Text

Final Operating Test (Sections a, B, and C) (Folder 3)
	ML16365A044
Person / Time
Site:	Indian Point
Issue date:	10/31/2016
From:	; Entergy Nuclear Indian Point 2
To:	; Operations Branch I
Shared Package
ML16076A436	List: ML16119A001; ML16365A041; ML16365A042; ML16365A043; ML16365A044; ML17047A597; ML17047A598; ML17047A599; ML17047A600; ML17047A601; ML17069A284; ML17206A442; ML18159A351;
References
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	Download: ML16365A044 (203)
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Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point Unit 2 Task No:

Task

Title:

Update Electrical Power Availability for Shutdown Safety Assessment KIA

Reference:

1940002.1.18 Job Performance Measure SRO Admin 1 SR0-3.8 No:

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:

Unit Shutdown in progress due to 23 EDG inoperable and extensive maintenance and repair required to restore operability.

The Unit has just entered MODE 4.

The shift has just completed a tag out to work on Breaker OSP

No Substation Work is in progress.

Required Materials: Marked up drawing 250907 IP-SMM-OU-104, Shutdown Risk Assessment Procedure (Att. 9.2)

Blank IP-SMM-OU-104, Attachment 9.1 General

References:

Drawing 250907, Electrical Distribution & Transmission System IP-SMM-OU-104, Shutdown Risk Assessment Procedure Initiating Cue: Given the above initial conditions, the Shift Manager has requested that you update the Electrical Power Availability section of the previously completed Shiftly Shutdown Safety Assessment in accordance with IP-SMM-OU-104.

You have been provided a copy of marked up drawing 250907 indicating the breakers tagged open associated with the 6.9 KV Gas Turbine Substation Bus tagout.

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Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: No Validation Time: 7 minutes Task Standard: Update IP-SMM-OU-104, Attachment 9.1 to show that Electrical Power Availability is now YELLOW from a Shutdown Risk perspective. The Score should be a 5 which would constitute a YELLOW condition.

1. Number of Emergency Diesel Generators Available - (Two)- 2 pts

2. Offsite Power Sources Available - (One)- 1pt

3. Switchyard work in progress - (No) - 1pt

4. Outage Unit's Appendix R Diesel Available - (No)- Opts

5. Severe weather OAP-008 in Effect with the potential for Loss of Offsite Power - (No)

- 1 pt.

Total Points= 5 or YELLOW Condition NOTE: The tagout for the 6.9KV Gas Turbine Substation Bus causes a loss of all available 13.BKV (credited offsite source) and the Unit 2 Appendix R Diesel.

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Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark.,,/)

1. Performance Step: Student reviews IP-SMM-OU-104, Attachment 9.1.

Standard: Student recognizes that per the initiating cue, that only the electrical section requires updating.

CUE: All other aspects of the Shutdown Safety Function Assessment remain unchanged, only the electrical portion requires updating. Complete just the Electrical Power Availability section on a blank Attachment 9.1.

Comment: Provide cue and blank form. Cue may be provided as a group in a classroom setting .

.,,/2. Performance Step: Student completes the Number of Emergency Diesel Generators Available line and assigns points per the procedure.

Standard: Student recognizes that only 23 EOG is unavailable and assigns 2 points.

Comment: >=Two Diesels Available is 2 points.

--/ 3. Performance Step: Student completes the Offsite Power Sources Available line and assigns points per the procedure.

Standard: Student recognizes that no 13.8KV Offsite sources are available and assigns 1 point.

Comment: One (1) is 1 point. Attachment 9.2 guidance states only 1 source of 138KV is credited regardless of the number of live feeders .

.,,/4. Performance Step: Student completes the Switchyard work in progress line and assigns points per the procedure Standard: Student recognizes that No Switchyard work is in progress. The tagout is complete and No Substation work is in progress per the initial conditions.

He assigns 1 point.

Comment: No switchyard work in progress results in 1 point. Attachment 9.2 guidance states: NOTE: If mitigating actions have been taken such that the work being performed can no longer be viewed as potential for inducing a LOOP event, then Attachment 1 "Switchyard Work In Progress" Power Availability Safety Function question should be recorded as a NO.

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Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark"'./)

-.J 5. Performance Step: Student completes the Outage Unit's Appendix R Diesel Generator Available line and assigns points per the procedure.

Standard: Student recognizes that the Appendix R Diesel is unavailable and assigns zero (0) points.

Comment: Student recognizes that the tagout precludes the use of the Appendix R

=

Diesel. No Appendix R Diesel O points.

-.J 6. Performance Step: Student completes the Severe weather OAP-008 in Effect with the potential for Loss of Offsite Power line and assigns points per the procedure.

Standard: Student recognizes that Severe weather OAP-008 is not in effect and assigns 1 point.

CUE: If requested, cue that no storms or severe weather have been reported or forecast.

Comment: Severe weather OAP-008 Not in effect =1 point.

-.J 7. Performance Step: Student completes the Electrical Power Availability Score by adding the respective points and determines the shutdown color for Electrical Power.

Standard: Student adds the numbers and determines a Total of 5 points and a YELLOW Condition.

Comment: Total should add to 5 points and a YELLOW Condition.

Terminating Cue: JPM Complete 4 of 6

Appendix C Page 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: - - - - - - - - - - - -

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Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

Unit Shutdown in progress due to 23 EDG inoperable and extensive maintenance and repair required to restore operability.

The Unit has just entered MODE 4.

The shift has just completed a tag out to work on Breaker OSP

No Substation Work is in progress.

Initiating Cue:

Given the above initial conditions, the Shift Manager has requested that you update the Electrical Power Availability section of the previously completed Shiftly Shutdown Safety Assessment in accordance with IP-SMM-OU-104. You have been provided a copy of marked up drawing 250907 indicating the breakers tagged open associated with the 6.9 KV Gas Turbine Substation Bus tagout.

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Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 2 Task No: 2000120121 Task

Title:

Review Daily Containment Leakage Calculation Job Performance Measure SRO Admin 2.1.25 (3.9)

KIA

Reference:

No: 2

~

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Performance x Classroom x 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:

1 . The plant has been operating at 100% power for the past several months.

2. The previous Daily Weld Channel Leakage Calculation was performed last mid-shift at 0005.

3. The time now is today at 0015.

4. A spare RO performed the Daily Weld Channel Leakage Calculation.

Required Materials: Calculator General

References:

2-PT-D001 Control Room Operations Surveillance Requirements Initiating Cue: The SM has directed you to Review the Daily Weld Channel Leakage Calculation per 2-PT-D001, page 28.

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Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: No Validation Time: 20 minutes Task Standard:

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Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

1. Performance Step: Obtain correct procedure and step Standard: Obtains correct procedure and step Comment:

.../2. Performance Step: Review 2-PT-D001, page 28 for today's reading NOTE: Review operator calculations on 2-PT-D001, page 28 Standard: Determine Zone Total is correct.

Determine Delta Hours is incorrect. The correct value should be 1450 minutes Determine Average Leakrate calculation is incorrect. The correct Average Leakrate value should be 15.3 Comment:

3 of 9

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

"13. Performance Step: Determine calculation is incorrect. Determine Containment leakrate exceeds TS 3.6.10 limit Standard: TS 3.6.10 Condition B for WC&PPS air consumption not within limits of SR 3.6.10.2.

SR 3.6.10.2 requires :S 0.2% containment free volume consumption per day.

TS Basis states that 15.2 scfm is equivalent to 0.2%

Comment: If candidate asks for additional information report, SM is conferring with Licensing, l&C and Management.

Terminating Cue: JPM Complete 4 of 9

No: 2-PT-0001 Rev: 16 CONTROL ROOM OPERATIONS SURVEILLANCE REQUIREMENTS Page: 28 of 40 Attachment 1 - Control Room 12 and 24 Hour Surveillance Requirements Page 16 of 27 WC&PPS (2)

Surveillance Requirement ComponenU Parameter lnstrumenU Location I Acceptance Criteria I Actual I Acceptable I Initials I Comments ARP SLF 1-4

> 47 PSIG SR 3.6.10.1 I WC&PPS I Weld Channel Low I CLEAR I YES/NO (1)

Pressure Zone 1 5710 CF Zone 2 5470 CF MODES 1, 2, 3 and 4 Zone 3 5560 CF Average Leak Rate is equal to the Zone 4 5460 CF Total leak rate divided by the difference in time Total (Hours times minutes).

22200 CF SR 3.6.10.2 I WC&PPS I (3)

I Average Leak Rate < 14.4 CFM 15.30 CFM YES/NO Recorder Leak Rate < 14.4 CFM OOS CFM YES/ NO Current Date and Time Date: TODAY Time: 0015 I Delta Hours 24 hrs 10 Previous Date and Time Date: YESTERDAY Time: 0005 I 1450 Minutes (1) Weld Channel Low Pressure Alarm is at 49 psig. IF the alarm is clear,> 47 psig can be verified.

(2) SR 3.6.10.2 shall be performed on the midnight shift as close to midnight as possible. Zero counters after readings.

(3) IF a WC&PPS zone is to be worked on or calibrated, average the other 3 channels, red circle the result and note the reason below.

NOTE: the values in this table are correct 5 of 9

Appendix C Page6 Form ES-C-1 SIMULATOR SETUP None.

6 of 9

Appendix C Page 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __

7 of 9

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

1. The plant has been operating at 100% power for the past several months.

2. The previous Daily Weld Channel Leakage Calculation was performed last mid-shift at 0005.

3. The time now is today at 0015.

4. A spare RO performed the Daily Weld Channel Leakage Calculation.

Initiating Cue:

The SM has directed you to Review the Daily Weld Channel Leakage Calculation per 2-PT-D001, page 28.

No: 2-PT-0001 Rev: 16 CONTROL ROOM OPERATIONS SURVEILLANCE REQUIREMENTS Page: 28 of 40 - Control Room 12 and 24 Hour Surveillance Requirements Page 16 of 27 WC&PPS (2)

Surveillance Component/ Instrument/ Acceptance Requirement Parameter Location Criteria I Actual I Acceptable I Initials I Comments ARP SLF 1-4

>47 PSIG SR 3.6.10.1 WC&PPS Weld Channel Low

( 1)

I CLEAR I YES/NO I TJ Pressure Zone 1 5710 CF Zone 2 5470 CF MODES 1, 2, 3 and 4 Zone 3 5560 CF Average Leak Rate is equal to the Zone 4 5460 CF Total leak rate divided by the difference in time Total (Hours times minutes).

22200 CF SR 3.6.10.2 WC&PPS (3)

Average Leak Rate < 14.4 CFM 14.0 CFM YES/NO TJ Recorder Leak Rate < 14.4 CFM OOS CFM YES I NO #11 Current Date and Time Date: TODAY Time: 0015 I Delta Hours 24 hrs 10 Previous Date and Time Date: YESTERDAY Time: 0005 I 1480 Minutes (1) Weld Channel Low Pressure Alarm is at 49 psig. IF the alarm is clear,> 47 psig can be verified.

(2) SR 3.6.10.2 shall be performed on the midnight shift as close to midnight as possible. Zero counters after readings.

(3) IF a WC&PPS zone is to be worked on or calibrated, average the other 3 channels, red circle the result and note the reason below

Appendix C Job Performance Measure Form ES-C-1

... Worksheet Facility: Indian Point Unit 2 Task No: 2000660122 Task

Title:

Reportablity for Safety Limit Violation Job Performance Measure SRO Admin 3 KIA

Reference:

2.2.22 (4.7) No:

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 unit is operating at 85% power during a power ascension following a refueling outage.

During the outage the Baffle Wall Up Flow modification was completed.

30 minutes ago Westinghouse notified the Control Room that the original analysis overestimated RCS flow.

Using the correct values for flow with Power greater than 25%, DNBR is 1.10 for new fuel assemblies located near the center of the core.

Required Materials: Technical Specifications NRC form 361 IP-SMM-11-108 Event Notification and Reporting EN-Ll-108 Event Notification and Reporting General

References:

Technical Specifications NRC form 361 IP-SMM-11-108 Event Notification and Reporting EN-Ll-108 Event Notification and Reporting 1 of 7

J Appendix C Job Performance Measure Form ES-C-1 Worksheet Initiating Cue: You are the CRS.

What must be done with plant power?

How soon must the first report to the NRC be made?

The ENS line is OOS. How do you contact the NRC?

Complete NRC form 361 for the event.

Time Critical Task: 60 minutes Validation Time: 45 minutes Task Standard: Questions answered correctly and NRC form 361 complete.

2 of 7

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..../)

v1. Performance Step: What must be done with plant power?

Standard: Identify Tech Spec Safety Limit Violation TS 2.1.1 IN MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Compliance is restored when power is less than 25%

however the plant must continue to MODE 3 within one hour Comment:

~ 2. Performance Step: How soon must the first report to the NRC be made?

Standard: IP-SMM-Ll-108 states that a TS Safety Limit violation is reportable to NRC Operations Center within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Comment: Attachment 10.1 Item 5 v 3. Performance Step: The ENS line is OOS. How do you contact the NRC?

Standard: IP-SMM-Ll-108 lists NRC Operations Center Commercial Telephone numbers.

Comment: Attachment 10.2, Initial Notifications. Non-Emergency Events.

3 of 7

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark"\/)

-.J 4. Performance Step: Complete NRC form 361 Standard: See attached Comment:

Terminating Cue: JPM Complete 4 of 7

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5 of 7

Appendix C Page 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ __

6 of 7

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

The unit is operating at 85% power during a power ascension following a refueling outage.

During the outage the Baffle Wall Up Flow modification was completed.

Westinghouse notified the Control Room that the original analysis overestimate RCS flow.

Using the correct values for flow with Power greater than 25%, DNBR is 1.10 for new fuel assemblies located near the center of the core.

Initiating Cue:

You are the CRS.

What must be done with plant power?

How soon must the first report to the NRC be made?

The ENS line is OOS. How do you contact the NRC?

Complete NRC form 361 for the event.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point Unit 2 Task No: 2000241602 Task

Title:

Review I Authorize a Liquid Waste Release KIA

Reference:

1940002.3.6 Job Performance Measure SROAdmin4 SR0-3.8 No:

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:

Unit is in MODE 5 for a forced outage.

Circulating Water Pumps Status:

o 21, 23, and 25 in service in slow speed.

o No other dilution flow sources are available or authorized.

A Liquid Radioactive Waste Release Permit Form has been completed manually IAW Section 4.1 of 2-SOP-5.1.5; Calculation and Recording of Radioactive Liquid Releases for the release of Liquid Waste Distillate Storage Tank #14.

R-54 is operable and aligned to WOST #14

WOST #14 has been properly recirculated and sampled by Chemistry.

Chemistry sample results have been obtained as follows:

o Total Gamma Activity= 4E-5 µCi/ml o Allowable Diluted Concentration= 5.31 E-7 µCi/ml o Boron Concentration = 1600 ppm Tank Level 75 inches o Tank Volume 17446 gallons

Release valve alignment has been reviewed SAT.

1 of 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Required Materials: 2-SOP-5.1.5; Calculation and Recording of Radioactive Liquid Releases.

Completed Radioactive Liquid Release Permit Form for WOST #14 Monitor Tank General

References:

2-SOP-5.1.5; Calculation and Recording of Radioactive Liquid Releases.

Completed Radioactive Liquid Release Permit Form for WOST #14 Monitor Tank Initiating Cue: Review the provided manually calculated Liquid Release Permit Form for the release of WOST #14 and authorize the release as the CRS.

Time Critical Task: No Validation Time: 29 minutes Task Standard: Student reviews the manually calculated Liquid radioactive Waste Release Permit Form and determines that the calculations for most restrictive discharge rate are incorrect based on an incorrect availaole dilution flow used in the calculations.

2of10

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark'\/)

"11. Performance Step: DETERMINE Available Dilution Flow {B) per Attachment 7 and RECORD result on permit:

Standard: Student determines that the recorded available dilution flow for release (B) is incorrect. Permit has recorded 420,000 gpm, however with only three circulating water pumps operating in slow speed the flow should be only 252,000 gpm. This is determined by using Table 2.

(84,000 gpm X 3)

NOTE: The incorrect value is 3 X 140,000 gpm (high speed flowrate).

Comment: If student reports this discrepancy to you as the evaluator, cue him to continue to review the calculations on the permit and update the results if necessary using the correct dilution flow rate.

2. Performance Step: Determine that Chemistry sample results have been properly transcribed on the permit:

o Total Gamma Activity= 4E-5 µCi/ml o Allowable Diluted Concentration= 5.31 E-7 µCi/ml o Boron Concentration = 1600 ppm o Tank Level 75 inches o Tank Volume 17 446 gallons Standard: Student recognizes that the Chemistry sample results have been properly transcribed on the permit Comment: All chemistry sample results have been properly recorded on the permit.

3. Performance Step: Determine that pounds of Boron correct on permit:

o Boron Concentration = 1600 ppm o Tank Volume 17446 gallons Standard: Determine correct 232 pounds of boron correct.

Comment:

3of10

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark..../)

..J 4. Performance Step: Determine that Maximum Chemical Release Rate {Re) is NOT correct because dilution flowrate is not correct o Boron Concentration = 1600 ppm o Available Dilution Flowrate should be 252,000 gpm o Resulting dilution flowrate should be 157 gpm Standard: Determine 262 gpm incorrect.

Correct values should be 157 gpm Comment: .

4of10

Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)

..J 5. Performance Step: DETERMINE Most Restrictive Release Rate (R) as follows:

1. CALCULATE the Radioactive Release Rate (Rr) 420,000 X 5.31E-7+4.0E-5 =5575 gpm Not Correct Not Critical 252,000 X 5.31 E-7 + 4.0E-5 = 3345 gpm Correct

2. SELECT the Most Restrictive Discharge rate (R) 157 gpm instead of previously calculated 250 gpm.

Critical Standard: Student determines that the Most Restrictive Discharge Rate of 157 gpm is less than the pump capacity (250 gpm)

Correct numbers are as follows:

1. Permissible Radioactive Release Rate (Rr) =

3345+/-50 gpm instead of previous calculated value of 5575 gpm.

2. Permissible Chemistry Release Rate (Re) = 157 +/-

2 gpm instead of the previously calculated 247 gpm.

=

3. Most Restrictive Release Rate (D) 157+/- 2 gpm instead of the previously selected value of 247 gpm.

Comment: Additional actions are required for dilution flow less than 250 gpm.

Borrow dilution flow from Unit 3 and recalculate

Obtain more dilution flow Unit 1 or Unit 2

Throttle discharge of tank to ensure discharge flow rate remains below most restrictive release rate

Return tank to holdup system

4. Performance Step: IF R-54 is in service, THEN CALCULATE maximum Radiation Monitor Alarm AND RECORD result on permit.

Standard: Student calculates new alarm and alert setpoints for R-54. New calculated alarm setpoint is slightly higher, so previous incorrect alarm setpoint is conservative and may be left at the previously selected setpoint.

