Text

Draft Operating Exam (Sections a, B, and C) (Folder 2)
	ML101720564
Person / Time
Site:	Ginna
Issue date:	05/21/2010
From:	Todd Fish; Operations Branch I
To:	Geckle M; 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
	ES-C-1, TAC U01766
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{{#Wiki_filter:Appendix C Job Performance Measure Form ES-C-1 Facility: Ginna Task No.: Task

Title:

Review a Critical Rod Position JPM No.: 2010 GINNA NRC JPM Calculation SA-1 KIA

Reference:

2.1.25 (3.9/ 4.2) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: x Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions:

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 Task Standard: Magnitude of errors in the Critical Rod Position calculation determined and all critical tasks evaluated as satisfactory.

Required Materials: Calculator Nomograph Tables General

References:

0-1.2.2, Critical Rod Position Calculation, Rev. 06600 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 Initiating Cue: The Shift Manager directs you to perform Step 6.10.2 of 0-1.2.2.

Time Critical Task: No Validation Time: 2010 GINNA NRC JPM SA-1, Revision 7 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 2 of 6 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a ...J) Start Time: _ _ __ 0-1.2.2 Performance Step: 1 Reviews 0-1.2.2 Standard:

Verifies each step has the required information and is initialed or signed
Verifies each recorded value is within the allowable range EXAMINER CUE: Hand the Candidate the marked up copy of 0-1.2.2 EXAMINER NOTE: 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. If the applicant stops after the first error has been identified, instruct him to complete the review of the entire procedure and to make any corrections on a blank 0-1.2.2 (hand him one at the identification of the first error) and then return both copies of 0-1.2.2 to the examiner when the review is complete. 0-1.2.2, Step 6.2.2 ...J Performance Step: 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:

1. 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

2. From the PCNDR.

                                      *      +         pcm Standard:

Verifies Control Rod worth is 129 (+1- 1) pcm vice 212 pcm.

                                 *    <...J) Records 129 (+J.. 1 pcm) in Step 6.2.2 EXAMINER NOTE:                 This error is derived from the Reactor Engineer using an EOl table vice a MOL table.

EXAMINER NOTE: 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 7 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION 0-1.2, step 6.4 Performance Step: 3 Boron Reactivity ...J Standard:

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

                        *    (...J) Recalculates and records in step 6.4.5 reactivity worth due to boron concentration change.

Candidates Value: _ _ _ pcm Allowable Values: -2452 to -2489 pcm EXAMINER NOTE: 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. EXAMINER NOTE: 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 -6.1 to -6.8. If the Candidate uses 6.1 they will get -2452 pcm and if they use -6.8 they will get 2489 pcm. 0-1.2.2, Step 6.6 Performance Step: 4 Total Reactivity Change Standard: Recalculates and records in step 6.6.6 the total reactivity change. Candidates Value: pcm Allowable Value: 815 pcm to 852 pcm EXAMINER NOTE: 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 7 NUREG 1021, Revision 9, Supplement 1

Appendix C j:>f 6 PERFORMANCE INFORMATION 0-1.2.2, Step 6.7.1 ,j Performance Step: 5 Estimated Critical Rod Position Standard: 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 EXAMINER NOTE: The acceptable range is based on the allowable values in step 6.6.6 (Total Reactivity Change). 0-1.2.2, Step 6.9 ,j Performance Step: 6 500 pcm Control Rod Bank Position Standard:

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 EXAMINER NOTE: The acceptable range as 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.

Terminating Cue: When the Candidate returns the procedure: Evaluation on the JPM is complete Stop Time: _ _ __ 2010 GINNA NRC JPM SA-1, Revision 7 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2010 GINNA NRC ,-'PM 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 7 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 I:lf 6 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

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 INITIATING CUE: The Shift Manager directs you to perform Step 6.10.2 of 0-1.2.2.

2010 GINNA NRC JPM SA-1, Revision 7 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Facility: Ginna Task No.: Task

Title:

Perform the Shift Manager Review JPM No.: 2010 GINNA NRC JPM of the 0-6.13, DAILY SA-2 SURVEILLANCE LOG KIA

Reference:

2.1.18 (3.6/3.8) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: x Classroom X Simulator - - - Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions:

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 H-13
SI Header Pressure is outside the acceptable boundaries.

Engineering has been informed and is 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.

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:

0-6.13, Daily Surveillance Log, Rev. 17400
CNG-OP-3.01-1000, Reactivity Management, Rev. 00501
Two consecutive RCS chemistry reports with RCS Boron concentration.

2010 GINNA NRC JPM SA-2, Revision 6 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Workshl~et

Technical Requirements Manual, Revision 39, TR-3.1.1
Control Room Curve Book.
P&ID 33013-1261, Revision 38
P&ID 33013-1265, Sheet 2, Revision 23.

Initiating Cue: You are the Shift Manager on the day shift. Review 0-6.13, DAI LY SURVEILLANCE LOG - ATIACHMENT 1, Modes 1, 2, and 3. Assume all other equipment is operating normally. Time Critical Task: No Validation Time: 21 Minutes 2010 GINNA NRC JPM SA-2, Revision 6 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: _ _ __ 0*6.13, Daily Surveillance Log, ATTACHMENT 1, MODES 1, 2, AND 3. Performance Step: 1 Reviews 0-6.13, Daily Surveillance Log, ATTACHMENT 1, MODES 1, 2, AND 3 Standard:

Verifies each initial block is filled and initialed
Verifies each recorded value is within the allowable range EXAMINER NOTE: Only values outside the allowable range are included in this JPM. Values outside the allowable range can be identified in any order. If the applicant stops after the first error has been identified, instruct him complete the review of the entire log and then return it to the examiner.

0-6.13, Daily Surveillance Log, ATTACHMENT 1, MODES 1, 2, AND 3, Boric Acid Tank Levels Performance Step: 2 Per Step 6.4.2.2 Standard:

Identifies both Boric Acid Tank Levels are less than 83%
Refers to Step 6.4.2.2 EXAMINER NOTE: Performance Steps 2 and 5 are associated with the BAST tank found less than the minimum requirement.

2010 GINNA NRC JPM SA-2, Revision 6 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 10 Form ES-C-1 PERFORMANCE INFORMATION 0-6.13, Daily Surveillance Log, Step 6.4.2.2 ,f Performance Step: 3 VERIFY inservice BASTs meet the Minimum VolumelTemperature concentration requirements of TRM Table 3.1.1-1 using the most current BAST samples. Standard:

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

                        *    (,f) Determines the number of gallons in the BAST using the curve book.

Candidate Value: ____ Gallons Allowable Values: 2160 gallons to 2964 gallons

                        *    (,f) 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 EXAMINER CUE: 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.

EXAMINER NOTE: 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 30%, for both BASTs, the Candidate will calculate 2964 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 2160 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. EXAMINER NOTE: 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 6 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 10 Form ES-C-1 PERFORMANCE INFORMATION Technical Reference Manual, Revision 39, TSR 3.1.1.2 Performance Step: 4 - NOTE-Only required to be performed when complying with TR 3.1.1.b. Verify boric acid storage tank level is within limit. Standard:

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 Comments:

Technical Reference Manual, Revision 39, TR 3.1.1 .y Performance Step: 5 Two boron injection subsystems shall be OPERABLE with each subsystem containing olne charging pump and either a or b below:

a. A flowpath from the RWST; or

b. 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.

Standard: Enters TR 3.1.1! Condition A and E: Initiates action to restore at least one boron injection subsystem to OPERABLE status. EXAMINER CUE: 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. When the Candidate indicates that the plant needs to take action for the TRM violation, cue them to "The crew will take the appropriate action for the inoperable BAST, proceed with the review and inform me when the review is complete." 2010 GINNA NRC JPM SA-2, Revision 6 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 10 Form ES-C-1 PERFORMANCE INFORMATION 0-6.13, Daily Surveillance Log, ATTACHMENT 1, MODES 1, 2, AND 3, SI Accumulator ."f Performance Step: 6 SI Accumulator 1A11B Maintain >730 and <760 Standard:

Identifies SI Accumulator pressure is less than 730 PSIG
Refers to Step 6.2.14

                        * (."f) Enters LCO 3.5.1, Accumulators - Condition B; restore the Accumulator to operable status within 24 hours EXAMINER CUE:        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. When the Candidate indicates that the plant needs to take action for the Technical Specification violation, cue them to uThe crew will take the appropriate action for the inoperable SI Accumulator, proceed with the review and inform me when the review is complete."

0-6.13, Daily Surveillance Log, ATTACHMENT 1, MODES 1, 2, AND 3, RCS Boron Changes < 15 ppm Performance Step: 7 RCS Boron Changes <15 ppm (CNG-OP-3.01-1000) Standard:

Identifies RCS Boron Concentration has changed by greater than 15 ppm.
Refers to CNG-OP-3.01-1000 EXAMINER NOTE: JPM Performance Steps 8 and 9 are associated with the Reactivity Anomaly (CNG-OP-3.01-1 000).

2010 GINNA NRC JPM SA-2, Revision 6 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 10 Form ES-C-1 PERFORMANCE INFORMATION CNG-OP-3.01-1000, Attachment 3, Step 7.a. Procedure Note 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. Procedure Note 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. ,J Performance Step: 8 a. 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 anailysis be repeated.

Standard:

Compares last two RCS boron samples, determines they are 17 ppm apart.

                        *    (,J) Directs Chemistry to repeat the RCS boron analysis.

EXAMINER CUE: 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 6/20 and 6/19 Chemistry Data Sheets. EXAMINER CUE: When the Candidate directs Chemistry to repeat the RCS boron analysis, provide a repeat back. EXAMINER NOTE: 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 6 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 10 Form ES-C-1 PERFORMANCE INFORMATION CNG-OP-3.01-1000, Attachment 3, Step 7.b. " Performance Step: 9 Upon notification of 15 ppm limit being exceeded the SM will perform the following: (1) Initiate a CR Standard: Specifies that a CR must be submitted EXAMINER CUE: The Condition Report has been submitted. EXAMINER CUE: After the Candidate submits the Condition Report, inform them "The General Supervisor - Shift Operations will complete Step 7.b. Complete the review of 0-6-13 and inform me when you are complete." Terminating Cue: After the applicant returns the log: Evaluation on this ..IPM is complete. Stop Time: _ _ __ 2010 GINNA NRC JPM SA-2, Revision 6 NUREG 1021, Revision 9, Supplement 1

Appendix 9 10 VERIFICATION OF COMPLETION Job Performance Measure No.: 2010 GINNA NRC JPM SA-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 SA-2, Revision 6 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 10 of 10 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

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 H 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.

INITIATING CUE: 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 6 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Facility: Ginna Task No.: Task

Title:

Perform a Safety Function JPM No.: 2010 GINNA NRC JPM Determination SA-3 KIA

Reference:

2.2.37 (3.6/4.6) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: x Classroom X Simulator --_. Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions:

The Plant is stable at 100% power.
Date: 6/2112010
Time: 1210
The following equipment is currently Out of Service:

o D Service Water Pump (LCO 3.7.8, Condition A was entered today at 1000 and all necessary paperwork has been completed.) o 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.) o 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.

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 108, Rev. 55 Handouts: Perform in a location with the following available:

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

Appendix C Job Performance Measure Form ES-C-1

Clean copies of A-52.4, Control of Limiting Conditions for Operating Equipment, Rev. 13900
Clean copies of A-52,3, Safety Function Determination Program, Rev. 5
Clean copies Technical Specifications Amendment 108, Rev. 55 Initiating Cue: Fill out an A-52.4, Attachment 1, through step 3.2.6, for the given plant conditions.

Time Critical Task: No Validation Time: 12 minutes 2010 GINNA NRC JPM SA-3, Revision 9 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 11 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a ..J) Start Time: _ _ __ Technical Specifications Performance Step: 1 Reviews D Service Water Pump LCD Standard:

Determines the plant is in LCD 3.7.8, Service Water System, Condition A, with a 72 hour completion time.
Determines the plant has until 6/24/2010 at 1000 before having to complete Required Action A.1 EXAMINER NOTE: 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 Performance Step: 2 Reviews B Containment Recirculation Fan LCD Standard:

Determines the plant is in LCD 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 6125/2010 at 1200 before having to complete Required Action D.1.

Technical Specifications Performance Step: 3 Determines B1 Battery Charger LCD Standard:

Determines the plant is in LCD 3.8.9, ECCS - Distribution System - MODES 1 . 2, 3, and 4.
Determines the plant has 2 hours (6/21/2010 at 1400) before having to complete Required Action C.1 2010 GINNA NRC JPM SA-3, Revision 9 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 1 PERFORMANCE INFORMATION A-52.4, Attachment 1 Performance Step: 4 Completes Steps 3.2.1 through 3.2.3 of A-52.4, Attachment 1. Standard:

See attached KEY.
Proceeds to Step 3.2.4 EXAMINER CUE: The EIN for B1 Battery Charger is BYCB1 A-52.4, Attachment 1, Step 3.2.4 Performance Step: 5 Perform Loss of Safety Function Determination PER Attachment 2

Standard:

Proceeds to Attachment 2 Comments:

A-52.4, Attachment 2 Performance Step: 6 Step 1.0 Have any of the following supporting system LCOs been entered? YES/NO Standard:

Circles YES in Step 1.0
Initials to the right of LCOs 3.6.6,3.7.8 and 3.8.9
Proceeds to Step 2.0 EXAMINER NOTE: 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.

EXAMINER NOTE: For step one the candidate must realize three support system LCOs have bec:m entered: B Containment Recirculation Fan (3.6.6), D Service Water Pump (3.7.8) and the B1 Battery Charger (3.8.9). 2010 GINNA NRC JPIVI SA-3, Revision 9 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 11 Form ES-C-1 PERFORMANCE INFORMATION A*52.4, Attachment 2 Performance Step: 7 Step 2.0 Has only one (1) LCO been entered (Le., total # of LCOs in effect is only 1)? YES/NO Standard:

Circles NO in Step 2.0
Determines a loss of safety function evaluation is required
Proceeds to Step 3.0 EXAMINER NOTE: Since there are multiple LCOs entered and three of them are supporting system LCOs, there is a potential loss of safety function.

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

Appendix C Page 6 of 11 PERFORMANCE INFORMATION A-52.4, Attachment 2 or A-52.3 Performance Step: 8 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 Standard:

References either Attachment 2 of A-S2.4 or Table 1 of A-S2.3
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-S2.4 or Table 1 "Supported Systems LCO(s)" column of A-S2.3.
Circles YES in Step 3.0
Proceeds to Substep A) of Step 3.0 EXAMINER NOTE: The candidate can use either Attachment 2 of A-52.4 or Table 1 of A-52.3. Both sources have the same information.

EXAMINER NOTE: If the candidate uses Attachment 2 of A-52.4, they will use 3.8.9 (the LCO for B1 Battery Charger) across the top and 3.7.8 (LCO for 0 Service Water Pump) or 3.6.6 (the LCO for B Containment Recirculation Fan) on the left most column and find an "empty" box at both intersections indicating a potential loss of safety function. EXAMINER NOTE: If the candidate uses Table 1 of A-52.3, they will select 3.8.9 in the "Support System LCO #" column and look in the "Supported Systems l.COs" Column and find LCO 3.6.6 and LCO 3.7.8 indicating there is a potential loss of safety function. 2010 GINNA NRC JPM SA-3, Revision 9 INUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 11 Form ES-C-1 PERFORMANCE INFORMATION A-52.4, Attachment 2 or A-52.3 Performance Step: 9

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

A. 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. Standard:

Uses Table 1 of A-52.3 and determines cascading is not allowed for LCO 3.8.9
References LCO 3.8.9 and determines Conditions C is applicable.
Determines the plant must enter LCO 3.8.9, Required Actions C.1
Proceeds to Substep B.

Comment: 2010 GINNA NRC ~IPM SA-3, Revision 9 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 11 Form PERFORMANCE INFORMATION A-52.4, Attachment 2 and A-52.4, Attachment 1, Step 3.2.4 ,j 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 C of LCO 3.8.9 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.S.9 Required Action statement C 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 9 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 9 of 11 Form ES-C-1 PERFORMANCE INFORMATION A-52.4, Step 3.2.5 Performance Step: 11 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 D I yellow D I orange D I red D EOOS highest top level system status color: green D I yellow D I orange 0 I red D Standard:

Marks both "yellow" boxes in Step 3.2.5.8
Initials Step 3.2.5
Enters LCO 3.8.9, REiquired Actions A.1, B.1 and C.1 EXAMINER CUE: 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 .,j Performance Step: 12 REQUIRED ACTIONS: Standard:

Fills out the REQUIRED ACTIONS Table lAW the attached key EXAMINER NOTE: See the attached Key.

Terminating Cue: After the REQUIRED ACTION Table is completed: Evaluation on this JPM is complete. Stop Time: _ _ __ 2010 GINNA NRC JPM SA-3, Revision 9 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 10 of 11 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2010 GINNA NRC JPM SA-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 SA-3, Revision 9 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 11 of 11 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

The Plant is stable at 100% power.
Date: 6/21/2010
Time: 1210
The following equipment is currently Out of Service:

o D Service Water Pump (LCO 3.7.8, Condition A was entered today at '1000 and all necessary paperwork has been completed.) o 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.) o Battery Charger B for maintenance. It is expected to be returned to service 6/22/2010 at 1200.

At 1200 today Battery Charger B1 was taken out of service to due a ground.
Condition Report CR-201 0-006284 has been initiated for the B1 Battery Charger !~round.
The crew has taken the appropriate action to stabilize the plant.

INITIATING CUE: Fill out an A-52.4, Attachment 1, through step 3.2.6, for the given plant conditions. 2010 GINNA NRC JPM SA-3, Revision 9 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 1 of 9 Form ES-C-1 PERFORMANCE INFORMATION Facility: Ginna Task No.: Task

Title:

Respond to a Contaminated Injured ..IPM No.: 2010 GINNA NRC JPM Person SA-4 KIA

Reference:

2.3.14 (3.4/3.8) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: x Classroom X Simulator - - - Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions:

The Reactor is operating at 100% power, Steady-State, MOL.
The Shift Manager is outside the control room at a meeting with Plant Management.
Auxiliary Operator has called the Control Room to report:

o A Chemist has received serious steam burns while performing RCS sampling activities. o The sampling system has been stabilized and no radioactive releases are in progress. o The Chemist is in pain. Task Standard: All critical tasks evaluated as scltisfactory. Required Materials: None General

References:

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 Handouts:
A-7, Procedure for Handling Injuries/Medical Emergencies at Ginna Station, Rev. 10200 2010 GINNA NRC JPM SA-4, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 2 of9 Form ES-C-1 PERFORMANCE INFORMATION

CNG-NL-1.01-1004, REGULATORY REPORTING, Rev. 00300 Initiating Cue: You are the CRS. Respond to the report of an injured chemistry technician.

Time Critical Task: No Validation Time: 8 minutes 2010 GINNA NRC JPIVI SA-4, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 9 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a -1J Start Time: _ _ _ _' A-7, Step 3.3.5 Performance Step: 1

The Control Room will respond and notify the site Medical Emergency Response Team via the plant page, pager, and/or radio in accordance with Attachment 1.

Standard:

Proceeds to Attachment 1 for Control Room actions EXAMINER NOTE: Steps 3.3.1 through 3.3.4 are applicable to the person in the field who discovers the Medical Emergency. Step 3.3.5 is the step which directs the Control Room to take actions per Attachment 1.

EXAMINER NOTE: The Candidate may not dispatch anybody to assess the medical emergency and provide first aid during this step since there is already an Auxiliary Operator at the scene and the next two steps will complete the required action of providing first aid and an assessment. EXAMINER CUE: When the Candidate determines the need for A-7, 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 A-7. 2010 GINNA NRC JPM SA-4, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of9 Form ES-C-1 PERFORMANCE INFORMATION A-7, Attachment 1 " Performance Step: 2 Upon notification of a Medical Emergency: If the report is for any pE:lrSOn 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 Standard: Calls 769-911 to request an ambulance.

EXAMINER CUE: Inform the Candidate the Wayne County Emergency Dispatch has sent an ambulance to Ginna. A-7, Attachment 1 " Performance Step: 3 Make an announcement over the PA and have the Medical Emergency Response Team respond. Standard: An announcement is mclde to include the following:

Intermediate Building (Hot Side)
Medical Emergency
Emergency medical team respond
All others remain clear of the area EXAMINER CUE: When the Candidate determines the need for A-7, 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 A-7.

EXAMINER CUE: Inform the Candidate the announcement has been made once they describe what they would announce. 2010 GINNA NRC JPM SA-4, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION A-7, Attachment 1 Procedure Note: Text message to "Ginncl Medical Responders" will provide notification to EmergenGY Medical Responders outside of the Operations Department. These personnel are an additional resource for first aid response. '" Performance Step: 4 Text message uGinna Medical Responders." Standard: Candidate describes thE~ process for sending the text message which includes:

Logs on to their email account.
Types "Ginna Medical Responders" in the To: field
Types the location of the emergency and the type of emergency in the text field.

EXAMINER CUE: The text message has been sent. EXAMINER CUE: The Communicator has reported to the Control Room and began performing Appendix A of A-7. EXAMINER CUE: The Shift Technical Advisor has reported to you that he is performing EPIP 1-5, Attachment 5, Notifications. EXAMINER NOTE: The communicator automatically reports to the control room after announcement of a medical emergency. A-7, Attachment 1 Performance Step: 5 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. Standard: Contacts and dispatches Fire Brigade Captain to the scene. EXAMINER CUE: The Fire Brigade Captain has acknowledged the order. The Fire Brigade Captain reports Radiation Protection has determined the Chemist is contaminated above Federal Limits and the ambulance has arrived and taken the Chemist to Rochester General Hospital. 2010 GINNA NRC JPM SA-4, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of9 Form ES-C-1 PERFORMANCE INFORMATION A-7, Attachment 1 Performance Step: 6 Notify the NRC in accordance with CNG-NL-1.01-1004, REGULATORY REPORTING if a person is transported off-site and is radioactively contaminated. Standard: Determines the need to notify the NRC and obtains procedure. EXAMINER CUE: Provide candidate with CNG-NL-1.01-1 004 when they indicate they would obtain the procedure. CNG-NL-1.01-1004, Step 5.1 Performance Step: 7 Any individual who has ;13 reportability concern shall:

Notify their supervisor
Initiate a Condition Report (CR).
Promptly notify the Shift Manager/Report Sponsor of the reportability concern.

Standard:

Notifies the Shift Manager
Submits a Condition Report EXAMINER CUE: Inform the Candidate the Shift Manager has been notified when they indicate they would perform the notification.

EXAMINER CUE: Inform the Candidate a Condition Report has been submitted when they indicate they would initiate a Condition report. 2010 GINNA NRC JPM SA-4, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 70f9 Form ES-C-1 PERFORMANCE INFORMATION CNG-NL-1.01-1004, Step 5.2 and Attachment 2 Procedure Note: 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. Procedure Note: 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. --J Performance Step: 8 A. Upon becoming aware of a potentially reportable event or concern, the Shift Manager shall:

1. 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.

Standard:

Reviews Attachment 2

                        *    (--J) Determines that an 8-hour prompt report is required.

EXAMINER CUE: If the Candidate wants to wait for the Shift Manager to review the attachment, inform them the Shift Manager directs them to immediate begin reviewing Attachment 2 and make necessary reports. Terminating Cue: After the reporting requirement is determined: Evaluation on this JPM is complete. Stop Time: _ _ _ __ 2010 GINNA NRC JPM SA-4, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 ()f 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2010 GINNA NRC JPM SA-4 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-4, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 9 c)f 9 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

The Reactor is operating at 100% power, Steady-State, MOL.
The Shift Manager is outside the control room at a meeting with Plant Management.
Auxiliary Operator has called the Control Room to report:

o A Chemist has received serious steam burns while performing RCS sampling activities. o The sampling system has been stabilized and no radioactive releases are in progress. o The Chemist is in pain. INITIATING CUE: You are the CRS. Respond to the report of an injured chemistry technician. 2010 GINNA NRC *.lPM SA-4, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Facility: Ginna Task No.: Task

Title:

Determine the EAL for an Event JPM No.: 2010 GINNA NRC JPM SA-5 KIA

Reference:

2.4.41 (2.9/4.6) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: x Classroom X Simulator -- Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions:

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 hours 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.
The wind at Elevation 33 is from 275" at 10 mph.
The temperature at Elevation 33 is 78° F.
The wind at Elevation 250 is from 270* at 12 mph.
The temperature at Elevation 250 is 80.5° F.

Task Standard: Correct EAL documented and EPIP 1-5, Attachment 3A completed and handed to the communicator within 15 minutes. Required Materials: None 2010 GINNA NRC JPM SA-5, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 General

References:

EPIP 1-0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION, Revision 04500
EPIP-1.3, SITE AREA EMERGENCY
EPIP 1-5, NOTIFICATIONS, Revision 08200 Handouts: Perform in a location with the following available:
EPIP 1-0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION, Revision 04500
EPIP-1.3, SITE AREA EMERGENCY
EPIP 1-5, NOTIFICATIONS, Revision 08200 Initiating Cue: You are the Shift Manager. As the Emergency Coordinator, perform the required actions. The time critical task clock starts after you have reviewed the INITIAL CONDITIONS and indicate that you are ready to begin.

Time Critical Task: Yes Validation Time: 12 Minutes 2010 GINNA NRC JPM SA-5, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure SIMULATOR SETUP N/A 2010 GINNA NRC JPM SA-5, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 9 Form ES-C-1 VERIFICATION OF COMPLETION (Denote Critical Steps with a ") Start Time: _ _ _ _' EPIP 1-0, Step 6.1 " Performance Step: 1 6.1 In the event of an abnormal condition the Control Room Personnel will 6.1.1 Perform the immediate responses defined in the appropriate plant procedures. 6.1.2 Identify the initiating conditions using either the guidelines of the EAL wall chart or Attachment 1 of this procedure. 6.1.3 Implement applicable Emergency Plan procedures 6.1.3.1 EPIP 1-4, General Emergency 6.1.3.2 EPIP 1-3, Site Area Emergency Standard:

Proceeds to either the EAL wall chart or Attachment 1

                              *    (-J) 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.

Proceeds to EPIP 1-3, Site Area Emergency EXAMINER NOTE: When the candidate indicates he/she is ready to begin:

Display the JPM Start Time clearly in the room. Log the Classification Start Time _ _ __ Log the Classification Stop Time ____' Classification Stop Time ____ - Classification Start Time =- - - - The Classification Stop Time is also the Time Critical Task Start Time for the notification aspect. EPIP-1-3, Step 6.1.1 Performance Step: 2 Announce to personnel that you have assumed the duties of Emergency Coordinator Standard: Simulates announcement to the Control Room. EXAMINER CUE: Acknowledge announcement. 2010 GINNA NRC JPM SA-5, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 9 Form ES-C-1 VERIFICATION OF COMPLETION EPIP 1-3, Step 6.1.2 Performance Step: 3 Direct Control Room personnel to use appropriate plant procedures to limit or CQrrect the condition. Standard: Directs CRS to continue efforts to restore vital power. EXAMINER CUE: Acknowledge direction. EPIP 1-3, Step 6.1.3 Procedure Note: IF THE SITE AREA EMERGENCY IS DECLARED DUE TO ER SEC.2, THEN THE FOLLOWING ANNOUNCEMENT WILL NOT BE MADE. Performance Step: 4 Direct an operator to make the following announcement over the page system:

                        "Attention all personnel. A Site Area Emergency has been declared. All personnel with emergency duties report to your duty locations. All other personnel standby and await further instructions. No eating, drinking or smoking until further notice."

Standard: Determines NOTE does not apply and directs an operator to make the announcement. EXAMINER CUE: The announcement has been made. The communicator has reported to the controll room. EXAMINER NOTE: There is no EPIP 1-3, Step 6.1.4. The procedure steps from 6.1.3 to 6.1.5. EPIP 1-3, 6.1.5 Performance Step: 5 Refer to EPIP 1-6, Site Evacuation. Standard: Acknowledges CUE and continues. EXAMINER CUE: Evacuation will be delayed because vital bus power restoration efforts are likely to be successful in the near term. Continue to the next step in EPIP 1.3. 2010 GINNA NRC JPM SA-5, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C 6 of 9 Form VERIFICATION OF COMPLETION EPIP 1-3, 6.1.6 Procedure CAUTION NEW YORK STATE, WAYNE COUNTY, AND MONROE COUNTY MUST BE NOTIFIED WITHIN 15 MINUTES OF CLASSIFICATION. Procedure CAUTION THE NRC MUST BE NOTIFIED AS SOON AS POSSIBLE, NOT TO EXCEED ONE HOUR FROM CLASSIFICATION. Performance Step: 6 Direct the communicator to implement EPIP 1-5, Notifications. Standard: Proceeds to EPIP 1-5, Notifications Comments: EPIP 1-5, 6.0 Procedure NOTE: The Shift Manager/Emergency Coordinator/Recovery Manager may delegate these actions to any available individual, except as noted below. " Performance Step: 7 6.0 Actions 6.1 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 Standard: Properly fills out EPIP-1-5, Attachment 3A - NEW YORK STATE RADIOLOGICAL EMERGENCY DATA FORM EXAMINER CUE: The Communicator has arrived in the Control Room and is waiting to receive Attachment 3A to transmit. EXAMINER CUE: Provide blank EPIP 1-5 when the need is identified. Direct the candidate to circle 2.8 - An Exercise. EXAMINER NOTE: A KEY is attached for your use. 2010 GINNA NRC JPM SA-5, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix Page 7 9 Form VERIFICATION OF COMPLETION EPIP 1-5, Attachment 3A " Performance Step: 8 Notify off-site authorities. Standard: Hand Attachment 3A to the communicator no later than 15 minutes after the Classification Time Critical Stop Time. EXAMINER NOTE: Log the Notification Time Critical Task Stop Time ____' Notification Stop Time _ _ _ - Classification Stop Time

Terminating Cue: After Attachment 3A is handed to the communicator: Evaluation on this JPM is complete. Stop Time: _ _ __ 2010 GINNA NRC JPM SA-5, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix of 9 Form VERIFICATION OF COMPLETION Job Performance Measure No.: 2010 GINNA NRC JPM SA-5 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-5, Revision 4 NUREG 1021, Revision 9, Supplement 1

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

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 hours 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.
The wind at Elevation 33 is from 275' at 10 mph.
The temperature at Elevation 33 is 78° F.
The wind at Elevation 250 is from 270' at 12 mph.
The temperature at Elevation 250 is 80.5° F.

INITIATING CUE: You are the Shift Manager. As the Emergency Coordinator, perform the required actions. The time critical task clock starts after you have reviewed t.he INITIAL CONDITIONS and indicate that you are ready to begin. 2010 GINNA NRC JPM SA-5, Revision 4 NUREG 1021, Revision 9, Supplement 1

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

Title:

Given a Set of Conditions, Perform ~IPM No.: 2010 GINNA NRC JPM a Critical Rod Position Calculation In RA-1 Accordance With 0-1.2.2, Critical Rod Position Calculation. KIA

Reference:

2.1.25 (3.9 14.2) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: x Classroom X Simulator --- Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulclte or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions:

The plant is in MODE 3, preparing for a reactor startup.
PPCS and PCNDR are not available
See attached Initial Conditions and Plant History page.

Task Standard: Critical Rod Position calculation performed within specified band and all critical tasks evaluated as satisfactory. Required Materials: Calculator General

References:

0-1.2.2, Critical Rod Position Calculation, Rev. 06600
Core Operating Limits Report, Cycle 35 Handouts:
0-1.2.2, Critical Rod Position Calculation, Rev. 06600
Core Operating Limits Report, Cycle 35
Nomograph Tables
Initial Conditions and Plant History page Initiating Cue: 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 Task: NO Validation Time: 30 minutes 2010 GINNA NRC JPM RA-1, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix of9 PERFORMANCE INFORMATION (Denote Critical Steps with a .,J) Start Time: _ _ __ 0-1.2.2, section 1.0 thru 5.0 Performance Step: 1 Reviews sections 1.0 thru 5.0. Standard:

Reviews sections 1.0 thru 3.0 and 5.0.
Fills out step 4.1, signs steps 4.2 and 4.3.

EXAMINER CUE: Provide the Plant History/Initial Conditions Handout EXAMINER CUE: 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. EXAMINER NOTE: See provided "Key" for details of all steps. 0-1.2.2, section 6.1 Performance Step: 2 Calculate the reactivity due to Power Defect. Standard: Using Attachment 2, Figure 5-21 (MOL) determines Power Defect to be between 11150 pcm and 1200 pcm. Candidate: PCM EXAMINER NOTE: The exact value from PCNDR is 1190 PCM. 0-1.2.2, section 6.2 Performance Step: 3 Calculate the reactivity due to Rod Worth. Standard: Using Attachment 5, Table 6-7 (MOL) determines Control Rod Worth to be between 129 pcm and 130 pcm Candidate: PCM EXAMINER NOTE: 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-l, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 9 Form ES-C-1 PERFORMANCE INFORMATION 0-1.2.2, section 6.3 Performance Step: 4 Calculate the reactivity due to Xenon. Standard:

Transposes Reactor IEngineering Pre-trip Xe Worth (2100 PCM) onto Step 6.3.4
Transposes Reactor IEngineering Current Xe Worth (75 PCM) onto Step 6.3.5
Calculates Xe Change as +2025 PCM in Step 6.3.6 Candidate: PCM Comment:

0-1.2.2, section 6.4 Performance Step: 5 Calculate the reactivity due to Boron. Standard:

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 EVALUATOR NOTE: 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 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of9 Form ES-C-1 PERFORMANCE INFORMATION 0-1.2.2, section 6.5 Performance Step: 6 Calculate the reactivity due to "effective" Samarium. Standard:

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 EXAMINER NOTE: Actual reactivity change due to Sm is -40 PCM. 0-1.2.2, section 6.6 Performance Step: 7 Calculate total reactivity change. Standard: Calculates the total reactivity change between 754 and 882 pcm. Candidate: PCM EXAMINER NOTE: 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 .,j Performance Step: 8 Estimated Critical Rod Position. Standard: Estimated Critical Rod Position must be within the band of Bank D 19 steps to Bank D 164 steps. Candidate: Steps EVALUATOR NOTE: Actual Critical Rod Position for the conditions is Bank 0 71 steps. The band established in the Standard (0-1.2) is :t 500 PCM around Bank 0 71 steps. 2010 GINNA NRC JPM RA-l, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C 5 of 9 PERFORMANCE INFORMATION 0-1.2.2, section 6.7.2 Performance Step: 9 DETERMINE Control Bank Insertion Limit for 0% Power from COLR. Standard:

Uses COLR to determine Bank C 51 steps.

Candidate: Steps

Initials step Comment:

0-1.2.2, section 6.7.3 Procedure Note: 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. Performance Step: 10 COMPARE the estimated critical rod position (Step 6.7.1) with the Insertion Limit (Step 6.7.2) Standard:

Determines Step 6.7.1 (D 71) is greater than Step 6.7.2 (C 51)
Initials step Comment:

0-1.2.2, section 6.7.4 Performance Step: 11 IF a change in the critical rod position is needed, THEN PERFORM Step 6.B. OTHERWISE MARK this Step N/A. Standard: Marks step N/A EXAMINER CUE: A change in Critical Rod Position is not needed. 2010 GINNA NRC JPM RA-1, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 9 PERFORMANCE INFORMATION 0-1.2.2, section 6.7.5 Performance Step: 12 IF a change in the critical rod position is NOT needed, THEN MARK Step 6.8 N/A. OTHERWISE MARK this Step N/A. Standard:

Marks Step 6.8 N/A.
Initials step EXAMINER CUE: 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 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 9 PERFORMANCE INFORMATION 0-1.2.2, section 6.9.1 -J Performance Step: 13 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 6.8.1 AND
Attachment 14, Table 6-3 OR Attachment 15, Table 6-4, OR Attachment 16 Table 6-5

1. + 500 pcm bank position _ __

2. - 500 pcm bank position _ __

Standard:

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

                        *   (-J) 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

                        *   (-J) Determines the - 500 pcm position between D 14 and D 28 Candidate:             Sts..p.§.

EXAMINER NOTE: To determine the allowable values when calculating the +1 500 pcm positions the + 49 pcm - 79 pcm determined when calculating the Total Reactivity Change in Step 6.6.6 was used. PCNOR calculated the + 500 pcm position to be 0 164 and the - 500 pcm position to be 0 19 Terminating Cue: When Step 6.9.1 is complete: Evaluation on this JPM is complete Stop Time: _ _ __ 2010 GINNA NRC JPM RA-1, Revision 5 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 ..IPM RA-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 RA-1, Revision 5 NUREG 1021, Revision 9, Supplement 1

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

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.

INITIATING CUE: 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 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Facility: Ginna Task No.: Task

Title:

Perform an RHR System Valve and JPM No.: 2010 GINNA NRC JPM Breaker Position Verification on the RA-2 Control Board Prior to Mode 3 Entry KIA

Reference:

2.1.29 (4.114.0) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: X Classroom - - Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions:

The unit is in Mode 4, heating up to Mode 3.
The operating crew is performing STP-O-30.2, RHR SYSTEM VALVE AND BREAKER POSITION VERIFICATION.

Task Standard: All three (3) mispositioned valves/switches identified. Required Materials: None General

References:

STP-O-30.2, RHR SYSTEM VALVE AND BREAKER POSITION VERIFICATION, Revision 00001 Handouts:

STP-O-30.2, Attachment 1, VALVE AND BREAKER POSITION VERIFICATION - MAIN CONTROL BOARD Section only Page 6/7
Have entire procedure on h,and if candidate wants to review Precautions or Prerequisites Initiating Cue: You are the HCO. Perform STP-O-30.2, Attachment 1, VALVE AND BREAKER POSITION VERIFICATION - MAIN CONTROL BOARD section. The simulator and corresponding indications are in a static

("FREEZE") condition. Time Critical Task: No Validation Time: 5 minutes 2010 GINNA NRC JPM RA-2, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 SIMULATOR SETUP IC: Mode 4, with RHR secured and aligned for ECCS

Place HCV-626, RHR HX Bypass, Controller in AUTO
Fails HCV-624, RHR HX OUTLET, CLOSED
Place MOV-852A, RX VESSEL DELUGE, MOV-852A Key Switch in ON 2010 GINNA NRC JPM RA-2, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 6 VERIFICATION OF COMPLETION (Denote Critical Steps with a "J) Start Time: _ _ __ STP-O-30.2, Attachment 1, Page 6 of 7 Procedure Note: Main Control Board position indication for MOV's is acceptable provided the valve is in the proper position for the plant conditions AND system alignment. Performance Step: 1 Perform STP-O-30.2, Attachment 1, VALVE AND BREAKER POSITION VERIFICATION - MAIN CONTROL BOARD. Standard: Reviews NOTE and begins alignment verification by initialing proper alignment position. EXAMINER CUE: Provide the handout. Acknowledge any report of a mispositioned component. If necessary, direct the candidate to complete the entire Main Control Board Attachment if he/she stops after reporting the first mispositioned component. EXAMINER NOTE: Only the mispositioned valves/switches are identified in the

                                ..IPM (Performance Steps 2, 3, 4). Errors can be identified in any order.

STP-O-30.2, Attachment 1, Page 6 of 7 " Performance Step: 2 Perform STP-O-30.2, Attachment 1, VALVE AND BREAKER POSITION VERIFICATION - MAIN CONTROL BOARD. Standard: Identifies HCV-626 Controller, RHR HX BYPASS, in AUTO rather than MAN UAL. Comment: 2010 GINNA NRC JPM RA-2, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 6 Form VERIFICATION OF COMPLETION STP-O-30.2, Attachment 1, Page 6 of 7 " Performance Step: 3 Perform STP-O-30.2, Attachment 1, VALVE AND BREAKER POSITION VERIFICATION - MAIN CONTROL BOARD. Standard: Identifies HCV-624, RHR HX OUTLET, CLOSED rather than OPEN. Comment: STP-O-30.2, Attachment 1, Page 6 of 7 " Performance Step: 4 Perform STP-O-30.2, Attachment 1, VALVE AND BREAKER POSITION VERIFICATION - MAIN CONTROL BOARD. Standard: Identifies MOV-852A, RX VESSEL DELUGE, KEY SWITH in ON rather than OFF Comment: Terminating Cue: When the candidate returns Attachment 1: Evaluation on this JPM is complete. Stop Time: _ _ __ 2010 GINNA NRC JPM RA-2, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 6 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 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 ot6 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

The unit is in Mode 4, heating up to Mode 3.
The operating crew is performing STP-O-30.2, RHR SYSTEM VALVE AND BREAKER POSITION VERIFICATION.

INITIATING CUE: You are the HCO. Perform STP-O-30.2, Attachment 1, VALVE AND BREAKER POSITION VERIFICATION - MAIN CONTROL BOARD section. The simulator and corresponding indications are in a static ("FREEZE") condition. 2010 GINNA NRC JPM RA-2, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES~C-1 Facility: Ginna Task No.: Task

Title:

Perform the RO Review of a Tag()ut JPM No.: 2010 GINNA NRC ..IPM For V-3968, 4B Condensate Heater RA-3 Discharge Check Valve. KIA

Reference:

2.2.13 (4.1/4.3) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: x Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions:

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-39S8.
Plant Management has determined the replacement of V-39S8 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.

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 10 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 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
Marked up copy of T-14E, Isolation and Restoration to Service of Condensate Heater 48, Rt9v. 009 (if requested)

Initiating Cue:

The Shift Manager directs you to perform the required review for block 14 of Attachment 7 of CNG-OP-1.01-1 007 to ensure V-3968 is properly isolated and ready to be replaced. When the review is complete sign block 14.
After signing block 14, return Attachments 7 and 8 to the Shift Manager.

Time Critical Task: No Validation Time: 15 Minutes 2010 GINNA NRC JPM RA-3, Revision 10 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 6 Form ES-C-1 VERIFICATION OF COMPLETION (Denote Critical Steps with a ~) Start Time: _ _ __ CNG-OP-1.01-1007 Performance Step: 1 Review CNG-OP-1.01-1007, Attachments 7 and 8 Standard: Reviews CNG-OP-1.01-1007, Attachments 7 and 8 EXAMINER CUE: Provide the candidate with all of the handouts except CNG OP-1.01-1007 and T-14E. If the Candidate requests the procedures, provide them with a copy. EXAMINER CUE: If the candidate stops after the first error is identified, direct them to complete their review of the entire document. EXAMINER NOTE: 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-1.01-1007, Attachment 7 Performance Step: 2 Refers to CNG-OP-1.01-1007 as needed. Standard: Identifies that the Remarks section of Attachment 7 should include a statement identifying that double isolation is not available for the high temperature system. EXAMINER NOTE: 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 "D.)uble 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 10 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of6 Form ES-C-1 VERIFICATION OF COMPLETION CNG-OP-1.01-1007, Attachment 8 -J Performance Step: 3 Refers to CNG-OP-1.0*1-1007 as needed. Standard: Determines that V-3997B should be OPEN vice CLOSED. EXAMINER NOTE: Since V-3997B is a vent valve, it should be open to ensure the system is depressurized. CNG-OP-1.01-1 007, Attachment 8 ,j Performance Step: 4 Refers to CNG-OP-1.01-1007 as needed. Standard: Determines that V-3966A was not included in the isolation boundary. EXAMINER NOTE: Without V-3966A Danger tagged OPEN Operations Department can not guarantee the Condensate side of the system will remain depressurized. Terminating Cue: When the Attachment is handed over: Evaluation on this JPM is complete. Stop Time: _ _ __ 2010 GINNA NRC JPM RA-3, Revision 10 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2010 GINNA NRCJPM 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 10 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET 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 the 48 Condensate Heater in service.
The 48 Low Pressure Heater has been isolated and vented per T-14E, Isolation and Restoration to Service of Condensate Heater 48
eSOMs is not available due to maintenance.

INITIATING CUE:

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.
After signing block 14, return Attachments 7 and 8 to the Shift Manager.

2010 GINNA NRC JPM RA-3, Revision 10 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Facility: Ginna Task No.: Task

Title:

Determine Steam Generator Tube ~IPM No.: 2010 GINNA NRC JPM Leakage Using Radiation Monitor R- RA-4

47. Air Ejector Radiation Monitor Low Range KIA

Reference:

2.3.15 (2.9/3.1) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: x 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:

The unit has been operating at 100% power for 175 days with some minor fuel leakage indicated.
No equipment is out-of-service (OOS).
Priority 1 PPCS alarm AR-PPCS-R47AR has just actuated.
Reactor Coolant System Pressure, Pressurizer Level and Charging Pumps speed are at their normal setpoints and stable.

Task Standard: SG Tube leakage determined within specified band and AP-SG.1 entry recommended Required Materials: None General

References:

AR-PPCS-R4 7AR, Revision 0
Steam Generator Tube Leak vs. R-47 Reading Conversion Table (Curve Book 06-004)
P-9, RADIATION MONITORING SYSTEM, Revision 9802 Handouts:
AR-PPCS-R47AR
Steam Generator Tube Leak vs. R-47 Reading Conversion Table (Curve Book 06-004)

Initiating Cue: You are the Head Control Operator; respond to AR-PPCS-R47AR as if you were in the control room. 2010 GINNA NRC JPM RA-4, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Time Critical Task: No Validation Time: 6 minutes 2010 GINNA NRC JPM RA-4, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 SIMULATOR SETUP N/A 2010 GINNA NRC JPIVI RA-4, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 ()f 8 Form ES-C-1 VERIFICATION OF COMPLETION (Denote Critical Steps with a ..J) Start Time: _ _ __ Performance Step: 1 Perform AR-PPCS-R4 7AR. Standard:

Informs the Control Room Supervisor of the alarm.
Reviews procedure.

EXAMINER CUE: When the Candidate informs the Control Room Supervisor of the alarm, provide a repeat back. EXAMINER CUE: When the Candidate determines the need for AR-PPCS R47AR, 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 AR-PPCS R47AR. EXAMINER CUE: The Candidate may ask for any additional PPCS alarms associate with the event. If this happens, inform them no other alarms associated with the event are in. (At this point we are simulating R47, an input to R47AR, is malfunctioning). EXAMINER NOTE: An AO may be dispatched for a local reading and/or to checkout the status of the monitor. If so, provide a repeat back. AR-PPCS-R-47 AR, Step 1 Performance Step: 2 If SG Tube Rupture is evident, then GO TO E-O, REACTOR TRIP OR SAFETY INJECTION. Standard: Answers NO and continues to Step 2 based on indication of RCS Pressure and Pressurizer Level in the Initiating Cue. Comment: 2010 GINNA NRC JPM RA-4, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 8 Form ES-C-1 VERIFICATION OF COMPLETION AR-PPCS-R-47 AR, Step 2 Performance Step: 3 Trend PPCS Point R-47G. Standard: Indicates they would trend R-47G on PPCS. EXAMINER CUE: It is not necessary for the Candidate to discuss how to place a PPCS point on trend. Once they have indicated they would trend R-47G, inform them "The point quality for R47G has just gone BAD and the trend function is NOT responding. Continue with the procedure while help is requested." AR-PPCS-R-47AR, Step 3 Performance Step: 4 Notify RP/Chemistry to IMMEDIATELY obtain and analyze an air ejector grab sample per CH-360, Primary to Secondary Leakage Sampling and Measurement. Standard: Simulates calling Chemistry and directs technician to IMMEDIATELY obtain and analyze an air ejector grab sample per CH-360, Primary to Secondary Leakage Sampling and Measurement. Communication should include a reference to the R-47 PPCS alarm and/or possible S/G tube leakage. EXAMINER CUE: Answer as Duty Chemistry Technician and provide a repeat back of the communication. EXAMINER CUE: If the Candidate asks, the following radiation monitors are reading: R-15: 2.8 e 7 CPM R-19: 1.6 e 2 CPM R-31: 2.0 e -2 mRlhr R-32: 2.33 e -2 mRlhr R-48: 1.4 e -2 pCi/cc 2010 GINNA NRC JPM RA-4, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 8 Form ES-C-1 VERIFICATION OF COMPLETION AR-PPCS-R-47 AR, Step 4 " Performance Step: 5 Determine the estimated leak rate using PPCS point R-47G or the Local Reading and the Conversion Table (Curve Book #06 004) Standard:

Contacts an AO for the local R-47 reading.
Describes location of Conversion Table #06-004 as being in a three ring binder (referred to as the Curve Book) located in the Main Control Room.

                        *   [(..J> Using Curve #06-004 and the local reading, determines SG tube leakage to be 200 GPD EXAMINER CUE:         When the Candidate contacts the AO for a local R-47 reading, report "R-47 reads 3.000E+04".

EXAMINER CUE: After the candidate correctly describes obtaining the Curve Book, provide Steam C:;enerator Tube Leak vs. R-47 Reading Conversion Table (CuII'Ve Book 06-004). AR-PPCS-R-47AR, Step 5 " Performance Step: 6 If any condition below is met, then GO TO AP-SG.1, STEAM GENERATOR TUBE LEAK:

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 greater than or e~qual to 5 gpd, OR
SM discretion Standard: Makes report to CRS that AP-SG.1 must be entered based on R 47 greater than or equal to 5 gpd (per conversion table).

EXAMINER NOTE: This procedure recommendation is considered critical because this will initiate action to begin a plant shutdown. Terminating Cue: After the procedure recommendation: Evaluation on this JPM is complete. Stop Time: _ _ __ 2010 GINNA NRC JPM RA-4, Revision 5 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 RA-4 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-4, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 8 JPM CUE SHEET INITIAL CONDITIONS:

The unit has been operating at 100% power for 175 days with some minor fuel leakage indicated.
No equipment is out-af-service (OOS).
Priority 1 PPCS alarm AR-PPCS-R47 AR has just actuated.
Reactor Coolant System Pressure, Pressurizer Level and Charging Pumps speed are at their normal setpoints and stable.

