ML15043A681

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

ML15043A681
Person / Time
Site:	Ginna
Issue date:	12/16/2014
From:	Exelon Generation Co
To:	D'Antonio J Operations Branch I
Shared Package
ML14174A998	List: ML14177A718 ML14339A320 ML15043A673 ML15043A675 ML15043A678 ML15043A679 ML15043A680 ML15043A681 ML15156A552
References
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{{#Wiki_filter:Appendix C Job Performance Measure Worksheet Form ES-C-1 JPM A1a RO 14 Admin -JPM A1a RO (REV_091114) NUREG 1021, Revision 9 Appendix C Facility: Task Title: Page 2 of 14 Form ES-C-1 Job Performance Measure Worksheet Ginna Calculate SOM for an Operating Reactor with an Untripable Rod Task No.: JPM No.: 2014 Admin -JPM A1a RO KIA

Reference:

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

• Plant is at 100%
• Tavg is at 574°F
• Date: Today
• MWD/MTU:

18000

• Boron sample date: Today; Boron Sample Time: 0001; Boron Concentration:

200 ppm

• Bank C: 225; Bank D: 217
• Rod K-7 has just been determined to be untripable.
• The CRS has directed you to calculate Shutdown Margin (SOM). and notify him if sufficient SDM exists for the current plant conditions.
• All Independent Verification steps will be performed upon completion of your calculation.

The operator will calculate Shutdown Margin in accordance with the 0-3.2, Shutdown Margin for an Operating

Reactor, and determine that sufficient SOM does NOT exist. 2014 Admin -JPM A1a RO NU REG 1021, Revision 9

Appendix C Page 3 of 14 Form ES-C-1 Job Performance Measure Worksheet Required Materials: Calculator Standard Procedure Reference Carts must be available to the operator General

References:

0-3.2, Shutdown Margin for an Operating

Reactor, Rev 03700 Technical Specifications; Appendix A to Facility Operating License for the R.E. Ginna Nuclear Power Plant; Docket No. 50-244, Amendment 116 Handouts:

None Time Critical Task: YES (1 hour) Validation Time: 29 minutes 2014 Admin -JPM A1a RO NUREG 1021, Revision 9 Appendix C Page 4 of 14 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with a I/) Provide Candidate with Initial Conditions/Cue (Last Page of this JPM). START TIME: Performance Step: 1 Standard: Comment: Performance Step: 2 Standard: Comment: 2014 Admin -JPM A1a RO 0-3.2, Step 6.1 Note: Shutdown Margin SHALL be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:

• All rod cluster control assemblies (RCCAs) are fully inserted except for the single RCCA of highest reactivity worth, which is assumed to be fully withdrawn.

IF any RCCAs is NOT capable of being fully inserted, THEN the reactivity worth of the RCCAs must be accounted for in the determination of SOM.

• In Modes 1 and 2, the fuel and moderator temperatures are changed to the nominal hot zero power temperature.

CHECK Tavg is at pro9ram Tavg: +/- 1.5°F. The operator obtains a copy of 0-3.2, reviews it and arrives at Step 6.0. The operator reads the Note, and proceeds to Step 6.1. The operator observes that Tavg = Tref (Initial Conditions). 0-3.2, Step 6.2 IF Tavg is NOT at program Tavg: +/- 1.5°F, ..... . The operator recognizes that this Step is NA. NUREG 1021, Revision 9 Appendix C Performance Step: 3 Standard: Comment: Performance Step: 4 Standard: Comment: 2014 Admin -JPM A1a RO Page 5 of 14 PERFORMANCE INFORMATION 0-3.2, Step 6.3 Form ES-C-1 Note: IF the following calculations will be performed by a Licensed

Operator, THEN ENSURE Independent Verification is performed by an STA OR the Reactor Engineer.

Note: IF the following calculations will be performed by an STA OR the Reactor Engineer, THEN ENSURE Independent Verification is performed by a Licensed Operator. RECORD the cycle burnup (PPCS point ID Burnup). DATE -----MWD/MTU -----The operator reads the Notes, and proceeds. The operator records Today's date in the DATE block. The operator records 18000 in the MWD/MTU block. 0-3.2, Step 6.4 OBTAIN last loop B boron sample results from on-duty RP AND RECORD date, time and concentration of sample. Sample Date: ---* Time: _____ Hours Concentration: ---ppm The operator records Today in the SAMPLE DATE block. The operator records 0001 in the TIME block. The operator records 200 ppm in the CONCENTRATION block. NUREG 1021, Revision 9 Appendix C Performance Step: 5 Standard: Comment: Performance Step: 6 Standard: Comment: 2014 Admin -JPM A1a RO Page 6 of 14 PERFORMANCE INFORMATION 0-3.2, Step 6.5 RECORD Reactor Power Level. % ----Form ES-C-1 The operator records 100 in the % block. 0-3.2, Step 6.6 RECORD Bank C and D positions. Bank C = steps ----Bank D = steps The operator records 225 steps in the BANK C block. The operator records 21-l steps in the BANK D block. NU REG 1021, Revision 9 Appendix C Performance Step: 7 Standard: Comment: 2014 Admin -JPM A1a RO Page 7 of 14 PERFORMANCE INFORMATION 0-3.2, Step 6. 7 Form ES-C-1 Note: WHEN determining values based on burnup, THEN the following curves indicated for the applicable burnup range SHALL be used:

• BOL to 6187 MWD/MTU Use BOL curves
• 6188 to 12,373 MWD/MTU Use MOL curves
• 12,374 to EOL MWD/MTU Use EOL curves The Total Power Defect determined in Step 6.7 will be a positive number. DETERMINE total Power Defect, using the appropriate Total Power Defect attachment.

USE Attachment 2, Total Power Defect Figure 5-20 (BOL), OR Attachment 3, Total Power Defect Figure 5-21 (MOL), OR Attachment 4, Total Power Defect Figure 5-22 (EOL), using the boron concentration recorded in Step 6.4 and power level recorded in Step 6.5 Total Power Defect:+ ____ pcm [.YJThe operator uses Attachrnent4, and determi.nes the intersection point qf 100% 011Jbe )\Axis. (power Level) and an interpolate(j200PPM

• curve{1/3 the distance toward the top of t.he curve between the.o PPM the 600 Pl?M Curves},

and reads corresponding point 'on the, XAxis (Total Power Defect in PCM); and determines ittO ["1] The operator records 3050+/-100 pcm inthe TOTAL POV\/ER DEFECT block: NUREG 1021, Revision 9 Appendix C Performance Step: 8 Standard: Comment: 2014 Admin -JPM A1a RO Page 8 of 14 PERFORMANCE INFORMATION 0-3.2, Step 6.8/6.8.1 Form ES-C-1 Note: During power operation ensuring that the shutdown bank is fully withdrawn, and the control banks are within the limits of LCO 3.1.6 verifies adequate shutdown margin (ITS 83.1.1 ). DETERMINE Control Rod negative reactivity available for insertion upon a Reactor trip as follows:

• DETERMINE the negative reactivity inserted upon trip from the ARO position assuming the most reactive rod remains stuck at the full out position using Attachment 1, Negative Reactivity Added On Trip From ARO, and the current burnup from Step 6.3.
• Rod Worth -Stuck Rod -pcm -----The operator reads the Note, and proceeds.

[°'JLThe operator uses Attachment1; and determines the Rod Worth -Stuck Rod fora Burnup of 18,000 MWD/MTU to be 5053 pcm. ['VJ The. operator records :-5053 pcm in the ROD WORTH -STUCK ROD block. NUREG 1021, Revision 9 Appendix C Performance Step: 9 Standard: Comment: 2014 Admin -JPM A1a RO Page 9 of 14 PERFORMANCE INFORMATION 0-3.2, Step 6.8.2 Form ES-C-1 Note: WHEN determining values based on burnup, THEN the following curves indicated for the applicable burnup range SHALL be used:

• BOL to 6187 MWD/MTU Use BOL curves
• 6188 to 12,373 MWD/MTU Use MOL curves
• 12,374 to EOL IVIWD/MTU Use EOL curves The Integral Rod Worth determined in Step 6.8.2 will always be a positive value. DETERMINE the integral rod worth from the rod position recorded in Step 6.6 to the full out position (ARO) using the appropriate Integral Rod Worth column BOL, MOL or EOL in Attachment

5. Bank Worth to Full Out + ____ pcm The operator reads the Note, and proceeds.

HJ The operator uses Attachments, and determines the Integral Rod WorthforEOL'conditions with.Sank.C.Rods at 225 Steps an.d Banko rods at21Tsteps'fo be18+/-1 pcm. [v']The operator records 18+/-1 pcm in the BANK WORTH TO FULL OUT blocl(. NUREG 1021, Revision 9 Appendix C Performance Step: 10 Standard: Comment: 2014 Admin -JPM A1a RO Page 10 of 14 PERFORMANCE INFORMATION 0-3.2, Step 6.8.3 Form ES-C-1 Note: Stuck rod worth may be obtained from the Stuck Rod Worth column of Attachment 1 for current core burnup. Dropped rods are worth +250 pcm. Rods misaligned low are worth the lower of either +250 pcm (which would indicate it is fully inserted) or +15 pcm/step. Note: IF there are no stuck, dropped, OR misaligned rod(s), THEN 0 pcm is to be entered. Caution: Available Shutdown Margin is further reduced by the worth of any Control Rod known to be stuck out, dropped, or misaligned low relative to the bank position. RECORD the control rod reactivity due to a known stuck (untripable), a dropped (fully inserted) and a misaligned low control rods.

• Stuck Rod + pcm
• Dropped Rod + *-----pcm
• Rod Misaligned Low + _____ pcm The operator reads the Notes and Caution, and proceeds.

[-/}.The operator uses .Attachment .1,, and determines the Stuck Rod Worth for a Burnup9f 18,000 MVVD/MTU to be 932 pcm. [°'1]The operator records 932 pcm in the STUCK ROD block. The operator records 0 pcm in the DROPPED ROD block. The operator records 0 pcm in the ROD MISALIGNED LOW block. NUREG 1021, Revision 9 Appendix C Performance Step: 11 Standard: Comment: Page 11 of 14 PERFORMANCE INFORMATION 0-3.2, Step 6.8.4 Form ES-C-1 DETERMINE the reduction in control rod reactivity due to known stuck (untripable), dropped (fully inserted) or misaligned low control rods. (+ pcm) +(+ ___ pcm)+ (+ __ pcm)=+ __ pcm Step 6.8.3.1 Step 6.8.3.2 Step 6.8.3.3 Unavailable Rod Worth [\/]The .ROd VJqrttde> be 932 pcm (932 pcrri +p pcm + o pcrn = 932 pcm) 0-3.2, Step 6.8.5 Performance Step: 12 DETERMINE the total available control rod negative reactivity. Standard: Comment: Performance Step: 13 Standard: Comment: 2014 Admin -JPM A1a RO (-pcm)+(+ __ . pcm)+(+ pcm)=-__ pcm Step 6.8.1 Step 6.8.2 Step 6.8.4 [v'J. The operator calculates unavailable Rod Worth to be -4103+/-1 pcm ( -5053 pcm + 18+/-1 pcm+ 932 pcm = -4103+/-1 pcm) 0-3.2, Step 6.9 CALCULATE the Shutdown Margin by adding the negative reactivity added by the control rods in Step 6.8.5 to the positive reactivity from Power Defect recorded in Step 6.7. (-pcm)+(+ ___ pcm)= -pcm Step 6.8.5

6. 7 [vi] The operator calculates Shutdown Margin to be -1053+/-101 pcm (-4103+/-1

+ 3050+/-100 pcm= -1103+/-101 pcm) NUREG 1021, Revision 9 Appendix C Performance Step: 14 Standard: Comment: Performance Step: 15 Standard: Comment: Terminating Cue: STOP TIME: 2014 Admin -JPM A1a RO Page 12 of 14 PERFORMANCE INFORMATION 0-3.2, Step 6.10 Form ES-C-1 Note: 1.8% delta K/K = 1800 pcm (Single Loop Operation) Note: 1.3% delta K/K = 1300 pcm (Two Loop Operation) LOCATE the required Shutdown Margin on Attachment 6, Required Shutdown Margin Figure COLR-2, AND CONVERT to pcm, using the latest boron sample recorded in Step 6.4, AND RECORD below. Required SOM ----pcm The operator reads the Notes, and proceeds. ["jTheoperator uses.Attachmenf6, and determines that for two loop operation and a Boron Concentration for 200 ppin, the required Shutdown Margin is 1.3 delta-K/K. The operator records 1300 pcm in the REQUIRED SOM block. 0-3.2, Step 6.11 VERIFY the Shutdown Margin requirements are satisfied as indicated by the value calculated in Step 6.9 being more negative than the Required SOM in Step 6.10. HJ The operator usesAttachment 6, and determines that the value calculated in Step 6.9 (1053+/-101) is NOT more negative than the Required SOM (1300) in Step 6.10. Evaluation on this JPM is complete. NUREG 1021, Revision 9 Appendix C Page 13of14 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2014 Admin -JPM A 1 a RO Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiner's Signature: Date: 2014 Admin -JPM A1a RO NUREG 1021, Revision 9 Appendix C INITIAL CONDITIONS: INITIATING CUE: Form ES-C-1 JPM CUE SHEET

• Plant is at 100%
• Tavg is at 574°F
• Date: Today
• MWD/MTU:

18000

• Boron sample date: Today; Boron Sample Time: 0001; Boron Concentration:

200 ppm

• Bank C: 225; Bank D: 217
• Rod K-7 has just been determined to be untripable.
• The CRS has directed you to calculate Shutdown Margin (SOM), and notify him if sufficient SOM exists for the current plant conditions.
• All Independent Verification steps will be performed upon completion of your calculation.

THIS IS A TIME CRITICAL JPM NUREG 1021, Revision 9 Appendix C Job Performance Measure Worksheet Form ES-C-1 JPM A1b RO 2014 Admin -JPM A1b RO (REV_091114) NU REG 1021, Revision 9 Appendix C Facility: Task Title: Page 2 of 8 Job Performance Measure Worksheet Ginna Task No.: Perform an Independent Verification JPM No.: of a Post-Trip Xenon Reactivity Calculation Form ES-C-1 320-001-01-01 2014 Admin -JPM A1 b RO KIA

Reference:

2.1.43 (4.1) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: x Classroom x Simulator Plant ---READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Provide Candidate with Initial Conditions/Cue (Last Page} of this JPM, and Handout 1. Initial Conditions:

• The planthas tripped from 50% power.
• The reactor had been operating at this power for the last 3 days prior to the trip.
• The XENON PREDICT program on the PPCS is NOT available.
• The Reactor Engineer has completed the Xenon Reactivity Calculation.
• It is currently 0900 on 12/3/14.

Initiating Cue:

• The*CRS directed you to independently verify theXenon Reactivity Calculation in accordance with Step 6.1.3 of 0-3, Hot Shutdown With Xenon Present.

Task Standard: The operator will complete an independent verification of the Xenon Reactivity Calculation and determine that Xenon will equal the value at time of shutdown at 2100 on *12/3/14. Required Materials: Calculator 2014 Admin -JPM A1b RO NU REG 1021, Revision 9 Appendix C Page 3 of 8 Form ES-C-1 Job Performance Measure Worksheet General

References:

0-3, Hot Shutdown With Xenon Present, Rev 04300 Handouts: Handout 1: Copy of 0-3, Hot Shutdown With Xenon Present, marked up for this JPM. Time Critical Task: NO Validation Time: 19 minutes 2014 Admin -JPM A 1 b RO NUREG 1021, Revision 9 Appendix C Page 4 of 8 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with a "'1) Provide Candidate with Initial Conditions/Cue (Last Page} of this JPM, and Handout 1. START TIME: Performance Step: 1 Standard: Comment: Performance Step: 2 Standard: Comment: 2014 Admin -JPM A 1 b RO 0-3, Step 6.1.3 COMPLETE Section 1.0 of Attachment 3, Independent Verification. The operator goes to Attachment

3. 0-3, Attachment 3, Step 1.0/1.1 NOTE: If calculations were performed by a Licensed

Operator, then Independent Verification is performed by an STA OR Reactor Engineer.

If calculations were performed by an STA OR Reactor Engineer, then Independent Verification is performed by a Licensed Operator. CALCULATE the date and time for Xenon to return to the value at time of shutdown by one of the following methods: IF the PPCS program, XENON PREDICT will be used to determine the date and time for Xenon to return to the value at time of shutdown, THEN ..... The operator reads the NOTE and proceeds. The operator recognizes that the XENON PREDICT program is OOS, marks this step NA, and proceeds to Step 1.2 NU REG 1021, Revision 9 Appendix C Performance Step: 3 Standard: Comment: Performance Step: 4 Standard: Comment: 2014 Admin -JPM A1b RO Page 5 of 8 PERFORMANCE INFORMATION 0-3, Attachment 3, Step 1.2/1.2.1 Form ES-C-1 IF Attachment 1, Time To Equilibrium Xenon, will be used to determine the date and time for Xenon to return to the value at time of shutdown, THEN PERFORM the following: OTHERWISE, MARK this Step NIA RECORD the average power for the 6 hours prior to reactor shutdown. [vi] The pperator records 5Q%. The operator initials Step 1.2.1. 0-3, Attachment 3, Step 1.2.2 DETERMINE the amount of time for Xenon to decay to the value at time of shutdown, using the Table in Attachment

1. USE the power level recorded in attachment Step 1.2.1 and the current burnup recorded in Prerequisite Step 5.9. [vlJ,tl)e pperator c)bserve:$

thatthe; current recorded in Prerequisite 5.9 is 12,514 MWD/MTU. [vi] Th.e operator uses Attachment

1. and finds the. intersecting point for 12500 MWD/MTU and 50% power to be 13.5 hours, and records.

The operator initials Step 1.2.2. NU REG 1021, Revision 9 Appendix C Performance Step: 5 Standard: EXAMINER NOTE: Comment: Terminating Cue: STOP TIME: 2014 Admin -JPM A1b RO Page 6 of 8 PERFORMANCE INFORMATION 0-3, Attachment 3, Step 1.2.5 Form ES-C-1 CALCULATE the date and time at which Xenon will equal the value at time of shutdown by adding the hours determined in Step 1.1.6 OR Step 1.2.2 to Prerequisite Step 5.8 and recording below. NJJhe'. operator o.bserves thaithe.*Date and time of the Trip were ()730on 1213/..14. N]The h?urs. !9 the time. of trip .anc:l wiH equal th'e Vqlue at time of shutdown at 21 oq 'oh 12/3/14, and records. The operator initials Step 6.1.3. The operator places Printed Name, signature and initials I space provided in Step 5.1 (Page 6 of 19 of 0-3). The operator may report that the time that was determined in the Independent Verification is different from the time determined by the RE in Step 6.1.2. Evaluation on this JPM is complete. NUREG 1021, Revision 9 Appendix C Page 7 of 8 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2014 Admin -JPM A'lb RO Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiner's Signature: Date: 2014 Admin -JPM A1b RO NUREG 1021, Revision 9 Appendix C INITIAL CONDITIONS: INITIATING CUE: Form ES-C-1 JPM CUE SHEET

• The plant has from 50% power.
• The reactor had been operating at this power for the last 3 days prior to the trip.
• The XENON PREDICT program on the PPCS is NOT available.
• The Reactor has completed the Xenon Reactivity Calculation.
• It is currently 0900 on 12/3/14.

The CRS directed you to independently verify the Xenon Reactivity Calculation in accordance with Step 6.1.3 of 0-3, Hot Shutdown With Xenon Present. NUREG 1021, Revision 9 HOT SHUTDOWN WITH XENON PRESENT 5.0 PREREQUISITES NOTE: 0-3 Revision 04300 Page 6of19 Steps in Section 5.0 may be performed concurrently OR in any order. COMPLETE signature/initial block below for all personnel performing this procedure. Print Name Signature Initials {i;i::t /PERFORM page check of this procedure. Shilt Manager has authorized performance of this procedure. _ d I f l NOTIFY CRS of start of this procedure. NOTIFY HCO to log start of this procedure. VERIFY plant is at Hot Shutdown conditions following power operations . .. VERIFY Both Reactor Coolant Pumps are operating. RECORD date and time of trip or shutdown _,,

• Date \. t. llitl Time b I $ 0 RECORD the cycle burnup from PPCS point ID BURNUP.
• MWD/MTU:

(? / S.:-l+/- HOT SHUTDOWN WITH XENON PRESENT NOTE 0-3 Revision 04300 Page 7of19 Control rods that are NOT able to be verified fully inserted include control rods that are confirmed stuck (untrippable) or have lost rod position indication. IF one or more control rods are NOT able to be verified fully inserted THEN CALCULATE required increase in boron concentration to compensate for the decrease in shutdown margin.

• Q x 150 ppm =

__ ppm No. of RCCA HOT SHUTDOWN WITH XENON PRESENT 0-3 Revision 04300 Page 8of19 6.0 PERFORMANCE NOTE The preferred method for determining Xenon reactivity is to use the PPCS program, XENON PREDICT. Use of Attachment 1, Time To Equilibrium Xenon, for a shutdown from non-equilibrium power conditions is an approximation and, if used, the results should be confirmed by the Reactor Engineer as soon as possible. [G0237] a. SELECT the XENON PREDICT button from the "Operations Menu" on the PPCS. b. OBTAIN "Projected values of Xenon reactivity from current conditions" plot by depressing the TREND PLOT button using XENON PREDICT on the PPCS. c. IF accessing XENON PREDICT WITHIN ONE hour of the time at which the Reactor was subcritical, THEN RECORD the Xenon value at time zero (current conditions) for this calculation. OTHERWISE, MARK this Step N/A. XE PCM d. IF NOT accessing XENON PREDICT within one hour of the time at which the Reactor was su bcritical, THEN RECORD the value of Xenon reactivity that existed at the time the Reactor went subcritical from the hourly PPCS logs (Point ID "XFXEK") using nearest hourly reading. OTHERWISE, MARK this Step N/A. XE PCM AJA Ntt \ }-J ,f.\. HOT SHUTDOWN WITH XENON PRESENT 6.1.1.1 (Continued)

e. MOVE the cursor on the plot to the location at which the Xenon value on the decaying side of the curve is equal to the Xenon value obtained in EITHER Step 6.1.1.1.c OR Step 6.1.1.1.d.

f. DETERMINE the number of hours for the projected Xenon to decay to the value of Xenon reactivity that existed at the time the Reactor went subcritical.

Hours: r:;A IF Attachment 1, Time To Equilibrium Xenon, will be ),Z/ used to determine the date and time for Xenon to " return to the value at time of shutdown, THEN PERFORM the following: OTHERWISE, MARK this Step N/A. fX RECORD the average power for the 6 hours V prior to reactor shutdown. \OO Power:---=--=---% DETERMINE the amount of time for Xenon to decay to the value at time of shutdown, using the Table in Attachment

1. USE the power level recorded in Step 6.1 .1 .2.a and the current burnup recorded in Prerequisite Step 5.9. Hours CALCULATE the date and time at which Xenon will equal the value at time of shutdown by adding the hours determined in Step 6.1.1.1.f OR 6.1.1.2.b to Step :5.8 and recording below. Date \ 2\ :\M Time 02 '-1 > COMPLETE Section 1.0 of Attachment 3, Independent Verification.

6.1.4. NOTIFY Reactor Engineering to provide an estimated critical position strategy to ensure that largB boron concentration changes are not required immediately prior to startup. 0-3 Revision 04300 Page 9of19 Appendix C Job Performance Measure Worksheet Form ES-C-1 JPM A2 RO 2014 Admin -JPM A2 RO (REV_091114) NUREG 1021, Revision 9 Appendix C Page 2of10 Form ES-C-1 Job Performance Measure Worksheet Facility: Ginna Task No.: Task Title: Perform RCS Leakrate JPM No.: 2014 Admin -JPM A2 RO KIA

Reference:

2.2.12 (3. 7) 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. Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1. Anitjating

• . ,,

, 2014 Admin -JPM A2 RO .*to.. reC()\g .. f2. ..

• 1a. .*.*.

AND .**** ****. * * : ';tl'.iie current RCS L.eakrate,

• . . r.n * . NUREG 1021, Revision 9

Appendix C Page 3 of 10 Form ES-C-1 Job Performance Measure Worksheet Task Standard: The operator will complete Attachment 3 in accordance with the KEY provided, and identify the LCO RCS Operational

Leakage, is NOT met. Required Materials:

Calculator Standard Procedure Reference Carts must be available to the operator General

References:

0-6.13, Daily Surveillance Log, Rev 18301 Handouts: Time Critical Task: Validation Time: S-12.4, RCS Leakage Record Instructions, Rev 05701 S-12.2, Operator Action In The Event of Indication of Significant Increase in Leakage, Rev 04700 Technical Specifications; Appendix A to Facility Operating License for the R.E. Ginna Nuclear Power Plant; Docket No. 50-244, Amendment 115 Handout 1: Attachment 3 of S-12.4 marked up as required. NO 11 minutes 2014 Admin -JPM A2 RO NU REG 1021, Revision 9 Appendix C (Denote Critical Steps with a '1) Page 4of10 PERFORMANCE INFORMATION Form ES-C-1 Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1. START TIME: Performance Step: 1 Standard: Comment: Performance Step: 2 Standard: Comment: 2014 Admin -JPM A2 RO S-12.4, Step 6.1.1 Reasons for Addition:

• A -Auto Make-up.
• B -Borate.
• D -Dilution.
• AID -Alternate Dilution S-12.4, Step 6.1.2 Diversions.
• LOGY-Yes ORN-No. NUREG 1021, Revision 9

Appendix C Performance Step: 3 Standard: Comment: 2014 Admin -JPM A2 RO Page 5 of 10 PERFORMANCE INFORMATION S-12.4, Step 6.1.3 Gallons Added. Form ES-C-1

• LOG the number of gallons added from the RMW AND B.A. integrators.

NUREG 1021, Revision 9 Appendix C Performance Step: 4 Standard: Comment: 2014 Admin -JPM A2 RO Page 6of10 PERFORMANCE INFORMATION S-12.4, Step 6.1.4 Calculated Leak Rate. Form ES-C-1

• OBTAIN Leak Rate from VCT level change if no diversion has occurred during the leakage calculation time period.
• Leakage can be calculated using the following formula:

(6.% VCT Level) (12 gal./1%) +(Additions in gal. during time period)

• Time (In Minutes) between level readings
• In the above formula, 12 gal./1 % is generally the conservative number used for the leak rate calculation.

IF an exact number is necessary THEN REFER to Attachment 1 AND Attachment 2 of this procedure.

• IF determining calculated leak rate from an auto makeup, AND NO diversion has taken place, THEN take the total gallons added between auto makeups AND divide by the time elapsed (in minutes).
• IF necessary LCV-112A can be switched to VCT position to calculate a leak rate.
• ENSURE LCV-1 '12A is returned to Auto after leakage calculation is complete or as necessary to maintain VCT Level.
• IF calculated leak rate is greater than 0.500 gpm, THEN submit a Condition Report for Engineering evaluation of impact on Chargijng Pump NPSH. The operator recognizes that the VCT Level change cannot be used to determine leak rate (Diversion has occurred).

The operator recognizes that the leak rate can be calculated from the last two Auto Make ups (1225 and 1415). NUREG 1021, Revision 9 Appendix C Performance Step: 5 Standard: Comment: 2014 Admin -JPM A2 RO Page 7 of 10 PERFORMANCE INFORMATION S-12.4, Step 6.1.5 Identified Leak Rate. Form ES-C-1

• This is the sum of the leak rates calculated from the RCDT, PRT, and CPLR, primary to secondary

leakrate, AND any other known leak rates.

• The following guidance is provided for the Charging Pump Leakoff Rate data:
• At 0.100 gpm: SUBMIT Condition Report for 12 week planning process.
• At 0.150 gpm: Condition Report upgraded to Priority Two; work within two week
• At 0.200 gpm: IF possible, THEN SECURE pump AND preferentially run other pumps until fixed.
• At 0.500 gpm: TAG affected pump PER S-3.2G, Charging Pump Isolation.

The operator recognizes that a check of the Identified Area Leakage reveals that the leakrates in these areas have not changed since the previous leakrate determinations (Initial Conditions). NUREG 1Q21, Revision 9 Appendix C Performance Step: 6 Standard: Comment: Performance Step: 7 Standard: Comment: Terminating Cue: STOP TIME: 2014 Admin -JPM A2 RO Page 8of10 PERFORMANCE INFORMATION S-12.4, Step 6.1.6 Unidentified Leak Rate. Form ES-C-1

• This is the differemce in leak rates between the calculated leak rate AND the identified leak rate. The operator initials the 1415 entry. S-12.4, Step 6.1. 7 RMW and Boric Acid Integrators.
• At 2400 hrs, LOG the 2400 hrs value of RMW AND Boric Acid Integrator reading from the MCB.
• CALCULATE the total number of gallons added to the RCS by subtracting the 0000 hrs (previous day 2400 hrs) reading from the current 2400 hrs reading for both RMW AND Boric Acid.
• To obtain a 24 hr leakage rate, ADD the total gallons of RMW AND Boric Acid. THEN divide by 1440 minutes.

N/A if a diversion occurred within the day. The operator determines that this step is NOT required yet. Evaluation on this JPNI is complete. NUREG 1021, Revision 9 Appendix C Page 9 of 10 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2014 Admin -JPM A2 RO Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiner's Signature: Date: 2014 Admin -JPM A2 RO NUREG 1021, Revision 9 Appendix C INITIAL CONDITIONS: INITIATING CUE: Form ES-C-1 JPM CUE SHEET

• The plant is at 100% power with 40 gpm Letdown flow.
• The VCT Level point on the PPCS is OOS.
• At 1020 the VCT level was 25% when the HCO started the Day Shift RCS Leakage Monitoring Surveillance, intending to monitor for about 4 hours.
• At 1125 a VCT Level instrument failure occurred which l&C -corrected and restored to operation within 10 minutes.
• It is currently 1415 and an Auto Makeup has just been completed.
• No VCT Diversion occurred.
• The ULR tool is temporarily OOS.
• The current Integrator Readings are as follows:
• RMW Reading:

240

• BA Reading 21.0
• A check of the Identified Area Leakage has not changed since the leakrate determinations were recorded.
• The CRS directed you to record the data for the recent Auto Makeup on Attachment 3, RCS Leakage Surveillance Record, AND determine the current RCS Leakrate.
• Identify Tech Spec LCOs, if any, that have been exceeded.

NUREG 1021, Revision 9 RCS LEAKAGE SURVEILLANCE RECORD INSTRUCTIONS S-12.4 Revision 05800 Page 22of29 c t a egory 3 3 39 .. Reviewed ---Time RMW BA Reading Reading --'2300 1< ,..., \0"20 \\'2.S \'?DO 0 }'2.'2.$ I '3. S 10.o..( Attachment 3, RCS Leakage Surveillance Record ec1on System Inventory Reason Gallons !dent Unidentd AD Diversion Added Calcula'ted Leak Leak BND BA+RMW Leak Rate Rate Rate --

• Oi"Z... .06& c,o<{ -Alo /J /S y A/o rJ IS A N 11.s.'1 ULR Tool Updated Page 1of2 Date* /2.[Z /ti Day: RMW Integrator 2400 HRS. 0000 HRS. a Total Gallons:

BA Integrator 2400 HRS. 0000 HRS. C:> Total Gallons: 24 Hr Leakage Rate, If NO Diversion Total RMW+BA= ___ gpm 1440 NOTE: IF Reactor Makeup Rate Increases by 0.25 gpm Over The Normal, REFER to S-12.2. NOTE: IF unidentified leak rate(ULR) meets critetlisted in 6.1.6, REFER to S-12.2, Operator Action In The Event Of Indication Of Significant Increase In Leakage Remarks: I ,.hJ.,.,,.1 r 15 c:;:.\-ll:t..<. Time Night Shift Location G.P.M. '2000 \°?,.COT .oe>I "2100 c t't..I\.

• 06"7 Remarks:

Section "C" Containment Condensate Collectors Total Fluid Dump Dump Released to Sum12 A: Time Time 1090 1091 (#Dumps) (Gal/Dump) oisg co'2o 1090 L_) 2.57 = L_) 06'28 1091 L_) 2.45 = L_) o'1S.3 /") 7'2. 7 1092 L_) 2.42 = L_) W{ 1093 L_) 3.05 = L_) TOTAL ---TOTAL= G.P.M. 1440 Remarks: Section "B"' Leakage From Identified Areas Time Location U"IOO 'Rc.o'T ,,,,.....,,, <:.f'L(;t. RCP Standpipe Time RCPNB Dump Dump Dump Time Time Time 1092 1093 ( ) D'153 oN<f o.353 ()/') '1 Day Shift Remarks: G.P.M. .ool .o'"lt..t Aux. Bldg. Sump SumoTk Time Section "D" -Containment Sump Pump Actuations

1. Last Calculated Leak Rate in gpm. Date: 2.Last Pump Actuation TIME: 3.Present Pump Date: Actuation TIME: 4.New Interval In Hours 5.GPM = Note 1 OR 2 STEP4 x (0.0167)

Remarks: PZR ReliefTank Temp Press Level

• oCX::. '!Oho/" "20/'i) NOTE 1: Pump "A" 98 Gals/Actuation, Pump "B" 140 Gals/Actuation NOTE 2: A Sump Level in gallons (120gal/ft){PPCS pt. L2039 or L2044) NOTE 3: IF sump leakage >0.02 gpm increase

occurred, Refer to S-12.2 RCS LEAKAGE SURVEILLANCE RECORD INSTRUCTIONS Attachment 3, RCS Leakage Surveillance Record, (Continued)

Section "E" Containment Temperature: PPCS TCV03 TCV08 POINTS Yesterdays Carry Over 0700-1900 g :,, c=t'l 1'/.1b 1900-0700 fS?.27. Cj'1.8.3 'lo.28 NOTE 1 -Tech Spec limit is s 125° F (SR 3.6.5.1 ), Refer to step 6.5 for Ad min Limits NOTE 2 -Admin Limit is from -0.2 TO+ 0.5 PSlG., Refer to 0-11 for maintaining pressure. NOTE 3 -Tech Spec limit "-2 psig and 51 psig ( SR 3.6.4.1 ). AVG. TEMP TCV17 SEE NOTE 1 9Z.77 '8& .'{'T foo.80 9 '3. >7 S-12.4 Revision 05800 Page 23 of 29 Page 2 of 2 Containment Pressure Pl-944 SEE Note 2 HCO SEE Note 3 SEE Note 4 0.35 0. '15 NOTE 4 -Refer to 0-11 for procedural guidance to obtain a containment pressure readin!J via an alternate path when Pl-944 out-of-service. Remarks: Section "F" Remarks: Containment Particulates -R11 (PPCS pt. R11H12) 1. Yesterday's 2400 hr avg __

2. Today's 1200 hr avg '2.o S 3. Difference Step 2 -Step 1 = ;:(o> -'2 o S

__ cpm INC or (AM) ______ cpm DEC 2or::; 4. Today's 1200 hr avg----*

5. Today's 2400 hr

6. Difference Step 5 -Step 4 = _ _JJ°J -2o5 ______ cpm INC or/

___ cpm DEC (PM) 7. G.P.M Leakage= (cpm -background cpm) (1.8 E -7) µC/CC Krypton 88 In Reactor Coolant = ( 11'1 -"'2-DO )(18 E-7l = __ D __ gpm 3. 01. 1.:--3 ) NOTE: If Containment Particulate Average Increases by 2000 cpm Over The Last Average, Refer To S-12.2 Section "G" Containment Gas -R12 (PPCS pt. R12H12) 1.Yesterday's 2400 hr avg 3'-!.S 2.Today's 1200 hr avg 3-'-{(;. 3.DifferenceStep2-Step1 (100)=( 3'-/(. -3'-f.5 )(100)= O_._.:S ___ %1NC Step 1 3'-/S or 4.Today's 1200 HR AVG 3t.../"' 5.Today's 2400 HR AVG 6.Difference Step 5-Step 4 (100) = ( Step 4 3 ro. 3i& ) (100) = 3 '-f,{. ____ %DEC ____ %INC or % DEC NOTE:-If Containment Gas Average increases by 20% over Last Average, Refer To S-12.2 SHIFT 1 SHIFT 2 (AM) (PM) Remarks:

• r :j.,-RCS LEAKAGE SURVEILLANCE RECORD INSTRUCTIONS S-12.( Revision 05800 Page 22of29 Attachment 3, RCS Leakage Surveillance Record Page 1 of 2 Date: 11..{z/Ji Category 3 3 39 Section "A" .. Day:

Reviewed ---System Inventory Reason Gallons I dent Unidentd RMW Integrator Time RMW BA AD Diversion Added Calculated Leak Leak ULRTool Reading Reading Leak Rate Updated B AID BA+ RMW Rate Rate 2400 HRS. 0000 HRS. 0 1200-----L, i/cT G 6"]Z. >> 0£,f:'., .oot../ Total Gallons: ') /L{ z. 2."?Joo \S 0 l\jp N 1$ lo LO ---** ---L>\JcT BA Integrator \\'LS v 2400 HRS. i ODDO HRS. 0 I '2.. '--X::.' 3o Cl i;,,,;o /\) 15 Total Gallons: l2-Z5 I 3>5 \0 .L{ I\ N 11.5. '--/ 24 Hr Leakage Rate, If NO 1'115 2'-!o 21 A N tl.5.b Diversion l'l.2S*l"ll5-

---

.a\JCT l.04) I

• O'-/<; I. oo(.. Total RMW+ BA= ___ gpm 1440 NOTE: IF Reactor Makeup Rate Increases by 0.25 gpm Over The Normal, REFER to S-12.2. NOTE: IF unidentified leak rate(ULR) meets ctria listed in 6.1.6, REFER to S-12.2, Operator Action In The Event Of Indication Of Significant Increase In Leakage Remarks:

DiVc>"hJ.. \ c.\.Jo>w>'l

• t: t1.., <. Time Night Shift Location G.P.M. zn,...,.. .ool 'Zloo C.Vt.\t .oG"'l Remarks:

Section "C" Containment Condensate Collectors Total Fluid Dump Dump Released to Sump A: Time Time 1090 1091 (#Dumps) (Gal/Dump) c Z<.s? Oc>U> 1090 L_) 2.57 = L_) 1091 L_) 2.45 = L_) o<r<.3 67'2..7 1092 L_) 2.42 = L_) 1'317 111 '"( 1093 L_) 3.05 = L_) TOTAL ---TOTAL= G.P.M. 1440 Remarks: Section "B" Leakage From Identified Areas Time Location 6'i'o6 1 .... ,..,.... cf1.j<, RCP Standpipe Time RCPAIB Dump Dump Dump Time Time Time 1092 1093 ( ) 01'1'( 0353 o'121 Day Shift Remarks: G.P.M. *OOI . "'"'"' Aux. Bldg. Sumo SumoTk Time Section "D" -Containment Sump Pump Actuations

1. Last Calculated Leak Rate in gpm. Date: 2.Last Pump Actuation TIME: 3.Present Pump Date: Actuation TIME: 4.New Interval In Hours 5.GPM = Note 1 OR 2 STEP4 x (0.0167)

Remarks: PZR ReliefTank Temp Press Level .06b 11/so/.'1 20fi NOTE 1: Pump "A" 98 Gals/Actuation, Pump "B" 140 Gals/Actuation NOTE 2: fl Sump Level in gallons (120gal/ft)(PPCS pt. L2039 or L2044) NOTE 3: IF sump leakage >D.02 gpm increase

occurred, Refer to S-12.2 Appendix C Job Performance Measure Worksheet Form ES-C-1 JPM A3 RO 2014 Admin -JPM A3 RO (REV_091714)

NUREG 1021, Revision 9 Appendix C Facility: Task Title: Page 2 of 7 Form ES-C-1 Job Performance Measure Worksheet Ginna Evaluate Steam Generator Tube Leakage from R-47 Reading Task No.: JPM No.: 2014 Admin -JPM A3 RO KIA

Reference:

2.3.5 (2.9) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: x Classroom x Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Provide Candidate with Initial Conditions/Cue (Last Page) of this JPM. Initial Conditions: Initiating Cue:

• The plant is operating at 100% power,
• The Secondary AO has called and indicated that the R-47 AMBER light .is blinking, and the R-47 bar graph indication, which is also AMBER, is reading 5.832E2 cpm.
• The AO reports that:
• The R-47 WARNING alarm setpoint is 4.56E2 cpm.
• T.he R-47 HIGH alarm setpoint is 9.11 E2 cpm.
• The HCO reports that the PPCS point R47G is reading 4.3 gpd and stable.*
• RP/Chemistry fois.beerlrequestedtoobtain andanalyze an air ejector grab sample.
• The crew is evaluating the need to enter AP-SG.1, Steam Generator Tube Leak. The CRS directed you to: 1. Determine if the R-4 7 alarm setpoints are set properly.

2. Determine the estimated Steam Generator Tube Leakrate based on the local R-47 reading.

2014 Admin -JPM A3 RO NU REG 1021, Revision 9 Appendix C Page 3 of 7 Form ES-C-1 Job Performance Measure Worksheet

3. Determine if AP-SG.1, Steam Generator Tube Leak, should be entered based on the known information.

Task Standard: The operator will determine that the R-47 alarm setpoints are set lower than identified by P-9, and that the local R-47 reading is too low to support entry into AP.SG.1. Required Materials: Calculator Standard Procedure Reference Carts must be available to the operator General

References:

AR-RMS-R47, R-47 Air Ejector Noble Gas Monitor, Rev 00000 AR-PPCS-R47 AR, SGTL Indicated, Rev 00000 Handouts: Time Critical Task: Validation Time: RE Ginna Curve Book, Curve 06*-004, Steam Generator Tube Leak Rate vs. RM-47 Reading, Rev 8/8/14 AP-SG.1, Steam Generator Leak, Rev 01500 P-9, Radiation Monitoring System, Rev 09900 None NO 7 minutes 2014 Admin -JPM A3 RO NUREG 1021, Revision 9 Appendix C Page 4 of 7 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with a "'1) Provide Candidate with Initial Conditions/Cue (Last Page) of this JPM. START TIME: Standard: EXAMINER CUE: EXAMINER NOTE: Comment: 2014 Admin -JPM A3 RO Determine if the R-47 alarm setpoints are set properly. The operator obtains P-9, Radiation Monitoring System. ['/]The operator uses P:-9 todeterniine that the required R.-47 HIGri alarm mustbe set at 9.11 E6 cpm,. Hl The operator compares the reported R-47 HiGH alarm setpoiQtfoth'at'requiredby R..:9;anddeterminesthat the R-47 HIGrfalarrii setpoint is incorrectly settqo. LOW. Hl The operator.uses p-9:fo determine that the R:47 WARNING alarm.stioulcf6e.set at 4.56E6 cpm. [ -/] T.he. operator R-4 7 WARNING alarm setpoir:itto,that and determines that the R-47 WARNING alarmsetpoint is set too LOW. If the operator requests the alarm setpoints as listed on the PPCS, indicate that the WARNING alarm is set at 4.56E6 cpm, and the HIGH alarm setpoint is set at 9.11 EG cpm. There is a potential that the alarm setpoints on the PPCS and the local instrument could be set differently. The PPCS alarm setpoints are set by IT personal controlling the PPCS Software. The alarm setpoints on the local instrument are set by operators. NUREG 1021, Revision 9 Appendix C Standard: EXAMINER CUE: Comment: Performance Step: 3 . --Standard: EXAMINER NOTE: Comment: Terminating Cue: STOP TIME: 2014 Admin -JPM A3 RO Page 5 of 7 PERFORMANCE INFORMATION Form ES-C-1 Determine the estimated Steam Generator Tube Leakrate based on the local R-47 reading. The operator obtains Curve 06-004, Steam Generator Tube Leak Rate vs. RM-47 Reading. [\/}The colllpares the locai R-47reading of 5.832E2 to Cur:ve #06'-004; and determines that Steam Generator Tube . If asked, report as the Secondary AO that the Air Ejector leakoff is 3.0 SCFM. Determine if AP-SG.1, Steam Generator Tube Leak, should be entered based on the known information . The operator obtains AP-SG.1 and reviews Entry Conditions and Symptoms. [-V] The operator comparesth.e known information to the AP-SG.1 Entry Conditionsand Symptoms and determines that none are met; and thatAP:.sG.1.should NOT be entered. The operator may indicate that AP-SG.1 could be entered based on the results of the requested Air Ejector grab sample. Evaluation on this JPM is complete. NUREG 1021, Revision 9 Appendix C Page 6 of 7 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2014 Admin -JPM A3 RO Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiner's Signature: Date: 2014 Admin -JPM A3 RO NUREG 1021, Revision 9 Appendix C INITIAL CONDITIONS: INITIATING CUE: Form ES-C-1 JPM CUE SHEET

• The plant is operating at 100% power.
• The Secondary AO has called and indicated that the R-47 AMBER light is blinking, and the R-47 bar graph indication, which is also AMBER, is reading 5.832E2 cpm.
• The AO reports that:
• The R-47 WARNING alarm setpoint is 4.56E2 cpm.
• The R-47 HIGH alarm setpoint is 9.11E2 cpm.
• The HCO reports that the PPCS point R47G is reading 4.3 gpd and stable.
• RP/Chemistry has been requested to obtain and analyze an air ejector grab sample.
• The crew is evaluating the need to enter AP-SG.1, Steam Generator Tube Leak. The CRS directed you to: 1. Determine if the R-47 alarm setpoints are set properly.

2. Determine the estimated Steam Generator Tube Leakrate based on the local R-47 reading.

3. Determine if AP-SG.1, Steam Generator Tube Leak, should be entered based on the known information.

NU REG 1021, Revision 9 Appendix C Job Performance Measure Worksheet Form ES-C-1 JPM A1a SRO 2014 Admin-JPM A1a SRO (REV_091514) NUREG 1021, Revision 9 \ Appendix C Facility: Task Title: Page 2 of 7 Job Performance Measure Worksheet Ginna Task No.: Determine Time to Boil for a Loss of JPM No.: Shutdown Cooling Form ES-C-1 2014 Admin -JPM A1a SRO KIA

Reference:

2.1.25 (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. Provide Candidate with Initial Conditions/Cue (Last Page of this JPM). Initial Conditions: Initiating Cue:

• The plant is in Mode 5 for a refueling outage.
• The reactor has been shutdown for 25 hours.
• The pressurizer is solid with L TOP in service.
• RCS temperature is 140°F.
• The Ginna Defense-In-Depth computer program used to calculate time to boil and core uncovery is .unavailable.

The Shift Manager has directed you to determine the Time to Boil given a Loss ofRHR and the following two sets of conditions: . .