=

252000 X 5.31E-7 + 157 8.52E-4 Correct Calculation. Not Critical 424000 X 5.31 E-7 + 250 =8.94E-4 Incorrect Calculation. Not Critical Comment:

5of10

Appendix C Page6 Form ES-C-1 Terminating Cue: JPM Complete 6of10

Appendix C Page 7 Form ES-C-1 RADIOACTIVE LIQUID RELEASE PERMIT INITIAL PERMIT# 160060 TANK ID 14WDST Tank Level:--1§___ (Inches) 17446 Volume (V),

gal RECIRC RATE 150 GPM Recirc Start: Today (Date) 00:00 (Time)

Recirc Stop: Today (Date) 08:00 (Time)

Chemistry Sample No. 6122 Sample Collection Todav (Date) 7:45 <Time)

Gamma Activity without Gas and Tritium is less than the admin limit of SMM-CY-001: Yes I No Total Gamma Activity 4.0E-5 µCi/ml Allowed Diluted Concentration (ADC) 5.31E-7 µCi/ml 3 Unit 2 Circulators TOTAL DILUTION FLOW (T) 252,000 (GPM) From: 0 Unit 3 Circulators 0 Service Water Pumps BORON: 1600 x 17446 x 8.33E-6 = 232 pounds ppm B tank vol (V), gal Maximum Chemical Release Rate (Re)= ( 252,000 x 1 ppm)+ 1600 = 157 gpm Avail Oil Flow (B), gpm ppm B Radioactive Release Rate: (Rr) = ( 252,000 x 5.31E-7 ) + 4.0E-5 = 3345 gpm Avail Oil Flow (B), gpm ADC, uCi/ml Gamma Act (C), uCi/ml Most Restrictive Release Rate (R) = 157 gpm (pump capacity most limiting)

Rad Monitor # 54 SOURCE CHECKED _x_ OPERABLE _lLYES - - NO (IF NO, COMPLETE ATT 3)

Maximum Alarm Setpoint = ( 252,000 x 5.31E-7 ) + 157 = 8.52E-4 uCi/ml Avail Oil Flow (B), gpm ADC, uCi/ml Most Restrictive Release Rate (R), gpm Actual Alarm Setpoint = 8.0E-4 uCi/ml Warn Setpoint = 6.0E-4 uCi/ml DISCHARGE FLOW METER & RECORDER OPERABLE _x_YES - - NO (IF NO, COMPLETE ATTACHMENT 3)

Release Authorized By: (Date)

RELEASE INITIATED: (Date) (Time)

RELEASE TERMINATED: (Date) (Time)

FINAL TK LEVEL: _ _ (Inches) gal TOTAL VOLUME RELEASED gal Remarks:

7of10

Appendix C Page 8 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: - - - - - - - - - - -

8of10

Appendix C Attachments Form ES-C-1

Unit is in MODE 5 for a forced outage.

Circulating Water Pumps Status:

o 21, 23, and 25 in service in slow speed.

o No other dilution flow sources are available or authorized.

A Liquid Radioactive Waste Release Permit Form has been completed manually IAW Section 4.1 of 2-SOP-5.1.5; Calculation and Recording of Radioactive Liquid Releases for the release of Liquid Waste Distillate Storage Tank #14.

R-54 is operable and aligned to WOST #14

WOST #14 has been properly recirculated and sampled by Chemistry.

Chemistry sample results have been obtained as follows:

o Total Gamma Activity= 4E-5 µCi/ml o Allowable Diluted Concentration= 5.31 E-7 µCi/ml o Boron Concentration = 1600 ppm Tank Level 75 inches o Tank Volume 17446 gallons

Release valve alignment has been reviewed SAT.

Initiating Cue:

Review the provided manually calculated Liquid Release Permit Form for the release of WOST #14 and authorize the release as the CRS.

9of10

Appendix C Attachments Form ES-C-1 ATTACHMENT 1 RADIOACTIVE LIQUID RELEASE PERMIT INITIAL PERMIT# 160060 TANK ID 14WDST Tank Level:_I§__ (Inches) 17446 Volume (V),

gal RECIRC RATE 150 GPM Recirc Start: Today (Date) 00:00 (Time)

Recirc Stop: Today (Date) 08:00 (Time)

Chemistry Sample No. 6122 Sample Collection Todav (Date) 7:45 <Time)

Gamma Activity without Gas and Tritium is less than the admin limit of SMM-CY-001: Yes I No Total Gamma Activity 4.0E-5 µCi/ml Allowed Diluted Concentration (ADC) 5.31E-7 µCi/ml 3 Unit 2 Circulators TOTAL DILUTION FLOW (T) 420,000 (GPM) From: 0 Unit 3 Circulators 0 Service Water Pumps BORON: 1600 x 17446 x 8.33E-6 = 232 pounds ppm B tank vol (V), gal Maximum Chemical Release Rate (Re)= ( 420000 x 1 ppm)+ 1600 = 262 gpm Avail Oil Flow (B), gpm ppm B Radioactive Release Rate: (Rr) = ( 420,000 x 5.31E-7 ) + 4.0E-5 = 5575 gpm Avail Oil Flow (B), gpm ADC, uCi/ml Gamma Act (C), uCi/ml Most Restrictive Release Rate (R) = 250 gpm (pump capacity most limiting)

Rad Monitor# 54 SOURCE CHECKED _x_ OPERABLE .JL.YES - - NO (IF NO, COMPLETE ATT 3)

Maximum Alarm Setpoint = ( 420,000 x 5.31E-7 ) + 250 = 8.94E-4 uCi/ml Avail Oil Flow (B), gpm ADC, uCi/ml Most Restrictive Release Rate (R), gpm Actual Alarm Setpoint = 8.0E-4 uCi/ml Warn Setpoint = 6.0E-4 uCi/ml DISCHARGE FLOW METER & RECORDER OPERABLE _X_YES - - NO (IF NO, COMPLETE ATTACHMENT 3)

Release Authorized By: (Date)

RELEASE INITIATED: (Date) (Time)

RELEASE TERMINATED: (Date) (Time)

FINAL TK LEVEL: _ _ (Inches) gal TOTAL VOLUME RELEASED gal Remarks:

10of10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point Unit 2 Task No: 1500010503 Task

Title:

Classify Event and Complete Form EP-1, Part 1 KIA

Reference:

1940002.4.41 Job Performance Measure SROAdmin 5 SR0-4.6 No:

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.

This is a TIME CRITICAL Job Performance Measure from the time you are told to begin until the time you classify the event. Also, from the time you classify the event until you complete the Radiological Emergency Data Form (EP-1, Part 1).

You will be allowed sufficient time to read the initial conditions and cue. You will then be allowed to ask questions about the conditions. However, once you review the E-Plan EALs, your clock starts.

Required Materials: IP-EP-120, Emergency Classification IPEC Emergency Action Level Charts I EAL Book Appropriate E-Plan Forms (EP-1, Part 1)

General

References:

IP-EP-120, Emergency Classification IPEC Emergency Action Level Charts I EAL Book Appropriate E-Plan Forms (EP-1, Part 1) 1 of 8

Appendix C Job Performance Measure Form ES-C-1 Worksheet Initial Conditions:

A Reactor Trip occurred approximately 15 minutes ago after 135 days @ 100% reactor power due to a major steam break on 21 SG in the Turbine Building. The MSIVs had to be closed manually from the Control Room, however, 21 MSIV did not close and cannot be closed remotely. 22 AFW Pump is tagged out.

The CRS has just informed you that he is transitioning from E-0 to FR-H.1 due to a RED condition on Heat Sink. The following conditions also exist:

21 SG is approaching dryout

21 RCP has been tripped due to high vibrations

23 ABFP is operating but has no flow indicated

RCS pressure is 1550 psig and increasing

RCS cold legs are 450°F and stable

High Head Safety Injection Pumps are operating

22 RHR pump is operating

All EDGs are operating

480V Bus 3A normal feeder has tripped and the 3A emergency supply breaker will not close.

All Containment conditions are normal.

The Turbine Building north end is not accessible but conditions are improving according to the Conventional NPO

l&C is investigating the cause of the 3A Bus problem and lack of 23 ABFP flow. A cutback controller problem is not suspected for the lack of 23 ABFP flow.

All SG WR levels are decreasing and below 20%.

There is no radiological release in progress.

Unit 3 remains stable at 100% power.

METEOROLOGICAL CONDITIONS:

Wind Speed: 0.9 meters/second Wind Direction: 285 degrees @ 10 meters Stability Class: c Initiating Cue:

The Shift Manager has become ill. You are the CRS and you must perform the duties of the Emergency Director until a replacement Shift Manager can arrive on site. You must Classify the event and Complete the NYS Radiological Emergency Data Form, Part 1.

This is a TIME CRITICAL JPM

Inform the examiner when you have classified the event.

Inform the examiner when you have completed the EP-1, Part 1 Form.

2 of 8

Appendix C Initial Conditions Form ES-C-1 Initiating Cue:

The Shift Manager has become ill. You are the CRS and you must perform the duties of the Emergency Director until a replacement Shift Manager can arrive on site. You must Classify the event and Complete the NYS Radiological Emergency Data Form, Part 1.

This is a TIME CRITICAL JPM

Inform the examiner when you have classified the event.

Inform the examiner when you have completed the EP-1, Part 1 Form.

You will be allowed sufficient time to read the initial conditions and cue. You will then be allowed to ask questions about the conditions. However, once you review the E-Plan EALs, your clock starts.

8 of 8

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point Unit 2 Task No: 0000420501 Task

Title:

Transfer to Hot Leg Recirculation KlA

Reference:

000011 EA 1. 13 Job Performance Measure No: SIM-A Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance x Actual Performance Classroom 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:

A Large Break LOCA occurred approximately 6.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ago.

The operating crew properly aligned Cold Leg Recirculation per 2-ES-1.3 Transfer to Cold Leg Recirculation using 21 and 22 Recirculation Pumps.

FSB Ventilation has been previously shutdown Required Materials: None General

References:

2-ES-1.4, Transfer to Hot Leg Recirculation Initiating Cue: You are the BOP and the CRS has directed you to align the Safety Injection System for Hot Leg Recirculation in accordance with ES-1 .4 up to step 20.

Time Critical Task: No Validation Time: 20 Minutes 1 of 12

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: The Safety Injection System is aligned for Hot Leg Recirculation.

2of12

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

1. Performance Step: Obtain Correct Procedure Standard: Obtains 2-ES-1.4 Transfer to Hot Leg Recirculation Comment:

2. Performance Step: Check Low Head Recirculation Flow Indicated Standard: Observes Flow indicated on Fl 946 A-0 on Panel SBF-2 Comment: Procedure Step 1

3. Performance Step: Check if FSB Ventilation previously shutdown Standard: Given in Initial Conditions FSB Ventilation is Shutdown Comment: 2

...J 4. Performance Step: Close Cold Leg Injection Valve Standard: Locate and rotate switch to close for either MOV 856A or 856E on Panel SBF-2 Comment: Procedure Step 3 3of12

Appendix C Page4 Form ES-C-1 Performance Information (Denote critical steps with a check mark--./)

.../ 5. Performance Step: Open Hot Leg Injection Valve to Loop 23 Standard: Locate and rotate switch for MOV-8568 on Panel SBF-2 Comment: Procedure Step 4

.../ 6. Performance Step: Close Cold Leg Injection Valve Standard: Locate and rotate switch to close for either MOV 856C or 8560 on Panel SBF-2 Comment: Procedure Step 5

.../ 7. Performance Step: Open Hot Leg Injection Valve to Loop 21 Standard: Locate and rotate switch for MOV-856F on Panel SBF-2 Comment: Procedure Step 6 4of12

Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

8. Performance Step: Check Recirculation System Alignment Standard: Locate indications for MOV 746 and 747 on Panel SBF-1 or SGF and observe one closed Observe Safety Injection Recirc Switch 6 is OFF on Panel SBF-1 Comment: Procedure Step 7 5of12

Appendix C Page6 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

.../ 9. Performance Step: Check System Alignment for Starting SI Pumps Standard: Locates and Observes 21 and 22 Recirculation Pump Running on SBF-1 Place 21 OR 22 Recirculation Pump in trip pullout Locates and Observes SI Pump Miniflow valves MOV-842 and 843 closed on SBF-1 Locate and rotate switch for MOV-888A & 8888 to OPEN on SBF-1 Locate and place toggle switch for SI Pump Low Suction Pressure Alarm to ON on SBF-1 Locate and Observe Recirculation Switch 7 in ON on SBF-1 Place Recirculation Switch 7 to OFF on SBF-1 Comment: Only the steps for placing recirc pump in trip pullout opening MOV-888A/B and recirculation switch 7 are critical for this step.

Procedure Step 8

10. Performance Step: Check SI Suction Pressure > 75 psig Standard: Locate and observe SI Pump Suction Pressure Indicator Pl-947 > 75 psig on Panel SBF-2 Comment: Candidate may also observe SI Pump Suction Low Pressure Alarm CLEAR on Panel SBF-1 Procedure Step 9 6of12

Appendix C Page 7 Form ES-C-1 Performance Information (Denote critical steps with a check mark '°'1) 11 . Performance Step: Observe Caution before Step 10 Standard: Caution is Not Applicable for this condition.

Comment:

.../ 12. Performance Step: Start 23 SI Pump Standard: Locate and Observe Bus 6A is Energized by OFF SITE POWER Locate and rotate switch for 23 Safety Injection Pump to START on Panel SBF-2.

Comment: Procedure Step 10

.../ 14. Performance Step: Verify 746 and 747 CLOSED Standard: Locate indications for MOV 746 and 747 on Panel SBF-1 or SGF and observe one valve closed.

Rotate switch for Opened valve to CLOSE on Panel SGF-1 Comment: Procedure Step 11 7of12

Appendix C Page 8 Form ES-C-1 Performance Information (Denote critical steps with a check mark -.J)

15. Performance Step: Check SI Pump Suction Pressure Greater than 75 psig Standard: Locate and observe SI Pump Suction Pressure Indicator Pl-947 > 75 psig on Panel SBF-2 Comment: Candidate may also observe SI Pump Suction Low Pressure Alarm CLEAR on Panel SBF-1 Procedure Step 12

16. Performance Step: Observe Caution before Step 13 Standard: Caution is Not Applicable for this condition.

Comment:

17. Performance Step: Start 21 SI Pump Standard: Locate and Observe Bus 5A is Energized by OFF SITE POWER Locate and rotate switch for 21 Safety Injection Pump to START on Panel SBF-2.

Comment: 21 SIP immediately trips on over current.

Procedure Step 13 8of12

Appendix C Page 9 Form ES-C-1 Performance Information (Denote critical steps with a check mark -.J)

19. Performance Step: Verify Adequate Recirculation Flow Standard: Observe Core Exit Thermocouples Stable or Decreasing on QSPDS Comment: Procedure Step 20 Terminating Cue: JPM Complete 9of12

Appendix C Page 10 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ __

10 of 12

Appendix C Simulator Setup Form ES-C-1 .

Initialize Simulator to any 100% Power IC Insert Malfunction MAL-RCS001A Rupture 21 Loop Cold Leg Perform Actions of E-0, E-1 and ES-1.3 when conditions require.

Insert Malfunction MOT-SIS001A Overcurrent Trip 21 SIP after transfer to cold leg recirc complete.

11 of 12

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

A Large Break LOCA occurred approximately 6.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ago.

The operating crew properly aligned Cold Leg Recirculation per 2-ES-1.3 Transfer to Cold Leg Recirculation using 21 and 22 Recirculation Pumps.

FSB Ventilation has been previously shutdown Initiating Cue:

You are the BOP and the CRS has directed you to align the Safety Injection System for Hot Leg Recirculation in accordance with ES-1.4 up to step 20.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 2 Task No: 0001080521 Task

Title:

Initiate Bleed and Feed Cooling per FR-H.1 KIA

Reference:

OOWE05A101 Job Performance Measure Sim-B (4.1/4.0) No:

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing: Performance 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: A Reactor Trip has occurred with the loss of Auxiliary Feedwater. All required actions of E-0 Reactor Trip or Safety Injection were complete and the CRS transitioned to ES-0.1 Reactor Trip Response. A RED Path on Heat Sink was identified and the CRS transitioned to FR-H.1 Response to Loss of Secondary Heat Sink. Off site power has remained available throughout the event. The average of the three lowest Wide Range Steam Generator levels is < 20%; RCPs were tripped.

Required Materials: FR-H.1 Response to Loss of Secondary Heat Sink General

References:

FR-H.1 Response to Loss of Secondary Heat Sink Initiating Cue: The CRS has directed you to immediately perform Steps 11 through 16 of FR-H.1 Response to Loss of Secondary Heat Sink.

Time Critical Task: N/A Validation Time: 5 Minutes 1 of 8

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: All required actions of Steps 11 through 16 of FR-H.1 Response to Loss of Secondary Heat Sink are complete 2 of 8

Appendix C 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

.../1. Performance Step: Actuate Safety Injection Standard: Safety Injection Pushbuttons for Train A and Train B are depressed Comment: Procedure Step 11

2. Performance Step: Check Power Supply to Charging Pumps Standard: Checks 480V Susses are powered from offsite power Comment: Procedure Step 12

3. Performance Step: Check If Charging Flow has been established Standard: Check CCW for Charging Pumps AVAILABLE YES Check at least one Charging Pump running NO Determines CCW was never lost to RCPs CUE: If asked CCW was never lost to RCPs. SM determines RCP seals are not affected.

Comment: Procedure Step 13 3 of 8

Appendix C 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

-./4. Performance Step: Establish Maximum Charging Flow Standard: Align Charging to RWST

Open LCV-1128 Charging pump suction from RWST

Close LCV-112C Charging pump suction from VCT Start additional charging pumps Starts all Charging Pumps

Set controllers to minimum (Not Critical)

Rotate all 3 pump switches to start Places Charging Pump Speed Controllers in MANUAL Opens HCV-142 Adjusts Charging Pumps Speed to Maximum Comment: Procedure Step 13c

5. Performance Step: Verify RCS Feed Path Standard: Check All Three pumps running at maximum flow Checks all SI Pumps are running Checks MOV-851A and MOV-851 Bare both OPEN Checks RHR Hx CCW outlet valves 822A and 8228 are OPEN Checks RHR MOVs 746 and 74 7 are OPEN Check SI feed path - Aligned Comment: Procedure Step 14 4 of 8

Appendix C 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark -1)

.../6. Performance Step: Establish RCS Bleed Path Standard: Verifies power is available to PRZR PORV block valves (Not critical)

Opens BOTH PORV block valves Opens PRZR PORV 456 Identifies PRZR PORV 455C did not open Comment: Procedure Step 15

.../1~. Pftrfoi'hi~nce;stit:>r **V~rifY~Adeg,9ar1:£t~' Bt**c:l .Pitfl;L, '\*~.. .**.or.*

. ..* .. . }'.: :;;;Ji! ..*..* **... . . (~ *<*1¥;~):,. /

i :At:."' .

2¥;f0. i ;:if,, . ..

Sfandarcf~: Verif~~:0~0"ftli~FlZR PORV.9l?ckfiyal~e&'arf ;5)P~N.e<Notqri~fe~I}

...Identifies PRZRPOR"~6~Cd1d.J1oto~ert(Not Cnfical) r" 0*::

.Plsp~tcl'lt~PQto M9C~2G~~~B@ffc:l e,r:aergt,~e t19V~3, ~o. ant!; .

Hcv:.:a101 ... ;:.,. *. /'Y p*:* '!!,;~** . w,; *. *

OPENS HCV~310crand"HCV~l10f "i*'L ..*.