INITIATING CUE: You are the Head Control Operator; respond to AR-PPCS-R47AR as if you were in the control room. 2010 GINNA NRC JPM RA-4, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Facility: Ginna Task No.: Task

Title:

Start an Emergency Diesel JPM No.: 2010 GINNA NRC JPM Generator During a Loss of All AG. ~ Power. KIA

Reference:

EPE 055 EA 1.02 (4.3/4.4) Alternate Path - RNO column entered twice. Once to start a DIG and once to start an SW Pump. Examinee: NRC Examiner: Facility Evaluator: Date: Method oftesting: 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:

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: None General

References:

ECA-O.O, LOSS OF ALL AC POWER, Revision 03401 Handouts: ECA-O.O, Step 7 (Pgs. 6 and 7 of 26) Initiating Cue: The Control Room Supervisor has directed you to perform ECA-O.O, Step 7 - Try To Restore Power to Any Train Of AC Emergency Busses for the A EDG. Time Critical Task: No Validation Time: 4 Minutes 2010 GINNA NRC JPM A, Revision 3 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SE,TUP 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 '8' EDG 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, set jltgmlct 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 3 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 8 Form ES-C-1 VERIFICATION OF COMPLETION (Denote Critical Steps with a .J) Start Time: _ _ __ ECA -0.0, Step 7.a Procedure Note:

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.

Performance Step: 1 Try To Restore Power to Any Train Of AC Emergency Busses:

a. Verify emergency DIG aligned for unit operation

Mode switch in UNIT
Voltage control selector in AUTO Standard:
Verifies DIG A Mode Switch selected to UNIT
Verifies DIG A MANUAL I AUTO VOLTAGE CONTROL selected to AUTO EXAMINER CUE: After the Initiating Cue is read, provide the ECA-O.O, Step 7 Handout.

EXAMINER NOTE: Switch nomenclature is different than the procedure nomenclature for the Mode and Voltage Control switches. ECA-O.O, Step 7.b Performance Step: 2 Check emergency DIGs - BOTH DIG RUNNING Standard:

Observes the following indications on the A and B DIGs o Frequency reads 61.2 Hz (On the green line) o Voltage reads 0 Volts o Amperage reads 0 Amps o Watts reads 0 Watts
Answers NO and prc>ceeds to 7.b. RNO Comment:

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

Appendix C Page 4 of VERIFICATION OF COMPLETION ECA-O.O, Step 7.b RNa b.1) Performance Step: 3 WHEN non-running DIG available for starting, THEN perform the following:

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

Comment: ECA-O.O, Step 7.b RNO b.2) " Performance Step: 4 Depress DIG RESET pushbutton Standard: Depresses DIG A RESET pushbutton EXAMINER NOTE:

DIG A will start at this time because the trip signal is cleared and the auto start signal is still present. The BLUE air start solenoid lights will extinguish.

EXAMINER NOTE:

The candidate should move quickly from this point. A DIG running without cooling water will trip in approximately 5 minutes.

ECA-O.O, Step 7.b RNa b.3) Performance Step: 5 Start DIG Standard:

Verifies DIG A is running by observing:

o Frequency reads 60 Hz (On the green line) o Voltage reads 480 Volts o Amperage reads - 1000 Amps o Watts reads 550 Watts EXAMINER NOTE: The candidate may rotate the A DIG start switch to START to align the breaker flags. 2010 GINNA NRC JPM A, Revision 3 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 8 Form ES-C-1 VERIFICATION OF COMPLETION ECA-O.O, Step 7.b RNO b.4) Performance Step: 6 IF DIG starts, THEN go to Step 7c. Standard: Proceeds to Step 7. c. Comment: ECA-O.O, Step 7.c Performance Step: 7 Check DIG voltage and frequency

Voltage - APPROXIMATELY 480V
Frequency - APPROXIMATELY 60 Hz Standard: Verifies Voltage and Frequency for the A DIG by observing:
Voltage - APPROXIMATELY 480V on A DIG Voltmeter
Frequency- APPROXIMATELY 60 Hz on A DIG Frequency Meter Comment:

ECA-O.O, Step 7.d Performance Step: 8 Verify adequate DIG cooling

1) Bus 17 and/or Bus 18 - ENERGIZED Standard: Verifies Bus 18 energized to approximately 480 Volts on MCB Bus 18 Voltmeter Comment:

ECA-O.O, Step 7.d Performance Step: 9 One SW Pump running for each running DIG Standard:

Determines NO SW Pumps running by observing all SW Pump RED lights extinguished andlor SW header pressure.
Proceeds to Step 7.d. RNO.

Comment: 2010 GINNA NRC JPM A, Revision 3 I\lUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 8 Form ES-C-1 VERIFICATION OF COMPLETION ECA-O.O, Step 7.d RNO -V Performance Step: 10 Manually energize busses and start SW Pumps. Standard: * (-V) Starts "An and/or "C" SW Pump by rotating the switch to the START position before "A" D/G trips on a cooling water related automatic setpoint.

Observes the pump or pumps started red light lit.

EXAMINER NOTE:

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.

ECA-O.O, Step 7.e Performance Step: 11 Verify at least one train of AC emergency busses - ENERGIZED

Bus 14 and Bus 18
Bus 16 and Bus 17 Standard: Verifies Busses 14 and 18 are energized to approximately 480 Volts.

Comment: Terminating Cue: When Step 7.1 "Return to procedure and step in effect" is read: Evaluation on this JPM is complete. Stop Time: _ _ __ 2010 GINNA NRC JPM A. Revision 3 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 A 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 A, Revision 3 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 lof 8 Form ES-C-1

                                     ..IPM CUE SHEET 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.

INITIATING CUE: The Control Room Supervisor has directed you to perform ECA 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 3 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Facility: Ginna Task No.: Task

Title:

In accordance with FR-C.1 , JPM No.: 2010 GINNA NRC RESPONSE TO INADEQUATE JPM B CORE COOLING, Isolate an SI Accumulator That Has Discharge(~ KIA

Reference:

006 A4.07 (4.4/4.4) Alternate Path - Step 17.d RNa 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:

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 Stl3PS 1 through 16 of FR-C, 1, RESPONSE TO INADEQUATE CORE COOLING.

Task Standard: A SI Accumulator depressurized and B SI Accumulator isolated. Required Materials: Marked up copy of FR-C.1 available in the simulator. General

References:

FR-C.1, RESPONSE TO INADEQUATE CORE COOLING, Revision 02600 Handouts: FR-C.1, Step 17 Initiating Cue: The CRS directs you to perform FR-C.1, Step 17, Time Critical Task: No Validation Time: 4 Minutes 2010 GINNA NRC JPM B, Revision 3 NUREG 1021, Revision 9, Supplement 1

Appendix Job Performance Measure 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 3 NUREG 1021, Revision 9, Supplement 1

Appendix C Page30f8 Form ES-C-1 VERIFICATION OF COMPLETION (Denote Critical Steps with a -V) Start Time: FR-C.1, Step 17 Performance Step: 1 Perform Step 17 - Check if SI Accumulators should be isolated Standard: Reviews Steps and considers conditions, as necessary. EXAMINER CUE: Provide copy of FR-C.1, Step 17. FR-C.1, Step 17.a Performance Step: 2 RCS hot leg temperatures - BOTH LESS THAN 390 of Standard: Observes RCS hot leg temperatures indicating less than 390'F on TI-409A1, 409B1, 410A1 and 410B1 and/or PPCS. Comment: FR-C.1, Step 17.b Performance Step: 3 Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves

MOV-841 MCC C position 12F
MOV-8S5 MCC D position 12C Standard: Directs Primary AO to close the following breaker:
MOV-8S5 MCC D position 12C EXAMINER NOTE: The candidate may not recognize power is not available to MOV-841 and therefore direct closure of that breaker.

EXAMINER NOTE: The simulator snap includes the breakers for MOV-841 and MOV-8SS already closed. There is not any action required by the Simulator Driver. EXAMINER CUE: Repeat back order. Wait one minute and then report that the breakers for MOV-8SS and MOV-841 (if they don't realize MOV-841 doesn't have power) are closed. 2010 GINNA NRC JPM B, Revision 3 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 8 Form ES-C-1 VERIFICATION OF COMPLETION FR-C.1, Step 17.c Performance Step: 4 Verify SI reset. Standard: Observes K-6, THERMAL OVERLOAD RELAY BYPASSED, extinguished. EXAMINER NOTE: If K-6 is extinguished then Safety Injection has been reset. EXAMINER NOTE: The Candidate may depress the SI Reset Pushbutton to ensure SI is reset. FR-C.1, Step 17.d >/ Performance Step: 5 Close SI Accumulator Discharge Valves

ACCUM A - MOV-841
ACCUM B - MOV-865 Standard: * (>/) 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 EXAMINER NOTE: MOV-841 will not close since there is no power available with Bus 14 de-energized. The candidate may not attempt to close it based on the Initial Conditions.

FR-C.1, Step 17.RNO d.1) Performance Step: 6 Perform the following to vent an unisolated accumulator:

1) Reset CI Standard: Depresses the CI RESET PB.

EXAMINER NOTE: Candidate may verify that A-26, CONTAINMENT ISOLATION, extinguishes. 2010 GINNA NRC JPM B, Revision 3 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 ()f 8 Form ES-C-1 VERIFICATION OF COMPLETION FR-C.1, Step 17.RNO d.2) Performance Step: 7 Ensure adequate air compressor(s) running. Standard:

Observes the Red light lit for the "C" Air Compressor running.

(MCB Back Panel)

Observes approximately 115 PSIG on Instrument Air Header Pressure.

EXAMINER NOTE: 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)

Performance Step: 8 Establish IA to CNMT. Standard:

Observes the Red light lit for AOV-5392.
Observes the AOV-5392 light dim on the CI/CVI panel.

Comment: FR-C.1, Step 17.RNO d.4) >I Performance Step: 9 Open vent valves for unisolated 51 ACCUMs.

ACCUM A, AOV-834A
ACCUM B, AOV-834B Standard: * <>I) Rotates the switch for AOV-834A to the OPEN position.

(MCB Back Panel)

Observes the Red Ii~Jht lit for AOV-834A.

EXAMINER NOTE: 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 3 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 8 Form ES-C-1 VERIFICATION OF COMPLETION FR-C.1, Step 17.RNO d.5) ..J Performance Step: 10 Open HCV-945. Standard: Opens HCV-945 by adjusting the demand controller on MCB Back Panel to a position greater than ZERO Comment: Terminating Cue: After the candidate has opened HCV-945: Evaluation on this JPM is complete. Stop Time: _ _ __ 2010 GINNA NRC JPM B, Revision 3 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 B Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiner's Signature: Date: 2010 GINNA NRC JPM B, Revision 3 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 8 JPM CUE SHEET INITIAL CONDITIONS:

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.

INITIATING CUE: The CRS directs you to perform FR-C.1, Step 17. 2010 GINNA NRC JPM B, Revision 3 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Facility: Ginna Task No.: Task

Title:

Start a Reactor Coolant Pump "IPM No.: 2010 GINNA NRC JPM during a plant startup and then C respond to an alarm associated with the pump just started KIA

Reference:

003 2.1.23 (4.3/4.4) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: X Classroom -- Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions:

The 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.

Task Standard: RCS Pressure controlled within required parameters and the A RCP manually tripped Required Materials: 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:I: 1.25, Revision 01601 2010 GINNA NRC "IPM C, Revision 4 NUREG 1021, Revision 9, Supplement 1

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

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 Initiating Cue: 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.

Time Critical Task: No Validation Time: 15 Minutes 2010 GINNA NRC JPM C, Revision 4 I\IUREG 1021, Revision 9, Supplement 1

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

Reset to IC for NRC JPM N-C
Ensure MALF RCS08A, -2.5, on Trigger 1
Place RCP Parameters on Group Display
LTOP 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 4 NUREG 1021, Revision 9, Supplement 1

Appendix C 4 13 Form L- .....-~- VERIFICATION OF COMPLETION (Denote Critical Steps with a ~) Start Time: _ _ __ 0-1.1, Step 6.5.10.3 Procedure Note: 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. 1/ Performance Step: 1 PLACE PCV 135 in MANUAL AND CONTROL RCS pressure at approximately 325 psig. Standard:

Reviews procedure note prior to Step 6.5.10.3
Balances the PCV 135 Automatic-to-Manual control and places the controller to Manual.

                                * (1/) Controls RCS pressure at 325 psig.

EXAMINER CUE: Provide the Candidate with the marked up copy of 0-1.1. 0-1.1, Step 6.5.10.4 Performance Step: 2 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. Standard: Based on Initial Conditions, marks the step N/A Comment: 2010 GINNA NRC JPM C, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix Page 5 13 VERIFICATION OF COMPLETION 0-1.1, Step 6.5.10.5 Performance Step: 3 CLOSELY MONITOR RCS heatup rate AND RCS pressure after starting of the 2nd RCP. Standard: Monitors RC8 heat up rate and pressure on PPC8. Comment: 0-1.1, Step 6.5.10.6 Performance Step: 4 8TART the 2nd RCP PE R S-2.1, starting instructions section AND MARK RCP NOT started N/A.

RCPA
RCP B Standard:
Marks RCP B step N/A
Refers to 8-2.1 for the A RCP EXAMINER CUE: Provide the Candidate with a marked up copy of S-2.1 when the need is identified.

S-2.1, Section 5.1 Procedure Note: Sections that will not be performed may be marked N/A. Performance Step: 5 STARTING RCPA Standard: Reviews procedure Comment: 2010 GINNA NRC JPM C, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix 6 of 13 Form VERIFICATION OF COMPLETION S-2.1, Step 5.1.3 Procedure Note: 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. Performance Step: 6 Start RCP A Oil Lift Pump. Standard:

Rotates the RCP A Oil Lift Pump handle to the START position.
Verifies red start light is lit
Marks the time.

EXAMINER NOTE: 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 st.art unless the pressure interlock is satisfied. 5-2.1 t Step 5.1.4 Procedure Note: 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. Performance Step: 7 AFTER 2 minutes, VERIFY RCP A Lift Pressure WHITE light is lit. Standard:

Verifies RCP A Lift Pressure WHITE light is lit.
Verifies 2 minutes has elapsed since the start of the Lift Oil Pump.

Comment: 2010 GINNA NRC JPM C, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 13 Form ES-C-1 VERIFICATION OF COMPLETION S-2.1, Step 5.1.5 Performance Step: 8 VERIFY RCP A No.1 Seal Leakoff is still in the NORMAL OPERATING RANGE of Attachment 3, RCP Seal Leakoff. Standard:

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.

Comment: S-2.1, Step 5.1.6 Performance Step: 9 Select RCP A on the Containment Sound Monitor, N/A if Sound Monitor is not available. Standard: Marks the step N/A Comment: S-2.1, Step 5.1.7 Performance Step: 10 Make a Plant Announcement that Rep A will be started. Standard: Announces starting Reactor Coolant Pump A. Comment: 2010 GINNA NRC JPM C, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix Page 8 13 Form VERIFICATION OF COMPLETION S-2.1, Step 5.1.8 Procedure Note:

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.

"1/ Performance Step: 11 Start RCP A. Standard:

May assign the seccmd board operator to adjust Charging Pump speed, when directed.
Starts RCP A and verifies flow.

                        *    ("1/) Adjusts PCV-135 as necessary to maintain RCS Pressure such that RCP #1 S.9al DP >220 PSID, as seen on PI-173, and no PORV lift (410 PSIG).

Comment: S-2.1, Step 5.1.9 Performance Step: 12 Tum off the Containment Sound Monitor (mark N/A if not used). Standard:

Marks the step N/A Comment:

S-2.1, Step 5.1.10 Performance Step: 13 WHEN the A RCP has been operating for greater than 1 minute, THEN STOP the RCP A Oil Lift Pump. Standard:

Verifies the RCP has been running for one minute .
Rotates the RCP A Oil Lift Pump counter-clockwise to the STOP position.

Comment: 2010 GINNA NRC JPM C, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 9 of 13 Form ES-C-1 VERIFICATION OF COMPLETION 5-2.1, Step 5.1.11 Performance Step: 14 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 Standard: Refers to Section 5.3 and begins verifying parameters.

EXAMINER CUE: If the Candidate asks Seal Return Heat Exchanger Outlet Temperature, inform them it is 80°F. SIMULATOR DRIVER: When this step is in progress, insert MALF RCS08A, -2.5, ramp over 30 seconds AR-A-24 Pe.rformance Step: 15 Responds to annunciator alarm. Standard: Acknowledges Main Control Board alarm A-24. Comment: AR-A-24, Step 1 Performance Step: 16 When first starting the plUmp, then allow 30 seconds for alarm to clear. Trip pump if alarm still does not clear. Standard: Reads step and may trip the RCP at this time. EXAMINER NOTE: 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 4 NUREG 1021, Revision 9, Supplement 1

Appendix Page 10 13 VERIFICATION OF COMPLETION AR-A-24, Step 2 Performance Step: 17 When operating, then verify level using RCP Oil Level Indicators and Plant Process Computer System. Standard:

Checks RCP A Oil Level at the RMS rack side panel
Checks Group Display RCPS on PPCS Comment:

AR-A-24, Step 2.1 Performance Step: 18 Immediately monitor the A RCP Motor bearing temperature. This can be done by using PPCS Group Display RCPS. Standard: Determines RCP Motor Bearing temperature is rising using PPCS Comment: AR-A-24, Step 2.2 Performance Step: 19 IF bearing temperatures AND indicated level appear normal, THEN initiate a CNMT entry to investigate the sight glass level. IF the lower bearing oil level is greater than 1" BELOW the notch on the sight glass, THEN prepare to remove the pump from service. Otherwise, the level is acceptable to continue operation. Standard: Determines conditions are NOT normal and proceeds to the next step. Comment: 2010 GINNA NRC JPM C, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 11 of 13 Form ES-C-1 VERIFICATION OF COMPLETION AR-A-24, Step 2.3 ..J Performance Step: 20 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 Cue: When RCP A is stopped: Evaluation on this JPM is complete. Stop Time: _ _ __ 2010 GINNA NRC JPM C, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 12 of 13 Form VERIFICATION OF COMPLETION Job Performance Measure No.: 2010 GINNA NRC JipM 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 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 1 1

                                     .JPM CUE SHEET INITIAL CONDITIONS:

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 wsed 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.

INITIATING CUE: 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 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Workshl~et Facility: Ginna Task No.: Task

Title:

Respond To a Control Room JPM No.: 2010 GINNA NRC JPM Evacuation D KJA

Reference:

APE 068 AA1.23 (4.3/4.4) ALTERNATE PATH: RNO implemented for reactor and turbine trip. Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: X Classroom - - Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions:

The 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.

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: 1 Minute 2010 GINNA NRC JPM D, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Pertormance Measure Form ES-C-1 SIMULATOR SETUP Reset to IC for NRC JPM-N-D 2010 GINNA NRC JPM D, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 8 Form ES-C-1 VERIFICATION OF COMPLETION (Denote Critical Steps with a ...J) Start Time: _ _ __ AP-CR.1, step 1 Performance Step: 1 Assumes the watch Standard: Walks down the MCB EXAMINER CUE:

Wait 15-30 seconds after the Initiating Cue then:

The SM reports noxious fumes in the Relay Room and has directed the CRS to enter into AP-CR.1, CONTROL ROOM INACCESSIBILITY. The CRS directs you to perform the Immediate Actions for AP-CR.1.

Acknowledge the r1epeatback.

AP-CR.1, step 1 Performance Step: 2 Verify Reactor Trip:

At least one train of reactor trip breakers - OPEN.
Neutron flux - LOWERING.
MRPI indicates - ALL CONTROL AND SHUTDOWN RODS ON BOTTOM.

Standard:

Determines no reactor trip breakers are open
Determines Neutron flux at 100% RTP
Determines MRPI indicates the reactor is not tripped EXAMINER NOTE: 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 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 8 Form ES-C-1 VERIFICATION OF COMPLETION AP-CR.1, step 1 RNa Performance Step: 3 Manually trip reactor. Standard:

Depresses the Reactor Trip Pushbutton on MCB
Determines no reactor trip breakers are open
Proceeds to step 1.a RNO EXAMINER NOTE: 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 RNO " Performance Step: 4 IF reactor trip breakers I\IOT open, THEN perform the following:

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

b. Verify rod drive MG sets tripped.

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

d. Reset lighting brea~,ers.

IF the Rx can NOT be tripped from the Control Room, THEN dispatch personnel to locally open the reactor trip breakers. Standard: a. (") Opens Bus 13 and Bus 15 normal feed breakers.

Red lights OFF and Green lights ON.

b. Rod drive MG sets tripped.

Rod Drive MG SE~t A and B Red lights OFF and Green lights ON.

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

Red lights ON and Green lights OFF.

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

Comment: 2010 GINNA NRC "IPM D, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix 5 of8 Form VERIFICATION OF COMPLETION AP-CR.1, step 2 Performance Step: 5 Verify Turbine Stop Valves - CLOSED Standard:

On EHC valve status panel observes SVL Open red light ON and SVR Open red lig ht ON.
Identifies Turbine stop valves are still open and goes to step 2RNO.

EXAMINER NOTE: Since the reactor trip signal initiates the turbine trip signal, the turbine did not receive an auto trip signal. AP-CR.1, step 2 RNO ..; Performance Step: 6 Manually trip turbine. IF turbine can NOT be tripped, THEN close both MSIVs. Standard:

Depresses Turbine Emergency Trip P/B
Determines the Turbine did not trip

                         * ('V) Rotates the Handswitch to the closed position for valves:

MSIV A, AOV-3517
MSIV B, AOV-3516
Observes Red light E!xtinguished and Green light lit for the following valves:
MSIV A, AOV-3517
MSIV B, AOV-3516 EXAMINER NOTE: Inserted malfunction has prevented manual turbine trip button from initiating the turbine trip.

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

Appendix C Page 6 of 8 Form ES-C-1 VERIFICATION OF COMPLETION Completion of Immediate Operator Actions Performance Step: 7 Communicate completion of the Immediate Operator Actions for AP-CR.1. Standard: Announces that the Immediate Operator Actions for AP-CR.1 are complete. EXAMINER CUE: Acknowledge report. Terminating Cue: When the immediate actions are reported as completed: Evaluation on this ..IPM is complete. Stop Time: _ _ __ 2010 GINNA NRC JPM D, Revision 4 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 ~IPM 0 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 0, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 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 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Facility: Ginna Task No.: Task

Title:

Placing LTOP on Service JPM No.: 2010 GINNA NRC JPM

                                                                             £ KIA

Reference:

010 A4.03 (4.0/3.8) 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:

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 throug h section 6.1 of 0-7, Alignment and Operation of the Reactor Vessel Overpressure Protection System, has been completed.

Task Standard: Place PCV-430 on service and all critical tasks evaluated as satisfactory . Required Materials: Panel key for LTOP operations. General

References:

0-7, Alignment and Operation of the Reactor Vessel Overpressure Protection System, Rev. 04'701
0-2.2, Plant Shutdown from Hot Shutdown to Cold Conditions, Rev.

15300 Handouts: Properly markup a copy of 0-7, Alignment and Operation of the Reactor Vessel Overpressure Protection System, Rev. 04701 to section 6.2. Initiating Cue: 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 Task: No Validation Time: 4 Minutes 2010 GINNA NRC JPM E, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 __________________________~VV~orkshe~e~t___________________________ 2010 GINNA NRC JPM E, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure SIMULATOR SETUP Reset to IC for NRC JPM-N-E Replace the On-line MCB Annunciator Tiles (C-5 and F-29) 2010 GINNA NRC JPM E, Revision 5 f\lUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 ()f VERIFICATION OF COMPLETION (Denote Critical Steps with a ..J) Start Time: _ _ __ 0-7, step 6.2.1 Performance Step: 1 VERIFY the following MCB Alarms extinguished:

AA-22 , RCS OVER-PRESS PROTECTION TRAIN A HI PRESS
AA-23 , RCS OVER-PRESS PROTECTION TRAIN B HI PRESS
AA-31 , RCS OVER-PRESS PROTECTION TRAIN C HI PRESS Standard: Verifies the following MCB Alarms are extinguished:
AA-22
AA-23
AA-31 Comment:

0-7, step 6.2.2 Performance Step: 2 ENSURE the PRZR PORV, PCV-430 Control Switch is in the CLOSE position. Standard:

Rotates PCV-430 control switch to the CLOSED position.
Verifies the Red light OFF and Green light ON for PCV-430 Comment:

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

Appendix C Page 5 of 9 Form ES-C-1 VERIFICATION OF COMPLETION 0-7, step 6.2.3 ,J Performance Step: 3 OPEN ACCUM TO SURGE TANK VLV SOV-8616A. (MCB Rear) Standard:

Requests LTOP key from the Shift Manager

                         * (,J) Rotates SOV-8E,16A to the OPEN position EXAMINER CUE:       Provide LTOP KEY when requested.

EXAMINER NOTE: There will not be any light indication on the MCB 0-7, step 6.2.4 ...j Performance Step: 4 ENSURE N2 ARMING VLV SOV-8619A is in the ARM position. (MCB Rear) Standard:

Uses proper key.

                        *   (,f) Rotates SOV-8619A to the ARM position EXAMINER NOTE:      There will not be any light indication on the MeB 0-7, step 6.2.5 Performance Step: 5 VERIFY CLOSED PRZR PORV, PCV-430.

Standard:

PCV-430 control switch is in the closed position.
Red light OFF and green light ON.

Comment: 0-7, step 6.2.6 Performance Step: 6 RECORD pressure indicated on OP ACCUM A N2 PRESSURE, PI-455. (MCB Rear) Standard: Pressure recorded as indicated on PI-455. EXAMINER NOTE: PI-455 will read approximately 750 psig. 2010 GINNA NRC JPM E, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of9 Form ES-C-1 VERIFICATION OF COMPLETION 0-7, step 6.2.7 Performance Step: 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.

Standard: Verifies Accumulator A pressure between 735 and 760 psig and marks step N/A. Comment: 0-7, step 6.2.8 Performance Step: 8 ENSURE CLOSED MOV 516 breaker, MCC C position 6C, VLV-516 RCS. Standard: Calls AO to verify MOV 516 breaker is closed Simulator Driver: Provide repeat back then report MOV 516 breaker, MCC C position 6C is CLOSED. EXAMINER NOTE: The breaker would be closed at this point in the plant shutdown. A quick rel;ponse from the Auxiliary Operator would be realistic. 0-7, step 6.2.9 Performance Step: 9 ENSURE OPEN PRZR PORV BLOCK VLV, MOV 516. Standard:

MOV 516, PRZR PORV BLOCK VLVis OPEN.
Red light ON and green light OFF.

Comment: 2010 GINNA NRC JPM E, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 ()f 9 Form ES-C-1 VERIFICATION OF COMPLETION 0-7, step 6.2.10 Performance Step: 10 RECORD the time Train A Overpressure Protection System is operable. Standard: Records current time. Comment: Terminating Cue: After the time is recorded or the candidate reports PCV-430 in service: Evaluation on this JPM is complete. Stop Time: _ _ _ _' 2010 GINNA NRC JPM E, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8of9 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 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 90f9 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

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 Vesse~1 Overpressure Protection System, has been completed.

INITIATING CUE: 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 5 NUREG 1021, Revision 9, Supplement 1

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

Title:

Initiate rapid boration in preparation JPM No.: 2010 GINNA NRC for proceeding to cold shutdown JPM F KIA

Reference:

004 A4.18 (4.3/4.1) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: x Classroom - - Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions:

The plant has had a reactor trip and is entering a forced outage.
Plant Management directed the RCS borated to refueling boron concentration
RCS boron concentration is 1300 PPM
Boric Acid Storage Tank concentration is 17000 ppm with a temperature of 130°F
The operating crew is performing 0-2.2, PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD CONDITIONS.
Engineering has calculated the minimum level in the BAST to be 30% and the minimum soluble temperature to preclude boron precipitation in the charging fluid to be 85°F Task Standard: Boration greater than 10 GPM established.

Required Materials: None General

References:

0-2.2, PLANT SHUTDOWN! FROM HOT SHUTDOWN TO COLD CONDITIONS, Revision 15:,00
S-3.1, BORON CONCENTRATION CONTROL, Attachment 9 RAPID BORATION, Revision 03101 Handouts:
S-3.1, BORON CONCENTPATION CONTROL, Attachment 9 RAPID BORATION, Revision 03101
A marked up copy of 0-2.2, PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD CONDITIONS, Revision 15300 2010 GINNA NRC JPM F, Revision 3 NUREG 1021, Revision 9, Supplement 1

Appendix Job Performance Measure Form Initiating Cue: Rapid boration will be used to raise boron concentration to the required value for CSD conditions and then to refueling boron concentration. The CRS directs you to perform steps 6.1.13 through 6.1.16 by establishing rapid boration at greater than 18 GPM in accordance with S-3.1, Attachment 9. Assume that operators are standing by at the required locations to perform the local tasks. Time Critical Task: No Validation Time: 12 Minutes 2010 GINNA NRC JPM F, Revision 3 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 ____________________________ VV_orkshe~e~t___________________________ SIMULATOR SETUP Reset to the IC for NRC JPM N-F. Ensure PPCS Variable Boration Dilution screen is clear. 2010 GINNA NRC JPM F, Revision 3 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 13 Form ES-C-1 VERIFICATION OF COMPLETION (Denote Critical Steps with a ~) Start Time: _ _ __ 0-2.2, step 6.1.13.1. ~ Performance Step: 1 IF a Rapid Boration method will be performed, THEN PERFORM the following to calculate the required Rapid Boration RCS boron concentration and the total amount of boric acid to be added: OTHERWISE, MARK this Step N/A.

1. VERI FY that the following requirements are satisfied:

a. All control and shutdown rods are fully inserted

b. AT LEAST one RCP running.

c. Pressurizer Backup Heaters are energized

d. Boration will continue to refueling concentration during cooldown

e. PPCS Point XFXEK will be greater than 2000 pcm for the duration of the boration to cold shutdown conditions.

Standard:

Verifies all control and shutdown rods are on the bottom using MRPI
Verifies both RCPs are running using FI-411, 412, 413, 414, 415 and 416.

                               * (~) Informs the Control Room Supervisor that the Pressurizer Backup Heaters are in AUTO vice ON by observing the handle position in the AUTO position.

References the initial conditions to determine the RCS boron concentration is going to refueling concentration.
Verifies PPCS Point XFXEK reads greater than 2000 pcm using PPCS EXAMINER CUE: When the Candidate informs the Control Room Supervisor of the position of the Pressurizer Backup Heaters, acknowledge the report and then inform them to place the Pressurizer Backup Heaters to the ON position and continue with the JPM.

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

Appendix C Page 5 13 VERIFICATION OF COMPLETION 0-2.2, step 6.1.13.2. Performance Step: 2 IF ALL the conditions in Step 6.1.13.1 are satisfied, THEN CALCULATE the required Rapid Boration RCS boron concentration as follows: OTHERWISE, MARK the Step N/A. (Rapid Boration method can NOT be used)

2075 +100 ppm= 2175 ppm Standard: Verifies step 6.1.13.2 is initialed and has an independent verification completed.

Comment: 0-2.2, step 6.1.13.3. Performance Step: 3 CALCULATE the TOTAL amount of Boric Acid to be added to reach the RCS Boron concentration determined in Step 6.1.13.2 using PPCS Variable Boration/Dilution Program OR tables. Standard: Verifies step 6.1.13.3 is initialed and has an independent verification completed. Comment: 0-2.2, step 6.1.13.4. Procedure Note: Boration should start as soon as practical after reactor shutdown to minimize schedule impacts. Performance Step: 4 INTIATE boration of the amount of boric acid calculated in Step 6.1.13.3 PER S-3.1, BClron Concentration Control Standard: Refers to S-3.1 Comment: 2010 GINNA NRC JPM F, Revision 3 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 13 VERIFICATION OF COMPLETION S-3.1, Attachment 9 Performance Step: 5 Perform S-3.1. Attachment 9. Standard:

Determines Attachment 9 is the appropriate Attachment to use.
Reviews Section 1.0 - PRECAUTIONS EXAMINER CUE: Provide S-3.1, Attachment 9.

EXAMINER NOTE: The initial conditions of this JPM have all of the required information to prevent the Candidate form performing any calculations. 5-3.1, Attachment 9, Step 2.1 Performance Step: 6 If desired, then maximize letdown flow by placing the 60 GPM orifice in service per S-3.2P, SWAPPING CVCS LETDOWN ORIFICE VALVES, Standard: Verifies 60 GPM orifice in service by observing the red light lit for AOV-202 and FI-134 indicating approximately 60 GPM Comment: 5-3.1, Attachment 9, Steps 2.2 and 2.2.1 Performance Step: 7 The Board Operator SHALL inform the CRS of the intent to change core reactivity. The CRS SHALL acknowledge the reactivity change and provide input and oversight Standard: Candidate informs CRS that he will be initiating rapid boration. EXAMINER CUE: Provide feedback on the understanding of the communication. 2010 GINNA NRC JPM F, Revision 3 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 13 Form ES-C-1 VERIFICATION OF COMPLETION S-3.1, Attachment 9, Steps 2.3 and 2.3.1 Performance Step: 8 Verify charging flow path Verify at least one char~~ing pump running Standard: 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 Comment: S-3.1, Attachment 9, Step 2.3.2 Performance Step: 9 ENSURE OPEN CHARGING VLV RHX TO LOOP B COLD, AOV-294. Standard: Verifies AOV-294, CHARGING VLV RHX TO LOOP B COLD, OPEN using the red light lit for AOV-294 Comment: S-3.1, Attachment 9, Step 2.3.3 Performance Step: 10 VERIFY CHARGING Fl.OW TO REGEN HX, HCV-142, demand set at 0% (Open) Standard: Verifies HCV-142 demand set at 0 (ZERO) %. EXAMINER NOTE: The valve is full open at ZERO demand. S-3.1, Attachment 9, Steps 2.4 Performance Step: 11 ENSURE an Operator is; stationed at the Boric Acid pumps to listen for proper pump operation. Standard: Determines AO standin~1 by per Initiating Cue. Comment: 2010 GINNA NRC JPM F, Revision 3 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 13 Form ES-C-1 VERIFICATION OF COMPLETION S-3.1, Attachment 9, Steps 2.5 Performance Step: 12 ENSURE an Operator is stationed at Seal Injection Filter to monitor differential pressure. Pressure should be less than 20 PSID on PIC-183. Standard: Determines AO standing by per Initiating Cue. SIMULATOR DRIVER: Report a value 15 PSID when requested. S-3.1, Attachment 9, Steps 2.6 Procedure CAUTION 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. Performance Step: 13 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. Standard: Contacts operator standing by at Seal Water HX and records 90 GF. SIMULATOR DRIVER: When contacted, report Seal Water HX Outlet temperature TI-120 reading 90°F and stable. S-3.1, Attachment 9, Steps 2.7 and 2.7.1 Procedure CAUTION IF seal injection is lost, THEN IMMEDIATELY RESTORE CCW (prior to Step 2.7.1) to RCP thermal barriers AND REFER to RCP Seal Malfunction, AP-RCP.1. " Performance Step: 14 ALIGN Rapid Boration flow path as follows:

CLOSE CCWfrom Rep Thermal Barrier, AOV-754A.

Standard: * <") Rotates the handswitch for AOV-754A to the closed position .

Verifies green indicating light lit for AOV-754A closed indication Comment:

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

Appendix C Page 9 of 13 Form ES-C-1 VERIFICATION OF COMPLETION S-3.1, Attachment 9, Steps 2.7.2 ..J Performance Step: 15 CLOSE CCW FROM Rep 1B THERMAL BARRIER, AOV-754B. Standard: * (..J) Rotates the handswitch for AOV-754B to the closed position .

Verifies green indicating light lit for AOV-754B closed indication Comment:

S-3.1, Attachment 9, Steps 2.7.3 Performance Step: 16 CLOSE Emergency Borate Inlet Isolation Valve to Charging Pumps, V-348B. Standard: Contacts AO to close Emergency Borate Inlet Isolation Valve to Charging Pumps, V-348B. SIMULATOR DRIVER: Repeat back order, clclse V-348B (Remote CVC28), wait a few seconds and report V-348B closed. S-3.1, Attachment 9, Steps 2.7.4 " Performance Step: 17 START one BA Transfer pump. Standard:

Candidate announces start and/or contacts AO at the BA Transfer Pump.

                        * (..J) Starts one BA Transfer Pump by rotating the handle to the START position.

Verifies red running light lit for BA transfer pump started SIMULATOR DRIVER: 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 2010 GINNA NRC JPM F, Revision 3 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 10 of 13 Form ES-C-1 VERIFICATION OF COMPLETION 8-3.1, Attachment 9, Steps 2.7.5 " Performance Step: 18 OPEN EMERG BA SUPPLY VLV, MOV-350. Standard: * ("> Rotates the handswitch for MOV-350 to the OPEN position.

Verifies the Red light lit and the Green light extinguished for MOV-350.

Comment: S-3.1, Attachment 9, Steps 2.7.6 Procedure CAUTION DURING Rapid Boration the following SHALL be monitored for proper operation:

Seal Water HX Outllet 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 LTON OUT TEMP, TI-130, to verify proper operation of NRHX LTON OUTLET TEMP (TI-130), TCV-130.
RCP (1N1B) Seal WTR Inlet TEMP (TI-1321 TI-125 (less than 140 OF)
HI RNG RCP ("lN18) Seal Leakoff (F-177/F-178) (1.0 to 5.0 GPM)
Total Boric Acid flow: (BA EMERG FLOW FI-113) AND (Boric Acid Flow), Chart Recorder
DIP Seal Injection Filter PRESS and CNTRLR (PIC-183),

Locally " Performance Step: 19 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.

SIMULATOR DRIVER: Open V-348B (Remote CVC28) in .25 increments. During JPM workup .62 = 18 GPM. 2010 GINNA NRC JPM F, Revision 3 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 11 of 13 Form VERIFICATION OF COMPLETION S-3.1, Attachment 9, Steps 2.7.7 Performance Step: 20 VERIFY Boric Acid flow. Standard: 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 3 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 12 13 VERIFICATION OF COMPLETION Job Performance Measure No.: 2010 GINNA NRC JPM F 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 F, Revision 3 NUREG 1021, Revision 9, Supplement 1

Appendix Page 1 13 JPM CUE SHEET 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
RCS boron concentration is 1300 PPM
Boric Acid Storage Tank concentration is 17000 ppm with a temperature of 130°F
The operating crew is performing 0-2.2, PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD CONDITIONS.
Engineering has calculated the minimum level in the BAST to be 30% and the minimum soluble temperature to preclude boron precipitation in the charging fluid to be 85°F INITIATING CUE: Rapid boration will be used to raise boron concentration to the required value for CSD conditions and then to refueling boron concentration. The CRS directs you to perform steps 6.1.13 through 6.1.16 by establishing rapid boration at greater than 18 GPM in accordance with S-3.1, Attachment 9. Assume that operators are standing by at the required locations to perform the local tasks.

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

Appendix C Job Performance Measure Form ES-C-1 Facility: Ginna Task No.: Task

Title:

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 (4.5/4.3) Alternate Path - Step 13.c RNO implemented to reduce the number of running CS Pumps. 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 s,imulate 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. AnothE~r board operator will respond to alarms NOT associated with the task. Time Critical Task: No Validation Time: 4 Minutes 2010 GINNA NRC ..IPM G, Revision 3 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 ~IPM G, Revision 3 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 8 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a "f) Start Time: _ _ __ E-1, Step 13.a Performance Step: 1 Monitor if CNMT Spray Should Be Stopped:

a. CNMT spray pumps - any running Standard:

Observes red light lit for each of two (2) CS pumps
Observes CS flow on FI-930 EXAMINER CUE: Provide a copy of E-1, Step 13 (Pgs. 11 and 12 of 23),

properly place-kept up to Step 13 E-1, Step 13.b Performance Step: 2 Determine number of CNMT spray pumps required from table: Standard:

Identifies that CNMT pressure is less than 4 psig on PI-945, 947, & 949 and lowering and observes 0-28, 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.

Comment: 2010 GINNA NRC JPM G, Revision 3 NUREG 1021, Revision 9, Supplement 1

Appendix 4 8 PERFORMANCE INFORMATION E-1, Step 13.c Performance Step: 3 CNMT spray pumps running - EQUAL TO NUMBER REQUIRED Standard:

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.G. RNO Comment:

E-1, Step 13.c RNO c.1) ,f Performance Step: 4 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 Standard: Rotates handles counter-clockwise and then pulls out to the locked position on the following pumps:

CS Pump A
CS Pump B Comment:

2010 GINNA NRC ~IPM G, Revision 3 NUREG 1021, Revision 9, Supplement 1

Page 5 of 8 Form ES-C-1 PERFORMANCE INFORMATION E-1, Step 13.c RNO c.2).a " Performance Step: 5 IF CNMT pressure < 4 psig, THEN perform the following:

a. Place NaOH Tank outlet valve switches to OPEN

AOV-836A
AOV-836B Standard: Rotates switches clockwise to the OPEN position .
AOV-836A
AOV-836B EXAMINER NOTE: 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 " Performance Step: 6 Reset CNMT Spray Standard: Depresses the CNMT Spray Reset PB and A-27, CNMT SPRAY, clears Comment: 2010 GINNA NRC JPM G, Revision 3 I\IUREG 1021, Revision 9, Supplement 1

Appendix Page 6 of 8 PERFORMANCE INFORMATION E-1, Step 13.c RNO c.2).c --J Performance Step: 7 Close discharge valves for idle CNMT Spray Pump:

CS pump 'A'
MOV-860A
MOV-860B
CS pump 'B'
MOV-860C
MOV-860D Standard: 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 EXAMINER NOTE: Considered critical because the intent of the step is to isolate a potential leak path out of CNMT.

Terminating Cue: After closing the four discharge valves or when the operator proceeds to Step 14: Evaluation on this JPM is complete. Stop Time: _ _ __ 2010 GINNA NRC JPM G, Revision 3 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 8 Form 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 3 I\IUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 8 Form ES-C-1 JPM CUE SHEET 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 Ie.wering 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 3 NUREG 1021. Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Facility: Ginna Task No.: Task

Title:

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

Reference:

E05 EA 1.1 (4.1 14.0) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: X Classroom - - Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions:

The plant was at power when both Main Feedwater Pumps tripped.
Bus 16 has an overcurrent fault
The operating crew is responding per FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK. No AFW Pumps can be started.

Task Standard: Both SAFW Pumps started with a flowpath to each S/G established. Required Materials: None General

References:

ATT-5.1, ATTACHMENT SAFW, Rev. 10
ATT-22.0, RESTORING FEED FLOW, Rev 00500
FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, Revision 03801 Handouts:
ATT-5.1 , ATTACHMENT SAFW
ATT -22.0, RESTORING FEED FLOW
FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK Initiating Cue: The CRS directs you to perform step 6 of FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, to feed the A S/G.

Time Critical Task: Yes 2010 GINNA NRC JPM H, Revision 4 NUREG 1021, Revision 9, Supplement 1

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

                ------------------~.          .~---------------------------

Validation Time: 6 Minutes 2010 GINNA NRC JPM H, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 WClrksheet SIMULATOR SETUP Reset to IC for NRC JPM N-H Placekeep the Control Room copy of FR-H.1 through s,tep 5. 2010 GINNA NRC JPM H, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 11 Form ES-C-1 VERIFICATION OF COMPLETION (Denote Critical Steps with a ..J) Start Time: _ _ __ FR-H.1, step 6 Performance Step: 1 Try to establish SAFW flow to at least one intact S/G:

a. Perform the following:

1) Align SAFW system for operation (Refer to ATT S.1 , ATTACHMENT SAFW)

Standard: Refers to Attachment S.1. EXAMINER ClIE: Provide a copy of ATT-5.1 EXAMINER NOTE: SAFW controls and indications are on the back of the MCa Panel. ATT-5.1, A)1) Procedure Caution: If selected S/G Wide Range Level less than SO Inches (100 Inches Adverse CNMT), then refer to Attachment 22.0, Restoring Feed Flow, prior to starting SAFW Pump. Performance Step: 2 A) Align SAFW Pump C to selected S/G as follows:

1) Ensure SI Reset Standard:

Determines S/G "AU WR level is greater than SO" by checking U-504 and U-SOS and associated recorders.
Observes K-6, THERMAL OVERLOAD RELAY BYPASSED extinguished or indicates that SI has NOT actuated EXAMINER NOTE: 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 or, in this case, has NOT actuated.

EXAMINER NOTE: Candidate may depress the SI reset pushbutton to ensure SI is reset. 2010 GINNA NRC JPM H, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 11 VERIFICATION OF COMPLETION ATT-5.1, A) 2) Performance Step: 3 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 Standard: 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 Comment:

ATT-5.1, A) 3) ..J Performance Step: 4

Open MOV-9629A, SAFW PUMP C SUCTION VLV Standard: * (..J) 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.

Comment: ATT -5.1, A) 4) Performance Step: 5 Verify at least 1 SW pump running Standard:

Returns to front of MCB and observes the Red light lit for the A, Band C Service Water pumps
Observes appmximately 55 psig on PI-2160 and 2161, SW Header Pressure.

Comment: 2010 GINNA NRC JPM H, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 11 Form ES-C-1 VERIFICATION OF COMPLETION ATT-5.1, A) Sa) Procedure Note: Perform step Sa to feed A S/G OR step 5b to feed B S/G. Performance Step: 6 To feed S/G A, go to stE!P 6. Standard: Proceeds to step 6 Comment: ATT-5.1, A) 6) Performance Step: 7 Restore SAFW flow as directed by procedure in effect. Standard: Transitions back to FR-H.1, Step 6.a.2 Comment: FR-H.1, step 6.a.2 Performance Step: 8 Determine SAFWflow requirements per ATT-22.0, ATTACHMENT RESTORING FEED FLOW Standard: Refers to ATT-22.0 Comment: 2010 GINNA NRC JPM H, Revision 4 NUREG 1021, Revision 9, Supplement 1

7 of 11 Form VERIFICATION OF COMPLETION ATT-22.0, step 1 Procedure Caution: Feed flow rates should be controlled to prevent excessive RCS cooldown and associated RCS pressure and inventory reduction. Procedure Note:

The attachment provides the desired feed flow rate when restoring feed flow to a S/G during FR-H.1
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, F0476, F0477)
S/G feedwater RTD temperature lowers (PPCS Point ID T2096, T2097)

Performance Step: 9 1. Initiate Feed flow as follows:

a. Bleed and Feed initiated or required Standard:

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 Comment:

AIT-22.0, step 1.a. RNO Performance Step: 10 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. Standard:

Determines both S/Gs Wide Range levels are greater than 50 inches
Determines the feedflow restoration rate is unlimited.
Proceeds to step 2.

Comment: 2010 GINNA NRC JPM H, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 11 Form ES-C-1 VERIFICATION OF COMPLETION ATT -22.0, step 2 Performance Step: 11 Check RCS Loop Hot Legs - BOTH HOT LEG TEMPERATURES LOWERING Standard: Determines both RCS Hot Leg Temperatures are lowering using either:

PPCS trend or
TI-409A 1 and TI-41 OA1 meter indications on the MCB Comment:

A TT -22.0, step 3 Performance Step: 12 Verify affected S/G is not faulted or ruptured Standard:

Verifies both S/Gs pressures are:
Greater than 110 psig using PI-468, 469, 482A, 478, 479 and 483A on MCB
Not depressurizing in an uncontrolled manner
Verifies R-15, 19, 31 and 32 are not on alarm
Verifies S/G levels are not rising in an uncontrolled manner.
Transitions back to FR-H.1, Step 6.a.3.

Comments: FR-H.1, step 6.a.3 ,f Performance Step: 13 Start selected SAFW pumps Standard: * (,f) 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 EXAMINER NOTE: The Candidate will be unable to start the 0 SAFW pump since Bus 16 has an overcurrent fault.

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

Appendix Page 9 of 11 VERIFICATION OF COMPLETION FR-H.1, step 6.a.4 Performance Step: 14 When intact S/G level GREATER THAN 50 inches (100 inches adverse CNMT), THEN verify SAFWflow GREATER THAN 215 GPM. Standard: Verifies flow GREATER THAN 215 GPM but LESS THAN 280 GPM per pump on FI-4084B. Comment: Terminating Cue: After SAFW flow is verified: Evaluation on this ..IPM is complete. Stop Time: _ _ __ 2010 GINNA NRC JPM H, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix 1 11 Form 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 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 11 of 11 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

The plant was at power when both Main Feedwater Pumps tripped.
Bus 16 has an overcurrent fault
The operating crew is responding per FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK. No AFW Pumps can be started.