• For present plant conditions,
• AND
• Exactly four (4) days from now based on the following conditions:
• RCS level will be reduced to 64 inches
• RCS temperature will be lowered to 100°F
• PRZR manway will be removed 2014 Admin -JPM A1a SRO NUREG 1021, Revision 9

Appendix C Page 3 of 7 Form ES-C-1 Job Performance Measure Worksheet Task Standard: The operator will use IP-OUT-2, Outage Risk Management, and determine that the Time to Boil for the present plant conditions is 2.46 hours, and for the projected conditions four days from now is .43 hours (25.96 +0.1/-0.0 minutes). Required Materials: Calculator Standard Procedure Reference Carts must be available to the operator General

References:

IP-OUT-2, Outage Risk Management, Rev 02000 Handouts: None Time Critical Task: NO Validation Time: 7 minutes 2014 Admin -JPM A 1 a SRO NUREG 1021, Revision 9 Appendix C Page 4 of "7 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with a '1) Provide Candidate with Initial Conditions/Cue (Last Page of this JPM). START TIME: Performance Step: 1 Standard: Comment: 2014 Admin -JPM A1a SRO IP-OUT-2, Attachment A .. 5, Core Cooling Present Plant conditions: Time to core boiling (saturation) and core uncovery can be determined from Attachments 5-14 of ME-98-115 (Attachment E, Time to Boil/Core Uncovery). Use the table which most closely matches actual plant conditions. The operator obtains a copy of IP-OUT-2, reviews it and arrives at Attachment E. The operator determines that Page 5 of 11 on Attachment E, Time to Reach Saturation with Pressurizer Full and RCS Closed, most closely approximates present plant conditions, and addresses this page. ['11 The operator finds the intersecting cell for Time after S.hutdown (hrs)"' 25 and Tin1e to Reach Saturation (hrs) w/Trcs = 140°F;to 2.46 hours. NU REG 1021, Revision 9 Appendix C Performance Step: 2 Standard: EXAMINER NOTE: Comment: Terminating Cue: STOP TIME: 2014 Admin -JPM A1a SRO Page 5 of 7 PERFORMANCE llNFORMA TION Form ES-C-1 IP-OUT-2, Attachment A.5, Core Cooling Projected Plant conditions four (4) days from now: Time to core boiling (saturation) and core uncovery can be determined from Attachments 5-14 of DA-ME-98-115 (Attachment E, Time to Boil/Core Uncovery). Use the table which most closely matches actual plant conditions. The operator obtains a copy of IP-OUT-2, reviews it and arrives at Attachment E. The operator that Page 7 of 11 on Attachment E, Time to Reach Saturation at 64" and RCS Open, most closely approximates present plant conditions, and addresses this page. [ 'l'J The Operator finds ,the intersect.ing cell for Time after Shutdown (hrs) ::'.120. alldTimetoReach Saturation (hrs) w/Trcs ::: 100°F to 0.43 hou'rs/2S:9() (+0.1/-0.0) minutes. The +0.1/0.0 allowance is based on the fact that there have been 121 hours rather than 120 hours since the shutdown, and the operator may interpolate between the 120 hour time to reach saturation in minutes and the 150 hour time to reach saturation in minutes. If this is the case, and the operator assumed a linear function between the two points, the time would be increased by approximately 0.1 minutes. Evaluation on this JPM is complete. NUREG 1021, Revision 9 Appendix C Page 6 of 7 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2014 Admin -JPM A1a SRO Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiner's Signature: Date: 2014 Admin -JPM A1a SRO NU REG 1021, Revision 9 Appendix C INITIAL CONDITIONS: INITIATING CUE: Record Answers Below: Present Plant Conditions: Projected Plant Conditions: (Four Days from now) Form ES-C-1 JPM CUE SHEET

• The plant is in Mode 5 for a refueling outage.
• The reactor has been shutdown for 25 hours.
• The pressurizer is solid with L TOP in service.
• RCS temperature is 140°F.
• The Ginna Defense-In-Depth computer program used to calculate time to boil and core uncovery is unavailable. The Shift Manager has directed you to determine the Time to Boil given a Loss of RHR and the following two sets of conditions:
• For present plant conditions, AND
• Exactly four (4) days from now based on the following conditions:
• RCS level will be reduced to 64 inches
• RCS temperature will be lowered to 100°F
• PRZR manway will be removed NUREG 1021, Revision 9

Appendix C Job Performance Measure Workshee,t Form ES-C-1 JPM A1b SRO 2014 Admin -JPM A1a SRO (REV_100414) NUREG 1021, Revision 9 Appendix C Page 2 of 10 Form ES-C-1 Job Performance Measure Worksheet Facility: Ginna Task No.: Task Title: Cold Weather Walkdown JPMNo.: 2014Admin-JPMA1b SRO KJA

Reference:

2.1.8 (4.1) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: x Classroom x Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handouts 1-2. Appendix C Page 3 of 10 Form ES-C-1 Job Performance Measure Worksheet Task Standard: The operator will review the most recent plant area temperature data and then use 0-22 to determine that two areas of the plant are too low in temperature. Then the operator will prioritize the actions of the Auxiliary Operators to tour these areas more frequently, and identify discrepancies and actions required in accordance with the attached KEY. Required Materials: None General

References:

0-22, Cold Weather Walkdown Procedure, Rev 01003 Handouts: Handout 1: 0-22, Cold Weather Walkdown Procedure, marked up as Time Critical Task: Validation Time: follows:

• Step 5.1: Several Names inserted/Signatures and Initials
• Step 5.2: Initialed
• Step 5.3: SM Identified/Date entered and initialed
• Step 5.4: Initialed
• Step 5.5: Initialed Handout 2: Completed Attachment 1 of 0-22, Cold Weather Walkdown Procedure NO 20 minutes 2014 Admin -JPM A1b SRO NUREG 1021, Revision 9

Appendix C Page 4of10 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with a '1) Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handouts 1-2. START TIME: Performance Step: 1 Standard: EXAMINER NOTE: Comment: 2014Admin-JPM A1b SRO 0-22, Step 6.1.1 Note: The instructions in this section are applicable at all times between November 1 and April 1. Note: Steps of this Procedure may be performed out of sequence with SRO concurrence. IF an abnormal condition exists that poses a hazard to plant operation, THEN SUBMIT a work request AND immediately notify Maintenance to correct the problem. OTHERWISE, MARK this Step N/A. The operator reads the Notes, and proceeds. The operator recognizes that no abnormal condition exists which poses a hazard to plant operation, and proceeds. These Steps may be performed in any order. NU REG 1021, Revision 9 Appendix C Performance Step: 2 Standard: EXAMINER CUE: EXAMINER NOTE: Comment: 2014 Admin -JPM A1b SRO Page !3of10 PERFORMANCE INFORMATION 0-22, Step 6.1.2 Form ES-C-1 Note: Routine thermometer readings are obtained with the Auxiliary Operators PDA. However when the Auxiliary Operators PDA is unavailable Attachment 1, Cold Weather Temperature Log may also be used to log the following readings. OBTAIN designated thermometer readings in potential cold areas once per shift. (Auxiliary Operator using PDA) The operator reads the Note, and proceeds. The operator reviews the completed Attachment 1 temperature readings and compares these to the minimum temperatures required by Precaution and Limitation 4.1. As Plant Management, ask the SM to provide recommendations for corrective actions to raise temperature in the affected area(s) AND to raise surveillance frequency until temperature can be restored. The operator establishes any or no prioritization for the Primary Operator Walkdown Tour. These Steps may be performed in any order. NUREG 1021, Revision 9 Appendix C Performance Step: 3 Standard: EXAMINER NOTE: Comment: Performance Step: 4 Standard: EXAMINER Cue: EXAMINER NOTE: Comment: 2014 Admin -JPM A1b SRO Page 6of10 PERFORMANCE INFORMATION 0-22, Step 6.1.3 Form ES-C-1 IF required by the Shift Manager, THEN PERFORM the following to install light weight easy view thermometers at locations susceptible to cold or hot air OR where temporary work setups would pose a freezing problem: OTHERWISE, MARK this Step NIA The operator recognizes that there are no light-weight easy-view thermometers that have been installed in any locations due to on-going work activities, and marks this Step NA, and proceeds. These Steps may be performed in any order. 0-22, Step 6.1.4 WHEN contacted by the Mechanical PM Analyst, THEN LOG open WR/TR numbers and descriptions generated from completion of M-1306.1, Maintenance Department Winterizing Inspection

Program, on Attachment

2. The operator recognizes that there are no open work orders/trouble reports numbers generated from M-1306.1, Ginna Station Maintenance Department, Winterizing Inspection

Program, and requests that the SM initials this step. If requested, as the SM Initial Sep 6.1.4. These Steps may be performed in any order. NU REG 1021, Revision 9

Appendix C Performance Step: 5 Standard: EXAMINER NOTE: Comment: Terminating Cue: STOP TIME: 2014 Admin -JPM A1b SRO Page 7of10 PERFORMANCE INFORMATION 0-22, Step 6.1.5 Form ES-C-1 IF snow accumulation reduces the 12 inch minimum from a fire hydrant nozzle to ground level, THEN NOTIFY Fire Brigade to implement SC-3.19, Snow Removal for Access to Fire Equipment. OTHERWISE, MARK this Step N/A. These Steps may be in any order. Evaluation on this JPM is complete. NUREG 1021, Revision 9 Appendix C Page 8of10 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2014 Admin -JPM A1b SRO Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiner's Signature: Date: 2014 Admin -JPM A1b SRO NUREG 1021, Revision 9 Appendix C KEY: Priority Area(s) for Secondary Side Operator: Priority Area(s) for Primary Side Operator: Priority Area(s) for Outside Operator: Discrepancies (If any): Required Actions (If any): Page 9of10 VERIFICATION OF COMPLETION Form The operator prioritizes Section 6.2.11 for the Secondary Operator Walkdown Tour and/or requires inspection of the Diesel Generator Room Bat a higher frequency than once every 12 hours. (JPM stee 2}. The operator establishes any or no prioritization for the Primary Operator Walkdown Tour (JPM Step 2). The operator prioritizes Section 6.4.1 for the Outside Operator Walkdown Tour and/or requires inspection of the Screenhouse at a higher frequency than once every 12 hours (JPM Step 2). The operator determines that the temperatures in the B Diesel Room and the North Wall Area temperatures are below that required by Precaution and Limitation 4.1 (JPM Step 2). Contact Plant Management to establish priority for corrective actions to raise temperature in the B Diesel Room and the Screenhouse North Wall Area temperatures (JPM Step 2). Notify the Fire Brigade to implement SC-3.19, Snow Removal for Access to Fire Equipment (JPM Step 5). 2014 Admin -JPM A 1 b SRO NUREG 1021, Revision 9 Appendix C INITIAL CONDITIONS: INITIATING CUE: Record Answers Below: Priority Area(s) for Secondary Side Operator: Priority Area(s) for Primary Side Operator: Priority Area(s) for Outside Operator: Discrepancies (If any): Required Actions (If any): Form ES-C-1 JPM CUE SHEET

• The weekly Cold Weather Walkdown is in progress, and the Primary, Secondary and Outside Auxiliary Operators have just completed their Walkdown Tours.
• The Auxiliary Operator PDA is unavailable,

however, the recently completed Attachment 1, Cold Weather Temperature Log, of 0-22, Cold Weather Walkdown Procedure, is available.

• A severe lake-effect storm is occurring with 12 inches of snow having accumulated over the last four hours, and the Outside AO has reported that the snow has reached the nozzles of several fire hydrants.
• There are no open work orders/trouble reports numbers generated from M-1306.1, Ginna Station Maintenance Department, Winterizing Inspection Program.
• There are no light-weight easy-view thermometers that have been installed in any locations due to on-going temporary work activities.
• Other than the weather concern, there are no hazards to plant operation at this time.
• You, as the Shift Manager, are required to review Attachment 1 and perform section 6.1, General Instructions, of 0-22, and prioritize any areas of concern for the Auxiliary Operator Walkdown Tours.
• Document discrepancies, if any, and any required action(s).

NUREG 1021, Revision 9 COLD WEATHER WALKDOWN PROCEDURE 5.0 PREREQUISITES NOTE 0-22 Revision 01003 Page a of 48 Steps in Section 5.0 may be performed concurrently OR in any order. 5.1. COMPLETE signature/initial block below for all personnel performing this procedure. Print Name Signature Initials 5.2. PERFORM page check of this procedure. 5.3. Shift Manager has authorized performance of this procedure. _ ....... \._ .. ...... 1A._ ... --re-J<->-l Shift Manager 'J Date 5.4. NOTIFY CRS of start of this procedure. 5.5. NOTIFY HCO to log start of this procedure. COLD WEATHER WALKDOWN PROCEDURE Attachment 1, Cold Weather Temperature Log Outside Air Temp (33' Level) or outside Door 11 if Met Tower is 008 tG Int. Bldg. East end, top of stairs from Door S-44 7 2-A Diesel Generator Room /'.,,,(_ B Diesel Generator Room lei + Main Feed Pump Room near NPSH Panel 7-g Main Feed Pump Room Northwest area -,..p, Main Feed Pump Room Southwest Area 7ti" MCC 1A Turbine Bldg. Basement l/t Screenhouse South Screen Bay Area, East side c;l-. Screenhouse, North wall Screenhouse, West wall t::;c;' Standby Aux. Feed Pump Room "g TSC Diesel Generator Room 1.c:,<@ TSC Batt Room Whenever Generator Rm Heat E-28 is "s on, N/A the rest of the time. Maintain > 66°F Aux Building North wall by MCC 1 E 71 Aux Building South wall by Door #29 10 Aux Building North of Door #28 l/f Battery Room A '75"" Battery Room B END OF SHIFT F!EVIEW by either Shift Manager or CRS 0*22 Revision 01003 Page 45 of 48 Page 1 of 1 Appendix C Job Performance Measure Worksheet Form ES-C-1 JPM A2 SRO 2014 Admin -JPM A2 SRO (REV_091514) NUREG 1021, Revision 9 Appendix C Page 2of10 Form ES-C-1 Job Performance Measure Worksheet Facility: Ginna Task No.: Task Title: Perform RCS Leakrate Surveillance JPM No.: 2014 Admin -JPM A2 SRO KJA

Reference:

2.2.12 (4.1) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: x Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1. 2014 Admin -JPM A2 SRO NUREG 1021, Revision 9 Appendix C Page 3of10 Form ES-C-1 Job Performance Measure Worksheet Task Standard: The operator will complete Attachment 3 in accordance with the KEY provided, and identify the LCO 3.4.13, RCS Operational

Leakage, is NOT met, and that the ACTION is to reduce leakage to within limits within 4 hours (A.1). Required Materials:

Calculator Standard Procedure Reference Carts must be available to the operator General

References:

0-6.13, Daily Surveillance Log, Rev 18301 Handouts: Time Critical Task: Validation Time: S-12.4, RCS Leakage Record Instructions, Rev 05701 S-12.2, Operator Action In The Event of Indication of Significant Increase in Leakage, Rev 04700 Technical Specifications; App1;;ndix A to Facility Operating License for the R.E. Ginna Nuclear Power Plant; Docket No. 50-244, Amendment 115 Handout 1: Attachment 3 of S*-12.4 marked up as required. NO 15 minutes 2014 Admin -JPM A2 SRO NUREG 1021, Revision 9 Appendix C (Denote Critical Steps with a '\/) Page 4 of 10 PERFORMANCE INFORMATION Form ES-C-1 Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1. START TIME: Performance Step: 1 Standard: Comment: Performance Step: 2 Standard: Comment: 2014 Admin -JPM A2 SRO S-12.4, Step 6.1.1 Reasons for Addition:

• A -Auto Make-up.
• B -Borate.
• D -Dilution.
• AID -Alternat1a Dilution S-12.4, Step 6.1.2 Diversions.
• LOGY-Yes ORN-No. NUREG 1021, Revision 9

Appendix C Performance Step: 3 Standard: Comment: 2014 Admin -JPM A2 SRO Page 5 of '10 PERFORMANCE INFORMATION S-12.4, Step 6.1.3 Gallons Added. Form ES-C-1

• LOG the number of gallons added from the RMW AND B.A. integrators.

NU REG 1021, Revision 9 Appendix C Performance Step: 4 Standard: Comment: 2014 Admin -JPM A2 SRO Page 6of110 PERFORMANCE INFORMATION S-12.4, Step 6.1.4 Calculated Leak Rate. Form ES-C-1

• OBTAIN Leak Rate from VCT level change if no diversion has occurred during the leakage calculation time period.
• Leakage can be calculated using the following formula:

(b.% VCT Level) (12 gal./1%) +(Additions in gal. during time period)

• Time (In Minutes) between level readings
• In the above formula, 12 gal./1% is generally the conservative number used for the leak rate calculation.

IF an exact number is necessary THEN REFER to Attachment 1 AND Attachment 2 of this procedure.

• IF determining calculated leak rate from an auto makeup, AND NO diversion has taken place, THEN take the total gallons added between auto makeups AND divide by the time elapsed (in minutes).
• IF necessary LCV-112A can be switched to VCT position to calculate a leak rate.
• ENSURE LCV-11 :2A is returned to Auto after leakage calculation is complete or as necessary to maintain VCT Level.
• IF calculated leak rate is greater than 0.500 gpm, THEN submit a Condition Report for Engineering evaluation of impact on Charging Pump NPSH. The operator recognizes that the VCT Level change cannot be used to determine leak rate (Diversion has occurred).

The operator recognizes that the leak rate can be calculated from the last two Auto Make ups (1225 and 1420) . . 'Ii,! NUREG 1021, Revision 9 Appendix C Performance Step: 5 Standard: Comment: 2014 Admin -JPM A2 SRO Page 7 of '10 PERFORMANCE INFORMATION S-12.4, Step 6.1.5 Identified Leak Rate. Form ES-C-1

• This is the sum of the leak rates calculated from the RCDT, PRT, and CPLR, primary to secondary

leakrate, AND any other known leak rates.

• The following guidance is provided for the Charging Pump Leakoff Rate data:
• At 0.100 gpm: SUBMIT Condition Report for 12 week planning process.
• At 0.150 gpm: Condition Report upgraded to Priority Two; work within two week
• At 0.200 gpm: IF possible, THEN SECURE pump AND preferentially run other pumps until fixed.
• At 0.500 gpm: TAG affected pump PER S-3.2G, Charging Pump Isolation.

The operator recognizes that a check of the Identified Area Leakage reveals that the leakrates in these areas have not changed since the previous leakrate determinations (Initial Conditions). NUREG 1021, Revision 9 Appendix C Performance Step: 6 Comment: Performance Step: 7 Standard: Comment: Terminating Cue: STOP TIME: 2014 Admin -JPM A2 SRO Page 8of10 PERFORMANCE INFORMATION S-12.4, Step 6.1.6 Unidentified Leak Rate. Form ES-C-1

• This is the difference in leak rates between the calculated leak rate AND the identified leak rate. The operator initials the 1415 entry. S-12.4, Step 6.1. 7 RMW and Boric Acid Integrators.
• At 2400 hrs, LOG the 2400 hrs value of RMW AND Boric Acid Integrator reading from the MCB.
• CALCULATE the total number of gallons added to the RCS by subtracting the 0000 hrs (previous day 2400 hrs) reading from the current 2400 hrs reading for both RMW AND Boric Acid.
• To obtain a 24 hr leakage rate, ADD the total gallons of RMW AND Boric Acid. THEN divide by 1440 minutes.

NIA if a diversion occurred within the day. The operator determines that this step is NOT required yet. Evaluation on this JPM is complete. NU REG 1021, Revision 9 Appendix C Page 9 of 10 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2014 Admin -JPM A2 SRO Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiner's Signature: Date: 2014 Admin -JPM A2 SRO NU REG 1021, Revision 9 Appendix C INITIAL CONDITIONS: INITIATING CUE: Form ES-C-1 JPM CUE SHEET

• The plant is at 1 OOOfc:, power with 40 gpm Letdown flow.
• The VCT Level point on the PPCS is OOS.
• At 1020 the VCT level was 25% when the HCO started the Day Shift RCS Leakage Monitoring Surveillance, intending to monitor for about 4 hours.
• At 1125 a VCT Level instrument failure occurred which l&C corrected and restored to operation within 1 O minutes.
• It is currently 1415 and an Auto Makeup has just been completed.
• No VCT Diversion occurred.
• The ULR tool is temporarily OOS.
• The current Integrator Readings are as follows:
• RMW Reading:

240

• BA Reading 21.0
• A check of the Identified Area Leakage has not changed since the leakrate determinations were recorded.
• The CRS directed you to record the data for the recent Auto Makeup on Attachment 3, RCS Leakage Surveillance Record, AND determine the current RCS Leakrate.
• Identify Tech Spec L.COs, if any, that have been exceeded; and if any LCOs are exceeded, identify any required Tech Spec ACTION. NUREG 1021, Revision 9

RCS LEAKAGE SURVEILLANCE RECORD INSTRUCTIONS S-12.4 Revision 05800 Page 22of29 c t 3 3 39 a egory .* Reviewed ---Time RMW BA Reading Reading "&I 'L --'2300 1< ,,.., lo7.o \\25 \"?DO 0 1'2.'2.$ 10.i.,( Attachment 3, RCS Leakage Surveillance Record S ctl "A" e o'n System Inventory Reason Gallons I dent Unidentd AD Diversion Added Calculated Leak Leak B AID BA+RMW Leak Rate Rate Rate --

• 07""Z-.o6g -co<{ Alo /J JS CjVCt '( A./o IV 15 A. N 11.5. '-I ULRTool Updated Page 1of2 Date* / z.{2. / d.-Day: 7'-.oeflv RMW Integrator 2400 HRS. 0000 HRS. 0 Total Gallons:

BA Integrator 2400 HRS. 0000 HRS. c Total Gallons: 24 Hr Leakage Rate, If NO Diversion Total RMW+BA= ___ gpm 1440 NOTE: IF Reactor Makeup Rate Increases by 0.25 gpm Over The Normal, REFER to S-12.2. NOTE: IF unidentified leak rate(ULR) meets criteris. listed in 6.1.6, REFER to S-12.2, Operator Action In The Event Of Indication Of Significant Increase In Leakage Remarks: O.-verhJ I ,.hJOu/*1 r 15 <::..c.eo-..Oc:. tl'2..<.. Time Night Shift Location G.P.M. '2ovo .ool 21 t>O c f'i..I\.

• Ol,'7 Remarks:

Section "C" Containment Condensate Collectors Total Fluid Dump Dump Released to Sump A: Time lime 1090 1091 (#Dumps) (Gal/Dump) oisg co2o 06'28 1090 L_) 2.57 = L_) o.'.3.S:l 1091 L_) 2.45 = L_) o7"2.7 1092 L_) 2.42 = L_) 11{ 1093 (__)3.05 = L_) TOTAL ---TOTAL= G.P.M. 1440 Remarks: Sec:tion "B" Leakage From Identified Areas Time Location 0'100 'Rccrr ,,...,....... <!.. Pt.lt. RCP Standoioe Time RCPA/B Dump Dump Dump Time lime Time 1092 1093 ( ) o'75"3 t:>No/ o3S3 o-,,_.., Day Shift Remarks: G.P.M. .ool .o"l'-1 Aux. Bldo. Sumo SumoTk Time Section "D" -Containment Sump Pump Actuations

1. Last Calculated Leak Rate in gpm. Date: 2.Last Pump Actuation TIME: 3.Present Pump Dale: Actuation TIME: 4.New Interval In Hours 5.GPM = Note 1 OR 2 STEP4 x (0.0167)

Remarks: PZR ReliefTank Temp Press Level .oot:. to.ho},., 2o/8 NOTE 1: Pump "A" 98 Gals/Actuation, Pump "B" 140 Gals/Actuation NOTE 2: /1 Sump Level in gallons (120gallft}(PPCS pt. L2039 or L2044) NOTE 3: IF sump leakage >0.02 gpm increase

occurred, Refer to S-12.2 RCS LEAKAGE SURVEILLANCE RECORD INSTRUCTIONS Attachment 3, RCS Leakage Surveillance Record, (Continued)

PPCS POINTS Yesterdays Carry Over 0700-1900 1900-0700 Section "E" Containment Temperature: q<>. 28 {00.80 NOTE 1 -Tech Spec limit is$ 125° F (SR 3.6.5.1 ), Refer to step 6.5 for Admin Limits NOTE 2 -Admin Limit is from -0.2 TO+ 0.5 PSIG., Refer to 0-11 for maintaining pressure. NOTE 3 -Tech Spec limit 2-2 psig and s1 psig (SR 3.6.4.1 ). AVG. TEMP SEE NOTE 1 9Z.77 S-12.4 Revision 05800 Page 23 of 29 Page 2 of 2 Containment Pressure Pl-944 SEE Note 2 SEE Note 3 SEE Note 4 0.3S C.'-15 HCO NOTE 4 -Refer to 0-11 for procedural guidance to obtain a containment pressure reading via an alternate path when Pl-944 out-of-service. Remarks: Section "F" Remarks: Containment Particulates -R11 (PPCS pt. R11H12) 1. Yesterday's 2400 hr avg __

2. Today's 1200 hr avg 2.o S 3. Difference Step 2 -Step 1 = ::(o!. -'20 S or (AM) z,.--,,,::.

4. Today's 1200 hr avg __ ...... _= __ _ ______ cpm DEC 5. Today's 2400 hr avg _,_/_.q_'9.,__

__ _ 6. Difference Step 5 -Step 4 = [ t:/'t -2o5 ______ cpmlNC or/ ____ b ___ cpm DEC (PM) 7. G.P.M Leakage= (cpm -background cpm) (1.8 E -7) µC/CC Krypton 88 In Reactor Coolant = ( 111 -"2..00 ) (1.8 E-7) = __ D __ gpm ( '3. ,,, l:--NOTE: If Containment Particulate Average Increases by 2000 cpm Over The Last Average, Refer To S-12.2 Section "G" Containment Gas -R12 (PPCS pt. R12H12) 1.Yesterday's 2400 hr avg 2.Today's 1200 hr avg 3'-1.S 3-<-((,. 3.Difference Step 2 -Step 1 (100) = ( 3 '1 -3 'i S ) (100) = 0 % INC Step 1 3'1s or 4.Today's 1200 HR AVG 3'i"' 5.Today's 2400 HR AVG 6.Difference Step 5 -Step 4 (100) = ( __ -'.3=-'c./'--'{."'--) (100) = Step4 3'i.4. . ____ %DEC ____ %INC or ___ __ % DEC NOTE:-If Containment Gas Average increases by 20% over Last Average, Refer To S-12.2 SHIFT 1 SHIFT 2 (AM) (PM) Remarks: ,i;', RCS LEAKAGE SURVEILLANCE RECORD INSTRUCTIONS Revision 05800 Page 22of29 Attachment 3, RCS Surveillance Record Page 1of2 Date: 17.. /z /11 Category 3.3.39 Section "A" Reviewed ---System Inventory Day: 7u.o..Jr.. ./ Reason Gallons ldent Unidentd RMW Integrator Time RMW BA AD Diversion Added Calculated Leak Leak ULR Tool Reading Reading Leak Rate Updated BAIO BA+ RMW Rate Rate 2400 HRS. 0000 HRS. 0 1200-'21L./Z. --*--6\/cT "07z. . oo'{ Total Gallons: 2.300 \S 0 l\/D N 1$ io'2..o -----L>\Jc:T BA Integrator \\'LS y 2400 HRS. A/o N 15 0000 HRS. 0 \ '2..0t-, 3o C) Total Gallons: l2.Z ') I 3:>5 10.Y /\ rJ 11.5. <-/ 24 Hr Leakage Rate, If NO /4/t!{ 2'-/D 2/ A N 1/5.e:,. Diversion JU_j*l'{l5

---

A\JCT Lo-'5"1

• I. oof... Total RMW+BA= ___ gpm 1440 NOTE: IF Reactor Makeup Rate Increases by 0.25 gpm Over The Normal, REFER to S-1:2.2.

NOTE: IF unidentified leak rate(ULR) meets c?!ria listed in 6.1.6, REFER to S-12.2, Operator Action In The Event Of Indication Of Significant Increase In Leakage Remarks: Divc:.,.h.1 \ ,. \5. "-", .... J.s .., \. H .., <. Time Night Shift Location G.P.M. 2,..,..,,. '21-.0T" .co\ Z100 C.VL\\

• 06"1 Remarks:

Section "C" Containment Condensate Collectors Total Fluid Dump Dump Released to Sum[! A: Time Time 1090 1091 (#Dumps) (Gal/Dump) OC>U> 1090 L__) 2.57 = L__) (>(:."ls o?>S> 1091 L__) 2.45 = L__) 67?..7 1092 L__) 2.42 = L__) 111"( 1093 L__) 3.05 = L__) TOTAL ---TOTAL= G.P.M. 1440 Remarks: Section "El" Leakage From Identified Areas Time Location 6"in6 tll:.01-1--- RCP Standoioe Time RCPA/B Dump Dump Dump Time Time Time 1092 1093 ( ) 01"{'( Day Shift Remarks: G.P.M. *OOl -0 "11.4 Aux. Bldg. Sumo SumoTk Time Section "D" -Containment Sump Pump Actuations

1. Last Calculated Leak Rate in gpm. Date: 2.Last Pump Actuation TIME: PZR ReliefTank Temo Press Level .06(,

2011r I 3.Present Pump Date: Actuation TIME: 4.New Interval In Hours 5.GPM = Note 1 OR 2 STEP4 X(0.0167) Remarks: NOTE 1: Pump "A" 98 Gals/Actuation, Pump "B" 140 Gals/Actuation NOTE 2: Ii Sump Level in gallons (120gal/ft)(PPCS pt. L2039 or L2044) NOTE 3: IF sump leakage >0.02 gpm increase

occurred, Refer to S-12.2 Appendix C Job Performance Measure Worksheet Form ES-C-1 JPM A3 SRO 2014 Admin -JPM A3 SRO (REV_091514)

NUREG 1021, Revision 9 Appendix C Page 2 of 7 Job Performance Measure Worksheet Facility: Ginna Task No.: Task Title: Evaluate the Impact of R-14 Failure JPM No.: on a Planned Gaseous Decay Tank Release KIA

Reference:

2.3.15 (3.1) Form ES-C-1 2014 Admin -JPM A3 SRO 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 or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Provide Candidate with Initial Conditions/Cue (Last Page of this JPM). 2014 Admin -JPM A3 SRO NUREG 1021, Revision 9 Appendix C Task Standard: Page 3 of 7 Form ES-C-1 Job Performance Measure Worksheet The operator will declare R-14 inoperable, and determine that (1) going releases (i.e. ventilation) may continue provided grab samples are taken and analyzed for isotopic activity at least once per 8 hours, that (2) at least one of either R-14 or R-14A5 must be restored to OPERABLE status within 30 days or it must be explained in the next Annual Radioactive Effluent Release Report, and that (3) the earliest time that the A Gas Decay Tank release can be initiated is 2 hours from now when the maintenance on R-14A is completed and the instrument is declared

OPERABLE, and ONLY if at least two independent samples of the tank's contents are analyzed, and at least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup. Required Materials:

Standard Procedure Reference Carts must be available to the operator General

References:

S-4.2.5, Release of Gas Decay Tank, Rev 01902 Handouts: Time Critical Task: Validation Time: Offsite Dose Calculation Manual (ODCM), Rev. 29, section 3.2 (Gaseous Effluent Monitors), Table 3.2-1 None NO 16 minutes 2014 Admin -JPM A3 SRO NUREG 1021, Revision 9 Appendix C Page 4 of 7 PERFORMANCE llNFORMATION Form ES-C-1 (Denote Critical Steps with a .YJ Provide Candidate with Initial Conditions/Cue (Last Page of this JPM). START TIME: Performance Step: 1 Standard: EXAMINER NOTE: Comment: 2014 Admin -JPM A3 SRO The SM has directed you to determine the required actions based on the failure of R-14. The operator declares H-14 inoperable. The operator reviews C.3.2 of the ODCM and Table 3.2-1. The operator recognizes that Plant Ventilation c is NOT met on Table 3.2-1 (i.e. currently 1 less than the minimum), and that ACTION 2 of Table 3.2-*1 is required. The operator determines that If the number of OPERABLE channels is less than required by the Minimum Channels OPERABLE requirement (i.e. 1 ), effluent releases via this pathway may continue provided grab samples are taken and analyzed for isotopic activity at least once per 8 hours. The operator recognizes that C.3.2 is NOT met because Plant Ventilation c is NOT met on Table 3.2-1, and identifies that at least one of either R-14 or R-14A5 must be restored to OPERABLE status within 30 days or, if not, explain in the next Annual Radioactive Effluent Release Report, pursuant to Section 6.2 of the ODCM, why this inoperability was not corrected in a timely manner. .. ..... "'h""*"'*

• ""'""

.* , *. The operator identifies that: at least one of either R-14 or R-14A5 must be restored to OPERABLE status within 30 days or it must be explained in the next Annual Radioactive Effluent Release Report. The actions may be identified in any order. NUREG 1021, Revision 9 Appendix C Performance Step: 2 Standard: EXAMINER NOTE: EXAMINER NOTE: Comment: Terminating Cue: STOP TIME: 2014 Admin -JPM A3 SRO Page 5 of 7 PERFORMANCE INFORMATION Form ES-C-1 Determine the earliest tim1e at which the A Gas Decay Tank release can start, and to identify any actions that will be required to start the release. The operator reviews C.3.2 of the ODCM and Table 3.2-1, and determines that since the A Gas Decay Tank release is NOT in progress, it cannot be initiated until at least two actions are taken:

• Restore R-14A5 to OPERABLE status (2 hours away) AND
• At least two independent samples of the tank's contents are analyzed, and at least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup. The operator must correctly interpret Note (b) of Table 3.2-1, which will not permit the initiation of the Gas Decay Tank Release until at least R-*14A5 is OPERABLE and two independent samples have been independently analyzed.

Otherwise, R-14 must be restored (4 hours away). IF R-14A is OPERABLE, R-14A5 is also OPERABLE. Evaluation on this JPM is complete. NUREG 1021, Revision 9 Appendix C Page Ei of 7 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2014 Admin -JPM A3 SRO Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiner's Signature: Date: 2014 Admin -JPM A3 SRO NUREG 1021, Revision 9 Appendix C INITIAL CONDITIONS: INITIATING CUE: Form ES-C-1 JPM CUE SHEET

• The plant is at 100% power.
• An A Gas Decay Tank release is being planned.
• The HCO reports that R-14A, Plant Vent Gas, is de-energized and declared inoperable (A-52.12 submitted) for preventative maintenance that will require 2 more hours, and must be completed before it can be returned to service.
• The HCO reports that R-14, Plant Vent Gas, has just failed LOW. l&C has indicated that it will take at least four hours to troubleshoot and correct the failure.

The SM has directed you to determine the required actions concerning the Aux Bldg ventilation release based on the additional failure of R-14. AND The SM has directed you to determine the earliest time at which the A Gas Decay Tank release can start, and to identify any actions that will be required to start the release. NU REG 1021, Revision 9 Appendix C Job Performance Measure Worksheet. Form ES-C-1 JPM A4b SRO NOTE: This JPM is intended to be used with Simulator Scenario N2014-301-2 2014 Admin -JPM A4b SRO (REV _100414) NUREG 1021, Revision 9 Appendix C Facility: Task Title: Page 2of7 Form ES-C-1 Job Performance Measure Worksheet Ginna Classify an Emergency Event Task No.: JPM No.: 2014 Admin -JPM A4b SRO KIA

Reference:

2.4.41 (4.6) 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. Provide Candidate with Initial Conditions/Cue (Last Page of this JPM). Initial Conditions: Initiating. Cue: The sequence of events that you have just perf?rmed on the recently completed Simulator Scenario must be evaluated for any Emergency Classifications.

• Determine the HIGHESTEmergency Classification that would have been made during the recently completed scenario.
• Prepare EP-Form-ALL25, GNP NY STATE RADIOLOGICAL EMERGENCY DATA FORM (Part 1), for notification by the Communicator.

A PORTION OF THIS JPM IS TIME CRITICAL. Task Standard: The operator will determine that the highest Emergency Classification that must be made throughout this scenario was an ALERT based on FA 1.1, HA2.1 and/or SA3.1; and complete EP-Form-ALL25 in accordance with the provided KEY, within 14 minutes. Required Materials: None General

References:

EPIP-1-0, Ginna Station Event and Classification, Rev 04900 2014 Admin -JPM A4b SRO NUREG 1021, Revision 9 Appendix C Handouts: Time Critical Task: Validation Time: Page 3 of 7 Form ES-C-1 Job Performance Measure Worksheet EP-Form-ALL25 RO, GNP NY STATE RADIOLOGICAL EMERGENCY DATA FORM (PART 1) None YES (Once the classification is made, the form must be completed within 14 Minutes) 20 minutes 2014 Admin -JPM A4b SRO NUREG 1021, Revision 9 Appendix C Page 4 of/' PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with a '1) START TIME: '1 Performance Step: 1 Standard: EXAMINER NOTE: Comment: 2014 Admin -JPM A4b SRO Determine the HIGHEST Emergency Classification that would have been made during the recently completed scenario. [ '1J The' Operator uses. EPI or the Wall Charts and deterrninesthat*an ALERT must be declared based on FA 1.1 (AN'(,'1oss'8r

\NYpofof)tial lossof either,Fuel.,Clad or RCS

[RED path condition exists Integrity])) OR [.,,/l The. pperaforuses EPIP-1-0 or the Wall, Charts and bedeelared on HA2.1 (Fire in ErrHER:Visible. damage.toANY or compor:tent within ANY Table H.:t area.OR .Contrp'f Room indicatioh of degraded. performance of ANY *satetY.-refated 'structure, system, or component within ANY Table f;-1 *area, [Intermediate Building]) OR NJ The dperatoruses Ef:>I or the Wall Charts and determines that an ALERT must be declared based on SA3.1 (Ari* acit8matidfrip; fc:l as-. , --indicated> by reactorpOwer > 5%:ANDManual ... actions taken' aHhe console successfully shut down the reactbr;asitidicatecFby reactor power< 5%) Only one of the classifications above must be made to satisfy the critical natur1e of this Step. NU REG 1021, Revision 9 Appendix C "\/ Performance Step: 2 Standard: Comment: Terminating Cue: STOP TIME: 2014 Admin -JPM A4b SRO Page 5 of "7 PERFORMANCE INFORMATION TIME CRITICAL START TIME: Form ES-C-1 Prepare EP-Form-ALL25, GNP NY STATE RADIOLOGICAL EMERGENCY DATA FORM (Part 1), for notification by the Communicator. [ "\/JJhe operator COMPLETES EP-Form-ALL25 in accordance with the provided. KEY. Evaluation on this JPM is complete. TIME CRITICAL STOP TIME: NUREG 1021, Revision 9 Appendix C Page 6 of 7 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2014 Admin -JPM A4b SRO Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiner's Signature: Date: 2014 Admin -JPM A4b SRO NUREG 1021, Revision 9 Appendix C INITIAL CONDITIONS: INITIATING CUE: Form ES-C-1 JPM CUE SHEET The sequence of events that you have just performed on the recently completed Simulator Scenario must be evaluated for any Emergency Classifications.

• Determine the HIGHEST Emergency Classification that would have been made durin9 the recently completed scenario.
• Prepare EP-Form-ALL25, GNP NY STATE RADIOLOGICAL EMERGENCY DATA FORM (Part 1), for notification by the Communicator.

A PORTION OF THIS JPM IS TIME CRITICAL. NUREG 1021, Revision 9 GNP NY STATE RADIOLOGICAL EMERGENCY DATA FORM {PART 1) EP-Form-ALL25 RO 0* 0* 0* 0* 0* RECS Message Number: "This is Ginna Station. Please stand by for roll call. "New York State" D "Monroe County" D "Wayne County" D 1. Message transmitted at: Date Time:---- Via: A. RECS B. Other 2. This is: A. An Actual Event &An Exercise

3. Classification:

.A. UNUSUAL EVENT {B.)o.LERT C. SITE AREA EMERGENCY EMERGENCY E. EMERGENCY TERMINATED F. RECOVERY

4. Classification Time: This Emergency Classification declared at: 5. Release of Radioactive Materials due to the Classified Evirnt: (A:) No Release Y. Release BELOW federal limits D to atmosphere D to water C. Release ABOVE federal limits D to atmosphere D to water D. Unmonitored release requiring evaluation

6. Protective Actions RECOMMENDATIONS:

@No need for Protective Actions outside the site boundary B. EVACUATE and implement the Kl plan for the following ERPA's (all remaining ERPA's to monitor the Emergency Alert System) W1 W2 W3 W4 WS W6 W7 M1 M2 M3 M4 MS C. SHELTER-IN-PLACE and implement the Kl plan for the following ERPA's (all remaining ERPA's to monitor the Emergency Alert System) M6 M7 MS M9 W1 W2 W3 W4 WS W6 W7 M1 M2 M3 M4 MS M6 M7 MS M9 7. EAL Number: --EAL Number \=(\-\,\..r i{ Brief Event Description and other significant information I l ,,:,_, 0* 8.ReactorStatus: /:::'\ _ 1 \\,,.,...l. o\= . A. Operational( ts:}Shutdown Time: (subcritical) O* 9. Wind Speed: A. 'f\)C S Miles/hour at elevation feet 0* 0* 10. Wind Direction: From: at elevation: _22£_feet

11. Stability Class: UNSTABLE NEUTRAL STABLE LlT t{)cs -250 ft temp 33 ft temp Alpha I Bravo I Echo I Foxtrot I Golf

---

1----------2.17 -1.95

-1.74 -0.65 +1.74 +4.77 12. Reported by: Name: Area Code: Number: *check box if information has changed since last form was transmitted. "Please stand by for roll call: New York State copy?" D "Monroe County copy?" D "Wayne County copy?" D FOR GINNA USE ONLY: Time Prepared: ,..-, Time Approved: Completed form sent to EP Director Prepared By: i"\f!.:.r>r\e Approved By: WAYNE COUNTY USE ONLY: Routing: _ALL _Dose Assess Calculator _RDO _Ginna Tech Rep _Field Team Coord. _Plotter _NYS Rad Health _Ops Officer _NYS Health (Ops room)_ Director -PIO MONROE COUNTY USE ONLY: Distribution:

1. Command Room (OEP Administrator)

2. EOC (Qnerations Desk) 3. Assessment Area (Rad Officer, Health, Field Team Coordinator.

Comguter Ogerations, Tech Reg) 4. Evaluator S. File -... -.... .. -J( <: Page 1 of 2 \ -\ t.,£.\<". \ , -\:*1'.'.:*"'-e",-.::> Appendix C Job Performance Measure Worksheet Form ES-C-1 JPM A4c SRO NOTE: This JPM is intended to be used with Simulator Scenario N2014-301-3 2014 Admin -JPM A4c SRO (REV _091514) NUREG 1021, Revision 9 Appendix C Facility: Task Title: Page 2 of 6 Form ES-C-1. Job Performance Measure Worksheet Ginna Classify an Emergency Event Task No.: JPM No.: 2014 Admin -JPM A4c SRO K/A

Reference:

2.4.41 (4.6) 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. Provide Candidate with Initial Conditions/Cue (Last Page of this JPM). Initial Conditions: Initiating Cue: The sequence th.at you have just performed on the recently corripletedSimurat6rScenario must be evaluatedforany Emergency Classifications.

• *
• Determine the HIGHEST Emergency Classification that would have been made during the recently completed scenario.
• GNP NY STATE RADIOLOGICAL EMERGENCY DATA FORM (Part 1), for notification by the Co1nrriunicator.

.. APORTION OF THIS JPM IS TIME CRITICAL.. Task Standard: The operator will determine that the highest Emergency Classification that must be made throughout this scenario was a SITE AREA EMERGENCY based on FS1 .1; and complete EP-Form-ALL25 in accordance with the provided KEY, within 14 minutes. Required Materials: None General

References:

EPIP-1-0, Ginna Station Event and Classification, Rev 04900 2014 Admin -JPM A4c SRO NUREG 1021, Revision 9 Appendix C Handouts: Time Critical Task: Validation Time: Page 3 of E> Form ES-C-1 Job Performance Measure Worksheet EP-Form-ALL25 RO, GNP NY STATE RADIOLOGICAL EMERGENCY DATA FORM (PART 1) None YES (Once the classification is made, the form must be completed within 14 Minutes) 20 minutes 2014 Admin -JPM A4c SRO NUREG 1021, Revision 9 Appendix C Page 4 of 6 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with a '1) START TIME: '1 Performance Step: 1 -\ Standard: Comment: ../ Performance Step: 2 Standard: Comment: Terminating Cue: STOP TIME: 2014 Admin -JPM A4c SRO Determine the HIGHEs1: Emergency Classification that would have been made during the recently completed scenario. [ ../f J"he;pperafor uses E.PI p:. 1 :.o. or the Wali Charts and SLTEAREA.EMERGENCYmustbe declared base(j ob.F=s1;1,et.oss or\potential lqss of. ANY twcrbarrJersr TIME CRITICAL START TIME: Prepare EP-Form-ALL25, GNP NY STATE RADIOLOGICAL EMERGENCY DATA FORM (Part 1), for notification by the Communicator. EP-:Forni-ALL25 in accordance

provided, KEY: Evaluation on this JPM is complete.

TIME CRITICAL STOP TIME: NU REG 1021, Revision 9 Appendix C Page 5 of 6 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2014 Admin -JPM A4c SRO Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiner's Signature: Date: 2014 Admin -JPM A4c SRO NUREG 1021, Revision 9 Appendix C INITIAL CONDITIONS: INITIATING CUE: Form ES-C-1 JPM CUE SHEET The sequence of events that you have just performed on the recently completed Simulator Scenario must be evaluated for any Emergency Classifications.

• Determine the HIGHEST Emergency Classification that would have been made during the recently completed scenario.
• Prepare EP-Form-ALL25, GNP NY STATE RADIOLOGICAL EMERGENCY DATA FORM (Part 1), for notification by the Communicator.

A PORTION OF THIS JPM IS TIME CRITICAL. NUREG 1021, Revision 9 (Y\ GNP NY STATE RADIOLOGICAL EMERGENCY DATA FORM (PART 1) EP-Form-ALL25 RO D* D* D* D* D* D* D* D* D* RECS Message "This is Ginna Station. Please stand by for roll call. "New York State" D "Monroe County" D "Wayne County" D 1. Message transmitted at: 2. This is: @An Exercise Date Time: A. An Actual Event Via: A. RECS B. Other 3. Classification: A. UNUSUAL EVENT GSITE AREA EMERGENCY E. EMERGENCY TERMINATED B. ALERT GENERAL EMERGENCY F. RECOVERY

4. Classification Time: Time\; rt\<l \o.s:;,1 O* This Emergency Classification declared at: Date T D,!c:) ... 'f c.:+

of Radioactive Materials due to the Classified Event: A. No Release B. Release BELOW federal limits D to atmosphere D to water c. Release ABOVE federal limits D to atmosphere D to water D. Unmonitored release requiring evaluation

6. Protective Actions RECOMMENDATIONS:

CA°)No need for Protective Actions outside the site boundary B. EVACUATE and implement the Kl plan for the following ERP A's (all remaining ERPA's to monitor the Emergency Alert System) W1 W2 W3 W4 W5 W6 W7 M1 M2 M3 M4 M5 M6 M7 M8 M9 c. SHELTER-IN-PLACE and implement the Kl plan for the following ERPA's (all remaining ERPA's to monitor the Emergency Alert System) W1 W2 W3 W4 W5 W6 W7 M1 M2 M3 M4 M5 M6 M7 MB M9 7. EAL Number: , Brief Event Description and other significant information !I EAL Number I

• -> .\ *,c._' \ 0 c:;1 y:: '1£_ <S, \,, i::t !I F;;: \, I '{ 0 I e'*"\u\VC"-\

.;<-\.f)

8. Reactor Status: I k.t....;.{-Jou..i!"..i Operational (8) Shutdown Date: T c,(c. 'I Time: \,f'V\C.

A. (subcritical)

9. Wind Speed: -A._tQ_ f._ Miles/hour at feet 10. Wind Direction:

From: \"\)C..; degrees at elevation: feet 11. Stability Class: UNSTABLE NEUTRAL STABLE Lff ?K s -f' i>C. $. =Ar Alpha / Bravo / Charlie / I Echo / Foxtrot I Golf -----------/----------/-------------------!------------------/-----------

---

/---------

250 ft temp 33 ft temp -2.17 -1.95 -1.74 -0.65 +1.74 +4.77 12. Reported by: Name: Area Code: Number:

• check box if information has changed since last form was transmitted.

"Please stand by for roll call: New York State copy?" D "Monroe County copy?" D "Wayne County copy?" 0 FOR GINNA USE ONLY: Time Prepared: '. Prepared By: Time Approved: Approved By: Completed form sent to EP Director I WAYNE COUNTY USE ONLY: [ Routing: _ALL _Dose Assess Calculator _ADO _Ginna Tech Rep _Field Team Coard. _Plotter i NYS Rad Health Ops Officer NYS Health (Ops room) Director PIO 1-----I MONROE COUNTY USE ONLY: Distribution:

1. Command Room (OEP Administrator)

2. EOC (Operations Desk) I 3. Assessment Area (Rad Officer.

Health. Field Team Coordinator, Computer Operations, Tech Rep) 4. Evaluator

5. File I Page 1 of 2 Appendix C Job Performance Measure Worksheet Form ES-C-1 JPM A4d SRO NOTE: This JPM is intended to be used with Simulator Scenario N2014-301-4 2014 Admin -JPM A4d SRO (REV_091514)

NUREG 1021, Revision 9 Appendix C Facility: Task Title: Page 2 of 6 Form ES-C-1 Job Performance Measure Worksheet Ginna Classify an Emergency Event Task No.: JPM No.: 2014 Admin -JPM A4d SRO KIA

Reference:

2.4.41 (4.6) 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. Provide Candidate with Initial Conditions/Cue (Last Page of this JPM). Initial Conditions: Initiating Cue: The sequence of events that you have just performed on the recently completed Simulator Scenario must be evaluated for any Emergency Classifications.

• Determine the HIGHEST Emergency Classification that would have been made during the recently completed scenario.
• Prepare EP-Form-ALL25, GNP NY STATE RADIOLOGICAL EMERGENCY DATA FORM (Part 1), for notification by the Communicator.
• A PORTION OF THIS JPM IS TIME CRITICAL.

Task Standard: The operator will determine that the highest Emergency Classification that must be made throughout this scenario was an ALERT based on FA 1.1; and complete EP-Form-ALL25 in accordance with the provided KEY, within 14 minutes. Required Materials: None General

References:

EPIP-1-0, Ginna Station Event and Classification, Rev 04900 2014 Admin -JPM A4d SRO NUREG 1021, Revision 9 Appendix C Handouts: Time Critical Task: Validation Time: Page 3of6 Form ES-C-1 Job Performance Mea1sure Worksheet EP-Form-ALL25 RO, GNP NY STATE RADIOLOGICAL EMERGENCY DATA FORM (PART 1) None YES (Once the classification is made, the form must be completed within 14 Minutes) 20 minutes 2014 Admin -JPM A4d SRO NUREG 1021, Revision 9 Appendix C Page 4 of 6 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with a -.J) START TIME: '\/ Performance Step: 1 Standard: Comment: -,J Performance Step: 2 Standard: Comment: Terminating Cue: STOP TIME: 2014 Admin -JPM A4d SRO Determine the HIGHEST Emergency Classification that would have been made during the recently completed scenario. [-VJ Tlie /operator uses EPIP-1-0 'or t:he Wall Charts and determines that* ari ALERT must be declared based* on, FA 1.1 (ANY loss orANY potential loss of either Fuel Clad or RCS (Table F-1)). TIME CRITICAL START TIME: Prepare EP-Form-ALL25, GNP NY STATE RADIOLOGICAL EMERGENCY DATA FORM (Part 1), for notification by the Communicator. HJ The operator COMPLETES EP-Form-ALL25 in. accordance with the provided KEY. Evaluation on this JPM is complete. TIME CRITICAL STOP TIME: NUREG 1021, Revision 9 Appendix C Page 5 of 6 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2014 Admin -JPM A4d SRO Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiner's Signature: Date: 2014 Admin -JPM A4d SRO NUREG 1021, Revision 9 Appendix C INITIAL CONDITIONS: INITIATING CUE: Form ES-C-1 JPM CUE SHEET The sequence of events that you have just performed on the recently completed Simulator Scenario must be evaluated for any Emergency Classifications.

• Determine the HIGHEST Emergency Classification that would have been made during the recently completed scenario.
• Prepare EP-Form-ALL25, GNP NY STATE RADIOLOGICAL EMERGENCY DATA FORM (Part 1), for notification by the Communicator.

A PORTION OF THIS JPM IS TIME CRITICAL. NUREG 1021, Revision 9 GNP NY STATE RADIOLOGICAL EMERGENCY DATA FORM (PART 1) EP-Form-ALL25 RO 0* 0* 0* 0* 0* 0* 0* 0* 0* RECS Message Number: ______ _ "This is Ginna Station. Please stand by for roll call. "New York State*" 0 "Monroe County 0 "Wayne County" 0 1. Message transmitted at: 2. This is: @An Exercise Date Time: A. An Actual Event Via: A. RECS B. Other 3. Classification: A. UNUSUAL EVENT C. SITE AREA EMERGENCY E. EMERGENCY TERMINATED (8.)ALERT D. GENERALEMERGENCY F. RECOVERY

4. Classification Time: " n.

This Emergency Classification declared at: Date\Ci:::.h-t-Time *-1,me j "' v 5. Release of Radioactive Materials due to the Classified Event: Cl No Release Release BELOW federal limits 0 to atmosphere [J to water c. Release ABOVE federal limits 0 to atmosphere [J to water D. Unmonitored release requiring evaluation 6'(Jotective Actions RECOMMENDATIONS: , AJ No need for Protective Actions outside the site boundary t3. EVACUATE and implement the Kl plan for the following ERPA's (all remaining ERPA's to monitor the Emergency Alert System) W1 W2 W3 W4 ws W6 W7 M1 M2 M3 M4 MS M6 M7 MB M9 c. SHEL TEA-IN-PLACE and implement the Kl plan for the following ERPA's (all remaining ERPA's to monitor the Emergency Alert System) W1 W2 W3 W4 W5 W6 W7 Mi M2 M3 M4 M5 M6 M7 MB M9 7. EAL Number: . Brief Eve.nt DescriP.tion ?nd other significant information-\ -\LC EAL Number \ ..\e ,> \e'. cc.. "\ . , I I \ b-'\ \c,f-,i;. o*'r S

8. Reactor Status: w \\:.<< D-s;:. f..L., .).-t.Jo

'-.0 ,_.) / A. Operational Shutdown Time: (subcritical)

9. Wind Speed: 33 A. 1'\>C.S Miles/hour at elevation feet 10. Wind Direction:

From:'??C 5 degrees at elevation: 33 fe13t 11 .. Stability Class: UNSTABLE NSJ.=IBAL STABLE =Jll Alpho I Bravo I Choclie '\ I Eoho I Foxtrot I Goll -----------1----------1----------

---

---

1--

---

250 ft temp 33 ft temp -2.17 -1.95 -1.7 ---0.65 +1.74 +4.77 12. Reported by: Name: Area Code: Number: *check box if information has changed since last form was transmitted.

"Please stand by for roll call: New York State copy?" 0 "Monroe County copy?" D "Wayne County copy?" D FOR GINNA USE ONLY: Time Prepared: Time Approved: Completed form sent to EP Director Prepared By: Approved By: WAYNE COUNTY USE ONLY: Routing: _ALL _Dose Assess Calculator _RDO _Ginna Tech Rep _Field Team Coard. _Plotter _NYS Rad Health _Ops Officer _NYS Health (Ops room) _Director _PIO MONROE COUNTY USE ONLY: Distribution:

1. Command Room (OEP Administrator)

2. EOC (Operations Desk) 3. Assessment Area (Rad Officer Health. Field Team Coordinator.

Computer Operations. Tech Rep) 4. Evaluator

5. File Page 1 of 2 Appendix C Job Performance Measure Worksheet Form ES-C-1 JPM A4e SRO NOTE: This JPM is intended to be used with Simulator Scenario N2014-301-5 2014 Admin -JPM A4e SRO (REV_ 100414) NUREG 1021, Revision 9

Appendix C Facility: Task Title: Page 2 of 6 Form ES-C-1 Job Performance Measure Worksheet Ginna Classify an Emergency Event Task No.: JPM No.: 2014 Admin -JPM A4e SRO KIA

Reference:

2.4.41 (4.6) 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. Provide Candidate with Initial Conditions/Cue (Last Page of this JPM). Initial Conditions: Initiating Cue: The .sequence of events that you have just performed on the recently completed Simulator Scenario must be evaluated for any Emergency Classifications.

