ML093200387

2009-08-DRAFT Operating Test

ML093200387
Person / Time
Site:	Wolf Creek
Issue date:	11/16/2009
From:	Apger G NRC Region 4
To:	Wolf Creek
References
50-482/09-301, ES-301, Rev 9, ES-301-1 50-482/09-301
Download: ML093200387 (289)

Text

ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1

{PRIVATE }Facility: ______Wolf Creek________ Date of Examination: __Aug 31 - Sept 4, 2009___

Examination Level: RO SRO X Operating Test Number: __________

Administrative Topic Type Code* Describe activity to be performed (see Note)

Complete a 1/M plot and determine the estimated critical Conduct of Operations R, M position and required actions.

(S.A.1.a) 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of operation. (CFR 41.10 / 43.5 /

45.2 / 45.6) (RO/SRO IR = 4.3 / 4.4)

Review completed dilution requirement calculation for one hour Conduct of Operations after a power reduction.

N, R (S.A.1.b) 2.1.37 Knowledge of procedures, guidelines or limitations associated with reactivity management. (CFR 41.1 / 43.6 /

45.6) (RO /SRO IR = 4.3 / 4.6)

Using a completed surveillance (STS AL-101, MDAFW Pump Equipment Control A Inservice Pump Test), evaluate acceptance criteria.

R, N (S.A.2) 2.2.12 Knowledge of surveillance procedures (CFR 41.10 /

45.13) (RO / SRO IR = 3.7 / 4.1)

Given a Liquid Release Permit determine if it is ready to be Radiation Control authorized for release to the environment.

N, R (S.A.3) 2.3.6 Ability to approve release permits. (CFR 41.13 / 43.4 /

45.10) (RO / SRO IR = 2.0 / 3.8)

In the simulator setting, perform the E-Plan classification.

Emergency Plan S, N 2.4.41 Knowledge of the emergency action level thresholds and classifications. (CFR 41.10 / 43.5 / 45.11) (RO/SRO IR = 2.9 /

(S.A.4) 4.6)

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

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

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

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

ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1

{PRIVATE }Facility: ______Wolf Creek________ Date of Examination: __Aug 31 - Sept 4, 2009___

Examination Level: RO x SRO Operating Test Number: __________

Administrative Topic Type Code* Describe activity to be performed (see Note)

Complete 1/M plot and determine the estimated critical Conduct of Operations position.

R, M (R.A.1.a) 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of operation. (CFR 41.10 / 43.5 /

45.2 / 45.6) (RO/SRO IR = 4.3 / 4.4)

Determine dilution requirements for one hour after a power Conduct of Operations reduction.

R, N (R.A.1.b) 2.1.37 Knowledge of procedures, guidelines or limitations associated with reactivity management. (CFR 41.1 / 43.6 /

45.6) (RO /SRO IR = 4.3 / 4.6)

Complete the calculation for surveillance STS AL-101, Equipment Control MDAFW Pump A Inservice Pump Test, evaluate/recommend N, R operable/inoperable and required actions.

(R.A.2) 2.2.12 Knowledge of surveillance procedures (CFR 41.10 /

45.13) (RO / SRO IR = 3.7 / 4.1)

Given radiological conditions evaluate the most efficient Radiation Control method to limit radiological exposure based on DAC hours.

R, N (R.A.3) 2.3.12 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. (CFR 41.12 / 45.9 /

45.10) (RO/SRO IR = 3.2 / 3.7)

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

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

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

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

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Wolf Creek Task No.: N/A Task

Title:

Given data, complete 1/M plot and JPM No.: R.A.1.a determine estimated critical rod position K/A

Reference:

2.1.23 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom x Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is in Hot Standby recovering from a short forced outage at middle of core life. The crew is performing a reactor startup in accordance with GEN 00-003, rev 72, Hot Standby To Minimum Load.

Figure 1, 1/M Plot, is provided.

Task Standard: Upon completion of the 1/M plot, the Examinee will determine that criticality will occur at a rod position BELOW minimum rod height (Bank C at 72 steps).

Required Materials: GEN 00-003, rev 72, Hot Standby to Minimum Load Figure 1 (from GEN 00-003), 1/M Plot Raw data Calculator, straight edge General

References:

GEN 00-003, rev 72, Hot Standby to Minimum Load SOER 88-2, Premature Criticality Events During Reactor Startup Handouts: GEN 00-003, rev 72, Hot Standby to Minimum Load Figure 1 (from GEN 00-003), 1/M Plot Raw data Initiating Cue: With the data supplied, complete the 1/M Plot. Determine the critical rod position per steps 6.20.5.2.

Time Critical Task: No

Appendix C Job Performance Measure Form ES-C-1 Worksheet Validation Time: 25 minutes

Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Performance Step: 1 Enter the supplied data on Figure 1 (Rod position and Cf section).

Standard: Enter the final rod position and final count rate (Cf) for each pull in the appropriate section. (See attached Key.)

Comment: GEN 00-003, step 6.20.5.2 Performance Step: 2 Calculate 1/M from data provided for each rod withdrawal sequence.

Standard: Calculate ratio from data provided. (See attached Key.)

Comment: GEN 00-003, step 6.20.5.2 Performance Step: 3 Determine estimated critical position for each rod withdrawal sequence.

Standard: For each calculated 1/M, place a point on the graph. Use a straight edge to locate the estimated critical position for each pull by taking the line from the last two plots out to the edge of the graph and comparing that position to the estimated critical position. (See attached Key.)

Comment: GEN 00-003, step 6.20.5.2

• Performance Step: 4 Inform Reactor Engineering (RXE) and maintain stable reactor conditions per GEN 00-003, step 6.20.5.3.

Standard: Realize that when rods are withdrawn to Bank B at 85 steps that flux is more than double its initial value.

Determine that estimated critical position is BELOW minimum rod height. (Bank C at 55 steps is BELOW minimum rod height Bank C at 72 steps.)

Comment: GEN 00-003, step 6.20.5.3 Terminating Cue: JPM is complete

Appendix C Page 4 of 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: R.A.1.a, Given data, complete 1/M plot and determine estimated critical rod position Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

Appendix C Page 5 of 6 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: The Plant is in Hot Standby recovering from a short forced outage at middle of core life. The crew is performing a reactor startup in accordance with GEN 00-003, rev 72, Hot Standby To Minimum Load. Figure 1, 1/M Plot, is provided.

INITIATING CUE: With the data supplied, complete the 1/M Plot. Determine the critical rod position per steps 6.20.5.2.

Maximum rod height Bank D at 81 steps Estimated critical position Bank D at 29 steps Minimum rod height Bank C at 72 steps Initial Count rate 520 cps Source Range NI-31 response to rod withdrawal Rod Position A50 A100 B35 B85 B135 Channel NI 31 SR 31 SR 31 SR 31 SR 31 SR 31 Final Counts (Cf) 592 735 852 1120 2600

Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Wolf Creek Task No.: N/A Task

Title:

Calculate Dilution for Power JPM No.: R.A.1.b Increase 1 Hour after Downpower K/A

Reference:

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom x Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The following plant conditions exist:

• Reactor and Turbine power have been reduced to 90% at 1%/min due to a steam leak in the Turbine Building.

• OFN MA-038, Rapid Plant Shutdown, was used to decrease power.

• RCS boron concentration is 688 ppm after the power reduction.

• The Information Services server for Paperless Environment is Out of Service.

Task Standard: Examinee completes calculation - determines ~648 gallons of water is necessary for the dilution.

Required Materials: WCRX-022 Curves and Tables, page 87. WCRX-01 Boration and Dilution Tables General

References:

OFN MA-038, rev 11, Rapid Plant Shutdown Handouts: WCRX-022 Curves and Tables dated 5/1/09. WCRX-01 Boration and Dilution Tables Initiating Cue: The Control Room Supervisor directs you to determine the required dilution amount for one hour after the power reduction.

Time Critical Task: No Validation Time: 25 minutes

Appendix C Page 2 of 4 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Performance Step: 1 Refers to Curves and Tables book, page 7.10 Rev 23, Reactivity Plan for Rapid Downpower Standard: Locates table for Dilution During 1 h Following Reduction Comment:

Performance Step: 2 Determines that a dilution of 6.8 ppm is required.

Standard: In the table references the section for a 1%/min power reduction to 90% is 6.8 ppm.

Comment:

• Performance Step: 3 Refers to the Boration/Dilution Tables for an initial boron concentration of 688 ppm and RCS temp of 585°F.

Standard: From the table determines that a combination of dilution for 5 ppm and 2 ppm result in the required dilution. A double interpolation of the tables results in a dilution of 648 gallons.

Comment:

• Performance Step: 4 Determines that the dilution amount is 474.4 for 5 ppm and 189.3 for 2 ppm.

Standard: Recommends a dilution of 648 gallons of water. (Acceptable range of 615 to 680 gallons of water)

Comment:

Terminating Cue: JPM is complete

Appendix C Page 3 of 4 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: R.A.1.b, Calculate Dilution for Power Increase 1 Hour after Downpower Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

Appendix C Page 4 of 4 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: The following plant conditions exist:

• Reactor and Turbine power have been reduced to 90% at 1%/min due to a steam leak in the turbine building.

• OFN MA-038 was used to decrease power.

• RCS boron Concentration is 688 ppm after the power reduction.

• The Information Services server for Paperless Environment is Out of Service.

INITIATING CUE: The Control Room Supervisor directs you to determine the required dilution amount for one hour after the power reduction.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Wolf Creek Task No.: N/A Task

Title:

Complete the Data Sheet for STS JPM No.: R.A.2 AL-101 MD AFW Pump A Inservice Test K/A

Reference:

2.2.12 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom x Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The following plant conditions exist:

• The plant is in Mode 1 at full power.

• No equipment is Out of Service.

• The CRS and the BOP have been performing STS AL-101, MD AFW Pump A Inservice Test.

• The BOP has been called away for a random Fitness for Duty assessment.

Task Standard: Completes calculations at step 9.3. Determines pump dP is SAT. Pump is operable. No corrective actions are initiated based on Attachment A or B data.

Required Materials: Partially complete STS AL-101, MD AFW Pump A Inservice Test General

References:

None Handouts: Partially complete STS AL-101, MD AFW Pump A Inservice Test

Appendix C Job Performance Measure Form ES-C-1 Worksheet Initiating Cue: The CRS directs you to complete Attachment A of the STS. Data required are documented in the procedure at the applicable step.

The CRS directs you to complete Attachment A of the STS. Data required are documented in the procedure at the applicable step.

Circle the correct choice from below:

The pump is operable/inoperable.

Corrective action is required/not required.

Time Critical Task: No Validation Time: 25 minutes

Appendix C Page 3 of 5 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Performance Step: 1 Refers to STS AL-101 and determines that step 9.3 is not complete.

Standard: Step 9.3 has no data and is not signed off.

Comment:

• Performance Step: 2 Determines that pump delta P is 1638.8 +/- .3 psid.

Standard: Completes step 9.3, calculates the psid, transfers the data to Attachment A, and circles the S in the S/U column.

Comment: Data collection at step 8.16; Calculation at 9.3

• Performance Step: 3 Determine if the pump is operable or inoperable.

Standard: The pump is operable.

Comment:

• Performance Step: 4 Determine if corrective action is required or not required.

Standard: Corrective action is not required.

Comment:

Terminating Cue: JPM complete

Appendix C Page 4 of 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: R.A.2, Complete the Data Sheet for STS AL-101, MD AFW Pump A Inservice Test Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

Appendix C Page 5 of 5 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: The following plant conditions exist:

• The plant is in Mode 1 at full power.

• No equipment is Out of Service.

• The CRS and the BOP have been performing STS AL-101, MD AFW Pump A Inservice Test

• The BOP has been called away for a random Fitness for Duty assessment..

INITIATING CUE: The CRS directs you to complete Attachment A of the STS. Data required are documented in the procedure at the applicable step.

Circle the correct choice from below:

The pump is operable/inoperable.

Corrective action is required/not required.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Wolf Creek Task No.: N/A Task

Title:

Determine DAC hours JPM No.: R.A.3 K/A

Reference:

2.3.12 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom x Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: You are the Balance of Plant Operator and Job Lead.

Task Standard: Upon completion of this JPM, the Examinee will have calculated the dose an NSO would receive working a job with and without wearing a full-face respirator and determined which provides the NSO with less dose received for the job.

Required Materials: Radiation Work Permit (RWP) 091001; Calculator General

References:

Radiation Work Permit (RWP) 091001 Handouts: Radiation Work Permit (RWP) 091001; Calculator Initiating Cue: An NSO is assigned a job in Containment to tag and drain some ECCS piping. Determine whether or not wearing a full-face respirator would be appropriate for the NSO completing the job. Show all calculations.

Time Critical Task: No Validation Time: 25 minutes

Appendix C Page 2 of 5 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

An NSO is assigned a job in Containment to tag and drain some ECCS piping. Determine whether or not wearing a full-face respirator would be appropriate for the NSO completing the job. Show all calculations.

RWP 091001 rev 3, task 4, Containment Building Tag out (Venting and Draining).

Health Physics technician states that there is a 23 mRem/hour background radiation field. The air sample taken in the area indicates a 1.5 DAC-hour field.

Historical data shows that the job takes two hours. It takes ~20% longer to do the job when wearing a full-face respirator.

Protection factor of a full-face respirator is 50.

1 DAC-hour = 2.5 mRem Performance Step: 1 Determine dose without wearing a full-face respirator.

Standard: (2 hr x 23 mRem/hr) + (2 hr x 1.5 DAC-hr x 2.5 mRem/DAC-hr) 46 mRem + 7.5 mRem 53.5 mRem received without wearing a full-face respirator Comment:

Performance Step: 2 Determine dose while wearing a full-face respirator.

Standard: It takes ~20% longer to perform the task while wearing a full-face respirator. So instead of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, it is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, 24 minutes or 2.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

(2.4 hr x 23 mRem/hr) + (2.4 hr x 1.5 DAC-hr x 2.5 mRem/DAC-hr)/50 protection factor 55.2 + 0.18 mRem 55.38 mRem received while wearing a full-face respirator Comment:

Appendix C Page 3 of 5 Form ES-C-1 PERFORMANCE INFORMATION

• Performance Step: 3 Should NSO wear the full-face respirator based on calculations performed?

Standard: Do not wear the full-face respirator. Less dose is received by the NSO.

53.5 mRem in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> < 55.38 mRem in 2.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Terminating Cue: JPM complete

Appendix C Page 4 of 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: R.A.3, Determine DAC hours Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

Appendix C Page 5 of 5 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: You are the Balance of Plant Operator and Job Lead.

INITIATING CUE: An NSO is assigned a job in Containment to tag and drain some ECCS piping.

RWP 091001 rev 3, task 4, Containment Building Tag out (Venting and Draining).

Health Physics technician states that there is a 23 mRem/hour background radiation field. The air sample taken in the area indicates a 1.5 DAC-hour field.

Historical data shows that the job takes two hours. It takes ~20%

longer to do the job when wearing a full-face respirator.

Protection factor of a full-face respirator is 50.

1 DAC-hour = 2.5 mRem Determine whether or not wearing a full-face respirator would be appropriate for the NSO completing the job. Show all calculations.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Wolf Creek Task No.: N/A Task

Title:

Complete the 1/M plot and JPM No.: S.A.1.a determine estimated critical rod position and any required actions K/A

Reference:

2.1.23 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom x Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is in Hot Standby recovering from a short forced outage at middle of core life. The crew is performing a reactor startup in accordance with GEN 00-003, rev 72, Hot Standby To Minimum Load.

Figure 1, 1/M Plot, is provided.

Task Standard: The Examinee will determine that criticality will occur at a rod position BELOW the zero power rod insertion limit (Bank C at 46 steps).

Required actions per GEN 00-003, rev 72, Hot Standby to Minimum Load, are:

1. Immediately insert all control banks

2. Emergency borate to reestablish required shutdown Required Materials: GEN 00-003, rev 72, Hot Standby to Minimum Load Figure 1 (from GEN 00-003), 1/M Plot Raw data Calculator, straight edge General

References:

GEN 00-003, rev 72, Hot Standby to Minimum Load SOER 88-2, Premature Criticality Events During Reactor Startup Handouts: GEN 00-003, rev 72, Hot Standby to Minimum Load Figure 1 (from GEN 00-003), 1/M Plot Raw data Initiating Cue: With the data supplied, complete the 1/M Plot. Determine the critical rod position per steps 6.20.5.2 and determine the required actions.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: No Validation Time: 25 minutes

Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Performance Step: 1 Complete the 1/M plot - enter the supplied data on Figure 1.

Standard: Enter the final rod position and final count rate (Cf) for each pull in the appropriate section. (See attached Key.)

Comment: GEN 00-003, step 6.20.5.2 Performance Step: 2 Calculate the 1/M from data provided for each rod withdrawal sequence.

Standard: Calculate ratio from data provided. (See attached Key.)

Comment: GEN 00-003, step 6.20.5.2 Performance Step: 3 Determine estimated critical position for each rod withdrawal sequence.

Standard: For each calculated 1/M, place a point on the graph. Use a straight edge to locate the estimated critical position for each pull by taking the line from the last two plots out to the edge of the graph and comparing that position to the estimated critical position. (See attached Key.)

Comment: GEN 00-003, step 6.20.5.2

• Performance Step: 4 Determine actions per GEN 00-003, step 6.20.5.3.

Standard: The Examinee will determine that criticality will occur at a rod position BELOW the zero power rod insertion limit (Bank C at 46 steps). Required actions per GEN 00-003, rev 72, Hot Standby to Minimum Load, are:

1. Immediately insert all control banks

2. Emergency borate to reestablish requires shutdown Comment: GEN 00-003, step 6.20.5.3 Terminating Cue: JPM is complete

Appendix C Page 4 of 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: S.A.1.a, Complete the 1/M plot and determine estimated critical rod position and any required actions Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

Appendix C Page 5 of 6 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: The Plant is in Hot Standby recovering from a short forced outage at middle of core life. The crew is performing a reactor startup in accordance with GEN 00-003, rev 72, Hot Standby To Minimum Load. Figure 1, 1/M Plot, is provided.

INITIATING CUE: With the data supplied, complete the 1/M Plot. Determine the critical rod position per steps 6.20.5.2.

Maximum rod height Bank D at 81 steps Estimated critical position Bank D at 29 steps Minimum rod height Bank C at 72 steps Initial Count rate 520 cps Source Range NI-31 response to rod withdrawal Rod Position A50 A100 B35 B85 B135 Channel NI 31 SR 31 SR 31 SR 31 SR 31 SR 31 Final Counts (Cf) 592 735 852 1120 4350

Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Wolf Creek Task No.: N/A Task

Title:

Approve Dilution for Power Increase JPM No.: S.A.1.b 1 Hour after Downpower K/A

Reference:

2.1.37 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom x Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The following plant conditions exist:

• Reactor and Turbine power have been reduced to 90% at 1%/min due to a steam leak in the Turbine Building.

• OFN MA-038, Rapid Plant Shutdown, was used to decrease power.

• RCS boron concentration is 688 ppm after the power reduction.

• The Information Services server for Paperless Environment is Out of Service.

Task Standard: Examinee determines that the dilution calculation as completed by the Reactor Operator is incorrect and does not approve the dilution calculation. Examinee discovers errors:

1. 6.6 ppm (0.5% /min power reduction)

2. total of 495 gallons of dilution (result of referring to the total gallons to BORATE 2 ppm from the correct chart)

Required Materials: WCRX-022 Curves and Tables, page 87. WCRX-01 Boration and Dilution Tables General

References:

OFN MA-038, rev 11, Rapid Plant Shutdown Handouts: WCRX-022 Curves and Tables dated 5/1/09. WCRX-01 Boration and Dilution Tables Initiating Cue: The Reactor Operator has calculated the required dilution amount for one hour after the power reduction. You are required to approve the calculation. After review, either approve the calculation, or reject and list any errors.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: No Validation Time: 25 minutes

Appendix C Page 3 of 5 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Performance Step: 1 Refers to Curves and Tables book, page 7.10 Rev 23, Reactivity Plan for Rapid Downpower Standard: Locates table for Dilution During 1 h Following Reduction Comment:

• Performance Step: 2 Determines that a dilution of 6.8 ppm is required.

Standard: In the table references the section for a 1%/min power reduction to 90% is 6.8 ppm. The supplied calculation lists 6.6 ppm, which is correct for a .5% /min power reduction.

Comment:

Performance Step: 3 Refers to the Boration/Dilution Tables for an initial boron concentration of 688 ppm and RCS temp of 585°F.

Standard: From the table determines that a combination of dilution for 5 ppm and 2 ppm result in the required dilution. A double interpolation of the tables results in a dilution of 648 gallons Comment:

• Performance Step: 4 Determines that the dilution amount is 474.4 for 5 ppm and 189.3 for 2 ppm.

Standard: The supplied calculation lists a total of 495 gallons of dilution.

This is the result of referring to the total gallons to BORATE 2 ppm from the correct chart.

The calculation should be DISAPPROVED.

Comment:

Terminating Cue: JPM is complete

Appendix C Page 4 of 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: S.A.1.b, Approve Dilution for Power Increase 1 Hour after Downpower Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

Appendix C Page 5 of 5 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: The following plant conditions exist:

• Reactor and Turbine power have been reduced to 90% at 1%/min due to a steam leak in the turbine building.

• OFN MA-038, Rapid Plant Shutdown, was used to decrease power.

• RCS boron concentration is 688 ppm after the power reduction.

• The Information Services server for Paperless Environment is Out of Service.

INITIATING CUE: The Reactor Operator has calculated the required dilution amount for one hour after the power reduction. You are required to approve the calculation. After review, either approve the calculation, or reject and list any errors.

The RO has determined that a total dilution of 6.6 ppm is required.

From the Boration/Dilution Tables the RO has determined that a dilution of 474.4 is required for 5 ppm reduction and a dilution of 20 gallons is required for a 2 ppm reduction.

The RO recommends a total dilution of 495 gallons.

Circle one of the following:

Approve/Disapprove

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Wolf Creek Task No.: N/A Task

Title:

Review/Approve the Data Sheet for JPM No.: S.A.2 STS AL-101, MDAFW Pump A Inservice Pump Test K/A

Reference:

2.2.12 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom x Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The following plant conditions exist:

• The plant is in Mode 1 at full power.

• No equipment is Out of Service.

• The CRS and the BOP have been performing STS AL-101, MDAFW Pump A Inservice Pump Test.

• The previous CRS has been called away for an urgent family emergency.

• You have been completed your turnover and have assumed the CRS duties.

Task Standard: Examinee reviews STS AL-101, MDAFW Pump A Inservice Pump Test, data sheets, Attachment A and B. Errors:

1. Math error at step 9.3 (Attachment A) - pump is operable

2. Step 8.15.2 Inboard seal leakage too low (Attachment A) -

initiate corrective action.

3. Attachment B: five minute outboard packing gland temperature exceeds 150°F (step 8.10.1 stop pump, initiate corrective action)

Examinee does not approve STS.

Required Materials: Completed STS AL-101, MDAFW Pump A Inservice Pump Test General

References:

None Handouts: Completed STS AL-101, MDAFW Pump A Inservice Pump Test

Appendix C Job Performance Measure Form ES-C-1 Worksheet Initiating Cue: The SM directs you to review/approve the just completed STS.

Circle the correct choice from below:

• The pump is operable/inoperable.

• Corrective action is required/not required.

List any errors in the STS.

Time Critical Task: No Validation Time: 25 minutes

Appendix C Page 3 of 5 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Performance Step: 1 Reviews the completed STS.

Standard: Completes the review and makes the below listed determinations.

Comment:

• Performance Step: 2 Determine if the pump is operable or inoperable.

Standard: The pump is operable. The data sheet is incorrect based on the math error in section 9.3.

Comment: Attachment A, step 9.3.2

• Performance Step: 3 Determine if corrective action is required or not required.

Standard: Corrective action is required, based on inboard seal leakage being greater than minimum. (235 ml/min is too low)

Comment: Attachment A, step 8.15.2

• Performance Step: 4 Determine if corrective action is required or not required.

Standard: Corrective action is required, based on outboard packing gland temperature exceeding 150 degrees F at the 5 minute period.

Comment: Attachment B, step 8.10.1 Performance Step: 5 Determine any errors in the STS.

Standard: Determines that the pump delta P contains a math error. 142 psig was used instead of 14.2 psig. The math error resulted in the pump delta P incorrectly being determined to be UNSAT.

Comment:

Terminating Cue: JPM complete

Appendix C Page 4 of 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: S.A.2, Review/Approve the Data Sheet for STS AL-101, MDAFW Pump A Inservice Pump Test Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

Appendix C Page 5 of 5 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: The following plant conditions exist:

• The plant is in Mode 1 at full power.

• No equipment is Out of Service.

• The previous CRS and the BOP have been performing STS AL-101, MDAFW Pump A Inservice Pump Test.

• The CRS has been called away for an urgent family emergency.

• You have completed your turnover and have assumed the CRS duties.

INITIATING CUE: The SM directs you to review/approve the just completed STS.

Circle the correct choice from below:

• The pump is operable/inoperable.

• Corrective action is required/not required.

List any errors in the STS.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Wolf Creek Task No.: N/A Task

Title:

Review a release permit for JPM No.: S.A.3 approval K/A

Reference:

2.3.6 Examinee

NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom x Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The plant is in Mode 1, 100%. A Secondary Liquid Waste Monitor Tank (THF04A) is ready for release to the environment.

Task Standard: Examinee reviews the Liquid Release Permit (LRP) and identifies three errors.

Required Materials: APF 07-001-02-13, THF04A release permit General

References:

APF 07-001-02-13, THF04A release permit, AP 07B-003, rev 6, Offsite Dose Calculation Manual, AP 07B-001, rev 17, Radioactive Releases Handouts: APF 07-001-02-13, THF04A release permit, Initiating Cue: Today is 8/31/09. Review the Liquid Release Permit for THF04A and identify three errors on the permit.

Time Critical Task: No Validation Time: 20 minutes

Appendix C Page 2 of 4 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Performance Step: 1 Review the form for errors.

Standard: Examinee reviews the form for errors.

Comment:

• Performance Step: 2 Identify that the permit should be for THF04A.

Standard: Identify the wrong tank has been identified on the permit as the tank that is being released.

Comment: Permit lists THF04B

• Performance Step: 3 Identify that the minimum dilution flowrate is too high.

Standard: Identify that the minimum dilution flowrate is too high (greater than the CWP capacity).

Comment: 2.79 x 106 gpm is greater than capacity of CWPs.

• Performance Step: 4 Identify expected monitor response exceeds High alarm setpoint.

Standard: Identify that the expected monitor response (HFL456) is greater than High setpoint (channel item 009).

Comment: 4.39 x 10-4 Ci/ml is greater than 9.81 x 10-5 Ci/ml Terminating Cue: JPM complete when errors identified.

Appendix C Page 3 of 4 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: S.A.3, Review a release permit for approval Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

Appendix C Page 4 of 4 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: The plant is in Mode 1, 100%. A Secondary Liquid Waste Monitor Tank (THF04A) is ready for release to the environment.

INITIATING CUE: Today is 8/31/09. Review the Liquid Release Permit for THF04A and identify three errors on the permit.

1.

2.

3.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Wolf Creek Task No.: N/A Task

Title:

Classify an Event Using the JPM No.: S.A.4 using Scenario Emergency Plan #2 K/A

Reference:

2.4.41 and 2.4.44 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: At the completion of the scenario the simulator is frozen. Classify the event and determine protective action recommendations, if any, based on plant conditions as they occurred during the scenario.

Task Standard: Examinee correctly classifies the event and determines protective action recommendations.

Required Materials: APF 06-002-01, rev 12, Emergency Action Levels, EPF 06-007-01, rev 10, Wolf Creek Generating Station Emergency Notification General

References:

EPP 06-005, rev 3, Emergency Classification, EPP 06-006, rev 4, Protective Action Recommendations, APF 06-002-01, rev 12, Emergency Action Levels, and EPF 06-007-01, rev 10, Wolf Creek Generating Station Emergency Notification Handouts: EPP 06-005, rev 3, Emergency Classification, EPP 06-006, rev 4, Protective Action Recommendations, APF 06-002-01, rev 12, Emergency Action Levels, and EPF 06-007-01, rev 10, Wolf Creek Generating Station Emergency Notification Initiating Cue: You are the Shift Manager. Based on the events in the scenario, classify events based on conditions at the time, determine protective action recommendations, if any, and enter the required data.

Required data is sections 3, 4, 5, and 8 on the Emergency Notification form.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: No Validation Time: 15 minutes

Appendix C Page 3 of 5 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Performance Step: 1 Using the Emergency Action Level flowchart diagnose plant conditions as they relate to the required classification of the event.

Standard: EAL No action this category EAL No action this category EAL No action this category EAL MSLB; 1, 2, 5, 7, 8 NOUE EAL No action this category EAL No action this category EAL No action this category EAL SSFM; 1, 2, 3 SAE EAL No action this category EAL No action this category EAL No action this category EAL No action this category EAL No action this category Classifies the event as a Site Area Emergency; Determines protective action recommendations are to evacuate CCL and JRR.

Comment:

• Performance Step: 2 Completes the required sections of the Emergency Notification form.

Standard: Section 3 Emergency Classification - See Key Section 4 Emergency Classification - See Key Section 5 Reason for Classification - See Key Section 8 Protective Action Recommendation - See Key Comment:

Terminating Cue: JPM complete when Examinee determines EAL classification and protective action recommendations, if any.

Appendix C Page 4 of 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: S.A.4, Classify an Event Using the Emergency Plan Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

Appendix C Page 5 of 5 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: At the completion of the scenario the simulator is frozen. Classify the event and determine protective action recommendations, if any, based on plant conditions as they occurred during the scenario.

INITIATING CUE: You are the Shift Manager. Based on the events in the scenario, classify events based on conditions at the time, determine protective action recommendations, if any, and enter the required data.

Required data is sections 3, 4, 5, and 8 on the Emergency Notification form.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Wolf Creek Date of Examination: Aug. 31 -

Sept. 4, 2009 Examination Level: RO SRO Operating Test Number:

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

Bolded font = alternate path System / JPM Title Type Code* Safety Function

a. 014 - Rod Position Indication System N, E, S 1 S1 -- Perform actions to retrieve a dropped or misaligned control rod.

(A2.04)

RO/SRO-I

b. 013 - Engineered Safety Features Actuation System (ESFAS) N, EN, S, A 2 S2 -- Perform actions to ensure CSAS actuated correctly. (Auto CSAS failed, candidate manually initiates CSAS)

(A4.01)

PRA: ESFAS is a Top 10 Risk Significant System at Wolf Creek RO/SRO-I/SRO-U

c. 006 - Emergency Core Cooling System (ECCS) M, A, S, E 3 S3 -- Perform action to ensure transfer of ECCS flowpath. (EJ HIS-8840 fails to open)

(A3.08)

PRA: BN & EJ are Top 10 Risk Significant System.

RO/SRO-I

d. 076 - Service Water System (SWS) N, S, A 4S S4 -- Perform actions to start Service Water pump or an Essential Service Water pump. (Service water pumps fail to start)

(A2.01)

PRA: Core Damage Frequency by Initiating Event (Loss of Service Water)

RO/SRO-I

e. 071 - Waste Gas Disposal System (WGDS) N, S 9 S5 -- Perform actions to set process radiation monitor alarm setpoints for Vent Release Permit for Waste Gas Decay Tank.

(A4.25)

RO/SRO-I/SRO-U

f. 016 - Non-Nuclear Instrumentation System N, A, S 7 S6 -- Perform actions to manually trip the Main Turbine. (Auto Turbine trip fails)

(K4.03)

RO/SRO-U

g. 029 - Containment Purge System (CPS) N, A, S 8 S7 -- Perform actions to ensure Containment Purge System isolation. (Auto CPIS fails, manual action required)

(A3.01)

RO/SRO-I

h. 007 - Pressurizer Relief Tank (PRT) N, S 5 S8 -- Perform actions to identify and isolate stuck open PORV.

(A2.01)

RO/SRO-I

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

i. 063 - DC Electrical Distribution System D, P, L, E 6 P1 -- Perform actions of EMG C-0 Attachment C, DC Load Shed for NK11, NK12, NK13 and NK14.

(K2.01)

PRA: Risk significant system (NK); Core Damaging Frequency by Initiating Event (Loss of Offsite Power); CD Events - LERF (P = 2004 NRC exam)

RO/SRO-I/SRO-U

j. 061 - Auxiliary / Emergency Feedwater (AFW) System N, EN, L 4S P2 -- Perform actions to cooldown the TDAFWP piping to restore AFW to > 270,000 LBM per hour.

(A2.06)

PRA: Risk significant system (AL)

RO/SRO-I

k. 006 - Emergency Core Cooling System (ECCS) N, R, E 3 P3 -- Perform Attachment B of OFN BG-045, Gas Binding of CCPs or SI Pumps - vent the SI pump due to gas binding.

(A2.04)

SOER 97-1, Potential Loss of High Pressure Injection and Charging Capability from Gas Intrusion RO/SRO-I/SRO-U

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

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 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 (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

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Wolf Creek Task No.: N/A Task

Title:

Misaligned rod recovery using OFN JPM No.: S1 SF-011, Realignment of Dropped, Misaligned Rod(s) and Rod Control Malfunctions K/A

Reference:

A2.04 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom Simulator x Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: You are the Reactor Operator. Thirty minutes ago control rod H-8 dropped. OFN SF-011, rev 007, Realignment of Dropped, Misaligned Rod(s) and Rod Control Malfunctions, is in progress. The plant has been stabilized with Tavg and Tref matched. I&C personnel have determined that the rod is misaligned due to a blown fuse in the stationary gripper coil circuit. The circuit has been verified good and the fuse has been replaced. Actions to commence recovery of H-8 are ready to be performed. I & C are standing by in the rod drive room.

Task Standard: Upon completion of this JPM, the Examinee will have recovered a misaligned rod per OFN SF-011, rev 007, Realignment of Dropped, Misaligned Rod(s) and Rod Control Malfunctions.

Required Materials: Simulator setup: IC 301. (Group password is WC. IC password is appLe1.) IC 301 should be ready to go with the malfunction already entered -- mSF13H8 (H-8 is at 115 steps).

NOTE: some elements of this JPM require additional Booth actions.

General

References:

OFN SF-011, rev 007, Realignment of Dropped, Misaligned Rod(s) and Rod Control Malfunctions.

Handouts: Marked up copy of OFN SF-011, rev 007, Realignment of Dropped, Misaligned Rod(s) and Rod Control Malfunctions.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Initiating Cue: The Control Room Supervisor directs you to recover the misaligned rod using steps 21 through 24 of OFN SF-011, rev 007, Realignment of Dropped, Misaligned Rod(s) and Rod Control Malfunctions.

Updating the rod position computer points and controlling Tavg with Tref is not necessary for this JPM. The misaligned rod occurred thirty minutes ago. The Call Superintendent, I & C and Reactor Engineering have been notified.

Time Critical Task: No Validation Time: 25 minutes

Appendix C Page 3 of 10 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

JPM begins at OFN SF-011, rev 007, Realignment of Dropped, Misaligned Rod(s) and Rod Control Malfunctions, step 21.

Performance Step: 1 Prepare to realign rod (s)

Standard: Completion of performance steps 1a through 1g.

Comment: OFN SF-011, steps 21a through 21g

• Performance Step: 1a Place ROD BANK AUTO/MAN SEL switch to the bank with the misaligned rod o SE HS-9 Standard: Locate SE HS-9 on RL003. Turn the selector switch to the CBD position Comment: (Step 21a)

Performance Step: 1b Direct I & C to locally verify rod bank selected by SE HS-9 is aligned properly by light indication on associated cabinets Standard: Contact I & C to verify light indication is proper for Control Bank D selected.

Comment: Cue: Acknowledge request. Report Lights are proper for Control Bank D being selected.

If asked: proper light indication is right handed lights lit on power cabinets 1BD & 2BD and right hand lights on power cabinets 1AC, 2AC and SCDE.

(Step 21b)

• Performance Step: 1c At RL003, record position of group step counter for group containing misaligned rod o Group step counter_______________

Standard: Locate the group step counters for Control Bank D on RL003.

Record the position of the group counter for the affected rod.

Comment: (Step 21c)

Appendix C Page 4 of 10 Form ES-C-1 PERFORMANCE INFORMATION

• Performance Step: 1e If rod(s) are misaligned low with respect to other rods in group, then perform the following:

1. Check DRPI LEDs for misaligned group - less than 228 steps

1. RNO: Insert rods in misaligned group until DRPI LEDs -

equals 222 steps

2. Withdraw rods in misaligned group until next set of DRPI LEDs for the misaligned group light Standard: First:

1. Examinee determines that H-8 is less than 228 steps; but group is greater than 228 steps. Examinee performs RNO.

Examinee inserts rods in misaligned group to 222 steps using SF HS-2, ROD MAN CTRL. Examinee monitors DRPI LEDs.

Then:

2. Examinee withdraws misaligned group using SF HS-2 ROD MAN CTRL until next set of DRPI LEDs for the misaligned group lights. Examinee monitors DRPI LEDs.

