ML102320408

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

ML102320408
Person / Time
Site:	Ginna
Issue date:	05/25/2010
From:	Fish T H Operations Branch I
To:	Constellation Energy Nuclear Group, Ginna
Hansell S
Shared Package
ML092470059	List: IR 05000244/2010301 ML100400205 ML101680575 ML101720347 ML101720553 ML101720560 ML101720564 ML102320373 ML102320386 ML102320393 ML102320408 ML102520045 ML102520054 ML102710006
References
TAC U01766
Download: ML102320408 (347)

Text

---Appendix C Job Performance Measure Form ES-C-1 Worksheet Ginna Task No.: Task Given a Set of Conditions, Perform JPM No.: 2010 GINNA NRC JPM a Critical Rod Position Calculation In RA-1 Accordance With 0-1.2.2, Critical Rod Position Calculation.

KIA 2.1.25 (3.9/4.2)

NRC Examiner:

Facility Date: Method of testing: Simulated Actual Performance:

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

Initial

• The plant is in MODE 3 preparing for a reactor startup.

• PPCS and PCNDR are not available

• See attached Initial Conditions and Plant History page. Task Critical Rod Position calculation performed within specified band and all critical tasks evaluated as satisfactory.

Required Calculator General

• 0-1.2.2, Critical Rod Position Calculation, Rev. 06600

• Core Operating Limits Report, Cycle 35

• BorationlDilution Tables

• 0-1.2.2, Critical Rod Position Calculation, Rev. 06600

• Core Operating Limits Report, Cycle 35

• BorationlDilution Tables

• Initial Conditions and Plant History page Initiating You are an extra RO in the control room for a reactor startup. The Shift Manager directs you to calculate a Critical Rod Position per 0-1.2.2 through Step 6.9.1. Time Critical No Validation 48 minutes 2010 GINNA NRC JPM RA-1, Revision NRC NUREG 1021! Revision 9, Supplement 1

Appendix C Page 2 of 9 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a ..J) Start Time: ____ Performance Step: 1 Standard:

EXAMINER CUE: EXAMINER CUE: EXAMINER NOTE: Performance Step: 2 Standard:

EXAMINER NOTE: Performance Step: 3 Standard:

EXAMINER NOTE: 0-1.2.2, section 1.0 thru 5.0 Reviews sections 1.0 thru 5.0. Reviews sections 1.0 thru 3.0 and 5.0. Fills out step 4.1, signs steps 4.2 and 4.3. Provide the Plant Historyllnitial Conditions Handout When the Candidate determines the need for 0-1.2.2, provide them with a copy. At your discretion you may have them describe how to obtain the current revision of the procedure and then hand them a copy of 0-1.2.2. See provided "Key" for details of all steps. 0-1.2.2, section 6.1 Calculate the reactivity due to Power Defect. Using Attachment 2, Figure 5-21 (MOL) determines Power Defect to be ;;:: 1150 pcm and S; 1200 pcm. Candidate:

PCM The exact value from PCNDR is 1190 PCM. 0-1.2.2, section 6.2 Calculate the reactivity due to Rod Worth. Using Attachment 5, Table 6-7 (MOL) determines Control Rod Worth to be between 129 pcm and 130 pcm Candidate:

PCM The exact value from PCNDR is +129.133 PCM. It is +/-0.5 pcm since the Candidate only has to pull the number off of a table. The error may come from rounding the number. 2010 GINNA NRC JPM RA-1, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 3 of 9 Form ES-C-1 Performance Step: 4 Standard:

Comment: Performance Step: 5 Standard:

EVALUATOR NOTE: PERFORMANCE INFORMATION 0-1.2.2, section 6.3 Calculate the reactivity due to Xenon. Transposes Reactor Engineering Pre-trip Xe Worth (2100 PCM) onto Step 6.3.4 Transposes Reactor Engineering Current Xe Worth (75 PCM) onto Step 6.3.5 Calculates Xe Change as +2025 PCM in Step 6.3.6 Candidate:

PCM 0-1.2.2, section 6.4 Calculate the reactivity due to Boron. In Step 6.4.3, calculates the change in Boron Concentration as +366 PPM In Step 6.4.4, determines AVG Boron Concentration to be 1133 PPM Using Attachment 10, Figure 5-3, determines Boron Worth to be between -6.7 and -6.8 PCM/PPM Calculates the change in reactivity due to Boron as between -2452 and -2488 PCM. Candidate:

PCM The actual boron worth is 6.75 PCM/PPM. The actual change in reactivity due to Boron is -2471 PCM. The band was derived from multiplying

-6.7 x 366 for the low end and -6.8 x 366 for the high end. 2010 GINNA NRC JPM RA-1, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 6 Standard:

EXAMINER NOTE: Performance Step: 7 Standard:

EXAMINER NOTE: Performance Step: 8 Standard:

EVALUATOR NOTE: Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION 0-1.2.2, section Calculate the reactivity due to "effective" Using Attachment 12, Figure 5-30: Determines current Sm worth >940 PCM but <960 PCM. Determines pre-trip Sm Worth >900 PCM but <920 PCM Calculates the change in reactivity due to Samarium as between -20 and -60 PCM. Candidate:

PCM Actual reactivity change due to Sm is -40 PCM. 0-1.2.2, section Calculate total reactivity Calculates the total reactivity change between 754 and 882 pcm. Candidate:

PCM The exact reactivity change is +833 PCM. The allowable band is + 49 pcm to -79 pcm. The band is based on the addition of all of the allowable bands during the calculation of the total reactivity change. 0-1.2.2, section 6.7.1 Estimated Critical Rod Position.

Estimated Critical Rod Position must be within the band of Bank D 19 steps to Bank D 164 steps. Candidate:

Steps Actual Critical Rod Position for the conditions is Bank 0 71 steps. The band established in the Standard (0-1.2) is +/- 500 PCM around Bank 0 71 steps. 2010 GINNA NRC JPM RA-1, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 9 Standard:

Comment: Procedure Note: Performance Step: 10 Standard:

Comment: Performance Step: 11 Standard:

EXAMINER CUE: Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION 0-1.2.2, section 6.7.2 DETERMINE Control Bank Insertion Limit for 0% Power from COLR. Uses COLR to determine Bank C 51 steps. Candidate:

Steps Initials step 0-1.2.2, section 6.7.3 IF the estimated Critical Rod Position indicates the Reactor will go critical with all rods out, OR the Reactor will go critical below the Control Bank Insertion Limits, OR a different critical rod position is desired, THEN a change in the critical rod position (i.e. charge in Boron concentration)

SHALL be determined.

COMPARE the estimated critical rod position (Step 6.7.1) with the Insertion Limit (Step 6.7.2) Determines Step 6.7.1 (D 71) is greater than Step 6.7.2 (C 51) Initials step 0-1.2.2, section 6.7.4 IF a change in the critical rod position is needed, THEN PERFORM Step 6.B. OTHERWISE MARK this Step N/A. Marks step N/A A change in Critical Rod Position is not needed. 2010 GINNA NRC JPM RA-1, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION 0-1.2.2, section 6.7.5 Performance Step: IF a change in the critical rod position is NOT needed, THEN MARK Step 6.8 N/A OTHERWISE MARK this Step N/A

• Marks Step 6.8 N/A

• Initials step EXAMINER If the Candidate did not ask during Performance Step 11, inform them "A change in Critical Rod Position is not needed." 2010 GINNA NRC JPM RA-1, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 7 of9 Form ES-C-1 PERFORMANCE

"./ Performance Step: 13 Standard:

EXAMINER NOTE: Terminating Cue: 0-1.2.2, section 6.9.1 CALCULATE the control rod bank position corresponding to 500 pcm from the estimated critical rod position using the estimated critical rod position from: Step 6.7.1 OR Step Attachment 14, Table 6-3 OR Attachment 15, Table 6-4, OR Attachment 16 Table 6-5 + 500 pcm bank position ___ -500 pcm bank position ___ Selects Data from Step 6.7.1 Uses Attachment 15, Table 6-4 Adds 500 pcm to the calculated value in Step 6.6.6 to determine the + 500 pcm Integral Worth ("./> Determines the + 500 pcm position between D 157 and D 174 Candidate:

Steps Subtracts 500 pcm to the calculated value in Step 6.6.6 to determine the -500 pcm Integral Worth <"./> Determines the -500 pcm position between D 14 and D 28 Candidate:

Steps To determine the allowable values when calculating the 500 pcm positions the + 49 pcm -79 pcm determined when calculating the Total Reactivity Change in Step 6.6.6 was used. PCNDR calculated the + 500 pcm position to be D 164 and the -500 pcm position to be D 19 When Step 6.9.1 is complete:

Evaluation on this JPM is complete Stop Time: ____ 2010 GINNA NRC JPM RA-1, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of9 Form ES-C-1 VERIFICATION OF Job Performance Measure No.: 2010 GINNA NRC JPM RA-1 Examinee's Date Facility Number of Time to Question Result: SAT Examiner's Signature:

2010 GINNA NRC JPM RA-l, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 90f9 Form ES-C-1 INITIAL INITIATING JPM CUE

• The plant is in MODE 3, preparing for a reactor startup.

• PPCS and PCNDR are not available

• See attached Initial Conditions and Plant History page. You are an extra RO in the control room for a reactor startup. The Shift Manager directs you to calculate a Critical Rod Position per 0-1.2.2 through Step 6.9.1. 2010 GINNA NRC JPM RA-1, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Job Performance Measure Form ES-C-1 Facility:

Ginna Task No.: Task Title: Perform a Daily Surveillance Log JPM No.: 2010 GINNA NRC JPM RA-2 KIA

Reference:

2.1.18 (3.6/ 3.8) Examinee:

NRC Examiner:

Facility Evaluator:

Date: Method of testing: Simulated Performance:

Actual Performance:

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

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue: Time Critical Task: Validation Time: The plant is at 100% power, Middle of Life (MOL). Today is 6/2112010 at 0715. Takes the required actions for all four (4) parameters outside their allowable values. Calculator 0-6.13, DAILY SURVEILLANCE LOG, Revision 17500 Technical Specifications, Amendment 109 0-6.13, DAILY SURVEILLANCE LOG, Revision 17500, Attachment 1, Page 1 and 2 of 10 (Have the entire procedure available upon request.) Technical Specifications, Amendment 109 You are the HCO. The Control Room Supervisor directs you to perform 0-6.13. Attachment 1, pages 1 and 2 of 10. No 15 Minutes 2010 GINNA NRC JPM RA-2, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP IC N-RA-2 2010 GINNA NRC JPM RA-2, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 30f9 Form ES-C-1 VERIFICATION OF (Denote Critical Steps with a .J) Start Time: ____ EXAMINER CUE: Provide the handout. Acknowledge any report of a parameter out of specification.

If necessary, direct the candidate to complete the entire JPM if they stop after reporting the first parameter out of specification.

EXAMINER NOTE: Only the parameters out of specification are identified in the JPM. Errors can be identified in any order. 0-6.13, Attachment 1 Performance Step: Reactor Coolant System Monitor (cc)

• Compares TI-409A and TI-41 OA to each other. Uses either PPCS or MCB indication to determine TI-41 OA is indicating approximately 12°F too high. Refers to Step 6.2.5 EXAMINER Performance Steps 1 and 2 are associated with the Reactor Coolant System Monitor channel check failing. 2010 GINNA NRC JPM RA-2, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 4 of 9 Form ES-C-1 VERIFICATION OF Procedure Note: " Performance Step: 2 Standard:

EXAMINER CUE: EXAMINER CUE: EXAMINER CUE: Performance Step: 3 Standard:

0-6.13, Step 6.2.5 The sections which follow provide specific guidance as referenced within Attachment 1 and Attachment

3. Power Range channels have a +/-2% deviation from highest to lowest channel Source Range channels are within one (1) decade of each other. RCS Subcooling Monitors have a +/-10% meter span channel check for operability.

PERFORM the following for channel deviations of the same parameter of +/-5% or greater of meter span. SUBMIT a Condition Report for channel with REFER TO ITS for channel operability requirements. Submits a Condition Report Recommends entering LCO 3.3.3 When the Candidate indicates they would submit a Condition Report, inform the Candidate "A Condition Report has been submitted." If the Candidate just informs the Control Room Supervisor, ask the Candidate "Make a recommendation on which LCO(s) must be entered." When the Candidate makes a recommendation on which LCO to enter, inform them "The Control Room Supervisor will fill out the required paperwork and take the required action for the LCO entry." 0-6.13, Attachment 1 and Step 6.2.6 [Attachment 1] Verify Total RCP Seal Leakoff [Step 6.2.6] VERIFY total RCP Seal Leakoff is less than 8.0 gallons per minute by adding MCB Seal Leakoff Flow Recorder F-177 and F-178. Uses FI-177 and FI-178 to determine total sealleakoff is greater than 8.0 GPM. EXAMINER NOTE: Performance Steps 3 and 4 are associated with the total RCP seal leakoff exceeding 8.0 GPM 2010 GINNA NRC JPM RA-2, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of9 Form ES-C-1 ..J Performance Step: 4 Standard:

EXAMINER CUE: Performance Step: 5 Standard:

EXAMINER NOTE: ..J Performance Step: 6 Standard:

EXAMINER CUE: VERIFICATION OF 0-6.13, Step 6.2.7 IF RCP Seal Leakoff flow exceeds 8.0 GPM, THEN SUBMIT a Condition Report. Submits a Condition Report When the Candidate indicates they would submit a Condition Report, inform the Candidate "A Condition Report has been submitted." 0-6.13, Attachment Sf Accumulator Maintain and Maintain>730 and <760 Determines SI Accumulator pressure is less than 730 psig. Performance Steps 5 and 6 are associated with SI Accumulator pressure less than 730 psig. 0-6.13, Step 6.2.14 MAINTAIN Sf Accumulator Pressure greater than 730 PSIG and less than 760 PSIG due to instrument uncertainty.

Otherwise, declare SI Accumulator inoperable PER ITS LCO 3.5.1. Recommends entering LCO 3.5.1 When the Candidate makes a recommendation on which LCO to enter, inform them "The Control Room Supervisor will fill out the required paperwork and take the required action for the LCO entry." 2010 GINNA NRC JPM RA-2, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 6 of9 Form ES-C-1 Performance Step: 7 Standard:

EXAMINER NOTE: Procedure Note: " Performance Step: 8 Standard:

EXAMINER CUE: EXAMINER CUE: EXAMINER CUE: VERIFICATION OF COMPLETION 0-6.13, Attachment 1 Power Range (cc) 2% Deviation Highest to Lowest PR Determines N-41 and N-44 deviate 3%. Performance Steps 7 and 8 are associated with N-41 and 44 deviating by 3%. 0-6.13, Step 6.2.5 The sections which follow provide specific guidance as referenced within Attachment 1 and Attachment

3. Power Range channels have a +/-2% deviation from highest to lowest channel Source Range channels are within one (1) decade of each other. RCS Subcooling Monitors have a +/-10% meter span channel check for operability.

PERFORM the following for channel deviations of the same parameter of +/-5% or greater of meter span. SUBMIT a Condition Report for channel with REFER TO ITS for channel operability requirements.

Submits a Condition Report Recommends entering LCO 3.3.1 When the Candidate indicates they would submit a Condition Report, inform the Candidate "A Condition Report has been submitted." If the Candidate just informs the Control Room Supervisor, ask the Candidate "Make a recommendation on which LCO{s) must be entered." "The Control Room Supervisor will fill out the required paperwork and take the required action for the entering LCO 3.3.1" 2010 GINNA NRC JPM RA-2, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Terminating Cue: When the candidate returns Attachment 1: Evaluation on this JPM is complete.

Stop Time: ____' 2010 GINNA NRC JPM RA-2, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2010 GINNA NRC JPM RA-2 Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: 2010 GINNA NRC JPM RA-2, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 9 of9 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

• The plant is at 100% power, Middle of life (MOL).

• Today is 6/21/2010 at 0715. INITIATING CUE: You are the HCO. The Control Room Supervisor directs you to perform 0-6.13, Attachment 1, pages 1 and 2 of 10. 2010 GINNA NRC JPM RA-2, Revision NRC NUREG 1021, Revision 9, Supplement 1

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Performance Measure Ginna Task No.: Task Perform the RO Review of a Tagout JPM No.: 2010 GINNA NRC JPM For V-3968, 4B Condensate Heater RA-3 Discharge Check Valve. KIA 2.2.13 (4.1/4.3)

NRC Examiner:

Facility Date: Method of testing: Simulated Actual Performance:

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

Initial Conditions: You are an extra RO in the Work Control Center Two days ago the plant was stable at 100% power when a downpower was required due to a leak from a crack in the valve body of V-3968, the 4B Condensate Heater Discharge Check Valve. The plant is stable at 47% reactor power to replace V-3968. Plant Management has determined the replacement of V-3968 will be completed with reactor power stable at 47%. The 4B Low Pressure Heater has been isolated and vented per 14E, Isolation and Restoration to Service of Condensate Heater 4B eSOMs is not available due to maintenance.

Task Standard:

Identify two errors associated with the Hold Boundary for V-3968. Required Materials:

None General

References:

CNG-OP-1.01-1007, Clearance and Safety Tagging, Rev. 00400 PID: 33013-1233, Rev. 30 PID: 33013-1903, Rev. 18 PID: 33013-1922, Rev. 17 PID: 33013-1923, Rev. 25 T-14E, Isolation and Restoration to Service of Condensate Heater 4B, Rev. 009 Handouts: CNG-OP-1.01-1007, Clearance and Safety Tagging, Rev. 00400 (if requested) PID: 33013-1233, Rev. 30 2010 GINNA NRC JPM RA-3, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Job Performance Measure Form ES-C-1 Initiating Cue: Time Critical Task: Validation Time: Worksheet PID: 33013-1903, Rev. 18 PID: 33013-1922, Rev. 17 PID: 33013-1923, Rev. 25 Marked up copies of Attachment 7 and 8, CNG-OP-1.01-1007, Clearance and Safety Tagging, Rev. 00400 Attachment 10, CNG-OP-1.01-1007, Clearance and Safety Tagging, Rev. 00400 (if requested) Marked up copy of T -14E, Isolation and Restoration to Service of Condensate Heater 48, Rev. 009 (if requested)

The Shift Manager directs you to perform the required review for block 14 of Attachment 7 of CNG-OP-1.01-1007 to ensure V-3968 is properly isolated and ready to be replaced.

When the review is complete, sign block 14 if there are not any errors. If errors are found, identify each error. No 52 Minutes 2010 GINNA NRC JPM RA-3, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 30f6 Form ES-C-1 VERIFICATION OF COMPLETION (Denote Critical Steps with a ...J) Start Time: ____ Performance Step: 1 Standard:

EXAMINER CUE: EXAMINER CUE: EXAMINER NOTE: Performance Step: 2 Standard:

EXAMINER NOTE: CNG-OP-1.01-1007 Review CNG-OP-1.01-1007, Attachments 7 and 8 Reviews CNG-OP-1.

0 1-1007, Attachments 7 and 8 Provide the candidate with all of the handouts except OP-1.01-1007 and T -14E. If the Candidate requests the procedures, provide them with a copy. If the candidate stops after the first error is identified, direct them to complete their review of the entire document.

All the data is correct in the Attachments with the exception of the errors listed below. The errors may be identified in any order. CNG-OP-1.01-1 007, Attachment 7 Refers to CNG-OP-1.01-1007 as needed. Identifies that the Remarks section of Attachment 7 should include a statement identifying that double isolation is not available for the high temperature system. Due to the elevated temperature of the Condensate System at V-3968, the Hold should have double valve protection/isolation.

However, due to plant power and system configuration this cannot be achieved.

Step 5.1 (R) states "Double valve protection should be used for systems containing explosive or oxidizing gases, and systems that are operating with a temperature greater than 200°F, or pressure greater than 500 pSig, if available.

Approval shall be obtained from an SRO to work with single valve isolation when double valve isolation is required." 2010 GINNA NRC JPM RA-3, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 4 of6 Form ES-C-1 Performance Step: 3 Standard:

EXAMINER NOTE: Performance Step: 4 Standard:

EXAMINER NOTE: Terminating Cue: Stop Time: ____ VERIFICATION OF CNG-OP-1.01-1 007, Attachment 8 Refers to CNG-OP-1.01-1007 as needed. Determines that V-3997B should be OPEN vice CLOSED. Since V-3997B is a vent valve, it should be open to ensure the system is depressurized.

CNG-OP-1.01-1007, Attachment 8 Refers to CNG-OP-1.01-1007 as needed. Determines that V-3966A was not included in the isolation boundary and should be tagged open. Without V-3966A Danger tagged OPEN Operations Department can not guarantee the Condensate side of the system will remain depressurized.

When the Attachment is handed over: Evaluation on this JPM is complete.

2010 GINNA NRC JPM RA-3, Revision NRC NUREG 1021, Revision 9, Supplement 1

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Appendix C Page 50f6 Form ES-C-1 VERIFICATION OF Job Performance Measure No.: 2010 GINNA NRC JPM RA-3 Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: 2010 GINNA NRC JPM RA-3, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 6 of6 Form ES-C-1 INITIAL INITIATING JPM CUE You are an extra RO in the Work Control Center Two days ago the plant was stable at 100% power when a downpower was required due to a leak from a crack in the valve body of V-3968, the 4B Condensate Heater Discharge Check Valve. The plant is stable at 47% reactor power to replace V-3968. Plant Management has determined the replacement of 3968 will be completed with reactor power stable at 47%. The 4B Low Pressure Heater has been isolated and vented per T-14E, Isolation and Restoration to Service of Condensate Heater 4B eSOMs is not available due to maintenance.

The Shift Manager directs you to perform the required review for block 14 of Attachment 7 of CNG-OP-1.01-1007 to ensure V-3968 is properly isolated and ready to be replaced.

When the review is complete, sign block 14 if there are not any errors. If errors are found, identify each error. 2010 GINNA NRC JPM RA-3, Revision NRC NUREG 1021, Revision 9, Supplement 1

---Appendix C Job Performance Measure Form ES-C-1 Worksheet Ginna Task No.: Task Monitor Critical Safety Function JPM No.: 2010 GINNA NRC JPM Status Trees RA-4 KIA 2.4.21 (4.0/4.6)

NRC Examiner:

Facility Date: Method of testing: Simulated Performance:

Actual Performance:

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

Initial Conditions:

• You are an extra RO.

• The plant has experienced a Reactor Trip and Safety Injection.

• It has been 10 minutes since the Reactor Tripped.

• I will be the Shift Manager. Task All Critical Safety Function challenges identified and the correct procedure transition recommended.

Required None General

• F-0.1, SUBCRITICALlTY, Revision 1

• F-0.2, CORE COOLING, Revision 00600

• F-0.3, HEAT SINK, Revision 4

• F-O.4, INTEGRITY, Revision 00400

• F-O.S, CONTAINMENT, Revision 2

• F-0.6, INVENTORY, Revision 4

• F-0.1, SUBCRITICALlTY, Revision 1

• F-0.2, CORE COOLING, Revision 00600

• F-0.3, HEAT SINK, Revision 4

• F-O.4, INTEGRITY, Revision 00400

• F-O.S, CONTAINMENT, Revision 2

• F-0.6, INVENTORY, Revision 4

• CSFST Card, RG&E 8/89 49/189 S 2010 GINNA NRC JPM RA-4, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Initiating Cue: Time Critical Task: Validation Time: Worksheet The SM has directed you to monitor the Critical Safety Function Status Trees. Using Data Sheet # 1, identify the status of each Critical Safety Function (CSF) on the CSFST card. Hand the card to the Shift Manager when complete and indicate (1) Which CSF is the highest priority and (2) What procedure is recommended, if any. No 12 Minutes 2010 GINNA NRC JPM RA-4, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP N/A 2010 GINNA NRC JPM RA-4, Revision NRC NUREG 1021, Revision 9, Supplement 1

Page 4 VERIFICATION OF COMPLETION (Denote Critical Steps with a ..J) Start Time: ____' Performance Slep: 1 Standard:

Comment: Performance Step: 2 Standard:

Comment: F-O.1 Monitor Subcriticality and determine correct terminus . MONITOR: (F-0.1) Power Range Intermediate Range SUR Source Range energized

• Source Range SUR as necessary

(..J) Correct terminus:

Yellow -FR-S.2 F-O.2 Monitor Core Cooling and determine correct terminus . MONITOR: (F-0.2) Core Exit Thermocouples RCS Subcooling RCP status RVLlS Cnmt Pressure

• Cnmt Radiation as necessary

(..J) Correct terminus:

Orange -FR-C.2 2010 GINNA NRC JPM RA-4, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 3 Standard:

Comment: Performance Step: 4 Standard:

Comment: Performance Step: 5 Standard:

Comment: Page 5 of 8 Form ES-C-1 VERIFICATION OF COMPLETION F-O.3 Monitor Heat Sink and determine correct terminus.

MONITOR: (F-0.3) SIG Level Feedwater Flow SIG Pressure Cnmt Pressure

• Cnmt Radiation as necessary

(-I) Correct terminus:

Yellow -FR-H.2 F-O.4 Monitor INTEGRITY and determine correct terminus.

MONITOR: (F-OA) RCS Cold Leg Temperature decrease over last 60 minutes RCS Cold Leg Temperature

• RCS Pressure, locate point on curve as necessary

(-I) Correct terminus:

Red -FR-P.1 F-O.5 Monitor CONTAINMENT and determine correct terminus.

MONITOR: (F-0.5) Cnmt Pressure Cnmt Sump 8 Level

• Cnmt Radiation as necessary

(-I) Correct terminus:

Orange -FR-Z.1 2010 GINNA NRC JPM RA-4, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 6 of 8 Form ES-C-1 Performance Step: 6 Standard:

Comment: Performance Step: 7 Standard:

Comment: Terminating Cue: Stop Time: ____ VERIFICATION OF COMPLETION Monitor INVENTORY and determine correct terminus MONITOR: (F-0.6) SI Pump status Pressurizer Level RCP status

• RVlIS as necessary

(..,J) Correct terminus:

Green Report to the SM Identify highest priority Critical Safety Function . Recommend procedure.

Identify highest priority.

Red terminus:

Integrity Recommend correct procedure:

Enter FR-Z.1 After the procedure recommendation:

Evaluation on this JPM is complete.

2010 GINNA NRC JPM RA-4, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 8 Form ES-C-1 VERIFICATION OF Job Performance Measure No.: 2010 GINNA NRC JPM Examinee's Date Facility Number of Time to Question Result: SAT Examiner's Signature:

2010 GINNA NRC JPM RA-4, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 8 Form ES-C-1 JPM CUE SHEET Initial

• You are an extra RO. The plant has experienced a Reactor Trip and Safety Injection. It has been 10 minutes since the Reactor Tripped. I will be the Shift Manager. Initiating The SM has directed you to monitor the Critical Safety Function Status Trees. Using Data Sheet # 1, identify the status of each Critical Safety Function (CSF) on the CSFST card. Hand the card to the Shift Manager when complete and indicate (1) Which CSF is the highest priority and (2) What procedure is recommended, if any. Data Sheet # 1 Reactor Power is 0% All Reactor Trip 8reakers are Open Intermediate Range indication is 5x10-7 Amps Intermediate Range SUR is 0 DPM Source Range instruments are deenergized.

RCS Pressure is 34 psig "A" RCS hot Leg Temperature is 180°F "A" RCS cold Leg Temperature is 235°F "8" RCS hot Leg Temperature is 184°F "8" RCS cold Leg Temperature is 237°F Pressurizer water level is 0% RVLlS water level is 53% CETs are 506°F A SI pump is running No RHR Pumps are running "A" RCP Pump is tripped "8" RCP Pump is tripped Cnmt Pressure is 32 psig R-29, Cnmt Radiation Monitor reads 1500 mrem/hr R-30, Cnmt Radiation Monitor reads 1600 mrem/hr Cnmt Sump "An is 78 inches Cnmt Sump "8" is 78 inches "A" Stream Generator Wide Range Water Level is 270 inches "8" Stream Generator Wide Range Water Level is 250 inches "A" Stream Generator Narrow Range Water Level is 0% "8" Stream Generator Narrow Range Water Level is 0% "A" Stream Generator Pressure is 905 psig "8" Stream Generator Pressure is 1150 psig TDAFW Pump is not running "A" MDAFW Pump is running "8" MDAFW Pump is running "A" MDAFW Pump flow is 100 gpm "8" MDAFW Pump flow is 105 gpm 2010 GINNA NRC JPM RA-4, Revision NRC NUREG 1021, Revision 9, Supplement 1

---Appendix C Job Performance Measure Form ES-C-1 Worksheet Ginna Task No.: Task Independently Verify a Critical Rod JPM No.: 2010 GINNA NRC ..IPM Position Calculation SA-1 KiA 2.1.25 (3.9/4.2)

NRC Examiner:

Facility Date: Method of testing: Simulated Actual Performance:

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

Initial

• A plant startup is in progress following a forced outage PCNDR and PPCS are unavailable (It was available at the time the Critical Rod Position was calculated by the Reactor Engineer) See attached Plant Status and History The Reactor Engineer has completed 0-1.2.2 up to step 6.10.2. I will be the Shift Manager. Task Magnitude of errors in the Critical Rod Position calculation determined and all critical tasks evaluated as satisfactory.

Required Calculator General

• 0-1.2.2, Critical Rod Position Calculation, Rev. 06600 COLR, Cycle 35 Boration/Dilution Tables Handouts: Marked up copy of 0-1.2.2, Critical Rod Position Calculation, Rev. 06600. Clean copy of 0-1.2.2, Critical Rod Position Calculation, Rev. 06600 Boration/Dilution Tables COLR, Cycle 35 Initiating The Shift Manager directs you to reperform 0-1.2.2 on a clean copy to obtain an independent verification of the Reactor Engineer's calculations.

If there are differences between your calculations and the Reactor Engineer's calculations, identify and report them to the Shift Manager. 2010 GINNA NRC "IPM SA-1, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: No Validation Time: 45 Minutes 2010 GINNA NRC JPM SA-1, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 7 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a ...J) Start Time: ____ Performance Step: 1 Standard:

EXAMINER CUE: EXAMINER NOTE: Performance Step: 2 Standard:

EXAMINER NOTE: EXAMINER NOTE: 0-1.2.2 Reviews 0-1.2.2 Verifies each step has the required information and is initialed or signed Verifies each recorded value is within the allowable range Hand the Candidate the marked up and clean copy of 0-1.2.2 Only values outside the allowable range are included in this JPM. The Candidate's calculated values may be different than the Reactor Engineer's.

These differences are acceptable as long as they do not affect the Critical Steps. Values outside the allowable range can be identified in any order. 0-1.2.2, Step 6.2.2 DETERMINE Control Rod worth from the position in Step 6.2.1 to the full out position.

USE one of the following methods AND MARK the method NOT used N/A: From the appropriate HFP Integral Rod Worth attachment.

USE Attachment 4, Table 6-6 OR Attachment 5, Table 6-7 OR Attachment 6, Table 6-8 From the PCNDR. * + pcm Verifies Control Rod worth is 129 (+1-1) pcm vice 212 pcm. (v) Records 129 (+1-1 pcm) in Step 6.2.2 This error is derived from the Reactor Engineer using an EOl table vice a MOL table. The allowable band is based just on rounding errors since the number is obtained directly from a table. 2010 GINNA NRC JPM SA-1, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 4 of7 Form ES-C-1 Performance Step: 3 "1/ Standard:

EXAMINER NOTE: EXAMINER NOTE: Performance Step: 4 Standard:

EXAMINER NOTE: PERFORMANCE INFORMATION 0-1.2, step 6.4 Boron Reactivity Identifies the Pretrip/Shutdown Boron Concentration was recorded incorrectly, 910 vice 950. Records 950 in Step 6.4.1 Recalculates and records step 6.4.3 as 366 ppm Recalculates AVG Boron to be 1133 vice 1108 ("1/) Recalculates and records in step 6.4.5 reactivity worth due to boron concentration change. Candidates Value: pcm Allowable Values: -2452 to -2489 pcm There is no error band in the first four bullets since only simple arithmetic is involved.

They are not critical steps since they feed into the reactivity worth due to boron concentration change calculation; a critical step. The allowable values for step 6.4.5 are based on the Candidate recalculating Step 6.4.4, Differential Boron Worth. The acceptable band is -6.7 to -6.8. If the Candidate uses 6.7 they will get -2452 pcm and if they use -6.8 they will get 2489 pcm. 0-1.2.2, Step 6.6 Total Reactivity Change Recalculates and records in step 6.6.6 the total reactivity change. Candidates Value: pcm Allowable Value: 815 pcm to 852 pcm The allowable values are based on the error associated with the calculations that feed into the total reactivity calculation.

2010 GINNA NRC JPM SA-1, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 50f7 Form ES-C-1 Performance Step: 5 Standard:

EXAMINER NOTE: Performance Step: 6 Standard:

EXAMINER NOTE: Terminating Cue: Stop Time: ____ PERFORMANCE 0-1.2.2, Step 6.7.1 Estimated Critical Rod Position Recalculates and records the Critical Rod Position in step 6.9.7.1 Candidates Value: steps Allowable Value: 0 -69 steps to 0 -73 steps The acceptable range is based on the allowable values in step 6.6.6 (Total Reactivity Change). 0-1.2.2, Step 6.9 500 pcm Control Rod Bank Position

• Recalculates and records the + 500 pcm. Candidates Value: steps Allowable Value: 0 -161 steps to 0 -166 steps

• Recalculates and records the -500 pcm. Candidates Value: steps Allowable Value: 0 -17 steps to 0 -21 steps The acceptable range is based on the allowable values in step 6.6.6 (Total Reactivity Change). The critical part of the Performance Step is to correctly identify the +1-500 pcm positions, not identify what number is the + 500 pcm position and what number is the -500 pcm position.

When the Candidate identifies all of the errors: Evaluation on the JPM is complete 2010 GINNA NRC JPM SA-1, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2010 GINNA NRC JPM SA-1 Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: 2010 GINNA NRC JPM SA-1, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 7 of 7 Form ES-C-1 INITIAL INITIATING JPM CUE A plant startup is in progress following a forced outage PCNDR and PPCS are unavailable (It was available at the time the Critical Rod Position was calculated by the Reactor Engineer) See attached Plant Status and History The Reactor Engineer has completed 0-1.2.2 up to step 6.10.2. I will be the Shift Manager. The Shift Manager directs you to reperform 0-1.2.2 on a clean copy to obtain an independent verification of the Reactor Engineer's calculations.

If there are differences between your calculations and the Reactor Engineer's calculations, identify and report them to the Shift Manager. 2010 GINNA NRC JPM SA-1, Revision NRC NUREG 1021, Revision 9, Supplement 1

---Appendix C Job Performance Measure Form ES-C-1 Worksheet Ginna Task No.: Task Perform the Shift Manager Review JPM No.: 2010 GINNA NRC JPM of the 0-6.13, DAILY SA-2 SURVEILLANCE LOG KIA 2.1.18 (3.6/3.8)

NRC Examiner:

Facility Date: Method of testing: Simulated Actual Performance:

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

Initial Conditions:

• It is 6/21/2010 at 0900 Reactor power has been stable at 100% for the past 50 days following a refueling outage. An A-52.4 has been submitted on CETs A-7, E-4, E-10 and H-13 SI Header Pressure is outside the acceptable boundaries.

Engineering has been informed and is investigating Yesterday afternoon S-9J, BLENDING TO RWST, was completed. At 0600 today Maintenance has isolated AOV-112B, Emergency Makeup RWST to Charging Pump, by plaCing a freeze seal between V-357, RWST Suction Check Valve to Charging Pumps, and 112B due to suspected leakage by AOV-112B.

Task Standard:

Identify the three errors and perform all critical tasks satisfactory.

Required Materials:

None General

References:

• 0-6.13, Daily Surveillance Log, Rev. 17400 CNG-OP-3.01-1000, Reactivity Management, Rev. 00501 Technical Requirements Manual, Revision 39 Control Room Curve Book. P&ID 33013-1261, Revision 38 P&ID 33013-1265, Sheet 2, Revision 23. Handouts:

• Attachment 1 of 0-6.13, Daily Surveillance Log, Rev. 17400 0-6.13, Daily Surveillance Log, Rev. 17400 (If requested) CNG-OP-3.01-1000, Reactivity Management, Rev. 00501 2010 GINNA NRC JPM SA-2, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Job Performance Measure Form ES-C-1 Initiating Cue: Time Critical Task: Validation Time: Worksheet Two consecutive RCS chemistry reports with RCS Boron concentration. Technical Requirements Manual, Revision 39 Control Room Curve Book. P&ID 33013-1261, Revision 38 P&ID 33013-1265, Sheet 2, Revision 23. You are the Shift Manager on the day shift. Review 0-6.13, DAILY SURVEILLANCE LOG -ATTACHMENT 1, Modes 1, 2, and 3. If any problem(s) are identified, then explain all of the problem(s) in detail AND any required actions. If actions of other individuals are required, describe their required actions as well. No Minutes 2010 GINNA NRC JPM SA-2, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 11 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a ") Start Time: ____ EXAMINER NOTE: Initially hand the Candidate a copy of Attachment 1, MODES 1, 2 and 3 of 0-6.13, Daily Surveillance Log. Hand out the remaining references as the Candidate requests them. EXAMINER NOTE: Only values outside the allowable range are included in this JPM. Values outside the allowable range can be identified in any order. Performance Step: 1 Standard:

Comment: Performance Step: 2 Standard:

EXAMINER NOTE: 0-6.13, Daily Surveillance Log, ATTACHMENT 1, MODES 1, 2, AND 3. Reviews 0-6.13, Daily Surveillance Log, ATTACHMENT 1, MODES 1, 2, AND 3

• Verifies each initial block is filled and initialed

• Verifies each recorded value is within the allowable range 0-6.13, Daily Surveillance Log, ATTACHMENT 1, MODES 1, 2, AND 3, Boric Acid Tank Levels Per Step 6.4.2.2

• Identifies both Boric Acid Tank Levels are less than 83%

• Refers to Step 6.4.2.2 Performance Steps 2 and 5 are associated with the BAST tank found less than the minimum requirement.

2010 GINNA NRC JPM SA-2, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 4 of 11 Form ES-C-1 ..J Performance Step: 3 Standard:

EXAMINER CUE: EXAMINER NOTE: EXAMINER NOTE: PERFORMANCE INFORMATION 0-6.13, Daily Surveillance Log, Step 6.4.2.2 VERIFY inservice BASTs meet the Minimum VolumelTemperature concentration requirements of TRM Table 3.1.1-1 using the most current BAST samples. Refers to page 7 of 10 of the 0-6.13 for BAST Boron concentration or the Chemistry data handout to determine BAST Boron concentration (..J) Determines the number of gallons in the BAST using the curve book. Candidate Value: ____ Gallons Allowable Values: 4320 gallons to 5040 gallons (..J) Using TRM Table 3.1.1-1, Boric Acid Storage Tank Requirements determines the Minimum Volume in the BAST is 5210 gallons References TSR 3.1.1.2 When the Candidate determines the need for the Chemistry data, provide them with a copy. At your discretion you may have them describe how to obtain the current Chemistry data and then hand them a copy. The following explanation is the basis for the allowable values. EXisting BAST volume is calculated using the following formula: [<<% on MCB/100) x 3460) + 444] X 2. Using 60% for both BASTs, the Candidate will calculate 5040 gallons. If the Candidate uses 36 gallons per %, (since the curve book has 3600 gallons as the capacity of a BAST) then the calculation will be 4320 gallons. This calculation is a critical step to prevent the Candidate from simply guessing that the level in the BAST is less than the minimum allowable level. The Candidate will use the BAST Boron Concentration to determine the concentration is 10000 to 11000 ppm. Then, using Table 3.1.1-1, determine that the minimum required volume is 5210 gallons. 2010 GINNA NRC JPM SA-2, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 5 of 11 Form ES-C-1 Performance Step: 4 Standard:

Comments:

'" Performance Step: 5 Standard:

EXAMINER CUE: PERFORMANCE INFORMATION Technical Reference Manual, Revision 39, TSR 3.1.1.2 -NOTE-Only required to be performed when complying with TR 3.1.1.b. Verify boric acid storage tank level is within limit. Determines that the plant is not complying not with TR 3.1.1.a. since there is not a flowpath from the RWST to the suction of the Charging Pumps. Proceeds to TR 3.1.1 Technical Reference Manual, Revision 39, TR 3.1.1 Two boron injection subsystems shall be OPERABLE with each subsystem containing one charging pump and either a or b below: A flowpath from the RWST; or A flowpath containing an OPERABLE boric acid transfer pump and a boric acid storage tank which meets the limits specified in Table TR 3.1.1-1. Enters TR 3.1.1, Condition A and E: Initiates action to restore at least one boron injection subsystem to OPERABLE status. The Candidate may either inform the Control Room Supervisor to declare the BAST inoperable or they may initiate action to complete an A-52.12. Either action is acceptable.

2010 GINNA NRC JPM SA-2, Revision NRC NUREG 1021, Revision 9, Supplement 1

-I Appendix Page 6 of 11 Form ES-C-1 Performance Step: 6 Standard:

EXAMINER CUE: Performance Step: 7 Standard:

EXAMINER NOTE: PERFORMANCE INFORMATION 0-6.13, Daily Surveillance Log, ATTACHMENT 1, MODES 1, 2, AND 3, SI Accumulator SI Accumulator 1 Al1 B Maintain>730 and <760 Identifies SI Accumulator pressure is less than 730 PSIG Refers to Step 6.2.14 (-I) Enters LCO 3.5.1, Accumulators

-Condition B; Restore the Accumulator to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (-I) Enters LCO 3.5.1, Accumulators

-Condition D; Enter LCO 3.0.3 immediately. (-I) Enters LCO 3.0.3 The Candidate may either inform the Control Room Supervisor to declare the SI Accumulator inoperable or they may initiate action to complete an A-52.4. Either action is acceptable.

0-6.13, Daily Surveillance Log, ATTACHMENT 1, MODES 1, 2, AND 3, RCS Boron Changes < 15 ppm RCS Boron Changes < 15 ppm (CNG-OP-3.01-1000) Identifies RCS Boron Concentration has changed by greater than 15 ppm. Refers to CNG-OP-3.01-1000 JPM Performance Steps 8 and 9 are associated with the Reactivity Anomaly (CNG-OP-3.01-1000).

2010 GINNA NRC JPM SA-2, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 7 of 11 Form ES-C-1 Procedure Note Procedure Note " Performance Step: 8 Standard:

EXAMINER CUE: EXAMINER CUE: EXAMINER NOTE: PERFORMANCE INFORMATION CNG-OP-3.01-1000, Attachment 3, Step 7.a. The limit for the change in boron concentration between two full power steady-state condition samples of the RCS is 15 ppm. This limit is based upon a normal sampling frequency with no more than two days between sample dates. Injection of significant amounts of boric acid from the BASTs to the RCS may lead to an apparent reactivity anomaly. This may occur due to the BAST boron having significantly higher B-1 0 isotopic concentration than the RCS boron. The apparent reactivity anomaly will be evident by the RCS boron concentration after the addition being lower than would be expected due to normal daily fuel depletion. The Head Control Operator will compare each full power steady-state RCS boron sample data with the previous full power steady state condition data. (1) IF the difference is 15 ppm or greater, THEN the following SHALL be performed: Notify the SM Request the analysis be repeated. Compares last two RCS boron samples, determines they are 17 ppm apart. (") Directs Chemistry to repeat the RCS boron analysis.

If the Candidate informs you that they would have the Head Control Operator re-compare steady state RCS boron analyses, inform them the HCO is not available to perform the requested actions and to perform the required actions themselves.

If the Candidate requests the last two steady state RCS boron analyses, provide them with the 6120 and 6119 Chemistry Data Sheets. When the Candidate directs Chemistry to repeat the RCS boron analysis, provide a repeat back. This step is identified as a Critical Step to ensure prompt and proper action is initiated; not just submitting a Condition Report and waiting for someone else to follow up. 2010 GINNA NRC JPM SA-2, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 8 of 11 Form ES-C-1 PERFORMANCE

>/ Performance Step: 9 Standard:

CNG-OP-3.01-1000, Attachment 3, Step 7.b. Upon notification of 15 ppm limit being exceeded the SM will perform the following: Initiate a CR (2) IF there is indication of a reactivity change, commence an investigation as to the cause of reactivity IF the cause is determined quickly, THEN the cause will be noted on the Daily Chemistry Report and on the CR under immediate actions taken. IF the cause cannot be determined quickly and a second analysis confirms the condition, THEN the SM will perform the following: Request the STA to evaluate information on exceeding limit and cause. STA may request additional technical assistance or information and will determine if additional actions are required. Request the Reactor Engineer or alternate to report of the plant, to assist in investigation Request the General Supervisor

-Chemistry or alternate, to report to the plant to investigate sampling and analysis methods. Inform the Manager -Nuclear Operations or alternate of the investigation.

He will determine if the Plant Operations Review Committee should be called into session. Specifies that a CR must be submitted Analyzes to determine if there is an indication of a reactivity change (>/) Commences an investigation as to the cause of the reactivity change Requests the STA to evaluate information on exceeding the limit and cause Requests the Reactor Engineer or alternate to assist in the investigation Requests the General Supervisor

-Chemistry or alternate to investigate Informs the Manager -Nuclear Operations (>/) Request samples be taken at thirty minute intervals.

