ML14279A079

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

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE 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 4.3 plant procedures during all modes of plant operation.

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

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

REV. 0

JPM TITLE: DETERMINE ULTIMATE HEAT SINK TEMPERATURE JPM NUMBER: NRCL121-A1 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 I1A, 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 60.1°F ASW Pp 1-1 In-service to CCW HX 1-1 TI-1484 61.4°F ASW Pp 1-2 In-STBY TI-1485 60.2°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 61.5°F 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 REV. 0

JPM TITLE: DETERMINE ULTIMATE HEAT SINK TEMPERATURE JPM NUMBER: NRCL121-A1 EVALUATOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 Obtains STP I1A, Attachment 12.1.

Sat: ______ Unsat _______

Comment:

2.**

0B Determine ocean temperature 2.1 Reads NOTE prior to step 37.a.

N/A checked for step 37.a (Method 1) 2.2 (TI-311 is Out of Service and CWP 1-2 is not running)

Performed step 37.b (Method 2), and 1B 2.3 recorded Pacific Ocean water temperature, 61.4°F (TI-1484).**

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

Determined 61.4°F is the highest available 2.5 3B indication.

2.6 Adds 0.7°F 4B Recorded 62.1°F as the corrected ocean 2.7 5B temperature. **

2.8 Checks N/A for step 37.c (Method 3)

Sat: ______ Unsat _______

Comment:

NRCL121-A1 PAGE 3 OF 5 REV. 0

JPM TITLE: DETERMINE ULTIMATE HEAT SINK TEMPERATURE JPM NUMBER: NRCL121-A1 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) to inform SFM to review SR 3.7.9.2 Checked step 37.d.2) due to ocean temperature determined to be greater than 3.4 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 REV. 0

69-20232 01/27/14 Page 15 of 26 STP I-1A (UNIT 1)

ATTACHMENT 12.1 TITLE: MODE 1 Shift Checklist APPL TECH SPEC A. CHECK / VERIFICATION FROM CONTROL ROOM MODE REFERENCE PERF 1 SR 3.7.9.2 37. Determine the Ultimate Heat Sink (UHS) temperature using one of the following methods:

NOTE: Temperature indicators are only available when their associated pumps are running.

a. Method 1 - Record Pacific Ocean water temp as read on the following indicators: N/A [ X ] ______

TI-311 (T2400A)

TI-328 (T2401A)

EY (CWP 1-1)

(CWP 1-2)

_______F

_______F Record the highest of the available indicators.

N/A [ ]

N/A [ ]

F

K Instrument Error Correction Add the highest available indicator reading and the Instrument Error 1.9 F SW Correction. F

b. Method 2 - Record Pacific Ocean water temp on the following indicators: N/A [ ] __NRC__

ER TI-1484 (ASWP 1-1) _61.4__F N/A [ ]

TI-1485 (ASWP 1-2) _______F N/A [X ]

Record the highest of the available indicators. 61.4 F Instrument Error Correction 0.7 F N Add the highest available indicator reading and the Instrument Error Correction. 62.1°F A

STP_I-1Au1r27.DOC 06 0515.1508

69-20232 01/27/14 Page 16 of 26 STP I-1A (UNIT 1)

ATTACHMENT 12.1 TITLE: MODE 1 Shift Checklist APPL TECH SPEC A. CHECK / VERIFICATION FROM CONTROL ROOM MODE REFERENCE PERF 1 SR 3.7.9.2 c. Method 3 - If Method 1 and Method 2 are not (Continued) available, M&TE may be used. N/A [X ] ______

Instrument Used: ____________________

Cal Due Date: ____________________

Reading using M&TE F Uncertainty of M&TE F

EY Add M&TE ocean temp and uncertainty NOTE: Tech Spec Bases B3.7.9 specifies that the UHS is F

common to both units. Therefore any required action due to elevated ocean water temp would apply to both units as required. K depending on mode requirements. Notify the Unit 2 SFM

d. IF corrected ocean temp is > [60F] AND [62F],

SW 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 />. ______

ER e. IF corrected ocean temp is > [62F] AND [64F],

f.

THEN perform the following:

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 />.

IF corrected ocean temp is > [64F],

N/A [ ]

_NRC_

_NRC_

THEN place both CCW HXs in service: N/A [ X ] ______

N A

STP_I-1Au1r27.DOC 06 0515.1508

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 60.1°F ASW Pp 1-1 In-service to CCW HX 1-1 TI-1484 61.4°F ASW Pp 1-2 In-STBY TI-1485 60.2°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 61.5°F 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 REV. 0

69-20232 01/27/14 Page 15 of 26 STP I-1A (UNIT 1)

ATTACHMENT 12.1 TITLE: MODE 1 Shift Checklist APPL TECH SPEC MODE REFERENCE A. CHECK / VERIFICATION FROM CONTROL ROOM PERF 1 SR 3.7.9.2 37. Determine the Ultimate Heat Sink (UHS) temperature using one of the following methods:

NOTE: Temperature indicators are only available when their associated pumps are running.

a. Method 1 - Record Pacific Ocean water temp as read on the following indicators: N/A [ ] ______

TI-311 (T2400A) (CWP 1-1) _______F N/A [ ]

TI-328 (T2401A) (CWP 1-2) _______F N/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 the following indicators: 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 indicator reading and the Instrument Error Correction. °F STP_I-1Au1r27.DOC 06 0515.1508

69-20232 01/27/14 Page 16 of 26 STP I-1A (UNIT 1)

ATTACHMENT 12.1 TITLE: MODE 1 Shift Checklist APPL TECH SPEC MODE REFERENCE A. CHECK / VERIFICATION FROM CONTROL ROOM PERF 1 SR 3.7.9.2 c. Method 3 - If Method 1 and Method 2 are not (Continued) available, 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 [ ] ______

STP_I-1Au1r27.DOC 06 0515.1508

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: LJACO-02R Title: DETERMINE ULTIMATE HEAT SINK TEMPERATURE Examinee:

Evaluator:

Results:

Comments:

Sat Print Unsat on Signature Total Time:

Date minutes Rev 4A an EC was performed to change to current rev and step of I-1A Ve approved by the ILT supervisor. Also changed ASW to 61.5 degrees per TIP 20048 act 16.

References:

rs i 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:

Time Allotment:

al Yes 10 Minutes No X in Critical Steps:

Job Designation:

2, 3 RO rig Task Number:

Rating:

G2.1.23

4.3 OAUTHOR

REVIEWED BY:

DAVID RICHARDS / CHARLES HIBBARD JOHN P. LYLE DATE:

DATE:

05/04/11 05/04/11 TRAINING SUPERVISOR APPROVED BY: KEN JOHNSTON DATE: 05/05/11 MANAGER - OPERATIONS REV. 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:

Initial Conditions:

on STP I-1A, MODE 1 Shift Checks, Step 37 (SR 3.7.9.2)

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.

Ve Current plant conditions for the Circ Water and ASW systems are as follows:

Component CWP 1-1 CWP 1-2 ASW Pp 1-2 rs i Status In-service Cleared ASW Pp 1-1 In-service to CCW HX 1-1 In-STBY Current Ocean Water Temperature TI-311 TI-328 TI-1484 TI-1485 61°F 61°F 61.5°F 60°F CWP 2-1 Cleared TI-311 61°F CWP 2-2 Cleared TI-328 61°F al ASW Pp 2-1 In-service to CCW HX 2-1 ASW Pp 2-2 Cleared TI-1484 TI-1485 61.5°F 61°F in 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.

rig Task Standard:

DO NOT READ TASK STANDARD TO EXAMINEE Ultimate Heat Sink temperature is determined based on given information and Shift Foreman informed of results.

O DOCCONTENT.dll PAGE 2 OF 5 REV. 4A

JPM TITLE: DETERMINE ULTIMATE HEAT SINK TEMPERATURE JPM NUMBER: LJACO-02R INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtains correct procedure. 1.1 Obtains STP I-1A, Attachment 12.1.

Note: Provide exam copy of STP I-1A,

2. **Determines UHS temperature using method 1.

2.1 on Attachment 12.1, Step 37.

Step was: Sat: _______ Unsat _______*

Reads NOTE prior to step 37.a.

Ve 2.2 Records the Pacific Ocean water temperature, 61°F on TI-311.**

rs i 2.3 2.4 Checks N/A for TI-328, since CWP 1-2 is not running.

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

2.5 Adds 1.9°F, and writes 62.9°F as the corrected ocean temperature. Initials al 2.6 step 37.a.**

Checks N/A for methods 2 and 3.

in Step was: Sat: _______ Unsat _______*

rig O

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

DOCCONTENT.dll PAGE 3 OF 5 REV. 4A

JPM TITLE: DETERMINE ULTIMATE HEAT SINK TEMPERATURE JPM NUMBER: LJACO-02R INSTRUCTOR WORKSHEET Step Expected 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 62°F, and on 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-Ve 3.3 4).

Checks N/A for step 37.e.

Stop Time:

Total Time:

rs i Step was: Sat: _______ Unsat _______*

(Enter total time on the cover page) al in rig O

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

DOCCONTENT.dll PAGE 4 OF 5 REV. 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 CWP 1-1 CWP 1-2 Status In-service Cleared ASW Pp 1-1 In-service to CCW HX 1-1 on Current Ocean Water Temperature TI-311 TI-328 TI-1484 61°F 61°F 61.5°F ASW Pp 1-2 CWP 2-1 CWP 2-2 Ve In-STBY Cleared Cleared TI-1485 TI-311 TI-328 60°F 61°F 61°F Initiating Cue:

ASW Pp 2-2 rs ASW Pp 2-1 In-service to CCW HX 2-1 i

Cleared TI-1484 TI-1485 61.5°F 61°F 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.

al in rig O

DOCCONTENT.dll PAGE 5 OF 5 REV. 4A

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE 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.

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

REV. 0

JPM TITLE: DETERMINE DILUTION REQUIREMENTS TO RAISE JPM NUMBER: NRCL121-A2 POWER EVALUATOR W ORKSHEET 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 REV. 0

JPM TITLE: DETERMINE DILUTION REQUIREMENTS TO RAISE JPM NUMBER: NRCL121-A2 POWER EVALUATOR W ORKSHEET 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:

Calculate reactivity change for 10% 2.1 From graph power coefficient is -15.47 2.** change in power pcm/% power.

0B 2.2 Recorded (-)154.7 pcm for 10% increase in power. **

Sat: ______ Unsat _______

Comment:

Recorded 45.9 pcm for Control Bank D at Calculate reactivity change due to change 3.1 210 steps.

3.** 1B in rod position (From graph, A. Control Bank D Integral Rod Worth)

Recorded 98.1 pcm for Control Bank D at 3.2 200 steps.

(From graph, A. Control Bank D Integral Rod Worth)

Recorded (+)52.2 pcm for change in rod 3.3 position. **

(98.1 - 45.9 )

Sat: ______ Unsat _______

Comment:

NRCL121-A2 PAGE 3 OF 5 REV. 0

JPM TITLE: DETERMINE DILUTION REQUIREMENTS TO RAISE JPM NUMBER: NRCL121-A2 POWER EVALUATOR WORKSHEET Recorded (-)102.5 pcm)reactivity from change Calculate reactivity left after accounting in rods position on total reactivity from change 4.** 4.1 in power. **

change in rod position.

2B

(-154.7 + 52.2)

Sat: ______ Unsat _______

Comment:

Note: The examinee may set up a ratio to get the primary water needed, Determines amount of primary water to or may do two steps (determine 5.** add power change needing dilution, 3B and then dilution for that power change).

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

5.1 (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 REV. 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 REV. 0

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

Evaluator:

Results: Sat Print Unsat on Signature Total Time:

Date minutes Comments:

Ve

References:

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

No X Time Critical: Yes No X Time Allotment:

Critical Steps:

al 15 Minutes 2-6 Job Designation:

Task Number:

in RO G2.1.25 rig Rating: 3.9 O

JOHN P. LYLEED HURST AUTHOR: GARY HUTCHISON DATE: 12/10/09 REV. 1

JPM TITLE: DETERMINE DILUTION REQUIREMENTS JPM NUMBER:

FOR A POWER INCREASE NRCL081LJA_ROA1 INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the procedure and told the step Required Materials:

Initial Conditions:

with which to begin.

Calculator, Reactivity Briefing Sheet on Unit 1 was ramped down due to problems with Govenor valve 4. Unit 1 Initiating Cue:

Ve has been at 90% power for 3 days with Control Bank D at 200 steps.

Shift Foreman directs you to determine the dilution or boration requirements to increase power to 95% assuming final rod position of Task Standard:

rs 210 steps using the data from the Reactivity Briefing Sheet.

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

al in rig O

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

JPM TITLE: DETERMINE DILUTION REQUIREMENTS JPM NUMBER:

FOR A POWER INCREASE NRCL081LJA_ROA1 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Operator obtains correct procedure 1.1 Operator obtains Reactivity Briefing Sheet.

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

2.

power Ve

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

3.

rs i

• • Calculates reactivity from change in rod position 2.2 3.1 Operator determines PCM for 5%

increase in power. (-62.85 pcm) **

Step was: Sat: _______ Unsat _______*

Operator determines PCM for Control Bank D at 210 steps. (28 pcm) **

3.2 Operator determines PCM for Control al 3.3 Bank D at 200 steps. (59.8 pcm) **

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

Step was: Sat: _______ Unsat _______*

rig O

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

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

JPM TITLE: DETERMINE DILUTION REQUIREMENTS JPM NUMBER:

FOR A POWER INCREASE NRCL081LJA_ROA1 INSTRUCTOR WORKSHEET Step Expected Operator Actions

4. ** Calculates reactivity left after 4.1 Accounts for reactivity from change accounting change in rod position. in rods position on total reactivity from change in power. (-62.8 + 31.8 =

-31.05 pcm)**

5. **Determines % power change from reactivity associated with dilution.

5.1 on Step was: Sat: _______ Unsat _______*

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

-12.57 pcm/% power)**

6. Ve

• • Determines amount of primay water Step was: Sat: _______ Unsat _______*

6.1 Determines that 230 (+/- 5 ) gallons to add.

rs i of primary water is required. (2.47%

• 93 gal/% = 230 gallons) **

Step was: Sat: _______ Unsat _______*

Stop Time:

Total Time:

al (Enter total time on the cover page) in rig O

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

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

JPM TITLE: DETERMINE DILUTION REQUIREMENTS JPM NUMBER:

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

Answer Key required.

Ve Operator determines that 230 (+/- 5 ) gallons of primary water is rs i al in rig O

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

EXAMINEE CUE SHEET JPM NUMBER:

NRCL081LJA_ROA1 Initial Conditions: Unit 1 was ramped down due to problems with Govenor valve 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 on 210 steps using the data from the Reactivity Briefing Sheet.

Ve rs i al in rig O

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

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-A3 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: G2.2.37 - Ability to determine operability and/or availability of 3.6 safety related equipment Note: This is an admin JPM (RO), intended for the classroom setting.

AUTHOR: LISA TORIBIO/ DATE:

OPERATIONS ABDUL KADIR/ DATE:

REPRESENTATIVE:

REV. 0

JPM TITLE: PERFORM OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A3 EVALUATOR W ORKSHEET 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-A3 PAGE 2 OF 9 REV. 0

JPM TITLE: PERFORM OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A3 EVALUATOR W ORKSHEET 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-A3 PAGE 3 OF 9 REV. 0

JPM TITLE: PERFORM OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A3 EVALUATOR W ORKSHEET 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:

Determines status of power to operable Determines S/U Power is operable and 2.** 2.1 marks the appropriate "boxes" on Att 4, vital buses.

0B page 6. **

Determines that a D/G is operable for 4kV 2.2 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:

Determines onsite power supply Note: Examinee may complete either 3.** 1B operability. step 3 (page 7) or both steps 4 and 5 (page 8 of this JPM).

Determines that D/G 1-2 and 1-3 are 3.1 operable and marks the appropriate "boxes" on Att 4, page 6. **

Sat: ______ Unsat _______

Comment:

NRCL121-A3 PAGE 4 OF 9 REV. 0

JPM TITLE: PERFORM OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A3 EVALUATOR W ORKSHEET Step Expected Operator Actions Determines that refueling cavity level is 23.4 feet ( 23 feet above the vessel 4.**

2B Determines status of refueling cavity. 4.1 flange) and the upper internals are removed (i.e., core onload is in progress) and marks the appropriate "boxes" on Att 4, page 6.

Determines that S/U power is operable and 4.2 marks the appropriate "boxes" on Att 4, page 6.

Sat: ______ Unsat _______

Comment:

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

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

Sat: ______ Unsat _______

Comment:

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

Sat: ______ Unsat _______

Comment:

NRCL121-A3 PAGE 5 OF 9 REV. 0

JPM TITLE: PERFORM OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A3 EVALUATOR W ORKSHEET Step Expected Operator Actions Determines status of Instrument AC Determines that all vital instrument AC 7.** 7.1 power panels are operable and marks Power Panels.

5B appropriate "boxes" on Att 4, page 6. **

Sat: ______ Unsat _______

Comment:

Determines that all vital DC buses are 8.** 6B Determines status of Vital DC Power 8.1 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-A3 PAGE 6 OF 9 REV. 0

JPM TITLE: PERFORM OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A3 EVALUATOR W ORKSHEET NRCL121-A3 PAGE 7 OF 9 REV. 0

JPM TITLE: PERFORM OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A3 EVALUATOR W ORKSHEET NRCL121-A3 PAGE 8 OF 9 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A3 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 NRCL121-A3 PAGE 9 OF 9 REV. 0

AD8.DC55 R38 Page 35 of 66 Unit 1 Outage Safety Checklist - Mode 6 RCS Level Greater Than or Equal to 111' Attachment 4: Page 6 of 7 All of the following DC Bus 1-1 Operable 1 of the following DC Bus 1-2 Operable Aux Power Operable S/U Power Operable DC Bus 1-3 Operable 1 of the following Cross-tie capability for each Operable Vital Bus D/G Operable for each Operable Vital Bus 1 of the following 2 of the following D/G 1-1 Operable D/G 1-2 Operable D/G 1-3 Operable All of the following 1 of the following All of the following Cavity Level > 23 ft above the vessel flange (> 137 ft)

Upper Internals removed All of the following Aux Power Operable S/U Power Operable 1 of the following D/G 1-1 Operable D/G 1-2 Operable D/G 1-3 Operable 1 of the following (Different D/G than credited Operable D/G above)

D/G 1-1 Operable, or Available PY 1-1 Operable D/G 1-2 Operable, or Available D/G 1-3 Operable, or Available PY 1-1A Operable All of the following as required by Tech Specs PY 1-2 Operable 4KV & 480V Bus F Operable PY 1-3 Operable 4KV & 480V Bus G Operable PY 1-3A Operable 4KV & 480V Bus H Operable PY 1-4 Operable AD8!DC55u3r38.DOC 1126.1027

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: LJAEC-01R Title: PERFORM OUTAGE SAFETY CHECKLIST Examinee:

Evaluator:

Testing Method: Perform Print Simulate on Signature Date Results:

Comments:

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

References:

rs 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.

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

AD8.DC55, Outage Safety Scheduling, Attachment 7.4, Rev. 36 Alternate Path: Yes No X Time Critical:

Time Allotment:

al Yes 10 minutes No X in Critical Steps:

Job Designation:

Rev Comments/TIPs:

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

RO This JPM was rewritten; therefore, no revision bars were used.

rig DCPP Task # / Rating:

Gen KA # / Rating:

Incorporated TIP 19743-29.

NA G2.2.37 NA

3.6 OAUTHOR

REVIEWED BY:

DAVE RICHARDS / CHARLES HIBBARD JOHN P. LYLE DATE:

DATE:

04/28/11 04/28/11 TRAINING SUPERVISOR APPROVED BY: ERIK WERNER DATE: 04/28/11 LINE MANAGER REV. 5A

JPM TITLE: PERFORM OUTAGE SAFETY CHECKLIST JPM NUMBER: LJAEC-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 Required Materials:

told what step to begin the task at.

on being done in the plant or lab, and after identifying the appropriate procedure for the task, the examinee may be given the procedure and Make a copy of Technical Specifications available for reference.

Unit 1 is currently in Mode 6 with Core onload in progress.

Initial Conditions:

Ve Current plant parameters are as follows:

Cleared Available rs Offsite power sources i

Onsite power sources Startup power Aux power Diesel Generator 1 Diesel Generator 2 Diesel Generator 3 Operable X NA X

X NA X X

Vital bus crosstie 4kV & 480v Bus F X NA 4kV & 480v Bus G X NA al Onsite distribution sys.

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

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 REV. 5A

JPM TITLE: PERFORM OUTAGE SAFETY CHECKLIST JPM NUMBER: LJAEC-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.

on Ve rs i al in rig O

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DOCCONTENT.DLL PAGE 3 OF 9 REV. 5A

JPM TITLE: PERFORM OUTAGE SAFETY CHECKLIST JPM NUMBER: LJAEC-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.

on 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) operable vital buses.

Ve

• • 2. Determines status of power to 2.1 Determines S/U Power is operable and marks the appropriate "boxes" on Att 4, page 6. **

rs i 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 al 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.

in

• • 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. **

rig Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

O

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DOCCONTENT.DLL PAGE 4 OF 9 REV. 5A

JPM TITLE: PERFORM OUTAGE SAFETY CHECKLIST JPM NUMBER: LJAEC-01R INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 4. Determines status of refueling Note: Examinee may complete either step cavity. 4.1 or step 4.2 (see logic in Att 4, page 6).

4.1 on 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. **

Ve 4.2 Determines that S/U power is operable and marks the appropriate "boxes" on Att 4, page 6. **

• • 5. Determines D/G operability. rs i Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat) 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 al available and marks appropriate "boxes" on Att 4, page 6.

Step was: Sat: ______ Unsat _______*

in [ ] Comment # (required for Unsat) rig O

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DOCCONTENT.DLL PAGE 5 OF 9 REV. 5A

JPM TITLE: PERFORM OUTAGE SAFETY CHECKLIST JPM NUMBER: LJAEC-01R INSTRUCTOR WORKSHEET Step Expected Operator Actions

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

on 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 Ve 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

• • 7. Determines status of Instrument AC Power Panels.

rs i operable in Mode 6.

Note: If requested, provide access to Tech Specs.

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 _______*

al [ ] Comment # (required for Unsat) in Stop Time:

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

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DOCCONTENT.DLL PAGE 6 OF 9 REV. 5A

KEY (Steps 2, 3, 6, and 7) x x

x x

x on x

x Ve x

x rs i al in rig x

x x

x x

x O x x x

DOCCONTENT.DLL PAGE 7 OF 9 REV. 5A

on Ve rs i al in rig O

DOCCONTENT.DLL PAGE 8 OF 9 REV. 5A

JPM NUMBER: LJAEC-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 Offsite power sources Onsite power sources Startup power Aux power on Diesel Generator 1 Diesel Generator 2 Operable X NA X

NA X X

Ve Vital bus crosstie Diesel Generator 3 4kV & 480v Bus F 4kV & 480v Bus G X

X X

NA NA rs Onsite distribution sys.

i Instrument AC Panels 4kV & 480v Bus H 4kV & 480v Bus F 4kV & 480v Bus G 4kV & 480v Bus H PY-11 PY-11A X

X X

X NA NA NA NA NA NA X

X PY-12 X NA PY-13 X NA al Refueling cavity level PY-13A PY-14 23.4 Feet X

X NA NA in 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.

rig O

DOCCONTENT.DLL PAGE 9 OF 9 REV. 5A

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE 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.

AUTHOR: LISA TORIBIO/ DATE:

OPERATIONS ABDUL KADIR/ DATE:

REPRESENTATIVE:

REV. 0

JPM TITLE: REVIEW LIQUID RADWASTE DISCHARGE CHECKLIST JPM NUMBER: NRCL121-A4 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-1-68 is open when SW-1-67 should be open)

NRCL121-A4 PAGE 2 OF 5 REV. 0

JPM TITLE: REVIEW LIQUID RADWASTE DISCHARGE CHECKLIST JPM NUMBER: NRCL121-A4 EVALUATOR WORKSHEET Start Time:

Step Expected Operator Actions Review step 12.1 - Parts 1 and 2 of Reviewed Parts 1 and 2 of CAP A-5,

1. discharge permit complete and signed by 1.1 Attachment 11.1 and determined parts 1 & 2 Chemistry are complete and signed by Chemistry Sat: ______ Unsat _______

Comment:

Review step 12.2 - Appropriate tank Identified that PWR 0-2 has been correctly

2. identified 2.1 circled for discharge Sat: ______ Unsat _______

Comment:

Review steps 12.3 (RE-18 adjustment) & Identified that RE-18 setpoint doesnt require

3. 12.4 (FIT-243 not operable actions) 3.1 adjustment 3.2 Identified FIT-243 is OPERABLE Sat: ______ Unsat _______

Comment:

Review step 12.5 - Discharge flowpath Identified that LWS-0-436 to U1 CCW,

4. aligned to inservice U1 CCW heat 4.1 marked as OPEN exchanger identified Identified that LWS-0-439 to U2 CCW, 4.2 marked as CLOSED Sat: ______ Unsat _______

Comment:

NRCL121-A4 PAGE 3 OF 5 REV. 0

JPM TITLE: REVIEW LIQUID RADWASTE DISCHARGE CHECKLIST JPM NUMBER: NRCL121-A4 EVALUATOR WORKSHEET Step Expected Operator Actions Review steps 12.6 thru 12.9 - valves Identified that steps 12.6 through 12.9 signed

5. 5.1 closed as completed Sat: ______ Unsat _______

Comment:

Identified CCW HX 11 should be circled to be 6.** Review step 12.10 - ASW checklist 6.1 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-A4 PAGE 4 OF 5 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A4 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-A4 PAGE 5 OF 5 REV. 0

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

Examinee:

Evaluator:

Results: Sat Print Unsat on Signature Total Time:

Date minutes Comments:

Ve Designed for SRO Candidates in a classroom setting.

References:

Rev. 35A rs i OP G-1:II, Liquid Radwaste System - Discharge of Liquid Radwaste, CAP A-5, Liquid Radwaste Discharge Management, Rev. 41A Alternate Path: Yes X No Time Critical:

Time Allotment:

al Yes 20 minutes No X in Critical Steps:

Job Designation:

4 SRO rig K/A:

Rating:

G 2.3.6; Ability to approve release permits.

3.8 O

AUTHOR: GARY HUTCHISON DATE: 08/12/2008 REV. 1

JPM TITLE: REVIEW LIQUID RADWASTE JPM NUMBER: NRCADM061C-A4 DISCHARGE CHECKLIST 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 Required Materials:

on identifying the appropriate procedure for the task, the examinee may be given the procedure and told the step with which to begin.

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:

Ve 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:

Task Standard:

rs As the Unit 1 Shift Foreman, review OP G-1:II Attachments 9.1 & 9.5 i

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.

2 Technical errors were identified:

• Attachment 9.1 page 2, CCW HX 1-2 is circled to be used for the al

• 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.

in rig O

NRCADM061C-A4.DOC Page 2 of 6 REV. 1

JPM TITLE: REVIEW LIQUID RADWASTE JPM NUMBER: NRCADM061C-A4 DISCHARGE CHECKLIST INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Review checks on page 1 of 1.1 Determines Batch number matches CAP Attachment 9.1.

on 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.

Ve 1.4 Identifies that dilution flowrate is adequate.

• • 2. Review Manual Valve Lineup Verification on page 2 of rs i 1.5 Identifies that RE-18 setpoint doesnt require adjustment.

Step was: Sat: ______ Unsat _______*

2.1 Determines that CCW HX 12 is to be circled to be used, but that valve Attachment 9.1 alignment is for CCW HX 11.

• • 3.

al Review Attachment 9.5 PWR alignment checklist.

Step was: Sat: ______ Unsat _______*

3.1 Determines that PWR 0-2 has been aligned for discharge instead of PWR in 0-1.

Step was: Sat: ______ Unsat _______*

rig

• • 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.

O Step was: Sat: ______ Unsat _______*

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

NRCADM061C- Page 3 of 6 REV. 1 A4.DOC

JPM TITLE: REVIEW LIQUID RADWASTE JPM NUMBER: NRCADM061C-A4 DISCHARGE CHECKLIST INSTRUCTOR WORKSHEET Stop Time:

Total Time:

on (Enter total time on the cover page)

Ve rs i al in rig O* Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

NRCADM061C- Page 4 of 6 REV. 1 A4.DOC

JPM NUMBER: NRCADM061C-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 on discrepancies noted and determine if the discharge checklist should be approved or not approved based on your review.

Technical Errors Identified:

Ve

[ ] APPROVE Discharge rs i [ ] DO NOT Approve Discharge al in rig O

NRCADM061C- Page 5 of 6 REV. 1 A4.DOC

REVIEW LIQUID RADWASTE DISCHARGE CHECKLIST JPM NUMBER: NRCADM061C-A4 ATTACHMENT 1, SIMULATOR SETUP The simulator is not needed for the performance of this JPM.

on Ve rs i al in rig O

NRCADM061C- Page 6 of 6 REV. 1 A4.DOC

JPM TITLE: REVIEW LIQUID RADWASTE JPM NUMBER: NRCADM061C-A4 DISCHARGE CHECKLIST.

ANSWER KEY 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 on 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:

Ve .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.

[ ] APPROVE Discharge rs .5 has PWR 0-2 aligned when PWR 0-1 should be.

i [ X ] DO NOT Approve Discharge al in rig O

NRCADM061C- Page 7 of 6 REV. 1 A4.DOC

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:

STP I-1A, Routine Shift Checks Required by Licenses, Attachment 12.1, Rev. 126

References:

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: G2.1.25 - Conduct of Operations 3.9 Note: This is an admin JPM (SRO), intended for the classroom setting.

AUTHOR: LISA TORIBIO/ DATE:

OPERATIONS ABDUL KADIR/ DATE:

REPRESENTATIVE:

REV. 0

JPM TITLE: VERIFY A DETERMINATION OF ULTIMATE HEAT JPM NUMBER: NRCL121-A5 SINK TEMPERATURE EVALUATOR W ORKSHEET 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 61.1°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 REV. 0

JPM TITLE: VERIFY A DETERMINATION OF ULTIMATE HEAT JPM NUMBER: NRCL121-A5 SINK TEMPERATURE EVALUATOR W ORKSHEET Start Time:

Step Expected Operator Actions 1.** Review Step 37, Method 1 Data. 1.1 Read NOTE prior to step 37.a Method 1 incorrectly used. CWP 1-2 is not 1.2 running (Per note, temperature indicator not available) and TI-311 is out of calibration.**

Sat: ______ Unsat _______

Comment:

NOTE: The sheet may not be completed as the key is however, some manner must be used to determine the correct ocean temperature

2. Perform Step 37, Method 2 2.1 Used method 2 to determine ocean temperature:

TI-1484 = 59.5°F TI-1485. = 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:

Determine ocean temperature monitoring 3.1 Required ocean temperature monitoring is 37.d 3.**

required (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) **

Sat: ______ Unsat _______

Comment:

4.1 LCO is met, UHS is OPERABLE (less than 4.** Evaluates LCO 3.7.9 (UHS) **

64°F)**

Sat: ______ Unsat _______

Comment:

NRCL121-A5 PAGE 3 OF 5 REV. 0

JPM TITLE: VERIFY A DETERMINATION OF ULTIMATE HEAT JPM NUMBER: NRCL121-A5 SINK TEMPERATURE EVALUATOR W ORKSHEET 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 REV. 0

69-20232 01/27/14 Page 15 of 26 STP I-1A (UNIT 1)

ATTACHMENT 12.1 TITLE: MODE 1 Shift Checklist APPL TECH SPEC MODE REFERENCE A. CHECK / VERIFICATION FROM CONTROL ROOM PERF 1 SR 3.7.9.2 37. Determine the Ultimate Heat Sink (UHS) temperature using one of the following methods:

NOTE: Temperature indicators are only available when their associated pumps are running.

a. Method 1 - Record Pacific Ocean water temp as read on the following indicators: GLH N/A [ ] ______

TI-311 (T2400A)

TI-328 (T2401A)

EY (CWP 1-1)

(CWP 1-2)

_______F 61.1

_______F Record the highest of the available indicators. 61.1 F N/A [X]

N/A [ ]

K Instrument Error Correction Add the highest available indicator reading and the Instrument Error 1.9 F SW Correction. 63.0 F

b. Method 2 - Record Pacific Ocean water temp on the following indicators: N/A [ X] ______

ER TI-1484 (ASWP 1-1) _59.5__F N/A [ ]

TI-1485 (ASWP 1-2) _______F N/A [ ]

Record the highest of the available indicators. 59.5°F Instrument Error Correction 0.7 F N Add the highest available indicator reading and the Instrument Error Correction. 60.2°F A

STP_I-1Au1r27.DOC 06 0515.1508

69-20232 01/27/14 Page 16 of 26 STP I-1A (UNIT 1)

ATTACHMENT 12.1 TITLE: MODE 1 Shift Checklist APPL TECH SPEC MODE REFERENCE A. CHECK / VERIFICATION FROM CONTROL ROOM PERF 1 SR 3.7.9.2 c. Method 3 - If Method 1 and Method 2 are not available, M&TE may be used. GLH N/A [X] ______

(Continued)

Instrument Used: ____________________

Cal Due Date: ____________________

Reading using M&TE F Uncertainty of M&TE F

EY Add M&TE ocean temp and uncertainty NOTE: Tech Spec Bases B3.7.9 specifies that the UHS is F

common to both units. Therefore any required action due to elevated ocean water temp would apply to both units as required. K depending on mode requirements. Notify the Unit 2 SFM

d. IF corrected ocean temp is > [60F] AND [62F],

SW 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 />. ____X__

ER e. IF corrected ocean temp is > [62F] AND [64F],

f.

THEN perform the following:

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 />.

IF corrected ocean temp is > [64F],

N/A [ ]

GLH

______

GLH

______

THEN place both CCW HXs in service: GLH N/A [X] ______

N A

STP_I-1Au1r27.DOC 06 0515.1508

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 61.1°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 hours 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 REV. 0

69-20232 01/27/14 Page 15 of 26 STP I-1A (UNIT 1)

ATTACHMENT 12.1 TITLE: MODE 1 Shift Checklist APPL TECH SPEC MODE REFERENCE A. CHECK / VERIFICATION FROM CONTROL ROOM PERF 1 SR 3.7.9.2 37. Determine the Ultimate Heat Sink (UHS) temperature using one of the following methods:

NOTE: Temperature indicators are only available when their associated pumps are running.

a. Method 1 - Record Pacific Ocean water temp as read on the following indicators: GLH N/A [ ] ______

TI-311 (T2400A) (CWP 1-1) _______F N/A [X]

TI-328 (T2401A) (CWP 1-2) 61.1

_______F N/A [ ]

Record the highest of the available indicators. 61.1 F Instrument Error Correction 1.9 F Add the highest available indicator reading and the Instrument Error Correction. 63.0 F

b. Method 2 - Record Pacific Ocean water temp on the following indicators: N/A [ X] ______

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 indicator reading and the Instrument Error Correction. °F STP_I-1Au1r27.DOC 06 0515.1508

69-20232 01/27/14 Page 16 of 26 STP I-1A (UNIT 1)

ATTACHMENT 12.1 TITLE: MODE 1 Shift Checklist APPL TECH SPEC MODE REFERENCE A. CHECK / VERIFICATION FROM CONTROL ROOM PERF 1 SR 3.7.9.2 c. Method 3 - If Method 1 and Method 2 are not available, M&TE may be used. GLH N/A [X] ______

(Continued)

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. GLH

______

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 />. GLH

______

f. IF corrected ocean temp is > [64F],

THEN place both CCW HXs in service: GLH N/A [X] ______

STP_I-1Au1r27.DOC 06 0515.1508

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: LJACO-02S Title: VERIFY A DETERMINATION OF ULTIMATE HEAT SINK TEMPERATURE Examinee:

Evaluator:

Results: Sat Print Unsat on Signature Total Time:

Date minutes Comments:

Ve 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:

12.1, Rev. 121 rs i STP I-1A, Routine Shift Checks Required by Licenses, Attachment Technical Specifications, DCPP Units 1 & 2 Alternate Path: Yes X No Time Critical:

Time Allotment:

al Yes 10 Minutes No X in Critical Steps:

Job Designation:

2, 4 SRO rig Task Number:

Rating:

G2.1.23

4.4 OAUTHOR

REVIEWED BY:

DAVID RICHARDS / CHARLES HIBBARD JOHN P. LYLE DATE:

DATE:

05/04/11 05/04/11 TRAINING SUPERVISOR APPROVED BY: KEN JOHNSTON DATE: 05/05/11 MANAGER - OPERATIONS REV. 4A

JPM TITLE: VERIFY A DETERMINATION OF ULTIMATE HEAT SINK JPM NUMBER: LJACO-02S TEMPERATURE 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 Required Materials:

Initial Conditions:

begin.

