Text

DC 2018-01 Final Operating Test
	ML18064A353
Person / Time
Site:	Diablo Canyon
Issue date:	02/09/2018
From:	Vincent Gaddy; Operations Branch IV
To:	; Pacific Gas & Electric Co
References
	Download: ML18064A353 (315)
	v • d • e

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Diablo Canyon Date of Examination: 01/19/2018 Examination Level: RO SRO Operating Test Number: L162 Administrative Topic (see Note) Type Describe activity to be performed Code*

Determine Affected Indicators Due To Malfunction of Eagle 21 Protection or Conduct of Operations N, R Control Channel (NRCL162-A1) 2.1.7 Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrument interpretation.

(4.4)

Calculate Rod Position Alignment and Rod Insertion Limits Conduct of Operations N, R 2.1.23 Ability to perform specific system and (NRCL162-A2) integrated plant procedures during all modes of plant operation.

(4.3)

Calculate Axial Flux Difference Equipment Control 2.2.42 Ability to recognize system parameters that M, R are entry-level conditions for Technical (NRCL162-A3) Specifications. (3.9) (modified from L061C)

Calculate Maximum Stay Time Radiation Control 2.3.4 Knowledge of radiation exposure limits M, R under normal or emergency conditions.

(NRCL162-A4) (3.2)

(modified from L111 NRC)

NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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

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

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

Rev 1

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Diablo Canyon Date of Examination: 01/19/2018 Examination Level: RO SRO Operating Test Number: L162 Administrative Topic (see Note) Type Describe activity to be performed Code*

Review AP-5 Bistable Trip Authorization Form Conduct of Operations N, R 2.1.7 Ability to evaluate plant performance and (NRCL162-A5) make operational judgements based on operating characteristics, reactor behavior, and instrument interpretation.

(4.7)

Review Rod Position Alignment and Rod Insertion Limits Conduct of Operations N, R 2.1.23 Ability to perform specific system and (NRCL162-A6) integrated plant procedures during all modes of plant operation.

(4.3)

Verify AFD is within Tech Spec Limits Equipment Control 2.2.42 Ability to recognize system parameters that M, R are entry-level conditions for Technical (NRCL162-A7) Specifications. (4.6) (Modified from L061C)

Approve Liquid Waste Release Permit Radiation Control 2.3.6 Ability to approve release permits. (3.8)

M, R (Modified from L061C)

(NRCL162-A8)

Perform an Emergency Classification Emergency Plan 2.4.41 Emergency Procedures/Plan.

N, R (4.6)

(NRCL162-A9)

NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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

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

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

Rev 1

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL162-A1

Title:

Determine affected indicators due to malfunction of Eagle 21 protection or control channel.

Examinee:

Evaluator:

Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments: Designed for RO candidates in a classroom setting.

References:

OP AP-5, Malfunction of Eagle 21 Protection or Control Channel

Handout with Annunciator and Reactor Trip and ESF Bistable Channels status Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 20 minutes Critical Steps: 1.3, 1.5 Job Designation: RO Rev Comments New Gen KA # 2.1.7 - Ability to evaluate plant performance and make 4.4 operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

AUTHOR: JARED SMITH DATE: 10/31/17 OPERATIONS REPRESENTATIVE: CHRIS MEHIGAN DATE: 10/31/17 REV.0

JPM TITLE: Determine affected indicators due to malfunction of JPM NUMBER: NRCL162-A1 Eagle 21 protection or control channel.

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 examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee. The examiner will then ask if any clarifications are needed. Since this is an administrative JPM, and the simulator is not used, the examinee may be given a copy of the required materials below. The examinee should be given the Initial cue sheet (page 7) along with the handout and procedure.

Required Materials:

OP AP-5, Malfunction of Eagle 21 Protection or Control Channel

Handout with Annunciator and Reactor Trip and ESF Bistable Channels status Initial Conditions: GIVEN:

Unit 1 is at 100% power

The control room received multiple alarms including PK 06-01 PPS Channel Set Failure and PK 06-04 PPS Trouble. OP AP-5, Malfunction of Eagle 21 Protection or Control Channel is in progress due to a LCP halt.

All Primary and Secondary control systems are within their normal operating limits and controlling properly.

Unit 2 BOPCO has been assigned to perform AP-5 att. 4.3Eagle 21 Rack Inspection/Compensatory Measure Tracking Sheet and identification of which red LEDs are LIT.

Initiating Cue:

The Shift Foreman has directed you to determine which protection set and rack is impacted as well as the affected indicators.

Document your findings before reporting out. This should include any necessary corrections, comments, and notifications.

Task Standard: DO NOT READ TASK STANDARD TO EXAMINEE

Determined Protection Set 2 Rack 8 affected from LCP Halt.

Determined affected indicators: PT-506, LT-519/549, TE-433A/B, TE-443A/B, TE-420A/421A/422A/420B/421B, and PT-936.

NRCL162-A1 r0 PAGE 2 OF 7 REV.0

JPM TITLE: Determine affected indicators due to malfunction JPM NUMBER: NRCL162-A1 of Eagle 21 protection or control channel.

EVALUATOR WORKSHEET Start Time:

Step Expected Operator Actions 1.** Note: Exam copy of OP AP-5 and Handout provided to examinee.

Obtain correct procedure 1.1 Referenced OP AP-5, Malfunction of Eagle 21 Protection or Control Channel.

Perform Step 2. Determine Extent of 1.2 Observed NOTEs 1 and 2 prior to step 2.

Eagle 21 Instrument Failure:

(RNO column shall be used)

IF PK 06-01 OR PK 06-03 is ON, 1.3** Step 2.a.1. RNO Checked PK 06-01 is ON (examinee performed actions in Response Not Obtained column)

Referenced handout with Annunciator windows PK06-01 and PK06-04 in alarm.

Also, referenced handout with SSPS Protection and Safeguards Bistables illuminated (LC 519A/b, LC 549A/B, PC 936A). Determined Protection Set 2 Rack 8 is affected.

1.4 Step 2.a.2 RNO CUE: Another operator has been assigned to perform RNO steps 2.a.2.

(Att. 4.3 Eagle 21 Rack Inspection/Compensatory Measure Tracking Sheet and identification of which red LEDs are LIT).

IF PK 06-01 is ON, 1.5** Used handout with Reactor Trip and ESF THEN perform the following: Bistable Channels status and OP AP-5 attachment 4.1 "Reactor Trip and ESF Bistable Channels to be Placed in Correct Position per Technical Specifications."

Student determined Protection Set 2 Rack 8 affected Instrument Channels/Indicators are:

PT-506, LT-519/549, TE-433A/B, TE-443A/B, TE-420A/B, TE-421A/B, TE-422A, and PT-936.

- Denotes Critical Step and Sub Steps.

NRCL162-A1 r0 PAGE 3 OF 7 REV.0

JPM TITLE: Determine affected indicators due to malfunction JPM NUMBER: NRCL162-A1 of Eagle 21 protection or control channel.

EVALUATOR WORKSHEET 1.6 Student notified SFM of affected board indicators.

Step was: Sat: ______ Unsat _______

Comments:

Stop Time:

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

- Denotes Critical Step and Sub Steps.

NRCL162-A1 r0 PAGE 4 OF 7 REV.0

JPM TITLE: Determine affected indicators due to malfunction of JPM NUMBER: NRCL162-A1 Eagle 21 protection or control channel.

EVALUATOR WORKSHEET Follow-up Question Documentation:

Question: ____________________________________________________________________

Response: ____________________________________________________________________

NRCL162-A1 R0 PAGE 5 OF 7 REV.0

JPM TITLE: Determine affected indicators due to JPM NUMBER: NRCL162-A1 malfunction of Eagle 21 protection or control channel.

ANSWER KEY EXAMINEE RESPONSE

Determined Protection Set 2 Rack 8 affected from LCP Halt.

Determined affected indicators: PT-506, LT-519/549, TE-433A/B, TE-443A/B, TE-420A/421A/422A/420B/421B, and PT-936.

NRCL162-A1 R0 PAGE 6 OF 7 REV.00

JPM TITLE: Determine affected indicators due to malfunction of JPM NUMBER: NRCL162-A1 Eagle 21 protection or control channel.

EXAMINEE CUE SHEET Initial Conditions: GIVEN:

Unit 1 is at 100% power

The control room received multiple alarms including PK 06-01 PPS Channel Set Failure and PK 06-04 PPS Trouble. OP AP-5, Malfunction of Eagle 21 Protection or Control Channel is in progress due to a LCP halt.

All Primary and Secondary control systems are within their normal operating limits and controlling properly.

Unit 2 BOPCO has been assigned to perform AP-5 att. 4.3Eagle 21 Rack Inspection/Compensatory Measure Tracking Sheet and identification of which red LEDs are LIT.

Initiating Cue:

The Shift Foreman has directed you to determine which protection set/rack is impacted and the affected indicators.

Document your findings before reporting out. This should include any necessary corrections, comments, and notifications.

EXAMINEE RESPONSE NRCL162-A1 R0 PAGE 7 OF 7 REV.00

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL162-A2

Title:

Calculate Rod Position Alignment and Rod Insertion Limits Examinee:

Evaluator:

Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments: Designed for RO candidates in a classroom setting.

References:

STP I-1A Routine Shift Checks Required by Licenses, Rev. 137

COLR 1, U1, COLR for Diablo Canyon Unit 1, Rev. 11

COLR 2, U2, COLR for Diablo Canyon Unit 2, Rev. 10

PPC Data printout Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 1.1, 2.1, 3.2, 3.3, 3.4, 3.6 Job Designation: RO Rev Comments New Gen KA # G2.1.23 Ability to perform specific system and integrated 4.3 plant procedures during all modes of plant operation.

AUTHOR: JARED SMITH DATE: 10/31/17 OPERATIONS REPRESENTATIVE: CHRIS MEHIGAN DATE: 10/31/17 REV.0 P0

JPM TITLE: Calculate Rod Position Alignment and Rod Insertion JPM NUMBER: NRCL162-A2 Limits 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 examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee. The examiner will then ask if any clarifications are needed. Since this is an administrative JPM, and the simulator is not used, the examinee may be given a copy of the required materials below. The examinee should be given the Initial cue sheet along with the handout and procedure.

Required Materials:

STP I-1A Routine Shift Checks Required by Licenses, Rev. 137

COLR, U1, COLR for Diablo Canyon Unit 1, Rev. 11

COLR, U2, COLR for Diablo Canyon Unit 2, Rev. 10

PPC Data (Handout)

Initial Conditions: GIVEN:

Unit 1 has been at reduced power for the past 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months due to the Heater 2 Drain Pump being out of service for maintenance.

All Unit 1 individual rod position PPC addresses have a quality code of good (green) on PPC GRPDIS-DRPI.

Initiating Cue:

You are directed to complete STP I-1A steps 12.10 through 12.12.

Document whether each step is satisfactory before reporting out to the Shift Foreman. This should include any necessary comments and/or notifications.

Task Standard: DO NOT READ TASK STANDARD TO EXAMINEE

Step 12.10, Determined each rod position on DRPI is within 12 steps of its group step counter.

Step 12.11, Checked all shutdown bank step counters are above 225 steps.

Step 12.12, Determined COLR insertion limits are NOT met.

Step 12.12.6, Notified the SFM that the performance of step 12.13 is required within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months due to COLR insertion limits not met.

NRCL162-A2 r0 PAGE 2 OF 11 REV.0

JPM TITLE: Calculate Rod Position Alignment and Rod JPM NUMBER: NRCL162-A2 Insertion Limits EVALUATOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Perform step 12.10 Rod Position Note: Observed Note prior to step.

Alignment Examinee referenced handouts for information.

1.1** Checked DRPI indications and group step counters. Determined to be within 12 steps of each other. Initialed step 12.10.1.

DRPI indicated Control Banks A & B at 228 steps. CBA & CBB step counters indicated 229 steps (1 step difference).

DRPI indicated CBC at 222 steps. CBC group step counters indicated 215 steps (7 step difference). DRPI indicated CBD at 96 steps. CBD group step counters indicated 87 steps (9 step difference). All Shutdown banks indicated 228 steps on DRPI and 229 steps on the group step counters (1 step difference).

1.2 Marked step 12.10.1.a N/A.

1.3 Marked step 12.10.1.b N/A.

1.4 Initialed step 12.10.2. Information given in initial conditions.

Step was: Sat: ______ Unsat _______

Comments:

- Denotes Critical Step and Sub Steps.

NRCL162-A2 r0 PAGE 3 OF 11 REV.0

JPM TITLE: Calculate Rod Position Alignment and Rod JPM NUMBER: NRCL162-A2 Insertion Limits EVALUATOR WORKSHEET Step Expected Operator Actions

2. Perform step 12.11 Shutdown Bank Note: Examinee referenced handouts COLR Insertion Limits for information.

2.1** Checked all shutdown bank step counters. All shutdown bank step counters indicated 229 steps.

Determined all are above 225 steps.

Initialed step 12.11.1.

2.2 Determined step 12.11.2 is N/A.

2.3 Determined step 12.11.3 is N/A.

Step was: Sat: ______ Unsat _______

Comments:

- Denotes Critical Step and Sub Steps.

NRCL162-A2 r0 PAGE 4 OF 11 REV.0

JPM TITLE: Calculate Rod Position Alignment and Rod JPM NUMBER: NRCL162-A2 Insertion Limits EVALUATOR WORKSHEET Step Expected Operator Actions

3. Perform step 12.12 Control Bank Note: Examinee referenced handouts COLR Insertion Limits for information.

3.1 Determined thermal power level to be 65.4%. (Used PPC point U4300A15).

Initialed step 12.12.1.

Note: Examinee referenced Unit1 COLR 3.2** Recorded Insertion limit: Control Bank D at 90 steps (acceptable range is Bank D 89 - 91 steps) or Control Bank C at 217 steps (acceptable range is CBC 217-218 steps). Initialed step 12.12.2.

3.3** Recorded demand bank position: Bank D at 87 steps or Bank C at 215 steps.

Initialed step 12.12.3.

3.4** Checked each control bank is NOT at or above the insertion limit. Control Banks C & D are below the COLR Insertion limits. Examinee applied note to step 12.12.4.

3.5 Checked sequence and overlap limits specified in the COLR are met. Initialed step 12.12.5. (Note is acceptable) 3.6** Determined COLR insertion limits are NOT met. Notified SFM that step 12.13 to be performed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months due to COLR insertions limits not met.

(Examinee may initial step 12.12.6 or leave blank).

Step was: Sat: ______ Unsat _______

- Denotes Critical Step and Sub Steps.

NRCL162-A2 r0 PAGE 5 OF 11 REV.0

JPM TITLE: Calculate Rod Position Alignment and Rod JPM NUMBER: NRCL162-A2 Insertion Limits EVALUATOR WORKSHEET Comments:

Stop Time:

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

- Denotes Critical Step and Sub Steps.

NRCL162-A2 r0 PAGE 6 OF 11 REV.0

JPM TITLE: Calculate Rod Position Alignment and Rod JPM NUMBER: NRCL162-A2 Insertion Limits EVALUATOR WORKSHEET Follow-up Question Documentation:

Question: ____________________________________________________________________

Response: ____________________________________________________________________

NRCL162-A2 R0 PAGE 7 OF 11 REV.0

JPM TITLE: Calculate Rod Position Alignment and Rod JPM NUMBER: NRCL162-A2 Insertion Limits ANSWER KEY EXAMINEE RESPONSE

Step 12.10, Determined each rod position on DRPI is within 12 steps of its group step counter.

Step 12.11, Checked all shutdown bank step counters are above 225 steps.

Step 12.12, Determined COLR insertion limits are NOT met.

Step 12.12.6, Notified the SFM that the performance of step 12.13 is required within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months due to COLR insertion limits not met.

NRCL162-A2 R0 PAGE 8 OF 11 REV.0

JPM TITLE: Calculate Rod Position Alignment and Rod JPM NUMBER: NRCL162-A2 Insertion Limits ANSWER KEY NRCL162-A2 R0 PAGE 9 OF 11 REV.0

JPM TITLE: Calculate Rod Position Alignment and Rod JPM NUMBER: NRCL162-A2 Insertion Limits ANSWER KEY NRCL162-A2 R0 PAGE 10 OF 11 REV.0

JPM TITLE: Calculate Rod Position Alignment and Rod JPM NUMBER: NRCL162-A2 Insertion Limits EXAMINEE CUE SHEET Initial Conditions: GIVEN:

Unit 1 has been at reduced power for the past 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months due to the Heater 2 Drain Pump being out of service for maintenance.

All Unit 1 individual rod position PPC addresses have a quality code of good (green) on PPC GRPDIS-DRPI.

Initiating Cue:

You are directed to complete STP I-1A steps 12.10 through 12.12.

Document whether each step is satisfactory before reporting out to the Shift Foreman. This should include any necessary comments and/or notifications.

EXAMINEE RESPONSE Step 12.10 Result:

Step 12.11 Result:

Step 12.12 Result:

NRCL162-A2 R0 PAGE 11 OF 11 REV.0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL162-A3

Title:

CALCULATE AXIAL FLUX DIFFERENCE (AFD)

Examinee:

Evaluator:

Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments: Designed for RO candidates in a classroom setting.

References:

STP I-1C, Routine Weekly Checks Required By Licenses, Section 12.2, Rev.

116C

Volume 9B, Curves and Miscellaneous Data, Figure R23-1F-1, Unit 1 Cycle 21 RAOC Limits, Rev. 331 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 2.3, 2.4, 4.2, 5.2, 7.2, 8.1 Job Designation: RO Rev Comments New Gen KA # G2.2.42 Ability to recognize system parameters that are entry-level 3.9 conditions for Technical Specifications.

AUTHOR: JARED SMITH DATE: 10/31/17 OPERATIONS REPRESENTATIVE: CHRIS MEHIGAN DATE: 10/31/17 REV.0

JPM TITLE: CALCULATE AXIAL FLUX DIFFERENCE (AFD) JPM NUMBER: NRCL162-A3 INSTRUCTOR 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 examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee. The examiner will then ask if any clarifications are needed. Since this is an administrative JPM, and the simulator is not used, the examinee may be given a copy of the required materials below.

Required Materials:

Copy of STP I-1C, Routine Weekly Checks Required By Licenses, Section 12.2 Axial Flux Difference (AFD), Rev. 116C

Volume 9B, Curves and Miscellaneous Data, Figure R23-1F-1, Unit 1 Cycle 15 RAOC Limits, Rev. 331

Axial Flux Difference data (Handout)

Initial Conditions: Given:

Unit 1 rapidly ramped down power due to tube failures on the No. 3 and No. 4 Feedwater Heaters. Reactor power is currently stable at approximately 87%.

PK03-25, PPC RX ALARM AXIAL FLUX/ROD POSITION input 1251 is illuminated.

Indicated Reactor Power based on U1169A05 is 86.8%.

U4300A15 is not available.

PPC MAX NI power is 100.3% per latest STP R-2B1.

Initiating Cue:

Unit 1 BOPCO has been tasked with performing STP I-1C, Routine Weekly Checks Required By Licenses, Section 12.2 Axial Flux Difference (AFD). Determine if AFD is within the RAOC limits.

Document all your findings before reporting out to the Shift Foreman.

Task Standard: DO NOT READ TASK STANDARD TO EXAMINEE

Determined NI-42C and NI-43C exceeds RAOC limits.

Notified Shift Foreman that 2 excore channels exceed AFD limits.

NRCADM162-A3 PAGE 2 OF 7 REV. 0 R0.DOC

JPM TITLE: CALCULATE AXIAL FLUX DIFFERENCE (AFD) JPM NUMBER: NRCL162-A3 INSTRUCTOR W ORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 Obtained STP I-1C, Section 12.2.

Note: Provide exam copy of STP I-1C, Section 12.2 and AFD Handout.

Step was: Sat: _______ Unsat _______*

2. **Calculate current RTP %. 2.1 Ensured step 12.2.1 is marked N/A.

(Given in initial conditions) 2.2 Obtained MAX NI Power from initial conditions and recorded as 100.3%.

Ensured step 12.2.2.a box STP R-2B1, PPC Operator Heat Balance box is left unchecked and STP R-2B2/R-2B3 boxes marked N/A.

Initialed step 12.2.2.a 2.3 Calculated % RTP as follows:

U1169A05 value (86.8) / PPC Max (100.3) x 100. Approximately 86.5%

RTP. (86.4% -86.6% is acceptable).**

Note: Provide calculator (if necessary).

2.4 Verified RTP % to be 86.5%**

Step was: Sat: _______ Unsat _______*

3. Obtain the correct Figure. 3.1 Obtained Figure R23-1F-1 for Unit 1 from Volume 9.

Note: Provide exam copy of Figure R23-1F-1.

Step was: Sat: _______ Unsat _______*

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

NRCADM162-A3 PAGE 3 OF 7 REV. 0 R0.DOC

JPM TITLE: CALCULATE AXIAL FLUX DIFFERENCE (AFD) JPM NUMBER: NRCL162-A3 INSTRUCTOR W ORKSHEET Step Expected Operator Actions

4. **Determine Upper AFD Limit. 4.1 Referenced R23-1F-1.

4.2 Step 12.2.3, Determined Upper AFD Limit to be +14.0%.**

Step was: Sat: _______ Unsat _______*

5. **Determine Lower AFD Limit. 5.1 Referenced R23-1F-1.

5.2 Step 12.2.3, Determined Lower AFD Limit to be -14.5% (14.0% - 14.5%

is acceptable) **

Step was: Sat: _______ Unsat _______*

6. Record indicated AFD values 6.1 Step 12.2.4, Recorded indicated AFD values for each NI.

Step was: Sat: _______ Unsat _______*

7. **Determine AFD is within limits. 7.1 Step 12.2.4, Determined that AFD is within limits for NIs 41C and 44C and Yes boxes marked.

7.2 Determined that AFD is outside the limits for NIs 42C and 43C and No boxes are marked.**

Step was: Sat: _______ Unsat _______*

8. **Check at LEAST 3 excore channels 8.1 Step 12.2.5, Determined that 2 excore are within AFD Limits. channels are NOT within AFD limits.

(Examinee may include note on step 12.2.5) Informed SFM of the surveillance results.**

Step was: Sat: _______ Unsat _______*

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

NRCADM162-A3 PAGE 4 OF 7 REV. 0 R0.DOC

JPM TITLE: CALCULATE AXIAL FLUX DIFFERENCE (AFD) JPM NUMBER: NRCL162-A3 INSTRUCTOR W ORKSHEET Stop Time:

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

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

NRCADM162-A3 PAGE 5 OF 7 REV. 0 R0.DOC

JPM TITLE: CALCULATE AXIAL FLUX DIFFERENCE (AFD) JPM NUMBER: NRCL162-A3 ANSWER KEY EXAMINEE RESPONSE

Determined NI-42C and NI-43C exceeds RAOC limits.

Notified Shift Foreman that 2 excore channels exceed AFD limits.

NRCADM162-A3 PAGE 6 OF 7 REV. 0 R0.DOC

JPM TITLE: CALCULATE AXIAL FLUX DIFFERENCE (AFD) JPM NUMBER: NRCL162-A3 Initial Conditions: Given:

Unit 1 rapidly ramped down power due to tube failures on the No. 3 and No. 4 Feedwater Heaters. Reactor power is currently stable at approximately 87%.

PK03-25, PPC RX ALARM AXIAL FLUX/ROD POSITION input 1251 is illuminated.

Indicated Reactor Power based on U1169A05 is 86.8%.

U4300A15 is not available.

PPC MAX NI power is 100.3% per latest STP R-2B1.

Initiating Cue:

Unit 1 BOPCO has been tasked with performing STP I-1C, Routine Weekly Checks Required By Licenses, Section 12.2 Axial Flux Difference (AFD). Determine if AFD is within the RAOC limits.

Document all your findings before reporting out to the Shift Foreman.

EXAMINEE RESPONSE NRCADM162-A3 PAGE 7 OF 7 REV. 0 R0.DOC

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL162-A4

Title:

Calculate Maximum Stay Time Examinee:

Evaluator:

Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments: Designed for RO candidates in a classroom setting.

modified from L081NRCADM04, L061NRCADM04, & L111NRCADM04

References:

RP1.ID6, Personnel Dose Limits and Monitoring Requirements, Rev 15 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 3, 4 Job Designation: RO Rev Comments New Gen KA # G2.3.4 Knowledge of radiation exposure limits under normal 3.2 or emergency conditions.

AUTHOR: JARED SMITH DATE: 10/31/17 OPERATIONS REPRESENTATIVE: CHRIS MEHIGAN DATE: 10/31/17 REV.0

JPM

Title:

CALCULATE MAXIMUM STAY TIME JPM Number: NRCL162-A4 INSTRUCTOR 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 examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.

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

Required Materials:

RP1.ID6, Personnel Dose Limits and Monitoring Requirements, Rev 15

Calculator Initial Conditions: Given:

The Work Control Shift Foreman (WCSFM) and Work Control Lead (WCL) have assigned you to hang an outage clearance in two locations, which are both in a High Radiation Area.

The first portion of the clearance is in an area where the dose rate is 280 mrem/hr, and the work there will take 45 minutes.

The second portion of the clearance is in an area where the dose rate is 430 mrem/hr; it is not known how long this work will take.

Your current year exposure history (per NRC Form 4) is as follows:

Deep Dose Equivalent (DDE) = 969 mrem

Committed Dose Equivalent (CDE) = 37 mrem

Committed Effective Dose Equivalent (CEDE) = 258 mrem

Lens Dose Equivalent (LDE) = 24 mrem

Shallow Dose Equivalent (SDE) = 555 mrem

Effective Dose Equivalent (EDE) = 1331 mrem Initiating Cue:

The WCSFM has directed you to determine the maximum time you can stay in the High Radiation Area above, to complete the 2nd portion of the clearance (once you have completed the first portion of the clearance), and still remain within DCPP administrative annual exposure guideline for Total Effective Dose Equivalent (TEDE, whole body) dose.

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

Task Standard:

Determined maximum stay time to be 0.46 hrs (0.46 - 0.47 hrs, or 27.6 - 28.2 minutes).

NRCL162-A4 R0 PAGE 2 OF 7 REV. 0

JPM TITLE: CALCULATE MAXIMUM STAY TIME JPM NUMBER: NRCL162-A4 INSTRUCTOR W ORKSHEET Start Time:

Step Standards

1. Determines current TEDE. Note: TEDE = EDE + CEDE. Steps preceding step 3.2 may be performed in any order.

1.1 Determined current TEDE by adding the EDE (1331 mrem) to the CEDE (258 mrem) = 1589 mrem.

Step was: Sat: ______ Unsat _______

2. Determines dose required to Note: Dose Rate x Stay Time = Dose complete 1st portion of clearance. used for 1st portion of clearance.

2.1 Multiplied dose rate (280 mrem/hr) time stay time (3/4 hour) =

210 mrem used for 1st portion of clearance.

Step was: Sat: ______ Unsat _______

- 3. Determines nd dose margin allowed Note: All guidelines and limits can be for 2 portion of clearance. found in RP1.ID6.

3.1 Determined administrative guideline is 2000 mrem for the year.

3.2 Determined dose margin for 2nd portion of clearance by subtracting current annual dose (1589 mrem) and dose for 1st portion of clearance (210 mrem) from dose limit (2000 mrem); 2000 - (1589 + 210) =

201 mrem margin (for job). **

Step was: Sat: ______ Unsat _______

- Denotes a Critical Step.

NRCL162-A4 R0 PAGE 3 OF 7 REV. ERROR!

REFERENCE SOURCE NOT FOUND.

JPM TITLE: CALCULATE MAXIMUM STAY TIME JPM NUMBER: NRCL162-A4 INSTRUCTOR W ORKSHEET Step Standards

- 4. Determines nd maximum stay time 4.1 Stay Time = Margin / Dose Rate (for 2 portion of clearance).

4.2 Stay Time = 201 mrem / 430 mrem/hr..

4.3 Stay Time = 0.467 hrs (allowable range is 0.46-0.47 hrs, or 27.6 -

28.2 minutes) **

Step was: Sat: ______ Unsat _______

Stop Time:

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

- Denotes a Critical Step.

NRCL162-A4 R0 PAGE 4 OF 7 REV. ERROR!

REFERENCE SOURCE NOT FOUND.

JPM TITLE: ERROR! REFERENCE SOURCE NOT FOUND. JPM NUMBER: NRCL162-A4 INSTRUCTOR W ORKSHEET EXAMINEE RESPONSE

Determined maximum stay time to be 0.46 hrs (0.46 - 0.47 hrs, or 27.6 - 28.2 minutes).

TEDE = EDE + CEDE 1589 mrem = EDE (1331 mrem) + CEDE (258 mrem)

Dose Rate x Stay Time = Dose (280 mrem/hr) x (3/4 hour) = 210 mrem

(Admin. Guideline = 2000 mrem); 2000 - (1589 + 210) = 201 mrem margin

Stay Time = Margin / Dose Rate Stay Time = 201 mrem / 430 mrem/hr Stay Time = 0.467 hrs (allowable range is 0.46-0.47 hrs, or 27.6 - 28.2 minutes)

- Denotes a Critical Step.

NRCL162-A4 R0 PAGE 5 OF 7 REV. ERROR!

REFERENCE SOURCE NOT FOUND.

EXAMINEE CUE SHEET JPM NUMBER: NRCL162-A4 Initial Conditions: Given:

The Work Control Shift Foreman (WCSFM) and Work Control Lead (WCL) have assigned you to hang an outage clearance in two locations, which are both in a High Radiation Area.

The first portion of the clearance is in an area where the dose rate is 280 mrem/hr, and the work there will take 45 minutes.

The second portion of the clearance is in an area where the dose rate is 430 mrem/hr; it is not known how long this work will take.

Your current year exposure history (per NRC Form 4) is as follows:

Deep Dose Equivalent (DDE) = 969 mrem

Committed Dose Equivalent (CDE) = 37 mrem

Committed Effective Dose Equivalent (CEDE) = 258 mrem

Lens Dose Equivalent (LDE) = 24 mrem

Shallow Dose Equivalent (SDE) = 555 mrem

Effective Dose Equivalent (EDE) = 1331 mrem Initiating Cue:

The WCSFM has directed you to determine the maximum time you can stay in the High Radiation Area above, to complete the 2nd portion of the clearance (once you have completed the first portion of the clearance), and still remain within DCPP administrative annual exposure guideline for Total Effective Dose Equivalent (TEDE, whole body) dose.

ANSWER (Stay Time) =

Work Area (use back of sheet as needed)

NRCL162-A4 R0 PAGE 6 OF 7 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL162-A4 EXAMINEE RESPONSE ANSWER (Stay Time) =

NRCL162-A4 R0 PAGE 7 OF 7 REV. 0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL162-A5

Title:

Review AP-5 Bistable Trip Authorization Form Examinee:

Evaluator:

Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments: Designed for SRO candidates in a classroom setting.

References:

OP AP-5, Malfunction of Eagle 21 Protection or Control Channel, Rev 43

Technical Specifications 3.3.1, 3.3.2, 3.4.12 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 20 minutes Critical Steps: 1.4, 1.7, 1.8 Job Designation: SRO Rev Comments New Gen KA # G2.1.7 (4.7) Ability to evaluate plant performance and make 4.7 operational judgement based on operating characteristics, reactor behavior, and instrument interpretation.

AUTHOR: JARED SMITH DATE: 10/31/17 OPERATIONS REPRESENTATIVE: CHRISTOPHER MEHIGAN DATE: 10/31/17 REV.0

JPM TITLE: REVIEW AP-5 BISTABLE TRIP AUTHORIZATION FORM JPM NUMBER: NRCL162-A5 EVALUATOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator.

The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee. The examiner will then ask if any clarifications are needed. Since this is an administrative JPM, and the simulator is not used, the examinee may be given a copy of the required materials below. The examinee should be given the Initial cue sheet (page 6) along with the handout and procedure.

Required Materials:

OP AP-5, Malfunction of Eagle 21 Protection or Control Channel, Rev.

43 Initial Conditions: GIVEN:

Unit 1 is at 100% power.

STP I-4-P506, Main Turbine First Stage Pressure Channel PT-506 Calibration is in progress. PC-506A is in the required status for the duration of the surveillance test.

The control room received multiple alarms including PK 06-01 PPS Channel Set Failure and PK 06-04 PPS Trouble. OP AP-5, Malfunction of Eagle 21 Protection or Control Channel is in progress due to a LCP halt on Protection Set 2 Rack 8.

All Primary and Secondary control systems are within their normal operating limits and controlling properly. All operator actions have been completed. The WCSFM has completed AP-5, attachment 4.4, Bistable Trip Authorization, for the LCP Halt.

Initiating Cue:

The Shift Manager has directed you to perform a review of AP-5 attachment 4.4 Bistable Trip Authorization form in accordance with step 8 of the procedure.

Document all your findings before reporting out. This should include any necessary corrections, comments, and notifications.

Task Standard: DO NOT READ TASK STANDARD TO EXAMINEE

Determined LC-549A P-14 shall be included on attachment 4.4 with the required Bistable status as TRIPPED.

Determined PC-936B Hi-Hi Contmt Press Phase B Isolation and Contmt Spray / Hi-Hi Contmt Press Steam Line Isolation required status is BYPASS.

Determined PC-936A Contmt Hi Press S.I. required status is Tripped.

No other bistables are incorrectly identified for inclusion.

Note: Examinee may include that TC-433A should be omitted from the bistable trip authorization form. This is not required to meet the task standard.

Start Time:

NRCL162-A5 r0 PAGE 2 OF 7 REV.0

JPM TITLE: REVIEW AP-5 BISTABLE TRIP AUTHORIZATION FORM JPM NUMBER: NRCL162-A5 EVALUATOR WORKSHEET Step Expected Operator Actions Note: Provide exam copy of AP-5 with attachment 4.4 completed.

1. Obtain correct procedure 1.1 Referenced OP AP-5 Malfunction of Eagle 21 Protection or Control Channel.

Note: Examinee may reference AP-5 att.

4.1 for Protection Set 2 Rack 8.

Note: Per initial conditions, PC-506A is in the required status for STP I-4-P506.

Operator identified AP-5, Attachment 1.2 Verified LC-519A P-14 required status 4.4 errors. is Tripped.

1.3 Verified LC-519B S/G Lo Lvl Trip/AFW pump start required status is Tripped.

1.4** Determined LC-549A P-14 required status is Tripped and should be included on attachment 4.4.

1.5 Verified LC-549B S/G Lo Lvl Trip/AFW pump start required status is Tripped.

1.6 Determined TC-433A LTOP should not be included on attachment 4.4.

1.7** Determined PC-936B Hi-Hi Contmt Press Phase B Isolation and Contmt Spray required status is Bypass.

1.8** Determined PC-936A Contmt Hi Press S.I. required status is Tripped.

1.9 Notified Shift Manager of errors.

Note: Student should add missing data, line out and correct mistakes on AP-5 attachment 4.4.

Step was: Sat: ______ Unsat _______

- Denotes Critical Step and Sub Steps.

NRCL162-A5 r0 PAGE 3 OF 7 REV.0

JPM TITLE: REVIEW AP-5 BISTABLE TRIP AUTHORIZATION FORM JPM NUMBER: NRCL162-A5 EVALUATOR WORKSHEET Comments:

Stop Time:

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

- Denotes Critical Step and Sub Steps.

NRCL162-A5 r0 PAGE 4 OF 7 REV.0

JPM TITLE: REVIEW AP-5 BISTABLE TRIP AUTHORIZATION FORM JPM NUMBER: NRCL162-A5 EVALUATOR WORKSHEET Follow-up Question Documentation:

Question: ____________________________________________________________________

Response: ____________________________________________________________________

NRCL162-A5 R0 PAGE 5 OF 7 REV.0

JPM TITLE: REVIEW AP-5 BISTABLE TRIP AUTHORIZATION FORM JPM NUMBER: NRCL162-A5 ANSWER KEY EXAMINEE RESPONSE

Determined LC-549A P-14 shall be included on attachment 4.4 with the required Bistable status as TRIPPED.

Determined TC-433A should be omitted from the bistable trip authorization form.

Determined PC-936B Hi-Hi Contmt Press Phase B Isolation and Contmt Spray / Hi-Hi Contmt Press Steam Line Isolation required status is BYPASS.

Determined PC-936A Contmt Hi Press S.I. required status is Tripped.

No other bistables are incorrectly identified for inclusion.

Note: Examinee may include that TC-433A should be omitted from the bistable trip authorization form. This is not required to meet the task standard.

Print OP AP-5, Malfunction of Eagle 21 Protection or Control Channel, Attachment 4.4. Enter the following data into the indicated locations on the Attachment. 1 Failed Instrument Channel(s) LCP Halt Date/Time: (today) / (now)

Protection Set 2 Rack 8 Bistable or Device to be Defeated or Tripped Location Required Status LC 519A P-14 SET 2 RACK 8 Tripped LC 519B S/G Lo Lvl Trip/AFW SET 2 RACK 8 Tripped Pump Start LC 549B S/G Lo Lvl Trip/AFW SET 2 RACK 8 Tripped Pump Start Tripped Error #1(Not a Critical TC-433A LTOP SET 2 RACK 8 Step)

PC 936B Hi-Hi Contmt Press SET 2 RACK 8 Tripped Bypass Error #2 Phase B Isolation and Contmt Spray/Hi-Hi Contmt Press Steam Line Isolation PC 936A Contmt Hi Press S.I. SET 2 RACK 8 Bypass Tripped Error #3 LC-549A P-14 SET 2 RACK 8 Tripped Error #4 1

NOTE: The following intentional errors have been made: a) LC-549A is missing, TRIPPED b)

PC-936B required status is BYPASS c) PC-936A required status is TRIPPED d) TC-433A should be omitted from the bistable trip form (Not a critical step).

NRCL162-A5 R0 PAGE 6 OF 7 REV.0 0

JPM TITLE: REVIEW AP-5 BISTABLE TRIP AUTHORIZATION FORM JPM NUMBER: NRCL162-A5 EXAMINEE CUE SHEET Initial Conditions: GIVEN:

Unit 1 is at 100% power.

STP I-4-P506, Main Turbine First Stage Pressure Channel PT-506 Calibration is in progress. PC-506A is in the required status for the duration of the surveillance test.

The control room received multiple alarms including PK 06-01 PPS Channel Set Failure and PK 06-04 PPS Trouble. OP AP-5, Malfunction of Eagle 21 Protection or Control Channel is in progress due to a LCP halt on Protection Set 2 Rack 8.

All Primary and Secondary control systems are within their normal operating limits and controlling properly. All operator actions have been completed. The WCSFM has completed AP-5, attachment 4.4, Bistable Trip Authorization, for the LCP Halt.

Initiating Cue:

The Shift Manager has directed you to perform a review of AP-5 attachment 4.4 Bistable Trip Authorization form in accordance with step 8 of the procedure.

Document all your findings before reporting out. This should include any necessary corrections, comments, and notifications.

EXAMINEE RESPONSE NRCL162-A5 R0 PAGE 7 OF 7 REV.0 0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL162-A6

Title:

Review Rod Position Alignment and Rod Insertion Limits Examinee:

Evaluator:

Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments: Designed for SRO candidates in a classroom setting.

References:

STP I-1A Routine Shift Checks Required by Licenses, Rev. 137

COLR 1, U1, COLR for Diablo Canyon Unit 1, Rev. 11

COLR 2, U2, COLR for Diablo Canyon Unit 2, Rev. 10

PPC Data printout Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 3.3, 3.4, 3.6 Job Designation: SRO Rev Comments New Gen KA # G2.1.23 - Ability to perform specific system and integrated 4.4 plant procedures during all modes of plant operation.

AUTHOR: JARED SMITH DATE: 10/31/17 OPERATIONS REPRESENTATIVE: CHRISTOPHER MEHIGAN DATE: 10/31/17 REV.0

JPM TITLE: Verify Rod Position Alignment and Rod Insertion Limits JPM NUMBER: NRCL162-A6 EVALUATOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator.

The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee. The examiner will then ask if any clarifications are needed. Since this is an administrative JPM, and the simulator is not used, the examinee may be given a copy of the required materials below. The examinee should be given the initial cue sheet along with the handout and procedure.

Required Materials:

STP I-1A Routine Shift Checks Required by Licenses, Rev. 137

COLR, U1, COLR for Diablo Canyon Unit 1, Rev. 11

COLR, U2, COLR for Diablo Canyon Unit 2, Rev. 10

PPC Data (Handout)

Initial Conditions: GIVEN:

Unit 1 has been at reduced power for the past 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months due to the Heater 2 Drain Pump being out of service for maintenance.

All Unit 1 individual rod position PPC addresses have a quality code of good (green) on PPC GRPDIS-DRPI.

Initiating Cue:

Unit 1 BOPCO has just completed STP I-1A, Routine Shift Checks Required by Licenses, section 12.10 through 12.12.

As the Shift Foreman, review the completed section of STP I-1A for accuracy. Document all your findings before reporting out to the Shift Manager. This should include any necessary corrections, comments, notifications, and the identification of applicable TS/ECG and associated actions if appropriate.

Task Standard: DO NOT READ TASK STANDARD TO EXAMINEE

Step 12.10, Determined each rod position on DRPI was within 12 steps of its group step counter.

Step 12.11,Checked all shutdown bank step counters were above 225 steps.

Note: Step 12.12.5 is not required to meet the task standard.

Determined step 12.12.5 was applicable and needed to be performed.

Step 12.12.6, Determined COLR insertion limits were NOT met, perform step 12.13 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Determined Tech Spec 3.1.6 is applicable due to control bank insertion limits not met, per SR 3.1.6.2.

NRCL162-A6 r0 PAGE 2 OF 11 REV.0

JPM TITLE: Verify Rod Position Alignment and Rod Insertion Limits JPM NUMBER: NRCL162-A6 EVALUATOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Review step 12.10 Rod Position Note: Observed Note prior to step.

Alignment Examinee referenced handouts for information.

1.1 Reviewed each rod position on DRPI indications and group step counters.

Determined to be within 12 steps of each other. Ensured step 12.10.1 was initialed.

1.2 Ensured step 12.10.1.a was marked N/A.

1.3 Ensured step 12.10.1.b was marked N/A.

1.4 Ensured step 12.10.2 was initialed.

Information given in initial conditions.

Step was: Sat: ______ Unsat _______

Comments:

- Denotes Critical Step and Sub Steps.

NRCL162-A6 r0 PAGE 3 OF 11 REV.0

JPM TITLE: Verify Rod Position Alignment and Rod Insertion Limits JPM NUMBER: NRCL162-A6 EVALUATOR WORKSHEET Step Expected Operator Actions

2. Review step 12.11 Shutdown Bank Note: Examinee referenced handouts COLR Insertion Limits for information.

2.1 Determined all shutdown bank step counters were above 225 steps. Ensured step 12.11.1 was initialed.

2.2 Ensured step 12.11.2 was marked N/A.

2.3 Ensured step 12.11.3 was marked N/A.

Step was: Sat: ______ Unsat _______

Comments:

- Denotes Critical Step and Sub Steps.

NRCL162-A6 r0 PAGE 4 OF 11 REV.0

JPM TITLE: Verify Rod Position Alignment and Rod Insertion Limits JPM NUMBER: NRCL162-A6 EVALUATOR WORKSHEET Step Expected Operator Actions 3.** Review step 12.12 Control Bank Note: Examinee referenced handouts COLR Insertion Limits for information.

3.1 Ensured thermal power level to be 65.4%. (Used PPC point U4300A15).

Ensured step 12.12.1 was initialed.

Note: Examinee referenced Unit1 COLR 3.2 Checked Unit 1 Insertion limit: Control Bank D at 90 steps. Determined that CBD at 90 steps is correct. (Acceptable range is Bank D 89 - 91 steps). Ensured step 12.12.2 was initialed.