2010 GINNA NRC JPM SA-2, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 9 of 11 Form ES-C-1 PERFORMANCE EXAMINER If the Candidate asks, inform them "there is indication of a reactivity change and the cause can not be determined quickly." Terminating After the applicant returns the log: Evaluation on this JPM is complete.

Stop Time: ____ 2010 GINNA NRC JPM SA-2, Revision NRC NUREG 1021, Revision 9, Supplement 1

---

Appendix C Page 10 of 11 Form ES-C-1 VERIFICATION OF Job Performance Measure No.: 2010 GINNA NRC ..IPM SA-2 Examinee's Date Facility Number of Time to Question Result SAT Examiner's Signature: 2010 GINNA NRC JPM SA-2, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 11 of 11 Form ES-C-1 INITIAL INITIATING JPM CUE SHEET It is 6/21/2010 at 0900 The reactor power has been stable at 100% for the past 50 days following a refueling outage. An A-52.4 has been submitted on CETs A-7, E-4, E-10 and 13 SI Header Pressure is outside the acceptable boundaries.

Engineering has been informed and are investigating At 0600 today Maintenance has isolated AOV-112B, Emergency Makeup RWST to Charging Pump, by placing a freeze seal between V-357, RWST Suction Check Valve to Charging Pumps, and AOV-112B due to suspected leakage by AOV-112B.

You are the Shift Manager on the day shift. Review 0-6.13, DAILY SURVEILLANCE LOG -ATTACHMENT 1, Modes 1, 2, and 3. 2010 GINNA NRC JPM SA-2, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Job Performance Measure Form ES-C-1 Ginna Task No.: Task Perform a Safety Function JPM No.: 2010 GINNA NRC JPM Determination SA-3 KIA 2.2.37 (3.6/4.6)

NRC Examiner:

Facility Date: Method of testing: Simulated Actual Performance:

x Classroom X Simulator

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

Initial Conditions: The Plant is stable at 1 00% power. Date: 6/21/2010 Time: 1210 The following equipment is currently Out of Service: D Service Water Pump (lCO 3.7.8, Condition A was entered today at 1000 and all necessary paperwork has been completed.) B Containment Recirculation Fan (lCO 3.6.6, Condition D was entered on 6/18/2010 at 1200 and all necessary paperwork has been completed.) Battery Charger B for maintenance.

It is expected to be returned to service 6/22/2010 at 1200. At 1200 today Battery Charger B 1 was taken out of service to due a ground. Condition Report CR-201 0-006284 has been initiated for the B 1 Battery Charger ground. The crew has taken the appropriate action to stabilize the plant. Task Standard:

Properly fill out A-52.4 through Step 3.2.6 Required Materials:

None General

References:

A-52.4, Control of Limiting Conditions for Operating EqUipment, Rev. 13900 A-52.3, Safety Function Determination Program, Rev. 5 Technical Specifications Amendment 109 2010 GINNA NRC JPM SA-3, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Handouts:

Initiating Cue: Time Critical Task: Validation Time: Job Performance Form Attachment 1 and 2 of A-52.4, Control of Limiting Conditions for Operating Equipment, Rev. 13900 A-52.4, Control of Limiting Conditions for Operating Equipment, Rev. 13900 A-52.3, Safety Function Determination Program, Rev. 5 Technical Specifications Amendment 109 Fill out an A-52.4, Attachment 1, through step 3.2.6, and Attachment 2 for the given plant conditions.

The EIN for Battery Charger B1 is BYCB1. A "what if' risk assessment in EOOS has been ran and it was determined the highest PRF color is yellow and the highest top level system status color is yellow. No 12 minutes 2010 GINNA NRC JPM SA-3, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 10 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a ..J) Start Time: ____' Performance Step: 1 Standard:

EXAMINER NOTE: Performance Step: 2 Standard:

Performance Step: 3 Standard:

Comment: Technical Specifications Reviews D Service Water Pump LCD Determines the plant is in LCD 3.7.8, Service Water System, Condition A, with a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time. Determines the plant has until 6/24/2010 at 1000 before having to complete Required Action A.1 It is not critical for the Candidate to complete the performance steps in the listed order. The order listed is the order the validators performed the steps. Technical Specifications Reviews 8 Containment Recirculation Fan LCD Determines the plant is in LCO 3.6.6, Containment Spray (CS), Containment Recirculation Fan Cooler (CRFC), and NaOH Systems, Condition D, with a 7 day completion time. Determines the plant has until 6/25/2010 at 1200 before having to complete Required Action D.1. Technical Specifications Determines 81 Battery Charger LCO Determines the plant is in LCD 3.8.4, ECCS -Distribution System -MODES 1, 2, 3, and 4. Determines the plant has 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (6/21/2010 at 1400) before having to complete Required Action A.1 2010 GINNA NRC JPM SA-3, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 10 Form ES-C-1 PERFORMANCE Performance Step: 4 Standard:

Comment: Performance Step: 5 Standard:

Comments:

Performance Step: 6 Standard:

EXAMINER NOTE: EXAMINER NOTE: A-52.4, Attachment 1 Completes Steps 3.2.1 through 3.2.3 of A-S2.4, Attachment

1.

• See attached KEY.

• Proceeds to Step 3.2.4 A-52.4, Attachment 1, Step 3.2.4 Perform Loss of Safety Function Determination PER Attachment 2

• Proceeds to Attachment 2 A-52.4, Attachment 2 Step 1.0 Have any of the following supporting system LCOs been entered? YES/NO

• Circles YES in Step 1.0

• Initials to the right of LCOs 3.6.6,3.7.8 and 3.8.4

• Proceeds to Step 2.0 Attachment 2 of A-52.4 is a worksheet to aid the operator in performing the Safety Function Determination.

It is expected the Candidate will fill out Attachment 2 in the same manner as the key, but there may be slight differences, which is acceptable.

For step one the candidate must realize three support system LCOs have been entered: B Containment Recirculation Fan (3.6.6), D Service Water Pump (3.7.8) and the B1 Battery Charger (3.8.4). 2010 GINNA NRC JPM SA-3, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 5 of 10 Form ES-C-1 Performance Step: 7 Standard:

EXAMINER NOTE: " Performance Step: 8 Standard:

EXAMINER CUE: PERFORMANCE INFORMATION A-52.4, Attachment 2 Step 2.0 Has only one (1) LCO been entered (Le., total # of LCOs in effect is only 1)? YES/NO Circles NO in Step 2.0 Determines a loss of safety function evaluation is required Proceeds to Step 3.0 Since there are multiple LCOs entered and three of them are supporting system LCOs, there is a potential loss of safety function.

A-52.4, Attachment 2 or A-52.3 Step 3.0 Using the attached Loss of Safety Function Matrix, determine if any combination of LCO's has the potential to result in a loss of safety function.

Only combinations which are not shaded in the box require further evaluation (Le., "empty" boxes). Do any combination of LCOs result in a potential loss of safety function?

YES/NO References either Attachment 2 of A-52.4 or Table 1 of A-52.3 Determines a potential loss of safety function exists and further evaluation is required as indicated by either the empty box in Attachment 2 of A-52.4 or Table 1 "Supported Systems LCO(s)" column of A-52.3. <") Circles NO in Step 3.0 Proceeds to Attachment 1 If the Candidate does not circle NO in step 3.0 on Attachment 2, ask the follow up question after both Attachments are submitted "Explain the flowpath through Attachment 2." 2010 GINNA NRC JPM SA-3, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Performance Step: 9 Standard:

Comment: PERFORMANCE INFORMATION A-52.4, Attachment 2 or A-52.3 If YES, a potential loss of safety function exists. Therefore, perform the following: Verify that at least one train of the affected functions is available to mitigate the accidents listed in the Applicable Safety Analysis bases section of the LCO(s).

Refer to A-52.3 for additional guidance.

If loss of safety function exists, then enter all affected LCOs or LCO 3.0.3. Uses Table 1 of A-52.3 and determines cascading is not allowed for LCO 3.8.4 References LCO 3.8.4 and determines Conditions C is applicable. Determines the plant must enter LCO 3.8.4, Required Actions C.1 Proceeds to Substep B. 2010 GINNA NRC JPM SA-3, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 10 Form ES-C-1 PERFORMANCE INFORMATION A*S2.4, Attachment 2 and A*S2.4, Attachment 1, Step 3.2.4 1/ Performance Step: 10

• If YES, a potential loss of safety function exists. Therefore, perform the following:

B. If a loss of safety function does not exist, ensure that multiple support system inoperablilities do not result in an inappropriate extension of the supported system's Completion Time. If the supported system inoperablility would be extended beyond that allowed by its specific LCO Completion Time, enter the supported system Conditions and Required Actions immediately upon exiting of the first support system LCO that no longer applies. Standard:

• Determines Condition A of LCO 3.8.4 Required Action statement does not extend already entered LCOs. * (1/) Initials Step 3.2.4 of A-52.4, Attachment

1. EXAMINER NOTE: LCO 3.8.4 Required Action statement A requires B1 Battery Charger to be restored by 1400 on 6/21/2010, while the next Required Action statement does not require completion until 1000 on 6/24/2010, therefore no inappropriate time extension will occur. 2010 GINNA NRC JPM SA-3, Revision NRC NUREG 1021, Revision 9, Supplement 1

-I Appendix C Performance Step: 11 Standard:

EXAMINER CUE: Performance Step: 12 Standard:

EXAMINER NOTE: Terminating Cue: Stop Time: ____ Page 8 of 10 Form ES-C-1 PERFORMANCE INFORMATION A-52.4, Step 3.2.5 PERFORM a "what if' risk assessment in EOOS for inoperable equipment lAW Step 3,2.5. 3.2.5.8 EOOS highest PRF color: green 0 I yellow 0 I orange 0 I red 0 EOOS highest top level system status color: green 0 I yellow 0 I orange 0 I red 0 Marks both "yellow" boxes in Step 3.2,5.8 Initials Step 3.2.5 Enters LCO 3.8.4, Required Actions A.1 When the Candidate gets to Step 3.2.5, inform them the "what if" risk assessment in EOOS has been performed and the highest PRF color is YELLOW and the highest top level system status color is YELLOW. A-52.4, Step 3.2.6 REQUIRED ACTIONS: Fills out the REQUIRED ACTIONS Table lAW the attached key See the attached Key. After the REQUIRED ACTION Table is completed:

Evaluation on this JPM is complete.

2010 GINNA NRC JPM SA-3, Revision NRC NUREG 1021, Revision 9, Supplement 1

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Appendix C Page 9 of 10 Form ES-C-1 VERIFICATION OF Job Performance Measure No.: 2010 GINNA NRC JPM SA-3 Examinee's Date Facility Number of Time to Question Result: SAT Examiner's Signature: 2010 GINNA NRC JPM SA-3, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 10 of 10 Form ES-C-1 INITIAL INITIATING JPM CUE The Plant is stable at 100% power. Date: 6/21/2010 Time: 1210 The following equipment is currently Out of Service: D Service Water Pump (LCO 3.7.8, Condition A was entered today at 1000 and all necessary paperwork has been completed.) B Containment Recirculation Fan (LCO 3.6.6, Condition D was entered on 6/18/2010 at 1200 and all necessary paperwork has been completed.) Battery Charger B for maintenance.

It is expected to be returned to service 6/22/2010 at 1200. At 1200 today Battery Charger B 1 was taken out of service to due a ground. Condition Report CR-2010-006284 has been initiated for the B1 Battery Charger ground. The crew has taken the appropriate action to stabilize the plant. Fill out an A-52.4, Attachment 1, through step 3.2.6, and Attachment 2 for the given plant conditions.

The EIN for Battery Charger B1 is BYCB1. A "what if' risk assessment in EOOS has been ran and it was determined the highest PRF color is yellow and the highest top level system status color is yellow. 2010 GINNA NRC JPM SA-3, Revision NRC NUREG 1021, Revision 9, Supplement 1

---Appendix C Page 1 of 11 Form ES-C-1 PERFORMANCE INFORMATION Facility: Task No.: Task Respond to a Contaminated Injured No.: 2010 GINNA NRC JPM Person SA-4 KIA 2.3.14 (3.4/3.8)

NRC Examiner:

Facility Date: Method of testing: Simulated Performance:

Actual Performance:

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

Initial

• The Reactor is operating at 100% power, Steady-State, MOL. The Shift Manager and Shift Technical Advisor are outside the control room at a meeting with Plant Management. 15 minutes ago an Auxiliary Operator called the Control Room and informed them of the following: A Chemist received serious steam burns while performing RCS sampling activities in the sample room. The sampling system has been stabilized and no radioactive releases are in progress. The Chemist is in pain. The Chemist has been determined to be radioactively contaminated and is enroute to Rochester General Hospital by ambulance.

Mercy Flight services are not required.

Task Correctly identifies all required onsite and offsite notifications and associated time limits. Required None General

References:

A-7, Procedure for Handling Injuries/Medical Emergencies at Ginna Station, Rev. 10200

• EPIP 1-5, Notifications, Rev. 08200 2010 GINNA NRC JPM SA-4, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 2 of 11 Form ES-C-1 Handouts:

Initiating Cue: Time Critical Task: Validation Time: PERFORMANCE INFORMATION CNG-NL-1.01-1004, REGULATORY REPORTING, Rev. 00300 OPG-NOTIFICATION, Revision 02200 A-7, Procedure for Handling Injuries/Medical Emergencies at Ginna Station, Rev. 10200 EPIP 1-5, Notifications, Rev. 08200 CNG-NL-1.01-1004, REGULATORY REPORTING, Rev. 00300 OPG-NOTIFICATION, Revision 02200 Determine and write down on the paper provided the following information for the event described in the Initial Conditions:

1. All onsite and offsite notifications required by the Control Room during and after the event. Include any time limitations associated with the notification(s), if applicable.

2. All announcements that must be made and personnel that must be dispatched by the Control Room to ensure the Chemist receives prompt first aid and appropriate medical attention.

For announcements that must be made, include all information required in the announcement.

No 14 Minutes 2010 GINNA NRC JPM SA-4, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 11 Form ES-C-1 PERFORMANCE (Denote Critical Steps with a "./) Start Time: _____' EXAMINER CUE: When the Candidate determines the need for any procedure, provide them with a copy. At your discretion you may have them describe how to obtain the current revision of the procedure prior to handing them a copy. "./ Performance Step: 1 Standard:

Comment: "./ Performance Step: 2 Standard:

A-7, Attachment 1 Upon notification of a Medical Emergency:

If the report is for any person experiencing the following problems, immediately contact Wayne County Emergency Dispatch by calling 769-911 and request an ambulance:

• Unconscious

• Chest Pains

• Having difficulty breathing

• Having excessive bleeding Contacts Wayne County Emergency (Calls 769-911) to request an ambulance A-7, Attachment 1 Make an announcement over the PA and have the Medical Emergency Response Team respond. An announcement is made to include the following:

• Intermediate Building (Hot Side)

• Medical Emergency

• Emergency medical team respond

• All others remain clear of the area Comment: 2010 GINNA NRC JPM SA-4, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 11 Form ES-C-1 Procedure Note: ..J Performance Step: 3 Standard:

Comment: ..J Performance Step: 4 Standard:

Comment: PERFORMANCE INFORMATION A-7, Attachment 1 Text message to "Ginna Medical Responders" will provide notification to Emergency Medical Responders outside of the Operations Department.

These personnel are an additional resource for first aid response . Text message "Ginna Medical Responders." Sends a text message to all Ginna Medical Responders.

A-7, Attachment 1 The Control Room should dispatch the Fire Brigade Captain to the scene, (if within the protected area) to assist with communication, ensure plant equipment is secure, and to report to the Control Room if any additional needs arise, or conditions change. Contacts and dispatches Fire Brigade Captain to the scene. 2010 GINNA NRC JPM SA-4, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 11 Form ES-C-1 PERFORMANCE INFORMATION A-7, Appendix "A", Step 3 V Performance Step: 5 Standard:

Comment: V Performance Step: 6 Standard:

Comment: Inform the Wayne County Emergency Dispatcher of the number of people injured and the extent of injuries, if known For contaminated patients or if there are multiple patients, alert the hospital to begin arrangements to receive Ginna Station patient(s).

Rochester General Hospital or Newark Wayne Community Hospital.

Request to speak to the Emergency Department Triage Nurse and report the accident and any pertinent information.

Give the nurse a phone number to call back to confirm the emergency.

The hospital will not initiate their plan unless the can confirm there is an actual emergency.

Upon receipt of the confirming telephone call, give the number of casualties, whether they are contaminated or not and any other pertinent information request by the Triage Nurse. Informs the Wayne County Emergency Dispatcher that one person is injured and contaminated. Calls Rochester General Hospital's Emergency Department A*7, Appendix "A", Step 6 Notify the following personnel AS SOON AS POSSIBLE, during actual or drill conditions.

a) Notify Industrial Safety & Health Wayne Fitzgerald ext. 5215 (Director, Safety &Health) Notify GS Radiation Protection in cases of major contamination, exposures or any injury occurring within the RCA. Fred Mis Notifies Industrial Safety & Health, Wayne Fitzgerald. Notifies GS Radiation Protection, Fred Mis. 2010 GINNA NRC JPM SA-4, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 6 of 11 Form ES-C-1 " Performance Step: 7 Standard:

Comment: " Performance Step: 8 Standard:

Comment: PERFORMANCE INFORMATION EPIP 1-5, Attachment 5, Steps 2 and 3 2. When offsite assistance has been requested, activate:

-Security -Ginna Management Emergency Preparedness Contact the NRC resident inspector Contacts Security Notifies Ginna Management Notifies Emergency Preparedness Notifies NRC resident inspector.

OPG-NOTIFICATION, ATTACHMENT 1

• Ops

• Entry into A-7 HANDLING INJURIES/MEDICAL EMERGENCIES AT GINNA Sr. VP & CNO STATION procedure Entry into EOP/AOP or ER procedures (not including AR proecedures) Entry into S-12.2, OPERATOR ACTION IN THE EVENT OF INDICATION OF SIGNIFICANT INCREASE IN LEAKAGE Notifies Ops Management Notifies Sr. VP &CNO (Senior Management) 2010 GINNA NRC JPM SA-4, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 9 Standard:

Comment: Procedure Note: Procedure Note: ,j Performance Step: 10 Standard:

Comment: Terminating Cue: Stop Time: ____ Page 7 of 11 Form ES-C-1 PERFORMANCE INFORMATION CNG-NL-1.01-1004, Step Any individual who has a reportability concern Notify their supervisor Initiate a Condition Report (CR). Promptly notify the Shift Manager/Report Sponsor of reportability Notifies the Shift Manager Submits a Condition Report CNG-NL-1.01-1004, Step 5.2 and Attachment 2 This section describes the process for determining whether an event or condition meets any of the criteria specified in Attachment 2, Immediate Notification and Written Reporting Requirements.

Complete notifications of an Emergency Event form the Control Room, including updates and reclassifications, are made according to each station's Emergency Plan implementing procedures.

A. Upon becoming aware of a potentially reportable event or concern, the Shift Manager shall: Review Attachment 2 to determine if an immediate Emergency Notification System (ENS) report to the Nuclear Regulatory Commission (NRC) is required, if a written report is required, or if a report to another agency is required.

Determines that an a-hour prompt report to the NRC is required.

After the reporting requirement is determined:

Evaluation on this JPM is complete.

2010 GINNA NRC JPM SA-4, Revision NRC NUREG 1021, Revision 9, Supplement 1

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Appendix C Page 8 of 11 Form ES-C-1 VERIFICATION OF Job Performance Measure No.: 2010 GINNA NRC ..IPM SA-4 Examinee's Date Facility Number of Time to Question Result: SAT Examiner's Signature: 2010 GINNA NRC JPM SA-4, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 9 of 11 Form ES-C-1 INITIAL INITIATING JPM CUE The Reactor is operating at 100% power, Steady-State, MOL. The Shift Manager and Shift Technical Advisor are outside the control room at a meeting with Plant Management. 15 minutes ago an Auxiliary Operator called the Control Room and informed them of the following: A Chemist received serious steam burns while performing RCS sampling activities in the sample room. The sampling system has been stabilized and radioactive releases are in The Chemist is in pain. The Chemist has been determined to be radioactively contaminated and is enroute to Rochester General Hospital by ambulance.

Mercy Flight services are not required.

Determine and write down on the paper provided the following information for the event described in the Initial Conditions:

1. All onsite and offsite notifications required by the Control Room during and after the event. Include any time limitations associated with the notification(s), if applicable.

2. All announcements that must be made and personnel that must be dispatched by the Control Room to ensure the Chemist receives prompt first aid and appropriate medical attention.

For announcements that must be made, include all information required in the announcement.

2010 GINNA NRC SA-4, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 10 of 11 Form ES-C-1 JPM CUE CANDIDATE NAME: ___________List all onsite and offsite notifications required by the Control Room during and after the Include any time limitations associated with the notification(s), if 2010 GINNA NRC JPM SA-4, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 11 of 11 Form ES-C-1 JPM CUE SHEET CANDIDATE NAME: ___________

_ Describe all announcements that must be made and personnel that must be dispatched by the Control Room to ensure the Chemist receives prompt first aid and appropriate medical attention.

For announcements that must be made, include all information required in the announcement.

2010 GINNA NRC JPM SA-4, Revision NRC NUREG 1021, Revision 9, Supplement 1

---Appendix Job Performance Measure Form ES-C-1 Facility: Task No.: Task Title: Determine the EAL for an Event 2010 GINNA NRC SA-5 KIA

Reference:

2.4.41 (2.9/4.6)

NRC Examiner:

Facility Date: Method of testing: Simulated Actual Performance:

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

Initial

• A reactor trip occurred when off-site power was lost 15 minutes ago. Both diesel generators failed to start automatically and neither will start from the Main Control Board. Operators and maintenance personnel have been dispatched to attempt to start them locally. The operating crew is in ECA-O.O, LOSS OF ALL AC POWER, at Step 9. RG&E reports that the cause of the loss of circuits 767 and 7T is unknown at this time and approximately 2 to 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> will be required to perform necessary switching operations to restore the circuits. The STA is monitoring the CSFST's for information only. There is no ORANGE or RED Path. No SI Signal is present. The TDAFW Pump is operating and feeding both SG's. RCS Pressure is 2090 psig, decaying very slowly. RCS Temperature and Pressurizer Level are stable near no load values. There are no RMS alarms. No release is in progress or anticipated.

Task Correct EAL documented within 15 minutes and EPIP 1-5, Attachment 3A completed and handed to the communicator within 15 minutes. Required None General

References:

EPIP 1-0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION, Revision 04500

• EPIP 1-5, NOTIFICATIONS, Revision 08200 2010 GINNA NRC JPM SA-5, Revision NRC NUREG 1021, Revision 9, Supplement 1

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_..__.__.._---------------

Appendix Job Performance Measure Form ES-C-1 Worksheet Handouts:

Initiating Cue: Time Critical Task: Validation Time: EPIP 1-0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION, Revision 04500 EPIP 1-5, NOTIFICATIONS, Revision 08200 Meteorological Data from the Plant Processing Computer.

You are the Shift Manager. First, classify the event described in the initial conditions.

Record the EAL Number for the classification on the sheet provided and return it to me. Second, fill out Attachment 3a of EPIP 1-5, NOTIFICATIONS.

When you have completed the portion required to be filled out by the Shift Manager, return the form to me. The time critical task clock starts after you have reviewed the INITIAL CONDITIONS and indicate that you are ready to begin. Yes 12 Minutes 2010 GINNA NRC ..IPM SA-5, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP N/A 2010 GINNA NRC JPM SA-5, Revision NRC NUREG 1021, Revision 9, Supplement 1

---Appendix Page 4 8 Form VERIFICATION OF (Denote Critical Steps with a ..J) Start Time: ____ ..J Performance Step: 1 Standard:

EXAMINER NOTE: EPIP 1-0, Step 6.1 In the event of an abnormal condition the Control Room Personnel will Perform the immediate responses defined in the appropriate plant procedures. Identify the initiating conditions using either the guidelines of the EAL wall chart or Attachment 1 of this procedure. Implement applicable Emergency Plan procedures 6.1.3.1 EPIP 1-4, General Emergency 6.1.3.2 EPIP 1-3, Site Area Emergency Proceeds to either the EAL wall chart or Attachment 1 (\I) Selects EAL 6.1.4 (SAE) -Loss of both trains of AC busses for greater than 15 minutes (Trip from Mode 1 and/or currently in Mode 3) within 15 minutes after starting the classification.

When the candidate indicates he/she is ready to Display the JPM Start Time clearly in the Log the Classification Start Time __Log the Classification Stop Time __Classification Stop Time ____ -Classification Time The Classification Stop Time is also the Time Critical Start Time for the notification 2010 GINNA NRC JPM SA-5, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 5 of 8 Form ES-C-1 Procedure " Performance Step: Standard:

EXAMINER NOTE: Performance Step: 3 Standard:

EXAMINER NOTE: Terminating Cue: Stop Time: ____ VERIFICATION OF COMPLETION EPIP 1-5, 6.0 The Shift Manager/Emergency Coordinator/Recovery Manager may delegate these actions to any available individual, except as noted below. 6.0 Actions Shift Manager, Emergency Coordinator, Recovery Manager 6.1.1 When the Control Room has Command and Control, the Emergency Coordinator is responsible for filling out Part I of Attachment 3a (either manually or electronically).

This action shall not be delegated Properly fills out EPIP-1-5, Attachment 3A -NEW YORK STATE RADIOLOGICAL EMERGENCY DATA FORM A KEY is attached for your use. EPIP 1-5, Attachment 3A Notify off-site authorities.

Hand Attachment 3A to the examiner no later than 15 minutes after the Classification Time Critical Stop Time. Log the Notification Time Critical Task Stop Time ___ Notification Stop Time ___-Classification Stop Time ---= After Attachment 3A is handed to the examiner:

Evaluation on this JPM is complete.

2010 GINNA NRC JPM SA-5, Revision NRC NUREG 1021, Revision 9, Supplement 1

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Appendix C Page 6 of 8 Form ES-C-1 VERIFICATION OF Job Performance Measure No.: 2010 GINNA NRC ..'PM SA-5 Examinee's Date Facility Number of Time to Question Result: SAT Examiner's Signature: 2010 GINNA NRC JPM SA-5, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 7 of 8 Form ES-C-1 INITIAL INITIATING JPM CUE A reactor trip occurred when off-site power was lost 15 minutes ago. Both diesel generators failed to start automatically and neither will start from the Main Control Board. Operators and maintenance personnel have been dispatched to attempt to start them locally. The operating crew is in ECA-O.O, LOSS OF ALL AC POWER, at Step 9. RG&E reports that the cause of the loss of circuits 767 and 7T is unknown at this time and approximately 2 to 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> will be required to perform necessary switching operations to restore the circuits. The STA is monitoring the CSFST's for information only. There is no ORANGE or RED Path. No SI Signal is present. The TDAFW Pump is operating and feeding both SG's. RCS Pressure is 2090 psig, decaying very slowly. RCS Temperature and Pressurizer Level are stable near no load values. There are no RMS alarms. No release is in progress or anticipated.

You are the Shift Manager. First, classify the event described in the initial conditions.

Record the EAL Number for the classification on the sheet provided and return it to me. Second, fill out Attachment 3a of EPIP 1-5, NOTIFICATIONS.

When you have completed the portion required to be filled out by the Shift Manager, return the form to me. The time critical task clock starts after you have reviewed the INITIAL CONDITIONS and indicate that you are ready to begin. 2010 GINNA NRC SA-5, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 8 Form ES-C-1 JPM CUE SHEET CANDIDATE NAME: __________

_ EAL Number: ____ 2010 GINNA NRC JPM SA-5, Revision NRC NUREG 1021, Revision 9, Supplement 1

--Appendix C Job Performance Measure Form ES-C-1 Worksheet Ginna Task No.: Task Start an Emergency Diesel No.: 2010 GINNA NRC JPM Generator During a Loss of All AC 8. Power. KIA

Reference:

EPE 055 EA 1.02 Alternate Path -Once to start an SW Pump, once to energize a bus and then once to trip the Diesel. Examinee:

NRC Facility Evaluator: Method of Simulated Performance:

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

Initial Conditions:

• Ginna lost all off-site power due to severe weather.

• The 'B' EDG is unavailable due to maintenance.

• The 'A' EDG failed to automatically start.

• The crew is performing ECA-O.O, LOSS OF ALL AC POWER. Task Standard:

Busses 14 and 18 energized and at least one SW Pump cooling the DIG. Required Materials: General

References:

ECA-O.O, LOSS OF ALL AC POWER, Revision Handouts:

ECA-O.O, Step 7 (Pgs. 6 and 7 of Initiating Cue: The Control Room Supervisor has directed you to perform Step 7 -Try To Restore Power to Any Train Of AC Emergency Busses for the A EDG. Time Critical Task: No Validation Time: 6 Minutes 2010 GINNA NRC JPM A, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 SIMULATOR SETUP Reset to IC for NRC JPM N-A Placekeep the Control Room copy of ECA-O.O through step 6 and the Note prior to step 7. Hang Tags on the 'B' EDG (Bus 16 and 17 Supply breakers, 'B' EDG START/STOP switch and the pushbutton on the front of the Main Control Board). With the simulator running, go to the INSIGHT menu and set jltgmlct to TRUE. As soon as the normal lights go out and the emergency lights come on, setjltgmlct back to FALSE and freeze the simulator.

If the lights need to come back on after the JPM set jltgmlcc to TRUE. As soon as the normal lights come on and emergency lights go out, set jltgjlcc to FALSE. 2010 GINNA NRC JPM A, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 3 of9 VERIFICATION OF COMPLETION (Denote Critical Steps with a ..J) Start Time: ____ Procedure Note: Performance Step: 1 Standard:

EXAMINER CUE: EXAMINER NOTE: Performance Step: 2 Standard:

Comment: ECA -0.0, Step 7.a Conditions should be evaluated for Site Contingency Reporting (Refer to EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION). AO should frequently monitor the TDAFW pump until AC power is restored.

Try To Restore Power to Any Train Of AC Emergency Busses: Verify emergency DIG aligned for unit operation Mode switch in UNIT Voltage control selector in AUTO Verifies DIG A Mode Switch selected to UNIT Verifies DIG A MANUAL I AUTO VOLTAGE CONTROL selected to AUTO After the Initiating Cue is read, provide the ECA-O.O, Step 7 Handout. Switch nomenclature is different than the procedure nomenclature for the Mode and Voltage Control switches.

ECA-O.O, Step 7.b Check emergency DIGs -BOTH DIG RUNNING Observes the following indications on the A and B DIGs Frequency reads 61.2 Hz (On the green line) Voltage reads 0 Volts Amperage reads 0 Amps Watts reads 0 Watts Answers NO and proceeds to 7.b. RNO 2010 GINNA NRC JPM A, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 4 of 9 Form ES-C-1 Performance Step: 3 Standard:

Comment: Performance Step: 4 Standard:

Comment: Performance Step: 5 Standard:

EXAMINER NOTE: EXAMINER NOTE: VERIFICATION OF COMPLETION ECA-O.O, Step 7.b RNO WHEN non-running DIG available for starting, THEN perform

1) Depress DIG FIELD RESET Depresses DIG A FIELD RESET pushbutton.

ECA-O.O, Step 7.b RNO b.2) Depress DIG RESET pushbutton Depresses DIG A RESET pushbutton ECA-O.O, Step 7.b RNO b.3) Start DIG (..J) Rotates the A DIG CONTROL START/STOP switch to the START position. Verifies DIG A is running by observing: Frequency reads 60 Hz (On the green line) Voltage reads 480 Volts Amperage reads -1000 Amps Watts reads 550 Watts The BLUE air start solenoid lights will extinguish.

The candidate should move quickly from this point. A DIG running without cooling water will trip in approximately 5 minutes. 2010 GINNA NRC A, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page Performance Step: 6 Standard:

Comment: Performance Step: 7 Standard:

Comment: Performance Step: 8 Standard:

Comment: VERIFICATION OF COMPLETION ECA-O.O, Step 7.b RNO IF DIG starts, THEN go to Step Proceeds to Step 7.c. ECA-O.O, Step 7.c Check DIG voltage and frequency Voltage -APPROXIMATELY 480V Frequency

-APPROXIMATELY 60 Hz Verifies Voltage and Frequency for the A DIG by observing: Voltage -APPROXIMATEL Y 480V on A DIG Voltmeter Frequency

-APPROXIMATELY 60 Hz on A DIG Frequency Meter ECA-O.O, Step 7.d Verify adequate DIG cooling 1) Bus 17 andlor Bus 18 -ENERGIZED

• Determines Bus 18 is deenergized by observing: Voltage -0 Volts Frequency -0 Hz

• Proceeds to Step 7.d. RNO. 2010 GINNA NRC JPM A, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 9 Standard:

EXAMINER NOTE: Performance Step: 10 Standard:

Comment: Performance Step: 11 Standard:

EXAMINER NOTE: Page 6 of 9 Form ES-C-1 VERIFICATION OF COMPLETION ECA-O.O, Step 7.d Manually energize busses and start SW ("./) Rotates the D/G A SYNCHROSCOPE switch to the BUSS 18 position. ("./) Rotates the DIG A BUS 18 SUPPLY BREAKER to CLOSE. Determines Bus 18 is deenergized by observing: Voltage -Approximately 480 Volts Frequency

-Approximately 60 Hz The Candidate must use system knowledge to know you can not close the DIG supply breaker to Bus 18 without the synchroscope selected to the Bus 18 position.

ECA-O.O, Step 7.d One SW Pump running for each running DIG Determines NO SW Pumps running by observing all SW Pump RED lights extinguished and/or SW header pressure. Proceeds to Step 7.d. RNO. ECA-O.O, Step 7.d Manually energize busses and start SW ("./) Starts "A" andlor "C" SW Pump by rotating the switch to the START position before "An DIG trips on a cooling related automatic set point. Observes the pump or pumps started red light lit. SW header pressure will rise to approximately 40 PSIG after one pump is started. The candidate may elect to start a second SW pump to get SW header pressure above 55 PSIG. 2010 GINNA NRC JPM A, Revision NRC NUREG 1021, Revision 9, Supplement 1

Page 7 9 Form VERIFICATION OF COMPLETION EXAMINER 15 seconds after starting the service water pumps, as an Auxiliary Operator call the Candidate and inform them "Local annunciators are indicating a Loss of Service Water to the EDG A and high Jacket Water and Lube Oil temperatures." ECA-O.O, Step 7.d RNO " Performance Step: 12 IF adequate cooling can NOT be supplied to a running DIG, THEN petform the following:

1) Pull stop the DIG AND immediately depress associated VOLA TE SHUTDOWN pushbutton.

Standard: Rotates the A DIG CONTROL START/STOP switch to the STOP position and pulls the switch to the PULL STOP position . Depresses the VOLTAGE SHUTDOWN pushbutton for the A D/G. Comment: Terminating When the VOLTAGE SHUTDOWN pushbutton is depressed:

Evaluation on this JPM is complete.

Stop Time: ____ 2010 GINNA NRC JPM A, Revision NRC NUREG 1021, Revision 9, Supplement 1

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Appendix Form ES-C-1 VERIFICATION OF Job Performance Measure No.: 2010 GINNA NRC JPM A Examinee's Date Facility Number of Time to Question Result: SAT Examiner's Signature: 2010 GINNA NRC JPM A, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 9 of9 Form INITIAL INITIATING JPM CUE

• Ginna lost all off-site power due to severe weather.

• The 'B' EDG is unavailable due to maintenance.

• The 'A' EDG failed to automatically start.

• The crew is performing ECA-O.O, LOSS OF ALL AC POWER. The Control Room Supervisor has directed you to perform 0.0, Step 7 -Try To Restore Power to Any Train Of AC Emergency Busses for the A EDG. 2010 GINNA NRC JPM A, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Ginna Task No.: Task In accordance with FR-C.1. ,-'PM No.: 2010 GINNA NRC RESPONSE TO INADEQUATE JPMB CORE COOLING. Isolate an SI Accumulator That Has Discharged KIA

Reference:

006 A4.07 Alternate Path -Step 17.d RNO compensatory action for an MOV with no power Examinee:

NRC Examiner:

Facility Evaluator:

Date: Method of testing: Simulated Performance:

Actual Performance:

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

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue: Time Critical Task: Validation Time: A loss of coolant accident has occurred. Bus 14 is de-energized. Multiple equipment failures resulted in a RED Path on CORE COOLING. The crew has completed Steps 1 through 16 of FR-C.1, RESPONSE TO INADEQUATE CORE COOLING. A SI Accumulator depressurized and B SI Accumulator isolated.

Marked up copy of FR-C.1 available in the simulator.

FR-C.1, RESPONSE TO INADEQUATE CORE COOLING, Revision 02600 FR-C.1, Step The CRS directs you to perform FR-C.1, Step No 4 Minutes 2010 GINNA NRC JPM B, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP Reset to IC for NRC JPM N-B Ensure remotes EDS035 and EDS036 indicate CLOSED. Placekeep the Control Room copy of FR-C.1 Step 16 with the procedural path reflecting the equipment failed in the initial setup. 2010 GINNA NRC JPM B, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 8 Form ES-C-1 VERIFICATION OF (Denote Critical Steps with a Start Time: ____ Performance Step: 1 Standard:

EXAMINER CUE: Performance Step: 2 Standard:

Comment: Performance Step: 3 Standard:

EXAMINER NOTE: EXAMINER NOTE: EXAMINER CUE: FR-C.1, Step 17 Perform Step 17 -Check if SI Accumulators should be isolated Reviews Steps and considers conditions, as necessary.

Provide copy of FR-C.1, Step 17. FR-C.1, Step 17.a RCS hot leg temperatures

-BOTH LESS THAN 390 'F Observes RCS hot leg temperatures indicating less than 390'F on TI-409A1, 409B1, 410A1 and 410B1 and/or PPCS. FR-C.1, Step 17.b Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves

• MOV-841 MCC C position 12F

• MOV-865 MCC D position 12C Directs Primary AO to close the following breaker:

• MOV-865 MCC D position 12C The candidate may not recognize power is not available to MOV-841 and therefore direct closure of that The simulator snap includes the breakers for MOV-841 MOV-86S already closed. There is not any action by the Simulator Repeat back order. Wait one minute and then report that breakers for MOV-86S and MOV-841 (if they don't MOV-841 doesn't have power) are 2010 GINNA NRC ,JPM B, Revision NRC NUREG 1021, Revision 9, Supplement 1

Page 4 Form Performance Step: 4 Standard:

EXAMINER NOTE: EXAMINER NOTE: Performance Step: 5 Standard:

EXAMINER NOTE: Performance Step: 6 Standard:

EXAMINER NOTE: VERIFICATION OF Step 17.c Verify SI reset. Observes THERMAL OVERLOAD RELAY BYPASSED, extinguished.

If is extinguished then Safety Injection has been reset. The Candidate may depress the SI Reset Pushbutton to ensure SI is reset. FR-C.1, Step 17.d Close SI Accumulator Discharge Valves ACCUM A -MOV-841 ACCUM B -MOV-86S (\I) Takes the MOV-865 switch to the CLOSED position and the GREEN light illuminates Verifies the GREEN light lit for MOV-865 Proceeds to Step 17. d. RNO for no power to MOV-841 MOV-841 will not close since there is no power available with Bus 14 The candidate may not attempt to close it based on the Initial Conditions.

Step 17.RNO d.1) Perform the following to vent an unisolated accumulator:

1) Reset CI Depresses the CI RESET PB. Candidate may verify that CONTAINMENT ISOLATION, extinguishes.

2010 GINNA NRC JPM B, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 5 of 8 Form ES-C-1 Performance Step: 7 Standard:

EXAMINER NOTE: Performance Step: 8 Standard:

Comment: Performance Step: 9 Standard:

EXAMINER NOTE: VERIFICATION OF COMPLETION FR-C.1, Step 17.RNO Ensure adequate air compressor(s) Observes the Red light lit for the "C" Air Compressor running. (MCB Back Panel) Observes approximately 115 PSIG on Instrument Air Header Pressure.

The definition of adequate air compressors running is: * "A" and "B" lAC; or * "C" lAC; or

• Service Air Compressor FR-C.1, Step 17.RNO d.3) Establish IA to CNMT. Observes the Red light lit for AOV-5392. Observes the AOV-5392 light dim on the CI/CVI panel. FR-C.1, Step 17.RNO Open vent valves for unisolated SI ACCUM A, AOV-834A ACCUM B, AOV-834B (-,J) Rotates the switch for AOV-834A to the OPEN position. (MCB Back Panel) Observes the Red light lit for AOV-834A.

PI-941, pressure indicator for the A SI Accumulator, indicates 0 because the A electrical train is deenergized.

The Candidate must go to the front of the Main Control Board to determine the pressure in the A SI Accumulator.

2010 GINNA NRC JPM B, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 6 of 8 Form ES-C-1 VERIFICATION OF COMPLETION FR-C.1, Step 17.RNO d.5) " Performance Step: 10 Open HCV-945.

Opens HCV-945 by adjusting the demand controller on MCB Back Panel to a position greater than ZERO Comment: Terminating After the candidate has opened HCV-945: Evaluation on this JPM is complete.

Stop Time: ____ 2010 GINNA NRC JPM B, Revision NRC NUREG 1021, Revision 9, Supplement 1

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Appendix C Page 7 8 Form VERIFICATION OF Job Performance Measure No.: 2010 GINNA NRC JPM B Examinee's Date Facility Number of Time to Question Result: SAT Examiner's Signature: 2010 GINNA NRC JPM B, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 8 of 8 Form ES-C-1 INITIAL INITIATING JPM CUE A loss of coolant accident has occurred. Bus 14 is de-energized. Multiple equipment failures resulted in a RED Path on CORE COOLING. The crew has completed Steps 1 through 16 of FR-C.1, RESPONSE TO INADEQUATE CORE COOLING. The CRS directs you to perform FR-C.1, Step 17. 2010 GINNA NRC ..IPM B, Revision NRC NUREG 1021, Revision 9, Supplement 1

--Appendix C Job Performance Measure Form ES-C-1 Worksheet Ginna Task No.: Task Start a Reactor Coolant Pump JPM No.: 2010 GINNA NRC JPM during a plant startup and then C respond to an alarm associated with the pump just started KIA

Reference:

0032.1.23 ALTERNATE PATH: Alarm Response action to trip the RCP NRC Examiner:

Facility Date: Method of testing: Simulated Actual Performance:

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

Initial

• The plant is returning to service from a refueling outage. B RCP is running and the S-2.1, REACTOR COOLANT PUMP OPERATION, used to start the pump has been closed out. A new is being used to start the A RCP and is complete up to Step 5.1.3. The Containment Sound Monitor will not be used during the RCP starts. The crew is performing 0-1.1, PLANT HEATUP FROM COLD SHUTDOWN TO HOT SHUTDOWN, and has reached step 6.5.10.3 -PLACE PCV 135 in MANUAL AND CONTROL RCS pressure at approximately 325 psig An Auxiliary Operator is at the A RCP to monitor the start. Task RCS Pressure controlled within required parameters and the A RCP manually tripped Required None General

References:

0-1.1, PLANT HEATUP FROM COLD SHUTDOWN TO HOT SHUTDOWN, Revision 16401 S-2.1, REACTOR COOLANT PUMP OPERATION, Revision 04500 AR-A-24, RCP OIL LEVEL +/- 1.25, Revision 01601 2010 GINNA NRC JPM C, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Job Performance Measure Form ES-C-1 Handouts:

Initiating Cue: Time Critical Task: Validation Time: Worksheet A marked up copy of 0-1.1 up to the NOTE prior to Step 6.5.10.3 A marked up copy of S-2.1, REACTOR COOLANT PUMP OPERATION, up to Step 5.1.2. A marked up copy of Attachment 5, RCP A, to S-2.1 The CRS has assigned you to start the A RCP in accordance with Steps 6.5.10.3 through 6.5.10.6 of 0-1.1, PLANT HEATUP FROM COLD SHUTDOWN TO HOT SHUTDOWN.

Another operator will respond to alarms not directly related to this task and is available for adjusting Charging Pump speed during the RCP start, but you must direct any adjustments.

No 15 Minutes 2010 GINNA NRC C, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 SIMULATOR SETUP

• Reset to IC for NRC JPM N-C

• Ensure MALF RCS08A, -2.S, on Trigger 1

• Place RCP Parameters on Group Display

• L TOP Display on overhead monitor

• Replace C-S and F-29 alarm tiles

• Placekeep the Control Room copy of 0-1.1 up to Step 6.S.10.3, and S-2.1 up to Step S.O 2010 GINNA NRC JPM C, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 1 VERIFICATION OF COMPLETION (Denote Critical Steps with a ") Start Time: ____ Procedure Note: " Performance Step: 1 Standard:

EXAMINER CUE: Performance Step: 2 Standard:

Comment: 0-1.1, Step 6.5.10.3 The Operator should be ready to open PCV-135 should a pressure spike occur when the Reactor Coolant Pump is started. IF RCS pressure goes down after RCP start, THEN closing on PCV 135 will raise RCS pressure faster than raising Charging Pump speed. IF RCS pressure rises, THEN it may be necessary to lower Charging Pump speed OR open PCV 135. PLACE PCV 135 in MANUAL AND CONTROL RCS pressure at approximately 325 psig .

