ML083110665

R. E. Ginna Final - Operating Exam, Sections a, B, and C (Folder 3)

ML083110665
Person / Time
Site:	Ginna
Issue date:	10/17/2008
From:	Ginna
To:	NRC Region 1
Hansell S
Shared Package
ML080030004	List: IR 05000244/2008301 ML081360258 ML082950349 ML082950384 ML082950389 ML082950422 ML082950425 ML082950432 ML083110590 ML083110619 ML083110659 ML083110665 ML083510111 ML083660253
References
TAC U01687
Download: ML083110665 (237)

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{{#Wiki_filter:! Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Ginna Task No.: 001-008-01-01 TasWJPM

Title:

Critical Rod Position Calculation JPM NO.: 2008 NRC JPM N-RA-1 WA

Reference:

2.1.25 3.9 14.2 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testina: Simulated Performance: Actual Performance: X Classroom X Simulator I - Plant Applicability: RO/SRO SUBMITTED BY: Ted Coe DATE: 6/30/08 Developer REVIEWED BY: Art Vest DATE: 6/30/08 Training Technical Reviewer REVIEWED BY: Don Dettman DATE: 6/30/08 Operations Technical Reviewer APPROVED BY: John Brown DATE: 6/30/08 Training Management Page 1 of 7

Appendix C Job Perforrnance Measure Form ES-C-1 Worksheet Task Standard: Critical Rod Position Calculation performed correctly and all critical tasks evaluated as satisfactory. Required Materials: Calculator, Nomogragh Tables General

References:

0-1.2.2, Critical Rod Position Calculation, Rev. 06500 Handouts: 0-1.2.2, Critical Rod Position Calculation, Rev. 06500 Time Critical Task: NO Validation Time: 30 minutes Alternate Path: NO Instructor Notes: Have a copy of 0-1.2.2, Critical Rod Position Calculation, Rev. 06500, ready to give to the CRS during the Initiating Cue. READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions: You are an extra RO. 0 The plant is in MODE 3. The reactor is at normal operating temperature and pressure. The Reactor tripped 48 hours ago. 0 The PPCS and PCNDR are unavailable. Initiating Cue: The Shift Manager instructs you to calculate an Estimated Critical Position using 0-1.2.2 up to Step 5.7.1 using the given parameters. CUE: Hand the Operator a copy of 0-1.2.2, Critical Rod Position Calculation, Rev. 06500. Note to examiner: If asked about Rod Control before or after the reactor trip, all aspects of Rod Control were working as designed. Page 2 of 7

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION START TIME: II = CRITICAL STEP 0-1.2.2, section 1.0 thru 4.0 Performance Step: 1 Reviews sections 1.O thru 4.0. Standard: Reviews and understands sections 1.O thru 4.0. Initials for step 3.1. Comment: 0-1.2.2, section 5.1 4 Performance Step: 2 Calculate the reactivity due to Power Defect. Standard: Using the correct curves for time in life determine Power Defect within +/- 50 PCM. ACTUAL: 1150 PCM STUDENT: PCM See provided KEY for details. Comment: 0-1.2.2, section 5.2 4 Performance Step: 3 Calculate the reactivity due to Rod Worth. Standard: Using correct Integral Rod Worth table for time in life determine Integral Rod Worth within +/- 20 PCM. ACTUAL: 128.4 PC:M STUDENT: PCM See provided KEY for details. Comment: Page 3 of 7

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION 0-1.2.2, section 5.3 4 Performance Step: 4 Calculate the reactivity due to Xenon. Standard: Using correct Xenon Worth curve determine reactivity due to the change in Xenon within +/- 100 PCM. ACTUAL: 1930 PCXJ STUDENT: PCM See provided KEY for details. Comment: 0-1.2.2, section 5.4 4 Performance Step: 5 Calculate the reactivity due to Boron. Standard: Differential Boron Concentration should be made without error. Using correct Boron Worth curve determine Differential Boron Worth to within +/- 0.1 PCM. ACTUAL: -6.90 PCXJ STUDENT: PCM Reactivity added due to Boron Concentration change should be made without error. Discrepancies due to error carried forward are not considered an error in calculation. ACTUAL: -690 PCM STUDENT: PCM See provided KEY for details. Comment: 0-1.2.2, section 5.5 4 Performance Step: 6 Calculate the reactivity due to the change in effective Samarium. Standard: Using the correct curve determine the reactivity added due to effective Samarium within +/- 12.5 PCM. ACTUAL: -35 PCM STUDENT: PCM See provided KEY for details. Comment: Page 4 of 7

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION 0-1.2.2, section 5.6 4 Performance Step: 7 Calculate total reactivity change. Standard: Total reactivity change should be within +/- 350 PCM. ACTUAL: 2483.4 PCM STUDENT: PCM See provided KEY for details. Comment: 0-1.2.2, section 5,7.1 4 Performance Step: 8 Estimate Critical Rod Position. Standard: Estimated Critical Rod Position must be within the band of Bank C (34) Steps and/or BANK B (165) Steps, +/- (30) steps CALCULATED VALUE ECP ACTUAL: BANK &-STEPS 34 and/or BANK STEPS 165 STUDENT: BANK STEPS See provided KEY for details. Comment: CUE if the COLR is asked for: Read your Initiating Cue again. Terminating Cue: Evaluation on this JPM is complete. STOP TIME: TIME CRITICAL STOP TIME: Page 5 of 7

Appendix C Job PerforAance Measure Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC JPM N-RA-1 Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiners Signature: Date: Page 6 of 7

Appendix C Job Performance Measure Form ES-C-1 JPM CUE SHEET Initial Conditions: 0 You are an extra RO. 0 The plant is in MODE 3. 0 The reactor is at normal operating temperature and pressure. 0 The Reactor tripped 48 hours ago. The PPCS and PCNDR are unavailable. Initiating Cue: The Shift Manager instructs you to calculate an Estimated Critical Position using 0-1.2.2 up to Step 5.7.1 using the given parameters. Plant Status for Estimated Critical Rod Position Cvcle 34 Reactor power prior to reactor trip. 50 % (Assume steady state power for > 50 hours) Burnup 7,000 Mwd/mtu Time reactor subcritical to now 48 hours Last Boron sample prior to trip Performed 1 hour before trip, was 1300 ppm. Boron/RMW added since last sample, prior to trip 14,000 BAST ppm 0 gal boric acid 0 gal RMW Rod position prior to shutdown D Bank 180 Steps Time from now to estimated criticality 2 hours Current boron concentration from sample 2 hours ago. 1400 ppm Page 7 of 7

Appendix C Job Performance Measure Form ES-C-1 Worksheet FaciIity: Ginna Task No.: 015-004-04-01A Task/JPM

Title:

Manually Calculate QPTR JPM NO.: 2008 NRC JPM N-RA-2 WA

Reference:

2.1.7 4.4 / 4.7 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testina: Simulated Performance: Actual Performance: X Classroom Simulator X Plant Applicability: RO/SRO SUBMITTED BY: Ted Coe DATE: 6/30/08 Developer REVIEWED BY: Art Vest DATE: 6/30/08 Training Technical Reviewer REVIEWED BY: Vince Fabrizio DATE: 6/30/08 Operations Technical Reviewer APPROVED BY: John Brown DATE: 6/30/08 Training Management Y Page 1 of 8

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: QPTR correctly calculated and all critical tasks evaluated as satisfactory. Required Materials: Volts/Mamp values sheets 0-6.4 JPM N-RA-2 Key General

References:

0-6.4: Core Quadrant Power Tilt Calculation, Rev. 23 Handouts: 0-6.4: Core Quadrant Power Tilt Calculation, Rev. 23 Time Critical Task: NO Validation Time: 15 minutes Alternate Path: NO Instructor Notes: Ensure a marked up copy of 0-6.4: Core Quadrant Power Tilt Calculation and Volts/Mamp values sheets are ready to give to the operator during the Initiating Cue. Use 0-6.4 JPM N-RA-2 Key for correct values. READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions: You are the HCO. 0 I will be the CRS if you need one. 0 The plant was at 100% power when Control Rod G-9dropped. 0 AP-RCC.3, Dropped Rod Recovery was entered. The plant is now at 92.5% and stable. PPCS is out of service. Initiating Cue: The CRS directs you to perform a QPTR per Attachment 1 of 0-6.4, Quadrant Power Tilt Ratio Calculation. CUE: Hand the Operator marked up copies of 0-6.4: Core Quadrant Power Tilt Calculation, Rev. 23 and Volts/Mamp values sheets. Page 2 of 8

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP For the 2008 ILT NRC Exam load I/C # 179 if simulator is used and ensure PPCS monitors are off. or Any 100% IC (IC-19). The plant in a normal 100% power lineup. In a normal 50/50 electric lineup. Insert Malf. ROD02 - G9 Dropped Rod G-9 (Stationary Grippers). Place rods in manual. Ensure PPCS monitors are off. Allow plant to stabilize and Freeze. Page 3 of 8

-Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION START TIME:

.I= CRITICAL STEP 0-6.4, step 6.1.1 thru 6.1.3 Performance Step: 1        0   IF one power range channel is inoperable, THEN ENSURE the QPTR Monitor alarm has been declared nonfunctional, AND PERFORM TSR 3.2.4.2. IF NOT, THEN MARK this Step N/A.

0 IF one power range channel is inoperable AND Thermal Power is less than 75% RTP, THEN CALCULATE the Quadrant Power Tilt Ratio using the remaining three power range channels. IF NOT, THEN MARK this Step N/A . 0 IF one power range channel is inoperable when greater than or equal to 75% RTP AND the channel is NOT expected to be returned to service within 12 hours, THEN NOTIFY Reactor Engineering as soon as possible since a flux map may need to be performed. IF NOT, THEN MARK this Step N/A. Standard: Marks all (3) steps N/A Comment: 0-6.4, step 6.1.4 Note Performance Step: 1 Volts/Mamp values for upper and lower detectors; determine if values are less than 3 months old. Standard: 0 Looks on sheets provided for Volts/Mamp values for proper date. Determines walues are less than 3 months old. Note: Applicant may use the wrong data sheet, this will yield an incorrect answer. Comment: Page 4 af 8

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION 0-6.4, step 6.1.4 / Att. 1 step 1 /, Performance Step: 2 Records Mamps and Volts/Mamps for each channel and calculates total volts for each power range channel. Standard: 0 Obtains Power Range detector currents from NI drawer pictures. 0 Obtains Volts/Mamp values from provided sheets. 0 Records all values on Attachment 1. 0 See 0-6.4 JPM N-RA-2 Key for correct values. 0 Critical criteria for values from sheets must be exactly correct. 0 Critical criteria for values from meters must be +/- .010. 0 Initials for step completion. Comment: 0-6.4, step 6.1.4 / Att. 1 step 2 Note

 ,/ Performance Step: 4 IF one power range channel inoperable, THEN the Highest (Total) in numerator of the equation below must be multiplied by three instead of four AND only the three operable channels are to be summed in the denominator.

Standard: 0 Uses all four channels in QPTR calculation. Comment: 0-6.4, step 6.1.4 / Att. 1 step 2 4 Performance Step: 5 Calculate QPTR. Standard: Correctly calculates QPTR. See 0-6.4 JPM N-RA-2 Key for correct values (QPTR = 1.053). Critical criteria for calculated value must be +/- .015. Initials for step completion. Comment: Page 5 of 8

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION 0-6.4 Att. 1, step 3 Performance Step: 6 Independent Verification. Standard: Asks for an iridependent verification. CUE: No further actions are required. Comment: Terminating Cue: Evaluation on this JPM is complete. STOP TIME: TIME CRITICAL STOP TIME: Page 6 of 8

Appendix C Job Performance Measure Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC JPM N-RA-2 Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiners Signature: Date: Page 7 of 8

Appendix C Job Performance Measure Form ES-C-1 JPM CUE SHEET Initial Conditions: You are the HCO. I will be the CRS if you need one. 0 The plant was at 100% power when Control Rod G-9dropped. AP-RCC.3, Dropped Rod Recovery was entered. 0 The plant is now at 92.5% and stable. PPCS is out of service. Initiating Cue: The CRS directs you to perform a QPTR per Attachment 1 of 0-6.4, Quadrant Power Tilt Ratio Calculation. Page 8 of 8

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Ginna TasWJPM

Title:

Tagout Boundary for B Heater JPM NO.: 2008 NRC JPM N-RA-3 Drain Tank Pump WA

Reference:

2.2.13 4.1 / 4.3 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testina: Simulated Performance: Actual Performance: X Classroom X Simulator Plant Applicability: RO/SRO SUBMITTED BY: Ted Coe DATE: 6/30/08 Developer REVIEWED BY: Art Vest DATE: 6/30/08 Training Technical Reviewer REVIEWED BY: Vince Fabrizio DATE: 6/30/08 Operations Technical Reviewer APPROVED BY: John Brown DATE: 6/30/08 Training Management Page 1 of 7

Appendix C Job Perforimance Measure Form ES-C-1 Worksheet Task Standard: Provide adequate Hold Boundary for B Heater Drain Tank Pump and all critical tasks evaluated as satisfactory. Required Materials: None General

References:

A-1401, Station Holding Rules, Rev.06300 PID: 33013-1923, Rev. 22 PID: 10905-00358, Rev. 2 PID: 33013-0653 Rev. 13 Handouts: A-1401, Station Holding Rules, Rev.06300 PID: 33013-1923, Rev. 22 PID: 10905-00358, Rev. 2 PID: 33013-0653 Rev. 13; Time Critical Task: NO Validation Time: 20 minutes Alternate Path: NO Instructor Notes: Ensure a copy of A-1401, Station Holding Rules, Rev.06300 is ready to give to the operator during the Initiating Cue. 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: 0 The unit was at 80% Power. 0 You are an extra RO in the Work Control Center. 0 B Heater Drain Tank Pump is making noises and will require a lower pump bearing replacement. The plant has down powered to 40% to make repairs to the 6 Heater Drain Tank Pump. Heater Drain Tank temperature is 305°F. Heater Drain Tank pressure is 74 psig. Initiating Cue: The Shift Manager requests you to determine the Hold Boundaries for the E? Heater Drain Tank Pump. Gland Seal and Service Water side Holds will be held by a different Hold section. On the request below, record Equipment NamedEIN, the Required Positions, type of tag to be hung and order tags are to be hung per A-1401, Station Holding Rules requirements. When completed, provide list and any comments to the Shift Manager. See Examiner with any questions or concerns concerning the Hold. CUE: Hand the Operator a copy of A-1401, Station Holding Rules, Rev.06300. Page 2 of 7

Appendix C Job Perforniance Measure Form ES-C-1 PERFORMANCE INFORMATION START TIME: II= CRITICAL STEP Examiners Note: Due to the elevated temperature of the Heater Drain Tank (HDT) the Hold should have double valve pratection/isolation. However due to plant power and system configuration this cannot be achieved. There are (2)acceptable options:

a. Request an Exceptional Hold. or

b. Reduce system temperature to less than 200°F.

CUE: Hand the Operator a copy of PID: 33013-1923,Rev. 22 and PID: 33013-0653Rev. 13 when asked for. CUE: When asked for direction on Hold, ask for recommendation (see a. and b. above). CUE: Write Hold as an Exceptional Hold. A-1401 Performance Step: 1 Refers to procedure, A-1401 as needed. Standard: Uses A-1401 as needed. Comment: Prints Performance Step: 2 Refers to prints as needed: PID: 33013-1923, Rev. 22 PID: 10905-00358, Rev. 2 PID: 33013-0653 Rev. 13 Standard: Uses prints as needed: PID: 33013-1923, Rev. 22 PID: 10905-00358, Rev. 2 PID: 33013-0653 Rev. 13 CUE: Only if asked for provide PID: 10905-00358this can be done at any time. Comment: Page 3 of 7

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION 4 Performance Step: 3 Determines Hold Boundary for B Heater Drain Tank Pump. Standard: See Key on next page. 0 Equipment may be listed in any order. Comment: Page 4 of 7

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION KEY FOR PREFORMANCE STEP ## 3 REQUEST EQUIPMENT NAMES / EIN FOR REQUIRED TYPE OF TAG ORDER ISOLATED WORK AREA POSITION REQUIRED TAGS TO BE HUNG I ~.

1. I V-4114 Closed Hold 3 I 2. I V-4118 Closed 1 Hold 13

3. V-4116 Closed Hold 3

4. V-4120 Closed Hold 3

5. V-3098 ** Open Hold or No Tag 4

6. V-2967A ** Open Hold or No Tag 4

7. V-2967B ** Open Hold or No Tag 4

8. V-3094D

• Open Hold or No Tag 4

9. V-3093F" Open Hold or No Tag 4

         " B Heater Drain Tank Pump MCB           Pull/Stop             Block            1 H/S I/HDPIB Racked out/Knife      Hold             2 switch
                                                  ~. open 12.

13. I 14. I 19 20.

 *To satisfy the critical step for V-3094D and V-3093F, either valve or both valves may be listed as drain paths.
 **To satisfy the critical step for a vent path, either V-3098 and/or V-2967A and V-2967B may be listed as vent paths.

Comments:

1. Identifies (2) valve boundary (with bleed valve) cannot be provided per 5.6.a.2, for fluids greater than 200°F if unit stays at 40% to perform work.

2. For tag order, 1 and 2 must be first and second, any tag 3s can be in any order after 1 and 2 and before any 4s. Tag 4s can be in any order after all the 3s are hung.

Terminating Cue: Evaluation on this JPM is complete. STOP TIME: TIME CRITICAL STOP TIME: Page 5 of 7

Appendix C Job Performance Measure Form ES-C-I VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC JPM W-RA-3 Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiners Signature: Date: Page 6 of 7

Appendix C Job Performance Measure Form ES-C-1 JPM CUE SHEET Initial Conditions: The unit was at 80% Power. You are an extra RO in the Work Control Center.

                              " B Heater Drain Tank. Pump is making noises and will require a lower pump bearing replacement.

The plant has down powered to 40% to make repairs to the " 6Heater Drain Tank Pump. Heater Drain Tank temperature is 305°F. Heater Drain Tank pressure is 74 psig. Initiating Cue: The Shift Manager requests you to determine the Hold Boundaries for the " B Heater Drain l a n k Pump. Gland Seal and Service Water side Holds will be held by a different Hold section. On the request below, record Equipment Names/EIN, the Required Positions, type of tag io be hung and order tags are to be hung per A-1401, Station Holding Rules requirements. When completed, provide list and any comments to the Shift Manager. See Examiner with any questions or concerns concerning the Hold. REQUEST EQUIPMENT NAMES / EIN FOR ISOLATED WORK AREA REQUIRED POSITION TYPE OF TAG REQUIRED ORDER TAGS TO BE 11 HUNG I I 1. I I 2. I I 3. 1 I 4. I 5. 6. 7. 8. 11. 12. 13. 14. 15. 17. 18. 19 20. Comments: Page 7 of 7

Appendix C Job Performance Measure Form ES-C-1 Worksheet FaciIity: Ginna Task No.: 344-006-05-01 TasMJPM

Title:

Monitor Critical Safety Function JPM NO.: 2008 NRC JPM N-RA-4 Status Trees WA

Reference:

2.4.13 4.0 14.6 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testina: Simulated Performance: Actual Performance: X Classroom X Simulator -- Plant Applicability: RO/SRO SUBMITTED BY: Ted Coe DATE: 6/30/08 Developer REVIEWED BY: Art Vest DATE: 6/30/08 Training Technical Reviewer REVIEWED BY: Vince Fabrizio DATE: 6/30/08 Operations Technical Reviewer APPROVED BY: John Brown DATE: 6/30/08 Training Management Page 1 of 7

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: Correctly monitor CSFSTs and reporthecommend correct red path/procedure and all critical tasks evaluated as satisfactory. Required Materials: CSFST Binder with cards and Grease pencils or equivalent. General

References:

F-0.1: SUBCRITICALITY CSFST F-0.2: CORE COOLING CSFST F-0.3: HEAT SINK CSFST F-0.4: INTEGRITY CSFST F-0.5: CONTAINMENT CSFST F-0.6: INVENTORY CSFST Handouts: CSFST Binder Time Critical Task: NO Validation Time: 10 minutes Alternate Path: NO Instructor Notes: Ensure CSFST Binder with cards and Grease pencils or equivalent are available and data sheet # l . 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: 0 You are an extra RO. The plant has experienced a Reactor Trip and a Safety Injection. I will be the CRS. The SM has directed you to monitor Critical Safety Function Status Trees. It has been 65 minutes since the Reactor Tripped. Tavg just prior to the trip was 574OF. Initiating Cue: Monitor ALL the Critical Safety Function Status Trees us,,ig Data Sheet

                           # 1 and make a written report to the CRS identifying each Critical Safety Function, which CSF is the highest priority and what procedure is recommended.

Page 2 of 7

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION START TIME: .I= CRITICAL STEP F-0.1 4 Performance step: 1 Monitor Subcriticality and determine correct terminus. Standard: MONITOR: (F-0.1) PowerRange Intermediate Range SUR Source Range energized Source Range SUR as necessary Correct terminus: Orange - FR-S.l Comment: F-0.2 4 Performance Step: 2 Monitor Core Cooling and determine correct terminus. Standard: MONITOR: (F-0.2) 0 Core Exit Thermocouples 0 RCS Subcooling 0 RCP status 0 RVLlS Cnmt Pressure 0 Cnmt Radiation as necessary Correct terminus: Red - FR-C.1 Comment: F-0.3 /, Performance Step: 3 Monitor ,sat Sink and determine correct terminus. I Standard: MONITOR: (F-0.3) 0 S/G Level Feedwater Flow 0 S/G Pressure 0 Cnmt Pressure 0 Cnmt Radiation as necessary Correct terminus: Green Comment: Page 3 of 7

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION F-0.4 4 Performance Step: 4 Monitor INTEGRITY and determine correct terminus. Standard: MONITOR: (F-0.4) 0 RCS Cold Leg Temperature decrease over last 60 minutes RCS Cold Leg Temperature 0 RCS Pressure, locate point on curve as necessary Correct terminus: Green Comment: F-0.5 /, Performance Step: 5 Monitor CONTAINMENT and determine correct terminus. Standard: MONITOR: (F-0.5) 0 Cnmt Pressure 0 Cnmt Sump 3 Level 0 Cnmt Radiation as necessary Correct terminus: Red - FR-Z.l Comment: F-0.6 /, Performance step: 6 Monitor INVENTORY and determine correct terminus. Standard: MONITOR: (F-0.6) SI Pump status Pressurizer Level RCP status RVLlS as necessary Correct terminus: Yellow - FR-1.2 Comment: Page 4 of 7

Appendix C Job Performance Measure Form ES-C-1 PERFORMANICE INFORMATION Report to CRS /, Performance Step: 7 Identify highest priority Critical Safety Function. Recommend procedure. Standard: Identify highest priority. RED terminus: Core Cooling Recommend correct procedure: Enter FR-C.1, Comment: Terminating Cue: Evaluation on this JPM is complete. STOP TIME: TIME CRITICAL STOP TIME: Page 5 of 7

I Appendix C Job Performance Measure Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC JPM N-RA-4 Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiners Signature: Date: Page 6 oil 7

Appendix C Job Performance Measure Form ES-C-1 JPM CUE SHEET Initial Conditions: 0 You are an extra RO. 0 The plant has experienced a Reactor Trip and a Safety Injection. 0 I will be the CRS. 0 The SM has directed you to monitor Critical Safety Function Status Trees. 0 It has been 65 minutes since the Reactor Tripped. 0 Tavg just prior to the trip was 574°F. Initiating Cue: Monitor ALL the Critical Safety Function Status Trees using Data Sheet

                       # 1 and make a written report to the CRS identifying each Critical Safety Function, which CSF is the highest priority and what procedure is recommended.

Data Sheet ## 1 Reactor Power is 0% All Reactor Trip Breakers are Open Intermediate Range indication is 3x10-l Intermediate Range SUR is 0.1 Source Range Indication is lx103 Source Range SUR is 0.1 RCS Pressure is 982 psig A RCS cold Leg Temperature is 495°F A RCS cold Leg Temperature is 490°F B RCS cold Leg Temperature is 493°F B RCS cold Leg Temperature is 491°F Pressurizer water level is 0% RVLlS water level is 40% CETs are 709°F No SI pumps are running (2) RHR Pumps are running A RCP Pump is tripped 9 RCP Pump is tripped Cnmt Pressure is 62 psig R-29, Cnmt Radiation Monitor reads 1500 mrem/hr R-30, Cnmt Radiation Monitor reads 1600 mrem/hr Cnmt Sump A is 200 inches Cnmt Sump B is 120 inches A Stream Generator Water Level is 27% B Stream Generator Water Level is 28% A Stream Generator Pressure is 922 psig BStream Generator Pressure is 920 psig TDAFW Pump is not running A MDAFW Pump is running B MDAFW Pump is running A MDAFW Pump flow is 100 gpm B MDAFW Pump flow is 105 gpm Page 7 of 7

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Ginna Task No.: 001-008-01-02 TasWJPM

Title:

Verify Estimated Critical Rod JPM NO.: 2008 NRC JPM N-SA-1 Position Calculation WA

Reference:

2.1.37 4.6 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testina: Simulated Performance: Actual Performance: X Classroom X Simulator -- Plant Applicability: SRO SUBMITTED BY: Ted Coe DATE: 6/30/08 Developer REVIEWED BY: Art Vest DATE: 6/30/08 Training Technical Reviewer REVIEWED BY: Doua Gomez DATE: 6/30/08 Operations Technical Reviewer APPROVED BY: John Brown DATE: 6/30/08 Training Management Page 1 of 8

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: Critical Rod Position Calculation verification performed correctly finding all errors and all critical tasks evaluated as satisfactory. Required Materials: Calculator, Nomogragh Tables General

References:

0-1.2.2, Critical Rod Position Calculation, Rev. 06500 Handouts: Completed 0-1.2.2, Critical Rod Position Calculation, Rev. 06500 Time Critical Task: NO Validation Time: 30 minutes Alternate Path: NO Instructor Notes: Have a copy of a completed copy of 0-1.2.2, Critical Rod Position Calculation, Rev. 06500, ready to give to the CRS during the Initiating Cue. READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions: You are the Control Room Supervisor. 0 The plant is in MODE 3. 0 The reactor is at normal operating temperature and pressure. The Reactor tripped 48 hours ago. The PPCS and PCNDR are unavailable. The HCO has completed an Estimated Critical Position using 0-1.2.2. Initiating Cue: The Shift Manager instructs you to perform the independent verification of 0-1.2.2, Critical Rod Position Calculation, up thru Step 5.7.1, using the given parameters. Report all results to the Shift Manager. CUE: Hand the Operator a marked up copy of 0-1.2.2, Critical Rod Position Calculation, Rev. 06500. Page 2 of 8

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION START TIME: .I= CRITICAL STEP 0-1.2.2, section 1.O thru 4.0 Performance Step: 1 Reviews sections 1.O thru 4.0. Standard: Reviews and understands sections 1.Othru 4.0. Verifies initials on step 3.1. Comment: 0-1.2.2, section 5.1 Performance Step: 2 Verifies correct calculation of the reactivity due to Power Defect. Standard: Discovers no errors. Using the correct curves for time in life determine Power Defect. Comment: ACTUAL: 1150 PCM_ HCO: 1150 PCM 0-1.2.2, section 5.2 4 Performance Step: 3 Verifies correct calculation of the reactivity due to Rod Worth. Standard: Discovers error in Rod Worth reactivity calculation. Using correct integral Rod Worth table for time in life determines reactivity due to Rod Worth. Comment: ACTUAL: 128.5 PCM HCO: 194 PCM Page 3 of 8

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCIE INFORMATION 0-1.2.2, section 5.3 Performance Step: 4 Verifies correct calculation of the reactivity due to Xenon. Standard: Discovers no errors. Using correct Xenon Worth curve determine reactivity due to the change in Xenon. Comment: ACTUAL: 1930 PChJ HCO: 1930 PCM 0-1.2.2, section 5.4 Performance Step: 5 Verifies correct calculation of the reactivity due to Boron. Standard: Discovers no errors. Using correct Boron 'Worth curve determine Differential Boron. Reactivity added due to Boron Concentration change should be made without error. Comment: Differential Boron: ACTUAL: -6.90 PCM HCO: -6.90 PCM Boron Con. Change: ACTUAL: -690 PCM HCO: -690 PCM 0-1.2.2, section 5.5 /, Performance step: 6 Verifies correct calculation of the reactivity due to the change in "effective" Samarium. Standard: Discovers error in reactivity added due Samarium calculation. Using the correct curve determine the reactivity added due to effective Samarium. Comment: ACTUAL: -35 PCM HCO: -185 PCM Page 4 of 8

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION 0-1.2.2, section 5.6 .( Performance Step: 7 Verifies correct calculation of total reactivity change. Standard: Discovers error in total reactivity change. Total reactivity change calculated. Comment: ACTUAL: 2483.4 PCM HCO: 2399 PCM 0-1.2.2, section 5.7 4 Performance Step: 8 Verifies correct Estimate Critical Rod Position. Standard: Discovers error in calculated value for ECP. Determines Estimated Critical Rod Position. Comment: ACTUAL: BANK C STEPS 34 . HCO: BANK C STEPS 3 9 . Page 5 of 8

Appendix C Job Performance Measure Form ES-C-1 PERFORMANICEINFORMATION Standard: Informs the SM of the following errors: 0 Reactivity dlue to Integral Rod Worth. Reactivity due to Samarium. 0 Total Reactivity Change. 0 Estimated Critical Rod Position. Informs the SM that the ECP will have to be reperformed (or words to that effect). Cue: Acknowledge report. Comment: Terminating Cue: Evaluation on this JPM is complete. STOP TIME: TIME CRITICAL STOP TIME: Page 6 of 8

I Appendix C Job Performance Measure Form ES-C-1 VERI Fl CAT1ON OF COMPLETION Job Performance Measure No.: 2008 NRC JPM I\-SA-1 Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiners Signature: Date: Page 7 of 8

Appendix C Job Performance Measure Form ES-C-1 JPM CUE SHEET Initial Conditions: 0 You are the Control Room Supervisor. 0 The plant is in MODE 3. 0 The reactor is at normal operating temperature and pressure. 0 The Reactor tripped 48 hours ago. 0 The PPCS and PCNDR are unavailable. 0 The HCO has completed an Estimated Critical Position using 0-1.2.2. Initiating Cue: The Shift Manager instructs you to perform the independent verification of 0-1-2.2, Critical Rod Position Calculation, up thru Step 5.7.1, using the given parameters. Report all results to the Shift Manager. Plant Status for Estimated Critical Rod Position Cvcle 34 Reactor power prior to reactor trip. 50 Yo (Assume steady state power for > 50 hours) Burnup 7,000 Mwd/mtu Time reactor subcritical to now 48 hours Last Boron sample prior to trip Performed 1 hour before trip, was 1300 ppm. Boron/RMW added since last sample, prior to trip 14,000 BAST ppm 0 gal boric acid 0 gal RMW Rod position prior to shutdown D Bank 180 Steps Time from now to estimated criticality 2 hours Current boron concentration from sample 2 hours ago. 1400 ppm Page 8 (of 8

Appendix C Job Perfoirmance Measure Form ES-C-1 Worksheet Facility: Ginna Task No.: 341-030-03-02A Task/JPM

Title:

A-52.12, Nonfunctional Equipment JPM No.: 2008 NRC N-SA-2 Important to Safety WA

Reference:

2.1.18 3.8 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testina: Simulated Performance: Actual Performance: X Classroom X Simulator -- Plant Applicability: SRO SUBMITTED BY: Ted Coe DATE: 6/30/08 Developer REVIEWED BY: Art Vest DATE: 6/30/08 Training Technical Reviewer REVIEWED BY: Vince Fabrizio DATE: 6/30/08 Operations Technical Reviewer APPROVED BY: John Brown DATE: 6/30/08 Training Management Page 1 of 7

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: Determined the QPTR Monitor Alarm is inoperable, fill out A-52.12, Attachment 1 correctly and all critical tasks evaluated as satisfactory. Required Materials: Attached Key. General

References:

A-52.12 Nonfunctional Equipment Important to Safety, Rev. 05900 Technical Requirements Manual (TRM) Rev. 35 Handouts: A-52.12 Nonfunctional Equipment Important to Safety, Rev. 05900 A-52.12 att. 1 (4 pages), A-52.12 att. 2 (1 page) Time Critical Task: NO Validation Time: 20 minutes Alternate Path: NO Instructor Notes: Have a copy of A-52.12 Nonfunctional Equipment Important to Safety, Rev. 05900 and A-52.12 att. 1 (4 pages), ready to give to the CRS when cued. READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions: You are the CRS. 0 The plant is at 98% power, no equipment is out of service. Initiating Cue: The CO has just complete'd S-26.1, Computer Program Check. All sections were performed sat, except the QPTR Monitor Alarm did not alarm. Page 2 d 7

I Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION START TIME: d = CRITICAL STEP Notifications Performance Step: 1 May notify the following people: SM, WCC, Maintenance, WWM, Operations and Plant Supervision Standard: Notifies SM and others as time permits. (May be done at any time.) Cue: Acknowledge reports. Comment: TRM TR 3.2.4 Condition II Performance Step: 2 QPTR Monitor Alarm is inoperable IAW TR 3.2.4 - The QPTR monitor alarm shall be OPERABLE when in MODE 1 with THERMAL POWER > 50% RTP Standard: QPTR Monitor Alarm is inoperable IAW TR 3.2.4 due to alarm not alarming and Thermal Power is at 98%. Comment: TRM - TR 3.2.4 Required Action and Completion Time 4 Performance Step: 3 Required Action A.l or A.2 needs to be completed. Standard: Determines Required Action A.l or A.2 needs to be completed once within 24 hours and everv 24 hours there after. Cue: After examinee determines QPTR Monitor Alaim is inoperable, as the SM tell the examinee to fill out the appropriate paper work. Comment: CUE: Hand the examinee a copy of A-52.12 Nonfunctional Equipment important to Safety, Rev. 05900 and Attachment 1 (4 pages). Page 3 of 7

Appendix C Job Perforrnance Measure Form ES-C-1 PERFORMANCE INFORMATION A-52.12 Attachment I page 1 4 Performance Step: 4 Properly fill in appropriate data on A-52.12 Att. I, Page 1 of 4. Standard: See attached Key for requirements. Critical task is to determine correct REQUIRED COMPLETION DATWIME in Step 6.6.1(10). CUE : When requested provide the following information: 0 The CR number is CR-2008-000792. 0 The work order number is: W02344061. The HCO has determined with the QPTR Monitor Alarm OOS, EOOS PRF color is GREEN and EOOS Top Level System Status is GREEN. Comment: A-52.12 Attachment I page 2 Performance Step: 5 Properly fill in appropriate data on A-52.12 Att. I, Page 2 of 4. Standard: See attached Key for requirements. CUE when CRS determines an A-52.16 is required: The WCC will fill out the A-52.16, Comment: A-52.12 Attachment Ipage 3 Performance Step: 6 Properly fill in appropriate data on A-52.12 Att. I, Page 3 of 4. Standard: See attached Key for requirements. Comment: A-52.12 Attachment I page 4 Performance Step: 7 Properly fill in appropriate data on A-52.12 Att. I, Page 4 of 4. Standard: See attached Key for requirements. Comment: Page 4 of 7

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION A-52.12 Attachment 2 page 1 Performance Step: 8 Properly fill in appropriate data on A-52.12 Att. 2, Page 1 of 1. Standard: See attached Key for requirements. This is a non-critical step. Performance is optional and is not required at this time but is required when required action is performed. Candidate may ormay not fill this page out. CUE: If requested provide A-52.12 Attachment 2, to candidate. Comment: Terminating Cue: Evaluation on this JPM is complete. STOP TIME: TIME CRITICAL STOP TIME: Page 5 of 7

Appendix C Job Performance Measure Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC N-SA-2 Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiners Signature: Date: Page 6 of 7

                                                                                          ~

Appendix C Job Perforniance Measure Form ES-C-1 JPM ClJE SHEET Initial Conditions: You are the CRS. The plant is at 98% power, no equipment is out of service. Initiating Cue: The CO has just completed S-26.1, Computer Program Check. All sections were performed sat, except the QPTR Monitor Alarm did not alarm. Page 7 of 7

1 Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Ginna Task No-: 342-004-03-02A TasWJPM

Title:

Review the Tagout Boundary for B JPM No.: 2008 NRC JPM N-SA-3 Heater Drain Tank Pump WA

Reference:

2.2.13 4.3 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testina: Simulated Performance: Actual Performance: X Classroom X Simulator -- Plant Applicability: SRO SUBMITTED BY: Ted Coe DATE: 6/30/08 Developer REVIEWED BY: Art Vest DATE: 6/30/08 Training Technical Reviewer REVIEWED BY: Vince Fabrizio DATE: 6/30/08 Operations Technical Reviewer APPROVED BY: John Brown DATE: 6/30/08 Training Management Page 1 of 6

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: Identify Hold Boundary foir B Heater Drain Tank Pump is inadequate and all critical tasks evaluated as satisfactory. Required Materials: None General

References:

A-1401, Station Holding Rules, Rev.06300 PID: 33013-1923, Rev. 22 PID: 10905-0035B, Rev. 2 PID: 33013-0653 Rev. 13 Handouts: A-1401, Station Holding Rules, Rev.06300 PID: 33013-1923, Rev. 2i! PID: 10905-0035B, Rev. 2 PID: 33013-0653 Rev. 13 Time Critical Task: NO Validation Time: 20 minutes Alternate Path: NO Instructor Notes: Ensure a copy of A-1401, Station Holding Rules, Rev.06300, is ready to give to the operator during the Initiating Cue. 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: 0 The unit was at 80% POWER. 0 You are an extra SRO in the Work Control Center. 0 B Heater Drain Tanik Pump is making noises and will require a lower pump bearing replacement. The plant has down powered to 40% to make repairs to the B Heater Drain Tank Pump. Heater Drain Tank temperature is 305°F. Heater Drain Tank pressure is 74 psig. Initiating Cue: The Shift Manager requests you to review the Hold Boundaries for the B Heater Drain Tank Pump. Gland Seal and Service Water side Holds will be held by a different Hold section. On the request below, an extra RO has recorded the Equipment Names/EIN, the Required Positions, type of tags to be hung and order tags are to be hung per A-1401, Station Holding Rules requirements to perform the work. When completed, provide an update to the Shift Manager. See Examiner with any questions or concerns concerning the Hold. CUE: Hand the Operator a copy of A-1401, Station Holding Rules, Rev.06300. Page 2 of 6

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION START TIME: 4 = CRITICAL STEP Examiners Note: Due to the elevated temperature of the Heater Drain Tank (HDT) the Hold should have double valve profection/isolation. However due to plant power and system configuration this cannot be achieved. There are (2) acceptable options:

a. Request an Exceptional Hold. or

b. Reduce system temperature to less than 200°F.

CUE: Hand the Operator a copy of PID: 33013-1923, Rev. 22 and PID: 33013-0653 Rev. 13 when asked for. CUE: When asked for direction on Hold, ask for recommendation (seea. and b. above). CUE: Write Hold as an Exceptional Hold. A-1401 Performance Step: 1 Refers to procedure, A-1401 as needed. Standard: Uses A-1401 as needed. Comment: Prints Performance Step: 2 Refers to prints as needed: PID: 33013-1923, Rev. 22 PID: 10905-00358, Rev. 2 PID: 33013-0653 Rev. 13 Standard: Uses prints as needed: 0 PID: 33013-1923, Rev. 22 0 PID: 10905-0035B, Rev. 2 0 PID: 33013-0653 Rev. 13 CUE: Only if asked for, provide PID: 10905-0035B, this can be done at any time. Comment: Page 3 olf 6

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE I NFORMATION /, Performance step: 3 Determines Hold Boundary for B Heater Drain Tank Pump. Standard: Hold boundary is inadequate for the following reasons: 0 V-3098 should be Open not Closed and should be a 4 for order. 0 V-4120 should1 be Closed not Open and should be a 3 for order. 0 V-4116 must be added as a Hold tag, Closed and order should be a 3. 0 V-3094C is for the A HDT pump and should not be listed. V-3093F should be listed as Open/Hold/4. Identifies of the following issues associated with fluids greater than 200°F.

1. Identifies (2) valve boundary (with bleed valve) is not provided per 5.6.a.2, for fluids greater than 200°F if unit stays at 40% to perform work.

2. Identifies can work B Heater Drain Tank Pump as an Exceptional Hold at 40%.

3. Lower Power as needed to lower HDT fluid temperature to less than 200°F.

Comment: Terminating Cue: Evaluation on this JPM is complete. STOP TIME: TIME CRITICAL STOP TIME: Page 4 olf 6

Appendix C Job Performance Measure Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC JPM N-SA-3 Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiners Signature: Date: Page 5 of 6

Appendix C Job Performance Measure Form ES-C-1 JPM CUE SHEET Initial Conditions: 0 The unit was at 80%#POWER. 0 You are an extra SRO in the Work Control Center. 0 B Heater Drain Tank Pump is making noises and will require a lower pump bearing replacement. The plant has down powered to 40% to make repairs to the W Heater Drain Tank Pump. Heater Drain Tank temperature is 305°F. Heater Drain Tank pressure is 74 psig. Initiating Cue: The Shift Manager requests you to review the Hold Boundaries for the B Heater Drain Tank Pump. Gland Seal and Service Water side Holds will be held by a different Hold section. On the request below, an extra RO has recorded the Equipment Names/EIN, the Required Positions, type of tags to be hung and order tags are to be hung per A-1 401, Station Holding Rules requirements to perform the work. When completed, provide an update to the Shift Manager. See Examiner with any questions or concerns concerning the Hold. REQUEST 17. 18. 19 20. Comments: None.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Ginna Task No.: 073-008-01-01 TasWJPM

Title:

Implement the requirements of JPM NO.: 2008 NRC JPM N-SA-4 ODCM for RMS Operability. WA

Reference:

2.3.15 3.1 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testina: Simulated Performance: Actual Performance: X Classroom X Simulator ~- Plant Applicability SRO SUBMITTED BY: Ted Coe DATE: 6/30/08 Developer REVIEWED BY: Art Vest DATE: 6/30/08 Training Technical Reviewer REVIEWED BY: Don Dettman DATE: 6/30/08 Operations Technical Reviewer APPROVED BY: John Brown DATE: 6/30/08 Training Management Page 1 oil 6

I Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: Identify Gas Delay Tank release must be secured and Aux Building ventilation may continue provided (8) hour samples are taken and all critical tasks evaluated as satisfactory. Required Materials: None General

References:

Offsite Dose Calculation Manual (ODCM), Rev. 21 S-4.2.5, Release of Gas Decay Tank Rev. 19 Handouts: Offsite Dose Calculation Manual (ODCM), Rev. 21 S-4.2.5, Release of Gas Decay Tank Rev. 19 Time Critical Task: NO Validation Time: 15 minutes Alternate Path: NO Instructor Notes: None READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions: You are the CRS. 0 The plant is in MODE 1 with a normal at power lineup. R-14A5 has been out of service for the past week. A Gas Decay Tank is being released per S-4.2.5, Release of Gas Decay Tank. The HCO informs you R-14 radiation monitor has just failed low. All other plant equipment is operating properly. Initiating Cue: What are your actions? Examiners Note: If asked for S-4.2.5, Release of Gas Decay Tank Rev. 19 provide a copy. Page 2 of 6

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION START TIME:

 .I= CRITICAL STEP ODCM Performance Step: 1    Identifies entry into ODCM required.

Standard: Recognizes entry condition for OCDM and finds a copy of the OCDM. Comment: ODCM, section 3.2

 ,,/ Performance Step: 2    Enters section 3.2, Gaseous Effluent Monitors.

Reads and understands Controls, Applicability, Notes and Actions (2). Standard: First Action: N/A. Second Action: With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.2-1. Restore the inoperable instrumentation to OPERABLE status within 30 days or, if not, explain in the next Annual Radioactive Effluent Release Report, pursuant to Section 6.2 of the ODCM, why this inoperability was not corrected in a timely manner. CUE: Acknowledge report. Comment: ODCM, section 3.2 /,, Performance step: 3 Enters section 3.2, Gaseous Effluent Monitors. Reads and understands Controls, Applicability, Notes and Actions for: A GDT Release Standard: 1. Identifies R-14 is required for GDT release. Orders A GDT release secured, per table 3.2-1, step c, note (b). CUE: Acknowledge report. Comment: Page 3 of 6

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION ODCM, section 3.2 /, Performance Step: 4 Enters section 3.2, Gaseous Effluent Monitors. Reads and understands Controls, Applicability, Notes and Actions for: Aux Building Ventilation running Standard: 1. Identifies Aux Building Ventilation still running with R-14 and R-14A5 out of service. Orders action # 2: If the number of OPERABLE channels is less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided (orders) grab samples are taken and analyzed for isotopic activity at least once per 8 hours, per table 3.2-1, step c, action 2. CUE: Acknowledge report. Comment: Terminating Cue: Evaluation on this JPM is complete. STOP TIME: TIME CRITICAL STOP TIME: Page 4 of 6

Appendix C Job Performance Measure Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC JPhrrl N-SA-4 Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiners Signature: Date: Page 5 olf 6

Appendix C Job Petforrnance Measure Form ES-C-1 JPM ClUE SHEET Initial Conditions: 0 You are the CRS. The plant is in MODE 1 with a normal at power lineup. 0 R-14A5 has been out of service for the past week. 0 A Gas Decay Tank is being released per S-4.2.5, Release of Gas Decay Tank. 0 The HCO informs you R-14 radiation monitor has just failed low. 0 All other plant equipment is operating properly. Initiating Cue: What are your actions? Page 6 of 6

Appendix C Job Perforrnance Measure Form ES-C-1 Worksheet FaciIity : Ginna Task No.: 340-001-05-02C TasWJPM

Title:

Event Classification JPM NO.: 2008 NRC JPM N-SA-5 WA

Reference:

2.4.41 4.6 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testina: Simulated Performance: Actual Performance: X Classroom Simulator -- >( Plant Applicability: SRO SUBMITTED BY: Ted Coe DATE: 6/30/08 Developer REVIEWED BY: Art Vest DATE: 6/30/08 Training Technical Reviewer REVIEWED BY: Vince Fabrizio DATE: 6/30/08 Operations Technical Reviewer APPROVED BY: John Brown DATE: 6/30/08 Training Management Page 1 of 5

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: Correct classification level, EAL number and all critical tasks evaluated as satisfactory. Required Materials: None General

References:

EPlP 1-0: Ginna Station Event Evaluation and Classification, Rev. 04200 Handouts: EPIP 1-0: Ginna Station Event Evaluation and Classification, Rev. 04200 Time Critical Task: YES, 15 minutes Validation Time: 10 minutes Alternate Path: NO Instructor Notes: To be performed follo\h,.ig an evaluated simulator scenario. READ TO THE EXAMINEE I will explain the initial conditions, which steps to sitnulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions: 0 You have just completed an evaluated simulator scenario. Initiating Cue: Classify this event per EPIP 1-0. Provide classification level and EAL number. This is a time critical JPM. Page 2 of 5

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION 1/ = CRITICAL STEP Performance Step: 1 Locate a controlled copy of EPlP 1.O, Ginna Station Event Evaluation and Classification. Standard: Locates a controlled copy of EPlP 1.O. Comment: EPlP 1.0, section 4.0 Performance Step: 2 Review Precautions section of procedure. Standard: Reviews Precautions section of procedure. Comment: EPlP 1.O, section 5,,0 Performance Step: 3 Review Prerequisites section of procedure. Standard: Reviews Prerequisites section of procedure. Comment: EPlP 1.0, section 6.0 4 Performance Step: 4 Evaluate event as per EPlP 1.O. Standard: 0 Determines event classification and EAL number correctly per simulator scenario guide. Makes declaration within 15 minutes of initiating cue. Comment: Terminating Cue: Evaluation on this JPM is complete. STOP TIME: TIME CRITICAL STOP TIME: Page 3 of 5

I Appendix C Job Performance Measure Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC JPM N-SA-5 Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiners Signature: Date: Page 4 of 5

Appendix C Job Performance Measure Form ES-C-1 JPM CUE SHEET Initial Conditions: You have just comple!ted an evaluated simulator scenario. Initiating Cue: Classify this event per EPlP 1-0. Provide classification level and EAL number. This is a time critical JPM. Page 5 of 5

Appendix C Job Perforrnance Measure Form ES-C-1 Worksheet Facility: Ginna Task No.: 004-037-01-01 TasWJPM

Title:

Alternate Dilution of the RCS (R/B JPM No.: 2008 NRC JPM A occurs during dilution) WA

Reference:

004 A2.16 3.2 / 3.6 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testinq: Simulated Performance: Actual Performance: X Classroom Simulator -;X- Plant Applicability: RO/SRO SUBMITTED BY: Ted Coe DATE: 6/30/08 Developer REVIEWED BY: Art Vest DATE: 6/30/08 Training Technical Reviewer REVIEWED BY: Don Dettman DATE: 6/30/08 Operations Technical Reviewer APPROVED BY: John Brown DATE: 6/30/08 Training Management Page 1 of 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: Alternate dilution is secured and all critical tasks evaluated as satisfactory. Required Materials: None General

References:

S-3.1, Boron Concentration Control, Rev. 02900 S-12.4, RCS Leakage Surveillance Record Instructions, Rev.54 Handouts: S-3.1,Boron Concentration Control, Rev. 02900 S-12.4, RCS Leakage Surveillance Record Instructions, Rev.54, Attachment RCS Leakage Surveillance Record Time Critical Task: NO Validation Time: 15 minutes Alternate Path: Yes Instructor Notes: Have the Reactivity Binder cleaned and a copy of S-12.4, Attachment RCS Leakage Surveillance Record available for examinee. READ TO THE EXAMINEE I will explain the initial conditions, which steps to sirnulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions: You are the HCO. I will be the CRS and the CO if you need one. 0 The plant is at -98%)power in a normal 50/50at power lineup. The unit has been operating at rated power for the last 16 months. 0 Attachment 1, Makeup Determinations of S-3.1, Boron Concentration Control has been completed. Initiating Cue: Perform an alternate dilution of 100 gallons of water at 20 gpm to maintain Tavg at Tref. Page 2 of 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP For the 2008 ILT NRC Exam load I/C # 171 or Any 100% IC (IC-19). The plant in a normal -98% power lineup. In a normal 50/50electric lineup. RMW PUMP 1B in Pull-Stop. Ensure Tavg is slightly below Tref. Insert NIS07A, PR Channel Failure CH: N-41 failed low on Manual Trigger 1. Control Rods in auto. Set RMW to BA Blender flow control valve, HCV-111 controller to 40 gpm. Page 3 of 9

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION START TIME; II = CRITICAL STEP S-3.1, Att. 4, step 1.O Performance step; 1 ENSURE Attachment 1, Makeup Determinations, is complete. Standard: Given in the initial cue. Comment: S-3.1, Att. 4, step 2.0 and 2.1 Performance step: 2 2.0 The board operator SHALL inform the CRS (SM in the CRSs absence) of the intent to change core reactivity. 2.1 The CRS (SM in the CRSs absence) SHALL acknowledge the reactivity manipulation and provide input and oversight. Standard: Informs CRS of 100 gallons of water addition. (or something to that effect) CUE: Acknowledge report. Comment: S-3.1 ,Att. 4, step 3.0 -,/ Performance Step; 3 PLACE RMW MODE SELECTOR control switch to ALT DIL position. Standard: RMW MODE SELECTOR in ALT DIL. Comment: S-3.1, Att. 4, step 4.0 Performance Step: 4 SET RMW TO BA BLENDER FLOW CONTROL VLV, HCV 111, controller to the desired flow rate. Standard: RMW TO BA BLENDE3 FLOW CONTROL VLV, HCV 111, controller, set to 20 gpm. Comment: Page 4 of 9

I I Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION S-3.1, Att. 4, step 5.0 4 Performance Step: 5 SET the RMW COIUNTER, YIC-111, to the quantity determined in Attachment 1, Step 2.1. Standard: RMW COUNTER, YIC-111 set to 100 gallons. Comment: S-3.1, Att. 4, step 6.0 /, Performance Step: 6 PLACE RMW CONTROL control switch to START position. Standard: RMW CONTROL switch to START and released. Red light on, Green light off. Comment: S-3.1, Att. 4, step 7.0 Performance Step: 7 VERIFY the following: 0 RMW PUMP 1A OR 1B STARTS. 0 REACTOR MAKEUP TO VCT, AOV 1lOC, opens. RMW TO BA BLENDER FLOW CONTROL VLV, HCV 111, valve throttles open to the preset flow position. REACTOR MAKEUP TO CHG PUMP, AOV-1 lOB, opens. Standard: RMW PUMP 1A STARTS. Red light on, Green light off. 0 AOV 1lOC, opens. Red light on,Green light off. HCV 111, valve throttles open to the preset flow position. AOV-1lOB, opens. Red light on, Green light off. SIM OPERATOR: As soon as the student hias completed verifying proper lineup insert Manual Trigger 1. Comment: Page 5 of 9

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION (Start Alternate Path) II Performance Step: 8 PLACE RMW CONTROL switch to STOP position. Standard: The examinee determines a Rod Block exists and per the note prior tcll step 6.0 immediately secures the dilution operation. 0 RMW CONTROL switch in STOP. Red light off, Green light on. CUE: Acknowledge reports. (Ask for recommendationsas needed.) CUE: HCO continue with S-3.1 Attachment 4, the CO will address the other issues, Comment: S-3.1, Att. 4, step 8.0 (End Alternate Path) Performance Step: 9 WHEN dilution is camplete, THEN PERFORM the followina: 8.1 PLACE RMW MODE SELECTOR control switch 6 AUTO position. 8.2 PLACE RMW CONTROL switch to START position, and verify RMW control red light illuminated. 8.3 SET RMW 'TO BA BLENDER FLOW CONTROL VLV, HCV 111, controller to the normal flow setpoint of 40 GPM. Standard: 8.1 RMW MODE SELECTOR control switch to AUTO position. 8.2 RMW CONTROL switch in START position, Red light on, Green li'ght off. 8.3 RMW TO 814 BLENDER FLOW CONTROL VLV, HCV 111, controller at 40 GPM. Comment: S-3.1, Att. 4, step 9.0 Performance Step: 10 RECORD the amourit of reactor makeup water added on S-12.4, RCS Leakage Surveillance Record Instructions, Attachment RCS Leakage Surveillance Record. Standard: Amount added in gallons of water recorded on S-12.4, RCS Leakage Surveillance Record Instructions, Attachment RCS Leakage Surveillance Record. Comment: Page 6 of 9

Appendix C Job Perforrnance Measure Form ES-C-1 PERFORMANCE INFORMATION S-3.1, Att. 4, step 10.0 Performance Step; 11 The board operator SHALL inform the CRS (SM in the CRSs absence) the reactivity manipulation is complete. Standard: CRS notified that reactivity manipulation is complete. CUE: Acknowledge report. Comment: Terminating Cue: Evaluation on this JPM is complete. STOP TIME: TIME CRITICAL STOP TIME: Page 7 of 9

Appendix C Job Performance Measure Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC JPhI A Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

ResuIt : SAT UNSAT Examiners Sianature: Date: Page 8 of 9

Appendix C Job Perforimance Measure Form ES-C-1 JPM CUE SHEET Initial Conditions: You are the HCO. I will be the CRS and the CO if you need one. The plant is at -98% power in a normal 50/50at power lineup. 0 The unit has been operating at rated power for the last 16 months. 0 Attachment 1, Makeup Determinations of S-3.1, Boron Concentration Control has been completed. Initiating Cue: Perform an alternate dilution of 100 gallons of water at 20 gpm to maintain Tavg at Tref. Page 9 of 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet FaciIity : Ginna Task No.: 006-018-05-01A TasWJPM

Title:

Transfer ECCS to Cold Leg JPM No.: 2008 NRC JPM 6 Recirculation (Alt. Path) WA

Reference:

EPE 011 EA1.ll 4.2/4.2 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testina: Simulated Performance: Actual Performance: X Classroom Simulator -- X Plant Applicability: RO/SRO SUBMITTED BY: Ted Coe DATE: 6/30/08 Developer REVIEWED BY: Art Vest DATE: 6/30/08 Training Technical Reviewer REVIEWED BY: Don Dettman DATE: 6/30/08 Operations Technical Reviewer APPROVED BY: John Brown DATE: 6/30/08 Training Management Page 1 of 14

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: One RHR pump running, taking suction from the Containment B sump and all critical tasks evaluated as satisfactory. Required Materials: DC power panel key. General

References:

ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Rev. 04200 Handouts: ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Rev. 04200 Time Critical Task: NO Validation Time: 15 minutes Alternate Path: YES Instructor Notes: The simulator will stay in freeze until the candidate is ready to take the watch. This is very important as the RWST level will lower as soon as the simulator goes to run. Booth Operator: Keep the simulator in Freeze until the candidate has the watch. READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions: You are the HCO. 0 Reactor trip with SI occurred. 0 The has CRS initiated loss of coolant actions 0 RWST level is at 28% and trending down slowly. 0 The Control Room crew is currently at Step 22 of E-1. Initiating Cue: The CRS directs you to transfer to Cold Leg Recirculation per ES-1.3, Transfer to Cold Leg Recirculation. Page 2 01 14

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP For the 2008 ILT NRC Exam load I/C # 172 arid Freeze the simulator until the operator is ready to start then go to run. or Any at power IC. Max break LOCA. Insert MALF RCS03B. Ensure (4) SW pumps running. Complete E-l up to Step 19 with RWST Level > 28% (approx. 29%). Ensure both CS Pumps are running. Ensure A CCW Pump is running. Ensure B CCW Pump is secured. Insert trip CLG02B for B CCW Pump. Ensure MOV-738A and 7388 are closed. Freeze simulator until operator ready to start then go to run. Page 3 of 14

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION START TIME: .I= CRITICAL STEP ES-1.3, step 1 Performance Step: 1 Verify RWST level - GREATER THAN 15% Standard: Monitors RWST Level. IF sump recirculation NOT in progress, THEN pull-stop all pumps taking suction from RWST, EXCEPT one SI pump AND yo to ECA-1.l, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1. Comment: ES-1.3, step 2 Performance Step: 2 Verify CNMT Sump B Level - AT LEAST 113 INCHES Standard: Locates and identifiles CNMT Sump B Level is at least 113 INCHES. (2) 113 inches Red indicator lights lit on CNMT Sump Level Indicator. Comment: ES-1.3, step 3 Performance Step: 3 Reset SI Standard: Depresses SI reset P/B. Comment: ES-1.3, step 4.a Performance Step: 4 Check IF Unnecessary Pumps Can Be Stopped:

a. Three SI pumps - RUNNING Standard: Locates and identifies A, B and C SI pumps running.

Red lights on and Green lights off. Comment: Page 4 of 14

Appendix C Job Perforimance Measure I Form ES-C-1 PERFORMANCE INFORMATION ES-1.3, step 4.b 4 Performance Step: 5 Stop SI pump C arid place both switches in PULL STOP Standard: Locates and identifies Bus 14 SI pump C and places switch in PULL STOP. Locates and identifies Bus 16 SI pump C and places switch in PULL STOP. Red lights off and Green lights off. Comment: ES-1.3, step 4.c I/ Performance Step: 6 Stop both RHR pumps and place in PULL STOP Standard: Locates and identifies A RHR pump and places switch in PULL STOP. Locates and identifiles B RHR pump and places switch in PULL STOP. Red lights off and Green lights off. Comment: ES-1.3, step 4.d Performance Step: 7 Both CNMT spray plumps - RUNNING Standard: Locates and identifies A and B CNMT spray pumps running. Red lights on and Green lights off. Comment: Page 5 of 14

I Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION Standard: Locates and identiffies A CS pump switch and places in PULL STOP. or Locates and identifies B CS pump switch and places in PULL STOP. Red light off and Green light off for secured pump. Comment: ES-1.3, step 4.f Performance Step: g Check CNMT pressure - LESS THAN 28 PSlG Standard: Locates and identifies on Pl-944, 945,947 or 949 CNMT pressure is c28 psig. Comment: ES-1.3, step 4.g /, Performance step: 10 Place NaOH Tank outlet valve switches to OPEN AOV-836A AOV-836B Standard: Locates, identifies and places NaOH Tank outlet valve switches to OPEN. AOV-836A is open 0 AOV-836B is open Comment: ES-1.3, step 4. h 4 Performance Step: 11 Reset CNMT spray Standard: Depresses Containnient Spray reset P/B. Comment: Page 6 of 14

                                                                      ~~

Appendix C Job Performance Measure FormES-C-1 PERFORMANCE INFORMATION ES-1.3, step 4.i /, Performance step: 12 Close discharge valves for idle CNMT spray pump(s) PumpA IMOV-860A MOV-8608 PumpB MOV-860C MOV-860D Standard: Locates, identifies ;and closes discharge valves for idle CNMT spray pump stopped in Performance Step 8. Pump A MOV-860A MOV-860B - Closed or Pump B FJIOV-860C MOV-860D - Closed Red lights off and Green lights on for closed valves. Comment: ES-1.3,step 5.a Performance step: 1 3 Establish Adequate SW Flow:

a. Verify at lea.st two SW pumps - RUNNING Standard: Locates and identifies (4) Service Water Pumps running.

Red lights on and Green lights off. Comment: ES-1.3, step 5.b Performance step: 1 4 Verify AUX BLDG S'W isolation valves - OPEN MOV-4615 and MOV-4734 MOV-4616 and MOV-4735 Standard: Locates and identifies AUX BLDG SW isolation valves. MOV-4615 aind MOV-4734 - OPEN MOV-4616 aind MOV-4735 - OPEN Red lights on and Green lights off. Comment: ES-1.3, step 5.c Performance step: 1 5 Determine required SW flow to CCW HXs per table: Cue: You have 6000 gpm total Service Water flow. 3000 gpm to each heat exchanger. Standard: Total of 5000 gpm - 6000 gpm equally divided to both HXs. Normal SW Discharge alignment. Comment: Page 7 of 14

Appendix C Job Perforrnance Measure Form ES-C-1 PERFORMANCE INFORMATION ES-1.3, step 5.d Performance Step: 16 Direct A 0 to adjust SW flow to required value. IF on normal SW discharge: V-4619, CCW HX A V-4620, CCW HX B Cue: You have 6000 gpm total Service Water flow. 3000 gpm to each heat exchanger. Standard: Determines no adjustments are needed. Comment: ES-1.3, step 6.a Standard: Locates A CCW Pump - Red light on and Green light off. Locates 6 CCW Pump - Red light off and Green light on. Identifies B CCW pump not running and goes to 6.a RNO Comment: ES-1.3, step 6.a.l RNO (START Alternate Path) Performance step: 18 Start CCW pumps as power Supply permits (122 kw each). Standard: Locates and starts E3 CCW Pump. Red light off. Green light on. White light on. Identifies 6 CCW pump will not start. Comment: ES-1.3, step 6.a.2 RNO /, Performance Step: 19 IF both CCW pumps are running, THEN go to step 6.b. Standard: Determines both CC:W pumps are not running and does not go to step 6.b. Goes to RNO step 6.a.3. Comment: Page 8 01 14

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION ES-1.3, step 6.a.3 RNO (End Alternate Path) 4 Performance Step: 20 IF only one CCW pump is running, THEN perform the following: a) Place NRHx temperature control valve TCV-130 to MANUAL and close valve. b) Manually open CCW MOV to only one operable RHR loop. Open hAOV-738A or Open htlOV-7386 c) Go to step 7. Standard: Places NRHx temperature control valve TCV-130 to MANUAL and closes valve. Locates, identifies and opens only (1) CCW valve to one RHR Hx: MOV-738A .- open or MOV-738B .. open Red light on and Green light off for open valve. e) Goes to step 7. Does not perform step 6.b. Comment: ES-1.3, step 7.a Performance Step: 21 Verify RHR System Alignment:

a. Verify the following valves - CLOSED o RHR suction valves from loop A hot leg MOV-700 MOV-701 o RHR discharge valves to loop 6 cold leg MOV-720 MOV-721 Standard: Locates, identifies and verifies closed:

MOV-700 MOV-701 MOV-720 MOV-721 Red lights off and Green lights on. Comment: Page 9 of 14

I t Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION ES-1.3, step 7.b Performance Step: 22 Verify RHR pump suction crosstie valves - OPEN MOV-704A MOV-7046 Standard: Locates, identifies ;and verifies open: MOV-704A MOV-7040 Red lights on and Green lights off. Comment: ES-1.3, step 7.c Performance Step: 23 Verify the following valves - OPEN o RHR pump discharge to Rx vessel deluge valves MOV-852A MOV-8526 o RHR suction from sump 6 (inside CNMT) MOV-851A MOV-8516 Standard: Locates, identifies and verifies open: MOV-852A MOV-852B MOV-851A MOV-851B Red lights on and Green lights off. Comment: ES-1.3, step 7.d Performance Step: 24 Verify RCDT pump suction valves from sump B - CLOSED MOV-1813A MOV-18138 Standard: Locates, identifies and verifies closed: MOV-1813A MOV-1813 6 Red lights off and Green lights on. Comment: Page 10 of 14

Appendix C Job Perforrnance Measure Form ES-C-1 PERFORMANCE INFORMATION ES-1.3,step 8.a 4 Performance Step: 25 Close RWST outlet valve to RHR pump suction, MOV-856 (turn on DC power key switch) Standard: Locates, identifies and closes (turns on DC power key switch): 0 MOV-856 - IClosed Red light off and Green light on. Comment: ES-1.3, step 8.b 4 Performance step: 26 Open both RHR suction valves from sump 6 (outside CNMT) MOV-850A -.OPEN MOV-8506 *. OPEN Standard: Locates, identifies and opens: 0 MOV-850A -open 0 MOV-850B -open Red lights on and Green lights off. Comment: ES-1.3, step 8.c (START Alternate Path) 4 Performance step: 27 Check MOV-738A AND MOV-738B - BOTH OPEN Standard: Locates, identifies and verifies: (one valve will be shut due to only having (1) CCW pump available - Performance Step 17) MOV-738A -Open 0 MOV-738B -Open Red light on and Green light off for open valve Red light off and Green light on for closed valve. Goes to step 8.c RNO since both valves are not open. Comment: Page 11 of 14

I I Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION ES-1.3, step 8.c RNO (End Alternate Path) 4 Performance Step: 28 Perform the following:

1) IF MOV-738A open, THEN start RHR Pump A and go to step Ibd.

