approved or not approved based on your review.

Technical Errors Identified:

Attachment 9.1 page 2, CCW HX 1-2 is circled to be used for the release, but SW-1-67 is opened when SW-1-68 should be opened.

Attachment 9.5 has PWR 0-2 aligned when PWR 0-1 should be.

[ ] APPROVE Discharge [ X ] DO NOT Approve Discharge NRCADM061C

-A4.DOC Page 7 of 6 R EV. 1 NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-A5 Title: VERIFY A DETERMINATION OF ULTIMATE HEAT SINK TEMPERATURE Examinee: Evaluator:

Print Signature Date Testing Method:

Perform X Simulate Results: Sat Unsat Total Time:

minutes Comments:

References:

STP I-1A, Routine Shift Checks Required by Licenses, Attachment 12.1, Rev. 126 Technical Specifications, DCPP Units 1 & 2 Alternate Path:

Yes X No Time Critical:

Yes No X Time Allotment:

10 minutes Critical Steps:

2.3, 3.1, 4.1 Job Designation:

SRO Rev Comments:

modified from LJACO-02S Gen KA / Rating:

G2.1.2 5 - Conduct of Operations 3.9 Note: This is an admin JPM (SRO), intended for the classroom setting.

AUTHOR: LISA TORIBIO/ DATE: OPERATIONS REPRESENTATIVE

ABDUL KADIR/ DATE: R EV. 0 JPM TITLE: VERIFY A DETERMINATION OF ULTIMATE HEAT SINK TEMPERATURE JPM NUMBER: NRCL121-A5 EVALUATOR WORKSHEET Directions:

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

Completed copy of STP I

-1A, Attachment 12.1, MODE 1 Shift Checklist, Step 37 (SR 3.7.9.2).

LCO 3.7.9 Initial Conditions GIVEN: Unit 1 is at 50% power CWP 1-2 out of service for replacement of damaged screens Unit 2 is in day 14 of a refueling outage.

Current plant conditions for the Circ Water and ASW systems are as follows: Component Status Current Ocean Temperature CWP 1-1 In-service TI-311 Out of Calibration CWP 1-2 Cleared TI-328 6 1.1 F ASW Pp 1-1 In-service to CCW HX 1

-1 TI-1484 59.5 F ASW Pp 1-2 In-STBY TI-1485 61.4 F CWP 2-1 Cleared TI-311 60.3 F CWP 2-2 Cleared TI-328 60.4 F ASW Pp 2-1 In-service to CCW HX 2

-1 TI-1484 59.5 F ASW Pp 2-2 Cleared TI-1485 60.4 F Initiating Cue:

Unit 1 BOPCO has just completed STP I

-1A, "Routine Shift Checks Required by Licenses," Attachment 12.1, Step 37.

BOPCO has just informed you that the Ultimate Heat Sink Temperature requires 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> recordings for the given conditions.

Review the completed STP data sheet and determine if the unit is in a LCO ACTION statement for Ultimate Heat Sink and what frequency of ocean temperature monitoring is required. DO NOT READ TASK STANDARD TO EXAMINEE Task Standard:

STP I-1A, "Routine Shift Checks Required by Licenses," Attachment 12.1, is reviewed and it is determined the calculation of Ultimate Heat Sink temperature was incorrect. The correct temperature is above the limit for increased monitoring (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />), but the LCO is satisfied, (temperature is less than 64°F) NRCL121-A5 PAGE 2 OF 5 R EV. 0 JPM TITLE: VERIFY A DETERMINATION OF ULTIMATE HEAT SINK TEMPERATURE JPM NUMBER: NRCL121-A5 EVALUATOR WORKSHEET Start Time:

Step Expected Operator Actions 1.** Review Step 37, Method 1 Data

. 1.1 Read NOTE prior to step 37.a 1.2 Method 1 incorrectly used. CWP 1

-2 is not running (Per note, temperature indicator not available) and TI-311 is out of calibration.**

Sat: ______ Unsat _______

Comment: 2. Perform Step 37, Method 2 2.1 NOTE: The sheet may not be completed as the key is however, some manner must be used to determine the correct ocean temperature Used method 2 to determine ocean temperature

TI-1484 = 59.5°F TI-148 5. = N/A 2.2 Added 0.7°F for instrument error correction 2.3 Determined ocean temperature to be between 60 and 62

°F (60.2°F) Sat: ______ Unsat _______ Comment: 3.** Determine ocean temperature monitoring required 3.1 Required ocean temperature monitoring is 37.d (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) **

Sat: ______ Unsat _______

Comment: 4.** Evaluates LCO 3.7.9 (UHS) ** 4.1 LCO is met, UHS is OPERABLE (less than 6 4°F)** Sat: ______ Unsat _______

Comment: NRCL121-A5 PAGE 3 OF 5 R EV. 0 JPM TITLE: VERIFY A DETERMINATION OF ULTIMATE HEAT SINK TEMPERATURE JPM NUMBER: NRCL121-A5 EVALUATOR WORKSHEET KEY Is the unit in an ACTION statement for Ultimate Heat Sink? Yes / No. (From 3.7.9 bases: The UHS is required to be OPERABLE and is considered OPERABLE if it is at or below the maximum temperature that would allow the ASW to operate for at least 30 days following the DBA without exceeding the maximum design temperature of the CCW system. To meet this condition, the UHS temperature should not exceed 64°F unless two CCW heat exchangers are in service during normal unit operation. With two heat exchangers in service, operation with elevated UHS temperatures as high as 70°F is acceptable.

) What is the frequency of ocean temperature monitoring required?

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Stop Time:

Total Time:

(Enter total time on the cover page)

Follow up Question Documentation

Question: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

Response: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

NRCL121-A5 PAGE 4 OF 5 R EV. 0 69-20232 01/27/14 Page 15 of 26 STP I-1A (UNIT 1) ATTACHMENT 12.1 TITLE: MODE 1 Shift Checklist STP_I-1Au1r27.DOC 06 0515.1508 APPL MODE TECH SPEC

REFERENCE A. CHECK / VERIFICATION FROM CONTROL ROOM PERF 37.Determine the Ultimate Heat Sink (UHS) temperature using one of the following methods:NOTE: Temperature indicators are only available whentheir associated pumps are running.

a.Method 1 - Record Pacific Ocean water temp as readon the following indicators:N/A [ ] ______ TI-311 (T2400A) (CWP 1-1) _______FN/A [ ] TI-328 (T2401A) (CWP 1-2) _______FN/A [ ] Record the highest of the available indicators. F Instrument Error Correction 1.9 F Add the highest available indicator reading and the Instrument Error Correction. F b.Method 2 - Record Pacific Ocean water temp on thefollowing indicators:N/A [ ] ______ N/A [ ] TI-1484 (ASWP 1-1) ___FTI-1485 (ASWP 1-2) _______FN/A [ ] Record the highest of the available indicators. F Instrument Error Correction 0.7 F Add the highest available indicator reading and the Instrument Error Correction.°F 1 SR 3.7.9.2 69-20232 01/27/14 Page 16 of 26 STP I-1A (UNIT 1) ATTACHMENT 12.1 TITLE: MODE 1 Shift Checklist STP_I-1Au1r27.DOC 06 0515.1508 APPL MODE TECH SPEC

REFERENCE A. CHECK / VERIFICATION FROM CONTROL ROOM PERF c.Method 3 - If Method 1 and Method 2 are notavailable, M&TE may be used.N/A [ ] ______ Instrument Used: ____________________Cal Due Date: ____________________Reading using M&TE F Uncertainty of M&TE F Add M&TE ocean temp and uncertainty F NOTE: Tech Spec Bases B3.7.9 specifies that the UHS is common to both units. Therefore any required action due to elevated ocean water temp would apply to both units depending on mode requirements. Notify the Unit 2 SFM as required.

d.IF corrected ocean temp is > [60F] AND [62F],THEN perform the following:N/A [ ] 1)Notify SFM to review Tech Spec SR 3.7.9.2.______ 2)Record ocean temp every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

______ e.IF corrected ocean temp is > [62F] AND [64F],THEN perform the following:N/A [ ] 1)Notify SFM to review Tech Spec SR 3.7.9.2.______ 2)Record ocean temp every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

______ f.IF corrected ocean temp is > [64F],THEN place both CCW HXs in service:N/A [ ] ______ SR 3.7.9.2 (Continued) 1 EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A5 Initial Conditions:

GIVEN: Unit 1 is at 50% power CWP 1-2 out of service for replacement of damaged screens Unit 2 is in day 14 of a refueling outage.

Current plant conditions for the Circ Water and ASW systems are as follows: Component Status Current Ocean Temperature CWP 1-1 In-service TI-311 Out of Calibration CWP 1-2 Cleared TI-328 6 1.1 F ASW Pp 1-1 In-service to CCW HX 1

-1 TI-1484 59.5 F ASW Pp 1-2 In-STBY TI-1485 61.4 F CWP 2-1 Cleared TI-311 60.3 F CWP 2-2 Cleared TI-328 60.4 F ASW Pp 2-1 In-service to CCW HX 2

-1 TI-1484 59.5 F ASW Pp 2-2 Cleared TI-1485 60.4 F Initiating Cue:

Unit 1 BOPCO has just completed STP I

-1A, "Routine Shift Checks Required by Licenses," Attachment 12.1, Step 37.

BOPCO has just informed you that the Ultimate Heat Sink Temperature requires 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> recordings for the given conditions.

Review the completed STP data sheet and determine if the unit is in a LCO ACTION statement for Ultimate Heat Sink and what frequency of ocean temperature monitoring is required. Is the unit in an ACTION statement for Ultimate Heat Sink? Yes /

No. What is the frequency of ocean temperature monitoring required?

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> NRCL121-A5 PAGE 5 OF 5 R EV. 0 69-20232 01/27/14 Page 15 of 26 STP I-1A (UNIT 1) ATTACHMENT 12.1 TITLE: MODE 1 Shift Checklist STP_I-1Au1r27.DOC 06 0515.1508 APPL MODE TECH SPEC

REFERENCE A. CHECK / VERIFICATION FROM CONTROL ROOM PERF 37.Determine the Ultimate Heat Sink (UHS) temperature using one of the following methods:NOTE: Temperature indicators are only available whentheir associated pumps are running.

a.Method 1 - Record Pacific Ocean water temp as readon the following indicators:N/A [ ] ______ TI-311 (T2400A) (CWP 1-1) _______FN/A [ ] TI-328 (T2401A) (CWP 1-2) _______FN/A [ ] Record the highest of the available indicators. F Instrument Error Correction 1.9 F Add the highest available indicator reading and the Instrument Error Correction. F b.Method 2 - Record Pacific Ocean water temp on thefollowing indicators:N/A [ ] ______ TI-1484 (ASWP 1-1) _______FN/A [ ] TI-1485 (ASWP 1-2) _______FN/A [ ] Record the highest of the available indicators. F Instrument Error Correction 0.7 F Add the highest available indicator reading and the Instrument Error Correction.

°F 1 SR 3.7.9.2

69-20232 01/27/14 Page 16 of 26 STP I-1A (UNIT 1) ATTACHMENT 12.1 TITLE: MODE 1 Shift Checklist STP_I-1Au1r27.DOC 06 0515.1508 APPL MODE TECH SPEC

REFERENCE A. CHECK / VERIFICATION FROM CONTROL ROOM PERF c.Method 3 - If Method 1 and Method 2 are notavailable, M&TE may be used.N/A [ ] ______ Instrument Used: ____________________Cal Due Date: ____________________Reading using M&TE F Uncertainty of M&TE F Add M&TE ocean temp and uncertainty F NOTE: Tech Spec Bases B3.7.9 specifies that the UHS is common to both units. Therefore any required action due to elevated ocean water temp would apply to both units depending on mode requirements. Notify the Unit 2 SFM as required.

d.IF corrected ocean temp is > [60F] AND [62F],THEN perform the following:N/A [ ] 1)Notify SFM to review Tech Spec SR 3.7.9.2.______ 2)Record ocean temp every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

______ e.IF corrected ocean temp is > [62F] AND [64F],THEN perform the following:N/A [ ] 1)Notify SFM to review Tech Spec SR 3.7.9.2.______ 2)Record ocean temp every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

______ f.IF corrected ocean temp is > [64F],THEN place both CCW HXs in service:N/A [ ] ______ SR 3.7.9.2 (Continued) 1 NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: LJACO-02S Title: VERIFY A DETERMINATION OF ULTIMATE HEAT SINK TEMPERATURE Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: This JPM requires that STP I-1A, Attachment 12.1, Step 37 be filled out ahead of time. The required data is included in an attachment to this JPM. Rev 4A changes to current rev of I-1A approved by ILT supervisor

References:

STP I-1A, Routine Shift Checks Required by Licenses, Attachment 12.1, Rev. 121 Technical Specifications, DCPP Units 1 & 2 Alternate Path:

Yes X No Time Critical:

Yes No X Time Allotment:

10 Minutes Critical Steps:

2, 4 Job Designation: SRO Task Number:

G2.1.23 Rating: 4.4 AUTHOR: DAVID RICHARDS / CHARLES HIBBARD DATE: 05/04/11 REVIEWED B Y: JOHN P. LYLE DATE: 05/04/11 TRAINING SUPERVISOR APPROVED B Y: KEN JOHNSTON DATE: 05/05/11 MANAGER - OPERATIONS R EV. 4A JPM TITLE: VERIFY A DETERMINATION OF ULTIMATE HEAT SINK TEMPERATURE JPM NUMBER: LJACO-02S INSTRUCTOR WORKSHEET Directions:

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

Completed copy of STP I-1A, Attachment 12.1, MODE 1 Shift Checklist, Step 37 (SR 3.7.9.2) Initial Conditions:

Unit 1 is at 50% power with CWP 1-2 out of service for replacement of damaged screens. Unit 2 is in day 14 of a refueling outage. Current plant conditions for the Circ Water and ASW systems are as follows: Component Status Current Ocean Water Temperature CWP 1-1 In-service TI-311 61F CWP 1-2 Cleared TI-328 61F ASW Pp 1-1 In-service to CCW HX 1-1 TI-1484 61.5F ASW Pp 1-2 In-STBY TI-1485 60F CWP 2-1 Cleared TI-311 61F CWP 2-2 Cleared TI-328 61F ASW Pp 2-1 In-service to CCW HX 2-1 TI-1484 62F ASW Pp 2-2 Cleared TI-1485 61F Initiating Cue:

Unit 1 BOPCO has just completed STP I-1A, "Routine Shift Checks Required by Licenses," Attachment 12.1, Step 37.

BOPCO has determined that the Ultimate Heat Sink Temperature is satisfactory for the given conditions. Review the completed STP data sheet and determine if his assessment is correct and implement any actions needed based on your review.

DO NOT READ TASK STANDARD TO EXAMINEE Task Standard:

STP I-1A, "Routine Shift Checks Required by Licenses," Attachment 12.1, Step 33 reviewed for completeness and any actions implemented based on your review. DOCCONTENT.dll PAGE 2 OF 6 R EV. 4A JPM TITLE: VERIFY A DETERMINATION OF ULTIMATE HEAT SINK TEMPERATURE JPM NUMBER: LJACO-02S INSTRUCTOR WORKSHEET Start Time: StepExpected Operator Actions

1. Obtains correct procedure 1.1 Obtains completed STP I-1A, Attachment 12.1, Step 37. Note: Provide completed exam copy of STP I-1A, Attachment 12.1, Step

37. Step was: Sat: _______ Unsat _______*

2. **Verifies UHS temperature method 1.

2.1 Reads NOTE prior to step 37.a. 2.2 Verifies that the Pacific Ocean water temperature of 61F is entered for TI-311.** 2.3 Verifies that the TI-328 entry (CWP 1-2) is checked "N/A", because the pump is not running (per Note). 2.4 Verifies that 61F is entered as the highest temperature

.** 2.5 Notes that the instrument error was added incorrectly.** Note: The value entered on the completed STP I-1A was 61.9 F. The correct value is 62.9 F. Step was: Sat: _______ Unsat _______*

• Denotes an entry required on the JPM cover sheet. **Denotes a Critical Step.

DOCCONTENT.dll PAGE 3 OF 6 R EV. 4A JPM TITLE: VERIFY A DETERMINATION OF ULTIMATE HEAT SINK TEMPERATURE JPM NUMBER: LJACO-02S INSTRUCTOR WORKSHEET StepExpected Operator Actions

3. Verifies UHS temperature using methods 2

& 3. 3.1 Verifies that "N/A" is checked for Method 2.

3.2 Verifies that "N/A" is checked for Method 3. Step was: Sat: _______ Unsat _______*

4. **Verifies appropriate Tech Spec actions are taken. 4.1 Determines that step 37.d was completed incorrectly

.** Note: The step on the completed STP I

-1A was marked "N/A." Step d should have been initialed and the Unit 1 SFM informed of the actions in the step.

4.2 Notes that Unit 1 needs to record UHS temperatures every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in the Operations Shift Log.** Note: Unit 2 SFM does not need to be informed since Unit 2 is in a refueling outage (not in Modes 1- 4). 4.3 Verifies step 37.e is checked "N/A." 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.

DOCCONTENT.dll PAGE 4 OF 6 R EV. 4A EXAMINEE CUE SHEET JPM NUMBER: LJACO-02S Initial Conditions:

Unit 1 is at 50% power with CWP 1

-2 out of service for replacement of damaged screens. Unit 2 is in day 14 of a refueling outage. Current plant conditions for the Circ Water and ASW systems are as follows: Component Status Current Ocean Water Temperature CWP 1-1 In-service TI-311 61F CWP 1-2 Cleared TI-328 61F ASW Pp 1-1 In-service to CCW HX 1-1 TI-1484 61.5F ASW Pp 1-2 In-STBY TI-1485 60F CWP 2-1 Cleared TI-311 61F CWP 2-2 Cleared TI-328 61F ASW Pp 2-1 In-service to CCW HX 2-1 TI-1484 62F ASW Pp 2-2 Cleared TI-1485 61F Initiating Cue:

Unit 1 BOPCO has just completed STP I-1A, "Routine Shift Checks Required by Licenses," Attachment 12.1, Step 37.

BOPCO has determined that the Ultimate Heat Sink Temperature is satisfactory for the given conditions. Review the completed STP data sheet and determine if his assessment is correct and implement any actions needed based on your review. DOCCONTENT.dll PAGE 5 OF 6 R EV. 4A N UCLEAR P OWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE M EASURE AUTHOR:L ISAT ORIBIOD ATE:06/20/2014OPERATIONSR EPRESENTATIVE

A BDULK ADIRD ATE:06/20/2014R EV.0 Number: NRCL121-A6 Title: DETERMINE DILUTION REQUIREMENTS TO RAISE POWER Examinee: Evaluator: Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments:

References:

DCPP Unit 2 Cycle 18 Reactivity Briefing Sheet (263 to 310 EFPD) Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 2.2, 3.3, 4.1, 5.1 Job Designation:

RO or SRO Rev Comments: modified from L081 NRC ADMRO1 Gen KA / Rating: G2.1.25 - Conduct of Operations 3.9 Note: This is an admin JPM (RO), intended for the classroom setting.

JPM TITLE: DETERMINE DILUTION REQUIREMENTS TO RAISE POWER JPM NUMBER: NRCL121-A6 EVALUATOR WORKSHEET Directions:

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

Calculator, Reactivity Briefing Sheet from the Reactivity Handbook Initial Conditions Given: Unit 2 was ramped down due to high vibration on the main turbine.

Unit 2 has been at 80% power for 3 days.

Control Bank D is at 200 steps Initiating Cue:

The Shift Foreman directs you to determine the dilution or boration requirements to raise power to 90% assuming final rod position of 210 steps using the data from the Reactivity Briefing Sheet (from Reactivity Handbook)

DO NOT READ TASK STANDARD TO EXAMINEE Task Standard:

Determined that 928 (+/

- 5 ) gallons of primary water is required for the 10% power increase.

NRCL121-A6 PAGE 2 OF 5 R EV. 0 JPM TITLE: DETERMINE DILUTION REQUIREMENTS TO RAISE POWER JPM NUMBER: NRCL121-A6 EVALUATOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure.

1.1 **********************************

Cue: Provide examinee with reactivity briefing sheet, if not already done.

Sat: ______ Unsat _______

Comment: 2.0B** Calculate reactivity change for 10% change in power 2.1 From graph power coefficient is

-15.47 pcm/% power.

2.2 Record ed (-)154.7 pcm for 10% increase in power.

• • Sat: ______ Unsat _______

Comment: 3.1B** Calculate reactivity change due to change in rod position 3.1 Recorded 45.9 pcm for Control Bank D at 210 steps.

(From graph, A. Control Bank D Integral Rod Worth) 3.2 Recorded 98.1 pcm for Control Bank D at 2 00 steps.

(From graph, A. Control Bank D Integral Rod Worth) 3.3 Recorded (+)52.2 pcm for change in rod position.

• • (98.1 - 45.9 ) Sat: ______ Unsat _______

Comment: NRCL121-A6 PAGE 3 OF 5 R EV. 0 JPM TITLE: DETERMINE DILUTION REQUIREMENTS TO RAISE POWER JPM NUMBER: NRCL121-A6 EVALUATOR WORKSHEET 4.2B** Calculate reactivity left after accounting change in rod position.

4.1 Recorded (-)102.5 pcm

)reactivity from change in rods position on total reactivity from change in power.

• • (-154.7 + 52.2) Sat: ______ Unsat _______

Comment: 5.3B** Determines amount of primary water to add Note: The examinee may set up a ratio to get the primary water needed, or may do two steps (determine power change needing dilution, and then dilution for that power change).

5.1 Determined 928 (+/- 5 ) gallons of primary water is required.

(102.5 pcm/15.47 pcm/% = 6.63 % pwr) (6.63% x 140 gal/% =

928 gallons (+/- 5 gallons) ** Note: The critical "part" of the above step is the dilution gallons, as the data can be manipulated several different ways in one or more steps to arrive at the right answer. Sat: ______ Unsat _______

Comment: Stop Time:

Total Time:

(Enter total time on the cover page)

Follow up Question Documentation

Question: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

Response: ___________________________________________________________________

______________________________________________________________________________

NRCL121-A6 PAGE 4 OF 5 R EV. 0 EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A6 Initial Conditions:

Given: Unit 2 was ramped down due to high vibration on the main turbine.

Unit 2 has been at 80% power for 3 days.

Control Bank D is at 200 steps Initiating Cue:

The Shift Foreman directs you to determine the dilution or boration requirements to raise power to 90% assuming final rod position of 210 steps using the data from the Reactivity Briefing Sheet (from Reactivity Handbook)

Answer (show work)

NRCL121-A6 PAGE 5 OF 5 R EV. 0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL081LJA_ROA1 Title: DETERMINE DILUTION REQUIREMENTS FOR A POWER INCREASE Examinee:

Evaluator:

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

References:

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

Yes No X Time Critical:

Yes No X Time Allotment:

15 Minutes Critical Steps:

2-6 Job Designation:

RO Task Number:

G2.1.25 Rating: 3.9 JOHN P. LYLE E D HURST AUTHOR: GARY HUTCHISON DATE: 12/10/09 R EV. 1 JPM TITLE: DETERMINE DILUTION REQUIREMENT S FOR A POWER INCREASE JPM NUMBER: NRCL081LJA_ROA1 INSTRUCTOR WORKSHEET Directions:

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

Calculator, Reactivity Briefing Sheet Initial Conditions:

Unit 1 was ramped down due to problems with Govenor valve 4. Unit 1 has been at 90% power for 3 days with Control Bank D at 200 steps. Initiating Cue:

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

Operator determines that 230 (+/- 5 ) gallons of primary water is required. NRCL081LJA_ROA1 rev 1.doc PAGE 2 OF 6 R EV. 1 JPM TITLE: DETERMINE DILUTION REQUIREMENT S FOR A POWER INCREASE JPM NUMBER: NRCL081LJA_ROA1 INSTRUCTOR WORKSHEET Start Time: StepExpected 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 _______*

• Denotes an entry required on the JPM cover sheet. **Denotes a Critical Step.

NRCL081LJA_ROA1 rev 1.doc PAGE 3 OF 6 R EV. 1 JPM TITLE: DETERMINE DILUTION REQUIREMENT S FOR A POWER INCREASE JPM NUMBER: NRCL081LJA_ROA1 INSTRUCTOR WORKSHEET StepExpected 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 (+/- 5 ) 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)*Denotes an entry required on the JPM cover sheet. **Denotes a Critical Step.

NRCL081LJA_ROA1 rev 1.doc PAGE 4 OF 6 R EV. 1 JPM TITLE: DETERMINE DILUTION REQUIREMENT S FOR A POWER INCREASE JPM NUMBER: NRCL081LJA_ROA1 ANSWER K EY Initial Conditions:

Unit 1 was ramped down due to problems with Govenor valve 4. Unit 1 has been at 90% power for 3 days with Control Bank D at 200 steps Initiating Cue:

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

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

NRCL081LJA_ROA1 rev 1.doc PAGE 5 OF 6 R EV. 1 EXAMINEE CUE SHEET JPM NUMBER: NRCL081LJA_ROA1 Initial Conditions:

Unit 1 was ramped down due to problems with Govenor valve 14 . Reactor power is now stabilized at approximately 90% with Control Bank D at 200 steps Initiating Cue:

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

NRCL081LJA_ROA1 rev 1.doc PAGE 6 OF 6 R EV. 1 NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-A 7 Title: VERIFY OUTAGE SAFETY CHECKLIST Examinee: Evaluator:

Print Signature Date Testing Method:

Perform X Simulate Results: Sat Unsat Total Time:

minutes Comments:

References:

AD8.DC55, Outage Safety Scheduling, Att 4, page 6, Rev. 38 Alternate Path:

Yes No X Time Critical:

Yes No X Time Allotment:

10 minutes Critical Steps:

3 Job Designation:

S RO Rev Comments:

Modified from LJAEC-01S Gen KA / Rating:

G2.2.37 - Ability to determine operability and/or availability of safety related equipment 4.6 Note: This is an admin JPM (SRO), intended for the classroom setting.

AUTHOR: LISA TORIBIO DATE: OPERATIONS REPRESENTATIVE

ABDUL KADIR DATE: R EV. 0 JPM TITLE: VERIFY OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A 7 EVALUATOR WORKSHEET Directions:

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

Calculator, Reactivity Briefing Sheet from the Reactivity Handbook Initial Conditions Unit 1 is currently in MODE 6 with a Core Load planned to start on the next shift (upper internals are installed). Current plant parameters are as follows:

Operable Cleared Offsite power sources Startup power X Aux power X Onsite power sources Diesel Generator 1 X Diesel Generator 2 X Diesel Generator 3 X Vital bus crosstie 4kV & 480v Bus F X 4kV & 480v Bus G X 4kV & 480v Bus H X Onsite distribution sys.

4kV & 480v Bus F X 4kV & 480v Bus G X 4kV & 480v Bus H X Instrument AC Panels PY-11 X PY-11A X PY-12 X PY-13 X PY-13A X PY-14 X Vital DC Power DC Bus 1-1 X DC Bus 1-2 X DC Bus 1-3 X Refueling cavity level 13 5 Feet NRCL121-A 7 PAGE 2 OF 8 R EV. 0 JPM TITLE: VERIFY OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A 7 EVALUATOR WORKSHEET Initiating Cue:

The Unit 1 Control Operator has just completed AD8.DC55, Outage Safety Scheduling, Att 4, page 6, Unit 1 Outage Safety Checklist

- Mode 6 RCS Level Greater Than or Equal to 111', for the current plant conditions.

The Control Operator has determined that the checklist is satisfactory.

Perform a review of the completed checklist and determine if it is acceptable. If not, document any discrepancies found DO NOT READ TASK STANDARD TO EXAMINEE Task Standard:

Review completed of the completed portion of AD8.DC55, Outage Safety Scheduling, Att 4, page 6, Unit 1 Outage Safety Checklist

- Mode 6 RCS Level Greater Than or Equal to 111'.

Determined the checklist is NOT acceptable.

Identified and documented that the status of refueling cavity is incorrect.

Identified and documented that D/G 1

-2 has been incorrectly credited as both the operable and available diesel when a different D/G is required to be available or operable

. NRCL121-A 7 PAGE 3 OF 8 R EV. 0 JPM TITLE: VERIFY OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A 7 EVALUATOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure.

1.1 Obtained completed copy of AD8.DC55, Att 4, page 6, Unit 1 Outage Safety Checklist

- Mode 6 RCS Level Greater Than or Equal to 111'.

Sat: ______ Unsat _______

Comment: 2. Status of On-site power 2.1 Determined status is satisfactory (requires aux or startup power AND cross

-tie capability or operable diesels to operable vital buses) Aux Power is operable and the appropriate "box" on Att 4, page 6 marked. Cross tie capability is available for the Operable Vital Buses F and G and the appropriate "boxes" on Att 4, page 6 marked. Sat: ______ Unsat _______

Comment: NRCL121-A 7 PAGE 4 OF 8 R EV. 0 JPM TITLE: VERIFY OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A 7 EVALUATOR WORKSHEET 3.** Status of On

-site Power supply 3.1 Determin ed status incorrectly marked as satisfactory (requires 1condition met)

- 2 diesels (not met - only D/G 1

-2 correctly marked) OR either cavity level w/ internals removed (not met - both marked incorrectly, cavity level is less than 23' above the flange

)** or both Aux and Startup power and (not met - correctly marked only Aux available)

AND One diesel operable (met - D/G 1-2 correctly marked) AND Different diesel (from 1-2) operable

• • (not met - D/G 1-2 incorrectly marked. No other D/G available or operable) Sat: ______ Unsat _______

Comment: 4. Status of 480 VAC 4.1 4 kV buses F and G, as well as 480V buses F and G, are operable and the appropriate "boxes" on Att 4, page 6 are marked.

Sat: ______ Unsat _______

Comment: NRCL121-A 7 PAGE 5 OF 8 R EV. 0 JPM TITLE: VERIFY OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A 7 EVALUATOR WORKSHEET 5. Status of Instrument AC Power Panels Note: The boxes at the bottom of the right hand column of Att 4, page 6 are a continuation of the boxes at the bottom of the left hand column. Note: Tech Spec 3.8.2 states only one vital buses required to be operable in Mode 6.

5.1 Determine d that all vital instrument AC power panels are operable and marks appropriate "boxes" on Att 4, page 6.

Comment: 6. Status of Vital DC Power 6.1 Determined that all vital DC buses are operable and marks appropriate "boxes" on Att 4, page 6.

Comment: Stop Time:

Total Time:

(Enter total time on the cover page)

Follow up Question Documentation

Question: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

Response: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

NRCL121-A 7 PAGE 6 OF 8 R EV. 0 Unit 1 Outage Safety Checklist - Mode 6 RCS Level Greater Than or Equal to 111' AD8.DC55 R38 Page 35 of 66 Attachment 4: Page 6 of 7 AD8!DC55u3r38.DOC 1126.1027 )#2&3)(!-4)4)4))) 5#$/!&! ,678,7~# 9,678,7~# ,678,7~# :;;);;;);,~# ~# ~#  !$!7~# !7~# 3' "))#2&3)$E0 (0-EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A 7 Initial Conditions:

Unit 1 is currently in MODE 6 with a Core Load planned to start on the next shift (upper internals are installed). Current plant parameters are as follows:

Operable Cleared Offsite power sources Startup power X Aux power X Onsite power sources Diesel Generator 1 X Diesel Generator 2 X Diesel Generator 3 X Vital bus crosstie 4kV & 480v Bus F X 4kV & 480v Bus G X 4kV & 480v Bus H X Onsite distribution sys.

4kV & 480v Bus F X 4kV & 480v Bus G X 4kV & 480v Bus H X Instrument AC Panels PY-11 X PY-11A X PY-12 X PY-13 X PY-13A X PY-14 X Vital DC Power DC Bus 1-1 X DC Bus 1-2 X DC Bus 1-3 X Refueling cavity level 13 5 Feet Initiating Cue:

The Unit 1 Control Operator has just completed AD8.DC55, Outage Safety Scheduling, Att 4, page 6, Unit 1 Outage Safety Checklist

- Mode 6 RCS Level Greater Than or Equal to 111', for the current plant conditions.

The Control Operator has determined that the checklist is satisfactory.

Perform a review of the completed checklist and determine if it is acceptable. If not, document any discrepancies found NRCL121-A 7 PAGE 7 OF 8 R EV. 0 EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A 7 Document Answer Here VITAL AC Power is:

Acceptable / Not Acceptable*

• Not acceptable due to:

NRCL121-A 7 PAGE 8 OF 8 R EV. 0 Unit 1 Outage Safety Checklist - Mode 6 RCS Level Greater Than or Equal to 111' AD8.DC55 R38 Page 35 of 66 Attachment 4: Page 6 of 7 AD8!DC55u3r38.DOC 1126.1027 )#2&3)(!-4)4)4))) 5#$/!&! ,678,7~# 9,678,7~# ,678,7~# :;;);;;);,~# ~# ~#  !$!7~# !7~# 3' "))#2&3)$E0 (0-JPM TITLE: VERIFY OUTAGE SAFETY CHECKLIST JPM NUMBER: LJ A EC-01 S INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 6. Verifies TS required 4kV and 480V bus operability.

6.1 Verifies 4 kV buses F and G, as well as 480V buses F and G, are operable and the appropriate "boxes" on Att 4, page 6 are marked. ** Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

Note: The boxes at the bottom of the right hand column of Att 4, page 6 are a continuation of the boxes at the bottom of the left hand column.

Note: Tech Spec 3.8.2 says that only one of these vital buses is required to be operable in Mode 6.

Note: If requested, provide access to Tech Specs. ** 7. Determines status of Instrument AC Power Panels. 7.1 Determines that all vital instrument AC power panels are operable and marks appropriate "boxes" on Att 4, page 6. ** Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

Stop Time:

Total Time:

(Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet. ** Denotes Critical Step and Sub Steps. DOCCONTENT

.DLL PAGE 6 OF 10 R EV. 5 A x x x x x x x x x x x x x x x x x x x x x x x x x x DOCCONTENT

.DLL PAGE 7 OF 10 R EV. 5 A

DOCCONTENT

.DLL PAGE 8 OF 10 R EV. 5 A JPM NUMBER: LJ A EC-01 S EXAMINEE CUE SHEET Initial Conditions:

Unit 1 is currently in Mode 6 with a Core Load planned to start on the next shift (upper internals are removed).

Current plant parameters are as follows: Cleared Available Operable Offsite power sources Startup power NA X Aux power X NA Onsite power sources Diesel Generator 1 X Diesel Generator 2 X Diesel Generator 3 X Vital bus crosstie 4kV & 480v Bus F X NA 4kV & 480v Bu s G X NA 4kV & 480v Bus H NA X Onsite distribution sys.

4kV & 480v Bus F X NA 4kV & 480v Bus G X NA 4kV & 480v Bus H NA X Instrument AC Panels PY-11 X NA PY-11A X NA PY-12 X NA PY-13 X NA PY-13A X NA PY-14 X NA Refueling cavity level 139 Feet DOCCONTENT

.DLL PAGE 9 OF 10 R EV. 5 A JPM NUMBER: LJ A EC-01 S EXAMINEE CUE SHEET Initiating Cue:

The Unit 1 Control Operator has just completed AD8.DC55, Outage Safety Scheduling, Att 4, page 6, Unit 1 Outage Safety Checklist -

Mode 6 RCS Level Greater Than or Equal to 111', for the current plant conditions. The Control Operator has determined that the VITAL AC POWER portion of the checklist is satisfactory.

Perform a review of the completed checklist and determine if the VITAL AC POWER portion is acceptable. If not, document any discrepancies you found.

Document Your Answer Here VITAL AC POWER is: Acceptable Not Acceptable*

• Discrepancies:

DOCCONTENT

.DLL PAGE 10 OF 10 R EV. 5 A NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-A 8 Title: REVIEW LIQUID RADWASTE DISCHARGE CHECKLI ST Examinee: Evaluator:

Print Signature Date Testing Method:

Perform X Simulate Results: Sat Unsat Total Time:

minutes Comments:

References:

OP G-1:II, Liquid Radwaste System - Discharge of Liquid Radwaste, Rev. 37A CAP A-5, Liquid Radwaste Discharge Management, Rev. 48 Alternate Path:

Yes No X Time Critical: Yes No X Time Allotment:

10 minutes Critical Steps:

1.2, 1.3 Job Designation:

S RO Rev Comments:

modified from L061C NRC ADM04 Gen KA / Rating:

G2.3.11 - Ability to control radiation releases.

4.3 Note: This is an admin JPM (SRO), intended for the classroom setting.

AUTHOR: L ISA TORIBIO/ DATE: 06/20/2014 OPERATIONS REPRESENTATIVE

ABDUL KADIR/ DATE: 06/20/2014 REV. 0 JPM TITLE: REVIEW LIQUID RADWASTE DISCHARGE CHECKLI ST JPM NUMBER: NRCL121-A 8 EVALUATOR WORKSHEET Directions:

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

OP G-1:II, Liquid Radwaste System

- Discharge of Liquid Radwaste, Rev.37A, completed Section 12 Initial Conditions GIVEN: Unit 1 is in MODE 5 Unit 2 is at 45%

CCW HX 2-1 is in service CWP 2-1 is in service CWP 2-2 is secured No Unit 1 CWPs are running

Chemistry has issued a discharge permit for PWR 0-2 using CAP A-5 Att. 11.1 parts 1 & 2. OP G-1:II Section 12 has been completed and ready for signature. Initiating Cue:

Review OP G

-1:II Section 12 Discharge Checklists for accuracy and completeness. Make a recommendation to the Shift Foreman to approve or not approve the discharge permit. Justify your answer DO NOT READ TASK STANDARD TO EXAMINEE Task Standard:

Recommends not approving the discharge permit due to inadequate dilution flow.

NRCL121-A8 PAGE 2 OF 4 R EV. 0 JPM TITLE: REVIEW LIQUID RADWASTE DISCHARGE CHECKLI ST JPM NUMBER: NRCL121-A 8 EVALUATOR WORKSHEET Start Time:

Step Expected Operator Actions 1.0B** Review section 12 (steps 12.1 through 12.18) 1.1 Steps 12.1 through 12.14 reviewed as completed correctly.

1.2 Determined that actual current dilution flow was incorrectly calculated by the operator (actual flowrate is 0.455 x 10 6 gpm (0.433 + 0.011 + 0.011 x 10 6 gpm)) ** NOTE: assumed flow may be determined by no ting which pumps were credited (checkmarks next to pumps at step 12.15) and/or the use of "N/A" of 12.16 (contact chemistry if flowrate is inadequate) 1.3 Recommends not approving the discharge permit because the actual flowrate is less than the required flowrate (8.77 x 10 5 gpm) ** Sat: ______ Unsat _______

Comment:

Stop Time:

Total Time:

(Enter total time on the cover page)

KEY: The Shift Foreman SHOULD / SHOULD NOT approve the discharge permit because:

actual flowrate is less than required flowrate. (actual of 0.455 x 10 6 gpm vs. required 8.77 x 10 5 gpm) Follow up Question Documentation

Question: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

Response: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

NRCL121-A8 PAGE 3 OF 4 R EV. 0 EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A 8 Initial Conditions: GIVEN: Unit 1 is in MODE 5 Unit 2 is at 45% CCW HX 2-1 is in service CWP 2-1 is in service CWP 2-2 is secured No Unit 1 CWPs are running Chemistry has issued a discharge permit for PWR 0-2 using CAP A-5 Att. 11.1 parts 1 & 2. OP G-1:II Section 12 has been completed and ready for signature. Initiating Cue: Review OP G

-1:II Section 12 Discharge Checklists for accuracy and completeness. Make a recommendation to the Shift Foreman to approve or not approve the discharge permit. Justify your answer The Shift Foreman SHOULD / SHOULD NOT approve the discharge permit because:

NRCL121-A8 PAGE 4 OF 4 R EV. 0

• • • ISSUED FOR USE BY: _______________________ DATE: ____________ EXPIRES: ____________ ***

DIABLO CANYON POWER PLANT OPERATING PROCEDURE UNITS 1&2 OP G-1:II Rev. 37A Page 1 of 51 Liquid Radwaste System - Discharge of Liquid Radwaste Effective Date QUALITY RELATED Table of Contents OP_G-1~IIu3r37.DOC 1228.0741 1. SCOPE...........................................................................................................1 2. DISCUSSION..................................................................................................1 3. RESPONSIBILITIES.......................................................................................2 4. PREREQUISITES...........................................................................................2 5. PRECAUTIONS AND LIMITATIONS..............................................................2 6. INSTRUCTIONS.............................................................................................3 7. REFERENCES...............................................................................................5 8. RECORDS......................................................................................................5 9. Discharging Chemical Drain Tank 0-1 (0-2)....................................................6 10. Discharging Laundry and Hot Shower Tank 0-1 (0-2)....................................13 11. Discharging Floor Drain Receiver 0-1 (0-2)...................................................20 12. Discharging Process Waste Receiver 0-1 (0-2).............................................28 13. Discharging Demineralizer Regen Receiver 0-1 (0-2)...................................36 14. Discharging Laundry/Distillate Tank 0-1 (0-2)...............................................44 1. SCOPE 1.1 This procedure provides instructions to safely discharge liquid radwaste. 2. DISCUSSION 2.1 The primary goal of this procedure is to control liquid radwaste (LRW) discharges and prevent an inadvertent or unmonitored release. 2.2 This procedure should be performed in conjunction with CAP A-5, "Liquid Radwaste Discharge Management." 2.3 This procedure should be performed in conjunction with CAP A-11, "Liquid Radwaste Processing System Selection." 2.4 Liquid radwaste discharges are performed using an "Authorization for Discharge of Liquid Radwaste Batch," Form 69-20877, referred to as the "discharge permit" throughout this procedure. 2.5 Valves for LRW alignment and discharge are controlled by the Aux Board Human-Machine Interface (HMI).

12/29/11

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCADM061C-A4 Title: Review Liquid Radwaste Discharge Checklist.

Examinee:

Evaluator:

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

g.

References:

OP G-1: II , Liquid Radwaste System - Discharge of Liquid Radwaste, Rev. 35A CAP A-5, Liquid Radwaste Discharge Management, Rev. 41A Alternate Path:

Yes X No Time Critical:

Yes No X Time Allotment:

20 minutes Critical Steps: 4 Job Designation:

S RO K/A: G 2.3.6; Ability to approve release permits.

Rating: 3.8 AUTHOR: GARY HUTCHISON DATE: 08/12/2008 R EV. 1 JPM TITLE: REVIEW LIQUID RADWASTE DISCHARGE CHECKLIST JPM NUMBER: NRCADM 061C-A4 INSTRUCTOR WORKSHEET Directions:

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

OP G-1:II, Liquid Radwaste System - Discharge of Liquid Radwaste, Rev. 35A Completed Attachments 9.1 & 9.5 CAP A-5 Completed Attachment 11.1 Parts 1 & 2. Initial Conditions:

Chemistry has issued a discharge permit for PWR 0-1 using CAP A-5 Att. 11.1 parts 1 & 2. OP G-1:II Attachments 9.1 & 9.5 have been completed. Initiating Cue:

As the Unit 1 Shift Foreman, review OP G-1:II Attachments 9.1 & 9.5 Discharge Checklists for accuracy and completeness. Document any discrepancies noted and determine if the discharge checklist should be approved or not approved based on your review. Task Standard:

2 Technical errors were identified:

Attachment 9.1 page 2, CCW HX 1-2 is circled to be used for the release, but SW-1-67 is opened when SW-1-68 should be opened PWR 0-2 has been aligned for discharge instead of PWR 0-1 Discharge authorization was not approved. NRCADM061C

-A4.DOC Page 2 of 6 R EV. 1 JPM TITLE: REVIEW LIQUID RADWASTE DISCHARGE CHECKLIST JPM NUMBER: NRCADM 061C-A4 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Review checks on page 1 of Attachment 9.1.

1.1 Determines Batch number matches CAP A-5 Att. 11.1 number.

1.2 Identifies that Valve alignment is complete. 1.3 Identifies that independent verification of Valve alignment is complete.

1.4 Identifies that dilution flowrate is adequate.

1.5 Identifies that RE-18 setpoint doesn't require adjustment.

Step was: Sat: ______ Unsat _______*

• • 2. Review Manual Valve Lineup Verification on page 2 of .1 2.1 Determines that CCW HX 12 is to be circled to be used, but that valve alignment is for CCW HX 11.

Step was: Sat: ______ Unsat _______*

• • 3. Review Attachment 9.5 PWR alignment checklist. 3.1 Determines that PWR 0-2 has been aligned for discharge instead of PWR 0-1. Step was: Sat: ______ Unsat _______*

• • 4. Determine if Authorization should be approved.

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

Step was: Sat: ______ Unsat _______*

• Denotes an entry required on the JPM cover sheet. ** Denotes a Critical Step.

NRCADM061C

-A4.DOC Page 3 of 6 R EV. 1 JPM TITLE: REVIEW LIQUID RADWASTE DISCHARGE CHECKLIST JPM NUMBER: NRCADM 061C-A4 INSTRUCTOR WORKSHEET Stop Time:

Total Time:

(Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet. ** Denotes a Critical Step.

NRCADM061C

-A4.DOC Page 4 of 6 R EV. 1 JPM NUMBER: NRCADM 061C-A4 EXAMINEE CUE SHEET Initial Conditions:

Chemistry has issued a discharge permit for PWR 0-1 using CAP A-5 Att. 11.1 parts 1 & 2. OP G-1:II Attachments 9.1 & 9.5 have been completed. Initiating Cue:

As the Unit 1 Shift Foreman, review OP G-1:II Attachments 9.1 & 9.5 Discharge Checklists for accuracy and completeness. Document any discrepancies noted and determine if the discharge checklist should be approved or not approved based on your review.

Technical Errors Identified:

[ ] APPROVE Discharge [ ] DO NOT Approve Discharge

NRCADM061C

-A4.DOC Page 5 of 6 R EV. 1 REVIEW LIQUID RADWASTE DISCHARGE CHECKLIST JPM NUMBER: NRCADM 061C-A4 ATTACHMENT 1, SIMULATOR SETUP The simulator is not needed for the performance of this JPM.

NRCADM061C

-A4.DOC Page 6 of 6 R EV. 1 JPM TITLE: REVIEW LIQUID RADWASTE DISCHARGE CHECKLIST. JPM NUMBER: NRCADM 061C-A4 ANSWER K EY Initial Conditions:

Chemistry has issued a discharge permit for PWR 0-1 using CAP A-5 Att. 11.1 parts 1 & 2. OP G-1:II Attachments 9.1 & 9.5 have been completed. Initiating Cue:

As the Unit 1 Shift Foreman, review OP G-1:II Attachments 9.1 & 9.5 Discharge Checklists for accuracy and completeness. Document any discrepancies noted and determine if the discharge checklist should be approved or not approved based on your review.

Technical Errors Identified:

Attachment 9.1 page 2, CCW HX 1-2 is circled to be used for the release, but SW-1-67 is opened when SW-1-68 should be opened.

Attachment 9.5 has PWR 0-2 aligned when PWR 0-1 should be.

[ ] APPROVE Discharge [ X ] DO NOT Approve Discharge NRCADM061C

-A4.DOC Page 7 of 6 R EV. 1 NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-A 9 Title: CLASSIFICATION OF A FUEL HANDLING ACCIDENT IN CONTAINMENT Examinee: Evaluator:

Print Signature Date Testing Method:

Perform X Simulate Results: Sat Unsat Total Time:

minutes Comments:

References:

EP G-1, Accident Classification and Emer Plan Activation, Rev.43 Forms 69-21608, 69-21609, 69-21610 (06/19/12, 07/24/13, 12/5/11)

Alternate Path:

Yes No X Time Critical:

Yes X No Time Allotment:

1 5 minutes Critical Steps: 2, 3 Job Designation:

SRO Rev Comments:

Bank LJE-017 Gen KA / Rating:

G2.4.38 - Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required.

4.4 Note: This is an admin JPM (SRO), intended for the classroom setting.

AUTHOR: LISA TORIBIO DATE: 06/20/2014 OPERATIONS REPRESENTATIVE

ABDUL KADIR DATE: 06/20/2014 R EV. 0 JPM TITLE: CLASSIFICATION OF A FUEL HANDLING ACCIDENT IN CONTAINMENT JPM NUMBER: NRCL121-A 9 EVALUATOR WORKSHEET Directions:

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

EP G-1, and EAL Wall Charts.

Vol 11, Emergency Plan, App D (classification bases), should be available to the examinee.

Initial Conditions GIVEN: Unit 1 is REFUELING Core off-loading is in progress Containment closure has been established The fuel handling crew in containment has just reported seeing bubbles in the transfer canal area from an assembly that has just been placed into the upender. Visual inspection showed the appearance of some structural damage to the assembly Radiation Monitor RE

-2 has also just alarmed, and reads 25 mR/hour at this time There are no other Radiation Monitors in alarm Initiating Cue:

The Shift Manager directs you to classify the event DO NOT READ TASK STANDARD TO EXAMINEE Task Standard:

In less than 15 minutes, classifies the event as Alert, RA2.1 Damage to irradiated fuel resulting in a valid high alarm on RM

-2 (>21 mr/hr) NRCL121-A 9 PAGE 2 OF 4 R EV. 0 JPM TITLE: CLASSIFICATION OF A FUEL HANDLING ACCIDENT IN CONTAINMENT JPM NUMBER: NRCL121-A 9 EVALUATOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure.

1.1 References EP G all pages of wall chart provided Sat: ______ Unsat _______ Comment: 2. 0B** Accurately classify the event.

2.1 Classified

the event as Alert, RA2.1 ** Sat: ______ Unsat _______

Comment: 3.1B** Classification time less than 15 minutes 3.1 Classified the event

< 15 min. of the Event Initiation Time.