3.3** Reviewed demand bank position: Bank D at 96 steps. Determined step 12.12.3 demand bank position CBD at 96 steps is incorrect (DRPI indication was used).

Verified demand bank position should be CBD at 87 steps.

3.4** Determined each control bank is NOT at or above the insertion limit. Determined step 12.12.4 should NOT be initialed.

(Examinee may include/recommend a NOTE on step).

3.5 Determined step 12.12.5 IS applicable and step 12.12.5 should be performed.

All control banks are NOT fully withdrawn due to being at reduced (65.4%) power.

3.6** Determined step 12.12.6 is applicable.

Determined Step 12.13 shall be performed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Examinee determined Tech Spec 3.1.6 is applicable due to control bank COLR insertion limits NOT met, per SR 3.1.6.2.

Step was: Sat: ______ Unsat _______

- Denotes Critical Step and Sub Steps.

NRCL162-A6 r0 PAGE 5 OF 11 REV.0

JPM TITLE: Verify Rod Position Alignment and Rod Insertion Limits JPM NUMBER: NRCL162-A6 EVALUATOR WORKSHEET Comments:

Stop Time:

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

- Denotes Critical Step and Sub Steps.

NRCL162-A6 r0 PAGE 6 OF 11 REV.0

JPM TITLE: Verify Rod Position Alignment and Rod Insertion Limits JPM NUMBER: NRCL162-A6 EVALUATOR WORKSHEET Follow-up Question Documentation:

Question: ____________________________________________________________________

Response: ____________________________________________________________________

NRCL162-A6 R0 PAGE 7 OF 11 REV.0

JPM TITLE: Verify Rod Position Alignment and Rod Insertion Limits JPM NUMBER: NRCL162-A6 ANSWER KEY EXAMINEE RESPONSE

Step 12.10, Determined each rod position on DRPI was within 12 steps of its group step counter.

Step 12.11,Checked all shutdown bank step counters were above 225 steps.

Note: Step 12.12.5 is not required to meet the task standard. Determined step 12.12.5 was applicable and needed to be performed.

Step 12.12.6, Determined COLR insertion limits were NOT met, perform step 12.13 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Determined Tech Spec 3.1.6 is applicable due to control bank insertion limits not met, per SR 3.1.6.2.

NRCL162-A6 R0 PAGE 8 OF 11 REV.0

JPM TITLE: Verify Rod Position Alignment and Rod Insertion Limits JPM NUMBER: NRCL162-A6 ANSWER KEY NRCL162-A6 R0 PAGE 9 OF 11 REV.0

JPM TITLE: Verify Rod Position Alignment and Rod Insertion Limits JPM NUMBER: NRCL162-A6 ANSWER KEY NRCL162-A6 R0 PAGE 10 OF 11 REV.0

JPM TITLE: Verify Rod Position Alignment and Rod Insertion Limits JPM NUMBER: NRCL162-A6 EXAMINEE CUE SHEET Initial Conditions: GIVEN:

Unit 1 has been at reduced power for the past 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months due to the Heater 2 Drain Pump being out of service for maintenance.

All Unit 1 individual rod position PPC addresses have a quality code of good (green) on PPC GRPDIS-DRPI.

Initiating Cue:

Unit 1 BOPCO has just completed STP I-1A, Routine Shift Checks Required by Licenses, section 12.10 through 12.12.

As the Shift Foreman, review the completed section of STP I-1A for accuracy. Document all your findings before reporting out to the Shift Manager. This should include any necessary corrections, comments, notifications, and the identification of applicable TS/ECG and associated actions if appropriate.

EXAMINEE RESPONSE Step 12.10 Result:

Step 12.11 Result:

Step 12.12 Result:

NRCL162-A6 R0 PAGE 11 OF 11 REV.0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL162-A7

Title:

VERIFY AFD IS WITHIN TECH SPEC LIMITS Examinee:

Evaluator:

Print Signature Date Testing Method Perform X Simulate Results: Sat Unsat Total Time: minutes Comments: This JPM requires that STP I-1C, Section 12.2 be filled out ahead of time. The required data is included in an attachment to this JPM.

References:

STP I-1C, Routine Weekly Checks Required By Licenses, Section 12.2, Rev. 116C Volume 9B, Curves and Miscellaneous Data, Figure R23-1F-1, Unit 1 Cycle 21 RAOC Limits, Rev. 331 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 Minutes Critical Steps: 5.3, 7.2, 8.1, 9.3, 9.4 Job Designation: SRO Task Number: G2.2.42 Ability to recognize system parameters that are entry-level conditions for Technical Specifications.

Rating: /4.6 AUTHOR: JARED SMITH DATE: 10/31/17 OPERATIONS REPRESENTATIVE: CHRISTOPHER MEHIGAN DATE: 10/31/17 REV.0

JPM TITLE: VERIFY AFD IS WITHIN TECH SPEC LIMITS JPM NUMBER: NRCL162-A7 INSTRUCTOR W ORKSHEET Directions: The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee. The examiner will then ask if any clarifications are needed. Since this is an administrative JPM, and the simulator is not used, the examinee may be given a copy of the required materials below.

Required Materials:

Completed Copy of STP I-1C, Routine Weekly Checks Required By Licenses, Section 12.2 Axial Flux Difference (AFD), Rev. 116C

Volume 9B, Curves and Miscellaneous Data, Figure R23-1F-1, Unit 1 Cycle 15 RAOC Limits, Rev. 331

Axial Flux Difference data (Handout)

Initial Conditions: Given:

Unit 1 rapidly ramped down power due to tube failures on the No. 3 and No. 4 Feedwater Heaters. Reactor power is currently stable at approximately 87%.

PK03-25, PPC RX ALARM AXIAL FLUX/ROD POSITION input 1251 is illuminated.

Indicated Reactor Power based on U1169A05 is 86.8%.

U4300A15 is not available.

PPC MAX NI power is 100.3% per latest STP R-2B1.

Initiating Cue:

Unit 1 BOPCO has just completed STP I-1C, Routine Weekly Checks Required By Licenses, Section 12.2.

As the Shift Foreman, review the completed STP I-1C data sheet for accuracy and completeness. Document all your findings before reporting out to the Shift Manager. This should include any necessary corrections, comments, notifications, and the identification of applicable TS/ECG and associated actions, if appropriate.

Task Standard: DO NOT READ TASK STANDARD TO EXAMINEE

Step 12.2.3, Determined that -15.0% recorded for Lower AFD Limit is incorrect. The correct Lower AFD Limit is -14.5% (Acceptable range

-14.0% - -14.5%).

Step 12.2.4, Determined that AFD is outside the limits for NIs 42C and 43C and Yes boxes are incorrectly marked. The No boxes should be marked.

Step 12.2.5, Determined that at least 3 excore channels are NOT within AFD limits and the step is incorrectly initialed. Tech Spec 3.2.3. Condition A is applicable. Reduce thermal power to less than 50% RTP within 30 minutes.

NRCL162-A7 R0.DOC PAGE 2 OF 7 REV. 0

JPM TITLE: VERIFY AFD IS WITHIN TECH SPEC LIMITS JPM NUMBER: NRCL162-A7 INSTRUCTOR W ORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 Obtained STP I-1C, Section 12.2.

Note: Provide completed exam copy of STP-I-1C, Section 12.2.

Step was: Sat: _______ Unsat _______*

2. Verify current RTP %. 2.1 Ensured step 12.2.1 is marked N/A.

(U4300A15 is not available, per initial conditions) 2.2 Ensured step 12.2.2.a MAX NI Power is 100.3% and step initialed.

2.3 Calculated U1169A05 value (86.8) / PPC Max (100.3) x 100. Approximately 86.5% RTP (86.4% - 86.6% RTP is acceptable).

Note: Provide calculator (if necessary).

2.4 Verified RTP % to be 86.5%.

Step was: Sat: _______ Unsat _______*

3. Obtain the correct Figure. 3.1 Obtained Figure R23-1F-1 for Unit 1 from Volume 9.

Note: Provide exam copy of Figure R23-1F-1.

Step was: Sat: _______ Unsat _______*

4. Verify Upper AFD Limit. 4.1 Referenced R23-1F-1.

4.2 Step 12.2.3, Determined Upper AFD Limit to be +14.0%.

4.3 Verified +14.0% recorded for Upper AFD Limit.

Step was: Sat: _______ Unsat _______*

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

NRCL162-A7 R0.DOC PAGE 3 OF 7 REV.0

JPM TITLE: VERIFY AFD IS WITHIN TECH SPEC LIMITS JPM NUMBER: NRCL162-A7 INSTRUCTOR W ORKSHEET Step Expected Operator Actions

5. **Verify Lower AFD Limit. 5.1 Referenced R23-1F-1.

5.2 Step 12.2.3, Determined Lower AFD Limit to be approximately -14.5%.

(14.0% -14.5% is acceptable) 5.3 Determined that -15.0% recorded for Lower AFD Limit is incorrect. **

Step was: Sat: _______ Unsat _______*

6. Verify indicated AFD values 6.1 Step 12.2.4, Verified indicated AFD values recorded for each NI.

Step was: Sat: _______ Unsat _______*

7. **Verify AFD is within limits. 7.1 Step 12.2.4 Verified that AFD is within limits for NIs 41C and 44C and Yes boxes marked.

7.2 Determined that AFD is outside the limits for NIs 42C and 43C and Yes boxes are incorrectly marked.**

Step was: Sat: _______ Unsat _______*

8. **Verify that 2 excore channels exceed 8.1 Step 12.2.5, Determined that BOPCO has AFD Limit. incorrectly initialed that no more than one channel is exceeding the AFD limit.

Step was: Sat: _______ Unsat _______*

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

NRCL162-A7 R0.DOC PAGE 4 OF 7 REV.0

JPM TITLE: VERIFY AFD IS WITHIN TECH SPEC LIMITS JPM NUMBER: NRCL162-A7 INSTRUCTOR W ORKSHEET Step Expected Operator Actions

9. **Determine AFD exceeds Tech Spec 9.1 Referred to Tech Spec 3.2.3.

Limits.

9.2 Referred to Unit 1 COLR Figure 2.

Note: Provide exam copy of Unit 1 COLR Figure 2 (if necessary). (Operator may use Figure R23-1F-1 instead of Unit 1 COLR Figure 2 because these figures provide the same information).

9.3 Determined AFD is not within limits.**

9.4 Determined TS 3.2.3 condition A is applicable, reduce thermal power to less than 50% within 30 minutes.**

Step was: Sat: _______ Unsat _______*

Stop Time:

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

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

NRCL162-A7 R0.DOC PAGE 5 OF 7 REV.0

JPM TITLE: VERIFY AFD IS WITHIN TECH SPEC LIMITS JPM NUMBER: NRCL162-A7 EXAMINEE RESPONSE

Step 12.2.3, Determined that -15.0% recorded for Lower AFD Limit is incorrect. The correct Lower AFD Limit is -14.5%(Acceptable range -14.0% - -14.5%).

Step 12.2.4, Determined that AFD is outside the limits for NIs 42C and 43C and Yes boxes are incorrectly marked. The No boxes should be marked.

Step 12.2.5, Determined that at least 3 excore channels are NOT within AFD limits and the step is incorrectly initialed. Tech Spec 3.2.3. Condition A is applicable. Reduce thermal power to less than 50% RTP within 30 minutes.

NRCL162-A7 R0.DOC PAGE 6 OF 7 REV. 0

JPM TITLE: VERIFY AFD IS WITHIN TECH SPEC LIMITS JPM NUMBER: NRCL162-A7 Initial Conditions: Given:

Unit 1 rapidly ramped down power due to tube failures on the No. 3 and No. 4 Feedwater Heaters. Reactor power is currently stable at approximately 87%.

PK03-25, PPC RX ALARM AXIAL FLUX/ROD POSITION input 1251 is illuminated.

Indicated Reactor Power based on U1169A05 is 86.8%.

U4300A15 is not available.

PPC MAX NI power is 100.3% per latest STP R-2B1.

Initiating Cue:

Unit 1 BOPCO has just completed STP I-1C, Routine Weekly Checks Required By Licenses, Section 12.2.

As the Shift Foreman, review the completed STP I-1C data sheet for accuracy and completeness. Document all your findings before reporting out to the Shift Manager. This should include any necessary corrections, comments, notifications, and the identification of applicable TS/ECG and associated actions, if appropriate.

EXAMINEE RESPONSE NRCL162-A7 R0.DOC PAGE 7 OF 7 REV. 0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL162-A8

Title:

Approve Liquid Radwaste Release Permit.

Examinee:

Evaluator:

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

References:

OP G-1:II, Liquid Radwaste System - Discharge of Liquid Radwaste, Rev. 38 CAP A-5, Liquid Radwaste Discharge Management, Rev. 49 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 20 minutes Critical Steps: 1.8, 2.1, 3.3, 4.1 Job Designation: SRO K/A: G 2.3.6; Ability to approve release permits.

Rating: 3.8 AUTHOR: JARED SMITH DATE: 10/31/17 OPERATIONS REPRESENTATIVE: CHRISTOPHER MEHIGAN DATE: 10/31/17 REV.0

JPM TITLE: APPROVE LIQUID RADWASTE RELEASE JPM Number: NRCL162-A8 PERMIT.

INSTRUCTOR 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 examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee. The examiner will then ask if any clarifications are needed. Since this is an administrative JPM, and the simulator is not used, the examinee may be given a copy of the required materials below.

Required Materials:

OP G-1:II, Liquid Radwaste System - Discharge of Liquid Radwaste, Rev. 38 Completed section 12

CAP A-5, Rev. 49 Completed Attachment 11 Parts 1 & 2.

Initial Conditions:

Chemistry has issued a discharge permit for PWR 0-2 using CAP A-5 Att. 11 parts 1 & 2. OP G-1:II section 12 has been completed up to step 12.19

Both Units are operating a full power. CCW heat exchangers 1-1 and 2-1 are currently in service.

Initiating Cue:

As the Unit 1 Shift Foreman, review OP G-1:II section 12, Discharging Process Waste Receiver 0-1 (0-2), and CAP A-5 attachment 11 for accuracy and completeness.

Document any discrepancies noted and determine if the discharge checklist should be approved or not approved.This should include any necessary corrections, comments, notifications, and the identification of applicable TS/ECG and associated actions if appropriate.

Task Standard: DO NOT READ TASK STANDARD TO EXAMINEE

Step 12.9, Determined PWR 0-1 has been aligned for discharge instead of PWR 0-2

Step 12.10, Determined the incorrect CCW HX 1-2 was circled to be used for the release.

Determined RE-18 Calibration expiration date is overdue, making RM-18 INOPERABLE. SFM Reviewed applicable portions of ECG 39.3.

Discharge authorization was not approved.

NRCL162-A8 Page 2 of 6 REV.0

JPM TITLE: APPROVE LIQUID RADWASTE RELEASE JPM NUMBER: NRCL162-A8 PERMIT.

INSTRUCTOR W ORKSHEET Start Time:

Step Expected Operator Actions

- 1. Review OP G-1:II section 12 1.1 Checked Step 12.1 is initialed.

page 1. Reviewed parts 1 and 2 of the discharge permit are complete and signed (CAP A-5 Attachment 11).

1.2 Reviewed CAP A-5 Att. 11 parts 1a through 1k are complete and filled out correctly. Checked steps with initials needed are filled out with valid date/time.

1.3 Reviewed part 2 of the discharge permit complete. No errors identified.

1.4 Checked Step 12.2 is initialed with PWR 0-2 circled.

1.5 Checked steps 12.3 and 12.4 are marked N/A. Identified that RE-18 setpoint does not require adjustment. FIT-243 is OPERABLE.

1.6 Reviewed step 12.5 performed and independently verified with discharge flowpath aligned to Unit 1.

1.7 Checked steps 12.6 through 12.8 were performed and initialed.

1.8 Checked step 12.9 is initialed.

Identified error with PWR 0-1 being lined up for discharge instead of PWR 0-2.**

Step was: Sat: ______ Unsat _______*

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

NRCL162-A8 Page 3 of 7 REV.0

JPM TITLE: APPROVE LIQUID RADWASTE RELEASE JPM NUMBER: NRCL162-A8 PERMIT.

INSTRUCTOR W ORKSHEET Step Expected Operator Actions

- 2. Review Auxiliary Saltwater 2.1 Checked step 12.10 performed and checklist (Manual Valve Lineup) independently verified with initials.

verification. OP G-1:II, page 2 Determined that CCW HX 1-1 is to be of Section 12. circled and to be used, but identified that valve alignment is for CCW HX 1-2.**

Step was: Sat: ______ Unsat _______*

- 3. Review OP G-1:II section 12 3.1 Checked step 12.11 is initialed.

pages 2 -3.

3.2 Checked step 12.12 is initialed.

3.3 Checked step 12.13.1 is initialed.

Identified RE-18 Calibration date has expired.** RE-18 is now INOPERABLE 3.4 Checked step 12.13.2 is initialed and channel checked.

3.5 Checked step 12.13.3 is marked N/A.

RR-102 is OPERABLE.

3.6 Checked step 12.13.4 is initialed, source check performed on RE-18 with count rate transcribed on Part 3 of the discharge permit.

3.7 Identified step 12.14 is marked N/A.

3.8 Using step 12.15 table, compared specified Minimum dilution water flowrate with the current dilution flow.

Determined there is adequate dilution flow.

3.9 Checked step 12.16 is marked N/A.

3.10 Verified step 12.17 and 12.18 are complete and initialed.

Step was: Sat: ______ Unsat _______*

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

NRCL162-A8 Page 4 of 7 REV.0

JPM TITLE: APPROVE LIQUID RADWASTE RELEASE JPM NUMBER: NRCL162-A8 PERMIT.

INSTRUCTOR W ORKSHEET Step Expected Operator Actions

- 4. Determine if Authorization of 4.1 Determined that the Authorization permit should be approved. should not be approved, based on multiple conditions not meeting the procedural requirements. In addition, it was discovered that RM-18 was INOPERABLE due to expired calibration date. Referred to ECG 39.3 Condition A.**

Step was: Sat: ______ Unsat _______*

Stop Time:

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

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

NRCL162-A8 Page 5 of 7 REV.0

JPM TITLE: APPROVE LIQUID RADWASTE RELEASE JPM NUMBER: NRCL162-A8 PERMIT.

EXAMINEE RESPONSE

PWR 0-1 has been aligned for discharge instead of PWR 0-2.

OP G-1:II Section 12 page 2, CCW HX 1-2 is circled to be used for the release.

Determined RE-18 Calibration expiration date is overdue, making RM-18 INOPERABLE. SFM Reviewed applicable portions of ECG 39.3.

Discharge authorization was not approved.

[ ] APPROVE Discharge [ X ] DO NOT Approve Discharge

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

NRCL162-A8 Page 6 of 7 REV.0

JPM TITLE: APPROVE LIQUID RADWASTE RELEASE JPM NUMBER: NRCL162-A8 PERMIT.

Initial Conditions:

Chemistry has issued a discharge permit for PWR 0-2 using CAP A-5 Att. 11 parts 1 & 2. OP G-1:II section 12 has been completed up to step 12.19

Both Units are operating a full power. CCW heat exchangers 1-1 and 2-1 are currently in service.

Initiating Cue:

As the Unit 1 Shift Foreman, review OP G-1:II section 12, Discharging Process Waste Receiver 0-1 (0-2), and CAP A-5 attachment 11 for accuracy and completeness.

Document any discrepancies noted and determine if the discharge checklist should be approved or not approved.This should include any necessary corrections, comments, notifications, and the identification of applicable TS/ECG and associated actions if appropriate.

[ ] APPROVE Discharge [ ] DO NOT Approve Discharge

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

NRCL162-A8 Page 7 of 7 REV.0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL162-A9

Title:

Perform an Emergency Classification Examinee:

Evaluator:

Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments: Designed for SRO candidates in a classroom setting. (Note: Any Unsat step requires a numbered comment; use back as needed.)

References:

EP G-1, Accident Classification and Emergency Plan Activation, Rev.44 Forms 69-21608, 69-21609, 69-21610 (06/19/12, 7/24/13, 12/5/11)

Alternate Path: Yes No X Time Critical: Yes X No Time Allotment: 15 minutes Critical Steps: 2.1,3.1 Job Designation: SRO Rev Comments New Gen KA # GEN.2.4.41 - Knowledge of the emergency action level 4.6 thresholds and classifications.

AUTHOR: JARED SMITH DATE: 10/31/17 OPERATIONS REPRESENTATIVE: CHRISTOPHER MEHIGAN DATE: 10/31/17 REV.0

JPM TITLE: CLASSIFICATION OF A LOSS OF REACTOR VESSEL INVENTORY JPM NUMBER: NRCL162-A9 AFFECTING CORE DECAY HEAT REMOVAL CAPABILITY WITH IRRADIATED FUEL IN THE REACTOR VESSEL 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 examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee. The examiner will then ask if any clarifications are needed. Since this is an administrative JPM, and the simulator is not used, the examinee may be given a copy of the required materials below.

Required Materials:

EP G-1, and EAL Wall Charts.

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

Initial Conditions: GIVEN:

Unit 1 is in MODE 6 and core offload is in progress.

Unit 2 is at 100% power. Diesel Generator 2-2 is out of service for maintenance.

A seismic event has just been felt by the Control Room operations staff, and PK15-24 Seismic Instr System alarm has just annunciated.

The highest Earthquake Force Monitor indicator registered 0.160 g on all axis. Both 230kV and 500kV offsite power sources are affected and are unavailable to DCPP. GCC reports that 230kV power is expected to be available within thirty-five minutes. All available diesel generators started as required.

All Unit 1 RVRLIS indications are indicating erroneous values. Unit 1 control room operators observe NI-31 and NI-32 source range detectors oscillating full scale with abnormal count rate fluctuations. Containment closure is established. Refueling SRO reports reactor cavity level is lowering.

Initiating Cue:

The Shift Manager has directed you to classify the event.

Task Standard: DO NOT READ TASK STANDARD TO EXAMINEE

Reported to the Shift Manager, in less than 15 minutes, that Unit 1 Site Area Emergency, CS2.4, is the appropriate emergency plan classification.

Basis: Unit 1, Mode 6, with Containment Closure Established:

Reactor Vessel level cannot be monitored with indication of core uncovery as evidenced by erratic source range monitor indication.

NRCL162-A9 r0 PAGE 2 OF 7 REV. 0

JPM TITLE: CLASSIFICATION OF A LOSS OF REACTOR VESSEL INVENTORY JPM NUMBER: NRCL162-A9 AFFECTING CORE DECAY HEAT REMOVAL CAPABILITY WITH IRRADIATED FUEL IN THE REACTOR VESSEL EVALUATOR WORKSHEET Start Time:

Step Expected Operator Actions

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

Step was: Sat: ______ Unsat _______

2.** Accurately classify the event. 2.1** Classified the event as Unit 1 Site Area Emergency CS2.4.

Classification made: _______________

Step was: Sat: ______ Unsat _______

3.** Classify the event in a timely manner. 3.1** Classified the event < 15 min. of the Event Initiation Time. **

Classification Time: _____________

Event Initiation Time: _____________

(Event initiation time is JPM Start Time)

Difference: ____________ min**

Step was: Sat: ______ Unsat _______

Comments:

Stop Time:

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

- Denotes Critical Step and Sub Steps.

NRCL162-A9 r0 PAGE 3 OF 7 REV.0 0

JPM TITLE: CLASSIFICATION OF A LOSS OF REACTOR VESSEL INVENTORY JPM NUMBER: NRCL162-A9 AFFECTING CORE DECAY HEAT REMOVAL CAPABILITY WITH IRRADIATED FUEL IN THE REACTOR VESSEL EVALUATOR WORKSHEET NRCL162-A9 R0 PAGE 4 OF 7 REV.0

JPM TITLE: CLASSIFICATION OF A LOSS OF REACTOR VESSEL INVENTORY JPM NUMBER: NRCL162-A9 AFFECTING CORE DECAY HEAT REMOVAL CAPABILITY WITH IRRADIATED FUEL IN THE REACTOR VESSEL EVALUATOR WORKSHEET Follow-up Question Documentation:

Question: ____________________________________________________________________

Response: ____________________________________________________________________

NRCL162-A9 R0 PAGE 5 OF 7 REV.0

JPM TITLE: CLASSIFICATION OF A LOSS OF REACTOR VESSEL JPM NUMBER: NRCL162-A9 INVENTORY AFFECTING CORE DECAY HEAT REMOVAL CAPABILITY WITH IRRADIATED FUEL IN THE REACTOR VESSEL ANSWER KEY EXAMINEE RESPONSE Correct Classification: Unit 1 Site Area Emergency, CS2.4

Basis: Unit 1, Mode 6, with Containment Closure Established: Reactor Vessel level cannot be monitored with indication of core uncovery as evidenced by erratic source range monitor indication.

Lower Level Classifications:

UNUSUAL EVENT SU1.1 on Unit 2 for a loss of ALL offsite AC power to Unit 2 Vital 4kV buses F, G, and H for greater than 15 minutes.

ALERT HA1.1 for both units due to Operating Basis Earthquake (EFM Alert alarm indicating >

0.133 g on the Z axis) exceeded.

NRCL162-A9 R0 PAGE 6 OF 7 REV.0

JPM TITLE: CLASSIFICATION OF A LOSS OF REACTOR VESSEL JPM NUMBER: NRCL162-A9 INVENTORY AFFECTING CORE DECAY HEAT REMOVAL CAPABILITY WITH IRRADIATED FUEL IN THE REACTOR VESSEL EXAMINEE CUE SHEET Initial Conditions: GIVEN:

Unit 1 is in MODE 6 and core offload is in progress.

Unit 2 is at 100% power. Diesel Generator 2-2 is out of service for maintenance.

A seismic event has just been felt by the Control Room operations staff, and PK15-24 Seismic Instr System alarm has just annunciated.

The highest Earthquake Force Monitor indicator registered 0.160 g on all axis. Both 230kV and 500kV offsite power sources are affected and are unavailable to DCPP. GCC reports that 230kV power is expected to be available within thirty-five minutes. All available diesel generators started as required.

All Unit 1 RVRLIS indications are indicating erroneous values. Unit 1 control room operators observe NI-31 and NI-32 source range detectors oscillating full scale with abnormal count rate fluctuations. Containment closure is established. Refueling SRO reports reactor cavity level is lowering.

Initiating Cue:

The Shift Manager has directed you to classify the event.

EXAMINEE RESPONSE NRCL162-A9 R0 PAGE 7 OF 7 REV.0

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Diablo Canyon Date of Examination: 01/19/2018 Exam Level: RO SRO-I SRO-U Operating Test Number: L162 Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code* Safety Function

a. (S1) (004.A2.14) Establish Emergency Boration (Bank LJC-063) A,D,S 1

b. (S2) (013.A4.01) Respond to CVI Actuation (Modified from A,EN,M,S 2 NRCL081LJC-S5)

c. (S3) (006.A1.13) Respond to High Accumulator Pressure (Bank LJC-009) D,S 3 (RO Only)

d. (S4) (E03.EA1.1) Start Reactor Coolant Pumps (Bank LJC-044) D,E,L,S 4P

e. (S5) (022.A4.01) Respond to CFCU High Vibration A,N,S 5

f. (S6) (064.A4.01) Transfer Vital 4kV Bus from D/G to Startup (Modified E,L,M,S 6 from Bank LJC-087)

g. (S7) (045.A4.01) Perform Load Trim to Match Tave to Tref N,S 4S

h. (S8) (060.AA1.02) Respond to Gaseous Rad Release A,N,S 9 In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i. (P1) (004.A2.06) Isolate Dilution Flow Paths (LJP-062) D,E,L 1

j. (P2) (064.A3.06) Perform a Local Start of a Diesel Generator (LJP-038) A,D,E,L 6

k. (P3) (067.AA1.08) Manually Operate the Cardox System (LJP-138A) A,D 8

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

Type Codes Criteria for R /SRO-I/SRO-U (A)lternate path 4-6/4-6 /2-3 (C)ontrol room (D)irect from bank 9/ 8/ 4 (E)mergency or abnormal in-plant 1/ 1/ 1 (EN)gineered safety feature 1/ 1/ 1 (control room system)

(L)ow-Power/Shutdown 1/ 1/ 1 (N)ew or (M)odified from bank including 1(A) 2/ 2/ 1 (P)revious 2 exams 3/ 3/ 2 (randomly selected)

(R)CA 1/ 1/ 1 (S)imulator Rev 0

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Diablo Canyon Date of Examination: 01/19/2018 Exam Level: RO SRO-I SRO-U Operating Test Number: L162 Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code* Safety Function

a. (S1) (004.A2.14) Establish Emergency Boration (Bank LJC-063) A,D,S 1

b. (S2) (013.A4.01) Respond to CVI Actuation (Modified from A,EN,M,S 2 NRCL081LJC-S5) c.

d. (S4) (E03.EA1.1) Start Reactor Coolant Pumps (Bank LJC-044) D,E,L,S 4P

e. (S5) (022.A4.01) Respond to CFCU High Vibration A,N,S 5

f. (S6) (064.A4.01) Transfer Vital 4kV Bus from D/G to Startup (Modified E,L,M,S 6 from Bank LJC-087)

g. (S7) (045.A4.01) Perform Load Trim to Match Tave to Tref N,S 4S

h. (S8) (060.AA1.02) Respond to Gaseous Rad Release A,N,S 9 In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i. (P1) (004.A2.06) Isolate Dilution Flow Paths (LJP-062) D,E,L 1

j. (P2) (064.A3.06) Perform a Local Start of a Diesel Generator (LJP-038) A,D,E,L 6

k. (P3) (067.AA1.08) Manually Operate the Cardox System (LJP-138A) A,D 8

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

Type Codes Criteria for R /SRO-I/SRO-U (A)lternate path 4-6/4-6 /2-3 (C)ontrol room (D)irect from bank 9/ 8/ 4 (E)mergency or abnormal in-plant 1/ 1/ 1 (EN)gineered safety feature 1/ 1/ 1 (control room system)

(L)ow-Power/Shutdown 1/ 1/ 1 (N)ew or (M)odified from bank including 1(A) 2/ 2/ 1 (P)revious 2 exams 3/ 3/ 2 (randomly selected)

(R)CA 1/ 1/ 1 (S)imulator Rev 0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL162-LJCS1

Title:

Establish Emergency Boration Examinee: ____________________________________________

Evaluator: ______________________________ ________________________________ __________________

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

References:

OP AP-6, Emergency Boration, Rev. 20 Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 4.1, 4.2, 4.3 Job Designation: RO or SRO Rev Comments/LRN TIPS: Bank LJC-063 004.A2.14 - Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Emergency Gen KA # / Rating: Boration. 3.8 / 3.9 AUTHOR: LISA TORIBIO DATE: 10/24/17 OPERATIONS REPRESENTATIVE: CHRISTOPHER MEHIGAN DATE: 10/24/17 REV. 0

JPM TITLE: Establish Emergency Boration JPM NUMBER: NRCL162-LJCS1 INSTRUCTOR WORKSHEET Directions: All actions taken by 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 steps 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.

Initial Conditions: Unit 1 is shutdown in Mode 3 when an unexplained positive reactivity addition causes source range counts to rise.

Initiating Cue: The Shift Foreman directs you to emergency borate in accordance with OP AP-6, Emergency Boration.

NOTE: Do NOT provide examinee with Task Standard Task Standard: Emergency boration has been established from the RWST per OP AP-6 by performing the following:

Opening 8805A and/or 8805B

Closing LCV-112B and/or LCV-112C

Adjusting charging flow to >90 gpm

- Denotes Critical Step and Sub-Steps Page 2 of 8 Rev. 0

JPM TITLE: Establish Emergency Boration JPM NUMBER: NRCL162-LJCS1 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. OP AP-6, Step 1.a - 1.g - Initiate emergency 1.1 Ensured charging in service.

boration using make-up controls.

1.2 Placed VCT makeup control in the BORATE mode.

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

1.3 Determined amount of boric acid required per Appendix A.

1.4 Set TARGET BATCH.

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

1.5 Reset the BATCHED GALLONS indicator to ZERO.

1.6 Set BORIC ACID FLOW SP > 30 gpm.

1.7 Pressed START and checked for 30 gpm boric acid flow.

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 3 of 8 Rev. 0

JPM TITLE: Establish Emergency Boration JPM NUMBER: NRCL162-LJCS1 INSTRUCTOR WORKSHEET

<< Alternate Path - Start Point >>

2. OP AP-6, Step 1.g, RNO - Initiate emergency 2.1 Determined 30 gpm boric acid flow NOT boration using make-up controls. achieved.

Note: Operator may attempt to open FCV-110B manually, and may not complete all normal method emergency boration once FCV-110B is found failed closed.

2.2 Diagnosed that FCV-110B is failed closed.

2.3 Verified boric acid transfer pump is selected to high speed.

2.4 Closed HCV-104 (BATP 1-1) or HCV-105 (BATP 1-2), as applicable.

2.5 Verified that VCT pressure is less than 30 psig.

2.6 Determined that emergency boration flow of at least 30 gpm is NOT attainable.

Step was: Sat __________ Unsat __________

Comments:

3. OP AP-6, Step 2 - Initiate alternate boration 3.1 Read NOTE prior to Step 2.

method using CVCS-8104.

3.2 Attempted to open 8104.

3.3 Diagnosed that 8104 will NOT open.

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

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 4 of 8 Rev. 0

JPM TITLE: Establish Emergency Boration JPM NUMBER: NRCL162-LJCS1 INSTRUCTOR WORKSHEET Step Expected Operator Actions Note: Only 8805A OR 8805B need be open to satisfy critical step.

- 4. OP AP-6, Step 2, RNO - Initiate alternate ** 4.1 Opened 8805A and 8805B.

boration method using the RWST.

Note: Closing either LCV-112B OR LCV-112C satisfies critical step.

- 4.2 Closed LCV-112B and LCV-112C.

- 4.3 Adjusted charging flow to greater than 90 gpm.

<< Alternate Path - End Point >>

Cue: Another Operator will complete AP-6" Step was: Sat __________ Unsat __________

Comments:

Stop Time:

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

- Denotes Critical Step and Sub-Steps Page 5 of 8 Rev. 0

JPM TITLE: Establish Emergency Boration JPM NUMBER: NRCL162-LJCS1 INSTRUCTOR WORKSHEET Follow up Question Documentation:

Question: _____________________________________________________________________________________

Response: _____________________________________________________________________________________

- Denotes Critical Step and Sub-Steps Page 6 of 8 Rev. 0

JPM TITLE: Establish Emergency Boration JPM NUMBER: NRCL162-LJCS1 ATTACHMENT 1, SIMULATOR SETUP Restore the simulator to IC-14 (HSB, 550°F, MOL).

Trip the reactor.

Reset all shutdown bank step counters to zero.

Perform a rod bank update on the PPC.

Verify NR-45 is displaying source ranges.

Enter Lesson Drill file 1063 Description Increase VCT level Ensures VCT pressure < 30 psig Causes source range NIs to increase by four decades over 10 minutes.

FCV-110B fails closed.

8104 fails closed.

Runs for 10 sec.

Acknowledges alarms If desired, create temporary JPM setup IC.

Inform the examiner that the simulator setup is complete.

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

Page 7 of 8 Rev. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL162-LJCS1 Initial Conditions: Unit 1 is shutdown in Mode 3 when an unexplained positive reactivity addition causes source range counts to rise.

Initiating Cue: The Shift Foreman directs you to emergency borate in accordance with OP AP-6, Emergency Boration.

Page 8 of 8 Rev. 0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL162-LJCS2

Title:

Respond to CVI Activation Examinee: ____________________________________________

Evaluator: ______________________________ ________________________________ __________________

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

OP H-4:I, Containment Ventilation - Make Available and Place in Service, Rev. 38

References:

AR PK02-06, Containment Vent Isolation, Rev. 16 Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 4.2, 4.3, 4.4 Job Designation: RO or SRO Rev Comments Modified from NRCL081LJC-S5 013.A4.01- Ability to manually operate and/or monitor in the Gen KA # / Rating: control room: ESFAS-initiated equipment which fails to actuate 4.5 / 4.8 AUTHOR: LISA TORIBIO DATE: 08/27/17 OPERATIONS REPRESENTATIVE: CHRISTOPHER MEHIGAN DATE: 10/25/17 REV.0

JPM TITLE: Respond to CVI Activation JPM NUMBER: NRCL162-LJCS2 INSTRUCTOR WORKSHEET Directions: All actions taken by 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 steps with which to begin.

Required Materials: (Required materials here)

Initial Conditions: Given:

Unit 1 is at 75% power preparing for a refueling outage.

Operations Manager permission is given to begin purging containment

Shift Foreman will address required Tech Spec actions for the containment purge Initiating Cue: The Shift Foreman directs you to place Containment Purge in service by performing OP H-4:I starting at step 9.12. Fan S-3 will be used NOTE: Do NOT provide examinee with Task Standard Task Standard: All Purge Supply and Exhaust Valves are Closed:

RCV-11, Containment Purge Exhaust Valve

FCV-660, Containment Purge Supply Valve

FCV-678, Supply to Gas and Air Particulate Monitors RE-11 & RE-12

- Denotes Critical Step and Sub-Steps Page 2 of 7 Rev.0

JPM TITLE: Respond to CVI Activation JPM NUMBER: NRCL162-LJCS2 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. OP H-4:I, Steps 9.12.1-9.12.3 - Opens 1.1 Opened FCV-660 on VB4.

Containment Purge Supply Valves.

1.2 Opened FCV-661 on VB4.

1.3 Determined S-3 will be used and N/As step 9.12.2.

1.4 Note: Determined Chemistry notification not required in current mode (step 9.12.3)

Step was: Sat __________ Unsat __________

Comments:

2. OP H-4:I, Step 9.12.4,5 - Opens Containment 2.1 Opened RCV-11 on VB4.

Purge Exhaust valves.

2.2 Opened RCV-12 on VB4.

Step was: Sat __________ Unsat __________

Comments:

2.3 Note: RM-44 high rad in Containment begins when Fan E-3 switch taken to ON.

3. OP H-4:I, Step 9.12.6,7 - Starts Containment 3.1 Started Fan E-3 on VB4.

Purge Fans.

3.2 Started Fan S-3 on VB4.

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 3 of 7 Rev.0

JPM TITLE: Respond to CVI Activation JPM NUMBER: NRCL162-LJCS2 INSTRUCTOR WORKSHEET Step Expected Operator Actions

<< Alternate Path - Start Point >>

- 4. AR PK02-06, CONTMT VENT ISOLATION. 4.1 Verified CVI automatic actions have taken place by checking Monitor Light Box B.

- 4.2 Closed FCV-660

- 4.3 Closed FCV-678

- 4.4 Closed RCV-11 4.5 Stopped Fan E-3 4.6 Stopped Fan S-3

<< Alternate Path - End Point >>

Cue: "Another Operator will continue in the procedure."

Step was: Sat __________ Unsat __________

Comments:

Stop Time:

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

- Denotes Critical Step and Sub-Steps Page 4 of 7 Rev.0

JPM TITLE: Respond to CVI Activation JPM NUMBER: NRCL162-LJCS2 INSTRUCTOR WORKSHEET Follow up Question Documentation:

Question: _____________________________________________________________________________________

Response: _____________________________________________________________________________________

- Denotes Critical Step and Sub-Steps Page 5 of 7 Rev.0

JPM TITLE: Respond to CVI Activation JPM NUMBER: NRCL162-LJCS2 ATTACHMENT 1, SIMULATOR SETUP Initialize the simulator to IC-11 (75%, MOL)

Run Lesson NRC162-LJCS2.

Check BELLS ON Inform the examiner that the simulator setup is complete.

If Simulator is in FREEZE, go to RUN when the examinee is given the cue sheet.

Page 6 of 7 Rev.0

EXAMINEE CUE SHEET JPM NUMBER: NRCL162-LJCS2 Initial Conditions: Given:

Unit 1 is at 75% power preparing for a refueling outage.

Operations Manager permission is given to begin purging containment

Shift Foreman will address required Tech Spec actions for the containment purge Initiating Cue: The Shift Foreman directs you to place Containment Purge in service by performing OP H-4:I starting at step 9.12. Fan S-3 will be used Page 7 of 7 Rev.0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL162-LJCS3

Title:

Respond to High Accumulator Pressure Examinee: ____________________________________________

Evaluator: ______________________________ ________________________________ __________________

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

AR PK02-05, Accum Pressure HI-LO, Rev. 18A

References:

OP B-3B:I, Accumulator Fill and Pressurize, Rev. 28A Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 20 minutes Critical Steps: 5.1, 5.3, 5.5, 5.6, 5.7, 5.8 Job Designation: RO / SRO Rev Comments Bank LJC-009 006.A1.13 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: accumulator pressure (level, boron Gen KA # / Rating: concentration) 4.0 / 4.0 AUTHOR: LISA TORIBIO DATE: 10/24/17 OPERATIONS REPRESENTATIVE: CHRISTOPHER MEHIGAN DATE: 10/24/17 LINE MANAGER REV. 0

JPM TITLE: Respond to High Accumulator Pressure JPM NUMBER: NRCL162-LJCS3 INSTRUCTOR WORKSHEET Directions: All actions taken by 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 steps with which to begin.

Required Materials: None Initial Conditions: Unit is at 100% power. PK02-05 is in alarm Initiating Cue: The Shift Foreman directs you to respond to the alarm and take necessary action to return accumulator parameters to normal in accordance with AR PK02-05 and applicable procedure(s) as required NOTE: Do NOT provide examinee with Task Standard Task Standard: PK02-05 Alarm is cleared for Accum 1-1 Press Hi by performing the following:

1) Closing SI-1-8880, Nitrogen Fill Header Isolation Valve

2) Opening SI-1-8875A, Accum Vent & N2 Fill Valve

3) Opening HCV-943, Accumulator N2 Vent Control Valve

4) Reducing Accumulator 1-1 pressure until PK02-05 is CLEARED

5) Closing HCV-943, Accumulator N2 Vent Control, AND SI-1-8875A, Accum Vent & N2 Fill Valves

6) Opening SI-1-8880, Nitrogen Fill Header Isolation Valve in accordance with AR PK02-05, Accum Pressure HI-LO and OP B-3B:I, Accumulator Fill and Pressurize.

- Denotes Critical Step and Sub-Steps Page 2 of 8 Rev. 0

JPM TITLE: Respond to High Accumulator Pressure JPM NUMBER: NRCL162-LJCS3 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Referenced correct procedure 1.1 Entered AR PK02-05, Accum Pressure HI-LO Step was: Sat __________ Unsat __________

Comments:

2. AR PK02-05, Step 2.1.1, Check both pressure 2.1 Checked PI-960 and PI-961 to verify alarm is not indicators to confirm the alarm and the high or due to instrument failure low pressure condition Note: When Tech Spec referred to, provide the following cue:

Cue: The Shift Foreman is addressing all Technical Specification requirements at this time."

2.2 Determined Annunciator PK02-10, ACCUM LEVEL HI-LO was NOT in 2.3 Determined the alarm condition is accumulator 11 high pressure and transitions to Section 2.2 for High Accumulator Pressure Step was: Sat __________ Unsat __________

Comments:

3. AR PK02-05, Step 2.2.1, Check if high pressure 3.1 Determined level is normal and pressure is high is due to a level increase from previous step Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 3 of 8 Rev. 0

JPM TITLE: Respond to High Accumulator Pressure JPM NUMBER: NRCL162-LJCS3 INSTRUCTOR WORKSHEET Step Expected Operator Actions

4. AR PK02-05, Step 2.2.2, Transition to OP B-3B:I, 4.1 Referenced OP B-3B:I, step 6.4 (after reviewing Accumulators - Fill and Pressurize applicable P&Ls)

Step was: Sat __________ Unsat __________

Comments:

- 5. OP B-3B:I, Accumulators - Fill and Pressurize, ** 5.1 Closed SI-1-8880, Nitrogen Fill Header Isolation step 6.4, Venting an Accumulator Valve.