• Determine the HIGHEST Emergency Classification that would have been made during the recently completed scenario.
• Prepare EP-Form-ALL25, GNP NY STATE RADIOLOGICAL EMERGENCY DATA FORM (Part 1), for notification by the Communicator.

-. _, A PORTION OF THIS JPM IS TIME CRITICAL. Task Standard: The operator will determine that the highest Emergency Classification that must be made throughout this scenario was a SITE AREA EMERGENCY based on FS1 .1; and complete EP-Form-ALL25 in accordance with the provided KEY, within 14 minutes. Required Materials: None General

References:

EPIP-1-0, Ginna Station Event and Classification, Rev 04900 2014 Admin -JPM A4e SRO NUREG 1021, Revision 9 Appendix C Handouts: Time Critical Task: Validation Time: Page 3 of 6 Form ES-C-1 Job Performance Measure Worksheet EP-Form-ALL25 RO, GNP NY STATE RADIOLOGICAL EMERGENCY DATA FORM (PART 1) None YES (Once the classification is made, the form must be completed within 14 Minutes) 20 minutes 2014 Admin -JPM A4e SRO NUREG 1021, Revision 9 Appendix C Page 4 of 6 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with a "1) START TIME: ,/ Performance Step: 1 Standard: Comment: ,/ Performance Step: 2 Standard: Comment: Terminating Cue: STOP TIME: 2014 Admin -JPM A4e SRO Determine the HIGHEST Emergency Classification that would have been made during the recently completed scenario. HJ The operator uses EPIP-1-CJofthe V\/ait Charts and determines that a SITE AREA EMERGENCY must be declared based on FS1.1 (Loss or potential loss of ANY two .barriers) TIME CRITICAL START TIME: Prepare EP-Form-ALL25, GNP NY STATE RADIOLOGICAL EMERGENCY DATA FORM (Part 1), for notification by the Communicator. [-VJ The operator COMPLETES EP-Form-ALL25 in accordance with the provided KEY: Evaluation on this JPM is complete. TIME CRITICAL STOP TIME: NU REG 1021, Revision 9 Appendix C Page 5 of 6 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2014 Admin -JPM A4e SRO Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiner's Signature: Date: 2014 Admin -JPM A4e SRO NUREG 1021, Revision 9 Appendix C INITIAL CONDITIONS: INITIATING CUE: Form ES-C-1 JPM CUE SHEET The sequence of events that you have just performed on the recently completed Simulator Scenario must be evaluated for any Emergency Classifications.

• Determine the HIGHEST Emergency Classification that would have been made during the recently completed scenario.
• Prepare EP-Form-ALL25, GNP NY STATE RADIOLOGICAL EMERGENCY DATA FORM (Part 1), for notification by the Communicator.

A PORTION OF THIS JPM IS TIME CRITICAL. NUREG 1021, Revision 9 n A. r lte. GNP NY STATE RADIOLOGICAL EMERGENCY DATA FORM (PART 1) EP-Form-ALL25 RO 0* 0* 0* 0* 0* 0* 0* 0* 0* RECS Message Number: "This is Ginna Station. Please stand by for roll call. "New York State" O "Monroe County" 0 "Wayne County" 0 1. Message transmitted at: 2. This is: CV An Exercise Date Time: A. An J\ctual Event Via: A. RECS B. Other 3. Classification: A. UNUSUAL EVENT AREA EMERGENCY E. EMERGENCY TERMINATED B. ALERT . GENERAL EMERGENCY F. RECOVERY

4. Classification Time: This Emergency Classification declared at: Date '\c-.:!...:.

..... Time.-\, 1"'! 0+: Cle,.:.;,.&* .>.J I 5. Release of Radioactive Materials due to the Classified Event: A. No Release B. Release BELOW federal limits 0 to atmosphere 0 to water @) Release ABOVE federal limits Ji to atmosphere D to water D. Unmonitored release requiring evaluation

6. Protective Actions RECOMMENDATIONS: No need for Protective Actions outside the site boundary B. EVACUATE and implement the Kl plan for the following ERPA's (all remaining ERPA's to monitor the Emergency Alert W1 W2 W3 W4 W5 W6 W7 Ml M2 M3 M4 MS M6 M7 MB M9 c. SHEL TEA-IN-PLACE and implement the Kl plan for the following ERPA's (all remaining ERPA's to monitor the Emergency Alert System) W1 W2 W3 W4 W5 W6 W7 M1 M2 1\113 M4 M5 M6 M7 MS M9 7. EAL Number: Brief Event and other significant information EAL Number -*1 l,.,. (:: (',C

.):;;: Fi;\ \ L"f"' 1 c 'e *;:... l ,;2,.;;'1

i. 'I. \)f.k "'* ,..)f. 8. Reactor Status: ' G.l*,..;)+J.01..:>.rJ Operationa1(sfihutdown Date: 10&-i Time: ,,,.....£'.

A. (subcritical)

9. Wind Speed: -A.

Miles/hour at elevation '3:..1__ feet 10. Wind Direction: From: degrees at elevation: feet 11. Stability Class: UNSTABLE NEUTRAL STABLE Alpha J Bravo I Charlie 16, I Echo \ Foxtrot I Golf b. T -ITC.f. __ = .tl. -----------!----------!----

---

\--

---.J----1------------------1-----------

---

!---------

250 ft temp 33 ft temp -2.17 -1.95 -1.:r4 -0.65 +1.74 +4.77 12. Reported by: Name: Area Code: Number:

• check box if information has changed since last form was transmitted.

"Please stand by for roll call: New York State copy?" D "Monroe County copy?" 0 "Wayne County copy?" 0 FOR GINNA USE ONLY: Time Prepared: \' r--* <ft Prepared By: 1"-J.,a. .. r. e,_ Time Approved: Completed form sent to EP Director Approved By: WAYNE COUNTY USE ONLY: Routing: _ALL _Dose Assess Calculator _ADO _Ginna Tech Rep _Field Team Coord. _Plotter _NYS Rad Health _Ops Officer _NYS Health (Ops room) _.Director _PIO I MONROE COUNTY USE ONLY: Distribution:

1. Command Room (OEP Administrator)

2. EOC (Qj;)erations Desk) 3. Assessment Area (Rad Officer, Health, Field Team Coordinator.

Computer Operations, Tech Rep) 4. Evaluator

5. File Page 1 of 2 Appendix C Job Performance Measure Worksheet SIM JPM A Form ES-C-1 2014 Systems -Control Room JPM A (Rev_110314)

NUREG 1021, Revision 9 Appendix C Page 2of15 Form ES-C-1 Job Performance Measure Worksheet Facility: Ginna Task No.: Task Title: Lineup RCDT Pump for Core Cooling JPM No.: 2014 Systems -Control Room JPM A KIA

Reference:

005 A2.03 (2.9/3.1) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: x Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1. Initial Conditions:

• The plant is in a lowered inventory condition.
• Both RHR Pumps have tripped.
• AP-RHR.1, Loss of RHR, was entered and attempts to restart the pumps were unsuccessful.
• The crew is in progress of establishing Containment Integrity per 0-1.1 B, Establishing CNMT Integrity, and all personnel are clear of Containment.

Initiating Cue: The CRS has directed you to lineup and start the RCDT pumps to provide core cooling per ER-RHR.1, Section 6.2, Closed Loop RCS to RHR Cooling. Task Standard: The operator will line up the RCDT pumps to provide core cooling per Section 6.2 of ER-RHR.1. Required Materials: None General

References:

AP-RHR.1, Loss of RHR, Rev 02200 2014 Systems -Control Room JPM A NU REG 1021, Revision 9 Appendix C Handouts: Time Critical Task: Validation Time: Page 3of15 Form ES-C-1 Job Performance Measure Worksheet ER-RHR.1, RCDT Pump Operation for Core Cooling, Rev 00601 Handout 1: Blank copy of ER-RHR.1, RCDT Pump Operation for Core Cooling. NO 10 minutes 2014 Systems -Control Room JPM A NU REG 1021, Revision 9 Appendix C Page 4 of 15 Form ES-C-1 Job Performance Measure Worksheet SIMULATOR OPERATIONAL GUIDELINES

• Simulator reset to IC-2 (85" Loop Level)
• Insert MALF RHR 1A and RHR 1B
• Insert REM-RCS11, CLOSED, to isolate RVLIS Valves
• Insert IND-RCS11, 0%, RVLIS A Meter Reading
• Insert IND-RCS13, 0%, RVLIS A Meter Reading
• Insert A-20, RHR LO FLOW, Annunciator Tile
• Insert C-5, L TOP HI/LOW Temp, Annunciator Tile
• Insert F-29, L TOP Hi/Low Pressure, Annunciator Tile
• Insert the following on Trigger #1 o REMOTE-MIS67 and MIS68 to Close (RCDT Suction AOV 1003A and B CLOSED) o REMOTE-MISOS and MIS06 to 0 (RCDT Pump Discharge Valves V1726/1727 CLOSED) o REMOTE-MIS09 and MIS10 to 1 (RCDT Pump to RHR HX V1811A and B OPEN) o REMOTE-RHROS to 0 (RHR HX Bypass V712A CLOSED) o REMOTE-RHR01 to 0 (RHR Pump A Discharge Valve V709A CLOSED) o REMOTE-RHR02 to 0 (RHR Pump B Discharge Valve V709B CLOSED) o REMOTE-EDSOSS and EDS056 to Close (MOV-1813A and B Breakers CLOSED)
• Ensure RHR Screen (Group Display NPSH) is displayed on PPCS
• FREEZE the Simulator OR
• IC 156 (December, 2014)
• Ensure RHR Screen (Group Display NPSH) is displayed on PPCS
• Place simulator in RUN
• Place simulator in FREEZE
• Place simulator in RUN when directed by examiner NOTE: The Simulator/Floor Instructor will need to control the BOP during the performance of this JPM. NOTE: The Simulator/Booth Instructor will need to operate Trigger #1 at Performance Step 8 of this JPM, and provide a cue to the operator at Performance Step 20 of this JPM (See Body of JPM). 2014 Systems -Control Room JPM A NU REG 1021, Revision 9

Appendix C Page 5of15 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with a -VJ Provide Candidate with Initial Conditions/Cue (Last Page of this JPM} and Handout 1. START TIME: Performance Step: 1 Standard: Comment: Performance Step: 2 Standard: Comment: Performance Step: 3 Standard: Comment: ER-RHR.1, Step 6.2.1 Caution: RCDT pump discharge relief valve lifts at 132 psig. Verify RCS pressure less than 100 psig. IF NOT, then consult plant staff for other means of cooling RCS. The operator reads the Caution, and proceeds. The operator observes MCB indication Pl-420 or PPCS RCS pressure indication (or equivalent) and determines pressure is less than 100 psig. ER-RHR.1, Step 6.2.2 IF there are personnel in CNMT, ..... The operator confirms via initial conditions no personnel are in CNMT. ER-RHR.1, Step 6.2.3 IF entry is from AP-RHR.1,THEN initiate measures to establish CNMT closure, (refer to 0-1.1 B, Establishing CNMT Integrity, for guidance). The operator confirms via initial conditions that establishing CNMT Integrity is in progress. 2014 Systems -Control Room JPM A NUREG 1021, Revision 9 Appendix C Performance Step: 4 Standard: Comment: Performance Step: 5 Standard: Comment: Performance Step: 6 Standard: Comment: 6of15 PERFORMANCE INFORMATION ER-RHR.1, Step 6.2.4 IF entry is from AP-RHR.2, ..... Form ES-C-1 The operator confirms via initial conditions that entry was from AP-RHR.1, and proceeds. ER-RHR.1, Step 6.2.5 Continue to monitor core exit T/Cs. The operator observes CET indication on PPCS. ER-RHR.1, Step 6.2.6/6.2.6.1 Align RHR CNMT sump suction valves for RCDT pump RCS loop suction as follows:

• Close RHR suction valves from sump B inside CNMT:
• MOV-851A Closed
• MOV-851 B CLOSED The operator observes the MOV-851A Green status light is LIT, and the Red status light is OFF. The operator observes the MOV-851 B Green status light is LIT, and the Red status light is OFF. 2014 Systems -Control Room JPM A NU REG 1021, Revision 9

Appendix C --4. Performance Step: 7 Standard: Comment: -J ... Performance Step: 8 Standard: SIM DRIVER: Comment: Page 7of15 PERFORMANCE INFORMATION ER-RHR.1, Step 6.2.6.2 Form ES-C-1 Open RHR suction valves from sump 8 outside CNMT:

• MOV-850A Open
• MOV-8508 Open [-/]The operator places the MOV-850A Control Switch to OPEN and releases; and observes the Red status light is LIT, and the Green status light is OFF. [-/]The operator places the MOV-8508 Control Switch to OPEN and releases; and observes the Red status light is LIT, and the Green status light is OFF. ER-RHR.1, Step 6.2.7/6.2.7.1 Dispatch AO with locked valve key to locally perform the following:
• Place RCDT pump suction valve switches to CLOSE.
• LCV-1003A Switch In CLOSE
• LCV-10038 Switch In CLOSE ['1] The operator directs AO to locally place LCV-1003N8 switches in CLOSE. When contacted as AO, insert Trigger 1. Report that these valves are CLOSED. 2014 Systems -Control Room JPM A NUREG 1021, Revision 9

Appendix C -) Performance Step: 9 Standard: SIM DRIVER: Comment: -) Performance Step: 1 O Standard: SIM DRIVER: Comment: Page 8of15 PERFORMANCE INFORMATION ER-RHR.1, Step Close RCDT pump manual discharge valves (AUX BLDG sub-basement).

• V-1726 Closed
• V-1727 Closed Form ES-C-1 [\/]The operator directs AO to locally CLOSE V-1726 and V1727. Report that these valves are CLOSED. ER-RHR.1, Step 6.2.7.3 Open RCDT pump discharge valves to RHR (AUX BLDG bsmt west behind stairway).
• V-1811A Open
• V-1811 B Open [\I] The operator directs AO to locally OPEN V-1811A and V-1811 B. Report that these valves are OPEN. 2014 Systems -Control Room JPM A NUREG 1021, Revision 9

Appendix C -J Performance Step: 11 Standard: SIM DRIVER: Comment: -J Performance Step: 12 Standard: SIM DRIVER: Comment: -J Performance Step: 13 Standard: SIM DRIVER: Comment: Page 9of15 PERFORMANCE INFORMATION ER-RHR.1, Step 6.2.7.4 Form ES-C-1 Close RHR Hx bypass isolation valve V-712A (AUX BLDG bsmt RHR Hx room wall). [\/']The operator directs AO to locally CLOSE V-712A. Report that this valve is CLOSED. ER-RHR.1, Step 6.2.7.5 Close RHR pump A discharge valve V-709A (AUX BLDG basement). [\/']The operator directs AO to locally CLOSE V-709A. Report that this valve is CLOSED. ER-RHR.1, Step 6.2.7.6 Close RHR pump B discharge valve V-7098 (AUX BLDG basement). [\/']The operator directs AO to locally CLOSE V-709B. Report that this valve is CLOSED. 2014 Systems -Control Room JPM A NU REG 1021, Revision 9 Appendix C Performance Step: 14 Standard: SIM DRIVER: EXAMINER NOTE: Comment: v Performance Step: 15 Standard: Comment: Page 10of15 PERFORMANCE INFORMATION ER-RHR.1, Step 6.2.7.7 Form ES-C-1 Dispatch AO with locked valve key to unlock and close breakers for RCDT pump suction valves from sump B.

• MOV-1813A breaker (MCC C Pos 13M) Closed
• MOV-18138 breaker (MCC D Pos 13M) Closed The operator directs AO to check CLOSE MOV-1813A and 18138 Breakers.

The operator observes the MOV-1813A Green status light is LIT, and the Red status light is OFF. The operator observes the MOV-18138 Green status light is LIT, and the Red status light is OFF. Report that these breakers are CLOSED. These Breakers are already closed for plant configuration. ER-RHR.1, Step 6.2.8 WHEN local valve alignment

complete, THEN open RCDT pump suction valves from sump B.

• MOV-1813A Open
• MOV-18138 Open [v] The operator places the MOV-1813A Control Switch to OPEN and observes the Red status light is LIT, and the Green status light is OFF.

operator places the MOV-18138 Control Switch to OPEN and observes the Red status light is LIT, and the Green status light is OFF. 2014 Systems -Control Room JPM A NUREG 1021, Revision 9 Appendix C Page 11 of 15 PERFORMANCE INFORMATION ER-RHR.1, Step 6.2 .. 9 Form ES-C-1 ..../. Performance Step: 16 Start RCDT pump A. Standard: [..../] The operator places the RCDT Pump A Control Switch in the START position and observes the Red status light is LIT, and the Green status light is OFF. Comment: ER-RHR.1, Step 6.2.10 --./ Performance Step: 17 Start RCDT pump B. Standard: Comment: [\I] The operator places the RCDT Pump Bin the START position and observes the Red status light is LIT, and the Green status light is OFF. ER-RHR.1, Step 6.2.11 '1* Performance Step: 18 Open RHR Hx A outlet valves HCV-625. Standard: [\i] The operator rotates HCV-625 controller adjust knob clockwise until controller output demand is 0%. Comment: 2014 Systems -Control Room JPM A NU REG 1021, Revision 9 Appendix C Page 12of15 PERFORMANCE INFORMATION ER-RHR.1, Step 6.2.12 Form ES-C-1 ..J, Performance Step: 19 Open RHR Hx B outlet valve HCV-624. Standard: [.Y] The operator rotates HCV-624 controller adjust knob clockwise until controller output demand is 0%. Comment: Performance Step: 20 Standard: SIM DRIVER: Comment: ER-RHR.1, Step 6.2.13 Direct AO to locally verify discharge pressure on RCDT pumps (AUX BLDG bsmt by RHR Hx room gate). The operator contacts the AO and requests RCDT Pump discharge pressure. As the AO, report that RCDT Pump discharge pressure is approximately 40 psig and stable. 2014 Systems -Control Room JPM A NU REG 1021, Revision 9 Appendix C Page 13of15 PERFORMANCE INFORMATION ER-RHR.1, Step 6.2.14 Form ES-C-1 Caution: Reactor Coolant Drain Tank pumps may be insufficient for decay heat removal. Performance Step: 21 Verify flow on Fl-626. Standard: The operator reads the Caution and proceeds. Comment: Terminating Cue: STOP TIME: The operator observes approximately 100 GPM of flow on Fl-626. Evaluation on this JPM is complete. 2014 Systems -Control Room JPM A NUREG 1021, Revision 9 Appendix C Page 14of15 VERIFICATION OF COMPLETION Job Performance Measure No.: 2014 Systems -Control Room JPM A Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiner's Signature: Date: Form ES-C-1 2014 Systems -Control Room JPM A NU REG 1021, Revision 9 Appendix C INITIAL CONDITIONS: INITIATING CUE: Form ES-C-1 JPM CUE SHEET

• The plant is in a lowered inventory condition.
• Both RHR Pumps have tripped.
• AP-RHR.1, Loss of RHR, was entered and attempts to restart the pumps were unsuccessful.
• The crew is in progress of establishing Containment Integrity per 0-1.1 B, Establishing CNMT Integrity, and all personnel are clear of Containment.

The CRS has directed you to lineup and start the RCDT pumps to provide core cooling per ER-RHR.1, Section 6.2, Closed Loop RCS to RHR Cooling. NUREG 1021, Revision 9 Appendix C Job Performance Measure Worksheet SIM JPM B Form ES-C-1 2014 Systems -Control Room JPM B (Rev_110314) NU REG 1021, Revision 9 Appendix C Facility: Task Title: Page 2 of 16 Form ES-C-1 Job Performance Measure Worksheet Ginna Verify Containment Isolation and Heat Removal Task No.: JPM No.: 2014 Systems -Control Room JPM B (Alternate Path) KIA

Reference:

EPE E14 EA1.1 (3.7/3.7) 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. Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1. Initial Conditions: Initiating Cue:

• The plant tripped from 100% power and safety injection has actuated.
• The crew entered E-0, Reactor Trip or Safety Injection, and then transitioned to E-2, Faulted Steam Generator Isolation.
• Due to a degrading transient, an Orange Path now exists on the Containment Critical Safety Function Status Tree. The CRS has directed you to verify Containment Isolation and Heat Removal systems are operating as expected by performing FR-Z.1, Response to High Containment

Pressure, starting from Step 1. 2014 Systems -Control Room JPM B NUREG 1021, Revision 9

Appendix C Page of 16 Form ES-C-1 Job Performance Measure Worksheet Task Standard: The operator will take action to verify Containment Isolation and Heat Removal systems are operating in accordance with Steps 1-3 of FR-Z.1. When the operator discovers that two Containment Isolation Valves have failed to close as expected the operator will close or direct that alternative valves be closed in accordance with ATT-3.0, Attachment Cl/CVI. When it is revealed that one of the two actions on ATT-3.0 were unsuccessful at providing Containment Isolation, the operator will need to take actions to trip the Reactor Coolant Pumps, and close an alternate valve in the CCW System to fully achieve Containment Isolation. Required Materials: None General

References:

AR-A-27, Containment Spray 2/3 + 2/3 > 28 PSI, Rev 9 AR-A-28, Containment Spray Channel Alert 2/3 > 28 PSI, Rev 8 CNG-OP-1.01-1000, Conduct of Operations, Rev 01000 Handouts: Time Critical Task: Validation Time: F-0.5, Containment, Rev 2 FR-Z.1, Response to High Containment

Pressure, Rev 01200 ATT-3.0, Attachment Cl/CVI,,

Rev 01200 P-7, Safety Injection and Containment Spray Systems, Rev 23 Handout 1: Blank copy of FR-Z.1, Response to High Containment Pressure Handout 2: Blank copy of ATT-3.0, Attachment Cl/CVI. NO 10 minutes 2014 Systems -Control Room JPM B NU REG 1021, Revision 9 Appendix C Page 4 of 16 Form ES-C-1 Job Performance Measure Worksheet SIMULATOR OPERATIONAL GUIDELINES

• Initiate to any 100% IC {IC-19)
• Insert Malfunctions RPSOSA and RPSOSB, No Manual (Failure of CS Automatic Actuation/No Manual, Both Trains)
• Insert Malfunction STM11A, 1. 7e+05 (Steam Line Break Inside Containment,

'A' S/G)

• Insert Malfunction RPS11-A5A and RPS11-A5B, Fail As-ls (MOV-813 and 814 fail as-is on T-Signal, cannot be operated)
• Insert REM-EDS054, Closed, on T-1 (Breaker for MOV-817)
• Place simulator in RUN
• Carry out action of E-0 and transition to E-2.
• Upon transition to E-2, increase malfunction STM11A to 1.7e+07 (Steam Rupture Inside Containment,

'A' S/G)

• Ensure Annunciator A-28 is LIT, that Containment Pressure is > 28 psig, and that CS has NOT automatically actuated
• Place simulator in FREEZE
• Place simulator in RUN when directed by examiner OR
• IC 157 (December, 2014)
• Place simulator in RUN
• Place simulator in FREEZE
• Place simulator in RUN when directed by examiner NOTE: The Simulator/Floor Instructor will need to control the BOP during the performance of this JPM. NOTE: The SIM DRIVER will need to respond as the AO at Performance Step 3, make a report from the field at Step 10, and insert REM-EDS054 at Step 11 of this JPM (See Cues in Body of JPM). 2014 Systems -Control Room JPM B NU REG 1021, Revision 9

Appendix C Page 5 of 16 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with a"\/) Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1. START TIME: Performance Step: 1 Standard: Comment: FR-Z.1 Step 1 Note: FOLDOUT Page should be open and monitored periodically. Verify All Cl And CVI Valve Status Lights -BRIGHT The operator observes all Cl And CVI Valve Status Lights are BRIGHT except MOV-813 and MOV-814. The operator proceeds to the Step 1 RNO. At any time during this JPM, the operator may recognize that automatic actions have failed, and take manual action as needed to operate equipment as needed (See CNG-OP-1.01-1000, Step 5 .. 10.C.4). While the operator may take this action, and it is permitted by procedures, and expected; if the action is not taken the operator will still be successful by adherence to the procedure assigned. NOTE: Any attempt by the operator to actuate CS by depressing two MCB pushbuttons simultaneously will not be successful (pushbutton operation has failed). 2014 Systems -Control Room JPM B NU REG 1021, Revision 9 Appendix C Performance Step: 2 Standard: EXAMINER CUE: Comment: Page 6of16 PERFORMANCE INFORMATION FR-Z.1 Step 1 RNO Form ES-C-1 IF flow path NOT required, THEN manually close affected Cl and CVI valves. IF valves can NOT be verified closed by MCB indication, THEN close alternate isolation valves. (Refer to ATT-3.0, ATTACHMENT Cl/CVI). The operator recognizes that the Rx Support Cooler CCW flowpaths are NOT required under the current conditions. The operator observes the MOV-813 Red status light is LIT, and the Green status light is OFF. The operator places the MOV-813 Control Switch to CLOSE, and observes Red status light is LIT, and the Green status light is OFF. The operator observes the MOV-814 Red status light is LIT, and the Green status light is OFF. The operator places the MOV-814 Control Switch to CLOSE, and observes Red status light is LIT, and the Green status light is OFF. The operator refers to ATT-3.0. When the operator is looking to find ATT-3.0, PROVIDE operator with Handout 2 (ATT-3.0). 2014 Systems -Control Room JPM B NU REG 1021, Revision 9 Appendix C --.j* Performance Step: 3 Standard: SIM DRIVER NOTE: Comment: Page 7of16 PERFORMANCE INFORMATION ATT-3.0 Step 1 Form ES-C-1 Note: Locked valve key may be required for local operations. For each of the following AUTO ISOL VALVES that will not close, take the action directed in the ALTERNATE ISOLATION column. MOV-813 (CCW) Locally close MOV-813 (AB Int Level). MOV-814 (CCW) Close V-815A (AB INT LEVEL) The operator reads the Note, and proceeds. The operator will contact an AO and direct that MOV-813 be locally closed. [--.1] The operator will contact an AO and direct that V-815A be locally closed. The operator will proceed to Step 2 of FR-Z.1 while the local action is taking place. The AO action will be delayed until Performance Step 10. Upon completion of Performance Step 10, as the AO, report that V-81 SA has been locally closed, and report that MOV-813 will NOT operate manually. There is NO Remote for V-81 SA (Not Modeled). 2014 Systems -Control Room JPM B NUREG 1021, Revision 9 Appendix C Performance Step: 4 Standard: Comment: Performance Step: 5 Standard: Comment: Page 8of16 PERFORMANCE INFORMATION FR-Z.1 Step 2/2.a Form ES-C-1 Caution: IF ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, IS IN EFFECT, THEN CNMT SPRAY SHOULD BE OPERATED AS DIRECTED IN ECA-1.1, RATHER THAN STEP 2 BELOW. Caution: IF E-1, LOSS OF REACTOR OR SECONDARY

COOLANT, IS IN EFFECT, THEN CNMT SPRAY SHOULD BE OPERATED AS DIRECTED IN E-1, LOSS OF REACTOR OR SECONDARY COOL.ANT, RATHER THAN STEP 2 BELOW. Verify CNMT Spray Actuated:

• Verify RWST outlet to SI and CNMT spray pumps -OPEN
• MOV-896A
• MOV-896B The operator reads the Cautions, and proceeds.

The operator observes the MOV-896A Red status light is LIT and the Green status light is OFF. The operator observes the MOV-896B Red status light is LIT and the Green status light is OFF. FR-Z.1 Step 2.b Verify CNMT spray pumps -RUNNING The operator observes the A Containment Spray Pump Green status light is LIT, and the Red status light is OFF. The operator observes the B Containment Spray Pump Green status light is LIT, and the Red status light is OFF. The operator observes Containment pressure to be ==40 psig. The operator proceeds to the Step 2.b RNO. 2014 Systems -Control Room JPM B NU REG 1021, Revision 9 Appendix C "1* Performance Step: 6 Standard: Comment: Performance Step: 7 Standard: Comment: Page 9 of 16 PERFORMANCE INFORMATION FR-Z.1 Step 2.b RNO Manually start pumps. Form ES-C-1 ["1] The operator places the A Containment Spray Pump Control Switch to START and observes the Red status light is LIT, and the Green status light is OFF. ["1] The operator places the B Containment Spray Pump Control Switch to START and observes the Red status light is LIT, and the Green status light is OFF. FR-Z.1 Step 2.c Verify NaOH flow (Fl-930) The operator observes Fl-930 and notes flow at "O." The operator proceeds to the Step 2.c RNO. 2014 Systems -Control Room JPM B NU REG 1021, Revision 9 Appendix C . .../. Performance Step: 8 Standard: EXAMINER NOTE: Comment: Page '10 of 16 PERFORMANCE INFORMATION FR-Z.1 Step 2.c RNO Form ES-C-1 IF NaOH flow NOT indicated, THEN place switches for NaOH tank outlet valves to OPEN.

• AOV-836A
• AOV-8368

['-1] The operator places the Control Switch for AOV-836A in OPEN. ['-1] The operator places the Control Switch for AOV-8368 in OPEN. One of the two valve Control Switches must be in the OPEN position to satisfy the Critical Step. Flow on Fl-930 will NOT be observed until Performance Step 10. When the Containment Spray Pump Discharge Valves are OPEN. 2014 Systems -Control Room JPM B NUREG 1021, Revision 9 Appendix C Performance Step: 9 Standard: Comment: Page 11 of 16 PERFORMANCE INFORMATION FR-Z.1 Step 2.d Verify CNMT spray pump discharge valves -OPEN MOV-860A MOV-8608 MOV-860C MOV-8600 Form ES-C-1 The operator observes the MOV-860A Green status light is LIT, and the Red status light is OFF. The operator observes the MOV-8608 Green status light is LIT, and the Red status light is OFF. The operator observes the MOV-860C Green status light is LIT, and the Red status light is OFF. The operator observes the MOV-8600 Green status light is LIT, and the Red status light is OFF. The operator proceeds to the Step 2.d RNO. 2014 Systems -Control Room JPM 8 NU REG 1021, Revision 9 Appendix C Page '12 of 16 PERFORMANCE INFORMATION FR-Z.1 Step 2.d RNO Form ES-C-1 Performance Step: 1 o Ensure at least one in each set valves -OPEN. Standard: EXAMINER NOTE: Comment: MOV-860A or MOV-8608 MOV-860C or MOV-8600 1'11 The operator places the MOV-860A Control Switch in OPEN and observes the Red status light is LIT, and the Green status light is OFF. OR Iv'l The operator places the MOV-8608 Control Switch in OPEN and observes the Red status light is LIT, and the Green status light is OFF. AND lv'l The operator places the MOV-860C Control Switch in OPEN and observes the Red status light is LIT, and the Green status light is OFF. OR 1'11 The operator places the MOV-8600 Control Switch in OPEN and observes the Red status light is LIT, and the Green status light is OFF. The operator will observe flow on Fl-930. The operator may all OPEN all four valves, however, at least one valve in each set must be OPEN to satisfy the Critical Nature of this Step. SIM DRIVER: Call the Control Room as the AO and report "V-815A has been locally closed, however MOV-813 will NOT operate manually." 2014 Systems -Control Room JPM B NUREG 1021, Revision 9 Appendix C Page 13of16 PERFORMANCE INFORMATION Form ES-C-1 \ EXAMINER NOTE: ALTERNATE PATH DECISION POINT OCCURS IN THE NEXT STEP vi Performance Step: 11 Standard: SIM DRIVER NOTE: Comment: ATT-3.0 Step 1 Note: Locked valve key may be required for local operations. For each of the following AUTO ISOL VALVES that will not close, take the action directed in the AL TERNA TE !SOLA TION column. MOV-813{CCW): IF MOV-813 can not be closed, THEN perform the following:

• Direct AO with locked valve key to unlock and close breaker for MOV-817 (MCC D POS 1 OC)
• Stop both RCPs
• Manually close MOV-817 (MCB). IF MOV-817 will not close, THEN direct AO to locally close MOV-817 (AB INT LEVEL). The operator reads the NOTE, and proceeds.

The operator will refer to ATT-3.0, contact the AO, and direct that the AO unlock and close the breaker for MOV-817. [vi] The operator will place the A RCP Control Switch to STOP and observe the Green status light is LIT, and the Red status light is OFF. [vi] The operator will place the 8 RCP Control Switch to STOP and observe the Green status light is LIT, and the Red status light is OFF. [vl]The operator will place the MOV-817 Control Switch to CLOSE and observe the Green status light is LIT, and the Red status light is OFF. The operator returns to FR-Z.1. Upon direction from the operator to unlock and close the MOV-817 breaker, operate Trigger 1 (REM-EDS054 (MOV-817 Breaker Closed). Call as AO and report that you have unlocked and closed the MOV-817 breaker. 2014 Systems -Control Room JPM B NU REG 1021, Revision 9 Appendix C Page 14 of 16 PERFORMANCE INFORMATION FR-Z.1 Step 3/3.a Form ES-C-1 Performance Step: 12 Verify CNMT RECIRC Fans Running: Standard: Comment: All fans -RUNNING The operator observes the A CNMT RECIRC Fan Red status light is LIT, and the Green status light is OFF. The operator observes the B CNMT RECIRC Fan Red status light is LIT, and the Green status light is OFF. The operator observes the C CNMT RECIRC Fan Red status light is LIT, and the Green status light is OFF. The operator observes the D CNMT RECIRC Fan Red status light is LIT, and thE3 Green status light is OFF. FR-Z.1 Step 3.b Performance Step: 13 Charcoal filter dampers green status lights -EXTINGUISHED Standard: The operator observes the A CNMT RECIRC Fan Charcoal Filter Damper Red status light is LIT, and the Green status light is OFF. Comment: Terminating Cue: STOP TIME: The operator observes the C CNMT RECIRC Fan Charcoal Filter Damper Red status light is LIT, and the Green status light is OFF. Evaluation on this JPM is complete. 2014 Systems -Control Room JPM B NUREG 1021, Revision 9 Appendix C Page 15of16 VERIFICATION OF COMPLETION Job Performance Measure No.: 2014 Systems*- Control Room JPM B Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiner's Signature: Date: Form ES-C-1 2014 Systems -Control Room JPM B NUREG 1021, Revision 9 Appendix C INITIAL CONDITIONS: INITIATING CUE: Form ES-C-1 JPM CUE SHEET

• The plant tripped from 100% power and safety injection has actuated.
• The crew entered E-0, Reactor Trip or Safety Injection, and then transitioned to E-2, Faulted Steam Generator Isolation.
• Due to a degrading transient, an Orange Path now exists on the Containment Critical Safety Function Status Tree. The CRS has directed you to verify Containment Isolation and Heat Removal systems are operating as expected by performing FR-Z.1, Response to High Containment

Pressure, starting from Step 1. NUREG 1021, Revision 9

Appendix C Job Performance Measure Worksheet SIM JPM C Form ES-C-1 2014 Systems -Control Room JPM C (Rev_110314) NU REG 1021, Revision 9 Appendix C Facility: Task Title: Page 2 of 20 Form ES-C-1 Job Performance Measure Worksheet Ginna CVCS Leak Isolation Task No.: JPM No.: 2014 Systems -Control Room JPM C (Alternate Path) KIA

Reference:

004 A4.08 (3.8/3.4) 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. Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1. Initial Conditions: Initiating Cue: Task Standard:

• The Plant is at 100% power.
• Based on plant conditions the crew has entered AP-CVCS.1, "CVCS Leak," and has completed steps 1-5.
• Pressurizer level is stable.
• The leak is believed to be in the Containment and RP has been directed to sample the Containment for entry.
• The HCO is monitoring the automatic VCT makeups that are occurring.

While the CRS and the HCO continue to monitor plant conditions, continue with AP-CVCS.1 starting with Step 6 to control RCS inventory to maintain Pressurizer level stable. The operator will isolate Normal Letdown and Charging, recognize that both operating Charging Pumps have tripped, use AP-CVCS.1 or CVCS.3 to restore flow, and then place Excess Letdown in service. 2014 Systems -Control Room JPM C NU REG 1021, Revision 9 Appendix C Page 3 of 20 Form ES-C-1 Job Performance Measure Worksheet Required Materials: None General

References:

S-3.2, Charging and Volume Control, Rev 02000 Handouts: Time Critical Task: Validation Time: AR-A-4, REGEN HX LETDOWN OUT HIGH TEMP 395°F, Rev 00700 AP-CVCS.1, CVCS Leak, Rev 01501 AR-B-9, RCP 1A LABYR SEAL LO DIFF PRESS 15" H20, Rev 10 AR-B-10, RCP 18 LABYRSEAL LO DIFF PRESS 15" H20, Rev 10 AP-CVCS.3, Loss of All Charging Flow, Rev 01300 ATT-9.1, Attachment Excess LID, Rev 00800 Handout 1: AP-CVCS.1, CVCS Leak, marked up through Step 5. (with all ATTs/FIGs) Handout 2: Blank copy of AP-CVCS.3, Loss of All Charging Flow Handout 3: FIG-4.0, Figure RCP Seal Leakoff NO 20 minutes 2014 Systems -Control Room JPM C NUREG 1021, Revision 9 Appendix C Page 4 of 20 Form ES-C-1 Job Performance Measure Worksheet SIMULATOR OPERATIONAL GUIDELINES

• Initiate to any 100% power IC
• Place simulator in RUN
• Ensure C Charging Pump running in AUTO, B Charging Pump running in MANUAL, and the A Charging Pump available, but OFF
• Insert Malfunction CVC03, 30 GPM Line Leak upstream of Regenerative Heat Exchanger)
• Respond to annunciator procedures and enter AP-CVCS.1, "CVCS Leak"
• Perform steps 1-5 of AP-CVCS.1
• Ensure Przr Level and VCT Level are normal Letdown is in service, and that the VCT is aligned to the suction of the Charging Pumps
• Insert Malfunctions CVC12B and CVC12C on Trigger #1 (Charging Pumps 'B' and 'C' Trip)
• Place simulator in FREEZE
• Place simulator in RUN when directed by examiner OR
• Initiate to IC-158 (December, 2014)
• Place simulator in RUN
• Place simulator in FREEZE
• Place simulator in RUN when directed by examiner NOTE: The Floor Instructor will need to control BOP during the performance of this JPM. The SIM DRIVER will need to insert Trigger #1 at Step 4 of this JPM. 2014 Systems -Control Room JPM C NU REG 1021, Revision 9

Appendix C Page 5 of 20 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with a -VJ Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1. START TIME: Performance Step: 1 Standard: Comment: ..,j* Performance Step: 2 Standard: Comment: AP-CVCS.1, Step 6 Check for leak in Charging Line to REGEN Hx: Annunciator A-4, REGEN HX LETDOWN OUT HI TEMP 395°F -EXTINGUISHED Regen Hx Ltdn Outlet Temp -LESS THAN 350°F AND STABLE (Tl-127) The operator observes that Annunciator A-4 is LIT, and proceeds to the Step 6 RNO. AP-CVCS.1, Step 6 RNO a Perform the following to isolate normal letdown: Close letdown isolation, AOV-427. ["1] The operator places the AOV-427 Control Switch to CLOSE, and observes the Green status light is LIT, Red status light is OFF. 2014 Systems -Control Room JPM C NU REG 1021, Revision 9 Appendix C Performance Step: 3 Standard: EXAMINER NOTE: Comment: Page 6 of 20 PERFORMANCE INFORMATION AP-CVCS.1, Step 6 RNO b Form ES-C-1 Close letdown orifice valves (AOV-200A, AOV-2008, and AOV-202). The operator observes the Green status light is LIT, Red status light is OFF. The operator places the AOV-200A Control Switch to CLOSE. This valve auto closed when AOV-427 was CLOSED by interlock. 2014 Systems -Control Room JPM C NU REG 1021, Revision 9 Appendix C Performance Step: 4 Standard: SIM DRIVER: Standard: EXAMINER NOTE: Comment: Page 7 of 20 PERFORMANCE INFORMATION AP-CVCS.1, Step 6 RNO c Close letdown isolation, AOV-371. Form ES-C-1 The operator places the AOV-371 Control Switch to CLOSE, and observes the Green status light is LIT, Red status light is OFF. After Operator CLOSES AOV-371, INSERT Trigger #1 The operator observes one or more of the following:

• Charging flow goes to 0 GPM
• Charging Pumps have tripped
• AR-B-9, RCP 1A LABYR SEAL LO DIFF PRESS 15" H20, is LIT
• AR-B-10, RCP 1 B LABYR SEAL LO DIFF PRESS 15" H20, is LIT
• AR-G-25, MOTOH OFF CENTER SECTION PUMPS EXCEPT MFW AND AFW PUMPS. The operator uses the ARP for these annunciators to go to CVCS.3, or enters this procedure directly based on meeting the entry conditions.

Based on a Step 1 of AP-CVCS.1 which is a Continuous Action Step (CAS), the operator may start the A Charging Pump and stabilize Pressurizer level. If so, the operator may continue in AP-CVCS.1. If so, go to JPM Step 9. EXAMINER NOTE: ALTERNATE PATH DECISION POINT OCCURS WHEN THE CHARGING PUMPS TRIP 2014 Systems -Control Room JPM C NU REG 1021, Revision 9 Appendix C Performance Step: 5 Standard: EXAMINER CUE: Comment: "'1 ..

• Performance Step: 6 Standard:

Comment: Page 8 of 20 PERFORMANCE INFORMATION AP-CVCS.3, Step 1 Check Charging Pumps -ANY RUNNING Form ES-C-1 The operator observes that the Green status lights for the A, B and C Charging Pumps are LIT, and the White status lights on Charging Pump B and C are LIT; and proceeds to the Step 1 RNO. When the operator is looking to find AP-CVCS.3, PROVIDE operator with Handout 2 CAP-CVCS.3). AP-CVCS.3, Step 1 RNO Start two charging pumps. IF at least one pump cannot be started, THEN .... ['1'] The operator places START Switch for the A Charging Pump to the START Position, and observes Red status light is LIT, and the Green status light is OFF. 2014 Systems -Control Room JPM C NUREG 1021, Revision 9 Appendix C *"\/ Performance Step: 7 Standard: EXAMINER NOTE: Comment: Performance Step: 8 Standard: Comment: Page 9 of 20 PERFORMANCE INFORMATION AP-CVCS.3, Step 2 Check Charging Pump Conditions: Form ES-C-1

• Check charging pump discharge pressure

-GREATER THAN RCS PRESSURE AND STABLE

• Check charging flow -NORMAL
• Check RCP labyrinth seal dp -GREATER THAN 15 INCHES AND STABLE The operator observes Charging Pump discharge pressure to be 2400 psig. The operator observes Charging Pump flow to be 0 gpm. ["\/]The operator adjusts the Charging Pump speed to raise RCP Seal flow to stabilize Pressurizer level. The operator observes the 1 A RCP labyrinth seal D/P to be between 15-80 inches H20. The operator observes the 1 B RCP labyrinth seal D/P to be between 15-80 inches H20. HCV-142 should remain closed during the recovery of Charging flow. AP-CVCS.3, Step 3 Return To Guidance In Effect The operator returns to AP-CVCS.1 Step 6 RNO d. 2014 Systems -Control Room JPM C NU REG 1021, Revision 9

Appendix C ...j* Performance Step: 9 Standard: Comment: Page 10 of 20 PERFORMANCE INFORMATION AP-CVCS.1, Step 6 RNO d Form ES-C-1 Close charging flow control valve, HCV-142 WHILE adjusting charging pump speed to maintain:

• RCP labyrinth seal D/P between 15 inches and 80 inches
• PRZR level at program [..../]The operator simultaneously adjusts HCV-142 Controller to 100% (Valve Fully Closed) and adjust B Charging Pump speed to maintain RCP Labyrinth Seal D/P 15-80 inches, and Przr Level at program level (56%). AP-CVCS.1, Step 6 RNO e Performance Step: 10 Close charging to loop B cold leg, AOV-294.

Standard: The operator places the AOV-294 Control Switch to CLOSE, and observes the Green status light is LIT, Red status light is OFF. Comment: AP-CVCS.1, Step 6 RNO f Performance Step: 11 Go to Step 9. Standard: The operator proceeds to Step 9 Comment: 2014 Systems -Control Room JPM C NU REG 1021, Revision 9 Appendix C Page '11 of 20 PERFORMANCE INFORMATION AP-CVCS.1, Step 9 Form ES-C-1 Performance Step: 12 Check RCP Seal Indications: Standard: Comment:

• Seal injection flows -GREATER THAN 6 GPM AND STABLE
• RCP labyrinth seal D/Ps -GREATER THAN 15 INCHES AND APPROXIMATELY EQUAL
• RCP seal inlet temperatures

-STABLE The operator observes the 1A RCP seal injection flow to be ==8 gpm and stable. The operator observes the 1 B RCP seal injection flow to be ==8 gpm and stable. The operator observes the 1A RCP labyrinth seal D/P to be between 15-80 inches H20. The operator observes the 1 B RCP labyrinth seal D/P to be between 15-80 inches H20. The operator observes the 1A RCP seal inlet temperature to be ==110°F. The operator observes the 1 B RCP seal inlet temperature to be ==110°F. 2014 Systems -Control Room JPM C NU REG 1021, Revision 9 Appendix C Page 12 of 20 PERFORMANCE INFORMATION AP-CVCS.1, Step 1 OI Form ES-C-1 Performance Step: 13 Check RCP Seal Leakoff Flows: Standard: EXAMINER CUE: Comment: RCP seal leakoff flows -WITHIN THE NORMAL OPERATING RANGE OF FIG-4.0, FIGURE RCP SEAL LEAKOFF RCP seal leakoff flows -ST ABLE The operator observes the 1 A RCP Seal Leakoff flow to be between 1-5 gpm, and compares this with FIG-4.0. The operator observes the 1 B RCP Seal Leakoff flow to be between 1-5 gpm, and compares this with FIG-4.0. When the operator is looking to find FIG-4.0, PROVIDE operator with Handout 3 (FIG-4.0). AP-CVCS.1, Step 1 *1 Performance Step: 14 Evaluate Local Leak Investigation -CVCS SYSTEM INTACT IN AUX BLDG Standard: The operator recognizes that this action is NA and proceeds. SIM DRIVER: If AO directed to investigate leakage in the Aux Building, report that no leakage has been detected in the Aux Building. Comment: 2014 Systems -Control Room JPM C NU REG 1021, Revision 9 Appendix C Page 13 of 20 PERFORMANCE INFORMATION AP-CVCS.1, Step 12/12.a Form ES-C-1 Performance Step: 15 Evaluate Plant Status: Standard: Comment: Performance Step: 16 Standard: Comment:

• Leak location identified The operator recognizes that the leak is in Containment on the normal Charging Line. The operator recognizes that the leak is in Containment on the normal Charging Line. AP-CVCS.1, Step 12.b Check RCS leakage within limits (Refer to leakage surveillance sheet and ITS section 3.4.13) The operator recognizes with HCV-142 closed the leak is isolated and proceeds.

AP-CVCS.1, Step 12.c Performance Step: 17 At least one charging flowpath -AVAILABLE FOR INVENTORY CONTROL Standard: Comment:

• AOV-294
• AOV-392A
• Seal Injection The operator recognizes that the seal injection path is available for inventory

control, and proceeds.

2014 Systems -Control Room JPM C NU REG 1021, Revision 9 Appendix C Page 14 of 20 PERFORMANCE INFORMATION AP-CVCS.1, Step 13 Form ES-C-1 Performance Step: 18 Check Normal Or Excess Letdown -IN SERVICE Standard: The operator recognizes that neither Normal nor Excess Letdown is in service and proceeds to the Step 13 RNO. Comment: Performance Step: 19 Standard: Comment: Performance Step: 20 Standard: Comment: AP-CVCS.1, Step 13 RNO IF normal letdown desired, THEN establish normal letdown. (Refer to ATT-9.0, ATTACHMENT LETDOWN) IF normal letdown NOT available, THEN establish excess letdown if desired (Refer to ATT-9.1, ATTACHMENT EXCESS LID). The operator recognizes that Normal Letdown has been isolated to isolate a leak per this procedure and proceeds to ATT-9.1. ATT-9.1, Step A The following conditions must be met to place excess letdown in service: IA to CNMT -ESTABLISHED CCW-IN SERVICE PRZR level -GREATER THAN 13% The operator observes that Instrument Air to Containment is established. The operator observes that CCW is in service. The operator observes that Pressurizer level is greater than 13%. 2014 Systems -Control Room JPM C NU REG 1021, Revision 9 Appendix C Page 15 of 20 PERFORMANCE. INFORMATION ATT-9.1, Step B/B.1 Form ES-C-1 Performance Step: 21 Establish excess letdown: Standard: Comment: Ensure EXCESS LTDN LOOP A COLD TO Hx, AOV-310 is closed. The operator observes that the AOV-310 Green status light is LIT, and the Red status light is OFF. ATT-9.1, Step B.2 Performance Step: 22 Ensure EXCESS L TDN flow control valve, HCV-123 is closed, demand at 0. Standard: The operator observes that the HCV-123 Controller output is 0. Comment: Performance Step: 23 Standard: Comment: A TT-9.1, Step 8.3 Ensure SEAL OR EXCESS LTDN RETURN ISOL VALVE, MOV-313, is open. The operator observes that the MOV-313 Red status light is LIT, and the Green status light is OFF. 2014 Systems -Control Room JPM C NUREG 1021, Revision 9 Appendix C Page 16 of 20 PERFORMANCE INFORMATION ATT-9.1, Step B.4 Form ES-C-1 -) Performance Step: 24 Place excess letdown divert valve, AOV-312, to DIVERT. Standard: [-/]The operator places the AOV-312 Control Switch to DIVERT, and observes the Red status light is LIT, and the Green status light is OFF. Comment: A TT-9.1, Step B.5 Performance Step: 25 Ensure CCW FROM EX LTDN Hx, AOV-745 -OPEN. Standard: The operator observes that the AOV-745 Red status light is LIT, and the Green status light is OFF. Comment: A TT-9.1, Step B.6 -) Performance Step: 26 Open EXCESS LTDN LOOP A COLD TO HX, AOV-310. Standard: [-/]The operator places the AOV-310 Control Switch to OPEN, and observes the Red status light is LIT, and the Green status light is OFF. Comment: 2014 Systems -Control Room JPM C NU REG 1021, Revision 9 Appendix C --./ Performance Step: 27 Standard: Comment: Page 17 of 20 PERFORMANCE INFORMATION ATT-9.1, Step B .. 7/7.a Form ES-C-1 CAUTION: DIVERTING EXCESS LETDOWN TO RCDT WILL RESULT IN eves HUT LEVEL RISE OF APPROXIMATEL y 4% PER HOUR. Flush approximately 10 gallons to RCDT as follows (3.2 gal/%, PPCS Point ID U003).