Comment: (Step 21e)

• Performance Step: 1f At lift coil disconnect panel, place all lift coil disconnect switches for other rods in affected bank to ROD DISCONNECTED position.

Standard: Locate disconnect panel behind the simulator Control Boards on the north wall. Place the toggle switches for M12, D12, M4 and D4 to ROD DISCONNECTED position.

Comment: (Step 21f)

Performance Step: 1g At RL003, record position of group step counter for group misaligned o Group step counter__________________

Standard: Locate the group step counter for group containing H-8 on RL003. Record the position of the group counter for the affected group.

Comment: (Step 21g)

Performance Step: 2 () Adjust turbine load as necessary to maintain Tavg within 3°F of Tref Standard: NA - Maintaining Tavg - Tref matched is not required per Initiating Cues.

Appendix C Page 5 of 10 Form ES-C-1 PERFORMANCE INFORMATION Comment: Booth operator may adjust Turbine load as the rod is withdrawn (3% per minute).

(Step 22)

Performance Step: 3 () Realign misaligned rod(s) to associated group position:

Standard: Complete 3a through 3c performance steps.

Comment: (Step 23)

• Performance Step: 3a Check misaligned rod - IN SHUTDOWN GROUP Standard: Determine control rod H8 is not in a shutdown group. Perform RNO.

Comment: (Step 23a)

• Performance Step: At Pulse-to-Analog Converter cabinet, hold AUTO-MANUAL RNO 3a switch in MANUAL.

Standard: Contact I & C (or Aux Building watch) and direct the AUTO-MANUAL switch be held in MANUAL Comment: Cue: Respond as I & C (AB watch) and acknowledge report I will hold the switch in MANUAL BOOTH action: Use Remote Function rSF05, select MANUAL.

(23a RNO)

• Performance Step: 3b Realign misaligned rod(s) to associated group position Standard: At RL003, using ROD MAN CTRL, SF HS-2, while monitoring DRPI panel, verify only control rod H8 moves during recovery of misaligned rod.

Comment: (Step 23b)

• Performance Step: 3 Check misaligned rod(s) - IN SHUTDOWN GROUP Standard: Determine control rod H8 is not in shutdown group. Perform RNO.

Comment: (Step 23b)

Appendix C Page 6 of 10 Form ES-C-1 PERFORMANCE INFORMATION

• Performance Step: At Pulse-to-Analog Converter cabinet, release AUTO-MANUAL RNO3c switch Standard: Contact I & C (AB watch) and direct the AUTO-MANUAL switch be released.

Comment: Cue: Acknowledge request.

BOOTH Actions: Use Remote Function rSF05, select AUTO.

(Step 23c RNO)

Performance Step: 4 Reset misaligned rod(s)

Standard: Complete 4a through 4k performance steps.

Comment: (Step 24)

• Performance Step: 4a At lift coil disconnect panel, place all lift coil disconnect switches for affected bank to ROD CONNECTED position.

Standard: Locate disconnect panel behind the simulator Control Boards on the north wall. Place the toggle switches for M12, D12, M4 and D4 to the ROD CONNECTED position.

Comment: (Step 24a)

• Performance Step: 4b On RL003, open window and reset affected group step counter by hand to position recorded in Step 21g.

Standard: Locate RL003. Reset affected group step counter to position recorded in step 21g (see Performance step 1g).

Comment: (Step 24b)

• Performance Step: 4c On RL003, reset rod control urgent failure alarm o SF HS-4 Standard: Locate SF HS-4 on RL003. Depress SF HS-4. Main Control Board alarm 79A clears.

Comment: (Step 24c)

Appendix C Page 7 of 10 Form ES-C-1 PERFORMANCE INFORMATION

• Performance Step: 4d Verify proper operation of affected rods by moving affected rods 6 steps in each direction.

Standard: At RL003 panel, using ROD MAN CTRL, SF HS-2, Examinee inserts and withdraws affected rods six steps.

Comment: (Step 24d)

• Performance Step: 4e Move affected group to position recorded in Step 21c.

Standard: At RL003, using ROD MAN CTRL, SF HS-2, Examinee moves affected group to position recorded in Step 21c (Performance step 1c).

Comment: (Step 24e)

• Performance Step: 4f Place ROD BANK AUTO/MAN SEL switch in MAN position o SE HS-9 Standard: Locate SF HS-9 on RL003. Turn the selector switch to MAN position.

Comment: (Step 24f)

• Performance Step: 4g Direct I & C to locally verify rod bank selected by SE HS-9 is aligned properly by light indications on associated cabinets.

Standard: Contact I & C to verify light indication is proper for Control Bank D selected.

Comment: Cue: Acknowledge request. Report Lights are proper for manual rod control being selected with bank D ready to move.

(Step 24g)

Appendix C Page 8 of 10 Form ES-C-1 PERFORMANCE INFORMATION Comment: The examinee should complete either Performance step 4h or 4i.

• Performance Step: 4h If the bank D group step counters are at the same count, then direct I & C to ensure the master cycler binary counter is set on 4 or 5.

Standard: Contact I & C to check the Master Cycler binary counter.

Comment: Cue: Report as I & C. Acknowledge request. Report Master Cycler binary counter is on 5.

BOOTH action: Check rSF07. If jnxtgrpn = 2 then OK. If jnxtgrpn = 1 then type in 2 and execute.

(Step 24h)

• Performance Step: 4i If the bank D group step counters are set at different counts, then direct I & C to ensure the master cycler binary counter is set on 1 or 2.

Standard: Contact I & C to check the Master Cycler binary counter.

Comment: Cue: Report as I&C. Acknowledge request. Report Master Cycler binary counter is on 1.

(Step 24i)

Performance Step: 4j Update computer rod position program using STN RJ-001, Verification of Operability of Computer Processes.

Standard: N/A - Updating the program not required per Initiating Cues.

Comment: (Step 24j)

Performance Step: 4k Go to step 28 Standard: N/A - Not required per Initiating Cues. JPM complete Comment: (Step 24k)

Terminating Cue: Completion of step 24 and transition to step 28 of OFN SF-011.

Appendix C Page 9 of 10 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: S1, Misaligned rod recovery using OFN SF-011, Realignment of Dropped, Misaligned Rod(s) and Rod Control Malfunctions Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

Appendix C Page 10 of 10 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: You are the Reactor Operator. Thirty minutes ago control rod H-8 dropped. OFN SF-011, rev 007, Realignment of Dropped, Misaligned Rod(s) and Rod Control Malfunctions, is in progress.

The plant has been stabilized with Tavg and Tref matched. I&C personnel have determined that the rod is misaligned due to a blown fuse in the stationary gripper coil circuit. The circuit has been verified good and the fuse has been replaced. Actions to commence recovery of H-8 are ready to be performed. I & C are standing by in the rod drive room.

INITIATING CUE: The Control Room Supervisor directs you to recover the misaligned rod using steps 21 through 24 of OFN SF-011, rev 007, Realignment of Dropped, Misaligned Rod(s) and Rod Control Malfunctions.

Updating the rod position computer points and controlling Tavg with Tref is not necessary for this JPM. The misaligned rod occurred thirty minutes ago. The Call Superintendent, I&C and Reactor Engineering have been notified.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Wolf Creek Task No.: N/A Task

Title:

ESFAS - CSAS failure to auto JPM No.: S2 actuate K/A

Reference:

A4.01 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom Simulator x Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: You are the Reactor Operator. The plant has experienced a reactor trip and safety injection from full power. The crew is performing EMG E-0, rev 21, Reactor Trip or Safety Injection.

Task Standard: Upon completion of this JPM, the Examinee will have manually stopped all Reactor Coolant Pumps and initiated Containment Spray Actuation Signal (CSAS).

Required Materials: Simulator setup: IC-302. (Group password is WC, IC password is appLe1).

General

References:

EMG E-0, rev 21, Reactor Trip or Safety Injection, Attachment F, Automatic Signal Verification Handouts: EMG E-0, rev 21, Reactor Trip or Safety Injection, Attachment F, Automatic Signal Verification, step F11, Verify Containment Spray Not Required.

Initiating Cue: The Control Room Supervisor has assigned you to perform EMG E-0, rev 21, Attachment F, Automatic Signal Verification, step F11.

Time Critical Task: No Validation Time: 15 minutes

Appendix C Page 2 of 6 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Nomenclature of JPM follows EMG E-0, rev 21, Attachment F - Automatic Signal Verification, step F11.

Performance Step: 1 F11. Verify Containment Spray not required Standard: Completion of performance steps 1a and RNO Comment: EMG E-0, Attachment F, step F11 Performance Step: 1a Containment pressure - has remained < 27psig o 00-059A, CSAS - not LIT o 00-059B, CISB - not LIT o GN PR-934 Standard: Examinee determines:

o 00-059A, CSAS - NOT LIT o 00-059B, CISB - LIT o GN PR-934 - displays > 27 psig in Containment (se RL018)

Examinee shifts to RNO column.

Comment: (Step F11a)

Performance Step: Perform the following:

1RNO Standard: Examinee performs RNO column at step F11. These are performance steps 11RNO-1 through 11RNO-6 Comment: (Step F11 RNO)

Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: Stop all RCPs 1RNO 1 Standard: At panel RL021, locate RCPs. Stop all RCPs using appropriate handswitches. (Green lights LIT when stopped) o BB HIS-37 for RCP A o BB HIS-38 for RCP B o BB HIS-39 for RCP C o BB HIS-40 for RCP D Comment: Examinee may verify amps decreasing after RCP pump stopped.

(step F11 RNO1)

• Performance Step: If Containment spray has not actuated, then actuate containment 1RNO 2 spray.

o SB HS-43 and SB HS-45 o SB HS-44 and SB HS-46 Standard: Examinee manually actuates Containment Spray using o SB HS-43 and SB HS-45 o SB HS-44 and SB HS-46 Comment: Main Control Board alarm 59A, CSAS illuminates.

(step F11 RNO2)

• Performance Step: Check ESFAS status panel CSAS section - all white lights lit 1RNO 3 o Red train o Yellow train Standard: Locate ESFAS panels CSAS sections - all white lights are NOT LIT for both trains of CSAS EN HV-6, CS SYS DISCH VLV (CS pump A) - NOT LIT EN HV-12, CS SYS DISCH VLV (CS pump B) - NOT LIT Comment: (step F11 RNO3)

Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: If any CSAS component not properly aligned, then manually 1RNO 4 align associated component.

Standard: At RL017, Examinee depresses the OPEN pushbutton for EN HV-6. Red light LIT, Green light extinguishes.

At RL017, Examinee depresses the OPEN pushbutton for EN HV-12. Red light LIT, Green light extinguishes.

EN HV-6, CS SYS DISCH VLV (CS pump A) - LIT EN HV-12, CS SYS DISCH VLV (CS pump B) - LIT Comment: (step F11 RNO4)

Performance Step: Check ESFAS status panel CISB section - all white lights LIT 11RBO 5 o Red train o Yellow train Standard: Locate ESFAS panels CISB sections - all white lights are LIT for both trains of CISB Comment: (step F11 RNO5)

Performance Step: If any CISB valve not CLOSED, then manually close valves. If 11RNO 6 valve(s) can not be closed, then manually or locally isolate affected containment penetration. Refer to Attachment E, Valves Closed by Containment Isolation Signal Phase B.

Standard: NA - valves are CLOSED Comment: Performance of step F11 and its RNO completes this JPM.

Lead examiner may stop the JPM anytime after step F11.

(step F11 RNO6)

Terminating Cue: Once step F11 of Attachment F is completed, the JPM can be terminated at the Lead Examiners discretion.

Appendix C Page 5 of 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: S2, ESFAS - CSAS failure to auto actuate Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: You are the Reactor Operator. The plant has experienced a reactor trip and safety injection from full power. The crew is performing EMG E-0, rev 21, Reactor Trip or Safety Injection.

INITIATING CUE: The Control Room Supervisor has assigned you to perform EMG E-0, rev 21, Attachment F, Automatic Signal Verification, step F11.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Wolf Creek Task No.: N/A Task

Title:

ECCS Automatic Transfer JPM No.: S3 K/A

Reference:

A3.08 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom Simulator x Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: You are the Reactor Operator. A LOCA has occurred. Cold Leg recirculation has been aligned and 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> have elapsed since the Safety Injection. TSC has directed transferring to Hot Leg Recirculation using EMG ES-13, Transfer to HL Recirc.

Task Standard: Upon completion of this JPM, the Examinee will have established Hot Leg Recirculation per EMG ES-13, rev 11, Transfer to Hot Leg Recirculation.

Required Materials: Simulator set up 302 - still being built - verify that the override for EJ HIS-8840 failure to open is in.

Group password is WC, IC password is appLe1.

General

References:

EMG ES-13, rev 11, Transfer to Hot Leg Recirculation Handouts: EMG ES-13, rev 11, Transfer to Hot Leg Recirculation Initiating Cue: The Control Room Supervisor directs you to transfer to Hot Leg Recirculation per EMG ES-13, rev 11, Transfer to Hot Leg Recirculation.

Report when the task is complete.

Time Critical Task: No Validation Time: 25 minutes

Appendix C Page 2 of 13 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Performance Step: 1 Align red train RHR for Hot Leg Recirculation:

Standard: Completion of performance steps 1a through 1d.

Comment: EMG ES-13 step 1a through d

• Performance Step: 1a Place power lockout for EJ HV-8809A in NON-ISO position o EJ HIS-8809AA Standard: Locate EJ HIS-8809AA on panel RL017. Depress NON-ISO pushbutton and lock it down. Verify White light is LIT.

Comment: (EMG ES-13, step 1a)

• Performance Step: 1b Close RHR to Accumulator Injection Loops 1 & 2 valve o EJ HIS-8809A Standard: Locate EJ HIS-8809A on panel RL017. Depress the CLOSE pushbutton. Verify the Green light is LIT (Red light goes out).

Comment: (EMG ES-13, step 1b)

• Performance Step: 1c Place power lockout for EJ HV-8809A in ISO position.

o EJ HIS-8809AA Standard: Locate EJ HIS-8809AA on panel RL017. Depress the ISO pushbutton. Verify the NON-ISO pushbutton releases and the White light is extinguished.

Comment: ALM 00-049C, RHR Loop 1 Flow Lo, alarm actuates when EJ HV-8809A is closed - expected alarm (EMG ES-13, step 1c)

• Performance Step: 1d Open RHR train A hot leg recirc valve o EJ HIS-8716A Standard: Locate EJ HIS-8716A on panel RL017. Open valve using the OPEN pushbutton. Verify the Red light LIT and the Green light is extinguished.

Comment: (EMG ES-13, step 1d)

Appendix C Page 3 of 13 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 2 Align Yellow train RHR for Hot Leg Recirculation:

Standard: Completion of performance steps 2a through 2d Comment: EMG ES-13 step 2a through d

• Performance Step: 2a Place the power lockout for EJ HV-8809B in the NON-ISO position o EJ HIS-8809BA Standard: Locate EJ HIS-8809BA on RL017. Press the NON-ISO pushbutton and lock it down. Verify the White light is LIT.

Comment: (EMG ES-13, step 2a)

• Performance Step: 2b Close RHR to Accumulator Injection Loops 3 & 4 valve o EJ HIS-8809B Standard: Locate EJ HIS-8809B on panel RL017. Close valve using the CLOSE pushbutton. Verify Green light LIT and the Red light is extinguished.

Comment: (EMG ES-13, step 2b)

• Performance Step: 2c Place power lockout for EJ HV-8809B in the ISO position o EJ HIS-8809BA Standard: Locate EJ HIS-8809BA on panel RL017. Depress the ISO pushbutton. Verify the NON-ISO pushbutton releases and White light is extinguished.

Comment: ALM 00-050C, RHR Loop 2 Flow Lo, alarm actuates when EJ HV-8809B is closed - expected alarm (EMG ES-13, step 2c)

Appendix C Page 4 of 13 Form ES-C-1 PERFORMANCE INFORMATION

• Performance Step: 2d Open RHR Train B Hot Leg Recirc isolation valve o EJ HIS-8716B Standard: Locate EJ HIS-8716B on panel RL017. Open the valve by depressing the OPEN pushbutton. Verify the Red light LIT and the Green light is extinguished.

Comment: (EMG ES-13, step 2d)

Performance Step: 3 Establish RHR Lot Leg Recirculation:

Standard: Completion of performance steps 3a, 3b and its RNO, and 3c Comment: EMG ES-13 step 3a through c

• Performance Step: 3a Place power lockout for EJ HV-8840 in NON-ISO position o EJ HIS-8840A Standard: Locate EJ HIS-8840A on panel RL017. Depress the NON-ISO pushbutton and lock it down. Verify the White light LIT.

Comment: (EMG ES-13 step 3a)

• Performance Step: 3b Open RHR Hot Leg Recirc valve o EJ HIS-8840 Standard: Locate EJ HIS-8840 on panel RL017. Open the valve by pressing the OPEN pushbutton. Recognize valve will not open and transition to the RNO column at step 3b.

Comment: (EMG ES-13 step 3b)

Performance Step: Perform the following:

RNO3b Standard: Completion of performance steps RNO3b 1 through 2e.

Comment: EMG ES-13 step 3bRNO b1 through b2e

Appendix C Page 5 of 13 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: If radiation levels permit, then locally open the valve.

RNO3b 1 Standard: Contact Building watch to locally open the valve.

(Health Physics may be contacted to determine local radiation levels.)

Comment: CUE: Local radiation levels are too high to permit local opening of EJ HIS-8840.

(EMG ES-13 step 3b RNO b1)

Performance Step: If RHR Hot Leg Recirculation can not be established then RNO3b 2 reestablish RHR Cold Leg Recirculation:

Standard: Completion of performance steps RNO3b 2a through e.

Comment: (EMG ES-13 step 3b RNO b2)

• Performance Step: Place power lockout for EJ HV-8809A/B switches in NON-ISO RNO3b 2a position.

o EJ HIS-8809AA o EJ HIS-8809BA Standard: Locate EJ HIS-8809AA and EJ HIS-8809BA on panel RL017.

Depress the NON-ISO pushbutton(s) and lock it (them) down.

Verify that the White light is LIT for each.

Comment: (EMG ES-13 step 3b RNO b2a)

• Performance Step: Open RHR to Accumulator Injection Loops 1 & 2 and 3 & 4 RNO3b 2b valves.

o EJ HIS-8809A o EJ HIS-8809B Standard: Locate EJ HIS-8809A/B on panel RL017. Open the valve(s) by depressing their respective OPEN pushbuttons. Red light is LIT and the Green light extinguishes.

Comment: (EMG ES-13 step 3b RNO b2b)

Appendix C Page 6 of 13 Form ES-C-1 PERFORMANCE INFORMATION

• Performance Step: Place power lockout for EJ HV-8809A/B switches in ISO position.

RNO3b 2c o EJ HIS-8809AA o EJ HIS-8809BA Standard: Locate EJ HIS-8809AA and EJ HIS-8809BA on panel RL017.

Depress the ISO pushbutton(s). Verify the NON-ISO pushbutton releases and White light is extinguished.

Comment: (EMG ES-13 step 3b RNO b2c)

• Performance Step: Close RHR train A Hot Leg Recirc valve RNO3b 2d o EJ HIS-8716A Standard: Locate EJ HIS-8716A on panel RL017. Close the valve by depressing the CLOSE pushbutton. Green light is LIT and Red light is extinguished.

Comment: (EMG ES-13 step 3b RNO b2d)

• Performance Step: Close RHR train B Hot Leg Recirc Isolation valve RNO3b 2e o EJ HIS-8716B Standard: Locate EJ HIS-8716B on panel RL017. Close the valve by depressing the CLOSE pushbutton. Green light is LIT and Red light is extinguished.

Comment: Return to the Action/Expected response column.

(EMG ES-13 step 3b RNO b2e)

• Performance Step: 3c Place power lockout for EJ HV-8840 in ISO position o EJ HIS-8840A Standard: Locate EJ HIS-8840A on panel RL017. Depress the ISO pushbutton. Verify the NON-ISO pushbutton releases and the White light is extinguished.

Comment: (EMG ES-13 step 3c)

• Performance Step: 4 Check RHR Hot Leg Recirc flow - flow indicated o EJ FI-988 Standard: Locate EJ FI-988 on panel RL018. Flow is not indicated.

Comment: EMG ES-13 step 4

Appendix C Page 7 of 13 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 5 Align red train SI for Hot Leg Recirculation:

Standard: Completion of performance steps 5a through 5f Comment: EMG ES-13 step 5a through f

• Performance Step: 5a Stop SI pump A o EM HIS-4 Standard: Locate EM HIS-4 on panel RL017. Turn handswitch to the STOP position. Red light extinguishes and Green light is LIT.

Comment: No flow indicated on EM FI-918.

(EMG ES-13 step 5a)

• Performance Step: 5b Close SI pump A discharge to cold leg injection valve o EM HIS-8821A Standard: Locate EM HIS-8821A on panel RL017. Depress the Close pushbutton. The Red light extinguishes and the Green light is LIT.

Comment: (EMG ES-13 step 5b)

• Performance Step: 5c Place power lockout for EM HV-8802A in NON-ISO position o EM HIS-8802AA Standard: Locate EM HIS-8802AA on panel RL017. Depress and lockdown the NON-ISO pushbutton. White light is LIT.

Comment: (EMG ES-13 step 5c)

• Performance Step: 5d Open SI pump A discharge to hot leg injection valve o EM HIS-8802A Standard: Locate EM HIS-8802A on panel RL017. Depress the Open pushbutton. Green light is extinguished and the Red light is LIT.

Comment: EM ZL-8802AA (SI pump A discharge to hot leg injection) indicates Red light LIT and Green lit extinguished.

(EMG ES-13 step 5d)

Appendix C Page 8 of 13 Form ES-C-1 PERFORMANCE INFORMATION

• Performance Step: 5e Place power lockout for EM HV-8802AA in ISO position o EM HIS-8802AA Standard: Locate EM HIS-8802AA on panel RL017. Depress the ISO pushbutton. The NON-ISO pushbutton releases. The White light extinguishes.

Comment: (EMG ES-13 step 5e)

• Performance Step: 5f Start the SI pump A o EM HIS-4 Standard: Locate EM HIS-4 on panel RL017. Turn handswitch to the RUN position. Green light extinguishes and Red light is LIT.

Comment: Discharge flow is indicated on EM FI-918.

(EMG ES-13 step 5f)

Performance Step: 6 Align Yellow train SI for Hot Leg Recirculation Standard: Completion of performance steps 6a through 6 f Comment: EMG ES-13 step 6a through f

• Performance Step: 6a Stop SI pump B o EM HIS-5 Standard: Locate EM HIS-5 on panel RL017. Turn handswitch to the STOP position. Red light extinguishes and Green light is LIT.

Comment: No flow indicated on EM FI-922.

(EMG ES-13 step 6a)

• Performance Step: 6b Close SI pump B discharge to cold leg injection valve o EM HIS-8821B Standard: Locate EM HIS-8821B on panel RL017. Depress the Close pushbutton. Red light extinguishes and Green light is LIT.

Comment: (EMG ES-13 step 6b)

Appendix C Page 9 of 13 Form ES-C-1 PERFORMANCE INFORMATION

• Performance Step: 6c Place power lockout for EM HV-8802B in NON-ISO position o EM HIS-8802BA Standard: Locate EM HIS-8802BA on panel RL017. Depress and lockdown the NON-ISO pushbutton. White light is LIT.

Comment: (EMG ES-13 step 6c)

• Performance Step: 6d Open SI pump B discharge to hot leg injection valve o EM HIS-8802B Standard: Locate EM HIS-8802B on panel RL017. Depress the Open pushbutton. Green light extinguishes and Red light is LIT.

Comment: EM ZL-8802BA (SI pump B to hot leg injection) indication Green light extinguishes and Red lit is LIT.

(EMG ES-13 step 6d)

• Performance Step: 6e Place power lockout for EM HV-8802BA in ISO position o EM HIS-8802BA Standard: Locate EM HIS-8802Ba on panel RL017. Depress the ISO pushbutton. The NON-ISO pushbutton releases. The White light is extinguished.

Comment: (EMG ES-13 step 6e)

• Performance Step: 6f Start SI pump B o EM HIS-5 Standard: Locate EM HIS-5 on panel RL017. Move the handswitch to the RUN position. Green light extinguishes and Red light is LIT.

Comment: Discharge flow is indicated on EM FI-922.

(EMG ES-13 step 6f)

Performance Step: 7 Isolate SI pump cold leg injection Standard: Completion of performance steps 7a through 7c Comment: EMG ES-13 step 7a through c

Appendix C Page 10 of 13 Form ES-C-1 PERFORMANCE INFORMATION

• Performance Step: 7a Place power lockout for EM HV-8835 in NON-ISO position o EM HIS-8835A Standard: Locate EM HIS-8835A on panel RL017. Depress and lockdown the NON-ISO pushbutton. The White light is LIT.

Comment: (EMG ES-13 step 7a)

• Performance Step: 7b Close SI pumps to cold leg injection valve o EM HIS-8835 Standard: Locate EM HIS-8835 on panel RL017. Depress the Close pushbutton. The Red light extinguishes and the Green light is LIT.

Comment: EM ZL-8835A (SI pumps to cold leg injection) indication Red light extinguishes and Green light is LIT.

(EMG ES-13 step 7b)

• Performance Step: 7c Place power lockout for EM HV-8835 in ISO position o EM HIS-8835A Standard: Locate EM HIS-8835A on panel RL017. Depress the ISO pushbutton. The NON-ISO pushbutton releases and the White light extinguishes.

Comment: (EMG ES-13 step 7c)

• Performance Step: 8 Check SI pump discharge flow - flow indicated o EM FI-918 o EM FI-922 Standard: Locate EMFI-918 and EM FI-922 on panel RL017. Flow is indicated.

Comment: EMG ES-13 step 8 Performance Step: 9 Verify core cooling:

Standard: Completion of performance steps 9a through 9d Comment: EMG ES-13 step 9a through d

Appendix C Page 11 of 13 Form ES-C-1 PERFORMANCE INFORMATION

• Performance Step: 9a Check RCS subcooling - > 30°F [45°F]

Standard: Locate subcooling monitors (BB TI-1390A /B) on panel RL022.

Subcooling is > 30°F.

Comment: (EMG ES-13 step 9a)

• Performance Step: 9b Check RVLIS - available Standard: Locate RVLIS on panel RL021. RVLIS is available.

Forced flow range: BB LI-1312 and BB LI-1322 Natural Circ range: BB LI-1311 and BB LI-1321 Comment: (EMG ES-13 step 9b)

• Performance Step: 9c Determine required RVLIS indication:

Standard: RCPs running Required RVLIS level 4 84% Forced flow range 3 56% Forced flow range 2 39% Forced flow range 1 28% Forced flow range 0 69% Natural Circ range Comment: (EMG ES-13 step 9c)

• Performance Step: 9d Check RVLIS indication - greater than required Standard: RVLIS is NOT greater than required Comment: CRS CUE: I will contact the TSC for further guidance.

(EMG ES-13 step 9d)

• Performance Step: 10 Return to procedure and step in effect Standard: Examinee has completed JPM.

Comment: EMG ES-13 step 10 Terminating Cue: Completion of EMG ES-13 step 10.

Appendix C Page 12 of 13 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: S3, ECCS Automatic Transfer Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

Appendix C Page 13 of 13 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: You are the Reactor Operator. A LOCA has occurred. Cold Leg recirculation has been aligned and 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> have elapsed since the Safety Injection. TSC has directed transferring to Hot Leg Recirculation using EMG ES-13, Transfer to HL Recirc.

INITIATING CUE: The Control Room Supervisor directs you to transfer to Hot Leg Recirculation per EMG ES-13, Transfer to Hot Leg Recirculation.

Report when the task is complete.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Wolf Creek Task No.: N/A Task

Title:

Loss of Service Water - start ESW JPM No.: S4 K/A

Reference:

A2.01 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom Simulator x Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Service Water pump has tripped.

Task Standard: Upon completion of this JPM, the Examinee will have placed Essential Service Water (ESW) in service per ALR 00-008B, rev 12, Service Water Press Hi Lo.

Required Materials: Simulator IC 30. Two Service Water pumps were in service. A running Service Water pump has tripped. Only one Service Water pump is running. ALR 00-008B, Service Water Press Hi Lo is illuminated. Only the low flow Service water pump will start, Service water pressure will be

< 85 psig.

Use Component Malfunctions, Breakers, 52B, select bkrWS01PA for Service Water pump A to TRIP.

Use the Lightening rod override key on the Instructor Station toolbar -

override Service Water pump B final value to STOP/PTL (IOR P13015 f:1)

General

References:

ALR 00-008B, rev 12, Service Water Press Hi Lo Handouts: ALR 00-008B, rev 12, Service Water Press Hi Lo Initiating Cue: You are the Reactor Operator. The Control Room Supervisor (CRS) has directed you to perform ALR 00-008B, rev 12, Service Water Press Hi Lo. The CRS will refer to any SYS procedures.

Time Critical Task: No

Appendix C Job Performance Measure Form ES-C-1 Worksheet Validation Time: 20 minutes

Appendix C Page 3 of 9 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Performance Step: 1 Check Service Water pumps discharge pressure - < 80 psig o 1PI-WS009A Standard: Locate 1PI-WS009A on panel RL014. Determine Service Water pressure is < 80 psig Comment: ALR 00-008B step 1 Performance Step: 2 Check Liquid Waste Release using Service Water System for dilution flow - not in progress Standard: Determine liquid release using Service Water NOT in progress Comment: CRS CUE: No liquid release using Service Water is in progress.

If the Examinee looks in the Liquid Release Permit (LRP) notebook, no LRP permit has been issued for a liquid release.

ALR 00-008B step 2 Performance Step: 3 Verify Service Water System leakage is not the cause of Service Water low pressure.

Standard: Contact Site watch or Building watches to walk down Service Water System.

Comment: Site/Building Watch CUE: No Service Water System leaks.

ALR 00-008B step 3

Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION

• Performance Step: 4 Start Standby Service Water pumps, as necessary, to establish discharge pressure greater than 85 psig.

o 1HS-WS001A for pump A (SL-41, SL-4, PA02) (tripped) o 1HS-WS002A for pump B (SL-31, SL-3, PA01) o 1HS-WS003A for pump C (SL-31, SL-3, PA01) (running) o 1HS-WS004A for Low Flow pump (SL-41, SL-4, PA02)

Standard: Locate handswitches at panel RL013.

o 1HS-WS001A for pump A (SL-41, SL-4, PA02) o 1HS-WS002A for pump B (SL-31, SL-3, PA01) (wont start) o 1HS-WS003A for pump C (SL-31, SL-3, PA01) o 1HS-WS004A for Low Flow pump (SL-41, SL-4, PA02)

Attempt to start a Service Water pump B by manipulating the handswitch in the RUN direction. It will NOT start.

Attempt to start the Low Flow pump, it will START, but pressure will still be less than 85 psig. Transition to the RNO column.

Comment: CUE: may be needed for Site Watch and CRS ALR 00-008B step 4 Performance Step: Perform the following to put the required ESW trains inservice:

RNO4 Standard: Completion of performance steps RNO4a through RNO4e.

Comment: ALR 00-008B step 4 RNO

Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION

• Performance Step: Open ESW to UHS.

RNO4a o EF HIS OPEN (TRN A) o EF HIS OPEN (TRN B)

Standard: Locate EF HIS-37 at panel RL019. Depress the Open pushbutton for EF HIS-37. The Green light extinguishes and the Red light is LIT.

Locate EF HIS-38 at panel RL019. Depress the Open pushbutton for EF HIS-38. The Green light extinguishes and the Red light is LIT.

Comment: (ALR 00-008B step 4 RNO a)

• Performance Step: Close ESW to Service Water SYS valves.

RNO4b o EF HIS CLOSED (TRN A) o EF HIS CLOSED (TRN A) o EF HIS CLOSED (TRN B) o EF HIS CLOSED (TRN B)

Standard: Locate EF HIS-39 at panel RL019. Depress the Close pushbutton for EF HIS-39. The Red light extinguishes and the Green light is LIT.

Locate EF HIS-41 at panel RL019. Depress the Close pushbutton for EF HIS-41. The Red light extinguishes and the Green light is LIT.

Locate EF HIS-40 at panel RL019. Depress the Close pushbutton for EF HIS-40. The Red light extinguishes and the Green light is LIT.

Locate EF HIS-42 at panel RL019. Depress the Close pushbutton for EF HIS-42. The Red light extinguishes and the Green light is LIT.

Comment: (ALR 00-008B step 4 RNO b)

Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION

• Performance Step: Start ESW pumps.

RNO4c o EF HIS-55A (pump A) o EF HIS-56A (pump B)

Standard: Locate EF HIS-55A at panel RL019. Manipulate the handswitch to the RUN position. The Green light extinguishes and the Red light is LIT.

Locate EF HIS-56A at panel RL019. Manipulate the handswitch to the RUN position. The Green light extinguishes and the Red light is LIT.

Comment: ALM 00-055A, ESW PMP A PRESS LO, is an expected alarm.

ALM 00-055B, ESW PMP B PRESS LO, is an expected alarm.

Examinee may check ESW pump discharge flows EF FI-53 (pump A) and /or EF FI-54 (pump B).

(ALR 00-008B step 4 RNO c)

• Performance Step: Close the Service WTR/ESW cross connect valves.

RNO4d o EF HIS CLOSED (TRN A) o EF HIS CLOSED (TRN A) o EF HIS CLOSED (TRN B) o EF HIS CLOSED (TRN B)

Standard: Locate EF HIS-23 at panel RL019. Depress the Close pushbutton for EF HIS-23. The Red light extinguishes and the Green light is LIT.

Locate EF HIS-25 at panel RL019. Depress the Close pushbutton for EF HIS-25. The Red light extinguishes and the Green light is LIT.

Locate EF HIS-24 at panel RL019. Depress the Close pushbutton for EF HIS-24. The Red light extinguishes and the Green light is LIT.

Locate EF HIS-26 at panel RL019. Depress the Close pushbutton for EF HIS-26. The Red light extinguishes and the Green light is LIT.

Comment: ALMs 55A, 56B and 8B will clear.

(ALR 00-008B step 4 RNO d)

Appendix C Page 7 of 9 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: Refer to SYS EF-200, Operation of the ESW System.

RNO4e Standard: Examinee does not need to refer to SYS EF-200, Operation of the ESW System for the successful completion of this JPM.

Examinee returns to the Action/Expected Response column.

See Initiating Cue.

Comment: CRS CUE: I will assign SYS EF-200, Operation of the ESW System to the Relief Crew.

(ALR 00-008B step 4 RNO e)

• Performance Step: 5 Check Service Water pumps discharge pressure - > 140 psig o 1PI-WS009A Standard: Locate 1PI-WS009A on panel RL014. Determine Service Water pressure is NOT > 140 psig. Transition to RNO column.

Comment: ALR 00-008B step 5

• Performance Step: Return to procedure and step in effect.

RNO5 Standard: Examinee has completed ALR 00-08B, Service Water Press Hi Lo. JPM is complete.

Comment:

Terminating Cue: Examinee has completed JPM at Step 5RNO, Return to procedure and step in effect.

Appendix C Page 8 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: S4, Loss of Service Water - start ESW Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

Appendix C Page 9 of 9 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: The Service Water pump has tripped.

INITIATING CUE: You are the Reactor Operator. The Control Room Supervisor (CRS) has directed you to perform ALR 00-008B, Service Water Press Hi Lo. The CRS will refer to any SYS procedures.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Wolf Creek Task No.: N/A Task

Title:

Set RM-11R setpoints for Waste JPM No.: S5 Gas Decay Tank Gas Release Permit K/A

Reference:

A4.25 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom Simulator x Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Chemistry has generated a Gas Release Permit for a Waste Gas Decay Tank release to the environs.

Task Standard: Upon completion of this JPM, the Examinee will have properly entered into the RM-11R, the High and Low release setpoints for a Waste Gas Decay Tank Gas Release Permit.

Required Materials: APF 07B-001-08-06, Gas Decay Tank Release Permit; SYS SP-121, rev 18, Operation of the G. A. Monitor System; RM-11R General

References:

SYS SP-121, rev 18, Operation of the G. A. Monitor System Handouts: APF 07B-001-08-06, Gas Decay Tank Gas Release Permit; SYS SP-121, rev 18, Operation of the G. A. Monitor System Initiating Cue: You are the Reactor Operator. The Control Room Supervisor (CRS) directs you to enter the Gas Release Permit setpoints at the RM-11R in preparation of a release of a Waste Gas Decay Tank to the environs per SYS SP-121, rev 18, Operation of the G. A. Monitor System.

Time Critical Task: No Validation Time: 15 minutes

Appendix C Page 2 of 8 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

SYS SP-121 rev 18, Operation of the G. A. Monitor System, section 6.3, Channel item &

Release setpoint operations using RM-11R (SP056A)

Booth operator MUST ensure RM-11R setpoints for channels 009 and 010 are returned to their NORMAL values inbetween Examinees.

Performance Step: 1 NOTE: If entering release setpoints for a safety related monitor, section 6.6, Channel Item & Release Setpoint Operations Using RM-23 should be used.