• Reviews procedure note prior to Step 6.5.10.3

• Balances the PCV 135 Automatic-to-Manual control places the controller to

• b t) Controls RCS pressure at 325 psig. Provide the Candidate with the marked up copy of 0-1.1. 0-1.1, Step 6.5.10.4 IF the containment sound monitor is to be used for the RCP being started, THEN TURN ON the containment sound monitor for the respective RCP. OTHERWISE, MARK this Step N/A. Based on Initial Conditions, marks the step N/A 2010 GINNA NRC JPM C, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 13 Form ES-C-1 Performance Step: 3 Standard:

Comment: Performance Step: 4 Standard:

EXAMINER CUE: Procedure Note: Performance Step: 5 Standard:

Comment: VERIFICATION OF COMPLETION 0-1.1, Step 6.5.10.5 CLOSELY MONITOR RCS heatup rate AND RCS pressure after starting of the 2 nd RCP. Monitors RCS heat up rate and pressure on PPCS. 0-1.1, Step 6.5.10.6 START the 2 nd RCP PER S-2.1, starting instructions section AND MARK RCP NOT started N/A.

• RCPA

• RCP B

• Marks RCP B step N/A

• Refers to S-2.1 for the A RCP Provide the Candidate with a marked up copy of S-2.1 when the need is identified.

S-2.1, Section Sections that will not be performed may be marked STARTING RCP A Reviews procedure 2010 GINNA NRC JPM C, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 6 of 13 Form ES-C-1 Procedure Note: Performance Step: 6 Standard:

EXAMINER NOTE: Procedure Note: Performance Step: 7 Standard:

Comment: VERIFICATION OF COMPLETION 5-2.1, Step 5.1.3 Starting the Oil Lift Pump will increase RCP seal clearances and may result in a change of state for MCB Alarm B-17, RCP 1A No. 1 SEAL HI-LO FLOW. Start RCP A Oil Lift Pump. ("./) Rotates the RCP A Oil Lift Pump handle to the

• Verifies red start light is lit

• Marks the time __' The time should be marked to ensure the lift Oil Pump has been running for at least 2 minutes prior to starting the RCP but the RCP will not start unless the pressure interlock is satisfied.

5-2.1, Step 5.1.4 A pressure interlock prevents starting of the RCP unless a minimum oil pressure is available to the Upper Thrust Shoes of the Motor Thrust Bearing. AFTER 2 minutes, VERIFY RCP A Lift Pressure WHITE light is lit.

• Verifies RCP A Lift Pressure WHITE light is lit.

• Verifies 2 minutes has elapsed since the start of the Lift 2010 GINNA NRC JPM C, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 13 Form Performance Step: 8 Standard:

EXAMINER NOTE: Performance Step: 9 Performance Step:

VERIFICATION OF COMPLETION S-2.1, Step 5.1.5 VERIFY RCP A No.1 Seal Leakoff is still in the NORMAL OPERATING RANGE of Attachment 3, RCP Seal Leakoff.

• Refers to S-2.1 , Attachment 3, and determines the combination of #1 Seal Leak Rate and #1 Seal DP are within the NORMAL OPERATING RANGE.

• Determines the #1 Seal Leak Rate using RCP A F-177 and A SEAL FLOW F-175

• Determines the #1 Seal DP using PI-173

• Using the combination of #1 Seal Leak Rate and #1 Seal DP verifies their intersection is within the NORMAL OPERATING RANGE on Attachment

3. The normal #1 Seal leak rate is approximately 1.2 GPM at 325 psig. The maximum allowable

1. 1 Seal leak rate is 1.25 GPM at 325 psig. S-2.1, Step 5.1.6 Select RCP A on the Containment Sound Monitor, N/A if Sound Monitor is not available.

Marks the step N/A S-2.1, Step 5.1.7 Make a Plant Announcement that RCP A will be started. Announces starting Reactor Coolant Pump A. 2010 GINNA NRC JPM C, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 8 of 13 Form ES-C-1 Procedure Note: Performance Step: 11 Standard:

EXAMINER Performance Step:

Performance Step:

VERIFICATION OF COMPLETION S-2.1, Step 5.1.8 During solid plant operations when starting an RCP, control RCS pressure such as to maintain >220 psid on the #1 seal DP indicator and below the PORV setpoint of 410 psig. Maintain RCS pressure at approximately 325 psig, as indicated on PI-420, by setting of the Low Pressure Letdown Controller, PCV-135 . Start RCP A. May assign the second board operator to adjust Charging Pump speed, when directed. Starts RCP A and verifies flow. (...J) Adjusts PCV-135 as necessary to maintain RCS Pressure such that RCP #1 Seal DP >220 PSID, as seen on PI-173, and no PORV lift (410 PSIG). RCP A start time: ____' S-2.1, Step Turn off the Containment Sound Monitor (mark N/A if not

• Marks the step N/A S-2.1, Step 5.1.10 WHEN the A RCP has been operating for greater than 1 minute, THEN STOP the RCP A Oil Lift Pump.

• Verifies the RCP has been running for one minute .

• Rotates the RCP A Oil Lift Pump counter-clockwise to STOP 2010 GINNA NRC JPM C, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 14 EXAMINER SIMULATOR Performance Step:

Performance Step:

EXAMINER Page VERIFICATION OF S-2.1, Step 5.1.11 Monitor the following parameters for RCP A lAW Section 5.3, Normal Operation:

• RCP A Bearing Temps (PPCS or Recorder)

• RCP A Seal Leakoff Flows

• RCP A #1 Seal DIP

• Seal Return Heat Exchanger Outlet Temperature (AO)

• RCP A Oil Levels

• RCP A Vibration Monitor Refers to Section 5.3 and begins verifying parameters.

If the Candidate asks Seal Return Heat Exchanger Outlet Temperature, inform them it is 80°F. When this step is in progress, insert MALF RCS08A, -2.5, ramp over 30 seconds AR-A-24 Responds to annunciator alarm. Acknowledges Main Control Board alarm A-24. AR-A-24, Step 1 When first starting the pump, then allow 30 seconds for alarm to clear. Trip pump if alarm still does not clear. Reads step and may trip the RCP at this time. The critical task for stopping the RCP is met if the candidate trips the RCP at any time after reading this step but before the RCP A breaker trips on overcurrent.

RCP A will trip on overcurrent after approximately 3.5 minutes. 2010 GINNA NRC JPM C, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 10 of 13 Form ES-C-1 Performance Step: 17 Standard:

Comment: Performance Step: 18 Standard:

EXAMINER NOTE: Performance Step: 19 Standard:

Comment: VERIFICATION OF COMPLETION AR-A-24, Step 2 When operating, then verify level using RCP Oil Level Indicators and Plant Process Computer System.

• Checks RCP A Oil Level at the RMS rack side panel

• Checks Group Display RCPS on PPCS AR-A-24, Step Immediately monitor the A RCP Motor bearing temperature. can be done by using PPCS Group Display Determines RCP Motor Bearing temperature is rising RCP Motor Bearing temperature is on the computer behind the Candidate on the AR-A-24, Step IF bearing temperatures AND indicated level appear THEN initiate a CNMT entry to investigate the sight glass I F the lower bearing oil level is greater than 1" BELOW the on the sight glass, THEN prepare to remove the pump service. Otherwise, the level is acceptable to continue Determines conditions are NOT normal and proceeds to the 2010 GINNA NRC "IPM C, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 11 of 13 Form ES-C-1 VERIFICATION OF COMPLETION AR-A-24, Step 2.3 --J Performance Step: If level is 1.5" below normally indicated level and visibly lowering then: Trip the reactor When all E-O immediate actions done, then trip affected RCP Standard: Trip the reactor (N/A) (--J) Trips RCP A before the breaker trips on overcurrent.

Comment: Terminating When RCP A is stopped: Evaluation on this JPM is complete.

Stop Time: ____ 2010 GINNA NRC "IPM C, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 12 of 13 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2010 GINNA NRC JPM C Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: 2010 GINNA NRC JPM C, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 13 of 13 Form ES-C-1 INITIAL INITIATING JPM CUE The plant is returning to service from a refueling outage. B RCP is running and the S-2.1, REACTOR COOLANT PUMP OPERATION, used to start the pump has been closed out. A new S-2.1 is being used to start the A RCP and is complete up to Step 5.1.3. The Containment Sound Monitor will not be used during the RCP starts. The crew is performing 0-1.1, PLANT HEATUP FROM COLD SHUTDOWN TO HOT SHUTDOWN, and has reached step 6.5.10.3-PLACE PCV 135 in MANUAL AND CONTROL RCS pressure at approximately 325 psig An Auxiliary Operator is at the A RCP to monitor the start. The CRS has assigned you to start the A RCP in accordance with Steps 6.5.10.3 through 6.5.10.6 of 0-1.1, PLANT HEA TUP FROM COLD SHUTDOWN TO HOT SHUTDOWN.

Another operator will respond to alarms not directly related to this task and is available for adjusting Charging Pump speed during the RCP start, but you must direct any adjustments.

2010 GINNA NRC JPM C, Revision NRC NUREG 1021, Revision 9, Supplement 1

--Appendix Job Performance Measure Form ES-C-1 Facility: Task No.: Task Title: Start a Reactor Coolant Pump JPM No.: 2010 GINNA NRC JPM During a Plant Startup C -SRO UPGRADE ONLY KIA

Reference:

0032.1.23 (4.3 14.4)

NRC Examiner:

Facility Date: Method of testing: Simulated Actual Performance:

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

Initial

• The plant is returning to service from a refueling outage. B RCP is running and the S-2.1, REACTOR COOLANT PUMP OPERATION, used to start the pump has been closed out. A new is being used to start the A RCP and is complete up to Step 5.1.3. The Containment Sound Monitor will not be used during the RCP starts. The crew is performing 0-1.1, PLANT HEA TUP FROM COLD SHUTDOWN TO HOT SHUTDOWN, and has reached step 6.5.10.3 -PLACE PCV 135 in MANUAL AND CONTROL RCS pressure at approximately 325 psig An Auxiliary Operator is at the A RCP to monitor the start. Task RCS Pressure controlled within required parameters and the A RCP manually tripped Required None General

References:

0-1.1, PLANT HEATUP FROM COLD SHUTDOWN TO HOT SHUTDOWN, Revision 16401 S-2.1, REACTOR COOLANT PUMP OPERATION, Revision 04500 AR-A-24, RCP OIL LEVEL +/- 1.25, Revision 01601 2010 GINNA NRC JPM C, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Job Performance Measure Form ES-C-1 Handouts:

Initiating Cue: Time Critical Task: Validation Time: Worksheet A marked up copy of 0-1.1 up to the NOTE prior to Step 6.5.10.3 A marked up copy of S-2.1, REACTOR COOLANT PUMP OPERATION, up to Step 5.1.2. A marked up copy of Attachment 5, RCP A, to S-2.1 The CRS has assigned you to start the A RCP in accordance with Steps 6.5.10.3 through 6.5.10.6 of 0-1.1, PLANT HEATUP FROM COLD SHUTDOWN TO HOT SHUTDOWN. Another operator will respond to alarms not directly related to this task and is available for adjusting Charging Pump speed during the RCP start, but you must direct any adjustments.

No 15 Minutes 2010 GINNA NRC JPM C, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 SIMULATOR SETUP

• Reset to IC for NRC JPM N-C-U

• Place RCP Parameters on Group Display

• L TOP Display on overhead monitor

• Replace C-5 and F-29 alarm tiles

• Placekeep the Control Room copy of 0-1.1 up to Step 6.5.10.3, and S-2.1 up to Step 5.0 2010 GINNA NRC JPM C, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 11 Form ES-C-1 VERIFICATION OF (Denote Critical Steps with a Start Time: ____EXAMINER NOTE: This JPM only to be administered to SRO Upgrade Candidates Procedure Note: " Performance Step: 1 Standard:

EXAMINER CUE: Performance Step: 2 Standard:

Comment: 0-1.1, Step 6.5.10.3 The Operator should be ready to open PCV-135 should a pressure spike occur when the Reactor Coolant Pump is started. IF RCS pressure goes down after RCP start, THEN closing on PCV 135 will raise RCS pressure faster than raising Charging Pump speed. IF RCS pressure rises, THEN it may be necessary to lower Charging Pump speed OR open PCV 135. PLACE PCV 135 in MANUAL AND CONTROL RCS pressure at approximately 325 psig.

• Reviews procedure note prior to Step 6.5.10.3

• Balances the PCV 135 Automatic-to-Manual control places the controller to * (") Controls RCS pressure at 325 psig. Provide the Candidate with the marked up copy of 0-1.1. 0-1.1, Step 6.5.10.4 IF the containment sound monitor is to be used for the RCP being started, THEN TURN ON the containment sound monitor for the respective RCP. OTHERWISE, MARK this Step N/A. Based on Initial Conditions, marks the step N/A 2010 GINNA NRC JPM C, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 11 Form ES-C-1 Performance Step: 3 Standard:

Comment: Performance Step: 4 Standard:

EXAMINER CUE: Procedure Note: Performance Step: 5 Standard:

Comment: VERIFICATION OF COMPLETION 0-1.1, Step 6.5.10.5 CLOSELY MONITOR RCS heatup rate AND RCS pressure after starting of the 2 nd RCP. Monitors RCS heat up rate and pressure on PPCS. 0-1.1, Step 6.5.10.6 START the 2 nd RCP PER S-2.1, starting instructions section AND MARK RCP NOT started N/A.

• RCPA

• RCP B

• Marks RCP B step N/A

• Refers to S-2.1 for the A RCP Provide the Candidate with a marked up copy of S-2.1 when the need is identified.

S-2.1, Section Sections that will not be performed may be marked STARTING RCP A Reviews procedure 2010 GINNA NRC JPM C, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 6 of 11 Form ES-C-1 Procedure Note: Performance Step: 6 Standard:

EXAMINER NOTE: Procedure Note: Performance Step: 7 Standard:

Comment: VERIFICATION OF COMPLETION S-2.1, Step 5.1.3 Starting the Oil Lift Pump will increase RCP seal clearances and may result in a change of state for MCB Alarm B-17, RCP 1A No. 1 SEAL HI-La FLOW . Start RCP A Oil Lift Pump. (...J) Rotates the RCP A Oil Lift Pump handle to the

• Verifies red start light is lit

• Marks the time __ The time should be marked to ensure the Lift Oil Pump has been running for at least 2 minutes prior to starting the RCP but the RCP will not start unless the pressure interlock is satisfied.

S-2.1, Step 5.1.4 A pressure interlock prevents starting of the RCP unless a minimum oil pressure is available to the Upper Thrust Shoes of the Motor Thrust Bearing. AFTER 2 minutes, VERIFY RCP A Lift Pressure WHITE light is lit.

• Verifies RCP A Lift Pressure WHITE light is lit.

• Verifies 2 minutes has elapsed since the start of the Lift 2010 GINNA NRC JPM C, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 11 Form ES-C-1 Performance Step: 8 Standard:

EXAMINER NOTE: Performance Step: 9 Performance Step:

VERIFICATION OF COMPLETION S-2.1, Step 5.1.5 VERIFY RCP A No.1 Seal Leakoff is still in the NORMAL OPERATING RANGE of Attachment 3, RCP Seal Leakoff.

• Refers to S-2.1, Attachment 3, and determines the combination of #1 Seal Leak Rate and #1 Seal DP are within the NORMAL OPERATING RANGE.

• Determines the #1 Seal Leak Rate using RCP A F-177 and A SEAL FLOW F-175

• Determines the #1 Seal DP using PI-173

• Using the combination of #1 Seal Leak Rate and #1 Seal DP verifies their intersection is within the NORMAL OPERATING RANGE on Attachment

3. The normal #1 Seal leak rate is approximately 1.2 GPM at 325 psig. The maximum allowable

1. 1 Seal leak rate is 1.25 GPM at 325 psig. S-2.1, Step 5.1.6 Select RCP A on the Containment Sound Monitor, N/A if Sound Monitor is not available.

Marks the step N/A S-2.1, Step Make a Plant Announcement that RCP A will be Announces starting Reactor Coolant Pump A. 2010 GINNA NRC JPM C, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Procedure Note: Performance Step: 11 Standard:

EXAMINER Performance Step:

Performance Step:

Page 8 of 11 Form ES-C-1 VERIFICATION OF COMPLETION S-2.1, Step 5.1.8 During solid plant operations when starting an RCP, control RCS pressure such as to maintain >220 psid on the #1 seal DP indicator and below the PORV setpoint of 410 psig. Maintain RCS pressure at approximately 325 psig, as indicated on PI-420, by setting of the Low Pressure Letdown Controller, PCV-135. Start RCP A. May assign the second board operator to adjust Charging Pump speed, when directed. Starts RCP A and verifies flow. (") Adjusts PCV-135 as necessary to maintain RCS Pressure such that RCP #1 Seal DP >220 PSID, as seen on PI-173, and no PORV lift (410 PSIG). RCP A start time: ___ S-2.1, Step 5.1.9 Tum off the Containment Sound Monitor (mark N/A if not used).

• Marks the step N/A S-2.1, Step 5.1.10 WHEN the A RCP has been operating for greater than 1 minute, THEN STOP the RCP A Oil Lift Pump.

• Verifies the RCP has been running for one minute.

• Rotates the RCP A Oil Lift Pump counter-clockwise to STOP Comment: 2010 GINNA NRC JPM C, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 9 of 11 Form ES-C-1 VERIFICATION OF COMPLETION When RCP A Oil Lift Pump is stopped: Evaluation on this JPM is complete.

Terminating Cue: Stop Time: ____ 2010 GINNA NRC JPM C, Revision NRC NUREG 1021, Revision 9, Supplement 1

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Appendix C Page 10 of 11 Form ES-C-1 VERIFICATION OF Job Performance Measure No.: 2010 GINNA NRC JPM C -SRO UPGRADE ONLY Examinee's Date Facility Number of Time to Question Result: SAT Examiner's Signature: 2010 GINNA NRC JPM C, Revision NRC NUREG 1021, Revision 9, Supplement 1

Page 11 of Form JPM CUE INITIAL INITIATING The plant is returning to service from a refueling outage. B RCP is running and the S-2.1, REACTOR COOLANT PUMP OPERATION, used to start the pump has been closed out. A new S-2.1 is being used to start the A RCP and is complete up to Step 5.1.3. The Containment Sound Monitor will not be used during the RCP starts. The crew is performing 0-1.1, PLANT HEA TUP FROM COLD SHUTDOWN TO HOT SHUTDOWN, and has reached step 6.5.10.3 -PLACE PCV 135 in MANUAL AND CONTROL RCS pressure at approximately 325 psig An Auxiliary Operator is at the A RCP to monitor the start. The CRS has assigned you to start the A RCP in accordance with Steps 6.5.10.3 through 6.5.10.6 of 0-1.1, PLANT HEATUP FROM COLD SHUTDOWN TO HOT SHUTDOWN.

Another operator will respond to alarms not directly related to this task and is available for adjusting Charging Pump speed during the RCP start, but you must direct any adjustments.

2010 GINNA NRC JPM C, Revision NRC NUREG 1021, Revision 9, Supplement 1

--Appendix Job Performance Measure Form ES-C-1 Worksheet Ginna Task No.: Task Respond To a Control Room JPM No.: 2010 GINNA NRC JPM Evacuation o KIA

Reference:

APE 068 AA1.23 ALTERNATE PATH: RNO implemented for reactor and turbine trip. Examinee:

NRC Facility Evaluator: Method of Simulated Performance:

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

Initial Conditions:

• The plant is at 100% power in a normal SO/50 electric plant lineup.

• The CO and the SM are in the Relay Room investigating an issue. Task Standard:

Immediate actions of AP-CR.1 completed from memory. Required Materials:

None General

References:

AP-CR.1, CONTROL ROOM INACCESSIBILITY, Rev. 02402 Handouts:

None Initiating Cue: You are the HCO assigned the Control Room Monitoring function.

Time Critical Task: No Validation Time: 'I Minute 2010 GINNA NRC JPM 0, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 SIMULATOR SETUP Reset to IC for NRC JPM-N-D TUR02 TUR17A TUR17B RPS05A NO MAN RPS05B NO MAN RPS07S RPS07T OVR-TUR04 FALSE OVR-EDS47D FALSE 2010 GINNA NRC JPM 0, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 30f7 Form ES-C-1 VERIFICATION OF COMPLETION (Denote Critical Steps with a ..J) Start Time: ____ Performance Step: 1 Standard:

EXAMINER CUE: Performance Step: 2 Standard:

EXAMINER NOTE: AP-CR.1, step 1 Assumes the watch Walks down the MCB 15-30 seconds after the Initiating Cue inform the Candidate "There are noxious fumes in the Main Control Room. The Control Room Supervisor and Shift Technical Advisor are incapacitated. " AP-CR.1, step 1 Verify Reactor Trip: At least one train of reactor trip breakers -OPEN. Neutron flux -LOWERING. MRPI indicates

-ALL CONTROL AND SHUTDOWN RODS ON BOTTOM.

• Determines no reactor trip breakers are open

• Determines Neutron flux at 100% RTP

• Determines MRPI indicates the reactor is not tripped

• Proceeds to step 1.a RNO No action has been taken yet to trip the reactor, therefore the candidate should enter the RNO column to manually trip the reactor. 2010 GINNA NRC JPM 0, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 4 of7 Form ES-C-1 Performance Step: 3 Standard:

EXAMINER NOTE: Performance Step: 4 Standard:

Simulator Driver: VERIFICATION OF COMPLETION AP-CR.1, step 1 RNO Manually trip reactor.

• Depresses the Reactor Trip Pushbutton on MCB

• Determines no reactor trip breakers are open Candidate may also check nuclear power and MRPI for further verification that the reactor has NOT tripped. AP-CR.1, steps 1.a thru 1.d IF reactor trip breakers NOT open, THEN perform the

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. (...J) Opens Bus 13 normal feed breakers. Verifies Red light OFF and Green lights ON for Bus 13 Verifies A Rod drive MG sets Red light OFF and Green light ON. Closes Bus 13 normal feed breakers. Red lights ON and Green lights OFF. Resets lighting breakers by depressing Bus 13 Lighting Breaker green Push buttons. (...J) Calls Secondary Auxiliary Operator to open the A and B reactor trip breakers Acknowledge the order and then insert MALFUNCTION ROD06B. 2010 GINNA NRC JPM 0, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 5 of 7 Form ES-C-1 Performance Step: 5 Standard:

EXAMINER NOTE: "J Performance Step: 6 Standard:

EXAMINER NOTE: Terminating Cue: Stop Time: _____ VERIFICATION OF AP-CR.1, step 2 Verify Turbine Stop Valves -CLOSED On EHC valve status panel observes SVL Open red light ON and SVR Open red light ON. Identifies Turbine stop valves are still open and goes to step 2 RNO. Since the reactor trip signal initiates the turbine trip signal, the turbine did not receive an auto trip signal. AP-CR.1, step 2 RNa Manually trip turbine. IF turbine can NOT be tripped, THEN close both MSIVs. Depresses Turbine Emergency Trip P/B Determines the Turbine did not trip ("J) Rotates the Handswitch to the closed position for valves:

• MSIV A, AOV-3517

• MSIV B, AOV-3516 Observes Red light extinguished and Green light lit for following

• MSIV A, AOV-3517

• MSIV B, AOV-3516 Inserted malfunction has prevented manual turbine trip button from initiating the turbine trip. When the verifies both MSIVs are closed: Evaluation on this JPM is complete.

2010 GINNA NRC JPM D, Revision NRC NUREG 1021, Revision 9, Supplement 1

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Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF Job Performance Measure No.: 2010 GINNA NRC JPM D Examinee's Date Facility Number of Time to Question Result: SAT Examiner's Signature: 2010 GINNA NRC D, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page? of? Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

• The plant is at 100% power in a normal 50/50 electric plant lineup.

• The CO and the SM are in the Relay Room investigating an issue. INITIATING CUE: You are the HCO assigned the Control Room Monitoring function.

2010 GINNA NRC JPM D, Revision NRC NUREG 1021, Revision 9, Supplement 1

--Appendix Job Performance Measure Form ES-C-1 Facility: Task No.: Task Title: Placing L TOP on Service JPM No.: 2010 GINNA NRC JPM £ KIA

Reference:

010 A4.03 (4.0/3.8)

NRC Examiner:

Facility Date: Method of testing: Simulated Actual Performance:

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

Initial

• A unit shutdown is in progress The control room team is performing procedure 0-2.2, Plant Shutdown from Hot Shutdown to Cold Conditions, and has reached 6.4.21 -Place the Overpressure Protection System in service. Section 1 through section 6.1 of 0-7, Alignment and Operation of the Reactor Vessel Overpressure Protection System, has been completed.

Task Place PCV-430 on service and all critical tasks evaluated as satisfactory . Required Panel key for L TOP operations.

General

References:

0-7, Alignment and Operation ofthe Reactor Vessel Overpressure Protection System, Rev. 04701 0-2.2, Plant Shutdown from Hot Shutdown to Cold Conditions, Rev. 15300 Properly markup a copy of 0-7, Alignment and Operation of the Reactor Vessel Overpressure Protection System, Rev. 04701 to section 6.2. Initiating You are an extra RO. The Shift Manager directs you to place PCV-430 in service per 0-7, Alignment and Operation of the Reactor Vessel Overpressure Protection System, Section 6.2. Time Critical No Validation 4 Minutes 2010 GINNA NRC JPM E, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 SIMULATOR SETUP Reset to IC for NRC Replace the On-Line MCB Annunciator Tiles (C-5 and 2010 GINNA NRC JPM E, Revision NRC NUREG 1021, Revision 9, Supplement 1

Page 9 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a ..J) Start Time: ____ Performance Step: 1 Standard:

Comment: Performance Step: 2 Standard:

Comment: 0-7, step VERIFY the following MCB Alarms 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 Verifies the following MCB Alarms are extinguished: AA-22 AA-23 AA-31 0-7, step 6.2.2 ENSURE the PRZR PORV, PCV-430 Control Switch is in the CLOSE position. Rotates PCV-430 control switch to the CLOSED position. Verifies the Red light OFF and Green light ON for PCV-430 2010 GINNA NRC E, Revision NRC NUREG 1021, Revision 9, Supplement 1

-v Appendix C Page 4 of 9 Form ES-C-1 Performance Step: 3 Standard:

EXAMINER CUE: EXAMINER NOTE: ..J Performance Step: 4 Standard:

EXAMINER NOTE: Performance Step: 5 Standard:

Comment: Performance Step: 6 Standard:

EXAMINER NOTE: PERFORMANCE INFORMATION 0-7, step 6.2.3 OPEN ACCUM TO SURGE TANK VLV SOV-8616A. (MCB Rear)

• Requests L TOP key from the Shift Manager * (-V) Rotates SOV-8616A to the OPEN position Provide L TOP KEY when There will not be any light indication on the 0-7, step ENSURE N2 ARMING VLV SOV-8619A is in the ARM (MCB

• Uses proper key. * (-V) Rotates SOV-8619A to the ARM position There will not be any light indication on the 0-7, step VERIFY CLOSED PRZR PORV,

• PCV-430 control switch is in the closed position.

• Red light OFF and green light ON. 0-7, step 6.2.6 RECORD pressure indicated on OP ACCUM A N2 PRESSURE, PI-455. (MCB Rear) Pressure recorded as indicated on PI-455. PI-455 will read approximately 750 psig. 2010 GINNA NRC JPM E, Revision NRC NUREG 1021, Revision 9, Supplement 1

Page 5 9 Form ES-C-1 Performance Step: 7 Standard:

Comment: PERFORMANCE INFORMATION 0-7, step 6.2.7 IF Accumulator A pressure is NOT between 735 and 760 psig, THEN CHARGE the 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 N/A. Verifies Accumulator A pressure between 735 and 760 psig and marks step N/A. 2010 GINNA NRC E, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 6 of 9 Form ES-C-1 PERFORMANCE EXAMINER NOTE: At this point in the plant shutdown the operator would expect the MOV-516 breaker to be closed. However, to design ..IPM Step 8 as a Critical Task, when the position of the breaker is checked, it will be reported that the breaker is OPEN. Based on this, there are two possibilities: Upon discovering the breaker OPEN, the Candidate directs the Primary Auxiliary Operator to "Ensure the breaker for MOV-516 is CLOSED," (Even though the candidate may inform the CRS that the breaker has been discovered out of position). Upon discovering the breaker OPEN, the Candidate informs the CRS that the breaker is out of position, and stops performing the task pending investigation.

The following step is cued for the two likely situations.

0-7, step 6.2.8 " Performance Step: ENSURE CLOSED MOV 516 breaker, MCC C position 6C, VLV-516 RCS.

Calls the Primary Auxiliary Operator and directs that they check the position of the MOV-516 breaker. EXAMINER When the Primary AO is directed to check the position of the MOV-516 breaker, report that the Breaker is OPEN.

<") Directs the Primary Auxiliary Operator to CLOSE the 516 Breaker. Examiner provide the appropriate Cue(s): EXAMINER If the Candidate directs the Primary Auxiliary Operator to "Ensure the breaker for MOV-516 is CLOSED" as the Primary AO, report that "the MOV-516 breaker has been CLOSED." EXAMINER If the Candidate informs the CRS that the breaker was OPEN, as the CRS, acknowledge the report and direct the candidate to continue with the task. EXAMINER If the Candidate requests an investigation as to why the breaker was OPEN, as the Shift Manager, report that an investigation is underway, and direct the candidate to continue with the task. 2010 GINNA NRC JPM E, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 7 of 9 Form ES-C-1 Performance Step: 9 Standard:

EXAMINER CUE: Performance Step: 10 Terminating Cue: Stop Time: ____ PERFORMANCE INFORMATION 0-7, step 6.2.9 ENSURE OPEN PRZR PORV BLOCK VLV, MOV 516. (") Rotates MOV 516, PRZR PORV BLOCK VLV to OPEN. Red light ON and green light OFF. If the Candidate realizes the switch should be in the OPEN position at this point in the plant shutdown and requests an investigation as to why the valve was closed, inform them the Shift Manager will take the required actions for the misposition, continue with the JPM." 0-7, step 6.2.10 RECORD the time Train A Overpressure Protection System is operable.

Records current time. After the time is recorded or the candidate reports PCV-430 in service: Evaluation on this JPM is complete.

2010 GINNA NRC JPM E, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2010 GINNA NRC JPM E Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: 2010 GINNA NRC JPM E, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 9 9 INITIAL INITIATING JPM CUE A unit shutdown is in progress The control room team is performing procedure 0-2.2, Plant Shutdown from Hot Shutdown to Cold Conditions, and has reached 6.4.21 -Place the Overpressure Protection System in service. Section 1 through section 6.1 of 0-7, Alignment and Operation of the Reactor Vessel Overpressure Protection System, has been completed.

You are an extra RO. The Shift Manager directs you to place PCV-430 in service per 0-7, Alignment and Operation of the Reactor Vessel Overpressure Protection System, Section 6.2. 2010 GINNA NRC JPM E, Revision NRC NUREG 1021, Revision 9, Supplement 1

--Appendix C Job Performance Measure Form ES-C-1 Worksheet Ginna Task No.: Task Initiate rapid boration in preparation JPM No.: 2010 GINNA NRC for proceeding to cold shutdown JPM F KIA 004 A4.18 (4.3/4.1)

NRC Examiner:

Facility Date: Method of testing: Simulated Actual Performance:

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

Initial Conditions: The plant has had a reactor trip and is entering a forced outage. Plant Management directed the RCS borated to refueling boron concentration The crew has prepared to emergency borate using S-3.1, BORON CONCENTRATION CONTROL, Attachment 9 -RAPID BORATION, up to step 2.3. Task Boration greater than 10 GPM established.

Required None General

References:

0-2.2, PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD CONDITIONS, Revision 15300 S-3.1, BORON CONCENTRATION CONTROL, Attachment 9 RAPID BORATION, Revision 03101 Handouts: Marked up copy of S-3.1, BORON CONCENTRATION CONTROL, Attachment 9-RAPID BORATION, Revision 03101 Initiating The CRS directs you to establish rapid boration at greater than 18 GPM in accordance with S-3.1, Attachment 9 starting at step 2.3. Assume operators are standing by at the required locations to perform the local tasks. Time Critical No Validation 9 Minutes 2010 GINNA NRC JPM F, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP Reset to the IC for NRC JPM Ensure PPCS Variable Boration Dilution screen is 2010 GINNA NRC F, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 10 Form ES-C-1 VERIFICATION OF COMPLETION (Denote Critical Steps with a Start Time: ____ Performance Step: 1 Standard:

Comment: Performance Step: 2 Standard:

Comment: Performance Step: 3 Standard:

EXAMINER NOTE: S-3.1, Attachment 9, Steps 2.3 and 2.3.1 Verify charging flow path Verify at least one charging pump running Verifies the A and C Charging Pumps are running using the red light lit for each charging pump and flow indicated on FI-128C, FI-115A and FI-116A S-3.1, Attachment 9, Step 2.3.2 ENSURE OPEN CHARGING VLV RHX TO LOOP B COLD, AOV-294. Verifies AOV-294, CHARGING VLV RHX TO LOOP B COLD, OPEN using the red light lit for AOV-294 S-3.1, Attachment 9, Step 2.3.3 VERIFY CHARGING FLOW TO REGEN HX, HCV-142, demand set at 0% (Open) Verifies HCV-142 demand set at 0 (ZERO) %. The valve is full open at ZERO demand. 2010 GINNA NRC JPM F, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 4 of 10 Form ES-C-1 Performance Step: 4 Standard:

Comment: Performance Step: 5 Standard:

SIMULATOR DRIVER: Procedure CAUTION Performance Step: 6 Standard:

SIMULATOR DRIVER: VERIFICATION OF COMPLETION S-3.1, Attachment 9, Steps 2.4 ENSURE an Operator is stationed at the Boric Acid pumps to listen for proper pump operation.

Determines AO standing by per Initiating Cue. S*3.1, Attachment 9, Steps 2.5 ENSURE an Operator is stationed at Seal Injection Filter to monitor differential pressure.

Pressure should be less than 20 PSID on PIC-183. Determines AO standing by per Initiating Cue. Calls the Primary Auxiliary Operator and requests the differential pressure reading on PIC-183 Report a value 15 PSID when requested.

S-3.1, Attachment 9, Steps 2.6 Boron precipitation in the seal water heat exchanger may occur IF seal water outlet temperature drops below the minimum soluble temperature based on boron concentration in solution.

SLOWLY THROTTLE CLOSE Seal Water HX CCW Outlet ISOL VLV, valve 768, UNTIL Seal Water HX Outlet TEMP IND, TI-120, reads between 85°F and 95°F AND RECORD indicated temperature.

Contacts operator standing by at Seal Water HX and records 90 'F. When contacted, report Seal Water HX Outlet temperature TI-120 reading 90*F and stable. 2010 GINNA NRC F, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 5 of 10 Form ES-C-1 Procedure CAUTION (prior to Step 2.7.1) Performance Step: 7 Standard:

Comment: Performance Step: 8 Standard:

Comment: Performance Step: 9 Standard:

SIMULATOR DRIVER: VERIFICATION OF COMPLETION S-3.1, Attachment 9, Steps 2.7 and IF seal injection is lost, THEN IMMEDIATELY RESTORE to RCP thermal barriers AND REFER to RCP Seal ALIGN Rapid Boration flow path as

• CLOSE CCW from RCP Thermal Barrier, AOV-754A. (") Rotates the handswitch for AOV-754A to the

• Verifies green indicating light lit for AOV-754A S-3.1, Attachment 9, Steps CLOSE CCW FROM RCP 1B THERMAL BARRIER,

• <") Rotates the handswitch for AOV-754B to the

• Verifies green indicating light lit for AOV-754B 5-3.1, Attachment 9, Steps 2.7.3 CLOSE Emergency Borate Inlet Isolation Valve to Charging Pumps, V-348B. Contacts AO to close Emergency Borate Inlet Isolation Valve to Charging Pumps, V-348B. Repeat back order, close V-3488 (Remote CVC28), wait a few seconds and report V-3488 closed. 2010 GINNA NRC JPM F, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 6 of 10 Form ES-C-1 VERIFICATION OF COMPLETION S-3.1, Attachment 9, Steps 2.7.4 ...J Performance Step: 10 START one SA Transfer pump. Standard: Candidate announces start and/or contacts AO at the SA Transfer Pump. (..J) Starts one SA Transfer Pump by rotating the handle to the START position. Verifies red running light lit for SA transfer pump started SIMULATOR As the AO standing by at the BA Transfer Pump: Report BA Transfer Pump just started as running with no abnormal conditions.

EXAMINER NOTE: Operator may go behind MCB and verify discharge pressure on PI-108, BA XFER PUMP DISCH PRESS EXAMINER NOTE: Annunicator G-1 will momentarily extinguish then immediately come back in. S-3.1, Attachment 9, Steps 2.7.5 ...J Performance Step: 11 OPEN EMERG SA SUPPLY VLV, MOV-350. Standard: (...J) Rotates the handswitch for MOV-350 to the Verifies the Red light lit and the Green light extinguished for MOV-350. Comment: 2010 GINNA NRC JPM F, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 7 of 10 Form ES-C-1 VERIFICATION OF Procedure CAUTION S-3.1, Attachment 9, Steps 2.7.6 DURING Rapid Boration the following SHALL be monitored for proper operation: Seal Water HX Outlet TEMP IND, TI-120 (105 of -115 OF) Seal Water HX CCW Outlet ISOL VLV, V-768, may be adjusted as required to maintain temperature during rapid boration. NON REG HX LTDN OUT TEMP, TI-130, to verify proper operation of NRHX LTDN OUTLET TEMP (TI-130), TCV-130. RCP (1N'IB) Seal wrR Inlet TEMP (TI-1321 TI-125 than 140 HI RNG RCP (1N1B) Seal Leakoff (F-177/F-178)

(1.0 to 5.0 GPM) Total Boric Acid flow: (BA EMERG FLOW FI-113) (Boric Acid Flow), Chart DIP Seal Injection Filter PRESS and CNTRLR --j Performance Step: SLOWLY THROTILE OPEN EMERGENCY BORATE INLET ISOLATION VALVE TO CHARGING PUMPS, V-348B to desired flowrate.

Standard: Contacts AO standing by V-348B to slowly throttle OPEN the valve . With the candidate observing FI-113, provides necessary direction to establish greater than 18 GPM. EXAMINER If the Candidate directs Auxiliary Operator(s) to take station at V-768 and/or TI-120, provide a repeat back. If the Candidate requests the reading on TI-120, inform them 120 still reads 90°F and steady." If the Candidate directs closing V-768 a few turns, provide repeat back and in 10-15 seconds inform them V-768 has been throttled closed and TI-120 is indicating 110°F and steady." EXAMINER TI-130, TCV-130, TI-132, TI-125, F-177, F-178 and FI-113 are all on the Main Control Board and the Plant Processing Computer.

EXAMINER CUE: If the Candidate requests the reading on PIC-183, inform them it is "15 psid and steady." SIMULATOR DRIVER: Open V-348B (Remote CVC28) in .25 increments.

During JPM workup .62 = 18 GPM. 2010 GINNA NRC JPM F, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 10 Form ES-C-1 VERIFICATION OF S-3.1, Attachment 9, Steps 2.7.7 Performance Step: 13 VERIFY Boric Acid flow. Standard:

Uses FI-113 to determines flow established in accordance with Initiating Cue. Comment: Terminating Cue: After BA flow is verified: Evaluation on this JPM is complete.

Stop time: ____ 2010 GINNA NRC JPM F, Revision NRC NUREG 1021, Revision 9, Supplement 1

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Appendix C Page 9 of 10 Form ES-C-1 VERIFICATION OF Job Performance Measure No.: 2010 GINNA NRC ..IPM F Examinee's Date Facility Number of Time to Question Result: SAT Examiner's Signature: 2010 GINNA NRC JPM F, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 10 of 10 Form ES-C-1 INITIAL INITIATING JPM CUE The plant has had a reactor trip and is entering a forced outage. Plant Management directed the RCS borated to refueling boron concentration The crew has prepared to emergency borate using S-3.1, BORON CONCENTRATION CONTROL, Attachment 9 RAPID BORATION, up to step 2.3. The CRS directs you to establish rapid boration at greater than 18 GPM in accordance with S-3.1, Attachment 9 starting at step 2.3. Assume operators are standing by at the required locations to perform the local tasks. 2010 GINNA NRC JPM F, Revision NRC NUREG 1021, Revision 9, Supplement 1

--Appendix C Job Performance Measure Form ES-C-1 Worksheet Ginna Task No.: Task Evaluate Containment Spray (CS) JPM No.: 2010 GINNA NRC JPM flow requirements and reduce flow G in accordance with E-1! LOSS OF REACTOR OR SECONDARY COOLANT KIA

Reference:

026 A4.01 Alternate Path -Step 13.c RNO implemented to reduce the number of running CS Pumps. Examinee:

NRC Facility Evaluator: Method of Simulated Performance:

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

Initial Conditions:

• Plant has experienced a DBA LOCA The crew has completed E-O and is at Step 13 of E-1, LOSS OF REACTOR OR SECONDARY COOLANT.

• CNMT pressure is lowering slowly Task Standard:

Both CS Pumps secured with system controls and valves properly aligned. Required Materials:

A marked up copy of E-1 completed to Step 13 available in the simulator.

General

References:

E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Revision 03900 Handouts:

E-1, Step 13 Initiating Cue: Perform Step 13 of E-1. Another board operator will respond to alarms NOT associated with the task. Time Critical Task: No Validation Time: 4 Minutes 2010 GINNA NRC JPM G, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 SIMULATOR SETUP Reset to IC for JPM N-G Placekeep the Control Room copy of E-O to the transition to E-1, and E-1 through completion of Step 12. 2010 GINNA NRC JPM G, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 3 of 8 Form ES-C-1 PERFORMANCE (Denote Critical Steps with a ..J) Start Time: ____ Performance Step: 1 Standard:

EXAMINER CUE: Performance Step: 2 Standard:

Comment: E-1, Step Monitor if CNMT Spray Should Be

a. CNMT spray pumps -any running Observes red light lit for each of two (2) CS pumps Observes CS flow on FI-930 Provide a copy of E-1, Step 13 (Pgs. 11 and 12 of 23), properly place-kept up to Step 13 E-1, Step Determine number of CNMT spray pumps required from Identifies that CNMT pressure is less than 4 psig on PI-945, 947, & 949 and lowering and observes D-28, CNMT PRESSURE 4 PSI, extinguished Determines four (4) CRF running by observing red lights lit. Using the values for CNMT pressure and number of Recirc Fans Running, determines 0 CNMT Spray Pumps are required.

2010 GINNA NRC JPM G, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 4 of 8 Form ES-C-1 Performance Step: 3 Standard:

Comment: " Performance Step: 4 Standard:

Comment: PERFORMANCE INFORMATION E-1, Step 13.c CNMT spray pumps running -EQUAL TO NUMBER REQUIRED Observes 2 CS pumps running using the red light lit for each pump. Recalls no CS pumps are required per step 13.b. Proceeds to step 13.c. RNO E-1, Step 13.c RNO c.1) Stop CNMT spray pumps as necessary to meet table requirements:

IF CNMT spray pump is to be stopped, THEN perform the following:

1) Place CNMT Spray Pump in PULL STOP Rotates handles counter-clockwise and then pulls out to the locked position on the following pumps: CS Pump A CS Pump B 2010 GINNA NRC JPM G, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 5 of 8 Form ES-C-1 Performance Step: 5 Standard:

EXAMINER NOTE: Performance Step: 6 Standard:

Comment: PERFORMANCE INFORMATION E-1. Step 13.c RNO IF CNMT pressure

< 4 psig, THEN perform the Place NaOH Tank outlet valve switches to OPEN AOV-836A AOV-836B Rotates switches clockwise to the OPEN position. AOV-836A AOV-836B Considered critical because it properly aligns the valves in the event that CS Pumps must be manually started should CNMT pressure start to rise. E-1, Step 13.c RNO c.2).b Reset CNMT Spray Depresses the CNMT Spray Reset PB and A-27, CNMT SPRAY, clears 2010 GINNA NRC JPM G, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 8 Form ES-C-1 " Performance Step: 7 Standard:

EXAMINER NOTE: Terminating Cue: Stop Time: ____ PERFORMANCE INFORMATION E-1, Step 13.c RNa Close discharge valves for idle CNMT Spray

• CS pump 'A'

• MOV-860A

• MOV-860B

• CS pump 'B'

• MOV-860C

• MOV-860D Closes (GREEN light illuminated) each of the four (4) valves associated with the idle CNMT Spray Pumps by rotating switches counter-clockwise:

• MOV-860A

• MOV-860B

• MOV-860C

• MOV-860D Considered critical because the intent of the step is to isolate a potential leak path out of CNMT. After closing the four discharge valves or when the operator proceeds to Step 14: Evaluation on this JPM is complete.

2010 GINNA NRC JPM G, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 8 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2010 GINNA NRC JPM G Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: 2010 GINNA NRC JPM G, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 8 of 8 Form ES-C-1 JPM CUE INITIAL CONDITIONS:

• Plant has experienced a DBA LOCA The crew has completed E-O and is at Step 13 of E-1, LOSS OF REACTOR OR SECONDARY COOLANT. CNMT pressure is lowering slowly INITIATING CUE: Perform Step 13 of E-1. Another board operator will respond to alarms NOT associated with the task. 2010 GINNA NRC JPM G, Revision NRC NUREG 1021, Revision 9, Supplement 1

--Appendix C Job Performance Measure Form ES-C-1 Worksheet-_.._---------

Ginna Task No.: Task Place Standby AFW System In JPM No.: 2010 GINNA NRC JPM Service per FR-H.1, RESPONSE H TO LOSS OF SECONDARY HEAT SINK KIA

Reference:

E05 EA1.1 Alternate Path -RNO entry during ATT-22.0 NRC Examiner:

Facility Date: Method of testing: Simulated Actual Performance:

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

Initial Conditions:

• The plant was at power when both Main Feedwater Pumps tripped. Bus 16 has an overcurrent fault. The A Motor Driven Auxiliary Feedwater Pump is removed for maintenance. The Turbine Driven Auxiliary Feedwater Pump has steam supplied to it from both the A and B Steam Generators but is not supplying feedwater.