• Slowly open EXCESS L TON flow control valve, HCV-123, to maintain excess letdown temperature less than 195°F and pressure less than 100 psig. [--./]The operator calls up PPCS Point LI003. [--./]The operator adjusts the HCV-123 Controller such that output rises above 0. The operator observes Tl-122 less than 195°F. The operator observes Pl-121 less than 100 psig. ATT-9.1, Step B .. 7.b Performance Step: 28 Ensure approximately 1 O gallons is flushed to the RCDT. Standard:

The operator observes the RDCT level rise approximately 3%. Comment: 2014 Systems -Control Room JPM C NUREG 1021, Revision 9 Appendix C '1 Performance Step: 29 Standard: Comment: '1 Performance Step: 30 Standard: Comment: Terminating Cue: STOP TIME: Page 1' 8 of 20 PERFORMANCE INFORMATION ATT-9.1, Step 8.7.c Form ES-C-1 IF RCP seal return has been established, THEN place EXCESS LTDN HX DIVERT TO VCT OR RCDT VALVE, AOV-312, to NORMAL. IF NOT, THEN leave AOV-312 in DIVERT. ['1] The operator recognizes that RCP Seal return has been established and places the AOV-312 Control Switch to NORMAL, and observes the Green status light is LIT, and the Red status light is OFF. ATT-9.1, Step 8.8 Adjust charging pump speed to control PRZR level and labyrinth seal D/P. ['1] The operator simultaneously adjusts HCV-142 and Charging Pump speed to maintain RCP Labyrinth Seal. D/P 15-80 inches, and Przr Level is approaching program level (56% ). Evaluation on this .. IPM is complete. 2014 Systems -Control Room JPM C NUREG 1021, Revision 9 Appendix C Page 19 of 20 VERIFICATION OF COMPLETION Job Performance Measure No.: 2014 Systems -Control Room JPM C Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiner's Signature: Date: Form ES-C-1 2014 Systems -Control Room JPM C NUREG 1021, Revision 9 Appendix C INITIAL CONDITIONS: INITIATING CUE: Form ES-C-1 JPM CUE SHEET

• The Plant is at 100% power.
• Based on plant conditions the crew has entered AP-CVCS.1, "CVCS Leak," and has completed steps 1-5.
• Pressurizer level is stable.
• The leak is believed to be in the Containment and RP has been directed to sample the Containment for entry.
• The HCO is monitoring the automatic VCT makeups that are occurring.

While the CRS and the HCO continue to monitor plant conditions, continue with AP-CVCS .. 1 starting with Step 6 to control RCS inventory to maintain Pressurizer level stable. NU REG 1021, Revision 9 EOP: TIT LE: REV: 01501 AP-eVeS.1 eves LEAK PAGE 3 of 12 STEP ACTION/EXPECTED RESPONSE i-----*-t RESPONSE NOT OBTAINED 1---------. NOTE: o Cond.it:iuns shouJd be evnluated for sitc:i contingency reporting (Refer to EPTP--J .0, GlNNA STATlON EVENT EVAT.UATTON AND CLASSTFICATTON. o A local radiation emergency should be declared for any unexplained area radiation monitor alarm. PRZR Level - LEVEL STABLE \_} IF PRZR 1eve1 Jowerinp,. THEN start l add1tional charging pumps and rais*: speed Lo raise PRZR level to program. l.E. PRZR leVl:'J. continues to J.ower. THEN close letdown isoli1tion AOV-li27 AND c'xcess letdown AOV--310. IF available charging pumps are running at maximum speed with letdown iso1a ted. AND PRZR l eve1 L; lowering. THEN trip the reactor and go to E-0. REACTOR TRIP OR SAFETY INJECTION. EOP: T!Tl E: REV: 01501 AP-CVCS.l eves LEAK PAGE 4 of 12 STEP ACTION/EXPECTED RESPONSE 1-------1 RESPONSE NOT OBTAINED 1----------. NOT!*:: /IF VCT level lowers to ')",{., charging pump su tion will iw:ap to RW:1'1'. This may require a load reduction. VCT Makeup System: /:Xeri fy VCT 1eve1 - TllAN tz:,.1;7,, ,* Lhe following:

1) RMW mode selector switch in AUTO 2) RMW control armed RED LTGllT /1Ll'l' 0check VCT lr:vel: o Level GREATER THAN 20% OR o Level -STAHLE OR RISING ;1. Perfurm the following:

1) Ensure charging pump uuct:i.on a li gn0:d to J\WST

• LCV-l 12H
• LCV-ll2C

2) Go tu Step 3. OPEN CLOSED c. Pr,;rform following:

1) Ensure letdown divert valve. LCV-112A, aligned to VCT. 2) Manually raise VCT makeup flow as follows:

a) Ensure BA transfer pumps and RMW pumps running. h) Adjust RMW flow control valve. HCV--111. t.o i-aise i-;MVJ f J ow. c) Adjusr hori.c acid flow t.o maintain required concentration. fF VC:T level c11n NOT l>e mainlained, THEN refer lo ER-CVCS. 1, REACTOR MAKt.rnP CONTROL MALFUNCTION. if necessary. EOP: r I TLE: REV: 01501 AP-CVCS.l eves LEAI'\ PAGE 5 of 12 STEP ACTION/EXPECTED RESPONSE

---

*-t f\ESPONSE NOT OBTAINED---------.

NOTE: 1\ .load recluctjon may be rf!quirc:d if <2h;1rg,ing pump is nlign<:*d t RWST. Charging Pump Suction To VCT: ,WT level -GREATER THAN 20% charging pumps to VCT n LCV-1J2C open o LCV-Jl2B

a. IF VCT level can NOT be maintained

?,real.er Lha11 .">%. THEN pe1form Lhe following: l) Ensure charging, pump suction altgned to RWST 0 LCV-*112B OJWI1 o LCV-112C closed 2) C:ontJnur:; wi.th Step 4. WHEN VCT level than 20%. THEN do Step 3h. If RCS Leakage In le*akag.e is.indicated in CNMT. > / JllEN peorform t*hE' following: '-1 f/1 k l'NM'I' d. . . . c ec , ra iatHrn rnonJ tors -/:) I

• NORMAL .,J&:i rect PP to samp1 e CNMT for
• R-2
• R-1
• R--lOA
• R-11
• R-12 g,;NMT sump A pump run frequency

.. (C' NORMAL (Refer to l.E'akage , surveillance sheet) r/ c:ntry. fi;JCon t:Lnue with Step ,'.1, ** CNMT L,, clc;ared for c:ntry, HIEN dispatch personnel to investigate C:NMT for RCS leakage. REV: 01501 I [Op AP-CVCS.l eves LEAI\ PAGE 6 of 12 STEP ACTION/EXPECTED RESPONSE

---

'"""

RESPONSE NOT OBTAINED

---

.... * * * * * * * * * * * * * * *

• w * * * * * * * * * ****""-********

CAUTION RADIATION PROTECTION TECHNICIAN SHOULD BE CONSIJLTED PRIOR TO ENTERING A HIGH AIRBORNE AREA. * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * + *

• eifeck If RCS Leakage In AUX , BLDG:
• R-Lj
• R-9
• R-1 OB
• R-13
• R-J l1

. f ,Xux BLDG sump pump run [requency NORMAL (Refer to leakag2 surveillance sheet) *. JAUX BLDG sump tank leak rate -NORMAL (Rc'!fer to 1 surveillance Dis pa Ld1 AO To AUX BLDC To Investigate CVCS Leak (lockerl area keys requir('(l) Appendix C Job Performance Measure Worksheet SIM JPM D Form ES-C-1 2014 Systems -Control Room JPM D (Rev_110314) NUREG 1021, Revision 9 Appendix C Facility: Task Title: Page 2of13 Form ES-C-1 Job Performance Measure Worksheet Ginna Depressurize the RCS During a SGTR Task No.: JPM No.: 2014 Systems -Control Room JPM D (Alternate Path) KIA

Reference:

EPE 038 EA1.04 (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. Provide Candidate with Initial Conditions/Cue {Last Page of this JPM) and Handout 1. Initial Conditions: Initiating Cue: Task Standard:

• The plant has experienced a Steam Generator Tube Rupture.
• The crew has completed E-3, Steam Generator Tube Rupture, through Step 17.
• However, an attempt to re-establish Instrument Air to the Containment has been unsuccessful.
• The RCS has been cooled to target temperature.
• The crew is ready to commence RCS depressurization.

The CRS has directed you to depressurize the RCS to minimize break flow starting with Step 18 of E-3. The operator will determine that Pressurizer Spray and the normal use of the Pressurizer PORVs is not possible, and use ATT-12.0 to open one Pressurizer PORV; and then close the PORV Block Valve when it is recognized that the previously opened Pressurizer PORV has failed OPEN. 2014 Systems -Control Room JPM D NU REG 1021, Revision 9 Appendix C Page 3of13 Job Performance Measure Worksheet Required Materials: MCB Control Switch Key (Green) General

References:

E-3, Steam Generator Tube Rupture, Rev 04800 ATT-12.0 Attachment N2 POHVs, Rev 6 Form ES-C-1 Handouts: Handout 1: Blank copy of E-3, Steam Generator Tube Rupture Handout 2: Attachment 12.0, Attachment N2 PORVS Time Critical Task: NO Validation Time: 15 minutes 2014 Systems -Control Room JPM D NU REG 1021, Revision 9 Appendix C Page 4of13 Form ES-C-1 Job Measure Worksheet SIMULATOR OPERATIONAL GUIDELINES

• Reset the Simulator t.o any 100% power IC
• Insert Malf SGN04B, 500 gpm (SGTR on 'B' SIG)
• Fail Instrument Air Valve to Containment closed (OVR-Dl-MISOSC, False)
• Perform Steps 1-17 of E-3
• Ensure that AOV-5392 is closed
• Ensure PPCS is available
• To insert PORV failures when ATT-12.0 is performed:

o Set Trigger 30 = x08i160a (N2 ARMING VLV SOV-86198 switch to ARM) o Set Trigger 29 = x08i161a (N2 ARMING VLV SOV-8619A switch to ARM) o Insert Malf PZROSB, 100% on Trigger 30 o Insert Malf PZROSA, 100% on Trigger 29

• Place simulator in FREEZE
• Place simulator in RUN when directed by examiner OR
• Initiate to IC-159 (December, 2014)
• Place simulator in RUN
• Place simulator in FREEZE
• Place simulator in RUN when directed by examiner NOTE: The Floor Instructor will need to control BOP during the performance of this JPM. 2014 Systems -Control Room JPM D NU REG 1021, Revision 9

Appendix C Page 5of13 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with a..../) Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1. START TIME: Performance Step: 1 Standard: Comment: Performance Step: 2 Standard: Comment: E-3, Step 18 NOTE: SI ACCUMS may inject during RCS depressurization Depressurize RCS To Minimize Break Flow And Refill PRZR:

• Check the following:
• Ruptured S/G Level -LESS THAN 90% [80% adverse CNMT]
• Any RCP -RUNNING
• IA to CNMT -AVAILABLE The operator reads the Note, and proceeds.

The operator observes that the B S/G is less than 90% (==21%). The operator observes that both RCPs are running. The operator observes that the AOV-5392 Green status light is LIT, and the Red status light is OFF, and proceeds to the Step 18 RNO. E-3, Step 18 RNO Go to Step 19. The operator proceeds to Step 19. 2014 Systems -Control Room JPM D NU REG 1021, Revision 9 Appendix C Performance Step: 3 Standard: Comment: Performance Step: 4 Standard: EXAMINER CUE: Comment: Page 6of13 PERFORMANCE INFORMATION E-3, Step 19/19.a Form ES-C-1 Caution: THE PRT MAY RUPTURE IF A PRZR PORV IS USED TO DEPRESSURIZE THE RCS. THIS MAY RESULT IN ABNORMAL CNMT CONDITIONS. Caution: CYCLING OF THE PRZR PORV SHOULD BE MINIMIZED. Caution: THE UPPEH HEAD REGION MAY VOID DURING RCS DEPRESSURIZATION IF RCPS ARE NOT RUNNING. THIS MAY RESULT IN RAPIDLY RISING PRZR LEVEL. Note: If auxiliary spray is in use, spray flow may be enhanced by closing normal charging valve AOV-294 and normal spray valves. Note: When using PRZR PORV select one with an operable block valve. Depressurize RCS Using PRZR PORV To Minimize Break Flow And Refill PRZR:

• Verify IA to CNMT -AVAILABLE.

The operator reads the three Cautions and proceeds. The operator reads the two Notes and proceeds. The operator observes that the AOV-5392 Green status light is LIT, and the Red status light is OFF, and proceeds to the Step 19 RNO. E-3, Step 19.a RNO Refer to ATT-12.0, ATTACHMENT N2 PORVS to operate PO RVs. The operator refers to ATI-12.0 to operate the Pressurizer PORV, and reviews. When the operator is looking to find ATT-12.0, PROVIDE operator with Handout 2 (ATT-12.0). 2014 Systems -Control Room JPM D NU REG 1021, Revision 9 Appendix C Performance Step: 5 Standard: Comment: Performance Step: 6 Standard: EXAMINER NOTE: Comment: Page 7of13 PERFORMANCE INFORMATION E-3, Step 19.b PRZR PORVs -AT LEAST ONE AVAILABLE Form ES-C-1 The operator observes the PCV-430 Green status light LIT, and the Red status light OFF, and determines that it is available. The operator observes the PCV-431C Green status light LIT, and the Red status light OFF, and determines that it is available. E-3, Step 19.c Open one PRZR PORV until ANY of the following conditions satisfied:

• PRZR level -GREATER THAN 75% [65% adverse CNMT] OR
• RCS pressure

-LESS THAN SATURATION USING FIG-1.0, FIGURE MIN SUBCOOLING OR

• BOTH of the following:
• RCS pressure

--LESS THAN RUPTURED S/G PRESSURE

• PRZR level -GREATER THAN 10% [30% adverse CNMT] The operator refers to ATT-12.0 to operate the Pressurizer PORV. SROs should determine that the Minimum Subcooling stopping criteria is based on 520+/-5°F and 870+/-50 psig (Or actual plant conditions).

Inform the ROs that to stop depressurizing at an RCS pressure 870+/-50 psig based on MINIMUM Subcooling. 2014 Systems -Control Room JPM D NU REG 1021, Revision 9 Appendix C --.) Performance Step: 7 Standard: EXAMINER NOTE: Comment: Page 8of13 PERFORMANCE INFORMATION A TT-12.0, Step A Form ES-C-1 NOTE: If RCS overpressurization accumulator pressure lowers to less than 200 psig, then recharge accumulators using S-29.2, Charging The Reactor Vessel Overpressure Protection System Accumulators with N2. This will require reset of Cl and XY relays for the N2 supply to CNMT, AOV-846. NOTE: For FR-H.1 Bleed and Feed the PORV block valve is not required to be When IA to CNMT NOT available, THEN perform the following to operate one (or both) PRZR PORV (s) in accordance with guidance provided by the procedure step: Select a PORV with an operable block valve, obtain a key for the RCS overpressurization system, and perform the step below:

• PCV-431C:
• Verify block valve MOV-515 -OPEN AND OPERABLE
• Place ACCUM TO SURGE NTK VLV SOV-8616B to OPEN
• PCV-430:
• Verify block valve MOV-516 -OPEN AND OPERABLE
• Place ACCUM TO SURGE NTK VLV SOV-8616A to OPEN The operator reads both Notes and proceeds.

The operator observes the MOV-515 Red status light is LIT, Green status light is OFF. [--.)]The operator places the SOV-8616B Key Control Switch to OPEN. OR The operator observes the MOV-516 Red status light is LIT, Green status light is OFF. [-'1] The operator places the SOV-8616A Key Control Switch to OPEN. These valves have status lights that are NOT operational. The SOVs are located on the rear of the MCB. 2014 Systems -Control Room JPM D NUREG 1021, Revision 9 Appendix C '1 Performance Step: 8 Standard: EXAMINER NOTE: Comment:

• -.J Performance Step: 9 Standard:

Comment: Page 9of13 PERFORMANCE INFORMATION ATT-12.0, Step B Form ES-C-1 To depressurize the RCS in accordance with the guidance provided by the EOP step, perform the following:

• For PCV-431C, place overpressurization system arming switch, N2 ARMING VLV SOV-86198 to ARM
• For PCV-430, place overpressurization system arming switch, N2 ARMING VL.V SOV-8619A to ARM [v!] The operator places the. SOV:-8619B:t(ey c6ntrg1Switch to.**. ***OPEN.

. . * .. . .... , . ... * .. ***"** . . . . . . . OR operator.pl<lcesthe*sov-s619A to .. i OPEN'.' ii* .. * *. i .. I *** : i. .* ** ;* ;::!'"'** ..

• These valves have status lights that are NOT operational.

The PORV that is opened by the Operator will fail OPEN. E-3, Step 19.d Close PRZR PORV The operator observes RCS pressure and PRZR level. The operator compares RCS pressure to FIG-1.0, FIGURE MIN SUBCOOLING [v!] The operator determines that one of the three stop criteria have been met, and attempts to close the PORV (Performance Step 10). 2014 Systems -Control Room JPM D NUREG 1021, Revision 9 Appendix C ';,,/ Performance Step: 10 Standard: Comment: Page 10of13 PERFORMANCE INFORMATION ATT-12.0, Step D Form ES-C-1 WHEN depressurization

complete, THEN close the PORV(s) by performing the foUowing:

• For PCV-431 C:
• Place N2 ARMING VLV SOV-8619B to BLOCK
• Place ACCUM TO SURGE TNK VLV 8616B to CLOSE
• For PCV-430:
• Place N2 ARMING VLV SOV-8619A to BLOCK
• Place ACCUM TO SURGE TNK VLV 8616A to CLOSE [;,,/]The operator places the SOV-8619B Key Control Switch to BLOCK. [;,,/]The operator places the SOV-8616B Key Control Switch to CLOSE. OR [;,,/]The operator places the SOV-8619A Key Control Switch to BLOCK. [;,,/]The operator places the SOV-8616A Key Control Switch to CLOSE. [;,,/]The.operator observes the previously opened PRZR PORV Red status light is LIT, Green status light is OFF, and recognizes that the PORV has failed to Close. 2014 Systems -Control Room JPM D NU REG 1021, Revision 9

Appendix C Page 11 of 13 PERFORMANCE INFORMATION Form ES-C-1 \ EXAMINER NOTE: ALTERNATE PATH DECISION POINT OCCURS IN THE NEXT STEP -'1 Performance Step: 11 Standard: Comment: E-3, Step 19.d RN() IF either PRZR PORV can NOT be closed, THEN close associated block valve. [-'1] If PCV-430 is OPEN, the operator places the MOV-516 to CLOSE, and observes the Green status light is LIT, Red status light is, OFF. OR [-'1] If PCV-431 C is OPEN, the operator places the MOV-515 to CLOSE, and observes the Green status light is LIT, Red status light is OFF. E-3, Step 20 Performance Step: 12 Check RCS Pressure -RISING Standard: The operator observes RCS pressure is rising. Comment: Terminating Cue: Evaluation on this JPM is complete. STOP TIME: 2014 Systems -Control Room JPM D NU REG 1021, Revision 9 Appendix C Page 12 of 13 VERIFICATION OF COMPLETION Job Performance Measure No.: 2014 Systems -Control Room JPM D Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiner's Signature: Date: Form ES-C-1 2014 Systems -Control Room JPM D NU REG 1021, Revision 9 Appendix C INITIAL CONDITIONS: INITIATING CUE: Form ES-C-1 JPM CUE SHEET

• The plant has experienced a Steam Generator Tube Rupture.
• The crew has completed E-3, Steam Generator Tube Rupture, through Step 17.
• However, an attempt to re-establish Instrument Air to the Containment has been unsuccessful.
• The RCS has been cooled to target temperature.
• The crew is ready to commence RCS depressurization.

The CRS has directed you to depressurize the RCS to minimize break flow starting with Step 18 of E-3. NU REG 1021, Revision 9 Appendix C Job Performance Measure SIM JPM E Form ES-C-1 2014 Systems -Control Room JPM E (Rev_110314) NU REG 1021, Revision 9 Appendix C Page 2of17 Job Performance Measure Worksheet Facility: Ginna Task No.: Task Title: Synchronize Generator On-Line with JPM No.: Improper Load Pickup KIA

Reference:

045 A2.17 (2.7*/2.9*) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Form ES-C-1 2014 Systems -Control Room JPM E (Alternate Path) 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. Provide Candidate with Initial Conditions/Cue (Last Page of this JPM} and Handouts 1-2. Initial Conditions: Initiating Cue:

• The generator is being started following a refueling outage.
• The generator is at 1800 rpm and the turbine is fully warmed up.
• The generator output voltage is 19 KV.
• MTC is negative for this Startup.
• The CRS has directed you to synchronize the generator on-line per 0-1.2, Plant Startup From Hot Shutdown to Full Load, steps 6.13.1 through 6.13.10.
• The HCO will control the primary plant. Task Standard:

The operator will synchronizei the Main Generator to the Electrical Grid, and when it is recognized that the Automatic Load Pickup has failed to function, the operator will manually load the Turbine to 40 to 60 MW, without reverse powering the Main Generator. Required Materials: None 2014 Systems -Control Room JPM E NU REG 1021, Revision 9 Appendix C Page 3 of 17 Form ES-C-1 Job Performance Measure Worksheet General

References:

0-1.2, Plant Startup From Hot Shutdown to Full Load, Rev 20101 FIG-13.0, Figure Back Pressure, Rev O Handouts: Time Critical Task: Validation Time: NOTE: Handout 1: 0-1.2, Plant Startup From Hot Shutdown to Full Load (Pages 1-11, 55, and 66-74) Handout 2: 0-1.2, ATT-2, No Load Excitation Limits for#1 and #11 Transformers NO 15 minutes The operators should be pre-briefed in the Briefing Room prior to performance of this JPM. 2014 Systems -Control Room JPM E NU REG 1021, Revision 9 Appendix C Page 4of17 Form ES-C-1 Job Performance Measure Worksheet SIMULATOR OPERATIONAL GUIDELINES

• Reset to IC-8 (Turbine 1800 rpm)
• Withdraw control rods to ensure reactor

> 15% but < 20%

• Ensure FRVs in Auto
• Ensure generator output voltage at 19 KV
• Insert MALF TUR18, 1 MW (Failure of Turbine Auto Load Pickup)
• Ensure Grid frequency

[Remote E-MIS11] is adjusted so that when the examinee places the Synchroscope to ON it is moving slowly in the SLOW direction (e.g. 60.02 Hz). OR

• Ensure Grid voltage [Remote E-MIS10]

is low enough to allow the examinee to adjust incoming voltage to slightly greater than system voltage, while maintaining generator voltage< 19.3 KV (Step 6.13.4)

• Set REM EDS017 to Closed (Sta 13A Man Disconnect 1G13A73)
• Set REM EDS016 to Closed (Sta 13A Man Disconnect 9X13A71)
• Select PBACK on the PPCS Screen in front of the Turbine Control Station.
• FREEZE
• IC 160 (August, 2014)
• Place simulator in RUN.
• Place simulator in FREEZE.
• Select PBACK on the PPCS Screen in front of the Turbine Control Station.
• Place simulator in RUN when directed by examiner.

NOTE: The Simulator/Floor Instructor will need to control Primary Plant during the performance of this JPM. 2014 Systems -Control Room JPM E NUREG 1021, Revision 9 Appendix C Page 5of17 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with a >I) Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handouts 1-2. START TIME: Performance Step: 1 Standard: EXAMINER NOTE: Comment: ..,J.* Performance Step: 2 Standard: EXAMINER NOTE: EXAMINER CUE: Comment: 0-1.2, Step 6.13.1 PLACE synchroscope switch handle in CIRCUIT BKR 1 G 13A72 SYNCHROSCOPE. The operator places synchroscope switch handle in CIRCUIT BKR 1G 13A72 SYNCHROSCOPE. There is a single switch handle that may be placed in either CIRCUIT BKR 1G 13A72 SYNCHROSCOPE, or CIRCUIT BKR 9X 13A72 SYNCHROSCOPE. 0-1.2, Step 6.13.2 Note: WHEN next step is performed, THEN MCB Alarm J-5, #11 OR #12 TRANSFORMER OUT OF SYNCH, will cycle in and out of alarm as the Generator phases in and out of sync with the grid. PLACE CIRCUIT BKR *1G 13A72 SYNCHROSCOPE control switch to ON. The operator reads the Note, and proceeds. [>/]The operator rotates CIRCUIT BKR 1G 13A72 SYNCHROSCOPE control switch clockwise to the ON position. Alarm J-5 may cycle in and out of alarm per the note. (If Alarm J-5 is cycling in and out of alarm): "The CRS gives you permission to allow alarm J-5 to flash." 2014 Systems -Control Room JPM E NU REG 1021, Revision 9 Appendix C --./ Performance Step: 3 Standard: EXAMINER NOTE: Comment: Page 6of17 PERFORMANCE INFORMATION 0-1.2, Step 6.13.3 Form ES-C-1 Note: Synchroscope should be rotating slowly in the FAST (clockwise) direction in the next step. IF Turbine Generator frequency is slightly higher than system frequency, THEN synchroscope should be rotating in the FAST (clockwise) direction. IF rotating counter clockwise, THEN a raise in speed will be required. IF Turbine Generator speed adjustment must be made, THEN PERFORM the following: OTHERWISE, MARK this Step N/A. 1. ADJUST SETTER up OR down 1 rpm. (Turbine EH Control Panel) 2. DEPRESS GO pushbutton. (Turbine EH Control Panel) 3. REPEAT Steps 6.13.3.1AND6.13.3.2 UNTIL synchroscope is rotating slow in the FAST (clockwise) direction. The operator reads the Note, and proceeds.

• The operator observes the SYNCHROSCOPE (MCB right section)
• [vi] The operator adjusts setter up or down 1 rpm and depresses GO pushbutton until synchroscope is rotating slow in the FAST direction.

o Up or down arrow pushbuttons depressed to raise / lower the setter o GO pushbutton depressed to cause the turbine speed to change until the REFERENCE matches the SETTER

• Up, down, and GO pushbuttons are located on EH control panel.
• Digital REFERENCE and SETTER indication is located above the EH control panel.
• It is likely that the operator will need to perform this action TWICE. 2014 Systems -Control Room JPM E NU REG 1021, Revision 9

Appendix C Performance Step: 4 Standard: EXAMINER NOTE: Comment: Page 7of17 PERFORMANCE INFORMATION 0-1.2, Step 6.13.4/4.1 Form ES-C-1 WHEN Turbine is at synchronous speed, THEN REPEAT the following as necessary to ensure generator INCOMING VOLTMETER (GENERATOR) voltage is slightly higher than system RUNNING VOLTMETER (SYSTEM) voltage:

• CHECK voltage on all three phases. The operator rotates the GENERA TOR VOLTMETER switch to each phase position and compares:
• INCOMING VOLTMETER (GENERATOR) voltage to the RUNNING VOLTMETER (SYSTEM) voltage o A-B phase o B-C phase o C-A phase
• INCOMING VOLTMETER (GENERATOR) is located to the left of the SYNCHROSCOPE.
• RUNNING VOLTMETER (SYSTEM) is located to the right of the SYNCHROSCOPE.

2014 Systems -Control Room JPM E NU REG 1021, Revision 9 Appendix C Performance Step: 5 Standard: EXAMINER NOTE: EXAMINER NOTE: Comment: Performance Step: 6 Standard: Comment: Page 8 of 17 PERFORMANCE INFORMATION 0-1.2, Step 6.13.4.2 Form ES-C-1 WHILE maintaining voltage within the acceptable operating region of Attachment 2, No Load Excitation Limits for #1 and #11 Transformers, TRY to adjust BASE ADJUSTER to make INCOMING VOLTMETER (GENERATOR) voltage slightly higher than RUNNING VOLTMETER (SYSTEM) voltage. The operator refers to Attachment 2 The operator observes the INCOMING VOLTMETER (GENERATOR) voltage and RUNNING VOLTMETER (SYSTEM) voltage. The operator places the BASE ADJUSTER to RAISE until INCOMING VOLTMETER (GENERATOR) voltage is slightly higher than RUNNING VOLTMETER (SYSTEM) voltage. The operator does NOT allow GENERA TOR voltage to exceed 19.3 KV (per Attachment

2) Initial IC setup may make the performance of this step unnecessary (removed previous CT status) Voltage will remain within the acceptable operating region of Attachment 2 as long as the Examinee keeps the GENERATOR voltage<

19.3 KV. 0-1.2, Step 6.13.4.3 IF INCOMING VOLTMETER (GENERATOR) voltage CANNOT be made slightly higher than RUNNING VOLTMETER (SYSTEM)

voltage,

...... . The operator marks this step NA. 2014 Systems -Control Room JPM E NU REG 1021, Revision 9 Appendix C Performance Step: 7 Standard: Comment: Performance Step: 8 Standard: Comment: Performance Step: 9 Standard: EXAMINER CUE: (HCO) Comment: Page 9of17 PERFORMANCE INFORMATION 0-1.2, Step 6.13.5 Form ES-C-1 PLACE CIRCUIT BKR 1G 13A72 SYNCHROSCOPE control switch to OFF. The operator Rotates CIRCUIT BKR 1 G 13A72 SYNCHROSCOPE control switch counter clockwise to OFF. 0-1.2, Step 6.13.6 WHEN disconnects are closed at 13A, THEN OBSERVE the following (red) CLOSED lights ILLUMINATED:

• GENERATOR DISCONNECT 1G13A71
• GENERATOR DISCONNECT 9X13A73 The operator observes the 1G13A71 Red status light is LIT and the Green status light is OFF. The operator observes the 9X13A73 Red status light is LIT and the Green status light is OFF. 0-1.2, Step 6.13. 7 ENSURE Reactor power is between 15% to 20%. The operator observes Power Range channels Nl-41 C, Nl-42C, Nl-43C, and Nl-44C between 15% and 20% (Or equivalent).

(If asked to report power level): "Power level is 18 (current power level)". 2014 Systems -Control Room JPM E NU REG 1021, Revision 9 Appendix C Page 10of17 PERFORMANCE INFORMATION 0-1.2, Step 6.13.8 Form ES-C-1 Performance Step: 10 REVIEW CAUTION at beginning of Subsection 6.9. Standard: The operator reads Caution prior to Step 6.9.1, and proceeds. Comment: vi Performance Step: 11 Standard: EXAMINER CUE: Comment: 0-1.2, Step 6.13.9 PLACE CIRCUIT BKR 1G 13A72 SYNCHROSCOPE control switch to ON. [vi] The operator rotates CIRCUIT BKR 1G 13A72 SYNCHROSCOPE control switch clockwise to ON. (If Alarm J-5 is cycling in and out of alarm): "The CRS gives you permission to allow alarm J-5 to flash." 2014 Systems -Control Room JPM E NU REG 1021, Revision 9 Appendix C Performance Step: 12 Standard: EXAMINER NOTE: Comment: Performance Step: 13 Standard: Comment: Page 11 of 17 PERFORMANCE INFORMATION 0-1.2, Step 6.13.10/10.1 Form ES-C-1 Caution: At low MWei output, Turbine loading requirements SHALL be observed PER EOP, FIG-13.0, Figure Back Pressure

• Operation in the Avoid Region SHOULD be minimized.
• Operation in the DO NOT OPERA TE region SHALL be limited to 5 minutes.

PERFORM the following to CLOSE CIRCUIT BKR 1G 13A72 BUS 1 115KV:

• WITH RG&E Energy Control Center concurrence, TRY to adjust BASE ADJUSTER so generator INCOMING VOLTMETER (GENERATOR) voltage is slightly higher than system RUNNING VOLTMETER (SYSTEM) voltage as indicated on all three phases. The operator refers to FIG-13.0 or calls up PBACK on the PPCS. The operator the INCOMING VOLTMETER (GENERATOR) voltage and RUNNING VOLTMETER (SYSTEM) voltage and determines that no adjustment is needed. Completed previously.

Further adjustment should not be required. 0-1.2, Step 6.13.10.2 IF INCOMING VOLTMETER (GENERATOR) voltage CANNOT be adjusted slightly higher than system RUNNING VOLTMETER (SYSTEM)

voltage,

..... . The operator Marks 6.13.10.2. a and b N/A. 2014 Systems -Control Room JPM E NU REG 1021, Revision 9 Appendix C Performance Step: 14 Standard: Comment: Page 12 of 17 PERFORMANCE INFORMATION 0-1.2, Step 6.13.10.3 Form ES-C-1 REVIEW Steps 6.13.10.4 thru 6.13.10.6 prior to closing CIRCUIT BKR 1 G 13A72 BUS 1 115KV to ensure timely actions are taken for automatic load pickup to preclude a generator trip from reverse power. The operator reviews Steps 6.13.10.4 thru 6.13.10.6. 0-1.2, Step 6.13.10.4 Note: MCB Alarm J-*5, #11 or #12 TRANSFORMER OUT OF SYNCH, will stay EXTINGUISHED during performance of next step . ...J . Performance Step: 15 WHEN synchroscope rotating slow in the FAST (clockwise) direction AND approaching 12 o'clock position, THEN CLOSE Cl RCU IT BKR 1 G 13A 72 BUS 1 115KV so breaker closes at the approximate point of synchronism ( 12 o'clock).

• RECORD time of closure Standard:

The operator observes the synchroscope. EXAMINER NOTE: EXAMINER CUE: Comment: [....f] The operator rotates 1 G 13A 72 breaker pistol-grip switch clockwise to the CLOSE position when the synchroscope is approaching 12 o'clock. The operator observes the 1 G 13A72 Red status lights LIT, Green status lights OFF. The operator records time of closure. Examinee may not record breaker closure time until after automatic load pickup is verified. This is acceptable to ensure timely actions are taken for automatic load pickup to preclude a generator trip from reverse power. IF the operator communicates actions to the CRS, as CRS, acknowledge. 2014 Systems -Control Room JPM E NUREG 1021, Revision 9 Appendix C Page 13 of 17 PERFORMANCE INFORMATION Form ES-C-1 EXAMINER NOTE: ALTERNATE PATH DECISION POINT OCCURS IN THE NEXT STEP Performance Step: 16 Standard: Comment: 0-1.2, Step 6.13.10.5 Note: Load is to be maintained between 40 to 60 MW UNTIL hold time in Step 6.14.5.2 is completed. VERIFY Automatic load pickup occurs within approximately 10 seconds. The operator observes Generator load and determines that automatic load pickup is NOT raising load to the expected range. 2014 Systems -Control Room JPM E NU REG 1021, Revision 9 Appendix C Page 14of17 PERFORMANCE INFORMATION 0-1.2, Step 6.13.10.6 Form ES-C-1 ..J Performance Step: 17 IF automatic load pickup does NOT occur within approximately 10 seconds, THEN PERFORM the following: Standard: EXAMINER CUE: EXAMINER NOTE: Comment: Performance Step: 18 Standard: Comment: OTHERWISE, MARK this Step N/A. a. DEPRESS TURB. MANUAL pushbutton. (Turbine EH Control Panel) b. INTERMITTENTLY DEPRESS the following pushbuttons as necessary to adjust generator gross load between 40 to 60 MW:

• MANUAL CONTROL VALVE LOWER
• MANUAL CONTROL VALVE RAISE [-/]The operator depresses TURB. MANUAL pushbutton.

The operator observes OPER PAN light off and TURB MANUAL light is LIT. The operator observes digital Generator Gross MW indication. [-/] The operator intermittently depresses the RAISE pushbutton to adjust generator gross load to between 40 to 60 MW. IF the operator communicates actions to the CRS, as CRS, acknowledge. The Main Generator will Reverse Power in about 40 seconds if the operator does NOT take this action. 0-1.2, Step 6.13.10.7 PLACE CIRCUIT BKR 11G 13A72 SYNCHROSCOPE control switch to OFF. The operator rotates CIRCUIT BKR 1 G 13A72 SYNCHROSCOPE control switch counter clockwise to the OFF position. 2014 Systems -Control Room JPM E NU REG 1021, Revision 9 Appendix C Performance Step: 19 Standard: Comment: Terminating Cue: STOP TIME: Page of 17 PERFORMANCE INFORMATION 0-1.2, Step 6.13.10.8 Form ES-C-1 REMOVE synchroscope switch handle from CIRCUIT BKR 1 G 13A72 SYNCHROSCOPE. The operator removes synchroscope switch handle from CIRCUIT BKR 1G 13A72 SYNCHROSCOPE. Evaluation on this JPM is complete. 2014 Systems -Control Room JPM E NU REG 1021, Revision 9 Appendix C Page 16of17 VERIFICATION OF COMPLETION Job Performance Measure No.: 2014 Systems -Control Room JPM E Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiner's Signature: Date: Form ES-C-1 2014 Systems -Control Room JPM E NUREG 1021, Revision 9 Appendix C INITIAL CONDITIONS: INITIATING CUE: Form ES-C-1 JPM CUE SHEET

• The generator is being started following a refueling outage.
• The generator is at 1800 rpm and the turbine is fully warmed up.
• The generator output voltage is 19 KV.
• MTC is negative for this Startup.
• The CRS has directed you to synchronize the generator line per 0-1.2, Plant Startup From Hot Shutdown to Full Load, steps 6.13.1 through 6.13.10.
• The HCO will control the primary plant. NUREG 1021, Revision 9

Appendix C Job Performance Measure Worksheet SIM JPM F Form ES-C-1 2014 Systems -Control Room JPM F (Rev_110314) NU REG 1021, Revision 9 Appendix C Facility: Task Title: Pagie 2of13 Job Performance Measure Worksheet Ginna Task No.: Continuous Rod Motion During Re-JPM No.: alignment of Misaligned Control Rod Form ES-C-1 2014 Systems -Control Room JPM F (Alternate Path) KIA

Reference:

001 A4.06 (2.9/3.2) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: x Classroom Simulator x Plant ---READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1. Initial Conditions: Initiating Cue: Task Standard:

• While performing control rod testing in accordance with STP-0-1, Rod Control System, Shutdown Bank Rod 111 failed to move inward with the rest of the Shutdown Bank rods.
• l&C was notified, and a control circuit card was replaced.

Follow up readings show the circuit was repaired successfully.

• ER-RCC.2, Restoring a Misaligned RCC, has been entered to restore the misaligned rod. ER-RCC.2 has been completed up to the start of Section 6.2.
• The CRS has directed you to continue rod restoration per Section 6.2 of ER-RCC.2.
• The CO will control the secondary plant. The operator will move the misaligned rod to a position in the core lower than its associated bank, and then realign the Shutdown Bank with the misaligned rod. While aligning the Shutdown Bank with the misaligned rod, the operator will diagnose a continuous rod insertion accident and manually trip the reactor.

2014 Systems -Control Room JPM F NU REG 1021, Revision 9 Appendix C Page 3of13 Form ES-C-1 Job Performance Measure Worksheet Required Materials: Lift Coil Cabinet Key (White) General

References:

ER-RCC.2, Restoring a Misaligned RCC, Rev 01701 Handouts: Time Critical Task: Validation Time: AP-RCC.1, Continuous Control Rod Withdrawal/Insertion, Rev 11 E-0, Reactor Trip Or Safety Injection, Rev 04602 A-503.1, Emergency and Abnormal Operating Procedures Users Guide, Rev 04409 Handout 1: Blank copy of ER-RCC.1, Restoring a Misaligned RCC. Handout 2: Blank copy of AP--RCC.1, Continuous Control Rod Withd rawa I/Insertion NO 15 minutes 2014 Systems -Control Room JPM F NU REG 1021, Revision 9 Appendix C Page 4of13 Form ES-C-1 Job Performance Measure Worksheet SIMULATOR OPERATIONAL GUIDELINES

• Place simulator in IC-27, 70% power
• Ensure the Shutdown Banks are selected on the MRPI Display Screen.
• Insert MALF ROD03-111, UNTRIPPABLE (rod 111, no motion)
• Insert Shutdown Bank until a 12 step deviation occurs, ensure Step Counters matched and less than 212 Steps, and clear MALF ROD3 on Rod 111
• Adjust turbine as necessary for Tavg control, plant stabilization
• Insert OVR-Dl-ROD02B, TRUE (Uncontrolled Rod Motion on IN SIGNAL) on Trigger #1 . *
• FREEZE OR
• IC-161 (December, 2014)
• Verify that Step Counters and RBU correct.
• Place simulator in RUN
• Place simulator in FREEZE
• Place simulator in RUN when directed by examiner NOTE: The Floor Instructor will need to ccmtrol Secondary Plant during the performance of this JPM at Step 8. The SIM DRIVER will need to operate Trigger #1 at Step 12 of this JPM. 2014 Systems -Control Room JPM F NU REG 1021, Revision 9

Appendix C Page 5 of 13 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with a '1) Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1. START TIME: Performance Step: 1 Standard: Comment: Performance Step: 2 Standard: Comment: Performance Step: 3 Standard: Comment: ER-RCC.2, Step 6.2.1 IF affected bank group step counters not in agreement, THEN STEP RODS OUT step. The operator observes Shutdown Bank A Step Counters for Group 1 and 2 are both 211 Steps. ER-RCC.2, Step 6.2.2 RECORD the MCB step counter position for the affected group. Bank ---Steps __ _ The operator observes the Shutdown Bank step counters, and records the Bank as "'Shutdown" and the Steps as "211 ". ER-RCC.2, Step 6.2.3 PLACE control rod bank selector switch to the affected bank. The operator observ13s the Control Rod Bank Selector Switch is in the SBA. 2014 Systems -Control Room JPM F NUREG 1021, Revision 9 Appendix C Performance Step: 4 Standard: Comment: --.j Performance Step: 5 Standard: EXAMINER NOTE: Comment: Page fi of 13 PERFORMANCE INFORMATION ER-RCC.2, Step 6.2 .. 4 IF the misaligned RCC is in a Control Bank ..... . Form ES-C-1 The operator recognizes that this step is Not Applicable and proceeds. ER-RCC.2, Step 6.2.5 DISCONNECT all lift coils for the affected bank except the one for the misaligned RCC. The operator obtains the Lift Coil Cabinet Key. [-'1] The operator opens the Lift Coil Switch Cabinet and places the Disconnect Switch for Control Rods E3, C9, K5, 13, C5, E11 and K9 in the DOWN position. The TOGGLE SWITCH is above the Nomenclature in the Lift Coil Switch Cabinet. 2014 Systems -Control Room JPM F NUREG 1021, Revision 9 Appendix C -V Performance Step: 6 Standard: EXAMINER NOTE: Comment: Performance Step: 7 Standard: Comment: Page 7of13 PERFORMANCE INFORMATION ER-RCC.2, Step 6.2.Ei/6.2.6.1 Form ES-C-1 Note: To determine if a misaligned rod is moving, a MRPI transition should occur within 12 steps. Note: Alarm C-30, Rod Control Urgent Failure Rod Stop will annunciate as insertion starts. PERFORM the following to align the RCC with its bank position: INSERT the misaligned RCC until it transitions to one MRPI position below its bank. The operator reads both Notes and proceeds. ["'] The operator places the Rod Control (In/Hold/Out) Switch to IN and observes MRPI for Control Rod 111 to make the first transition at 212 Steps. ["']The operator releases the Rod Control (In/Hold/Out) Switch when the MRPI display for Control Rod 111 transitions to 200 Steps. The operator acknowledges AR-C-30, Rod Control Urgent Failure Rod Stop, and notes that this is an expected alarm. The operator observes MRPI (or equivalent) and determines that Rod 111 stops moving. The other rods in Shutdown Bank A are at 212 Steps. ER-RCC.2, Step 6.2.6.2 IF rod will NOT move, ..... The operator recognizes that the condition is NOT met, and proceeds. 2014 Systems -Control Room JPM F NU REG 1021, Revision 9 Appendix C Performance Step: 8 Standard: Floor Instructor: Comment: ...J. Performance Step: 9 Standard: Comment: Page 8of13 PERFORMANCE INFORMATION ER-RCC.2, Step 6.2.6.3 LOWER Turbine Load to match Tavg to Tref. Form ES-C-1 The operator requests that the BOP match Tavg and Tref. Functioning as the BOP, adjust Turbine Load as needed to match Tavg and Tref. ER-RCC.2, Step 6.2 .. 6.4 RECONNECT all lift coils on affected bank . The operator obtains the Lift Coil Cabinet Key. [...J] The operator opens the Lift Coil Cabinet and places the Disconnect Switch for Control Rods E3, C9, K5, 13, C5, E11 and K9 in the UP position. ER-RCC.2, Step 6.2.6.5 ...j Performance Step: 1 o DISCONNECT the lift coil for the misaligned RCC. Standard: The operator obtains the Lift Coil Cabinet Key. Comment: [...J] The operator opens the Lift Coil Cabinet and places the Disconnect Switch for Control Rod 111 in the DOWN position. 2014 Systems -Control Room JPM F NU REG 1021, Revision 9 Appendix C -.../ Performance Step: 11 Standard: Comment: Page 9of13 PERFORMANCE !INFORMATION ER-RCC.2, Step 6.2.6.6 Form ES-C-1 Note: The Rod Control alarm reset pushbutton will reset urgent failure alarms without resetting the counters. Note: The alarm reset pushbutton also removes the Pulser inhibits for manual andl auto rod operation, and the lockups for the stationary and moveable grippers. To ensure stationary gripper engagement, riesetting the urgent failure places the stationary coil on hi voltage initially, then low voltage. RESET Urgent Failure alarm by pushing the ROD CONTROL ALARM RESET pushbutton. The operator reads both Notes and proceeds. [-.../] The operator depresses the ROD CONTROL ALARM RESET pushbutton, and acknowledges that AR-C-30 has cleared. 2014 Systems -Control Room JPM F NUREG 1021, Revision 9 Appendix C Page 10 of 13 PERFORMANCE INFORMATION Form ES-C-1 EXAMINER NOTE: ALTERNATE PATH DECISION POINT OCCURS IN THE NEXT STEP '1 Performance Step: 12 Standard: SIM DRIVER: EXAMINER CUE: EXAMINER NOTE: Comment: ER-RCC.2, Step 6.2.6.7 INSERT the affected bank to the same MRPI transition as its misaligned rod The operator places the Rod Control (In/Hold/Out) Switch to IN and observes MRPI for the Shutdown Bank Rods (Except Control Rod 111) transitions to 200, and then releases the Switch. After Operator has initiated rod motion, INSERT Trigger #1 The operator observes that the Shutdown Bank rods continue to insert after the Rod Control (In/Hold/Out) Switch has been released,*and transitions to AP-RCC.1. The operator may attempt to place the Rod Control bank Select Switch to MANUAL before entering AP-RCC.1. When it is apparent that the operator is looking for RCC.1, provide Handout 2 to the operator. Based on CNG-OP-1.01-1000 (Conduct of Operations)

criteria, the operator may manually trip the reactor without addressing AP-RRC.1.

If so, move to JPM Step 15. 2014 Systems -Control Room JPM F NU REG 1021, Revision 9 Appendix C Page 11 of 13 PERFORMANCE INFORMATION AP-RCC.1, Step 1.a-c Form ES-C-1 Performance Step: 13 Evaluate Rod Control System Operability: Standard: Comment: '1 Performance Step: 14 Standard: EXAMINER NOTE: Comment: Terminating Cue: STOP TIME: Check turbine load ** STABLE Place Rods to MANUAL Verify control rod motion stops The operator places the Control Rod Bank Selector Switch to MANUAL, and observes that the Shutdown Bank Controls Rods are still moving, and proceeds to the Step 1.c RNO. AP-RCC.1, Step 1.c RNO Manually trip the reactor and go to E-0, REACTOR TRIP or SAFETY INJECTION. [-VJ The operator manually trips the reactor by depressing one of the Reactor Emergency Trip pushbuttons, and begins to perform the Immediate Actions of E-0. There are two Reactor Emergency Trip pushbuttons either of which will manually trip the reactor when depressed. Evaluation on this JPM is complete. 2014 Systems -Control Room JPM F NU REG 1021, Revision 9 Appendix C Page 12 of 13 VERIFICATION OF COMPLETION Job Performance Measure No.: 2014 Systems -Control Room JPM F Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiner's Signature: Date: Form ES-C-1 2014 Systems -Control Room JPM F NUREG 1021, Revision 9 Appendix C INITIAL CONDITIONS: INITIATING CUE: Form ES-C-1 JPM CUE SHEET

• While performing control rod testing in accordance with STP-0-1, Rod Control System, Shutdown Bank Rod 111 failed to move inward with the rest of the Shutdown Bank rods.
• l&C was notified, and a control circuit card was replaced.

Follow up readings show the circuit was repaired successfully.

• ER-RCC.2, Restoring a Misaligned RCC, has been entered to restore the misaligned rod. ER-RCC.2 has been completed up to the start of Section 6.2.
• The CRS has directed you to continue rod restoration per Section 6.2 of ER-RCC.2.
• The CO will control the secondary plant. NU REG 1021, Revision 9

Appendix C Job Performance Measure Worksheet SIM JPM G Form ES-C-1 2014 Systems -Control Room JPM G (Rev_110314) NU REG 1021, Revision 9 Appendix C Facility: Task Title: Page 2of16 Form ES-C-1 Job Performance Measure Worksheet Ginna Transfer Instrument Bus B to Normal Supply Task No.: JPM No.: 2014 Systems -Control Room JPM G (Alternate Path) KIA

Reference:

062 A 1.03 (2.5/2.8) 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. Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1. Initial Conditions: Initiating Cue: Task Standard:

• The B Instrument Bus has been on the Maintenance Power supply for the last four hours to allow completion of maintenance on the normal supply transformer.
• Maintenance has been completed and the Hold Clearance has been removed.
• It is now desired to restore the B Instrument Bus to its normal power supply.
• There are no failed or defeated protection channels.

The CRS has directed you to transfer the "B" Instrument Bus from the Maintenance power supply to the normal power supply per Section 6.3 of ER-INST.3, Instrument Bus Power Restoration. The operator will restore Instrument Bus B to its normal power supply in accordance with ER-INST.3, and take manual control of the Pressurizer Pressure Controller ( 431 K) to stabilize Pressurizer

pressure, when it is recognized that the controller has failed in AUTO. 2014 Systems -Control Room JPM G NUREG 1021, Revision 9

Appendix C Page 3 of 16 Job Performance Measure Worksheet Required Materials: Protection Rack Key Instrument Bus/DC Cabinet Key General

References:

ER-INST.3, Instrument Bus Power Restoration, Rev 01200 CNG-OP-1.01-1000, Conduct of Operations, Rev 01000 Form ES-C-1 Handouts: Handout 1: Blank copy of ER-INST.3, Instrument Bus Power Restoration. Time Critical Task: NO Validation Time: 20 minutes 2014 Systems -Control Room JPM G NU REG 1021, Revision 9 Appendix C Page 4 of 16 Form ES-C-1 Job Performance Measure Worksheet SIMULATOR OPERATIONAL GUIDELINES

• Initiate to any 100% IC
• Align the B Instrument Bus to the Maintenance power supply in accordance with Section 6.2 of ER-INST.3
• Insert MALF PZR04 at 100% on Trigger #1 (PRZR Master Pressure Control failure)
• FREEZE the Simulator OR
• IC 162 (December, 2014)
• Place simulator in RUN
• Place simulator in FREEZE
• Place simulator in RUN when directed by examiner.