Standard: NA: process radiation monitor being used for the evolution is not safety related.

Comment: SYS SP-121 NOTE before step 6.3.1

• Performance Step: 2 To change the value of a Supervisor RM-80 database Channel Item, perform the following: Select the desired channel per step

6.1.2. Standard

Reference procedure step 6.1.2: At the RM-11R Ensure Grid 1 is displayed

1. Key in the three digit Channel ID number displayed on the grid (103)

2. Press the SEL key

3. Check the selected channel outlined in white Comment: (procedure step 6.3.1.1 directs to procedure step 6.1.2 of SYS SP-121)

• Performance Step: 3 Place Supervisor Master Key in the key slot and turn to the SUPERVISOR position.

Standard: Lower right corner of console/keyboard, key turned clockwise to the SUPERVISOR position.

Comment: (procedure step 6.3.1.2)

Appendix C Page 3 of 8 Form ES-C-1 PERFORMANCE INFORMATION

• Performance Step: 4 RM-11R Displays the Supervisor RM-80 database for 103.

Standard: At the console/keyboard:

1. Press the LIT key

2. Press the Grid 5 key

3. Press the SEL key

4. Verify the Supervisor RM-80 database screen is displayed for 103 Comment: (procedure step 6.3.1. parts 3, 4, 5, 6)

• Performance Step: 5 Select Channel Item for High setpoint (Channel Item 009)

Standard: At the console/keyboard, select desired Channel Item to be changed.

1. Press the minus (-) key

2. Key in desired Channel Item number (9)

3. Press the SEL key

4. Check the selected Channel Item is backlit Comment: (procedure step 6.3.1. parts 7, 8, 9, 10)

• Performance Step: 6 Enter setpoint data for High setpoint (Channel Item 009) from Gas Release Permit Standard: At the console/keyboard:

1. Key in the desired Channel Item value in the correct format. Example: 5.79E-5 is keyed in as 5, 7, 9, -, 0, 5

2. GDT channel item 9 setpoint is 6.23 E+4 (keyed as 6, 2, 3, +, 0, 4)

3. Press the ENTER key Comment: (procedure step 6.3.1. parts 11, 12)

Appendix C Page 4 of 8 Form ES-C-1 PERFORMANCE INFORMATION

• Performance Step: 7 Verify setpoint data entry is correct.

Standard: On the RM-11R CRT screen:

A message area will appear at the bottom of the screen,

1. If the data in the message area is correct, then press the ENTER key and proceed to step 6.3.1.14.

2. If the data in the message area is incorrect, then press the CLEAR key and return to step 6.3.1.11.

Examinee should press the ENTER key.

Comment: (procedure step 6.3.1 part 13)

• Performance Step: 8 Verify Channel Item 009 updated.

Standard: On the RM-11R CRT screen:

If the entry is accepted, then the message at the bottom of the CRT will indicate the value accepted and the value for that item will be updated in the RM-80 Column and the Master Column.

(If the entry is not accepted, then an error message will be displayed at the bottom of the CRT. Press the CLEAR key, and return to step 6.3.1.11.)

Examinee verifies setpoint value accepted in BOTH columns.

Comment: (procedure step 6.3.1 parts 14, 15)

Performance Step: 9 Examinee recognizes that the same actions at RM-11R must be performed for Low setpoint, Channel Item 010.

Standard: Examinee uses procedure steps 6.3.1 parts 7 through15.

Comment:

Appendix C Page 5 of 8 Form ES-C-1 PERFORMANCE INFORMATION

• Performance Step: 10 Select Channel Item for Low setpoint (Channel Item 010)

Standard: At the console/keyboard, select desired Channel Item to be changed.

1. Press the minus (-) key

2. Key in desired Channel Item number (10)

3. Press the SEL key

4. Check the selected Channel Item is backlit OR Select Channel Item (010) by depressing the SEL key. (see procedure NOTE). Check the selected Channel Item is backlit (010).

Procedure NOTE: The Channel Item number may be advanced by depressing the SEL key.

Comment: (procedure step 6.3.1. parts 7, 8, 9, 10)

• Performance Step: 11 Enter setpoint data for Low setpoint (Channel Item 010) from Gas Release Permit Standard: At the console/keyboard:

1. Key in the desired Channel Item value in the correct format. Example: 5.79E-5 is keyed in as 5, 7, 9, -, 0, 5

2. GDT channel item 10 setpoint is 8.83 E+2 (keyed as 8, 8, 3, +, 0, 2)

3. Press the ENTER key Comment: (procedure step 6.3.1. parts 11, 12)

• Performance Step: 12 Verify setpoint data entry is correct.

Standard: On the RM-11R CRT screen:

A message area will appear at the bottom of the screen,

1. If the data in the message area is correct, then press the ENTER key and proceed to step 6.3.1.14.

2. If the data in the message area is incorrect, then press the CLEAR key and return to step 6.3.1.11.

Examinee should press the ENTER key.

Comment: (procedure step 6.3.1 part 13)

Appendix C Page 6 of 8 Form ES-C-1 PERFORMANCE INFORMATION

• Performance Step: 13 Verify Channel Item 010 updated.

Standard: On the RM-11R CRT screen:

If the entry is accepted, then the message at the bottom of the CRT will indicate the value accepted and the value for that item will be updated in the RM-80 Column and the Master Column.

(If the entry is not accepted, then an error message will be displayed at the bottom of the CRT. Press the CLEAR key, and return to step 6.3.1.11.)

Examinee verifies setpoint value accepted in BOTH columns.

Comment: (procedure step 6.3.1 parts 14, 15)

Performance Step: 14 When no further changes are desired, then turn the Supervisor Master Key to the NORMAL position.

Standard: Lower right corner of console/keyboard, key turned counter clockwise to the NORMAL position.

Comment: (procedure step 6.3.1 part 16)

Performance Step: 15 Gas Decay Tank Release Permit High and Low setpoints have been entered at the RM-11R. The Examinee has completed the JPM when the High and Low setpoints have been entered at the RM-11R.

Standard: Examinee has completed JPM. Examinee returns permit to Examiner.

Comment:

Terminating Cue: Examinee has completed JPM when High and Low setpoints have been entered at the RM-11R. Examinee returns permit to Examiner.

Appendix C Page 7 of 8 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: S5, Set RM-11R setpoints for Waste Gas Decay Tank Gas Release Permit Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

Appendix C Page 8 of 8 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: Chemistry has generated a Gas Release Permit for a Waste Gas Decay Tank release to the environs.

INITIATING CUE: You are the Reactor Operator. The Control Room Supervisor (CRS) directs you to enter the Gas Release Permit setpoints at the RM-11R in preparation of a release of a Waste Gas Decay Tank to the environs per SYS SP-121, rev 18, Operation of the G.

A. Monitor System.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Wolf Creek Task No.: N/A Task

Title:

Respond to Main Turbine Hi-Hi JPM No.: S6 Vibration K/A

Reference:

K4.03 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom Simulator x Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: You are the Balance of Plant Operator. Following a power reduction, the plant is ready to return to full power.

Task Standard: Upon completion of this JPM, the Examinee will have completed the procedures to manually trip the reactor and will have manually tripped the turbine when it fails to automatically trip.

Required Materials: Simulator setup - IC at power < 100% -- see Initial Condition. With bearings 1 and 2 > 12 mils and MCB 119A actuated.

Insert Malfunctions:

mAC02C - Turbine trip fail - No Auto trip on Rx trip/SI mAC06A at 13 mils for Turbine Bearing #1 vibration, increasing to 14.6 mils over 5-10 minutes and mAC06B at 13 mils for Turbine Bearing #2 vibration, increasing to 14.6 mils over 5-10 minutes.

FREEZE. Go to RUN at Lead Examiners discretion.

General

References:

ALR 00-119A, rev 12, Turbine Vibration Hi and OFN AC-002, rev 16, Main Turbine High Vibration Handouts:

Initiating Cue: The Control Room Supervisor has directed you to respond to ALR 00-119A, rev 12, Turbine Vibration Hi.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: No Validation Time: 15 minutes

Appendix C Page 3 of 8 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Performance Step: 1 ALR 00-119A, step 1: Go to OFN AC-002, Main Turbine High Vibration, step 1 while continuing with this procedure Standard: Examinee transitions to OFN AC-002, Main Turbine High Vibration, step 1.

Comment: (If asked) CRS CUE: I will reassign the remainder of ALR 119A.

ALR 00-119 step 1 Performance Step: 2 Check Main Turbine Vibration - requires turbine trip

a. Perform the following:

Use NPIS "Turn on Code" MTG OR Dispatch operator to Panel AC-121 in EHC Room to record data on Attachment B, Panel AC-121 Operation SPEED VIBRATION LIMIT ON ANY JOURNAL THAT REQUIRES TURBINE TRIP LESS THAN 800 GREATER THAN 8 mils rpm 800 - 1400 rpm 10 mils for 2 minutes OR GREATER THAN 14 mils at any time 1400 - 1800 rpm 10 mils for 15 minutes OR greater than or equal to 12 mils at any time with symptoms of high vibration present

b. Check vibration limit - GREATER THAN LIMIT Standard: Using NPIS computer terminal, selects MTG display.

Determines that bearing #1 and #2 both exceed 12 mils.

Dispatches operator to EHC Room (may request CRS to dispatch operator).

Comment: CRS CUE: I will dispatch an operator.

OFN AC-002 step 1

Appendix C Page 4 of 8 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 3 Check initial reactor power - 50%

Standard: Using the Power Range meters on RL004, or NPIS displays, determines that power is greater than 50%.

Comment: OFN AC-002 step 2 Performance Step: 4 Trip the reactor Standard: Manually trips reactor from RL006 (SB HS-1) or RL004 (SB HS-

42) by turning Reactor Trip switch to TRIP.

Verify rods drop (DRPI).

Comment: CRS CUE: If asked: Continue with the OFN AC-002.

OFN AC-002 step 3 Performance Step: 5 Ensure turbine trip Standard: Turbine NOT tripped.

Determines STOP valves OPEN on RL006 Panel AC XX-2.

Comment: OFN AC-002 step 4

• Performance Step: 6 Manually trip the turbine Standard: Locates and pushes Trip button on RL005, Turbine Panel AC XX-1 Verifies STOP valves CLOSED on RL006 Panel AC XX-2.

Comment: OFN AC-002 step 4. Once Examinee determines the Turbine is tripped, the Examiner may terminate the JPM.

Appendix C Page 5 of 8 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 7 Go to EMG E-0, Reactor Trip or Safety Injection, while continuing with this procedure Standard: Examinee requests direction from CRS.

Comment: CRS CUE: I will assign another operator to perform the actions of EMG E-0. Continue with the OFN.

OFN AC-002 step 5 Performance Step: 8 Check turbine vibration - stable or decreasing Standard: Using NPIS computer terminal, selects MTG display.

Determines that bearing #1 and #2 continue to exceed 12 mils.

Vibration continues to INCREASE.

Transition to RNO column to perform 6RNOa through d - these are performance steps 8RNOa through d Comment: OFN AC-002 step 6 Performance Step: Perform the following:

8RNO a

a. Start both MDAFW Pumps.

Standard: Action does not require Operator action due to the Reactor Trip.

Both MDAFW pumps should be operating. Examinee should verify operation of MDAFW pumps at panel RL005.

• AL HIS-23A, MD AFP A - Red light LIT

• AL HIS-22A, MD AFP B - Red light LIT Comment: OFN AC-002 step 6 RNO a Performance Step: b. Trip both MFP's.

8RNOb Standard: Action does not require Operator action due to the Reactor Trip.

Both MFPs should be tripped. Examinee should verify by Main Control Board alarm 00-120A (MFP A Trip) and 00-123A (MFP B Trip) are illuminated.

Comment: OFN AC-002 step 6 RNO b

Appendix C Page 6 of 8 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: c. Place condenser vacuum pumps in Pull To Lock (PTL).

8RNOc Standard: On RL023, place Condenser Vac Pump A, CG HIS- 1, in Pull to Lock. Verify Red light extinguished and Green light LIT.

On RL023, place Condenser Vac Pump B, CG HIS- 2, in Pull to Lock. Verify Red light extinguished and Green light LIT.

On RL023, place Condenser Vac Pump C, CG HIS- 3, in Pull to Lock. Verify Red light extinguished and Green light LIT.

Comment: OFN AC-002 step 6 RNO c Performance Step: d. Open Condenser vacuum breaker valve 8RNOd o AD HIS-113 Standard: On RL023, CLOSE Condenser Vac Breaker AD HIS-113, by depressing CLOSE pushbutton. Verify Red light extinguishes and Green light LIT.

Comment: OFN AC-002 step 6 RNO d Performance Step: 9 When Turbine is verified tripped at OFN AC-002 step 4 or at the end of the performance of OFN AC-002 step 6, the Examiner can terminate the JPM.

Standard: Turbine is tripped Comment:

Terminating Cue: Turbine is tripped.

Appendix C Page 7 of 8 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: S6, Respond to Main Turbine Hi-Hi Vibration Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

Appendix C Page 8 of 8 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: You are the Balance of Plant Operator. Following a power reduction, the plant is ready to return to full power.

INITIATING CUE: The Control Room Supervisor has directed you to respond to ALR 00-119A, rev 12, Turbine Vibration Hi.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Wolf Creek Task No.: N/A Task

Title:

Verify Containment Purge Isolation JPM No.: S7 K/A

Reference:

A3.01 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom Simulator x Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Containment mini-purge exhaust is operating per SYS GT-120, section 6.1. A Control Room Ventilation Isolation Signal (CRVIS) has occurred.

Task Standard: Upon completion of this JPM, the Examinee will have verified that Containment Purge System is isolated.

Required Materials: Simulator IC 304. Group password is WC. IC password is appLe1.

Ensure IC 304 has these malfunctions inserted: Malfunctions:

MSA07A & mSA07B for the inadvertent CRVIS.

MSA10A & mSA10B for the CPIS.

Figure out how to have GTHZ11 & 12 NOT LIT, but will turn lit when the pushbuttons for GT HIS-11/12 are depressed.

mSA27GT09 for GTHZ11 mSA27GT10 for GTHZ12 General

References:

ALR 00-063A, rev 15A, CRVIS, ALR 00-059D, rev 11, CPIS.

Handouts: ALR 00-063A, rev 15A, CRVIS, ALR 00-059D, rev 11, CPIS Initiating Cue: You are the Reactor Operator. The Control Room Supervisor (CRS) directs you to perform ALR 00-063A, CRVIS.

Time Critical Task: No Validation Time: 25 minutes

Appendix C Page 2 of 7 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Examinee begins in ALR 00-063A, rev 15A, CRVIS. Examinee transitions to ALR 00-059D, rev 11, CPIS.

Performance Step: 1 Check EMGs - not in effect Standard: Examinee asks CRS if any EMGs are in effect.

Comment: CUE: CRS response: There are no EMGs in effect.

(ALR 00-063A step 1)

Performance Step: 2 Check Annunciator 00-063C, CTRL RM CL2 HI CRVIS - clear Standard: Locates 00-063C. Verifies alarm is clear.

Comment: ALR 00-063A step 2 Performance Step: 3 Check Annunciator 00-063D, CTRL RM RAD HI CRVIS - clear Standard: Locates 00-063D. Verifies alarm is clear.

Comment: ALR 00-063A step 3 Performance Step: 4 Check Annunciator 00-059D, CPIS - clear Standard: Locates 00-059D. Verifies alarm is actuated. Transitions to RNO column.

RNO: Go to ALR 00-059D, CPIS, step 1 Comment: Transition to ALR 00-059D, CPIS ALR 00-063A step 4 Performance Step: 5 Check if Control Room Ventilation Isolation Actuated:

a. Annunciator 00-063A, CRVIS - LIT Standard: Annunciator 00-063A, CRVIS - LIT Comment: (ALR 00-059D step 1)

Appendix C Page 3 of 7 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 6 Check Fuel Handling - in progress Standard: Examinee verifies NO fuel handling in progress. Transition to RNO column.

RNO: Go to step 4.

Comment: CRS CUE: If asked: No fuel handling is in progress.

ALR 00-059D step 2

• Performance Step: 7 Verify Containment Purge Isolation:

a. Check ESFAS status panel CPIS section - all White light lit o Red train o Yellow train Standard: Locate ESFAS status panels at panel RL018. Locate CPIS section.

o Red train - Determines that all White lights are NOT LIT o GTHZ12 is NOT LIT o Yellow train - All White lights are NOT LIT o GTHZ11 is NOT LIT Transition to RNO column.

Comment: ALR 00-059D step 4 Performance Step: 8 Step 4 RNO a: Perform the following:

Standard: Completion of performance steps 8a, 8b, 8c and 8d.

Comment: ALR 00-059D step 4 RNOa

• Performance Step: 8a Manually actuate containment purge isolation o SA HS-11 (Red train) o SA HS-15 (Yellow train)

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION Standard: Locate SA HS-11 on panel RL018. Depress the ACTUATE pushbutton.

Locate SA HS-15 on panel RL018. Depress the ACTUATE pushbutton.

Comment: ALR 00-059A 4 RNO a. 1 Performance Step: 8b If any CPIS component NOT properly aligned, then manually align component. If component(s) can NOT be aligned, then manually or locally isolate containment penetration.

Standard: Locate CPIS section on ESFAS status panels (panel RL018).

o Red train: All white lights are NOT LIT o GTHZ12 is NOT LIT o Yellow train: All white lights are NOT LIT o GTHZ11 is NOT LIT Comment: ALR 00-059A 4 RNO a. 2

• Performance Step: 8c Manually align component GTHZ11 Standard: At RL020, depress CLOSE pushbutton for GT HIS-11, CTMT Mini Purge Exh Inner CTMT Iso.

At ESFAS panel for Yellow train CPIS section, GTHZ11 - White Light LIT Comment: ALR 00-059A 4 RNO a. 2 continued

• Performance Step: 8d Manually align component GTHZ12 Standard: At RL020, depress CLOSE pushbutton for GT HIS-12, CTMT Mini Purge Exh Outer CTMT Iso.

At ESFAS panel for Red train CPIS section, GTHZ12 - White Light LIT Comment: Once CPIS section Red and Yellow train all White lights are LIT, the JPM is complete. At Lead Examiners discretion, the JPM can be stopped at this point.

ALR 00-059A 4 RNO a. 2

Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION Terminating Cue: All White lights LIT for CPIS section Red and Yellow trains.

Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: S7, Verify Containment Purge Isolation Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: Containment mini-purge exhaust is operating per SYS GT-120, section 6.1. A Control Room Ventilation Isolation Signal (CRVIS) has occurred.

INITIATING CUE: You are the Reactor Operator. The Control Room Supervisor (CRS) directs you to perform ALR 00-063A, CRVIS.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Wolf Creek Task No.: N/A Task

Title:

Isolate a leaking PORV JPM No.: S8 K/A

Reference:

A2.01 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom Simulator x Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: You are the Reactor Operator. The plant is at power with no abnormal lineups and no equipment out of service. No one is in Containment.

Task Standard: At the completion of this JPM, the leaking Pressurizer PORV will be isolated and the PRT level will be stable.

Required Materials: Simulator IC 305. Group password is WC. IC password is appLe1.

Ensure malfunction mBB19B at 5% is inserted into the IC.

General

References:

Alarm Response Procedure ALR 00-034E rev 9, PRT Press High Handouts: ALR 00-034E rev 9, PRT Press High Initiating Cue: The PRT Pressure High alarm has illuminated, the CRS directs you to respond to the alarm using ALR 00-34E rev 9, PRT Press High.

Time Critical Task: No Validation Time: 20 minutes

Appendix C Page 2 of 7 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Performance Step: 1 Check Pressurizer Relief Tank Pressure - GREATER THAN 6 PSIG o BB PI-469 Standard: On panel RL021 Examinee reads gauge BB PI-469 and determines pressure is > 6 psig Comment: ALR 00-034E step 1 Performance Step: 2 Check If Containment Should Be Evacuated:

o PRT Pressure - INCREASING o PRT Pressure - APPROACHING RUPTURE DISC RELEASE PRESSURE NO: RNO is to go to step 4 Standard: On panel RL021 Examinee references BB PI-469 and determines that PRT pressure is NOT near rupture disc pressure and from the RNO goes to step 4.

Comment: ALR 00-034E step 2 Performance Step: 3 Ensure PRT Nitrogen Supply Containment Isolation Valves -

CLOSED o BB HIS-8026 o BB HIS-8027 Standard: On panel RL001 Examinee references BB HIS-8026 and BB HIS-8027 and determines that Green light is LIT for both and Red light is extinguished for both.

Comment: ALR 00-034E step 4

Appendix C Page 3 of 7 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 4 Check For Pressurizer PORV leakage:

a. Check Pressurizer PORV discharge temperature -

greater than Normal o BB TI-463 Standard: On RL021 Examinee references BB TI-463 and determines that PORV discharge temperature is HIGHER than normal.

Comment: Normal PORV discharge temperature is Containment temperature, typically 75°F.

ALR 00-034E step 5

• Performance Step: 5 Identify And Isolate Leaking PORV:

a. Close PZR PORV 455A block valve o BB HIS-8000A

b. Check the following:

Pressurizer PORV Discharge Temperature -

DECREASING o BB TI-463 Pressurizer Pressure - INCREASING o BB PI-456 o BB PI-457 o BB PI-458 Standard: a. On RL021, closes BB HV-8000A by depressing the CLOSE pushbutton on BB HIS-8000A. Verifies that Green light is LIT and Red light is extinguished.

b On RL021, references BB TI-463, and determines that Pressurizer PORV discharge temperature is STABLE.

On RL002, references BB PI-456, BB PI-457, and BB PI-458 and determines that Pressurizer pressure is DECREASING.

Transition to RNO column Step 6b.

Comment: ALR 00-034E step 6

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION

• Performance Step: Perform the following:

6RNO b

1. Open PZR PORV 455A block valve.

o BB HIS-8000A

2. Go To Step 6.d Standard: On RL021, opens BB HV-8000A by pushing the OPEN pushbutton on BB HIS-8000A. Verifies that Green light is extinguished and Red light is LIT.

Transition back to step 6d.

Comment: ALR 00-034E step 6 RNO b1 and b2

• Performance Step: 6d Close PZR PORV 456A block valve.

o BB HIS-8000B Standard: On RL021, closes BB HV-8000B by depressing the CLOSE pushbutton on BB HIS-8000B. Verifies that Green light is LIT and Red light is extinguished.

Comment: ALR 00-034F step 6d

Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION

• Performance Step: 6e Check the following:

Pressurizer PORV discharge temperature -

DECREASING o BB TI-463 Pressurizer pressure - INCREASING o BB PI-456 o BB PI-457 o BB PI-458 Standard: On RL021, references BB TI-463, and determines that Pressurizer PORV discharge temperature is DECREASING.

On RL002, references BB PI-456, BB PI-457, and BB PI-458 and determines that Pressurizer pressure is INCREASING.

Reports to the CRS that the PORV BB HV-8000B was leaking and is isolated per ALR 00-034F.

Comment: At this point the Lead Examiner may acknowledge the report and inform the Examinee that the CRS will finish the Alarm response procedure.

JPM complete when Examinee identifies and isolates the leaking PORV.

ALR 00-034E step 6e Performance Step: 6e JPM complete when Examinee identifies and isolates the leaking PORV.

Standard: JPM Complete when Examinee identifies and isolates the leaking PORV.

Comment: ALR 00-034F step 6e Terminating Cue: Examinee reports to the CRS that the PORV BB HV-8000B was leaking and is isolated per ALR 00-034F at step 6e.

Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: S8, Isolate a leaking PORV Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: You are the Reactor Operator. The plant is at power with no abnormal lineups and no equipment out of service. No one is in Containment.

INITIATING CUE: The PRT Level Hi Lo alarm has illuminated, the CRS directs you to respond to the alarm using ALR 00-34E rev 9, PRT Press High.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Wolf Creek Task No.: N/A Task

Title:

DC Load Shedding JPM No.: P-1 K/A

Reference:

K2.01 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: X Actual Performance:

Classroom Simulator Plant X READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: You are the Turbine Bldg. Operator, a loss of all AC power has occurred.

Task Standard: Upon completion of this JPM the Examinee will have shed DC loads from NK01, NK02, NK03 and NK04 per Attachment C of EMG C-0, Loss of All AC Power.

Required Materials: Ensure an "Information Only" copy of Attachment C to EMG C-0 is available.

General

References:

EMG C-0, Loss of All AC Power, Rev. 18, Attachment C.

Handouts: Ensure an "Information Only" copy of Attachment C to EMG C-0 is available.

Initiating Cue: The Control Room Supervisor (CRS) directs you to shed non-essential DC loads using Attachment "C" of EMG C-0.

Upon arriving at a component, describe what you expect to see, what you and what you expect to happen.

Time Critical Task: No Validation Time: 20 minutes

Appendix C Page 2 of 7 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Performance Step: 1 Battery NK-11:

Standard: Locate the NK Busses for NK-11 on the 2016' level of the Control Bldg., second door on the east, past the missile door (SWGR #1 room). Complete elements 1a through 1h.

Comment: Attachment C of EMG C-0

• Performance Step: 1a Disconnect NK-4110.

Standard: Locate disconnect NK4110 on NK-41. Open the disconnect by rotating the handle down to the OFF position.

Comment: Cue: Handle is in the OFF position.

• Performance Step: 1b Disconnect NK-4111.

Standard: Locate disconnect NK4111 on NK-41. Open the disconnect by rotating the handle down to the OFF position.

Comment: Cue: Handle is in the OFF position.

• Performance Step: 1c Disconnect NK-4112.

Standard: Locate disconnect NK4112 on NK-41. Open the disconnect by rotating the handle down to the OFF position.

Comment: Cue: Handle is in the OFF position.

• Performance Step: 1d Disconnect NK-4113.

Standard: Locate disconnect NK4113 on NK-41. Open the disconnect by rotating the handle down to the OFF position.

Comment: Cue: Handle is in the OFF position.

• Performance Step: 1e Disconnect NK-4119.

Standard: Locate disconnect NK4119 on NK-41. Open the disconnect by rotating the handle down to the OFF position.

Comment: Cue: Handle is in the OFF position.

Appendix C Page 3 of 7 Form ES-C-1 PERFORMANCE INFORMATION

• Performance Step: 1f Disconnect NK-4120.

Standard: Locate disconnect NK4120 on NK-41. Open the disconnect by rotating the handle down to the OFF position.

Comment: Cue: Handle is in the OFF position.

• Performance Step: 1g Disconnect NK-5114.

Standard: Locate disconnect NK5114 on NK-51. Open the disconnect by rotating the handle down to the OFF position.

Comment: Cue: Handle is in the OFF position.

• Performance Step: 1h Disconnect NK-5117.

Standard: Locate disconnect NK5117 on NK-51. Open the disconnect by rotating the handle down to the OFF position.

Comment: Cue: Handle is in the OFF position.

Performance Step: 2 Battery NK-13.

Standard: Locate the NK Busses for NK-13 on the 2016' level of the Control Bldg., second door on the east side, past the missile door (SWGR #1 to SWGR #3 room). Complete element 2a.

Comment:

• Performance Step: 2a Disconnect NK-4302.

Standard: Locate disconnect NK4302 on NK-43. Open the disconnect by rotating the handle down to the OFF position.

Comment: Cue: Handle is in the OFF position.

Performance Step: 3 Battery NK-12:

Standard: Locate the NK Busses for NK-12 on the 2016' level of the Control Bldg., third door on the east, past the missile door (SWGR #4 room then through to SWGR #4 to SWGR #2 room). Complete element 3a.

Comment:

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION

• Performance Step: 3a Disconnect NK-4204.

Standard: Locate disconnect NK4204 on NK-42. Open the disconnect by rotating the handle down to the OFF position.

Comment: Cue: Handle is in the OFF position.

Performance Step: 4 Battery NK-14:

Standard: Locate the NK Busses for NK-14 on the 2016' level of the Control Bldg., third door on the east side, past the missile door (SWGR

1. 4 room). Complete elements 4a through 4h.

Comment: Cue: Handle is in the OFF position.

• Performance Step: 4a Disconnect NK-4407.

Standard: Locate disconnect NK4407 on NK-44. Open the disconnect by rotating the handle down to the OFF position.

Comment: Cue: Handle is in the OFF position.

• Performance Step: 4b Disconnect NK4408.

Standard: Locate disconnect NK4408 on NK-44. Open the disconnect by rotating the handle down to the OFF position.

Comment: Cue: Handle is in the OFF position.

• Performance Step: 4c Disconnect NK-4411.

Standard: Locate disconnect NK4411 on NK-44. Open the disconnect by rotating the handle down to the OFF position.

Comment: Cue: Handle is in the OFF position.

• Performance Step: 4d Disconnect NK-4412.

Standard: Locate disconnect NK4412 on NK-44. Open the disconnect by rotating the handle down to the OFF position.

Comment: Cue: Handle is in the OFF position.

Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION

• Performance Step: 4e Disconnect NK-4413.

Standard: Locate disconnect NK4413 on NK-44. Open the disconnect by rotating the handle down to the OFF position.

Comment: Cue: Handle is in the OFF position.

• Performance Step: 4f Disconnect NK-4417.

Standard: Locate disconnect NK4417 on NK-44. Open the disconnect by rotating the handle down to the OFF position.

Comment: Cue: Handle is in the OFF position.

• Performance Step: 4g Disconnect NK-5416.

Standard: Locate disconnect NK5416 on NK-54. Open the disconnect by rotating the handle down to the OFF position.

Comment: Cue: Handle is in the OFF position.

• Performance Step: 4h Disconnect NK-5417.

Standard: Locate disconnect NK5417 on NK-54. Open the disconnect by rotating the handle down to the OFF position.

Comment: Cue: Handle is in the OFF position.

Terminating Cue: The JPM is complete when NK-5417 has been turned to OFF.

Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: P-1, DC Load Shedding Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: You are the Turbine Bldg. Operator, a loss of all AC power has occurred.

INITIATING CUE: The Control Room Supervisor (CRS) directs you to shed non-essential DC loads using Attachment "C" of EMG C-0.

Upon arriving at a component, describe what you expect to see, what you expect to do, and what you expect to happen.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Wolf Creek Task No.: N/A Task

Title:

JPM No.: P-2 AFW Pump and Piping Cooldown K/A

Reference:

A2.06 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: X Actual Performance:

Classroom Simulator Plant X READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: You are the Turbine Bldg. Operator, the plant is experiencing a Loss of Heat Sink Event and the Control Room is responding using EMG FR-H1 rev 19A, Response to Loss of Secondary Heat Sink.

Task Standard: Upon completion of this JPM the Examinee will have locally tripped the Turbine Driven Auxiliary Feedwater Pump (TDAFP) and will have cooldowned the TDAFP piping per SYS AL-400, rev 9, AFW Pump and Piping Cooldown.

Required Materials:

General

References:

EMG FR-H1 rev 19A, Response to Loss of Secondary Heat Sink, SYS AL-400 rev 9, AFW Pump and Piping Cooldown.

Handouts:

Initiating Cue: The Control Room Supervisor informs you that at the step 5 RNO of EMG FR-H1, the BOP noted the TD AFW pump discharge temperature is at 230°F and directs you to perform steps 6.1.5.2 and applicable portions of 6.1.5.3 through 6.1.5.6a (as required to cool down the TD AFW Pump) of SYS AL-400. Notify the Control Room when you have completed the required actions. Prerequisites have been completed.

Upon arriving at a component, describe what you expect to see, what you and what you expect to happen.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: No Validation Time: 25 minutes

Appendix C Page 3 of 7 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

NOTE: AP 21-005, CONTROL OF PIPE CAPS AND VENT/DRAIN FLANGES, is used in support of routine evolutions. The initial conditions of this JPM are not considered routine.

Examinees may vary their vent techniques.

Performance Step: 1 IF the turbine drive AFW pump is affected, THEN prevent pump auto start as follows:

Standard: Perform elements 1a and 1b.

Comment: SYS AL-400 step 6.1.5.2

• Performance Step: 1a Locally trip the turbine drive AFW pump.

Standard: Locate the Turbine Driven Aux Feed Pump on the 2000' level of Area 5, east side of the corridor. Locally trip the Trip and Throttle valve by pushing down on the mechanical overspeed trip lever.

The lever is located on the south end of the turbine.

Comment: Cue: The trip linkage is moved away from the Trip and Throttle valve.

• Performance Step: 1b Ensure Aux. Feedwater Pump Turbine Mechanical Trip light FC ZL-312DA is LIT.

Standard: Contact Control Room and verify status of the light.

Comment: Cue: Acknowledge the request; report Red light is lit on FC ZL-312DA.

Performance Step: 2 Vent affected pumps as necessary to remove any steam.

Standard: Perform elements 2a and 2b.

Comment: SYS AL-400, step 6.1.5.3, last two asterisk items

• Performance Step: 2a AL-V123 for TD AFW pump - VENTED Standard: Locate the valve on the north end of the pump. Remove the flange. Open the valve by turning the handwheel in the counter-clockwise direction.

Comment: After Examinee explains the process of venting via AL-V123, CUE: Flange is removed. Handwheel stops turning, stem is extended, steam is coming from vent.

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION

• Performance Step: 2b AL-V124 for TD AFW pump - VENTED Standard: Locate valve on the south end of the pump. Remove the flange.

Open the valve by turning the handwheel in the counter-clockwise direction.

Comment: After examinee explains the process of venting via AL-V124, CUE: Flange is removed. Handwheel stops turning, stem is extended, steam is coming from vent.

Performance Step: 3 IF additional cooling is desired, THEN cool affected pumps by opening casing and discharge drain valves.

Standard: Call Control Room for guidance.

Comment: CUE: If asked temperature is slowly decreasing. If Control Room called, No additional cooling required.

SYS AL-400, step 6.1.5.4 Performance Step: 4 Repeat steps as necessary until all affected AFW Pump temperatures are less than 200°F. (Mark N/A if steps are not repeated.)

Standard: Recognize Control Room stated no further cooling required.

Comment: CUE: Control Room Temperature is at 190°F and decreasing.

SYS AL-400 step 6.1.5.5 Performance Step: 5 WHEN all temperatures are less than 200° F, THEN realign AFW Pumps as follows:

Standard: Complete element 5a.

Comment: SYS AL-400, step 6.1.5.6 Performance Step: 5a Ensure all vent and drain valves are closed and flanged. (Mark N/A if pump was not affected)

Standard: Complete elements 5a(1) through 5a(4)

Comment:

Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: AL-V080 for TD AFW pump - CLOSED and FLANGED 5a(1)

Standard: Recognize valve was not used.

Comment: SYS AL-400, step 6.1.5.6 item 9 Performance Step: AL-V114 for TD AFW pump - CLOSED and FLANGED 5a(2)

Standard: Recognize valve was not used.

Comment: SYS AL-400, step 6.1.5.6 item 10

• Performance Step: AL-V123 for TD AFW pump - CLOSED and FLANGED 5a(3)

Standard: Check the valve closed by turning the handwheel in the clockwise direction. Replace the flange on AL-V123 ensuring that a new gasket has been installed and the old one removed.

Comment: After Examinee describes closing valve, CUE: "handwheel stops turning, stem is retracted," after Examinee describes reinstalling flange, "flange is installed".

SYS AL-400, step 6.1.5.6 item 11

• Performance Step: AL-V124 for TD AFW pump - CLOSED and FLANGED 5a(4)

Standard: Check the valve closed by turning the handwheel in the clockwise direction. Replace the flange on AL-V124 ensuring that a new gasket has been installed and the old one removed.

Comment: After Examinee describes closing valve, CUE: "handwheel stops turning, stem is retracted," after Examinee describes reinstalling flange, "flange is installed".

SYS AL-400, step 6.1.5.6 item 12 Terminating Cue: Report completion of task to Control Room.

Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: P-2, AFW Pump and Piping Cooldown Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: You are the Turbine Bldg. Operator, the plant is experiencing a Loss of Heat Sink Event and the Control Room is responding using EMG FR-H1 rev 19A, Response to Loss of Secondary Heat Sink.

INITIATING CUE: The Control Room Supervisor informs you that at the step 5 RNO of EMG FR-H1, the BOP noted the TD AFW pump discharge temperature is at 230°F and directs you to perform steps 6.1.5.2 and applicable portions of 6.1.5.3 through 6.1.5.6a (as required to cool down the TD AFW Pump) of SYS AL-400. Notify the Control Room when you have completed the required actions. Prerequisites have been completed.

Upon arriving at a component, describe what you expect to see, what you expect to do, and what you expect to happen.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Wolf Creek Task No.: N/A Task

Title:

Gas Binding of ECCS Pumps JPM No.: P-3 K/A

Reference:

A2.04 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: x Actual Performance:

Classroom Simulator Plant x READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: You are the Auxiliary Building Operator. The plant has experienced a Small Break LOCA. The Reactor has tripped and Safety Injection has been actuated.

Task Standard: Upon completion of this JPM, the Examinee will have vented Safety Injection Pump B.