Mechanical Maintenance is investigating the problem. The crew is responding per FR-H.1 and has completed the procedure up to step 5 While in FR-H.1 the A S/G sustained a 120 GPM tube rupture. Task Standard:

The C SAFW Pump started with a flowpath to the B S/G established.

Required Materials:

None General

References:

• ATT-22.0, RESTORING FEED FLOW, Rev 00500 FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, Revision 03801 Handouts:

• ATT-22.0, RESTORING FEED FLOW FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK 2010 GINNA NRC JPM H, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Initiating Cue: The CRS directs you to complete steps 5 and 6 of FR-H.1 to feed the B S/G. Time Critical Task: No Validation Time: 6 Minutes 2010 GINNA NRC JPM H, Revision NRC NUREG 1021. Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 SIMULATOR SETUP Reset to IC for NRC N-H Placekeep the Control Room copy of E-O immediate Placekeep the Control Room copy of Placekeep the Control Room copy of FR-H.1 through step Place tags on MOV-4007 and the A MDAFW 2010 GINNA NRC JPM H, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 4 of 11 Form ES-C-1 VERIFICATION OF COMPLETION (Denote Critical Steps with a ../) Start Time: ____ Performance Step: 1 Standard:

EXAMINER NOTE: Performance Step: 2 Standard:

EXAMINER CUE: EXAMINER NOTE: FR-H.1, step 5 Reset SI If Actuated <../) Depresses the SI RESET pushbutton Verifies Annunicator K-6 extinguishes.

During a Safety Injection, MOV thermal overload relays are bypassed.

The thermal overloads are put back in service by resetting Safety Injection.

Therefore, if K-6 is extinguished, SI is RESET. FR-H.1, step 6 Try to establish SAFW flow to at least one intact S/G: Perform the following:

1) Align SAFW system for operation (Refer to A 5.1, ATTACHMENT SAFW) Refers to Attachment 5.1. Provide a copy of A TT-5.1 SAFW controls and indications are on the back of the MCB Panel. 2010 GINNA NRC JPM H, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 5 of 11 Form ES-C-1 Procedure Performance Step: Standard:

Comment: Performance Step: 4 Standard:

Comment: VERIFICATION OF COMPLETION ATT-5.1, A) If selected S/G Wide Range Level less than 50 Inches (100 Inches Adverse CNMT), then refer to Attachment 22.0, Restoring Feed Flow, prior to starting SAFW Pump. If SW is not available to SBAFW THEN refer to ER-AFW.1 ALTERNATE WTER SUPPLY TO THE AFW PUMPS, to align city water to the SBAFW Pumps. Determines S/G "A" WR level is greater than 50" by checking LI-504 and LI-505 and associated recorders. Verifies SW is available by verifying PI-2060 and 2061 indicate approximately 55 psig. Observes the Red light lit for the A, C and D Service Water pumps ATT-5.1, B) Align SAFW Pump C to selected S/G as follows: 1) Ensure SI Reset Observes K-6, THERMAL OVERLOAD RELAY BYPASSED extinguished or indicates that SI has NOT actuated 2010 GINNA NRC H, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 6 of 11 Form Performance Step: 5 Standard:

Comment: Performance Step: 6 Standard:

Comment: Performance Step: 7 Standard:

Comment: VERIFICATION OF COMPLETION ATT-5.1, 8) 2) Ensure the following valves open: MOV-9701A, SAFW PUMP C DISCHARGE VLV MOV-4616, AUX BLDG SW ISOL VLV MOV-9704A, SAFW PUMP C ISOL VLV Verifies Red light is lit for the following valves: MOV-9701A, SAFW PUMP C DISCHARGE VLV MOV-4616.

AUX BLDG SW ISOL VLV MOV-9704A, SAFW PUMP C ISOL VLV ATT-5.1, 8) 3) Open MOV-9629A.

SAFW PUMP C SUCTION VLV (",f) Rotates the handswitch to the OPEN position (RED light illuminated) on MOV-9629A, SAFW PUMP C SUCTION VLV. Observes the Red light lit for MOV-9629A, SAFW PUMP C SUCTION VLV. ATT-5.1, A) 4) Verify at least 1 SW pump running Returns to front of MCB and observes the Red light lit for the A, C and 0 Service Water pumps Observes approximately 55 psig on PI-2160 and 2161, SW Header Pressure.

2010 GINNA NRC JPM H. Revision NRC NUREG 1021, Revision 9, Supplement 1

-I Appendix C Procedure Note: Performance Step: 8 Standard:

EXAMINER CUE: EXAMINER CUE: EXAMINER NOTE: Performance Step: 9 Standard:

Comment: Page 7 1 VERIFICATION OF ATT-S.1, B) Sb) Perform step 5a to feed A S/G OR step 5b to feed 8 S/G. To feed S/G 8, perform the following: Ensure MOV-9746, SAFW PMP D EMERG DISCH VLV, open Close MOV-9704A, SAFW PUMP C ISOL VLV Open either SAFW CROSSOVER VLV: MOV-97038 Verify open MOV-97048, SAFW PUMP D ISOL VLV. Calls an Auxiliary Operator to determine the position of 9746 (-I) Rotates the switch for MOV-9704A to the CLOSE position and observes the Green light lit and Red light extinguished. (-I) Rotates the switch for MOV-9703A to the OPEN position and observes the Red light lit and Green light extinguished. Calls an Auxiliary Operator to determine the position of 97048 When contacted as an Auxiliary Operator to check to position of MOV-9746, inform the Candidate "MOV-9746 indicates OPEN." When contacted as an Auxiliary Operator to check to position of MOV-9704B, inform the Candidate "MOV-9704B indicates OPEN." Since only Train A has power, the Candidate will not attempt to manipulate MOV-9703B.

ATT-S.1, B) 6) Restore SAFW flow as directed by procedure in effect. Transitions back to FR-H.1, Step 6.a.2 2010 GINNA NRC JPM H, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 8 of 11 Performance Step: 10 Standard:

Comment: Procedure Caution: Procedure Note: Performance Step: 11 Standard:

Comment: VERIFICATION OF COMPLETION FR-H.1, step 6.a.2 Determine SAFW flow requirements per ATT-22.O, ATTACHMENT RESTORING FEED FLOW Refers to ATT-22.0 ATT -22.0, step 1 Feed flow rates should be controlled to prevent excessive RCS cooldown and associated RCS pressure and inventory reduction. The attachment provides the desired feed flow rate restoring feed flow to a S/G during If feedwater is restored via main feedwater or condensate the following may be used to indicate flow to the S/G: S/G feedwater flow meters (MCB) S/G feedwater flow recorders (MCB) S/G feedwater flow (PPCS Point ID F0466, F0467, S/G feedwater RTD temperature lowers (PPCS Point T2096, Initiate Feed flow as follows: Bleed and Feed initiated or required Determines Bleed and Feed has not been initiated by observing PCV-430 and 431C are CLOSED Determines Bleed and Feed is not required by observing greater than 50 inches of water in both S/Gs and PZR pressure less than 2335 psig. Proceeds to 1.a RNO 2010 GINNA NRC ..IPM H, Revision NRC NUREG 1021, Revision 9, Supplement 1

-I Appendix Performance Step: 12 Standard:

EXAMINER NOTE: Performance Step: 13 Standard:

Comment: Performance Step: 14 Standard:

Comment: Terminating Cue: Stop Time: ____ Page 9 11 Form ES-C-1 VERIFICATION OF COMPLETION ATT -22.0, step 1.a. RNa IF feedwater flow to affected S/G greater than 50 gpm OR affected SG level greater than 50 inches (100 inches adverse CNMT), THEN fill as desired to restore narrow range greater than 7% (25% adverse CNMT) and go to step 2 of this attachment. Determines both S/Gs Wide Range levels are greater than 50 inches Determines the feedflow restoration rate is unlimited.

The Candidate may perform steps 2 and 3 of A TT -22.0. Those steps are not necessary to perform. FR-H.1, step 6.a.3 Start selected SAFW pumps (-I> Rotates the handle for the C SAFW Pump to the START position (RED light illuminated) Verifies the Red light is lit for the C SAFW Pump FR-H.1, step 6.a.4 When intact S/G level GREATER THAN 50 inches (100 inches adverse CNMT), THEN verify SAFWflow GREATER THAN 215 GPM. Verifies flow GREATER THAN 215 GPM but LESS THAN 280 GPM per pump on FI-4084B.

After SAFW flow is verified:

Evaluation on this JPM is complete.

2010 GINNA NRC JPM H, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C 10 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2010 GINNA NRC JPM H Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: 2010 GINNA NRC JPM H, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 11 of 11 Form ES-C-1 INITIAL INITIATING JPM CUE The plant was at power when both Main Feedwater Pumps tripped. Bus 16 has an overcurrent fault. The A Motor Driven Auxiliary Feedwater Pump is removed for maintenance. The Turbine Driven Auxiliary Feedwater Pump has steam supplied to it from both the A and B Steam Generators but is not supplying feedwater.

Mechanical Maintenance is investigating the problem. The crew is responding per FR-H.1 and has completed the procedure up to step 5 While in FR-H.1 the A SIG sustained a 120 GPM tube rupture. The CRS directs you to complete steps 5 and 6 of FR-H.1 to feed the B S/G. 2010 GINNA NRC ..'PM H, Revision NRC NUREG 1021, Revision 9, Supplement 1

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Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Task No.: Task Title: Release the "D" Gas Decay Tank ..IPM 2010 GINNA NRC JPM I KIA

Reference:

071 A4.27 Alternate Path -R-14 goes into alarm and the release must be secured. Examinee:

NRC Facility Evaluator: Method of Simulated Performance:

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

Initial Conditions:

• Today is 4/26/2010.

• The "D" GDT is full and approved for release.

• The "D" GDT does not have elevated activity.

• The previous crew has started S-4.2.5. Task Standard:

Lineup and release the D GDT in accordance with the procedure and secure the release Required Materials:

Hard Hat, Safety Glasses, Hearing Protection, Safety Shoes and Dosimetry.

General

References:

S-4.2.5, Release of Gas Decay Tank, Rev. 19 Handouts:

Marked up copy of S-4.2.5, Release of Gas Decay Tank, Rev. 19 Initiating Cue: The Control Room Supervisor directs you to release the "D" GDT per 4.2.5, Release of Gas Decay Tank. The Extra Auxiliary Operator has removed the required tag out and completed the necessary paperwork.

2010 GINNA NRC JPM I, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: No Validation Time: 11 Minutes 2010 GINNA NRC JPM I, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP N/A 2010 GINNA NRC JPM I, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 4 of 10 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a -V) Start Time: ___ Performance Step: 1 Standard:

Evaluators Cue: Performance Step: 2 Standard:

Comments:

S-4.2.5, Section 1, 2, 3 and 4 Reviews Sections 1, 2, 3 and 4 Reviews sections 1, 2, 3 and 4 Provide the candidate with the JPM I Handout (a copy of the procedure completed up to Section 5). S-4.2.5, Section 5 INSTRUCTIONS: This procedure is divided into the following sections:

N/A sections for tanks not to be released.

5.1 GDT A Release 5.2 GDT B Release 5.3 GDT C Release 5.4 GDT D Release Marks Sections 5.1, 5.2 and 5.3 as N/A. 2010 GINNA NRC JPM I, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 3 Standard:

EXAMINER CUE: EXAMINER CUE: EXAMINER CUE: EXAMINER NOTE: Performance Step: 4 Standard:

EXAMINER CUE: EXAMINER NOTE: Performance Step: 5 Standard:

EXAMINER CUE: EXAMINER NOTE: Page 5 of 10 Form ES-C-1 PERFORMANCE INFORMATION S-4.2.5, Section 5.4 GDT D Release: 5.4.1 Close inlet AOV to D GDT PCV-1 039A. Verifies PCV-1039A GREEN light is lit and initials the step. A Caution Tag is installed on the switch. (There may actually be a caution tag on the switch if the D GDT is being held for release.)

After the switch is located: The Green light for PCV-1039A is LIT. If the Candidate calls the Control Room and requests permission to operate Caution Tagged valves, give them permission.

The switch is on the Waste Panel S-4.2.5, step Close GDT D Reuse Control Verifies the switch for AOV-1632 is in the CLOSED position (GREEN light) and initials step. After the switch is located: The Green light for AOV-1632 is LIT. The switch is on the Waste Panel S-4.2.5, step Close GDT D outlet AOV to Gas Analyzer Verifies the GREEN light lit for PCV-10398 and initials step. After the switch is located: The Green light for AOV-1039B is LIT. The switch is on the Waste Panel 2010 GINNA NRC JPM I, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 6 Standard:

EXAMINER NOTE: EXAMINER NOTE: EXAMINER CUE: EXAMINER CUE: Performance Step: 7 Standard:

EXAMINER EXAMINER Page 6 of 10 Form ES-C-1 PERFORMANCE INFORMATION S-4.2.5, step Lock closed GOT manual outlet valves on all (GOT A) V-1617 Locked Closed __ (GOT B) V-1618 Locked Closed __ (GOT C) V-1619 Locked Closed __ (GOT 0) V-1620 Locked Closed __ Verifies the following valves are locked closed and initials: V-1617 ___ V-1618 ___ V-1619 ___ V-1620 ___ To check the valve locked close the Candidate will attempt to rotate the valve in the Clockwise direction and check to see if the locking device is locked. The Candidate may perform Performance Steps 6 and 7 in reverse order to minimize the number of times required to walk up and down stairs. For each valve, the locks are locked and the valves do not rotate in the clockwise direction.

If asked, the eSoms location for these valves are Aux BLO Intermediate level GOT alley 5' (V-1617 and 1618) and l' 1619 and 1620) elevation.

S-4.2.5, step 5.4.5 Close GOT release AOV to Plant Vent via Charcoal Filter 14. Simulates rotating knob for RCV-14 Counter Clockwise direction Observes Green light lit. Observes air pressure reads 0 psig on the air pressure gauge. The knob does not rotate in the counter clockwise direction.

The switch is on the Waste Panel 2010 GINNA NRC JPM I, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 8 Standard:

EXAMINER CUE: Performance Step: 9 Standard:

EXAMINER CUE: EXAMINER CUE: Performance Step: 10 Standard:

EXAMINER CUE: EXAMINER CUE: EXAMINER CUE: EXAMINER CUE: Page 7 of 10 Form ES-C-1 PERFORMANCE INFORMATION 5-4.2.5, step 5.4.6 Remove Hold on V-1620. Verifies the hold on V-1620 is removed and step initials.

The Extra Auxiliary Operator has removed the Danger Tag and completed the necessary paperwork.

S-4.2.5, step Unlock and open GOT 0 manual outlet Describes unlocking V-1620 Simulates rotating V-1620 in the Counter Clockwise direction After the candidate describes lock removal: The Lock is removed. The valve no longer rotates in that direction.

5-4.2.5, step 5.4.7 Throttle open GOT release AOV to Plant Vent via Charcoal Filter RCV-014 (may be full open) to desired release rate. (..J) Simulates rotating knob for RCV-14 Clockwise Observes both RED and GREEN light lit. Observes air pressure rising on the air pressure gauge. Air pressure is rising. When the valve is being opened: Both the Red and Green lights are lit. When the valve is full open: The Red light is lit. R-14 indicates increasing counts Approximately 10 to 15 seconds after RCV-14 is opened, as the Control Room, inform the Candidate "R-14 reads 2 X 10 5 CPM." Also, R-14 indicates 2 X 10 5 CPM on the Waste Panel. 2010 GINNA NRC JPM I, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 10 Form ES-C-1 PERFORMANCE INFORMATION S-4.2.5, Section 4.0 --./ Performance Step: 11 4.0 Precautions:

4.2 Insure that RCV-14 closes in event of a high alarm on R-14. Standard:

• (--./) Simulates rotating knob for RCV-14 Counter Clockwise

• Observes the GREEN light lit.

• Observes air pressure lowering on the air pressure gauge. EXAMINER CUE: Air pressure is EXAMINER CUE: When the valve is closed: The Green light is EXAMINER CUE: R-14 indicates lowering Terminating Cue: When the Candidate closes RCV-14: This JPM is complete.

Stop Time: ___ 2010 GINNA NRC JPM I, Revision NRC NUREG 1021, Revision 9, Supplement 1

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Appendix C Page 9 of 10 Form ES-C-1 VERIFICATION OF Job Performance Measure No.: 2010 GINNA NRC JPM I Examinee's Date Facility Number of Time to Question Result: SAT Examiner's Signature: 2010 GINNA NRC JPM I, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 10 of 10 Form ES-C-1 INITIAL INITIATING JPM CUE

• Today is 4/26/2010.

• The "D" GDT is full and approved for release.

• The "D" GDT does not have elevated activity.

• The previous crew has started S-4.2.5. The Control Room Supervisor directs you to release the tiD" GDT per S-4.2.5, Release of Gas Decay Tank. The Extra Auxiliary Operator has removed the required tagout and completed the necessary paperwork.

2010 GINNA NRC I, Revision NRC NUREG 1021, Revision 9, Supplement 1

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

Ginna Task No.: Task Title: Secure Ventilation Systems During JPM No.: 2010 GINNA NRC a Fire JPM J KIA

Reference:

APE067 AA1.05 (3.0/3.1)

Examinee:

NRC Facility Evaluator: Method of Simulated Performance:

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

Initial Conditions:

• A fire has occurred on the intermediate floor of the Auxiliary Building. The operators are responding per procedure FRP-5.0, Auxiliary Building (AB) Intermediate Floor. Auxiliary Building Ventilation system is in operation. All equipment required to enter the Auxiliary Building has been donned. Task Standard:

Secure Auxiliary Building ventilation fans specified in the procedure.

Required Materials:

Hard Hat, Safety Glasses, Hearing Protection, Safety Shoes and Dosimetry.

General

References:

FRP-5.0, Auxiliary Building (AB) Intermediate Floor, Rev. 801 Handouts:

A marked up copy of FRP-5.0, Auxiliary Building (AB) Intermediate Floor, Rev. 801 Initiating Cue: The Shift Manager has directed you to secure ventilation in accordance with FRP-5.0, Step 1.5. Time Critical Task: No 2010 GINNA NRC JPM J, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Validation Time: 8 Minutes 2010 GINNA NRC JPM J, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP N/A 2010 GINNA NRC JPM J, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 4 of 10 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a ..J) Start Time: ___ Procedure Note: ..J Performance Step: 1 Standard:

EXAMINER CUE: EXAMINER NOTE: EXAMINER NOTE: EXAMINER NOTE: EXAMINER NOTE: EXAMINER CUE: FRP-5.0, step 1.5 Securing AB Exh C will cause automatic shutdown of A AHU and B supply. Turning the master switch to OFF will secure other fans listed: Ventilation: Upon conformation of any fire in the Auxiliary Building, secure the following

(***). FAN SWITCH BUS/MCC/LP POSITION *** AB Exh C Local D 3M

• Simulates rotating the AB Exh C switch to STOP

• Verifies the RED light is extinguished.

The as found position is the switch in the ON position and the RED light lit. These Performance Steps may be performed in any order. The switch is located on the AB Exh C fan housing on the Intermediate Building (Hot Side) Top Level. When the Candidate turns off AB Exh C the AB Supply A AHU and the AB B Supply fan will deenergize.

If the Candidate realizes this, they may skip Performance Step 2. (***) Identifies the fans that must be secured to ensure ventilation is secured to the area. After the Candidate rotates the switch to STOP, inform them "The RED light is extinguished." 2010 GINNA NRC JPM J, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 10 Form ES-C-1 Performance Step: 2 Standard:

EXAMINER CLlE: EXAMINER NOTE: EXAMINER NOTE: EXAMINER NOTE: EXAMINER CUE: PERFORMANCE INFORMATION FRP-5.0, step 1.5.1 Upon confirmation of any fire in the Auxiliary Building, secure the following

(***). SWITCH BUS/MCC/LP POSITION *** AB Supply A AHU Vent Panel 13 8C AB B Supply Vent Panel C 5F Simulates rotating the AUX BLDG AIR HANDLING UNIT switch to STOP. OR Verifies GREEN lights are lit for the A and B AB Supply AHU. The as found position is the GREEN lights lit for both the 1A AUX BLDG SUPPLY AIR HANDLING UNIT AND SUPPLY FAN 1B. The switch is located at the Auxiliary Building Ventilation Panel in the Intermediate Building (Hot Side) Middle Level. This is a common switch for both the AB Supply A AHU and AB B Supply fans. The Candidate may not perform this step since when they turn off AB Exh C the AB Supply A AHU and the AB B Supply fan will deenergize.

After either operating the AB Exh C switch or AUX BLDG AIR HANDLING UNIT switch: The GREEN lights are lit for the AB Supply A and B AHU 2010 GINNA NRC JPM J, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 10 Form ES-C-1 PERFORMANCE Performance Step: 3 Standard:

EXAMINER CUE: EXAMINER NOTE: EXAMINER NOTE: EXAMINER NOTE: EXAMINER NOTE: EXAMINER CUE: FRP-5.0, step 1.5.1 Upon conformation of any fire in the Auxiliary Building, the following FAN SWITCH BUS/MCC/LP IB Exh. NB Local FlO IP Exh. C Local (IB cold) F CA Exh. NB Vent Panel FlO AB Exh. F Local ACPOPAB02 Simulates rotating the Control Switch For Auxiliary Ventilation System (Master Control) switch to the OFF Simulates rotating the following switches to the OFF

• IB Exh. NB

• IP Exh. C

• CA Exh. NB

• AB Exh. F The as found position is in the ON position.

The Candidate may either operate the Master Control Switch or each fan's switch individually.

Either choice is correct. The Master Switch controls the IB Exh. AlB, IB Exh. C, CA Exh. AlB and AB Exh. F fans. Per 1.5.1, the Candidate may not take any action during this Performance Step. The Master Control Switch is located at the Auxiliary Building Ventilation Panel in the Intermediate Building (Hot Side) Middle Level. The IB Exh. AlB switch is located in the Intermediate Building (Hot Side) Top Level. The IB Exh. C switch is located in the Intermediate Building (Cold Side) Basement.

The CA Exh. AlB switch is at the Auxiliary Building Ventilation Panel in the Intermediate Building Middle Level. The AB Exh. F is in the Auxiliary Building Middle Level. After the Candidate manipulates any of the listed switches, inform them "The switch is in the OFF position." 2010 GINNA NRC JPM J, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Procedure Note: " Performance Step: 4 Standard:

EXAMINER CUE: EXAMINER NOTE: EXAMINER CUE: Performance Step: 5 Standard:

EXAMINER CUE: EXAMINER NOTE: Page 7 of 10 Form ES-C-1 PERFORMANCE INFORMATION FRP-5.0, step 1.5.1 The following must be secured LOCALLY. G fan will trip with 1 fire detector signal in G HEPA, and alarm. If 4 detectors signal, S02 suppression will actuate. Upon conformation of any fire in the Auxiliary Building, secure the following

(***). FAN SWITCH BUS/MCC/LP POSITION *** AB Main Exh. A Vent Panel 11A 9 Simulates rotating the AUX BLDG MAIN EXH FAN A switch to STOP. The as found position is RED light is lit. The switch is located at the Auxiliary Building Ventilation Panel in the Intermediate Building Middle Level. After rotating the switch to the STOP position, inform the Candidate the GREEN light is lit. FRP-5.0, step 1.5.1 Upon conformation of any fire in the Auxiliary Building, secure the following

(***). FAN SWITCH BUS/MCC/LP POSITION *** AB Main Exh. B Vent Panel 11B 23 Verifies the GREEN light is lit for the AUX BLDG MAIN EXH FAN B The as found position is GREEN light is lit. The light is located at the Auxiliary Building Ventilation Panel in the Intermediate Building Middle Level. 2010 GINNA NRC ..IPM J, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 10 Form ES-C-1 .,j Performance Step: 6 Standard:

EXAMINER NOTE: EXAMINER CUE: Terminating Cue: Stop Time: ___ PERFORMANCE INFORMATION FRP-5.0, step 1.5.1 Upon conformation of any fire in the Auxiliary Building, secure the following

(***). FAN SWITCH BUS/MCC/LP POSITION *** G Fan Local 14 21A Simulates rotating the G Fan switch to TRIP The switch is located at the G Fan Control Panel in the Auxiliary Building Top Level. If asked, inform the Candidate conditions permit you to transit to the fan's control switch. When the Candidate secures the G Fan: Evaluation on this JPM is complete.

2010 GINNA NRC JPM J, Revision NRC NUREG 1021, Revision 9, Supplement 1

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Appendix C Page 9 of 10 Form ES-C-1 VERIFICATION OF Job Performance Measure No.: 2010 GINNA NRC JPM J Examinee's Date Facility Number of Time to Question Result: SAT Examiner's Signature: 2010 GINNA NRC ..IPM J, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 10 of 10 Form ES-C-1 INITIAL INITIATING JPM CUE A fire has occurred on the intermediate floor of the Auxiliary Building. The operators are responding per procedure FRP-5.0, Auxiliary Building (AB) Intermediate Floor. Auxiliary Building Ventilation system is in operation. All equipment required to enter the Auxiliary Building has been donned. The Shift Manager has directed you to secure ventilation in accordance with FRP-5.0, Step 1.5. 2010 GINNA NRC JPM J, Revision NRC NUREG 1021, Revision 9, Supplement 1

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Appendix C Page 1 of 7 Form ES-C-1 PERFORMANCE INFORMATION Facility:

Ginna Task 039-008-01-04A Task Title: Locally Operate the ARVs JPM 2010 GINNA NRC JPM K KIA

Reference:

039 G2.1.30 (4.4/4.0)

NRC Examiner:

Facility Date: Method of testing: Simulated Performance:

x Actual Performance:

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

Initial

• You are the Head Control Operator The plant has experienced an uncontrollable Control Room Complex fire. The crew performed the required actions of AP-CR 1, CONTROL ROOM INACCESSIBILITY, and transitioned to ER-FIRE.1, ALTERNATE SHUTDOWN FOR CONTROL COMPLEX FIRE. You have completed Attachment 3, HEAD CONTROL OPERATOR (HCO) The Shift Manager is stabilizing the plant in MODE 3. All the required Appendix R equipment has been retrieved from the Appendix R locker outside the Control Room. Task Locally operate the ARV in accordance with the procedure.

Required Hard Hat, Safety Glasses, Double Hearing Protection, Safety Shoes and Dosimetry.

General

References:

ER-FIRE.1, ALTERNATE SHUTDOWN FOR CONTROL COMPLEX FIRE, Revision 2900 P-15.2, DUMP STEAM THROUGH ARV'S LOCALLY, Revision O. 2010 GINNA NRC JPM Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 2 of 7 Form ES-C-1 PERFORMANCE INFORMATION Handouts:

P-15.2, DUMP STEAM THROUGH ARV'S LOCALLY, Revision O. Initiating Cue: The Shift Manager directs you to locally open the "A" Atmospheric Relief Valve, V-3411, three turns per P-15.2. Time Critical Task: No Validation Time: 5 Minutes 2010 GINNA NRC K, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 30f7 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a-1) Start Time: Performance Step: 1 Standard:

EXAMINER NOTE: EXAMINER NOTE: Performance Step: 2 Standard:

EXAMINER NOTE: -1 Performance Step: 3 Standard:

EXAMINER CUE: P-15.2, Step 2.1 Obtain radio and establish communications with the Control Room. Establish radio communication with Shift Manager. At this point in ER-FIRE.1 all Control Room Personnel in the plant would have obtained radios from an Appendix R locker outside the Control Room. The Candidate may not perform this step since a communications check was completed earlier in ER-FIRE.1.

P-15.2, Step Obtain Ladder if Verifies a ladder is in place at A ladder is normally in place to allow access to the P-15.2, Step 2.3 Operate the handwheel on the "A" ARV (3411) to position valve as required by Control Room personnel.

Simulates turning the "A" ARV (3411) handwheel in the clockwise direction to position the valve to approximately three full turns open. The handwheel turned as desired. 2010 GINNA NRC JPM K, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 4 of7 Form ES-C-1 Performance Step: 4 Standard:

EXAMINER NOTE: EXAMINER CUE: Performance Step: 5 Standard:

EXAMINER CUE: Performance Step: 6 Standard:

EXAMINER CUE: PERFORMANCE INFORMATION P-15.2, Step 2.1 Report action to Shift Manager. Leaves noisy area (18 Main Steam Area) to make report. Reports over radio to Shift Manager that ARV-3411 is three full hand turns open. If the radio call is made from the Main Steam Area: III cannot hear you over the background noise". Acknowledge the report and then direct the Candidate to, "Slowly throttle closed the valve 1 full turn." P-15.2, Step 2.3 Operate the handwheel on the "AI> ARV (3411) to position valve to two full turns open. Simulates turning the handwheel in the clockwise direction on the "A" ARV (3411) to position valve to two full turns open. The handwheel will not turn. P-1S.2, Note prior to Step 2.3 If the ARV will not close, isolate the ARV with its root isolation.

Proceeds to "AI> ARV Root Isolation Valve (V3507) and simulates closing the valve fully by rotating the handwheel in the clockwise direction.

The handwheel turned as desired. 2010 GINNA NRC JPM K, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page 5 of 7 Form ES-C-1 Performance Step: 7 Standard:

EXAMINER NOTE: Terminating Cue: Stop Time: PERFORMANCE INFORMATION P-1S.2, Step 2.1 Report action to Shift Manager. Leaves noisy area (IB Main Steam Area) to make report. Reports over radio to Shift Manager that ARV-3411 is three full handturns open. However, because it would not close, its Root isolation valve (V3507) was closed. If the radio call is made from the Main Steam Area: "I cannot hear you over the background noise".

Otherwise, provide a repeat back. After the Candidate reports to the Shift Manager: Evaluation on this JPM is complete.

2010 GINNA NRC ,IPM K, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2010 GINNA NRC JPIVI K Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: 2010 GINNA NRC ..IPM K, Revision NRC NUREG 1021, Revision 9, Supplement 1

Appendix Page? of? Form ES-C-1 INITIAL INITIATING JPM CUE You are the Head Control Operator The plant has experienced an uncontrollable Control Room Complex fire. The crew performed the required actions of AP-CR.1 , CONTROL ROOM INACCESSIBILITY, and transitioned to ER-FIRE.1 , ALTERNATE SHUTDOWN FOR CONTROL COMPLEX FIRE. You have completed Attachment 3, HEAD CONTROL OPERATOR (HCO) The Shift Manager is stabilizing the plant in MODE 3. All the required Appendix R equipment has been retrieved from the Appendix R locker outside the Control Room. The Shift Manager directs you to locally open the "A" Atmospheric Relief Valve, V-3411, three turns per P-15.2. 2010 GINNA NRC .JPM K, Revision NRC NUREG 1021, Revision 9, Supplement 1

PROGRAM: Ginna Operations Training MODULE: 2010 Initial License Operator Training Class TOPIC: NRC Simulator Exam Scenario N 10-1-1

REFERENCES:

1. 0-6.9.2, Establishing and/or Transferring Offsite Power to Bus 12A112B 2. AR-E-14, LOSS B INSTR. BUS 3. ER-INST.3, Instrument Bus Power Restoration

4. S-3.2E, Placing In or Removing From Service Normal Letdown/Excess Letdown S. R-E-20, CNMT OR PLANT VENT RAD MON PUMP TRIP 6. AR-F-6, PRESSURIZER HEATER BREAKER TRIP 7. Technical Specification 3.8.7, AC Instrument Bus Sources Modes 1-4 8. Technical Specification 3.8.9, Distribution Systems -Modes 1,2,3 and 4 9. AR-F-2, PRESSURIZER HIGH PRESS 2310 PSI 10. AR-F-10, PRESSURIZER LO PRESS 220S PSI 11. AP-PZR.1, Abnormal PZR Pressure 12. ER-INST.1, Reactor Protection Bistable Defeat After Instrumentation Loop Failure 13. Technical Specification 3.4.1, RCS Pressure, Temperature, and Flow Departure From Nucleate Boiling (DNB) Limits 14. Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation 1S. Technical Specification 3.3.2, ESFAS Instrumentation

16. AR-I-27, ROTOR ECCENTRICITY OR VIBRATION

17. AP-TURB.3, Turbine Vibration

18. AP-TURB.S, Rapid Downpower

19. E-O, Reactor Trip and Safety Injection

20. FR-H.1, Response to a Loss of Secondary Heat Sink 21. E-2, Faulted Steam Generator Author: David Lazarony, Western Technical Services, Inc. Facility Review: Pat Landers, Principal Ops Training Specialist, 04/29/2010 Rev. 052610 -1 Scenario Event NRC Scenario Facility: Scenario No.: 1 Op Test No.: N10-1 Operators: (SRO) (RO) (BOP) Initial The plant is at 49% power (BOL). The plant power was reduced several days ago due to a malfunction on the A MFW Pump. Corrective Maintenance has been completed, and the pump is ready to be restarted.

RG&E Energy Control Center has requested that the electric plant be aligned to a 0/100 configuration on circuit 7T to allow the RG&E personnel to perform an insulator inspection on the 767 Line. Per Chemistry direction Normal Letdown is at 60 gpm.

! The following equipment is Out-Of-Service:

The B AFW Pump is OOS for Bearing i Replacement.

Event Malt. Event Type* No. No.

1 N-BOP Shift Electric Loss of B Instrument Bus 2 Pressurizer Pressure (PT -449) fails High Main Turbine High Vibration/EHC control failure 4 TUR05E TUR09D Feed Line Rupture Inside Containment 5 6 C-BOP Main Turbine Failure to Auto Trip A AFW Pump Fails after start 7 C-BOP Standby AFW fails to function OVR-I * (N)ormal, (R)eactivity, (I)nstrument, (C)om pone nt, (M)ajor -2 Scenario Event NRC Scenario Ginna 2010 NRC Scenario #1 The plant is at 49% power (BOL). The plant power was reduced several days ago due to a malfunction on the A MFW Pump. Corrective Maintenance has been completed, and the pump is ready to be restarted.

RG&E Energy Control Center has requested that the electric plant be aligned to a 0/100 configuration on circuit 7T to allow the RG&E personnel to perform an insulator inspection on the 767 Line. Per Chemistry direction Normal Letdown is at 60 gpm. The following equipment is Out-Of-Service:

The B AFW Pump is OOS for Bearing Replacement.

Shortly after taking the watch, the operator will shift the Electric Line-up from 50/50 to 0/100 in accordance with 0-6.9.2, Establishing and/or Transferring Offsite Power to Bus 12A112B. Shortly afterwards, a loss of the B Instrument Bus will occur. The operator will respond in accordance with AR-E-14, LOSS B INSTR. BUS. Power will be restored to the bus per guidance in ER-INST.3, Instrument Bus Power Restoration, which will include the isolation and establishment of Normal Letdown in accordance with S-3.2E, Placing In or Removing From Service Normal Letdown/Excess Letdown. The operator will address two additional MCB Annunciators; AR-E-20, CNMT OR PLANT VENT RAD MON PUMP TRIP, and AR-F-6, PRESSURIZER HEATER BREAKER TRIP, while restoring from the transient.

The operator will address Technical SpeCification 3.8.7, AC Instrument Bus Sources Modes 1-4, and 3.8.9, Distribution Systems -Modes 1, 2, 3 and 4. After this, the controlling Pressurizer Pressure Transmitter will fail High, causing the Spray Valves to open. The operator will respond in accordance with AR-F-2, PRESSURIZER HIGH PRESS 2310 PSI and AR-F-10, PRESSURIZER LO PRESS 2205 PSI, and enter AP-PZR.1, Abnormal PZR Pressure.

AP-PZR.1 will refer the operator to ER-INST.1, Reactor Protection Bistable Defeat After Instrumentation Loop Failure, for the defeat of PT-449. The operator will address Technical Specification 3.4.1, RCS Pressure, Temperature, and Flow Departure From Nucleate Boiling (DNB) Limits; 3.3.1, Reactor Trip System (RTS) Instrumentation; and 3.3.2, ESFAS Instrumentation.

Following this, a turbine high vibration condition on Bearing #5 will develop within about 60 seconds, and an EHC failure will occur causing the turbine to shift to manual. The operator will respond in accordance with AR-I-27, ROTOR ECCENTRICITY OR VIBRATION; and enter TURB.3, Turbine Vibration; and then AP-TURB.5, Rapid Downpower.

The operator will need to lower the Turbine Load using Manual EHC control. During the load reduction, a feed line rupture inside Containment will occur. The Reactor will trip and Safety Injection will actuate causing the operator to enter E-O, Reactor Trip or Safety Injection.

Auto turbine trip will fail to occur, but manual trip will be successful.

On the Reactor Trip the A AFW Pump will fail to Autostart, then trip after it is manually started, and the TDAFW Pump will trip on overspeed.

The operator will transition from E-O to FR-H.1, Response to a Loss of Secondary Heat Sink. The operator will unsuccessfully attempt to place the Standby AFW System in service, and then attempt to restore a Secondary Heat Sink using the MFW System. Once the Secondary Heat Sink is re-established using MFW, the operator will transition back to E-O, and then transition to E-2, Faulted Steam Generator Isolation.

-

Scenario Event NRC Scenario The scenario will terminate at Step 9 of E-2, after the crew has determined that a transition to 1, Loss of Reactor or Secondary Coolant, is required.

Critical Tasks: FR-H.1 Establish feedwater flow into at least one Steam Generator before RCS Bleed and Feed is required.

Safety Significance:

Failure to establish feedwater flow into at least one Steam Generator results in the crew having to rely upon the lower-priority action of having to initiate RCS Bleed and Feed to minimize the possibility of core uncovery.

Failure to perform this task, when able to do so, constitutes incorrect performance that leads to degradation of the RCS and/or fuel cladding fission product barriers.

E-2A Isolate the Faulted Steam Generator before transitioning out of E-2. Safety Significance:

Failure to isolate a Faulted SG that can be isolated causes challenges to the Critical Safety Functions that would not otherwise occur. Failure to isolate flow could result in an unwarranted Orange or Red Path condition on RCS Integrity, Subcriticality (if cooldown is allowed to continue uncontrollably) and/or Containment (if the break is inside Containment).

Scenario Event NRC Scenario SIMULATOR OPERATOR INSTRUCTIONS ACTMTY o .. ......'. . '.. . *.....,. Reset to Temp IIC 49% power BOL 176 (NRC 1). T=O, TUR02, Turbine fails to Auto trip To take B MDAFW pump OOS: Pull stop the B MDAFW pump Inset OVR-DO-FDW-06A, OFF (Green light OFF) Place PROTECT tags on A MDAFW and *rDAFW pumps Insert MALF RPS07K (Autostart failure of A Insert OVR-DI-FDW42D

= FALSE CLOSED, unable to Insert MALF FDW15B (SAFW pump 0 Set Trigger 30 = True when a reactor trip signal received from either Set REM FDW32, Severity = 0, T -30 (Trip valve trips to simulate overspeed condition on Set Trigger 29 to x06i236b = = 1 to activate when MDAFW pump manually Insert MALF FDW11A, 30 second delayed, T-29 MDAFW pump trip on manual start MALF EDS07B, on MALF PZR02D, 2500, 0 Ramp, on MALF TUR05E, 8 Mils, 60 second Ramp on MALF TUR09D, on T-3 (120 second MALF FDW09A, 2E+7, 120 second Ramp, on Prior to Crew

• Hang Protective Tags on the A MDAFW Pump and o the TDAFW Pump Steam Supply Valves.

• Place Black Dot on MCB Annunciator J-28 Crew Briefing o

• Assign Crew Positions based on evaluation requirements

• Review the Shift Turnover Information with the crew.

• Conduct Pre-job Brief using marked up copy of 0-6.9.2, Section 6.4 marked up as follows: o All steps in Sections 6.4.1 are marked NA o All steps in Sections 6.4.3 are marked NA o T-O Begin Familiarization Period -

Scenario Event NRC Scenario ACTMTY t . ,,;:., At direction of Event 1 0 examiner At direction of Event 2 0 examiner Trigger #1 EDS07B At direction of Event 3 0 examiner Trigger#2 PZR02D At direction of Event 4 0 examiner Trigger#3 TUR05E TUR09D At direction of Event 5 0 examiner Trigger #4 FDW09A Continued Event 6 0 from Event 5 T=O TUR02 Continued Event 7 0 from Event 5 T=O RPS07K Continued Event 8 0 from Event 5 T=O OVR-FDW42A FDW15B ..... .. Shift Electric Plant Loss of B Instrument Bus PT -449 fails High 2500, No Ramp Main Turbine High Vibration/EHC control failure 8 mils, 60 second 120 second Feed Line Rupture Inside 2E+ 7, 180 second Main Turbine Failure to Auto NOTE: This Malfunction is inserted in the IC at T = A AFW Pump Fails after NOTE: This Malfunction is inserted in the IC at T = T -29 (When pump manually started) (30 Standby AFW fails to NOTE: This Malfunction is inserted in the IC at T = FALSE (MOV-9629A CLOSED, unable to (SAFW pump D Terminate the scenario upon direction of Lead Examiner -0 i Appendix Operator Action Form ES-O-2 Op Test No.: N10*1 Scenario # 1 Event # 1 Page 7 of 50 Event

Description:

Shift Electric Plant I Shortly after taking the watch, the operator will shift the Electric Line-up from 50/50 to

• 0/100 in accordance with 0-6.9.2, Establishing andlor Transferring Offsite Power to Bus 12A112B. Booth Operator Instructions:

NA Indications Available:

NA 0-6.9.2, ESTABLISHING ANDIOR TRANSFERRING OFFSITE POWER TO BUS 12A1BUS 12B CO (Step 6.4.2) ESTABLISH Offsite Power . 12B Bus using Circuit 7T as (1.) VERIFY CLOSED CIRCUIT BKR 7T1352 34 KV BUS. (2.) TURN ON BUS 12B ALT FEED FROM 7T, 52/12AX SYNCHROSCOPE (3.) CLOSE BUS 12B ALT FEED FROM 7T,52/12AX.

(4.) IF BUS 12B NORMAL FEED FROM 767, 52/12BX was previously closed, THEN PERFORM the following:

IF NOT, THEN MARK this Substep N/A VERIFY BUS 12B NORMAL FEED FROM 767, 52/12BX OPENS. (Green AND White light indication is expected.) PLACE BUS 12B NORMAL FEED FROM 767, 52/12BX Control switch to the TRIP position AND THEN to AUTO. (5.) VERIFY BUS 12B NORMAL FEED FROM 767, 52/12BX is OPEN AND RESET. (Green light illuminated AND White light extinguished.)

(6.) IF BUS 12B NORMAL FEED FROM NOTE: 52/12BX is OPEN. 767, 52/12BX is NOT OPEN, THEN (7.) VERIFY approximately 4000 VOLTS is indicated on BUS 12B VOLTMETER 4160 V.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 1 Event # -.;...____ Page 8 of 50 Event

Description:

Shift Electric Plant co (8.) TURN OFF BUS 12B ALT FEED FROM 7T, 52/12AX SYNCHROSCOPE AND REMOVE the handle. SIM DRIVER: Use REM EDS50 to clear 12B transformer alarm L-28 At the discretion of the Lead Examiner move to Event #2.

Appendix Operator Action Form ES-O-2 Op Test No.: N10-1 Scenario # 1 Event #

____ Page 9 of 50 Event

Description:

Loss of B Instrument Bus Shortly afterwards, a loss of the B Instrument Bus will occur. The operator will respond in accordance with AR-E-14, LOSS B INSTR. BUS. Power will be restored to the bus per guidance in ER-INST.3, Instrument Bus Power Restoration, which will include the isolation and re-establishment of Normal Letdown in accordance with S-3.2E, Placing In or Removing From Service Normal Letdown/Excess Letdown. The operator will address three additional MCB Annunciators; AR-E-20, CNMT OR PLANT VENT RAD MON PUMP TRIP; AR-F-6, PRESSURIZER HEATER BREAKER TRIP; and K032, SG BLOWDOWN TANK HIGH LEVEL while restoring from the transient.

The operator will address Technical Specification 3.8.7, AC Instrument Bus Sources Modes 1-4, and 3.8.9, Distribution Systems -Modes 1, 2, 3 and 4. Booth Operator Instructions:

Operate Trigger #1 (EDS07B) Indications Available: Multiple MCB Annunciators MCB Annunciator E-14, LOSS B INSTR. BUS White and Red Bistable Status lights extinguish VCT Level {L T -112} fails low causing continuous Auto Makeup Tavg-Tref is 12°F (1 st Stage Pressure has failed Low), with an Auto Rod Inward green Status light, but NO Auto Rod motion Normal Letdown has isolated due to one PZR level channel failing low AR-E-14, LOSS B INSTR BUS CRS Restore power to Instrument Bus (Refer to ER-INST.3, BUS POWER CRS Evaluate plant conditions determine if additional action required by referring to the ITS LCO 3.8.7 and 3.8.8 CRs 3. Notify the following:

NOTE: The CRS may notify . theWCC.a SM Booth Instructor:

as WCCS, a Electricians acknowledge.Electrical Planner NOTE: The CRS will go to INST.3.

Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 1 Event # 2 Page 10 of 50 Event

Description:

Loss of B Instrument Bus ER-INST.3, INSTRUMENT BUS POWER RESTORATION (Step 4.1.1) Verify an alternate power is available by checking supply voltage Maintenance-Supply voltage approximately 120 volts (EIICVTAUX, above Instr Bus D) (Step 4.1.2) Close letdown isolation valve, NOTE: The HCO will isolate AOV-427. Normal Letdown. NOTE: VCT level indication is lost, and with LID isolated, actual level is lowering, and CRS should direct AO to monitor VCT level locally (no ER-INST.3 procedure guidance)

HCO (Step 4.1.3) Place charging pump controllers NO'rE: The HCO will place in MANUAL Charging Pump speed control in Manual. NOTE: The HCO may place the Auto Makeup to the VCT in Manual to prevent overfilling the VCT. (Step 4.1.4) Place hotweillevel controller manual, if (Step 4.1.5) Place PRZR CONTROLLER 431K in MANUAL, HCO (Step 4.1.6) Place rods in NOTE: The HCO will place Rods in Manual. (Step 4.1.7) Transfer Instrument Bus to an NOTE: The CRS will direct the available power supply. (Maintenance or bus to be energized from the Normal) Maintenance supply Appendix Operator Action Form ES-D-2 Op Test No.: Nl0-l Scenario # 1 Event # ...,:2:.-____

Page 11 of . Event

Description:

Loss of B Instrument Bus Unlocks A, C, &D cabinets to ensure no other instrument busses are on the Maintenance supply Unlocks B cabinet, and shifts NOTE: Instrument Bus B is maintenance bus supply breaker i now re-energized forcibly to the left (Step 4.1.8) Checks Instrument Bus B supply ! NOTE: 0-6.11 requires voltage within ITS limits (Refer to 0-6.11, voltage between 113-123V 'I Surveillance Requirements/Routine Ops Check . (Step 4.1.9) Go to Step 4.4 . (Step 4.4.1) Verify one Charging Pump i AUTO, IF HCO (Step 4.4.2) Verify PRZR i CONTROLLER 431K in HCO ,(step 4.4.3) IF letdown isolation valve, 427 has been closed, THEN restore as HCO (Step 4.4.3.1) Complete removal of normal NOTE: Removed per Section letdown from service per S-3.2E, PLACING 5.2 of S-3.2E IN OR REMOVING FROM SERVICE NORMAL LETDOWN/EXCESS LETDOWN. NOTE: The CRS will hand this off to the HCO or the CO . . S-3.2E, PLACING IN OR REMOVING FROM SERVICE NORMAL LETDOWN/EXCESS LETDOWN I I I HCO/ (Step 5.2.1) Place Charging Pumps CO i I Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 1 Event # _2;;;;.....

____ Page 12 of ...,;5;.;;,0---..., Event

Description:

Loss of B Instrument Bus HCOI (Step 5.2.2) Close Letdown Orifice isolation CO valves AOV-200A Closed AOV-200B Closed AOV-202 Closed HCOI (Step 5.2.3) Close LTDN ISOLATION VLV CO RHR to NRHX AOV-427. (Step 5.2.4) Reduce charging flow while throttling closed charging flow to Regenerative Heat Exchanger HCV-142 to maintain >20" RCP labyrinth seal t.P. Shift to single Charging Pump operations if desired. HCOI (Step 5.2.5) Close Letdown Isol vlv RHR to CO NRHX AOV-371. HCO/ (Step 5.2.6) Place NRHX L TDN OUTLET CO TEMP (TI-130) TCV-130 in MANUAL/CLOSED TE: The CRS will continue with ER-INST.3.

ER-INST.3, INSTRUMENT BUS POWER RESTORATION (Step 4.4.3.2) Restore normal letdown per S-NO'rE: Restored per Section 3.2E, PLACING IN OR REMOVING FROM 5.3 of S-3.2E SERVICE NORMAL LETDOWN/EXCESS LETDOWN. NOTE: The CRS will hand this off to the HCO or the CO. S-3.2E, PLACING IN OR REMOVING FROM SERVICE NORMAL LETDOWN/EXCESS LE'rDOWN Appendix Operator Action Form ES-O-2 Op Test No.: N10*1 Scenario # Event # ....;2=--____

Page 13 of ..;;.;50;"'--11

• Event

Description:

Loss of B Instrument Bus HCOI (Step 5.3.1) Determine if a flush is required. If the letdown line has been isolated for less than one hour perform section 5.3.2 and N/A section 5.3.3 with permission of the Shift Manager or Control Room Foreman. HCOI (Step 5.3.2) Restore Letdown Without a CO Flush HCOI (Step 5.3.2.1) Ensure letdown is secured per CO Step 5.2 prior to restoring.

HCOI (Step 5.3.2.2) If charging flowpath to Loop B CO COLD leg is desired (preferred method) perform the following:

HCOI (Step 5.3.2.2.1)

Ensure charging valve to CO Loop B Hot, AOV-392A is closed. HCOI (Step 5.3.2.2.2)

Open charging valve to Loop CO B Cold, AOV-294. HCOI (Step 5.3.2.3) If Charging flowpath to Loop B CO HOT leg is desired, ..... HCOI (Step 5.3.2.4) Start a second Charging Pump CO at minimum speed. HCOI (Step 5.3.2.5) Slowly open charging flow to CO Regenerative Heat Exchanger HCV-142 to reduce labyrinth seall1P to -40". HCOI (Step 5.3.2.5.1)

Adjust Charging Pump CO speed to establish

-40" labyrinth seall1P with HCV-142 full open. NOTE: Since letdown has been isolated ON L Y a few minutes, a flush will NOT be required.

NOTE: Charging alignment to the Hot Leg will NOT be desired.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 1 Event # ...;2;;;.....

____ Page 14 of 50 Event

Description:

Loss of B Instrument Bus HCOI (Step 5.3.2.5.2)

Establish gpm CO line HCOI (Step 5.3.2.7) Place Low PRESS CO PRESS PCV-135 in MANUAL at -60% HCOI (Step 5.3.2.7.1)

Place NRHX LTON CO TEMP, TI-130, in MANUAL at -60% HCOI (Step 5.3.2.8) Open Letdown Isolation CO RHR to NRHX HCOI (Step 5.3.2.9) Place L TON LOOP B CO LEG TO RHX AOV-427 to OPEN and to HCOI (Step 5.3.2.10)

Open desired Letdown CO valve AOV-200A, 200B, or 202 (proceed next step without HCOI (Step 5.3.2.11)

Adjust LOW PRESS L CO PRESS PCV-135 to achieve pressure of -250 psig on HCOI (Step 5.3.2.12)

Place LOW PRESS L CO PRESS, PCV-135IN HCOI (Step 5.3.2.13)

Place NRHX L TON OUTLET Examiner NOTE: At the CO TEMP (TI-130) TCV-130 in AUTO at the discretion of the Lead normal setpoint.

Examiner move to Event #3. HCOI (Step 5.3.2.14)

Place Pressurizer CO control (Charging Pump) in NOTE: The CRS will continue with ER-INST.3, Step 4.4.4.

Appendix Operator Action Form ES-D-2 Op Test No.: Nl0*1 Scenario # 1 Event # ._2______ Page 15 of

-. Event

Description:

Loss of B Instrument Bus . , ER-INST 3 INSTRUMENT BUS POWER RESTORATION I i (Step 4.4.4) Restore EH control AUTOIIMP IN, IF I (Step 4.4.5) Restore ROD CONTROL BANK NOTE: The HCO will place the SELECTOR Switch to AUTO, if desired. Rods back in Auto. HCO (Step 4.4.6) Verify CNMT ventilation isolation I is reset. I (Step 4.4.7) Verify hotwell level controller in I AUTO, if desired. i (Step 4.4.8) Restore desired SW (Step 4.4.9) Ensure motor fire pump (Step 4.4.10) Dispatch an AO to verify proper! NOTE: The CRS will dispatch operation of battery chargers if necessary.

anAO. Booth Instructor:

as AO, acknowledge.

HCOI . (Step 4.4.11) Evaluate MCB annunciator NOTE: Annunciators E-20, CO

• status (refer to AR procedures) 6, and K-32 need followup i NOTE: These annunciators . may be addressed in ANY order. AR-E-20, CNMT OR PLANT VENT RAD MON PUMP TRIP CO 1. Investigate problem at associated Note: The operator will i recognize pump is off due to loss of Inst. Bus and restart Pump.

Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # Event # _2_______ Page 16 of ...;;;,;50;"""-11 Event

Description:

Loss of B Instrument Bus AR-F-6, PRESSURIZER HEATER BREAKER TRIP HCO 1. Monitor RCS NOTE: Entry into AP-PRZR.1 is NOT necessary.

The HCO Go to AP-PRZR.1, if necessary will recognize HTR TRIP due to loss of Instr. Bus and Reset. NOTE: The CRS will continue with ER-INST.3.

AR-K-32, SG BLOWDOWN TANK HIGH LEVEL CO 1. Direct AO to remove and then SIM DRIVER: Insert REM restore Blowdown per T-14.F.1, SG SGN05, RESET, Blowdown System Operation ER-INST.3, INSTRUMENT BUS POWER RESTORATION (Step 4.4.12) IF Instrument Bus D was NOTE: Instrument Bus D was affected, THEN ...... . NOT affected. (Step 4.4.13) IF Instrument Bus A or C is NOTE: Instrument Bus A or C being powered from associated emergency is NOT being powered form AC Bus, then ..... . the emergency AC Bus. (Step 4.4.14) Return to procedure or guidance in effect. NOTE: The CRS will address the Technical Specifications.

TECHNICAL SPECIFICATION 3.8.7, AC INSTRUMENT BUS SOURCES -MODES 1, 2, 3AND 4 CRS LCO 3.8.7 The following AC instrument bus power sources shall be OPERABLE:

a) Inverters for Instrument Buses A and C; and Class 1 E constant voltage transformer (CVT) for Instrument Bus B.

Appendix Operator Action Form ES-D-2 . Op Test No.: N10-1 Scenario # 1 Event # .._2_____ Page 17 of . Event

Description:

Loss of B Instrument Bus TECHNICAL SPECIFICATION 3.8.9, DISTRIBUTION SYSTEMS -MODES 1, 2, 3 AND4 LCO 3.8.9 Train A and Train B of the following electrical power distribution subsystems shall be OPERABLE:

a) AC power; b} AC instrument bus power; and c} DC power APPLICABILITY:

modes 1, 2, 3 and 4. CRS CONDITION REQUIRED ACTION COMPLETION TIME B.OneAC B.1 Restore AC Instrument bus Instrument bus electrical power

• electrical power distribution distribution train train to inoperable.

OPERABLE 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. status. At the discretion of the Lead Examiner move to Event #3.

Appendix Operator Action Form ES-D-2

• Op Test No.: N10-1 Scenario # Event # 3 Page 18 of 50 Event

Description:

Pressurizer Pressure (PT -449) fails High After this, the controlling Pressurizer Pressure Transmitter will fail High, causing the

• Spray Valves to open. The operator will respond in accordance with AR-F-2, *

• PRESSURIZER HIGH PRESS PSI and AR-F-10, PRESSURIZER LO PRESS* 2205 PSI, and enter AP-PZR.1, Abnormal PZR Pressure.

AP-PZR.1 will refer the operator to ER-INST.1, Reactor Protection Bistable Defeat After Instrumentation Loop Failure, for the defeat of PT-449. The operator will address Technical Specification 3.4.1, RCS Pressure, Temperature, and Flow Departure From Nucleate Boiling (DNB) Limits; 3.3.1, Reactor Trip System (RTS) Instrumentation; and 3.3.2, ESFAS Instrumentation .

• Booth Operator Instructions:

Operate Trigger #2 (PZR02D (2500) Indications Available:

• MCB Annunciator F-2, PRESSURIZER HIGH PRESS 2310

• PI-449 reading 2250 psig, all others lowering slowly

• Both Presssurizer Spray Valves fully OPEN

• Master pressure Controller 431 K output at 100%

• MCB Annunciator F-10, PRESSURIZER LO PRESS 2205 (15seconds delayed) The HCO may take action to place 431 K in MANUAL control, or the Spray Valve Controllers in MANUAL control, before arriving at the procedurally directed step, per the Guidance of A-503.1. NOTE: The crew may enter AP-PRZR.1 directly.

AR-F-2, PRESSURIZER HI PRESS 2310 PSI (Step 1) IF RCS pressure is high, THEN go NOTE: Pressurizer Pressure is to AP-PRZR. 1 . NOT high. (Step 2) IF due to instrument failure, THEN NOTE: While an instrument refer to ER-INST.1, REACTOR has failed, the failure has PROTECTION BISTABLE DEFEAT AFTER created a pressure transient, INSTRUMENTATION LOOP FAILURE and AP-PRZR.1 is the appropriate procedure.

Appendix Operator Action Form ES-O-2 Op Test No.: N10-1 Scenario # 1 Event # 3 Page 19 of 50 -----I Event

Description:

Pressurizer Pressure (PT -449) fails High AR-F-10, PRESSURIZER LO PRESS 2205 PSI NOTE: This alarm will occur if the Spray Valves are open =15 seconds. HCO (Step 1) Perform a channel check. CRS (Step 2) Go to the applicable procedure: AP-TURB.2, if turbine load rejection has occurred. AP-PRZR.1, if pressure is abnormal for plant condition. ER-INST.1, if channel failed CRS (Step 3) Refer to ITS LCO 3.4.1 NOTE: The CRS will go to

• PRZR.1. AP-PRZR.1, ABNORMAL PRESSURIZER PRESSURE HCO (Step

1) Check PRZR Pressure: All 4 narrow range APPROXIMATELY (Step 1 RNO) IF one pressure channel NOTE: The CRS may refer to deviates significantly from the other 3. THEN ER-INST.1 here, or later when perform the following:

the pressure transient has been verified to be under a) IF the controlling PRZR pressure channel control.has failed. THEN place controller, 431 K, in MANUAL and adjust output to restore PRZR pressure Refer to ER-INST.1. PROTECTION BISTABLE AFTER INSTRUMENTATION HCO (Step 2) Check Reactor Power-STABLE Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # Event # 3 Page 20 of 50Event

Description:

Pressurizer Pressure (PT -449) fails High HCO (Step 3) Check PRZR a) Pressure-LESS THAN b) Pressure-GREATER 2000 HCO (Step 4) Check PRZR Heater a) PRZR proportional breaker-b) PRZR heater backup group-HCO (Step 5) Verify Normal PRZR Spray NOTE: The HCO may take CLOSED action to place 431 K in MANUAL control, or the Spray AOV-431A Valve Controllers in MANUAL o AOV-431B control, before arriving at THIS step, per the Guidance of 503.1. (Step 5 RNO) Place Controllers in at 0% (Step 6) Check PRZR Pressure 431 K, Demand-LESS THAN HCO * (Step 7) Check PRZR a) PORVs-b) Annunciator F-19. PRZR OUTLET HI TEMP EXTINGUISHED CRS c} Go to Step 9 Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # Event # ...,;3;;.....

____ Page 21 of _5;;.,;0:"--11 Event

Description:

Pressurizer Pressure (PT -449) fails High (Step 9) Check PRZR Safety Valves: Position indicator-LESS THAN 0.1 INCH Annunciator F-18. PRZR SAFETY VLV OUTLET HI TEMP EXTINGUISHED Annunciator AA-13, PRESSURIZER SAFETY VALVE EXTINGUISHED. (Step 10) Check AUX Spray Valve, AOV-296 -CLOSED HCO (Step 11) Check PRZR Pressure Control Restored:

a) Pressure-TRENDING TO 2235 PSIG CRS b) Go to Step 16 HCO {Step 16} Check PRT Indications:

a} Level-BETWEEN 61% and 84% b) Pressure-APPROXIMATELY 1.5 PSIG AND STABLE c} Temperature-AT CNMT AMBIENT TEMPERATURE AND STABLE HCO (Step 17) Establish PRZR Pressure Control In Auto: a} Verify 431 K in AUTO i Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 1 Event # ____ Page 22 of _5...,0__-11 Event

Description:

Pressurizer Pressure (PT -449) fails High HCO (Step 17 RNO) Place 431 K in AUTO, if NOTE: 431K cannot be placed desired. in Auto until the Instrument is defeated.

IF the Instrument has NOT been defeated in accordance with ER-INST.1, i the CRS may refer to this procedure here. ER-INST.1, REACTOR PROTECTION BISTABLE DEFEAT AFTER INSTRUMENTATION LOOP FAILURE (Step 4.1) Identify the failed instrument channel by observation of the bistable status light board, MCB annunciators, and the MCB metering indication.

CRS (Step 4.2) WHEN a failed instrument loop NOTE: The CRS will refer to and/or channel has been identified, THEN PRZR Pressure Channel

• refer to the appropriate section of this Failures, Section 4.4. procedure listed below: (Step 4.4.1) IF the controlling PRZR Pressure channel has failed (normally 449, but PT -429 may be selected as controlling channel), THEN place HC-431 Kin i MANUAL at about 50% and control

• HCO (Step 4.4.2) IF PT -430 OR PT-431 has NOTE: Neither PT -430 nor

• failed, THEN ....... . PT-431 has HCO (Step 4.4.3) Close the associated block NOTE: The Pressurizer

• valve ..... PORVs have NOT been affected. (Step 4.4.4) IF hot leg streaming has been NOTE: hot leg streaming has causing single channel T runback Signals, NOT been causing runback THEN ..... . Signals.

Appendix D Operator Action Form ES-D-2 OpTest No.: N10-1 Scenario # 1 Event # ____ Page 23 of ...,.;5;.;;,0---11

-Event

Description:

Pressurizer Pressure (PT -449) fails High i (Step 4.4.5) Refer to the appropriate attachment to defeat the associated control functions:

NOTE: The CRS will go to the PRZR PRESSURE PI-449 YELLOW CHANNEL Attachment.

NOTE: The CRS will hand this off to the CO. ER-INST.1, REACTOR PROTECTION BISTABLE DEFEAT AFTER INSTRUMENTATION LOOP FAILURE I YELLOW CHANNEL ATTACHMENT PRZR PRESSURE PI-449 HCO (Step 1) IF PRZR Pressure channel failure : NOTE: The failure did NOT resulted in a runback, THEN ....... I result in a runback. I CO (Step 2) In the PLP PRZR PRESS AND LEVEL rack, check the PRZR pressure DEFEAT switch P/429A position.

0 IF P/429A is in NORMAL, THEN place P/429A to DEFEAT-1.

CO (Step 3) In the RIL INSERTION LIMIT rack, PLACE T/405F DELTA T DEFEAT switch to , Loop B UNIT 2. I I CO (Step 4) In the (YELLOW) Y-1 PROTECTION CHANNEL 4 rack, PLACE the following bistable proving switches to DEFEAT (UP) AND verify the proving light status is correct: 408 LOOP B-2 OVER TEMP TRIP 449 CHANNEL 4 NOTE: Both BIS proving lights should be ON after defeat. LOW PRESS TRIP HCO (Step 5) PLACE the PRZR pressure recorder transfer switch (MCB) to position 1-3 i HCO . (Step 6) Verify the bistable status lights listed i above are lit. Examiner NOTE: At the discretion of the Lead Examiner move to Event #4. i Appendix Operator Action Form ES-D-2 OpTest No.: N10-1 Scenario # 1 Event # _3_______

Page 24 of _5;,;0:"'-_11

• Event

Description:

Pressurizer Pressure (PT -449) fails High HCO/ (Step 7) Delete 404/408 from processing CO performing the following on the a) Select "Group Update" b) Select "List Server Groups" c) Select 404_408 from the pick list d) Turn "OFF" scan processing, then click the "Set Scan Processing" button e) Answer prompts f) On the "Sub/Delete/Restore" display g) Select Point ID T0404 h) Turn "ON" scan processing i) Select "Change" j) On the "Sub/Delete/Restore" display k) Select Point ID P0449 I) Turn "OFF" scan processing m) Select "Change" HCO (Step 8) GO TO step NOTE: The CRS will return to the body of the procedure. (Step 4.4.6) Restore the following systems to NOTE: The HCO will return automatic operation as necessary:

431 K to Auto. o PRZR Pressure control

• HC 431K

• PRZR Spray Valves

• PRZR Heaters HCO 0 PRZR Level Control HCO 0 Rod Control CO 0 Steam Dump CO 0 Turbine EH control (Step 4.4.7) Open associated block valve

• NOTE: 1\10 Block Valve was closed in step 4.4.3 I Closed.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 1 Event # 3 Page 25 of 50

-Event

Description:

Pressurizer Pressure (PT -449) fails High (Step 4.4.8) Check the following ITS Sections for a) Section 3.3.1, Table 3.3.1-1, Functions 5, 7a, and 7b (7b not required for PT -449) b) Section 3.3.2, Table 3.3.2-1, Function 1d (not required for PT-449) c) Section 3.3.3, Table 3.3.3-1, Functions 1 and 6 (Step 4.4.9) Check TRM 3.4.3, Anticipated Transients Without Scram (A TWS) mitigation (Step 4.4.10) IF turbine runback has occurred AND rods are in MANUAL, ...... (Step 4.4.11) Restore AUTO Rod Control, if desired. (Step 4.4.12) GO TO step 4.15 (Step 4.15.1) IF necessary, verify an operable channel is selected for the affected recorder. (Step 4.15.2) Verify the following systems in AUTO if desired: o Rod Control CO 0 Turbine EH control HCO 0 PRZR Pressure control

• HC 431K

• PRZR spray valves

• PRZR heaters HCO 0 PRZR level control NOTE: The CRS will evaluate Technical Specifications.

NOTE: The CRS will evaluate Technical Requirements Manual. NOTE: The failure did NOT result in a runback. NOTE: The HCO will place the Rods in Auto.

Appendix Operator Action Form ES-D-2 OpTest No.: N10-1 Scenario # Event # _3______ Page 26 of _5;;,;0;""-11 Event

Description:

Pressurizer Pressure (PT -449) fails High Steam Dump (unless 1 st pressure co o MFW control co o S/G Atmos Relief Vlv Control (Step 4.15.3) Notifications to the following

• NOTE: The CRS may notify people will be made by the Shift Manager: the SM/STA Operations Supervision Booth Instructor:

as SM/STA, acknowledge. STA (Step 4.15.4) During normal working hours, NOTE: The CRS may notify Maintenance personnel shall be notified theWCC. immediately of the problem. . Booth Instructor:

as WCCS, i acknowledge. (Step 4.15.5) During back shifts Maintenance personnel will be called in. HOWEVER, the Shift Manager may defer calling people in, IF repairs may be deferred to the next working day. AP*PRZR.1, ABNORMAL PRESSURIZER PRESSURE (Step 17.b) Verify PRZR Spray Valves in Auto. (Step .c) Verify PRZR Heaters restored: PRZR proportional heaters PRZR backup heaters RESET (Step 18) Evaluate MCB Annunciator Status (Refer to AR Procedures)

CRS . (Step 19) Notify Higher Supervision Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # Event # _3______ Page 27 of ...,;5;.;;;,0-1 Event

Description:

Pressurizer Pressure (PT -449) fails High (Step 20) Notify Reactor Engineer Transient Monitoring NOTE: The CRS will address the Technical Specifications.

TECHNICAL SPECIFICATION 3.4.1, RCS PRESSURE, TEMPERATURE, AND DEPARTURE FROM NUCLEATE BOILING (DNB) (LCO 3.4.1) RCS DNB Parameters pressurizer pressure, RCS temperature, and RCS total flow rate shall within the limits specified in the APPLICABILITY:

Mode 1. ACTIONS:

REQUIRED COMPLETION ACTION TIME A. One or more A. 1 Restore 2 RCS DNB RCS parameters not parameter(s) within limits. within TECHNICAL SPECIFICATION 3.3.1, REACTOR TRIP (RTS) INSTRUMENTATION LCO 3.3.1 The RTS instrumentation for Function in Table 3.3.1-1 shall APPLICABILITY:

According to Table 3.3.1-1 (Functions 5, 7a, 7b) ACTIONS Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 1 Event #

Page 28 of 50 Event

Description:

Pressurizer Pressure (PT -449) fails High CONDITION REQUIRED COMPLETION ACTION TIME A. One or more A.1 Enter the Immediately functions with Condition one channel referenced in inoperable. . Table 3.3.1-1 for the channel(s).

D. As required 0.1 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> by Required Place channel Action A. 1 and referenced by in trip Table 3.3.1-1 K. As required K1 . 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> by Required Place channel Action A.1 and referenced by in trip Table 3.3.1-1 TECHNICAL SPECIFICATION 3.3.2, ESFAS INSTRUMENTATION LCO 3.3.2 The ESFAS instrumentation for each Function in Table 3.3.2-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.2-1. (Function I,d) ACTIONS CONDITION A. One or more Functions with . one channel or i train inoperable L. As required by Required Action A. 1 and referenced by Table 3.3.2-1 REQUIRED ACTION A.1 Enter the Condition referenced in Table 3.3.2-1 for the channel or train L.1 Place channel in trip COMPLETION TIME Immediately 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. At the discretion of the Lead Examiner move to Event #4.

Appendix Operator Action Form ES-D-2 Op Test No.: N10*1 Scenario # 1 Event # 4 Page 29 of 50 -Event

Description:

Main Turbine High Vibration/EHC control failure Following this, a turbine high vibration condition on Bearing #5 will develop within about 60 seconds, an EHC failure will occur causing the turbine to shift to manual. The . operator will respond in accordance with AR-I-27, ROTOR ECCENTRICITY OR VIBRATION; and enter AP-TURB.3, Turbine Vibration; and then AP-TURB.5, Rapid Downpower.

The operator will need to lower the Turbine Load using Manual EHC control. ! Booth Operator Instructions:

Operate Trigger #3 (TUR05E (10 mils), TUR09D (120 sec delayed>> Indications Available: MCB Annunciator 1-27, ROTOR ECCENTRICITY OR VIBRATION MCB Turbine Bearing Recorder Bearing 5 indicating high, bearings 4 and 6 rising at a lower rate. Back of MCB Turbine Bearing Vibration Panel Bearing 5 indicating high, bearings 4 and 6 rising at a lower rate. Turbine Controls indicate the following (60 seconds delayed) OPER PAN -DARK IMP PRESS OUT -DARK TURB MANUAL -LIT MANUAL CONTROL VALVE LOWER -LIT MANUAL CONTROL VALVE FAST -LIT MANUAL CONTROL VALVE RAISE -LIT NOTE: The crew may enter AP-TURB.3 directly.

AR-I-27, ROTOR ECCENTRICITY OR VIBRATION cal 1. Go to NOTE: The CRS will go to TURB.3. AP-TURB.3, TURBINE VIBRATION i (Step 1) Verify Turbine Vibration-. BEARINGS LESS THAN co (Step 2) Check Turbine Bearings through NO.8 Vibration-LESS THAN 7 Appendix Operator Action Form ES-D-2 OpTest No.: N10-1 Scenario # 1 Event # _4..;...-____ Page 30 of 50 . Event

Description:

Main Turbine High Vibration/EHC control failure (Step 2 RNO) Attempt to stabilize vibration as follows: IF generator on line, THEN begin reducing load to stabilize vibrations. (Refer to TURB.S, RAPID LOAD REDUCTION NOTE: The CRS will go to TURB.S and conduct . briefing" prior to commencing load reduction AP-TURB.5, RAPID LOAD REDUCTION HCO (Step 1) Initiate Load a) Verify rods in CO Reduce turbine load in Auto I(Step 1.b RNO) IF Auto Control is NOTE: The CO will need to inoperable, THEN reduce turbine adjust Turbine Load in load in manual at the desired rate. MANUAL. HCO Initiate boration at the rate . NOTE: The HCO will initiate a ! determined in boration.

CALC HCO Place PRZR backup heaters to (*Step 2) Monitor RCS Tavg

• Tavg-GREATER THAN

• Tavg-LESS THAN 579°F (Step 3) Adjust Boric Acid Addition Rate As Examiner NOTE: After load Necessary To (refer to has been reduced in Manual CALC): "2%, at the discretion of the Lead Examiner move to

• Maintain rods above the insertion Events #5-8.limit

• Match Tavg and Tref

• Compensate for Xenon (*Step 4) Monitor PRZR TRENDING TO 2235 PSIG IN Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # Event # 4 Page 31 of 50 i Event

Description:

Main Turbine High Vibration/EHC control failure (*Step 5) Monitor MFW Regulating RESTORING S/G LEVEL TO 52% IN AUTO (*Step 6) Monitor PRZR Level-TO PROGRAM IN AUTO To ensure conditions are met for FR-H.1 entry in the next scenario, the next events should be initiated after -2% load reduction has been completed.

At the discretion of the Lead Examiner move to Events #5-8.

Appendix Operator Action Form ES-D-2 . Op Test No.: N10-1 Scenario # Event # ...,;5;.:.

• ..;.6.:..,;7.:.,..

&;;;;....;.8

__ Page of Event

Description:

Feed Line Rupture Inside Containment I A AFW Pump Fails after start! TDAFW Pump overs peed tripl Standby AFW fails to function Containment NR Pressure starts to rise. Feedflow A SG starts to rise. A SG NR Level starts to lower. E-O, REACTOR TRIP OR SAFETY INJECTION HCO (Step 1) Verify Reactor Trip: At least one train of reactor trip breakers -OPEN Neutron flux -LOWERI NG MRPI indicates

-ALL CONTROL AND SHUTDOWN RODS ON BOnOM (Step 2) Verify Turbine Stop NOTE: Auto turbine trip will CLOSED i NOT occur. Depresses Manual Turbine Trip button (Step 3) Verify Both Trains of AC Busses Energized to at Least 440 Bus 14 and Bus 18 Appendix Operator Action Form ES-D-2 Op Test No.: Nl0-1 Scenario # 1 Event # _5;;,.:.*..;;,6:..,;.7..:..

• .;;;.&..;;,8

__ Page -==---of ...;;.;50:"'-_1 Event

Description:

Feed Line Rupture Inside Containment I A AFW Pump Fails after start! TDAFW Pump overs peed tripl Standby AFW fails to function (*Step 4) Check if SI is Actuated: Any SI Annunciator

-LIT NOTE: 0-28. CNMT Press SI sequencing

-BOTH (*Step 5) Verify CNMT Spray Not Required: Annunciator A-27. CNMT CNMT pressure-LESS THAN 28 NOTE: Containment Pressure will be rising. and will exceed 28 psig. This is a Continuous Action Step, and will need to be verified when the conditions are met (i.e. by performing Step 5 RNO). (Step 5 RNO) Verify CNMT spray initiated. (Step 6) Direct Operator to Perform A 27.0, ATTACHMENT AUTOMATIC NOTE: The CRS will hand off ATT-27.0 to either the HCO or the CO, and continue with the other operator in E-O. Examiner following operator performing ATT-27.0 continue below. Examiner following operator NOT performing ATT-27.0 continue at page 37. E-O, REACTOR TRIP OR SAFETY INJECTION, ATTACHMENT 27.0, ATTACHMENT AUTOMATIC ACTION VERIFICATION Appendix Operator Action Form ES-D-2 Op Test No.: Scenario # 1 Event # ..,.;5:;.:"..;;,6:..;,7..:..,.:;;.&..;;,8

__ Page .::......

of _5;;.;0;"""-11

-Event Feed Line Rupture Inside Containment I A AFW Pump Fails after start! TDAFW Pump overs peed tripl Standby AFW fails to function All SI pumps -RUNNING

• Both RHR pumps RUNNING HCOI (Step 2) Verify CNMT RECIRC CO All fans -RUNNING Charcoal filter dampers green lights -

HCOI (Step 3) Check If Main Steamlines Should Se CO Any MSIV -OPEN Check CNMT pressure-LESS THAN 18 PSIG Ensure BOTH MSIVs closed and go Step HCOI (Step 4) Verify MFW MFW pumps -TRIPPED MFW Isolation valves -CLOSED SIG A, AOV-3995 S/G B, AOV-3994 S/G Slowdown and sample valves HCOI (Step 5) Verify At Least Two SW CO HCOI (Step 6) Verify CI and CI and CVI annunciators

-LIT Appendix Operator Action Form ES-O-2 , Op Test No.: N10-1 Scenario # Event # _5;;.:.,..;;.6'1.,,;7

..., &.;;.;..;;.8

__ Page of _5_0__Event Feed Line Rupture Inside Containment / A AFW Pump Fails start! TDAFW Pump overs peed trip/ Standby AFW fails to Annunciator A-26, CNMT ISOLATION Annunciator A-25, CNMT VENTILATION ISOLATION Verify CI and CVI valve status BRIGHT CNMT RECIRC fan coolers SWoutlet valve status lights -BRIGHT FCV-4561 FCV-4562 Letdown orifice valves -CLOSED AOV-200A AOV-200B AOV-202 HCOI . (Step 7) Check CCW System Verify CCW pump -AT LEAST ONE RUNNING HCOI (Step 8) Verify SI and RHR Pump SI flow indicators

-CHECK FOR FLOW RHR flow indicator

-CHECK (Step 7b RNa) IF RCS pressure less than NOTE: RCS Pressure is > 150 150 psig ...... . psig. HCOI (Step 9) Verify SI Pump and RHR CO Emergency RHR pump discharge to Rx deluge -MOV-852A Appendix Operator Action Form ES-D-2 Op Test No.: Scenario # 1 Event # _5;;,,:..,,;;;,6,:...;7

.....&;;.;..;.,8

__ Page of ....5-.0--11 Event Feed Line Rupture Inside Containment I A AFW Pump Fails after start! TDAFW Pump overspeed tripl Standby AFW fails to function

• Verify SI pump C -RUNNING Verify SI pump A -RUNNING Verify SI pump B -RUNNING Verify SI pump C discharge valves

• MOV-871A

• MOV-871B (Step 10) Verify CREATS Actuation: At least one damper in each flowpath Normal Supply Air Normal Return Air Lavatory Exhaust Air CREATS fans -BOTH RUNNING E-O, REACTOR TRIP OR SAFETY INJECTION

• Examiner following operator NOT performing ATT-27.0 continue HERE. (Step 7) Verify Both MDAFW Pumps NOTE: The B AFW Pump is CO Running OOS, and the A AFW Pump will fail to START. CO (Step 7 RNa) Manually start both MDAFW NOTE: The TDAFW Pump will pumps. trip on overspeed IF less than 2 MDAFW pumps are running, Booth Instructor: (Delay THEN manually open TDAFW pump steam report on governor valve reset supply valves. 5 minutes). MOV-3505A MOV-3504A Appendix Operator Action Form ES-D-2 Op Test No.: Scenario # Event # _5;;;.:"..;;,6.:....;'

7...,.;;.;.&..;;,8__

Page .::........

of Event Feed Line Rupture Inside Containment I A AFW Pump Fails after start! TDAFW Pump overs peed tripl Standby AFW fails to function AFW flow -INDICATED TO AFW flow from each MDAFW pump LESS THAN 230 HCOI (Step 8 RNO) Manually align valves as NOTE: There will be no AFW CO necessary flow, and manually alignment of valves will NOT restore flow. HCOI (*Step 9) Monitor Heat Check S/G narrow range level -NOTE: Adverse Containment GREATER THAN 7% [25% ADVERSE Numbers should be used, until CNMT] in any S/G Containment Pressure is less than 4 psig. HCOI (Step 9 RNO) Perform the Verify total AFW flow GREATER THAN IF total AFW is less than 200 GPM, THEN manually start pumps and align valves to establish greater than 200 gpm AFW flow. IF AFW flow greater than 200 gpm can flow can NOT be established, THEN go to FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK. Step 1.

• NOTE: The CRS will go to .H.1. FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK (Step 1) Check If Secondary Heat Sink RCS pressure-GREATER THAN ANY NON-FAULTED S/G PRESSURE Check RCS cold leg temperature GREATER THAN 350°F i I Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 1 Event # .....;5;;,j"..;;,6,:....;7..1..'

&;;;..;;.8

__ Page of ...;;;.,;50;;"""-11

-Event Feed Line Rupture Inside Containment I A AFW Pump Fails after start! TDAFW Pump overspeed tripl Standby AFW fails to function CO (*Step 2) Monitor Secondary Heat Sink: Verify either S/G level-WIDE RANGE GREATER THAN 50 inches [100 inches adverse CNMT] Verify PRZR pressure-LESS THAN 2335 PSIG HCO (Step 3.a) Try to Establish AFW Flow To Least One Intact a) Check Blowdown and (Step 3.a RNO) Place Blowdown and sample valve switches to CLOSE (Step 3.b) Verify 2 MDAFW i (Step 3.b RNa) Perform the NOTE: The TDAFW Pump is NOT available, however, the IF the TDAFW is available THEN ..... . SBAFW System is available.

IF SBAFW is available THEN go to Step 4. HCO (Step 4) Stop Both RCPs HCO (Step 5) Reset SI if Actuated CO (Step 6) Try and Establish SAFW Flow To Least One Intact a) Perform the Align SAFW system for operation (Refer to ATT-5.1, ATTACHMENT SAFW) ATTACHMENT-S.i, ATTACHMENT SAFW Appendix Operator Action Form ES-D-2 Op Test No.: Scenario # Event # _5;;;.:.*..;;;,6..,;.

7.,:.*.;;;.&...;;.8

__ Page of Event Feed Line Rupture Inside Containment I A AFW Pump Fails after start! TDAFW Pump overspeed tripl Standby AFW fails to function

• NOTE: The CO will attempt to align Train B to feed the B SG due to the fault in A SG. (Step B) Align SAFW Pump 0 to S/G as

1) Ensure SI 2) Ensure the following valves MOV-9701 B. SAFW PUMP 0 DISCHARGE MOV-4615, AUX BLDG SW ISOL VLVS MOV-9704B, SAFW PUMP 0 ISOL VLV MOV-9746, SAFW PMP 0 EMERG DISCH VLV Open MOV-9629B, SAFW PUMP SUCTION Verify at least 1 SW pump running Sa) To feed S/G B, go to step 6. 6) Restore SAFW flow as directed by procedure in effect. NOTE: The CO will report that the 0 SBAFW Pump is ready to be started. FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK CRS! (Step 6.a.2) Determine SAFW flow NOTE: The CRS will direct the CO requirements per ATT-22.0, ATTACHMENT CO to use ATT-22.0 to RESTORING FEED FLOW . determine the allowable rate of feed flow to the B SG.

Appendix Operator Action Form ES*D*2 Op Test No.: Scenario # 1 Event # _5;;.:,*..;;,6,:...;.

7**.;;.;.&..;;,8__

Page of _5;;;,;0;;""1 Event Feed Line Rupture Inside Containment / A AFW Pump Fails after start/ TDAFW Pump overspeed trip/ Standby AFW fails to function ATT-22.0, ATTACHMENT RESTORING FEED FLOW CO 1. Initiate Feed flow as NOTE: The CO will determine that the B SG can be filled as a) Bleed and Feed initiated or required.

desired to restore Narrow IF feedwater flow to affected S/G Range Level to > 25%. when a greater than 50 gpm OR affected SG Feedwater flow source is level greater than 50 inches (100 restored.inches adverse CNMT). THEN as desired to restore narrow greater than 7% (25% CNMT) and go to step 2 of i Check RCS Loop Hot Legs-BOTH HOT LEG TEMPERATURES Return to step 1 of this FR-H.1, RESPONSE TO lOSS OF SECONDARY HEAT SINK CO (Step 6.a.3) Start selected SAFW NOTE: The 0 SBAFW Pump will fail to start, and the CRS IF greater than 215 gpm total SAFW will direct the CO to start the C flow can NOT be established, THEN i SAFW pump per Section A of go to Step 7 ATI-5.1. ATTACHMENT-5.1, ATTACHMENT SAFW (Step A) Align SAFW Pump C to S/G as

1) Ensure SI 2) Ensure the following valves MOV-9701A, SAFW PUMP MOV-4616, AUX BLDG SW MOV-9704A, SAFW PUMP C ISOL VLV NOTE: MOV-9629A will NOT 3) Open MOV-9629A, SAFW PUMP C open. HCO/CO should inform SUCTIONVLV CRS that suction valve to C SAFW pump cannot be opened. i i Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 1 Event #

__ Page of ....5....0---11 Event Feed Line Rupture Inside Containment I A AFW Pump Fails after start! TDAFW Pump overs peed tripl Standby AFW fails to function FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK eRS eo eo eo eRS (Step 6.a RNO) If greater than 215 gpm total SAFW flow can NOT be established, THEN go to Step 7 (Step 7) Try to Establish MFW Flow to at Least One S/G Check any MFW pump AVAILABLE Check condensate system: Condensate pump-MFW pump suction pressure GREATER THAN 200 PSIG Establish MFW flow: Check MFW pump discharge valves-CLOSED Verify MFW regulating or bypass valves-OPERABLE Depress MANUAL push buttons for A and B MFW regulating valve and bypass valve controllers AND adjust to 0 0 Yo demand. Open MFIV's for both S/G's: S/G A. AOV-3995 S/G B. AOV-3994 Dispatch AO to restore MFW pump SW cooling I i I i I NOTE: This will require that the operator open a valve that had previously failed open and had been closed per Att.27.0.

NOTE: The eRS will dispatch anAO. Booth Instructor:

as AO, acknowledge, and immediately reports that SW is verified.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 1 Event #

7:..l.'.:;::&..;;:8

__ Page of 50 Event

Description:

Feed Line Rupture Inside Containment I A AFW Pump Fails after startl TDAFW Pump overspeed tripl Standby AFW fails to function HCO I I I I I CRS CO

• Verify S/G blowdown key switches in NORMAL Ensure Annunciator H-4, MAIN FEED PUMP OIL EXTINGUISHED Close Condensate Bypass valve, AOV-3959 Ensure Annunciator H-11, Feed PUMP SEAL WATER LO DIFF PRESS 15 PSI-EXTINGUISHED Ensure one MFW pump recirc valve-OPEN Start Selected MFW pump Open MFW pump discharge valve Open MFW regulating or bypass valves to control MFW flow per requirements of AIT-22.0, A IT ACHMENT RESTORING FEED FLOW Go to Step 11 Step 11. Check S/G Levels: Narrow range level in at least one S/G-GREATER THAN 7% [25% adverse CNMT] IF feed flow verified and level riSing in at Least one S/G, THEN maintain flow to Restore narrow range level greater than 7% [25% adverse CNMT]. Return to procedure and step in effect. NOTE: The CRS will Booth Instructor:

as acknowledge and reports that switches are ! I i I I NOTE: The CO will determine that the B SG can be filled as desired to restore Narrow Range Level to > 25%, when a Feedwater flow source is restored.

!

• NOTE: The CRS will determine that a Secondary Heat Sink has been restored with the MFW System, and return to E-O, Step 9. I Appendix Operator Action Form ES-D-2 Op Test No.: Scenario # Event # _5;;.:",.;;,6:..,;.

7......,

__ Page of _5;;.,;0;"""'1 Event Feed Line Rupture Inside Containment I A AFW Pump Fails start! TDAFW Pump overs peed trip/ Standby AFW fails to CRITICAL TASK (FR-H.1) Establish feedwater flow into at least one Steam Generator before Bleed and Feed is Safety Significance:

Failure to establish feedwater flow into at least one Generator results in the crew having to rely upon the lower-priority action of having initiate RCS Bleed and Feed to minimize the possibility of core uncovery.

Failure perform this task, when able to do so. constitutes incorrect performance that leads degradation of the RCS and/or fuel cladding fission product E*O, REACTOR TRIP OR SAFETY INJECTION CO (*Step 9) Monitor Heat Sink:

• Check S/G narrow range level -NOTE: Adverse Containment

! GREATER THAN 7% [25% ADVERSE Numbers should be used, until CNMT] in any S/G Containment Pressure is less than 4 psig. I I

• Check S/G narrow range level i S/G LESS THAN I Control feed flow to maintain S/G narrow range level between 7% [25% adverse CNMT] and 50%. I I ! CO I (Step 10) Check If TDAFW Pump Can Be I Stopped: i I I Both MDAFW pumps -RUNNING NOTE: None of the AFW Pumps are running. (Step 10 RNO) Go to Step 11 I (Step 11) Check CCW Flow to RCP

-Annunciator A-7, RCP 1A RETURN HI TEMP OR LO Annunciator A-15. RCOP 1B CCW RETURN HI TEMP OR LOW FLOW EXTINGUISHED Appendix Operator Action Form ES-D-2 Op Test No.: Scenario # 1 Event # _5;;.:*_5;;.,0;""'-11

• .;.17*..;;&;;..8;....-_

Page of Event Feed Line Rupture Inside Containment I A AFW Pump Fails start! TDAFW Pump overspeed tripl Standby AFW fails to (*Step 12) Monitor RCS Tavg -STABLE OR TRENDING TO i(Step 12 RNO) If temperature less 547°F and lowering.