5.2 Reviewed CAUTION prior to opening Accum vent valve

- 5.3 Positioned valve control switch for SI-1-8875A to OPEN 5.4 Reviews CAUTION prior to opening Accum N2 vent control valve

- 5.5 Manipulated potentiometer to OPEN valve HCV-943 until accumulator pressure decreased to approximately 625 psig and PK02-05 CLEARED Note: HCV-943 may be fully closed prior to closing SI-1-8875A.

- 5.6 Positioned valve control switch for SI-1-8875A to CLOSE

- 5.7 Manipulate the potentiometer to CLOSE valve HCV-943

- 5.8 Opened SI-1-8880, Nitrogen Fill Header Isolation Valve.

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 4 of 8 Rev. 0

JPM TITLE: Respond to High Accumulator Pressure JPM NUMBER: NRCL162-LJCS3 INSTRUCTOR WORKSHEET Step Expected Operator Actions

6. Monitor accumulator pressure 6.1 Ensured that PK02-05 is no longer in alarm 6.2 Continued to monitor accumulator pressure Note: Once operator transitions back to AR PK02-05 provide the following CUE:

Cue: Pressure has remained constant for 20 minutes" Note: If cause investigation desired, provide the following CUE:

Cue: SFM/crew have found and corrected the cause of problem" Step was: Sat __________ Unsat __________

Comments:

Stop Time:

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

- Denotes Critical Step and Sub-Steps Page 5 of 8 Rev. 0

JPM TITLE: Respond to High Accumulator Pressure JPM NUMBER: NRCL162-LJCS3 INSTRUCTOR WORKSHEET Follow up Question Documentation:

Question: _____________________________________________________________________________________

Response: _____________________________________________________________________________________

- Denotes Critical Step and Sub-Steps Page 6 of 8 Rev. 0

JPM TITLE: Respond to High Accumulator Pressure JPM NUMBER: NRCL162-LJCS3 ATTACHMENT 1, SIMULATOR SETUP Restore the simulator to IC-10 (100% MOL)

Run Lesson drl_1009 and run for 10 seconds or manually insert the following:

Command Description Use the chart function for accumulator Monitor accumulator 1-1 pressure pressure psisacc(1) insert psisacc(1) 665 Increases accumulator 11 pressure to 650 psig RUN, then FRZ after 10 seconds Run for 10 seconds Inform the examiner that the simulator setup is complete.

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

Page 7 of 8 Rev. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL162-LJCS3 Initial Conditions: Unit is at 100% power. PK02-05 is in alarm Initiating Cue: The Shift Foreman directs you to respond to the alarm and take necessary action to return accumulator parameters to normal in accordance with AR PK02-05 and applicable procedure(s) as required Page 8 of 8 Rev. 0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL162-LJCS4

Title:

Start Reactor Coolant Pump Examinee: ____________________________________________

Evaluator: ______________________________ ________________________________ __________________

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

References:

EOP E-1.2, Post LOCA Cooldown and Depressurization, App B, Rev. 23 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 2.1, 9.1 Job Designation: RO / SRO Rev Comments/LRN TIPS: Bank LJC-044 E03.EA1.1 - Ability to operate and/or monitor the following as they apply to the LOCA Cooldown and Depressurization: components, and functions of control and safety systems including instrumentation, signals, interlocks, failure modes, and automatic Gen KA # / Rating: and manual features. 4.0 / 4.0 AUTHOR: LISA TORIBIO DATE: 10/24/17 OPERATIONS REPRESENTATIVE: CHRISTOPHER MEHIGAN DATE: 10/24/17 REV. 0

JPM TITLE: Start Reactor Coolant Pump JPM NUMBER: NRCL162-LJCS4 INSTRUCTOR WORKSHEET Directions: All actions taken by 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 steps 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.

Initial Conditions: Given:

A small break loss of coolant accident has occurred. All reactor coolant pumps (RCPs) were previously secured in EOP E-0 when RCS pressure lowered to less than 1300 psig. The operators have just reached Step 14.d of EOP E-1.2 Initiating Cue: The Shift Foreman directs you to start RCP 1-2 in accordance with Appendix B of EOP E-1.2.

NOTE: Do NOT provide examinee with Task Standard Task Standard:

RCP 1-2 lift oil pump was started and allowed to run prior to starting RCP 1-2

RCP 1-2 is running

- Denotes Critical Step and Sub-Steps Page 2 of 9 Rev. 0

JPM TITLE: Start Reactor Coolant Pump JPM NUMBER: NRCL162-LJCS4 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 Referenced EOP E-1.2, Appendix B.

1.2 Read NOTE and CAUTION.

Cue: RCP seal cooling has been maintained.

Step was: Sat __________ Unsat __________

Comments:

- 2. EOP E-1.2, Appendix B, Step 1 - Start oil lift ** 2.1 Started the RCP 1-2 oil lift pump.

pump and run for 2 minutes.

2.2 Verified that the RCP 1-2 oil lift pump has started.

2.3 Waited for two minutes prior to starting the RCP.

Note: Step 2.3 is not critical since timer will not allow start of RCP until after two minutes.

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 3 of 9 Rev. 0

JPM TITLE: Start Reactor Coolant Pump JPM NUMBER: NRCL162-LJCS4 INSTRUCTOR WORKSHEET Step Expected Operator Actions

3. EOP E-1.2, Appendix B, Step 2 - Reset SI, Phase 3.1 Determined that SI is reset (by observing A or Phase B as necessary to provide RCP PK08-22 is ON and/or SI Monitor Box SI red support systems. status light OFF) or Depressed the SI RESET pushbuttons.

3.2 Determined that Containment Isolation Phase A and Phase B are reset (by observing PK02-01 OFF and/or Phase A and Phase B red monitor lights OFF) or Depressed the Phase A and Phase B RESET pushbuttons.

Step was: Sat __________ Unsat __________

Comments:

4. EOP E-1.2, Appendix B, Step 3 - Ensure CCW 4.1 Observed that the following CCW valves are valves open to RCP thermal barrier and oil OPEN (VB1/Phase B status lights):

coolers.

FCV-355

FCV-356

FCV-749

FCV-363

FCV-750

FCV-357 Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 4 of 9 Rev. 0

JPM TITLE: Start Reactor Coolant Pump JPM NUMBER: NRCL162-LJCS4 INSTRUCTOR WORKSHEET Step Expected Operator Actions

5. EOP E-1.2, Appendix B, Step 4 - Ensure seal DP 5.1 Observed that RCP 1-2 seal DP is greater than GREATER THAN 255 PSID 255 psid (PI-187A/PPC).

Step was: Sat __________ Unsat __________

Comments:

6. EOP E-1.2, Appendix B, Step 5 - Ensure Seal 6.1 Verified seal injection flow (FI-143) between 8 Injection flow between 8 GPM to 13 GPM. and 13 GPM.

Step was: Sat __________ Unsat __________

Comments:

7. EOP E-1.2, Appendix B, Step 6 - Ensure Seal 7.1 Determined that RCP 1-2 SEAL NO 1 RTN FLOW Leak Off flow WITHIN limits shown on (FR 159/PPC) is within limits on Appendix B Appendix B graph. graph.

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 5 of 9 Rev. 0

JPM TITLE: Start Reactor Coolant Pump JPM NUMBER: NRCL162-LJCS4 INSTRUCTOR WORKSHEET Step Expected Operator Actions

8. EOP E-1.2, Appendix B, Step 7 - Ensure closed 8.1 Observed that the PCV-455A CLOSED and PCV-PCV-455A and B, Normal PZR Spray Vlvs, AUTO 455B CLOSED green lights are ON, with optional. controllers in AUTO. (The operator may shift the controllers to MANUAL.)

Step was: Sat __________ Unsat __________

Comments:

- 9. EOP E-1.2, Appendix B, Step 8 - Start RCP 1-2. ** 9.1 Started RCP 1-2.

9.2 Verified RCP 1-2 has started.

9.3 Verified normal operation of RCP 1-2 by observing RCP 1-2 motor amps and loop 2 flow (FI-424, FI-425, FI-426, PPC).

Step was: Sat __________ Unsat __________

Comments:

Stop Time:

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

- Denotes Critical Step and Sub-Steps Page 6 of 9 Rev. 0

JPM TITLE: Start Reactor Coolant Pump JPM NUMBER: NRCL162-LJCS4 INSTRUCTOR WORKSHEET Follow up Question Documentation:

Question: _____________________________________________________________________________________

Response: _____________________________________________________________________________________

- Denotes Critical Step and Sub-Steps Page 7 of 9 Rev. 0

JPM TITLE: Start Reactor Coolant Pump JPM NUMBER: NRCL162-LJCS4 ATTACHMENT 1, SIMULATOR SETUP INIT to JPM IC-218 This SNAP allows entry into EOP E-1.2, POST LOCA Cooldown and Depressurization, Step 14.d. SI, Containment Isolation Phase A, and Containment Isolation Phase B are reset. Leave simulator in FREEZE.

Inform the examiner that the simulator setup is complete.

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

Page 8 of 9 Rev. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL162-LJCS4 Initial Conditions: Given:

A small break loss of coolant accident has occurred. All reactor coolant pumps (RCPs) were previously secured in EOP E-0 when RCS pressure lowered to less than 1300 psig. The operators have just reached Step 14.d of EOP E-1.2 Initiating Cue: The Shift Foreman directs you to start RCP 1-2 in accordance with Appendix B of EOP E-1.2.

Page 9 of 9 Rev. 0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL162-LJCS5

Title:

Respond to CFCU High Vibration Examinee: ____________________________________________

Evaluator: ______________________________ ________________________________ __________________

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

OP F-2:II, Component Cooling Water System - Changing Over Pumps and Common Components, Rev. 15 OP H-2:I, Containment Fan Cooler Units - Make Available and System Operation, Rev. 37A.

References:

AR PK01-21, CONTMT FAN CLRS, Rev. 14 Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 3.3, 4.1 Job Designation: RO or SRO Rev Comments New 022.A4.01- Ability to manually operate and/or monitor in the Gen KA # / Rating: control room: CCS fans 3.6 / 3.6 AUTHOR: LISA TORIBIO DATE: 08/27/17 OPERATIONS REPRESENTATIVE: CHRISTOPHER MEHIGAN DATE: 10/24/17 REV.0

JPM TITLE: Respond to CFCU High Vibration JPM NUMBER: NRCL162-LJCS5 INSTRUCTOR WORKSHEET Directions: All actions taken by 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 steps with which to begin.

Required Materials: (Required materials here)

Initial Conditions: Given:

Unit 1 is at 100%.

Maintenance has requested shutdown of CCW Pump 1-2 in preparation for routine maintenance later this shift.

Initiating Cue: The Shift Foreman directs you to start CCW Pump 1-3 and shutdown CCW Pump 1-2 per OP F-2:II Section 6.1.

NOTE: Do NOT provide examinee with Task Standard Task Standard: CFCU High Vibration is addressed by performing the following:

Resetting VIB ALARM RESET to validate CFCU 1-3 high vibration condition

Depressing STOP button for CFCU 1-3 to shutdown the fan

- Denotes Critical Step and Sub-Steps Page 2 of 9 Rev.0

JPM TITLE: Respond to CFCU High Vibration JPM NUMBER: NRCL162-LJCS5 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 Referenced OP F-2:II, Step 6.1, Changing Over CCW Pumps.

1.2 Placed CCW Pump 1-3 Standby Select switch in "MAN".

1.3 Placed CCW Pump 1-3 Control Switch in "START".

1.4 Monitored CCW header flow and motor amperage prior to shutting down CCW Pump 1-2.

Note: High vibration on CFCU 1-3 is triggered 5 seconds after CCW Header C flow exceeds 2500 gpm.

Step was: Sat __________ Unsat __________

Comments:

<< Alternate Path - Start Point >>

2. AR PK01-21, CONTMT FAN CLRS 2.1 Responded to AR PK01-21, CONTMT FAN CLRS .

2.2 Determined alarm was caused by high vibration (INPUT 0434).

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 3 of 9 Rev.0

JPM TITLE: Respond to CFCU High Vibration JPM NUMBER: NRCL162-LJCS5 INSTRUCTOR WORKSHEET Step Expected Operator Actions

- 3. AR PK01-21, step 2.3.1 - Fan Cooler High 3.1 Determined alarm was caused by high vibration Vibration. on CFCU 1-3.

3.2 Read NOTE regarding vibration alarm is expected when starting, stopping, or shifting speeds on a CFCU and determined it does not apply.

- 3.3 Attempted to reset high vibration alarm by pressing VIB ALARM RESET pushbutton (VB1).

3.4 Identified reflash of PK01-21 due to valid high vibration condition on CFCU 1-3. (alarm returned)

Step was: Sat __________ Unsat __________

Comments:

- 4. AR PK01-21, step 2.3.3 - Actions if High Vib ** 4.1 Pressed STOP button for CFCU 1-3 on VB-1.

alarms again for the same CFCU.

Note: CFCU 1-5 is in standby and is also a bus G component. If the Candidate requests guidance on which standby CFCU should be started, provide the following CUE:

Cue: "Maintain the previous bus configuration for the running CFCUs."

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 4 of 9 Rev.0

JPM TITLE: Respond to CFCU High Vibration JPM NUMBER: NRCL162-LJCS5 INSTRUCTOR WORKSHEET Step Expected Operator Actions

5. OP H-2:I, Step 6.2.1 - Starting a CFCU" 5.1 Referenced OP H-2:I, Step 6.2, Starting a CFCU.

5.2 Read NOTE prior to Step 6.2.1.

Note: If the Candidate asks if this is an initial start of the CFCU following mainentance, provide the following CUE:

Cue: "This is NOT initial start of the CFCU following mainentance".

5.3 Ensured SPEED SELECT switch for chosen CFCU is selected to LOW.

5.4 Depressed switch to start fan.

5.5 Checked that fan current stabilizes Step was: Sat __________ Unsat __________

Comments:

6. OP H-2:I, Step 6.2.4 - CFCU High Speed desired 6.1 Noted High Speed IS desired.

6.2 Pressed STOP button for CFCU just started on VB-1.

6.3 Immediately placed SPEED SELECT switch in "HIGH" AND depressed select switch to restart the CFCU.

6.4 Returned CFCU Speed Select switch to "LOW".

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 5 of 9 Rev.0

JPM TITLE: Respond to CFCU High Vibration JPM NUMBER: NRCL162-LJCS5 INSTRUCTOR WORKSHEET Step Expected Operator Actions

7. OP H-2:I, Step 6.2.5 - Annunciator PK01-21, 7.1 Checked annunciator printout and confirms "CONTMT FAN CLRS," in Alarm. cause is high vibration on the CFCU just started.

7.2 Reset high vibration alarm by pressing VIB ALARM RESET pushbutton (VB1) and notes that PK01-21 does NOT reflash.

Note: If Examinee is ready to contact Maintenance regarding CFCU, provide the following CUE:

Cue: "Another Operator will continue in the procedure."

<< Alternate Path - End Point >>

Step was: Sat __________ Unsat __________

Comments:

Stop Time:

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

- Denotes Critical Step and Sub-Steps Page 6 of 9 Rev.0

JPM TITLE: Respond to CFCU High Vibration JPM NUMBER: NRCL162-LJCS5 INSTRUCTOR WORKSHEET Follow up Question Documentation:

Question: _____________________________________________________________________________________

Response: _____________________________________________________________________________________

- Denotes Critical Step and Sub-Steps Page 7 of 9 Rev.0

JPM TITLE: Respond to CFCU High Vibration JPM NUMBER: NRCL162-LJCS5 ATTACHMENT 1, SIMULATOR SETUP Initialize the simulator to IC-11 (75%, MOL)

Run Lesson NRC162-LJCS5.

Check BELLS ON Inform the examiner that the simulator setup is complete.

If Simulator is in FREEZE, go to RUN when the examinee is given the cue sheet.

Page 8 of 9 Rev.0

EXAMINEE CUE SHEET JPM NUMBER: NRCL162-LJCS5 Initial Conditions: Given:

Unit 1 is at 100%.

Maintenance has requested shutdown of CCW Pump 1-2 in preparation for routine maintenance later this shift.

Initiating Cue: The Shift Foreman directs you to start CCW Pump 1-3 and shutdown CCW Pump 1-2 per OP F-2:II Section 6.1.

Page 9 of 9 Rev.0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL162-LJCS6

Title:

Transfer Vital 4kV Bus from D/G to Startup Examinee: ____________________________________________

Evaluator: ______________________________ ________________________________ __________________

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

References:

OP J-6B:V, Diesel Generator 12, Manual Operations, Rev. 37 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 20 minutes Critical Steps: 3.2, 3.3, 3.4, 3.5, 5.1, 5.2, 7.1, 9.1, 9.4, 11.1, 11.2, 11.4, 11.5, 12.5, 12.6, 12.7 Job Designation: RO or SRO Rev Comments Modified from Bank LJC-087 064.A4.01- Ability to manually operate and/or monitor in the Gen KA # / Rating: control room: Local and remote operation of the ED/G. 4.0 / 4.3 AUTHOR: LISA TORIBIO DATE: 08/27/17 OPERATIONS REPRESENTATIVE: CHRISTOPHER MEHIGAN DATE: 10/24/17 REV.0

JPM TITLE: Transfer Vital 4kV Bus from D/G to Startup JPM NUMBER: NRCL162-LJCS6 INSTRUCTOR WORKSHEET Directions: All actions taken by 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 steps with which to begin.

Required Materials: None Initial Conditions: Given:

Unit 1 experienced a small break loss of coolant accident.

230 kV Power was unavailable at the time of the event and vital 4kV buses transferred to their respective Diesel Generators

230 kV has been restored and vital 4kV buses are being transferred off the Diesels and on to Startup.

Initiating Cue: The Shift Foreman directs you to parallel Diesel Generator 12 with Startup power, then unload and shutdown the Diesel Generator, per OP J-6B:V.

NOTE: Do NOT provide examinee with Task Standard Task Standard: Vital 4kV Bus G Transfer is complete such that:

Startup Power is supplying 4kV bus G

D/G 1-2 is shutdown and in an OPERABLE standby configuration by performing the following sequence:

1) Taking Mode Selector Switch to MANUAL

2) Ensuring D/G 1-2 is operating at 60 Hz

3) Placing Bus G Xfer to S/U PWR C/O switch to CUT-OUT

4) Resetting 4kV Bus G Auto Xfer and verifying blue indicating light is off

5) Inserting Sync key into Startup Feeder Breaker switch and turning to ON

6) Ensuring synchroscope is turning slowly in the counterclockwise (SLOW) direction and closing 52-HG-14 with the synchroscope slightly before 12 oclock

7) Turning the Sync key to the OFF position

8) Inserting Sync key into D/G 1-2 Feeder Breaker switch and turning to ON

9) Reducing load to approximately 0.1 MW and opening breaker 52-HG-5

10) Shutting down D/G 1-2 by taking the MAN MODE select switch to STOP

11) Placing D/G DIR PWR, LOSS OF FLD & BKR OC PROT RLYS C/O SW to CUT-OUT

12) Returning Mode Selector Switch to AUTO In accordance with OP J-6B:V, Diesel Generator 12, Manual Operations, Section 6.4.

Start

- Denotes Critical Step and Sub-Steps Page 2 of 10 Rev.0

JPM TITLE: Transfer Vital 4kV Bus from D/G to Startup JPM NUMBER: NRCL162-LJCS6 INSTRUCTOR WORKSHEET Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 Referenced OP J-6B:V, Step 6.4.

Step was: Sat __________ Unsat __________

Comments:

2. OP J-6B:V, step 6.4.1 - Check that the breaker 2.1 Read Note.

for the oncoming power supply is available and that its potential light is ON.

2.2 Checked breaker 52-HG-14 is available.

2.3 Checked white potential light ON.

Step was: Sat __________ Unsat __________

Comments:

- 3. OP J-6B:V, step 6.4.2 - Prepare the diesel 3.1 Read CAUTION.

generator for parallel to Startup power.

- 3.2 Placed Mode Selector Switch to MANUAL.

- 3.3 Adjusted Man Speed Control switch to obtain frequency of 60 Hz, as necessary.

- 3.4 Placed Bus G Xfer to S/U PWR C/O switch to CUT-OUT.

- 3.5 Reset 4kV Bus G Auto Xfer and verifies indicating light (blue light) is off.

3.6 Verified generator protective relays CUT-IN.

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 3 of 10 Rev.0

JPM TITLE: Transfer Vital 4kV Bus from D/G to Startup JPM NUMBER: NRCL162-LJCS6 INSTRUCTOR WORKSHEET Step Expected Operator Actions

4. OP J-6B:V, step 6.4.3 - Ensure 4kV bus G at 60 4.1 Verified 60 Hz indicated on Bus G frequency Hz using governor speed control as needed. indication.

4.2 Adjusted Man Speed Control switch to obtain 60 Hz, as necessary.

Step was: Sat __________ Unsat __________

Comments:

- 5. OP J-6B:V, step 6.4.4 - Ensure 4kV bus G at 60 ** 5.1 Inserted Sync key into Startup Feeder Breaker Hz using governor speed control as needed. switch.

- 5.2 Turned key to ON position.

Step was: Sat __________ Unsat __________

Comments:

6. OP J-6B:V, step 6.4.5 - Check proper 6.1 Observed light out at the 12 oclock position.

synchroscope function.

6.2 Observed lights full bright at 6 oclock position.

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 4 of 10 Rev.0

JPM TITLE: Transfer Vital 4kV Bus from D/G to Startup JPM NUMBER: NRCL162-LJCS6 INSTRUCTOR WORKSHEET Step Expected Operator Actions

- 7. OP J-6B:V, step 6.4.6 - Adjust DG 1-2 speed Note: D/G 1-2 is operating well below the load using the governor speed control for the limit which is considered NORMAL in the appropriate generator response. procedure.

- 7.1 Adjusted Man Speed Control switch to obtain synchroscope turning slowly in the counterclockwise (SLOW) direction.

Step was: Sat __________ Unsat __________

Comments:

Note: D/G 1-2 voltage is already within 2 volts of Aux Power and no adjustment is required

8. OP J-6B:V, step 6.4.7 - Adjust DG 1-2 voltage to 8.1 Adjusted Man/Auto Volt Control switch to within 2 volts of the oncoming power voltage match diesel voltage, w/in 2 volts, to the incoming auxiliary power voltage, as necessary.

Step was: Sat __________ Unsat __________

Comments:

- 9. OP J-6B:V, step 6.4.8 WHEN the ** 9.1 When Synchroscope was slightly before 12 synchroscope pointer is approaching and is just oclock (counter clockwise direction), closed 52-slightly before the 12 o'clock position, CLOSE HG-14.

Breaker 52-HG-14.

9.2 Verified RED light on 52-HG-14 indicating breaker is closed.

9.3 Observed VARS-OUT.

- 9.4 Turned Sync key to OFF position.

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 5 of 10 Rev.0

JPM TITLE: Transfer Vital 4kV Bus from D/G to Startup JPM NUMBER: NRCL162-LJCS6 INSTRUCTOR WORKSHEET Step Expected Operator Actions

10. OP J-6B:V, step 6.5.1,2 - Separating DG 1-2 10.1 Adjusted Man Speed Control switch to obtain from 4160V Bus G. about 0.5 MW at 0.5 MW every two minutes.

Note: After Candidate has completed first adjustment to lower D/G 1-2 load, provide the following CUE:

Cue: "Diesel generator 12 has been at 0.5 MW for 5 minutes."

Step was: Sat __________ Unsat __________

Comments:

- 11. OP J-6B:V, step 6.5.3-.6 - Separating DG 1-2 ** 11.1 Inserted Sync key into D/G 1-2 Feeder Breaker from 4160V Bus G. switch.

- 11.2 Turned Sync key to ON position.

11.3 Read CAUTION.

- 11.4 Reduced load to about 0.1 MW.

- 11.5 Promptly Opened Bkr. 52-HG-5.

11.6 Verified GREEN light on 52-HG-5 indicating breaker is open.

11.7 Adjusted diesel generator 12 speed and voltage to approximately 60 Hz and 119 VAC indicated, as required.

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 6 of 10 Rev.0

JPM TITLE: Transfer Vital 4kV Bus from D/G to Startup JPM NUMBER: NRCL162-LJCS6 INSTRUCTOR WORKSHEET Step Expected Operator Actions

- 12. OP J-6B:V, step 6.6 - Manually Secure DG 1-2 12.1 Checked Open 52-HG-5.

from the Control Room and Return to Standby Configuration 12.2 Verified DG 1-2 mode selector switch in MANUAL.

12.3 Verified DG 1-2 at 60 hz and 119 vac (may require slight adjustment).

12.4 Verified Feeder Synch switch is in OFF.

- 12.5 Shut down DG 1-2

- 12.6 Placed D/G DIR PWR, LOSS OF FLD & BKR OC PROT RLYS C/O SW to CUT-OUT.

- 12.7 Placed DG1-2 Mode sel switch in AUTO.

12.8 Verified S/U Pwr C/O switch is CUT IN.

Note: If asked about stator temperature trending, provide the following CUE:

Cue: "Stator temperature was NOT placed on trend in step 6.2.15."

Note: If asked about poly bottles, provide the following CUE:

Cue: "No poly bottles were installed at the DG fuel leakoff lines."

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 7 of 10 Rev.0

JPM TITLE: Transfer Vital 4kV Bus from D/G to Startup JPM NUMBER: NRCL162-LJCS6 INSTRUCTOR WORKSHEET Stop Time:

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

Follow up Question Documentation:

Question: _____________________________________________________________________________________

Response: _____________________________________________________________________________________

- Denotes Critical Step and Sub-Steps Page 8 of 10 Rev.0

JPM TITLE: Transfer Vital 4kV Bus from D/G to Startup JPM NUMBER: NRCL162-LJCS6 ATTACHMENT 1, SIMULATOR SETUP Initialize the simulator to IC-218 Run Lesson NRC162-LJCS6 Check BELLS ON Inform the examiner that the simulator setup is complete.

If Simulator is in FREEZE, go to RUN when the examinee is given the cue sheet.

Page 9 of 10 Rev.0

EXAMINEE CUE SHEET JPM NUMBER: NRCL162-LJCS6 Initial Conditions: Given:

Unit 1 experienced a small break loss of coolant accident.

230 kV Power was unavailable at the time of the event and vital 4kV buses transferred to their respective Diesel Generators

230 kV has been restored and vital 4kV buses are being transferred off the Diesels and on to Startup.

Initiating Cue: The Shift Foreman directs you to parallel Diesel Generator 12 with Startup power, then unload and shutdown the Diesel Generator, per OP J-6B:V.

Page 10 of 10 Rev.0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL162-LJCS7

Title:

Perform Turbine Load Trim to Match Tave to Tref Examinee: ____________________________________________

Evaluator: ______________________________ ________________________________ __________________

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

References:

OP C-3:III, Main Unit Turbine - At Power Operations, Rev. 36 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 3.1, 3.3, 4.3, 4.4, 5.2 Job Designation: RO or SRO Rev Comments New 045.A4.01- Ability to manually operate and/or monitor in the control room: Turbine Valve Indications (throttle, governor, Gen KA # / Rating: control). 3.1 / 2.9 AUTHOR: LISA TORIBIO DATE: 08/27/17 OPERATIONS REPRESENTATIVE: CHRISTOPHER MEHIGAN DATE: 10/24/17 REV.0

JPM TITLE: Perform Turbine Load Trim to Match Tave to Tref JPM NUMBER: NRCL162-LJCS7 INSTRUCTOR WORKSHEET Directions: All actions taken by 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 steps with which to begin.

Required Materials: None Initial Conditions: Given:

Unit 1 is at 75% following a ramp due to Heater #2 Drip Pump maintenance.

Current control band for Tave/Tref is plus or minus 0.5 oF.

Initiating Cue: The Shift Foreman directs you to perform a small turbine load adjustment of up to 12 MW at 0.7 MW/min with feedbacks out, following the guidance of OP C-3:III, Section 6 as necessary to maintain the current control band.

NOTE: Do NOT provide examinee with Task Standard Task Standard:

Ramp Rate LESS THAN 5 MW/min entered into Turbine Control HMI #

Load Target LESS THAN current MW Output entered into Turbine Control HMI

Tave matched to Tref within 0.5oF*

o Rods remain at CBD at 192 steps o Boron concentration remains at 919 ppm

At the Evaluator's discretion, this element of the Task Standard may be met by lowering Tave in the direction of Tref and the associated cue provided prior to step 6.1 of this JPM.

Ramp rate above 5 MW/min should only be utilized under abnormal conditions and requires following the guidance of OP AP-25, Rapid Load Reduction or Shutdown.

- Denotes Critical Step and Sub-Steps Page 2 of 9 Rev.0

JPM TITLE: Perform Turbine Load Trim to Match Tave to Tref JPM NUMBER: NRCL162-LJCS7 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 Referenced OP C-3:III, Main Unit Turbine - At Power Operations, Step 6.1 Step was: Sat __________ Unsat __________

Comments:

2. OP C-3:III, step 6.1.1,2 - Changing Turbine 2.1 Read Note.

Load.

2.2 Ensured VPL was out of the way to make the load change.

2.3 Noted current Turbine output was greater than 150 MWe and referenced Decision Tree for appropriate feedback configuration Note: If asked for SFM concurrence for leaving feedbacks out of service, provide the following CUE:

Cue: "Refer to the initial cue".

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 3 of 9 Rev.0

JPM TITLE: Perform Turbine Load Trim to Match Tave to Tref JPM NUMBER: NRCL162-LJCS7 INSTRUCTOR WORKSHEET Step Expected Operator Actions

- 3. OP C-3:III, steps 6.1.3-6.1.5 - Specifies Turbine ** 3.1 Selected the RAMP RATE button on Turbine Ramp Rate. Control HMI (CC3).

3.2 Read NOTE regarding ramp rates > 5 MW/min; determined note is N/A for trim.

Note: Expected rate from initial cue is 0.7 MW/min.

- 3.3 Entered ramp rate in MW/MIN on the popup screen and pressed OK.

3.4 Confirmed correct rate-of-change appeared in the RAMP RATE window.

Step was: Sat __________ Unsat __________

Comments:

- 4. OP C-3:III, steps 6.1.6-6.1.8 - Specifies Turbine 4.1 Read NOTE regarding Load Target and Actual Load Target. Load not being equal when feedbacks are out and determined note is applicable.

4.2 Noted Tave is LESS THAN Tref and determined Turbine load must be LOWERED.

- 4.3 Selected the LOAD TARGET button on Turbine Control HMI (CC3).

Note: Expected load target from initial cue is less than or equal to 12 MW in total reduction.

- 4.4 Entered a target load lower than current load AND pressed OK.

4.5 Confirmed correct load appeared in the LOAD TARGET window.

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 4 of 9 Rev.0

JPM TITLE: Perform Turbine Load Trim to Match Tave to Tref JPM NUMBER: NRCL162-LJCS7 INSTRUCTOR WORKSHEET Step Expected Operator Actions

- 5. OP C-3:III, steps 6.1.9 - Initiate ramp by 5.1 Read NOTEs regarding lag between Actual Load pressing GO. and Load Setpoint.

- 5.2 Pressed the GO button on Turbine Control HMI (CC3).

5.3 Monitored Tave/Tref mismatch for delta less than 0.5 oF.

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 5 of 9 Rev.0

JPM TITLE: Perform Turbine Load Trim to Match Tave to Tref JPM NUMBER: NRCL162-LJCS7 INSTRUCTOR WORKSHEET Step Expected Operator Actions

6. OP C-3:III, steps 6.2 - Places ramp on HOLD. Note: Evaluator may elect to wait for Tave to be matched to Tref within 0.5oF, or optionally provide the following CUE once observation of load trim rate and target have been deemed adequate.

Cue: "Using Time Compression, Tave is now matched to Tref within 0.5oF."

Note: Provide the following CUE once Tave has been matched to Tref within 0.5oF (actual or simulated using time compression).

Cue: "Place the ramp on HOLD and extinguish the HOLD button light".

6.1 Pressed the HOLD button on Turbine Control HMI (CC3).

6.2 Observed LOAD REFERENCE number in pop-up above HOLD button.

6.3 Pressed the LOAD TARGET button.

6.4 Entered the LOAD REFERENCE number from the pop-up above the HOLD button as the new LOAD TARGET.

6.5 Pressed GO.

6.6 Verified HOLD light went out.

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 6 of 9 Rev.0

JPM TITLE: Perform Turbine Load Trim to Match Tave to Tref JPM NUMBER: NRCL162-LJCS7 INSTRUCTOR WORKSHEET Stop Time:

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

Follow up Question Documentation:

Question: _____________________________________________________________________________________

Response: _____________________________________________________________________________________

- Denotes Critical Step and Sub-Steps Page 7 of 9 Rev.0

JPM TITLE: Perform Turbine Load Trim to Match Tave to Tref JPM NUMBER: NRCL162-LJCS7 ATTACHMENT 1, SIMULATOR SETUP Initialize the simulator to IC-160 Check BELLS ON.

Inform the examiner that the simulator setup is complete.

If Simulator is in FREEZE, go to RUN when the examinee is given the cue sheet.

Page 8 of 9 Rev.0

EXAMINEE CUE SHEET JPM NUMBER: NRCL162-LJCS7 Initial Conditions: Given:

Unit 1 is at 75% following a ramp due to Heater #2 Drip Pump maintenance.

Current control band for Tave/Tref is plus or minus 0.5 oF.

Initiating Cue: The Shift Foreman directs you to perform a small turbine load adjustment of up to 12 MW at 0.7 MW/min with feedbacks out, following the guidance of OP C-3:III, Section 6 as necessary to maintain the current control band.

Page 9 of 9 Rev.0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL162-LJCS8

Title:

Respond to Gaseous Rad Release Examinee: ____________________________________________

Evaluator: ______________________________ ________________________________ __________________

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

OP B-1A:X, CVCS - VCT Degassing, Unit 1, Rev. 33 OP AP-14, Tank Ruptures, Rev. 20

References:

AR PK04-24, VCT PRESS/LVL TEMP, Rev 19 Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 6.1, 6.2, 6.3 Job Designation: RO or SRO Rev Comments New 060.AA1.02- Ability to operate and/or monitor the following as they Gen KA # / Rating: apply to the Accidental Gaseous Radwaste: Ventilation System 2.9 / 3.1 AUTHOR: LISA TORIBIO DATE: 08/27/17 OPERATIONS REPRESENTATIVE: CHRISTOPHER MEHIGAN DATE: 10/24/17 REV.0

JPM TITLE: Respond to Gaseous Rad Release JPM NUMBER: NRCL162-LJCS8 INSTRUCTOR WORKSHEET Directions: All actions taken by 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 steps with which to begin.

Required Materials: None Initial Conditions: Given:

Unit 1 is at 75% power.

Chemistry requests a VCT degas to be completed per OP B-1A:X. The prerequisites and all applicable precautions and limitations are complete. Steps 6.1.1 through 6.1.5 are complete.

Initiating Cue: The Shift Foreman directs you to commence VCT degas starting at step 6.1.6 of OP B-1A:X. Per the completed reactivity brief, utilize blended flow of 20.8 gpm primary water and 2.9 gpm of boric acid..

NOTE: Do NOT provide examinee with Task Standard Task Standard: Auxiliary Building Ventilation is realigned through the charcoal filters for Unit 1:

"S" Signal Test on POV1 and POV2

Auxiliary Building Ventilation selected to Safeguards Only (VB4 select switch set to Safeguards Only

Auxiliary Building Ventilation Charcoal Filter Preheater energized (VB4 control switch set to "ON" In accordance with OP AP-14, Tank Ruptures, Section 6.

- Denotes Critical Step and Sub-Steps Page 2 of 9 Rev.0

JPM TITLE: Respond to Gaseous Rad Release JPM NUMBER: NRCL162-LJCS8 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. OP B-1A:VII, step 6.1.6 - Align VCT for Note: Rupture of VCT triggers off LCV-112A degassing. control switch being taken to VC TK 1.1 Attempted to align LCV-112A, VCT Level Cont Divert Vlv, to VC TK.

Step was: Sat __________ Unsat __________

Comments:

<< Alternate Path - Start Point >>

2. AR PK04-24, VCT PRESS/LVL TEMP. 2.1 Responded to AR PK04-24, VCT PRESS/LVL TEMP.

2.2 Determined cause of alarm is input 744, Volume Cont Tk Press < 15 psig.

Step was: Sat __________ Unsat __________

Comments:

3. AR PK04-24, steps 2.1.1-2.1.3 - VCT Pressure 3.1 Checked indication to confirm alarm Hi/Lo

PI-139, VCT Pressure (VB2)

LI-112, VCT Level (VB2) 3.2 Determined low pressure is NOT due to level change.

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 3 of 9 Rev.0

JPM TITLE: Respond to Gaseous Rad Release JPM NUMBER: NRCL162-LJCS8 INSTRUCTOR WORKSHEET Step Expected Operator Actions

4. AR PK04-24, step 2.1.4 - VCT Pressure low 4.1 Determined there are no evolutions currently in without a corresponding change in level. progress that would cause VCT pressure to drop abruptly.

4.2 Determined RCP seal return flows were normal.

Note: Booth Operator will report both alarms OFF when candidate call at next step.

4.3 Called the Auxiliary Building Nuclear Operator to verify Hydrogen and Nitrogen low pressure alarms were OFF at the Aux Board HMI.

Note: Provide the following cue if candidate attempts to evaluate possibility of voiding.

Cue: "Another Operator will evaluate possibility of voiding."

4.4 Determined VCT pressure was low due to a potential tank rupture and went to OP AP-14, Tank Ruptures.

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 4 of 9 Rev.0

JPM TITLE: Respond to Gaseous Rad Release JPM NUMBER: NRCL162-LJCS8 INSTRUCTOR WORKSHEET Step Expected Operator Actions

5. Op AP-14, step 1 - Alert Plant Personnel. 5.1 Made PA to alert plant personnel of VCT rupture in Aux Bldg.

Note: If candidate contacts RP to evacuate personnel from the Aux Bldg, provide the following CUE:

Cue: "The RP Supervisor has been notified and is handling evacuation of the Aux Bldg."

5.2 Noted need to perform EP R-2, Release of Airborne Radioactive Materials Initial Assessment Cue: "Another Operator will perform the required EP R-2 Assessment."

Step was: Sat __________ Unsat __________

Comments:

- 6. Op AP-14, Section 6, step 6.1 - Place Aux Bldg ** 6.1 Selected "S" Signal Test on Ventilation Through Charcoal Filters for Unit 1.

POV1

POV2

- 6.2 Placed Auxiliary Building Ventilation in Safeguards Only (VB4)

- 6.3 Selected Aux Bldg Vent Char Fltr Preheater Control Switch to "ON" to energize charcoal heaters (VB4)

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 5 of 9 Rev.0

JPM TITLE: Respond to Gaseous Rad Release JPM NUMBER: NRCL162-LJCS8 INSTRUCTOR WORKSHEET Step Expected Operator Actions

7. Op AP-14, Section 6, step 6.2 - Place Aux Bldg Note: When candidate request alignment of Ventilation Through Charcoal Filters for Unit 2 Unit 2 Aux Bldg ventilation, provide the following CUE:

Cue: "Another Operator will complete the procedure."

<< Alternate Path - End Point >>

Step was: Sat __________ Unsat __________

Comments:

Stop Time:

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

- Denotes Critical Step and Sub-Steps Page 6 of 9 Rev.0

JPM TITLE: Respond to Gaseous Rad Release JPM NUMBER: NRCL162-LJCS8 INSTRUCTOR WORKSHEET Follow up Question Documentation:

Question: _____________________________________________________________________________________

Response: _____________________________________________________________________________________

- Denotes Critical Step and Sub-Steps Page 7 of 9 Rev.0

JPM TITLE: Respond to Gaseous Rad Release JPM NUMBER: NRCL162-LJCS8 ATTACHMENT 1, SIMULATOR SETUP Initialize the simulator to IC-11 (75%, MOL)

Ensure starting VCT pressure range is between 20-24 psig.

Run Lesson NRC162-LJCS8.

Check BELLS ON Inform the examiner that the simulator setup is complete.

If Simulator is in FREEZE, go to RUN when the examinee is given the cue sheet.

Page 8 of 9 Rev.0

EXAMINEE CUE SHEET JPM NUMBER: NRCL162-LJCS8 Initial Conditions: Given:

Unit 1 is at 75% power.

Chemistry requests a VCT degas to be completed per OP B-1A:X. The prerequisites and all applicable precautions and limitations are complete. Steps 6.1.1 through 6.1.5 are complete.

Initiating Cue: The Shift Foreman directs you to commence VCT degas starting at step 6.1.6 of OP B-1A:X. Per the completed reactivity brief, utilize blended flow of 20.8 gpm primary water and 2.9 gpm of boric acid..

Page 9 of 9 Rev.0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL162-P1

Title:

Isolate Dilution Flow Paths Examinee: ____________________________________________

Evaluator: ______________________________ ________________________________ __________________

Print Signature Date Testing Method: Perform Simulate X Results: Sat __________ Unsat __________ Total Time: __________ minutes Comments: This is a Unit 1 JPM

References:

EOP FR-S.1, Response to Nuclear Power Generation/ATWS, Rev. 21.

OP1.ID2, TCOAs, Rev 9 (& TCOA database); TCOA item 21 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 25 minutes Critical Steps: 3.2, 8.3 Job Designation: RO / SRO Rev Comments/LRN TIPS: Bank LJP-062 004.A2.06 - Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Inadvertent Gen KA # / Rating: boration/dilution. 4.2 / 4.3 AUTHOR: LISA TORIBIO DATE: 07/27/17 OPERATIONS REPRESENTATIVE: CHRIS MEHIGAN DATE: 10/25/17 REV. 0

JPM TITLE: Isolate Dilution Flow Paths JPM NUMBER: NRCL162-P1 INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue.

The task standard will NOT be read to the examinee. The examiner will then ask if any clarifications are needed. The examinee should be given the required materials shown below, and access to other plant references as appropriate.

Equipment operation Cues are contingent on proper operation by the examinee and should be adjusted should equipment operation differ from expected.

Required Materials: Provide a copy of the reference procedure (partial procedure allowed), if the task is being done in the plant or lab; U1 EOP FR-S.1, App D.

Initial Conditions: Given:

Unit 1 is experiencing an inadvertent dilution

Emergency boration is being used to stabilize the plant Initiating Cue: The Shift Foreman directs you to check and isolate any dilution flowpaths to the RCS in accordance with EOP FR-S.1, Appendix D, Step 2.

NOTE: Do NOT provide examinee with Task Standard Task Standard: Dilution flow paths to the RCS have been checked and isolated such that the following normally OPEN valves are CLOSED:

CVCS-1-8519, Primary Water to Cation Demineralizer 11 Valve

CVCS-1-8469, Primary Water to Blender Isolation Valve in accordance with EOP FR-S.1.

Time Critical This JPM was evaluated against TCOA # 21 (During power ops - terminate dilution within 15 Operator Action minutes after Rod Lo-Lo Insertion Limit Alarm).

(TCOA): This TCOA:

Is NOT applicable to this JPM; the initial conditions and control room actions for the TCOA are not met, these local actions constitute only part of the operator response, and no formal time validation of these local actions has been performed. The steps required to successfully accomplish the task are designated as critical steps.

- Denotes Critical Step and Sub-Steps Page 2 of 10 Rev. 0

JPM TITLE: Isolate Dilution Flow Paths JPM NUMBER: NRCL162-P1 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. EOP FR-S.1, Appendix D, Step 2.a.1 - Ensure 1.1 Located valve CVCS-1-8539 at the demineralizer closed valve CVCS-1-8539, primary water to manifold on the 100' elevation (Mixed Bed 1-1 mixed bed demineralizer 11. outside wall) of the auxiliary building.

1.2 Ensured CVCS-1-8539 is closed.

Cue: Valve will not move in CW direction.