Checklist, Step 37 (SR 3.7.9.2) on Completed copy of STP I-1A, Attachment 12.1, MODE 1 Shift Unit 1 is at 50% power with CWP 1-2 out of service for replacement of Ve 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 CWP 1-1 CWP 1-2 rs i Status In-service Cleared ASW Pp 1-1 In-service to CCW HX 1-1 Current Ocean Water Temperature TI-311 TI-328 TI-1484 61°F 61°F 61.5°F ASW Pp 1-2 In-STBY TI-1485 60°F al CWP 2-1 CWP 2-2 Cleared Cleared ASW Pp 2-1 In-service to CCW HX 2-1 TI-311 TI-328 TI-1484 61°F 61°F 62°F in Initiating Cue:

ASW Pp 2-2 Cleared TI-1485 Required by Licenses, Attachment 12.1, Step 37.

61°F Unit 1 BOPCO has just completed STP I-1A, Routine Shift Checks rig 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.

O Task Standard:

DO NOT READ TASK STANDARD TO EXAMINEE 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 REV. 4A

JPM TITLE: VERIFY A DETERMINATION OF ULTIMATE HEAT SINK JPM NUMBER: LJACO-02S TEMPERATURE INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtains correct procedure 1.1 Obtains completed STP I-1A, Attachment 12.1, Step 37.

on Note: Provide completed exam copy of STP I-1A, Attachment 12.1, Step 37.

Step was: Sat: _______ Unsat _______*

2.

Ve

• • Verifies UHS temperature method 1. 2.1 Reads NOTE prior to step 37.a.

rs i 2.2 2.3 Verifies that the Pacific Ocean water temperature of 61°F is entered for TI-311.**

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 61°F is entered as the al 2.5 highest temperature.**

Notes that the instrument error was added incorrectly.**

in Note: The value entered on the completed STP I-1A was 61.9°F. The correct value is 62.9°F.

rig Step was: Sat: _______ Unsat _______*

O

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

DOCCONTENT.dll PAGE 3 OF 6 REV. 4A

JPM TITLE: VERIFY A DETERMINATION OF ULTIMATE HEAT SINK JPM NUMBER: LJACO-02S TEMPERATURE INSTRUCTOR WORKSHEET Step Expected Operator Actions

3. Verifies UHS temperature using 3.1 Verifies that N/A is checked for methods 2 & 3. Method 2.

3.2 Verifies that N/A is checked for Method 3.

4. **Verifies appropriate Tech Spec actions are taken.

4.1 on Step was: Sat: _______ Unsat _______*

Determines that step 37.d was completed incorrectly.**

Ve Note: The step on the completed STP I-1A was marked N/A. Step d should rs i 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 al 4.3 refueling outage (not in Modes 1-4).

Verifies step 37.e is checked N/A.

in Step was: Sat: _______ Unsat _______*

rig Stop Time:

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

O

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

DOCCONTENT.dll PAGE 4 OF 6 REV. 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 CWP 1-1 CWP 1-2 Status In-service Cleared ASW Pp 1-1 In-service to CCW HX 1-1 on Current Ocean Water Temperature TI-311 TI-328 TI-1484 61°F 61°F 61.5°F ASW Pp 1-2 CWP 2-1 CWP 2-2 Ve In-STBY Cleared Cleared TI-1485 TI-311 TI-328 60°F 61°F 61°F Initiating Cue:

ASW Pp 2-2 rs ASW Pp 2-1 In-service to CCW HX 2-1 i

Cleared TI-1484 TI-1485 62°F 61°F 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 al sheet and determine if his assessment is correct and implement any actions needed based on your review.

in rig O

DOCCONTENT.dll PAGE 5 OF 6 REV. 4A

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE 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.

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

REV. 0

JPM TITLE: DETERMINE DILUTION REQUIREMENTS TO RAISE JPM NUMBER: NRCL121-A6 POWER EVALUATOR W ORKSHEET 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 REV. 0

JPM TITLE: DETERMINE DILUTION REQUIREMENTS TO RAISE JPM NUMBER: NRCL121-A6 POWER EVALUATOR W ORKSHEET 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:

Calculate reactivity change for 10% 2.1 From graph power coefficient is -15.47 2.** change in power pcm/% power.

0B 2.2 Recorded (-)154.7 pcm for 10% increase in power. **

Sat: ______ Unsat _______

Comment:

Recorded 45.9 pcm for Control Bank D at Calculate reactivity change due to change 3.1 210 steps.

3.** 1B in rod position (From graph, A. Control Bank D Integral Rod Worth)

Recorded 98.1 pcm for Control Bank D at 3.2 200 steps.

(From graph, A. Control Bank D Integral Rod Worth)

Recorded (+)52.2 pcm for change in rod 3.3 position. **

(98.1 - 45.9 )

Sat: ______ Unsat _______

Comment:

NRCL121-A6 PAGE 3 OF 5 REV. 0

JPM TITLE: DETERMINE DILUTION REQUIREMENTS TO RAISE JPM NUMBER: NRCL121-A6 POWER EVALUATOR WORKSHEET Recorded (-)102.5 pcm)reactivity from change Calculate reactivity left after accounting in rods position on total reactivity from change 4.** 4.1 in power. **

change in rod position.

2B

(-154.7 + 52.2)

Sat: ______ Unsat _______

Comment:

Note: The examinee may set up a ratio to get the primary water needed, Determines amount of primary water to or may do two steps (determine 5.** add power change needing dilution, 3B and then dilution for that power change).

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

5.1 (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 REV. 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 REV. 0

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

Evaluator:

Results: Sat Print Unsat on Signature Total Time:

Date minutes Comments:

Ve

References:

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

No X Time Critical: Yes No X Time Allotment:

Critical Steps:

al 15 Minutes 2-6 Job Designation:

Task Number:

in RO G2.1.25 rig Rating: 3.9 O

JOHN P. LYLEED HURST AUTHOR: GARY HUTCHISON DATE: 12/10/09 REV. 1

JPM TITLE: DETERMINE DILUTION REQUIREMENTS JPM NUMBER:

FOR A POWER INCREASE NRCL081LJA_ROA1 INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the procedure and told the step Required Materials:

Initial Conditions:

with which to begin.

Calculator, Reactivity Briefing Sheet on Unit 1 was ramped down due to problems with Govenor valve 4. Unit 1 Initiating Cue:

Ve has been at 90% power for 3 days with Control Bank D at 200 steps.

Shift Foreman directs you to determine the dilution or boration requirements to increase power to 95% assuming final rod position of Task Standard:

rs 210 steps using the data from the Reactivity Briefing Sheet.

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

al in rig O

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

JPM TITLE: DETERMINE DILUTION REQUIREMENTS JPM NUMBER:

FOR A POWER INCREASE NRCL081LJA_ROA1 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Operator obtains correct procedure 1.1 Operator obtains Reactivity Briefing Sheet.

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

2.

power Ve

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

3.

rs i

• • Calculates reactivity from change in rod position 2.2 3.1 Operator determines PCM for 5%

increase in power. (-62.85 pcm) **

Step was: Sat: _______ Unsat _______*

Operator determines PCM for Control Bank D at 210 steps. (28 pcm) **

3.2 Operator determines PCM for Control al 3.3 Bank D at 200 steps. (59.8 pcm) **

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

Step was: Sat: _______ Unsat _______*

rig O

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

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

JPM TITLE: DETERMINE DILUTION REQUIREMENTS JPM NUMBER:

FOR A POWER INCREASE NRCL081LJA_ROA1 INSTRUCTOR WORKSHEET Step Expected Operator Actions

4. ** Calculates reactivity left after 4.1 Accounts for reactivity from change accounting change in rod position. in rods position on total reactivity from change in power. (-62.8 + 31.8 =

-31.05 pcm)**

5. **Determines % power change from reactivity associated with dilution.

5.1 on Step was: Sat: _______ Unsat _______*

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

-12.57 pcm/% power)**

6. Ve

• • Determines amount of primay water Step was: Sat: _______ Unsat _______*

6.1 Determines that 230 (+/- 5 ) gallons to add.

rs i of primary water is required. (2.47%

• 93 gal/% = 230 gallons) **

Step was: Sat: _______ Unsat _______*

Stop Time:

Total Time:

al (Enter total time on the cover page) in rig O

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

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

JPM TITLE: DETERMINE DILUTION REQUIREMENTS JPM NUMBER:

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

Answer Key required.

Ve Operator determines that 230 (+/- 5 ) gallons of primary water is rs i al in rig O

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

EXAMINEE CUE SHEET JPM NUMBER:

NRCL081LJA_ROA1 Initial Conditions: Unit 1 was ramped down due to problems with Govenor valve 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 on 210 steps using the data from the Reactivity Briefing Sheet.

Ve rs i al in rig O

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

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-A7 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: SRO Rev Comments: Modified from LJAEC-01S G2.2.37 - Ability to determine operability and/or availability of Gen KA / Rating: 4.6 safety related equipment Note: This is an admin JPM (SRO), intended for the classroom setting.

AUTHOR: LISA TORIBIO DATE:

OPERATIONS ABDUL KADIR DATE:

REPRESENTATIVE:

REV. 0

JPM TITLE: VERIFY OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A7 EVALUATOR W ORKSHEET 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 135 Feet NRCL121-A7 PAGE 2 OF 8 REV. 0

JPM TITLE: VERIFY OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A7 EVALUATOR W ORKSHEET 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-A7 PAGE 3 OF 8 REV. 0

JPM TITLE: VERIFY OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A7 EVALUATOR W ORKSHEET Start Time:

Step Expected Operator Actions Obtained completed copy of AD8.DC55, Att 4,

1. Obtain the correct procedure. 1.1 page 6, Unit 1 Outage Safety Checklist - Mode 6 RCS Level Greater Than or Equal to 111'.

Sat: ______ Unsat _______

Comment:

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

2. Status of On-site power 2.1 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-A7 PAGE 4 OF 8 REV. 0

JPM TITLE: VERIFY OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A7 EVALUATOR W ORKSHEET Determined 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)**

3.** Status of On-site Power supply 3.1

• 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 kV buses F and G, as well as 480V buses F

4. Status of 480 VAC 4.1 and G, are operable and the appropriate "boxes" on Att 4, page 6 are marked.

Sat: ______ Unsat _______

Comment:

NRCL121-A7 PAGE 5 OF 8 REV. 0

JPM TITLE: VERIFY OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A7 EVALUATOR W ORKSHEET Note: The boxes at the bottom of the right hand column of Att 4, page 6

5. Status of Instrument AC Power Panels 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.

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

Comment:

Determined that all vital DC buses are

6. Status of Vital DC Power 6.1 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-A7 PAGE 6 OF 8 REV. 0

AD8.DC55 R38 Page 35 of 66 Unit 1 Outage Safety Checklist - Mode 6 RCS Level Greater Than or Equal to 111' Attachment 4: Page 6 of 7 All of the following DC Bus 1-1 Operable 1 of the following DC Bus 1-2 Operable Aux Power Operable S/U Power Operable DC Bus 1-3 Operable 1 of the following Cross-tie capability for each Operable Vital Bus D/G Operable for each Operable Vital Bus 1 of the following 2 of the following D/G 1-1 Operable EY D/G 1-2 Operable D/G 1-3 Operable K

Cavity level < 137 feet SW All of the following 1 of the following All of the following ER Cavity Level > 23 ft above the vessel flange (> 137 ft)

Upper Internals removed All of the following Aux Power Operable Must be a different D/G. Cannot be D/

S/U Power Operable G 1-2 N 1 of the following D/G 1-1 Operable A D/G 1-2 Operable D/G 1-3 Operable 1 of the following (Different D/G than credited Operable D/G above)

D/G 1-1 Operable, or Available PY 1-1 Operable D/G 1-2 Operable, or Available D/G 1-3 Operable, or Available PY 1-1A Operable All of the following as required by Tech Specs PY 1-2 Operable 4KV & 480V Bus F Operable PY 1-3 Operable 4KV & 480V Bus G Operable PY 1-3A Operable 4KV & 480V Bus H Operable PY 1-4 Operable AD8!DC55u3r38.DOC 1126.1027

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A7 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 135 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-A7 PAGE 7 OF 8 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A7 Document Answer Here VITAL AC Power is:

Acceptable / Not Acceptable*

• Not acceptable due to:

NRCL121-A7 PAGE 8 OF 8 REV. 0

AD8.DC55 R38 Page 35 of 66 Unit 1 Outage Safety Checklist - Mode 6 RCS Level Greater Than or Equal to 111' Attachment 4: Page 6 of 7 All of the following DC Bus 1-1 Operable 1 of the following DC Bus 1-2 Operable Aux Power Operable S/U Power Operable DC Bus 1-3 Operable 1 of the following Cross-tie capability for each Operable Vital Bus D/G Operable for each Operable Vital Bus 1 of the following 2 of the following D/G 1-1 Operable D/G 1-2 Operable D/G 1-3 Operable All of the following 1 of the following All of the following Cavity Level > 23 ft above the vessel flange (> 137 ft)

Upper Internals removed All of the following Aux Power Operable S/U Power Operable 1 of the following D/G 1-1 Operable D/G 1-2 Operable D/G 1-3 Operable 1 of the following (Different D/G than credited Operable D/G above)

D/G 1-1 Operable, or Available PY 1-1 Operable D/G 1-2 Operable, or Available D/G 1-3 Operable, or Available PY 1-1A Operable All of the following as required by Tech Specs PY 1-2 Operable 4KV & 480V Bus F Operable PY 1-3 Operable 4KV & 480V Bus G Operable PY 1-3A Operable 4KV & 480V Bus H Operable PY 1-4 Operable AD8!DC55u3r38.DOC 1126.1027

JPM TITLE: VERIFY OUTAGE SAFETY CHECKLIST JPM NUMBER: LJAEC-01S INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 6. Verifies TS required 4kV and 6.1 Verifies 4 kV buses F and G, as well 480V bus operability. as 480V buses F and G, are operable and the appropriate "boxes" on Att 4, page 6 are marked. **

on 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 Ve 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

• • 7. Determines status of Instrument AC Power Panels.

rs i operable in Mode 6.

Note: If requested, provide access to Tech Specs.

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 _______*

al [ ] Comment # (required for Unsat) in Stop Time:

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

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DOCCONTENT.DLL PAGE 6 OF 10 REV. 5A

x x

x x

x on x

Ve x

x x

x rs i x

x x al x

in x

rig x x

x x

O x

x x

x x

x x

DOCCONTENT.DLL PAGE 7 OF 10 REV. 5A

on Ve rs i al in rig O

DOCCONTENT.DLL PAGE 8 OF 10 REV. 5A

JPM NUMBER: LJAEC-01S 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 Offsite power sources Onsite power sources Startup power Aux power on Diesel Generator 1 Available Operable X NA NA X X

Ve Vital bus crosstie Diesel Generator 2 Diesel Generator 3 4kV & 480v Bus F X

X X

NA rs i Onsite distribution sys.

Instrument AC Panels 4kV & 480v Bus G 4kV & 480v Bus H 4kV & 480v Bus F 4kV & 480v Bus G 4kV & 480v Bus H PY-11 X

X X

X NA NA NA NA NA NA X

X PY-11A X NA PY-12 X NA al Refueling cavity level PY-13 PY-13A PY-14 139 Feet X

X X

NA NA NA in rig O

DOCCONTENT.DLL PAGE 9 OF 10 REV. 5A

JPM NUMBER: LJAEC-01S 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.

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

Ve Document Your Answer Here VITAL AC POWER is:

• Discrepancies:

rs Acceptable i

Not Acceptable*

al in rig O

DOCCONTENT.DLL PAGE 10 OF 10 REV. 5A

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-A8 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 Steps: 1.2, 1.3 Job Designation: SRO 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: LISA TORIBIO/ DATE: 06/20/2014 OPERATIONS ABDUL KADIR/ DATE: 06/20/2014 REPRESENTATIVE:

REV. 0

JPM TITLE: REVIEW LIQUID RADWASTE DISCHARGE CHECKLIST JPM NUMBER: NRCL121-A8 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 REV. 0

JPM TITLE: REVIEW LIQUID RADWASTE DISCHARGE CHECKLIST JPM NUMBER: NRCL121-A8 EVALUATOR WORKSHEET Start Time:

Step Expected Operator Actions Review section 12 (steps 12.1 through 1.1 Steps 12.1 through 12.14 reviewed as 1.** 12.18) completed correctly.

0B Determined that actual current dilution flow 1.2 was incorrectly calculated by the operator (actual flowrate is 0.455 x 106 gpm (0.433 +

0.011 + 0.011 x 106 gpm)) **

NOTE: assumed flow may be determined by noting 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)

Recommends not approving the discharge 1.3 permit because the actual flowrate is less than the required flowrate (8.77 x 105 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 106 gpm vs. required 8.77 x 105 gpm)

Follow up Question Documentation:

Question: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

Response: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

NRCL121-A8 PAGE 3 OF 4 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A8 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 REV. 0

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

1&2 D IABLO C ANYON P OWER P LANT OP G-1:II OPERATING PROCEDURE Rev. 37A UNITS Page 1 of 51 Liquid Radwaste System - Discharge of Liquid Radwaste 12/29/11 Effective Date QUALITY RELATED Table of Contents

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).

OP_G-1~IIu3r37.DOC 1228.0741

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

Examinee:

Evaluator:

Results: Sat Print Unsat on Signature Total Time:

Date minutes Comments:

Ve Designed for SRO Candidates in a classroom setting.

References:

Rev. 35A rs i OP G-1:II, Liquid Radwaste System - Discharge of Liquid Radwaste, CAP A-5, Liquid Radwaste Discharge Management, Rev. 41A Alternate Path: Yes X No Time Critical:

Time Allotment:

al Yes 20 minutes No X in Critical Steps:

Job Designation:

4 SRO rig K/A:

Rating:

G 2.3.6; Ability to approve release permits.

3.8 O

AUTHOR: GARY HUTCHISON DATE: 08/12/2008 REV. 1

JPM TITLE: REVIEW LIQUID RADWASTE JPM NUMBER: NRCADM061C-A4 DISCHARGE CHECKLIST 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 Required Materials:

on identifying the appropriate procedure for the task, the examinee may be given the procedure and told the step with which to begin.

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:

Ve 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:

Task Standard:

rs As the Unit 1 Shift Foreman, review OP G-1:II Attachments 9.1 & 9.5 i

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.

2 Technical errors were identified:

• Attachment 9.1 page 2, CCW HX 1-2 is circled to be used for the al

• 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.

in rig O

NRCADM061C-A4.DOC Page 2 of 6 REV. 1

JPM TITLE: REVIEW LIQUID RADWASTE JPM NUMBER: NRCADM061C-A4 DISCHARGE CHECKLIST INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Review checks on page 1 of 1.1 Determines Batch number matches CAP Attachment 9.1.

on 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.

Ve 1.4 Identifies that dilution flowrate is adequate.

• • 2. Review Manual Valve Lineup Verification on page 2 of rs i 1.5 Identifies that RE-18 setpoint doesnt require adjustment.

Step was: Sat: ______ Unsat _______*

2.1 Determines that CCW HX 12 is to be circled to be used, but that valve Attachment 9.1 alignment is for CCW HX 11.

• • 3.

al Review Attachment 9.5 PWR alignment checklist.

Step was: Sat: ______ Unsat _______*

3.1 Determines that PWR 0-2 has been aligned for discharge instead of PWR in 0-1.

Step was: Sat: ______ Unsat _______*

rig

• • 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.

O Step was: Sat: ______ Unsat _______*

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

NRCADM061C- Page 3 of 6 REV. 1 A4.DOC

JPM TITLE: REVIEW LIQUID RADWASTE JPM NUMBER: NRCADM061C-A4 DISCHARGE CHECKLIST INSTRUCTOR WORKSHEET Stop Time:

Total Time:

on (Enter total time on the cover page)

Ve rs i al in rig O* Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

NRCADM061C- Page 4 of 6 REV. 1 A4.DOC

JPM NUMBER: NRCADM061C-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 on discrepancies noted and determine if the discharge checklist should be approved or not approved based on your review.

Technical Errors Identified:

Ve

[ ] APPROVE Discharge rs i [ ] DO NOT Approve Discharge al in rig O

NRCADM061C- Page 5 of 6 REV. 1 A4.DOC

REVIEW LIQUID RADWASTE DISCHARGE CHECKLIST JPM NUMBER: NRCADM061C-A4 ATTACHMENT 1, SIMULATOR SETUP The simulator is not needed for the performance of this JPM.

on Ve rs i al in rig O

NRCADM061C- Page 6 of 6 REV. 1 A4.DOC

JPM TITLE: REVIEW LIQUID RADWASTE JPM NUMBER: NRCADM061C-A4 DISCHARGE CHECKLIST.

ANSWER KEY 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 on 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:

Ve .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.

[ ] APPROVE Discharge rs .5 has PWR 0-2 aligned when PWR 0-1 should be.

i [ X ] DO NOT Approve Discharge al in rig O

NRCADM061C- Page 7 of 6 REV. 1 A4.DOC

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-A9 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: 15 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 4.4 emergency plan, including supporting or acting as emergency coordinator if required.

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

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

REV. 0

JPM TITLE: CLASSIFICATION OF A FUEL HANDLING ACCIDENT JPM NUMBER: NRCL121-A9 IN CONTAINMENT EVALUATOR W ORKSHEET 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-A9 PAGE 2 OF 4 REV. 0

JPM TITLE: CLASSIFICATION OF A FUEL HANDLING ACCIDENT JPM NUMBER: NRCL121-A9 IN CONTAINMENT EVALUATOR W ORKSHEET Start Time:

Step Expected Operator Actions 1.1 References EP G all pages of wall

1. Obtain the correct procedure.

chart provided Sat: ______ Unsat _______

Comment:

2.1 Classified the event as Alert,

2. ** Accurately classify the event.

RA2.1 **

0B Sat: ______ Unsat _______

Comment:

Classified the event < 15 min. of the Event Initiation Time. **

Classification Time: _____________

3.**

1B Classification time less than 15 minutes 3.1 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-A9 PAGE 3 OF 4 REV. 0

69-21608 (06/19/12) EP G-1 Page 1 of 1 GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Offsite dose resulting from an actual or imminent release of Offsite dose resulting from an actual or imminent release of gaseous Any unplanned release of gaseous or liquid radioactivity to the Any unplanned release of gaseous or liquid radioactivity to the gaseous radioactivity exceeds 1000 mRem TEDE or 5000 mRem radioactivity exceeds 100 mRem TEDE or 500 mRem thyroid CDE environment that exceeds 200 times the Radiological Effluent environment that exceeds two times the Radiological Effluent thyroid CDE for the actual or projected duration of the release for the actual or projected duration of the release Technical Specifications (RETS) limits for 15 minutes or longer Technical Specifications (RETS) limits for 60 minutes or longer using actual meteorology 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF RG1.1 RS1.1 RA1.1 RU1.1 Valid reading on ANY monitors that exceeds or is expected Valid reading on ANY radiation monitors that exceeds or is Valid reading on ANY LIQUID monitors > Table R-1 column Valid reading on ANY LIQUID monitors > Table R-1 column to exceed Table R-1 column "GE" for > 15 min. (Note 1) expected to exceed Table R-1 column "SAE" for > 15 min. "Alert" for > 15 min. "UE" for > 60 min.

(Note 1)

Note 1: If dose assessment results are available at the time of Note 1: If dose assessment results are available at the time of RA1.2 RU1.2 declaration, the classification should be based on dose assessment declaration, the classification should be based on dose assessment Valid reading on ANY GASEOUS monitors > Table R-1 col- Valid reading on ANY GASEOUS monitors > Table R-1 col-instead of radiation monitor readings. While necessary declarations instead of radiation monitor readings. While necessary declarations umn "UE" for > 60 min.

should not be delayed awaiting results, the dose assessment should be should not be delayed awaiting results, the dose assessment should be umn "Alert" for > 15 min.

1 initiated / completed in order to determine if the classification is initiated / completed in order to determine if the classification should be warranted. See EAL RG1.2 subsequently escalated. See EAL RS1.2 RA1.3 RU1.3 Confirmed sample analyses for gaseous or liquid releases Confirmed sample analyses for gaseous or liquid releases RG1.2 RS1.2 indicate concentrations or release rates > 2 x RETS limits for Offsite Rad indicate concentrations or release rates > 200 x RETS limits Dose assessment using actual meteorology indicates doses Dose assessment using actual meteorology indicates doses for > 15 min. > 60 min.

Conditions

> 1,000 mRem TEDE or 5,000 mRem thyroid CDE at or > 100 mRem TEDE or 500 mRem thyroid CDE at or beyond beyond the site boundary the site boundary RG1.3 RS1.3 Field survey results indicate closed window dose rates Field survey indicates closed window dose rate

> 1,000 mRem/hr expected to continue for > 1 hr, at or > 100 mRem/hr that is expected to continue for > 1 hr, at or beyond the site boundary beyond the site boundary OR OR Analyses of field survey samples indicate thyroid CDE of Field survey sample analysis indicates thyroid CDE of 5,000 mRem for 1 hr of inhalation, at or beyond the site > 500 mRem for 1 hr of inhalation at or beyond the site boundary boundary R Damage to Irradiated Fuel or Loss of Water Level that Has or Will Result in the Uncovering of Irradiated Fuel Outside the Reactor Vessel 1 2 3 4 5 6 DEF Unexpected Increase in plant radiation 1 2 3 4 5 6 DEF Abnormal RA2.1 RU2.1 Rad Damage to irradiated fuel or loss of water level that has or will Valid low water level alarm indicating uncontrolled water level Level Table R-1 Effluent Monitor Classification Thresholds result in the uncovering of irradiated fuel outside the reactor decrease in the reactor refueling cavity, spent fuel pool, or vessel resulting in a valid high alarm on ANY of the following fuel transfer canal with all irradiated fuel assemblies remain-Rad Release Point Monitor GE SAE Alert UE radiation monitors: ing covered by water Effluent - New Fuel Storage Area Rad Mon RM-59, Hi Rad AND 1(2)-RM-14/14R ----- ----- Offscale hi 8.0E+4 cpm (6.5 mR/hr) Unplanned direct area radiation monitor reading increases

- Spent Fuel Pool Area Rad Mon RM-58, Hi Rad Gaseous 2.0E-3 µCi/cc (20 mR/hr)

Plant Vent 1(2)-RM-24/24R ----- ----- 1.0E-6 µCi/cc 1.0E-8 µCi/cc - Contmt Area Mon High Rad RM-2, Hi Rad RU2.2 1(2)-RM-28/28R ----- ----- (21 mR/hr) 1.0E-5 µCi/cc 1.0E-7 µCi/cc - Containment Ventilation Exhaust Radiation Monitor Unplanned valid direct radiation area monitor reading None None increases by a factor of 1000 over normal* levels 1(2)-RM-87 3.0E-9 amps 3.0E-10 amps RM-44A/B high alarm

---

----- Normal levels may be considered as the highest reading in the past twenty four 2

(1.35E-4 µCi/cc) (24) hours excluding the current peak value 2.0E+1µCi/cc 2.0E0µCi/cc 1(2)-RM- RA2.2 71/72/73/74 A water level drop in the reactor refueling cavity, spent fuel Onsite Rad With Steam Dump or 3.0E+5 cpm 3.0E+4 cpm 3.0E+3 cpm 3.0E+2 cpm pool or fuel transfer canal that will result in irradiated fuel Main Steam one or more SRVs Conditions, becoming uncovered open on affected SG Spent Fuel Events Release of radioactive material or increases in radiation levels Oily Water Separator within the facility that impedes operation of systems required to 0-RM-3 ----- -----

Effluent 6.0E+4 cpm

• 6.0E+2 cpm

• maintain safe operations or to establish or maintain cold shutdown 1 2 3 4 5 6 DEF Liquid Liquid Radwaste 0-RM-18 ----- ----- RA2.3 Discharge Line Effluent Offscale hi

• 1.0E+5 cpm

• Valid radiation monitor readings > 15 mR/hr in areas requiring SGBD Tank Liquid continuous occupancy to maintain plant safety functions:

1(2)-RM-23 ----- -----

Effluent Offscale hi

• 2.0E+4 cpm

• Control Room (0-RM-1)

OR

• With effluent discharge not isolated Central Alarm Station (by survey)

RA2.4 Valid radiation monitor readings > 2 R/hr in the following areas requiring infrequent access to maintain plant safety functions:

- Auxiliary Building

- Fuel Handling Building

- Turbine Building

- Intake Structure Natural and destructive phenomena affecting the plant Vital Area Natural and destructive phenomena affecting the Protected Area Table H-1 Vital Areas

- Containment

- Auxiliary Building

- Fuel Handling Building

- Turbine Building

- Intake Structure EYHA1.1 1 2 3 4 5 EFM "Alert" alarm or CP M-4, "Earthquake" indicates 6

Operating Basis Earthquake (> 0.2 g on the X or Y axis or

> 0.133 g on the Z axis) exceeded HA1.2 Tornado or high winds > 80 mph (36.36 m/sec) within DEF HU1.1 1 2 3 4 5 Seismic event identified by ANY TWO of the following:

- Earthquake felt in plant

- Seismic event confirmed by PK15-24 main HU1.2 annunciator "SEISMIC INSTR SYSTEM"

- U.S. Geological Survey (USGS)

Report by plant personnel of tornado or high winds > 80 mph 6 DEF 1

Natural &

None

- RWST

- CST K

Note 2: If vehicle crash is a hostile action, see Subcategory H.4 EALs for possible classification Protected Area boundary and resulting in visible damage to ANY Table H-1 plant structures / equipment or Control Room indication of degraded performance of those systems HA1.3 Vehicle crash within Protected Area boundary and resulting in visible damage to ANY Table H-1 plant structures or equipment or control room indication of degraded performance of those (36.36 m/sec) striking within Protected Area boundary Destructive Phenomena ER systems (Note 2)

HA1.4 Turbine failure-generated missiles result in ANY visible damage to or penetration of ANY Table H-1 area HA1.5 Uncontrolled flooding in ANY Table H-1 area that results in degraded safety system performance as indicated in the HU1.3 Report of turbine failure resulting in casing penetration or damage to turbine or generator seals HU1.4 Uncontrolled flooding in ANY Table H-1 area that has the potential to affect safety related equipment needed for the SW Control Room or that creates industrial safety hazards (e.g., current operating mode electric shock) that precludes access necessary to operate or monitor safety equipment HU1.5 Hurricane warning or tsunami (actual or warning) affecting the Protected Area Fire or explosion affecting the operability of plant safety systems Fire within Protected Area boundary not extinguished within 15 required to establish or maintain safe shutdown minutes of detection 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF HA2.1 HU2.1 2 Fire or explosion resulting in EITHER: Fire in buildings or areas contiguous to ANY Table H-1 area Fire or Explosion None N Note 3: If the fire or explosion is a hostile action, see Subcategory H.4 EALs for possible classification

- Visible damage to any Table H-1 plant structures containing safety systems or components

- Control Room indication of degraded performance of systems required to establish or maintain safe shutdown (Note 3) not extinguished within 15 min. of Control Room notification or validation of a Control Room alarm (Note 3)

HU2.2 Natural and destructive phenomena affecting the Protected Area 1 2 3 4 5 6 DEF H

Hazards 3

A Release of toxic, corrosive, asphyxiant or flammable gases within or contiguous to a Vital Area which jeopardizes operation of systems required to establish or maintain safe shutdown HA3.1 1 2 3 4 5 6 DEF Report by plant personnel of an unanticipated explosion within Protected Area boundary resulting in visible damage to permanent structure or equipment (Note 3)

HU3.1 Release of toxic, corrosive, asphyxiant or flammable gases deemed detrimental to normal operation of the plant 1 2 3 4 5 Report or detection of toxic, corrosive, asphyxiant or 6 DEF Report or detection of toxic, corrosive or asphyxiant gases Toxic within or contiguous to ANY Table H-1 area in concentrations flammable gases that have entered or could enter the Owner None None and that may result in an atmosphere Immediately Dangerous to Controlled Area in amounts that can adversely affect normal Flammable Life and Health (IDLH) plant operations Gas HA3.2 HU3.2 Report or detection of gases in concentration > the Lower Recommendation by local, county or state officials to Flammability Limit within or contiguous to ANY Table H-1 area evacuate or shelter site personnel based on offsite event Hostile action resulting in loss of physical control of the facility Hostile action within the Protected Area Hostile action within the Owner Controlled Area Confirmed security condition or threat which indicates a potential or airborne attack threat degradation in the level of safety of the plant 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF HG4.1 HS4.1 HA4.1 HU4.1 A hostile action has occurred such that plant personnel are A hostile action is occurring or has occurred within the A hostile action is occurring or has occurred within the A security condition that does not involve a hostile action as 4 unable to operate equipment required to maintain safety functions OR Protected Area as reported by the Security Watch Commander Owner Controlled Area as reported by the Security Watch Commander OR reported by the Security Watch Commander OR A credible site-specific security threat notification Security A hostile action has caused: A valid notification from NRC of an airliner attack threat OR Failure of Spent Fuel Cooling systems within 30 min. of the site A valid notification from NRC providing information of an AND aircraft threat Imminent fuel damage is likely for a freshly off loaded reactor core in pool Control Room evacuation has been initiated and plant control cannot Control Room evacuation has been initiated be established 5 None HS5.1 1 2 3 4 5 6 DEF HA5.1 1 2 3 4 5 6 DEF None Control Control Room evacuation has been initiated Entry into OP AP 8A, Control Room Inaccessibility, for Room AND Control Room evacuation Evacuation Control of the plant cannot be established per OP AP-8A, Control Room Inaccessibility, within 15 min.

Other conditions existing which in the judgment of the SM/SEC/ED Other conditions existing which in the judgment of the SM/SEC/ED Other conditions existing which in the judgment of the SM/SEC/ED Other conditions existing which in the judgment of the SM/SEC/ED warrant declaration of General Emergency warrant declaration of Site Area Emergency warrant declaration of an Alert warrant declaration of a UE 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF HG6.1 HS6.1 HA6.1 HU6.1 6 Other conditions exist which in the judgment of the SM/SEC/ED indicate that events are in process or have Other conditions exist which in the judgment of the SM/SEC/ED indicate that events are in progress or have Other conditions exist which in the judgment of the SM/SEC/ED indicate that are in progress or have occurred Other conditions exist which in the judgment of the SM/SEC/ED indicate that events are in progress or have occurred which involve actual or imminent substantial core occurred which involve an actual or likely major failures of which involve an actual or potential substantial degradation occurred which indicate a potential degradation of the level of Judgment degradation or melting with potential for loss of containment plant functions needed for protection of the public. ANY of the level of safety of the plant. ANY releases are expected safety of the plant. No releases of radioactive material integrity or security events that result in an actual loss of releases are not expected to result in exposure levels which to be limited to small fractions of the EPA Protective Action requiring offsite response or monitoring are expected unless physical control of the facility. Releases can be reasonably exceed EPA Protective Action Guideline exposure levels (1 Guideline exposure levels (1 Rem TEDE and 5 Rem thyroid further degradation of safety systems occurs expected to exceed EPA Protective Action Guideline Rem TEDE and 5 Rem thyroid CDE) beyond the site CDE) exposure levels (1 Rem TEDE and 5 Rem thyroid CDE) boundary offsite for more than the site boundary Damage to a loaded cask confinement boundary Table E-1 ISFSI Events/Conditions Mode applicability is N/A for ISFSI E

Natural Phenomena Accidents EU1.1

- High wind - Cask drop - Vehicle impact Damage to a loaded cask confinement boundary as None - Tornado - Cask tip-over - Airborne missile indicated by EITHER:

- Earthquake - Cask air inlet/outlet - Transmission tower Occurrence of ANY Table E-1 event/condition ISFSI - Lightning strike blockage collapse OR

- Fire - 500kV transmission Beyond normal ISFSI radiation reading

- Explosion line drop Diablo Canyon Power Plant Emergency Action Level Wall Chart 1 2 3 4 5 6 DEF Mode key: Power Operation Startup Hot Standby Hot Shutdown Cold Shutdown Refueling Defueled Sheet 1 of 3 Modes: ALL Revision Date: 6/19/12

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A9 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-A9 PAGE 4 OF 4 REV. 0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: LJE017 Title: CLASSIFICATION OF A FUEL HANDLING ACCIDENT IN CONTAINMENT Examinee:

Evaluator:

Testing Method: Perform Print X Simulate on Signature Date Results:

Comments:

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

rs i

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:

Time Critical:

al Yes Yes X No No X

in Time Allotment:

Critical Steps:

Job Designation:

15 minutes 2, 3 SRO/STA rig Rev Comments/TIPs:

DCPP Task # / Rating:

Gen KA # / Rating:

SAPN 50304333; TIPs 21257-91 145400 GEN.2.4.38 4.5 / 4.0 4.4 (SRO)

OAUTHOR:

APPROVED BY:

JOHN F. BUCKLEY JOHN BECERRA DATE:

DATE:

10/18/2010 10/23/2010 TRAINING SUPERVISOR APPROVED BY: ERIK WERNER DATE: 12/06/2010 LINE MANAGER REV. 1B

JPM TITLE: CLASSIFICATION OF A FUEL HANDLING JPM NUMBER: LJE017 ACCIDENT IN CONTAINMENT 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.