Required Materials: Attachment B of OFN BG-045, rev 1, Gas Binding of CCPS or SI Pumps General

References:

OFN BG-045, rev 1, Gas Binding of CCPS or SI Pumps Handouts: OFN BG-045, rev 1, Gas Binding of CCPS or SI Pumps Initiating Cue: The crew is responding to the event using EMG E-0 rev 21, Reactor Trip or Safety Injection. Concurrent with this procedure, the Control Room Supervisor (CRS) has determined that the B Safety Injection Pump has become gas bound and is using OFN BG-045, rev 1, Gas Binding of CCPS or SI Pumps, to restore the pump. Using OFN BG-045, the CRS directs you to visually inspect the B SI pump per step 14 and vent the pump using Attachment B per step 15.

Time Critical Task: No Validation Time: 25 minutes

Appendix C Page 2 of 7 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

AP 21-005, CONTROL OF PIPE CAPS AND VENT/DRAIN FLANGES, is used in support of routine evolutions. The initial conditions of this JPM are not considered routine. Examinees may vary their vent techniques.

Performance Step: 1 Check No Signs Of Mechanical Damage To Affected SI Pump.

Standard: Visually inspects Safety Injection (SI) pump B for mechanical damage.

Comment: B SI pump located 1974 of Auxiliary Building.

CUE: The pump and motor are normal.

OFN BG-045 rev 1, step 14 Performance Step: 2 Vent Affected SI Pump Using ATTACHMENT B, VENTING SAFETY INJECTION PUMPS Standard: Locates section B.2 of attachment B for venting SI pump B.

Comment: OFN BG-045 rev 1, step 15

• Performance Step: 3 Uncap and open SI PUMP B VENT, until a solid stream of water issues from vent.

o EM-V208 - VENTED Standard: Uncap and OPEN the valve by turning the handwheel in the counter-clockwise direction.

Comment: Valve is located 1974 of Aux. Bldg., B SI pump room; inside contaminated area of pump.

After examinee explains the process of venting via EM-V208, CUE: Cap is removed. Hoses are installed, if used.

Handwheel stops turning, stem is extended, water/gas mixture is coming from vent.

After approx. 1 minute:

CUE: Only water is coming from vent.

OFN BG-045, Attachment B, step B.2.1

Appendix C Page 3 of 7 Form ES-C-1 PERFORMANCE INFORMATION

• Performance Step: 4 Close and cap SI PUMP B VENT.

o EM-V208 - CLOSED/CAPPED Standard: Caps and CLOSES the valve by turning the handwheel in the clockwise direction.

Comment: After examinee explains the process of closing and capping EM-V208, CUE: Hose is removed, if used. Cap is installed.

Handwheel stops turning, stem is fully inserted.

OFN BG-045, Attachment B, step B.2.2

• Performance Step: 5 Uncap and open SI PUMP B VENT, until a solid stream of water issues from vent.

o EM-V209 - VENTED Standard: Uncap and OPEN the valve by turning the handwheel in the counter-clockwise direction.

Comment: Valve is located 1974 of Aux. Bldg., B SI pump room inside contaminated area of pump.

After examinee explains the process of venting via EM-V209, CUE: Cap is removed. Hose is installed, if used.

Handwheel stops turning, stem is extended, water is coming from vent.

After approx. 1 minute:

CUE: Only water is coming from vent.

OFN BG-045, Attachment B, step B.2.3

• Performance Step: 6 Close and cap SI PUMP B VENT.

o EM-V209 - CLOSED/CAPPED Standard: Caps and CLOSES the valve by turning the handwheel in the clockwise direction.

Comment: After examinee explains the process of closing and capping EM-V209, CUE: Hose is removed, if used. Cap is installed.

Handwheel stops turning, stem is fully inserted.

OFN BG-045, Attachment B, step B.2.4

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION

• Performance Step:7 Uncap and open SI PUMP B SUCT PP ISO, until a solid stream of water issues from vent.

o EM-V030 - VENTED Standard: Uncap and OPEN the valve by turning the handwheel in the counter-clockwise direction.

Comment: Valve is located 1974 of Aux. Bldg., B SI pump room outside of contaminated area of pump (north side).

After examinee explains the process of venting via EM-V030, CUE: Cap is removed. Hose is installed, if used.

Handwheel stops turning, stem is extended, steam is coming from vent.

After approx. 1 minute:

CUE: Only water is coming from vent.

OFN BG-045, Attachment B, step B.2.5

• Performance Step: 8 Close and cap SI PUMP B SUCT PP ISO.

o EM-V030 - CLOSED/CAPPED Standard: Caps and CLOSES the valve by turning the handwheel in the clockwise direction.

Comment: After examinee explains the process of closing and capping EM-V030, CUE: Hose is removed, if used. Cap is installed.

Handwheel stops turning, stem is fully inserted.

OFN BG-045, Attachment B, step B.2.6

Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION

• Performance Step: 9 Uncap and open SI PUMPS SUCTION CROSSTIE VENT, until a solid stream of water issues from vent.

o EM-V271 - VENTED Standard: Uncap and OPEN the valve by turning the handwheel in the counter-clockwise direction.

Comment: Valve is located 1988 Aux. Bldg., room 1203. Once Examinee determines location of valve, the Examiner may use the photograph of EM-V271.

After examinee explains the process of venting via EM-V271, CUE: Cap is removed. Hose is installed, if used.

Handwheel stops turning, stem is extended, water gas mixture is coming from vent.

After approx. 1 minute:

CUE: Only water is coming from vent.

OFN BG-045, Attachment B, step B.2.7

• Performance Step: 10 Close and cap SI PUMPS SUCTION CROSSTIE VENT.

o EM-V271 - CLOSED/CAPPED Standard: Caps and CLOSES the valve by turning the handwheel in the clockwise direction.

Comment: After examinee explains the process of closing and capping EM-V271, CUE: Hose is removed, if used. Cap is installed.

Handwheel stops turning, stem is fully inserted.

OFN BG-045, Attachment B, step B.2.8 Terminating Cue: The Examinee reports that the pump is vented and reports to the Control Room the completion of section B.2 of Attachment B of OFN BG-045 rev 1, Gas Binding of CCPS or SI Pumps.

Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: P-3, Gas Binding of ECCS Pumps Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: You are the Auxiliary Building Operator. The plant has experienced a Small Break LOCA. The Reactor has tripped and Safety Injection has been actuated.

INITIATING CUE: The crew is responding to the event using EMG E-0 rev 21, Reactor Trip or Safety Injection. Concurrent with this procedure, the Control Room Supervisor (CRS) has determined that the B Safety Injection Pump has become gas bound and is using OFN BG-045, rev 1, Gas Binding of CCPS or SI Pumps, to restore the pump. Using OFN BG-45, the CRS directs you to visually inspect the B SI pump per step 14 and vent the pump using Attachment B per step 15.

Formatted Appendix D Scenario Outline Form ES-D-1 Facility: __Wolf Creek_______ Scenario No.: ___1____ Op-Test No.: _______

Examiners: ____________________________ Operators: __________________________

Initial Conditions: The plant is at 100% power, Middle of Core life. The A ESW pump and the A EDG are tagged out of service.

Turnover: The A ESW pump is OOS for an upper motor bearing replacement, which causes the A EDG to be OOS. The National Weather Service has issued a Severe Thunderstorm Warning for Shawnee and Butler counties. Topeka System Dispatch (TSD) has notified WC of abnormal grid conditions based on weather conditions. Shift orders are to maneuver the plant generator output per TSD when conditions permit. TSD reports that under the current grid conditions that predicted grid voltage is 98.7% if WC were to come offline. OFN AF-025 Unit Limitations has been completed for the current plant conditions, and no further actions are required.

Event Malf. No. Event Event No. Type* Description Power range instrument SE NI-41B fails high. Rods step 1 mSE03A I - ATC, t+1 SRO in. Manual Rod Control must be selected (or the reactor trips).

Pressurizer Pressure Channel 456 fails high (PORV 456 2 mBB21B I - ATC, t+9 fails to SRO cycles) 2508 psig Loss of 345 kV Benton line. TSD will request Wolf 3 mSY03F R -- ATC t+16 Creek to lower load to 950 Mwe.

N - BOP, SRO Grid voltage droops to 89.9% (310kV). Class 1E busses 4 IRF C -- All t+25 pMA02 to NB01/2 voltage will decrease to the point where the 310 kV degraded voltage alarms come in.

After a 94 sec time delay, the busses will shed and mNE04B attempt to repower on the EDGs. Both EDGs are inoperable at this point.

The TDAFP fails to start in Auto, but can be started in 5 mAL01 C - BOP, t+28 SRO manual. (CT Manually start the Turbine Driven Auxiliary Feed Pump)

Appendix D 1 NUREG 1021 Revision 9

Loss All AC Power. The crew will enter EMG C-0, Loss 6 mSY01 M -- All of All AC Power, as neither safeguards bus is energized.

t+28 (CT Loss of All AC Power entry and response)

(CT Depressurize intact Steam Generator(s) at maximum rate)

NB01/2 bus is restored (EDG B supplying NB02 bus) 7 Delete M - All t+35 mNE04B

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D 2 NUREG 1021 Revision 9

Appendix D Scenario Outline Form ES-D-1 Scenario Summary:

The crew assumes the watch at MOL core conditions. A Essential Service Water pumped is tagged out to replace a faulty motor bearing, necessitating the tagout of the A Emergency Diesel Generator.

The turnover will include weather conditions that result in an unstable grid. Westar energy has predetermined actions for unstable grid conditions, and notifying Wolf Creek (WC) of these conditions and predicting the effect of the loss of WCs generation capability are specified in Westars directives.

Power Range channel SE NI-41B fails high. The crew will refer to OFN SB-008, Instrument Malfunction, Attachment R:

• Verify there is no turbine runback Formatted: Bullets and Numbering

• Place Rod control in manual

• Bypass the failed channel

• Return Rod Control to Automatic Pressurizer Pressure channel BB PI-456 fails high. The crew will refer to OFN SB-008, Instrument Malfunction, Attachment K:

• Identify failed channel Formatted: Bullets and Numbering

• Take manual control of master pressure controller

• Select out failed channel

• Return system to auto When the 345 kV line is lost, TSD will request the crew to decrease generator output to Formatted 950 Mwe. The crew will refer to OFN AF-025, Unit Limitations. Actions taken by the crew will include:

• Reduce Turbine load and reactor power per General Operating Procedures Formatted: Bullets and Numbering As the grid continues to degrade, the voltage will decrease to the point that Safeguards busses NB01/2 Degraded Voltage protection circuits are activated and function. The end result of the degraded voltage will be both NB busses deenergized with the balance of plant powered and the reactor not tripped. Shortly thereafter, the reactor will trip from a turbine trip that is caused by the unstable grid.

The Major event is a complete Loss of all AC power. The crew will respond using EMG C-0, Loss of All AC Power. Eventually EDG B will be available to power NB02.

Appendix D 3 NUREG 1021 Revision 9

The major actions of EMG C-0 are:

• Perform Immediate Actions Formatted: Bullets and Numbering

• Restore AC power

• Maintain plant conditions for optimal recovery

• Evaluate energized AC emergency bus

• Select recovery guideline after AC power restoration Critical Tasks for this scenario are:

• Manually start the Turbine Driven Auxiliary Feed Pump as this is the only Formatted: Bullets and Numbering method available to feed the steam generators during the rapid plant cooldown.

• Loss of All AC Power entry and response.

• Depressurize intact Steam Generator(s) at maximum rate to minimize RCS inventory loss.

Probabilistic Risk Analysis for scenario includes:

Core Damage Frequency By Event Tree:

Event Tree Core Damage Frequency (/yr) Percent Contribution Station Blackout 6.46E-06 35.79%

Station blackout event is also very high on the Initiating event contributing to Core Damage Frequency.

Technical Specifications (TS) for this scenario:

Event 1: TS 3.3.1; Reactor Trip System Instrumentation, Table 3.3.1-1, FU 2a, 3a, 3b, 6, 18c, 18d, 18e Cond A: Enter the condition referenced in the table Cond D: Perform SR 3.2.4.2 (QPTR, 12 hrs) and place channel in trip condition (72 hr)

Cond E: One channel inoperable - place channel in trip condition (72 hrs)

Cond T & S: One hour to verify P-8, P-9 and P-10 interlocks are in their required state for plant condition TR 3.3.17, Reactivity Control and Power Distribution Alarms Cond A: Perform SR 3.2.3.1 (once per hr)

Cond D: Perform SR 3.2.4.1 or SR 3.2.4.2 as applicable Event 2: TS 3.3.1; Table 3.3.1-1, FU 6, 8a and 8b Cond A: Enter the condition referenced in the table Cond E: One channel inoperable - place channel in trip condition (72 hrs)

Cond M: One channel inoperable - place channel in trip condition (72 hr)

TS 3.3.2, ESFAS Instrumentation, Table 3.3.2-1, FU 1d, and 8b Cond A: Enter the condition referenced in the table Cond D: One channel inoperable - place channel in trip condition (72 hr)

Appendix D 4 NUREG 1021 Revision 9

Cond L: One hour to verify P-11 interlock in the required state for plant condition TS 3.3.6, Containment Purge Isolation Instrumentation - Refer to only, no Conditions to enter TS 3.3.7, Control Room Ventilation System Actuation Instrumentation - Refer to only, no Conditions to enter Event 4: TS 3.8.1, AC Sources - Operating Cond A: One offsite circuit inoperable, perform SR 3.8.1.1 for Operable offsite circuit (1 hr - STS NB-005)

Cond B: One DG inoperable, perform SR 3.8.1.1 for Operable offsite circuit (1 hr - STS NB-005)

Cond D: Two offsite circuits inoperable Cond E: One offsite and one DG inoperable Cond F: Two DG inoperable Cond I: Three or more required AC sources inoperable (TS 3.0.3 immediately)

TS 3.8.4, DC Sources - Operating Cond A: One DC electrical power subsystem inoperable (and TS 3.0.3)

TS 3.8.9, Distribution Systems - Operating Cond A: Enter applicable cond/req. actions LCO 3.7.8 (immediately)

Cond B: Restore AC electrical power distribution subsystem to operable (8 hr)

Cond F: Two trains inoperable (TS 3.0.3 - immediately)

Appendix D 5 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1 Page 6 of 26 Event

Description:

Channel 1 Nuclear Instrument Fails High Time Position Applicants Actions or Behavior Booth Instructor: setup: IC 30; RBU at 229; Blue placard on A CCP; etc Formatted When directed, initiate Event 1 by activating Key 1. (mSE03A at 120%)

Indications available:

ALR 078A-PR CHANNEL DEV ALR 082A-PR OVER PWR ROD STOP ALR 083C-RX PARTIAL TRIP SB069 PR HI SETPT NC41R, PR HIFLUX NC41U/K Control Bank D rods stepping IN Actions may be taken prior to procedure entry: SE NI-41B CRS/RO/B identified as failure. No load reject/runback in progress. Rods OP taken to manual (SE HS-9)

Recognize Instrument failure and refer to OFN SB-008, rev 25, CRS Instrument Failure.

1. Check if secondary system instrument channel is CRS malfunctioning No Go to step 2

2. Check If Reactor Coolant System Instrument Channel or Controller is Malfunctioning CRS No Go to step 3 Formatted

3. Check if Containment Or RWST Channel is Malfunctioning:

CRS No Go to step 4 Appendix D 6 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1 Page 7 of 26 Event

Description:

Channel 1 Nuclear Instrument Fails High Time Position Applicants Actions or Behavior 4 Check if Nuclear Instrumentation System Channel is Malfunctioning:

CRS SE NI-41B failure identified.

Yes, go to Attachment R Formatted Formatted: Bullets and Numbering R1. Identify Failed Instrument Channel Formatted

• One power range flux or delta flux meter indicates Formatted: Bullets and Numbering abnormally higher or lower than other power range CRS/RO meters SE NI-41B failure Yes, Channel one indicates higher (120%) Formatted R2. Check Load Rejection - NOT IN PROGRESS

• Generator Load MW - STABLE Formatted: Bullets and Numbering

• Generator Load SET MW - STABLE CRS/RO No load rejection in progress Formatted RO R3. Switch Rod Control Bank Selector Switch To Manual Formatted: Bullets and Numbering RO/BOP R4. Bypass Failed Power Range Flux Channel:

a. At the Detector Current Comparator Drawer (N50), perform the following;

1) Turn the Upper Section switch to the failed power range flux channel.

2) Turn the Lower Section switch to the failed power range flux channel.

3) Turn the Power Mismatch Bypass switch to the failed power range flux channel.

RO/BOP 4) Turn the Rod Stop Bypass switch to the failed power range flux channel.

b. At the Comparator and Rate Drawer (N37/46), perform the following:

1) Turn the Comparator Channel Defeat switch to the failed power range channel.

Appendix D 7 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1 Page 8 of 26 Event

Description:

Channel 1 Nuclear Instrument Fails High Time Position Applicants Actions or Behavior NOTES

• It may take several minutes for power and Formatted: Bullets and Numbering temperature rate circuitry outputs to return to normal before switching back automatic rod control.

• Control Rods should be restored to their parked Formatted: Bullets and Numbering position when plant conditions allow at the direction of the CRS.

R5. Check Rod Control Bank Selector Switch In Auto RNO Formatted CRS/RO

() WHEN Tavg is within 1°F of Tref, THEN place rod control bank selector switch in auto.

R6. Monitor Rod Control System Response To Ensure Proper RO Control R7. Check Failed Power Range Flux Channel Not Used For Recording On NR-45 And OPT/OTT Recorders BOP Loop One is selected, select any other channel R8. Monitor The Following Technical Specification LCOs And Comply With Action Statements, As Appropriate:

TS 3.3.1; Reactor Trip System Instrumentation, Table 3.3.1-1, FU 2a, 3a, 3b, 6, 18c, 18d, 18e Cond A: Enter the condition referenced in the table Cond D: Perform SR 3.2.4.2 (QPTR, 12 hrs) and place channel CRS in trip condition (72 hr)

Cond E: One channel inoperable - place channel in trip condition (72 hrs)

Cond T & S: One hour to verify P-8, P-9 and P-10 interlocks are in their required state for plant condition Appendix D 8 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1 Page 9 of 26 Event

Description:

Channel 1 Nuclear Instrument Fails High Time Position Applicants Actions or Behavior TR 3.3.17, Reactivity Control and Power Distribution Alarms Cond A: Perform SR 3.2.3.1 (once per hr)

Cond D: Perform SR 3.2.4.1 or SR 3.2.4.2 as applicable Lead Examiner may direct initiation of the next event at his/her discretion Appendix D 9 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 2 Page 10 of 26 Event

Description:

Pressurizer Pressure Channel 456 Fails High Time Position Applicants Actions or Behavior Booth Instructor:

When directed, initiate Event 2 by activating Key 2 (mBB21B fails High)

Indications available:

ALR 00-34B PZR PRESS HI ALR 00-34C PZR PORV BLOCK ALR 00-34E PRT PRESS HI ALR 00-35B PORV OPEN ALR 00-83C RX PARTIAL TRIP SB069 PZR HP PB456A Actions may be taken prior to procedure entry: BB PI-456 failure CRS/RO high. Manual on PZR Press Master controller (BB PK-455A).

Actions necessary to minimize pressure transient.

Recognize Instrument failure and refer to OFN SB-008, rev 25, CRS Instrument Failure.

1. Check if Sec Sys Inst Channel is malfunctioning. NO

2. Check if RCS Inst Channel is malfunctioning. YES, go to ATT CRS K.

K1. Identify Failed Instrument Channel CRS/RO BB PI-456 Formatted K2. Check Failed Pressurizer Selected on PZR Pressure Control RO Selector Switch YES- BB PS-455F Formatted K3. Place Pressurizer Pressure Master Controller in Manual and RO Control Pressure. Select manual control on BB PK-455A Formatted Appendix D 10 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 2 Page 11 of 26 Event

Description:

Pressurizer Pressure Channel 456 Fails High Time Position Applicants Actions or Behavior K4. Select Alternate Pressurizer Pressure Channel for Pressure RO Control. Selects out BB PI-456 on BB PS-455F Formatted K5. Take following actions, as appropriate to stop pressure control transient.

A. Check Pressurizer Spray valves RESPONDING RO CORRECTLY-Yes Formatted B. PZR Control Heaters Operable - Yes Formatted C. Ensure PZR PORV-Closed - Yes Formatted Formatted Formatted: Bullets and Numbering K6. Return Pressurizer Pressure control to Automatic.

• Spray Valves Formatted: Bullets and Numbering

• Control Heaters

• Back up Heaters RO

• Open PORV Block valves

• Pressurizer Pressure Control Select automatic control on BB PK-455A Formatted: Bullets and Numbering K7. Monitor Pressure Response to ensure proper control. -Yes RO K8. Check failed Channel NOT used for Pressurizer Pressure BOP Recorder. No, BB PS 455 is selected Formatted Formatted K9. Check failed Pressure channel not used for OPT/ OTT BOP Recorder. Select alternate channel K10. Monitor Technical Specifications TS 3.3.1; Table 3.3.1-1, FU 6, 8a and 8b CRS Cond A: Enter the condition referenced in the table Cond E: One channel inoperable - place channel in trip condition (72 hrs)

Appendix D 11 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 2 Page 12 of 26 Event

Description:

Pressurizer Pressure Channel 456 Fails High Time Position Applicants Actions or Behavior Cond M: One channel inoperable - place channel in trip condition (72 hr)

TS 3.3.2, ESFAS Instrumentation, Table 3.3.2-1, FU 1d, and 8b (Refer also to 3.a.3, 5d, 6e, 7b)

Cond A: Enter the condition referenced in the table Cond D: One channel inoperable - place channel in trip condition (72 hr)

Cond L: One hour to verify P-11 interlock in the required state for plant condition TS 3.3.6, Containment Purge Isolation Instrumentation - Refer to only, no Conditions to enter TS 3.3.7, Control Room Ventilation System Actuation Instrumentation - Refer to only, no Conditions to enter At the discretion of the Lead Examiner, proceed to the next event.

Appendix D 12 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 3 Page 13 of 26 Event

Description:

Loss of 345 KV Line Time Position Applicants Actions or Behavior Booth Instructor:

When directed, initiate Event 3 by activating Key 3 (mSY03F ).

Topeka System Dispatch (TSD) calls after 2 minutes if the crew does not notice the loss of the Benton Line. We dont know why - we are preparing to dispatch a team.

Indications available:

On Panel RL014, BKR 345-70 and BKR 345-80 lights change from Red LIT to Green LIT.

Refer to OFN AF-025, rev 027,Unit Limitations.

CRS 1.Determine applicable step:

CRS

f. Go to Step 7. Formatted 7.Check WESTAR Transmission Services has Reported an Actual or Predicted Switchyard Voltage Degradation:

CRS No, go to step 9 Formatted

9. Check for conditions Requiring Unit Load Reduction:

CSR

a. Determine maximum unit load using Attachment A, Unit Load Limitations.

CRS Attachment A ( page 3 of 4): 345 KV Offsite Supply Loss of one 345 KV offsite line - YES Formatted Reduce Unit Load to less than 950 Mwe NET (995 GROSS) as directed by Topeka Dispatch Booth Cue: Formatted When called as Call Superintendent, direct the CRS to reduce power to 950 MWE net (995 MWE gross), per GEN 00-004, Power Generation. Formatted 9.b. Reduce unit load, as necessary, to satisfy load limits using appropriate procedure:

CRS Refer to GEN 00-004 rev 60, Power Operations.

Appendix D 13 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 3 Page 14 of 26 Event

Description:

Loss of 345 KV Line Time Position Applicants Actions or Behavior CRS/ Enter GEN 00-004, rev 60, Power Operations CREW 6.2.1 If control rods are not parked at 228 steps, realign to Formatted CRS 228 if desired. Formatted: Bullets and Numbering 6.2.2 When turbine load is being decreased use the Formatted BOP following techniques. (6.2.2.2 since MTC is negative). Formatted: Bullets and Numbering 6.2.2.2 If MTC is negative or zero, then perform the following:

a. If automatic Turbine unloading is desired, then control turbine load using automatic turbine-generator unloading selected to 1/2% per minute OR as directed by SM/CRS.

BOP

b. If automatic Turbine unloading is NOT desired, then perform Turbine load decrease using load limit potentiometer or the standby potentiometer in a slow controlled manner.

c. () Adjust control rods as necessary to maintain Tavg within 1.5°F of Tref.

6.2.3 () During power reduction, use boration, dilution, or Formatted: Bullets and Numbering control rods, as necessary, to maintain the axial flux Formatted CRS difference within the target band and control rods above the rod insertion limit.

Formatted 6.2.4 Ensure AE HV-38, HP FW HEATERS BYPASS Formatted CRS/RO VALVE, is closed using SYS AE-125, HP FW HEATER BYPASS THROTTLING OPERATIONS.

Formatted 6.2.5 Ensure one set of PZR backup heaters is energized. Formatted: Bullets and Numbering CRS/RO BB HIS-51A Formatted BB HIS-52A Formatted Formatted 6.2.6 If desired and RCS will be taken solid, then place PZR Formatted CRS/RO LEV MASTER CTRL in manual and maintain level Formatted: Bullets and Numbering Appendix D 14 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 3 Page 15 of 26 Event

Description:

Loss of 345 KV Line Time Position Applicants Actions or Behavior between program and 57%. NA - not desired Formatted Formatted 6.2.7 If automatic Turbine unloading is desired, then place Formatted: Bullets and Numbering EHC control on load set as follows:

1. () If desired to position Control Valves in their controlling range, then slowly decrease load limit pot until a 1-2 Mwe load decrease is noted.

2. Slowly decrease load set MW until the following CRS/BOP conditions are met:

o At set load light - lit AND o Load limit limiting light - NOT lit

3. Raise load limit pot slightly

4. Select 1/2 %/min loading rate.

5. Select decrease loading rate - ON Formatted Formatted 6.2.8 () Decrease Turbine load as desired while continuing Formatted: Bullets and Numbering CRS/BOP with this procedure. Formatted 6.2.9 Ensure Chemistry is promptly notified of each power Formatted: Bullets and Numbering change that is greater than or equal to 15% RTP within CRS a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period so that RCS DEI can be verified to satisfy SR 3.4.16.2.

6.2.10 When SM or CRS desires to stop one heater drain Formatted: Bullets and Numbering pump, THEN stop one heater drain pump using SYS AF-121, HEATER DRAIN PUMP OPERATION.

At the discretion of the Lead Examiner, proceed to the next event Appendix D 15 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # NA Page 16 of 26 Event

Description:

Automatic Signal Verification Time Position Applicants Actions or Behavior Booth Instructor:

When directed to initiate Event, activate KEY 4 (IRF pMA02 to 310 KV, mNE04B, mAL01, and mSY01 with a 2minute time delay)

Indications available:

ALR 00-024E, NG01 BUS UV ALR 00-025E, NG02 BUS UV ALR 00-026E, NG03 BUS UV When the turbine trips due to degraded grid voltage (PLU):

ALR 00-119B, TURB PWR LOAD IMBAL ALR 00-131B, GEN FIELD OV ALR 00-131C, VOLT REG TRIP TO MANUAL ALR 00-132D, EXCITER FIELD FORCING TS - if time allows TS 3.8.1, AC Sources - Operating Cond A: One offsite circuit inoperable, perform SR 3.8.1.1 for Operable offsite circuit (1 hr - STS NB-005)

Cond B: One DG inoperable, perform SR 3.8.1.1 for Operable offsite circuit (1 hr - STS NB-005)

Cond D: Two offsite circuits inoperable Cond E: One offsite and one DG inoperable Cond F: Two DG inoperable Cond I: Three or more required AC sources inoperable (TS CRS 3.0.3 immediately)

TS 3.8.4, DC Sources - Operating Cond A: One DC electrical power subsystem inoperable (and TS 3.0.3)

TS 3.8.9, Distribution Systems - Operating Cond A: Enter applicable cond/req. actions LCO 3.7.8 (immediately)

Cond B: Restore AC electrical power distribution subsystem to operable (8 hr)

Appendix D NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # NA Page 17 of 26 Event

Description:

Automatic Signal Verification Time Position Applicants Actions or Behavior Cond F: Two trains inoperable (TS 3.0.3 - immediately)

CRS EMG E-0, rev 21, Reactor Trip or Safety Injection CAUTION Accident conditions can cause higher than normal radiation levels. Health Physics monitoring may be required while performing local operator actions.

NOTES o Steps 1 thru 4 are immediate action steps Formatted: Bullets and Numbering o Foldout page shall be monitored throughout this procedure.

1. Verify Reactor Trip:

a. Check all rod bottom lights-LIT

b. Ensure reactor trip breakers an bypass breakers - OPEN

• SB ZL-1

• SB ZL-2 RO

• SB ZL-3

• SB ZL-4

c. Check intermediate range neutron flux - DECREASING

• SE NI-35B GAMMA METRICS

• SE NI-36B GAMMA METRICS

2. Verify Turbine Trip:

a. Check the following:

Main Stop Valves- ALL CLOSED Formatted: Bullets and Numbering BOP OR Turbine Auto Stop bistable lights - AT LEAST Formatted: Bullets and Numbering TWO LIT Appendix D NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # NA Page 18 of 26 Event

Description:

Automatic Signal Verification Time Position Applicants Actions or Behavior

3. Check AC Emergency Busses- AT LEAST ONE Formatted ENERGIZED RO NB01 voltage - NORMAL Formatted: Bullets and Numbering NB02 voltage - NORMAL Formatted NOTE: the degraded voltage has a 93 sec time delay BEFORE busses NB01 and NB02 are shed. At that time, the Crew will enter EMG C-0, Loss of All AC Power.

Enters EMG C-0, rev 18, Loss of All AC Power steps: Formatted CRS/CRE Formatted W

CT Loss of All AC Power entry and response. Formatted CAUTION Accident conditions can cause higher than normal radiation levels. Health Physics monitoring may be required while performing local operator actions.

Booth Instruction / Cue:

Use radio: Begin reporting in as building watches. Formatted NOTES o Steps 1 and 2 are Immediate Action steps Formatted: Bullets and Numbering o Foldout page shall be monitored throughout this procedure.

o CSF status trees shall be monitored for information only. Function Restoration (FR) Procedures shall not be implemented during this procedure.

1. Verify reactor trip Formatted RO a. Ensure reactor trip and bypass breakers - OPEN Formatted

b. Check intermediate range neutron flux - DECREASING Formatted Formatted

2. Verify turbine trip Formatted BOP

a. Check Main Stop Valves - ALL CLOSED Formatted

3. Check Main Generator Breakers and Exciter Breaker -

BOP OPEN Formatted Appendix D NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # NA Page 19 of 26 Event

Description:

Automatic Signal Verification Time Position Applicants Actions or Behavior

4. Check if RCS is isolated

a. Check PORVs - CLOSED

b. Check RCS Letdown to Regen HX valves - CLOSED

c. Check Reactor Coolant to Excess Letdown Heat HX -

CLOSED RO

d. Check reactor vessel head vents - AT LEAST ONE VALVE CLOSED IN EACH TRAIN

e. Dispatch operator to locally close RCS and PZR sample line Formatted isolation valves (SJ-V054, SJ-V057 and SJ-V103) Formatted Formatted Formatted Booth Instruction / Cue: Formatted Acknowledge request to close valves. These valves are not modeled. Wait a few Formatted minutes then report back that valves (SJ-V054, SJ-V057 and SJ-V103) are closed.

Formatted Formatted

5. Check total AFW flow > 270,000 lbm/hr Formatted NO, perform RNO to start TDAFWP (CT - The TDAFP fails to start in Auto, but can be started Formatted in manual.)

a. Ensure TDAFW pump running. If TDAFW pump not running Formatted perform the following:

1. Open steam supply valves BOP o AB HIS-5A Formatted o AB HIS-6A Formatted: Bullets and Numbering

2. Open trip throttle valve o FC HIS-312A Formatted: Bullets and Numbering

b. Ensure TDAFW control valves - OPEN or THROTTLED o AL KH-8A for SG A Formatted: Bullets and Numbering o AL HK-10A for SG B o AL HK-12A for SG C o AL HK-6A for SG D Formatted BOP 6. Check emergency oil pumps running Formatted Formatted Appendix D NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # NA Page 20 of 26 Event

Description:

Automatic Signal Verification Time Position Applicants Actions or Behavior

7. Check AC Emergency Bus Faults - AT LEAST ONE Formatted CLEARED Formatted CRS 00-018A - NOT LIT 00-021A - NOT LIT Formatted 8.Manually start both diesel generators from control room. Formatted RNO: Start both diesel generators locally using OFN KJ-032, Formatted RO Local Emergency Diesel Startup, while continuing with this procedure.

NOTE: EDG A not available - Turnover item. EDG B unavailable due to fuel failure Formatted Booth Instruction / Cue: Formatted When dispatched to determine cause of EDG B failure, report:

EDG B fuel line failure of some sort.

If directed to locally secure EDG B perform the following and report back to Control Room: Insert SIM GROUP file SHTDNDGB. (This leaves EGB B in LOC/MAN.) Formatted Formatted

9. Check AC emergency busses both energized Formatted o NB01 - NORMAL Formatted: Bullets and Numbering o NB02 - NORMAL Neither can be energized. RNO performed.

RNO

a. Manually energize AC emergency bus. Formatted: Bullets and Numbering

b. If either emergency bus can not be energized, then perform the following: Formatted RO 1. Locally shutdown associated diesel Formatted generator as follows: Formatted o Place Master Transfer switch to LOC/MAN Formatted KJ HS-9 for A Formatted KJ HS-109 for B Formatted o Stop the diesel Formatted KJ HS-8B for A Formatted KJ HS-108B for B Formatted Appendix D NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # NA Page 21 of 26 Event

Description:

Automatic Signal Verification Time Position Applicants Actions or Behavior

2. Try to energize affected AC emergency bus(es) from any available power supply while continuing with this procedure Formatted o Refer to OFN NB-030 Formatted Formatted

10. Check if AC power has been restored CRS RNO: Observe CAUTION prior to step 14 and continue with step 14. Formatted Formatted CAUTION An essential service water pump shall be allowed to automatically load on its energized AC emergency bus to provide diesel generator cooling.

Formatted Formatted

14. Place ECCS Pump switches in P.T.L. Formatted

a. CCPs Formatted: Bullets and Numbering

b. SI pumps RO/BOP c. RHR pumps

d. CTMT spray pumps

e. CCW pumps

15. Place the following equipment switches in Pull- To- Formatted Lock.

a. CTMT fan coolers Formatted: Bullets and Numbering RO/BOP b. Motor Driven AFW pumps

c. Control room AC

d. Class 1E AC Formatted

16. Dispatch personnel to locally isolate RCP seals Formatted CRS Formatted Booth Instruction / Cues: When contacted as building watch(es) to isolate RCP seals, Formatted report accordingly. Run SIMGROUP file ISOSEALS file. Formatted When valves are closed, report back to Control Room. Formatted Formatted Appendix D NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # NA Page 22 of 26 Event

Description:

Automatic Signal Verification Time Position Applicants Actions or Behavior

17. Check if TSC Diesel should be started. Formatted CRS Booth Instruction / Cues: Acknowledge direction as Site Watch to start TSC diesel.

Formatted

18. Establish Emergency Ventilation per Attachments A and Formatted CRS B.

Booth Instruction / Cues:

Building Watch cue: Acknowledge direction to perform Attachments. (A & B)

Security cues: Acknowledge directions to deenergize redundant security computer and take appropriate compensatory measures for the open doors

19. Check accumulator tank outlet isolation valves - OPEN Formatted RO Formatted

20. Check CST isolated from hotwell Formatted BOP Formatted Formatted: Bullets and Numbering

21. Isolate main steamlines Formatted

a. Close MSIVs Formatted

b. Ensure MSIVs - CLOSED BOP Formatted

c. Ensure MSIV bypass valves - CLOSED

d. Ensure main steamline drain valves - CLOSED Formatted Formatted Formatted

22. Verify feedwater isolation Formatted

a. MFPs - TRIPPED Formatted

b. Main feed reg valves - CLOSED Formatted BOP c. Bypass feed reg valves - CLOSED Formatted

d. MFIVs - CLOSED Formatted

e. Chemical injection valves - CLOSED Formatted Formatted Formatted

23. Verify blowdown isolated on all SGs BOP Formatted Formatted Formatted Formatted Appendix D NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # NA Page 23 of 26 Event

Description:

Automatic Signal Verification Time Position Applicants Actions or Behavior CAUTION Formatted o A faulted or ruptured S/G that is isolated should remain isolated. Formatted: Bullets and Numbering o Steam supply to TDAFW pump must be maintained from at least one S/G.

24. Check if SGs are not faulted - Yes, No SG is faulted.

CRS Stay in the Action/Expected Response column.