' "'"',J' '/,,:1;:~,:-s:;:; '"""'1"' -<,;,

Terminating Cue: JPM Complete 5 of 8

Appendix C 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No. Foxtrot 2011 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __

6 of 8

Appendix C Simulator Setup Form ES-C-1 SIMULATOR SET-UP Reset to 100% IC Insert malfunction AOV-RCS002A to CLOSE PCV-455C PZR POWER OPERATED RELIEF VALVE Insert malfunction MOC-AFW001 to ASIS AF1 AUX FEEDWATER PUMP MOTOR N0.21 Insert malfunction MOC-AFW002 to ASIS AF3 AUX FEEDWATER PUMP MOTOR N0.23 Insert malfunction CVH-ATS019A to CLOSE PCV-1139 AUX.F.W.PMP. N0.22 STM.STOP VLV Insert remote LOA-CFW190 to 99.00000 on event 1 BFD-2-21-H BFP 21 DISCHARGE STOP VALVE Insert remote LOA-CFW191 to 99.00000 on event 1 BFD-2-22-H BFP 22 DISCHARGE STOP VALVE Insert remote LOA-EPS431 to CLOSED on event 2 MCC26A-7MR RX VENT VLV 3100 BKR OPEN/CLOSE Insert remote LOA-EPS523 after 10 to CLOSED on event 2 MCC26B-7MR RX VENT VLV 3101 BKR OPEN/CLOSE Activate Trigger 1 Perform E-0 Reactor Trip or Safety Injection Steps 1-4 Transition to FR-H.1 Response to Loss of Secondary Heat Sink Step 1 Trip Reactor Coolant Pumps SNAP IC and Password protect 7 of 8

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

A Reactor Trip has occurred with the loss of Auxiliary Feedwater. All required actions of E-0 Reactor Trip or Safety Injection were complete and the CRS transitioned to ES-0.1 Reactor Trip Response. A RED Path on Heat Sink was identified and the CRS transitioned to FR-H.1 Response to Loss of Secondary Heat Sink. Off site power has remained available throughout the event. The average of the three lowest Wide Range Steam Generator levels is< 20%; RCPs were tripped.

Initiating Cue:

The CRS has directed you to immediately perform Steps 11through16 of FR-H.1 Response to Loss of Secondary Heat Sink.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 2 Task No: 0590140421 Task

Title:

Reset Track and Hold Job Performance Measure No: SimC KIA

Reference:

059000A.2.11 (3.0/3.3)

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:

A failure has occurred in 22 MBFP Speed Controller resulting in activation of Track and Hold.

The Shift Manager has determined that continued operation of the MBFP is desired.

Required Materials: None General

References:

2-ARP-FBF Initiating Cue: The CRS has directed you to reset Track and Hold in accordance with 2-ARP-FBF.

Time Critical Task: No Validation Time: 15 Minutes Task Standard: Track and Hold has been reset 1of8

Appendix C Page 2 Form ES-C-1 c Performance Information (Denote critical steps with a check mark,/)

1. Performance Step: Obtain correct procedure Standard: 2-ARP-FBF Comment:

2. Performance Step: Observe Caution and Note prior to step 3.2.1 Standard: Observes Caution and Note Comment:

3. Performance Step: Determine if Feed Pump is to remain in service Standard: Given in Initial Conditions CUE: IF asked, CRS directs the MBFP to remain in service.

Comment: Step 3.2.1

4. Performance Step: Determine if Percent Feedwater signal and Percent Hold signal are within 4% of each other Standard: Determines %FW and %Hold NOT within 4%

Comment: Step 3.2.1.1 c

2 of 8

Appendix C Page 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: - - - - - - - - - - - -

6 of 8

Appendix C Simulator Setup Form ES-C-1 Simulator Setup Reset to IC-11 Insert Malfunction:

Insert Override SWl-PC5050E SC-409 Fuse in 22 MBFP Controller to OFF Acknowledge alarm on Signal Processor Cabinet Allow Simulator to Run verify HOLD LED lit.

Delete Malfunction SWl-PCS050E Ensure HOLD LED still Lit.

Insert Malfunction CNH-PC5042B MCB CTRLR AUTO/MAN: SC-409 FEEDWATER PUMP 22 to 10 Ensure PERCENT FEEDWATER signal is greater than 4% Less than PERCENT TRACK & HOLD.

Rotate OVR POS potentiometer to MINIMUM Take Snap if performing more than once.

7 of 8

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

A failure has occurred in 22 MBFP Speed Controller resulting in activation of Track and Hold.

The Shift Manager has determined that continued operation of the MBFP is desired.

Initiating Cue: The CRS has directed you to reset Track and Hold in accordance with 2-ARP-FBF.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 2 Task No: 0030100401 Task

Title:

RCP #1 Seal Failure Actions KIA

Reference:

003000A201 Job Performance Measure No: Sim-D RO - 3.5 SRO - 3.9 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: Plant is at indicated power level. A malfunction is in progress on 24 RCP.

Required Materials: 2-AOP-RCP-1 General

References:

2-AOP-RCP-1, Reactor Coolant Pump Malfunctions Initiating Cue: You are the ATC and the CRS has directed you to perform the actions of AOP-RCP-1, Reactor Coolant Malfunction for the indicated malfunction on 24 RCP.

Time Critical Task: No Validation Time: 10 minutes Task Standard: AOP-RCP-1 actions completed.

1of7

.I Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

Plant is at indicated power level. A malfunction is in progress on 24 RCP.

Initiating Cue:

You are the ATC and the CRS has directed you to perform the actions of AOP-RCP-1, Reactor Coolant Malfunction for the indicated malfunction on 24 RCP.

Facility: Indian Point Unit 2 Task No:

Task

Title:

Transfer 6.9KV buses 1 through 4 to Buses 5 and 6 (Station Aux Transformer)

KIA 062000A4.01 Job Performance Measure No: Sim E

Reference:

(3.3/3.1)

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:

Plant Shutdown is in progress. Load has been stabilized at - 35 MWe.

Buses 5 and 6 are energized from the Station Auxiliary Transformer.

Buses 1 - 4 are energized from the Unit Auxiliary Transformer Required Materials: 2-SOP-27.1.4 and blank 2- DSR-1 General

References:

2-SOP-27.1.4 Initiating Cue: You are directed to transfer 6.9KV buses 1, 2, 3, 4 to the Station Aux Transformer in accordance with 2-SOP-27.1.4. All applicable prerequisites per 2-SOP-27.1.4 have been met.

Time Critical Task: No Validation Time: 10 Minutes

Task Standard: Susses 1 - 4 are energized from the Station Auxiliary Transformer.

Performance Information (Denote critical steps with a check mark..../)

1. Performance Step: Obtain and review 2-SOP-27 .1.4 Standard:

Comment:

2. Performance Step: Ensure LESS THAN 50 volt difference between Station and Unit Auxiliary Transformer Tap Changers in MANUAL and adjusting.

Standard: Less than 50 volt difference between Station and Unit Auxiliary Transformer Comment: This step is critical if voltage difference is > 50V Procedure Step 4.1.2.1

'1 3. Performance Step: Place 6900V Bus No. 1 synchroscope in Bus 1-Bus 5 position.

Standard: Synchroscope rotated to Bus 1-Bus 5 position Comment: Procedure Step 4.1.2.2

'1 4. Performance Step: If Synchroscope is at 12 o'clock then close Bus 1-5 tie breaker UT1 -ST5 Standard: Rotate Switch to CLOSE Red Light ON Green Light OFF Comment: Procedure Steps 4.1.2.3 & 4.1.2.4

Performance Information (Denote critical steps with a check mark "\/)

v5. Performance Step: OPEN 6900V Bus No. 1 Normal Feed Breaker UT-1 Standard: Rotate Switch to OPEN Green Light ON Red Light OFF Comment: Procedure Step 4.1.2.5

6. Performance Step: Place 6900V Bus No. 1 synchroscope switch to OFF Standard: Rotate Synchroscope switch to OFF Comment: Procedure Step 4.1.2.6

7. Performance Step: Verify Station Aux Transformer and Unit Aux Transformer supplying voltage in the normal range specified in 2-DSR-1 Standard: Normal 7050 - 7200 Min/Max 7025 I 7250 Comment: 2-DSR-1 may be referenced at this time but not required.

8. Performance Step: Ensure LESS THAN 50 volt difference between Station and Unit Auxiliary Transformer Tap Changers in MANUAL and adjusting.

Standard: Less than 50 volt difference between Station and Unit Auxiliary Transformer Comment: This step is critical if voltage difference is> 50V Procedure Step 4.1.3.1

Performance Information (Denote critical steps with a check mark '1)

'\J 9. Performance Step: Place 6900V Bus No. 2 synchroscope in Bus 2-Bus 5 position.

Standard: Synchroscope rotated to Bus 2-Bus 5 position Comment: Procedure Step 4.1.3.2

'\J 10. Performance Step: If Synchroscope is at 12 o'clock then close Bus 2-5 tie breaker UT2-ST5 Standard: Rotate Switch to CLOSE Red Light ON Green Light OFF Comment: Procedure Steps 4.1.3.3 & 4.1.3.4

'\J 11. Performance Step: OPEN 6900V Bus No. 2 Normal Feed Breaker UT-2 Standard: Rotate Switch to OPEN Green Light ON Red Light OFF Comment: Procedure Step 4.1.3.5

12. Performance Step: Place 6900V Bus No. 2 synchroscope switch to OFF Standard: Rotate Synchroscope switch to OFF Comment: Procedure Step 4.1.3.6

Performance Information (Denote critical steps with a check mark '1)

13. Performance Step: Verify Station Aux Transformer and Unit Aux Transformer supplying voltage in the normal range specified in 2-DSR-1 Standard: Normal 7050 - 7200 Min/Max 7025 I 7250 Comment:

NOTE: JPM may be terminated at this time at Evaluators discretion.

14. Performance Step: Ensure LESS THAN 50 volt difference between Station and Unit Auxiliary Transformer Tap Changers in MANUAL and adjusting.

Standard: Less than 50 volt difference between Station and Unit Auxiliary Transformer Comment: This step is critical if voltage difference is > SOV Procedure Step 4.1.4.1

--./ 15. Performance Step: Place 6900V Bus No. 3 synchroscope in Bus 3-Bus 6 position.

Standard: Synchroscope rotated to Bus 3-Bus 6 position Comment: Procedure Step 4.1.4.2

Performance Information (Denote critical steps with a check mark .J)

..J 16. Performance Step: If Synchroscope is at 12 o'clock then close Bus 3-6 tie breaker UT3-ST6 Standard: Rotate Switch to CLOSE Red Light ON Green Light OFF Comment: Procedure Steps 4.1.4.3 & 4.1.4.4

..J 17. Performance Step: OPEN 6900V Bus No. 3 Normal Feed Breaker UT-3 Standard: Rotate Switch to OPEN Green Light ON Red Light OFF Comment: Procedure Step 4.1.4.5

18. Performance Step: Place 6900V Bus 3 synchroscope switch to OFF Standard: Rotate Synchroscope switch to OFF Comment: Procedure Step 4.1.4.6

19. Performance Step: Verify Station Aux Transformer and Unit Aux Transformer supplying voltage in the normal range specified in 2-DSR-1 Standard: Normal 7050 - 7200 Min/Max 7025 I 7250 Comment:

Performance Information (Denote critical steps with a check mark '1)

20. Performance Step: Ensure LESS THAN 50 volt difference between Station and Unit Auxiliary Transformer Tap Changers in MANUAL and adjusting.

Standard: Less than 50 volt difference between Station and Unit Auxiliary Transformer Comment: This step is critical if voltage difference is > 50V Procedure Step 4.1.5.1

-.J 21. Performance Step: Place 6900V Bus No. 4 synchroscope in Bus 4-Bus 6 position.

Standard: Synchroscope rotated to Bus 4-Bus 6 position Comment: Procedure Step 4.1.5.2

-./ 22. Performance Step: If Synchroscope is at 12 o'clock then close Bus 4-6 tie breaker UT4-ST6 Standard: Rotate Switch to CLOSE Red Light ON Green Light OFF Comment: Procedure Steps 4.1.5.3 & 4.1.6.4

Performance Information (Denote critical steps with a check mark "1)

" 23. Performance Step: OPEN 6900V Bus No. 4 Normal Feed Breaker UT-4 Standard: Rotate Switch to OPEN Green Light ON Red Light OFF Comment: Procedure Step 4.1.5.5

24. Performance Step: Place 6900V Bus 4 synchroscope switch to OFF Standard: Rotate Synchroscope switch to OFF Comment: Procedure Step 4.1.5.6

25. Performance Step: Verify Station Aux Transformer and Unit Aux Transformer supplying voltage in the normal range specified in 2-DSR-1 Standard: Normal 7050 - 7200 Min/Max 7025 I 7250 Comment:

Terminating Cue: JPM Complete

VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and d a t e : - - - - - - - - - - - -

Simulator Setup Initial Conditions:

Plant Shutdown is in progress. Load has been stabilized at - 35 MWe.

Buses 5 and 6 are energized from the Station Auxiliary Transformer.

Buses 1 - 4 are energized from the Unit Auxiliary Transformer Initiating Cue:

You are directed to transfer 6.9KV buses 1, 2, 3, 4 to the Station Aux Transformer in accordance with 2-SOP-27.1.4. All applicable prerequisites per 2-SOP-27.1.4 have been met.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point Unit 2 Task No: 0390030401 Task

Title:

Instrument Failure Steam Flow KIA

Reference:

035000A301 (4.0/3.9) Job Performance Measure No: SIM-F 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:

Reactor is at indicated power

Steady State, Equilibrium Xenon

No equipment out of service Required Materials: None General

References:

2-AOP-INST-1 Instrument/Controller Failures Initiating Cue: You are to take the appropriate actions to stabilize the plant in response to indications and annunicators.

Time Critical Task: No Validation Time: 20 Minutes Task Standard: 22 SG FRV in manual controlling SG level 1of8

Appendix C Page2 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

1. Performance Step: Determine an Instrument failure has occurred.

Standard: Correctly identifies 22 SG channel B failure Comment:

2. Performance Step: Rotate affected controlling channel selector switches to channel A Standard: Rotate both switches to A position STM GEN NO 22 STEAM FLOW CONTROL TRANSFER Comment: The Steam Flow switch will not function. The Feed Reg Valve must be placed in manual to control level

..J* 3: Perf&rminc.r$tep::v Re&tq,f! affeete(f:sG;le~~fto P1'.09rJm~~i; ' .

. , . '..cJPt *** ********** '" .}'~&: ....... /c.** .;,;.;:

.Stpnda,rd=':;:;,.

>- ,,~., ,*--._;(:.

FW;,r:egulat~t gfaced'rnlll'~riual*a~~'YeYel:

,, , -';:'?'.*., .:-, -,,: f-:, .-<i::.o:<;~~,*,~ '.:~n:,,-- >>., =. ;,- , >".:;:**;r, , *,

re'tc)rett~

.,-<J<.* ,.,,

nbtti.~1:

2 of 8

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

NOTE:

Candidate may place Main Boiler Feed Pump Master Controller to Manual.

Controlling Steam Flow is an input to the speed control system. The action is not critical (necessary). The control system will slow the feed pumps, but they will still maintain adequate feed flow.

4. Performance Step: Return controls used to stabilize plant conditions to auto as desired.

Standard: Determine that Main Feed Reg Valve must remain in manual If candidate asks for direction regarding returning controls to automatic, ask "What actions do you recommend"?

Comment: Step 4.67

5. Performance Step: Refer to appropriate Tech Spec as described in the AOP.

Standard: NA CUE: Inform operator as CRS that the proper Tech Spec Tables have been referred to.

Comment: Step 4.68 3 of 8

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

6. Performance Step: Review notes prior to step 4.69 Standard: Notes reviewed Comment:

.../ 7. Performance Step: Verify placing Steam Flow Mismatch Bistable Trip Switch for the failed channel in trip will not cause a Rx Trip or Safety Injection and trip the appropriate Steam Flow Mismatch Bistable Trip Switch for the failed channel Standard: IAW Attachment 4 of 2-AOP-INST-1, Loop 2B SF>FWF in White rack A-10 is placed in trip position.

CUE: Inform operator as CRS that ALL bistables associated with failed channel are to be tripped.

Once SG level is stabilized inform operator that remainder of watch will monitor plant while bistables are tripped.

Comment: Step 4.69 and Attachment 4 4 of 8

Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..../)

8. Performance Step: Review notes prior to step 4. 70 Standard: Notes reviewed Comment:

.../ 9. Performance Step: Verify placing High Steam Flow Bistable Trip Switch for the failed channel in trip will not cause a Rx Trip or Safety Injection and trip the appropriate High Steam Flow Bistable Trip Switch for the failed channel.

c Standard: IAW Attachment 5 of 2-AOP-INST-1, Loop 2B High SF SI in White rack A-10 is placed in trip position.

CUE: Inform operator as CRS that ALL bistables associated with failed channel are to be tripped If required, inform operator that failed channel will not be repaired at this time.

Comment: Step 4.70 and Attachment 5 Terminating Cue: JPM Complete 5 of 8

\

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

Reactor at indicated power.

Steady State, equilibrium Xenon.

No equipment out of service.

Initiating Cue:

You are to take the appropriate actions to stabilize the plant in response to indications and an nu nicators.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 2 Task No: 0730300121 Task

Title:

Change Radiation monitor setpoint (SOP-12.3.2)

KIA

Reference:

073000A402 Job Performance Measure No: Sim-G Examinee: NRG Examiner:

Facility Evaluator: Date:

Method of testing: Performance 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:

Preparations are being made to release 23 Large Gas Decay Tank

The release permit has been prepared and requires R-44 alarm setpoint to be set at 9.00 x 10-3 µci/cc Required Materials: SOP-12.3.2, Digital Radiation Monitoring System Operation (Local or SRO)

SOP-12.3.3 Radiation Monitor Setpoint Control General

References:

SOP-12.3.2, Digital Radiation Monitoring System Operation (Local or SRO)

SOP-12.3.3 Radiation Monitor Setpoint Control Initiating Cue: You are the ATC and the CRS has directed you to reset R-44 Actual Alarm 3

setpoint to 9.00x 10- µCi/cc in accordance with 2-SOP-12.3.2, Digital Radiation Monitor System Operation (Local or SRO)

Time Critical Task: N/A Validation Time: 10 Minutes Task Standard: R-44 Alarm setpoint changed to 9.00x 10"3 µCi/cc.

1 of 7

Appendix C 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..,/)

1. Performance Step: Obtain correct procedure Standard: Obtains 2-SOP-12.3.2 Comment:

2. Performance Step: Review Precautions and Limitations Standard: P&Ls reviewed Comment:

-./3. Performance Step: Prepare SRO for data entry per step 4.7 (NOTE:

procedure step refers to step 4.6 as an option. This step is used if alarm reset is performed locally)

Standard: Verifies remote light is lit at SRO Set Program mode key switch to ENTER DATA Comment: Setting key switch is only critical action Procedure Steps 4.8.1.1, 4. 7.1 and 4. 7 .2

4. Performance Step: Observe NOTE before step 4.8.1.2 Standard: Reviews NOTE Comment:

2 of 7

Appendix C 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark..../)

5. Performance Step: Display current setpoint Press "CH" Key Enter channel Number "O" Press "FUNC" key Enter "O" Press "DISP" key Standard: "CH" key depressed "O entered for channel number "FUNC" key depressed "O" entered "DISP: key depressed Comment: Procedure Step 4.8.1.2

6. Performance Step: Observe NOTE before step 4.8.1.3 Standard: Reviews NOTE Comment:

3 of 7

Appendix C 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

.../ 7. Performance Step: Enter New Setpoint Press "CH" Key Enter channel Number "O" Press "FUNC" key Enter "O" Press "DATA" key Enter new value (three digits) without decimal point "900" Press EXP key Press "DISP OP" key Enter exponent (two digits) "03" Press "ENTER" key Standard: "CH" key depressed "0" entered for channel "FUNC" key depressed "0" entered "DATA" key depressed "900" entered for setpoint "EXP" key depressed "DIS OP" key depressed "03" entered for exponent "ENTER" key depressed Comment: Procedure Step 4.1.8.3

.../9. Performance Step: Place the program Mode Key Switch to RUN on the SRO when data has been entered Standard: Mode Key Switch placed to RUN Comment: Procedure Step 4.1.8.4 Terminating Cue: JPM is complete 4 of 7

Appendix C 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: - - - - - - - - - - - -

5 of 7

Appendix C Simulator Setup Form ES-C-1 SIMULATOR SET-UP Reset to any IC 6 of 7

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

Preparations are being made to release 23 Large Gas Decay Tank

The releaswe permit has been prepared and requires R-44 alarm setpoint to be set at 9.00 x 10-3 µci/cc Initiating Cue:

You are the ATC and the CRS has directed you to reset R-44 Actual Alarm setpoint to 9.00x 10-3 µCi/cc in accordance with 2-SOP-12.3.2, Digital Radiation Monitor System Operation (Local or SRO)

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point Unit 2 Task No: 0000300521 Task

Title:

Reset Containment Phase A KIA

Reference:

103000A.3.01 Job Performance Measure No: Sim H (3.9/4.2)

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:

A LARGE BREAK LOCA has just occurred.