2) IF MOV-738B open, THEN start RHR Pump B and go to step 8d.

Standard: Locates, identifies and starts: RHR Pump A if MOV-738A is open. RHR Pump B if MOV-738B is open. Red light on and Green light off for started pump. Goes to step 8.d. Comment: ES-1.3, step 8.d Performance Step: 29 Start one RHR pump - ONE RHR PUMP RUNNING Standard: Locates, identifies and verifies RHR pump started in previous step is still running. Red light on and Green light off for running pump. Comment: ES-1.3, step 9 Performance Step: 30 Check RWST Levell - LESS THAN 15% Standard: Locates and determines what RWST Level is. CUE: No further action is required. Comment: Terminating Cue: Evaluation on this JPM is complete. STOP TIME: TIME CRITICAL STOP TIME: Page 12 of 14

Appendix C Job Performance Measure Form ES-C-1 VERlFlCATlOrJ OF COMPLETION Job Performance Measure No.: 2008 NRC JPhA B Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiner's Signature: Date: Page 13 of 14

Appendix C Job Performance Measure Form ES-C-1 JPM CUE SHEET Initial Conditions: You are the HCO. Reactor trip with SI occurred. The has CRS initiated loss of coolant actions RWST level is at 28% and trending down slowly. The Control Room crew is currently at Step 22 of E-1. Initiating Cue: The CRS directs you to transfer to Cold Leg Recirculation per ES-1.3, Transfer to Cold Leg Recirculation. Page 14 of 14

Appendix C Job Perforrnance Measure Form ES-C-1 Worksheet Facility: Ginna Task No.: 005-001-01-01 TasWJPM

Title:

Placing LTOP on Service JPM No.: 2008 NRC JPM C WA

Reference:

010 A4.03 4.0/3.8 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testinq: Simulated Performance: Actual Performance: X Classroom Simulator ~- X Plant Applicability: RO/SRO SUBMllTED BY: Ted Coe DATE: 6/30/08 Developer REVIEWED BY: Art Vest DATE: 6/30/08 Training Technical Reviewer REVIEWED BY: Don Dettman DATE: 6/30/08 Operations Technical Reviewer APPROVED BY: John Brown DATE: 6/30/08 Training Management Page 1 of 9

I Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: Place PC-430 on service and all critical tasks evaluated as satisfactory. Required Materials: (1) Panel key for LTOP operations. General

References:

0-7, Alignment and 0perai:ion of the Reactor Vessel Overpressure Protection System, Rev. 04701 0-2.2, Plant Shutdown from Hot Shutdown to Cold Conditions, Rev. 15000 Handouts: 0-7, Alignment and Operation of the Reactor Vessel Overpressure Protection System, Rev. 04.701 Time Critical Task: NO Validation Time: 10 minutes Alternate Path: NO Instructor Notes: Ensure a marked up copy 0-7, Alignment and Operation of the Reactor Vessel Overpressure Protection System, Rev. 04701 is ready to give to the operator during the Initiating Cue. READ TO THE EXAMINEE I will explain the initial conditions, which steps to sirnulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions: You are an extra ROI. A unit shutdown is in progress. 0 The control room team is performing procedure 0-2.2, Plant Shutdown from Hot Shutdown to Cold Conditions and are at step 6.4.20 waiting for LTiOP to be placed on service. 0 Section 1 through section 6.1 of 0-7, Alignment and Operation of the Reactor Vessel Clverpressure Protection System has been completed. Initiating Cue: The Shift Manager directs you to place PCV-430 on service per 0-7, Alignment and Operation of ,the Reactor Vessel Overpressure Protection System section 6.2. CUE: Hand the Operator a marked up copy of copy 0-7, Alignment and Operation of the Reactor Vessel Overpressure Protection System, Rev. 04701. Page 2 01 9

Appendix C Job Perforrnance Measure Form ES-C-1 Worksheet SIMULATOR SETUP For the 2008 ILT NRC Exam load I/C # 173 or Any shutting down IC where LTOP is ready to be placed on service. 0 Tave is between 350°F and 330°F. At least (1) RCP is running. RCS pressure is -325 psig. Properly markup a copy of 0-7, Alignment and Operation of the Reactor Vessel Overpressure Protection System, Rev. 04701 to section 6.2. 0 Use Override IND-RCS43 to set A Accumulator pressure to 710 psig. Page 3 of 9

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION START TIME: .I= CRITICAL STEP 0-7, step 6.2.1 Performance Step: 1 VERIFY the following MCB Alarms extinguished: AA-22, RCS OVER-PRESS PROTECTION TRAIN A HI PRESS AA-23, RCS OVER-PRESS PROTECTION TRAIN B HI PRESS AA-31, RCS OVER-PRESS PROTECTION TRAIN C HI PRESS Standard: MCB Alarms out: AA-22 AA-23 AA-31 Comment: 0-7, step 6.2.2 4 Performance Step: 2 ENSURE the PRZR PORV, PCV-430 Control Switch is in the CLOSE position. Standard: PCV-430 coritrol switch is in the closed position. 0 Red light off i3nd Green light on. Comment: 0-7, step 6.2.3 Performance step: 3 OPEN ACCUM TO SURGE TANK VLV SOV-8616A. (MCB Rear) Standard: Gets proper k.ey from CRS desk. 0 SOV-8616A open. Comment: Page 4 of 9

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION 0-7, step 6.2.4 4 Performance Step: 4 ENSURE N2 ARMING VLV SOV-8619A is in the ARM position. (MCB Rear) Standard: Uses proper key. SOV-8619A is in ARM. Comment: 0-7, step 6.2.5 Performance Step: 5 VERIFY CLOSED PRZR PORV, PCV-430. Standard: PCV-430 control switch is in the closed position. Red light off and Green light on. Comment: 0-7, step 6.2.6 Performance Step: 6 RECORD pressure indicated on OP ACCUM A N2 PRESSURE, Pl-455. (MCB Rear) Standard: Pressure recorded as shown on Pl-455. Comment: 0-7, step 6.2.7 4 Performance Step: 7 IF Accumulator A pressure is NOT between 735 and 760 psig, THEN CHARGE thle accumulator as PER S-29.2, Charging the Reactor Vessel Overpressure Protection System Accumulators with N2. IF Accumulator A pressure is correct, THEN MARK this Step NIA. Examiners Note: Annunciator AA-14, N2 Accum A Lo Press 725 psi alarms at 725 psi. Standard: Checks Accumulator A pressure is between 735 and 760 psig. 0 Identifies the need to charge the AAccumulator. CUE after it is identified the AAccumulator must be recharged: For the purposes of this JPM, ten minutes have passed and the AAccumulator has been charged with nitrogen per S-29.2. BOOTH OPERATOR: Delete override IND-RCS43 when directed to by the evaluator. Comment: Page 5 of 9

Appendix C Job Perforrnance Measure Form ES-C-1 PERFORMANCE INFORMATION 0-7, step 6.2.7 Performance Step: 8 Checks Accumulator A pressure is between 735 and 760 psig. Standard: 0 Checks Accumulator A pressure is between 735 and 760 psig. Charging is not required. Comment: 0-7, step 6.2.8 Performance Step: g ENSURE CLOSED)MOV 516 breaker, MCC C position 6C, VLV-516 RCS. Standard: Calls A 0 to verify h4OV 516 breaker is closed CUE: Acknowledge request. REPORT: MOV 516 breaker, MCC C positiion 6C is closed. Comment: 0-7, step 6.2.9 Performance Step: 10 ENSURE OPEN PRZR PORV BLOCK VLV, MOV 516. Standard: 0 MOV 516, FRZR PORV BLOCK VLV is open. 0 Red light on and Green light off. Comment: 0-7, step 6.2.10 Performance Step: 11 RECORD the time Train A Overpressure Protection System is operable. Standard: Records current time. Comment: Page 6 of 9

Appendix C Job Perforrnance Measure Form ES-C-1 PERFORMANCE INFORMATION Standard: Reports PCV-430 is on service. CUE: Acknowledge report. Comment: Terminating Cue: Evaluation on this JPM is complete. STOP TIME: TIME CRITICAL STOP TIME: Page 7 of 9

Appendix C Job Perforniance Measure Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC JPM C Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiners Signature: Date: Page 8 of 9

Appendix C Job Perforrnance Measure Form ES-C-1 JPM CUE SHEET Initial Conditions: You are an extra RO. A unit shutdown is in progress. The control room team is performing procedure 0-2.2, Plant Shutdown from Hol Shutdown to Cold Conditions and are at step 6.4.20 waiting for LTOP to be placed on service. Section 1 through s'ection 6.1 of 0-7, Alignment and Operation of the Reactor Vessel Overpressure Protection System has been completed. Initiating Cue: The Shift Manager directs you to place PCV-430 on service per 0-7, Alignment and Operation of the Reactor Vessel Overpressure Protection System section 6.2. Page 9 of 9

Appendix C Job Perforrnance Measure Form ES-C-1 Wolrksheet Facility: Ginna Task No.: 344-068-05-02 Task/JPM

Title:

Respond To a Control Room JPM No.: 2008 NRC JPM D Evacuation WA

Reference:

APE 068 AA1.23 4.3 / 4.4. Examinee: NRC Examiner: Facility Evaluator: Date: Method of testina: Simulated Performance: Actual Performance: X Classroom Simulator -- X Plant Applicability: RO/SRO SUBMITTED BY: Ted Coe DATE: 6/30/08 Developer REVIEWED BY: Art Vest DATE: 6/30/08 Training Technical Reviewer REVIEWED BY: Don Dettman DATE: 6/30/08 Operations Technical Reviewer APPROVED BY: John Brown DATE: 6/30/08 Training Management Page 1 of 8

Appendix C Job Perforimance Measure Form ES-C-1 Worksheet Task Standard: Immediate actions of AP-CR. 1 completed from memory and all critical tasks evaluated as satisfa'ctory. Required Materials: None General

References:

AP-CR. 1, CONTROL ROOM INACCESSIBILITY, Rev.24 Handouts: AP-CR.1, CONTROL ROOM INACCESSIBILITY, Rev.24 Time Critical Task: NO Validation Time: 5 minutes Alternate Path: Yes Instructor Notes: Evaluator will act as the CRS for the initiating cue. 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: 0 You are the HCO. 0 The CO and the Skl are in the Relay Room investigating an issue. 0 I will be the CRS if you need one. 0 The plant is at 100% power in a normal 50/50at power lineup. Initiating Cue: You have the watch. Page 2 of 8

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP For the 2008 ILT NRC Exam load I/C # 174 or Any 1OOoh IC (IC-19). The plant in a normal 100% power lineup. 0 In a normal 50150 electric lineup. 0 Insert TUR02, Turbine failure to Auto trip. 0 Insert TUR17A, Turbine Stop Valve: VLV 0545. 0 Insert TURl7B, Turbine Stop Valve: VLV 0544. 0 Insert RPS05A, Reactor trip A breaker failure. 0 Insert RPS05B, Reactor trip B breaker failure. A-RPSl2 0 TURB12A,B,C,D A-ROD05 Page 3 of 8

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION START TIME: .I= CRITICAL STEP To Evaluator: All Operator actions shall be frorn memory, without the aid of the procedure. CRS Initiating Cue: Status update, Ready. (wait for response) I have just been informed there are poisonous fumes coming up from the Relay Room. Entering AP-CR.1, CONTROL ROOM INACCESSIBILITY. HCO, perform immediate operator actions for AP-CR.1. End of Update. AP-CR.1, step 1 (Start Alternate Path) Performance Step: 1 Verify Reactor Trip: 0 At least one train of reactor trip breakers - OPEN. Neutron flux - LOWERING. MRPl indicates - ALL CONTROL AND SHUTDOWN RODS ON BOTTOM. Standard: Reactor is not tripped. No reactor trip breakers are OPEN. Neutron flux at 100%. MRPl indicates ALL CONTROL AND SHUTDOWN RODS are still at normal positions. Goes to step 1 RNO. Comment: AP-CR.l, step 1 RNO Performance step: 2 Manually trip reactor. Standard: Depresses Reactor Trip Pushbutton Reactor is not tripped. No reactor trip breakers are OPEN. Neutron flux at 1OOoh. 0 MRPl indicates ALL CONTROL AND SHUTDOWN RODS are still at normal positions. Goes to RNO step I .a. Comment: Page 4 of 8

Appendix C Job Perforrnance Measure Form ES-C-1 PERFORMANCE INFORMATION AP-CR.1 steps 1.ia thru 1.d RNO /, Performance Step: 3 IF reactor trip breakers NOT open, THEN perform the following:

a. Open Bus 13 and Bus 15 normal feed breakers.

b. Verify rod drive MG sets tripped.

c. Close Bus 13 and Bus 15 normal feed breakers.

d. Reset lighting breakers.

IF the Rx can NOT be tripped from the Control Room, THEN dispatch personnel to locally open the reactor trip breakers. Standard: a. Opens Bus 13 arid Bus 15 normal feed breakers. Red lights Oiff and Green lights on.

b. Rod drive MG sets tripped.

0 Rod Drive MG set A and B Red lights off and Green lights on.

c. Closes Bus 13 and Bus 15 normal feed breakers.

Red lights on and Green lights off.

d. Resets lighting breakers by depressing Bus 13 and 15 Lighting Breaker green Pmhbuttons.

(ONLY a, b and c are critical steps. Step d is NOT a critical step.) Comment: AP-CR.1 step 2 Performance step: 4 Verify Turbine Stop Valves - CLOSED Standard: On EHC valve statu:; panel. SVL Open red light on and SVR Open red light on. Identifies Turbine stop valves are still open and goes to step 2 RNO. Comment: Page 5 of 8

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION AP-CR.1, step 2 FINO (End Alternate Path) 4 Performance Step: 5 Manually trip turbine. IF turbine can NOT be tripped, THEN close both MSIVs. Standard: Depresses Turbine Emergency Trip P/B - Turbine Does not Trip. Closes A MSIV and B MSlV Handswitch MSlV A, AOV-3517 to close. Handswitch MSlV B, AOV-3516 to close. Red lights off and Green lights on. (Critical Steps are closing A and B MSIVs.) Comment: Completion of lmimediate Operator Actions Performance Step: 6 CRS, Immediate Olperator Actions for AP-CR. 1 are complete. Standard: informs CRS that, Ummediate Operator Actions for AP-CR.1 are complete. CUE: Acknowledge report. CUE: No further actions are required. Comment: Terminating Cue: Evaluation on this; JPM is complete. STOP TIME: TIME CRITICAL STOP TIME: Page 6 of 8

Appendix C Job Performance Measure Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC JPM D Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT INS ,T Examiners Signature: Date: Page 7 of 8

Appendix C Job Performance Measure Form ES-C-1 JPM ClJE SHEET Initial Conditions: You are the HCO. 0 The CO and the Skl are in the Relay Room investigating an issue. I will be the CRS if you need one. The plant is at 100% power in a normal 50150 at power lineup. Initiating Cue: You have the watch. Page 8 of 18

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Job Performance Measure Form ES-C Worksheet FaciIity : Ginna Task No.: 076-004-05-01 TasWJPM

Title:

Respond to a Total Loss of SW JPM No.: 2008 NRC JPM E WA

Reference:

076 A2.01 3.5* / 3.7* Examinee: NRC Examiner: Facility Evaluator: Date: Method of testina: Simulated Performance: Actual Performance: X Classroom Simulator -- X Plant Applicability: RO/SRO SUBMITTED BY: Ted Coe DATE: 6/30/08 Developer REVIEWED BY: Art Vest DATE: 6/30/08 Training Technical Reviewer REVIEWED BY: Don Dettman DATE: 6/30/08 Operations Technical Reviewer APPROVED BY: John Brown DATE: 6/30/08 Training Management Page 1 of 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: E-0 immediate actions performed, RCPs tripped, Letdown isolated and all critical tasks evaluated iis satisfactory. Required Mater lalj; .. None General

References:

AP-SW.2, LOSS OF SERVICE WATER, Rev. 00801 E-0, REACTOR TRIP OR SAFETY INJECTION, Rev. 04100 Handouts: AP-SW.2, LOSS OF SERWICE WATER, Rev. 00801 Time Critical Task: NO Validation Time: 10 minutes Alternate Path: YES Instructor Notes: Ensure a copy of AP-SW.2, LOSS OF SERVICE WATER, Rev. 00801 is ready to give to the operator. Candidate may perform actions from memory, but must verify actions with the procedure. READ TO THE EXAMINEE I will explain the initial conditions, which steps to siinulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions: You are the CO. I will be the CRS if you need one. The plant is at 100% power in a normal 50/50electrical lineup. Initiating Cue: You have the watch. Page 2 of 9

Appendix C Job Perforimance Measure Form ES-C-1 Worksheet SIMULATOR SETUP For the 2008 ILT NRC Exam load I/C # 175 and insert CLGOlA and CLGOlC (or remote 1) one minute after the candidate takes the watch. or Any 100% IC (IC-19). 0 The plant in a normal 100% power lineup. 0 In a normal 50/50electric lineup. 0 Ensure A and C Service Water pumps are running. Insert CLGO1B and CLGO1D. 0 Insert CLGOlA and CLGOlC (or remote 1) one minute after the candidate takes the watch. Page 3 of 9

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION

.I= CRITICAL STEP Booth Operator: One minute after the candidate takes the watch insert CLGOI A and CLGOIC (or Remote 1).

/, Performance Step: 1 Identifies that A and C Service Water pumps are tripped. Standard: identifies that A and C Service Water pumps are tripped. informs the CRS that A and C Service Water pumps are tripped. CUE: Acknowledge reports and ask for recommendation. CUE: CO start B and D Service Water pumps. Comment: Performance Step: 2 Starts B and ID Service Water pumps. Standard: 0 Places switlches for B and D Service Water pumps to start. 0 Identifies that B and D Service Water pumps are tripped. Informs the CRS that B and D Service Water pumps are tripped CUE: Acknowledge reports and ask for recommendation. CUE: CO Perform AP-SW.2, LOSS OF SERVICE WATER Evaluator: Hand the Operator a copy AP-SW.2, LOSS OF SERVICE WATER, Rev. 00801. Comment: Page 4 of 9

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION AP-SW.2, step 1 PerformanceStep: 3 Verify 480V AC Ernergency Busses 17 and 18 - ENERGIZED. Standard: Busses 17 and 18 voltage meters read -480 volts. Normal feeds to Bus 17 and 18 are closed. Red lights on and Green lights off. Comment: AP-SW.2, step 2a PerformanceStep: 4 Verify SW Pump Alignment: Check at least one SW pump running in each loop: 0 A or B pump in loop A. C or D plump in loop B. Standard: 0 A and C SW Pumps Tripped (given in initial cue). 0 6 and D SW Pumps not running. Red lights off and Green lights on. 0 Recognizes no Service Water pumps running. Goes to step 2a RNO. CUE: Acknowledge any report. Comment: AP-SW.2, step 2.a.l RNO (Start Alternate Path) PerformanceStep: 5 a. Perform the following:

1) Manually start SW pumps as necessary (257 kw each).

Standard: Attempt to start E3 and D SW Pumps by taking associated control switches to Start. Recognizes 13 and D SW Pumps trip. Red lights off, White lights on and Green lights on. May report SW pump trips to the CRS. CUE: Acknowledge any report. Comment: Page 5 of 9

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION AP-SW.2, step 2.a.2 RNO Performance Step: 6 IF adequate cooling can NOT be supplied to a running DIG, THEN perform the following: a) Pull stop affected D/G. b) Immediately depress voltage shutdown pushbutton. Standard: 0 D/G A and E3 voltmeters read 0 volts. 0 Recognizes no Diesel Generators are running and performs no actions. CUE: Acknowledge any report. Comment: AP-SW.2, step 2.a.3.a RNO /, Performance Step: 7 IF no SW pumps cain be operated, THEN perform the following: a) Trip the reactor. Standard: Depresses Reactor Emergency Trip Pushbutton. CUE: Acknowledge any report. Comment: AP-SW.2, step 2.a.3.b RNO /, Performance Step; 8 WHEN all E-0Immediate Actions done, THEN trip BOTH RCPs. Standard: E-0 Immediate Actions: (these actions performedfrom memory)

1. Verify Reactor Trip - Neutron flux lowering, at least one train of Reactor trip breakers open and MRPl indicates all rods are on the bottom.

2. Verifies Turbine is tripped - Turbine Stop valves are closed as indicated on EHC valve status panel. SVL Closed Green light on and SVIR Closed Green light on.

3. Verify Both Trains of AC Emergency Busses energized to at least 420 volts: Busses 14,16,17 and 18 Volt meters for Busses 14, 16, 17 and 18 all read -480 VAC.

4. Check if SI is Actuated: Any SI Annunciator - LIT -

Annunciators D-19,21, 22 and 28 extinguished and no indications that an SI is required. TriD both RCPs:

1. A RCP IUS to Stop Red light off and Green light on.

2. B RCP H/Sto Stop Red light off and Green light on.

(Critical steps are to trip both RCPs.) CUE: Acknowledge any report. Comment: Page 6 of 9

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION AP-SW.2, step 2.a.3.c RNO /, Performance Step: g Close letdown isol, AOV-427. Standard: AOV-427 switch in Closed. Red light off and Green light on. CUE: Acknowledge any report. Comment: AP-SW.2, step 2.a.3.d RNO (End Alternate Path) Performance Step: 10 Close excess letdown, HCV-123. Standard: HCV-123 is at 0% demand. CUE: Acknowledge any report. CUE: No further action is required. Comment: Terminating Cue: Evaluation on this JPM is complete. STOP TIME: TIME CRITICAL STOP TIME: Page 7 of 9

Appendix C Job Perforniance Measure Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC JPM E Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiners Signature: Date: Page 8 OF 9

Appendix C Job Performance Measure Form ES-C-1 JPM CUE SHEET Initial Conditions: 0 You are the CO. 0 I will be the CRS if you need one. 0 The plant is at 100% power in a normal 50/50electrical lineup. Initiating Cue: You have the watch. Page 9 of 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Ginna Task No.: 064-007-01-01A TasWJPM

Title:

Shutdown the "A" Emergency Diesel JPM No.: 2008 NRC JPM F Generator WA

Reference:

064 A4.06 3.9 / 3.9 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testina: Simulated Performance: Actual Performance: x Classroom Simulator -- X Plant Applicability: RO/SRO SUBMITTED BY: Ted Coe DATE: 6/30/08 Developer REVIEWED BY: Art Vest DATE: 6/30/08 Training Technical Reviewer REVIEWED BY: Don Dettman DATE: 6/30/08 Operations Technical Reviewer APPROVED BY: John Brown DATE: 6/30/08 Training Management Page 1 o'f 13

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: The A D/G shutdown arid all critical tasks evaluated as satisfactory. Required Materials: None General

References:

STP-0-12.1: EMERGENCY DIESEL GENERATOR A, Rev. 00201 Handouts: STP-0-12.1: EMERGENCY DIESEL GENERATOR A, Rev. 00201 Time Critical Task: NO Validation Time: 20 minutes Alternate Path: NO Instructor Notes: Ensure a marked up copy of STP-0-12.1: EMERGENCY DIESEL GENERATOR A, Rev. 00201 is ready to give to the operator during the Initiating Cue. 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: 0 You are an extra RO. 0 The plant is at 100% power with a normal electrical lineup. 0 The A EDG is running for the monthly surveillance per STP-O-12.1 through Step 6.2.42. All readings have been taken and evaluated as satisfactory. There is an A 0 available at the A D/G. The Diesel has run for 65 minutes, all readings have been taken. The A 0 has the data sheets. Bi-Annual selected Service Water Pump starts are not required. Initiating Cue: The CRS has directed you to shutdown the A D/G per STP-0-12.1 steps 6.3 through 6.3.19. CUE: Hand the Operator a marked up copy of STP-0-12.1, EMERGENCY DIESEL GENERATOR A, Rev. 00201. Page 2 of 13

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Appendix C Job Performance Measure Form ES-C-1 Worksheet SlMULATOFl SETUP For the 2008 ILT NRC Exam load I/C # 176 and Insert Manual Triggers 1 and 2 to reset DG1A ELCP Annunciator Panel, when requested in performance step 24. or 100% power IC with normal electrical lineup (IC-19). 0 " A O/Grunning at between 2025 and 2050 KW per STP-0-12.1, step 6.2.36 rev. 00201. Ensure "A" SW running and "C"SW stopped. Ensure SW selected to "A" SW Pump. Complete and mark up STP-0-12.1 through Step 6.2.42. Insert Manual Triggers 1 and 2 to reset DGIA ELCP Annunciator Panel, when requested in performance step 24. Page 3 of '13

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION START TIME: .I= CRITICAL STEP STP-0-12.1 ,step 6.3.1.1 Performance Step: 1 WHEN Emergency Diesel Generator A has operated between 2025 and 2050 K\rY for a period of greater than 60 minutes but less than or equal to 115 minutes, THEN UNLOAD Emergency Diesel Generator 14 as follows:

1. RECORD time unloading begins.

Standard: Records time unloading begins. Comment: STP-0-12.1 ,step 6.3.1.2 Performance step; 2 IF the D/G A LOAD LIMIT on mechanical governor is NOT in the MAX FUEL position, THEN PERFORM the following: OTHERWISE, MARK this Step N/A Cue when asked (aboutLoad Limit: LOAD LIMIT is NOT at Max Fuel.

a. ADJUST Emergency Diesel Generator A load to between 1925 and 1950 Kw using the D/G A GOVERNOR switch AND MAINTAIN Power Factor 0.9 (lag) using the D/G A AUTO VOL.TAGE CONTROL RHEOSTAT as necessary.

b. RESTORE LOAD LIMIT setting to normal (MAX FUEL).

Cue when told to adjust Load Limit: LOAD LIMIT is now at Max Fuel. Standard: 0 Calls the AO to request if LOAD LIMIT setting is at MAX FUEL. 0 Adjusts D/G A load to between 1925 and 1950 Kw using the D/G A GOVERNOR switch. 0 Maintains Power Factor 0.9 (lag) using the D/G A AUTO VOLTAGE CONTROL RHEOSTAT. 0 Calls the A 0 to restore LOAD LIMIT setting to MAX FUEL. Comment: Page 4 of 13

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION - STP-0-12.1, step1 6.3.1.3 Performance Step: 3 IF the Mechanical Governor was adjusted to lock the load, THEN ADJUST Emergency Diesel Generator A load to between 2150 and 2175 KCV using D/G A GOVERNOR switch AND MAINTAIN Power Factor at approximately 0.9 (lag) using D/G A AUTO VOLTAGE CONTROL RHEOSTAT as necessary. Standard: Adjusts D/G A load to between 2150 and 2175 Kw using D/G A GOVERNOR switch. Maintains Power Factor at approximately 0.9 (lag) using D/G A AUT'O VOLTAGE CONTROL RHEOSTAT. Comment: STP-0-12.1, step 6.3.1.4 1/ Performance Step: 4 UNLOAD Emergency Diesel Generator A; to 400 KW by intermittently turning D/G A GOVERNOR switch in the lower direction, AND MAINTAIN Power Factor at approximately 0.9 (lag) using D/G A AUTO VOLTAGE CONTROL RHEOSTAT as necessary. Standard: Does not violate the D/G A unloading rate of approximately 500 KW every 30 seconds. Unloads D/G A, to 400 KW by intermittently turning D/G A GOVERNOR switch in the lower direction. Maintains Power Factor at approximately 0.9 (lag) using D/G A AUTO VOLTAGE CONTROL RHEOSTAT. Comment: STP-0-12.1, step 6.3.2 Performance Step: 5 IF Bi-Annual selected Service Water Pump starts are required, THEN PERFORM Attachment 13, Bi-Annual Service Water Pump Starts. OTHERWISE, MARK this Step AND Attachment 13 N/A. Standard: Determines from Initiating Cue, not required, marks step N/A. Comment: STP-0-12.1, step 6.3.3 Page 5 01 I 3

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION .\I Performance Step: 6 WHEN Emergency Diesel Generator A load has been reduced to 400 KW, THEN TRIP one Emergency Diesel Generator A supply breaker. Standard: WHEN D/G A is at -400 KW, TRIPS one D/G A supply breaker for' Bus 14 or Bus 18. Green light on,red light off. If Diesel Glenerator Trips on Reverse Power due to operator error, the step will be evaluated as Unsat. Comment: STP-0-12.1, step 6.3.4 .\I Performance Step: 7 WHEN Emergency Diesel Generator A load has been reduced to approximately 200 KW AND Power Factor is 0.9 (lag), THEN TRIP the remaining closed Emergency Diesel Generator A supply breaker. Standard: WHEN D/G A load is at -200 KW and Power Factor is 0.9 (lag), TRIPS the remaining closed D/G A supply breaker for Bus 14 or Bus 18. Green light on, red light off. 0 If Diesel Generator Trips on Reverse Power due to operator error, the step will be evaluated as Unsat. Comment: STP-0-12.1, step 6.3.5 Performance Step: 8 RECORD time breaker was opened. Standard: Records time breaker was opened. Comment: Page 6 o f 13

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION STP-0-12.1, step 6.3.6 Performance Step: 9 IF Attachment 13, Eli-Annual Service Water Pump Starts, was performed, THEN ENSURE Service Water Pumps AND Selector Switches are aligned to the desired configuration. OTHERWISE, MARK this Step N/A. Standard: Determines from Initiating Cue, not required, marks step N/A. Comment: STP-0-12.1, step 6,.3.7 4 Performance Step: IO PLACE DIG A UNIT'/PARALLEL OPERATION SELECTOR switch to UNIT position. Standard: D/G A UNIT/PARALLEL OPERATION SELECTOR switch in UNIT position. Comment: STP-0-12.1, step 6.3.8 Performance Step: 11 PLACE D/G A SYNCHROSCOPE switch in the BUS 14 or BUS 18 position. Standard: D/G A SYNCHROSCOPE switch in the BUS 14 or BUS 18 position. Comment: STP-0-12.1, step 6.3.9 Performance Step: 12 IF Emergency Diesel Generator A frequency is high, THEN OPERATE D/G A GOVERNOR switch to return to a setting of between 60 and 60.1 Hertz (revolving slowly in the clockwise direction) AND TRANSFER frequency setting data to Attachment 3, As Found/As Left Voltage and Frequency. OTHERWISE, MARK this Step N/A. Standard: Determines frequency is satisfactory, marks step N/A. Comment: STP-0-12.1, step 6.3.1 0 Page 7 of 13

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 13 PLACE D/G A SYNCHROSCOPE switch to the OFF position. Standard: D/G A SYNCHROSCOPE switch in off. Comment: STP-0-12.1, step 6.3.1 1 Performance step: 14 MEASURE the Emergency Diesel Generator A speed using a photo-tachometer, AND RECORD speed data on Attachment 3, As Found/As Left Voltage and Frequency. Standard: 0 Directs the A 0 to measure the D/G A speed using a Photo-tachometer. 0 Records the speed data on Attachment 3. CUE: A D/G speed is 900 rpm. Comment: STP-0-12.1, step 6.3.1 2 Performance Step: 15 ADJUST D/G A AUTO VOLTAGE CONTROL RHEOSTAT to establish Emergenlcy Diesel Generator A output voltage between 480 and 490 Volts (adjust as close to 480 volts as possible) AND RECORD voltage (dataon Attachment 3, As Found/As Left Voltage and Frequency. Standard: D/G A output voltage between 480 and 490 Volts. Records voltage data on Attachment 3. Comment: STP-0-12.1, step 6.3.1 3 Performance Step: 16 RECORD the as left DIG A AUTO VOLTAGE CONTROL RHEOSTAT position on Attachment 14, Auto Voltage Control Rheostat After Stait As Left, by sketching in the dial setting, Standard: Sketching in the dial setting on Attachment 14. Comment: STP-0-12.1, step 6.3.1 4 Page 8 of 13