Required Materials: *

• EP G-1, and EAL Wall Charts.

on 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.

Initial Conditions:

GIVEN:

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

• Unit 1 is REFUELING. Core off-loading is in progress and rs containment closure has been established

• The fuel handling crew in containment has just reported seeing i

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:

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

in 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 rig (21 mr/hr)

O LJE017.DOC PAGE 2 OF 4 REV. 1B

JPM TITLE: CLASSIFICATION OF A FUEL HANDLING JPM NUMBER: LJE017 ACCIDENT IN CONTAINMENT INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 References EP G-1.

• • 2. Accurately classify the event. 2.1 on Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

Classifies the event as Alert, RA2.1 **

Ve Classification made: _______________

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

rs i Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat) 3.1 Classifies the event < 15 min. of the Event Initiation Time. **

Classification Time: _____________

al Event Initiation Time: _____________

(Event initiation time is JPM Start Time)

Difference: ____________ min**

in Step was: Sat: ______ Unsat _______*

rig Stop Time:

[ ] Comment # (required for Unsat)

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

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

LJE017.DOC PAGE 3 OF 4 REV. 1B

JPM NUMBER: LJE017 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 on 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:

Ve The Shift Manager has directed you to classify the event rs i al in rig O

LJE017.DOC PAGE 4 OF 4 REV. 1B

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE sNumber: NRCL121-S1 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: 15 minutes Critical Steps: 2 Job Designation: RO or SRO Rev Comments: Bank LJC-066 Gen KA / Rating: 001 A2.03 - Ability to (a) predict the impacts of the following 3.5/4.2 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 AUTHOR: LISA TORIBIO DATE: 06/20/2014 OPERATIONS ABDUL KADIR DATE: 06/20/2014 REPRESENTATIVE:

REV. 0

JPM TITLE: VERIFY MISALIGNED ROD IS NOT STUCK JPM NUMBER: NRCL121-S1 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-S1 PAGE 2 OF 6 REV. 0

JPM TITLE: VERIFY MISALIGNED ROD IS NOT STUCK JPM NUMBER: NRCL121-S1 EVALUATOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 Obtained copy of OP AP-12B Sat: ______ Unsat _______

Comment:

Step 14.a - Verify Misaligned Rod NOT 2.1

2. Read three CAUTIONS prior to step 14.a STUCK - check CBD group counters 2.2 Checked both groups of bank D at the same step as the demand counter Step 14.b - Record bank step counters 2.3 Recorded ALL bank demand positions (all banks)

Step 14.c - Rotate Rod Bank Selector 2.4 Rotated Rod Bank Selector switch to Control

• • Switch to AFFECTED Bank Bank D (CBD) **

Note: Operator may call up the CBD Step 14.d - Record PPC postion for the address listed in App. B of AP-12B Bank (U0052), or record the value from an existing PPC group display.

Displayed the Control Bank D position 2.5 from the plant computer and records the value.

Step 14.e - Drive the affected bank in Inserted rods for Control Bank D until a

• • several steps (enough to see a DRPI 2.6 DRPI change is observed **

change)

Checked that rod K2 moves and diagnosed Step 14.f - Check misaligned rod DRPI 2.7 that rod K2 is not stuck. **

• • position changes with bank position.

(must verbalize to examiner or SFM)

Step 14. G - g. Return the rods in the Withdrew Control Bank D until the bank

• • affected bank to the step counter position 2.8 was restored to its previously recorded recorded in Step 14.b position **

Sat: ______ Unsat _______

Comment:

NRCL121-S1 PAGE 3 OF 6 REV. 0

JPM TITLE: VERIFY MISALIGNED ROD IS NOT STUCK JPM NUMBER: NRCL121-S1 EVALUATOR WORKSHEET Stop Time:

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

Follow up Question Documentation:

Question: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

Response: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

NRCL121-S1 PAGE 4 OF 6 REV. 0

JPM Title: VERIFY MISALIGNED ROD IS NOT STUCK JPM Number: NRCL121-S1 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-S1 PAGE 5 OF 6 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-S1 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-S1 PAGE 6 OF 6 REV. 0

• • • UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***

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 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 symptoms 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 a. Align each group in the bank to the same BANK - AT THE SAME STEP ON demanded step DEMAND STEP COUNTER 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 Grp 2 Steps 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 OP_AP-12Bu3r14.DOC 02 0907.0956

• • • UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***

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 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 f. Contact Reactor Engineering Group for changes with bank position. 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 OP_AP-12Bu3r14.DOC 02 0907.0956

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: LJC-066 Title: VERIFY MISALIGNED ROD IS NOT STUCK Examinee:

Evaluator:

Testing Method: Perform Print Simulate on Signature Date Results:

Comments:

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

References:

rs i OP AP-12B, Control Rod Misalignment, Rev. 14B Alternate Path: Yes No X Time Critical:

Time Allotment:

al Yes 15 minutes No X in Critical Steps:

Job Designation:

Rev Comments/TIPs:

4, 6, 7 RO/SRO SAPN 50304333; TIPs 20669-33, 21256-43 rig DCPP Task # / Rating:

Gen KA # / Rating:

EC revision 24C was for Simulator terminology changes.

EC approved by LOB supervisor.

80200 001.A2.03 4.0 3.5 / 4.2 OAUTHOR:

APPROVED BY:

JOHN F. BUCKLEY JOHN BECERRA DATE:

DATE:

09/13/2010 09/19/2010 TRAINING SUPERVISOR APPROVED BY: KEN JOHNSTON DATE: 09/27/2010 LINE MANAGER REV. 24B

JPM TITLE: VERIFY MISALIGNED ROD IS 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 Required Materials:

Initial Conditions:

None on appropriate procedure for the task, the examinee may be given the procedure and told the step with which to begin.

Unit 1 is at approximately 75% power and was in the process of being Ve 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 Initiating Cue:

implemented.

rs The Shift Foreman directs you to verify that the misaligned rod is not i

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 al reported the Shift Foreman.

in rig O

LJC066.DOC PAGE 2 OF 6 REV. 24B

JPM TITLE: VERIFY MISALIGNED ROD IS 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 _______*

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

2.1 2.2 on

[ ] Comment # (required for Unsat)

Reads CAUTIONS prior to Step 14.a.

Checks both groups of bank D at the Ve same step as the demand counter.

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

3. Record the bank step counter shutdown banks. rs i position for all control banks and 3.1 Records the bank demand positions.

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

• • 4. Place the bank selector to the 4.1 Turns the ROD BANK/MODE al affected bank. SELECT switch to the CBD position. **

Step was: Sat: ______ Unsat _______*

in [ ] Comment # (required for Unsat) rig O

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

LJC066.DOC PAGE 3 OF 6 REV.24B

JPM TITLE: VERIFY MISALIGNED ROD IS NOT STUCK JPM NUMBER: LJC-066 INSTRUCTOR WORKSHEET Step Expected Operator Actions

5. Record the plant process computer 5.1 Displays the Control Bank D position position for the affected bank. from the plant computer and records the value.

on 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.

Ve

• • 6. Drive the affected bank in several Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat) 6.1 Inserts rods for Control Bank D until steps (enough to see a DRPI change).

rs i a DRPI change is observed. **

6.2 Checks that rod K2 moves and 6.3 diagnoses that rod K2 is not stuck. **

(must verbalize to examiner or SFM)

Reports status to Shift Foreman.

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

Step was: Sat: ______ Unsat _______*

in

• • 7. Return the rods in the affected bank to the position recorded in

[ ] Comment # (required for Unsat) 7.1 Withdraws Control Bank D until the bank is restored to its previously rig OP AP-12B, Step 14.a. recorded position. **

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

O 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 REV.24B

JPM TITLE: VERIFY MISALIGNED ROD IS 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 on Place Rod Control Switch to Manual after simulator goes to freeze.

Inform the examiner that the simulator setup is complete.

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

rs i al in rig O

LJC066.DOC PAGE 5 OF 6 REV.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 Initiating Cue:

implemented.

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

Ve rs i al in rig O

LJC066.DOC PAGE 6 OF 6 REV.24B

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-S2 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: 10 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 4.5/4.8 control room: ESFAS-initiated equipment which fails to actuate AUTHOR: LISA TORIBIO DATE: 06/20/2014 OPERATIONS ABDUL KADIR DATE: 06/20/2014 REPRESENTATIVE:

REV. 0

JPM TITLE: MANUALLY ISOLATE PHASE A COMPONENTS - JPM NUMBER: NRCL121-S2 TRAIN A & B FAILURES 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-S2 PAGE 2 OF 7 REV. 0

JPM TITLE: MANUALLY ISOLATE PHASE A COMPONENTS - JPM NUMBER: NRCL121-S2 TRAIN A & B FAILURES 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:

Observed the following on the CONTAINMENT ISOLATION PHASE A 2.1 portion of Monitor Light Box B:

2. Step 3 - Ensure Phase A actuated

• 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:

Note: Operator may manually actuate PHASE A Isolation, but this will Step 3 RNO - Manually close Phase A not work. Alignment steps (as

3. valves with White Status lights ON 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.

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

Sat: ______ Unsat _______

Comment:

NRCL121-S2 PAGE 3 OF 7 REV. 0

JPM TITLE: MANUALLY ISOLATE PHASE A COMPONENTS - JPM NUMBER: NRCL121-S2 TRAIN A & B FAILURES EVALUATOR WORKSHEET Step Expected Operator Actions Closed each open Containment Isolation Phase A valve on VB-1. **

Step 3 RNO (continued) - Close valves 4.1

• 9355A/B 4.** on VB1

• 9356A/B

• 8880 Verified that each Containment Isolation 4.2 Phase A valve has closed (Red light OFF, Green light ON, and/or white light OFF on MLB).

Sat: ______ Unsat _______

Comment:

Closed each open Containment Isolation Phase A valve on VB-2. **

• 8149C

• RW isolations IC and OC Step 3 RNO (continued) - Close valves 5.1

• 8152 5.** on VB2

• 8045

• 8029

• 8100

• 8112 Verified that each Containment Isolation 5.2 Phase A valve has closed (Red light OFF, Green light ON, and/or white light OFF on MLB).

Sat: ______ Unsat _______

Comment:

NRCL121-S2 PAGE 4 OF 7 REV. 0

JPM TITLE: MANUALLY ISOLATE PHASE A COMPONENTS - JPM NUMBER: NRCL121-S2 TRAIN A & B FAILURES EVALUATOR WORKSHEET Step Expected Operator Actions Closed open Containment Isolation Phase Step 3 RNO (continued) - Close valves 6.1 A valve on VB-3. **

6.**

on VB3

• FCV-633 Verified that each Containment Isolation 6.2 Phase A valve has closed (Red light OFF, Green light ON, and/or white light OFF on MLB).

Sat: ______ Unsat _______

Comment:

Closed open Containment Isolation Phase Step 3 RNO (continued) - Close valves 7.1 A valve on VB-3. **

7.** on VB4

• FCV-584 Verified that each Containment Isolation 7.2 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-S2 PAGE 5 OF 7 REV. 0

JPM TITLE: MANUALLY ISOLATE PHASE A COMPONENTS - JPM NUMBER: NRCL121LJC-S2 TRAIN A & B FAILURES 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-S2 PAGE 6 OF 7 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-S2 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-S2 PAGE 7 OF 7 REV. 0

• • • UNCONTROLLED DOCUMENT - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***

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 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 b. Open Main Gen Output Bkrs 532 and 632.

1. Green lights - ON IF Either breaker will NOT open, OR THEN Notify GCC Diablo Control (8-449-6717) to isolate Unit 1 at the

2. Turbine speed - LOWERING 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: Perform the following:

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

4. ENSURE Containment Vent Isol: Perform the following:

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

EOP_E-0u1r43.DOC 03A 1220.0812

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:

Testing Method: Perform Print Simulate on Signature Date Results:

Comments:

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

rs i

References:

EOP E-0, Reactor Trip or Safety Injection, Rev 43 Alternate Path: Yes X No Time Critical:

Time Allotment:

al Yes 10 minutes No X in Critical Steps:

Job Designation:

3, 4, 5, 6 RO/SRO rig Rev Comments/TIPs:

DCPP Task # / Rating:

Gen KA # / Rating:

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.

197200 013.A4.01 4.3 4.5 / 4.8 OAUTHOR:

REVIEWED BY:

ORRIN OLIVER/LISA TORIBIO

.

DATE:

DATE:

04/24/14

.

TRAINING SUPERVISOR APPROVED BY: . DATE: .

LINE MANAGER REV. 30

JPM TITLE: MANUALLY ISOLATE PHASE A COMPONENTS - JPM NUMBER: LJC-026 TRAIN A & B FAILURES 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.

Required Materials:

on 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.

Provide a copy of the reference procedure (partial procedure allowed), if Initial Conditions:

Ve the task is being done in the plant or lab.

A Unit 1 reactor trip and safety injection has occurred.

Initiating Cue:

Task Standard:

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

i NOTE: Do NOT provide the student with the 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.

al in rig O

LJC026.DOC PAGE 2 OF 8 REV. 30

JPM TITLE: MANUALLY ISOLATE PHASE A JPM NUMBER: LJC-026 COMPONENTS - TRAIN A & B FAILURES INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 References EOP E-0, Appendix E, Step 3.

2. Ensure Containment Isolation 2.1 on Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

Observes the following on the Phase A.

Ve CONTAINMENT ISOLATION PHASE A portion of Monitor Light Box B:

Train A red activate light - OFF rs i Train B red activate light - OFF White status lights - OFF Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat) al in rig O

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

LJC026.DOC PAGE 3 OF 8 REV. 30

JPM TITLE: MANUALLY ISOLATE PHASE A JPM NUMBER: LJC-026 COMPONENTS - TRAIN A & B FAILURES INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 3. Manually aligns Phase A Note: Operator may manually actuate equipment on VB-1 PHASE A Isolation, but this will not work. Alignment steps (as well as the vales themselves) that follow 3.1 3.2 on may be performed in any order.

Turns the Phase A actuation switch to ACTUATE. (optional)

Positions the MONITOR LIGHT Ve 3.3 TEST switch to TEST.

Identifies open Phase A Isol valves using the CONTAINMENT rs i 3.4 ISOLATION PHASE A portion of Monitor Light Box B or Control Board switch indications.

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

• 9355A/B

• 9356A/B

• 8880 al 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).

in Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat) rig O

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

LJC026.DOC PAGE 4 OF 8 REV. 30

JPM TITLE: MANUALLY ISOLATE PHASE A JPM NUMBER: LJC-026 COMPONENTS - TRAIN A & B FAILURES INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 4. Manually aligns Phase A 4.1 Identifies open Phase A Isol valves equipment on VB-2 using the CONTAINMENT ISOLATION PHASE A portion of Monitor Light Box B or Control 4.2 on Board switch indications.

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

• 8149C

• RW isolations IC and OC Ve

• 8152

• 8045

• 8029 rs i 4.3

• 8100

• 8112 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 _______*

al

• • 5. Manually aligns Phase A equipment on VB-3

[ ] Comment # (required for Unsat) 5.1 Identifies open Phase A Isol valves using the CONTAINMENT ISOLATION PHASE A portion of in 5.2 Monitor Light Box B or Control Board switch indications.

Closes each open Containment rig 5.3 Isolation Phase A valve on VB-3. **

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

O 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 REV. 30

JPM TITLE: MANUALLY ISOLATE PHASE A JPM NUMBER: LJC-026 COMPONENTS - TRAIN A & B FAILURES INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 6. Manually aligns Phase A 6.1 Identifies open Phase A Isol valves equipment on VB-4 using the CONTAINMENT ISOLATION PHASE A portion of Monitor Light Box B or Control 6.2 6.3 on Board switch indications.

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

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

rs i 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:

al (Enter total time on the cover page) in rig O

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

LJC026.DOC PAGE 6 OF 8 REV. 30

JPM TITLE: MANUALLY ISOLATE PHASE A COMPONENTS - JPM NUMBER: LJC-026 TRAIN A & B FAILURES ATTACHMENT 1, SIMULATOR SETUP Restore the simulator to IC-10 (100%, MOL).

Enter Lesson Drill file 1026 or manually insert the following:

Command insert MAL_PPL1A 2 insert MAL_PPL1B 2 insert MAL_PPL2A 1 on Description Phase A Failure Train A/ B Inadvertent S1 Actuation Train A insert MAL_PPL2B 1 Ve delIA MAL_PPL2A 2 delay=2 delIA MAL_PPL2B 2 delay=2

rs RUN, then FRZ after 40 seconds Runs simulator.

Inform the examiner that the simulator setup is complete.

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

al in rig O

LJC026.DOC PAGE 7 OF 8 REV. 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.

on Ve rs i al in rig O

LJC026.DOC PAGE 8 OF 8 REV. 30

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-S3 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: 25 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 4.3/4.5 they apply to a Station Blackout: Restoration of power from offsite AUTHOR: LISA TORIBIO DATE: 06/20/2014 OPERATIONS ABDUL KADIR DATE: 06/20/2014 REPRESENTATIVE:

REV. 0

JPM TITLE: ENERGIZE VITAL BUSES FROM THE 230KV SYSTEM JPM NUMBER: NRCL121-S3 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-S3 PAGE 2 OF 9 REV. 0

JPM TITLE: ENERGIZE VITAL BUSES FROM THE 230KV SYSTEM JPM NUMBER: NRCL121-S3 EVALUATOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 References ECA-0.3, step 2 Sat: ______ Unsat _______

Comment:

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

2.** power Placed ALL (7) 4KV and 12KV auto-2.2 transfer relay cutout switches in CUTOUT.

2.3 Pressed ALL (7) auto-transfer relay reset PBs to reset auto transfer relays. **

2.4 Verified all (7) auto transfer relay blue lights OUT.

2.5 Placed all Condensate/Booster Pump Selector Switches in MANUAL.

2.6 Read Caution prior to verifying 4 and 12 kV breakers open 2.7 Verified that ALL 4kV and 12 kV Aux and S/U Fdr Bkrs are OPEN .

Sat: ______ Unsat _______

Comment:

3.1 Observed that SI signal is not present - may

3. Step 3 - Verify SI Reset reset SI again Sat: ______ Unsat _______

Comment:

NRCL121-S3 PAGE 3 OF 9 REV. 0

JPM TITLE: ENERGIZE VITAL BUSES FROM THE 230KV SYSTEM JPM NUMBER: NRCL121-S3 EVALUATOR WORKSHEET Step Expected Operator Actions 4.1 Checked the status of 500KV power (may 4.** Step 4 - Check 500 kV available 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 Continued to next step per step 4 RNO.

Comment:

5.1 Checked status of CB-212 (visual check at

5. Step 5 - Check 230 kV available VB-5, and/or phone call).

Cue: (from SM) 230KV power is stable, and CB-212 is closed.

Observed that S/U transformer power 5.2 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-S3 PAGE 4 OF 9 REV. 0

JPM TITLE: ENERGIZE VITAL BUSES FROM THE 230KV SYSTEM JPM NUMBER: NRCL121-S3 EVALUATOR WORKSHEET Step Expected Operator Actions Observed that U-2 S/U crosstie is 6.** Step 5.b RNO - close VU-11 6.1 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.

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

6.3 Observed that S/U Transformer 1-2 feeder Step 5.d VU-14 is CLOSED.

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

Comment:

NRCL121-S3 PAGE 5 OF 9 REV. 0

JPM TITLE: ENERGIZE VITAL BUSES FROM THE 230KV SYSTEM JPM NUMBER: NRCL121-S3 EVALUATOR WORKSHEET Step Expected Operator Actions

Cue: The SFM reports that all ESF 7.** Step 5.f - Energize 4 kV Vital buses 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 REV. 0

JPM Title: ENERGIZE VITAL BUSES FROM THE 230KV JPM Number: NRCL121-S3 SYSTEM Attachment 1, Simulator Setup Initialize the simulator to IC-10 (100%, MOL).

Enter lesson file NRCL121-LJCS3.lsn:

A (Continued on Next Page)

NRCL121-S3 PAGE 7 OF 9 REV. 0

JPM Title: ENERGIZE VITAL BUSES FROM THE 230KV JPM Number: NRCL121-S3 SYSTEM , Simulator Setup (Continued from Previous Page)

A NRCL121-S3 PAGE 8 OF 9 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-S3 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-S3 PAGE 9 OF 9 REV. 0

• • • UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR PACIFIC GAS AND ELECTRIC COMPANY USE *** NUMBER EOP ECA-0.3 DIABLO CANYON POWER PLANT REVISION 17 PAGE 2 OF 29 TITLE: Restore 4kV Buses UNIT 1 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 GO TO Step 2 (Next Page)

Bus - AVAILABLE:

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 EOP_ECA-0!3u1r17.DOC 03A 1220.0725

• • • UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR PACIFIC GAS AND ELECTRIC COMPANY USE *** NUMBER EOP ECA-0.3 DIABLO CANYON POWER PLANT REVISION 17 PAGE 3 OF 29 TITLE: Restore 4kV Buses UNIT 1 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 EOP_ECA-0!3u1r17.DOC 03A 1220.0725

• • • UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR PACIFIC GAS AND ELECTRIC COMPANY USE *** NUMBER EOP ECA-0.3 DIABLO CANYON POWER PLANT REVISION 17 PAGE 4 OF 29 TITLE: Restore 4kV Buses UNIT 1 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 EOP_ECA-0!3u1r17.DOC 03A 1220.0725

• • • UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR PACIFIC GAS AND ELECTRIC COMPANY USE *** NUMBER EOP ECA-0.3 DIABLO CANYON POWER PLANT REVISION 17 PAGE 5 OF 29 TITLE: Restore 4kV Buses UNIT 1 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

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

Unit

a. Check OCB-212 closed a. GO TO Step 6 (Next Page)

OR Request GCC Diablo Control (8-449-6717) to close 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 b. IF Unit 2 Startup Bus 2-1 is energized available white status light - ON (VB5)

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 EOP_ECA-0!3u1r17.DOC 03A 1220.0725

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:

AR PK01-21, CONTMT FAN CLRS, Rev. 14

References:

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, 4.2 / 4.1 or response procedures.

AUTHOR: DATE:

OPERATIONS REPRESENTATIVE: DATE:

REV. 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 inspection

• 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 References OP H-2:I, Section 6.4, 0B 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 Verified SPEED SELECT switch for CFCU is selected to LOW.

2.3 Depressed switch to start fan.

2.4 Checked that fan current stabilizes.

2.5 Attempted reset of PK01-21 caused by high vibration 2.6 Implemented 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 3.1 Confirmed high vibration condition on High Vibration. 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 - Shuts 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 (Enter total time on the cover page)

Time:

• • 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.

NRCL121-S4.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 inspection 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.

NRCL121-S4.DOCX PAGE 7 OF 7 REV. 0

Containment Fan Cooler Units - Make Available OP H-2:I R34 and System Operation Page 15 of 18 UNIT 1 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".

OP_H-2~Iu1r34.DOC 0507.1056

Containment Fan Cooler Units - Make Available OP H-2:I R34 and System Operation Page 16 of 18 UNIT 1

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."

OP_H-2~Iu1r34.DOC 0507.1056

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

1 D IABLO C ANYON P OWER P LANT AR PK01-21 ANNUNCIATOR RESPONSE Rev. 14 UNIT Page 1 of 6 CONTMT FAN CLRS 09/30/10 Effective Date QUALITY RELATED

1. ALARM INPUT DESCRIPTION INPUT PRINTOUT/DETAILS DEVICE SETPOINT STEP 149 Contmt Fan Clr 1-1 OC Trip 49X-1F-2 Hi 447 amps 2.2 Lo 267 amps 150 Contmt Fan Clr 1-2 OC Trip 49X-1F-1 Hi 447 amps 2.2 Lo 267 amps 228 Contmt Fan Clr 1-3 OC Trip 49X-1G-1 Hi 447 amps 2.2 Lo 267 amps 229 Contmt Fan Clr 1-5 OC Trip 49X-1G-2 Hi 447 amps 2.2 Lo 267 amps 300 Contmt Fan Clr 1-4 OC Trip 49X-1H-1 Hi 447 amps 2.2 Lo 267 amps 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)

AR_PK01-21u1r14.DOC 0920.1316

CONTMT FAN CLRS AR PK01-21 R14 Page 2 of 6 UNIT 1 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 T1065A Temp Contmt Fan Mtr 1-1 0-Bd Brg T1066A Temp 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 T1069A Temp Contmt Fan Mtr 1-2 Inbd Brg T1070A Temp Contmt Fan Mtr 1-2 0-Bd Brg T1071A Temp 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 T1074A Temp

` Contmt Fan Mtr 1-3 Inbd Brg T1075A Temp Contmt Fan Mtr 1-3 0-Bd Brg T1076A Temp 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 T1079A Temp Contmt Fan Mtr 1-4 Inbd Brg T1080A Temp Contmt Fan Mtr 1-4 0-Bd Brg T1081A Temp 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 T1084A Temp Contmt Fan Mtr 1-5 Inbd Brg T1085A Temp Contmt Fan Mtr 1-5 0-Bd Brg T1086A Temp 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 T1089A Temp (Continued)

AR_PK01-21u1r14.DOC 0920.1316

CONTMT FAN CLRS AR PK01-21 R14 Page 3 of 6 UNIT 1 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_PK01-21u1r14.DOC 0920.1316

CONTMT FAN CLRS AR PK01-21 R14 Page 4 of 6 UNIT 1 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_PK01-21u1r14.DOC 0920.1316

CONTMT FAN CLRS AR PK01-21 R14 Page 5 of 6 UNIT 1 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_PK01-21u1r14.DOC 0920.1316

CONTMT FAN CLRS AR PK01-21 R14 Page 6 of 6 UNIT 1

5. LOGIC DIAGRAM AR_PK01-21u1r14.DOC 0920.1316

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121LJC-S5 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:

AR PK11-21, High Radiation, Rev. 31

References:

OP AP-11, Malfunction of Component Cooling Water System, Rev 31.

Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 15 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 3.9 / 3.9 control room: effluent release AUTHOR: DATE:

OPERATIONS REPRESENTATIVE: DATE:

REV. 0

JPM TITLE: RESPOND TO HIGH RADIATION ON RE-17A/B JPM NUMBER: NRCL121LJC-S5 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.

• PK11-21 has just alarmed Initiating Cue: The Shift Foreman directs you to respond to the alarm per AR PK11-21, High Radiation, step 2.4.

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

Task Standard: RCV-16 closed in accordance with AR PK11-21.

NRCL121-S5.DOCX PAGE 2 OF 7 REV. 0

JPM TITLE: RESPOND TO HIGH RADIATION ON RE-17A/B JPM Number: NRCL121LJC-S5 INSTRUCTOR WORKSHEET Start Time:

Step Standards

1. 1. Step 2.4.1 - Identify process 1.1 Read NOTE prior to step 2.4.1.

monitors in alarm.

1.2 Observed 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 process monitors in alarm Step was: Sat: ______ Unsat _______

Comments:

• • Denotes a Critical Step.

NRCL121-S5.DOCX PAGE 3 OF 7 REV.0

JPM TITLE: RESPOND TO HIGH RADIATION ON RE-17A/B JPM Number: NRCL121LJC-S5 INSTRUCTOR WORKSHEET Step Standards

3. ** Step 2.4.3 - Ensure appropriate 0B Note: May have already completed this automatic action has occurred action based on RE-17A/B alarm condition.

3.1 Noted 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.

NRCL121-S5.DOCX PAGE 4 OF 7 REV.0

JPM TITLE: RESPOND TO HIGH RADIATION ON RE-17A/B JPM Number: NRCL121LJC-S5 INSTRUCTOR WORKSHEET Followup Question Documentation:

Question: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

Response: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

NRCL121-S5.DOCX PAGE 5 OF 7 REV.0

JPM TITLE: RESPOND TO HIGH RADIATION ON 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.

NRCL121-S5.DOCX PAGE 6 OF 7 REV.0

EXAMINEE CUE SHEET JPM Number: NRCL121LJC-S5 Initial Conditions: Given:

• Unit 1 is at 100% power.

• PK11-21 has just alarmed Initiating Cue: The Shift Foreman directs you to respond to the alarm per AR PK11-21, High Radiation, step 2.4.

NRCL121-S5.DOCX PAGE 7 OF 7 REV.0

HIGH RADIATION AR PK11-21 R31 Page 4 of 8 UNIT 1 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_PK11-21u1r31.DOC 0809.0613

HIGH RADIATION AR PK11-21 R31 Page 7 of 8 UNIT 1 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 AR_PK11-21u1r31.DOC 0809.0613

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121LJCS6 Title: INITIATE A NATURAL CIRCULATION COOLDOWN Examinee:

Evaluator:

Print Signature Date Testing Method: Perform Simulate Results: Sat Unsat Total Time: minutes Comments: RO Only

References:

EOP E0.2, Natural Circulation Cooldown, Rev. 26 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 20 minutes (average validation time ___ min)

Critical Steps: 4 Job Designation: RO Rev Comments/TIPs: LJC046 Gen KA # / Rating: 002.A4.02 Ability to manually operate and/or monitor in the 4.3 control room: Indications necessary to verify natural circulation from appropriate level, flow, and temperature indications and valve positions upon loss of forced circulation AUTHOR: DATE:

OPERATIONS REPRESENTATIVE: DATE:

REV. 0

JPM TITLE: INITIATE A NATURAL CIRCULATION COOLDOWN JPM NUMBER: NRCL121LJC-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. 26 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 565°F (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 (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 Actions

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 Checked steam release capabilities of all S/Gs available.

2.2 Checked feed flow available to all S/Gs.

Step was: Sat: ______ Unsat _______

Comments:

3. Step 10.b - Establish Cooldown 3.1 Noted that C/D rate is limited to 25°F/hr.

3.2 Observed 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.** Step 10.b RNO - Initiate cooldown, using 0B Note: The 10%ers are already in AUTO, 10% steam dumps, at < 25°F/hr 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 the 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 Established 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 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) 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 565°F (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 (page 6) .

nrcl121-s6.docx PAGE 7 OF 7 REV. 0

• • • UNCONTROLLED DOCUMENT - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***

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 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 1) IF Feedwater to inactive loop(s) NOT AVAILABLE 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 -

EOP_E-0!2u1r27.DOC 03A 0306.1257

• • • UNCONTROLLED DOCUMENT - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***

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 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

10. INITIATE RCS Cooldown To Cold Shutdown: (Continued)

b. Establish LESS THAN a 25°F/hr b. Perform the following:

COOLDOWN RATE by dumping steam to the condenser:

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) TAVG - 543°F

2) PK08-07, LO-LO TAVG PERMISSIVE P ON a) Place Train A AND B Steam Dump Control in Bypass Intlk b) Ensure PK07-05 STM DUMP CONTROL BYPASS - ON EOP_E-0!2u1r27.DOC 03A 0306.1257

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: LJC-046 Title: INITIATE A NATURAL CIRCULATION COOLDOWN Examinee:

Evaluator:

Testing Method: Perform Print Simulate on Signature Date Results:

Comments:

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

References:

rs i EOP E-0.2, Natural Circulation Cooldown, Rev. 26 Alternate Path: Yes No X Time Critical:

Time Allotment:

Critical Steps:

al Yes 20 minutes 4

No X in Job Designation:

Rev Comments/TIPs:

RO/SRO TIP 22360-01; updated to do on 10%ers, vs HC-507 (since stm dumps would rig DCPP Task # / Rating:

Gen KA # / Rating:

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.

896800 E09.EA1.2 4.0 3.6 / 3.9 OAUTHOR:

REVIEWED BY:

JOHN F. BUCKLEY JOHN BECERRA DATE: 03/08/2012 03/09/2012 TRAINING SUPERVISOR APPROVED BY: KEN JOHNSTON DATE: 03/12/2012 LINE MANAGER REV. 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 Required Materials:

told what step to begin the task at.

on being done in the plant or lab, and after identifying the appropriate procedure for the task, the examinee may be given the procedure and Provide a copy of the reference procedure (partial procedure allowed), if the task is being done in the plant or lab.

Initial Conditions: Given:

Ve

• Unit 1 has tripped from 100% power.

• EOP E-0.1, Reactor Trip Response, is complete; RCPs are not available.

rs

• EOP E-0.2 has been performed up to and including Step 9.

i

• 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 565°F (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 al in accordance with EOP E-0.2, Step 10.

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

in 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).

rig O

LJC046.DOC PAGE 2 OF 7 REV. 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.

2. Check status of all S/Gs.

1.3 Reads NOTE.

on Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat) 2.1 Checks steam release capabilities of all Ve S/Gs are available.

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

rs i 2.3 Notes that C/D rate is limited to 25°F/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.

al Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat) in rig O

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

LJC046.DOC PAGE 3 OF 7 REV. 17

JPM TITLE: INITIATE A NATURAL CIRCULATION COOLDOWN JPM NUMBER: LJC-046 INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 4. Initiates cooldown, using 10% Note: The 10%ers are already in steam dumps, at < 25°F/hr AUTO, maintaining temperature under load; it will only take a few percent increase in demand to on 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 Ve should be throttled back. Once the examinee has demonstrated that he/she can control the rate rs i 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 (< 25°F/hr). **

4.2 PCV-20 is taken to MANUAL (by pressing the MAN PB), and the al raise/lower PBs are used to attain a slow cooldown (< 25°F/hr). **

4.3 PCV-21 is taken to MANUAL (by pressing the MAN PB), and the in raise/lower PBs are used to attain a slow cooldown (< 25°F/hr). **

4.4 PCV-22 is taken to MANUAL (by rig pressing the MAN PB), and the raise/lower PBs are used to attain a slow cooldown (< 25°F/hr). **

(continued on next page)

O

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

LJC046.DOC PAGE 4 OF 7 REV. 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 on accordingly.

Cue: (once cooldown rate is properly established) Another operator Ve will continue with E-0.2 performance.

Stop Time:

rs i Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

Total Time: (Enter total time on the cover page) al in rig O

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

LJC046.DOC PAGE 5 OF 7 REV. 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.

on Go to RUN when the examinee is given the cue sheet (or the sim can remain in RUN, since the plant is stable)

Ve rs i al in rig O

LJC046.DOC PAGE 6 OF 7 REV. 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.

• Boration to Cold Shutdown is complete on EOP E-0.2 has been performed up to and including Step 9.

DG 1-2 was crosstied to non-vital power; two CRDM fans are running, and Pzr heaters are available Ve The plant is stable @ approx 565°F (TH), and 2235 psig. AFW is throttled in MANUAL to help with stability.

Initiating Cue:

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

i al in rig O

LJC046.DOC PAGE 7 OF 7 REV. 17

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121LJCS7 Title: PERFORM OP AP15 IMMEDIATE ACTIONS FOR MAIN FEED PUMP TRIP Examinee:

Evaluator:

Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments:

OP AP15, Loss of Feedwater Flow, Rev 24.

References:

Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 5 minutes Critical Steps:

Job Designation: RO/SRO Rev Comments: Modified NRCLCJ051501 Gen KA / Rating: 059.A2.07 3.0 / 3.3 AUTHOR:

DATE:

OPERATIONS REPRESENTATIVE: DATE:

REV. 0

JPM TITLE: Perform OP AP-15 Immediate Actions for Main JPM NUMBER: NRCL121LJC-S7 Feed Pump Trip 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 alarmed

• 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.

NRCL121-S7.DOCX PAGE 2 OF 7 ERROR! REFERENCE SOURCE NOT FOUND.

JPM TITLE: Perform OP AP-15 Immediate Actions for Main JPM Number: NRCL121LJC-S7 Feed Pump Trip INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. ** Step 1 - Check Reactor power Less 0B 1.1 Determined power is greater than 80%.

Than 80%.

1.2 Perform step 1 RNO Started AFW Pp 1-2.**

Started AFW Pp 1-3.**

Step was: Sat: ______ Unsat _______

Comments:

2. Step 2 - Reduce Turbine Load. 2.1 Determined turbine load is greater than 650 MW 2.2 Determined 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:

NRCL121-S7.DOCX PAGE 3 OF 7 REV. 0

JPM TITLE: Perform OP AP-15 Immediate Actions for Main JPM Number: NRCL121LJC-S7 Feed Pump Trip INSTRUCTOR WORKSHEET Step Expected Operator Actions

3. Step 3 - MFW Pp Suction Pressure 3.1 Determined MFW Pp Suction Pressure is GREATER THAN 260 PSIG greater than 260 PSIG Step was: Sat: ______ Unsat _______

Comments:

4. ** Step 4 - Rods Controlling Properly in 4.1 Checked Tave / Tref mismatch greater than 1.5 oF.