INITIATING CUE: The CRS directs you to perform step 6 of FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, to feed the A S/G. 2010 GINNA NRC JPM H, Revision 4 NUREG 1021, Revision 9, Supplement 1

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

Title:

Release the "0' Gas Decay Tank ~IPM No.: 2010 GINNA NRC JPM I KIA

Reference:

071 A4.27 (4.4/4.0) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: x Actual Performance: Classroom - - - Simulator - - - Plant X READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions:

Today is 4/26/2010.
The "0' GDT is full and approved for release.
The"O'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. 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"O' GDT per S 4.2.5, Release of Gas Decay Tank. The Extra Auxiliary Operator will remove the required tagouts and complete the necessary paperwork. Simulate all actions; do not manipulate any equipment. Time Critical Task: No 2010 GINNA NRC JPM I, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Validation Time: 11 Minutes 2010 GINNA NRC JPM I, Revision 4 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 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 10 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a -Y) Start Time: _ __ 5-4.2.5, Section 1, 2, 3 and 4 Performance Step: 1 Reviews Sections 1, 2, 3 and 4 Standard: Reviews sections 1, 2, 3 and 4 Evaluator's Cue: Provide the candidate with the JPM I Handout (a copy of the procedure completed up to Section 5). 5-4.2.5, Section 5 Performance Step: 2 INSTRUCTIONS: 5.0.1 This procedure is divided into the following sections: N/A sections for tanks not to be released. 5.1 GOT A Release 5.2 GOT B Release 5.3 GOT C Release 5.4 GDT D Release Standard: Marks Sections 5.1, 5.2 and 5.3 as N/A Comments: 2010 GINNA NRC JPM I, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 10 Form ES-C-1 PERFORMANCE INFORMATION 5-4.2.5, Section 5.4 Performance Step: 3 GOT 0 Release: 5.4.1 Close inlet AOV to 0 GOT PCV-1039A. Standard: Verifies PCV-1039A GREEN light is lit and initials the step. EXAMINER CUE: A Caution Tag is installed on the switch. (There may actually be a caution tag on the switch if the 0 GOT is being held for release.) EXAMINER CUE: After the switch is located: The Green light for PCV-1039A is LIT. EXAMINER NOTE: The switch is on the Waste Panel S-4.2.5, step 5.4.2 Performance Step: 4 Close GOT 0 Reuse Control AOV. Standard: Verifies the switch for AOV-1632 is in the CLOSED position (GREEN light) and initials step. EXAMINER CUE: After the switch is located: The Green light for AOV-1632 is LIT. EXAMINER NOTE: The switch is on the Waste Panel S-4.2.5, step 5.4.3 Performance Step: 5 Close GOT 0 outlet AOV to Gas Analyzer PCV-10398. Standard: Verifies the GREEN light lit for PCV-10398 and initials step. EXAMINER CUE: After the switch is located: The Green light for AOV-10398 is LIT. EXAMINER NOTE: The switch is on the Waste Panel 2010 GINNA NRC JPM I, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 10 Form ES-C-1 PERFORMANCE INFORMATION S-4.2.5, step 5.4.4 Performance Step: 6 Lock closed GOT rnanual outlet valves on all tanks.

                             *   (GOT A) V-1617 Locked Closed _ _
                             *   (GOT B) V-1618 Locked Closed _ _
                             *   (GOT C) V-1619 Locked Closed _ _
                             *   (GOT 0) V-1620 Locked Closed _ _

Standard: Verifies the following valves are locked closed and initials:

V-1617 _ _
V-1618 _ _
V-1619 _ _
V-1620 _ __

EXAMINER NOTE: 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. EXAMINER NOTE: 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. EXAMINER CUE: For each valve, the locks are locked and the valves do not rotate in the clockwise direction. EXAMINER CUE: If asked, the eSoms location for these valves are Aux BLO Intermediate level GOT alley 5' (V-1617 and 1618) and l' (V 1619 and 1620) elevation. 5-4.2.5, step 5.4.5 Performance Step: 7 Close GOT release AOV to Plant Vent via Charcoal Filter RCV 14. Standard:

Simulates rotating knob for RCV-14 Clockwise direction
Observes Green light lit.
Observes air pressure reads 0 psig on the air pressure gauge.

EXAMINER CUE: The knob does not rotate in the clockwise direction. EXAMINER NOTE: The switch is on the Waste Panel 2010 GINNA NRC JPM I, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 10 Form ES-C-1 PERFORMANCE INFORMATION S-4.2.5, step 5.4.6 Performance Step: 8 Remove Hold on V-1620. Standard: Verifies the hold on V-1620 is removed and step initials. EXAMINER CUE: The Extra Auxiliary Operator has removed the Danger Tag and completed the necessary paperwork. S-4.2.5, step 5.4.6.1 ..J Performance Step: 9 Unlock and open GOT D manual outlet valve. Standard:

Describes unlocking V-1620
Simulates rotating V-1620 in the Counter Clockwise direction EXAMINER CUE: After the candidate describes lock removal: The Lock is removed.

EXAMINER ClIE: The valve no longer rotates in that direction. S-4.2.5, step 5.4.7 ..J Performance Step: 10 Throttle open GOT release AOV to Plant Vent via Charcoal Filter RCV-014 (may be full open) to desired release rate. Standard:

H) Simulates rotating knob for RCV-14 Clockwise
Observes both RED and GREEN light lit.
Observes air pressure rising on the air pressure gauge.

EXAMINER CUE:

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

Appendix C Page 8 of 10 Form ES-C-1 PERFORMANCE INFORMATION S-4.2.5, step 5.4.8 Performance Step: 11 Notify Control Room that GOT 0 release has been initiated.

GOT 0 Pressure _ _
Time Control Hoom Notified _ _

Standard:

Reads PI-1039
Records pressure in the 0 GOT
Simulates contacting control room and records the time.

EXAMINER CUE: o GOT pressure indicates as indicated. EXAMINER CUE: When the control room is contacted: Provide a repeat back. Terminating Cue: When the Candidate records 0 GOT pressure: This JPM is complete. Stop Time: _ _ _' 2010 GINNA NRC JPM I, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 9 of 10 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2010 GINNA NRC JPM I 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 I, Revision 4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 10 ()f 10 Form ES-C-1

                                     ~IPM  CUE SHEET INITIAL CONDITIONS:

Today is 4/26/2010.
The "0' GDT is full and approved for release.
The "0' GDT does not have elevated activity.
The previous crew has started S-4.2.5.

INITIATING CUE: The Control Room Supervisor directs you to release the "0' GDT per S-4.2.5, Release of Gas Decay Tank. The Extra Auxiliary Operator will remove the required tag outs and complete the necessary paperwork. Simulate all actions; do not manipulate any equipment. 2010 GINNA NRC JPM I, Revision 4 NUREG 1021, Revision 9, Supplement 1

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 JPMJ KIA

Reference:

APE067 AA1.05 (3.0/3.1) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: x Actual Performance: Classroom - - - Simulator Plant X READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions:

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 Vent!ilation 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. Simulate all actions; do not manipulate any equipment. 2010 GINNA NRC JPM J, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: No Validation Time: 8 Minutes 2010 GINNA NRC JPM J, Revision 5 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 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 11 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a -J) Start Time: _ __ FRP-5.0, step 1.5 Procedure Note: Securing AB Exh G will cause automatic shutdown of A AHU and B supply. Turning the master switch to OFF will secure other fans listed: -J Performance Step: 1 Ventilation: 1.5.1 Upon conformation of any fire in the Auxiliary Building, secure the following (***). S'NiTCH BUS/MCC/LP POSITION

                             *** AB Exh C       Local              D                   3M Standard:

Simulates rotating the AB Exh C switch to STOP
Verifies the RED light is extinguished.

EXAMINER NOTE: These Performance Steps may be performed in any order. EXAMINER NOTE: The switch is located on the AB Exh C fan housing on the Intermediate Building (Hot Side) Top Level. EXAMINER NOTE: When the Candidate turns off AB Exh C the AS Supply A AHU and the AB B Supply fan will deenergize. If the Candidate realizes this, they may skip Performance Step 2. EXAMINER NOTE: (***) Identifies the fans that must be secured to ensure ventilation is secured to the area. EXAMINER CUE: RED light is extinguished. 2010 GINNA NRC "IPM J, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page S of 11 Form ES-C-1 PERFORMANCE INFORMATION FRP-S.O, step 1.S.1 Performance Step: 2 Upon confirmation of any fire in the Auxiliary Building, secure the following (***). BUS/MCC/LP POSITION

                        *** AB Supply A AHU Vent Panel          13                  BC AB B Supply          Vent Panel           C                  SF Standard:              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. EXAMINER NOTE: The switch is located at the Auxiliary Building Ventilation Panel in the Intermediate Building (Hot Side) Middle Level. EXAMINER NOTE: This is a common switch for both the AB Supply A AHU and AB B Supply fans. EXAMINER NOTE: 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. EXAMINER CUE: 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 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 11 Form ES-C-1 PERFORMANCE INFORMATION FRP-5.0, step 1.5.1 Performance Step: 3 Upon conformation of ~ny fire in the Auxiliary Building, secure the following (***). FAN ~SWITCH BUS/MCC/LP POSITION IB Exh. NB Local FID 4B/3F IP Exh. C Local (IB cold) F 4D CA Exh. NB Vent Panel F/D 2K12H AB Exh. F I_ocal ACPDPAB02 12 Standard: Simulates rotating the AUX BLDG EXH FANS MASTER CONTROL Switch to the OFF position. OR Simulates rotating the following switches to the OFF position:

IB Exh. NB
IP Exh. C
CA Exh. NB
AB Exh. F EXAMINER NOTE: 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.

EXAMINER NOTE: The Master Control Switch is located at the Auxiliary Building Ventilation Panel in the Intermediate Building (Hot Side) Middle Level. EXAMINER NOTE: 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. EXAMINER CUE: The switch is in the OFF position. 2010 GINNA NRC JPM J, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 11 Form ES-C-1 PERFORMANCE INFORMATION FRP*5.0, step 1.5.1 Procedure Note: 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.

j Performance Step: 4 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 Standard:             Simulates rotating the AUX BLDG MAIN EXH FAN A switch to STOP.

OR Verifies the GREEN light is lit for the AUX BLDG MAIN EXH FAN A EXAMINER NOTE: The switch is located at the Auxiliary Building Ventilation Panel in the Intermediate Building Middle Level. EXAMINER NOTE: For Performance Steps 4 and 5: Either the AB Main Exh. A or AB Main Exh B. fans will be running. The Candidate will only be required to secure one fan. The Candidate is expected to just verify the other fan is not running by observing the GREEN light is lit. EXAMINER CUE: After either rotating the switch to the STOP position or if the fan was initial tripped and the Candidate is verifying the fan not running: GREEN light is lit 2010 GINNA NRC JPM J, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 11 Form ES-C-1 PERFORMANCE INFORMATION FRP-5.0, step 1.5.1 .y Performance Step: 5 Upon conformatior[ of any fire in the Auxiliary Building, secure the following (***). FAN SWITCH BUS/MCC/LP POSITION

                        *** AB Main Exh. 8 Vent Panel           11B                23 Standard:             Simulates rotating the AUX BLDG MAIN EXH FAN B switch to STOP.

OR Verifies the GREEN light is lit for the AUX BLDG MAIN EXH FAN B EXAMINER NOTE: The switch is located at the Auxiliary Building Ventilation Panel in the Intermediate Building Middle Level. EXAMINER NOTE: For Performance Steps 4 and 5: Either the AB Main Exh. A or AB Main Exh B. fans will be running. The Candidate will only be required to secure one fan. The Candidate is expected to just v'erify the other fan is not running by observing the GREEN light is lit. EXAMINER CUE: After either rotating the switch to the TRIP position or if the fan was initial tripped and the Candidate is verifying the fan not running: GREEN light is lit FRP-5.0, step 1.5.1 .y Performance Step: 6 Upon conformation of any fire in the Auxiliary Building, secure the following (***). FAN SWITCH BUS/MCC/LP POSITION

                        *** G Fan            Local             14                  21A Standard:             Simulates rotating the G Fan switch to TRIP EXAMINER NOTE:        The switch is located at the G Fan Control Panel in the Auxiliary Building Top Level.

EXAMINER CUE: If asked, inform the Candidate conditions permit you to transit to the fan's control switch. Terminating Cue: When the Candidate secures the G Fan: Evaluation on this JPM is complete. 2010 GINNA NRC JPM J, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 9 of 11 Form ES-C-1 PERFORMANCE INFORMATION Stop Time: _ __ 2010 GINNA NRC JPM J, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 10 of 11 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2010 GINNA NRC JPM J 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 J, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 11 of 11 Form ES-C-1 JPM CUE SHEET 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 (AS) Intermediate Floor.
Auxiliary Building Ventilation system is in operation.
All equipment required to enter the Auxiliary Building has been donned.

INITIATING CUE: The Shift Manager has directed you to secure ventilation in accordance with FRP-5.0, Step 1.5. Simulate all actions; do not manipulate any equipment. 2010 GINNA NRC JPM J, Revision 5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 1 of 7 Form ES-C-1 PERFORMANCE INFORMATION Facility: Ginna Task No.: 039-008-01-04A Task

Title:

Locally Operate the ARVs JPM No.: 2010 GINNA NRC JPM K KIA

Reference:

039 G2.1.30 (4.4/4.0) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: x Actual Performance: Classroom --- Simulator Plant X READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions:

You are the Head Control Operator
The plant has experienced an uncontrollable Control Room Complex fire.
The crew preformed the required actions of AP-CR 1, CONTROL ROOM INACCESSIBILITY, and transitioned to ER-FIRE.1, ALTERNATE SHUTDOWN FOR CONTROL CONPLEX FIRE.
You have completed Attachment 3, HEAD CONTROL OPERATOR (HCO)
The Shift Manager is ~)tabilizing the plant in MODE 3.
All the required Appendix R equipment has been retrieved from the Appendix R locker outside the Control Room.

Task Standard: Locally operate the ARV in accordance with the procedure. Required Materials: Hard Hat, Safety Glasses, Hearing Protection, Safety Shoes and Dosimetry. General

References:

ER-FIRE.1, ALTERNATE SHUTDOWN FOR CONTROL COMPLEX FIRE, Revision 2900
P-1S.2, DUMP STEAM THROUGH ARV'S LOCALLY, Revision O.

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

Appendix C Page 20f7 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. Simulate all actions; do not manipulate any equipment. Time Critical Task: No Validation Time: 5 Minutes 2010 GINNA NRC ..IPM K, Revision 3 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 7 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a -V) Start Time: _ _ __ P-1S.2, Step 2.1 Performance Step: 1 Obtain radio and establish communications with the Control Room. Standard: Establish radio communication with Shift Manager. EXAMINER NOTE: 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. EXAMINER NOTE: The Candidate may not perform this step since a communications check was completed earlier in ER-FIRE.1. P-1S.2, Step 2.2 Performance Step: 2 Obtain Ladder if needed. Standard: Verifies a ladder is in place at V-3411. EXAMINER NOTE: A ladder is normally in place to allow access to the valve. P-1S.2, Step 2.3 -V Performance Step: 3 Operate the handwheel on the "A" ARV (3411) to position valve as required by Control Room personnel. Standard: Simulates turning the "A" ARV (3411) handwheel in the counter clockwise direction to position the valve to approximately three full turns open. EXAMINER CUE: The handwheel turned as desired. 2010 GINNA NRC JPM K, Revision 3 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION P-15.2, Step 2.1 Performance Step: 4 Report action to Shift Manager. Standard:

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.

EXAMINER NOTE: If the radio call is made from the Main Steam Area: "I cannot hear you over the background noise". EXAMINER CUE: Acknowledge the report and then direct the Candidate to, "Slowly throttle closed the valve 1 full turn." P-15.2, Step 2.3 Performance Step: 5 Operate the handwheel on the "A" ARV (3411) to position valve to two full turns open. Standard: Simulates turning the handwheel in the clockwise direction on the "A" ARV (3411} to position valve to two full turns open. EXAMINER CUE: The handwheel will not turn. P-15.2, Note prior to Step 2.3 ~ Performance Step: 6 If the ARV will not close, isolate the ARV with its root isolation. Standard: Proceeds to "An ARV Root Isolation Valve (V3507) and simulates closing the valve fully by rotating the handwheel in the clockwise direction. EXAMINER CUE: The handwheel turned as desired. EXAMINER CUE: If asked, the eSoms location for this valve is 18 Cold Mezzanine Steam Header A Area, 6' Elevation 2010 GINNA NRC JPM K, Revision 3 NUREG 1021, Revision 9, Supplement 1

Appendix C Pa~le 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION P-1S.2, Step 2.1 Performance Step: 7 Report action to Shift Manager. Standard:

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.

EXAMINER NOTE: If the radio call is made from the Main Steam Area: "I cannot hear you over the background noise". Otherwise, provide a repeat back. Terminating Cue: After the Candidate reports to the Shift Manager: Evaluation on this JPM is complete. Stop Time: 2010 GINNA NRC JPM K, Revision 3 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 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 JPM K, Revision 3 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

You are the Head Control Operator
The plant has experienced an uncontrollable Control Room Complex fire.
The crew preformed the required actions of AP-CR.1 ,

CONTROL ROOM INACCESSIBILITY, and transitioned to ER-FIRE.1, ALTERNATE SHUTDOWN FOR CONTROL CONPLEX FIRE,

You have completed Attachment 3, HEAD CONTROL OPERATOR (HCO)
The Shift Mana'ger 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.

INITIATING CUE: The Shift Manager directs you to locally open the A Atmospheric Relief Valve, V-341'1, three turns per P-1S.2. Simulate all actions; do not manipulate any equipment. 2010 GINNA NRC JPM K, Revision 3 NUREG 1021, Revision 9, Supplement 1

Scenario Event Description NRC Scenario 1 Facility: Ginna Scenario No.: 1 Op Test No.: N10-1 Examiners: Operators: (SRO) (RO) (BOP) Initial Conditions: I 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 i 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. . Turnover: i The following equipment is Out-Of-Service: The B AFW Pump is OOS for Bearing i I Replacement. Event Malf. Event Type* Event No. No. Description 1 NA N-BOP Shift Electric Plant N-SRO 2 EDS07B C-RO Loss of B Instrument Bus C-BOP C(TS)-SRO 3 PZR02D I-RO Pressurizer Pressure (PT-449) fails High i I(TS)-SRO 4 TUR05E R-RO Main Turbine High Vibration/EHC control failure - I TUR09D C-BOP C-SRO 5 FDW09A

M-RO Feed Line Rupture InsideContamment M-BOP I

I M-SRO 6 TUR02 NA Main Turbine Failure to Auto 1"ril 7 RPS07K C-BOP A AFW Pump Fails afte start 8 REM NA TDAFW Pump overspeed trip i FDW32 9

OVR C-RO Standby AFW fails to function FDW42A FDW15B I

            *  (N)ormal,     (R)eactivity,   (I)nstrument,      (C)omponent,      (M)ajor I
                                                        - 2

Scenario Event Description NRC Scenario 1 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 andlor 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 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 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 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. 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.

- 3

Scenario Event Description NRC Scenario 1 The scenario will terminate at Step 9 of E-2, after the crew has determined that a transition to E ": Loss of Reactor or Secondary Coolant, is required. Critical Tasks: FR-H.1 Establish feedwater flow into at least one Steam Generator before Res 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).

-4

Scenario Event Description NRC Scenario 1 SIMULATOR OPERATOR INSTRUCTIONS o Reset to Temp IIC 176 (NRC 1). 49% power BOL T=O, TUR02, Turbine fails to Auto trip To take B MDAFW pump OOS:

Pull stop the B MDAFW pump
Inset OVR-DO-FDW-1SA, OFF (Green light OFF)
Place PROTECT tags on A MDAFW and TDAFW pumps Insert MALF RPS07K (Autostart failure of A MDAFW pump)

Insert FDW20A (AOV-3995 fails to Close on SI) Insert OVR-DI-FDW42D = FALSE (MOV-9629A CLOSED, unable to OPEN) Insert MALF FDW15B (SAFW pump D failure) Set Trigger 30 = True when a reactor trip signal is received from either Train Set REM FDW32, Severity = 0, T-30 (Trip valve 3652 trips to simulate overspeed condition on TDAFW pump)

Set Trigger 29 to x06i236b = 1 to activate when A MDAFW pump manually started Insert MALF FDW11A, T-29 (A MDAFW pump trip on manual start switch) MALF EDS07B, on T-1 MALF PZR02D, 2500,0 Ramp. on T-2 MALF TUR05E, 10 Mils, 60 second Ramp on T-3 MALF TUR09D, on T-3 (120 second Delay) MALF FDW09A, 2E+7. 120 second Ramp, on T-4 o Prior to Crew Briefing RUN Hang Protective Tags on the A MDAFW Pump and the TDAFW Pump Steam Supply Valves. o Crew Briefing

Assign Crew Positions based on evaluation requirements
Review tne 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 in Sections 6.4.3 are marked NA

-5

-~.----- Scenario Event Description NRC Scenario 1 At direction of Event 1 Shift Electric Plant 0 examiner At direction of Event 2 Loss of B Instrument Bus 0 examiner Trigger #1 EDS07B At direction of Event 3 PT-449 fails High 0 examiner Trigger#2 2500, No Ramp PZR02D At direction of Event 4 Main Turbine High Vibration/EHC control failure 0 examiner Trjgger#3 10 mils, 60 second Ramp TUR05E TUR09D 120 second delay At direction of Event 5 Feed Line Rupture Inside Containment 0 examiner Trigger #4 2E+7, 180 second Ramp FDW09A Continued Event 6 Main Turbine Failure to Auto Trip from Event 5 T=O NOTE:: This Malfunction is inserted in the IC at T = O. TUR02 D Continued Event 7 A AFW Pump Fails after start from Event 5 T=O NOTE: This Malfunction is inserted in the IC at T = O. RPS07K T-29 (When pump manually started) 0 Continued I Event 8 TDAFW Pump overs peed trip from Event 5 T=O NOTE: This Malfunction is inserted in the IC at T = O. REM -FDW32 0%, T-30 (Rx Trip from either Train) Continued Event 9 Standby AFW fails to function D from Event 5 T=O NOTE: This Malfunction is inserted in the IC at T = O. OVR-FDW42A FALSE (MOV-9629A CLOSED, unable to OPEN) FDW15B (SAFW pump D failure) Terminate the scenario upon direction of Lead Examiner

-6

Appendix D Operator Actio,..:..n~_ _ _ _ _ _ _.. :. F. .:. o.;. .rm.;. . . ,; ;E; . ;S;. .-;. .D. .; -2;;. . Test No.: N10-1 Scenario # 1 Event # Page 7 of 51

                                                                 ----------                                         --~I

Description:

Shift Electric Plant ~ I Shortly after taking the watch, the operator will shift the Electric line-up from 50/50 to ' 01100 in accordance with 0-6.9.2, Establishing andlor Transferring Offsite Power to Bus , 12A112B. Booth Operator Instructions: NA Available: NA (1.) VERIFY CLOSED CI 7T1352 34 KV BUS. (2.) TURN ON BUS 12B ALT FROM 7T, 52/12AX SYNCHROSCOPE (3.) CLOSE BUS 12B ALT 7T,52/12AX. (4.) IF BUS 12B NORMAL FEED FROM 767, 52!12BX was previously closed, THEN PERFORM the following: IF NOT , THEN MARK t h'IS Su bstep N/A

a. VERIFY BUS 12B NORMAL FEED FROM 767, 52/12BX OPENS. (Green AND White light indication is expected.)

b. PLACE BUS 12B NORMAL FEED FROM 767, 52/12BX Control switch to thl3 TRIP i i position AND THEN to AUTO.

         ,                                                             I I

(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 VOL TMETER 4160 V. i i I

Appendix 0 Operator Action Form ES-O-2 Op Test No.: Nl0-1 Scenario # Event # _ _ _ _ _ Page 8 of 51

                                                                                      --'---I Event Descriptior:         Shift Electric Plant (8.) TURN OFF BUS 12B ALT FEED FROM 7T, 52/12AX SYNCHROSCOPEANDREMOVE 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 0 Operator Action Form ES-D-2

                 - - Scenario #

N10-1 1 Event # 2

                                                              ~--------

Page 9 of 51

                                                                                               ~~I 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.

   ~-          ~

I Booth Operator Instructions:

                                   .                        ---------------1 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 (LT-112) fails low causing continuolls 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 AR-E-14, LOSS B INSTR BUS

1. Restore power to Instrument (Refer to ER-INST.3.

BUS POWER CRS 2. Evaluate plant conditions to determine if additional action is required by referring to the following: 3.8.8

3. Notify the following: . NOTE: The CRS may notify o SM i theWCC.

o Electricians

Booth Instructor: as WCCS, acknowledge.

NOTE: The CRS will go to ER INST.3.

Appendix 0 Operator Action Form ES-O-2 Op Test No.: N10-1 Scenario # Event # 2 Page 10 of 51

                                                                ~--------                           ~--~

. Event

Description:

Loss of B Instrument Bus ER-INST.3, INSTRUMENT BUS POWER RESTORATION co (Step 4.1.1) Verify an alternate power supply is available by checking supply voltage as follows:

-.J Maintenance- Supply voltage approximately 120 volts (EI1CVTAUX, above lnstr Bus D)

                                                               ------~------------------~
~r (Step 4.1.2) Close letdown isolation valve,    : NOTE: The HCO will isolate AOV-427.                                         Normal Letdown.                 i NOTE: VCT level indication is  I lost, and with UD isolated,

actual level is lowering, and I' CRS should direct AO to monitor VCT level locally (no ER-INST.3 procedure

                                                                       , guidance) i I

i HCO (Step 4.1.3) Place charging pump controllers I NOTE: The HCO will place in MANUAL . Charging Pump speed control in Manual. (Step 4.1.4) Place hotwelilevel controller to manual, if desired. HCO (Step 4.1.5) Place PRZR PRESS CONTROLLER 431K in MANUAL, if necessary. i HCO (Step 4.1.6) Place rods in MANUAL. NOTE: The HCO will place Rods in Manual. CRS

                     .I   (Step 4.1.7) Transfer Instrument Bus to an available power supply. (Maintenance or NOTE: The CRS will direct the bus to be energized from the L   .---~---

I Normal) Maintenance supply

                                                                -----~--------------------~

Appendix D Operator Action Form ES-D-2 N10*1 Scenario # Event # Loss of B Instrument Bus o Unlocks A, C, & D cabinets to ensure no other instrument busses are on the Maintenance supply o Unlocks B cabinet, and shifts NOTE: Instrument Bus B is maintenance bus supply breaker i now re-energized forcibly to the right (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 co              4,1.9) Go to Step 4.4

'" ,. HCO ,(Step 4.4.1) Verify one _~TO, IF desired, EE i

~".

I ~o HCO (Step 4.4.2) Verify PRZR PRESS CONTROLLER 431 K in AUTO (step 4.4.3) IF letdown isolation valve, AOV

                                                                         -t".

I [427 has been closed, THEN restore Letdown r-----1 I, as follows: ------+,-------------, I ,HCO (Step 4.4.3,1) Complete removal of normal I NOTE: Removed per Section

 .             'I        "  letdown from service per S-3,2E, PLACING i 5.2 of S-3.2E i

IN OR REMOVING FROM SERVICE i

 !                        !  NORMAL LETDOWN/EXCESS LETDO~
 ~.             I        I                                                   'I* -N-O-T-E-:-T-he-C-R-S-w-j-II-ha-n-d-t-hi-s-'

I : . . off to the HCO or the CO, \'

  ;-S-.3-.2-E-"-:P-LA-CING IN      OR REMOVING FROM SERVICE NORMAL LETDOWN/EXCESS'

Appendix D Operator Action Form ES-D-2 N10-1 Scenario # 1 Event # Loss of B Instrument Bus (Step 5.2.2) Close Letdown Orifice isolation valves AOV--200A Closed AOV-200B Closed AO\l-202 Closed (Step 5.2.3) Close LTON RHR to NRHX AOV-427. HCOI 5.2.4) Reduce charging flow CO closed charging flow to

                      ",,,.:'n""-:::OTI\/(> Heat Exchanger
                    "'..,.,'"' >20" RCP labyrinth seal ~P. Shift to Charging Pump operations if (Step 5.2.6) Place NRHX LTON OUTLET TEMP (TI-130) TCV-130 in MANUAL/CLOSED INSTRUMENT BUS POWER RESTORATION

tt CRS (Step 4.4.3.2) Restore normal letdown per S- NOTE: Restored per Section 3.2E, PLACING IN OR REMOVING FROM 5.3 of S-3.2E

       ,             SERVICE NORMAL LETDOWN/EXCESS                                                      .
            -~I****
                  'LETDOWN.                                                                             .

! , NOTE: The CRS will hand this I

                  .                                                        off to the HCO or the CO.

, S-3.2E, PLACING IN OR REMOVING FROM SERVICE NORMAL LETDOWN/EXCESS LETDOWN

Appendix D Operator Action Form ES-D-2 N 10-1 Scenario # Loss of B Instrument ~ r~.-.:: ~-.:~~ ~ =):;~~l~-:~:~:_,-~*w'=:l~l~3-,">~~l~ --',_ ~ ~ ,~"" "" 7'~- ...> t

    ~~--::;.£_--~~-- ~-~~-~=--------~                                         .
                                                                  -~~~~ ~~~-- -~~---~ -~~-~ -~~-~

HCOI * (Step 5.3.1) Determine if a flush is required. NOTE: Since letdown has CO If the letdown line has been isolated for less been isolated ONLY a few than one hour perform section !;.3.2 and N/A minutes, a flush will NOT be section 5.3.3 with permission of the Shift required. Manager or Control Room Foreman. I i HCOI (Step 5.3.2) Restore Letdown Without a i CO Flush (Step 5.3.2.1) Ensure letdown is secured per CO Step 5.2 prior to restoring. I (Step 5.3.2.2) If charging flow path to Loop B I COLD leg is desired (preferred method) ,

                    ! perform the following:

i I I i HCOI (Step 5.3.2.2.1) Ensure charging CO Loop B Hot, AOV-392A is closed. HCOI (Step 5.3.2.2.2) Open charging ! CO

B Cold, AOV-294. I I

HC01-j (Step 5.3.2.3) If Charging flowpath to Loop B I NOTE: Charging alignment to I CO . HOT leg is desired, .....

the Hot Leg will NOT be I I [ desired.

HCOI ! (Step 5.3.2.4) Start a second Charging Pump

                    '1 CO     !  at minimum speed.

I

 '--'--+-H-C-O/         (Step 5.3.2.5) Slowly open charging flow to CO        Regenerative Heat Exchanger HCV-142 to
                     . reduce labyrinth seal .1P to -40".

I-*-~--- --------+------------------~

                      * (Step 5.3 2.5.1) Adjust Charging Pump speed to establish -40" labyrintl seal .1P with HCV-142 full open.                                    ,                                    I I

Appendix D Operator Action Form ES-D-2 Op Test No.: N10*1 Scenario # Event # 2 Page 14 of 51

                                                           ~--------                        ~~I Event

Description:

Loss of B Instrument Bus (Step 5.3.2.5.2) Establish ~20 gpm charging line flow. i HCOI (Step 5.3.2.7) Place Low CO PRESS PCV-135 in MANUAL 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 valve CO RHR to NRHX AOV-371. (Step 5.3.2.9) Place LTON LEG TO RHX AOV-427 to to AUTO. HCOI desired Letdown orifice

valve AOV-200A, 2008, or 202 (proceed to next step without delay).

(Step 5.3.2.11) Adjust LOW PHESS PRESS PCV-135 to achieve Let,doviln pressure of -250 psig on PI-1 (Step 5.3.2.12) Place LOW PRESS LTON PRESS, PCV-135IN AUTO. (Step 5.3.2.13) Place NRHX LTDN OUTLET TEMP (TI-130) TCV-130 in AUTO at the setpoint. 5.3.2.14) Place (Charging Pump) in AUTO. NOTE: The CRS will continue with ER-INST.3, Step 4.4.4.

Appendix D Operator Action Form ES-D-2 N10-1 Scenario # Event # 2 Page 15 of

                                                         ~----

Loss of B Instrument Bus ER-INST.3, INSTRUMENT BUS POWER RESTORATION (Step 4.4.4) Restore EH control to AUTOIlIVIP IN, IF desired. (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 is reset. Verify hotwell level if desired. CO (Step 4.4.8) Restore desired SW pump alignment. 4.4.9) Ensure motor fire pump breaker 4.4.10) Dispatch an AO to verify proper NOTE: The CRS will dispatch of battery chargers if necessary. an AO. Booth Instructor: as AO, acknowledge. HCOI (Step 4.4.11) Evaluate MCB annunciator NOTE: Annunciators E-20, F CO status (refer to AR procedures) 6, and K-32 need followup 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 skid. recognize pump is off due to loss of Inst. Bus and restart Pump.

Appendix D Operator Action Form ES-O-2 N10*1 Scenario # Loss of B Instrument pressure. NOTE: Entry into AP-PRZR.1 Go to AP-PRZR.1, if necessary is NOT necessary. The HCO will recognize HTR TRIP due to loss of Instr. Bus and Reset. i NOTE: The CRS will continue AR*K-32, SG BLOWDOWN TANK HIGH LEVEL

1. Direct AO to remove and restore Blowdown per T-14.

Blowdown System Operation ER*INST.3, INSTRUMENT BUS POWER RESTORATION CRS i CRS (Step 4.4.13) IF Instrument Bus A or C is Instrument Bus A or C I ~_

  ~+__AC        b_ei_n_g_p_ow_e_r_e_d_fr_om_a_s_so_c_ia_te_d_e_m_e_r_!~.e Bus, then ... ...

__n_.c..._y~lf-i_S_N_O_T_b_e_in_g_p_o_w._e_re_d_f_or_m_---l

                                                                                       ' the I       I CRS  I (Step 4.4.14) Return to procedure or I
   ~            guidance in effect.
                                                                      --~l-N-O-T-E-:-T-h-e-C-R-s-w-i-II-ad-d-r-es-s~

the Technical Specifications. I I... ! _-"--I- - - - - - - - 1 I TECHNICAL SPECIFICATION 3.8.7, AC INSTRUMENT BUS SOURCES - MODES 1, 2,3 AND 4

Appendix D Operator Action Form ES-D-2 Test No.: Nl0*l Scenario #

Description:

Loss of B Instrument LCO 3.8.7 The following AC instrument bus power sources shall be OPERABLE: a) Inverters for Instrument Buses A and C; and b) Class 1E constant voltage transformer (CVT) for Instrument Bus B. Instrument g~sE~~BLE U status. TECHNICAL SPECIFICATION 3.8.9, DISTRIBUTION SYSTEMS - MODES 1, 2, 3 AND4 LCO 3.8.9 Train A and Train B of following electrical power distribution subsystems shall be OPERABLE: a) AC power; b) AC instrument bus power; and c) DC power and 4.

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

Description:

Loss of B Instrument Bus B. One AC B.1 Restore AC :2 hours. Instrument bus Instrument bus electrical power electrical power distribution distribution train train to inoperable. OPERABLE status. L _____ At the discretion of the Lead Examiner move to Event #3.

Appendix D Operator Action Form ES-D-2 lap Test No.:

                    - Nl0*l   Scenario #      1         Event #

3 Page 19 of 51 Event

Description:

Pressurizer Pressure (P'T -449) fails High ~

    .fter 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 l3istable 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 I. i Master pressure Controller 431 K output at 100%

- MCB Annunciator F-10, PRESSURIZER LO PRESS 2205 (15seconds delayed)

NOTE: The HCO may take

action to place 431 K in i

MANUAL control, or the Spray Valve Controllers in MANUAL control, before arriving at the procedurally directed step, per

the Guidance of A-503.1. ,,

I I I . ._ - --t~OTE: The crew may enter i

AP-PRZR.1 directly.

AR-F-2, PRESSURIZER HI PRESS 2310 PSI

                                                 .... ~-    ...- - -...                                      I i

I (Step 1) IF RCS pressure is high, THEN go I NOTE: Pressurizer Pressure is i i to AP-PRZR.1.

NOT high.

i

                      . (Step 2) IF due to instrument failure, THEN        i NOTE: While an instrument i

refer to ER-INST.1, REACTOR

has failed, the failure has i

PROTECTION BISTABLE DEFEAT AFTER created a pressure transient, INSTRUMENTATION LOOP FAILURE and AP-PRZR.1 is the appropriate procedure. I I

Appendix 0 Operator Action Form ES-O-2 Op Test No.: Nl0-1 Scenario # 1 Event # 3 Page 20 of 51

                                                               ~--------                             ~~.

" 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 (Step 1) Perform a channel check. (Step 2) Go to the applicable

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

                 -l"_~______________________~i_PR_Z_R_.1_.             .

I' L L---J-- AP -PRZR.1, ABNORMAL PRESSURIZER PRESSURE NOTE: The CRS will go to AP __________ ~ I (Step 1) Check PRZR Pressure:

All 4 narrow range channels I APPROXIMATELY EQUAL (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 a) IF the controlling PRZR pressure channel been verified to be under has failed. THEN place controller, 431 K, control.

in MANUAL and adjust output to restore PRZR pressure i b) Refer to ER-INST.1. REACTOR PROTECTION BISTABLE DEFEAT AFTER INSTRUMENTATION LOOP FAILURE. i I i HCO I (Step 2) Check Reactor Power-I ;

Appendix 0 Operator Action Form ES-O-2 Op Test No.: N10-1 Scenario # 1 Event # 3 Page 21 of 51

                --                                       ~----

Event

Description:

Pressurizer Pressure (PT-449) fails High HCO (Step 3) Check PRZR Pressum: a) Pressure- LESS THAN 2235 PSIG b) Pressure- GREATER THAN 2000 PSIG (Step 4) Check PRZR Heater Status: a) PRZR proportional heater breaker- CLOSED b) PRZR heater backup group- ON HCO (Step 5) Verify Normal PRZR Spray Valves NOTE: The HCO may take CLOSED action to place 431 K in o AOV-431A MANUAL control, or the Spray Valve Controllers in MANUAL o AOV-4318 control, before arriving at THIS step, per the Guidance of A 503.1. (Step 6) Check PRZR Pressure 431 K, Demand- LESS THAN 50% (Step 7) Check PRZR PORVs: a) PORVs- CLOSED b) Annunciator F-19. PRZR PORV OUTLET HI TEMP 145"F EXTINGUISHED c) Go to Step 9

Appendix 0 Operator Action Form ES-O-2 Scenario # 1 Event # Test No.:

                - N10-1                                      3
                                                            ------- Page 22  of 51

Description:

Pressurizer Pressure (PT-449) fails High HCO (Step 9) Check PRZR Safety Valves: o Position indicator- LESS THAN 0.1 INCH o Annunciator F-18. PRZR SAFETY VLV OUTLET HI TEMP 145"F EXTINGUISHED o Annunciator AA-13, PRESSURIZER SAFETY VALVE POSITION EXTINGUISHED. PRZR Pressure Pressure- TRENDING TO 2235 PSIG CRS i b) Go to Step 16 HCO (Step 16) Check PRT Indications: b) Pressure PSIG AND STABLE c) Temperature- AT CNMT AMBIENT TEMPERATURE AND STABLE (Step 17) Establish PRZR Pressure In Auto:

        !                      a) Verify 431 K in AUTO i

Appendix 0 Operator Action Form ES-O-2 Test No,: N10-1 Scenario # 1 Event # 3 Page 23 of 51

                                                           ~--------                         ~~

Description:

Pressurizer Pressure (F'T-449) fails High HCO (Step 17 RNO) Place 431K 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, the CRS may refer to this i procedure here, ER-INST.1, REACTOR PROTECTION BISTABLE DEFEAT AFTER INSTRUMENTATION LOOP FAILURE HCO (Step 4.1) Identify the failed instrument channel by observation of the bistable status light board, MCB annunciators, and the MCB

                * (Step 4.2) WHEN a failed instrument loop        NOTE: The CRS will refer to I and/or channel has been identified, THEN         PRZR

refer to the appropriate section of this HCO (Step 4.4.1) IF the controlling PRZR Pressure channel has failed 449, but PT-429 may be selected as controlling channel), THEN place HC-431 Kin MANUAL at about 50% and control pressure manually f------~--+_----------~~-----____i_-~~~~~~~---------_!

(Step 4.4.2) IF PT-430 OR PT-431 has NOTE: Neither PT-430 nor failed, THEN ... "'" PT-431 has failed. 4.4.3) Close the associated block NOTE: The Pressurizer PORVs have NOT been affected, HCO (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 Op Test No.: N10-1 Scenario # Event # ...,;3::....-_ _ _ _ Page 24 of _5_1---iJ Event

Description:

Pressurizer Pressure (PT-449) fails High b======== ==-====================~=====-===================~_=~ 4.4.5) Refer to the appropriate to defeat the associated control NOTE: The CRS will hand this off to the CO. ER-INST.1, REACTOR PROTECTION BISTABLE DEFEAT AFTER INSTRUMENTATION LOOP FAILURE YELLOW CHANNEL ATTACHMENT PRZR PRESSURE PI-449 (Step 1) IF PRZR Pressure channel failure NOTE: The failure did NOT resulted in a runback, THEN ...... result in a run back. CO (Step 2) In the PLP PRZR PRESS LEVEL rack, check the PRZR DEFEAT switch P/429A position. o IF P/429A is in NORMAL, place P/429A to DEFE,l\T-1. (Step 3) In the RIL INSERTION LIMIT rack, PLACE T/405F DELTA T DEFEAT switch to Loop 8 UNIT 2. i I (Step 4) In the (YELLOW) Y-1

                    . PROTECTION CHANNEL 4 rack, PLACE the following bistable proving switches to I                      DEFEAT (UP) AND verify the proving light status is correct:

408 LOOP 8-2 OVER TEMP TRIP NOTE: 80th B/S proving lights should be ON after defeat. 449 CHANNEL 4 I LOW PRESS TRIP HCO (Step 5) PLACE the PRZR pressure lO\."UIUOI transfer switch (MCB) to position 1-3 I I HCO (Step 6) Verify the bistable i I I above are lit. i

Appendix D Operator Action Form ES-O-2 N10-1 Scenario # Event # Pressurizer Pressure HCOI (Step 7) Delete 404/408 from processing by CO performing the following on the PPCS: a} Select "Group Update" display 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 "SublDeleteIRestore" display g) Select Point ID T0404 h) Turn "ON" scan processing i) Select "Change" j) On the "SublDelete/Restore" display k) Select Point ID P0449 I) Turn "OFF" scan processing m) Select "Change" (Step 8) GO TO step 4.4.6 (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

HC431K
PRZR Spray Valves HCO (Step 4.4.7) Open associated closed in step 4.4.3

Appendix D Operator Action Form ES-D-2 I Op Tes' No.' :,., Scenario' , Eve"" _3~_ _ _ _ Page 26 of ...;..51~-II . Event DescriPtion:-- Pressurizer Pressure (PT-449) fails High CRS (Step 4.4.8) Check the followin~~ ITS NOTE: The CRS will evaluate Sections for LCO's: Technical Specifications. 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, TablE3 3.3.2-1, Function 1d (not n~quired 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, ,A.nticipated Transients Without Scram (ATWS) mitigation Technical Requirements Manual. (Step 4.4.10) IF turbine I occurred AND rods are in MANUAL, result in a runback. HCO (Step 4.4.11) Restore AUTO Rod NOTE: The HCO will place the desired. Rods in Auto. CRS 4.4.12) GO TO step 4.15 (Step 4.15.1) IF necessary, verify an operable channel is selected for the affected recorder. HCO . (Step 4.15.2) Verify the followin!] systems in

                 , AUTO if desired:

o Rod Control CO 0 Turbine EH control HCO 0 PRZR Pressure control

HC431K
PRZR spray valves
PRZR heaters o PRZR level control

Appendix 0 Operator Action Form ES-O-2 N10-1 Scenario #

Description:

Pressurizer Pressure co co 0 S/G Atmos Relief Vlv CRS i (Step 4.15.3) Notifications to the following NOTE: The

people will be made by the Shift Manager: the SM/STA o Operations Supervisior . Booth o STA SM/STA, acknowledge.

CRS * (Step 4.15.4) During normal working hours, NOTE: The CRS may notify

                ! Maintenance personnel shall be notified           theWCC.

I immediately of the problem. Booth Instructor: as WCCS, I

                                                                  . acknowledge.

CRS (Step 4.15.5) During back shifts Maintenance personnel will be called in. HOWEVER, the

                . Shift Manager may defer callin9              IF I repairs may be deferred to the next AP-PRZR.1, ABNORMAL PRESSURIZER PRESSURE 17.b) Verify PRZR Spray Valves in heaters breaker-Closed

PRZR backup heaters HESET in AUTO

                  * (Step 18) Evaluate MCB (Refer to AR Procedures)

19) Notify Higher Supervision

Appendix D Operator Action Form ES-D-2

               - - Scenario #

N10-1 1 Event #

Description:

Pressurizer Pressure (Step 20) Notify Reactor Engim~er for Transient Monitoring Program

NOTE: The CRS will address the Technical Specifications.

SPECIFICATION 3.4.1, RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING (DNB) LIMITS CRS I' (LCO 3.4.1) RCS DNB Parameters pressurizer pressure, RCS average i temperature, and RCS total flow rate

                                       , A.1 Restore ReS DNB parameters not   parameter(s} to within limits. within limil.

TECHNICALSPECIFICATION 3.3.1, REACTOR TRIP (RTS) INSTRUMENTATIO~ I CRS LeO 33Th .. 1 e RTS instrumentatton . for eac h I Function in Table 3,3.1-1 shall be H-I l __ i OPERABLE. APPLICABILITY: According to Table 3.3.1-1 (Functions 5, 7a, 7b) I i I I I

Appendix 0 Operator Action Form ES-O-2 Op Test No.: N10-1 Scenario # 1 Event # 3 Page 29 of 51

                                                                                               ~;""-""I Event

Description:

Pressurizer Pressure (PT-449) fails High A 1 Enter the Immecliately Condition referenced in Table 3.3.1-1 for the channel(s). D. As required i 0.1 6 hours i by Required Place channel

                        . Action A.1 and         in trip referenced by Table 3.3.1-1 K. As required       K.1                6 hours by Required          Place channel Action A.1 and       in trip referenced by Table 3.3.1-1 i                TECHNICAL SPECIFICATION 3.3.2, ESFAS INSTRUMENTATION I

! i LCO 3.3.2 The ESFAS instrum~3ntation for I I each Function in Table 3.3.2-1 shall be

                      . OPERABLE.

I i

           !          i i

i APPLICABILITY: According to (Function I.d) i i i i

                      . ACTIONS I                     I i

I i CONDITION REQUIRED COMPLETION ACTION TIME I A One or more Ai Enter the Functions with . Condition immediately i one channel or I referenced in train inoperable Table 3.3.2-1

                                              . for the channel i or train L. As required   I   L.1             I 13 hours.

i by Required . Place channel I Action A.1 and I in trip referenced by Table 3.3.2-1 I I I I At the discretion of the Lead Examiner move to Event #4.

Appendix D Operator Action Form ES-D-2 Test No.: N10-1 Scenario # 1 Event # 4 Page 30 of 51

                                                             ~--------                ~~

Description:

Main Turbine High Vibration/EHC control failure ~ OIlOWing this, a turbine high vibration condition on Beari~g #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 I Downpower. The operator will need to lower the Turbine Load using Manual EHC . control. I Booth Operator Instructions: Operate Trigger #3 (TUR05E (10 mils), TUR09D (120 sec delayed)) Indications Available:

MCB Annunciator 1-27, ROTOR ECCENTIRICITY 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 AP-TURB.3, TURBINE VIBRATION (Step 1) Verify Turbine Vibration BEARINGS LESS THAN 14MILS CO (Step 2) Check Turbine Bearings No.1 through NO.8 Vibration- LESS THAN 7 MILS

Appendix 0 Operator Action Form ES-O-2 Scenario # 1 EVEmt # i Op Test No.:

                  - N10-1                                         _4.:....-____ Page        31    of   51
                                                                                                     ~;"""'-II Event

Description:

Main Turbine High Vibration/EHC control failure CO (Step 2 RNO) Attempt to stabilize vibration as follows: IF generator on line, THEN be~jin reducing load to stabilize vibrations. (RE3fer to AP TURB.S, RAPID LOAD REDUCTION NOTE: The CRS will go to AP TURB.S and conduct "mini briefing" prior to commencing load reduction AP-TURB.5, RAPID LOAD REDUCTION (Step 1) I nitiate Load Reduction a) Verify rods in AUTO b) Reduce turbine load in Auto as follows: (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. c) Initiate boration at the rate NOTE: The HCO will initiate a determined in OPG-REACTIVITY boration. CALC HCO d) Place PRZR backup hE!aters 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 i Necessary To (refer to OPG-REACTIVITY

                    . CALC):

Maintain rods above thE9 insertion limit
Match Tavg and Tref
Compensate for Xenon

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # Event # _4.:.-_ _ _ _ Page 32 of 51

                                                                                    ......;..;....--{

, Event

Description:

Main Turbine High Vibration/EHC control failure Ib.."===================~=.= = = = = = = = = = = = = = = . . . ! To ensure conditions are met for FR-H.1 entry in the next scenario, the next events should be initiated after - 5% load reduction has been completed. At the discretion of the Lead Examiner move to Events #5-9.

Appendix D Operator Actior,.:...l_ _ _ _ _ _ _ _ _...;F...;o;.;.;rm.;.;...;;;E;.;;.S...;;-D;..;-2;;... Op Test No.: N10*1 Scenario # 1 Event # 5, 6, 7, 8 & 9 Page ~ of Event

Description:

Feed Line Rupture Inside Containment / A AFW Pump Fails start! TDAFW Pump overs peed tripl Standby AFW fails to Uring 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. The main turbine failure to Auto trip will require CO to initiate a manual turbine trip. 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. operator will unsuccessfully attempt to place the Standby AFW System in service, I* The and then attempt to restore a Secondary Heat Sink using the MFW System. Once the i 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. The scenario will terminate at Step 9 of E-2, after the crew has, determined that a transition to E-1, Loss of Reactor or Secondary Coolant, is required. I Booth Operator Instructions: Operate Trigger #4 (FDW09A (2E+7 over 180

seconds>>

i

, Indications Available:

Containment NR Pressure starts to rise.
Feedflow A SG starts to rise.
A SG NR Level starts to lower.