Step was: Sat __________ Unsat __________

Comments:

2. EOP FR-S.1, Appendix D, Step 2.a.2 - Ensure 2.1 Located valve CVCS-1-8538 at the demineralizer closed valve CVCS-1-8538, primary water to manifold on the 100' elevation (Mixed Bed 1-1 mixed bed demineralizer 12. outside wall) of the auxiliary building.

2.2 Ensured CVCS-1-8538 is closed.

Cue: Valve will not move in CW direction.

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 3 of 10 Rev. 0

JPM TITLE: Isolate Dilution Flow Paths JPM NUMBER: NRCL162-P1 INSTRUCTOR WORKSHEET Step Expected Operator Actions

- 3. EOP FR-S.1, Appendix D, Step 2.a.3 - Ensure 3.1 Located valve CVCS-1-8519 at the demineralizer closed valve CVCS-1-8519, primary water to manifold on the 100' elevation (Outside wall of cation demineralizer 11. cation demin) of the auxiliary building.

- 3.2 Ensured CVCS-1-8519 is closed.

Cue: Valve moved CW.

(If turned further)

Valve stopped moving CW. (hit seat)

Step was: Sat __________ Unsat __________

Comments:

4. EOP FR-S.1, Appendix D, Step 2.a.4 - Ensure 4.1 Located valve CVCS-1-8500A at the closed valve CVCS-1-8500A primary water to demineralizer manifold on the 100' (Outside deborating demineralizer 1-1 and 1-2 inlet. wall of Deborating Demins).

4.2 Ensured CVCS-1-8500A is closed.

Cue: Valve will not move in CW direction.

EOP FR-S.1, Appendix D, Step 2.a.5 - Ensure 4.3 Located valve CVCS-1-8500B.

closed valve CVCS-1-8500B primary water to deborating demineralizer 1-1 and 1-2 outlet.

4.4 Ensured CVCS-1-8500B is closed.

Cue: Valve will not move in CW direction.

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 4 of 10 Rev. 0

JPM TITLE: Isolate Dilution Flow Paths JPM NUMBER: NRCL162-P1 INSTRUCTOR WORKSHEET Step Expected Operator Actions

5. EOP FR-S.1, Appendix D, Step 2.b.1 - Ensure 5.1 Located valve CVCS-1-8506A at the closed valve CVCS-1-8506A. demineralizer manifold on the 100' elevation (Outside wall of Deborating Demins).

5.2 Ensured CVCS-1-8506A is closed.

Cue: Valve will not move in CW direction.

EOP FR-S.1, Appendix D, Step 2.b.2 - Ensure 5.3 Located valve CVCS-1-8506B at the closed valve CVCS-1-8506B. demineralizer manifold on the 100' elevation (Outside wall of Deborating Demins).

5.4 Ensured CVCS-1-8506B is closed.

Cue: Valve will not move in CW direction.

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 5 of 10 Rev. 0

JPM TITLE: Isolate Dilution Flow Paths JPM NUMBER: NRCL162-P1 INSTRUCTOR WORKSHEET Step Expected Operator Actions

6. EOP FR-S.1, Appendix D, Step 2.c.1 - Ensure Note: If area is a surface contamination area, closed valve CVCS 8464B, primary water to allow the Operator to point to the valves boric acid pumps 11 & 12. from outside the SCA.

6.1 Located valve CVCS-1-8464B at the boric acid pump skid on the 100' elevation of the auxiliary building.

6.2 Ensured CVCS-1-8464B is closed.

Cue: Valve will not move in CW direction.

EOP FR-S.1, Appendix D, Step 2.c.2 - Ensure 6.3 Located valve CVCS-1-8464A at the boric acid closed valve CVCS-1-8464A, primary water to pump skid on the 100' elevation of the auxiliary boric acid pumps 11 & 12. building.

6.4 Ensured CVCS-1-8464A is closed.

Cue: Valve will not move in CW direction.

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 6 of 10 Rev. 0

JPM TITLE: Isolate Dilution Flow Paths JPM NUMBER: NRCL162-P1 INSTRUCTOR WORKSHEET Step Expected Operator Actions

7. EOP FR-S.1, Appendix D, Step 2.d.1 - Ensure 7.1 Located valve CVCS-1-8435 outside the blender chemical mixing tank is isolated. room on the 100' elevation of the auxiliary building.

7.2 Ensured CVCS-1-8435 is closed.

Cue: Valve will not move in CW direction.

EOP FR-S.1, Appendix D, Step 2.d.2 - Ensure 7.3 Located valve CVCS-1-8454 outside the blender chemical mixing tank is isolated. room on the 100' elevation of the auxiliary building.

7.4 Ensured CVCS-1-8454 is closed.

Cue: Valve will not move in CW direction.

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 7 of 10 Rev. 0

JPM TITLE: Isolate Dilution Flow Paths JPM NUMBER: NRCL162-P1 INSTRUCTOR WORKSHEET Step Expected Operator Actions

- 8. EOP FR-S.1, Appendix D, Step 2.d.3 - Check 8.1 Located flow indicating transmitter FIT-111 flow on FIT-111. outside the blender room on the 100 elevation of the auxiliary building in Mechanical Panel 1-PM-96.

Cue: FIT-111 indicates 10 gpm.

8.2 Located valve CVCS-1-8469 outside the blender room on the 100 elevation of the auxiliary building.

- 8.3 Closed CVCS-1-8469.

Cue: FIT-111 indicates 0 gpm.

Step was: Sat __________ Unsat __________

Comments:

Stop Time:

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

- Denotes Critical Step and Sub-Steps Page 8 of 10 Rev. 0

JPM TITLE: Isolate Dilution Flow Paths JPM NUMBER: NRCL162-P1 INSTRUCTOR WORKSHEET Follow up Question Documentation:

Question: _____________________________________________________________________________________

Response: _____________________________________________________________________________________

- Denotes Critical Step and Sub-Steps Page 9 of 10 Rev. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL162-P1 Initial Conditions: Given:

Unit 1 is experiencing an inadvertent dilution

Emergency boration is being used to stabilize the plant Initiating Cue: The Shift Foreman directs you to check and isolate any dilution flowpaths to the RCS in accordance with EOP FR-S.1, Appendix D, Step 2.

Page 10 of 10 Rev. 0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL162-P2

Title:

Perform a Local Start of a Diesel Generator Examinee: ____________________________________________

Evaluator: ______________________________ ________________________________ __________________

Print Signature Date Testing Method: Perform Simulate X Results: Sat __________ Unsat __________ Total Time: __________ minutes Comments: This is a Unit 1 JPM

References:

OP AP-8A, Control Room Inaccessibility, Establishing HSB, Rev. 43 Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 20 minutes Critical Steps: 1.3, 2.2, 2.3, 3.2, 4.2, 8.2, 9.2 Job Designation: RO / SRO Rev Comments/LRN TIPS: Bank LJP-038 064.A3.06 - Ability to monitor automatic operation of the ED/G Gen KA # / Rating: system including: start and stop. 3.3 / 3.4 AUTHOR: LISA TORIBIO DATE: 08/24/17 OPERATIONS REPRESENTATIVE: CHRIS MEHIGAN DATE: 10/25/17 REV. 0

JPM TITLE: Perform a Local Start of a Diesel Generator JPM NUMBER: NRCL162-P2 INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue.

The task standard will NOT be read to the examinee. The examiner will then ask if any clarifications are needed. The examinee should be given the required materials shown below, and access to other plant references as appropriate.

Equipment operation Cues are contingent on proper operation by the examinee and should be adjusted should equipment operation differ from expected.

Required Materials: Copy of OP AP-8A (Unit 1), Section 9, Step 9.6 Initial Conditions: Given:

A fire in the vertical boards has required an evacuation of the control room.

U-1 control has been established from the Hot Shutdown Panel.

Initiating Cue: The Shift Foreman directs you to establish local control and start diesel generator 1-2 in accordance with OP AP-8A, Section 9, Step 9.6.

NOTE: Do NOT provide examinee with Task Standard Task Standard: Diesel Generator 1-2 has been started by sequentially

1) Placing 125V DC Control Power Transfer Switch (EQD-12) to OFF

2) Placing droop switch to the ISOC position

3) Placing the Mode Control selector switch to the TEST position

4) Placing the diesel generator 12 control selection switch to the LOCAL position

5) Placing the Remote Shutdown Fuse Selector (43DC-12/SS) switch to the BACKUP position

6) Placing the 125V DC control Power transfer switch (EQD-12) in BACKUP position.

7) Placing the Engine Control switch to the START position.

in accordance with OP AP-8A, Section 9, Step 9.6.

Site Safety All personnel entering the Diesel Generator room shall have double hearing protection in their Standard: possession. The individual performer shall have double hearing protection in place prior to simulating the manual start of Diesel Generator 1-2. Per TQ2.ID8, Rev. 17, the same safety standard shall be used for simulated tasks.

- Denotes Critical Step and Sub-Steps Page 2 of 10 Rev. 0

JPM TITLE: Perform a Local Start of a Diesel Generator JPM NUMBER: NRCL162-P2 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

- 1. OP AP-8A, Step 9.6.2 - Place the 125 VDC 1.1 Read and observed procedure CAUTIONs prior Control Power Transfer Switch (EQD-12) in to Step 9.6.

OFF.

1.2 Located the 125 V DC Control Power Transfer Switch on the right side of the DG 1-2 DC Cont Pwr Transfer Switch Panel.

- 1.3 Placed the 125V DC Control Power Transfer Switch (EQD-12) in OFF Cue: EQD-12 is in the OFF (middle) position.

Step was: Sat __________ Unsat __________

Comments:

- 2. OP AP-8A, Step 9.6.3, 4 -Place Droop Switch on 2.1 Located the diesel generator 12 droop switch excitation cubicle to "ISOC" and place Mode on the excitation cubicle.

Control Switch in "Test".

- 2.2 Placed the droop switch to the ISOC position.

Cue: The Droop Switch is in the ISOC position.

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 3 of 10 Rev. 0

JPM TITLE: Perform a Local Start of a Diesel Generator JPM NUMBER: NRCL162-P2 INSTRUCTOR WORKSHEET Step Expected Operator Actions

- 2.3 Placed the Mode Control selector switch to the TEST position.

Cue: The Mode Control Switch is in the TEST position.

Step was: Sat __________ Unsat __________

Comments:

Step Expected Operator Actions

- 3. OP AP-8A, Step 9.6.5 - Place Control Selection 3.1 Located the diesel generator 12 control switch on excitation cubicle in "LOCAL". selection switch on the excitation cubicle.

- 3.2 Placed the diesel generator 12 control selection switch to the LOCAL position.

Cue: The Control Selector Switch is in the LOCAL position.

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 4 of 10 Rev. 0

JPM TITLE: Perform a Local Start of a Diesel Generator JPM NUMBER: NRCL162-P2 INSTRUCTOR WORKSHEET Step Expected Operator Actions

- 4. OP AP-8A, Step 9.6.6 - Place Remote Shutdown 4.1 Located the 43DC-12/SS switch on the diesel Fuse Selector switch (43DC-12/SS) on control generator 12 local control panel.

panel in "BACKUP".

- 4.2 Placed the Remote Shutdown Fuse Selector switch to the BACKUP position.

Cue: The Remote Shutdown Fuse Selector switch is in the BACKUP position.

Step was: Sat __________ Unsat __________

Comments:

5. OP AP-8A, Step 9.6.7 - Place 125 VDC Control 5.1 Placed the 125V DC Control Power Transfer Power Transfer Switch (EQD-12) in "NORMAL". Switch to NORMAL.

Cue: The EQD-12 is in the NORMAL (top) position.

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 5 of 10 Rev. 0

JPM TITLE: Perform a Local Start of a Diesel Generator JPM NUMBER: NRCL162-P2 INSTRUCTOR WORKSHEET Step Expected Operator Actions

6. OP AP-8A, Step 9.6.8 - Press Alarm Relay Reset 6.1 Located the alarm relay reset push button on pushbutton on control panel. diesel generator 12 local control panel.

6.2 Depressed the alarm relay reset push button.

Cue: The Alarm Reset push button has been depressed and returned to normal.

Step was: Sat __________ Unsat __________

Comments:

7. OP AP-8A, Step 9.6.9 - Place engine control Note: Per DCP Site Safety Standards, the switch (DE-12) on control panel in "START". individual performer should have double hearing protection in place prior to simulating start of Diesel Generator 1-2.

7.1 Read NOTE 7.2 Located the START/STOP switch at the diesel generator 12 local control panel.

7.3 Placed the START/STOP switch to the START position.

Cue: There was no audible noise level change in the room (the diesel generator did not start).

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 6 of 10 Rev. 0

JPM TITLE: Perform a Local Start of a Diesel Generator JPM NUMBER: NRCL162-P2 INSTRUCTOR WORKSHEET Step Expected Operator Actions

<< Alternate Path - Start Point >>

- 8. OP AP-8A, Step 9.6.10.a-c - IF DG 1-2 did NOT 8.1 Located control power transfer switch EQD-12 start, transfer Control Power to Backup. opposite the diesel generator 12 local control panel.

- 8.2 Placed the 125V DC control Power transfer switch (EQD-12) in OFF, waits 10 seconds, then places in BACKUP position.

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

Step was: Sat __________ Unsat __________

Comments:

- 9. OP AP-8A, Step 9.6.10.d - Place engine control 9.1 Located the Engine Control switch at the diesel switch (DE-12) on control panel in "START". generator 12 local control panel.

- 9.2 Placed the Engine Control switch to the START position.

Cue: Normal DG startup noise level is heard.

<< Alternate Path - End Point >>

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 7 of 10 Rev. 0

JPM TITLE: Perform a Local Start of a Diesel Generator JPM NUMBER: NRCL162-P2 INSTRUCTOR WORKSHEET Step Expected Operator Actions

10. OP AP-8A, Step 9.6.11 - Contact HSDP 10.1 Notified the SFM at the U-1 HSDP of DG status, and asks if 4KV bus voltage is satisfactory Cue: The U-1 SFM reports that DG 1-2 operation and 4KV bus voltage are satisfactory.

Step was: Sat __________ Unsat __________

Comments:

Stop Time:

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

- Denotes Critical Step and Sub-Steps Page 8 of 10 Rev. 0

JPM TITLE: Perform a Local Start of a Diesel Generator JPM NUMBER: NRCL162-P2 INSTRUCTOR WORKSHEET Follow up Question Documentation:

Question: _____________________________________________________________________________________

Response: _____________________________________________________________________________________

- Denotes Critical Step and Sub-Steps Page 9 of 10 Rev. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL162-P2 Initial Conditions: Given:

A fire in the vertical boards has required an evacuation of the control room.

U-1 control has been established from the Hot Shutdown Panel.

Initiating Cue: The Shift Foreman directs you to establish local control and start diesel generator 1-2 in accordance with OP AP-8A, Section 9, Step 9.6.

Page 10 of 10 Rev. 0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL162-P3

Title:

Manually Operate the Cardox System Examinee: ____________________________________________

Evaluator: ______________________________ ________________________________ __________________

Print Signature Date Testing Method: Perform Simulate X Results: Sat __________ Unsat __________ Total Time: __________ minutes Comments: This is a Unit 2 JPM

References:

Units 1&2, OP K-2B:II, Manual Use of the Cardox System, Rev. 11 Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 2.4, 3.1, 3.2 Job Designation: RO or SRO Rev Comments/LRN TIPS: Bank LJP-138A 067.AA1.08 - Ability to operate and / or monitor the following as they apply to the Plant Fire on Site: Fire fighting equipment used on Gen KA # / Rating: each class of fire. 3.4 / 3.7 AUTHOR: LISA TORIBIO DATE: 08/30/17 OPERATIONS REPRESENTATIVE: CHRISTOPHER MEHIGAN DATE: 10/25/17 REV. 0

JPM TITLE: Manually Operate the Cardox System JPM NUMBER: NRCL162-P3 INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue.

The task standard will NOT be read to the examinee. The examiner will then ask if any clarifications are needed. The examinee should be given the required materials shown below, and access to other plant references as appropriate.

Equipment operation Cues are contingent on proper operation by the examinee and should be adjusted should equipment operation differ from expected.

Required Materials: Copy of OP K-2B:II, Section 6.3.

Initial Conditions: Given:

A fire has been reported in the Unit 2 Cable Spreading Room.

Automatic actuation of the Cable Spreading Room cardox has not occurred.

Manual Control Room actuation of the Unit 2 Cable Spreading Room did not work.

There are NO personnel in either Cable Spreading Room.

Initiating Cue: The Shift Foreman directs you to locally actuate cardox discharge to the Unit 2 Cable Spreading Room, per OP K-2B:II, Step 6.3.

NOTE: Do NOT provide examinee with Task Standard Task Standard: Cardox is initiated to the U2 Cable Spreading Room for the proper duration, in accordance with OP K-2B:II by performing the following:

Opening 2-FCV-102

Opening 0-FCV-104

Reclosing 2-FCV-102

- Denotes Critical Step and Sub-Steps Page 2 of 7 Rev. 0

JPM TITLE: Manually Operate the Cardox System JPM NUMBER: NRCL162-P3 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. OP K-2B:II, Step 6.3.1 - Attempts local 1.1 Read NOTE prior to Step 6.3.1.

discharge to U-2 Cable Spreading Room via pushbutton.

1.2 For 2-FCV-102, pulled cover and depressed button.

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

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

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 3 of 7 Rev. 0

JPM TITLE: Manually Operate the Cardox System JPM NUMBER: NRCL162-P3 INSTRUCTOR WORKSHEET

<< Alternate Path - Start Point >>

Step Expected Operator Actions

- 2. OP K-2B:II, Step 6.3.2.a-c - Manually actuates 2.1 Read CAUTION prior to Step 6.3.2.a.

CO2 to the Cable Spreading Room.

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

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

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

- 2.3 Verified abort valve for Unit 2 Cable Spreading Room is open (2-HCV-2074).

Cue: The valve operator for 2-HCV-2074 is in line/parallel with the piping.

- 2.4 Broke glass and opened pilot for 2-FCV-102.

2.5 Read note prior to step to open 0-FCV-104.

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

Step was: Sat __________ Unsat __________

Comments:

- Denotes Critical Step and Sub-Steps Page 4 of 7 Rev. 0

JPM TITLE: Manually Operate the Cardox System JPM NUMBER: NRCL162-P3 INSTRUCTOR WORKSHEET Step Expected Operator Actions

- 3. OP K-2B:II, Step 6.3.2.d-e - Manually opens the ** 3.1 At the storage tank, broke glass and opened the Selector Pilot Control Valve. 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 between 2 minutes and 35 to 2 minutes 45 seconds.

Cue: Two minutes and 40 seconds have elapsed.

- 3.2 Closed the Selector Pilot Control Valve 2-FCV-102.

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

<< Alternate Path - End Point >>

Step was: Sat __________ Unsat __________

Comments:

Stop Time:

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

- Denotes Critical Step and Sub-Steps Page 5 of 7 Rev. 0

JPM TITLE: Manually Operate the Cardox System JPM NUMBER: NRCL162-P3 INSTRUCTOR WORKSHEET Follow up Question Documentation:

Question: _____________________________________________________________________________________

Response: _____________________________________________________________________________________

- Denotes Critical Step and Sub-Steps Page 6 of 7 Rev. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL162-P3 Initial Conditions: Given:

A fire has been reported in the Unit 2 Cable Spreading Room.

Automatic actuation of the Cable Spreading Room cardox has not occurred.

Manual Control Room actuation of the Unit 2 Cable Spreading Room did not work.

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.

Page 7 of 7 Rev. 0

Appendix D (rev 11) Scenario Outline Form ES-D-1 Facility: Diablo Canyon (PWR) Scenario No: 1 Op-Test No: L162 NRC Examiners: Operators:

Initial Conditions: 3% power with CCP 1-2 In Service (75 gpm letdown); MFP 1-1 supplying S/Gs; on Startup Power; MOL, 1234 ppm boron Turnover: In OP L-3, performing step 6.28, raising power to 8%.

Event Malf Event Event Description No No. Type* (See Summary for Narrative Detail) 1 N/A R (ATC, Raise reactor power from 3% to 8% OP L-3, sec 6.28 SRO) 2 XMT_RMS23_3 1E+006 TS, I S/G Blowdown RM-23 fails high. FCV-498/ FCV-499 and half (BOP, of sample valves fail to isolate, but can be manually closed SRO) (ECG 39.3.B)(PK11-17) 3 PMP_CVC2_2 OVERLOAD_DEV_FAIL TS, C Centrifugal Charging Pump 1-2 OC Trip requiring restoration (ALL) of letdown (TS 3.5.2.A) (AP-17) 4 XMT_MSS1_3 15 ramp=300 I (ATC, PT-507, Steam Generator Header Pressure Transmitter, slow SRO) failure low causing Group I dumps to close. (AP-5)

PMP_AFW1_2 OVERLOAD_DEV_FAIL 5 TS, C MFP 1-1 trips. MDAFW pumps start but trip; requires start of PMP_AFW2_2 OVERLOAD_DEV_FAIL (ALL) TDAFW pump. (TS 3.7.5.D)(PK09-12, AP-15)

BST_MFW1_1 1 6 MAL_MSS6A 90 ramp=240 M S/G 1-1 Safety Lifts; reseats 10 seconds after SI (ALL)

MAL_MSS6A 0 delay=10 cd='jpplsia' 7 CVC9CVC_CCP11_MTRSHEAR C CCP 1-1 shaft shear 30 seconds after SI delay=30 cd='jpplsia' (BOP) 8 VLV_PZR4_2 0.3 cd='jpplsia' del C Pressurizer PORV PCV-455C fails slightly open on trip ay=60 (BOP) requiring manual isolation by associated block valve 9 MAL_RCS3B 3.5 cd='V1_240S_1 or M SBLOCA after SI is terminated in E-1.1 V1_241S_1' delay=0 ramp=15 (ALL)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor L162 NRC ES-D-1-01 r1.docx Page 1 of 3 Rev 1

Appendix D (rev 11) Scenario Outline 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) (Event 7,8) 2

3. Abnormal events (1-4) (Events 2,3,4,5) 4

4. Major transients (1-2) (Events 6,9) 2

5. EOPs entered/requiring substantive actions (1-2) (E-1.1) 1

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

7. Critical tasks (2-3)(See description below) 2 Critical Task Justification Reference (S1CT-1) Close the block MOV upstream of The open PORV and block valve constitute the

Westinghouse Owners the stuck open PORV prior to performance degradation of a fission product barrier. Closing the Group WCAP-17711-NP of step 8 of EOP E-0, Reactor Trip or Safety block valve is essential to safety since failure to do Injection. so results in the unnecessary continuation of the degraded condition.

(S1CT-2) Reinitate SI before a severe Degraded core cooling is caused by a substantial

Background Information challenge to the Core Cooling Critical Safety loss of primary coolant. Reinitiation of high for WOG Emergency Function develops (magenta path on F-0.2 pressure safety injection is the most effective Response Guideline Core Cooling). method to restore RCS inventory and core cooling. HFRC2BG Rev 3.

The effectiveness of safety injection in restoring core cooling is determined by the trend in core exit TC temperatures or RVLIS full range when the RCPs are tripped.

Per NUREG-1021, Appendix D, if an operator or crew significantly deviates from or fails to follow procedures that affect the maintenance of basic safety functions, those actions may form the basis of a CT identified in the post-scenario review.

L162 NRC ES-D-1-01 r1.docx Page 2 of 3 Rev 1

SCENARIO

SUMMARY

- NRC #1

1. Control rods are used to raise power from 2% to 8% OP L-3, Secondary Plant Startup, step 6.28. ATC operator complies with 1 step pull and wait procedural requirement while monitoring relevant controls and diverse indicators. Shift Foreman provides reactivity oversight.

2. S/G Blowdown RM-23 fails high resulting in only a partial blowdown isolation. The crew responds, manually isolating the unactuated sample isolation valves and realigning blowdown discharge to the Equipment Drain Receiver, following the guidance of AR PK11-17, SG BLOW DOWN HI RAD. Shift Foreman enters ECG 39.3.B, Radioactive Liquid Effluent Monitoring Instrumentation, for Steam Generator Blowdown Tank (RM-23) inoperable.

3. Charging Pump CCP 1-2 trips on over current. The crew responds by entering OP AP-17, Loss of Charging to restore normal charging and letdown. Shift Foreman enters Tech Spec 3.5.2.A, ECCS - Operating, for one ECCS train inoperable.

4. PT-507, Steam Generator Header Pressure Transmitter, 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.

5. MFP 1-1 trips on high vibration. Both MDAFW pumps start initially, but trip on overcurrent. The crew enters AR PK09-12, Main Feedwater Pump Trip, and follow the guidance of OP AP-15, Loss of Feedwater Flow, Section B: Single Operating MFP Trips, starting the TDAFW pump, tripping the turbine, and inserting rods in manual to reduce power to 2%. Shift Foreman enters Tech Spec 3.7.5.D, AFW System, for two AFW trains inoperable.

6. S/G 1-1 Safety lifts causing uncontrollable depressurization of S/G 1-1. Shift Foreman directs board operators to trip the reactor and initiate Safety Injection once reactor trip has been verified. The crew enters EOP E-0, Reactor Trip or Safety Injection. The safety valve reseats 45 seconds after Safety Injection initiates. The crew throttles AFW to control the cooldown as they work their way towards SI termination.

7. CCP 1-1 fails due to a sheared shaft 30 seconds after SI actuation. The board operator identifies the condition based on low motor amps and flow.

8. Board operators also identify PCV-455C in mid-position. The valve will not close and must be isolated using the associated block valve 8000B (S1CT-1) Close the block MOV upstream of the stuck open PORV before performing step 8 of EOP E-0).

9. Once termination criteria has been met, the crew transitions to EOP E-1.1, SI Termination. A SBLOCA occurs immediately following the shutdown of Safety Injection Pump 1-2. The crew performs the final critical task of reinitiating Safety Injection (S1CT-2) Reinitate SI before a severe challenge to the Core Cooling Critical Safety Function develops (magenta path on F-0.2 Core Cooling).

The scenario is terminated once ECCS pumps have been restarted.

L162 NRC ES-D-1-01 r1.docx Page 3 of 3 Rev 1

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 1 Event No.: 1 Page 1 of 16 Event

Description:

Raise Power to 8%

Time Position Applicants Actions or Behavior Note: Procedure step numbers are included at the front of each action/comment in parenthesis, where applicable.

(OP L-3, Secondary Plant Startup, starting at step 6.28)

SRO Reads NOTE prior to step 6.28 ATC * (6.28) Slowly raises power to 8% by pulling control rods one step at a time.

SRO Provides reactivity oversight while raising power BOP * (6.29) Monitors feed/steam delta P (PI-509, VB3 or CC2, DFWCS HMI on CC3)

(6.30) Verifies that DFWCS maintains constant delta P during rise in power SRO

Reads NOTE prior to step 6.31 Proceed to the next event once reactivity manipulation adequately observed and power > 3.5%, per the lead examiner.

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 1 Event No.: 2 Page 2 of 16 Event

Description:

S/G Blowdown RM-23 Fails High Time Position Applicants Actions or Behavior ALL Diagnosis made by using one or more of the following:

PK11-17, SG BLOW DOWN HI RAD

Several blowdown isolation and sample valves going closed SRO Implements PK11-17, SG BLOW DOWN HI RAD (AR PK11-17, SG BLOW DOWN HI RAD)

SRO/ATC * (1) Reads input 1242 and determines failure is from RE-23, goes to section 2.1 for General Actions SRO/BOP (2.1.1) Determines blowdown isolated and SG Blowdown Tank shift to Equipment Drain Receiver did not occur (partial isolation only)

Closes OC SG blowdown isolation valves (red light out, green light lit) o FCV-151, FCV-154 (VB3)

Closes SG blowdown sample valves (red light out, green light lit) o FCV-250, FCV-248 (VB3)

Closes FCV-498, Disch Tunnel (red light out)

Opens FCV-499, Equip Drn Rcvr (blue light lit)

SRO (2.1.2 - 2.1.9) Performs several evaluate steps and directs Chemistry to sample S/Gs.

SRO/BOP (2.1.10) Places the RE 19 & 23 Hi Rad SG BD & Smpl Vlvs (O.C.) Iso Defeat C/O SW in "CUT IN" (up) position (VB3)

SRO Enters ECG 39.3.B, Radioactive Liquid Effluent Monitoring Instrumentation, for Steam Generator Blowdown Tank (RM-23) inoperable. Required actions: Stop any discharge in progress. Discharges may be made, provided grab samples are performed prior to release.

Restore to OPERABLE status within 30 days.

Proceed to the next event once ECG addressed, per the lead examiner.

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 1 Event No.: 3 Page 3 of 16 Event

Description:

Centrifugal Charging Pump 1-2 OC Trip Time Position Applicants Actions or Behavior ALL Diagnosis of CCP 1-2 OC trip is made from one or more of the following:

CCP 12 blue OC light is lit, and the pump is no longer running (VB2, lower center)

PK0417, CCP 12 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)

SRO Implements OP AP17, Loss of Charging, Section A, Loss of All Charging (OP AP-17, Loss of Charging starting at section A, Loss of All 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 SRO) (VB2, lower center)

SRO/ATC * (1.f) Establishes charging flow to RCP seals only (all CC2, right side) o Throttles FCV128 open to establish 813 gpm each to RCP seal o Throttles HCV142 to closed or nearly closed (continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 1 Event No.: 3 Page 4 of 16 Event

Description:

Centrifugal Charging Pump 1-2 OC Trip (cont)

Time Position Applicants Actions or Behavior (OP AP-17, Loss of Charging starting at section A, Loss of All Charging, cont)

SRO/ATC * (1.g,h) Adjusts charging in manual to return level to program(FCV128) (CC2)

(2) Adjusts HCV142 to maintain RCP seal flows 813 gpm (CC2)

(3.a) Checks Pzr level > 17% (CC2 recorder, PPC, VB2 meter)

SRO/BOP * (3.b) Checks letdown in service; determines normal letdown can be restored (VB2, upper left skirt)

(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 (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 and returns to AUTO (VB2, upper middle).

o (1j) Adjusts TCV130 for 90oF110oF on TI130 and returns to AUTO (VB2, upper middle).

o (1k) Checks RV8117 Letdown Relief Valve tailpipe temperature to verify relief valve is seated (TI129 VB2, middle)

(OP AP-17, Loss of Charging starting at section A, Loss of All Charging, cont)

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)

(continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 1 Event No.: 3 Page 5 of 16 Event

Description:

Centrifugal Charging Pump 1-2 OC Trip (cont)

Time Position Applicants Actions or Behavior (OP AP-17, Loss of Charging starting at section A, Loss of All Charging, cont)

SRO/ATC * (4.a - d.) Checks VCT Makeup Control o Checks VCT level 14% to 87% (LI-112 on VB2) o Reads NOTE prior to step 4.b o Checks VCT pressure 15 to 60 psig (PI-135 on VB2) o VCT makeup control (YIC-100) in AUTO mode and set for current RCS boron concentration which is displayed on lamicoid above ATC PPC displays (CC2)

SRO/BOP * (4.e) Verifies instrument air is available (VB4 lower left area)

(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:

o Verify only one subsystem in the ECCS train is inoperable, and determine there is no common cause failure in the same subsystem in the operable ECCS train within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months o Restore train to operable status within 14 days.

Proceed to the next event once Tech Specs addressed, per the lead examiner.

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 1 Event No.: 4 Page 6 of 16 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 * (1.0) 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 * (2.0) Determines that the failure is not Eagle21 related (PK0601 and PK0603 are OFF)

SRO/ATC * (3.0) Determines failure is not associated with a T channel (VB2)

SRO/ATC * (4.0) Verifies steam dumps are not open as result of instrument failure or spurious actuation. (Dumps SHOULD be open to maintain temperature for current 3% power conditions. Shift Foreman SHOULD NOT enter RESPONSE NOT OBTAINED column)

(continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 1 Event No.: 4 Page 7 of 16 Event

Description:

Steam Header Pressure Transmitter PT507 Slow Failure (cont)

Time Position Applicants Actions or Behavior (OP AP5, Malfunction of Eagle21 Protection or Control Channel, cont.)

SRO * (5.0) Notifies I&C of the PT507 failure, as time permits SRO

Reads CAUTION prior to step 6 SRO * (6.0) Notes requirements to take channel OOS prior to maintenance SRO/BOP * (7.0) 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.

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 1 Event No.: 5 Page 8 of 16 Event

Description:

MFP 1-1 trips; MDAFW pumps start but trip Time Position Applicants Actions or Behavior Note: If the crew manually trips the reactor in response to this failure, the scenario major event (S/G safety valve lifting) will be initiated and the scenario continued. A manual reactor trip would be considered a post-scenario Critical Task.

ALL Diagnoses MFP 1-1 trip from one or more of the following:

PK09-12, Main Feedwater Pump Trip (PK09-12, Main Feedwater Pump Trip, (if entered))

SRO * (1) Reads input 557 and confirms MFP 1-1 has tripped; goes to section 2.1 for General Actions SRO * (2.1.1-2.1.2) Notes Reactor is below 15% , therefore, auto Rx trip doesn't apply, nor does the requirement to manually trip the reactor.

(2.1.3) Notes programmed ramp is not applicable for current configuration

(2.1.4) Implements OP AP-15, Loss of Feedwater Flow (OP AP15, Loss of Feedwater Flow)

SRO

Determines Section B: Single Operating MFP Trips is the appropriate section; goes to page 8.

(Section B: Single Operating MFP Trips:

(1) Checks power is less than 15%

SRO/BOP * (2) Checks status of AFW pumps (VB3) o Notes MDAFW pumps have tripped.

o Step requires all AFW pumps to be running; starts TDAFW pump

(3) Determines MFP 1-2 is NOT latched (therefore NOT available for loading); follows RNO to step 5.

(continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 1 Event No.: 5 Page 9 of 16 Event

Description:

MFP 1-1 trips; MDAFW pumps start but trip (cont)

Time Position Applicants Actions or Behavior SRO/BOP * (5) Directs/performs manual trip of the Main Turbine (CC3)

SRO/ATC * (6) Manually inserts control rods to reduce reactor power to approximately 2% (CC1)

(7) Ensures PZR Backup Heaters are ON (CC1)

(8) Contacts Reactor Engineering for guidance on additional boric acid requirements

(9) Checks PZR level and pressure trending to program band SRO

Reviews Tech Specs and enters Tech Spec 3.7.5.D - TWO AFW trains inoperable.

Required actions: Be in MODE 3 in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and MODE 4 in 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months .

Proceed to the next event once crew has reduced power and addressed Tech Specs, per the lead examiner.

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 1 Event No.: 6 Page 10 of 16 Event

Description:

S/G 1-1 Safeties Lift Requiring Safety Injection Time Position Applicants Actions or Behavior ALL Crew identifies steam leak by one or more of the following:

Sound of steam flow

Increased Steam Flow: PPC, VB3, CC3 steam flow meters, record, and trends

Lowering S/G 1-1 pressure and level: VB3 and PPC

RCS Cooldown Indications: PPC, VB2, and CC1 trends

RCS temperature lowering, pressurizer level and pressure lowering based on the following:

Annunciator Response Alarms:

AR PK09-01, S/G 1-1 PRESS, LVL FLOW (due to lowering S/G 1-1 pressure and level)

AR PK09-15, DIGITAL FEEDWATER CONT SYSTEM (due to feedflow/steam flow mismatch)

AR PK05-16, PZR PRESSURE HI/LO (pressure low due to cooldown)

AR PK04-06, PROTECT CHANNEL ACTIVATED (for Tave less than 554 oF on loop 1 due to cooldown)

SRO/ATC

Directs/performs manual Reactor Trip and Safety Injection ALL

Performs Immediate Actions SRO

Implements EOP E-0, Reactor Trip or Safety Injection (continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 1 Event No.: 6,7,8 Page 11 of 16 Event

Description:

S/G 1-1 Safeties Lift Requiring Safety Injection CCP 1-1 Shaft Shear 30 seconds after Safety Injection PCV-455C lifts on trip (CT)

Time Position Applicants Actions or Behavior (EOP E-0, Reactor Trip or Safety Injection)

SRO/ATC * (1) Verifies reactor trip (trip bkrs open (VB2 upper left), rods on bottom (VB2 upper left DRPI panel), NIs decreasing (CC1 left)

(2) Verifies turbine trip (stop valves closed) (CC3 HMI or VB2 RPS indicator lamps).

SRO/BOP * (3) Checks vital 4kv buses (VB4, vital busses F/G/H have white lights on mimic busses)

SRO/ATC * (4) Checks if SI actuated (PK08-21 ON, also checks VB1 red train lights and/or train equipment to verify both trains actuated)

SRO * (5) Directs App E implemented (usually to BOP)(see page 15)

SRO/ATC * (6) Checks RCS temperature - stable (temps will initially be dropping due to faulted S/G; AFW should be throttled back (VB2, upper panel lower area)

SRO/ATC * (7) Checks Pzr PORVs and Pzr safeties (closed) / PORV block valves (all open, and no elevated tailpipe temps or sonic flows on safeties/PORVs (VB2 - upper panel, far right);

checks Pzr sprays closed (CC2) o Identifies 455C is OPEN and attempts closing valve but is unsuccessful (VB2) o Closes block valve 8000B (S1CT-1)**

(8) Checks RCP trip criteria (RCS pressure [VB2, PPC] < 1300 psig and SI or ECCS CCPs running (VB1 and VB2))

- (Critical Task)(S1CT-1, Close the block MOV upstream of the stuck open PORV prior to performance of step 8 of EOP E-0).

(continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 1 Event No.: 6 Page 12 of 16 Event

Description:

S/G 1-1 Safeties Lift Requiring Safety Injection Time Position Applicants Actions or Behavior (EOP E-0, Reactor Trip or Safety Injection, cont)

SRO/ATC * (9) Determines S/G are NOT faulted o May note S/G 1-1 is depressurized, but has stabilized o None are completely depressurized SRO/BOP * (10) Determines S/G are NOT ruptured o Checks RE-71/72/73/74 and RE-15/19 recorders on VB2 (and PPC); (all normal) o PK11-06/18-OFF, PK 11-17 in from previous RM-23 failure.

SRO/ATC * (11) Checks RCS intact o (11a) Determines containment pressure is normal (VB1 meters, PPC) o (11b) Determines containment sump levels normal (VB1 meters, PAMS) o (11c) Determines containment radiation is normal (RM-11, 02, 07)

SRO/ATC * (12) Checks if ECCS Flow Should Be Reduced o RCS Subcooling > 20 oF (YI-31 on VB2 - upper panel, far right or SPDS) o Secondary Heat Sink Total AFW Flow > 435 gpm (VB3)

S/G NR Level > 15% on at least one S/G (VB3) o WR RCS Pressure Stable or Rising o PRZ Level > 12%

SRO/ATC * (13) Checks SI Reset (continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 1 Event No.: 6,7 Page 13 of 16 Event

Description:

S/G 1-1 Safeties Lift Requiring Safety Injection CCP 1-1 Shaft Shear 30 seconds after Safety Injection Time Position Applicants Actions or Behavior (EOP E-0, Reactor Trip or Safety Injection, cont)

Note: CCP 1-1 has a sheared shaft and may still be running if not shutdown as part of EOP E-0, Appendix E actions SRO/ALL * (14) Aligns Charging o (14.a) Checks ECCS CCP running Identifies low amperage on CCP 1-1 indicating a sheared shaft (VB2)

Shuts down CCP 1-1 (VB2) o (14.b) Depresses Vital 4kV Auto Transfer Relay Resets: Blue Light - OFF o (14.c,d) Stops CCP 1-3 if CCP 1-1 still running; will leave CCP 1-3 running if they secure CCP 1-1.

SRO/ALL * (15) Checks RCS pressure stable or rising - (VB2)

(16) Isolates Charging Injection o Closes 8803A & B (VB2) o Closes 8801A & B (VB2)

SRO/ATC * (17) Establishes normal charging flow o (17.a) Opens HCV-142 to 20% (CC2)

SRO/BOP o (17.b) Opens 8107 and 8108, Norm Charging to Regen Hx Stop Valves (VB2).

o (17.c) Ensures 8146 OR 8147 - OPEN (VB2) o (17.d) Ensures 8145 AND 8148 - CLOSED SRO/ATC o (17.e) Throttles open FCV-128 to establish charging flow.

(18) Controls Charging Flow to Maintain PZR Level o (6.a) Adjusts FCV-128 charging flow and HCV-142 to maintain:

PZR Level - Stable, between 17% and 60%.

o Seal injection to each RCP between 8 and 13 gpm.

(19) Transitions to EOP E-1.1, SI Termination, Step 7.

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 1 Event No.: 9 Page 14 of 16 Event

Description:

SBLOCA after SI Termination in E-1.1 (CT)

Time Position Applicants Actions or Behavior (EOP E-1.1, SI Termination)

Note: Procedure is started on step 7 since first six steps are duplicated in last part of E-0, just prior to transition.

SBLOCA is triggered on shutdown on SI pump 1-2.

SRO/BOP * (7) Checks if SI pumps should be stopped o (7.a) Checks RCS Pressure -

Stable or rising Greater than 1650 psig No SI flow indications o (7.b) Stops both SI Pumps

(8) Checks if RHR pumps should be stopped o (8.a) Checks RHR pumps running with suction aligned to the RWST o (8.b) Shuts down both RHR pumps Note: Indications of SBLOCA may have been identified prior to reaching this step and addressed as Fold Out Page action.

ALL * (9) Ensures ECCS Flow Not Required o (9.a) Subcooling greater than 20oF o (9.b) PZR Level GREATER THAN 12%

ALL * (9.a RNO) Start ECCS Pps as necessary o (9.a.1.b RNO) Starts available SI Pumps (S1CT-2)**

o (9.a.1.c RNO) Starts one RHR pump o (9.a.2.a RNO) Open 8803A and 8803B o (9.a.2.b RNO) Open 8801A and 8801B o (9.a.2.c RNO) Close 8107 and 8108

- (Critical Task)(S1CT-2, Reinitiate SI before a severe challenge to the Core Cooling Critical Safety Function develops. Note: only 1 SI pump is required to meet the critical task.

Scenario may be terminated any time after Injection Flow has been re-established (completion of S1CT-2).

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 1 Event No.: 7 Page 15 of 16 Event

Description:

EOP E-0, Reactor Trip or Safety Injection, Appendix E, ESF Auto Actions, Secondary and Auxiliaries Status Time Position Applicants Actions or Behavior (EOP E-0, Appendix E)

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 (PK14-01 ON, output bkrs OPEN, CC3 right side)

(3 & 4) Verifies Phase A and Containment Vent Isolation complete (VB1, ESF status lights, red lights ON, white lights OFF);

(5) Verify ESF (SI) actuation complete BOP * (6) Verifies Feedwater isolation complete (F.W. Isolation and S.G. Level Portions of Monitor Light Box C: red lights ON, white light OFF.

BOP * (7) Determines Containment Spray and Phase B Isolation is NOT required (Contmt Isol, Phase B portion of Monitor Light Box D: red lights are OFF)

BOP * (8) Checks Main Steamline Isolation complete (Main Steam Isolation portion of Monitor Light Box D: red light OFF, white light are OFF)

BOP * (9) Checks AFW status o AFW Pp 1-2 and 1-3 both tripped o TDAFW IS required.

o Verifies min of 435 gpm flow (VB3 center) or S/G level > 15%

(continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 1 Event No.: 7 Page 16 of 16 Event

Description:

EOP E-0, Reactor Trip or Safety Injection, Appendix E, ESF Auto Actions, Secondary and Auxiliaries Status (cont)

Time Position Applicants Actions or Behavior (EOP E-0, Appendix E)

Note: CCP 1-1 has a sheared shaft and may still be running if not previously identified BOP * (10) Checks ECCS flows (charging injection (VB2 upper panel left), SI, RHR (both on VB1 upper panel) o Identifies low amperage on CCP 1-1 indicating a sheared shaft (VB2) o Shuts down CCP 1-1 (VB2)

(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) Checks excess letdown; notes NOT in service prior to trip

(13) Checks secondary systems (MFPs tripped (VB2, green lights ON), stops all but one CB Pp set, takes LCV-12 control switch to CONT ONLY.