1B AUTO.

4.2 Determined rods are NOT controlling properly in Auto.

4.3 Placed Rod Control in MANUAL.** (step 4 RNO) 4.4 Inserted 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)

NRCL121-S7.DOCX PAGE 4 OF 7 REV. 0

JPM TITLE: Perform OP AP-15 Immediate Actions for Main JPM Number: NRCL121LJC-S7 Feed Pump Trip INSTRUCTOR WORKSHEET Followup Question Documentation:

Question: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

Response: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

NRCL121-S7.DOCX PAGE 5 OF 7 REV. 0

JPM TITLE: Perform OP AP-15 Immediate Actions for JPM NUMBER: NRCL121LJC-S7 Main Feed Pump Trip ATTACHMENT 1, SIMULATOR SETUP INIT to IC 10.

Run lesson NRCL121-LJCS7 or manually insert the following:

Inform the examiner that the simulator setup is complete.

Go to RUN when instructed by examiner.

NRCL121-S7.DOCX PAGE 6 OF 7 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121LJC-S7 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 alarmed

• 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 .

NRCL121-S7.DOCX PAGE 7 OF 7 REV. 0

• • • UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***

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

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 OP_AP-15u1r24.DOC 02 0726.1101

• • • UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***

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 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.

OP_AP-15u1r24.DOC 02 0726.1101

• • • UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***

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 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: b. Trip the Reactor and GO TO EOP E-0.T35691 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

3. CHECK MFW Pp Suction Pressure - GREATER a. Verify standby condensate booster THAN 260 PSIG 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.

OP_AP-15u1r24.DOC 02 0726.1101

• • • UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***

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 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 TAVG and T REF.

5. CONTINUE Load Reduction:

a. Verify programmed ramp continues: a. IF Unit Load is greater than 550 MW, THEN set up a ramp as follows:

DEH MW feedback in service

1) DEH MW feedback in service.

TARGET set for 550 MW

2) DEH IMP feedback in service.

RAMP RATE at 225 MW/min to 650 MW 3) TARGET set for 550 MW.

RAMP RATE at 25 MW/min to 550 MW 4) RAMP RATE at 25 MW/min.

5) Press GO.

6. CHECK Charging Flow - ADEQUATE TO Control Charging flow in MANUAL.

PREVENT FLASHING IN THE LETDOWN SYSTEM

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.

OP_AP-15u1r24.DOC 02 0726.1101

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT Job Performance Measure Number: NRCLJC051-501 Title: PERFORM OP AP-15 IMMEDIATE ACTIONS Examinee:

Evaluator:

Results:

Comments:

Sat Print Unsat on Signature Total Time:

Date minutes Ve

References:

rs i OP AP-15, Loss of Feedwater Flow, Rev. 17 Alternate Path: Yes X No Time Critical:

Time Allotment:

al Yes 5 minutes No X in Critical Steps:

Job Designation:

1.1, 2.3, 4.2 RO/SRO rig KA Number:

Rating:

04s/059/A2.07 3.0/3.3 OAUTHOR:

APPROVED BY:

JACK BLACKWELL N/A DATE:

DATE:

02/28/2007 JPM COORDINATOR APPROVED BY: N/A DATE:

TRAINING LEADER REV. 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:

Initial Conditions:

None on Unit 1 is at 72% and increasing to 100% power following a power reduction for maintenance. All systems aligned for normal full power Ve 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:

Task Standard: rs The SFM directs you to take appropriate actions to respond to plant conditions.

i 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.

al in rig O

NRCLJC051501.DOC PAGE 2 OF 6 REV. 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 on 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.

Ve

• • 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 rs Verify programmed ramp occurring i **

2.1 2.2 2.3 Determines turbine load is >650 MW Determines programmed ramp NOT occurring Manually initiates ramp

• Places DEH MW and IMP feedback in service

• Sets TARGET LOAD = 650 MW

• Sets RAMP RATE for = 225 MW/min al

• Presses GO Step SAT:___________ UNSAT:________*

3.

in CHECK Load Transient Bypass Actuated 3.1 Checks Load Transient Bypass Relay actuated

• Blue and Red light ON PK10-07 CNDS SYS TRANSIENT BYPASS rig alarm ON Step SAT:___________ UNSAT:________*

O

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

NRCLJC051501.DOC PAGE 3 OF 6 REV. 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 T REF Stop Time: ___________

Total Time: ___________

on Step SAT:___________ UNSAT:________*

Ve rs i al in rig O

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

NRCLJC051501.DOC PAGE 4 OF 6 REV. 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.

on Ve rs i al in rig O

NRCLJC051501.DOC PAGE 5 OF 6 REV. 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 on

Insert MAL cnd1 act1,0,0,d Ve Go to RUN until MFP Trip alarm actuates FREEZE Simulator

rs Inform the examiner that the simulator setup is complete.

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

i al in rig O

NRCLJC051501.DOC PAGE 6 OF 6 REV. 1

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121LJC-S8 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 3.9 / 3.8 the control room: Transfer of ECCS flowpaths prior to recirculation AUTHOR: DATE:

OPERATIONS REPRESENTATIVE: DATE:

REV. 0

JPM TITLE: ALIGN RHR PUMP 12 FOR HOT LEG RECIRCULATION JPM NUMBER: NRCL121LJC-S8 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 GIVEN:

Initial Conditions:

• 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 REV. 0

JPM TITLE: ALIGN RHR PUMP 12 FOR HOT LEG RECIRCULATION JPM NUMBER: NRCL121LJC-S8 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. Observed that RHR pump 12 running.

Step was: Sat: ______ Unsat _______

Comments:

3. Step 7 - Align RHR pump 12 for Hot 3.1 Opened valve 8716B.

Leg RecircOpen 8716B, RHR Verifies valve open.

pump 12 discharge crosstie valve.

3.2 Attempted 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 REV. 0

JPM TITLE: ALIGN RHR PUMP 12 FOR HOT LEG RECIRCULATION JPM NUMBER: NRCL121LJC-S8 INSTRUCTOR WORKSHEET Step Expected Operator Actions

4. Step 7.b RNO 4.1 Opened 8809A AND B **

4.2 Closed 8716B, RHR Pp 2 Disch Crosstie Vlv **

4.3 Throttled 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 5.1 Contacted TSC to evaluate CCW System TSC to evaluate CCW System train train separation.

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 REV. 0

JPM TITLE: ALIGN RHR PUMP 12 FOR HOT LEG RECIRCULATION JPM NUMBER: NRCL121LJC-S8 ATTACHMENT 1, SIMULATOR SETUP Restore 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 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121LJC-S8 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 REV. 0

• • • UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***

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 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 a. Perform the following:

Crosstie Vlv

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)

EOP_E-1!4u1r19.DOC 03A 1015.0808

• • • UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***

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 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

8. ALIGN RHR Pp 1 For Hot Leg Recirculation:

a. Open 8716A, RHR Pp 1 Disch Crosstie a. Perform the following:

Vlv

1) Open 8809A.

b. Open 8703, RHR to Hot Legs 1 and 2

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 EOP_E-1!4u1r19.DOC 03A 1015.0808

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL081LJC-S3 Title: ALIGN RHR PUMP 12 FOR HOT LEG RECIRCULATION Examinee:

Evaluator:

Results: Sat Print Unsat on Signature Total Time:

Date minutes Comments:

Ve rs i

References:

EOP E-1.4, Transfer to Hot Leg Recirculation, Rev. 19 Alternate Path:

Time Critical:

Time Allotment:

al Yes Yes 10 minutes X No No X in Critical Steps:

Job Designation:

4 RO/SRO rig Task Number:

Rating:

KA 006A4.05 3.9/3.8 O

AUTHOR: GARY HUTCHISON DATE: 04/29/09 REV. 0

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

NRCL081LJC-S3 INSTRUCTOR WORKSHEET Directions: No PLANT controls or equipment are to be operated during the performing of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are Required Materials:

Initial Conditions:

None on needed. The examinee may be given the applicable procedure and step with which to begin.

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

Ve 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.

The Shift Foreman directs you to align RHR pump 12 for hot leg Task Standard:

EOP E-1.4. rs recirculation, per EOP E-1.4, steps 6 - 7.

RHR pump 12 aligned for hot leg recirculation in accordance with i

al in rig O

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

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

NRCL081LJC-S3 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

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

2. Check RHR pump 12 running. 2.1 on Step was: Sat: ______ Unsat _______*

Observes that RHR pump 12 is running.

Step was: Sat: ______ Unsat _______*

3. Open 8716B, RHR pump 12 Ve discharge crosstie valve.

3.1 3.2 Opens valve 8716B.

Verifies valve open.

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

rs i Step was: Sat: ______ Unsat _______*

4.1 4.2 Attempts to open valve 8703, goes to RNO after determining 8703 will not open.

Cuts in series contactors for 8809A AND B **

4.3 Opens 8809A AND B **

4.4 Close 8716B, RHR Pp 2 Disch al 4.5 Crosstie Vlv **

Throttle RHR HX Outlet valve as needed to maintain motor current LESS THAN 57 amps if needed in Stop Time:

Step was: Sat: ______ Unsat _______*

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

O

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

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

JPM NUMBER:

NRCL081LJC-S3 EXAMINEE CUE SHEET Initial Conditions: A Unit 1 reactor trip and safety injection has occurred. Cold leg recirculation was initiated just over 10.5 hours5.787037e-5 days <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.

on Ve rs i al in rig O

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

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

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

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

Command vlv rhr7 1,0,0,0,d,0 Description on 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.

Ve Inform the examiner that the simulator setup is complete.

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

rs i al in rig O

NRCL081LJC-S3.DOC PAGE 5 OF 5 REV. 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: 15 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 3.4/3.7 as they apply to the Plant Fire on Site: Fire fighting equipment used on each class of fire AUTHOR: LISA TORIBIO DATE: 06/20/2014 OPERATIONS ABDUL KADIR DATE: 06/20/2014 REPRESENTATIVE:

REV. 0

JPM TITLE: MANUALLY OPERATE THE CARDOX SYSTEM JPM NUMBER: NRCL121-P1 EVALUATOR W ORKSHEET 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 REV. 0

JPM TITLE: MANUALLY OPERATE THE CARDOX SYSTEM JPM NUMBER: NRCL121-P1 EVALUATOR W ORKSHEET Start Time:

Step Expected Operator Actions Step 6.3.1 - Attempt LOCAL discharge to 1.1 Read NOTE prior to step 6.3.1.

1. U-2 Cable Spreading Room (CSR) 1.2 For 2-FCV-102, pulled cover and depressed 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 CO2 piping.

1.3 Determined that CO2 discharge did not occur, and moved on to next step.

Sat: ______ Unsat _______

Comment:

NRCL121-P1 PAGE 3 OF 7 REV. 0

JPM TITLE: MANUALLY OPERATE THE CARDOX SYSTEM JPM NUMBER: NRCL121-P1 EVALUATOR W ORKSHEET Step 6.3.2 - Manually actuate CARDOX 2.1 Read CAUTION prior to step 6.3.2.a.

2. ** at local station 0B0B Step 6.3.2.a - Personnel clear of CSR 2.2 Ensured 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.

2.3 Ensured abort valve for Unit 2 Cable Step 6.3.2.b - Ensure 2-HCV-2074 open 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 2.4 Broke glass and opened pilot for valve 2-FCV-102. **

Cue: NO audible flow noise is heard in the CO2 piping.

Sat: ______ Unsat _______

Comment:

NRCL121-P1 PAGE 4 OF 7 REV. 0

JPM TITLE: MANUALLY OPERATE THE CARDOX SYSTEM JPM NUMBER: NRCL121-P1 EVALUATOR W ORKSHEET 6.3.2.d - At the storage tank, manually 3.1

3. ** Read note prior to step 6.3.2.d open the Selector Pilot Control Valve 1B1B 3.2 Broke glass and opened the Pilot Valve for Master Valve 0-FCV-104. **

Cue: Audible flow noise is heard in the CO2 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 3.3 Closed the Pilot Valve for 2-FCV-102. **

valve 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 CO2 piping.

Sat: ______ Unsat _______

Comment:

NRCL121-P1 PAGE 5 OF 7 REV. 0

JPM TITLE: MANUALLY OPERATE THE CARDOX SYSTEM JPM NUMBER: NRCL121-P1 EVALUATOR W ORKSHEET Stop Time:

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

Follow up Question Documentation:

Question: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

Response: ____________________________________________________________________

______________________________________________________________________________

______________________________________________________________________________

NRCL121-P1 PAGE 6 OF 7 REV. 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 REV. 0

Low Pressure Cardox - Manual Use Of The Cardox OP K-2B:II R10 System Page 5 of 14 UNITS 1&2 6.3 Locally Actuating CO2 to Unit 2 Cable Spreading Room NOTE: The instructions of Section 6.3 can be found on a lamicoid at local CO2 actuation station UNIT 2 CABLE SPREAD RM CO2 FIRE SYSTEM CONTROL STATION, in Auxiliary Building Stairway #1 on the 128 ft level.

6.3.1 At local CO2 actuation station, pull cover and push button for 2-FCV-102.

6.3.2 IF CO2 failed to actuate by pushbutton, THEN perform the following:

CAUTION: Performing the following steps will cause an immediate discharge of CO2.

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 CO2 discharge did NOT occur, THEN at storage tank, break glass and open pilot valve for 0-FCV-104.

e. WHEN CO2 has discharged for 155 to 165 seconds, THEN at local CO2 actuation station, close pilot valve for 2-FCV-102.

OP_K-2B~IIu3r10.DOC 0918.0652

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: LJP-138A Title: MANUALLY OPERATE THE CARDOX SYSTEM Examinee:

Evaluator:

Testing Method: Perform Print Simulate on Signature Date Results:

Comments:

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

References:

rs Note: This is a U-2 JPM.

i U1 & 2 OP K-2B:II, Manual Use of the Cardox System, Rev. 10 Alternate Path: Yes X No Time Critical:

Time Allotment:

al Yes 15 minutes No X in Critical Step(s):

Job Designation:

Rev Comments/TIPs:

2, 3 RO/SRO Rev 2A EC revision per SAPN 50586181, to match procedure revision rig DCPP Task # / Rating:

Gen KA # / Rating:

TIP 22308-02; per R115 examiner/examinee feedback.

666600 067.AA1.08 3.7 3.4 / 3.7 OAUTHOR:

REVIEWED BY:

JOHN F. BUCKLEY RON FORTIER FOR JOHN BECERRA DATE:

DATE:

02/13/2012 2/13/12 TRAINING SUPERVISOR APPROVED BY: ERIK WERNER DATE: 2/20/12 LINE MANAGER REV. 2A

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 on 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:

Initial Conditions: Given:

Ve Copy of U1&2 OP K-2B:II, Section 6.3.

Initiating Cue:

• rs A fire has been detected in the Unit 2 Cable Spreading Room.

DC power has been lost to the cardox control circuitry.

i There are NO personnel in either Cable Spreading Room.

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:

al Cardox is initiated to the U2 Cable Spreading Room for the proper duration, in accordance with OP K-2B:II.

in rig O

LJP138A.DOC PAGE 2 OF 6 REV. 2A

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 1.1 Reads NOTE prior to step 6.3.1.

Cable Spreading Room via pushbutton. 1.2 For 2-FCV-102, pulls cover and on 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.

Ve **********************************

Cue: NO audible flow noise is heard in the CO2 piping.

rs i

1.3 Determines that CO2 discharge did not occur, and moves on to next step.

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat) al in rig O

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

LJP138A.DOC PAGE 3 OF 6 REV. 2A

JPM TITLE: MANUALLY OPERATE THE CARDOX SYSTEM JPM NUMBER: LJP-138A INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 2. Manually actuates CO2 to the 2.1 Reads CAUTION prior to Cable Spreading Room. step 6.3.2.a.

2.2 Verifies personnel are clear of the on Unit 2 Cable Spreading Room.

Cue: There are no personnel in the Cable Spreading Room.

Ve Note: The valve handle is parallel to the pipe when the valve is open.

rs i 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.

al 2.4 Breaks glass and opens pilot for 2-FCV-102. **

in Cue: NO audible flow noise is heard in the CO2 piping.

2.5 Reads note prior to step to open rig 0-FCV-104. **

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

O

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

LJP138A.DOC PAGE 4 OF 6 REV. 2A

JPM TITLE: MANUALLY OPERATE THE CARDOX SYSTEM JPM NUMBER: LJP-138A INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 3. Manually Opens the Selector Pilot 3.1 At the storage tank, breaks glass and Control Valve. opens the Master Valve 0-FCV-104. **

on

Cue: Audible flow noise is heard in the CO2 piping.

Ve Note: Give following Cue only after examinee verbalizes that valve will be kept open for 2 minutes and 40 seconds.

rs i

Cue: Two minutes and 40 seconds have 3.2 elapsed.

Closes the Selector Pilot Control Valve 2-FCV-102. **

al Cue: There is no more audible flow noise in the CO2 piping.

in Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat) rig Stop Time:

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

O

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

LJP138A.DOC PAGE 5 OF 6 REV. 2A

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: on 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 Ve rs i al in rig O

LJP138A.DOC PAGE 6 OF 6 REV. 2A

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: 068.AA1.21 - Ability to operate and / or monitor the following as 3.9/4.1 they apply to the Control Room Evacuation: Transfer of controls from control room to shutdown panel or local control AUTHOR: LISA TORIBIO DATE: 06/20/2014 OPERATIONS ABDUL KADIR DATE: 06/20/2014 REPRESENTATIVE:

REV. 0

JPM TITLE: ALIGN 480V BUS G FOR CONTROL FROM THE HOT JPM NUMBER: NRCL121-P2 SHUTDOWN PANEL EVALUATOR W ORKSHEET 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 REV. 0

JPM TITLE: ALIGN 480V BUS G FOR CONTROL FROM THE HOT JPM NUMBER: NRCL121-P2 SHUTDOWN PANEL EVALUATOR W ORKSHEET Start Time:

Step Expected Operator Actions Step 2.a. - Place the control transfer Located 480V vital bus 1G aux relay panel 1.** cutout switches for 480V vital bus 1G to 1.1 in the vital switchgear room.

the CUT-IN position.

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

The aux relay panel may be opened.

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

• FCV-95, switch 43X-1230.**

Cue: (may be given after each switch operation)

The switch is in the CUTIN (up) position.

• CFCU 15, switch 43X-1G-02.**

• Emergency Borate valve 8104, switch 1.3 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 REV. 0

JPM TITLE: ALIGN 480V BUS G FOR CONTROL FROM THE HOT JPM NUMBER: NRCL121-P2 SHUTDOWN PANEL EVALUATOR W ORKSHEET Step 2.b - Open 480V vital bus 1G 2.1 Opened the following breakers:

2. breakers to prevent spurious operation.

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 52-1G-14. **

• FCV-363, bkr 52-1G-23. **

• 8100, bkr 52-1G-26. **

• FCV-431, bkr 52-1G-28 **

Comment:

3.1 Informed the HSDP Operator that the 480V Bus

3. Report alignment complete 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 REV. 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 REV. 0

Control Room Inaccessibility - Establishing Hot OP AP-8A R38 Standby Page 39 of 60 UNIT 1 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 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

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:

Testing Method: Perform Print Simulate on Signature Date Results:

Comments:

Sat Ve Unsat Total Time: minutes rs (Note: Any Unsat step requires a numbered comment; use back as needed.)

References:

Alternate Path:

Time Critical:

Yes Yes i

OP AP-8A, Control Room Inaccessibility - Establishing Hot Stby, Rev. 36 No No X

X Time Allotment:

Critical Steps:

al 30 minutes 1, 2 in Job Designation:

Rev Comments/TIPs:

RO/SRO 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 rig DCPP Task # / Rating:

Gen KA # / Rating:

Supervisor.

812400 068.AA1.21 4.2 3.9 / 4.1 OAUTHOR:

REVIEWED BY:

JOHN F. BUCKLEY JOHN BECERRA DATE:

01/25/2011 01/25/2011 TRAINING SUPERVISOR APPROVED BY: ERIK WERNER DATE: 02/03/2011 LINE MANAGER REV. 17B

JPM TITLE: ALIGN 480V BUS G FOR CONTROL FROM THE HOT JPM NUMBER: LJP-007 SHUTDOWN PANEL 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.

on 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 Required Materials:

Ve from expected.

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:

• rs i 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 al at the Hot Shutdown Panel, per OP AP-8A, App F, step 2.

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

in Task Standard: Breakers and switches aligned for 480 vac bus 1G per App F, step 2 of OP AP-8A.

rig O

LJP007.DOC PAGE 2 OF 5 REV.17B

JPM TITLE: ALIGN 480V BUS G FOR CONTROL FROM THE HOT JPM NUMBER: LJP-007 SHUTDOWN PANEL INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

• • 1. Place the control transfer cutout 1.1 Locates 480V vital bus 1G aux relay switches for 480V vital bus 1G to the CUT-IN position.

on 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.

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

rs i

• 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.**

al *

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

switch 43X-1G-04, BATP 1-2.**

in *

• switch 43X-1G-44, LCV-106.**

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

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

O

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

LJP007.DOC PAGE 3 OF 5 REV.17B

JPM TITLE: ALIGN 480V BUS G FOR CONTROL FROM THE HOT JPM NUMBER: LJP-007 SHUTDOWN PANEL INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 2. Open 480V vital bus 1G breakers 2.1 Opens the following breakers:

to prevent spurious operation.

• FCV-356 bkr 52-1G-36. **

on

Cue: (may be given after each breaker operation) The breaker is in the OFF position.

Ve *

• 9003A bkr 52-1G-48. **

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

rs i

• 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 al 480V Bus 1G Alignment is complete.

Step was: Sat: ______ Unsat _______*

in Stop Time:

[ ] Comment # (required for Unsat) rig Total Time: (Enter total time on the cover page)

O

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

LJP007.DOC PAGE 4 OF 5 REV.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 Initiating Cue:

Panel.

on align bus 1G 480 VAC loads for control from the Hot Shutdown The Shift Foreman directs you to align bus 1G 480 vac loads for control Ve at the Hot Shutdown Panel, per OP AP-8A, App F, step 2.

rs i al in rig O

LJP007.DOC PAGE 5 OF 5 REV.17B

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-P3 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 3.4/3.8 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 AUTHOR: LISA TORIBIO DATE: 06/20/2014 OPERATIONS ABDUL KADIR DATE: 06/20/2014 REPRESENTATIVE:

REV. 0

JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER JPM NUMBER: NRCL121-P3 STORAGE TANK 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 This JPM was evaluated against TCOA # 35 (Realign the AFW pumps Operator Action to a new suction source within 20 minutes).

(TCOA): 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 REV. 0

JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER JPM NUMBER: NRCL121-P3 STORAGE TANK EVALUATOR W ORKSHEET Start Time:

Step Expected Operator Actions Step 6.1.1 - Check OPEN FP 0 4 1.1 Read NOTEs 1 and 2 prior to step

1. (115' Elev., in FWST vault).

1.2 Located FP-0-4.

1.3 Checked the position of FP-0-4 (large, rising stem valve).

Cue: Valve stem extends 12-14" from valve handwheel (open).

1.4 Determined FP-0-4 is open Sat: ______ Unsat _______

Comment:

Step 6.1.2 - Check AFW suction being 2.1 Read Step 6.1.2 and determined that step does

2. realigned from the CST not need to be performed.

Sat: ______ Unsat _______

Comment:

Step 6.1.3 - Check MU-0-1557 closed 3.1 Located MU-0-1557.

3. (100' Elev., chain operated, in hallway 3.1 near RWST vault) 3.2 3.2 Checked MU-0-1557 closed.

Cue: (if tugs on chainfall in CW direction) Valve will not move 3.3 (closed). (if examinee climbs up ladder; flashlight needed) Pointer is on "C" (closed).

3.4 Determined MU-0-1557 is closed.

Sat: ______ Unsat _______

Comment:

NRCL121-P3 PAGE 3 OF 8 REV. 0

JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER JPM NUMBER: NRCL121-P3 STORAGE TANK EVALUATOR W ORKSHEET Step 6.1.4 - First Bullet - Verify MU 0 Note: Steps 4 and 5 may be performed 284 closed (100' Elev., north end of in any order (steps are bullets in hallway).

OP D-1:V). Both valves are rising stem handwheel operated Note: MU-0-284 and 286 are the valves ( 10" rise when open);

4. downstream isolations for the in-line 4.1 MU-0-284 is normally OPEN.

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].

4.2 Located MU-0-284 4.3 Checked MU-0-284 position.

Cue: Valve stem is 10" out from valve handwheel.

4.4 Closed 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:

Step 6.1.4 - Second Bullet - Verify 5.1 Located MU-0-286

5. closed MU-0-286 (100' Elev., north end of hallway).

5.2 Checked MU-0-286 position.

Cue: Valve stem is 1" out from valve handwheel, and won't move in CW direction.

5.3 Determined MU-0-286 is closed Sat: ______ Unsat _______

Comment:

NRCL121-P3 PAGE 4 OF 8 REV. 0

JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER JPM NUMBER: NRCL121-P3 STORAGE TANK EVALUATOR W ORKSHEET Step 6.1.5 - Open FP-0-306 and FP 6.1 Read Step 6.1.5 and determined that step 6.

307 (chain operated, normally locked needs to be performed.

closed 100' Elev., above MU Water pps, near north wall).

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 Located FP-0-306.

6.3 Unlocked and opened FP-0-306. **

Cue: (if chainfall operated to turn valve operator CCW to open) The valve moved several turns CCW and stopped (open seat).

6.4 Located FP-0-307.

6.5 Unlocked and opened FP-0-307. **

Cue: (if chainfall operated to turn valve operator CCW to open) The valve moved several turns CCW and stopped (open seat).

Sat: ______ Unsat _______

Comment:

NRCL121-P3 PAGE 5 OF 8 REV. 0

JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER JPM NUMBER: NRCL121-P3 STORAGE TANK EVALUATOR W ORKSHEET Step 6.1.6 - Open FCV 436 and 437 Note: These valves in the next several

7. (100' Elev., AFW Pp 2-1 room) steps may be operated in any order (steps are bullets).

7.1 Located FCV-436 and FCV-437.

7.2 Opened FCV- 436 and FCV-437**.

Cue: (for each valve) Pointer is at "O" (open).

Sat: ______ Unsat _______

Comment:

Step 6.1.7 - Close AFW pump 8.1 Located and Closed FW-2-121**

8.

suctions from CST

Cue: (for FW-2-121, HW operated valve)

Pointer is at "CLOSED".

8.2 Located and Closed 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-P3 PAGE 6 OF 8 REV. 0

JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER JPM NUMBER: NRCL121-P3 STORAGE TANK EVALUATOR W ORKSHEET Step 6.1.8 - If necessary, vent AFW **********************************

pump casings Cue: Suction to the AFW pumps was

9. NOT lost.

9.1 Determined venting is not required.

Sat: ______ Unsat _______

Comment:

Step 6.1.9 - Notify Control Room 10.1 Notified the Control Room AFW pumps 10.

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-P3 PAGE 7 OF 8 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-P3 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 REV. 0

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

2 D IABLO C ANYON POWER P LANT OP D-1:V OPERATING PROCEDURE Rev. 19 UNIT Page 1 of 15 Auxiliary Feedwater System - Alternate Auxiliary Feedwater Supplies 12/24/13 Effective Date QUALITY RELATED Table of Contents

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.

OP_D-1~Vu2r19.doc 1212.0935

Auxiliary Feedwater System - Alternate Auxiliary OP D-1:V R19 Feedwater Supplies Page 2 of 15 UNIT 2

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."

OP_D-1~Vu2r19.doc 1212.0935

Auxiliary Feedwater System - Alternate Auxiliary OP D-1:V R19 Feedwater Supplies Page 3 of 15 UNIT 2

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 OP_D-1~Vu2r19.doc 1212.0935

Auxiliary Feedwater System - Alternate Auxiliary OP D-1:V R19 Feedwater Supplies Page 4 of 15 UNIT 2 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.

OP_D-1~Vu2r19.doc 1212.0935

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:

Testing Method: Perform Print Simulate on Signature Date Results:

Comments:

Ve Sat _____ Unsat _____ Total Time: _______ TCOA Time: ______

(Note: Any Unsat step requires a numbered comment; use back as needed.)

This is a U-2 JPM

References:

rs i 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:

Time Allotment:

Critical Steps:

al Yes 40 minutes 4, 6, 7, 8, 9 X No in Job Designation:

Rev Comments/TIPs:

RO/SRO SAPN 50304333; TIPs 21236-50, 21257-56, 22418-61. Rev 1B constitutes a rig DCPP Task # / Rating:

Gen KA # / Rating:

minor change for reference procedure rev #s. Change approved by Exam Support Group Supervisor.

546400 061.A2.04 4.0 3.4 / 3.8 O

AUTHOR:

REVIEWED BY:

JOHN F. BUCKLEY JOHN BECERRA DATE:

DATE:

02/12/2011 02/25/11 TRAINING SUPERVISOR APPROVED BY: ERIK WERNER DATE: 02/25/11 LINE MANAGER REV. 1B

JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER JPM NUMBER: LJP-104A STORAGE TANK 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.

on 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 Required Materials:

Ve from expected.

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

Initial Conditions:

• rs Copy of Unit 2 OP D-1:V, Section 6.1 and Attachment 1.

i PG&E 909 key.

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 al accordance with OP D-1:V, Section 6.1.

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

in 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.

rig 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 O 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).

LJP104A.DOC PAGE 2 OF 9 REV. 1B

JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER JPM NUMBER: LJP-104A STORAGE TANK INSTRUCTOR WORKSHEET Start Time: (also start time for TCOA)

Step Expected Operator Actions

1. Check OPEN FP-0-4 1.1 Reads NOTEs (115' Elev., in FWST vault).

1.2 1.3 on Locates FP-0-4.

Checks the position of FP-0-4 (large, rising stem valve).

Ve Cue: Valve stem extends 12-14" from valve handwheel (open).

2. Checks AFW suction being realigned from the CST rs i Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat) 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.

al Check closed MU-0-1557 (100' Elev., chain operated, in hallway near RWST vault).

3.1 3.2 Locates MU-0-1557.

Checks Closed MU-0-1557.

in **********************************

Cue: (if tugs on chainfall in CW direction) Valve will not move (closed). (if examinee climbs up rig ladder; flashlight needed) Pointer is on "C" (closed).

Step was: Sat: ______ Unsat _______*

O [ ] Comment # (required for Unsat)

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

LJP104A.DOC PAGE 3 OF 9 REV. 1

JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER JPM NUMBER: LJP-104A STORAGE TANK INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 4. Verify closed MU-0-284 Note: Steps 4 and 5 may be performed (100' Elev., north end of hallway). in any order because these steps are bullets in OP D-1:V. Both Note: MU-0-284 and 286 are the downstream isolations for the in-line strainers. One will be in service, and the other OOS.

4.1 on valves are rising stem handwheel operated valves ( 10" rise when open); MU-0-284 is normally OPEN.

Locates MU-0-284 Ve This JPM is written for current plant conditions, but if the "lower" strainer is in service

[MU-1-286], then make step 4 4.2 Checks MU-0-284 position.

Cue: Valve stem is 10" out from

[ie, both strainers OOS].

rs non-critical, and step 5 critical i

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).

al **********************************

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat) 5.

in Verify closed MU-0-286 (100' Elev., north end of hallway).

5.1 5.2 Locates MU-0-286 Checks MU-0-286 position.

rig **********************************

Cue: Valve stem is 1" out from valve handwheel, and won't move in CW direction.

O Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

LJP104A.DOC PAGE 4 OF 9 REV. 1

JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER JPM NUMBER: LJP-104A STORAGE TANK INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 6. Open FP-0-306 and FP-0-307 6.1 Reads Step 6.1.5 and determines that (chain operated, normally locked step needs to be performed.

closed 100' Elev., above MU Water pps, near north wall).

on 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.

Ve ***********************************

Cue: The SFM has assigned another operator to complete the sealed rs i 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 al stopped (open seat).

6.4 Locates FP-0-307.

in 6.5 Unlocks and opens FP-0-307. **

Cue: (if chainfall operated to turn rig operator CCW to open) The valve move several turns CCW and stopped (open seat).

Step was: Sat: ______ Unsat _______*

O [ ] Comment # (required for Unsat)

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

LJP104A.DOC PAGE 5 OF 9 REV. 1

JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER JPM NUMBER: LJP-104A STORAGE TANK INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 7. Locally open FCV-436 and 437 Note: These valves in the next several fully steps may be operated in any (100' Elev., AFW Pp 2-1 room). order because these steps are 7.1 7.2 on bullets in OP D-1:V.

Locates FCV-436 and FCV-437.

Opens FCV- 436 and FCV-437**.

Ve Cue: (for each valve) Pointer is at "O" (open).

• • 8. Close AFW Pp suctions from CST.

rs i Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat) 8.1 Locates and Closes each valve:

AFW Pp 1 FW-2-121**

2 FW-2-159**

3 FW-2-180**

al **********************************

Cue: (for FW-2-121, HW operated valve) Pointer is at "CLOSED".

in **********************************

Cue: (for FW-2-159 and FW-2-180, handle operated butterfly valves) rig Handle is down to the "perpendicular to pipe" position.

Note the time the examinee closed the final normal suction valve (TCOA stop O time): _________________________

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

LJP104A.DOC PAGE 6 OF 9 REV. 1

JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER JPM NUMBER: LJP-104A STORAGE TANK INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 9. If suction to the AFW Pps was 9.1 Locates the AFW pump vents:

lost, vent the AFW Pp casings as AFW pp21 - FW-2-127 necessary to remove trapped air.

on AFW pp22 AFW pp23

-

-

-

FW-2-128 FW-2-165 FW-2-186 Note: These valves may be operated in any order because these steps are bullets in OP D-1:V. They are Ve "T" handle valves on top of each pump.

rs i 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.

al 9.3 Shuts each vent valve. **

Cue: (For each vent): Flow has stopped.

in The valve will not move any further CW.

rig 9.4 Replaces each vent cap.

Cue: (For each vent): The pipe cap is secured on the end of the pipe.

O **********************************

Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

LJP104A.DOC PAGE 7 OF 9 REV. 1

JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER JPM NUMBER: LJP-104A STORAGE TANK INSTRUCTOR WORKSHEET Step Expected Operator Actions

10. Notify the Control Room that the 10.1 Notifies the Control Room.

suction for the AFW Pps is now available from the FWST.

on Step was: Sat: ______ Unsat _______*

[ ] Comment # (required for Unsat)

Stop Time:

Total Time:

Ve (Enter total time on the cover page)

TCOA Start Time:

TCOA Stop Time:

TCOA Total Time:

rs i (enter TCOA time on front page)

TCOA: SAT al UNSAT (TCOA time must be < 19 minutes) in rig O

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

LJP104A.DOC PAGE 8 OF 9 REV. 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 on supply to Fire Water Storage Tank, and to vent the AFW pumps, in accordance with OP D-1:V, Section 6.1.

Ve rs i al in rig O

LJP104A.DOC PAGE 9 OF 9 REV. 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 Malf Event Event No No. Type* 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, CCW Pp 1-2 overcurrent trip. (AP-11; TS 3.7.7.A)

SRO) 4 PMP_TUR2 C (BOP, Thermal overload of AC Bearing Oil Pump (AP-29).

OVERLOAD_DEV_FAIL SRO) 5 XMT_MSS1_3 I (SRO, PT-507 slow failure low causing Group I dumps to close. (AP-5)

ATC) 6 MAL_RCS3A 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_RCS3A 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 C (BOP) On SI, running CCPs trip on OC, standby pump fail to autostart - CT )

PMP_CVC2

• (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-0D: Manually initiate Safety Injection before transitioning to any E-1, E-2, or E-3 series procedure)**.

8. Crews 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 fails to autostart, but can be started manually. (Critical Task E-0I: Establish flow from at least one high-head ECCS pump before transition out of E-0)**.

10. 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.: L121-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 Malf Event Event No No. Type* Description 1 XMT_RMS11_3 I (SRO, RM-12 (containment gaseous radiation monitor) fails high requiring BOP) 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 C (SRO, Seal Injection Filter 1-1 plugs causing reduction in charging flow to RCP ramp=30 ATC) seals.

4 MAL_EPS4E DIFF C (SRO, Loss of 4KV Vital Bus H (diff trip); alternate equipment is placed in BOP) service, and Tech Specs are implemented (AP-27) (TS 3.4.11.C, 3.8.4.A).

5 LOA_CND1 5E-5 C (SRO, Slow vacuum leak develops as result of loop seal maintenance activities LOA_CND1 1 LT 1010 BOP) requiring ramp. (AP-7 and AP-25).

R (ATC) 6 LOA_CND1 5E-5 M (ALL) Loop seal fails during Maintenance attempt to back out of field activity LOA_CND1 1 LT 1010 resulting in rapid loss of vacuum; turbine/Rx trip (AP-7).