25. Check if SGs tubes are intact -YES Formatted CRS Formatted Booth Instruction / Cue: Formatted If contacted as HP, report that the steam lines will be surveyed. Formatted Formatted Formatted

26. Check intact SG levels Formatted BOP Formatted Formatted Formatted

27. Check DC Bus Loads

a. Shed loads per Attachment C Formatted CRS Formatted

b. Dispatch personnel to monitor DC pwr supply Formatted Formatted Booth Instruction / Cue: If contacted as building watch, acknowledge direction to Formatted perform Attachment C, Shed DC Loads Formatted Formatted Formatted

28. Check CST to AFW SUCT PRESS > 62.9 PSIG BOP Formatted Formatted CAUTIONS Formatted o S/G press shall be maintained > 160# Formatted o S/G NR level shall be maintained > 6% in at least one S/G Formatted: Bullets and Numbering o S/G B or C should not be depressurized to ensure steam to TDAFW pump Appendix D NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # NA Page 24 of 26 Event

Description:

Automatic Signal Verification Time Position Applicants Actions or Behavior NOTES Formatted o S/Gs should be depressurized at maximum rate to minimize RCS inventory loss. Formatted o PZR level may be lost and reactor upper head voiding may occur due to Formatted depressurization of SGs. Depressurization should not be stopped to prevent these Formatted: Bullets and Numbering occurrences. Formatted Formatted Formatted

29. Check if intact SGs should be depressurized to 260 psig Formatted

a. Check intact SG NR levels > 6% in at least one SG Formatted: Bullets and Numbering CRS/BOP b. Dump steam at maximum rate using SG ARVs (CT Depressurize intact Steam Generator(s) at maximum rate) Formatted Formatted CAUTIONS Formatted o SR and IR channels are monitored for possible reactor restart. RCS cooldown Formatted: Bullets and Numbering shall be stopped to maintain subcritical conditions. This is especially important at Formatted end-of-life.

o Gamma Metrics shall be monitored if normal NIs becomes erratic.

Formatted Formatted NOTE The following step is based on having a negative moderator temperature coefficient.

RO 30. Check reactor subcritical Formatted Formatted

31. Check if S/G Depressurization should be stopped. Formatted

a. Check intact SG narrow range levels - > 6% [29%] IN Formatted: Bullets and Numbering AT LEAST ONE SG CRS b. Check RCS cold leg temperature - > 270°F

c. Check depressurized SG pressures - < 260 psig

d. Control depressurized SG ARVs to maintain SG pressures at 260 psig Appendix D NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # NA Page 25 of 26 Event

Description:

Automatic Signal Verification Time Position Applicants Actions or Behavior EMG C-0 Foldout Page Criteria

1. SI RESET CRITERIA - If SI signal exits or SI signal actuates, then reset SI signal to permit manual loading of equipment on AC emergency busses.

2. POWER RESTORATION CRITERIA - If power is restored to an AC emergency bus during the performance of steps 14 through 39, then go to step 40.

3. AFW SUPPLY SWITCHOVER CRITERIA - If CST suction pressure decreases to less than 2.6 psig, then switch to alternate AFW supply.

Booth Instruction: When directed: Call as Call Supt/WWM: EDG B repairs are complete. It is available to power NB02.

Do the following to allow Restoration of EDG B instructions:

If EDG B is NOT in LOC/MAN (i.e. no local actions previously taken), then Delete malfunction mNE04B, Depress Engine Shutdown Reset KJ HS112 (Soft Panel NE106).

The EDG should start and load NB02.

If EDG B is in LOC/MAN at NE106 (i.e., local operator actions occurred), then delete the malfunction mNE04B, Depress Engine Shutdown Reset KJ HS112 (Soft Panel NE106), followed by depressing START pushbutton KJHS101C (Soft Panel NE106).

These actions start EDG B. To energizeNB02: at Soft Panel NE106, take KJHS109 to AUTO NOTE:

Step 9 RNO is a continuous action step (Try to energize affected AC emergency bus(ses) from any available power supply while continuing with this procedure.)

When EDG becomes available to restore power to the bus, the crew should use Foldout page #2 - If power is restored to an AC emergency bus during the performance of steps 14 through 39, then go to step 40.

Power to NB02 is restored, energized by EDG B -- Transitions CRS to Step 40

40. Stabilize SG pressures BOP a. Set SG ARV controllers to automatically maintain existing SG pressures Appendix D NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # NA Page 26 of 26 Event

Description:

Automatic Signal Verification Time Position Applicants Actions or Behavior

b. Control total steam flow as necessary to maintain SG pressures stable NOTE SI shall be reset to permit manual loading of equipment on AC emergency bus RO 41. Check SI - RESET

42. Check the following equipment loaded on energized AC emergency busses:

a. ESW pump Formatted: Bullets and Numbering

b. 480v 1E busses CREW c. Battery charges

d. Instrumentation and control power

e. Emergency lighting

f. Communications

g. Fuel Pool cooling pump The scenario will be terminated at the discretion of the Lead Examiner.

Appendix D NUREG 1021 Revision 9

Appendix D Scenario Outline Form ES-D-1 Facility: __Wolf Creek________________ Scenario No.: ___2____ Op-Test No.: _____

Examiners: ____________________________ Operators: _____________________

Initial Conditions: The plant is restarting after a forced outage that lasted 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />. The Main Turbine is at 1800 RPM ready to be synchronized to the grid. The plant is at BOL conditions.

RCS boron concentration is @ 2033 ppm. Rod Control is in Manual with bank D at 180 steps.

GEN 00-003, Hot Standby to Minimum Load, is complete to step 6.41. SYS AC-120, Main Turbine Startup, is complete up to step 6.4, Synchronizing the Main Generator.

Turnover: Shift orders are to continue the plant startup. Complete SYS AC-120 to synchronize the Main Generator. Fuel conditioning limits are not in effect. The B Stator Cooling water pump is Out of Service for a rework condition following the outage. It is currently in PMT and is expected back in 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

Event Event Malf. No. Event Description No. Type*

1 N - All Synchronize the Main Generator to the grid and increase generator load to prevent reverse power.

t+1 2 mBG01A R -- ATC Volume Control Tank Level control channel BG LI-112 fails low. The result is a 1/2 swapover from the VCT to the t + 15 I -- SRO RWST.

3 mAE15A I - BOP, Steam Generator Level Control channel AE LI-551 fails 4 SRO low.

t + 22 4 mAC06H C -- All The turbine trips on HI-HI bearing vibration.

t + 25 5 mAE14A C -- All A feedwater leak (8E6 lbm/hr) in Containment develops on the A Steam Generator feedline. (CT Isolate faulted t + 32 Steam Generator) 6 mSF17A M -- All Failure of the RX to trip in Auto and Manual (CT Direct local Reactor Trip) t + 32 mSF17B 7 mAL04A C - BOP, Post trip malfunction SRO t + 32 Failure of the A MDAFP to auto start (CT Manually start A MDAFP)

Appendix D 1 NUREG 1021 Revision 9

Appendix D Scenario Outline Form ES-D-1 8 mSA27A C - BOP, Post trip malfunction B08, 09, SRO t + 32 10 & 07 Failure of the MSIVs to auto close (CT Manually close the MSIVs)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D 2 NUREG 1021 Revision 9

Appendix D Scenario Outline Form ES-D-1 Scenario Summary:

The crew assumes the watch with the Main Turbine at 1800 RPM and ready to be synchronized to the grid. This is a normal evolution with no malfunctions. This event is complete when the generator is synced and some load is assumed by the generator to prevent reverse power. This is not a reactivity event at Wolf Creek because reactor power is increased prior to generator synchronization using the Steam Dump System.

This strategy allows a bumpless transfer.

At the discretion on the Lead Evaluator the malfunction for VCT level will be activated.

The result of the failure is that the VCT outlet valve that is controlled by the BG LI-112 channel will close and the RWST valve to the VCT will open. This event will require the SRO to transition to OFN SB-008, Instrument Malfunctions, and select Attachment U for guidance. Attachment U will direct the crew to isolate letdown flow, reduce charging to minimum and take local actions to close and deenergize the RWST to VCT valve.

Steam Generator Level channel AE LI-551 fails low. The crew will refer to OFN SB-008, Instrument Malfunctions, Attachment F. At low power the SGs are fed using the Main Feed Regulating Bypass valves. When using the bypass valves the control system uses actual level and nuclear power (programmed level) to develop a signal to the positioner. When level channel AE LI-551 fails low, the error signal will be large in the open valve direction. The operator will have to:

• Take manual control of the Feed Reg Bypass valve

• Match Steam flow and Feed flow

• Select out the failed channel on RL006

• Return the valve to automatic control When the Turbine Hi-Hi Vibration malfunction is activated, the Main Turbine will trip.

Since Reactor Power is less than 49% (P-9), the reactor will not trip. The crew will respond using OFN MA-001, Load Rejection or Turbine Trip.

At the discretion of the Lead Evaluator, the malfunction for a Steam Generator A feedwater leak inside Containment will be activated. This malfunction will result in:

• A Steamline Pressure Safety Injection (SI), Reactor Trip and High Containment Pressure SI actuation. The crew will utilize EMG E-0, Reactor Trip or Safety Injection.

• Major event: The reactor will fail to trip in Auto and Manual (Major event). The crew will transition to EMG FR-S1, Response to Nuclear Power Generation/ATWT, where local actions to trip the reactor will be successful. The crew will transition back to EMG E-0, Reactor trip or Safety Injection.

• The A MDAFP will fail to start in Auto. It will start in manual.

• The MSIVs will fail to close in Auto. They can be manually closed.

Appendix D 3 NUREG 1021 Revision 9

Appendix D Scenario Outline Form ES-D-1 Critical Tasks (CT) for this scenario are:

• Direct local Reactor Trip

• Isolate faulted Steam Generator

• Manually start A MDAFP

• Manually close the MSIVs Probabilistic Risk Analysis (PRA) for scenario includes:

Core Damage Frequency By Event Tree (Reference PSA 08-0002)

Core Damage Percent Event Tree Frequency (/yr) Contribution Station Blackout 6.46E-06 35.79%

Small LOCA 5.35E-06 29.65%

Interfacing Systems LOCA 1.93E-06 10.68%

Very Small LOCA 1.27E-06 7.05%

Steam Generator Tube Rupture 8.77E-07 4.86%

Loss of Reactor Coolant Pump Seal Cooling Following a Transient Initiator 5.91E-07 3.28%

Transients With Power Conversion Systems Available 3.30E-07 1.83%

Reactor Vessel Failure 3.00E-07 1.66%

Steamline Break 1.88E-07 1.40%

Transients Without Power Conversion Systems Available 1.71E-07 0.95%

Medium LOCA 1.46E-07 0.81%

Loss of All Service Water 8.30E-08 0.46%

Anticipated Transient Without Scram 6.67E-08 0.37%

Technical Specifications (TS) and Technical Requirements Manual (TR):

Event 2: TS 3.5.2, ECCS - Operating Cond A: Restore to operable (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to restore)

Event 3: TS 3.3.1, Reactor Trip System Instrumentation, Table 3.3.1-1, FU 14 Cond E: One channel inoperable - place channel in trip (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />)

TS 3.3.2, ESFAS Instrumentation, Table 3.3.2-1, FU 5c, 6d Cond A: Channel inoperable - enter Condition per Table (immediately)

Cond D: One channel inoperable - place channel in trip (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />)

Cond I: One channel inoperable - place channel in trip (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />)

Appendix D 4 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 1 Page 5 of 58 Event

Description:

Reduce PowerParallel the Main Turbine Generator To the Grid Time Position Applicants Actions or Behavior Booth Instructor: Set up simulator in IC 8. RBU at 180 for CB D, others at 229.

Blue placard on A CCP. CWP disabled. Run files etc.

No action required for event 1 Indications available:

None Applicable Per GEN 00-003, direct the RO/BOP to synchronize the Main CRS Turbine to the grid using SYS AC-120, rev 66, section 6.4. Step 6.4.1 is complete.

6.4.2 Establish Main Generator field as follows:

CRS Notify System Operations that the Generator is ready to be synchronized.

Ensure POWER SYS STABILIZER MODE SEL switch is in normal unless SystemOperationsSystem Operations directs otherwise.

BOP o o MB HS NORMAL Ensure Sync Check Relay Bypass switch in off position.

a.Ensurea. Ensure Sync Check Relay Bypass switch handle BOP removed.

o o MA HS HANDLE REMOVED BOP NOTE:

When Exciter Field Breaker is racked in and open, the manual (DC) regulator receives a signal to drive it to the low limit.Thelimit. The regulator position cannot be changed when Exciter Breaker is open.

Appendix D 5 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 1 Page 6 of 58 Event

Description:

Reduce PowerParallel the Main Turbine Generator To the Grid Time Position Applicants Actions or Behavior Place REG MODE TRANSFER switch in manual.

BOP o MB HS MANUAL Check the green light lit on the DC MAN VOLT REG.

BOP o o MB ZL GREEN LIGHT LIT Verify Turbine Speed - AT 1800 RPM BOP Close EXCITER FIELD BKR.

BOP o o MB HS CLOSED At panel MA104B, ensure Meter And Relay personnel have enabled distance relay 321G. (3.1.4)

CRS o Relay 321G - ENABLED o Relay 321G - DROP FLAG RESET o Relay 332G - DROP FLAG RESET BOOTH OPERATOR Report Cue:

o Relay 321G - ENABLED o Relay 321G - DROP FLAG RESET o Relay 332G - DROP FLAG RESET Place MAIN GEN VOLTMETER 0 SEL switch in any position except off.

BOP o MA HS NOT IN OFF Appendix D 6 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 1 Page 7 of 58 Event

Description:

Reduce PowerParallel the Main Turbine Generator To the Grid Time Position Applicants Actions or Behavior Adjust MB HS-5, DC MAN VOLT REG BKR, as necessary to establish Main Generator voltage at 24.5 KV on all three BOP phases.

o MA EI AT 24.5 KV Adjust MB HS-6, AC AUTO VOLT REG BKR as necessary to zero Voltage Regulator Manual/Auto Signal Match.

BOP o MB EI 0 VOLTAGE MISMATCH Transfer REG MODE TRANSFER switch to auto.

o MB HS AUTO BOP

• MB ZL-3, REG MODE MAN/AUTO Red Light o - LIT BOP NOTE:

13% to 16% reactor power level is desired. This ensures an adequate number of Steam Dumps are open to support synchronizing Main Generator without all Steam Dumps going closed and requires minimal rod movement.

6.4.3 Synchronize Main Generator to grid as follows:

Select first switchyard breaker to be synchronized using MA HS-2, BKR SEL switch.

BOP

• Breaker 1 - SELECTED OR

• Breaker 2 - SELECTED Appendix D 7 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 1 Page 8 of 58 Event

Description:

Reduce PowerParallel the Main Turbine Generator To the Grid Time Position Applicants Actions or Behavior BOP NOTE:

Matching Generator transformer voltage with switchyard voltage must be as close as possible to avoid system upset.

Adjust MB HS-6, AC AUTO VOLT REG BKR, as necessary to establish GeneratorTransformerGenerator Transformer Voltage between 1 KV and 2 KV higher than switchyard voltage.

BOP o MA EI-8 For Transformer Voltage o MA EI-9 For Switchyard Voltage BOP NOTE:

When adjusting Turbine speed at or near 1800 rpm, response to small changes may require between 15 seconds and 30 seconds to stabilize.

Adjust Main Generator speed for synchronizing as follows:

a. Adjust load set using INCREASE LOAD pushbutton or DECREASE LOAD pushbutton as necessary to rotate BOP the Main Generator Synchroscope inthein the fast direction.

o MA SI-6 BOP Ensure rotation of the synchroscope is between 30 seconds Appendix D 8 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 1 Page 9 of 58 Event

Description:

Reduce PowerParallel the Main Turbine Generator To the Grid Time Position Applicants Actions or Behavior and 90 seconds by adjusting load set as necessary.

Check selected breaker Sync Check Permissive white light is lit only when the synchroscope pointer is in the up direction.

• MA ZL LIT OR

• MA ZL LIT Ensure Generator transformer voltage is between 1 KV and 2 BOP KV higher than switchyard voltage.

o MA EI-8 o MA EI-9 WHEN selected breaker Sync CheckPermissiveCheck Permissive white light is lit for theselectedthe selected breaker, THEN close selected breaker.

BOP

• MA HS CLOSED OR

• MA HS CLOSED Ensure selected switchyard breaker closed.

Breaker 1 - CLOSED

• At RL006, MA ZL-3A BOP

• At RL014, 1ZL-SY010 OR Breaker 2 - CLOSED Appendix D 9 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 1 Page 10 of 58 Event

Description:

Reduce PowerParallel the Main Turbine Generator To the Grid Time Position Applicants Actions or Behavior

• At RL006, MA ZL-4A

• At RL014, 1ZL-SY011 BOP NOTE:

o Once the initial 50 MWe to 100 MWe has been picked up using INCREASE LOAD, consideration should be given to swapping to load limit potentiometer control for increased plant stability.

o Computer point MAP0001 may update quicker and should be monitored in addition to the digital load MW meter.

6.4.4 Load Main Generator:

1. Press INCREASE LOAD pushbutton to increase Generator load between 50 megawatts and 100 megawatts as soon as possible to prevent Generator motoring and maintain load BOP stability.

2. Select Generator loading rate as directed by the SM/CRS.

6.4.5 Close the other switchyard breaker:

BOP 1. Select open switchyard breaker on MA HS-2, BKR SEL.

• Breaker 1 - SELECTED Appendix D 10 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 1 Page 11 of 58 Event

Description:

Reduce PowerParallel the Main Turbine Generator To the Grid Time Position Applicants Actions or Behavior OR

• Breaker 2 - SELECTED

2. Close selected switchyard breaker.

• MA HS CLOSED OR

• MA HS CLOSED Ensure selected switchyard breaker closed.

Breaker 1 - CLOSED

• At RL006, MA ZL-3A

• At RL014, 1ZL-SY010 OR BOP Breaker 2 - CLOSED

• At RL006, MA ZL-4A

• At RL014, 1ZL-SY011 Place BKR SEL switch in off position.

o MA HS OFF 6.4.6 Open Bus Duct Cooling Unit Heater breaker.

BOP oPG1502 - OPEN 6.4.7 At AC XX-1, EHC Panel, select SLOW STARTING RATE.

BOP Appendix D 11 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 1 Page 12 of 58 Event

Description:

Reduce PowerParallel the Main Turbine Generator To the Grid Time Position Applicants Actions or Behavior 6.4.8 Section 6.4, Synchronizing Main Generator, complete.

SRO Lead Examiner may direct initiation of the next event at his discretion Appendix D 12 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 2 Page 13 of 58 Event

Description:

Stop B MFPVCT Level Channel Fails Low Time Position Applicants Actions or Behavior Booth Instructor:

When directed, initiate Event 2 by activating Key 1, or2 (insert mBG01A at 1.7%)

Initiating Cue(s):

BG LI-112, VCT LEV meter goes to zero output on RL002 ALR 00-42C VCT Press Hi/Lo (approx 5 min after failure)

RCS Tavge decreasing/Steam dumps closing BG-V-112B closed (normally open)

BG-V-112D open (normally closed)

Based on changing plant conditions, or the MCB annunciator, CREW determine that VCT Level Channel 112 (BG LI-112) has failed low.

CRS Transition to OFN SB-008, rev 25, Instrument Malfunctions

1. Check If Secondary System Instrument Channel Is CRS Malfunctioning: NO

2. Check If Reactor Coolant System Instrument Channel OR CRS Controller Is Malfunctioning: NO

3. Check If Containment Or RWST Channel Is Malfunctioning:

CRS NO

4. Check If Nuclear Instrumentation System Channel Is CRS Malfunctioning: NO Appendix D 13 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 2 Page 14 of 58 Event

Description:

Stop B MFPVCT Level Channel Fails Low Time Position Applicants Actions or Behavior

5. Check If VCT Level Channel Is Malfunctioning:

a. Go to Attachment U, VCT LEVEL CHANNEL MALFUNCTION CRS U1. Identify failed VCT level channel

a. Compare VCT level channel indications to confirm VCT level channel failure RO o BG LI-112 o BG LI-185 o BG LI-149F o BGL0149 U2. Check failed VCT level channel identified as RO L-112 L-185 RO U3.Check VCT level channel - FAILING LOW (yes)

U4. (r) Check if RWST Switchover Has Occurred:

a. Either VCT Discharge Isolation valve closed.

• BG HIS-112B - CLOSED, normally OPEN RO

• BG HIS-112C

b. Either RWST Isolation To CCP Suction valves open.

• BN HIS-112D - OPEN, normally CLOSED

• BN HIS-112E U5. Isolate Letdown:

a. Close letdown orifice isolation valves.

RO o BG HIS-8149AA o BG HIS-8149BA Appendix D 14 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 2 Page 15 of 58 Event

Description:

Stop B MFPVCT Level Channel Fails Low Time Position Applicants Actions or Behavior o BG HIS-8149CA

b. Close Charging Header Backpressure Control Valve.

o BG HC-182

c. Ensure CCP A, CCP B, or NCP - AT LEAST ONE RUNNING

d. Establish 32 gpm seal injection flow.

o BG FK-121 o BG FK-462 U6. Check VCT Level - GREATER THAN 5%

RO U7. Check Failed VCT Level Channel Identified As:

RO o L-112 U8. (r) Open VCT Discharge Isolation Valve:

a. Station turbine building operator to open breaker NG01AFF2 when valve is open.

b. On RL001, open VCT Discharge Isolation Valve.

o BG HIS-112B RO c. WHEN valve indicates open, THEN direct turbine building operator to open breaker.

o NG01AFF2

d. Locally ensure VCT Discharge Isolation Valve - FULL OPEN o BG LCV-112B Appendix D 15 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 2 Page 16 of 58 Event

Description:

Stop B MFPVCT Level Channel Fails Low Time Position Applicants Actions or Behavior Booth Instruction / Cues:

Report as building watch.

When BG HIS-112B indicates OPEN, insert component remote function (valves) movBGLCV0112B to RACK OUT RO U9. (r) Close RWST Isolation To CCP Suction Valve:

a. Locally close BN LCV-112D at breaker NG01AEF1 by depressing the close push button.

b. WHEN valve indicates closed, THEN open breaker.

o NG01AEF1

c. Locally ensure RWST Isolation To CCP Suction valve - FULL CLOSED o BN LCV-112D CRS

d. Refer to applicable TRM (boration) and TS (ECCS) sections:

o TS 3.5.2 TS 3.5.2, ECCS - Operating Cond A: Restore to operable (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to restore)

Check Failed VCT LevelChannel Identified As:

• L-185 Go to Step U-13 Appendix D 16 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 2 Page 17 of 58 Event

Description:

Stop B MFPVCT Level Channel Fails Low Time Position Applicants Actions or Behavior Booth Instruction and Cues:

Respond as building watch as appropriate.

When directed to local close and de-energize BN LCV-112D

• Insert Over ride P01023B, BNHIS112D Charg Pmps Suct from RWS Green Lamp ON

• After 10 seconds: insert OVR P01023A BNHIS-112D Chg Pumps Suct from RWS Red Lamp OFF

• Insert Over ride P01023B, BNHIS112D Charg Pmps Suct from RWS Green Lamp OFF

• Insert Component Remote Function movBNLCV0112D RF: Rack out to RACK OUT

• Insert Component Remote Function movBNLCV0112D RF: MAN ADJUST to ZERO U10. Check Failed VCT Level Channel Identified As:

o L-185 CRS RNO: Go to Step U-13 U13. Stabilize The Plant:

a. Stop any plant operations requiring rod motion.

RO

b. Ensure AE HIS-38 is closed.

c. (r) Adjust turbine load as necessary to maintain Tavg within 3°F of Tref.

U14. Establish 60 GPM Charging Flow:

a. Check CCP A, CCP B, Or NCP - AT LEAST ONE RUNNING

• BG HIS-1A

• BG HIS-2A

• BG HIS-3 RO

b. Adjust CCP or NCP Flow Control valve and Charging Header Back Pressure Control Valve, as necessary, to establish 60 gpm charging flow.

o BG FK-121 o BG FK-462 Appendix D 17 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 2 Page 18 of 58 Event

Description:

Stop B MFPVCT Level Channel Fails Low Time Position Applicants Actions or Behavior o BG HC-182

c. Adjust Charging Header Flow Control, as necessary, to establish between 8 gpm and 13 gpm seal injection flow to each RCP.

o BG HC-182 U15. Check If Letdown Can Be Established:

a. PZR Level - GREATER THAN 18%

b. Establish normal letdown:

1)Ensure Letdown SystemContainmentSystem Containment IsolationvalvesIsolation valves open.

o BG HIS-8152 o BG HIS-8160

2) Ensure RCS Letdown ToRegenerativeTo Regenerative Heat Exchanger valves open.

o BG HIS-459 o BG HIS-460 RO

3) Place Letdown Heat Exchanger OutleOutlet tPressurepressure Controller in manual and full open.

o BG PK-131

4) Open Orifice Isolation Valves, as necessary, to establish desired letdown flow.

o BG HIS-8149AA o BG HIS-8149BA o BG HIS-8149CA

5) Adjust Letdown Heat Exchanger Outlet Pressure Controller to maintain between 300 psig and 350 psig and place in automatic.

o BG PK-131 U16.

RO Adjust Charging Flow, As Necessary, To Maintain PZR Level Appendix D 18 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 2 Page 19 of 58 Event

Description:

Stop B MFPVCT Level Channel Fails Low Time Position Applicants Actions or Behavior U17. Check VCT Level Failure Corrected - NO; CRS RNO - basically do not continue At the discretion of the Lead Examiner, proceed to the next event.

At the discretion of the Lead Examiner, proceed to the next event Appendix D 19 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 43 Page 20 of 58 Event

Description:

SG Level channel failure Time Position Applicants Actions or Behavior Booth Instructor:

When directed, initiate Event 3 by activating KEY 2 (mAE15A4 to 0%)

Indications available:

SG A level AE LI-551 indication lowering 108A, SG A LEV LO 108B, SG A LEV DEV 108C, SG A FLOW MISMATCH Possibly 83C, RX PARTIAL TRIP, if level gets low enough Actions may be taken prior to procedure entry: AE LI-551 CRS/BOP failure identified; Bypass FRV (AE LK-550) taken to manual, match steam and feed flow.

Respond to MCB Alarm ALR 00-108A rev 4A (or ALR 00-108C, CREW rev 7)

1. Check Steam Generator A controlling Level Channel - LESS THAN 30%

BOP

• AE LI-519

• AE LI-551 AE LI-551 indicates less than 30%

2. Check for Instrument Failure: Check steam generator A controlling level channel - WITHIN 7% OF REMAINING S/G A LEVEL CHANNEL BOP

• AE LI-519

• AE LI-551 RNO: Enter the RNO, Since AE LI-551 is failed low,low the crew would go to the RNO

2. RNO:

BOP 1. Place Feedwater Reg valve or Feedwater Reg Bypass control valve in MANUAL Appendix D 20 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 43 Page 21 of 58 Event

Description:

SG Level channel failure Time Position Applicants Actions or Behavior

• FK AEAE FK-510 (FRV)

• FK AEAE LK-550 (FRBV) 2.RNO:

2. Adjust feedwater reg valve or feedwater reg bypass control valve as necessary to establish steam generator level at program value.

BOP

• AE FK-510

• AE LK-550 2.RNO:

3.Select alternate channel for control.

BOP o AE LS-519C (Selects AE LI-519) 2.RNO:

4.Return feedwater reg valve or feedwater reg bypass control valve to automatic.

BOP

• AE FK-510

• AE LK-550 2.RNO:

5.Go to OFN SB-008, rev 25, INSTRUMENT CRS MALFUNCTIONS, Step 1.

CRS Enters OFN SB-008, rev 25, INSTRUMENT MALFUNCTIONS BOP 1. Check If Secondary System Instrument Channel Is Appendix D 21 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 43 Page 22 of 58 Event

Description:

SG Level channel failure Time Position Applicants Actions or Behavior Malfunctioning:

a. Determine appropriate attachment for malfunctioning channel from table below:

• S/G Level (AE) L-551

b. Go to appropriate attachment for malfunctioning secondary system channel (Attachment F)

OFN SB-008, Attachment F F1. Identify Failed Narrow Range S/G Level Instrument Channel:

a. Ccompare narrow range S/G level indications to confirm a BOP narrow range S/G level channel failure:

• AE LI-551 F2. Check Failed S/G level Channel Selected On S/G Level Selector Switch

• AE LS-519C BOP RNO: (Level Channel 519 was selected in the Alarm Response so the crew will Go to Step F7).

This step will be performed if the crew did not go to the ALR first.

F3. Place affected SG feed reg (bypass) control valve - IN BOP MANUAL (AE FK-510) AE LK-550 (FRBV)

F4. Adjust affected feedwater reg (bypass) valve, as BOP necessary, to establish steam generator level at program:

(AE FK-510) AE LK-550 (FRBV)

Appendix D 22 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 43 Page 23 of 58 Event

Description:

SG Level channel failure Time Position Applicants Actions or Behavior F5. Select alternate SG level channel for feedwater control:

BOP AE LS-519C F6. Restore affected SG feed reg (bypass) valve controller to -

AUTO BOP (AE LK-550 - Feed reg bypass valve controller for SG A)

Appendix D 23 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 43 Page 24 of 58 Event

Description:

SG Level channel failure Time Position Applicants Actions or Behavior F7. Monitor The Following Technical Specifications for LCOs And Comply With Action Statements As Appropriate:

• 3.3.1, REACTOR TRIP SYSTEM INSTRUMENTATION

• 3.3.2, ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION

• 3.3.4, REMOTE SHUTDOWN INSTRUMENTATION, Table 3.3.4, REMOTE SHUTDOWN INSTRUMENTATION, Table 3.3.4-1, function 8 (Not Applicable) 3.3.3, ACCIDENT MONITORING INSTRUMENTATION, Table 3.3.3-1, function 13 (Not Applicable)

CRS o TS 3.3.1, Reactor Trip System Instrumentation, Table 3.3.1-1, FU 14 Cond E: One channel inoperable - place channel in trip (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) o TS 3.3.2, ESFAS Instrumentation, Table 3.3.2-1, FU 5c, 6d Cond A: Channel inoperable - enter Condition per Table (immediately)

Cond D: One channel inoperable - place channel in trip (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />)

Cond I: One channel inoperable - place channel in trip (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />)

On Lead Examiners cue, proceed to the next event Appendix D 24 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 54 Page 25 of 58 Event

Description:

Main Turbine High Vibration TripCCW system leak Time Position Applicants Actions or Behavior Booth Instructor:

When directed, initiate Event 5 4 by activating KEY 3.

Indications available:

CCW Surge Tank level loweringMCB Alarms:

53D112B, MECH OVSP TURB TRIP 113A, TURB VIB HI-HI TURB TRIP 113E, 24/125V X-TRIP TURB TRIP 113F, UNIT TRIP TURB TRIP 114F, ETS PRESS LO TURB TRIP 119A, TURB VIB HI CCW SRG TK B LEV HI LO after a period of time CCW M/U valve OPENS CRS Enters OFN AC-002 rev 16, Main Turbine High Vibration NOTES o If a Reactor TRIP occurs during the performance of this procedure, EMG E-0, REACTOR TRIP OR SAFETY INJECTION should be performed.

o Vibration readings will be inaccurate when turbine speed is below 800 rpm due to sensitivity of the vibration probes.

o When the turbine high vibration trip is enabled, a turbine TRIP will occur if 2/2 sensors on any bearing reaches 12 mils with a 6 second time delay.

o Vibration readings to manually TRIP Turbine must be on both vibration probes from the same bearing.

NOTE If a leak has occurred on the non-running train, it may not be desirable to start the pump in that train.

1. Check Main Turbine vibration - REQUIRES TURBINE TRIP

a. Perform the following:

CRS Use NPIS Turn on Code MTG OR Appendix D 25 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 54 Page 26 of 58 Event

Description:

Main Turbine High Vibration TripCCW system leak Time Position Applicants Actions or Behavior Dispatch operator to Panel AC-121 in EHC room to record data on Attachment B, Panel AC-121 Operation Speed Vibration limit on any journal that requires Turbine trip 1400-1800 rpm 10 mils for 15 minutes OR greater than or equal to 12 mils at any time with symptoms of high vibration present

b. Check vibration limit - GREATER THAN LIMIT Booth Instruction / Cue:

Respond as building operator if dispatched to EHC room to record data.

2. Check initial reactor power - GREATER THAN OR EQUAL TO 50%

NO - RNO: Perform the following:

CRS a. Trip the Turbine

b. Go to OFN MA-001, Load Rejection or Turbine Trip, while continuing with this procedure.

c. Go to step 6.

CRS Enters OFN MA-001, rev 13, Load Rejection or Turbine Trip

1. Check Turbine - NOT TRIPPED RNO CRS a. the reactor is NOT tripped

b. Then, go to Attachment A, Turbine Trip Check CCW Pumps- ONE RUNNING IN EACH TRAIN Note: If crew utilizes OFN AC-002, they will be directed to transition back to this procedure while continuing with OFN AC-002.

CREW Attachment A, Turbine Trip Appendix D 26 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 54 Page 27 of 58 Event

Description:

Main Turbine High Vibration TripCCW system leak Time Position Applicants Actions or Behavior Start CCW pump(s), as necessary, to establish one running in each train.

NOTE If reactor trip occurs while performing this attachment, go to EMG E-0, REACTOR TRIP OR SAFETY INJECTION A1. Verify Turbine Trip:

1. Check the following:

Main Stop Valves- ALL CLOSED OR Turbine Auto Stop bistable lights - AT LEAST TWO BOP LIT

2. Check main generator breakers and exciter breaker-OPEN o MA ZL-3A o MA ZL-4A o MA ZL-2 A2. Stabilize Tavg and Reactor Power

a. Ensure Steam Dumps operating properly CRS/

b. () Adjust control rods as necessary to maintain reactor CREW critical and the desired power

c. Adjust controllers to maintain a target Tavg/Tref temperature error between 0 and +5°F A3. Check PZR Pressure - Stable at or trending to 2235 psig RO RO A4. Check PZR Level-Stable at or trending to program level BOP A5. Check S/G Levels - Stable between 45% and 55%

BOP A6. Verify Main Turbine Oil Pump Alignment:

Appendix D 27 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 54 Page 28 of 58 Event

Description:

Main Turbine High Vibration TripCCW system leak Time Position Applicants Actions or Behavior No problems A7. Align MSR and Turbine Drains:

BOP Due to turbine start up only AC HIS-253 and AC HIS-251 need to be opened.

A8. Ensure compliance with Technical Specification 3.1.6, CRS Control Rod Insertion Limits A9. Shutdown Main Generator:

a. Match flags on main generator and exciter field breakers BOP b. Place Regulator Mode Transfer Switch in Manual

c. Locally close breaker for bus duct cooling unit heater

d. Secure core monitor and pyrolysate collector (SYS CC-130)

Booth Instruction / Cue:

If contacted as building watch, respond that the core monitor and pyrolysate collector will be secured per SYS CC-130.

A10. Monitor Turbine Coastdown

a. Ensure main turbine oil temperatures is being maintained grater than 90 °F BOP

b. Check turbine speed-Less than 5 rpm RNO when <5 RPM, do step A10.c

c. Ensure turning gear engaged A11. Check S/G Safety Valves Remained Closed during BOP turbine trip (yes)

A12. Match flags on Unit Auxiliary 13.8 KV breakers - No BOP action required.

CRS A13. Shutdown Unnecessary Plant Equipment Appendix D 28 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 54 Page 29 of 58 Event

Description:

Main Turbine High Vibration TripCCW system leak Time Position Applicants Actions or Behavior On Lead Examiners cue, proceed to the next event Appendix D 29 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 54 Page 30 of 58 Event

Description:

Main Turbine High Vibration TripCCW system leak Time Position Applicants Actions or Behavior Check location of leak- Identified as one the following:

• Safety loop Train A

• Safety loop Train B (YES)

CREW

• Service Loop Inside CTMT

• Service Loop Outside CTMT Check Leak On Service Loop INSIDE CONTAINMENT RO/BOP Go to step 12 Check Leak on Service Loop - OUTSIDE CONTAINMENT RO/BOP Go to Step 19 Check Leak Identified on - SAFETY LOOP RO/BOP Ensure a CCW pump in intact CCW train - RUNNING RO/BOP RO/BOP Ensure intact CCW train aligned to supply service loop:

Appendix D 30 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 54 Page 31 of 58 Event

Description:

Main Turbine High Vibration TripCCW system leak Time Position Applicants Actions or Behavior Appendix D 31 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 54 Page 32 of 58 Event

Description:

Main Turbine High Vibration TripCCW system leak Time Position Applicants Actions or Behavior Appendix D 32 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 6, 7, 8, 9, 105, Page 33 of 58 6, 7, 8 Event

Description:

Loss of power, bus failure, steamFeed line break IRC, ATWT, MSIV failure, , and MDTDAFW failure Time Position Applicants Actions or Behavior Booth Instructor:

When directed, initiate Eevent 56 by activating KEY 4 or (insert malfunctions mAE14A Feedwater Break IRC at 8E6; preloads already inserted: mAL04A MD AFW Pump A fails to auto start, mSF17A, mSF17B (Reactor Fails to trip in Auto and Manual, and mSA27AB08 and AB09, AB10 and AB07 MSIVs fail to close in Auto)

Indications available:

SG A feed flow increases. Containment humidity increases. Containment pressure increases.