E-O, REACTOR TRIP MRPI indicates - ALL SHUTDOWN RODS ON i NOTE: Auto turbine trip will

                                                                             , NOT occur.

CO , Emergency

                     ! Busses Energized to at Least 440 VOLTS:

Bus 14 and Bus 18

Appendix D Operator Action Form ES-D-2 N10-1 Scenario # Event # 5, 6, 7, 8 & 9 Page ~ of _5.;..1;""'1

Description:

Feed Line Rupture Inside Containment I A AFW Pump Fails after start! TDAFW Pump overspeed tripl Standby AFW fails to function HCO (*Step 4) Check if SI is Actuated:

Any SI Annunciator - LIT : NOTE: D-28, CNMT Press
SI sequencing - BOTH TRAINS STARTED.

HCO . (*Step 5) Verify CNMT Spray Not Required: I. Annunciator A-27, CNMT SPRAY EXTINGUISHED

CNMT pressure- LESS THM~ 28 NOTE: Containment Pressure PSIG 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 (Le. by performing Step 5 RNO). HCO (Step 5 RNO) Verify CNMT I (Step 6) Direct Operator to Perform 27.0, ATTACHMENT AUTOMATIC ACTION i VERIFICATION NOTE: The CRS will hand off ATI-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 ATI-27.0 continue at page 38. E-O, REACTOR TRIP OR SAFETY INJECTION, ATTACHMENT 27.0, ATTACHMENT AUTOMATIC ACTION VERIFICATION

Appendix 0 Operator Action Form ES-D-2 N10*1 Scenario # 1 Event # 5, 6, 7, 8 & 9 Page =--- of _5;;..1;"--11 Feed line Rupture Inside Containment I A AFW Pump Fails after start! TDAFW Pump overspeed tripl Standby AFW fails to function (Step 1) Verify SI and RHR Pumps Running:

All SI pumps - RUNNING
Both RHR pumps - RUNNING (Step 2) Verify CNMT RECIRC Fans Running:

Charcoal filter dampers green lights - EXTINGUISHED (Step 3) Check If Main Steamlines Should Be Isolated:

Any MSIV - OPEN

               .*    Check CNMT pressure- LESS PSIG

4) Verify MFW Isolation:

HCOI CO

6) Verify CI and CVI:

CI and CVI annunciators - LIT

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # Event # 5, 6, 7, 8 & 9 Page ~ of _5,;..1_-iI Event

Description:

Feed Line Rupture Inside Containment I A AFW Pump Fails after start! TDAFW Pump overspeed tripl Standby AFW fails to function Annunciator A-26, CNMT ISOLATION

Annunciator A-25, CNMT VENTILATION ISOLATION
CI and CVI valve status lights
CNMT RECIRC fan coolers, valve status lights
FCV-4561
FCV-4562 Letdown orifice valves
AOV-200A
AOV-200B
AOV-202 (Step 7) Check CCW System Status:
Verify CCW pump - AT LEAST RUNNING (Step 8) Verify SI and RHR Pump SI flow indicators - CHECK FOR FLOW RHR flow indicator - CHECK FOR FLOW (Step 7b RNO) IF RCS pressure less than NOTE: RCS Pressure is > 150 150 psig ...... . psig.

HCOI (Step 9) Verify SI Pump and RHR Pump CO Emergency Alignment:

RHR pump discharge to Rx vessel deluge OPEN
MOV-852A

Appendix D Operator Action Form ES-D-2 N10-1 Scenario # Event # 5, 6, 7, 8 & 9 Page ~ of _5~1_-t1 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

Verify SI pump A
Verify 81 pump B - RUNNING
Verify SI pump C OPEN
MOV-871A
MOV-871B HCOI (Step 10) Verify CREATS Actuation:

CO

At least one damper in each flowpath CLOSED
Normal Supply Air
Normal Return Air
Lavatory Exhaust Air
CREATS fans - BOTH E-O, REACTOR TRIP OR. SAFETY INJECTION Examiner following operator I NOT performing ATT-27.0 I continue HERE.

7) Verify Both MDAFW Pumps NOTE: The B AFW Pump is OOS, and the A AFW Pump will fail to START CO (Step 7 RNO) Manually start both MDAFW NOTE: The TDAFW Pump will pumps. trip on overspeed.

IF less than 2 MDAFW pumps are running, THEN manually open TDAFW pump steam supply valves,

MOV-3505A

Appendix D Operator Action Form ES-D-2 ~IP Test No.: N10-1 Scenario # Event # 5, 6, 7, 8 & 9 Page ~ of _5.;..1_~1 II Event

Description:

Feed Line Rupture Inside Containment I A AFW Pump Fails after start! TDAFW Pump overspeed tripl Standby AFW fails to function i __ HCOI (Step 8) Verify AFW Valve Alignment: CO

AFW flow - INDICATED TO BOTH S/G(s)
AFW flow from each MDAFW pump LESS THAN 230 GPM (Step 8 RNa) Manually align valves as NOTE: There will be no AFW necessary flow, and manually alignment of valves will NOT restore flow.

(*Step 9) Monitor Heat Sink:

Check S/G narrow range level NOTE: Adverse Containment GREATER THAN 7% Numbers should be CNMT] in any S/G (Step 9 RNa) Perform the following:

Verify total AFW flow GREATER THAN 200 GPM IF total AFW is less than 200 GPM, THEN manually start pumps and align valves to establish greater than 200 gprr AFW flow .

                     . IF AFW flow greater than 200 gom can flow
                     . can NOT be established, THEN go to FR
                     ! H,1, RESPONSE TO LOSS OF HEAT SINK. Step 1.

The CRS will go to FR-i H.1. FR*H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK HCO (Step 1) Check If Secondary Heat Sink Is Required: a) RCS pressure- GREATER THAN ANY NON-FAULTED S.lG PRESSURE b) Check RCS cold leg temperature GREATER THAN 350°F

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # Event # 5, 6, 7,8 & 9 Page ~ of .-;..51_~ 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 2) Monitor Secondary HE!at Sink: o Verify either S/G level- WIDE RANGE GREATER THAN 50 inches [100 inches adverse CNMT] o Verify PRZR pressure- LESS THAN 2335 PSIG HCO 3.a) Try to Establish AFV\/ Flow To At One Intact S/G: a) Check Blowdown and Valves-CLOSED (Step 3.a RNO) Place Blowdown valve switches to CLOSE CO to Step 4. HCO (Step 5) Reset SI if Actuated CO (Step 6) Try and Establish SAFW Flow To At Least One Intact S/G: a) Perform the following:

1) Align SAFW system for operation (Refer to ATT-5.1, ATTACHMENT SAFW)

ATTACHMENT-5.1, ATTACHMENT SAFW

Appendix 0 Operator Action Form ES-O-2 Op Test No.: N10-1 Scenario # 1 Event # 5,6,7,8 & 9 Page ~ of ....,;5;;..;..1--11 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 i align Train B to feed the B SG due to the fault in A SG. (Step B) Align SAFW Pump 0 to selected S/G as follows:

1) Ensure SI reset

2) Ensure the following valves open:

MOV-9701 B, SAFW PUMP D DISCHARGE
MOV-4615. AUX BLDG SW ISOL VLVS
MOV-9704B, SAFW PUMP D ISOL VLV
MOV-9746, SAFW PMP 0 EMERG DISCH VLV

3) Open MOV-9629B, SAFW fJUMP 0 SUCTION VLV

4) Verify at least 1 SW pump fJnning 5a) 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 D FR H 1 , RESPONSE TO LOSS OF SECONDA RY HEAT S INK i CRS! (Step 6.a.2) Determine SAFW flow NOTE: The CRS will direct the CO requirements per ATT-22.0, ATfACHMENT CO to use ATT-22.0 to RESTORING FEED FLOW determine the allowable rate of feed flow to the B SG. i ATT-22.0, ATTACHMENT RESTORING FEED FLOW

Appendix D Operator Action Form ES-D-2 N10-1 Scenario # Event # 5, 6, 7, 8 & 9 Page _41_ of _5;;...1~-iI Feed Line Rupture Inside Containment I A AFW Pump Fails after start! TDAFW Pump overspeed tripl Standby AFW fails to function co 1. Initiate Feed flow as follows: NOTE: The CO will determine a) Bleed and Feed initiated or required. that the B SG can be filled as desired to restore Narrow b) IF feedwater flow to affected S/G Range Level to > 25%, when a greater than 50 gpm OH affected SG Feedwater flow source is level greater than 50 inches (100 restored. inches adverse CNMT). THEN fill as desired to restore narrow range greater than 7% (25% c:dverse CNMT) and go to step 2 of this attachment.

2. Check RCS Loop Hot Legs- BOTH HOT LEG TEMPERATURES LOWERING Return to step 1 of this attachment.

                             , RESPONSE TO LOSS OF SECONDARY HEAT SINK (Step 6.a.3) Start selected SAFW pump(s)               NOTE: The 0 SBAFW Pump

a. IF greater than 215 gpm total SAFW will fail to start, and the CRS flow can NOT be established, THEN will direct the CO to start the C go to Step 7 SAFW pump per Section A of ATI-5.1.

ATTACHMENT-S.1, ATTACHMENT SAFW L -_ _ _ _ _ _ _ _ _ _ _~------------_ _---------------~------------ ..--------~ CO (Step A) Align SAFW Pump C to selected S/G as follows:

1) Ensure SI reset

2) Ensure the following valves open

MOV-9701A, SAFW PUMP C DISCHARGE
MOV-4616, AUX BLDG SW ISOL VLVS
MOV-9704A, SAFW PUMP C ISOL VLV

3) Open MOV-9629A, SAFW PUMP C , NOTE: MOV-9629A will NOT SUCTION VLV : open. HCO/CO should inform

                                                                             , CRS that suction valve to C SAFW pump cannot be opened.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 1 Event # 5,6, 7, 8 & 9 Page ~ of _5_1_..,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 FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK CRS (Step 6.a RNa) If greater than 215 gpm total SAFW flow can NOT be established, THEN go to Step 7 CO (Step 7) Try to Establish Least One S/G

Check any MFW pump Check condensate system:
Condensate pump RUNNING
MFW pump suction GREATER THAN 200 Establish MFW flow:
Check MFW pump discharge valves-CLOSED
Verify MFW regulatin\J or bypass valves- OPERABLE
Depress MANUAL push buttons for A and B MFW regulating valve and bypass valve controllers AND adjust to 0% demand.
Open MFIV's for both S/G's: NOTE: This will require that the operator open a valve that
S/G A. AOV-3995 had previously failed open and
S/G B. AOV-3994 had been closed per Att.27.0.

i CRS

Dispatch AO to restore MFW pump SW cooling HCO
Verify S/G blowdown key NOTE: The CRS will dispatch switches in NORMAL an AO.

Booth Instructor: as AO, acknowledge.

Appendix D Operator Action Form ES-D-2 Scenario # 1 Event # ~ of ...;;.,51';"'-_11 00 Test No.:

                    - N10-1                                            5, 6, 7, 8 & 9       Page Event

Description:

Feed Line Rupture Inside Containment I A AFW Pump Fails after start! TDAFW Pump overs peed trip/ Standby AFW fails to function

Ensure Annunciator /-1-4, MAIN FEED PUMP 01 L SYSTEM EXTINGUISHED
Close Condensate Bypass valve, I

AOV-3959 I i

Ensure Annunciator H-11 , Feed :

PUMP SEAL WATER LO DIFF Ii PRESS 15 PSI- EXTINGUISHED

                                                          ----------+--------------------~

Ensure one MFW pump i

valve- OPEN I I

Start Selected MFW pump I i.

i Open MFW pump valve

                                                           *1(:1181:::

Open MFW regulating or bypass I ! NOTE: The CO will determine valves to control MFW flow per that the B SG can be filled as requirements of ATT-22.0, desired to restore Narrow ATTACHMENT RESTORING Range Level to > 25%, when a Feedwater flow source is FEED FLOW i

Go to Step 11 I

i Step 11. Check S/G Levels: NOTE: The CRS will a) Narrow range level in at least one determine that a Secondary Heat Sink has been restored S/G- GREATER THAN 7% [25% with the MFW System, and adverse CNMT] return to E-O, Step 9. IF feed flow verified and level rising in at Least one 8/G, THEN maintain flow to Restore narrow range level greater than 7% [25% adverse CNIVIT]. b) Return to procedure and step In effect.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 1 Event # 5, 6, 7, 8 & 9 Page ~ of _5.;;..1~-I; Event

Description:

Feed Line Rupture Inside Containment I A AFW Pump Fails after start! TDAFW Pump overspeed tripl Standby AFW fails to function (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 ReS 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 ReS and/or fuel cladding fission product barriers. E-O, REACTOR TRIP OR SAFETY INJECTION i i I co

C*Step 9) Monitor Heat Sink:

I

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 Check S/G narrow range level BOTH I S/G LESS THAN 50% Control feed flow to maintain S/G narrow range level between 7% [2~)% adverse CNMT] and 50%. I CO (Step 10) Check IfTDAFW Pump Can Be

Stopped.
Both MDAFW pumps - RUNNING
NOTE: None of the AFW running.

CRS (Step 10 RNO) Go to Step 11 HCO . (Step 11) Check CCW Flow to RCP Thermal Barriers:

Annunciator A-7, RCP 1A CCW RETURN HI TEMP OR LO FLOW EXT INGU ISH ED
Annunciator A-15, ReOp 1B CCW RETURN HI TEMP OR LOW FLOW EXTINGUISHED

Appendix D Operator Action Form ES-D-2 Test No.: N10-1 Scenario # Event # 5,6, 7, 8 & 9 Page ~ of _5,;;..1_-i1 Event

Description:

Feed Line Rupture Inside Containment I A AFW Pump Fails after startl TDAFW Pump ov'~rspeed tripl Standby AFW fails to function Heo (*Step 12) Monitor RCS Tavg - STABLE AT OR TRENDING TO 547°F (Step 12 RNO) If temperature k~ss than 547°F and lowering, THEN perl'orm the following:

Stop dumping steam.
Ensure reheater steam supply valves are closed.

IF cooldown continues, THEN control total feed flow between 20 qpm to 230 gpm until narrow range level greater than

7% [25% adverse CNMT] in at least one S/G.
WHEN S/G level greater than 7% [25%

adverse CNMT] in one S/G, THEN limit feed flow to that required to level in at least one S/G. IF cooldown continues, MSIVs.

Check PRZR pressure - LE:SS THAN 2260 PSIG
Normal PRZR spray valves - CLOSED
PCV-431A
B (Step 14) Monitor RCP Trip Criteria:
RCP status - AI\JY RCP RLNNING

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # Event # 5, 6, 7, 8 & 9 Page ~ of _5;;..1;....-.~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 CRS (Step 14c RNO) Go to Step 15. co 15) Check If S/G Secondary Side Is NOTE: The A SG is depressurizing in n Pressure in both S/Gs- STABLE OR uncontrolled manner. RISING Pressure in both S/Gs- GREATER THAN 110 PSIG CRS (Step 15 RNO) IF any S/G pressure lowering in an uncontrolled manner OR depressurized, THEN go to E-2, STEAM GENERATOR ISOLATION, E-2, FAULTED STEAM CO (Step 1) Check MSIV of CLOSED (Step 2) Check If Any S/G . . . .,""nn i Intact:

Check pressure in S/G A- STABLE OR RISING depressurized.

OR --.--+----+_ ~---------- --~ ... .. - - + _ - - - - - - - - - _ _ _ _ _ i

Check pressure in S/G B - STABLE OR RISING CO (Step 3) Check Faulted S/G Status: NOTE: The A SG is depressurized.
Faulted S/G pressure - LOWERING IN AN UNCONTROLLED MANNER OR

Appendix D Operator Action Form ES-D-2 Op Test No.:

                - Nl0*1   Scenario #       1    Event #     5,6, 7, 8 & 9 Page ~   of ..;;;..51~~

Event

Description:

Feed Line Rupture Inside Containment I A AFW Pump Fails after start! TDAFW Pump overspeed tripl Standby AFW fails to function

Faulted S/G - COMPLETELY DEPRESSURIZED CO (Step 4) Isolate Feed Flow to
Close or verify closed the valves:
Faulted S/G MDAFW pump discharge valve
S/G A, MOV-4007
S/G A, AOV-3995
MDAFW pump crosstie valves BOTH CLOSED
MOV-4000A
S/G A, MOV-9701A
S/G A, AOV-4297 (Step 5) Isolate Steam Flow From S/G:

Verify faulted S/G ARV S/G AOV-3411

Appendix D Operator Action Form ES-D-2 Test No.: Nl0-1 Scenario # Event # 5, 6, 7, 8 & 9 Page:::"'- of _5.;;..1_~1

Description:

Feed Line Rupture Inside Containment I A AFW Pump Fails after start! TDAFW Pump overs peed tripl Standby AFW fails to function Verify faulted S/G blowdown and sample valves CLOSED

S/G A, AOV-5738 and AOV-5735 (E-2 A) Isolate the Faulted Steam Generator before transitioning out of E-2.

Safety Significance: Failure to isolate a Faulte!d SG that can be isolated causes challenges to the Critical Safety Functions thelt 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).

Dispatch AO to complete faulted S/G NOTE: The CRS will dispatch isolation (Refer to ATT-1 00, anAO.

ATTACHMENT FAULTED S/G) Booth Instructor: as AO, Narrow range level - GREATER 7% [25% adverse CNMT] Control feed flow to maintai:1 range level between 17% [25% CNMT] and 50% (Step 7) Check Secondary Radiation Levels

                  . NORMAL

Steamline radiation monitor (R-31 and R 32)
Air ejector radiation monitor (R-15)
S/G blowdown radiation monitor (R-19)
Request Chem Tech activity

Appendix D Operator Action Form ES-D-2 Test No.: Nl0-l Scenario # 1 Event # 5, 6, 7, 8 & 9 Page ~ of _5;;..1~""1

Description:

Feed Line Rupture Inside Containment I A AFW Pump Fails after start! TDAFW Pump overspeed tripl Standby AFW fails to function (Step 8) Adjust Steam Dump to Minimize RCS Heatup:

Determine allowable intact S/G pressure using maximum hot leg temperature (Refer to FIG-7.0, FIGURE INTACT S/G PRESSURE)
Check condenser steam dump available: NOTE: Steam Dump to the Condenser is NOT available.

(Step 8b RI\JO) Perform the following

Adjust intact S/G ARV to pressure determined from FIG-7.0, FIGURE INTACT S/G PRESSURE.

Terminate the Exam at the discretion of the Lead Examiner

UNIT STATUS: Power Level: 49% RCS [B] 1710 ppm BAST [B]: 14000 ppm Power History: The Plant is at 49% powl3r (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 hours ago

A-S2.4 Equipment !Date Time ]1 Reason 1 Required Actions InI Requir~d Completion I I Required Action not met I ' B MDAFW Pump

               --1----1... -- .

_1_/10 I 0330 I Bearing n I',ITS. . 3.7,5 n _ _ I Date{T_lm I 6 days from _ _e-+I~~~~____________~ I ITS 3.7.5 Replacement Enter Condition B today's I Enter Condition G date/time Required Action B.1: Restore Required Action G.1: Be in Mode 3 MDAFW Train to OPERABLE in 6 hours Status in 7 days AND Required Action G.2: Be in Mode 4 in 12 hours

Scenario Event Description NRC Scenario 2 Facility: Ginna Scenario No.: 2 Op Test No.: N10-1 Examiners: Operators: (SRO) (RO) (BOP) Initial Conditions: 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. Turnover: The following equipment is Out-Ot-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 3 CVC12C C-RO C Charging Pump trips i C-SRO 4 TUR16B I-BOP Turbine Impulse Pressure (PT -486) fails High I-SRO 5 A-FDW30 R-RO A MFW Pump Oil Sump HI-LO Level/Rapid DownpowerlStuck Rod ROD-G11 C-BOP C(TS)-SRO 6 SGN04B M-RO SGTR M-BOP M-SRO 7 RPS07A NA A SI Pump fails to start in AUTO 8 RPS07C NA C SI Pump fails to start in AUTO RPS07D

     *   (N)ormal,    (R)eactivity,   (I)nstrument,    (C)OITl ponent,    (M}ajor
                                                -2

Scenario Event Description NRC Scenario 2 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-Ot-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 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. 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. Then, Main Turbine 1st 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.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 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 AP SG.l, 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, Stearn 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.

-3

Scenario Event Description NRC Scenario 2 Critical Tasks: 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 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 &P between the ruptured SG and the intact SGs. Upon a loss of &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 ReS leakage into the SG. 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.

- 4

Scenario Event Description NRC Scenario 2 SIMULATOR OPERATOR INSTRUCTIONS o Reset to Temp IIC 177 (NRC 2). 100% power EOL T=O: MALF SIS03B, Trip of 'B" SI pump (OOS contingency) MALF RPS07 A, Autostart failure of A SI pump MALF RPS07C, Autostart failure of C SI pump on Bus 14 MALF RPS07D, Autostart failure of C SI pump on Bus 16 Set Trigger #30 = x06i188a==1 (C SWP CS to STOP) Insert MALF CLG09C, 100%, T-30 (SWP C Discharge Check Valve fails OPEN) Set Trigger #29 = x06i188b==1 (C SWP CS to CLOSE) Insert MALF CLG01D T-29 (SWP 0 Trip) MALF CVC10A, 100,5 second Ramp, on T-1 MALF CVC12C, on T-2 MALF TUR16B, 1050, 0 Ramp, on T-3 ANN A-FDW30, ON, on T-4 MALF ROD03-Gll, OPEN, on T-4 MALF SGN04B, 250, 0 Ramp, on T-5 o Prior to Crew Briefing RUN Hang PROTECT Tags on AlC SI Pump Control Switches o Crew Briefing 1 . Assign Crew Positions based on evaluation requirements

2. Review the Shift Turnover Information with the crew.

3. Provide the crew a copy of P-17, Operations Control Room Operating Instructions, Attachment 7, CROI-? Swapping Service Water Pumps.

0 T-O Begin Familiarization Period At direction of Event 1 Swap Service Water Pumps/O Service Water Pump Trip 0 examiner CLG09C (T-30) 'T-30 (C SWP CS to STOP), Discharge Check Valve sticks OPEN CLG01D (T-29) T-29 (C SWP CS to CLOSE), D SWP Trips At direction of Event 2 VCT Level 112 Fails HIGH 0 examiner Trigger #1 100% ramped at 5 seconds CVC10A

-5

Scenario Event Description NRC Scenario 2 At direction of Event 3 C Charging Pump trips 0 examiner Trigger#2 CVC12C 0 At the Event 4 Turbine Impulse Pressure (PT -486) fails High completion of the CRS Brief Trigger#3 OR at 1050, No Ramp TUR16B direction of examiner 0 At direction of Event 5 A MFW Pump Oil Sump HI-LO Level/Rapid examiner DownpowerlStuck Rod Trigger #4 Severity = ON A-FDW30 ROD03-G11 0 At direction of Event 6 SGTR examiner Trigger #5 .250 gpm, No Ramp SGN04B 0 At direction of Event 7 A SI Pump fails to start in AUTO examiner T=O NOTE: This Malfunction is inserted in the IC at T = O. RPS07A 0 Continued Event 8 C SI Pump fails to start in AUTO from Event 6 T=O NOTE: This Malfunction is inserted in the IC at T = O. RPS07C RPS07D o Terminate the scenario upon direction of Lead Examiner

- 6

Appendix D Operator Action OpTest No.. N10*1 Scenario # 2 Event # ...;.._ _ _ _ Page 7 of ....5-..4--1 Event

Description:

Swap Service Water PumpslD 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 I 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 wiH respond in accordance with AR-J-9, SAFEGUARDS BREAKER TRIP. The operator will address Technical Specification I 3.7.8, Service Water (SW) System. .

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

Description:

Swap Service Water PumpsiD Service Water Pump Trip (Step 1.4.3) VERIFY B Service Water Pump NOTE: The CO will contact the in NOT rotating. AO. SIM DRIVER: as AO, confirm that B SW pujmp is NOT rotating. tep 1.4.4) VERIFY Service Water header ressure 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 NOTE: The CO will contact the Service Water Pump de-energized. AO. SIM DRIVER: as AO, acknowledge.(Not simulated) (Step 1.7.3) VERIFY Service Water header I pressure on PI-2160 and PI-2161 rises. CO (Step 1.6.1) STOP C Service Water Pump (Step 1.6.2) VERIFY motor heater for C NOTE: The CO will contact the Service Water Pump energized. 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.

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

                                                          ----------     Page       9   of  54
                                                                                           ----~

Event

Description:

Swap Service Water PumpslD Service Water Pump Trip (Step 1.6.4) VERIFY Service Water header NOTE: The SW Header pressure on PI-2160 and PI-2161 lowers. 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:

MCB Annunciator J-9, SAFEGUARDS BREAKER TRIP
0 SWP Green and White Breaker Status lights are LIT AR-J-9, SAFEGUARD BREAKER TRIP CRS 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.

CRS 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.: Scenario # 2 Event # _ _ _ _ _ _ Page N10-1 10 of _5;;.4~-I Event

Description:

Swap Service Water Pumps/D Service Water Pump Trip CO Notify AO to perform the following: NOTE: The CO will contact the AO. 81M DRIVER: as AO, acknowledge, and after a short delay report that the D SW Pump has tripped and that the shaft is stopped.

Investigate
Report findings back to Control Room CRS IF 81 is NOT required, THEN reset or re closure of a breaker should not be attempted.

CRS IF SI is required, THEN ... NOTE: SI is NOT required. CO Notify Electricians. NOTE: The CRS may notify theWCC. SIM DRIVER: as WCCS, acknowledge. CRS Refer to ITS LCO for affected equipment. NOTE: The CRS will evaluate Technical Specifications. CRS Notify higher supervision. 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) SYSTEM 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.: Nl0-l Scenario # 2 Event # -..;.._ _ _ _ _ Page 11 of _5;;;..4~-I Event

Description:

Swap Service Water PumpsJD Service Water Pump Trip CRS APPLICABILITY: MODES 1, 2, :3, and 4. ACTIONS CONDITION REQUIRED COMPLETION ACTION TIME A.OneSW A.1 Restore SW 14 days pump pump to inoperable. OPERABLE status. At the discretion of the Lead Examiner move to Event #2.

Appendix D Operator Action Form ES-D-2 OpTest No.: N10-1 Scenario # 2 Event # ...,;2;;......_ _ _ _ Page 12 of ....5..... 4--1 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 Instructions: 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 % 8:..;6:...-_ _ _ _ _ _ _ _ _ _ _ _ _ _--'

NOTE: The CRS may ask the HCO/CO to address this ARP based on the PPCS Alarm. If NOT, VCT Level will be at 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 FigurEl1 to Attachment 1 of the ARP. respond to VCT level transmitter failure. HCO (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. HCO (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 D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # . .2_______ Page 13 of ....;5;..;,4--t Event

Description:

VCT Level 112 Fails HIGH

Inform AO to notify Control Hoom for NOTE: The CRS/HCO will manual makeup requirement when LI dispatch an AO.

139 indicates approximately 20%. SIM 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.

Refer to ER-CVCS.1 REACTOR MAKEUP CONTROL MALFUNCTION, for manual guidance.

NOTE: The CRS will go to ER CVCS.1 or may use S-3.1, Boron Concentration Control, Attachment a, Manual Makeup ER-CVCS.1, REACTOR MAKEUP CONTROL MALFUNCTION HCO (Step 4.2.1) IF the Reactor Makeup System does not respond in AUTO, THEN perform the following: HCO (Step 4.2.1.1) DETERMINE the amoUlnt of 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. HCO (Step 4.2.1.2) SET the BA integrator for the desired amount of BA. HCO (Step 4.2.1.3) PLACE the RMW Mode selector switch to BORATE. HCO (Step 4.2.1.4) ADJUST boric acid flow NOTE: If using Att.a, CROI control valve HCV-110A to the maximum uses "desired rate." flowrate in AUTO. HCO (Step 4.2.1.5) TURN the RMW Control switch to START and verify flow on the recorder.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # _2;;;..._ _ _ _ Page 14 of Event

Description:

VeT Level 112 Fails HIGH HCO (Step 4.2.1.6) WHEN the desired amount of Boric Acid has been added, ENSURE the Boration stops. HCO (Step 4.2.1.7) WHEN the boration stops, PLACE the RMW Mode selector switch to DILUTE. HCO (Step 4.2.1.8) SET RMW flow c()ntrol val CHV-111 to the desired flow ratl~, 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. HCO (Step 4.2.1.10) TURN the RMW Control switch to START and verify flow on recorder. 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 equipment is repaired. remainder of the scenario. At the discretion of the Lead Examiner move to Event #3.

Appendix D Operator Action Form ES-D-2 Op Test No.: Nl0-1 Scenario # 2 Event # ....;3~_ _ _ _ Page 15 of ....,;5;,...4--1 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 FEED PUMPS
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)
RCP Seal Lab;irinth DPs read low (15-20 ,,; H2O)

AR-G-25, MOTOR OFF CTR SECT PMPS EXCEPT MAIN & AUX FEED PMPS HCO (Step 1) Determine which pump has tripped (white light at switch will be lit). HCO (Step 2) VERIFY standby pump Auto starts NOTE: The HCO will start the OR start standby pump, IF required. B Charging Pump, and may take MANUAL control of Charging Pump speed_ HCO (Step 3) IF all charging pump(s) tripped, NOTE: All Charging Pumps THEN ....... are NOT tripped. CRS (Step 4) Notify Electrician. NOTE: The eRS may notify the Wee/Electricians. SIM DRIVER: as WCCS/Electricians, acknowledge. CRS (Step 5) Refer to ITS LeO 3.7.5. NOTE: 3.7.5 is AFW, and N/A to this event

Appendix D Operator Action Form ES-D-2 Op Test No.: N10*1 Scenario # 2 Event # _3~________ Page 16 of _5;.,4__-1 Event DeSCription: C Charging Pump trips CRS (Step 6) Refer to TRM TR 3.1.1 and 3.1.2. NOTE: With 2 charging pumps, requirements are met, but crew may submit A-S2.12 for tracking At the discretion of the Lead Examiner move to Event #4.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # _4~_ _ _ _ Page 17 of ..,;;5;..;.4--1 Event

Description:

Turbine Impulse Pressure (PT-486) fails High Then, Main Turbine 1st 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. Booth Operator Instructions: Operate Trigger #3 (TLlR16B (1050>> Indications Available:

PI-486 indicates upscale high
MCB Annunciator G-22; ADFCS SYSTEM TROUBLE
PPCS Annunciator RP27Q - First Stage Turb Press Channel Dev 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 due to Instrument Out of Range. COl (Step 4.1.6) NOTIFY I&C of the ADFACS AO alarm. CRS REFER TO ER-INST.1 REACTOR PROTECTION BISTABLE DEFEAT AFTER INSTRUMENTATION LOOP FAILURE for action to defeat failed instrumen1(s). NOTE: The CRS will go to ER INST.1. ER-INST.1, REACTOR PROTECTION BISTABLE DEFEAT AFTER INSTRUMENTATION LOOP FAILURE HCOI (Step 4.1) IDENTIFY the failed instrument NOTE: PT-486 indicator has CO channel by observation for the bistable status failed HIGH light board, MCB annunciators, and the MCB metering indication.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # _4.;......_ _ _ _ Page ~ of ....;5;..;.4---f 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: CO (Step 4.12.1) IF turbine first stage pressure NOTE: PT -485 has NOT channel PT-485 fails, THEN ... failed. CO (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 i (Step 4.12.2.2) For a PT-486 failure HIGH, NOTE: The CO will arm the

                  , Stearn Dump will NOT arm on load rejection.           Stearn Dumps.

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). CO (Step 4.12.2.3) Refer to Attachment FIRST STAGE PRESSURE PI-486, BLUE, to defeat channel AND to restore AUTOMATIC contro\. NOTE: The CRS will hand this off to the CO, and the CO will coordinate with the HCO to complete the Attachment. ER-INST.1, REACTOR PROTECTION BISTABLE DEFEAT AFTER INSTRUMENTATION LOOP FAILURE BLUE CHANNEL ATTACHMENT FIRST STAGE PRESSURE PI-486 CO (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:

Appendix D Operator Action Form ES-D-2 Op Test No.: Nl0-l Scenario # 2 Event # _4..;....____ Page .l!L- of 54 Event

Description:

Turbine Impulse Pressure (PT-486) fails High

TURBINE PWR TRIP NO"rE: Light is OFF HCOI (Step 2) VERIFY the AMSAC TF~IPPED CO status light (MCB) is extinguished.

COl (Step 3) VERIFY the TL 400 bistable NOTE: The CO will dispatch AO indicating light (FOX 3-RELAY FlOOM) is anAO. extinguished. SIM DRIVER: as AO, acknowledge. COl (Step 4) IF> 35% power, THEN verify NOTE: The CO will contact the AO AMSAC feedwater Flow bistables are reset AO. by observing the following: (FOX 3 RELAY SIM DRIVER: as AO, ROOM) acknowledge. TU466 TRIP STATUS LIGHT EXTINGUISHED TU467 TRIP STAUS LIGHT EXTINGUISHED TU476 TRIP STATUS LIGHT EXTINGUISHED TU477 TRIP STATUS LIGHT EXTINGUISHED COl (Step 5) PLACE switch TPS/486 (FOX 3 NOTE: The CO will contact the AO RELAY ROOM) to the TRIP position AND AO. verify TU486 TRIP STATUS light is lit. SIM DRIVER: as AO, acknowledge, and use REM TUR23 =TRIP. COl (Step 6) IF > 40% power, THEN verify the AMSAC AUTO BLOCK status light (MCB) is HCO extinguished. CO (Step 7) Delete the computer pOint from the PPCS by performing the following:

a. On the "Sub/Delete/Restore" display

Appendix D 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

c. Turn "OFF" scan processing

d. Select "Change" HCOI GO TO step 4.15.

CO HCO (Step 4.15.1) IF necessary, verify an NIA operable channel is selected for the affected recorder .

                  * (Step 4.15.2) VERIFY the following systems in AUTO if desired:

HCO

Rod control CO
Turbine EH control HCO
PRZR Pressure control
HC 431K
PRZR spray valves
PRZR heaters HCO
PRZR level control st CO
Steam Dump (unless 1 staoe pressure NOTE: The CO has previously failed) armed the Steam Dumps.
MFW control
SIG Atmos Relief Vlv Control CRS (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 SMISTA, acknowledge.

Operations Supervision
STA

Appendix D 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 (Step 4.15.4) During normal working hours, NOTE: The CRS may notify Maintenance personnel shall be notified theWCC. immediately of the problem. SIM DRIVER: as WCCS, acknowledge. CRS (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 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 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-LO 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 I 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-LO LEVEL CO (Step 1) Notify AO to check MFVII pumps oil NOTE: The CRS will dispatch sumps for Hi/Low levels. 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 pl:lrform the NOTE: The CRS will direct the following: 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 D Operator Action Form ES-D-2 Op Test No.: 2 Event # .....;.,5_ _ _ _ _ Page ~ of _5;;,.4;""-11 Event

Description:

A MFW Pump Oil Sump HI-LO LevellRapid DownpowerlStuck Rod I. Obtain an oil sample for Chemistry. II. Drain oil to clear the alarm. III. Monitor for additional inleakage. IV. IF inleakage is apparent, THEN reduce power to approximately 50% RTP per 0-5.1 OR AP TURB.5 AND remove the pump from service. NOTE: The CRS will go to AP TURB.5. o AP- rURBo5, RAPID LOAD REDUCTION NOTE: 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 Reduction NOTE: CRS conducts load reduction briefing

a. Verify rods in AUTO CO b. Reduce turbine load in Auto as follows:

1. Place Turbine EH Control in OPER PAN., IMP PRESS IN, if desired.

2. Select desired rate on thumbwheel.

3. Reduce the setter to the desired load.

4. 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--t Event

Description:

A MFW Pump Oil Sump HI-LO LeveVRapid DownpowerlStuck Rod HCO c. Initiate boration at the rate The HCO will initiate a determined in OPG-REACTIVITY boration. CALC.

d. 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 OPG-REACTIVITY CALC)

HCO (Step 4) Monitor PRZR Pressure TREN to 2235 PSIG IN AUTO CO (Step 5) Monitor MFW RESTORING S/G LEV HCO (Step 6) Monitor PRZR Level - TRENDING TO PROGRAM IN AUTO CONTROL 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 LTOP HI-LOW TEMPERATURE HCO IF rods are out of sequence, THEN ... NO"rE: The rods are NOT moving out of sequence. HCO IF rod positon deviation, THEN:

Appendix D 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 LeveVRapid DownpowerlStuck 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 AP RCC.2. AP-RCC.2, RCC/RPI MALFUNCTION HCO (Step 1) Place Rods to Manual 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 down power. HCO (Step 2) Check Dropped Rod Indication:

Annunciator E-28, POWER RANGE ROD DROP ROD STOP 5%/5 SECONDS- EXTINGUISHED
Annunciator C-14, ROD BOrrOM ROD STOP - EXTINGUISHED.

HCO (Step 3) Check Tavg - STABLE AT NOTE: The CRS may direct PROGRAM. Perform the following: that the Turbine be taken to Manual or left in Auto based on the indications of one Stuck Rod during a rapid down power.

a. Place EH control in MANUAL.

b. Manually adjust turbine load to match Tavg and Tret.

CO I (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 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 (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:

a. Verify all rods in affected group - NOTE: Rod G-11 is not WITHIN +/- 12 STEPS OF aligned ASSOCIATED GROUP STEP COUNTER CRS (Step 7 RNO) Refer to ITS Section 3.1.4.

CRS (Step 8) Check QPTR LESS THAN 1.02 CRS 8 RNO) Refer to ITS Section 3.2.4. CRS ! (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.

CRS 9 RNO) Perform the following

Appendix D Operator Action Form ES-D-2 Op Test No.: N10*1 Scenario # 2 Event # _5;;....._ _ _ _ Page ~ of _5

                                                                                                       ....4__-11 Event

Description:

A MFW Pump Oil Sump HI-LO LevelJRapid DownpowerlStuck Rod Refer to ITS section 3.1.7 for required action.

b. Consult Reactor Engineer and plant staff to evaluated MRPI.

c. Go to Step 11 NOTE: The CRS will evaluate technical Specifications.

TECHNICAL SPECIFICATION 3.1.4, ROD GROUP ALIGNMENTS CRS LCO 3.1.4 All shutdown and control rods shall be OPERABLE, with all individual indicated rod positions within 12 steps of their group step counter demand position. CRS APPLICABILITY: MODES 1, MODE 2 with Keff;;::1.0. CRS ACTIONS CONDITION REQUIRED COMPLETION ACTION TIME

Appendix D Operator Action Form ES-D-2 Op Test No.: Nl0-l Scenario # 2 Event # ...... 5_ _ _ _ _ Page ~ of _5;;,.4';""-1 Event

Description:

A MFW Pump Oil Sump HI-LO Level/Rapid DownpowerlStuck Rod B. One rod not B.1.1 Verify 1 hour within SOMis alignment within the limits. limits specified in the COLA. OR B.1.2 Initiate 1 hour boration to restore SDMto within limit. AND 2 hours B.2 Reduce THERMAL POWER to S75% RTP. AND Once per 12 8.3 Verify SDM is within the hours limits specified in theCOLR AND B.4 Perform SR 72 hours 3.2.1.1 AND B.5 Perform SR 72 hours 3.2.2.1 AND 5 days 8.6 Re 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 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 011 Sump HI-LO Level/Rapid DownpowerlStuck Rod CRS 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.: Nl0-l Scenario # 2 Event # 5 Page 30 of 54 Event

Description:

A MFW Pump Oil Sump HI-La LevellRapid DownpowerlStuck Rod A.OPTRnot A.I Reduce 2 hours after each with limit. THERMAL QPTR POWER~ 3% determination from RTP lor each 1% of QPTR .1.00. AND A.2 Determine QPTR Once per 12 AND hours A.3 Perform SR 3.2.1.1 , SR, 3.2.1.2 and 24 hours after SR3.2.2.1 achieving equiliblium conditions from a THERMAL POWER reduction per Required Action A.l AND Once per 7 days AND thereafter A.4 Reevaluate Prior to increasing safety THERMAL analyses and POWER above confirm the limit of results remain Required Action valid for the A.' duration of operetion under this condition. AND A.5 Normalize excore Prior to increasing detectors to THERMAL restore OPTR POWER above to within limit. the limito! AND Required Action A.l A.S Perform SR 3.2.1.1, SR Within 24 hours 3.2.1.2 and after achieving SR 3.2.2.1 equilibrium conditions at RTP not to exceed 48 hours after increasing THERMAL POWER above the limito! Required Action a.l At the discretion of the Lead Examiner move to Events #6-8.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # _6.;.:.,..;.7....;;&;..;;8~_ _ Page ~ of ...,;5:;..;,4---1 Event

Description:

8GTRI A 81 Pump fails to start in AUTOI C 51 Pump fails to start in AUTO 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 I pressure and charging flow to minimize primary-to-secondary leakage.

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 CRS (Step 1) If SG Tube Rupture is evident, THEN go to E-O, REACTOR TRIP OR SAFETY INJECTION. CO (Step 2) Trend PPCS point R-47G. co (Step 3) Notify RP/Chemistry to NOTE: The CRS may notify IMMEDIATELY obtain and analyze an air RPIChem istry. ejector grab sample per CH-360. Primary to 81M DRIVER: as Secondary Leakage Sampling and RP/Chemistry, acknowledge. Measurement.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # _6';":'...;.7...;&~8.;...._ _ Page ~ of _5.;..4~-I Event

Description:

5GTRI A 51 Pump fails to start in AUTOI C 51 Pump fails to start in AUTO CO (Step 4) Determine the estimated leak rate using PPCS point R47G or the H-47 Local Reading and the Conversion Table (Curve Book #06-004). CRS (Step 5) IF any condition below is met, THEN go to AP-SG.1, STEAM GENERATOR TUBE LEAK:

R47G (PPCS) greater than !; 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 AP SG_1. AP-SG.1, STEAM GENERATOR TUBE LEAK HCO (Step 1) Monitor PRZR Level- STABLE AT PROGRAM LEVEL HCO (Step 1 RNO) IF PRZR level lowering, THEN start additional charging pumps and raise speed as necessary to stabilize PRZR level. HCO (Step 1 RNO) If PRZR level continues to lower, THEN close letdown isolation, AOV 427 and excess letdown AOV-310. CRS (Step 1 RNO) IF available charging pumps are running at maximum speed with letdown isolated, AND PRZR level is lowering, THEN trip the reactor and go to E-O, REACTOR TRIP OR SAFETY IN..IECTION.

Appendix D Operator Action Form ES-D-2 Op Test No.: Nl0-l Scenario # 2 Event # _6;,:,'..;..7..;;&;.;;8~__ Page ~ of .....;5;...4-----t Event

Description:

SGTRI A SI Pump fails to start in AUTOI C SI Pump fails to start in AUTO NOTE: The CRS will go to E O. 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 CO .* (Step 2) Verify turbine Stop Valves

                  *. CLOSED CO         (Step 3) Verify Both Trains of AC Emergency Busses Energized to at Least 440 VOLTS:

Bus 14 and Bus 18
Bus 16 and Bus 17 HCO (Step 4) Check if SI is Actuated:
Any SI Annunciator - LIT
SI sequencing - BOTH TRAINS STARTED.

HCO (Step 5) Verify CNMT Spray Not Required:

Annunciator A-27, CNMT SPRAY EXTINGUISHED
CNMT pressure LESS THAN 28 PSIG HCO (Step 6) Direct Operator to Perform ATT 27.0, ATTACHMENT AUTOMATIC ACTION VERIFICATION.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # ..;6;;.:.*.;..7.;;;&..;;8_ _ _ Page ~ of _5;:;..4-=---11 Event

Description:

SGTRI A SI Pump fails to start in AUTOI C SI Pump fails to start in AUTO 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, ATTACHMENT AUTOMATIC ACTION VERIFICATION HCOI (Step 1) Verify 51 and RHR Pumps Running: CO

All 51 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 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 51 Pumps. Failure to perform this task will leave the plant in an unanalyzed condition. HCOI

Both RHR pumps - RUNNING CO HCOI (Step 2) Verify CNMT RECIRC Fans CO Running:
All fans - RUNNING
Charcoal filter dampers green status lights - EXTINGUISHED

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # -L- Event # _6;;.:.._7..;;;&;..;8~__ Page ~ of _5:;.,4':"'--1 Event

Description:

8GTRI A 81 Pump fails to start in AUTOI C 81 Pump fails to start in AUTO HCOI (Step 3) Check If Main Steam lines Should Se CO Isolated:

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 (0.5X106 Ib/hr) from either S/G 6

High-High steam flow (4.4X10 Ib/hr) from either S/G HCOI (Step 3a RNO) Go to Step 4.

CO HCOI * (Step 4) Verify MFW Isolation: CO

i. MFW pumps TRIPPED

MFW Isolation valves - CLOSED
S/G A, AOV-3995
S/G S, AOV-3994
S/G Slowdown 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

Annunciator A-26, CNMT ISOLATION

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # _6.;.:.._7_&;...;;8~_ _ Page ~ of _5.;;,.4';""'-\1 Event

Description:

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 lights BRIGHT CNMT RECIRC fan coolers SW outlet valve status lights - BRIGHT
FCV-4561
FCV-4562 Letdown orifice valves - CLOSED
AOV-200A
AOV-200B
AOV-202 HCOI (Step 7) Check CCW System Status:

CO

Verify CCW pump - AT LEAST ONE RUNNING HCOI (Step 8) Verify SI and RHR Pump Flow:

CO

SI flow indicators - CHECK FOR FLOW HCOl (Step 8a RNO) IF RCS pressure less than CO 1350 psig
RHR flow indicator - CHECK FOR FLOW HCOI (Step 8b RNO) IF RCS pressure less than CO 150 psig HCOI (Step 9) Verify SI Pump and RHR Pump CO Emergency Alignment:
RHR pump discharge to Rx vessel deluge - OPEN
MOV-852A

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # ...;6;;.:.*.;..7.;;;&...;;8_ _ _ Page ~ of ...,;5;..;,4--1 Event

Description:

8GTRI A 81 Pump fails to start in AUTOI C 81 Pump fails to start in AUTO

Verify SI pump C - RUI\II\IING
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 aligned to discharge line B: o MOV-871 B open o MOV-871A closed

                  * (Step 9d.3 RNO) Go to Step 10 HCOI       (Step 10) Verify CREATS Actuation:

CO

At least one damper in each flowpath CLOSED
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.

COl (Step 7) Verify Both MDAFW Pumps Running HCO COl (Step 8) Verify AFW Valve Alignment: HCO

AFW flow -INDICATED TO BOTH S/G(s)

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # _6;.:.,..;..7..-&.-8_ _ _ Page ~ of .....;5:..:,4---1 Event

Description:

SGTRI A SI Pump fails to start in AUTOI C SI Pump fails to start in AUTO

AFW flow from each MDAFW pump LESS THAN 230 G PM COl (Step 9) Monitor Heat Sink:

HCO

Check SIG narrow range level GREATER THAN 7% [2S% ADVERSE CNMT] in any S/G
Check SIG narrow range level BOTH SIG LESS THAN 50%
Control feed tlow to maintain S/G narrow range level between 7% [25% adverse CNMT] and 50%.

COl (Step 10) Check If TDAFW Pump Can Be Stopped: HCO

Both MDAFW pumps - RUNNING
PULL STOP TDAFW pump steam supply valves
MOV-3S04A
MOV-3S0SA COl (Step 11) Check CCW Flow to RCP Thermal Barriers:

HCO

Annunciator A-7, RCP 1A CCW RETURN HI TEMP OR LO FLOW EXTINGUISHED
Annunciator A-15, RCP 1B CCW RETURN HI TEMP OR LOW FLOW EXTINGUISHED COl (Step 12) Monitor RCS Tavg - STABLE AT OR TRENDING TO 547Q F HCO

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # _6;:;.1*..;,7..;;&;;.,8;;....._ _ Page ~ of _5...4"""-1 Event

Description:

SGTRI A SI Pump fails te) start in AUTOI C SI Pump fails to start in AUTO (Step 12 RNO) If temperature less than 547!lF and lowering. THEN perform the following:

Stop dumping steam.
Ensure reheater steam supply valves are closed.
IF cooldown continues, THEN control total feed flow between 200 gpm to 230 gpm until narrow range level greater than 7% [25% adverse CNMT] in at least one S/G.
WHEN S/G level greater than 7% [25%

adverse CNMT] in one S/G. THEN limit feed flow to that required to maintain level in at least one S/G.

IF cooldown continues, THEN close both MSIVs.

COl (Step 13 ) Check PRZR PORVs and Spray Valves: HCO

PORVs - CLOSED
Auxiliary Spray valves (AOV-296)

CLOSED

Check PRZR pressure - LESS THAN 2260 PSIG
Normal PRZR spray valves .. CLOSED
PCV-431A
PCV-431B COl (Step 14) Monitor RCP Trip Criteria:

HCO

RCP status - ANY RCP RUNNING 1----+----1
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 D Operator Action Form ES-D*2 Op Test No.: N10-1 Scenario # 2 Event # _6-.,..;..7..;,;&....8_ _ _ Page ~ of ....;5;...;,4---1 Event

Description:

SGTRI A SI Pump fails to start in AUTOI C SI Pump fails to start in AUTO CRS (Step 14c RNO) Go to Step 15. CO (Step 15) Check If SIG Secondary Side Is Intact:

Pressure in both SIGs - STABLE OR RISING
Pressure in both SIGs - GREATER THAN 110 PSIG CO (Step 16) Check if SIG Tubes Are Inctact:
Air ejector radiation monitors (R-15, R 47, R-48) - NORMAL (Step 16 RNO) Go to E-3, STEA,M GENERATOR TUBE RUPTURE, Step 1.