7 MAL_AFW1 1 C (BOP) Immediately following the Rx Trip, TDAFW trips on overspeed and cd='fnispr_1 lt 5 MDAFW 1-3 fails to autostart, requiring manual start of motor driven PMP_AFW2 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.1E: 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.1A: 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.: L121-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 Malf Event Event No No. Type* Description 1 MAL_NIS6D 200 (ramp I (ALL) NI-44 slowly fails high causing unwarranted rod motion (TS in slowly) 3.3.1.D, E,S,T; ECGs 37.2, 37.3) (AP-5) 2 PMP_CND2 C (SRO, Condensate Booster Pump 1-3 Trips on overcurrent. Standby fails BLOCK_AUTO_STRT BOP) to autostart (AP-15).

PMP_CND3_MTRF 15.0 3 MAL_RCS4F 35 delay=0 C (ALL) 35 gpm tube leak ramps in over 2 minutes on S/G 1-2, requiring ramp=120 R (ATC) power reduction. (TS 3.4.15.A) (AP-3) 4 MAL_CWS2C 1.3 C (SRO, Condenser in-leakage in SW quadrant requiring 25 MW/min ramp delay=0 ramp=2 BOP) (AP-20) 5 MAL_RCS4F 400 M (ALL) S/G 1-2 ruptures (400 gpm) requiring Safety Injection.

delay=0 ramp=120 6 VLV_SIS3_1 1 C (BOP) 8801A/B fail to open on SI, requiring manual opening to establish VLV_SIS4_1 1 high head ECCS injection (CT) 7 insert MAL_MSS1B M (ALL) MSLB on S/G 1-2 inside containment downstream of flow 3500000.0 cd='fnispr lt restrictor on Rx Trip resulting in faulted/ruptured S/G (CT) 5.0' delay=0 ramp=60 8 insert VLV_MSS7_2 1.0 C (BOP) MSIVs on leads 1 & 2 fail to close in auto, but can be closed insert VLV_MSS8_2 1.0 manually delIA VLV_MSS7_2 2 delIA VLV_MSS8_2 2

• (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-0D: 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-2A: 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 Tube 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

Appendix D (rev 9) Required Operator Actions Form ESD1 Facility: Diablo Canyon (PWR) Scenario No.: 4 OpTest No.: L121NRC Examiners: Operators:

Initial Conditions: 100%, MOL, 961 ppm boron Turnover: Bus H Work Week: AFW 12 OOS, D/G 11 OOS Maintenance in progress on PCV20.

CCP 11 In Service.

Event Malf Event Type* Event No No. Description 1 XMT_CVC20_3 I (SRO, BOP) VCT level LT114 gradually fails high causing letdown flow to divert to the LHUTs. Automakeup commences when actual level falls to 14% (AP19);

2 MAL_SEI1 .15 delay=0 ramp=5 C (SRO, BOP) PCV456 slowly drifts open following small seismic and can VLV_PZR5_2 0.25 delay=0 not be closed. Associated block valve is closed to isolate the ramp=5 PORV (AP13) (TS 3.4.11.B, CT) 3 R(ALL) Call from Grid Control Center for Unit 1 backdown order to shed 350 MW within 10 minutes due to grid disturbance (AP25) 4 MAL_ROD3A_ROD B10 C (ALL) Dropped rod and urgent failure at 855 MW inhibits auto rod MAL_ROD3A STATIONARY motion and requires rods to be taken to manual (AP 12C)(TS 3.1.4.B).

5 MAL_SEI1 .17 delay=0 ramp=6 M (ALL) Second seismic results in full load rejection. Rods are still in MAL_SYD3 56.0 delay=3 manual and crew must trip the reactor based on first step of ramp=30 AP2.

6 MAL_SEI1 .3 delay=0 ramp=6 C(SRO, BOP) Loss of Startup immediately following Rx Trip. D/G 13 fails MAL_SYD2 0 to auto start but can be manually started.

7 MAL_RCS1D 50%_dba M (ALL) Strong aftershock results in LBLOCA. ECCS CCPs and SIP 11 MTRF 15 cd='jpplsia or jpplsib' trip on overcurrent reducing the amount of high head injection.

PMP_SIS1_MTRF 15.0 cd='jpplsia or jpplsib' 8 PMP_RHR1 BLOCK_AUTO_STRT C (BOP) RHR 11 and CSP 11 fail to autostart, but may be manually PMP_CSS1 BLOCK_AUTO_STRT started (CTs).

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor L121 NRC ESD104 r1.doc Page 1 of 3 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD1 Target Quantitative Attributes (Per Scenario; See Section D.5.d) (from form ES3014) Actual Attributes

1. Total malfunctions (5-8) (Events 1,2,4,5,6,7,8) 7

2. Malfunctions after EOP entry (1-2) (Events 6,7,8) 3

3. Abnormal events (2-4) (AP19, AP25, AP12C, AP2) 4

4. Major transients (1-2) (Events 5&7) 2

5. EOPs entered/requiring substantive actions (1-2) (E0.1, E1) 2

6. EOP contingencies requiring substantive actions (0-2) (ECA0.3) 1

7. Critical tasks (2-3)(See Scenario Summary) 3 L121 NRC ESD104 r1.doc Page 2 of 3 Rev 1

SCENARIO

SUMMARY

- NRC #4

1. Volume Control Tank (VCT) level channel LT114 fails high, causing letdown to divert to the LHUTs.

Automatic reactor makeup will maintain VCT level above 14%. The crew diagnoses the level channel failure by comparing other VCT parameters, and addresses issue following OP AP19, Malfunction of the Reactor Makeup Control System guidance. LCV112A control is set to the VCT position.

2. Small seismic causes PCV456 to slowly drift open and must be isolated using the associated 8000C block valve. Shift Forman enters TS 3.4.11.B Pressurizer Power Operated Relief Valves (PORVs). (Critical Task: Isolate PORV prior to pressurizer pressure lowering to 1950 psig (low pressurizer pressure Rx trip setpoint)).

3. Grid Control Center (GCC) calls with a backdown order for DCPP due to grid disturbance. Shift Manager directs Unit 1 to shed 350 MW in the next 10 minutes. Crew commences ramp using guidance of OP AP 25, Rapid Load Reduction or Shutdown to reduce load.

4. At 855 MW, a Rod Control Urgent Failure occurs and rod B10 is drops. Crew places rod control in manual and enters OP AP12C, Dropped Control Rod. Turbine is used to return Tave to Tref. Shift Foreman enters TS 3.1.4.B Rod Group Alignments.

5. A large seismic event occurs, resulting in a 500kV grid instability/underfrequency condition. Unit separates from the grid. Crew enters OP AP2, Full Load Rejection, and trips the reactors based on unavailability of auto rod control.

6. Crew enters E0, Reactor Trip or Safety Injection, and transitions into E0.1, Reactor Trip Response to stabilize the plant. Startup power is lost and D/G 13 fails to autostart due to a shutdown relay, reducing vital 4kV power to a single bus (D/G 11 out of service from initial conditions). ECA0.3, Restore 4kV Buses is implemented in parallel with E0.1. D/G 13 shutdown relay is reset from the control room and the diesel started in manual.

7. A large aftershock occurs resulting in a LBLOCA. ECCS CCPs (High Head Injection) and SIP 11 (Intermediate Head Injection) all trip on overcurrent. Crew reenters E0, Reactor Trip or Safety Injection, and transitions to E1, Loss of Reactor or Secondary Coolant.

8. RHRP 11 (Low Head Injection) and CSP 11 (Containment Spray) fail to autostart, but may be manually started (Critical Task E0H: Manually start at least one low head ECCS pump before transition out of E0 and Critical Task E0E: Manually actuate at least the minimum required complement of containment cooling equipment before an extreme (redpath) challenge develops to the containment critical safety function.)

The scenario is terminated once crew has completed actions of EOP E1 and is waiting to transition to Cold Leg Recirc.

L121 NRC ESD104 r1.doc Page 3 of 3 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 1 Page 1 of 30 Event

Description:

Raise reactor power from 10E8 to 2%

Time Position Applicants Actions or Behavior Note: Procedure step numbers are included at the front of each action/comment in parenthesis, where applicable.

(OP L2, Secondary Plant Startup, starting at step 6.1.26)

SRO Reads NOTE regarding PK0403 (Tave deviation from Tref) prior to step 6.1.26 ATC (6.1.26) Slowly raises power to 2% by pulling control rods, observing 3 step pull and wait administrative limit.

SRO Reads NOTE regarding indications for point of adding heat Lowering startup rate Rising steam dump demand, pressurizer level, Tave SRO Provides reactivity oversight while raising power.

ATC (6.1.26.a) Verifies proper plant response at point of adding heat:

Steam dumps begin to modulate AFW flow rises to maintain SG level at programmed level (68%)

ATC (6.1.26.b) Continuously monitors Tave, T, and NI response while raising power.

ATC Stabilizes power at approximately 2% reactor power.

SRO/BOP (6.1.27) Places RM2 High Alarm Setpoint select switch in the MODES 1&6 position.

Proceed to next event after RM2 High Alarm Setpoint select switch set to Mode 1&6 position, per lead examiner.

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 4 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 2 Page 2 of 30 Event

Description:

PT403 Low Time Position Applicants Actions or Behavior Note: AR PK0507, SUBCOOLING MARGIN LO/LOLO and AR PK0509, RVLIS LO LVL, RVLIS/SCMM TROUBLE, both alarm. SRO may use either PK to address the issue provided all applicable TS and ECGs are identified.

All Diagnoses PT403 has failed high from one or more of the following (VB2):

PK0507, SUBCOOLING MARGIN LO/LOLO PK0509, RVLIS LO LVL, RVLIS/SCMM TROUBLE VB3 Indications:

PR403, LOOP 4 HOT LEG PRESS - WIDE RANGE = 0 psig (bottom of scale low)

YI31, SUBCOOL MARGIN MON - TRAIN B = 40oF (bottom of scale low)

If AR PK0507 is entered; otherwise this section is N/A SRO/ATC (1.0) Identifies inputs 1152 (Subcooled Mon Lo Margin From RVLIS A or B) and 1600 (Subcooled Mon LoLo Margin from RVLIS Train B) and goes to section 2.1 for General Actions SRO Reads NOTE regarding P10 prior to step 2.1 SRO/BOP (2.1.1) Observes diverse RCS pressure and temperature indications and determines subcooled margin is NOT low. Identifies PR403 reading bottom of scale as indication of failed instrument (PPC, CC1, CC2, VB2)

SRO (2.1.2) Determines RCS is NOT approaching a saturated condition and continues to next step ALL (2.1.3) Confirms specific instrument failure as PT403:

o (2.1.4.a) Determines failure is associated with RVLIS/SCMM, Train B o (2.1.4.b) Checks trainspecific subcooling indications to confirm failure (PPC, SPDS Train B, YI31 on VB2, PAM4 Display - may use any)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 5 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 2 Page 3 of 30 Event

Description:

PT403 Fails Low (cont)

Time Position Applicants Actions or Behavior (AR PK0507, continued)

SRO Reads NOTE regarding possible Thermocouple Monitoring System failure (PK0515) and determines it doesnt apply SRO (2.1.3) Confirms specific instrument failure as PT403 (continued):

o (2.1.3.c) Notes PK0515 is NOT in alarm and continues to next step o (2.1.3.d) References AP5, Malfunction of Protection or Control Channel as time permits (described later in this section)

SRO (2.1.4) Reviews ECG 7.8, Accident Monitoring Instrumentation for applicability.

Determines LCO is meet (required number of channels and minimum channels operable =1)

If AR PK0509 is entered; otherwise this section is N/A SRO/ATC (1.0) Identifies inputs 1208 (Reactor Vessel Level Lo Train B) and 1209 (RVLIS/SCMM Trouble Train B); goes to section 2.1 for General Actions SRO Reads NOTE regarding O/E on erroneous RVLIS low level alarms prior to step 2.1.1 SRO/BOP (2.1.1) Checks RVLIS on PAM 4 and determines low subcooled margin reading is causing the alarm (PAM4 is located in area behind vertical boards)

SRO (2.1.2) Determines RVLIS is NOT low and continues to next step SRO/BOP (2.1.3) Observes diverse RCS pressure and temperature indications and determines subcooled margin is NOT low (continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 6 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 2 Page 4 of 30 Event

Description:

PT403 Fails Low (cont)

Time Position Applicants Actions or Behavior (AR PK0509, continued)

ALL (2.1.4) Identifies specific instrument failure as PT403:

o (2.1.4.a) Determines failure is associated with RVLIS/SCMM, Train B o (2.1.4.b) Checks PAM4 (Train B) I/O Summary Screen inputs and identifies failed pressure transmitter (PAM4 is located in area behind vertical boards)

SRO (2.1.5) Enters TS 3.3.3.A,Post Accident Monitoring Instrumentation for inoperable channel associated with RCS Pressure (Wide Range) and Reactor Vessel Level Indicating System (RVLIS)functions. Required action: restore to operable status within 30 days If OP AP5 is referenced; otherwise this section is N/A Note: PT403 provides no controlling functions. Shift Foreman may go directly to OP AP5, Attachment 4.1 to identify / confirm previous identification of applicable Tech Specs and ECGs.

SRO Enters TS 3.3.3.A,Post Accident Monitoring Instrumentation for inoperable channel associated with RCS Pressure (Wide Range) and Reactor Vessel Level Indicating System (RVLIS)functions. Required action: restore to operable status within 30 days.

Reviews ECG 7.8, Accident Monitoring Instrumentation for applicability. Determines LCO is meet (required number of channels and minimum channels operable =1)

SRO/BOP Places Out of Service stickers on the following affected equipment:

PR403 (VB2)

RVLIS TRAIN B (PAM 1, behind VB5)

Subcooled Margin Monitor (PAM4, behind VB3)

Proceed to the next event once Tech Specs have been addressed per lead examiner

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 7 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 3 Page 5 of 30 Event

Description:

CCW 12 Overcurrent Trip Time Position Applicants Actions or Behavior ATC Observes PK0109 (CCW Pumps) alarming and informs the Shift Foreman.

ATC/BOP Observes the CCW Pp 12 has a blue OC light illuminated (VB1, left side), and reports condition to Shift Foreman.

Note: The Shift Foreman may implement AR PK0109, or enter OP AP11, "Malfunction of Component Cooling Water System "

(If AR PK0109 is entered; otherwise this section is N/A)

SRO/ATC (1.0) Identifies input 432 (CCW Pps OC Trip) and goes to section 2.4 SRO/BOP (2.4.1) Determines standby CCW pump did not start; (BOP) takes CCW Pp 13 to MAN and starts pump SRO/BOP (2.4.2) Confirms blue indicating light for overcurrent trip is illuminated for CCW Pp 12 (VB1)

SRO (2.4.3) Notes standby CCW Pp 13 has been started and continues to next step SRO/BOP (2.4.4) Dispatches operator to walkdown 4kV Bus G SRO (2.4.4a,b,c) Recognizes breaker reclose attempt is not appropriate (may refer to Ops Policy B2). Directs maintenance to investigate (continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 8 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 3 Page 6 of 30 Event

Description:

CCW 12 Overcurrent Trip (cont)

Time Position Applicants Actions or Behavior (AR PK0109, continued)

SRO (2.4.5) Enters Tech Spec 3.7.7.A - One vital CCW loop inoperable. Required actions:

restore vital loop to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Notes applicability of LCO 3.0.4 (entry into Mode 1 is not allowed until 3.7.7.A exited)

(If OP AP11, Malfunction of Component Cooling Water System, is entered; otherwise this section is N/A)

SRO Determines SECTION A, LOSS OF A CCW PUMP/HIGH CCW SYSTEM TEMP, is the appropriate section SRO/BOP (1) Ensures at least two CCW pumps running; (BOP) takes CCW Pp 13 to MAN and starts it. (VB1, far left side)

SRO/BOP (2) Checks CCW HX outlet temperature is normal (VB1) (It is)

SRO Enters Tech Spec 3.7.7.A - One vital CCW loop inoperable. Required actions: restore vital loop to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Proceed to the next event once standby CCW pump has been started and Tech Specs have been addressed per lead examiner.

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 9 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 4 Page 7 of 30 Event

Description:

AC Lube Oil pump Trips on Thermal Overload Time Position Applicants Actions or Behavior Note: PK1216, Turbine Lube Oil System, will come in prior to PK1206, Turbine. The SRO may elect to follow guidance from either annunciator response as both will direct the crew to OP AP29, Main Turbine Malfunction for problem resolution.

All Diagnoses AC Lube Oil Pump trip from one or more of the following :

VB3 Indications:

AR PK1216, TURBINE LUBE OIL SYSTEM and AR PK1206, TURBINE.

VB4 Indications:

Main Turbine Turning Gear - Supervisory Screen indicates 0 RPM, Turning Gear amps =

0, MN TURB TURN GEAR, MODE SELECT indicator is GREEN (off)

AC Bearing Oil status light indicates pump is not running; PI846, MN TURB BRG OIL PRESS = 0 psig Note: Emergency DC Bearing Oil Pump has 10 psig autostart setpoint. Following appropriate diagnostics, crew may manually start pump prior to procedural direction described in the following steps.

(If AR PK1216 is entered; otherwise this section is N/A)

SRO/ATC (1.0) Identifies inputs 719 (High or low bearing oil header pressure) and 726 (Turb Gen Brg Oil Pp 11 AC OC or UV) and goes to section 2.1 (General Actions)

BOP (2.1.1) Determines Emergency DC Bearing Oil Pump did not automatically start; may start pump manually (VB4, lower left skirt)

SRO (2.1.2) Notes PK0921 is NOT in alarm and continues to next step SRO (2.1.3) Transitions to OP AP29, "Main Turbine Malfunction" (continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 10 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 4 Page 8 of 30 Event

Description:

AC Lube Oil pump Trips on Thermal Overload Time Position Applicants Actions or Behavior Note: If Emergency DC Bearing Oil Pump has been started, PK1206 will clear.

(If AR PK1206 is entered; otherwise this section is N/A)

SRO/ATC (1.0) Identifies input 697 (Main Turb Lo Speed and Turning Gear Selected) and goes to section 2.1 (General Actions)

SRO (2.1.1 & 2.1.2) Determines input condition is not applicable and continues to next step SRO (2.1.3) Transitions to OP AP29, "Main Turbine Malfunction" (OP AP29, Main Turbine Malfunction")

SRO (1) Checks AR PK1211 TURBINE TRIP is OFF (it is)

Note: If crew has not yet started Emergency DC Bearing Oil Pump, AR PK1206 will still be ON. Crew should recognize this as a symptom, not a cause and proceed on to appropriate input.

SRO (2) Checks AR PK1206 TURBINE is OFF. (status dependent on prior actions; see note above)

SRO (3) Checks AR PK1216 TURBINE LUBE OIL SYSTEM is ON; continues to Appendix 3.2 (OP AP29, Appendix 3.2 - TURBINE LUBE OIL SYSTEM (PK1216) )

Note: If crew Emergency DC Bearing Oil Pump was started, step is N/A as input will have cleared. SRO may elect to review Appendix 3.2 to verify all required actions have been completed.

SRO (3) Responds to input 719 (PPC Lube Oil Pressure Alarm)

SRO/BOP (3.1) Determines lube oil pressure is low (VB4, PI846)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 11 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 4 Page 9 of 30 Event

Description:

AC Lube Oil pump Trips on Thermal Overload Time Position Applicants Actions or Behavior (OP AP29, Appendix 3.2 , continued)

SRO/BOP (3.2.1) Starts Emergency DC Bearing Oil pump manually (VB4, lower left skirt)

SRO/BOP (3.2.2) Checks lube oil pressure has returned to normal band (VB4, PI846) (It has)

SRO (4) Responds to input 724 (Turbine Generator Emergency Bearing Oil Pump Running)

SRO/BOP (4.1) Checks bearing oil pressure greater than 20 psig (VB4, PI846). (It is reading slightly over 20 psig)

SRO (5) Responds to input 726 (AC or DC Bearing Oil Pump OC or UV)

SRO (5.1) Contacts maintenance to determine cause of pump trip Proceed to the next event when once Lube Oil Pressure restored per Lead Examiner

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 12 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 5 Page 10 of 30 Event

Description:

Steam Header Pressure Transmitter PT507 Slow Failure Time Position Applicants Actions or Behavior All Diagnoses PT507 failed low from one or more of the following:

CC2 Indications:

Tave, Pressurizer level, Pressurizer pressure rising CC3 Indications:

HC507 demand lowers to 0%

VB3 Indications:

Group I 40% Steam Dump (PCV1, 3, 6, 8) - go closed Dump Demand (UI500) lowers to 0%.

SRO/ATC Takes manual control of HC507 and reopens Group I dump valves to stabilize plant SRO Enters OP AP5, "Malfunction of Eagle21 Protection or Control Channel" (OP AP5, Malfunction of Eagle21 Protection or Control Channel)

SRO/ATC (1) Confirms that Steam Generator pressure was NOT controlling properly in Auto and has been taken to manual (CC3, HC507). Directs Tave be returned to prior steadystate value SRO/BOP (2) Determines that the failure is not Eagle21 related (PK0601 and PK0603 are OFF)

SRO/ATC (3) Determines failure is not associated with a T channel (VB2)

SRO (4) Verifies steam dumps are not open as result of instrument failure or spurious actuation. (Dumps SHOULD be open to maintain temperature for current 2% power conditions. Shift Foreman SHOULD NOT enter RESPONSE NOT OBTAINED column)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 13 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 5 Page 11 of 30 Event

Description:

Steam Header Pressure Transmitter PT507 Slow Failure Time Position Applicants Actions or Behavior (OP AP5, Malfunction of Eagle21 Protection or Control Channel, cont.)

SRO (5) Notifies I&C of the PT507 failure, as time permits SRO Reads CAUTION prior to step 6 SRO (6) Notes requirements to take channel OOS prior to maintenance SRO/BOP (7) Places Outof -Service (OOS) stickers on affected indicators:

o May reference Attachment 4.1 to verify there are no Reactor Trip or Emergency Safeguard Bistable channels that must be tripped per Tech Specs.

o May review Attachment 4.2 for PT507 control functions and indications; places OOS sticker on PR507 (VB3).

Proceed to the next event when crew has stabilized temperature, per the lead examiner.

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 14 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 6 Page 12 of 30 Event

Description:

60 gpm RCS Leak - Loop 1 Cold Leg Time Position Applicants Actions or Behavior ALL Diagnoses RCS leak from one or more of the following:

Drain and/or Sump high level alarms (PK0117, PK1501)

Pzr level lowering (PPC, CC2 recorder, VB2 meters)

Pzr level high; charging flow demand and/or low level deviation alarms (PK0521)

Containment parameters slowly rising (temp, press) (PPC, VB1 recorder, PAMS panels)

Note: Leak ramps in over 1 minute. The crew may raise charging by opening FCV128 and adjusting HCV142 (CC2) in order to maintain pressurizer level prior to entering OP AP1, "Excess RCS Leakage".

SRO Enters OP AP1, "Excess RCS Leakage" (OP AP1, Excess RCS Leakage)

SRO/ATC (1) Determines charging flow and/or pressurizer level NOT normal o Charging flow is elevated and pressurizer level is slowly lowering (CC2)

(1) Adjusts charging and seal flow to maintain pressurizer level o Adjusts seal flows using HCV142 (CC2) to maintain 813 gpm o May raise charging in manual using master level controller (HC459D)(CC2) or flow controller (FCV128)(CC2)

Note: Monitoring Pressurizer level and charging flow NORMAL is a Continuous Action. Associated RNO steps are performed when crew reports applicable conditions exist (i.e. unable to maintain pressurizer level).

SRO/ATC (1) Determines pressurizer level is still lowering (Continuous Action to Monitor)

SRO/BOP (1 RNO) Starts second charging pump (VB2, Lower middle skirt)

(1 RNO) May isolate letdown as pressurizer level continues to drop o Closes 8149C, and closes LCV459/460 (VB2, upper middle skirt)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 15 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 6 Page 13 of 30 Event

Description:

60 gpm RCS Leak - Loop 1 Cold Leg (Continued)

Time Position Applicants Actions or Behavior (OP AP1, Excess RCS Leakage, continued)

ATC (1 RNO) Checks for continuing decrease in pressurizer level o Readjusts charging and seal flow (CC1) o Determines pressurizer level is stable (PPC, VB2, CC2) (Continuous Action to Monitor)

SRO/ATC (2) Checks RCS pressure greater than 2210 psig and stable or rising (VB2) ( 22202250 psig)

SRO/ATC (3) Determines CVCS Makeup can keep up with leak o Makeup Control is in AUTO (CC2) o VCT Level is being maintained within the control band (PPC, VB2 RCDR4 just below DRPI) o Continuous Action to Monitor VCT Level Note: Step (4) actions are directed at identifying and isolating the leak.

SRO/BOP (4.a) Rules out Seal Table leak o RE7 not in alarm(PPC) o No audible alarm from MIDS panel (back of VBs)

SRO/BOP (4.b) Rules out S/G Tube Leak o Main Steam Line Rad Monitors RM71/72/73/74 not in alarm (VB2/PPC) o SJAE Rad Monitor RM15/15R not in alarm (VB2/PPC) o S/G Blowdown Rad Monitor RM23 not in alarm (VB2/PPC) o S/G sample activity RM19 not in alarm (VB2/PPC) o PK1106/17/18 are all out (continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 16 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 6 Page 14 of 30 Event

Description:

60 gpm RCS Leak - Loop 1 Cold Leg (Continued)

Time Position Applicants Actions or Behavior (OP AP1, Excess RCS Leakage, continued)

SRO/BOP (4.c) Rules out RCS inleakage to CCW o CCW Surge Tank Pressure is not in alarm (PK0114) o CCW Surge Tank Level is stable (VB1, upper left just below Monitor Light Box B) o CCW Rad Monitors RM17A/B not in alarm (PPC) (PK1121) o CCW surge tank vent, RCV16, remains open (VB1, lower left)

SRO/BOP (4.d) Rules out pressurizer steam space leak through safeties and PORVs o Pressurizer safety valves and PORVs closed (VB2, upper right panel) o PORV tailpipe temperature is less than 200oF (TI463: VB2, upper right panel)

SRO/BOP (4.e) Notes no indications (indicator or alarm) of reactor vessel flange leakage (VB2 indicator and PK1102 alarm)

SRO/BOP (4.f) Observes that RCP seal leakage is normal (VB2, PPC)

SRO/BOP (4.g) Notes no indication of RCS valve packing leakage (PK0508 alarm)

ALL (4.h) Observes several containment environmental indicators - NOT normal o CFCU drip pan drain level in alarm (PK0117) o Containment sump and reactor cavity sump levels rising (PAM1) o Containment radiation monitors RM11 and RM12 trending upward (PPC) o Containment air temperature/pressure may be slightly elevated (VB1, upper left)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 17 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 6 Page 15 of 30 Event

Description:

60 gpm RCS Leak - Loop 1 Cold Leg (Continued)

Time Position Applicants Actions or Behavior (OP AP1, Excess RCS Leakage, continued)

SRO/BOP (4.h.1 RNO) Contacts Chemistry to sample Reactor cavity samples for increased activity SRO (4.h.1 RNO) Considers making Containment entry to pinpoint sources of RCS leak Note 1: Following step performed if crew diagnostics has not ruled out CVCS leak inside Containment.

Note 2: Letdown isolation may have been completed earlier as part of step 1 RNO, continuous action.

SRO/BOP (4.h.3.ab RNO) Isolates letdown (VB2, upper skirt) o Closes 8149A, B, and C o Closes LCV459 and 460 (4.h.3.c RNO) Isolates charging (VB2, lower skirt) o Closes 8107 and 8108 Note: Performed if letdown/charging isolated in previous step, else, N/A.

SRO/ATC Throttles back charging to stabilize Pressurizer level (CC2)

Reestimates leakrate by throttling FCV128 for flow and maintaining RCP seals 813 gpm using HCV142 (CC2)

Determines leak was not isolated If TS has already been addressed, proceed to the next event once crew determines leak is not isolated, per the lead examiner, else continue to next page

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 18 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 6 Page 16 of 30 Event

Description:

60 gpm RCS Leak - Loop 1 Cold Leg (Continued)

Time Position Applicants Actions or Behavior (OP AP1, Excess RCS Leakage, continued)

Note: If isolated, charging and/or letdown may be placed back in service (as time permits).

SRO/BOP (5.a RNO) Opens 8107 and 8108 (charging header isolation valves) (VB2)

SRO/ATC (4.h.1 RNO) Throttles charging to control pressurizer level (CC2)

Note: If directed to restore letdown, board operators will implement OP B1A:XII, Section 6.2, otherwise section is N/A (continue on next page).

BOP (6.2.2) Ensures adequate pressurizer level o Checks pressurizer level greater than 17% (VB2 upper right, PPC) o Checks PK0521, low level alarm input (544) NOT in o Checks PK0421, high HX room temp (1161) NOT in (6.2.3) Places TCV130 in manual and adjusts to 35%40% demand (VB2, lower middle).

(6.2.4) Ensures letdown isolation valve 8152 is open (VB2, upper middle skirt)

(6.2.5.6) Places letdown back pressure control valve, PCV135, in manual and opens to 50% (VB2, lower middle)

(6.2.7) Opens letdown isolation valves LCV459 and LCV460 (VB2, middle upper skirt)

ATC (6.2.810) Checks FCV128 in manual and raises charging to 87 gpm while maintaining RCP seal injection flow to between 8 GPM and 13 GPM per RCP using HCV142 (CC2)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 19 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 6 Page 17 of 30 Event

Description:

60 gpm RCS Leak - Loop 1 Cold Leg (Continued)

Time Position Applicants Actions or Behavior (OP AP1, Excess RCS Leakage, letdown restoration (OP B1A:XII) continued)

BOP Reads CAUTION prior to step 6.2.11 regarding high letdown temperature and the potential for lifting RV8117.

(6.2.1216) While monitoring PI135 (VB2, upper middle) o Opens letdown orifice isolation valve 8149C to establish flow (VB2, upper middle skirt) o Adjusts PCV135 to control at 350 psig (VB2, lower middle) o Checks letdown flow and pressure stable (approximately 75 gpm with pressure less than 400 psig) (VB2, upper middle) o Returns PCV135controller to AUTO o Checks RV8117 tailpipe temperature to verify relief valve did not lift (TI129, VB2 middle)

ATC (6.2.18) Adjusts FCV128 to return pressurizer level on reference (CC2)

BOP (6.2.20,21) Adjusts TCV130 to maintain normal letdown temperature, then returns controller to AUTO (VB2, lower middle)

(remainder of OP AP1 continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 20 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 6 Page 18 of 30 Event

Description:

60 gpm RCS Leak - Loop 1 Cold Leg (Continued)

Time Position Applicants Actions or Behavior (OP AP1, Excess RCS Leakage, continued from page 16)

Note: Leak size estimate and entry into TS may have been performed earlier at SRO's discretion .

SRO/ATC (5) Estimates leak size (STP R10C and/or available indications)

SRO (5 RNO) Compares leak estimate with T.S. 3.4.13 limits o Enters Tech Spec 3.4.13.A - RCS operational leakage not within limits for reasons other than pressure boundary leakage or primary to secondary leakage.. Required actions: reduce leakage to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Proceed to the next event once TS addressed, per the lead examiner.

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 21 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 7,8,9 Page 19 of 30 Event

Description:

700 gpm SBLOCA on Loop 1 Running Charging Pumps trip on SI, Autostart Fails (CT)

ATWS, Both manual and 13D/E Fail to Open Time Position Applicants Actions or Behavior ALL Diagnoses change in RCS leak from one or more of the following:

Pzr level dropping rapidly (PPC, CC2 recorder, VB2 meters)

Pzr pressure dropping (PPC, CC2 recorder, VB2 meters)

Containment parameters rising (temp, press) (PPC, VB1 recorder, PAMS panels)

Increased rate of change on sump levels (PAMS panel)

Note: Leak ramps in over 1 minute. If not previously done, crew may attempt to isolate letdown prior to initiating a manual Safety Injection (SI).

SRO/ATC ** Initiates manual SI (CC2, far right)

(Critical Task E0D to manually initiate Safety Injection before transitioning to any E1, E2, or E3 series procedure) **

(EOP E0, Reactor Trip or Safety Injection")

Note: Attempts to manually trip the reactor may be done prior to entry into EOP E0 or as part of E0, step 1 RNO.

ALL Performs immediate actions:

(1) Ensure reactor trip:

o Identifies reactor is NOT tripped based on the following:

Rx Trip breakers did NOT open (VB2)

NIs are NOT lowering (CC1)

Rod bottom lights are NOT lit(VB2); moves to step 1 RNO (continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 22 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 8 Page 20 of 30 Event

Description:

ATWS, Both manual and 13D/E Fail to Open (Continued)

Time Position Applicants Actions or Behavior (EOP E0, Reactor Trip or Safety Injection", continued)

ATC Attempts trip using manual switch (CC1 or VB2)

BOP Notes that manual trip already attempted (or may retry manual reactor trip VB2)

Observes that reactor is still critical (same indications as when trip attempted)

Opens breakers for busses 13D and 13E (VB5, lower panel 480 vac bus breakers) to de energize the rod drive MGs; breakers will not open May dispatch operator to open reactor trip breakers locally SRO Notes reactor is still not tripped. Verifies that attempt to manually open 13D/E was unsuccessful and transitions to EOP FRS.1 (EOP FRS1, "Response to Nuclear Power Generation / ATWS")

SRO/ATC (1) Inserts control rods(CC1); SRO directs local opening of RTA/RTB. (May have already been directed by BOP)

SRO/BOP (2) Verifies turbine trip (stop valves closed) (CC3 HMI or VB2 RPS indicator lamps)

SRO/BOP (3) Checks AFW status

a. Both MDAFPs running (VB3, left skirt)

b. TDAFP is off and is not required ( VB3, center skirt)

SRO Reads CAUTION prior to step 4.a regarding Main Feed Pumps tripping on SI; SI is already in and Main Feed Pumps are tripped (continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 23 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 8 Page 21 of 30 Event

Description:

ATWS, Both manual and 13D/E Fail to Open (Continued)

Time Position Applicants Actions or Behavior (EOP FRS1, "Response to Nuclear Power Generation / ATWS", continued)

Note 1: Valves are already aligned for Emergency Boration as result of SI, however CCP 13 and the running ECCS charging pump (started in Event 6 as part of OP AP1) tripped just after the SI; the remaining ECCS CCP failed to autostart.

Note 2: The Critical Task to start ECCS CCPs (Event #9) is NOT associated with establishing Emergency Boration flow to the RCS since power is < 5% based on initial plant conditions. Criteria to manually start ECCS CCPs is defined by DCPP Critical Task Identification Number E0I, and is associated with a SBLOCA where RCS pressure is below highhead ECCS pump shutoff head and both highhead ECCS CCPs failed to start automatically. Details for this Critical Task can be found on page 23.

SRO/BOP (4.a) Checks Emergency Boration initiated:

1. 8805A OR 8805B OPEN (VB2center skirt; both are open)

2. LCV112 B OR LCV112C CLOSED (VB2center skirt; both are closed)

3. Verifies AT LEAST 90 GPM charging flow (charging injection flow: VB2just left of DRPI)

Manually starts available ECCS CCP (CCP1 1 or CCP 12 (if failed autostart not previously identified) (VB2 - center skirt)

Checks for adequate flow SRO/BOP (4.b) Checks pressurizer pressure less than 2335 PSIG (VB2, upper right)

SRO/BOP (5) Verifies Containment Vent Isolation (CVI) by checking CVI valve positions on VB4 or far right portion of Monitor Light Box B on VB1 (all valves are closed)

SRO/BOP (6.a) Checks no personnel in Containment (was part of Turnover; may not voice)

(6.b) Announces ATWS on Public Address System (continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 24 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 8 Page 22 of 30 Event

Description:

ATWS, Both manual and 13D/E Fail to Open (Continued)

Time Position Applicants Actions or Behavior (EOP FRS1, "Response to Nuclear Power Generation / ATWS", continued)

Note: Portions of EOP E0 are implemented in parallel with EOP FRS.1. The implemented steps of EOP E0 appear below. Body of EOP FRS.1 is continued on page xx.

SRO (7) Notes SI actuated and directs RO (usually the BOP) to IMPLEMENT the following:

o EOP E0, Steps 1 through 4 o EOP E0, Appendix E, Steps 1 through 10 (Implementation of EOP E0, Steps 14)

BOP (1) Verifies reactor trip (trip bkrs open (VB2 upper left), rods on bottom (VB2 upper left DRPI panel), NIs decreasing (CC1 left))

BOP (2) Verifies turbine trip (stop valves closed) (CC3 HMI or VB2 RPS indicator lamps)

BOP (3) Checks vital 4kv busses (VB4, vital busses F/G/H have white lights on mimic busses)

BOP (4.a) Checks if SI actuated (PK0821 ON)

(4.b) Checks VB1 red light and/or train equipment to verify both trains actuated)

(Implementation of EOP E0,Appendix E, Steps 110)

BOP (1a) Checks no personnel in Containment (part of turnover; may not voice)

(1b) Announces trip/SI on PA system Note: Unit is currently aligned for backfeed from 500kV. Tripping the Unit will result in transfer to Start Up (230 kV).