All required actions of E-0, Reactor Trip or Safety Injection have been completed.

Safety Injection has been RESET in accordance with E-1, Loss of Reactor or Secondary Coolant.

Required Materials: None General

References:

2-E-1 Loss of Reactor or Secondary Coolant Initiating Cue: You are the BOP and the CRS has directed you to Reset Containment Isolation Phase A in accordance with E-1, Loss of Reactor or Secondary Coolant step 6.

Time Critical Task: No Validation Time: 10 Minutes Task Standard: Phase A is reset using Key Switches.

1 of 7

Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark .Y)

1. Performance Step: Obtain correct procedure Standard: Hand Candidate procedure Comment:

.../ 2. Performance Step: Place IVSW switches to OPEN Standard: 1410, 1413, SOV-3518 and SOV-3519 placed to OPEN on Panel SN Comment:Step 6.a

.../ 3. Performance Step: Place Containment Rad Monitor WCPS Valves control switch to OPEN Standard: Rad Mon WCPS Supply and Return valves switch to OPEN on Panel SN Comment: Step 6.b 2 of 7

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark'\/)

" 4. Performance Step: Place personnel and equipment hatch solenoids control switches to INCIDENT Standard: Verify Personnel and Equipment hatch solenoids control switches to INCIDENT Comment: Step 6.c Panel SMF

" 5. Performance Step: Place control switches for all remaining Phase A isolation valves to CLOSE Standard: All remaining Phase A switches to CLOSE on Panel SN Comment: Step 6.d Panel SNF

~ 6. Performance Step: Reset Phase A Standard: Depress Phase A reset buttons Train A and Train B one at a time Comment: Step 6.e Panel SNF 3 of 7

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

"' 7. Performance Step: Verify Phase A Reset Standard: Verify Phase A Not Reset Audible relays do not "Click" May go to relays to verify Comment: Step 6.f Panel SNF Terminating Cue: JPM Complete 4 of 7

Appendix C Page 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and d a t e : - - - - - - - - - - - -

5 of 7

Appendix C Simulator Setup Form ES-C-1 Reset to any 100% IC Insert Malfunction MAL RCS002B Loop 22 RCS Leak Severity Value= 1 AOV CVC004B Variable Position 201 Letdown lsol Valves Severity Value= 0 AOV CVC005B Variable Position 201 Letdown lsol Valves Severity Value= 0 Insert Override SWl-CVC036A 201/202 Letdown lsol Viv 201 Control Switch OPEN POSITION Allow Simulator to Run Perform actions of E-0, Attachment 1 and E-1 up to step 6.

Freeze Simulator.

Take a Snapshot if JPM to be performed more than once.

6 of 7

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

A LARGE BREAK LOCA has just occurred.

All required actions of E-0, Reactor Trip or Safety Injection have been completed.

Safety Injection has been RESET in accordance with E-1, Loss of Reactor or Secondary Coolant.

Initiating Cue:

You are the BOP and the CRS has directed you to Reset Containment Isolation Phase A in accordance with E-1, Loss of Reactor or Secondary Coolant step 6.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 2 Task No: 0840010521 Task

Title:

Perform the Required Actions to Trip the Reactor from the Cable Spreading Room 000068A 1. 14 Job Performance Measure KIA

Reference:

_(~4_.2_/4_.4~)_ _ _ __ No: In-Plant-I 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:

1. The CCR has been evacuated due to a fire and 2-AOP-SSD-1, Control Room Inaccessibility Safe Shutdown Control, has been implemented.

2. The reactor could not be tripped from the Control Room.

Required Materials: None General

References:

2-AOP-SSD-1, Control Room Inaccessibility Safe Shutdown Control Initiating Cue: The CRS has directed you to trip the reactor from the Cable Spreading Room in accordance with 2-AOP-SSD-1, Attachment 1.

Time Critical Task: No Validation Time: 15 minutes Task Standard: The reactor is tripped 1 of 6

Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark -V)

1. Performance Step: Obtains correct procedure and step Standard: 2-AOP-SSD-1, Attachment 1, Step 1 Comment:

2. Performance Step: Determine if Cable Spreading Room is accessible Standard: Determines Cable Spreading Room is accessible CUE: If requested, Cable Spreading Room is accessible Comment: Step 1.1

3. Performance Step: Trip reactor using Reactor Trip Breaker's local trip buttons Standard: Identifies RTA and RTB breaker push buttons indicates proper movement CUE: After simulated movement, breakers do NOT open Comment: Step 1.2 2 of 6

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark '\/)

-.J 4. Performance Step: Trip 21 Rod Drive MG Set Breaker Standard: Generator No.21 switch indicates proper direction of movement for PULLOUT Motor No.21 switch indicates proper direction of movement for PULLOUT NOTE: The first MG set breaker switch does not open. The second MG set breaker switch does open resulting in shutdown of its Rod Drive MG set CUE: Generator or Motor switch to Pull-Out successful, breaker is open.

NOTE: Steps 4 & 5 can be performed in any order Comment: Step 1.3 RNO

-.J 5. Performance Step: Trip 22 Rod Drive MG Set Breaker Standard: Generator No.22 switch indicates proper direction of movement for PULLOUT Motor No.22 switch indicates proper direction of movement for PULLOUT NOTE: The first MG set breaker switch does not open. The second MG set breaker switch does open resulting in shutdown of its Rod Drive MG set.

After the second MG set is deenergized, the reactor is tripped CUE: Generator or Motor switch to Pull-Out successful, breaker is tripped Comment: Step 1.3 RNO 3 of 6

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark~)

6. Performance Step: Notify CRS of reactor Status Standard: Inform CRS that the reactor is tripped CUE: Acknowledge as CRS Comment:

Terminating Cue: JPM Complete 4 of 6

Appendix C Page 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: - - - - - - - - - - - -

5 of 6

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

1. The CCR has been evacuated due to a fire and 2-AOP-SSD-1, Control Room Inaccessibility Safe Shutdown Control, has been implemented.

2. The reactor could not be tripped from the Control Room.

Initiating Cue:

The CRS has directed you to trip the reactor from the Cable Spreading Room in accordance with 2-AOP-SSD-1, Attachment 1.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 2 Task No: 0630030324 Task

Title:

Startup 24 Battery Charger Job Performance Measure KIA

Reference:

063000A.4.01 No: ln-Plant-J (2.8/3.1)

Examines: 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:

1. Plant conditions are shutdown and stable.

2. NPOs are standing by for any remote operations

3. Electrical power is available at Motor Control Center (MCC) 27A and the DC is aligned IAW COL 27.1.6.

4. Precautions and Limitations of 2-SOP-27.1.6 have been reviewed -

Satisfactory.

Required Materials: None General

References:

2-SOP-27.1.6, Instrument Bus, DC Distribution system and PA System Inverter Initiating Cue: The CRS has instructed you place #24 Battery Charger in service using 2-SOP-27.1.6.with current flow and proper battery room ventilation Time Critical Task: No 1 of 11

Appendix C Job Performance Measure Form ES-C-1 Worksheet Validation Time: 15 minutes Task Standard: #24 Battery Charger in service with current flow and proper battery room ventilation.

2of11

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1) 1 . Performance Step: Obtains correct procedure and step Standard: 2-SOP-27.1.6 Comment:

2. Performance Step: Review precautions & limitations and Initial Conditions Standard: P&Ls previously reviewed.

Comment: Review of P&Ls not necessary. Candidate may choose to review P&Ls

3. Performance Step: Verify DC output breaker OFF Standard: Locates and verifies Output breaker OFF CUE: After locating breaker, cue that it is OFF Comment: Step 4.12.1 3 of 11

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

4. Performance Step: Verify AC input breaker OFF Standard: Locates and verifies Input breaker OFF CUE: After locating breaker, cue that it is OFF Comment: Step 4.12.2

5. Performance Step: Close the 480 Volt breaker at the appropriate MCC Standard: Direct the Nuc Watch NPO to close breaker 4E on MCC27A CUE: Nuc Watch responds "The breaker is CLOSED" Comment: Step 4.12.3 4of11

Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark "'1)

6. Performance Step: Verify the Equalizing-High Rate timer is OFF Standard: Locates and verifies timer is OFF CUE: If necessary, cue that it is OFF Comment: Step 4.12.4

.../ 7. Performance Step: Place the AC input breaker to ON Standard: Indicates proper movement of control to CLOSE AC input breaker CUE: After locating and simulating proper movement, cue that breaker is ON Comment: Step 4.12.5 5 of 11

Appendix C Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark '°'1)

.../ 8. Performance Step: Verify 24 Battery voltage Standard: Have student locate battery room door and explain how voltage is measured.

Check 24 Battery voltage with a Digital voltmeter.

CUE: 24 Battery voltage is 128 VDC Comment: Step 4.12.5.1

.../ 9. Performance Step: Adjust 24 Battery Charger output DC volts to 24 Battery voltage using FLOAT Adjustment Screw to as close as possible to battery voltage (128).

Standard: 24 Battery Charger output voltage adjusted to 128 voe CUE: After demonstrating method for adjusting voltage, output voltage is 128VDC Comment: Step 4.12.5.2 6 of 11

Appendix C Page 7 Form ES-C-1 Performance Information (Denote critical steps with a check mark~)

.../ 10. Performance Step: Place the DC output breaker to ON Standard: Indicates proper movement of control to CLOSE DC output breaker CUE: After locating and simulating proper movement, cue that breaker is ON Comment: Step 4.12.6

.../ 11. Performance Step: Adjust 24 Battery Charger output voltage to 130*

132VDC Standard: Battery Charger output voltage increased to 130 to 132VDC CUE: Output voltage is 130 VDC Comment: Step 4.12.6.1

12. Performance Step: Record Battery Charger Output DC Amperes Standard: Refers to Charger Ampere meter CUE: DC Output amps read 125 Amps Comment: Step 4.12.6.2 7 of 11

Appendix C Page 8 Form ES-C-1 Performance Information (Denote critical steps with a check mark--./)

13. Performance Step: LOAD associated Static Inverter on the DC Bus Standard: Recognize that inverter needs to be loaded at this point.

CUE: Inverter has been loaded by another operator.

Comment: Step 4.12.6.5

14. Performance Step: Verify the output current increases to greater than zero Standard: Locates and observes output current meter CUE: After locating meter, report current is >O Comment: Step 4.12.7

15. Performance Step: If associated battery is connected AND its voltage is greater than 127VDC, THEN VERIFY under voltage relay target is RESET.

Standard: Relay target located and is reset. The Green light is lit CUE: Output voltage is 130 VDC Comment: Step 4.12.8 8 of 11

Appendix C Page 9 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

16. Performance Step: Verify that ~p of the battery exhaust fan is 0.08 to 0.37 inches H20 Standard: Locates and verifies ~p of 24 battery exhaust fan CUE: If necessary cue that ~pis 0.2 inches H20 Comment: Step 4.12.9 Terminating Cue: JPM Complete 9of11

Appendix C Page 10 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ __

1Oof11

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

1. Plant conditions are shutdown and stable.

2. NPOs are standing by for any remote operations

3. Electrical power is available at Motor Control Center (MCC) 27A and the DC is aligned IAW COL 27.1.6.

4. Precautions and Limitations of 2-SOP-27.1.6 have been reviewed -

Satisfactory.

Initiating Cue:

The CRS has instructed you place #24 Battery Charger in service using 2-SOP-27 .1.6.with current flow and proper battery room ventilation

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 2 Task No: 0840360524 Task

Title:

Perform the Required Actions to Locally Start 23 Charging Pump Without Instrument Air Available 000068A106 Job Performance Measure No: ln-Plant-K KIA

Reference:

(4.1/4.2)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance x Actual Performance 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:

1. The CCR has been evacuated due to a fire and 2-AOP-SSD-1, Control Room Inaccessibility Safe Shutdown Control, has been implemented.

2. The Spare NPO is standing by in Turbine Building

3. Attachment 8 Steps 1-6 have been completed.

Required Materials: Wrench General

References:

2-AOP-SSD-1 Control Room Inaccessibility Safe Shutdown Control Initiating Cue: The CRS has directed you to locally start 23 Charging Pump per 2-AOP-SSD-1, Attachment 8, Step 8. 7 - 8.12.

Time Critical Task: No Validation Time: 20 minutes 1of8

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: Scoop tube is uncoupled and Charging Pump is running.

2 of 8

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

../ 4. Performance Step: Open 288 RWST Manual Inlet Stop (22 charging pump cell)

Standard: locate and open valve 288 CUE: After valve is located, Valve is open Comment: Step 8.8

../ 5. Performance Step: Close 297 (BORIC ACID BLENDER OUTLET STOP)

(Concentrates Holding Tank Cell - PAB 98' near FCV-110B)

Standard: Request location of valve (98' PAB)

CUE: After valve location described Valve Closed Comment: Valve 297 is a diaphragm valve located approximately half way down the left wall.

4 of 8

Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

6. Performance Step: Unlock and place Substation 12FD3 Breaker 1M in the vertical position Standard: Direct NPO to Unlock and place breaker in vertical position CUE: NPO reports breaker in vertical position Comment: Step 8.10

7. Performance Step: Close Substation 12FD3 Breaker 1M by operating CLOSE/TRIP switch Standard: Direct NPO to close breaker.

CUE: NPO reports Breaker Closed Comment: Step 8.11 5 of 8

Appendix C Page6 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

.../ 8. Performance Step: Raise 23 charging pump speed to maximum Standard: Adjust Scoop tube to maximum position CUE: Scoop tube is in maximum position Comment: Step 8.12 Terminating Cue: JPM Complete 6 of 8

Appendix C Page 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __

7 of 8

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

1. The CCR has been evacuated due to a fire and 2-AOP-SSD-1, Control Room Inaccessibility Safe Shutdown Control, has been implemented.

2. The Spare NPO is standing by in Turbine Building

3. Attachment 8 Steps 1-6 have been completed.

Initiating Cue:

The CRS has directed you to locally start 23 Charging Pump per 2-AOP-SSD-1, Attachment 8, Step 8. 7 - 8.12.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 2 Task No:

Task

Title:

Electrical Verification - Offsite Power Sources Surveillance 1940002.1.18 Job Performance Measure KIA

Reference:

RO - 3.6 No: RO Admin 1

~-------~

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:

Unit is in MODE 1, 100% Power.

13.8 KV Gas Turbine Substation Bus is tagged for an emergent maintenance issue.

21 EOG is scheduled to be removed from service for scheduled preventative maintenance activities within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Required Materials: 2-PT-W019; Electrical Verification - Offsite Power Sources and AC Distribution General

References:

2-PT-W019; Electrical Verification - Offsite Power Sources and AC Distribution 1of9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Initiating Cue: The CRS has requested that you complete the control room portion of surveillance 2-PT-W019; Electrical Verification - Offsite Power Sources and AC Distribution.

All procedure precautions, limitations, and prerequisites have been reviewed and signed off.

Procedure sections 4.1 and 4.2 have also been completed, including verification that all offsite power feeders are available from the Consolidated Edison District Operator.

Procedure Step 4. 7 for local verification of MCC status has been completed.

Time Critical Task: No Validation Time: 20 minutes Task Standard: Using indications in the simulator and scripted evaluator cues complete procedure sections 4.3 through section 7.0, step 7.1.1.

2 of 9

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark'\/)

'\/1. Performance Step: VERIFY 138 K.V. MO. DISC. SW BKR. 4 is Closed (Panel SHF}

Standard: Student locates and verifies breaker is closed and initials step 4.3.1 Comment: Procedure step 4.3.1.

'\/2. Performance Step: VERIFY Station Auxiliary Transformer output voltage as indicated on 6900V Bus Voltmeter (Panel SHF or FCR} is between 7.0 and 7.225 kV.

Standard: Student locates and verifies voltage is between 7.0 and 7.2.

The candidate may use the meter on the Supervisory Panel {SHF} or go behind the Flight Panel.

Comment: Procedure step 4.3.2.

'\/4. Performance Step: VERIFY the following:

Breaker GT1at13.8 kV Gas Turbine Bus is closed. Breaker is OPENED.(Setup}

Breakers GT2 at 13.8 kV Gas Turbine Bus is closed. Breaker is OPENED.(Setup}

Breaker 52-0SP at SBO/APP. R Switchgear 6.9KV Bus CLOSED

Gas Turbines are NOT only source of power to 13.8 KV Gas Turbine Bus

Unit 2 Appendix R Diesel Generator is NOT only source of power to 13.8KV Gas Turbine Bus Standard: Student locates and verifies breakers and contacts CUE: NPO reports OSP Breaker is closed App R diesel is not the only source of power to 13.8 Kv Gas Turbine Bus Comment: Procedure step 4.4.1.

3 of 9

Appendix C Page4 Form ES-C-1 Performance Information (Denote critical steps with a check mark -V)

-Va. Performance Step: VERIFY 6.9 kV buses are aligned and energized as follows:

Standard: Candidate:

o checks Normal Feed for all buses.

o records bus voltage (approximately 7.2 kV for all buses) o initials step 4.3.2.

Comment: Procedure step 4.5.1 .

.../9. Performance Step: IF in Modes 1, 2, 3, or 4, THEN VERIFY Essential Buses are aligned and energized as follows:

Standard: Candidate:

o checks STA SERV TRANS and Normal Feed breakers closed for all buses.

o records bus voltage (approximately 495 V for all buses) o initials steps 4.6.1 o recognizes that the cross-tie breakers are open Cue if necessary that the cross-tie breakers are open and racked out.

Comment: Procedure step 4.6.1.

10. Performance Step: !.E in Mode 5 or 6, THEN VERIFY the necessary Safeguards Buses (2A, 3A, 5A or 6A) required to support LCO 3.8.10 are OPERABLE, by recording energized bus voltages and breaker positions:

Standard: Student N/As the step.

Comment: Procedure step 4.6.2. Unit is in MODE 1.

4 of 9

Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark'\/)

11. Performance Step: VERIFY MCCs are energized (breakers closed):

Standard: Given in Initial Conditions CUE: If necessary, All MCC breakers closed locally.

Comment: Procedure step 4.7.1.

12. Performance Step: RECORD date/time test is completed:

Standard: Student records current date/time and initials step 4.8.1.

Comment: Procedure step 4.8.1.

13. Performance Step: Performer Prints name, initials, signs, and dates in Section

5.0. Standard

Performer Prints name, initials, signs, and dates in Section

5.0. Comment

Procedure step 5.0.