(14) Verifies proper operation of Aux Bldg and Control Rm vent systems (VB4 vent status light panel white lights); turns on aux bldg vent charcoal filter preheater (VB4 lower panel, left side) and verifies containment iodine fans secured (VB4, lower panel),

BOP * (15) Verifies available DGs running normally (VB4, freq (60), volts (120), speed (900))

(16) Verifies vital batteries supplied by chargers (charger and bus volts on VB5, upper panel middle/lower area);

(17) Verifies MSRs reset (CC3 Triconex HMI)

(18) Throttles RCP seal injection flows to normal if needed (FCV-128, to 8-13 gpm each, CC2)

(19) Checks PK11-04 NOT IN (SFP alarm)

(20) Notifies Shift Foreman of completion.

(Board Operator will rejoin crew upon completion of Appendix or when called upon by Shift Foreman)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Attachment 1 - Scenario Set-up & Booth Actions X = manual entry required TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION X IC RESTORE 150 3% power BOL, CB - 1234 X Setup N/A Check 75 gpm letdown in service.

BOL Reactivity Handbook and Charts The Plant Abnormal Status Board for Surveillance Requirements FWPs on Long Recirc Copies of Procedures, Attachments; Appendixes; Foldout Pages; Annunciator OP L-3 (marked up), PK09-12, 11-17, AP-5, AP-15, AP-17, EOP E-0, E-1.1 Response Procedures and commonly used forms are in binders and NOT Marked up X 0 min Tools > Simple SBT Before crew takes the watch.

Use Simple SBT, Data Recorder File: sbt_sim.drb, min 960 iterations (30 sec).

Critical Task Specific Data Capture:

S2CT1: 8000B Position.

S2CT2: SI pump amps, discharge pressure, and suction pressure X 0 min Lesson L161 NRC-S1.lsn After SFM reports the crew has taken the watch, load session MALS, OVRs, etc. by FILE or MANUALLY (below)

X Evt-1: Raise Power Want power to reach at least 3.5% prior to next event so delta T is (approx. 3 min after adequate for subsequent failures such as Evt-4 (PT-507 failure).

taking watch per lead Monitor power for Mode transitions risk.

examiner)

X Evt-2: S/G Blowdown Aux Watch - When dispatched to check status of RE-23, wait 5-6 RM-23 fails high minutes, then report local panel indication is pegged high. No spings (Once once reactivity currently alarming in the area, however.

manipulation adequately observed, per the lead examiner)

X Evt-3: Centrifugal Record which pump is started (CCP 1-1 or 1-3).

Charging Pump 1-2 When dispatched to check pump (Aux Watch) and breaker:

OC Trip.

(Turbine Watch) report breaker 52-HG-09 tripped open; no (Once Evt-2 ECG has obvious cause.

been addressed, per * (Aux Watch) report smell of burnt insulation, hot to the lead examiner) touch.

X Evt-4: PT-507 Fails Expect call to I&C for failure.

High Note where OOS stickers are placed on Sim floor for clean-up (exam (Once Evt-3 TS have security).

been addressed, per lead examiner)

X Evt-5: MFP 1-1 trips. When dispatched to check AFW pumps (Aux Watch) and MFP and MDAFW pumps start breakers (Turbine Watch):

but trip (Once * (Turbine Watch) report:

temperature has o All stop valves indicate closed on pedestal; been stabilized, per verified locally as well.

lead examiner) o dropped flag on breaker 52-HH-08 (AFW 1-2) and tripped open o dropped flag on breaker 52-HF-09 (AFW 1-3) and tripped open

(Aux Watch) report no obvious cause on MDAFW pumps (cont on next page)

L162 NRC ES-D-2-01 r0.docx Page 17 of 20 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Attachment 1 - Scenario Set-up & Booth Actions (cont)

X = manual entry required A = activate from EVENT file TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Evt-6:S/G 1-1 Safeties Malfunction ramps in over 240 seconds to allow crew time to Lift Requiring Safety manually safety inject.

Injection (Once crew has reduced power, per lead examiner)

Evt-7: CCP 1-1 shaft If sent to locally investigate, report that pump is making loud, high-shear 30 seconds pitched whining noise.

after SI (post-EOP entry)

Evt-8:PCV-455C fails 30% open 60 seconds RECORD TIME AT WHICH 8000B is closed: _____________________

after SI (post-EOP entry)

Evt-9:SBLOCA after SI is terminated in E-1.1 RECORD TIME AT WHICH SI PUMPS ARE STARTED BY CREW PER E-1.1 (post-EOP entry)

Pump Time L162 NRC ES-D-2-01 r0.docx Page 18 of 20 Rev 0

Diablo Canyon Power Plant Operations Shift Log Unit 1 Unit 1 Days at Power: 0 Days Operating Mode: 2 Gross Generation: 0 MWe Power Level: 3% Net Generation: 0 MWe Today - Dayshift Shift Manager Turnover:

PRA RISK STATUS NEXT SHIFT: Green GRID STATUS NEXT SHIFT: Normal AVERAGE RCS CALCULATED LEAKRATE: 0.01 gpm CONDENSER INLEAKAGE: < 0.01 gpd CONDENSER D/Ps: NW 5.9 SW 6.4 NE 6.3 SE 6.1 PSID MAIN GENERATOR H2 USAGE: 325 scfd / 327 scfd 5 day ave SPENT FUEL POOL: Temp = 80oF; Time to 200oF = 30 hrs using actual temp (F-ID-7A)

NEW PRIORITY WORK:

None SHUTDOWN TECH SPECS / ECGS:

None ECG ACTIONS THAT IF COMPLETION TIME NOT MET ECG 0.3 IS ENTERED:

None TURNOVER ITEMS:

Reactor trip occurred 7 days ago.

The reactor was declared critical and power stabilized at 2% power late last shift.

CCP 1-2 is in service with 75 gpm letdown.

The unit is currently aligned to Startup.

MFP 1-1 is in service and supplying feedwater.

MFP 1-2 is in the process of being aligned and is unavailable at this time.

No one is in Containment.

PRIORITY ITEMS FOR NEXT SHIFT:

Continue with OP L-3, step 6.28, and raise power to approximately 8%.

Shift Foreman Turnover ANNUNCIATORS IN ALARM:

There are no unexpected alarms - all current alarms are consistent with current mode and power level.

TURNOVER ITEMS:

U-1: 3% and preparing to raise power to approximately 8%.

U-2: 100% power REACTIVITY MANAGEMENT:

Time in core life: _BOL_.

Power History: Previously at 100% for 17 days. Currently power level is approximately 3% following a reactor trip a week ago (MFP trip during maintenance).

Boron concentration is _1234 ppm_ from a sample taken 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago.

Control Rod Height: 136 steps on CBD.

CONDITIONAL SURVEILLANCES & INCREASED MONITORING:

None OTHER ABNORMAL PLANT STATUS

None

Appendix D (rev 11) Scenario Outline Form ES-D-1 Facility: Diablo Canyon (PWR) Scenario No: 2 Op-Test No: L162 NRC Examiners: Operators:

Initial Conditions: 50% with CCP 1-3 and MFP 1-1 OOS; CCP 1-2 IS; MOL, 1000 ppm boron Turnover: MFP 1-2 has elevated vibrations. ODM held earlier established action plan with ramping guidelines should conditions degrade.

Event Malf Event Event Description No No. Type* (See Summary for Narrative Detail) 1 GGACRL_94BTVSP 1 C, BOP Gen Voltage Regulator fails requiring manual voltage control on the base adjuster (PK14-22).

2 VLV_CVC16_2 .11 delay=15 ramp=3 TS, C CVCS-8152 fails to 90% closed requiring Excess Letdown to (ALL) be placed in service (PK04-21, AP-18) (TS 3.6.3.A).

3 MAL_SEI1 0.12 delay=0 ramp=15 C, TS Large seismic event causes rupture of RWST. (PK06-20, TS ASISRWST 1.6e6 delay=10 ramp=1800 only 3.5.4.B).

(SRO) 4 MAL_MFW2B 2.45 delay=0 ramp=60 C (ALL) Vibrations on MFP 1-2 rise to ODM limit, requiring predesignated Unit 1 shutdown at 6 MW/min. (AP-25).

5 MAL_SEI1 0.2 cd='bsisrwst lt 54.6' M DBA LOCA on aftershock.

delay=0 ramp=10 (ALL)

MAL_RCS1C 100%_DBA cd='bsisrwst lt 54.5' 6 MAL_PPL5A BOTH C ATWS (13D/E Work)

MAL_PPL5B BOTH (BOP) 7 MAL_PPL1A FAILURE_TO_INIT C Phase A Train A fails to actuate.

(BOP) 8 MAL_CNM3 100 cd='rsih8980 lt 0.02' C (ATC) Sump blockage.

delay=60 ramp=15

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor L162 NRC ES-D-1-02 r1.docx Page 1 of 4 Rev 1

Appendix D (rev 11) Scenario Outline 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 1,2,4,5,6,7,8) 7

2. Malfunctions after EOP entry (1-2) (Events 6,7,8) 3

3. Abnormal events (1-4) (Events 1,2,4) 3

4. Major transients (1-2) (Event 5) 1

5. EOPs entered/requiring substantive actions (1-2) (E-1, E-1.3, ECA-1.3) 3

6. EOP contingencies requiring substantive actions (0-2) (ECA-1.3) 1

7. Critical tasks (2-3)(See description below) 2 Critical Task Justification Reference (S2CT-1) Initiate reactor trip prior The safeguards systems that protect the plant during

Westinghouse Owners to performance of E-0, step 2. accidents are designed assuming that only decay heat and Group WCAP-17711-NP pump heat are being added to the RCS. Failure to manually

Calc G.2 Rev 5 (08151-trip the reactor causes a extreme challenge to the 2169) subcriticality critical safety function (red path on F-0.1

OP1.ID2, Time Critical subcriticality) beyond that irreparably introduced by the Operator Actions Rev 8A, postulated conditions. #34.

(S2CT-2) Stop all running ECCS Failure to stop the cavitating pumps leads to damage

Background Information pumps with suction aligned to the sufficient to render the pumps unavailable for use once an for Westinghouse Owners containment recirc sump by the alternate make-up supply is aligned to the RCS. Group Sump Blockage completion of ECA-1.3, step 5: Guideline, Rev 0.

CCP 1-1

CCP 1-2

SIP 1-1

SIP 1-2

RHRP 1-1

RHRP 1-2 Per NUREG-1021, Appendix D, if an operator or crew significantly deviates from or fails to follow procedures that affect the maintenance of basic safety functions, those actions may form the basis of a CT identified in the post-scenario review.

L162 NRC ES-D-1-02 r1.docx Page 2 of 4 Rev 1

SCENARIO

SUMMARY

- NRC #2

1. Generator Voltage Regulator trips due to a loss of sensing voltage. The crew responds by entering AR PK14-22, GENERATOR VLTG REG TRIP and determine the voltage regulator is now operating in manual mode. Annunciator guidance is followed to maintain a lagging power factor.

2. Letdown Hx Inlet Valve, CVCS-8152 fails 90% closed causing letdown to divert to the Pressurizer Relief Tank. AR PK04-21, LETDOWN PRESS / FLOW TEMP comes into alarm, directing the crew to isolate Normal Letdown and place Excess Letdown in service per OP B-1A:IV, CVCS - Excess Letdown - Place In Service and Remove From Service. Alternately, the crew may elect to enter OP AP-18, Letdown Line Failure, which provides equivalent guidance. Shift Foreman enters TS 3.6.3.A - Containment Isolation Valves, for one containment isolation valve inoperable.

3. A 0.12 g seismic event results in a rupture of RWST, causing level to lower rapidly. The crew identifies RWST level lowering by monitoring level indications on VB-2 or by evaluating AR PK06-20, PPC Select which identifies RWST level is below the alarm setpoint. Field operators report a crack in the RWST extending down to approximately the 50% level. The Shift Foreman enters TS 3.5.4.B - Refueling Water Storage Tank (RWST) for borated water volume less than the required minimum of 455,300 gallons

(~94%).

4. Vibrations on MFP 1-2 rise to 2.5 mil which corresponds to a ODM limit, requiring predesignated Unit 1 shutdown at 6 MW/min. A ramp is commenced following the guidance of OP AP-25, Rapid Load Reduction or Shutdown.

5. A 0.20 g seismic aftershock results in 100% DBA LOCA.

6. The crew enters E-0, Reactor Trip or Safety Injection, performing their immediate actions. A reactor trip fails to automatically actuate (ATWS); manual Rx Trip control switches are ineffective as well. Control board operators perform their respective response actions: ATC drives control rods inward and BOP manually opens control rod breakers 13D/E on VB5 (S2CT-1) Initiate reactor trip prior to performance of E-0, step 2).

7. With the reactor tripped, the crew continues on, checking for actuation of emergency safeguards equipment and diagnosing conditions consistent with a large break LOCA (high containment pressure, loss of pressurizer pressure and level, loss of subcooling, high containment sump levels). The crew identifies RCP trip criteria are met, and with Shift Foreman concurrence, trip all four RCPs. Shift Foreman directs the BOP Operator to complete Appendix E, ESF AUTO ACTIONS, SECONDARY AND AUXILIARIES STATUS, and continues on in E-0. Train A of Phase A, Containment Isolation, fails to actuate, requiring board operators to manually align the associated inside containment isolation valves.

(continued on next page)

L162 NRC ES-D-1-02 r1.docx Page 3 of 4 Rev 1

SCENARIO

SUMMARY

- NRC #2

8. The Shift Foreman continues through E-0 diagnostic steps, and transitions to E-1, Loss of Reactor or Secondary Coolant. Functional restoration status trees are checked and crew identifies transition criteria for FR-P.1, Response to Imminent Pressurized Thermal Shock. Conditions will be met for exiting the procedure at the first step.

When RWST level reaches 33%, the crew transitions immediately to E-1.3, Transfer to Cold Leg Recirculation, and performs the required alignment steps. When RWST suction valve SI-8980 is isolated, ECCS recirculation flow is lost due to sump blockage. The crew transitions to ECA-1.3, Sump Blockage either directly, or by way of ECA-1.1, Loss of Emergency Coolant Recirculation, where they secure all running ECCS pumps (S2CT-2, Stop all running ECCS pumps with suction aligned to the containment recirc sump by the completion of ECA-1.3, step 5).

The scenario is terminated once Critical Task S2CT-2 is complete.

L162 NRC ES-D-1-02 r1.docx Page 4 of 4 Rev 1

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 2 Event No.: 1 Page 1 of 19 Event

Description:

Generator Voltage Regulator Trip Time Position Applicants Actions or Behavior Note: Procedure step numbers are included at the front of each action/comment in parenthesis, where applicable.

ALL Diagnosis made by using one or more of the following:

PK014-22, GENERATOR VLTG REG TRIP, in alarm

Main Gen Auto Voltage Regulator Mode Selector light indicating "TEST" SRO Implements PK014-22, GENERATOR VLTG REG TRIP (PK14-22, GENERATOR VLTG REG TRIP)

SRO/ATC * (2.1.1-2.1.3) Reads input 830 and determines only the voltage regulator tripped.

o Notes that Main Gen Auto Voltage Regulator Mode Selector light has changed state from AUTO (red) to TEST (amber).

o Determines Main Generator Voltage Regulator has failed to manual.

SRO Reads NOTE regarding need to use Main Generator Manual Voltage Base Adjuster for voltage changes once the Main Gen Auto Vltg Reg Mode Sel switch is placed in "OFF" (next step).

SRO/BOP * (2.1.3.a) Places the Main Gen Auto Vltg Reg Mode Sel switch in "OFF" (CC3).

(2.1.3.b) Places the Supplementary Excitation (Power System Stabilizer) control switch in "OFF" (CC3).

SRO * (2.1.3.c) Directs board operator to maintain a lagging power factor while on the Main Generator Manual Voltage Base Adjuster.

SRO/BOP * (2.1.3.d) Contacts Turbine Watch to check the exciter control panel for the cause of the voltage regulator trip (dropped flag).

(2.1.3.e) Requests SM Contact maintenance.

Proceed to the next event once PK actions complete, per the lead examiner.

- Critical Task L162 NRC ES-D-2-02 r0.docx Page 1 of 23 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 2 Event No.: 2 Page 2 of 19 Event

Description:

Letdown Hx Inlet Valve, CVCS-8152 fails 90% closed Time Position Applicants Actions or Behavior Note: The crew may address the malfunction using only PK04-21, or may elect to enter OP AP-18, Letdown Line Failure, which provides equivalent guidance. Both procedure flowpaths are described below.

ALL Diagnosis made by using one or more of the following:

AR PK04-21, LETDOWN PRESS / FLOW TEMP in alarm

Letdown flow lowering slightly (VB2)

Letdown RV temperature elevated (VB2)

Position lights for Letdown Hx Inlet Valve, CVCS-8152, indicating mid stroke (both red and green lights illuminated)

SRO AR PK04-21, LETDOWN PRESS / FLOW TEMP in alarm (AR PK04-21, LETDOWN PRESS / FLOW TEMP)(N/A if not used)

SRO/ATC * (1) Reads input 320 and determines failure is from 8152 going partially closed, goes to section 2.1 for General Actions SRO * (2.1.1) Notes need to direct Chemistry to isolate argon injection if letdown is isolated.

Note: The SFM may elect to treat letdown passing through letdown RV valve 8117 as a letdown leak.

SRO * (2.1.2) Notes reduced letdown flow, elevated temperature on letdown RV-8117, and mid-position indication on letdown Hx inlet valve CVCS-8152.

May transition to OP AP-18, Letdown Line Failure. (see Page 3)

SRO * (2.1.3-2.1.7) Determines steps are N/A.

(continued on next page)

- Critical Task L162 NRC ES-D-2-02 r0.docx Page 2 of 23 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 2 Event No.: 2 Page 3 of 19 Event

Description:

Letdown Hx Inlet Valve, CVCS-8152 fails 90% closed (cont)

Time Position Applicants Actions or Behavior SRO/BOP * (2.1.8) Determines RV-8117, letdown to the PRT has lifted o (2.1.8.a) Directs BOP to monitor PRT pressure, level and temperature. (VB2) o (2.1.8.b) Notes need to reset RV-8117 when plant conditions permit o (2.1.8.c,d) Determines RV-8117 leakrate to PRT is greater than 0.1 gpm References Tech Specs and enters Tech Spec 3.6.3.A - Containment Isolation Valves for one or more penetration flow paths with one containment isolation valve inoperable. Required actions: isolate the affected penetration flow path within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Closes CVCS-8149C, 75 gpm Ltdn Orifice Stop valve Determines CVCS-8152 can NOT be closed from the Control Room (VB2)

SRO/BOP * (2.1.9.a) Determines normal letdown can NOT be maintained and ensures letdown is isolated by checking the following valves CLOSED:

o CVCS-8149A, 45 gpm Ltdn Orifice Stop (VB2) o CVCS-8149B, 75 gpm Ltdn Orifice Stop (VB2) o CVCS-8149C, 75 gpm Ltdn Orifice Stop (VB2) o CVCS-HCV-133, Ltdn from RHR HX Out (VB2) o Establish Excess Letdown (see next page), per OP B1A:IV, CVCS - Excess Letdown - Place In Service and Remove From Service (OP AP-18, Letdown Line Failure (if used))

SRO/ATC * (1) Ensures no load changes are in progress.

SRO/BOP * (2) Isolates letdown o Ensures Letdown Orifice Stop Valve, 8149C Closed (VB2) o Closes Regen Heat Exchanger Inlet Valves, LCV-459 and 460 (VB2) o Verifies RHR to Letdown Flow Control Valve, HCV133 (RHR Ltdn) closed (VB2)

(continued on next page)

- Critical Task L162 NRC ES-D-2-02 r0.docx Page 3 of 23 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 2 Event No.: 2 Page 4 of 19 Event

Description:

Letdown Hx Inlet Valve, CVCS-8152 fails 90% closed (cont)

Time Position Applicants Actions or Behavior (OP AP-18, Letdown Line Failure, cont)

SRO/ATC * (3) Checks for RCS Leakage - verifies that Pzr level and RCS press are both stable/rising (there was never an indication of leakage) (VB2, CC2, PPC)

(4) Reduces charging to minimum (RCP seals only), using FCV128 (or HC459D) and HCV142 (approx. 8 gpm on RCP seals, with HCV142 closed (or near closed) (CC2).

SRO/BOP * (5) Establish Excess Letdown (see below), per OP B1A:IV, CVCS - Excess Letdown -

Place In Service and Remove From Service

(6) Contacts RP and Chemistry regarding Excess Letdown being placed in service (OP B1A:IV, CVCS - Excess Letdown - Place In Service and Remove From Service)

ATC * (6.1.1) Verifies charging at minimum (seals only)

BOP * (6.1.2) Contacts RP for rad conditions/posting Note: If Shift Manager asked in regard to flushing or crew attempts to perform flush, provide the following cue:

CUE: Excess letdown line flushing is NOT needed.

BOP * (6.1.3) Skips line flush, moves on to next step

(6.1.4) Opens FCV-361, CCW to Excess Ltdn HX (VB1)

(6.1.5) Verifies pot for HCV-123, Excess Letdown Pressure Control, CLOSED (at 0) (VB2)

(6.1.6) Opens 8166/8167, Excess Letdown isolation valves (VB2)

(6.1.7) is N/A

(6.1.8) Slowly opens HCV-123 to establish excess letdown (VB2)

(6.1.9) Adjusts HCV-123 to provide approximately 40 gpm letdown at NOP ATC/BOP * (to end of scenario) HCV-123 and FCV-128 (or HC-459D) are now used to control Pzr Level Proceed to the next event once Excess Letdown established and Tech Specs addressed, per the lead examiner.

- Critical Task L162 NRC ES-D-2-02 r0.docx Page 4 of 23 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 2 Event No.: 3 Page 5 of 19 Event

Description:

RWST Rupture from Seismic Event Time Position Applicants Actions or Behavior ALL

Earthquake is diagnosed from one or more of the following:

PK15-24, Seismic Instrument System (actuated on triggers).

Physical shaking and noise from the earthquake.

Various tank alarms going in and out (due to water shifting from earthquake, programmed into simulator modeling).

ATC/BOP

During board walkdown and/or review of tank alarms coming in/out, RWST level is diagnosed as dropping from review of actual levels (VB2, far left, top) and/or PK06-20 (PPC Select alarm, with low RWST level required to be assigned)

Note: As part of post-seismic event walkdown duties, Aux Watch would identify RWST water at the 140' level, outside Containment. If Control Room has not directed Aux Watch to investigate, call will be made to Control Room to report the problem 5 minutes after the initiating event.

SRO

Implements Tech Spec 3.5.4.B, (1 hr to restore, which is not possible; otherwise S/D and cooldown is required)

References Tech Specs and enters Tech Spec 3.5.4.B - Refueling Water Storage Tank (RWST) for borated water volume less than the required minimum (equivalent level 94.5%). Required action is to restore to minimum level within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (continued on next page)

- Critical Task L162 NRC ES-D-2-02 r0.docx Page 5 of 23 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 2 Event No.: 4 Page 6 of 19 Event

Description:

Rising MFP 1-2 Vibrations Time Position Applicants Actions or Behavior Note: As noted in Turnover, System Engineer is actively evaluating MFP 1-2 vibrations. If Control Room has not identified increased level by the time Tech Specs addressed (above), call from field will be made to Control Room requesting data.

BOP

During board walkdown notes vibration levels on MFP 1-2 have increased to 2.5 mil which corresponds to an ODM threshold for a 6 MW/min ramp SRO

Implements OP AP-25, Rapid Load Reduction SRO * (1a) 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 (1b) MW and IMP feedbacks are placed in service (all on Triconex turbine HMI, CC3) o (1c) 60 MWe load target is entered into Triconex HMI o (1d) Sets ramp rate to 6 mw/min o (1e) Pushes GO SRO/ATC * (2) Verifies that control rods are inserting properly in AUTO (VB2)

SRO/ATC * (3) Verifies ON all pressurizer backup heaters (CC1)

SRO/ATC * (4) Verifies charging flow adequate to prevent letdown flashing: may take manual control of Pzr level o Places HC-459D (master level controller) or FCV-128 (charging flow controller) in manual (CC2) o Keeps charging high enough to prevent letdown from flashing (VB2)

(continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 2 Event No.: 4 Page 7 of 19 Event

Description:

Rising MFP 1-2 Vibrations (cont)

Time Position Applicants Actions or Behavior (OP AP-25, Rapid Load Reduction (cont))

SRO/BOP * (5) Verifies DFWCS in AUTO and controlling S/G levels (CC3 MFW HMI, VB3, PPC) o Checks MFW control and bypass valves in AUTO o Checks both MFPs and their controller in AUTO o May check level trends, as well as steam flow/feed flow trends (CC3, PPC, and/or big VB3 DFWCS electronic recorders)

Note: Boration values described below are representative of the conditions given, but will vary based on the actual ramp rate and target specified by SRO.

SRO/ATC * (6) Performs boration (the following guidance is on the boration checklist in the reactivity handbook) o Presses STOP on M/U Ctrlr HMI (CC2) o Presses BORATE on HMI o Sets target gallons for boration (as decided above, and per the Shift Foreman);

verifies batch is reset o Sets boric acid flowrate o Presses START, and monitors boration o Once stopped, either returns to AUTO (presses AUTO, then START), or performs additional boration per the Shift Foreman SRO

The Shift Foreman provides reactivity oversight for the ramp SRO/BOP * (7) Checks MFP suction pressure greater than 260 psig (VB3)

SRO/ATC * (8) Checks Tavg trending to Tref (PPC, CC1)

(9) Checks Pressurizer pressure and level trending to programmed band (PPC, CC2)

Next event triggered as soon as ramp commenced, per Lead Examiner

- Critical Task L162 NRC ES-D-2-02 r0.docx Page 7 of 23 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 2 Event No.: 5,6 Page 8 of 19 Event

Description:

Seismically Induced Large Break LOCA ATWS Time Position Applicants Actions or Behavior Phase B actuation is time 0 for TCOA to trip the RCPs within 5 minutes of meeting RCP trip criteria in EOP network. (Red Phase B lights will illuminate under PK01 Annunciator Panel).

Record Start Time: _______________

ALL LOCA is diagnosed from one or more of the following:

Sudden loss of Pressurizer level coincident with loss of subcooling and RCS pressure approaching atmospheric

Numerous AR PKs coming into alarm associated with sump levels and containment environment ATWS is diagnosed from one or more of the following:

AR PK04-11 and PK04-12, REACTOR TRIP INITIATE in alarm

AR PK04-14, REACTOR TRIP ACTUATED NOT in alarm

DRPI indication of rods NOT inserted

Reactor Trip Breakers closed (red light on)

SRO

Directs/performs manual Reactor Trip followed by manual Safety Injection once Reactor Trip has been verified.

Implements EOP E-0, Reactor Trip or Safety Injection (EOP E-0, Reactor Trip or Safety Injection)

Note: Attempts to manually trip the reactor may be done prior to entry into EOP E-0 or as part of E-0, 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 ATC/BOP * (1 RNO) May attempt trip using manual switch (CC1 or VB2)

(continued on next page)

- Critical Task L162 NRC ES-D-2-02 r0.docx Page 8 of 23 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L161-NRC Scenario No.: 2 Event No.: 5,6 Page 9 of 19 Event

Description:

Seismically Induced Large Break LOCA (cont)

ATWS (cont) (CT)

Time Position Applicants Actions or Behavior (EOP E-0, Reactor Trip or Safety Injection(cont))

SRO/BOP * (1 RNO) 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 which causes breakers to open (S2CT-1)**

o Dispatches operator to open reactor trip breakers locally

- (Critical Task)(S2CT-1) Initiate reactor trip prior to performance of E-0, step 2.

SRO/ATC * (2) Verifies turbine trip (stop valves closed) (CC3 HMI or VB2 RPS indicator lamps).

SRO/BOP * (3) Checks vital 4kv buses (VB4)

SRO/ATC * (4) Checks if SI actuated (PK08-21 ON, also checks VB1 red train lights and/or train equipment to verify both trains actuated) (VB1 upper right, or CC2 right)

SRO * (5) Directs App E implemented (usually to BOP)(see page 18) o

(6) Checks RCS temperature stable or lowering to 547 F o Notes temperature has dropped significantly due to LBLOCA,(VB2) o May throttle AFW to minimum, but recognizes low temperature is due to LOCA

(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 )

PORVs closed and associated block valves open (VB2) o Pzr Sprays closed (green lights on) (CC2)

(continued on next page)

- Critical Task L162 NRC ES-D-2-02 r0.docx Page 9 of 23 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 2 Event No.: 5 Page 10 of 19 Event

Description:

Seismically Induced Large Break LOCA (cont)

Time Position Applicants Actions or Behavior (EOP E-0, Reactor Trip or Safety Injection, continued)

SRO/ATC * (8) Checks RCP trip criteria; o Ensures all RCPs are tripped (VB2) (TCOA)*

o Action to trip RCPs may have already been completed as part of Foldout Page items 2.0 or 3.0 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 o Checks RE-71/72/73/74 and RE-15/19 recorders onVB2 (and PPC); (all normal) o PK11-06/17/18 (all OFF) o May request samples SRO/ALL * (11) Checks RCS intact (it is not) (note: only one valid abnormal reading needed to transition from E-0)

(11a) Determines containment pressure is NOT normal (VB1 meters, PPC)

(11b) Determines containment sump levels NOT normal (VB1 meters, PAMS)

(11c) Determines containment radiation is NOT normal (RM-11, 02, 07 are all in alarm)

(11 RNO) Places 2nd ASW/CCW HX in service (opens FCV-603 and FCV-431, VB1 far left), and transitions to EOP E-1, Loss of Reactor or Secondary Coolant SRO

Performs procedure transition brief for E-1, and implements CSFST (if required)

(TCOA) #67 - Trip RCPs within 5 minutes of meeting RCP trip criteria in EOP network.

(continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 2 Event No.: 5 Page 11 of 19 Event

Description:

Seismically Induced Large Break LOCA (cont)

Time Position Applicants Actions or Behavior Note: A CSFST RED or MAGENTA path may occur prior to EOP E-1 entry or before the end of the scenario (FR-P.1 on PTS); If it occurs, it will be a short entry (perform a single step and exit)

SRO Implements FR-P.1, Imminent PTS (if RED or MAGENTA path occurs)

(ONLY IF FR-P.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 E-1, Loss of Reactor or Secondary Coolant (EOP E-1, Loss of Reactor or Secondary Coolant)

SRO/ATC * (1) Checks RCPs tripped (already done, VB2)

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 RE-71/72/73/74 and RE-15/19 recorders on VB2 (and PPC; no upward trends or spikes, unless containment shine is noted), and PK11-06/17/18 (alarms not in); requests chemistry to sample S/Gs for activity (as follows, if done):

o Verifies phase A containment isolation reset (VB1) o Opens FCV-584 (air to containment) (VB4, lower left) o Opens blowdown isolation valves inside containment (FCV-760, 761, 762, 763) if requested for sampling SRO/BOP * (4) Maintains S/G levels 25-65%

(5) Re-verifies PORVs closed and associated block valves open (VB2 - upper panel, far SRO/BOP right)

(continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 2 Event No.: 5 Page 12 of 19 Event

Description:

Seismically Induced Large Break LOCA (cont)

Time Position Applicants Actions or Behavior (EOP E-1, Loss of Reactor or Secondary Coolant)

SRO/ATC * (6) Determines Containment Spray should remain in service o (a) PK01-18 is ON o (b) Checks if Spray Additive Tank Level is less than 16% (VB1, to right of Cont Press/Temp display)

Assigns continuous action to monitor level, and isolate tank when level falls below 16% by performing the following (step 6c):

Reset both trains of Containment Spray (VB1, middle)

Close 8994A and 8994B Dispatch operator to open breakers for 8994A/B (VB1, middle skirt)

(7)Containment radiation levels are above normal (PK11-21 is ON, RE-2/RE-7 in alarm)

(b RNO) Verifies spray system still in service (VB1, middle skirt)

SRO * (8) Determines ECCS flow should NOT be reduced o (a) RCS subcooling is less than 20oF (SCMM YI-31, lower center VB2)

SRO/ATC

Reads CAUTION regarding running RHR pump with cooling to associated heat exchanger

(9) 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 11 SRO/ATC * (11) Checks if Diesel Generators should be stopped o Checks Vital 4kV buses powered from Off-Site (they are) o Resets SI o Stops all D/Gs and places respective control switch in AUTO (continued on next page)

- Critical Task L162 NRC ES-D-2-02 r0.docx Page 12 of 23 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 2 Event No.: 5 Page 13 of 19 Event

Description:

Seismically Induced Large Break LOCA (cont)

Time Position Applicants Actions or Behavior (EOP E-1, Loss of Reactor or Secondary Coolant)

SRO/ALL * (12) Evaluates Plant Status o (a) Verifies cold leg recirculation capability - notes power available to both RHR pumps o (b) Checks Aux building radiation monitor - all are Normal o (c) Checks if RHR pumps are on recirculation - they are 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 * (13) 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)

ALL * (Note) (If step 13 is reached prior to 33% in the RWST) The crew will preview EOP E-1.3 ATC * (14) When RWST level of 33% is reached, RHR Pps are verified STOPPED; o Transitions to EOP E-1.3, Transfer to Cold Leg Recirculation (continued on next page)

- Critical Task L162 NRC ES-D-2-02 r0.docx Page 13 of 23 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 2 Event No.: 5 Page 14 of 19 Event

Description:

E-1.3, Cold Leg Recirc Alignment (TCOA)

Time Position Applicants Actions or Behavior (EOP E-1.3, Transfer to Cold Leg Recirculation)

At 33% in RWST is time 0 for TCOA to complete transition to cold leg recirc in 10 minutes (PK03-01 will also alarm).

Record Start Time: _______________

Note: Due to the time critical nature of this procedure, the SFM will assign App EE to a Reactor Operator and continue on through the main procedure body with the remaining Operator.

SRO * (1) Implement Appendix EE BOP * (1) App EE assigned/performed:

(App EE, 1) All (6) series contactor switches are cut in (VB2, upper panel)

(App EE, 2, 3) Verifies reset of SI and both trains of Phase A and Phase B (VB1, upper panel)

(App EE, 4) Ensures ASW/CCW is aligned to 2 ASW Pumps through 2 heat exchanges (2 CCW HXs are in service, VB1, far left)

(App EE, 5) Places RHR HX 1-2 in service

Opens outlet valve, FCV-364 (VB1, far right)

(App EE, 6) Places RHR HX 1-1 in service

Opens outlet valve FCV-365 (VB1, far right)

(App EE, 7 & 8) Verifies CCP 1-3 stopped (VB2); makes PA announcement concerning Cold Leg Recirc

(App EE, 9) Dispatches operators to rack in breakers for 8980 and 8976.

SRO/ATC * (2, 3) Verifies RHR Pp 1-2 stopped and closes 8700B (VB1, lower right)

(4, 5) Verifies RHR Pp 1-1 stopped and closes 8700A (VB1, lower right)

(6) Closes RHR crosstie valves 8716 A/B (VB1, lower center)

(7) Isolates ECCS Pp recirc paths by closing 8974 A/B, and closing 8105 / 8106 (VB2)

(8) Verifies recirc sump level > 92 ft ( VB1 upper right side)

(TCOA) #8 - Transfer to cold leg recirculation within 10 minutes after RWST reaches low level setpoint.

(continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 2 Event No.: 5 Page 15 of 19 Event

Description:

E-1.3, Cold Leg Recirc Alignment (cont) (TCOA)

Time Position Applicants Actions or Behavior (EOP E-1.3, Transfer to Cold Leg Recirculation)

Note: TCOA completion time is associated with completing alignment of first train of ECCS; it is not necessary to record completion time for second train.

SRO/ATC * (9) Places RHR Pump 1-2 in Cold Leg Recirc Alignment o 9.a Checks RHR Pp 1-2 stopped and 8700B closed o 9.b Opens recirc suction valve 8982B (VB1, lower right) o 9.c Ensures RHR Hx 1-2 in service per Appendix EE (VB1, lower right) o 9.d Starts RHR Pp 1-2 (verifies flows, amps) (both on VB1, lower right) o 9.e Opens crosstie 8804B (VB1, lower center) o 9.f-h Verifies SI Pps running and RHR Pp amps w/i limits

(10) Crossties SI Pump Suction to Charging Pump Suction o 10.a Opens crossties 8807A and/or 8807B (VB1, lower center)

(TCOA completion time ___________)

o 10.b Verifies CCP 1-1 and 1-2 running SRO/ATC * (11) Places RHR Pump 1-1 in Cold Leg Recirc Alignment o 11a Checks RHR Pp 1-1 stopped and 8700A Closed o 11.b Opens recirc suction valve 8982A (VB1, lower right) o 11.c Ensures RHR Hx 1-1 is in service per Appendix EE (VB1, lower right) o 11.d Starts RHR Pp 1-1 (verifies flows, amps) (both on VB1, lower right) o 11.e Opens crosstie 8804A (VB1, lower center) o 11.f-h Verifies SI Pps running and RHR Pp amps w/i limits SRO/ATC * (12) Observes one train of RHR train is now in cold leg recirc lineup Note: Closing SI-8980 triggers sump blockage malfunction event. Fold Out Page, Item 3 directs transition to a contingency procedure (ECA-1.1 or 1-3) for a loss of emergency coolant recirculation, depending on the cause.

ATC * (13) Closes normal ECCS pump suction valves: 8805 A/B, 8976, and 8980 (continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 2 Event No.: 5 Page 16 of 19 Event

Description:

E-1.3, Cold Leg Recirc Alignment (cont)

Time Position Applicants Actions or Behavior (EOP E-1.3, Transfer to Cold Leg Recirculation)

Note: ECCS pump cavitation will become evident almost immediately. The crew will transition to ECA-1.3, Sump Blockage Guideline as a result. Transition to ECA-1.1 is also possible, and the crew will be directed to ECA-1.3 after performing additional diagnostics.

SRO/ATC * (14) Checks both RHR Pumps running in Cold Leg Recirc Alignment SRO/BOP * (15) Checks if Containment Spray Additive Tank should be isolated o 15.a Observes PK01-18, CONTAINMENT SPRAY ACTUATED is on.

o 15.b Determines Spray Additive Tank level is greater than 16% and isolation is not required at this time (VB1)

SRO/ATC * (16) Checks if Containment Spray Alignment from RHR System is required o 16.a Determines RWST level is NOT less 4%, continues to step 17 to reduce RHR flow (VB1)

Note: The crew transition to address a loss of injection flow is expected by this point, with ECA-1.3, Sump Blockage Guideline, the most probable path. See next page. If crew transitioned to ECA-1.1, Loss of Emergency Coolant Recirculation, they will be redirected to ECA-1.3 on the first step.

(continued on next page)

- Critical Task L162 NRC ES-D-2-02 r0.docx Page 16 of 23 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 2 Event No.: 8 Page 17 of 19 Event

Description:

ECA-1.3, Sump Blockage Guideline (CT)

Time Position Applicants Actions or Behavior (ECA-1.3, Sump Blockage Guideline)

SRO

Reads caution that any pump receiving suction from a RHR pump should be stopped before stopping the RHR pump.

Reads caution that If any ECCS pump loses suction or shows indication of cavitation, the pump should be stopped.

Reads note that CSF Status Trees should be monitored for information only

Reads note that Indications of cavitation or sump level change should be monitored following any change of recirculation flow.

Note: The following step assumes ECCS pumps are still operating. SRO should follow the RNO column if the RHR pumps have been shutdown due to evidence of cavitation.

SRO/ATC * (1) Checks RHR pumps for indications of cavitation

(1 RNO 1) Verifies containment spray from RHR is secured by checking 9003A and 9003B closed (VB1)

(1 RNO 2) Reduces RHR flow by throttling RHR Hx Inlet Flow Control Valves, HCV-637 and HCV-638 (VB1)

(1 RNO 3) Determines throttling flow is ineffective and secures ECCS Pumps taking suction from RHR:

o CCP 1-1 **

o CCP 1-2**

o SIP 1-1**

o SIP 1-2**

(1 RNO 4) Determines cavitation CANNOT be prevented and secures RHR pumps:

o RHR 1-1**

o RHR 1-2**

- (Critical Task) (S2CT-2, Stop all running ECCS pumps with suction aligned to the containment recirc sump by the completion of ECA-1.3, step 5).

Scenario may be terminated any time after running CCPs, SIPs, and RHRPs have shutdown (completion of S2CT-2)

- Critical Task L162 NRC ES-D-2-02 r0.docx Page 17 of 23 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 2 Event No.: 7 Page 18 of 19 Event

Description:

EOP E-0, Reactor Trip or Safety Injection, Appendix E, ESF Auto Actions, Secondary and Auxiliaries Status Phase A Train A fails to actuate Time Position Applicants Actions or Behavior (EOP E-0, Appendix E)

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 (PK14-01 ON, output bkrs OPEN, CC3 right side)

(3 & 4) Verifies Phase A and Containment Vent Isolation complete (VB1, ESF status lights, red lights ON, white lights OFF) o Determines Phase A, Train A (inside containment)did not actuate and performs manual isolation of the following valves:

9355A 9356A CVCS-8112, Seal Water Return FCV-253, 255, 258, 500 - Rad Waste Isolation

(5) Verify ESF (SI) actuation complete; manual alignment of Train B pumps and valves will be required.

BOP * (6) Verifies Feedwater isolation complete (F.W. Isolation and S.G. Level Portions of Monitor Light Box C: red lights ON, white light OFF.

BOP * (7) Verifies Containment Spray and Phase B Isolation (Contmt Isol, Phase B portion of Monitor Light Box D: red lights are ON)

BOP * (8) Checks Main Steamline Isolation complete (Main Steam Isolation portion of Monitor Light Box D: red light ON, white light are OFF)

BOP * (9) Checks AFW status o AFW Pp 1-2 and 1-3 both running; TDAFW is NOT required.

o Verifies min of 435 gpm flow (VB3 center) or S/G level > 15%

(continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 2 Event No.: 7 Page 19 of 19 Event

Description:

EOP E-0, Reactor Trip or Safety Injection, Appendix E, ESF Auto Actions, Secondary and Auxiliaries Status (cont)

Phase A Train A fails to actuate Time Position Applicants Actions or Behavior (EOP E-0, Appendix E)

BOP * (10) Checks 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 (Shift Foreman may direct operator to continue on in Appendix E, or redirect to higher priority tasks)

BOP * (12) Checks excess letdown in service prior to trip o Closes EXCESS LTDN, CVCS- 8166 and 8167

(13) Checks secondary systems (MFPs tripped (VB2, green lights ON), stops all but one CB Pp set, takes LCV-12 control switch to CONT ONLY.

(14) Verifies proper operation of Aux Bldg and Control Rm vent systems (VB4 vent status light panel white lights); turns on aux bldg vent charcoal filter preheater (VB4 lower panel, left side) and verifies containment iodine fans secured (VB4, lower panel),

BOP * (15) Verifies available DGs running normally (VB4, freq (60), volts (120), speed (900))

(16) Verifies vital batteries supplied by chargers (charger and bus volts on VB5, upper panel middle/lower area);

(17) Verifies MSRs reset (CC3 Triconex HMI)

(18) Throttles RCP seal injection flows to normal if needed (FCV-128, to 8-13 gpm each, CC2)

(19) Checks PK11-04 NOT IN (SFP alarm)

(20) Notifies Shift Foreman of completion.