60E - CTMT SUMP A/B LEV HI 60F - CTMT SUMP C/D LEV HI 88C - HI CTMT PRESS SI RX TRIP OFN AB-041, Steamline or Feedline Break, may or may not be entered, based on the pace of the feedline break.Main Control Room lighting goes out, some restores when the available EDG picks up the bus. Multiple UV alarms on Safeguards busses. Reactor trip alarms.

NOTE: Crew should perform manual Reactor Trip and Safety Injection actuation.

Reactor fails to trip in Manual (or Auto); Crew enters EMG FR-S1, rev 15A, Response to Nuclear Power generator/ATWS CRS/Crew EMG E-0, rev 21, Reactor Trip or Safety Injection CAUTION Accident conditions can cause higher than normal radiation levels. Health Physics monitoring may be required while performing local operator actions.

NOTES Appendix D 33 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 6, 7, 8, 9, 105, Page 34 of 58 6, 7, 8 Event

Description:

Loss of power, bus failure, steamFeed line break IRC, ATWT, MSIV failure, , and MDTDAFW failure Time Position Applicants Actions or Behavior Steps 1 thru 4 are immediate action steps Foldout page shall be monitored throughout this procedure.

1. Verify Reactor Trip:

Check all rod bottom lights -- LIT; No - perform RNO Manually trip reactor. If reactor power is greater than or equal to 5% OR IR range power is increasing, then perform the following:

1. Direct operator to monitor CSFST

2. Transition to EMG FR-S1, rev 15A, EMG FR-S1, Response to Nuclear Power generator/ATWS RO Ensure reactor trip breakers an bypass breakers - OPEN

• SB ZL-1

• SB ZL-2

• SB ZL-3

• SB ZL-4 Check intermediate range neutron flux - DECREASING SE NI-35B GAMMA METRICS SE NI-36B GAMMA METRICS EMG FR-S1, rev 15A, EMG FR-S1, Response to Nuclear CRS Power generator/ATWS

1. Verify Reactor trip (CT - RO and BOP actions) Perform RNO:

RNO:

1. Manually trip reactor (both RO and BOP panels -- reactor RO/BOP trip pushbuttons)

2. If reactor will not trip then perform the following

• Insert control rods in auto or manual (RO)

Appendix D 34 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 6, 7, 8, 9, 105, Page 35 of 58 6, 7, 8 Event

Description:

Loss of power, bus failure, steamFeed line break IRC, ATWT, MSIV failure, , and MDTDAFW failure Time Position Applicants Actions or Behavior

• Manually deenergize rod drive motor generators

• Open the breakers for PG-19 and PG-20 (BOP)

• If PG20 does NOT deenergize open PG HIS-3

• Dispatch operator to trip & bypass breakers (RO)

• When reactor trip breakers and bypass are open or all Rod Bottom Lights LIT, reclose the breakers for PG-19 & PG-20 (RO)

• Continue with step 2 Booth Instruction / Cue:

Respond as building watch.

When contacted as building watch to open reactor trip and bypass breakers, insert Remote Functions:

rSF02A and rSF02B to OPEN (RX trip bypass breakers) rSF03A and rSF03B to OPEN (Rx trip breakers)

Report back to Control Room when reactor trip and bypass breakers are open.

2. Verify Turbine trip BOP Turbine is tripped

3. Check Main Gen & Exciter Bkrs - OPEN BOP Appendix D 35 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 6, 7, 8, 9, 105, Page 36 of 58 6, 7, 8 Event

Description:

Loss of power, bus failure, steamFeed line break IRC, ATWT, MSIV failure, , and MDTDAFW failure Time Position Applicants Actions or Behavior

4. Verify AFW pumps running (CT-Start A MDAFW Pump)

a. Check motor driven AFW pumps - RUNNING. No, perform RNO BOP RNOa. MDAFW pump A is not running. Manually start AFW pump

b. Check TDAFW pump - RUNNING (yes)

5. Check SI NOT in progress. Perform RNO:

RO RNO: SI is in progress, Check ECCS flow greater than 90 gpm and go to step 9.

9. Check PZR pressure < 2335 psig RO RO 10. Verify containment purge isolation

11. Check Safety Injection NOT actuated - it is, Perform RNO RNO:

RO Perform step 1 - 7 of EMG E-0 while continuing with this procedure CRS Assign an operator to perform EMG E-0 steps 1-7.

12.Check it the following trips have occurred:

CRS

a. Reactor trip

b. Turbine trip

13. Verify Rx Subcritical CRS Rx is subcritical, go to step 25.

RO 25. Check Rx trip bkrs - OPEN Appendix D 36 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 6, 7, 8, 9, 105, Page 37 of 58 6, 7, 8 Event

Description:

Loss of power, bus failure, steamFeed line break IRC, ATWT, MSIV failure, , and MDTDAFW failure Time Position Applicants Actions or Behavior NOTE: Booth operator should have already called and reported that reactor trip and bypass breakers are open.

26. Continue boration until adequate shutdown margin is CRS obtained

27. Check CRDM fans - ALL AVAILABLE RUNNING RO

28. Return to procedure and step in effect CRS Transitions to EMG E-0 rev 21, Reactor Trip and Safety CREW Injection CRS Directs EMG E-0, rev 21, Reactor Trip and Safety Injection May reperform steps 1 - 6 of EMG E-0, even though EMG FR-CRS S1 assigned an operator to perform those steps.

NOTE: Secondary temperature and pressure has been decreasing due to failure of MSIVs to close.

Appendix D 37 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 6, 7, 8, 9, 105, Page 38 of 58 6, 7, 8 Event

Description:

Loss of power, bus failure, steamFeed line break IRC, ATWT, MSIV failure, , and MDTDAFW failure Time Position Applicants Actions or Behavior May direct use Foldout page item #3 to isolate the faulted Steam Generator.

Faulted SG Isolation Criteria: If any SG pressure decreasing in an uncontrolled manner or any SG completely depressurized, then the following may be performed:

a. Close main steam isolation valves.

b. Isolate fed flow to faulted SG

c. Maintain total feed flow greater than 270, 000 lbm/hr CRS until narrow range level in at least one SG is greater than 6%

(CT - Close MSIVs by depressing the All Close buttons on RL006 or depressing close on the individual valves)

(Recall SG A feedline break and MSIVs fail to auto close.)

(CT - Isolate faulted Steam Generator)

1. Verify reactor trip:

a. Check all rod bottom lights - LIT RO

b. Ensure reactor trip and bypass breakers - OPEN

c. Check IR neutron flux - DECREASING

2. Verify Turbine Trip:

a. Check the following:

Main Stop Valves- ALL CLOSED OR Turbine Auto Stop bistable lights - AT LEAST TWO LIT BOP b.Check main generator breakers and exciter breaker-OPEN

• MA ZL-3A

• MA ZL-4A

• MA ZL-2

3. Check AC Emergency Busses- AT LEAST ONE RO ENERGIZED Appendix D 38 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 6, 7, 8, 9, 105, Page 39 of 58 6, 7, 8 Event

Description:

Loss of power, bus failure, steamFeed line break IRC, ATWT, MSIV failure, , and MDTDAFW failure Time Position Applicants Actions or Behavior

• NB01 Voltage - NORMAL

• NB02 voltage - NORMAL - NB02 Bus Lock Out

4. Check any indication SI is actuated- LIT

a. Check any indication SI is actuated - LIT

• Annunciator 00-30A, NF039A LOCA SEQ ACTUATED LIT OR

• Annunciator 00-031A, NF039B LOCA SEQ ACTUATED - LIT OR

• ESFAS status panel SIS section - ANY WHITE RO LIGHTS LIT OR

• Partial Trip Status Permissive/block status panel- SI RED LIGHT LIT

b. Ensure both trains of SI actuated o SB HS-27 o SB HS-28 CAUTION If offsite power is lost after SI reset, manual action may be required to restore safeguards equipment to the required configuration.

5. Check if SI is required:

• SI was manually actuated AND was required OR

• RCS pressure LESS THAN OR EQUAL TO 1830 PSIG OR

• Any S/G pressure LESS THAN OR EQUAL TO RO 615 PSIG OR

• Containment pressure GREATER THAN OR EQUAL TO 3.5 PSIG OR

• RCS subcooling- LESS THAN 30 °DEGREES F.

OR Appendix D 39 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 6, 7, 8, 9, 105, Page 40 of 58 6, 7, 8 Event

Description:

Loss of power, bus failure, steamFeed line break IRC, ATWT, MSIV failure, , and MDTDAFW failure Time Position Applicants Actions or Behavior

• PZR LEVEL - LESS THAN 6% (33%)

6. Check Main Generator breakers and exciter breakers -

BOP OPEN

7. Verify Automatic actions using Attachment F, AUTOMATIC SIGNAL VERIFICATION ROCRS No power on NB02

8. Check Total AFW Flow- GREATER THAN 270,000 LBM/.HR - NO, perform RNO RNO: Perform the following:

Perform the following:

a. IF S/G narrow range level in at least one S/G is greater than 6% (29%), THEN control feed flow to maintain narrow range BOP level and go to Step 98.

b. Manually start pumps and align valves as necessary to establish greater than 270,00 lbm/hr AFW flow. (CT - Start MDAFW A)

(NOTE: CT actions may have been performed while in EMG FR-S1.)(Start TDAFW)

Appendix D 40 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 6, 7, 8, 9, 105, Page 41 of 58 6, 7, 8 Event

Description:

Loss of power, bus failure, steamFeed line break IRC, ATWT, MSIV failure, , and MDTDAFW failure Time Position Applicants Actions or Behavior

9. Check RCS Cold Leg Temperatures - No , perform RNO

• Stable at or trending to 557 degrees F for condenser steam dumps

• Stable at or trending to 561°F for S/G ARVs RNO: Perform the following:

If temperature is less than setpoint and decreasing, THEN perform the following:

1. Stop dumping steam.

BOP 2. Close Main Turbine Stop and control valves startup drains.

o -AC HIS-134

3. IF cooldown continues, THEN control total feed flow to limit RCS cooldown. Maintain total feed flow greater than 270,000 lbm/hr until narrow range level greater than 6%

(29%) in at least one S/G/

4. If cooldown continues due to excessive steam flow, then close main steamline isolation valves, bypass valves, and drain valves.

(CT - Close MSIVs by depressing the All Close buttons on RL006 or depressing close on the individual valves)

10. Establish S/G Pressure Control:

a. Check condenser AVAILABLE.

o C-9 LIT o MSIV - OPEN NO o Circulating Water pumps-RUNNING NO BOP RNO: Perform the following:

1. Use S/G ARVs

2. Got to Step 110 Appendix D 41 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 6, 7, 8, 9, 105, Page 42 of 58 6, 7, 8 Event

Description:

Loss of power, bus failure, steamFeed line break IRC, ATWT, MSIV failure, , and MDTDAFW failure Time Position Applicants Actions or Behavior

11. Check PZR PORVs CLOSED o BB HIS-455A RO o BB HIS-456 A Power to block valves - AVAILABLE o BB HIS-8000A o BB HIS-8000B RCS pressure - LESS THAN 2185 PSIG

12. Check Normal PZR spray Valves-CLOSED o BB ZL-455B RO o BB ZL-455C

13. Check PZR Safety Valves-CLOSED o BB ZL-8010A RO o BB ZL-8010B o BB ZL-8010C NOTE Seal injection flow shall be maintained to all RCPs.

14. Check if RCPs should be stopped:

a. Check RCPs- ANY RUNNING (If RCS pressure <1400 RO psigs, RCPs were stopped. RNO: go to step 15)

b. Check RCS pressure-LESS THAN 1400 PSIG (If RCS pressure > 1400 psig, go to RNO: GO TO STEP 15)

c. Check ECCS pumps - AT LEAST ONE RUNNING Appendix D 42 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 6, 7, 8, 9, 105, Page 43 of 58 6, 7, 8 Event

Description:

Loss of power, bus failure, steamFeed line break IRC, ATWT, MSIV failure, , and MDTDAFW failure Time Position Applicants Actions or Behavior

d. Check operator controlled cooldown - NOT IN PROGRESS

e. Stop all RCPs GO TO STEP 14

15. Direct Operator To Monitor Critical Safety Functions Using EMG F-0, CRITICAL SAFETY FUNCTION STATUS TREES CRS (CSFST).

16. Check if S/Gs Are Not Faulted

a. Check all pressures in all S/Gs b.o NO S/G PRESSURE DECREASING IN AN UNCONTROLLED MANNER c.o NO S/G COMPLETELY DEPRESSURIZED.

CRS Perform RNO: PERFORM THE FOLLOWING:

1. Ensure BIT Inlet And Outlet Valves are open o EM HIS-8803A o EM HIS-8803B o EM HIS-8801A o EM HIS-8801B

2. Go to EMG E-2, Faulted Steam Generator Isolation, step 1.

NPERFORM THE FOLLOWING:

Ensure BIT Inlet And Outlet Valves are open

• EM HIS-8803A

• EM HIS-8803B

• EM HIS-8801A

• EM HIS-8801BOTE: Crew transitions to EMG E-2, rev 13, Faulted Steam Generator Isolation Appendix D 43 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 6, 7, 8, 9, 105, Page 44 of 58 6, 7, 8 Event

Description:

Loss of power, bus failure, steamFeed line break IRC, ATWT, MSIV failure, , and MDTDAFW failure Time Position Applicants Actions or Behavior Go to Direct EMG E-2, rev 13, FAULTED STEAM CRS GENERATOR ISOLATION, step 1 NOTE Foldout page shall be monitored throughout this procedure.

1. Check Steamlines On All S/Gs - ISOLATED

a. Ensure main steamline isolation valve(s)-CLOSED o AB HIS-14 for S/G A o AB HIS-17 for S/G B o AB HIS-20 for S/G C o AB HIS-11 for S/G D

b. Ensure main steamline isolation bypass valves -CLOSED o AB ZL-15A for S/G A BOP o AB ZL-18A for S/G B o AB ZL-21A FOR S/G C o AB ZL-21 A FOR S/G D

c. Ensure main steamline low point drain valves (s) - CLOSED o AB HIS-9 for S/G A o AB HIS-8 for S/G B o AB HIS-7 for S/G C o AB HIS-10 for S/G D

2. Check if Limitations For Fault In Area 5 Are required:

a. Check if steam is issuing from vent openings at 2000 foot elevation on south end of Turbine Building

b. Warn local operators of adverse conditions in main steam CRS enclosure

c. Use S/G ARV pressure indicating controllers on RL006 for S/G pressure indication during subsequent recovery actions.

d. Use pressure and flow indications to determine valve position for valves located in the main steam enclosure Appendix D 44 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 6, 7, 8, 9, 105, Page 45 of 58 6, 7, 8 Event

Description:

Loss of power, bus failure, steamFeed line break IRC, ATWT, MSIV failure, , and MDTDAFW failure Time Position Applicants Actions or Behavior

e. DO NOT RESET AFAS-TD until turbine driven AFW pump shutdown is required.

f. Use manual initiation of AFAS-TD as necessary to restart turbine driven AFW pump.

Booth Instruction / Cue:

Respond as building watch: No steam is issuing from vent openings at 2000 south end of Turbine Building

3. Check If Any S/G Is Not Faulted:

a. Check pressure in all S/Gs CRS Any S/G PRESSURE STABLE OR ANY S/G PRESSURE INCREASING

4. Identify Faulted S/Gs:

a. Check pressure in all S/Gs:

CRS Any S/G PRESSURE DECREASING IN AN UNCONTROLLED MANNER OR ANY S/G COMPLETELY DEPRESSURIZED Appendix D 45 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 6, 7, 8, 9, 105, Page 46 of 58 6, 7, 8 Event

Description:

Loss of power, bus failure, steamFeed line break IRC, ATWT, MSIV failure, , and MDTDAFW failure Time Position Applicants Actions or Behavior NOTE: A SG feedline should be recognized as the faulted steam generator.

CAUTION If the turbine driven AFW pump is the only available source of feed flow, steam supply to the turbine driven afw AFW pump must be maintained from at least one S/G.

5. Isolated Faulted S/Gs:

a. Close AFW flow control valves to faulted S/Gs

-AL HK-10A 7A and AL HK-9A 8A for S/G BA

b. Locally close steam supply to turbine driven AFW pump from faulted S/G(s) -- N/A for SG A BOP

c. Ensure S/G ARV on faulted S/G(s) - CLOSED AB PIC-1A for S/G A (CT - Isolate faulted steam generator)

(NOTE: Crew may have used EMG E-0 Foldout item #3, Faulted Steam Generator to isolate the faulted steam generator)

6. Verify Feedline Isolated On Faulted S/G(s)

a. -Main feedwater reg valve- CLOSED AE ZL-5120 for S/G AB

b. Main feedwater reg bypass valve-CLOSED BOP AE ZL-550

c. Main feedwater isolation valve-CLOSED AE HIS-39 for SG A

d. Main feedwater chemical injection valve-CLOSED AE HIS-43 for SG A Appendix D 46 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 6, 7, 8, 9, 105, Page 47 of 58 6, 7, 8 Event

Description:

Loss of power, bus failure, steamFeed line break IRC, ATWT, MSIV failure, , and MDTDAFW failure Time Position Applicants Actions or Behavior

7. Verify Blowdown and Sampling Isolated On Faulted SG(s)

-SG upper Sample Isolation valves-CLOSED BOP

• BM HIS-1920 for SG A CAUTION If any PZR PORV opens because of high PZR pressure, the PORV shall be monitored to ensure it recloses after pressure decreases to less than 2335 psig.

8. Check PZR PORVs And Block Valves:

a. Power to block valves-AVAILABLE o -BB HIS-8000A o -BB-HIS-8000B RO

b. PZR PORVs - CLOSED o -BB HIS-455A o -BB HIS -456A

c. RCS pressure- LESS THAN 2185 PSIG

9. Check If Uncontrolled Cooldown Has Stopped.

a. -Check RCS hot leg temps-STABLE OR INCREASING CRS

b. -Control steam flow and feed flow as necessary to maintain stable RCS hot leg temps CAUTIONS Appendix D 47 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 6, 7, 8, 9, 105, Page 48 of 58 6, 7, 8 Event

Description:

Loss of power, bus failure, steamFeed line break IRC, ATWT, MSIV failure, , and MDTDAFW failure Time Position Applicants Actions or Behavior o If steamline in Area 5 of AUX BLDG are not intact, extreme caution will be necessary when performing local surveys.

o If offsite power is lost after SI reset, manual action may be required to restore safeguards equipment to the required configuration.

10. Determine Secondary Radiation Levels:

-a. Direct Health Physics to survey steamlines in Area 5 of Aux Bldg.

CRS

-b. Check S/G sampling-ISOLATED

-c. Ensure SI-RESET. Reset SI.

10d. Check Instrument Air header pressure - GREATER THAN 105 PSIG.

o KA PI-40

e. Open CCW To Radwaste System Isolation Valves o EG HS-69 o EG HS-70 Perform the following:

-Ensure ESW To Air Compressor Valves-OPEN BOP *EF HIS-43

• EF HIS-44

f. Open all S/G sample isolation valves o BM HIS-65 for S/G A o BM HIS-35 for S/G A o BM HIS-66 for S/G B o BM HIS-36 for S/G B o BM HIS-67 for S/G C o BM HIS-37 for S/G C o BM HIS-68 for S/G D o BM HIS-38 for S/G D Appendix D 48 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 6, 7, 8, 9, 105, Page 49 of 58 6, 7, 8 Event

Description:

Loss of power, bus failure, steamFeed line break IRC, ATWT, MSIV failure, , and MDTDAFW failure Time Position Applicants Actions or Behavior 10g. Direct Chemistry to sample all S/Gs for activity -Reset and close Air Compressor Breaker Reset Switches

• KA HIS-2C CRS *KA HIS-3C Booth Instructions/ Cue:

If contacted at HP, acknowledge direction to survey steam lines in Area 5.

If contacted as Chemistry, acknowledge direction to sample al Steam Generators for activity.

Open CCW To Radwaste System Isolation Valves

• EG HS-69

• EG HS-70

11. Check IF S/G Tubes Are Intact:

a. Condenser air discharge radiation-NORMAL BEFORE ISOLATION o GEG 925

b. SG blowdown and sample radiation-NORMAL o BML 256 o SJL 026 o Sample result CRS

c. Turbine driven aux. Feedwater pump exhaust radiation-NORMAL o FCT 381

d. SG Steamline radiation-NORMAL o ABS 114 FOR SG A o ABS 113 FOR SG B o ABS 112 FOR SG C o ABS 111 FOR SG D Appendix D 49 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 6, 7, 8, 9, 105, Page 50 of 58 6, 7, 8 Event

Description:

Loss of power, bus failure, steamFeed line break IRC, ATWT, MSIV failure, , and MDTDAFW failure Time Position Applicants Actions or Behavior o Local surveys

e. SG narrow range levels - NO LEVEL INCREASING IN AN UNCONTROLLED MANNER

12. Check If ECCS Flow Should Be Reduced:

a. RCS subcooling - GREATER THAN 30°F (45°F)

b. Secondary heat sink:

Total feed flow to intact S/Gs - GREATER THAN 270,000 LBM/HR OR CRS Narrow range level in at least one intact SG - GREATER THAN 6% (29%)

c. RCS pressure - STABLE OR INCREASING

d. PZR level-GREATER THAN 6% (33%)

e. Go to EMG ES-03, SI TERMINATION, STEP 1 Scenario may be terminated when crew enters EMG ES-03, SI termination Appendix D 50 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # 6, 7, 8, 9, 105, Page 51 of 58 6, 7, 8 Event

Description:

Loss of power, bus failure, steamFeed line break IRC, ATWT, MSIV failure, , and MDTDAFW failure Time Position Applicants Actions or Behavior Appendix D 51 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # NA Page 52 of 58 Event

Description:

Automatic Signal Verification Time Position Applicants Actions or Behavior EMG E-0, rev 21, Reactor Trip or Safety Injections, Attachment F, AUTOMATIC SIGNAL VERIFICATION NOTE: The CRS will assign an operator to perform Attachment F.

F1. Verify Feedwater Isolation:

a. Main Feedwater Pumps - TRIPPED o -annunciator 00-120A, MFP A TRIP-LIT o -annunciator 00-123A, MFP B TRIP-LIT

b. Main feedwater reg valves - CLOSED o -AE ZL-510 FOR SG A o -AE ZL-520 FOR SG B o -AE ZL-530 FOR SG C o -AE ZL-540 FOR SG D

c. Main Feedwater reg bypass valves - CLOSED o -AE ZL-550 FOR SG A RO/BOPR o -AE ZL-560 FOR SG B O o AE ZL-570 FOR SG C o -AE ZL-580 FOR SG D

d. Main Feedwater islolationisolation valves - CLOSED o -AE HIS-39 FOR SG A o -AE HIS-40 FOR SG B o -AE HIS-41 FOR SG C o -AE HIS-42 FOR SG D

e. Main Feedwater chemical Injection valves - CLOSED o -AE HIS-43 FOR SG A o -AE HIS-44 FOR SG B o -AE HIS-45 FOR SG C o -AE HIS-46 FOR SG D Appendix D NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # NA Page 53 of 58 Event

Description:

Automatic Signal Verification Time Position Applicants Actions or Behavior

f. Check ESFAS status panel SGBSIS section - ALL WHITE LIGHTS LIT o -Red Train o -Yellow train F2. Verify Containment isolation Phase A:

a. Check ESFAS status panel CISA section-ALL WHITE LIGHTS LIT RO/BOPR o -Red Train O

o -Yellow Train ONLY RED TRAIN IS ACTUATED F3. Verify AFW Pumps Running:

Critical Task

a. Check motor driven AFW pumps-BOTH RUNNING, RNO: Manually start pumps AL HIS-22A - MDAFW pump B - RUNNING RO/BOPR AL HIS-23A - MDAFW pump A - NOT RUNNING. Start O MDAFW pump A (CT)

b. Check turbine driven AFW pump - RUNNING a.MUST START TDAFW (CT)

F4. Verify ECCS pumps - RUNNING:

RO/BOPR a. Check CCPs - BOTH RUNNING O

b. Check SI pumps - BOTH RUNNING Appendix D NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # NA Page 54 of 58 Event

Description:

Automatic Signal Verification Time Position Applicants Actions or Behavior

c. Check RHR pumps - BOTH RUNNING Verify CCW Alignment:

a.Check CCW pumps-ONE RUNNING IN EACH TRAIN b.Check one pair of CCW service loop Supply And Return Valves for an operating CCW pump-OPEN

-EG ZL-15 AND EG ZL-53 OR

-EG ZL-16 AND EG ZL-54 F5. Verify CCW Alignment:

a. Check CCW pumps - ONE RUNNING IN EACH TRAIN RO/BOP b. Check one pair of CCW service loop Supply And Return Valves for an operating CCW pump - OPEN EG ZL-15 AND EG ZL-53 OR EG ZL-16 AND EG ZL-54 F6. Check ESW Pumps - BOTH RUNNING RO/BOPR O

F7. Check Containment Fan Coolers - RUNNING IN SLOW SPEED RO/BOPR O

F8. Verify Containment Purge Isolation:

a. Check ESFAS status panel CPIS section - ALL WHITE RO/BOPR LIGHTS LIT O

o -Red Train o -Yellow Train Appendix D NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # NA Page 55 of 58 Event

Description:

Automatic Signal Verification Time Position Applicants Actions or Behavior F9. Verify Both Trains Of Control Room Ventilation Isolation:

a. Check ESFAS status panel CRVIS section - ALL WHITE LIGHTS LIT RO/BOPR o -RED Train O o -YELLOW Train

b. Ensure Control Room outer door - CLOSED F10. Verify Main Steamline Isolation Not Required:

a. Check containment pressure - HAS REMAINED LESS THAN 17 PSIG o -GN PR-934

b. Check either condition below - SATISFIED:

Low Steamline pressure SI Not Blocked & S/G Critical Pressure has remained > 615 psig Task Or Low Steam Line pressure SI Blocked and steamline pressure rate has remained < 100 RO/BOPR psi/50 sec O

Perform RNO:

Verify Steamline Isolation:

1. If any main steamline isolation valve is NOT closed, THEN perform the following:

fast a. Closeclose main steamline isolation valves. (CT)

-AB HS-79

-AB HS-80

2. Check ESFAS status panel SLIS section - ALL WHITE Appendix D NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # NA Page 56 of 58 Event

Description:

Automatic Signal Verification Time Position Applicants Actions or Behavior LIGHTS EXCEPT MAIN STEAM ISOLATION VALVES LIT o -RED Red Train o -Yellow Train F11. Verify Containment Spray Not Required:

a. Containment pressure - HAS REMAINED LESS THAN RO/BOPR 27 PSIG:

O o Annunciator 00-059A, CSAS-NOT LIT o Annunciator 00-059b, CISB-NOT LIT o GN PR-934 Appendix D NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # NA Page 57 of 58 Event

Description:

Automatic Signal Verification Time Position Applicants Actions or Behavior F12. Verify ECCS Flow:

a. Check Centrifugal Charging Pumps To Boron Injection Tank Flow meters - FLOW INDICATED o EM FI-917A o EM FI-917B

b. Check RCS pressure - LESS THAN 1700 PSIG

c. Check SI Pump Discharge Flow meters - FLOW INDICATED RO/BOPR O

o -EM FI-918 o -EM FI-922

d. Check RCS pressure - LESS THAN 325 PSIG

e. Check RHR To Accumulator Injection Loop Flow meters

- FLOW INDICATED o -EJ FI-618 o -EJ FI-619 F13. Verify AFW Valves - PROPERLY ALIGNED:

a. Check ESFAS status panel AFAS section - ALL WHITE LIGHTS EXCEPT THE FOLLOWING LIT o -AL HV-9 FOR RED TRAIN RO/BOPR o -AL HV-11 FOR RED TRAIN O o -AL HV-5 FOR YELLOW TRAIN o -AL HV-7 FOR YELLOW TRAIN

b. Check white train ESFAS status panel AFAS section -

ALL WHITE LIGHTS LIT Appendix D NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 12 Event # NA Page 58 of 58 Event

Description:

Automatic Signal Verification Time Position Applicants Actions or Behavior F14. Verify SI Valves- PROPERLY ALIGNED:

a. Check ESFAS status panel SIS section -SYSTEM LEVEL WHITE LIGHTS ALL LIT RO/BOPR O

o -Red Train o -Yellow Train Check If NCP Should Be Stopped:

a. CCPs- ANY RUNNING RO/BOPR b. Stop NCP O

o -BG HIS-3 RO/BOPR Return To Procedure And Step In Effect O

Appendix D NUREG 1021 Revision 9

Appendix D Scenario Outline Form ES-D-1 Facility: __Wolf Creek________________ Scenario No.: ___3____ Op-Test No.: _______

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: ____100% power, EOL_________________________________________

Turnover: EDG B out of service for MTN PMs - expected back in six hours. TS 3.8.1 conditions A & B entered; STS NB-005, Breaker Alignment Verification has been completed

- due in seven hours.

MDAFW pump B tagged out/out of service for due to Emergent work (SM Concern).

Expected return is six hours. TS 3.7.5 condition B entered.

Event Malf. No. Event Event No. Type* Description 1 mBB22 I -- PZR level channel BB LI-459A failure high.

A ATC, OFN SB-008, Instrument Malfunctions, Attachment J t+2 SRO 2 bkrDPA R- Condensate pump A trip D01A ATC t+8 OFN AF-025, Unit Limitations, Attachment A C-BOP, OFN MA-038, Rapid Plant Shutdown SRO 3 ANN- M- All Seismic event followed by a Reactor trip occurs.

E098 EMG E-0, Reactor Trip or Safety Injection t+25 ANN-D099 This event series sets up the scenario for the Major event ANN- EMG FR-H1, Response to Loss of Secondary Heat Sink.

C098 mSF15A mSF15B

4 mNB01 (Post Reactor trip) NB01 & NB02 trip mNB02 t+25 mNE02 C -- (Post reactor trip) EDG A autostart feature disabled - manual A ATC, available SRO (CT - start EDG A in order to energize NB01 bus)

Recall NB02 bus unavailable because EDG B out of service as part of Turnover item.

5 mAL02 TDAFW pump trip (broken linkage) t+25 mtrDPA MDAFW pump A trip (shaft seizure)

L01A mBG13 CCP A trips due to overcurrent A

M- Loss of all Auxiliary Feedwater All EMG FR-H1, Response to Loss of Secondary Heat Sink (CT - Establish RCS bleed and feed before Steam Generators dry out)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Scenario summary:

Plant is at 100% power, End of life (EOL). Emergency Diesel Generator (EDG) B is tagged out/out of service for MTN - Preventative Maintenance (PM). Expected return is six hours.

Technical Specifications (TS) 3.8.1 condition A & B entered. STS NB-005, Breaker Alignment Verification, complete (due in seven hours).

Motor Drive Auxiliary Feedwater Pump (MDAFWP) B is tagged out/out of service for due to Emergent work (SM Concern). Expected return is six hours. Technical Specification 3.7.5 condition B entered.

Pressurizer (PZR) level (controlling) channel BB LI-459A fails high. Crew responds using OFN SB-008, Instrument Malfunctions, Attachment J.

• Attachment J: Select an alternate level channel as the controlling channel.

• Crew stabilizes the plant.

Condensate pump A trips. The crew responds by entering OFN AF-025, Unit Limitations.

Attachment A will require a downpower evolution.

Downpower guidance per OFN AF-025: If one condensate pump is lost, reduce power as necessary to maintain Main Feed Pump (MFP) suction pressure greater than 340 psig on AEP0006 for A MFP and AEP0005 for B MFP.

• Crew responds by performing a downpower.

• Crew stabilizes the plant.

A seismic event occurs resulting in an inadvertent reactor trip. EMG E-0, Reactor Trip or Safety Injection is entered. (Major event)

Post trip, both NB01 and NB02 busses trip. Due to the Maintenance PMs (see Turnover item),

Emergency Diesel Generator B will not start and load onto NB02 bus. Emergency Diesel Generator A must be manually started by the Control Room and then it will load onto NB01 bus.

As the scenario progresses, the Turbine Driven Auxiliary Feedwater Pump (TDAFW pump) trips due to broken linkage and the Motor Driven Auxiliary Feedwater Pump A will trip due to shaft seizure and BOTH cannot be restarted. Motor Driven Auxiliary Feedwater Pump B cannot be started (see Turnover item). No Auxiliary Feedwater (AFW) to the Steam Generators is available. Note that the running CCP (CCP A) trips off due to overcurrent.

The crew enters EMG FR-H1, Response to Loss of Secondary Heat Sink (Major event).

Mitigation strategy: the crew uses the Foldout page of EMG FR-H1, Bleed and Feed.

EMG FR-H1, Response to Loss of Secondary Heat Sink, Major Actions:

• Attempt restoration of RCS bleed and feed flow to the S/Gs

• Initiation of RCS bleed and feed heat removal

• Restore and verify secondary heat sink

• Termination of RCS bleed and feed heat removal

Scenario has two Critical Tasks (CT):

1. Starting the EDG A to re-energize NB01 bus

2. Establish RCS bleed and feed before Steam Generators (SG) dry out.

Probabilistic Risk Analysis for this scenario includes:

Top 10 Human Action Failures by the Importance Measure Rankings (Reference PSA-07-0001)

F-V RRW Total Event Name Description Point Est. F-V RAW RRW Birnbaum Rank Rank Rank FAILURE OF RCS COOL 4.89E-03 2.61E-02 6.32 1.027 9.64E-05 1 8 34 OPA-OD1-EXE DOWN &

DEPRESSURIZE -

SGR EVENT - EXE FAILURE OF RCS COOL 5.00E-02 2.49E-02 1.47 1.026 8.97E-06 2 39 OPA-OD2-EXE DOWN &

DEPRESSURIZE AFTER OVERFIL-EXE FAILURE TO ALIGN & 4.68E-03 2.45E-02 6.2 1.025 9.43E-05 3 9 40 OPA-RRI1-EXE START 1 SI OR CCP PUMP - EXE FAILURE TO 2.97E-02 2.40E-02 1.78 1.025 1.46E-05 4 41 ESTABLISH FEED &

OPA-OFB-EXE BLEED COOLING -

EXE Technical Specifications exercised:

Event 1: TS 3.3.1, Reactor Trip System Instrumentation, Table 3.3.1-1 FU 9 Cond A: Required function inoperable - enter condition per Table (immediately)

Cond M: One channel inoperable - place channel in trip (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />)

TS 3.3.4, Remote Shutdown Instruments, Table 3.3.4-1 FU 12 Minimum channels met - not action required TS 3.3.3. Accident Monitoring Instrumentation, Table 3.3.3-1, FU 11 Minimum channels met - no action required NOTE: Event 3: TR 3.3.11, Seismic Instrumentation. Because the reactor trip follows, this TR will probably not be determined.

Cond. A: Restore required seismic monitoring equipment to operable (24 hrs); perform a channel calibration (10 days), initiate action to analyze data (immediately)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 1 Page 1 of 19_

Event

Description:

PZR level channel BB LI-459 failure high BOOTH INSTRUCTIONS: Set up simulator in IC 50, RBU at 229, CWP enabled, Blue placard on A CCP. Run files etc.

When directed, INITIATE event 1 by activating KEY 1.

Indications available:

Meter BB LI-459 indication high 32D, PZR HI LEV DEV HTRS ON 83C, RX PARTIAL TRIP Bistable PZR HI WTR LEV LB459A Time Position Applicants Actions or Behavior CREW Respond to Main Control Board (MCB) alarms and board indications.

Actions taken prior to procedure entry may include: Identifies BB LI-459 failure, Select MANUAL on PZR LEVEL CONTROLLER (BB LK-459)

CREW Enters OFN SB-008, rev 25, Instrument Malfunctions CREW 1.Check if Secondary System instrument channel is malfunctioning.

a. Determine appropriate attachment for malfunctioning channel or controller

a. RNO: If secondary system channel is NOT malfunctioning, then go to step 2.

CREW 2. Check if RCS instrument channel or controller is malfunctioning

a. Determine appropriate attachment for malfunctioning channel or controller From Table below: BB LI-459, Go to Att. J, PZR Level Channel Malfunction

b. Go to appropriate attachment for malfunctioning RCS channel or controller

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 1 Page 2 of 19_

Event

Description:

PZR level channel BB LI-459 failure high Time Position Applicants Actions or Behavior RO J1. Identify failed instrument channel

a. Compare Pressurizer level indications to confirm a Pressurizer level Channel failure:

o BB LI-459A RO J2. Check failed Pressurizer level channel selected on PZR level control Selector switch.

o BB LS-459D RO J3. Select alternate Pressurizer level channel for level control.

o BB LS-459D NOTE Letdown flow is isolated and pressurizer control heaters are deenergized if the controlling level falls below 17%. Both must be d manually realigned once level control is re-established.

RO J4. Check letdown flow - ESTABLISHED

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 1 Page 3 of 19_

Event

Description:

PZR level channel BB LI-459 failure high Time Position Applicants Actions or Behavior RO J5. Manually control charging and letdown to stabilize Pressurizer level at level appropriate for plant power.