• • Classification Time:

_____________

Event Initiation Time

_____________

(Event initiation time is JPM Start Time)

Difference: ____________ min** 3.2 Sat: ______ Unsat _______

Comment: Stop Time:

Total Time:

(Enter total time on the cover page)

Follow up Question Documentation

Question: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

Response: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

NRCL121-A 9 PAGE 3 OF 4 R EV. 0 RevisionDate:6/19/12Modekey: 1PowerOperationRefuelingDefueled 2Startup 5 6 3 4DEFHotShutdownColdShutdownHotStandbyDiabloCanyonPowerPlantEmergencyActionLevelWallChartSheet1of3Modes:ALLOnsiteRadConditions,SpentFuelEventsNoneNoneRU1.1ValidreadingonANYLIQUIDmonitors>TableR-1column"UE"for>60min.RU1.2ValidreadingonANYGASEOUSmonitors>TableR-1col-umn"UE"for>60min.RA1.1ValidreadingonANYLIQUIDmonitors>TableR-1column"Alert"for>15min.RS1.1ValidreadingonANYradiationmonitorsthatexceedsorisexpectedtoexceedTableR-1column"SAE"for>15min.(Note1)RS1.2Doseassessmentusingactualmeteorologyindicatesdoses>100mRemTEDEor500mRemthyroidCDEatorbeyondthesiteboundaryRA1.2ValidreadingonANYGASEOUSmonitors>TableR-1col-umn"Alert"for>15min.RA1.3Confirmedsampleanalysesforgaseousorliquidreleasesindicateconcentrationsorreleaserates>200xRETSlimitsfor>15min.RU2.1Validlowwaterlevelalarmindicatinguncontrolledwaterleveldecreaseinthereactorrefuelingcavity,spentfuelpool,orfueltransfercanalwithallirradiatedfuelassembliesremain-ingcoveredbywaterANDUnplanneddirectarearadiationmonitorreadingincreasesRA2.1DamagetoirradiatedfuelorlossofwaterlevelthathasorwillresultintheuncoveringofirradiatedfueloutsidethereactorvesselresultinginavalidhighalarmonANYofthefollowingradiationmonitors:-NewFuelStorageAreaRadMonRM-59,HiRad(6.5mR/hr)-SpentFuelPoolAreaRadMonRM-58,HiRad(20mR/hr)-ContmtAreaMonHighRadRM-2,HiRad(21mR/hr)-ContainmentVentilationExhaustRadiationMonitorRM-44A/Bhighalarm(1.35E-4µCi/cc)RA2.3Validradiationmonitorreadings>15mR/hrinareasrequiringcontinuousoccupancytomaintainplantsafetyfunctions:ControlRoom(0-RM-1)ORCentralAlarmStation(bysurvey)RG1.1ValidreadingonANYmonitorsthatexceedsorisexpected toexceedTableR-1column"GE"for>15min.(Note1)Doseassessmentusingactualmeteorologyindicatesdoses

>1,000mRemTEDEor5,000mRemthyroidCDEatorbeyondthesiteboundaryRG1.2AnyunplannedreleaseofgaseousorliquidradioactivitytotheenvironmentthatexceedstwotimestheRadiologicalEffluent TechnicalSpecifications(RETS)limitsfor60minutesorlongerAnyunplannedreleaseofgaseousorliquidradioactivitytothe environmentthatexceeds200timestheRadiologicalEffluent TechnicalSpecifications(RETS)limitsfor15minutesorlongerOffsitedoseresultingfromanactualorimminentreleaseofgaseous radioactivityexceeds100mRemTEDEor500mRemthyroidCDE fortheactualorprojecteddurationofthereleaseOffsitedoseresultingfromanactualorimminentreleaseof gaseousradioactivityexceeds1000mRemTEDEor5000mRem thyroidCDEfortheactualorprojecteddurationoftherelease usingactualmeteorologyUnexpectedIncreaseinplantradiationDamagetoIrradiatedFuelorLossofWaterLevelthatHasorWill ResultintheUncoveringofIrradiatedFuelOutsidetheReactor VesselRU1.3Confirmedsampleanalysesforgaseousorliquidreleasesindicateconcentrationsorreleaserates>2xRETSlimitsfor

>60min.Note1:Ifdoseassessmentresultsareavailableatthetimeofdeclaration,theclassificationshouldbebasedondoseassessment insteadofradiationmonitorreadings.Whilenecessarydeclarations shouldnotbedelayedawaitingresults,thedoseassessmentshouldbe initiated/completedinordertodetermineiftheclassificationis warranted.SeeEALRG1.2Note1:Ifdoseassessmentresultsareavailableatthetimeof declaration,theclassificationshouldbebasedondoseassessment insteadofradiationmonitorreadings.Whilenecessarydeclarations shouldnotbedelayedawaitingresults,thedoseassessmentshouldbe initiated/completedinordertodetermineiftheclassificationshouldbe subsequentlyescalated.SeeEALRS1.2RU2.2Unplannedvaliddirectradiationareamonitorreadingincreasesbyafactorof1000overnormal*levelsNormallevelsmaybeconsideredasthehighestreadinginthepasttwentyfour(24)hoursexcludingthecurrentpeakvalueRA2.2Awaterleveldropinthereactorrefuelingcavity,spentfuelpoolorfueltransfercanalthatwillresultinirradiatedfuelbecominguncoveredReleaseofradioactivematerialorincreasesinradiationlevelswithinthefacilitythatimpedesoperationofsystemsrequiredto maintainsafeoperationsortoestablishormaintaincoldshutdownRA2.4Validradiationmonitorreadings>2R/hrinthefollowingareasrequiringinfrequentaccesstomaintainplantsafetyfunctions:-AuxiliaryBuilding-FuelHandlingBuilding

-TurbineBuilding-IntakeStructure56DEF123456DEF123456DEF123456DEF123456DEF1234RS1.3Fieldsurveyindicatesclosedwindowdoserate>100mRem/hrthatisexpectedtocontinuefor>1hr,atorbeyondthesiteboundaryORFieldsurveysampleanalysisindicatesthyroidCDEof

>500mRemfor1hrofinhalationatorbeyondthesiteboundary56DEF1234Fieldsurveyresultsindicateclosedwindowdoserates

>1,000mRem/hrexpectedtocontinuefor>1hr,ator beyondthesiteboundaryORAnalysesoffieldsurveysamplesindicatethyroidCDEof 5,000mRemfor1hrofinhalation,atorbeyondthesite boundaryRG1.3---------------3.0E-10amps2.0E0 mCi/cc3.0E+4cpm----------

---

Offscalehi1.0E-6 mCi/cc1.0E-5 mCi/cc3.0E+3cpm6.0E+4cpm*Offscalehi*

Offscalehi*8.0E+4cpm2.0E-3 mCi/cc1.0E-8 mCi/cc1.0E-7 mCi/cc3.0E+2cpm6.0E+2cpm*

1.0E+5cpm*

2.0E+4cpm*TableR-1EffluentMonitorClassificationThresholdsReleasePointMonitorGESAEAlertUEPlantVentMainSteamOilyWaterSeparatorEffluentLiquidRadwasteDischargeLineEffluentSGBDTankLiquidEffluent---------------3.0E-9amps2.0E+1 mCi/cc3.0E+5cpm---------------*Witheffluentdischargenotisolated1(2)-RM-14/14R1(2)-RM-24/24R1(2)-RM-28/28R1(2)-RM-871(2)-RM-71/72/73/74WithSteamDumporoneormoreSRVsopenonaffectedSG0-RM-30-RM-181(2)-RM-23GaseousLiquid--------------------AbnormalRadLevelRadEffluent R GENERALEMERGENCY SITEAREAEMERGENCY ALERT UNUSUALEVENT 2OffsiteRadConditions 1NoneHS4.1AhostileactionisoccurringorhasoccurredwithintheProtectedAreaasreportedbytheSecurityWatch CommanderHA1.1EFM"Alert"alarmorCPM-4,"Earthquake"indicatesOperatingBasisEarthquake(>0.2gonthe"X"or"Y"axisor>0.133gonthe"Z"axis)exceededHG4.1AhostileactionhasoccurredsuchthatplantpersonnelareunabletooperateequipmentrequiredtomaintainsafetyfunctionsORAhostileactionhascaused:FailureofSpentFuelCoolingsystemsANDImminentfueldamageislikelyforafreshlyoffloadedreactorcoreinpoolAhostileactionisoccurringorhasoccurredwithintheOwnerControlledAreaasreportedbytheSecurityWatch CommanderORAvalidnotificationfromNRCofanairlinerattackthreat within30min.ofthesiteHU4.1AsecurityconditionthatdoesnotinvolveahostileactionasreportedbytheSecurityWatchCommanderORAcrediblesite-specificsecuritythreatnotificationORAvalidnotificationfromNRCprovidinginformationofanaircraftthreatHA4.1HU1.1SeismiceventidentifiedbyANYTWOofthefollowing:-Earthquakefeltinplant-SeismiceventconfirmedbyPK15-24mainannunciator"SEISMICINSTRSYSTEM"-U.S.GeologicalSurvey(USGS)HU2.1FireinbuildingsorareascontiguoustoANYTableH-1areanotextinguishedwithin15min.ofControlRoomnotificationorvalidationofaControlRoomalarm(Note3)HA2.1FireorexplosionresultinginEITHER:-VisibledamagetoanyTableH-1plantstructurescontainingsafetysystemsorcomponents-ControlRoomindicationofdegradedperformanceofsystemsrequiredtoestablishormaintainsafeshutdown(Note3)HU3.1Reportordetectionoftoxic,corrosive,asphyxiantorflammablegasesthathaveenteredorcouldentertheOwnerControlledAreainamountsthatcanadverselyaffectnormal plantoperationsHA3.1Reportordetectionoftoxic,corrosiveorasphyxiantgaseswithinorcontiguoustoANYTableH-1areainconcentrationsthatmayresultinanatmosphereImmediatelyDangeroustoLifeandHealth(IDLH)NaturalanddestructivephenomenaaffectingtheProtectedAreaHU1.2Reportbyplantpersonneloftornadoorhighwinds>80mph(36.36m/sec)strikingwithinProtectedAreaboundaryHU2.2ReportbyplantpersonnelofanunanticipatedexplosionwithinProtectedAreaboundaryresultinginvisibledamage topermanentstructureorequipment(Note3)HU1.3ReportofturbinefailureresultingincasingpenetrationordamagetoturbineorgeneratorsealsHU1.4UncontrolledfloodinginANYTableH-1areathathasthepotentialtoaffectsafetyrelatedequipmentneededforthecurrentoperatingmodeHU1.5Hurricanewarningortsunami(actualorwarning)affectingtheProtectedAreaNaturalanddestructivephenomenaaffectingtheplantVitalAreaHA1.2Tornadoorhighwinds>80mph(36.36m/sec)withinProtectedAreaboundaryandresultinginvisibledamageto ANYTableH-1plantstructures/equipmentorControlRoomindicationofdegradedperformanceofthosesystemsHA1.3VehiclecrashwithinProtectedAreaboundaryandresultinginvisibledamagetoANYTableH-1plantstructuresorequipmentorcontrolroomindicationofdegradedperformanceofthose systems(Note2)HA1.4Turbinefailure-generatedmissilesresultinANYvisibledamagetoorpenetrationofANYTableH-1areaHA1.5UncontrolledfloodinginANYTableH-1areathatresultsindegradedsafetysystemperformanceasindicatedintheControlRoomorthatcreatesindustrialsafetyhazards(e.g.,

electricshock)thatprecludesaccessnecessarytooperateormonitorsafetyequipmentFirewithinProtectedAreaboundarynotextinguishedwithin15minutesofdetectionFireorexplosionaffectingtheoperabilityofplantsafetysystems requiredtoestablishormaintainsafeshutdownReleaseoftoxic,corrosive,asphyxiantorflammablegaseswithinorcontiguoustoaVitalAreawhichjeopardizesoperationofsystems requiredtoestablishormaintainsafeshutdownReleaseoftoxic,corrosive,asphyxiantorflammablegasesdeemed detrimentaltonormaloperationoftheplantHU3.2Recommendationbylocal,countyorstateofficialstoevacuateorsheltersitepersonnelbasedonoffsiteeventHA3.2Reportordetectionofgasesinconcentration>theLowerFlammabilityLimitwithinorcontiguoustoANYTableH-1areaConfirmedsecurityconditionorthreatwhichindicatesapotentialdegradationinthelevelofsafetyoftheplantHostileactionwithintheOwnerControlledArea orairborneattackthreatHostileactionwithintheProtectedAreaHostileactionresultinginlossofphysicalcontrolofthefacilityHU6.1OtherconditionsexistingwhichinthejudgmentoftheSM/SEC/ED warrantdeclarationofaUEOtherconditionsexistwhichinthejudgmentoftheSM/SEC/EDindicatethateventsareinprogressorhaveoccurredwhichindicateapotentialdegradationofthelevelof safetyoftheplant.Noreleasesofradioactivematerialrequiringoffsiteresponseormonitoringareexpectedunless furtherdegradationofsafetysystemsoccursEntryintoOPAP8A,ControlRoomInaccessibility,forControlRoomevacuationHA5.1ControlRoomevacuationhasbeeninitiatedHS5.1ControlRoomevacuationhasbeeninitiatedANDControloftheplantcannotbeestablishedperOPAP-8A,ControlRoomInaccessibility,within15min.ControlRoomevacuationhasbeeninitiatedandplantcontrolcannotbeestablishedOtherconditionsexistwhichinthejudgmentoftheSM/SEC/EDindicatethatareinprogressorhaveoccurredwhichinvolveanactualorpotentialsubstantialdegradation ofthelevelofsafetyoftheplant.ANYreleasesareexpectedtobelimitedtosmallfractionsoftheEPAProtectiveActionGuidelineexposurelevels(1RemTEDEand5RemthyroidCDE)HA6.1OtherconditionsexistingwhichinthejudgmentoftheSM/SEC/EDwarrantdeclarationofanAlertHS6.1OtherconditionsexistwhichinthejudgmentoftheSM/SEC/EDindicatethateventsareinprogressorhaveoccurredwhichinvolveanactualorlikelymajorfailuresof plantfunctionsneededforprotectionofthepublic.ANYreleasesarenotexpectedtoresultinexposurelevelswhichexceedEPAProtectiveActionGuidelineexposurelevels(1 RemTEDEand5RemthyroidCDE)beyondthesiteboundaryOtherconditionsexistingwhichinthejudgmentoftheSM/SEC/EDwarrantdeclarationofSiteAreaEmergencyHG6.1OtherconditionsexistwhichinthejudgmentoftheSM/SEC/EDindicatethateventsareinprocessorhaveoccurredwhichinvolveactualorimminentsubstantialcore degradationormeltingwithpotentialforlossofcontainmentintegrityorsecurityeventsthatresultinanactuallossofphysicalcontrolofthefacility.ReleasescanbereasonablyexpectedtoexceedEPAProtectiveActionGuidelineexposurelevels(1RemTEDEand5RemthyroidCDE) offsiteformorethanthesiteboundaryOtherconditionsexistingwhichinthejudgmentoftheSM/SEC/EDwarrantdeclarationofGeneralEmergencyNoneNoneTableH-1VitalAreas-Containment-AuxiliaryBuilding

-FuelHandlingBuilding

-TurbineBuilding

-IntakeStructure

-RWST

-CST56DEF123456DEF123456DEF123456DEF123456DEF123456DEF123456DEF123456DEF123456DEF123456DEF123456DEF123456DEF123456DEF123456DEF123456DEF123456DEF1234Hazards HNatural&DestructivePhenomenaFireorExplosionControlRoomEvacuationToxicandFlammableGasSecurityJudgment 1 2 3 4 5 656DEF1234Note2:Ifvehiclecrashisahostileaction,seeSubcategoryH.4EALsforpossibleclassificationNoneNoneNoneEU1.1DamagetoaloadedcaskconfinementboundaryDamagetoaloadedcaskconfinementboundaryasindicatedbyEITHER:OccurrenceofANYTableE-1event/conditionORBeyondnormalISFSIradiationreadingModeapplicabilityisN/AforISFSIISFSI ENoneNote3:Ifthefireorexplosionisahostileaction,seeSubcategoryH.4EALsforpossibleclassificationNaturalPhenomena-Highwind-Tornado-Earthquake-LightningstrikeTableE-1ISFSIEvents/Conditions-Caskdrop

-Casktip-over-Caskairinlet/outletblockage-Fire

-Explosion-Vehicleimpact-Airbornemissile-Transmissiontowercollapse-500kVtransmissionlinedropAccidentsNaturalanddestructivephenomenaaffectingtheProtectedArea56DEF123469-21608(06/19/12)Page1of1EPG-1 EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A 9 Initial Conditions:

GIVEN: Unit 1 is REFUELING Core off-loading is in progress Containment closure has been established The fuel handling crew in containment has just reported seeing bubbles in the transfer canal area from an assembly that has just been placed into the upender. Visual inspection showed the appearance of some structural damage to the assembly Radiation Monitor RE

-2 has also just alarmed, and reads 25 mR/hour at this time There are no other Radiation Monitors in alarm Initiating Cue:

The Shift Manager directs you to classify the event NRCL121-A 9 PAGE 4 OF 4 R EV. 0 NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: LJE0 17 Title: CLASSIFICATION OF A FUEL HANDLING ACCIDENT IN CONTAINMENT Examinee:

Evaluator:

Print Signature Date Testing Method:

Perform X Simulate Results: Sat Unsat Total Time: minutes Comments: (Note: Any Unsat step requires a numbered comment; use back as needed.)

References:

EP G-1, Accident Classification and Emer Plan Activation, Rev.43 Forms 69-21608, 69-21609, 69-21610 (06/19/12, 12/5/11, 12/5/11)

Alternate Path:

Yes No X Time Critical:

Yes X No Time Allotment:

15 minutes Critical Steps:

2 , 3 Job Designation:

SRO/STA Rev Comments/TIPs:

SAPN 50304333; TIPs 21257-91 DCPP Task # / Rating: 145400 4.5 / 4.0 Gen KA # / Rating

GEN.2.4.38 4.4 (SRO) AUTHOR: JOHN F. BUCKLEY DATE: 10/18/2010 APPROVED B Y: JOHN BECERRA DATE: 10/23/2010 TRAINING SUPERVISOR APPROVED B Y: ERIK WERNER DATE: 12/06/2010 LINE MANAGER R EV. 1B JPM TITLE: CLASSIFICATION OF A FUEL HANDLING ACCIDENT IN CONTAINMENT JPM NUMBER: LJ E0 1 7 INSTRUCTOR WORKSHEET Directions:

No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.

The examiner will then ask if any clarifications are needed. Since this is an administrative JPM, and the simulator is not used, the examinee may be given a copy of the required materials below.

Required Materials:

EP G-1, and EAL Wall Charts. Vol 11, Emergency Plan, App D (classification bases), should be available to the examinee.

Initial Conditions:

GIVEN: Unit 1 is REFUELING. Core off-loading is in progress and containment closure has been established The fuel handling crew in containment has just reported seeing bubbles in the transfer canal area from an assembly that has just been placed into the upender. Visual inspection showed the appearance of some structural damage to the assembly Radiation Monitor RE-2 has also just alarmed, and reads 25 mR/hour at this time There are no other Radiation Monitors in alarm Initiating Cue:

The Shift Manager has directed you to classify the event NOTE: Do NOT provide the student with the Task Standard.

Task Standard:

Reports to the Shift Manager, in less than 15 minutes, that Alert, RA2.1, is the appropriate emergency plan classification.

Damage to irradiated fuel resulting in a valid high alarm on RM-2 (21 mr/hr)

LJE 017.DOC PAGE 2 OF 4 R EV. 1B JPM TITLE: CLASSIFICATION OF A FUEL HANDLING ACCIDENT IN CONTAINMENT JPM NUMBER: LJ E0 1 7 INSTRUCTOR WORKSHEET Start Time: Step Expected Operator Actions

1. Obtain the correct procedure.

1.1 References EP G-1. Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

• • 2. Accurately classify the event.

2.1 Classifies the event as Alert, RA2.1 ** Classification made: _______________

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

• • 3. Classify the event in a timely manner. 3.1 Classifies the event

< 15 min. of the Event Initiation Time.

• • Classification Time: _____________

Event Initiation Time: _____________

(Event initiation time is JPM Start Time) Difference: ____________ min** Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for 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.

LJE 017.DOC PAGE 3 OF 4 R EV. 1B JPM NUMBER: LJ E0 1 7 EXAMINEE CUE SHEET Initial Conditions:

GIVEN: Unit 1 is REFUELING. Core off-loading is in progress and containment closure has been established The fuel handling crew in containment has just reported seeing bubbles in the transfer canal area from an assembly that has just been placed into the upender. Visual inspection showed the appearance of some structural damage to the assembly Radiation Monitor RE

-2 has also just alarmed, and reads 25 mR/hour at this time There are no other Radiation Monitors in alarm Initiating Cue:

The Shift Manager has directed you to classify the event LJE 017.DOC PAGE 4 OF 4 R EV. 1B NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE sNumber: NRCL121-S 1 Title: VERIFY MISALIGNED ROD IS NOT STUCK Examinee: Evaluator:

Print Signature Date Testing Method:

Perform X Simulate Results: Sat Unsat Total Time:

minutes Comments:

References:

OP AP-12B, Control Rod Misalignment, Rev. 14B Alternate Path:

Yes _______ No X Time Critical:

Yes No X Time Allotment:

1 5 minutes Critical Steps:

2 Job Designation:

RO or SRO Rev Comments:

Bank LJ C-066 Gen KA / Rating:

001 A2.03 - Ability to (a) predict the impacts of the following malfunction or operations on the CRDS

- and (b) based on those predictions,use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Effect of stuck rod or Misaligned rod 3.5/4.2 AUTHOR: L ISA TORIBIO DATE: 06/20/2014 OPERATIONS REPRESENTATIVE

ABDUL KADIR DATE: 06/20/2014 REV. 0 JPM TITLE: VERIFY MISALIGNED ROD IS NOT STUCK JPM NUMBER: NRCL121-S 1 EVALUATOR WORKSHEET Directions:

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. The examinee may be given the procedure and told the step with which to begin.

Required Materials:

None Initial Conditions GIVEN: Unit 1 is at approximately 75% power and was in the process of being returned to 100% following curtailment for condenser cleaning.

The power increase was stopped 5 minutes ago when control rod K2 was observed to be 12 steps below the other Control Bank D rods based on DRPI.

Procedure OP AP

-12B, Control Rod Misalignment has been implemented Initiating Cue:

The Shift Foreman directs you to verify that the misaligned rod is not stuck in accordance with OP AP

-12B, Step 14 DO NOT READ TASK STANDARD TO EXAMINEE Task Standard:

All actions of OP AP

-12B, step 14, completed, the status of control rod K2 verified(not stuck), the bank restored to its original position and the results reported the Shift Foreman NRCL121-S 1 PAGE 2 OF 6 R EV. 0 JPM TITLE: VERIFY MISALIGNED ROD IS NOT STUCK JPM NUMBER: NRCL121-S 1 EVALUATOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure.

1.1 Obtained copy of OP AP

-12B Sat: ______ Unsat _______

Comment: 2. Step 14.a

- Verify Misaligned Rod NOT STUCK - check CBD group counters 2.1 Read three CAUTIONS prior to step 14.a 2.2 Check ed both groups of bank D at the same step as the demand counter Step 14.b

- Record bank step counters (all banks) 2.3 Recorded ALL bank demand positions

• • Step 14.c

- Rotate Rod Bank Selector Switch to AFFECTED Bank 2.4 Rotated Rod Bank Selector switch to Control Bank D (CBD) **

Step 14.d

- Record PPC postion for the Bank Note: Operator may call up the CBD address listed in App. B o f AP-12B (U0052), or record the value from an existing PPC group display.

2.5 Displayed the Control Bank D position from the plant computer and records the value. ** Step 14.e

- Drive the affected bank in several steps (enough to see a DRPI change) 2.6 Inserted rods for Control Bank D until a DRPI change is observed **

• • Step 14.f

- Check misaligned rod DRPI position changes with bank position.

2.7 Checked that rod K2 moves and diagnose d that rod K2 is not stuck. **

(must verbalize to examiner or SFM)

• • Step 14. G - g. Return the rods in the affected bank to the step counter position recorded in Step 14.b 2.8 Withdr ew Control Bank D until the bank was restored to its previously recorded position ** Sat: ______ Unsat _______

Comment: NRCL121-S 1 PAGE 3 OF 6 R EV. 0 JPM TITLE: VERIFY MISALIGNED ROD IS NOT STUCK JPM NUMBER: NRCL121-S 1 EVALUATOR WORKSHEET Stop Time:

Total Time:

(Enter total time on the cover page)

Follow up Question Documentation

Question: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

Response: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

NRCL121-S 1 PAGE 4 OF 6 R EV. 0 JPM Title:

VERIFY MISALIGNED ROD IS NOT STUCK JPM Number: NRCL121-S 1 Attachment 1, Simulator Setup Restore the simulator to IC

-11 (75%, MOL).

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

Run Lesson NRCL121

-LJCS1.lsn Place Rod Control Switch to Manual after simulator goes to freeze.

Inform the examiner that the simulator setup is complete.

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

NRCL121-S 1 PAGE 5 OF 6 R EV. 0 EXAMINEE CUE SHEET JPM NUMBER: NRCL121-S 1 Initial Conditions:

GIVEN: Unit 1 is at approximately 75% power and was in the process of being returned to 100% following curtailment for condenser cleaning.

The power increase was stopped 5 minutes ago when control rod K2 was observed to be 12 steps below the other Control Bank D rods based on DRPI.

Procedure OP AP

-12B, Control Rod Misalignment has been implemented Initiating Cue:

The Shift Foreman directs you to verify that the misaligned rod is not stuck in accordance with OP AP

-12B, Step 14

NRCL121-S 1 PAGE 6 OF 6 R EV. 0 PACIFIC GAS AND ELECTRIC COMPANY NUMBER OP AP-12B DIABLO CANYON POWER PLANT REVISION 14B

PAGE 5 OF 13 TITLE: Control Rod Misalignment UNITS 1 AND 2 OP_AP-12Bu3r14.DOC 02 0907.0956 *** UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

14. VERIFY Misaligned Rod is NOT STUCK:

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • CAUTION 1: If driving in the rods a few steps will cause the rod bank to go below the Low Low Insertion Limit, reduce load before driving the rods in. CAUTION 2: An open Movable Gripper coil or fuse will cause further misalignment during the following steps, immediately stop rod motion if this occurs. CAUTION 3: If rod misalignment is suspected based on symp toms other than rod position versus demand indication, then contact Plant Reactor Engineering Group for guidance before proceeding to move the misaligned rod.

a. CHECK GRP 1 AND GRP 2 OF EACH BANK - AT THE SAME STEP ON DEMAND STEP COUNTER a. Align each group in the bank to the same demanded step 1) Select MANUAL on Rod Control Selector Switch for adjusting the Control Banks. 2) Select Individual Bank on the Rod Control Selector Switch to adjust Shutdown banks.

b. Record bank demand positions: Bank Grp 1 Steps Grp 2 Steps Control Bank A Control Bank B Control Bank C Control Bank D Shutdown Bank A Shutdown Bank B Shutdown Bank C Shutdown Bank D

c. Rotate the Rod Bank Selector Switch to the - AFFECTED BANK

d. Record the Plant Processor Computer position for the Bank (see Appendix B for the Address)

Bank Position __

________________

THIS STEP CONTINUED ON NEXT PAGE PACIFIC GAS AND ELECTRIC COMPANY NUMBER OP AP-12B DIABLO CANYON POWER PLANT REVISION 14B

PAGE 6 OF 13 TITLE: Control Rod Misalignment UNITS 1 AND 2 OP_AP-12Bu3r14.DOC 02 0907.0956 *** UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

14. VERIFY Misaligned Rod is NOT STUCK: (Continued)

e. Drive the affected bank in several steps (enough to see a DRPI change)

f. Check misaligned rod DRPI position changes with bank position. f. Contact Reactor Engineering Group for guidance concerning the stuck rod.

g. Return the rods in the affected bank to the step counter position recorded in Step 14.b.

NOTE 1: During rod recovery, an URGENT FAILURE alarm (PK03-17) will occur if the misaligned rod is in any bank other than Shutdown Bank C or D. NOTE 2: For Control and Shutdown Banks, the PPC will show bank position (Refer to Appendix B for addressable points). If affected bank is Control Bank D, its position is also shown on the P/A converter HMI (P/A Converter Cabinet PNPAC, back of DC Hold Cabinet, 115' Aux Bldg).

15. RESTORE Rod Bank Alignment:

a. Verify power is reduced as necessary such that the steady state power level attained after the rod is recovered is LESS THAN power level determined in Step 13. b. RECORD the Misaligned Rod As Found Position: Bank _______________

Position _______________

c. Open Lift Coil Disconnect Switches on All Rods in the Affected Bank Except the Misaligned Rod

d. Set Affected Group Step Counter - TO THE DRPI POSITION OF THE MISALIGNED ROD.

THIS STEP CONTINUED ON NEXT PAGE NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: LJC-066 Title: VERIFY MISALIGNED ROD IS NOT STUCK Examinee:

Evaluator:

Print Signature Date Testing Method:

Perform Simulate Results: Sat Unsat Total Time: minutes Comments: (Note: Any Unsat step requires a numbered comment; use back as needed.)

References:

OP AP-12B, Control Rod Misalignment, Rev. 14B Alternate Path:

Yes No X Time Critical:

Yes No X Time Allotment:

15 minutes Critical Steps:

4 , 6 , 7 Job Designation:

RO/SRO Rev Comments/TIPs:

SAPN 50304333; TIPs 20669

-33, 21256-43 EC revision 24C was for Simulator terminology changes.

EC approved by LOB supervisor.

DCPP Task # / Rating: 80200 4.0 Gen KA # / Rating

001.A2.03 3.5 / 4.2 AUTHOR: JOHN F. BUCKLEY DATE: 09/13/2010 APPROVED B Y: JOHN BECERRA DATE: 09/19/2010 TRAINING SUPERVISOR APPROVED B Y: KEN JOHNSTON DATE: 09/27/2010 LINE MANAGER R EV. 24B JPM TITLE: VERIFY MISALIGNED ROD I S NOT STUCK JPM NUMBER: LJC-066 INSTRUCTOR WORKSHEET Directions:

No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The task standard will NOT be read to the student. 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 approximately 75% power and was in the process of being returned to 100% following curtailment for condenser cleaning. The power increase was stopped 5 minutes ago when control rod K2 was observed to be 12 steps below the other Control Bank D rods based on DRPI. Procedure OP AP-12B, Control Rod Misalignment has been implemented. Initiating Cue:

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

NOTE: Do NOT provide the student with the Task Standard.

Task Standard:

All actions of OP AP-12B, step 14, have been completed and the status of control rod K2 (stuck or not stuck) has been verified, and the results reported the Shift Foreman. LJC066.DOC PAGE 2 OF 6 R EV. 24B JPM TITLE: VERIFY MISALIGNED ROD I S NOT STUCK JPM NUMBER: LJC-066 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure.

1.1 References OP AP-12B. Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

2. Check Grp 1 and grp 2 of each bank - at the same step on demand step counter.

2.1 Reads CAUTIONS prior to Step 14.a. 2.2 Checks both groups of bank D at the same step as the demand counter.

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

3. Record the bank step counter position for all control banks and shutdown banks.

3.1 Records the bank demand positions.

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

• • 4. Place the bank selector to the affected bank.

4.1 Turns the ROD BANK/MODE SELECT switch to the CBD position.

• • Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps. LJC066.DOC PAGE 3 OF 6 R EV.24B JPM TITLE: VERIFY MISALIGNED ROD I S NOT STUCK JPM NUMBER: LJC-066 INSTRUCTOR WORKSHEET Step Expected Operator Actions

5. Record the plant process computer position for the affected bank.

5.1 Displays the Control Bank D position from the plant computer and records the value.

Note: Operator may call up the CBD address listed in App. B of

AP-12B (U0052), or record the value from an existing group display. Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

• • 6. Drive the affected bank in several steps (enough to see a DRPI change). 6.1 Inserts rods for Control Bank D until a DRPI change is observed.

• • 6.2 Checks that rod K2 moves and diagnoses that rod K2 is not stuck.

• • (must verbalize to examiner or SFM) 6.3 Reports status to Shift Foreman.

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

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

• • 7. Return the rods in the affected bank to the position recorded in OP AP-12B, Step 14.a.

7.1 Withdraws Control Bank D until the bank is restored to its previously recorded position. **

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

Stop Time:

Total Time:

(Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps. LJC066.DOC PAGE 4 OF 6 R EV.24B JPM TITLE: VERIFY MISALIGNED ROD I S NOT STUCK JPM NUMBER: LJC-066 ATTACHMENT 1, SIMULATOR SETUP Restore the simulator to IC-11 (75%, MOL). Verify step counters and RBU are updated to current CBD rod position. Enter Lesson Drill file 1066 Description Sets rod k2 15 steps below Bank Run simulator for 90 seconds Place Rod Control Switch to Manual after simulator goes to freeze.

Inform the examiner that the simulator setup is complete.

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

LJC066.DOC PAGE 5 OF 6 R EV.24B JPM NUMBER: LJC-066 EXAMINEE CUE SHEET Initial Conditions:

Unit 1 is at approximately 75% power and was in the process of being returned to 100% following curtailment for condenser cleaning. The power increase was stopped 5 minutes ago when control rod K2 was observed to be 12 steps below the other Control Bank D rods based on DRPI. Procedure OP AP-12B, Control Rod Misalignment has been implemented.

Initiating Cue:

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

LJC066.DOC PAGE 6 OF 6 R EV.24B NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-S 2 Title: MANUALLY ISOLATE PHASE A COMPONENTS

- TRAIN A & B FAILURES Examinee: Evaluator:

Print Signature Date Testing Method:

Perform X Simulate Results: Sat Unsat Total Time:

minutes Comments:

References:

EOP E-0, Reactor Trip or Safety Injection, Rev 43 Alternate Path:

Yes __X No Time Critical:

Yes No X Time Allotment:

1 0 minutes Critical Steps:

4, 5, 6 , 7 Job Designation:

RO or SRO Rev Comments:

Bank LJC-026 Gen KA / Rating:

013.A4.01 - Ability to manually operate and/or monitor in the control room:

ESFAS-initiated equipment which fails to actuate 4.5/4.8 AUTHOR: L ISA TORIBIO DATE: 06/20/2014 OPERATIONS REPRESENTATIVE

ABDUL KADIR DATE: 06/20/2014 REV. 0 JPM TITLE: MANUALLY ISOLATE PHASE A COMPONENTS

- TRAIN A & B FAILURES JPM NUMBER: NRCL121-S 2 EVALUATOR WORKSHEET Directions:

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. The examinee may be given the procedure and told the step with which to begin.

Required Materials:

E-0, Reactor Trip or Safety Injection, Appendix E Initial Conditions A Unit 1 reactor trip and safety injection have occurred Initiating Cue:

You are directed by the Shift Foreman to verify Containment Isolation Phase A in accordance with Appendix E, step 3, of EOP E

-0 DO NOT READ TASK STANDARD TO EXAMINEE Task Standard:

Containment Isolation Phase A completed in accordance with EOP E

-0 App E, step 3, and no non

-Phase A valves or equipment manipulated/operated. NRCL121-S 2 PAGE 2 OF 7 R EV. 0 JPM TITLE: MANUALLY ISOLATE PHASE A COMPONENTS

- TRAIN A & B FAILURES JPM NUMBER: NRCL121-S 2 EVALUATOR WORKSHEET Start Time:

Step Expected Operator Actions 1. Obtain the correct procedure.

1.1 References EOP E

-0, Appendix E, Step 3.

Sat: ______ Unsat _______

Comment: 2. Step 3 - Ensure Phase A actuated 2.1 Observed the following on the CONTAINMENT ISOLATION PHASE "A" portion of Monitor Light Box B:

Train A red activate light

- OFF Train B red activate light

- OFF White status lights

- ON 2.2 Determined Phase A actuated but has not fully isolated containment Sat: ______ Unsat _______

Comment: 3. Step 3 RNO

- Manually close Phase A valves with White Status lights ON Note: Operator may manually actuate PHASE A Isolation, but this will not work. Alignment steps (as well as the valves themselves) that follow may be performed in any order. 3.1 Turned the Phase A actuation switch to ACTUATE. (optional) 3.2 Positioned the MONITOR LIGHT TEST switch to TEST.

3.3 Identified open Phase A Isol valves using the CONTAINMENT ISOLATION PHASE "A" portion of Monitor Light Box (MLB) or Control Board switch indications.

Sat: ______ Unsat _______

Comment: NRCL121-S 2 PAGE 3 OF 7 R EV. 0 JPM TITLE: MANUALLY ISOLATE PHASE A COMPONENTS

- TRAIN A & B FAILURES JPM NUMBER: NRCL121-S 2 EVALUATOR WORKSHEET Step Expected Operator Actions 4.** Step 3 RNO (continued)

- Close valves on VB1 4.1 Closed each open Containment Isolation Phase A valve on VB

-1. ** 9355A/B 9356A/B 8880 4.2 Verified that each Containment Isolation Phase A valve has closed (Red light OFF, Green light ON, and/or white light OFF on MLB). Sat: ______ Unsat _______

Comment: 5.** Step 3 RNO (continued)

- Close valves on VB2 5.1 Closed each open Containment Isolation Phase A valve on VB

-2. ** 8149C RW isolations IC and OC 8152 8045 8 029 8100 8112 5.2 Verified that each Containment Isolation Phase A valve has closed (Red light OFF, Green light ON, and/or white light OFF on MLB). Sat: ______ Unsat _______

Comment: NRCL121-S 2 PAGE 4 OF 7 R EV. 0 JPM TITLE: MANUALLY ISOLATE PHASE A COMPONENTS

- TRAIN A & B FAILURES JPM NUMBER: NRCL121-S 2 EVALUATOR WORKSHEET Step Expected Operator Actions 6.** Step 3 RNO (continued)

- Close valves on VB3 6.1 Closed open Containment Isolation Phase A valve on VB

-3. ** FCV-633 6.2 Verified that each Containment Isolation Phase A valve has closed (Red light OFF, Green light ON, and/or white light OFF on MLB). Sat: ______ Unsat _______

Comment: 7.** Step 3 RNO (continued)

- Close valves on VB 4 7.1 Closed open Containment Isolation Phase A valve on VB

-3. ** FCV-584 7.2 Verified that each Containment Isolation Phase A valve has closed (Red light OFF, Green light ON, and/or white light OFF on MLB). Sat: ______ Unsat _______

Comment: Stop Time:

Total Time:

(Enter total time on the cover page)

Follow up Question Documentation

Question: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

Response: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

NRCL121-S 2 PAGE 5 OF 7 R EV. 0 JPM TITLE: MANUALLY ISOLATE PHASE A COMPONENTS

- TRAIN A & B FAILURES JPM NUMBER: NRCL121LJC-S2 ATTACHMENT 1, SIMULATOR SETUP Initialize the simulator to IC

-10 (100%, MOL).

Enter lesson file NRCL121-LJCS2.lsn: Inform the examiner that the simulator setup is complete.

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

NRCL121-S 2 PAGE 6 OF 7 R EV. 0 EXAMINEE CUE SHEET JPM NUMBER: NRCL121-S 2 Initial Conditions:

A Unit 1 reactor trip and safety injection have occurred Initiating Cue:

You are directed by the Shift Foreman to verify Containment Isolation Phase A in accordance with Appendix E, step 3, of EOP E

-0 NRCL121-S 2 PAGE 7 OF 7 R EV. 0 PACIFIC GAS AND ELECTRIC COMPANY NUMBER EOP E-0 DIABLO CANYON POWER PLANT REVISION 43

PAGE 20 OF 36 TITLE: Reactor Trip or Safety Injection UNIT 1 EOP_E-0u1r43.DOC 03A 1220.0812

• • • UNCONTROLLED DOCUMENT - DO NOT USE TO PERFORM WORK or ISSUE FOR USE *** APPENDIX E ESF AUTO ACTIONS, SECONDARY AND AUXILIARIES STATUS ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

1. NOTIFY Plant Personnel

a. Check NO personnel in containment

a. Actuate Containment Evacuation Alarm.

b. Announce Reactor Trip/SI on PA system 2. CHECK Main Generator Tripped:

a. PK14-01, Unit Trip - ON a. IF Backfeeding, THEN GO TO Step 3. IF NOT Backfeeding, THEN Manually initiate a Main Unit Trip.

b. 500KV bkrs - Both Open

1. Green lights - ON OR 2. Turbine speed - LOWERING b. Open Main Gen Output Bkrs 532 and 632. IF Either breaker will NOT open, THEN Notify GCC Diablo Control (8-449-6717) to isolate Unit 1 at the 500KV switchyard.

c. Exciter Field Breaker - Open c. WHEN Both 500KV bkrs open, THEN Open the Exciter Field Breaker manually or locally.

3. ENSURE Containment Isolation Phase A:

a. Phase A portion of Monitor Light Box B: Red Activated Lights-ON White Status Lights-OFF Perform the following: Manually actuate CONTMT ISOL PHASE A, OR Manually Close the Phase A Isol vlvs with White Status Lights-ON.

4. ENSURE Containment Vent Isol:

a. Containment Vent Isol portion of Monitor Light Box B: Red Activated Lights - ON White Status Lights - OFF Perform the following: Actuate CVI by Manual CONTMT ISOL PHASE A, OR Manually Close the CVI vlvs with White Status Lights-ON.

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: LJC-026 Title: MANUALLY ISOLATE PHASE A COMPONENTS

- TRAIN A & B FAILURES Examinee:

Evaluator:

Print Signature Date Testing Method:

Perform Simulate Results: Sat Unsat Total Time: minutes Comments: (Note: Any Unsat step requires a numbered comment; use back as needed.)

References:

EOP E-0, Reactor Trip or Safety Injection, Rev 43 Alternate Path:

Yes X No Time Critical:

Yes No X Time Allotment:

10 minutes Critical Steps:

3, 4, 5, 6 Job Designation:

RO/SRO Rev Comments/TIPs:

Revision 30 is for Attachment 1 changes due to new L

-3 simulator program and minor word replacement.

TIP 22427-46 incorporated for PCS validation.

DCPP Task # / Rating: 197200 4.3 Gen KA # / Rating

013.A4.01 4.5 / 4.8 AUTHOR: O RRIN OLIVER/LISA TORIBIO DATE: 04/24/14 REVIEWED B Y: . DATE: . TRAINING SUPERVISOR A PPROVED B Y: . DATE: . LINE MANAGER R EV. 30 JPM TITLE: MANUALLY ISOLATE PHASE A COMPONENTS

- TRAIN A & B FAILURES JPM NUMBER: LJC-026 INSTRUCTOR WORKSHEET Directions:

No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.

The examiner will then ask if any clarifications are needed. If the task is being done in the plant or lab, and after identifying the appropriate procedure for the task, the examinee may be given the procedure and told what step to begin the task at. Required Materials:

Provide a copy of the reference procedure (partial procedure allowed), if the task is being done in the plant or lab. Initial Conditions:

A Unit 1 reactor trip and safety injection has occurred. Initiating Cue:

You are directed by the Shift Foreman to verify Containment Isolation Phase A in accordance with Appendix E, step 3, of EOP E-0. NOTE: Do NOT provide the student with the Task Standard.

Task Standard:

Containment Isolation Phase A is complete in accordance with EOP E-0 App E, step 3, and no non Phase A valves or equipment have been manipulated. LJC026.DOC PAGE 2 OF 8 R EV. 30 JPM TITLE: MANUALLY ISOLATE PHASE A COMPONENTS

- TRAIN A & B FAILURES JPM NUMBER: LJC-026 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure.

1.1 References EOP E-0, Appendix E, Step 3. Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

2. Ensure Containment Isolation Phase A. 2.1 Observes the following on the CONTAINMENT ISOLATION PHASE "A" portion of Monito r

Light Box B: Train A red activate light

- O FF Train B red activate light

- OFF White status lights

- O FF Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps. LJC026.DOC PAGE 3 OF 8 R EV. 30 JPM TITLE: MANUALLY ISOLATE PHASE A COMPONENTS

- TRAIN A & B FAILURES JPM NUMBER: LJC-026 INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 3. Manually aligns Phase A equipment on VB-1 Note: Operator may manually actuate PHASE A Isolation, but this will not work. Alignment steps (as well as the vales themselves) that follow may be performed in any order.

3.1 Turns the Phase A actuation switch to ACTUATE. (optional) 3.2 Positions the MONITOR LIGHT TEST switch to TEST.

3.3 Identifies open Phase A Isol valves using the CONTAINMENT ISOLATION PHASE "A" portion of Monitor Light Box B or Control Board switch indications.

3.4 Closes each open Containment Isolation Phase A valve on VB-1.

• • 9355A/B 9356A/B 8880 3.5 Ensures that each Containment Isolation Phase A valve has closed (Red light OFF, Green light ON, and/or white light OFF on MLB).

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps. LJC026.DOC PAGE 4 OF 8 R EV. 30 JPM TITLE: MANUALLY ISOLATE PHASE A COMPONENTS

- TRAIN A & B FAILURES JPM NUMBER: LJC-026 INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 4. Manually aligns Phase A equipment on VB-2 4.1 Identifies open Phase A Isol valves using the CONTAINMENT ISOLATION PHASE "A" portion of Monitor Light Box B or Control Board switch indications.

4.2 Closes each open Containment Isolation Phase A valve on VB-2.

• • 8149C RW isolations IC and OC 8152 8045 8029 8100 8112 4.3 Ensures that each Containment Isolation Phase A valve has closed (Red light OFF, Green light ON, and/or white light OFF on MLB).

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

• • 5. Manually aligns Phase A equipment on VB-3 5.1 Identifies open Phase A Isol valves using the CONTAINMENT ISOLATION PHASE "A" portion of Monitor Light Box B or Control Board switch indications.

5.2 Closes each open Containment Isolation Phase A valve on VB-3.

• • FCV-633 5.3 Ensures that each Containment Isolation Phase A valve has closed (Red light OFF, Green light ON, and/or white light OFF on MLB).

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps. LJC026.DOC PAGE 5 OF 8 R EV. 30 JPM TITLE: MANUALLY ISOLATE PHASE A COMPONENTS

- TRAIN A & B FAILURES JPM NUMBER: LJC-026 INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 6. Manually aligns Phase A equipment on VB-4 6.1 Identifies open Phase A Isol valves using the CONTAINMENT ISOLATION PHASE "A" portion of Monitor Light Box B or Control Board switch indications.

6.2 Closes each open Containment Isolation Phase A valve on VB-4.

• • FCV-584 6.3 Ensures that each Containment Isolation Phase A valve has closed (Red light OFF, Green light ON, and/or white light OFF on MLB).

Note: ALL white lights on the Phase A MLB should now be OFF.

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

Stop Time:

Total Time:

(Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps. LJC026.DOC PAGE 6 OF 8 R EV. 30 JPM TITLE: MANUALLY ISOLATE PHASE A COMPONENTS

- TRAIN A & B FAILURES JPM NUMBER: LJC-026 ATTACHMENT 1, SIMULATOR SETUP Restore the simulator to IC-10 (100%, MOL). Enter Lesson Drill file 1026 or manually insert the following:

Command Description insert MAL_PPL1A 2 insert MAL_PPL1B 2 Phase A Failure Train A

/ B insert MAL_PPL2A 1 delIA MAL_PPL2A 2 delay=2 insert MAL_PPL2B 1 delIA MAL_PPL2B 2 delay=2 Inadvertent S1 Actuation Train A RUN, then FRZ after 40 seconds Runs simulator.

Inform the examiner that the simulator setup is complete.

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

LJC026.DOC PAGE 7 OF 8 R EV. 30 JPM NUMBER: LJC-026 EXAMINEE CUE SHEET Initial Conditions:

A Unit 1 reactor trip and safety injection have occurred.

Initiating Cue:

You are directed by the Shift Foreman to verify Containment Isolation Phase A in accordance with Appendix E, step 3, of EOP E-0.

LJC026.DOC PAGE 8 OF 8 R EV. 30 NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-S 3 Title: ENERGIZE VITAL BUSES FROM THE 230KV SYSTEM Examinee: Evaluator:

Print Signature Date Testing Method:

Perform X Simulate Results: Sat Unsat Total Time:

minutes Comments:

References:

EOP ECA-0.3, Restore Vital 4KV Busses, Rev 17 Alternate Path:

Yes ______X No Time Critical:

Yes No X Time Allotment:

2 5 minutes Critical Steps:

2, 4, 6, 7 Job Designation:

RO or SRO Rev Comments:

Gen KA / Rating:

055 EA1.07 - Ability to operate and monitor the following as they apply to a Station Blackout:

Restoration of power from offsite 4.3/4.5 AUTHOR: L ISA TORIBIO DATE: 06/20/2014 OPERATIONS REPRESENTATIVE

ABDUL KADIR DATE: 06/20/2014 REV. 0 JPM TITLE: ENERGIZE VITAL BUSES FROM THE 230KV SYSTEM JPM NUMBER: NRCL121-S 3 EVALUATOR WORKSHEET Directions:

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. The examinee may be given the procedure and told the step with which to begin.

Required Materials:

EOP ECA-0.3, Restore Vital 4KV Busses, Rev 17 Initial Conditions GIVEN: U-1 was at 100% power, when a loss of ALL OFFSITE power resulted in a reactor trip ALL DGs failed to start, and could not be started from the control room, or locally EOP ECA-0.3 has been implemented as directed by step 10 of ECA-0.0 Attempts to start Diesel Generators are in progress Initiating Cue:

The Shift Foreman directs you to implement EOP ECA

-0.3 starting at step 2, to attempt to restore power to any vital 4KV bus.

DO NOT READ TASK STANDARD TO EXAMINEE Task Standard:

ALL vital 4KV busses are energized from U

-2 startup power, crosstied to U-1 per EOP ECA

-0.3. NRCL121-S 3 PAGE 2 OF 9 R EV. 0 JPM TITLE: ENERGIZE VITAL BUSES FROM THE 230KV SYSTEM JPM NUMBER: NRCL121-S 3 EVALUATOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure.

1.1 References ECA

-0.3, step 2 Sat: ______ Unsat _______

Comment: 2.** Step 2 - Prepare buses for return of offsite power 2.1 Read NOTE prior to step 2.