(Board Operator will rejoin crew upon completion of Appendix or when called upon by Shift Foreman)

- Critical Task L162 NRC ES-D-2-02 r0.docx Page 19 of 23 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Attachment 1 - Scenario Set-up & Booth Actions X = manual entry required TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION X IC RESTORE 151 50% power MOL, CB - 1000 (MOL)

X Setup N/A CCP 1-3 & MFP 1-1 OOS; Caution Tags MFP 1-2 Elevated Vibrations (verify ~ 1.3 mils); clear vibration alarms on VB4 Verify PPC Select setup for RWST Level Low The Plant Abnormal Status Board for Surveillance Requirements Excess Ltdn Last in Service 3 days ago; CB - 1025 ppm Copies of Procedures, Attachments; Appendixes; Foldout Pages; OP B-1A:IV, PK04-21, PK06-20, PK14-22, AP-18, AP-25, EOP E-0, E-1, E-1.3, ECA-1.1, ECA-1.3 Annunciator Response Procedures and commonly used forms are in binders and NOT Marked up X 0 min Tools > Simple SBT Before crew takes the watch.

Use Simple SBT, Data Recorder File: sbt_sim.drb, min 960 iterations (30 sec).

Critical Task Specific Data Capture:

S2CT1: 13D and 13E Breaker Position.

S2CT2: RHR, SI, and Charging pump amps, discharge pressure, and suction pressure; SI-8980 position.

X 0 min Lesson L162 NRC-S2.lsn After SFM reports the crew has taken the watch, load session MALS, OVRs, etc. by FILE or MANUALLY (below)

X Evt-1:Gen Voltage Will automatically fail to manual. When dispatched (Turbine Watch) report back Regulator failure There is a dropped flag at the panel but can't tell what it is for; will have to get (approx. 3 min after assistance from Electrical Maintenance.

taking watch per lead examiner)

X Evt-2:CVCS-8152 90% Will contact RP for postings associated w/Excess Ltdn placed in service. Verify closed crew isolates flowpath once App E is entered.

(Once SFM exits PK When Aux Watch contacted, regarding level in RCDT, report approximately 20%

for Evt-1, per lead level.

examiner)

X Evt-3:Seismic/RWST If not yet dispatched, call C/R 5 minutes after seismic as part of Aux Bldg rupture(Once Evt-2 walkdown and report water is flooding the 115 back yard area due to a crack in TS have been the RWST at the mid-way (50%) point.

addressed, per lead examiner)

Evt-4:Seismic/RWST If contacted to verify vibrations on MFP 1-2, use Instructor Console to report rupture/MFP 1-2 values.

elevated vibs (Once Evt-2 TS have been addressed, per lead examiner)

X Evt-5: 100% DBA Note: Trigger point is set to ensure adequate break flow to fill recirc sump to 92 ft.

LOCA (Triggered on RWST Level adequate to stay in E-1.3)

X Evt-6: ATWS (13D/E Critical Task to open 13D/E. Radio Ops Rep on floor if needed to verify request to Work) (Post Trip) open Rx Breakers locally.

(cont on next page)

L162 NRC ES-D-2-02 r0.docx Page 20 of 23 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Attachment 1 - Scenario Set-up & Booth Actions (cont)

X = manual entry required A = activate from EVENT file TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Evt-7:Phase A Train A Phase A, Train A FAILS TO ACTUATE (post-EOP entry) fails to actuate - Post When called from C/R to close 8152, position @ 0% open Trip Evt-8:Sump blockage Critical Task to shutdown ECCS pumps with suction aligned to recirc when SI-8980 is sump.

closed L162 NRC ES-D-2-02 r0.docx Page 21 of 23 Rev 0

Diablo Canyon Power Plant Operations Shift Log Unit 1 Unit 1 Days at Power: 111 Days Operating Mode: 1 Gross Generation: 601 MWe Power Level: 50% Net Generation: 551 MWe Today - Dayshift Shift Manager Turnover:

PRA RISK STATUS NEXT SHIFT: Green GRID STATUS NEXT SHIFT: Normal AVERAGE RCS CALCULATED LEAKRATE: 0.01 gpm CONDENSER INLEAKAGE: < 0.01 gpd CONDENSER D/Ps: NW 5.9 SW 6.4 NE 6.3 SE 6.1 PSID MAIN GENERATOR H2 USAGE: 325 scfd / 327 scfd 5 day ave SPENT FUEL POOL: Temp = 80oF; Time to 200oF = 30 hrs using actual temp (F-ID-7A)

NEW PRIORITY WORK:

CCP 1-3 emergent motor bearing oil leak identified end of last shift.

SHUTDOWN TECH SPECS / ECGS:

None ECG ACTIONS THAT IF COMPLETION TIME NOT MET ECG 0.3 IS ENTERED:

ECG 8.1 -> CCP 1-3, due in 6 days.

TURNOVER ITEMS:

Unit was ramped to 50% 8 days ago for high vibrations on the MFP 1-1. Bearings replacement in progress. RTS estimate mid-day shift tomorrow.

ODM held for elevated vibrations on MFP 1-2; increased monitoring has been implemented. Should vibrations rise, but remain less than the 4.0 mil vibration limit of AR PK09-14, ODM decision calls for unit load reduction as follows, until vibration levels lower:

o 1.5-2.0 mils: 5.0 MW/min o 2.1-2.5 mils: 6.0 MW/min o 2.6-3.0 mils: 7.0 MW/min o 3.1-3.5 mils: 8.0 MW/min o 3.6-4.0 mils: 9.0 MW/min PRIORITY ITEMS FOR NEXT SHIFT:

Maintain plant stable at current power level.

Shift Foreman Turnover ANNUNCIATORS IN ALARM:

There are no unexpected alarms - all current alarms are consistent with current mode and power level.

TURNOVER ITEMS:

U-1: 50%. Slightly elevated vibrations on MFP 1-2

U-2: 100% power REACTIVITY MANAGEMENT:

Time in core life: _MOL_.

Power History: Steady State @ 50% for 8 days, previously at 100% for 103 day (MFP OOS for maintenance).

Boron concentration is _1000 ppm_ from a sample taken 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago.

Control Rod Height: 175 steps on CBD.

Diluting the RCS approximately 25 gallons every 1.5 hrs.

The last dilution was completed _15_ min ago.

CONDITIONAL SURVEILLANCES & INCREASED MONITORING:

None OTHER ABNORMAL PLANT STATUS

None

Appendix D (rev 11) Scenario Outline Form ES-D-1 Facility: Diablo Canyon (PWR) Scenario No: 3 Op-Test No: L162 NRC Examiners: Operators:

Initial Conditions: 75% with CFCU 1-5 OOS; MOL, 919 ppm boron Turnover: At 75% power due to grid instability.

Event Malf Event Event Description No No. Type* (See Summary for Narrative Detail) 1 EECKSELECT2382371XPWR 0 C, TS Load Tap Changer Auto Control Failure (PK20-04) TS (BOP, 3.8.1.A SRO) 2 XMT_CVC16_3 150 delay=0 ramp=15 I (BOP, TE-130 fails high (PK04-21, AP-5)

SRO) 3 N/A R (ALL) Backdown Order; Shed 150 mw over next 15 minutes (AP-25).

4 DSC_ROD1 cd='smss lt 800' C, TS DRPI loss of normal power requires ramp to be placed (ATC, on hold, rods taken to manual. (AR PK03-21) (TS SRO) 3.1.7.B) 5 MAL_MSS4 720000 delay=0 ramp=60 M (ALL) MSLB outside containment 6 VLV_MSS7_2, VLV_MSS8_2, C (ALL) All MSIVs fail open VLV_MSS9_2, VLV_MSS10_2 1

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor L162 NRC ES-D-1-03 r1.docx Page 1 of 3 Rev 1

Appendix D (rev 11) Scenario Outline 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) 6

2. Malfunctions after EOP entry (1-2) (Event 6) 1

3. Abnormal events (1-4) (Events 1,2,3,4) 4

4. Major transients (1-2) (Event 5) 1

5. EOPs entered/requiring substantive actions (1-2) (E-2, ECA-2.1) 2

6. EOP contingencies requiring substantive actions (0-2) (ECA-2.1) 1

7. Critical tasks (2-3)(See description below) 2 Critical Task Justification Reference (S3CT-1) Stop uncontrolled cooldown by An event or series of events which leads to a

Background Information controlling AFW flow before a severe relatively rapid and severe reactor vessel for WOG Emergency challenge to Integrity Safety Function downcomer cooldown can result in a thermal Response Guideline develops (magenta path on F-0.4 RCS shock to the vessel wall that may lead to a small Integrity) flaw, which may already exist in the vessel wall, growing into a larger crack. The growth or extension of such a flaw may lead, in some cases (where propagation is not stopped within the wall),

to a loss of vessel integrity (S3CT-2) Terminate SI prior to rupture of Failure to terminate ECCS flow when SI termination

Westinghouse Owners PRT by closing 8801A/B and/or 8803A/B. criteria are met results in overfill of the Pressurizer Group WCAP-17711-NP (Note: CT is met by closing either 8801A/B OR and the eventual rupture of the PRT. This 8803A/B.) constitutes the avoidable degradation of the RCS as a fission product barrier.

Per NUREG-1021, Appendix D, if an operator or crew significantly deviates from or fails to follow procedures that affect the maintenance of basic safety functions, those actions may form the basis of a CT identified in the post-scenario review.

L162 NRC ES-D-1-03 r1.docx Page 2 of 3 Rev 1

SCENARIO

SUMMARY

- NRC #3

1. Startup Transformer 1-1 Load Tap Changer control power supply fails. Crew responds per AR PK20-04, SU TRANSF 11, 12, OR 21 LOCAL ANNUN, and manually controls transformer voltage. Shift Foreman enters TS 3.8.1.A, AC Sources - Operating for one required offsite circuit inoperable.

2. Letdown heat exchanger temperature element TE-130 fails high, causing actual letdown temperature to lower. AR PK04-21, LETDOWN PRESS / FLO TEMP comes into alarm, directing the crew to take manual control of letdown temperature (TCV-130), to restore temperature to normal range. Alternately, the crew may elect to follow the guidance of OP AP-5, Malfunction of Eagle 21 Protection or Control Channel .

3. Shift Manager reports a confirmed Grid Control Center backdown order due to grid instability. Unit 1 is directed to shed 150 MW within 15 minutes. The Shift Foreman determines an appropriate ramp rate to meet the backdown order requirement (may assign this task to reactor operator) and implements OP AP-25, Rapid Load Reduction or Shutdown. The ATC determines an initial boration based on the Reactivity Handbook and advises the Shift Foreman of his recommendation. The BOP enters the programmed ramp into the turbine control system. The reactivity evolutions are implemented sequentially, with the Shift Foreman providing oversight.

4. DRPI power failure due to normal supply breaker tripping open near the end of the ramp. Ramp is placed on hold, rods are taken to manual, and Tave is matched within 1.5 oF (if required) per AR PK03-21, DRPI FAILURE / ROD BOTTOM. The Shift Foreman enters TS 3.1.7.B - Rod Position Indication for more than one DRPI per group inoperable.

5. A main steamline break develops downstream of the Main Steam Isolation Valves, outside containment.

The crew identifies the need to isolate the Main Steam Isolation Valves and perform a safety injection (SI) based on pressurizer pressure and level lowering rapidly. Shift Foreman directs a reactor trip and SI and enters EOP E-0, Reactor Trip or Safety Injection.

6. All four main steam isolation valves fail open. The crew transitions to EOP E-2, Faulted Steam Generator Isolation, and then to EOP ECA-2.1, Uncontrolled Depressurization of All Steam Generators. The crew performs the critical tasks of stopping the uncontrolled cooldown (S3CT-1) Stop uncontrolled cooldown before a severe challenge (magenta path ) develops on F-0.4 RCS Integrity by minimizing feedflow and then terminating safety injection (S3CT-2) Terminate SI prior to rupture of PRT.

The scenario is terminated once SI is terminated .

L162 NRC ES-D-1-03 r1.docx Page 3 of 3 Rev 1

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 3 Event No.: 1 Page 1 of 17 Event

Description:

Load Tap Changer Auto Control Failure 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 Startup Transformer 1-1 Load Tap Changer failed from one or more of the following (VB-5):

PK20-04, SU TRANSF 11, 12, OR 21 LOCAL ANNUN, input 943, 12kV Stup Xfmr 1-1 Loc Annunciator

S/U XFMR 1-1 TAP POSITION indicating 1

S/U XFMR 1-1 Low Side Voltage abnormally low SRO Implements PK20-04, SU TRANSF 11, 12, OR 21 LOCAL ANNUN (AR PK20-04, SU TRANSF 11, 12, OR 21 LOCAL ANNUN)

SRO/ATC * (1) Reads input 943 and determines failure is associated with 12kV Startup Transformer; goes to section 2.1 for General Actions SRO/BOP * (2.1.1) Dispatches an Operator to SUT 1-1 to investigate alarm.

SRO/BOP * (2.2.1) Identifies SUT 1-1 voltage not being adequately controlled BOP * (2.2.1.a) Pull S/U XFMR Low Side Voltage Adjust to MANUAL

(2.2.1.b) Raises S/U XFMR 1-1 Low Side Voltage to 129V indicated (continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 3 Event No.: 1 Page 2 of 17 Event

Description:

Load Tap Changer Auto Control Failure (cont)

Time Position Applicants Actions or Behavior (AR PK20-04, SU TRANSF 11, 12, OR 21 LOCAL ANNUN cont)

SRO * (2.2.2) May refer to OP J-2:VIII, Guidelines for Reliable Transmission Service for DCPP for operability guidance

(2.2.3) Requests Electrical Maintenance to investigate

(2.2.4) Enters TS 3.8.1, AC Sources - Operating, Condition A - for one offsite power source inoperable.

o Requires performance of partial STP I-1C within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and once every 8 hrs thereafter until offsite circuit is returned to OPERABLE status.

o Requires offsite circuit to OPERABLE status within 72 hrs.

Proceed to the next event once Tech Specs have been addressed, per the lead examiner.

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 3 Event No.: 2 Page 3 of 17 Event

Description:

Letdown heat exchanger temperature element, TE-130, Fails High Time Position Applicants Actions or Behavior ALL Diagnosis made by using one or more of the following:

TE-130 temperature high (VB2, center vertical)

PK04-21 alarm (on letdown low temp)

SRO May implement AR PK04-21, LETDOWN PRESS / FLOW TEMP or OP AP-5, Malfunction of Eagle 21 Protection or Control Channel (AR PK04-21, LETDOWN PRESS / FLOW TEMP, (if implemented - else mark N/A))

SRO/ATC * (1) Reads input 394 and determines failure is from TE-130, goes to section 2.1 for General Actions SRO * (2.1.1) Notes need to direct Chemistry to isolate argon injection if letdown is isolated

(2.1.2-2.1.4) Determines steps are N/A.

SRO/BOP * (2.1.5) Determines RV-8117, letdown to the PRT has lifted o (2.1.5.a) Places TCV-130 in "MAN". (VB2) o (2.1.5.b) Adjusts TCV-130 control setpoint back to normal range (VB2) o (2.1.5.c) Notes PK06-22 is NOT in alarm; step is N/A o (2.1.5.d) Notes TCV-130 did not fail to manual - was placed in manual; step is N/A

(2.1.5.e) Determines CCW flow to the Letdown Hx is adequate when in manual SRO * (2.1.6-2.1.12) Determines remaining steps are N/A.

(OP AP-5, Malfunction of Eagle 21 Protection or Control Channel, (if implemented - else mark N/A))

(continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 3 Event No.: 2 Page 4 of 17 Event

Description:

Letdown heat exchanger temperature element, TE-130, Fails High, continued Time Position Applicants Actions or Behavior (OP AP-5, Malfunction of Eagle-21 Protection or Control Channel, continued)

SRO/BOP * (1) Determines Primary and Secondary Control Systems are NOT controlling properly in AUTO (specifically TCV-130 has a failure)(VB2)

(1.a RNO) Places TCV-130 in "MAN" and adjusts TCV-130 control setpoint back to normal range (VB2)

(1.b RNO) Notes failure is due to single instrument and not an entire Process Control Rack SRO/BOP * (2) Determines not an Eagle-21 failure based on PK06-01 and PK06 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) Determines TE-130 is part of non-safety related control set IV

(b) Determines TI-130 is the only control board indicator affected and places OOS on VB2.

Proceed to the next event once manual temperature control is established, per the lead examiner.

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 3 Event No.: 3 Page 5 of 17 Event

Description:

Grid Control Center Backdown Order to Shed 150 MW over 15 minutes Time Position Applicants Actions or Behavior Cue: (from Shift Manager) I have just received and validated a backdown order from the Grid Control Center (GCC) due to instability on the 230 kV system. Unit 1 is directed to shed 150 MW total in the next 15 minutes. I will address OP J-2:VIII, OP AP-35, and Ops Policy B-1 requirements.

SRO Implements OP AP-25, Rapid Load Reduction (OP AP-25, Rapid Load Reduction)

SRO Enters OP AP-25, Rapid Load Reduction

(1.a) Notes runback/programmed ramp is not in progress (may not vocalize, since this ramp is initiated by the crew)

SRO/BOP

Commences ramp (guidance is also on lamicoid pegboard on CC3 or Shift Foreman will hand off Step 1 sheet to BOP):

o (1.b) MW and IMP feedbacks are placed in service (all on Triconex turbine HMI, CC3) o (1.c) 720 MWe (871-150, approximate) load target is entered into Triconex HMI o (1.d) Sets ramp rate to 15 mw/min (approximate rate; actual rate dictated by Shift Foreman) o (1.e) Pushes GO SRO o (1.f) Determines downpower is less than 15%.

ATC * (2) Verifies that control rods are inserting properly in AUTO (CC1)

(3) Turns Pressurizer Backup 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)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 3 Event No.: 3 Page 6 of 17 Event

Description:

Grid Control Center Backdown Order to Shed 150 MW over 15 minutes (cont)

Time Position Applicants Actions or Behavior (OP AP-25, 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)

Note: Boration values described below are representative of the conditions given, but will vary based on the actual ramp rate and target specified by SRO.

SRO/ATC * (6) Performs boration (the following guidance is on the boration checklist in the reactivity handbook) o Presses STOP on M/U Ctrl HMI (CC2) o Presses BORATE on HMI o Sets target gallons for boration verifies batch is reset o Sets boric acid flowrate o Presses START, and monitors boration o Once stopped, either returns to AUTO (presses AUTO, then START), or performs additional boration per the Shift Foreman(CC2)

SRO/BOP * (7) Checks MFP suction pressure greater than 260 psig (VB3)

SRO/ATC * (8) Checks Tavg trending to Tref (PPC, CC1)

(9) Checks Pressurizer pressure and level trending to programmed band (PPC, CC2)

Next event triggered automatically at Turbine Power < 735 MW

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 3 Event No.: 4 Page 7 of 17 Event

Description:

DRPI Power Failure During Ramp Time Position Applicants Actions or Behavior ALL DRPI power loss is diagnosed from one or more of the following:

DRPI Panel is "dark", with no rod position lights (VB2, left, black DRPI panel)

PK03-21 alarms on two inputs SRO Implements AR PK03-21, DRPI Failure / Rod Bottom (AR PK03-21, DRPI Failure / Rod Bottom)

SRO * (1) Selects section 2.1 from DRPI urgent failure input 553 SRO/ATC * (2.1.1) Takes manual control of rods by placing bank selector switch in MAN, and verifying normal manual speed on meter (45-51 gpm) (CC1 right)

Note: If SFM asks SM for guidance stopping the Backdown Order ramp, SM should provide the following cue:

Shift Manager Cue Unit 2 was directed to shed remaining load when DRPI lost power" SRO/ATC * (2.1.2) Places ramp on hold (ramp is close to completion)

SRO/ATC * (2.1.3) May review diverse indicators to be used (step counters, bank overlap, NIs, and RCS temperature) if moving rods is required due to Tave/Tref mismatch > 1.5oF prior to DRPI restoration.

SRO * (2.1.4) Enters Tech Spec 3.1.7.B - Rod Position Indication for more than one DRPI per group inoperable which requires rod control to be placed in manual immediately.

Crew will also need to perform the following monitoring actions until DRPI is returned to service:

o Monitor and record reactor coolant system Tavg once per hour o Verify rod position using indirectly using power distribution once every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months o Restore to operable status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 3 Event No.: 4 Page 8 of 17 Event

Description:

DRPI Power Failure During Ramp (cont)

Time Position Applicants Actions or Behavior (AR PK03-21, DRPI Failure / Rod Bottom)(cont)

Shift Manager Cue (if asked for next step) There are currently no loads on their backup source (from the OP O-13)

SRO/BOP * (2.1.5.a) Directs transfer of DRPI to backup power per OP A-3:I (all field actions; may send Nuclear Operator to normal breaker first to investigate)

SRO/ATC * (2.1.5.b) Once DRPI is restored, Rod Control is returned to auto by placing the back selector in AUTO, and verifying 8 spm on the speed indicator (CC1, right)

Proceed to the next event once control rods are back in AUTO, and Tech Specs have been discussed, per the lead examiner.

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 3 Event No.: 5,6 Page 9 of 17 Event

Description:

MSLB Outside Containment, downstream of MSIVs All MSIV Fail Open Time Position Applicants Actions or Behavior ALL Crew identifies RCS temperature lowering, pressurizer level and pressure lowering based on the following:

Annunciator Response Alarms:

AR PK09-01, S/G 1-1 PRESS, LVL FLOW (due to lowering S/G 1-1 pressure and level)

AR PK09-15, DIGITAL FEEDWATER CONT SYSTEM (due to feedflow/steam flow mismatch)

AR PK05-16, PZR PRESSURE HI/LO (pressure low due to cooldown)

AR PK04-06, PROTECT CHANNEL ACTIVATED (for Tave less than 554 oF on loop 1 due to cooldown)

RCS Cooldown Indications: PPC, VB2, and CC1 trends Increased Steam Flow: PPC, VB3, CC3 steam flow meters, record, and trends Lowering S/G 1-1 pressure and level: VB3 and PPC SRO

Directs manual reactor trip and shutting of MSIVs

Implements EOP E-0, Reactor Trip or Safety Injection ALL

Perform immediate actions (EOP E-0, Reactor Trip or Safety Injection)

SRO/ATC * (1) Verifies reactor trip (trip bkrs open (VB2 upper left), rods on bottom (VB2 upper left DRPI panel), NIs decreasing (CC1 left).

(2) Verifies turbine trip (stop valves closed) (CC3 HMI or VB2 RPS indicator lamps).

SRO/BOP * (3) Checks vital 4kv buses (VB4, all vital buses white lights on mimic buses with power supplied by Startup).

Note: SI setpoint is unlikely to be reached until after transition is made out of E-0.

SRO/ATC * (4) Checks if SI actuated (PK08-21 OFF, also checks SSPS ESF status lights on VB1 and PK02-02 to verify SI is NOT required).

(continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 3 Event No.: 5,6 Page 10 of 17 Event

Description:

MSLB Outside Containment, downstream of MSIVs (cont)

All MSIV Fail Open (cont)

Time Position Applicants Actions or Behavior (EOP E-0, Reactor Trip or Safety Injection)

Note: The Shift Foreman may direct closing of the MSIVs at VB3, which will be unsuccessful. Appendix L, Local Closing of Main Steam Isolation Valves, may be implemented at this time SRO/BOP * (4 RNO) Checks AFW status (VB3, AFW Pp 1-2 & 1-3 will be running), and exits E-0 for E-0.1 May throttle AFW LCVs on VB3 lower left to limit RCS cooldown.

ALL

Implements CSFSTs SRO

Transitions to EOP E-0.1, Reactor Trip Response, and performs procedure transition brief (EOP E-0.1, Reactor Trip Response)

Note : EOP E-0.1 actions will be performed until crew initiates SI or SI setpoint is reached, which will most likely occur before the first step of E-0.1 is complete. There is no requirement to perform any particular E-0.1 actions prior to the transition back to E-0.

ALL * (1) Checks Tavg stable or trending towards 547 oF. Notes cooldown is due to steam leak and directs safety injection. Re-enters to E-0.

(EOP E-0, Reactor Trip or Safety Injection(re-entry))

SRO/ATC * (1) Verifies reactor trip (trip bkrs open (VB2 upper left), rods on bottom (VB2 upper left DRPI panel), NIs decreasing (CC1 left).

(2) Verifies turbine trip (stop valves closed) (CC3 HMI or VB2 RPS indicator lamps).

SRO/BOP * (3) Checks vital 4kv buses (VB4, all vital buses white lights on mimic buses with power supplied by Startup).

(continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 3 Event No.: 5,6 Page 11 of 17 Event

Description:

MSLB Outside Containment, downstream of MSIVs (cont)

All MSIV Fail Open (cont)

Time Position Applicants Actions or Behavior (EOP E-0, Reactor Trip or Safety Injection)

SRO/ATC * (4) Checks if SI actuated (PK08-21 ON) and verifies two trains of SI SRO * (5) Directs App E implemented (usually to BOP)(see page 16)

ATC * (6) Checks RCS temperature - stable (temps will initially be dropping due to faulted S/G; AFW will be throttled back (VB2, upper panel lower area)

ATC * (7) Checks Pzr PORVs and Pzr safeties (closed) / PORV block valves (all open and power available), and no elevated tailpipe temps or 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; determines RCPs should remain running (VB1 and VB2))

SRO/ATC * (9) Checks for faulted S/Gs o Faulted - Notes S/G pressure continuing to lower on all S/Gs (VB3)

SRO

Transitions to EOP E-2 (next page)

(continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 3 Event No.: 5,6 Page 12 of 17 Event

Description:

MSLB Outside Containment, downstream of MSIVs (cont)

All MSIV Fail Open (cont)

Time Position Applicants Actions or Behavior (EOP E-2, Faulted S/G Isolation)

SRO Reads CAUTIONS prior to step 1 SRO/ATC * (1) Notes ALL MSIVs are still open and implements Appendix L, Local Closing of Main Steam Isolation Valves. Notes bypasses are closed (VB3, upper panel, left side)

SRO/ATC * (2) Checks for any intact S/G - all four S/G indicate pressure continuing to lower; transitions to ECA-2.1 SRO

Conducts update or procedure transition brief for ECA-2.1 (EOP ECA-2.1, Uncontrolled Depressurization of ALL S/Gs)

SRO/BOP * (1) Checks ALL S/Gs faulted; all S/G pressures are still dropping (VB3/PPC)

(2) Notes MSIVs still OPEN; ensures APP L in progress (VB3/field)

(2b-e) Verifies Main feed reg, bypass, isolation valves, blowdown, and 10%ers all CLOSED (VB3)

(2f) Closes FCV-37 and 38, TDAFW steam supply valves (VB3)

(2g) Closes TDAFW supply valves LCV-106, 107, 108, 109 (VB3)

(continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 3 Event No.: 5,6 Page 13 of 17 Event

Description:

MSLB Outside Containment, downstream of MSIVs (cont) (CT)

All MSIV Fail Open (cont)

Time Position Applicants Actions or Behavior (EOP ECA-2.1, Uncontrolled Depressurization of ALL S/Gs, cont)

Note: Step to check for 100oF/hr cooldown is a continuous action step. Throttling AFW will cause RED PATH on CSF-3 (Heat Sink). Crew will transition to EOP FR-H.1, check the first step, and return to this procedure.

ALL * (3) Controls feedflow to minimize RCS Cooldown o (3a) Observes RCS has cooled down more than 100oF in last hour (VB2/PPC)

(3a RNO) Throttles AFW to each S/G down to approx 25 gpm indicated on FI-157, FI-158, FI-159, and FI-160 (VB3) (S3CT-1)**

o (3b) Controls S/G levels < 65% NR (all below NR at this point) o (3c) Observes that RCS temperatures are still dropping slowly (VB2/PPC)

- (Critical Task) (S3CT-1) Stop uncontrolled cooldown by controlling AFW flow before a severe challenge to Integrity Safety Function develops SRO/ATC * (4) Checks of RCPs should be stopped o (4a) Determines subcooling is greater than than 20oF and goes to next step based on RNO direction

(5) Checks Pzr PORVs and Pzr Safeties and Spray Valves o Safeties closed (closed); no sonic flow, tailpipe temperature are normal (VB2 )

o PORVs closed and associated block valves open (VB2) o Pzr Sprays closed (green lights on) (CC2)

SRO/BOP * (6) Checks Secondary System Radiation and determines S/G are NOT ruptured o Checks RE-71/72/73/74 and RE-15/19 recorders on VB2 (and PPC); (all normal) o PK11-06/17/18 (all OFF) o Requests samples from Chemistry (continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 3 Event No.: 5,6 Page 14 of 17 Event

Description:

MSLB Outside Containment, downstream of MSIVs (cont)

All MSIV Fail Open (cont)

Time Position Applicants Actions or Behavior (EOP ECA-2.1, Uncontrolled Depressurization of ALL S/Gs, cont)

SRO/ATC * (7) Checks if RHR pumps should be stopped o (7.a,b) Determines pumps are aligned to RWST and RCS pressure is greater than 300 psig o (7.c) Resets SI o (7.d) Stops RHRP 1-1 and 1-2

(8) Verifies RCS pressure remains above 300 psig

(9, 10) Checks Containment Spray status, determines it was not actuated

(11) Determines RWST level is adequate (above 33%)

(12) Determines Accumulators do not require isolation (RCS Pressure > 250 psig)

SRO/ATC * (13) Checks if ECCS Flow Should Be Reduced o (13.a) RCS Subcooling > 20 oF (YI-31 on VB2 - upper panel, far right or SPDS) o (13.b) RCS Pressure Stable or Rising o (13.c) PRZ Level > 12%

(14) Checks SI Reset

(15) Resets Phase A (VB1)

SRO/ATC * (16) Establishes Instrument Air to Containment o (16.a) Opens FCV-584 (VB4) o (16.b) Checks header pressure greater than 90 psig

(17) Depresses Vital 4kV Auto Transfer Relay Resets for 4kV bus F/G/H: Blue Light - OFF (continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 3 Event No.: 5,6 Page 15 of 17 Event

Description:

MSLB Outside Containment, downstream of MSIVs (cont) (CT)

All MSIV Fail Open (cont)

Time Position Applicants Actions or Behavior (EOP ECA-2.1, Uncontrolled Depressurization of ALL S/Gs, cont)

ALL * (18) Stops all but on CCP (VB1)

(19) Checks RCS pressure stable or rising - (VB2)

(20) Isolates Charging Injection o (20.a) Checks open 8105 and 8106, CCP recirc valves (VB2) o (20.b) Closes 8803A & B (VB2) (S3CT-2)**

o (20.c) Closes 8801A & B (VB2) (S3CT-2)**

- (S3CT-2) Terminate SI prior to rupture of PRT by closing 8801A/B and/or 8803A/B.

Note only one pair of A and B valves needs to be closed to satisfy the critical task.

ALL * (21) Establishes normal charging flow o (21.a) Throttles HCV-142 (CC2) o (21.b) Ensures 8146 OPEN (VB2) o (21.c) Ensures 8145 AND 8148 - CLOSED (VB2) o (21.d) Opens 8107 and 8108, Norm Charging to Regen Hx Stop Valves (VB2) o (21.e) Throttles open FCV-128 to establish charging flow (CC2)

Scenario may be terminated any time after Injection Flow has been terminated (completion of S3CT-2)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 3 Event No.: 5 Page 16 of 17 Event

Description:

EOP E-0, Reactor Trip or Safety Injection, Appendix E, ESF Auto Actions, Secondary and Auxiliaries Status (CT)

Time Position Applicants Actions or Behavior (EOP E-0, Appendix E)

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 reactor trip/SI on PA system

(2) Checks main generator - tripped (PK14-01 ON, output bkrs open, CC3 right side)

(3 & 4) Verifies Phase A and Containment Vent Isolation complete (VB1, ESF status lights, red lights ON, white lights OFF);

(5) Verify ESF (SI) actuation complete; BOP

(6) Verifies Feedwater isolation complete (F.W. Isolation and S.G. Level Portions of Monitor Light Box C: red lights ON, white light OFF.

BOP * (7) Determines Containment Spray and Phase B Isolation is NOT required (Contmt Isol, Phase B portion of Monitor Light Box D: red lights are OFF)

BOP * (8) Checks Main Steamline Isolation complete (Main Steam Isolation portion of Monitor Light Box D: red light ON, white light are ON) o Determines Main Steamline Isolation is not complete.

o Directs field to implement Appendix L (may have been completed earlier in scenario)

BOP (9) Checks AFW status

AFW Pp 1-2 and 1-3 both running

TDAFW IS NOT required.

Verifies min of 435 gpm flow (VB3 center) or S/G level > 15%

(continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 3 Event No.: 5,6 Page 17 of 17 Event

Description:

EOP E-0, Reactor Trip or Safety Injection, Appendix E, ESF Auto Actions, Secondary and Auxiliaries Status MSLB Outside Containment, downstream of MSIVs Time Position Applicants Actions or Behavior (EOP E-0, Appendix E, cont)

BOP * (10) Checks 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 (Shift Foreman may direct operator to continue on in Appendix E, or redirect to higher priority tasks)

BOP * (12) Checks excess letdown; notes NOT in service prior to trip

(13) Checks secondary systems (MFPs tripped (VB2, green lights ON), stops all but one CB Pp set, takes LCV-12 control switch to CONT ONLY.

(14) Verifies proper operation of Aux Bldg and Control Rm vent systems (VB4 vent status light panel white lights); turns on aux bldg vent charcoal filter preheater (VB4 lower panel, left side) and verifies containment iodine fans secured (VB4, lower panel),

BOP * (15) Verifies available DGs running normally (VB4, freq (60), volts (120), speed (900))

(16) Verifies vital batteries supplied by chargers (charger and bus volts on VB5, upper panel middle/lower area);

(17) Verifies MSRs reset (CC3 Triconex HMI)

(18) Throttles RCP seal injection flows to normal if needed (FCV-128, to 8-13 gpm each, CC2)

(19) Checks PK11-04 NOT IN (SFP alarm)

(20) Notifies Shift Foreman of completion.

(Board Operator will rejoin crew upon completion of Appendix or when called upon by Shift Foreman)

- Critical Task L162 NRC ES-D-2-03 r0.docx Page 17 of 21 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Attachment 1 - Scenario Set-up & Booth Actions X = manual entry required TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION X IC RESTORE 152 75% power MOL, CB - 919 X Setup N/A CFCU 1-5 OOS The Plant Abnormal Status Board for Surveillance Requirements None Copies of Procedures, Attachments; Appendixes; Foldout Pages; OP B-1A:XII, PK03-21, PK04-21, PK20-04, AP-5, AP-25, EOP E-0, E0.1, E-2, ECA-2.1 Annunciator Response Procedures and commonly used forms are in binders and NOT Marked up X 0 min Tools > Simple SBT Before crew takes the watch.

Use Simple SBT, Data Recorder File: sbt_sim.drb, min 960 iterations (30 sec).

Critical Task Specific Data Capture:

S3CT1: AFW Flow and valve positions. Tcold, all loops.

S3CT2: PRT pressure and level; 8801A, 8801B,8803A, and 8803B valve positions(specifically when a complete flow path goes CLOSED).

X 0 min Lesson L161 NRC-S3.lsn After SFM reports the crew has taken the watch, load session MALS, OVRs, etc. by FILE or MANUALLY (below)

X Evt-1: LTC Auto Power Supply failure (normal and switch to backup) cause LTC to fail to low tap.

Controller Fails When turbine watch dispatched to check SUT 1-1, report local alarm panel in for (approx. 3 min after LTC V Reg to B/U and LTC upper/lower tap limit.

taking watch per lead examiner)

X Evt-2: TE-130 fails Letdown heat exchanger temperature element TE-130 fails high high (Once Evt-1 TS have been addressed, per lead examiner)

X Evt-3: Grid If GCC contacted, report call was made to SM to report conditions.

Disturbance, GCC ramp of 150 MW in 15 min (Cue given by SM)

X Evt-4: DRPI power DRPI power loss. Transfer to B/U when directed; delay 5 minutes to run command loss (LOA_ESPI BACKUP)

(Triggers off MW <

800)

X Evt-5: MSLB Outside MSLB outside containment Containment (Once temperature has been stabilized, per lead examiner)

(cont on next page)

L162 NRC ES-D-2-03 r0.docx Page 18 of 21 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Attachment 1 - Scenario Set-up & Booth Actions (cont)

X = manual entry required A = activate from EVENT file TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Evt-6: All 4 MSIVs fail All 4 MSIVs failed open. MSIVs will remain failed open for duration of open - Post Trip scenario. When directed to perform App L, respond to all calls stating unable to close and have requested assistance from mechanical maintenance.

L162 NRC ES-D-2-03 r0.docx Page 19 of 21 Rev 0

Diablo Canyon Power Plant Operations Shift Log Unit 1 Unit 1 Days at Power: 111 Days Operating Mode: 1 Gross Generation: 871 MWe Power Level: 75% Net Generation: 821 MWe Today - Dayshift Shift Manager Turnover:

PRA RISK STATUS NEXT SHIFT: Green GRID STATUS NEXT SHIFT: Normal AVERAGE RCS CALCULATED LEAKRATE: 0.01 gpm CONDENSER INLEAKAGE: < 0.01 gpd CONDENSER D/Ps: NW 5.9 SW 6.4 NE 6.3 SE 6.1 PSID MAIN GENERATOR H2 USAGE: 325 scfd / 327 scfd 5 day ave SPENT FUEL POOL: Temp = 80oF; Time to 200oF = 30 hrs using actual temp (F-ID-7A)

NEW PRIORITY WORK:

CFCU 1-5 OOS for backdraft damper replacement.

SHUTDOWN TECH SPECS / ECGS:

None ECG ACTIONS THAT IF COMPLETION TIME NOT MET ECG 0.3 IS ENTERED:

None TURNOVER ITEMS:

Unit was ramped to 75% yesterday under a backdown order associated with grid instability.

PRIORITY ITEMS FOR NEXT SHIFT:

Maintain current power level.

Shift Foreman Turnover ANNUNCIATORS IN ALARM:

There are no unexpected alarms - all current alarms are consistent with current mode and power level.

TURNOVER ITEMS:

U-1: maintain 75% - no one in containment.

U-2: maintain 75% - no one in containment.

REACTIVITY MANAGEMENT:

Time in core life: _MOL_.

Power History: Steady State at 100% for past 111 days.

Boron concentration is _919 ppm_ from a sample taken 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago.

Control Rod Height: 191 steps on CBD.

Diluting the RCS approximately 25 gallons every 1.5 hrs.

The last dilution was completed _30_ min ago.

CONDITIONAL SURVEILLANCES & INCREASED MONITORING:

None OTHER ABNORMAL PLANT STATUS

None

Appendix D (rev 11) Scenario Outline Form ES-D-1 Facility: Diablo Canyon (PWR) Scenario No: 4 Op-Test No: L162 NRC Examiners: Operators:

Initial Conditions: 100% with MAFW Pump 1-3 OOS; MOL, 878 ppm boron Turnover:

Event Malf Event Event Description No No. Type* (See Summary for Narrative Detail) 1 MAL_NIS6A 200 delay=0 ramp=420 I, TS NI-41 slow failure HIGH (AP-5; Multiple TS (see (ALL) summary section))

2 XMT_RCS6_3 -376.0 ramp=60 I, TS only PT-403 fails low (PK05-07, 09)(TS 3.3.3.A)

(SRO) 3 MAL_CWS2C 2.3 delay=0 ramp=2 C (ALL) Condenser In-leakage (PK12-05, AP-20 & 25) 4 XMT_CND29_3 282 ramp=240 C (BOP, CBP Set 1-3 high bearing temp when ramp reaches XMT_CND30_3 278 ramp=240 SRO) 1000 MW (PK10-06)

CD04CND_CDP13_MTFSEIZUR 1 cd='(h_v3_225r_1 and (txmtcbmo(3) gt 280))' delay=15 5 MAL_SEI1 0.15 delay=0 ramp=10 M (ALL) FCV-510 fails closed following seismic event.

CNV_MFW3_2 0 delay=0 ramp=60 6 MAL_RCS4F 600 cd='fnispr_2 lt 5' M (ALL) 600 gpm SGTR (S/G 1-2) delay=0 ramp=10 7 MAL_PPL3A BOTH, MAL_PPL3B BOTH C (ALL) SI Actuation Fails (both auto and manual) 8 CNV_RCS1_2 C (BOP) Prz Sprays failed closed / PORV used for CNV_RCS2_2 depressurization fails opened; block valve can not be closed

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor L162 NRC ES-D-1-04 r1.docx Page 1 of 4 Rev 1

Appendix D (rev 11) Scenario Outline 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 1,3,4,5,6,7,8) 7

2. Malfunctions after EOP entry (1-2) (Events 7,8) 2

3. Abnormal events (1-4) (Events 1,3,4) 3

4. Major transients (1-2) (Event 5,6) 2

5. EOPs entered/requiring substantive actions (1-2) (E-3, ECA-3.1) 2

6. EOP contingencies requiring substantive actions (0-2) (ECA-3.1) 1

7. Critical tasks (2-3)(See description below) 3 Critical Task Justification Reference (S4CT-1) Manually trip the reactor before Steam Generator Level below 15% narrow range in

WOG Backgd HFHR1BG_R3 S/G 1-1 reaches dry out conditions as 1 of 4 loops after a power level dependent time indicated by WR level less than 10%. delay, normally generates a reactor trip signal to protect against a loss of heat sink. For this scenario, power remains above 50%, so the time delay = 0.

Once the S/G has reached dry out conditions, it is no longer capable of RCS heat removal.

Furthermore, the S/G is susceptible to structural damage as the result of thermal shock once feedwater is re-established from the Auxiliary Feedwater System.

(S4CT-2) Manually align at least one train of FSAR analysis predicates acceptable results on the

WCAP-17711-NP, CT-2 SIS actuated safeguards before transition assumption that, at the very least, one train of

WOG Backgrnd HE0BG_R2 out of EOP E-0, Reactor Trip or Safety safeguards has actuated and is providing flow to Injection. the core. Failure to start and manually align the minimum required safeguards equipment results in the persistence of degraded emergency core cooling system capacity.

(S4CT-3) Isolate the ruptured steam SG inventory increase leads to water release

W Margin to Overfill (CN-generator from the intact steam generators through the S/G PORV or safety valve(s) or to SG CRA-05-53 Rev1) prior to commencing cooldown of the RCS overfill, which would seriously compromise the SG

W Offsite Doses (CN-CRA-in step 9.c (40% steam dumps) or 10.b (10% as a fission-product barrier and complicate 05-54) steam dump) by completing the following: mitigation.

SGTR UFSAR 15.4.3 Isolate feedwater by ensuring closed:

WCAP-17711-NP

LCV-107 (MDAFW Level Control Valve)

LCV-111 (TDAFW Level Control Valve)

Isolate steamflow by ensuring closed:

FCV-42 (S/G 1-2 MSIV)

FCV-37 (S/G 1-2 supply to TD AFW Pp)

Per NUREG-1021, Appendix D, if an operator or crew significantly deviates from or fails to follow procedures that affect the maintenance of basic safety functions, those actions may form the basis of a CT identified in the post-scenario review.

L162 NRC ES-D-1-04 r1.docx Page 2 of 4 Rev 1

SCENARIO

SUMMARY

- NRC #4

1. Power Range Nuclear Instrument NI-41 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 37.3 (Quadrant Power Tilt Ratio Alarms).

2. PT-403, RCS Wide Range Pressure Transmitter, fails low. The crew responds to PK05-07, Subcooling Margin Lo/Lo-Lo and PK05-09, RVLIS Lo Lvl RVLIS/SCMM Trouble, identifying the affected instrumentation. Shift Foreman addresses TS 3.3.3.A, Post Accident Monitoring Instrumentation

3. A saltwater leak develops in the SW quadrant of the condenser, bringing in AR PK12-05, COND PPS DISCH HDR CATION CONDT'Y HI. The crew determines cation conductivity is elevated and the Shift Foreman enters OP AP-20, Condenser Tube Leak, which calls for a 25 MW/min ramp to 50%. The crew immediately implements OP AP-25, Rapid Load Reduction or Shutdown to commence the ramp.