THEN perform Stop dumping steam. , Ensure reheater steam supply valves are closed. IF cooldown continues, THEN control total feed flow between 20 gpm to 230 I gpm until narrow range level greater than 7% [25% adverse CNMT] in at least one . i WHEN S/G level greater than 7% [25% adverse CNMT] in one S/G, THEN limit feed flow to that required to maintain i I level in at least one i IF cooldown continues, THEN close both MSIVs. i (Step 13 ) Check PRZR PORVs and Spray Valves: I

• PORVs -CLOSED I i ..AUXIliary Spray Valve (AOV-296) Check PRZR pressure -LESS THAN 2260 PSIG Normal PRZR spray valves -CLOSED PCV-431A PCV-431B (Step 14) Monitor RCP Trip Criteria: RCP status -ANY RCP RUNNING I NOTE: The RCPs were previously stopped. (Step 14c RNO) Go to Step 15.

Appendix Operator Action Form ES-D-2 Op Test No.: Scenario # 1 Event # _5;;;.:.*..;;,6:..,;, 7.....;;.;.&..;;,8__

Page of _5,;;..;0;""--11 Event Feed Line Rupture Inside Containment I A AFW Pump Fails start/ TDAFW Pump overspeed tripl Standby AFW fails to CO (Step 15) Check If S/G Secondary Side Is NOTE: The A SG is Intact: depressurizing in n uncontrolled manner. i Pressure in both S/Gs-STABLE OR RISING Pressure in both S/Gs-GREATER THAN 110 PSIG (Step 15 RNO) IF any S/G pressure in an uncontrolled manner OR depressurized.

THEN go to E-2, STEAM GENERATOR ISOLATION, Step J j NOTE: The CRS will go to E-2. I j E-2, FAULTED STEAM GENERATOR ISOLATION

! I CO (Step 1) Check MSIVof Faulted I CLOSED I i (Step 2) Check If Any S/G Secondary Side Is i Intact:

• Check pressure in S/G A-STABLE OR NOTE: The A SG is RISING depressurized.

OR Check pressure in S/G B -STABLE OR RISING CO (Step 3) Check Faulted S/G NOTE: The A SG is depressurized.

i I i

• Faulted S/G pressure -LOWERING IN AN UNCONTROLLED MANNER I OR Faulted S/G -(Step 4) Isolate Feed Flow to Faulted S/G:

Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # Event # .....;..;5

.....6...._7._&....8'-'-_ Page !..-of Event

Description:

! ! CO I I I CO I I ! I i I I I i Feed Line Rupture Inside Containment I A AFW Pump Fails after startl TDAFW Pump overspeed tripl Standby AFW fails to function !Close or verify closed the following valves:I ! Faulted S/G MDAFW pump ! discharge valve S/G A, MOV-4007 Faulted S/G MFW regulating valve I ! and bypass valve -CLOSED i I S/G A. HCV-466 and HCV-480 I I MFW isolation valves -CLOSED I S/G A. AOV-3995 !I MDAFW pump crosstie valves -! BOTH CLOSED i MOV-4000A

! MOV-4000B Faulted S/G SAFW pump S/G A. MOV-9701A Pull stop faulted S/G MDAFW pump Close faulted S/G TDAFW flow i S/G A. AOV-4297 I I ' (Step 5) Isolate Steam Flow From ! S/G: I Verify faulted S/G ARV -CLOSED S/G A. AOV-3411* Close faulted S/G TDAFW pump steam Critical Task supply valve and place in PULL S/G A. MOV-3505A Verify faulted S/G blowdown and valves -S/G A. AOV-5738 and AOV-5735 Appendix Operator Action Form ES-D-2 OpTest No.: N10-1 Scenario # 1 Event # _5;;.:.,..;,.6,....7...., __ Page of .....;..50

__....1

• Event Feed Line Rupture Inside Containment I A AFW Pump Fails after start! TDAFW Pump overspeed tripl Standby AFW fails to function CRITICAL TASK (E-2 A) Isolate the Faulted Steam Generator before transitioning out of E-2. Safety Significance:

Failure to isolate a Faulted SG that can be isolated causes challenges to the Critical Safety Functions that would not otherwise occur. Failure to isolate flow could result in an unwarranted Orange or Red Path condition on RCS Integrity, Subcriticality (if cooldown is allowed to continue uncontrollably) and/or Containment (if the break is inside Containment).

I -Dispatch AO to complete faulted S/G I NOTE: The CRS will isolation (Refer to ATT-10.0, I ATTACHMENT FAULTED Booth Instructor:

as AO, acknowledge.1 CO I (*Step 6) Monitor Intact S/G Levels: I Examiner NOTE: Terminate the Exam at the discretion of i

• the Lead Examiner. , Narrow range level-GREATER THAN I 7% [25% adverse CNMT] ! Control feed flow to maintain narrow range level between 17% [25% adverse CNMT] and 50% HCO (Step 7) Check Secondary Radiation Levels i NORMAL Steamline radiation monitor (R-31 and 32)I Air ejector radiation monitor (R-15) -S/G blowdown radiation monitor (R-19) , Request Chern Tech sample S/Gs for i I activity (Step 8) Adjust Steam Dump to Minimize RCS Heatup: i I Determine allowable intact S/G pressure using maximum hot leg temperature I(Refer to FIG-7.0, FIGURE INTACT S/G PRESSURE)I Check condenser steam dump available:

NOTE: Steam Dump to the \-Condenser is NOT available.

Appendix Operator Action Form ES-D-2 . Op Test No.: N10-1 Scenario # Event #

7....., __ Page of _5;..,;0;""'-;1 Event

Description:

Feed Line Rupture Inside Containment I A AFW Pump Fails after start! TDAFW Pump overspeed tripl Standby AFW fails to function CO (Step 8b RNO) Perform the following: Adjust intact S/G ARV to determined from FIG-7.D, I INTACT S/G PRESSURE.I i CRS .. Go to E-1, LOSS OF REACTOR OR I SECONDARY COOLANT, Step 1.I NOTE: The CRS will go to 1.i Terminate the Exam at the discretion of the Lead Examiner

---

UNIT STATUS: Power Level: 49% RCS [B] 1710 ppm BAST [B]: 14000 ppm Power The Plant is at 49% power (BOL), for Core Burnup: 150 MWD/MTU four days. INFORMATION NEEDED TO ASSUME TO SHIFT: The plant is at 49% power (BOL), with power level above P-9 The plant power was reduced several days ago due to a malfunction on the A Main Feedwater Pump. Corrective Maintenance has been completed, and the MFW pump is ready to be restarted. RG&E Energy Control Center has requested that the electric plant be aligned to a 0/100 configuration on circuit 7T to allow the RG&E personnel to perform an insulator inspection on the 767 Line. Evolution should occur immediately after crew assumes the watch to adhere to planned work schedule. Per Chemistry direction, Normal Letdown is at 60 gpm. The following equipment is Out-Of-Service: The B AFW Pump is OOS for Bearing Replacement.

LCO 3.7.5 was entered 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago.

A-52.4 Equipment Date Time Reason Required Actions Required I* -Required Action not met Completion DatefTime B MDAFWPump

_L/10 0330 Bearing ITS 3-.7-.-5--------r6 days from 1 ITS 3.7.5 Replacement Enter Condition B today's date/time Enter Condition G Required Action B.1: Restore Required Action G.1: Be in Mode 3 MDAFW Train to OPERABLE in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Status in 7 days AND Required Action G.2: Be in Mode 4 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> PROGRAM: Ginna Operations Training MODULE: 2010 Initial License Operator Training Class TOPIC: NRC Simulator Exam Scenario N10-1-2

REFERENCES:

1. P-17, Operations Control Room Operating Instructions

2. R-J-9, SAFEGUARDS BREAKER TRIP 3. Technical Specification 3.7.8, Service Water (SW) System 4. AR-A-2, VCT LEVEL 14 % 86 5. ER-CVCS.1, Reactor Makeup Control Malfunction

6. AR-G-25, MOTOR OFF CTR SECT PMPS EXCEPT MAIN &AUX FEED PMPS 7. AR-G-22, ADFCS SYSTEM TROUBLE 8. ER-INST.1, Reactor Protection Bistable Defeat After Instrumentation Loop Failure 9. AR-L-21, MAIN FEEDWATER PUMP OIL SUMP HI-LO LEVEL 10. AP-TURB.5, Rapid Downpower

11. AR-C-5, PPCS ROD SEQUENCE OR ROD DEVIATION/PPCS L TOP HI-LOW TEMPERATURE

12. AP-RCC.2, RCC/RPI Malfunction

13. Technical Specification 3.1.4, RCC/RPI Malfunction

14. Technical Specification 3.2.4, Quadrant Power Tilt Ratio 15. AR-PPCS-R47 AR, SGTL INDICATED

16. AP-SG.1, Steam Generator Tube Leak 17. E-O, Reactor Trip and Safety Injection

18. E-3, Steam Generator Tube Rupture Author: David Lazarony, Western Technical Services, Inc. Facility Review: Pat Landers, Principal Ops Training Specialist, 4/14/10 Rev. 052610 -1 Scenario Event NRC Scenario Facility:

Ginna Scenario No.: 2 Op Test No.: N10-1 Examiners:

Operators: (SRO) (RO) (BOP) Initial The Plant is at 100% power (EOl). Per the daily work schedule, CROI-7, Swapping Service Water Pumps, is to be performed this shift, swapping to A and D Service Water pumps.

The following equipment is Out-Of-Service:

The B SI Pump is OOS for Bearing Replacement.

Event Malf. No. Event Type* Event No. Description 1 ClG09C N-BOP Swap Service Water Pumps/D Service Water Pump Trip ClG01D C(TS)-SRO 2 CVC10A I-RO VCT level 112 Fails HIGH I-SRO C Charging Pump trips 3 CVC12C C-RO C-SRO Turbine Impulse Pressure (PT-486) fails High 4 I-BOP I-SRO : 5 R-RO A MFW Pump Oil Sump HI-lO level/Rapid DownpowerlStuck Rod ROD03-C-BOP G11 C(TS)-SRO 6 M-RO SGTR M-BOP M-SRO RPS07A C-RO A 81 Pump fails to start in AUTO RPS07C C SI Pump fails to start in AUTO RPS07D * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor -2 Scenario Event NRC Scenario Ginna 2010 NRC Scenario #2 The Plant is at 100% power (EOL). Per the daily work schedule, CROI-7, Swapping Service Water Pumps, is to be performed this shift, swapping to A and D Service Water pumps. The following equipment is Out-Of-Service:

The B SI Pump is OOS for Bearing Replacement.

Shortly after taking the watch, the operator will start the A Service Water pump and then stop the B Service Water Pump in accordance with P-17, Operations Control Room Operating Instructions.

Afterwards, the operator will start the D Service Water pump and then stop the C Service Water Pump. When the operator stops the C Service Water Pump, its Discharge Check Valve will stick Open, and the pump shaft will rotate backwards.

The operator will restart the C Service Water Pump, and the D Service Water Pump will trip. The operator will respond in accordance with AR-J-9, SAFEGUARDS BREAKER TRIP. The operator will address Technical Specification 3.7.8, Service Water (SW) System. Subsequently, VCT Level transmitter L T -112 will fail High. The operator will respond in accordance with AR-A-2, VCT LEVEL 14 % 86, and enter ER-CVCS.1, Reactor Makeup Control Malfunction.

Following this, the C Charging Pump will trip. The operator will respond in accordance with G-2S, MOTOR OFF CTR SECT PMPS EXCEPT MAIN & AUX FEED PMPS and start the B Charging Pump. Then, Main Turbine 1 st Stage Pressure Instrument PT -486 will fail High. The operator will respond in accordance with AR-G-22, ADFCS SYSTEM TROUBLE, and enter ER-INST.1, Reactor Protection Bistable Defeat After Instrumentation Loop Failure. After this, the MFW pump Oil Sump HI-LO level annunciator will alarm (L-21). The operator will respond in accordance with AR-L-21, MAIN FEEDWATER PUMP OIL SUMP HI-LO LEVEL, enter AP-TURB.S, Rapid Downpower, and remove the affected MFP from service. During the downpower Control Rod G-11 will stick in its original position.

The operator will respond in accordance with AR-C-S, PPCS ROD SEQUENCE OR ROD DEVIATION/PPCS L TOP HI-LOW TEMPERATURE, and enter AP-RCC.2, RCC/RPI Malfunction.

The operator will address Technical Specification 3.1.4, RCC/RPI Malfunction, and 3.2.4, Quadrant Power Tilt Ratio. Shortly afterwards, a Steam Generator Tube Rupture will occur on the B Steam Generator.

The operator will respond in accordance with AR-PPCS-R47AR, SGTL INDICATED, and enter SG.1, Steam Generator Tube Leak. Ultimately, the leak will be determined to be beyond the capability of the Charging Pump capacity, and the Reactor will trip and Safety Injection will actuate. The operator will enter E-O, Reactor Trip or Safety Injection.

On the Safety Injection, the A and C SI Pumps will fail to start in Auto, and the operator will be required to manually start the pumps. The operator will transition from E-O to E-3, Steam Generator Tube Rupture, isolate the flow into and out of the B Steam Generator, and then conduct a plant cooldown and depressurization.

The scenario will terminate at Step 36 of E-3, after the crew has controlled RCS pressure and charging flow to minimize primary-to-secondary leakage. -

Scenario Event NRC Scenario Critical Tasks: E-OI Establish flow from at least one high-head ECC8 Pump before transition out of E-O. Safety Significance:

Failure to start at least two SI Pumps, when they are available to start, results in a violation of the Facility License Condition.

The FSAR analysis results are predicted on the assumption of a minimum ECCS flowrate, which includes two SI Pumps. Failure to perform this task will leave the plant in an unanalyzed condition.

E-3A Isolate feedwater flow into and steam flow from the ruptured SG before a transition to ECA-3.1 occurs. Safety Significance:

Failure to isolate the ruptured SG causes a loss of D.P between the ruptured SG and the intact SGs. Upon a loss of D.P, the crew must transition to a contingency procedure that constitutes an incorrect performance that "necessitates the crew taking compensating action which complicates the event mitigation strategy." If the crew fails to isolate steam from the SG, or feed flow into the SG the ruptured SG pressure will tend to decrease to the same pressures as the intact SGs, requiring a transition to a contingency procedure, and delaying the stopping of RCS leakage into the SG. E-3C Oepressurize the RCS to meet 81 termination criteria before ruptured SG level reaches 100% Wide Range Level. Safety Significance:

Failure to stop the reactor coolant leakage into a ruptured SG by depressurizing the RCS (when it is possible to do so) needlessly complicates the mitigation of the event. It also constitutes a "significant reduction of Safety Margin beyond that irreparably introduced by the scenario.

If RCS depressurization does NOT occur, the inventory in the secondary side of the ruptured SG will occur leading to water release through the SG PORV or Safety Valve, which could cause and unisolable fault in the ruptured SG. -

Scenario Event NRC Scenario SIMULATOR OPERATOR INSTRUCTIONS Reset to Temp 100% power EOL o 177 (NRC 2). MALF SIS03B, Trip of 'B" SI pump (OOS MALF RPS07A, Autostart failure of A SI MALF RPS07C, Autostart failure of C SI pump on MALF RPS07D, Autostart failure of C SI pump on Set Trigger #30 =x06i188a==1 (C SWP CS to Insert MALF CLG09C, 100%, T-30 (SWP C

Check Valve fails Set Trigger #29 = x06i188b==1 (C SWP CS to Insert MALF CLG01D T-29 (SWP D MALF CVC10A, 100,5 second Ramp, on MALF CVC12C, on MALF TUR16B, 1050, 0 Ramp, on ANN A-FDW30, ON, on T MALF ROD03-G11, UNTRIPPABLE, on MALF SGN04B, 250, 0 Ramp, on Prior to Crew Hang PROTECT Tags on AlC SI Pump Control*

Switches

• Hang Black Dot on MCB Annunciator J-25 Crew Briefing Assign Crew Positions based on evaluation requirements Review the Shift Turnover Information with the crew. Provide the crew a copy of P-17, Operations Control Room Operating Instructions, Attachment 7, CROI-? Swapping Service Water Pumps. T-O Begin Familiarization 0 Period At direction of Event Swap Service Water Pumps/D Service Water Pump Trip 0 examiner CLG09C (T T-30 (C SWP CS to STOP), Discharge Check Valve sticks OPEN CLG01 D (T -29) T-29 (C SWP CS to CLOSE), D SWP Trips At direction of Event VCT Level 112 Fails HIGH 0 examiner Trigger 100% ramped at 5 seconds CVC10A -

At direction examiner At completion of the CRS Brief OR at direction of examiner At direction examiner At direction of examiner from Event 6 o Scenario Event NRC Scenario Event 3 Trigger#2 CVC12C Event 4 Turbine Impulse Pressure (PT -486) fails High Trigger#3 TUR16B 1050, No Ramp Event A MFW Pump Oil Sump HI-LO Level/Rapid DownpowerlStuck Rod Trigger #4 Alarm Severity = ON A-FDW30 ROD03 Severity = UNTRIPPABLE ROD03-G11 Event SGTR Trigger 250 gpm, No Ramp SGN04B Event A SI Pump fails to start in AUTO C SI Pump fails to start in AUTO NOTE: These Malfunctions are inserted in the IC at T=O. RPS07D Terminate the scenario upon direction of Lead Examiner Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # -.:...____

Page 7 of ....;5;;.,;.4---11

-Event

Description:

Swap Service Water Pumps/D Service Water Pump Trip Shortly after taking the watch, the operator will start the A Service Water pump and then stop the B Service Water Pump in accordance with P-17, Operations Control Room Operating Instructions.

Afterwards, the operator will start the D Service Water pump and then stop the C Service Water Pump. When the operator stops the C Service Water Pump, its Discharge Check Valve will stick Open, and the pump shaft will rotate backwards.

The operator will restart the C Service Water Pump, and the D Service Water Pump will trip. The operator will respond in accordance with AR-J-9, i SAFEGUARDS BREAKER TRIP. 3.7.8, Service Water (SW) System. The operator will address Technical Specification'

' i Booth Operator Instructions:

NA !Indications Available:

NA P-17, OPERATIONS CONTROL OPERATING INSTRUCTIONS ATTACHMENT 7, CROI SWAPPING SERVICE WATER PUMPS CO (Step 1.1.1) START A Service Water Pump (Step1.1.2)

VERIFY motor heater for A NOTE: The CO will contact the Service Water Pump de-energized.

AO. SIM DRIVER: as AO, acknowledge. (Step 1.1.3) VERIFY Service Water header pressure on PI-2160 and PI-2161 Rises. CO (Step 1.4.1) STOP B Service Water Pump (Step 1.4.2) VERIFY motor heater for B NOTE: The CO will contact the Service Water Pump energized.

AO. SIM DRIVER: as AO, acknowledge.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # _1.:...-____ Page 8 of

Event

Description:

Swap Service Water Pumps/D Service Water Pump Trip (Step 1.4.3) VERIFY B Service Water Pump NO"rE: The CO will contact the in NOT rotating.

AO. SIM DRIVER: as AO, confirm that B SW pump is NOT rotating. (Step 1.4.4) VERIFY Service Water header pressure on PI-2160 and PI-2161 lowers. CO (Step 1.7.1) START D Service Water Pump (Step 1.7.2) VERIFY motor heater for D Service Water Pump de-energized. (Step 1.7.3) VERIFY Service Water header pressure on PI-2160 and PI-2161 rises. CO (Step 1.6.1) STOP C Service Water Pump (Step 1.6.2) VERI FY motor heater for C Service Water Pump energized.

NOTE: The CO will contact the AO. SIM DRIVER: as AO, acknowledge.(Not simulated)

NOTE: The CO will contact the AO. SIM DRIVER: as AO, acknowledge. (Step 1.6.3) VERIFY C Service Water Pump NOTE: The CO will contact the in NOT rotating.

AO. SIM DRIVER: as AO, acknowledge, and report that the C SW Pump Shaft is rotating backwards.

i Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # --.;..____ Page 9 of .....,;5;...;,4---1 Event

Description:

Swap Service Water Pumps/D Service Water Pump Trip (Step 1.6.4) VERIFY Service Water header pressure on PI-2160 and PI-2161 Pressure will be lower than expected, AND the CRS will direct re-start of the C SW Pump. CO (Step 1.5.1) START C Service Water Pump (Step 1.5.2) VERIFY motor heater for C NOTE: The CO will contact the Service Pump de-energized.

AO. SIM DRIVER: as AO, acknowledge. (Step 1.5.3) VERIFY Service Water header pressure on PI-2160 and PI-2161 Rises . . Booth Operator Instructions:

NONE Trigger-29 (C SWP control switch to CLOSE causes D SWP to Trip) Indications Available:

• MeB Annunciator J-9, SAFEGUARDS BREAKER TRIP '. D SWP Green and White Breaker Status lights are LIT AR-J-9, SAFEGUARD BREAKER TRIP IF alarm is due to loss of SW pump(s), NOTE: Although the alarm is THEN due to the D SW Pump tripping, there are three SW Pumps running, and the CRS will NOT address AP-SW.2. IF alarm is due to loss of RHR pump{s), NOTE: The alarm is NOT due THEN ... to a loss of an RHR Pump.

Appendix D Operator Action Form ES-D-2 OpTest No.: N10-1 Scenario # 2 Event # _1.;......

____ Page 10 of 54 i Event

Description:

Swap Service Water Pumps/D Service Water Pump Trip *

• Investigate Report findings back to Control Room CRS IF SI is NOT required, THEN reset or closure of a breaker should not be attempted.

CRS IF SI is required, THEN ... CO Notify Electricians.

CRS Refer to ITS LCO for affected equipment.

CRS Notify higher supervision.

NOTE: The CO will contact the AO. SIM DRIVER: as AO, acknowledge, and after a short delay report that the D SW . Pump has tripped and that the shaft is stopped. NOTE: SI is NOT required.

NOTE: The CRS may notify theWCC. SIM DRIVER: as WCCS, acknowledge.

NOTE: The CRS will evaluate Technical Specifications.

NOTE: The CRS may restart the B SW Pump and shutdown the A SW Pump, returning the SW Pump alignment to the original configuration, to ensure one pump per Train is operating.

TECHNICAL SPECIFICATION 3.7.8, SERVICE WATER (SW) CRS LCO 3.7.8 four SW pumps and the SW loop header shall be OPERABLE.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # ...:.._____ Page 11 of 54-'---II Event

Description:

Swap Service Water Pumps/D Service Water Pump Trip CRS APPLICABILITY:

MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED COMPLETION ACTION TIME A. One SW A.1 Restore SW 14 days pump pump to inoperable.

OPERABLE status. At the discretion of the Lead Examiner move to Event #2.

Appendix Operator Action Form ES-O-2 OpTest No.: N10-1 Scenario # 2 Event # 2 Page 12 of 54 Event

Description:

VCT Level 112 Fails HIGH Subsequently, VCT Level transmitter LT-112 will fail High. The operator will respond in accordance with AR-A-2, VCT LEVEL 14 % 86, and enter ER-CVCS.1, Reactor Makeup Control Malfunction.

Booth Operator Operate Trigger #1 (CVC10A (100% -5 second ramp)) Indications Available: PPCS Alarm: L0112 VOLUME CONTROL TANK LEVEL, HALM VCT Level (LI-112) indicates 100%

• LCV-112A indicates full Divert to Holdup Tank (HUT) VCT Pressure (PI-115) slowly lowers MCB Annunciator A-2, VCT LEVEL 14 % 86 NOTE: The CRS may ask the HCO/CO to address this ARP based on the PPCS Alarm. If NOT, VCT Level will be at i 14% when the alarm occurs. AR-A-2, VCT LEVEL 14 % 86 HCO (Step 1) IF channel failure is indicated, THEN NOTE: The HCO will address refer to Attachment 1 and Figure 1 to Attachment 1 of the ARP. respond to VCT level transmitter failure. (Step1) Notify AO to monitor LI-139 in valve NOTE: The CRS/HCO will alley, and report reading. dispatch an AO. 81M DRIVER: as AO, acknowledge. (Step 2) Full divert to HUT will result from NOTE: Action based upon solenoid energizing at 83% level. Place direction found in A-503.1. LCV-112A in the "VCT" position.

HCO (Step 3) Auto makeup will NOT occur.

Appendix Operator Action Form ES-O-2 Op Test No.: N10-1 Scenario # 2 Event #

____ Page 13 of Event

Description:

VCT Level 112 Fails HIGH

• Inform AO to notify Control Room for manual makeup requirement when 139 indicates approximately 20%. i. Refer to ER-CVCS.1 REACTOR MAKEUP CONTROL MALFUNCTION, for manual guidance.

NOTE: The CRS/HCO will dispatch an AO. 81M DRIVER: as AO, acknowledge, and monitor T _L 139 in INSIGHT to report local LI-139 reading. Report initial level 21% to prompt initiation of manual makeup. NOTE: The CRS will go to CVCS.1 or may use S-3.1, Boron Concentration Control, Attachment 8, Manual Makeup ER-CVCS.1, REACTOR MAKEUP CONTROL MALFUNCTION (Step 4.2.1) IF the Reactor Makeup System does not respond in AUTO, THEN perform the following: (Step 4.2.1.1) DETERMINE the amount of i NOTE: The HCO will BA required to be blended with 100 gallons determine the BA to add to be of RMW to produce a boron concentration to "'1 gallon. RCS boron concentration. (Step 4.2.1.2) SET the BA integrator for the desired amount of BA. (Step 4.2.1.3) PLACE the RMW Mode selector switch to BORATE. (Step 4.2.1.4) ADJUST boric acid flow NOTE: If using Att.8, eROI control valve HCV-110A to the maximum uses "desired rate." f10wrate in AUTO. (Step 4.2.1.5) TURN the RMW Control switch to START and verify flow on the recorder.

i I Appendix Operator Action Form ES-D-2

• Op Test No.: N10-1 Scenario # 2 Event # ..__2_____ Page 14 of 54 .............Event

Description:

VeT Level 112 Fails HIGH (Step 4.2.1.6) WHEN the desired amount Boric Acid has been added, ENSURE Boration (Step 4.2.1.7) WHEN the boration PLACE the RMW Mode selector switch (Step 4.2.1.8) SET RMW flow control CHV-111 to the desired flow rate, in HCO (Step 4.2.1.9) SET the reactor makeup water NOTE: If using Att.8, CROI integrator for 100 gallons. allows adding as much water as is desired. . (Step 4.2.1.10)

TURN the RMW i switch to START and verify flow on HCO (Step 4.2.1.11)

REPEAT as necessary to SIM DRIVER NOTE: The AO maintain a satisfactory water level in the monitoring VCT will need to . Volume Control Tank until the malfunctioning remain throughout the i equipment is remainder of the scenario.

At the discretion of the Lead Examiner move to Event #3.

Appendix Operator Action Form ES-D-2

• Op Test No.: N10-1 Scenario # Event # ...,;3:..-

____ Page 15 of Event

Description:

C Charging Pump trips Following this, the C Charging Pump will trip. The operator will respond in accordance with AR-G-25, MOTOR OFF CTR SECT PMPS EXCEPT MAIN & AUX FEED PMPS and start the B Charging Pump. Booth Operator Instructions:

Operate Trigger #2 (CVC12C) Indications Available:

• MCB Annunciator G-25, MOTOR OFF CENTER SECTION PUMPS/EXCEPT MAIN . AND AUX FEEDPUMPS

• • C Charging Pump Green and White Breaker Status Lights are LIT

• Charging Line Flow (FI-128C) reads low (12 gpm)

• RCP Seal Flow (FI-115A1116A) reads low (5 gpm) I. RCP Seal Labyrinth DPs read low (15-20" H20) AR-G-25, MOTOR OFF CTR SECT PMPS EXCEPT MAIN & AUX FEED PMPS (Step 1 )

Determine which pump has (white light at switch will be (Step 2) VERIFY standby pump Auto starts NOTE: The HCO will start the OR start standby pump, IF B Charging Pump, and may take MANUAL control of Charging Pump speed. (Step 3) IF all charging pump(s) tripped, NOTE: All Charging Pumps

• are NOT CRS (Step 4) Notify NOTE: The CRS may notify the WCC/Electricians.

81M DRIVER: as

• WCC8/Electricians, acknowledge.

CRS (Step 5) Refer to ITS LCO NOTE: 3.7.5 is AFW, and N/A to this event Appendix 0 Operator Action Form ES-O-2 . Op Test No.: N10-1 Scenario # 2 Event # ____ Page 16 of "';;';""'-11 Event

Description:

C Charging Pump trips NOTE: With 2 charging pumps, requirements are met. but crew may submit A-52.12 for tracking At the discretion of the Lead Examiner move to Event #4.

Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # 4 Page 17 of 54

! Event

Description:

Turbine Impulse Pressure (PT -486) fails High I Then, Main Turbine 1 st Stage Pressure Instrument PT-486 will fail High. The operator will respond in accordance with AR-G-22, ADFCS SYSTEM TROUBLE, and enter . INST.1, Reactor Protection Bistable Defeat After Instrumentation Loop Failure.

• Booth Operator Instructions:

Operate Trigger #3 (TUR16B (1050)) I Indications Available: PI-486 indicates upscale MCB Annunciator G-22; ADFCS SYSTEM PPCS Annunciator RP27Q -First Stage Turb Press Channel AR-G-22, ADFCS SYSTEM TROUBLE COl (Step 4.1) CHECK ADFACS EMMI monitor NOTE: The CRS will dispatch AO (Relay Room) for the cause of the failure by anAO. performing the following:

SIM DRIVER: as AO, acknowledge, and report that alarm is "PT486 Out of Range" (Step 4.1.6) NOTIFY I&C of the ADFACS alarm. REFER TO ER-INST.1 PROTECTION BISTABLE DEFEAT INSTRUMENTATION LOOP FAILURE action to defeat failed NOTE: The CRS will go to INST.1. ER-INST.1, REACTOR PROTECTION BISTABLE DEFEAT INSTRUMENTATION LOOP (Step 4.1) IDENTIFY the failed instrument NOTE: PT -486 indicator has channel by observation for the bistable status failed HIGH light board, MCB annunciators, and the MCB metering indication.

Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # _4.:....-____ Page 18 of 54 Event

Description:

Turbine Impulse Pressure (PT -486) fails High (Step 4.2) WHEN a failed instrument loop NOTE: The CRS will refer to and/or channel has been indentified, THEN Section 4.12. refer to the appropriate section of this procedure listed below: (Step 4.12.1) IF turbine first stage pressure NOTE: PT -485 has NOT channel PT -485 fails, THEN ... failed. (Step 4.12.2) IF turbine first stage pressure channel PT-486 fails, THEN the following should be considered:

CO (Step 4.12.2.1)

For a PT -486 failure LOW, NOTE: PT -486 has NOT failed Low. CO (Step 4.12.2.2)

For a PT -486 failure HIGH, Steam Dump will NOT arm on load rejection.

THEREFORE, the Steam Dump Mode Selector Switch should be placed in MANUAL, THEN returned to NORMAL (This will ARM Steam Dump and allow dump operation).

NOTE: The CO will arm the Steam Dumps. Examiner NOTE: At the discretion of the Lead Examiner move to Event #5. CO (Step 4.12.2.3)

Refer to Attachment FIRST STAGE PRESSURE PI-486, BLUE, to defeat . channel AND to restore AUTOMATIC . i control. I NOTE: The CRS will hand this off to the CO, and the CO will coordinate with the HCO to I complete the Attachment.

ER-INST.1, REACTOR PROTECTION BISTABLE DEFEAT INSTRUMENTATION LOOP BLUE CHANNEL ATTACHMENT FIRST STAGE PRESSURE Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # _4.;.....____ Page 19 of 54 Event

Description:

Turbine Impulse Pressure (PT -486) fails High (Step 1) In the (BLUE) B-1 PROTECTION CHANNEL 3 rack, PLACE the following bistable proving switch to DEFEAT (UP) AND verify the proving light status is correct:

• 486 CHANNEL 3

• TURBINE PWR TRIP HCOI (Step 2) VERIFY the AMSAC TRIPPED CO status light (MCB) is extinguished.

COl (Step 3) VERIFY the TL 400 bistable AO indicating light (FOX 3-RELAY ROOM) is extinguished. (Step 4) IF> 35% power, THEN verify AM SAC feedwater Flow bistables are reset by observing the following' (FOX 3 RELAY ROOM) TLl466 TRIP STATUS LIGHT EXTINGUISHED TLl467 TRIP STAUS LIGHT EXTINGUISHED TLl476 TRIP STATUS LIGHT EXTINGUISHED TLl477 TRIP STATUS LIGHT EXTINGUISHED

! COl * (Step 5) PLACE switch TPS/486 (FOX AO RELAY ROOM) to the TRIP position AND verify TLl486 TRIP STATUS light is lit. NO"rE: Ught is OFF NOTE: The CO will SIM DRIVER: as NOTE: The CO will contact the AO. SIM DRIVER : as AO ,

• acknowledge.

i i ! I i NOTE: The CO will contact the i AO. SIM DRIVER: as acknowledge, and use TUR23 = (Step 6) IF > 40% power, THEN verify the AMSAC AUTO BLOCK status light (MCB) is HCO extinguished.

---

Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # 4 Page 20 of 54 Event

Description:

Turbine Impulse Pressure (PT -486) fails High (Step 7) Delete the computer point from PPCS by performing the

a. On the "Sub/Delete/Restore" display b. Select Point 10 P0486 c. Turn "OFF" scan processing

d. Select "Change" HCO/ GO TO step (Step 4.15.1) IF necessary, verify an N/A I operable channel is selected for the affected recorder. (Step 4.15.2) VERIFY the following in AUTO if HCO

• Rod CO

• Turbine EH HCO

• PRZR Pressure

• HC 431K

• PRZR spray valves

• PRZR HCO

• PRZR level

• Steam Dump (unless 1 st stage pressure NOTE: The CO has previously failed) armed the Steam Dumps.

• MFW control

• S/G Atmos Relief Vlv Control (Step 4.15.3) Notifications to the following NOTE: The CRS may notify people will be made by the Shift Manager: the SM/STA. SIM DRIVER: as SM/ST A, acknowledge.

• Operations Supervision Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # 4 Page 21 of 54 Event

Description:

Turbine Impulse Pressure (PT -486) fails High

• STA CRS (Step 4.15.4) During normal working hours, NOTE: The CRS may notify Maintenance personnel shall be notified theWCC. immediately of the problem. 81M DRIVER: as WCC8, acknowledge. (Step 4.15.5) During back shifts Maintenance personnel will be called in. HOWEVER, the Shift Manager may defer calling people in, IF repairs may be deferred to the next working day. At the discretion of the Lead Examiner move to Event #5.

Appendix D Operator Action Form ES-D-2 OpTest No.: N10-1 Scenario # 2 Event # ____ Page of .....;5-.4-""';i Event

Description:

A MFW Pump Oil Sump HI-LO Level/Rapid DownpowerlStuck Rod After this, the MFW pump Oil Sump HI-LO level annunciator will alarm (L-21). The operator will respond in accordance with AR-L-21, MAIN FEEDWATER PUMP OIL SUMP HI-La LEVEL, enter AP-TURB.5, Rapid Downpower, and remove the affected MFP from service. During the downpower Control Rod G-11 will stick in its original

• position.

The operator will respond in accordance with AR-C-5, PPCS ROD SEQUENCE OR ROD DEVIATION/PPCS LTOP HI-LOW TEMPERATURE, and enter AP-RCC.2, RCC/RPI Malfunction.

The operator will address Technical Specification i 3.1.4, RCC/RPI Malfunction, and 3.2.4, Quadrant Power Tilt Ratio. Booth Operator Instructions:

Operate Trigger #4 (A-FDW30 (ON); ROD03-G11)

Indications Available:

• MCB Annunciator L-21, MAIN FEEDWATER PUMP OIL SUMP HI-LO LEVEL AR-L-21, MAIN FEEDWATER PUMP OIL SUMP HI-La LEVEL CO (Step 1) Notify AO to check MFW pumps oil sumps for Hi/Low levels. NOTE: The CRS will dispatch an AO. SIM DRIVER: as AO, acknowledge.

SIM DRIVER: as AO, report that the sight glass level is -1" from the top of the sight glass on B MFW pump, and higher than he observed on his last round -4 hrs ago. The level on A MFW pump oil sump is normal. CO (Step 2) AFTER Hi/Low level is determined, THEN perform the applicable substep: a. IF level is low, THEN ... NOTE: The Level is NOT Low. b. IF level is high, THEN perform the following:

NOTE: The CRS will direct the AO to take these actions. SIM DRIVER: as AO, acknowledge, and report that during the collection of the sample for Chemistry, sample is milky in appearance, indicating the presence of water.

Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # -.,;;.5_____ Page of Event

Description:

A MFW Pump Oil Sump HI-LO Level/Rapid DownpowerlStuck Rod Obtain an oil sample Drain oil to clear the alarm. Monitor for additional inleakage. IF inleakage is apparent, reduce power to 50% RTP per 0-5.1 OR TURB.S AND remove the from TE: The CRS will go to B.S. AP-TURB.5, RAPID LOAD REDUCTION NO'rE: The CRS/CO may notify the CENG Generation Dispatch.

SIM DRIVER: as CENG Generation Dispatch, acknowledge.

NOTE: The CRS may notify the RG&E ECC. SIM DRIVER: as RG&E ECC, acknowledge.

HCO (Step 1) Initiate Load NOTE: CRS conducts load reduction briefing Verify rods in AUTO CO Reduce turbine load in Auto Place Turbine EH Control OPER PAN., IMP PRESS IN, Select desired rate Reduce the setter to the Depress the Go button. NOTE: The CO will start the load decrease.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # _5;.......

____ Page of _5..;..4_""1 Event

Description:

A MFW Pump Oil Sump HI-LO Level/Rapid Downpower/Stuck Rod d. Initiate boration at the rate determined in CALC. Place PRZR backup heaters switch to ON. HCO (Step 2) Monitor RCS Tavg

• Tavg -GREATER THAN 545°F

• Tavg -LESS THAN 579°F HCO (Step 3) Adjust Boric Acid Addition Rate As Necessary To (refer to CALC) HCO (Step 4) Monitor PRZR Pressure TRENDING to 2235 PSIG IN AUTO CO (Step 5) Monitor MFW Regulating Valves RESTORING SIG LEVEL TO 52% in AUTO HCO (Step 6) Monitor PRZR Level-TRENDING TO PROGRAM IN AUTO CONTROL The HCO will initiate a boration.

NOTE: Stuck rod causes C-5 alarm NOTE: The CRS should NOT stop the load decrease, but at the same time address the Stuck Rod. NOTE: The crew may enter AP-RCC.2 directly.

AR-C-5, PPCS ROD SEQUENCE OR ROD DEVIATION/PPCS L TOP TEMPERATURE HCO IF rods are out of sequence, THEN ... NOTE: The rods are NOT moving out of sequence.

HCO IF rod positon deviation, THEN:

Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # ____ Page of _5,;.,4';"""-11 Event

Description:

A MFW Pump Oil Sump HI-La Level/Rapid Downpower/Stuck Rod GO TO AP-RCC.2, RCC/RPI MALFUNCTION Check PPCS for operablility (S-26.1 , COMPUTER PROGRAM CHECK) Check PPCS for Fail Over Refer to ITS 3.1.4 and ITS 3.1.6. NOTE: The CRS will go to RCC.2. AP-RCC.2, RCC/RPI MALFUNCTION HCO (Step 1) Place Rods to NOTE: The CRS may direct that the Rods be taken to Manual or left in Auto based on the indications of one Stuck Rod during a rapid downpower.

HCO (Step 2) Check Dropped Rod Indication: Annunciator E-28, POWER RANGE ROD DROP ROD STOP 5%/5 SECONDS-EXTINGUISHED Annunciator C-14, ROD BOTTOM ROD STOP -EXTINGUISHED.

HCO (Step 3) Check Tavg -STABLE NOTE: The CRS may direct PROGRAM. Perform the that the Turbine be taken to Manual or left in Auto based on the indications of one Stuck Rod during a rapid downpower. Place EH control in MANUAL. Manually adjust turbine load to match Tavg and Tref. CO (Step 4) Verify Annunciator G-15, STEAM NOTE: G-15 is LIT due to DUMP ARMED -EXTINGUISHED.

previous action taken during PT -486 failure Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # _5______ Page of ....;54;""-'-11 Event

Description:

A MFW Pump Oil Sump HI-LO Level/Rapid Downpower/Stuck Rod (Step 5) Check Main Generator Load GREATER THAN 15 MW. HCO (Step 6) Establish Stable Plant Conditions

a. Tavg -TRENDING TO TREF b. PRZR pressure -TRENDING TO 2235 PSIG IN AUTO c. PRZR level -TRENDING TO PROGRAM IN AUTO CONTROL CO d. MFW Regulating Valves RESTORING S/G LEVEL TO 52% IN AUTO CRS (Step 7) Check Control Rod Alignment: Verify all rods in affected group -NOTE: Rod G-11 is not WITHIN +/- 12 STEPS OF aligned ASSOCIATED GROUP STEP COUNTER (Step 7 RNO) Refer to ITS Section 3.1.4. Examiner NOTE: At the discretion of the Lead Examiner move to Event #6-8. (Step 8) Check QPTR -LESS THAN 1.02 (Step 8 RNO) Refer to ITS Section 3.2.4. (Step 9) Verify All Individual Rod Position Indication Per Bank Operable. MRPI system -NO MRPI SYSTEM ALARMS MRPI system -NO KNOWN PROBLEMS WITH MRPI SYSTEM THAT XOULD RENDER ROD POSITION INDICATION INOPERABLE.

Appendix Operator Action Form ES-D-2

• Op Test No.: N10-1 Scenario # 2 Event # ....;;.,5_____ Page of Event

Description:

A MFW Pump Oil Sump HI-LO Level/Rapid DownpowerlStuck Rod Refer to ITS section 3.1.7 for required action. Consult Reactor Engineer and plant staff to evaluated MRPI. Go to Step 11 NOTE: The CRS will evaluate technical Specifications.

TECHNICAL SPECIFICATION 3.1.4, ROD GROUP ALIGNMENTS LCO 3.1.4 All shutdown and control shall be OPERABLE, with all indicated rod positions within 12 steps their group step counter APPLICABILITY:

MODES 1, MODE with ACTIONS CONDITION REQUIRED COMPLETION ACTION TIME Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # 5 Page _54 of .......Event

Description:

A MFW Pump Oil Sump HI-LO Level/Rapid DownpowerlStuck Rod B. One rod not B,1.1 Verify 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> within SDMis alignment within the limits. limits specified in the COLR. OR B.1.2 Initiate 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> boration to restore SDMto within limit. AND 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> B.2 Reduce THERMAL POWER to S75% RTP. AND 8.3 Verify SDM is within the Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> limits specified in the COLR AND B.4 Perform SR 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 3.2.1.1 AND B.5 Perform SR 3.2.2.1 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND B.6 5 days evalutate safety analyses and confirm results remain valid for duration of operation under these conditions.

TECHNICAL SPECIFICATION 3.2.4, QUADRANT POWER TilT RATIO CRS LCO 3.2.4 QUADRANT POWER TILT RATION (QPTR)

Appendix Operator Action Form ES-D-2 of .......Op Test No.: Nl0*1 Scenario # 2 Event # ____ Page _54-Event

Description:

A MFW Pump Oil Sump HI-LO Level/Rapid DownpowerlStuck Rod APPLICABILITY:

MODES 1 with THERMAL POWER> 50% RTP ACTIONS CONDITION REQUIRED COMPLETION ACTION TIME Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # 5 Page 30 of =-1 Event

Description:

A MFW Pump Oil Sump HI-LO Level/Rapid DownpowerlStuck Rod

• A. QPTR not with limit. A.1 Reduce THERMAL POWER:.: 3% from RTP for each 1% of QPTR.1.00.

AND A.2 Determine QPTR AND A3 Perform SR 3.2.1.1, SR, 3.2.1.2 and SR 3.2.2.1 AND A.4 Reevaluate safety analyses and confirm results remain valid for the duration of operation under this condition.

AND A.5 Normalize excore detectors to restore QPTR to within limit. AND AS Perform SR 3.2.1.1,SR 3.2.1.2 and SR 3.2.2.1 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after each QPTR determination Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 24 hours after achieving equilibrium conditions from a THERMAL POWER reduction per Required ActionA.1

AND Once per 7 days thereafter Prior to increasing THERMAL POWER above the limit of Required Action A1 Prior to increasing THERMAL POWER above the limit of Required Action A1 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after achieving equilibrium conditions at RTP not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after increasing THERMAL POWER above the limit of Required Action a.1 At the discretion of the Lead Examiner move to Events #6-8.

Appendix Operator Action Form ES-D-2 Op Test No.: Scenario # 2 Event # _6;..&.;;..;..7

___ Page of ...,;5;..;,4--1 Event SGTRI A SI Pump fails to start in AUTOI C SI Pump fails to start Shortly afterwards, a Steam Generator Tube Rupture will occur on the B Steam Generator.

The operator will respond in accordance with AR-PPCS-R47AR, SGTL INDICATED, and enter AP-SG.1, Steam Generator Tube Leak. Ultimately, the leak will be determined to be beyond the capability of the Charging Pump capacity, and the Reactor will trip and Safety Injection will actuate. The operator will enter E-O, Reactor Trip or Safety Injection.

On the Safety Injection, the A and C SI Pumps will fail to start in Auto, and the operator will be required to manually start the pumps. The operator will transition from E-O to E-3, Steam Generator Tube Rupture, isolate the flow into and out of the B Steam Generator, and then conduct a plant cooldown and depressurization.

The scenario will terminate at Step 36 of E-3, after the crew has controlled RCS .