\/14. Performance Step: Offsite AC electrical power sources SHALL be considered OPERABLE in Modes 1 through 4, when the following is satisfied ill: in Modes 5 or 6, THEN "N/A" this table):

Standard: Student circles acceptable YES for all sections (procedure steps)

Comment: Procedure step 6.1.1.

15. Performance Step: Offsite AC electrical power sources SHALL be considered OPERABLE in Modes 5 and 6, when the following is satisfied (IF in Modes 1 through 4, THEN "N/A" this table):

Standard: Student N/As step.

Comment: Procedure step 6.1.2. Unit is in MODE 1.

5 of 9

Appendix C Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark -Y)

"116. Performance Step: Based on the recorded data, are all Acceptance Criteria of Section 6.1 satisfied for the current plant operating Mode?

Standard: Student circles YES.

Comment: Procedure step 7.1.1.

Terminating Cue: JPM Complete 6 of 9

Appendix C Page 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ __

7 of 9

Appendix C Simulator Setup Form ES-C-1 Simulator Setup Any 100% IC 6.9 KV Gas Turbine Substation Bus is tagged for an emergent maintenance issue.

8 of 9

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

Unit is in MODE 1, 100% Power.

13.8 KV Gas Turbine Substation Bus is tagged for an emergent maintenance issue.

21 EOG is scheduled to be removed from service for scheduled preventative maintenance activities within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Initiating Cue:

The CRS has requested that you complete the control room portion of surveillance 2-PT-W019; Electrical Verification - Offsite Power Sources and AC Distribution.

All procedure precautions, limitations, and prerequisites have been reviewed and signed off.

Procedure sections 4.1 and 4.2 have also been completed, including verification that all offsite power feeders are available from the Consolidated Edison District Operator.

Procedure Step 4.7 for local verification of MCC status has been completed.

9 of 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 2 Task No: 2000120121 Task

Title:

Perform Daily Containment Leakage Calculation Job Performance Measure RO Admin 2 2.1.25 (3.9)

KIA

Reference:

No:

~

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Performance x Classroom x 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:

1. The plant has been operating at 100% power for the past several months.

2. The previous Daily Weld Channel Leakage Calculation was performed last mid-shift at 0010.

3. Weld Channel & Containment Penetration Leak Rate Counters were reset

4. The time now is today at 0025.

Required Materials: Calculator General

References:

2-PT-D001 Control Room Operations Surveillance Requirements Initiating Cue: The CRS has directed you to perform the Daily Weld Channel Leakage Calculation per 2-PT-D001, page 28.

1of9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: No Validation Time: 20 minutes Task Standard: Surveillance Table correctly completed.

2 of 9

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark -V) 1 . Performance Step: Obtain correct procedure and step Standard: Obtains correct procedure and step Comment:

-./2. Performance Step: Complete 2-PT-0001, page 28 for today's reading NOTE: Compare operators 2-PT-0001, page 28 with attached 2-PT-0001, page 28.

Standard: Weld Channel Low Pressure Alarm CLEAR or existing value.

Fills out 2-PT-0001, page 28 and calculates leakage with total

leakage 9720 scf, average leakrate 6.68 (6.6 - 6.8) and IFR-1126 reading of 6.74 Each zone integrator reset to 0 (Not Critical)

Comment:

3. Performance Step: Return competed 2-PT-0001, Page 27 to CRS for review.

Standard: Gives CRS completed 2-PT-0001, page 28 Comment:

3 of 9

Appendix C Page 4 Form ES-C-1 Terminating Cue: JPM Complete 4 of 9

~~-~---~~~~~,~~~~~~~~~~~~~~~-~~~~~~~~~~~~~~~-~~-~--~~~-

CONTROL ROOM OPERATIONS SURVEILLANCE REQUIREMENTS of40 L ~****~------~~

AN~Wl

-~*ttach~nt ~--~ Contr~~ Room ~-2 and 24_ Hour Surveilla~~* Req':i~remenm Page 16 of WC&PPl(2) 1.rtmumefltf AG~

Paramemr l~Ort CriWfla ARP SLF 14

>47 PSJG SR ::t6.Hl1 I Wc&PPS I Wea Charmel Low Pr.sure

-ZOOll 1

-Zone 2

-lone MOO-ES 1. 2,::; and 4

-Zone.it 3

Alfflraa LNk Rme ~ eqtmi wtoo TOOii

mre~bytne dihml'ICle in tilne lam* miinutHl 3.5.1112 I WC&PPS I ---

~rLPk~te Oare: IOOAY Time: 0025 ~ Hours 24 tim Hi Time Date: YESTfRDA"! Time 0011 14%iS MimJtwe (1} low Preisure Alam1 is at 49 paig. IF the alal'm ts > 47 ~ can be verified.

C~1lCK Gf.h.A&JB 3J:t 10.2 shall be performed oo the ml~ht ~as close to midnight as pos.sib~- Zsro counters after readings.

~ WC&PPS zone is to be worned on or ~llbratoo, av~ the other 3 cilannth~-. red the rnult and not* the rMSO!i 5 of 9

Appendix C Page 6 Form ES-C-1 SIMULATOR SETUP Reset simulator to any at power IC Set Weld Channel Flow Integrators to Zone 1 2340 Zone 2 2410 Zone 3 2920 Zone 4 2050 Total Leakage 9720 Recorder Leak Rate 6. 74 Leave Simulator in freeze during performance of JPM so zone totals do not change Use Insight screen to set zone integrators; VCASZON, enter.

fhis will yield all four zones, (1 ), (2), (3), and (4). Set lines 1 through 4 to totals listed above. (ie, 1=

XXXX). On Panel SL set total flow recorder to value listed above for recorder.

6 of 9

Appendix C Page 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __

7 of 9

No: 2-PT-0001 Rev: 16 CONTROL ROOM OPERATIONS SURVEILLANCE REQUIREMENTS Page: 28 of 40 - Control Room 12 and 24 Hour Surveillance Requirements Page 16 of 27 WC&PPS (2)

Surveillance Requirement Component/

Parameter Instrument/

Location I Acceptance Criteria I Actual I Acceptable I Initials Comments ARP SLF 1-4

> 47 PSIG I I I I YES/ NO SR 3.6.10.1 WC&PPS Weld Channel Low Pressure I ( 1)

Zone 1 CF Zone 2 CF MODES 1, 2, 3 and 4 Zone 3 CF Average Leak Rate is equal to the Zone4 CF Total leak rate divided by the difference in time Total CF (Hours times minutes).

SR 3.6.10.2 I WC&PPS I (3)

I Average Leak Rate < 14.4 CFM CFM YES/ NO Recorder Leak Rate < 14.4 CFM CFM YES/ NO Current Date and Time Date: Time:

Delta Hours_ _ __

Previous Date and Time Date: Time:

(1) Weld Channel Low Pressure Alarm is at 49 psig. IF the alarm is clear,> 47 psig can be verified.

(2) SR 3.6.10.2 shall be performed on the midnight shift as close to midnight as possible. Zero counters after readings.

(3) IF a WC&PPS zone is to be worked on or calibrated, average the other 3 channels, red circle the result and note the reason below

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point Unit 2 Task No: 2000390121 Task

Title:

Determine Isolation Boundaries for a Tagout of 21 SIP Job Performance Measure KIA

Reference:

1940012213 (4.1/4.3) No: RO Admin 3 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 Shift Manager has determined that 21 Safety Injection Pump must be tagged out to replace FE-7245.

Clearance Number is 2C20

Tagout Number is Sl-001.

Required Materials:

General

References:

EN-OP-102, Protective and Caution Tagging

9321-2735 Flow Diagram Safety Injection System

9321-27 46 Flow Diagram Isolation Valve Seal Water Initiating Cue: You are the Spare RO and the CRS has directed you to determine the mechanical piping components only to isolate and drain 21 Safety Injection Pump for a tag out.

1of9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: No Validation Time: 20 minutes Task Standard: Mechanical Components identified.

2 of 9

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

1. Performance Step: Obtain Correct Drawing Standard: Obtains 9321-2735 9321-2746 Comment:

-.J 2. Performance Step: Discharge Valve closed First Standard: MOV-850A CLOSED FE-6456 is an equivalent Comment: Attachment 9.2 of EN-OP-102 lists sequence for pumps

-.J 3. Performance Step: Pump Recirc Test Line Stop Valve Standard: 1870A Closed Comment:

...J 4. Performance Step: Suction Valve Closed Second Standard: 848AClosed Comment:

3 of 9

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..../)

"5. Performance Step: SI Pump Thrust Balance Flow line Stop Standard: 1843A Closed Comment:

6. Performance Step: Pump Drain Standard: Remove Cap down stream 7306 Open Drain Line 7306 Comment:

7. Performance Step: Pump Vent Standard: Remove Cap downstream of 427 4 Open Vent Valve 427 4 OR If 6456 NOT used as a boundary 6677 Open 7309 Open 7310 Open Comment: Either will provide an adequate vent path for Terminating Cue: JPM Complete 4 of 9

Appendix C Ecme 5 Form ES-C-1

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I TEST LI~7 a:i:::r, 0

ITEM:

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I

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tr:

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6"-SI-151R-1199 665 "N" (TYP. l 5 of 9

Appendix C Page6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __

6 of 9

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

The Shift Manager has determined that 21 Safety Injection Pump must be tagged out to replace FE-7245.

Clearance Number is 2C20

Tagout Number is Sl-001.

Initiating Cue:

You are the Spare RO and the CRS has directed you to determine the mechanical piping components only to isolate and drain 21 Safety Injection Pump for a tag out.

6658§9 ,-.,

tlbl 3/4" T58 PT 923 0256854!

t.OTE 'L' .

a:

I OR.<1111 ... I L.C .

0 3

it)

I SAFETY co~ '° H INJECTION Cl

if> TEST LINE ""

<Q..;

I")

7352 L.D.

l"J 6'*SH51R Utt. l61l .

<D

?'-

f"'-

Ct; 1

">~ ~Z\. 600# FLGS. <l5.:,.j f55~

0::

,.,/'(,-+

v\.'!'c,0 (\j *

-;;... -~

~ 1 rn- 1

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,.....I

(/)

ITEM:~ H I

. ~ CAS!t \!ENT

(/) <

22SIP 1 2 L:J 884A HYP.J ...' '"

l"J 112*-C56

. IOOIA 314'-ThilLINE #161 '

I")

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,£i x""

lIJ t'*SH:OI~

l---ta:l-J 6"-SI-151R-#i99 6655.

3/4'-S:-151liN4!i7 HEM:

21SIP SEE NOTE UN" (TYP.l Q2545541 SAFFTY TN, !Fr.HON P! JMPS

NUCLEAR MANAGEMENT NON-QUALITY RELATED EN-OP-102-01 REV.10

'Entergy MANUAL INFORMATIONAL USE PAGE 7 OF 30 Protective and Caution Ta Forms & Checklist ATTACHMENT 9.3 T AGOUT TAGS SHEET CLEARANCE: MANUAL TAGOUT:~~~~~~~-

Tag Tag Equipment Place. Place. Rest. 1st Rest. 2nd Placement/R Serial Type Equipment Description Place. Placement !st Verif 2nd Verif Rest. Restoration Verif Verif emoval No. Eauioment Location Sea. Confornration Date/Time Date/Time Seq. Configuration Date/Time Date/Time Tag Notes

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 2 Task No:

Task

Title:
Determine Radiological Conditions, RWP Requirements, and Potential Dose KIA
Reference:
1940002.3.7 Job Performance Measure RO Admin 4 R0-3.5 No:
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:
1. Unit is in MODE 1, 100% Power
2. You have been assigned to perform the 21 Residual Heat Removal Pump Test IAW procedure 2-PT-Q028A.
3. You have been provided with a copy of the most recently completed survey of the radiological conditions in 21 RHR Cell when the pump was running for testing.
4. You have been provided with a copy of Radiological Work Permit (RWP) No:
20162002.
Required Materials: Radiological Work Permit (RWP) No; 20162002.
21 RHR Cell Radiological Survey Data 3-PT-Q028A; 21 Residual Heat Removal Pump Test General
References:
Radiological Work Permit (RWP) No; 20162002.
21 RHR Cell Radiological Survey Data 2-PT-Q028A; 21 Residual Heat Removal Pump Test 1 of 8
Appendix C Job Performance Measure Form ES-C-1 Worksheet Initiating Cue: In preparation for a pre-job briefing determine the following from the provided materials:
1. RWP Task Number
2. Dosimetry required
3. Dose Alarm setpoint
4. Dose Rate Alarm setpoint
5. Protective Clothing Requirements
6. Determine Low Dose Waiting Area in 21 RHR Cell
7. Determine highest contamination reading and location from survey
8. At what accumulated dose must you leave the RCA in accordance with RWP 20162002?
9. What is your maximum Stay Time?
Time Critical Task: NO Validation Time: 15 minutes Task Standard: Student uses the RWP and Radiological Survey to properly answer the above questions in preparation for a pre-job briefing.
2 of 8
Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)
'11. Performance Step: RWP Task Number Standard: Student determines that Task 2 is the proper task for performing tests.
Comment:
'12. Performance Step: Dosimetry required Standard: Student determines that a Whole Body DLR I Electronic Dosimeter is required.
Comment:
..J 3. Performance Step: Dose Alarm setpoint Dose Rate Alarm setpoint Standard: Student determines that the dose alarm is set at 10.00 mrem and the dose rate alarm is set at 100.00 mrem.
Comment:
'14. Performance Step: Protective Clothing Requirements Standard: Student determines that a contaminated entry requires Protective Coveralls, High and Low Shoe covers, Hood, Hard Hat Cover, Cotton Liners and Rubber Gloves.
Comment: If asked, cue that HP approval has not been granted for reduced protective clothing requirements .
..J 5. Performance Step: Determine Low Dose Waiting Area in 21 RHR Cell Standard: Student determines from survey that the Step off pad (SOP) areas with 0.2 mrem/hr general area dose rates are the low dose waiting areas.
Comment:
3 of 8
Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)
.../ 6. Performance Step: Determine highest contamination reading and location from survey Standard: Student determines that the pump pedestal area, smear location 6 with a contamination level of 10,000 DPM/cm 2 is the highest level in cell.
Comment:
~ 7. Performance Step: At what accumulated dose must you leave the RCA in accordance with RWP 20162002?
Standard: Student determines that he must leave the RCA at 80% of the accumulated dose alarm setpoint. 80% of 10.0 mrem is 8.0 mrem.
Comment:
"Ja. Performance Step: What is your maximum Stay Time Standard: 80 minutes in 6 mrem/hr field would result in an accumulated dose of 8.0 mrem.
Comment:
Terminating Cue: JPM Complete 4 of 8
Appendix C Page 5 Form ES-C-1
1. RWP Task Number? Task2 Whole Body DLR and
2. Dosimetry required?
Electronic Reading Dosimeter
3. Dose Alarm setpoint? 10.0 mrem
4. Dose Rate Alarm setpoint? 100 mrem/hr Protective Coveralls, High and Low Shoe covers, Hood, Hard
5. Protective Clothing Requirements?
Hat Cover, Cotton Liners and Rubber Gloves Determine Low Dose Waiting Area in 21
6. 0.2 mrem/hr RHR Cell?
Determine highest contamination reading
7. Location 6 10,000 DPM/cm 2 and location from survey?
At what accumulated dose must you leave
8. the RCA in accordance with RWP 8 mrem 20162002?
9. What is your maximum Stay Time? 90 Minutes 5 of 8
Appendix C Page 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's signature and d a t e : - - - - - - - - - - -
6 of 8
Appendix C Simulator Setup Form ES-C-1 Simulator Setup N/A RO Admin JPM in classroom 7 of 8
Initial Conditions:
1. Unit is in MODE 1, 100% Power
2. You have been assigned to perform the 21 Residual Heat Removal Pump Test IAW procedure 2-PT-Q028A.
3. You have been provided with a copy of the most recently completed survey of the radiological conditions in 21 RHR Cell when the pump was running for testing.
4. You have been provided with a copy of Radiological Work Permit (RWP) No: 20162002.
Initiating Cue:
In preparation for a pre-job briefing determine the following from the provided materials:
1. RWP Task Number?
2. Dosimetry required?
3. Dose Alarm setpoint?
4. Dose Rate Alarm setpoint?
'1. Protective Clothing Requirements?
6. Determine Low Dose Waiting Area in 21 RHR Cell?
7. Determine highest contamination reading and location from survey?
8. At what accumulated dose must you leave the RCA in accordance with RWP 20162002?
9. What is your maximum Stay Time?
8 of 8
Appendix D Scenario Outline Form ES-D-1 Facility: Indian Point 2 Scenario No.: _1_ Op-Test No.: _1_
Examiners: Operators:
Initial Conditions: 4% power. No equipment out of service for current conditions. Startup is in progress.
Turnover: Currentl:i at Step 4.33 of POP-1.3. The FSS is prepared to perform turbine latch and reset per SOP-26.4. Raise power to 6-8% in preparations for turbine startup.
Event Malf. No. Event Type* Event No. Description N
CRS/BOP 1 - R Raise power to 6-8%
ATC I
2 XMT-SGN046A PT-449C fails high (TS)
ALL 3 MOC-CVCOOS c 21 Charging Pump Trip CRS/ATC 4 PLP-SIS006 c RWST leak (TS)
CRS 5 RLY-PPL487 c Inadvertent Safety Injection CRS/BOP MOC-RHR003 MOC-RHR004 6 MOC-CNM008 c Failure of 21 and 22 RHR Pumps and 21 and 25 FCUs BOP to start on SI signal MOC-CNM012 M
7 MAL-RCS006B Small Break Loss of Coolant Accident ALL 8 - - Loss of Recirculation Capability
(N)ormal, (R)eactivity, (I )nstrument, (C)omponent, (M)ajor IPEC Unit 2 2016 Page 1 of 16 Scenario 1
Scenario 1 Summary The evaluation begins with the plant at 4% power with no equipment out of service.
After taking the watch, the team will proceed to raise power as directed. This will require withdrawing controls rods and/or diluting the RCS which will provide a reactivity event for the ATC operator. SG levels will be controlled in manual using the feed regulation bypass valves which will provide a normal operation for the BOP operator. The CRS will direct the evolution and get credit for a normal operation.
After sufficient power increase, 24 SG Pressure Transmitter PT-449C will fail high. This will cause the Atmospheric Dump Valve for 23 SG to open requiring the controller to be placed in manual by the ATC. The CRS will enter AOP-1 NST-1. Bistables for the failed channel will be tripped by the BOP. This will count as an instrument failure for all operators and a tech spec call forthe CRS.
After bistables has been tripped for the PT-449C failure, the running charging pump will trip. The CRS will enter AOP-CVCS-1. The ATC will start another charging pump to restore charging.
The CRS and ATC will get credit for a component failure.
Next, a fork truck crashes into the RWST resulting in a large leak 10 feet from the bottom of the tank. It will take 40 minutes for the tank to drain from 36' to 10'. The team will perform actions of the ARP for RWST Level Low alarm and the CRS will determine that a TS required shutdown must commence.
An inadvertent train A SI will occur when RWST level reaches -28 feet. The CRS will direct entry into E-0, Reactor Trip or Safety Injection and be credited with a component failure. 21 and 22 RHR pumps and 21 and 25 FCU will fail to auto start. The BOP will have to start these components manually. After SI and RHR pumps are secured in ES-1.1, a small break LOCA will occur. This is the major event for the team. The team will determine that the RCS is not intact and transition to E-1, Loss of Reactor or Secondary Coolant. When RWST level lowers to 9.24 feet a transition to ES-1.3, Transfer to Cold Leg Recirculation will occur. The containment sump level will not support recirculation pump operation requiring a transition to ECA-1.1, Loss of Emergency Coolant Recirculation.
The team will makeup to the RWST (may be done early from ARP response), reduce operating ECCS equipment taking suction from the RWST to one train, and initiate RCS cooldown. The scenario will be terminated when makeup to the RWST has been initiated, containment spray has been stopped and SI pumps have been reduced to one train.
Procedure flow path: POP-1.3, AOP-INST-1, AOP-CVCS-1, ARP-SBF-1, E-0, ES-1.1, E-0, E-1, ES-1.3, ECA-1.1 IPEC Unit 2 2016 Page 2of16 Scenario 1
CRITICAL TASKS:
1. WOG ECA-1.1 - B:
Make up to the RWST and minimize outflow before the end of the scenario.
2. Non-WOG ES-1.1 :
Manually start HHSI and RHR pumps as necessary to provide core cooling for LOCA with pumps secured during termination.
3. WOG ECA-1.1 -A:
Stop ECCS pumps with suction aligned to the RWST before HHSI pumps lose suction.
EXPLANATION OF CREDITED ACTIONS:
Event 1 - Power escalation. ATC will withdraw rods and/or dilute. The BOP will be controlling SG levels in manual. The CRS will coordinate the evolution.
Event 2 - 24 SG Press Instrument Failure. The ATC will place the ADV in manual and close it.
The BOP will trip bistables. The CRS will determine TS actions.
Event 3 - 21 Charging Pump trip. ATC will start another charging pump. The CRS will implement procedure for the failure.
Event 4 - RWST Leak. The ATC may line up to fill RWST. The CRS will evaluate TS.
Event 5 - Inadvertent SI. The CRS will implement the procedure. The BOP will establish charging.
Event 6 - Failure of component to autostart. The BOP will have to manually start 21 and 22 RHR Pumps and 21 and 25 FCUs.
Event 7 - SBLOCA . This is the major event for all operators.
Event 8 - Loss of Recirculation Capability. This is a contingency EOP for all operators.
IPEC Unit 2 2016 Page 3of16 Scenario 1
2016 _Scenario_ 1_Setup_Rev1
!At Time --i~~ent - Action I Descript:o~---~--------*--
[-oo:OO:O~T~~-:-1--~~~~e Event 30 lt920 < 28 -desc r;~~~-;~~--- .-----------.. -
1::00:00 None rc-;~-~te E~rent 29 xaoi125a==l - r b/ l hb I vu J desc xa01125a Ip rs- pus utton
_,___, _ . r