RO J6. Ensure PZR control heaters - ON RO J7. Place charging/letdown flow control in automatic RO J8. Monitor PZR level response to ensure proper control CRS J9. Check failed PZR level channel - NOT USED FOR RECORDER CRS J10. Monitor the following Technical Specification LCOs and comply with Action Statements as appropriate:

TS 3.3.1, Reactor Trip System Instrumentation, Table 3.3.1-1 FU 9 Cond A: Required function inoperable - enter condition per Table (immediately)

Cond M: One channel inoperable - place channel in trip (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />)

(TS 3.3.4, Remote Shutdown Instruments, Table 3.3.4-1 FU 12 Minimum channels met - not action required TS 3.3.3. Accident Monitoring Instrumentation, Table 3.3.3-1, FU 11 Minimum channels met - no action required)

Lead Examiner may direct initiation of the next event at his discretion

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 2 Page 4 of 19_

Event

Description:

Condensate pump A trip.

BOOTH INSTRUCTIONS: When directed, INITIATE event 2 by activating KEY 2.

Indications available:

AD HIS-1, CNDS Pump A, light indication change from RED to GREEN and AMBER (pump stopped / tripped)

AD FIK-7B, CNDS Pump A Recirc CTRL, from AUTO to MAN (0 % output to 100% output)

AD ZL-7B, CNDS Pump A Recirc Valve, light indication from GREEN to RED AD PI-25, CNDS Pumps Disch Press, indicates decreasing pressure ALR 00-107C, CNDS PMP SUCT STR P HI ALRs 00-120B / 123B, MFP A/B SUCT PRESS LO Time Position Applicants Actions or Behavior CREW Responds to MCB alarms and board indications. Identify A Condensate pump is tripped.

CREW Enters OFN AF-025, rev 27, Unit Limitations CRS 1.Determine applicable step:

a. Check Stator Cooling Water System - NORMAL

b. Check Generator Hydrogen System - NORMAL

c. Check Main Transformers - NORMAL

d. Check all the following transformers - NORMAL o Start-up transformer o XNB01 transformer o XNB02 transformer o Unit Auxiliary transformer

e. Check Condenser Vacuum - NORMAL

f. Go to step 7.

CRS 7. Check Westar Transmission Services (WETS) has reported an actual or predicted switchyard voltage degradation -- NO RNO: go to step 9

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 2 Page 5 of 19_

Event

Description:

Condensate pump A trip Time Position Applicants Actions or Behavior CRS 9. Check for conditions requiring Unit Load reduction:

a. Determine maximum unit load using Attachment A, Unit Load Limits

b. Reduce unit load, as necessary, to satisfy load limits using the appropriate procedure GEN 00-004, Power Operation OR GEN 00-005, Minimum Load to Hot Standby OR OFN MA-038, Rapid Plant Shutdown OR Attachment D, Turbine/Generator Load Decrease using Steam Dumps CRS Attachment A, Unit Load Limits, Feed & Condensate section:

Condition requiring load reduction Maximum Unit Load One Condensate pump out of service see NOTE (2) If one cond. pump is lost, reduce power as necessary to maintain MFP suction pressure greater than 340 psig on AEP0006 for A MFP and AEP0005 for B MFP.

BOOTH Cue: When contacted as Call Supt. recommends using OFN MA-038, Rapid Plant Shutdown.

If contacted as System OPS Generation or System Transmission, acknowledge Wolf Creek Turbine/Generator load reduction.

CREW OFN MA-038 rev 11, Rapid Plant Shutdown NOTES o Foldout page shall be monitored throughout this procedure o Steps 1-4 may be performed in any order.

o Load reduction at greater than 5% / minute will arm condenser steam dumps o When reducing load with Decrease Loading Rate on, the difference between load set and actual load should be less than 200MW. Prior to depressing the Hold or Off pushbuttons or establishing Load Limit control, ensure the At Set Load light is on to prevent an uncontrolled load decrease.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 2 Page 6 of 19_

Event

Description:

Condensate pump A trip Time Position Applicants Actions or Behavior CRS/BOP 1. () Reduce turbine load

a. Check desired unloading rate - 5% / minute

b. Place control valves in their operating range as necessary by slowly decreasing load limit pot until a 1-2 Mwe load decrease is noted

c. Slowly decrease Load Set MW until AT SET LOAD light is on and LOAD LIMIT LIMITING light extinguishes

d. Raise Load Limit pot slightly

e. Set Loading/Unloading Rate Limit to desired value and adjust as necessary during decrease to maintain desired rate

f. Select Decrease Loading Rate - ON

g. Decrease Load Set MW toward desired load

h. Continue with this procedure while reducing turbine load Booth Instructions / Cue:

If called as Work Week Manager (WWM), acknowledge request to repair A Condensate Pump & will form a team for the repairs. If asked, repairs shouldnt take more than a few hours.

CRS/RO 2. () Borate RCS and adjust control rods as necessary to maintain the following:

o Target Tavg/Tref temperature error between 0°F and 5°F o Control rods above the rod insertion limits RO 3. Energize PZR backup heaters BOP 4. () Check AE HV Open AE HIS-38 CLOSED

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 2 Page 7 of 19_

Event

Description:

Condensate pump A trip Time Position Applicants Actions or Behavior RO 5. Check PZR PORVs:

a. RCS pressure - < 2335 psig

b. PZR PORVs - CLOSED

c. RCS pressure - > 2185 psig

d. PORV block valves - OPEN RO 6. Check PZR pressure - stable at or trending to 2235 psig RO 7. Check PZR level - stable at or trending to program level BOP 8. Check SG levels - controlling between 45% and 55%

CRS 9. Check reactor power - less than 60% -- NO, perform RNO RNO:

a. If final desired power level is greater than or equal to 60% then go to step 35

b. If final desired power level is less than 60% then do not continue until reactor power is less than 60%

Lead Examiner may direct initiation of the next event at his discretion.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 3 Page 8 of 19_

Event

Description:

Seismic event and reactor trip BOOTH INSTRUCTIONS: When directed, INITIATE event 3 by activating KEY 3, inserting seismic event and inadvertent reactor trip Indications available:

MCB alarms --

98E, SEISMIC RECORDER ON 98D, OBE 98C, R SPCTRM OBE EXCEED 98B, SSE Reactor trip occurs Time Position Applicants Actions or Behavior CREW Respond to MCB indications.

CREW OFN SG-003 rev 15, Natural Events.

CRS Directs OFN SG-003 rev 15, Natural Events CRS 1. Determine appropriated attachment for Natural Event:

Attachment A, Earthquake Response CRS 2. Go to appropriate attachment CRS Directs Attachment A, Earthquake Response CRS A1. Check EQ magnitude - GREAT ENOUGH TO START SEISMIC RECORDER NOTE: Reactor trip occurs. The CREW may not actually enter OFN SG-003, Natural Events.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 3 Page 9 of 19_

Event

Description:

Seismic event and reactor trip Time Position Applicants Actions or Behavior CREW Enters EMG E-0, rev 21, Reactor trip or Safety Injection FOLDOUT PAGE FOR EMG E-0

1. RCP TRIP CRITERIA IF all conditions listed below occur, THEN trip all RCPs:

o RCS pressure - LESS THAN 1400 PSIG o CCPs or SI pumps - AT LEAST ONE RUNNING o Operator controlled cooldown - NOT IN PROGRESS

2. SI ACTUATION CRITERIA IF either condition listed below occurs, THEN actuate SI and go to EMG E-0, REACTOR TRIP OR SAFETY INJECTION, Step 1:

RCS subcooling - LESS THAN 30°F [45°F]

OR Pressurizer level - CANNOT BE MAINTAINED GREATER THAN 6% [33%]

3. FAULTED S/G ISOLATION CRITERIA IF any S/G pressure decreasing in an uncontrolled manner OR any S/G completely depressurized, THEN the following may be performed:

a. Close main steam isolation valves.

b. Isolate feed flow to faulted S/G(s).

c. Maintain total feed flow greater than 270,000 lbm/hr until narrow range level in at least one S/G is greater than 6% [29%].

4. RUPTURED S/G ISOLATION CRITERIA IF any S/G level increases in an uncontrolled manner OR any S/G has abnormal radiation, AND narrow range level in affected S/G(s) is greater than 6% [29%], THEN the following may be performed.

a. Close ruptured S/G AFW flow control valves.

b. IF any ruptured S/G AFW flow control valve cannot be closed AND total AFW flow to intact S/Gs can be maintained greater than 270,000 lbm/hr without associated AFW Pump, THEN perform the following:

1) Stop associated MD AFWP and place in PTL OR decrease TDAFWP speed to 2000 rpm.

2) Dispatch an Operator to locally isolate affected AFW flow control valve.

3) WHEN affected AFW flow control valve is isolated, THEN restart MD AFWP OR Restore TD AFWP speed as necessary.

5. COLD LEG RECIRCULATION CRITERIA IF RWST level decreases to less than 36%, THEN go to EMG ES-12, TRANSFER TO COLD LEG RECIRCULATION, Step 1.

6. AFW SUPPLY SWITCHOVER CRITERIA IF CST suction pressure decreases to less than 2.6 psig, THEN switch to alternate AFW suction supply.

CAUTION:

Accident conditions can cause higher than normal radiation levels. Health Physics monitoring may be required while performing local operator actions.

NOTES o Steps 1 through 4 are immediate action steps.

o Foldout page shall be monitored throughout this procedure.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 4 Page 10 of 19_

Event

Description:

NB01 & NB02 trip. EDG A autostart feature disabled - manual start available.

Time Position Applicants Actions or Behavior BOOTH INSTRUCTIONS: Event 4 is preloaded (EDG A autostart feature disabled) and uses Key 3 with a 9 second delay (NB01 and NB02 trip).

INDICATIONS: Various MCB alarms No WHITE light LIT, NB ZL-5, 4.16 KV bus NB01 No WHITE light LIT, NB ZL-6, 4.16 KV bus NB02 CRS Directs EMG E-0, rev 21, Reactor Trip or Safety Injection RO 1. Verify Rx trip.

a. Check all rod bottom lights lit

b. Ensure reactor trip breakers and bypass breakers open

c. Check neutron flux decreasing BOP 2. Verify turbine trip.

a. Check the following:

Main Stop valves - all closed OR Turbine auto stop bistable light - at least two lit RO 3. Check AC emergency busses - at least one energized NB01 voltage- normal NB02 voltage - normal CT - Start EDG A in order to energize NB01 busImmediate Action (EMG E-0 step 3 RNO)

NB01 & NB02 trip. EDG A autostart feature disabled - manual start available Recall: NB02 bus unavailable because EDG B out of service as part of Turnover item

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 4 Page 11 of 19_

Event

Description:

NB01 & NB02 trip. EDG A autostart feature disabled - manual start available.

Time Position Applicants Actions or Behavior RO 3.RNO Perform the following: (CT - Start EDG A in order to energize NB01 bus)

a. Depress the Start/reset pushbutton for any stopped Diesel Generator o KJ HS-8A for EDG A o KJ HS-108A for EDG B

b. If at least one AC emergency bus is now energized, then go to step 4.

c. Direct operator to monitor Critical Safety Functions for information only using EMG F-0, Critical Safety Function Status Trees (CSFST).

d. Go to EMG C-0, Loss of all AC Power, step 1 NOTE: Bus NB01 is energized by the EDG A once the CR starts the EDG.

RO 4. Check if Safety Injection is actuated:

a. Check any indication SI is actuated - lit Ann. 00-030A/00-0031A, NF039A/B LOCA SEQ ACTUATED - lit OR ESFAS status panel SIS section - any white lights lit OR Partial trip status Permissive / Block status panel - SI red light lit

b. Check both trains of SI actuated o Ann. 00-030A/00-031A, NF039A/B LOCA SEQ ACTUATED - lit RNO Perform the following:

1. Check SI required:

RCS pressure 1830 psig OR Any SG 615 psig OR CTMT pressure 3.5 psig OR

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 3 Page 12 of 19_

Event

Description:

Time Position Applicants Actions or Behavior RO RNO 1 cont.

RCS subcooling < 30°F OR PZR level < 6%

2. If SI is required, then manually actuate SI and go to step 6.

3. If SI is not required, then perform the following:

a. Direct operator to monitor CSF using EMG F-0, Critical Safety Function Status Trees.

b. Go to EMG ES-02, Reactor Trip Response, step 1 CAUTION If offsite power is lost after SI reset, manual action may be required to restore safeguards equipment to the required configuration.

CREW 5. Check if SI is required:

SI was manually actuated AND was required OR RCS pressure is currently or has been 1830 psig OR Any S/G pressure is currently or has been 615 psig OR CTMT pressure is currently or has been 3.5 psig OR RCS subcooling is currently or has been < 30°F PZR level is currently or has been < 6%

BOP 6. Check Main Generator breakers & Exciter breaker - open o MA ZL-3A and 4A o MB ZL-2 CRS 7. Verify automatic actions using Attachment F, Automatic Signal Verification

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 3 Page 13 of 19_

Event

Description:

Time Position Applicants Actions or Behavior CRS Directs EMG Attachment, F, Automatic Signal Verification RO/BOP EMG Attachment, F, Automatic Signal Verification F1. Verify feedwater isolation F2. Verify CISA F3. Verify AFW pumps running

a. Check motor driven AFW pumps - both running

b. Check turbine driven AFW pump - running F4. Verify ECCS pumps running F5. Verify CCW alignment F6. Check ESW pumps both running F7. Check CTMT fan coolers running in slow speed F8. Verify CPIS F9. Verify CRVIS F10. Verify main steamline isolation not required F11. Verify CTMT spray not required F12. Verify ECCS flow F13. Verify AFW valve alignment.

F14. Verify SI valves Properly aligned F15. Check if NCP should be stopped F16. Return to procedure & step in effect

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: Event No.: 5 Page 14 of 19 Event

Description:

Loss of all Auxiliary Feedwater TDAFW pump trip (broken linkage), MDAFW pump A trip (shaft seizure) and CCP A pump trip.

Time Position Applicants Actions or Behavior BOOTH INSTRUCTIONS / Cue: Event 5 failures are preloaded BOP 8. Check AFW flow > 270,000 lbm/hr - No Perform RNO RNO:

a. If SG narrow range level in at least one SG is > 6%, then control feed flow to maintain narrow range and go to step 9

b. manually start pumps and align valves as necessary to establish >

270,000 lbm/hr AFW flow

c. If total AFW flow > 270,000 lb/m can not be established, then perform the following:

1. Direct operator to monitor Critical Safety Functions using EMG F-0, Critical Safety Function Status Trees (CSFST)

2. Ensure BIT inlet and outlet valves are open o EM HIS-8803A o EM HIS-8803B o EM HIS-8801A o EM HIS-8801B

3. Continue with Attachment F and go to EMG FR-H1, Response to Loss of Secondary Heat Sink, step 1 BOOTH Cue: If contacted as Building watches to investigate pump trips, respond: I will investigate.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 5 Page 15 of 19_

Event

Description:

Loss of all Auxiliary Feedwater TDAFW pump trip (broken linkage), MDAFW pump A trip (shaft seizure) and CCP A pump trip.

Time Position Applicants Actions or Behavior MCB ALARM INDICATIONS:

128A, AFP DISCH PRESS LO; 128E, TDAFP SPD HILO; 129A, MDAFP A TROUBLE; 42E, CHARGING PMP TROUBLE CRS Directs EMG FR-H1, rev 19A, Response to Loss of Secondary Heat Sink CAUTIONS o If total feed flow is less than 270,000 lbm/hr due to operator action, this procedure shall not be performed.

o If a non-faulted S/G is available, feed flow shall not be reestablished to any faulted S/G.

NOTE: Foldout page shall be monitored throughout this procedure.

FOLDOUT PAGE FOR EMG FR-H1

1. BLEED AND FEED CRITERIA IF RCS bleed and feed has NOT been established AND RCS pressure is greater than any non-faulted S/G pressure AND any condition listed below occurs, THEN OBSERVE CAUTION PRIOR TO STEP 29 and go to Step 29.

Wide range level in any 3 S/Gs - LESS THAN 26% [47%]

OR RCS pressure - GREATER THAN 2335 PSIG DUE TO LOSS OF SECONDARY HEAT SINK OR CCPs - NONE AVAILABLE

2. COLD LEG RECIRCULATION CRITERIA IF RWST level decreases to less than 36%, THEN go to EMG ES-12, TRANSFER TO COLD LEG RECIRCULATION, Step 1.

3. AFW SUPPLY SWITCHOVER CRITERIA IF CST suction pressure decreases to less than 2.6 psig, THEN switch to alternate AFW suction supply.

BOOTH Cue: If dispatched to investigate CCP A pump trip, report: I will investigate.

If dispatched to CCP pump breaker, report an Overcurrent flag is dropped.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 5 Page 16 of 19_

Event

Description:

Loss of Auxiliary Feedwater (AFW)

Time Position Applicants Actions or Behavior CRS 1. Check if Secondary heat sink is required

a. RCS pressure - > any non-faulted S/G pressure

b. RCS hot leg temp - > 350°F CREW 2. Verify RCS Bleed and Feed - not required

a. Check WR level in all S/Gs - 26% [47%]

b. Check RCS press - 2335 psig RO 3. Check CCP status - at least one available RNO: Observe CAUTION prior to step 29 and go to step 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 5 Page 17 of 19_

Event

Description:

Loss of Auxiliary Feedwater.

Time Position Applicants Actions or Behavior CAUTION:

Steps 29 through 33 must be performed quickly in order to establish heat removal by RCS bleed and feed.

RO 29. Reduce heat input to RCS

a. Stop all RCPs o BB HIS-37 for RCP A o BB HIS-38 for RCP B o BB HIS-39 for RCP C o BB HIS-40 for RCP D

b. Turn off all PZR heaters o BB HIS-50 o BB HIS-51A o BB HIS-52A RO 30. Actuate SI o SB HS-27 o SB HS-28 CRS 31. Verify ECCS feed path

a. Check high pressure ECCS pumps CCPs - at least one running OR SI pumps - at least one running

b. Verify SI feed path alignment:

Check CCP to BIT flow meters - flow indicated OR o EM FI-917A o EM FI-917B

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 5 Page 18 of 19_

Event

Description:

Loss of Auxiliary Feedwater Time Position Applicants Actions or Behavior CRS 31b cont.

Check SI pump discharge flow meters - flow indicated OR o EM FI-918 o EM FI-922 Check ESFAS status SIS section - System level white lights all lit o Red train o Yellow train CREW 32. Establish RCS bleed path:

a. Check power to block valves - AVAILABLE o BB HIS-8000A o BB HIS-8000B

b. Place both cold overpressure Block/Arm switch in ARM position o BB HS-8000A o BB HS-8000B

c. Check PZR PORV block valves - BOTH OPEN (CT - Establish RCS bleed and feed before Steam Generators dry out)

d. Open both PZR PORVs o BB HIS-455A o BB HIS-456A CREW 33. Verify adequate RCS bleed path:

o PZR PORV block valves - both open o PZR PORVs - both open CRS 34. Perform steps 1-7 of EMG E-0, Reactor Trip or Safety Injection, while continuing with this procedure.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 5 Page 19 of 19_

Event

Description:

Loss of Auxiliary Feedwater Time Position Applicants Actions or Behavior CRS 35. Maintain RCS heat removal:

o Maintain ECCS flow to RCS o Maintain PZR PORVs - Both OPEN CAUTION:

If offsite power is lost after SI reset, manual action may be required to restore safeguards equipment to the required configuration.

RO 36. Reset SI o SB HS-42A o SB HS-43A RO 37. Reset Containment Isolation Phase A and Phase B o SB HS-56 for phase A o SB HS-53 for phase A o SB HS-55 for phase B o SB HS-52 for phase B BOP 38. Establish Instrument Air to Containment CRS 39. Continue attempts to establish Secondary heat sink in at least one SG When Bleed and Feed is established, Lead Examiner may terminate scenario at his discretion.

Appendix D Scenario Outline Form ES-D-1 Facility: __Wolf Creek________________ Scenario No.: ___4____ Op-Test No.: _______

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: 68% power Turnover: Load reduction in progress per GEN 00-004, Power Operations, section 6.2, in order to remove A Main Feed pump from service due to high vibration.

Use SYS AE-320, Turbine Driven Main Feedwater Pump Shutdown.

Event Malf. Event Event No. No. Type* Description 1 R- Reduce power using GEN 00-004, Power Operations and ATC remove A Main Feed Pump from service using SYS AE-t+1 320, Turbine Driven Main Feedwater Pump Shutdown N- (crew may reference / enter OFN AF-025, Unit Limitations, BOP, also)

SRO 2 mBB23 I- Pressurizer Spray valve (BB PCV-455B) fails open because A ATC, PZR Spray Controller BB PK-455B fails high - manual t+15 SRO control available OFN SB-008, Instrument Malfunctions, Attachment V 3 mAE15 I -- S/G C level AE LI-553 failure high C4 BOP, OFN SB-008, Instrument Malfunctions, Attachment F t+20 SRO ALR 00-110C, SG C Flow Mismatch ALR 00-110B, SG C Lev Dev 4 mBG13 C -- Normal Charging Pump (NCP) trip; a Centrifugal Charging C ATC, Pump must be started, letdown restored etc t+27 SRO ALR 00-042A, Charging Line Flow HiLo (SYS BG-120, CVCS Startup or SYS BG-201, Shifting Charging Pumps -

either may be used to restore letdown)

ALR 00-042E, Charging Pump Trouble (Step 7 re-establishes letdown) 5 mBB02 M -- All 500 gpm Steam Generator Tube Rupture on S/G A B OFN BB-07A, Steam Generator Tube Leakage (eventually t+35 EMG E-0, Reactor Trip or Safety Injection & EMG E-3, Steam Generator Tube Rupture)

5 EMG E-3, Steam Generator Tube Rupture actions:

CT - Isolate feed flow to the ruptured SG.

CT - Cooldown & Depressurize RCS to meet the following SI termination criteria before the end of the scenario.

• RCS subcooling greater than 30°F

• RCS pressure - stable or increasing

• PZR level greater than 6%

6 mSA27 C- Post trip: BIT outlet valves (EM HIS-8801A and EM HIS-EM01 ATC, 8801B) do not open. Manual open available t+43 and SRO mSA27 CT - Open BIT outlet valves (EM HIS-8801A and EM EM02 HIS-8801B) before the end of the scenario or before needless red or orange path occurs.

EMG E-0, Reactor Trip or Safety Injection, Attachment F or allowed post Immediate Action completion

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Scenario summary Plant is at 68% power with a load reduction in progress to remove A Main Feed Pump (MFP) from service due to high vibration. GEN 00-004, Power Operations, section 6.2 in progress for load reduction. Crew will use SYS AE-320, Turbine Driven Main Feedwater Pump Shutdown, to remove A MFP from service.

Crew reduces power per GEN 00-004, Power Operations, section 6.2, Power Decrease. Crew may reference OFN AF-025, Unit Limitations, Attachment A (one main feedwater pump from service requires plant at 62% power). Crew removes A MFP from service using SYS AE-320, Turbine Driven Main Feedwater Pump Shutdown (see step 6.2.12 of GEN 00-004).

• Crew stabilizes unit at lower power and removes pump from service.

Pressurizer (PZR) Spray Valve BB PCV-455B fails open due to PZR Spray Controller BB PK-455B failure (high). Manual control of BB PK-455B available.

• Crew responds by performing OFN SB-008, Instrument Malfunctions, Attachment V.

• Crew stabilizes the plant.

Steam Generator (S/G) C level channel AE LI-553 failure high. Crew responds by performing OFN SB-008, Instrument Malfunctions, Attachment F. An alternate level channel is selected for control.

• ALR 00-110C, SG C Flow Mismatch or ALR 00-110B, SG C Lev Dev, may be used prior to entry of OFN SB-008, Instrument Malfunctions.

• Crew stabilizes the plant.

Normal Charging Pump (NCP) trip. Crew responds using ALR guidance. A Centrifugal Charging Pump is started. Normal letdown must be restored (either using ALR guidance or SYS BG-120, CVCS Startup or SYS BG-201, Shifting Charging Pumps).

• ALR 00-042A, Charging Line Flow HiLo

• ALR 00-042E, Charging Pump Trouble

• Crew stabilizes the plant.

Major event: A 500 gpm Steam Generator Tube Rupture (SGTR) on S/G A is diagnosed per OFN BB-07A, Steam Generator Tube Leakage.

SGTR requiring a manual Reactor trip and Safety Injection Signal actuation per Foldout page criteria of OFN BB-07A. Mitigation procedure will be EMG E-3, Steam Generator Tube Rupture.

1. Crew responds using OFN BB-07A, Steam Generator Tube Leakage.

2. Crew responds using EMG E-0, Reactor Trip or Safety Injection.

3. Crew responds using EMG E-3, Steam Generator Tube Rupture.

EMG E-3, Steam Generator Tube Rupture, Major Actions:

a. Identify and isolate ruptured S/Gs

b. Cooldown and establish RCS subcooling margin

c. Depressurize RCS to restore inventory

d. Terminate SI to stop primary to secondary leakage

e. Prepare for cooldown to cold shutdown Scenario has three Critical Tasks (CT):

1. Open BIT outlet valves EM HIS-8801A & EM HIS-8801B

2. Crew isolates feed flow to ruptured steam generator.

3. Cooldown and Depressurize the RCS to meet Safety Injection termination criteria using EMG E-3, Steam Generator Tube Rupture

-- RCS subcooling greater than 30°F

-- RCS pressure stable or increasing

-- PZR level greater than 6%

Probabilistic Risk Analysis for this scenario includes:

Top 10 Human Action Failures by the Importance Measure Rankings F-V rank 1 Failure of RCS Cooldown & Depressurize - SGR event Core Damage Frequency by Initiating Event and by Event Tree and by Larger Early Release Frequency Consequence Steam Generator Tube Rupture Technical Specifications exercised:

Event 3 TS 3.3.1, Reactor Trip System Instrumentation, Table 3.3.1-1, FU 14 Cond A: Function / channel inoperable - enter condition per table (immediately)

Cond E: One channel inoperable - place channel in trip (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />)

TS 3.3.2, Engineered Safety Features Actuation System Instrumentation, table 3.3.2-1, FU 5c and 6d Cond A: Function / channel inoperable - enter condition per table (immediately)

Cond D: One channel inoperable - place channel in trip (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />)

Cond I: One channel inoperable - place channel in trip (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />)

NOTE: Event 4 TR 3.1.9, Boron Injection System - Operating -- may be looked at

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: _1____ Page __1_ of _38__

Event

Description:

Reduce power using GEN 00-004, Power Operations and remove A Main Feed Pump from service using SYS AE-320, Turbine Driven Main Feedwater Pump Shutdown Time Position Applicants Actions or Behavior CREW Using Gen 00-004, rev 60, Power Operations, section 6.2.2.2, continue power reduction.

BOP 6.2.2.2 If MTC is negative or zero, then perform the following:

a. If automatic Turbine unloading is desired, then control turbine load using automatic turbine-generator unloading selected to 1/2% per minute OR as directed by SM/CRS.

b. If automatic Turbine unloading is NOT desired, then perform Turbine load decrease using load limit potentiometer or the standby potentiometer in a slow controlled manner.

c. () Adjust control rods as necessary to maintain Tavg within 1.5°F of Tref.

CRS/RO 6.2.3 () During power reduction, use boration, dilution, or control rods, as necessary, to maintain the axial flux difference within the target band and control rods above the rod insertion limit.

CRS/RO 6.2.4 Ensure AE HV-38, HP FW HEATERS BYPASS VALVE, is closed using SYS AE-125, HP FW HEATER BYPASS THROTTLING OPERATIONS.

CRS/RO 6.2.5 Ensure one set of PZR backup heaters is energized.

CRS/RO 6.2.6 If desired and RCS will be taken solid, then place PZR LEV MASTER CTRL in manual and maintain level between program and 57%.

NA - not desired

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: _1____ Page 2 of 38 Event

Description:

Reduce power using GEN 00-004, Power Operations and remove A Main Feed Pump from service using SYS AE-320, Turbine Driven Main Feedwater Pump Shutdown Time Position Applicants Actions or Behavior CRS/BOP 6.2.7 If automatic Turbine unloading is desired, then place EHC control on load set as follows:

1. () If desired to position Control Valves in their controlling range, then slowly decrease load limit pot until a 1-2 Mwe load decrease is noted.

2. Slowly decrease load set MW until the following conditions are met:

o At set load light - lit AND o Load limit limiting light - NOT LIT

3. Raise load limit pot slightly.

4. Select 1/2% / minute loading rate.

5. Select decrease loading rate - ON CRS/BOP 6.2.8 () Decrease Turbine load as desired while continuing with this procedure CRS 6.2.9 Ensure Chemistry is promptly notified of each power change that is greater than or equal to 15% RTP within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period so that RCS DEI can be verified to satisfy SR 3.4.16.2.

CRS 6.2.10 When SM or CRS desires to stop one heater drain pump, THEN stop one heater drain pump using SYS AF-121, HEATER DRAIN PUMP OPERATION. NA - not desired to remove a Heater Drain Tank pump.

CRS 6.2.11 If operating with a positive MTC and reactor power is less than 65%, then open Steam Dumps as follows: NA - operating with a negative MTC NOTE: When 60%, Crew should secure the Main feedwater Pump A per GEN 00-004, step 6.2.12.2 CRS 6.2.12.2. If two Main Feedwater Pumps are running, then secure one using SYS AE-320, Turbine Driven Main feedwater Pump Shutdown

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: _1____ Page 3 of 38 Event

Description:

Reduce power using GEN 00-004, Power Operations and remove A Main Feed Pump from service using SYS AE-320, Turbine Driven Main Feedwater Pump Shutdown Time Position Applicants Actions or Behavior CRS/CREW SYS AE-320, (rev 20), Turbine Driven Main feedwater Pump Shutdown, section 6.1 CAUTION: If a secondary cooldown is in progress, ensure a flowpath for feed to SGs can be maintained.

NOTE: At 62% power, two MFPs at 4400 rpm will equate to one MFP at 5400 rpm.

BOP 6.1.1 Place MFP turb A speed control in manual.

o FC SK-509B - MANUAL CAUTION: Monitor feedwater flow and SG levels, during performance of the following steps.

BOP 6.1.2 Place MFP A recirc ctrl valve in manual and open o FC FIC-2B - MANUAL AND o FC SI-2B - OPEN BOP 6.1.3 Slowly decrease MFP turb A speed ctrl to 3500 rpm o FC SK-509C - OUTPUT DECREASED o FC SI 3800 rpm BOP 6.1.4 Adjust MFP turb A man speed ctrl pot, to achieve a zero indication on MFP Turb A man/auto sig match o FC HK SETTING ADJUSTED o FC EI ZERO

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: ___1__ Page _4_ of 38_

Event

Description:

Remove A Main Feed Pump from service using SYS AE-320, Turbine Driven Main Feedwater Pump Shutdown Time Position Applicants Actions or Behavior BOP 6.1.5 Depress MFP turb A speed ctrl transfer switch manual pushbutton o FC HIS manual BOP 6.1.6 Slowly decrease MFP turb A man speed ctrl pot to 1100 rpm o FC HK SETTING DECREASED o FC SI 1100 rpm NOTE: ESFAS should not be blocked, unless both Main feedwater pumps are being secured.

BOP 6.1.7. To prevent a spurious AFW system actuation, ensure one of the following Conditions is met:

MFP turb B trip/test switch is reset o FC HIS-118 - RESET Ensure AFP ESFAS block train A & B switches are in the block position o FC HS BLOCK o FC HS BLOCK BOP 6.1.8 Depress MFP turb A trip/reset switch trip pushbutton o FC HIS TRIPPED BOP 6.1.9 Ensure MFP A disch vlv closes o AE HIS CLOSED

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: _1____ Page _5_ of _38 Event

Description:

Remove A Main Feed Pump from service using SYS AE-320, Turbine Driven Main Feedwater Pump Shutdown Time Position Applicants Actions or Behavior BOP 6.1.10 Close MFP A recirc ctrl valve o AE FIC-2B - CLOSED BOP 6.1.11 When MFP A coasts down to zero speed, then ensure MFP turb A Turn gear engage light illuminated o FC ZL-82A - LIT BOP 6.1.12 Open the following MFP turbine A drains:

1. MFP turb A 1st stg S/U drn vlv o FC HIS OPEN

2. MFP turb A HPSV above seat drn valve o FC HIS OPEN

3. MFP turb A HPSV below seat drn valve o FC HIS OPEN BOP 6.1.13 Open MFP A disch valve o AE HIS OPEN BOP 6.1.14 If MFP A will be shutdown for a prolonged period, then close the Following valves, to prevent seal water flow from overfilling the Miscellaneous Condensate Drain Tank:

1. SG FWP A seal water supply reg vlv PDV-58 inlet iso vlv o AE-V995 - CLOSED

2. SG FWP A seal water supply reg vlv PDV-58 bypass vlv o AE-V994 - CLOSED

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: _1____ Page _6__ of _38 Event

Description:

Remove A Main Feed Pump from service using SYS AE-320, Turbine Driven Main Feedwater Pump Shutdown Time Position Applicants Actions or Behavior BOOTH CUE: If called as building watch to close valves AE-V995 and AE-V994, report back in a four minutes that the valves are closed. These valves are not modeled.

BOP 6.1.15 If desired to secure MFP A lube oil system, then perform section 6.3, Shutdown of MFP A lube oil system.

CREW Section 6.1. Shutdown of Main Feedwater Pump A, complete.

BOOTH CUE: If called as Call Supt./WWM, the MFP A lube oil system does not need to be shutdown.

When Main Feedwater Pump A is shutdown and At Lead evaluator direction, activate Event 2 by inserting KEY 1.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: _2____ Page __7_ of _38 Event

Description:

Pressurizer Spray Controller BB PK-455B fails high in automatic (PZR spray valve BB PCV-455B fails open). Manual control of BB PK-455B is available.

Time Position Applicants Actions or Behavior INDICATIONS: RCS pressure decreases when Spray valve opens BB PK-455B meter indication increasing BB ZL-455B light indication goes from Red & green dual indication to Red indication only CRS/RO Actions may be taken before procedure entry: Identify failed instrument; Place controller in Manual (BB PK-455B or BB PK-455A)

CREW Enters OFN SB-008, rev 25, Instrument Malfunctions CRS 1. Check if Secondary system instrument channel is malfunctioning

a. Determine appropriate attachment for malfunctioning channel from table below RNOa. If secondary system channel is not malfunctioning, then go to step 2

CRS/RO 2. Check if RCS instrument channel or controller is malfunctioning:

a. Determine appropriate attachment for malfunctioning channel or controller from table below:

Variable Channels Attachment PZR Spray Controller BB PK-455B/BB PK-455C Attachment V

b. Go to appropriate attachment for malfunctioning RCS system channel or controller

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: _2____ Page __8_ of 38 Event

Description:

Pressurizer Spray Controller BB PK-455B fails high in automatic (PZR spray valve BB PCV-455B fails open). Manual control of BB PK-455B is available.

Time Position Applicants Actions or Behavior CREW Performs OFN SB-008, Attachment V, PZR Pressure Controller Failure RO V1. Check PZR spray valve(s) - failed open BB ZL-455B BB ZL-455C NOTE:

If I&C is not available or there is not sufficient time Control Room personnel will need to pull the card in RP043. A screwdriver will be needed to pull the card.

RO V2. Place affected PZR spray controller or PZR pressure master controller in manual and control spray flow:

BB PK-455B BB PK-455C BB PK-455A CREW V3. Go to step 9 CRS V9. Direct I&C to determine and correct cause of malfunction.

CRS V10. Return to procedure and step in effect.

BOOTH CUE: If contacted as WWM, respond I will assemble a team.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: _3____ Page _9__ of 38 Event

Description:

S/G C level AE LI-553 failure high.

Time Position Applicants Actions or Behavior BOOTH INSTRUCTIONS: At Lead Examiner discretion, initiate Event 3 by activating Key 2.

INDICATIONS:

Meter indication AE LI-553 increasing.

Alarm 00-110C, SG C Flow Mismatch Alarm 00-110B, SG C Lev Dev CRS/BOP Actions may be taken before procedure entry: Identify failed instrument, AE LI-533 failure; Place MFW Reg Valve in Manual (AE FK-530) and match steam and feed flow.

CREW May enter ALR 00-110B, or go directly to OFN SB-008, rev 25, Instrument Malfunctions CRS/CREW ALR 00-110B, rev 007, SG C Lev Dev

1. Check SG C controlling level channel 5% > program level OR 5% < program level

2. Check instruments - operating properly:

o SG C controlling channel - within 6% of remaining SG C narrow range level channels AE LI-539 AE LI-553 RNO: Perform the following:

a. Place Feedwater Reg Valve (FRV) or Feedwater Reg Bypass Control Valve (FRBV) in manual AE FK-530 AE LK-570

b. Adjust FRV or FRBV as necessary to establish SG level at program value AE FK-530 AE LK-570

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: __3___ Page _10__ of 38 Event

Description:

S/G C level AE LI-553 failure high.