• pressure and charging flow to minimize primary-to-secondary leakage. I Booth Operator Instructions:

Operate Trigger #5 (SGN04B (250 gpm>> Indications Available: Pri1 PPCS Alarm: R47AR, SGTL Indicated MCB Annunciator F-10, PRESSURIZER LO PRESS 2205RMS PROCESS MONITOR HIGH ACTIVITY R-15 Air Ejector Monitor reads upscale high Pressurizer Level starts to decrease NOTE: The crew may enter AP-SG.1 directly.

AR-PPCS-R47AR, SGTL INDICATED (Step 1) If SG Tube Rupture is THEN go to E-O, REACTOR TRIP SAFETY (Step 2) Trend PPCS point R-47G. (Step 3) Notify RP/Chemistry to NOTE: The CRS may notify IMMEDIATELY obtain and analyze an air RP/Chemistry.

ejector grab sample per CH-360, Primary to SIM DRIVER: as Secondary Leakage Sampling and RP/Chemistry, acknowledge.

Measurement.

Appendix Operator Action Form ES-D-2 . Op Test No.: N10*1 Scenario # 2 Event # ....;6;...;&;;;...;..7

___ Page of Event SGTRI A SI Pump fails to start in AUTOI C SI Pump fails to start (Step 4) Determine the estimated leak rate using PPCS point R47G or the R-47 Local Reading and the Conversion Table (Curve Book #06-004). (Step 5) IF any condition below is met, go to AP-SG.1, STEAM GENERATOR R47G (PPCS) greater than 5 gpd, OR R-47 greater than or equal to 5 gpd (per conversion table), OR Air ejector grab sample indicates SG tube leakage 5 gpd, OR SM discretion.

NOTE: The CRS will go to SG.1. AP-SG.1, STEAM GENERATOR TUBE LEAK (Step 1) Monitor PRZR Level-STABLE PROGRAM (Step 1 RNO) IF PRZR level lowering, start additional charging pumps and speed as necessary to stabilize PRZR (Step 1 RNO) If PRZR level continues lower, THEN close letdown isolation, 427 and excess letdown (Step 1 RNO) IF available charging are running at maximum speed with

• isolated, AND PRZR level is lowering, THEN trip the reactor and go to E-O, REACTOR TRIP OR SAFETY INJECTION.

Appendix Operator Action Form ES-D-2 Op Test No.: Scenario # 2 Event # _6...&;.;..;;...7

___ Page of __1 Event 8GTRI A 81 Pump fails to start in AUTOI C 81 Pump fails to start in AUTO ! NOTE: The CRS will go to O. E-O, REACTOR TRIP OR SAFETY INJECTION (Step 1) Verify Reactor Trip: At least one train of reactor trip breakers -OPEN Neutron flux -LOWERING MRPI indicates

-ALL CONTROL AND NOTE: G-11 rod is NOT on SHUTDOWN RODS ON BOTTOM the bottom. CO * (Step 2) Verify turbine Stop Valves (Step 3) Verify Both Trains of AC Busses Energized to at Least 440 Bus 14 and Bus 18 Bus 16 and Bus 17 i HCO (Step 4) Check if SI is NOTE: CRS will likely direct manual SI/CI if not yet auto actuated Any SI Annunciator

-LIT SI sequencing

-BOTH (Step 5) Verify CNMT Spray Not Required: Annunciator A-27, CNMT CNMT pressure -LESS THAN 28 PSIG (Step 6) Direct Operator to Perform A 27.0, ATTACHMENT AUTOMATIC

• VERIFICATION.

Appendix Operator Action Form ES-D-2

• Op Test No.: N10-1 Scenario # Event # _6;;..&;;.;..;..7

___ Page of _5;;.,4;""-11 Event SGTRI A SI Pump fails to start in AUTOI C SI Pump fails to start NOTE: The CRS will hand off ATT-27.0 to either the HCO or

• the CO, and continue with the other operator in E-O. Examiner following operator performing ATT-27.0 continue below. Examiner following operator NOT performing ATT-27.0 continue at page 36. E-O, REACTOR TRIP OR SAFETY INJECTION, ATTACHMENT 27.0, AUTOMATIC ACTION HCOI (Step 1) Verify SI and RHR Pumps All SI pumps -RUNNING NOTE: There are NO SI Pumps running. (Step 1.a RNO) Manually start SI pumps CRITICAL TASK (E-OI) Establish flow from at least one high-head ECCS Pump before transition out of E-O. Safety Significance:

Failure to start at least two SI Pumps, when they are available to results in a violation of the Facility License Condition The FSAR analysis results are on the assumption of a minimum ECCS flowrate, which includes two SI Pumps. Failure

• perform this task will leave the plant in an unanalyzed condition.

I HCOI

• Both RHR pumps -RUNNING I CO ! HCOI (Step 2) Verify CNMT RECIRC CO All fans -RUNNING Charcoal filter dampers green status lights -EXTINGUISHED Appendix Operator Action Form ES-D-2 : Op Test No.: N10-1 Scenario # 2 Event # _6.;...&___7 ___ Page .::...-of ,...;5;;..;,4---11 Event 5GTRI A 51 Pump fails to start in AUTOI C 51 Pump fails to start in AUTO HCOI (Step 3) Check If Main Steamlines Should CO Any MSIV -OPEN Check CNMT pressure -LESS THAN 18 PSIG Check if ANY main steamlines should be isolated: Low Tavg (545°F) AND high steam flow (O.5x10 6 Ib/hr) from either S/G High-High steam flow (4.4x10 6 Ib/hr) from either S/G HCOI (Step 3a RNO) Go to Step HCOI i (Step 4) Verify MFW MFW pumps -TRIPPED MFW Isolation valves -CLOSED S/G A, AOV-3995 S/G B, AOV-3994 S/G Blowdown and sample valves CLOSED HCOI I (Step 5) Verify At Least Two SW Pumps CO HCOI (Step 6) Verify CI and CI and CVI annunciators Annunciator A-26, CNMT ISOLATION Appendix Operator Action Form ES-D-2 Op Test No.: Event

Description:

HCOI CO HCOI CO HCOI CO HCOI CO HCOI CO N10-1 Scenario # 2 Event # _6....&__7 ___ Page of _5;;,.4;"'--11 SGTRI A SI Pump fails to start in AUTOI C SI Pump fails to start in AUTO Annunciator A-25, CNMT VENTILATION ISOLATION Verify CI and CVI valve status CNMT RECIRC fan coolers valve status lights -FCV-4561 FCV-4562 Letdown orifice valves -CLOSED AOV-200A AOV-200B AOV-202 (Step 7) Check CCW System Status: Verify CCW pump -AT LEAST (Step 8) Verify SI and RHR Pump Flow: SI flow indicators

-CHECK FOR FLOW (Step 8a RNO) IF RCS pressure less 1350 RHR flow indicator

-CHECK (Step 8b RNO) IF RCS pressure less 150 * (Step 9) Verify SI Pump and RHR Pump Emergency Alignment: RHR pump discharge to Rx deluge -MOV-852A Appendix Operator Action Form ES-D-2 Op Test No.: Scenario # 2 Event # _6;;..&;;;;..;..7

___ Page of .....,;5;;,..;.4--11 Event 8GTRI A 81 Pump fails to start in AUTO! C 81 Pump fails to start in AUTO Verify SI pump C -RUNNING Verify SI pump A RUNNING

• Verify SI pump B -RUNNING (Step 9d RNO) Perform the following: (Step 9d.1 RNO) Ensure SI pumps A and C running. IF either pump NOT running THEN .. * (Step 9d.2 RNO) Ensure SI pump C to discharge line MOV-871 B open o MOV-871A (Step 9d.3 RNO) Go to Step HCOI (Step 10) Verify CREATS At least one damper in each flowpath Normal Supply Air Normal Return Air Lavatory Exhaust Air CREATS fans -BOTH RUNNING E-O, REACTOR TRIP OR SAFETY INJECTION Examiner following operator NOT performing ATT-27.0 continue HERE. (Step 7) Verify Both MDAFW HCO COl (Step 8) Verify AFW Valve AFW flow -INDICATED TO i Appendix Operator Action Form ES-D-2 OpTest No.: Scenario # 2 Event # ...;6;;..&;:;;...;..7

___ Page of Event 5GTRI A 51 Pump fails to start in AUTOI C 51 Pump fails to start AFW flow from each MDAFW LESS THAN 230 GPM (Step 9) Monitor Heat Sink: HCO Check S/G narrow range level GREATER THAN 7% [25% ADVERSE CNMT] in any S/G Check S/G narrow range level BOTH S/G LESS THAN 50% Control feed flow to maintain S/G narrow range level between 7% [25% adverse CNMT] and 50%. COl (Step 10) Check If TDAFW Pump Can HCO I Both MDAFW pumps -RUNNING PULL STOP TDAFW pump supply MOV-3504A MOV-3505A (Step 11) Check CCW Flow to RCP HCO Annunciator A-7, RCP 1A RETURN HI TEMP OR LO Annunciator A-15, RCP 1 B CCW RETURN HI TEMP OR LOW FLOW EXTINGUISHED (Step 12) Monitor RCS Tavg -STABLE OR TRENDING TO HCO Appendix Operator Action Form ES-D-2 Op Test No.: N1D-1 Scenario # 2 Event # _6;;...;;.;&..;.7

____ Page of 54 Event

Description:

5GTRI A 51 Pump fails to start in AUTOI C 51 Pump fails to start in AUTO (Step 12 RNO) If temperature less 547()F and lowering, THEN perform Stop dumping steam. Ensure reheater steam supply valves IF cooldown continues, THEN total feed flow between 200 gpm to gpm until narrow range level greater 7% [25% adverse CNMT] in at least S/G. WHEN S/G level greater than 7% adverse CNMT] in one S/G, THEN feed flow to that required to level in at least one IF cooldown continues, THEN close (Step 13 ) Check PRZR PORVs and Spray Valves: HCO PORVs -CLOSED Auxiliary Spray valves (AOV-296) Check PRZR pressure -LESS 2260 Normal PRZR spray valves -CLOSED PCV-431A PCV-431B COl i (Step 14) Monitor RCP Trip Criteria:

HCO RCP status -ANY RCP RUNNING SI pumps -AT LEAST TWO RUNNING RCS pressure minus maximum S/G NOTE: Criteria should NOT be pressure -LESS THAN 210 psi [240 psi met adverse CNMT]

Appendix Operator Action Form ES-D-2

• Op Test No.: N10-1 Scenario # Event # _6;;..&;;;.;..;..7

___ Page of _5;;...4';""-""1 Event SGTRI A SI Pump fails to start in AUTOI C SI Pump fails to start CRS (Step 14c RNO) Go to Step 15. (Step 15) Check If S/G Secondary Side Pressure in both S/Gs -STABLE OR RISING Pressure in both S/Gs -THAN 110 (Step 16) Check if S/G Tubes Are Inctact: Air ejector radiation monitors (R-15, 47, R-48) -NORMAL (Step 16 RNO) Go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1. NOTE: The CRS will go to 3. E-3, STEAM GENERATOR TUBE RUPTURE HCO (*Step 1) Monitor RCP Trip Criteria: RCP status -ANY RCP RUNNING NOTE: Both RCPs are RUNNING. SI pumps -AT LEAST TWO RUNNING RCS pressure minus maximum S/G NOTE: Trip criteria is NOT pressure -LESS THAN 210 psi [240 psi met. adverse CNMT] (Step 1c RNO) Go to step 2 (Step 2) Identify Ruptured S/G(s): Unexpected rise in either S/G narrow NOTE: The CO reports that range there is an unexpected increase in B SG Level. OR Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # _6.;...-&...7____ Page of -Event SGTRI A SI Pump fails to start in AUTOI C SI Pump fails to start in AUTO High radiation indication on main steamline radiation monitor R-31 for S/G A

• R-32 for S/G RP reports high radiation from activity CO (Step 3) Isolate Flow From Ruptured S/G(s): NOTE: B is ruptured Adjust ruptured S/G ARV controller to 10S0 psig in AUTO Check ruptured S/G ARV -CLOSED Close ruptured S/G TDAFW pump steam supply valve and place in PULL STOP S/G A, MOV-3S0SA

• S.G B, Verify ruptured S/G blowdown valve CLOSED S/G B, AOV-5737 CO . (Step 4) Complete Ruptured S/G Isolation: Close ruptured S/G MSIV -RUPTURED S/G MSIV CLOSED Dispatch AO to complete ruptured S/G NOTE: The CRS will dispatch isolation (Refer to ATT-16.0, anAO. ATTACHMENT RUPTURED S/G part A) SIM DRIVER: as AO, acknowledge, and perform all remotes associated with A 16.0 (Schedule File ATT16SGBpartA.sch).

CO (Step S) Check Ruptured S/G Level: Narrow range level-GREATER THAN 7% [2S% adverse CNMT]

Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # _6.;..;;;&...;.7

____ Page of _54;;"';"'--11 Event SGTRI A SI Pump fails to start in AUTOI C SI Pump fails to start in AUTO Close MDAFW pump discharge valve to ruptured S/G S/G B, MOV-4008 Pull stop MDAFW pump for ruptured S/G Close TDAFW pump flow control valve to ruptured S/G S/G B, AOV-4298 Verify MDAFW pump crosstie CLOSED MOV-4000A MOV-4000B CO (Step 6) Verify Ruptured S/G Isolated: Check ruptured MSIV -CLOSED Check TDAFW pump steam supply from ruptured S/G -ISOLATED Ruptured S/G pressure -THAN 300 CRITICAL TASK (E-3A) Isolate feedwater flow into and steam flow from the ruptured SG before a transition to ECA-3.1 occurs. Safety Significance:

Failure to isolate the ruptured SG causes a loss of LlP between the ruptured SG and the intact SGs. Upon a loss of LlP, the crew must transition to a contingency procedure that constitutes an incorrect performance that "necessitates the crew taking compensating action which complicates the event mitigation strategy." If the crew fails to isolate steam from the SG, or feed flow into the SG the ruptured SG pressure will tend to decrease to the same pressures as the intact SGs, requiring a transition to a contingency procedure, and delaying the stopping of RCS leakage into the SG. CO * (Step 7) Establish Condenser Steam Pressure Verify condenser available Intact S/G MSIV -OPEN Appendix Operator Action Form ES-D-2 OpTest No.: Scenario # 2 Event # .._6._&...;.7

____ Page of Event SGTRI A SI Pump fails to start in AUTOI C SI Pump fails to start in AUTO Annunciator G-1S, STEAM DUMP ARMED -LIT Adjust condenser steam dump controller HC-484 to maintain intact S/G pressure and verify in AUTO Place steam dump mode selector switch to MANUAL HCO (Step 8) Reset SI (Step 9) Initiate RCS Cooldown: (Step 9a) Determine required core temperature from below

• 1000-1049 psig (S12°F)

• 10S0-1099 psig (S19°F) (Step 9b) IF ruptured S/G MSIV THEN initiate dumping steam to from intact S/G at maximum CO (Step 9c) Core exit TICs -LESS i REQUIRED (Step 9c RNO) Continue with Step 10.WHEN NOTE: The CO will initiate a core exit TICs less than required, THEN do cooldown, and proceed on in Step 9d. the procedure.

When the target temperature of 512°F is reached perform Step 9.d. i (Step 9d) Stop RCS cooldown and stablilize core exit TICs less than required temperature (Step 10) Monitor Intact S/G Level: Narrow range level -GREATER THAN 7% [2S% adverse CNMT]

Appendix Operator Action Form ES-D-2 OpTest No.: N10-1 Scenario # 2 Event # _6.-&.......7___ Page of _5.... Event SGTRI A SI Pump fails to start in AUTOI C SI Pump fails to start in AUTO Control feed flow to maintain narrow range level between 17% [25% adverse CNMT] and 50% (Step 11) Monitor PRZR PORVs and Power to PORV block valves PORVs -CLOSED Block valves -AT LEAST ONE OPEN (Step 12) Reset CI: Depress CI reset push button Verify annunciator A-26, ISOLATION

-

CO (Step 13) Monitor AC Bus Power: Verify Safeguards Busses 14,16, 17 and 18 -GREATER THAN 440 VOLTS Verify All AC Busses -BUSSES ENERGIZED BY OFFSITE POWER Normal feed breakers to all 480 volt busses -CLOSED Emergency DIG output breakers NOTE: Both EDGs are running -OPEN unloaded.

CO (Step 14) Verify Adequate SW Flow: Check at least two SW pumps Dispatch AO to establish normal NOTE: The CRS will dispatch shutdown alignment (Refer to ATI-17.0, anAO. ATTACHMENT SD-1) SIM DRIVER: as AO, acknowledge.

Run SCHEDULE file SD-1.sch Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # _6;...&;;.;..;...7

___ Page of __54__Event

Description:

5GTRI A 51 Pump fails to start in AUTOI C 51 Pump fails to start in AUTO i (Step 15) Establish IA to SNMT: Verify non-safeguards busses energized o Bus 13 normal feed -Bus 15 normal feed -CLOSED Verify turbine building SW valves -MOV-4613 and MOV-4670 MOV-46134 and MOV-4664 Verify adequate air compressors Check IA supply: Pressure -GREATER THAN 60 PSIG Pressure -STABLE OR RISING Reset both trains of XY relays for IA CNMT Verify IA to CNMT AOV-5392 -OPEN I HCO (Step 16) Check if RHR pumps Should Be Stopped: Check RCS pressure -GREATER 300 psig [350 psig adverse Stop RHR pumps and place both in NOTE: The HCO will STOP AUTO both RHR Pumps. HCO (Step 17) Establish Charging Flow:

• Charging pumps -ANY (Step 17a RNO) Perform the IF CCW flow is lost to any RCP NOTE: CCW flow has NOT thermal barrier OR any RCP #1 been lost to the Thermal seal outlet temperature greater Barriers, nor is any RCP #1 than 235°F, THEN ... . seal outlet temperature greater than 235°F.

Appendix Operator Action Form ES-D-2 OpTest No.: Scenario # 2 Event #

___ Page of Event SGTRI A SI Pump fails to start in AUTOI C SI Pump fails to start in AUTO Ensure HCV-142 demand at 0% Align charging pump suction to RWST: LCV-112B -OPEN LCV-112C -CLOSED Start charging pumps and establish 75 NOTE: C Charging Pump has gpm total charging flow tripped previously . Charging line flow Seal injection (Step 18) Check if RCS Cooldown Should Core exit TICs LESS THAN REQUIRED TEMPERATURE Stop RCS cooldown NOTE: If NOT previously done, when the target temperature of 512°F or 519°F has been reached. Stabilize core exit TICs -LESS REQUIRED (Step 19) Check Ruptured SIG Pressure STABLE OR (Step 20) Check RCS Subcooling based Core Exit TICs -GREATER THAN USING FIG-1.0, FIGURE (Step 21) Depressurize RCS To Break Flow and Refill Check the following: Ruptured S/G level-LESS THAN 90% [80% adverse CNMT] Any RCP -RUNNING IA to CNMT -AVAILABLE Appendix Operator Action Form ES-O-2 Op Test No.: N10*1 Scenario # 2 Event # _6;;..&.;;;..;..7

___ Page of ...;;.,54';""'-1 Event

Description:

SGTRJ A SI Pump fails to start in AUTOI C SI Pump fails to start in AUTO -Spray PRZR with maximum available spray until ANY of the following conditions satisfied:

I PRZR level-GREATER THAN 75% [65% adverse CNMT] OR oRCS pressure -LESS THAN SATURATION USING FIG-1.0, FIGURE MIN SUBCOOLING OR o BOTH of the following: RCS pressure -LESS THAN RUPTURED S/G PRESSURE PRZR level-GREATER THAN 10% [30% adverse CNMT]

• Close normal PRZR spray valves: Adjust normal spray valve controller to 0% DEMAND Verify PRZR spray valves-CLOSED

• PCV-431A

• PCV--431 B Verify auxiliary spray valve (AOV-296) CLOSED CRS

• GO to Step 24. (Step 24) Check if SI Flow Should RCS subcooling based on core exit TICs -GREATER THAN O°F USING FIG-1.0, FIGURE MIN SUBCOOLING

• Secondary heat sink: Total feed flow to S/G(s) GREATER THAN 200 GPM AVAILABLE Appendix Operator Action Form ES-D-2 OpTest No.: Scenario # 2 Event # _6._.....&_7

____ Page of _5,;.4.=...--I)

Event 8GTRI A 81 Pump fails to start in AUTOI C 81 Pump fails to start in AUTO Narrow range level in at least one intact SIG -GREATER THAN 7% [25% adverse CNMT] HCO RCS pressure -STABLE OR RISING HCO PRZR level -GREATER THAN [30% adverse CRITICAL TASK (E-3C) Depressurize the RCS to meet SI termination criteria before ruptured SG level reaches 100% Wide Range Level. Safety Significance:

Failure to stop the reactor coolant leakage into a ruptured SG by depressurizing the RCS (when it is possible to do so) needlessly complicates the mitigation of the event. It also constitutes a "significant reduction of Safety Margin beyond that irreparably introduced by the scenario.

If RCS depressurization does NOT occur, the inventory in the secondary side of the ruptured SG will occur leading to water release through the SG PORV or Safety Valve, which could cause and unisolable fault in the ruptured SG. HCO (Step 25) Stop SI Pumps and Place In AUTO NOTE: The HCO will STOP I the A & C Pumps. i (Step 26) Establish Required Charging . Charging pumps -ANY RUNNING .* Establish 22 gpm charging line flow NOTE: The HCO will establish 22 gpm of Charging flow. HCO (Step 27) Monitor SI Reinitiation Criteria RCS subcooling based on core exit TICs -GREATER THAN OaF USING FIG 1.0, FIGURE MIN SUBCOOLING PRZR level-GREATER THAN [30% adverse Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # _6::;..&=-:..7

___ Page of ....,;54;;";""-1 Event

Description:

SGTRI A SI Pump fails to start in AUTOI C SI Pump fails to start in AUTO (Step 28) Check if SI ACCUMs Should Be Isolated: Check the following: RCS subcooling based on exit TICs -GREATER O°F USING FIG-1.0, MIN PRZR level-GREATER Dispatch AO with locked valve key to NOTE: The CRS will dispatch locally close breakers for 81 ACCUM anAO. discharge valves SIM DRIVER: as AO, acknowledge, and use REM EOS-035 and EDS-036. MOV-841, MCC C position 12F MOV-865, MCC D position 12C Close SI ACCUM discharge valves MOV-841 MOV-865 Locally reopen breakers for MOV-841 and NOTE: The CRS will dispatch MOV-865 an AO. SIM DRIVER: as AO, acknowledge, and use REM EDS-035 and EDS-036. (Step 29) Verify Adequate SW Flow to CCW Hx: Verify at least three SW pumps (Step 29a RNO) Manually start pumps as NOTE: Three SW Pumps are power supply permits (257 kw each). IF less running. than two SW pumps can be operated, THEN ... Verify AUX BLDG SW isolation valves AT LEAST ONE SET i Appendix Operator Action Form ES-D-2 Op Test No.: , Event

Description:

HCO HCO HCO N10-1 Scenario # ...L.. Event # ....;6;..&;;;..;..7

___ Page of _5;;,.4;......-t SGTRI A SI Pump fails to start in AUTOI C SI Pump fails to start in AUTO MOV-4616 and MOV-4735 Verify CNMT RECIRC fan annunciator 2, HIGH TEMPERATURE ALARM EXTINGUISHED (Step 30) Check if Normal CVCS Operation Can Be Established Verify IA restored:

0 IA to CNMT (AOV-5392)

-OPEN 0 IA pressure -GREATER THAN 60 PSIG Verify instrument bus D -ENREGIZED CCW pumps-ANY RUNNING Charging pump -ANY RUNNING (Step 31) Check if Seal Return Flow Should Be Established Verify RCP #1 seal outlet temperature

• LESS THAN 235°F Verify RCP seal outlet valves -OPEN 0 0 Reset both trains of XY relays for RCP seal return isolation valve MOV-313 Open RCP seal return isolation valve MOV-313 Verify RCP #1 seal leakoff flow LESS THAN 6.0 GPM Verify RCP #1 sealleakoff flow GREAT THAN 0.8 GPM HCO (Step 32) Verify PRZR THAN 20 % [40% adverse Appendix Operator Action Form ES-D-2 Op Test No.: Scenario # 2 Event #

____ Page of Event SGTRI A SI Pump fails to start in AUTOI C SI Pump fails to start in AUTO HCO (Step 33) Establish Normal Letdown: Establish charging line flow to REGEN Hx -GREATER THAN 22 GPM Place the following switches to CLOSE: 0 Letdown orifice valves (AOV-200A, AOV-200B, and AOV-202) 0 Letdown isolation valve AOV-371 0 Loop B cold leg to REGEN Hx 427 Place letdown controllers in MAN UAL at 40% open 0 TCV-130 0 PCV-135 Reset both trains of XY relays for 371 and AOV-427 Open AOV-371 Place letdown isolation AOV-427 to OPEN and THEN place to AUTO Open letdown orifice valves as necessary Place PCV-135 in AUTO and 250 psig Place TCV-130 in AUTO at the normal setpoint Adjust charging pump speed and 142 HCO (Step 34) Check VCT Makeup System: Adjust boric acid flow control valve AUTO to 9.5 Adjust RMW flow control valve in to 40 Verify the following: RMW mode selector switch in NOTE: Previous VCT level AUTO failure precludes Auto makeup Appendix Operator Action Form ES-D-2 Op Test No.: Scenario # Event # _6...&-...;..7___ Page of _5....40--11 Event 5GTRI A 51 Pump fails to start in AUTOI C 51 Pump fails to start in AUTO RMW control armed -RED LIGHT LIT Check VCT level: NOTE: The CRS/HCO will contact the AO. 51M DRIVER: as AO, acknowledge, and monitor T _L 139 in INSIGHT to report . local LI-139 reading. Level -GREATER THAN 20% OR Level-STABLE OR RISING (Step 35) Check Charging Pump Suction

• Aligned to VCT: VCT level -GREATER THAN 20% 51M DRIVER: Report local VCT level reading Verify charging pumps aligned to VCT (Step 35b RNO) Manually align valves LCV-112C -OPEN LCV-112B -CLOSED ("'Step 36) Control RCS Pressure Charging Flow Minimize

• Leakage: Perform appropriate action(s) from table: At the discretion of the Lead Examiner terminate the Exam.

---

UNIT STATUS: Power Level: 100% RCS [B] 310 ppm BAST [B]: 14000 ppm Power The plant is at 100% power (EOL), Core Burnup: 16000 MWD/MTU and has been on-line for 450 days. INFORMATION NEEDED TO ASSUME TO SHIFT: The Plant is at 100% power (EOl). Per the daily work schedule, CROI-7, Swapping Service Water Pumps, is to be performed immediately after assuming the watch, shifting to A and D Service Water pumps in service. The following equipment is Out-Of-Service: The B SI Pump is OOS for Bearing Replacement.

lCO 3.5.2 was entered 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> ago, and maintenance is scheduled to be completed sometime next shift.

A-52.4 Equipment Date Time Reason Required Actions Required Require( Action not met Completion Daterrime B SI Pump _1_/10 0330 Bearing ITS 3.5.2 36 hrs from ITS 3.5.2 Replacement Enter Condition A current Enter Conditi( nB date/time Required Action A.1: Restore the Required Acti on B.1: Be in Mode 3 Train to OPERABLE Status in 72 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> hours AND Required Acti on B.2: Be in Mode 4 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> PROGRAM: Ginna Operations Training MODULE: 2010 Initial License Operator Training Class TOPIC: NRC Simulator Exam Scenario N 1 0-1-4

REFERENCES:

1. T-5G, Swapping Condensate Pumps With At Least One MFP Running 2. AR-G-8, 4KV MOTOR OVERLOAD 3. AR-G-25, MOTOR OFF SECT PMPS EXCEPT MAIN & AUX FEED PMPS 4. STP-O-1, Rod Control System 5. AR-C-14, ROD BOTTOM ROD STOP 6. AR-C-29, MRPI SYSTEM FAILURE 7. AP-RCC.2, RCC/RPI Malfunction

8. Technical Specification 3.1.7, Rod Position Indication

9. Technical Specification 3.14, Rod Group Alignment Limits 10. AR-F-4, PRESSURIZER LEVEL DEVIATION

-5 NORMAL +5 11. AR-F-28, PRESSURIZER HI LEVEL CHANNEL ALERT 87% 12. ER-INST.1, Reactor Protection Bistable Defeat After Instrumentation Loop Failure 13. Technical Specification 3.3.1, Reactor Trip System Instrumentation

14. Technical Specification 3.3.3, Post Accident Monitoring Instrumentation

15. AR-G-25, MOTOR OFF CTR SECT PMPS EXCEPT MAIN &AUX FEED PMPS 16. AR-H-17, FEED PUMP NET POSITIVE SUCTION HEAD 17. AP-FW.1, Abnormal MFW Pump Flow or NPSH 18. AP-TURB.5, Rapid Load Reduction

19. A-503.1, Emergency and Abnormal Operating Procedures Users Guide 20. E-O, Reactor Trip and Safety Injection

21. E-2, Faulted Steam Generator

22. ECA-2.1, Uncontrolled Depressurization of All Steam Generators

23. FR-H.1, Response to Loss of Secondary Heat Sink Author: David Lazarony, Western Technical Services, Inc. Facility Review: Pat Landers, Principal Ops Training Specialist, 4/29/2010 Rev. 060810 -1 Scenario Event NRC Scenario Facility:

Ginna Scenario No.: 4 Op Test No.: N10-1 Examiners:

Operators: (SRO) (RO) (BOP) Initial The Plant is at 100% power (MOL). It is expected that immediately after turnover the crew will swap Condensate Pumps per Maintenance Dept Work Order, and conduct routine Rod Control exercises on Control Bank D. .

The following equipment is Out-Of-Service:

The B AFW Pump is OOS for Bearing Replacement.

Event Malf. No. Event Event No. Type* Description 1 CND04B Swap Condensate Pumps (Start B, Secure C)/B Condensate Pump Trip C-SRO ROD13C-I-RO Rod Control Exercise/MRPI Failure K7 I (TS}-SRO Pressurizer Level (L T -428) Fails HIGH 3 I-RO I(TS}-SRO Heater Drain Pump A trips/Rapid Downpower 4 C-RO C-BOP C-SRO 5 C-BOP B SG ARV Controller (AOV-3410) fails in AUTO C-SRO STM05A M-RO MSIVs Close and SG Safeties lift/fail OPEN (1 per SG) STM05B M-BOP STM09A M-SRO STM09B 7 RPS07M TDAFW Pump Steam Supply Valves to Open in AUTO RPS07N * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor -

Scenario Event NRC Scenario Ginna 2010 NRC Scenario #4 The Plant is at 100% power (MOL). It is expected that immediately after turnover the crew will swap Condensate Pumps in preparation for taking C Condensate Pump OOS for maintenance, and conduct routine Rod Control surveillance on Control Bank D. The following equipment is Out-Of-Service:

The B AFW Pump is OOS for Bearing Replacement.

Shortly after taking the watch, the operator will swap Condensate Pumps in accordance with 5G, Swapping Condensate Pumps With At Least One MFP Running. After the B Condensate Pump is started, the motor will trip on overload in 60 seconds. The operator will address 8, 4KV MOTOR OVERLOAD, and AR-G-25, MOTOR OFF SECT PMPS EXCEPT MAIN &AUX FEED PMPS, and secure the evolution to swap condensate pumps. After this, the operator will conduct a routine Rod Control surveillance on Control Bank 0 in accordance with STP-0-1, Rod Control System. When the rods are being returned to their normal position, a MRPI detector coil stack failure will occur which will result in an indication that one of the exercised Control Rods appears to have dropped into the core. The operator will respond in accordance with AR-C-14, ROD BOTTOM ROD STOP and AR-C-29, MRPI SYSTEM FAILURE, and enter AP-RCC.2, RCC/RPI Malfunction.

The operator will address Technical Specification 3.1.7, Rod Position Indication, and 3.14, Rod Group Alignment Limits. Next, Pressurizer Level Transmitter LT-428 will fail High. The operator will respond in accordance with AR-F-4, PRESSURIZER LEVEL DEVIATION

-5 NORMAL +5, and AR-F-28, PRESSURIZER HI LEVEL CHANNEL ALERT 87%, and enter ER-INST.1, Reactor Protection Bistable Defeat After Instrumentation Loop Failure. The operator will address Technical Specification 3.3.1, Reactor Trip System Instrumentation, and 3.3.3, Post Accident Monitoring Instrumentation.

After this, the A Heater Drain Pump will trip. The operator will respond in accordance with G-25, MOTOR OFF CTR SECT PMPS EXCEPT MAIN &AUX FEED PMPS, and/or AR-H-17, FEED PUMP NET POSITIVE SUCTION HEAD, and enter AP-FW.1, Abnormal MFW Pump Flow or NPSH. The operator will reduce load to 70% in accordance with AP-TURB.5, Rapid Load Reduction.

During the down power, the B Steam Generator ARV (AOV-341 0) Controller will fail in Auto such that the valve goes fully Open. The operator will respond in accordance with A-503.1, Emergency and Abnormal Operating Procedures Users Guide, and close the valve manually.

At a Turbine load of about 550 MWe, both MSIVs will inadvertently fail shut. The Reactor will trip, and the operator will enter E-O, Reactor Trip or Safety Injection.

On the plant trip one or more SG Safety Valves will open. and the lowest set valve will stick in the OPEN position on each SG. Additionally, the A AFW Pump will trip upon an automatic start signal. and the TDAFW Pump Steam Supply Valves will fail to open upon an automatic signal. The operator will be required to manually start the TDAFW Pump to restore Secondary Heat Sink. The operator will transition from E-O to E-2, Faulted Steam Generator Isolation, and then to ECA-2.1, Uncontrolled Depressurization of All Steam Generators.

The scenario will terminate at Step 16 of ECA-2.1, after the crew has correctly determined whether plant conditions meet SI Termination criteria.

-

Scenario Event NRC Scenario Critical Tasks: E-OF Establish 230 gpm of AFW Flow to the Steam Generators before transition out of E-O, unless the transition is made to FR-H.1, and then before the RCPs are manually tripped to limit heat input to the RCS. Safety Significance:

Failure to establish a Secondary Heat Sink through the initiation of AFW flow unnecessarily challenges both the HEAT SINK and the CORE COOLING Critical Safety Functions.

Additionally, the FSAR Safety Analysis results are predicated on the assumption that at least one train of safeguards actuates and delivers a minimum amount of AFW flow to the Steam Generators.

Failure to perform this task, when the ability to do so exists, results in a violation of the Facility license Condition and places the plant in an unanalyzed condition.

ECA-2.1 A Control the AFW flowrate to 50 gpm per SG in order to minimize the RCS Cooldown rate before a severe challenge (Orange Path) develops to the integrity CSF. Safety Significance:

Failure to control the AFW flow rate to the SGs leads to an unnecessary and avoidable severe challenge to the integrity CSF. Also, failure to perform the Critical Task increases challenges to the SUBCRITICALITY and CONTAINMENT Critical Safety Functions which otherwise would not occur.

Scenario Event NRC Scenario SIMULATOR OPERATOR INSTRUCTIONS Reset to Temp IIC 100% power MOL o 179 (NRC 4). T=O: PULL STOP the B MDAFW Pump Set Trigger 30 = True when a reactor trip signal occurs on either Train A or B Set Trigger 29 = x06i240b==1 (Start Switch on B Cond Pump) Insert MALF STM09A, 100%, 0 ramp, T-30 (Safety valve 3S08 on B SG opens after Rx trip) Insert MALF STM09B, 100%, 0 ramp. T -30 (Safety valve 3S09 on A SG opens after Rx trip) Insert MALF CND04B, 60 sec delay, T -29 Insert MALF RPS07M, Steam Supply Valve to TDAFW pump fails to OPEN Insert MALF RPS07N, Steam Supply Valve to TDAFW pump fails to OPEN Insert MALF FDW11A, A AFW Pump Trip Insert OVR-DO-FDW06A, OFF (Green light on B MDAFW Pump Disch Valve MOV-4008)

Insert MALF ROD13C-K7, on T-1 Insert MALF PZR03C, 100%, No Ramp, on T-2 Insert MALF HTR02A, on T-3 Insert MALF STM04C, 100%, No Ramp, on T-4 Insert MALF STMOSA, 0%, No Ramp. on T-S Insert MALF STMOSB, 0%, No Ramp, on T-S Prior to Crew

• Hang PROTECT tags on the A MDAFW TDAFWpumps

• Hang Black Dot on MCB Annunciator J-2S Crew Assign Crew Positions based on evaluation requirements Review the Shift Turnover Information with the crew. Provide the crew with a copy of T-5G, Swapping Condensate Pumps With At Least One MFP Running. Ensure Pre-job Brief conducted on the sequence of this swapover. Provide the crew with a copy of STP-O-1, Rod Control System; with Attachment 1 marked up as shown in the Turnover Information (Last Page of Simulator Guide) o T-O Begin Familiarization Period -

Scenario Event NRC Scenario At direction of 0 examiner At direction of 0 examiner At direction of 0 examiner At direction of 0 examiner At direction of 0 examiner At direction of 0 examiner Continued 0 from Event 6 o Event 1 Swap Condensate Pumps (Start B, Secure C)/B Trigger #29 Condensate Pump Trip CND04B NOTE: T -29 tied to B Cond Pump CS to Start (60 seconds delayed) Event 2 Rod Control Exercise/MRPI Failure Trigger #1 ROD13C-K7 Event 3 Pressurizer Level (L T -428) Fails HIGH Trigger#2 PZR03C 100%, No Ramp Event 4 Heater Drain Pump A trips/Rapid Downpower Trigger#3 HTR02A Event 5 B SG ARV Controller (AOV-3410) fails in AUTO Trigger #4 100%, No Ramp STM04C Event 6 MSIVs Close, SG Safeties lift/fail OPEN (1 per SG) Trigger #5 STM05A 0%, No Ramp STM05B 0%, No Ramp T = 0 (T-30) NOTE: This Malfunction is inserted in the IC at T = 0, S"rM09A T-30 (Rx Trip) STM09B 100%, No Ramp 100%, No Ramp Event 7 TDAFW Pump Steam Supply Valves to Open in AUTO T=O NOTE: This Malfunction is inserted in the IC at T = O. RPS07M RPS07N Terminate the scenario upon direction of Lead Examiner -

Appendix Operator Action Form ES-D-2 . Op Test No.: N10-1 Scenario # 4 Event # _1.;...-____

Page 7 of Event Swap Condensate Pumps (Start B, Secure C)/B Condensate Pump Trip Shortly after taking the watch, the operator will swap Condensate Pumps in accordance with T-5G, Swapping Condensate Pumps With At Least One MFP Running. After the B Condensate Pump is started, the motor will trip on overload in 60 seconds. The operator will address AR-G-8, 4KV MOTOR OVERLOAD, and AR-G-25, MOTOR OFF SECT PMPS EXCEPT MAIN & AUX FEED PMPS, and secure the evolution to swap , condensate pumps. I SIM DRIVER Instructions:

NA !Indications Available:

NA T-5G, SWAPPING CONDENSATE PUMPS WITH AT LEAST ONE MAIN FEED PUMP RUNNING i i (Step 6.4.1) PLACE the MCB switch for . Condensate Pump B in PULL STOP. (Step 6.4.2) CLOSE Condensate Pump B NOTE: The CO will contact an discharge block valve, V-3921. AO.AO Booth Instructor:

as AO, acknowledge, and use CND14=O, then report that 3921 is CLOSED. (Step 6.4.3) OPEN Condensate Pump B NOTE: The CO will contact an recirc valve, V-3910. AO. Booth Instructor:

as AO, acknowledge, and then report that V-391 0 is OPEN (not simulated). (Step 6.4.4) IF desired THEN PLACE Hotwell NOTE: The CO will place LC-Level Controller, LC-107, in Manual. 107 in MANUAL. OTHERWISE, MARK this Step N/A. (Step 6.4.5) PLACE Condensate Pump B the

• MCB in AUTO Appendix Operator Action Form ES-O-2 Op Test No.: Scenario # 4 Event # ____ Page 8 of 51 Event Swap Condensate Pumps (Start B, Secure C}/B Condensate Pump Trip NOTE: The CO will START the B Condensate Pump. CO (Step 6.4.7) WHILE SLOWLY OPENING NOTE: The CO will contact an

• Condensate Pump B Discharge Block AO. V-3921, MONITOR Trim Valve position on Booth Instructor:

as AO, the MCB. acknowledge, and take NO ACTION, Pump will trip 60 seconds after START. SIM DRIVER Instructions:

NA Note: Trigger-29 (CND04B) tied to B Cond Pump Control Switch to START (60 seconds delayed) Indications Available: MCB Annunciator G-8,4KV MOTOR OVERLOAD MCB Annunciator G-8, MOTOR OFF CTR SECT PMPS EXCEPT MAIN & AUX FEED PMPS B Condensate P Green and White Breaker Status AR-G-8, KV MOTOR OVERLOAD CO (Step 1) DETERMINE which pump tripped: CHECK Bus breakers for protective relay flags and possible smoke/flames. IF multiple pumps trip, THEN EVALUATE isolating bus. NOTIFY electricians AND mechanics NOTE: The CRS may notify the WCC/Electricians. Booth Instructor:

as WCCS/Electricians, acknowledge.

CRS

• GO TO appropriate procedure: E-O if reactor tripped AP-CW.1 if CW pump tripped AP-FW.1 if MFW pump tripped NOTE: No identified procedures are applicable.

Appendix Operator Action Form ES-O-2 Op Test No.: Scenario # 4 Event # ____ Page 9 of Event Swap Condensate Pumps (Start B, Secure C}/B Condensate Pump Trip CRS . (Step 2) IF no pump tripped, THEN NOTE: The 8 Condensate Pump tripped. AR-G-25, MOTOR OFF CTR SECT PMPS EXCEPT MAIN & AUX FEED PMPS (Step 1) Determine which pump has tripped , NOTE: The 8 Condensate (white light at switch will be lit). Pump tripped. i (Step 2) Verify standby pump Auto starts . start standby pump, IF i (Step 3) IF all charging pump(s) tripped, NOTE: The Charging Pumps , THEN go .... did NOT trip. CRS (Step 4) Notify NOTE: The CRS may notify the WCC/Electricians.

Booth Instructor:

as WCCS/Electricians, acknowledge.

CRS (Step 5) Refer to ITS LCO 3.7.5. NOTE: Does not apply CRS (Step 6) Refer to TRM TR 3.1.1 and 3.1.2. NOTE: Do not apply NOTE: The CRS will suspend . the swap of the 8 Condensate Pump. NOTE: The CO will return 107 to AUTO.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event # _1.;...-____ Page 10 of _5._1__.-1 Event

Description:

Swap Condensate Pumps (Start B, Secure C)/B Condensate Pump Trip NOTE: The CO may contact the AO, and direct that the original configuration be restored.

IF SO, SIM DRIVER: as AO, acknowledge, and use CND14=100, then report that V-3921 is OPEN, and then report that V-391 0 is CLOSED. At the discretion of the Lead Examiner move to Event #2.

Appendix Operator Action Form ES-D-2 Op Test No.: N1Q*1 Scenario # 4 Event # 2 Page 11 of 51 Event

Description:

Rod Control Exercise/MRPI Failure After this, the operator will conduct a routine Rod Control surveillance on Control Bank D in accordance with STP-O-1, Rod Control System. When the rods are being returned to their normal position, a MRPI detector coil stack failure will occur which will result in an indication that one of the exercised Control Rods appears to have dropped into the core. The operator will respond in accordance with AR-C-14, ROD BOTTOM ROD STOP and i AR-C-29, MRPI SYSTEM FAILURE, and enter AP-RCC.2, RCC/RPI Malfunction.

The operator will address Technical Specification 3.1.7, Rod Position Indication, and 3.14, Rod Group Alignment Limits. 81M DRIVER Instructions:

NA Indications Available:

NA (Step 6.6.1) PLACE ROD CONTROL SELECTOR switch to CBD position. (Step 6.6.2) RECORD individual rod position . NOTE: This Attachment is indication AND group step counter values for already in progress and was the Control Bank 0 on Attachment 1, Rod provided to the crew upon Position.

turnover. (Step 6.6.3) PERFORM the following substeps for all rods in the Control Bank D UNTIL all have been transitioned: REFER TO Attachment 2,

Transition Band, to determine when change in individual rod position DETERMINE direction Control Bank will be moved AND MARK the NOT selected Rods moving IN -Group should move before Group 1 . OR Rods moving OUT -Group should move before Group Appendix Operator Action Form ES-D-2 OpTest No.: N10-1 Scenario # 4 Event #

____ Page 12 of _5;;.,1;"""--11 Event

Description:

Rod Control Exercise/MRPI Failure MOVE Control Bank D in the desired direction.

HCO VERIFY groups within the bank are moving in the correct sequence. WHEN each rod transitions on THEN STOP AND RECORD position on Attachment 1, Rod Position. (Step 6.6.4) CHECK that individual rod MRPI transition occurred within plus or minus 2 steps of the individual detector coil locations as indicated by the step counters on Attachment 2, Acceptable Transition Band. (Step 6.6.5) IF any individual rod MRPI NOTE: All MRPI transitions transition checked in Step 6.6.4 did NOT will occur within plus or minus occur within plus or minus 2 steps ... 2 steps. (Step 6.6.6) RETURN Control Bank D to initial position as indicated by the Group Counters on Attachment 1, Rod SIM DRIVER When HCO is restoring Control Bank D, after bank has been moved IN/OUT -3 steps towards their normal position, operate 1 (ROD13C-K7)

Indications Available: MCB Annunciator C-29, MRPI SYSTEM FAILURE No flux prompt drop on Power Range recorder Tavg remains steady K-7 ERR on MRPI dis la screen NOTE: The crew may enter AP-RCC.2 directly.