BOP (2) Checks main generator - tripped (PK1401 ON, output bkrs open, and exciter field bkr open, CC3 right side); Determines generator is NOT tripped (2 RNO) Determines Unit is still backfeeding (PK1401 if OFF) and goes to step 3 (continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 25 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 8 Page 23 of 30 Event

Description:

ATWS, Both manual and 13D/E Fail to Open (Continued)

Time Position Applicants Actions or Behavior (Implementation of EOP E0,Appendix E, Steps 110, continued)

BOP (3 & 4) Verifies Phase A and containment vent isolation complete (VB1, Monitor Light Box B status lights, red lights ON, white lights OFF)

Note: Critical Task to start ECCS CCP may have be completed during Emergency Boration (step 4 of FRS.1) or by crew if identified earlier as failed autostart.

BOP (5) Verifies ESF (SI) actuation complete (Monitor Light Box CSI, red light ON, white lights, some ON) o Identifies white lights associated with ASW and ECCS charging pumps

• • Manually starts available ECCS CCP (CCP1 1 or CCP 12)

(Critical Task E-0-I: Establish flow from at least one highhead ECCS pump before transition out of E0) **

BOP (6) Verifies Feedwater isolation complete (normal FWI portion is complete, with red light ON, and white lights OFF) (S/G portion: red light is ON, white lights OFF)

BOP (7 & 8) Checks containment spray, Phase B, and main steam isolation - NOT required (red lights are OFF for ESF for these on VB1, and white lights are OFF)

BOP (9) Checks AFW status (MDAFPs running, TDAFP is off and not required, VB3 center area); verifies either min of 435 gpm flow (VB3 center) or S/G level > 15% (VB3 center)

BOP (10) Verifies ECCS flows (charging injection (VB2 upper panel left), SI, RHR (both on VB1 upper panel); expected is that only CCPs will be delivering flow at current RCS pressure (continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 26 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 8 Page 24 of 30 Event

Description:

ATWS, Both manual and 13D/E Fail to Open (Continued)

Time Position Applicants Actions or Behavior (Implementation of EOP E0,Appendix E, Steps 110, continued)

BOP Reports ESF and AFW status to SFM (EOP FRS1, "Response to Nuclear Power Generation / ATWS", continued from page 22)

SRO/ATC (8) Checks expected trips have occurred

a. Rx Trip Breakers OPEN (VB2, upper left)

b. Reverifies all four turbine stop valves CLOSED (CC3 HMI or VB2, RPS indicator lamps)

SRO/ATC (9) Checks Rx Subcritical

a. Power Range NI's LESS THAN 5% (CC1)

b. Negative startup rate on Intermediate Range Channels (CC1)

c. Goes to Step 19 (procedurally directed)

Note: Actions of Step 19 (Shutdown Margin verification) are directed by SRO through Shift Manager.

SRO/BOP (19) Verifies adequate Shutdown Margin

a. Contacts Chemistry to sample RCS for Boron Concentration

b. Requests performance of STP R19, Shutdown Margin Calculation

c. Notes need to borate to shutdown concentration (accomplished through ECCS injection from RWST).

SRO (20) Returns to first step of E0, REACTOR TRIP OR SAFETY INJECTION

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 27 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 7,9 Page 25 of 30 Event

Description:

700 gpm SBLOCA on Loop 1 (continued)

Running Charging Pumps trip on SI, Autostart Fails (continued) (CT)

Time Position Applicants Actions or Behavior (EOP E0, Reactor Trip or Safety Injection")

SRO Implements EOP E0, Reactor Trip or Safety Injection ALL Crew reverifies E0 immediate actions (normal response, now that trip bkrs are open) o Verifies reactor trip (trip bkrs open, rods on bottom, NIs decreasing) o Verifies turbine trip (stop valves closed (CC3 HMI or VB2 RPS indicator lamps) o Checks vital 4kv busses (VB4, vital busses F/G/H have white lights on mimic busses) o Checks SI actuated (PK0821 ON)

Note: Steps 110 may have been implemented earlier and do not need to be repeated.

SRO (5) Directs App E implemented (usually to BOP)

BOP Implements App E:

(1a) Checks no personnel in Containment (part of turnover; may not voice)

(1b) Announce trip/SI on PA system (2) Checks main generator - tripped (PK1401 ON, output bkrs open, and exciter field bkr open, CC3 right side); Determines generator is NOT tripped (2 RNO) Determines Unit is still backfeeding (PK1401 if OFF) and goes to step 3 (3 & 4) Verifies Phase A and containment vent isolation complete (VB1, Monitor Light Box B status lights, red lights ON, white lights OFF)

(5) Verify ESF (SI) actuation complete (ESF/SI red light ON, white lights some ON);

o Identifies white lights associated with ECCS charging pumps

• • Manually starts available ECCS CCP (CCP1 1 or CCP 12)

(Critical Task E-0-I: Establish flow from at least one highhead ECCS pump before transition out of E0)**

(continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 28 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 8&9 Page 26 of 30 Event

Description:

700 gpm SBLOCA on Loop 1 (continued)

Time Position Applicants Actions or Behavior (EOP E0, Appendix E, continued)

BOP (6) Verifies Feedwater isolation complete (normal FWI portion is complete, with red light ON, and white lights OFF) (S/G portion: red light is ON, white lights OFF)

(7 & 8) Checks containment spray, Phase B, and main steam isolation - NOT required (red lights are OFF for ESF for these on VB1, and white lights are OFF)

(9) Checks AFW status (MDAFPs running, TDAFP does not start; verifies either min of 435 gpm flow (VB3 center) or S/G level > 15% (VB3 center)

(10) Verifies ECCS flows (charging injection (VB2 upper panel left), SI, RHR (both on VB1 upper panel)

(11) Reports ESF and AFW status to the Shift Foreman (12 & 13) Checks excess letdown - not in service (8166/8167 closed); turns on aux bldg vent charcoal filter preheater (VB4 lower panel, left side)

(14) Checks secondary systems (MFPs tripped (VB2, green lights ON), verifies only one CB Pp set running, condenser is available) (VB3)

(15) Verifies proper operation of Aux Bldg and Control Rm vent systems (VB4 vent status light panel white lights); verifies containment iodine fans secured (VB4, lower panel)

(16 21) Verifies available DGs running normally (VB4, freq (60), volts (120), speed (900)); verifies vital batteries supplied by chargers (charger and bus volts on VB5, upper panel middle/lower area); verifies MSRs reset (CC3 Triconex HMI); throttles RCP seal injection flows to normal (FCV128, to 813 gpm each, CC2); checks PK1104 NOT IN (SFP alarm); notifies Shift Foreman of completion (EOP E0, Reactor Trip or Safety Injection", continued)

SRO/ATC (6) Checks RCS temperature - stable (temps may be dropping due to SBLOCA/ECCS flows; AFW may be throttled back (VB2 meters, upper panel lower area)

SRO/ATC (7) Checks Pzr PORVs and Pzr safeties (closed) / PORV block valves (all open), and no sonic flows on safeties/PORVs (tailpipe temps might be slightly elevated, but consistent with containment temperatures from the SBLOCA) (VB2 - upper panel, far right); checks Pzr sprays closed (CC2)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 29 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 7 Page 27 of 30 Event

Description:

700 gpm SBLOCA on Loop 1 (continued)

Time Position Applicants Actions or Behavior (EOP E0, Reactor Trip or Safety Injection", continued)

Note: RCPs may already be tripped based on E0 fold out page guidance for RCP Trip Criteria SRO/ATC (8) Checks RCP trip criteria - observes RCS pressure (may or may not be < 1300 psig; stops RCPs if < 1300 psig (VB1 and VB2) (Continuous Action)

ATC/BOP (9) Checks for faulted S/Gs o Faulted - checks all S/G pressures on VB3 (no uncontrolled drop or depressurized)

ATC/BOP (10) Checks ruptured S/Gs Ruptured - checks RE71/72/73/74 and RE15/19 recorders on VB2 (and PPC); (all normal), and PK1106/17/18 (all OFF); may request samples SRO/ALL (11) Checks RCS intact (it is not) (note: only one valid abnormal reading needed to transition from E0) o (11a) Checks containment pressure normal (it is elevated) (VB1 meters, PPC) o (11b) Checks containment sump level normal (already be elevated) (VB1 meters, PAMS) o (11c) Checks containment radiation normal (elevated) (PK1121 and PK1119)

(11 RNO) Places 2nd ASW/CCW HX in service (opens FCV603 and FCV431, VB1 far left)

SRO Checks Critical Safety Function Status Trees and transitions to EOP E1, Loss of Reactor or Secondary Coolant (continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 30 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 7 Page 28 of 30 Event

Description:

700 gpm SBLOCA on Loop 1 (continued)

Time Position Applicants Actions or Behavior (EOP E1, "Loss of Reactor or Secondary Coolant")

SRO/ATC (1) Checks RCPs tripped (already done, VB2)

(1) Continues to maintain RCP seal flows 813 gpm (FCV128) (CC2)

SRO/ALL (2 & 3) Checks for faulted/ruptured S/Gs o Faulted - checks all S/G pressures on VB3 (not uncontrolled drop/depressurized; all are dropping slowly, as the primary is now the heat sink for the secondary) o Ruptured - checks RE71/72/73/74 and RE15/19 recorders on VB2 (and PPC; no upward trends or spikes, unless containment shine is noted), and PK1106/17/18 (alarms not in); requests chemistry to sample S/Gs for activity (as follows, if done):

Verifies phase A containment isolation reset (VB1)

Opens FCV584 (air to containment) (VB4, lower left)

Opens blowdown isolation valves inside containment (FCV760, 761, 762, 763)

May require blocking low steamline pressure MSI/SI (due to low steamline pressures); two block switches on CC2 taken to block position BOP (4) Maintains S/G levels 20 [25] 65% (VB3, AFW controls)

SRO/ATC (5) Check Pzr PORVs (closed) / blocks (open/powered) (VB2 - upper panel, far right)

SRO/ATC (6) Verifies containment spray in service (PK0118 OFF, containment spray is not in service, and not required) (VB1)

SRO/ALL (7) Checks ECCS termination criteria (not met, SCM is < 20F, Pzr level is also below 12% [40%])

(continued on next page

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 31 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 7 Page 29 of 30 Event

Description:

700 gpm SBLOCA on Loop 1 (continued)

Time Position Applicants Actions or Behavior (EOP E1, "Loss of Reactor or Secondary Coolant", continued)

Note: If RCS pressure is still stabilized at this point, RHR pumps will be shut down [until needed later] (if pressure going down, they will be left in service); either condition is satisfactory for now.

SRO/ATC (8) Maintains RHR pumps running, and aligns cooling (may open FCV364 and 365 now

[will open in later step], VB1 far left lower)

SRO/ALL (9) Checks S/G pressures (VB3) and RCS pressure consistent with LOCA (they are, although RCS pressure may be almost stable at saturation)

SRO/BOP (10) Check if DGs should be stopped (busses are powered from Aux and S/U, so they can be secured) (VB4)

SRO/ATC (11.a, b) Verifies recirc capability (RHR Pps have power (VB1), checks aux bldg rad levels (RM04, 06, 10, 13 show no elevated readings) (PPC, back RMS panels), and checks RHR systems alarms (PK0216 and PK0217 off) for intersystem LOCA (ISLOCA no indications other than for SBLOCA)

SRO/ATC (11.c) Checks RHR Pps running, and establishes cooling to the heat exchangers (by opening FCV364/365, as noted above), if not already open (and pumps running) (all on VB1)

SRO/ALL (11.d) Implements App P (2nd/manual check of ESF status lights; may be a lower priority)

ALL (11.e, f, g) Requests RCS samples; monitors turbine status (oil Pps, coastdown, etc),

checks SFP status (continued on next page

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 32 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 7 Page 30 of 30 Event

Description:

700 gpm SBLOCA on Loop 1 (continued)

Time Position Applicants Actions or Behavior (EOP E1, "Loss of Reactor or Secondary Coolant", continued)

SRO (12) Determines that post LOCA cooldown procedure is appropriate (RCS pressure is >

300 psig [VB2, PPC, CC2], and no RHR flow [VB2])

SRO Transitions to EOP E1.2, PostLOCA Cooldown and Depressurization, and may perform a procedure transition brief Terminate the scenario once transition is made to EOP E-1.2, per the lead examiner.

• • Critical Task L121 NRC Sim Exam 01 r0a.doc Page 33 of 39 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 2 Event No.: 1 Page 1 of 23 Event

Description:

RM12 failure (containment gas rad monitor) (TS)

Time Position Applicants Actions or Behavior Note: Procedure step numbers are included at the front of each action/comment in parenthesis, where applicable.

ATC Observes PK1121 (High Process Radiation) alarming and informs the Shift Foreman.

ATC/BOP Check PPC for upscale radiation monitor reading and trends o Notes RM12 reading top of scale, with instantaeous rise.

o No other rad monitors are in alarm (PK1121, High Process Radiation)

SRO/ATC Enters PK1121, High Process Radiation (1.0) Identifies input 1066 (Process Monitor HiRad) and goes to section 2.1, General Actions.

SRO/ATC (2.1.1) Checks annunciator printout (or A&E viewer / Ronan display) to verify alarm input is RM12 ALL (2.1.2) Investigates causes of high radiation alarms o Check PPC for upscale radiation monitor reading and trends Notes RM12 reading top of scale, with instantaeous rise.

No other rad monitors are in alarm o May check for other indications of possible RCS leak Pzr level drop and/or charging letdown mismatch (ATC, CC2, PPC)

Containment pressure and temperature (recorder, VB1, left, lower)

Containment sump levels (PAMS panel behind VB5)

Note: Steps 2.1.32.1.9 require no action if cause of alarm is an instrument failure.

SRO (2.1.39) Determines alarm is result of instrument failure; no action required and goes to associated individual input step (2.4)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 02 r0a.doc Page 4 of 31 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 2 Event No.: 1 Page 2 of 23 Event

Description:

RM12 failure (containment gas rad monitor, continued) (TS)

Time Position Applicants Actions or Behavior (PK1121, High Process Radiation, continued)

SRO/BOP (2.4.1) Checks digital radition monitor display for overrange (behind VBs)

SRO (2.4.2, 3) Notes RE12 was not previously in alarm (no reflash), and has no associated automatic actions (2.4.4) Notes step does not apply (for RE3 only)

SRO (2.4.5) Notes RM12 has failed (now out of service); directs CFCU Drain Collection to be put in service per OP H2:I Section 6.5, Operating the CFCU Drain Collections System (OP H2:I Section 6.5, Operating the CFCU Drain Collections System)

BOP (6.5.1) Places drain collection in service:

o Aligns CFCU Drain Valve Selector Switch to position corresponding to CFCU currently operating in SLOW speed (VB1, middle left under CFCU controls)

Reports that Drain Collection is in service (PK1121, High Process Radiation, continued)

SRO Reads Notes regarding expected RM response to valid RCS leak (2.4.6) Determines there are no other indications corroborating an active RCS leak.

(continued on next page)

• • Critical Task L121 NRC Sim Exam 02 r0a.doc Page 5 of 31 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 2 Event No.: 1 Page 3 of 23 Event

Description:

RM12 failure (containment gas rad monitor, continued) (TS)

Time Position Applicants Actions or Behavior (PK1121, High Process Radiation, continued)

SRO Reviews TS 3.4.15.C, RCS Leakage Detection Instrumentation o requires one containment atmosphere particulate rad monitor and either the containment atmophere gaseous rad monitor or CFCU condensate collection monitor to be operable Notifies I&C of RM12 failure (OP H2:I Section 6.5, Operating the CFCU Drain Collections System)

BOP Reports that Drain Collection is in service Proceed to the next event once Tech Specs are addressed, per Lead Examiner

• • Critical Task L121 NRC Sim Exam 02 r0a.doc Page 6 of 31 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 2 Event No.: 2 Page 4 of 23 Event

Description:

CCP 11 Overcurrent Trip (TS)

Time Position Applicants Actions or Behavior ALL Diagnoses CCP 11 OC trip using one or more of the following indications:

CCP 11 blue OC light is lit, and the pump is no longer running (VB2, lower center)

PK0418, CCP 11 alarm (OC trip input)

PKs 0501 - 0504, due to RCP seal low flow alarms Observes low charging flow and/or RCP seal flows (CC2, PPC, VB2 meters)

Observes letdown has isolated (VB2, upper skirt)

BOP/ATC May check CCW flow to RCP thermal barriers (VB1, left)

May check RCP parameters to verify cooling (PPC picture, VB2 meters)

Note: The Shift Foreman may enter any of the annunciator response procedures for the low RCP seal flows (not expected); if used, will be directed to go to AP17 for actions.

SRO Implements OP AP17, Loss of Charging, Section A, Loss of All Charging (OP AP17, "Loss of Charging")

SRO/BOP (1.a ) Verifies suction flow path o VCT level and pressure - normal (VB2, PPC) o LCV112B and LCV112C open (CCP suction) (VB2, lower center)

SRO (1.b) Determines that pump venting not required at this time SRO/BOP (1.c) Verifies 8105 and 8106 open (CCP recircs) (VB2, lower center)

SRO/ATC (1.d) Closes FCV128 (CC2 right side)

SRO/BOP (1.e) Starts standby CCP (specific pump specified by SFM) (VB2, lower center)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 02 r0a.doc Page 7 of 31 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 2 Event No.: 2 Page 5 of 23 Event

Description:

CCP 11 Overcurrent Trip, continued (TS)

Time Position Applicants Actions or Behavior (OP AP17, "Loss of Charging", continued)

SRO/ATC (1.f) Establishes charging flow to RCP seals only (all CC2, right side)

Throttles FCV128 open to establish 813 gpm each to RCP seal Throttles HCV142 to closed or nearly closed SRO/ATC (1.g,h) Adjusts charging in manual to return level to program(FCV128) (CC2)

SRO/ATC (2) Adjusts HCV142 to maintain RCP seal flows 813 gpm (CC2)

SRO/ATC (3.a) Checks Pzr level > 17% (it is) (CC2 recorder, PPC, VB2 meter)

SRO/BOP (3.b) Checks letdown in service (it is NOT) (VB2, upper left skirt)

SRO (3.b RNO) Directs letdown be placed in service per App R ALL May perform reactivity brief prior to placing letdown in service (continued on next page)

• • Critical Task L121 NRC Sim Exam 02 r0a.doc Page 8 of 31 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 2 Event No.: 2 Page 6 of 23 Event

Description:

CCP 11 Overcurrent Trip, continued (TS)

Time Position Applicants Actions or Behavior (OP AP17, "Loss of Charging", App R)

BOP/ATC Reads CAUTION prior to step 1, App. R regarding high letdown temperature and the potential for lifting RV8117.

o (1.a) Checks FCV355 open (it is) (VB1, lower left skirt) o (1.b) Opens TCV130 to 40% demand (VB2, lower middle) o (1.c) Ensures 8149A,B, and C are closed (they are) (VB2, upper middle skirt) o (1.d) Opens LCV459 and LCV460 (VB2, upper middle skirt) o (1.e) Checks 8152 open (it is) (VB2, upper middle skirt) o (1.f) Opens PCV135 to 60% demand (VB2, lower middle) o (1.g) Adjusts charging to 87 gpm (ATC) (CC2) o (1.h) Opens 8149B or C - 75 gpm orifice stop valve (VB2, upper middle skirt) o (1.i) Adjusts PCV135 for 350 psig on PI135 (VB2, upper middle). Places in AUTO if desired o (1j) Adjusts TCV130 for 90oF110oF on TI130 (VB2, upper middle). Places in AUTO if desired o (1k) Checks RV8117 Letdown Relief Valve tailpipe temperature to verify relief valve is seated (TI129 VB2, middle) o (1l) Notifies Shift Foreman that normal letdown has been restored (OP AP17, "Loss of Charging", continued)

SRO/ATC (3.c) Adjusts charging in manual to return level to program by throttling FCV128 for flow, and maintaining RCP seal flows 813 gpm using HCV142 (CC2)

SRO/BOP (4) Checks VCT makeup system in auto (it is) o (4.a) Checks VCT level between 14% and 87% (it is) (VB2 meter, CC2 PPC) o (4.b) Checks VCT press 1560 psig (it is) (VB2 meter/recorder, CC2 PPC)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 02 r0a.doc Page 9 of 31 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 2 Event No.: 2 Page 7 of 23 Event

Description:

CCP 11 Overcurrent Trip, continued (TS)

Time Position Applicants Actions or Behavior (OP AP17, "Loss of Charging", continued)

SRO/ATC (4.c,d) Checks Makeup system set for current boron and in AUTO (it is; no changes needed) (CC2 M/U HMI)

SRO/BOP (4.e) Verifies instrument air is available (it is) (VB4 lower left area)

SRO/BOP (5) Checks LCV112B and LCV112C open, providing suction from the VCT(VB2, middle skirt)

SRO (6) Reviews Tech Specs and enters Tech Spec 3.5.2.A - One train of ECCS inoperable.

Required actions: restore train to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Proceed to the next event once Tech Specs are addressed, per Lead Examiner

• • Critical Task L121 NRC Sim Exam 02 r0a.doc Page 10 of 31 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 2 Event No.: 3 Page 8 of 23 Event

Description:

Seal Injection Filter 11 Plugged Time Position Applicants Actions or Behavior ALL Diagnoses plugged seal injection filter using one or more of the following indications:

Lowering seal injection flow to all RCPs (VB2, middle right)

PKs 0501 - 0504, due to RCP seal low flow alarms PKs 0422 for High RCP Seal injection Filter DP BOP/ATC May check CCW flow to RCP thermal barriers (VB1, left)

May check RCP parameters to verify cooling (PPC picture, VB2 meters)

ATC Attempts to raise seal injection flow using HCV142. (CC2)

Identifies potential impact on Pressurizer level (charging flow lowering as more flow is directed toward seals); readjusts to maintain pressurizer level.

SRO/ANY Identifies input 498 for PK0422, "RCP Seal Injection Filter DeltaP Hi" SRO Enters PK0422, CP Seal Injection Filter DeltaP Hi (1) Determines input is for RCP Seal Injection Filter 11 and goes to General Actions section.

SRO Reads CAUTION regarding 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> limit for operating RCPs without injection flow Note: If seal flow adjustment was previously attempted, it is not necessary to repeat action SRO/ATC (2.1.1) Attempts to throttle HCV142 to establish 813 gpm seal injection flow to each RCP.

o Recognizes charging flow lowering with no change in seal flow o Readjusts seal flow to maintain pressurizer level (continued on next page)

• • Critical Task L121 NRC Sim Exam 02 r0a.doc Page 11 of 31 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 2 Event No.: 3 Page 9 of 23 Event

Description:

Seal Injection Filter 11 Plugged (continued)

Time Position Applicants Actions or Behavior (PK0422, "RCP Seal Injection Filter Delta P Hi" continued)

SRO Reads NOTE prior to step 2.1.2 regarding potential impact on seal and bearing temperatures.

SRO/ANY (2.1.2) Directs board operator to monitor RCP radial bearing temperatures on the PPC SRO/BOP (2.1.3) Directs Nuclear Operator to swap seal injection filter 11 to filter 12 per OP B IA:I, Section 6.3 SRO (2.1.4) Contacts Maintenance to replace seal injection filter 11.

SRO/ATC Directs ATC to reestablish RCP seal flow, once filter is swapped.

Proceed to the next event once seals injection has been returned to normal, per Lead Examiner.

• • Critical Task L121 NRC Sim Exam 02 r0a.doc Page 12 of 31 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 2 Event No.: 4 Page 10 of 23 Event

Description:

4kV Bus H Differential Trip Time Position Applicants Actions or Behavior ALL Diagnoses loss of 4KV Bus H from one or more of the following:

Numerous equipment alarms associated with the loss of 4KV Bus H equipment PK1616 and PK1617 4KV Bus H alarms (both related to loss of bus)

Blue light on 4KV Bus H (diff) (VB4)

White lights out on 4KV and 480 vac Bus H (VB4)

BOP Diagnoses differential trip on Bus H due to alarms (above), blue light on Bus H, and loss of power available white light on Bus H (VB4, middle skirt)

SRO Implements OP AP27, Loss of Vital 4kV and/or 480V Bus (OP AP27, "Loss of Vital 4kV and/or 480V Bus")

SRO/BOP (1) Checks vital 4KV busses energized (only Bus H OFF; other white bus lights checked ON) (VB4, skirt)

SRO/ATC (2) Checks DRPI energized (aligned to normal power supply, Bus F, no impact) (VB2, upper left)

BOP (3) Confirms 4KV Bus H is tripped on differential (VB4, blue light on bus)

SRO (4) Notifies maintenance of bus fault ATC/BOP (5) Checks alternate pumps running on 4kV busses; all required pumps are still running (continued on next page)

• • Critical Task L121 NRC Sim Exam 02 r0a.doc Page 13 of 31 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 2 Event No.: 4 Page 11 of 23 Event

Description:

4kV Bus H Differential Trip (continued)

Time Position Applicants Actions or Behavior (OP AP27, "Loss of Vital 4kV and/or 480V Bus", continued)

SRO/BOP (6) Checks 480 vac vital busses - only bus 1H deenergized (VB4 - white power light for each 480 vac bus)

BOP (Att 4.3) Implements Attachment 4.3 for bus 1H:

o (1.a) Places PCV456C Pzr PORV in CLOSE position (due to 8000C loss of power)

(VB2, upper panel, far right), and refers the Shift Foreman to TS 3.4.11 (TS 3.4.11.C (1 hr))

o (1.b) Assigns personnel to perform necessary nuclear operator actions, (Battery Charger transfer is a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> action.) (Note: Step 2 actions will be calls to the field)

(2.a) Initiate performance of D/G margin assessment for additional bus loading per OP O13 (2.b) Transfer of following equipment to backup power (as required):

Battery 13 to charger 131 per OP J9:II Instrument AC PY15 per OP J10:VII Diesel Fuel Transfer Pp 01 per OP13 Control Room Power per O13 Control Room Vent Power Panel A2 switch no. EPCA2 per OP O13 (2.c) Verify Control Room Vent Power Panel D2 switch no. EPCD2 is NOT on backup power supply per OP O13 (2.d) Verify Aux Bldg Switchgear Supply and Exhaust Fans S43 and E43 are running (redundant equipment) o (1.c) Verifies Pressurizer heater group 13 and Battery 11 and 12 NOT on backup power supplies (they are not) o (1.d) Verifies redundant equipment on the other 480V buses is running Starts Makeup Water Transfer Pump 02 (VB3, lower middle); all other redundant equipment is running o (1.e) Verifies other minor equipment status (as time permits)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 02 r0a.doc Page 14 of 31 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 2 Event No.: 4 Page 12 of 23 Event

Description:

4kV Bus H Differential Trip (continued)

Time Position Applicants Actions or Behavior (OP AP27, "Loss of Vital 4kV and/or 480V Bus", continued)

SRO (7) Evaluates Tech Specs and ECGs (longer specs as time permits, per lead examiner):

o TS 3.4.11.C - PORV block valve (1 hr) o TS 3.8.1.B - AC Sources - operating (STP I1C w/I 1 hr, continues to be in effect (D/G 11 already OOS))

o TS 3.8.4.A - DC Sources - operating (restore batt charger) (2 hrs) o NOTE: may not have time to look up all (longer time limit) Tech Specs prior to next event o TS 3.6.3.A & C - Containment isolation valves (4 hrs, 72 hrs) o TS 3.8.9.A - Distribution system (vital bus) - operating (8 hrs to restore) o TS 3.7.3.A - MFIVs, MFRVs & bypasses, etc (72 hrs) o TS 3.8.7 - Inverters (only a trouble alarm at this point, so none INOPERABLE) o ECG 23.6.A - Vital 480 vac swgr class 1 ventilation (30 days)

SRO/BOP (8) Check unloaded DGs (N/A based on scenario setup - D/G 11 OOS)

SRO (9) Checks OPERABILITY of ESF equipment (pumps, valves lost due to Bus H loss)

SI Pp 12, RHR Pp 12, and CS Pp 12 all OOS (VB1, skirt)

AFW 12 OOS (but was cleared as part of setup)

FCV440 (MFW Isolation Valve)

Proceed to the next event once the Tech Spec actions above have been addressed, per the lead examiner.

• • Critical Task L121 NRC Sim Exam 02 r0a.doc Page 15 of 31 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 2 Event No.: 5 Page 13 of 23 Event

Description:

Slow Vacuum Leak on Main Turbine Time Position Applicants Actions or Behavior ATC/BOP Observes slowly degrading condenser vacuum (condenser pressure rising: VB3, PPC, CC2; MW lowering: CC3, PPC) (PK1011)

SRO Implements OP AP7, Degraded Condenser, Section A: Loss of Condenser Vacuum (OP AP7, "Degraded Condenser, Section A")

SRO Reads CAUTIONS regarding Attachments to be performed if both CWPs are lost, and guidance to trip reactor if actions to stabilize the plant appear unlikely to succeed Note: ATC and/or BOP will be directed to monitor the turbine for how close they are getting to the turbine trip setpoint. They can see both vacuum and the setpoint on the turbine controller screens (CC3), and can also compare condenser vacuum with the Attachment 2 "curve" in OP AP7, showing power level vs allowable turbine operation area.

SRO/BOP (1) Checks condenser pressure less than turbine trip setpoint (Attachment 2) (It is)

SRO/BOP (2) Directs load reduction to maintain Condenser pressure below turbine trip setpoint (Attachment 2 limits)

Note: Ramp may be started by implementing OP AP25, or by using ramp guidance lamicoid on CC3, and continuing with OP AP7. Follow up with OP AP25 procedural guidance should be completed as time permits.

SRO Implements OP AP25, Rapid Load Reduction (OP AP25, Rapid Load Reduction)

SRO Enters OP AP25, Rapid Load Reduction (1.a) Determines runback/programmed ramp is not in progress (may not vocalize, since this ramp is initiated by the crew)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 02 r0a.doc Page 16 of 31 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 2 Event No.: 5 Page 14 of 23 Event

Description:

Slow Vacuum Leak on Main Turbine (continued)

Time Position Applicants Actions or Behavior (OP AP25, "Rapid Load Reduction", continued)

SRO/BOP Starts load reduction (guidance is also on lamicoid pegboard on CC3):

o (1.b) Places MW and IMP feedbacks in service (all on Triconex turbine HMI, CC3) o (1.c) Sets load target (per the Shift Foreman) o (1.d) Sets ramp rate (per the Shift Foreman) o (1.e) Pushes GO SRO/BOP (1.f) Contacts chemistry if 15%/hr shut down rate is exceeded SRO/ATC (2) Ensures control rods are inserting in AUTO (CC1)

(3) Turns Pressurizer heaters on (CC1)

(4) Checks charging adequate to prevent flashing in the letdown system; may take manual control to ensure adequate flow (CC2)

SRO/BOP (5) Ensures DFWCS is controlling S/G levels in AUTO (MFW control/bypass valves; MFPs all in AUTO) (CC2)(VB3)

SRO/ATC (6) Determines boration requirements; borates RCS as needed) (CC2)

SRO/BOP (7) Checks MFP suction pressure greater than 260 psig (VB3)

SRO/ATC (8) Checks Tave trending to Tref (PPC, CC1)

(9) Checks Pressurizer pressure and level trending to programmed band (PPC, CC2)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 02 r0a.doc Page 17 of 31 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 2 Event No.: 5 Page 15 of 23 Event

Description:

Slow Vacuum Leak on Main Turbine (continued)

Time Position Applicants Actions or Behavior (OP AP7, "Degraded Condenser, Section A", continued)

Note: Vacuum leak is stopped approximately 1 minute following PA; Maintenance will call Control Room identifying the cause SRO/BOP (3) Makes PA announcement regarding loss of condenser vacuum (directs plant personnel to stop any activity that could have impact).

SRO/BOP (4) Checks condenser pressure less than 10" Hg ABS (it is)

SRO/BOP (5) Checks Condenser Parameters o SJAE Aftercondenser Vent Flow: Meter is without power (PY15 not yet on backup) (VB3, Center) o Condenser pressure is stable or improving due to isolation of leak (VB3, Center)

SRO/BOP Places ramp on hold (all on Triconex turbine HMI, CC3)

Removes DEH MW and IMP feedbacks from service Sets VPL 12% above new load value Proceed to the next event once crew has stabilizer plant, per the lead examiner.

• • Critical Task L121 NRC Sim Exam 02 r0a.doc Page 18 of 31 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 2 Event No.: 6 Page 16 of 23 Event

Description:

Loop Seal Failure / Rapid Loss of Turbine Vacuum (Rx Trip)

Time Position Applicants Actions or Behavior ATC/BOP Observes rapidly degrading condenser vacuum (rising pressure, VB3, PPC, CC2)

May trip turbine and/or reactor manually prior to automatic trips Note 1: Vacuum leak is of significant magnitude. Crew will not have time to recommence ramp and will enter EOP E0, Reactor Trip or Safety Injection once Reactor Trip occurs. Crew members should independently verify first four steps of EOP E0 (immediate actions) prior to Shift Foreman confirming expected plant response.

Note 2: Turbine Driven AFW (TDAFW) pump trips on over speed and AFW 13 fails to autostart. Board Operator may attempt to start pumps after performing immediate actions, but should not interrupt Shift Foreman confirmation steps. Pump status should be reported as part of step 4 RNO.

(EOP E0,"Reactor Trip or Safety Injection")

SRO/ATC (1) Verifies reactor trip (trip bkrs open, rods on bottom, NIs decreasing) (VB2, CC1)

SRO/ATC (2) Verifies turbine trip (stop valves closed) (CC3 HMI or VB2 RPS indicator lamps)

SRO/BOP (3) Checks vital 4kv bus status (VB4, vital busses F and G have white lights on mimic busses) o Buses F and G are energized from Startup Power (230 kV); Bus H is de energized from earlier failure.

SRO/ATC (4.a) Checks if SI actuated (PK0821 OFF, also checks SSPS ESF status lights on VB1 and PK0202) o SI is NOT required SRO/BOP (4.a.2 RNO) Announces Rx Trip on PA (continued on next page)

• • Critical Task L121 NRC Sim Exam 02 r0a.doc Page 19 of 31 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 2 Event No.: 6,7 Page 17 of 23 Event

Description:

Loss of Turbine Vacuum, Rx Trip (continued)

TDAFW Overspeed Trip and MDAFW 13 autostart failure (CT)

Time Position Applicants Actions or Behavior (EOP E0,"Reactor Trip or Safety Injection", continued)

Note: AFW 13 provides approximately 600 gpm total flow to S/G 3 & 4 and, as the only available pump, should not be throttled back.