2.2 Placed ALL (7) 4KV and 12KV auto

-transfer relay cutout switches in CUTOUT.

• • 2.3 Presse d ALL (7) auto

-transfer relay reset PBs to reset auto transfer relays. ** 2.4 Verifie d all (7) auto transfer relay blue lights OUT.

2.5 Place d all Condensate/Booster Pump Selector Switches in MANUAL.

2.6 Read Caution prior to verifying 4 and 12 kV breakers open 2.7 Verifie d that ALL 4kV and 12 kV Aux and S/U Fdr Bkrs are OPEN . Sat: ______ Unsat _______

Comment: 3. Step 3 - Verify SI Reset 3.1 Observed that SI signal is not present

- may reset SI again Sat: ______ Unsat _______

Comment: NRCL121-S 3 PAGE 3 OF 9 R EV. 0 JPM TITLE: ENERGIZE VITAL BUSES FROM THE 230KV SYSTEM JPM NUMBER: NRCL121-S 3 EVALUATOR WORKSHEET Step Expected Operator Actions 4.** Step 4 - Check 500 kV availabl e 4.1 Check ed the status of 500KV power (may use sync key on CC3 and/or phone call).

4.2 **********************************

Cue: 500KV power is NOT available; it is expected back in 2 to 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

4.3 Continue d to next step per step 4 RNO.

Comment: 5. Step 5 - Check 230 kV available 5.1 Checked status of CB

-212 (visual check at VB-5, and/or phone call).

Cue: (from SM) 230KV power is stable, and CB

-212 is closed.

• • • • • • • • • 5.2 Observe d that S/U transformer power available light is NOT ON, and goes to step 5b RNO actions.

Cue: (from SM) S/U transformer 1

-1 is faulted, and has been isolated.

NRCL121-S 3 PAGE 4 OF 9 R EV. 0 JPM TITLE: ENERGIZE VITAL BUSES FROM THE 230KV SYSTEM JPM NUMBER: NRCL121-S 3 EVALUATOR WORKSHEET Step Expected Operator Actions 6.** Step 5.b RNO - close VU-11 6.1 Observed that U-2 S/U crosstie is energized (white light on VB-5 above VU-11 is ON) ********************************** Cue: (if asked) U-2 SFM reports that VU-24 is closed, and U-2 S/U bus voltage is stable.

Note: If, during the following step, VU-12 is closed in error, it is critiquable, but not a critical miss

-step. 6.2 Inserted sync key in VU-11, turned to ON, and closed VU-11 (may remove key when done). **

Step 5.d 6.3 Observed that S/U Transformer 1

-2 feeder VU-14 is CLOSED.

Step 5.e 6.4 Observed that S/U feeder to vital 4KV buses 52-HG-15 is CLOSED.

Comment: NRCL121-S3 PAGE 5 OF 9 R EV. 0 JPM TITLE: ENERGIZE VITAL BUSES FROM THE 230KV SYSTEM JPM NUMBER: NRCL121-S 3 EVALUATOR WORKSHEET Step Expected Operator Actions 7.** Step 5.f - Energize 4 kV Vital buses

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • Cue: The SFM reports that all ESF pump interlock devices have been installed.

7.1 Inserted Sync Key, turned ON, and CLOSED S/U breaker for Bus F. **

Note: Busses may be energized in any order. 7.2 Inserted Sync Key, turned ON, and CLOSED S/U breaker for Bus G. ** 7.3 Inserted Sync Key, turned ON, and CLOSED S/U breaker for Bus H. ** 7.4 Removed sync key (optional)

Sat: ______ Unsat _______

Comment:

Stop Time:

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

Follow up Question Documentation

Question: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

Response: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

NRCL121-S3 PAGE 6 OF 9 R EV. 0 JPM Title:

ENERGIZE VITAL BUSES FROM THE 230KV SYSTEM JPM Number:

NRCL121-S 3 Attachment 1, Simulator Setup Initialize the simulator to IC

-10 (100%, MOL).

Enter lesson file NRCL121

-LJCS3.lsn:

(Continued on Next Page)

A NRCL121-S 3 PAGE 7 OF 9 R EV. 0 JPM Title:

ENERGIZE VITAL BUSES FROM THE 230KV SYSTEM JPM Number:

NRCL121-S 3 Attachment 1, Simulator Setup (Continued from Previous Page)

A NRCL121-S 3 PAGE 8 OF 9 R EV. 0 EXAMINEE CUE SHEET JPM NUMBER: NRCL121-S 3 Initial Conditions:

GIVEN: U-1 was at 100% power, when a loss of ALL OFFSITE power resulted in a reactor trip ALL DGs failed to start, and could not be started from the control room, or locally EOP ECA-0.3 has been implemented as directed by step 10 of ECA

-0.0 Attempts to start Diesel Generators are in progress Initiating Cue:

The Shift Foreman directs you to implement EOP ECA

-0.3 starting at step 2, to attempt to restore power to any vital 4KV bus.

NRCL121-S 3 PAGE 9 OF 9 R EV. 0 PACIFIC GAS AND ELECTRIC COMPANY NUMBER EOP ECA-0.3 DIABLO CANYON POWER PLANT REVISION 17

PAGE 2 OF 29 TITLE: Restore 4kV Buses UNIT 1 EOP_ECA-0!3u1r17.DOC 03A 1220.0725 *** UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE***ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED *************************************************************************************** CAUTION 1: If a bus has been subjected to a significant electrical fault condition such as a large ground, then it should not be reenergized without an evaluation or equipment inspection. CAUTION 2: Energizing a 4 kV vital bus during bus stripping operations could cause a safety hazard to the local operator and should be done in a controlled, safe manner. ***************************************************************************************

1. CHECK D/G Associated with De-energized Bus - AVAILABLE: GO TO Step 2 (Next Page)

a. Start D/Gs either manually or locally a. Continue attempts to return D/Gs to service. REFER TO ANNUNCIATOR RESPONSE PROCEDURE for PK16, PK17 and PK18 Windows - ON for possible solutions to D/G FAILURE AND GO TO Step 2

b. Verify bus energized b. Continue attempts to energize the bus AND GO TO Step 2

c. RETURN TO Procedure and Step in effect NOTE: If the D/G associated with the deenergized bus is running but will not load on the bus, it must be shutdown to permit the Auto Transfer Relay to be reset.

2. PREPARE Buses for Return of Offsite Power

a. Place AUTO TRANSFER to START-UP CUTOUT switch in the CUTOUT position for all 4 kV and 12 kV buses

b. Depress the AUTO BUS TRANSFER Reset pushbuttons on all 4 kV and 12 kV buses Blue lights - OFF

c. Place all condensate and booster pump selector switches in MANUAL (VB-3)

THIS STEP CONTINUED ON NEXT PAGE

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EOP ECA-0.3 DIABLO CANYON POWER PLANT REVISION 17

PAGE 3 OF 29 TITLE: Restore 4kV Buses UNIT 1 EOP_ECA-0!3u1r17.DOC 03A 1220.0725 *** UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE***ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

2. PREPARE Buses for Return of Offsite Power (Continued)

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • CAUTION: Do not open a breaker that is supplying power to a bus. ***************************************************************************************

d. Open all Aux and Startup Feeders to Deenergized 4 kV Vital Buses F, G, & H 52-HH-13 52-HH-14 52-HG-13 52-HG-14 52-HF-13 52-HF-14 e. Open all Aux and Startup Feeders to Deenergized 4 kV Nonvital Buses D & E 52-HE-2 52-HE-3 52-HD-15 52-HD-14 f. Open all Aux and Startup Feeders to Deenergized 12 kV Buses D & E 52-VD-8 52-VD-4 52-VE-2 52-VE-6 3. VERIFY SI Reset

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EOP ECA-0.3 DIABLO CANYON POWER PLANT REVISION 17

PAGE 4 OF 29 TITLE: Restore 4kV Buses UNIT 1 EOP_ECA-0!3u1r17.DOC 03A 1220.0725 *** UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE***ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Power source availability is based on SFM discretion. Convenience, reliability and urgency are to be considered.

4. CHECK 500kV Power Available: GO TO Step 5 (Next Page)

a. IMPLEMENT OP J-2:V, BACKFEEDING THE UNIT FROM THE 500 kV SYSTEM

b. Close 4 kV Aux feeder Breakers to supply Vital Buses Bus H, 52-HH-13 Bus G, 52-HG-13 Bus F, 52-HF-13

c. IMPLEMENT OP AP-26, LOSS OF OFFSITE POWER, to energize 11D and 11E to provide main bank transformer cooling. d. RETURN TO Procedure and Step in effect

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EOP ECA-0.3 DIABLO CANYON POWER PLANT REVISION 17

PAGE 5 OF 29 TITLE: Restore 4kV Buses UNIT 1 EOP_ECA-0!3u1r17.DOC 03A 1220.0725 *** UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE***ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

5. CHECK 230kV Power Available to Either Unit GO TO Step 6 (Next Page)

a. Check OCB-212 closed OR Request GCC Diablo Control (8-449-6717) to close a. GO TO Step 6 (Next Page) NOTE: Transformer load limits are not a concern when energizing vital bus loads due to the small amount of loading. Transformer limits will be checked in OP AP-26, "LOSS OF OFFSITE POWER", if it is determined that non-vital loads are required.

b. Check Startup Transformer 1-1 power available white status light - ON (VB5) b. IF Unit 2 Startup Bus 2-1 is energized THEN Close the startup bus crosstie breaker 52-VU-11, check normal voltage on Startup Bus 1-1, AND GO TO Step 5.d. IF NOT THEN GO TO Step 6 (Next Page)

c. Close 52-VU-12, and check normal voltage on Startup Bus 1-1.

d. Verify the feeder breaker to Startup transformer 1-2 CLOSED 52-VU-14 e. Verify common 4 kV startup feeder CLOSED 52-HG-15 f. Close 4 kV Startup feeder breakers to supply Deenergized vital buses Bus H, 52-HH-14 Bus G, 52-HG-14 Bus F, 52-HF-14

g. RETURN TO Procedure and Step in effect

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121LJC-S4 Title: RESPOND TO CFCU HIGH VIBRATION Examinee: Evaluator:

Print Signature Date Testing Method:

Perform X Simulate Results: Sat Unsat Total Time:

minutes Comments:

References:

AR PK01-21, CONTMT FAN CLRS, Rev. 14 OP H-2:I, "Containment Fan Cooler Units

- Make Available and System Operation", Rev. 34.

Alternate Path:

Yes X No Time Critical:

Yes No X Time Allotment:

15 minutes Critical Steps:

3 Job Designation:

RO/SRO Rev Comments

Gen KA / Rating:

G2.4.31 - Knowledge of annunciator alarms, indications, or response procedures.

4.2 / 4.1 AUTHOR: DATE: OPERATIONS REPRESENTATIVE

DATE: R EV. 0 JPM Title:

Respond to CFCU High Vibration JPM Number: NRCL121LJC-S4 INSTRUCTOR WORKSHEET Directions:

All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee. 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 at which to begin. Required Materials:

None. Initial Conditions:

Given: Unit 1 is at 100% power Maintenance has requested shutdown of CFCU 1-2 for a routine inspectio n Initiating Cue:

The Shift Foreman directs you to start CFCU 1-1 and shutdown CFCU 1-2 in accordance with OP H

-2:I, "Containment Fan Cooler Units

- Make Available and System Operation"

. NOTE: Do NOT provide the student with the Task Standard.

Task Standard: PK01-21, "CONTMT FAN CLRS" alarm for high vibration is cleared and CFCU 1-1 is shutdown in accordance with AR PK01

-21 and OP H-2:I. NRCL121LJC-S4 PAGE 2 OF 7 REV. 0 JPM Title:

Respond to CFCU High Vibration JPM Number: NRCL121LJC-S4 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure.

1.1 0BReferences OP H-2:I, Section 6.4, "Swapping Running CFCUs"

. Step was: Sat: ______ Unsat _______

Comments: 2. Step 6.4.1 - Start CFCU 1-1. 2.1 Reads notes prior to step 6.4.1 2.2 Verifie d SPEED SELECT switch for CFCU is selected to "LOW".

2.3 Depresse d switch to start fan. 2.4 Check ed that fan current stabilizes.

2.5 Attempted reset of PK01

-21 caused by high vibration 2.6 Implement ed AR PK01-21. Step was: Sat: ______ Unsat _______

Comments: ** Denotes a Critical Step.

NRCL121LJC-S4 PAGE 3 OF 7 REV. 0 JPM Title:

Respond to CFCU High Vibration JPM Number: NRCL121LJC-S4 INSTRUCTOR WORKSHEET Step Expected Operator Actions

3. Implements Section 2.3, Fan Cooler High Vibration

. 3.1 Confirm ed high vibration condition on CFCU 1-1. . 3.2 Read note prior to step 2.3.2.

3.3 Presses VIB ALARM RESET pushbutton on VB-1 to reset alarm 1B** Step 2.3.3

- Shut s down CFCU 1

-1. 3.4 Notes reflash of PK01

-21. 3.5 Presses STOP button for CFCU 1

-1 on VB-1** (step 2.3.3.a)

. 3.6 Reports unable to perform the CFCU swap. **********************************

Cue: The SFM will contact maintenance to investigate

. *********************

Step was: Sat: ______ Unsat _______

Comments: Stop Time:

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

• • Denotes a Critical Step.

NRCL121LJC-S4 PAGE 4 OF 7 REV. 0 JPM Title:

Respond to CFCU High Vibration JPM Number: NRCL121LJC-S4 INSTRUCTOR WORKSHEET Followup Question Documentation

Question: ___________________________________________________________________

_ ______________________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

___________________

___________________________________________________________

______________________________________________________________________________

Response: ___________________________________________________________________

_ _________________________________

_____________________________________________

______________________________________________________________________________

______________________________________________________________________________

_________________________________________________

_____________________________

______________________________________________________________________________

• • Denotes a Critical Step.

NRCL121LJC-S4 PAGE 5 OF 7 REV. 0 JPM TITLE: Respond to CFCU High Vibration JPM NUMBER: NRCL121LJC-S4 ATTACHMENT 1, SIMULATOR SETUP INIT to IC

10. Shutdown CFCU 1

-1 and clear all alarms Verify CFCU 2, 4, and 5 running in LOW speed; CFCU running in HIGH Note: Entering drill file prior to shutting down CFCU 1

-1 will corrupt drill logic.

Enter drill file NRCL121-LJCS4 or manually insert the following:

Inform the examiner that the simulator setup is complete.

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

NRCL 121-S 4.DOCX PAGE 6 OF 7 REV. 0 EXAMINEE CUE SHEET JPM NUMBER: NRCL121LJC-S4 Initial Conditions:

Given: Unit 1 is at 100% power Maintenance has requested shutdown of CFCU 1-2 for a routine inspectio n Initiating Cue:

The Shift Foreman directs you to start CFCU 1-1 and shutdown CFCU 1-2 in accordance with OP H

-2:I, "Containment Fan Cooler Units

- Make Available and System Operation"

. NRCL 121-S 4.DOCX PAGE 7 OF 7 REV. 0 Containment Fan Cooler Units

- Make Available and System Operation OP H-2:I R34 Page 15 of 18 UNIT 1 OP_H-2~Iu1r34.DOC 0507.1056 6.4 Swapping Running CFCUs NOTE 1: In low speed, a CFCU will start approximately 10 to 14 seconds after the control switch is depressed. There is no time delay if high speed is selected.Ref 7.2.1 NOTE 2: A CFCU vibration alarm (PK01-21) can be expected when shifting a running CFCU to high speed. NOTE 3: If an RCP oil level is near an alarm setpoint level, starting, stopping, or changing configuration of CFCUs may bring in an RCP alarm due to changes in local air temperature. NOTE 4: As a conservative action, Operators will administratively consider any CFCU running in high speed INOPERABLE per POA 50560735. NOTE 5: A CFCU can be declared OPERABLE two minutes after high speed operation is secured (either left in OFF or low speed) per POA 50560735. 6.4.1 Start the selected CFCU as follows: a. Place SPEED SELECT switch in "LOW" AND press switch to start the CFCU. b. Check current stabilizes.

c. IF high speed operation is desired, THEN perform the following: 1. Press "STOP" pushbutton for the CFCU.

2. Immediately place SPEED SELECT switch in "HIGH" AND press switch to restart the CFCU. 3. Check current stabilizes.

4. Return CFCU SPEED SELECT switch to "LOW".

Containment Fan Cooler Units

- Make Available and System Operation OP H-2:I R34 Page 16 of 18 UNIT 1 OP_H-2~Iu1r34.DOC 0507.1056 d. IF annunciator PK01-21, "CONTMT FAN CLRS," alarms, THEN perform the following: 1. Check annunciator printout to confirm cause as high vibration on the CFCU just started. 2. Press VIB ALARM RESET pushbutton to reset the alarm. (VB1) 3. IF alarm returns, THEN IMPLEMENT AR PK01-21, "Contmt Fan Clrs." 6.4.2 Stop CFCU being removed from service PER OP H-2:II, "Containment Fan Coolers - Shutdown, Placing in Standby, and Clearing."

• • • ISSUED FOR USE BY: _______________________ DATE: ____________ EXPIRES: ____________ ***

DIABLO CANYON POWER PLANT ANNUNCIATOR RESPONSE UNIT 1 AR PK01-21 Rev. 14 Page 1 of 6 CONTMT FAN CLRS Effective Date QUALITY RELATED AR_PK01-21u1r14.DOC 0920.1316 1. ALARM INPUT DESCRIPTION INPUT PRINTOUT/DETAILS DEVICE SETPOINT STEP 149 Contmt Fan Clr 1-1 OC Trip 49X-1F-2 Hi 447 amps Lo 267 amps 2.2 150 Contmt Fan Clr 1-2 OC Trip 49X-1F-1 Hi 447 amps Lo 267 amps 2.2 228 Contmt Fan Clr 1-3 OC Trip 49X-1G-1 Hi 447 amps Lo 267 amps 2.2 229 Contmt Fan Clr 1-5 OC Trip 49X-1G-2 Hi 447 amps Lo 267 amps 2.2 300 Contmt Fan Clr 1-4 OC Trip 49X-1H-1 Hi 447 amps Lo 267 amps 2.2 433 Contmt Fan Clr 1-2 Vib Hi YS10 > 3 in/sec G 2.3 YS16 > 150% NORM 434 Contmt Fan Clr 1-3 Vib Hi YS11 > 3 in/sec G 2.3 YS17 > 150% NORM 435 Contmt Fan Clr 1-4 Vib Hi YS12 > 3 in/sec G 2.3 YS18 > 150% NORM 436 Contmt Fan Clr 1-5 Vib Hi YS13 > 3 in/sec G 2.3 YS19 > 150% NORM (Continued) 09/30/10 AR PK01-21 R14 Page 2 of 6 CONTMT FAN CLRS UNIT 1 AR_PK01-21u1r14.DOC 0920.1316 INPUT PRINTOUT/DETAILS DEVICE SETPOINT STEP 441 Contmt Fans Temp PPC T4007C 2.1 INPUTS TO T4007C PPC ID Contmt Fan Mtr 1-1 Inbd Brg Temp T1065A Contmt Fan Mtr 1-1 0-Bd Brg Temp T1066A Contmt Fan 1-1 Stator Temp T1067A 219°F (see NOTE)

Contmt Fan 1-1 Inbd Brg Temp T1068A Contmt Fan 1-1 Outbd Brg Temp T1069A Contmt Fan Mtr 1-2 Inbd Brg Temp T1070A Contmt Fan Mtr 1-2 0-Bd Brg Temp T1071A Contmt Fan 1-2 Stator Temp T1072A 219°F (see NOTE)

Contmt Fan 1-2 Inbd Brg Temp T1073A Contmt Fan 1-2 Outbd Brg Temp T1074A ` Contmt Fan Mtr 1-3 Inbd Brg Temp T1075A Contmt Fan Mtr 1-3 0-Bd Brg Temp T1076A Contmt Fan 1-3 Stator Temp T1077A 219°F (see NOTE)

Contmt Fan 1-3 Inbd Brg Temp T1078A Contmt Fan 1-3 Outbd Brg Temp T1079A Contmt Fan Mtr 1-4 Inbd Brg Temp T1080A Contmt Fan Mtr 1-4 0-Bd Brg Temp T1081A Contmt Fan 1-4 Stator Temp T1082A 219°F (see NOTE)

Contmt Fan 1-4 Inbd Brg Temp T1083A Contmt Fan 1-4 Outbd Brg Temp T1084A Contmt Fan Mtr 1-5 Inbd Brg Temp T1085A Contmt Fan Mtr 1-5 0-Bd Brg Temp T1086A Contmt Fan 1-5 Stator Temp T1087A 219°F (see NOTE)

Contmt Fan 1-5 Inbd Brg Temp T1088A Contmt Fan 1-5 Outbd Brg Temp T1089A (Continued)

AR PK01-21 R14 Page 3 of 6 CONTMT FAN CLRS UNIT 1 AR_PK01-21u1r14.DOC 0920.1316 INPUT PRINTOUT/DETAILS DEVICE SETPOINT STEP 442 Contmt Fan Clr 1-1 Vib Hi YS9 > 3 in/sec G 2.3 YS15 > 150% NORM NOTE: On the PPC only, an additional alarm is received when this parameter reaches 293°F. 2. OPERATOR ACTIONS 2.1 Fan High Temperature (Input 441) 2.1.1 Check annunciator and PPC printouts to determine affected CFCU. 2.1.2 REFER TO STP M-51, "Routine Surveillance Test of Containment Fan Cooler Units," for acceptable CFCU CCW flows, and check that CCW flow to the affected CFCU is adequate:

• CFCU 1-1: FI-34

• CFCU 1-2: FI-35

• CFCU 1-3: FI-36

• CFCU 1-4: FI-37

• CFCU 1-5: FI-38 2.1.3 IF Containment ambient air temperature is 120°F or above, THEN REFER TO TS 3.6.5, "Containment Air Temperature". NOTE: A CFCU can be run up to the temperatures listed below without affecting component lifetime:

• CFCU motor stator: 219°F

• CFCU motor inboard bearing: slow speed 180°F, fast speed 206°F

• CFCU motor outboard bearing: slow speed 180°F, fast speed 206°F

• CFCU fan inboard bearing: 180°F

• CFCU fan outboard bearing: 180°F 2.1.4 IF any CFCU is left in service with actual high temperature alarms, THEN document the following in a notification:

• The time period alarm limits were exceeded

• The maximum temperature reached 2.1.5 IF CFCU stator temperature is 293°F or above, THEN contact engineering to evaluate securing the CFCU. 2.1.6 IF necessary to stop or start CFCUs, THEN REFER TO the appropriate OP H-2 series procedure(s).

AR PK01-21 R14 Page 4 of 6 CONTMT FAN CLRS UNIT 1 AR_PK01-21u1r14.DOC 0920.1316 2.1.7 Probable Causes

• High Containment ambient temperature

• Low CCW flow to CFCU fan motor

• CFCU fan motor stator temperature out-of-limit

• CFCU fan or fan motor bearing temperature out-of-limit 2.2 Fan Cooler Overcurrent Trip (Inputs 149, 150, 228, 229, 300) 2.2.1 Check annunciator and PPC printouts to determine affected fan cooler. NOTE: CFCUs are normally in service sufficient to maintain Containment environment below 120°F. 2.2.2 IF needed to maintain acceptable Containment environment, THEN place another available CFCU in service PER OP H-2:I, "Containment Fan Cooler Units-Make Available and System Operation." CAUTION: To preclude further damage or creation of an electrical safety hazard, do NOT restart the tripped CFCU until the trouble has been investigated by maintenance. 2.2.3 Before attempting a restart of the tripped CFCU, direct maintenance to investigate. 2.2.4 REFER TO TS 3.6.6, "Containment Spray and Cooling Systems". 2.2.5 Probable Causes

• Motor overload sufficient to heat thermal device to opening temperature

• Fault in motor or on feeder cable causing instantaneous overload trip 2.3 Fan Cooler High Vibration (Inputs 433, 434, 435, 436, 442) 2.3.1 Check annunciator printout to determine affected fan cooler. NOTE: A CFCU vibration alarm can be expected when starting or stopping a CFCU or shifting a running CFCU to high speed. 2.3.2 Reset the vibration alarm on the Main Control Board.

AR PK01-21 R14 Page 5 of 6 CONTMT FAN CLRS UNIT 1 AR_PK01-21u1r14.DOC 0920.1316 2.3.3 IF the annunciator comes ON again due to high vibration, THEN perform the following: a. Press the "STOP" button on the Main Control Board to shut down the affected CFCU. b. Start another available CFCU PER OP H-2:I, Section 6.2, "Starting a CFCU." c. Direct maintenance to investigate.

d. REFER TO TS 3.6.6, "Containment Spray and Cooling Systems". 2.3.4 Probable Causes

• Imbalance in CFCU motor or fan

• Starting a CFCU

• Stopping a CFCU

• Shifting a running CFCU to high speed 3. AUTOMATIC ACTIONS None 4. REFERENCES 4.1 OP H-2:II, "Containment Fan Coolers Shutdown and Clearing" 4.2 106714, "OVID - Component Cooling Water System" 4.3 437600, "Schematic Diagram Containment Fan Coolers" 4.4 501121, "Electrical Schematic Diagram - Main Annunciator" (Inputs 228, 229, 300, 442) (Electrical Drawing Section 8) 4.5 501122, "Electrical Schematic Diagram - Main Annunciator" (Inputs 149, 150, 433, 434, 435, 436, 441) (Electrical Drawing Section 8)

AR PK01-21 R14 Page 6 of 6 CONTMT FAN CLRS UNIT 1 AR_PK01-21u1r14.DOC 0920.1316 5. LOGIC DIAGRAM

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121LJC-S 5 Title: RESPOND TO HIGH RADIATION ON RE-17A/B Examinee: Evaluator:

Print Signature Date Testing Method:

Perform X Simulate Results: Sat Unsat Total Time:

minutes Comments:

References:

AR PK11-21, "High Radiation", Rev. 31 OP AP-11, "Malfunction of Component Cooling Water System", Rev 31.

Alternate Path:

Yes No X Time Critical:

Yes No X Time Allotment:

1 5 minutes (average validation time 10 min) Critical Steps:

3 Job Designation:

RO/SRO Rev Comments

Gen KA / Rating:

073.A4.01 - Ability to manually operate and/or monitor in the control room:

effluent release 3.9 / 3.9 AUTHOR: DATE: OPERATIONS REPRESENTATIVE

DATE: R EV. 0 JPM TITLE: RESPOND T O HIGH RADIATION O N RE-17A/B JPM NUMBER: NRCL121LJC-S 5 INSTRUCTOR WORKSHEET Directions:

All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee. 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 at which to begin. Required Materials:

None. Initial Conditions:

Given: Unit 1 is at 100% power.

PK1 1-21 has just alarmed Initiating Cue

The Shift Foreman directs you to respond to the alarm per AR PK 1 1-21, High Radiation, step 2.4. NOTE: Do NOT provide the student with the Task Standard.

Task Standard:

RCV-16 closed in accordance with AR PK 1 1-21. NRCL 121-S 5.DOCX PAGE 2 OF 7 REV. 0 JPM TITLE: RESPOND T O HIGH RADIATION O N RE-17A/B JPM Number: NRCL12 1LJC-S5 INSTRUCTOR WORKSHEET Start Time:

Step Standards 1. 1. Step 2.4.1

- Identify process monitors in alarm

. 1.1 Read NOTE prior to step 2.4.1

. 1.2 Observe d both 17A and 17B in alarm

. Step was: Sat: ______ Unsat _______

Comments: 2. Step 2.4.2

- Check process monitor high rad was already in alarm state.

Cue: No other process monitors were in alarm prior to this event

. ***********************************

2.1 Determines no other proces s monitors in alarm Step was: Sat: ______ Unsat _______

Comments: ** Denotes a Critical Step.

NRCL 121-S 5.DOCX PAGE 3 OF 7 REV.0 JPM TITLE: RESPOND T O HIGH RADIATION O N RE-17A/B JPM Number: NRCL12 1LJC-S5 INSTRUCTOR WORKSHEET Step Standards 3. 0B** Step 2.4.3

- Ensure appropriate automatic action has occurred Note: May have already completed this action based on RE

-17A/B alarm condition.

3.1 Note d automatic closure of RCV

-16 did NOT occur. 3.2 Closed RCV

-16 *********************************

Cue: Another Operator will continue with performance of PK11

-21. *********************************

Step was: Sat: ______ Unsat _______

Comments:

Stop Time:

Total Time:

(Enter total time on the cover page)

• • Denotes a Critical Step.

NRCL 121-S 5.DOCX PAGE 4 OF 7 REV.0 JPM TITLE: RESPOND T O HIGH RADIATION O N RE-17A/B JPM Number: NRCL12 1LJC-S5 INSTRUCTOR WORKSHEET Followup Question Documentation

Question: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

Response: ____________________________________________________________________

___________________________________________________________________________

___ ______________________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

NRCL 121-S 5.DOCX PAGE 5 OF 7 REV.0 JPM TITLE: RESPOND T O HIGH RADIATION O N RE-17A/B JPM Number: NRCL121LJC

-S5 ATTACHMENT 1, SIMULATOR SETUP INIT to IC

10. Run lesson NRCL121-LJCS5 or manually insert the following:

Inform the examiner that the simulator setup is complete.

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

NRCL 121-S 5.DOCX PAGE 6 OF 7 REV.0 EXAMINEE CUE SHEET JPM Number: NRCL121LJC

-S5 Initial Conditions:

Given: Unit 1 is at 100% power.

PK1 1-21 has just alarmed Initiating Cue:

The Shift Foreman directs you to respond to the alarm per AR PK 1 1-21, High Radiation, step 2.4. NRCL 121-S 5.DOCX PAGE 7 OF 7 REV.0 AR PK11-21 R31 Page 4 of 8 HIGH RADIATION UNIT 1 AR_PK11-21u1r31.DOC 0809.0613 2.4 Process Radiation Monitors Actions (Input 1066)

NOTE: An overranged digital radiation monitor display will display "E.EEE+E." 2.4.1 Check the following process monitors:

• RE-3, Oily Water Separator 0-1 Influent

• RE-11, Containment Air Particle Radiation Monitor

• RE-12, Containment Radio Gas Radiation Monitor

• RE-13, RHR Exhaust Duct Air Particle Radiation Monitor

• RE-17A, Component Cooling Water Liquid

• RE-17B, Component Cooling Water Liquid

• RE-18, Liquid Radwaste Overboard Radiation Monitor

• RE-22, Gas Decay Tank Plant Vent

• RE-44A, Containment Purge Exhaust Duct

• RE-44B, Containment Purge Exhaust Duct 2.4.2 IF the process monitor high rad alarm was already in alarm, THEN perform ONE of the following:

• Check the high rad reflash module for the new alarm received.

• Check rad monitor panels for alarms. 2.4.3 IF automatic actions are required PER Section 3, "Automatic Actions," THEN ensure appropriate automatic actions have occurred. 2.4.4 IF RE-3 is in alarm (unexpected, not spurious due to a fire pump start), OR the Oily Water Separator influent is suspected to be radioactive, THEN direct chemistry to sample the Oily Water Separator liquid. 2.4.5 IF RM-12 is out-of-service OR a Containment Ventilation Isolation (CVI) occurs, THEN place the CFCU Collection System in service PER OP H-2:I Section 6.5, "Operating the CFCU Drain Collection System."

AR PK11-21 R31 Page 7 of 8 HIGH RADIATION UNIT 1 AR_PK11-21u1r31.DOC 0809.0613 2.4.9 IF RM-13, RM-44A, or RM-44B alarm is NOT due to sampling or pre-planned evolution, THEN perform the following: a. Place the Signal Test switch in "S" (POV-1 and POV-2 panels). b. Place the Aux Bldg Vent Char Fltr Prehtr Control switch in "ON" (VB4). 2.4.10 IF the RM-44A, or RM-44B detector is overranged, THEN perform the following: a. Check the following actions occurred: 1. Digital display indicates "E.EEE+E"

2. Alert, High, and Fail/Ack lights ON (Control Room) 3. Containment Ventilation Isolation

4. High Voltage Disable light ON (local panel)

5. Anti-jam circuit fuse OPEN b. Notify maintenance. 2.4.11 Probable Causes

• High radiation sensed by the detector

• Surveillance test in progress

• Instrument failed high

• Switchyard switching evolutions

• Start of Fire Pp 0-1 or Fire Pp 0-2 (RE-3) 3. AUTOMATIC ACTIONS 3.1 RE-1, 2, 3, 4, 6, 7, 10, 11, 12, and 13 - none NOTE: If Containment Ventilation Isolation (CVI) bypass switch is selected to BYPASS, CVI actuation is disabled for that RM. 3.2 RE-44A and 44B - Containment Ventilation isolation 3.3 RE-17A and 17B - RCV-16 closes to isolate CCW surge tank vent 3.4 RE isolates discharge to outfall and opens recirc to EDR 3.5 RE Isolates Gas Decay Tank discharge to Plant Vent NUCLEARP OWERGENERATIOND IABLOCANYONP OWERPLANTJ OBPERFORMANCEMEASURE AUTHOR:D ATE:OPERATIONSR EPRESENTATIVE

D ATE:R EV.0 Number:NRCL121LJC S6Title:INITIATEANATURALCIRCULATIONCOOLDOWNExaminee:Evaluator:PrintSignatureDateTestingMethod:PerformSimulateResults:SatUnsatTotalTime:minutesComments:ROOnly

References:

EOPE 0.2,NaturalCirculationCooldown,Rev.26AlternatePath:YesNoXTimeCritical:YesNoXTimeAllotment:20minutes(averagevalidationtime___min)CriticalSteps:4JobDesignation:RORevComments/TIPs:LJC 046GenKA#/Rating:002.A4.02Abilitytomanuallyoperateand/ormonitorinthecontrolroom:Indicationsnecessarytoverifynaturalcirculationfromappropriatelevel,flow,andtemperatureindicationsandvalvepositionsuponlossofforcedcirculation4.3 JPM TITLE: INITIATE A NATURAL CIRCULATION COOLDOWN JPM NUMBER: NRC L 121LJC-S6 INSTRUCTOR WORKSHEET Directions:

No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.

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 at which to begin.

Required Materials:

EOP E-0.2, Natural Circulation Cooldown, Rev. 2 6 Initial Conditions:

GIVEN: Unit 1 has tripped from 100% power.

EOP E-0.1, Reactor Trip Response, is complete; RCPs are not available.

EOP E-0.2 has been performed up to and including Step 9.

Boration to Cold Shutdown is complete DG 1-2 was crosstied to non

-vital power; two CRDM fans are running, and Pzr heaters are available The plant is stable @ approx 565F (T H), and 2235 psig. AFW is throttle d in MANUAL to help with stability

. Initiating Cue:

The Shift Foreman directs you to initiate a natural circulation cooldown in accordance with EOP E

-0.2, Step 10 (page 6) . NOTE: Do NOT provide the student with the Task Standard.

Task Standard:

A natural circulation cooldown using the 10% steam dumps initiated in accordance with EOP E

-0.2 (see examiner note on step 4)

. NRCL121-S6.DOCX PAGE 2 OF 7 REV. 0 JPM TITLE: INITIATE A NATURAL CIRCULATION COOLDOWN JPM NUMBER: NRCL121LJC-S6 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Action s 1. References EOP E-0.2. 1.1 Read CAUTION 1.2 Read NOTE. Step was: Sat: ______ Unsat _______

Comments: 2. Step 10.a - Check status of all S/Gs.

2.1 Check ed steam release capabilities of all S/Gs a vailable. 2.2 Checked feed flow available to all S/Gs.

Step was: Sat: ______ Unsat _______

Comments:

3. Step 10.b - Establish Cooldown 3.1 Note d that C/D rate is limited to 25F/hr. 3.2 Observe d that the MSIVs are closed, and went to the RNO to use the 10% steam dumps. Step was: Sat: ______ Unsat _______

Comments: ** Denotes Critical Step and Sub Steps.

nrcl121-s6.docx PAGE 3 OF 7 REV. 0 JPM TITLE: INITIATE A NATURAL CIRCULATION COOLDOWN JPM NUMBER: NRCL121LJC-S6 INSTRUCTOR WORKSHEET Step Expected Operator Actions 4.0B** Step 10.b RNO

- Initiate cooldown, using 10% steam dumps, at < 25F/hr Note: The 10%ers are already in AUTO, maintaining temperature under load; it will only take a few percent increase in demand to start a slow cooldown. Monitor the examinee to see that they throttle the cooldown rate to attain the desired rate. It is expected that the rate may initially overshoot the limit, but should be throttled back. Once the examinee has demonstrated that t he rate can be controlled w/i limits, the ending cue may be given. 4.1 (one at a time) Each 10% valve (PCV-19, 20, 21, 22) taken to MANUAL and the raise/lower PBs used to attain a slow cooldown (< 25 F/hr). 4.2 Establishe d cooldown rate (< 25

°F/hr).**. Step was: Sat: ______ Unsat _______

Comments: ** Denotes Critical Step and Sub Steps.

nrcl121-s6.docx PAGE 4 OF 7 REV. 0 JPM TITLE: INITIATE A NATURAL CIRCULATION COOLDOWN JPM NUMBER: NRCL121LJC-S6 INSTRUCTOR WORKSHEET Step Expected Operator Actions

5. Step 11 - Monitor for stagnant loops **********************************

Cue: (if step 11 referenced)

Another operator will monitor for inactive loops / stagnation, and act accordingly.

Cue: (once cooldown rate is properly established)

Another operator will continue with E

-0.2 performance.

Step was: Sat: ______ Unsat _______

Comments: Stop Time:

Total Time:

(Enter total time on the cover page)

• • Denotes Critical Step and Sub Steps.

nrcl121-s6.docx PAGE 5 OF 7 REV. 0 JPM TITLE: INITIATE A NATURAL CIRCULATION COOLDOWN JPM NUMBER: NRCL121LJC-S6 ATTACHMENT 1, SIMULATOR SETUP In it IC 216 ( 5 40-5 55 F, NOP, S/G levels in manual for stability, and 10%ers set in auto for a stable press/temp; two NV bussed have been powered up from DG 1

-2 to allow for Pzr htr and CRDM fan operation

). Select E-0.2 display on SPDS.

Select grpdis " cooldown" on a CC2 PPC computer; also, select the plot "rcs cooldown" on an active factory trend screen.

Inform the examiner that the simulator setup is complete.

Go to RUN when the examinee is given the cue sheet (or the sim can remain in RUN, since the plant is stable) nrcl121-s6.docx PAGE 6 OF 7 REV. 0 EXAMINEE CUE SHEET JPM NUMBER: NRCL121LJC-S6 Initial Conditions:

GIVEN: Unit 1 has tripped from 100% power.

EOP E-0.1, Reactor Trip Response, is complete; RCPs are not available.

EOP E-0.2 has been performed up to and including Step 9.

Boration to Cold Shutdown is complete DG 1-2 was crosstied to non

-vital power; two CRDM fans are running, and Pzr heaters are available The plant is stable @ approx 565F (T H), and 2235 psig. AFW is throttle d in MANUAL to help with stability

.

Initiating Cue: The Shift Foreman directs you to initiate a natural circulation cooldown in accordance with EOP E

-0.2, Step 10 (page 6) . nrcl121-s6.docx PAGE 7 OF 7 REV. 0 PACIFIC GAS AND ELECTRIC COMPANY NUMBER EOP E-0.2 DIABLO CANYON POWER PLANT REVISION 27

PAGE 6 OF 27 TITLE: Natural Circulation Cooldown UNIT 1 EOP_E-0!2u1r27.DOC 03A 0306.1257 *** UNCONTROLLED DOCUMENT - DO NOT USE TO PERFORM WORK or ISSUE FOR USE *** ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED *************************************************************************************** CAUTION: A low steamline pressure SI may occur if RCS pressure remains above P-11 (1915 psig) and steamline pressure drops below 700 psig (setpoint 600 psig rate sensitive). *************************************************************************************** NOTE: An Inactive loop is any RCS loop that is not available for cooling the RCS due to a loss of the capability to feed or steam its S/G.

10. INITIATE RCS Cooldown To Cold Shutdown:

a. Check status of all S/Gs: a. Perform the following Steam release capabilities - ALL S/Gs AVAILABLE 1) IF Feedwater to inactive loop(s) NOT available, THEN Ensure the following paths from inactive loop(s) isolated:

Feed flow - ALL S/Gs AVAILABLE MSIV and Bypass Valves S/G 1 - FCV-41/FCV-25 S/G 2 - FCV-42/FCV-24 S/G 3 - FCV-43/FCV-23 S/G 4 - FCV-44/FCV-22 Steam supply valves from inactive loop(s) to TDAFW Pp S/G 2 - FCV-37 S/G 3 - FCV-38 Blowdown isolation valves(s) from inactive loop(s) S/G 1 - FCV-760 S/G 2 - FCV-761 S/G 3 - FCV-762 S/G 4 - FCV-763 2) Maintain cooldown rate in RCS cold legs less than maximum allowable limits of Appendix SL.

3) GO TO Step 10.c (Page 7).

- THIS STEP CONTINUED ON NEXT PAGE -

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EOP E-0.2 DIABLO CANYON POWER PLANT REVISION 27

PAGE 7 OF 27 TITLE: Natural Circulation Cooldown UNIT 1 EOP_E-0!2u1r27.DOC 03A 0306.1257 *** UNCONTROLLED DOCUMENT - DO NOT USE TO PERFORM WORK or ISSUE FOR USE *** ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 10. INITIATE RCS Cooldown To Cold Shutdown: (Continued)

b. Establish LESS THAN a 25°F/hr COOLDOWN RATE by dumping steam to the condenser: b. Perform the following:

1) Check MSIVs - OPEN i. Dump steam using S/G 10% steam dumps.

2) Check Condenser - AVAILABLE ii. Establish LESS THAN a 25°F/hr COOLDOWN RATE iii. GO TO Step 11 (Page 8).

3) Dump Steam as follows:

a) Place HC-507 in Manual and Reduce demand to 0%. -

Preferred. OR Raise setpoint on HC-507 to achieve 0% demand.

b) Place Steam Dump in Steam Pressure Mode c) Adjust HC-507 Steam Pressure Controller Manually - Preferred OR Ensure HC-507 in auto and adjust HC-507 controller setpoint.

c. Maintain S/G narrow range level - 20% to 65% d. At P-12 Actuation:

1) T AVG - 543°F

2) PK08-07, LO-LO T AVG PERMISSIVE P ON a) Place Train A AND B Steam Dump Control in Bypass Intlk b) Ensure PK07-05 STM DUMP CONTROL BYPASS - ON

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: LJC-046 Title: INITIATE A NATURAL CIRCULATION COOLDOWN Examinee:

Evaluator:

Print Signature Date Testing Method:

Perform Simulate Results: Sat Unsat Total Time: minutes Comments: (Note: Any Unsat step requires a numbered comment; use back as needed.)

References:

EOP E-0.2, Natural Circulation Cooldown, Rev. 26 Alternate Path:

Yes No X Time Critical:

Yes No X Time Allotment:

20 minutes Critical Steps:

4 Job Designation:

RO/SRO Rev Comments/TIPs:

TIP 22360-01; updated to do on 10%ers, vs HC

-507 (since stm dumps would have to be in auto @ start, per E

-0.1) EC revision 17B was for procedure revision number change and Simulator terminology update. EC approved by LOB supervisor.

DCPP Task # / Rating: 896800 4.0 Gen KA # / Rating

E09.EA1.2 3.6 / 3.9 AUTHOR: JOHN F. BUCKLEY DATE: 03/08/2012 REVIEWED B Y: JOHN BECERRA 03/09/2012 TRAINING SUPERVISOR APPROVED B Y: KEN JOHNSTON DATE: 03/12/2012 LINE MANAGER R EV. 17B JPM TITLE: INITIATE A NATURAL CIRCULATION COOLDOWN JPM NUMBER: LJC-046 INSTRUCTOR WORKSHEET Directions:

No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.

The examiner will then ask if any clarifications are needed. If the task is being done in the plant or lab, and after identifying the appropriate procedure for the task, the examinee may be given the procedure and told what step to begin the task at. Required Materials:

Provide a copy of the reference procedure (partial procedure allowed), if the task is being done in the plant or lab. Initial Conditions:

Given: Unit 1 has tripped from 100% power. EOP E-0.1, Reactor Trip Response, is complete; RCPs are not available.

EOP E-0.2 has been performed up to and including Step 9. Boration to Cold Shutdown is complete DG 1-2 was crosstied to non

-vital power; two CRDM fans are running, and Pzr heaters are available The plant is stable @ approx 565F (T H), and 2235 psig. AFW is throttle d in MANUAL to help with stability. Initiating Cue:

The Shift Foreman directs you to initiate a natural circulation cooldown in accordance with EOP E

-0.2, Step 10.

NOTE: Do NOT provide the student with the Task Standard.

Task Standard:

A natural circulation cooldown using the 10% steam dumps has been initiated in accordance with EOP E-0.2 (see examiner note on step 4). LJC046.DOC PAGE 2 OF 7 R EV. 17 JPM TITLE: INITIATE A NATURAL CIRCULATION COOLDOWN JPM NUMBER: LJC-046 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure.

1.1 References

EOP E-0.2. 1.2 Reads CAUTION.

1.3 Reads NOTE.

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

2. Check status of all S/Gs.

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

2.2 Checks feed flow is available to all S/Gs. 2.3 Notes that C/D rate is limited to 25F/hr. Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

3. Check MSIVs open.

3.1 Observes that the MSIVs are closed, and goes to the RNO to use the 10%

steam dumps. Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps. LJC046.DOC PAGE 3 OF 7 R EV. 17 JPM TITLE: INITIATE A NATURAL CIRCULATION COOLDOWN JPM NUMBER: LJC-046 INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 4. Initiates cooldown, using 10% steam dumps, at < 25F/hr Note: The 10%ers are already in AUTO, maintaining temperature under load; it will only take a few percent increase in demand to start a slow cooldown. Monitor the examinee to see that he/she throttles the cooldown rate to attain the desired rate. It is expected that the rate may initially overshoot the limit, but should be throttled back. Once the examinee has demonstrated that he/she can control the rate w/i limits, the ending cue may be given. 4.1 PCV-19 is taken to MANUAL (by pressing the MAN PB), and the raise/lower PBs are used to attain a slow cooldown (< 25F/hr). **

4.2 PCV-20 is taken to MANUAL (by pressing the MAN PB), and the raise/lower PBs are used to attain a slow cooldown (< 25F/hr). **

4.3 PCV-21 is taken to MANUAL (by pressing the MAN PB), and the raise/lower PBs are used to attain a slow cooldown (< 25F/hr). **

4.4 PCV-22 is taken to MANUAL (by pressing the MAN PB), and the raise/lower PBs are used to attain a slow cooldown (< 25F/hr). ** (continued on next page)

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps. LJC046.DOC PAGE 4 OF 7 R EV. 17 JPM TITLE: INITIATE A NATURAL CIRCULATION COOLDOWN JPM NUMBER: LJC-046 INSTRUCTOR WORKSHEET Step Expected Operator Actions

4. (con't)

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • Cue: (if step 11 referenced) Another operator will monitor for inactive loops / stagnation, and act accordingly.

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • Cue: (once cooldown rate is properly established) Another operator will continue with E-0.2 performance.

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

Stop Time:

Total Time:

(Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps. LJC046.DOC PAGE 5 OF 7 R EV. 17 JPM TITLE: INITIATE A NATURAL CIRCULATION COOLDOWN JPM NUMBER: LJC-046 ATTACHMENT 1, SIMULATOR SETUP Init IC 216 ( 540-555 F, NOP, S/G levels in manual for stability, and 10%ers set in auto for a stable press/temp; two NV bussed have been powered up from DG 1-2 to allow for Pzr htr and CRDM fan operation). Select E-0.2 display on SPDS. Select grpdis "cooldown" on a CC2 PPC computer; also, select the plot "rcs cooldown" on an active factory trend screen. Inform the examiner that the simulator setup is complete.

Go to RUN when the examinee is given the cue sheet (or the sim can remain in RUN, since the plant is stable)

LJC046.DOC PAGE 6 OF 7 R EV. 17 JPM NUMBER: LJC-046 EXAMINEE CUE SHEET Initial Conditions:

Given: Unit 1 has tripped from 100% power. EOP E-0.1, Reactor Trip Response, is complete; RCPs are not available.

EOP E-0.2 has been performed up to and including Step 9. Boration to Cold Shutdown is complete DG 1-2 was crosstied to non

-vital power; two CRDM fans are running, and Pzr heaters are available The plant is stable @ approx 565F (TH), and 2235 psig. AFW is throttled in MANUAL to help with stability.

Initiating Cue:

The Shift Foreman directs you to initiate a natural circulation cooldown in accordance with EOP E

-0.2, Step 10.

LJC046.DOC PAGE 7 OF 7 R EV. 17 NUCLEARP OWERGENERATIOND IABLOCANYONP OWERPLANTJ OBPERFORMANCEMEASURE AUTHOR:D ATE:OPERATIONSR EPRESENTATIVE

D ATE:R EV.0 Number:NRCL121LJC S7Title:P ERFORMOPAP 15IMMEDIATEA CTIONSFORM AINF EEDP UMPT RIPExaminee:Evaluator:PrintSignatureDate TestingMethod:PerformXSimulateResults:SatUnsatTotalTime:minutesComments:

References:

OPAP 15,"LossofFeedwaterFlow",Rev24.AlternatePath:YesXNoTimeCritical:YesNoXTimeAllotment:5minutesCriticalSteps:JobDesignation:RO/SRORevComments:ModifiedNRCLCJ051 501GenKA/Rating:059.A2.073.0/3.3 JPM TITLE: Perform OP AP

-15 Immediate Actions for Main Feed Pump Trip JPM NUMBER: NRCL121LJC-S 7 INSTRUCTOR WORKSHEET Directions:

All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee. 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 at which to begin. Required Materials:

None. Initial Conditions:

Given: Unit 1 is at 100% power.