Time Position Applicants Actions or Behavior 2RNOc. Select alternate channel for control AE LS-539C for level AE FS-530C for feed flow AB FS-532C for steam flow BOP 2RNOd. Return FRV or FRBV to automatic AE FK-530 AB LK-570 2RNOe. GO to OFN SB-008, Instrument Malfunctions CRS/CREW Enters OFN SB-008, Instrument Malfunctions (rev 25)

BOP 1. Check if Secondary System instrument channel is malfunctioning:

a. Determine appropriate attachment for malfunctioning channel from table below:

VARIABLE CHANNELS ATTACHMENT Steam level (AE) L-553 Attachment F CRS Directs Attachment F, SG Level Channel Malfunction BOP F1. Identify failed narrow range SG level instrument channel:

a. Compare narrow range SG level indication to confirm a narrow range SG level channel failure o SG C:

AE-LI-537 AE LI-538 AE LI-539 AE LI-553

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: _3____ Page _11__ of _38 Event

Description:

S/G C level AE LI-553 failure high.

Time Position Applicants Actions or Behavior BOP F2. Check failed SG level channel selected on level selector switch AE LS-539C (others are also listed in the procedure), RNO F2.

Go to Step F7 NOTE: If crew performed the ALR first, it may alter how they proceed through the OFN attachment.

BOP F3. Place affected SG feed reg control valve - in manual AE FK-530 (other FRVs are listed in the procedure)

BOP F4. Adjust affected feedwater reg valve, as necessary, to establish SG level at program (AE FK-530)

BOP F5. Select alternate SG level channel for feedwater control AS LS-539C CRS F6. Restore affected SG feed reg valve controller to - AUTO BOOTH Cue: If called as Call Sup /WWM, respond: I will assemble a team.

CRS F7. Monitor the following TS for LCOs and comply with appropriate action statements as appropriate:

TS 3.3.1, Reactor Trip System Instrumentation, Table 3.3.1-1, FU 14 Cond A: Function / channel inoperable - enter condition per table (immediately)

Cond E: One channel inoperable - place channel in trip (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />)

TS 3.3.2, Engineered Safety Features Actuation System Instrumentation, table 3.3.2-1, FU 5c and 6d Cond A: Function / channel inoperable - enter condition per table (immediately)

Cond D: One channel inoperable - place channel in trip (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />)

Cond I: One channel inoperable - place channel in trip (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />)

BOOTH INSTRUCTIONS: At Lead examiner discretion, initiate Event 4 by activating Key 3.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: _4____ Page _12_ of _38 Event

Description:

Normal Charging Pump (NCP) trip. (ALR 00-042A, rev 13, CHG LINE FLOW HILO)

Time Position Applicants Actions or Behavior INDICATIONS:

NCP indication (BG HIS-3) goes from Red light lit to Green light lit Various MCB Alarms actuate:

00-042A, Charging Line Flow HiLo and 00-042E Charging Pump trouble 00-041A, Seal Inj to RCP Flow Lo and 00-038A, LTDN Regen HX Temp Hi BOOTH Cue: If dispatched to investigate NCP trip, respond: I will investigate. If dispatched to NCP breaker, respond: Overcurrent flag is tripped.

If contacted as WWM, respond : I will assemble a team.

If contacted as Electrical Maintenance (MTN): I will assemble a team.overcurrent flag is dropped.

CRS Enters and directs ALR 00-042A, rev 013, Charging Line Flow HiLo CRS/RO 1. Check charging header flow - > 150gpm o BG FI-121A, RNO1. Go to step 5.

CRS/RO 5. Check charging header flow - < 45 gpm o BG FI-121A CAUTION:

If gas binding or pumps is suspected, performance of OFN BG-045, Gas Binding of CCPs or SI Pumps, should be considered.

6. Check charging pumps - ANY RUNNING CRS/RO BG HIS-1A for CCP A BG HIS-2A for CCP B BG HIS-3 for NCP RNO6. Perform the following:

6RNOa. Close letdown orifice isolation valves o BG HIS-8149AA o BG HIS-8149BA o BG HIS-8149CA 6RNOb. Start any available charging pump BG HIS-1A for CCP A BG HIS-2A for CCP B BG HIS-3 for NCP

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: __4___ Page _13 of _38 Event

Description:

Normal Charging Pump (NCP) trip.

Time Position Applicants Actions or Behavior RO 7. Check PZR level - at program value o BB LR-459 RNO7. Perform the following:

a. Place running charging pump flow controller in manual and adjust charging flow as necessary to establish PZR level at program value.

BG FK-121 for CCP BG FK-462 for NCP

b. Establish desired letdown using SYS BG-120, Chemical and Volume Control System Startup or SYS BG-201, Shifting Charging Pumps.

RO 8. Check letdown heat exchanger outlet temperature - < 130°F o BG TI-130 RO 9. Check charging header flow and letdown flow - BALANCED RNO9. Adjust charging & letdown as necessary to maintain PZR level at program CAUTION:

Total pump flow should be maintained above 175 gpm to minimize the effects of low flow cavitation.

RO 10. Verify CCP adequate flow:

a. Check CCPs - ANY RUNNING BG HIS-1A for CCP A BG HIS-2A for CCP B

b. Check CCP recirc valve - OPEN BG-HIS-8110 for CCP A BG HIS-8111 for CCP B CRS 11. Return to procedure and step in effect.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: _4____ Page 14__ of 38 Event

Description:

Normal Charging Pump (NCP) trip.

Time Position Applicants Actions or Behavior CRS Enters and directs ALR 00-042E, rev 10, Charging Pump Trouble RO 1. Check previously running charging pump - tripped o BG HIS-1A for CCP A o BG HIS-2A for CCP B o BG HIS-3 for NCP CRS 2. Contact Electrical Maintenance to determine cause of pump trip BOOTH Cue: If dispatched as building watch to investigate NCP trip, respond: I will investigate. If dispatched to NCP breaker, respond: Overcurrent flag is tripped.

If contacted as WWM, respond: I will assemble a team.

If contacted as Electrical MTN: I will assemble a team.overcurrent flag is dropped.

RO 3. Check charging pumps - none running o BG HIS-1A for CCP A o BG HIS-2A for CCP B o BG HIS-3 for NCP RO 4. Close letdown orifice isolation valves.

o BG HIS-8149AA o BG HIS-8149BA o BG HIS-8149CA CAUTION: If gas binding of pumps is suspected, performance of OFN BG-045, Gas Binding of CCPs or SI Pumps, should be performed.

RO 5. Establish charging flow

a. Check RCS temperature - > 350°F

b. Start CCP aligned for normal charging.

BG HIS-1A for CCP A BG HIS-2A for CCP B

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: _4____ Page 15_ of 38 Event

Description:

Normal Charging Pump (NCP) trip.

Time Position Applicants Actions or Behavior RO 5c. Go to step 6 RO 6. Ensure RCP seal injection - between 8gpm and 13 gpm to each RCP o BG FR-157 for RCP A o BG FR-156 for RCP B o BG FR-155 for RCP C o BG FR-154 for RCP D RO 7. Reestablish letdown

a. Check RCS letdown to regen HX valves open o BG HIS-459 o BG HIS-460

b. Place letdown HX outlet pressure control in manual o BG PK-131

c. Open letdown HX outlet pressure control between 90% and 100%

o BG PK-131

d. Open desired letdown orifice isolation valve(s).

BG HIS-8149AA BG HIS-8149BA BG HIS-8149CA

e. Adjust letdown HX outlet pressure control to establish letdown HX outlet pressure between 340 psig and 360 psig o BG PI-131

f. Place letdown HX outlet pressure control in auto o BG PK-131

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: _4____ Page 16__ of 38 Event

Description:

Normal Charging Pump (NCP) trip.

Time Position Applicants Actions or Behavior RO 8. Check charging header flow and letdown flow - BALANCED RNO8. Adjust charging & letdown as necessary to maintain PZR level at program value.

NOTE: Total pump flow should be maintained above 175 gpm to minimize the effects of low flow RO 9. Verify CCP adequate flow:

a. Check CCPs - any running BG HIS-1A for CCP A BG HIS-2A for CCP B

b. Check CCP recirc valve - open BG HIS-8110 for CCP A BG HIS-8111 for CCP B CRS 10. Ensure compliance with Technical Specifications and TRM:

a. Check plant - in Modes 1, 2, or 3

b. Refer to TR 3.1.9 and Technical Specification 3.5.2 CRS/CREW 11. Return to procedure and step in effect.

BOOTH INSTRUCTIONS: At Lead examiner discretion, initiate Event 5 by activating Key 4.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: __5___ Page 17_ of 38 Event

Description:

500 gpm Steam Generator Tube Rupture on Steam Generator A (OFN BB-07A, Steam Generator Tube Leakage)

Time Position Applicants Actions or Behavior INDICATIONS: Decreasing level PZR MCB annunciators 61B, Process Rad Hi followed by 00-061A, Process Rad HiHi RM-11R (SP056A) shows and alarms increasing radiation on process radiation monitor GE RE-92, Condenser Air Discharge Monitor CREW/CRS Begins diagnostics for Steam Generator Tube Rupture (SGTR) and enters OFN BB-07A, rev 8, Steam Generator Tube Leakage FOLDOUT PAGE FOR OFN BB-07A

1. SI ACTUATION CRITERIA IF any condition listed occurs, THEN trip the reactor, actuate SI, and go to EMG E-0, REACTOR TRIP OR SAFETY INJECTION Step 1.

RCS subcooling based on subcooling monitor - LESS THAN 30°F SUBCOOLING WITH REACTOR TRIPPED OR Pressurizer pressure - CANNOT BE MAINTAINED OR Pressurizer level - CANNOT BE MAINTAINED GREATER THAN 6%

OR All of the following conditions exist:

o Normal charging is maximized from one pump.

AND o Letdown is isolated.

AND o Pressurizer level is decreasing.

CAUTION If reactor trip or safety injection actuates during this procedure, go to EMG E-0, Reactor Trip or Safety Injection, step 1.

RO 1. Check PZR level - > 6%

RO 2. Check PZR level - > 17%

RO 3. Check PZR level - stable or increasing RNO 3 - see next page

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: _5____ Page _18 of _38 Event

Description:

500 gpm Steam Generator Tube Rupture on Steam Generator A Time Position Applicants Actions or Behavior RO RNO3 cont. If PZR level < program, then perform the following:

a. Control charging flow as necessary to maintain PZR level

b. If PZR level cannot be maintained, then close letdown orifice isolation valves as necessary to stabilize PZR level BG HIS-8149AA BG HIS-8149BA BG HIS-8149CA CREW 4. Try to identify the leaking SG Unexpected increase in any SG narrow range level OR Radiation from any SG steam line radiation monitor OR Radiation form any SG steam line survey OR Radiation from any SG sample RNO4. Try to identify leaking SG:

a. Direct HP to survey steamlines & blowdown lines as necessary to determine leaking SG NOTES o If VCT level cannot be maintained, the Rx is tripped since after swapover to the RWST the high boron injection flowrate makes an orderly shutdown difficult.

o If the leak rate is still within the capacity of a charging pump, after swapover to the RWST, it is not desirable to actuate SI and go to EMG E-3.

CREW 5. Check VCT level - BEING MAINTAINED BY NORMAL MAKEUP

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: _5____ Page 19_ of 38 Event

Description:

500 gpm Steam Generator Tube Rupture on Steam Generator A (EMG E-0, Reactor Trip or Safety Injection)

Time Position Applicants Actions or Behavior CRS/CREW Use OFN BB-07A FOLDOUT page criteria to direct Reactor trip and Safety Injection. Enter EMG E-0, rev 21, Reactor Trip or Safety Injection FOLDOUT PAGE FOR EMG E-0

1. RCP TRIP CRITERIA IF all conditions listed below occur, THEN trip all RCPs:

o RCS pressure - LESS THAN 1400 PSIG o CCPs or SI pumps - AT LEAST ONE RUNNING o Operator controlled cooldown - NOT IN PROGRESS

2. SI ACTUATION CRITERIA IF either condition listed below occurs, THEN actuate SI and go to EMG E-0, REACTOR TRIP OR SAFETY INJECTION, Step 1:

RCS subcooling - LESS THAN 30°F [45°F]

OR Pressurizer level - CANNOT BE MAINTAINED GREATER THAN 6% [33%]

3. FAULTED S/G ISOLATION CRITERIA IF any S/G pressure decreasing in an uncontrolled manner OR any S/G completely depressurized, THEN the following may be performed:

a. Close main steam isolation valves.

b. Isolate feed flow to faulted S/G(s).

c. Maintain total feed flow greater than 270,000 lbm/hr until narrow range level in at least one S/G is greater than 6% [29%].

4. RUPTURED S/G ISOLATION CRITERIA IF any S/G level increases in an uncontrolled manner OR any S/G has abnormal radiation, AND narrow range level in affected S/G(s) is greater than 6% [29%], THEN the following may be performed.

a. Close ruptured S/G AFW flow control valves.

b. IF any ruptured S/G AFW flow control valve cannot be closed AND total AFW flow to intact S/Gs can be maintained greater than 270,000 lbm/hr without associated AFW Pump, THEN perform the following:

1) Stop associated MD AFWP and place in PTL OR decrease TDAFWP speed to 2000 rpm.

2) Dispatch an Operator to locally isolate affected AFW flow control valve.

3) WHEN affected AFW flow control valve is isolated, THEN restart MD AFWP OR Restore TD AFWP speed as necessary.

5. COLD LEG RECIRCULATION CRITERIA IF RWST level decreases to less than 36%, THEN go to EMG ES-12, TRANSFER TO COLD LEG RECIRCULATION, Step 1.

6. AFW SUPPLY SWITCHOVER CRITERIA IF CST suction pressure decreases to less than 2.6 psig, THEN switch to alternate AFW suction supply.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: _5____ Page 20_ of 38 Event

Description:

500gpm SGTR, EMG E-0, rev 21, Reactor Trip or Safety Injection Time Position Applicants Actions or Behavior CAUTION Accident conditions can cause higher than normal radiation levels. Health Physics monitoring may be required while performing local operator actions.

NOTES o Steps 1 through 4 are immediate action steps.

o Foldout page shall be monitored throughout this procedure.

RO/CRS 1. Verify reactor trip

a. Check all rod bottom lights - LIT

b. Ensure reactor trip & bypass breakers - OPEN

c. Check IR neutron flux - DECREASING BOP/CRS 2. Verify turbine trip

a. Check the following:

Main stop valves - ALL CLOSED OR Turbine auto stop bistables - AT LEAST TWO LIT RO/CRS 3. Check AC emergency busses - at least one energized NB01 voltage - NORMAL NB02 voltage - NORMAL RO/CRS 4. Check if Safety Injection is Actuated:

a. Check any indication SI is actuated - LIT 00-030A, NF039A LOCA Seq Actuated - LIT OR 00-031A, NF039B LOCA Seq Actuated - LIT OR ESFAS status panel SIS section - any white lights LIT OR Partial Trip Status Permissives/Block status panel - SI red light lit

b. Check both trains of SI actuated o 00-030A, NF039A LOCA Seq Actuated - LIT o 00-031A, NF039B LOCA Seq Actuated - LIT

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: _5____ Page _21 of 38 Event

Description:

500gpm SGTR, EMG E-0, rev 21, Reactor Trip or Safety Injection Time Position Applicants Actions or Behavior CAUTION If offsite power is lost after SI reset, manual action may be required to restore safeguards equipment to the required configuration.

CRS 5. Check if SI is required:

SI was manually actuated AND was required OR RCS pressure is currently or has been - 1830 psig OR Any SG pressure is currently or has been - 615 psig OR Containment pressure is currently or has been - 305 psig OR RCS subcooling is currently or has been - < 30°F [45°F] OR PZR level is currently or has been - < 6% [33%]

BOP 6. Check Main Generator Breakers & Exciter Breaker - open o MA ZL-3A o MA Zl-4A o MB ZL-2 CRS 7. Verify Automatic Actions using Attachment F, Automatic Signal Verification BOP 8. Check total AFW flow - > 270,000 lbm/hr RNO8. Perform the following:

a. If SG NR level in at least one SG is > 6% [29%], then control feed flow to maintain NR level and go to step 9.

b. Manually start pumps and align valves as necessary to establish

>270,000 lbm/hr AFW flow

c. If total AFW flow > 270,000 lbm/hr cannot be established, then perform:

1) Direct operator to monitor CSF using EMG F-0, CSFST

2) Ensure BIT inlet and outlet valves are open

3) Continue with At. F and go to EMG FR-H1, Response to Loss of Secondary Heat Sink, step 1

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: _6____ Page 22_ of 38 Event

Description:

CT: BIT outlet valves EM HIS-8801A & EM HIS-8801B do not open upon SI actuation - manual open available.

Time Position Applicants Actions or Behavior INDICATION: No ECCS flow indication on EM FI-917A or EM FI-917B. BIT outlet valves EM HIS-8801A/B indicate closed (green lights are lit).

RO/BOP Determines BIT outlet valves EM HIS-8801A and EM HIS-8801B are not open. (EMG E-0, Att F, step F12)

RO/BOP CT: Opens BIT outlet valves EM HIS-8801A and EM HIS-8801B after completion of Immediate Action steps (opening the valves may have occurred after the Immediate Actions were performed and reported back as completed to the CRS) OR they may be opened using Attachment F of EMG E-0.

Attachment F, Automatic Signal Verification RO/BOP F1. Verify Feedwater Isolation F2. Verify Containment Isolation Phase A F3. Verify AFW Pumps running F4. Verify ECCS pumps running F5. Verify CCW alignment F6. Check ESW pumps - both running F7. Check Containment fan coolers - running in slow speed F8. Verify Containment purge isolation F9. Verify both trains of Control Room ventilation isolation F10. Verify Main Steamline isolation not required F11. Verify Containment Spray not required

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: _6____ Page 23 of 38 Event

Description:

CT: BIT outlet valves EM HIS-8801A & EM HIS-8801B do not open upon SI actuation - manual open available Time Position Applicants Actions or Behavior EMG E-0, Attachment F, cont.

RO/BOP F12. Verify ECCS flow:

a. Check CCP to BIT flow meters - NO flow indicated o EM FI-917A o EM FI-917B RNOa. Perform the following CT: Open the BIT valves

1) If BIT valves have not been closed by operator action then manually start pumps and align valves

2) If BIT valves are closed by operator action, then go to step 13 F13. Verify AFW valves - properly aligned F14. Verify SI valves - properly aligned F15. Check is NCP should be stopped:

a. CCPs - any running

b. Stop NCP o BG HIS-3 F16. Return to procedure and step in effect

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: _5____ Page 24of 38 Event

Description:

500gpm SGTR, EMG E-0, rev 21, Reactor Trip or Safety Injection Time Position Applicants Actions or Behavior

4. RUPTURED S/G ISOLATION CRITERIA IF any S/G level increases in an uncontrolled manner OR any S/G has abnormal radiation, AND narrow range level in affected S/G(s) is greater than 6% [29%], THEN the following may be performed.

a. Close ruptured S/G AFW flow control valves.

b. IF any ruptured S/G AFW flow control valve cannot be closed AND total AFW flow to intact S/Gs can be maintained greater than 270,000 lbm/hr without associated AFW Pump, THEN perform the following:

1) Stop associated MD AFWP and place in PTL OR decrease TDAFWP speed to 2000 rpm.

2) Dispatch an Operator to locally isolate affected AFW flow control valve.

3) WHEN affected AFW flow control valve is isolated, THEN restart MD AFWP OR Restore TD AFWP speed as necessary.

CRS/BOP Directs Foldout Item #4, Ruptured SG Isolation Criteria when level in ruptured SG > 6% [29%]

CT: Isolate ruptured steam generator (Close ruptured steam generator AFW flow control valves)

RO 9. Check RCS cold leg temperatures Stable at to trending to 557°F for condenser steam dumps Stable at or trending to 561°F for SG ARVs RNO9. Perform the following:

a. If temp. is < setpoint and decreasing, then perform the following steps:

1) Stop dumping steam

2) If any MSIV is open, then close Main Turbine Stop & Control Valves Startup Drains

3) If cooldown continues then control total feed flow to limit RCS cooldown.

Maintain total feed flow > 270,000 lbm/hr until NR level > 6% [29%] in at least one SG

4) If cooldown continues due to excessive steam flow, then close MSIVs, bypass valves and drain valves

b. If temperature is > setpoint and increasing, then perform one of the following:

Dump steam to condenser Dump steam using SG ARVs

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: __5___ Page 25_ of 38 Event

Description:

500gpm SGTR, EMG E-0, rev 21, Reactor Trip or Safety Injection Time Position Applicants Actions or Behavior BOP 10. Establish SG pressure control

a. Check condenser - AVAILABLE o C-9 lit o MSIV - OPEN o Circ water pumps - RUNNING

b. Place steam header pressure control in manual o AB PK-507

c. Manually set steam header pressure control output to zero o AB PK-507

d. Place steam dump select switch to STEAM PRESS position o AB US-500Z

e. Place steam header pressure control in Automatic o AB PK-507 RO 11. Check PZR PORVs

a. Check PZR PORVs - CLOSED o BB HIS-455A o BB HIS-455B

b. Power to block - AVAILABLE

c. RCS pressure - < 2185 psig RO 12. Check normal PZR spray valves - CLOSED o BB ZL-455B o BB ZL-455C RO 13. Check PZR safety valves - CLOSED o BB ZL-8010A o BB ZL-8010B o BB ZL-8010C

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: _5____ Page 26_ of 38 Event

Description:

500gpm SGTR, EMG E-0, rev 21, Reactor Trip or Safety Injection Time Position Applicants Actions or Behavior NOTE:

Seal injection flow shall be maintained to all RCPs.

RO 14. Check if RCPs should be stopped:

a. Check RCPs - any running RNOa. Go to step 15

b. Check RCS pressure - < 1400 psig RNOb. Go to step 15

c. Check ECCS pumps - at least one running RNOc. Go to step 15 CCP or SI pump

d. Check operator controlled cooldown - not in progress RNOd. Go to step 15

e. Stop all RCPs CRS 15. Direct Operator to monitor Critical Safety Functions using EMG F-0, Critical Safety Function Status trees (CSFST)

BOP 16. Check is SGs are not faulted:

a. Check pressures in all SG -

o No SG pressure decreasing in an uncontrolled manner o No SG completely depressurized BOP 17. Check if SG tubes are intact:

a. Direct HP to survey steamlines in Area 5 of the Aux Building

b. Condenser air discharge radiation - Normal before isolation o GEG 925

c. SG blowdown & sample radiation - Normal before isolation o BML 256 o SJL 026

d. Turbine driven auxiliary feedwater pump exhaust radiation - normal o FCT 381

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: _5____ Page 27_ of 38 Event

Description:

500gpm SGTR, EMG E-0, rev 21, Reactor Trip or Safety Injection Time Position Applicants Actions or Behavior Step 17. cont.

BOP 17e. SG steam line radiation - NORMAL o ABS 114 for SG A o ABS 113 for SG B o ABS 112 for SG C o ABS 111 for SG D CRS/RO RNO17. Perform the following:

1. Ensure BIT inlet and outlet valves are open o EM HIS-8803A o EM HIS-8803B o EM HIS-8801A o EM HIS-8801B

2. Go to EMG E-3, Steam Generator Tube Rupture, step 1 CRS Crew transitions from EMG E-0 to EMG E-3

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: __5___ Page 28_ of 38 Event

Description:

500gpm SGTR, EMG E-3, rev 21, Steam Generator Tube Rupture (SGTR)

Time Position Applicants Actions or Behavior CREW Enters EMG E-3, rev 21, Steam Generator Tube Rupture (SGTR)

FOLDOUT PAGE FOR EMG E-3

1. SI REINITIATION CRITERIA IF following performance of Step 31, either condition listed below occurs, THEN start ECCS pumps as necessary to reestablish RCS subcooling and PZR level and go to EMG C-31, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.

RCS subcooling - LESS THAN 30°F [45°F]

OR Pressurizer level - CANNOT BE MAINTAINED GREATER THAN 6% [33%]

2. SECONDARY INTEGRITY CRITERIA IF all conditions listed below are satisfied, THEN go to EMG E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1:

o Any S/G pressure is decreasing in an uncontrolled manner OR any S/G has completely depressurized o Affected S/G has NOT been isolated using EMG E-2, FAULTED STEAM GENERATOR ISOLATION o Affected S/G is NOT needed for RCS cooldown

3. MULTIPLE TUBE RUPTURE CRITERIA IF any intact S/G level increases in an uncontrolled manner OR any intact S/G has abnormal radiation, THEN stop any RCS cooldown and depressurization in progress, stabilize the plant, and go to EMG E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.

4. COLD LEG RECIRCULATION CRITERIA IF RWST level decreases to less than 36%, THEN go to EMG ES-12, TRANSFER TO COLD LEG RECIRCULATION, Step 1.

5. AFW SUPPLY SWITCHOVER CRITERIA IF CST suction pressure decreases to less than 2.6 psig, THEN switch to alternate AFW suction supply.

NOTES o Foldout page shall be monitored throughout this procedure.

o Personnel should be available for sampling during this procedure.

o Seal injection flow shall be maintained to all RCPs.

CRS 1. Check if RCPs should be stopped:

a. Check RCPs - ANY RUNNING

b. Check RCS pressure - < 1400 psig

c. Check ECCS pumps - AT LEAST ONE RUNNING CCP or SI pump

d. Check operator controlled cooldown - NOT IN PROGRESS

e. Stop all RCPs (RNO for a-d: Observe CAUTION prior to step 2 and go to step 2)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: _5____ Page 29 of 38 Event

Description:

500gpm SGTR, EMG E-3, rev 21, Steam Generator Tube Rupture (SGTR)

Time Position Applicants Actions or Behavior CAUTION If steamlines are not intact, extreme caution will be necessary when performing local surveys.

2. Identify ruptured SGs:

CRS Level increasing in an uncontrolled manner OR High turbine driven AFW exhaust radiation OR High radiation from any SG steamline radiation monitor OR High radiation from any SG steamline survey OR High radiation from any SG sample BOOTH CUE: If contacted as HP to survey steam lines in Area 5: respond I will perform the survey.

CAUTION If the turbine driven AFW pump is the only available source of feed flow, steam supply to the turbine driven AFW pump must be maintained from at least one S/G.

3. Isolate flow from ruptured SGs:

CRS

a. Adjust ruptured SG ARV controller setpoint to 1160 psig

b. Check ruptured SG ARV - CLOSED

c. Locally close steam supply to turbine driven AFW pump from ruptured SG(s) NA for SG A AB-V085 for SG B AB-V087 for SG C

d. Locally isolate main steamline low point drain valve from ruptured SG(s)

Close AB-V062 for SG A Close AB-V072 for SG B Close AB-V082 for SG C Close AB-V052 for SG D BOOTH INSTRUCTION: To activate closure of AB-V062

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: _5____ Page 30_ of 38 Event

Description:

500gpm SGTR, EMG E-3, rev 21, Steam Generator Tube Rupture (SGTR)

Time Position Applicants Actions or Behavior BOP 4. Verify blowdown a & upper sampling isolated on ruptured SGs:

a. SG blowdown containment isolation valves - closed BM HIS-1A for SG A BM HIS-2A for SG B BM HIS-3A for SG C BM HIS-4A for SG D

b. SG upper sample isolation valves - closed BM HIS-19 for SG A BM HIS-20 for SG B BM HIS-21 for SG C BM HIS-22 for SG D CAUTION At least one SG shall be maintained available for RCS cooldown.

CRS 5. Isolate steamline on ruptured SGs:

a. Close main steamline isolation valve AB HIS-14 for SG A AB HIS-17 for SG B AB HIS-20 for SG C AB HIS-11 for SG D

b. Ensure main steamline isolation bypass valves - closed o AB ZL-15A for SG A o AB ZL-18A for SG B o AB ZL-21A for SG C o AB ZL-12A for SG D

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: _5____ Page 31 of 38 Event

Description:

500gpm SGTR, EMG E-3, rev 21, Steam Generator Tube Rupture (SGTR)

Time Position Applicants Actions or Behavior CAUTION If any ruptured S/G is also faulted and the affected S/G is not needed for RCS cooldown, feed flow to that S/G shall remain isolated during subsequent recovery actions.

BOP 6. Check if feed flow should be isolated to ruptured SG(s):

a. Check ruptured SG(s) narrow range level - >6% [29%]

BOP 7. Stop feed flow to ruptured SG(s) CT: Isolate ruptured SG A

a. Close affected SG(s) MD AFP flow control valve(s)

AL HK-7A for SG A AL HK-9A for SG B AL HK-11A for SG C AL HK-5A for SG D

b. Close affected SG(s) TD AFWP flow control valve(s)

AL HK-8A for SG A AL HK-10A for SG B AL HK-12A for SG C AL HK-6A for SG D BOP 8. Establish SG pressure control:

a. Check condenser available

b. Place steam header pressure control in manual

c. Manually set steam header pressure control output to zero

d. Place steam dump select switch in STEAM PRESS position

e. Place steam header pressure control in automatic

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: ___5__ Page 32 of 38 Event

Description:

500gpm SGTR, EMG E-3, rev 21, Steam Generator Tube Rupture (SGTR)

Time Position Applicants Actions or Behavior CRS 9. Verify ruptured SG(s) isolation

a. Check ruptured SG(s) - not needed for RCS cooldown

b. Verify ruptured SG(s) steamline has been isolated from at least one intact SG:

Main steam isolation valve, bypass valve, and drain valve on ruptured SG - closed OR Attachment A, Main Steam header isolation - Control Room -

completed

c. Verify steam supply to turbine driven AFW pump from ruptured SG(s) -

CLOSED AB-V085 for SG B AB-V087 for SG C CAUTION At EOL, if a control rod is stuck or SI flow is reduced, an inadvertent restart may occur. Symptoms for subcriticality red path and transition to EMG FR-S1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS, shall be closely monitored during subsequent steps.

CREW 10. Check ruptured SG(s) pressure - > 275 psig NOTE If high steam pressure rate setpoint (100 psi/50 sec) is exceeded after low steamline pressure SI signal is blocked, main steamline isolation will occur.

RO 11.Check if low steamline pressure SI should be blocked:

a. Check RCS pressure - <1970 psig o P-11 light - LIT

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: __5___ Page 33_ of 38 Event

Description:

500gpm SGTR, EMG E-3, rev 21, Steam Generator Tube Rupture (SGTR)

Time Position Applicants Actions or Behavior

b. Block low steamline pressure SI o SB HS-9 o SB HS-10 RNOa. When RCS pressure is < 1970 psig then block low steamline pressure SI. Continue with step 12.

CREW Determine target plant conditions from table below:

LOWEST TARGET CORE TARGET INTACT TARGET DUMP RUPTURED S/G EXIT S/G CONDENSER CONTROLLER PRESSURE (PSIG) TEMPERATURE STEAM PRESSURE SETPOINT

(°F) (PSIG)

>1200 519 [504] 791 [691] 5.27 [4.61]

1100 TO 1199 508 [493] 717 [624] 4.78 [4.16]

1000 TO 1099 496 [481] 642 [557] 4.28 [3.71]

900 TO 999 484 [469] 573 [495] 3.82 [3.30]

800 TO 899 470 [455] 500 [430] 3.33 [2.87]

700 TO 799 455 [440] 430 [367] 2.87 [2.45]

600 TO 699 438 [423] 359 [304] 2.39 [2.03]

500 TO 599 420 [405] 294 [247] 1.96 [1.65]

400 TO 499 398 [383] 227 [188] 1.51 [1.25]

300 TO 399 372 [357] 163 [133] 1.09 [0.89]

275 TO 299 364 [350] 147 [118] 0.98 [0.79]

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: __5___ Page 34_ of 38 Event

Description:

500gpm SGTR, EMG E-3, rev 21, Steam Generator Tube Rupture (SGTR)

Time Position Applicants Actions or Behavior CAUTION If RCPs are NOT running, the cooldown and depressurization steps may cause a red or orange path condition on the integrity status tree for the ruptured loop. Step 48 shall be completed before reevaluating the red or orange path condition and transition to EMG FR-P1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITIONS, if required.

NOTES o After operator initiated RCS cooldown has been started, RCP trip criteria no longer applies.

o When RCS average temperature is less than 550°F, the condenser steam dump low temperature interlock must be bypassed to keep cooldown valves open.

CRS 13. Initiate RCS cooldown

a. Dump steam to condenser at maximum rate:

1) Ensure STM HDR PRESS CTRL in manual o AB PK-507

2) Set STM HDR PRESS CTRL potentiometer to target setpoint value o AB PK-507

3) Manually adjust STM HDR PRESS CTRL to slowly open a maximum of 3 cooldown valves o AB PK-507

4) When P-12 interlock actuates, then place both STEAM DUMP BYPASS INTERLOCK switches to BYP/INTLK o AB HS-63 o AB HS-64

5) Place STM HDR PRESS CTRL in auto to continue cooldown at maximum rate o AB PK-507 CT: (Cooldown and) Depressurize the RCS to meet Safety Injection termination criteria using EMG E-3, Steam Generator Tube Rupture.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: __5___ Page 35 of 38 Event

Description:

500gpm SGTR, EMG E-3, rev 21, Steam Generator Tube Rupture (SGTR)

Time Position Applicants Actions or Behavior CREW 14. Check intact SG levels:

a. Check NR level in at least one SG - > 6% [29%]

b. Control feed flow to maintain NR level in all SGs between 29% [29%]

and 50%

CAUTION If any PZR PORV opens because of high PZR pressure, the PORV shall be monitored to ensure it recloses after pressure decreases to less than 2335 psig.

CREW 15. Check PZR PORVs and block valves:

a. Power to block valves - AVAILABLE o BB HIS-8000A o BB HIS-8000B

b. PZR PORVs - CLOSED o BB HIS-455A o BB HIS-456A

c. RCS pressure - < 2185 psig CREW 16. Check PZR Safety valves - CLOSED o BB ZL-8010A o BB ZL-8010B o BB ZL-8010C

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: __5___ Page 36 of 38 Event

Description:

500gpm SGTR, EMG E-3, rev 21, Steam Generator Tube Rupture (SGTR)

Time Position Applicants Actions or Behavior CAUTION If offsite power is lost after SI reset, manual action may be required to restore safeguards equipment to the required configuration.

RO 17. Reset SI o SB HS-42A o SB HS-43A RO 18. Reset Containment Isolation Phase A & Phase B o SB HS-56 for phase A o SB HS-53 for phase A o SB HS-55 for phase B o SB HS-52 for phase B CREW 19. Establish Instrument Air to Containment

a. Ensure ESW to air compressor valves - open o EF HIS-43 o EF HIS-44

b. Reset and close air compressor breaker reset switches o KA HIS-2C o KA HIS-3C

c. Check instrument air pressure - > 105 psig o KA PI-40

d. Check PZR pressure master controller - < 50% output signal o BB PK-455A

e. Open instrument air supply containment isolation valve o KA HIS-29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: _5____ Page 37_ of 38 Event

Description:

500gpm SGTR, EMG E-3, rev 21, Steam Generator Tube Rupture (SGTR)

Time Position Applicants Actions or Behavior CAUTION After RHR pumps have been stopped, RCS pressure shall be monitored for RHR pump restart criteria.

CRS 20. Check if RHR pumps should be stopped:

a. Check RHR pumps - any running

b. Check RHR system - aligned for injection

c. Check RCS pressure - > 325 psig

d. Stop RHR pumps and place in standby o EJ HIS-1 o EJ HIS-2

e. Check RCS pressure > 325 psig during subsequent recovery actions RNOe. If RCS pressure decreases in an uncontrolled manner to < 325 psig, then manually restart RHR pumps to provide injection to the RCS.

CREW 21. Check if RCS cooldown should be stopped:

a. Check RCS temperatures - < target temperature Core Exit TCs or RCS hot leg RTDs

b. Ensure steam dump valves - closing o Condenser steam dumps o ARVs

c. Adjust steam dump controllers, as necessary, to automatically maintain RCS temperature stable below target temperature AB PK-507 or Intact ARVs Terminate scenario at Lead Evaluators discretion.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4___ Event No.: _5____ Page 38_ of 38 Event

Description:

500gpm SGTR, EMG E-3, rev 21, Steam Generator Tube Rupture (SGTR)

Time Position Applicants Actions or Behavior CREW 22. Check ruptured SG Pressure - stable or increasing CREW 23. Check RCS subcooling - > 50°F [65°F]

CREW 24. Depressurize RCS using normal Spray to minimize break flow and refill PZR

a. Verify normal PZR spray - available RCP D running RCPs A, B, and C running All RCPs running

b. Spray PZR with maximum available spray until any of the following conditions Are satisfied:

PZR level - > 75% [61%] or RCS subcooling - < 30°F [45°F] or Both of the following

1) RCS pressure - < ruptured SGs pressure

2) PZR level - > 6% [33%]

c. Close normal spray valves o BB PK-455B o BB PK-455C

d. Observe CAUTION prior to step 30 and go to step 30