4. Annunciator AR PK10-06, CNDS & CNDS BSTR PPS comes into alarm due to rising bearing temperatures on Condensate Booster Pump Set (CBP) 1-3. Reactor operators identify rapidly rising bearing temperatures using plant process computer trends. The crew manually starts CBP 1-2 and secures CBP 1-3 to prevent motor damage.

(Note: Malfunction is designed to trip CBP 1-3 if crew has not shut the pump down within 15 seconds of bearing temperature reaching 280oF. The Autostart of CBP 1-2 has been disabled and will require a manual start).

5. A 0.15 seismic event results in Main Feed Reg valve FCV-510 failing closed. S/G 1-1 level can not be maintained. S/G 1-1 Low Level trip has been disabled and the crew must manually trip the reactor (S4CT-1) Manually trip the reactor before S/G 1-1 reaches dry out conditions.

6. A 600 gpm tube rupture develops on S/G 1-2 when the reactor trips. The crew enters EOP E-0, Reactor Trip or Safety Injection, and identifies the rupture based on various radiation alarms, rising counts on RM-72, and the inability to maintain RCS pressure and pressurizer level following the trip.

7. Both auto and manual Safety Injection (SI) actuation signals fail and the crew must manually start and align SI actuated equipment (S4CT-2) Manually align at least one train of SIS actuated safeguards before transition out of EOP E-0.

(continued on next page)

L162 NRC ES-D-1-04 r1.docx Page 3 of 4 Rev 1

SCENARIO

SUMMARY

- NRC #4

8. The crew transitions to EOP E-3, Steam Generator Tube Rupture, and where they perform the critical task of isolating S/G 1-2 (S4CT-3) Isolate the ruptured steam generator from the intact steam generators prior to commencing cooldown of the RCS.*** Depressurization of the RCS is commenced following the cooldown. Pressurizer spray valves fail to operate and a PORV must be used. When the crew attempts to stop the depressurization, both the PORV and associated block valve fail to operate in the closed direction, and the Shift Foreman transitions to EOP ECA-3.1, SGTR with Loss of Reactor Coolant - Subcooled Recovery Desired.

The scenario is terminated once the cooldown to Cold Shutdown in ECA-3.1 has been commenced or verified.

- - CT / TCOA note: SGTR was evaluated against Time Critical Operator Actions (TCOAs) # 2 (SGTR); initial power level and supporting equipment conditions differ significantly from the conditions used in this scenario. For these reasons, the S/G TCOAs will remain critical (a critical task, per WOG), but TCOA time limits will not be applied to this scenario.

L162 NRC ES-D-1-04 r1.docx Page 4 of 4 Rev 1

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 4 Event No.: 1 Page 1 of 25 Event

Description:

Power Range Nuclear Instrument NI-41 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 NI-41 failure from the following:

NI-41 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 NI-41 failing high) (CC1)

SRO Enters OP AP-5, Malfunction of Eagle-21 Protection or Control Channel (OP AP-5, Malfunction of Eagle-21 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 choose to use the turbine load to raise Tave, or may "move up" a substep in OP AP-5 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 L162 NRC ES-D-2-04 r0.docx Page 1 of 29 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 4 Event No.: 1 Page 2 of 25 Event

Description:

Power Range Nuclear Instrument NI-41 Slow Failure High, continued Time Position Applicants Actions or Behavior (OP AP-5, Malfunction of Eagle-21 Protection or Control Channel, continued)

SRO/ATC * (2) Determines not an Eagle-21 failure based on PK06-01 and PK06 OFF SRO * (3) Notes no impact since Loop 2 is selected for TR-411 recorder (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 NI-41 (CC1, VB2) and OTdT (VB2)

(b) Determines NI-41 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 N41 position (this one cause defeat alarm, PK07-07, and allows rod movement) o Places power mismatch switch to the N41 position o Places quadrant power tilt upper section to the N41 position o Places quadrant power tilt lower section to the N41 position o Places comparator defeat switch to the N41 position (continued on next page)

- Critical Task L162 NRC ES-D-2-04 r0.docx Page 2 of 29 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 4 Event No.: 1 Page 3 of 25 Event

Description:

Power Range Nuclear Instrument NI-41 Slow Failure High, continued Time Position Applicants Actions or Behavior (OP AP-5, Malfunction of Eagle-21 Protection or Control Channel, continued)

SRO * (8) Evaluates Tech Specs and ECGs:

o TS 3.3.1.E - One channel inoperable for OTDelta-T trip (place in trip within 72 hrs);

o TS 3.3.1.D - One power range neutron flux-high channel inoperable (Hi flux trip)

(place in trip within 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 (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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and once per hour thereafter) o Equip Control Guideline (ECG) 37.3 - Quadrant Power Tilt Ratio Alarm inoperable (verify QPTR within limits of TS 3.2.4 once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months )

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 L162 NRC ES-D-2-04 r0.docx Page 3 of 29 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 4 Event No.: 2 Page 4 of 25 Event

Description:

PT-403, RCS Wide Range Pressure Transmitter, Fails Low Time Position Applicants Actions or Behavior Note: AR PK05-07, SUBCOOLING MARGIN LO/LO-LO and AR PK05-09, 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 PT-403 has failed low from one or more of the following (VB-2):

PK05-07, SUBCOOLING MARGIN LO/LO-LO

PK05-09, RVLIS LO LVL, RVLIS/SCMM TROUBLE VB-3 Indications:

PR-403, LOOP 4 HOT LEG PRESS - WIDE RANGE = 0 psig (bottom of scale low)

YI-31, SUBCOOL MARGIN MON - TRAIN B = -40oF (bottom of scale low)

If AR PK05-07 is entered; otherwise this section is N/A SRO/ATC * (1.0) Identifies input 1600 (Subcooled Mon Lo-Lo Margin from RVLIS Train B) and goes to section 2.1 for General Actions SRO Reads NOTE regarding P-10 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 PR-403 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 PT-403:

o (2.1.4.a) Determines failure is associated with RVLIS/SCMM, Train B o (2.1.4.b) Checks train-specific subcooling indications to confirm failure (PPC, SPDS Train B, YI-31 on VB2, PAM4 Display - may use any)

(continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 4 Event No.: 2 Page 5 of 25 Event

Description:

PT-403, RCS Wide Range Pressure Transmitter, Fails Low (cont)

Time Position Applicants Actions or Behavior (AR PK05-07, continued)

SRO Reads NOTE regarding possible Thermocouple Monitoring System failure (PK05-15) and determines it doesnt apply SRO * (2.1.3) Confirms specific instrument failure as PT-403 (continued):

o (2.1.3.c) Notes PK05-15 is NOT in alarm and continues to next step o (2.1.3.d) References AP-5, 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 met (required number of channels and minimum channels operable

=1)

If AR PK05-09 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 L162 NRC ES-D-2-04 r0.docx Page 5 of 29 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 4 Event No.: 2 Page 6 of 25 Event

Description:

PT-403, RCS Wide Range Pressure Transmitter, Fails Low (cont)

Time Position Applicants Actions or Behavior (AR PK05-09, continued)

ALL * (2.1.4) Identifies specific instrument failure as PT-403:

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 AP-5 is referenced; otherwise this section is N/A Note: PT-403 provides no controlling functions. Shift Foreman may go directly to OP AP-5, 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.

SRO/BOP Places Out of Service stickers on the following affected equipment:

PR-403 (VB-2)

RVLIS TRAIN B (PAM 1, behind VB-5)

Sub-cooled Margin Monitor (VB-2)

Proceed to the next event once Tech Specs have been addressed per lead examiner

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 4 Event No.: 3 Page 7 of 25 Event

Description:

Condenser In-Leakage Time Position Applicants Actions or Behavior Observes PK12-05 (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.

o May check PPC point AN590BA to verify elevated Cation Conductivity value.

SRO/BOP * (2.1.1) Contacts Polisher Watch to investigate cause of alarm SRO * (2.1.2) Enters OP AP-20, Condenser Tube Leak (OP AP-20, Condenser Tube Leak )

SRO/ATC * (1) Determines condensate cation conductivity is greater than 1.0 µS/cm (PPC and/or Polisher Watch report) o Directs Polisher Watch to monitor chemistry data and alert control room for adverse trend o Compares PPC 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)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 4 Event No.: 3 Page 8 of 25 Event

Description:

Condenser In-Leakage, continued Time Position Applicants Actions or Behavior (OP AP-20, 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) (PPC) o Identifies South West 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 FCV-230 (condensate polisher demineralizer bypass valve) goes open for any reason.

(3) Performs actions to prevent bypass of condensate demineralizers o (3.a) Verifies FCV-230 closed (VB3, lower right skirt) o (3.b) Directs Turbine Watch to open supply breaker for FCV-230 SRO/BOP * (4) Monitors Feedwater Cation Conductivity for indications of condensate demin breakthrough; (PPC)

SRO/BOP * (5) Evaluates Attachment 4.1, Condenser Tube Leak Corrective Action Limits o Determines minimum ramp is 25MW/min down to 50% power o Initiates ramp (CC3, Turbine Control HMI) (see next page)

SRO/BOP * (6-11) May perform additional actions to minimize secondary contamination in parallel with implementation of OP AP-25.

o Takes manual control and closes Condenser Hotwell Reject Valve, LCV-12 (VB3, lower right skirt) o Directs field realignment of CWP 1-1 Auto Reclose and SCW Hx (continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 4 Event No.: 3 Page 9 of 25 Event

Description:

Condenser In-Leakage, continued Time Position Applicants Actions or Behavior (OP AP-25, Rapid Load Reduction )

SRO * (1a) 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 (1b) MW and IMP feedbacks are placed in service (all on Triconex turbine HMI, CC3) o (1c) 550 MWe load target is entered into Triconex HMI o (1d) Sets ramp rate to 25 mw/min o (1e) Pushes GO o (1f) Notifies Chemistry of power decrease greater than 15% in one hour SRO/ATC * (2) Verifies that control rods are inserting properly in AUTO (VB2)

SRO/ATC * (3) Verifies ON all pressurizer backup heaters (CC1)

SRO/ATC * (4) Verifies charging flow adequate to prevent letdown flashing: may take manual control of Pzr level o Places HC-459D (master level controller) and/or FCV-128 (charging flow controller) in manual (CC2) o Keeps charging high enough to prevent letdown from flashing (VB2)

SRO/BOP * (5) Verifies DFWCS in AUTO and controlling S/G levels (CC3 MFW HMI, VB3, PPC) o Checks MFW control and bypass valves in AUTO o Checks both MFPs and their controller in AUTO o May check level trends, as well as steam flow/feed flow trends (CC3, PPC, and/or big VB3 DFWCS electronic recorders)

(continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 4 Event No.: 3 Page 10 of 25 Event

Description:

Condenser In-Leakage, continued Time Position Applicants Actions or Behavior (OP AP-25, Rapid Load Reduction (cont))

Note: Boration values described below are representative of the conditions given, but will vary based on the actual ramp rate and target specified by SRO.

SRO/ATC * (6) Performs boration (the following guidance is on the boration checklist in the reactivity handbook) o Presses STOP on M/U Ctrlr HMI (CC2) o Presses BORATE on HMI o Sets target gallons for boration (as decided above, and per the Shift Foreman);

verifies batch is reset o Sets boric acid flowrate o Presses START, and monitors boration o Once stopped, either returns to AUTO (presses AUTO, then START), or performs additional boration per the Shift Foreman SRO

The Shift Foreman provides indirect reactivity oversight for the ramp SRO/BOP * (7) Checks MFP suction pressure greater than 260 psig (VB3)

SRO/ATC * (8) Checks Tavg trending to Tref (PPC, CC1)

(9) Checks Pressurizer pressure and level trending to programmed band (PPC, CC2)

Next event is set to auto trigger at 1000 MW

- Critical Task L162 NRC ES-D-2-04 r0.docx Page 10 of 29 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 4 Event No.: 4 Page 11 of 25 Event

Description:

Condensate Booster Pump 1-3 High Bearing Temperature During Ramp Time Position Applicants Actions or Behavior Note: Condensate Booster Pump 1-3 pump bearing temperatures rise over four minutes. This causes alarm PK10-06. The pump shaft will seize and the pump trips on overcurrent 15 seconds after bearing temperature reaches 280 degrees if not shutdown by the crew. Autostart of standby CBP 1-2 will fail, requiring manual start by the crew ALL Diagnoses CBP 1-3 high pump bearing temperature and trip from the following:

PK10-06, CNDS & CNDS BSTR PPS , in alarm

Rising pump bearing temperatures on PPC Note: Crew may follow guidance of AR PK10-06 for engineering evaluation or may elect to shutdown pump based on OP1.DC10, Conduct of Operations guidance for protection of plant equipment.

AR PK10-06 CNDS & CNDS BSTR PPS (If used, else mark N/A)

SRO/BOP * (2.3.1) Dispatches an Operator to determine cause of high temperature SRO/ATC

Reads NOTE regarding temperature limits prior to step 2.3.2

(2.3.2) Notes requirement to document temperature and lapsed time period if pump set is left in service with actual high temperature alarms

(2.3.3) Notes direction to contact engineering for evaluation if stator temperature is 248oF or above SRO/BOP * (2.3.4.a) Starts standby CBP 1-2 (VB3, lower center skirt)

(2.3.4.b) Stops CBP 1-3 (VB3, lower center skirt)

OP1.DC10, Conduct of Operations - guidance for protection of plant equipment (27.22.6)

SRO/BOP

Starts standby CBP 1-2 (VB3, lower center skirt)

Stops CBP 1-3 (VB3, lower center skirt)

(continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 4 Event No.: 4 Page 12 of 25 Event

Description:

Condensate Booster Pump 1-3 High Bearing Temperature During Ramp, continued Time Position Applicants Actions or Behavior ALL (If not stopped preemptively) Diagnoses CBP 1-3 overcurrent trip from the following:

PK10-06, CNDS & CNDS BSTR PPS , reflashes

Reduction in Feedpump Suction Pressure (VB3, upper right center)

Overcurrent (blue) light on for CBP 1-3 (VB3, lower center skirt)

SRO Enters OP AP-15: Section D Loss of Feedwater Flow - Condensate/Booster Pump Set Trip (OP AP-15: Section D, Loss of Feedwater Flow - Condensate/Booster Pump Set Trip (N/A if already stopped)

SRO/BOP * (1) Determines all available CBPs running

(2) Checks Main Feed Pump suction pressure greater than 260 psig (VB3, upper center)

SRO

May direct Turbine Watch to walk down pump and breaker

May request maintenance to investigate issue

(3) Exits AP-15 Proceed to the next event once Condensate Booster Pump failure has been addressed, per lead examiner

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 4 Event No.: 5 Page 13 of 25 Event

Description:

Loop 1 Feedwater Reg Valve, FCV-510, Fails Closed following seismic event (CT)

Time Position Applicants Actions or Behavior ALL Diagnoses feedflow problem from one or more of the following:

Lowering Feedflow on S/G 1-1 only (VB3, DFWCS screen (CC3))

FCV-510 Valve Actual Position (DFWCS screen (CC3)

PK09-01, SG 1-1 PRESS, LVL FLOW (feed flow less than steam flow)

SRO/ATC

Attempts to take manual control of FCV-510, but valve is unresponsive.

Recognizes level drop should cause automatic Reactor Trip when level falls below 15%

in S/G 1-1 .

Note: Automatic Reactor Trip at S/G level < 15% has been defeated.

SRO

Directs manual reactor trip (S4CT-1)**

Implements EOP E-0, Reactor Trip or Safety Injection

- (Critical Task) (S4CT-1) Manually trip the reactor before S/G 1-1 reaches dry out conditions as indicated by WR level less than 10%.

(continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 4 Event No.: 5 Page 14 of 25 Event

Description:

Loop 1 Feedwater Reg Valve, FCV-510, Fails Closed, continued Time Position Applicants Actions or Behavior (EOP E-0, Reactor Trip or Safety Injection)

ATC * (1) Verifies reactor trip (trip breakers open(VB2 upper left), rods on bottom (VB2 upper left DRPI panel), Nis decreasing (CC1 left))

ATC * (2) Verifies turbine trip (stop valves closed) (CC3 HMI or VB2 RPS indicator lamps)

BOP * (3) Checks vital 4kv busses (VB4, vital bus F/G/H all have a white lights on the mimic buses)

ATC/BOP * (4) Checks if SI actuated (PK08-21 OFF, also checks SSPS ESF status lights on VB1 and PK02-02 to verify SI is NOT required)

ATC/BOP * (4 RNO) Checks AFW status (VB3, AFW Pp 1-2 will be running), and exits E-0 for E-0.1 ALL

Implements CSFSTs SRO

Transitions to EOP E-0.1, Reactor Trip Response, and performs procedure transition brief (continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 4 Event No.: 5 Page 15 of 25 Event

Description:

Loop 1 Feedwater Reg Valve, FCV-510, Fails Closed, continued Time Position Applicants Actions or Behavior (EOP E-0.1, Reactor Trip Response)

Note 1: EOP E-0.1 actions will be performed until crew identifies SGTR, which will most likely occur within the first step or two of E-0.1; there is no requirement to perform any particular E-0.1 actions prior to the transition back to E-0.

ATC/BOP * (1) Checks Tavg stable or trending towards Tref (if should be); may start TDAFW if levels low and throttle LCVs to control RCS temperature (VB3)

ATC/BOP * (2) Checks Feedwater Isolation (FWI) complete

Checks Tave < 554°F (expected, given initial power level)

Checks FWI MLB (monitor light box) (VB1, upper center), RED light ON, WHITE lights OFF (they are, this actuation occurs if < 554°F)

Checks AFW flow > 435 gpm (the flow will be adequate, and S/G levels will be at or near normal) (VB3)

ATC * (3) Checks all control rods - fully inserted (they are) (VB2 upper left, for DRPI panel)

ATC/BOP * (4) Checks Pzr and level control

Checks Pzr level > 17% (it is) (VB2 meter, CC2 recorder, PPC)

Checks charging and letdown in service (they both are) (CC2 and VB2 CVCS mimic)

Checks Pzr level trending to 22%; operates FCV-128 and HCV-142 (CC2) to control Pzr level 22% - 60% (RNO)

Operates Pzr heaters as needed (auto/manual) to maintain normal pressure (normal auto operation expected at this point, with pressure returning to normal or normal already)

(continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 4 Event No.: 6,7 Page 16 of 25 Event

Description:

600 GPM SGTR on S/G 1-2 SI Actuation Fails (both auto and manual) (CT)

Time Position Applicants Actions or Behavior ALL Diagnoses of SGTR is made using one or more of the following:

Pressurizer level and pressure lowering (PPC, CC2, VB2)

S/G 1-2 level rising (PPC, VB3)

Main steam line hi-rad rising, loop 2 (RM-72) (PPC, VB2) (not visible for several minutes after initial break)

SRO/BOP

May attempt to isolate letdown (VB2, upper center skirt)

Note: Failure of both Auto and Manual actuation of Safety Injection will require manual starting of ECCS pumps and positioning of injection flowpath valves. These manipulation may be completed as part of EOP E-0, Appendix E. (see page 23).

ALL

Initiates manual SI (CC2, far right) o Determines Manual SI unsuccessful (may try VB1 switch, which fails as well) o Performs manual alignment of SI equipment (S4CT-2)**

- (Critical Task) (S4CT-2) Manually align at least one train of SIS actuated safeguards before transition out of EOP E-0, Reactor Trip or Safety Injection. Note only one train is required to meet the critical task.

(Re-enters EOP E-0, 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/G/H have white lights on mimic busses)

(continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 4 Event No.: 6 Page 17 of 25 Event

Description:

600 GPM Post-Trip SGTR on S/G 1-2 (cont)

Time Position Applicants Actions or Behavior (EOP E-0, Reactor Trip or Safety Injection , continued)

SRO/ATC * (4) Checks SI actuated (PK08-21 is OFF but equipment is manually aligned) o Both trains of SI/RHR pumps running (VB1 skirt)

SRO * (5) Directs implementation of App E (usually given to BOP); See page 23 SRO/ATC * (6) Checks RCS temperature stable or lowering to 547oF o AFW Pp 1-2 is running; may start TDAFW if not previously started.

SRO/ATC * (7) Checks Pzr PORVs and Pzr Safeties and Spray Valves o Safeties closed (closed); no sonic flow, tailpipe temperature normal (VB2 - upper panel, far right) o PORVs closed and associated block valves open (VB2 - upper panel, far right) o Pzr Sprays closed (green lights on) (CC2)

SRO/ATC * (8) Checks RCP trip criteria; o RCS WR Pressure is greater than 1300 PSIG, trip criteria is not met (VB2).

SRO/ATC * (9) Determines S/G are NOT faulted o No S/G lowering in an uncontrolled manner or completely depressurized SRO/ATC * (10) Checks for ruptured S/G o Notes RE-72 elevated with and S/G 1-2 level rising o Directs transition to EOP E-3, Steam Generator Tube Rupture (continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 4 Event No.: 6 Page 18 of 25 Event

Description:

600 GPM Post-Trip SGTR on S/G 1-2 (cont) (CT)

Time Position Applicants Actions or Behavior (EOP E-3, Steam Generator Tube Rupture )

SRO/ATC * (1) Checks if RCPs should be stopped (VB2)

(2) Identifies S/G 1-2 as ruptured (RM-72 in alarm, previous indications of rising level without feed during E-0)

SRO/BOP * (3) Implements Appendix FF to isolate ruptured S/G 1-2 (see pg 25)

SRO/ATC Reads CAUTION regarding maintaining isolation of Faulted/Ruptured S/G

(4.a) Checks ruptured S/G level is greater than 15%

(4.b) Closes AFW LCVs to S/G 1-2 (LCV-107, LCV-111) (VB3, skirt) (S4CT-3)**

- (Critical Task)(partial S4CT-3, Isolate the ruptured steam generator from the intact steam generators prior to commencing cooldown of the RCS in step 9.c SRO/ATC * (5) Observes ruptured S/G is greater than 225 psig (PPC, VB3)

(6) Determines required Core Exit Temperature based on current S/G 1-2 pressure.

(7) Checks Main Condenser available (VB3)

SRO/ATC

Reads two CAUTIONS regarding Main Steam Line Isolation

(8) Blocks Low Steamline Pressure SI o (8.a) Checks RCS Pressure - LESS THAN 1915 PSIG o (8.b) Checks PK08-06, PZR SI PERMISSIVE P ON o (8.c) Blocks LO Steamline Pressure SI, Train A and B, verifies PK08-17 ON (it is)

(continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 4 Event No.: 6 Page 19 of 25 Event

Description:

600 GPM Post-Trip SGTR on S/G 1-2 (cont)

Time Position Applicants Actions or Behavior (EOP E-3, Steam Generator Tube Rupture )

SRO

Reads CAUTION that RCP Trip Criteria is NOT applicable after operator begins RCS cooldown.

(9) Initiates RCS Cooldown Using 40% Steam Dumps o (9.a) Verifies Appendix FF is complete Note: If AR PK 08-07, Lo Lo Tave Permissive (P-12) is active, Shift Foreman will need to pull step 9.d forward to unblock the 40% steam dump valves. If 40% dump valves not used, following step is N/A.

SRO/ATC * (9) Initiates RCS Cooldown Using 40% Steam Dumps (continued) o (9.b) Places Steam Dumps in Steam Pressure Mode Place HC-507 in MANUAL and reduce demand to 0%

Place Steam Dump Mode Select Switch in STEAM PRESSURE o (9.c) Dumps steam at maximum rate possible without achieving a main steam line isolation (less than 120 psi/min).

o (9.d) Places Steam Dump Control in Bypass Intlk (Train A and B) to re-arm 40%

dumps if P-12 activates (or is already active) o (9.e) Will continue on in procedure at step 11 while cooldown continues.

o (9.f) Stops the cooldown when ALL Core Exit Thermocouples are less than required target temperature.

o (9.g) Stabilizes temperature slightly less than required temperature using steam dumps in AUTO.

Note: If MSL Isolation occurs while using 40% steam dumps, Shift Foreman may elect to continue cooldown using 10% dump valves (described below) to avoid unnecessary delays. N/A if 10% dump valves not used.

SRO/ATC * (10) Initiates RCS Cooldown Using 10% Steam Dumps o (10.a) Verifies Appendix FF is complete o (10.b) Manually opens PCV-19, 21, and 22 (10% Steam Dumps) to 100% to dump steam at maximum possible rate.

o (10.c) Continues on in procedure at step 11 while cooldown continues.

o (10.d) Stops the cooldown when ALL Core Exit Thermocouples are less the required target temperature.

o (10.e) Stabilizes temperature slightly less than required temperature using steam dumps in AUTO (continued on next page)

L162 NRC ES-D-2-04 r0.docx Page 19 of 29 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 4 Event No.: 6 Page 20 of 25 Event

Description:

600 GPM Post-Trip SGTR on S/G 1-2 (cont)

Time Position Applicants Actions or Behavior Note: If MSL Isolation occurs while using 40% steam dumps, Shift Foreman may elect to continue cooldown using 10% dump valves (described below) to avoid unnecessary delays. N/A if 10% dump valves not used.

SRO/BOP * (11) Controls AFW flow to maintain intact S/G levels 20% - 65%; should raise AFW flow to intact S/Gs before or immediately after starting cooldown (VB3, skirt)

SRO/BOP * (12) CHECK PZR PORVs and Block Valves o (12.a,c) Power available to block valves and all open o (12.b) PZR PORVs - all closed Note: May elect not to reset SI since never actuated due to malfunction SRO/BOP * (13) Resets Safety Injection (VB1)

SRO/BOP * (14) Resets both Trains Phase A (Phase B was not in) (VB1)

SRO/BOP * (15) Restores Instrument Air to Containment and checks header pressure greater than 90 psig (VB4)

SRO/BOP * (16) Shuts down RHR pumps SRO/ATC * (17) Checks RCS cooldown stopped before continuing on to depressurization of RCS SRO/BOP * (18) Checks ruptured S/G pressure stable or rising (should be 950-1040 psig, and stable)

SRO/BOP * (19) Checks Subcooling greater than 40oF (continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 4 Event No.: 6 Page 21 of 25 Event

Description:

600 GPM Post-Trip SGTR on S/G 1-2 (cont)

Time Position Applicants Actions or Behavior (EOP E-3, Steam Generator Tube Rupture, continued)

ALL

Reads note regarding use of a PORV for depressurization if normal spray is determined to be ineffective

(20) Attempts to depressurization of RCS using normal Pressurizer Sprays o Both 455A and 455B fail to open o Determines sprays are ineffective; moves on to PORVs

(21) Depressurizes the RCS using one PZR PORV o Depressurizes the RCS to minimize break flow and refill the PZR until one of the criteria of Appendix GG is met:

RCS Pressure < ruptured S/G pressure, and Pzr level at least 12%, OR, Pzr level > 74%, OR, SCM < 20 F o Attempts to close the PORV, but PORV and associated block valve both fail open

(22) Determines RCS pressure is NOT rising, goes to RNO o (22.a RNO) Checks PRT parameters to confirm leakage is from PORV.

o (22.b RNO) Transitions to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -

SUBCOOLED RECOVERY DESIRED

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 4 Event No.: 8 Page 22 of 25 Event

Description:

Ruptured S/G With Loss of Reactor Coolant Time Position Applicants Actions or Behavior (EOP ECA-3.1, SGTR with Loss of Reactor Coolant - Subcooled Recovery Desired )

SRO/ATC * (1) Resets SI - (VB1) (not required due to earlier failure - never actuated)

(2) Resets Containment Isol Phase A & B - should be reset (VB1)

(3) Establishes instrument air to containment - should be established (VB4)

SRO/BOP * (4) Checks all AC buses energized by offsite power - they are (VB4, VB5)

SRO/ATC * (5) Places all PZR heater switches in OFF (CC1)

(6-7) Checks Containment Spray not actuated (VB1)

(8) Checks ruptured S/G level > 15% (VB3, PPC)

(9) Checks RHR Pumps running (VB2), RCS pressure > 300 psig (VB2, PPC) - RHR Pumps already stopped as part of E-3 actions.

(11) Evaluates plant status (only expected ation is to call Chemistry for RCS sample)

(12-15) Prepares to initiate RCS cooldown Note: The crew is not expected to perform a cooldown to complete the scenario. The scenario may be run until the crew has discussed a cooldown and is ready to begin.

SRO/ATC * (16) Initiates RCS cooldown to cold shutdown The scenario is terminated once the cooldown to Cold Shutdown has been commenced or verified.

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 4 Event No.: 6,7 Page 23 of 25 Event

Description:

600 GPM Post-Trip SGTR on S/G 1-2 SI Actuation Fails (both auto and manual) (CT)

Time Position Applicants Actions or Behavior (EOP E-0, Appendix E - ESF Auto Actions, Secondary and Auxiliaries Status)

Note: Failure of both Auto and Manual actuation of Safety Injection will require manual starting of ECCS pumps and positioning of injection flowpath valves. These manipulation may be completed prior to performance of Appendix E.

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 reactor trip/SI on PA system

(2) Checks main generator - tripped (PK14-01 ON, output bkrs OPEN, CC3 right side)

(3 & 4) Verifies Phase A and Containment Vent Isolation complete (VB1, ESF status lights, red lights ON, white lights OFF - may need to actuate due to SI failure);

(5) Verify ESF (SI) actuation complete; manual alignment of Safety Injection pumps and valves will be required due to actuation failure (S4CT-2)**

- (Critical Task) (S4CT-2) Manually align at least one train of SIS actuated safeguards before transition out of EOP E-0, Reactor Trip or Safety Injection. Note only one train is required to meet the critical task.

BOP * (6) Verifies Feedwater isolation complete (F.W. Isolation and S.G. Level Portions of Monitor Light Box C: red lights ON, white light OFF.

BOP * (7) Determines Containment Spray and Phase B Isolation is NOT required (Contmt Isol, Phase B portion of Monitor Light Box D: red lights are OFF)

BOP * (8) Checks Main Steamline Isolation complete (Main Steam Isolation portion of Monitor Light Box D: red light OFF, white light are OFF)

BOP (9) Checks AFW status

AFW Pp 1-2 running; TDAFW IS required.

Verifies min of 435 gpm flow (VB3 center) or S/G level > 15%

(continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 4 Event No.: 6 Page 24 of 25 Event

Description:

600 GPM Post-Trip SGTR on S/G 1-2 (cont)

Time Position Applicants Actions or Behavior (EOP E-0, Appendix E)

BOP * (10) Checks 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 (Shift Foreman may direct operator to continue on in Appendix E, or redirect to higher priority tasks)

BOP * (12) Checks excess letdown; notes NOT in service prior to trip

(13) Checks secondary systems (MFPs tripped (VB2, green lights ON), stops all but one CB Pp set, takes LCV-12 control switch to CONT ONLY.

(14) Verifies proper operation of Aux Bldg and Control Rm vent systems (VB4 vent status light panel white lights); turns on aux bldg vent charcoal filter preheater (VB4 lower panel, left side) and verifies containment iodine fans secured (VB4, lower panel),

BOP * (15) Verifies available DGs running normally (VB4, freq (60), volts (120), speed (900))

(16) Verifies vital batteries supplied by chargers (charger and bus volts on VB5, upper panel middle/lower area);

(17) Verifies MSRs reset (CC3 Triconex HMI)

(18) Throttles RCP seal injection flows to normal if needed (FCV-128, to 8-13 gpm each, CC2)

(19) Checks PK11-04 NOT IN (SFP alarm)

(20) Notifies Shift Foreman of completion.

(Board Operator will rejoin crew upon completion of Appendix or when called upon by Shift Foreman)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 4 Event No.: 6 Page 25 of 25 Event

Description:

600 GPM Post-Trip SGTR on S/G 1-2 (CT)

Time Position Applicants Actions or Behavior (EOP E-3, Appendix FF, Isolate Faulted Steam Generator )

BOP Reads CAUTION regarding TDAFW as only source of feedflow prior to step 1

(1) Reads step to ensure 10% steam dump controller in AUTO

(2) Checks S/G 1-2 10% steam dump valve closed (PCV-20) (VB3)

(3) Verifies S/G 1-2 MSIV and bypass (FCV-42 and FCV-24) valves closed (VB3) o Closing FCV-42 is part of (S4CT-3)**

(4) Verifies S/G 1-2 supply to TD AFW Pp (FCV-37) closed (VB3, skirt)**

(5) Verifies S/G 1-2 SGBD valves (FCV-154 and FCV-248) closed (VB3, lower left

(6) Verifies S/G 1-2 is isolated from intact S/G (S/G 1-2 MSIV and MSIV Bypass are both closed as are all intact S/G MSIV and MSIV Bypasses)

(7) Informs Shift Foreman S/G 1-2 isolation is complete

- (Critical Task) (Part of S4CT-3: Isolate the ruptured steam generator prior to commencing a cooldown of the RCS)

BOP * (8) Removes 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

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Attachment 1 - Scenario Set-up & Booth Actions X = manual entry required TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION X IC RESTORE 153 100% power MOL, CB - 878 X Setup N/A MDAFW 1-3 OOS Verify AutoReclose Lamacoid is realigned to CWP 1-1 The Plant Abnormal Status Board for Surveillance Requirements None Copies of Procedures, Attachments; Appendixes; Foldout Pages; PK05-07, PK05-09, PK10-06, PK12-05, AP-5, AP-15, AP-20, AP-25, EOP E-0, E-0.1, E-3, ECA-3.1 Annunciator Response Procedures and commonly used forms are in binders and NOT Marked up X 0 min Tools > Simple SBT Before crew takes the watch.

Use Simple SBT, Data Recorder File: sbt_sim.drb, min 960 iterations (30 sec).

Critical Task Specific Data Capture:

S4CT1: NI Power Level and S/G 1-1 level.

S4CT2: ECCS pump discharge pressure and amps; 8801A/B, 8803A/B, 8805A/B, and 112B/C valve positions

S4CT3: LCV-107, LCV-111, FCV-42, FCV-24, FCV-37 valve positions X 0 min Lesson L161 NRC-S4.lsn After SFM reports the crew has taken the watch, load session MALS, OVRs, etc.

by FILE or MANUALLY (below)

X Evt-1: NI-41 Fails High Slow failure high on NI-41 (approx. 3 min after taking watch per lead examiner)

X PT-403: Fails Low PT-403 fails low (once TS for Evt-1 have been addressed per lead examiner)

X Evt-3: Cond Tube When Polisher Watch contacted, use PPC screen values to report conductivity Leak (once Evt-2 TS value after verifying failure has completed ramp. Location of leak is SW quad.

addressed per lead See Lesson File for drills to swap Hx and Auto Reclose as well as opening examiner) breaker for FCV-230.

X Evt-4: CBP Set 1-3 Brg When dispatched to pump, report back no oil visible in the motor bearing sight (Triggers off MW < glass. Charred appearance around the bearing housing.

800)

X Evt-5: FRV-510 fails Auto reactor trips have been overridden for Critical Task purposes.

closed (Once crew has shutdown CWP)

Evt-6:600 gpm SGTR 600 gpm SGTR on S/G 1-2 (ramps in immediately after trip)

Evt-7:Auto/Man SI Auto/Manual SI failed - requires manual alignment of ECCS valves and starting failed (post-trip) of pumps.

(cont on next page)

L162 NRC ES-D-2-04 r0.docx Page 26 of 29 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Attachment 1 - Scenario Set-up & Booth Actions (cont)

X = manual entry required A = activate from EVENT file TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Evt-8A: PRZ Sprays PZR Sprays failed closed - forces crew to PORV Failed Closed (post-trip)

Evt-8B: PRZ Sprays PORV used for depressurization and associated block valve will fail Failed Closed (post- open - forces transition into ECA-3.1 trip)

L162 NRC ES-D-2-04 r0.docx Page 27 of 29 Rev 0

Diablo Canyon Power Plant Operations Shift Log Unit 1 Unit 1 Days at Power: 111 Days Operating Mode: 1 Gross Generation: 1197 MWe Power Level: 100% Net Generation: 1147 MWe Today - Dayshift Shift Manager Turnover:

PRA RISK STATUS NEXT SHIFT: Green GRID STATUS NEXT SHIFT: Normal AVERAGE RCS CALCULATED LEAKRATE: 0.01 gpm CONDENSER INLEAKAGE: < 0.01 gpd CONDENSER D/Ps: NW 4.9 SW 4.4 NE 4.3 SE 5.1 PSID MAIN GENERATOR H2 USAGE: 325 scfd / 327 scfd 5 day ave SPENT FUEL POOL: Temp = 80oF; Time to 200oF = 30 hrs using actual temp (F-ID-7A)

NEW PRIORITY WORK:

None SHUTDOWN TECH SPECS / ECGS:

TS 3.7.5.B MDAFW 1-3 OOS, due in 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months ECG ACTIONS THAT IF COMPLETION TIME NOT MET ECG 0.3 IS ENTERED:

None TURNOVER ITEMS:

MDAFW 1-3 OOS for routine maintenance; expected back next shift.

PRIORITY ITEMS FOR NEXT SHIFT:

Maintain current power level.

Shift Foreman Turnover ANNUNCIATORS IN ALARM:

There are no unexpected alarms - all current alarms are consistent with current mode and power level.

TURNOVER ITEMS:

U-1: maintain 100% - no one in containment.

U-2: maintain 100%.

REACTIVITY MANAGEMENT:

Time in core life: _MOL_.

Power History: Steady State at 100% for past 111 days.

Boron concentration is _878 ppm_ from a sample taken 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago.

Control Rod Height: 229 steps on CBD.

Diluting the RCS approximately 25 gallons every 1.5 hrs.

The last dilution was completed _30_ min ago.

CONDITIONAL SURVEILLANCES & INCREASED MONITORING:

None OTHER ABNORMAL PLANT STATUS

None

Appendix D (rev 11) Scenario Outline Form ES-D-1 Facility: Diablo Canyon (PWR) Scenario No: 5 Op-Test No: L162 NRC Examiners: Operators:

Initial Conditions: 100% with AFWP 1-2 OOS; MOL, 878 ppm boron Turnover:

Event Malf Event Event Description No No. Type* (See Summary for Narrative Detail) 1 VLV_PZR6_2 0.1 delay=0 ramp=5 C, TS PCV-474 slowly drifts open (AP-13)(TS 3.4.11.B).

(BOP, SRO) 2 PK1823_0132 1 C, TS Ground on ASW Pump 1-1 (PK18-23)(TS 3.7.8.A).

(BOP, SRO) 3 GGAHRL_62GSC3TVSP 0 C (ATC, Partial Stator Water cooling flow/partial runback (PK14-MAL_GEN3 LO_FLOW delay=10 SRO) 19, PK12-12, AP-25).

delIA MAL_GEN3 2 cd='smss lt 925' 4 MAL_CVC8A C (ATC, Seal Injection Filter 1-1 plugs causing reduction in SRO) charging flow to RCP seals (PK04-22).

5 RLY_PPL37 CLOSED(TRUE) M (ALL) Spurious Phase B causes isolation of CCW Header C requiring Reactor Trip and tripping of all four RCPs (PK01-08, AP-11).

6 MAL_AFW1 1 cd='H_V3_109M_1 GT 0.1' C (ALL) Bus F trips on differential on reactor trip causing loss of MAL_MFW2A,B 25 cd='fnispr lt 5.0' DRPI and AFW pump 1-3. Both MFPs Trip and TDAFP MAL_EPS4C_2 DIFFERENTIAL trips on overspeed; (post trip).

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor L162 NRC ES-D-1-05 r1.docx Page 1 of 3 Rev 1

Appendix D (rev 11) Scenario Outline 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) 6

2. Malfunctions after EOP entry (1-2) (Events 6) 1

3. Abnormal events (1-4) (Events 1,2,3,4) 4

4. Major transients (1-2) (Event 5) 1

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

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

7. Critical tasks (2-3)(See description below) 2 Critical Task Justification Reference (S5CT-1) Trip all four Reactor Coolant RCPs are susceptible to catastrophic failure and a

FSAR Accident Analysis, Pumps (RCPs) as indicated by: loss of reactor coolant flow if left running in the Section 15.2.5 - Partial

RCP Breaker position = OPEN absence of adequate bearing cooling flow. If the Loss of Forced Ractor

RCP Amperage lowering reactor is at power at the time of the accident, the Coolant Flow

RCP thrust bearing temperatures immediate effect of loss of coolant flow is a rapid lowering increase in the coolant temperature. This increase could result in DNB with subsequent fuel damage if prior to a partial loss of reactor coolant the reactor is not tripped promptly.

flow due to Reactor Coolant Pump failure.

(S5CT-2) Establish a secondary heat sink as A loss of all feedwater transient is characterized by

FR-H.1 Background indicated by: a depletion of secondary inventory and eventual Document (HFRH1BG),

WR level rising degradation of secondary heat transfer capability. Rev. 3.

Core Exit Thermocouple As secondary heat transfer capability degrades, temperatures lowering core decay heat generation will increase RCS temperature and pressure causing loss of RCS Prior to reaching bleed and feed criteria inventory similar in nature to a small break loss of which is defined as wide range S/G level in coolant accident. Failure to restore a secondary any three S/Gs less than 18% [26%] AND heat sink when it is possible to do so constitutes a narrow range S/G level in all four S/Gs less significant reduction of safety margin beyond that than 15% [25%] narrow range.

irreparably introduced by the scenario.

Per NUREG-1021, Appendix D, if an operator or crew significantly deviates from or fails to follow procedures that affect the maintenance of basic safety functions, those actions may form the basis of a CT identified in the post-scenario review.

L162 NRC ES-D-1-05 r1.docx Page 2 of 3 Rev 1

SCENARIO

SUMMARY

- NRC #5

1. Pressurizer Pressure Control Valve PCV-474 drifts open and must be isolated using the associated 8000-A block valve. Shift Forman enters TS 3.4.11.B Pressurizer Power Operated Relief Valves (PORVs) - for one PORV inoperable for reasons other than excessive seat leakage.

2. Running ASW Pump 1-1 experiences a ground on 4 kV Bus F. The crew follows the guidance of AR PK18-23, 4KV BUS F GROUND OC ALARM, and shuts down ASW pump 1-1 after starting the 1-2 pump. Shift Forman enters TS 3.7.8.A, Auxiliary Saltwater (ASW) System for one train inoperable.

3. Low Stator Coil Cooling Water flow causes a turbine runback. The crew responds per AR PK14-19, STATOR WTR CLG SYSTEM, and OP AP-25, Rapid Load Reduction or Shutdown. The low flow condition clears quickly (approximately 925 MW), and the crew stabilizes the plant.

4. 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. Reactor Operators verify CCP seal cooling is still being maintained by CCW and ATC operator throttles RCP seal injection hand control valve, HCV-142, as needed to maintain pressurizer level. Shift Foreman establishes bands for pressurizer level and confirms field operators have been dispatched to swap seal injection filters.

5. A spurious actuation of Train A, Phase B results in the isolation of CCW Header C. The crew responds per AR PK01-08, CCW HEADER C, or alternately, OP AP-11, Section E: Loss of CCW Flow to RCPs, which calls for tripping the reactor and then tripping all four RCPs. (S5CT-1) Trip all four Reactor Coolant Pumps (RCPs) .

6. The crew enters E-0, Reactor Trip or Safety Injection and performs their immediate actions. On the trip, 4 kV bus F trips on differential. DRPI loses power, but crew is able to determine the reactor has tripped based on diverse indications (lowering reactor power and reactor trip breakers open). MDAFW Pump 1-3 is also lost due to the bus failure. Both main feedpumps trip and the TDAFW pump trips on overspeed leading to Loss of Heat Sink condition. The crew transitions to EOP FR-H.1, Response to Loss of Secondary Heat Sink. With the condenser available, Main Feed is used to restore a secondary side heat sink (S5CT-2) Establish a secondary heat sink.