PK09-12, Main Feedwater Pump Trip, and PK09

-13, Main Feedwater Pump No. 11, have just alarme d The Shift Foreman has announced he is entering OP AP

-15, Loss of Feedwater Flow Initiating Cue:

The Shift Foreman directs you to take appropriate actions to respond to plant conditions

. NOTE: Do NOT provide the student with the Task Standard.

Task Standard:

The Immediate Actions for a Loss of Feedwater were performed in accordance OP AP

-15, Loss of Feedwater Flow, from memory, with follow up using the procedure

. NRCL 121-S 7.DOCX PAGE 2 OF 7 ERROR! REFERENCE SOURCE NOT FOUND

.

JPM TITLE: Perform OP AP

-15 Immediate Actions for Main Feed Pump Trip JPM Number: NRCL121LJC-S 7 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. 0B** Step 1 - Check Reactor power Less Than 80%. 1.1 Determine d power is greater than 80%

. 1.2 Perform step 1 RNO Start ed AFW Pp 1-2.** Start e d AFW Pp 1-3.** Step was: Sat: ______ Unsat _______

Comments: 2. Step 2 - Reduce Turbine Load

. 2.1 Determine d turbine load is greater than 650 MW 2.2 Determine d programmed ramp executing appropriately

DEH MW feedback in service TARGET set for 550 MW RAMP RATE at 225 MW/min

. Step was: Sat: ______ Unsat _______ Comments:

NRCL 121-S 7.DOCX PAGE 3 OF 7 R EV. 0 JPM TITLE: Perform OP AP

-15 Immediate Actions for Main Feed Pump Trip JPM Number: NRCL121LJC-S 7 INSTRUCTOR WORKSHEET Step Expected Operator Actions

3. Step 3 - MFW Pp Suction Pressure GREATER THAN 260 PSIG 3.1 Determine d MFW Pp Suction Pressure is greater than 260 PSIG Step was: Sat: ______ Unsat _______

Comments: 4. 1B** Step 4 - Rods Controlling Properly in AUTO. 4.1 Check ed Tave / Tref mismatch greater than 1.5 o F. 4.2 Determine d rods are NOT controlling properly in Auto

. 4.3 Place d Rod Control in MANUAL

.** (step 4 RNO) 4.4 Inser t ed rods at maximum available rate of 48 steps/min

. ** **********************************

Cue: Another Operator will continue with performance of OP AP-15. **********************************

Step was: Sat: ______ Unsat _______

Comments:

Stop Time:

Total Time:

(Enter total time on the cover page)

NRCL 121-S 7.DOCX PAGE 4 OF 7 R EV. 0 JPM TITLE: Perform OP AP

-15 Immediate Actions for Main Feed Pump Trip JPM Number: NRCL121LJC-S 7 INSTRUCTOR WORKSHEET Followup Question Documentation

Question: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

Response: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

NRCL 121-S 7.DOCX PAGE 5 OF 7 R EV. 0 JPM TITLE: Perform OP AP

-15 Immediate Actions for Main Feed Pump Trip ATTACHMENT 1, SIMULATOR SETUP JPM NUMBER: NRCL121LJC-S 7 INIT to IC

10. Run lesson NRCL121-LJCS 7 or manually insert the following:

Inform the examiner that the simulator setup is complete.

Go to RUN when instructed by examiner

. NRCL 121-S 7.DOCX PAGE 6 OF 7 R EV. 0 EXAMINEE CUE SHEET JPM NUMBER: NRCL121LJC-S 7 Initial Conditions:

Given: Unit 1 is at 100% power.

PK09-12, Main Feedwater Pump Trip, and PK09

-13, Main Feedwater Pump No. 11, have just alarme d The Shift Foreman has announced he is entering OP AP

-15, Loss of Feedwater Flow Initiating Cue:

The Shift Foreman directs you to take appropriate actions to respond to plant conditions

. NRCL 121-S 7.DOCX PAGE 7 OF 7 R EV. 0 PACIFIC GAS AND ELECTRIC COMPANY NUMBER OP AP-15 NUCLEAR POWER GENERATION REVISION 24 DIABLO CANYON POWER PLANT PAGE 1 OF 14 ABNORMAL OPERATING PROCEDURE UNIT TITLE: Loss of Feedwater Flow 1 INFO ONLY EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED OP_AP-15u1r24.DOC 02 0726.1101 *** UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***

1. SCOPE 1.1 This procedure provides guidance to mitigate feedwater flow transients caused by the trip of a Main Feedwater Pump (MFP), Heater 2 Drain Pump, or a Condensate/Booster Pump

Set. 1.2 This procedure is divided into four sections as follows:

1.2.1 Section A: ONE MFP TRIPS WITH BOTH MFPs OPERATING - Page 3 1.2.2 Section B: SINGLE OPERATING MFP TRIPS - Pg. 8 1.2.3 Section C: HEATER 2 DRAIN PUMP TRIP - Pg. 10 1.2.4 Section D: CONDENSATE/BOOSTER PUMP SET TRIP - Pg. 11

2. SYMPTOMS 2.1 Anticipated or actual MFP transient.

2.2 Indicated SG feedwater flow and level decreasing.

2.3 Main Feedwater pump discharge pressure decreasing (PI-49, PI-50).

2.4 Main Feedwater pump suction pressure decreasing.

2.5 Main Feedwater header pressure decreasing (PI-508).

2.6 Feedline/Steamline differential pressure decreasing (PI-509).

2.7 Possible Main Annunciator Alarms:

2.7.1 STEAM GENERATOR NO. _____ PRESS, LVL, FLOW (PK09-01, 02, 03, or 04) Stm Gen _____ Lvl Lo Dev From Setpoint Stm Gen _____ Fw Flo less than Stm Flo 2.7.2 PROTECT CHANNEL ACTIVATED (PK04-07). Stm Gen _____ Lvl Lo-Lo 1/3 PACIFIC GAS AND ELECTRIC COMPANY NUMBER OP AP-15 DIABLO CANYON POWER PLANT REVISION 24

PAGE 2 OF 14 TITLE: Loss of Feedwater Flow UNIT 1 OP_AP-15u1r24.DOC 02 0726.1101 *** UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***

2.7.3 MAIN FEEDWATER PUMP TRIP (PK09-12).

2.7.4 MAIN FEEDWATER PUMP NO. _____ (PK09-13, 14). Feedwater trouble alarms.

2.7.5 HEATER 2 DRAIN TANK LVL HI-LO (PK10-13).

Htr - 2 Drn Tk Lvl Hi-Lo.

Htr - 2 Drn Tk Lvl Hi Trip.

2.7.6 HEATER 2 DRAIN TANK PUMP (PK10-14).

Htr - 2 Drn Tk Pp OC Trip.

Htr - 2 Drn Tk Pp Lo Lvl Trip. Htr - 2 Drn Tk Pp L.O. Press Lo.

2.7.7 CNDS & CNDS BSTR PPS (PK10-06). CND and CND Bstr Pps OC Trip.

CND and CND Bstr Pps Auto Start.

PACIFIC GAS AND ELECTRIC COMPANY NUMBER OP AP-15 DIABLO CANYON POWER PLANT REVISION 24

PAGE 3 OF 14 TITLE: Loss of Feedwater Flow UNIT 1 OP_AP-15u1r24.DOC 02 0726.1101 *** UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***SECTION A: ONE MFP TRIPS WITH BOTH MFPs OPERATING ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED *************************************************************************************** CAUTION: If it appears that continuation of deliberate operator actions to stabilize the plant ON LINE will not be successful, manually trip the reactor and go to EOP E-0. ***************************************************************************************

1. CHECK Reactor Power - LESS THAN 80%

Start the following: AFW Pp 1-2 AFW Pp 1-3

2. REDUCE Turbine Load:T35691 a. Check turbine load greater than 650 MW. a. GO TO Step 3.

b. Check programmed ramp occurring: DEH MW feedback in service TARGET set for 550 MW RAMP RATE at 225 MW/min to 650 MW RAMP RATE at 25 MW/min to 550 MW b. Trip the Reactor and GO TO EOP E-0.T35691 3. CHECK MFW Pp Suction Pressure - GREATER THAN 260 PSIG

a. Verify standby condensate booster pump sets - RUNNING. b. Verify the following: FCV OPEN LCV CLOSED c. IF MFW Pp suction pressure remains less than 260 psig, THEN OPEN the following: FCV-55 TCV-23 d. IF MFW Pp suction pressure is LESS THAN 190 psig, THEN TRIP the Reactor AND GO TO EOP E-0.

PACIFIC GAS AND ELECTRIC COMPANY NUMBER OP AP-15 DIABLO CANYON POWER PLANT REVISION 24

PAGE 4 OF 14 TITLE: Loss of Feedwater Flow UNIT 1 OP_AP-15u1r24.DOC 02 0726.1101 *** UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***

SECTION A: ONE MFP TRIPS WITH BOTH MFPs OPERATING (Continued) ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

4. VERIFY Rods Controlling Properly in AUTO Manually insert control rods at 48 steps/min as required to match T AVG and T REF. 5. CONTINUE Load Reduction:

a. Verify programmed ramp continues: DEH MW feedback in service TARGET set for 550 MW RAMP RATE at 225 MW/min to 650 MW RAMP RATE at 25 MW/min to 550 MW a. IF Unit Load is greater than 550 MW, THEN set up a ramp as follows:

1) DEH MW feedback in service. 2) DEH IMP feedback in service. 3) TARGET set for 550 MW.

4) RAMP RATE at 25 MW/min.

5) Press GO.

6. CHECK Charging Flow - ADEQUATE TO PREVENT FLASHING IN THE LETDOWN SYSTEM Control Charging flow in MANUAL.

7. VERIFY DFWCS - IN AUTO:

a. Feed Reg Valve control in AUTO. a. Control S/G levels in MANUAL.

b. MFP Speed control in AUTO. b. Control FW/STM HDR P in MANUAL. 8. BORATE RCS:

Refer to the Reactivity Handbook to determine the quantity of boric acid to add.

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT Job Performance Measure Number: NRCLJC051-501 Title: PERFORM OP AP

-15 IMMEDIATE ACTIONS Examinee:

Evaluator:

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

References:

OP AP-15, Loss of Feedwater Flow, Rev. 17 Alternate Path:

Yes X No Time Critical:

Yes No X Time Allotment:

5 minutes Critical Steps:

1.1, 2.3, 4.2 Job Designation: RO/SRO KA Number:

04s/0 59/A 2.0 7 Rating: 3.0/3.3 AUTHOR: JACK BLACKWELL DATE: 02/28/2007 APPROVED B Y: N/A DATE: JPM COORDINATOR APPROVED B Y: N/A DATE: TRAINING LEADER R EV. 1 JPM TITLE: PERFORM AP-15 IMMEDIATE ACTIONS JPM NUMBER: NRCLJC051-501 INSTRUCTOR WORKSHEET Directions:

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

None Initial Conditions:

Unit 1 is at 72% and increasing to 100% power following a power reduction for maintenance. All systems aligned for normal full power operation. PK09-12, Main Feedwater Pump Trip, and PK09-13, Main Feedwater Pump No. 11, have just alarmed. The Shift Foreman has announced he is entering OP AP-15, Loss of Feedwater Flow.

Initiating Cue:

The SFM directs you to take appropriate actions to respond to plant conditions. Task Standard:

DO NOT READ TO STUDENTS

The Immediate Actions for a Loss of Feedwater are performed in accordance OP AP-15, Loss of Feedwater Flow, from memory, with follow up using the procedure.

NRCLJC051501.DOC PAGE 2 OF 6 R EV. 1 JPM TITLE: PERFORM AP-15 IMMEDIATE ACTIONS JPM NUMBER: NRCLJC051-501 INSTRUCTOR WORKSHEET Start Time: Step Expected Operator Actions EVALUATOR:

Cue Simulator Operator when ready to start DO NOT ALLOW APPLICANT TO REVIEW AP-15 PRIOR TO START OF JPM

. NOTE: Sequence of performance may vary and is not critical to JPM performance.

• • 1. CHECK Reactor Power Less Than 80%

• • 1.1 Checks power at 72% Step SAT:___________ UNSAT:________*

• • 2. REDUCE Turbine Load: Check turbine load > 650 MW

2.1 Determines

turbine load is >650 MW Verify programmed ramp occurring 2.2 Determines programmed ramp NOT occurring ** 2.3 Manually initiates ramp Places DEH MW and IMP feedback in service Sets TARGET LOAD = 650 MW Sets RAMP RATE for = 2 25 MW/min Presses GO Step SAT:___________ UNSAT:________*

3. CHECK Load Transient Bypass Actuated 3.1 Checks Load Transient Bypass Relay actuated Blue and Red light ON PK10-07 CNDS SYS TRANSIENT BYPASS alarm ON Step SAT:___________ UNSAT:________*

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step. NRCLJC051501.DOC PAGE 3 OF 6 R EV. 1 JPM TITLE: PERFORM AP-15 IMMEDIATE ACTIONS JPM NUMBER: NRCLJC051-501 INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 4. VERIFY Rod Control in AUTO 4.1 Checks Rod Control in MANUAL

• • 4.2 Places Rods in Auto and Verifies rods inserting to control T AVG to TREF Step SAT:___________ UNSAT:________*

Stop Time: ___________

Total Time: ___________

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step. NRCLJC051501.DOC PAGE 4 OF 6 R EV. 1 EXAMINEE CUE SHEET JPM NUMBER: NRCLJC051-501 Initial Conditions:

Unit 1 is at 72% and increasing to 100% power following a power reduction for maintenance. All systems aligned for normal full power operation. PK09-12, Main Feedwater Pump Trip, and PK09-13, Main Feedwater Pump No. 11, have just alarmed. The Shift Foreman has announced he is entering OP AP-15, Loss of Feedwater Flow. Initiating Cue:

The SFM directs you to take appropriate actions to respond to plant conditions.

NRCLJC051501.DOC PAGE 5 OF 6 R EV. 1 JPM TITLE: PERFORM AP-15 IMMEDIATE ACTIONS JPM NUMBER: NRCLJC051-501 ATTACHMENT 1, SIMULATOR SETUP Initialize the simulator in Expert Screen using "init j3bc030." Ensure Simulator is in FREEZE just at MFP TRIP alarms PK09-12/13 Inform the examiner that the simulator setup is complete.

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

OR Initialize to IC-511 Ramp unit to 72% power and stabilize Place Rods in Manual On Triconex Panel, BYPASS MFP 11 RUNBACK.

Insert MAL mfw2a act 25,0,30,d,0 Insert MAL cnd1 act1,0,0,d Go to RUN until MFP Trip alarm actuates FREEZE Simulator Inform the examiner that the simulator setup is complete.

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

NRCLJC051501.DOC PAGE 6 OF 6 R EV. 1 NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL 12 1LJC-S 8 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 Rev Comments/TIPs:

NRCL081LJC

-S3 Gen KA # / Rating:

006.A4.05 - Ability to manually operate and/or monitor in the control room:

Transfer of ECCS flowpaths prior to recirculation 3.9 / 3.8 AUTHOR: DATE: OPERATIONS REPRESENTATIVE

DATE: R EV. 0 JPM TITLE: ALIGN RHR PUMP 12 FOR HOT LEG RECIRCULATION JPM NUMBER: NRCL 12 1LJC-S 8 INSTRUCTOR WORKSHEET Directions:

All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee. 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 at which to begin. Required Materials:

EOP E-1.4 Initial Conditions:

GIVEN: A Unit 1 reactor trip and safety injection has occurred Cold leg recirculation was initiated just over 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> ago Both RHR pumps are running 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. NRCL121-S8.DOCX PAGE 2 OF 6 R EV. 0 JPM TITLE: ALIGN RHR PUMP 12 FOR HOT LEG RECIRCULATION JPM NUMBER: NRCL 12 1LJC-S 8 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions 1. Obtain the correct procedure.

1.1 References EOP E

-1.4. Step was: Sat: ______ Unsat _______

Comments: 2. Step 6 - Check RHR pump 12 running.

Observe d that RHR pump 12 running. Step was: Sat: ______ Unsat _______

Comments: 3. Step 7 - Align RHR pump 12 for Hot Leg RecircOpen 8716B, RHR pump 12 discharge crosstie valve.

3.1 Open ed valve 8716B.

Verifies valve open.

3.2 Attempt ed to open valve 8703

, when valve did not open, went to step 7.b RNO Step was: Sat: ______ Unsat _______

Comments:

• • Denotes Critical Step and Sub Steps.

nrcl121-s8.docx PAGE 3 OF 6 R EV. 0 JPM TITLE: ALIGN RHR PUMP 12 FOR HOT LEG RECIRCULATION JPM NUMBER: NRCL 12 1LJC-S 8 INSTRUCTOR WORKSHEET Step Expected Operator Actions

4. Step 7.b RNO 4.1 Opened 8809A AND B **

4.2 Close d 8716B, RHR Pp 2 Disch Crosstie Vlv ** 4.3 Throttle d RHR HX Outlet valve as needed to maintain motor current LESS THAN 57 amps (if needed) 4.4 Went to step 9 Step was: Sat: ______ Unsat _______

Comments:

5. Step 9 - Contact Plant Engineering in TSC to evaluate CCW System train separation. 5.1 Contact ed TSC to evaluate CCW System train separation

. **********************************

Cue: Another Operator will continue with performance of EOP E-1.4. **********************************

Step was: Sat: ______ Unsat _______

Stop Time:

Total Time:

(Enter total time on the cover page)

• • Denotes Critical Step and Sub Steps.

nrcl121-s8.docx PAGE 4 OF 6 R EV. 0 JPM TITLE: ALIGN RHR PUMP 12 FOR HOT LEG RECIRCULATION ATTACHMENT 1, SIMULATOR SETUP JPM NUMBER: NRCL 12 1LJC-S 8 Restor e IC 207 This SNAP allows entry into EOP E

-1.4 at Step 6. Both SI and RHR pumps are running.

Manually insert the following:

Command Description vlv rhr7 1,0,0,0,d,0 Fails 8703 closed Inform the examiner that the simulator setup is complete.

Go to RUN when the examinee is given the cue sheet. nrcl121-s8.docx PAGE 5 OF 6 R EV. 0 EXAMINEE CUE SHEET JPM NUMBER: NRCL 12 1LJC-S 8 Initial Conditions:

GIVEN: A Unit 1 reactor trip and safety injection has occurred Cold leg recirculation was initiated just over 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> ago Both RHR pumps are running 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. nrcl121-s8.docx PAGE 6 OF 6 R EV. 0 PACIFIC GAS AND ELECTRIC COMPANY NUMBER EOP E-1.4 DIABLO CANYON POWER PLANT REVISION 19

PAGE 7 OF 12 TITLE: Transfer To Hot Leg Recirculation UNIT 1 EOP_E-1!4u1r19.DOC 03A 1015.0808 *** UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

6. CHECK RHR Pp 2 Is Running IF RHR Pp 2 is NOT available, THEN GO TO Step 8 (Next Page).

7. ALIGN RHR Pp 2 For Hot Leg Recirculation:

a. Open 8716B, RHR Pp 2 Disch Crosstie Vlv a. Perform the following: 1) Open 8809B

2) Close 8716B, RHR Pp 2 Disch Crosstie Vlv 3) Throttle RHR HX Outlet valve as needed to maintain motor current LESS THAN 57 amps. 4) GO TO Step 8 (Next Page).

b. Open 8703, RHR to Hot Legs 1 and 2 b. Perform the following: 1) Open 8809A AND B

2) Close 8716B, RHR Pp 2 Disch Crosstie Vlv 3) Throttle RHR HX Outlet valve as needed to maintain motor current LESS THAN 57 amps. 4) GO TO Step 9 (Next Page).

c. Adjust HCV-637, RHR Hx 2 Outlet Flow Control Vlv to maintain:

Suction to SI Pps, RHR Pp 2 motor current LESS THAN 57 AMPS

d. GO TO Step 9 (Next Page)

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EOP E-1.4 DIABLO CANYON POWER PLANT REVISION 19

PAGE 8 OF 12 TITLE: Transfer To Hot Leg Recirculation UNIT 1 EOP_E-1!4u1r19.DOC 03A 1015.0808 *** UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

8. ALIGN RHR Pp 1 For Hot Leg Recirculation:

a. Open 8716A, RHR Pp 1 Disch Crosstie Vlv b. Open 8703, RHR to Hot Legs 1 and 2 a. Perform the following: 1) Open 8809A. 2) Close 8716A, RHR Pp 1 Disch Crosstie Vlv. 3) Throttle RHR HX Outlet valve as needed to maintain motor current LESS THAN 57 amps. 4) GO TO Step 9.

c. Adjust HCV-638 to maintain: Suction to SI Pps RHR Pp 1 motor current LESS THAN 57 amps NOTE: The Technical Support Center shall determine train separation requirements within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of event initiation.

9. CONTACT Plant Engineering In Technical Support Center To Evaluate CCW System Train Separation

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

-S3 Title: ALIGN RHR PUMP 12 FOR HOT LEG RECIRCULATION Examinee:

Evaluator:

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

References:

EOP E-1.4, Transfer to Hot Leg Recirculation, Rev. 19 Alternate Path:

Yes X No Time Critical:

Yes No X Time Allotment:

10 minutes Critical Steps:

4 Job Designation: RO/SRO Task Number:

KA 006A4.05 Rating: 3.9/3.8 AUTHOR: GARY HUTCHISON DATE: 04/29/09 R EV. 0 JPM TITLE: ALIGN RHR PUMP 12 FOR H OT LEG RECIRCULATION JPM NUMBER: NRCL081LJC

-S3 INSTRUCTOR WORKSHEET Directions:

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

None Initial Conditions:

A Unit 1 reactor trip and safety injection has occurred. Cold leg recirculation was initiated just over 10.5 hours5.787037e-5 days <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. NRCL081LJC

-S3.DOC PAGE 2 OF 5 R EV. 0 JPM TITLE: ALIGN RHR PUMP 12 FOR H OT LEG RECIRCULATION JPM NUMBER: NRCL081LJC

-S3 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure.

1.1 References EOP E-1.4. Step was: Sat: ______ Unsat _______*

2. Check RHR pump 12 running.

2.1 Observes that RHR pump 12 is running. Step was: Sat: ______ Unsat _______*

3. Open 8716B, RHR pump 12 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)

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps. NRCL081LJC

-S3.DOC PAGE 3 OF 5 R EV. 0 JPM NUMBER: NRCL081LJC

-S3 EXAMINEE CUE SHEET Initial Conditions:

A Unit 1 reactor trip and safety injection has occurred. Cold leg recirculation was initiated just over 10.5 hours5.787037e-5 days <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. NRCL081LJC

-S3.DOC PAGE 4 OF 5 R EV. 0 JPM TITLE: ALIGN RHR PUMP 12 FOR H OT LEG RECIRCULATION JPM NUMBER: NRCL081LJC

-S3 ATTACHMENT 1, SIMULATOR SETUP Select RELAP JPM IC 628. Click the BYPASS SWCK button on the expert screen to continue after control boards are aligned. Cutout series contactors for 8009A & B Manually insert the following:

Command Description vlv rhr7 1,0,0,0,d,0 Fails 8703 closed This SNAP allows entry into EOP E-1.4 at Step 6. Both SI and RHR pumps are running. Hang control board caution tags on 8105 and 8106. Inform the examiner that the simulator setup is complete.

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

NRCL081LJC

-S3.DOC PAGE 5 OF 5 R EV. 0 NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-P1 Title: MANUALLY OPERATE THE CARDOX SYSTEM Examinee: Evaluator:

Print Signature Date Testing Method:

Perform X Simulate Results: Sat Unsat Total Time:

minutes Comments: This is a UNIT 2 JPM

References:

U1 & 2 OP K

-2B:II, Manual Use of the Cardox System, Rev. 10 Alternate Path:

Yes __X No Time Critical:

Yes No X Time Allotment:

1 5 minutes Critical Steps: 2, 3 Job Designation:

RO or SRO Rev Comments:

Bank LJP-138A Gen KA / Rating:

067.AA1.08

- Ability to operate and / or monitor the following as they apply to the Plant Fire on Site:

Fire fighting equipment used on each class of fire 3.4/3.7 AUTHOR: LISA TORIBIO DATE: 06/20/2014 OPERATIONS REPRESENTATIVE

ABDUL KADIR DATE: 06/20/2014 R EV. 0 JPM TITLE: MANUALLY OPERATE THE CARDOX SYSTEM JPM NUMBER: NRCL121-P1 EVALUATOR WORKSHEET Directions:

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

U1&2 OP K-2B:II, Section 6.3.

Initial Conditions Given: A fire has been detected in the Unit 2 Cable Spreading Room.

DC power has been lost to the cardox control circuitry.

There are NO personnel in either Cable Spreading Room Initiating Cue:

The Shift Foreman directs you to locally actuate cardox discharge to the Unit 2 Cable Spreading Room, per OP K

-2B:II, step 6.3 DO NOT READ TASK STANDARD TO EXAMINEE Task Standard:

Cardox initiated to the U2 Cable Spreading Room for the proper duration, in accordance with OP K

-2B:II. NRCL121-P1 PAGE 2 OF 7 R EV. 0 JPM TITLE: MANUALLY OPERATE THE CARDOX SYSTEM JPM NUMBER: NRCL121-P1 EVALUATOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Step 6.3.1

- Attempt LOCAL discharge to U-2 Cable Spreading Room (CSR) 1.1 Read NOTE prior to step 6.3.1. 1.2 For 2-FCV-102, pulled cover and depresse d button. Note: Knowledge of the systems and IC may lead examinee to move to step 6.3.2. In that case, step 1 is N/A. **********************************

Cue: NO audible flow noise heard in the CO 2 piping. **********************************

1.3 Determined

that CO 2 discharge did not occur, and moved on to next step.

Sat: ______ Unsat _______

Comment: NRCL121-P1 PAGE 3 OF 7 R EV. 0 JPM TITLE: MANUALLY OPERATE THE CARDOX SYSTEM JPM NUMBER: NRCL121-P1 EVALUATOR WORKSHEET 2.0B 0B** Step 6.3.2

- Manu ally actuate CARDOX at local station 2.1 Read CAUTION prior to step 6.3.2.a. Step 6.3.2.a

- Personnel clear of CSR 2.2 Ensur ed personnel are clear of the Unit 2 Cable Spreading Room.

Cue: There are no personnel in the Cable Spreading Room.

Note: The valve handle is in line/parallel to the pipe when the valve is open. Step 6.3.2.b

- Ensure 2-HCV-2074 open 2.3 Ensur ed abort valve for Unit 2 Cable Spreading Room was open (2-HCV-2074). **********************************

Cue: The valve operator for 2-HCV-2074 is in line/parallel with the piping. **********************************

Step 6.3.2.c

- Open 2-FCV-102 pilot valve 2.4 Bro ke glass and opened pilot for 2-FCV-102. ** **********************************

Cue: NO audible flow noise is heard in the CO 2 piping. **********************************

Sat: ______ Unsat _______

Comment: NRCL121-P1 PAGE 4 OF 7 R EV. 0 JPM TITLE: MANUALLY OPERATE THE CARDOX SYSTEM JPM NUMBER: NRCL121-P1 EVALUATOR WORKSHEET 3.1B 1B** 6.3.2.d - At the storage tank , manually open the Selector Pilot Control Valve 3.1 Read note prior to step 6.3.2.d 3.2 B r oke glass and open ed the Pilot Valve for Master Valve 0

-FCV-104. ** **********************************

Cue: Audible flow noise is heard in the CO 2 piping. **********************************

Note: Give following Cue only after examinee verbalizes that valve will be kept open for 2 minutes and 40 seconds.

Cue: Two minutes and 40 seconds have elapsed. **********************************

Step 6.3.2.e

- Close 2-FCV-102 pilot valve 3.3 Close d the Pilot Valve for 2-FCV-102. ** Note: This is the valve opened in step 6.3.2.c. The valve is closed to ensure any subsequent actuation does not result in Cardox going to the CSR again.

Cue: There is no more audible flow noise in the CO 2 piping. **********************************

Sat: ______ Unsat _______

Comment: NRCL121-P1 PAGE 5 OF 7 R EV. 0 JPM TITLE: MANUALLY OPERATE THE CARDOX SYSTEM JPM NUMBER: NRCL121-P1 EVALUATOR WORKSHEET Stop Time:

Total Time:

(Enter total time on the cover page)

Follow up Question Documentation

Question: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

Response: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

NRCL121-P1 PAGE 6 OF 7 R EV. 0 EXAMINEE CUE SHEET JPM NUMBER: NRCL121-P1 Initial Conditions:

Given: A fire has been detected in the Unit 2 Cable Spreading Room.

DC power has been lost to the cardox control circuitry.

There are NO personnel in either Cable Spreading Room Initiating Cue:

The Shift Foreman directs you to locally actuate cardox discharge to the Unit 2 Cable Spreading Room, per OP K

-2B:II, step 6.3

NRCL121-P1 PAGE 7 OF 7 R EV. 0 Low Pressure Cardox

- Manual Use Of The Cardox System OP K-2B:II R10 Page 5 of 14 UNITS 1&2 OP_K-2B~IIu3r10.DOC 0918.0652 6.3 Locally Actuating CO 2 to Unit 2 Cable Spreading Room NOTE: The instructions of Section 6.3 can be found on a lamicoid at local CO 2 actuation station UNIT 2 CABLE SPREAD RM CO 2 FIRE SYSTEM CONTROL STATION, in Auxiliary Building Stairway #1 on the 128 ft level. 6.3.1 At local CO 2 actuation station, pull cover and push button for 2-FCV-102. 6.3.2 IF CO 2 failed to actuate by pushbutton, THEN perform the following: CAUTION: Performing the following steps will cause an immediate discharge of CO

2. a. Ensure personnel clear of the Unit 2 Cable Spreading Room. b. Ensure OPEN 2-HCV-2074, Cable Spreading Room Cardox Abort Vlv (U-2). c. Break glass and open pilot valve for 2-FCV-102. NOTE: Master valve 0-FCV-104 should fail open on a loss of control power. d. IF CO 2 discharge did NOT occur, THEN at storage tank, break glass and open pilot valve for 0-FCV-104. e. WHEN CO 2 has discharged for 155 to 165 seconds, THEN at local CO 2 actuation station, close pilot valve for 2-FCV-102.

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: LJP-138A Title: MANUALLY OPERATE THE CARDOX SYSTEM Examinee:

Evaluator:

Print Signature Date Testing Method:

Perform Simulate Results: Sat Unsat Total Time: minutes Comments: (Note: Any Unsat step requires a numbered comment; use back as needed.)

Note: This is a U-2 JPM.

References:

U1 & 2 OP K

-2B:II, Manual Use of the Cardox System, Rev.

10 Alternate Path:

Yes X No Time Critical:

Yes No X Time Allotment:

15 minutes Critical Step(s): 2, 3 Job Designation:

RO/SRO Rev Comments/TIPs:

Rev 2 A EC revision per SAPN 50586181, to match procedure revision TIP 22308-02; per R115 examiner/examinee feedback. DCPP Task # / Rating: 666600 3.7 Gen KA # / Rating

067.AA1.08 3.4 / 3.7 AUTHOR: JOHN F. BUCKLEY DATE: 02/13/2012 REVIEWED B Y: RON FORTIER FOR JOHN BECERRA DATE: 2/13/12 TRAINING SUPERVISOR APPROVED B Y: ERIK WERNER DATE: 2/20/12 LINE MANAGER R EV. 2 A JPM TITLE: MANUALLY OPERATE THE CARDOX SYSTEM JPM NUMBER: LJP-138A INSTRUCTOR WORKSHEET Directions:

No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.

The examiner will then ask if any clarifications are needed. The examinee should be given the "required materials" shown below, and access to other plant references as appropriate. Equipment operation "Cues" are contingent on proper operation by the examinee, and should be "adjusted" should equipment operation differ from expected.

Required Materials:

Copy of U1&2 OP K-2B:II, Section 6.

3. Initial Conditions:

Given: A fire has been detected in the Unit 2 Cable Spreading Room. DC power has been lost to the cardox control circuitry. There are NO personnel in either Cable Spreading Room. Initiating Cue:

The Shift Foreman directs you to locally actuate cardox discharge to the Unit 2 Cable Spreading Room, per OP K-2B:II, step 6.3 NOTE: Do NOT provide the student with the Task Standard.

Task Standard:

Cardox is initiated to the U2 Cable Spreading Room for the proper duration, in accordance with OP K-2B:II. LJP 138 A.DOC PAGE 2 OF 6 R EV. 2 A JPM TITLE: MANUALLY OPERATE THE CARDOX SYSTEM JPM NUMBER: LJP-138A INSTRUCTOR WORKSHEET Start Time: Step Expected Operator Actions

1. Attempts local discharge to U-2 Cable Spreading Room via pushbutton.

1.1 Reads NOTE prior to step 6.3.1. 1.2 For 2-FCV-102, pulls cover and depresses button

. Note: Knowledge of the systems and IC may lead examinee to move to step 6.3.2. In that case, step 1 is N/A. ********************************** Cue: NO audible flow noise is heard in the CO 2 piping. **********************************

1.3 Determines that CO 2 discharge did not occur, and moves on to next step. Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps. LJP 138 A.DOC PAGE 3 OF 6 R EV. 2 A JPM TITLE: MANUALLY OPERATE THE CARDOX SYSTEM JPM NUMBER: LJP-138A INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 2. Manually actuates CO 2 to the Cable Spreading Room.

2.1 Reads CAUTION prior to step 6.3.2.a.

2.2 Verifies personnel are clear of the Unit 2 Cable Spreading Room.

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • Cue: There are no personnel in the Cable Spreading Room.

Note: The valve handle is parallel to the pipe when the valve is open.

2.3 Verifies abort valve for Unit 2 Cable Spreading Room is open

(2-HCV-2074). ********************************** Cue: The valve operator for 2-HCV-2074 is in line/parallel with the piping.

2.4 Breaks glass and opens pilot for 2-FCV-102. ** **********************************

Cue: NO audible flow noise is heard in the CO 2 piping. **********************************

2.5 Reads note prior to step to open 0-FCV-104. ** Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps. LJP 138 A.DOC PAGE 4 OF 6 R EV. 2 A JPM TITLE: MANUALLY OPERATE THE CARDOX SYSTEM JPM NUMBER: LJP-138A INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 3. Manually Opens the Selector Pilot Control Valve.

3.1 At the storage tank, breaks glass and opens the Master Valve 0-FCV-104. ** ********************************** Cue: Audible flow noise is heard in the CO 2 piping. **********************************

Note: Give following Cue only after examinee verbalizes that valve will be kept open for 2 minutes and 40 seconds.

Cue: Two minutes and 40 seconds have elapsed. **********************************

3.2 Closes the Selector Pilot Control Valve 2-FCV-102. ** ********************************** Cue: There is no more audible flow noise in the CO 2 piping. **********************************

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

Stop Time:

Total Time:

(Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps. LJP 138 A.DOC PAGE 5 OF 6 R EV. 2 A JPM NUMBER: LJP-138A EXAMINEE CUE SHEET Initial Conditions:

Given: A fire has been detected in the Unit 2 Cable Spreading Room. DC power has been lost to the cardox control circuitry. There are NO personnel in either Cable Spreading Room.

Initiating Cue:

The Shift Foreman directs you to locally actuate cardox discharge to the Unit 2 Cable Spreading Room, per OP K-2B:II, step 6.3 LJP 138 A.DOC PAGE 6 OF 6 R EV. 2 A NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-P2 Title: ALIGN 480V BUS G FOR CONTROL FROM THE HOT SHUTDOWN PANEL Examinee: Evaluator:

Print Signature Date Testing Method:

Perform Simulate X Results: Sat Unsat Total Time:

minutes Comments:

References:

OP AP-8A, Control Room Inaccessibility

- Establishing Hot Stby, Rev.

36 Alternate Path:

Yes _______ No X Time Critical:

Yes No X Time Allotment:

20 minutes Critical Steps: 1, 2 Job Designation:

RO or SRO Rev Comments:

Bank LJP-007 Gen KA / Rating:

06 8.AA1.21 - Ability to operate and / or monitor the following as they apply to the Control Room Evacuation:

Transfer of controls from control room to shutdown panel or local control 3.9/4.1 AUTHOR: LISA TORIBIO DATE: 06/20/2014 OPERATIONS REPRESENTATIVE

ABDUL KADIR DATE: 06/20/2014 R EV. 0 JPM TITLE: ALIGN 480V BUS G FOR CONTROL FROM THE HOT SHUTDOWN PANEL JPM NUMBER: NRCL121-P2 EVALUATOR WORKSHEET Directions:

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

Provide a copy of the reference procedure (partial procedure allowed), if the task is being done in the plant or lab; U1 OP AP

-8A, App F Initial Conditions GIVEN: A fire in the control boards has caused a Unit 1 Control Room evacuation.

OP AP-8A is being performed and the operating crew is ready to align bus 1G 480 VAC loads for control from the Hot Shutdown Panel Initiating Cue:

The Shift Foreman directs you to align bus 1G 480 vac loads for control at the Hot Shutdown Panel, per OP AP

-8A, App F, step 2 DO NOT READ TASK STANDARD TO EXAMINEE Task Standard:

Breakers and switches aligned for 480 vac bus 1G per App F, step 2 of OP AP-8A. NRCL121-P2 PAGE 2 OF 5 R EV. 0 JPM TITLE: ALIGN 480V BUS G FOR CONTROL FROM THE HOT SHUTDOWN PANEL JPM NUMBER: NRCL121-P2 EVALUATOR WORKSHEET Start Time:

Step Expected Operator Actions 1.** Step 2.a. - Place the control transfer cutout switches for 480V vital bus 1G to the CUT-IN position.

1.1 Locate d 480V vital bus 1G aux relay panel in the vital switchgear room.

Note: CUT IN / CUT OUT switches are located inside the aux relay panel. The aux relay panel may be opened. 1.2 Place d the following switches to the CUT

-IN position:

FCV-95 , switch 43X

-1230.** ***************************************

Cue: (may be given after each switch operation) The switch is in the CUTIN (up) position.

1.3 CFCU 15, switch 43X

-1G-02.** Emergency Borate valve 8104, switch 43X-1G-57.** BATP 1-2, switch 43X

-1G-04.** LCV-106, switch 43X

-1G-44.** LCV-107, switch 43X

-1G-68.** Sat: ______ Unsat _______

Comment: NRCL121-P2 PAGE 3 OF 5 R EV. 0 JPM TITLE: ALIGN 480V BUS G FOR CONTROL FROM THE HOT SHUTDOWN PANEL JPM NUMBER: NRCL121-P2 EVALUATOR WORKSHEET 2. Step 2.b - Open 480V vital bus 1G breakers to prevent spurious operation.

2.1 Open ed the following breakers:

Cue: (may be given after each breaker operation)

The breaker is in the OFF position.

FCV-356 bkr 52

-1G-36. ** 9003A , bkr 52-1G-48. ** 8982A , bkr 52-1G-58. ** LCV-112C , bkr 52-1G-11.** 8805B , bkr 52-1 G-14. ** FCV-363 , bkr 52-1G-23. ** 8100 , bkr 52-1G-26. ** FCV-431 , bkr 52-1G-28 ** Comment: 3. Report alignment complete 3.1 Inform ed the HSDP Operator that the 480V Bus 1G Alignment is complete.

Sat: ______ Unsat _______

Comment: Stop Time:

Total Time:

(Enter total time on the cover page)

Follow up Question Documentation

Question: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

Response: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

NRCL121-P2 PAGE 4 OF 5 R EV. 0 EXAMINEE CUE SHEET JPM NUMBER: NRCL121-P2 Initial Conditions:

GIVEN: A fire in the control boards has caused a Unit 1 Control Room evacuation.

OP AP-8A is being performed and the operating crew is ready to align bus 1G 480 VAC loads for control from the Hot Shutdown Panel Initiating Cue:

The Shift Foreman directs you to align bus 1G 480 vac loads for control at the Hot Shutdown Panel, per OP AP

-8A, App F, step 2 NRCL121-P2 PAGE 5 OF 5 R EV. 0 Control Room Inaccessibility

- Establishing Hot Standby OP AP-8A R38 Page 39 of 60 UNIT 1 OP_AP-8Au1r38.DOC 0326.2035 Phone Nos. HSDP x3107, x3781; DSDP x1355, x3179 D/G 1-1 x1249; D/G 1-2 x1251; D/G 1-3 x1438 12kV Rms x1247; 4kV Rms x1747; 480 V Rms x1372 Appendix F 480V Bus Alignment 1. 480V Vital Bus F a. Place Control Transfer Cutout Switches (green Lamicoids) to CUT-IN EQUIPMENT SWITCH POSITION Letdown Orifice 43BX CUT-IN CFCU 1-2 43X-1F-1 CUT-IN b. Open the following breakers to prevent spurious operation. FCV-430 52-1F-11 OPEN LCV-112B 52-1F-12 OPEN 8805A 52-1F-19 OPEN FCV-750 52-1F-23 OPEN 2. 480V Vital Bus G a. Place Control Transfer Cutout Switches (green Lamicoids) to CUT-IN EQUIPMENT SWITCH POSITION AFW Pp 1, FCV-95 43X-1230 CUT-IN CFCU 1-5 43X-1G-02 CUT-IN Emerg Borate 8104 43X-1G-57 CUT-IN BATP 1-2 43X-1G-04 CUT-IN LCV-106 43X-1G-44 CUT-IN LCV-107 43X-1G-68 CUT-IN b. Open the following breakers to prevent spurious operation. FCV-356 52-1G-36 OPEN 9003A 52-1G-48 OPEN 8982A 52-1G-58 OPEN LCV-112C 52-1G-11 OPEN 8805B 52-1G-14 OPEN FCV-363 52-1G-23 OPEN 8100 52-1G-26 OPEN FCV-431 52-1G-28 OPEN NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: LJP-007 Title: ALIGN 480V BUS G FOR CONTROL FROM THE HOT SHUTDOWN PANEL Examinee:

Evaluator:

Print Signature Date Testing Method:

Perform Simulate Results: Sat Unsat Total Time: minutes Comments: (Note: Any Unsat step requires a numbered comment; use back as needed.)

References:

OP AP-8A, Control Room Inaccessibility - Establishing Hot Stby, Rev. 36 Alternate Path:

Yes No X Time Critical:

Yes No X Time Allotment:

30 minutes Critical Steps:

1, 2 Job Designation:

RO/SRO Rev Comments/TIPs:

SAPN 50304333; TIPs 20047

-03, 21257-34; reduced scope of task to performing only one vital bus (vs whole appendix); Rev 17B constitutes a minor change for reference procedure rev #s. Change approved ILC Supervisor.

DCPP Task # / Rating: 812400 4.2 Gen KA # / Rating

068.AA1.21 3.9 / 4.1 AUTHOR: JOHN F. BUCKLEY 01/25/2011 REVIEWED B Y: JOHN BECERRA DATE: 01/25/2011 TRAINING SUPERVISOR APPROVED B Y: ERIK WERNER DATE: 02/03/2011 LINE MANAGER REV. 17 B JPM TITLE: ALIGN 480V BUS G FOR CONTROL FROM THE HOT SHUTDOWN PANEL JPM NUMBER: LJP-007 INSTRUCTOR WORKSHEET Directions:

No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.

The examiner will then ask if any clarifications are needed. The examinee should be given the "required materials" shown below, and access to other plant references as appropriate.

Equipment operation "Cues" are contingent on proper operation by the examinee, and should be "adjusted" should equipment operation differ from expected.

Required Materials:

Provide a copy of the reference procedure (partial procedure allowed), if the task is being done in the plant or lab; U1 OP AP-8A, App F. Initial Conditions:

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

The Shift Foreman directs you to align bus 1G 480 vac loads for control at the Hot Shutdown Panel, per OP AP-8A, App F, step 2.

NOTE: Do NOT provide the student with the Task Standard.

Task Standard:

Breakers and switches aligned for 480 vac bus 1G per App F, step 2 of OP AP-8A. LJP007.DOC PAGE 2 OF 5 R EV.17B JPM TITLE: ALIGN 480V BUS G FOR CONTROL FROM THE HOT SHUTDOWN PANEL JPM NUMBER: LJP-007 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actio ns ** 1. Place the control transfer cutout switches for 480V vital bus 1G to the CUT-IN position.

1.1 Locates 480V vital bus 1G aux relay panel in the vital switchgear room.

Note: CUT IN / CUT OUT 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 43X-1230, FCV-95.**

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • Cue: (may be given after each switch operation) The switch is in the CUTIN (up) position.

switch 43X-1G-02, CFCU 15.**

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

switch 43X-1G-04, BATP 1-2.**

switch 43X-1G-44, LCV-106.** switch 43X-1G-68, LCV-107.** Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

• Denotes an entry required on the JPM cover sheet. ** Denotes Critical Step and Sub Steps. LJP007.DOC PAGE 3 OF 5 R EV.17B JPM TITLE: ALIGN 480V BUS G FOR CONTROL FROM THE HOT SHUTDOWN PANEL JPM NUMBER: LJP-007 INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 2. Open 480V vital bus 1G breakers to prevent spurious operation.

2.1 Opens the following breakers: FCV-356 bkr 52-1G-

36. ** ************************************ Cue: (may be given after each breaker operation) The breaker is in the OFF position.

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

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

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

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

FCV-363 bkr 52-1G-

23. ** 8100 bkr 52-1G-26. **

FCV-431 bkr 52-1G-28 ** 2.2 Informs the HSDP Operator that the 480V Bus 1G Alignment is complete.

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

Stop Time:

Total Time:

(Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet. ** Denotes Critical Step and Sub Steps. LJP007.DOC PAGE 4 OF 5 R EV.17B JPM NUMBER: LJP-007 EXAMINEE CUE SHEET Initial Conditions:

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

The Shift Foreman directs you to align bus 1G 480 vac loads for control at the Hot Shutdown Panel, per OP AP-8A, App F, step 2.

LJP007.DOC PAGE 5 OF 5 R EV.17B NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-P 3 Title: ALIGN ALTERNATE AFW FROM THE FIRE WATER STORAGE TANK Examinee: Evaluator:

Print Signature Date Testing Method:

Perform Simulate X Results: Sat Unsat Total Time:

minutes Comments: This is a UNIT 2 JPM

References:

Unit 2 OP D

-1:V, Aux Feedwater System

- Alternate AFW Supplies, Rev. 18 OP1.ID2, TCOAs, Rev 5 (& TCOA database); TCOA item 35 Alternate Path:

Yes _______ No X Time Critical:

Yes X No Time Allotment:

20 minutes Critical Steps: 4, 6, 7, 8, 9 Job Designation:

RO or SRO Rev Comments:

Bank LJP-104A Gen KA / Rating:

061 A2.04 - Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

pump failure or improper operation 3.4/3.8 AUTHOR: LISA TORIBIO DATE: 06/20/2014 OPERATIONS REPRESENTATIVE

ABDUL KADIR DATE: 06/20/2014 R EV. 0 JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER STORAGE TANK JPM NUMBER: NRCL121-P 3 EVALUATOR WORKSHEET Directions:

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

Copy of the reference procedure (partial procedure allowed):

• Unit 2 OP D-1:V, Section 6.1 and Attachment 1.

• PG&E "909" key. Initial Conditions Following a reactor trip from 100% power, the Unit 2 CST level has just lowered to less than 10%

Initiating Cue:

The Shift Foreman gives you a PG&E 909 key and directs you to transfer U-2 AFW pump suction supply to Fire Water Storage Tank in accordance with OP D

-1:V, Section 6.1 DO NOT READ TASK STANDARD TO EXAMINEE Task Standard:

U-2 AFW pump suction aligned to the Fire Water Storage Tank, in accordance with OP D-1:V. Time Critical Operator Action (TCOA): This JPM was evaluated against TCOA # 35 (Realign the AFW pumps to a new suction source within 20 minutes). This TCOA:

is applicable to this JPM, so the steps in this task related to the TCOA will be critical. This task is also time critical with a start time of the beginning of the task, and ending when the alignment is completed (venting not required). The time limit is 19 minutes (20 minutes minus one minute to read the procedure step and give the direction to the field operator). NRCL121-P3 PAGE 2 OF 8 R EV. 0 JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER STORAGE TANK JPM NUMBER: NRCL121-P 3 EVALUATOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Step 6.1.1

- Check OPEN FP 0 4 (115' Elev., in FWST vault)

. 1.1 R ead NOTEs 1 and 2 prior to step 1.2 Locate d FP-0-4. 1.3 Check ed the position of FP 4 (large, rising stem valve).

Cue: Valve stem extends 12-14" from valve handwheel (open)

. **********************************

1.4 Determined FP 4 is open Sat: ______ Unsat _______

Comment: 2. Step 6.1.2

- Check AFW suction being realigned from the CST 2.1 Read Step 6.1.2 and determine d that step does not need to be performed.

Sat: ______ Unsat _______

Comment: 3. Step 6.1.3

- Check MU-0-1557 closed (100' Elev., chain operated, in hallway near RWST vault

) 3.1 3.1 Locate d MU-0-1557. 3.2 3.2 Check ed MU-0-1557 closed. 3.3 **********************************

Cue: (if tugs on chainfall in CW direction) Valve will not move (closed). (if examinee climbs up ladder; flashlight needed) Pointer is on "C" (closed)

. **********************************

3.4 Determined M U-0-1557 is closed. Sat: ______ Unsat _______

Comment: NRCL121-P 3 PAGE 3 OF 8 R EV. 0 JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER STORAGE TANK JPM NUMBER: NRCL121-P 3 EVALUATOR WORKSHEET 4. Step 6.1.4 - First Bullet - Verify MU 0 284 closed (100' Elev., north end of hallway). Note: MU-0-284 and 286 are the downstream isolations for the in

-line strainers. One will be in service, and the other OOS. This JPM is written for current plant conditions, but if the "lower" strainer is in service [MU 286], then make step 4 non

-critical, and step 5 critical [ie, both strainers OOS].

4.1 Note: Steps 4 and 5 may be performed in any order (steps are bullets in OP D-1:V). Both valves are rising stem handwheel operated valves ( 10" rise when open);

MU-0-284 is normally OPEN. 4.2 Locate d MU-0-284 4.3 Check ed MU-0-284 position.

Cue: Valve stem is 10" out from valve handwheel.