NOTE: The CRS will go to E 3. E-3, S"rEAM GENERATOR TUBE RUPTURE HCO (*Step 1) Monitor RCP Trip Criteria:

RCP status -ANY RCP RUNNING NOTE: Both RCPs are RUNNING.

I. SI pumps -AT LEAST TWO RUNNING

RCS pressure minus maximum SIG NOTE: Trip criteria is NOT pressure - LESS THAN 210 psi [240 psi met.

adverse CNMT] (Step 1c RNO) Go to step 2 CO (Step 2) Identify Ruptured S/G(s):

                  **    Unexpected rise in either SIG narrow                        NOTE: The CO reports that range level                                                 there is an unexpected increase in B SG Level.

OR

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

                                         - 2     Event #     _6.;;.:,:..;7...;&;;;..;;.8_ _ _ Page    ~ of _5;;.,4':""--1 Event

Description:

5GTRI A 51 Pump fails to start in AUTOI C 51 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 B OR

RP reports high radiation from S/G activity sample.

CO (Step 3) Isolate Flow From Ruptured S/G(s): NOTE: B is ruptured

Adjust ruptured S/G ARV controller to 1050 psig in AUTO
Check ruptured S/G ARV - CLOSED I- Close ruptured S/G TDAFW pump steam supply valve and place in PULL STOP
S/G A, MOV-3505A
S.G B, MOV-3504A

                   -    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 -FtUPTURED S/G MSIV CLOSED

Dispatch AO to complete ruptured S/G NOTE: The CRS will dispatch isolation (Refer to ATT-16.0, anAO.

AITACHMENT RUPTURED S/G part A) SIM DRIVER: as AO, acknowledge, and perform all remotes associated with AIT 16.0 (Schedule File ATT16SGBpartA.sch). CO (Step 5) Check Ruptured S/G Level:

Narrow range level- GREATER THAN 7% [25% adverse CNMT]

Appendix D Operator Action Form ES-D-2 Op Test No.: N10*1 Scenario #: 2 Event#: _6;;;.:*...;.7...;;&;;..8;;;...._ _ Page ~ of ~54__-I Event

Description:

SGTRI A 51 Pump falls te) start in AUTOI C 51 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 valves 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 - GREATER THAN 300 PSIG CRITICAL TASK (E-3A) Isolate feedwater flow into and stearn 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 ~P between the ruptured SG and the intact SGs. Upon a loss of ~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. CO (Step 7) Establish Condenser Steam Dump Pressure Control:

Verify condenser available
Intact S/G MSIV - OPEN

Appendix D Operator Action Form ES-D-2 Op Test No.: N10*1 Scenario # 2 Event # ~6.:..;7....;&;;;...;;.8_ _ _ Page ~ of _5;;;;.,4';""--11 Event

Description:

8GTRI A 81 Pump fails tC) start in AUTOI C 81 Pump fails to start in AUTO

Annunciator G-15. 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 CO (Step 9) Initiate RCS Cooldown:

                  * (Step 9a) Determine required core exit temperature from below table:

1000-1049 psig (512"F)
1050-1099 psig (519°F)

CO (Step 9b) IF ruptured SIG MSIV closed, THEN initiate dumping steam to condenser from intact SIG at maximum rate. CO (Step 9c) Core exit TICs - LESS THAN i REQUIRED TEMPERATURE CO (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. (Step 9d) Stop Rcs cooldown and stablilize core exit TICs less than required temperature CO (Step 10) Monitor Intact SIG Level:

Narrow range level- GREATER THAN 7% [25% adverse CNMT]

Appendix D Operator Action Form ES-D-2 Op Test No.: N10*1 Scenario # 2 Event # _6.;;.:,-.;7...;&;;..;;.8___ Page ~ of _5;..4';""-1 Event

Description:

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%

HCO (Step 11) Monitor PRZR PORVs, and Block Valves:

                  !. Power to PORV block valves AVAILABLE

PORVs - CLOSED
Block valves - AT LEAST ONE OPEN HCO (Step 12) Reset CI:
Depress CI reset push button
Verify annunciator A-26, CNMT ISOLATION - EXTINGUISHED CO * (Step 13) Monitor AC Bus Power:

I. 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 RUNNING
Dispatch AO to establish normal NOTE: The CRS will dispatch shutdown alignment (Refer to ATT-17.0, anAO.

ATTACHMENT SD-1) SIM DRIVER: as AO, acknowledge. Run SCHEDULE file SD-1.sch

Appendix D Operator Action Form ES-D*2 Op Test No.: N10-1 Scenario # 2 Event # _6;;.:.'.;..7.;;.;&~8___ Page ~ of _5;;.,4':-"'-1 Event

Description:

SGTRI A SI Pump fails to start in AUTOI C SI Pump falls to start in AUTO

Verify non-safeguards bUSSElS energized o Bus 13 normal feed - CL.OSED OR o Bus 15 normal feed - CL.OSED
Verify turbine building SW isolation valves - OPEN o MOV-4613 and MOV-467'0 o MOV-46134 and MOV-4664
Verify adequate air compressors RUNNING
Check IA supply:

o Pressure - GREATER THAN 60 PSIG o Pressure - STABLE OR RISING

Reset both trains of XY rela~rs for IA to CNMT AOV-5392
Verify IA to CNMT AOV-5392 - OPEN HCO (Step 16) Check if RHR pumps Should Be Stopped:
Check RCS pressure - GREATEF~ THAN 300 psig [350 psig adverse CNMT]
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 RUNNING I (Step 17a RNO) Perform the following:

IF CCW flow is lost 10 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 D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # _6;;.:.,-.7_&..;;8_ _ _ Page ~ of ...,;5;..;.4--1 Event

Description:

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 gpm total charging flow
Charging line flow
Seal injection CO (Step 18) Check if RCS Cooldown Should be Stopped:
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 THAN REQUIRED TEMPERATURE CO (Step 19) Check Ruptured SIG Pressure STABLE OR RISING CO (Step 20) Check RCS Subcooling based On Core Exit TICs - GREATER THAN 20°F USING FIG-1.0, FIGURE MIN SUBCOOLING HCO * (Step 21) Depressurize RCS To Minimize Break Flow and Refill PRZR:
Check the following:

o Ruptured SIG level- LESS THAN 90% [80% adverse CNMT] o Any RCP - RUNNING o IA to CNMT - AVAILABLE

Appendix D Operator Action Form ES-D-2 Op Test No.: Nl0-1 Scenario # 2 Event # _6;;.:.*..;.7..;;&;..;8;.....-_ _ Page ~ of _5;;..4~~1 Event

Description:

8GTRI A SI Pump fails to start in AUTOI C 81 Pump fails to start in AUTO

Spray PRZR with maximum available spray until ANY of the following conditions satisfied:

o PRZR level- GREATER THAN 75% [65% adverse CNMT] OR oRCS pressure - LESS THAN SATURATION USING FIG-1.0, FIGURE MIN SUBCOOLING lOR o BOTH of the following:

RCS pressure LESS THAN RUPTURED SIG PRESSURE
PRZR level GREATER THAN 10% [30%

adverse CN MT]

Close normal PRZR spray valves:
Adjust normal spray valve controller to 0% DEMAND
Verify PRZR spray valv!s- CL.OSED
PCV-431A
PCV-431B
Verify auxiliary spray valve (AOV-296)

CLOSED CRS i. GO to Step 24. CO (Step 24) Check if SI Flow Should Be Terminated:

RCS subcooling based on core exit TICs

                         - GREATER THAN OQF USING FIG-1.0, FIGURE MIN SUBCOOLING CO

Secondary heat sink:
Total feed flow to S/G(s)

GREATER THAN 200 GPM AVAILABLE

Appendix D Operator Action Form ES-D-2 Op Test No.: N10*1 Scenario # 2 Event # _6~,~7....;&;;.8.;;...._ _ Page ~ of _5;;;..4;"-'-1 Event

Description:

SGTRI A SI Pump fails to start In AUTOI C SI 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 OB RISING HCO .* PRZR level- GREATER THAN 10%

[30% adverse CNMT] RITICAL 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 the A & C Pumps. HCO (Step 26) Establish Required Charging Line Flow:

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 Reintitiation Criteria

RCS subcooling based on core exit TICs

                         - GREATER THAN OaF USING FIG 1.0, FIGURE MIN SUBCOOLING

PRZR level GREATER THAN 10%

[30% adverse CNMT]

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # ~6,~7...;&~8_ _ _ Page ~ of _5;..,4';"""-1 Event

Description:

SGTRI A SI Pump fails t() start in AUTOI C SI Pump fails to start in AUTO HCO (Step 28) Check if SI ACCUMs Should Be Isolated:

Check the following:
RCS subcooling based on core exit TICs - GREATER THAN OaF USING FIG-1.0, FIGURE MIN SUBCOOLING
PRZR level- GREATER THAN 10%
Dispatch AO with locked valve key to NOTE: The CRS will dispatch locally close breakers for SI ACCUM anAO.

discharge valves SIM DRIVER: as AO, acknowledge, and use REM EDS-035 and EDS-036.

MOV-841, MCC C position 12F
MOV-865, MCC D position 12C
Close SI ACCUM discharge valves o MOV-841 o 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. CO (Step 29) Verify Adequate SW Flow to CCW Hx:

Verify at least three SW pumps RUNNING CO (Step 29a RNO) Manually start pumps as NOTE: Three SW Pumps are power supply permits (257 kweach). IF less running.

than two SW pumps can be operated, THEN ...

Verify AUX BLDG SW isolation valves AT LEAST ONE SET OPEN

Appendix D Operator Action Form ES-D-2 Op Test No.: Nl0*1 Scenario # 2 Event # _6;;;.:.*..;.7.;;&;..;:8;......_ _ Page ~ of ....5;..;.4....... Event

Description:

SGTRI A SI Pump fails to start in AUTOI C SI Pump fails to start in AUTO o MOV-4615 and MOV-47~34 o MOV-4616 and MOV-47a5 HCO

Verify CNMT RECIRC fan annunciator C

2. HIGH TEMPERATURE ALARM EXTINGUISHED HCO (Step 30) Check if Normal CVCS Operation Can Be Established

Verify IA restored:

0 IA to CNMT (AOV-5392) - OPEN 0 IA pressure - GREATEn THAN 60 PSIG

Verify instrument bus D - EI\lREGIZED
CCW pumps - ANY RUNNING
Charging pump - ANY RUNNING HCO I (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 AOV-270A 0 AOV-270B
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 Level-GREATER THAN 20 % [40% adverse CNMT]

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # _6.;;..:,~7....;&;;..8.;;...._ _ Page .:2...- of Event

Description:

5GTRI A 51 Pump fails to start in AUTOI C 51 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 AOV 427

Place letdown controllers in MANUAL at 40% open 0 TCV-130 0 PCV-135
Reset both trains of XY relays for AOV 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 f----+--

in AUTO and 250 psig

Place TCV-130 in AUTO at the normal setpoint
Adjust charging pump speed and HCV 142 HCO (Step 34) Check VCT Makeup System:
Adjust boric acid flow control valve in AUTO to 9.5 gpm
Adjust RMW flow control valve in AUTO to 40 gpm
Verify the following:

o RMW mode selector switch in NOTE: Previous VCT level AUTO failure precludes Auto makeup

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 2 Event # _6;;.:,..;,7...;;&;;..8;;...._ _ Page ~ of _5;;;.,4';"""-1 Event

Description:

8GTRI A 81 Pump fails to start in AUTOI C 81 Pump fails to start in AUTO o RMW control armed - RED NOTE: Light will be OFF LIGHT LIT

Check VCT level: NOTE: The CRS/HCO will contact the AO.

81M DRIVER: as AO, acknowledge, and monitor T _L 139 in INSIGHT to report local LI-139 reading. o Level- GREATER THAN 20% OR Level- STABLE OR RISING HCO (Step 35) Check Charging Pump Suction Aligned to VCT:

VCT level- GREATER THAN 20% 81M DRIVER: Report local VCT level reading
Verify charging pumps aligned to VCT (Step 35b RNO) Manually align valves
LCV-112C - OPEN
LCV-112B - CLOSED HCO (*Step 36) Control RCS Pressure And Charging Flow Minimize RCS-To-Secondary Leakage:
Perform appropriate action(s) from table:

At the discretion of the Lead Examiner terminate the Exam.

UNIT STATUS: Power level: 100% RCS [8] 310 ppm BAST [B]: 14000 ppm Power History: 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 SHIF1":

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-Ot-Service:

The B SI Pump is OOS tor Bearing Replacement. lCO 3.5.2 was entered 36 hours ago, and maintenance is scheduled to be completed sometime next shift.

A-52.4 Equipment Date Time Reason Required Actions Required Required Action not met Completion DatelTime B 81 Pump J-'10 0330 Bearing ITS 3.5.2 36 hrs from ITS 3.5.2 Replacement Enter Condition A current Enter Condition B date/time Required Action A.1: Restore the Required Action B.1: Be in Mode 3 Train to OPERABLE Status in 72 in 6 hours hours AND Required Action B.2: Be in Mode 4 in 12 hours

Scenario Event Description NRC Sce,nario 3 Facility: Ginna Scenario No.: 3 Op Test No.: N10-1 Examiners: Operators: (SRO) (RO) (BOP) Initial Conditions: [ The plant is at 70% power (MOL). The plant was taken to 50% due to a failure of the B MFW Pump. Corrective Maintenance was performed and plant power raised to 70% four days ago. The plant has been holding at this power level to observe the

                       . B MFW Pump operating characteristics. The plant power is now to be raised to
                       ! 100% power using 0-5.2, Load Ascension, Step 6.2.33, Placing Condensate I Booster Pumps in service.

i Turnover: I The following equipment is Out-Of-Service: The B SI Pump is OOS for Bearing i Replacement.

~.

Event Malf. No. Event Type* I Event No. Description 1 NA R-RO Load Ascension/Start Condensate Booster Pumps N-BOP i N-SRO 2 i GEN02 I C-BOP Generator Hydrogen Temperature (Cold Gas) Instrument Fails High I C-SRO 3 RCS11F I-RO BLoop Thot RTD fails Low I-BOP I(TS)-SRO 4 i FDW07C C-BOP FRV B Controller Fails Low C-SRO nd 5 ROD02-F2 R-RO Dropped Rod/2 Dropped Rod ROD02-B8 i C(TS)-SRO 6 RCS03D M-RO Large Break LOCA on BLoop Tcold M-BOP M-SRO 7 SIS02A NA Failure of A Train SIS in Auto 8 RPS07F NA Failure of the B RHR Pump to start in AUTO

        *    (N)ormal,     (R}eactivity,    (I)nstrument,     (C)omponent,      (M)ajor II
                                                      -2

Scenario Event Description NRC Sc!nario 3 Ginna 2010 NRC Scenario #3 The plant is at 70% power (MOL). The plant was taken to 50% due to a failure of the B MFW Pump. Corrective Maintenance was performed and plant power raised to 70% four days ago. The plant has been holding at this power level to observe the B MFW Pump operating characteristics. The plant power is now to be raised to 100% power using 0-5.2, Load Ascension, Step 6.2.33, Placing Condensate Booster Pumps in service. The following equipment is Out-Of-Service: The B SI Pump is OOS for Bearing Replacement. Shortly after taking the watch, the operator will raiSl9 power in accordance with 0-5.2, Load Ascension. The operator will be required to start the Condensate Booster Pumps, and then start the load ascension. The operator will addr!ss S-3.1, Boron Concentration Control, to start the load ascension. Shortly after the load increase has begun, the Generator Hydrogen Temperature (Cold Gas/TT 2023) Instrument will fail High causing the Temperature Controller to increase cooling flow to the Main Generator, and Generator Gas temperatures to start to decrease. The operator will respond in accordance with AR-J-1, HYDROGEN PANEL TROUBLE, and AR-H-22, H2 CLR TEMP HI/BYP VLV < 70% OPEN. Using AR-H-22, the operator will take manual control of the Generator Hydrogen Temp Controller (TC-2023), as necessary, to control Generator Gas Temperature. When the Generator Gas Temperature is under control, the operator will start a second Condensate Booster Pump in accordance with 0-5.2, Load Ascension. After this, a Thot RTD will fail Low. The operator will respond in accordance with AR-F-24, RCS AVG .6T DEVIATION 3°F and/or AR-F-15, RCS TAVG DEV 4°F, and enter ER-INST.1, RPS Bistable Defeat After Instrument Loop Failure. The operator will address Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation and 3.3.2, ESFAS Instrumentation. Subsequently, the B Feed Reg Valve Controller output will fail Low. The operator will respond in accordance with A-503.1, Emergency and Abnormal Operating Procedures Users Guide, and take manual control of the FRV to restore SG B level. The B Steam Generator Feed Control will remain in MANUAL through the remainder of the scenario. Shortly afterwards, Control Rod F-2 in Control Bank A will drop into the core. The operator will respond using AR-C-14, ROD BOTTOM ROD STOP, and enter AP-RCC.3, Dropped Rod Recovery. The operator will address Technical Specification 3.1.4, Rod Group Alignment Limits; and 3.2.4, QPTR. While the dropped rod is being investigated, a second Control Rod will drop, and the operator will manually trip the R.eactor in accordance with the previous guidance in Step 1 of AP-RCC.3. Upon Reactor Trip, a Large Break LOCA will occur, and Safety Injection will actuate. Upon Safety Injection actuation, only Train B of SIS will actuate, and the operator will need to manually actuate the A Train of Safety Injection. Upon the auto actuation of the B Train of Safety Injection, the B RHR Pump will fail to automatically start. The operator will need to manually start the B RHR Pump. The operator wlll enter E-O, Reactor Trip or Safety Injection. The operator will transition from E-O to E-1, Loss of Reactor or Secondary Coolant, and then transition to ES-1.3, Transfer to Cold Leg Recirculation, when RWST level reaches 28%. The operator will establish a Cold Leg Recirculation lineup.

- 3

Scenario Event Description NRC Scenario 3 The scenario will terminate at Step 9 of ES-1.3, after the crew has completed the lineup for RHR Sump Recirculation Critical Tasks: E-OH Manually start at least one low-head ECCS Pump before transition out of E-O. Safety Significance: Failure to start at least one RHR Pump, when one is 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 one RHR Pump. Failure to perform this task will leave the plant in an unanalyzed condition, and constitutes mis-operation which leads to degraded ECCS capacity. ES-1.3A Transfer to Cold Leg Recirculation and establish flow with at least one RHR Pump aligned to the Containment Sump, and discharging through an OPERABLE RHR HX and injecting into the Rx Vessel. Safety Significance: Omission or incorrect performance of this task results in adverse consequences and significant degradation in the mitigative capability of the plant. Failure to transfer to CLR before the RWST empties results in a loss of all pumped ECCS flow, and an unnecessary challenge to the CORE COOLING Critical Safety Function.

-4

Scenario Event Description NRC Scenario 3 SIMULATOR OPERATOR INSTRUCTIONS o Reset to Tern p IIC 178 (NRC 3). 70% power MOL T=O: MALF SIS03B to prevent start of B SI pump (OOS contingency) MALF SIS02A, MAN AVAIL (Failure of A SI Train to automatically activate) MALF RPS07F (Autostart failure of B RHR pump)

Set Trigger 30 TRUE when a reactor trip signal is received on either Train (RCS03D at Event 6) Insert MALF GEN02, 200,30 second Ramp, on T-1 Insert MALF RCS11F, 540°, No Ramp, on T-2 Insert MALF FDW07C, 0%,60 second Ramp on T-3 Insert MALF ROD02-F2, on T-4 Insert MALF ROD02-B8, on T-5 o i Prior to Crew Briefing RUN

Hang PROTECT Tags on A and C SI Pump Control Switches
SE~t Xenon speed to "0" (current value) after resetting IC o Crew Briefing I 1. Assign Crew Positions based on evaluation requirements

2. Review the Shift Turnover Information with the crew.

3. Provide the crew with a Reactivity Plan for the load ascension.

4. Provide the crew with a copy of 0-5.2, Step 6.2.2and beyond, and S-3.1.

T-O Begin Familiarization 0 Period At direction of Event 1 Load Ascension/Start Condensate Booster Pumps 0 examiner 0 At direction of Event 2 Generator Hydrogen Temperature (Cold Gas) Instrument examiner Fails High Trjgger #1 200°, ramped at 30 seconds GEN02 At direction of Event 3 BLoop Thot RTD fails Low 0 examiner Trigger#2 540°, No Ramp RCS1'IF

-5

Scenario Event Description NRC SCElnario 3 At direction of Event 4 FRV B Controller Fails Low 0 examiner Trigger#3 0%, ramped at 60 seconds FDW07C At direction of Event 5 Dropped Dropped Rod 0 examiner Trigger #4 ROD02-F2 Trigger #5 NOTE: T-5 will be inserted during the investigation of the first dropped rod. ROD02-B8 Continued Event 6 Large Break LOCA on BLoop Tcold 0 from Event 5 (Rx Trip) T =0 (T-30) DBA, No Ramp (Tied to T-30, Rx Trip) RCS03D Continued Event 7 Failure of A Train SIS in Auto 0 from Event 6 T=O NOTE: This Malfunction is inserted in the IC at T = O.

                 ! SIS02A Continued      Event 8                   Failure of the B RHR Pump to start in AUTO 0  from Event 6 T=O                       NOTE: This Malfunction is inserted in the IC at T = O.

RPS07F o Terminate the scenario upon direction of Lead Examiner

-6

Appendix D Operator Action Form E8-D-2 Op Test No.: N10-1 Scenario # 3 Evel1t# ....;.._ _ _ _ _ Page 7 of 54

                                                                                                --';;"~-II Event

Description:

Load Ascension/Start Condensate Booster Pumps I after taking the watch, the operator will raise power in accordance with 0-5.2, Load Ascension. The operator will be requin3d to start the Condensate Booster Pumps, and then start the load ascension. The operator will address 8-3.1, Boron Concentration Control, to start the load ascension. Booth Operator Instructions: NA . Indications Available: NA 0-5.2, LOAD ASCENSION being made per Step 6.2.24. Steps 6.2.26 thru 6.2.32 are completed. (Step 6.2.33) WHEN trim valves are closed AND MFW Pump suction pressure

                    . approaches 200 PSIG, THEN PLACE Condensate Booster Pumps in service as follows:

(Step 6,2,33.1) ADJUST TRIM VLV

                    . CONTROL, AOV-9508D AOV-9508G, controller output in AUTO UNTIL the first (Step 6.2,33,3) PLACE the standby                 NOTE: The CO will place one Condensate Pump control switch in the             Condensate Pump in Pull STOP position AND INDICATE which          Stop, was placed in PULL STOF" CO      (Step 6,2.33.4) PLACE one Condensate              NOTE: The CO will START BO(JstE~r Pump switch to the RUN position        one Condensate Booster INDICATE which pump was placed in          Pump.

Aeeendix 0 Oeerator Action Form ES-O-2 N10-1 -.;..._ _ _ _ Page 8 of 54 '\1 Op Test No.: L~vent

Description:

Load Ascension/Start Condensate Booster Pumps (Step 6.2.33,5) IF the Condensate Booster NOTE: The CO will depress Pump low suction pressure trip in NOT reset, the RESET pushbutton. THEN DEPRESS CNST BSTR PMPS START/RESET green RESET pushbutton. CO i (Step 6.2.33.6) VERIFY CONDENSATE NOTE: The Condensate I BOOSTER PUMP selected to RUN started. ! Booster Pump will start in AUTO. CO * (Step 6.2.33.7) IF the CONDENSATE NOTE: The Condensate BOOSTER PUMP selected to RUN in the Booster Pump did start.

                     \, previous Step did NOT automatically start ...

CRS (Step 6.2.33.8) CONTINUE power ascension while maintaining the VLV POSITION LIMIT i approximately 10% above the SETTER NOTE: The CRS will continue with the load increase. The HCO will Dilute, and the CO will increase load on the Turbine based on Step 6.2.25. S-3.1, BORON CONCENTRATION CONTROL ATTACHMENT 4, ALTERNATE DILUTION

                                                                 ----~----------------."'~--~

NOTE: The crew will perform dilutions based upon the

                                                                           . Reactivity Plan provided.

HCO (Step 1) ENSURE Attachment 1 Determinations, is complete. HCO (Step 2) The board operator SHALL the CRS of the intent to change core

                        , reactivity.

1- HCO (Step 3) The CRS SHALL acknowledge the reactivity manipulation and provide input and oversight.

Appendix 0 Operator Action Form ES-O-2 Op Test No.: N10-1 Scenario # 3 Event # Page 9 of 54

                                                            ~--------             ~~~I Event

Description:

Load Ascension/Start Condensate Booster Pumps HCO (Step 4) PLACE RMW MODE SELECTOR control switch to ALT DILUTE position, HCO I (Step 5) SET RMW TO BA BLENDER FLOW CONTROL VLV, HCV-111 ,cont.roller to the

                  , desired flowrate,

6) SET the RMW COUNTER, quantity determined in .. ~~.k~~~.

7) PLACE RMW to START position.

RMW Pump 1A or 1B

REACTOR MAKEUP TO 110C OPENS.

RMW TO BA Blender Flow Control Valve, AOV-111, throttles to preset flow rate, REACTOR MAKEUP to CHG PUMP, AOV-110B, opens (Step 9,1) PLACE RMW MODE SELECTOR control switch to AUTO position, (Step 9.2) PLACE RMW CONTHOl control switch to START position, and v1srify RMW control red light IllUMINATED,

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 3 Event

Description:

Load Ascension/Start (Step 9.3) SET RMW TO BA BL.ENDER FLOW CONTROL VALVE, HCV-111, controller to the desired setpoint, normally 40 GPM. i HCO (Step 9.4) RECORD the amount of reactor makeup water added on S-12A RCS Leakage Surveillance Instructions, Attachment RCS Leakage Surv(3illance Record. (Step 9.5) INFORM the CRS thE! manipulation is complete. 9.6) PLACE the "DILUTE" Human

                        ",rfl",rm~~n   Label next to the RMW Mode switch on the MCB.

0-5.2, LOAD CO 6.2.24) Continue with the load ascension as follows: CO (1) Verify the VALVE POS LIMIT light is extinguished CO (2) IF the valve position limit light is illuminated, then LOWER EH Control until i the valve position limit light is EXTINGUISHED as follows: Otherwis,e, mark this step as N/A

ENSURE SETTER and are matched.
ENSURE load rate thumbwheel 10%/hr

i. LOWER the SETTER setpoint (GREEN) Tpushbutton.

DEPRESS GO.

Appendix D Operator Action Form ES-D-2 . Op Test No.: N10-1 Scenario # 3 Event # ~ _ _ _ _ Page 11 of .....;;;,.54~-II Event

Description:

Load Ascension/Start Condensate Booster Pumps

WHEN valve position light extinguishes, then DEPRESS HOLD.
ENSURE Setter and Reference are matched.

CO 6.2.25) Continue with the load as follows:

                        ) RAISE the Setter setpoint to the using the (ORANGE) ...

(2) DEPRESS the GO pushbutton.

                    * (3) ENSURE VLV POSITION LIMIT setpoint

---+~--t' is adjusted as required (4) OBSERVE turbine load rises at the I-----+---~ desired rate I NOTE: The CRS will continue I with Step 6.2.33.9. 0-5.2, LOAD (Step 6.2.33.9) RAISE TRIM VLV CONTROL, AOV 95080 AOV-9~i08G, controller setpoint to approximately At the discretion of the Lead Examiner move to Event #2.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 3 Eve1t # ....;2~_ _ _ _ Page 12 of _5.:;,.4';""1 Event

Description:

Generator Hydrogen Temperature (Cold Gas) Instrument Fails High r - - - - - - - - - -....- - - - - - - - - - - - - - - - - - - - - - - - - - - - , I Shortly after the load increase has begun, the Generator Hydrogen Temperature (Cold

Gasm-2023) RTD will fail High causing the Temperature Controller to increase cooling flow to the Main Generator, and Generator Gas temperatures to start to decrease. The operator will respond in accordance with AR-J-1, HYDROGEN PANEL TROUBLE, and AR-H-22, H2 CLR TEMP HI/BYP VLV < 70% OPEN. Using AR-H-22, the operator will take manual control of the Generator Hydrogen Temp Controller (TC-2023), as necessary, to control Generator Gas Temperature. When the Generator Gas Temperature is under control, the operator will start a second Condensate Booster IP in accordance with 0-5.2, Load Ascension.

Booth Operator Instructions: Operate Trigger #1 (GEN02 (200 *30 second Q Ramp)) Indications Available:

MCB Annunciator J-1, Hydrogen Panel
MCB Annunciator H-22, H2 CLR TEMP HI/BYP VLV <70% OPEN

.* Gen Gas temp Recorder RK-30 Temps Dt3creasing I. Pt. 9 on RK-30 abruptly increases to 200°F I. TC-2023 output moving toward 0% AR~~,HYDROGENPANEL Notify an AO to investigate usin~ the NOTE: The CRS will dispatch applicable AR-H 2-PANEL-#. an AO to check the Hydrogen Panel. Booth Instructor: as AO, acknowledge, use MIS54 ACK to acknowledge the alarm, and and report that the I HYDROGEN PRESSURE HI or LOW LOW annunciator #2 AR-H-22, H2 CLR TEMP HIIBYP VLV < 70% OPEN

1) CHECK for H2 Cooler controller NOTE: The CO will place the failure (Back of MCB center Section). IF the TC-2023 in MANUAL and Controller has failed THEN PLACE the control output. Controller was Controller in Manual at 50% responding to the FAILED HI RTD.

Appendix 0 Operator Action Form ES-O-2 Op Test No.: N10-1 Scenario # 3 Event # _2~________ Page 13 of ...;;,.54':"'--11 Event Description Generator Hydrogen Temperature (Cold Gas) Instrument Fails High co (Step 2) If the controller demand is less than NOTE: Controller was at 0% 20%, THEN PLACE the controller in (full OPEN position) MANUAL at 50% (Step 3) MONITOR generator gas NOTE: Pt 9 on RK-30 has temperatures AND MAINTAIN Cold Gas failed HIGH Temperature between 38 and 45 degrees C. SIM DRIVER: Report ALL (MCB Back - Recorder RK-30) temperatures on the Generator Gas Temperature Monitor are trending downward (T-31.4 procedure) (Step 4) IF the condensate cool!~r is in NOTE: The CRS will contact service, THEN DIRECT an AO to raise the AO.

                 , Condensate flow through the Cooler by Booth Instructor: as AO, throttling closed CNST COOLER BYPASS, acknowledge.

V-3928. CO (Step 5) IF the condensate cooler is NOT in NOTE: The condensate cooler service AND it is desired to place it in is in service. I

service, THEN ...

(Step 6) CHECK Condensate Cooler J~P (MCB Back - Diff Press PI-2036 -Max 10 PSI D). NOTE: The CRS may notify theWCC. Booth Instructor: as WCCS,

acknowledge.

NOTE: The CRS will continue ! the load increase using 0-I 0-5.2, LOAD ASCENSION I

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 3 Event # 2 Page 14 of 54

                                                              ~--------                    --~i

Event Description Generator Hydrogen Temperature (Cold Gas) Instrument Fails High (Step 6.2.33.10) WHEN CONDENSATE TRIM CONTROL AOV, valve 9!50SG, is less one Condensate Booster than 20% OPEN, THEN PLACE a second : Pump.

CONDENSATE BOOSTER PUMP switch to the RUN position AND INDICATE which pump was placed in RUN.

CONDENSATE BOOSTER PUMP CO (Step 6.2.33.11) IF the CONDENSATE NOTE: The CO will depress BOOSTE PUMP selected to RUN in the the RESET pushbutton.
previous Step did NOT automatically start, THEN DEPRESS CONDST BSTR PMPS START/RESET yellow START pushbutton.

OTHERWISE, MARK the Step NlA. CO (Step 6.2.33.12) PLACE the third i CONDENSATE BOOSTER PUMP the AUTO position AND INDICATE pump was placed in AUTO.

_ _CONDENSATE CO (Step 6.2.33.13) ALIGN HOTWELL LEVEL, LC-107, controller as follows:

CO (Step 6.2.33.13a) ENSURE HOTWElL lEVEL, LC-107, controller setpoint is at

approximately 24 inches.

CO * (Step 6.2.33.13b) PLACE HOTVIIELL LEVEL, LC-1 07, controller to the AUTO position. CO (Step 6.2.33.14) PLACE the standby Condensate Pump control switch in the AUTO positions AND INDICATE which pump was placed in AUTO.

__CONDENSATE At the discretion of the Lead

Appendix D Operator Action Form ES-D-2 N10-1 Scenario # 3

Description:

BLoop Thot RTD fails After this, a Thot RTD will fail Low. The operator will respond in accordance with AR-F 24, RCS AVG b.T DEVIATION 3°F and/or AR-F-15, RCS TAVG DEV 4°F, and enter ER INST.1, RPS Bistable Defeat After Instrument Loop Failure. The operator will address

Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation and 3.3.2, I ESFAS Instrumentation .
Booth Operator Instructions: Operate Trigger #2 (RCS11 F (540°)

Indications Available:

MCB Annunciator F-24, RCS AVG b.T DEVIATION 3°F
MCB Annunciator F-15, RCS TAVG DEV 4°F
MCB Annunciator F-14, CHARGING PUMP SPEED
Tavg-Tref deviation is 4°F low
Outward Rod Motion Red status light is LIT, but without Rod Motion in automatic control
TI-404 indicates lower than other RCS temperature indications (Step 1) Place Rods in Manual will be blocked)

                                                                      . NOTE: a turbine fun back NOT occurring.
,__--+-_  ,CRS        (Step 4) IF a Tavg channel has failed, THEN go to ER-INST.1.

I : I I CRS 1(Step 5) IF average Tavg has failed, THEN ... , NOTE: average Tavg has NOT failed. I I

NOTE: The CRS will go to ER

_ _ _ _- LINST.1.

                                                                      \ ___________________          ~

AR-F-24, RCS AVG t.T DEVIATION 3°F

Appendix 0 Operator Action Form ES-O-2 Op Test No.: N10-1 Scenario # 3 Event # _3~_ _ _ _ Page 16 of -.;..54~~ Event

Description:

BLoop Thot RTD fails Low ER-INST.1, RPS BISTABLE DEFEAT AFTER INSTRUMENT LOOP FAILURE HCO/ (Step 4.1) Identify the failed instrument CO channel by observation of the bistable status board, MCB annunciators, and the MCB indication. HCOI (Step 4.2) WHEN a failed instrument loop NOTE: The CRS will identify CO andlor channel has been identified, THEN an RCS Tavg or ll.T Failure, refer to the appropriate section of this and go to Section 4.3. listed below: HCO (Step 4.3.1) IF annunciator F-15, RCS TAVG DEV 4°F, is lit, THEN AUTOMATIC Rod control will be blocked and MANUAL rod control will be required. (Step 4.3.2) An RTD failure will affect Steam NOTE: unwarranted Steam Dump response if in AUTOMATiC TAVG Dump is NOT occurring. control. IF unwarranted Steam Dump is occurring, THEN .... HCO (Step 4.3.3) An RTD (Tavg) failure will affect NOTE: The HCO will place the PRZR level setpoint. Place charging in Charging Pump Speed in MANUAL to stabilize PRZR level. MANUAL CRS (Step 4.3.4) Since Rod Insertion Limits (RIL) are generated from average ll. T, and RTD failure may result in unwarranted RIL alarms.

Refer to ITS LCOs 3.1.5 and 3.1.6 to determine actual insertion limits.

Appendix D Operator Action Form ES-D-2 N10-1 Scenario # 3 BLoop Thot RTD fails (Step 4.3.5) IF hot leg streaming has been NOTE: Power level too low for causing single channell::. T runback signals, hot leg streaming to be a THEN .. " concern (Step 4.3.6) Refer to the appropriate NOTE: The CRS will attachment for defeat of the associated determine that the Yellow control functions: Channel Attachment Tavg 404/Delta T 408 applies.

TAVG 404/DELTAT 408 YELLOW CHANNEL NOTE: The CRS will hand this I off to the CO, to coordinate ER-INST.1, RPS BISTABLE DEFEAT AFTER INSTRUMENT LOOP FAILURE YELLOW CHANNEL ATTACHMENT TAVG 404/DELTA T 408 (Step 1) Verify Rod Control selector switch in MANUAL HCO i (Step 2) Verify Charging Pump speed
controllers in MANUAL CO (Step 3) In the RIL INSERTION LIMIT rack, PLACE T/405 DELTA T DEFEAT switch to LOOP 8 UNIT 2 (Defeats the l:l T Runback and Rodstop for the failed channel AND removes the associated l:l T input from the RIL computer-Annunciators F-30 AND f-31 will clear if lit).

NOTE prior to Step 4: IF an RTD has failed, NOTE: RTD failure has THEN 80TH annunciators F-15 AND F-24 occurred. will be lit. CO (Step 4) In the STEAM DUMP rack, PLACE

              . the TAVG DEFEAT switch T/4018 to LOOP 8 UNIT 2 (removes the failed TAVG channel the Rod Control, Steam Dump AND Level Systems).

Appendix D Operator Action Form ES-D-2 Op Test No.: NiO-l Scenario # 3 Event # 3 Page 18 of 54

                                                               ~--------                           ~~~i i Event

Description:

BLoop Thot RTD fails l.ow CO (Step 5) In the (YELLOW) Y-1 PROTECTION CHANNEL 4 rack, PLACE the following bistable proving switches to DEFEAT (UP) AND verify the pmving light status is correct

404 LOOP B-2 HIGH TAVG Light OFF IF TI- NOTE: Light ON 404;::579°F LOW TAVG Light OFF IF TI-i NOTE: Light ON 404s545°F
408 LOOP B-2 OVER TEMP TRIP Light OFF IF TI-40BBHI- NOTE: Light ON 40BA OVERPOWER TRIP Light OFF IF TI-4082:TI 408C NOTE: Light ON HCO (Step 6) Verify the bistable status lights listed NOTE: All Bistable lights are

                    ! above are lit. IF any bistable status light         LIT.

above is NOT lit, THEN ...

HCOI (Step 7) Delete 404/408 from th,s CO performing the following:

Answer prompts CRS (Step 8) GO TO Step 4.3.7

                     ,RPS BISTABLE DEFEAT AFTER INSTRUMENT LOOP FAILURE (Step 4.3.7) Restore following automatic operation as

Appendix 0 Operator Action Form ES-O-2 Op Test No.: N10-1 Scenario # 3 Event

Description:

BLoop Thot RTD fails NOTE: The HCO will place Charging Pump Speed Control back in AUTO. HCO o Rod control NOTE: The HCO will place Rods back in AUTO. CO 0 Steam Dump CO 0 Turbine EH control CRS (Step 4.3.8) Check the following ITS

NOTE: The CRS Will evaluate Sections for LCO's: the Technical Specifications.

(Step 4.3.8a) Section 3.3.1, Table 3.31-1, Functions 5 and 6 (Step 4.3.8b) Section 3.3.2, Table 3.3.2-1 Function 4d CRS (Step 4.3.9) GO TO Step 4.15 HCO (Step 4.15.1) IF necessary, verify an operable channel is selected for the affected recorder. systE!mS in

HC431K
PRZR level control
Steam Dump (Unless 1 pressure failed)

Appendix D Operator Action:..:.-_ _ _ _ _ _ _--.;.F. .; o. ;. rm;.;. .;. .;E. ;. S. ;. -. ; ;D_-.; ;. .2 Op Test No.: N10-1 Scenario # 3 Event # 3 Page 20 of 54

                                                            ~-------                                           ~~~.

Event Description BLoop Thot RTD fails Low

S/G Atmas 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.

Booth Instructor: as SM/STA, acknowledge. CRS (Step 4.15.4) During normal working hours, NOTE: The CRS may notify Maintenance personnel shall be notified the WCC. immediately of the problem. Booth Instructor: as WCCS, 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. NOTE: The CRS will evaluate the Technical Specifications. TECHNICAL SPECIFICATION 3.3.1, REACTOR TRIP SYSTEM (RTS) INSTRUMENTATION LCO 3.3.1 The RTS instrumentation Function in Table 3.3.1-1 shall be OPERABLE. (functions 5 & 6) APPLICABILITY: According to Table 3.3.1-1 CRS ACTIONS CONDITION REQUIRED ACTION

Appendix 0 Operator Action Form ES-O-2 Test No.: Nl0-1 Scenario # 3 Event # 3 Page 21 of 54 Description BLoop Thot RTD fails Low A. 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 .

               . D. As required       0.1 Place by Required               channel in      6 hours Action A.1 and            trip referenced by 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. (Function 4.d)

CRS APPLICABILITY: According to Table 3.3.2-1 ACTIONS CONDITION REQUIRED COMPLETION ACTION TIME A. One or more A.1 Enter the Immediately Functions Condition with one referenced channel or in Table train 3.3.2-1 for inoperable the channel or train. F.1 Place F. As required channel in 6 hours by Required trip Actions A.1 and referenced by Table 3.3.2-1 At the discretion of the Lead

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 3 Event # 4 Page 22 of 54

                                                                 ~--------                    ~~~

Event

Description:

FRV B Controller Fails L.ow ~ UbSeqUentIY' the B Feed Reg Valve Controller output will fail Low. The operator will respond in ciccordance with A-503.1, Emergency and Abnormal Operating Procedures . Users Guide, and take manual control of the FRV to restore SG B level. The B Steam Generator Fee~Control will remain in MANU,l~L through the remainder of the scenario. ' i s ' Booth Operator Instructions: Operate Trigger #3 (FDW07C (0% Ramped at 60 Seconds>> rlndications Available:

   -_ MCB Annunciator G-22, ADFCS TROUBLE

,\ FRV476 Controller Output moves toward 0% output i-Feed Flow < Steam Flow in the B Steam Generator

~ NR Level in B Steam Generator starts to decrease 4.1) CHECK ADFACS EMMI monitor          NOTE: The CRS will dispatch Room) for the cause of the failure by  anAO.

the following: Sim Driver: as AO, acknowledge and report the monitor shows alarm is "8 FRV Position Mismatch." (Step 4.1,6) NOTIFY I&C of the ADFACS alarm. NOTE: CRS may also enter AP-FW.1 directly A-503.1, EMERGENCY AND ABNORMAL OPERATING PROCEDURES USERS GUIDE

Appendix D Operator Action Form ES-D-2 N10-1 Scenario # 3

Description:

FRV B Controller Fails (Step 5) Actions are permitted tD mitigate or NOTE: The CO will take compensate for equipment or controller MANUAL control of the B FRV failures or to isolate leaks. Permitted actions Controller. 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. AP-FW.1, ABNORMAL MFW FLOW or NPSH CRS (Step 1) Check MFW requireme:nts:

a. Power - GREATER THAN 50%

b. Both MPW pumps running

c. Go to Step 3 CRS (Step 3) Check S/G Status:

MFW flows> Steam flows CO (Step 3 RNO): IF MFW regulating valves NOTE: The CO will take

                 . NOT controlling in Auto, THEN place              MANUAL control of the B FRV affected S/G(s) MFW regulating valvE! and       Controller, if not done SG level previously.

At the discretion of the Lead Examiner move to Event #5.

Appendix D Operator Action Form ES-D-2 N10-1 Scenario # 3 Event # nd Dropped Rod/2 Dropped IShortly afterwards, Control Rod F-2 in Control Bank A will drop into the core. The operator will respond using AR-C-14, ROD BOTTOM ROD STOP, and enter AP-RCC.3, Dropped Rod Recovery. The operator will address Technical Specification 3.1.4, Rod Group Alignment Limits; and 3.2.4, QPTR. While the dropped rod is being investigated, a second Control Rod will drop, and the operator will manually trip the Reactor in accordance_with the previbus guidance in Ste2...:L2lA--"-P_--=-R:....::C-'C'-'-.-=-3.'----_ _ _ _ _ _ _---l . Booth Operator Instructions: Operate Trigger #4 (ROD02-F2) Indications Available:

MCB Annunciator C-14, ROD BOTTOM R.OD STOP
MCB Annunciator C-5, PPCS ROD SEQUENCE OR ROD DEVIATION
MCB Annunciator E-26, POWER RANGE CHANNEL DEV .:t 2%
MCB Annunciator E-28, POWER RANGE ROD DROP/STOP -5%/5 SEC
MRPI F-2 Rod indicates on bottom
- IR N35 prompt drop and flux recovery

i. Tavg decreases I. Rod out motion Red status light is LIT, but outward rod motion blocked in Auto NOTE: The crew may enter AP-RCC.3, directly.

AR-C-14, ROD BOTTOM ROD STOP i (Step 1) IF reactor is critical, THEN PERFORM the following: HCO

VERIFY Rod on the bottom i CRS
REFER TO AP-RCC.3, Dropped Rod Recovery POWER RANGE ROD DROP ROD STOP -5%/5 SEC

1) Refer to AP-RCC.3 NOTE: The CRS will go to AP RCC.3. !

AP-RCC.3, DROPPED ROD RECOVERY (Step 1) Verify Only One Rod Has

2) Place Rods to MANUAL NOTE: Rods should already be in MANUAL.

Appendix D Operator Action Form ES-D-2 Scenario # 3 Event # 5 Page 25 of 54 Op Test No.: N10-1

                                                            -=:..---

nd

Description:

Dropped Rod/2 Dropped Rod HCO (Step 3) Check Tavg - STABLE AT NOTE: Tavg will be lowering PROGRAM due to the dropped rod. CO (Step 3 RNO) Perform the following:

Place EH control in MANUA.L
Manually adjust turbine load to match Tavg and Tref.

CO * (Step 4) Verify Annunciator G-15, i DUMP ARMED - EXTINGUISHED CO (Step 5) Check Main Generator Load GREATER THAN 15 MW HCO * (Step 6) Establish Stable Plant

Tavg - TRENDING TO TREF
PRZR pressure - TRENDING TO 2235 PSIG IN AUTO
PZRZ level- TRENDING TO PROGRAM IN AUTO CONTROL CO
MFW Regulating Valves - F:ESTORING NOTE: The CO still has S/G LEVEL TO 52% IN AUTO MANUAL control of the B FRV, i CO (Step 6d RNO) Perform the following:

o Place affected S/G(s) MFW regulating valve in MANUAL o Restore S/G level to 52% (Step 7) Check QPTR - LESS THAN 1,02 i NOTE: QPTR will be> 1.02. (Step 7 RNO) Refer to ITS section 3.2.4. CRS (Step 8) Evaluate Control Rod

Appendix D Operator Action Form ES-D-2 Scenario # 3 Event # nd Dropped Rod/2 Dropped

Direct I&C to locally investigate rod NOTE: The CRS may notify failure the WCC/I&C.

Booth Instructor: as WCCSJI&C, acknowledge. Refer to ER-RCC.1, RETRI EVAL OF A i

DROPPED RCC
Rod failure identified and corrected - NOTE: The cause of the DROPPED ROD REPAIRED . dropped rod is still being investigated.

(Step 8d RNO) Perform the following: CRS (Step 8d.1 RNa) Consult Reactor Engineer NOTE: The CRS may notify and ITS section 3.1.4 for operational the RE. concerns. Booth Instructor: as RE, acknowledge. nd NOTE: Insert 2 dropped rod after ITS have been researched TECHNICAL SPECIFICATION 3.1.4, ROD GROUP ALIGNMENTS ~I CRS i LCO 3.1.4 All shutdown and control rods I shall be OPERABLE, with all individual indicated rod positions within 12 steps of I their group step counter demand position . CRS

APPLICABILITY: MODE 1, MODE 2 with Keff i

                     ;::, 1.0.

i i i i ACTIONS CONDITION REQUIRED i I ACTION i I I

Appendix D Operator Action Form ES-D-2 . Op Test No.: N1Q-1 Scenario # 3 Event # 5 Page 27 of 54 nd . Event Description Dropped Rod/2 Dropped Rod B. One rod not 8.1.1 Verify SDM 1 hour within is within the alignment limits limits specified in the COLR. OR 1 hour 8.1.2 Initiate boration to restore SDM to within limit. AND B.2 Reduce 2 hours THERMAL POWER to

                                             !575% RTP.

AND Once per 12 B.3 VerITy SDM hours in within the limits specified in the COLR. AND 72 hours 8.4 Perform SR 3.2.1.1. AND 85 Perform SR 72 hours 3.2.2.1. AND 8.6 Re-evaluate 5 days safety analyses and confirm results remain valid for duration of operation underthese conditions. TECHNICAL SPECIFICATION 3.2.4, QUADRANT POWER TILT RATIO (QPTR) Leo 3.2.4 The QPTR shall be::; 1.02.

                   . APPLICABILITY: MODE 1 with THERMAL POWER >50% RTP.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 3 Event # 5 Page 28 of 54 Event

Description:

. Dropped Rod/2 nd Droppl~d Rod CONDITION REQUIRED ACTION

Appendix D Operator Action Form ES-D-2 Test No.: N10-1 Scenario # 3 Event # Dropped Rod/2 nd Dropp(~d A. QPTR not A.l Restore 2 hours after each within limit. THERMAL QPTR POWER;;: 3% determination from RTP for each 1% of QPTR> 1.00. AND A.2 Determine QPTR Once per 12 AND flours A.3 Perform SR 3.2.1.1, SR 3.2.1.2 and 24 hours after SR 3.2.2.1. achieving equilibrium conditions from a THERMAL POWER reducllon AND per Required Action A1 AND Once per 7 days thereafter A.4 Re-evaluated safety analyses and Prior to increasing confirm THERMAL results remain POWER above valid for the the limit of duration of Required Action operation A.l under this condition. AND AS Normalize Prior to increasing excore THERMAL detectors to POWER above restore QPTR the limit of to within limit Required Action A.l AND A.6 Perform SR 3.2.1.1,SR Within 24 hours 3.2.1.2, and after achieving SR 3.2.2.1. equilibrium conditions at RTP not to exceed 48 hours after increasing THERMAL POWER above the limit of Required Action A.1

Appendix D Operator Action Form ES-D-2 N10-1 Scenario # 3 Dropped Rod/2 nd Booth Operator Instructions: Operate Trigger #5 {ROD02-FS} Indications Available: .* MRPI F-8 Rod indicates on bottom i . IR N35 prompt drop and flux recovery AP-RCC.3, (Step 1) Verify Only One Rod Has r1r",.,.,n"rl (Step 1 RNO) IF 2 or more rods dropped, THEN trip the reactor AND go to E-O, REACTOR TRIP OR SAFETY INJECTION. When the Reactor is tripped, move to Events #6-8.