Ins~rt-~alfunction RLY-PPL487 RELAY FAILURES: SIA-1 (A) 00:00:00 one to ENERGIZE on event 30 SAFETY INJECTION AUTO delete in 130 MASTER RL Y

_1~---1 ~n~~rt malfunction MAL- lsMAL~-;~EAK LOCA L00~-;--
l 00:00:00 None RCS006B after 60 to 3.00000 on event 7 I HOT LEG (NR) 1 1~~; . ~:-~1~K~o~:~::~~:~~C- ---r~;;";~;-;*-U_M_P_N,O. 2;--~~-~~;--
1 I, Tinsert malfunction MOC- I - .
I 00:00:00 J None I RHR00 3 to AUT_ CLS I RHRl RHR PUMP NO. 21 MOTOR 1~~:~~:~~ None 1~~~:0;1~~E~-~~c= ' ' ' ........ r~~~~~J~~R~~~~::r
[-~~-:~~:~~-1~:n:---'[ ~~~~i~it~~~~c=-----------i--~~g~~J~:T1~~~T---. . . . .-.
~rt malfunction XMT- !FIXED OUTPUT: LT-3300 OO:OO:OO None I CNM018A to 39.70000 I CONTAINMENT SUMP LEVEL
~~-:~~:~~-r~:~:--- ~~~;;~~~f~~~~-=------ -~~~~ ~E~r:~~LT-330i RECIRC-*
1
- 1-Insert-~~lfunction XMT-1 I:' . . -
OO*OO*OO None SGN046A to 1400.00000 on I FIXED OUTPUT: PT-449C S/G 24
. . t I PRESSURE CH. 3 r even 2 I
-00:00:00 I None I In;~rt malfunction MOc"- Cl ~HA~GIN~-;~p 21 MOTOR r CVC005 to TRIP on event 3 I OO:OO:OO None Insert remote PLP-SIS006 to REFUELING WATER STORAGE 10.00000 in 2400 on event 4 I TANK LEV 1 -*-;;~~*;~-~i~::*--- 1 ~~::~:Tfun~t~~N:sl32=3~*-r;;~-~~~;~-Zc;;-~~-;. ;~~
IPEC Unit 2 2016 Page 4of16 Scenario 1
Simulator Setup and Instructor Directions EXPECTED RESPONSE/INSTRUCTOR Setup/Event INSTRUCTOR ACTIONS CUES IC Reset Reset Simulator to 100% power IC SES Setup Run setup file:
Schedule 2016_Scenario_1_Setup_Rev1 Verify batch file has been loaded.
File Place 21 Charging pump in service and secure all others Event 1 Power Increase Acknowledge notifications Event 2 Actuate Trigger 2 SG Press Instrument 449C fails high At lead evaluator direction Role Play When SM, l&C or Work Inform team that work package is being Control are notified developed. Bistables need to be tripped.
Event 3 Actuate Trigger 3 21 Charging Pump trip At lead evaluator direction Role Play When NPOor No reason for failure will be provided.
Maintenance dispatched to investigate Event 4 Actuate Trigger 4 RWST leak At lead evaluator direction Role Play Maintenance personnel call There is a large puncture of RWST about 8 the control room to report ft above the bottom of the tank.
vehicle accident.
Role Play When called about makeup Chemistry will report that the BASTs are at to RWST. 12% boric acid.
NPO will verify valve 1860 is open.
NPO will operate CVCS valves as requested for RWST fill.
IPEC Unit 2 2016 Page 5of16 Scenario 1
Simulator Setup and Instructor Directions EXPECTED RESPONSE/INSTRUCTOR Setup/Event INSTRUCTOR ACTIONS CUES Event 5/6 On automatic trigger when Inadvertent SI with failure of 21 and 22 RWST level reaches 28 ft. RHR pumps and 21 and 25 FCUs to autostart.
Event 7/8 Activate trigger 7 after SI SBLOCA/Loss of Recirculation Capability and RHR pumps are secured.
Role Play If TSC Contacted Inform team that makeup to RWST is desired. BAST concentration is 12%. Valve 1860 is open.
Role Play At CCR Request Perform LOAs to makeup to RWST.
IPEC Unit 2 2016 Page 6 of 16 Scenario 1
Op-Test No.: 1 Scenario No.: 1 Event No.: 1 Event
Description:
Power Ascension Time Position Applicant's Actions or Behavior Note:
The reactivity plan for the power ascension should be developed by team in briefing room prior to taking the watch. The plan could call for dilution and/or rod withdrawal.
CRS Assigns roles for power ascension ATC Reviews reactivity plan ATC If rods are withdrawn:
Places/verifies rods are in Manual
Withdraws rods
Observes:
o Proper rod motion o Tavg BOP Peer checks rod withdrawal ATC If dilution is performed:
Places RCS Makeup control to Stop
Place RCS Makeup Mode selector to Dilute
Adjusts integrator to desired dilution amount
Places RCS Makeup control to Start
Observes:
o Proper makeup response o Tavg IPEC Unit 2 2016 Page 7of16 Scenario 1
Op-Test No.: 1 Scenario No.: 1 Event No.: 1 Event
Description:
Power Ascension BOP Peer check dilution Adjust Low Flow Feed Reg Valves to maintain SG levels.
Lead Evaluator When the following has been demonstrated/observed:
Sufficient load ascension.
Sufficient normal plant operations by the BOP.
Then instruct Booth to insert Event 2.
IPEC Unit 2 2016 Page 8of16 Scenario 1
Op-Test No.: 1 Scenario No.: 1 Event No.: 2 Event
Description:
PT-449C (24 SG Channel C Pressure Transmitter) Fails High Time Position Applicant's Actions or Behavior Recognizes failure of the instrument and announces to the crew.
ATC 24 SG ADM will be open due to the failure ATC States that 24 SG ADM will be placed in manual and closed.
ATC Closes 24 ADV.
Announces entry into 2-AOP-INST-1, Instrument or Controller CRS Failure.
Determines that SG pressure instrument failure has occurred and CRS goes to procedure section.
Reviews TS tables 3.3.2-1 and 3.3.3-1 for failed instrument.
Will determine that:
For 3.3.3-1 the spec is still met since 2 SG press channels CRS are required per SG.
For 3.3.2-1 the spec is not met. Condition D applies for SG High DP and High Steam Flow with Low SG Press. These conditions require placing channels in trip in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .
Note:
If needed, prompt CRS as the SM that bistables need to be tripped.
Will trip bistables in Rack B-9:
PC-449A BOP PC-419C PC-419F When the following has been demonstrated/observed:
Lead Evaluator
Bistables tripped .
Tech Specs addressed .
Then instruct Booth to insert Event 3.
IPEC Unit 2 2016 Page 9 of 16 Scenario 1
Op-Test No.: 1 Scenario No.: 1 Event No.: 3 Event
Description:
Running Charging Pump Trips Time Position Applicant's Actions or Behavior Recognizes and announces that charging pump has tripped.
Pump indication will change.
ATC PZR level will lower.
RCP Thermal Barrier Low Deta-P Alarm will annunciate Announces entry into 2-AOP-CVCS-1, Chemical and Volume CRS Control System Malfunctions Determines there is:
ATC
Adequate VCT pressure and level
No evidence of gas binding
No flashing of the letdown line .
ATC Starts a charging pump CRS Exits AOP.
ATC May place charging pump in automatic control.
When the following has been demonstrated/observed:
Lead Evaluator
Charging re-established and pressurizer level is stable .
Then instruct Booth to insert Event 4.
IPEC Unit 2 2016 Page 10of16 Scenario 1
Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Event
Description:
RWST Leak due to Fork Lift Crash Time Position Applicant's Actions or Behavior Note:
After the RWST Low Level Alarm annunciates, a call will be made to the team that a forklift has crashed into the RWST and caused a leak about 8 feet above the ground.
Review ARP for RWST Low Level alarm. Determine that 36'10" is BOP the level that meets the TS value of 345,000 gallons.
Check TS. Will determine:
LCO 3.5.4 will not be met.
Condition C requires RWST to be made operable within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .
CRS Since Condition C will not be met, Condition D will need to be addressed which requires being in Mode 3 in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and Mode 4 in an additional 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
Align makeup to RWST per 2-SOP-10.1.1:
Adjust make up to 10 gpm boric acid flow BOP
Adjust primary water flow to about 78 gpm (not critical)
Have NPO open 297 and fail air to 11 OB and 111 B
Have NPO open 295 and 350
Place Makeup Mode Selector in Manual to start fill Brief a shutdown or possibly elect to trip the plant due to being CRS below 250 MW.
The next event (inadvertent SI) is triggered from RWST level Lead Evaluator reaching 28'. It is not expected that much action for plant shutdown will occur prior to reaching this level.
IPEC Unit 2 2016 Page 11 of 16 Scenario 1
Op-Test No.: 1 Scenario No.: 1 Event No.: 5/6 Event
Description:
Inadvertent SI and failure of SI components to autostart.
Time Position Applicant's Actions or Behavior Announce to team to perform the immediate operator actions of E-0 CRS Reactor Trip or Safety Injection Verifies reactor trip:
Trip breakers open ATC
Flux decreasing
Rod bottom lights lit
RPls less than 12.5 inches Verifies Turbine Trip:
ATC
All stop valves closed Verifies power to 480V busses:
BOP
All busses energized Checks SI status:
ATC
SI annunciator lit
3 SI pumps running
One train is activated Begins Attachment 1, Automatic Action Verification:
(Done in parallel. Actual actions for event listed)
Checks adverse containment conditions - not adverse
Starts 1 charging pump
Align charging suction to the RWST by opening 112B and closing 112C BOP
Places VCT makeup to stop
Dispatches NPO to reset lighting and MCCs 24A,27A,29A
Stops all condensate pumps
Start RHR pumps
Start 21 and 25 FCUs
Places airlock switches in incident mode
Notifies CRS that attachment is complete ATC Verifies AFW flow ATC Verifies SI Flow ATC Stops 1 RHR pump ATC Checks RCP cooling BOP Dispatches NPO to close SW valves FCV-1111 /1112 and SWN-6/7 IPEC Unit 2 2016 Page 12of16 Scenario 1
Op-Test No.: 1 Scenario No.: 1 Event No.: 5/6 Event
Description:
Inadvertent SI and failure of SI components to autostart.
ATC Checks RCS temperature ATC Checks PORVs and spray valves closed ATC Checks if RCPs should be stopped - they will be left on ATC Checks for faulted SG - none faulted ATC Checks for ruptured SG - none ruptured ATC Checks if RCS is intact - RCS is intact Checks if SI should be terminated: (conditions will be met)
Subcooling greater than 19°F
Total feedflow greater than 400 gpm or SG NR greater than ATC 10%
RCS pressure greater than 1720 psig and stable or increasing
PZR level greater than 14%
CRS Transition to 2-ES-1.1, SI Termination Reset SI:
Check CCW pumps running Place Main and Bypass FRVs in closed ATC or BOP Use keys to defeat automatic SI Reset SI trains A and B Verify reset Terminate SI:
ATC or BOP
Secure SI Pumps
Secure/verify secured RHR Pumps When SI and RHR pumps are secured, instruct booth operator to Lead Evaluator insert Event 7.
IPEC Unit 2 2016 Page 13of16 Scenario 1
Op-Test No.: 1 Scenario No.: Event No.: 7 Event
Description:
Small Break Loss of Coolant Accident Time Position Applicant's Actions or Behavior Diagnose SBLOCA from:
ALL
Lowering PZR level
Lowering Subcooling CRS Transition back to E-0 when LOCA is recognized ALL Re-perform steps of E-0 with LOCA Depending on timing of crew, RCP trip criteria may be met and ATC or BOP RCPs will be tripped.
CRS Transition to E-1 at step 15 of E-0 Note:
There should not be much time in E-1 based on crew pace and RWST level Reset Phase A:
Place IVWS switches to open on SN ATC or BOP
Place Rad Monitor WCPS switches to open on SN
Place Phase A switches to closed on SN
Reset Phase A by pressing reset buttons Note that one RWST Level Low Low 9.24 FT is in and RWST is at BOP 9.24' CRS Transition to 2-ES-1.3, Transfer to Cold Leg Recirculation Lead Evaluator Actions will continue with Event 8 .
IPEC Unit 2 2016 Page 14of16 Scenario 1
Op-Test No.: 1 Scenario No.: 1 Event No.: 8 Event
Description:
Loss of Recirculation Capability Time Position Applicant's Actions or Behavior Either from foldout of 2-ES-1.3 of step 1 RNO, determine that CRS transfer to 2-ECA-1.1, Loss of Emergency Coolant Recirculation, is required.
Verify sump blockage is not occurring:
No erratic flow ATC
No abnormal sump level
No Low Head Injection Line Low Alarm
No SI Pump Suction Low Press Alarm CRS Determine that recirculation equipment is available ATC Verify FCU and SW for containment cooling CRS Evaluate spray pump requirements - none running Note:
Team will get response (prompt if needed) from TSC that makeup to RWST is desired, BAST concentration is 12%, and Valve 1860 (RWST Inlet Stop) has been verified open.
Align makeup to RWST per 2-SOP-10.1.1: (critical task actions listed, may have been done earlier)
Adjust make up to 10 gpm boric acid flow BOP
Adjust primary water flow to about 78 gpm (not critical)
Have NPO open 297 and fail air to 11 OB and 111 B
Have NPO open 295 and 350
Place Makeup Mode Selector in Manual to start fill Initiate Cooldown to CSD at <100 F/hr: (critical task actions)
Evaluate cooldown due to the LOCA ATC
If plant has cooled down <1000F in past hour, then dump steam with HP Dumps or ADVs to maintain <100°F/hr cooldown.
ATC Verify SI status IPEC Unit 2 2016 Page 15of16 Scenario 1
Op-Test No.: 1 Scenario No.: 1 Event No.: 8 Event
Description:
Loss of Recirculation Capability ATC Verify SI has been reset ATC Stop all but one SI pump (critical task step)
Stop one RHR pump if RCS pressure is <320 psig (350 adverse) or ATC both if above (critical task step)
If both above critical tasks have been met, scenario can be Lead Evaluator terminated at this point.
Terminate the scenario when at least two of the critical tasks have Lead Evaluator been addressed.
Emergency Plan Follow Up:
For this scenario, the following conditions occurred regarding Emergency Declarations:
ALERT due to vehicle crash into RWST EAL HA 1.3
ALERT due to loss of RCS barrier FA 1.1
Possible SAE due to Orange Path on Core Cooling with loss of RCS barrier FS 1.1 IPEC Unit 2 2016 Page 16of16 Scenario 1
Appendix D Scenario Outline Form ES-D-1 Facility: Indian Point 2 Scenario No.: ~ Op-Test No.: _1 Examiners: Operators:
Initial Conditions: 100% power. 21 CCW and 23 SI Pumps are OOS for preventive maintenance.
Turnover: Team has been directed to reduce power to 90% in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to support turbine valve testing.
Event Malf. Event Event No. No. Type* Description N
1 CRS/BOP Power Reduction.
RATC CNH-2 PCS003 c 22 MFRV fails as is in automatic.
CRS/ATC A
3 MOC- c 23 Service Water Pump trips. TS SWS008 CRS/BOP MOT-CCW002 B
c 4 CRS/BOP 22 CCW Pump trips and 23 fails to auto start. TS MOC-CCW001
/3 5
FLX- c CCW leak on running charging pump cooling line.
CCW014 CRS/ATC BKR-PPL003/
4 M 6 Steam break with MSIVs failing to close and ATWS with LOOP.
AOV- ALL SGN001/
2/3/4A MOC-7 SIS001/2 c 21 and 22 SI Pumps fail to start on SI.
CRS
/3
(N)ormal, (R)eactivity, (I )nstrument, (C)omponent, (M)ajor IPEC Unit2 2016 Page 1 of 17 Scenario 3
SESSION OUTLINE:
The evaluation begins with the plant at 100% power steady state operation. 23 SI Pump is out of service for maintenance.
After taking the watch, the team will begin lowering power as directed in turnover. The ATC will borate for a reactivity manipulation. The BOP will lower load with the governor for a normal operation. The CRS will be credited with a normal operation for supervising the evolution.
During the downpower, 22 MFRV will fail to 35% in automatic. The team will see level in 22 SG trending high or low and place the FRV controller in manual. 22 SG level will have to be controlled in manual for the rest of the scenario.
Next, 23 Service Water Pump will trip. The BOP will start another pump to maintain essential service water header pressure. The CRS will evaluate tech specs.
After sufficient load decrease, 22 CCW pump trips and the available standby CCW pump do not auto start as expected. The team will respond by manually starting one of the standby CCW pumps. When a CCW pump is running, a 25 gpm leak will occur on 22 Charging Pump CCW cooling line. The team will start another charging pump and take actions in accordance with AOP-CCW-1, Loss of Component Cooling and isolate the leak by closing local valves in the Charging Pump cell. The CCW pump trip and failure to auto start is Tech Spec entry. Two CCW pumps inoperable is a tech spec entry. The charging pump being inoperable is a TRM entry.
After completion of the Subsequent Actions of AOP-CCW-1, a steam break will occur in the Turbine Building. The team will attempt to manually trip the plant, close MSIVs, and perform actions of E-0, Reactor Trip or Safety Injection.
The reactor will not trip from the Control Room and the team will respond per FR-S.1, Response to Nuclear Power Generation I ATWS and will SID the reactor by manually inserting control rods and initiating Emergency Boration. The reactor trip breakers will be locally opened and the team will transition to E-0, Reactor Trip or Safety Injection. Following SI actuation, 21 and 22 SI pumps do not auto start.
The MSIVs will fail to auto close and cannot be closed from the control room. The team will take actions per ECA-2.1, Uncontrolled Depressurization of All Steam Generators. When at least one MSIV is closed locally, the team will transition to E-2, Faulted Steam Generator Isolation.
Procedure flow path: POP-2.1, AOP-INST-1, ARP-SJF, ARP-SGF, AOP-CCW-1, AOP-UC-1, E-0, FR-S.1, E-0, E-2, ECA-2.1, E-2.
IPEC Unit2 2016 Page 2of17 Scenario 3
CRITICAL TASKS:
1. WOG FR-S.1-C Insert negative reactivity into the core by at least 1 of the following methods before Step 4 of FR-S.1 is complete:
De-energize the Rod Drive MG sets
Manually insert the rods
Establish Emergency Boration.
2. Non-WOG Start at least one safety injection pump to make up for RCS inventory loss before entry into E-2.