BOP (4.a.3 RNO) Controls total feedflow to S/Gs

• • Starts AFW 13 (if not previously started) (VB3, lower left skirt)

• • Maintains greater than 435 gpm until NR S/G level is greater than 15% in at least one S/G. (VB3, upper center (just below PK10 window)

(Critical Task FRH.1E, Establish greater than 435 gpm feedwater flow rate to the S/Gs before 3 of 4 WR levels indicate less than 18%)**

SRO Transitions to EOP E0.1, Reactor Trip Response; performs procedure transition brief (EOP E0.1,"Reactor Trip Response")

Note: AFW 13 trips on overcurrent when S/G 13 or S/G 14 reaches 13.5% NR which will determine length of time crew stays in E0.1, "Reactor Trip Response" SRO/ANY (1) Checks RCS temperature stable or trending to 547oF (VB2, lower center chart recorders or PPC) o May set 10% dump controllers to 1005 psig, (83.8% setpoint) (VB3, lower left)

SRO/ANY (2) Checks Feedwater Status o RCS temperature < 554oF (VB2, lower center chart recorders or PPC) (It is) o Checks Feedwater Isolation has occurred Feedwater Isolation portion of Monitor Light Box C (VB1)

(Red lights ON / White lights OFF) o Checks total AWF flow greater than 435 GPM (VB3, upper middle)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 02 r0a.doc Page 20 of 31 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 2 Event No.: 6 Page 18 of 23 Event

Description:

Rx Trip Response Time Position Applicants Actions or Behavior (EOP E0.1,"Reactor Trip Response")

SRO/ATC (3) Checks Rods fully inserted (VB2DRPI)

SRO/ATC (4) Checks Pressurizer level controls o (a) Level greater than 17% (VB2, middle right) o (b) Charging in service with adequate flow (VB2)(CC2) o (c) Letdown in service (VB2, upper middle skirt) o (d) Pressurizer level trending to 22% (VB2, middle right)

(may adjust charging to maintain level 22% to 60%)

o (e) May energize pressurizer heaters (CC1, lower left)

SRO/ATC (5) Checks Pressurizer pressure control o (a) Pressure greater than 1850 psig (VB2, far right) o (b) Pressure stable or trending to 2235 psig (VB2)(CC2)

SRO/BOP (6) Checks S/G NR levels o (a) Reports all S/G NR levels less than 15% (VB3, upper middle) (S/G 3&4 levels rising; no flow to S/G 1&2)

(a RNO) Maintains AFW flow greater than 435 until S/G levels greater than 15%

o (b) Will control AFW flow to maintain S/G NR levels between 20% and 65%

o (c, d) Checks TD AFW Pump required for heat removal Reports TD AFW pump is not available for heat removal (tripped on overspeed) (VB3, center skirt)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 02 r0a.doc Page 21 of 31 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 2 Event No.: 6 Page 19 of 23 Event

Description:

Rx Trip Response (continued)

Time Position Applicants Actions or Behavior (EOP E0.1,"Reactor Trip Response")

SRO/BOP (7) Evalutes transferring steam dumps to Pressure Control Mode o (a,b) Notes Steam dumps are NOT in steam pressure mode (CC2) and MSIVs are open (VB3, left middle) o (c) Reports Condenser is NOT available (PK0814 is OFF; Condenser at atmospheric pressure)

(c.1, RNO) Closes MSIVs (VB3, left middle)

(c.2, RNO) If not performed earlier, adjusts 10% dump controllers to 1005 psig, (83.8% setpoint) (VB3, lower left)

Proceed to the next event when Step 7 (above) complete, per Lead Evaluator

• • Critical Task L121 NRC Sim Exam 02 r0a.doc Page 22 of 31 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 2 Event No.: 8 Page 20 of 23 Event

Description:

MDAFW 13 trips on overcurrent leading to Loss Of Heat Sink condition Time Position Applicants Actions or Behavior ALL Notes AFW Pp 13 tripped on overcurrent (VB3, lower skirt)

ALL Observes S/G level less than 15% NR during EOP E0.1 or RED PATH for Heat Sink on CSFSTs SRO Enters EOP FRH.1 (LOSHS) due to loss of AFW (complete) and low S/G levels (EOP FRH.1,"Loss of Secondary Heat Sink")

SRO (1) Determines total feedflow less than 435 gpm is NOT the result of operator actions SRO/ATC (2) Determines Secondary Heat Sink is required o (a) RCS Pressure is GREATER than any intact S/G ; (RCS pressure (VB2); S/G pressure (VB3))

o (b) RCS Hot Leg Temp is GREATER than 350 oF; (VB2, lower (chart recorder))

SRO/ATC (3) Checks at least one ECCS CCP available (CCP 12; VB2, lower left)

SRO/BOP (4.a) Verifies Blowdown and Sample isolation valves outside containment are closed (VB3, lower left skirt)

SRO/BOP (4.b.1) Verifies CST level is GREATER than 10% (VB3, middle)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 02 r0a.doc Page 23 of 31 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 2 Event No.: 8 Page 21 of 23 Event

Description:

MDAFW 13 trips on overcurrent leading to Loss Of Heat Sink condition (continued)

Time Position Applicants Actions or Behavior (EOP FRH.1,"Loss of Secondary Heat Sink", continued)

SRO/BOP (4.b.2) Verifies none of the AFW pumps are running (VB3, middle)

(4.bc RNOs) Dispatches operators to locally check lineups and investigate pump trips; May check for status on bus H and potential for getting AFW 12 returned to service SRO/ATC (5) Stops all four RCPs (VB2, right)

Note: Step may have already been completed during performance of EOP E0.1.

SRO/BOP (6) Adjusts 10% dump controllers to 1005 psig, (83.8% setpoint) (VB3, lower left)

SRO/BOP Reads CAUTION regarding monitoring of Hotwell level (7.a) Checks at least one Condensate Booster Pump Set running in recirc (VB3, lower center skirt)

SRO/ATC (7.b) Takes manual control of all Main Feedwater Reg Valves and Main Feedwater Reg Valves Bypasses and sets demand to zero (DFWCS HMI on CC3)

SRO/BOP (7.c) Checks Feedwater Isolation Valves open (VB3, lower left)

SRO/BOP (7.d) Determines Main Feedwater is NOT available (Condenser NOT available) (PK0814 in NOT lit) and goes to step 9 (Establish Feed from Condensate System)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 02 r0a.doc Page 24 of 31 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 2 Event No.: 8 Page 22 of 23 Event

Description:

MDAFW 13 trips on overcurrent leading to Loss Of Heat Sink condition (continued)

Time Position Applicants Actions or Behavior (EOP FRH.1,"Loss of Secondary Heat Sink", continued)

SRO/ALL Reads CAUTIONS before step 9.a regarding blocking/unblocking of automatic SI actuation Reads CAUTION regarding parallel performance of S/G and RCS depressurization (steps 9.c in parallel with steps 9.ab) and the need to stop S/G depressurization if PK0606 comes in before SI signal are blocked (needed to prevent unwanted SI)

(9.a.1) Depressurizes RCS to less than 1915 PSIG (P11) using one Pressurizer PORV (VB2, upper right)

(9.a.2) After P11 actuates (PK0806), blocks RCS low pressure SI ((2) train switches) and low steamline pressure SI signals ((2) train switches)(CC2)

(9.a.3) Maintains RCS pressure below P11 (1500 and 1865 PSIG) using PORV (VB2)

SRO/BOP (9.b.1) Verifies Main Feedwater Isolation Valves OPEN (VB3, lower left)

SRO/BOP (9.b.2) Verifies Main Feedwater Isolation signal OFF (PK0911); resets as needed (VB3, center)

SRO/ATC (9.b.3) Throttles open Main Feedwater Reg Valves OR Main Feedwater Bypass Valves (CC3 DFWCS HMI)

SRO/BOP (9.b.4) Bypasses feedwater heaters and condensate demineralizers (FCV55 and FCV 230) (VB3, skirt, lower right)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 02 r0a.doc Page 25 of 31 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 2 Event No.: 8 Page 23 of 23 Event

Description:

MDAFW 13 trips on overcurrent leading to Loss Of Heat Sink condition (continued)

(CT)

Time Position Applicants Actions or Behavior (EOP FRH.1,"Loss of Secondary Heat Sink", continued)

SRO/BOP Reads CAUTION before step 9.c regarding potential for low Tave Feedwater Isolation (9.c) Depressurizes at least ONE intact S/G to LESS THAN 490 PSIG at MAXIMUM RATE:

o (9.c.1) Verifies all MSIV and MSIV bypass valves closed (VB3, lower left) o (9.c.2) Places one 10% dump valve in manual and opens to 100%; Red light ON, green light OFF (VB3, middle)

SRO/ATC o (9.c.3) Checks charging in service; may maximize during depressurization to prevent losing Pressurizer level during the cooldown SRO/BOP **(9.c.4) Establishes feedflow to at least one S/G (VB3)

(Critical Task FRH.1A, 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) **

o (9.c.5) Stabilizes depressurized S/G pressure at 480 PSIG (VB3)

Sets depressurized S/G 10% dump valve setpoint to current S/G pressure, approx. 40% (or below) on controller Returns controller to AUTO Terminate the scenario once feedwater flow from the Condensate System is established , per the Lead Examiner.

• • Critical Task L121 NRC Sim Exam 02 r0a.doc Page 26 of 31 Rev 0

Appendix D (rev 9) Scenario Event Description Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 1 Page 1 of 19 Event

Description:

NI44 Slow Failure High Time Position Applicants Actions or Behavior Note: Procedure step numbers are included at the front of each action/comment in parenthesis, where applicable.

ALL Diagnoses power range NI44 failure from the following:

NI44 meter failing high (CC1, VB2 lower chart)

Several PK alarms, all associated with power range NIs, have alarmed Turbine power (PPC, CC3 turbine control) has not changed, Tave is close to Tref, but controls rods are moving in (CC1)

ATC Takes control rods to manual (due to inward rod motion caused by NI44 failing high) (CC1)

SRO Enters OP AP5, "Malfunction of Eagle21 Protection or Control Channel" (OP AP5, Malfunction of Eagle21 Protection or Control Channel)

Note: Depending on how quickly this failure is diagnosed, and how quickly control rods are placed in manual (fairly high worth area for rods), there may be an immediate need to control temperature. If needed, the Shift Foreman may chose to use the turbine load to raise Tave, or may "move up" a substep in OP AP5 to bypass the C2 rod stop (that prevents outward rod motion), so that rods are again available. If failure identified fairly quickly, these responses may be delayed until rod control is restored (below).

SRO/ATC (1) Determines Primary and Secondary Control Systems are NOT controlling properly in AUTO (specifically Rod Control has a failure)

(1.a RNO) Verifies Rod Control has been taken to manual. Restores Tave to Tref (if needed; see note above). This may be done by ramping the turbine down, or by moving rods out (see below for bypassing rod stop C2)

(1.b RNO) Notes failure is due to single instrument and not an entire Process Control Rack SRO Reads NOTES regarding Channel Set Failure Alarm and failure of LCP prior to step 2 and determines they are not applicable for this failure (continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r0a.doc Page 4 of 27 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 1 Page 2 of 19 Event

Description:

NI44 Slow Failure High, continued Time Position Applicants Actions or Behavior (OP AP5, Malfunction of Eagle21 Protection or Control Channel, continued)

SRO/BOP (2) Determines not an Eagle21 failure based on PK0601 and PK0603 OFF SRO (3) Notes no Delta T channel failure (step is N/A) (VB2)

SRO/BOP (4) Checks steam dumps not actuated (no armed, open, or tripped open signals) (VB3)

SRO (5) Notifies I&C SRO Reads CAUTION before step 6 regarding Eagle 21 design feature associated with rack issues and notes as N/A for this failure (6) Reminds crew of necessity to ensure affected channels are removed from service prior to maintenance SRO/BOP (7) Reviews Attachments 4.1 (Rx Trip and ESF Bistable Channel positioning per TS) and 4.2 (Process Control System Racks) to determine affected controls and indicators (a) Places OOS tags on NI44 (CC1, VB2) and OTT (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 (continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r0a.doc Page 5 of 27 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 1 Page 3 of 19 Event

Description:

NI44 Slow Failure High, continued Time Position Applicants Actions or Behavior (OP AP5, Malfunction of Eagle21 Protection or Control Channel, continued)

SRO (8) Evaluates Tech Specs and ECGs:

o TS 3.3.1.E One channel inoperable for OTDeltaT trip (place in trip within 72 hrs);

o TS 3.3.1.D - One power range neutron fluxhigh channel inoperable (Hi flux trip)

(72 hrs) (also 12 hrs on QPTR surveillance) o TS 3.3.1.S - One or more channels or trains inoperable (P10 permissive check)

(verify status within 1 hr) o TS 3.3.1.T - One or more channels or trains inoperable (P7, P8, P9 permissive checks) (verify status within 1 hr) o Equip Control Guideline (ECG) 37.2 Axial Flux Difference Monitor Alarm inoperable (verify AFD within limits for each operable channel within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and once per hour thereafter) o Equip Control Guideline (ECG) 37.3 Quadrant Power Tilet Ratio Alarm inoperable (verify QPTR within limits of TS 3.2.4 once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)

SRO/ATC If not completed earlier, checks Tave restored to Tref (CC1 or CC3)

Returns rods to AUTO (CC1)

Proceed to the next event once Tech Specs are addressed, per Lead Examiner

• • Critical Task L121 NRC Sim Exam 03 r0a.doc Page 6 of 27 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 2 Page 4 of 19 Event

Description:

Condensate Booster Pump (CBP) 13 Overcurrent Trip Time Position Applicants Actions or Behavior ALL Diagnoses CBP 13 trip from the following:

PK1006, "CNDS & CNDS BSTR PPS", in alarm Low Feedpump Suction Pressure (VB3, upper right center)

Overcurrent (blue) light on for CBP 13 (VB3, lower center skirt)

SRO May enter PK1006, which directs crew to OP AP15 (section D, for Cond/booster Pp trip)

BOP May start standby CBP 12 (failed to autostart) (VB3, lower center skirt)

SRO Enters OP AP15: Section D "Loss of Feedwater Flow - Condensate/Booster Pump Set Trip" (OP AP15: Section D, "Loss of Feedwater Flow - Condensate/Booster Pump Set Trip")

SRO/BOP (1) Determines all available CBPs are NOT running (CBP 12 did NOT autostart as expected)

(1 RNO) o Takes CBP 12 Standby Select Switch to MAN (VB3, lower center skirt) o Starts CBP 12 (checks amps stable) (VB3, lower center skirt)

SRO/BOP (2) Checks Main Feed Pump suction pressure greater than 260 psig (VB3, upper center)

SRO May direct Turbine Watch to walkdown pump and breaker; may contact maintenance to investigate issue (3) Exits AP15 Proceed to the next event when AP15 exited, per Lead Examiner

• • Critical Task L121 NRC Sim Exam 03 r0a.doc Page 7 of 27 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 3 Page 5 of 19 Event

Description:

S/G 12 Tube Leak (35 gpm)

Time Position Applicants Actions or Behavior ALL Diagnoses Steam Generator Tube Leak from the following:

Increased charging flow (PPC, CC2)

Air ejector offgas hirad in alarm (PPC, RM15/15R) (PK1106)

Steam generator blowdown hirad and/or isolation (PPC, RM19,23) (PK1117)

Main steam line hirad (RM72) (PPC, PK1118)

ATC Observes PK1106 (SJAE HIRAD) alarming and informs the Shift Foreman.

ATC/BOP May check PPC and/or VB2 Recorders (lower left) for upscale readings/ trends on rad monitors If AR PK1106 is entered; otherwise this section is N/A SRO/ATC (1) Identifies input 423 (SJAE HiRad) and goes to section 2.1, General Actions.

SRO/BOP (2.1.1) Checks for upscale readings on both 15 and 15R (PPC, RCDR3 VB2 lower left)

(both are in alarm; may be over ranged) o (2.1.1.a) Implements OP O4, "Primary to Secondary Steam Generator Tube Leak Detection" o (2.1.1.b) Notifies Chemistry of abnormal condition o (2.1.1.c) Transitions to OP AP3 (continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r0a.doc Page 8 of 27 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 3 Page 6 of 19 Event

Description:

S/G 12 Tube Leak (35 gpm), continued Time Position Applicants Actions or Behavior Note: Review of OP O4 shutdown criteria is also covered as part of OP AP3, "Steam Generator Tube Failure" (if not addressed during AR PK1106 response)

OP O4, "Primary to Secondary Steam Generator Tube Leak Detection" Implementation BOP Reviews OP O4 for action levels and shutdown criteria Evaluates OP O4 action level using PPC Group Display Determines current OP O4 action level as 3b (leak >= 150 gpd) and updates Shift Foreman SRO Enters OP AP3 "Steam Generator Tube Failure" (OP AP3 "Steam Generator Tube Failure")

SRO Reads NOTE prior to step 1 regarding requirement to complete procedure actions unless superseded by EOP E3 ("Steam Generator Tube Rupture")

Note: Maintaining Pressurizer level stable is a Continuous Action. Associated RNO steps are performed when crew reports applicable conditions exist (i.e unable to maintain pressurizer level).

SRO/ATC (1) Checks pressurizer level and charging flow o May take manual control and attempt to adjust charging and seal flow to maintain pressurizer level (CC2) o (1.a) Determines charging flow is NOT maintaining pressurizer level stable (CC2, PPC)

SRO/BOP (1.a RNO) Starts additional charging pump when requested by ATC (VB2, center skirt)

SRO/ATC (1.b) Checks for continuing decrease in pressurizer level o Readjusts charging and seal flow (CC2) o Determines pressurizer level is stable (CC2, PPC) (Continuous Action to Monitor)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r0a.doc Page 9 of 27 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 3 Page 7 of 19 Event

Description:

S/G 12 Tube Leak (35 gpm), continued Time Position Applicants Actions or Behavior (OP AP3, "Steam Generator Tube Failure", continued)

SRO/BOP (2) Takes actions to identify affected steam generator o (2.a) Determines that no S/G levels are rising unexpectedly (VB3 meters, PPC) o (2.b) Identifies main steamline rad monitors RM71 and 72 rising (corresponds to S/G 12; RM71 reading is elevated as result of shine and is reading considerably lower than RM72 ) (VB2 recorders, upper left; PPC) o (2.c) Verifies S/G blowdown isolation/sample valves open (VB3 lower left)

(Depending on pace of crew, blowdown may have isolated due to high rad on RM23; RNO step is performed to allow sampling by chemistry)

(2.c RNO) Checks blowdown isolation due to RM12 in alarm (PPC, RCDR3 VB2 lower left); Places RE19, 23 Hi Rad S/G Blowdown and Sample Valve iso defeat cutout switch to "cutin" and opens blowdown sample valves (FCV244, 24, 248, 250) (VB3, lower left skirt) o (2.d) Contacts Chemistry to perform S/G sampling SRO/ATC (3) Determines VCT level can be maintained by RCS makeup (CC2,VB2, PPC)

(Continuous Action to Monitor)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r0a.doc Page 10 of 27 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 3 Page 8 of 19 Event

Description:

S/G 12 Tube Leak (35 gpm), continued Time Position Applicants Actions or Behavior (OP AP3, "Steam Generator Tube Failure", continued)

Note 1: OP O4, action level 3b corresponds to T.S. 3.4.13.d (150 gpd primary to secondary leakage), Action B, which requires the unit to be in MODE 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Note 2: Once the shutdown commences, however, continuous radiation monitoring via RM15 and 15R is no longer valid (power reduction invalidates the rad monitor's cpmgpd conversion factor). OP O4 guidance for Action Level 3b (section 6.6) is as follows for Rx power 50%:

The shutdown should begin promptly, but may be delayed for up to 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. Once power reduction begins, Rx power shall be less than 50% in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and shutdown to MODE 3 within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

SRO (4) Determines plant shutdown is required based on OP O4 shutdown criteria o (4.a) Reviews OP O4 criteria and PPC GRPDIP OP O4 data and concurs with action level 3b assessment o (4.b) Implements OP AP25 to take unit offline May perform reactivity brief prior to entry (5) May perform additional actions to minimize secondary contamination o (5.a) Contacts polisher wash to reduce number of vessels in service o (5.b) Checks Aux Steam aligned to Unit 2 SRO/BOP o (5.c,e) Directs Turbine Watch to align gland sealing steam supply to Aux Steam and close VAC733 o (5.d) Contacts Aux Senior regarding discharge of condensate (current permit likely invalidated by leak)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r0a.doc Page 11 of 27 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 3 Page 9 of 19 Event

Description:

S/G 12 Tube Leak (35 gpm), continued Time Position Applicants Actions or Behavior (OP AP25, "Rapid Load Reduction or Shutdown")

SRO (1.a) Determines runback/programmed ramp is not in progress (may not vocalize, since this ramp is initiated by the crew)

SRO/BOP Starts load reduction (guidance is also on lamicoid pegboard on CC3):

o (1.b) Places MW and IMP feedbacks in service (all on Triconex turbine HMI, CC3) o (1.c,d) Sets load target and ramp rate (expected ~ 10MW/min to 150 MW, but at discretion of Shift Foreman) o (1.e) Pushes GO o (1.f) Contacts Chemistry to advise 15%/hr shutdown rate will be exceeded SRO/ATC (2) Ensures control rods are inserting in AUTO (3) Turns Pressurizer heaters on (CC1)

(4) Checks charging adequate to prevent flashing in the letdown system; may take manual control to ensure adequate flow (CC2)

SRO/BOP (5) Ensures DFWCS is controlling S/G levels in AUTO (MFW control/bypass valves; MFPs all in AUTO) (CC2)(VB3)

SRO/ATC (6) Determines boration requirements; borates RCS as needed) (CC2)

SRO/BOP (7) Checks MFP suction pressure greater than 260 psig (VB3)

SRO/ATC (8) Checks Tave trending to Tref (PPC, CC1)

(9) Checks Pressurizer pressure and level trending to programmed band (PPC, CC2)

SRO If not already completed, reviews T.S. 3.4.13.d, Action B - greater than 150 gpd primary to secondary leakage. Required actions: be in MODE 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 5 in 36 hrs.

Proceed to the next event once ramp commenced, per Lead Examiner

• • Critical Task L121 NRC Sim Exam 03 r0a.doc Page 12 of 27 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 4 Page 10 of 19 Event

Description:

Condenser InLeakage Time Position Applicants Actions or Behavior Observes PK1205 (COND PPS DISCH HRD CATION CONDT'Y HI) alarming and informs the ATC Shift Foreman.

(1) Identifies input 1104 (Cond Pps Disch Header Cation Conductivity Hi) and goes to SRO/ATC section 2.1, General Actions.

SRO/BOP (2.1.1) Contacts Polisher Watch to investigate cause of alarm SRO (2.1.2) Enters OP AP20 "Condenser Tube Leak" (OP AP20 "Condenser Tube Leak")

SRO/BOP Reads NOTE regarding delay time between Control Room readout and realtime values for Secondary Chemistry (1) Determines condensate cation conductivity is greater than 1.0 S/cm (may report units as mhos/cm, which is equivalent) (DDR10, VB3 far right, middle, points 17,18,19) o Directs Polisher Watch to monitor chemistry data and alert control room for adverse trend o Compares DDR values and trend with those reported by Polisher Watch; may contact Chemistry to perform additional sampling o May direct Chemistry to sample Condensate Storage Tank (CST) as possible source of sodium contamination (continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r0a.doc Page 13 of 27 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 4 Page 11 of 19 Event

Description:

Condenser InLeakage, continued Time Position Applicants Actions or Behavior (OP AP20 "Condenser Tube Leak", continued)

SRO/BOP Reads NOTE regarding identification of leak location and implementation of compensatory actions.

(2) Determines area of leak (condenser quadrant) (DDR10, VB3 far right, middle) o Identifies point 7 is elevated, indicating leak in condenser outlet, SW quadrant o Requests confirmation of location from Polisher Watch o May direct Chemistry to sample locally SRO/BOP Reads CAUTION regarding requirement to trip Rx if FCV230 (condensate polisher demineralizer bypass valve) goes open for any reason.

(3) Performs actions to prevent bypass of condensate demineralizers o (3.a) Verifies FCV230 closed (VB3, lower right skirt) o (3.b) Directs Turbine Watch to open supply breaker for FCV230 SRO/BOP (4) Monitors Feedwater Cation Conductivity for indications of condensate demin breakthrough; (DDR10, point 32 greater than 0.25 S/cm indicates breakthrough, requiring Rx Trip) (DDR10, VB3 far right, middle)

Note: Ramp adjustment is required if current rate is less than 25 MW/min and power is still greater than 50%

SRO/BOP (5) Evaluates Attachment 4.1,"Condenser Tube Leak Corrective Action Limits" Determines minimum ramp is 25MW/min down to 50% power Changes rate to min of 25 MW/min (CC3, Turbine Control HMI)

SRO/BOP (611) May perform additional actions to minimize secondary contamination (not previously performed as part of AP3) o Takes manual control and closes Condenser Hotwell Reject Valve, LCV12 (VB3, lower right skirt) o Directs field realignment of CWP 11 Auto Reclose and SCW Hx Proceed to the next event once minimum ramp rate establish, per Lead Examiner

• • Critical Task L121 NRC Sim Exam 03 r0a.doc Page 14 of 27 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 5 Page 12 of 19 Event

Description:

S/G 12 Tube Rupture (400 gpm)

Time Position Applicants Actions or Behavior ALL Diagnoses Steam Generator Tube Rupture from the following:

Pressurizer level and pressure lowering (PPC, CC2, VB2)

S/G 12 level rising (PPC, VB3)

Main steam line hirad rising, loops 1 & 2 (RM71 and 72) (PPC, VB2)

SRO/BOP May attempt to isolate letdown (VB2, upper center skirt)

SRO/ATC Initiates manual SI (CC2, far right)

ALL Crew enters EOP E0 on trip/SI actuation and silently performs immediate actions:

Verifies reactor trip (trip bkrs open, rods on bottom, NIs decreasing)

Verifies turbine trip (stop valves closed (CC3 HMI or VB2 RPS indicator lamps)

Checks vital 4kv busses (VB4, vital busses F/G/H have white lights on mimic busses)

Checks if SI actuated (PK0821 ON, also checks VB1 red train lights and/or train equipment to verify both trains actuated)

(EOP E0, Reactor Trip or Safety Injection")

Note: Immediate action steps are reverified by Shift Foreman after first being performed independently by each member of crew SRO/ATC (1) Verifies reactor trip (trip bkrs open, rods on bottom, NIs decreasing) (VB2, CC1)

SRO/ATC (2) Verifies turbine trip (stop valves closed) (CC3 HMI or VB2 RPS indicator lamps)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r0a.doc Page 15 of 27 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 5,6 Page 13 of 19 Event

Description:

S/G 12 Tube Rupture (400 gpm), continued 8801A/B fail to open on SI (CT)

Time Position Applicants Actions or Behavior (EOP E0, Reactor Trip or Safety Injection", continued)

SRO/BOP (3) Checks vital 4kv bus status (VB4, vital busses F/G/H have white lights on mimic busses)

SRO/ATC (4) Checks SI actuated (PK0821 ON, also checks VB1 red train light ON and/or train equipment to verify both trains actuated) o Both trains of SI actuated as indicated by PK0821, SI red light above Monitor Light Box C (VB1), and both trains of SI/RHR pumps running (VB1 skirt)

SRO (5) Directs implementation of App E (usually given to BOP)

Note: Critical task to establish high head ECCS flow prior to exiting EOP E0 requires manually opening of 8801A/B. Action is addressed as part of App E, step 5 alignment verification, but may be addressed as soon as failure is identified. Manual realignment should be communicated to Shift Foreman as part of step 11 status report.

BOP Implements App E (ESF Auto Actions, Secondary and Auxiliaries Status):

(1a) Checks no personnel in Containment (part of turnover; may not voice)

(1b) Announces trip/SI on PA system (2) Checks main generator - tripped (PK1401 ON, output bkrs open, and exciter field bkr open, CC3 right side)

(3 & 4) Verifies Phase A and Containment Vent Isolation complete (VB1, Monitor Light Box B: red lights ON, white lights OFF)

(5) Verifies ESF (SI) actuation complete (SI Portion of Monitor Light Box C: red light ON, white lights some ON);

o Identifies white lights associated with 8801A/B injection valves (failed closed)

• • Manually opens 8801A and/or 8801B and verifies injection flow (VB2, upper left, next to DRPI)

(Critical Task E0D, Establish high head ECCS flow prior to exiting EOP E0) **

(continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r0a.doc Page 16 of 27 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 5,7,8 Page 14 of 19 Event

Description:

S/G 12 Tube Rupture (400 gpm), continued MSLB on S/G 12 inside containment MSIVs on leads 1 & 2 fail to close in auto, but can be closed manually Time Position Applicants Actions or Behavior (EOP E0, Appendix E, continued)

BOP (6) Verifies Feedwater isolation complete (F.W. Isolation and S.G. Level Portions of Monitor Light Box C: red lights ON, white lights OFF)

(7) Checks containment spray, Phase B - NOT required (Contmt Isol, Phase B portion of Monitor Light Box D: red lights are OFF); may also note containment pressure, while elevated, is well below actuation setpoint)

Note: Based on operator pace through App E., MSLI may not have actuated by time operator reaches procedural step to verify isolation (isolation actuates approximately 2 minutes after the trip). Main Steam Isolation Valves FCV41 and FCV42 (leads 1 & 2) fail to close, but can be manually actuated from VB3. Numerous related indicators and subsequent alarms occur over the course of the scenario, providing the crew ample opportunity to identify and correct the failure.

BOP (8) Checks Main Steamline Isolate complete (Main Steam Isolation portion of Monitor Light Box D: red light ON, white light, some ON) o Identifies white lights associated with FCV41 and FCV42 (failed open) o Manually closes FCV41 and FCV42 (VB3, center left)

Note: Step to control AFW to limit cooldown may have already been completed (E0, step 6 RNO) by other crew members; actions taken in Appendix E should reflect overall mitigation strategy (maintain secondary heat sink while limiting cooldown)

BOP (9) Checks AFW status (AFW Pp 13 is running, TDAFP will start once 2 out of 4 S/G levels falls below 15% (with time delay))

o Determines if TD AFW Pp 11 is needed (if not already running) (VB3, middle center skirt) o Verifies either min of 435 gpm flow (VB3 center) or S/G level > 15% (VB3 center)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r0a.doc Page 17 of 27 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 5 Page 15 of 19 Event

Description:

S/G 12 Tube Rupture (400 gpm), continued Time Position Applicants Actions or Behavior (EOP E0, Appendix E, continued)

BOP (10) Verifies ECCS flows (charging injection (VB2 upper panel left), SI, RHR (both on VB1 upper panel); shuts down CCP 13 (VB2, middle center skirt)

(11) Reports ESF and AFW status to the Shift Foreman (Shift Foreman may direct operator to continue with Appendix E, or redirect to higher priority tasks)

BOP (12 & 13) Checks excess letdown - not in service (8166/8167 closed); turns on aux bldg vent charcoal filter preheater (VB4 lower panel, left side)

(14) Checks secondary systems (MFPs tripped (VB2, green lights ON), stops all but one CB Pp set, takes LCV12 control switch to CONT ONLY. Determines Condenser is NOT available (MSIVs are closed) and directs field operators to break vacuum when turbine is less than 200 rpm (15) Verifies proper operation of Aux Bldg and Control Rm vent systems (VB4 vent status light panel white lights); verifies containment iodine fans secured (VB4, lower panel)

(16 21) Verifies available DGs running normally (VB4, freq (60), volts (120), speed (900)); verifies vital batteries supplied by chargers (charger and bus volts on VB5, upper panel middle/lower area); verifies MSRs reset (CC3 Triconex HMI); throttles RCP seal injection flows to normal (FCV128, to 813 gpm each, CC2); checks PK1104 NOT IN (SFP alarm); notifies Shift Foreman of completion (EOP E0, Reactor Trip or Safety Injection", continued)

SRO/ATC (6) Checks RCS temperature - stable (temps will initially be dropping due to faulted S/G (VB2, upper panel lower area); Throttles AFW as required to control temperature (VB3, lower left skirt)

SRO/ATC (7) Checks Pzr PORVs and Pzr safeties (closed) / PORV block valves (all open); notes elevated tailpipe temps due to containment environment; no sonic flows on safeties/PORVs (VB2 - upper panel, far right); checks Pzr sprays closed (CC2)

SRO/ATC (8) Checks RCP trip criteria (RCS pressure [VB2, PPC] < 1300 psig and SI or ECCS CCPs running, criteria could be met depending on timing of events) (VB1 and VB2)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r0a.doc Page 18 of 27 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 7 Page 16 of 19 Event

Description:

MSLB on S/G 12 inside containment (CT)

Time Position Applicants Actions or Behavior (EOP E0, Reactor Trip or Safety Injection", continued)

SRO/ATC (9) Checks for faulted S/Gs o Faulted - notes 12 S/G pressure is dropping uncontrollably and/or completely depressurized (PPC, VB3) o Transitions to EOP E2, "Faulted Steam Generator Isolation" (EOP E2, "Faulted Steam Generator Isolation)

SRO Reads three CAUTIONS prior to step 1 SRO/ATC (1) Verifies ALL MSIVs and bypasses are closed (VB3, upper panel, left side)

SRO/ATC (2) Checks for any intact S/G (11, 13, and 14 S/Gs have stable pressures, consistent with the RCS cooldown from the 12 S/G); continues in E2 SRO/ATC (3) Identifies 12 S/G as faulted (VB3, pressure is still dropping in uncontrolled manner, or completely depressurized at this point)

SRO/BOP (4) Implements Appendix HH, "Isolate Faulted Steam Generator" (see page 17) (CT)

SRO/ATC (5) Checks CST level > 10% (VB3, upper panel, center area meter and recorders)

SRO/ATC (6) Checks for ruptured S/Gs o Ruptured - notes valid alarm on PK1106, PK1117, or PK1118 (RM23 is failed high) and upward trend on RM19, 15/15R, and RM72 (recorders on VB2 (and PPC))

o Transitions to EOP E3, "Stem Generator Tube Rupture" (continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r0a.doc Page 19 of 27 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 7 Page 17 of 19 Event

Description:

MSLB on S/G 12 inside containment (CT)

Time Position Applicants Actions or Behavior (EOP E2, "Appendix HH, "Isolate Faulted Steam Generator")

BOLD substeps below must be assigned prior to exit from EOP E2 (Critical Task E2A: Isolation of Faulted S/G initiated before transition out of EOP E2) **

BOP Reads CAUTION regarding TDAFW as only source of feedflow prior to step 1 (1) Isolates faulted S/G 12

a. Verifies MFIV FCV439 closed (all of these controls on VB3, lower left) (already closed)

b. Verifies SGBD valves FCV761, 154, and 248 closed (IC, OC, and sample) (already closed)

c. Verifies S/G 12 10% steam dump closed (PCV20) (isolated as part of setup)

• • d. Closes TDAFP AFW LCV107 Closes MDAFP AFW LCV111 for 12 S/G to isolate AFW

• • e. Closes FCV37 to isolate steam from 12 S/G to TDAFP

f. Verifies AFW flow to at least one intact S/G (VB3, upper panel, center area meters)

g. Informs Shift Foreman S/G 12 isolation is complete BOP (2) Removes WR Thot input to SCMM for loop 2 (behind boards, PAMS panel behind VB3)

(a) Goes to PAM4 panel (b) Presses Configuration Summary (c) Presses Failed S/G (d) Presses the PB for the Thot to be disabled (2)

(e) Presses Disable Loop 2 (continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r0a.doc Page 20 of 27 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 5 Page 18 of 19 Event

Description:

S/G 12 Tube Rupture (400 gpm), continued Time Position Applicants Actions or Behavior (EOP E3, "Steam Generator Tube Rupture)

SRO/ATC (1) Checks if RCPs should be stopped (probably already stopped in E0) (VB2)

SRO/ATC (2) Identifies S/G 12 as ruptured (RM72 in alarm, previous indications of rising level without feed during E0)

SRO/BOP (3) Implements Appendix FF to isolate ruptured S/G 12 (EOP E3, "Appendix FF, "Isolate Faulted Steam Generator")

Note: Majority of actions will have already been completed as part of (EOP E2, "Appendix HH, "Isolate Faulted Steam Generator")

BOP Reads CAUTION regarding TDAFW as only source of feedflow prior to step 1 (1) Reads step to insure 10% steam dump controller in AUTO and set to 86.7%; notes valves is OOS and isolated from initial conditions.

(2) Checks S/G 12 10% steam dump valve closed (PCV20) (VB3)

(3) Verifies S/G 12 MSIV and bypass () valves closed (VB3)

(4) Verifies S/G 12 supply to TD AFW Pp (FCV37) closed (VB3, skirt)

(5) Verifies S/G 12 SGBD valves (FCV154 and FCV248) closed (VB3, lower left skirt)

(6) Verifies S/G 12 is isolated from intact S/G (S/G 12 MSIV and MSIV Bypass are both closed as are all intact S/G MSIV and MSIV Bypasses)

(7) Informs Shift Foreman S/G 12 isolation is complete BOP (8) Verifies removal of WR Thot input to SCMM for loop 2 (behind boards, PAMS panel behind VB3) o Goes to PAM4 panel o Checks Loop 2 Thot Disabled (continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r0a.doc Page 21 of 27 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 5 Page 19 of 19 Event

Description:

S/G 12 Tube Rupture (400 gpm), continued Time Position Applicants Actions or Behavior (EOP E3, "Appendix FF, "Isolate Faulted Steam Generator")

BOP (9) Prepares for S/G sampling (a) Notifies Chemistry to sample S/G using CAP AP1 (b) Verifies SI and Phase A Isolation are reset (VB1, center)

(c) Verifies instrument air to containment (FCV584) is open (VB4, lower left skirt)

(d) Opens S/G blowdown isolation valves inside containment if contacted by Chemistry for sampling (EOP E3, "Steam Generator Tube Rupture, continued)

SRO/ATC Reads CAUTION regarding maintaining isolation of Faulted/Ruptured S/G (do not feed)

(4.a) Notes ruptured S/G level is less than 15% [25% if still in adverse containment conditions]

(4.a RNO) Applies CAUTION and does NOT apply RNO action to feed ruptured S/G SRO/ATC (5) Observes ruptured S/G is LESS THAN 225 psig; transitions to EOP ECA3.1, "SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED" per RNO Terminate the scenario once transition is made to ECA 3.1 , per the Lead Examiner.

• • Critical Task L121 NRC Sim Exam 03 r0a.doc Page 22 of 27 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 1 Page 1 of 27 Event

Description:

VCT Level Channel LT114 Slow Failure High Time Position Applicants Actions or Behavior Note: Procedure step numbers are included at the front of each action/comment in parenthesis, where applicable.