Appendix D Operator Action Form ES-D-2 N10-1 Scenario # 3 Event # _6;;,:,'.;..7..;;&~8___ Page _31_ of ...,;5;..;,4---" Large Break LOCA on BLoop Teoldl Failure of A Train SIS in Autol Failure of the B RHR Pump to start in AUTO ~

  . pon Reactor Trip,-a Large Break LOCA will occur, and Safety Injection will actuate.

Upon Safety Injection actuation, only Train B of SIS will actuate, and the operator will need to manually actuate the A Train of Safety Injection. Upon the auto actuation of the

B Train of Safety Injection, the B RHR Pump will fali! to automatically start. The operator will need to manually start the B RHR Pump. The operator will enter E-O, Reactor Trip or Safety Injection. The operator will transition from E-O to E-1, Loss of Reactor or
Secondary Coolant, and then transition to ES-1.3, Transfer to Cold Leg Recirculation, i when RWST level reaches 28%. The operator will establish a Cold Leg Recirculation I ~~neup. The scenario will terminate at Step 9 of ES*-1.3, after the crew has completed the

~eup for RHR Sump Recirculation. Booth Operator Instructions: NA I NOTE: Trigger-30 tied to Rx Trip condition will actuate (RCS03D (DBA)) I .. - : c : - - : : - : - - - - - - - -

Indications Available:

I. Pzr Pressure rapidly drops

Pzr level drops to 0%
Containment pressure rapidly rises

,. Train A Safety Injection equipment fails to start

i. Train B Safety Injection equipment starts, E~xcept for the B RHR Pump which fails to start 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 SHUTDOWN RODS ON CO i (Step 3) Verify Both Trains of AC Emergency Busses Energized to at Least 440 VOLTS:

Appendix D Operator Action Form ES-D-2 N10*1 Scenario # 3 Event # _6;:;..:.*....;,.7....;;;&;..;;8~_ _ Page ~ of Large Break LOCA on BLoop Tcoldl Failure of A Train SIS in Auto/ Failure of the B RHR to start in AUTO Check if SI is Actuated: SI Annunciator LIT sequencing - BOTH TRAINS NOTE: The A Train of SI has STARTED. NOT actuated. HCO (Step 4b RNO) Manually actuate SI and CI NOTE: The HCO will manually actuate SI and CI per A-503. 1. HCO (*Step 5) Verify CNMT Spray Not Recuired: NOTE: Containment Spray is required.

Annunciator A-27, CNMT SPRAY EXTINGUISHED
CNMT pressure - LESS THAN 28 PSIG HCO (Step 5 RNO) Verify CNMT spray initiated.
IF CNMT spray NOT initiated. THEN .. NOTE: Containment Spray has actuated.

(Step 6) Direct Operator to Perform ATT 27.0, ATTACHMENT AUTOMATIC ACTION VERIFICATION 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.

Appendix D Operator Action Form ES-D-2 Op Test No.: N1Q..1 Scenario # 3 Event # _6;;J.'..;..7~&;..;;8~ _ _ Page =--- of ....,.;5;..;,4--"'1 Event Description Large Break LOCA on BLoop Tcoldl Failure of A Train SIS in Autol Failure of the B RHR Pump to start in AUTO REACTOR TRIP OR SAFETY INJECTION, ATTACHMENT 27.0, ATTACHMENT AUTOMATIC ACTION VERIFICATION (Step 1) Verify SI and RHR Pumps Running' i i I

I
All SI pumps - RUNNING The Pump is i

OOS. i !

             !                    1a RNO) Manually start SI CO

Both RHR pumps - RUNNING NOTE: The operator must manually start the B RHR Pump.

1b start RHR pumps i i CRITICAL TASK (E-O--H) Manually start at least one low-head ECCS Pump before transition out of E-O. Safety Significance: Failure to start at least one RHR Pump, when one is available to start, results in a violation of the Facility License Conditicm. The FSAR analysis results are predicted on the assumption of a minimum ECCS flowrate, which includes one RHR Pump. Failure to perform this task will leave the plant in an unanalyzed condition, and constitutes mis-operation

 !   which leads to degraded ECCS capacity.

HCOI (Step 2) Verify CNMT RECIRC Fans CO Running: i

All fans - RUNNING i
Charcoal filter dampers green status lights - EXTINGUISHED I

i i (Step 3) Check If Main Steamlines Should Be i

  !                        Isolated:                                               I

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 3 Event # 6,7 & 8 Page ~ of -.;.,54';"""-1\ Event

Description:

Large Break LOCA on BLoop Tcoldl Failure of A Train SIS in Autol Failure of the B RHR Pump to start in AUTO NOTE: Both MSIVs are Closed .

                  . (Step 3a RNO) Go to Step 4.

4) Verify MFW Isolation:

MFW pumps - TRIPPED MFW Isolation valves CLOSED (Step 5) Verify At Least Two SW Pumps RUNNING HCOI CO

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

Appendix D Operator Action Form ES-D-2 N1O*1 Scenario # 3 Event # _6;;..l,'...;..7...;;;&;.,;;8~_ _ Page ~ of _5;;..4~-I1 IEvent Description Large Break LOCA on BLoop Tcoldl Failure of A Train SIS in Autol Failure of the B RHR Pump to start in AUTO HCOI (Step 7) Check CCW System Status: CO

Verify CCW pump - AT LEAST ONE RUNNING HCOI 8) Verify SI and RHR Pump Flow:

CO SI flow indicators - CHECK FOR FLOW RHR flow indicator - CHECK FOR FLOW (Step 9) Verify SI Pump and mergency Alignment:

MOV-852A
MOV-8528
Verify SI pump C - RUNNING
Verify SI pump A - RUNNING
Verify SI pump 8 - RUNNING NOTE: The 8 SI Pump is OOS.

HCOI (Step 9d RNa) Perform the following: CO

Ensure SI pumps A and C running
Ensure SI pump C aligned to discharge line B:
MOV-871 B open NOTE: CO will have to open manually due to 8 SI pump

                                                                                   .OOS

Go to Step 10

Appendix 0 Operator Action Form ES-D-2 N10-1 Scenario # 3 Event # _6;;..:.'..;...7..;.&....;8___ Page ~ of ..,;..54';"'-""1 Large Break LOCA on BLoop TcoldJ Failure of A Train SIS in Autol Failure of the B RHR Pump to start in AUTO

At least one damper in each flowpath CLOSED
Normal Supply Air
Normal Return Air
Lavatory Exhaust Air
CREATS fans - BOTH E*O, REACTOR TRIP OR SAFETY IN..IECTION (Step 7) Verify Both MDAFW Running HCO AFW flow - INDICATED TO BOTH S/G(s)

AFW flow from each LESS THAN 230 GPM COl (*Step 9) Monitor Heat Sink: HCO

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.
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%.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 3 Event # _6:;,:,'..;..7..;;;&;..;:8~_ _ Page ~ of _5;:;.4':"--11 Event

Description:

Large Break LOCA on BLoop Tcoldl Failure of A Train SIS in Autol Failure of the B RHR Pump to start in AUTO (Step 10) Check If TDAFW Pump Can Be Stopped: i HCO

Both MDAFW pumps - RUNNING
PULL STOP TDAFW pump supply valves
MOV-3S04A
MOV-350SA COl (Step 11) Check CCW Flow to RCP Thermal Barriers:

HCO

i. Annunciator A-7, RCP 1A CCW RETURN HI TEMP OR La FLOW EXTINGUISHED

Annunciator A-15, RCOP 18 CCW RETURN HI TEMP OR LOW FLOW EXTINGUISHED

(*Step 12) Monitor RCS Tavg STABLE AT OR TRENDING TO 547°F cal (Step 12 RNa) If temperature less than ~ ', ___ 1-_H_C_o~_5_4_7_oF __a_nd__ following: pe_IT_O._r_m_t_he____~--------------------~ lo_w_e_ri_ng_'_T_H_E_N__

Stop dumping steam.
Ensure reheater steam supply valves are closed.
IF cooldown continues, THEN control total feed flow between 20 gpm to 230 ,

gpm until narrow range level greater than i 7% [25% adverse CNMT] in 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 S/G.

Appendix D Operator Action ,_ _ _ _ _ _ _ _ _ _F;..,;o;;,:.rm:..:.:..::E;;,;;S;.,:-D:;.,-=-2 Op Test No.: N10-1 Scenario # 3 Evert # 6,7& 8 Page ~ of 54 Event

Description:

Large Break LOCA on BLoop Teoldl Failure of A Train SIS in Autol Failure of the B RHR Pump to start in AUTO

IF cooldown continues, THEN close both NOTE: Both MSIVs are MSIVs. Closed.

COl (Step 13 ) Check PRZR PORVs and Spray Valves:

PORVs - CLOSED
Auxiliary Spray valves (AOV-296)

CLOSED

Check PRZR pressure LESS THAN 2260 PSIG

                  '. Normal PRZR spray valves .- CLOSED

RCP status - ANY RCP RUNNING NOTE: The RCP Trip criteria has been met almost since the start of the LOCA, and the RCPs should be stopped by (Step 15) Check If SIG Secondary Side Is Intact:
Pressure in both SIGs STABLE OR RIAING
Pressure in both SIGs GREATER THAT 110 PSIG Intact:

Appendix D Operator Action ,_ _ _ _ _ _ _ _ _.....;..Fo;;.;.r.;.;..m;.,;E;..;S;..;-D

                                                                                                                   ...-.;;;..2 Test No,:       N10-1   Scenario #       3     Eve~t#       _6;.:"..;..7..,;;.&;.,;8_ _ _ Page       ~   of   54 Event

Description:

Large Break LOCA on BLoop Tcoldl Failure of A Train SIS in Failure of the B RHR Pump to start in AUTO

Air ejector radiation monitors 47, R-48) - NORMAL
S/G Olowdown radiation monitor (R-19)

NORMAL

Steamline radiation monitors (R-31 and R-32) - NORMAL COl (Step 17) Check If RCS IS Intac'::

HCO

CNMT area radiation monitors NORMAL CRS (Step 17 RNO) Go to E-1, LOSS OF REACTOR OR SECONDARY Step 1, NOTE: The CRS will go to E 1,

                                                                                      ! NOTE: RCS << 300 PSIG due to DBA LOCA conditions than 475                     NOTE: Crew continues on to i  gpm, THEN return to the procedure and step                         E-1 transition

in effect.

E-1, LOSS OF REACTOR OR SECONDARY COOLANT HCO (Step 1) Monitor RCP Trip Criteria:

Appendix D Operator Action Form ES-D-2 Or: Test No.: N10-1 Scenario # 3 Evenl# _6.;..:,_7....;&....;8_____ Page ~ of _5....;4___-1 Event

Description:

Large Break LOCA on BLoop Tcoldl Failure of A Train SIS in Autol Failure of the B RHR Pump to start in AUTO I CRS ! (Step 1 RNO) Go to Step 2. NOTE: The RCP Trip criteria has been met almost since the start of the LOCA, and the RCPs should be stopped by now CO (Step 2) Check If S/G Intact:

Pressure in both S/Gs RISING
Pressure in both S/Gs THAN 110 PSIG

3) Monitor Intact S/G Levels:

Narrow range level - GREATER THAN 7% [25% adverse CNMT]

Control feed flow to maintain range level between 17% [2!5% ""'1\/<=1'<""

CNMT] and 50% CO (Step 4) Monitor If Secondary Radiation Levels Are Normal

Steamline radiation monitor (R-31 and R-32)

                    .*    Request Chem Tech sample S/Gs for                     NOTE: The CRS may contact activity                                              Chemistry.

Booth Instructor: as

                   ~                                                            Chemistry, acknowledge.

He:;(*Step 5) Monitor PRZR PORV Status-:- - t - - - - - - - - - - - - - - l

Appendix D Operator .Action Form ES-D-2 Test No.: N10*' Scenario # 3 Event # _6;;..:.,~7...;;;&;..;;8;.....-_ _ Page _41_ of ...;..54~-li

Description:

Large Break LOeA on BLoop Tcoldl Failure of A Train SIS in Autol Failure of the B RHR Pump to start in AUTO HCO (Step 6) Reset SL HCO (Step 7) Reset CI:

Depress CI reset pushbutton
Verify annunciator A-26, CNMT ISOLATION - EXTINGUISHED CO (Step 8) Verify Adequate SW
Check at least two SW pumps RUNNING
Dispatch AO to establish normal NOTE: The CRS will dispatch shutdown alignment (Refer to ATT-17.0, an AO.

ATTACHMENT SD-1) i Booth Instructor: as AO, CO (Step 9) Establish IA to CNMT:

Verify non-safeguards busses energized from offsite power
Bus 13 normal feed OR turbine bUilding SW lS018t1<>n valves - OPEN
MOV-4613 and MOV-4670
MOV-4614 and MOV-4664
Verify adequate air compressors RUNNING
Check IA supply:
Pressure - GREATER THAN 60 PSIG
Pressure - STABLE OR RISING

Appendix D Operator Action Form ES-[)..2 Op Test No.: N10-1 Scenario # 3 Event # _6:;.1,'..;.7-=&:..;;8~_ _ Page ~ of 54 Event

Description:

Large Break LOCA on BLoop Tcoldl Failure of A Train SIS in Autol Failure of the B RHR Pump to start in AUTO Reset both trains of XY relays for IA to CNMT AOV-5392

Verify IA to CNMT AOV-53!~2 - OPEN (Step 10) Check Normal Power Available To Charging Pumps:
Bus 14 normal feed breaker
Bus 16 normal feed breaker - I.JLUu,c:

(Step 11) Check If Charging Flow Established: Charging pumps - ANY RUNNING NOTE: There are Charging Pumps

                    *   (Step 11a RNO) Perform thl3 following:

IF CCW flow is lost to any RCP NOTE: CCW flow to the RCP thermal barrier OR any RCP #1 seal has NOT been lost, nor is any outlet temperature greater than RCP #1 seal outlet 235°F, THEN ...... .
temperature greater than I. 235"F.
Ensure HCV-142 open, demand at 0%.

(Step 11 Continued) suction aligned to RWST:

LCV-112B - OPEN
LCV-112C CLOSED
Start charging pumps and adjust charging flow as necessary to PRZR level

                                                                                 . NOTE: The HCO will start two I Charging Pumps.

12) Check If SI Should Be Terminated:

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 3 Event # _6::.z.,..;.7..;:;&:..;:8:....-__ Page ~ of ~54';""-I1 Event

Description:

Large Break LOCA on BLoop Teoldl Failure of A Train SIS in Autol Failure of the B RHR Pump to start in AUTO

Pressure - GREATER psig [1650 psig adverSH Do NOT stop SI

13) Monitor If CNMT Spray Should Be CNMT spray pumps - ANY RUNNING Determine number of CNMT spray pumps required from table CNMT spray pumps runnin!~ EQUAL TO NUMBER REQUIRED HCO i (*Step 14) Monitor IF RHR Pumps Should Be Stopped:

Check RCS pressure:
Pressure - GREATER THAN psig [350 psig adverse CNMT]

(Step 14 RNO) Go to Step 16. (Step 16) CHECK IF Should Be Stopped:

Verify Safeguards busses 14, 16, 17, and 18 voltage GREATEH THAN 440 VOLTS
Verify Safeguards busses 14, 16, 17, and 18 voltage energized by offsite power:
Emergency DIG output breakers OPEN

Appendix 0 Operator Action Form ES-O-2 Test No.: N10-1 Scenario # 3 Event # _6:;,.:.,..;".7..,;;;&;..:8:...-_ _ Page ~ of _54_-11

Description:

Large Break LOCA on BLoop Tcold/ Failure of A Train SIS in Autol Failure of the B RHR Pump to start in AUTO

AC emergency bus normal feed breakers - CLOSED
Stop any unloaded emergency DIG and NOTE: Both DIGs are running place in standby (Refer to ATT-8.1, unloaded.

ATIACHMENT DIG STOP) NOTE: The CRS will hand this off to the CO. CRS/HCO Examiner continue on page 45. ATT-8.1, ATTACHMENT DIG STOP i CO (Step A) Perform the following to STOP DIG

                   . A and restore to AUTO:

I. Verify DIG A Bus 14 supply breaker is OPEN.

Verify DIG A Bus 18 supply breaker is OPEN.
Using DIG A GOVERNOR, adjust DIG A speed to return frequency to 69 Hz
Using DIG A AUTO VOLTAGE CONTROL rheostat adjust DIG A voltage to 480 volts Place DIG A CONTROL switch to STOP r

AND immediately depress DIG A VOL T AGE SHUTDOWN button until voltage decays to zero. I i

After -60 seconds, perform the following: I
Depress DIG A FIELD 1

I

Depress DIG A RESET i
Verify DIG A AIR START SOLENOI I lights LIT II I
Verify DIG A START RELAY -

LIT I I

IF alternate cooling is being supplied to NOTE: Alternate cooling is I the DIG A per ER-D/G.2, AL TERNATE NOT being supplied to either COOLING FOR EMERGENCY DIG ... DIG.

I I I

Appendix D Operator Action Form ES-D-2 N10-1 Scenario # 3 Event # _6;;,:,'..;..7..;.&~8_ _ _ Page ~ of ....,;5;..;,4---"J

Description:

Large Break LOCA on BLoop Tcoldl Failure of A Train SIS in Autol Failure of the B RHR Pump t() start in AUTO (Step B) Perform the following to STOP DIG B and restore to AUTO:

Verify DIG B Bus 16 supply breaker is OPEN.
Verify DIG B Bus 17 supply breaker is OPEN.
Using DIG B GOVERNOR, adjust DIG B speed to return frequency to 60 Hz
Using DIG B AUTO VOLTAGE CONTROL rheostat adjust DIG voltage to 480 volts
Place DIG B CONTROL AND immediately depress DIG B VOLTAGE SHUTDOWN button lintil voltage decays to zero.
After -60 seconds, perform the following:
Verify DIG B AIR lights LIT
Verify DIG B START LIT
IF alternate cooling is being supplied to NOTE: Alternate cooling is the DIG B per ER-D/G.2, ALTERNATE NOT being supplied to either COOLING FOR EMERGENCY D/GS .... D/G.

E-1, LOSS OF REACTOR OR SECONDARY COOLANT CRS/HCO Examiner continue HERE. HCO (Step 17) Evaluate Plant Status:

Check auxiliary building radiation NORMAL
Plant vent iodine (R-1 OB)
Plant vent particulate (R-13)

Appendix 0 Operator Action Form ES-O-2 N10-1 Scenario # 3 Event # _6~,..:..7..;;&;.,,;;8;....-_ _ Page ~ of _5;;..4;"'-~1 Large Break LOCA on 8 Loop Tcoldl Failure of A Train SIS in Auto/ Failure of the B RHR Pump to start in AUTO

LTON line monitor (R-9)
CHG pump room (R-4)
WHEN TSC is manned, THEN ... NOTE: The TSC will NOT be manned.

              '. Verify adequate Rx head cooling:

Verify at least one control rod shroud fan - RUNNING
Verify one Rx compartment cooling fan - RUNNING (Step 18) Verify CNMT Sump R,ecirculation Capability:
Check RHR and Support systems:
At least one recirculation flowpath, including required power supplies, from Sump B and back to RCS available per ATT-14.5, ATTACHMENT RHR SYSTEM
At least one SW pump available.
At least one CCW pump available.
At least one CCW Hx available.
Check SW pumps - AT LEAST 2 PUMPS AVAILABLE
Dispatch AO to check AUX BLDG sub NOTE: The CRS will dispatch basement for RHR system leakage (AUX anAO.

BLDG sub-basement key may be Booth Instructor: as AO, required) acknowledge. HCO (Step 19) Check If RCS Cooldown And Depressurization Is Required:

RCS pressure - GREATER THAN 300 psig (350 psig adverse CNMT)

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 3 Event # -.;;.:6,_7_&;.....;..8_ _ _ Page ~ of _5.;...4'---11 Event Description" Large Break LOCA on BLoop Teoldl Failure of A Train SIS in Auto/ Failure of the B RHR Pump tel start in AUTO (Step 19 RNO) IF RHR pump flow greater NOTE: RHR Pump flow is > than 475 gpm, THEN go to Step 20. 450 gpm. HCO (Step 20) Establish Adequate SW Flow:

Verify at least two SW pumps RUNNING Verify AUX BLDG SW isolation valves OPEN
MOV-4615 and MOV-4734
MOV-4616 and MOV-4735
Determine required SW flow to CCW NOTE: The CRS will HXs per table: determine that the REQUIRED SW FLOW is a Total of 5000 6000 gpm equally divided to in-service HX.

SIM DRIVER: Use PID SWS2 to adjust SW flows HCOI (Step 20 continued) Direct AO to adjust SW

NOTE: The CRS will dispatch AO flow to required value an AO.
IF on normal SW discharge:

o V-4619, CCWHXA o V-4620, CCW HX B Booth Instructor: as AO, acknowledge, and use REM

CLG45 & 46 .14 to equalize

                                                                                  " SW flows. THEN, as AO,

report that flows are equalized.

HCO 21) Establish CCW flow to RHR Hxs:

Check both CCW pumps - RUNNING HCO (Step 21 RNO) Perform the following:
Start CCW pumps as power supply NOTE: The HCO will START permits (122 kweach) the A CCW Pump.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 3 Event # _6.;;..:,~7....;&....;8~__ Page ~ of _54"'-----i1 Event

Description:

Large Break LOCA on 8 Loop Tcoldl Failure of A Train SIS in Autol Failure of the B RHR PlUmp to start in AUTO valves to

MOV-738A
MOV-738B (Step 22) Check If Transfer To Cold Leg Recirculation Is Required:

HCO (Step RNO) Return to Step 17. NOTE: The CRS will continue in procedural loop until RWST is at the Switch over Criteria of 28%. ES-1.3, TRANSFER TO COLD LEG RECIRCULATION HCO (Step 3) Reset SI HCO (Step 4) Check IF Unnecessary Pumps Can Be Stopped: I HCO (Step 4a) Three SI pumps RUNNING NOTE: The B SI Pump is OOS.

Appendix D Operator Action Form ES-D-2 Test No.: N10-1 Scenario # 3 Event # _6;;.:.*..;..7..;..&...;.8_ _ _ Page ~ of _54';"";"'--11

Description:

Large Break LOCA on B: Loop Tcoldl Failure of A Train SIS in Autol Failure of the B RHR Pump to start in AUTO (Step 4c) Stop both RHR pumps and place in . NOTE: The HCO will STOP PULL STOP both RHR Pumps. (Step 4d) 80th CNMT spray pumps RUNNING HOD (Step 4e) Pull stop one CNMT spray pump NOTE: The HCO will STOP one CS Pump. (Step 4f) Check CNMT pressure LESS NOTE: Containment Pressure THAN 26 PSIG will be < 26 psig.

AOV-8368 (Step 4h) Reset CNMT spray (Step 4i) Close discharge valves for idle CNMT spray pump(s)
Pump A o MOV-860A o MOV-8608
Pump 8 o MOV-860C
MOV-860D CO (Step 5) Establish Adequate SW Flow:
Verify at least two SW pumps RUNNING

Appendix D Operator Action Form ES-D-2 Test No.: N10-1 Scenario # 3 Event # _6;;.:.,..;.,7...;;.&;..;8_ _ _ Page ~ of _5;;..4..........."

Description:

Large Break LOCA on BLoop Tcoldl Failure of A Train SIS in Autol Failure of the B RHR Pump to start in AUTO

Verify AUX BLDG SW isolation valves OPEN
MOV-4615 and MOV-4734
MOV-4616 and MOV-4735 Determine required SW flow to CCW HXs per table:
Direct AO to adjust Sw flow to required NOTE: If NOT previously value performed, The CRS will dispatch an AO.
IF on normal SW discharge:
V-4619, CCW HX A
V-4620, CCW.HX B Booth Instructor: as AO, acknowledge, and use REM CLG46 = .14 to equalize SW flows. THEN, as AO, report that flows are equalized.

i HCO (Step 6) Establish CCW flow to HHR Hxs:

Check both CCW pumps - RUNNING
Open CCW valves to RHR
MOV-738A
MOV-738B HCO (Step 7) Verify RHR System Ali9nment:
Verify the following valves - CLOSED
RHR suction valves from loop A hot leg
MOV-700
MOV-701
RHR discharge valves leg
MOV-720

Appendix 0 Operator Action,_ _ _ _ _ _ _ _ _ _..;..F.;;,;or..;.;m.;.,;E::,:S:..-.::,D.:-2;... Op Test No.: N10-1 Scenario # 3 Event # ~6*.....:7...:&:::..::;.8_ _ _ Page _51_ of 54 Event

Description:

Large Break LOCA on 8 Loop Tcoldl Failure of A Train SIS in Autol Failure of the B RHR Pump to start in AUTO

Verify RHR pump suction crosstie valves

                        -OPEN

MOV-704A
MOV-704B Verify the following valves
RHR pump discharge to Rs deluge valves
MOV-852A
MOV-852B
RHR suction from sump B (inside CNMT)
MOV-851A
MOV-851B
Verify RCDT pump suction valves from sump B CLOSED
MOV-1813A
MOV-1813B
Check MOV-738A and BOTH OPEN
Start one RHR pump - ONE RHR PUMP NOTE: The HCO will START RUNNING one RHR Pump.

Appendix D Operator Action Form ES-D-2 N10-1 Scenario # 3 Event # _6;;.\,'..;..7~&;...;8~_ _ Page =-- of _5.;..4~-11

Description:

Large Break LOCA on BLoop Tcoldl Failure of A Train SIS in Autol Failure of the B RHR Pump to start in AUTO Transfer to Cold Leg Recirculation and establish flow with at least one RHR Pump aligned to the Containment Sump, and discharging through an OPERABLE RHR HX and injecting into the Rx Vessel. Safety Significance: Omission or incorrect performance of this task results in adverse consequences and significant degradation in the mitigative capability of the plant Failure to transfer to CLR before the RWST empties results in a loss of all pumped ECCS flow, and an unnecessary challenge to the CORE COOLING Critical Safety Function. (Step 9) Check RWST Level - L:::SS THAN 15% Terminate the Exam at the discretion of the Lead Examiner

UNIT STATUS: Power Level: 75% RCS (B] 1135 ppm BAST [B]: 17500 ppm Power History: The plant has been at 75% power Core Burnup: 10000 MWD/MTU for four days. INFORMATION NEEDED TO ASSUME TO SHIFT:

The plant is at 75% power (MOL).
The plant was taken to 50% due to a failure of the B Main Feed Water Pump.
Corrective Maintenance was performed and plant power raised to this power level four days ago. The plant has been holding at this power level to observe the B MFW Pump operating characteristics.
The plant power is now to be raised to 100% power using 0-5.2, Load Ascension, Step 6.2.33, Placing Condensate Booster Pumps in service.
60 gpm letdown orifice is in service in preparation for the load ascension.
A reactivity plan has been developed which will return the unit to full power over the next 3 hour period.
The original 0-5.2 used to raise power to 75% has been closed out, and a new one re-opened commencing with Step 6.2.25.

The following equipment is Out-Of-Service:

The B SI Pump is OOS for Bearing Replacement. LCO 3.5.2 was entered 24 hrs ago.

A-S2.4 Equipment Date Time Reason Required Actions Required Required Action not met Completion DatelTime ITS 48hrsfrom the Irs 3.5.2 Replacement Enter Condition A current date and Enter Condition B time Required Action A.1: Restore the Required Action B.1 Be in Mode 3 Train to OPERABLE Status in 72 in 6 hours hours AND Required Action B.2: Be in Mode 4 in 12 hours

Scenario Event Description NRC Scenario 4 Facility: Ginna Scenario No.: 4 Op Test No.: N10-1 Examiners: Operators: (SRO) (RO) (BOP)

                  --~    ..

Initial Conditions: I The Plant is at 100% power (MOL). It is expected that immediately after turnover i the crew will swap Condensate Pumps per Maintenance Dept Work Order, and

                      , conduct routine Rod Control exercises on Control Bank D.

Turnover: The following equipment is Out-Of-Service: The B AFW Pump is OOS for Bearing Replacement. Event Malf. No. Event Event No. Type* I Description 1 CND04B N-BOP Swap Condensate Pumps (Start B, Secure C)/B Condensate Pump Trip C-SRO 2 ROD13C- N-RO Rod Control ExercisefMRPI Failure K7 C(TS)-SRO 3 PZR03C I-RO Pressurizer Level (LT -428) Fails HIGH I(TS)-SRO 4 HTR02A C-RO . Heater Drain Pump A trips/Rapid Downpower C-BOP C-SRO 5 STM04C C-BOP B SG ARV Controller (AOV-341 0) fails in AUTO C-SRO 6 STM05A M-RO MSIVs Close STM05B M-BOP M-SRO 7 STM09A NA SG Safeties lift/fail OPEN (1 per SG) STM09B 8 RPS07M NA TDAFW Pump Steam Supply Valves to Open in AUTO I RPS07N i 9 FDW11A NA A AFW Pump trips on Start

        *  (N)ormal,     (R)eactivity,  (I)nstrument,      (C)om ponent,     (M)ajor
                                                  -2

Scenario Event Description NRC Scenario 4 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 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. 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 BOn-OM 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 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 accordance with AP-TURB.5, Rapid Load Reduction. During the downpower, 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 critE~ria.

-3

Scenario Event Description NRC Scenario 4 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.

-4

Scenario Event Description NRC Scenario 4 SIMULATOR OPERATOR INSTRUCTIONS

      !""'<O~~=""'7>!:1M~f'~l'Il'~~~_""Ij/<~~'f~~Et.('~-Ifg,~,,>,,,~~"'~~'~'\""\:;<":~i~"7J
             '*ili""r::f0*i~3~", ~            14"~Jll                                  ~",,"",' ~0~-"-"""V-\"'if'" '1\@1~j~""';';'~;~;l" "<--' ~ ~',,,\~ ~ ~
     'Fr",,-;j""J'i"~""'~.d""""""                                                       "~-'/"'?r,                                                      ,,~-'\,"

t ....

                                                                                                                              \,.,,",                  ,I,
   ~                                 _'~~                                               .,r~l~,.,~~* .,. j.~" r,. ',. ;rjr~": ~:,~~ i::'.>,,">~ ':;,.7  -"'Al> ~5}'"' ,.../< -,".~"'"l~~~1
   '~~~:                                                                                                                                                   ~

0 Reset to Temp IIC 100% power MOL 179 (NRC 4). T=O: 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 3508 on B SG opens after Rx trip) Insert MALF STM09B, 100%,0 ramp, T-30 (Safety valve 3509 on A SG opens after Rx trip) 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 CND04B, 60 sec delay, T-29 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 STM05A1B, 0%, No Ramp, on T-5 10 Prior to Crew RUN Hang PROTECT tags on the A MDAFW and TDAFW Briefing pumps 0 Crew Briefing

1. Assign Crew Positions based on evaluation requirements

2. Review the Shift Turnover Information with the crew,

3. 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.

4. 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) i 0 T-O Begin Familiarization Period 0 At direction of Event 1 Swap Condensate Pumps (Start B, Secure C)/B examiner Condensate Pump Trip i Trigger #29 I

NOTE: T-29 tied to B Cond Pump CS to Start (60 CND04B i seconds delayed) I I

- 5

...-~--~~~ ---~~----------------------

Scenario Event Description NRC Scenario 4 examiner Trigger #1 ROD13C-K7 At direction of Event 3 Pressurizer Level (L T -428) Fails HIGH 0 examiner Trigger#2 100%, No Ramp PZR03C At direction of Event 4 Heater Drain Pump A trips/Rapid Downpower 0 examiner Trigger#3 HTR02A At direction of Event 5 B SG ARV Controller (AOV-3410) fails in AUTO 0 examiner Trigger #4 100%, No Ramp STM04C At direction of Event 6 MSIVs Close 0 examiner Trigger #5 STM05A 0%, No Ramp STM05B 0%, No Ramp Continued Event 7 SG Safeties lift/fail OPEN (1 per SG) from Event 6 T = 0 (T-30) NOTE: This Malfunction is inserted in the IC at T = 0, T-30 (Rx Trip) STM09A 100%, No Ramp STM09B 100%, No Ramp Continued Event 8 TDAFW Pump Steam Supply Valves to Open in AUTO 0 from Event 6 T=O NOTE: This Malfunction is inserted in the IC at T = O. RPS07M RPS07N Continued Event 9 A AFW Pump trips on Start 0 from Event 6 T=O NOTE: This Malfunction is inserted in the IC at T = O. FDW11A Terminate the scenario upon direction of Lead Examiner

-6

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event # ...;..._ _ _ _ Page 7 of 51

                                                                                                    '-;;";'--..0\1 Event

Description:

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 Instructions: NA NA SWAPPING CONDENSATE PUMPS WITH AT LEAST ONE MAIN FEED PUMP RUNNING (Step 6.4.1) PLACE the MCB switch for Condensate Pump B in PULL STOP.

           !   COl    I* (Step 6.4.2) CLOSE Condensate Pump B            . NOTE: The CO will contact an AO       discharge block valve, V-3921.                  lAO.
                                                                         . Booth Instructor: as AO, i acknowledge, and use REM-i I CND14=0, then report that V-i is CLOSED.

CO (Step 6.4.3) OPEN Condensate Pump B NOTE: The CO will contact an recircvalve, V-3910. AO. i 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 I NOTE: The CO will place LC Level Controller, LC-107, in Manual. 1107 in MANUAL. OTHERWISE, MARK this Step N/A pum~ CO (Step 6.4.5) PLACE Condensate MCB in AUTO

i i i

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event # -.;.._ _ _ _ Page 8 of ....,;5;;,.;.1--11 Event

Description:

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 Valve, 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 Pump Green and White Breaker Status light_s,.a_re_L_I_T_ _ _ _ _ _ _ _.-..1 I L _ _ __

AR-G-8, KV MOTOR OVERLOAD I-----\- co_t(Ste p 1) DETERMINE which pum~p-t-riP-p-e-d:--,-------------i

          .          '. CHECK Bus breakers for protective relay flags and possible smoke/flames.
                                                              ---+--------------1 I. IF multiple pumps trip, THEN EVALUATE isolating bus.

I I

NOTIFY electricians AND mechanics NOTE: The CRS may notify the WCC/Electricians.

Booth Instructor: as WCCS/Electricians,

                                                                       . acknowledge.

GO TO appropriate procedure:

i

E-O if reactor trippecl
AP-CW.1 if CW pump tripped I

I

AP-FW.1 if MFW pump tripped I NOTE: No identified
I procedures are applicable.

I

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Evel1t # ~ _ _ _ _ Page 9 of ...,.;5;;,.;.1-1 Event

Description:

Swap Condensate Pumps (Start B, Secure C)/B Condensate Pump Trip lb....==== NOTE: The B Condensate Pump tripped. AR-G-25, MOTOR OFF CTR SECT PMPS EXCEPT MAIN & AUX FEED PMPS CO (Step 1) Determine which pump has tripped NOTE: The B Condensate (white light at switch will be lit). Pump tripped. (Step 2) Verify standby pump Auto starts OR start standby pump, IF required HCO (Step 3) IF all charging pump(s) trippE~d, I NOTE: The Charging Pumps THEN go .... I did NOT trip. CRS i (Step 4) Notify Electrician. NOTE: The CRS may notify the WCC/Electricians. Booth Instructor: as WCCS/E lectricians, acknowledge.

5) Refer to ITS LCO 3.7.5. NOTE: Does not apply

6) Refer to TRM TR 3.1.1 and NOTE: The CRS will suspend the swap of the B Condensate Pump.

NOTE: The CO will return LC 107 to AUTO.

Appendix 0 Operator Action Form ES-O-2 Op Test No.: N10*1 Scenario # 4 Event # _ _ _ _ _ Page 10 of 51

                                                                                      --'---,1 Event Description        Swap Condensate PumJ)s (Start B, Secure C)/B Condensate Pump Trip NOTE: The CO may contact the AO, and direct that the original configuration be restored.

IF S0, SIM DRIVER: as AO, acknowledge, and use REM CND14=1 00, then report that V-3921 is OPEN, and then report that V-391 0 is CLOSED. At the discretion of the Lead

Appendix 0 Operator Actio,_n_ _ _ _ _ _ _ _ _F_o_r_m_E_S_-O_-2_ Op Test No.: N1(l..1 Scenario # 4 Event # ...,;2;;;.-..._ _ _ _ Page 11 of _5;;...1~_1I , Event

Description:

Rod Control Exercise/MRPI Failure ~ After this, the operator will conduct a routine Rod Control surveillance on Control Bank 0 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 i 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 BOnOM ROD STOP and AR-C-29, MRPI SYSTEM FAILURE, and enter AP-RCC.2, RCC/RPI Malfunction. The will address Technical Specification 3.1.7, Rod Position Indication, and 3.14, ! Group Alignment Limits. SIM DRIVER Instructions: NA Available: NA STP-O-1, ROD CONTROL SYSTEM HCO (Step 6.6.1) PLACE ROD CONTROL SELECTOR switch to CBD position. HCO (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 D on Attachment 1, Rod provided to the crew upon Position. turnover. HCO (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, Acceptable Transition Band, to determine change in individual rod position occur.
DETERMINE direction Control Bank D will be moved AND MARK the direction NOT selected N/A.
Rods moving IN - Group 2 should move before! Group 1.

OR 1

Rods moving OUT -- Group 1 should move

Appendix 0 Operator Action Form ES-O-2 Scenario # 4 Event #

                     --N10-1

Description:

Rod Control Exercise/MRPI

MOVE Control Bank D in the desired direction.
VERIFY groups within the bank are moving in the correct sequElnCe.
WHEN each rod transitions STOP AND RECORD IJU<:IH!U!

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 its i I initial position as indicated by the Group Step

           .               Counters on Attachment 1, Rod Position.

I SIM DRIVER Instructions: When HCO is restoring Control Bank D, after bank has been moved IN/OUT - 3 steps towards their normal position, operate Trigger 1 (ROD13C-K7) Indications Available:

MCB Annunciator C-29, MRPI SYSTEM FAILURE l
No flux prompt drop on Power Range recQrder

i. Tavg remains steady K-7 ERR on MRPI dis~lay screen NOTE: The crew may enter I

I AP-RCC.2 directly. AR-C-29, MRPI SYSTEM FAILURE EE HCO I. (Step 1) Verify rod indication using the MRPI I CRT OR PPCS Computer.

                                                                    ----~--------------------~

I CRS i(step 2) GO TO AP-RCC.2

Appendix D Operator Action Form ES-D-2 N10-1 Scenario # 4 Event # Rod Control Exercise/MRPI HCO (Step 3) Check SYSTEM STATUS pages f-~ CRS (Step 4) Notify the following: NOTE: The CRS may notify the WCC/I&C/RE. Booth Instructor: as i WCCSII&C/RE, acknowledge.

Operations Supervision

                                                      -      I

Reactor Engineer I
I&C (call in during off hours) I (Step 5) IF indications do NOT suggest a I
problem with Control Rods OR the Rod Control System, THEN perform PT-1 to determine MRPI System operability.

CRS (Step 6) Refer to ITS LCO 3.1.7. I--- CRS (Step 7) Refer to S-26.2. i I NOTE: The CRS will go to AP RCC.2. I AP-RCC.2, RCC/RPI MALFUNCTION i I (Step 1) Place Rods to Manual ! NOTE: The HCO will leave the i Rods in MANUAL. I I HCO . (Step 2) Check Dropped Rod Indication: Annunciator E-28, POWER RANGE NOTE: E-28 extinguished ROD DROP ROD STOP 5°Al/5 SECONDS - EXTINGUISHED I i 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 I prompt drop in neutron flux, or *

   ~__~______ ~_O_D_R_E_C_O_V_E_R_Y_.________________~_T_a_v_g_d_ro_p_.____________~i

Appendix D Operator Action Form ES-D-2 . Op Test No.:

                  - - Scenario #

Nl0-l 4 Event # 2

                                                              ~--------

Page 14 of 51

~~

Event

Description:

Rod Control Exercise/MRPI Failure

Tavg -lowering CRS
IF NOT, THEN go to StE=p 3 (Step 3) Check Tavg - STABLE AT PROGRAM (Step 6) Establish Stable Plant Conditions:
Tavg TRENDING TO TREF
PRZR pressure - TREf\IDING TO 2235 PSIG IN AUTO PRZR level- TRENDING TO i*

                    .. PROGRAM IN AUTO CONTROL MFW Regulation Valves - RESTORING S/G LEVEL TO 52% IN AUTO HCO       (Step 7) Check Control Rod Alignment:
                                                              -----+--------------------~

i. Verify all rods in affected group - i NOTE: Rod K-7 position WITHING +/- 12 STEPS OF . cannot be determined ASSOCIATED GROUP STE:P COUNTER CRS (Step 7 RNO) Refer to ITS Section 3:1.4. NOTE: The CRS will evaluate Technical Specifications.

HCO (Step 8) Check QPTR - LESS THAN 1.02 . NOTE: Since a Rod has NOT dropped, QPTR will NOT be > 1.02.

Appendix 0 Operator Actio.;..;.n_ _ _ _ _ _ _ _.;..F.;..or;.;..m;.;....;;;E;.;S...;-D;..-..;;;2;... N10-1 Scenario # 4 Event # Rod Control Exercise/MRPI i (Step 9) Verify All Individual Rod Position Indication Per Bank Operable:

MRPI system - NO MRPI SYSTEM ALARMS
MRPI system - NOT KNOWN PROBLEMS WITH MRPI SYSTEM THAT COULD RENDER ROD POSITION INDICATION INOPERABLE (Step 9 RNO) Perform the following:
Refer to ITS section 3.1.7 for required action.
Consult Reactor Engineer and plant NOTE: The CRS may notify staff to evaluate MRPI and to the WCCII&C/RE.

perform flux map per ITS. Booth Instructor: as WCCSII&C/RE, acknowledge. CRS

Go to Step 11 HCO (Step 11) Verify Affected Group Step Counters Operable:
Affected bank group step counter movement - CONSISTENT WITH MRPO TRANSITIONS (Evaluate affected bank using PT-1, ROD CONTROL SYSTEM).
Group step counters for "'TT<T~'rt WITHIN 1 STEP OF EACH

              . (Step 12) Check Reactor Conditions:

Rod insertion limit alarms EXTINGUISHED

          --I*       NIS PR ill- WITHIN DESIRED OPERATING BAND NOTE: Normal ill values CRS      (Step 13) Evaluated Plant Conditions:

Rod/MRPI malfunction - REPAIRED NOTE: The MRPI proble. m will I NOT be repaired.

Appendix D Operator Action Form ES-D-2 OpTest No.: N10-1 Scenario # 4 Event # _2=--_ _ _ _ Page 16 of 51

                                                                                                                             ---II Event

Description:

Rod Control Exercise/MRPI Failure 'f:"~_

       --1;
      ,~-
                                     ,:  -: ~--.~~ _::? .:.,; ~,~r:;\ ._!:,:;:., :-",:,..             .' -
                                                                                                         ~
                                                                                                           ~ - ~- ,..;;;

~ -'--~---~~~--~ ---~--~~~-~.~~~~ --~........ ---~---. -- --~--:.~.-~ (Step 13 RNO) Return to Step B I

                                                                        ..                     I TECHNICAL SPECIFICATION 3.1.7, ROD POSITION INDICATION LCO 3.1.7 The Microprocessor Rod Position Indication (MRPI) System and the Demand Position Indication System shaB be OPERABLE.

CRS MODES 1, CONDITION REQUIRED ACTION A. One MRPI A1 Verify the Once perS per group position of hours inoperable the rods for one or wlth more groups. inoperable position ind icators by using movable incore detectors OR 8 hours A2 Reduce THERMAL POWER to

0;50% RTP TECHNICAL SPECIFICATION 31 . .4, ROD GROUP ALIGNMENT LIMITS i LCO 3.1.4 All shutdown and control rods shall be OPERABLE, with all individual indicated rod positions within 12 steps of their group step counter demand position.

i

Appendix D Operator Action Form ES-O-2 N10-1 Scenario # 4 Event # Rod Control Exercise/MRPI - ~

   ~  ,--       -1~3                ::,-,'-:~"~:~:-     ~-       2~~-~f~\'::<~'(                     --~~

~. 1"" """ _____ _ _ _._ _ _

                     ~                       ~,  __   ~'_~~                          ___ ~~~ _ _----"_____ ~~ ___ ~

CRS APPLICABILITY: MODES 1. MODE 2 with Keff::::1.0. I I ACTIONS I CONDITION REQUIRED COMPLETION! ACTION TIME

6. One rod not 6.1.1 Verify SDM 1 hour within is within the alignment limits limtts. specified in the COLR.

OR 1 hour B.1.2 Initiate boration to restore SDM to within limit. AND B.2 Reduce 2 hours THERMAL POWER to

                                                      $75% RTP.

AND B.3 Verify SDM Once per 12 is with in the limits hours specified in the COLR. AND 72 hours BA Perform SR 3.2.1.1 AND B.5 Perform SR 72 hours 3.2.2.1. AND 6.6 Re-evaluate safety 5 days analysis and confirm results remain valid for duration of operation under these conditions. I I I I

Appendix D Operator Action Form ES-D-2 0;:> Test No.: N10*1 Scenario # 4 Event # ....::.2_ _ _ _ _ Page 18 of 51

                                                                                  --"---Ii Event

Description:

Rod Control Exercise/MRPI Failure At the discretion of the Lead Examiner move to Event #3.

Appendix D Operator Action Form ES-O-2 I Op Test No.: N10-1 Scenario # 4 Event # _3;;....-_ _ _ _ Page 19 of 51

Description:

Pressurizer Level (LT -428) Fails HIGH I 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. I 151M 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 energize
Charging Pump A Speed Control goes to O~_O_u_t,-p_u_t._ _ _ _ _ _ _ _ _ _ _- - - l 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 REM 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: LT-428 will indicate high compared to the others. HCO (Step 2) Verify Backup Heaters on at

Appendix D Operator Action Form ES-O-2 Scenario # 4 Event # 3 Page 20 of 51 Op Test No.:

                 -N10-1
                                                                ~--------                      ~~

Event

Description:

Pressurizer Level (L T -428) Fails HIGH HCO (Step 3) Check charging pump speed and NOTE: Auto pump has controls. i reduced to MIN speed (Step 4) Check Letdown in ",,,,nllr,,, I (Step 5) Control Charging and Letidoviin AR-F-28, PRESSURIZER HIGH (Step 1) Perform a channel check 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 AFTER INSTRUMENTATION LOOP FAILURE HCOI (Step 4.1) Identify the failed instrument CO channel by observation of the bistable status light board, MCB annunciators, and the MCB metering indication. (Step 4.2) WHEN a failed instrument loop NOTE: The CRS will and/or 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.

Appendix D Operator Action Form ES-D-2 N10-1 Scenario # 4 Event # _3;;...-_ _ _ _ Page 21 of _5;;..1~-I1

Description:

Pressurizer Level (LT-428) Fails HIGH '" . - ~ -- - '. - ~

~_=-::3",-_~~~~=-:_~~~~5'_!':,-'; ,:', :")~ ___:_ ~ ~_L                                 _ _ ~~~_~_ ~_~_~ ~~    __

i (Step 4.5,1) IF PRZR low level heater cut out : NOTE: The Instrument failed I has occurred, THEN.... HIGH.

           !                                                                    I i
                      * (Step 4.5.2) If letdown isolation valve. AOV-             NOTE: Normal Letdown did 427 has closed, THEN ...                                 NOT isolate.

(Step 4.5.3) REFER to the appropriate NOTE: The CRS will attachment for defeat of the associated determine that BLUE control functions. CHANNEL PRZR Level LI 428, should be addressed.

PRZR LEVEL LI-428 BLUE CHANNEL i NOTE: The CRS will hand this off to the CO, who will coordinate with the HCa.

I I REACTOR PROTECTION BISTABLE DEFEAT AFTER INSTRUMENTATION LOOP FAILURE BLUE CHANNEL ATTACHMENT PRZR LEVEL LI-428 I (Step 1) In the PLP PRESS AND LEVEL NOTE: The HCO will take i rack, check the PRZR level defeat switch MANUAL control of Charging lI428A position. Pump Speed. i

IF Ll428A is in NORMAL, THEN place L 428A to DEFEAT-3.

(Step 2) In the (BLUE) B-1 PROTECTION CHANNEL 3 rack, PLACE the bistable proving switch 428, CHANNEL ;~ HIGH LEVEL TRIP to DEFEAT (UP). Proving light will be OFF since the channel failed HIGH (87%). HCO (Step 3) PLACE PRZR LEVEL F~ECORDER transfer switch (MCB) to position 427. I (Step 4) Verify the bistable status above is lit. I I I

Appendix D Operator Actio,_n_________F_o_r_m_E_S_-D_-_2_ Pressurizer Level (L T-428)

IF the bistable status light above is NOT NOTE: The Bistable status lit, THEN ..... . light is LIT.