4.4 Close d MU-0-284. ** **********************************

Cue: Valve stem is now only about an inch from the handwheel, and the handwheel won't move in CW direction (closed).

Sat: ______ Unsat _______

Comment: 5. Step 6.1.4 - Second Bullet - Verify closed MU-0-286 (100' Elev., north end of hallway).

5.1 Locate d MU-0-286 5.2 Check ed MU-0-286 position.

Cue: Valve stem is 1" out from valve handwheel, and won't move in CW direction.

5.3 Determined MU 286 is closed Sat: ______ Unsat _______

Comment: NRCL121-P 3 PAGE 4 OF 8 R EV. 0 JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER STORAGE TANK JPM NUMBER: NRCL121-P 3 EVALUATOR WORKSHEET 6. Step 6.1.5

- Open FP-0-306 and FP 307 (chain operated, normally locked closed 100' Elev., above MU Water pps, near north wall).

6.1 Read Step 6.1.5 and determine d that step needs to be performed.

Note: FP-0-306 and -307 are normally chained and locked closed. These valves may be operated in any order (steps are bullets

). ***********************************

Cue: The SFM has assigned another operator to complete the sealed component change forms.

6.2 Locate d FP-0-306. 6.3 Unlock ed and open ed FP-0-306. ** ***********************************

Cue: (if chainfall operated to turn valve operator CCW to open) The valve move d several turns CCW and stopped (open seat).

6.4 Locate d FP-0-30 7. 6.5 Unlock ed and open ed FP-0-30 7. ** ***********************************

Cue: (if chainfall operated to turn valve operator CCW to open) The valve move d several turns CCW and stopped (open seat).

Sat: ______ Unsat _______

Comment: NRCL121-P 3 PAGE 5 OF 8 R EV. 0 JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER STORAGE TANK JPM NUMBER: NRCL121-P 3 EVALUATOR WORKSHEET 7. Step 6.1.6 - Open FCV 436 and 437 (100' Elev., AFW Pp 2

-1 room) Note: These valves in the next several steps may be operated in any order (steps are bullets

). 7.1 Locate d FCV-436 and FCV

-437. 7.2 Open ed FCV- 436 and FCV

-437**. **********************************

Cue: (for each valve) Pointer is at "O" (open). **********************************

Sat: ______ Unsat _______

Comment: 8. Step 6.1.7 - Close AFW pump suctions from CST 8.1 Locate d and Close d FW-2-121** **********************************

Cue: (for FW-2-121, HW operated valve) Pointer is at "CLOSED". **********************************

8.2 Locate d and Close d FW-2-159 & 180** **********************************

Cue: (for FW-2-159 and FW-2-180, handle operated butterfly valves)

Handle is down to the "perpendicular to pipe" position.

Note the time the examinee closed the final normal suction valve (TCOA stop time): _________________________

Sat: ______ Unsat _______

Comment: NRCL121-P 3 PAGE 6 OF 8 R EV. 0 JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER STORAGE TANK JPM NUMBER: NRCL121-P 3 EVALUATOR WORKSHEET 9. Step 6.1.8

- If necessary, vent AFW pump casings

Cue: Suction to the AFW pumps was NOT lost. **********************************

9.1 Determine d venting is not required.

Sat: ______ Unsat _______

Comment: 10. Step 6.1.9 - Notify Control Room 10.1 Notifie d the Control Room AFW pump s now available from the FWST Sat: ______ Unsat _______

Comment: Stop Time:

Total Time:

(Enter total time on the cover page)

Follow up Question Documentation

Question: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

Response: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

NRCL121-P 3 PAGE 7 OF 8 R EV. 0 EXAMINEE CUE SHEET JPM NUMBER: NRCL121-P 3 Initial Conditions: Following a reactor trip from 100% power, the Unit 2 CST level has just lowered to less than 10%

Initiating Cue: The Shift Foreman gives you a PG&E 909 key and directs you to transfer U-2 AFW pump suction supply to Fire Water Storage Tank in accordance with OP D

-1:V, Section 6.1

NRCL121-P3 PAGE 8 OF 8 R EV. 0

• • • ISSUED FOR USE BY: _______________________ DATE: ____________ EXPIRES: ____________ ***

DIABLO CANYON POWER PLANT OPERATING PROCEDURE UNIT 2 OP D-1:V Rev. 19 Page 1 of 15 Auxiliary Feedwater System - Alternate Auxiliary Feedwater Supplies Effective Date QUALITY RELATED Table of Contents OP_D-1~Vu2r19.doc 1212.0935 1. SCOPE ........................................................................................................... 1 2. DISCUSSION ................................................................................................. 1 3. RESPONSIBILITIES ....................................................................................... 2 4. PREREQUISITES ........................................................................................... 2 5. PRECAUTIONS AND LIMITATIONS .............................................................. 2 6. INSTRUCTIONS ............................................................................................. 3 6.1 Transferring AFW Pump Suction Supply to the FWST .................................... 3 6.2 Transferring AFW Pump Suction Supply to the Raw Water Reservoir from the CST .......................................................................................................... 5 6.3 Making Up to the CST from the Condenser Hotwell ........................................ 6 6.4 Supplying AFW Pump Suction from the Makeup Water Transfer Tank via the Makeup Water Transfer Pumps ................................................................ 7 6.5 Supplying AFW Pump Suction from the FWST Using the Diesel-Driven Portable Long Term Cooling Water Pump ....................................................... 9 6.6 Transferring AFW Pump Suction Supply to the CST ..................................... 10 6.7 Swapping AFW Pump Suction Line Raw Water Strainers ............................. 12 7. REFERENCES ............................................................................................. 13 8. RECORDS .................................................................................................... 13 ATTACHMENTS:

1. AFW Supply from FWST ............................................................................... 14 2. AFW Supply from M/U Transfer Tank ........................................................... 15 1. SCOPE 1.1 This procedure provides the necessary instructions for aligning alternate feedwater sources to the AFW System, returning to the preferred normal CST source, and swapping raw water suction strainers.T33170/T35018 1.2 These sources of AFW are listed in preferred order of use.Ref 7.2.2 2. DISCUSSION 2.1 This procedure is referred to whenever the Condensate Storage Tank (CST) is less than 10% and alternate Auxiliary Feedwater (AFW) to the steam generators is required.

Auxiliary Feedwater System

- Alternate Auxiliary Feedwater Supplies OP D-1:V R19 Page 2 of 15 UNIT 2 OP_D-1~Vu2r19.doc 1212.0935 3. RESPONSIBILITIES 3.1 Shift Foreman is responsible for system alignment and operation of equipment required by this procedure. 4. PREREQUISITES 4.1 Ensure that the following systems or components are in service, as applicable to the specific water supply to be used:

• Main Steam

• Plant Electrical

• Fire Water Storage Tank

• Condensate Storage Tank

• Condenser hotwell

• Makeup Water System

• Diesel-Driven Portable Long Term Cooling Water Pumps

5. PRECAUTIONS AND LIMITATIONS 5.1 Do not align alternate sources of supply to the AFW System unless the CST is not available as the normal source. 5.2 Volume 9B Section IF contains data on the CST volume required considering time maintaining hot standby and plant cooldown rate. 5.3 AFW pump recirc return to the CST at 50 gpm per pump shall be accounted for when making "time remaining" calculations for AFW supplies other than the CST. 5.4 Sealed component change forms shall be filled out where appropriate as required by OP1.DC20, "Sealed Components."

Auxiliary Feedwater System

- Alternate Auxiliary Feedwater Supplies OP D-1:V R19 Page 3 of 15 UNIT 2 OP_D-1~Vu2r19.doc 1212.0935 6. INSTRUCTIONS 6.1 Transferring AFW Pump Suction Supply to the FWSTRef 7.2.2 NOTE 1: This is the preferred source of alternate water supply. NOTE 2: Attachment 1 has a drawing depicting this alignment. 6.1.1 Check OPEN FP-0-4, FWST to Fire Pump Suction (115 ft, FWST Vault). 6.1.2 IF AFW pump suction is being realigned to the FWST from a source other than the CST, THEN unlock and open the following (sealed closed, chain operated, above MU Water Pump 0-1):

• FP-0-306, Firewater to AFW Pumps

• FP-0-307, Firewater to AFW Pumps 6.1.3 Check CLOSED and sealed MU-0-1557, Raw Water Header Isolation (sealed closed, chain operated, U1 100 ft hallway at entrance to RWST Vault). 6.1.4 Ensure CLOSED the following (U1, 100 ft N end of hallway):

• MU-0-284, Strainer 97 Outlet Isolation Valve

• MU-0-286, Strainer 98 Outlet Isolation Valve 6.1.5 IF AFW pump suction is being realigned to the FWST from the CST, THEN unlock and open the following (sealed closed, chain operated, above MU Water Pump 0-1):

• FP-0-306, Firewater to AFW Pumps

• FP-0-307, Firewater to AFW Pumps NOTE: The components for the following steps are located in Unit 2. 6.1.6 Unseal and open the following (sealed closed, 100 ft AFW Pump 2-1 Room):

• FW-2-FCV-436, Raw Water to AFW Pump 2-1

• FW-2-FCV-437, Raw Water to AFW Pumps 2-2 & 2-3 6.1.7 Unseal and close AFW pump suctions from the CST:

• FW-2-121, AFW Pump 2-1 Suction Valve

• FW-2-159, AFW Pump 2-2 Suction Valve

• FW-2-180, AFW Pump 2-3 Suction Valve Auxiliary Feedwater System

- Alternate Auxiliary Feedwater Supplies OP D-1:V R19 Page 4 of 15 UNIT 2 OP_D-1~Vu2r19.doc 1212.0935 6.1.8 IF suction to the AFW pumps was lost, THEN vent the AFW pump casings as necessary to remove trapped air:

• FW-2-127, AFW Pump 2-1 Casing Vent

• FW-2-128, AFW Pump 2-1 Casing Vent

• FW-2-165, AFW Pump 2-2 Casing Vent

• FW-2-186, AFW Pump 2-3 Casing Vent NOTE: CST level may increase since AFW pump recirc returns to the CST. 6.1.9 Notify the Control Room that the suction for the AFW pumps is now available from the FWST. CAUTION: With AFW pumps running and suction supply aligned to the FWST, suction to all AFW pumps will be lost (common mode failure) if FWST level reaches the lower usable limit before suction is transferred back to the CST or to another alternate source. 6.1.10 Advise the Control Room as follows: a. IF at any time FWST level drops to 6%, THEN STOP all AFW pumps until pump suction has been transferred to another source. b. Before FWST level reaches its lower usable limit, perform ONE of the following:

• Transfer AFW pump suction to the CST PER Section 6.6. OR

• Transfer AFW pump suction to another desired source PER applicable section of this procedure.

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: LJP-104A Title: ALIGN ALTERNATE AFW FROM THE FIRE WATER STORAGE TANK Examinee:

Evaluator:

Print Signature Date Testing Method:

Perform Simulate Results: Sat _____ Unsat _____ Total Time: _______ TCOA Time: ______ Comments: (Note: Any Unsat step requires a numbered comment; use back as needed.)

This is a U-2 JPM

References:

Unit 2 OP D-1:V, Aux Feedwater System - Alternate AFW Supplies, Rev. 18 OP1.ID2, TCOAs, Rev 5 (& TCOA database); TCOA item 35 Alternate Path:

Yes No X Time Critical:

Yes X No Time Allotment:

40 minutes Critical Steps:

4, 6, 7, 8, 9 Job Designation:

RO/SRO Rev Comments/TIPs:

SAPN 50304333; TIPs 21236-50, 21257-56, 22418-61. Rev 1B constitutes a minor change for reference procedure rev #s. Change approved by Exam Support Group Supervisor.

DCPP Task # / Rating: 546400 4.0 Gen KA # / Rating

061.A2.04 3.4 / 3.8 AUTHOR: JOHN F. BUCKLEY DATE: 02/12/2011 REVIEWED B Y: JOHN BECERRA DATE: 02/25/11 TRAINING SUPERVISOR APPROVED B Y: ERIK WERNER DATE: 02/25/11 LINE MANAGER R EV. 1B JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER STORAGE TANK JPM NUMBER: LJP-104A INSTRUCTOR WORKSHEET Directions:

No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.

The examiner will then ask if any clarifications are needed. The examinee should be given the "required materials" shown below, and access to other plant references as appropriate.

Equipment operation "Cues" are contingent on proper operation by the examinee, and should be "adjusted" should equipment operation differ from expected.

Required Materials:

Provide a copy of the reference procedure (partial procedure allowed), if the task is being done in the plant or lab: Copy of Unit 2 OP D-1:V, Section 6.1 and Attachment 1. PG&E "909" key. Initial Conditions:

Following a reactor trip from 100% power, the Unit 2 CST level has just lowered to less than 10%. Initiating Cue:

The Shift Foreman directs you to transfer U-2 AFW pump suction supply to Fire Water Storage Tank, and to vent the AFW pumps, in accordance with OP D-1:V, Section 6.1.

NOTE: Do NOT provide the student with the Task Standard.

Task Standard:

U-2 AFW pump suction is supplied from the Fire Water Storage Tank, with the pumps vented, in accordance with OP D-1:V. Time Critical Operator Action (TCOA): This JPM was evaluated against TCOA # 35 (Realign the AFW pumps to a new suction source within 20 minutes). This TCOA:

is applicable to this JPM, so the steps in this task related to the TCOA will be critical. This task is also time critical with a start time of the beginning of the task, and ending when the alignment is completed (venting not required). The time limit is 19 minutes (20 minutes minus one minute to read the procedure step and give the direction to the field operator).

LJP 104 A.DOC PAGE 2 OF 9 R EV. 1B JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER STORAGE TANK JPM NUMBER: LJP-104A INSTRUCTOR WORKSHEET Start Time:

(also start time for TCOA)

Step Expected Operator Actions

1. Check OPEN FP-0-4 (115' Elev., in FWST vault).

1.1 Reads NOTEs 1.2 Locates FP-0-4. 1.3 Checks the position of FP-0-4 (large, rising stem valve).

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • Cue: Valve stem extends 12-14" from valve handwheel (open). **********************************

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

2. Checks AFW suction being realigned from the CST 2.1 Reads Step 6.1.2 and determines that step does not need to be performed.

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

3. Check closed MU-0-1557 (100' Elev., chain operated, in hallway near RWST vault).

3.1 Locates MU-0-1557. 3.2 Checks Closed MU-0-1557. ********************************** Cue: (if tugs on chainfall in CW direction) Valve will not move (closed). (if examinee climbs up ladder; flashlight needed) Pointer is on "C" (closed).

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

• Denotes an entry required on the JPM cover sheet. ** Denotes a Critical Step.

LJP 104 A.DOC PAGE 3 OF 9 R EV. 1 JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER STORAGE TANK JPM NUMBER: LJP-104A INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 4. Verify closed MU-0-284 (100' Elev., north end of hallway

). Note: MU-0-284 and 286 are the downstream isolations for the in-line strainers. One will be in service, and the other OOS.

This JPM is written for current plant conditions, but if the "lower" strainer is in service

[MU-1-286], then make step 4 non-critical, and step 5 critical [ie, both strainers OOS]

. Note: Steps 4 and 5 may be performed in any order because these steps are bullets in OP D-1:V. Both valves are rising stem handwheel operated valves ( 10" rise when open); MU-0-284 is normally OPE N. 4.1 Locates MU-0-284 4.2 Checks MU-0-284 position.

Cue: Valve stem is 10" out from valve handwheel.

4.3 Closes MU-0-284. ** ********************************

• • Cue: Valve stem is now only about an inch from the handwheel, and the handwheel won't move in CW direction (closed).

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

5. Verify closed MU-0-286 (100' Elev., north end of hallway).

5.1 Locates MU-0-286 5.2 Checks MU-0-286 position.

Cue: Valve stem is 1" out from valve handwheel, and won't move in CW direction.

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

[ ] Comment # (required for Unsat)

• Denotes an entry required on the JPM cover sheet. ** Denotes a Critical Step.

LJP 104 A.DOC PAGE 4 OF 9 R EV. 1 JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER STORAGE TANK JPM NUMBER: LJP-104A INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 6. Open FP-0-306 and FP-0-307 (chain operated, normally locked closed 100' Elev., above MU Water pps, near north wall).

6.1 Reads Step 6.1.5 and determines that step needs to be performed.

Note: FP-0-306 and -307 are normally chained and locked closed. These valves may be operated in any order because these steps are bullets in OP D

-1:V. *********************************** Cue: The SFM has assigned another operator to complete the sealed component change forms.

6.2 Locates FP-0-306. 6.3 Unlocks and opens FP-0-306.

• • *********************************** Cue: (if chainfall operated to turn operator CCW to open) The valve move several turns CCW and stopped (open seat). ***********************************

6.4 Locates FP-0-307. 6.5 Unlocks and opens FP-0-307.

• • *********************************** Cue: (if chainfall operated to turn operator CCW to open) The valve move several turns CCW and stopped (open seat). ***********************************

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

• Denotes an entry required on the JPM cover sheet. ** Denotes a Critical Step.

LJP 104 A.DOC PAGE 5 OF 9 R EV. 1 JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER STORAGE TANK JPM NUMBER: LJP-104A INSTRUCTOR WORKSHEET Step Expected Operator Actions ** 7. Locally open FCV-436 and 437 fully (100' Elev., AFW Pp 2-1 room).

Note: These valves in the next several steps may be operated in any order because these steps are bullets in OP D

-1:V. 7.1 Locates FCV-436 and FCV-437.

7.2 Opens FCV- 436 and FCV-437**.

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • Cue: (for each valve) Pointer is at "O" (open). **********************************

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

• • 8. Close AFW Pp suctions from CST. 8.1 Locates and Closes each valve:

AFW Pp 1 FW-2-121** 2 FW-2-159** 3 FW-2-180** **********************************

Cue: (for FW-2-121, HW operated valve) Pointer is at "CLOSED". **********************************

Cue: (for FW-2-159 and FW-2-180, handle operated butterfly valves) Handle is down to the "perpendicular to pipe" position.

Note the time the examinee closed the final normal suction valve (TCOA sto p time): _________________________

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

• Denotes an entry required on the JPM cover sheet. ** Denotes a Critical Step.

LJP 104 A.DOC PAGE 6 OF 9 R EV. 1 JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER STORAGE TANK JPM NUMBER: LJP-104A INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 9. If suction to the AFW Pps was lost, vent the AFW Pp casings as necessary to remove trapped air. 9.1 Locates the AFW pump vents:

AFW pp 2 1 - FW-2-1 27 - FW-2-128 AFW pp 2 2 - FW-2-165 AFW pp 2 3 - FW-2-186 Note: These valves may be operated in any order because these steps are bullets in OP D-1:V. They are "T" handle valves on top of each pump. 9.2 Removes vent cap and opens vent valve for each vent.

• • ********************************** Cue: (For each vent): The pump has vented completely and you have a steady stream of water coming from the vent.

9.3 Shuts each vent valve.

• • ********************************** Cue: (For each vent): Flow has stopped. The valve will not move any further CW. **********************************

9.4 Replaces each vent cap.

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • Cue: (For each vent): The pipe cap is secured on the end of the pipe. **********************************

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

• Denotes an entry required on the JPM cover sheet. ** Denotes a Critical Step.

LJP 104 A.DOC PAGE 7 OF 9 R EV. 1 JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER STORAGE TANK JPM NUMBER: LJP-104A INSTRUCTOR WORKSHEET Step Expected Operator Actions

10. Notify the Control Room that the suction for the AFW Pps is now available from the FWST.

10.1 Notifies the Control Room.

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

Stop Time:

Total Time:

(Enter total time on the cover page)

TCOA Start Time: TCOA Stop Time: TCOA Total Time:

(enter TCOA time on front page)

TCOA: SAT UNSAT (TCOA time must be < 19 minutes)

• Denotes an entry required on the JPM cover sheet. ** Denotes a Critical Step.

LJP 104 A.DOC PAGE 8 OF 9 R EV. 1 JPM NUMBER: LJP-104A EXAMINEE CUE SHEET Initial Conditions:

Following a reactor trip from 100% power, the Unit 2 CST level has just lowered to less than 10%.

Initiating Cue:

The Shift Foreman directs you to transfer U-2 AFW pump suction supply to Fire Water Storage Tank, and to vent the AFW pumps, in

accordance with OP D-1:V, Section 6.1.

LJP 104 A.DOC PAGE 9 OF 9 R EV. 1 Appendix D (rev 9)

Required Operator Actions Form ES-D-1 Facility: Diablo Canyon (PWR)

Scenario No: 1 Op-Test No: L121 NRC Examiners:

Operators:

Initial Conditions

10E-8 with AFW in service, MOL, 1660 ppm boron Turnover: At OP L-2, step 6.1.25, ready to raise power to 2%.

Continue to raise power, and stabilize at 2%. Event No Malf No. Event Type* Event Description 1 N/A R(ATC) Raise reactor power from 10E

-8 to 2% per OP L-2, sec 6.1 2 XMT_RCS6_3 (I) SRO PT-403 fails low (TS 3.3.3.A, ECG 7.8) (Used for SRO TS/ECG Only) 3 PMP_CCW2_MTRF C (BOP, SRO) CCW Pp 1-2 overcurrent trip. (AP-11; TS 3.7.7.A) 4 PMP_TUR2 OVERLOAD_DEV_FAIL C (BOP, SRO) Thermal overload of AC Bearing Oil Pump (AP-29). 5 XMT_MSS1_3 I (SRO, ATC) PT-507 slow failure low causing Group I dumps to close. (AP-5) 6 MAL_RCS 3 A 0.06 C (ALL) RCS leak ramps in over 1 minute. Leak is within the capacity of charging (60 gpm), but requires second pump to be started. (AP-1, TS 3.4.13.A

) 7 MAL_RCS 3 A 0.75 M (ALL) 700 gpm SBLOCA requiring Safety Injection (SI)

- (Auto SI failed; manual SI is required CT). 8 MAL_PPL5A/B M (ALL) ATWS, Both manual trip and 13D/E fail

. 9 PMP_CVC1 PMP_CVC2 C (BOP) On SI, running CCPs trip on OC, standby pump fail to autostart

- CT ) *(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor L121 NRC ES

-D-1-01 r1.doc Page 1 of 3 Rev 1 Appendix D (rev 9)

Required Operator Actions Form ES-D-1 Target Quantitative Attributes (Per Scenario; See Section D.5.d) (from form ES301

-4) Actual Attributes

1. Total malfunctions (5

-8) (Events 2,3,4,5,6,7,8,9) 8 2. Malfunctions after EOP entry (1

-2) (Events 8&9) 2 3. Abnormal events (2

-4) (AP-11,29,5,1) 4 4. Major transients (1

-2) (Events 7&8) 2 5. EOPs entered/requiring substantive actions (1-2) (E-1) 1 6. EOP contingencies requiring substantive actions (0

-2) (FR-S.1) 1 7. Critical tasks (2

-3)(See Scenario Summary) 2 L121 NRC ES

-D-1-01 r1.doc Page 2 of 3 Rev 1 SCENARIO

SUMMARY

- NRC #1 1. Control rods are used to raise power from 10E

-8 Amps (IR) to 2% per OP L-2, Hot Standby to Startup Mode, step 6.1.25.

2. PT-403 fails low. Crew responds to PK05-07, Subcooling Margin Lo/Lo

-Lo and PK05-09, RVLIS Lo Lvl RVLIS/SCMM Trouble and identifies affected instrumentation. Shift Foreman addresses TS 3.3.3.A, Post Accident Monitoring Instrumentation and ECG 7.8, Accident Monitoring Instrumentation.

3. CCW 1-2 trips on overcurrent and CCW 1

-3 must be started manually (auto

-start blocked) per direction in PK01-09 or as directed by OP AP-11 , Malfunction of Component Cooling Water System, Section A. T.S. 3.7.7, Vital Component Cooling Water (CCW) System, is entered for one loop of CCW inoperable.

4. AC Lube Oil Pump trips on thermal overload. Crew responds to PK12-16,Turbine Lube Oil System and is directed to OP AP-29, Main Turbine Malfunction to start the DC Backup Pump (autostart failed).

5. PT-507 slowly fails low causing Group I dumps to close. Crew diagnoses the failure and takes manual control of HC

-507. OP AP-5, Malfunction of Eagle 21 Protection or Control Channel is used to address the failure and return primary and secondary to normal bands.

6. 60 gpm RCS leak develops on Loop 1, ramping in over 1 minute. Crew evaluates plant symptoms and enters OP AP-1, Excessive Reactor Coolant System Leakage

, which directs starting of a second charging pump to maintain pressurizer level. Shift Foreman enters T.S. 3.4.13.A, RCS Operational Leakage based on the estimated leak size.

7. 700 gpm SBLOCA on Loop 1 cold leg. Auto Safety Injection (SI) fails to actuate, requiring manual SI (Critical Task E D: Manually initiate Safety Injection before transitioning to any E

-1, E-2, or E-3 series procedure

)**. 8. Crew's attempt to trip reactor from the control room is unsuccessful. Shift Foreman enters EOP E-0 (Reactor Trip or Safety Injection) and transitions to EOP FR-S.1, Response to Nuclear Power Generation / ATWS. 9. On SI, running CCPs trip on overcurrent. Remaining ECCS CCP fail s to autostart, but can be started manually.

(Critical Task E I: Establish flow from at least one high

-head ECCS pump before transition out of E

-0)**. 1 0. After addressing ATWS condition, crew transitions through E-0 (Reactor Trip or Safety Injection) and E-1 (Loss of Reactor or Secondary Coolant) to E-1.2 (Post LOCA Cooldown and Depressurization) . The scenario is terminated at entry into E

-1.2, Post LOCA Cooldown and Depressurization.

L121 NRC ES

-D-1-01 r1.doc Page 3 of 3 Rev 1 Appendix D (rev 9)

Required Operator Actions Form ES-D-1 Facility: Diablo Canyon (PWR)

Scenario No.:

2 Op-Test No.: L 1 2 1-NRC Examiners:

Operators:

Initial Conditions

100%, MOL, 961 ppm boron Turnover: Bus H Work Week: AFW 1

-2 OOS, D/G 1

-1 OOS Maintenance in progress on PCV

-20. CCP 1-1 In Service.

Event No Malf No. Event Type* Event Description 1 XMT_RMS 11_3 I (SRO, BOP) RM-12 (containment gaseous radiation monitor) fails high requiring crew to place leak detection system in service (TS 3.4.15.C) 2 PMP_CVC1_MTRF C (ALL) CCP 1-1 OC Trip requiring restoration of letdown (TS 3.5.2.A) (AP-17) 3 MAL_CVC8A 100.0 ramp=30 C (SRO, ATC) Seal Injection Filter 1

-1 plugs causing reduction in charging flow to RCP seals. 4 MAL_EPS4 E DIFF C (SRO, BOP) Loss of 4KV Vital Bus H (diff trip); alternate equipment is placed in service, and Tech Specs are implemented (AP-27) (TS 3.4.11.C, 3.8.4.A). 5 LOA_CND1 5E

-5 LOA_CND1 1 LT 1010 C (SRO, BOP) R (ATC) Slow vacuum leak develops as result of loop seal maintenance activities requiring ramp. (AP-7 and AP-25). 6 LOA_CND1 5E

-5 LOA_CND1 1 LT 1010 M (ALL) Loop seal fails during Maintenance attempt to back out of field activity resulting in rapid loss of vacuum; turbine/Rx trip (AP-7). 7 MAL_AFW1 1 cd='fnispr_1 lt 5 PMP_AFW2 C (BOP) Immediately following the Rx Trip, TDAFW trips on overspeed and MDAFW 1-3 fails to autostart, requiring manual start of motor driven pump (CT). 8 PMP_AFW2_MTRF M (ALL) Crew transitions to E

-0.1. MDAFW 1

-3 trips on overcurrent leading to Loss Of Heat Sink condition. Secondary heat sink is restored using condensate (CT). *(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor L121 NRC ES

-D-1-02 r1.doc Page 1 of 3 Rev 1 Appendix D (rev 9)

Required Operator Actions Form ES-D-1 Target Quantitative Attributes (Per Scenario; See Section D.5.d) (from form ES301

-4) Actual Attributes

1. Total malfunctions (5

-8) (Events 1,2,3,4,5,6,7,8) 8 2. Malfunctions after EOP entry (1

-2) (Event 7) 1 3. Abnormal events (2

-4) (AP-17, AP-27, AP-7, AP-25) 4 4. Major transients (1

-2) (Events 6&8) 2 5. EOPs entered/requiring substantive actions (1

-2) (E-0.1) 1 6. EOP contingencies requiring substantive actions (0

-2) (FR-H.1) 1 7. Critical tasks (2-3) (See Scenario Summary) 2 .L121 NRC ES

-D-1-02 r1.doc Page 2 of 3 Rev 1 SCENARIO

SUMMARY

- NRC #2 1. RM-12 fails high and crew responds using guidance of AR PK11-21, High Radiation which calls for CFCU Drain Collection System to be placed in service. Shift Foreman enters TS 3.4.15.C, RCS Leakage Detection Instrumentation.

2. CCP 1-1 trips on overcurrent causing letdown to isolate. Crew restores charging and letdown using OP AP-17, Loss of Charging and addresses TS 3.5.2.A, ECCS

- Operating. 3. In-service Seal Injection Filter 1

-1 plugs, reducing flow to RCP seals and bringing in AR PK04-22, RCP Seal Inj Fltr Delta

-P Hi. Crew throttles RCP seal injection hand control valve, HCV

-142, as needed to maintain pressurizer level and directs field operator to swap seal injection filters.

4. 4 kV bus H trips on differential. OP AP-27, Loss of Vital 4kV and/or 480V Bus is used to stabilize and respond to the loss of the bus, and restoration of equipment. Applicable short actions Tech Specs:

TS 3.4.11.C-Pressurizer Power Operated Relief Valves; Operating; 3.8.4.A

-DC Sources.

(Already in TS 3.8.1.B-AC Sources for D/G 1

-1 OOS). 5. Slow vacuum leak develops as result of maintenance activities on the Turbine loop seal, requiring crew to reduce load. Vacuum stabilizes when seal work is stopped in response to PA from Control Room (OP AP-7, Degraded Condenser and OP AP

-25, Rapid Load Reduction or Shutdown

) 6. Loop seal fails during maintenance attempt to back out of field activity. Vacuum degrades rapidly, quickly reaching the automatic Turbine trip setpoint.(OP AP-7, Degraded Condenser)

7. Turbine driven AFW pump trips on overspeed and cannot be restarted. The remaining motor driven AFW pump (MDAFW 1

-3) fails to auto start and must be started manually (Critical Task FR

-H.1-E: Establish greater than 435 gpm feedwater flow rate to available S/Gs before 3 of 4 WR levels indicate less than 18%

). 8. Crew transitions from E-0, Reactor Trip or Safety Injection to E-0.1, Reactor Trip Response to stabilize the plant. MDAFW 1

-3 trips on overcurrent leading to Loss Of Heat Sink condition.

EOP FR-H.1, Response to Loss of Secondary Heat Sink is used to establish secondary feedwater from the condensate system.

(Critical Task FR-H.1-A: Establish feedwater flow into at least one S/G before RCS bleed and feed is required (i.e. before WR S/G level in any 3 S/G is less than 18% OR Pressurizer pressure is greater than 2335 psig due to a loss of secondary heat sink

). The scenario is terminated in FR

-H.1, once condensate flow to the steam generators has been established.

L121 NRC ES

-D-1-02 r1.doc Page 3 of 3 Rev 1 Appendix D (rev 9) Required Operator Actions Form ES-D-1 Facility: Diablo Canyon (PWR)

Scenario No.:

3 Op-Test No.: L 1 2 1-NRC Examiners:

Operators:

Initial Conditions

75%, MOL, 1014 ppm boron Turnover: Bus H Work Week: AFW 1

-2 OOS, D/G 1

-1 OOS Maintenance in progress on PCV

-20. CCP 1-1 In Service.

Event No Malf No. Event Type* Event Description 1 MAL_NIS6D 200 (ramp in slowly)

I (ALL) NI-44 slowly fails high causing unwarranted rod motion (TS 3.3.1.D , E,S,T; ECGs 37.2, 37.3) (AP-5) 2 PMP_CND2 BLOCK_AUTO_STRT PMP_CND3_MTRF 15.0 C (SRO, BOP) Condensate Booster Pump 1

-3 Trips on overcurrent. Standby fails to autostart (AP-15). 3 MAL_RCS4F 35 delay=0 ramp=120 C (ALL) R (ATC) 35 gpm tube leak ramps in over 2 minutes on S/G 1

-2, requiring power reduction. (TS 3.4.15.A) (AP-3) 4 MAL_CWS2C 1.3 delay=0 ramp=2 C (SRO, BOP) Condenser in

-leakage in SW quadrant requiring 25 MW/min ramp (AP-20) 5 MAL_RCS4 F 400 delay=0 ramp=120 M (ALL) S/G 1-2 ruptures (400 gpm) requiring Safety Injection.

6 VLV_SIS3_1 1 VLV_SIS4_1 1 C (BOP) 8801A/B fail to open on SI, requiring manual opening to establish high head ECCS injection (CT) 7 insert MAL_MSS1B 3500000.0 cd='fnispr lt 5.0' delay=0 ramp=60 M (ALL) MSLB on S/G 1

-2 inside containment downstream of flow restrictor on Rx Trip resulting in faulted/ruptured S/G (CT) 8 insert VLV_MSS7_2 1.0 insert VLV_MSS8_2 1.0 delIA VLV_MSS7_2 2 delIA VLV_MSS8_2 2 C (BOP) MSIVs on leads 1 & 2 fail to close in auto, but can be closed manually *(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor L121 NRC ES

-D-1-03 r1.doc Page 1 of 3 Rev 1 Appendix D (rev 9) Required Operator Actions Form ES-D-1 Target Quantitative Attributes (Per Scenario; See Section D.5.d) (from form ES301

-4) Actual Attributes

1. Total malfunctions (5

-8) (Events 1,2,3,4,5,6,7,8) 8 2. Malfunctions after EOP entry (1

-2) (Events 6,8) 2 3. Abnormal events (2

-4) (AP-5, AP-15, AP-3, AP-20) 4 4. Major transients (1

-2) (Event 5,7) 2 5. EOPs entered/requiring substantive actions (1

-2) (E-2, E-3) 2 6. EOP contingencies requiring substantive actions (0

-2) (terminate @ ECA

-3.1 entry) 0 7. Critical tasks (2

-3) (See Scenario Summary) 2 L121 NRC ES

-D-1-03 r1.doc Page 2 of 3 Rev 1 SCENARIO

SUMMARY

- NRC #3 1. NI-44 slowly fails high causing inward rod motion. Crew diagnoses failure, and once motion is deemed unwarranted, takes rods to manual. Failure is addressed per OP AP-5, Malfunction of Eagle 21 Protection or Control Channel, which removes the failed channel from service and directs the Shift Foreman to address Tech Specs 3.3.1.D,E,S,T Reactor Trip System Instrumentation; ECG 37.2 Axial Flux Difference (AFD) monitoring, and ECG 3.73 (Quadrant Power Tilt Ratio Alarms)

. 2. Condensate Booster Pump 1

-3 trips and standby pump fails to autostart. Crew responds by manually starting standby pump and following guidance of OP AP-15, Loss of Feedwater Flow

. 3. S/G 1-2 develops a 35 gpm tube leak over a two minute period. Crew determines leak rate and enters OP AP-3, Steam Generator Tube Failure. Leak is also evaluated per OP O-4, Primary to Secondary Steam Generator Tube Leak Detection, which directs crew to reduce power by 50% in the next hour and be in Mode 3 within two hours. Shift Foreman determines TS 3.4.13.A, RCS Operations Leakage applies. 4. A saltwater leak develops in the SW quadrant of the condenser, requiring the crew to raise the ramp rate to 25 MW/min per OP AP-20, Condenser Tube Leak

. 5. S/G 1-2 ruptures during ramp, requiring crew to initiate a Safety Injection and enter EOP E-0, Reactor Trip or Safety Injection. 6. On the SI, two of the charging injection isolation valves fail to open, but are opened manually in order to supply high

-head ECCS injection.

(Critical Task E D: Establish high head ECCS flow prior to exiting EOP E

-0) ** 7. On the Reactor Trip, a Main Steam Line Break occurs on S

/G 1-2 inside containment, downstream of the flow restrictor, resulting in a faulted/ruptured condition.

The S/G will be isolated per EOP E-2 , Faulted S/G Isolation (Critical Task E-2-A: Isolation of Faulted S/G initiated before transition out of EOP E-2) ** 8. MSIVs on steam leads 1 and 2 fail to isolate and are closed manually by the crew.

The crew will continue to mitigate the casualty following the guidance of EOP E-3, Steam Generator Tub e Rupture, and transition to EOP ECA-3.1, SGTR with Loss of Reactor Coolant

- Subcooled Recovery Desired. The scenario is terminated once crew transitions to ECA 3.1, SGTR with Loss of Reactor Coolant - Subcooled Recovery.

L121 NRC ES

-D-1-03 r1.doc Page 3 of 3 Rev 1 AppendixD(rev9)RequiredOperatorActionsFormES D 1L121NRCES D 1 04r1.docPage1of3Rev1Facility:DiabloCanyon(PWR)ScenarioNo.: 4Op TestNo.: L121 NRCExaminers:Operators:InitialConditions:100%,MOL,961ppmboronTurnover:BusHWorkWeek:AFW1 2OOS,D/G1 1OOSMaintenanceinprogressonPCV 20.CCP1 1InService.EventNoMalfNo.EventType*EventDescription1XMT_CVC20_3I(SRO,BOP)VCTlevelLT 114graduallyfailshighcausingletdownflowtodiverttotheLHUTs.Auto makeupcommenceswhenactuallevelfallsto14%(AP 19);2MAL_SEI1.15delay=0ramp=5VLV_PZR5_20.25delay=0ramp=5C(SRO,BOP)PCV 456slowlydriftsopenfollowingsmallseismicandcannotbeclosed.AssociatedblockvalveisclosedtoisolatethePORV(AP 13)(TS3.4.11.B,CT)3R(ALL)CallfromGridControlCenterforUnit1backdownordertoshed350MWwithin10minutesduetogriddisturbance(AP 25)4MAL_ROD3A_RODB10MAL_ROD3ASTATIONARYC(ALL)Droppedrodandurgentfailureat855MWinhibitsautorodmotionandrequiresrodstobetakentomanual(AP 12C)(TS3.1.4.B).5MAL_SEI1.17delay=0ramp=6MAL_SYD356.0delay=3ramp=30M(ALL)Secondseismicresultsinfullloadrejection.RodsarestillinmanualandcrewmusttripthereactorbasedonfirststepofAP 2.6MAL_SEI1.3delay=0ramp=6MAL_SYD20C(SRO,BOP)LossofStartupimmediatelyfollowingRxTrip.D/G1 3failstoautostartbutcanbemanuallystarted.7MAL_RCS1D50%_dbaMTRF15cd='jpplsiaorjpplsib'PMP_SIS1_MTRF15.0cd='jpplsiaorjpplsib'M(ALL)StrongaftershockresultsinLBLOCA.ECCSCCPsandSIP1 1triponovercurrentreducingtheamountofhighheadinjection.8PMP_RHR1BLOCK_AUTO_STRTPMP_CSS1BLOCK_AUTO_STRTC(BOP)RHR1 1andCSP1 1failtoautostart,butmaybemanuallystarted(CTs).*(N)ormal,(R)eactivity,(I)nstrument,(C)omponent,(M)ajor AppendixD(rev9)RequiredOperatorActionsFormES D 1L121NRCES D 1 04r1.docPage2of3Rev1TargetQuantitativeAttributes(PerScenario;SeeSectionD.5.d)(fromformES301 4)ActualAttributes1. Totalmalfunctions(5-8)(Events1,2,4,5,6,7,8)72. MalfunctionsafterEOPentry(1-2)(Events6,7,8)33. Abnormalevents(2-4)(AP 19,AP 25,AP 12C,AP 2)44. Majortransients(1-2)(Events5&7)25. EOPsentered/requiringsubstantiveactions(1-2)(E 0.1,E 1)26. EOPcontingenciesrequiringsubstantiveactions(0-2)(ECA 0.3)17. Criticaltasks(2-3)(SeeScenarioSummary)3 L121NRCES D 1 04r1.docPage3of3Rev1SCENARIO

SUMMARY

-NRC#41.VolumeControlTank(VCT)levelchannelLT 114failshigh,causingletdowntodiverttotheLHUTs.AutomaticreactormakeupwillmaintainVCTlevelabove14%.ThecrewdiagnosesthelevelchannelfailurebycomparingotherVCTparameters,andaddressesissuefollowingOPAP 19,MalfunctionoftheReactorMakeupControlSystemguidance.LCV112AcontrolissettotheVCTposition.2.SmallseismiccausesPCV 456toslowlydriftopenandmustbeisolatedusingtheassociated8000 Cblockvalve.ShiftFormanentersTS3.4.11.BPressurizerPowerOperatedReliefValves(PORVs).(CriticalTask:IsolatePORVpriortopressurizerpressureloweringto1950psig(lowpressurizerpressureRxtripsetpoint)).3.GridControlCenter(GCC)callswithabackdownorderforDCPPduetogriddisturbance.ShiftManagerdirectsUnit1toshed350MWinthenext10minutes.CrewcommencesrampusingguidanceofOPAP 25,RapidLoadReductionorShutdowntoreduceload.4.At855MW,aRodControlUrgentFailureoccursandrodB10isdrops.CrewplacesrodcontrolinmanualandentersOPAP 12C,DroppedControlRod.TurbineisusedtoreturnTavetoTref.ShiftForemanentersTS3.1.4.BRodGroupAlignments

.5.Alargeseismiceventoccurs,resultingina500kVgridinstability/underfrequencycondition.Unitseparatesfromthegrid.CrewentersOPAP 2,FullLoadRejection ,andtripsthereactorsbasedonunavailabilityofautorodcontrol.6.CrewentersE 0,ReactorTriporSafetyInjection ,andtransitionsintoE 0.1,ReactorTripResponsetostabilizetheplant.Start uppowerislostandD/G1 3failstoautostartduetoashutdownrelay,reducingvital4kVpowertoasinglebus(D/G1 1outofservicefrominitialconditions).ECA 0.3,Restore4kVBusesisimplementedinparallelwithE 0.1.D/G1 3shutdownrelayisresetfromthecontrolroomandthedieselstartedinmanual.7.AlargeaftershockoccursresultinginaLBLOCA.ECCSCCPs(HighHeadInjection)andSIP1 1(IntermediateHeadInjection)alltriponovercurrent.CrewreentersE 0,ReactorTriporSafetyInjection,andtransitionstoE 1,LossofReactororSecondaryCoolant.8.RHRP1 1(LowHeadInjection)andCSP1 1(ContainmentSpray)failtoautostart,butmaybemanuallystarted(CriticalTaskE0-H:ManuallystartatleastonelowheadECCSpumpbeforetransitionoutofE 0andCriticalTaskE0-E:Manuallyactuateatleasttheminimumrequiredcomplementofcontainmentcoolingequipmentbeforeanextreme(redpath)challengedevelopstothecontainmentcriticalsafetyfunction.)ThescenarioisterminatedoncecrewhascompletedactionsofEOPE 1andiswaitingtotransitiontoColdLegRecirc.

AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage4of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 1Page1of 30EventDescription:Raisereactorpowerfrom10E 8to2%TimePositionApplicant'sActionsorBehaviorNote:Procedurestepnumbersareincludedatthefrontofeachaction/commentinparenthesis,whereapplicable.(OPL 2,SecondaryPlantStartup,startingatstep6.1.26)SROReadsNOTEregardingPK04 03(TavedeviationfromTref)priortostep6.1.26ATC (6.1.26)Slowlyraisespowerto2%bypullingcontrolrods,observing3steppullandwaitadministrativelimit.SROReadsNOTEregardingindicationsforpointofaddingheat Loweringstartuprate Risingsteamdumpdemand,pressurizerlevel,TaveSROProvidesreactivityoversightwhileraisingpower.ATC (6.1.26.a)Verifiesproperplantresponseatpointofaddingheat: Steamdumpsbegintomodulate AFWflowrisestomaintainSGlevelatprogrammedlevel(68%)ATC (6.1.26.b)ContinuouslymonitorsTave,T,andNIresponsewhileraisingpower.ATCStabilizespoweratapproximately2%reactorpower.SRO/BOP (6.1.27)PlacesRM 2HighAlarmSetpointselectswitchintheMODES1&6position.ProceedtonexteventafterRM 2HighAlarmSetpointselectswitchsettoMode1&6position,perleadexaminer.**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage5of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 2Page2of 30EventDescription:PT 403LowTimePositionApplicant'sActionsorBehaviorNote:ARPK05 07,"SUBCOOLINGMARGINLO/LO LO"andARPK0509,"RVLISLOLVL,RVLIS/SCMMTROUBLE",bothalarm.SROmayuseeitherPKtoaddresstheissueprovidedallapplicableTSandECGsareidentified.AllDiagnosesPT 403hasfailedhighfromoneormoreofthefollowing(VB 2): PK05 07,"SUBCOOLINGMARGINLO/LO LO" PK05 09,"RVLISLOLVL,RVLIS/SCMMTROUBLE"VB 3Indications: PR 403,"LOOP4HOTLEGPRESS-WIDERANGE"=0psig(bottomofscalelow) YI 31,"SUBCOOLMARGINMON-TRAINB"= 40 o F(bottomofscalelow)IfARPK05 07isentered;otherwisethissectionisN/ASRO/ATC (1.0)Identifiesinputs1152(SubcooledMonLoMarginFromRVLISAorB)and1600(SubcooledMonLo LoMarginfromRVLISTrainB)andgoestosection2.1forGeneralActionsSROReadsNOTEregardingP 10priortostep2.1SRO/BOP (2.1.1)ObservesdiverseRCSpressureandtemperatureindicationsanddeterminessubcooledmarginisNOTlow.IdentifiesPR 403readingbottomofscaleasindicationoffailedinstrument(PPC,CC1,CC2,VB2)SRO (2.1.2)DeterminesRCSisNOTapproachingasaturatedconditionandcontinuestonextstepALL (2.1.3)ConfirmsspecificinstrumentfailureasPT403:o (2.1.4.a)DeterminesfailureisassociatedwithRVLIS/SCMM,TrainBo (2.1.4.b)Checkstrain specificsubcoolingindicationstoconfirmfailure(PPC,SPDSTrainB,YI 31onVB2,PAM4Display-mayuseany)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage6of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 2Page3of 30EventDescription:PT 403FailsLow(cont)TimePositionApplicant'sActionsorBehavior(ARPK05 07,continued)SROReadsNOTEregardingpossibleThermocoupleMonitoringSystemfailure(PK05 15)anddeterminesitdoesn'tapplySRO (2.1.3)ConfirmsspecificinstrumentfailureasPT 403(continued):o (2.1.3.c)NotesPK05 15isNOTinalarmandcontinuestonextstepo (2.1.3.d)ReferencesAP 5,"MalfunctionofProtectionorControlChannel"astimepermits(describedlaterinthissection)SRO (2.1.4)ReviewsECG7.8,"AccidentMonitoringInstrumentation"forapplicability.DeterminesLCOismeet(requirednumberofchannelsandminimumchannelsoperable=1)IfARPK05 09isentered;otherwisethissectionisN/ASRO/ATC (1.0)Identifiesinputs1208(ReactorVesselLevelLoTrainB)and1209(RVLIS/SCMMTroubleTrainB);goestosection2.1forGeneralActionsSROReadsNOTEregardingO/EonerroneousRVLISlowlevelalarmspriortostep2.1.1SRO/BOP (2.1.1)ChecksRVLISonPAM4anddetermineslowsubcooledmarginreadingiscausingthealarm(PAM4islocatedinareabehindverticalboards)SRO (2.1.2)DeterminesRVLISisNOTlowandcontinuestonextstepSRO/BOP (2.1.3)ObservesdiverseRCSpressureandtemperatureindicationsanddeterminessubcooledmarginisNOTlow(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage7of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 2Page4of 30EventDescription:PT 403FailsLow(cont)TimePositionApplicant'sActionsorBehavior(ARPK05 09,continued)ALL (2.1.4)IdentifiesspecificinstrumentfailureasPT403:o (2.1.4.a)DeterminesfailureisassociatedwithRVLIS/SCMM,TrainBo (2.1.4.b)ChecksPAM4(TrainB)I/OSummaryScreeninputsandidentifiesfailedpressuretransmitter(PAM4islocatedinareabehindverticalboards)SRO (2.1.5)EntersTS3.3.3.A,"PostAccidentMonitoringInstrumentation"forinoperablechannelassociatedwithRCSPressure(WideRange)andReactorVesselLevelIndicatingSystem(RVLIS)functions.Requiredaction:restoretooperablestatuswithin30daysIfOPAP 5isreferenced;otherwisethissectionisN/ANote:PT 403providesnocontrollingfunctions.ShiftForemanmaygodirectlytoOPAP 5,Attachment4.1toidentify/confirmpreviousidentificationofapplicableTechSpecsandECGs.SRO EntersTS3.3.3.A,"PostAccidentMonitoringInstrumentation"forinoperablechannelassociatedwithRCSPressure(WideRange)andReactorVesselLevelIndicatingSystem(RVLIS)functions.Requiredaction:restoretooperablestatuswithin30days. ReviewsECG7.8,"AccidentMonitoringInstrumentation"forapplicability.DeterminesLCOismeet(requirednumberofchannelsandminimumchannelsoperable=1)SRO/BOPPlacesOutofServicestickersonthefollowingaffectedequipment: PR 403(VB 2) RVLISTRAINB(PAM1,behindVB 5) Sub cooledMarginMonitor(PAM4,behindVB 3)ProceedtothenexteventonceTechSpecshavebeenaddressedperleadexaminer**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage8of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 3Page5of 30EventDescription:CCW1 2OvercurrentTripTimePositionApplicant'sActionsorBehaviorATCObservesPK01 09(CCWPumps)alarmingandinformstheShiftForeman.ATC/BOPObservestheCCWPp1 2hasablueOClightilluminated(VB1,leftside),andreportsconditiontoShiftForeman.Note:TheShiftForemanmayimplementARPK0109,orenterOPAP 11,"MalfunctionofComponentCoolingWaterSystem"(IfARPK01 09isentered;otherwisethissectionisN/A)SRO/ATC (1.0)Identifiesinput432(CCWPpsOCTrip)andgoestosection2.4SRO/BOP (2.4.1)DeterminesstandbyCCWpumpdidnotstart;(BOP)takesCCWPp1 3toMANandstartspumpSRO/BOP (2.4.2)ConfirmsblueindicatinglightforovercurrenttripisilluminatedforCCWPp1 2(VB 1)SRO (2.4.3)NotesstandbyCCWPp1 3hasbeenstartedandcontinuestonextstepSRO/BOP (2.4.4)Dispatchesoperatortowalkdown4kVBusGSRO (2.4.4a,b,c)Recognizesbreakerrecloseattemptisnotappropriate(mayrefertoOpsPolicyB 2).Directsmaintenancetoinvestigate(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage9of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 3Page6of 30EventDescription:CCW1 2OvercurrentTrip(cont)TimePositionApplicant'sActionsorBehavior(ARPK01 09,continued)SRO (2.4.5)EntersTechSpec3.7.7.A-OnevitalCCWloopinoperable.Requiredactions:restorevitallooptooperablestatuswithin72hours NotesapplicabilityofLCO3.0.4(entryintoMode1isnotalloweduntil3.7.7.Aexited)(IfOPAP 11,MalfunctionofComponentCoolingWaterSystem,isentered;otherwisethissectionisN/A)SRODeterminesSECTIONA,LOSSOFACCWPUMP/HIGHCCWSYSTEMTEMP,istheappropriatesectionSRO/BOP (1)EnsuresatleasttwoCCWpumpsrunning;(BOP)takesCCWPp1 3toMANandstartsit.(VB1,farleftside)SRO/BOP (2)ChecksCCWHXoutlettemperatureisnormal(VB1)(Itis)SROEntersTechSpec3.7.7.A-OnevitalCCWloopinoperable.Requiredactions:restorevitallooptooperablestatuswithin72hoursProceedtothenexteventoncestandbyCCWpumphasbeenstartedandTechSpecshavebeenaddressedperleadexaminer.**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage10of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 4Page7of 30EventDescription:ACLubeOilpumpTripsonThermalOverloadTimePositionApplicant'sActionsorBehaviorNote:PK12 16,"TurbineLubeOilSystem",willcomeinpriortoPK12 06,"Turbine".TheSROmayelecttofollowguidancefromeitherannunciatorresponseasbothwilldirectthecrewtoOPAP29,"MainTurbineMalfunction"forproblemresolution.AllDiagnosesACLubeOilPumptripfromoneormoreofthefollowing:VB 3Indications: ARPK12 16,"TURBINELUBEOILSYSTEM"andARPK12 06,"TURBINE".VB 4Indications: MainTurbineTurningGear-SupervisoryScreenindicates0RPM,TurningGearamps=0,MNTURBTURNGEAR,MODESELECTindicatorisGREEN(off) ACBearingOilstatuslightindicatespumpisnotrunning;PI 846,"MNTURBBRGOILPRESS"=0psigNote:EmergencyDCBearingOilPumphas10psigautostartsetpoint.Followingappropriatediagnostics,crewmaymanuallystartpumppriortoproceduraldirectiondescribedinthefollowingsteps.(IfARPK12 16isentered;otherwisethissectionisN/A)SRO/ATC (1.0)Identifiesinputs719(Highorlowbearingoilheaderpressure)and726(TurbGenBrgOilPp1 1ACOCorUV)andgoestosection2.1(GeneralActions)BOP (2.1.1)DeterminesEmergencyDCBearingOilPumpdidnotautomaticallystart;maystartpumpmanually(VB4,lowerleftskirt)SRO (2.1.2)NotesPK09 21isNOTinalarmandcontinuestonextstepSRO (2.1.3)TransitionstoOPAP 29,"MainTurbineMalfunction"(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage11of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 4Page8of 30EventDescription:ACLubeOilpumpTripsonThermalOverloadTimePositionApplicant'sActionsorBehaviorNote:IfEmergencyDCBearingOilPumphasbeenstarted,PK12 06willclear.(IfARPK12 06isentered;otherwisethissectionisN/A)SRO/ATC (1.0)Identifiesinput697(MainTurbLoSpeedandTurningGearSelected)andgoestosection2.1(GeneralActions)SRO (2.1.1&2.1.2)DeterminesinputconditionisnotapplicableandcontinuestonextstepSRO (2.1.3)TransitionstoOPAP 29,"MainTurbineMalfunction"(OPAP 29,"MainTurbineMalfunction")SRO (1)ChecksARPK12 11"TURBINETRIP"isOFF(itis)Note:IfcrewhasnotyetstartedEmergencyDCBearingOilPump,ARPK12 06willstillbeON.Crewshouldrecognizethisasasymptom,notacauseandproceedontoappropriateinput.SRO (2)ChecksARPK12 06"TURBINE"isOFF.(statusdependentonprioractions;seenoteabove)SRO (3)ChecksARPK12 16"TURBINELUBEOILSYSTEM"isON;continuestoAppendix3.2(OPAP 29,Appendix3.2-"TURBINELUBEOILSYSTEM(PK1216))Note:IfcrewEmergencyDCBearingOilPumpwasstarted,stepisN/Aasinputwillhavecleared.SROmayelecttoreviewAppendix3.2toverifyallrequiredactionshavebeencompleted.SRO (3)Respondstoinput719(PPCLubeOilPressureAlarm)SRO/BOP (3.1)Determineslubeoilpressureislow(VB 4,PI846)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage12of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 4Page9of 30EventDescription:ACLubeOilpumpTripsonThermalOverloadTimePositionApplicant'sActionsorBehavior(OPAP 29,Appendix3.2,continued)SRO/BOP (3.2.1)StartsEmergencyDCBearingOilpumpmanually(VB 4,lowerleftskirt)SRO/BOP (3.2.2)Checkslubeoilpressurehasreturnedtonormalband(VB 4,PI 846)(Ithas)SRO (4)Respondstoinput724(TurbineGeneratorEmergencyBearingOilPumpRunning)SRO/BOP (4.1)Checksbearingoilpressuregreaterthan20psig(VB 4,PI846).(Itisreadingslightlyover20psig)SRO (5)Respondstoinput726(ACorDCBearingOilPumpOCorUV)SRO (5.1)ContactsmaintenancetodeterminecauseofpumptripProceedtothenexteventwhenonceLubeOilPressurerestoredperLeadExaminer**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage13of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 5Page10of 30EventDescription:SteamHeaderPressureTransmitterPT 507SlowFailureTimePositionApplicant'sActionsorBehaviorAllDiagnosesPT 507failedlowfromoneormoreofthefollowing:CC 2Indications: Tave,Pressurizerlevel,PressurizerpressurerisingCC 3Indications: HC 507demandlowersto0%VB 3Indications: GroupI40%SteamDump(PCV 1,3,6,8)-goclosed DumpDemand(UI 500)lowersto0%.SRO/ATCTakesmanualcontrolofHC 507andreopensGroupIdumpvalvestostabilizeplantSROEntersOPAP 5,"MalfunctionofEagle 21ProtectionorControlChannel"(OPAP 5,MalfunctionofEagle 21ProtectionorControlChannel)SRO/ATC (1)ConfirmsthatSteamGeneratorpressurewasNOTcontrollingproperlyinAutoandhasbeentakentomanual(CC3,HC 507).DirectsTavebereturnedtopriorsteady statevalueSRO/BOP (2)DeterminesthatthefailureisnotEagle 21related(PK06 01andPK06 03areOFF)SRO/ATC (3)DeterminesfailureisnotassociatedwithaTchannel(VB2)SRO (4)Verifiessteamdumpsarenotopenasresultofinstrumentfailureorspuriousactuation.(DumpsSHOULDbeopentomaintaintemperatureforcurrent2%powerconditions.ShiftForemanSHOULDNOTenterRESPONSENOTOBTAINEDcolumn)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage14of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 5Page11of 30EventDescription:SteamHeaderPressureTransmitterPT 507SlowFailureTimePositionApplicant'sActionsorBehavior(OPAP 5,MalfunctionofEagle 21ProtectionorControlChannel,cont.)SRO (5)NotifiesI&CofthePT 507failure,astimepermitsSROReadsCAUTIONpriortostep6SRO (6)NotesrequirementstotakechannelOOSpriortomaintenanceSRO/BOP (7)PlacesOut of-Service(OOS)stickersonaffectedindicators:o MayreferenceAttachment4.1toverifytherearenoReactorTriporEmergencySafeguardBistablechannelsthatmustbetrippedperTechSpecs.o MayreviewAttachment4.2forPT 507controlfunctionsandindications;placesOOSstickeronPR507(VB 3).Proceedtothenexteventwhencrewhasstabilizedtemperature,pertheleadexaminer.**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage15of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 6Page12of 30EventDescription:60gpmRCSLeak-Loop1ColdLegTimePositionApplicant'sActionsorBehaviorALLDiagnosesRCSleakfromoneormoreofthefollowing: Drainand/orSumphighlevelalarms(PK01 17,PK15 01) Pzrlevellowering(PPC,CC2recorder,VB2meters) Pzrlevelhigh;chargingflowdemandand/orlowleveldeviationalarms(PK0521) Containmentparametersslowlyrising(temp,press)(PPC,VB1recorder,PAMSpanels)Note:Leakrampsinover1minute.ThecrewmayraisechargingbyopeningFCV 128andadjustingHCV 142(CC2)inordertomaintainpressurizerlevelpriortoenteringOPAP 1,"ExcessRCSLeakage".SROEntersOPAP 1,"ExcessRCSLeakage"(OPAP 1,"ExcessRCSLeakage")SRO/ATC (1)Determineschargingflowand/orpressurizerlevelNOTnormalo Chargingflowiselevatedandpressurizerlevelisslowlylowering(CC2) (1)Adjustschargingandsealflowtomaintainpressurizerlevelo AdjustssealflowsusingHCV 142(CC2)tomaintain8 13gpmo Mayraisecharginginmanualusingmasterlevelcontroller(HC459D)(CC2)orflowcontroller(FCV128)(CC2)Note:MonitoringPressurizerlevelandchargingflowNORMALisaContinuousAction.AssociatedRNOstepsareperformedwhencrewreportsapplicableconditionsexist(i.e.unabletomaintainpressurizerlevel).SRO/ATC (1)Determinespressurizerlevelisstilllowering(ContinuousActiontoMonitor)SRO/BOP (1RNO)Startssecondchargingpump(VB2,Lowermiddleskirt) (1RNO)Mayisolateletdownaspressurizerlevelcontinuestodropo Closes8149C,andclosesLCV 459/460(VB2,uppermiddleskirt)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage16of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 6Page13of 30EventDescription:60gpmRCSLeak-Loop1ColdLeg(Continued)TimePositionApplicant'sActionsorBehavior(OPAP 1,"ExcessRCSLeakage",continued)ATC (1RNO)Checksforcontinuingdecreaseinpressurizerlevelo Readjustschargingandsealflow(CC1)o Determinespressurizerlevelisstable(PPC,VB2,CC2)(ContinuousActiontoMonitor)SRO/ATC (2)ChecksRCSpressuregreaterthan2210psigandstableorrising(VB2)(2220 2250psig)SRO/ATC (3)DeterminesCVCSMakeupcankeepupwithleako MakeupControlisinAUTO(CC2)o VCTLevelisbeingmaintainedwithinthecontrolband(PPC,VB2RCDR 4justbelowDRPI)o ContinuousActiontoMonitorVCTLevelNote:Step(4)actionsaredirectedatidentifyingandisolatingtheleak.SRO/BOP (4.a)RulesoutSealTableleako RE 7notinalarm(PPC)o NoaudiblealarmfromMIDSpanel(backofVBs)SRO/BOP (4.b)RulesoutS/GTubeLeako MainSteamLineRadMonitorsRM 71/72/73/74notinalarm(VB2/PPC)o SJAERadMonitorRM15/15Rnotinalarm(VB2/PPC)o S/GBlowdownRadMonitorRM 23notinalarm(VB2/PPC)o S/GsampleactivityRM 19notinalarm(VB2/PPC)o PK1106/17/18areallout(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage17of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 6Page14of 30EventDescription:60gpmRCSLeak-Loop1ColdLeg(Continued)TimePositionApplicant'sActionsorBehavior(OPAP 1,"ExcessRCSLeakage",continued)SRO/BOP (4.c)RulesoutRCSinleakagetoCCWo CCWSurgeTankPressureisnotinalarm(PK0114)o CCWSurgeTankLevelisstable(VB1,upperleftjustbelowMonitorLightBoxB)o CCWRadMonitorsRM17A/Bnotinalarm(PPC)(PK11 21)o CCWsurgetankvent,RCV 16,remainsopen(VB1,lowerleft)SRO/BOP (4.d)RulesoutpressurizersteamspaceleakthroughsafetiesandPORVso PressurizersafetyvalvesandPORVsclosed(VB2,upperrightpanel)o PORVtailpipetemperatureislessthan200 o F(TI 463:VB2,upperrightpanel)SRO/BOP (4.e)Notesnoindications(indicatororalarm)ofreactorvesselflangeleakage(VB2indicatorandPK11 02alarm)SRO/BOP (4.f)ObservesthatRCPsealleakageisnormal(VB2,PPC)SRO/BOP (4.g)NotesnoindicationofRCSvalvepackingleakage(PK05 08alarm) ALL (4.h)Observesseveralcontainmentenvironmentalindicators-NOTnormalo CFCUdrippandrainlevelinalarm(PK01 17)o Containmentsumpandreactorcavitysumplevelsrising(PAM1)o ContainmentradiationmonitorsRM 11andRM 12trendingupward(PPC)o Containmentairtemperature/pressuremaybeslightlyelevated(VB1,upperleft)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage18of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 6Page15of 30EventDescription:60gpmRCSLeak-Loop1ColdLeg(Continued)TimePositionApplicant'sActionsorBehavior(OPAP 1,"ExcessRCSLeakage",continued)SRO/BOP (4.h.1RNO)ContactsChemistrytosampleReactorcavitysamplesforincreasedactivitySRO (4.h.1RNO)ConsidersmakingContainmententrytopinpointsourcesofRCSleakNote1:FollowingstepperformedifcrewdiagnosticshasnotruledoutCVCSleakinsideContainment.Note2:Letdownisolationmayhavebeencompletedearlieraspartofstep1RNO,continuousaction.SRO/BOP (4.h.3.a bRNO)Isolatesletdown(VB2,upperskirt)o Closes8149A,B,andCo ClosesLCV459and460 (4.h.3.cRNO)Isolatescharging(VB2,lowerskirt)o Closes8107and8108Note:Performedifletdown/chargingisolatedinpreviousstep,else,N/A.SRO/ATC ThrottlesbackchargingtostabilizePressurizerlevel(CC2) Re estimatesleakratebythrottlingFCV 128forflowandmaintainingRCPseals8 13gpmusingHCV 142(CC2) DeterminesleakwasnotisolatedIfTShasalreadybeenaddressed,proceedtothenexteventoncecrewdeterminesleakisnotisolated,pertheleadexaminer,elsecontinuetonextpage**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage19of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 6Page16of 30EventDescription:60gpmRCSLeak-Loop1ColdLeg(Continued)TimePositionApplicant'sActionsorBehavior(OPAP 1,"ExcessRCSLeakage",continued)Note:Ifisolated,chargingand/orletdownmaybeplacedbackinservice(astimepermits).SRO/BOP (5.aRNO)Opens8107and8108(chargingheaderisolationvalves)(VB2)SRO/ATC (4.h.1RNO)Throttleschargingtocontrolpressurizerlevel(CC2)Note:Ifdirectedtorestoreletdown,boardoperatorswillimplementOPB 1A:XII,Section6.2,otherwisesectionisN/A(continueonnextpage).BOP (6.2.2)Ensuresadequatepressurizerlevelo Checkspressurizerlevelgreaterthan17%(VB2upperright,PPC)o ChecksPK05 21,lowlevelalarminput(544)NOTino ChecksPK04 21,highHXroomtemp(1161)NOTin (6.2.3)PlacesTCV 130inmanualandadjuststo35% 40%demand(VB2,lowermiddle). (6.2.4)Ensuresletdownisolationvalve8152isopen(VB2,uppermiddleskirt) (6.2.5.6)Placesletdownbackpressurecontrolvalve,PCV 135,inmanualandopensto50%(VB2,lowermiddle) (6.2.7)OpensletdownisolationvalvesLCV 459andLCV 460(VB2,middleupperskirt)ATC (6.2.8 10)ChecksFCV 128inmanualandraiseschargingto87gpmwhilemaintainingRCPsealinjectionflowtobetween8GPMand13GPMperRCPusingHCV 142(CC2)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage20of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 6Page17of 30EventDescription:60gpmRCSLeak-Loop1ColdLeg(Continued)TimePositionApplicant'sActionsorBehavior(OPAP 1,"ExcessRCSLeakage",letdownrestoration(OPB 1A:XII)continued)BOPReadsCAUTIONpriortostep6.2.11regardinghighletdowntemperatureandthepotentialforliftingRV 8117. (6.2.12 16)WhilemonitoringPI 135(VB2,uppermiddle)o Opensletdownorificeisolationvalve8149Ctoestablishflow(VB2,uppermiddleskirt)o AdjustsPCV 135tocontrolat350psig(VB2,lowermiddle)o Checksletdownflowandpressurestable(approximately75gpmwithpressurelessthan400psig)(VB2,uppermiddle)o ReturnsPCV 135controllertoAUTOo ChecksRV8117tailpipetemperaturetoverifyreliefvalvedidnotlift(TI 129,VB2middle)ATC (6.2.18)AdjustsFCV 128toreturnpressurizerlevelonreference(CC2)BOP (6.2.20,21)AdjustsTCV130tomaintainnormalletdowntemperature,thenreturnscontrollertoAUTO(VB2,lowermiddle)(remainderofOPAP 1continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage21of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 6Page18of 30EventDescription:60gpmRCSLeak-Loop1ColdLeg(Continued)TimePositionApplicant'sActionsorBehavior(OPAP 1,"ExcessRCSLeakage",continuedfrompage16)Note:LeaksizeestimateandentryintoTSmayhavebeenperformedearlieratSRO'sdiscretion.SRO/ATC (5)Estimatesleaksize(STPR 10Cand/oravailableindications)SRO (5RNO)ComparesleakestimatewithT.S.3.4.13limitso EntersTechSpec3.4.13.A-RCSoperationalleakagenotwithinlimitsforreasonsotherthanpressureboundaryleakageorprimarytosecondaryleakage..Requiredactions:reduceleakagetowithinlimitswithin4hoursProceedtothenexteventonceTSaddressed,pertheleadexaminer.**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage22of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 7,8,9Page19of 30EventDescription:700gpmSBLOCAonLoop1RunningChargingPumpstriponSI,AutostartFails(CT)ATWS,Bothmanualand13D/EFailtoOpenTimePositionApplicant'sActionsorBehaviorALLDiagnoseschangeinRCSleakfromoneormoreofthefollowing: Pzrleveldroppingrapidly(PPC,CC2recorder,VB2meters) Pzrpressuredropping(PPC,CC2recorder,VB2meters) Containmentparametersrising(temp,press)(PPC,VB1recorder,PAMSpanels) Increasedrateofchangeonsumplevels(PAMSpanel)Note:Leakrampsinover1minute.Ifnotpreviouslydone,crewmayattempttoisolateletdownpriortoinitiatingamanualSafetyInjection(SI).SRO/ATC**InitiatesmanualSI(CC2,farright)(CriticalTaskE 0 DtomanuallyinitiateSafetyInjectionbeforetransitioningtoanyE 1,E 2,orE 3seriesprocedure)**(EOPE 0,"ReactorTriporSafetyInjection")Note:AttemptstomanuallytripthereactormaybedonepriortoentryintoEOPE 0oraspartofE 0,step1RNO.ALLPerformsimmediateactions: (1)Ensurereactortrip:o IdentifiesreactorisNOTtrippedbasedonthefollowing: RxTripbreakersdidNOTopen(VB2) NIsareNOTlowering(CC1) RodbottomlightsareNOTlit(VB2);movestostep1RNO(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage23of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 8Page20of30EventDescription:ATWS,Bothmanualand13D/EFailtoOpen(Continued)TimePositionApplicant'sActionsorBehavior(EOPE 0,"ReactorTriporSafetyInjection",continued)ATC Attemptstripusingmanualswitch(CC1orVB2)BOP Notesthatmanualtripalreadyattempted(ormayre trymanualreactortripVB2) Observesthatreactorisstillcritical(sameindicationsaswhentripattempted) Opensbreakersforbusses13Dand13E(VB5,lowerpanel480vacbusbreakers)tode energizetheroddriveMGs;breakerswillnotopen MaydispatchoperatortoopenreactortripbreakerslocallySRO Notesreactorisstillnottripped.Verifiesthatattempttomanuallyopen13D/EwasunsuccessfulandtransitionstoEOPFR S.1(EOPFR S1,"ResponsetoNuclearPowerGeneration/ATWS")SRO/ATC (1)Insertscontrolrods(CC1);SROdirectslocalopeningofRTA/RTB.(MayhavealreadybeendirectedbyBOP) SRO/BOP (2)Verifiesturbinetrip(stopvalvesclosed)(CC3HMIorVB2RPSindicatorlamps)SRO/BOP (3)ChecksAFWstatusa. BothMDAFPsrunning(VB3,leftskirt)b. TDAFPisoffandisnotrequired(VB3,centerskirt)SROReadsCAUTIONpriortostep4.aregardingMainFeedPumpstrippingonSI;SIisalreadyinandMainFeedPumpsaretripped(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage24of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 8Page21of 30EventDescription:ATWS,Bothmanualand13D/EFailtoOpen(Continued)TimePositionApplicant'sActionsorBehavior(EOPFR S1,"ResponsetoNuclearPowerGeneration/ATWS",continued)Note1:ValvesarealreadyalignedforEmergencyBorationasresultofSI,howeverCCP1 3andtherunningECCSchargingpump(startedinEvent6aspartofOPAP 1)trippedjustaftertheSI;theremainingECCSCCPfailedtoautostart.Note2:TheCriticalTasktostartECCSCCPs(Event#9)isNOTassociatedwithestablishingEmergencyBorationflowtotheRCSsincepoweris<5%basedoninitialplantconditions.CriteriatomanuallystartECCSCCPsisdefinedbyDCPPCriticalTaskIdentificationNumberE0-I,andisassociatedwithaSBLOCAwhereRCSpressureisbelowhighheadECCSpumpshutoffheadandbothhighheadECCSCCPsfailedtostartautomatically.DetailsforthisCriticalTaskcanbefoundonpage23.SRO/BOP (4.a)ChecksEmergencyBorationinitiated:1. 8805AOR8805BOPEN(VB2 centerskirt;bothareopen)2. LCV 112BORLCV 112CCLOSED(VB2 centerskirt;bothareclosed)3. VerifiesATLEAST90GPMchargingflow(charginginjectionflow:VB2 justleftofDRPI) ManuallystartsavailableECCSCCP(CCP11orCCP1 2(iffailedautostartnotpreviouslyidentified)(VB2-centerskirt) ChecksforadequateflowSRO/BOP (4.b)Checkspressurizerpressurelessthan2335PSIG(VB2,upperright)SRO/BOP (5)VerifiesContainmentVentIsolation(CVI)bycheckingCVIvalvepositionsonVB 4orfarrightportionofMonitorLightBoxBonVB 1(allvalvesareclosed)SRO/BOP (6.a)ChecksnopersonnelinContainment(waspartofTurnover;maynotvoice) (6.b)AnnouncesATWSonPublicAddressSystem(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage25of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 8Page22of 30EventDescription:ATWS,Bothmanualand13D/EFailtoOpen(Continued)TimePositionApplicant'sActionsorBehavior(EOPFR S1,"ResponsetoNuclearPowerGeneration/ATWS",continued)Note:PortionsofEOPE 0areimplementedinparallelwithEOPFR S.1.TheimplementedstepsofEOPE 0appearbelow.BodyofEOPFR S.1iscontinuedonpagexx.SRO (7)NotesSIactuatedanddirectsRO(usuallytheBOP)toIMPLEMENTthefollowing:o EOPE 0,Steps1through4o EOPE 0,AppendixE,Steps1through10(ImplementationofEOPE 0,Steps1 4)BOP (1)Verifiesreactortrip(tripbkrsopen(VB2upperleft),rodsonbottom(VB2upperleftDRPIpanel),NIsdecreasing(CC1left))BOP (2)Verifiesturbinetrip(stopvalvesclosed)(CC3HMIorVB2RPSindicatorlamps)BOP (3)Checksvital4kvbusses(VB4,vitalbussesF/G/Hhavewhitelightsonmimicbusses)BOP (4.a)ChecksifSIactuated(PK08 21ON) (4.b)ChecksVB1redlightand/ortrainequipmenttoverifybothtrainsactuated)(ImplementationofEOPE0,AppendixE,Steps1 10)BOP (1a)ChecksnopersonnelinContainment(partofturnover;maynotvoice) (1b)Announcestrip/SIonPAsystemNote:Unitiscurrentlyalignedforbackfeedfrom500kV.TrippingtheUnitwillresultintransfertoStartUp(230kV).BOP (2)Checksmaingenerator-tripped(PK14 01ON,outputbkrsopen,andexciterfieldbkropen,CC3rightside);DeterminesgeneratorisNOTtripped (2RNO)DeterminesUnitisstillbackfeeding(PK14 01ifOFF)andgoestostep3(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage26of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 8Page23of 30EventDescription:ATWS,Bothmanualand13D/EFailtoOpen(Continued)TimePositionApplicant'sActionsorBehavior(ImplementationofEOPE0,AppendixE,Steps1 10,continued)BOP (3&4)VerifiesPhaseAandcontainmentventisolationcomplete(VB1,MonitorLightBoxBstatuslights,redlightsON,whitelightsOFF)Note:CriticalTasktostartECCSCCPmayhavebecompletedduringEmergencyBoration(step4ofFR S.1)orbycrewifidentifiedearlierasfailedautostart.BOP (5)VerifiesESF(SI)actuationcomplete(MonitorLightBoxC SI,redlightON,whitelights,someON)o IdentifieswhitelightsassociatedwithASWandECCSchargingpumps**ManuallystartsavailableECCSCCP(CCP11orCCP1 2) (CriticalTaskE-0-I:EstablishflowfromatleastonehighheadECCSpumpbeforetransitionoutofE 0) ** BOP (6)VerifiesFeedwaterisolationcomplete(normalFWIportioniscomplete,withredlightON,andwhitelightsOFF)(S/Gportion:redlightisON,whitelightsOFF)BOP (7&8)Checkscontainmentspray,PhaseB,andmainsteamisolation-NOTrequired(redlightsareOFFforESFfortheseonVB1,andwhitelightsareOFF)BOP (9)ChecksAFWstatus(MDAFPsrunning,TDAFPisoffandnotrequired,VB3centerarea);verifieseitherminof435gpmflow(VB3center)orS/Glevel>15%(VB3center)BOP (10)VerifiesECCSflows(charginginjection(VB2upperpanelleft),SI,RHR(bothonVB1upperpanel);expectedisthatonlyCCPswillbedeliveringflowatcurrentRCSpressure(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage27of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 8Page24of 30EventDescription:ATWS,Bothmanualand13D/EFailtoOpen(Continued)TimePositionApplicant'sActionsorBehavior(ImplementationofEOPE0,AppendixE,Steps1 10,continued)BOP ReportsESFandAFWstatustoSFM(EOPFR S1,"ResponsetoNuclearPowerGeneration/ATWS",continuedfrompage22)SRO/ATC (8)Checksexpectedtripshaveoccurreda. RxTripBreakersOPEN(VB2,upperleft)b. Re verifiesallfourturbinestopvalvesCLOSED(CC3HMIorVB2,RPSindicatorlamps)SRO/ATC (9)ChecksRxSubcriticala. PowerRangeNI'sLESSTHAN5%(CC1)b. NegativestartuprateonIntermediateRangeChannels(CC1)c. GoestoStep19(procedurallydirected)Note:ActionsofStep19(ShutdownMarginverification)aredirectedbySROthroughShiftManager.SRO/BOP (19)VerifiesadequateShutdownMargina. ContactsChemistrytosampleRCSforBoronConcentrationb. RequestsperformanceofSTPR 19,ShutdownMarginCalculationc. Notesneedtoboratetoshutdownconcentration(accomplishedthroughECCSinjectionfromRWST).SRO (20)ReturnstofirststepofE 0,REACTORTRIPORSAFETYINJECTION**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage28of39Rev0Op TestNo.:L121 NRCScenarioNo.:1EventNo.: 7,9Page25of30EventDescription:700gpmSBLOCAonLoop1(continued)RunningChargingPumpstriponSI,AutostartFails(continued)(CT)TimePositionApplicant'sActionsorBehavior(EOPE 0,"ReactorTriporSafetyInjection") SROImplementsEOPE 0,ReactorTriporSafetyInjection ALLCrewre verifiesE 0immediateactions(normalresponse,nowthattripbkrsareopen)o Verifiesreactortrip(tripbkrsopen,rodsonbottom,NIsdecreasing)o Verifiesturbinetrip(stopvalvesclosed(CC3HMIorVB2RPSindicatorlamps)o Checksvital4kvbusses(VB4,vitalbussesF/G/Hhavewhitelightsonmimicbusses)o ChecksSIactuated(PK08 21ON)Note:Steps1 10mayhavebeenimplementedearlieranddonotneedtoberepeated.SRO (5)DirectsAppEimplemented(usuallytoBOP) BOPImplementsAppE: (1a)ChecksnopersonnelinContainment(partofturnover;maynotvoice) (1b)Announcetrip/SIonPAsystem (2)Checksmaingenerator-tripped(PK14 01ON,outputbkrsopen,andexciterfieldbkropen,CC3rightside);DeterminesgeneratorisNOTtripped (2RNO)DeterminesUnitisstillbackfeeding(PK14 01ifOFF)andgoestostep3 (3&4)VerifiesPhaseAandcontainmentventisolationcomplete(VB1,MonitorLightBoxBstatuslights,redlightsON,whitelightsOFF) (5)VerifyESF(SI)actuationcomplete(ESF/SIredlightON,whitelightssomeON);o IdentifieswhitelightsassociatedwithECCSchargingpumps**ManuallystartsavailableECCSCCP(CCP11orCCP1 2)(CriticalTaskE-0-I:EstablishflowfromatleastonehighheadECCSpumpbeforetransitionoutofE 0)**(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage29of39Rev0Op TestNo.:L121 NRCScenarioNo.:1EventNo.:8&9Page26of 30EventDescription:700gpmSBLOCAonLoop1(continued)TimePositionApplicant'sActionsorBehavior(EOPE 0,AppendixE,continued)BOP (6)VerifiesFeedwaterisolationcomplete(normalFWIportioniscomplete,withredlightON,andwhitelightsOFF)(S/Gportion:redlightisON,whitelightsOFF) (7&8)Checkscontainmentspray,PhaseB,andmainsteamisolation-NOTrequired(redlightsareOFFforESFfortheseonVB1,andwhitelightsareOFF) (9)ChecksAFWstatus(MDAFPsrunning,TDAFPdoesnotstart;verifieseitherminof435gpmflow(VB3center)orS/Glevel>15%(VB3center) (10)VerifiesECCSflows(charginginjection(VB2upperpanelleft),SI,RHR(bothonVB1upperpanel) (11)ReportsESFandAFWstatustotheShiftForeman (12&13)Checksexcessletdown-notinservice(8166/8167closed);turnsonauxbldgventcharcoalfilterpreheater(VB4lowerpanel,leftside) (14)Checkssecondarysystems(MFPstripped(VB2,greenlightsON),verifiesonlyoneCBPpsetrunning,condenserisavailable)(VB3) (15)VerifiesproperoperationofAuxBldgandControlRmventsystems(VB4ventstatuslightpanelwhitelights);verifiescontainmentiodinefanssecured(VB4,lowerpanel) (1621)VerifiesavailableDGsrunningnormally(VB4,freq(60),volts(120),speed(900));verifiesvitalbatteriessuppliedbychargers(chargerandbusvoltsonVB5,upperpanelmiddle/lowerarea);verifiesMSRsreset(CC3TriconexHMI);throttlesRCPsealinjectionflowstonormal(FCV 128,to8 13gpmeach,CC2);checksPK11 04NOTIN(SFPalarm);notifiesShiftForemanofcompletion(EOPE 0,"ReactorTriporSafetyInjection",continued)SRO/ATC (6)ChecksRCStemperature-stable(tempsmaybedroppingduetoSBLOCA/ECCSflows;AFWmaybethrottledback(VB2meters,upperpanellowerarea)SRO/ATC (7)ChecksPzrPORVsandPzrsafeties(closed)/PORVblockvalves(allopen),andnosonicflowsonsafeties/PORVs(tailpipetempsmightbeslightlyelevated,butconsistentwithcontainmenttemperaturesfromtheSBLOCA)(VB2-upperpanel,farright);checksPzrspraysclosed(CC2)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage30of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 7Page27of 30EventDescription:700gpmSBLOCAonLoop1(continued)TimePositionApplicant'sActionsorBehavior(EOPE 0,"ReactorTriporSafetyInjection",continued)Note:RCPsmayalreadybetrippedbasedonE 0foldoutpageguidanceforRCPTripCriteriaSRO/ATC (8)ChecksRCPtripcriteria-observesRCSpressure(mayormaynotbe<1300psig;stopsRCPsif<1300psig(VB1andVB2)(ContinuousAction)ATC/BOP (9)ChecksforfaultedS/Gso Faulted-checksallS/GpressuresonVB3(nouncontrolleddropordepressurized)ATC/BOP (10)ChecksrupturedS/Gs Ruptured-checksRE 71/72/73/74andRE 15/19recordersonVB2(andPPC);(allnormal),andPK1106/17/18(allOFF);mayrequestsamplesSRO/ALL (11)ChecksRCSintact(itisnot)(note:onlyonevalidabnormalreadingneededtotransitionfromE 0)o (11a)Checkscontainmentpressurenormal(itiselevated)(VB1meters,PPC)o (11b)Checkscontainmentsumplevelnormal(alreadybeelevated)(VB1meters,PAMS)o (11c)Checkscontainmentradiationnormal(elevated)(PK11 21andPK11 19) (11RNO)Places2 ndASW/CCWHXinservice(opensFCV 603andFCV 431,VB1farleft)SRO ChecksCriticalSafetyFunctionStatusTreesandtransitionstoEOPE 1,LossofReactororSecondaryCoolant(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage31of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 7Page28of 30EventDescription:700gpmSBLOCAonLoop1(continued)TimePositionApplicant'sActionsorBehavior(EOPE 1,"LossofReactororSecondaryCoolant")SRO/ATC (1)ChecksRCPstripped(alreadydone,VB2) (1)ContinuestomaintainRCPsealflows8 13gpm(FCV 128)(CC2)SRO/ALL (2&3)Checksforfaulted/rupturedS/Gso Faulted-checksallS/GpressuresonVB3(notuncontrolleddrop/depressurized;allaredroppingslowly,astheprimaryisnowtheheatsinkforthesecondary)o Ruptured-checksRE 71/72/73/74andRE 15/19recordersonVB2(andPPC;noupwardtrendsorspikes,unlesscontainment"shine"isnoted),andPK11 06/17/18(alarmsnotin);requestschemistrytosampleS/Gsforactivity(asfollows,ifdone): VerifiesphaseAcontainmentisolationreset(VB1) OpensFCV 584(airtocontainment)(VB4,lowerleft) Opensblowdownisolationvalvesinsidecontainment(FCV 760,761,762,763) MayrequireblockinglowsteamlinepressureMSI/SI(duetolowsteamlinepressures);twoblockswitchesonCC2takentoblockpositionBOP (4)MaintainsS/Glevels20[25]65%(VB3,AFWcontrols)SRO/ATC (5)CheckPzrPORVs(closed)/blocks(open/powered)(VB2-upperpanel,farright)SRO/ATC (6)Verifiescontainmentsprayinservice(PK01 18OFF,containmentsprayisnotinservice,andnotrequired)(VB1)SRO/ALL (7)ChecksECCSterminationcriteria(notmet,SCMis<20 F,Pzrlevelisalsobelow12%[40%])(continuedonnextpage**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage32of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 7Page29of 30EventDescription:700gpmSBLOCAonLoop1(continued)TimePositionApplicant'sActionsorBehavior(EOPE 1,"LossofReactororSecondaryCoolant",continued)Note:IfRCSpressureisstillstabilizedatthispoint,RHRpumpswillbeshutdown[untilneededlater](ifpressuregoingdown,theywillbeleftinservice);eitherconditionissatisfactoryfornow.SRO/ATC (8)MaintainsRHRpumpsrunning,andalignscooling(mayopenFCV 364and365now[willopeninlaterstep],VB1farleftlower)SRO/ALL (9)ChecksS/Gpressures(VB3)andRCSpressureconsistentwithLOCA(theyare,althoughRCSpressuremaybealmoststableatsaturation)SRO/BOP (10)CheckifDGsshouldbestopped(bussesarepoweredfromAuxandS/U,sotheycanbesecured)(VB4)SRO/ATC (11.a,b)Verifiesrecirccapability(RHRPpshavepower(VB1),checksauxbldgradlevels(RM 04,06,10,13shownoelevatedreadings)(PPC,backRMSpanels),andchecksRHRsystemsalarms(PK02 16andPK02 17off)forintersystemLOCA(ISLOCAnoindicationsotherthanforSBLOCA)SRO/ATC (11.c)ChecksRHRPpsrunning,andestablishescoolingtotheheatexchangers(byopeningFCV 364/365,asnotedabove),ifnotalreadyopen(andpumpsrunning)(allonVB1)SRO/ALL (11.d)ImplementsAppP(2 nd/manualcheckofESFstatuslights;maybealowerpriority)ALL (11.e,f,g)RequestsRCSsamples;monitorsturbinestatus(oilPps,coastdown,etc),checksSFPstatus(continuedonnextpage**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam01r0a.docPage33of39Rev0Op TestNo.:L121 NRCScenarioNo.: 1EventNo.: 7Page30of 30EventDescription:700gpmSBLOCAonLoop1(continued)TimePositionApplicant'sActionsorBehavior(EOPE 1,"LossofReactororSecondaryCoolant",continued)SRO (12)DeterminesthatpostLOCAcooldownprocedureisappropriate(RCSpressureis>300psig[VB2,PPC,CC2],andnoRHRflow[VB2])SROTransitionstoEOPE 1.2,Post LOCACooldownandDepressurization,andmayperformaproceduretransitionbriefTerminate the scenario once transition is made to EOP E-1.2, per the lead examiner. **CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam02r0a.docPage4of31Rev0Op TestNo.:L121 NRCScenarioNo.: 2EventNo.: 1Page1of 23EventDescription:RM 12failure(containmentgasradmonitor)(TS)TimePositionApplicant'sActionsorBehaviorNote:Procedurestepnumbersareincludedatthefrontofeachaction/commentinparenthesis,whereapplicable.ATCObservesPK11 21(HighProcessRadiation)alarmingandinformstheShiftForeman.ATC/BOP CheckPPCforupscaleradiationmonitorreadingandtrendso NotesRM 12readingtopofscale,withinstantaeousrise.o Nootherradmonitorsareinalarm(PK11 21,HighProcessRadiation)SRO/ATCEntersPK11 21,HighProcessRadiation (1.0)Identifiesinput1066(ProcessMonitorHiRad)andgoestosection2.1,GeneralActions.SRO/ATC (2.1.1)Checksannunciatorprintout(orA&Eviewer/Ronandisplay)toverifyalarminputisRM 12ALL (2.1.2)Investigatescausesofhighradiationalarmso CheckPPCforupscaleradiationmonitorreadingandtrends NotesRM 12readingtopofscale,withinstantaeousrise. Nootherradmonitorsareinalarmo MaycheckforotherindicationsofpossibleRCSleak Pzrleveldropand/orchargingletdownmismatch(ATC,CC2,PPC) Containmentpressureandtemperature(recorder,VB1,left,lower) Containmentsumplevels(PAMSpanelbehindVB 5)Note:Steps2.1.32.1.9requirenoactionifcauseofalarmisaninstrumentfailure.SRO (2.1.3 9)Determinesalarmisresultofinstrumentfailure;noactionrequiredandgoestoassociatedindividualinputstep(2.4) (continued on next page)

• • CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam02r0a.docPage5of31Rev0 Op TestNo.:L121 NRCScenarioNo.: 2EventNo.: 1Page2of 23EventDescription:RM 12failure(containmentgasradmonitor,continued)(TS)TimePositionApplicant'sActionsorBehavior (PK11 21,HighProcessRadiation,continued)SRO/BOP (2.4.1)Checksdigitalraditionmonitordisplayforoverrange(behindVBs)SRO (2.4.2,3)NotesRE 12wasnotpreviouslyinalarm(noreflash),andhasnoassociatedautomaticactions (2.4.4)Notesstepdoesnotapply(forRE 3only)SRO (2.4.5)NotesRM 12hasfailed(nowoutofservice);directsCFCUDrainCollectiontobeputinserviceperOPH 2:ISection6.5,OperatingtheCFCUDrainCollectionsSystem(OPH 2:ISection6.5,OperatingtheCFCUDrainCollectionsSystem)BOP (6.5.1)Placesdraincollectioninservice:o AlignsCFCUDrainValveSelectorSwitchtopositioncorrespondingtoCFCUcurrentlyoperatinginSLOWspeed(VB1,middleleftunderCFCUcontrols) ReportsthatDrainCollectionisinservice(PK11 21,HighProcessRadiation,continued)SRO ReadsNotesregardingexpectedRMresponsetovalidRCSleak (2.4.6)DeterminestherearenootherindicationscorroboratinganactiveRCSleak. (continued on next page)

• • CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam02r0a.docPage6of31Rev0 Op TestNo.:L121 NRCScenarioNo.: 2EventNo.: 1Page3of 23EventDescription:RM 12failure(containmentgasradmonitor,continued)(TS)TimePositionApplicant'sActionsorBehavior (PK11 21,HighProcessRadiation,continued)SRO ReviewsTS3.4.15.C,RCSLeakageDetectionInstrumentationo requiresonecontainmentatmosphereparticulateradmonitorandeitherthecontainmentatmopheregaseousradmonitororCFCUcondensatecollectionmonitortobeoperable NotifiesI&CofRM 12failure(OPH 2:ISection6.5,OperatingtheCFCUDrainCollectionsSystem)BOP ReportsthatDrainCollectionisinserviceProceedtothenexteventonceTechSpecsareaddressed,perLeadExaminer**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam02r0a.docPage7of31Rev0Op TestNo.:L121 NRCScenarioNo.: 2EventNo.: 2Page4of 23EventDescription:CCP1 1OvercurrentTrip(TS)TimePositionApplicant'sActionsorBehaviorALLDiagnosesCCP1 1OCtripusingoneormoreofthefollowingindications: CCP1 1blueOClightislit,andthepumpisnolongerrunning(VB2,lowercenter) PK04 18,CCP1 1alarm(OCtripinput) PKs05 01-05 04,duetoRCPseallowflowalarms Observeslowchargingflowand/orRCPsealflows(CC2,PPC,VB2meters) Observesletdownhasisolated(VB2,upperskirt)BOP/ATC MaycheckCCWflowtoRCPthermalbarriers(VB1,left) MaycheckRCPparameterstoverifycooling(PPCpicture,VB2meters)Note:TheShiftForemanmayenteranyoftheannunciatorresponseproceduresforthelowRCPsealflows(notexpected);ifused,willbedirectedtogotoAP 17foractions.SROImplementsOPAP 17,LossofCharging,SectionA,LossofAllCharging(OPAP 17,"LossofCharging")SRO/BOP (1.a)Verifiessuctionflowpatho VCTlevelandpressure-normal(VB2,PPC)o LCV 112BandLCV 112Copen(CCPsuction)(VB2,lowercenter)SRO (1.b)DeterminesthatpumpventingnotrequiredatthistimeSRO/BOP (1.c)Verifies8105and8106open(CCPrecircs)(VB2,lowercenter)SRO/ATC (1.d)ClosesFCV 128(CC2rightside)SRO/BOP (1.e)StartsstandbyCCP(specificpumpspecifiedbySFM)(VB2,lowercenter)(continuedonnextpage)**C riticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam02r0a.docPage8of31Rev0 Op TestNo.:L121 NRCScenarioNo.: 2EventNo.: 2Page5of 23EventDescription:CCP1 1OvercurrentTrip,continued(TS)TimePositionApplicant'sActionsorBehavior (OPAP 17,"LossofCharging",continued)SRO/ATC (1.f)EstablisheschargingflowtoRCPsealsonly(allCC2,rightside) ThrottlesFCV 128opentoestablish8 13gpmeachtoRCPseal ThrottlesHCV 142toclosedornearlyclosedSRO/ATC (1.g,h)Adjustscharginginmanualtoreturnleveltoprogram(FCV 128)(CC2)SRO/ATC (2)AdjustsHCV 142tomaintainRCPsealflows8 13gpm(CC2)SRO/ATC (3.a)ChecksPzrlevel>17%(itis)(CC2recorder,PPC,VB2meter)SRO/BOP (3.b)Checksletdowninservice(itisNOT)(VB2,upperleftskirt)SRO (3.bRNO)DirectsletdownbeplacedinserviceperAppRALL Mayperformreactivitybriefpriortoplacingletdowninservice(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam02r0a.docPage9of31Rev0Op TestNo.:L121 NRCScenarioNo.: 2EventNo.: 2Page6of 23EventDescription:CCP1 1OvercurrentTrip,continued(TS)TimePositionApplicant'sActionsorBehavior (OPAP 17,"LossofCharging",AppR) BOP/ATC ReadsCAUTIONpriortostep1,App.RregardinghighletdowntemperatureandthepotentialforliftingRV8117. o (1.a)ChecksFCV 355open(itis)(VB1,lowerleftskirt) o (1.b)OpensTCV 130to40%demand(VB2,lowermiddle) o (1.c)Ensures8149A,B,andCareclosed(theyare)(VB2,uppermiddleskirt) o (1.d)OpensLCV 459andLCV 460(VB2,uppermiddleskirt) o (1.e)Checks8152open(itis)(VB2,uppermiddleskirt) o (1.f)OpensPCV 135to60%demand(VB2,lowermiddle) o (1.g)Adjustschargingto87gpm(ATC)(CC2) o (1.h)Opens8149BorC-75gpmorificestopvalve(VB2,uppermiddleskirt) o (1.i)AdjustsPCV 135for350psigonPI135(VB2,uppermiddle).PlacesinAUTOifdesired o (1j)AdjustsTCV 130for90 o F 110 o FonTI 130(VB2,uppermiddle).PlacesinAUTOifdesired o (1k)ChecksRV 8117LetdownReliefValvetailpipetemperaturetoverifyreliefvalveisseated(TI 129VB2,middle) o (1l)NotifiesShiftForemanthatnormalletdownhasbeenrestored (OPAP 17,"LossofCharging",continued) SRO/ATC (3.c)AdjustscharginginmanualtoreturnleveltoprogrambythrottlingFCV128forflow,andmaintainingRCPsealflows8 13gpmusingHCV 142(CC2) SRO/BOP (4)ChecksVCTmakeupsysteminauto(itis)o (4.a)ChecksVCTlevelbetween14%and87%(itis)(VB2meter,CC2PPC)o (4.b)ChecksVCTpress15 60psig(itis)(VB2meter/recorder,CC2PPC)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam02r0a.docPage10of31Rev0Op TestNo.:L121 NRCScenarioNo.: 2EventNo.: 2Page7of 23EventDescription:CCP1 1OvercurrentTrip,continued(TS)TimePositionApplicant'sActionsorBehavior (OPAP 17,"LossofCharging",continued)SRO/ATC (4.c,d)ChecksMakeupsystemsetforcurrentboronandinAUTO(itis;nochangesneeded)(CC2M/UHMI)SRO/BOP (4.e)Verifiesinstrumentairisavailable(itis)(VB4lowerleftarea)SRO/BOP (5)ChecksLCV 112BandLCV 112Copen,providingsuctionfromtheVCT(VB2,middleskirt)SRO (6)ReviewsTechSpecsandentersTechSpec3.5.2.A-OnetrainofECCSinoperable.Requiredactions:restoretraintooperablestatuswithin72hours. ProceedtothenexteventonceTechSpecsareaddressed,perLeadExaminer**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam02r0a.docPage11of31Rev0Op TestNo.:L121 NRCScenarioNo.: 2EventNo.: 3Page8of 23EventDescription:SealInjectionFilter1 1PluggedTimePositionApplicant'sActionsorBehaviorALLDiagnosespluggedsealinjectionfilterusingoneormoreofthefollowingindications: LoweringsealinjectionflowtoallRCPs(VB2,middleright) PKs05 01-05 04,duetoRCPseallowflowalarms PKs04 22forHighRCPSealinjectionFilterDPBOP/ATC MaycheckCCWflowtoRCPthermalbarriers(VB1,left) MaycheckRCPparameterstoverifycooling(PPCpicture,VB2meters)ATC AttemptstoraisesealinjectionflowusingHCV 142.(CC2) IdentifiespotentialimpactonPressurizerlevel(chargingflowloweringasmoreflowisdirectedtowardseals);readjuststomaintainpressurizerlevel.SRO/ANYIdentifiesinput498forPK04 22,"RCPSealInjectionFilterDelta PHi"SROEntersPK04 22,CPSealInjectionFilterDelta PHi (1)DeterminesinputisforRCPSealInjectionFilter1 1andgoestoGeneralActionssection.SROReadsCAUTIONregarding24hourlimitforoperatingRCPswithoutinjectionflowNote:Ifsealflowadjustmentwaspreviouslyattempted,itisnotnecessarytorepeatactionSRO/ATC (2.1.1)AttemptstothrottleHCV 142toestablish8 13gpmsealinjectionflowtoeachRCP.o Recognizeschargingflowloweringwithnochangeinsealflowo Readjustssealflowtomaintainpressurizerlevel(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam02r0a.docPage12of31Rev0 Op TestNo.:L121 NRCScenarioNo.: 2EventNo.: 3Page9of 23EventDescription:SealInjectionFilter1 1Plugged(continued)TimePositionApplicant'sActionsorBehavior(PK04 22,"RCPSealInjectionFilterDeltaPHi"continued)SROReadsNOTEpriortostep2.1.2regardingpotentialimpactonsealandbearingtemperatures.SRO/ANY (2.1.2)DirectsboardoperatortomonitorRCPradialbearingtemperaturesonthePPCSRO/BOP (2.1.3)DirectsNuclearOperatortoswapsealinjectionfilter1 1tofilter1 2perOPB IA:I,Section6.3SRO (2.1.4)ContactsMaintenancetoreplacesealinjectionfilter1 1.SRO/ATCDirectsATCtoreestablishRCPsealflow,oncefilterisswapped.Proceedtothenexteventoncesealsinjectionhasbeenreturnedtonormal,perLeadExaminer.**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam02r0a.docPage13of31Rev0Op TestNo.:L121 NRCScenarioNo.: 2EventNo.: 4Page10of 23EventDescription:4kVBusHDifferentialTripTimePositionApplicant'sActionsorBehaviorALLDiagnoseslossof4KVBusHfromoneormoreofthefollowing: Numerousequipmentalarmsassociatedwiththelossof4KVBusHequipment PK16 16andPK16 174KVBusHalarms(bothrelatedtolossofbus) Bluelighton4KVBusH(diff)(VB4) Whitelightsouton4KVand480vacBusH(VB4)BOPDiagnosesdifferentialtriponBusHduetoalarms(above),bluelightonBusH,andlossofpoweravailablewhitelightonBusH(VB4,middleskirt)SROImplementsOPAP 27,LossofVital4kVand/or480VBus(OPAP 27,"LossofVital4kVand/or480VBus")SRO/BOP (1)Checksvital4KVbussesenergized(onlyBusHOFF;otherwhitebuslightscheckedON)(VB4,skirt)SRO/ATC (2)ChecksDRPIenergized(alignedtonormalpowersupply,BusF,noimpact)(VB2,upperleft)BOP (3)Confirms4KVBusHistrippedondifferential(VB4,bluelightonbus)SRO (4)NotifiesmaintenanceofbusfaultATC/BOP (5)Checksalternatepumpsrunningon4kVbusses;allrequiredpumpsarestillrunning(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam02r0a.docPage14of31Rev0 Op TestNo.:L121 NRCScenarioNo.: 2EventNo.: 4Page11of 23EventDescription:4kVBusHDifferentialTrip(continued)TimePositionApplicant'sActionsorBehavior(OPAP 27,"LossofVital4kVand/or480VBus",continued)SRO/BOP (6)Checks480vacvitalbusses-onlybus1Hdeenergized(VB4-whitepowerlightforeach480vacbus)BOP (Att4.3)ImplementsAttachment4.3forbus1H:o (1.a)PlacesPCV 456CPzrPORVinCLOSEposition(dueto8000Clossofpower)(VB2,upperpanel,farright),andreferstheShiftForemantoTS3.4.11(TS3.4.11.C(1hr))o (1.b)Assignspersonneltoperformnecessarynuclearoperatoractions,(BatteryChargertransferisa2houraction.)(Note:Step2actionswillbecallstothefield) (2.a)InitiateperformanceofD/GmarginassessmentforadditionalbusloadingperOPO 13 (2.b)Transferoffollowingequipmenttobackuppower(asrequired): Battery1 3tocharger1 31perOPJ 9:II InstrumentACPY 15perOPJ 10:VII DieselFuelTransferPp01perOP 13 ControlRoomPowerperO 13 ControlRoomVentPowerPanelA2switchno.EPCA2perOPO 13 (2.c)VerifyControlRoomVentPowerPanelD2switchno.EPCD2isNOTonbackuppowersupplyperOPO 13 (2.d)VerifyAuxBldgSwitchgearSupplyandExhaustFansS 43andE 43arerunning(redundantequipment)o (1.c)VerifiesPressurizerheatergroup13andBattery11and12NOTonbackuppowersupplies(theyarenot)o (1.d)Verifiesredundantequipmentontheother480Vbusesisrunning StartsMakeupWaterTransferPump02(VB3,lowermiddle);allotherredundantequipmentisrunningo (1.e)Verifiesotherminorequipmentstatus(astimepermits)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam02r0a.docPage15of31Rev0 Op TestNo.:L121 NRCScenarioNo.: 2EventNo.: 4Page12of 23EventDescription:4kVBusHDifferentialTrip(continued)TimePositionApplicant'sActionsorBehavior(OPAP 27,"LossofVital4kVand/or480VBus",continued)SRO (7)EvaluatesTechSpecsandECGs(longerspecsastimepermits,perleadexaminer):o TS3.4.11.C-PORVblockvalve(1hr)o TS3.8.1.B-ACSources-operating(STPI 1Cw/I1hr,continuestobeineffect(D/G1 1alreadyOOS))o TS3.8.4.A-DCSources-operating(restorebattcharger)(2hrs)o NOTE:maynothavetimetolookupall(longertimelimit)TechSpecspriortonextevento TS3.6.3.A&C-Containmentisolationvalves(4hrs,72hrs)o TS3.8.9.A-Distributionsystem(vitalbus)-operating(8hrstorestore)o TS3.7.3.A-MFIVs,MFRVs&bypasses,etc(72hrs)o TS3.8.7-Inverters(onlyatroublealarmatthispoint,sononeINOPERABLE)o ECG23.6.A-Vital480vacswgrclass1ventilation(30days)SRO/BOP (8)CheckunloadedDGs(N/Abasedonscenariosetup-D/G1 1OOS)SRO (9)ChecksOPERABILITYofESFequipment(pumps,valveslostduetoBusHloss) SIPp1 2,RHRPp1 2,andCSPp1 2allOOS(VB1,skirt) AFW1 2OOS(butwasclearedaspartofsetup) FCV 440(MFWIsolationValve)ProceedtothenexteventoncetheTechSpecactionsabovehavebeenaddressed,pertheleadexaminer.**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam02r0a.docPage16of31Rev0Op TestNo.:L121 NRCScenarioNo.: 2EventNo.: 5Page13of 23EventDescription:SlowVacuumLeakonMainTurbineTimePositionApplicant'sActionsorBehaviorATC/BOPObservesslowlydegradingcondenservacuum(condenserpressurerising:VB3,PPC,CC2;MWlowering:CC3,PPC)(PK10 11)SROImplementsOPAP 7,DegradedCondenser,SectionA:LossofCondenserVacuum(OPAP 7,"DegradedCondenser,SectionA")SROReadsCAUTIONSregardingAttachmentstobeperformedifbothCWPsarelost,andguidancetotripreactorifactionstostabilizetheplantappearunlikelytosucceedNote:ATCand/orBOPwillbedirectedtomonitortheturbineforhowclosetheyaregettingtotheturbinetripsetpoint.Theycanseebothvacuumandthesetpointontheturbinecontrollerscreens(CC3),andcanalsocomparecondenservacuumwiththeAttachment2"curve"inOPAP 7,showingpowerlevelvsallowableturbineoperationarea.SRO/BOP (1)Checkscondenserpressurelessthanturbinetripsetpoint(Attachment2)(Itis)SRO/BOP (2)DirectsloadreductiontomaintainCondenserpressurebelowturbinetripsetpoint(Attachment2limits)Note:RampmaybestartedbyimplementingOPAP 25,orbyusingrampguidancelamicoidonCC3,andcontinuingwithOPAP 7.FollowupwithOPAP 25proceduralguidanceshouldbecompletedastimepermits.SROImplementsOPAP 25,RapidLoadReduction(OPAP 25,RapidLoadReduction)SROEntersOPAP 25,RapidLoadReduction (1.a)Determinesrunback/programmedrampisnotinprogress(maynotvocalize,sincethisrampisinitiatedbythecrew)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam02r0a.docPage17of31Rev0Op TestNo.:L121 NRCScenarioNo.: 2EventNo.: 5Page14of 23EventDescription:SlowVacuumLeakonMainTurbine(continued)TimePositionApplicant'sActionsorBehavior(OPAP 25,"RapidLoadReduction",continued)SRO/BOP Startsloadreduction(guidanceisalsoonlamicoidpegboardonCC3):o (1.b)PlacesMWandIMPfeedbacksinservice(allonTriconexturbineHMI,CC3)o (1.c)Setsloadtarget(pertheShiftForeman)o (1.d)Setsramprate(pertheShiftForeman)o (1.e)PushesGOSRO/BOP (1.f)Contactschemistryif15%/hrshutdownrateisexceededSRO/ATC (2)EnsurescontrolrodsareinsertinginAUTO(CC1) (3)TurnsPressurizerheaterson(CC1) (4)Checkschargingadequatetopreventflashingintheletdownsystem;maytakemanualcontroltoensureadequateflow(CC2)SRO/BOP (5)EnsuresDFWCSiscontrollingS/GlevelsinAUTO(MFWcontrol/bypassvalves;MFPsallinAUTO)(CC2)(VB3)SRO/ATC (6)Determinesborationrequirements;boratesRCSasneeded)(CC2)SRO/BOP (7)ChecksMFPsuctionpressuregreaterthan260psig(VB3)SRO/ATC (8)ChecksTavetrendingtoTref(PPC,CC1) (9)ChecksPressurizerpressureandleveltrendingtoprogrammedband(PPC,CC2)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam02r0a.docPage18of31Rev0 Op TestNo.:L121 NRCScenarioNo.: 2EventNo.: 5Page15of 23EventDescription:SlowVacuumLeakonMainTurbine(continued)TimePositionApplicant'sActionsorBehavior(OPAP 7,"DegradedCondenser,SectionA",continued)Note:Vacuumleakisstoppedapproximately1minutefollowingPA;MaintenancewillcallControlRoomidentifyingthecauseSRO/BOP (3)MakesPAannouncementregardinglossofcondenservacuum(directsplantpersonneltostopanyactivitythatcouldhaveimpact).SRO/BOP (4)Checkscondenserpressurelessthan10"HgABS(itis)SRO/BOP (5)ChecksCondenserParameterso SJAEAftercondenserVentFlow:Meteriswithoutpower(PY 15notyetonbackup)(VB3,Center)o Condenserpressureisstableorimprovingduetoisolationofleak(VB3,Center)SRO/BOP Placesramponhold(allonTriconexturbineHMI,CC3) RemovesDEHMWandIMPfeedbacksfromservice SetsVPL1 2%abovenewloadvalueProceedtothenexteventoncecrewhasstabilizerplant,pertheleadexaminer.**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam02r0a.docPage19of31Rev0Op TestNo.:L121 NRCScenarioNo.: 2EventNo.: 6Page16of 23EventDescription:LoopSealFailure/RapidLossofTurbineVacuum(RxTrip)TimePositionApplicant'sActionsorBehaviorATC/BOP Observesrapidlydegradingcondenservacuum(risingpressure,VB3,PPC,CC2) Maytripturbineand/orreactormanuallypriortoautomatictripsNote1:Vacuumleakisofsignificantmagnitude.Crewwillnothavetimetore commencerampandwillenterEOPE 0,ReactorTriporSafetyInjectiononceReactorTripoccurs.CrewmembersshouldindependentlyverifyfirstfourstepsofEOPE 0(immediateactions)priortoShiftForemanconfirmingexpectedplantresponse.Note2:TurbineDrivenAFW(TDAFW)pumptripsonoverspeedandAFW1 3failstoautostart.BoardOperatormayattempttostartpumpsafterperformingimmediateactions,butshouldnotinterruptShiftForemanconfirmationsteps.Pumpstatusshouldbereportedaspartofstep4RNO.(EOPE 0,"ReactorTriporSafetyInjection")SRO/ATC (1)Verifiesreactortrip(tripbkrsopen,rodsonbottom,NIsdecreasing)(VB2,CC1)SRO/ATC (2)Verifiesturbinetrip(stopvalvesclosed)(CC3HMIorVB2RPSindicatorlamps)SRO/BOP (3)Checksvital4kvbusstatus(VB4,vitalbussesFandGhavewhitelightsonmimicbusses)o BusesFandGareenergizedfromStartupPower(230kV);BusHisde energizedfromearlierfailure.SRO/ATC (4.a)ChecksifSIactuated(PK08 21OFF,alsochecksSSPSESFstatuslightsonVB1andPK02 02)o SIisNOTrequiredSRO/BOP (4.a.2RNO)AnnouncesRxTriponPA(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam02r0a.docPage20of31Rev0Op TestNo.:L121 NRCScenarioNo.:2EventNo.: 6,7Page17of23EventDescription:LossofTurbineVacuum,RxTrip(continued)TDAFWOverspeedTripandMDAFW1 3autostartfailure(CT)TimePositionApplicant'sActionsorBehavior(EOPE 0,"ReactorTriporSafetyInjection",continued)Note:AFW1 3providesapproximately600gpmtotalflowtoS/G3&4and,astheonlyavailablepump,shouldnotbethrottledback.BOP (4.a.3RNO)ControlstotalfeedflowtoS/Gs**StartsAFW1 3(ifnotpreviouslystarted)(VB3,lowerleftskirt)**Maintainsgreaterthan435gpmuntilNRS/Glevelisgreaterthan15%inatleastoneS/G.(VB3,uppercenter(justbelowPK10window)(CriticalTaskFRH.1-E,Establishgreaterthan435gpmfeedwaterflowratetotheS/Gsbefore3of4WRlevelsindicatelessthan18%)**SROTransitionstoEOPE 0.1,"ReactorTripResponse";performsproceduretransitionbrief(EOPE 0.1,"ReactorTripResponse")Note:AFW1 3tripsonovercurrentwhenS/G1 3orS/G1 4reaches13.5%NRwhichwilldeterminelengthoftimecrewstaysinE 0.1,"ReactorTripResponse"SRO/ANY (1)ChecksRCStemperaturestableortrendingto547 o F(VB2,lowercenterchartrecordersorPPC)o Mayset10%dumpcontrollersto1005psig,(83.8%setpoint)(VB3,lowerleft)SRO/ANY (2)ChecksFeedwaterStatuso RCStemperature<554 o F(VB2,lowercenterchartrecordersorPPC)(Itis)o ChecksFeedwaterIsolationhasoccurred FeedwaterIsolationportionofMonitorLightBoxC(VB1)(RedlightsON/WhitelightsOFF)o CheckstotalAWFflowgreaterthan435GPM(VB3,uppermiddle)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam02r0a.docPage21of31Rev0Op TestNo.:L121 NRCScenarioNo.:2EventNo.: 6Page18of23EventDescription:RxTripResponseTimePositionApplicant'sActionsorBehavior(EOPE 0.1,"ReactorTripResponse")SRO/ATC (3)ChecksRodsfullyinserted(VB2 DRPI)SRO/ATC (4)ChecksPressurizerlevelcontrolso (a)Levelgreaterthan17%(VB2,middleright)o (b)Charginginservicewithadequateflow(VB2)(CC2)o (c)Letdowninservice(VB2,uppermiddleskirt)o (d)Pressurizerleveltrendingto22%(VB2,middleright) (mayadjustchargingtomaintainlevel22%to60%)o (e)Mayenergizepressurizerheaters(CC1,lowerleft)SRO/ATC (5)ChecksPressurizerpressurecontrolo (a)Pressuregreaterthan1850psig(VB2,farright)o (b)Pressurestableortrendingto2235psig(VB2)(CC2)SRO/BOP (6)ChecksS/GNRlevelso (a)ReportsallS/GNRlevelslessthan15%(VB3,uppermiddle)(S/G3&4levelsrising;noflowtoS/G1&2) (aRNO)MaintainsAFWflowgreaterthan435untilS/Glevelsgreaterthan15%o (b)WillcontrolAFWflowtomaintainS/GNRlevelsbetween20%and65%o (c,d)ChecksTDAFWPumprequiredforheatremoval ReportsTDAFWpumpisnotavailableforheatremoval(trippedonoverspeed)(VB3,centerskirt)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam02r0a.docPage22of31Rev0 Op TestNo.:L121 NRCScenarioNo.:2EventNo.: 6Page19of23EventDescription:RxTripResponse(continued)TimePositionApplicant'sActionsorBehavior(EOPE 0.1,"ReactorTripResponse")SRO/BOP (7)EvalutestransferringsteamdumpstoPressureControlModeo (a,b)NotesSteamdumpsareNOTinsteampressuremode(CC2)andMSIVsareopen(VB3,leftmiddle)o (c)ReportsCondenserisNOTavailable(PK08 14isOFF;Condenseratatmosphericpressure) (c.1,RNO)ClosesMSIVs(VB3,leftmiddle) (c.2,RNO)Ifnotperformedearlier,adjusts10%dumpcontrollersto1005psig,(83.8%setpoint)(VB3,lowerleft)ProceedtothenexteventwhenStep7(above)complete,perLeadEvaluator**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam02r0a.docPage23of31Rev0Op TestNo.:L121 NRCScenarioNo.: 2EventNo.: 8Page20of 23EventDescription:MDAFW1 3tripsonovercurrentleadingtoLossOfHeatSinkconditionTimePositionApplicant'sActionsorBehaviorALLNotesAFWPp1 3trippedonovercurrent(VB3,lowerskirt)ALLObservesS/Glevellessthan15%NRduringEOPE 0.1orREDPATHforHeatSinkonCSFSTsSROEntersEOPFR H.1(LOSHS)duetolossofAFW(complete)andlowS/Glevels(EOPFRH.1,"LossofSecondaryHeatSink")SRO (1)Determinestotalfeedflowlessthan435gpmisNOTtheresultofoperatoractionsSRO/ATC (2)DeterminesSecondaryHeatSinkisrequiredo (a)RCSPressureisGREATERthananyintactS/G;(RCSpressure(VB2);S/Gpressure(VB3))o (b)RCSHotLegTempisGREATERthan350o F;(VB2,lower(chartrecorder))SRO/ATC (3)ChecksatleastoneECCSCCPavailable(CCP1 2;VB2,lowerleft)SRO/BOP (4.a)VerifiesBlowdownandSampleisolationvalvesoutsidecontainmentareclosed(VB3,lowerleftskirt)SRO/BOP (4.b.1)VerifiesCSTlevelisGREATERthan10%(VB3,middle)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam02r0a.docPage24of31Rev0Op TestNo.:L121 NRCScenarioNo.: 2EventNo.: 8Page21of 23EventDescription:MDAFW1 3tripsonovercurrentleadingtoLossOfHeatSinkcondition(continued)TimePositionApplicant'sActionsorBehavior(EOPFRH.1,"LossofSecondaryHeatSink",continued)SRO/BOP (4.b.2)VerifiesnoneoftheAFWpumpsarerunning(VB3,middle) (4.b cRNOs)Dispatchesoperatorstolocallychecklineupsandinvestigatepumptrips;MaycheckforstatusonbusHandpotentialforgettingAFW1 2returnedtoserviceSRO/ATC (5)StopsallfourRCPs(VB2,right)Note:StepmayhavealreadybeencompletedduringperformanceofEOPE 0.1.SRO/BOP (6)Adjusts10%dumpcontrollersto1005psig,(83.8%setpoint)(VB3,lowerleft)SRO/BOP ReadsCAUTIONregardingmonitoringofHotwelllevel (7.a)ChecksatleastoneCondensateBoosterPumpSetrunninginrecirc(VB3,lowercenterskirt)SRO/ATC (7.b)TakesmanualcontrolofallMainFeedwaterRegValvesandMainFeedwaterRegValvesBypassesandsetsdemandtozero(DFWCSHMIonCC3)SRO/BOP (7.c)ChecksFeedwaterIsolationValvesopen(VB3,lowerleft)SRO/BOP (7.d)DeterminesMainFeedwaterisNOTavailable(CondenserNOTavailable)(PK08 14inNOTlit)andgoestostep9(EstablishFeedfromCondensateSystem)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam02r0a.docPage25of31Rev0Op TestNo.:L121 NRCScenarioNo.: 2EventNo.: 8Page22of 23EventDescription:MDAFW1 3tripsonovercurrentleadingtoLossOfHeatSinkcondition(continued)TimePositionApplicant'sActionsorBehavior(EOPFRH.1,"LossofSecondaryHeatSink",continued)SRO/ALLReadsCAUTIONSbeforestep9.aregardingblocking/unblockingofautomaticSIactuationReadsCAUTIONregardingparallelperformanceofS/GandRCSdepressurization(steps9.cinparallelwithsteps9.a b)andtheneedtostopS/GdepressurizationifPK06 06comesinbeforeSIsignalareblocked(neededtopreventunwantedSI) (9.a.1)DepressurizesRCStolessthan1915PSIG(P11)usingonePressurizerPORV(VB2,upperright) (9.a.2)AfterP 11actuates(PK08 06),blocksRCSlowpressureSI((2)trainswitches)andlowsteamlinepressureSIsignals((2)trainswitches)(CC2) (9.a.3)MaintainsRCSpressurebelowP 11(1500and1865PSIG)usingPORV(VB2)SRO/BOP (9.b.1)VerifiesMainFeedwaterIsolationValvesOPEN(VB3,lowerleft)SRO/BOP (9.b.2)VerifiesMainFeedwaterIsolationsignalOFF(PK09 11);resetsasneeded(VB3,center)SRO/ATC (9.b.3)ThrottlesopenMainFeedwaterRegValvesORMainFeedwaterBypassValves(CC3DFWCSHMI)SRO/BOP (9.b.4)Bypassesfeedwaterheatersandcondensatedemineralizers(FCV 55andFCV 230)(VB3,skirt,lowerright)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam02r0a.docPage26of31Rev0 Op TestNo.:L121 NRCScenarioNo.: 2EventNo.: 8Page23of 23EventDescription:MDAFW1 3tripsonovercurrentleadingtoLossOfHeatSinkcondition(continued)(CT)TimePositionApplicant'sActionsorBehavior(EOPFRH.1,"LossofSecondaryHeatSink",continued)SRO/BOPReadsCAUTIONbeforestep9.cregardingpotentialforlowTaveFeedwaterIsolation (9.c)DepressurizesatleastONEintactS/GtoLESSTHAN490PSIGatMAXIMUMRATE:o (9.c.1)VerifiesallMSIVandMSIVbypassvalvesclosed(VB3,lowerleft)o (9.c.2)Placesone10%dumpvalveinmanualandopensto100%;RedlightON,greenlightOFF(VB3,middle)SRO/ATCo (9.c.3)Checkscharginginservice;maymaximizeduringdepressurizationtopreventlosingPressurizerlevelduringthecooldownSRO/BOP**(9.c.4)EstablishesfeedflowtoatleastoneS/G(VB3)(CriticalTaskFR H.1-A,EstablishfeedwaterflowintoatleastoneS/GbeforeRCSbleedandfeedisrequired(i.e.beforeWRS/Glevelinany3S/Gislessthan18%ORPressurizerpressureisgreaterthan2335psigduetoalossofsecondaryheatsink)**o (9.c.5)StabilizesdepressurizedS/Gpressureat480PSIG(VB3) SetsdepressurizedS/G10%dumpvalvesetpointtocurrentS/Gpressure,approx.40%(orbelow)oncontroller ReturnscontrollertoAUTOTerminatethescenariooncefeedwaterflowfromtheCondensateSystemisestablished,pertheLeadExaminer.**CriticalTask AppendixD(rev9)ScenarioEventDescriptionFormES D 2 L121NRCSimExam03r0a.docPage4of27Rev0Op TestNo.:L121 NRCScenarioNo.: 3EventNo.: 1Page1of 19EventDescription:NI 44SlowFailureHighTimePositionApplicant'sActionsorBehaviorNote:Procedurestepnumbersareincludedatthefrontofeachaction/commentinparenthesis,whereapplicable.ALLDiagnosespowerrangeNI 44failurefromthefollowing: NI 44meterfailinghigh(CC1,VB2lowerchart) SeveralPKalarms,allassociatedwithpowerrangeNIs,havealarmed Turbinepower(PPC,CC3turbinecontrol)hasnotchanged,T aveisclosetoT ref ,butcontrolsrodsaremovingin(CC1)ATCTakescontrolrodstomanual(duetoinwardrodmotioncausedbyNI 44failinghigh)(CC1)SROEntersOPAP 5,"MalfunctionofEagle 21ProtectionorControlChannel"(OPAP 5,MalfunctionofEagle 21ProtectionorControlChannel)Note:Dependingonhowquicklythisfailureisdiagnosed,andhowquicklycontrolrodsareplacedinmanual(fairlyhighworthareaforrods),theremaybeanimmediateneedtocontroltemperature.Ifneeded,theShiftForemanmaychosetousetheturbineloadtoraiseTave,ormay"moveup"asubstepinOPAP 5tobypasstheC2rodstop(thatpreventsoutwardrodmotion),sothatrodsareagainavailable.Iffailureidentifiedfairlyquickly,theseresponsesmaybedelayeduntilrodcontrolisrestored(below).SRO/ATC (1)DeterminesPrimaryandSecondaryControlSystemsareNOTcontrollingproperlyinAUTO(specificallyRodControlhasafailure) (1.aRNO)VerifiesRodControlhasbeentakentomanual.RestoresTavetoTref(ifneeded;seenoteabove).Thismaybedonebyrampingtheturbinedown,orbymovingrodsout(seebelowforbypassingrodstopC2) (1.bRNO)NotesfailureisduetosingleinstrumentandnotanentireProcessControlRackSROReadsNOTESregardingChannelSetFailureAlarmandfailureofLCPpriortostep2anddeterminestheyarenotapplicableforthisfailure(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam03r0a.docPage5of27Rev0Op TestNo.:L121 NRCScenarioNo.: 3EventNo.: 1Page2of 19EventDescription:NI 44SlowFailureHigh,continuedTimePositionApplicant'sActionsorBehavior(OPAP 5,MalfunctionofEagle 21ProtectionorControlChannel,continued)SRO/BOP (2)DeterminesnotanEagle 21failurebasedonPK06 01andPK06 03OFFSRO (3)NotesnoDeltaTchannelfailure(stepisN/A)(VB2)SRO/BOP (4)Checkssteamdumpsnotactuated(noarmed,open,ortrippedopensignals)(VB3)SRO (5)NotifiesI&CSROReadsCAUTIONbeforestep6regardingEagle21designfeatureassociatedwithrackissuesandnotesasN/Aforthisfailure (6)RemindscrewofnecessitytoensureaffectedchannelsareremovedfromservicepriortomaintenanceSRO/BOP(7)ReviewsAttachments4.1(RxTripandESFBistableChannelpositioningperTS)and4.2(ProcessControlSystemRacks)todetermineaffectedcontrolsandindicators (a)PlacesOOStagsonNI 44(CC1,VB2)andOTT(VB2) (b)Determines NI-44 provides control inputs and can be defeated/bypassed (these actions may be done at several steps in OP AP-5; pg 19 of Att 4.1) (all of these switches are "in back" on the NI panels, all on the right hand cabinet, four switches on the top drawer, and the last switch on the middle drawer) o Places rod stop bypass switch to N44 position (this one cause defeat alarm, PK07-07, and allows rod movement) o Places power mismatch switch to the N44 position o Places quadrant power tilt upper section to the N44 position o Places quadrant power tilt lower section to the N44 position o Places comparator defeat switch to the N44 position(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam03r0a.docPage6of27Rev0 Op TestNo.:L121 NRCScenarioNo.: 3EventNo.: 1Page3of 19EventDescription:NI 44SlowFailureHigh,continuedTimePositionApplicant'sActionsorBehavior(OPAP 5,MalfunctionofEagle 21ProtectionorControlChannel,continued)SRO (8)EvaluatesTechSpecsandECGs:o TS3.3.1.EOnechannelinoperableforOTDelta Ttrip(placeintripwithin72hrs);o TS3.3.1.D-Onepowerrangeneutronfluxhighchannelinoperable(Hifluxtrip)(72hrs)(also12hrsonQPTRsurveillance)o TS3.3.1.S-Oneormorechannelsortrainsinoperable(P10permissivecheck)(verifystatuswithin1hr)o TS3.3.1.T-Oneormorechannelsortrainsinoperable(P7,P8,P9permissivechecks)(verifystatuswithin1hr)o EquipControlGuideline(ECG)37.2AxialFluxDifferenceMonitorAlarminoperable(verifyAFDwithinlimitsforeachoperablechannelwithin1hourandonceperhourthereafter)o EquipControlGuideline(ECG)37.3QuadrantPowerTiletRatioAlarminoperable(verifyQPTRwithinlimitsofTS3.2.4onceevery12hours)SRO/ATC Ifnotcompletedearlier,checksTaverestoredtoTref(CC1orCC3) ReturnsrodstoAUTO(CC1)ProceedtothenexteventonceTechSpecsareaddressed,perLeadExaminer**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam03r0a.docPage7of27Rev0Op TestNo.:L121 NRCScenarioNo.: 3EventNo.: 2Page4of 19EventDescription:CondensateBoosterPump(CBP)1 3OvercurrentTripTimePositionApplicant'sActionsorBehaviorALLDiagnosesCBP1 3tripfromthefollowing: PK10 06,"CNDS&CNDSBSTRPPS",inalarm LowFeedpumpSuctionPressure(VB3,upperrightcenter) Overcurrent(blue)lightonforCBP1 3(VB3,lowercenterskirt)SROMayenterPK10 06,whichdirectscrewtoOPAP 15(sectionD,forCond/boosterPptrip)BOPMaystartstandbyCBP1 2(failedtoautostart)(VB3,lowercenterskirt)SROEntersOPAP 15:SectionD"LossofFeedwaterFlow-Condensate/BoosterPumpSetTrip"(OPAP 15:SectionD,"LossofFeedwaterFlow-Condensate/BoosterPumpSetTrip")SRO/BOP (1)DeterminesallavailableCBPsareNOTrunning(CBP1 2didNOTautostartasexpected) (1RNO)o TakesCBP1 2StandbySelectSwitchtoMAN(VB3,lowercenterskirt)o StartsCBP1 2(checksampsstable)(VB3,lowercenterskirt)SRO/BOP (2)ChecksMainFeedPumpsuctionpressuregreaterthan260psig(VB3,uppercenter)SRO MaydirectTurbineWatchtowalkdownpumpandbreaker;maycontactmaintenancetoinvestigateissue (3)ExitsAP 15ProceedtothenexteventwhenAP 15exited,perLeadExaminer**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam03r0a.docPage8of27Rev0Op TestNo.:L121 NRCScenarioNo.: 3EventNo.: 3Page5of 19EventDescription:S/G1 2TubeLeak(35gpm)TimePositionApplicant'sActionsorBehaviorALLDiagnosesSteamGeneratorTubeLeakfromthefollowing: Increasedchargingflow(PPC,CC2) Airejectoroff gashi radinalarm(PPC,RM 15/15R)(PK11 06) Steamgeneratorblowdownhi radand/orisolation(PPC,RM 19,23)(PK1117) Mainsteamlinehirad(RM 72)(PPC,PK11 18)ATCObservesPK11 06(SJAEHI RAD)alarmingandinformstheShiftForeman.ATC/BOPMaycheckPPCand/orVB2Recorders(lowerleft)forupscalereadings/trendsonradmonitorsIfARPK11 06isentered;otherwisethissectionisN/ASRO/ATC (1)Identifiesinput423(SJAEHiRad)andgoestosection2.1,GeneralActions.SRO/BOP (2.1.1)Checksforupscalereadingsonboth15and15R(PPC,RCDR 3VB2lowerleft)(bothareinalarm;maybeoverranged)o (2.1.1.a)ImplementsOPO 4,"PrimarytoSecondarySteamGeneratorTubeLeakDetection"o (2.1.1.b)NotifiesChemistryofabnormalconditiono (2.1.1.c)TransitionstoOPAP 3(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam03r0a.docPage9of27Rev0 Op TestNo.:L121 NRCScenarioNo.: 3EventNo.: 3Page6of19EventDescription:S/G1 2TubeLeak(35gpm),continuedTimePositionApplicant'sActionsorBehaviorNote:ReviewofOPO 4shutdowncriteriaisalsocoveredaspartofOPAP 3,"SteamGeneratorTubeFailure"(ifnotaddressedduringARPK11 06response)OPO 4,"PrimarytoSecondarySteamGeneratorTubeLeakDetection"ImplementationBOP ReviewsOPO 4foractionlevelsandshutdowncriteria EvaluatesOPO 4actionlevelusingPPCGroupDisplay DeterminescurrentOPO 4actionlevelas3b(leak>=150gpd)andupdatesShiftForemanSROEntersOPAP 3"SteamGeneratorTubeFailure"(OPAP 3"SteamGeneratorTubeFailure")SROReadsNOTEpriortostep1regardingrequirementtocompleteprocedureactionsunlesssupersededbyEOPE 3("SteamGeneratorTubeRupture")Note:MaintainingPressurizerlevelstableisaContinuousAction.AssociatedRNOstepsareperformedwhencrewreportsapplicableconditionsexist(i.eunabletomaintainpressurizerlevel).SRO/ATC (1)Checkspressurizerlevelandchargingflowo Maytakemanualcontrolandattempttoadjustchargingandsealflowtomaintainpressurizerlevel(CC2)o (1.a)DetermineschargingflowisNOTmaintainingpressurizerlevelstable(CC2,PPC)SRO/BOP (1.aRNO)StartsadditionalchargingpumpwhenrequestedbyATC(VB2,centerskirt)SRO/ATC (1.b)Checksforcontinuingdecreaseinpressurizerlevelo Readjustschargingandsealflow(CC2)o Determinespressurizerlevelisstable(CC2,PPC)(ContinuousActiontoMonitor)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam03r0a.docPage10of27Rev0 Op TestNo.:L121 NRCScenarioNo.: 3EventNo.: 3Page7of19EventDescription:S/G1 2TubeLeak(35gpm),continuedTimePositionApplicant'sActionsorBehavior(OPAP 3,"SteamGeneratorTubeFailure" ,continued)SRO/BOP (2)Takesactionstoidentifyaffectedsteamgeneratoro (2.a)DeterminesthatnoS/Glevelsarerisingunexpectedly(VB3meters,PPC)o (2.b)IdentifiesmainsteamlineradmonitorsRM 71and72rising(correspondstoS/G1 2;RM 71readingiselevatedasresultofshineandisreadingconsiderablylowerthanRM 72)(VB2recorders,upperleft;PPC)o (2.c)VerifiesS/Gblowdownisolation/samplevalvesopen(VB3lowerleft)(Dependingonpaceofcrew,blowdownmayhaveisolatedduetohighradonRM 23;RNOstepisperformedtoallowsamplingbychemistry) (2.cRNO)ChecksblowdownisolationduetoRM 12inalarm(PPC,RCDR 3VB2lowerleft);PlacesRE 19,23HiRadS/GBlowdownandSampleValveisodefeatcutoutswitchto"cut in"andopensblowdownsamplevalves(FCV 244,24,248,250)(VB3,lowerleftskirt)o (2.d)ContactsChemistrytoperformS/GsamplingSRO/ATC (3)DeterminesVCTlevelcanbemaintainedbyRCSmakeup(CC2,VB2,PPC)(ContinuousActiontoMonitor)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam03r0a.docPage11of27Rev0 Op TestNo.:L121 NRCScenarioNo.: 3EventNo.: 3Page8of19EventDescription:S/G1 2TubeLeak(35gpm),continuedTimePositionApplicant'sActionsorBehavior(OPAP 3,"SteamGeneratorTubeFailure" ,continued)Note1:OPO 4,actionlevel3bcorrespondstoT.S.3.4.13.d(150gpdprimarytosecondaryleakage),ActionB,whichrequirestheunittobeinMODE3in6hoursandMODE5in36hours.Note2:Oncetheshutdowncommences,however,continuousradiationmonitoringviaRM 15and15Risnolongervalid(powerreductioninvalidatestheradmonitor'scpm gpdconversionfactor).OPO 4guidanceforActionLevel3b(section6.6)isasfollowsforRxpower50%:Theshutdownshouldbeginpromptly,butmaybedelayedforupto3hours.Oncepowerreductionbegins,Rxpowershallbelessthan50%in1hourandshutdowntoMODE3withinthenext2hours.SRO (4)DeterminesplantshutdownisrequiredbasedonOPO 4shutdowncriteriao (4.a)ReviewsOPO 4criteriaandPPCGRPDIPOPO 4dataandconcurswithactionlevel3bassessmento (4.b)ImplementsOPAP 25totakeunitoffline MayperformreactivitybriefpriortoentrySRO/BOP (5)Mayperformadditionalactionstominimizesecondarycontaminationo (5.a)Contactspolisherwashtoreducenumberofvesselsinserviceo (5.b)ChecksAuxSteamalignedtoUnit2o (5.c,e)DirectsTurbineWatchtoalignglandsealingsteamsupplytoAuxSteamandcloseVAC 733o (5.d)ContactsAuxSeniorregardingdischargeofcondensate(currentpermitlikelyinvalidatedbyleak)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam03r0a.docPage12of27Rev0 Op TestNo.:L121 NRCScenarioNo.: 3EventNo.: 3Page9of19EventDescription:S/G1 2TubeLeak(35gpm),continuedTimePositionApplicant'sActionsorBehavior(OPAP 25,"RapidLoadReductionorShutdown")SRO (1.a)Determinesrunback/programmedrampisnotinprogress(maynotvocalize,sincethisrampisinitiatedbythecrew)SRO/BOP Startsloadreduction(guidanceisalsoonlamicoidpegboardonCC3):o (1.b)PlacesMWandIMPfeedbacksinservice(allonTriconexturbineHMI,CC3)o (1.c,d)Setsloadtargetandramprate(expected~10MW/minto150MW,butatdiscretionofShiftForeman)o (1.e)PushesGOo (1.f)ContactsChemistrytoadvise15%/hrshutdownratewillbeexceededSRO/ATC (2)EnsurescontrolrodsareinsertinginAUTO (3)TurnsPressurizerheaterson(CC1) (4)Checkschargingadequatetopreventflashingintheletdownsystem;maytakemanualcontroltoensureadequateflow(CC2)SRO/BOP (5)EnsuresDFWCSiscontrollingS/GlevelsinAUTO(MFWcontrol/bypassvalves;MFPsallinAUTO)(CC2)(VB3)SRO/ATC (6)Determinesborationrequirements;boratesRCSasneeded)(CC2)SRO/BOP (7)ChecksMFPsuctionpressuregreaterthan260psig(VB3)SRO/ATC (8)ChecksTavetrendingtoTref(PPC,CC1) (9)ChecksPressurizerpressureandleveltrendingtoprogrammedband(PPC,CC2)SRO Ifnotalreadycompleted,reviewsT.S.3.4.13.d,ActionB-greaterthan150gpdprimarytosecondaryleakage.Requiredactions:beinMODE3in6hoursandMODE5in36hrs.Proceedtothenexteventoncerampcommenced,perLeadExaminer**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam03r0a.docPage13of27Rev0Op TestNo.:L121 NRCScenarioNo.: 3EventNo.: 4Page10of 19EventDescription:CondenserInLeakageTimePositionApplicant'sActionsorBehaviorATCObservesPK12 05(CONDPPSDISCHHRDCATIONCONDT'YHI)alarmingandinformstheShiftForeman.SRO/ATC (1)Identifiesinput1104(CondPpsDischHeaderCationConductivityHi)andgoestosection2.1,GeneralActions.SRO/BOP (2.1.1)ContactsPolisherWatchtoinvestigatecauseofalarmSRO (2.1.2)EntersOPAP 20"CondenserTubeLeak"(OPAP 20"CondenserTubeLeak")SRO/BOPReadsNOTEregardingdelaytimebetweenControlRoomreadoutandreal timevaluesforSecondaryChemistry (1)Determinescondensatecationconductivityisgreaterthan1.0 S/cm(mayreportunitsasmhos/cm,whichisequivalent)(DDR 10,VB3farright,middle,points17,18,19)o DirectsPolisherWatchtomonitorchemistrydataandalertcontrolroomforadversetrendo ComparesDDRvaluesandtrendwiththosereportedbyPolisherWatch;maycontactChemistrytoperformadditionalsamplingo MaydirectChemistrytosampleCondensateStorageTank(CST)aspossiblesourceofsodiumcontamination(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam03r0a.docPage14of27Rev0 Op TestNo.:L121 NRCScenarioNo.: 3EventNo.: 4Page11of 19EventDescription:CondenserInLeakage,continuedTimePositionApplicant'sActionsorBehavior(OPAP 20"CondenserTubeLeak",continued)SRO/BOPReadsNOTEregardingidentificationofleaklocationandimplementationofcompensatoryactions. (2)Determinesareaofleak(condenserquadrant)(DDR 10,VB3farright,middle)o Identifiespoint7iselevated,indicatingleakincondenseroutlet,SWquadranto RequestsconfirmationoflocationfromPolisherWatcho MaydirectChemistrytosamplelocallySRO/BOPReadsCAUTIONregardingrequirementtotripRxifFCV 230(condensatepolisherdemineralizerbypassvalve)goesopenforanyreason. (3)Performsactionstopreventbypassofcondensatedemineralizerso (3.a)VerifiesFCV 230closed(VB3,lowerrightskirt)o (3.b)DirectsTurbineWatchtoopensupplybreakerforFCV 230SRO/BOP (4)MonitorsFeedwaterCationConductivityforindicationsofcondensatedeminbreakthrough;(DDR 10,point32greaterthan0.25S/cmindicatesbreakthrough,requiringRxTrip)(DDR 10,VB3farright,middle)Note:Rampadjustmentisrequiredifcurrentrateislessthan25MW/minandpowerisstillgreaterthan50%SRO/BOP (5)EvaluatesAttachment4.1,"CondenserTubeLeakCorrectiveActionLimits" Determinesminimumrampis25MW/mindownto50%power Changesratetominof25MW/min(CC3,TurbineControlHMI)SRO/BOP (6 11)Mayperformadditionalactionstominimizesecondarycontamination(notpreviouslyperformedaspartofAP 3)o TakesmanualcontrolandclosesCondenserHotwellRejectValve,LCV 12(VB3,lowerrightskirt)o DirectsfieldrealignmentofCWP1 1AutoRecloseandSCWHxProceedtothenexteventonceminimumramprateestablish,perLeadExaminer**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam03r0a.docPage15of27Rev0Op TestNo.:L121 NRCScenarioNo.: 3EventNo.: 5Page12of 19EventDescription:S/G1 2TubeRupture(400gpm)TimePositionApplicant'sActionsorBehaviorALLDiagnosesSteamGeneratorTubeRupturefromthefollowing: Pressurizerlevelandpressurelowering(PPC,CC2,VB2) S/G1 2levelrising(PPC,VB3) Mainsteamlinehiradrising,loops1&2(RM 71and72)(PPC,VB2)SRO/BOP Mayattempttoisolateletdown(VB2,uppercenterskirt)SRO/ATC InitiatesmanualSI(CC2,farright)ALLCrewentersEOPE 0ontrip/SIactuationandsilentlyperformsimmediateactions: Verifiesreactortrip(tripbkrsopen,rodsonbottom,NIsdecreasing) Verifiesturbinetrip(stopvalvesclosed(CC3HMIorVB2RPSindicatorlamps) Checksvital4kvbusses(VB4,vitalbussesF/G/Hhavewhitelightsonmimicbusses) ChecksifSIactuated(PK08 21ON,alsochecksVB1redtrainlightsand/ortrainequipmenttoverifybothtrainsactuated)(EOPE 0,"ReactorTriporSafetyInjection")Note:Immediateactionstepsarere verifiedbyShiftForemanafterfirstbeingperformedindependentlybyeachmemberofcrewSRO/ATC (1)Verifiesreactortrip(tripbkrsopen,rodsonbottom,NIsdecreasing)(VB2,CC1)SRO/ATC (2)Verifiesturbinetrip(stopvalvesclosed)(CC3HMIorVB2RPSindicatorlamps)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam03r0a.docPage16of27Rev0 Op TestNo.:L121 NRCScenarioNo.: 3EventNo.: 5,6Page13of19EventDescription:S/G1 2TubeRupture(400gpm),continued8801A/BfailtoopenonSI(CT)TimePositionApplicant'sActionsorBehavior(EOPE 0,"ReactorTriporSafetyInjection",continued)SRO/BOP (3)Checksvital4kvbusstatus(VB4,vitalbussesF/G/Hhavewhitelightsonmimicbusses)SRO/ATC (4)ChecksSIactuated(PK08 21ON,alsochecksVB1redtrainlightONand/ortrainequipmenttoverifybothtrainsactuated)o BothtrainsofSIactuatedasindicatedbyPK08 21,SIredlightaboveMonitorLightBoxC(VB1),andbothtrainsofSI/RHRpumpsrunning(VB1skirt)SRO (5)DirectsimplementationofAppE(usuallygiventoBOP)Note:CriticaltasktoestablishhighheadECCSflowpriortoexitingEOPE 0requiresmanuallyopeningof8801A/B.ActionisaddressedaspartofAppE,step5alignmentverification,butmaybeaddressedassoonasfailureisidentified.ManualrealignmentshouldbecommunicatedtoShiftForemanaspartofstep11statusreport.BOPImplementsAppE(ESFAutoActions,SecondaryandAuxiliariesStatus): (1a)ChecksnopersonnelinContainment(partofturnover;maynotvoice) (1b)Announcestrip/SIonPAsystem (2)Checksmaingenerator-tripped(PK14 01ON,outputbkrsopen,andexciterfieldbkropen,CC3rightside) (3&4)VerifiesPhaseAandContainmentVentIsolationcomplete(VB1,MonitorLightBoxB:redlightsON,whitelightsOFF) (5)VerifiesESF(SI)actuationcomplete(SIPortionofMonitorLightBoxC:redlightON,whitelightssomeON);o Identifieswhitelightsassociatedwith8801A/Binjectionvalves(failedclosed)**Manuallyopens8801Aand/or8801Bandverifiesinjectionflow(VB2,upperleft,nexttoDRPI)(CriticalTaskE 0 D,EstablishhighheadECCSflowpriortoexitingEOPE 0)**(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam03r0a.docPage17of27Rev0 Op TestNo.:L121 NRCScenarioNo.: 3EventNo.: 5,7,8Page14of 19EventDescription:S/G1 2TubeRupture(400gpm),continuedMSLBonS/G1 2insidecontainmentMSIVsonleads1&2failtocloseinauto,butcanbeclosedmanuallyTimePositionApplicant'sActionsorBehavior(EOPE 0,AppendixE,continued)BOP (6)VerifiesFeedwaterisolationcomplete(F.W.IsolationandS.G.LevelPortionsofMonitorLightBoxC:redlightsON,whitelightsOFF) (7)Checkscontainmentspray,PhaseB-NOTrequired(ContmtIsol,PhaseBportionofMonitorLightBoxD:redlightsareOFF);mayalsonotecontainmentpressure,whileelevated,iswellbelowactuationsetpoint)Note:BasedonoperatorpacethroughAppE.,MSLImaynothaveactuatedbytimeoperatorreachesproceduralsteptoverifyisolation(isolationactuatesapproximately2minutesafterthetrip).MainSteamIsolationValvesFCV 41andFCV 42(leads1&2)failtoclose,butcanbemanuallyactuatedfromVB3.Numerousrelatedindicatorsandsubsequentalarmsoccuroverthecourseofthescenario,providingthecrewampleopportunitytoidentifyandcorrectthefailure.BOP (8)ChecksMainSteamlineIsolatecomplete(MainSteamIsolationportionofMonitorLightBoxD:redlightON,whitelight,someON)o IdentifieswhitelightsassociatedwithFCV 41andFCV 42(failedopen)o ManuallyclosesFCV 41andFCV 42(VB3,centerleft)Note:SteptocontrolAFWtolimitcooldownmayhavealreadybeencompleted(E 0,step6RNO)byothercrewmembers;actionstakeninAppendixEshouldreflectoverallmitigationstrategy(maintainsecondaryheatsinkwhilelimitingcooldown)BOP (9)ChecksAFWstatus(AFWPp1 3isrunning,TDAFPwillstartonce2outof4S/Glevelsfallsbelow15%(withtimedelay))o DeterminesifTDAFWPp1 1isneeded(ifnotalreadyrunning)(VB3,middlecenterskirt)o Verifieseitherminof435gpmflow(VB3center)orS/Glevel>15%(VB3center)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam03r0a.docPage18of27Rev0 Op TestNo.:L121 NRCScenarioNo.: 3EventNo.: 5Page15of 19EventDescription:S/G1 2TubeRupture(400gpm),continuedTimePositionApplicant'sActionsorBehavior(EOPE 0,AppendixE,continued)BOP (10)VerifiesECCSflows(charginginjection(VB2upperpanelleft),SI,RHR(bothonVB1upperpanel);shutsdownCCP1 3(VB2,middlecenterskirt) (11)ReportsESFandAFWstatustotheShiftForeman(ShiftForemanmaydirectoperatortocontinuewithAppendixE,orredirecttohigherprioritytasks)BOP (12&13)Checksexcessletdown-notinservice(8166/8167closed);turnsonauxbldgventcharcoalfilterpreheater(VB4lowerpanel,leftside) (14)Checkssecondarysystems(MFPstripped(VB2,greenlightsON),stopsallbutoneCBPpset,takesLCV 12controlswitchtoCONTONLY.DeterminesCondenserisNOTavailable(MSIVsareclosed)anddirectsfieldoperatorstobreakvacuumwhenturbineislessthan200rpm (15)VerifiesproperoperationofAuxBldgandControlRmventsystems(VB4ventstatuslightpanelwhitelights);verifiescontainmentiodinefanssecured(VB4,lowerpanel) (1621)VerifiesavailableDGsrunningnormally(VB4,freq(60),volts(120),speed(900));verifiesvitalbatteriessuppliedbychargers(chargerandbusvoltsonVB5,upperpanelmiddle/lowerarea);verifiesMSRsreset(CC3TriconexHMI);throttlesRCPsealinjectionflowstonormal(FCV 128,to8 13gpmeach,CC2);checksPK11 04NOTIN(SFPalarm);notifiesShiftForemanofcompletion(EOPE 0,"ReactorTriporSafetyInjection",continued)SRO/ATC (6)ChecksRCStemperature-stable(tempswillinitiallybedroppingduetofaultedS/G(VB2,upperpanellowerarea);ThrottlesAFWasrequiredtocontroltemperature(VB3,lowerleftskirt)SRO/ATC (7)ChecksPzrPORVsandPzrsafeties(closed)/PORVblockvalves(allopen);noteselevatedtailpipetempsduetocontainmentenvironment;nosonicflowsonsafeties/PORVs(VB2-upperpanel,farright);checksPzrspraysclosed(CC2)SRO/ATC (8)ChecksRCPtripcriteria(RCSpressure[VB2,PPC]<1300psigandSIorECCSCCPsrunning,criteriacouldbemetdependingontimingofevents)(VB1andVB2)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam03r0a.docPage19of27Rev0 Op TestNo.:L121 NRCScenarioNo.: 3EventNo.: 7Page16of 19EventDescription:MSLBonS/G1 2insidecontainment(CT)TimePositionApplicant'sActionsorBehavior(EOPE 0,"ReactorTriporSafetyInjection",continued)SRO/ATC (9)ChecksforfaultedS/Gso Faulted-notes1 2S/Gpressureisdroppinguncontrollablyand/orcompletelydepressurized(PPC,VB3)o TransitionstoEOPE 2,"FaultedSteamGeneratorIsolation"(EOPE 2,"FaultedSteamGeneratorIsolation)SROReadsthreeCAUTIONSpriortostep1SRO/ATC (1)VerifiesALLMSIVsandbypassesareclosed(VB3,upperpanel,leftside)SRO/ATC (2)ChecksforanyintactS/G(1 1,1 3,and1 4S/Gshavestablepressures,consistentwiththeRCScooldownfromthe1 2S/G);continuesinE 2SRO/ATC (3)Identifies1 2S/Gasfaulted(VB3,pressureisstilldroppinginuncontrolledmanner,orcompletelydepressurizedatthispoint)SRO/BOP (4)ImplementsAppendixHH,"IsolateFaultedSteamGenerator"(seepage17)(CT)SRO/ATC (5)ChecksCSTlevel>10%(VB3,upperpanel,centerareameterandrecorders)SRO/ATC (6)ChecksforrupturedS/Gso Ruptured-notesvalidalarmonPK1106,PK11 17,orPK11 18(RM 23isfailedhigh)andupwardtrendonRM 19,15/15R,andRM 72(recordersonVB2(andPPC))o TransitionstoEOPE 3,"StemGeneratorTubeRupture"(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam03r0a.docPage20of27Rev0 Op TestNo.:L121 NRCScenarioNo.: 3EventNo.: 7Page17of 19EventDescription:MSLBonS/G1 2insidecontainment(CT)TimePositionApplicant'sActionsorBehavior(EOPE 2,"AppendixHH,"IsolateFaultedSteamGenerator")BOLDsubstepsbelowmustbeassignedpriortoexitfromEOPE 2(CriticalTaskE 2-A:IsolationofFaultedS/GinitiatedbeforetransitionoutofEOPE 2)**BOPReadsCAUTIONregardingTDAFWasonlysourceoffeedflowpriortostep1 (1)IsolatesfaultedS/G1 2a.VerifiesMFIVFCV 439closed(allofthesecontrolsonVB3,lowerleft)(alreadyclosed)b.VerifiesSGBDvalvesFCV 761,154,and248closed(IC,OC,andsample)(alreadyclosed)c.VerifiesS/G1 210%steamdumpclosed(PCV 20)(isolatedaspartofsetup)**d.ClosesTDAFPAFWLCV 107ClosesMDAFPAFWLCV111for1 2S/GtoisolateAFW**e.ClosesFCV 37toisolatesteamfrom1 2S/GtoTDAFPf.VerifiesAFWflowtoatleastoneintactS/G(VB3,upperpanel,centerareameters)g.InformsShiftForemanS/G1 2isolationiscompleteBOP (2)RemovesWRThotinputtoSCMMforloop2(behindboards,PAMSpanelbehindVB3)(a)GoestoPAM4panel(b)Presses"ConfigurationSummary"(c)Presses"FailedS/G"(d)PressesthePBfortheThottobedisabled(2)(e)Presses"DisableLoop2"(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam03r0a.docPage21of27Rev0 Op TestNo.:L121 NRCScenarioNo.: 3EventNo.: 5Page18of 19EventDescription:S/G1 2TubeRupture(400gpm),continuedTimePositionApplicant'sActionsorBehavior(EOPE 3,"SteamGeneratorTubeRupture)SRO/ATC (1)ChecksifRCPsshouldbestopped(probablyalreadystoppedinE 0)(VB2)SRO/ATC (2)IdentifiesS/G1 2asruptured(RM 72inalarm,previousindicationsofrisinglevelwithoutfeedduringE 0)SRO/BOP (3)ImplementsAppendixFFtoisolaterupturedS/G1 2(EOPE 3,"AppendixFF,"IsolateFaultedSteamGenerator")Note:Majorityofactionswillhavealreadybeencompletedaspartof(EOPE 2,"AppendixHH,"IsolateFaultedSteamGenerator")BOPReadsCAUTIONregardingTDAFWasonlysourceoffeedflowpriortostep1 (1)Readssteptoinsure10%steamdumpcontrollerinAUTOandsetto86.7%;notesvalvesisOOSandisolatedfrominitialconditions. (2)ChecksS/G1 210%steamdumpvalveclosed(PCV 20)(VB3) (3)VerifiesS/G1 2MSIVandbypass()valvesclosed(VB3) (4)VerifiesS/G1 2supplytoTDAFWPp(FCV 37)closed(VB3,skirt) (5)VerifiesS/G1 2SGBDvalves(FCV154andFCV248)closed(VB3,lowerleftskirt) (6)VerifiesS/G1 2isisolatedfromintactS/G(S/G1 2MSIVandMSIVBypassarebothclosedasareallintactS/GMSIVandMSIVBypasses) (7)InformsShiftForemanS/G1 2isolationiscompleteBOP (8)VerifiesremovalofWRThotinputtoSCMMforloop2(behindboards,PAMSpanelbehindVB3)o GoestoPAM4panelo ChecksLoop2ThotDisabled(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam03r0a.docPage22of27Rev0 Op TestNo.:L121 NRCScenarioNo.: 3EventNo.: 5Page19of 19EventDescription:S/G1 2TubeRupture(400gpm),continuedTimePositionApplicant'sActionsorBehavior(EOPE 3,"AppendixFF,"IsolateFaultedSteamGenerator")BOP (9)PreparesforS/Gsampling(a)NotifiesChemistrytosampleS/GusingCAPAP 1(b)VerifiesSIandPhaseAIsolationarereset(VB1,center)(c)Verifiesinstrumentairtocontainment(FCV 584)isopen(VB4,lowerleftskirt)(d)OpensS/GblowdownisolationvalvesinsidecontainmentifcontactedbyChemistryforsampling(EOPE 3,"SteamGeneratorTubeRupture,continued)SRO/ATCReadsCAUTIONregardingmaintainingisolationofFaulted/RupturedS/G(donotfeed) (4.a)NotesrupturedS/Glevelislessthan15%[25%ifstillinadversecontainmentconditions] (4.aRNO)AppliesCAUTIONanddoesNOTapplyRNOactiontofeedrupturedS/GSRO/ATC (5)ObservesrupturedS/GisLESSTHAN225psig;transitionstoEOPECA 3.1,"SGTRWITHLOSSOFREACTORCOOLANTSUBCOOLEDRECOVERYDESIRED"perRNOTerminate the scenario once transition is made to ECA 3.1 , per the Lead Examiner.**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam04r0a.docPage4of35Rev0Op TestNo.:L121 NRCScenarioNo.: 4EventNo.: 1Page1of 27EventDescription:VCTLevelChannelLT 114SlowFailureHighTimePositionApplicant'sActionsorBehaviorNote:Procedurestepnumbersareincludedatthefrontofeachaction/commentinparenthesis,whereapplicable.ALLDiagnosesLT 114failinghighusingoneormoreofthefollowingindications: VCTlevelandpressurelowering(diverseindicatorsofactuallevelchange)(PPC,VB2uppercenter) LI 112(VB2,meterupperright)andLI 114(PPCpointL0112A)failtochannelcheck VCTlevelcontrolvalveLCV 11AdivertingtoLHUT(VB2centerskirt;amberlightilluminated) AutomakeupifactualVCTlevellowers14%(CC2)SROImplementsOPAP 19,"MalfunctionofReactorMakeupControlSystem"(OPAP 19,"MalfunctionofReactorMakeupControlSystem")SRO/ATC (1)ChecksMakeupControllerinsetfordesiredmode(usuallyAUTO)andselectedtoSTART(CC2)SRO/BOP (2)VerifiesMakeupSystempumpsandvalvesareproperlyalignedandinAUTO(VB2,bottomrightskirt)ALL (3)DeterminesLI 112andLI 114doNOTchannelcheck(LT 114failedHigh)o L0112A(PPCpointforLI114)isreading100%,LI 112(VB2)isreadingbetween14% 50%(dependingonactionstakenbycrew)o MaydispatchTurbineWatchtocheckLI 114readingatHSDP(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam04r0a.docPage5of35Rev0 Op TestNo.:L121 NRCScenarioNo.: 4EventNo.: 1Page2of 27EventDescription:VCTLevelChannelLT 114SlowFailureHighTimePositionApplicant'sActionsorBehaviorNote:ARPKsreferencedinRNOdonotalarm-transmitterfailedat100%,butNOToverranged(OOR)SRO/BOP (3RNO)ReferencesassociatedPKsandAppendiceso (a)MayreferenceARPK06 21(ProcessControlSystemTrouble)andARPK06 22(ProcessControlSystem(PCS)ChannelOOS);noactionsdirectedbyPKso (b)ReferstoAppendixAguidancetoidentifyfailedtransmitter (1.a)ChecksPCSHMItodeterminewhichchannelhasfailed(locatedtoleftofPPClargedisplay) (1.b)Reviewscontrolfunctions/indicationsforLT 112andLT 114o (c)DeterminesLT 114hasfailedhighSRO/ATC (4)Verifiessuctionalignmentforrunningchargingpumpo CCP1 1amps,dischargeflow(VB2,UnderDRPI)(CC2)o VCTlevelandpressurearewithinnormalbandsSRO/BOP (5)ContactsI&Ctoinvestigatefailure (6)RealignsLCV 112AdivertvalvetoVCT(VB2,rightskirt)ProceedtothenexteventonceAP 19actionscomplete,perLeadExaminer**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam04r0a.docPage6of35Rev0Op TestNo.:L121 NRCScenarioNo.: 4EventNo.: 2Page3of 27EventDescription:PCV 456(PORV)DriftsOpenFollowingSeismic(CT)TimePositionApplicant'sActionsorBehaviorALLDiagnosesPCV 456openusingoneormoreofthefollowingindications: PK05 20,"PZRRELIEF/SAFETYVLVSOPEN"inalarm PK05 23,"PZRSAFETYORRELIEFLINETEMP"inalarm Pressurizerpressurelowering(CC2,VB2),backupheaterson(CC1),spraysclosed(CC2) BothREDandGREENpositionindicatorlightsilluminatedonPCT456(VB2,farright,lower) PORVdischargetemperatureelevated(TI 463)(VB2,farright,middle)SRO/BOP TakesactiontomanuallyclosePCV 456(unsuccessful) **Closesassociatedblockvalve(8000C)(CriticalTask:IsolatePORVpriortopressurizerpressureloweringto1950psig(lowpressurizerpressureRxtripsetpoint))**Note:PK05 23willredirectcrewtoPK05 20forguidance(PK05 20,PressurizerRelief/SafetyValvesOpen)ifentered,elseN/ASRO/ATC (1)Identifiesinput1211(PzrReliefVlvPCV 456Open)andgoestosection2.1,GeneralActionsSRO (2.1.1)NotesrequirementtoenterEOPE 0,"ReactorTriporSafetyInjection"ifreactortripsatanytime. ReadsNOTEregardingisenthalpicsteamreleasecorrespondingtoaPORVtailpipetemperatureofapproximately230 o F;MaydirectboardoperatortocheckcurrentPORVdischargetemp(TI463)(VB2,farright,middle) (2.1.2)Checksforindicationsofrapiddropinactualpressurizerpressure;maytransitiontoOPAP 13(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam04r0a.docPage7of35Rev0 Op TestNo.:L121 NRCScenarioNo.: 4EventNo.: 2Page4of 27EventDescription:PCV 456(PORV)DriftsOpenFollowingSeismic,continuedTimePositionApplicant'sActionsorBehavior(OPAP 13,"MalfunctionofReactorPressureControlSystem")ifentered;elseN/ASRO (1)NotestherearenoloadchangesinprogressSRO/BOP (2)ChecksallPORVsclosed(PCV 474,455C,456)(VB2,farright,lower)o NotesPCV 456positionlightsindicatevalveisopen (2RNO)Checkspressurizerpressurelessthan2335psig(itis);o MayreattemptclosingPCV 456(valveremainsoffitsseat)o Checksassociatedblockvalve8000CisclosedSRO/BOP (3)Checkspressurizersafetyreliefvalvesclosed(VB2,farright,middle)o Sonicflowreadingzero(theyare)o Tailpipetemperature185 o F(theyare)ALLReadsCAUTIONregardingpotentialneedforstoppingRCPsifsprayvalvehasfailed (4.a)Checksnormalpressurizersprayvalvesclosed(PCV 455A/B)(CC2,uppermiddleright)(greenlightsOn,bothareclosed) (4.b)Checksauxsprayvalvesclosed(8145&8146)(VB2,farrightskirt)(bothareclosed)SRO/ATC (5)Checkspressurizerbackupheaterstatus(farleftCC1)(5.a)Heatersarelineduptonormalpower(normalpowerindicatinglightsareilluminated(CC1)(5.b,c)StatusofheaterswilldependonpressuretransientfromPORVopening Ifpressurizerpressure>2250psig,ensuresallheatersturnedoff Ifpressurizerpressure<2210psig,ensuresallheatersturnedon(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam04r0a.docPage8of35Rev0 Op TestNo.:L121 NRCScenarioNo.: 4EventNo.: 2Page5of 27EventDescription:PCV 456(PORV)DriftsOpenFollowingSeismic,continuedTimePositionApplicant'sActionsorBehavior(OPAP 13,"MalfunctionofReactorPressureControlSystem",continued)SRO (6)DeterminesallpressurecontrolchannelsareOPERABLESRO/ATC (7)Restorespressurizerpressuretonormalband(2210 2260psig)SRO ReviewsTechSpecsandentersTechSpec3.4.11.B-OnePORVinoperableforreasonsotherthanexcessiveseatleakage.o Requiredactions: Closeassociatedblockvalvewithin1hour Removepowerfromassociatedblockvalvewithin1hour RestoreClassIPORVtoOPERABLEstatuswithin72hoursProceedtothenexteventonceT.S.addressed,perLeadExaminer**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam04r0a.docPage9of35Rev0Op TestNo.:L121 NRCScenarioNo.: 4EventNo.: 3Page6of 27EventDescription:GridDisturbance-GCCBackdownOrdertoShed350MWTimePositionApplicant'sActionsorBehaviorCue:(fromShiftManager)IhavejustreceivedavalidbackdownorderfromtheGridControlCenter(GCC)duetoagriddisturbance.PerOpsPolicyB 1,rampunit1down350MWinthenext10minutes.SROImplementsOPAP 25,RapidLoadReduction(OPAP 25,RapidLoadReduction)SROEntersOPAP 25,RapidLoadReduction (1.a)Determinesrunback/programmedrampisnotinprogress(maynotvocalize,sincethisrampisinitiatedbythecrew)SRO/BOP Rampisstarted(guidanceisalsoonlamicoidpegboardonCC3):o (1.b)MWandIMPfeedbacksareplacedinservice(allonTriconexturbineHMI,CC3)o (1.c)840MWe(1190 350,approximate)loadtargetisenteredintoTriconexHMIo (1.d)Setsramprateto35mw/min(approximaterate;actualratedictatedbyShiftForeman)o (1.e)PushesGOSRO/BOPo (1.f)Maymakecallstochemistryif/when15%/hrshutdownrateisexceededATC (2)VerifiesthatcontrolrodsareinsertingproperlyinAUTO(CC1) (3)TurnsPressurizerheaterson(CC1) (4)Checkschargingadequatetopreventflashingintheletdownsystem;maytakemanualcontroltoensureadequateflow(CC2)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam04r0a.docPage10of35Rev0Op TestNo.:L121 NRCScenarioNo.: 4EventNo.: 3Page7of 27EventDescription:GridDisturbance-GCCBackdownOrdertoShed350MWTimePositionApplicant'sActionsorBehavior(OPAP 25,"RapidLoadReduction",continued)SRO/BOP (5)EnsuresDFWCSiscontrollingS/GlevelsinAUTO(MFWcontrol/bypassvalves;MFPsallinAUTO)(CC2)(VB3)SRO/ATC (6)Determinesborationrequirements;boratesRCSasneeded)(CC2)SRO/BOP (7)ChecksMFPsuctionpressuregreaterthan260psig(VB3)SRO/ATC (8)ChecksTavetrendingtoTref(PPC,CC1) (9)ChecksPressurizerpressureandleveltrendingtoprogrammedband(PPC,CC2)Proceedtothenexteventwhengeneration=855MW,perLeadExaminer**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam04r0a.docPage11of35Rev0Op TestNo.:L121 NRCScenarioNo.: 4EventNo.: 4Page8of 27EventDescription:RodControlUrgentFailure/DroppedRodTimePositionApplicant'sActionsorBehaviorALLDiagnosesdroppedcontrolrod/rodcontrolurgentfailureusingoneormoreofthefollowingindications: PK03 17,"RODCONTURGENTFAILURE"inalarm PK03 21,"DRPIFAILURE/RODBOTTOM"inalarm PK03 10,"PWRRNGDEV/QPTR"inalarm DroppedrodindicatedonDRPI(VB2) Autorodmotionstops(CC1) I andpowerrangedeviationinareaofNI 42SROImplementsOPAP 12V,"DroppedControlRod"(OPAP 12C,"DroppedControlRod")SRO/BOP (1)Determinessinglecontrolroddropped(controlbankD,rodB10)(DRPI,VB2)SRO/ATC (2)Placesrodcontrolinmanual(CC1)SRO/BOP (3)Stopsanyloadchangesinprogress(CC3)o Placesramponhold,ifstillinprogresso Iframpcomplete,removesMWandImpulsefeedbacksandresetsVPLSRO/ATCReadsNOTEregardingimpactdilutionwouldhaveoninitialshutdownmargindetermination (4)Stopsborationifstillinprogress(MakeupControlHMI,CC2)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam04r0a.docPage12of35Rev0 Op TestNo.:L121 NRCScenarioNo.: 4EventNo.: 4Page9of 27EventDescription:RodControlUrgentFailure/DroppedRodTimePositionApplicant'sActionsorBehavior(OPAP 12C,"DroppedControlRod",continued)SRO/BOP (5)ChecksTavewithin+/-1.5 o FTref;adjuststurbineloadasneededtobringwithinband(CC3)SRO (6)ChecksAxialFluxDifference(AFD)withinT.S.3.2.3limits(itis)Note:MayrequestSMassignperformanceofSTPR 25tootheravailablepersonnelSRO (7)VerifiesQPTRislessthan1.02(itis)Note:MayrequestSMassignperformanceofSTPR 19tootheravailablepersonnel.SRO (8)PerformsSTPR 19,Attachment9.4withinanhourtoverifySDMwithinlimitsofCOLRSRO (9.a.RNO)IdentifiesRodControlUrgentFailurehasoccurred(a.1RNO)DirectscrewnottomoverodsorresetUrgentFailure(a.2RNO)Contactsmaintenancefortrouble shooting(a.3RNO)ReferstoARPK03 17,"RodControlUrgentFailure"(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam04r0a.docPage13of35Rev0 Op TestNo.:L121 NRCScenarioNo.: 4EventNo.: 4Page10of 27EventDescription:RodControlUrgentFailure/DroppedRod(continued)TimePositionApplicant'sActionsorBehavior(ARPK03 17,"RodControlUrgentFailure")SRO ReviewsAnnunciatorGeneralActionso MaynoteactionsalreadycompletedaspartofOPAP 12Co ReviewsapplicableTechSpecsandECGs EntersTechSpec3.1.4.B-Onerodnotwithinalignmentlimits Requiredactions:o Restorerodtowithinalignmentlimitswithin1hourORo VerifyorrestoreSDMtobewithinCOLRlimitswithin1houralongwithseriesofactionstoverifySDMismaintainedProceedtothenexteventonceT.S.addressed,perLeadExaminer**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam04r0a.docPage14of35Rev0Op TestNo.:L121 NRCScenarioNo.: 4EventNo.: 5Page11of 27EventDescription:FullLoadRejection/ReactorTripTimePositionApplicant'sActionsorBehaviorALLDiagnoseslossofload(full loadrejection)usingoneormoreofthefollowingindications: PK14 05,"GeneratorUnderfrequency"inalarm PK14 24,"Unit's500kVBreakersOpen"inalarm PK20 25500"kVSwitchyard"inalarm GroupIandIIsteamdumpsarmed,open,andsteaming(VB3) Maingeneratoroutputbreakerstrippedopen(CKTBKRs632and532)(CC3,farright)Note:Step1ofOPAP 2,"FullLoadRejection"directscrewtotriptheRxandgotoEOPE 0ifcontrolrodsfailtoinsertinauto.ShiftForemanmayelecttotripreactorbasedonplanconditionsandenterEOPE 0directly.SROImplementsOPAP 2,"FullLoadRejection"(OPAP 2,"FullLoadRejection")ifentered;elseN/ASRO/ATC (1)DeterminescontrolrodsarenotinsertinginAuto (1RNO)ShiftForemandirectsReactorTripandtransitionstoEOPE 0,"ReactorTriporSafetyInjection"(EOPE 0,"ReactorTriporSafetyInjection")ALLCrewentersEOPE 0onRxTripandsilentlyperformsimmediateactions: Verifiesreactortrip(tripbkrsopen,rodsonbottom,NIsdecreasing) Verifiesturbinetrip(stopvalvesclosed(CC3HMIorVB2RPSindicatorlamps) Checksvital4kvbusses(VB4,vitalbussesF/G/Hhavewhitelightsonmimicbusses)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam04r0a.docPage15of35Rev0 Op TestNo.:L121 NRCScenarioNo.: 4EventNo.: 5,6Page12of27EventDescription:FullLoadRejection/ReactorTrip(continued)LossofStartupPowerTimePositionApplicant'sActionsorBehavior(EOPE 0,"ReactorTriporSafetyInjection")SRO/ATC (1)Verifiesreactortrip(tripbkrsopen,rodsonbottom,NIsdecreasing)SRO/ATC (2)Verifiesturbinetrip(stopvalvesclosed)(CC3HMIorVB2RPSindicatorlamps)SRO/BOP (3)Checksvital4kvbusstatus(VB4,whitelightsonmimic;onlyvitalbusGisilluminated)o Determinesonlyonevitalbusisenergized(BusG,whichispoweredbyD/G1 2) BusesFandHaredeenergized(whitelightsoutonVB4mimic) Maynotelossof230kVandfailureofD/G1 3tostart(shutdownrelaytripped) MaynoteD/G1 1OOSsincebeginningofshiftNote:ShiftForemanmayelecttopostponeimplementEOPECA 0.3untilreviewofimmediateactionshasbeencompletedandprioritiesevaluatedbasedonplantconditions.(seepg16foractions)SRO/BOP (3.a.2RNO)DirectsoperatortoIMPLEMENTEOPECA 0.3,"LossofAllVitalACPower"SRO/ATC (4)ChecksforSIactuated(PK08 21:ON)o (4.aRNO)DeterminesSIisneitheractuatednorrequired PK02 02isOFF Safeguardsbistablestatuslightsareout(logicforSIisnotmadeup)(VB1,leftupperarea,justbelowPK01andPK02)o (4.a.2.RNO)AnnouncesReactorTriponPA(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam04r0a.docPage16of35Rev0Op TestNo.:L121 NRCScenarioNo.:4EventNo.: 5Page13of27EventDescription:FullLoadRejection/ReactorTrip(continued)TimePositionApplicant'sActionsorBehavior(EOPE 0,"ReactorTriporSafetyInjection",continued)SRO/ATCo (4.a.3RNO)ControlsAFWflowtoreducecooldownwhilemaintainingasecondaryheatsink Checksforadequatesecondaryheatsink(S/Glevel15%inatleast1S/GortotalAFWflow435gpm)(VB3,upperright) MonitorsRCSLoopTcoldsforindicationsofcooldown(VB2,lowercenterchartrecordersorPPC);throttlesfeedflowifcooldowncontinues(VB3,lowerleft)SRO TransitionstoE 0.1("ReactorTripResponse")(EOPE 0.1,"ReactorTripResponse")Note:Step1ofE 0.1partiallyrepeatslastdirectiongiveninE 0(reducecooldown/maintainheatsink),butalsolooksatpotentialforheatup.Actualactionsrequiredwilldependonlength/depthofpre triptransient.SRO/ATC (1)ChecksRCStemperaturestableortrendingto547 o FbasedonRCSLoopTcolds(RCPstripped)(VB2,lowercenterchartrecordersorPPC)o IfRCStemp<547 o Fanddecreasing: checkssteamdumps(VB3,indicatorlightsmiddle)andS/Gblowdownisolationvalvesoutsidecontainment(VB3,lowerleftskirt)allclosed.AlsochecksMSRsresetononTurbineControlHMI(CC3) throttlesAFWfeedflowasneededtostopcooldownwhilemaintainingheatsink(S/Glevel15%inatleast1S/GortotalAFWflow435gpm)(VB3,upperright)o RCStemp>547 o Fandincreasing Ifrequired,sets10%dumpcontrollersto1005psig,(83.8%setpoint)(VB3,lowerleft) verifiesdumpsmodulateopentocontroltemperatureat547 o F MonitoringofRCStemperaturestableassignedasContinuousAction(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam04r0a.docPage17of35Rev0 Op TestNo.:L121 NRCScenarioNo.:4EventNo.: 5Page14of27EventDescription:FullLoadRejection/ReactorTrip(continued)TimePositionApplicant'sActionsorBehavior(EOPE 0.1,"ReactorTripResponse",continued)Note:IfTaveisstillgreaterthan554 o F,feedwaterisolationwillNOTbein(dependentonpre triptransient)SRO/ATC (2)ChecksFeedwaterStatus(a)RCStemperature<554 o F(VB2,lowercenterchartrecordersorPPC)(b)ChecksFeedwaterIsolationhasoccurredFeedwaterIsolationportionofMonitorLightBoxC(VB1)(RedlightsON/WhitelightsONforFCV 438,440,and441duetobusFandHpowerloss);contactsTurbineWatchtoclosevalves(c)CheckstotalAWFflowgreaterthan435GPM(VB3,uppermiddle)SRO/ATC (3)ChecksRodsfullyinserted(VB2 DRPI)SRO/ATC (4)ChecksPressurizerlevelcontrolso (a)Levelgreaterthan17%(VB2,middleright)o (b)Charginginservicewithadequateflow(VB2)(CC2)o (c)Letdowninservice(VB2,uppermiddleskirt)o (d)Pressurizerleveltrendingto22%(VB2,middleright) (mayadjustchargingtomaintainlevel22%to60%)o (e)Mayenergizepressurizerheaters(CC1,lowerleft)SRO/ATC ReadsCAUTIONregardingAuxSprayandnotesasN/A(AuxSpraynotinservice) (5)ChecksPressurizerpressurecontrolo (a)Pressuregreaterthan1850psig(VB2,farright)o (b)Pressurestableortrendingto2235psig(VB2)(CC2)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam04r0a.docPage18of35Rev0 Op TestNo.:L121 NRCScenarioNo.:4EventNo.: 5Page15of27EventDescription:FullLoadRejection/ReactorTrip(continued)TimePositionApplicant'sActionsorBehavior(EOPE 0.1,"ReactorTripResponse",continued)SRO/ATC (6)ChecksS/GNRlevelsgreaterthan15%o (a)ReportsallS/GNRlevelsgreaterthan15%(VB3,uppermiddle)o (b)WillcontrolAFWflowtomaintainS/GNRlevelsbetween20%and65%o (c,d)ChecksTDAFWPumprequiredforheatremoval ReportsTDAFWpumpisrequiredforheatremoval(onlyrunningAFWpumpuntilbusFpowerrestored)(VB3,centerskirt) MonitoringofS/GlevelsassignedasContinuousActionProceedtothenexteventonce4kVBusFisreenergized,perLeadEvaluator**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam04r0a.docPage19of35Rev0Op TestNo.:L121 NRCScenarioNo.: 4EventNo.: 5,6Page16of27EventDescription:FullLoadRejection/ReactorTrip(continued)LossofStartupPowerTimePositionApplicant'sActionsorBehaviorNote1:ImplementationofEOPECA 0.3maybeassignedtoindividualcontroloperator(typicallytheBOP)andperformedinparallelwithactionsofcrew.Note2:ThefollowingactionsaredirectedaspartEOPE 0,step3RNO(EnsureVital4kVBusStatus),directedonpage12ofthisoutline.(EOPECA0.3,"Restore4kVBuses")BOP ReadsCAUTIONregardingriskofhazardsassoicatedwithsignificantelectricalfaultconditions ReadsCAUTIONregardingsafetyoflocaloperatorsifbusisreenergizedduringstippingofloads (1)ChecksavailabilityofD/Gsassociatedwithdenergizedvitalbuseso Maycontactelectricalmaintenanceand/orworkcontroltoexpeditereturnofD/G1 1o IdentifiesD/G1 3ShutdownRelayactuated(PK18 15inalarm);nootherproblemsindicatedonbusF MaydispatchoperatortowalkdownD/G1 3 MaytakeD/G1 3modeselectswitchtoMAN(ifnottakentomanual,resetofshutdownrelaywillresultinAutostartofD/GandloadingofBusFequipment)(VB4,belowandtoleftofShutdownRelayReset) (1.a)StartsD/G1 3o ResetsD/G1 3ShutdownRelayandAlarmReset(VB4,farrightcenter-yellowlamicoid,justbelowD/G1 3tach)o VerifiesShutdownRelayresets(PK18 15clears) Ifmodeselectswitchwastakentomanual,manuallystartsD/G1 3(VB4belowandtoleftofShutdownRelayReset) (1.b)VerifiesBusFenergizedo InformsShiftForemanD/G1 3isrunningandbusFenergizedNote:MaycontinueoninECA0.3whilewaitingforreportbackfromfieldonD/G1 3status.(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam04r0a.docPage20of35Rev0 Op TestNo.:L121 NRCScenarioNo.: 4EventNo.: 5,6Page17of27EventDescription:FullLoadRejection/ReactorTrip(continued)LossofStartupPowerTimePositionApplicant'sActionsorBehavior(EOPECA0.3,"Restore4kVBuses",continued)BOP ReadsNOTEpriortostep2regardingD/Grunningwithdeenergizedbus (2)Preparesbusesforreturnofoffsitepowero (a)PlacesAUTOTRANSFERtoSTART UPCUTOUTswitchestoCUTOUTpositionforall4kVand12kVbuses(VB4andVB5skirt,switcheslocateddirectlyabovecorrespondingAUTOXFRRESETpushbuttons(Bluelightsilluminated)(7switches)o (b)DepressesAUTOXFRRESETpushbuttonsonall4kVand12kVbusesandverifiesbluelightsgoout(VB4andVB5skirt,nexttoilluminatedbluelights)o (c)PlacescondensateboosterpumpselectorswitchestoMANposition(VB3,lowerrightskirt)ReadsCAUTIONtonotopenbreakersupplyingpowertoabuso (d)OpensallAuxandStartupFeederBreakerstoDeenergized4kVVitalBuses(VB4skirt) Opens52 HH 13(AuxXFMR1 2to4kVBusH) Opens52 HH 14(S/UXFMR1 2to4kVBusH) Opens52 HF 13(AuxXFMR1 2to4kVBusF) Opens52 HF 14(S/UXFMR1 2to4kVBusF)o (e)OpensallAuxandStartupFeederBreakerstoDeenergized4kVNon VitalBuses(VB5skirt) Opens52 HE 2(AuxXFMR1 2to4kVBusE) Opens52 HE 3(S/UXFMR1 2to4kVBusE) Opens52 HD 15(AuxXFMR1 2to4kVBusD) Opens52 HD 14(S/UXFMR1 2to4kVBusD)o (f)OpensallAuxandStartupFeederBreakerstoDeenergized12kVBuses(VB5skirt) Opens52 VD 8(AuxXFMR1 2to4kVBusE) Opens52 VD 4(S/UXFMR1 2to4kVBusE) Opens52 VE 2(AuxXFMR1 2to4kVBusD) Opens52 VE 6(S/UXFMR1 2to4kVBusD)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam04r0a.docPage21of35Rev0 Op TestNo.:L121 NRCScenarioNo.: 4EventNo.: 5,6Page18of27EventDescription:FullLoadRejection/ReactorTrip(continued)LossofStartupPowerTimePositionApplicant'sActionsorBehavior(EOPECA0.3,"Restore4kVBuses",continued)BOP (3)VerifiesSIisReset(notesSInotactuatedorrequired)Note:Ifcontacted,GenerationControlCenter(GCC)willreportboth230kVand500kVlinesareoutofserviceasresultofearthquake;scopeofdamageisstillbeingevaluatedandreturntoservicetimeisyettobedetermined.BOP ReadsNOTEregardingShiftForemandiscretionforselectingpreferredoffsitepowersourceo MayconsultwithShiftForemanregardingpreferredsourceo MaycontactGenerationControlCenter(GCC)todeterminestatusof500kVand/or230kVpower (4)Checks500kVPowerAvailableo Mayusesyncswitchon500kVcircuitbreakers(532or632)tocheckpoweravailability(CC3,farright)o Determines500kVisnotavailable (5)Checks230kVPowerAvailabletoeitherUnito Notes230kVBusindicatorlightisnotlit(farright,topofskirt,VB5)o Determines230kVisnotavailableProceedtothenexteventonce4kVBusFisreenergized,perLeadEvaluator**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam04r0a.docPage22of35Rev0Op TestNo.:L121 NRCScenarioNo.:4EventNo.: 7,8Page19of 27EventDescription:LargeBreakLOCARHRandContainmentSprayPumpAutostartFailures(CT)TimePositionApplicant'sActionsorBehaviorNote:TheDBALBLOCAwilloccurrapidly,causinganimmediateSafetyInjection;noactionsareexpectedotherthanrecognitionoftheearthquakeandSIpriortoreentryintoE 0,startingatstep1.(EOPE 0,"ReactorTriporSafetyInjection")SRO/ATC (1)Verifiesreactortrip(tripbkrsopen,rodsonbottom,NIsdecreasing)SRO/ATC (2)Verifiesturbinetrip(stopvalvesclosed)(CC3HMIorVB2RPSindicatorlamps)SRO/BOP (3)Checksvital4kvbusstatus(VB4,whitelightsonmimic;busesFandGarebothilluminated)o Determinestwovitalbusesenergized(BusGandF,bothpoweredbyrespectiveD/Gs)o MaynoteD/G1 1OOSsincebeginningofshiftNote:CriticaltasktomanuallystartatleastonelowheadECCSpumpmustbecompletedbeforetransitionoutofE 0.ActionisaddressedaspartofAppE,step5alignmentverification,butmaybeaddressedassoonasfailureisidentified.SRO/ATC (4)ChecksSIactuated(PK08 21ON,alsochecksVB1redtrainlightONand/ortrainequipmenttoverifybothtrainsactuated)o BothtrainsofSIactuatedasindicatedbyPK,SIredlighto MayreportSIpumpsNOTrunning(SIPp1 1trippedonOC;SIPp1 2hasnopower-BusHdeenergized)o MayreportRHRpumpstatus(RHRPp1 1didnotautostart,mayhavebeenstartedmanually**