ALL Diagnoses LT114 failing high using one or more of the following indications:

VCT level and pressure lowering (diverse indicators of actual level change) (PPC, VB2 upper center)

LI112 (VB2, meter upper right) and LI114 (PPC point L0112A) fail to channel check VCT level control valve LCV11A diverting to LHUT (VB2 center skirt; amber light illuminated)

Automakeup if actual VCT level lowers 14% (CC2)

SRO Implements OP AP19, "Malfunction of Reactor Makeup Control System" (OP AP19, "Malfunction of Reactor Makeup Control System")

SRO/ATC (1) Checks Makeup Controller in set for desired mode (usually AUTO) and selected to START (CC2)

SRO/BOP (2) Verifies Makeup System pumps and valves are properly aligned and in AUTO (VB2, bottom right skirt)

ALL (3) Determines LI112 and LI114 do NOT channel check (LT114 failed High) o L0112A (PPC point for LI114) is reading 100%, LI112 (VB2) is reading between 14%50% (depending on actions taken by crew) o May dispatch Turbine Watch to check LI114 reading at HSDP (continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r0a.doc Page 4 of 35 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 1 Page 2 of 27 Event

Description:

VCT Level Channel LT114 Slow Failure High Time Position Applicants Actions or Behavior Note: AR PKs referenced in RNO do not alarm - transmitter failed at 100%, but NOT overranged (OOR)

SRO/BOP (3 RNO) References associated PKs and Appendices o (a) May reference AR PK0621 (Process Control System Trouble) and AR PK06 22 (Process Control System (PCS) Channel OOS); no actions directed by PKs o (b) Refers to Appendix A guidance to identify failed transmitter (1.a) Checks PCS HMI to determine which channel has failed (located to left of PPC large display)

(1.b) Reviews control functions/indications for LT112 and LT114 o (c) Determines LT114 has failed high SRO/ATC (4) Verifies suction alignment for running charging pump o CCP 11 amps, discharge flow (VB2, Under DRPI)(CC2) o VCT level and pressure are within normal bands SRO/BOP (5) Contacts I&C to investigate failure (6) Realigns LCV112A divert valve to VCT (VB2, right skirt)

Proceed to the next event once AP19 actions complete, per Lead Examiner

• • Critical Task L121 NRC Sim Exam 04 r0a.doc Page 5 of 35 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 2 Page 3 of 27 Event

Description:

PCV456 (PORV) Drifts Open Following Seismic (CT)

Time Position Applicants Actions or Behavior ALL Diagnoses PCV456 open using one or more of the following indications:

PK0520, "PZR RELIEF/SAFETY VLVS OPEN" in alarm PK0523, "PZR SAFETY OR RELIEF LINE TEMP" in alarm Pressurizer pressure lowering (CC2, VB2), back up heaters on (CC1), sprays closed (CC2)

Both RED and GREEN position indicator lights illuminated on PCT456 (VB2, far right, lower)

PORV discharge temperature elevated (TI463) (VB2, far right, middle)

SRO/BOP Takes action to manually close PCV456 (unsuccessful)

• • Closes associated block valve (8000C)

(Critical Task: Isolate PORV prior to pressurizer pressure lowering to 1950 psig (low pressurizer pressure Rx trip setpoint))**

Note: PK0523 will redirect crew to PK0520 for guidance (PK0520, Pressurizer Relief/Safety Valves Open) if entered, else N/A SRO/ATC (1) Identifies input 1211 (Pzr Relief Vlv PCV456 Open) and goes to section 2.1, General Actions SRO (2.1.1) Notes requirement to enter EOP E0, "Reactor Trip or Safety Injection" if reactor trips at any time.

Reads NOTE regarding isenthalpic steam release corresponding to a PORV tailpipe temperature of approximately 230oF; May direct board operator to check current PORV discharge temp (TI463) (VB2, far right, middle)

(2.1.2) Checks for indications of rapid drop in actual pressurizer pressure; may transition to OP AP13 (continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r0a.doc Page 6 of 35 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 2 Page 4 of 27 Event

Description:

PCV456 (PORV) Drifts Open Following Seismic , continued Time Position Applicants Actions or Behavior (OP AP13, "Malfunction of Reactor Pressure Control System") if entered; else N/A SRO (1) Notes there are no load changes in progress SRO/BOP (2) Checks all PORVs closed (PCV474, 455C, 456) (VB2, far right, lower) o Notes PCV456 position lights indicate valve is open (2 RNO) Checks pressurizer pressure less than 2335 psig (it is);

o May reattempt closing PCV456 (valve remains off its seat) o Checks associated block valve 8000C is closed SRO/BOP (3) Checks pressurizer safety relief valves closed (VB2, far right, middle) o Sonic flow reading zero (they are) o Tailpipe temperature 185oF (they are)

ALL Reads CAUTION regarding potential need for stopping RCPs if spray valve has failed (4.a) Checks normal pressurizer spray valves closed (PCV455A/B) (CC2, upper middle right) (green lights On, both are closed)

(4.b) Checks aux spray valves closed (8145 & 8146) (VB2, far right skirt) (both are closed)

SRO/ATC (5) Checks pressurizer backup heater status (far left CC1)

(5.a) Heaters are lined up to normal power (normal power indicating lights are illuminated (CC1)

(5.b,c) Status of heaters will depend on pressure transient from PORV opening If pressurizer pressure > 2250 psig, ensures all heaters turned off If pressurizer pressure < 2210 psig, ensures all heaters turned on (continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r0a.doc Page 7 of 35 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 2 Page 5 of 27 Event

Description:

PCV456 (PORV) Drifts Open Following Seismic , continued Time Position Applicants Actions or Behavior (OP AP13, "Malfunction of Reactor Pressure Control System", continued)

SRO (6) Determines all pressure control channels are OPERABLE SRO/ATC (7) Restores pressurizer pressure to normal band (22102260 psig)

SRO Reviews Tech Specs and enters Tech Spec 3.4.11.B - One PORV inoperable for reasons other than excessive seat leakage.

o Required actions:

Close associated block valve within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Remove power from associated block valve within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Restore Class I PORV to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Proceed to the next event once T.S. addressed, per Lead Examiner

• • Critical Task L121 NRC Sim Exam 04 r0a.doc Page 8 of 35 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 3 Page 6 of 27 Event

Description:

Grid Disturbance -GCC Backdown Order to Shed 350 MW Time Position Applicants Actions or Behavior Cue: (from Shift Manager) I have just received a valid backdown order from the Grid Control Center (GCC) due to a grid disturbance. Per Ops Policy B1, ramp unit 1 down 350 MW in the next 10 minutes.

SRO Implements OP AP25, Rapid Load Reduction (OP AP25, Rapid Load Reduction)

SRO Enters OP AP25, Rapid Load Reduction (1.a) Determines runback/programmed ramp is not in progress (may not vocalize, since this ramp is initiated by the crew)

SRO/BOP Ramp is started (guidance is also on lamicoid pegboard on CC3):

o (1.b) MW and IMP feedbacks are placed in service (all on Triconex turbine HMI, CC3) o (1.c) 840 MWe (1190350, approximate) load target is entered into Triconex HMI o (1.d) Sets ramp rate to 35 mw/min (approximate rate; actual rate dictated by Shift Foreman) o (1.e) Pushes GO SRO/BOP o (1.f) May make calls to chemistry if/when 15%/hr shut down rate is exceeded ATC (2) Verifies that control rods are inserting properly in AUTO (CC1)

(3) Turns Pressurizer heaters on (CC1)

(4) Checks charging adequate to prevent flashing in the letdown system; may take manual control to ensure adequate flow (CC2)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r0a.doc Page 9 of 35 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 3 Page 7 of 27 Event

Description:

Grid Disturbance -GCC Backdown Order to Shed 350 MW Time Position Applicants Actions or Behavior (OP AP25, "Rapid Load Reduction", continued)

SRO/BOP (5) Ensures DFWCS is controlling S/G levels in AUTO (MFW control/bypass valves; MFPs all in AUTO) (CC2)(VB3)

SRO/ATC (6) Determines boration requirements; borates RCS as needed) (CC2)

SRO/BOP (7) Checks MFP suction pressure greater than 260 psig (VB3)

SRO/ATC (8) Checks Tave trending to Tref (PPC, CC1)

(9) Checks Pressurizer pressure and level trending to programmed band (PPC, CC2)

Proceed to the next event when generation = 855 MW, per Lead Examiner

• • Critical Task L121 NRC Sim Exam 04 r0a.doc Page 10 of 35 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 4 Page 8 of 27 Event

Description:

Rod Control Urgent Failure / Dropped Rod Time Position Applicants Actions or Behavior ALL Diagnoses dropped control rod / rod control urgent failure using one or more of the following indications:

PK0317, "ROD CONT URGENT FAILURE" in alarm PK0321, "DRPI FAILURE/ROD BOTTOM" in alarm PK0310, "PWR RNG DEV/QPTR" in alarm Dropped rod indicated on DRPI (VB2)

Auto rod motion stops (CC1)

I and power range deviation in area of NI42 SRO Implements OP AP12V, "Dropped Control Rod" (OP AP12C, "Dropped Control Rod")

SRO/BOP (1) Determines single control rod dropped (control bank D, rod B10) (DRPI, VB2)

SRO/ATC (2) Places rod control in manual (CC1)

SRO/BOP (3) Stops any load changes in progress (CC3) o Places ramp on hold, if still in progress o If ramp complete, removes MW and Impulse feedbacks and resets VPL SRO/ATC Reads NOTE regarding impact dilution would have on initial shutdown margin determination (4) Stops boration if still in progress (Makeup Control HMI, CC2)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r0a.doc Page 11 of 35 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 4 Page 9 of 27 Event

Description:

Rod Control Urgent Failure / Dropped Rod Time Position Applicants Actions or Behavior (OP AP12C, "Dropped Control Rod", continued)

SRO/BOP (5) Checks Tave within +/- 1.5oF Tref; adjusts turbine load as needed to bring within band (CC3)

SRO (6) Checks Axial Flux Difference (AFD) within T.S. 3.2.3 limits (it is)

Note: May request SM assign performance of STP R25 to other available personnel SRO (7) Verifies QPTR is less than 1.02 (it is)

Note: May request SM assign performance of STP R19 to other available personnel.

SRO (8) Performs STP R19, Attachment 9.4 within an hour to verify SDM within limits of COLR SRO (9.a. RNO) Identifies Rod Control Urgent Failure has occurred (a.1 RNO) Directs crew not to move rods or reset Urgent Failure (a.2 RNO) Contacts maintenance for troubleshooting (a.3 RNO) Refers to AR PK0317, "Rod Control Urgent Failure" (continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r0a.doc Page 12 of 35 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 4 Page 10 of 27 Event

Description:

Rod Control Urgent Failure / Dropped Rod (continued)

Time Position Applicants Actions or Behavior (AR PK0317, "Rod Control Urgent Failure")

SRO Reviews Annunciator General Actions o May note actions already completed as part of OP AP12C o Reviews applicable Tech Specs and ECGs Enters Tech Spec 3.1.4.B - One rod not within alignment limits Required actions:

o Restore rod to within alignment limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OR o Verify or restore SDM to be within COLR limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> along with series of actions to verify SDM is maintained Proceed to the next event once T.S. addressed, per Lead Examiner

• • Critical Task L121 NRC Sim Exam 04 r0a.doc Page 13 of 35 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 5 Page 11 of 27 Event

Description:

FullLoad Rejection / Reactor Trip Time Position Applicants Actions or Behavior ALL Diagnoses loss of load (fullload rejection) using one or more of the following indications:

PK1405, "Generator Underfrequency" in alarm PK1424, "Unit's 500 kV Breakers Open" in alarm PK2025 500 "kV Switchyard" in alarm Group I and II steam dumps armed, open, and steaming (VB3)

Main generator output breakers tripped open (CKT BKRs 632 and 532) (CC3, far right)

Note: Step 1 of OP AP2, "Full Load Rejection" directs crew to trip the Rx and go to EOP E0 if control rods fail to insert in auto. Shift Foreman may elect to trip reactor based on plan conditions and enter EOP E0 directly.

SRO Implements OP AP2, "Full Load Rejection" (OP AP2, "Full Load Rejection") if entered; else N/A SRO/ATC (1) Determines control rods are not inserting in Auto (1 RNO) Shift Foreman directs Reactor Trip and transitions to EOP E0, "Reactor Trip or Safety Injection" (EOP E0,"Reactor Trip or Safety Injection")

ALL Crew enters EOP E0 on Rx Trip and silently performs immediate actions:

Verifies reactor trip (trip bkrs open, rods on bottom, NIs decreasing)

Verifies turbine trip (stop valves closed (CC3 HMI or VB2 RPS indicator lamps)

Checks vital 4kv busses (VB4, vital busses F/G/H have white lights on mimic busses)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r0a.doc Page 14 of 35 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 5,6 Page 12 of 27 Event

Description:

FullLoad Rejection / Reactor Trip (continued)

Loss of Startup Power Time Position Applicants Actions or Behavior (EOP E0,"Reactor Trip or Safety Injection")

SRO/ATC (1) Verifies reactor trip (trip bkrs open, rods on bottom, NIs decreasing)

SRO/ATC (2) Verifies turbine trip (stop valves closed) (CC3 HMI or VB2 RPS indicator lamps)

SRO/BOP (3) Checks vital 4kv bus status (VB4, white lights on mimic; only vital bus G is illuminated) o Determines only one vital bus is energized (Bus G, which is powered by D/G 1 2)

Buses F and H are deenergized (white lights out on VB4 mimic)

May note loss of 230kV and failure of D/G 13 to start (shutdown relay tripped)

May note D/G 11 OOS since beginning of shift Note: Shift Foreman may elect to postpone implement EOP ECA0.3 until review of immediate actions has been completed and priorities evaluated based on plant conditions. (see pg 16 for actions)

SRO/BOP (3.a.2 RNO) Directs operator to IMPLEMENT EOP ECA0.3, "Loss of All Vital AC Power" SRO/ATC (4) Checks for SI actuated (PK0821: ON) o (4.a RNO) Determines SI is neither actuated nor required PK0202 is OFF Safeguards bistable status lights are out (logic for SI is not made up)

(VB1, left upper area, just below PK01 and PK02) o (4.a.2. RNO) Announces Reactor Trip on PA (continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r0a.doc Page 15 of 35 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 5 Page 13 of 27 Event

Description:

FullLoad Rejection / Reactor Trip (continued)

Time Position Applicants Actions or Behavior (EOP E0,"Reactor Trip or Safety Injection", continued)

SRO/ATC o (4.a.3 RNO) Controls AFW flow to reduce cooldown while maintaining a secondary heat sink Checks for adequate secondary heat sink (S/G level 15% in at least 1 S/G or total AFW flow 435 gpm) (VB3, upper right)

Monitors RCS Loop Tcolds for indications of cooldown (VB2, lower center chart recorders or PPC); throttles feedflow if cooldown continues (VB3, lower left)

SRO Transitions to E0.1 ("Reactor Trip Response")

(EOP E0.1,"Reactor Trip Response")

Note: Step 1 of E0.1 partially repeats last direction given in E0 (reduce cooldown/maintain heat sink), but also looks at potential for heatup. Actual actions required will depend on length/depth of pretrip transient.

SRO/ATC (1) Checks RCS temperature stable or trending to 547oF based on RCS Loop Tcolds (RCPs tripped) (VB2, lower center chart recorders or PPC) o If RCS temp < 547oF and decreasing :

checks steam dumps (VB3, indicator lights middle) and S/G blowdown isolation valves outside containment (VB3, lower left skirt) all closed.

Also checks MSRs reset on on Turbine Control HMI (CC3) throttles AFW feedflow as needed to stop cooldown while maintaining heat sink (S/G level 15% in at least 1 S/G or total AFW flow 435 gpm) (VB3, upper right) o RCS temp > 547oF and increasing If required, sets 10% dump controllers to 1005 psig, (83.8% setpoint)

(VB3, lower left) verifies dumps modulate open to control temperature at 547oF Monitoring of RCS temperature stable assigned as Continuous Action (continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r0a.doc Page 16 of 35 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 5 Page 14 of 27 Event

Description:

FullLoad Rejection / Reactor Trip (continued)

Time Position Applicants Actions or Behavior (EOP E0.1,"Reactor Trip Response", continued)

Note: If Tave is still greater than 554oF, feedwater isolation will NOT be in (dependent on pretrip transient)

SRO/ATC (2) Checks Feedwater Status (a) RCS temperature < 554oF (VB2, lower center chart recorders or PPC)

(b) Checks Feedwater Isolation has occurred Feedwater Isolation portion of Monitor Light Box C (VB1)

(Red lights ON / White lights ON for FCV438, 440, and 441 due to bus F and H power loss); contacts Turbine Watch to close valves (c) Checks total AWF flow greater than 435 GPM (VB3, upper middle)

SRO/ATC (3) Checks Rods fully inserted (VB2DRPI)

SRO/ATC (4) Checks Pressurizer level controls o (a) Level greater than 17% (VB2, middle right) o (b) Charging in service with adequate flow (VB2)(CC2) o (c) Letdown in service (VB2, upper middle skirt) o (d) Pressurizer level trending to 22% (VB2, middle right)

(may adjust charging to maintain level 22% to 60%)

o (e) May energize pressurizer heaters (CC1, lower left)

SRO/ATC Reads CAUTION regarding Aux Spray and notes as N/A (Aux Spray not in service)

(5) Checks Pressurizer pressure control o (a) Pressure greater than 1850 psig (VB2, far right) o (b) Pressure stable or trending to 2235 psig (VB2)(CC2)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r0a.doc Page 17 of 35 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 5 Page 15 of 27 Event

Description:

FullLoad Rejection / Reactor Trip (continued)

Time Position Applicants Actions or Behavior (EOP E0.1,"Reactor Trip Response", continued)

SRO/ATC (6) Checks S/G NR levels greater than 15%

o (a) Reports all S/G NR levels greater than 15% (VB3, upper middle) o (b) Will control AFW flow to maintain S/G NR levels between 20% and 65%

o (c, d) Checks TD AFW Pump required for heat removal Reports TD AFW pump is required for heat removal (only running AFW pump until bus F power restored) (VB3, center skirt)

Monitoring of S/G levels assigned as Continuous Action Proceed to the next event once 4kV Bus F is reenergized, per Lead Evaluator

• • Critical Task L121 NRC Sim Exam 04 r0a.doc Page 18 of 35 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 5,6 Page 16 of 27 Event

Description:

FullLoad Rejection / Reactor Trip (continued)

Loss of Startup Power Time Position Applicants Actions or Behavior Note 1: Implementation of EOP ECA0.3 may be assigned to individual control operator (typically the BOP) and performed in parallel with actions of crew.

Note 2: The following actions are directed as part EOP E0, step 3 RNO (Ensure Vital 4kV Bus Status), directed on page 12 of this outline.

(EOP ECA0.3,"Restore 4kV Buses")

BOP Reads CAUTION regarding risk of hazards assoicated with significant electrical fault conditions Reads CAUTION regarding safety of local operators if bus is reenergized during stipping of loads (1) Checks availability of D/Gs associated with denergized vital buses o May contact electrical maintenance and/or work control to expedite return of D/G 11 o Identifies D/G 13 Shutdown Relay actuated (PK1815 in alarm); no other problems indicated on bus F May dispatch operator to walk down D/G 13 May take D/G 13 mode select switch to MAN (if not taken to manual, reset of shutdown relay will result in Autostart of D/G and loading of Bus F equipment) (VB4, below and to left of Shutdown Relay Reset)

(1.a) Starts D/G 13 o Resets D/G 13 Shutdown Relay and Alarm Reset (VB4, far right center - yellow lamicoid, just below D/G 13 tach) o Verifies Shutdown Relay resets (PK1815 clears)

If mode select switch was taken to manual, manually starts D/G 13 (VB4 below and to left of Shutdown Relay Reset)

(1.b) Verifies Bus F energized o Informs Shift Foreman D/G 13 is running and bus F energized Note: May continue on in ECA 0.3 while waiting for report back from field on D/G 13 status.

(continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r0a.doc Page 19 of 35 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 5,6 Page 17 of 27 Event

Description:

FullLoad Rejection / Reactor Trip (continued)

Loss of Startup Power Time Position Applicants Actions or Behavior (EOP ECA0.3,"Restore 4kV Buses", continued)

BOP Reads NOTE prior to step 2 regarding D/G running with deenergized bus (2) Prepares buses for return of offsite power o (a) Places AUTO TRANSFER to STARTUP CUTOUT switches to CUTOUT position for all 4kV and 12kV buses ( VB4 and VB5 skirt, switches located directly above corresponding AUTO XFR RESET pushbuttons (Blue lights illuminated) (7 switches) o (b) Depresses AUTO XFR RESET pushbuttons on all 4kV and 12kV buses and verifies blue lights go out (VB4 and VB5 skirt, next to illuminated blue lights) o (c) Places condensate booster pump selector switches to MAN position (VB3, lower right skirt)

Reads CAUTION to not open breaker supplying power to a bus o (d) Opens all Aux and Startup Feeder Breakers to Deenergized 4kV Vital Buses (VB4 skirt)

Opens 52HH13 (Aux XFMR 12 to 4kV Bus H)

Opens 52HH14 (S/U XFMR 12 to 4kV Bus H)

Opens 52HF13 (Aux XFMR 12 to 4kV Bus F)

Opens 52HF14 (S/U XFMR 12 to 4kV Bus F) o (e) Opens all Aux and Startup Feeder Breakers to Deenergized 4kV NonVital Buses (VB5 skirt)

Opens 52HE2 (Aux XFMR 12 to 4kV Bus E)

Opens 52HE3 (S/U XFMR 12 to 4kV Bus E)

Opens 52HD15 (Aux XFMR 12 to 4kV Bus D)

Opens 52HD14 (S/U XFMR 12 to 4kV Bus D) o (f) Opens all Aux and Startup Feeder Breakers to Deenergized 12kV Buses (VB5 skirt)

Opens 52VD8 (Aux XFMR 12 to 4kV Bus E)

Opens 52VD4 (S/U XFMR 12 to 4kV Bus E)

Opens 52VE2 (Aux XFMR 12 to 4kV Bus D)

Opens 52VE6 (S/U XFMR 12 to 4kV Bus D)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r0a.doc Page 20 of 35 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 5,6 Page 18 of 27 Event

Description:

FullLoad Rejection / Reactor Trip (continued)

Loss of Startup Power Time Position Applicants Actions or Behavior (EOP ECA0.3,"Restore 4kV Buses", continued)

BOP (3) Verifies SI is Reset (notes SI not actuated or required)

Note: If contacted, Generation Control Center (GCC) will report both 230kV and 500kV lines are out of service as result of earthquake; scope of damage is still being evaluated and return to service time is yet to be determined.

BOP Reads NOTE regarding Shift Foreman discretion for selecting preferred offsite power source o May consult with Shift Foreman regarding preferred source o May contact Generation Control Center (GCC) to determine status of 500kV and/or 230 kV power (4) Checks 500 kV Power Available o May use sync switch on 500kV circuit breakers (532 or 632) to check power availability (CC3, far right) o Determines 500 kV is not available (5) Checks 230 kV Power Available to either Unit o Notes 230kV Bus indicator light is not lit (far right, top of skirt, VB5) o Determines 230 kV is not available Proceed to the next event once 4kV Bus F is reenergized, per Lead Evaluator

• • Critical Task L121 NRC Sim Exam 04 r0a.doc Page 21 of 35 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 7,8 Page 19 of 27 Event

Description:

Large Break LOCA RHR and Containment Spray Pump Autostart Failures (CT)

Time Position Applicants Actions or Behavior Note: The DBA LBLOCA will occur rapidly, causing an immediate Safety Injection; no actions are expected other than recognition of the earthquake and SI prior to reentry into E0, starting at step 1.

(EOP E0,"Reactor Trip or Safety Injection")

SRO/ATC (1) Verifies reactor trip (trip bkrs open, rods on bottom, NIs decreasing)

SRO/ATC (2) Verifies turbine trip (stop valves closed) (CC3 HMI or VB2 RPS indicator lamps)

SRO/BOP (3) Checks vital 4kv bus status (VB4, white lights on mimic; buses F and G are both illuminated) o Determines two vital buses energized (Bus G and F, both powered by respective D/Gs) o May note D/G 11 OOS since beginning of shift Note: Critical task to manually start at least one low head ECCS pump must be completed before transition out of E0. Action is addressed as part of App E, step 5 alignment verification, but may be addressed as soon as failure is identified.

SRO/ATC (4) Checks SI actuated (PK0821 ON, also checks VB1 red train light ON and/or train equipment to verify both trains actuated) o Both trains of SI actuated as indicated by PK, SI red light o May report SI pumps NOT running (SI Pp 11 tripped on OC; SI Pp 12 has no power - Bus H deenergized) o May report RHR pump status (RHR Pp 11 did not auto start, may have been started manually**; RHR Pp 12 has no power - Bus H deenergized)

• • Critical Task E0H: Manually start at least one low head ECCS pump before transition out of E0 (continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r0a.doc Page 22 of 35 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 7,8 Page 20 of 27 Event

Description:

Large Break LOCA RHR and Containment Spray Pump Autostart Failures (CT)

Time Position Applicants Actions or Behavior (EOP E0,"Reactor Trip or Safety Injection", continued)

SRO (5) Directs implementation of App E (usually given to BOP)

Note: Critical task to manually start at least one low head ECCS pump must be completed before transition out of E0; may have been addressed during performance of immediate actions BOP Implements App E (ESF Auto Actions, Secondary and Auxiliaries Status):

(1a) Checks no personnel in Containment (part of turnover; may not voice)

(1b) Announces trip/SI on PA system (2) Checks main generator - tripped (PK1401 ON, output bkrs open, and exciter field bkr open, CC3 right side)

(3 & 4) Verifies Phase A and Containment Vent Isolation complete (VB1, Monitor Light Box B: red lights ON, white lights OFF) o Notes only white light is associated with seal water Phase A isolation valve, inside containment; outside containment valve is closed (5) Verifies ESF (SI) actuation complete (SI Portion of Monitor Light Box C: red light ON, white lights some ON);

(5.a RNO) Determines CCP 11, 12, and SI 11 are tripped on overcurrent o Notes CCW 13, RHR 12, SI 12, and CFCU 14 not running due to loss of Bus H o Identifies RHR 11 autostart failure; manually starts pump** (if not previously identified)

• • Critical Task E0H: Manually start at least one low head ECCS pump before transition out of E0 (continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r0a.doc Page 23 of 35 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 7,8 Page 21 of 27 Event

Description:

Large Break LOCA RHR and Containment Spray Pump Autostart Failures (CT)

Time Position Applicants Actions or Behavior (EOP E0, Appendix E, continued)

Note: If Feedwater Isolation activated during E0.1 (RCS temp < 554oF), manual isolation may already be complete BOP (6) Verifies Feedwater isolation complete (F.W. Isolation and S.G. Level Portions of Monitor Light Box C: red lights ON, white lights OFF)

(6.a RNO)Notes white light ON for FW Isolation Valve FCV440 (also bus H);

contacts Turbine Watch to close valve (may wait to contact until after Shift Foreman status update at step 11)

Note: Critical task to start Containment Spray Pump (CSP) 11 may have been addressed during performance of immediate actions BOP (7) Determines Containment Spray and Phase B Isolation is required (Contmt Isol, Phase B portion of Monitor Light Box D: red lights are ON)

(7.a.1 RNO) May attempt to manually initiate Containment Isolation Phase B/Spray (VB1, directly below containment environment indications)

(7.a.2 RNO) Notes white lights on for Containment Spray Pump 12, Containment Spray valves 8994B and 9001B, and CCW valves: FCV746, FCV357, FCV749 are all due to loss of bus H. Identifies failed autostart of Containment Spray Pump 11; manually starts pump**

(7.a.3 RNO) Maintains RCP seal injection between 813 gpm (may need to start CCP 13)

(7.a.4 RNO) Notes RCPs are already tripped due to loss of 12 kV power

• • Critical task E0E: manually actuate at least the minimum required complement of containment cooling equipment before an extreme (redpath) challenge develops to the containment critical safety function. Minimum required complement of containment cooling equipment is defined as 2 Containment Fan Cooling Units (CFCUs) and 1 Containment Spray Pump.

(continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r0a.doc Page 24 of 35 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 7 Page 22 of 27 Event

Description:

Large Break LOCA Time Position Applicants Actions or Behavior (EOP E0, Appendix E, continued)

BOP (8) Checks Main Steamline Isolation complete (Main Steam Isolation portion of Monitor Light Box D: red light ON, white light are OFF)

Note: Step to control AFW to limit cooldown may have already been completed (E0, step 6 RNO) by other crew members; actions taken in Appendix E should reflect overall mitigation strategy (9) Checks AFW status o AFW Pp 13 and TDAFP both running o Reverifies min of 435 gpm flow (VB3 center) or S/G level > 25% (adverse containment) (VB3 center)

BOP (10) Checks ECCS flows (charging injection (VB2 upper panel left), SI, RHR (both on VB1 upper panel); notes RHR 11 is the only available and running ECCS pump (11) Reports ESF and AFW status to the Shift Foreman (Shift Foreman may direct operator to continue on in Appendix E, or redirect to higher priority tasks)

BOP (12 & 13) Checks excess letdown - not in service (8166/8167 closed); turns on aux bldg vent charcoal filter preheater (VB4 lower panel, left side)

(14) Checks secondary systems (MFPs tripped (VB2, green lights ON), stops all but one CB Pp set, takes LCV12 control switch to CONT ONLY. Determines Condenser is NOT available (MSIVs are closed) and directs field operators to break vacuum when turbine is less than 200 rpm (15) Verifies proper operation of Aux Bldg and Control Rm vent systems (VB4 vent status light panel white lights); verifies containment iodine fans secured (VB4, lower panel)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r0a.doc Page 25 of 35 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 7 Page 23 of 27 Event

Description:

Large Break LOCA Time Position Applicants Actions or Behavior (EOP E0, Appendix E, continued)

(16) Verifies available DGs running normally (VB4, freq (60), volts (120), speed (900))

(17) Verifies vital batteries supplied by chargers (charger and bus volts on VB5, upper panel middle/lower area);

(18) Verifies MSRs reset (CC3 Triconex HMI)

(19) Throttles RCP seal injection flows to normal if needed (FCV128, to 813 gpm each, CC2)

(20) Checks PK1104 NOT IN (SFP alarm)

(21) Notifies Shift Foreman of completion (EOP E0, Reactor Trip or Safety Injection", continued)

SRO/ATC (6) Checks RCS temperature stable or lowering to 547oF o Notes temperature has dropped significantly due to LBLOCA,(VB2, upper panel lower area) o May throttle AFW back, but with no impact - may verbalize secondary no longer functioning as heat sink (VB3, lower left skirt)

SRO/ATC (7) Checks Pzr PORVs and Pzr Safeties and Spray Valves o Safeties closed (closed); no sonic flow, tailpipe temperature is elevated, but consistent with containment environment (VB2 - upper panel, far right) o PORVs closed and associated block valves open, with exception of PCV456 failure from earlier which has already been addressed (VB2 - upper panel, far right) o Pzr Sprays closed (green lights on) (CC2)

SRO/ATC (8) Checks RCP trip criteria; notes RCPs already tripped from loss of 12 kV (VB2)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r0a.doc Page 26 of 35 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 7 Page 24 of 27 Event

Description:

Large Break LOCA RHR and Containment Spray Pump Autostart Failures Time Position Applicants Actions or Behavior (EOP E0, Reactor Trip or Safety Injection", continued)

SRO/ATC (9) Determines S/G are NOT faulted o May note S/Gs are depressurizing, but as consequence of LBLOCA cooldown o None are completely depressurized SRO/ATC (10) Determines S/G are NOT ruptured Checks RE71/72/73/74 and RE15/19 recorders onVB2 (and PPC); (all normal)

PK1106/17/18 (all OFF)

May request samples SRO/ALL (11) Checks RCS intact (it is not) (note: only one valid abnormal reading needed to transition from E0)

(11a) Determines containment pressure is NOT normal (it is elevated) (VB1 meters, PPC)

(11b) Determines containment sump levels NOT normal (they are elevated) (VB1 meters, PAMS)

(11c) Determines containment radiation is NOT normal (RM11, 02, 07 are all in alarm)

(11 RNO) Places 2nd ASW/CCW HX in service (opens FCV603 and FCV431, VB1 far left), and transition to EOP E1, "Loss of Reactor or Secondary Coolant" (continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r0a.doc Page 27 of 35 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 7 Page 25 of 27 Event

Description:

Large Break LOCA Time Position Applicants Actions or Behavior (EOP E0, Reactor Trip or Safety Injection", continued)

SRO Performs procedure transition brief for E1, and implements CSFST (if required)

Note: A CSFST MAGENTA path may occur prior to EOP E1 entry or before the end of the scenario (FRP.1 on PTS); If its occurs, it will be a short entry (perform a single step and exit)

SRO Implements FRP.1, Imminent PTS (if MAGENTA path occurs)

(ONLY IF FRP.1, Imminent PTS, is entered; otherwise, this section is N/A)

SRO/ATC (1) Checks RCS pressure (low), and RHR flow (normal); exits to procedure in effect SRO Implements EOP E1, Loss of Reactor or Secondary Coolant (EOP E1, Loss of Reactor or Secondary Coolant)

SRO/ATC (1) Checks RCPs tripped (already done, VB2)

ATC/BOP (2 & 3) Checks for faulted/ruptured S/Gs o Faulted - checks all S/G pressures on VB3 (not uncontrolled drop/depressurized; all are dropping slowly, as the primary is now the heat sink for the secondary) o Ruptured - checks RE71/72/73/74 and RE15/19 recorders on VB2 (and PPC; no upward trends or spikes, unless containment shine is noted), and PK1106/17/18 (alarms not in); requests chemistry to sample S/Gs for activity (as follows, if done):

Verifies phase A containment isolation reset (VB1)

Opens FCV584 (air to containment) (VB4, lower left)

Opens blowdown isolation valves inside containment (FCV760, 761, 762, 763) if requested for sampling (continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r0a.doc Page 28 of 35 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 7 Page 26 of 27 Event

Description:

Large Break LOCA Time Position Applicants Actions or Behavior (EOP E1, Loss of Reactor or Secondary Coolant)

BOP (4) Maintains S/G levels 2065%

(5) Reverifies PORVs closed and associated block valves open (PCV456 failure BOP addressed earlier) (VB2 - upper panel, far right)

ATC (6) Determines Containment Spray should remain in service o (a) PK0118 is ON o (b) Containment radiation levels are above normal (PK1121 is ON, RE2/RE7 in alarm (b RNO) Verifies spray system still in service (VB1, middle skirt)

ATC (7) Determines ECCS flow should NOT be reduced o (a) RCS subcooling is less than 20oF (SCMM YI31, lower center VB2)

SRO/ATC Reads CAUTION regarding running RHR pump with cooling to associated heat exchanger; may note Hx already in service (8) Determines RHR pump should NOT be stopped o (a.1) Notes pressure is less than 300 psig (a.1 RNO) Checks all available RHR pumps running, continues to step 10 SRO/BOP (10) Determines D/G should NOT be stopped o (a) Offsite power is not available, Bus F and G currently supplied by respective D/Gs (a.1 RNO) May implement OP AP26, "Loss of Offsite Power" (Offsite power will not be returned; observable Control Room actions repeat steps of ECA 0.3 performed earlier in the scenario)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r0a.doc Page 29 of 35 Rev 0

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 7 Page 27 of 27 Event

Description:

Large Break LOCA Time Position Applicants Actions or Behavior (EOP E1, Loss of Reactor or Secondary Coolant)

SRO/ATC (10.b) Resets SI (VB1, center, below PK2)

SRO/ALL (11) Evaluates Plant Status o (a) Verifies cold leg recirculation capability - power available to RHR 11 o (b) Checks Aux building radiation monitor - all are Normal o (c) Checks if running RHR pump is on recir - it is not o (d) Directs RO to Implement Appendix P, Monitor Light Box Verification (checks ECCS valve lineup) o (e) Contacts Chemistry to sample the RCS and place H2 analyzers in service o (f) Checks Turbine status (oil pumps, coast down, etc) o (g) Checks for alarms on Spent Fuel Pool level and temperature SRO/ATC (12) Determines that post LOCA cooldown procedure (EOP 1.2) is not appropriate o (RCS pressure is < 300 psig (VB2, PPC, CC2) o RHR flow > 100 gpm (VB2)

Stays in E1, awaiting transition to Cold Leg Recirc (RWST @ 33%)

The scenario is terminated once crew has completed actions of EOP E1 and is waiting to transition to Cold Leg Recirc, per Lead Evaluator

• • Critical Task L121 NRC Sim Exam 04 r0a.doc Page 30 of 35 Rev 0