AR-C-29, MRPI SYSTEM FAILURE (Step 1) Verify rod indication using the CRT OR PPCS (Step 2) GO TO AP-RCC.2 Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event # ....;2=--____

Page 13 of 51 Event

Description:

Rod Control Exercise/MRPI Failure (Step 3) Check SYSTEM STATUS pages CRS (Step 4) Notify the NOTE: The CRS may notify the WCC/I&C/RE.

Booth Instructor:

as . WCCS/I&C/RE, acknowledge. Operations Supervision Reactor Engineer I&C (call in during off hours) (Step 5) IF indications do NOT suggest problem with Control Rods OR the Control System, THEN perform PT-1 determine MRPI System CRS (Step 6) Refer to ITS LCO 3.1.7. (Step 7) Refer to S-26.2.

• NOTE: The CRS will go to RCC.2. AP-RCC.2, RCC/RPI MALFUNCTION HCO (Step 1) Place Rods to NOTE: The HCO will leave the Rods in MANUAL. (Step 2) Check Dropped Rod Indication: Annunciator E-28, POWER RANGE NOTE: E-28 extinguished ROD DROP ROD STOP 5%/5 SECONDS -EXTINGUISHED Annunciator C-14, ROD BOTTOM ROD NOTE: C-14 lit STOP -EXTINGUISHED (Step 2 RNO) IF the following conditions NOTE: There will be NO exist, THEN go to AP-RCC.3, DROPPED prompt drop in neutron flux, or ROD RECOVERY.

Tavg drop. i Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event # .....:2=--____

Page 14 of _5;;..,;1;......_, Event

Description:

Rod Control Exercise/MRPI Failure Reactor Power -lowering

• Tavg CRS

• IF NOT, THEN go to Step (Step 3) Check Tavg -STABLE (Step 4) Verify Annunciator G-15, DUMP ARMED -(Step 5) Check Main Generator Load GREATER THAN 15 (Step 6) Establish Stable Plant Conditions: Tavg -TRENDING TO TREF PRZR pressure -TRENDING TO 2235 PSIG IN AUTO PRZR level -TRENDING PROGRAM IN AUTO MFW Regulation Valves -RESTORING S/G LEVEL TO 52% I N AUTO (Step 7) Check Control Rod Alignment: Verify all rods in affected group -i NOTE: Rod K-7 position WITHING +/- 12 STEPS OF cannot be determined ASSOCIATED GROUP STEP COUNTER CRS (Step 7 RNO) Refer to ITS Section NOTE: The CRS will evaluate Technical Specifications. (Step 8) Check QPTR -LESS THAN 1.02 NOTE: Since a Rod has NOT dropped, QPTR will NOT be > 1.02.

Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event # ____ Page 15 of

-Event

Description:

Rod Control Exercise/MRPI Failure (Step 9) Verify All Individual Rod Indication Per Bank MRPI system -NO MRPI MRPI system -NOT PROBLEMS WITH MRPI THAT COULD RENDER POSITION INDICATION (Step 9 RNO) Perform the following: Refer to ITS section 3.1.7 required Consult Reactor Engineer and plant . NOTE: The CRS may notify staff to evaluate MRPI and to the WCC/I&C/RE.

perform flux map per ITS. Booth Instructor:

as WCCSfI&C/RE, acknowledge.

CRS

• Go to Step 11 (Step 11) Verify Affected Group Step Counters Operable: Affected bank group step movement -CONSISTENT MRPO TRANSITIONS affected bank using PT-1, CONTROL Group step counters for affected bank WITHIN 1 STEP OF EACH (Step 12) Check Reactor Conditions: Rod insertion limit NOTE: Extinguished EXTINGUISHED NIS PR .6.1-WITHIN DESIRED NOTE: Normal .6.1 values OPERATING BAND (Step 13) Evaluated Plant Conditions: Rod/MRPI malfunction

-REPAIRED . NOTE: The MRPI problem will I NOT be repaired.

Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event # _2______ Page 16 of _5;;.,1;"""-11 Event

Description:

Rod Control Exercise/MRPI Failure (Step 13 RNO) Return to Step 8 TECHNICAL SPECIFICATION 3.1.7, ROD POSITION INDICATION LCO 3.1.7 The Microprocessor Rod Indication (MRPI) System and the Position Indication System shall i OPERABLE. APPLICABILITY:

MODES 1, MODE 2 Kett 2: ACTIONS CONDITION REQUIRED COMPLETION ACTION TIME A. One A.1 Verify the Once per per group position of inoperable the for one or more groups.

position indicators by using movable incore detectors OR 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> A.2 Reduce THERMAL POWER to S50% RTP TECHNICAL SPECIFICATION 3.1.4, ROD GROUP ALIGNMENT LIMITS CRS LCO 3.1.4 All shutdown and control . shall be OPERABLE, with all . indicated rod positions within 12 steps their group step counter demand position.

Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event # 2 Page 17 of _5.;;.,1;""--1

-Event

Description:

Rod Control Exercise/MRPI Failure APPLICABILITY:

MODES 1, MODE 2 with Kef!;:: 1.0. ACTIONS CONDITION REQUIRED COMPLETION ACTION TIME B. One rod not B.1.1 Verify SDM 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> within is within the alignment limits limits. specified in the COLR. OR 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. 1.2 Initiate boration to restore SDM to within limit. AND B.2 Reduce 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> THERMAL POWER to S75% RTP. AND B.3 Verify SDM is within the limits Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> specified in the COLR. AND 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B.4 Perform SR 3.2.1.1. AND 8.5 Perform SR 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 3.2.2,1. AND B.6 Re-evaluate safety 5 days analysis and confirm results remain valid for duration of operation under these conditions.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event # ...=.2_____ Page 18 of Event

Description:

Rod Control Exercise/MRPI Failure At the discretion of the Lead Examiner move to Event #3.

i Appendix Operator Action Form ES-D-2 OpTest No.: N10-1 Scenario # 4 Event # _3;:;..-____

Page 19 of ....;5;..;.,1--11

-Event

Description:

Pressurizer Level (L T -428) Fails HIGH . Next, Pressurizer Level Transmitter L T-428 will fail High. The operator will respond in accordance with AR-F-4, PRESSURIZER LEVEL DEVIATION

-5 NORMAL +5, and F-28, PRESSURIZER HI LEVEL CHANNEL ALERT 87%, and enter ER-INST.1, Reactor. Protection Bistable Defeat After Instrumentation Loop Failure. The operator will address \ Technical Specification 3.3.1, Reactor Trip System Instrumentation, and 3.3.3, Post Accident Monitoring Instrumentation. . SIM DRIVER Instructions:

Operate Trigger #2 (PZR03C (100)) Indications Available: MCB Annunciator F-4, PRESSURIZER LEVEL DEVIATION

-5 NORMAL +5 MCB Annunciator F-28, PRESSURIZER HI LEVEL CHANNEL ALERT 87% LI-428 goes upscale high Backup Pzr Heaters Char in Pum A Seed Control oes to 0 Out Booth Instructor:

call as the WCCS and indicate that the Electricians have investigated the B Condensate Pump Trip. They believe that the Pump Breaker Trip was caused by spurious actuation of the Condensate Pump Motor Breaker overcurrent device. It has been reset, and the Pump can be restored to service. (NOTE: Sim Instructor ensure that CND14 = 1 (Full Open). If the B Condensate Pump is in PULL STOP, the CRS will direct that the Pump be placed in AUTO. AR-F-4, PRESSURIZER LEVEL DEVIATION

-5 NORMAL +5 HCO (Step 1) Perform a channel check.

• NOTE: L T -428 will indicate high compared to the others. HCO (Step 2) Verify Backup Heaters on at + 5%

Appendix D Operator Action Form ES-D-2 . Op Test No.: N10-1 Scenario # 4 Event # 3 Page 20 of 51 Event

Description:

Pressurizer Level (L T -428) Fails HIGH HCO * (Step 3) Check charging pump speed and , NOTE: Auto pump has controls.

! reduced to MIN speed HCO (Step 4) Check Letdown in service. HCO . (Step 5) Control Charging and Letdown as necessary to control level. CRS (Step 6) Go to the appropriate procedure:

• AP-RCS.1 for RCS leak

• ER-INST.1 for failed channel AR-F-28, PRESSURIZER HIGH LEVEL CHANNEL 87% HCO (Step 1) Perform a channel NOTE: L T-428 will indicate high compared to the others. HCO (Step 2) Check charging and letdown CRS (Step 3) For failed channel go to ER-INST.1 NOTE: The CRS will go to ER-. INST.1. ER-INST.1, REACTOR PROTECTION BISTABLE DEFEAT INSTRUMENTATION LOOP HCOI (Step 4.1) Identify the failed instrument CO channel by observation of the bistable status i light board, MCB annunciators, and the metering HCOI i (Step 4.2) WHEN a failed instrument loop NOTE: The CRS will CO andlor channel has been identified, THEN determine that PRZR Level refer to the appropriate section of this Channel Failures -Section procedure list below: 4.5, should be addressed.

i Appendix 0 Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event # 3 Page 21 of 51 Event

Description:

Pressurizer Level (L T -428) Fails HIGH HCO (Step 4.5.1) IF PRZR low level heater cut out . has occurred, THEN .... HCO (Step 4.5.2) If letdown isolation valve, 427 has closed, THEN ... CRS (Step 4.5.3) REFER to the appropriate . attachment for defeat of the associated control functions.

• PRZR LEVEL Lt-428 BLUE CHANNEL NOTE: The Instrument failed HIGH . NOTE: Normal Letdown did NOT isolate. NOTE: The CRS will determine that BLUE CHANNEL PRZR Level 428, should be addressed.

NOTE: The CRS will hand this off to the CO, who will coordinate with the HCO. ER-INST.1, REACTOR PROTECTION BISTABLE DEFEAT INSTRUMENTATION LOOP BLUE CHANNEL ATTACHMENT PRZR LEVEL CO (Step 1) In the PLP PRESS AND rack, check the PRZR level defeat Ll428A IF Ll428A is in NORMAL, THEN place 428A to DEFEAT-3. (Step 2) In the (BLUE) B-1 CHANNEL 3 rack, PLACE the proving switch 428, CHANNEL 3 LEVEL TRIP to DEFEAT (UP). Proving light will be OFF since the channel failed HIGH (87%). (Step 3) PLACE PRZR LEVEL RECORDER transfer switch (MCB) to position 427. (Step 4) Verify the bistable status light listed above is lit. NOTE: The HCO will take MANUAL control of Charging Pump Speed.

Appendix Operator Action Form ES-D-2 Op Test No.: N10*1 Scenario # 4 Event # 3 Page 22 of 51-. Event

Description:

Pressurizer Level (LT-428) Fails HIGH IF the bistable status light above is NOT NOTE: The Bistable status lit, THEN ...... light is LIT. (Step 5) REMOVE the PRZR level channel from the PPCS, by performing the following: On the "Sub/Delete/Restore" display Select Point ID L0428 Turn "OFF" scan processing Select "Change" (Step 6) GO TO Step 4.5.4 ER-INST.1, REACTOR PROTECTION BISTABLE DEFEAT INSTRUMENTATION LOOP (Step 4.5.4) Reset PRZR heaters breakers NOTE: Not necessary as necessary. (Step 4.5.5) Restore normal letdown as NOTE: Normal Letdown did follows, if desired. NOT isolate. (Step 4.5.6) WHEN PRZR level is restored to NOTE: The HCO will place

• normal, THEN place an operating Charging Pump Speed back in pump controller in AUTO. AUTO. (Step 4.5.7) Check the following ITS Sections for LCOs: Section 3.3.1, Table 3.3.1-1, Function 8 Section 3.3.3, Table 3.3.3-1, Function 2 Section . NOTE: PZR heaters

• unaffected CRS (Step 4.5.8) GO TO Step 4.15.

Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event # _3.......____ Page 23 of

-Event

Description:

Pressurizer Level (L T -428) Fails HIGH (Step 4.15.1) IF necessary, verify an operable channel is selected for the affected recorder. (Step 4.15.2) Verify the following systems in AUTO if desired:

• Rod Control CO

• Turbine EH control CO

• PRZR Pressure control o HC431K o PRZR spray valves o PRZR heaters HCO

• PRZR level control CO

• Steam Dump (unless 1 st stage pressure failed) CO

• MFW control CO

• S/G Atmos Relief Valve Control (Step 4.15.3) Notifications to the following people will be made by the Shift Manager

• Operations Supervision

• STA

• Maintenance (Step 4.15.4) During normal working hours, Maintenance personnel shall be notified immediately of the problem. NOTE: Rods may be in . Manual from previous MRPI failure. NOTE: IF NOT already done, the HCO will place Charging Pump Speed back in AUTO. NOTE: The CRS may notify the SM/STA. Booth Instructor:

as SM/STA, acknowledge.

NOTE: The CRS may notify the WCCII&C. Booth Instructor:

as WCCS/I&C, acknowledge.

Appendix Operator Action Form ES-O-2 Op Test No.: N10-1 Scenario # 4 Event # _3;;.....____ Page 24 of Event

Description:

Pressurizer Level (L T -428) Fails HIGH (Step 4.15.5) During back shifts Maintenance personnel will be called in. HOWEVER, the

• Shift Manager may defer calling people in, IF repairs may be deferred to the next TECHNICAL SPECIFICATION 3.3.1, REACTOR TRIP SYSTEM (RTS) INSTRUMENTATION LCO 3.3.1 The RTS instrumentation for Function in Table 3.3.1-1 shall OPERABLE. (Function APPLICABILITY:

According to Table 3.3.1-1 ACTIONS CONDITION REQUIRED COMPLETION ACTION TIME One or more A.1 Enter the ,Immediately Functions Condition

! with one referenced channel in Table inoperable.

3.3.1-1 for the channel(s)

I 0.1 Place 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> channel in trip. TECHNICAL SPECIFICATION 3.3.3, POST-ACCIDENT MONITORING LCO 3.3.3 The PAM instrumentation for Function in Table 3.3.3-1 shall Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event #

Page 25 of 51 Event

Description:

Pressurizer Level (L T -428) Fails HIGH ACTIONS CONDITION REQUIRED ACTION One or more A.1 Restore 30 Functions with one channel required channel At the discretion of the Lead Examiner move to Event #4.

Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event # _4______ Page of _5_1---11 Event

Description:

Heater Drain Pump A trips/Rapid Downpower After this, the A Heater Drain Pump will trip. The operator will respond in accordance . with AR-G-25, MOTOR OFF CTR SECT PMPS EXCEPT MAIN & AUX FEED PMPS, . . and/or AR-H-17, FEED PUMP NET POSITIVE SUCTION HEAD, and enter AP-FW.1, Abnormal MFW Pump Flow or NPSH. The operator will reduce load to 70% in i accordance with AP-TURB.5, Rapid Load Reduction . . SIM DRIVER Instructions:

Operate Trigger #3 (HTR02A) Indications Available: MCB Annunciator H-17, FEED PUMP NET POSITIVE SUCTION HEAD MCB Annunciator G-8, 480V MOTOR OVERLOAD MCB Annunciator G-25, MOTOR OFF CTR SECT PMPS EXCEPT MAIN & AUX FEED A Heater Drain Pump Green and White breaker status light are LIT. Condensate bypass valve OPEN PPCS Pri-1 alarm "CALPQ1" forpower >100% I . NOTE: The crew will probably i enter AP-FW.1 directly.

AR-G-25, MOTOR OFF CTR SECT PMPS EXCEPT MAIN & AUX FEED PMPS co (Step 1) Determine which pump has tripped (white light at switch will be lit). CO (Step 2) Verify standby pump Auto starts OR start standby pump, IF required.

CRS (Step 3) IF all charging pump(s) tripped, THEN .... CRS (Step 4) Notify Electrician CRS (Step 5) Refer to ITS LCO 3.7.5. NOTE: The CO will determine that the A Heater Drain Pump has tripped. NOTE: HOT pump does NOT have standby pump to start NOTE: The Charging Pumps have NOT tripped. CRS (Step 6) Refer to TRM TR 3.1.1 and 3.1.2.

Appendix Operator Action Form ES-D-2 i Op Test No.: N10-1 Scenario # 4 Event # _4.;.......

____ Page of _5....1___-1 Event

Description:

Heater Drain Pump A trips/Rapid Downpower

, AR-H-17 FEED PUMP NET POSITIVE SUCTION HEAD i CO (Step 1) CHECK Feedwater Pump parameters for proper parameter indication: Suction flow (FI-2004 & FI-2005) (PPCS I F2004 and F2005) J Suction press (PI-2044 & (PPCS P2044 and J i. Discharge press (PI-2046 & PI-2047) . (PPCS P2046 and j J i NPSH margin (PPCS NPMRMFDA and* NPMRMFPB)i I CRS (Step 2) IF Feed Pump net positive head is confirmed not to exist, THEN go i AP-FW.1, ABNORMAL MRW PUMP ON I I NOTE: The CRS will go to I FW.1.I I AP-FW.1, ABNORMAL MFW PUMP FLOW OR NPSH i I CO (Step 1) Check MRW Requirements:

• Power -GREATER THAN 50% Both MRW pumps -RUNNING i i CRS Go to Step 3* I I CO (Step 3) Check S/G Status I MFW flows -GREATER THAN I STEAM FLOWS I S/G levels stabilizing or returning to program i Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event # _________

Page 28 of 51 Event

Description:

Heater Drain Pump A trips/Rapid Downpower (Step 4) Verify At Least 2 Condensate Pumps -RUNNING CO (Step 5) Verify 80th HOT Pumps -RUNNING (Step 5 RNO) IF greater than 70 % power , and one HOT Pump has tripped, THEN reduce power to less than 70%. IF both HOT pumps have tripped, THEN reduce power to less than 50%. (Refer to AP-TURB.5, RAPID LOAD REDUCTION)

NOTE: The B Condensate Pump may automatically START. NOTE: The A Heater Drain Pump has tripped. NOTE: The CRS will go to TURB.S. AP-TURB.S, RAPID LOAD REDUCTION NOTE: The CO may notify the RG&E EGC, about the intent to reduce power level. Booth Instructor:

as RG&E EGC, acknowledge.

• NOTE: The CO may notify the CENG Generation Dispatch.

Booth Instructor:

as CENG Generation Dispatch, acknowledge. (Step 1) Initiate Load Reduction I

• Verify rods in i (Step 1a RNO) Perform the following: Place rods to MANUAL NOTE: If the Rods are NOT in AUTO, the HCO may place the Rods in AUTO, or drive rods in MANUAL.

• Adjust Rods to match Tavg and Tref. i I CO

• Reduce turbine load in Auto as follows:

Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event # _4..;....____ Page 29 of Event

Description:

Heater Drain Pump A trips/Rapid Downpower Place Turbine EH Control in OPER PAN., IMP PRESS IN, if desired. Select desired rate on thumbwheel Reduce the setter to the desired load Depress the GO button NOTE: The CO will start the load decrease.

• Initiate boration at the rate determined in NOTE: The HCO will initiate a OPG-REACTIVITY-CALC.

boration. Place PRZR backup heaters switch (Step 2) Monitor RCS Tavg Tavg -GREATER THAN 545°F Tavg -LESS THAN 579°F i (Step 3) Adjust Boric Acid Addition Rate Necessary To (refer to Maintain rods above the insertion limit Match Tavg and Tref Compensate for Xenon HCO (*Step 4) Monitor PRZR . TRENDING TO 2235 PSIG IN (*Step 5) Monitor MFW Regulating Valves RESTORING S/G LEVEL TO 52% IN (*Step 6) Monitor PRZR level-TO PROGRAM IN AUTO (Step 7) check IA Available to CNMT IA pressure -GREATER THAN 60 PSIG Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event # _4..;......

____ Page 30 of 51 Event

Description:

Heater Drain Pump A trips/Rapid Downpower Instr Air to CNMT Isol Valve, AOV-5392 OPEN (*Step 8) Check Steam Dump Status: Annunciator G-15. STEAM Steam dump operating properly in AUTO (Step 9) Check Hotwell Level: Hotweillevel controller in AUTO Controller demand LESS THAN 60% Hotwellievel at setpoint (Step 10) Check If Condensate Pumps Should Be Condensate booster pumps -2 PUMPS RUNNING Verify the following: Trim valve controller set at 375 NOTE: These conditions will psig NOT be met. Trim valve, GREATER THAN 80% open Annunciator AA-17, COND BSTR PMP DISCH HI PRESS LIT CRS (Step 10b RNO) Go to Step 18 CRS (Step 18) Evaluate Plant Status Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event # _4.:.....____ Page 31 of 51 Event

Description:

Heater Drain Pump A trips/Rapid Downpower IF load was reduced more than 15% RTP in one hour, THEN notify RP to obtain primary samples required by ITS LCO 3.4.16

• Power stable at desired level (Step 18b RNO) IF power greater than 20% and further reduction is required, THEN continue load reduction and return to Step 2. NOTE: The Load reduction will be =30%. NOTE: The CRS may notify the RP. Booth Instructor:

as RP, acknowledge.

NOTE: If NOT at the desired level, the CRS will loop back to Step 2, and THEN go to Step 19 when at 340 MWe. At the discretion of the Lead Examiner move to Event #5.

i Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event # 5 Page 32 of ...,;5;..;.1---1

Event

Description:

B SG ARV Controller (AOV-3410) fails in AUTO During the downpower, the B Steam Generator ARV (AOV-3410)

Controller will fail in Auto such that the valve goes fully Open. The operator will respond in accordance with A-503.1, Emergency and Abnormal Operating Procedures Users Guide, and close the valve manually.

SIM DRIVER Instructions:

Operate Trigger #4 (STM04C (100>> Indications Available:

• AOV-3410 red status light is LIT, Green status light is DARK.

• PPCS Alarm V341 0 OPEN

• B SG ARV Controller Red status light is LIT

• B SG ARV Controller output goes to 100% A-503.1, EMERGENCY AND ABNORMAL OPERATING PROCEDURES (Step 5) Actions are permitted to mitigate or NOTE: The CO will take compensate for equipment or controller Manual control of AOV-341 0 failure or to isolate leaks. Permitted actions and close the valve. include those actions necessary to take manual control and stabilize the affected parameters, or to isolate a leak. Examples include closing or isolating a failed open PORV, taking manual control of a failed FRV controller, etc. These deviations fall under . the Maintenance Rule. Therefore, 50.59 is not required.

At the discretion of the Lead Examiner move to Events #6-9.

Appendix Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # _6""",_7:.,0,8

..., _&..;..9__ Page of ..,.;5;..;,1--11 Event MSIVs Closel SG Safeties lift/fail OPEN (1 per SG)/ TDAFW Steam Supply Valves Fail to Open in AUTO/ A AFW Pump trips At a Turbine load of about 550 MWe, both MSIVs will inadvertently fail shut. The Reactor will trip, and the operator will enter E-O, Reactor Trip or Safety Injection.

On the plant trip one or more SG Safety Valves will open, and the lowest set valve will stick in the OPEN position on each SG. Additionally, the A AFW Pump will trip upon an automatic start signal, and the TDAFW Pump Steam Supply Valves will fail to open upon an automatic signal. The operator will be required to manually start the TDAFW Pump. to restore Secondary Heat Sink. The operator will transition from E-O to E-2, Faulted Steam Generator Isolation, and then to ECA-2.1, Uncontrolled Depressurization of All . . Steam Generators.

The scenario will terminate at Step 16 of ECA-2.1, after the crew I

• has correctly determined whether plant conditions meet SI Termination criteria.

I SIM DRIVER Instructions:

Operate Trigger #5 (STM05A1B, 0%) Indications Available: Both MSIVs Closed (green status lights are LIT, Red status lights are DARK) All Steam Dump Valves are full Open (Red status lights are LIT) RCS Pressure is increased to greater than 2335 psig. Both Pzr Spray valves full Open. Both Pzr PORVs full Open. At least three of the four Steam Generator Safety Valves on each Steam are E-O, REACTOR TRIP OR SAFETY INJECTION HCO (Step 1) Verify Reactor Trip: At least one train of reactor trip breakers -OPEN Neutron flux -LOWERING MRPI indicates -

ALL CONTROL AND SHUTDOWN RODS ON BOTTOM (Step 2) Verify Turbine Stop (Step 3) Verify Both Trains of AC Emergency i Busses Energized to at Least 440 VOL TS: i Appendix D Operator Action Form ES-D-2 OpTest No.: N10-1 Scenario # 4 Event # _6';;':'...;.7..:.., ,;;.:8,:..;&;.;..9;......_

Page of _5.;;.,1--'-11 Event

Description:

MSIVs Closel SG Safeties lift/fail OPEN (1 per SG)/ TDAFW Pump Steam Supply Valves Fail to Open in AUTOI A AFW Pump trips on Start Bus 16 and Bus 17 HCOI (Step 4) Check if SI is Actuated:

CO Any SI Annunciator

-LIT HCOI i (Step 4a RNO) IF any of the following CO

• conditions are met, THEN manually actuate SI and CI: PRZR pressure less than 1750 psig OR Steamline pressure less than 514 psig OR CNMT pressure greater than 4 psig OR

• SI sequencing started OR Operator determines SI required HCOI

• SI sequencing

-BOTH TRAINS CO STARTED. HCO (Step 5) Verify CNMT Spray Not Required: Annunciator A-27, CNMT EXTINGUISHED NOTE: The cooldown may NOT have created the conditions necessary to automatically actuate SI yet. NOTE: 0-19, PZR LOW PRESS, 1750 psig NOTE: With both Steam Generators depressurizing, RCS temperature and pressure will be lowering substantially, and SI will be required.

Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event # _6;;':"..;..7.:...;'

8;;..l.,.;;;.&.-.9

__ Page of

-Event MSIVs Closel SG Safeties lift/fail OPEN (1 per SG)/ TDAFW Pump Steam Supply Valves Fail to Open in AUTOI A AFW Pump trips on Start CNMT pressure -LESS THAN 28 PSIG (Step 6) Direct Operator to Perform A 27.0, ATTACHMENT AUTOMATIC NOTE: The CRS will hand off ATT-27.0 to either the HCO or the CO, and continue with the other operator in E-O. Examiner following operator performing ATT-27.0 continue below. Examiner following operator NOT performing ATT-27.0 continue at page 38. E-O, REACTOR TRIP OR SAFETY INJECTION . , ATTACHMENT 27 0 ATTACHMENT AUTOMATIC ACTION VERIFICATION I i I HCOI (Step 1) Verify SI and RHR Pumps Running: CO I

• All SI pumps -RUNNING i

• I Both RHR pumps -RUNNING I i HCOI (Step 2) Verify CNMT RECIRC Fans CO Running: All fans -RUNNING Charcoal filter dampers green lights -

I HCOI CO (Step 3) Check If Main Steamlines Should Be Isolated:

I

• Any MSIV -OPEN NOTE: Both MSIVs are Closed. I Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event # _6;;.,:*..;.,7.1.,;'

8;;.:.,* .;;.;.&..;;.9

__ Page of . Event MSIVs Close/ SG Safeties IiWfaii OPEN (1 per SG)/ TDAFW Pump Steam Supply Valves Fail to Open in AUTO/ A AFW Pump trips on Start HCOI (Step 4) Verify MFW Isolation:

CO MFW pumps -TRIPPED MFW Isolation valves -CLOSED SIG A. AOV-3995 SIG B. AOV-3994 SIG Blowdown and sample valves CLOSED HCOI (Step 5) Verify At Least Two SW Pumps CO RUNNING HCOI (Step 6) Verify CI and CVI: CO

• CI and CVI annunciators

-LIT Annunciator A-26. CNMT ISOLATION Annunciator A-25. CNMT VENTILATION ISOLATION Verify CI and CVI valve status lights BRIGHT CNMT RECIRC fan coolers SWoutiet valve status lights -BRIGHT FCV-4561 FCV-4562 Letdown orifice valves -CLOSED AOV-200A AOV-200B AOV-202 Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event #

8;;.:.,*.;;;;.&...;.9

__ Page of Event

Description:

MSIVs Close/ SG Safeties lift/fail OPEN (1 per SG)/ TDAFW Pump Steam Supply Valves Fail to Open in AUTO/ A AFW Pump trips on Start Verify CCW pump -AT LEAST HCOI (Step 8) Verify 51 and RHR Pump Flow: CO 51 flow indicators

-CHECK FOR FLOW RHR flow indicator

-CHECK HCOI (Step 7b RNO) IF RCS pressure less than NOTE: RCS Pressure will CO 150 psig manually ... remain> 150 psig. HCOI i (Step 9) Verify 51 Pump and RHR Pump CO . Emergency Alignment: RHR pump discharge to Rx deluge -MOV-852A MOV-852B Verify 51 pump C -RUNNING Verify 51 pump A -RUNNING Verify 51 pump B -RUNNING Verify 51 pump C discharge valves

• MOV-871A

• MOV-871B HCOI (Step 10) Verify CREATS Actuation:

CO At least one damper in each flowpath Normal Supply Air Appendix Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # .....;6;;,.i,.,..;,.7,:..;;8.,.;;;;.&.;.9

__ Page of _5;;;...1;""'1 Event MSIVs Close/ SG Safeties lift/fail OPEN (1 per SG)/ TDAFW Pump Steam Supply Valves Fail to Open in AUTO/ A AFW Pump trips on Start Lavatory Exhaust Air CREATS fans -BOTH RUNNING E-O, REACTOR TRIP OR SAFETY INJECTION Examiner following operator NOT performing ATT-27.0 continue HERE. (Step 7) Verify Both MDAFW Pumps NOTE: The A MDAFW Pump Running has failed, and the B MDAFW HCO Pump was OOS. (Step 7 RNO) Manually start both HCO IF less than 2 MDAFW pumps are NOTE: The CO/HCO will running, THEN manually open manually open the Steam TDAFW pump steam supply valves. Supply Valves to the TO AFW Pump. MOV-3S0SA MOV-3S04A (Step 8) Verify AFW Valve Alignment:

HCO AFW flow -INDICATED TO BOTH NOTE: TDAFW pump only S/G(s) AFW flow from each MDAFW pump LESS THAN 230 Appendix Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # 7:...;....9 __ Page of _5.;,..1_-11& ... Event MSIVs Closel SG Safeties lift/fail OPEN (1 per SG)/ TDAFW Pump Steam Supply Valves Fail to Open in AUTOI A AFW Pump trips on Start CRITICAL TASK Establish 230 gpm of AFW Flow to the Steam Generators before transition out of E-O, unless the transition is made to FR-H.1, and then before the RCPs are manually tripped to limit heat input to the RCS. Safety Significance:

Failure to establish a Secondary Heat Sink through the initiation of AFW flow unnecessarily challenges both the HEAT SINK and the CORE COOLING Critical Safety Functions.

Additionally, the FSAR Safety Analysis results are predicated on the assumption that at least one train of safeguards actuates and delivers a minimum amount of AFW flow to the Steam Generators.

Failure to perform this task, when the ability to do so exists, results in a violation of the Facility License Condition and places the plant in an unanalyzed condition. (*Step 9) Monitor Heat Sink: HCO Check SIG narrow range level GREATER THAN 7% [25% CNMT] in any COl (Step 9 RNO) Perform the following:

HCO Verify total AFW flow -GREATER THAN 200 GPM CRS

• Go to Step 10 (Step 10) Check If TDAFW Pump Can Both MDAFW pumps -RUNNING NOTE: The TDAFW Pump is the ONLY source of AFW flow. (Step 10 RNO) Go to Step 11 (Step 11) Check CCW Flow to RCP HCO Appendix Operator Action Form ES-D-2 Op Test No.: Event

Description:

COl HCO COl HCO COl HCO N10-1 Scenario # 4 Event # ...;;;.l6,:.,.;7

....,

Page of MSIVs Closel SG Safeties lift/fail OPEN (1 per SG)/ TDAFW Pump Steam Supply Valves Fail to Open in AUTO/ A AFW Pump trips on Start Annunciator A-7, RCP 1A RETURN HI TEMP OR LO Annunciator A-15, RCOP 1 B RETURN HI TEMP OR LOW FLOW

(*Step 12) Monitor RCS Tavg -STABLE NOTE: Because of the failed OR TRENDING TO 547°F open SG Safety Valves, RCS will be cooling (Step 12 RNO) If temperature less 547°F and lowering, THEN perform Stop dumping steam. Ensure reheater steam supply valves are I closed. IF cooldown continues, THEN total feed flow between 200 gpm to gpm until narrow range level greater 7% [25% adverse CNMT] in at least S/G. WHEN SIG level greater than 7% in SIG, THEN limit feed flow to required to maintain level in at least S/G. IF cooldown continues, THEN close both NOTE: Both MSIVs MSIVs. (Step 13 ) Check PRZR PORVs and Spray . Valves: PORVs -CLOSED Auxiliary Spray valves (AOV-296) CLOSED Check PRZR pressure -LESS 2260 Appendix Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Ellent # ...,;6;;.:,*..;,.7l.,.;:.

8;.:.*.;;;.&.;;;.9

__ Page of

-Ellent MSIVs Closel SG Safeties liftlfail OPEN (1 per SG)/ TDAFW Pump Steam Supply Valves Fail to Open in AUTOI A AFW Pump trips on Start Normal PRZR spray valves -CLOSED PCV-431A PCV-431B (Step 14) Monitor RCP Trip Criteria:

HCO ** RCP status -ANY RCP RUNNING SI pumps-AT LEAST TWO RUNNING RCS pressure minus maximum S/G NOTE: The RCP Trip Criteria pressure -LESS THAN 210 psi [240 psi will NOT be met. adverse CNMT] (Step 14c RNa) Go to Step 15. (Step 15) Check If SIG Secondary Side HCO Pressure in both SIGs -STABLE OR NOTE: Both SG Pressures are RISING decreasing uncontrollably. Pressure in both SIGs -GREATER THAN 110 PSIG CRS * (Step 15 RNa) IF any S/G pressure lowering in an uncontrolled manner OR depressurized, THEN go to E-2, STEAM GENERATOR ISOLATION, Step NOTE: The CRS will go to 2. E-2, FAULTED STEAM GENERATOR ISOLATION (Step 1) Check MSIVof Faulted S/G(s) -NOTE: Both MSIVs are CLOSED Closed. (Step 2) Check If Any S/G Side Is Appendix Operator Action Form ES-D-2 OpTest No.: N10-1 Scenario # 4 Event # _6;"l.*..;..7:..;.

8;.:.,.__ Page of Event

Description:

MSIVs Close! SG Safeties lift/fail OPEN (1 per SG)! TDAFW Pump Steam Supply Valves Fail to Open in AUTO! A AFW Pump trips on Start Check pressure in S/G A-STABLE OR NOTE: Both SG Pressures are RISING decreasing uncontrollably.

OR Check pressure in S/G B -STABLE OR RISING (Step 2 RNO) IF both S/G lowering in an uncontrolled manner, go to ECA-2.1, DEPRESSURIZATION OF BOTH GENERATORS.

Step NOTE: The CRS will go to ECA-2.1.

• ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS (Step 1) Check Secondary Verify all of the following: MSIVs -CLOSED NOTE: Both MSIVs are Closed. MFW flow control valves -CLOSED MFW regulating valves MFW bypass valves MFW pump discharge valves-CLOSED S/G blowdown and sample valves CLOSED TDAFW pump steam supply valves -NOTE: This cannot be PULL accomplished since the TO AFW Pump is the only source ofAFWflow. TDAFW pump flow control valves -NOTE: This cannot be accomplished since the TO AFW Pump is the only source ofAFWflow. S/G ARVs -CLOSED Appendix Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event # _6-.,....7_,.... 9__ Page .!:..-of _5;;;,.1;""-"'f

&.... Event MSIVs Close! SG Safeties liftlfail OPEN (1 per SG)/ TDAFW Pump Steam Supply Valves Fail to Open in AUTO/ A AFW Pump trips on Start Dispatch AO to locally isolate SIGs (Refer NOTE: The CRS will dispatch to ATT-10.0, ATTACHMENT FAULTED anAO. S/G) Booth Instructor:

as AO, i acknowledge. (Step 2) Control Feed Flow to Minimize (Step 2a) Check cooldown rate in RCS cold NOTE: The cooldown rate is legs -LESS THAN 100°F/HR i likely to be higher than . 100°F/HR. (Step 2a RNO) Lower feed flow to 50 gpm to NOTE: The CO will lower the each SIG and go to Step AFW flow rate to each SG to 50 gpm in an effort to control the cooldown rate. CRITICAL TASK (ECA-2.1 A) Control the AFW flowrate to 50 gpm per SG in order to minimize the RCS Cooldown rate before a severe challenge (Orange Path) develops to the integrity CSF. Safety Significance:

Failure to control the AFW flow rate to the SGs leads to an unnecessary and avoidable severe challenge to the integrity CSF. Also, failure to perform the Critical Task increases challenges to the SUBCRITICAUTY and CONTAINMENT Critical Safety Functions which otherwise would not occur. HCO (Step 2c) Check RCS hot leg temperature STABLE OR ST A . Actions taken in Step 2a RNO will reduce I AFW flow below the minimum required 200 gpm total needed to avoid entry into FR-H.1 conditions FR-H.1, RESPONSE to LOSS of SECONDARY HEAT SINK CAUTION before Step 1: If total feed flow is <200 gpm due to operator action, this procedure should not be performed Appendix Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # _6:;.:....:,.7:..;.

8*.,;;:.&..;;.9

__ Page of Event MSIVs Closel SG Safeties lift/fail OPEN (1 per SG)/ TDAFW Pump Steam Supply Valves Fail to Open in AUTOI A AFW Pump trips on Start

• CRS returns to ECA-2.1. Step ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS HCOI (Step 3) Monitor RCP Trip

• RCP status -ANY RCP RUNNING

• pumps -AT LEAST TWO RUNNING RCS pressure minus maximum S/G pressure -LESS THAN 210 psi [240 psi adverse CNMT] (Step 3c RNO) Go to Step 4 HCO (*Step 4) Monitor PRZR PORVs and Power to PORV block valves

.* PORVs-CLOSED Block valves -AT LEAST ONE OPEN HCOI . (Step 5) Check Secondary Radiation CO -Steamline radiation monitor (R-31 and R-i 32) Dispatch AO to locally check steam line radiation Request Chem Tech sample SIGs (Step 6) Reset SI Appendix Operator Action Form ES-D-2 Op Test No.: N10*1 Scenario # 4 Event # _6;;..l.,-.7

.... 9__ Page of __-11 , 8;.l.'.-&..-;;,.51 . Event MSIVs Close/ SG Safeties lift/fail OPEN (1 per SG)/ TDAFW Pump Steam Supply Valves Fail to Open in AUTOI A AFW Pump trips on Start (Step 7) Monitor If RHR Pumps Should . RHR pumps -ANY RUNNING IN.IECTION Check RCS Pressure: Pressure -GREATER THAN 300 psig [350 psig adverse CNMT] Pressure -STABLE OR RISING Stop RHR pumps and place in AUTO . NOTE: The HCO will STOP the RHR Pumps. (Step 8) Monitor If CNMT Spray Should Be . NOTE: Containment pressure Stopped: is normal. CNMT spray pumps -RUNNING CRS (Step 8a RNO) Go to Step 9 (Step 9) Check RWST Level -THAN (Step 10) Reset CI: Depress CI reset pushbutton Verify annunciator A-26. ISOLATION

-

CO i (Step 11) Verify Adequate SW Flow: Check at least two SW pumps Dispatch AO to establish normal NOTE: The CRS will dispatch shutdown alignment (Refer to ATT-17.0, anAO. ATTACHMENT SD-1) Booth Instructor:

as AO, acknowledge, and use Schedule file SD-1.sch.

Appendix Operator Action Form ES-D-2 Op Test No.: Nl0-1 Scenario # 4 Event # _6::;.:.*..;.7.:..;.

8**.;:;.&.;;.9

__ Page of Event MSIVs Close! SG Safeties lift/fail OPEN (1 per SG)! TDAFW Pump Steam Supply Valves Fail to Open in AUTOI A AFW Pump trips on Start (Step 12) Establish IA to CNMT: ** Verify non-safeguards busses energized

! from offsite power I

• Bus 13 normal feed -CLOSED I I OR

• Bus 15 normal feed -CLOSED i i I

• Verify SW isolation valves to turbine building -OPEN I ! I

• Verify adequate air compressor{s) I I RUNNING i

• Check IA supply:

• Pressure -GREATER THAN 60 I I PSIG I

• Pressure -STABLE OR RISING !

• Reset both trains of XV relays for IA to CNMT AOV-5392 I

• Verify IA to CNMT AOV-5392 -OPEN I I i I HCOI (Step 13) Check if SI ACCUMs Should Be CO Isolated:

• Both RCS hot leg temperatures

-LESS THAN 390°F ! I I i CRS (Step 13a RNO) Go to Step 14 CO (Step 14) Check Normal Power Available To i Charging Pumps: I

• Bus 14 normal feed breaker -CLOSED I

• Bus 16 normal feed breaker -CLOSED i ! HCO (Step 15) Check If Charging Flow Has Been Established:

Appendix Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event #

• .;;.8.:..;&;;..9;....-_

Page of Event MSIVs Closel SG Safeties lift/fail OPEN (1 per SG)I TDAFW Pump Steam Supply Valves Fail to Open in AUTOI A AFW Pump trips on Start

• Align charging pump suction to RWST: LCV-112B -OPEN CLOSED Start charging pumps as necessary and adjust charging flow to restore PRZR level HCO (*Step 16) Monitor SI Termination Criteria: SI pumps -ANY RUNNING Check RCS pressure: Pressure -GREATER THAN 1650 psig [1650 psig adverse CNMT] (Step 16b RNO) DO NOT stop SI pumps . Perform the HCO Energize PRZR heaters and PRZR spray to stabilized pressure greater than 1650 [1650 psig adverse CRS Return to Step 2 Terminate the Exam at the discretion of the Lead Examiner UNIT STATUS: Power Level: 100% RCS [BJ 1145 ppm BAST [B]: 17000 ppm Power The plant has been at 100% power Core Burnup: 10000 MWD/MTU (MOL), for 172 days. INFORMATION NEEDED TO ASSLIME TO SHIFT: The Plant is at 100% power (MOL). Immediately after turnover, it is requested that the crew swap Condensate Pumps in preparation for taking C Condensate Pump 005 for scheduled maintenance. After the Condensate Pump swap, the crew should complete the routine Rod Control surveillance on Control Bank D. The following equipment is Out-Of-Service: The B AFW Pump is 005 for Bearing Replacement.

LCD 3.7.5 entered 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago.

---

A-52.4 Equipment Date Time Reason Req uired Actions Required Required Action not met Completion Daterrime B MDAFWPump

_1-./10 Bearing ITS 3.7.5 (Current ITS 3.7.5 Replacement Enter Co dition B dateltime

+ 6 Enter Condition G days) Required Action B.1: Restore Required Action G.1: Be in Mode 3 MDAFW Train to OPERABLE in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Status in 7 days AND Required Action G.2: Be in Mode 4 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Mark Up Attachment 1 of STP-O-1 as follows, and provide to crew on Turnover:

Attachment 1 Rod Position SHUTDOWN INITIAL TRANSITION BANK POSITION POSITION PPCS STEP MRPI RPI CTR CRT E-3 1) 212 216 (GRP 1) 224 224 1-11 (GRP 1) 224 224 212 212 216 224 224 K-5 1) 2 216 224 1-3 (GRP 2) 224 224 212 212 215 224 224 C-5 (GRP 2) 224 224 21 5 224 E-11 2) 224 224 212 212 215 224 224 224 212 212 215 224 STEP COUNTER Attachment 1 Rod Position TRANSITION FINAL POSITION POSITION POSITION MRPI PPCS MRPI STEP MRPI CRT RPI CRT CTR CRT 0-4 (GRP 1) 224 224 212 216 224 G-7 (GRP 1) 224 224 212 212 216 224 J-10 (GRP 1) 224 224 212 212 216 J-4 2) 224 212 212 216 224 224 J-4 (GRP 2) 224 224 212 212 216 224 224 P COUNTER Attachment Rod CONTROL INITIAL TRANSITION FINAL BANK A POSITION POSITION POSITION MRPI PPCS MRPI PPCS CRT RPI CRT RPI F-2 (GRP 1) 224 224 200 224 B..a (GRP 224 224 200 204 216 224 224

• H-12 (GRP 224 224 200 204 216 224 224 L-6 1) 224 224 200 204 216 224 224 203 215 224 224 B-6 (GRP 2) 224 22 200 203 215 224 224 F-12 (GRP 2) 224 200 203 215 224 224 L..a (GRP 2) 224 224 200 203 215 224 224 STEP RECORD position of STEP COUNTER EACH rod WHEN it COUNTER Attachment Rod INITIAL FINAL POSITION POSITION POSITION MRPI PPCS MRPI STEP MRPI PPCS CRT RPI CRT CTR CRT RPI 1-17 (GRP 1) 225 212 21 225 225 G-5 (GRP 2) 225 225 212 212 216 E-7 (GRP 1) 225 225 212 212 216 225 225 G-9 (GRP 2) 225 225 212 212 216 225 225 STEP RECORD position of STEP COUNTER EACH rod WHEN it COUNTER