RHRPp1 2hasnopower-BusHdeenergized)**CriticalTaskE0-H

ManuallystartatleastonelowheadECCSpumpbeforetransitionoutofE 0(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam04r0a.docPage23of35Rev0 Op TestNo.:L121 NRCScenarioNo.:4EventNo.: 7,8Page20of 27EventDescription:LargeBreakLOCARHRandContainmentSprayPumpAutostartFailures(CT)TimePositionApplicant'sActionsorBehavior(EOPE 0,"ReactorTriporSafetyInjection",continued)SRO (5)DirectsimplementationofAppE(usuallygiventoBOP)Note:CriticaltasktomanuallystartatleastonelowheadECCSpumpmustbecompletedbeforetransitionoutofE 0;mayhavebeenaddressedduringperformanceofimmediateactionsBOPImplementsAppE(ESFAutoActions,SecondaryandAuxiliariesStatus): (1a)ChecksnopersonnelinContainment(partofturnover;maynotvoice) (1b)Announcestrip/SIonPAsystem (2)Checksmaingenerator-tripped(PK14 01ON,outputbkrsopen,andexciterfieldbkropen,CC3rightside) (3&4)VerifiesPhaseAandContainmentVentIsolationcomplete(VB1,MonitorLightBoxB:redlightsON,whitelightsOFF)o NotesonlywhitelightisassociatedwithsealwaterPhaseAisolationvalve,insidecontainment;outsidecontainmentvalveisclosed (5)VerifiesESF(SI)actuationcomplete(SIPortionofMonitorLightBoxC:redlightON,whitelightssomeON);(5.aRNO)DeterminesCCP1 1,1 2,andSI1 1aretrippedonovercurrento NotesCCW1 3,RHR1 2,SI1 2,andCFCU1 4notrunningduetolossofBusHo IdentifiesRHR1 1autostartfailure;manuallystartspump**(ifnotpreviouslyidentified)**CriticalTaskE0-H:ManuallystartatleastonelowheadECCSpumpbeforetransitionoutofE 0(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam04r0a.docPage24of35Rev0 Op TestNo.:L121 NRCScenarioNo.:4EventNo.: 7,8Page21of 27EventDescription:LargeBreakLOCARHRandContainmentSprayPumpAutostartFailures(CT)TimePositionApplicant'sActionsorBehavior(EOPE 0,AppendixE,continued)Note:IfFeedwaterIsolationactivatedduringE 0.1(RCStemp<554 o F),manualisolationmayalreadybecompleteBOP (6)VerifiesFeedwaterisolationcomplete(F.W.IsolationandS.G.LevelPortionsofMonitorLightBoxC:redlightsON,whitelightsOFF)(6.aRNO)NoteswhitelightONforFWIsolationValveFCV 440(alsobusH);contactsTurbineWatchtoclosevalve(maywaittocontactuntilafterShiftForemanstatusupdateatstep11)Note:CriticaltasktostartContainmentSprayPump(CSP)1 1mayhavebeenaddressedduringperformanceofimmediateactionsBOP (7)DeterminesContainmentSprayandPhaseBIsolationisrequired(ContmtIsol,PhaseBportionofMonitorLightBoxD:redlightsareON)(7.a.1RNO)MayattempttomanuallyinitiateContainmentIsolationPhaseB/Spray(VB1,directlybelowcontainmentenvironmentindications)(7.a.2RNO)NoteswhitelightsonforContainmentSprayPump1 2,ContainmentSprayvalves8994Band9001B,andCCWvalves:FCV 746,FCV 357,FCV 749areallduetolossofbusH.IdentifiesfailedautostartofContainmentSprayPump1 1;manuallystartspump**(7.a.3RNO)MaintainsRCPsealinjectionbetween8 13gpm(mayneedtostartCCP1 3)(7.a.4RNO)NotesRCPsarealreadytrippedduetolossof12kVpower**CriticaltaskE 0-E:manuallyactuateatleasttheminimumrequiredcomplementofcontainmentcoolingequipmentbeforeanextreme(redpath)challengedevelopstothecontainmentcriticalsafetyfunction.Minimumrequiredcomplementofcontainmentcoolingequipmentisdefinedas2ContainmentFanCoolingUnits(CFCUs)and1ContainmentSprayPump.(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam04r0a.docPage25of35Rev0 Op TestNo.:L121 NRCScenarioNo.:4EventNo.: 7Page22of 27EventDescription:LargeBreakLOCATimePositionApplicant'sActionsorBehavior(EOPE 0,AppendixE,continued)BOP (8)ChecksMainSteamlineIsolationcomplete(MainSteamIsolationportionofMonitorLightBoxD:redlightON,whitelightareOFF)Note:SteptocontrolAFWtolimitcooldownmayhavealreadybeencompleted(E 0,step6RNO)byothercrewmembers;actionstakeninAppendixEshouldreflectoverallmitigationstrategy (9)ChecksAFWstatuso AFWPp1 3andTDAFPbothrunningo Re verifiesminof435gpmflow(VB3center)orS/Glevel>25%(adversecontainment)(VB3center)BOP (10)ChecksECCSflows(charginginjection(VB2upperpanelleft),SI,RHR(bothonVB1upperpanel);notesRHR1 1istheonlyavailableandrunningECCSpump (11)ReportsESFandAFWstatustotheShiftForeman(ShiftForemanmaydirectoperatortocontinueoninAppendixE,orredirecttohigherprioritytasks)BOP (12&13)Checksexcessletdown-notinservice(8166/8167closed);turnsonauxbldgventcharcoalfilterpreheater(VB4lowerpanel,leftside) (14)Checkssecondarysystems(MFPstripped(VB2,greenlightsON),stopsallbutoneCBPpset,takesLCV 12controlswitchtoCONTONLY.DeterminesCondenserisNOTavailable(MSIVsareclosed)anddirectsfieldoperatorstobreakvacuumwhenturbineislessthan200rpm (15)VerifiesproperoperationofAuxBldgandControlRmventsystems(VB4ventstatuslightpanelwhitelights);verifiescontainmentiodinefanssecured(VB4,lowerpanel)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam04r0a.docPage26of35Rev0 Op TestNo.:L121 NRCScenarioNo.:4EventNo.: 7Page23of 27EventDescription:LargeBreakLOCATimePositionApplicant'sActionsorBehavior(EOPE 0,AppendixE,continued) (16)VerifiesavailableDGsrunningnormally(VB4,freq(60),volts(120),speed(900)) (17)Verifiesvitalbatteriessuppliedbychargers(chargerandbusvoltsonVB5,upperpanelmiddle/lowerarea); (18)VerifiesMSRsreset(CC3TriconexHMI) (19)ThrottlesRCPsealinjectionflowstonormalifneeded(FCV128,to8 13gpmeach,CC2) (20)ChecksPK11 04NOTIN(SFPalarm) (21)NotifiesShiftForemanofcompletion(EOPE 0,"ReactorTriporSafetyInjection",continued)SRO/ATC (6)ChecksRCStemperaturestableorloweringto547 o Fo NotestemperaturehasdroppedsignificantlyduetoLBLOCA,(VB2,upperpanellowerarea)o MaythrottleAFWback,butwithnoimpact-mayverbalizesecondarynolongerfunctioningasheatsink(VB3,lowerleftskirt)SRO/ATC (7)ChecksPzrPORVsandPzrSafetiesandSprayValveso Safetiesclosed(closed);nosonicflow,tailpipetemperatureiselevated,butconsistentwithcontainmentenvironment(VB2-upperpanel,farright)o PORVsclosedandassociatedblockvalvesopen,withexceptionofPCV 456failurefromearlierwhichhasalreadybeenaddressed(VB2-upperpanel,farright)o PzrSpraysclosed(greenlightson)(CC2)SRO/ATC (8)ChecksRCPtripcriteria;notesRCPsalreadytrippedfromlossof12kV(VB2)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam04r0a.docPage27of35Rev0 Op TestNo.:L121 NRCScenarioNo.:4EventNo.: 7Page24of 27EventDescription:LargeBreakLOCARHRandContainmentSprayPumpAutostartFailuresTimePositionApplicant'sActionsorBehavior(EOPE 0,"ReactorTriporSafetyInjection",continued)SRO/ATC (9)DeterminesS/GareNOTfaultedo MaynoteS/Gsaredepressurizing,butasconsequenceofLBLOCAcooldowno NonearecompletelydepressurizedSRO/ATC (10)DeterminesS/GareNOTruptured ChecksRE71/72/73/74andRE 15/19recordersonVB2(andPPC);(allnormal) PK1106/17/18(allOFF) MayrequestsamplesSRO/ALL (11)ChecksRCSintact(itisnot)(note:onlyonevalidabnormalreadingneededtotransitionfromE 0) (11a)DeterminescontainmentpressureisNOTnormal(itiselevated)(VB1meters,PPC) (11b)DeterminescontainmentsumplevelsNOTnormal(theyareelevated)(VB1meters,PAMS) (11c)DeterminescontainmentradiationisNOTnormal(RM 11,02,07areallinalarm) (11RNO)Places2 ndASW/CCWHXinservice(opensFCV 603andFCV 431,VB1farleft),andtransitiontoEOPE 1,"LossofReactororSecondaryCoolant"(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam04r0a.docPage28of35Rev0 Op TestNo.:L121 NRCScenarioNo.:4EventNo.: 7Page25of 27EventDescription:LargeBreakLOCATimePositionApplicant'sActionsorBehavior(EOPE 0,"ReactorTriporSafetyInjection",continued)SROPerformsproceduretransitionbriefforE 1,andimplementsCSFST(ifrequired)Note:ACSFSTMAGENTApathmayoccurpriortoEOPE 1entryorbeforetheendofthescenario(FR P.1onPTS);Ifitsoccurs,itwillbeashortentry(performasinglestepandexit)SROImplementsFR P.1,ImminentPTS(ifMAGENTApathoccurs)(ONLYIFFR P.1,ImminentPTS,isentered;otherwise,thissectionisN/A)SRO/ATC (1)ChecksRCSpressure(low),andRHRflow(normal);exitstoprocedureineffectSROImplementsEOPE 1,LossofReactororSecondaryCoolant(EOPE 1,"LossofReactororSecondaryCoolant)SRO/ATC (1)ChecksRCPstripped(alreadydone,VB2)ATC/BOP (2&3)Checksforfaulted/rupturedS/Gso Faulted-checksallS/GpressuresonVB3(notuncontrolleddrop/depressurized;allaredroppingslowly,astheprimaryisnowtheheatsinkforthesecondary)o Ruptured-checksRE 71/72/73/74andRE 15/19recordersonVB2(andPPC;noupwardtrendsorspikes,unlesscontainment"shine"isnoted),andPK11 06/17/18(alarmsnotin);requestschemistrytosampleS/Gsforactivity(asfollows,ifdone): VerifiesphaseAcontainmentisolationreset(VB1) OpensFCV 584(airtocontainment)(VB4,lowerleft) Opensblowdownisolationvalvesinsidecontainment(FCV 760,761,762,763)ifrequestedforsampling(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam04r0a.docPage29of35Rev0 Op TestNo.:L121 NRCScenarioNo.:4EventNo.: 7Page26of 27EventDescription:LargeBreakLOCATimePositionApplicant'sActionsorBehavior(EOPE 1,"LossofReactororSecondaryCoolant)BOP (4)MaintainsS/Glevels20 65%BOP (5)Re verifiesPORVsclosedandassociatedblockvalvesopen(PCV 456failureaddressedearlier)(VB2-upperpanel,farright)ATC (6)DeterminesContainmentSprayshouldremaininserviceo (a)PK01 18isONo (b)Containmentradiationlevelsareabovenormal(PK11 21isON,RE 2/RE 7inalarm(bRNO)Verifiesspraysystemstillinservice(VB1,middleskirt)ATC (7)DeterminesECCSflowshouldNOTbereducedo (a)RCSsubcoolingislessthan20 o F(SCMMYI 31,lowercenterVB2)SRO/ATC ReadsCAUTIONregardingrunningRHRpumpwithcoolingtoassociatedheatexchanger;maynoteHxalreadyinservice (8)DeterminesRHRpumpshouldNOTbestoppedo (a.1)Notespressureislessthan300psig(a.1RNO)ChecksallavailableRHRpumpsrunning,continuestostep10SRO/BOP (10)DeterminesD/GshouldNOTbestoppedo (a)Offsitepowerisnotavailable,BusFandGcurrentlysuppliedbyrespectiveD/Gs(a.1RNO)MayimplementOPAP 26,"LossofOffsitePower"(Offsitepowerwillnotbereturned;observableControlRoomactionsrepeatstepsofECA0.3performedearlierinthescenario)(continuedonnextpage)**CriticalTask AppendixD(rev9)RequiredOperatorActionsFormES D 2 L121NRCSimExam04r0a.docPage30of35Rev0 Op TestNo.:L121 NRCScenarioNo.:4EventNo.: 7Page27of 27EventDescription:LargeBreakLOCATimePositionApplicant'sActionsorBehavior(EOPE 1,"LossofReactororSecondaryCoolant)SRO/ATC (10.b)ResetsSI(VB1,center,belowPK2)SRO/ALL (11)EvaluatesPlantStatuso (a)Verifiescoldlegrecirculationcapability-poweravailabletoRHR1 1o (b)ChecksAuxbuildingradiationmonitor-allareNormalo (c)ChecksifrunningRHRpumpisonrecir-itisnoto (d)DirectsROtoImplementAppendixP,MonitorLightBoxVerification(checksECCSvalvelineup)o (e)ContactsChemistrytosampletheRCSandplaceH 2analyzersinserviceo (f)ChecksTurbinestatus(oilpumps,coastdown,etc)o (g)ChecksforalarmsonSpentFuelPoollevelandtemperatureSRO/ATC (12)DeterminesthatpostLOCAcooldownprocedure(EOP1.2)isnotappropriateo (RCSpressureis<300psig(VB2,PPC,CC2)o RHRflow>100gpm(VB2) StaysinE 1,awaitingtransitiontoColdLegRecirc(RWST@33%)ThescenarioisterminatedoncecrewhascompletedactionsofEOPE 1andiswaitingtotransitiontoColdLegRecirc,perLeadEvaluator**CriticalTask