NOTE: The Simulator/Floor Instructor will need to control the BOP during the performance of this JPM. 2014 Systems -Control Room JPM G NUREG 1021, Revision 9 Appendix C Page 5 of 16 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with Provide Candidate with Initial Conditions/Cue {Last Page of this JPM) and Handout 1. START TIME: Performance Step: 1 Standard: Comment: ER-INST.3, Step 6.3.1 Note: IF a turbine runback occurs, THEN GO TO AP-TURB.2, TURBINE LOAD REJECTION. Note: REFER TO Attachment 5, INSTRUMENT POWER SUPPLIES for equipment that could be affected by the swap of power supplies. Note: REFER TO P-10, INSTRUMENT FAILURE REFERENCE MANUAL (Appendix L) for additional information relating to Instrument Bus failures. Note: REFER TO P-12, ELECTRICAL SYSTEMS PRECAUTIONS, LIMITATIONS, AND SETPOINTS for additional information relating to instrument busses. Note: Drawing 3201-0102, 120V AC INSTRUMENT BUS LINE DIAGRAM can be referenced for information on the Instrument Bus Power Supplies. VERIFY that normal foed is available as follows:

• Inst Bus A -Supply voltage approximately 120 volts (El/INVTCVTA, above Inst Bus A).
• Inst Bus B-Annunciator E-14, LOSS B INSTR. BUS, extinguished.
• Inst Bus C -Supply voltage approximately 120 volts (El/INVTCVTB, above Inst Bus C).
• Inst Bus D -Annunciator E-30, LOSS D INSTR. BUS, extinguished The operator reads the Notes, and proceeds.

The operator observes that Instrument Bus A Supply Voltage is 120 Volts. The operator observes that E-14 is NOT LIT. The operator observes that Instrument Bus C Supply Voltage is 120 Volts. The operator observes that E-30 is NOT LIT. 2014 Systems -Control Room JPM G NU REG 1021, Revision 9 Appendix C ...J Performance Step: 2 Standard: Comment: .../. Performance Step: 3 Standard: Comment: Page 6of16 PERFORMANCE INFORMATION ER-INST.3, Step 6.3.2 Form ES-C-1 PLACE Rod Control Bank selector switch to MANUAL. [\i] The operator places Rod Control Bank Selector Switch to "M" (MANUAL) position. ER-INST.3, Step 6.3.3 REFER to the appropriate attachment for transfer of Instrument Bus power supply

• Attachment Instrument Bus A
• Attachment Instrument Bus B
• Attachment Instrument Bus C
• Attachment Instrument Bus D ['1] The operator refers to Attachment 2, Attachment Instrument Bus B. 2014 Systems -Control Room JPM G NU REG 1021, Revision 9

Appendix C Performance Step: 4 Standard: Comment:

• • ...j Performance Step: 5 Standard:

Comment: Page 7 of 16 PERFORMANCE INFORMATION ER-INST.3, Attachment 2, Step 1.0 Form ES-C-1 Caution: IF the reactor trip breakers are CLOSED AND Intermediate Range NIS trips are NOT BLOCKED, THEN transfer of INSTRUMENT BUS B power supply may result in a Reactor Trip. Note: Various single channel alarms will sound and can be reset as soon as power supply is transferred. VERIFY that any failed or defeated protection channels will not conflict with the Instrument Bus transfer to cause a Reactor Trip. Refer to Attachment e;, INSTRUMENT POWER SUPPLIES The operator reads the Caution and Note, and proceeds. The operator recognizes that there are no failed or defeated protection channels at the present time. ER-INST.3, Attachment 2, Step 2.0/2.1 To prepare for transfer, PERFORM the following: PLACE CHARGING PUMP SPEED CONTROLLERS (MCB) in MANUAL. The operator places the A Charging Pump controller mode select switch from AUTO to BALANCE. The operator balances controller output to "O" by adjusting manual control knob {Lower black knob). [\!']The operator places the A Charging Pump controller mode select switch in MANUAL. 2014 Systems -Control Room JPM G NUREG 1021, Revision 9 Appendix C "' Performance Step: 6 Standard: Comment: Performance Step: 7 Standard: EXAMINER NOTE: Comment: Page 8 of 16 PERFORMANCE INFORMATION ER-INST.3, Attachment 2, Step 2.2 Form ES-C-1 PLACE PRZR LEVEL DEFEAT switch L/428A (PLP) in defeat-2. ['/] The operator obtains Protection Rack Key and opens PLP PRZR PRESS and LEVEL Cabinet Door. ['/] The operator places the Przr Level Defeat Switch L/428A (PLP) in defeat-2. ER-INST.3, Attachment 2, Step 2.3 PLACE one Charging Pump (MCB) in AUTO, if desired. The operator places controller mode select switch from MANUAL to BALANCE. The operator balances controller output to "O" by adjusting manual control knob (Lower black knob). The operator places controller mode select switch in AUTO. The operator may choose to not place the controller in AUTO at this time. 2014 Systems -Control Room JPM G NUREG 1021, Revision 9 Appendix C "1. Performance Step: 8 Standard: Comment: "1 Performance Step: 9 Standard: Comment: Page 9 of 16 PERFORMANCE INFORMATION ER-INST.3, Attachment 2, Step 2.4 Form ES-C-1 PLACE PRZR PRESS CONTROLLER 431K in MANUAL. The operator places controller mode select switch from AUTO to BALANCE. The operator balances controller output to "O" by adjusting manual control knob (Lower black knob). [\!'] The operator places controller mode select switch in MANUAL. ER-INST.3, Attachment 2, Step 2.5 PLACE PRESSURIZER PRESSURE DEFEAT switch P/429A in defeat-2 (PLP). [\!']The operator places Pressurizer Pressure Defeat Switch P\429A in Defeat-2. [\!'] The operator closes and locks cabinet door. ER-INST.3, Attachment 2, Step 2.6 "1 Performance Step: 10 PLACE PRZR PRESS CONTROLLER 431 K (MCB) in AUTO. Standard: The operator places controller mode select switch from MANUAL to BALANCE. Comment: The operator balances controller output to "O" by adjusting manual control knob (Lower black knob). [\!']The operator places controller mode select switch in AUTO. 2014 Systems -Control Room JPM G NU REG 1021, Revision 9 Appendix C Page 10of16 PERFORMANCE INFORMATION ER-INST.3, Attachment 2, Step 3.0 Form ES-C-1 .'1 Performance Step: 11 TRANSFER Instrument Bus power supply as follows: Standard: Comment:

• IF on NORMAL FEED AND MAINTENANCE FEED desired, THEN TRANSFER to MAINTENANCE.
• IF on MAINTENANCE FEED AND NORMAL FEED desired, THEN TRANSFER to NORMAL {'1] The operator obtains the Instrument Bus/DC Cabinet Key and opens the Instrument Bus B door. {'1] The operator pushes mechanically interlocked breakers from Maintenance closed/Normal open to Normal closed/Maintenance open. ER-INST.3, Attachment 2, Step 4.0/4.1 ,;_J* Performance Step: 12 PERFORM the following to restore controls to normal: Standard:

EXAMINER NOTE: Comment: PLACE CHARGING PUMP SPEED CONTROLLERS in MANUAL. The operator places controller mode select switch from AUTO to BALANCE. The operator balances controller output to "O" by adjusting manual control knob (lower black knob). ['1] The operator places controller mode select switch in MANUAL. The Charging Controller may already be in MANUAL if it was NOT desired to it in AUTO at Step 2.3. IF so, the Step is NOT CRITCAL. 2014 Systems -Control Room JPM G NUREG 1021, Revision 9 Appendix C '1

• Performance Step: 13 Standard:

Comment: Page 11 of 16 PERFORMANCE INFORMATION ER-INST.3, Attachment 2, Step 4.2 Form ES-C-1 PLACE PRZR LEVEL DEFEAT switch, U428A (PLP) in NORMAL. [\/] The operator unlocks and opens PLP PRZR PRESS & LEVEL rack cabinet door. {'1] The operator places Przr Level Defeat Switch, L/428A in NORMAL. ER-INST.3, Attachment 2, Step 4.3 Performance Step: 14 PLACE one Charging Pump in AUTO (MCB), if desired. Standard: The operator places controller mode select switch from MANUAL to BALANCE. EXAMINER NOTE: Comment: The operator balances controller output to "O" by adjusting manual control knob (Lower black knob). The operator places controller mode select switch in AUTO. The operator may choose to not place the controller in AUTO at this time. 2014 Systems -Control Room JPM G NU REG 1021, Revision 9 Appendix C Page 12 of 16 PERFORMANCE INFORMATION ER-INST.3, Attachment 2, Step 4.4 Form ES-C-1 >/ Performance Step: 15 PLACE PRZR PRESS CONTROLLER 431K (MCB) in MANUAL. Standard: The operator places controller mode select switch from AUTO to BALANCE. Comment: '1. Performance Step: 16 Standard: Comment: The operator balances controller output to "O" by adjusting manual control knob (Lower black knob). [>/] The operator places controller mode select switch in MANUAL. ER-INST.3, Attachment 2, Step 4.5 PLACE PRESSURIZER PRESSURE DEFEAT switch P/429A (PLP) in NORMAL. [>/]The operator places Pressurizer Pressure Defeat Switch P/429A in Normal. 2014 Systems -Control Room JPM G NU REG 1021, Revision 9 Appendix C Page 13of16 PERFORMANCE INFORMATION Form ES-C-1 I EXAMINER NOTE: ALTERNATE PATH DECISION POINT OCCURS IN THE NEXT STEP ER-INST.3, Attachment 2, Step 4.6 Performance Step: 17 PLACE PRZR PRESS CONTROLLER 431K (MCB) in AUTO. Standard: The operator places controller mode select switch from MANUAL to BALANCE. SIM DRIVER: Comment: The operator balances controller output to "O" by adjusting manual control knob (Lower black knob). The operator places controller mode select switch in AUTO. Simulator Instructor operate Trigger #1 when operator places controller in AUTO. 2014 Systems -Control Room JPM G NU REG 1021, Revision 9 Appendix C -.J Performance Step: 18 Standard: EXAMINER NOTE: Comment: Terminating Cue: STOP TIME: Page 14of16 PERFORMANCE INFORMATION CNG-OP-1.01-1000, Step 5.10.C.2/3 Form ES-C-1 Recognize failed controller, take manual control and adjust controller output manually to maintain Przr pressure within normal band. The operator recognizes that the controller has failed in AUTO. [-.J] The operator places controller mode select switch in MANUAL. (-.J] The operator adjusts the controller output to restore Przr pressure within normal band. According to CNG-OP-1.01-1000, Section 5.10.C.2&3, Transients induced by the malfunction of an automatic system should be terminated by operator action to establish manual control with a proper demand signal. The need and intent to place a controller into manual operation should be communicated to the CRS before taking this action. Evaluation on this JPM is complete. 2014 Systems -Control Room JPM G NUREG 1021, Revision 9 Appendix C Page 15of16 VERIFICATION OF COMPLETION Job Performance Measure No.: 2014 Systems -Control Room JPM G Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiner's Signature: Date: Form ES-C-1 2014 Systems -Control Room JPM G NU REG 1021, Revision 9 Appendix C INITIAL CONDITIONS: INITIATING CUE: Form ES-C-1 JPM CUE SHEET

• The B Instrument Bus has been on the Maintenance Power supply for the last four hours to allow completion of maintenance on the normal supply transformer.
• Maintenance has been completed and the Hold Clearance has been removed.
• It is now desired to restore the B Instrument Bus to its normal power supply.
• There are no failed or defeated protection channels.

The CRS has directed you to tra'nsfer the "B" Instrument Bus from the Maintenance power supply to the normal power supply per Section 6.3 of ER-INST.3, Instrument Bus Power Restoration. NU REG 1021, Revision 9 Appendix C Job Performance Measure Worksheet SIM JPM H Form ES-C-1 2014 Systems -Control Room JPM H (Rev_ 110314) NU REG 1021, Revision 9 Appendix C Facility: Task Title: Page 2 of 15 Form ES-C-1 Job Performance MHasure Worksheet Ginna Defeat Failed RCS Temperature Channel Task No.: JPM No.: 2014 Systems -Control Room JPM H KIA

Reference:

016 A4.01 (2.9/2.8) 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. Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1. Initial Conditions: Initiating Cue:

• The plant was operating at 100% power when Tl-402 failed high.
• The crew took all the appropriate actions and the plant is stable at current plant conditions.
• The CRS has directed you to defeat the affected RCS temperature channel per Attachment 2 of ER-INST.1, Reactor Protection Bistable Defeat After Instrumentation Loop Failure.
• For JPM performance, you are NOT expected to perform any instrument defeat briefings.

Task Standard: The operator will defeat the failed channel in accordance with INST.1. Required Materials: Cabinet Keys General

References:

ER-INST.1, Reactor Protection Bistable Defeat After Instrumentation Loop Failure, Rev 03605 2014 Systems -Control Room JPM H NU REG 1021, Revision 9 Appendix C Handouts: Time Critical Task: Validation Time: Page 3of15 Form ES-C-1 Job Performance Measure Worksheet Handout 1: Blank copy of Attachment 2 of ER-INST.1, Reactor Protection Bistable Defeat After Instrumentation Loop Failure. NO 13 minutes 2014 Systems -Control Room JPM H NU REG 1021, Revision 9 Appendix C Page 4of15 Form ES-C-1 Job Performance Measure Worksheet SIMULATOR OPERATIONAL GUIDELINES

• Simulator reset to IC-19
• Insert MALF RCS11 B, 650 (Tl-402 -That-Fails High)
• Place rods in Manual
• Place both running Charging Pumps in Manual
• FREEZE the Simulator OR
• IC 163 (December, 2014)
• Place simulator in RUN
• Place simulator in FREEZE
• Place simulator in RUN when directed by examiner.

NOTE: The Simulator/Floor Instructor will need to control the BOP during the performance of this JPM. 2014 Systems -Control Room JPM H NU REG 1021, Revision 9 Appendix C Page 5of15 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with a -YJ Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1. START TIME: Performance Step: 1 Standard: Comment: Performance Step: 2 Standard: Comment: ER-INST.1, Attachment 2, Step 1.0 Note: IF a RTD has failed, THEN BOTH annunciators F-15 AND F-24 will be lit. Note: IF the TAVG circuit has failed, THEN annunciator F-15 will be lit AND annunciator F-24 will be extinguished. Note: IF the circuit has failed, THEN annunciator F-24 will be lit AND annunciator F-15 will be extinguished. ENSURE Rod Control selector switch in MANUAL. The operator reads the Notes, and proceeds. The operator observes that the Rod Bank Selector Switch is in M (Manual) ER-INST.1, Attachment 2, Step 2.0 ENSURE Charging Pump speed controllers in MANUAL. The operator observes that the A Charging Pump speed Controller is in MANUAL. The operator observes that the A Charging Pump speed Controller is in MANUAL. 2014 Systems -Control Room JPM H NUREG 1021, Revision 9 Appendix C ;._; Performance Step: 3 Standard: Comment: Page 6 of 15 PERFORMANCE INFORMATION ER-INST.1, Attachment 2, Step 3.0 Form ES-C-1 Note: The following Step removes the failed LiT input from the following functions:

• LiT Runback and Rodstop
• RIL computer
• Annunciators F-30 OP DELTA T TURBINE RUNBACK
• Annunciator F-31 OT DELTA T TURBINE RUNBACK In the RIL INSERTION LIMIT rack, PLACE T/405E DELTA T DEFEAT switch to LOOP A UNIT 2. The operator reads the Note, and proceeds.

["] The operator unlocks and opens the RIL Cabinet door. ["]The operator shifts the T/405E DELTA T DEFEAT switch to LOOP A UNIT 2. The operator closes and locks the RIL Cabinet door. 2014 Systems -Control Room JPM H NU REG 1021, Revision 9 Appendix C . ...J Performance Step: 4 Standard: Comment: Page/' of 15 PERFORMANCE INFORMATION ER-INST.1, Attachment 2, Step 4.0 Form ES-C-1 Note: The following Step removes the failed TAvG input from the following functions:

• Rod Control System
• Steam Dump System
• Pressurizer Level System In the STEAM DUMP rack, PLACE the TAVG DEFEAT switch T/401A to LOOP A UNIT 2. The operator reads the Note, and proceeds.

[...J] The operator unlocks and opens the Steam Dump Cabinet door. [...JJ The operator shifts the TAVG DEFEAT switch T/401A to LOOP A UNIT 2. The operator closes and locks the Steam Dump Rack Cabinet door. 2014 Systems -Control Room JPM H NU REG 1021, Revision 9 Appendix C Performance Step: 5 Standard: Comment: Page 8of15 PERFORMANCE INFORMATION ER-INST.1, Attachment 2, Step 5.0/5.1 Form ES-C-1 Note: The following bistable status lights are expected to be lit after the DEFEAT:

• LOOP A LO TAVG TC402A
• OPLlT LOOP A TC406A
• OT Ll T LOOP A TC406C Note: The following Annunciators are expected to be lit after the DEFEAT:
• G-9, RCS LOOP A HIGH TAVG 579 F
• F-7, RCS LOOP A LO TAVG 545 F
• F-32, RCS OP DEL TAT CHANNEL ALERT
• F-23, RCS OT DEL TAT CHANNEL ALERT DETERMINE the expected Bistable proving light status for the post defeat condition as follows:

RECORD the following Data: LOOP A-2 TAVG Tl-402 °F LOOP 1 A-2 TEMP Tl-4068 °F SP1 LOOP 1A-2 TEMP Tl-406A °F SP2 LOOP 1A-2 TEMP Tl-406C °F The operator reads the Notes, and proceeds. The operator observes Tl-402, and records 585°F in LOOP A-2 TAvG Tl-402 block. The operator observes Tl-4068, and records 76°F in LOOP 1A-2 TEMP Tl-4068 block. The operator observes Tl-406A, and records 67°F in T SP1 LOOP 1 A-2 TEMP Tl-406A block. The operator Tl-406C, and records 73°F in SP2 LOOP 1 A-2 TEMP Tl-406C block. 2014 Systems -Control Room JPM H NUREG 1021, Revision 9 Appendix C Performance Step: 6 Standard: Comment: Page 9of15 PERFORMANCE INFORMATION ER-INST.1, Attachment 2, Step 5.2 Form ES-C-1 DETERMINE the expBcted post defeat Bistable proving light status and circle the expected status in table below:

• 402 LOOP A-2
• HIGH T'AVG Light OFF IF Tl-402? 579°F
• LOW T'AVG Liight OFF IF Tl-402 545°F
• 406 LOOP A-2
• OVERTEMP TRIP Light OFF IF T-4068 ? Tl-406A
• OVERPOWER TRIP Light OFF IF Tl-4068?

Tl-406C The operator determines that Tl-402 is > 579°F, and circles OFF in the 402 LOOP A-2 HIGH T'AVG The operator determines that Tl-402 is > 545°F, and circles ON in the 402 LOOP A-2 LOW T'AVG The operator determines that Tl-4068 is> Tl-406A°F, and circles OFF in the 406 LOOP A-2 OVERTEMP TRIP The operator determines that Tl-4068 is> Tl-406C°F, and circles OFF in the 406 LOOP A-2 OVERPOWER TRIP 2014 Systems -Control Room JPM H NU REG 1021, Revision 9 Appendix C -J. Performance Step: 7 Standard: Comment: Page 10 of 15 PERFORMANCE INFORMATION ER-INST.1, Attachment 2, Step 6.0/6.1 Form ES-C-1 PLACE the affected channel Bistables in the Trip condition by PERFORMING the following: In the (WHITE) W-1 PROTECTION CHANNEL 2 rack, PLACE the following bistable proving switches to DEFEAT (UP) AND VERIFY the proving light status is correct per the table above:

• 402 LOOP A-2
• HIGH T'AVG
• LOWT'AVG
• 406 LOOP A-2
• OVERTEMP TRIP
• OVERPOWER TRIP [-/] The operator unlocks and opens the White Protection Channel 2 Cabinet door. [-/]The operator pulls out and lifts the 402 LOOP A-2 HIGH T'AVG proving switch to the DEFEAT (UP) position.

The operator verifies that the 402 LOOP A-2 HIGH T'AVG proving light is OFF. [-/] The operator pulls out and lifts the 402 LOOP A-2 LOW T'AVG proving switch to the DEFEAT (UP) position. The operator verifies that the 402 LOOP A-2 HIGH T'AVG proving light is ON. [-/] The operator pulls out and lifts the 406 LOOP A-2 OVERTEMP proving switch to the DEFEAT (UP} position. The operator verifies that the 406 LOOP A-2 OVERTEMP proving light is OFF. [-/] The operator pulls out and lifts the 406 LOOP A-2 OVERPOWER proving switch to the DEFEAT (UP) position. The operator verifies that the 406 LOOP A-2 OVERPOWER proving light is OFF. The operator closes and locks the White Protection Channel 2 Cabinet door. 2014 Systems -Control Room JPM H NUREG 1021, Revision 9 Appendix C Performance Step: 8 Standard: Comment: -'1 Performance Step: 9 Standard: Comment: Page '11 of 15 PERFORMANCE INFORMATION ER-INST.1, Attachment 2, Step 6.2 Form ES-C-1 VERIFY Correct Bistable Status Light and Annunciator status. The operator observes the LOOP A LO TAVG TC402A white bistable light is LIT and determines that the bistable light and Annunciator status is correct. The operator observes the OP L'.l T LOOP A TC406A white bistable light is LIT and determines that the bistable light and Annunciator status is correct. The operator observes the OT L'.l T LOOP A TC 406C white bistable light is LIT and determines that the bistable light and Annunciator status is correct. ER-INST .1, Attachment 2, Step 7 .017 .1 DELETE 402/406 from the PPCS by performing the following: SELECT "Group Update" display. [-°'11 The operator selects "Group Update" on the PPCS. ER-INST.1, Attachment 2, Step 7.2 -'1 Performance Step: 10 SELECT "List Server Groups". Standard: [-°'11 The operator selects "List Server Groups" on the PPCS (Group Update}. Comment: 2014 Systems -Control Room JPM H NU REG 1021, Revision 9 Appendix C Page 12 of 15 PERFORMANCE INFORMATION ER-INST.1, Attachment 2, Step 7.3 Form ES-C-1 -'1 Performance Step: 11 SELECT 402_ 406 from the pick list. Standard: [-'11 The operator selects "402_ 406" on the PPCS (List Server Groups). Comment: -'1 Performance Step: 12 Standard: Comment: ER-INST.1, Attachment 2, Step 7.4 TURN "OFF" scan processing, THEN click the "Set Scan Processing" button. [-'1] The operator turns OFF the 402_ 406 scan processing on the PPCS (402_ 406). [-'1] The operator clicks the "Set Scan Processing" button on the PPCS (402_ 406). ER-INST.1, 2, Step 7 .5 Performance Step: 13 ANSWER prompts. Standard: [-'11 The operator completes the PPCS deletion process by answering the required prompts. Comment: 2014 Systems -Control Room JPM H NUREG 1021, Revision 9 Appendix C Page 13of15 PERFORMANCE INFORMATION ER-INST.1, Attachment 2, Step 8.0 Performance Step: 14 GO TO step 6.2.7. Form ES-C-1 Standard: The operator proceeds to Step 6.2. 7 of the body of ER-INST.1 Comment: Terminating Cue: Evaluation on this JPM is complete. STOP TIME: 2014 Systems -Control Room JPM H NUREG 1021, Revision 9 Appendix C Page 14of15 VERIFICATION OF COMPLETION Job Performance Measure No.: 2014 Systems -Control Room JPM H Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiner's Signature: Date: Form ES-C-1 2014 Systems -Control Room JPM H NU REG 1021, Revision 9 Appendix C INITIAL CONDITIONS: INITIATING CUE: Form ES-C-1 JPM CUE SHEET

• The plant was operating at 100% power when Tl-402 failed high.
• The crew took all the appropriate actions and the plant is stable at current plant conditions.
• The CRS has directed you to defeat the affected RCS temperature chanrn31 per Attachment 2 of ER-INST.1, Reactor Protection Bistable Defeat After Instrumentation Loop Failure.
• For JPM performance, you are NOT expected to perform any instrument defeat briefings.

NUREG 1021, Revision 9 Appendix C Job Performance Measure Worksheet In-Plant JPM I Form ES-C-1 2014 Systems -In-Plant JPM I (Rev_090514) NU REG 1021, Revision 9 Appendix C Page 2 of 8 Form ES-C-1 Job Performance Measure Worksheet Facility: Ginna Task No.: Task Title: Locally Operate the ARVs JPM No.: 2014 Systems -Plant JPM I KIA

Reference:

APE 068AA1.01 (4.3/4.5) 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. Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1. 2014 Systems -In-Plant JPM I NUREG 1021, Revision 9 Appendix C Page 3 of 8 Form ES-C-1 Job Performance Measure Worksheet Task Standard: The operator will locally open the A Atmospheric Relief Valve, V-3411, three turns per P-15.2, and then isolate this valve when the handwheel will not rotate in the close direction. Required Materials: PPE (Hardhat, Safety Glasses, Hearing Protection, Safety Shoes etc.) General

References:

AP-CR.1, Control Room Inaccessibility, Rev 02403 Handouts: Time Critical Task: Validation Time: ER-FIRE.1, Alternate Shutdown For Control Complex Fire, Rev 03301 P-15.2, Dump Steam Through ARVs Locally, Rev 00002 Handout 1: Blank copy of P-15.2, Dump Steam Through ARVs Locally. NO minutes 2014 Systems -In-Plant JPM I NUREG 1021, Revision 9 Appendix C Page 4 of 8 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with a '1) Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1. START TIME: Performance Step: 1 Standard: EXAMINER NOTE: EXAMINER NOTE: Comment: Performance Step: 2 Standard: EXAMINER NOTE: Comment: P-15.2, Step 2.1 OBTAIN radio and establish communications with the Control Room. The operator recognizes from the Initial Conditions that they have a radio and are in communication with the Shift Manager. At this point in ER-FIRE.1 all Control Room Personnel in the plant would have obtained radios from an Appendix R locker outside the Control Room. The communications check was completed earlier in FIRE.1. P-15.2, Step 2.2 OBTAIN ladder, if needed. The operator verifies a ladder is in place at V-3411. A ladder is normally in place to allow access to the valve. 2014 Systems -In-Plant JPM I NUREG 1021, Revision 9 Appendix C Performance Step: 3 Standard: EXAMINER CUE: Standard: EXAMINER NOTE: EXAMINER CUE: Comment: Page e; of 8 PERFORMANCE INFORMATION P-15.2, Step 2.3 Form ES-C-1 Note: IF the ARV was opened using the handwheel, THEN the local handwheel must be used to close the ARV. OPERATE the handwheel on ARV-3411, S/G A ARV, as required by Control Room personnel. The operator reads the NOTE, and proceeds. The handwheel turned as desired. The operator leaves noisy area (IB Main Steam Area) to make report. The operator reports over radio to Shift Manager that ARV-3411 is three full hand turns open. If the radio call is made from the Main Steam Area: "I cannot hear you". Acknowledge the report and then state the following: The valve has been open for 15 minutes and the SM now directs you to "Slowly throttle closed the valve." 2014 Systems -In-Plant JPM I NUREG 1021, Revision 9 Appendix C Performance Step: 4 Standard: EXAMINER CUE: Standard: EXAMINER CUE: Standard: EXAMINER NOTE: Comment: Terminating Cue: STOP TIME: Page 6 of 8 PERFORMANCE INFORMATION P-15.2, Step 2.3/2.3.1 Form ES-C-1 Note: IF the ARV was opened using the handwheel, THEN the local handwheel must be used to close the ARV. OPERATE the handwheE31 on ARV-3411, S/G A ARV, as required by Control Room personnel. IF the handwheel on ARV-3411, S/G A ARV, will NOT close, THEN CLOSE V-3507, S/G A MS INLET BLOCK VLV TO ARV-3411. The operator reads the Note, and proceeds. The operator attempts to rotate the "A" ARV (3411) handwheel in the clockwise direction. The handwheel will not turn. The handwheel turned as desired. The operator leaves noisy area (IB Main Steam Area) to make report. The operator reports ovBr radio to Shift Manager that ARV-3411 is three full handturns open. However, because it would not close, its Root isolation valve (V3507) was closed. If the radio call is made from the Main Steam Area: "I cannot hear you". Evaluation on this JPM is complete. 2014 Systems -In-Plant JPM I NUREG 1021, Revision 9 Appendix C Page 7 of 8 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2014 Systems -In-Plant JPM I Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiner's Signature: Date: 2014 Systems -In-Plant JPM I NUREG 1021, Revision 9 Appendix C INITIAL CONDITIONS: INITIATING CUE: Form ES-C-1 JPM CUE SHEET

• You are the Head Control Operator.
• The plant has experienced an uncontrollable Control Room Complex fire.
• The crew performed the required actions of AP-CR.1, Control Room Inaccessibility, and transitioned to ER-FIRE.1, Alternate Shutdown For Control Complex Fire.
• You have completed Attachment 3, Head Control Operator (HCO) and are equipped with a radio.
• The Shift Manager is stabilizing the plant in MODE 3.
• All the required R equipment has been retrieved from the Appendix R locker outside the Control Room. The Shift Manager has directed you to locally open the A Atmospheric Relief Valve, V-3411, three turns per P-15.2, Dump Steam Through ARVs Locally.

NOTE: No plant equipment should be operated during the performance of this JPM. All actions must be SIMULATED. NUREG 1021, Revision 9 Appendix C Job Performance Measure In-Plant JPM J Form ES-C-1 2014 Systems -In-Plant JPM J (Rev_090514) NUREG 1021, Revision 9 Appendix C Page 2of13 Form ES-C-1 Job Performance MBasure Worksheet Facility: Ginna Task No.: Task Title: Isolate RCP Seals JPM No.: 2014 Systems -Plant JPM J KIA

Reference:

EPE 055 EA2.03 (3.9/4.7) 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. Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), Laser Pointer and Handout 1. Task Standard: The operator will locally isolate the RCP Seals per ATT-21.0. Required Materials: PPE (Hardhat, Safety Glasses, Hearing Protection, Safety Shoes etc.) Laser Pointer General

References:

ECA-0.0, Loss of All AC Powe!r, Rev 03800 2014 Systems -In-Plant JPM J NUREG 1021, Revision 9 Appendix C Page 3 of 13 Form ES-C-1 Job Performance Measure Worksheet ATT-21.0, Attachment RCS Isolation, Rev 00300 Handouts: Handout 1: Blank copy of ATT-21.0, Attachment RCS Isolation. Time Critical Task: NO Validation Time: 7 minutes 2014 Systems -In-Plant JPM J NUREG 1021, Revision 9 Appendix C Page 4 of *13 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with a '1) Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), Laser Pointer and Handout 1. START TIME: Examiner NOTE: Performance Step: 1 Examiner Cue: Standard: Examiner Cue: Standard: Examiner Cue: Standard: Examiner NOTE: Comment: The order of valve isolation is NOT Critical ATT-21.0, Bullet 1 Perform the following to locally complete isolation of the RCS:

• Close RCP #1 seal return isolation valve
• MOV-313 (Pen 108) If the operator requests*

eSOMS location for MOV-313: AB Bsmt, RSWT locked area, elev. 5. The declutch lever is depressed. The valve handwheel

rotates, and then stops rotating.

MOV-313 is located within a contaminated area and will require that the operator use the laser Pointer to identify the location and describe operation of the valve. See Page 12 for of this Valve. 2014 Systems -In-Plant JPM J NUREG 1021, Revision 9 Appendix C Performance Step: 2 Examiner Cue: Standard: Examiner Cue: Standard: Examiner Cue: Standard: Examiner NOTE: Comment: Page 5of13 PERFORMANCE INFORMATION Form ES-C-1 ATT-21.0, Bullet 2 Perform the following to locally complete isolation of the RCS:

• Close RCP seal injection needle valves
• V-300A (Pen 106)
• V-3008 (Pen 110) If the operator requests eSOMS location for V-300A and V-300B: AB Bsmt, RSWT locked area, elev. 4. The valve handwheel

rotates, and then stops rotating.

.* .. The valve handwheel

rotates, and then stops rotating.

V-300A and 300B are located within a contaminated area and will require that the c>perator use the laser Pointer to identify the location and describe operation of the valve. See Pages 10 & 11 for Pictures of these Valves. 2014 Systems -In-Plant JPM J NUREG 1021, Revision 9 Appendix C Performance Step: 3 Examiner Cue: Standard: Examiner Cue: Standard: Examiner Cue: Standard: Examiner Cue: Standard: Examiner Cue: Standard: Comment: Page 6 of 13 PERFORMANCE INFORMATION ATT-21.0, Bullet3 Form ES-C-1 Perform the following to locally complete isolation of the RCS:

• Close RCP CCW return valves (middle level by RWST)
• MOV-759A
• MOV-7598 If the operator requests eSOMS location for MOV-759A and MOV-759B:

AB Inter Crane Bay area, elev. 5. The declutch lever is depressed. The valve handwheel

rotates, and then stops rotating.

The declutch lever is depressed. The valve handwheel

rotates, and then stops rotating.

2014 Systems -In-Plant JPM J NUREG 1021, Revision 9 Appendix C Performance Step: 4 Examiner Cue: Standard: Examiner Cue: Standard: Examiner Cue: Standard: Examiner Cue: Standard: Examiner Cue: Standard: Comment: Page 7of13 PERFORMANCE INFORMATION ATT-21.0, Bullet 4 Form ES-C-1 Perform the following to locally complete isolation of the RCS:

• Close RCP CCW supply valves (middle level by RWST)
• MOV-749A
• MOV-749B If the operator requests eSOMS location for MOV-749A and MOV-749B:

AB Inter Crane Bay area, elev. 5. The declutch lever is depressed. The valve handwheel

rotates, and then stops rotating.

The declutch lever is depressed. The valve handwheel

rotates, and then stops rotating.

2014 Systems -In-Plant JPM J NUREG 1021, Revision 9 Appendix C Performance Step: 5 Examiner Cue: Standard: Examiner Cue: Standard: Examiner Cue: Standard: Examiner Cue: Standard: Examiner Cue: Standard: Comment: Terminating Cue: STOP TIME: Page 8 of 13 PERFORMANCE INFORMATION ATT-21.0, Bullet 5 Form ES-C-1 Perform the following to locally complete isolation of the RCS:

• Close CCW isolation valves for Rx support coolers
• MOV-813
• MOV-814 If the operator requests eSOMS location for MOV-813 and MOV-814:

AB Inter Crane Bay area, elev. 5. The declutch lever i!:; depressed. The valve handwheel

rotates, and then stops rotating.

The declutch lever is depressed. The valve handwheel

rotates, and then stops rotating.

Evaluation on this JPM is complete. 2014 Systems -In-Plant JPM J NUREG 1021, Revision 9 Appendix C Page 9 of 13 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2014 Systems -In-Plant JPM J Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiner's Signature: Date: 2014 Systems -In-Plant JPM J NUREG 1021, Revision 9 Appendix C 2014 Systems -In-Plant JPM J Page 10of13 VERIFICATION OF COMPLETION Form ES-C-1 NUREG 1021, Revision 9 Appendix C 2014 Systems -In-Plant JPM J Page 11 of 13 VERIFICATION OF COMPLETION Form ES-C-1 NUREG 1021, Revision 9 Appendix C 2014 Systems -In-Plant JPM J Page 12of13 VERIFICATION OF COMPLETION Form ES-C-1 NUREG 1021, Revision 9 Appendix C INITIAL CONDITIONS: INITIATING CUE: Form ES-C-1 JPM CUE SHEET

• The plant was operating at 100% power when it suffered a loss of all AC power.
• The crew entered ECA-0.0, Loss of All AC Power, and is at the step that directs local isolation of RCP Seals. The CRS has directed you to isolate RCP seals in accordance with the applicable portions of ATT-21.0, Attachment RCS Isolation.

NOTE: No plant equipment should be operated during the performance of this JPM. All actions must be SIMULATED. NUREG 1021, Revision 9 Appendix C Job Performance Measure Worksheet Form ES-C-1 In-Plant JPM K 2014 Systems -In-Plant JPM K (Rev_090514) NUREG 1021, Revision 9 Appendix C Page 2of13 Form ES-C-1 Job Performance Measure Worksheet Facility: Ginna Task No.: Task Title: Fire Water Cooling to CCW Heat Exchanger A JPM No.: 2014 Systems -Plant JPM K KIA

Reference:

APE 062 AA 1.07 (2.9/3.0) 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. Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), a Laser Pointer and Handout 1. 2014 Systems -In-Plant JPM K NUREG 1021, Revision 9 Appendix C Page 3 of 13 Form ES-C-1 Job Performance Measure Worksheet Task Standard: The operator will locally align fire water to CCW HX A in accordance with ER-CCW.1. Required Materials: PPE (Hardhat, Safety Glasses, Hearing Protection, Safety Shoes etc.) Laser Pointer General

References:

ATI-2.4, Attachment No Service Water Pumps, Rev 3 Handouts: Time Critical Task: Validation Time: ER-CCW.1, Fire Water Cooling to CCW and A SFP Heat Exchangers, Rev 00301 33013-1250 Sheet 2 Showing Shower Tagout Handout 1: Blank copy of ER-CCW.1, Fire Water Cooling to CCW and A SFP Heat Exchangers. NO 22 minutes 2014 Systems -In-Plant JPM K NUREG 1021, Revision 9 Appendix C Page 4of13 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with a --./) Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), a Laser Pointer and Handout 1. START TIME: Performance Step: 1 Standard: Examiner Cue: Standard: Examiner Cue: Comment: ER-CCW.1, Step 6.1.1 ENSURE the following valves are CLOSED

• SFP SKID HX SW INLET HOSE CONN ISOL VLV, V-8687 (Aux Bldg top floor by CCW Hxs).
• TIE IN VALVE FOR TEMP COOLING WATER SYSTEM. V-9184 (Aux Bldg top floor by G fan). The operator attempts to rotate the V-8687 handle in the clockwise direction.

The Handle will NOT rotate. The operator attempts to rotate the V-9184 handwheel in the clockwise direction. The Handwheel will NOT rotate. 2014 Systems -In-Plant JPM K NUREG 1021, Revision 9 Appendix C Performance Step: 2 Examiner Cue: Standard: Examiner Cue: EXAMINER NOTE: Standard: Examiner Cue: Standard: Examiner Cue: EXAMINER NOTE: Comment: Page 5of13 PERFORMANCE INFORMATION ER-CCW.1, Step 6.1.2/6.1.2.1 Form ES-C-1 Note: The Fire Hose Flange Connections and Gaskets are located in the Turbine Operating Floor Staged Equipment Locker. Note: Fire Hose is available in the Ginna Fire Trucks (Ginna 1 and 2). Note: Maintenance may assist as needed with the next step. PERFORM the following: REMOVE the Blind Flanges from V-8687 and V-9184. If requested, report that "Mechanical Maintenance and the Safety Group are available to assist." The operator reads the Notes, and proceeds. The operator proceeds to the Turbine Building hose locker and obtains the required flanges/gaskets, and necessary tools. Report that "You have the flanges/gaskets and tools in your possession." It is NOT the intention of the JPM for the operator to leave the RCA. The Examiner shall have the operator describe/point out the location prior to/after the JPM performance. Report that "The Flange has been removed." Report that "The Flange has been removed." The order of removal of the Blind Flanges is NOT critical. 2014 Systems -In-Plant JPM K NU REG 1021, Revision 9 Appendix C Performance Step: 3 Examiner Cue: Standard: Examiner Cue: Standard: Examiner Cue: EXAMINER NOTE: Comment: Page 6of13 PERFORMANCE INFORMATION ER-CCW.1, Step 6:1.2.2 Form ES-C-1 INSTALL the Flange, Fire Hose Connection on V-8687 and V-9184. If requested, report that "Mechanical Maintenance is providing assistance as directed by YOU." Report that "The Flange Fire Hose Connection has been Report that "The Flange Fire Hose Connection has been installed." The order of Flange Fire Hose Connection installation is NOT critical. 2014 Systems -In-Plant JPM K NUREG 1021, Revision 9 Appendix C Performance Step: 4 Examiner Cue: Examiner Cue: Comment: Performance Step: 5 Standard: Examiner Cue: Comment: Page 7 of 13 PERFORMANCE INFORMATION ER-CCW.1, Step 6.1.2.3 Form ES-C-1 INSTALL a 3" Fire Hose between V-8687 and V-9184.

• If requested, report that "Mechanical Maintenance is providing assistance as directed by YOU."
• A 3 inch Fire Hose is available.

Report that "The Fire Hose is connected." ER-CCW.1, Step 6.1.3/6.1.3.1 IF it is desired to supply the A CCW HX THEN PERFORM the following: CLOSE AUXILIARY BUILDING SERVICE WATER ISOLATIONS, MOV--4616 and MOV-4735. The operator recalls that MOV-4616 and MOV-4735 are closed (Initial Conditions). If the operator calls the Control Room for valve status, report that "MOV-4616 and MOV-4735 are closed." If the operator observes the two valves locally, report that "MOV-4616 and MOV-4735 indicate closed." 2014 Systems -In-Plant JPM K NUREG 1021, Revision 9 Appendix C Performance Step: 6 Standard: Examiner Cue: EXAMINER NOTE: Comment: Performance Step: 7 EXAMINER CUE: Standard: Examiner Cue: EXAMINER NOTE: Comment: Page 8of13 PERFORMANCE INFORMATION ER-CCW.1, Step 6.1.3.2 Form ES-C-1 CLOSE SW LOOP A INLET BLOCK VLV TO SFP HX A, V-4621. The valve handwheel

rotates, and then stops rotating.

The operator/Examiner will need to fit through some tight spaces to get to this valve. The Examiner may elect to have the operator use the Laser Pointer to point out the valve, and describe its operation. ER-CCW.1, Step 6.1.3.3 CLOSE SW LOOP BINNER ISOL VLV TO VENT & EYE WASH/SHOWER, V--4618A. If the operator requests eSOMs location for V-4618A, states "AB operating Component Cooling Water HX Platform, 9ft. elevation." The valve handle rotates, and then stops rotating. This valve is in the overhead. The Examiner may elect to have the operator use the Laser Pointer to point out the valve, and describe its operation. 2014 Systems -In-Plant JPM K NUREG 1021, Revision 9 Appendix C Performance Step: 8 Standard: Examiner Cue: Comment: Performance Step: 9 Standard: Examiner Cue: Comment: Page 9of13 PERFORMANCE INFORMATION ER-CCW.1, Step 6.1.3.4 Form ES-C-1 OPEN INLET BLOCK VLV TO CCW HX A, V-4617. The valve handwheel

rotates, and then stops rotating.

ER-CCW.1, Step 6.1.3.5 IF the Normal SW Discharge Flowpath is desired THEN OPEN CCW HX A SW OUTLET ISOL VLV, V-4619. The valve handwheel

rotates, and then stops rotating.

ER-CCW.1, Step 6.'l.3.6 Performance Step: 10 IF the Redundant SW Discharge Flowpath is desired .... Standard: The operator recognizes that the Redundant SW Discharge Flowpath is NOT desired, and proceeds. Comment: 2014 Systems -In-Plant JPM K NUREG 1021, Revision 9 Appendix C Performance Step: 11 Standard: Examiner Cue: Comment: Performance Step: 12 Standard: Examiner Cue: Comment: Page 10of13 PERFORMANCE INFORMATION ER-CCW.1, Step 6:1.3. 7 Form ES-C-1 Note: The following steps will cause the Motor and/or the Engine Fire Pump(s) to start:. OPEN TIE IN VALVE FOR TEMP COOLING WATER SYSTEM. V-9184. The operator reads the Note, and proceeds. The valve handwheel

rotates, and then stops rotating.

ER-CCW.1, Step 6.1.3.8 SLOWLY OPEN SFP SKID HX SW INLET HOSE CONN ISOL VLV, V-8687. The valve handle rotates, and then stops rotating. 2014 Systems -In-Plant JPM K NUREG 1021, Revision 9 Appendix C Performance Step: 13 Standard: Examiner Cue: Comment: Terminating Cue: STOP TIME: Page 11 of 13 PERFORMANCE INFORMATION ER-CCW.1, Step 6.1.3.9 Form ES-C-1 NOTIFY the Control Room that Fire Water Cooling is established to the A CCW HX. The operator contacts the Control Room and reports that Fire Water Cooling is established to the A CCW HX. As the BOP, acknowledge. Evaluation on this JPM is complete. 2014 Systems -In-Plant JPM K NUREG 1021, Revision 9 Appendix C Page 12of13 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2014 Systems -In-Plant JPM K Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiner's Signature: Date: 2014 Systems -In-Plant JPM K NUREG 1021, Revision 9 Appendix C INITIAL CONDITIONS: INITIATING CUE: Form ES-C-1 JPM CUE SHEET

• The plant was operating at power when a loss of all Service Water pumps occurred.
• The crew responded using the emergency operating procedures and Attachment 2.4, Attachment No Service Water Pumps, as required.
• The crew is ready to align alternate cooling to one CCW heat exchanger.
• A normal SW discharge alignment is desired.
• SW isolations MOV-4616 and MOV-4735 have been closed from the Control Room. The CRS has directed you to line up Fire Water Cooling from the plant fire header to the A CCW Heat Exchanger per ER-CCW.1, Fire Water Cooling to CCW and A SFP Heat Exchangers.

NOTE: No plant equipment should be operated during the performance of this JPM. All actions must be SIMULATED. NUREG 1021, Revision 9 PROGRAM: Ginna Operations Training MODULE: 2014 Initial License Operator Training Class TOPIC: NRC Simulator Exam Scenario N2014-301-2

REFERENCES:

1. Technical Specification 3.6.6, Containment Spray, Containment Recirculation Fan Cooler (CRFC), and NaOH Systems, Amendment 99 2. AR-A-17, MOTOR OFF RCP CCWP, Rev 9 3. AP-CCW.2, Loss of CCW During Power Operation, Rev 02201 4. Technical Specification

3. 7. 7, Component Cooling Water System, Amendment 80 5. AR-F-11, PZR LOW LEVEL 13%, Rev 4 6. ER-INST.1, Reactor Protection Bistable Defeat After Instrumentation Loop Failure, Rev 03605 7. S-3.2.E, Placing In or Removing From Service Normal Letdown/Excess

Letdown, Rev 02700 8. Technical Specification 3.4.9, Pressurizer, Amendment 80 9. Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, Amendment 112 10. TURB.2, Turbine Load Rejection, Rev 02301 11.AP-TURB.5, Rapid Load Reduction, Rev01600

12. AR-G-5, SIG/ B LEVEL DEVIATION

+/-7%, Rev 00701 13. Technical Specification LCO 3.7.3, Main Feedwater Isolation Valves (MFIVs), Main Feedwater Regulating Valves (MFRVs), and Associated Bypass Valves, Amendment 95 14. E-0, Reactor Trip and Safety Injection, Rev 04602 15. ATT-27.0, Attachment Automatic Action Verification, Rev 00300 16. E-2, Faulted Steam Generator Isolation, Rev 01301 17. ECA-2.1, Uncontrolled Depressurization of Both Steam Generators, Rev 03601 18. FR-P.1, Response to Imminent Pressurized Thermal Shock Condition, Rev 03200 Validation Time: 95 Minutes Author: David Lazarony, Essential Training & Consulting, LLC Facility Review: Rev. 110414 Scenario Event Description NRC Scenario 2 Facility: Ginna Scenario No.: 2 Op Test No.: N2014-301 Examiners: Operators: (SRO) (RO) (BOP) Initial Conditions: The plant is at 100% power (EOl), and has been at full power for 145 days. The area has experienced thunderstorms over the last 6 hours, and this is expected to continue for the next 6 hours. Turnover: The following equipment is Out-Of-Service: The B CNMT Spray Pump has been declared INOPERABLE due to excessive inboard vertical vibration during STP-0-3-COMP-B surveillance test yesterday. Engineering is evaluating the data. A-52.4 submitted for ITS 3.6.6, 72 hour Action. Event Malf. Event Type* Event No. No. Description 1 CLG05 C-RO Leak on the CCW System/B CCW Pump Trips CLG02A C{TS)-SRO 2 PZR03B I-BOP PZR Level Channel 427 fails LOW I-RO l{TS)-SRO 3 TUR11B R-RO Turbine Control Valve CV-L4 Drifts Closed N-BOP N-SRO 4 FDWO?C C-BOP B FRV fails AS-IS (Manual Control Available) C(TS)-SRO 5 STM03 M-RO MSLB Downstream of MSIVs with MSIVs Stuck OPEN STM05A M-BOP STM05B M-SRO 6 RPS05A C-RO RPS fails to Trip Rx in AUTO/Manual Pushbutton RPS05B C-SRO 7 STM03 NA Steam Break Degrades Creating PTS Concern 8 EDS01A C-BOP Loss of Offsite Power EDS01B C-SRO * (N)ormal, (R)eactivity, (I )nstrument, (C)omponent, (M)ajor Ginna 2014 NRC Scenario

1. 2 Scenario Event Description NRC Scenario 2 The plant is at 100% power (EOL), and has been at full power for 145 days. The area has experienced thunderstorms over the last 6 hours, and this is expected to continue for the next 6 hours. The following equipment is Out-Of-Service:

The B CNMT Spray Pump has been declared INOPERABLE due to excessive inboard vertical vibration during STP-0-3-COMP-B surveillance test yesterday. Engineering is evaluating the data. A-52.4 submitted for ITS 3.6.6, 72 hour Action. Shortly after taking the watch, a CCW System Supply Relief Valve will lift and fail to reseat causing a 30 gpm CCW System leak. Approximately two minutes afterwards the B CCW Pump will trip, and the B CCW Pump will automatically start. The operator will respond in accordance with AR-A-17, MOTOR OFF RCP CCWP, and enter AP-CCW.2, Loss of CCW During Power Operation. The operator will address Technical Specification 3.7.7, Component Cooling Water System. After this, Pressurizer Level Channel 427 will fail LOW, resulting in letdown isolation and energizing the pressurizer heaters. The crew will respond per AR-F-11, PZR LOW LEVEL 13%, and ER-INST.1, Reactor Protection Bistable Defeat After Instrumentation Loop Failure. They will defeat the failed channel, reset PZR heaters, reduce charging to a single charging pump, and re-establish letdown per S-3.2.E, Placing In or Removing From Service Normal Letdown/Excess Letdown. The crew will start a second charging pump and slowly restore PZR level to program (52%). The operator will address Technical Specification 3.3.1, Reactor Trip System {RTS) Instrumentation and 3.4.9, Pressurizer. Then, turbine control valve CVL-4 will drift closed. The crew will respond per AP-TURB.2, Turbine Load Rejection, begin a load reduction to less than 50% power using AP-TURB.5, Rapid Load Reduction. During the load reduction, a failure of the B FR\/ to control in AUTO. The operator will respond per AR-G-5, SIG/ B LEVEL DEVIATION +/-7%, or upon observing an abnormally high level in the B Steam Generator and control the B FRV manually. The operator will address Technical Specification 3.7.3, Main Feedwater Isolation Valves (MFIVs), Main Feedwater Regulating Valves (MFRVs), and Associated Bypass Valves. Subsequently, a major steamline break will occur in the Turbine Building downstream of the MSIVs. Both MSIVs will fail to close automatically in response to manual attempts from the MCB. The reactor will fail to trip automatically and manual pushbutton will not work, requiring opening of normal supply breakers for Bus 13 and Bus 15 to de-energize rod drive MG sets to trip the reactor. The crew will enter E-0, Reactor Trip or Safety Injection. The crew will ultimately transition to E-2, Faulted SIG Isolation. Since both MSIVs are failed open, and with a downstream break, both SGs will be affected and their pressures will lower concurrently. Eventually, the crew will transition to ECA-2.1, Uncontrolled Depressurization of Both Steam Generators. After the operator throttles AFW flow in ECA-2.1, the leak will increase in magnitude, resulting in an Orange Path on RCS Integrity. Simultaneously the event will be complicated by a Loss of Offsite Power. Both Emergency Diesel Generators will start and automatically repower the respective Emergency Busses, and the operator will need to establish AFW flow of 50 gpm to each Steam Generator. Scenario Event Description NRC Scenario 2 The crew will implement FR-P.1, Response to Imminent Pressurized Thermal Shock Condition, when RCS cold leg temperatures reach 311°F. In FR-P.1 the crew will stop the SI pumps and the RHR pumps. The scenario will be terminated after the SI and RHR pumps are secured. Critical Tasks: 1. Manually trip the reactor from the control room before transition to FR-S.1 Safety Significance: Failure to manually trip the reactor causes a challenge to the subcriticality CSF beyond that irreparably introduced by the postulated conditions. Additionally, it constitutes an "incorrect performance that necessitates the crew taking action which complicates the event mitigation strategy that demonstrates the inability by the crew to recognize a failure of the automatic actuation of the RPS. 2. Control the AFW flowrate to 50 gpm per SG in order to minimize the RCS Cooldown rate Safety Significance: Failure to control the AFW flow rate to the SGs when able to do so causes a challenge to the subcriticality and RCS Integrity CSFs beyond that irreparably introduced by the postulated conditions. Additionally, it constitutes an "incorrect performance that may necessitate the crew taking action which complicates the event mitigation strategy (Transition to FR-S.1 on inability to maintain a negative SUR). D D D *

• Bench Mark Prior to Crew Briefing Scenario Event Description NRC Scenario 2 SIMULATOR OPERATOR INSTRUCTIONS ACTIVITY DESCRIPTION Reset to Temp l/C 100% power EOL 172. (Built on IC-24) At T=O, insert:
• MALF RPS05A, [No Manual],

Reactor Trip Bkr A Failure

• MALF RPS05B, [No Manual],

Reactor Trip Bkr B Failure

• MALFSTM05A,

[100), MSIV Fails Open VLV 3517

• MALFSTM05B,

[100), MSIV Fails Open VLV 3516 To take B CS pump OOS:

• Pull stop the B CS pump Insert the following:
• MALF CLG02B, 0%, on T-1 (2 Min Delayed),

B CCW Pump Trip

• MALF CLG05, 30 gpm, on T-1
• MALF PZR03B [O], on T-2, PZR Level Channel 427 failure
• MALF TUR11B [O in 20 sec], on T-3, CVL-4 Failure
• MALF FDW07C, [101 ],on T-4, FRV fails as is on downpower
• MALFSTM03

[1E6] on T-5, Steamline Break outside CNMT downstream of MS I V's

• MALFFPS01-237

[15 seconds delayed], on T-5, Fire in Zone 37 (Int Building Clean Side Main Steamline and above)

• MALFSTM03,

[5E6], on T-6 Steamline Break outside CNMT downstream of MSIV's (larger for entry into FR-P.1)

• MALF EDS01A, on T-6 (Loss of Offsite Power)
• MALF EDS01 B, on T-6 (Loss of Offsite Power) RUN
• Hang Protective Tags per OPG-Protective Equipment.
• Place Black Dot on MCB Annunciator J-25 Crew Briefing Assign Crew Positions based on evaluation requirements Review the Shift Turnover Information with the crew .