HCO (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" ER-INST.1, REACTOR PROTECTION BISTABLE DEFEAT AFTER INSTRUMENTATION LOOP FAILURE HCO (Step 4.5.4) Reset PRZR heaters breakers NOTE: Not necessary as necessary.

HCO * (Step 4.5.5) Restore normal letdown as NOTE: Normal Letdown did follows, if desired. i NOT isolate. I HCO (Step 4.5.6) WHEN PRZR level is restored to NOTE: The HCO will place normal, THEN place an operating charging Charging Pump Speed back in pump controller in AUTO. AUTO. (Step 4.5.7) Check the following ITS Sections for LeOs: Function 2

NOTE: PZR heaters unaffected

Appendix D Operator Actio.;,.n:.-.._ _ _ _ _ _ _ _F;.. o;;;..;r.. ;.;m..;. . .;;;E;.;;;S;.. -D;;;.. .;;-2;.. . Op Test No.: N10-1 Scenario # 4 Event # 3 Page 23 of 51

                                                              ~--------                                          ~~~

Event

Description:

Pressurizer Level (LT-428) Fails HIGH (Step 4.15.1) IF necessary, verify an operable channel is selected for the affected recorder. i (Step 4.15.2) Verify the following systems in

                  .         if desired:

Turbine EH control PRZR Pressure control o HC 431K o PRZR spray valves o PRZR heaters HCO

PRZR level control NOTE: IF NOT already done, the HCO will place Charging Pump Speed back in AUTO.

st CO

Steam Dump (unless 1 stage pressure failed)
MFW control
S/G Atmos Relief Valve CRS (Step 4.15,3) Notifications to thH following NOTE: The CRS may notify people will be made by the Shift Manager the SM/STA
Maintenance CRS (Step 4.15.4) During normal working hours, NOTE: The CRS Maintenance personnel shall be notified the WCCII&C.

immediately of the problem. Booth Instructor: as WCCSII&C, acknowledge.

Appendix 0 Operator Action Form ES-O-2 N10-1 Scenario # 4 Event # Pressurizer Level (LT-428) ' (Step 4.15.5) Du ring back shifts Maintenance personnel will be called in. HOWEVER, the L Shift Manager may defer calling people in, IF , i repairs may be deferred to the next working , ' day. l ----'---] - - - - - TECHNICAL SPECIFICATION 3.3.1, REACTOR TRIP SYSTEM (RTS) INSTRUMENTATION LCO 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE. (Function 8) APPLICABILITY: According to 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)

D As required by 0.1 Place 6 hours Required Actions channel in A.1 and trip. eferenced by Table 33.1-1 i I TECHNICAL SPECIFICATION 3.3.3, POST-ACCIDENT MONITORING (PAM) INSTRUMENTATION CRS LCO 3.3.3 The PAM instrumentation for each

Function in Table 3.3.3-1 shall be OPERABLE.

I

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event # _3;:...._ _ _ _ Page 25 of 51

                                                                                           ---11 Event

Description:

Pressurizer Level (LT-428) Fails HIGH ACTIONS CONDITION REQUIRED COMPLETION ACTION TIME A. One or more ! A.1 Restore 30 days Functions required with one channel to required OPERABLE channel status. inoperable. At the discretion of the Lead Examiner move to Event #4.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event # 4 Page 26 of

                                                              ~--------                      ~~!

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. 81M 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 eTR 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" for power >100%

                                                          -----------------------------~

NOTE: The crew will probably 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 NOTE: The CO will determine I (white light at switch will be lit). that the A Heater Drain Pump has tripped.

          !   CO     (Step 2) Verify standby pump Auto starts OR

NOTE: HOT pump does NOT start standby pump, IF required. have standby pump to start CRS . (Step 3) IF all charging pump(s) tripped, NOTE: The Charging Pumps THEN .... have NOT tripped.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event # _4~ _ _ _ _ Page 27 of 51

                                                                                             ~---il Event Description           Heater Drain Pump A trips/Rapid Downpower AR-H-17, FEED PUMP NET POSITIVE SUCTION HEAD co I (Step 1) CHECK Feedwater Pump parameters for proper parameter indication:

Suction flow (FI-2004 & FI-2005) (PPCS F2004 and F2005)
Suction press (PI-2044 & PI-2045)

(PPCS P2044 and P2045)

Discharge press (p1-2046 (PPCS P2046 and P2047)
NPSH margin (PPCS NPMRMFPB)

(Step 2) IF Feed Pump net positive suction

                 . head is confirmed not to exist, THEN go to
                 ! AP-FW.1, ABNORMAL MRW PUMP FLOW NOTE: The CRS will go to AP FW.1.

AP-FW.1, ABNORMAL MFW PUMP FLOW OR NPSH CO (Step 1) Check MRW

Both MRW pumps CRS
Go to Step 3 CO (Step 3) Check S/G Status
MFW flows - GREATER THAN STEAM FLOWS
S/G levels stabilizing or returning to program

Appendix 0 Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # -+/--- Event # 4 Page 28 of 51

Description:

Heater Drain Pump A trips/Rapid Downpower (Step 4) Verify At Least 2 CondE:'!nsate NOTE: The B Condensate Pumps - RUNNING Pump may automatically START. (Step 5) Verify Both HOT Pumps - RUNNING NOTE: The A Heater Drain Pump has tripped. CRS (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 i AP-TURB.5, RAPID LOAD REDUCTION) NOTE: The CRS will go to AP TURB.5. AP-TURB.5, RAPID LOAD REDUCTION NOTE: The CO may notify the RG&E ECC, about the intent to reduce power level. Booth Instructor: as RG&E ECC, acknowledge. NOTE: The CO may notify the CENG Generation Dispatch. Booth Instructor: as CENG Generation Dispatch, acknowledge. HCO (Step 1) Initiate Load Reduction

Verify rods in AUTO HCO (Step 1a RNO) Perform the following:

Place rods to MANUAL NOTE: If the Rods are NOT in AUTO, the HCO may place the i Rods in AUTO, or drive rods in .

                                                                . MANUAL.

Adjust Rods to match Tavg and Tref.
Reduce turbine load in Auto as follows:

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event # 4 Page 29 . Event

Description:

Heater Drain Pump A trips/Rapid Downpower

Place Turbine EH Control in OPER PAN., IMP PRESS IN,
Select desired rate on thumbwheel
Reduce the setter to the! desired load
Depress the GO button NOTE: The CO will start the

                                                                       ! load decrease.

HCO

Initiate boration at the rate determined in i NOTE: The HCO will initiate a i OPG-REACTIVITY-CALC. I boration.
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 OPG-REACTIVITY CALC):
Maintain rods above the insertion limit HCO 4) Monitor PRZR Pressure-TO 2235 PSIG IN AUTO

(*Step 5) Monitor MFW Regulating Valves RESTORING S/G LEVEL TO 52% IN AUTO ("Step 6) Monitor PRZR Level- TRENDING TO PROGRAM IN AUTO CONTROL (Step 7) check IA Available to CNMT

IA pressure - GREATER THAN

Appendix D 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

8) Check Steam Dump Status

Annunciator G-1S. STEAM DUMP ARMED-LIT
Steam dump operating
Hotwell level at setpoint (Step 10) Check If Condensate ,-,,-,v',,,,,,.

Pumps Should Be Secured o Trim valve controller set at 375 i NOTE: These conditions will psig , NOT be met. o Trim valve, AOV-9508G GREATER THAN 80%

Appendix D 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% NOTE: The Load reduction will i RTP in one hour, THEN notify RP to be "'30%.

obtain primary samples required by ITS LCO 3.4.16 NOTE: The CRS may notify the RP. Booth Instructor: as RP, acknowledge.

Power stable at desired level 18b RNO) IF power greater than 20% NOTE: If NOT at the desired further reduction is required, THEN level, the CRS will loop back to
load reduction and return to Step 2. Step 2, and THEN go to Step 19 when at 340 MWe.

At the discretion of the Lead

Appendix D Operator Action Form ES-D-2 N10-1 Scenario # 4 Description.. B SG ARV Controller During the down power, the 8 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 ~alve 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 USERS GUIDE CO (Step 5) Actions are permitted to mitigate or NOTE: The CO will take compensate for equipment or controller Manual control of AOV-3410 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 D Operator Action Form ES-D-2

                                                                                                                  ~ of .....;5~-I

! Op Test No.: ,- Nl0-1 Scenario # 4 Event # _6;;.,;.,..;.,.7,:...,;8;.:."&.;.;..;..9_ _ Page Event

Description:

MSIVs Closel SG Safeties lift/fail OPEN (1 per SG)/ TDAFW Pump Steam Supply Valves to Open in AUTO/ A AFW Pump trips on Start 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 correctl ' determi l1 ed whether plant conditions meet SI Termination criteria.

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)

I. ReS 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 Generator are Open.

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 CO (Step 2) Verify Turbine Stop Valves CLOSED CO (Step 3) Verify Both Trains of AC Emergency Busses Energized to at Least 440 VOLTS:

Appendix D Operator Action Form ES-D-2 Scenario # Event # ~ of _5..;,.1_-11 Op Test No.: N10-1

                                       -4                  _6;':"..;,.7':...;8.....
                                                                                , ..;,.&..;,.9_ _ Page

Description:

MSIVs Closel SG Safeties liftlfail OPEN (1 per SG)J TDAFW Pump Steam Supply Valves to Open in AUTOI A AFW Pump trips on Start

Bus 16 and Bus 17 HCOI (Step 4) Check if SI is Actuated: NOTE: The cooldown may CO NOT have created the conditions necessary to automatically actuate SI yet.
Any SI Annunciator - LIT NOTE: 0-19, PZR LOW PRESS, 1750 psig HCOI (Step 4a RNO) IF any of the conditions are met, THEN manually 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 NOTE: With both Steam Generators depressurizing, RCS temperature and
pressure will be lowering i substantially, and SI will be required.

HCOI

SI sequencing - BOTH TRAINS CO STARTED.

i (Step 5) Verify CNMT Spray Not Required:

AnnUnciator A-27, CNMT SPRAY EXTINGUISHED

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event # ....;6;.:.,.;,.7,:.,.:8;,:..,.;;;;.&..;;;.9_ _ Page ~ of ....,;5;...;.1---11 Event

Description:

MSIVs Closel SG Safeties liWfaii OPEN (1 per SG)/ TDAFW Pump Steam Supply Valves to Open in AUTOI A AFW Pump trips on Start (Step 6) Direct Operator to Perform ATT 27.0, ATTACHMENT AUTOMATIC ACTION

                    . VERIFICATION 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. 1 Examiner following operator ~ NOT performing ATT-27.0

                   ~                                                                               continue at page 36.

E-O, REACTOR TRIP OR SAFETY INJECTION ATTACHMENT 27.0, ATTACHMENT AUTOMATIC ACTION VERIFICATION (Step 2) Verify CNMT RECIRC Fans Running:

All fans - RUNNING
Charcoal filter dampers green status lights - EXTINGUISHED HCOI (Step 3) Check If Main Steamlines Should Be CO Isolated:

I-----+-~.

Any MSIV - OPEN NOTE: Both MSIVs are Closed.

4.

Appendix D Operator Action,_ _ _ _ _ _ _ _ _ _ _ F........ orm_ES;...-_D....

                                                                                                                   .... -2_

Op Test No.: N10-1 Scenario # 4 Event # _6,;..;.._7'-',8.......;....&.... 9_ _ Page ~ of Event

Description:

MSIVs Closel SG Safeties lift/fail OPEN (1 per SG)/ TDAFW Pump Steam Supply Valves to Open in AUTO/ A AFW Pump trips on Start HCOI (Step 4) Verify MFW Isolation: CO

MFW pumps - TRIPPED

                  '. MFW Isolation valves - CLOSED

S/G A, AOV-3995
S/G B, AOV-3994
S/G Slowdown and sample valves CLOSED HCOI (Step 5) Verify At Least Two SW Pumps CO RUNNING
Annunciator A-25, CNMT VENTILATION ISOLATION
Verify CI and CVI valve status lights BRIGHT CNMT RECIRC fan coolers SW outlet valve status lights - BRIGHT
FCV-4561
FCV-4562

i. Letdown orifice valves - CLOSED

AOV-200A
AOV-200B
AOV-202

                                            '..;"",r",m Status:

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event # 6,7,8, & 9 Page ~ of ......;:;..51~...,! ! Event DescriptIon: MSIVs Closel SG Safeties lift/fail OPEN (1 per SG)I TDAFW Pump Steam Supply Valves to Open in AUTOI A AFW Pump trips on Start Verify CCW pump - AT LEAST ONE RUNNING HCOI (Step 8) Verify SI and RHR Pump Flow: CO

SI flow indicators - CHECK FOR FLOW
RHR flow indicator - CHECK FOR FLOW (Step 7b RNO) IF RCS pressun~ less than 150 psig manually ...
MOV-852A
MOV-852B
Verify SI pump C - RUNI\JING
Verify SI pump A - RUNNING
Verify SI pump B RUNNING
Verify SI pump C discharge OPEN
MOV-87iA
MOV-871B (Step 10) Verify CREATS Actuation:

flowpath

Appendix D Operator Action Form ES-D-2 OpTest No.: ~ Scenario # ..i- Eve:,t # 7,~8.... _6.;-.,.... , &.;. . . ;. 9_ _ Page ~ of .....;5;,....1---1 Event

Description:

MSIVs Closel SG Safeties lift/fail OPEN (1 per SG)/ TDAFW Pump Steam Supply Valves to Open in AUTOI A AFW Pump trips on Start E-O, REACTOR TRIP OR SAFETY INJECTION

                                                                          . Examiner following operator NOT performing ATT-27.0 continue HERE.

cal (Step 7) Verify Both MDAFW Pumps NOTE: The A MDAFW Pump Running has failed, and the B MDAFW HCO

                                                                          .1
                                                                          . Pump was OOS.

COl (Step 7 RNO) Manually start both MDAFW pumps. 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 TD AFW Pump.

o MOV-3505A o IVlOV-3504A COl (Step 8) Verify AFW Valve HCO AFW flow-INDICATED S/G(s) AFW flow from each LESS THAN 230 GPM

Appendix D Operator Action Form ES-D-2 01' Test No.: N10-1 Scenario # 4 Event # _6;:..:,...;.7..:...,;:..:8,...:;&;;.;9::.-_ Page ~ of _5;;.,1;"""--1 Event

Description:

MSIVs Close! SG Safeties lift/fail OPEN (1 per SG)I TDAFW Pump Steam Supply Valves to Open in AUTOI A AFW Pump trips on Start CRITICAL TASK (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 Generators. Failure to perform this task, when the ability to do so exists, results in a t1f"':lTlrln of the Facility License Condition and places the plant in an unanalyzed condition. Sink:

Check S/G narrow range GREATER THAN 7% [25%

CNMT] in any S/G (Step 9 RNa) Perform the following:

Verify total AFW flow THAN 200 GPM CRS
Go to Step 10 CRS (Step 10) Check IfTDAFW Pump Can Be Stopped:

i. Both MDAFW pumps RUNNING . NOTE: The TDAFW Pump is the ONLY source of AFW flow.

cal (Step 11) Check CCW Flow to RCP Thermal Barriers: HCO

Annunciator A-7, Rep 1A RETURN HI TEMP OR La EXTINGUISHED

Appendix D Operator .Action Form ES-D-2 Op Test No.: N10-1 Scenario # 4 Event # ....;6;;..:..,..;..7,:...;8~,.;;.;.&.-9_ _ Page ~ of _5..;..1"'-....,1 i Event

Description:

MSIVs Close/ SG Safeties lift/fail OPEN (1 per SG)/ TDAFW Pump Steam Supply Valves to Open in AUTOI A AFW Pump trips on Start Annunciator A-i5, RCOP 1 B CCW RETURN HI TEMP OR LOW FLOW EXTINGUISHED COl (*Step 12) Monitor RCS Tavg - STABLE AT NOTE: Because of the failed OR TRENDING TO 547°F open SG Safety Valves, the HCO ReS will be cooling down rapidly. COl (Step 12 RNO) If temperature IE~SS than 547°F and lowering, THEN perform the HCO following:

Stop dumping steam.
Ensure reheater steam supply valves are closed.
IF cooldown continues, THEN total feed flow between 200 gpm gpm until narrow range level 7%[25% adverse CNMT] ir at least one S/G.
WHEN S/G level greater than 7% in one S/G, THEN limit feed flow to that required to maintain level in at least one S/G.
IF cooldown continues, THEN close both NOTE: Both MSIVs are MSIVs. Closed.

(Step 13 ) Check PRZR PORVs and Spray

                    . Valves:

Check PRZR pressure - LESS THAN 2260 PSIG
Normal PRZR spray valves - CLOSED
PCV-431A
PCV-431B

Appendix D Operator Action Form ES-D-2 Test No.: N10-1 Scenario # 4 Event # _6;;.:.*..;..7l...,;'8;.:..,.;;;;.&. ;;;.9_ _ Page _41_ of _5;;,.1;....--,1

Description:

MSIVs Closel SG Safeties lift/fail OPEN (1 per SG)I TDAFW Pump Steam Supply Valves to, Open in AUTOI A AFW Pump trips on Start

  ~ -                                 ~.                   _.            -                           -

.:-~:~:: ,~~-;;::~~~~~~~~~ __.e_- :;c~~J~.~~~~_._._._~~~"_'~~:~~_._e_'__

COl (Step 14) Monitor RCP Trip Criteria: HCO

RCP status ANY RCP RUNNING
SI pumps - AT LEAST TWO RUI\INING RCS pressure minus maximum S/G NOTE: The RCP Trip Criteria I* pressure - LESS THAN 210 psi [240 psi will NOT be met.

adverse CNMT]

Pressure in both SIGs -. STABLE OR NOTE: Both SG Pressures are RISING decreasing uncontrOllably.

~--~~---4---------------------

Pressure in both SIGs -, GREATER THAN 110 PSIG CRS ,(Step 15 RNO) IF any SIG pressure lowering i in an uncontrolled manner OR completely
depressurized, THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.

i NOTE: The CRS will go to E 2. E-2, FAULTED STEAM GENERATOR ISOLATION CO (Step 1) Check MSIV of Faulted SfG(s) - NOTE: Both MSIVs are CLOSED Closed. CO (Step 2) Check If Any SIG Secondary Side Is Intact:

Check pressure in SIG A- STABLE OR
NOTE: Both SG Pressures are RISING Check pressure in SIG B RISING

Appendix D Operator Action Form ES-O-2 Op Test No.: N10-1 Scenario # 4 Event # 6,7,8, & 9 Page ~ of .-.;;..51~"" Event

Description:

MSIVs Closel SG Safeties lift/fail OPEN (1 per SG)/ TOAFW Pump Steam Supply Valves to Open in AUTOI A AFW Pump trips on Start

    -c,~ \ -:::      ~.: '3.3            :: . -,: :: ,,' :~~, - I   - oj' ~ ~:~  -=- ~: .--, "-~. ~
                                                                                                 '"..J ;" -     L          ~~ . w- ~  _::.       j
     ,   ----~~--- '"--~~-~--~~-- -~~~ --~~- -----=-"-:---~-~-~---~-~-..:

CRS (Step 2 RNO) IF both S/G pressures lowering in an uncontrolled marner, THEN go to ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM

                              , GENERATORS, Step 1 f------+----+
                                                                                                               ' NOTE: The CRS will go to i

I ECA-2.1. ~ ECA-2.1, UNCl~OLLED DEPRESSURIZATION OF Br H STEAM GENERATORS I CO (Step 1) Check Secondary Pressure I' ~. r* Boundary: f----l----.

Verify all of the following:

,~i                                                                                                               ~~!!,~BOth MSIVs are I'                                       I'
                !                          MSIVs - CLOSED
                .             I..*         M FW flow control valves - CLOSED                                                                           I

MFW regulating valves i
MFW bypass valves i
MFW pump discharge valves-CLOSED
S/G blowdown and sample valves i

CLOSED i

TDAFW pump steam supply valves NOTE: This cannot be PULL STOP accomplished since the TD AFW Pump is the only source i of AFWflow.

i

TDAFW pump flow control I NOTE: This cannot be CLOSED accomplished since the TD AFW Pump is the only source of AFW flow.

i

S/G ARVs - CLOSED Dispatch AO to locally isolate S/Gs (Refer NOTE: The CRS will dispatch to ATT-10.0, ATTACHMENT FAULTED anAO.

S/G) Booth Instructor: as AO, i acknowledge. I

Appendix D Operator Action Form ES-D-2 _6;;.1.,..;..7:...;,8;.:.,.:.;.&..;;.9_ _ Page ~ of .....;5:...;.1---i1 Op Test No.:

                       - - Scenario #

N10*1 4 Event # Event

Description:

MSIVs CloseJ SG Safeties liftJfail OPEN (1 per SG)I TDAFW Pump Steam Supply Valves to Open in AUTOI A AFW Pump trips on Start (Step 2) Control Feed Flow to Minimize RCS Cooldown:

                        * (Step 2a) Check cooldown rate in ReS cold                               NOTE: The cooldown rate is legs LESS THAN 100°F/HR                                                likely to be higher than 100°F/HR.

I CO (Step 2a RNO) Lower feed flow to 50 gpm to NOTE: The CO will lower the each S/G and go to Step 2c. AFW flow rate to each SG to 50 gpm in an effort to control (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. I 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. (Step 2c) Check RCS hot leg temperature I STABLE OR LOWERING. 1------1--- I STA I Actions taken in Step 2a RNO will reduce

AFW flow below the minimum n~quired 200 I gpm total needed to avoid entry into FR-H.1 I conditions FR-H.1, RESPONSE to LOSS of SECONDARY HEAT SINK CRS l--+--

L~-

 *1. ECA-2_..1, LIN.CONTROLLED DEPRESSURIZATION OF BO                                         ..T.H STEAM GENERATORS                    1 l..---.- - " - I_   ~                                                                        ~    .                                   I

Appendix D Operator Action Form ES-D-2 Scenario # 4 Event # ~ Test No.:

                 -N10-1                                     6,7,8, & 9    Page      of  51 Descri ption:         MSIVs Closel SG Safeties lift/fail OPEN (1 per SG)I TOAFW Pump

Steam Supply Valves to Open in AUTOI A AFW Pump trips on Start !
SI pumps - AT LEAST nNO
RCS pressure minus maximum pressure - LESS THAN 210 psi adverse CNMT]

(Step 5) Check Secondary Radiation

                    - NORMAL

Steamline radiation monitor 32)
Dispatch AO to locally cheer: steam line radiation
Request Chem Tech sample S/Gs for activity.

HCO (Step 6) Reset SI (Step 7) Monitor If RHR Pumps Stopped:

RHR pumps -ANY RUNNING IN INJECTION MODE
Check RCS Pressure:

Appendix D Operator Action Form ES-D-2 Test No.: N1D-1 Scenario # 4 Event # _6";';'...;.7.:.,.'..;.;8,...;;&_9___ Page ~ of ....;;,.51_-11 Event

Description:

MSIVs Closet SG Safeties liftffail OPEN (1 per SG)/ TDAFW Pump Steam Supply Valves to Open in AUTO! A AFW Pump trips on Start 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.

8) Monitor If CNMT Spray' Should Be I NOTE: Containment pressure

Stopped: IS normal.

CNMT spray pumps - RUNNING CRS (Step 8a RNO) Go to Step 9 HCO (Step 9) Check RWST Level- GREATER THAN 28% HCO (Step 10) Reset CI:

Depress CI reset
Verify annunciator A-26, ISOLATION - EXTINGUISHED CO (Step 11) Verify Adequate SW Flow:
Check at least two SW pumps RUNNING
Dispatch AO to establish normal NOTE: The CRS will dispatch shutdown alignment (Refer to ATI-17.0, anAO.

ATIACHMENT SD-1) Booth Instructor: as AO, acknowledge, and use

Schedule file SD-1.sch.

HCOI (Step 12) Establish IA to CNMT: CO

Verify non-safeguards bUSSi~S enl~rgized from offsite power
Bus 13 normal feed CLOSED

Appendix D Operator Action Form ES-D-2 Op Test No.: N10*1 Scenario # 4 Event # _6;;.:.*.;.7:...;.8;.:,.*.:.;.&..;;.9__ Page ~ of _5_1_-iI Event

Description:

MSIVs Close! SG Safeties lift/fail OPEN (1 per SG)/ TDAFW Pump Steam Supply Valves to Open in AUTOI A AFW Pump trips on Start ~*~~__2~'!~~~~ <- :~~____~____~_~_~_._-___

Appendix D Operator Action Form ES-D-2 Op Test No.: _N_10_-1_ Scenario # _4_ _ Event # 6, 7. 8, & 9 Page ~ of 51 ~ Event

Description:

MSIVs Closel SG Safeties IiWfaii OPEN (1 per SG)/ TDAFW Pur:;!: Steam Supply Valves to Open in AUTOI A AFW Pump trips on ;iart I

,:~~~____-: "~ .. ~~.~ t::"J"J-='- ;,-'--_~_~ =r;~ ~" ,7:, :::. '=s __~__'~___~_ ~~~: ---, , _3_~,~~

HCO (*Step 16) Monitor SI Termination Criteria: i

SI pumps - ANY RUNNING
Check RCS pressure:
Pressure - GREATER THAN 1650 psig [1650 psig adverse CNMT]

i i (Step 16b RNO) DO NOT stop SI pumps. j Perform the following: i HCO

Energize PRZR heaters and operate PRZR spray to stabilized RCS pressure greater than 1650 psig

[1650 psig adverse CNMT] I

Return to Step 2 i

Terminate the Exam at the

UNIT STATUS: Power Level: 100% RCS [B] 1145 ppm BAST [B]: 17000 ppm Power History: The plant has been at 100% power Core Burnup: 10000 MWD/MTU (MOL), for 172 days. INFORMATION NEEDED TO ASSUME 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 OOS 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 OOS for Bearing Replacement. LCO 3.7.5 entered 24 hours ago.

A-52.4 Eq uipment IDate I tTriieiReason Required Actions Required Required Action not met I Completion BMD AFW Pump I __Li10 I I 0330 I Bearing iTS 3.7.5 .. DatelTime (Curr~nt ITS 3,7,5 ,.

            ,                ' Replacement Enter Condition B            date/time + 6 Enter Condition G days)

Required Action B.1: Restore Required Action G,1: Be in Mode 3 MDAFW Train to OPERABLE in 6 hours Status in 7 days AND Required Action G.2: Be in Mode 4 in 12 hours

Mark Up Attachment 1 of STP-O-1 as follows, and provide to crew on Turnover: Attachment 1 Rod Position INITIAL FINAL POSITION POSITION POSITION PPCS MRPI STEP MRPI PPCS RPI CRT CTR CRT RPI E*3 (GRP 1) 224 212 216 224 224 224 224 212 212 216 224 224 224 224 212 212 216 224 224 RP 1) 224 224 6 224 224 1-3 (GRP 2) 224 224 212 224 224 C-S (GRP 2) 224 224 212 224 224

E*11 (GRP 2) 224 224 212 224 K-9 (GRP 2) 224 224 212 212 5 224 STEP RECORD position of STEP COUNTER EACH rod WHEN it COUNTER Attachment 1 Rod Position 224 224 224 224 224 224 STEP COUNTER

Attachment 1 Rod Position CONTROL BANK A PPCS RPI F-2 ( 1) 224 ! B-3 (GRP 1) 224 224 200 204 216 224 224 H-12 (GRP 1) 224 224 200 204 216 224 224 L-6 (GRP 1) 224 224 200 224 I H-2 (GRP 2) 224 224 203 215 224 I B-6 (GRP 2) 224 224 203 215 224 F-12 (GRP 2) 224 224 200 203 215 224 i L-3 (GRP 2) 224 224 200 203 215 224 RECORD position of EACH rod WHEN it Attachment 1 Rod Position CONTROL INITIAL BANKB POSITION MRPI PPCS MRPI PPCS CRT RPI CRT RPI 1-17 (GRP 1) 225 225 212 225 G-5 (GRP 2) 225 225 212 212 225 I E-7 (GRP 1) 225 225 212 212 225 225 225 212 216 225 STEP STEP COUNTER COUNTER

Scenario Event Description NRC Scenario 5 Facility: Ginna Scenario No.: 5 Op Test No.: N10-1 Examiners: Operators: (SRO) I (RO) (BOP) Initial Conditions: The plant is at 1 x 10-8 amps (BOL). The plant ran at 100% power for 12 days, and then tripped four days ago due to a MFW Pump failure. The repairs have been made and the plant is ready to be started back up. The crew will be directed to pull rods to the point of adding heat (POAH), and start the B MFW Pump, in accordance with 0-1.2, Plant Startup From Hot Shutdown to Full Power Load, Step 6.3.4 and beyond. Turnover: The following equipment is Out-Of-Service: The B Condensate Pump is OOS for Bearing Replacement. Event Malt. Event Type* i Event No. No. Description 1 NA R-RO Raise power to POAI-! N-SRO 2 NA N-BOP Testing of the MFW Oil Pumps N-SRO 3 CLG10 C-RO 480VAC Grounci/A CCW Pump trips w/B CCW Pump fails to start in AUTO CLG02A C(TS)-SRO A-EDS33 4 NIS05 C-BOP Loss of Compensating Voltage to Intermediate Range N35.

                          . C(TS)-SRO 5      EDS04D         C-BOP            Fault on 480V Bus 18/SW Pump D fails to start i

CLG01D C(TS)-SRO 6 CVC07A C-RO PCV-135 fails Closed C-SRO 7 RCS02D M-RO Loop B Cold Le~1 Break (1000 gpm) i M-BOP

M-SRO 8 RPS05A NA Failure of Reactor to Trip in AUTO and MANUAL RPS05B

                      ---1
       *   (N)ormal,      {R)eactivity,    (I)nstrument,    (C)omponent,       (M}ajor
                                                     -2

Scenario Event Description NRC Scenario 5 Ginna 2010 NRC Scenario #5 The plant is at 1 x 10-8 amps (BOL). The plant ran at 100% power for 12 days, and then tripped four days ago due to a MFW Pump failure. The repairs have been made and the plant is ready to be started back up. The crew will be directed to pull rods to the point of adding heat (POAH), and start the B MFW Pump, in accordance with 0-1.2, Plant Startup From Hot Shutdown to Full Power Load, Step 6.3.4 and beyond. The following equipment is Out-Of-Service: The B Condensate Pump is OOS for Bearing Replacement. Shortly after taking the watch, the operator will raise power to the POAH in accordance with Step 6.3.4 of 0-1.2, Plant Startup From Hot Shutdown to Full Power Load. The operator will raise reactor power and then control Tavg at 547 c F. After this, the operator will conduct the oil pump checks on the Main Feedwater (MFW) Pumps accordance with Attachment 5, Main Feed Pump A Startup, and Attachment 6, Main Feed Pump B Startup, of 0-1.2, Plant Startup From Hot Shutdown to Full Power Load, in preparation for starting the MFW Pumps. Subsequently, a 480VAC ground will occur on Bus 14 and the A CCW Pump will trip, and the B CCW Pump will fail to automatically start. The operator will either start the B CCW pump manually per A-503.1, Emergency and Abnormal Operating Procedures Users Guide; or respond in accordance with AR-A-22, CCW PUMP DISCHARGE LO PRESS 60 PSI, and enter AP-CCW.2, Loss of CCW During Power Operation. The operator will evaluate Technical Specification 3.7.7, CCW System. Shortly after this, the compensating voltage power supply for the Intermediate Range Nuclear Instrument N35 will fail Low. The operator will respond in accordance with AR-E-9, IR N-35 LOSS OF COMPENSATING VOLTAGE and enter ER-NIS.2, IR MALFUNTION. The operator will address Technical Specification 3.3.1, Reactor Trip Instrumentation. Shortly afterwards, a fault on 480V Bus 18 will occur resulting in Bus 18 de-energizing. The operator will respond in accordance with AR-L-2:3, BUS18 UNDER VOLTAGE SAFEGUARDS AR-L-5, SAFEGUARD BUS MAIN BREAKER OVERCURRENT TRIP, and/or AR-L-13, SAFEGUARDS BUS DIG BREAKER OVERCURRENT TRIP and enter AP-ELECT.17/18, Loss of Safeguards Bus 17/18. The D Service Water Pump has failed to start, leaving only the B SW Pump running. The operator may leave the A EDG running or trip it within AP-ELECT.17/18, but in either case align Alternate Cooling to the EDG. The operator will enter AP-SW.2, Loss of Service Water, and take actions to isolate non-essential SW loads. The operator will address Technical Specification 3.8.1, AC Sources - Modes 1, 2, 3, and 4; 3.8.9, Distribution Systems Modes 1, 2, 3,and 4; and 3.7.8, Service Water System. During the recovery, Letdown Pressure Control Valve PCV-135 will fail closed causing the Letdown Line Relief valve to lift to the PRT. The clperator will respond in accordance with AR-A 11, LETDOWN LINE HI PRESS 400 PSI, and take! manual control of the valve. After this, a 1000 gpm rupture will occur upstream of the Letdown Isolation Valve causing a Small Break LOCA. The operator will respond in accordance with AR-F-14, CHARGING PUMP SPEED, and enter AP-RCS.1, Reactor Coolant Leak. Eventually, the operator will trip the reactor, manually actuate Safety Injection, and enter E-O, Reactor Trip or Safety Injection. However, the operator will discover that the manual reactor trip push buttons have failed

-3

Scenario Event Description NRC Scenario 5 (automatic reactor trip has failed as well), and be required to de-energize the Rod Drive MG Sets in order to trip the reactor. The operator will proceed through E-O, and then transition to E-1, Loss of Reactor or Secondary Coolant, and then transition to ES-1.2, Post-LOCA Cooldown and Depressurization. The scenario will terminate at Step 10 of ES-1.2, after the crew has restored Pressurizer level to >20%. Critical Tasks: E-1C Trip all RCPs within 5 minutes of reaching trip criteria Safety Significance: Failure to trip all RCPs when required can lead to core uncovery and to fuel temperatures in excess of 2200°F. Analyses have shown that if the RCPs are tripped within 5 minutes of the trip criteria being met, PCT will remain below 2200 OF, and if this action is delayed beyond 5 minutes, this PCT will be exceeded. It is a management expectation that the RCPs be tripped as quickly as possible, but within 5 minutes when the trip criteria is met Failure to take this action represents mis operation by the operator which leads to degradation of the fuel cladding fission produce barrier, and a violation of a license condition. Manually trip the reactor prior to transition to FR-S.1, "Response to Nuclear Generation/ATWS." Safety Significance: Failure to trip the reactor when required causes a challenge to the Subcriticality Critical Safety Function that otherwise would not exist. This mis-operation by the operator necessitates the crew taking compensating action which complicates the event mitigation strategy and demonstrates an inability by the operator to recognize a failure of the automatic actuation of the RPS.

-4

Scenario Event Description NRC Scenario 5 SIMULATOR OPERATOR INSTRUCTIONS o Reset to Temp IIC 180 (NRC 5). T=O: Insert MALF CLG10 (Auto start failure of standby ccw pump on low pressure) Insert MALF RPS05A, NO MAN (Reactor trip breaker

                                                  .A failure)

Insert MALF RPS05B, NO MAN (Reactor trip breaker B failure) Insert MALF CLG01D (SWP 0 Trip) Set T-30 conditional on jmclg2a ==1 Insert MALF A-EDS33, OFF, 2 sec delay, on T-30 MALF CLG02A, on T-1 ANN A-EDS33, ON, on T-1 MALF NIS05A, 1E-8%, 0 Ramp, on T-2 MALF EDS04D, on T*3 MALF CVC07A, 0%, 0 Ramp, MAN AVAIL, on T-4 MALF RCS02D, 1000 gpm, 0 Ramp, on T-5 o Prior to Crew Briefing RUN Hang Protective Tags on the A and C Condensate Pumps. o CI"ew Briefing

1. Assign Crew Positions based on evaluation requirements

2. Review the Shift Turnover Information with the crew.

3. Hand out 0-1.2, Step 6.3 and substeps (p24-26), marked up as follows:

Step 6.3.1 -Initialed
Step 6.3.2.1 and 2 - NA
Step 6.3.3.1 - Initialed
Step 6.3.3.2.a - Initialed
Step 6.3.3.2.b - Record 111, Initialed
Step 6.3.3.2.c - Record D, Initialed
Step 6.3.3.2.d - Record 110, Initialed
Step 6.3.3.2.e - Record D, Initialed
Step 6.3.3.2.1- Record 1789, Initialed
Step 6.3.3.2.9 - Record 547, Initialed
Step 6.3.3.2.h - Initialed
Step 6.3.6 - Initialed
Step 6.3.7 -Initialed
Step 6.3.8 - NA
All other Steps blank

4. Low Power Attachment of 0-1.2 should be covered in the Pre-Job Briefing.

- 5

Scenario Event Description NRC Scenario 5

                 . Begin Familiarization i Period 0 At direction of   Event 1                    Raise power to POAH examiner At direction of   Event 2                    Testing of the MFW Oil Pumps 0    examiner At direction of   Event 3                    480VAC Ground/A CCW Pump trips w/B CCW Pump 0    examiner                                  fails to start in AUTO Trigger#1                  ON, (Simulates simultaneous 480V ground)

A-EDS33 CLG02A CLG10 (T=O) NOTE: This Malfunction is inserted in the IC at T = O. At direction of Event 4 Loss of Compensating Voltage to Intermediate Range 0 examiner N35 Trigger#2 1E-8%, No Ramp NIS05A 0 At direction of Event 5 Loss of Emergency Bus: 480V Bus 18/8W Pump D fails examiner to start (T8) Trigger #3 EDS04D CLG01D (T=O) NOTE: This Malfunction is inserted in the IC at T = O. 0 At direction of Event 6 !=)CV-135 fails Closed examiner Trigger #4 1)% (MAN AVAIL), No Ramp CVC07A 0 Continued Event 7 Loop B Cold Leg Break (1000 gpm) from Event 6 Trigger #5 1000 gpm, No Ramp RCS02D 0 Continued Event 8 Failure of Reactor to Trip in AUTO and MANUAL from Event 6 T=O NOTE: This Malfunction is inserted in the IC at T = O. RPS05A RPS05B o Terminate the scenario upon direction of Lead Examiner

- 6

Appendix D Operator Action Form ES-D-2 N10-1 Scenario # 5 Event # ....;..._ _ _ _ Page 7 of _5_3--1 Raise power to POAH I Shortly after taking the watch, the operator will raise power to the POAH in accordance

with Step 6.3.4 of 0-1.2, Plant Startup From Hot Shutdown to Full Power Load. The operator will raise reactor power and then control DRIVER Instructions: NA Available: NA 0-1.2, PLANT STARTUP FROM HOT SHUTDOWN TO FULL LOAD HCO (Step 6.3.4) WITHDRAW controlling bank of
NOTE: The HCO will raise Rods and raise Reactor Power to the pOint of i Reactor power.

adding heat without exceeding the capacity of one AFW Pump. cal (Step 6.3.5) VERIFY one of the following is CRS operating to control RCS Tavg AND MARK component NOT controlling Tavg N/A.

SG ARVs
Condenser Steam Dumps CO (Step 6.3.9) ENSURE Steps 1.1 through 1.5
are complete on the following MFW Pump Attachments for available Main Feed Water Pump(s):
Attachment 5, Main Feedwater Pump A I. Attachment 6, Main Feedwater Pump B NOTE: Final maintenance checks on MFP B are not completed, and Att.6 will NOT be performed ..

NOTE: The CRS will hand Attachment 5 off to the CO. At the discretion of the Lead Examiner move to Event #2.

,Appendix D Operator Action Form ES-D-2 i Op Test No.: N 10-1 Scenario # 5 Event # ....,:2=--_ _ _ _ Page 8 of ....,;5;;,;;.3--1 Event

Description:

Testing of the MFW Oil F)umps After this, the operator will conduct the oil pump checks on the Main Feedwater (MFW) I Pumps accordance with Attachment 5, Main Feed Pump A Startup, and Attachment 6,

Main Feed Pump B Startup, of 0-1.2, Plant Startup From Hot Shutdown to Full Power i Load, in preparation for starting the MFW Pumps.

                                                       ------------------------------~

SIM DRIVER Instructions: NA Indications Available: NA NOTE: The CO may perform these Attachments in any order. 0-1.2, PLANT STARTUP FROM HOT SHUTDOWN TO FULL LOAD ATTACHMENT 5, MAIN FEEDWATER PUMP A CO i (Step 1.0) PERFORM the following to align

and start MFW Pump A:

CO (Step 1.1) PLACE Feedwater Pump A Oil i Pump in service as follows:

                                                                        ,                                          i i

CO 1.1.1) START a i AC OIL PUMP AND MARK the Oil Pump started NIA. I i

1A1
1A2 1.1.2) PERFORM the following to ensure the FEEDWATER PUMP A DC OIL PUMP starts on low oil pressure i

                       . PLACE FEEDWATER PUMP A DC OIL PUMP in AUTO.

SLOWLY SELECT standby NOTE: The CO will need to FEEDWATER PUMP AAC OIL PUMP. move the Select Switch slowly.

i

                       . VERIFY FEEDWATER PUMP A DC OIL PUMP starts.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10*1 Scenario # 5 Event # 2 Page 9 of 53

                                                        ~--------                      ~~i Event

Description:

Testing of the MFW Oil Pumps

VERIFY MCB Alarm H-12, FEED PUMP DC OIL PUMP AUTO STAHT, annunciates.
VERIFY MCB Alarm H-4, MAIN FEED PUMP OIL SYSTEM, annunciates.
STOP FEEDWATER PUMP A DC OIL PUMP.
VERIFY MCB Alarm H-12, FEED PUMP DC OIL PUMP AUTO START is EXTINGUISHED.
VERIFY MCB Alarm H-4, MAIN FEED PUMP OIL SYSTEM, is EXTINGUISHED.
ENSURE FEEDWATER PUMP A DC OIL PUMP in AUTO.
SLOWLY SELECT the origi nal running . NOTE: The CO will need FEEDWATER PUMP A AC OIL PUMP.
move the Select Switch slowly.
OBSERVE FEEDWATER PUMP A DC OIL PUMP starts.
VERIFY MCB Alarm H-12, FEED PUMP DC OIL PUMP AUTO START, annunciates.
VERIFY MCB Alarm H-4, MAIN FEED PUMP OIL SYSTEM, annunciates.

                  **    STOP FEEDWATER PUMP A DC OIL PUMP.

VERIFY MCV Alarm H-12, FEED PUMP DC OIL PUMP AUTO START, is EXTINGUISHED.
VERIFY MCB Alarm H-4, MAIN FEED PUMP OIL SYSTEM, is EXTINGUISHED.
ENSURE FEEDWATER PUMP A DC OIL PUMP in AUTO.

NOTE: Final maintenance checks on MFP B are not completed, and Att.6 will NOT be performed*. At the discretion of the Lead Examiner move to Event #3.

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

                                         -5      Event #     3
                                                            ~--------

Page 10 of 53

                                                                                           ~~I Event

Description:

480VAC Ground/A CCW Pump trips w/B CCW Pump fails to start in AUTO . Subsequently, a 480VAC ground will occur on Bus 14 and the A CCW Pump will trip, I and the B CCW Pump will fail to automatically start. The operator will either start the B I CCW pump manually per A-503.1, Emergency and Abnormal Operating Procedures I Users Guide; or respond in accordance with AR-A-22, CCW PUMP DISCHARGE LO ! PRESS 60 PSI, and enter AP-CCW.2, Loss of CCW During Power Operation. The I operator will evaluate Technical Specification 3.7.7, CCW System. ! SIM DRIVER Instructions: Operate Trigger #1 (CLG02A, A-EDS33 (ON>> I Indications Available: I. MCB Annunciator, 480V GROUND

MCB Annunciator, CCW PUMP DISCHARGE LO PRESS 60 PSIG

i. A CCW Pump Green Breaker Status Light LIT

A CCW Pump White Breaker Status Light LIT
B CCW Pump Green Breaker Status Light LIT NOTE: The HCO may start the B CCW directly, or the crew may enter AP-CCW.2 directly.

AR-L-8, 480V GROUND CO (Step 1) Notify AOs to verify which 480V Bus NOTE: The CRS will dispatch has the ground. an AO. 51M DRIVER: as AO, acknowledge. (Step 2) Notify SS to determine WHAT NOTE: The CRS may notify eqUipment may be removed AND returned the SS. service on the affected Bus AND MCC(s). 51M DRIVER: as 55, acknowledge. (Step 3) IF necessary, THEN LCO 3.8.1 OR 3.8.2.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 5 Event # .....;3~____ Page 11 of ....,;5:..;;.3---,/ Event

Description:

480VAC Ground/A CCW Pump trips w/B CCW Pump fails to start in I

                           ~ro                                                                                 .

CRS (Step 4) IF necessary, THEN notify the NOTE: The CRS may notify following: the WCC/Electricians. 81M DRIVER: as WCC8/Electricians, acknowledge.

Electricians
Electric Planner AR-A-22, CCW PUMP DISCHARGE LO PRESS 60 PSI i CRS (Step 1) GO TO the applicable AP-CCW

                  . procedure:

i. AP-CCW.2, LOSS OF CCW DURING POWER OPERATION HCO (Step 2) Notify AO to check CCVV pumps.

HCO (Step 3) IF CCW pump cavitation is evident with normal CCW surge tank level as i indicated on LI-618, CRS (Step 4) Refer to ITS LCO 3.4.6, 3.4.7, 3.4.8, I 3.7.7,3.9.4 and 3.9.5. NOTE: The HCO may start the B CCW directly per the guidance of A-503.1, and/or the CRS may go to AP CCW.2. A-503.1, EMERGENCY AND ABNORMAL OPERATING PROCEDURES USERS GUIDE

Appendix 0 Operator Action Form ES-O-2 Op Test No.: N10-1 Scenario # 5 Event # ....;3:..-_ _ _ _ Page 12 of _5;;;,;3:"--11 Event

Description:

480VAC Ground/A CCW Pump trips w/B CCW Pump fails to start in AUTO HCO (Step 1) Manual backup is the insertion of a NOTE: The HCO may start the manual trip, actuation, or control signal after B CCW, restoring CCW flow, a given parameter has reached or exceeded and the crew MAY NOT enter the setpoint for the corresponding automatic the AP. signal, based on the observed failure of the automatic function to occur. Manual backup is in an attempt to restore or maintain the design function. Examiner NOTE: Although the CRS will probably NOT enter AP-CCW.2, it is scripted here in case he does. If NOT, proceed to Technical Specification evaluation on page 17. AP-CCW.2, LOSS OF CCW DURING POWER OPERATION HCO (Step 1) Check CCW Pump Status: Both CCW pump breaker with lights NOTE: The A CCW Pump i

EXTINGUISHED white Breaker Status light will be LIT.

(Step 1 RNO) Perform the following:

Ensure standby CCW pump running . NOTE: The HCO will start the

                                                                          . B CCW Pump here, if NOT previously started.

IF no CCW pump can be operated, .... NOTE: The B CCW Pump can be started.

IF annunciator A-22 , CCW PUMP . NOTE: Once the B CCW DISCHARGE LO PRESS 60 PSI, lit, ..... Pump is started, this annunciator will NOT be LIT.

HCO (*Step 2) Monitor CCW Surge Tank Level APPROXIMATELY 50% AND STABLE HCO , (*Step 3) Monitor CCW Hx Outlet

                   ! Temperature (MCB rear or PPCS point ID
                              )

Appendix D Operator Action Form ES-D-2 r: Tesl No., I: Event

Description:

N1Q.1 Scenario # 5 Event # ....;3~_ _ _ _ Page 13 480VAC Ground/A CCW Pump trips w/B CCW Pump fails to start in AUTO of _5;;.,;3;"""-1

i

                        -    CCW Hx Outlet temperature - LESS THAN 120°F HCO         (*Step 4) Monitor RCP Indications:
                        -    Annunciator A-7 (A-15), RCP 1A (1B)

CCW return Hi temp or low flow 165 gpm 125°F alarm - EXTINGUISHED

                        -    RCP motor bearings temperature (PPCS Group Display - RCPS OR RCP temperature monitor RK 20A recorder)       -

5 200°F.

i I i HCO (*Step 5) Monitor If Letdown Should Be Isolated:

                        -    Check annunciator A-12, Non-Regen Hx Letdown Out Hi Temp 145°F EXTINGUIHSED
                     !

Check Excess letdown temperature-I LESS THAN 195°F i i i i

HCOI (Step 6) Check CCW Valve Alignment-l AO NORMAL Check MCB CCW valves (Refer to ATT I* 1.0, ATTACHMENT AT POWER CCW ALIGNMENT) I i [ Direct AO to check local flow indications per ATT-1.1, ATTACHMENT NORMAL I NOTE: The CRS may dispatch

                                                                          . anAO.

CCWFLOW i I SIM DRIVER: as AO, acknowledge. HCOI . (Step 7) Locally Check Seal Water Hx CCW NOTE: The CRS may dispatch AO i Outlet Flow - NORMAL anAO. SIM DRIVER: as AO, acknowledge. J i i i (Step 8) check For CCW Leakage In CNMT:

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 5 Event # 3 Page 14 of 53

                                                           ~--------                        ~--~I Event

Description:

480VAC Ground/A CCW Pump trips w/B CCW Pump fails to start in AUTO

Level - STABLE
Sump A pumps - OFF
RCP oil levels - STABLE HCO . (Step 9) Check for CCW Leaka~le In AUX BLDG:
Start frequency of AUX BLDG sump pump(s) - NORMAL (Refer to ReS daily leakage log)
Waste holdup tank level- STABLE OR RISING AS EXPECTED HCO (Step 10) Verify CCW System l.eak IDENTIFIED
Leak identified NOTE: The CRS will answer this "YES" being aware that there is NO leak, and continue.
Isolate leak if possible
Refer to IP-ENV-3, RESPONSE TO A . NOTE: The CRS may NOT SPILL OF HAZARDOUS take this action, knowing that MATERIALIWASTE there is no leak.