Appendix C Job Perforniance Measure Form ES-C-1 PERFORMANCE INFORMATION 4 Performance Step: 17 TURN the D/G A CONTROL switch to the STOP position. Standard: D/G A CONTROL switch to STOP then spring returns to mid position (red flagged). Comment: STP-0-12.1, step 6.3.15 4 Performance Step: 18 PUSH AND HOLD the D/G A VOLTAGE SHUTDOWN button (Black button) for a few seconds immediately after stopping Emergency Diesel Generator A. Standard: Pushes and holds the DIG A VOLTAGE SHUTDOWN button for a few seconds immediately after stopping D/G A. CUE: If requested, report as the AO, A iD/G has stopped. Comment: STP-0-12.1, step 6.3.1 6 4 Performance Step: 19 WHEN the Emergency Diesel Generator A has stopped rolling, THEN PUSH the following buttons: D/GARESET 0 D/G A FIELD RESET Standard: D/G A RESET button depressed. 0 D/G A FIELD RESET button depressed. Comment: Page 9 of It 3

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION STP-0-12.1, step 6.3.17 Performance Step: 20 WHEN the Emergency Diesel Generator A is reset, THEN VERIFY the following indicating lamps are illuminated (MCB Rear): AIR START SOLENOID VALVE 1 POWER AVAILABLE AIR START SOLENOID VALVE 2 POWER AVAILABLE START RELAY 1 POWER AVAILABLE START REELAY 2 POWER AVAILABLE Standard: Verifies the following indicating lamps are illuminated: AIR START SOLENOID VALVE 1 POWER AVAILABLE 0 AIR START SOLENOID VALVE 2 POWER AVAILABLE 0 START RELAY 1 POWER AVAILABLE 0 START RELAY 2 POWER AVAILABLE Comment: STP-0-12.1, step 6.3.18 Performance step: 21 DECLARE Emergency Diesel Generator A unavailable. Standard: Informs the CRWHCO A DIG is unavailable. CUE: Acknowledge report. Comment: STP-0-12.1, step 6.3.19.1 Performance step: 22 VERIFY D/G A CONTROL switch reset alarm operability as follows:

1. VERIFY no other alarm condition exists on the Emergency Diesel Generator A alarm panel.

Standard: No alarms. CUE: If requested, report as the AO, nab other alarm condition exists on the Emergency Diesel Generator A alarm panel. Comment: Page 10 of 13

Appendix C Job Perforrriance Measure Form ES-C1 PERFORMANCE INFORMATION STP-0-12.1, step 6.3.1 9.2 /, Performance Step: 23 PLACE D/G A CONTROL switch in the PULL STOP position AND VERIFY the following: MCB Alarm qJ-24,EMERGENCY DIESEL GEN 1A PANEL, is illuminated. Emergency Diesel Generator A START RELAY 1 POWER AVAILABLE AND START RELAY 2 POWER AVAILABLE lights are extinguished (MCB). Standard: D/G A CONTROL switch in PULL STOP. MCB Alarm J-24, EMERGENCY DIESEL GEN 1A PANEL, is illuminated. Emergency Diesel Generator A START RELAY 1 POWER AVAILABLE AND START RELAY 2 POWER AVAILABLE lights are extinguished (MCB). Comment: STP-0-12.1, step 6.3.1 9.3 Performance Step: 24 DEPRESS ACK button at DGlA ELCP Annunciator Panel AND VERIFY Emergency Diesel Generator A shutdown reset annunciator (R3) is illuminated. Standard: Contacts A 0 to perfclrm step 6.3.19.3. CUE: Acknowledge request. Simulator Operator: Insert Manual Triggers 1 and 2 to reset DGlA ELCP Annunciator Panel. CUE: ACK button at DG1 A ELCP Annunlciator Panel has been depressed and (R3) is illuminated. Comment: Terminating Cue: Evaluation on this JPM is complete. STOP TIME: TIME CRITICAL STOP TIME: Page 11 of 13

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Appendix C Job Performance Measure Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC JPM F Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiners Signature: Date: Page 12 of 13

Appendix C Job Performance Measure Form ES-C-1 JPM CUE SHEET Initial Conditions: e You are an extra RO. e The plant is at 100% power with a normal electrical lineup. e The A EDG is running for the monthly surveillance per STP 12.1 through Step 6.2.42. All readings have been taken and evaluated as satisfactory. There is an A 0 available at the A DIG. The Diesel has run for 65 minutes, all readings have been taken. The A 0 has the data sheets. Bi-Annual selected Service Water Pump starts are not required. Initiating Cue: The CRS has directed you lo shutdown the A D/G per STP-0-12.1 steps 6.3 through 6.3.1 9. Page 13 of 13

I Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Ginna Task No.: 015-007-01-01A TasWJPM

Title:

Remove a Power Range Channel JPM No.: 2008 NRC JPM G from Service. WA

Reference:

015 A2.02 3.1 I 3.5* Examinee: NRC Examiner: Facility Evaluator: Date: Method of testina: Simulated Performance: Actual Performance: X Classroom Simulator --X Plant Applicability: RO/SRO SUBMITTED BY: Ted Coe DATE: 6/30/08 Developer REVIEWED BY: Art Vest DATE: 6/30/08 Training Technical Reviewer REVIEWED BY: Don Dettman DATE: 6/30/08 Operations Technical Reviewer APPROVED BY: John Brown DATE: 6/30/08 Training Management Page 1 of 13

I Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: Remove N-41 from service and all critical tasks evaluated as satisfactory. Required Materials: None General

References:

ER-NIS.3, PR Malfunction, Rev. 26 Handouts: ER-NIS.3, PR Malfunction, Rev. 26 Time Critical Task: NO Validation Time: 19 minutes Alternate Path: NO Instructor Notes: Ensure a marked up copy of ER-NIS.3, PR Malfunction, Rev. 26 is ready to give to the operator during the Initiating Cue. 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 objelctive for this Job Performance Measure will be satisfied. Initial Conditions: You are an extra RO. 0 Power Range channel N-41 drifted low over a period of several minutes and has been declared inoperable. No plant transient has occurred. 0 Procedure ER-NIS.3 is being implemented. 0 Reactor power is 100%. 0 No other channels have been defeated. Initiating Cue: The CRS has directed you to remove PR N-41 from service per ER-NIS.3. Step 4.4 Attachment N-41 Defeat. All notifications have been made and approvals received. CUE: Hand the Operator a marked up copy of ER-NIS.3, PR Malfunction, Rev. 26. Page 2 of 13

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP For the 2008 ILT NRC Exam load I/C # 177 or Select IC 19 (or any full power IC). Place Rods in manual. Place N-41 to Rod Drop Bypass, reduce gain to 0. Return Rod Drop Bypass to Normal. Adjust Tave = Tref. Page 3 of 13

Appendix C Job Performlance Measure Form ES-C-1 PERFORMANCE INFORMATION START TIME: .I= CRITICAL STEP ER-NIS.3, Att. N-41 Defeat, step 1 .I PerformanceStep: 1 IF the PPCS is operational, THEN delete NIS Channel 41 from processing by performing the following:

a. Select Group Update display.

b. Select List Server Groups.

c. Select NISI firom the pick list.

d. Turn OFF scan processing, then click the Set Scan Processing lbutton.

e. Answer prompts.

Standard: Deletes NIS Channel 41 from processing by performing the following: 0 Selects Group Update display. Selects List Server Groups. Selects NIS1 from the pick list. 0 Turns OFF scan processing, then clicks the Set Scan Processing button. Answers prompts. Comment: ER-NIS.3, Att. N-41 Defeat, step 2 Performance Step: 2 Verify the ROD CONTROL BANK SELECTOR switch (MCB) is in the M (MANUAL) poeition. Standard: ROD CONTROL BANK SELECTOR switch is selected to MANUAL. Comment: Page 4 of 13

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION ER-NIS.3, Att. N-41 Defeat, step 3 /,, Performance step: 3 Place the DROPPED ROD MODE switch (Power Range N41A drawer) to BYPASS AND verify the following: 0 DROPPED ROD BYPASS (local light) is lit. 0 POWER FIANGE-1 ROD DROP BYPASS (MCB bypass status light) is lit. 0 Annunciator (MCB) E-7, NIS TRIP BYPASS, is lit. Standard: Places the DROPPED ROD MODE to BYPASS AND verifies: 0 DROPPEC) ROD BYPASS (local light) is lit. POWER RANGE-1 ROD DROP BYPASS (MCB bypass status light) is lit. 0 Annunciator (MCB) E-7, NIS TRIP BYPASS, is lit. Comment: ER-NIS.3, Att. N-41 Defeat, step 4 4 Performance Step: 4 Place T/405E DELTA T DEFEAT switch (RIL Insertion Limit Rack) to LOOP A UNIT 1 (Defeats the delta T Runback and Rodstop for the failed channel AND removes the associated delta-T input from the RIL computer-Annunciators F-30 AND F-31 will clear if lit). Standard: Places T/405E DEiLTA T DEFEAT switch (RIL Insertion Limit Rack) to LOOP A UNIT 1 - Annunciators F-30 AND F-31 will clear if lit. Comment: Page 5 of 13

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION ER-NIS.3, Att. N-41 Defeat, step 5 /, Performance step: 5 Place the OVERTEMP TRIP bistable (Red R-1 Protection Channel 1 rack) proving switch to DEFEAT (UP) AND verify the following: Annunciator F-23, RCS 0T)T CHANNEL ALERT, is lit 0 Proving light OFF if 11-4058 > or = TI-405A IF any proving light status is NOT correct, THEN submit an ACTION Report on ,the discrepancy and continue with the channel defeat steps. Standard: Places the 0VERTE:MP TRIP bistable proving switch to DEFEAT (UP) AND verifies the following: 0 Annunciator F-23, RCS OT delta-T CHANNEL ALERT, is lit 0 Proving light OFF if TI-405B > or = TI-405A Comment: ER-NIS.3, Att. N-41 Defeat, step 6 /, Performance step: 6 Place the OVERPOWER TRIP bistable (Red R-1 Protection Channel 1 rack) proving switch to DEFEAT (UP) AND verify the following: 0 Annunciator F-32, RCS OP delta-T CHANNEL ALERT, is lit 0 Proving light OFF if TI-405B > or = TI-405C IF any proving light status is NOT correct, THEN submit an ACTION Report on the discrepancy and continue with the channel defeat steps.

 .\I Standard:            Places the OVERPOWER TRIP bistable proving switch to DEFEAT (UP) AND werifies the following:

0 Annunciator F-32, RCS OP delta-T CHANNEL ALERT, is lit 0 Proving light OFF if TI-405B > or = TI-405C Comment: Page 6 of 13

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION - ER-NIS.3, Att. N-41 Defeat, step 7 Performance Step: 7 Verify the following bistables are lit:

a. TC405A OP Delta T Loop A

b. TC405C OT Delta T Loop A Standard: Verifies bistables are lit:

a. TC405A OP Delta T Loop A

b. TC405C OT Delta T Loop A Comment:

ER-NEW, Att. N-41 Defeat, step 8 4 Performance Step: 8 Place the UPPER SECTION DEFEAT switch (Detector Current Comparator- Miscellaneous Control & Indications drawer) to the PRN41 position AND verify the following: Local light for CHANNEL DEFEAT upper section is lit. Standard: Places the UPPER SECTION DEFEAT switch to the PRN41 position AND verifiies: Local light for CHANNEL DEFEAT upper section is lit. Comment: ER-NIS.3, Att. N-41 Defeat, step 9 4 Performance Step: 9 Place the LOWER SECTION DEFEAT switch (Detector Current Comparator-MiscellaneousControls & Indications drawer) to the PRN41 position AND verify the following: 0 Local light for CHANNEL DEFEAT lower section is lit. Standard: Places the LOWER SECTION DEFEAT to the PRN41 position AND verifies: Local light for CHANNEL DEFEAT lower section is lit. Comment: Page 7 of 13

I Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION - ER-NIS.3, Att. N-41 Defeat, step 10 4 Performance Step: 10 Place the POWER MISMATCH BYPASS switch (Detector Current Comparator-Miscellaneous Controls & Indications drawer) to BYPASS PR N41. Standard: Places the POWER MISMATCH BYPASS to BYPASS PR N41. Comment: ER-NIS.3, Att. N-41 Defeat, step 11 4 Performance Step: 11 Place the ROD STOP BYPASS switch (Detector Current Comparator-Miscellaneous Controls & Indications drawer) to BYPASS PR N41. Standard: Places the ROD STOP BYPASS switch to BYPASS PR N41. Comment: ER-NIS.3, Att. N-41 Defeat, step 12 4 Performance Step: 12 Place the COMPARATOR CHANNEL DEFEAT switch (Comparator and Ratedrawer) to N41 AND verify the following: Local light for COMPARATOR DEFEAT is lit. Standard: Places the COMPARATOR CHANNEL DEFEAT switch to N41 AND verifies: Local light ,for COMPARATOR DEFEAT is lit. Comment: Page8of 13

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION ER-NIS.3, Att. N-41 Defeat, step 13 /, Performance Step: 13 Remove the 118V 51A AC INSTR POWER fuses (Power Range N41B drawer) AND verify the following alarms (MCB) are lit: E-18, POWER RANGE LOSS OF DETECTOR VOLTAGE E-19, POWER RANGE HI RANGE CHANNEL ALERT 108% E-21, POWER RANGE OVERPOWER ROD STOP 103% E-27, POWER RANGE LO RANGE CHANNEL ALERT 24% E-28, POWER RANGE ROD DROP ROD STOP -5%/5 SEC Standard: Removes the 118V !5A AC INSTR POWER fuses (Power Range N41B drawer) AND !verifiesthe following alarms (MCB) are lit: E-18, POWER RANGE LOSS OF DETECTOR VOLTAGE E-19, POWER RANGE HI RANGE CHANNEL ALERT 108% E-21, POWER RANGE OVERPOWER ROD STOP 103% E-27, POWER RANGE LO RANGE CHANNEL ALERT 24% E-28, POWER RANGE ROD DROP ROD STOP -5/0/5 SEC Comment: ER-NIS.3, Att. N-41 Defeat, step 13.1 Performance Step: 14 Verify the following red bistable lights (MCB) are lit: HI POW RANGE P-10 NC41M HI POW RANGE P-8 NC41N 0 LO POW RANGE TRIP NC41P 0 HI POW RANIGE TRIP NC41R HI POW RANIGE P-9 NC41S IF any bistable above is NOT lit, THEN the channel may not be in the tripped. Standard: Verifies the following red bistable lights (MCB) are lit: HI POW RANGE P-10 NC41M HI POW RANGE P-8 NC41N 0 LO POW RANGE TRIP NC41P 0 HI POW RANGE TRIP NC41R HI POW RANGE P-9 NC41S Note to Examiner: There are no more critical steps in the rest of this JPM. Comment: Page 9 of 13

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION ER-NEB, Att. N-41 Defeat, step 13.2 Performance Step: 15 Verify the following status lights (Power Range N41A drawer) are lit: 0 CONTROL POWER ON 0 LOSS OF DETECTOR VOLT 0 OVERPOVVER TRIP HIGH RANGE 0 OVERPOVVER ROD STOP 0 OVERPOVVER TRIP LOW RANGE 0 POWER ABOVE PERMISSIVE P10 0 POWER ABOVE PERMISSIVE P8 0 POWER ABOVE PERMISSIVE P9 0 DROPPED ROD ROD STOP 0 DROPPED ROD BYPASS Standard: Verifies the following status lights (Power Range N41A drawer) are lit: CONTROL POWER ON LOSS OF DETECTOR VOLT OVERPOWER TRIP HIGH RANGE OVERPOWER ROD STOP OVERPOWER TRIP LOW RANGE 0 POWER ABOVE PERMISSIVE P I 0 POWER ABOVE PERMISSIVE P8 POWER AEIOVE PERMISSIVE P9 DROPPED ROD ROD STOP 0 DROPPED ROD BYPASS Comment: ER-NIS.3, Att. N-41 Defeat, step 13.3 Performance step: 16 Verify the following status lights (Power Range N41B drawer) are extinguished: INSTRUMENT POWER ON CHANNEL ON TEST Standard: Verifies the following status lights (Power Range N41B drawer) are extinguished: INSTRUMENT POWER ON CHANNEL ON TEST Comment: Page IOof 13

Appendix C Job Perforniance Measure Form ES-C-1 PERFORMANCE INFORMATION ER-NIS.3, Att. N-41 Defeat, step 14 Performance Step: 17 Notify I&C to install jumpers across contacts 1-5 AND 4-8 of Power Range relays NC 41 MX (both A train and B train Protection Racks). This will remove N-41 from the logic circuit for reinstating the PR low power trip and the source ranges (P-10). Standard: Notifies I&Cto install jumpers across contacts 1-5 AND 4-8 of Power Range relays NC 41 MX (both A train and B train Protection Racks). CUE: Acknowledge request. Comment: ER-NIS.3, Att. N-41 Defeat, step 15 Performance Step: 18 hitiate an A-52.4 On N-41. Standard: Initiates an A-52.4 on N-41 or informs CRS to initiate A-52.4. CUE: CRS has initiated an A-52.4 for NI-41. Comment: ER-NIS.3, Att. N-41 Defeat, step 16 Performance Step: 19 Go to step 4.5-Standard: Goes to step 4.5. CUE: CRS will continue at step 4.5. Comment: Terminating Cue: Evaluation on this JPM is complete. STOP TIME: TIME CRITICAL STOP TIME: Page 11 of 13

Appendix C Job Performance Measure Form ES-C-1 VERlFlCATIOlV OF COMPLETION Job Performance Measure No.: 2008 NRC JPM G Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiners Signature: Date: Page 12 of 13

Appendix C Job Performance Measure Form ES-C-1 JPM CUE SHEET Initial Conditions: You are an extra RO. 0 Power Range channel N-41 drifted low over a period of several minutes and has been declared inoperable. No plant transient has occurred. 0 Procedure ER-NIS.3 is being implemented. Reactor power is 100%. 0 No other channels have been defeated. Initiating Cue: The CRS has directed you to remove PR N-41 from service per ER-NIS.3. Step 4.4 Attachment N-41 Defeat. All notifications have been made and approvals received. Page 13 of 13

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Ginna Task No.: 029-004-01-01A Task/JPM

Title:

Shutdown Containment Purge JPM No.: 2008 NRC JPM H K/A

Reference:

APE 036 AA1.01 3.3 13-81 Examinee: NRC Examiner: FaciIity Evaluator: Date: Method of testincr: Simulated Performance: Actual Performance: X Classroom Simulator -.- >( Plant Applicability: RO/SRO SUBMITTED BY: Ted Coe DATE: 6/30/08 Developer REVIEWED BY: Art Vest DATE: 6/30/08 Training Technical Reviewer REVIEWED BY: Don Dettman DATE: 6/30/08 Operations Technical Reviewer APPROVED BY: John Brown DATE: 6/30/08 Training Management Page 1 o f 7

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: The Containment Purge shiutdown and all critical tasks evaluated as satisfactory. Required Materials: None General

References:

S-23.2.2, Containment Purge Procedure, Rev. 04801 Handouts: S-23.2.2, Containment Purge Procedure, Rev. 04801 Time Critical Task: NO Validation Time: 5 minutes Alternate Path: NO Instructor Notes: Ensure a marked up copy of S-23.2.2, Containment Purge Procedure, Rev. 04801 is ready to give to the operator during the Initiating Cue. READ TO THE EXAMINEE I will explain the initial conditions, which steps to siniulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions: You are an extra RO. The plant is in cold shutdown. A Containment Purge is in progress. The Refuel SRO has requested Containment Purge be secured due to a Refueling Incident. RP has authorized securing the purge. Initiating Cue: The Shift Manager directs you to secure the Containment Purge per Step 6.3 of S-23.2.2. CUE: Hand the Operator a marked up copy of S23.2.2,Containment Purge Procedure, Rev. 04801. Page 2 of 7

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP For the 2008 ILT NRC Exam load I/C # 178 or Any cold shutdown IC. Remove purge flanges, MIS78. Place purge system in service with both fans running. S-23.2.2 signed off up to section 6.3. Page 3 of 7

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE I NFORMATlON START TIME: 4 = CRITICAL STEP S-23.2.2, step 6.3.1 4 Performance Step: 1 STOP Containment Purge Supply and Exhaust Fans Aif running. OTHERWISE MARK this step N/A. Standard: Switch to stop. Red lights off, Green lights on. Comment: S-23.2.2, step 6.3.2 4 Performance Step: 2 STOP Containment Purge Supply and Exhaust Fans 6if running OTHERWISE MARK this step N/A. Standard: Switch to stop. Red lights off, Green lights on. Comment: S-23.2.2, step 6.3.4 4 Performance Step: 3 CLOSE Containment Purge Supply Valve V-5869. Standard: Switch to close. Red light off, Green light on. Comment: S-23.2.2, step 6.3.4 4 Performan-e Step: 4 CLOSE Containment Purge Exhaust Valve V-5879. Standard: Switch to close. Red light off, Green light on. Comment: Page 4 of 7

Appendix C Job Performance Measure Form ES-C-1 PERFORMAFJCE IN FORMATION S-23.2.2, step 6.3.5 Performance step: 5 LOG information on Containment Purge Release Permit. Standard: Logs information on Containment Purge Release Permit. CUE: The HCO will do that. Comment: Terminating Cue: Evaluation on this JPM is complete. STOP TIME: TIME CRITICAL STOP TIME: Page 5 of 7

Appendix C Job Perforrnance Measure Form ES-C-1 VERIFICATlOhI O F COMPLETION Job Performance Measure No.: 2008 NRC JPM H Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

ResuIt : SAT UNSAT Examiners Signature: Date: Page 6 of 7

Appendix C Job Performance Measure Form ES-C-1 JPM CUE SHEET Initial Conditions: You are an extra RO. The plant is in cold shutdown. A Containment Purge is in progress. The Refuel SRO hlas requested Containment Purge be secured due to a Refueling Incident. RP has authorized securing the purge. Initiating Cue: The Shift Manager directs you to secure the Containment Purge per Step 6.3 of S-23.2.2. Page 7 of 7

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Ginna Task No.: 001-007-01-04A TasWJPM

Title:

Startup and Parallel Rod Drive MG JPM No.: 2008 NRC JPM I Set (Parallel Fails) KIA

Reference:

001 A4.0 8 3.7 13.4 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testina: Simulated Performance: X Actual Performance: Classroom Simulator -- Plant X ApplicabiIity: ROIS RO SUBMITTED BY: Ted Coe DATE: 6/30/08 Developer REVIEWED BY: Art Vest DATE: 6/30/08 Training Technical Reviewer REVIEWED BY: Don Dettman DATE: 6/30/08 Operations Technical Reviewer APPROVED BY: John Brown DATE: 6/30/08 Training Management Page 1 of 13

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: MG sets paralleled and all critical tasks evaluated as satisfactory. Required Materials: Proper Noise Protection, Hard Hat, Safety Glasses, Safety Shoes, Leather Gloves. General

References:

S-IA, Startup of Rod Drive Motor Generator Sets, Rev.18 Handouts: S-IA, Startup of Rod Drive Motor Generator Sets, Rev.18 Time Critical Task: NO Validation Time: 20 minutes Alternate Path: YES Instructor Notes: Ensure Proper Noise Protection, Hard Hat, Safety Glasses, Safety Shoes and leather gloves are worn as required. Ensure a marked up copy of S-lA, Startup of Rod Drive Motor Generator Sets, Rev. 18 is ready to give to the operator during the Initiating Cue. 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: 0 You are an extra RO. 0 Preparations for startup of Rod Control System are under way. 0 The 1 B MG set is runnting. Initiating Cue: The Shift Manager directs you to startup and parallel the 1A Rod Drive MG Set per S-1A section 5.3. Simulate all activities - DO NOT MANIPULATE ANY EQUIPMENT. CUE: Hand the Operator a marked up copy of S-1A, Startup of Rod Drive Motor Generator Sets, Rev.18. Page 2 of 13

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION START TIME: .( = CRITICAL STEP S-1A, step 5.3.1 Performance Step: 1 One MG set is running and carrying a steady electrical load. Standard: Verifies 1B MG set is running. Given in initial cue. CUE: 1B MG set is running, carrying a steady electrical load. 1A MG set is secured. Comment: S-1A, step 5.3.2 Performance step: 2 Verify remaining motor generator set ALARM BYPASS switch is in the BYPASS position. Standard: Verifies 1A MG set ALARM BYPASS switch is in the BYPASS position. CUE: 1A MG set ALARM BYPASS switch is in the BYPASS position. Comment: S-1A, step 5.3.3 Performance Step: 3 Verify the remaininlg Motor Generator set VOLTAGE ADJUST in full counter-clockwise position. Standard: 1A MG set VOLTAGE ADJUST is in full counter-clockwise position. CUE: 1A MG set \ 0 ,TAGE ADJUST is in full counter-clockwise position. Comment: S-1A, step 5.3.4.1 4 Performance Step: 4 Rotate the MOTOR NO. 1A CIRCUIT BREAKER CONTROL switch to CLOSE. Standard: Identifies the MOTOR NO. 1A CIRCUIT BREAKER CONTROL switch, and simulales rotating to CLOSE. CUE: Component is in desired position. Comment: Page 3 of 13

Appendix C Job Performance Measure Form ES-C-1 PERFORMANC: E INFORMATION CUE: Motor is at full speed. S-I A, step 5.3.4.2 /, Performance Step: 5 WHEN motor is at flull speed, THEN depress AND hold the FIELD FLASH pushibutton. Standard: Identifies FIELD FLASH pushbutton, and generator voltage indication (OUTPUT AC VOLTAGE METER). Simulate depressing and holding FIELD FLASH pushbutton. CUE: Component is in desired condition. Comment: S-I A, step 5.3.4.3 I, Performance Step: 6 WHEN Generator voltage has risen to > 234 volts AND is NOT increasing, THEN release the FIELD FLASH pushbutton. Standard: Simulates FIELD FLASH pushbutton released. CUE: Generator voltage has risen to 250 volts AND is steady. CUE: Component is in desired conditionl. Comment: S-IA, step 5.3.4.4 /, Performance Step: 7 Rotate the VOLTAGE ADJUST potentiometer clockwise UNTIL voltage is 260. Standard: Rotates the VOLTAGE ADJUST potentiometer clockwise UNTIL voltage is 260. CUE: Generator voltage has risen slowly to 260 volts. Comment: S-1A, step 5.3.5 Performance Step: 8 Verify FIELD CURRENT is ~ 1 . amps2 AND <4.8 amps as read on the FIELD CURRENT METER. Standard: identifies FIELD CURRENT METER. CUE: FIELD CURRENT is as read. Comment: Page 4 of 13

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION S-IA, step 5.3.6 Performance Step: g Verify FIELD CURFlENT alarm has cleared. (Alarm LED is located on the F1EL.DCURRENT METER) Standard: Identifies alarm LED on the FIELD CURRENT METER is out. CUE: Alarm LED on the FIELD CURRENT METER is out. Comment: S-I A, step 5.3.7 Performance Step: 10 Place ALARM BYPASS switch in the "ACTIVE position. Standard: Identifies ALARM BYPASS switch and simulates placing in "ACTIVE". CUE: Component is in desired position. Comment: S-I A, step 5.3.8 Performance step: 11 Verify MCB annunciator C-21 (Rod Control MG Set Trouble) is extinguished. Standard: Contacts control room on status of (2-21. CUE: C-21, (Rod Control MG Set Trouble) is extinguished. Comment: S-1A, step 5.3.9 /, Performance Step: 12 Rotate the synchronize switch to ON (on the MG set being started) AND allow a few seconds for the synchronizer to warm UP-Standard: Rotates the 1A synchronize switch to ON (AND allows a few seconds for the synchronizer to warm up. CUE: Component is in desired position. Comment: Page 5 of 13

Appendix C Job Performance Measure Form ES-C-1 PERFORMAN(; E INFOR MATI0N S-1A, step 5.3.10.11 /,, Performance Step: 13 Observe the Synchroscope (SydCRDMGAB) for indication when the two generators are in sync and trip the on-coming M/G Set Motor Breaker by rotating the circuit breaker control handle to the TRIP POSITION just after the Synchronizing Point (approximately 3 miinutes after 12). Standard: Observes the Synchroscope for indication when the two generators are in sync and trips the 1A M/G Set Motor Breaker by rotating the circuit breaker control handle to the TRIP POSITION just after the Synchronizing Point (approximately 3 minutes after 12). CUE: Component is in desired position. CUE: It has been 30 seconds and the Synchroscope indicates the two generators are not in parallel. Comment: S-1A, step 5.3.1 0.2 4 Performance Step: 14 Should the Generatlor fail to parallel within 30 seconds, THEN return the synchronize switch to OFF, AND proceed with steps 5.3.1 through 5.3.10 again. N/A if generator paralleled. Standard: Synchronize switch to OFF. Returns to step 5.3.1. CUE: Synchroscope indicates the two generators are not in parallel. CUE: Component is in desired position. Comment: S-1A, step 5.3.1 (Start Alternate Path) Performance Step: 15 One MG set is running and carrying a steady electrical load. Standard: Verifies 16 MG set i s running. Given in initial cue. CUE: 1B MG set is running, carrying a steady electrical load. Comment: S-1A, step 5.3.2 Performance Step: 16 Verify remaining motor generator set ALARM BYPASS switch is in the BYPASS position. Standard: Places 1A MG set ALARM BYPASS switch in the BYPASS position. CUE: 1A MG set ALARM BYPASS switch is in the BYPASS position. Page 6 of 13

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION Comment: S-1A, step 5.3.3 Performance Step: 17 Verify the remaining Motor Generator set VOLTAGE ADJUST in full counter-clockwise position. Standard: Adjusts 1A MG set VOLTAGE ADJUST to the full counter-clockwise position. CUE: 1A MG set VOLTAGE ADJUST is in full counter-clockwise position. Comment: S-1A, step 5.3.4.1

,/ Performance Step: 18      Rotate the MOTOR NO. 1A CIRCUIT BREAKER CONTROL switch to CLOSE.