Bench Mark D T-0 D At direction of examiner D At direction of examiner D At direction of examiner D At direction of examiner D At direction of examiner D Continued from Event 5 D After entry into ECA-2.1 At direction of examiner D Simultaneous with Event 7 D Scenario Event Description NRC Scenario 2 ACTIVITY DESCRIPTION . Begin Familiarization Period Event1 Leak on the CCW System/B CCW Pump Trips Trigger#1 CLG05 (30 gpm, No Ramp) CLG02B (B CCW Pump Trip 2 Minute Delayed) Event2 PZR Level Channel 427 fails LOW Trigger#2 PZR03B (0) Event 3 Turbine Control Valve CV-L4 Drifts Closed Trigger#3 TUR11 B (0 over 20 seconds) Event 4 B FRV fails AS-IS (Manual Control Available) Trigger#4 FDW07C (Current Controller Output) Event 5 MSLB Downstream of MSIVs with MSIVs Stuck Trigger#5 OPEN STM03 (1 E+6) FPS01-237 NOTE: The Fire Alarm is 15 seconds dealyed. STM05A (100) NOTE: These Malfunctions are inserted in the STM05B (100)] IC at T = 0. Event6 RPS fails to Trip Rx in AUTO/Manual Pushbutton MALF RPS05A, [No Manual] NOTE: These Malfunctions are inserted in the MALF RPS05B, [No Manual] IC at T = 0. Event 7 Steam Break Degrades Creating PTS Concern Trigger#6 STM03 (5E+6) Event 8 Loss of Offsite Power Trigger#6 EDS01A EDS01B Terminate the scenario upon direction of Lead Examiner Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# -----Page 7 of _4_9_1 Event

Description:

Leak on the CCW System/B CCW Pump Trips Shortly after taking the watch, a CCW System Supply Relief Valve will lift and fail to reseat causing a 30 gpm CCW System leak. Approximately two minutes afterwards the B CCW Pump will trip, and the B CCW Pump will automatically start. The operator will respond in accordance with AR-A-17, MOTOH OFF RCP CCWP, and enter AP-CCW.2, Loss of CCW During Power Operation. The operator will address Technical Specification 3.7.7, Component Cooling Water System. SIM DRIVER Instructions: Operate 'Trigger

1. 1 (CLGOS (30 gpm), CLG02B (2 minutes delayed))

Indications Available:

• CCW Surge Tank Level starts to lower .
• Two minutes later, the B CCW Pump trips and the A CCW Pump starts automatically
• MCB Annunciator A-17; MOTOR OFF RCP CCWP
• MCB Annunciator A-13, CCW SURGE TANK LO LEVEL 41.2% Time
• Pos. , Expected ActionstBehavior J . <comments
• NOTE: The crew may enter AP-CCW .2 directly.

AR-A-17, MOTOR OFF RCP CCWP HCO (Step 1) Verify which motor tripped. HCO (Step 2) IF a RCP has tripped, THEN ..... NOTE: An RCP has NOT tripped. CRS (Step 3) IF a CCW pump has tripped, THEN go to the applicable AP-CCW procedure:

• AP-CCW.2 (LOSS OF CCW DURING POWER OPERATION)

NOTE: The CRS will go to AP-CCW.2. AP-CCW.2, LOSS OF CCW DURING POWER OPERATION HCO (Step 1) Check CCW Pump Status:

• Both CCW pump breaker white lights -EXTINGUISHED
• Annunciator A-17, MOTOR OFF RCP CCWP -EXTINGUISHED Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

2 Event# Page 8 of 49 ---11 Event

Description:

Leak on the CCW System/B CCW Pump Trips . Expected Actions/Behav.ior . . Time*/ Pos. Comments HCO (Step 1 RNO) Perform the following:

• Ensure standby CCW pump running . IF no CCW pump can be operated, NOTE: The A CCW Pump is THEN ........

running.

• IF annunciator A-22, CCW PUMP NOTE: Annunciator A-22 is DISCHARGE LO PRESS {)0 PSI, lit, NOT lit. THEN ........

HCO (*Step 2) Monitor CCW Surge Tank Level -NOTE: The CCW Surge Tank APPROXIMATELY 50% AND STABLE .... Level is lowering. (Step 2 RNO) Perform the following:

• Open RMW to CCW surge tank, MOV-823.
• Start RMW pump(s) .
• IF surge tank level stable or rising, THEN NOTE: The makeup flow into control level at approximately 50% while the CCW Surge Tank will be continuing with Step 3. able to stabilize the tank level. HCO (*Step 3) Monitor CCW Hx Outlet Temperature (MCB rear or PPCS point ID T0621)
• CCW Hx Outlet temperature-LESS THAN 120°F HCO (*Step 4) Monitor RCP Indications:
• Annunciator A-7 (A-15), RCP 1A (18) CCW return Hi Temp or low flow 165 gpm 125°F alarm -EXTINGUISHED
• RCP motor bearings temperature (PPCS Group Display -RCPS OR RXP temperature monitor RK-30A recorder)

-200°F Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# -----Page 9 of 49 ---11 Event

Description:

Leak on the CCW System/B CCW Pump Trips Time .

• ... * .: Ex:pectecl

t(ctions/Bellavior:\; :. Cortjments

. .. HCO (*Step 5) Monitor If Letdown Should Be Isolated:

• Check annunciator A-12, Non-Regen Hx Letdown Out Hi Temp 145°F -EXTINGUISHED
• Check excess letdown temperature

-LESS THAN 195°F HCO (Step 6) Check CCW Valve Alignment -NORMAL

• Check MCB CCW valves (Refer to ATT-1.0, ATTACHMENT AT POWER CCW ALIGNMENT)
• Direct AO to check local flow indications NOTE: The CRS will dispatch per ATT-1.1, ATTACHMENT NORMAL an AO. CCW FLOW SIM DRIVER: as AO, acknowledge.

HCO (Step 7) Locally Check Seal Water Hx CCW NOTE: The CRS may direct Outlet Flow -NORMAL (Fl-605) the AO to report status of Seal Water Hx CCW Outlet Flow. If so, SIM DRIVER acknowledge as AO, and report flow is 96 gpm. SIM DRIVER: As AO, call and report that Relief Valve V770 (Near Sample Coolers) is lifting to the drain system. The leak appears to be isolable, and valves V772C (Inlet lso Valve) and V772D (Outlet lso Valve) are nearby. If directed to isolate the leak, Remove MALF CL GOS Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# Page ------10 of 49 Event

Description:

Leak on the CCW System/B CCW Pump Trips .Pos!!,,' Expected Actions/Behavior , ' :if" . .*. Time* .. ' NOTE: The CRS may contact Chemistry and direct them to isolate CCW to the Sample Coolers. If so, SIM DRIVER acknowledge as Chemistry. NOTE: After the CCW to the Sam pie Cooler is isolated the crew may elect to isolate SG Slowdowns. HCO/ (Step 8) Check for CCW Leakage In CNMT: AO

• Check CNMT sump A level:
• Level -ST ABLE
• Sump A pumps -OFF
• RCP oil levels -ST ABLE HCO/ (Step 9) Check for CCW Leakage In AUX AO BLDG:
• Start frequency of AUX BLDG sump pump(s)-NORMAL (Refer to RCS daily leakage log)
• Waste holdup tank level -STABLE OR NOTE: The CRS may direct RISING AS EXPECTED the AO to report status of the WHUT. If so, SIM DRIVER acknowledge as AO, and report level is slowly rising (Modify if leak is isolated).

HCO (Step 10) Verify CCW System Leak -IDENTIFIED

• Leak identified
• Isolate leak if possible NOTE: The leak has likely been discovered and isolated.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# ------Page 11 of 49 ---11 Event

Description:

Leak on the CCW System/B CCW Pump Trips .rime

• .*

Actions/Behavior ... ** .* *. comments ,, ',' ,,c ' .

• Refer to IP-ENV-3, RESPONSE TO A NOTE: The CRS may ask the SPILL OF HAZARDOUS SM to address.

MATERIAL/WASTE If so, SIM DRIVER acknowledge as OSM. HCO (Step 11) Check Normal or Excess Letdown -IN SERVICE HCO (Step 12) Check CCW System Isolated

• Surge tank level -APPROXIMATELY 50% * (Step 12a RNO) IF level less than 50%, NOTE: The Surge Tank Level THEN continue filling.

is stable (still rising if NOT isolated). IF;::: 50% THEN perform the following:

• Stop RMW pump(s) .
• Close MOV-823 . * (Step 12 Continued)

Surge tank level -STABLE HCO (Step 13) Direct RP To Sample CCW System NOTE: The CRS may notify For Chromates RP. SIM DRIVER: as RP, acknowledge. HCO/ (Step 14) Evaluate MCB Annunciator Status co (Refer to AR Procedures) CRS (Step 15) Evaluate Plant Conditions: Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# ------Page 12 of 49 ---11 Event

Description:

Leak on the eew System/B eew Pump Trips . *Expected Actions/Behavior* . . .. Time Pos. ..: f:omments .

• CCW system malfunction

-IDENTIFIED NOTE: Although the leak has AND CORRECTED. been isolated, the A CCW Pump has tripped, and needs to be evaluated.

• CCW system status adequate for power operation (Refer to ITS Section 3.7.7). CRS (Step 16) Notify Higher Supervision NOTE: The CRS may notify theWCC. SIM DRIVER: as wees, acknowledge.

CRS (Step 17) Return To Procedure Or Guidance In Effect NOTE: The CRS will likely check the Tech Specs. TECHNICAL SPECIFICATION 3.7.7, COMPONENT COOLING (CCW) WATER SYSTEM CRS 3.7.7 Two CCW trains, two CCW heat exchangers, and the CCW loop header shall be OPERABLE. CRS APPLICABILITY: MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED COMPLETION ACTION TIME A. OneCCW A.1 Restore 72 hours train CCW train to inoperable. OPERABLE status. NOTE: The CRS will likely conduct a Plant Status Brief. At the discretion of the Lead Examiner move to Event #2. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# ------Page 13 of 49 -------ll Event

Description:

Leak on the CCW System/B CCW Pump Trips Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# Page 14 of 49 2 Event

Description:

PZR Level Channel 427 fails LOW After this, Pressurizer Level Channel 427 will fail LOW, resulting in letdown isolation and de-energizing the pressurizer heaters. The crew will respond per AR-F-11, PZR LOW LEVEL 13%, and ER-INST.1, Reactor Protection Bistable Defeat After Instrumentation Loop Failure. They will defeat the failed channel, reset PZR heaters, reduce charging to a single charging pump, and re-establish letdown per S-3.2.E, Placing In or Removing From Service Normal Letdown/Excess Letdown. The crew will start a second charging pump and slowly restore PZR level to program (52%). The operator will address Technical Specification 3.3.1, Reactor Trip System {RTS) Instrumentation, 3.3.3, Post Accident Monitoring (PAM) Instrumentation, and 3.4.9, Pressurizer. SIM DRIVER Instructions: Operate Trigger #2 (PZR03B [O]) Indications Available:

• MCB Annunciator F-4, PRESSURIZER LEVEL DEVIATION

-5 NORMAL +5

• MCB Annunciator F-11, PRESSURIZER LO LEVEL 13%
• VCT Level {LT-112) starts to lower
• L T-427 indicates low compared to remaining PRZR Level Channels
• Normal Letdown has isolated due to one PZR level channel failinq low Time .

.. i* **. '.Actions/Behcit\iioF . *.. *. . . ... *. . *.* Coml"llen.ts

• . NOTE: The CRS may enter ER-INST.1 directly.

AR-F-4, PRESSURIZER LEVEL DEVIATION -5 NORMAL +5 HCO (Step 1) Perform a channel check. NOTE: L T-427 will indicate low compared to the others. HCO (Step 2) Verify Backup Heaters on at + 5% HCO (Step 3) Check charging pump speed and NOTE: Auto pump has controls. reduced to MIN speed. HCO (Step 4) Check Letdown in service. NOTE: Normal Letdown will auto isolate. HCO (Step 5) Control Charging and Letdown as necessary to control level. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# _2 _____ Page 15 of 49 ---11 Event

Description:

PZR Level Channel 427 f'ails LOW Time

Expected Actions/Behavior Comments

' !*' ' ,' ! CRS (Step 6) Go to the appropriate procedure:

• AP-RCS.1 for RCS leak
• ER-INST.1 for failed channel NOTE: The CRS will go to ER-INST.1. AR-F-11, PRESSURIZER LO Level 13% HCO (Step 1) Perform a channel check NOTE: LT-427 will indicate low compared to the others. CRS (Step 2) Go to the appropriate procedure:
• AP-RCS.1 for RCS leak
• ER-INST.1 for failed channel NOTE: The CRS will go to ER-INST.1. ER-INST.1, REACTOR PROTECTION BISTABLE DEFEAT AFTER INSTRUMENTATION LOOP FAILURE HCO (Step 6.1.1) IDENTIFY the failed instrument NOTE: The HCO will identify channel by observation of the bistable status that Ll-427 has failed LOW. light board, MCB annunciators, and the MCB metering indication.

HCO (Step 6.4.2) If letdown isolation valve, AOV-NOTE: Letdown isolated 427 has closed, THEN perform the following:

1. Place charging pump speed controllers in NOTE: The HCO will place MANUAL AND minimize charging flow. Charging Pump Speed in MANUAL. 2. Stop all but one charging pumps (s). NOTE: The HCO will stop one Charging Pump. 3. Adjust HCV-142 as necessary to maintain NOTE: The HCO will close RCP labyrinth seal AP between 20 and 80 HCV-142 due to letdown inches. isolation.

4. Place loop B cold leg to REGEN HX AOV-427 switch (MCB) to close position Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

2 Event# 2 Page 16 of 49 Event

Description:

PZR Level Channel 427 fails LOW Time 'iPos. <Expected Actions/Behavior . . . . .. . . *. . Comrilents

• • . 5. Consider placing excess letdown in NOTE: CRS will likely defeat service, refer to S-3.2E, PLAC1ING IN OR channel and then return REMOVING FROM SERVICE NORMAL Normal Letdown to service.

LETDOWN/EXCESS LETDOWN HCO (Step 6.3.4) REFER TO the appropriate NOTE: The CRS will go attachment to defeat the associated control Attachment 10, White Channel functions: -PRZR Level Ll-427. Attachment 9, Red Channel -PRZR Level LI-426 Attachment 10, White Channel -PRZR Level Ll-427 Attachment 11, Blue Channel -PRZR Level Ll-428 NOTE: The CRS will hand this off to the CO. ER-INST.1, REACTOR PROTECTION BISTABLE DEFEAT AFTER INSTRUMENTATION LOOP FAILURE ATTACHMENT 10 WHITE CHANNEL-PRZR LEVEL Ll-427 NOTE: The CO will likely conduct Instrument Defeat Brief. HCO (Step 1) Ensure Charging pump controllers are in MANUAL co (Step 2) In the PLP PRESS AND LEVEL NOTE: The CO will unlock and rack, check the PRZR level defeat switch open the PLP PRZR PRESS L/428A position. AND LEVEL Rack Cabinet, take the required action, and then close and lock the cabinet door.

• IF L/428A is in NORMAL, THEN place L-428A to DEFEAT-2.

co (Step 3) Notify the CRS that PRZR Heaters and Letdown can now be restored per steps 6.4.4 and 6.4.5. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# _2 ________ Page 17 of 49 Event

Description:

PZR Level Channel 427 fails LOW Time Pos. .* : ,, ... Comments 'i; . . .. co (Step 4) DETERMINE the expected Bistable proving light status for the post defeat condition as follows: RECORD the following Data:

• PRZR Level Ll-427 % co (Step 5) DETERMINE the expected post defeat Bistable proving light status and circle the expected status in table below:
• 427 CHANNEL 2 HIGH LEVEL TRIP NOTE: The CO will determine Light OFF if Ll-427 that the Proving Light should be ON in the Post-Defeat condition.

co (Step 6) In the (WHITE) W-1 PROTECTION NOTE: The CO will unlock and CHANNEL 2 rack, PLACE the following open the W-1 PROTECTION bistable proving switches to DEFEAT (UP) CHANNEL 2 Rack Cabinet, AND verify the proving light status is correct: take the required action, and 427 CHANNEL 2 then close and lock the cabinet HIGH LEVEL TRIP door. NOTE: The B/S proving light should be ON after defeat. HCO (Step 7) PLACE the PRZR level recorder transfer switch (MCB) to position 428. HCO (Step 8) VERIFY the bistable status lights AND Annunciators listed above are lit. HCO/ (Step 9) Remove the PRZR level channel co from the PPCS, by performing the following:

• On the "Sub/Delete/Restore" display
• Select Point ID L0427
• Turn "OFF" scan processing

.

• Select "Change"

.

• Answer prompts Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

2 Evemt # 2 Page 18 of 49 Event

Description:

PZR Level Channel 427' fails LOW .Pos. *' Expected Actions/Behavior Ccmurients Time ,*, CRS (Step 10) GO TO step 6.4.4 NOTE: The CRS will return to the body of the procedure. ER-INST.1, REACTOR PROTECTION BISTABLE DEFEAT AFTER INSTRUMENTATION LOOP FAILURE HCO (Step 6.4.4) Reset PRZR heaters breakers NOTE: Not necessary as necessary. HCO (Step 6.4.5) Restore normal letdown as NOTE: If excess letdown was follows, if desired. placed on service earlier then Section 6.6 (Removing Excess Letdown from Service) will be performed.

1. COMPLETE removal of normal letdown from service per S-3.2E, PLACING IN OR REMOVING FROM SERVICE NORMAL LETDOWN/EXCESS LETDOWN.

2. RESTORE normal letdown per S-3.2E, PLACING IN OR REMOVING FROM SERVICE NORMAL LETDOWN/EXCESS LETDOWN.

NOTE: The CRS will continue with ER-INST.1. S-3.2E, PLACING IN OR REMOVING FROM SERVICE NORMAL LETDOWN/EXCESS LETDOWN NOTE: This action will complete the removal of Normal Letdown from Service. HCO/ (Step 6.2.1) PLACE Charging Pumps in co MANUAL HCO/ (Step 6.2.2) ENSURE CLOSED Letdown co Orifice isolation valves. AOV-200A AOV-2008 AOV-202 Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# _2 _____ Page 19 of 49 ---11 Event

Description:

PZR Level Channel 427 fails LOW ,, 1Time Pos. Expected C()mments " ' ,' :'.' ,} " >" HCO/ (Step 6.2.3) CLOSE LTDN ISOLATION VLV co RHR to NRHX, AOV-427. HCO/ (Step 6.2.4) REDUCE charging flow while co throttling closed charging flow to Regenerative Heat Exchanger HCV-142 to maintain greater than 20" RCP labyrinth seal L'lP. HCO/ (Step 6.2.5) CLOSE LETDOWN ISOL VLV co RHR TO NRHX AOV-371. HCO/ (Step 6.2.6) PLACE NRHX L TDN OUTLET co TEMP (Tl-130) TCV-130 in MANUAL/ CLOSED. HCO/ (Step 6.3.1) 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 6.4 and N/A minutes, a flush will NOT be section 6.5 with permission of the Shift required. Manager or Control Room Supervisor. HCO/ (Step 6.4.1) Restore Letdown Without a co Flush HCO/ (Step 6.4.1.1) ENSURE letdown is secured co PER Section 6.2 prior to restoring. HCO/ (Step 6.4.1.2) IF charging flowpath to Loop B co COLD Leg is desired (preferred method), THEN PERFORM the following: ENSURE CLOSED CHARGING VLV RHX TO LOOP B HOT, AOV-392A. OPEN CHARGING VLV RHX TO LOOP B COLD LEG AOV-294. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Evemt # Page 20 of 49 2 Event

Description:

PZR Level Channel 427' fails LOW Time Pos .. ,' Expected Actions/Behavior !l Comments' HCO/ (Step 6.4.1.3) IF Charging flowpath to Loop NOTE: Charging alignment to co B HOT leg is desired, ..... the Hot Leg will NOT be desired. HCO/ (Step 6.4.2) START a second Charging co Pump at minimum speed. HCO/ (Step 6.4.3) SLOWLY OPEN charging flow to co Regenerative Heat Exchanger HCV-142 to reduce labyrinth seal to -40". HCO/ (Step 6.4.4) ADJUST Pump speed co while maintaining -40" labyrinth seal UNTIL HCV-142 is fully OPEN. HCO/ (Step 6.4.5) ESTABLISH greater than or co equal to 22 gpm charging line flow. HCO/ (Step 6.4.6) IF placing 40 GPM orifice in NOTE: A 60 gpm Orifice was co service ........ previously in service. HCO/ (Step 6.4.7) IF placing 60 GPM orifice in co service THEN .... PLACE LOW PRESS L TDN PRESS PCV-135 in MANUAL at -60% open. PLACE NRHX L TDN OUTLET TEMP (Tl-130) TCV-130 in MANUAL at -60% open. HCO/ (Step 6.4.8) OPEN LETDOWN ISOL VLV co RHR TO NRHX AOV-371. HCO/ (Step 6.4.9) PLACE L TDN LOOP B COLD co LEG TO RHX AOV-427 to OPEN and THEN to AUTO. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# 2 Page 21 of 49 Event

Description:

PZR Level Channel 427 fails LOW Time Pos. .E?('pected Actions/Behavior > .* *.*comments . HCO/ (Step 6.4.10) OPEN desired Letdown orifice co valve AOV-200A, AOV-2008, or AOV-202 AND MARK AOV's not opened N/A. AOV-200A AOV-2008 AOV-200 HCO/ (Step 6.4.11) ADJUST LOW PRESS L TDN co PRESS PCV-135 to achieve Letdown pressure of -250 psig on Pl-135. HCO/ (Step 6.4.12) PLACE LOW PRESS L TDN co PRESS, PCV-135 IN AUTO. HCO/ (Step 6.4.13) PLACE NRHX L TDN OUTLET Examiner NOTE: At the co TEMP (Tl-130) TCV-130 in AUTO at the discretion of the Lead setpoint recorded in Step 5.4. Examiner move to Event #3. HCO/ (Step 6.4.14) PLACE Pressurizer level co control (Charging Pump) to AUTO. ER-INST.1, REACTOR PROTECTION BISTABLE DEFEAT AFTER INSTRUMENTATION LOOP FAILURE HCO (Step 6.4.6) WHEN PRZR level is restored to normal, THEN place an operatini;:i charging pump controller in AUTO. HCO (Step 6.3.6) Open associated block valve NOTE: No Block Valve was closed in step 4.4.3 Closed. CRS (Step 6.4. 7) Check the following ITS Sections for LCOs:

• Section 3.3.1, Table 3.3.1-1, Function 8
• Section 3.3.3, Table 3.3.3-1, Function 2

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# 2 Page 22 of 49 Event

Description:

PZR Level Channel 427 fails LOW Time" Pos.

• Expected Actions/Behavior Comments
• Section 3.4.9 CRS (Step 6.4.8) GO TO Step 6.15. HCO (Step 6.15.1) IF necessary, VERIFY an operable channel is selected for the affected recorder.

HCO (Step 6.15.2) Verify the following systems in AUTO if desired: 0 Rod Control co 0 Turbine EH control HCO 0 PRZR Pressure control

• HC 431K
• PRZR spray valves
• PRZR heaters HCO 0 PRZR level control co 0 Steam Dump (unless 1st stage pressure failed) co 0 MFW control co 0 S/G Atmos Relief Viv Control CRS (Step 6.15.3) NOTIFY the following people: NOTE: The CRS may notify 0 Operations Supervision the SM/STA/WWM.

0 STA SIM DRIVER: as 0 Work Week Manager SM/STA/WWM, acknowledge. CRS (Step 6.15.4) REFER to the following for NOTE: The CRS may ask the Notification Requirements: SM. SIM DRIVER: as SM, acknowledge. CNG-NL-1.01-1004, REGULATORY REPORTING OPG-NOTI

FICATION, REQUIRED NOTIFICATIONS TO THE PSC/PIO/CEG SENIOR MANAGEMENT/OPERATIONS MANAGEMENT Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

2 Event# _2 _____ Page 23 of 49 Event

Description:

PZR Level Channel 427 fails LOW . . > . Pqs.: .. Comments Time Expected Actions/Be.havior !*'. *; .. NOTE: The CRS will address the Technical Specifications. TECHNICAL SPECIFICATION 3.3.1, REACTOR TRIP (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 3.3.1-1 (Function

8) ACTIONS CONDITION REQUIRED COMPLETION NOTE: Function 8 is affected.

ACTION TIME A. One or more A.1 Enter the Immediately functions with Condition one channel referenced in inoperable. Table 3.3.1-1 for the channel(s). D. As required D.1 6 hours by Required Place channel in Action A.1 and trip referenced by Table 3.3.1-1 TECHNICAL SPECIFICATION 3.4.9, PRESSURIZER CRS LCO 3.4.9: The pressurizer shall be OPERABLE. CRS APPLICABILITY: modes 1, 2 and 3. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# 2 Page 24 of 49 ---11 Event

Description:

PZR Level Channel 427 fails LOW * .* *pos. . .. Expected Actions/Behavior

• • .. < Comments)"

Time .. , ,c i', CONDITION REQUIRED COMPLETION NOTE: The CRS will identify ACTION TIME that the crew was in this TS B. Pressurizer B.1 Be in MODE 6 hours. LCO when the Heaters tripped heaters 3. on low pressurizer level, and capacity not within limits. AND out of this TS LCO when the heaters were reset. B.2 Be in MODE 4. 12 hours. NOTE: The CRS may address LCO 3.3.3, but determine that this TS is met using in-service instruments. At the discretion of the Lead Examiner move to Event #3. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# Page 25 of 49 3 Event

Description:

Turbine Control Valve CV-L4 Drifts Closed Then, turbine control valve CVL-4 will drift closed. The crew will respond per AP-TURB.2, Turbine Load Rejection, begin a load reduction to less than 50% power using AP-TURB.5, Rapid Load Reduction. SIM DRIVER Instructions: Operate Trigger #3 (TUR11 B (20 over 20 seconds)) Indications Available:

• MW lowering on turbine
• CLV-4 closing/closes
• Rx Power lowering (7-8% change)
• Tref lowering
• Rods stepping in to lower Tavg
• RCS Pressure lowering during transient
• MCB Annunciator AR-G-15, STEAM DUMP ARMED
• Steam dumps cycle * * ** .* Expected;Actions/Behavior\

.;tc11ic:;.:;::J1K Cotri1ments Time *POS; ' '*' "' ,,,, ,",' ,, j *. AP-TURB.2, TURBINE LOAD REJECTION HCO (Step 1 *) Montor RCS Tavg

• Tavg-GREATER THAN 545°F
• Tavg-LESS THAN 579°F co (Step 2) Check Turbine Valves:
• Turbine stop valves and reheat steam valves-OPEN
• Turbine control valves-ALL VALVES AT APPROXIMATELY THE SAME POSITION CRS (Step 2 RNO) If failure of turbine control NOTE: The CRS may use valves indicated, THEN reduce power to less both AP-TURB.2 and 5 than 80% (refer to AP-TURB.5, RAPID simultaneously during the LOAD REDUCTION).

down power. SIM DRIVER: as Plant Management, direct that power be lowered to 70%. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# _3 _____ Page 26 of _4_9_-11 Event

Description:

Turbine Control Valve CV-L4 Drifts Closed Time Pos. Expected Actions/Behavior ' comments. NOTE: The CRS will go to AP-TURB.5 and conduct Rapid Load Reduction Brief prior to commencing load reduction. AP-TURB.5, RAPID LOAD REDUCTION HCO (Step 1) Initiate Load Reduction a) Verify rods in AUTO co b) Reduce turbine load in Auto as follows:

• Place Turbine EH Control in NOTE: OPER PAN IMP OPER PAN., IMP PRESS IN, if PRESS IN is desired.

desired.

• Select desired rate on NOTE: The operator will thumbwheel select 1 %/Min.
• Reduce the setter to the desired load
• Depress the GO button HCO c) Initiate boration at the rate NOTE: The HCO will initiate a determined in OPG-REACTIVITY-boration.

CALC HCO d) Place PRZR backup heaters switch to ON HCO (*Step 2) Monitor RCS Tavg NOTE: This is a Continuous

• Tavg-GREATER THAN 545°F Action. The CRS will make both board operators aware.
• 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
• Match Tavg and Tref
• Compensate for Xenon Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

2 Event# _3 _____ Page 27 of _4_9_-11 Event

Description:

Turbine Control Valve CV-L4 Drifts Closed Time Pos. ,, Expected Actions/Behc:lvi(:>r <;[ **comments HCO (*Step 4) Monitor PRZR Pressure-NOTE: This is a Continuous TRENDING TO 2235 PSIG IN AUTO Action. The CRS will make both board operators aware. co (*Step 5) Monitor MFW Regulating Valves-NOTE: This is a Continuous RESTORING SIG LEVEL TO 52% IN AUTO Action. The CRS will make both board operators aware. HCO (*Step 6) Monitor PRZR Level-TRENDING NOTE: This is a Continuous TO PROGRAM IN AUTO CONTROL Action. The CRS will make both board operators aware. co (Step 7) Check IA Available To CNMT IA pressure -GREATER THAN 60 PSIG Instr Air to CNMT lsol Valve, AOV-5392 -OPEN HCO/ (Step 8) Check Steam Dump Status: co Annunciator G-15, STEAM DUMP ARMED -NOTE: The Steam Dump LIT System will be ARMED. Steam dump operating properly in AUTO co (Step 9) Check Hotwell Level: Hotwell level controller in AUTO Controller demand LESS THAN 60% Hotwell level at setpoint co (Step 9 RNO) IF controller demand approaching 70% (large Reject Valve Opens), THEN place controller in Manual and control level. CRS/ (Step 10) Check If Condensate Booster co Pumps Should Be Secured Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# Page 28 of 49 -----------

---

ii 3 Event

Description:

Turbine Control Valve CV-L4 Drifts Closed Time Pos. Expected Actions/Behavior Corrimen!$, ,, ... Condensate booster pumps -2 PUMPS NOTE: There are two RUNNING Condensate Booster Pumps running. Verify the following: Verify reactor power is 70%-75'Vo NOTE: Rx power is expected to be> 75%. CRS (Step 10.b RNO) Go to Step 18. CRS (Step 18) Evaluate Plant Status IF load was reduced more than 15% RTP in NOTE: The CRS may call one hour, THEN notify RP to obtain primary Chemistry to address the samples required by ITS LCO 3.4.16 samples. If so, SIM DRIVER acknowledge as Chemistry (Note that Sample Coolers were previously isolated). NOTE: The CRS address remaining steps of AP-TURB.2 while continuing the power reduction. (While still in downpower) At the discretion of the Lead Examiner move to Event #4. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# _4 _____ Page 29 of Event

Description:

B FRV fails AS-IS {Manual Control Available) During the load reduction, a failure of the B FRV to control in AUTO. The operator will respond per AR-G-5, SIG/ B LEVEL DEVIATION +/-7%, or upon observing an abnormally high level in the B Steam Generator and control the B FRV manually. The operator will address Technical Specification 3.7.3, Main Feedwater Isolation Valves (MFIVs), Main Feedwater Regulating Valves (MFRVs), and Associated Bypass Valves. SIM DRIVER Instructions: Operate Trigger #4 (FDW07C (Current Controller Output in%)) Indications Available:

• Feed flow in the B SG will stabilize the downpower
• B SG level starts to rise .
• MCB Annunciator G-22, ADFCS SYSTEM TROUBLE
• MCB Annunciator G-5, SIG LEVEL DEVIATION

+/-7% Time Pos. Expected ! Comments , NOTE: The CO will dispatch the AO to the relay room to check the ADFCS Panel. SIM DRIVER: as AO report that ADFCS Panel indicates "Control Card Failure" after 3 minutes. AR-G-5, SIG LEVEL DEVIATION +/-7% co (Step 4.1) PERFORM a channel check of the following:

• Ll-471
• Ll-472
• Ll-473 co (Step 4.2) IF Main Feedwater is supplying the SIG, THEN PERFORM the following as necessary:
• PLACE SG B MFW REG VLV HCV-476 NOTE: The CO will take in MANUAL. manual control of the B FRV, and control B S/G level manually.
• PLACE FW FLOW LOOP B BYPASS VLV HCV-481 in
• MANUAL .
• CONTROL SG level manually

. Appendix D Operator Action Form ES-0-2 Op Test No.: N2014-301 Scenario# 2 Event# _4 _____ Page 30 of 49 Event

Description:

B FRV fails AS-15 (Manual Control Available) Time Pos. Expected Actions/Behavior Comments NOTE: The CRS will most likely NOT check the Tech Specs during the transient. The Examiner may need to check this after the scenario TECHNICAL SPECIFICATION 3.7.3, MAIN FEEDWATER ISOLATION VALVES (MFIVS), MAIN FEEDWATER REGULATING VALVES (MFRVS), AND ASSOCIATED BYPASS VALVES CRS 3.7.3 Two MFIVs, two MFRVs, and associated bypass valves shall be OPERABLE. CRS APPLICABILITY: MODES 1, 2, and 3 except when both steam generators are isolated from both main feedwater pumps. ACTIONS CONDITION REQUIRED COMPLETION ACTION TIME B.One or more B.1 Close or 72 hours MFRV(s) isolate inoperable. MFRV(s). AND B.2 Verify Once per 7 day MFRV(s) is closed or isolated. NOTE: The CRS will likely conduct a Plant Status Brief. At the discretion of the Lead Examiner move to Events #5-8. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# _5_.,_6..._, 7_&_8 __ Page _31_ of _4_9_1 Event

Description:

MSLB Downstream of MSIVs with MSIVs Stuck OPEN I RPS fails to Trip Rx in AUTO/Manual Pushbutton /Steam Break Degrades Creating PTS Concern I Loss of Offsite Power Subsequently, a major steamline break will occur in the Turbine Building downstream of the MSIVs. Both MSIVs will fail to close automatically in response to manual attempts from the MCB. The reactor will fail to trip automatically and manual pushbutton will not work, requiring opening of normal supply breakers for Bus 13 and Bus 15 to deenergize rod drive MG sets to trip the reactor. The crew will enter E-0, Reactor Trip or Safety Injection. The crew will ultimately transition to E-2, Faulted SIG Isolation. Since both MSIVs are failed open, and with a downstream break, both SGs will be affected and their pressures will lowe1r concurrently. Eventually, the crew will transition to ECA-2.1, Uncontrolled Depressurization of Both Steam Generators. After the operator throttles AFW flow in ECA-2.1, the leak will increase in magnitude, resulting in an Orange Path on RCS Integrity. Simultaneously the event will be complicated by a Loss of Offsite Power. Both Emergency Diesel Generators will start and automatically repower the respective Emergency Susses, and the operator will need to re-establish AFW flow of 50 gpm to each Steam Generator. The crew will implement FR-P.1, Response to Imminent Pressurized Thermal Shock Condition, when RCS cold leg temperatures reach 311°F. In FR-P.1 the crew will stop the SI pumps and the RHR pumps. The scenario will be terminated after the SI and RHR pumps are secured. SIM DRIVER Instructions: Operate Trigger #5 (STM03 (1 E+6), FDS-1-237 [15 seconds delayed]) Indications Available:

• Numerous MCB Annunciators.
• Pressurizer pressure and level start to lower.
• RCS Tavg starts to lower.
• Steam break heard in Control Room.
• Intermediate Building Fire alarm (15 seconds delayed).

Time Pos., ;'Expected Actions/Behavior ,j *. ! \I .I' ,' ' .. ,, ,,. " E-0, REACTOR TRIP OR SAFETY INJECTION HCO (Step 1) Verify Reactor Trip: Immediate Action

• At least one train of reactor trip breakers

-OPEN

• Neutron flux -LOWERING NOTE: The reactor will NOT trip automatically or via manual pushbutton.
• MRPI indicates

-ALL CONTROL AND SHUTDOWN RODS ON BOTTOM Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# _5 ..... _6 ...... 7_&_8 __ Page of _4_9_-11 Event

Description:

Time Pos; HCO ,, MSLB Downstream of MSIVs with MSIVs Stuck OPEN I RPS fails to Trip Rx in AUTO/Manual Pushbutton I Steam Break Degrades Creating PTS Concern I Loss of Offsite Power Expected Actions/Behavior '* Com,ments . (Step 1 RNO) Manually trip reactor. Immediate Action

• IF reactor trip breakers NOT open, THEN perform the following:
• Open Bus 13 and Bus 15 normal feed breakers.
• Verify rod drive MG sets tripped .
• Close Bus 13 and Bus 15 normal feed breakers.
• Reset lighting breakers

.

• IF the reactor will NOT trip OH IF power NOTE: The reactor will Trip range NIS indicates greater than 5%, when the Rod Drive MG THEN Sets are de-energized.

CRITICAL TASK 1. Manually trip the reactor from the control room before transition to FR-S.1 Safety Significance: Failure to manually trip the reactor causes a challenge to the subcriticality CSF beyond that irreparably introduced by the postulated conditions. Additionally, it constitutes an "incorrect performance that necessitates the crew taking action which complicates the event mitigation strategy that demonstrates the inability by the crew to recognize a failure of the automatic actuation of the RPS. co (Step 2) Verify Turbine Stop Valves -Immediate Action CLOSED co (Step 3) Verify Both Trains of AC Emergency Immediate Action Susses Energized to at Least 440 VOL TS:

• Bus 14 and Bus 18
• Bus 16 and Bus 17 HCO (*Step 4) Check if SI is Actuated:

Immediate Action Appendix D Operator Action Form ES-0-2 Op Test No.: N2014-301 Scenario# 2 Event# 5, 6, 7 & 8 Page :.:...._ of Event

Description:

Time Pos. HCO/ co HCO CRS MSLB Downstream of MSIVs with MSIVs Stuck OPEN I RPS fails to Trip Rx in AUTO/Manual Pushbutton I Steam Break Degrades Creating PTS Concern l Loss of Offsite Power .. Expected Actions/Behavior , Comments

• Any SI Annunciator-LIT NOTE: Based on Pressurizer

Pressure, the HCO may Manually actuate SI and Cl. If Not, auto actuation will occur.

• SI sequencing

-BOTH TRAINS STARTED. Foldout Page NOTE: The crew will monitor these conditions throughout the performance of E-0. RCP TRIP CRITERIA LOSS OF SW CRITERIA AFW SUPPLY SWITCHOVER CRITERION SFP COOLING CRITERIA NOTE: The CRS may dispatch an AO to address the status of the SFPCS. If so, SIM DRIVER acknowledge as AO, and report in 5 Minutes that the SFPCS is operating normally. (*Step 5) Verify CNMT Spray Not Required:

• Annunciator A-27, CNMT SPRAY -EXTINGUISHED
• CNMT pressure-LESS THAN 28 PSIG NOTE: Containment Pressure will be normal (The Steam Break is outside Containment).

(Step 6) Direct Operator to Perform ATT-27.0, ATTACHMENT AUTOMATIC ACTION VERIFICATION Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# _5_.,_6.._, 7_&_8__ Page ::.__ of _4_9_-11 Event

Description:

Time Pos. MSLB Downstream of MSIVs with MSIVs Stuck OPEN I RPS fails to Trip Rx in AUTO/Manual Pushbutton I Steam Break Degrades Creating PTS Concern I' Loss of Offsite Power Expected Actions/Behavior , ,, Comments NOTE: The CRS will hand off ATT-27.0 to either the HCO or the CO, and continue with the other operator in E-0. Examiner following operator performing ATT-27.0 continue below. Examiner following operator NOT performing ATT-27.0 continue at Page 37. E-0, REACTOR TRIP OR SAFETY INJECTION, ATTACHMENT 27.0, ATTACHMENT AUTOMATIC ACTION VERIFICATION HCO/ (Step 1) Verify SI and RHR Pumps Running: co

• All SI pumps -RUNNING
• Both RHR pumps -RUNNING HCO/ (Step 2) Verify CNMT RECIRC Fans co Running:
• All fans -RUNNING
• Charcoal filter dampers green status lights-EXTINGUISHED HCO/ (Step 3) Check If Main SteamlinHs Should Be co Isolated:
• Any MSIV -OPEN
• Check CNMT pressure-LESS THAN 18 PSIG
• Check if ANY main should be isolated:
• Low Tavg (545°F) AND high steam NOTE: Tavg will be LOW flow (0.5x106 lb/hr) from either S/G with Hi Steam Flow from both S/Gs. OR Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

2 Event# _5_.,_6.._, 7_&_8 __ Page of Event

Description:

Time Pos. HCO/ co HCO/ co HCO/ co HCO/ co MSLB Downstream of MSIVs with MSIVs Stuck OPEN I RPS fails to Trip Rx in AUTO/Manual Pushbutton I Steam Break Degrades Creating PTS Concern I Loss of Offsite Power Expected , "' , , , , ,, Comments

• High-High steam flow (4.4x106 lb/hr) from either SIG
• Verify MSIV closed on the affected NOTE: The HCO/CO will S/G(s) attempt to close the MSIVs however, they will NOT Close. (Step 3.d RNO) Manually close valves. (Step 4) Verify MFW Isolation:
• MFW pumps -TRIPPED
• MFW Isolation valves -CLOSED
• SIG A, AOV-3995
• SIG B, AOV-3994
• SIG Slowdown and sample valves -CLOSED (Step 5) Verify At Least Two SW Pumps -RUNNING (Step 6) Verify Cl and CVI:
• Cl and CVI annunciators

-LIT

• Annunciator A-26, CNMT ISOLATION
• Annunciator A-25, CNMT VENTILATION ISOLATION
• Verify Cl and CVI valve status lights -BRIGHT
• CNMT RECIRC fan coolers SW outlet valve status lights -BRIGHT
• FCV-4561
• FCV-4562 Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

2 Event# _5_.,_6 .... , 7_&_8 __ Page _4_9_...i Event

Description:

Time **Pos .. HCO/ co HCO/ co HCO/ co MSLB Downstream of MSIVs with MSIVs Stuck OPEN I RPS fails to Trip Rx in AUTO/Manual Pushbutton I Steam Break Degrades Creating PTS Concern I Loss of Offsite Power . Actions/Behavior Comments**

• Letdown orifice valves -CLOSED
• AOV-200A
• AOV-2008
• AOV-202 (Step 7) Check CCW System Status:
• Verify CCW pump-AT LEAST ONE RUNNING (Step 8) Verify SI and RHR Pump Flow:
• 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 psig ....... 150 psig. (Step 9) Verify SI Pump and RHR Pump Emergency Alignment:

• RHR pump discharge to Rx vessel deluge -OPEN
• MOV-852A
• MOV-8528
• Verify SI pump C -RUNNING
• Verify SI pump A -RUNNING
• Verify SI pump 8 -RUNNING
• Verify SI pump C discharge valves -OPEN
• MOV-871A
• MOV-8718 Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

2 Event# _5_.,_6.._, 7_&_8 __ Page of _4_9_-11 Event

Description:

Time HCO/ co HCO/ co HCO/ co HCO/ co HCO/ co MSLB Downstream of MSIVs with MSIVs Stuck OPEN I RPS fails to Trip Rx in AUTO/Manual Pushbutton I Steam Break Degrades Creating PTS Concern I Loss of Offsite Power ;t" *' . ' ' " ... Comments Expected Actions/Behavior .. (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 (Step 11) Verify Cl and CVI During a Fire Event A confirmed fire has occurred in the control complex or cable tunriel (fire systems SOS, S06,S08,Z05,Z18,orZ19).

(Step 11 RNO) Go to END E-0, REACTOR TRIP OR SAFETY INJECTION Examiner following operator NOT performing ATT-27.0 continue HERE. (Step 7) Verify Both MDAFW Pumps Running (Step 8) Verify AFW Valve Alignment:

• AFW flow-INDICATED TO BOTH S/G(s)
• AFW flow from each MDAFW pump -LESS THAN 230 GPM (*Step 9) Monitor Heat Sink:

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# _5_.,_6._, 7_&_8 __ Page of _4_9_-i1 Event

Description:

Time , Pos.',, co CRS co HCO HCO HCO MSLB Downstream of MSIVs with MSIVs Stuck OPEN I RPS fails to Trip Rx in AUTO/Manual Pushbutton I Steam Break Degrades Creating PTS Concern I Loss of Offsite Power Expected Actions/Behavior " Comments

• Check S/G narrow range level ,_ GREATER THAN 7% [25% ADVERSE CNMT] in any S/G (Step 9.a RNO) Perform the following:

Verify total AFW flow -GREATER THAN NOTE: AFW flow is 200 GPM expected to be 200 gpm. IF total AFW is less than 200 gpm, THEN .... Go to Step 10. (Step 10) Check If TDAFW Pump Can Be Stopped:

• Both MDAFW pumps -RUNNING NOTE: Both of the AFW Pumps are running.
• PULL STOP TDAFW pump steam supply valves
• MOV-3504A
• MOV-3505A (Step 11) Check CCW Flow to RCP Thermal Barriers:
• Annunciator A-7, RCP 1A CCW RETURN HI TEMP OR LO FLOW EXTINGUISHED
• Annunciator A-15, RCP 1 B CCW RETURN HI TEMP OR LOW FLOW -EXTINGUISHED

(*Step 12) Monitor RCS Tavg -STABLE AT NOTE: Tavg is ==400°F and OR TRENDING TO 547°F lowering. (Step 12 RNO) If temperature less than 54 7°F and lowering, THEN perform the following:

• Stop dumping steam .

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# _5,,_6 ..... _7_&_8 __ Page ::..__ of _4_9 __ 11 Event

Description:

Time* Pos. HCO HCO CRS MSLB Downstream of MSIVs with MSIVs Stuck OPEN I RPS fails to Trip Rx in AUTO/Manual Pushbutton I Steam Break Degrades Creating PTS Concern I Loss of Offsite Power .Expected*.Actions/Behavior

• comments
• 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 SIG.
• WHEN SIG level greater than 7% [25% adverse CNMT] in one SIG, THEN limit feed flow to that required to maintain level in at least one SIG.
• IF cooldown continues, THEN close both NOTE: The MSIVs have MS IVs. failed OPEN, and cannot be closed. (Step 13 ) Check PRZR PORVs and Spray Valves:
• PORVs -CLOSED
• Auxiliary Spray Valve (AOV-296)

-CLOSED

• Check PRZR pressure

-LESS THAN 2260 PSIG

• Normal PRZR spray valves -CLOSED
• PCV-431A
• PCV-4318 (Step 14) Monitor RCP Trip Criteria:
• RCP status -ANY RCP RUNNING NOTE: The RCPs are both running.
• SI pumps -AT LEAST TWO RUNNING
• RCS pressure minus maximum SIG NOTE: The RCP trip criteria pressure

-LESS THAN 210 psi [240 psi is NOT met. adverse CNMTl (Step 14c RNO) Go to Step 15. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# _5 ......... 6.._, _7 _&_B __ Page of _4_9 __ 11 Event

Description:

Time Pos. co CRS HCO/ co co co CRS MSLB Downstream of MSIVs with MSIVs Stuck OPEN I RPS fails to Trip Rx in AUTO/Manual Pushbutton I Steam Break Degrades Creating PTS Concern I Loss of Offsite Power ' Expected Actions/Behavior ... Comments (Step 15) Check If S/G Secondary Side Is NOTE: The A SG is Intact: depressurizing in an

• Pressure in both S/Gs-ST ABLE OR uncontrolled manner (===200 RISING psig and lowering).
• Pressure in both S/Gs-GREATER THAN 110 PSIG (Step 15 RNO) IF any SIG pressure lowering NOTE: While Steam in an uncontrolled manner OR completely pressure in both SGs is depressurized, THEN go to E-2, FAULTED greater than 110 psig, both STEAM GENERATOR ISOLATION, Step 1. SG pressures are lowering.