3. WOG ECA-2.1-A Control AFW flow to not less than 85-100 gpm per SG to minimize RCS cooldown rate before an Integrity orange path develops.
EXPLANATION OF CREDITED ACTIONS:
Event 1 - Power Reduction. The ATC will borate and possibly drive rods. The BOP will lower turbine load using the governor. The CRS will coordinate the evolution.
Event 3 - Service water pump trip. The BOP will have to start another service water pump. The CRS will evaluate tech specs.
Event 4 - CCW Pump trip with aut-start failure. The BOP will have to start another CCW pump.
With one pump already OOS, this puts the plant in a tech spec action statement.
Event 5- CCW leak at charging pump. The ATC will have to secure the running charging pump and start another to allow for leak isolation. The CRS will evaluate the TS, but since already in an action for the same LCO, this is not credited for TS count.
Event 6 - Steam break with ATWS and failure of MS IVs to close. This is the major event for the team.
Event 7 - 21 and 22 SI pumps fail to start on SI. Only crediting the CRS since either operator could take action for this.
IPEC Unit2 2016 Page 3of17 Scenario 3
2016_Scenario_3_Setup_Rev1 On At Time Action Description Event CCW-NT-14 COMPONENT COOLING Insert override SWI-00:00:00 None WATER PUMP N0.21 CONTROL CCWOO lA SWITC
-~Ii 1- Insert m~lfunctionMOC- Sll SAFETY INJECTION PUMP 21 OO:OO:OO I None SISOOl to AUT CLS MOTOR
,.......... -----***--r-**----r*--*-*---*-*~--------~-~ ~-~*~,~-~~-~,----~---~---
Insert malfunction AOV- GENERAL FAILURE: MS-1-21 MAIN OO:OO:OO None SGNOOlA to FAIL AS IS TEAM STOP VALVE MS-1-21
-!insert malfunction AOV- GENERAL FAILURE: MS-1-22 MAIN 00:00:00 one I SGN002A to FAIL AS IS
~-~"~--~--~---
STEAM STOP VALVE MS-1-22 Insert malfunction AOV- GENERAL FAILURE: MS-1-23 MAIN 00:00:00 None SGN003A to FAIL AS IS STEAM STOP VALVE MS-1-23 Insert malfunction AOV- GENERAL FAILURE: MS-1-24 MAIN 00:00:00 None SGN004A to FAIL AS IS STEAM STOP VALVE MS-1-24 Insert malfunction BKR-00:00:00 e REACTOR TRIP BKR PPL003 to FAIL ASIS Insert malfunction BKR-00:00:00 None 52/RTB REACTOR TRIP BKR PPL004 to FAIL ASIS Insert malfunction MOC-SWS008 to TRIP on event 3
-1 SW3 SERVICE WATER PUMP MOTOR 23 00:00:00 None ~l~~;;,e:de s;.,,_ ----~I :=;~~~~.~~~~~~g{ING
~0:00:00 -None -~~~::~~~.~~~on ~~gil~~g~i;;~;~~~~ONENT I ~vent 4
-~~:oo:~~---~N_o_n_e_, ~:.~r~c;~!LO:-event I ~:r cH~~~~RG cLR
---*-** *---*-r:---*****------***---**--*--*--**---~*---------~******- ----*---~---*-* . .........-~------
Insert malfunction MAL-00:00:00 None SGN004A to 5.00000 in 606 ~~V2 ~Ni:gR LEAK DNSTRM CHK on event 6
~~~~~00 *r~one*-r-insert_m_a_lfu_n_c-ti_o_n_M_A_L __---..-*-LOSS OF STATION AUX

I EPSOOl on event 30 TRANSFORMER (NR)
I 0(5:.oO:Oo-- - sert ov;ri~f~Swl-SIS003 - T-5 SI PUMP #23 CONT SW
. Create Event 30 J*i_p==l -desc ii 00:00:00 Jl_p
-'~-----..--*--*----*-1*1~sert malfunction MOC- . .
86/P trips SI2-3ASIPUMP MOTOR 22 480 BUS OO:OO:OO 1 nvu"I SIS003 to AUT_CLS l 3A IPEC Unit2 2016 Page 4of17 Scenario 3
1~~~00:00 ~::~---r*~~~~~;1~~~;:~~6c- 1
~~-2A SI PUMP MOTOR 22 480 BUS
---i~~~~T;~4i10~6.~~~~~~gfING-m-*~_.-.--m*~-
lo~~O:OO
~--**-
Insert override SWI-None CCWOOlA SWITC r*~o:o~-~~-INone ~sert malfun;ti~n DLY- ---~I 62-PC-600/X CCP LOW DISCH PRESS-CW004 to 28800.00000 TIMER I 00~00:00 I None I I~~~~?'v'~~~~SWI-SIS003~ J~i.~~NT-5 SI PUMP #23 CONT SW ........._""*****
Insert malfunction CNH- MCB CTRLR FIXED AUTO ONLY:
00:00:00 None PCS007D to 35.00000 in 600 FIC-427 SG 22 FD REG VLV CONT on event 2 NM IPEC Unit2 2016 Page 5of17 Scenario 3
Simulator Setup and Instructor Directions Setup/Event INSTRUCTOR ACTIONS EXPECTED RESPONSE/INSTRUCTOR CUES IC Reset Reset Simulator to 100% power IC SES Setup Run setup file: Verify schedule is loaded.
Schedule File Ensure 23 SWP is running on the essential header.
Ensure 22 CCW Pump is in service Ensure 21 Charging Pump is in service Tagout 21 CCW and 23 SI Pumps Event1 Power Reduction Acknowledge notifications Event 2 Actuate Trigger 2 22 MFRV automatic failure Event3 Actuate Trigger 3 23 SWPtrip At lead evaluator direction Role Play When NPO or No reason for failure will be provided.
Maintenance dispatched to investigate Event 4 Actuate Trigger 4 22 CCW Pump trip.
At lead evaluator direction Role Play When NPO or Bearings are extremely hot on 22 CCW Maintenance dispatched Pump.
to investigate Event 5 Is actuated by Trigger 4 CCW leak at running charging pump.
with delay.
IPEC Unit2 2016 Page 6of17 Scenario 3
Simulator Setup and Instructor Directions Setup/Event INSTRUCTOR ACTIONS EXPECTED RESPONSE/INSTRUCTOR CUES Role Play When NPO dispatched to In -3 minutes report there a lot of water at investigate running charging pump (21) due to a CCW leak. Leak is downstream of 833A which is a cooler inlet for 21 Charging Pump. The leak can be isolated, but will require securing CCW to running pump (close 833A and 7570).
When charging pumps are swapped, delete the FLX-CCW014 malfunction and report that 833A and 7570 are closed.
Role Play If NPO asked to make up Fill by opening 831 on CCW pump simulator to CCW surge tank. drawinq paqe.
Event6 At lead evaluator Steam leak in steam bridge area.
direction: MSIVs do not close.
Reactor does not trip Activate Trigger 6 Role Play When NPO called to trip Defeat trip breaker malfunctions after 60 reactor locally seconds.
Role Play When called to close Cannot access the MSIV area.
MSIVs and investigate steam leak.
Role Play If ConEd contacted Offsite power is available to 138KV and 13.BKV. Problem is the station auxiliary transformer. If the team wants to close 52GT 25 or 26, they can.
Role Play At CCR Request Perform LOAs per EOPs.
IPEC Unit2 2016 Page 7of17 Scenario 3
Op-Test No.: 1 Scenario No.: 3 Event No.: 1 Event
Description:
Power Reduction Time Position Applicant's Actions or Behavior Note:
The reactivity plan for the power reduction should be developed by the team in the briefing room prior to takin J the watch. The plan could call for boration and/or rod insertion CRS Obtain POP-2.1 and SM permission for power reduction CRS Direct ATC/BOP to perform a Reactivity Calculation for the power reduction ATC/BOP Prepare Reactivity Calculation using the Daily Reactivity Sheet WCR-1 CRS Assigns roles for power reduction ATC Reviews reactivity plan ATC If rods are inserted:
Places/verifies rods are in Manual
Inserts rods specified number of steps
Observes:
0 Proper rod motion 0 Tavg 0 Power BOP Peer checks rod insertion ATC If boration is performed:
Energize All Pressurizer Heaters
Places RCS Makeup control to Stop
Place RCS Makeup Mode selector to borate
Adjusts integrator to desired boration amount
Places RCS Makeup control to Start
Observes:
0 Proper makeup response 0 Tavg 0 Power BOP Peer check boration IPEC Unit2 2016 Page 8of17 Scenario 3
Op-Test No.: 1 Scenario No.: 3 Event No.: 1 Event
Description:
Power Reduction Note:
As soon as load is taken off, the booth operator will insert Event 2.
ATC/BOP Initiate Turbine Load Reduction at desired rate
Governor (Preferred)
Load Limit 1
Load Limit 2 ATC Maintain the manual setpoint for the MFRV Controllers Nulled.
ATC Adjust Control Rod to maintain AFD Lead Evaluator When the following has been demonstrated/observed:
Sufficient load reduction .
Sufficient normal plant operations by the BOP .
Then instruct Booth to insert Event 3.
IPEC Unit2 2016 Page 9of17 Scenario 3
Op-Test No.: 1 Scenario No.: Event No.: 2 Event
Description:
22 MFRV slowly fails to 35% in automatic.
I Time Position Applicant's Actions or Behavior ATC Will note that 22 SG level is trending down.
ATC/BOP Respond to SG Level Deviation alarm.
ATC Place 22 MFRV in manual and restore SG level.
May enter AOP-INST-1. There are no actions taken by the CRS procedure.
CRS Resume power reduction.
Once MFRV is in manual and level is being controlled in 22 SG, Lead Evaluator actions can be tracked in Event 1 .
IPEC Unit2 2016 Page 10of17 Scenario 3
Op-Test No.: 1 Scenario No.: 3 Event No.: 3 Event
Description:
23 Service Water Pump trips.
Time Position Applicant's Actions or Behavior Acknowledge service water header low pressure alarm and BOP announce 23 SW Pump tripped.
BOP Start an additional Essential SW pump per ARP-SJF Review Tech Spec LCO 3.7.8 Will determine:
CRS
LCO not satisfied since 3 essential pumps required .
Condition A applies .
Plant is in a 72 action statement to restore pump or swap headers.
When the following has been demonstrated/observed:
Lead Evaluator
SW pressure is stable .
Tech Specs have been reviewed .
Then instruct Booth to insert Event 4.
IPEC Unit2 2016 Page 11 of 17 Scenario 3
Op-Test No.: 1 Scenario No.: 3 Event No.: 4 Event
Description:
22 CCW Pump trips and 23 fails to auto-start.
Time Position Applicant's Actions or Behavior BOP Acknowledge the numerous alarms associated with CCW.
Determine that 22 CCW Pump has tripped and 23 CCW Pump did BOP not auto start on low pressure as expected.
Start 23 CCW Pump per ARP-SGF (or administrative guidance to BOP take manual action when automatic did work as expected)
Evaluate Tech Spec LCO 3.7.7 Will determine:
CRS
LCO not met since only one train is operable.
Condition A applies .
Plant is in 72 action statement to restore a train of CCW .
Event 5 is triggered with event 4 on a delay and takes time to be Lead Evaluator noticed by operators.
IPEC Unit2 2016 Page 12of17 Scenario 3
Op-Test No.: 1 Scenario No.: 3 Event No.: 5 Event
Description:
CCW leak on running charging pump Time Position Applicant's Actions or Behavior Recognize that CCW surge tank level is lowering or acknowledge BOP "Component Coolant Low Surge Tank" alarm that comes in about 5 minutes after entering trigger 4.
CRS Enters 2-AOP-CCW-1, Loss of Component Cooling Water.
Determines that system leak is occurring that does not require a CRS trip, and goes to procedure section.
BOP Dispatches NPOs to make up the surge tank and look for leaks.
Note:
If the team misunderstands leak location, it is possible that the procedure section for losing charging will be followed. This would lead to running 21 Charging Pump at maximum speed and placing backup cooling in place.
When leak location is reported to control room, give order to swap CRS to another charging pump.
ATC Place 22 or 23 Charging Pump in service and secure 21.
CRS Direct leak be isolated.
Will check for systems affected by isolation. Once isolated, no ATC/BOP systems are affected.
CRS Evaluate Tech Specs for LCO 3.7.7 which is already not met.
When the following has been demonstrated/observed:
Lead Evaluator
Leak isolated .
Operability evaluated .
Then instruct Booth to insert Event 6.
IPEC Unit2 2016 Page 13of17 Scenario 3
Op-Test No.: 1 Scenario No.: 3 Event No.: 6/7 Event
Description:
Steam break with MSIVs failing to close and ATWS with LOOP I 21 and 22 SI Pumps fail to start on SI.
Time Position Applicant's Actions or Behavior ALL Hear steam leak.
Diagnoses steam leak by observing:
Steam flow ATC
Power
Temperature May enter 2AOP-UC-1, Uncontrolled Cooldown, or just give out CRS order to trip the reactor and close MS IVs.
ATC Attempts to trip the reactor, BOP Attempts to trip the reactor.
One of the team members will dispatch an NPO to trip the reactor ALL locally.
Will announce entry into 2-FR-S.1, Response to Nuclear Power CRS Generation/ATWS.
ATC Will check that the reactor did not trip and will insert control rods.
BOP Will trip the turbine. May attempt to close MSIVs. Will not go closed.
BOP Will check that AFW flow is > 800 gpm.
ATC/BOP Start a charging pump (SI and LOOP will strip the charging pump).
BOP Open MOV-333.
BOP/ATC Place both boric acid transfer pumps in fast.
BOP/ATC Place charging in manual.
BOP Open 112B and close 112C.
IPEC Unit2 2016 Page 14of17 Scenario 3
Op-Test No.: 1 Scenario No.: 3 Event No.: 6/7 Event
Description:
Steam break with MSIVs failing to close and ATWS with LOOP I 21 and 22 SI Pumps fail to start on SI.
BOP/ATC Place make up controls in stop.
BOP/ATC Run charging pump at least 75 gpm.
ATC Check PZR pressure < 2335 psig (it will be)
BOP Verifies VC isolation.
Checks that turbine and reactor are tripped (the reactor will be CRS tripped by now).
CRS Exits 2-FR-S.1 and goes to 2-E-O step 1.
May attempt to close MSIVs at this point. Operator should be CRS dispatched to attempt to gain entry and close MSIVs.
ATC Verifies reactor trip - it is tripped.
ATC Verifies turbine trip - it is tripped.
BOP Verifies power to 480V busses - it will be via EDGs.
ATC Checks SI status. SI has occurred automatically.
Start 21 and 22 SI pumps. This may have already been done by ATC BOP or ATC.
ATC Checks both trains of SI actuated.
Begins Attachment 1, Automatic Action Verification:
(Done in parallel. Actual actions for event listed)
Checks adverse containment conditions - not adverse
Starts 1 charging pump
Align charging suction to the RWST by opening 112B and closing 112C BOP
Places VCT makeup to stop
Dispatches NPO to reset lighting and MCCs 24A,27A,29A
Stops all condensate pumps
Start RHR pumps
Start 21 and 25 FCUs
Places airlock switches in incident mode
Notifies CRS that attachment is complete IPEC Unit2 2016 Page 15of17 Scenario 3
Op-Test No.: 1 Scenario No.: 3 Event No.: 6/7 Event
Description:
Steam break with MSIVs failing to close and ATWS with LOOP I 21 and 22 SI Pumps fail to start on SI.
ATC Verifies AFW flow - may proactively reduce to 400 gpm.
ATC Verifies SI Flow ATC Stops 1 RHR pump ATC Checks RCP cooling - no CCW, stop RCPs if not already done.
BOP Dispatches NPO to close SW valves FCV-1111/1112 and SWN-6/7 ATC Checks RCS temperature ATC Checks PORVs and spray valves closed ATC Checks if RCPs should be stopped - they will already be off.
ATC Checks for faulted SG. All are faulted.
CRS Transitions to 2-E-2, Faulted SG Isolation CRS Determines all SGs are faulted.
CRS Transitions to 2-ECA-2.1, Check secondary pressure boundry - Room is not accessible and ATC other actions have been attempted.
ATC Check cooldown and determine if more than 100 F in past hour.
Reduces AFW flow to 85-100 to each SG if cooldown was ATC
>100°F/hr.
If cooldown is <100 F/hr, then the CRS should ensure that the CRS minimum AFW flow for heat sink (400 gpm total) is used to attempt to stabilize RCS hot leg tempertures.
Note:
At this point the booth operator will close 22 MSIV.
CRS Transition back to 2-E-2 based on the foldout.
When the team transitions back to E-2, the scenario may be Lead Evaluator terminated.
IPEC Unit2 2016 Page 16of17 Scenario 3
Emergency Plan Follow Up:
For this scenario, the following conditions occurred regarding Emergency Declarations:
SAE due to inability to trip the reactor at the control console. SS 2.1 IPEC Unit2 2016 Page 17of17 Scenario 3
Appendix D Scenario Outline Form ES-D-1 Facility: Indian Point 2 Scenario No.: 4 Op-Test No.: _1 Examiners: Operators:
Initial Conditions:
Reset simulator to 100% power IC The Plant is at 100% power.
Turnover:
Perform power reduction to 60% to remove 22 MBFP from service.
Event Malf. No. Event Event No. Type* Description R (ATC) 1 N/A N (CRS) Power Reduction N (BOP) 2 XMT- I (ALL)
VCT Level Failure CVC019A 3 XMT- I (ALL)
RCS028A Pressurizer Pressure Instrument failure.
TS(CRS) 4 FLX-Flooding in 480V room.
FPS008 5 MAL- C(ALL)
EPSOO?D Loss of 480V Bus 6A.
TS(CRS) 6 XMT- M(ALL)
RCS030A Pressurizer Pressure failing causing trip.
7 AOV- C(ALL)
RCS003A PORV failure 8 MAL-EPSOO?C/ M(ALL) Loss of 480V buses due to flooding.
B/A
(N)ormal, (R)eactivitv, (I lnstrument, (C)omponent, (Mlajor IPEC Unit 2 2016 Page 1 of 18 Scenario 4
SESSION OUTLINE:
The evaluation begins with the plant at 100% power steady state operation with no significant equipment is out of service:
After taking the watch, the team will reduce power as directed to allow for securing 22 MBFP.
After sufficient load reduction, VCT level instrument will fail low causing charging pump suction to swap to RWST. The team will restore normal suction using AOP-CVCS-1.
After restoring charging suction to the VCT, controlling Pressurizer Pressure instrument fails high. Team performs actions of AOP-INST-1 and swaps pressure control to an unaffected channel. TS will be reviewed.
After PRZR pressure control has been returned to automatic, the fire main adjacent to the 480V switchgear room ruptures resulting in flooding. The team should implement AOP- FLOOD -1 which provides directions for identifying and isolating the source of flooding. Flooding in the room will continue and the door to the 480V room fails, causing floodwater to enter the 480V room and 480V Bus 6A to fault. The team will then implement AOP-480V-1, Loss of Normal Power to Any Safeguards 480V Bus.
Then, Pressurizer Pressure Channel 3 fails high resulting in a reactor trip and the associated PORV Block valve opens.