HCO (Step 11) Check Normal or Excess Letdown . NOTE: Normal letdown is in

                   -IN SERVICE                                    service.

HCO (Step 12) Check CCW System Leak Isolated

Surge tank level- APPROXIMATELY 50%

(Step 13) Direct RP To Sample CCW System NOTE: The CRS may NOT For Chromates take this action, knowing that there is no leak.

Appendix D Operator Action Form ES-D-2 _________ Page Scenario #

                                           -  5     Event #    ~3 Op Test No.:       N10-1                                                               15   of   53
                                                                                              "';"--11 Event

Description:

480VAC Ground/A CCW Pump trips w/B CCW Pump fails to start in AUTO (Step 14) Evaluate MCB Annunciator Status (Refer to AR Procedures) CRS (Step 15) Evaluate Plant Conditfons:

CCW system malfunction -IDENTIFIED AND CORRECTED
CCW system status adequate for power operation (Refer t ITS Section 3.7.7).

CRS (Step 16) Notify Higher supervision NOTE: The CRS may notify theWCC. SIM DRIVER: as WCCS, acknowledge. (Step 17) Return to Procedure Or Guidance In Effect Examiner NOTE: If the CRS does NOT enter AP-CCW.2, continue HERE. TECHNICAL SPECIFICATION 3.7.7, COMPONENT COOLING WATER (CCW) SYSTEM

                  . LCO 3.7.7 Two CCW trains, two CCW heat            NOTE: CRS should exchangers, and the CCW loop header shall          recognize escalating MODE I be OPERABLE.                                      change to >5% power cannot occur with LCO not met.

I MPLICABILlTY: MODES 1, 2, 3" and 4. CRS CONDITION REQUIRED COMPLETION ACTION TIME A.OneCCW A.1 Restore 72 hours train CCWtrain inoperable. to OPERABLE status. At the discretion of the Lead Examiner move to Event #4.

. Appendix D Operator Action Form ES-D-2 Op Test No.: Nl0-1 Scenario # 5 Event # _4~_ _ _ _ Page 1i- of .....;5;..;.,3---t i Event

Description:

Loss of Compensating Voltage to Intermediate Range N35 Shortly after this, the compensating voltage power supply for the Intermediate Range Nuclear Instrument N35 will fail Low. The operator will respond in accordance with AR E-9, IR N-35 LOSS OF COMPENSATING VOLTAGE and enter ER-NIS.2, IR MALFUNTION. The operator will address Technical Specification 3.3.1, Reactor Trip Instru mentation. i 81M DRIVER Instructions: Operate Trigger #2 (NI805A (1 E-8%)} I [,ndications Available:

MCB Annunciator E-9, IR N-35 LOSS OF COMPENSATING VOLTAGE AR-E-9, IR N-35 LOSS OF COMPENSATION VOLrAGE CRS (Step 1) Refer to ER-NIS.2 NOTE: The CRS will go to ER NIS2.

ER-NIS.2, IR MALFUNCTION (Step 4.1) Defeat the reactor trip and rod NOTE: E-7 alarm, NIS TRIP stop function for the affected channel by BYPASS, will light placing the level trip switch in the BYPASS i position. I CRS (Step 4.2) Notify I&C to repair the faulty NOTE: The CRS may notify channel. . the WCCII&C. SIM DRIVER: as WCCSII&C, acknowledge. CRS (Step 4.3) Refer to ITS Section 3.3.1, Table 3.3.1-1, function 3 and Function 16a for NIS intermediate range channel operability requirements.

Appendix D Operator Action Form ES-D-2 Op Test No.: Nl0-1 Scenario # 5 Event # _4..;...._ _ _ _ _ Page 1l.- of ..-;;.;53~""1 Event

Description:

Loss of Compensating Voltage to Intermediate Range N35 NOTE: The CRS will evaluate Technical Specifications and determine that per Condition E, reactor SID is required to reduce power to <5e-11 amps (can't raise power> 8% due to CCW pump failure). TECHNICAL SPECIFICATION 3.3.1, REACTOR TRIP SYSTEM (RTS) INSTRUMENTATION CRS LCO 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE. APPLICABILITY: According to Table CRS ACTIONS CONDITION REQUIRED COMPLETION ACTION TIME A. One or more A.1 Enter the Immediately Functions Condition with one referenced channel in Table inoperable. 3.3.1-1 for the OR channel(s). Two source range channels inoperable. E. As required E.1 Reduce :2 hours. by Required THERMAL REQUIRED ACTION Action A.1 POWER to and < 5E-11 referenced amps. by Table 3.3.1-1. OR E.2 Increase :1 hours THERMAL No mode change with CCW POWER to pump inoperable.

                                            <=: 8% RTP.

Appendix D Operator Action,_ _ _ _ _ _ _ _ _ _ _ _F;..o;.:r.:.;m.;..;;:E.::;S..;-D;..-.;;2_ OpTest No.: Nl0-1 Scenario # 5 Event # _4.:.-_ _ _ _ Page ~ of --.53__.." Event Description Loss of Compensating Voltage to Intermediate Range N35 S, As required Verify by Required interlock is Action A.1 in required and state for referenced existing by Table plant 3.3.1-1, conditions. OR S.2 Declare 1 hour associated RTS Function channel{s) inoperable. NOTE: The CRS will evaluate Technical Specifications and determine that reactor SID is required to reduce power to

                                                                         <5e-11 amps.

At the discretion of the Lead Examiner move to Event #5.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 5 Event # 5 Page 19 of 53

                                                             ~----

Event

Description:

Fault on 480V Bus 18/8W Pump D fails to start Shortly afterwards, a fault on 480V Bus 18 will occur resulting in Bus 18 de-energizing. The operator will respond in accordance with AR-L-23, BUS18 UNDER VOLTAGE SAFEGUARDS, AR-L-5, SAFEGUARD BUS MAIN BREAKER OVERCURRENT TRIP, andlor AR-L**13, SAFEGUARDS BUS DIG BREAKER OVERCURRENT TRIP and enter AP-ELECT.17/18, Loss of Safeguards Bus 1,'/18. The D Service Water Pump has failed to start, leaving only the B SW Pump running. The operator may leave the A EDG running or trip it within AP-ELECT.17/18, but in either case align Alternate Cooling to the EDG. The operator will enter AP-SW.2, Loss of Service Water, and take actions to isolate non-essential SW loads. The operator will address Technical Specification 3.8.1, AC Sources - Modes 1, 2, 3, and 4; 3.8.9, Distribution Systems - Modes 1, 2, 3,and 4; and 3.7.8, Service Water System. 181M DRIVER Instructions: Operate Trigger #3 (EDS04D) Indications Available:

MCB Annunciator L-23, BUS 18 UNDER VOLTAGE SAFEGUARDS
MCB Annunciator L-5, SAFEGUARD BUS MAIN BREAKER OVERCURRENT TRIP
MCB Annunciator L-13, SAFEGUARDS BUS DIG BREAKER OVERCURRENT TRIP
Multiple MCB Annunciators
Bus 18 Volts indicating 0 i.
Bus 18 amperage indicating 0 A EDG starts, voltage at 480 VAC, but will not load on Bus 18.

NOTE: The crew may enter AP-ELECT.17/18 directly. AR-L-23, BUS 18 UNDER VOLTAGE SAFEGUARDS L-20 OR NOTE: These annunciators L-28 ..... are NOT LIT. CRS (Step 2) IF DIG ties onto the bus or conditions warrant clOSing in:

GO TO AP-ELEC.17/18 OR AP-ELEC.2.
Check local bus UV cabinets. (See Comments)
Check DIG for proper operation.
Notify electricians, I&C, and Performance Monitoring.

Appendix D Operator Action Form ES-D-2 Op Test No.: N1()..1 Scenario # 5 Event # 5 Page of 53

                                                               ...;;;..---         20 Event Description          Fault on 480V Bus 18/SW Pump D fails to start CRS      (Step 4) Refer to ITS LCO 3.8.1 OR 3.8.2.

~L_13' SAFEGUARDS BUS DIG BREAKER OVERCURRENT TRIP I CRS (Step 1) Notify Electricians. CRS (Step 2) Investigate overcurrent condition. I CRS (Step 3) Refer to ITS LCO 3.8.1 or 3.8.2. CRS (Step 4) When electricians haVE! corrected the overcurrent condition, reset alarm by going to the AFTER TRIP position on the i applicable breaker. I NOTE: The CRS will go to AP I ELEC.17/18. I AP-ELECT.17/18, LOSS OF SAFEGUARDS BUS 17/18 CO (Step 1) Verify Emergency DIG Associated I NOTE: The A DIG is I With Affected Bus - RUNNING RUNNING, but its breaker is NOT Closed.

Bus 18 - DIG A i

CO (Step 2) Verify Both trains Of AC Emergency Busses Energized To At Least 420 VOLTS:

Bus 14 and Bus 18
NOTE: Bus 18 is de-energized.
Bus 16 and Bus 17 CO (Step 2 RNa) IF Bus 14 AND Bus 16 are NOTE: Bus 16 is energized.

deenergized, THEN ..... i. IF one train deenergized, THEN perform the following:

Ensure DIG aligned for unit operation

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 5 Event # 5 Page 21 of 53 Event

Description:

Fault on 480V Bus 18/SW Pump D fails to start

Mode switch in UNIT
Voltage control selector in AUTO
Check DIG running.

IF NOT, THEN ..... NOTE: The A DIG is RUNNING, but its breaker is NOT Closed. Adjust DIG voltage to approximat,sly 480V.

Adjust DIG frequency to approximately 60 Hz.

CO (Step 3) Verify Service Water System Operation:

SW pumps - AT LEAST ONE RUNNING NOTE: The 0 SW Pump has IN EACH LOOP failed to Start, ONLY the B SW Pump is RUNNING.
A or B pump in Loop A
C or 0 pump in Loop B CO (Step 3a RNO) Perform the following:
Manually start SW pump as necessary NOTE: The CO may attempt (357 kweach). to START the 0 SW Pump, but it will fail.
IF adequate cooling can NOT be NOTE: The CRS will have to supplied to a running DIG. decide whether or not 1 SW Pump is adequate cooling.

IF NOT, the CRS will direct that the A DIG be stopped, and address ER-D/G.2 for Alternate Cooling. If SO, which is scripted, CRS will continue.

IF no SW pumps can be op~rated, NOTE: The B SW Pump is THEN .... RUNNING.
IF only one SW pump can be operated, THEN refer to AP-SW.2, LOSS OF SERVICE WATER.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 5 Event # 5 Page 22 of 53 . Event

Description:

Fault on 480V Bus 18/SW Pump D fails to start NOTE: The CRS will go to AP SW.2. AP-SW.2, LOSS OF SERVICE WATER (Step 1) Verify 480V AC Emergency Busses NOTE: Bus 18 is de 17 and 18 - ENERGIZED energized. (Step 1 RNa) Ensure associated O/G(s) running and attempt to manually load busses 17 andlor 18 onto their respective O/G(s). IF neither bus 17 nor bus 18 can be NOTE: Bus 17 is energized. energized, THEN ....... co (*Step 2) verify SW Pump Alignment:

Check at least one SW pump running in each loop
A or B pump in loop A NOTE: The B SW Pump is RUNNING.
C or 0 pump in loop B NOTE: Both C and 0 SW i Pumps are OFF.

Co * (Step 2a RNa) Perform the following:

Manually start SW pumps as NOTE: The CO may attempt necessary (257 kweach). to START the 0 SW Pump, but it will fail.
IF adequate cooling can NOT be NOTE: The CRS will direct supplied to a running DIG, action based on whether or THEN ...... NOT one SW Pump can adequately cool the DIG.
IF no SW pumps can be operated, NOTE: The B SW Pump is THEN ....... RUNNING.

eRS

IF only one SW pump can be operated, THEN go to Step 3.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 5 Event # 5 Page 23 of 53 Event Description Fault on 480V Bus 18/SW Pump D fails to start (Step 3) Align Alternate Cooling To One DIG (Refer to ER-D/G.2, ALTERNATE COOLING FOR EMERGENCY DIGs):

IF B or D SW Pump is operating, THEN NOTE: The CRS will dispatch align alternate cooling to DIG A per ER anAO.

D/G.2. SIM DRIVER: as AO, acknowledge, and use REM I GEN21 = OPEN. co (Step 4) Isolate SW To Non-Essential Loads

Close screenhouse SW isolation valves
MOV-4609
MOV-4780
Close air conditioning SW isolation valves
MOV-4663
MOV-4733
Direct AO to perform Part C of ATT-2.2, NOTE: The CRS will dispatch ATTACHMENT SW ISOLATION anAO.

SIM DRIVER: as AO, i acknowledge. Co (Step 5) Monitor Plant Equipmel1t Cooled By SW - TEMPERATURES STABLE

Exciter
MFP oil coolers
Instrument air compressors
Bus duct coolers
Seal Oil unit
Turbine lube oil cooler
CCWHx
SFP Hx
AFPs
Condensate Pumps

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 5 Event # 5 Page 24 of Event

Description:

Fault on 480V Bus 18/SW Pump D fails to start (Step 6) Notify Higher Supervision NOTE: The CRS may notify theWCC. SIM DRIVER: as WCCS, acknowledge. CO (Step 7) Check SW System Status:

Check SW loop header pressures:
PPCS SW low pressure alarm status

                             -NOT LOW

PPCS point 10 P21f>O
PPCS point 10 P21f>1
Pressure in both loops STABLE OR RISING
Check SW loop header pressures NOTE: The SW System GREATER THAN 40 PSIG pressures are < 40 psig.

COl * (Step 7a RNO) Locally isolate sel,acted NOTE: The CRS will dispatch SW loads as desired (Refer to ATT 2.2, . anAO. AO ATTACHMENT SW ISOLATION) SIM DRIVER: as AO, acknowledge. CO ** (Step 7b) Check at least one SW pump running in each loop:

A or B pump in loop A NOTE: The B SW Pump is RUNNING.
C or 0 pump in loop B NOTE: Both C and 0 SW Pumps are OFF.

                    *   (Step 7b RNO) Perform the following:

Continue efforts to start at least one SW pump in each loop.
I F at least two SW pumps can be NOTE: Two SW Pumps operated, THEN, ..... . cannot be operated.

Appendix D Operator Action Form ES-O-2 Op Test No.: N10-1 Scenario # 5 Event # 5 Page 25 of 53 Event

Description:

Fault on 480V Bus 18/SW Pump 0 fails to start

NOTE: The CRS will continue efforts to restore the SW System.

TECHNICAL SPECIFICATION 3.8.1, AC SOURCES - MODES 1, 2, 3 AND 4 LCO 3.8.1 The following AC electrical sources shall be OPERABLE:

One qualified independent offsite power circuit connected between the offsite transmission network and each of the onsite 480 V safeguards buses required by LCO 3.8.9, "Distribution Subsystems

                         - MODES 1, 2, 3, and 4"; and

Two emergency diesel generators (DGs) capable of supplying their rE~spective onsite 480 V safeguards buses required by LCO 3.8.9.

CRS APPLICABILITY: MODES 1, 2, 3, and 4. CRS ACTIONS CRS CONDITION REQUIRED COMPLETION ACTION TIME B. One DG B.1 Perform SR 1 hoUl" inoperable. 3.8.1.1 for the offsite AND circuit. Once per 8 hours thereafter B. Declare required feature{s) supported by the inoperable DG inoperable when its required redundant feature(s) is inoperable. AND

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 5 Event # 5 Page 26 of 53 Event

Description:

Fault on 480V Bus 18/SW Pump 0 fails to start B.3.1 Determine OPERABLE DG is not inoperable due to common cause failure. OR B.3.2 Perform SR 3.8.1.2 for OPERABLE DG. AND B.4 Restore DG to OPERABLE status. TECHNICAL SPECIFICATION 3.S.9, DISTRIBUTION SYSTEMS - MODES 1, 2, 3 AND4 CRS I LCO 3.8.9 Train A and Train B of the following electrical power distribution subsystems shall be OPERABLE:

                                                                     ~ ...

AC power.

I CRS APPLICABILITY: MODES 1, 2,3, and 4. i ACTIONS CRS I CONDITION REQUIRED COMPLETION ACTION TIME A. OneAC electrical power distribution train A.i Restore AC electrical power distribution train to l 8h,"ffi inoperable OPERABL E status. TECHNICAL SPECIFICATION 3.7.S, SERVICE WATER (SW) SYSTEM i

Appendix 0 Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 5 Event # 5 Page 27 of 53 Event

Description:

Fault on 480V Bus 18/SW Pump 0 fails to start CRS LCO 3.7.8 Four SW pumps and the SW loop header shall be OPERABLE. CRS APPLICABILITY: MODES 1, 2, 3, and 4. CRS CONDITION REQUIRED COMPLETION ACTION TIME D. Three or 0.1 Enter more SW applicable pumps or conditions and loop Required header Actions of inoperable LCO 3.7.7, "CCW System: for the component cooling water heat exchanger(s) made inoperable by SW. Enter LCO Immediately 3.0.3. At the discretion of the Lead Examiner move to Event #6.

Appendix D Operator Action Form ES-D-2 Test No.: Scenario # 5 Event # 6 Page of 53 N10-1

                                                              -.;;..---            28

Description:

PCV-135 fails Closed

During the recovery, Letdown Pressure Control Valve PCV-135 will fail closed causing i the Letdown Line Relief valve to lift to the PRT. The operator will respond in accordance with AR-A-11, LETDOWN LINE HI PRESS 400 PSI, and take manual control of the valve.

i SIM DRIVER Instructions: Operate Trigger #4 (CVC07A (O%>> Indications Available:

PCV-135 Controller output goes to 100
MCB Annunciator A-11, LETDOWN LI NE HI PRESS 400 PSI AR-A-11, LETDOWN LINE HI PRESS 400 PSI HCO (Step 1) Adjust PCV-135 controller to lower NOTE: The HCO will take setting. manual control of PCV-135, and adjust Letdown Pressure to ==250 psig.

HCO (Step 2) Transfer PCV-135 controller to

                   . manual if necessary.

HCO (Step 3) Verify letdown flow (FI-'134) is consistent with letdown orifice in service. At the discretion of the Lead Examiner move to Events #7-8.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 5 Event # _7;...&;;..;;..8_ _ _ Page ~ of _5;....3---11 Event

Description:

Loop B Cold Leg Break (1000 gpm)/ Failure of Reactor to Trip in AUTO and MANUAL i After this, a 1000 gpm rupture will occur upstream of the Letdown Isolation Valve

causing a Small Break LOCA. The operator will respond in accordance with AR-F-14, CHARGING PUMP SPEED, and enter AP-RCS.1, Reactor Coolant Leak. Eventually, the operator will trip the reactor, manually actuate Safety Injection, and enter E-O, Reactor Trip or Safety Injection. However, the operator will discover that the manual reactor trip pushbuttons have failed (automatic reactor trip has failed as well), and be required to de-energize the Rod Drive MG Sets in order to trip the reactor. The operator will proceed through E-O, and then transition to E-1, Loss of Reactor or Secondary Coolant, and then transition to ES-1.2, Post-LOCA Cooldown and Depressurization.

I The scenario will terminate at Step 10 of ES-*1.2, after the crew has restored Pressurizer level to > 20%.

                      ----------------------------------------------------~

181M DRIVER Instructions: Operate Trigger #5 (RCS02D (1000 gpm)) . Indications Available:

Pressurizer pressure decreases

!. Pressurizer level decreases

A Charging Pump speed increases

**      Charging flow increases

!. Narrow Range Containment Pressure starts to increase

MCB Annunciator F-10; PRESSURIZER LO PRESS 2205 PSI

;.      MCB Annunciator F-4; PRESSURIZER LEVEL DEVIATION -5 NORMAL +5 NOTE: The crew may enter E O directly due to the size of the leak.

AR-F-14, CHARGING PUMP SPEED HCO (Step 1) check pump speed, control in AUTO

 ,                       OR MANUAL.

t HCO (Step 2) check PRZR level and press i HCO (Step 3) Check RCS Tavg channels cmd Tavg chart recorder for normal indication. I I CRS (Step 4) Refer to applicable procedure: i

AP-CVCS.1, CVCS Leak
AP-RCS.1, REACTOR COOLANT LEAK

Appendix D Operator Action Form ES-D-2 Test No.: N1D-1 Scenario # 5 Event # _7;...&;;;..;;;.8_ _ _ Page ~ of 53

Description:

Loop B Cold Leg Break (1000 gpm)1 Failure of Reactor to Trip in AUTO and MANUAL NOTE: The CRS will go to AP RCS.1. AP-RCS.1, REACTOR COOLANT LEAK (*Step 1) Monitor PRZR Level PROGRAM LEVEL (Step 1 RNO) IF PRZR level lowering, THEN NOTE: The HCO will raise start additional charging pumps and raise speed of Charging Pumps. speed to raise PRZR level to program. IF PRZR level continues to lower, THEN NOTE: The HCO will isolate close letdown isolation AOV-42i' AND Normal Letdown. excess letdown AOV-310. IF available charging pumps are running at maximum speed with letdown isolated, AND PRZR level is lowering, THEN trip the reactor and go to E-O, REACTOR TRIP or SAFETY INJECTION. NOTE: The CRS will direct a I manual reactor trip, and go to . E-O. I E-O, REACTOR TRIP OR SAFETY INJECTION HCO (Step 1) Verify Reactor Trip: NOTE: The Reactor will fail to trip in Auto and Manually.

At least one train of reactor trip breakers

                       -OPEN

Neutron flux - LOWERING
MRPI indicates - ALL CONTROL AND SHUTDOWN RODS ON BOTTOM (Step 1 RNO) Manually trip reactor.

IF reactor trip breakers NOT open, THEN perform the following:

Open Bus 13 and Bus 15 normal feed breakers.

Appendix D Operator Action Form ES-D-2 OpTest No.: N10-1 Scenario # 5 Event # _7.;.....;;.;&...;8_ _ _ _ Page ~ of 53 Event

Description:

Loop B Cold Leg Break (1000 gpm)/ Failure of Reactor to Trip in AUTO and MANUAL

Close Bus 13 and Bus 15 normal feed breakers.
Reset lighting breakers.

i IF the reactor will NOT trip ......... NOTE: De-energizing Bus 13 and 15 causes the Rods to insert. CRITICAL TASK (E-O A) Manually trip the reactor prior to transition to FR-S.1, "Response to Nuclear Generation/ATWS." Safety Significance: Failure to trip the reactor when required causes a challenge to the Subcriticality Critical Safety Function that otherwise would not exist. This mis-operation by the operator necessitates the crew taking compensating action which complicates the event mitigation strategy and demonstrates an inability by the operator to recognize a failure of the automatic actuation of the RPS. CO (Step 2) Verify turbine Stop Valves CLOSED CO (Step 3) Verify Both Trains of AC Busses Energized To At Least 440

i. Bus 14 and Bus 18 NOTE: Bus 18 is de energized.

i. Bus 16 and Bus 17 HCO (Step 3 RNO) Attempt to start any failed NOTE: The A DIG breaker has emergency DIG to restore power to all AC previously failed, and actions emergency busses. taken will be dependent upon how this was mitigated previously .

IF Bus 14 AND Bus 16 are deenergized, NOTE: Busses 14 and 16 are I THEN go to ...... .. both energized.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 5 Event # -=...7.;.;&...;;8~___ Page ~ of --::;,;53:;""-1 Event

Description:

Loop B Cold Leg Break (1000 gpm)/ Failure of Reactor to Trip in AUTO and MANUAL NOTE: SI mayor may NOT have actuated at this point. If it has, continue with Step 5.

Any SI Annunciator - LIT HCO! * (Step 4a RNO) IF any of the' 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 p ,

OR

SI sequencing started OR
Operator determines SI
IF SI is NOT required, .... ,

HCOI * (Step 4b RNO) SI sequencing - BOTH NOTE: The leak is sized so CO TRAINS STARTED, that SI will be required, HCO (*Step 5) Verify CNMT Spray Not Required:

Annunciator A-27, CNMT SPRAY EXTINGUISHED
CNMT pressure - LESS THAN 28 PSIG HCOI (Step 6) Direct Operator to Perform ATT CO 27.0, ATTACHMENT AUTOMATIC ACTION VERIFICATION

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 5 Event # _7:...;&:;;..;;..8_ _ _ Page ~ of _5_3_"'i Event

Description:

Loop B Cold Leg Break (1000 gpm)/ Failure of Reactor to Trip in AUTO and MANUAL 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 HCOI (Step 1) Verify SI and RHR Pumps Running: CO

All SI pumps - RUNNING
Both RHR pumps - RUNNING (Step 2) Verify CNMT RECIRC Fans RUNNING:
All fans RUNNING
Charcoal filter dampers green lights - EXTINGUISHED HCOI (Step 3) Check If Main Steamlines CO Isolated:
Any MSIV - OPEN NOTE: Both MSIVs are Closed.

(Step 3a RNO) Go to Step 4. HCOI (Step 4) Verify MFW Isolation: CO

MFW pumps - TRIPPED

                  **    MFW Isolation valves

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 5 Event # _7;....;;;.;&..;;;8_ _ _ _ Page ~ of .-.;;.;53~-11

Event

Description:

Loop B Cold Leg Break (1000 gpm)/ Failure of Reactor to Trip in AUTO and MANUAL

S/G B, AOV-3994
SIG blowdown and sample valves CLOSED (Step 5) Verify At Least Two SW Pumps - NOTE: Only the B SW Pump RUNNING is running.

HCOI (Step 5 RNO) Perform the following: CO

                    !. Ensure one SW pump running on each energized screen house AC emergency bus:

Bus 17
Bus 18 NOTE: Bus 18 is de energized.
IF offsite power NOT available ..... NOTE: Off-Site Power is available.

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 SW outlet valve status lights - BRIGHT
FCV-4561
FCV-4562
Letdown orifice valves - CLOSED
AOV-200A

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 5 Event # _7:....:;.&..;;;8_ _ _ _ Page ~ of _5;;;.;3~~; Event

Description:

Loop B Cold Leg Break (1000 gpm)/ Failure of Reactor to Trip in AUTO and MANUAL

AOV-200B
AOV-202 HCOI (Step 7) Check CCW System Status:

CO

Verify CCW pump - AT LEJ\ST ON E NOTE: The B CCW Pump is RUNNING RUNNING.

i HCOI (Step 8) Verify SI And RHR Pump Flow: CO

SI flow indicators - CHECK FOR FLOW NOTE: The leak is sized so that RCS pressure mayor may NOT be > 1350 psig.

i HCOI * (Step 8a RNO) IF RCS pressure less CO than 1350 psig ..... HCOI

RHR flow indicator - CHECK FOR CO FLOW HCOI
IF RCS pressure less than '150 psig ...
NOTE: The leak is sized so CO that RCS pressure will be>

150 psig. HCOI (Step 9) Verify SI Pump And RHR Pump CO Emergency Alignment:

RHR pump discharge to Rx vessel deluge - OPEN
MOV-852A
MOV-852B
Verify SI pump C - RUNNING
Verify SI pump A - RUNNING
Verify SI pump B - RUNNING

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 5 Event # _7.;....;.;&...;;8_ _ _ _ Page ~ of _5;;.,;3;;""'-i1 Event

Description:

Loop B Cold Leg Break (1000 gpm)/ Failure of Reactor to Trip in AUTO and MANUAL

Verify SI pump C discharge valves OPEN
MOV-817A
MOV-817B NOTE: MOV-817B is Closed.

HCOI * (Step ge RNO) Manually open valves as CO necessary. (Step 10) Verify CREATS Actuation:

At least one damper in each flowpath CLOSED
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.

Examiner NOTE: RCS pressure will drop to within 210 psig [240 psig Adverse Containment) shortly after the LOCA, and the SI Pumps are operating. The five minute Clock to stop the RCPs should start when this occurs. Record Time: COl (Step 7) Verify Both MDAFW Pumps Running HCO

Appendix D Operator Action Form ES-D-2

Op Test No.: N10-1 Scenario # 5 Event # _7;....;;;;;&...;;8_ _ _ _ Page ~ of _5_3_"'1 Event

Description:

Loop B Cold Leg Break (1000 gpm)/ Failure of Reactor to Trip in AUTO and MANUAL HCO

AFW flow - INDICATED S/G(s)
AFW flow from each MDAFW pump LESS THAN 230 GPM

(*Step 9) Monitor Heat Sink: HCO

Check S/G narrow range level NOTE: Adverse Containment GREATER THAN 7O/C0 [25O/co adverse Numbers sho uId be us ed,unnI CNMT] in any S/G
Containment Pressure is less than 4 psig.
Check S/G narrow range level BOTH S/G LESS THAN 50%

COl * (Step 9 Continued) Control feed flow to maintain S/G narrow range level HCO between 7% [25% adverse CNMT] and 50%. COl (Step 10) Check If TDAFW Pump Can Be Stopped: HCO

Both MDAFW pumps - RUNNING
PULL STOP TDAFW pump steam supply valves
MOV-3504A i
MOV-3505A COl (Step 11) Check CCW Flow to R.CP thermal Barriers:

HCO

Annunciator A-7. RCP 1A CCW RETURN HI TEMP OR LOW FLOW I EXTINGUISHED i

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 5 Event # _7....&;;...;...8_ _ _ Page ~ of _5-.3~1 Event

Description:

Loop B Cold Leg Break (1000 gpm)/ Failure of Reactor to Trip in AUTO and MANUAL

Annunciator A-15, RCP 1B GCW RETURN HI TEMP OR LOW FLOW EXTINGUISHED

(*Step 12) Monitor RCS Tavg - STABLE AT OR TRENDING TO 547°F (Step 13) Check PRZR Valves: HCO

PORVs - CLOSED
Auxiliary spray valve (AOV-296) -.

CLOSED

Check PRZR pressure - LESS THAN 2260 PSIG
Normal PRZR spray valves - CLOSED
PCV-431A
PCV-431B COl (Step 14) Monitor RCP Trip Critmia:

HCO

RCP status - ANY RCP RUNNING NOTE: Both RCPs should be RUNNING unless previously

                                                                              . tripped on Trip Criteria.

SI pumps - AT LEAST TWO RUNNING
RCS pressure minus maximum SiG NOTE: Both RCPs should be pressure - LESS THAN 210 psi RUNNING unless previously tripped on Trip Criteria.

Appendix D Operator Action Form ES-D-2 Op Test No.: Nl0-l Scenario # 5 Event # _7;.....;;;.;&..;.8_ _ _ _ Page ~ of _5;;";"'''1 Event

Description:

Loop B Cold Leg Break (1000 gpm)/ Failure of Reactor to Trip in AUTO and MANUAL CRITICAL TASK (E-1C) Trip all RCPs within 5 minutes of reaching trip criteria Safety Significance: Failure to trip all RCPs when required can lead to core uncovery and to fuel temperatures in excess of 2200°F. Analyses have shown that if the RCPs are tripped within 5 minutes of the trip criteria being met, PCT will remain below 2200°F, and if this action is delayed beyond 5 minutes, this PCT will be exceeded. It is a management expectation that the RCPs be tripped as quickly as possible, but within 5 minutes when the trip criteria is met. Failure to take this action represents mis-operation by the operator which leads to degradation of the fuel cladding fission produce barrier, and a violation of a license condition. Record Pump Stop Time: Subtract time recorded at time of the RCP Trip Criteria met on p38 _ _ =__ minutes. COl (Step 15) Check If S/G SecondaTY Side Is Intact: HCO

Pressure in both S/Gs - STABLE OR RISING
Pressure in both S/Gs - GREATER THAN 110 PSIG COl (Step 16) Check If S/G Tubes are Intact HCO
Air ejector radiation moniton;(R-15, R-47, R-48) - NORMAL
S/G blowdown radiation monitor (R-19)

NORMAL

Steamline radiation monitors (R-31 and R-32) - NORMAL COl (Step 17) Check If RCS Is Intact:

HCO

CNMT area radiation monitors NORMAL
R-2

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 5 Event # _7.;.....;.;&...;8_ _ _ _ Page ~ of _5,;;.;3~~1 Event

Description:

Loop B Cold Leg Break (1000 gpm)/ Failure of Reactor to Trip in AUTO and MANUAL

R-30
CNMT pressure - LESS THAN 0.5 PSIG CRS * (Step 17 RNO) Go To E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.

NOTE: The CRS will go to E 1. E-1, LOSS OF REACTOR OR SECONDARY COOLANT HCO (Step 1) Monitor RCP Trip Criteria:

RCP status - ANY RCP RUNNING
SI pumps-AT LEAST TWO RUNNING
RCS pressure minus maximum S/G pressure - LESS THAN 21 (I psi [240 psi adverse CNMT]
Stop both Reps NOTE: If the RCPs have NOT been stopped prior to this step, they will be stopped here.

CRITICAL TASK (E-1C) Trip all RCPs within 5 minutes of reaching trip criteria Safety Significance: Failure to trip all Reps when required can lead to core uncovery and to fuel temperatures in excess of 2200°F. Analyses have shown that if the Reps are tripped within 5 o minutes of the trip criteria being met, PCT will remain below 2200 F, and if this action is delayed beyond 5 minutes, this PCT will be exceeded. It is a management expectation that the RCPs be tripped as quickly as possible, but within 5 minutes when the trip criteria is met. Failure to take this action represents mis-operation by the operator which leads to degradation of the fuel cladding fission produce barrier, and a violation of.a license condition . . Record Pump Stop Time: _ _ __ Subtract time recorded at time of the Rep Trip Criteria met on p38 _ _ = _ _ minutes.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 5 Event # _7,;...;:;;&,.;;;8_ _ _ _ Page _41_ of _5;;.;3;;....-~ I Even. DescripUon: Loop B Cold Leg Break (1000 gpm)/ Failure of Reactor to Trip in AUTO and MANUAL co (Step 2) Check If S/G Secondary Side Is Intact:

Pressure in both S/Gs RISING Pressure in both S/Gs THAN 110 PSIG CO (*Step 3) Monitor Intact S/G
Narrow range level - GREATER 7% - [25% adverse CNMT]
Control feed flow to maintain n~:mrf\\AI range level between 17% [25% adverse CNMT] and 50%

(Step 4) Monitor If Secondary Radiation Levels Are Normal

Steamline radiation monitor R-31 and R 32)
Request Chem Tech SamplE! S/Gs for NOTE: The CRS may contact activity Chemistry.

SIM DRIVER: as Chemistry, acknowledge. HCO (*Step 5) Monitor PRZR PORV Status:

Power to PORV block valves AVAILABLE
PORVs - CLOSED
Block valves - AT LEAST ONE OPEN HCO (Step 6) Reset SI HCO (Step 7) Reset CI:
Depress CI reset pushbutton

Appendix 0 Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 5 Event # 7&8 Page ~ of 53 Event

Description:

Loop B Cold Leg Break (1000 gpm)/ Failure of Reactor to Trip in AUTO and MANUAL

Verify annunciator A-26, CNMT ISOLATION - EXTINGUISHED CO (Step 8) Verify Adequate SW Flow:
Check at least two SW pumps - NOTE: ONLY the B SW Pump RUNNING is RUNNING.

CO * (Step 8a RNO) Manually start SW pumps NOTE: These steps have as power supply permits (257 kweach). been previously performed without success. IF less than two SW pump running, THEN perform the following:

Ensure SW isolation.
Refer to AP-SW.2, LOSS OF SERVICE WATER CO * (Step 8b) Dispatch AO to establish NOTE: The CRS will dispatch normal shutdown alignment (Refer to anAO.

ATT-17.0, ATTACHMENT 8D-1) SIM DRIVER: as AO, acknowledge. HCOI (Step 9) Establish IA to CNMT: CO Verify non-safeguards busses energized from offsite power

Bus 13 normal feed - CLOSED OR
Bus 15 normal feed - CLOSED
Verify turbine building SW isolation valves - OPEN
MOV4614 and MOV-46"70
MOV-4664

                    *   (Step 9 RNO) Perform the following:

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 5 Event # ....;..7..;;.&;..;:8~_ _ _ Page ~ of 53 Event

Description:

Loop B Cold Leg Break (1000 gpm)/ Failure of Reactor to Trip in AUTO and MANUAL

Restore IA using service air NOTE: The SA Compressor compressor OR diesel air can be started.

compressor (refer to ATT-11.2, ATTACHMENT DIESEL AIR COMPRESSOR)

Go to Step 9d.
Check IA supply:
Pressure - GREATER THAN 60 PSIG
Pressure - STABLE OR RISING
Reset both trains of XY relays for IA to CNMT AOV-5392 - OPEN
Verify IA to CNMT AOV-5392 - OPEN HCO (Step 10) Check Normal Power Available To Charging Pumps:
Bus 14 normal feed breaker - CLOSED us 16 normal feed breaker - CLOSED HCO (Step 11) Check If Charging Flow Has Been Established:
Charging pumps - ANY RUNNING NOTE: There are NO Charging Pumps running.

                    *   (Step 11a RNO) Perform the following:

IF CCW flow is lost to any RCP NOTE: CCW flow to the RCP thermal barrier OR any RCP #1 seal has NOT been lost, nor is any outlet temperature greater than RCP #1 seal outlet 235°F, THEN temperature greater than 235°F.
Ensure HCV-142 open, demand at 0%.

ep 11b) Charging pump suction igned to RWST:

Appendix D Operator Action Form ES-D-2 Op Test No,: N1()-1 Scenario # 5 Event # _7_& 8 _ _ _ Page ~ of _5..;..3_-li Event

Description:

Loop B Cold Leg Break (1000 gpm)/ Failure of Reactor to Trip in AUTO and MANUAL

LCV-112C - CLOSED HCO * (Step 11b RNO) Manually align valves as necessary.

HCO * (Step 11c) Start charging pumps and NOTE: The HCO will start two adjust charging flow as necessary to Charging Pumps restore PRZR level Terminated: NOTE: RCS Pressure will be < psig 1650 psig. HCOI * (Step 12a RNO) Do NOT stop SI pumps, CRS Go to Step 13. HCO (*Step 13) Monitor If CNMT Sprcay Should Be Stopped: .

CNMT spray pumps - ANY RUNNING NOTE: The CS Pumps will NOT be running.

CRS * (Step 13a RNO) Go to Step 14. HCO (*Step 14) Monitor If RHR Pumps Should Be Stopped:

                  .*     Check RCS pressure:

Pressure - GREATER THAN 300 psig
RCS pressure - STABLE OR RISING
RHR pumps - ANY RUNNING IN INJECTION MODE

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 5 Event # 7&8 Page ~ of 53 [I Event

Description:

Loop B Cold Leg Break (1000 gpm)1 Failure of Reactor to Trip in AUTO and MANUAL NOTE: The HCO will STOP the RHR Pumps.

Dispatch AO to perform ATT-14.6, NOTE: The CRS will dispatch ATTACHMENT RHR PRESS anAO.

REDUCTION, Part A SIM DRIVER: as AO, acknowledge. Monitor INSIGHT prhr629a for RHR pump A discharge pressure. CO (Step 15) Check RCS And SfG Pressures

Check pressures in both SfGs - STABLE OR RISING
Check pressures in both SfGs GREATER THAN 110 PSIG
Check RCS pressure - STABLE OR LOWERING CO (Step 16) Check If Emergency DIGs Should i i Be Stopped:

I I* Verify Safeguards busses 14,16, 17, and 18 voltage - GREATER THAN 440 NOTE: Bus 18 is de energized. VOLTS - CO (Step 16a RNO) Perform the following: NOTE: The CRS will wait on Electrician's report for restoration of Bus 18.

Restore bus voltage (Refer to AP I ELEC.2, SAFEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW I

FREQUENCY) i I !

Continue with Step 17, voltage restored, THEN do Step 16b 5

and c. I (Step 17) Evaluate Plant Status:

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 5 Event # _7.:....:;;&...;;;8_ _ _ _ Page ~ of _5....3_-11 Event

Description:

Loop B Cold Leg Break (1000 gpm)/ Failure of Reactor to Trip in AUTO and MANUAL Check auxiliary building radation NORMAL

Plant vent iodine (R-10B)
Plant vent particulate (R-13)
Plant vent gas (R-14)
CCW liquid monitor (R-'I?)
LTON line monitor (R-9)
CHG pump room (R-4)
WHEN TSC is manned, THEN request NOTE: The TSC will NOT be evaluation of sampling requirements. manned.
RCS boron
RCS activity
CNMT hydrogen
CNMT sump boron
CNMT Sump pH
Verify adequate Rx head cooling:
Verify at least one control rod shroud fan - RUNNING
Verify one Rx compartment cooling fan RUNNING HCO (Step 18) Verify CNMT Sump Recirculation Capability:
Check RHR and Support systems:
At least one recirculation flowpath, NOTE: The CRS will dispatch including required power supplies, . anAO.

from Sump B and back to RCS SIM DRIVER: as AO, available per ATT-14.5, acknowledge. ATTACHMENT RHR SYSTEM

At least one SW pump available.
At least one CCW

Appendix D Operator Action Form ES-D-2 . Op Test No.: N10-1 Scenario # 5 Event # _7;...&.;;;...;..8_ _ _ Page ~ of _5=3~

Event

Description:

Loop B Cold Leg Break {1000 gpm)/ Failure of Reactor to Trip in AUTO and MANUAL

Check SW pumps - AT LEJl.8T 2 NOTE: ONLY the B SW Pump PUMPS AVAILABLE is RUNNING.

                     *    (Step 18b RNO) Attempt to restore     at               NOTE: The CRS may notify least 2 SW pumps to operable.                          theWCC.

SIM DRIVER: as WCCS, acknowledge, and report that electrical power will not be restored to Bus 18 for some time. IF only 1 SW pump available, THEN refer toATT-2.1, ATTACHMENT MIN SWfor additional guidance. NOTE: The CRS may hand this off to the CO. ATT-2.1, ATTACHMENT MIN SERVICE WATER (Step 1) Ensure SW isolation as follows:

Both TURB BLDG SW loops isolated
MOV-4613/MOV-4670 AT LEAST ONE CLOSED
MOV-4614/MOV-4664 Jl,T LEAST ONE CLOSED
Screen house SW loop isolated
MOV-4609/MOV-4780 AT LEAST ONE CLOSED
Air conditioning SW loop isolated
MOV-4663/MOV-4733 AT LEAST ONE CLOSED
At least one AUX BLDG SW loop isolated
MOV-4616/MOV-4735 AT LEAST ONE CLOSED OR
MOV-4615/MOV-4734 AT LEAST ONE CLOSED

Appendix D Operator Action Form ES-D-2

Op Test No.: N10*1 Scenario # 5 Event # _7;..&;:;;..;;;.8_ _ _ Page ~ of _5_3_-11 Event

Description:

Loop B Cold Leg Break (1000 gpm)J Failure of Reactor to Trip in AUTO and MANUAL CO (Step 2) Dispatch AO to AUX BLDG to NOTE: The CO will dispatch isolate SW to the SFP Hxs anAO. SIM DRIVER: as AO, acknowledge. CO (Step 3) Request TSC evaluate closing Bus NOTE: The TSC will NOT be Tie 17-18 and start of a second SW pump. manned. CO (Step 4) Align SW to ONLY ONE AUX BLDG SW 100p/CCW Hx.

CCW Hx A, MOV-4616 and MOV-4735 OPEN OR
CCW Hx B, MOV-4615 and MOV-4734 OPEN CO (Step 5) WHEN SW restored to selected NOTE: SW has NOT been AUX BLDG SW loop, THEN ..... restored.

E-1, LOSS OF REACTOR OR SECONDARY COOLANT HCO * (Step 18c) Dispatch AO to check AUX NOTE: The CRS will dispatch BLDG sUb-basement for RHR system : anAO. leakage (AUX BLDG sUb-basement key SIM DRIVER: as AO, may be required) acknowledge. (Step 19) Check If RCS Cooldown And Depressurization Is Required:

RCS pressure - GREATER THAN 300 psig [350 psig adverse CNMT]
Go to ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, Step 1.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 5 Event # _7;...&.;.....;..8_ _ _ Page ~ of _5.;;..;3~""1 Event

Description:

Loop B Cold Leg Break (1000 gpm)/ Failure of Reactor to Trip in AUTO and MANUAL NOTE: The CRS will go to ES 1.2. ES-1.2, POST*LOCA COOLDOWN AND DEPRESSURIZATION HCO (*Step 1) Monitor If RHR Pumps Should Be NOTE: The RHR Pumps are Stopped: Stopped.

RHR pumps - ANY RUNNING IN INJECTION MODE CRS .* (Step 1a RNO) Go to Step 2..

(Step 2) Monitor AC Bus Power: Verify Safeguards Busses 14,16,17, TE: Bus 18 is de-and 18 - GREATER THAN 440 VOLTS energized. (Step 2a RNO) Perform the following:

Restore bus voltage (Refer to AP NOTE: The CRS will most ELEC.2, SAFEGUARD BUSSES LOW likely wait on Electrician's VOLTAGE OR SYSTEM LOW report for restoration of Bus FREQUENCY) 18.
Continue with Step 3, WHEN bus voltage restored, THEN do Step 2b.

HCO (Step 3) Establish 75 GPM Charging Flow:

Charging pumps - ANY RUNNING NOTE: Two Charging Pumps should be RUNNING.
Align charging pump suction to RWST:
LCV-112B - OPEN
LCV-112C - CLOSED
Start charging pumps as necessary (75 kw each) and establish 75 gpm total charging flow

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 5 Event # 7&8 Page ~ of 53 Event

Description:

Loop B Cold Leg Break (1000 gpm)/ Failure of Reactor to Trip in AUTO and MANUAL

Seal injection flow CO (Step 4) Establish Condenser Steam Dump Pressure Control:
Verify condenser available: NOTE: Steam Dump to the Condenser is NOT available.

CO * (Step 4a RNO) Place S/G ARV controllers in AUTO at desired pressure and go to Step 5. CO (*Step 5) Monitor Intact S/G Levels:

Narrow range level GREATER THAN 7% [25% adverse CNMT)
Control feed flow to maintain narrow range level between 17% [25% adverse CNMT] and 50%

HCO (Step 6) Deenergize PRZR Heaters

Place PRZR proportional heaters in PULL STOP
Place PRZR backup heaters in OFF Consult TSC for a recommended NOTE: The TSC will NOT be minimum indicated PRZR w;ater level manned.

that will ensure heaters are covered CO P 7) Initiate RCS Cooldown To Cold tdown:

Establish and maintain cooldown rate using CET's - BETWEEN 80°F/HR AND 10QoF/HR
Use RHR system if in service NOTE: RHR is NOT in service.
Dump steam to condenser from intact NOTE: Steam Dump to the S/G(s) ..... . Condenser is NOT available.

Appendix D Operator Action Form ES-D-2 Op Test No.: N10-1 Scenario # 5 Event # ...;,..7,;:;;.&..;;,8_ _ _ Page ~ of 2LJi Event

Description:

Loop B Cold Leg Break (1000 gpm)/ Failure of Reactor to Trip in AUTO and MANUAL co * (Step 7c RNO) Manually open intact NOTE: C/D rate due to S/Gs ARVs to establish a cooldown rate accidenUSI flow will be using CET's between 80 0 F/HR AND >100°F/hr, and additional 100°F/HR. IF any ARV can NOT be operator C/D is NOT likely. opened manually, THEN ..... HCOI (Step 8) Check RCS Subcooling Based On CO Core Exit TICs - GREATER THAN O°F USING FIG-1.0, FIGURE MIN SUBCOOLING HCO (Step 9) Check SI and RHR Pump Status:

SI pumps ANY RUNNING NOTE: All Sl Pumps are RUNNING.

OR

RHR pumps - ANY RUNNING IN NOTE: The RHR Pumps are INJECTION MODE Stopped.

HCO (Step 10) Depressurize RCS To Refill PRZR:

Depressurize using normal PRZR spray if NOTE: The RCPs have been available tripped.

HCO * (Step 10a RNO) Depressurize using one NOTE: The PRZR PORVs can PRZR PORV. IF IA NOT available, be opened. THEN ...... HCO * (Step 10b) PRZR level- GREATER THAN 20%

Stop RCS depressurization Terminate the Exam at the discretion of the Lead Examiner

UNIT STATUS: Power Level: 0% (BOL) RCS [B] 1790 ppm BAST [B]: 17,500 ppm Power History: The reactor was taken critical last Core Burnup: 150 MWO/MTU shift. INFORMATION NEEDED TO ASSUME TO SHIFT:

The plant is at 1 x 10-8 amps (BOL).
The 60 gpm Letdown Orifice is in service.
The plant ran at 100% power for 12 days, and then tripped four days ago due to a MFW Pump failure.
The repairs have been made and the plant is ready to be started back up.

The crew will be directed to pull rods to the point of adding heat (POAH), and start the A MFW Pump, in accordance with 0-1.2, Plant Startup From Hot Shutdown to Full Power Load, Step 6.3.4 and beyond.

T -16A, Turbine Pre-Startup, is complete up to Section 5.11, Warm-up and pressurization of Main Steam Header.

The following equipment is Out-Of-Service:

The B Condensate Pump is OOS for Bearing Replacement, has been out of service for 24 hrs. A-52.12 submitted for tracking.

A-52.12 Equipment Date Time Reason Required Actions Required Required Action not met Completion DatelTime I B Condensate _1_/10 0800 Bearing I I TRACKING I I Pump I I Replacement I I ONLY I}}

v t e Letter Sequence Draft Other
TAC:U01766, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML102320373, ML102320386, ML102320393, ML102320408, ML102520045, ML102520054, ML102710006
MONTHYEAR2010-05-05 [Table View]

ML101720564

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