NOTE: The CRS will go to E-2. NOTE: The CRS will likely conduct an Alignment Brief. E-2, FAUL TED STEAM GENERATOR ISOLATION Foldout Page NOTE: The crew will monitor these conditions throughout the performance of E-2. LOSS OF SW CRITERIA (Step 1) Check MSIV of Faulted S/G(s) -NOTE: BOTH MSIVs are CLOSED OPEN. (Step 1 RNO) Manually close valve. IF valve will NOT close from MCB, THEN NOTE: The CRS will dispatch AO with locked valve kHy to locally dispatch an AO to address closed faulted S/G(s) MSIV as follows: the status of the MSIVs. If so, SIM DRIVER acknowledge as AO, after 5 minutes, report that steam in the local spaces is preventing access. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# _5 ..... _6._, 7_&_8 __ Page _41_ of Event

Description:

\,' Time Pos. co co MSLB Downstream of MSIVs with MSIVs Stuck OPEN I RPS fails to Trip Rx in AUTO/Manual Pushbutton /Steam Break Degrades Creating PTS Concern I Loss of Offsite Power . . *. . .: Expected Actions/Behavior

• SIGA
• close IA to MSIV, V-5408A
• open vent valves V-5471 AND V-5473
• SIG B
• close IA to MSIV, V-5409B
• open vent valves V-5472 AND V-5474 (Step 2) Check If Any SIG Secondary Side Is Intact:
• Check pressure in SIG A-ST ABLE OR NOTE: The A SG is RISING depressurized.

OR

• Check pressure in SIG B -ST ABLE OR RISING (Step 2 RNO) IF both SIG pressures lowering in an uncontrolled manner, THEN go to ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS, Step 1. NOTE: The CRS will likely conduct an Alignment Brief. ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS HCOI Foldout Page NOTE: The crew will co monitor these conditions throughout the performance of ECA-2.1.

LOSS OF SW CRITERIA SI REINITIATION CRITERIA E-2 TRANSITION CRITERIA COLD LEG RECIRCULATION SWITCHOVER CRITERION Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# _s ..... _6 ..... _7_&_8 __ Page of Event

Description:

Time Pos. co CRS MSLB Downstream of MSIVs with MSIVs Stuck OPEN I RPS fails to Trip Rx in AUTO/Manual Pushbutton I Steam Break Degrades Creating PTS Concern I Loss of Offsite Power

• Expected Actions/Behavior Comments AFW SUPPLY SWITCHOVER CRITERION E-3 TRANSITION CRITERIA (Step 1) Check Secondary Pressure Boundary:

a. Verify all of the following:

• MSIVs -CLOSED NOTE: Both MSIVs are failed OPEN.
• MFW flow control valves -CLOSED
• MFW regulating valves
• MFW bypass valves
• MFW pump discharge valves -NOTE: The CO will re-CLOSED energize MCC A and B to re-power the MFW Pump Discharge Valves.
• SIG blowdown and sample valves -CLOSED
• TDAFW pump steam supply valves -PULL STOP
• TDAFW pump flow control valves -CLOSED
• SIG ARVs -CLOSED (Step 1 RNO) Manually close valves one NOTE: The CRS will loop at time. If valves can NOT be closed. dispatch an AO to address THEN dispatch AO to locally isolate the status of the MS IVs. flowpaths, one at a time If so, SIM DRIVER acknowledge as AO, after 5 minutes, report that steam in the local spaces is preventing access.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event t:f. _s ..... _6.._, 7_..._& .... s __ Page of _4_9---11 Event

Description:

Time Pos. * .* CRS co co MSLB Downstream of MSIVs with MSIVs Stuck OPEN I RPS fails to Trip Rx in AUTO/Manual Pushbutton I Steam Break Degrades Creating PTS Concern I Loss of Offsite Power Expected J:'ctions/Behavior Comments (Step 1.b) Dispatch AO to locally isolate NOTE: The CRS will S/Gs (Refer to ATT-10.0, ATTACHMENT dispatch an AO. FAULTED S/G) If so, SIM DRIVER acknowledge as AO, after 5 minutes, report that steam in the local spaces is preventing access. (Step 2) Control Feed Flow to Minimize RCS Cool down:

• Check cooldown rate in RCS cold legs -NOTE: The cooldown rate is LESS THAN 100°F/HR likely to be higher than 100°F/HR.

(Step 2a RNO) Lower feed flow to 50 gpm to NOTE: The CO will lower each S/G and go to Step 2c. the AFW flow rate to each SG to 50 gpm in an effort to control the cooldown rate. CRITICAL TASK: 2. Control the AFW flowrate to 50 gpm per SG in order to minimize the RCS Cooldown rate (EXAMINER NOTE: The operator may have difficulty adjusting the flowrate to 50 gpm without the control valve going completely CLOSED) Safety Significance: Failure to control the AFW flow rate to the SGs when able to do so causes a challenge to the subcriticality and RCS Integrity CSFs beyond that irreparably introduced by the postulated conditions. Additionally, it constitutes an "incorrect performance that may necessitate the crew taking action which complicates the event mitigation strategy (Transition to FR-*S.1 on inability to maintain a negative SUR). SIM DRIVER Instructions: Operate Trigger #6 (STM03 (5E+6), EDS01A, and EDS01B) Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# _5_.,_6.._, 7_&_8 __ Page _4_9_-i1 Event

Description:

MSLB Downstream of MSIVs with MSIVs Stuck OPEN I RPS fails to Trip Rx in AUTO/Manual Pushbutton I Steam Break Degrades Creating PTS Concern I Loss of Offsite Power T"; 1me Pos.

• Expected Actions/Behavior Comments Indications Available:
• Numerous MCB Annunciators

.

• Control Room lights go dark .
• Both EmerQ ency Diesels start and repower their respective ESF Susses . NOTE: Since SI is NOT reset, the AFW valves will OPEN fully on Sequencer actuation requiring the operator to re-throttle AFW flow to 50 gpm per SG. CRITICAL TASK: 2. Control the AFW flowrate to 50 gpm per SG in order to minimize the RCS Cooldown rate {EXAMINER NOTE: The operator may have difficulty adjusting the flowrate to 50 gpm without the control valve going completely CLOSED) Safety Significance:

Failure to control the AFW flow rate to the SGs when able to do so causes a challenge to the subcriticality and RCS Integrity CSFs beyond that irreparably introduced by the postulated conditions. Additionally, it constitutes an "incorrect performance that may necessitate the crew taking action which complicates the event mitigation strategy (Transition to FR-S.1 on inability to maintain a negative SUR). Examiner NOTE: The crew will continue on in ECA-2.1 until an Orange Path develops on RCS Integrity, at which time the crew will transition to FR-P.1. NOTE: A Red path on Heat Sink will exist because the operator has throttled AFW flow to 50 gpm per SG. However, FR-H.1 will NOT be addressed because the Red Path exists due to operator action. FR-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# _5_.,_6...,, _7_&_8 __ Page of _4_9 __ 11 Event

Description:

Time Pos. HCO/ co HCO HCO co co MSLB Downstream of MSIVs with MSIVs Stuck OPEN I RPS fails to Trip Rx in AUTO/Manual Pushbutton I Steam Break Degrades Creating PTS Concern I Loss of Offsite Power : Expected Actions/Behavior

; Comments

" Foldout Page NOTE: The crew will monitor these conditions throughout the performance ofFR-P.1. LOSS OF SW CRITERIA (Step 1) Check RCS Pressure -GREATER NOTE: RCS pressure is > THAN 300 PSIG [350 PSIG CNMT] 300 psig. (step 2) Check if RCS Cold Leg NOTE: Cold Leg temperatures -STABLE OR RISING temperatures will be lowering. (Sep 2 RNO) Try to stop RCS cooldown: Ensure S/G ARV's closed Close both SIG MSIVs. NOTE: Both MSIVs have failed OPEN. NOTE: The CRS may dispatch an AO. If so, SIM DRIVER acknowledge as AO, after 5 minutes, report that steam in the local spaces is preventing access. Ensure MFW flow control valves

• MFW regulating valves
• MFW bypass valves Ensure MFW pumps are tripped Ensure reheater steam supply valves are closed. IF S/G pressure less than condensate NOTE: The CO may stop pressure, THEN stop all condensate pumps. the Condensate Pumps. IF RHR system in service, THEN .... NOTE: RHR is NOT in service.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# _5 __ ,_6.._, 7_&_8 __ Page _4_9_-11 Event

Description:

Time* Pos. co co co HCO HCO CRS MSLB Downstream of MSIVs with MSIVs Stuck OPEN I RPS fails to Trip Rx in AUTO/Manual Pushbutton I Steam Break Degrades Creating PTS Concern l Loss of Offsite Power Expected Actions/Behavior .. Comments Control total feed flow to non-faulted SIG(s) NOTE: Both SGs are greater than 200 gpm until narrow range faulted. level greater than 7% [25% adverse CNMT] in at least one non-faulted SIG. WHEN SIG level greater than 7% [25% adverse CNMT] in one non-faulted SIG, THEN limit feed flow to stop RCS cooldown. (Step 3) Check if any SIG Secondary is intact: 0 Pressure in both SIG's-ST ABLE or Rising 0 Pressure in both SIG's Greater than 110 PSIG (Step 3 RNO) Minimize cooldown from faulted SIG's. Close faulted SIG's TDAFW pump steam NOTE: This action has supply valves already been taken.

• SIG A, MOV-3505A
• SIG B, MOV-3504A IF BOTH SIGs faulted, THEN control AFW NOTE: Both SGs are feed flow to 50 GPM to each S/G. faulted.

If ANY SIG NOT FAUL TED, THEN ..... NOTE: Both SGs are faulted. (Step 4) Check PRZR PORV Block Valves: Power to PORV block valves-AVAILABLE Block valves-AT LEAST ONE OPEN. (Step 5) Check PRZR PORV Status: Check Reactor Vessel OverprEissure NOTE: L TOPs is NOT in Protection is on service. service. (Step 5 RNO) Go to step 5d. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 2 Event# _s ..... _,6.._, 7_&_8 __ Page of _4_9_-;i Event

Description:

Time Pos: HCO HCO HCO HCO HCO MSLB Downstream of MSIVs with MSIVs Stuck OPEN I RPS fails to Trip Rx in AUTO/Manual Pushbutton I Steam Break Degrades Creating PTS Concern I Loss of Offsite Power Actions/Behavior

0 Comments (Step 5.d) PRZR pressure

-LESS THAN 2335 psig Verify PRZR PORVs -CLOSED (Step 6) Check if SI Pumps-ANY RUNNING NOTE: All three SI Pumps are running. (Step 7) Check if SI Can be terminated:

• RCS subcooling based on core exit NOTE: SI Termination T/Cs-GREATER THAN :50°F USING Criteria will be met. FIG-1.0, FIGURE MIN SUBCOOLING
• Check RVLIS Indication NOTE: RVLIS is at 100%.
• Fluid Fraction (any RCP running)-GREATER THAN 82% (Step 8) Reset SI (Step 9) STOP SI AND RHR Pumps and Place in AUTO Terminate the Exam at the discretion of the Lead Examiner SRO Examiner Perform Admin JPM A4b on CRS TURNOVER SHEET for NRG Exam Scenario

1. 2 Core Age: EOL Procedure in Use: ACTIONS/NOTES:

100% Power, Equilibrium Xe

• The plant is at 100% power (EOL), and has been at full power Outside Air Temp= 82°F for 145 days. Water Temp= 70°F
• The area has experienced thunderstorms over the last 6 hours, and this is expected to continue for the next 6 hours.
• The B CNMT Spray Pump has been declared INOPERABLE due to excessive inboard vertical vibration during STP-0-3-COMP-B surveillance test yesterday.

Engineering is Boron: 297 ppm RCS LEAKAGE: (gpm) evaluating the data. A-52.4 submitted for ITS 3.6.6, 72 hour _ Total: .021 Action. BAST: 17,400 ppm Identified: .003

• Letdown flow is on the 60 gpm Orifice . RCS Activity:

Normal Unidentified: .018

• The following Alarms are in:
• J-25, SAFEGUARDS EQUIPMENT LOCKED OFF (B Cont Spray Pump OOS)
• Protected equipment IAW OPG Protected Equipment.

Equie.ment Prob/ems/OOS: Planned Activities for Shift: Electrical Sy:stem 0(2erator Declarations See NOTES * !'Jone in effect BAST RWST 151 hour dilution stabilization 2n° hour dilution stabilization (gal) (gal) (gal RMW) (gal RMW) 10% at 1% per minute 70 446 358 181 10% at 10% per hour 68 434 360 185 50% at 1 % per minute 315 2039 2182 1264 50% at 10% per hour 273 1760 1038 591 TURNOVER SHEET for NRC Exam Scenario

1. 2 A-52.4 EQUIPMENT DATE/TIME 005 LCO TITLE EXP DATE ECO 'B' Cont Spray Pump Yesterday, 24hrs ago 3.6.6.A CS system 72 hours 30 hours from now AM A-52.12 EQUIPMENT DATE/TIME 005 TRM/ODCM TITLE EXP DATE ECO PROGRAM:

Ginna Operations Training MODULE: 2014 Initial License Operator Training Class TOPIC: NRC Simulator Exam Scenario N2014-301-3

REFERENCES:

1. Technical Specification

3. 7.5, Auxiliary Feedwater (AFW) System, Amendment 88 2. Technical Specification 3.1. 7, Rod Position Indication, Amendment 114 3. 0-6.9.2, Establishing and/or Transferring Offsite Power to Bus 12A/12B, Rev 02201 4. AR-E-14, LOSS B INSTR. BUS, Rev 12 5. ER-INST.3, Instrument Bus Power Restoration, Rev 01200 6. S-3.2E, Placing In or Removing From Service Normal Letdown/Excess

Letdown, Rev 02700 7. AR-K-32, CV AIR DRYER LOW PRESS SG B/D TANK HIGH LEVEL, Rev 01000 8. Technical Specification 3.8.7, AC Instrument Bus Sources -Modes 1-4, Amendment 80 9. Technical Specification 3.8.9, Distribution Systems -Modes 1, 2, 3 and 4, Amendment 80 10. AR-F-2, PRESSURIZER HI PRESS 2310 PSI, Rev 11 11. AR-F-10, PRESSURIZER LO PRESS 2205 PSI, Rev 10 12. AP-PRZR.1, Abnormal Pressurizer

Pressure, Rev 01700 13. ER-INST.1, Reactor Protection Bistable Defeat After Instrumentation Loop Failure, Rev 03605 14. Technical Specification 3.4.1, RCS Pressure, Temperature, and Flow Departure From Nucleate Boiling (DNB) Limits, Amendment 80 15. Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, Amendment 112 16. Technical Requirement 3.4.3, Anticipated Transient Without Scram (ATWS) Mitigation, Rev Rev 31 17. AR-1-27, ROTOR ECCENTRICITY OR VIBRATION, Rev 01301 18. AP-TURB.3, Turbine Vibration, Rev 01700 19. AP-TURB.5, Rapid Load Reduction, Rev 01600 20. E-0, Reactor Trip and Safety Injection, Rev 04602 21. ATT-27.0, Attachment Automatic Action Verification, Rev 00300 22. E-1, Loss of Reactor or Secondary

Coolant, Rev 04100 23. F-0.3, Heat Sink, Rev 4 24. FR-H.1, Response to Loss of Secondary Heat Sink, Rev 04002 25. ATT-5.1, Attachment SAFW, Rev 01002 26. ATT-22.0, Attachment Restoring Feed Flow, Rev 00600 27. E-2, Faulted Steam Generator Isolation, Rev 01301 Validation Time: 116 Minutes Author: David Lazarony, Essential Training

& Consulting, LLC Facility Review: Rev. 110414 Scenario Event Description NRC Scenario 3 Facility: Ginna Scenario No.: 3 Op Test No.: N2014-301 Examiners: Operators: (SRO) (RO) (BOP) Initial Conditions: The plant is at 48% power (MOL). 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 running for retest. 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. The 767 line will remain OPERABLE throughout the inspection. Turnover: The following equipment is Out-Of-Service: The B AFW Pump is OOS for Bearing Replacement. A-52.4 submitted for ITS 3.7.5, 7 day Action. MRPI for Rod G3 indicates on the bottom, however, this is a confirmed instrumentation problem (l&C is working). 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-BOP l(TS)-SRO 4 TUR05E R-RO Main Turbine High Vibration/Downpower N-BOP N-SRO 5 CND03A C-BOP Hotwell Level Transmitter fails HIGH C-SRO 6 FDW09A M-RO Feed Line Rupture Inside Containment/Turbine fails to Auto Trip M-BOP M-SRO 7 SIS02A C-RO Safety Injection fails to actuate Automatically SIS02B C-SRO 8 RPS07K C-BOP A AFW Pump to Auto Start/Trips after Manual Start!TDAFW Pump REM C-SRO trips on Overspeed/ Standby AFW fails to function FDW32 OVR FDW42A FDW15B * (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Ginna 2014 NRC Scenario

1. 3 Scenario Event Description NRC Scenario 3 The plant is at 48% power (MOL). 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 running for retest. 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. The 767' line will remain OPERABLE throughout the inspection.

The following equipment is Out-Of-Service: The B AFW Pump is OOS for Bearing Replacement. A-52.4 submitted for ITS 3.7.5, 7 day Action. MRPI for Rod G3 indicates on the bottom, however, this is a confirmed instrumentation problem (l&C is working). Shortly after taking the watch, the operator will shift the Electric Line-up from 50/50 to 0/100 in accordance with 0-6.9.2, Establishing and/or Transferring Offsite Power to Bus 12N12B. Shortly afterwards, a loss of the B Instrument Bus will occur. The operator will respond in accordance with AR-E-14, LOSS B INSTR. BUS. Power will be restored to the bus per guidance in ER-INST.3, Instrument Bus Power Restoration, which will include the isolation and establishment of Normal Letdown in accordance with S-3.2E, Placing In or Removing From Service Normal Letdown/Excess Letdown. The operator will address AR-K-32, CV AIR DRYER LOW PRESS SG BID 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. 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 tile 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 TRM-3.4.3, Anticipated Transient Without Scram (ATWS) Mitigation. Following this, a turbine high vibration condition on Bearing #5 will develop within about 3 minutes. The operator will respond in accordance with AR-1-27, 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 to stabilize the vibrations. During the load reduction Hotwell Level Transmitter will fail HIGH. The operator will need to manually control the Hotwell Level Controller. Subsequently, a feed line rupture inside Containment will occur. The Reactor will trip however, the Turbine will fail to trip automatically and Safety Injection will fail to actuate automatically. The operator will enter E-0, Reactor Trip or Safety Injection. 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-0 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-0, and then transition to E-2, Faulted Steam Generator Isolation. Scenario Event Description NRC Scemario 3 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.

Critical Tasks: 1. Manually actuate Safety Injection before transition out of E-0 into ES-0.1 Safety Significance: Failure to actuate Safety Injection when it is required to be actuated, and can be actuated, violates the assumptions of the Safety Analysis and constitutes incorrect performance that could lead to misdiagnosis of the event, implementation of an incorrect mitigation strategy and ultimately degradation of the RCS and/or fuel cladding fission product barriers.

2. Establish feedwater flow into at least one Steam Generator before RCS Bleed and Feed is required.

Safety Significance: Failure to establish feedwater flow into at least one Steam Generator results in the crew having to rely upon the lower-priority action of having to initiate RCS Bleed and Feed to minimize the possibility of core uncovery. Failure to perform this task, when able to do so, constitutes incorrect performance that leads to degradation of the RCS and/or fuel cladding fission product barriers. Bench Mark D D Prior to Crew Briefing Scenario Event Description NRC Scenario 3 SIMULATOR OPERATOR INSTRUCTIONS ACTIVITY DESCRIPTION Reset to Temp l/C 48% power MOL 171. (Built on IC-20) To take B MDAFW pump OOS:

• Pull stop the B MDAFW pump
• Insert OVR-DO-FDW-06A, OFF (4008 Green light OFF)
• Close MOV-4008
• Close MOV-4000A and B
• OVR-DO-FDW21 A=OFF (MOV-4000A Green Lamp)
• OVR-DO-FDW22A=OFF (MOV-40006 Green Lamp) Insert MALF ROD 11-G3 (MRPI G3 on Bottom) Insert SIS02A (SIS Train A fails in AUTO) Insert SIS02B (SIS Train B fails in AUTO) Insert TUR02 (Turbine Fails to AUTO Trip) Insert MALF RPS07K (Autostart failure of A MDAFW pump) Insert OVR-Dl-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 = x06i236b = = 1 to activate when A MDAFW pump manually started Insert MALF FDW11A, 30 second delayed, 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, 8 Mils, 180 second Ramp on T-3 MALF CND03A, 48 inches, on T-4 MALF FDW09A, 2E+7, 120 second Ramp, on T-5 RUN

• Hang Protective Tags per OPG-Protective Equipment.
• Hang Caution Tags on MOV-4000A and B
• Place Black Dot on all required MCB Annunciators D D D D D D D D Bench Mark Scenario Event Description NRC Scenario 3 ACTIVITY Crew Briefing DESCRIPTION
• Assign Crew Positions based on evaluation requirements
• Review the Shift Turnover Information with the crew .
• Conduct Pre-job Brief using marked up copy of 0-6.9.2, Section 6.4 marked up as follows:

o All steps in Sections 6.4.1 are marked NA o All steps in Sections 6.4.3 are marked NA T-0 Begin Familiarization Period At direction of Event1 Shift Electric Plant examiner At direction of Event2 Loss of B Instrument Bus examiner Trigger#1 EDS07B At direction of Event 3 Pressurizer Pressure (PT-449) fails HIGH examiner Trigger#2 PZR02D 2500, No Ramp At direction of Event4 Main Turbine High Vibration/Downpower examiner Trigger#3 NOTE: TUR05E

• Initial Value is 8 mils over 180 second ramp to cause Annunciator 1-27.
• When 1-27 is received, THEN modify TUR05E to 9.6 mils over 480 seconds.
• WHEN crew stops Load Reduction, THEN modify TUR05E to the current value. When Turbine Event 5 Hotwell Level Transmitter fails HIGH Placed in GO Trigger#4 CND03A 48inches At direction of Event 6 Feed Line Rupture Inside Containment/Turbine examiner Trigger #5 fails to Auto Trip FDW09A 2E+7, 180 second Ramp TUR02 entered at T = 0 D D Bench Mark Continued from Event 6 Continued from Event 6 Scenario Event Description NRC Scenario 3 ACTIVITY DESCRIPTION Event 7 Safety Injection fails to actuate Automatically T=O NOTE: These Malfunctions inserted in the IC at Sl502A T=O. 515028 Event 8 A AFW Pump to Auto Start/Trips after Manual StartrrDAFW Pump trips on Overspeed/

Standby AFW fails to function NOTE: These Malfunctions inserted in the IC at T=O. RPS07K T-29 (When pump manually started) (30 seconds delayed) REM FDW32 = 0 T-30 (Conditional on Rx Trip) OVR-FDW42A FALSE (MOV-9629A CLOSED, unable to OPEN) FDW15B (SAFW pump D failure) Terminate the scenario upon direction of Lead Examiner Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# -----Page 8 of _5_8_ Event

Description:

Shift Electric Plant Shortly after taking the watch, the operator w1ill shift the Electric Line-up from 50/50 to 0/100 in accordance with 0-6.9.2, Establishing and/or Transferring Offsite Power to Bus 12A/12B. SIM DRIVER Instructions: NA Indications Available: NA Time' Pos. Expected Actions/Behavior . Comments . . .. 0-6.9.2, ESTABLISHING AND/OR TRANSFERRING OFFSITE POWER TO BUS 12A/BUS 128 NOTE: The CO will contact the RG&E Energy Control Center, and inform them that the Ginna Electric Plant will be realigned. SIM DRIVER: Acknowledge as RG&E ECC. (Step 6.4.2) ESTABLISH Offsite Power to 12B Bus using Circuit 7T as follows: co (1.) MARK BUS 12B ALT FEED FROM NOTE: 52/12BX is CLOSED. 767, 52/12BX, breaker initial position:

• OPEN r
• CLOSED co (2.) VERIFY CLOSED CIRCUIT BKR 7T1352 34 KV BUS. co (3.) TURN ON BUS 12B ALT FEED FROM 7T, 52/12AX SYNCHROSCOPE co (4.) CLOSE BUS 12B ALT FEED FROM NOTE: J-6/L-28 will be 7T, 52/12AX.

expected alarms. NOTE: When the CO closes the 52/12AX the 52/12BX will auto OPEN. co (5.) IF BUS 12B ALT FEED FROM 767, NOTE: 52/12BX was 52/12BX, was initially OPEN, THEN CLOSED. ..... Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# -----Page 9 of 58 ---;1 Event

Description:

Shift Electric Plant *Time* I};., Expected Actions/Behavior /, I* .i. ,' " \, co (6.) IF BUS 12B NORMAL FEED FROM 767, 52/12BX, was initially CLOSED, THEN PERFORM the following: OTHERWISE, MARK this Step N/A.

• VERIFY breaker OPENED (Green light ILLUMINATED, White light ILLUMINATED).
• PLACE BUS 12B NORMAL FEED FROM 767, Ei2/12BX, control switch to TRIP AND THEN to AUTO.
• VERIFY breaker is OPEN AND RESET (Green light ILLUMINATED, White light EXTINGUISHED).

co (7.) IF BUS 12B NORMAL FEED FROM NOTE: 52/12BX is OPEN. 767, 52/12BX, is NOT OPEN, .... co (8.) VERIFY BUS 12B VOLTMETER 4160 V indicates approximately 4000 VOLTS on all 3 phases. co (9.) VERIFY Bus 16 and Bus 17 voltmeter indicates greater than 440 volts on all 3 phases. co (10.) TURN OFF BUS 12:8 ALT FEED FROM 7T, 52/12AX SYNCHROSCOPE AND REMOVE the handle. CRS (Step 6.7) IF required, THEN RESET 12A SIM DRIVER: Use REM and 12B Alarm Panels in Relay Room EDS50 to clear 12B Annex. transformer alarm L-28 NOTE: The CRS will likely conduct a Plant Status Brief. At the discretion of the Lead Examiner move to Event #2. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# _2 _____ Page 1 o of _s_a_, Event

Description:

Loss of 8 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 AR-K-32, CV AIR DRYER LOW PRESS SG B/D 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. SIM DRIVER Instructions: Operate Trigger #1 (EDS07B) Indications Available:

• Multiple MCB Annunciators
• MCB Annunciator E-14, LOSS B INSTR. BUS
• White and Red Bistable Status lights extinguish
• VCT Level (L T-112) fails low causing continuous Auto Makeup
• Tavg-Tref is 12°F (151 Stage Pressure has failed Low), with an Auto Rod Inward green Status light, but NO Auto Rod motion
• Normal Letdown has isolated due to one PZR level channel failinQ low Time Pos.'

'Actions/&h'avio1"':: 1!1 ' ****comments AR-E-14, LOSS B INSTR BUS CRS 1. Restore power to Instrument Bus B (Refer to ER-INST.3, INSTRUMENT BUS POWER RESTORATION) CRS 2. Evaluate plant conditions to determine if additional action is required by referring to the following: 0 ITS LCO 3.8. 7 and 3.8.8 CRs 3. Notify the following: NOTE: The CRS may notify 0 SM theWCC. 0 Electricians SIM DRIVER: as wees, 0 Electrical Planner acknowledge. NOTE: The CRS will go to ER-INST.3. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# _2 _____ Page 11 of 58 ---n Event

Description:

Loss of B Instrument Bus *Time, Pos. '": Actions/Behavio.r Comments* ER-INST.3, INSTRUMENT BUS POWER RESTORATION co (Step 6.1.1) IF Any instrument bus is deenergized THEN PERFORM the following: Verify an alternate power supply is available by checking supply voltage as follows: Maintenance-Supply voltage approximately 120 volts (El/CVTAUX, above Instr Bus D) HCO (Step 6.1.2) Close letdown isolation valve, NOTE: The HCO will isolate AOV-427. Normal Letdown. NOTE: VCT level indication is lost, and with LID isolated, actual level is lowering, and CRS may direct AO to monitor VCT level locally (no ER-INST.3 procedure guidance) If so, SIM DRIVER: as AO, acknowledge, and Use Insight from Scenario Setup, or Monitor VCT level on drawing VCT1 and report value to CRS {When requested or the remainder of the scenario). HCO (Step 6.1.3) Place charging pump controllers NOTE: The HCO will place in MANUAL Charging Pump speed control in Manual OR may secure one of the two Charging Pumps altogether. NOTE: The HCO may place the Auto Makeup to the VCT in Manual to prevent overfilling the VCT. co (Step 6.1.4) Place hotwell level controller to manual, if desired. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# _2 _____ Page 12 of 58 ---ti Event

Description:

Loss of B Instrument Bus Time ***pos. I* *. Expected Actions/Behavior Comments ' . HCO (Step 6.1.5) Place PRZR PRESS CONTROLLER 431 Kin MANUAL, if necessary. HCO (Step 6.1 .6) Place rods in MANUAL. NOTE: The HCO will place Rods in Manual. CRS (Step 6.1. 7) Transfer Instrument Bus to an NOTE: The CRS will direct the available power supply. (Maintenance or bus to be energized from the Normal) Maintenance supply. co 0 IF on NORMAL FEED AND NOTE: Instrument Bus Bis MAINTENANCE FEED desired, THEN now re-energized. TRANSFER to MAINTENANCE co (Step 6.1.8) CHECK Instrument Bus supply NOTE: 0-6.11 requires voltage within ITS limits. (Refer to 0-6.11, voltage between 113-123V SURVEILLANCE REQUIREMENT/ROUTINE OPERATIONS CHECK SHEET) CRS (Step 6.1.9) Go to Step 6.4 HCO (Step 6.4.1) VERIFY one Charging Pump in AUTO, IF desired. HCO (Step 6.4.2) VERIFY PRZR PRESS CONTROLLER 431 Kin AUTO. HCO (St5ep 6.4.3) RESTORE PRZR Heaters as required. HCO (step 6.4.4) IF letdown isolation valve, AOV-427 has been closed, THEN RESTORE Letdown as follows: Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# 2 Page 13 of 58 Event

Description:

Loss of B Instrument Bus Time ' Pos. Actions/Behavior( .* , , (:omrrients ' . ,.,i;. * . HCO (Step 6.4.4.1) COMPLETE removal of NOTE: Removed per Section normal letdown from service per S-3.2E, 6.2 of S-3.2E PLACING IN OR REMOVING FROM SERVICE NORMAL LETDOWN/EXCESS LETDOWN NOTE: The CRS will hand this off to the HCO or the CO, and continue on in ER-INST.3. S-3.2E, PLACING IN OR REMOVING FROM SERVICE NORMAL LETDOWN/EXCESS LETDOWN HCO/ (Step 6.2.1) PLACE Charging Pumps in co MANUAL HCO/ (Step 6.2.2) ENSURE CLOSED Letdown co Orifice isolation valves. AOV-200A AOV-2008 AOV-202 HCO/ (Step 6.2.3) CLOSE LTDN ISOLATION VLV co RHR to NRHX, AOV-427. HCO/ (Step 6.2.4) REDUCE charging flow while co throttling closed charging flow to Regenerative Heat Exchanger HCV-142 to maintain greater than 20" RCP labyrinth seal HCO/ (Step 6.2.5) CLOSE LETDOWN ISOL VLV co RHR TO NRHX AOV-371. HCO/ (Step 6.2.6) PLACE NRHX L TON OUTLET co TEMP (Tl-130) TCV-130 in MANUAL/ CLOSED. NOTE: The CRS will continue with ER-INST.3. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# _2 _____ Page 14 of _5_8_-11 Event

Description:

Loss of B Instrument Bus Time PQs .. .*. . . . Cornmenfs

• • • • • Ex:pected
• . . ER-INST.3, INSTRUMENT BUS POWER RESTORATION CRS (Step 6.4.3.2)

RESTORE normal letdown per NOTE: Restored per Section S-3.2E, PLACING IN OR REMOVING FROM 6.3 and 6.4 of S-3.2E SERVICE NORMAL LETDOWN/EXCESS LETDOWN. NOTE: The CRS will hand this off to the HCO or the CO, and continue on in ER-INST.3. S-3.2E, PLACING IN OR REMOVING FROM SERVICE NORMAL LETDOWN/EXCESS LETDOWN HCO/ (Step 6.3.1) 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 fi.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. HCO/ (Step 6.4.1) Restore Letdown Without a co Flush. HCO/ (Step 6.4.1.1) ENSURE letdown is secured co PER Section 6.2 prior to restoring. HCO/ (Step 6.4.1.2) IF charging flowpath to Loop B co COLD Leg is desired (preferred method}, THEN PERFORM the following: ENSURE CLOSED CHARGING VLV RHX TO LOOP B HOT, AOV-392A. OPEN CHARGING VLV RHX TO LOOP B COLD LEG AOV-294. HCO/ (Step 6.4.1.3) IF Charging flowpath to Loop NOTE: Charging alignment to co B HOT leg is desired, ..... the Hot Leg will NOT be desired. HCO/ (Step 6.4.2) START a second Charging co Pump at minimum speed. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# 2 Page 15 of 58 Event

Description:

Loss of B Instrument Bus Time, Pos. , , ', Expected Actions/Behavior, HCO/ (Step 6.4.3) SLOWLY OPEN charging flow to CO Regenerative Heat Exchanger HCV-142 to reduce labyrinth seal .1P to -40". HCO/ (Step 6.4.4) ADJUST Charging Pump speed CO while maintaining -40" labyrinth seal .1P UNTIL HCV-142 is fully OPEN. HCO/ (Step 6.4.5) EST A8LISH greater than or CO equal to 22 gpm charging line flow. HCO/ (Step 6.4.6) IF placing 40 GPM orifice in CO service THEN PERFORM the following PLACE LOW PRESS L TDN PRESS PCV-135 in MANUAL at -40% open. PLACE NRHX L TDN OUTLET TEMP (Tl-130) TCV-130 in MANUAL at-40% open. HCO/ (Step 6.4. 7) IF placing 60 GPM orifice in CO service THEN .... HCO/ co (Step 6.4.8) OPEN LETDOWN ISOL VLV RHR TO NRHX AOV-371. HCO/ (Step 6.4.9) PLACE L TDN LOOP 8 COLD CO LEG TO RHX AOV-427 to OPEl\J and THEN to AUTO. HCO/ (Step 6.4.10) OPEN desired Letdown orifice CO valve AOV-200A, AOV-2008, or AOV-202 AND MARK AOV's not opened N/A. AOV-200A AOV-2008 AOV-200 Jr' , Comments NOTE: A 40 gpm Orifice was previously in service. , , Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# _2 _____ Page 16 of _5_8_1 Event

Description:

Loss of B Instrument Bus Time. Pos. ' Expected Actions/Behavior .Comments

/' HCO/ (Step 6.4.11) ADJUST LOW PRESS L TON co PRESS PCV-135 to achieve Letdown pressure of-250 psig on Pl-135. HCO/ (Step 6.4.12) PLACE LOW PRESS L TON co PRESS, PCV-135 IN AUTO. HCO/ (Step 6.4.13) PLACE NRHX L TDN OUTLET Examiner NOTE: At the co TEMP (Tl-130)

TCV-130 in AUTO at the discretion of the Lead setpoint recorded in Step 5.4. Examiner move to Event #3. HCO/ (Step 6.4.14) PLACE Pressurizer level co control (Charging Pump) to AUTO. NOTE: The CRS will continue with ER-INST.3, Step 6.4.5. ER-INST.3, INSTRUMENT BUS POWER RESTORATION co (Step 6.4.5) RESTORE EH control to AUTO/IMP IN, If desired. HCO (Step 6.4.6) RESTORE ROD CONTROL NOTE: The HCO will place the BANK SELECTOR Switch to AUTO, if Rods back in Auto. desired. HCO (Step 6.4.7) VERIFY CNMT ventilation isolation is reset. HCO (Step 6.4.8) VERIFY Hotwell level controller in AUTO, if desired. co (Step 6.4.9) RESTORE desired SW pump alignment. co (Step 6.4.10) ENSURE motor fire pump breaker closed. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# _2 _____ Page 17 of 58 Event

Description:

Loss of B Instrument Bus Time Pos. '*'.' Expected Actions/Behavfor , '

• I I Comments.

c* CO/AO (Step 6.4.11) DISPATCH an AO to verify NOTE: The CRS may dispatch proper operation of Battery Chargers if an AO. necessary.

If so, SIM DRIVER: as AO, acknowledge. HCO/ (Step 6.4.12) EVALUATE MCB Annunciator NOTE: Annunciator K-32 co status (refer to AR procedures) needs follow-up. AR-K-32, SG SLOWDOWN TANK HIGH LEVEL co 1. Direct AO to remove and then SIM DRIVER: Insert REM restore Slowdown per T-14.F.1, SG SGN05, RESET, Slowdown System Operation ER-INST.3, INSTRUMENT BUS POWER RESTORATION CRS (Step 6.4.13) IF Instrument Bus D was NOTE: Instrument Bus D was affected, THEN ....... NOT affected. CRS (Step 6.4.14) IF Instrument Bus A or C is NOTE: Instrument Bus A or C being powered from associated emergency is NOT being powered form AC Bus, then ...... the emergency AC Bus. CRS (Step 6.4.15) RETURN to procedure or guidance in effect. NOTE: The CRS will likely conduct a Plant Status Brief. NOTE: The CRS will address the Technical Specifications. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# _2 ____ Page 18 of 58 ---11 Event

Description:

Loss of B Instrument Bus Time Pos .. ' Expected Actions/Behavior Comme.nts TECHNICAL SPECIFICATION 3.8.7, AC INSTRUMENT BUS SOURCES-MODES 1, 2, 3 AND 4 CRS LCO 3.8.7 The following AC instrument bus power sources shall be OPERABLE: a) Inverters for Instrument Buses A and C; and b) Class 1 E constant voltage transformer (CVT) for Instrument Bus B. CRS APPLICABILITY: MODES 1, 2,. 3, AND 4. CONDITION REQUIRED COMPLETION NOTE: The CRS will take ACTION TIME ACTIONS B.1 and B.2. B. Class 1E B.1 Power AC 2 hours CVTfor AC Instrument Bus Instrument B from its non-Bus B Class 1 E CVT. inoperable AND B.2 Restore 7 Days Class 1E CVTfor AC Instrument Bus B to OPERABLE status. TECHNICAL SPECIFICATION 3.8.9, DISTRIBUTION SYSTEMS-MODES 1, 2, 3 AND4 CRS LCO 3.8.9 Train A and Train B of the following electrical power distriibution subsystems shall be OPERABLE: a) AC power; b) AC instrument bus power; and c) DC power CRS APPLICABILITY: modes 1, 2, 3 and 4. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# 2 Page 19 of 58 Event

Description:

Loss of B Instrument Bus Time Pos. 1 Expected . ;:,* : .. Comments***: ... CONDITION REQUIRED COMPLETION NOTE: The CRS will note that ACTION TIME while Instrument Bus B was B. One AC B.1 Restore AC 2 hours. OOS, they were in B.1, but Instrument Instrument came out of this action when bus electrical bus power to the Bus was power electrical distribution power restored. train distribution inoperable. train to OPERABLE status. At the discretion of the Lead Examiner move to Event #3. Appendix D Operator Action Form ES-D-2 3 Event# 3 Op Test No.: N2014-301 Scenario# Page 20 of 58 Event

Description:

Pressurizer Pressure (PT-449) fails HIGH After this, the controlling Pressurizer Pressure Transmitter will fail HIGH, causing the Spray Valves to open. The operator will respond in accordance with AR-F-2, PRESSURIZER HIGH PRESS 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 TRM-3.4.3, Anticipated Transient Without Scram (ATWS) Mitigation. SIM DRIVER Instructions: Operate Trigger #2 (PZR02D (2500)) Indications Available:

• MCB Annunciator F-2, PRESSURIZER HIGH PRESS 2310
• Pl-449 reading 2250 psig, all others lowering slowly
• Both Presssurizer Spray Valves fully OPEN
• Master pressure Controller 431 K output at 100%
• PPCS Alarm PZR AVG PRESS HI ALARM
• MCB Annunciator F-10, PRESSURIZER LO PRESS 2205 (15 seconds delayed)

' *. *. -'!'*.* . " .*.' *+ * ... Time Pos *.. , . -'*, .. EC* .. "" NOTE: The HCO may take action to place 431 Kin MANUAL control, or the Spray Valve Controllers in MANUAL control, before arriving at the procedurally directed step, per the Guidance of A-503.1. NOTE: The crew may enter AP-PRZR.1 directly. AR-F-2, PRESSURIZER HI PRESS 2310 PSI CRS (Step 1) IF RCS pressure is high, THEN go NOTE: Pressurizer Pressure is to AP-PRZR.1 . NOT high. CRS (Step 2) IF due to instrument

failure, THEN NOTE: While an instrument refer to ER-INST.1, REACTOR has failed, the failure has PROTECTION BISTABLE DEFEAT AFTER created a pressure transient, INSTRUMENTATION LOOP FAILURE and AP-PRZR.1 is the appropriate procedure.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# Page 21 of 58 -----------

---

ti 3 Event

Description:

Pressurizer Pressure (PT-449) fails HIGH Time. Pos. *.***.Expected Actions/Behavior , ... **comments . . . AR-F-10, PRESSURIZER LO PRESS 2205 PSI NOTE: This alarm will occur if the Spray Valves are open :::::15 seconds. HCO (Step 1) Perform a channel checl<. CRS (Step 2) Go to the applicable procedure:

• AP-TURB.2, if turbine load rejection has occurred.
• AP-PRZR.1

, if pressure is abnormal for plant condition.

• ER-INST.1, if channel failed CRS (Step 3) Refer to ITS LCO 3.4.1 NOTE: The CRS will go to AP-PRZR.1. AP-PRZR.1, ABNORMAL PRESSURIZER PRESSURE HCO (Step 1) Check PRZR Pressure:
• All 4 narrow range channels-APPROXIMATELY EQUAL HCO/ (Step 1 RNO) IF one pressure channel NOTE: The CRS may refer to CRS 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 b) Refer to ER-INST.1. REACTOR PROTECTION BISTABLE DEFEAT AFTER INSTRUMENTATION LOOP FAILURE. HCO (Step 2) Check Reactor Power-ST ABLE Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# _3 _____ Page 22 of _5_8_-41 Event

Description:

Pressurizer Pressure (PT-449) fails HIGH Time <' Expected Actions/Behavior, , Comments .. .. HCO (Step 3) Check PRZR Pressure: a) Pressure-LESS THAN 2235 PSIG b) Pressure-GREATER THAN 2000 PSIG HCO (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 Kin 0 AOV-431A MANUAL control, or the Spray AOV-4318 Valve Controllers in MANUAL 0 control, before arriving at THIS step, per the Guidance of A-503.1. HCO (Step 5 RNO) Place Controllers in MANUAL at 0% Demand. HCO (Step 6) Check PRZR Pressure Controller, 431 K, Demand-LESS THAN 50% HCO (Step 7) Check PRZR PORVs: a) PORVs-CLOSED b) Annunciator F-19. PRZR PORV OUTLET HI TEMP '145°F-EXTINGUISHED CRS c) Go to Step 9 Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# 3 Page 23 of 58 Event

Description:

Pressurizer Pressure (PT-449) fails HIGH Time Pos. 1* . . . Actions/Behavior

• Comments<*.

.. HCO (Step 9) Check PRZR Safety Valves: 0 Position indicator-LESS THAN 0.1 INCH 0 Annunciator F-18. PRZR SAFETY VLV OUTLET HI TEMP 145°F-EXTINGUISHED 0 Annunciator AA-13, PRESSURIZER SAFETY VALVE POSITION-EXTINGUISHED. HCO (Step 10) Check AUX Spray Valve, AOV-296 -CLOSED HCO (Step 11) Check PRZR Pressure Control Restored: a) Pressure-TRENDING TO 2235 PSIG CRS b) Go to Step 16 HCO (Step 16) Check PRT Indications: a) Level-BETWEEN *>1 % and 84% b) Pressure-APPROXIMATELY 1.5 PSIG AND ST ABLE c) Temperature-AT CNMT AMBIENT TEMPERATURE AND STABLE HCO (Step 17) Establish PRZR Pressure Control In Auto: a) Verify 431 K in AUTO Appendix D Operator Action Form ES-0-2 Op Test No.: N2014-301 Scenario# 3 Event# 3 Page 24 of 58 -----------

---

11 Event

Description:

Pressurizer Pressure (PT-449) fails HIGH Time Pos. Expected Actions/Behavior 0 ** Comments.: HCO (Step 17 RNO) Place 431 Kin AUTO, if NOTE: 431 K 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 procedure here. ER-INST.1, REACTOR PROTECTION BISTABLE DEFEAT AFTER INSTRUMENTATION LOOP FAILURE HCO (Step 6.1.1) IDENTIFY the failed instrument channel by observation of the bistable status light board, MCB annunciators, and the MCB metering indication. CRS (Step 6.1.2) WHEN a failed instrument loop NOTE: The CRS will refer to and/or channel has been identified, THEN PRZR Pressure Channel refer to the appropriate section of this Failures, Section 6.3. procedure listed below: HCO (Step 6.3.1) IF the controlling PRZR Pressure channel has failed (normally PT-449, but PT-429 may be selected as controlling channel), THEN PLACE HC-431 K in MANUAL at about 50% and control pressure manually HCO (Step 6.3.2) IF PT-430 OR PT-431 has NOTE: Neither PT-430 nor failed, THEN ........ PT-431 has failed. HCO (Step 6.3.3) IF hot leg streaming has been NOTE: hot leg streaming has causing single channel L'l T runback signals, NOT been causing runback THEN ...... signals. HCO (Step 6.3.4) REFER TO the appropriate NOTE: The CRS will go to the attachment to defeat the associated control PRZR PRESSURE Pl-449 functions: YELLOW CHANNEL Attachment

8.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# _3 _____ Page 25 of _5_8_1 Event

Description:

Pressurizer Pressure (PT-449) fails HIGH Time Pos *.. . ..* Expected Actions/Behavior

• . ** ... Coitllllents NOTE: The CRS will hand this off to the CO. ER-INST.1, REACTOR PROTECTION BISTABLE DEFEAT AFTER INSTRUMENTATION LOOP FAILURE ATTACHMENT 8 YELLOW CHANNEL-PRZR PRESSURE Pl-449 NOTE: The CO will likely conduct Instrument Defeat Brief. HCO (Step 1) IF PRZR Pressure channel failure NOTE: The failure did NOT resulted in a run back, THEN ....... result in a runback.

co (Step 2) In the PLP PRZR PRESS AND NOTE: The CO will unlock and LEVEL rack, VERIFY the PRZR pressure open the PLP PRZR PRESS DEFEAT switch P/429A position. AND LEVEL Rack Cabinet, 0 IF P/429A is in NORMAL, THEN take the required action, and place P/429A to DEFEAT-*1. then close and lock the cabinet door. co (Step 3) In the RIL INSERTION LIMIT rack, NOTE: The CO will unlock and PLACE T/405F DELTA T DEFEAT switch to open the RIL Insertion Limit Loop B UNIT 2. Rack Cabinet, take the required action, and then close and lock the cabinet door. co (Step 4) DETERMINE the expected Bistable proving light status for the post defeat condition as follows: RECORD the following Data:

• PRZR Pressure Pl-449 PSIG
• LOOP 1 B-2 TEMP Tl-408B OF
• T SP1 LOOP 1 B-2TEMP Tl-408A OF DETERMINE the expected post defeat Bistable proving light status and circle the expected status in table below: 408 LOOP B-2 NOTE: The CO will determine
• OVERTEMP TRIP Light OFF IF Tl-408B that the Proving Light should ;::: Tl-408A be ON in the Post-Defeat condition.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# _3 _____ Page 26 of _5.;.;8;....__ 11 Event

Description:

Pressurizer Pressure (PT-449) fails HIGH Time

• 1*. Pos.*

..... *,: .. *comments 449 CHANNEL 4 NOTE: The CO will determine

• LOW PRESS TRIP Light OFF IF Pl-449:::.;

that the Proving Light should 1873 psig be ON in the Post-Defeat condition. co (Step 5) In the (YELLOW) Y-1 NOTE: The CO will unlock and PROTECTION CHANNEL 4 rack, PLACE open the Y-1 PROTECTION the following bistable proving switches to CHANNEL 4 Rack Cabinet, DEFEAT (UP) AND verify the proving light take the required action, and status is correct: then close and lock the cabinet 408 LOOP B-2 door. OVER TEMP TRIP 449 CHANNEL 4 NOTE: Both B/S proving lights LOW PRESS TRIP should be ON after defeat. HCO (Step 6) PLACE the PRZR pressure recorder transfer switch (MCB) to position 1 *-3 HCO (Step 7) VERIFY the bistable status lights Examiner NOTE: At the AND Annunciators listed above am lit. discretion of the Lead Examiner move to Event #4. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# 3 Page 27 of 58 Event

Description:

Pressurizer Pressure (PT-449) fails HIGH *, ' *' Time , Pos. Expected. Act.ions/Behavior . . Comments . HCO/ (Step 8) DELETE 404/408 from processing co by performing the following on the PPCS:

• SELECT "Group Update" display
• SELECT "List Server Groups"
• SELECT 404_ 408 from the pick list
• TURN "OFF" scan processing, THEN click the "Set Scan Processing" button
• ANSWER prompts
• SELECT the "Sub/Delete/Restore" display
• SELECT Point ID T0404
• TURN "ON" scan processing
• SELECT "Change"
• ANSWER prompts
• SELECT the "Sub/Delete/Restore" display
• SELECT Point ID P0449
• TURN "OFF" scan processing
• SELECT "Change"
• ANSWER prompts CRS (Step 9) GO TO step 6.3.5 NOTE: The CRS will return to the body of the procedure.