Following reactor trip, flooding in the 480V Room will result in sequential loss of all remaining 480V busses. The team will transition from E-0, Reactor Trip or Safety Injection to ECA-0.0, Loss of All AC Power. PORV 456 will fail open but can be manually closed by placing its control switch to close. AFW to the S/Gs will be supplied by 22 ABFP. CCW will be lost to the RCPs and the RCPs must be tripped. The team will progress through ECA-0.0 taking actions to isolate RCP seals and depressurize the S/Gs. The scenario will end when the team has demonstrated the ability to depressurize S/Gs.
Procedure flow path: AOP-CVCS-1, AOP-INST-1, AOP-FLOOD-1, AOP-480V-1, E-0, ECA-0.0 IPEC Unit 2 2016 Page 2of18 Scenario 4
CRITICAL TASKS:
1. ECA-0.0 -- A Manually close the open PZR PORV before completing Step 3 of ECA-0.0.
2. ECA-0.0 -- B Establish at least 400 gpm AFW flow to the S/Gs before SIG WR level decreases to below 14%
3. ECA-0.0 Trip all RCPs within 5 minutes of entering ECA-0.0.
4. ECA-0.0 -- G If all of the following conditions are met, depressurize intact S/Gs at
<100°F/hr:
Any intact SIG NR level >10%
SIG pressure does not decrease below 110 psig
RCS cold leg temperature >295°F
SUR 0 or negative EXPLANATION OF CREDITED ACTIONS:
Event 1 - Power reduction. ATC will insert control rods and/or borate. The BOP will lower turbine power. The CRS will coordinate the evolution.
Event 2 - VCT level instrument failure low. The ATC and BOP both have control board indications that will be used to diagnose failure. The BOP will acknowledge alarms and take action to restore Charging Pump suction to the VCT. The ATC will have to monitor for reactivity effects when the Charging Pump is taking suction from RWST.
Additionally, the ATC will secure makeup at the proper time. The CRS will coordinate and supervise activities.
Event 3 - PZR pressure failure. ATC will have to control pressure in manual. BOP will defeat failed channel. The CRS will coordinate and supervise activities and evaluate TS.
Event 4 - Flooding in 480V room is not credited. It gives reason for loss of 480V busses.
Event 5 - Loss of 6A require ATC to start a charging pump and BOP to start SW. The CRS will coordinate and supervise activities and evaluate TS.
Event 6 - The second PZR pressure instrument failure will result in a reactor trip.
Event 7 - The PORV failure will require the ATC to close the PORV. The CRS will have to direct/concur with this action.
Event 8 - Loss of all 480V busses causes team to enter ECA-0.0.
IPEC Unit 2 2016 Page 3 of 18 Scenario 4
2016_scenario_4_setup_rev0.html Insert malfunction XMT-00:00:00 None RCS028A to 2500.00000 in 23 on FIXED OUTPUT: PT-455 PZR PRESS CH.I
,---*---*-""' __,.__ event 3 malfunction FLX-FPS008 HEADER B (Pl 1&1 Insert malfunction MAL-00:00:00 None 480V BUS 6A FAULT EPS007D on event 5 r-----*----,---" - - - - - - - - - r - - - - * - - *. --------"""""""""------*-*-**"""
Insert malfunction XMT-FIXED OUTPUT: PT-457 PZR 00:00:00 None RCS030A to 2500.00000 on PRESS CH.3 event 6 OO:OO:OO INon~flnsert malfunction MAL- " ----
r 1 EPS007C after 20 on event 30 Insert malfunction MAL-00:00:00 None V BUS 3A FAULT EPS007B after 120 on event 30 te event 29 xeoi327c==l -
PCV-456 Close Pos xeoi327c I F-----..* - F_ _ _ _ _ _ _I_n_s"e_rt_m-al_fu_n_c-ti-on_A_O_V__---~NERAL FAILURE: PCV-456 PZR 00:00:00 None WER OPERATED RELIEF I RCS003A to NIA on event 29 AL VE
[
~~:00:00-1~ ~:-1 Ins~rt malfunction XM--T------~F-IX_E_D__
I 0 O_U_T_P_U-T: LT-112 VCT J CVC019A to 0 on event 2 LEVEL IPEC Unit 2 2016 Page 4of18 Scenario 4
Simulator Setup and Instructor Directions Setup/Event INSTRUCTOR ACTIONS EXPECTED RESPONSE/INSTRUCTOR CUES IC Reset Reset Simulator to 100% power IC SES Setup Run setup file:
Schedule File Ensure 23 SWP is running on the essential header.
Place 23 Charging pump in service and secure all others Event1 Power Reduction Acknowledge notifications Event2 Actuate Trigger 2 VCT Level Failure At lead evaluator direction Role Play When NPO or No reason for failure will be provided.
Maintenance dispatched to investigate Event 3 Actuate Trigger 3 PRZR Pressure Instrument fails high At lead evaluator direction Role Play When l&C or Work Notify Operations that a Part 21 Defective part Control are notified notification was just received on the installed PZR Pressure transmitters and that they are working up plans to replace them all, one at a time.
Event4 Actuate Trigger 4 Flex leak inserts fire main header rupture.
At lead evaluator direction Role Play NPO makes report of In -3 minutes report there a lot of water flooding to control room between the fire doors, outside the 480v room. The outer door is not draining well and the fire main in the entrance vestibule is ruptured IPEC Unit 2 2016 Page 5of18 Scenario 4
Simulator Setup and Instructor Directions Setup/Event INSTRUCTOR ACTIONS EXPECTED RESPONSE/INSTRUCTOR CUES Role Play If order is made to close After several minutes, report that valve is isolation valves locked open and key is broke in lock. Need to get bolt cutters. (Stall until after ECA-0.0 is entered).
If order is made to open 480V room back door 480V room rear door cannot be opened If order is made to secure running Fire pumps Do not secure all three pumps until after ECA-0.0 has been entered. If the booth instructor attempts to stop fire pumps, they restart. You can try - but you will probably not be successful. Leave at least one running until entry into ECA-0.0 Event 5 At lead evaluator Bus 6A Fault direction:
Activate Trigger 5 and call CCR and let them know that the door to the 480V room has failed.
Room has several inches of water on it (UP TO SWITCHGEAR)
Event 6 At lead evaluator 2n° Pressurizer Pressure Channel Fails high direction:
Activate Trigger 6 Events 7/8 On timer from trigger 30 All 480V AC busses sequentially trip over 120 seconds after 86P trips.
Trigger 30 auto actuates PORV 456 fails open -3 minutes after when 86P trips (30 reactor trip (40 seconds after loss of all AC).
seconds after reactor When CS is placed to close, conditional trip) trigger 29 will activate and delete the open failure.
IPEC Unit 2 2016 Page 6of18 Scenario 4
Simulator Setup and Instructor Directions Setup/Event INSTRUCTOR ACTIONS EXPECTED RESPONSE/INSTRUCTOR CUES Role Play If ConEd contacted Offsite power is available to 138KV and 13.BKV. If the team wants to close 52GT 25 or 26, they can. It won't help because all of the 480V buses are faulted. Problem is not due to loss of offsite power.
Role Play At CCR Request Perform LOAs to locally stop all EDGs.
Role Play At CCR Request Locally isolate RCP seals, stop MBFP DC oil pump.
Role Play At CCR Request Report power restoration to one 480 V bus will be accomplished within 45 minutes.
Role Play If directed by the CCR to Acknowledge requests to perform actions, use 12FD3 (ASSS) power but don't perform any of the actions prior to to supply CCW, SI, the end of the scenario.
Charging, RHR, or AFW.
If CT to isolate RCP seals is not performed or is performed incorrectly, then consult with lead evaluator and at his discretion perform requested actions to align ASSS power to charging pumps.
If an excuse is needed to stall or delay ASSS power supply alignment, call CCR as NPO or team sent to align ASSS power and report that procedure requires entry into 480V room to verify equipment supply breaker open and remove control power fuses (i.e., 23 Charging Pump at bus 6A).
NPO believes this is unsafe due to several inches of water on floor.
IPEC Unit 2 2016 Page 7of18 Scenario 4
Op-Test No.: _1_ Scenario No.:__..!_ Event No.: _1_ Page _1_of _l Event
Description:
Power Reduction e Position Applicant's Actions or Behavior Note:
The reactivity plan for the power reduction should be developed by the team in the briefing room prior to takin ~ the watch. The plan could call for boration and/or rod insertion CRS Obtain POP-2.1 and SM permission for power reduction CRS Direct ATC/BOP to perform a Reactivity Calculation for the power reduction ATC/BOP Prepare Reactivity Calculation using the Daily Reactivity Sheet WCR-1 CRS Assigns roles for power reduction ATC Reviews reactivity plan ATC If rods are inserted:
Places/verifies rods are in Manual
Inserts rods specified number of steps
Observes:
0 Proper rod motion 0 Tavg 0 Power BOP Peer checks rod insertion ATC If boration is performed:
Energize All Pressurizer Heaters
Places RCS Makeup control to Stop
Place RCS Makeup Mode selector to borate
Adjusts integrator to desired boration amount
Places RCS Makeup control to Start
Observes:
0 Proper makeup response 0 Tavg 0 Power BOP Peer check boration IPEC Unit 2 2016 Page 8of18 Scenario 4
Op-Test No.: _1_ Scenario No.:~ Event No.: _1_ Page _1_of _l Event
Description:
Power Reduction ATC/BOP Initiate Turbine Load Reduction at desired rate
Governor (Preferred)
Load Limit 1
Load Limit 2 ATC Maintain the manual setpoint for the MFRV Controllers Nulled.
ATC Adjust Control Rod to maintain AFD Lead Evaluator When the following has been demonstrated/observed:
Sufficient load reduction .
Sufficient normal plant operations by the BOP .
Then instruct Booth to insert Event 2.
IPEC Unit 2 2016 Page 9 of 18 Scenario 4
Op-Test No.: _1_ Scenario No.: _1_ Event No.: __£__ Page _1_of _1 Event
Description:
VCT level instrument fails low causing automatic makeuQ and charging QUmQ suction to swag to the RWST.
e Position Applicant's Actions or Behavior CREW Diagnose VCT Level Instrument failing low by the following:
Automatic Makeup to VCT initiating
VCT Level Low Alarm (FB-1)
Charging Pump Suction swaps to RWST (LCV-112B opens LCV-112C closes)
CRS Enters AOP-CVCS-1 BOP Place and hold LCV-112C in Ooen BOP When LCV-112C indicates Full Ooen olace LCV-112B in Close BOP When LCV-112B indicates Full Closed olace LCV-112C in Auto ATC Place Makeuo Control in Stoo ATC Place Makeuo Mode Selector Switch in Manual CRS Determine if RCS Temperature was affected by RWST makeup.
ATC Makeup or divert from VCT as necessary to maintain VCT Pressure 2-5 psi above pre-event value.
Pre-event value was 20 psig CRS Complete AOP actions:
Have Chemistry determine RCS Boron concentration
Have NPO monitor running Charging Pump
Make notifications Lead Evaluator Request Booth Operator initiate Event 3 IPEC Unit 2 2016 Page 10of18 Scenario 4
Op-Test No.: 1 Scenario No.: 4 Event No.: 3 Page 1 of 1 Event
Description:
Pressurizer Pressure Instrument Failure Time Position Applicant's Actions or Behavior ATC/BOP Diagnose Failure of controlling PZR pressure instrument ATC Place affected control system in Manual and stabilize plant:
Takes manual control of master PZR pressure controller CRS Direct Perform Immediate Operator Actions of AOP-INST-1 ATC Silently evaluates for failure of control system inputs
Rod Control
Pressurizer Pressure
Pressurizer Level Control
MBFP Speed Control
SG Level Control
SG Pressure Control CRS/ATC Enter AOP-INST-1 and Re-perform IOAs verbalizing each input CRS/ATC Determine an Instrument failure has occurred. PT-455 CRS Identify aooropriate section of procedure BOP Defeat Channel as follows:
At Rack B-6 take P/455A to defeat 1&4
At Rack B-8 take T/411A to defeat Loop 1 ATC Place the PZR Pressure Recorder to record an operable channel ATC Return PZR Pressure Master Controller to automatic CRS Evaluates TS. May ask as followup CRS Reviews TS tables 3.3.2-1 and 3.3.3-1 for failed instrument.
Will determine that:
For 3.3.1-1 Functions 5 & 7 specs are not met. Condition E applies for OTl!.T and Pressurizer Pressure - High. Condition K applies for Pressurizer Pressure - Low. These conditions require placing channels in trip in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .
For 3.3.2-1 Functions 1d and 7 specs are not met. Condition D applies for Pressurizer Pressure - Low. Condition J applies for ESFAS Interlocks. Condition D requires placing channels in trip in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Condition J requires verifying Interlock in correct state IPEC Unit 2 2016 Page 11 of 18 Scenario 4
Op-Test No.: 1 Scenario No.: 4 Event No.: 3 Page 1 of 1 Event
Description:
Pressurizer Pressure Instrument Failure Lead Evaluator When the plant is stable and the channel defeated:
Then instruct Booth to insert Event 4 IPEC Unit 2 2016 Page 12of18 Scenario 4
Op-Test No.: 1 Scenario No.: 4 Event No.: 4 Page 1 of 1 Event
Description:
Flooding in 480V Room Time Position Applicant's Actions or Behavior ALL Diagnose fire alarms:
0 Investigate the cause of the auto start of the fire pumps.
BOP Perform ARPs for associated alarms.
CRS Implement AOP-FLOOD-1:
0 Determine source of flooding is from Fire system.
0 Direct activities of personnel to attempt leak isolation.
Lead Evaluator When the team has been informed of area of flooding:
Then instruct Booth to insert Event 5 IPEC Unit 2 2016 Page 13of18 Scenario 4
Op-Test No.: 1 Scenario No.: 4 Event No.: 5 Page 1 of 1 Event
Description:
Loss of 480V Bus 6A Time Position Applicant's Actions or Behavior BOP Diagnose loss of 480V Bus 6A CRS Enters AOP-480V-1 ATC Starts 21 or 22 Charging pump BOP Starts 21 SWP BOP Checks that 21 and 22 CCW are runnina CRS Evaluates TS 3.8.9 for loss of 480 V bus 6A Will determine Condition A not satisfied
Restore electrical power distribution system to OPERABLE in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .
Lead Evaluator When the plant has been stabilized:
Then instruct Booth to insert Event 6 IPEC Unit 2 2016 Page 14of18 Scenario 4
Op-Test No.: _1_ Scenario No.: _+/-__ Event No.: 61718 Page _1_of _]
Event
Description:
Trip due to second PZR pressure instrument I Loss of 480V busses due to flooding I PORV failure Time Position Examinee's Actions or Behavior ALL Diaqnose plant trip CRS Directs team to perform immediate actions of E-0 When the CRS directs "Perform the Immediate Operator Actions of E-0, the A TC and BOP will first perform the IOAs silently only announcing unexpected conditions. The crew will then re-perform the IOAs verbalizing each item. Depending on timing, these steps may or may not be completed before transition to ECA-0.0 ATC Verifies Reactor Trip:
Reactor trip and bypass breakers open
Rod bottom lights lit
IRPls < 12.5 inches
Nuclear flux decreasinq ATC Verifies Turbine Trip by observinq stop valves closed BOP Check status of 480V buses 6A is de-energized and other 480V busses are sequentially de-energizing ATC Check SI status Determine SI is not actuated ALL Diagnose when all 480V busses have been lost CRS Transitions to ECA-0.0, Loss of All AC Power and directs crew actions during implementation of ECA-0.0 ATC Verify Reactor trip
Reactor trip breakers open
Nuclear flux decreasing
Rod bottom lights lit
IRPls < 12.5 inches Verify Turbine is tripped ATC Verifies Turbine Trip by observing stop valves closed IPEC Unit 2 2016 Page 15of18 Scenario 4
Op-Test No.: _1_ Scenario No.: _1_ Event No.: 6/7/8 Page_1_of ~
Event
Description:
Trip due to second PZR pressure instrument I Loss of 480V busses due to flooding I PORV failure ATC Check if RCS is isolated o Isolates letdown o Close LCV-459 o Close 200A, B, and C o Notes PORV is open and closed PORV ALL Trip RCPs due to loss of CCW to oil coolers.
CRS/BOP Try to restore power
Ma manual! actuate Safet ln"ection ALL 0 en all Control Room Cabinets IPEC Unit 2 2016 Page 16of18 Scenario 4
Op-Test No.: _1_ Scenario No.:~ Event No.: 6/7/8 Page_1_of ~
Event
Description:
Trip due to second PZR pressure instrument I Loss of 480V busses due to flooding I PORVfailure Time Position Examinee's Actions or Behavior BOP Place equipment to Pullout
Containment Spray Pumps
SI Pumps
FCUs
Motor Drive ABFPs
Turning Gear Oil pump
Bearing Oil pump
Turbine Auxiliary Oil pump
CCW Pumps
RHR Pumps Reset Safety Injection when directed by the CRS CRS Direct RO/BOP to reset Safety Injection Dispatch Personnel to Locally Close Valves to Isolate RCP Seals and Place Valve Switches in CLOSED position
MOV-222, Seal Water Return lsolation(Valve is Bound OPEN)
RCP Seal Injection valves 250A, B, C, and D
FCV-789, CCW return From RCP Thermal Barrier TEAM Isolate the CST Check status of SGs - MSIVs, Main FW regulating and bypass valves and blowdown isolation valves - all Closed Check if any SG is faulted - No SGs are faulted Check if all SG tubes are intact - Yes all SG tubes are intact Check Intact SG levels - control with AFW flow Check DC bus loads - has call made to Technical Support Center Check CST level> 2 ft- Yes IPEC Unit 2 2016 Page 17of18 Scenario 4
Op-Test No.: _1_ Scenario No.: __A_ Event No.: 6/7/8 Page_1_of ~
Event
Description:
Trip due to second PZR pressure instrument I Loss of 480V busses due to flooding I PORV failure CRS/ATC Verify SG NR > 10% in at least one SG ATC Oum steam usin SG ADVs to cool down at <1 OOF/hr Lead Evaluator When cooldown is bein controlled, terminate scenario Emergency Plan Follow Up:
For this scenario, the following conditions occurred regarding Emergency Declarations:
NUE due to flooding in the 480V Room HU 1.4 SAE due to Loss of All AC for 2! 15 minutes SS 1.1 IPEC Unit 2 2016 Page 18of18 Scenario 4

ML16365A044

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