The scenario is terminated once Critical Task S5CT-2 is complete.

L162 NRC ES-D-1-05 r1.docx Page 3 of 3 Rev 1

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 5 Event No.: 1 Page 1 of 17 Event

Description:

Pressurizer Pressure Control Valve PCV-474 (PORV) Drifts Open Time Position Applicants Actions or Behavior ALL Diagnoses PCV-474 open using one or more of the following indications:

PK05-20, PZR RELIEF/SAFETY VLVS OPEN in alarm

PK05-23, 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 PCV-474 (VB2, far right, lower)

PORV discharge temperature elevated (TI-463) (VB2, far right, middle)

SRO/BOP

Takes action to manually close PCV-474 (unsuccessful)

Closes associated block valve (8000A)

Note: AR PK05-23 will redirect crew to AR PK05-20 for guidance (AR PK05-20, Pressurizer Relief/Safety Valves Open) if entered, else N/A SRO/ATC * (1) Identifies input 1150 (Pzr Relief Vlv PCV-474 Open) and goes to section 2.1, General Actions SRO * (2.1.1) Notes requirement to enter EOP E-0, 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 (TI-463) (VB2, far right, middle)

(2.1.2) Checks for indications of rapid drop in actual pressurizer pressure; may transition to OP AP-13 (continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 5 Event No.: 1 Page 2 of 17 Event

Description:

Pressurizer Pressure Control Valve PCV-474 (PORV) Drifts Open, (continued)

Time Position Applicants Actions or Behavior (OP AP-13, 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 (PCV-474, 455C, 456) (VB2, far right, lower) o Notes PCV-474 position lights indicate valve is open

(2 RNO) Checks pressurizer pressure less than 2335 psig (it is);

o May reattempt closing PCV-474 (valve remains off its seat) o Ensures associated block valve 8000A 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 (PCV-455A/B) (CC2, upper middle right) (green lights On, both are closed)

(4.b) Checks aux spray valves closed (8145 & 8148) (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)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 5 Event No.: 1 Page 3 of 17 Event

Description:

Pressurizer Pressure Control Valve PCV-474 (PORV) Drifts Open, (continued)

Time Position Applicants Actions or Behavior (OP AP-13, 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 (2210-2260 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 8000A within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Remove power from 8000A within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Proceed to Next Event once Tech Specs addressed, per Lead Examiner

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 5 Event No.: 2 Page 4 of 17 Event

Description:

Ground on ASW Pp 1-1 Time Position Applicants Actions or Behavior ALL Diagnoses ground using one or more of the following indications:

PK18-23, 4KV BUS F GROUND OC ALARM in alarm SRO Implements PK18-23, 4KV BUS F GROUND OC ALARM (AR PK18-23, 4KV BUS F GROUND OC ALARM)

SRO/ATC * (1) Identifies input 132 (ASW Pp 1-1 Fdr Grd) and goes to section 2.1, General Actions SRO * (2.1.1) Determines ASW Pp 1-1 must be shut down (May use OP E-5:IV - see below).

o Places ASW Pp 1-2 Standby Select Switch to Manual (VB1) o Starts ASW Pp 1-2 (VB1) o Shuts down ASW Pp 1-1 (VB1)

(2.1.2) Determines ground was limited to ASW Pp 1-1 (PK18-23 clears when pump is shutdown)

(2.1.3) Directs maintenance to locate and repair the defective circuit

(2.1.4) Enters TS 3.7.8.A, - Operating, Condition A - for one ASW train inoperable; restore to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

OP E-5:IV, Auxiliary Saltwater System - Swapping Pumps or HXs During Single CCW HX Operation (N/A if not used)

BOP

Reviews PRECAUTIONS AND LIMITATIONS

Performs Section 6.1-Swapping an ASW Pump and CCW Heat Exchanger Train o (6.1.1) Notes ASW Pump 1-1 is running with CCW HX 1-1 in service (VB1) o (6.1.2) Contacts Intake Watch to secure continuous chlorination to ASW Bay 1-1 o (6.1.3) Contacts Aux Watch to ensure no liquid radwaste discharge in progress o (6.1.4) Directs U2 to place standby ASW pump in MANUAL (continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 5 Event No.: 2 Page 5 of 17 Event

Description:

Ground on ASW Pp 1-1 (cont)

Time Position Applicants Actions or Behavior OP E-5:IV, Auxiliary Saltwater System (cont)(N/A if not used)

BOP o (6.1.5) Places Mode Selector Switch for ASW pump 1-2 in "MANUAL" (VB1) o (6.1.6) Places Control Switch for ASW pump 1-2 in "START" to start ASW pump 1-2 (VB1) o (6.1.7) Ensures ASW pump 1-2 amps are stable (VB1)

BOP o (6.1.8) Opens CCW HX saltwater inlet valve FCV-603 (VB1) o (6.1.9) Ensures differential pressure across both CCW HXs is within normal range (VB1) o (6.1.10) Opens CCW HX 1-2 shell-side outlet valve FCV-431 (VB1) o (6.1.11) Closes CCW HX 1-1 shell-side outlet valve FCV-430 (VB1) o (6.1.12) Closes CCW HX 1-1 saltwater inlet valve FCV-602 (VB1) o (6.1.13) Checks that differential pressure across HX1-1 is less than 50 inches (VB1)

BOP o (6.1.14) Shuts down ASW Pump 1-1 (VB1) o (6.1.15) May elect to place Mode Selector Switch for ASW pump 1-1 in "MANUAL" (VB1) o (6.1.16) Directs U2 to place standby ASW pump in "AUTO" o (6.1.17) Updates SRO on current ASW train alignment o (6.1.18) May direct Intake Watch to align ASW Bay 1-2 for continuous chlorination Proceed to Next Event once Tech Specs addressed, per Lead Examiner

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 5 Event No.: 3 Page 6 of 17 Event

Description:

Loss of Stator Cooling Partial Runback Time Position Applicants Actions or Behavior ALL Diagnoses Stator cooling runback from the following:

PK14-19, Stator Wtr Clg System, alarms with Stator Clg Wtr Coil flow low and very low inputs (0266, 0666)

RUNBACK light is on, on turbine HMI (CC3)

PK12-12, DEH System, alarms, with input 0715, Turbine Runback

MW are dropping (CC3, PPC)

SRO Dispatches TB watchstander to stator cooling water skid to investigate Note: SRO may initially enter OP AP-30, as directed by AR PK14-19, or may go directly to OP AP-25 to address the runback.

OP AP-30, Main Generator Malfunction SRO Implements OP AP-30 Section G, Stator Wtr Clg System Trouble (as time permits)

SRO/ATC (1) Identifies alarm inputs PK14-19 0266 & 0666 SRO/BOP (2) Identifies turbine runback initiated SRO Goes to OP AP-25 and delegates OP AP-30 to BOP to implement OP AP-25, Rapid Load Reduction or Shutdown SRO/BOP (1) Verifies runback in progress (dropping MW, RED runback light) (CC3)

ATC (2) Verifies that control rods are inserting properly in AUTO (VB2, intermittent green IN light)

(continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 5 Event No.: 3 Page 7 of 17 Event

Description:

Loss of Stator Cooling Partial Runback (Continued)

Time Position Applicants Actions or Behavior OP AP-25, Rapid Load Reduction, con't ATC (3) Verifies ON all pressurizer backup heaters (CC1, left)

(4) Places HC-459D (master level controller) and/or FCV-128 (charging flow controller) in manual (CC2)

Keeps charging high enough to prevent letdown from flashing (VB2)

BOP (5) Verifies DFWCS in AUTO and controlling S/G levels (CC3 MFW HMI, VB3, PPC)

Checks MFW control and bypass valves in AUTO

Checks both MFPs and their controller in AUTO

May check level trends, as well as steam flow/feed flow trends (CC3, PPC, and/or big VB3 DFWCS electronic recorders)

ATC (6) RCS is borated per reactivity handbook for approx 25% load reduction (the following guidance is on the boration checklist in the reactivity handbook) o Presses STOP on M/U Ctrlr HMI (CC2) o Presses BORATE on HMI o Sets target gallons for boration (as decided above, and per the Shift Foreman);

verifies batch is reset o Sets boric acid flowrate o Presses START, and monitors boration o Once stopped, either returns to AUTO (presses AUTO, then START), or performs additional boration per the Shift Foreman SRO The Shift Foreman provides indirect reactivity oversight for the ramp BOP (7) Checks secondary system status:

(7a) MFP suction is verified adequate (PPC, VB3 meter; will remain > 260 psig)

(continued on next page)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 5 Event No.: 3 Page 8 of 17 Event

Description:

Loss of Stator Cooling Partial Runback (Continued)

Time Position Applicants Actions or Behavior OP AP-25, Rapid Load Reduction, con't ATC (8) Verifies proper operation of steam dumps, Tave trending to Tref (VB3, red/green indicator lights; Tave/Tref from CC1 recorder/PPC)

(9) Checks pressurizer pressure and level trending to program (actual will be close to program, but may need adjustments) (CC2, PPC)

SRO (10) Determines if it is desired to shut down the #2 Htr Drip Pp (it is currently running, can remain running or be shutdown at this power level) (VB3, upper panel, center)

(11) Determine if the unit can remain on line; the Shift Foreman determines that the unit can remain at this power level ALL (12) Stabilizes the plant once ramp completed (as time permits)

Tave within 1.5 oF of Tref (ATC)

Axial flux difference (AFD) in target band (or borating to get it there); rods > RIL (ATC)

S/Gs are trending towards program level (CC3, VB3, PPC) (they will be stable and close to program level of 65%) (BOP)

MFP D/Ps are on program (DFWCS HMI on CC3) (D/P will be very close to program, and stable) (BOP)

Pzr pressure and level stable, in normal bands (CC2, PPC) (ATC)

Returns turbine to standby status (BOP)

Takes MW and IMP pressure feedbacks OUT on Triconex turbine control HMI (CC3)

Sets valve position limit (VPL) to 1-2% above current value (same controller)

May perform reactivity brief, or update (ALL)

Note: It is not anticipated that the crew will progress past this point in AP-25.

Next Event Auto Triggers when boration is within 15 gallons of target

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 5 Event No.: 4 Page 9 of 17 Event

Description:

Seal Injection Filter 1-1 Plugged Time Position Applicants Actions or Behavior ALL Diagnoses Reactor Makeup Controller problem from the following:

Lowering seal injection flow to all RCPs (VB2, middle right)

PKs 05-01, 05-02, 05-03, 05-04 in alarm due to RCP seal low flow alarms

PKs 04-22 in alarm 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)

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 HCV-142 (seal backpressure) and/or FCV-128 (charging flow controller). (CC2)

Identifies potential impact on Pressurizer level (charging flow lowering as more flow is directed toward seals); re-adjusts to maintain pressurizer level.

ATC

Identifies input 498 for PK04-22, RCP Seal Injection Filter Delta-P Hi AR PK04-22, RCP Seal Injection Filter Delta-P Hi SRO * (1) Determines input is for RCP Seal Injection Filter 1-1 and goes to General Actions section.

Reads CAUTION regarding 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 HCV-142 while adjusting FCV-128 to establish 8-13 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)

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 5 Event No.: 4 Page 10 of 17 Event

Description:

Seal Injection Filter 1-1 Plugged (cont)

Time Position Applicants Actions or Behavior (AR PK04-22, 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/ATC * (2.1.2) Directs board operator to monitor RCP radial bearing temperatures on the PPC Note: Booth Operator will respond to phone call, but will not perform swap; this failure sets up the subsequent event.

SRO/BOP * (2.1.3) Directs Nuclear Operator to swap seal injection filter 1-1 to filter 1-2 per OP B-1A:I, Section 6.3 SRO * (2.1.4) Contacts Maintenance to replace seal injection filter 1-1.

Proceed to Next Event once control of charging reestablished, per Lead Examiner

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Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 5 Event No.: 5 Page 11 of 17 Event

Description:

Spurious Phase B and Isolation of CCW Header C Time Position Applicants Actions or Behavior ALL Diagnoses Spurious Phase B and Isolation of CCW Header C using one or more of the following indications:

PK01-08, CCW HEADER C in alarm

PK05-01,02,03,04, RCPs in alarm

PK04-21, LETDOWN PRESS / FLO TEMP in alarm

FCV-355, HDR C ISOL VLV (VB1)

FCV-356, CCW SSPLY to RCP'S and RX VSL SPRT CLRS (VB1)

FCV-749, RCP BRG OIL & SPRT CLR RTN ISO VLV in the CLOSED position (VB1)

FCV-750, RCP THERMAL BARRIER RTN ISO VLV in the CLOSED position (VB1)

SRO/ATC Identifies inputs 1372, 265, 428, 429 for AR PK01-08, AR PK01-08, U1, CCW HEADER C Note: Crew may enter AR PK01-08 or OP AP-11, Malfunction of Component Cooling Water System.

(AR PK01-08, CCW HEADER C) (Mark N/A if not used) Note: Multiple inputs are received for this AR PK, all of which result in a reactor trip and tripping of the RCPs. Only the first is listed below.

SRO * (1) Follows input 428 for RCP Thermal Barrier CCW Flo Lo and goes to step 2.2.

Reads CAUTION regarding high flow and determines it does not apply

Read NOTE regarding actuation of Containment Isolation Phase B due to the isolation of CCW header C and the associated conditions related to tripping the reactor and stopping RCPs; determines the NOTE will apply.

SRO/BOP * (2.2.1) Ensures two CCW pumps running (VB1).

(2.2.2) Determines FCV-355, Header C Supply and FCV-356, Supply to RCP and Rx Vessel Support Coolers are both CLOSED and cannot be opened (VB1).

SRO/ATC * (2.2.3) Checks RCP lower radial bearing temperatures and determines they are rising.

(2.2.4) Attempts to maintain seal injection flow between 8 and 13 gpm, but is unable to due to clogged seal injection filter.

(continued on next page)

- Critical Task L162 NRC ES-D-2-05 r0.docx Page 11 of 21 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 5 Event No.: 5 Page 12 of 17 Event

Description:

Spurious Phase B and Isolation of CCW Header C (cont) (CT)

Time Position Applicants Actions or Behavior (PK01-08, CCW HEADER C, continued)(Mark N/A if not used)

Note: Initial Implementation of E-0, Reactor Trip or Safety Injection will cover performance of operator immediate action steps. Transition to OP AP-28 is not expected due to subsequent failures taking precedence.

ALL * (2.2.5) Determines alarm is due to Thermal Barrier low flow AND is coincident with a loss of seal injection in MODE 1. Previews required actions with crew:

o (2.2.5.a) Reactor Trip (ATC) and Implementation of E-0, Reactor Trip or Safety Injection.

o (2.2.5.b) Trip the RCPs (BOP).

o (2.2.5.c) Transition to OP AP-28, Section F, Loss of Seal Inj and Thermal Barrier Cooling Water (ATC)

ALL (2.2.5.a) Crew implements EOP E-0 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 buses G/H have white lights on mimic busses)

SRO/BOP (2.2.5.b) Directs Tripping of all four RCPs (VB2) o Trips RCP 1-1**

o Trips RCP 1-2**

o Trips RCP 1-3**

o Trips RCP 1-4**

(2.2.5.a, cont) Directs Implementation of remaining steps E-0, Reactor Trip or Safety Injection

- (Critical Task)(S5CT-1) Trip all four Reactor Coolant Pumps (RCPs)

(continued on next page)

- Critical Task L162 NRC ES-D-2-05 r0.docx Page 12 of 21 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 5 Event No.: 5 Page 13 of 17 Event

Description:

Loss of Seal Injection and Thermal Barrier Cooling / Reactor Trip (CT)

Time Position Applicants Actions or Behavior (OP AP-11, Section E: Loss of CCW Flow to RCPs )(Mark N/A if not used)

ALL

Reads CAUTION regarding Seal Outlet and RCP Radial Bearing Temperatures.

(1) Attempts to reestablish CCW flow to RCP lube oil coolers by opening -

o FCV-355, Header C Supply (VB1) o FCV-356, Supply to RCP and Rx Vessel Support Coolers (VB1) o FCV-749, RCP BRG OIL & SPRT CLR RTN ISO VLV (VB1) o FCV-363, RCP BRG OIL & SPRT CLRS RTN ISOL VLV O.C (VB1)

(1a RNO) Valves reclose and CCW flow to RCPs CANNOT be restored. RNO actions are assigned o (1.a.1) Trip the Reactor (ATC) o (1.a.2) Trips the affected RCPs (BOP)

RCP 1-1**

RCP 1-2**

RCP 1-3**

RCP 1-4**

- (Critical Task)(S5CT-1) Trip all four Reactor Coolant Pumps (RCPs)

Note: The loss of heat sink is expected to be evident shortly after reactor trip SRO Transitions to EOP E-0, Reactor Trip or Safety Injection.

(continued on next page)

- Critical Task L162 NRC ES-D-2-05 r0.docx Page 13 of 21 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 5 Event No.: 6 Page 14 of 17 Event

Description:

Loss of Secondary Heat Sink Time Position Applicants Actions or Behavior (EOP E-0, Reactor Trip or Safety Injection)

SRO/ATC * (1) Verifies reactor trip (trip breakers open(VB2 upper left), rods on bottom (VB2 upper left DRPI panel), NIs decreasing (CC1 left))

(2) Verifies turbine trip (stop valves closed) (CC3 HMI or VB2 RPS indicator lamps)

SRO/BOP * (3) Checks vital 4kv busses (VB4, vital buses G/H have a white lights on the mimic buses; bus F has a blue differential light indicating the bus has tripped)

SRO/ATC * (4) Checks if SI actuated (PK08-21 OFF, also checks SSPS ESF status lights on VB1 and PK02-02 to verify SI is NOT required)

ALL * (4 RNO) Checks AFW status (VB3), and determines there is no AFW flow.

MDAFW 1-2 OOS

MDAFW 1-3 has no power due to loss of bus F

TDAFW tripped on overspeed ALL Implements CSFSTs Identifies RED PATH for Heat Sink on CSFSTs SRO Enters EOP FR-H.1 (LOSHS) due to loss of AFW (complete) and low S/G levels (continued on next page)

- Critical Task L162 NRC ES-D-2-05 r0.docx Page 14 of 21 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 5 Event No.: 6 Page 15 of 17 Event

Description:

Loss of Secondary Heat Sink (cont)

Time Position Applicants Actions or Behavior (FR-H.1, Response to Loss of Secondary Heat Sink)

SRO * (1) Determines total feedflow less than 435 gpm is NOT the result of operator actions SRO/BOP * (2) Determines Secondary Heat Sink is required

(a) RCS Pressure is GREATER than any intact S/G ; (RCS pressure (VB2); S/G pressure (VB3))

(b) RCS Hot Leg Temp is GREATER than 350oF; (VB2, lower (chart recorder))

SRO/ATC * (3) Checks at least one ECCS CCP available

1-2 CCP is "available" (green and white lights lit) (VB2)

SRO/BOP * (4.a) Verifies Blowdown and Sample isolation valves outside containment are closed (VB3, lower left skirt)

(4.b.2) Verifies none of the AFW pumps are running (VB3, middle)

(4.b-c RNOs) Dispatches operators to locally check lineups and investigate pump trips; May check on status on getting AFW 1-2 returned to service.

(5) Notes RCPs are already stopped.(VB2, right)

(6) Adjusts 40% dump controllers to 1005 psig, (83.8% setpoint) (CC3, far left)

(continued on next page)

- Critical Task L162 NRC ES-D-2-05 r0.docx Page 15 of 21 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 5 Event No.: 6 Page 16 of 17 Event

Description:

Loss of Secondary Heat Sink (cont)

Time Position Applicants Actions or Behavior (FR-H.1, Response to Loss of Secondary Heat Sink)

SRO/BOP Reads CAUTION regarding monitoring of Hotwell level

(7.a) Checks at least one Condensate Booster Pump Set running in recirc (VB3, 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)

(continued on next page)

- Critical Task L162 NRC ES-D-2-05 r0.docx Page 16 of 21 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Op-Test No.: L162-NRC Scenario No.: 5 Event No.: 6 Page 17 of 17 Event

Description:

Loss of Secondary Heat Sink (cont) (CT)

Time Position Applicants Actions or Behavior (FR-H.1, Response to Loss of Secondary Heat Sink)

SRO/BOP * (7.d) Establishes Main Feedwater flow capability

(7.d.1) Determines Condenser is available, C9 (PK08-14) is ON

(7.d.2) Checks MSIVS OPEN

(7.d.3) Checks manual isolation for HP steam to MFW Pumps - OPEN

(7.d.4) Determines both Main Feedwater Pumps are available, but not latched; goes to RNO

(7.d.4) Restarts MFW Pump a) Ensure FCV-53 AND FCV-54 switches in RECIRC.

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

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

d) Press RAMP UP TO IDLE, ensure ramp to ~ 600 RPM.

e) Press IDLE TO STANDBY, ensure ramp to ~ 3000 RPM.

(7.d.5) Raises MFW Pp speed until discharge pressure is 100 PSIG GREATER THAN S/G Pressure SRO/ATC * (7.d.6) Checks PK09-11, FEEDWATER ISOLATION - OFF

(7.d.7) Throttles open Mn Fdwtr Cont Bypass Vlvs OR Mn Fdwtr Cont Vlvs

(8.a) Determines S/G NR Levels are NOT GREATER THAN 15% in at least one S/G (8.a RNO) Verifies and maintains Feedflow to at least one S/G such that

WR S/G Level is rising **

Core Exit TCs are lowering**

- (S5CT-2) Establish a secondary heat sink prior to reaching bleed and feed criteria.

Terminate the scenario once secondary side heat sink has been reestablished (completion of S5CT-2), per the Lead Examiner

- Critical Task L162 NRC ES-D-2-05 r0.docx Page 17 of 21 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Attachment 1 - Scenario Set-up & Booth Actions X = manual entry required TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION X IC RESTORE 154 100% power MOL, CB - 919 X Setup N/A MDAFW 1-2 OOS The Plant Abnormal Status Board for Surveillance Requirements None Copies of Procedures, Attachments; Appendixes; Foldout Pages; OP B-1A:I, OP E-5:IVPK01-08, PK04-22, PK05-01, 02, 03, 04, PK05-20, PK05-23, PK14-19, PK18-23, AP-11, AP-13, AP-25, AP-28, AP-30 EOP E-0, E-0.1, FR-H.1 Annunciator Response Procedures and commonly used forms are in binders and NOT Marked up X 0 min Tools > Simple SBT Before crew takes the watch.

Use Simple SBT, Data Recorder File: sbt_sim.drb, min 960 iterations (30 sec).

Critical Task Specific Data Capture:

S5CT1: RCP Breaker Position

S5CT2: AFW Flow, S/G Level, CETs X 0 min Lesson L161 NRC-S5.lsn After SFM reports the crew has taken the watch, load session MALS, OVRs, etc. by FILE or MANUALLY (below)

X Evt-1: PCV-455C drifts When contacted as Turbine Watch, remove power from 8000A after 5 minute open delay using field action portion of lesson file (Remove Pwr From 8000A)

(approx. 3 min after taking watch per lead examiner)

X Evt-2: ASWP 1-1 Gnd When contacted as Turbine Watch, report check at 4kV breaker for ASW 1-1 (Once Evt-1 TS have indicates low reading for Ammeter Selector position 1. Delay approximately 5 been addressed, per minutes prior to making report. If directed to clear ASW pump 1-1, use Field lead examiner) Action portion of lesson file (Clear ASW 1-1)

X Evt-3: Partial Runback When dispatched as Turbine Watch to check stator cooling, wait until runback has on Stator Cooling loss cleared (925 MW). Report backup pump is running, no clear indication of what (Once Evt-2 TS have caused the in-service pump to trip.

been addressed, per lead examiner)

X Evt-4: Seal Inj Filter When dispatched as Aux Watch, report filter dP reading slightly over 60 #s (after 5 Plugged minute delay)

(Triggers off boration 15 gal from finish)

X Evt-5: Spurious Phase Partial Phase B caused by single SSPS relay. Critical Task to trip all four RCPs due to B (single SSPS relay) a loss of all cooling and potential for catastrophic failure of the pumps.

(Once charging control re-est, per lead examiner)

(cont on next page)

L162 NRC ES-D-2-05 r0.docx Page 18 of 21 Rev 0

Appendix D (rev 11) Required Operator Actions Form ES-D-2 Attachment 1 - Scenario Set-up & Booth Actions (cont)

X = manual entry required A = activate from EVENT file TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Evt-6A: Trip of Trip of FW pumps added to ensure low S/G level for entry into FR-H.1.

TDAFW and FW Main feed will be success path to restore secondary side cooling.

Pumps; loss of 4kV When dispatched as Aux Watch to check on TDAFW pump, after 4 Bus F - Post Trip minutes, report trip latch mechanism has shattered; unable to reset pump.

If contacted regarding status of MDAFW 1-2, report minimum estimate for RTS is 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

Evt-6B: Loss of 4kV Loss of 4kV Bus F causes loss of MDAFW 1-3. Files to support AP-27 for Bus F - Post Trip loss of Bus F are contained in the Field Actions branch of the lesson file.

L162 NRC ES-D-2-05 r0.docx Page 19 of 21 Rev 0

Diablo Canyon Power Plant Operations Shift Log Unit 1 Unit 1 Days at Power: 110 Days Operating Mode: 1 Gross Generation: 1197 MWe Power Level: 100% Net Generation: 1147 MWe Today - Dayshift Shift Manager Turnover:

PRA RISK STATUS NEXT SHIFT: Green GRID STATUS NEXT SHIFT: Normal AVERAGE RCS CALCULATED LEAKRATE: 0.01 gpm CONDENSER INLEAKAGE: < 0.01 gpd CONDENSER D/Ps: NW 4.9 SW 4.4 NE 4.3 SE 4.1 PSID MAIN GENERATOR H2 USAGE: 325 scfd / 327 scfd 5 day ave SPENT FUEL POOL: Temp = 80oF; Time to 200oF = 30 hrs using actual temp (F-ID-7A)

NEW PRIORITY WORK:

AFW 1-2 emergent motor bearing oil leak identified end of last shift.

SHUTDOWN TECH SPECS / ECGS:

TS 3.7.5.B AFW 1-2, due in 65 hours7.523148e-4 days 0.0181 hours 1.074735e-4 weeks 2.47325e-5 months .

ECG ACTIONS THAT IF COMPLETION TIME NOT MET ECG 0.3 IS ENTERED:

None TURNOVER ITEMS:

None PRIORITY ITEMS FOR NEXT SHIFT:

Maintain current power level.

Shift Foreman Turnover ANNUNCIATORS IN ALARM:

There are no unexpected alarms - all current alarms are consistent with current mode and power level.

TURNOVER ITEMS:

U-1: maintain 100% - no one in containment.

U-2: maintain 100%.

REACTIVITY MANAGEMENT:

Time in core life: _MOL_.

Power History: Steady State at 100% for past 111 days.

Boron concentration is _878 ppm_ from a sample taken 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago.

Control Rod Height: 229 steps on CBD.

Diluting the RCS approximately 25 gallons every 1.5 hrs.

The last dilution was completed _30_ min ago.

CONDITIONAL SURVEILLANCES & INCREASED MONITORING:

None OTHER ABNORMAL PLANT STATUS

None

ES-301 Transient and Event Checklist Form ES-301-5 Group I (I1, I2, R1, R2)

Facility: DCPP Date of Exam: Jan 19, 2018 Operating Test Number: L162 A E Scenarios P V Day-1 (S4) Day-2 (S1) Day-3 (S2) Day-4 (S5)

P E T M L N CREW CREW CREW CREW O I I T POSITION POSITION POSITION POSITION T N C A I A T S A B S A B S A B S A B L M N Y R T O R T O R T O R T O U T P O C P O C P O C P O C P M(*)

E R I U RX 1 1 0 RO1 NOR 1 1 1 SRO-I I/C 1,3,7 2,3,5,7,8 1,2,4,6,7 13 4 4 2 SRO-U MAJ 5,6 6,9 5 5 2 2 1 TS 0 0 2 2 RX 1 1 1 1 0 RO2 NOR 1 1 1 SRO-I I/C 1,3,4,7,8 3,4,5 1,2,6 11 4 4 2 SRO-U MAJ 5,6 6,9 5 5 2 2 1 TS 0 0 2 2 RX 1 1 0 RO NOR 1 1 1 SRO-I1 I/C 1,3,4,7 1,2,4 3,4,6 10 4 4 2 SRO-U MAJ 5,6 5 5 4 2 2 1 TS 1,2 2,3 4 0 2 2 RX 1 1 1 1 0 RO NOR 1 1 1 SRO-I2 I/C 2,3,4,5 2,4,8 1,2,3,4,6 12 4 4 2 SRO-U MAJ 6,9 5 5 4 2 2 1 TS 2,3,5 1,2 5 0 2 2 Instructions:

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

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

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

4. For new reactor facility licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO I applicants in either the ATC or BOP position to best evaluate the SRO I in manipulating plant controls.

ES-301, Page 26 of 27 Rev 1

ES-301 Transient and Event Checklist Form ES-301-5 Group II (I3, I4, R3, R4)

Facility: DCPP Date of Exam: Jan 19, 2018 Operating Test Number: L162 A E Scenarios P V Day-1 (S4) Day-2 (S1) Day-3 (S2) Day-4 (S5)

P E T M L N CREW CREW CREW CREW O I I T POSITION POSITION POSITION POSITION T N C A I A T S A B S A B S A B S A B L M N Y R T O R T O R T O R T O U T P O C P O C P O C P O C P M(*)

E R I U RX 1 1 0 RO3 NOR 1 1 1 SRO-I I/C 1,3,7 2,3,5,7,8 1,2,4,6,7 13 4 4 2 SRO-U MAJ 5,6 6,9 5 5 2 2 1 TS 0 0 2 2 RX 1 1 1 1 0 RO4 NOR 1 1 1 SRO-I I/C 1,3,4,7,8 3,4,5 1,2,6 11 4 4 2 SRO-U MAJ 5,6 6,9 5 5 2 2 1 TS 0 0 2 2 RX 1 1 0 RO NOR 1 1 1 SRO-I2 I/C 1,3,4,7 1,2,4 3,4,6 10 4 4 2 SRO-U MAJ 5,6 5 5 4 2 2 1 TS 1,2 2,3 4 0 2 2 RX 1 1 1 1 0 RO NOR 1 1 1 SRO-I3 I/C 2,3,4,5 2,4,8 1,2,3,4,6 12 4 4 2 SRO-U MAJ 6,9 5 5 4 2 2 1 TS 2,3,5 1,2 5 0 2 2 Instructions:

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

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

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

4. For new reactor facility licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO I applicants in either the ATC or BOP position to best evaluate the SRO I in manipulating plant controls.

ES-301, Page 26 of 27 Rev 1

ES-301 Transient and Event Checklist Form ES-301-5 Group III (I5, R5, R6)

Facility: DCPP Date of Exam: Jan 19, 2018 Operating Test Number: L162 A E Scenarios P V Day-1 (S4) Day-2 (S1) Day-3 (S2) Day-4 (S5)

P E T M L N CREW CREW CREW CREW O I I T POSITION POSITION POSITION POSITION T N C A I A T S A B S A B S A B S A B L M N Y R T O R T O U T O R T O U T P O C P O C P R C P O C P M(*)

E R I U RX 1 1 0 RO5 NOR 1 1 1 SRO-I I/C 1,3,7 2,3,5,7,8 1,2,4,6,7 13 4 4 2 SRO-U MAJ 5,6 6,9 5 5 2 2 1 TS 0 2 2 RX 1 1 1 1 0 RO6 NOR 1 1 1 SRO-I I/C 1,3,4,7,8 3,4,5 8 4 4 2 SRO-U MAJ 5,6 6,9 4 2 2 1 TS 0 2 2 RX 1 1 1 1 0 RO NOR 1 1 1 SRO-I5 I/C 1,3,4,7 2,3,4,5 2,4,8 11 4 4 2 SRO-U MAJ 5,6 6,9 5 5 2 2 1 TS 1,2 2,3,5 5 0 2 2 RX 1 1 0 RO NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2 Instructions:

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

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

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

4. For new reactor facility licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO I applicants in either the ATC or BOP position to best evaluate the SRO I in manipulating plant controls.

ES-301, Page 26 of 27 Rev 1

ES-301 Transient and Event Checklist Form ES-301-5 Group IV (I6, R7, R8)

Facility: DCPP Date of Exam: Jan 19, 2018 Operating Test Number: L162 A E Scenarios P V Day-1 (S4) Day-2 (S1) Day-3 (S2) Day-4 (S5)

P E T M L N CREW CREW CREW CREW O I I T POSITION POSITION POSITION POSITION T N C A I A T S A B S A B S A B S A B L M N Y R T O R T O U T O R T O U T P O C P O C P R C P O C P M(*)

E R I U RX 1 1 0 RO5 NOR 1 1 1 SRO-I I/C 1,3,7 2,3,5,7,8 1,2,4,6,7 13 4 4 2 SRO-U MAJ 5,6 6,9 5 5 2 2 1 TS 0 2 2 RX 1 1 1 1 0 RO6 NOR 1 1 1 SRO-I I/C 1,3,4,7,8 3,4,5 8 4 4 2 SRO-U MAJ 5,6 6,9 4 2 2 1 TS 0 2 2 RX 1 1 1 1 0 RO NOR 1 1 1 SRO-I5 I/C 1,3,4,7 2,3,4,5 2,4,8 11 4 4 2 SRO-U MAJ 5,6 6,9 5 5 2 2 1 TS 1,2 2,3,5 5 0 2 2 RX 1 1 0 RO NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2 Instructions:

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

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

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

4. For new reactor facility licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO I applicants in either the ATC or BOP position to best evaluate the SRO I in manipulating plant controls.

ES-301, Page 26 of 27 Rev 1

ES-301 Transient and Event Checklist Form ES-301-5 Spare Facility: DCPP Date of Exam: Jan 19, 2018 Operating Test Number: L162 A E Scenarios P V Spare Day-2 (S1) Day-3 (S2) Day-4 (S5)

P E T M L N CREW CREW CREW CREW O I I T POSITION POSITION POSITION POSITION T N C A I A T S A B S A B S A B S A B L M N Y R T O R T O R T O R T O U T P O C P O C P O C P O C P M(*)

E R I U RX 3 3 3 1 1 0 RO NOR 1 1 1 SRO-I I/C 1,2,4 4,6 1,2,6 4 4 2 SRO-U MAJ 5 5 5 2 2 1 TS 1,4 0 2 2 RX 1 1 0 RO NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2 RX 1 1 0 RO NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2 RX 1 1 0 RO NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2 Instructions:

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

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

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

4. For new reactor facility licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO I applicants in either the ATC or BOP position to best evaluate the SRO I in manipulating plant controls.

ES-301, Page 26 of 27 Rev 1

ES-301 Competencies Checklist Form ES-301-6 Facility: DCPP Date of Examination: January 19, 2018 Operating Test No.: L162 GROUP I APPLICANTS RO RO RO1 RO2 SRO-I1 SRO-I2 SRO-I SRO-I Competencies SRO-U SRO-U SRO-U SRO-U SCENARIO SCENARIO SCENARIO SCENARIO 1 2 4 5 1 2 4 5 1 2 4 5 1 2 4 5 Interpret/ Diagnose 2,3,4,5, 1,2,3,4, 3,4,5,6 1,2,3,4, 6,7,8 5,6,7,8 5,6,7,8, 1,2,3,4, 5,6,7,8 1,2,3,4, 2,3,4,5, 1,2,3,4, 2,3,5,8 5,6 6,7,8 5,6,7,8 1,2,3,4, 5,6,9 1,3,4,5, 1,2,3,4, 6,7,8 5,6 9

Events and Conditions Comply With and Use 1,2,6,7, 1,2,3,4, 3,4,5,6 1,2,3,4, 2,4,5,6, 8 5,6,7,8 5,6,9 7,8 1,2,3,4, 2,3,5,6, 1,2,4,5, 1,3,6,7 5,6 7,8,9 6,7,8 1,3,4,5 6,9 1,3,6,7, 1,2,5,6 8

Procedures (1)

Operate Control 3,4,5,6 2,4,5,8 2,3,5,6, 1,2,4,5, 1,3,5,6, 7,8,9 6,7 7 1,3,4,5, 6,9 1,2,3,4, 1,2,5,6 5,6,7,8 Boards (2)

Communicate 1,2,3,4, 1,2,3,4, 2,3,4,5, 1,2,3,4, 5,6,7,8 5,6,7,8 6 5,6,7,8, 1,2,3,4, 5,6,7,8 1,2,3,4, 2,3,5,6, 1,2,3,4, 1,2,3,4, 5,6 7,8,9 5,6,7,8 5,6,7,8 1,3,4,5, 6,9 1,2,3,4, 1,2,3,4, 5,6,7,8 5,6 9

and Interact Demonstrate 1,2,4,5, 1,2,4,5, 6,7,8 6,8 1,2,3,4, 5,6,9 1,2,3,4, 5,6 Supervisory Ability (3)

Comply With and 1,2 2,3 2,3,5 1,2 Use Tech Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant. (This includes all rating factors for each competency.) (Competency Rating factors as described on forms ES-303-1 and ES-303-3.)

ES-301, Page 27 of 27

ES-301 Competencies Checklist Form ES-301-6 Facility: DCPP Date of Examination: January 19, 2018 Operating Test No.: L162 GROUP II APPLICANTS RO RO RO3 RO4 SRO-I3 SRO-I4 SRO-I SRO-I Competencies SRO-U SRO-U SRO-U SRO-U SCENARIO SCENARIO SCENARIO SCENARIO 1 2 4 5 1 2 4 5 1 2 4 5 1 2 4 5 Interpret/ Diagnose 2,3,4,5, 1,2,3,4, 3,4,5,6 1,2,3,4, 6,7,8 5,6,7,8 5,6,7,8, 1,2,3,4, 5,6,7,8 1,2,3,4, 2,3,4,5, 1,2,3,4, 2,3,5,8 5,6 6,7,8 5,6,7,8 1,2,3,4, 5,6,9 1,3,4,5, 1,2,3,4, 6,7,8 5,6 9

Events and Conditions Comply With and Use 1,2,6,7, 1,2,3,4, 3,4,5,6 1,2,3,4, 2,4,5,6, 8 5,6,7,8 5,6,9 7,8 1,2,3,4, 2,3,5,6, 1,2,4,5, 1,3,6,7 5,6 7,8,9 6,7,8 1,3,4,5 6,9 1,3,6,7, 1,2,5,6 8

Procedures (1)

Operate Control 3,4,5,6 2,4,5,8 2,3,5,6, 1,2,4,5, 1,3,5,6, 7,8,9 6,7 7 1,3,4,5, 6,9 1,2,3,4, 1,2,5,6 5,6,7,8 Boards (2)

Communicate 1,2,3,4, 1,2,3,4, 2,3,4,5, 1,2,3,4, 5,6,7,8 5,6,7,8 6 5,6,7,8, 1,2,3,4, 5,6,7,8 1,2,3,4, 2,3,5,6, 1,2,3,4, 1,2,3,4, 5,6 7,8,9 5,6,7,8 5,6,7,8 1,3,4,5, 6,9 1,2,3,4, 1,2,3,4, 5,6,7,8 5,6 9

and Interact Demonstrate 1,2,4,5, 1,2,4,5, 6,7,8 6,8 1,2,3,4, 5,6,9 1,2,3,4, 5,6 Supervisory Ability (3)

Comply With and 1,2 2,3 2,3,5 1,2 Use Tech Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant. (This includes all rating factors for each competency.) (Competency Rating factors as described on forms ES-303-1 and ES-303-3.)

ES-301, Page 27 of 27

ES-301 Competencies Checklist Form ES-301-6 Facility: DCPP Date of Examination: January 19, 2018 Operating Test No.: L162 GROUP III APPLICANTS RO RO5 RO6 RO SRO-I5 SRO-I SRO-I SRO-I Competencies SRO-U SRO-U SRO-U SRO-U SCENARIO SCENARIO SCENARIO SCENARIO 1 2 4 5 1 2 4 5 1 2 4 5 1 2 4 5 Interpret/ Diagnose 1,2,3,4, 1,2,3,4, 1,2,3,4, 5,6,7,8, 5,6,7,8 5,6,7,8 2,3,4,5, 1,2,3,4, 2,3,5,8 6,7,8 5,6,7,8 1,2,3,4, 5,6,9 1,3,4,5, 6,7,8 9

Events and Conditions Comply With and Use 1,2,3,4, 2,4,5,6, 1,2,3,4, 5,6,9 7,8 5,6,7,8 2,3,5,6, 1,2,4,5, 1,3,6,7 7,8,9 6,7,8 1,3,4,5 6,9 1,3,6,7, 8

Procedures (1)

Operate Control 2,4,5,8 2,3,5,6, 1,2,4,5, 1,3,5,6, 7,8,9 6,7 7 1,3,4,5, 6,9 1,2,3,4, 5,6,7,8 Boards (2)

Communicate 1,2,3,4, 1,2,3,4, 1,2,3,4, 5,6,7,8, 5,6,7,8 5,6,7,8 2,3,5,6, 1,2,3,4, 1,2,3,4, 7,8,9 5,6,7,8 5,6,7,8 1,3,4,5, 6,9 1,2,3,4, 5,6,7,8 9

and Interact Demonstrate 1,2,3,4, 5,6,9 1,2,4,5, 6,8 Supervisory Ability (3)

Comply With and 2,3,5 2,3 Use Tech Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant. (This includes all rating factors for each competency.) (Competency Rating factors as described on forms ES-303-1 and ES-303-3.)

ES-301, Page 27 of 27

ES-301 Competencies Checklist Form ES-301-6 Facility: DCPP Date of Examination: January 19, 2018 Operating Test No.: L162 GROUP IV APPLICANTS RO RO7 RO8 RO SRO-I6 SRO-I SRO-I SRO-I Competencies SRO-U SRO-U SRO-U SRO-U SCENARIO SCENARIO SCENARIO SCENARIO 1 2 4 5 1 2 4 5 1 2 4 5 1 2 4 5 Interpret/ Diagnose 1,2,3,4, 1,2,3,4, 1,2,3,4, 5,6,7,8, 5,6,7,8 5,6,7,8 2,3,4,5, 1,2,3,4, 2,3,5,8 6,7,8 5,6,7,8 1,2,3,4, 5,6,9 1,3,4,5, 6,7,8 9

Events and Conditions Comply With and Use 1,2,3,4, 2,4,5,6, 1,2,3,4, 5,6,9 7,8 5,6,7,8 2,3,5,6, 1,2,4,5, 1,3,6,7 7,8,9 6,7,8 1,3,4,5 6,9 1,3,6,7, 8

Procedures (1)

Operate Control 2,4,5,8 2,3,5,6, 1,2,4,5, 1,3,5,6, 7,8,9 6,7 7 1,3,4,5, 6,9 1,2,3,4, 5,6,7,8 Boards (2)

Communicate 1,2,3,4, 1,2,3,4, 1,2,3,4, 5,6,7,8, 5,6,7,8 5,6,7,8 2,3,5,6, 1,2,3,4, 1,2,3,4, 7,8,9 5,6,7,8 5,6,7,8 1,3,4,5, 6,9 1,2,3,4, 5,6,7,8 9

and Interact Demonstrate 1,2,3,4, 5,6,9 1,2,4,5, 6,8 Supervisory Ability (3)

Comply With and 2,3,5 2,3 Use Tech Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant. (This includes all rating factors for each competency.) (Competency Rating factors as described on forms ES-303-1 and ES-303-3.)

ES-301, Page 27 of 27

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