Standard: Identifies switch, and simulate rotating to CLOSE. CUE: Component is in desired position. Comment: CUE: Motor is i a t full speed. S-1A, step 5.3.4.2 /, Performance Step: 19 WHEN motor is at flAl speed, THEN depress AND hold the FIELD FLASH pushbutton. Standard: Identifies FIELD FLASH pushbutton, and generator voltage indication (OUTPUT AC VOLTAGE METER). Simulate depressing and holding FIELD FLASH pushbutton. CUE: Component is in desired conditioni. Comment: S-1A, step 5.3.4.3 /, Performance Step: 20 WHEN Generator voltage has risen to > 234 volts AND is NOT increasing, THEN release the FIELD FLASH pushbutton. Standard: Simulates FIELD FLASH pushbutton released. CUE: Generator voltage has risen to 250 volts AND is steady. CUE: Component is in desired condition. Comment: Page 7 of 13

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION S-1 A, step 5.3.4.4 4 Performance step: 21 Rotate the VOLTAGE ADJUST potentiometer clockwise UNTIL voltage is 260. Standard: Rotates the VOLTAGE ADJUST potentiometer clockwise UNTIL voltage is 260. CUE: Generator voltage has risen slowly to 260 volts. Comment: S-1 A, step 5.3.5 Performance Step: 22 Verify FIELD CURRENT is >1.2 amps AND <4.8 amps as read on the FIELD CUFlRENT METER. Standard: Identifies FIELD CURRENT METER. CUE: FIELD CURRENT is as read. Comment: S-1A, step 5.3.6 Performance Step: 23 Verify FIELD CURRENT alarm has cleared. (Alarm LED is located on the FIELD CURRENT METER) Standard: Identifies alarm LEID on the FIELD CURRENT METER is out. CUE: Alarm LED on the FIELD CURRENT METER is out. Comment: S-1A, step 5.3.7 Performance Step: 24 Place ALARM BYPASS switch in the "ACTIVE position. Standard: Identifies ALARM BYPASS switch and simulates placing in "ACTIVE". CUE: Component is in desired positian. Comment: Page 13 of 13

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION S-1A, step 5.3.8 Performance Step: 25 Verify MCB annunciiator C-21 (Rod Control MG Set Trouble) is extinguished. Standard: Contacts control room on status of (2-21. CUE: (2-21, (Rod Control MG Set Trouble!) is extinguished. Comment: S-1 A, step 5.3.9 4 Performance Step: 26 Rotate the synchronize switch to ON (on the MG set being started) AND allow i3 few seconds for the synchronizer to warm UP. Standard: Rotates the 1A synchronize switch to ON (AND allows a few seconds for the synchronizer to warm up. CUE: Component is in desired position. Comment: S-1A, step 5.3.1 0.1 /, Performance step: 27 Observe the Synchroscope (SynKRDMGAB) for indication when the two generators are in sync and trip the on-coming M/G Set Motor Breaker by rotating the circuit breaker control handle to the TRIP POSITIONjust after the Synchronizing Point (approximately 3 minutes after 12). Standard: Observes the Synchroscope for indication when the two generators are in sync and trips the 1A M/G Set Motor Breaker by rotating the circuit breaker control handle to the TRIP POSITIONjust after the Synchronizing Point (approximately 3 minutes after 12). CUE: Component is in desired position. CUE: Synchroscope indicates the two generators are in parallel. Comment: Page 9 of 13

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION S-1 A, step 5.3.10.2 (End Alternate Path) Performance Step: 28 Should the Generator fail to parallel within 30 seconds, THEN return the synchronize switch to OFF, AND proceed with steps 5.3.1 through 5.3.10 again. N/A if generator paralleled. Standard: Synchronize switch in on. Step N/Ad. CUE: Synchroscope indicates the two generators are in parallel. Comment: S-1A, step 5.3.1 0.3 Performance Step: 29 Turn the Synchronize switch to the OFF position. Standard: Synchronize switch in the OFF position. CUE: Component is in desired position. Comment: S-1A, step 5.3.1 1 Performance Step: 30 Verify ROD DRIVE M-G SET 1A (MCB center section) red status light is lit. Standard: Calls Control Rooni to verify ROD DRIVE M-G SET 1A red status light is lit. CUE: From Control Room, ROD DRIVE M-G SET 1A red status light is lit. Comment: S-1A, step 5.3.12 Performance Step: 31 Verify ROD DRIVE M-G SET 1B (MCB center section) red status light is lit. Standard: Calls Control Roorn to verify ROD DRIVE M-G SET 1B red status light is lit. CUE: From Control Room, ROD DRIVE M-G SET 1B red status light is lit. Comment: Page 10 of 13

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION S-1A, step 5.3.13 /, Performance Step: 32 Adjust MG1A and MG16 voltages to minimize MG CIRCULATING CUfWENT (indicated on CIRCULATING CURRENT METER) with MG OUTPUT AC VOLTAGE close to 260 volts (between 250 and 270 volts) and FIELD CURRENT

                           >1.2 amps and <4.Iamps on both MGs.

Standard: MG OUTPUT AC VOLTAGE close to 260 volts (between 250 and 270 volts) and IFIELD CURRENT >1.2 amps and ~ 4 . amps 8 on both MGs. Records Circulatingi Current. CUE: CIRCULATING CURRENT is as read. Comment: S-1A, step 5.3.14 Performance step: 33 Verify MCB annunciator C-21 (Rod Control MG Set Trouble) is extinguished. Standard: Contacts control rotom on status of C-21. CUE: (2-21, (Rod Control MG Set Trouble) is extinguished. Comment: Terminating Cue: Evaluation on this; JPM is complete. STOP TIME: TIME CRITICAL STOP TIME: Page 111 of 13

Appendix C Job Performance Measure Form ES-C-1 VERIFICAT10N 0F COMPLETION Job Performance Measure No.: 2008 NRC JPM I Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiners Signature: Date: Page 12 of 13

Appendix C Job Perforrriance Measure Form ES-C-1 JPM CI.JE SHEET Initial Conditions: You are an extra RO. Preparations for startup of Rod Control System are under way. The 1B MG set is running. Initiating Cue: The Shift Manager directs you to startup and parallel the 1A Rod Drive MG Set per S-1A section 5.3. Simulate all activities - DO NOT MANIPULATE ANY EQUIPMENT. Page 13 of 13

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Ginna Task No.: 062-029-05-04E TasWJPM

Title:

Align Fire Water System to Fill the JPM No.: 2008 NRC JPM J CSTs Using Condensate Tranisfer System WA

Reference:

061 K4.01 4.1 /4.2 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testina: Simulated Performance: X Actual Petformance: Classroom Simulator -- Plant X Applicability: RO/SRO SUBMITTED BY: Ted Coe DATE: 6/30/08 Developer REVIEWED BY: Art Vest DATE: 6/30/08 Training Technical Revitewer REVIEWED BY: Don Dettman DATE: 6/30/08 Operations Technical Reviewer APPROVED BY: John Brown DATE: 6/30/08 Training Management Page 1 of 7

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: Line up to fill CST in accordance with ER-AFW.l section 4.3.1 and all critical tasks evaluated as satisfactory. Required Materials: Proper Noise Protection, Hard Hat, Safety Glasses, Safety Shoes, Gloves. (2) Spanner wrenches and Fire Hose. General

References:

ER-AFW.l,: ALTERNATE \NATER SUPPLY TO THE AFW PUMPS, Rev. 03001 Handouts: ER-AFW.1,: ALTERNATE WATER SUPPLY TO THE AFW PUMPS, Rev. 03001 Time Critical Task: Yes Validation Time: 11 minutes Alternate Path: NO Instructor Notes: Ensure Proper Noise Protection, Hard Hat, Safety Glasses, Safety Shoes, Gloves are worn as required. Ensure a marked up copy of ER-AFW.1, ALTERNATE WATER SUPPLY TO THE AFW PUMPS, Rev.03001 is ready to give to the operator during the Initiating Cue. READ TO THE EXAMINEE I will explain the initial conditions, which steps to siinulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions: You are an extra RO. The Plant has experienced a loss of Offsite Power. CST inventory is depleted with level < 5 ft. 0 The AFW pumps are providing S/G inventory. Initiating Cue: The Shift Manager directs you to align the Fire Water System to fill the CSTs using the Condensate Transfer System in accordance with ER-AFW.1 section 4.3.1. Simulate all activities - DO NOT MANIPULATE ANY EQUIPMENT. This is a time critical JPM. CUE: Hand the Operator a marked up copy of ER-AFW.l, Rev. 03001. Page 2 of 7

Appendix C Job Performlance Measure Form ES-C-1 PERFORMANCE INFORMATION START TIME:

.I= CRITICAL STEP ER-AFW.l, step 43.1.1 Performance Step: 1      Place Howell Level Controller LC-107 in manual at 50%.

Standard: Simulates requesting Control Room place Hotwell Level Controller in manual and 50% output. CUE: Acknowledge request and inform the examinee that the Hotwell Level controller is in manual at 50% output. Comment: ER-AFW.l, step 431.2 /, Performance Step: 2 Close or verify closed the following valves: CNDST XFE.R PUMP DISCH ISOL TO HOSE TAPS, valve 4049C CNDST XFER PUMP DISCH SAMPLE, valve 4049A CNDST XFER PUMP DISCH TO MIX BED POLISHER DI'S, valve 4050 CNDST XFER PUMP DISCH TO CST, valve 9509C CNDST XFER PUMP SUCTION ISOL FROM HOWELL, valve 4046 (in east condenser pit) CNDST XFER PUMP SUCTION FROM A&B CST, valve 4047 0 OUTSIDE CIST FILL ISOL, valve 9509D Standard: Finds, identifies and closes or verifies closed the following valves:

1. CNDST XFER PUMP DISCH ISOL TO HOSE TAPS, valve 4049C

2. CNDST XFER PUMP DISCH SAMPLE, valve 4049A

3. CNDST XFER PUMP DISCH TO MIX BED POLISHER DI'S, valve 4050

4. CNDST XFER PUMP DISCH TO CST, valve 9509C

5. CNDST XFER PUMP SUCTION ISOL FROM HOWELL, valve 4046 (in east condenser pit) 6 . CNDST XFER PUMP SUCTION FROM A&B CST, valve 4047

7. OUTSIDE CST FILL ISOL, valve 9509D CUE: Component is in desired position. (for each valve operated)

Comment: Page 3 of 7

Appendix C Job Perforrnance Measure Form ES-C-1 PERFORMANCE INFORMATION ER-AFW.1, step 4.3.1.3 Performance Step: 3 Obtain two spanner wrenches (on handrail by Cond Transfer Pump). Standard: Locates spanner wrenches. CUE: You have two spanner wrenches. Comment: ER-AFW.l, step 4.3.1.4 Performance Step: 4 Isolate/remove and cap all temporary hoses from the connections at CNDST XFER PUMP DISCH ISOL TO HOSE TAPS, valve 4049C. Standard: Finds and simulates; removing and capping hoses connected at valve 4049C. CUE: All hoses are disconnected and capped. Comment: ER-AFW.l, step 4.3.1 -5 Performance Step: 5 Run the hose from fire water hose reel #2 (located by Battery Room door) AND connect at CNDST XFER PUMP DISCH ISOL TO HOSE TAPS, valve 4049C. Standard: Simulates running hose from hose reel #2 to valve 4049C. CUE: The hose is connected between hose reel #2 and valve 4049C. Comment: ER-AFW.l, step 4.3.1.6 NOTE Performance Step: 6 NOTE: The Diesel Fire Pump should auto start while performing the following. Standard: Placekeeps and reads note. May inform control room. CUE: Acknowledge report, if made. Comment: Page 4 of 7

Appendix C Job Petforrnance Measure Form ES-C-1 PERFORMANCE INFORMATION ER-AFW.l, step 4.3.1.6 /, Performance Step: 7 Slowly open the following valves: CNDST XFER PUMP RECIRC, valve 4048 CNDST XFER PUMP DlSCH ISOL TO HOSE TAPS, valve 40496 0 TURBINE BLDG HOSE REEL #2 ISOL,valve 5178 Standard: Finds, identifies and slowly opens the following valves:

1. CNDST XFE-R PUMP RECIRC, valve 4048

2. CNDST XFER PUMP DISCH ISOL TO HOSE TAPS, valve 4049C

3. TURBINE BLDG HOSE REEL #2 ISOL,valve 5178 CUE: Component is in desired position. (for each valve operated)

Comment: Record TIME CRITICAL STOP TIME, must be less than 12 minutes from start time. ER-AFW.l, step 4.3.1 -7 Performance Step: 8 Fill CSTS as requireld. Standard: Monitors filling CST. CUE: No further action required. Comment: Terminating Cue: Evaluation on this ,JPM is complete. STOP TIME: TIME CRITICAL STOP TIME: Page 5 of 7

Appendix C Job Performance Measure Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC JPM J Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiners Signature: Date: Page 6 of 7

Appendix C Job Performance Measure Form ES-C-1 JPM CliJE SHEET Initial Conditions: You are an extra RO. 0 The Plant has experienced a loss of Offsite Power. CST inventory is depleted with level < 5 ft. 0 The AFW pumps are providing S/Ginventory. Initiating Cue: The Shift Manager directs you to align the Fire Water System to fill the CSTs using the Condensate Transfer System in accordance with ER-ANV.1 section 4.3.1. Simulate all activities - DO NOT MANIPULATE ANY EQUIPMENT. This is a time critical JPM. Page 7 of 7

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Ginna Task No.: 062-030-05-04A WA

Reference:

APE 077 AA1.05 3.9 / 4.0 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testina: Simulated Performance: X Actual Performance: Classroom Simulator -.- Plant X Applicability: RO/SRO SUBMITTED BY: Ted Coe DATE: 6/30/08 Developer REVIEWED BY: Art Vest DATE: 6/30/08 Training Technical Reviewer REVIEWED BY: Don Dettman DATE: 6/30/08 Operations Technical Reviewer APPROVED BY: John Brown DATE: 6/30/08 Training Management Page 1 of 6

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: Perform a manual trip of a relay for undervoltage protection on Bus 14 and all critical tasks evaluated as satisfactory. Required Materials: Proper Noise Protection, Hard Hat, Safety Glasses, Safety Shoes, Gloves. Undervoltage cabinet key #25 (the use of this key will be simulated). General

References:

ER-UV.l, TRIP OF FAILED AC EMERGENCY UV RELAY, Rev. 5 Handouts: ER-UV.l, TRIP OF FAILED AC EMERGENCY UV RELAY, Rev. 5 Time Critical Task: NO Validation Time: 10 minutes Alternate Path: NO Instructor Notes: Ensure Proper Noise Protection, Hard Hat, Safety Glasses, Safety Shoes, Gloves are worn as required. Ensure a marked up copy of ER-UV.1, TRIP OF FAILED AC EMERGENCY UV RELAY, Rev. 5 is ready to give to the operator during the Initiating Cue and undervoltage cabinet key #25. READ TO THE EXAMINEE I will explain the initial conditions, which steps to sirnulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions: You are an extra RO. The control room has received L-14, Bus 14 Undervoltage Safeguards annunciator. Procedure ER-UV.l, TRIP OF FAILED AC EMERGENCY UV RELAY is being performed and the control room staff is at step 4.2.2. Initiating Cue: The CRS directs you to perform a manual trip of Loss of Voltage 27 D/B relay for Bus 14 per Attachment BUS 14, PART B of ER-UV.l. Simulate all activities - DO NOT MANIPULATE ANY EQUIPMENT. Bus 14, Attachment BUS 14, PART A of ER-UV.l has NOT been performed. CUE: Hand the Operator a marked up copy of ER-UV.l, TRIP OF FAILED AC EMERGENCY UV RELAY, Rev. 5 and undervoltagecabinet key #25. Page 2 of 6

Appendix C Job Performance Measure Form ES-C-1 ~~ PERFORMANCE INFORMATlON START TIME:

  .J = CRITICAL STEP ER-UV.1, Att. Bus 14, part 6, step 6.1 Performance Step: 1      Verify Part A has NlOT been performed.

Standard: Verifies with Part A has not been performed, given in initiating cue, may call control room or may check Part A for Bus 14. CUE: If requested, report as CRS Part A for Bus 14, has not been performed. If local indications are checked: Component is in as found position. Comment: ER-UV.l, Att. Bus 14, part B, step 8.2

  /,  Performance Step: 2       Place the TEST ENABLE key switch (S20)on the BUS 14 Auxiliary Relay Rack (bottom left hand corner) to the TEST position. (Key cannot be removed w hen in TEST position.)

Standard: Locates key switch and simulates inserting key and rotating key to TEST position. CUE: Component is in desired position. Comment: Page 3 of 6

Appendix C Job Performance Measure Form ES-C-1 PERFORMANCE INFORMATION ER-UV.1, Att. Bus 14, part B, step B.3 /, Performance Step: 3 Place each individual Auxiliary Relay toggle switch to the TRIP position and verify that each Yellow UV light energizes or remains energized. (Located on the Auxiliary Relay Rack) 0 Relay BX1/14 Toggle sw itch to TRIP Yellow UV Light LIT MCB Annuriciator L-14 ENERGIZED 0 Relay BX2/14 Toggle switch to TRIP Yellow UV Light LIT Relay BX3/114 Toggle switch to TRIP Yellow UV Light LIT Relay BX4/14 Toggle switch to TRIP Yellow UV Light LIT 0 Relay BX5/14 Toggle switch to TRIP Yellow UV Light LIT 0 Relay BX6/14 Toggle switch to TRIP Yellow UV Light LIT Standard: Locates each toggle switch listed and simulates toggling switch to TRIP. Verifies UV light lit for each toggle switch operated. 0 Relay BX1/74 Toggle sw itch in TRIP Yellow UV Light LIT MCB Annunciator L-14 ENERGIZED 0 Relay BX2/14 Toggle switch in TRIP Yellow UV Light LIT 0 Relay BX3/14 Toggle switch in TRIP Yellow UV Light LIT 0 Relay BX4/14 Toggle switch in TRIP Yellow UV Light LIT 0 Relay 6 x 9 1 4 Toggle switch in TRIP Yellow UV Light LIT 0 Relay BX6/14 Toggle switch in TRIP Yellow UV Light LIT CUE: Component is in desired position. / Light is lit. / MCB Ann. Is energized. Comment: ER-UV.l, Att. Bus 14, part B, step B.4 Performance Step: 4 Return to step 4-2.3-Standard: Contacts the control room to continue on at step 4.2.3. CUE: Acknowledge report. Comment: Terminating Cue: Evaluation on this JPM is complete. STOP TIME: TIME: CRITICAL STOP TIME: Page 4 of 6

Appendix C Job Perforniance Measure Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC JPM K Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiners Signature: Date: Page 5 of 6

Appendix C Job Perforrnance Measure Form ES-C-1 JPM CUE SHEET Initial Conditions: You are an extra RO. The control room hias received L-14, Bus 14 Undervoltage Safeguards annunciator. Procedure ER-UV:I, TRIP OF FAILED AC EMERGENCY UV RELAY is being performedand the control room staff is at step 4.2.2. Initiating Cue: The CRS directs you to perform a manual trip of Loss of Voltage 27 D/B relay for Bus 14 per Attachment BUS 14, PART B of ER-UV.l. Simulate all activities - DO NOT MANIPULATE ANY EQUIPMENT. Bus 14, Attachment BUS 14, PART A of ER-UV.l has NOT been performed. Page 6 of 6

Facilty: R. E. Ginna Scenario No.: 1 Op-Test No.: 1 Scenario

Description:

After the crew takes the watch, PT-486, Turbine First :Stage Pressure fails low. This results in Steam Dum1s being armed, but not open. The crew should determine the instrument is failed, verify AR-G-15, and implement ER-INST.1, Reactor Protection Bistable Defeat after Instrumentation Failure, to place the appropriate RPS bistables in the trip condition. After the crew completes actions for PT-486, Loop 6 Thot TE-404A fails high. This results in the steam dumps opening. The crew should take action to stabilize the plant, implement ER-INST.1, and close the steam dumps. The ATC should place Rods and Charging pump A in manual. The SRO should refer to and enter TS 3.3.1 Condition D and Action D.l and 3.3.2 Condition F and Action F.l. After the crew stabilizes the plant but before the failed channel is defeated, a 10 GPM primary-to-secondary leak develops in Steam Generator 6. The crew should implement AP-SG.1, Steam Generator Tube Leakalie. The SRO should refer to and enter TS 3.4.13 Condition B and Actions B.l and 8.2. Due to the steam generator tube leakage, the crew should initiate a plant shutdown with a turbine ramp rate of 3%/min per AP-SG.l. During the plant shutdown, RCP 1B Vibration rises. The crew should implement AR-AA-18 and/or AR-AA-26. Vibrations rise to the point of requiring a manual reactor trip to allow securing RCP 1B. After the crew trips the reactor and secures RCP 1B, a. steam leak downstream of the MSlVs occurs, which causes the tube leakage to rise to 400 gpm. MSlV B fails to close automatically or manually from the Contr )I Room requiring local closure. SI Pump C fails to auto start and RHR Pump A trips on start after an SI. The crew should manually start SI Pump C. The crew should implement E-0, transition to E-2, and then to E-3. The crew should send an A 0 to locally close the failed MSlV and secure feeding S/G B when level requirements are met (> 7% NR). The local closure of the MSlV will be successful after entry into E-3. Once in E-3 the crew may need to feed S/G B to > 7% NR and then re-isolate feed flow. The scenario may be ended after the crew completes the initial cool down of the RCS in E-3. Revision 00 Page 2 of 17

Facilty: R. E. Ginna Scenario No.: 1 Op-Test No.: 1 CRITICAL TASKS CT E-0-1 Task: Establish flow from at least one train of high pressure SI pumps (two pumps running with flow to opposite trains) before transition out of E-0. Cues: A SI pump 00s B SI pump running C SI pump not running Indication: C SI pump manually started from MCB Feedback: B and C SI pump indicate running from status lights and SI flow indicated CT E-3-A Task: Isolate feedwater flow into and steam flow from the ruptured steam generator before a transition to ECA-3.1 occurs. Cues: Indication of SGTR 0 Increasing SG water level 0 Steam generator radiation and 0 SI actuated and 0 Rx trip actuated Indication: Manipulations of controls to isolate the ruptured SG 0 MSlVclosed 0 Local isolation by attachment Ruptured SG initiated 0 ARV setpoint adjusted to 1050 in Auto 0 SG blowdown and sample valve closed (verify) 0 TDAFW steam supply valve from ruptured SG closed 0 MDAFW and TDAFW discharge valve to ruptured SG closed 0 Main feed reg and bypass valve to ruptured SG closed, main feedwater pumps tripped (verity) Feedback: Ruptured SG pressure stable or increasing. No indication of feed flow to ruptured SG. Revision 00 Page 3 of 17

Facilty: R. E. Ginna Scenario No.: 1 Op-Test No.: 1 Scenario Timeline: Event Time Delay Ramp Number (Min) Key Evenlt HH: MM:SS HH:MM:SS Final NIA LOAD SGNOl B NIA oo:oo:oo oo:oo:oo 0 SIG LEVEL CHANNEL FAILURE: LT-461(I) 1 2 TUR16B 1 oo:oo:oo oo:oo:oo 0 FIRST STAGE PRESSURE TRANSMITTER FAILURE : PT-486 2 *** (- 11) RCS11F 3 oo:oo:oo oo:oo:oo 980 RTD FAILURE : LP B HOT TE-404A (TT-404)lV 3 *** (-18) SGN04B 5 oo:oo:oo 0O:Ol :oo 10 SIG B TUBE LEAK AT TUBE SHEET - 4 (-22) NIA NIA oo:oo:oo oo:oo:oo NIA PLANT POWER REDUCTION 5 *** (-28) RCS15B 7 oo:oo:oo 00:03:00 25 RCP HIGH VIBRATION RCP-1B SHAFT - 5 RCS15D 7 oo:oo:oo 00:03:00 10 RCP HIGH VIBRATION : RCP-1B SEISMIC 6 *** (-32) STM03 9 oo:oo:oo oo:oo:oo 200,000 STEAMLINE BREAK OUTSIDE CNMT DOWNSTREAMOF MSIV'S - 6 *** (-32) SGN04B NIA oo:oo:oo 00:03:00 400 S/GB TUBE LEAK AT TUBE SHEET 6 LOAD STM05B NIA oo:oo:oo oo:oo:oo 100 MAIN STEAM ISOLATION VALVE FAILURE : VLV 3516 - 6 LOAD RPS07C NIA oo:oo:oo oo:oo:oo 1 AUTO FAIL: C SI PUMP ON BUS 14 6 LOAD RPS07D NIA oo:oo:oo oo:oo:oo 1 AUTO FAIL: C SI PUMP ON BUS 16 - 6 LOAD RHRO1A N/A oo:oo:oo oo:oo:oo 1 RHR PUMP 1A TRIP

• • • Events initiated on cue from NRC Lead Examiner Estimated Time: 65 Minutes Revision 00 Page 4 ot 17

Appendix D Required Operator Actions Form ES-13-2 Op-Test No.: 1 Scenario No.: 1 Event N0.: 1 Event

Description:

(T=2) PT-486, Turbine First Stage Pressure Fails Low Indications: 0 Pl-486 on vertical section of Board 1 failed Lo 0 G-15, Steam Dump Armed lit i t after 205 seconds - Recognizes failure of IPT-486 and reports to SRO. Refers to Annunciator Response Procedure AR-G-15 and determines that ER-INST.1, Reactor Protection Bistable Defeat After InstrumentationFailure should be entered. - Enters ER-INST.l and determines Section 4.12 is the correct section to implement. ~ Determines that the Steam Dump system should not be reset. ~ Refers to Attachment FIRST STAGE PRESSURE Pl-486, BLUE, to defeat channel AND to restore AUTOMATIC control. - Places the following bistable proving switch to DEFEAT (UP) AND verifies the proving light status is correct in the (BLUE) B-1 PROTECTION CHANNEL 3 rack: 486 CHANNEL 3 TURBINE PWR TRIP Light ON - Verifies the AMSAC TRIPPED status light (MCB) is extinguished. - Requests an A 0 verify the TL 400 bistable indicating light (FOX 3-RELAY ROOM) is extinguished. - Sends an A 0 to verify AMSAC feedwater flow bistables are reset: (FOX 3 RELAY ROOM) 0 TU466 TRIP STATUS LIGHT EXTINGUISHED 0 TU467 TRIP STATUS LIGHT EXTINGUISHED TU476 TRIP STATUS LIGHT EXTINGUISHED 0 TU477 TRIP STATUS LIGHT EXTINGUISHED - Requests A 0 place switch TPS/486 (FOX 3-RELAY ROOM) to the TRIP position AND verify TL486 TRIP STATUS light is lit. - Verifies the AMSAC AlJTO BLOCK status light (MCB) is extinguished. - Deletes the computer point from the PPCS by performing the following on the Sub/Delete/Restore display: 0 Select Point ID PO486 0 Turn OFF scan processing 0 Select Change End of Event R. E. Ginna Nuclear Plant Page 5 of 17 Revision 00

Appendix D Required Operator Actions Form ES-I)-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 2 Event

Description:

(- T = l l ) Loop 6 ThotTE-404A fails high Indications: 0 Steam Dumps indicate open 0 F-14, CHARGING PUMP SPEED LIT 0 F-15, RCS TAVG DEV 4°F LIT F-16, TAVG-TREF DEVIATION +/- 5 'F LIT 0 F-23, RCS OTAT CHANNEL ALERT LIT F-24, RCS AVG AT DEVIATION LIT 0 F-32, RCS OPAT CHANNEL ALERT LIT RCS Tavg lowering TI 404 higher than TI-401 through TI-403

                                                          'E-404A and reports to SRO.                          -

failure is causing Steam Dump operation and e Selector Switch to Manual, places Steam Dump

                                                           )de selector to MANUAL.                             -

JUAL to stabilize PRZR level. -

                                                            .5 and 3.1.6 to determine actual insertion limits. -

ELTA T 408 YELLOW CHANNEL attachment for defrai lector switch in MANUAL. - speed controllers in MANUAL. - Check the following ITS Sections for LCOs: 9 Section 3.3.1, Table 3.3.1-1, Functions 5 and 6 o Enters Condition D and Action D.l 0 Section 3.3.2, Table 3.3.2-1, Function 4d R. E. Ginna Nuclear Plant Page 6 of 17 Revision 00

Appendix D Required Operator Actions Op-Test No.: 1 Scenario No.: 1 Event No.: 3 Event

Description:

(- T=l8) S/G B Tube Leak of = 10 gpm Indications: 0 PRZR Level slowly lowering 0 PRZR Pressure slowly lowering 0 PPCS, computer point SGTL Indicated 0 15 rising or in alarm - Time Position Applicants Actions or Behavior - ATC/BOP Recognizes indications and alarms and reports to SRO. - SRO/ATC Refers to AR-PPCS-1 (SGTL Indicated) 0 Trends PPCS ipoint R-47G. 0 Notifies RP/Chemistry to IMMEDIATELY obtain and analyze an air ejector grab sa.mple per CH-SAMP-SG-LEAKRATE. 0 Determines the estimated leak rate using PPCS point R47G or the FI-47 Local Reading and the Conversion Table (Curve Book #06-004). 0 IF any condition below is met, THEN go to AP-SG.l, STEAM GENERATOR TUBE LEAK: o R47G (PPCS) greater than 5 gpd OR o R-47 greater than or equal to 5 gpd (per conversion table) - SRO Enters AP-SG.1, Steam Generator Tube Leakage - ATC Monitors PRZR Level and starts additional charging pumps, or raises chargirtg pump speed, as necessary to stabilize PRZR level. - Crew Monitors S/G tube leak rate and estimates S/G tube leak rate: 0 Charging/Letdown mismatch A VCT LeveVTiime PPCS Point R47G 0 R-47 drawer indication (using conversion table, Curve Book #06-004 I ATC/BOP Determines total RCS to secondary leak rate is not less than 1 gallon per minute (1440 GPD) - SRO Moves forward in procedure to step 8 and orders a plant shutdown. - SRO Notifies Higher Supervision. Crew Performs parts A AND E3 of ATT-16.1, ATTACHMENT SGTL. - SRO Dispatches an A 0 to perform T-35H, Nuclear House Heating Steam To Boiler Steam Supply Change Over R. E. Ginna Nuclear Plant Page 7 of 17 Revision 00

Appendix D Required Operator Actions Op-Test No.: 1 Scenario No.: 1 Event No.: 3 Event

Description:

(- T=l8) S/G B Tube Leak of = 10 gpm Indications: 0 PRZR Level slowly lowering 0 PRZR Pressure slowly lowering PPCS, computer point SGTL Indicated

         .15 rising or in alarm Position SRO                   Requests RP obtain the following samples:

0 RCS boron 0 RCS activity (ITS 3.4.16) ATC Monitors PRZR Pressure - TRENDING TO 2235 PSlG IN AUTO or Control PRZR pressure by one of the following: 0 431K in MANUAL 0 Manual control of PRZR heaters and sprays SRO IF PRZR pressure can NOT be controlled manually, THEN refers to AP-PRZR.1, Abnormal Pressurizer Pressure. BOP Monitors MFW Regulating Valves - RESTORING S/G LEVEL TO 52% IN AUTO or perform the following: 0 Place affected S/G(s) MFW regulating valve in MANUAL 0 Restore S/Glevel to 52% SRO IF S/G level can NOT be controlled manually, THEN refer to AP-FW.1, Abnormal MFW Pump Flow Or NPSH. End of Event R. E. Ginna Nuclear Plant Page 8 of 17 Revision 00

I Appendix D Required Operator Actions Form E S - C Z Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Event

Description:

(- T=22) Provides ATC and BOP with instructions for down power. - Verifies Rods in AUTO or adjusts rods in MANUAL to maintain Tavg to Tref. - Reduces turbine load irn Auto as follows: 0 Places Turbine EH Control in OPER PAN., IMP PRESS IN 0 Selects rate of 3%/min on thumbwheel 0 Reduces the setter to zero. 0 Depresses the GO button. - Initiates boration (-2-4 gal/% load reduction) at flowrate directed by SRO. - Places PRZR backup heaters switch to ON. - Transfers 4160V Auxiliary loads from #11 Transformer. 0 Places Bus 12A - BUS 11A TIE SYNCHROSCOPEto ON. 0 Closes BUS l i ! A - BUS 11A TIE 4160V. 0 Places BUS 12'A - BUS 11A TIE SYNCHROSCOPEto OFF. Opens BUS 11A NORMAL FEED 4160V. Places BUS 1I B - BUS 12B TIE SYNCHROSCOPEto ON. Closes BUS 11B - BUS 12B TIE 4160V. Places BUS 1 1B - BUS 12B TIE SYNCHROSCOPE to OFF. Opens BUS 11B NORMAL FEED 4160V. 0 Requests an A 0 reset alarms L-20 AND L-28, locally in the Relay Room Addition - Monitors Tavg 545-57ggFand verifies proper operation of Rods in Auto or controls rods manually. - Adjusts Boric Acid addition rate as necessary to: Maintain contra11 rods above insertion limits Match Tavg and Tref 0 Compensate for Xenon - End of Event R. E. Ginna Nuclear Plant Page 9 of 17 Revision 00

Appendix D Required Operator Actions Form ES-9-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 5 Event

Description:

(- T=28) RCP B High Vibration Indications 0 AA-18, Reactor Coolant Pump Vibration Alert 0 AA-26, Reactor Coolant Pump Vibration Danger Id reports to SRO. - I at the RCP VIBRATION panel: 0 Determines which pump is causing the alarm MENT SOUND MONITOR for abnormal noise from the mp's instrumentation for abnormal indications. Shaft and Motor Casinlg. - SRO/ATC Performs the following if pump shaft vibration level rises to 20 mils or greater OR motor casing vibration rises to 5 mils or greater: Trips the reactor WHEN all E-0 Immediate Actions done, THEN trip the affected RCF(s) GOto E-0, REACTOR TRIP OR SAFETY INJECTION. - R. E. Ginna Nuclear Plant Page 10 of 17 Revision 00

Appendix D Required Operator Actions Form ES-D-2 - Op-Test No.: 1 Scenario No.: 1 Event No.: 6 Event

Description:

Main Steam Line Break Downstream of MSlVs which ciiuses S/G tube leak to rise to a 400 GPM tube rupturf? in S/G B. MSlV B fails to close automatically or manually from the MCB, SI Pump C fails to Auto Start on SI Signal, RHR Pump A trips on auto start. Indications: 0 PRZR Level lowering e PRZR Pressure lowering e RCS Tcold, Thot, Tavg lowering 0 S/G pressures lowering 0 Steam flow noise 0 R-32 rising or in alarm

         -15 rising Position                                 Applicants Actions or Behavior                       -

ATC/BOP Recognizes indications and alarms and reports to SRO. - ATC Verifies Reactor Tripped 0 At least one set of reactor trip breakers open 0 Neutron flux lowering 0 MRPl indicates all rods on bottom - BOP Verifies all turbine stop valves closed BOP Verifies Buses 14, 16, 1 ;7, and 18 > 440V ATC Checks if SI has been actuated by verifying SI annunciators and SI sequencing started both trains. SRO Enters E-0, Reactor Trip or Safety Injection and re-verifies Immediate Actions before continuing with supplemental actions. ATC Verifies Containment Spray not required by verifying Containment pressure < 28 psig and annunciator A-27, Containment Spray is not lit. BOP Performs ATT-27.0, Attachment Automatic Action Verification Manually starts SI Pumps C (Critical Task CT E-0-4)) Reports RHR Pump A tripped ATC Verifies MDAFW pump El running with flow to B S/G and running at e 230 gpm. Verifies TDAFW Pump running by verifying MOV-3505A and MOV-3504A open. ATC Verifies AFW flow to both S/Gs or manually aligns TDAFW Pump to S/G A. R. E. Ginna Nuclear Plant Page 11 of 17 Revision 00

Appendix D Required Oilerator Actions Form ES-D-2 )p-Test No.: 1 Scenario No.: 1 Event No.: 6 Event

Description:

Aain Steam Line Break Downstream of MSlVs which causes S/G tube leak to rise to a 400 GPM tube ruptlire I S/G B. MSlV B fails to close automatically or manually from the MCB, SI Pump C fails to Auto Start on Si jignal, RHR Pump A trips on auto start. ndications: 0 PRZR Level lowering 0 PRZR Pressure lowering 0 RCS Tcold, Thot, Tavg lowering 0 S/G pressures lowering 0 Steam flow noise 0 R-32 rising or in alarm O F 15 rising Time Position ._ ATC Monitors Heat Sink 0 Verifies S/G NR levels > 7% or verifies total AFW 200 gpm 0 Isolates AFW flow to any S/G >50% NR 0 Controls S/G levels 7-50% NR - ATC Determines TDAFW Pump should not be stopped. - ATC Verifies annunciators A-7(A-15), CCW Pump lA(1B) Return HI Temp or LOW Flow are not lit. - ATC Monitors RCS Tavg 0 Stops dumping steam (Steam Dumps or ARV) 0 Ensures Reheater steam supply valves closed 0 Limits feed flow to maintain one S/G > 7% NR 0 Closes MSlVs (Notes MSlV B failed and reports to SRO may have been done during ATT. 27-0) - ATC Verifies both PORVs closed, Auxiliary Spray valve AOV-296 closed, and wt-3n RCS pressure c 2260 psig verifies both Spray Valves are closed - Verifies RCP Trip Criteria 0 Verifies an RCP running 0 Verifies at least two SI Pumps running 0 Verifies RCS pressure- maximum S/G pressure >210 psid or secures RCP 1A - ATC Verifies S/G pressures and determines S/G 16 is not intact. - SRO Transitions to E-2, Faulted Steam Generator Isolation - BOP Attempts to manually close MSlV B. - SRO Dispatches A 0 with locked valve key to locally close faulted S/G B MSlV - R. E. Ginna Nuclear Plant Page 12 of 17 Revision 00

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 6 Event

Description:

Main Steam Line Break Downstream of MSlVs which causes S/G tube leak to rise to a 400 GPM tube ruptxe in S/G B. MSlV B fails to close automatically or manuiAly from the MCB, SI Pump C fails to Auto Start on SI Signal, RHR Pump A trips on auto start. Indications: 0 PRZR Level lowering PRZR Pressure lowering 0 RCS Tcold, Thot, Tavg lowering 0 SIG pressures lowering 0 Steam flow noise 0 R-32rising or in alarm Position Applicants Actions or Behavior S R O B 0P Checks If Any SIG Secondary Side Is Intact: Checks pressure in SIG A - STABLE OR RISING OR

          ~

0 Checks pressure in SIG 6 - STABLE OR RISING - CREW Checks Faulted SIG Status: Faulted SIG pressure - LOWERING IN AN UNCONTROLLED MANNER OR 0 Faulted S/G - COMPLETELY DEPRESSURIZED IF both S/G pressures stable or rising, THEN searches for initiating break ard goes to Step 6 . Main steam lines 0 Main feed lines 0 SIG blowdown system 0 Sample systerri R. E. Ginna Nuclear Plant Page 13 of 17 Revision 00

Appendix D Required OpeFrator Act ions Form ES-D--5 - Event

Description:

Main Steam Line Break Downstream of MSlVs which causes S/G tube leak to rise to a 400 GPM tube rupture in S/G 6. MSlV B fails to close automatically or manually from the MCB, SI Pump C fails to Auto Start on SI Signal, RHR Pump A trips on auto start. PRZR Level lowering PRZR Pressure lowering RCS Tcold, Thot, Tavg lowering 0 S/G pressures lowering 0 Steam flow noise R-32 rising or in alarm 15 rising Position BOP Isolates Feed Flow To Faulted S/G. Closes or verifies closed the following valves: MDAFW puimp B discharge valve, MOV-4008 0 MFW regulating valve and bypass valve to S/G B, HCV-476 and HCV-481 MFW isolatiion valve to S/G B, AOV-3994 0 BOTH MDANV pump crosstie valves - MOV-4000A and MOV-40008 0 SAFW pump discharge valve to S/G B, MOV-9704B 0 Pull stops faulted S/G MDANV pump B Closes TDAFW flow control valve to S/G 6 - AOV-4298. SRO/BOP Isolates Steam Flow From Faulted S/G: Verifies faulted WG ARV CLOSED - S/G B, AOV-3410 Closes faulted S/G TDAFW pump steam supply valve and place in PULL STOP S/G B, MOV-3504A 0 Verifies faulted S/G blowdown and sample valves CLOSED - S/GB, AOV-5737 and AOV-5736 0 Dispatches A 0 to complete faulted S/G isolation (Refer to ATT-10.0, ATTACHMENT IFAULTED S/G) SRO/BOP Monitors Intact S/G Levels: 0 Maintains total feed flow greater than 200 gpm until narrow range levt greater than 7% in S/G A. Controls feed flow to maintain narrow rang level in S/G A between 17% and 50% IF narrow range level in any S/G continues to rise in an uncontrolled manner THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, R. E. Ginna Nuclear Plant Page 14 of 17 Revision 00

Amendix D Reauired ODerator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 6 Event

Description:

Main Steam Line Break Downstream of MSlVs which causes S/G tube leak to rise to a 400 GPM tube ruptlr'e in S/G B. MSlV B fails to close automatically or manually from the MCB, SI Pump C fails to Auto Start on SI Signal, RHR Pump A trips on auto start. Indications: 0 PRZR Level lowering I 0 PRZR Pressure lowering 1 0 RCS Tcold, Thot, Tavg lowering 1 S/G pressures lowering 0 Steam flow noise 1 0 R-32 rising or in alarm Applicant's Actions or Behavior Checks Secondary Radiation Levels - NORMAL 0 Steam line radiation monitors (R-31 and R-32) 0 Air ejector radiation monitor (R-15) 0 S/G blowdown radiation monitor (R-19) Requests RP sample S/Gs for activity - Transitions to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1. - Monitors RCP Trip Criteria Stops RCP 1A IF AT LEAST TWO SI pumps RUNNING and RCS pressure minus maximum S/G pressure is LESS THAN 210 psid. - Identifies Ruptured S/G is S/G B by: 0 Unexpected rise in S/G narrow range level 0 High radiation indication on main steam line B radiation monitor R Isolates Flow From S/G B (Critical Task CT E-3--A) 0 Adjusts ruptured S/G ARV controller to 1050 psig in AUTO and checks ruptured S/G A I W CLOSED when ruptured S/G pressure less than 1050 psig 0 Closes TDAFW pump steam supply valve MOV-3504A and places in PULL STOP Ensures S/G B blowdown valve, AOV-5737 - CLOSED - Completes Ruptured S/G B Isolation: (Critical Task CT E-3--A) 0 Ensures MSlV 8,AOV-3516 Closed 0 Dispatches A 0 to complete ruptured S/G isolation for S/G B (Refer to ATT-16.0, ATTACHMENT RUPTURED S/G part A) R. E. Ginna Nuclear Plant Page 15 of 17 Revision 00

Appendix D Required OpeIrator Actions Form ES-D-2 - Op-Test No.: 1 Scenario No.: 1 Event No.: 6 Event

Description:

Main Steam Line Break Downstream of MSlVs which causes S/G tube leak to rise to a 400 GPM tube rupturt in S/G 6. MSIV B fails to close automatically or manually from the MCB, SI Pump C fails to Auto Start on SI Signal, RHR Pump A trips on auto start. Indications: 0 PRZR Level lowering 0 PRZR Pressure lowering 0 RCS Tcold, Thot, Tavg lowering 0 S/G pressures lowering 0 Steam flow noise 0 R-32 rising or in alarm Position - BOP Checks Ruptured S/G Level: (Critical Task CT E-3-A) Ensures S/G B Narrow range level - GREATER THAN 7% o IF ruptured S/G NOT faulted and Narrow Range level is c 71 ' 0, THEN performs the following: Maintains feed flow to ruptured S/G until level greater than 7%

                                                       . Continues with Step 6. WHEN ruptured S/G level greater than 7%, THEN does Steps 5b through e.

Ensures MDAFW pump discharge valve to S/G B, MOV-4008 closed. Ensures MDANV pump B in Pull Stop Ensures TDAFVV pump flow control valve to S/G 6, AOV-4298 closea 0 Ensures MDAFVV pump crosstie valves closed o MOV-40100A o MOV-401006 - BOP Verifies Ruptured S/G Isolated: 0 Checks MSlV B, AOV-3516 closed 0 Checks TDAFW pump steam supply from S/G B MOV-3504A isolated 0 Verifies S/G 6 pressure - GREATER THAN 300 PSlG BOP Establishes Condenser Steam Dump Pressure Control: 0 Determines Intact MSlV A is closed and adjusts S/G ARV controllers to maintain S/G ,4pressure in AUTO and goes to Step 8. ATC/BOP Resets SI R. E. Ginna Nuclear Plant Page 16 of 17 Revision 00

Appendix D Required Oberator Act ions Form ES-0-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 6 Event

Description:

Main Steam Line Break Downstream of MSlVs which causes S/G tube leak to rise to a 400 GPM tube rupttire in S/G 8.MSlV B fails to close automatically or manually from the MCB, SI Pump C fails to Auto Start on S Signal, RHR Pump A trips on auto start. I Indications: 0 PRZR Level lowering 0 PRZR Pressure lowering 0 RCS Tcold, Thot, Tavg lowering 0 S/G pressures lowering Steam flow noise 0 R-32 rising or in alarm 15 rising Position _c Crew Initiates RCS Cooldown: 0 Determines required core exit temperature for S/G B pressure 0 Manually initiates dumping steam from intact S/G at maximum rate using S/G A ARV. 0 WHEN core exit T/Cs temperatures less than required, THEN stops RCS cooldown and stabilizes core exit T/Cs less than required temperature - End of Scenario - SRO Perform Emergency Plan Classification for final event Expected EAL: Alert, :3.1.2, RCS Leakage > 46 gpm Start Time: Stop Time: EAL: - R. E. Ginna Nuclear Plant Page 17 of 17 Revision 00

Facilty: R. E. Ginna Scenario No.: - 2 Op-Test No.: 1 Scenario

Description:

Shortly after the crew takes the watch, Pressurizer Master Pressure Controller PC-431K output fails high. Thi i causes the PRZR Spray Valves to open and Pressurizer heater to de-energize. The crew should take manuat control of the Spray Valve controllers and close the Spray Valves and implement AP-PRZR.1. The SRO should refer to TS 3.4.1 and COLR Section 2.lO.and enter TS 3.4.1 if Pressurizer Pressure drops below 2205 psig. SRO refers to TR 3.4.3 with PC-431K in Manual. PORV-431C is still OPERABLE but the ATWS mitigating system is not. After the crew addresses the Pressurizer Pressure Controller failure and restores RCS pressure, a 20 gpm RCS leak occurs in Hot Leg B. The crew should implement AP-RCS.1, Reactor Coolant Leak. The SRO should review TS 3.4.13 and enter Condition A and Action A.l. While implementing AP-RCS.1, Heater Drain Tank Pump 1A trips on overload. The crew should implement AP-FW.1, Abnormal MFW Pump Flow or NPSH. The crew should perform a down power to 70% due to the trip of Heater Drain Tank Pump 1A to ensure sufficient NPSH for the Main Feedwater Pumps. After the crew satisfies the reactivity manipulation requirements, LT-463 fails high forcing the S/G 1A MFW Reg Vlv controller HCV-466 to manual requiring manual (controlof S/G 1A level and implement AP-RN.1. The SRO should review Technical Specifications 3.3.1 and 3.3.2 and determine there are no actions for 2 instruments 00s on the same S/G and enters TS 3.0.3. The SRO should review TS 3.3.3 and enter Condition D and Action D.l. After the crew restores S/G 1A level to = 52% NR, the RCS leak rises requiring a reactor trip and entry into E-0, Reactor Trip or Safety Injection. The RHR Pumps, MDAFW Pump B, and the TDAFW Pump fail to start automatically, requiring the crew to start the pumps manually when SI occurs. MOV-313, Seal or Excess Letdown Return Isolation Valve, fails to close on a CI, requiring the crew to close MOV-313from the Main Control Board. The crew should transition to E-1, Loss olf Reactor or Secondary Coolant. During the injection phase RWST Level Channel 921 fails low. The crew should determine that an instrument failure has occurrec and continue in E-1 vice transition to ES-1.3, Transfer to Cold Leg Recirculation. The scenario may be secured when the crew reaches the decision point to transition to ES-1.3 or return to step 17 of E-1 based on the operable RWST level. Revision 00 Page 2 of 21

Facilty: R. E. Ginna Scenario No.: -. 2 Op-Test No.: 1 CRITICAL TASKS CT E-0--H Task: Manually start at least one RHR pump before traiisition out of E-0. Cues: SI Actuated RCS press e RHR pump shutoff head No RHR pump running Indication: Manipulation of controls to start at least one RHR pump. Feedback: Indication that a RHR Pump(s) are running 9 Breaker Status Lights 9 RHR Flow CT E-0--0 Task: Initiate CNMT isolation such that at least one valve is closed in Seal or Excess Letdown Return Line which is passing fluid out of containment. Cues: LOCA in CNMT and SI actuated and CNMT isolation valve MOV-313, Seal and Excess Letdown Return Isolation Valve, is not closed 9 Status lights indicate valve is open Indication: Manipulation of controls to isolate the flow path by closing MOV-313 before the end of the scenario. Feedback: Valve status lights indicate MOV-313 is closed. Revision 00 Page 3 of 21

Facilty: R. E. Ginna Scenario No.: 2 Op-Test No.: 1 Scenario Timeline: Event Time Delay Ramp Number (Min) Key Event HH:MM:SS HH:MM:SS Final NIA AT LOAD SGNOlB N/A oo:oo:oo oo:oo:oo 0 SIG LEVEL CHANNEL FAILURE: LT-461(1) 1 2 PZR04 1 oo:oo:oo 00:02:00 100 PRESSURIZER MASTER PRESSURE CONTROLLER FAILURE 2 ***(- 12) RCS02C 3 oo:oo:oo oo:oo:oo 20 RCS LEAK INTO CNMT: LOOP B HOT LEG (UNREC) 3 ***(- 19) HTR02A 5 oo:oo:oo oo:oo:oo 1 HEATER DRAIN TANK 1A TRIP - 4 ***(- 26) N/A N/A NIA N/A NIA POWER REDUCTION TO 70% 5 ***(- 32) SGNO1D 7 oo:oo:oo 00:03:00 70 S/G LEVEL CHANNEL FAILURE: LT-463 (IV) - 6 ***(- 38) RCS03C 9 oo:oo:oo 0O:Ol :oo 1 RCS DBA BREAK IN CNMT : LOOP B HOT LEG (UNREC) - 6 AT LOAD RPS07E NIA oo:oo:oo oo:oo:oo 1 AUTO FAIL: A RHR PUMP - 6 AT LOAD RPSO7F N/A oo:oo:oo oo:oo:oo 1 AUTO FAIL: B RHR PUMP - 6 AT LOAD RPS07L N/A oo:oo:oo oo:oo:oo 1 AUTO FAIL: B MDAFW PUMP - 6 AT LOAD RPS07M N/A oo:oo:oo oo:oo:oo 1 AUTO FAIL: TDAFW STM SUP MOV-3504A - 6 AT LOAD RPSO7N NIA oo:oo:oo oo:oo:oo 1 AUTO FAIL: TDAFW STM SUP MOV-3505A - 6 AT LOAD MIS05D N/A oo:oo:oo 0O:OO:OO ISOL SIGNAL ONLY (0) CNMT IS0 VLV FAILURE: MOV 313 (SEAL WTR RTN VLV) -

                ***                              oo:oo:oo 6                          A-SISO1        11                oo:oo:oo             ON (1)

B8: RWST HI-LO LEVEL 95 % 28 -

                ***                              oo:oo:oo 6                         IND-SIS44       11                oo:oo:oo                0 SI-LI-921 METER SIGNAL REFUELING VVATER STORAGE TANK LEVEL                    -

• • • Events initiated on cue from NRC Lead Examiner Estimated Time: 60 Minutes Revision 00 Page 4 of 21

Appendix D Required Operat or Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 1 Event

Description:

(T=2 minutes) Pressurizer Pressure Master Controller PC-431K output fails high Indications: i 0 Maximum output on PRZR PRES CONTROLLER 431K 1 0 Maximum output on PRESSURIZER SPRAY CONTROLLER PCV-431A and PCV-4318 0 Heater output at minimum 0 Both Spray Valves PCV-431A and B indicate open

tual RCS pressure wering (PI-429, PI-430, PI-431, and PI-449) -

Position Applicant's Actions or Behavior - ATC Recognizes indications and alarms and reports to SRO. - SRO/ATC Takes manual control of Pressurizer Pressure Control in one of the following ways: Places PRZR PRES CONTROLLER 431K in manual and lowers output using the Manual potentiometer to close PCV-431A and PC"- 431 B (z50%). 0 Places both PRESSURIZER SPRAY CONTROLLER PCV-431A ard PCV-431B in manual and closes Spray Valves by lowering output to 0 using the Manual potentiometer on each controller. - Enters AP-PRZR.1, Abnormal Pressurizer Pressure - Checks PRZR Pressure Channels 0 Reports PRZFl 1A-1 through 4, (PI-429, PI-430, PI-431, and PI-449% are reading approximately equal and trending down - Checks Reactor Power Stable 0 Reports that POWER RANGE 1 through 4 FLUX (NI-416 through hi-44B) are stable - Checks PRZR Pressure between 2235 and 2000 psig and not dropping uncontrollably. - Verifies PRZR PROPORTIONAL HEATERS Breaker closed (Red Light On) and energizes PRZR EIACKUP HEATERS by taking C/S to ON. - Verifies Normal PRZR Spray Valves closed by verifying PRESSURIZER SPRAY VALVE, AOV-431A and AOV-431 B status lights (Green Light On, R.?d Light Off). - Verifies PRZR PRESS CONTROLLER 431 K demand is less than 50% and lowers demand to restore PRZR pressure to 2235 psig. - Refers to TS 3.4.1 and COLR Section 2.10. Enters TS 3.4.1 if Pressurizer Pressure drops below 2205 psig. Refers to TR 3.4.3 with PC-431K in Manual. PORV-431C is still OPERABLE but the ATWS mitigating system is not. - End of Event R. E. Ginna Nuclear Plant Page 5 of 21 Revision 00

Appendix D Required Operator Actions Form ES-D Op-Test No.: 1 Scenario No.: 2 Event No.: 2 Event

Description:

(- T=12 minutes) RCS Leak Hot Leg B Indications: 0 Slowly lowering PRZR level 0 Slowly lowering RCS Pressure 0 Annunciator F-14, Charging Pump Speed 0 Rising indications or alarms on R-1OA, R-11, or Fi-12

          'CS alarm, R-11 Ra     ! of Change Position                               Applicant's Actions or Behavior ATC                    Recognizes indications aind alarms and reports to SRO.

SRO Enters AP-RCS.1, Reactor Coolant Leak ATC Monitors PRZR Level and starts additional charging pumps, or raises charging pump speed as necessary to stabilize PRZR level. ATC Check VCT Makeup System 0 Monitors VCT Level on LI-112 0 Ensures RMW Mode Selector in AUTO 0 Verifies RMW Armed red light lit 0 Verifies Makeup occurring between 20% and 30% on LI-112 ATC Determines Leakage is in Containment By: 0 Rising readings on any of the following Rad Monitors: R-2, R-7, R-10A, R-11, R-12 0 CNMT Sump A pump run frequency rises SRO Directs RP to sample Containment for entry and informs A 0 to be prepared to enter CNMT to search for leaks SRO Continues to eliminate otlher sources of leakage by dispatching A 0 to AUX BLDG for CVCS leaks with RP support. ATC Checks CCW System for leaks by: 0 Monitors CCW Surge Tank Level on LI-618 - - 50% and stable 0 Monitor CCW Radiation Monitor R-17 reading not rising and not in alarm ATC Checks Letdown indications Normal: 0 - Letdown Line Flow on LI-134 40 gpm Low Press Ltdn Pressure on PI-135 or PCV-135 250 psig Low Press Ltdn Pressure PCV-135 35% open (- 65% controller output) R. E. Ginna Nuclear Plant Page 6 of 21 Revision 00

Appendix D Required Operator Actions Form ES-0-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 2 Event

Description:

(- T=12 minutes) RCS Leak Hot Leg B Indications: 0 Slowly lowering PRZR level 0 Slowly lowering RCS Pressure 0 Annunciator F-14, Charging Pump Speed 0 Rising indications or alarms on R-1OA, R-11, or R-12

          'CS alarm, R-11 Rz     1 of Change                                                                - 1 Position                                  Applicant's Actions or Behavior                      -

ATC/BOP Checks Charging indications Normal Seal Injection Flows > 6 gpm and stable on FI 115A and FI-l16A 0 Labyrinth Seal D/Ps PI-131 and PI-124 > 15 inches and approximately equal 0 Charging Pump Discharge pressure PI-128 > RCS pressure PI-429, PI-430, PI-431, Pl-449 - ATC Checks AUX BLDG rad levels Normal by verifying no rise indication or alarrns on R-4, R-9, R-lOB, FI-13, or R-14 - ATC/BOP Checks PRT indications Normal 0 PRT Level 61%-84% on Ll-442 0 PRT Pressure -1.5 psig and stable on PI-440A and PI-440B 0 PRT Temperature at CNMT Ambient Temperature and Stable on TJ-

              ~

SROIATC Check S/Gs for leakage 0 Air Ejector rad monitors no rise or alarms on R-15, R-47, and R-48 0 S/G Blowdowin rad monitor R no rise or alarms Steam line rad monitors R-31 and R-32 no rise or alarms 0 No rise in S/G sample activities - ATC Checks SI Accumulator levels stable (not rising) on Ll-938 and Ll-934 - ATC Checks RCP Seal Leakoff flows stable and within normal operating range of Fig-4.0, Figure RCP S'eal Leakoff on F-175 to F-178 (Seal Leakoff Rec0rdo.a Crew Checks leak is not into RCDT by checking PPCS PID L1003 and RCS DailL Leakage Log - ATC Verifies Normal Letdown in service ATC Verifies RCS pressure and PRZR level are trending back to normal steady state values 2235 psig and 56% R. E. Ginna Nuclear Plant Page 7 of 21 Revision 00

Appendix D Required Operator Actions Form ES-D-2-- 3p-Test No.: 1 Scenario No.: 2 Event No.: 2 Event

Description:

(- T=12 minutes) RCS Leak Hot Leg B Indications: 0 Slowly lowering PRZR level 0 Slowly lowering RCS Pressure 0 Annunciator F-14, Charging Pump Speed 0 Rising indications or alarms on R-1OA, R-11, or Fl-12 plicants Actions or Behavior in AUTO 0 Determines Pressurizer Press Controller 431 K needs to stay in MANUAL 0 Pressurizer Spra>yValve Controllers PCV-43 A and PCV-43 B in AUTO (may be in manual from 431 K failure) 0 PRZR Proportional Heater Breaker Closed 0 PRZR Backup Heater C/S in AUTO (may be in ON after 431 K failure) 0 One Charging Pump Controller in AUTO itors - Refers to AR procedures e and determines TS 3.4.13 is not being met enters

                                                         .l.

R. E. Ginna Nuclear Plant Page 8 of 21 Revision 00

Appendix D Required Operator Act ions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 3 Event

Description:

(- T=19 minutes) Heater Drain Tank Pump 1A Trips 0 G-8, 4 KV Breaker Overload 0 G-25, Motor Off Ctr Sect Pumps Except Maini & Aux Feed Pumps 0 H-14, Condensate Hdr Lo Pressure 245 psi 0 H-17, Feed Pump Net Positive Suction Head 0 H-29, Fdwtr Htr and Drain Tank Level Hi-Lo or Presep Tk Hi Level 0 H-30, Condensate Bypass Valve Open 0 Condensate B Auto Starts (Green Flag on pump C/S w/Red Run indication) 0 Condensate Bypass Valve AOV-3959 indicatles open 0 Feed Pump 1A and 1B Suction Pressure indicators lower and then recover after Condensate pum!) starts and Condensate Bypass Valve opens IS and alarms and reports to SRO -

                                                   )wer turbine load to reduce reactor power e 100%      -

1 BOP I I Commences turbine load reduction - ormal MFW Pump Flow or NPSH - 0 Verifies Power > 50% IFW Pumps Running - 0 Checks MFW Flow greater than Steam Flow in both S/Gs stabilizing or trending back to 52% NR - ondensate Pumps running - ily one Heater Drain Pump running. - eduction to 70% is required (May determine to use AT-R. E. Ginna Nuclear Plant Page 9 of 21 Revision 00

Appendix D Required Operator Actions Form ES-D Op-Test No.: 1 Scenario No.: 2 Event No.: 4 Event

Description:

(- T=26 minutes) Applicants Actions or Behavior Provides ATC and BOP with instructions for down power. I I ATC I Verifies Rods in AUTO or adjusts rods in MANUAL to maintain Tavg to Tref. Reduces turbine load in Auto as follows: 0 Places Turbine EH Control in OPER PAN., IMP PRESS IN 0 Selects rate on thumbwheel per SRO instructions. 0 Reduces the load setter per SRO instructions. 0 Depresses the GlO button. Initiates a boration of 2-4 gals/% (60-120 gals) at a rate per SRO instructions. Adjusts Turbine load rate, Boric Acid flow rate, and/or Rods to maintain Tavg to Tref. Verifies Turbine Load reduction stops when Load = Setter End of Event R. E. Ginna Nuclear Plant Page 10 of 21 Revision 00

Amendix D Reauired OrBerator Actions Form ES-0-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 5 Event

Description:

(- T=32 minutes) S/G A Level LT-463 fails high Indications: 0 Ll-463 rising 0 S/G A FRV controller in manual u s - Recognizes indications and alarms and reports to SRO. ~ Takes action to stabilize S/G A level by adjusting S/G A FRV controller in manual to restore S/GI Level to 52% on Ll-462. Continues to control S/G A level in manual during the down power to 70%. SRO Enters ER-INST.l and goes to step 4.8. - SRO Determines that one channel is already tripped per ER-INST.l, that tripping another channel will initiate a reactor trip, and does NOT give an order to continue with the ER procedure attachment for tripping the second bistable. ~ ATC/BOP If the SRO does not recognize the effect of tripping second channel and gives the order to complete the attachment for tripping the channel, at least one RO candidate recognizes the effect and communicates it to the SRO. Checks ITS 0 Reviews Technical Specifications 3.3.1 and 3.3.2 and determines there are no actions for 2 instruments inoperable on the same S/G and enters TS 3.0.3. 0 The SRO shoiuld review TS 3.3.3 and enter Condition D and Action End of Event __p R. E. Ginna Nuclear Plant Page 11 of 21 Revision 00

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Event

Description:

(- T=38 minutes) Large Break LOCA Hot Leg B, RHR Pumps A and B lail to auto start on SI Signal, MDAFW Pump B and tt-e TDAFW Pump fail to auto start, MOV-313 fails to close on CI, RWST Level Channel 921 Fails Low during Injection Phase Indications: 0 PRZR and RCS Pressures dropping Rapidly 0 PRZR level dropping rapidly 0 Reactor trip on Low PRZR Pressure 0 Low RCS Pressure SI 0 R-11 rising and in alarm 0 R-29 and R-30, Containment Hi Range Rad Monitors rising 0 Containment Pressure rising rapidly 0 S/G Pressures relativt Istable - Applicant's Actions or Behavior 'W Recognizes alarms and indications and reports to SRO - Verifies Reactor Tripped One set of reactor trip breakers open 0 Neutron flux lowering 0 MRPl indicates all rods on bottom - Verifies all turbine stop valves closed - Verifies Buses 14, 16,17, and 18 =. 440V - Checks if SI has been actuated by verifying SI annunciators and SI sequencing started both trains. - Enters E-0, Reactor Trip or Safety Injection and re-verifies Immediate Actior s before continuing with.supplemental actions. - Verifies Containment Spray required by verifying Containment pressure > 213 psig and annunciator A-27,Containment Spray is lit and verifies Containmerit Spray is initiated. - BOP Perform ATT-27.0, Attachment Automatic Action Verification Manually start:; RHR Pumps A and B (Critical Task CT E-0-H) Manually starts TDAFW Pump and MDAFW Pump B Manually close! MOV-313, Seal or Excess Ltdn Return lsol Vlv (Critical Task CT E-0-0) 1 ATC Verifies MDAFW pump B running with flow to B S/G at c 230 gpm. Verifies TDAFW Pump running by verifying MOV-3505A and MOV-3504A open. - I ATC Verifies AFW flow to both S/Gs or manually aligns TDAFW Pump to S/G A. R. E. Ginna Nuclear Plant Page 12 of 21 Revision 00

Appendix D Required Operator Actions Form ES-D lp-Test No.: 1 Scenario No.: 2 Event No.: 6

vent

Description:

(- T=38 minutes) .arge Break LOCA Hot Leg B, RHR Pumps A and 6 fail to auto start on SI Signal, MDAFW Pump B and the 7DAFW Pump fail to auto start, MOV-313 fails to close or1 CI, RWST Level Channel 921 Fails Low during njection Phase ndications: 0 PRZR and RCS Pressures dropping Rapidly 0 PRZR level dropping rapidly 0 Reactor trip on Low PRZR Pressure 0 Low RCS Pressure SI 0 R-11 rising and in alarm 0 R-29 and R-30, Containment Hi Range Rad Monitors rising 0 Containment Pressure rising rapidly G Pressures relativt 1 stable P Time Position Ap ATC Monitors Heat Sink 0 Verifies S/G NR levels > 25% or verifies total AFW 200 gpm 0 Isolates AFW flow to any S/G > 50% NR 0 Controls S/G levels 25-50% NR SRO Determines TDAFW Purrip should not be stopped. ATC Verifies annunciators A-7(A-15), CCW Pump lA(1B) Return HI Temp or Low Flow are not lit. ATC Monitors RCS Tavg 0 Stops dumping steam (Steam Dumps or ARVs) 0 Ensures Reheater steam supply valves closed 0 Maintains total Feed flow at 200-230 gpm until one S/G is >25% NR 0 Limits feed flow to maintain one S/G > 25% NR 0 Closes MSlVs if (cooldowncontinues ATC Verifies both PORVs closed, Auxiliary Spray valve AOV-296 closed, and wher RCS pressure e 2260 psig both Spray Valves are closed ATC Verifies RCP Trip Criteria 0 Verifies both RCIPs running 0 Verifies at least two SI Pimps running 0 Verifies RCS pressure- maximum S/G pressure c240 psid and secures RCP 1A and RCP 1B by taking C/S to STOP BOP Determines both S/Gs are intact 0 Both S/G Pressuires stable or rising and > 110 psig R. E. Ginna Nuclear Plant Page 13 of 21 Revision 00

Amendix D Reauired Ot>eristorActions Form ES-D Op-Test No.: 1 Scenario No.: 2 Event No. : 6 Event

Description:

(- T=38 minutes) Large Break LOCA Hot Leg B, RHR Pumps A and B fail to auto start on SI Signal, MDAFW Pump B and the TDAFW Pump fail to auto start, MOV-313 fails to close on CI, RWST Level Channel 921 Fails Low during Injection Phase Indications: 0 PRZR and RCS Pressures dropping Rapidly 0 PRZR level dropping rapidly 0 Reactor trip on Low PRZR Pressure 0 Low RCS Pressure SI 0 R-11 rising and in alarm 0 R-29 and R-30, Containment Hi Range Rad Monitors rising 0 Containment Pressure rising rapidly I stable A p p l i c a n t s Actions or Behavior Checks that S/G Tubes Are Intact: 0 Verifies air ejectolr radiation monitors (R-15, R-47, or R-48) are not rising or in alarm 0 Verifies S/G blowdown radiation monitor (R-19) are not rising or in alarm 0 Verifies steam line radiation monitors (R-31 and R-32) are not rising or in alarm Checks If RCS Is Intact: 0 Reports CNMT area radiation monitors R-2, R-7, R-29, R-30 are rising and in alarm Reports CNMT pressure is rising and > 0.5 PSlG 0 Reports CNMT slump B level is rising and > 8 inches 0 Reports CNMT sump A level rising 0 Reports Annunciator C-19, CONTAINMENTSUMPA HI LEVEL is lit Transitions to E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1. Instructs Crew review foldout page criteria and to monitor Critical Safety Functions. Review Red Path Summaries, determines RCS Integrity red path criteria is met and transitions to FR-P.1, Response To Imminent Pressurized Thermal Shock Condition. Verifies RCS pressure is c 465 psig and RHR flow is > 475 gpm Returns to step in effect in E-1, Loss Of Reactor Or Secondary Coolant. Determines RCPs secured and goes to Step 2 Re-verifies S/Gs are intact and goes to step 3 R. E. Ginna Nuclear Plant Page 14 of 21 Revision 00

Appendix D Required Oberator Actions Form ES-0-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Event

Description:

(- T=38 minutes) Large Break LOCA Hot Leg 6, RHR Pumps A and B ifail to auto start on SI Signal, MDAFW Pump B and tt e TDAFW Pump fail to auto start, MOV-313 fails to clos8eon CI, RWST Level Channel 921 Fails Low during Injection Phase Indications: 0 PRZR and RCS Pressures dropping Rapidly 0 PRZR level dropping rapidly 0 Reactor trip on Low PRZR Pressure 0 Low RCS Pressure SI 0 R-11 rising and in alarm 0 R-29 and R-30, Containment Hi Range Rad Fdonitors rising I 0 Containment Pressure rising rapidly G Pressures relativf / stable ___i Position _ I BOP Monitors S/G and B levels: 0 Maintains total AFW flow greater that 200 gpm until at one SIG level is

                                           > 25% NR 0    Controls AFW flow to maintain SIG A and B NR levels between 25 /o-50%                                                                -

SRO/ATC Monitors Secondary Rad Levels are not rising on steam line rad monitors F-31 and R-32 and requests RP sample S/Gs for activity - ATC/BOP Verifies PORV block valves are energized, both PORVs are closed and at least one PORV block valve is open - ATC Resets SI by depressling SI Reset Pushbutton ~ ATC Resets CI by depressing CI Reset Pushbutton and verifies A-26, CNMT Isolation is not lit BOP Verifies at least 2 SW pumps are running - SRO Dispatches A 0 to establish normal shutdown alignment per ATT-17.0, ATTACHMENT SD-1 - BOP Establishes IA to CNlLBT Verifies Busses 13 and 15 powered through normal feeder breakers from offsite. Should also check bus voltage > 440V. Verifies Turbine Building SW isolation valves MOV-4613IMOV-467O and MOV-4614/MOV-4664 are open Verifies adequate air compressors are operating or starts additional air compressors Verifies IA pressure > 60 psig and stable or rising Resets both train XY relays for AOV-5392 and verifies AOV-5392 R. E. Ginna Nuclear Plant Page 15 of 21 Revision 00

Appendix D Required Operator Actions Form ES-KJT Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Event

Description:

(- T=38 minutes) Large Break LOCA Hot Leg 8, RHR Pumps A and B fail to auto start on SI Signal, MDAFW Pump B and the TDAFW Pump fail to auto start, MOV-313 fails to close on CI, RWST Level Channel 921 Fails Low during Injection Phase Indications: PRZR and RCS Pressures dropping Rapidly PRZR level dropping rapidly 0 Reactor trip on Low PRZR Pressure Low RCS Pressure SI 0 R-11 rising and in alarm R-29 and R-30, Containment Hi Range Rad Monitors rising 1 Containment Pressure rising rapidly Applicants Actions or Behavior /P Checks Bus 14 and 16 normal feeder breakers closed - Establishes Charging Flow 0 Checks CCW Flow has not been lost to either RCP thermal barrier (MOV-817, AOY-814, AOV-815, AOV-754A, and AOV-754B open w-th a CCW Pump running) and verifies #1 seal and verifies RCP 1A and 1B #1 Seal Outlet Temperature (TI-181 and TI-182) are 5 235*F 0 Ensures HCV-142, Charging Flow to Regen HX is open, controller demand is 0% Verifies Charging Pump suction is aligned to the RWST o Verifies LCV-l12B, Emerg Makeup RWST to Charging Puma is open and LCV-1128, VCT Outlet Vlv is closed I Starts charging pumps and adjusts Charging flow - t be terminated by verifying RCS pressure is < 1825 Pump may be secured - ump by placing the CS Pump C/S in PULL STOP and e is stable or lowering - failed RWST instrument to SRO. T level is > 28% and continues in E-1. R. E. Ginna Nuclear Plant Page 16 of 21 Revision 00

Appendix D Required Operator Actions Form ES-D-;!-

                                                                     ~

3p-Test No.: 1 Scenario No.: 2 Event No.: 6

vent

Description:

(- T=38 minutes) -arge Break LOCA Hot Leg B, RHR Pumps A and B fail lo auto start on SI Signal, MDAFW Pump B and the rDAFW Pump fail to auto start, MOV-313 fails to close oin CI, RWST Level Channel 921 Fails Low during njection Phase ndications: 0 PRZR and RCS Pressures dropping Rapidly 0 PRZR level dropping rapidly 0 Reactor trip on Low PRZR Pressure 0 Low RCS Pressure SI 0 R-11 rising and in alarm 0 R-29 and R-30, Containment Hi Range Rad Monitors rising 0 Containment Pressure rising rapidly

     ~

G Pressures relativc I stable Time ~ Position Applicants Actions or Behavior BOP Checks if Emergency D/Gs should be stopped 0 Verifies EDG A and B output breakers open 0 Verifies Bus 14,13us 16, Bus 17, and Bus 18 Voltages > 440 V and individual bus normal feeder breakers are closed 0 Stops both EDGs using ATT 8.1, Attachment DIG Stop o Verify D/G A Bus 14 supply breaker is OPEN. o Verify D/G A Bus 18 supply breaker is OPEN. o Using D/G A GOVERNOR, adjust D/G A speed to return frequency to 60 Hz. o Using D/tG A AUTO VOLTAGE CONTROL rheostat adjust D/C A voltage to 480 volts. o Place D/G A CONTROL switch to STOP AND immediately depress ID/G A VOLTAGE SHUTDOWN button until voltage decays to zero. o After -60 seconds, perform the following: Depress D/G A FIELD RESET

                                                       .. Depress D/G A RESET
                                                           \/erify D/G A AIR START SOLENOID lights - LIT
                                                        .  \/erify DIG A START RELAY lights - LIT R. E. Ginna Nuclear Plant                                                             Page 17 of 21 Revision 00

Appendix D Required Ocerator Actions Form ES-eJY - Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Event

Description:

(- T=38 minutes) Large Break LOCA Hot Leg B, RHR Pumps A and B fail to auto start on SI Signal, MDAFW Pump B and the TDARN Pump fail to auto start, MOV-313 fails to close on CI, RWST Level Channel 921 Fails Low during Injection Phase Indications: 0 PRZR and RCS Pressures dropping Rapidly 0 PRZR level dropping rapidly 0 Reactor trip on Low PRZR Pressure 0 Low RCS Pressure SI 0 R-11 rising and in alarm 0 R-29 and R-30, Containment Hi Range Rad Monitors rising I 0 Containment Pressure rising rapidly 2 Pressures relativl I stable - Position Applicants Actions or Behavior - BOP o Verify DIG B Bus 16 supply breaker is OPEN. o Verify DIG B Bus 17 supply breaker is OPEN. o Using DIG B GOVERNOR, adjust DIG B speed to return frequency to 60 Hz. o Using DIG B AUTO VOLTAGE CONTROL rheostat adjust GIG B voltage to 480 volts. o Place DIG B CONTROL switch to STOP AND immediately depress DIG B VOLTAGE SHUTDOWN button until voltage decays to zero. After -160 seconds, perform the following: o

                                                       . Depress DIG B FIELD RESET
                                                       . Depress DIG B RESET 9

Verify DIG 6 AIR START SOLENOID lights - LIT 9 Verify DIG B START RELAY lights - LIT - ATCIBOP Verifies CNMT Sump Recirculation Capability: 0 Checks RHR aind Support systems: o At least one recirculation flow path, including required power supplies, from Sump B and back to RCS available per ATT-14.5, ATTACHMENT RHR SYSTEM o At least one SW pump available. o At leasit one CCW pump available. o At least one CCW Hx available. Checks at least 2 SW pumps available 0 Dispatches A 0 to check AUX BLDG sub-basement for RHR system leakage (AUX BLDG sub-basement key may be required) R. E. Ginna Nuclear Plant Page 18 of 21 Revision 00

I Appendix D Required Operator Actions Form ES-D-2_ . Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Event

Description:

(- T=38 minutes) Large Break LOCA Hot Leg B, RHR Pumps A and B fail to auto start on SI Signal, MDAFW Pump B and the TDAFW Pump fail to auto start, MOV-313 fails to close on CI, RWST Level Channel 921 Fails Low during Injection Phase Indications: 0 PRZR and RCS Pressures dropping Rapidly 0 PRZR level dropping rapidly 0 Reactor trip on Low PRZR Pressure 0 Low RCS Pressure SI 0 R-11 rising and in alarm 0 R-29 and R-30, Containment Hi Range Rad Monitors rising 0 Containment Pressure rising rapidly

                                            -            M                                                   .-

Evaluates Plant Status: Checks auxiliary building radiation - NORMAL o Plant vlent iodine (R-106) o Plant vent particulate (R-13) o Plant vent gas (R-14) o CCW liquid monitor (R-17) o LTDN line monitor (R-9) o CHG pump room (R-4) 0 WHEN TSC is manned, THEN request evaluation of sampling requirements. o RCS boron o RCS activity o CNMT hydrogen o CNMT sump boron o CNMTSumppH 0 Verifies adequate Rx head cooling: o Verifies at least one control rod shroud fan - RUNNING o Verifies one Rx compartment cooling fan - RUNNING - SRO Verifies that RCS cooldown is not required 0 RCS Pressure :;465 psig 0 RHR Pump flow > 475 gpm R. E. Ginna Nuclear Plant Page 19 of 21 Revision 00

Appendix D Required Operator Actions Form E S - D - f-Op-Test No.: 1 Scenario No.: 2 E.vent No.: 6 Event

Description:

(- T=38 minutes) Large Break LOCA Hot Leg B, RHR Pumps A and B fail to auto start on SI Signal, MDAFW Pump B and the T D A W Pump fail to auto start, MOV-313 fails to close on CI, RWST Level Channel 921 Fails Low during Injection Phase Indications: PRZR and RCS Pressures dropping Rapidly PRZR level dropping rapidly Reactor trip on Low PRZR Pressure ~ Low RCS Pressure si R-11 rising and in alarm R-29 and R-30, Containment Hi Range Rad Monitors rising

~

Containment Pressure rising rapidly I

             'G Pressures relativt I stable Position                                 Applicant's Actions or Behavior BOP                  Establishes Adequate SW Flow 0   Verifies at least 2 SW pumps running Verifies MOV-4615/MOV-4734 Open 0   Verifies MOV-4616/MOV-4735 open 0   Verifies 5000-6000 gpm SW flow equally divided between CCW HX A and B or Dispatches SO to adjust flow to required value ATC                  Establishes flow to RHR HXs Starts Backup CCW Pump Opens CCW Valves to RHR HX A and B (MOV-738A and B)

SRO Checks If Transfer To Cold Leg Recirculation Is Required: 0 If RWST level > 28% returns to Step 17 0 If RWST level c 28%, transitions to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1 End of Scenario SRO Perform Emergency Plan Classification for final event Expected EAL: Site Area Emergency, 3.1.3, RVLlS can not be maintained

                                   < 77% with no RCPs running Start Time:                  -

Stop Time: .- EAL: R. E. Ginna Nuclear Plant Page 20 of 21 Revision 00

Appendix D Required Operator Actions Form ES-D.2 R. E. Ginna Nuclear Plant Page 21 of 21 Revision 00

Facilty: R. E. Ginna Scenario No.: _. 3 Op-Test No.: 1 Scenario

Description:

After the crew takes the watch they will initiate a power ascension to 100% power using 0-5.2, Load Ascension. When the crew has met reactivity manipulation requirements, or at the lead examiners discretion, Loop A Tco,,, TE-401B Fails Low with Rod Block failed. The crew should take manual control of RODS, stabilize the plant, and implement AP-RCC.1, Continuous Rod WithdrawaMnsertion and ER-INST.1, Reactor Protection Bistable Defeat after Instrumentation Loop Failure. The SRO should apply TS 3.3.1 Condition D, Action D.l and 3.3.2 Condition F, Action F.l. After the affected bistables have been tripped, containment Recirc Fan A will trip. The crew should start the standby Containment Recirc Fan. The SRO should apply TS 3.6.6 Condition D, Action D.l. After addressing the Containment Recirc Fan failure, LT-112, VCT Level instrument will fail. The crew should realign the LCV-112A to the VCT and refer to ER-CVCS.1, Reactor Makeup Control Malfunction for guidance on manual makeup. After the VCT level failure has been addressed, Feedwater Control Valve B, FCV-476, controller fails high. The crew should take manual control of FCV-476 and restore S/G B level to 52% NR. The crew should implement AP-FW.1, Abnormal MFW Pump Flow or NPSH. After the crew restores S/G B level, a Main Steam Line E3reak occurs downstream of the MSIVs. SI fails to actuate automatically and the MSlVs can not be closed from the control room or locally. The crew should manually initiate SI,attempt to close the MSlVs and implement the following procedures: E-0, Reactor Trip or Safety Injection, 0 E-2, Faulted Steam Generator Isolation, ECA-2.1, Uncontrolled Depressurization of Both Steam Generators and 0 FR-P.l, Response to Imminent Pressurized Thermal Shock Condition The scenario will end after the crew has taken action to minimize the RCS cooldown and stops SI and RHR pumps. Revision 00 Page 2 of 16

Facilty: R. E. Ginna Scenario No.: -. 3 Op-Test No.: 1 CRITICAL TASKS CT E-0--D Task: Manually initiate at least one train of SI before transition to E-1 Cues: RCS pressure e SI setpoint or CNMT pressure > SI setpoint and SI component failed to start Indication: Manipulation of control to activate at least one train of SI Feedback: SI components start, SI flow delivery to RCS CT FR-P.1-B Task: Control the AFW flow rate in order to minimize RCS cooldown rate before an extreme (red path) challenge develops to the Integrity CSF. Cues: RCS cold leg cooldown rate > 100°F in last 60 mlinutes. and Cold leg temperature on either cold leg is e 285°F and AFW flow rate to faulted S/G is > 50 gpm Indication: Manipulation of control to throttle AFW flow to both faulted S/Gto 50 gpm (within the ability to control the AFW control valves) Feedback: RCS cooldown slow and eventually stops. CT FR-P.1-A Task: Terminate SI flow so that if the challenge to integrity CSF is: Severe, an extreme challenge is prevented 0 Extreme, SI is terminated by the end of the scenario. Cues: Indication of a red or orange challenge to the integrity CSFST

                 -and Indication that SI termination criteria are met and AFW flow rate to faulted S/G is > 50 gpm Indication: Manipulation of control to terminate SI flow (SI and RHR pumps secured)

Feedback: SI and RHR flow rate zero. Revision 00 Page 3 of 16

Facilty: R. E. Ginna Scenario No.: -. 3 Op-Test No.: 1 Scenario Timeline: Event Time Delay Ramp Number (Min) Key Event . HH:MM:SS HH:MM:SS Final 1 0 NIA N/A oo:oo:oo oo:oo:oo NIA Power Ascension 2 ***(--15) RCSl 1C 1 oo:oo:oo oo:oo:oo 0 RTD Failure: LP A Cold TE-401B (TT-401)l AUTO 2 At Load ROD12 N/A oo:oo:oo oo:oo:oo ONLY (0) Rod Stop Failure 3 ***(- 22) OVR-MISO6D 3 oo:oo:oo 0O:OO:OO True (NULL) CP-HS-CR1A Stop Signal Containment Recirculation Fan No. 1A 3 *** OVR-MIS06B 3 oo:oo:oo oo:oo:oo ON CP-HS-CR1A White Lamp CONTAINMENT 13ECIRCULATION FAN NO 1A 3 A-EDS16 3 oo:oo:oo oo:oo:oo ON (1) J-9: Safeguard Breaker Trip 4 ***(--27) CVC1OA 5 oo:oo:oo 00:00:30 100 VCT Level Transmitter Failure: LT-112 5 ***( -32) FDW07C 7 oo:oo:oo 00:02:00 100 6 FRV FCV-476 - Manual Available 6 ***(-37) STM03 9 oo:oo:oo 0O:Ol :oo 4000000 Steamline Break Outside CNMT Downstream of MSlVs 6 At Load STM05A N/A oo:oo:oo oo:oo:oo 100 Main Steam Isolation Valve Failure: VLV 351 7 6 At Load STM05B N/A oo:oo:oo oo:oo:oo 100 Main Steam Isolation Valve Failure: VLV 3516 MANUAL 6 At Load SIS02A N/A oo:oo:oo oo:oo:oo AVAIL (0) SIS Train A Failure to Actuate MANUAL 6 At Load SIS02B N/A oo:oo:oo oo:oo:oo AVAIL (0) SIS Train B Failure to Actuate N/A At Load SGNO1B N/A oo:oo:oo oo:oo:oo 0 S/G Level Channel Failure: LT-461(I)

• • • Events initiated on cue from NRC Lead Examiner Estimated Time: 65 Minutes Revision 00 Page 4 of 16

Appendix D Required Operator Actions Form ES-0-2 -

ension Position SRO Provides instructions 1.0 ATC and BOP to continue raising power.

ATC Initiates Dilution per SRO instructions using 0-3.1 BOP Raises turbine load in Auto as follows: 0 Places Turbine EH Control in OPER PAN., IMP PRESS IN 0 Selects rate on thumbwheel per SRO instructions. 0 Raises the load setter SRO instructions. 0 Depresses the GO button. SRO Directs the BOP to StiWi Condensate Booster Pumps. BOP Adjusts TRIM VLV CCINTROL, AOV 9508D AOV-9508G, controller output AUTO UNTIL the first Trim Valve starts to open. BOP Places HOWELL LEVEL LC-107, Controller in the MAN position BOP Places the standby Condensate Pump control switch in the PULL STOP position. BOP Places one CONDENSATE BOOSTER PUMP switch to the RUN position i observes CONDENSATE BOOSTER PUMP selected to RUN starts. BOP Raises TRIM VLV CONTROL, AOV 9508D AOV-9508G controller setpoint approximately 375 psig. BOP Places a second CONIDENSATE BOOSTER PUMP switch to the RUN pos WHEN CONDENSATE TRIM CONTROL AOV, valve 9508G, is less than 2 OPEN. BOP Places the third CONDENSATE BOOSTER PUMP switch to the AUTO position. BOP Adjusts TRIM VLV CONTROL, AOV 9508D AOV-9508G, as necessary dur power ascension to maximize the MFWP available NPSH. Monitors PPCS Point NPAVMFPA and NPAVMFPB BOP Places HOWELL LEVEL, LC-107, controller in AUTO with controller setpc at approximately 24 inches. BOP Places the standby Condensate Pump control switch in AUTO. BOP/ATC Adjusts dilution flow rate and/ or Turbine Load rate as necessary to maintai Tavg at Tref. End of Event R. E. Ginna Nuclear Plant Page 5 of 16 Revision 00

Appendix D Required Operator Act ions Form ES-D-2 - 3p-Test No.: 1 Scenario No.: 3 Event No.: 2 Event

Description:

(- T=15 min) Loop A TcoldTE-401B Fails Low, Rod Block failed Indications: e F-4, PRESSURIZER LEVEL DEVIATION -5 NORMAL +5 e F-7, RCS LOOP A LO TAVG e F-14, CHARGING PUMP SPEED e F-15, RCS TAVG DEV 4°F e F-16, TAVG-TREF DEVIATION +/- 5°F 0 F-24, RCS AVG AT DEVIATION 3°F 0 LOOP 1A-1 DTEMP, Tl-4058 reads significantly higher than TI-406B, Tl-4078, and TI-408B e LOOP A-1 TAVG, TI-401 reads significantly lower than TI-402, TI-403, and TI-404 e Charging Pump A speed signal goes to minimum and charging flow lowers e PRZR Backup Heaters energized (Red light on)(PRZR Level setpoint lowers) e

                                                                                                          -4 Applicants Actions or Behavior                      /s BOP/ATC             Recognizes indication:; and alarms and reports to SRO.                        -

SRO Enters AP-RCC.1, Coritinuous Rod WithdrawaVlnsertion c BOP Checks turbine load - !STABLE - ATC Places Rod Control in Manual and verifies rod motion stops. - ATC Verifies Tavg between 547and 57gQF c ATC Restores Tavg to Tref using Rod insertion in Manual or Boration SRO/ATC Determines Tavg TI-401 failed - SRO Enters ER-INST.1, Reactor Protection Bistable Defeat After Instrumentation Loop Failure. - ATC Places Charging Pump A Speed Controller in MANUAL and adjusts charginq pump speeds to stabilize PRZR level. - SRO Refers to ITS LCOs 3.l.5and 3.1.6 to determine actual rod insertion limits. - SRO Determines that hot leg streaming does not apply. - SRO Directs BOP to perform Tavg 401/Delta T 405 Attachment. - +&+- BOP/ATC Verifies Rod Control selector switch in MANUAL. - I I BOP/ATC I I Verifies Charging Pump speed controllers in MANUAL.. - In the RIL INSERTION LIMIT rack, Places T/405E DELTA T DEFEAT switch tc LOOP A UNIT 2. - In the STEAM DUMP rack, Places the TAVG DEFEAT switch T/401A to LOQF A UNIT I . R. E. Ginna Nuclear Plant Page 6 of 16 Revision 00

Appendix D Required Operator Actions Form ES-D-2 3p-Test No.: 1 Scenario No.: 3 Event No.: 2

vent

Description:

(- T=15 min) -oop A TcoldTE-401B Fails Low, Rod Block failed ndications: F-4, PRESSURIZER LEVEL DEVIATION -5 NORMAL +5 F-7, RCS LOOP A LO TAVG F-14, CHARGING PUMP SPEED F-15, RCS TAVG DEV 4°F F-16, TAVG-TREF DEVIATION +/- 5°F F-24, RCS AVG AT DEVIATION 3°F 0 LOOP 1A-1 DTEMP, TI-4056 reads significantly higher than TI-406B, TI-407B, and TI-408B 0 LOOP A-1 TAVG, TI-401 reads significantly lower than TI-402, TI-403, and TI-404 0 Charging Pump A speed signal goes to minimum and charging flow lowers 0 PRZR Backup Heaters energized (Red light on) (PRZR Level setpoint lowers) 0 ( utward Rod Motion ( od Block circuit is inoperable) Time Position Applicant's Actions or Behavior BOP In the (RED) R-1 PROTECTION CHANNEL 1 rack 0 Places 401 LOOP A-1 HIGH T'AVG Bistable Proving Switch in DEFEAT (UP) Verifies 401 LOOP A-1 HIGH T'AVG Bistable Proving Light ON 0 Places 401 LOOP A-1 LOW T'AVG Bistable Proving Switch in DEFEAT (UP) 0 Verifies 401 LOOP A-1LOW T'AVG Bistable Proving Light OFF Places 405 LOOP A-1 OVERTEMP TRIP Bistable Proving Switch in DEFEAT (UP) 0 Verifies 405 LOlOP A-1 OVERTEMP TRIP Bistable Proving Light OFF Places 405 LOOP A-1 OVERPOWER TRIP Bistable Proving Switch DEFEAT (UP) 0 Verifies 405 LOOP A-1 OVERPOWER TRIP Bistable Proving Light OFF BOP/ATC Verifies proper bistable status lights and associated annunciators lit. G-9, RCS LOOP A HI TAVG 579" 0 TC401A Lo Tavlg 0 F-7, RCS LOOP A LO TAVG 545'F 0 TC405AOPAT F-32, RCS OPA'T CHANNEL ALERT 0 TC405COTAT 0 F-23, RCS OTAT CHANNEL ALERT R. E. Ginna Nuclear Plant Page 7 of 16 Revision 00

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 2 Event

Description:

(- T=15 min) Loop A TcoldTE-401B Fails Low, Rod Block failed Indications: 0 F-4, PRESSURIZER LEVEL DEVIATION -5 NORMAL +5 F-7, RCS LOOP A LO TAVG F-14, CHARGING PUMP SPEED 0 F-15, RCS TAVG DEV 4°F 0 F-16, TAVG-TREF DEVIATION +/- 5°F ~ 0 F-24, RCS AVG AT DEVIATION 3°F 0 LOOP 1A-1 DTEMP, TI-405B reads significantly higher than TI-406B, TI-407B, and TI-408B 0 LOOP A-1 TAVG, TI-401 reads significantly lower than TI-402, TI-403, and TI-404 0 Charging Pump A speed signal goes to minimum and charging flow lowers PRZR Backup Heaters energized (Red light on) (PRZR Level setpoint lowers) itward Rod Motion ( od Block circuit is inoperable) Position Applicants Actions or Behavior BOP Deletes 401/405 from the PPCS by performing the following: 0 Selects Grouip Update display 0 Selects List Sierver Groups 0 Selects 401-4.05 from the pick list 0 Turns OFF scan processing, then clicks the Set Scan Processing button 0 Answers promlpts ATC Restores following systems to automatic operation as necessary: 0 PRZR level control 0 Rod control SRO Checks the following ITS Sections for LCOs: 0 Section 3.3.1, Table 3.3.1-1, Functions 5 and 6 0 Section 3.3.2, Table 3.3.2-1, Function 4d Determines the followiing LCO Actions are applicable 3.3.1 Condition D Action D.l - Place associated channel in trip within 6 hrs 3.3.2, Condition F, Action F.l - Place associated channel in trip within 6 hrs End of Event R. E. Ginna Nuclear Plant Page 8 of 16 Revision 00

ADDendix D Reauired 0Derator Actions Form ES-D-2! Op-Test No.: 1 Scenario No.: 3 Event No.: 3 Event

Description:

(- T=22 min) Containment Recirculation Fan Cooler A Trips Indications: Red status light for Containment Recirc Fan A OFF Green and White status lights for Containment Recirc Fan ON J-9, Safeguard Breaker Tripped annunciator ON I I Time I Position I I Applicants Actions or Behavior - I ATC/BOP I I Recognizes alarms and indications and reports to SRO. I BOP/SRO Refers to AR-J-9, Safeguard Breaker Trip SRO Notifies A 0 to investigate and report findings to the Control Room. I SRO I I Determines reset or reclalsure of a breaker should not be attempted. I SRO Notifies Electricians or Work Control Center SRO Refer to ITS LCO 3.6.6 and determines Condition D, Action D.l should be entered. n R. E. Ginna Nuclear Plant Page 9 of 16 Revision 00

Appendix D Required Operator Actions Form ES-D-2-- Scenario No.: 3 Event No.: 4 Event

Description:

(- T=27 min) VCT Level Transmitter LT-112 Fails High 0 LI-112, VCT Level indicates 100% 0 VCT OR HOLDUP TK DIVERT VALVE LCV-112A indicates diverted to Holdup Tanks rot Room for manual makeup requirement when LI-EACTOR MAKEUP CONTROL MALFUNCTION, for uired per ER-CVCS.l R. E. Ginna Nuclear Plant Page 10 of 16 Revision 00

Amendix D Reauired Oberator Act ions Form ES-D-2

         ~  ~    ~

Op-Test No.: 1 Scenario No.: 3 Event No.: 5 Event

Description:

(- T=32 min) Feedwater Control Valve B, FCV-476, Auto Controller Fails High, w/Manual Control available 0 FCV-476 Controller output at 100% S/G B NR and WR Levels rising d indications and reports to SRO. - heck of LI-471, Ll-472, and Ll-473 - Takes manual control of FCV-476 and reduces output to restore level in S/G B wmal MFW Pump Flow or NPSH. - ients and determines 2 MFW Pumps required and cj continues to monitor S/G B level and adjust FCV-476 R. E. Ginna Nuclear Plant Page 11 of 16 Revision 00

Appendix D Required Operator Act ions Form ES-D Op-Test No.: 1 Scenario No.: 3 Event No.: 6 Event

Description:

(- T=37 min) Main Steam line break downstream of MSIVs, both MSlVs fail to close automatically or from the MCB, SI fails to actuate when setpoint reached Indications: 0 Gross Generator Load lowering 0 RCS Tcold, Thot, and Tavg lowering 0 Reactor Power rising 0 RCS and PRZR Pressure lowering 0 PRZR level lowering 0 S/G Pressures lowering Flow rising eam Flow Noise Position d d ATC/BOP Recognizes indications and alarms and reports to SRO. ATC Verifies Reactor Tripped 0 At least one set of reactor trip breakers open 0 Neutron flux lowering 0 MRPl indicates all rods on bottom BOP Verifies all turbine stop valves closed BOP Verifies Buses 14, 16, 17, and 18 > 440V ATC Checks if SI has been actuated by verifying SI annunciators and SI sequencing started both trains. Determines SI is not actuated and Manually actuates SI and CI by depressing SI and CI Manual Pushbuttons. (Critical Task CT E-O--D) SRO Enters E-0, Reactor Trip or Safety Injection and re-verifies Immediate Actions before continuing with supplemental actions. ATC Verifies Containment Spr,ay not required by verifying Containment pressure e 28 psig and annunciator 14-27, Containment Spray is not lit. BOP Perform ATT-27.0, Attachment Automatic Action Verification ATC Verifies MDAFW pump A and B running with flow to S/Gs and running at < 230 gpm. ATC Monitors Heat Sink 0 Verifies S/G NR levels > 7% or verifies total AFW 200 gpm Isolates AFW flow to any S/G > 50% NR 0 Controls S/G levels 7-50% NR ATC Secures TDAFW Pump by placing switches in Pull Stop for TDAFW Pump steam isolation valves MOV-3504A and MOV 3505A. R. E. Ginna Nuclear Plant Page 12 of 16 Revision 00

Appendix D Required Operator Actions Form ES-D Op-Test No.: 1 Scenario No.: 3 Elient No.: 6 Event

Description:

(- T=37 min) Main Steam line break downstream of MSIVs, both MSlVs fail to close automatically or from the MCB, SI fails to actuate when setpoint reached Indications: 0 Gross Generator Load lowering 0 RCS Tcold, Thot, and Tavg lowering 0 Reactor Power rising 0 RCS and PRZR Pressure lowering 0 PRZR level lowering 0 S/G Pressures lowering Flow rising eam Flow Noise Position Applicant's Actions or Behavior ATC Verifies annunciators A-7(A-15), CCW Pump lA(1B) Return HI Temp or Low Flow are not lit. ATC Monitors RCS Tavg and determines RCS temperatures is lowering 0 Stops dumping steam (Steam Dumps or ARVs) Ensures Reheater steam supply valves closed 0 Limits feed flow to 200-230 gpm (- 100 gpm per S/G) 0 Attempts to close both MSlVs (Notes MSlV A and B failed and reports to SRO) ATC Verifies both PORVs closed, Auxiliary Spray valve AOV-296 closed, and when RCS pressure e 2260 psig both Spray Valves are closed ATC Verifies RCP Trip Criteria 0 Verifies an RCP running 0 Verifies at least two SI Pumps running 0 Verifies RCS pressure-maximumS/G pressure >210 psid or secures RCP 1Aand 1B ATC Verifies S/G pressures and determines neither S/G is intact. SRO Transitions to E-2, Faulted Steam Generator Isolation BOP Attempts to manually close MSlV A and B. SRO Dispatches A 0 with locked valve key to locally closed faulted S/G A and B MSlVs if not done previously R. E. Ginna Nuclear Plant Page 13 of 16 Revision 00

Appendix D Required Operator Actions Form ES-0-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 6 Event

Description:

(- T=37 min) Main Steam line break downstream of MSIVs, both MSlVs fail to close automatically or from the MCB, SI frds to actuate when setpoint reached Indications: 0 Gross Generator Load lowering 0 RCS Tcold, Thot, and Tavg lowering 0 Reactor Power rising 0 RCS and PRZR Pressure lowering 0 PRZR level lowering 0 S/G Pressures lowering Flow rising eam Flow Noise P Position Applicants Actions or Behavior SRO/BOP Check If Any S/G Secondary Side Is Intact: 0 Check pressure in S/G A - STABLE OR RISING OR 0 Check pressure in S/G B - STABLE OR RISING IF both S/G pressures; lowering in an uncontrolled manner, THEN go to ECA-2.1, UNCONTROLLEID DEPRESSURIZATIONOF BOTH STEAM GENERATORS - SRO Determines Orange or Red path criteria for Integrity (PTS) are met and transitions to FR-P.1 (May occur directly from E-2) - SRO/ATC Determines RCS Pressure is > 250 psig - SRO/BOP Determines cold Leg temperatures are lowering and attempts to stop RCS Cooldown Verifies ARVs AOV-3411 and AOV-3410 are closed by verifying Green status light only 0 May attempt to close MSlVs again from MCB (valves will not close A 0 can not access valves due to location of steam break) 0 Verifies 0% valve position indicated on HCV-466, HCV-480, HCV-476, and HCV-481 0 Ensures MFW Pumps A and E3 C/Ss in PULL STOP 0 Ensures only green status lights for Reheater Steam Supply valves AOV-3425, 3426, 3427 and 3428 lit. If not positions cam on REHEATER STEAM SUPPLY CONTROLLER, TC-3040 to allow arm to go to center of cam. 0 Verifies S/G Fressure is c Condensate Pressure and Places Condensate Fump A, B, and C C/Ss in PULL STOP 0 Verifies Total AFW flow > 200 gpm (- 100 gpm per S/G) R. E. Ginna Nuclear Plant Page 14 of 16 Revision 00

Appendix D Required Operator Actions Form ES-0-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 6 Event

Description:

(- T=37 min) Main Steam line break downstream of MSIVs, both MSlVs fail to close automatically or from the MCB, SI fails to actuate when setpoint reached Indications: 0 Gross Generator Load lowering 0 RCS Tcold, Thot, and Tavg lowering 0 Reactor Power rising 0 RCS and PRZR Pressure lowering 0 PRZR level lowering i 0 S/G Pressures lowering I 0 Steam Flow rising Applicants Actions or Behavior rom faulted S/Gs 0 Verifies TDAFW Pump Steam Supply Valves MOV-3504A and MOV-3505A are in PULL STOP and closed Adjusts AFW flow to S/G A and B to 50 gpm each. (Critical Task CT-Checks PRZR PORV lblock valves have power available and at least one is ATC Ensures one PORV open if RCS pressure is > 2335 psig and closes when k s s than 2335 psig. - ATC Determines SI Pumps B and C running - SRO/ATC Checks if SI can be reset 0 Determines RCS subcooling > 50QFusing core exit T/Cs and Fig. 1 0 - Figure Min Sulbcooling 0 Verifies RVLIS; Fluid Fracture > 84% - ATC Verifies SI Reset - ATC Stops SI pumps B and C and RHR pumps A and B by placing C/Ss in STOF and returning to AUTO. (Critical Task CT FR-P.1-A) - End of Scenario R. E. Ginna Nuclear Plant Page 15 of 16 Revision 00

Appendix D Required Operator Act ions Form ES-13-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 6 Event

Description:

(- T=37 min) Main Steam line break downstream of MSIVs, both MSIVs fail to close automatically or from the MCB, SI fails to actuate when setpoint reached Indications: 0 Gross Generator Load lowering 0 RCS Tcold, Thot, and Tavg lowering 0 Reactor Power rising 0 RCS and PRZR Pressure lowering 0 PRZR level lowering 0 S/G Pressures lowering 1 0 Steam FIOW rising Applicants Actions or Behavior - Perform Emergency Plan Classification for final event Expected EAL: Alert, 1.4.1, Red Path on F-0.4 Integrity Start Time: Stop Time: .- R. E. Ginna Nuclear Plant Page 16 of 16 Revision 00

Facilty: R. E. Ginna Scenario No.: _. 4 Op-Test No.: 1 Scenario

Description:

Shortly after taking the watch, a fuel failure will occur. The crew should enter AP-RCS.3, High Reactor Coolant Activity and EPlP 1-13, Local radiation Emergency and place the 60 GPM letdown orifice in service, in accordance with S-3.2P, Swapping Letdown Orifice. The SRO should refer to TS 3.4.16 and enter appropriate actions after sample results are obtained. After the 60 gpm letdown orifice is in service, Steam Generator A Pressure Transmitter PT-469 fails low. The crew should implement ER-INST.1, Reactor Protection Bistable Defeat after Instrumentation Loop Failure, and place appropriate bistables in the tripped condition. The SRO should refer to TS 3.3.1, 3.3.2, and 3.3.3 and enter the appropriate actions. After ER-INST.l has been addressed, TT-130, Letdown xion-regenerative heat exchanger outlet temperature instrument fails low resulting in TCV-130 closing and letdown temperature rising. TCV-145 will bypass the ion exchangers due to high letdown temperature. The crew should implement AR-A-12, NON-REGEN HX LETDOWN OUT HI TEMP 145", take manual control of TCV-130, return letdown temperature to normal, and ensure ion exchangers are placed in service. After letdown temperature is returned to normal, MFW Pump B develops an oil leak requiring a down power to 50% power. The crew should enter AP-FW.1, Abnormal MFW Pump Flow or NPSH and perform the down power per AP-TURB.5, Rapid Load Reduction. After the reactivity manipulation is satisfied, the Condensate header ruptures resulting in a loss of normal feedwater. The crew should perform a manual trip. The manual trip pushbutton fails and the crew should trip the reactor by opening the Bus 13 and Bus 15 normal feeder breakers. The crew should note at some point that auto failure has occurred as evidenced by S/G level:; e 17% trip setpoint and reactor trip breakers still closed. The TDAFW pump fails to auto start and Bus 16 trips resulting in loss of the only operable Motor Driven AFW pump. The BOP should manually start the TDAFW Pump if not rut still running from AP-FW.l. The crew should perform the immediate actions of E-0, Fleactor Trip or Safety injection, and transition to ES-0.1, Reactor Trip Response. After at least one S/G NR level exceeds 7%, the TDAFW pump fails and the crew should note a red path condition on the Heat Sink Critical Safety Function after both S/G levels fall below 7% NR and transition to FR-H.l. The crew should start the Standby AFW Pumps and restore level in at least one S/G to > 7% Narrow Range. After performing the required actions of FR-H.l, the crew should transition back to ES-0.1. The scenario can be terminated after this transition. Revision 00 Page 2 of 18

Facilty: R. E. Ginna Scenario No.: 4 Op-Test No.: 1 CRITICAL TASKS CT E-0--A - Manually trip the reactor from the control room before both SG levels lower to 50 inches wide range level. Cues: D panel alarm annunciates ;and no reactor trip occurs Indication: Reactor trip and bypass breakers open OR Rod drive MG set breakers open Feedback: MRPl indicates rod on bottom Neutron flux lowering CT FR-H.l--E - Establish 200 gpm feed flow before both SG wide range levels lower below 50 inches. Cues: Indication of Rx trip and Indication that RCS pressure is > SG pressure and Total FW flow to SG is e 200 gpm Indication: Align and start the C SBAFW pump and establish > 200 gpm flow as indicated on flow indicator Fl-40848. Feedback: C SBAFW indicates running Flow is indicated to the SG(s) at > 200 gpm Steam generator level(s) rise:; Revision 00 Page 3 of 18

Facilty: R. E. Ginna Scenario No.: 4 Op-Test No.: 1 Scenario Timeline: Event Time Delay Ramp Number (Min) Key Everit HH: MM:SS HH:MM:SS Final - NIA NIA SGNOlB NIA oo:oo:oo oo:oo:oo 0 S/G LEVEL CHANNEL FAILURE: LT-461(I) - 1 1 RCS16 1 oo:oo:oo oo:oo:oo 60 FUEL CLADDING FAILURE - 2 ***(- 11) SGN03B 3 oo:oo:oo 00:00:00 0 SIG PRESSURE CHANNEL FAILURE: PT-469 (11) - 3 ***( -20) cvco5 5 oo:oo:oo oo:oo:oo 0 LOSS OF CCW TO NON-REGENERATIVE LETDOWN HX - 4 ***( -28) FDW04B 7 oo:oo:oo 00:10:00 100 FEEDWATER PUMP 1B LUBE OIL SYSTEM FAILURE - 5 (-30) N/A NIA oo:oo:oo oo:oo:oo NIA DOWN POWER TO 50% - 6 ***(- 35) CND08 9 oo:oo:oo 0O:Ol :oo 20000 CONDENSATE PIPE BREAK - 6 ***( -37) EDS04B 9 oo:oo:oo oo:oo:oo 1 LOSS OF EMERGENCY BUS: 480V BUS 16 - 6 Load RPS07M NIA oo:oo:oo oo:oo:oo 1 AUTO FAIL: TDAFW STM SUP MOV-3504A 6 Load RPS07N NIA oo:oo:oo oo:oo:oo 1 AUTO FAIL: TDAFW STM SUP MOV-3505A - 6 Load RPS05A NIA oo:oo:oo 0O:OO:OO NO MAN 6 1) REACTOR TRIP BREAKER A FAILURE - 6 Load RPS05B NIA oo:oo:oo 0O:OO:OO NO MAN t 1) REACTOR TRIP BREAKER B FAILURE - 6 ***(- 38) FDW12 11 oo:oo:oo oo:oo:oo 0 AFW TURBINE DRIVEN PUMP SPEED CONTROL FAILURE -

• • • Events initiated on cue from NRC Lead Examiner Estimated Time: 60 Minutes Revision 00 Page 4 of 18

Appendix D Required Operator Actions Form ES-D-2 - 3p-Test No.: 1 Scenario No.: 4 Event No.: 1 Event

Description:

(T=l min) iigh RCS Activity ndications: R-9. Letdown Line Monitor indication rising and in alarm 24, RMS Area Moni r High-Activity 1 Time Position ATC Recognizes alarms and indications and reports to SRO. - AT C/BOP Refers to AR-E-24 and AR-RMS-9 - SRO Enters AP-RCS.3, High.Reactor Coolant Activity - SRO Directs RP to sample RCS for activity -- ATC Places 60 GPM orifice in service per S-3.2P, Swapping CVCS Letdown Orifice Valves Verifies AOV-24.4 is in the BYPASS position. Places PCV-135 to MANUAL AND adjusts as necessary to control Low Pressure Letdown pressure at approximately 200 psig. Closes on-line 4.0gpm orifice valve and verifies standby 40 gpm orifice valve is closed (AOVQOOA and AOVPOOB), THEN immediately oper 60 gpm orifice valve, AOV-202 Adjusts PCV-135 to achieve Letdown pressure of - 250 psig on PI-135. Ensures PCV-135 controller signal is nulled/balanced and then place: PCV-135 to AUl'O. Ensures TCV-130 is in AUTO. Monitors Charging/Letdown mismatch and verifies Charging pump A responds in AUTO or adjusts charging flow manually. Requests an A01 locally adjust Reactor Coolant Pump Seal Injection Flow to maintain labyrinth seal D/P between 30 and 40 inches. Monitors Letdown temperature controller TCV-35 is controlling at desired value. Requests an A 0 verify local demin D/P <25 psid (DPI-100, DPI-101).

                                   -   Notifies Shift Chemistry Technician.

SRO Determines R-9 reading > 200 mR/hr and implements EPlP 1-13, Local Radiation Emergency concurrently with AP-RCS.3. SRO Directs RP to determine DI decontamination factor. SRO Directs RP to perform surveys in the AUX BLDG SRO Evaluates MCB annunciators. SRO Consults with plant staff lo determine if shutdown is required SRO Notifies higher supervision. SRO Refers to TS 3.4.16 and enters Condition A, Action A.l R. E. Ginna Nuclear Plant Page 5 of 18 Revision 00

Appendix D Required Operator Actions - Form ES-0-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 1 Event

Description:

(T=l min) High RCS Activity Indications: 0 R-9, Letdown Line Monitor indication rising arid in alarm R. E. Ginna Nuclear Plant Page 6 of 18 Revision 00

ADnendix D Reauired Onerator Actions Form ES-D-:r 3p-Test No.: 1 Scenario No.: 4 Event No.: 2

vent

Description:

(- T = l l min) Steam Generator A Pressure Transmitter PT-469 Fails Low ndications: 0 Fl-465, STEAM GEN A-2 STEAM FLOW reads lower than Fl-464, STEAM GEN A-1 STEAM FLOW and Fl-493, STEAM GEN A-3 STEAM FLOW 0 Pl-469, STEAM GEN A-2 PRESSURE failed low 0 G-22, ADFCS SYSTEM TROUBLE lit G-11, LO STEAM PRESSURE LOOP A 600 PSI

         .27, STM LINE A LC -0 PRESS CHANNEL AILERT 514 PSI Time           Position                                   Applicant's Actions or Behavior BOP                     Recognizes alarms and indications and reports to SRO.

SRO Enters ER-INST.l and goes to Section 4.9 and implements Attachment S/G Pressure Channel PI-469 White Channel BOP In the (WHITE) W2 PROTECTION CHANNEL 2 rack: Places the 469 LOOP A-2 LO LO PRESS SI bistable proving switch to DEFEAT (UP) Verifies the 469 LOOP A-2 LO LO PRESS SI bistable proving light OFF Places the 469 LOOP A-2 LOW PRESS bistable proving switch to DEFEAT (UP) Verifies the 469 LOOP A-2 LOW PRESS bistable proving light OFF Places the 465 LOOP A-2 HIGH TRIP bistable proving switch to DEFEAT (UP) Verifies the 465 LOOP A-2 HIGH TRIP bistable proving light OFF Places the 465 LOOP A-2 HI HI TRIP bistable proving switch to DEFEAT (UP) Verifies the 465 LOOP A-2 HI HI TRIP bistable proving light ON BOP/ATC Verifies the bistable status lights and annunciators listed are lit: 0 FC465A Hi Stearn Flow 0 FC465B Hi Hi Steam Flow 0 PC469A Lo Press SI G-11, LO STEAM PRESSURE LOOP A 600 PSI G-26, S/G A HI SNTEAM FLOW G-27, STM LINE A LO-LO PRESS CHANNEL ALERT 514 PSI R. E. Ginna Nuclear Plant Page 7 of 18 Revision 00

Appendix D Required Operiator Actions Form ES-D-2-- Op-Test No.: 1 Scenario No.: 4 Event No.: 2 Event

Description:

(- T = l l min) Steam Generator A Pressure Transmitter PT-469 Fails Low Indications: Fl-465, STEAM GEN A-2 STEAM FLOW reads lower than Fl-464, STEAM GEN A-1 STEAM FLOW and Fl-493, STEAM GEN A-3 STEAM FLOW 0 PI-469, STEAM GEN A-2 PRESSURE failed low 0 G-22, ADFCS SYSTEM TROUBLE lit G-11, LO STEAM PRESSURE LOOP A 600 PSI

          -27, STM LINE A LC -0 PRESS CHANNEL ALERT 514 PSI Time            Position                                 Applicants Actions or Behavior                     -*

BOP Deletes the channel from the PPCS by performing the following: 0 On the Sub/Delete/Restore display o Selects Point ID PO469 o Turns OFF scan processing o Selects Change On the Sub/DeIe!te/Restoredisplay o Selects Point ID F0465 o Turns OFF scan processing o Selects Change SRO Checks the following ITS Sections for LCOs: 0 Section 3.3.2, Table 3.3.2-1, Function 1e o Enters Condition L, Action L.l Section 3.3.2, Table 3.3.2-1, Functions 4d and 4e o Enters Clondition F, Action F.l Section 3.3.3, Table 3.3.3-1, Functions 24 and 25 o Determines requirements are still being met with one channel out of service, No further action required End of Event R. E. Ginna Nuclear Plant Page 8 of 18 Revision 00

Amendix D Reauired Oderator Actions Form E S - D T Op-Test No.: 1 Scenario No.: 4 Event No.: 3 Event

Description:

(- T=20 min) Letdown Non-Regenerative Heat Exchanger Outlet Teimperature TT-130 Fails Low Indications: A-12, NON-REGEN HX LETDOWN OUT HI TEMP 145'F 0 TI-130, NON-REGEN HX LTDN OUT TEMP faded low 0 LTDN DIVERT TO DI OR VCT, TCV-145 positioned to VCT in AUTO 1 0 NRHX LTDN OUTLET TEMP (TI-130) TCV-130 controller output 100%

                                'EMP begins to rise      _ -

Applicant's Actions or Behavior Recognizes alarms and indications and reports to SRO. - Refers to AR-A-12, NON-REGEN HX LETDOWN OUT HI TEMP 14FF - Ensures LTDN Divert to DI or VCT, TCV-145 is diverting to VCT. I Monitors for reactivity changes and RCP seal performance. - Adjusts NRHX LTDN outlet temp (TI-130) TCV-130 to maintain letdown tema at the normal value usiiig PPCS point T0145. - Checks for proper charging and letdown flows, and temperatures. 0 Charging Line Flow (FI-1288 or C) = 25 gpm. 0 LTDN Line Flow (FI-134) = 40 gpm 0 NRHX LTDN Cutlet Temp PPCS Point TO145 at the normal value. - Refers to S-8A, COMPONENT COOLING WATER SYSTEM STARTUP ANI) NORMAL OPERATlO~lVALVE ALIGNMENT. - Initiates Condition Report for Technical Evaluation. - End of Event - R. E. Ginna Nuclear Plant Page 9 of 18 Revision 00

Appendix D Required Operator Actions Op-Test No.: 1 Scenario No.: 4 Event No.: 4 Event

Description:

(- T=28 min) Feedwater Pump B Lube Oil System Leak Indications: 0 H-12, Feed Pump DC Oil Pump Auto Start 0 4, Main Feed PumF )il System Time Position Applicant's Actions or Behavior BOP Reports Annunciator ti-I 2 to SRO. 0 Verifies DC Oil Pump started. SRO/BOP Notifies A 0 to perform the following: 0 VERIFY Oil in the sump by LG-2764(2773)OR dipstick. 0 CHECK DC Oil Pump. 0 IF required, THEN START the other AC Oil Pump. BOP Reports Annunciator I-{-4to SRO. SR O B 0P Notifies A 0 to perform the following: 0 Check for leaks. 0 Check filter DP. SRO When MFW Pump trips, goes to AP-FW.1, Abnormal MFW Pump Flow or NPSH. ATC Verifies Reactor Power z 50%. SRO/BOP Determines only one MFW Pump running. ATC Verifies Reactor Power c: 75%. BOP Starts all 3 AFW pumps and verifies flow. SRO Initiates power reduction per AP-TURB.5, RAPID LOAD REDUCTION. SRO If S/G levels drop to 20% NR performs a manual reactor trip and goes to E-' Reactor Trip or Safety Injection. End of Event R. E. Ginna Nuclear Plant Page 10 of 18 Revision 00

Appendix D Required Operlator Act ions Form ES-D-2-- Op-Test No.: 1 Scenario No.: 4 Event No.: 5 Event

Description:

(-T=30) Down Pc ter to 50% Time Position A p p SRO Provides ATC and BOP with instructions for down power. ATC Verifies Rods in AUTO or adjusts rods in MANUAL to maintain Tavg to Tref. BOP Reduces turbine load in Auto as follows: 0 Places Turbine EH Control in OPER PAN., IMP PRESS IN Selects rate on thumbwheel per SRO instructions. Reduces the loact setter to 50% load value. Depresses the GIO button. ATC Initiates boration at 4 gal/% load reduction (-40-80 gals) per SRO instructions. ATC Places PRZR backup heater switch to ON. ATC/BOP Adjusts Turbine load rate, Boric Acid flowrate, Rods to maintain Tavg to Tref. BOP Verifies Turbine Load reduction stops when Load = Setter End of Event R. E. Ginna Nuclear Plant Page 11 of 18 Revision 00

Appendix D Required Operator Actions Form ES-D-,T - Op-Test No.: 1 Scenario No.: 4 Event No.: 6 Event

Description:

(-T=35 min) Condensate Line Break, Bus 16 Fault, Loss of all Feedwater Indications: 0 H-1, Feedwater Pump Lo Suct Press 185 PSI 0 H-11, Feed Pump Seal Water Lo Diff Press 15 PSI 0 H-14, Condensate Header Press Lo 0 H-17, Feed Pump Net Positive Suction Head 0 H-30, Condensate Bypass Valve Open 0 AA-9, Cond Bstr Pump Press Trip 100 PSI 425 0 AA-25, Cond Sys Lo Press 325 PSI 0 AA-30, Cond Bstr Pmp Lo Suct Press 100 PSI 0 Feed Flow c Steam Flow S/G NR and WR levels lowering itwell Level lowerinc vith Hotwell Level Controller LC-107 indicating full makeup signal Position BOP Recognizes alarms and indications and reports to SRO. SRO Orders Reactor Trip per AP-FW.l with no MFW Pumps running and goes to E 0, Reactor Trip or Safety Injection. ATC Verifies Reactor Tripped (Critical Task CT-E-0--A) 0 Opens Bus 13 And 15 normal feeder breakers 0 Verifies Rod Drive MG sets tripped 0 Closes Bus 13 and Bus 15 normal feeder breakers 0 Resets lighting bireakers 0 Verifies neutron flux lowering - Power range indicators NI-41 through NI-44 c 5% 0 Verifies MRPl indicates all rods on bottom BOP Manually trips turbine and verifies all turbine stop valves closed BOP Verifies Buses 14, 17, and 18 > 440V, determines Bus 16 is de-energized. ATC Determines SI is not actuated or required. 0 No SI Annunciators RCS Pressure > 1750 psig 0 Steam line Pressure > 514 psig 0 CNMT Pressure < 4 psig 0 SI not sequencing SRO Re-verifies Immediate Actions R. E. Ginna Nuclear Plant Page 12 of 18 Revision 00

Appendix D Required Operator Actions Form ES-D-2 lp-Test No.: 1 Scenario No.: 4 Event No.: 6 Event

Description:

(-T=35 min)

ondensate Line Break, Bus 16 Fault, Loss of all Feedwater ndications:

0 H-1, Feedwater Pump Lo Suct Press 185 PSI 0 H-11, Feed Pump Seal Water Lo Diff Press 15 PSI 0 H-14, Condensate Header Press Lo 0 H-17, Feed Pump Net Positive Suction Head 0 H-30, Condensate Bypass Valve Open 0 AA-9, Cond Bstr Pump Press Trip 100 PSI 425 0 AA-25, Cond Sys Lo Press 325 PSI 0 AA-30, Cond Bstr Pmp Lo Suct Press 100 PSI 0 Feed Flow c Steam Flow 0 S/G NR and WR levels lowering 0 Hotwell Level lowerinc with Hotwell Level C o n t l-8 + Applicants Actions or Behavior Transitions to ES-0.1, Reactor Trip Response - SRO/ATC/BOP Commences CSFST arid Foldout Page monitoring. Monitors Tavg at or trending to 5478F. - Checks PRZR level control Verifies at least one charging pump running 0 Verifies letdown in service 0 Verifies PRZR level > 13% and trending to 20% 0 Verifies PRZR Proportional and Backup Heaters ON - ATC/BOP Checks S/G feed Flow Status 0 Verifies RCS Tavgc 554°F 0 Verifies MFW regulating and bypass valves closed 0 Reports 0 gpm AFW flow and MDAFW pumps or MFW available 0 Opens MOV-3505A or MOV-3504A and verifies TDAFW pump flow to both S/Gs (NOTE TO LEAD EXAMINER: Cue Booth Operator to trip pump when at least one S/G NR level is > 7%) Closes MFW Pump Discharge Valves MOV-3977 and MOV-3976 Places both MF\N Pump C/Ss to PULL STOP Places MFW Regulating valve controllers in MANUAL and lowers output too. . Verifies all rods fully inserted using MRPl display When Narrow Range level in both S/Gs is c 7% with c 200 gpm total R. E. Ginna Nuclear Plant Page 13 of 18 Revision 00

Appendix D Required Operiator Actions Form ES-D Op-Test No.: 1 Scenario No.: 4 Edent No.: 6 Event

Description:

(-T=35 min) Condensate Line Break, Bus 16 Fault, Loss of all Feedwater Indications: H-1, Feedwater Pump Lo Suct Press 185 PSI H-11, Feed Pump Seal Water Lo Diff Press 15 P!SI H-14, Condensate Header Press Lo H-17, Feed Pump Net Positive Suction Head 0 H-30, Condensate Bypass Valve Open 0 AA-9, Cond Bstr Pump Press Trip 100 PSI 425 AA-25, Cond Sys Lo Press 325 PSI 0 AA-30, Cond Bstr Pmp Lo Suct Press 100 PSI 0 Feed Flow c Steam Flow 0 S/G NR and WR levels lowering

   . I Time s, transitions to FR-H.l, Response to Loss of Secondary Heat Sink.

ATC Verifies secondary heat sink required 0 RCS pressure is > S/G A and S/G B pressure 0 RCS Cold Leg temperature >3508F BOP/ATC Monitors Secondary Heat Sink (Continuous Action) 0 Verifies at least one S/GWide Range level 7 50 inches 0 Verifies PRZR pressure e 2335 psig SRO/BOP Determines neither MDAIFW pump available SRO/BOP Verifies TDAFW pump available(if not previously started and tripped in ES-0.1, if not available goes t o step to stop RCPs) NOTE: The following steps up to but not including stopping the RCPs will only be performed if the TDAFW ump start was not attempted previously. BOP/ATC Verifies S/G blowdown and sample valves closed 0 S/G 1A Bldn lsol AOV-5738 White Status Light Bright 0 S/G 1B Bldn lsol AOV-5737 White Status Light Bright S/G 1A Sample AOV-5735 White Status Light Bright 0 S/G 1B Sample AOV-5736 White Status Light Bright SRO/BOP Checks MCB indications for cause of AFW Failure 0 Verifies CST > 5 Ft 0 Determines one MDAFW pump unavailable because Bus 16 is de-energized the other is 00s for impeller replacement. R. E. Ginna Nuclear Plant Page 14 of 18 Revision 00

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 6 Event

Description:

(-T=35 min) Condensate Line Break, Bus 16 Fault, Loss of all Feedwater Indications: H-1, Feedwater Pump Lo Suct Press 185 PSI H-11, Feed Pump Seal Water Lo Diff Press 15 PSI H-14, Condensate Header Press Lo H-17, Feed Pump Net Positive Suction Head 0 H-30, Condensate Bypass Valve Open AA-9, Cond Bstr Pump Press Trip 100 PSI 42!5 0 AA-25, Cond Sys Lo Press 325 PSI 0 AA-30, Cond Bstr Pmp Lo Suct Press 100 PSI 0 Feed Flow e Steam Flow 0 S/GNR and WR levels lowering

          )twell Level lowerin! Nith Hotwell Level C                      o                   n                     u Position                                  Applicants Actions or Behavior                        .-

SRO/BOP Determines desired feed flow rate per ATT 22.0 0 Determines feed and bleed not in progress or required 0 If level > 5 0 feed as desired 0 If level e 50 feed affected S/G at 1.100 gpm until > 5 0 then fill as desired 0 After feed initiation: o Verify both hot leg temperatures lowering o Verify affected S/G is not faulted or ruptured - BOP Checks TDAFW Pump flow control valves open: AOV-4297 AOV-4298 - Starts TDAFW Pump by opening MOV-3504A and MOV-3505A - BOP Determines TDAFW pump is not feeding S/Gs - ATC Stops RCP 1A and 1B - SRO/ATC Verifies SI not actuated and goes to next step R. E. Ginna Nuclear Plant Page 15 of 18 Revision 00

Appendix D Required Oper'ator Actions Form ES-D Op-Test No.: 1 Scenario No.: 4 Event No.: 6 Event

Description:

(-T=35 min) Condensate Line Break, Bus 16 Fault, Loss of all Feedwater Indications: 0 H-1, Feedwater Pump Lo Suct Press 185 PSI H-11, Feed Pump Seal Water Lo Diff Press 15 PSI 0 H-14, Condensate Header Press Lo 0 H-17, Feed Pump Net Positive Suction Head 0 H-30, Condensate Bypass Valve Open 0 AA-9, Cond Bstr Pump Press Trip 100 PSI 425 0 AA-25, Cond Sys Lo Press 325 PSI 0 AA-30, Cond Bstr Pmp Lo Suct Press 100 PSI 0 Feed Flow c Steam Flow 0 S/G NR and WR levels lowering Nith Hotwell Level C o n t r o l

                              -                                                d Establishes S A W flow to at least one S/G (CT FR-H.1-E) 0  Using ATT. 5.1, Attachment SAFW, Aligns S A W Pump C to selected S/G as follows:

o Ensures SI Reset Ensures the following valves open: o

                                                   . FAOV-9701A, SAFW PUMP C DISCHARGE VLV CAOV-4616, AUX BLDG SW ISOL VLV
                                                   . CAOV-9704A, SAFW PUMP C ISOL VLV       I o  Opens MIOV-9629A, S A W PUMP C SUCTION VLV.

R. E. Ginna Nuclear Plant Page 16 of 18 Revision 00

Appendix D Required Operator Actions Form ES-K'IT - Op-Test No.: 1 Scenario No.: 4 Event No.: 6 Event

Description:

(-T=35 min) Condensate Line Break, Bus 16 Fault, Loss of all Feedwater Indications: 0 H-1, Feedwater Pump Lo Suct Press 185 PSI 0 H-11, Feed Pump Seal Water Lo Diff Press 1Ei PSI 0 H-14, Condensate Header Press Lo 0 H-17, Feed Pump Net Positive Suction Head 0 H-30, Condensate Bypass Valve Open ~ 0 AA-9, Cond Bstr Pump Press Trip 100 PSI 425 0 AA-25, Cond Sys Lo Press 325 PSI 0 AA-30, Cond Bstr Pmp Lo Suct Press 100 PSI 0 Feed Flow e Steam Flow 0 S/G NR and WR levels lowering btwell Level lowerinc iith Hotwell Level C o r u Position Applicant's Actions or Behavior - BOP To feed selected S/G: (CT FR-H.1-E) o

                                                       . S/G A - restores SAFW flow as directed by procedure in effect.

0R

                                                       . S/G B, performs the following:

0 Ensures MOV-9746, SAFW PMP D EMERG DlSCH VLV, open 0 Closes MOV-9704A, SAFW PUMP C ISOL VLV 0 Opens either SAFW CROSSOVER VLV: o MOV-9703A OR o MOV-9703B 0 Verifies open MOV-9704B, SAFW PUMP 3 SOL VLV 0 Restores SAFW flow as directed by procedure in effect. 0 Verifies selected S/G Wide Range level is > 50 inches and determmes from ATT-22 0, Attachment Restoring Feed Flow that flow can be started at > 235 gpm Starts SAFW Pump C by taking C/S to START 0 When intact S/G level GREATER THAN 50 inches (100 inches adverse CNhAT), THEN verify SAFW flow GREATER THAN 235 GPM R. E. Ginna Nuclear Plant Page 17 of 18 Revision 00

Appendix D Required Oper,ator Actions Form ES-D-2-- 3p-Test No.: 1 Scenario No.: 4 Event No.: 6

vent

Description:

(-T=35 min) 2ondensate Line Break, Bus 16 Fault, Loss of all Feedwater Indications: H-1, Feedwater Pump Lo Suct Press 185 PSI H-11, Feed Pump Seal Water Lo Diff Press 15 PSI H-14, Condensate Header Press Lo H-17, Feed Pump Net Positive Suction Head H-30, Condensate Bypass Valve Open AA-9, Cond Bstr Pump Press Trip 100 PSI 425 AA-25, Cond Sys Lo Press 325 PSI AA-30, Cond Bstr Pmp Lo Suct Press 100 PSI Feed Flow e Steam Flow S/G NR and WR levels lowering

          )twell Level lowerin: Nith Hotwell Level Controller LC-107 indicating full makeup signal Position                                Applicants Actions or Behavior SRO                   Goes to step 11 SRO/BOP               Checks Narrow Range Level in selected S/G > 7% or SAFW flow is > 235 gprri to selected S/G and selected S/G level WR and/or NR rising.

SRO Returns to step in effect in ES-0.1, Reactor Trip Response End of Scenario SRO Perform Emergency Plan Classification for final event Expected EAL: Site Area Emergency, 1.3.1, Red Path in F-0.3 Heat Sink Start Time: - Stop Time: - R. E. Ginna Nuclear Plant Page 18 of 18 Revision 00}}