HCO (Step 6.3.5) RESTORE the following NOTE: The HCO will return systems to automatic operation as 431 K to Auto. necessary: 0 PRZR Pressure control

• HC 431K
• PRZR Spray Valves
• PRZR Heaters HCO 0 PRZR Level Control HCO 0 Rod Control co 0 Steam Dump co 0 Turbine EH control Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

3 Event# _3 _____ Page 28 of _5_8_-11 Event

Description:

Pressurizer Pressure (PT-449) fails HIGH Time Pos. .. , .... Expected Actions/Behavior Comments* .. . HCO (Step 6.3.6) Open associated block valve NOTE: No Block Valve was closed in step 4.4.3 Closed. CRS (Step 6.3.7) REFER TO the following ITS NOTE: The CRS will evaluate Sections for LCO's: Technical Specifications. Section 3.3.1, Table 3.3.1-1, Functions 5, 7a, and 7b (7b not required for PT-449) Section 3.3.2, Table 3.3.2-1, Function 1 d (not required for PT-449) Section 3.3.3, Table 3.3.3-1, Functions 1 and 6 CRS (Step 6.3.8) REFER TO TRM 3.4.3, NOTE: The CRS will evaluate Anticipated Transients Without Scram Technical Requirements (ATWS) mitigation Manual. CRS (Step 6.3.9) IF turbine runback has occurred NOTE: The failure did NOT AND rods are in MANUAL, ...... result in a runback. HCO (Step 6.3.10) RESTORE AUTO Rod Control, NOTE: The HCO will place the if desired. Rods in Auto. CRS (Step 6.3.11) GO TO step 6.15 HCO (Step 6.15.1) IF necessary, VE HI FY an operable channel is selected for the affected recorder. HCO (Step 6.15.2) Verify the systems in AUTO if desired: 0 Rod Control co 0 Turbine EH control HCO 0 PRZR Pressure control

• HC 431K
• PRZR spray valves
• PRZR heaters HCO 0 PRZR level control Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

3 Event# 3 Page 29 of 58 Event

Description:

Pressurizer Pressure (PT-449) fails HIGH Time Pos. .Expected ActionsfBehavior Comments co 0 Steam Dump (unless 151 pressure failed) co 0 MFW control co 0 SIG Atmos Relief Viv Control CRS (Step 6.15.3) NOTIFY the following people: NOTE: The CRS may notify 0 Operations Supervision the SM/ST A/WWM. 0 STA SIM DRIVER: as 0 Work Week Manager SM/STA/WWM, acknowledge. CRS (Step 6.15.4) REFER to the following for NOTE: The CRS may ask the Notification Requirements: SM. SIM DRIVER: as SM, acknowledge. CNG-NL-1.01-1004, REGULATORY REPORTING OPG-NOTIFICATION, REQUIRED NOTIFICATIONS TO THE PSC/PIO/CEG SENIOR MANAGEMENT/OPERATIONS MANAGEMENT AP-PRZR.1, ABNORMAL PRESSURIZER PRESSURE HCO (Step 17.b) Verify PRZR Spray Valves in Auto. HCO (Step .c) Verify PRZR Heaters restored:

• PRZR proportional heaters breaker -Closed
• PRZR backup heaters RESET in AUTO CRS (Step 18) Evaluate MCB Annunciator Status (Refer to AR Procedures)

CRS (Step 19) Notify Higher Supervision Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# _3 ____ Page 30 of 58 ---11 Event

Description:

Pressurizer Pressure {PT-449) fails HIGH Expected Actions/Behavior . 'Comments Time Pos .. * ' ', ',' CRS (Step 20) Notify Reactor Engineer for Transient Monitoring Program NOTE: The CRS will address the Technical Specifications. TECHNICAL SPECIFICATION 3.4.1, RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING (DNB) LIMITS CRS (LCO 3.4.1) RCS DNB Parameters for NOTE: The CRS will pressurizer

pressure, RCS average determine that the crew be in temperature, and RCS total flow rate shall be and then out of this Technical within the limits specified in the COLR Specification during the course of this event. APPLICABILITY:

Mode 1. ACTIONS: CONDITION REQUIRED COMPLETION ACTION TIME A. One or more A.1 Restore 2 hours RCS DNB RCS DNB parameters not parameter(s) to within limits. within limit. TECHNICAL SPECIFICATION 3.3.1, REACTOR TRIP (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 3.3.1-1 (Functions 5, ?a) ACTIONS Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# 31 of 58 Event

Description:

Pressurizer Pressure {PT-449) fails HIGH . . . ', ,, Pos. Time Expected Actions/Behavior f' '""Cc:>.mments \ "' CONDITION REQUIRED COMPLETION NOTE: Functions 5 and 7a are ACTION TIME affected. A. One or more A.1 Enter the Immediately functions with Condition one channel referenced in inoperable. Table 3.3.1-1 for the channel(s). D. As required D.1 6 hours by Required Place channel in Action A.1 and trip referenced by Table 3.3.1-1 K. As required K.1 6 hours by Required Place channel in Action A.1 and trip referenced by Table 3.3.1-1 TECHNICAL REQUIREMENT 3.4.3, ANTICIPATED TRANSIENTS WITHOUT SCRAM (ATWS) MITIGATION CRS TR 3.4.3 ATWS Mitigation shall be OPERABLE as follows:

• Each PORV shall be capable of automatic actuation and each block valve shall be open;
• Manual rod insertion shall be OPERABLE; and
• ATWS Mitigation System Actuation Circuitry (AMSAC) shall be OPERABLE.

APPLICABILITY MODE 1 > 45% RTP. CONDITION REQUIRED COMPLETION ACTION TIME A. One or more A.1 Declare Immediately PORV ATWS automatic mitigating flow path capability inoperable. inoperable. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# _3 _______ Page 32 of 58 Event

Description:

Pressurizer Pressure (PT .. 449) fails HIGH At the discretion of the Lead Examiner move to Events #4-5. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# _4_&_5 ___ Page of Event

Description:

Main Turbine High Vibration/Downpower w/Hotwell Level Transmitter fails HIGH Following this, a turbine high vibration condition on Bearing #5 will develop within about 3 minutes. The operator will respond in accordance with AR-1-27, 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 to stabilize the vibrations. During the load reduction Hotwell Level Transmitter will fail HIGH. The operator will need to manually control the Hotwell Level Controller. SIM DRIVER Instructions: Operate Trigger #3

• Initial Value is 8 mils over 180 second ramp to cause Annunciator 1-27.
• When 1-27 is received, THEN modify TUR05E to 9.6 over 480 seconds.
• WHEN crew stops Load Reduction, THEN modify TUR05E to the current value. Indications Available:
• MCB Annunciator 1-27, ROTOR ECCENTRICITY OR VIBRATION
• MCB Turbine Bearing Recorder Bearing 5 indicating high, bearings 4 and 6 rising at a lower rate.
• Back of MCB Turbine Bearing Vibration Panell Bearing 5 indicating high, bearings 4 and 6 rising at a lower rate.
• Hotwell level controller output rising to greater than 60% ( 120 seconds delayed from Turbine in GO) Time
• Expected*

A9tions/Behavior. \ *comments . NOTE: The crew may enter AP-TURB.3 directly. AR-1-27, ROTOR ECCENTRICITY OR VIBRATION CO/ (Step 4.1) CHECK vibration levels on the CRS following: TURBINE VIBRATION, RK-14 (MCB front) Turbine Vibration Monitor (MCB rear) co (Step 4.2) IF high vibration on Bearings 1 -8, THEN GO TO AP-TURB.3. NOTE: The CRS will go to AP-TURB.3. AP-TURB.3, TURBINE VIBRATION Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# _4_&_5 ___ Page of _5.;.;8;...... ... 11 Event

Description:

Time .. Pos. I* co co co HCO co Main Turbine High Vibration/Down power w/Hotwell Level Transmitter fails HIGH .. */ Expected .. Cdmmerits

• . 0/ .. (Step 1) Verify Turbine Vibration-ALL BEARINGS LESS THAN 14 MILS (Step 2) Check Turbine Bearings l\lo.1 NOTE: The highest vibration through No. 8 Vibration-LESS THAN 7 MILS will be on Bearing #5 at 8-9 Mils. (Step 2 RNO) Attempt to stabilize vibration as follows:

IF generator on line, THEN begin reducing load to stabilize vibrations. (Refer to AP-TURB.5, RAPID LOAD REDUCTION NOTE: The CRS will go to AP-TURB.5 and conduct Rapid Load Reduction Brief prior to commencing load reduction. AP-TURB.5, RAPID LOAD REDUCTION (Step 1) Initiate Load Reduction a) Verify rods in AUTO b) Reduce turbine load in Auto as follows:

• Place Turbine EH Control in NOTE: IMP PRESS IN is OPER PAN., IMP PRESS IN, if desired.

desired.

• Select desired rate on NOTE: The operator will thumbwheel select 1 %/Min.
• Reduce the setter to the desired load
• Depress the GO button SIM DRIVER Instructions:

Operate Trigger #4 (CND03A (48 Inches)) HCO c) Initiate boration at the rate NOTE: The HCO will initiate determined in OPG-REACTIVITY-a boration. CALC Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# _4_&_5 ___ Page _5_8_ .... , Event

Description:

Time Pos. HCO HCO HCO HCO co HCO co HCO/ co Main Turbine High Vibration/Down power w/Hotwell Level Transmitter fails HIGH 'Expected Actions/Behavior

• . .. ."Comments.

d) Place PRZR backup heaters switch to ON (*Step 2) Monitor RCS Tavg NOTE: This is a Continuous

• Tavg-GREATER THAN 545°F Action. The CRS will make both board operators aware.
• Tavg-LESS THAN 579°F (Step 3) Adjust Boric Acid Addition Rate As Necessary To (refer to OPG-REACTIVITY-CALC):
• Maintain rods above the insertion limit
• Match Tavg and Tref
• Compensate for Xenon (*Step 4) Monitor PRZR Pressure-NOTE: This is a Continuous TRENDING TO 2235 PSIG IN AUTO Action. The CRS will make both board operators aware. (*Step 5) Monitor MFW Regulating Valves-NOTE: This is a Continuous RESTORING S/G LEVEL TO 52% IN AUTO Action. The CRS will make both board operators aware. (*Step 6) Monitor PRZR Level-TRENDING NOTE: This is a Continuous TO PROGRAM IN AUTO CONTROL Action. The CRS will make both board operators aware. (Step 7) Check IA Available To CNMT IA pressure

-GREATER THAN 60 PSIG Instr Air to CNMT lsol Valve, AOV-5392 -OPEN (Step 8) Check Steam Dump Status: Annunciator G-15, STEAM DUMP ARMED -LIT Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# _4_&_5 ____ Page of _5_8 __ 11 Event

Description:

Time .. p < o.s. co co CRS/ co Main Turbine High Vibration/Down power w/Hotwell Level Transmitter fails HIGH .. , *. Expected Actions/Behavior .. ' Comments, Steam dump operating properly in AUTO (Step 9) Check Hotwell Level: NOTE: The CO will recognize that the Hotwell Controller Output is greater than 60%. Hotwell level controller in AUTO Controller demand LESS THAN 60'Vo Hotwell level at setpoint (Step 9 RNO) IF controller demand NOTE: The CO will place approaching 70% (Large Reject Valve the Hotwell Controller in Opens), THEN place controller in Manual MANUAL. and control level. (Step 10) Check If Condensate Booster Pumps Should Be Secured Condensate booster pumps -2 PUMPS NOTE: There are NO RUNNING Condensate Booster Pumps running. At the discretion of the Lead Examiner move to Events #6-8. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# _6 ..... _7 ..... & ..... s ___ Page _s .... s_-11 Event

Description:

Feed Line Rupture Inside Containment/Turbine fails to Auto Trip ment/Safety Injection fails to actuate Automatically/A AFW Pump to Auto Start/Trips after Manual Start/TDAFW Pump trips on Overspeed/Standby AFW fails to function Subsequently, a feed line rupture inside Containment will occur. The Reactor will trip however, the Turbine will fail to trip automatically and Safety Injection will fail to actuate automatically. The operator will enter E-0, Reactor Trip or Safety Injection. 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-0 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-0, 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.

SIM DRIVER Instructions: Operate Trigger #5 (FDW09A, 2E+7over180 seconds) Indications Available:

• Containment NR Pressure starts to rise.
• Feedflow A SG starts to rise.
• A SG NR Level starts to lower. Time Pos. **Expected

< .* .. ; . * . ....... *. . . >Comments <;,,,,,,,, L ; ' , ' ,, ' E-0, REACTOR TRIP OR SAFETY INJECTION HCO (Step 1) Verify Reactor Trip: Immediate Action

• 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 -Immediate Action CLOSED co (Step 3) Verify Both Trains of AC Emergency Immediate Action Busses Energized to at Least 440 VOL TS:

• Bus 14 and Bus 18 Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

3 Event# _6_.,_7_&_8 ___ Page of _5_8_-11 Event

Description:

Time Pos. ' HCO

• Feed Line Rupture Inside Containment/Turbine fails to Auto Trip ment/Safety Injection fails 1to actuate Automatically/A AFW Pump to Auto Start/Trips after Manual Start/TDAFW Pump trips on Overspeed/Standby AFW fails to function Expected'Actions/Behavi()r

' r Comments ,, Bus 16 and Bus 17 (*Step 4) Check if SI is Actuated: Immediate Action

• Any SI Annunciator

-LIT NOTE: D-28, CNMT Press

• SI sequencing

-BOTH TRAINS STARTED. CRITICAL TASK 1. Manually actuate Safety Injection before transition out of E-0 into ES-0.1 Safety Significance: Failure to actuate Safety Injection when it is required to be actuated, and can be actuated, violates the assumptions of the Safety Analysis and constitutes incorrect performance that could lead to misdiagnosis of the event, implementation of an incorrect mitigation strategy and ultimately degradation of the RCS and/or fuel cladding fission product barriers. HCO/ Foldout Page NOTE: The crew will co monitor these conditions throughout the performance of E-0. RCP TRIP CRITERIA LOSS OF SW CRITERIA AFW SUPPLY SWITCHOVER CRITERION SFP COOLING CRITERIA NOTE: The CRS may dispatch an AO to address the status of the SFPCS. If so, SIM DRIVER acknowledge as AO, and report in 5 Minutes that the SFPCS is operating normally. HCO (*Step 5) Verify CNMT Spray Not Roquired:

• Annunciator A-27, CNMT SPRAY -EXTINGUISHED Appendix D Operator Action Form ES-D-2 Op Test No.: N2D14-301 Scenario#

3 Event# _6 ..... _7_&_8___ Page ::____ of _5_8_ ... 1 Event

Description:

Time* Pos. HCO CRS Feed Line Rupture Inside Containment/Turbine fails to Auto Trip ment/Safety Injection fails to actuate Automatically/A AFW Pump to Auto Start/Trips after Manual Start/TDAFW Pump trips on Overspeed/Standby AFW fails to function .. Expected Actions/Behavior Comments

• CNMT pressure-LESS THAN 28 NOTE: Containment PSIG Pressure will be rising, and will exceed 28 psig. This is a Continuous Action Step, and will need to be verified when the conditions are met (i.e. by performing Step 5 RNO). (Step 5 RNO) Verify CNMT spray initiated.

(Step 6) Direct Operator to Perform 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-0. Examiner following operator performing ATT-27.0 continue below. Examiner following operator NOT performing ATT-27.0 continue at Page 42. E-0, REACTOR TRIP OR SAFETY INJECTION, ATTACHMENT 27.0, ATTACHMENT AUTOMATIC ACTION VERIFICATION HCO/ (Step 1) Verify SI and RHR Pumps Running: co

• All SI pumps -RUNNING
• Both RHR pumps-RUNNING HCO/ (Step 2) Verify CNMT RECIRC Fans co Running:
• All fans -RUNNING Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

3 Event# _6 ..... _7_&_8 ___ Page Event

Description:

• rime i>os. HCOI co HCOI co HCOI co HCOI co Feed Line Rupture Inside Containment/Turbine fails to Auto Trip ment/Safety Injection fails to actuate Automatically/A AFW Pump to Auto Start/Trips after Manual Start/TDAFW Pump trips on Overspeed/Standby AFW fails to function 'Expected Actions/Behavior Comments.*
• Charcoal filter dampers green status lights -EXTINGUISHED (Step 3) Check If Main Steamlines Should Be Isolated:
• Any MSIV -OPEN
• Check CNMT pressure-LESS THAN 18 PSIG
• Ensure BOTH MSIVs closed and go to Step 4. (Step 4) Verify MFW Isolation:
• MFW pumps -TRIPPED
• MFW Isolation valves -CLOSED
• SIG A, AOV-3995
• SIG B, AOV-3994
• SIG Blowdown and sample valves -CLOSED (Step 5) Verify At Least Two SW Pumps -RUNNING (Step 6) Verify Cl and CVI:
• Cl and CVI annunciators

-LIT

• Annunciator A-26, CNMT ISOLATION
• Annunciator A-25, CNMT VENTILATION ISOLATION
• Verify Cl and CVI valve status lights -BRIGHT Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

3 Event# _6_.,_7_&_8___ Page !:____ of Event

Description:

Time Pos. : HCO/ co HCO/ co HCO/ co Feed Line Rupture Inside Containment/Turbine fails to Auto Trip ment/Safety Injection fails to actuate Automatically/A AFW Pump to Auto Start/Trips after Manual Start/TDAFW Pump trips on Overspeed/Standby AFW fails to function Expected Actions/Behavior. Comments.*

• CNMT RECIRC fan coolers SW outlet valve status lights -BRIGHT
• FCV-4561
• FCV-4562
• Letdown orifice valves -CLOSED
• AOV-200A
• AOV-2008
• AOV-202 (Step 7) Check CCW System Status:
• Verify CCW pump-AT LEAST ONE RUNNING (Step 8) Verify SI and RHR Pump Flow:
• 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 psig ....... 150 psig. (Step 9) Verify SI Pump and RHR Pump Emergency Alignment:

• RHR pump discharge to Rx vessel deluge -OPEN
• MOV-852A
• MOV-8528
• 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.: N2014-301 Scenario#

3 Event# _6 ..... _7_&_8 ___ Page _5_8_-11 Event

Description:

Time HCO/ co HCO/ co HCO/ co Feed Line Rupture Inside Containment/Turbine fails to Auto Trip ment/Safety Injection fails to actuate Automatically/A AFW Pump to Auto Start/Trips after Manual Start/TDAFW Pump trips on Overspeed/Standby AFW fails to function .:: ** ... Expected Actions/Behay!or. . *. Comments

• Verify SI pump C discharge valves -OPEN
• MOV-871A
• MOV-871B (Step 10) Verify GREATS Actuation:
• At least one damper in each flowpath

-CLOSED

• Normal Supply Air
• Normal Return Air
• Lavatory Exhaust Air
• GREATS fans-BOTH RUNNING (Step 11) Verify Cl and CVI During a Fire Event A confirmed fire has occurred in the control complex or cable tunnel (fire systems S05, S06,S08,Z05,Z18,orZ19).

Go to END E-0, REACTOR TRIP OR SAFETY INJECTION Examiner following operator NOT performing ATT-27.0 continue HERE. (Step 7) Verify Both MDAFW Pumps NOTE: The B AFW Pump is Running OOS, and the A AFW Pump will TRIP shortly after manual START. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# _6_.,_7_&_8 ___ Page _5_8_-11 Event

Description:

Time .. Pos. co HCO/ co HCO/ co HCO/ co HCO/ co Feed Line Rupture Inside Containment/Turbine fails to Auto Trip ment/Safety Injection fails to actuate Automatically/A AFW Pump to Auto Start/Trips after Manual Start/TDAFW Pump trips on Overspeed/Standby AFW fails to function Expe<:ted Actions/Beh<:tvior

• Comments

.. (Step 7 RNO) Manually start both MDAFW NOTE: The TDAFW Pump pumps. will trip on overspeed IF less than 2 MDAFW pumps are running, If dispatched as an AO, SIM THEN manually open TDAFW pump steam DRIVER: Report that supply valves. governor valve cannot be

• MOV-3505A reset in 5 minutes.
• MOV-3504A (Step 8) Verify AFW Valve Alignment:
• AFW flow-INDICATED TO BOTH S/G(s)
• AFW flow from each MDAFW pump -LESS THAN 230 GPM (Step 8 RNO) Manually align valves as NOTE: There will be no necessary AFW flow, and manually alignment of valves will NOT restore flow. (*Step 9) Monitor Heat Sink:
• Check S/G narrow range levell -NOTE: Adverse GREATER THAN 7% [25% ADVERSE Containment Numbers CNMT] in any SIG should be used, until Containment Pressure is less than 4 psig. (Step 9 RNO) 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 gpm AFW flow. IF AFW flow greater than 200 gpm can flow can NOT be established, THEN go to FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK. Step 1. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# _6_.._7_&_8 ___ Page of _5.-8_-l1 Event

Description:

,' 'Time f>os. * .. 1 .. Feed Line Rupture Inside Containment/Turbine fails to Auto Trip ment/Safety Injection fails to actuate Automatically/A AFW Pump to Auto Start/Trips after Manual Start/TDAFW Pump trips on Overspeed/Standby AFW fails to function Expected Actions/Behavior. .. comments . NOTE: The CRS will go to FR-H.1. Examiner NOTE: An Orange Path on Containment will also exist but the Red Path on Heat Sink will be a higher priority. FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK HCO/ Foldout Page NOTE: The crew will co monitor these conditions throughout the performance of FR-H.1. LOSS OF SW CRITERIA HCO (Step 1) Check If Secondary Heat Sink Is Required: a) RCS pressure-GREATER THAN ANY NON-FAUL TED SIG PRESSURE b) Check RCS cold leg temperature GREATER THAN 350°F co (*Step 2) Check if Bleed and Feed is NOTE: Adverse Required Containment Numbers Both S/G level wide range levels LESS should be used, until Containment Pressure is THAN 120 inches [160 inches adverse less than 4 psig. CNMTl CRS (Step 2 RNO) Go to Step 3. HCO (Step 3.a) Try to Establish AFW Flow To At Least One Intact S/G: a) Check Slowdown and Sample Valves-CLOSED Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# _6.....,,_7_&_8___ Page of ___;_58.__-1 1 Event

Description:

Time* Pos .... HCO co HCO HCO co Feed Line Rupture Inside Containment/Turbine fails to Auto Trip ment/Safety Injection fails to actuate Automatically/A AFW Pump to Auto Start/Trips after Manual Start/TDAFW Pump trips on Overspeed/Standby AFW fails to function I** .. Expected Actions/Behavior Comments. ' (Step 3.a RNO) Place Blowdown and sample valve switches to CLOSE (Step 3.b) Verify 2 MDAFW Pump-NOTE: Neither MDAFW AVAILABLE Pump is available. (Step 3.b RNO) Perform the following: NOTE: The TDAFW Pump IF the TDAFW is available THEN ...... is NOT available,

however, IF SBAFW is available THEN go to Step 4. the SBAFW System is available.

(Step 4) Stop Both RCPs NOTE: The HCO will stop both RCPs. (Step 5) Reset SI if Actuated (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 NOTE: The CO will attempt to align Train B to feed the B SG due to the fault in A SG.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# _6_,,_7_&_8 ___ Page of Event

Description:

Time Pos. co Feed Line Rupture Containment/Turbine fails to Auto Trip ment/Safety Injection fails to actuate Automatically/A AFW Pump to Auto Start/Trips after Manual Start/TDAFW Pump trips on Overspeed/Standby AFW fails to function Expected Actions/Behavior Comments ' ' (Step C) Align SAFW Pump D to selected SIG 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-97048, SAFW PUMP D ISOL VLV
• MOV-9746, SAFW PMP D EMERG DISCH VLV 3) Open MOV-96298, SAFW PUMP D SUCTION VLV 4) Verify at least 1 SW pump running Sa) To feed S/G B, go to step 6. 6) Restore SAFW flow as directed by procedure in effect. NOTE: The CO will report that the D SBAFW Pump is ready to be started.

FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK CRS/ (Step 6.a.2) Determine SAFW flow NOTE: The CRS will direct co requirements per ATT-22.0, ATTACHMENT the CO to use ATT-22.0 to RESTORING FEED FLOW determine the allowable rate of feed flow to the B SG. ATT-22.0, ATTACHMENT RESTORING FEED FLOW HCO (Step 1) Check affected SIG Loop RCS NOTE: The CO will Temperature determine that the B SG can be filled as desired to restore Narrow Range Level to > 25%, when a Feedwater flow source is restored. Tavg in the affected Loop Less Than 550°F. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# _.....6.-.7_&_8 ___ Page 58 Event

Description:

Feed Line Rupture Inside C1ontainment/Turbine fails to Auto Trip ment/Safety Injection fails to actuate Automatically/A AFW Pump to Auto Start/Trips after Mainual Start/TDAFW Pump trips on Overspeed/Standby AFW fails to function Time *'* .. Expected ActiOns/Behavior Comments' co Fill affected SIG as necessary to restore level CRS Go to Step 3. HCO (Step 3) Check RCS Loop Hot Legs -BOTH HOT LEG TEMPERATURES LOWERING HCOI (Step 4) Verify affected SIG is not faulted or NOTE: The B SG is NOT co ruptured. Faulted or Ruptured. FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK co (Step 6.a.3) Start selected SAFW pump{s) NOTE: The D SBAFW a. IF greater than 215 gpm total SAFW Pump will fail to start, and flow can NOT be established, THEN the CRS will direct the CO to go to Step 7 start the C SAFW pump per Section B of A TT -5.1. ATTACHMENT-5.1, ATTACHMENT SAFW co (Step B) Align SAFW Pump C to selected SIG as follows:

1) Ensure SI reset 2) Ensure the following valves open:

• MOV-9701 A, 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 SUCTION VLV NOT open . HCOICO should inform CRS that suction valve to C SAFW pump cannot be opened. FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK Appendix 0 Operator Action Form ES-0-2 Op Test No.: N2014-301 Scenario#

3 Event# _6_..,_7_&_8 ___ Page of Event

Description:

Time Pos ... CRS co co co CRS HCO co Feed Line Rupture Inside Containment/Turbine fails to Auto Trip ment/Safety Injection fails to actuate Automatically/A AFW Pump to Auto Start/Trips after Manual Start/TDAFW Pump trips on Overspeed/Standby AFW fails to function

• Expected Comments.

(Step 6.a RNO) If greater than 215 gpm total SAFW flow can NOT be established, THEN go to Step 7 (Step 7) Try to Establish MFW Flow to at Least One SIG

• Check any MFW pump AVAILABLE
• Check condensate system:
• Condensate pump -ANY RUNNING
• MFW pump suction pressure GREATER THAN 200 PSIG
• Establish MFW flow:
• Check MFW pump discharge valves-CLOSED
• Verify MFW regulating or bypass valves -OPERABLE
• Depress MANUAL pushbuttons 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: The operator may
• SIG A. AOV-3995 NOT open AOV-3995 because the A SIG is
• SIG B. AOV-3994 Faulted (Feed Line Fault).
• Dispatch AO to restore MFW pump NOTE: The CRS will SW cooling dispatch an AO. SIM DRIVER: as AO, acknowledge, and immediately reports that SW is verified.
• Verify SIG blowdown key switches in NORMAL
• Ensure Annunciator H-4, MAIN FEED PUMP OIL SYSTEM-EXTINGUISHED Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

3 Event# _6 .... _7_&_8 ___ Page _58 _ _,1 Event

Description:

Time .. Pos. co co co co co co CRS co ** .. * * * * * *

• Feed Line Rupture Inside Containment/Turbine fails to Auto Trip ment/Safety Injection fails to actuate Automatically/A AFW Pump to Auto Start/Trips after Manual Start/TDAFW Pump trips on Overspeed/Standby AFW fails to function Expectec.1*.Actions/Behavior

... Comments . Close Condensate Bypass valve, AOV-3959 Ensure Annunciator H-11, Feed NOTE: Whether or not this PUMP SEAL WATER LO DIFF Annunciator is LIT will PRESS 15 PSI-EXTINGUISHED depend on the control of the Hotwell Level, which is in MANUAL Control Ensure one MFW pump recirc valve-OPEN Start Selected MFW pump Open MFW pump discharge valve Open MFW regulating or bypass NOTE: The CO will valves to control MFW flow per determine that the B SG can requirements of ATT-22.0, be filled as desired to ATTACHMENT RESTORING FEED restore Narrow Range Level FLOW to> 25% per ATT-22.0, when a Feedwater flow source is restored. Go to Step 11 Step 11. Check SIG Levels: NOTE: Adverse a) Narrow range level in at least one Containment Numbers SIG-GREATER THAN 7% [25% should be used, until adverse CNMT] Containment Pressure is IF feed flow verified and level rising less than 4 psig. in at Least one SIG, THEN maintain flow to Restore narrow level NOTE: The CRS will greater than 7% [25% adverse determine that a Secondary CNMT]. Heat Sink has been restored b) Return to procedure and sti3p in with the MFW System, and effect. return to E-0, Step 9. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# _6 ..... _7....;.&....;.8 ___ Page of _5_8 _ _,1 Event

Description:

Time*** Pos .. ** ** Feed Line Rupture Inside Containment/Turbine fails to Auto Trip ment/Safety Injection fails to actuate Automatically/A AFW Pump to Auto Start/Trips after Manual Start/TDAFW Pump trips on Overspeed/Standby AFW fails to function

• .E:.icpected Actions/Behavior Comments

.. CRITICAL TASK 2. Establish feedwater flow into at least one Steam Generator before RCS Bleed and Feed is required. Safety Significance: Failure to establish feedwater flow into at least one Steam Generator results in the crew having to rely upon the lower-priority action of having to initiate RCS Bleed and Feed to minimize the possibility of core uncovery. Failure to perform this task, when able to do so, constitutes incorrect performance that leads to degradation of the RCS and/or fuel cladding fission product barriers. NOTE: The CRS will likely conduct an Alignment Brief. E-0, REACTOR TRIP OR SAFETY INJECTION co (*Step 9) Monitor Heat Sink:

• Check SIG narrow range level --NOTE: Adverse GREATER THAN 7% [25% ADVERSE Containment Numbers CNMT] in any SIG should be used, until Containment Pressure is less than 4 psig.
• Check SIG narrow range level BOTH SIG LESS THAN 50%
• Control feed flow to maintain SIG narrow NOTE: Adverse range level between 7% [25% adverse Containment Numbers CNMT] and 50%. should be used, until Containment Pressure is less than 4 psig. co (Step 10) Check If TDAFW Pump Can Be Stopped:
• Both MDAFW pumps -RUNNING NOTE: None of the AFW Pumps are running.

CRS (Step 10 RNO) Go to Step 11 HCO (Step 11) Check CCW Flow to RCP Thermal Barriers: Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# 6, 7 &8 Page _51_ of 58 Event

Description:

Time * *Pos.* HCO HCO HCO Feed Line Rupture Inside Containment/Turbine fails to Auto Trip ment/Safety Injection fails to actuate Automatically/A AFW Pump to Auto Start/Trips after Manual Start/TDAFW Pump trips on Overspeed/Standby AFW fails to function .. /

• Expected Actions/Behavior Comments/

. *.

• Annunciator A-7, RCP 1A CCW RETURN HI TEMP OR LO FLOW EXTINGUISHED
• Annunciator A-15, RCP 18 CCW RETURN HI TEMP OR LOW FLOW -EXTINGUISHED

(*Step 12) Monitor RCS Tavg -STABLE AT NOTE: The crew may take OR TRENDING TO 547°F the RNO action depending on how the crew has controlled Temperature to this point. (Step 12 RNO) If temperature less than 547°F and lowering, THEN perform the following:

• Stop dumping steam .
• Ensure reheater steam supply valves are closed.
• IF cooldown continues, THEN control NOTE: Adverse total feed flow between 20 gpm to 230 Containment Numbers gpm until narrow range level greater than should be used, until 7% [25% adverse CNMT] in at least one Containment Pressure is SIG. less than 4 psig.
• WHEN SIG level greater than 7% [25% NOTE: Adverse adverse CNMT] in one SIG, THEN limit Containment Numbers feed flow to that required to maintain should be used, until level in at least one SIG. Containment Pressure is less than 4 psig.
• IF cooldown continues, THEN close both MS IVs. (Step 13 ) Check PRZR PORVs and Spray Valves:
• PORVs -CLOSED
• Auxiliary Spray Valve (AOV-296)

-CLOSED Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# ___.6,_7_&_8___ Page of _5_8_-11 Event

Description:

Time.*' Pos. HCO CRS co CRS HCO/ co Feed Line Rupture Inside Containment/Turbine fails to Auto Trip ment/Safety Injection fails to actuate Automatically/A AFW Pump to Auto Start/Trips after Manual Start/TDAFW Pump trips on Overspeed/Standby AFW fails to function .. .* Comments

• Check PRZR pressure

-LESS THAN 2260 PSIG

• Normal PRZR spray valves -CLOSED
• PCV-431A
• PCV-431B (Step 14) Monitor RCP Trip Criteria:
• RCP status -ANY RCP RUNNING NOTE: The RCPs were previously stopped.

(Step 14c RNO) Go to Step 15. (Step 15) Check If SIG Secondary Side Is NOTE: The A SG is Intact: depressurizing in an

• Pressure in both S/Gs-ST ABLE OR uncontrolled manner. RISING
• Pressure in both S/Gs-GREATER THAN 110 PSIG (Step 15 RNO) IF any SIG pressure!

lowering in an uncontrolled manner OR completely depressurized, THEN go to E-2, FAUL TED STEAM GENERATOR ISOLATION, Step 1. NOTE: The CRS will go to E-2. NOTE: The CRS will likely conduct an Alignment Brief. E-2, FAUL TED STEAM GENERATOR ISOLATION Foldout Page NOTE: The crew will monitor these conditions throughout the performance of E-2. LOSS OF SW CRITERIA Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# _6 __ ._7_&_8___ Page ::.___ of _58_-11 Event

Description:

Time Pos. co co co co Feed Line Rupture Inside Containment/Turbine fails to Auto Trip ment/Safety Injection fails to actuate Automatically/A AFW Pump to Auto Start/Trips after Manual Start/TDAFW Pump trips on Overspeed/Standby AFW fails to function Expected Actions/Behavior Comments (Step 1) Check MSIV of Faulted Sl13(s) -NOTE: BOTH MSIVs are CLOSED CLOSED. (Step 2) Check If Any SIG Secondary Side Is Intact:

• Check pressure in SIG A-ST ABLE OR NOTE: The A SG is RISING depressurized.

OR

• Check pressure in SIG B -ST ABLE OR RISING (Step 3) Check Faulted SIG Status: NOTE: The A SG is depressurized.
• Faulted SIG pressure

-LOWERING IN AN UNCONTROLLED MANNER OR

• Faulted SIG -COMPLETELY DEPRESSURIZED (Step 4) Isolate Feed Flow to Faulted SIG:
• Close or verify closed the following valves:
• Faulted SIG MDAFW pump discharge valve
• SIG A, MOV-4007
• Faulted SIG MFW regulating valve and bypass valve -CLOSED
• SIG A, HCV-466 and HCV-480
• MFW isolation valves -CLOSED
• SIG A, AOV-3995
• MDAFW pump crosstie valves -BOTH CLOSED Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

3 Event# _6 ...... _7_&_8 ___ Page :!...__ of _5_8 __ 11 Event

Description:

Time co co co . * *

• Feed Line Rupture Inside Containment/Turbine fails to Auto Trip ment/Safety Injection fails to actuate Automatically/A AFW Pump to Auto Start/Trips after Manual Start/TDAFW Pump trips on Overspeed/Standby AFW fails to function Comments
• MOV-4000A
• MOV-40008 Faulted SIG SAFW pump discharge valve
• SIG A, MOV-9704A NOTE: MOV-9704A is OPEN from ATT-5.1, and must be closed. Pull stop faulted SIG MDAFW pump Close faulted SIG TDAFW flow control valve
• SIG A, AOV-4297 (Step 5) Isolate Steam Flow From Faulted SIG:
• Verify faulted SIG ARV -CLOSED
• SIG A, AOV-3411
• Close faulted SIG TDAFW pump steam supply valve and place in PULL STOP
• SIG A, MOV-3505A
• Verify faulted SIG blowdown and sample valves -CLOSED
• SIG A, AOV-5738 and AOV-5735
• Dispatch AO to complete faulted SIG NOTE: The CRS will isolation (Refer to ATT-10.0, dispatch an AO. ATTACHMENT FAULTED SIG) SIM DRIVER: as AO, acknowledge.

(*Step 6) Monitor Intact SIG Levels: Examiner NOTE: Terminate the Exam at the discretion of the Lead Examiner. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# _6 ..... _7_&_8___ Page =...__ of _5_8_-11 Event

Description:

Time+ Pos . .. HCO co co CRS Feed Line Rupture Inside Containment/Turbine fails to Auto Trip ment/Safety Injection fails to actuate Automatically/A AFW Pump to Auto Start/Trips after Manual Start/TDAFW Pump trips on Overspeed/Standby AFW fails to function Actions/Behavior . Comments"

• Narrow range level -GREATER THAN NOTE: Adverse 7% [25% adverse CNMT] Containment Numbers should be used, until Containment Pressure is less than 4 psig.
• Control feed flow to maintain narrow NOTE: Adverse range level between 17% [25% adverse Containment Numbers CNMT] and 50% should be used, until Containment Pressure is less than 4 psig. (Step 7) Check Secondary Radiation Levels -NORMAL
• Steamline radiation monitor (R-31 and R-32)
• Air ejector radiation monitor (R-*15)
• SIG blowdown radiation monitor (R-19)
• Request Chem Tech sample S/Gs for activity (Step 8) Adjust Steam Dump to Minimize RCS Heatup:
• Determine allowable intact SIG pressure using maximum hot leg temperature (Refer to FIG-7.0, FIGURE INTACT SIG PRESSURE)
• Check condenser steam dump available:

NOTE: Steam Dump to the Condenser is NOT available. (Step 8b RNO) Perform the following:

• Adjust intact SIG ARV to pressure determined from FIG-7.0, FIGURE INT ACT SIG PRESSURE.
• Go to E-1, LOSS OF REACTOR OR SECONDARY

COOLANT, Step 1.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 3 Event# _6 ..... _7_&_8 ___ Page _5_8_-ll Event

Description:

Time

• Feed Line Rupture Inside Containment/Turbine fails to Auto Trip ment/Safety Injection fails to actuate Automatically/A AFW Pump to Auto Start/Trips after Manual Start/TDAFW Pump trips on Overspeed/Standby AFW fails to function

>Expected Actions/Behavior . .*. Comments NOTE: The CRS will go to E-1. Terminate the Exam at the discretion of the Lead Examiner SRO Examiner Perform Admin JPM A4c on CRS TURNOVER SHEET for NRC Exam Scenario

1. 3 Core Age: MOL Procedure in Use: ACTIONS/NOTES:

48% Power, Equilibrium Xe

• The plant is at 48% power (MOL) . Outside Air Temp= 45°F
• The plant power was reduced several days ago due to a Water Temp= 45°F malfunction on the A MFW Pump.
• Corrective Maintenance has been completed, and the pump is running for retest.
• The B AFW Pump is OOS for Bearing Replacement.

A-52.4 submitted for ITS 3.7.5, 7 day Action. Boron: 1106 ppm RCS LEAKAGE: (gpm)

• MRPI for Rod G3 indicates on the bottom, however, this is a Total: . 021 confirmed instrumentation problem (l&C is working).

BAST: 17,400 ppm Identified: .003

• RG&E Energy Control Center has requested that the electric RCS Activity:

Normal Unidentified: .018 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. The 767 line will remain OPERABLE throughout the inspection.

• The following Alarms are in:
• C-5, PPCS ROD SEQUENCE OR ROD (MRPI Failure)
• DEVIATION/PPCS LTOP HI-LOW TEMPERATURE
• C-14, ROD BOTTOM (MRPI Failure)
• E-4, POWER RANGE UPPER DETECT FLUX DEV OR AUTO DEFEAT(<

50% Power)

• E-12, POWER RANGE LOWER DETECT FLUX DEV OR AUTO DEFEAT (< 50% Power)
• J-25, SAFEGUARDS EQUIPMENT LOCKED OFF (B MD AFW Pump OOS)
• Protected equipment IAW OPG Protected Equipment.

TURNOVER SHEET for NRC Exam Scenario

1. 3 Equie.ment Problems/OOS:

Planned Activities for Shift: Electrical 012erator Declarations See NOTES

• Align a 0/100 configuration on circuit 7T None in effect BAST RWST 1st hour dilution stabilization 2na hour dilution stabilization (gal) (gal) (gal RMW) (gal RMW) 10% at 1 % per minute 52 545 77 51 10% at 10% per hour 48 503 77 52 50% at 1 % per minute 229 2482 558 314 50% at 10% per hour 173 1860 296 98 A-52.4 EQUIPMENT DATE/TIME 005 LCO TITLE EXP DATE ECO 'B' MDAFW Pump Yesterday, 24hrs ago 3.7.5.B AFW system 7 days 2 days from now AM MRPI for Rod G3 Today 4hrs ago 3.1.7.A2 Rod Position Indication None None A-52.12 EQUIPMENT DATE/TIME 005 TRM/ODCM TITLE EXP DATE ECO PROGRAM:

Ginna Operations Training MODULE: 2014 Initial License Operator Training Class TOPIC: NRC Simulator Exam Scenario N2014-301-4

REFERENCES:

1. S-3.2P, Swapping CVCS Letdown Orifices, Rev 00401 2. P-17, Operations Control Room Operating Instructions, Attachment 12, CROl-12 Swapping Electro-Hydraulic Pumps, Rev 01602 3. AR-E-26, POWER RANGE CHANNEL DEV +/-2°/ci, Rev 12 4. AR-E-28, POWER RANGE ROD DROP ROD STOP -5%/5SEC, Rev 00700 5. ER-NIS.3, PR Malfunction, Rev 02603 6. Technical Specification 3.3.1, Reactor Trip Instrumentation, Amendment 112 7. CNG-OP-1.01-1000, Conduct of Operations, Rev 01000 8. AR-F-19, PRZR PORV OUTLET HI TEMP 145°F, Rev 01101 9. AP-PRZR.1, Abnormal Pressurizer

Pressure, Rev 01700 10. A-503.1, Emergency And Abnormal Operating Procedures Users Guide, Rev 04409 11. Core Operating Limits Report (COLR), Cycle 37, Rev 0 12. AP-RCS.1, Reactor Coolant Leak, Rev 02001 13. AR-F-9, PRT HI PRESS 5 PSI, Rev 00701 14. AP-TURB.5, Rapid Load Reduction, Rev 01600 15. ATT-23.0, Attachment Transfer 4160 V Loads, R.ev 0 16. Technical Specification 3.4.13, RCS Leakage, Amendment 100 17. Technical Specification 3.4.11, Pressurizer PORVs, Amendment 88 18. Technical Specification 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits, Amendment 80 19. TRM 3.4.3, Anticipated Transients Without Scram (ATWS) Mitigation, Rev 31 20. E-0, Reactor Trip and Safety Injection, Rev 04602 21. ATT-27.0, Attachment Automatic Action Verification, Rev 00300 22. E-1, Loss of Reactor or Secondary

Coolant, Rev 04100 23. ATT-8.1, Attachment DIG Stop, Rev 6 24. ES-1.2 Post-LOCA Cooldown and Depressurization, Rev 03601 25. ATT-15.0, Attachment RCP Start, Rev 11 26. FR-P.1, Response to Imminent Pressurized Thermal Shock Condition, Rev 03200 Validation Time: 108 Minutes Author: David Lazarony, Essential Training

& Consulting, LLC Facility Review: Rev. 110714 Scenario Event Description NRC Scenario 4 Facility: Ginna Scenario No.: 4 Op Test No.: N2014-301 Examiners: Operators: (SRO) (RO) (BOP) Initial Conditions: The plant is at 48% power (MOL). Power has been held at this level for approximately four days while corrective maintenance is performed on the A MFW Pump. Maintenance has just been completed. Chemistry has requested that Letdown flow be raised from 40 gprn to 60 gpm. Also, it is expected to swap EHC Pumps per P-17 for routine equipment rotation. The area has experienced severe weather over the last 6 hours, and this is expected to continue for the next 6 hours. Turnover: The following equipment is Out-Of-Service: The B AFW Pump is OOS for Bearing Replacement. Steam Flow channel FT-475 is OOS. The channel has been defeated per ER-INST.1. Event Malf. Event Type* Event No. No. Description 1 NA N-RO Swap Letdown Orifice (40 gpm to 60 gpm) N-SRO 2 NA N-BOP Alternate EHC Supply Pumps N-SRO 3 NIS06A C-RO Power Range N41 Upper Detector fails LOW/Letdown Pressure CVC07A I-BOP Controller Failure CVC23 l(TS)-SRO 4 PZR05B C-RO PORV Leak/Block Valve Failure C(TS)-SRO 5 TUR09D R-RO Downpower/Failurn of Turbine Control/EHC C-BOP C-SRO 6 PZR07 M-RO Pzr Steam Space Break M-BOP M-SRO 7 RPS11-C-RO Seal Water Return Isolation CIV Fails in AUTO A3 C-SRO * (N)ormal, (R)eactivity, (I )nstrument, (C)omponent, (M)ajor Ginna 2014 NRC Scenario

1. 4 Scenario Event Description NRC Scenario 4 The plant is at 48% power (MOL). Power has been held at this level for approximately four days while corrective maintenance is performed on the A MFW Pump. Maintenance has just been completed.

Chemistry has requested that Letdown flow be raised from 40 gpm to 60 gpm. Also, it is expected to swap EHC Pumps per P-17 for routine equipment rotation. The area has experienced severe weather over the last 6 hours, and this is expected to continue for the next 6 hours. The following equipment is Out-Of-Service: The B AFW Pump is OOS for Bearing Replacement. Steam Flow channel FT-475 is OOS. The channel has been defeated per INST.1. Shortly after taking the watch, the operator will swap Letdown Orifice Control valves in accordance with S-3.2P, Swapping CVCS Letdown Orifices. After this, the operator will alternate the EHC Supply Pump alignment in accordance with P-17, Operations Control Room Operating Instructions, Attachment 12, CROl-12 Swapping Hydraulic Pumps. Then, the N41 Power Ranger Upper Detector will fail Low. The operator will respond in accordance with AR-E-26, POWER RANGE CHANNEL DEV +/-2%, and/or AR-E-28, POWER RANGE ROD DROP ROD STOP -5%/5SEC, and then enter ER-NIS.3, PR Malfunction. The operator will address Technical Specification 3.3.1, Reactor Trip Instrumentation. While the CO is defeating the failed Power Range Channel, a failure of the Letdown Pressure Controller will cause PCV-135 to fail OPEN. The operator will need to take manual control of the failed controller, and control Letdown pressure manually. Subsequently, Pressurizer PORV-431C will fail partially open. The operator will respond in accordance with AR-F-18, PRZR PORV OUTLET HI TEMP 145°F, and enter AP-PZR.1, Abnormal Pressurizer Pressure. When the operator attempts to isolate the PORV, the Block Valve will fail to shut fully resulting in a 2-5 gpm leak into the PRT. The crew may implement AP-RCS.1, Reactor Coolant Leak, and prepare to make a Containment entry. Ultimately, the crew will be directed to take the unit off-line. The operator will address Technical Specification 3.4.11, Pressurizer PORVs, 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits, as well as TRM 3.4.3, Anticipated Transients Without Scram (A TWS) Mitigation. Although the crew will address Technical Specification 3.4.13, RCS Leakage, it is likely that at the current leakrate, this specification will be met. The operator will take the unit off line in accordance with AP-TURB.5, Rapid Load Reduction During the downpower, the Main Turbine will fail in automatic

control, and shift to manual control.

The operator will identify that the load reduction has been stopped, and use manual control of the turbine to restart and continue the downpower. The remainder of the downpower will need to be accomplished using manual control of the Turbine. When the plant is at approximately 40% power, the piping leading to the failed PORV will fail so that a vapor space Small Break LOCA occurs. The plant will trip and Safety Injection will be actuated, and the operator will enter E-0, Reactor Trip or Safety Injection. On the plant trip Containment Isolation Valve MOV-313, the Seal Water Return Line CIV, will fail to close automatically, requiring that the operator manually close this valve. Scenario Event Description NRC Scenario 4 The operator will transition from E-0 to E-1, Loss of Reactor or Secondary

Coolant, and then into ES-1.2 Post-LOCA Cooldown and Depressurization.

While in ES-1.2, an Orange Path may occur on the RCS Integrity Critical Safety Function Status Tree. The scenario will terminate at Step 14 of ES-1.2, after the crew has demonstrated the ability to evaluate/perform the SI flow reduction

sequence, or upon transition to FR-P.1, Response to Imminent Pressurized Thermal Shock Condition.

Critical Tasks: 1. 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.

2. Close the Seal Water Return Containment Isolation Valve before transition out of E-0. Safety Significance:

Failure to close at least one Containment Isolation Valve on each critical penetration under the postulated conditions when it is possible to do so, constitutes operation leading to degradation of the Containment Barrier. Failure to take this action leads to an unnecessary release of fission products to the auxiliary

building, increasing the potential for release to the environment, and reducing accessibility to vital equipment within the Auxiliary Building.

Higher radiation levels within the Auxiliary Building will result in a degradation of ALARA principles. 0 0 0 0 0 0 Bench Mark Prior to Crew Briefing Scenario Event D,escription NRC Scenario 4 SIMULATOR OPERATOR INSTRUCTIONS ACTIVITY DESCRIPTION Reset to Temp l/C 48% power MOL 151 (Built from IC-T=O: 20) OVR-DO-FDW21A=OFF (MOV-4000A Green Lamp) OVR-DO-FDW22A=OFF (MOV-4000B Green Lamp) MALF RPS11-A3, ISOL SIG ONLY Set T-30 = x06i230a==1 (Close for MOV-515) Insert MALF STM01 E, 0 Insert OVR-DO-FDW06A, OFF Insert MALF NIS06A, 0, on T-1 Insert MALF CVC07 A, 100, on T-2 Insert MALF CVC23, on T-2 Insert MALF PZR05B, 5, on T-3 Insert OVR-Dl-PZR04C, FALSE, on T-30 Insert OVR-Dl-PZR04D, TRUE, on T-30 Insert OVR-DO-PZR04A, ON, on T-30 Insert OVR-DO-PZR04B, ON, on T-30 Insert MALF TUR09D, 100, on T-4 lm;ert OVR-DO-TUR050=0FF (IMP IN), on T-4 Insert OVR-DO-TUR05P=ON (IMP OUT), on T-4 lm;ert MALF PZR07, 89000, on T-5 RUN

• Hang Protective Tags on the A MDAFW Pump and the TDAFW Pump Steam Supply Valves.
• Hang CAUTION tags on the B MDAFW pump and R-19 panel
• Hang Caution Tags on MOV-4000A and B.
• Place a Black Dot on annunciator J-25 for the Safeguards equipment OOS. Crew Briefing

1. Assign Crew Positions based on evaluation requirements

2. Review the Shift Turnover Information with thei crew. 3. Provide crew with a copy of S-3.2P and P-17, Attachment

12. T-0 Begin Familiarization Period Upon Event1 Swap Letdown Orifice (40 gpm to 60 gpm) Turnover Upon Event2 Alternate EHC Supply Pumps Completion of Orifice Swap Bench Mark ', D At direction of examiner D At direction of examiner D At direction of examiner D At direction of examiner Scenario Event Description NRC Scenario 4 ACTIVITY DESCRIPTION Event 3 Power Range N41 Upper Detector fails Trigger#1 LOW/Letdown Pressure Controller Failure NIS06A 0%, No Ramp Trigger#2 CVC07A 100%, No Ramp CVC23 NOTE: This Malfunction (Letdown Line Safety Valve fails OPEN) has been included to ensure that Letdown Pressure drops sufficiently on a Letdown Pressure Controller failure causing PCV-135 to fail OPEN. When this is inserted the SIM DRIVER will also be required to use INSIGHT and set cldsp 135 = 1.:.:1-Event 4 PORV Leak/Block Valve Failure Trigger#3 5%, No Ramp (Throttled back to 2% after the PZR05B operator attempts to close the PORV Block Valve) Trigger #30 (Block Valve CS to CLOSE) OVR-PZR04A, ON Block Valve fails in mid-position (Green light LIT) OVR-PZR04B, ON (Red light LIT) OVR-PZR04C, FALSE (Close signal) OVR-PZR04D, TRUE (Open signal) Event 5 Downpower/Failure of Turbine Control/EHC Trigger#4 TUR09D 100%, No Ramp OVR-TUR050=0FF NOTE: will need to insert: OVR-TUR05P=ON REM-EDS49=RESET REM-EDS50=RESET When performing ATT-23.0 Event 6 Pzr Steam Space Break (PORV Leakage)

Trigger#5 PZR07 89,,000, No Ramp Bench Mark D At direction of examiner D Scenario Event Description NRC Scenario 4 .ACTIVITY DESCRIPTION Event7 Seal Water Return Isolation CIV Fails in AUTO RPS11-A3 (T=O) NOTE: This MALF is entered at T=O, and will become effective on Reactor Trip/SIS/CIS Terminate the scenario upon direction of Lead Examiner Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# -----Page 8 of 67 Event

Description:

Swap Letdown Orifice (40 gpm to 60 gpm) Shortly after taking the watch, the operator will swap Letdown Orifice Control valves in accordance with S-3.2P, Swapping CVCS Letdown Orifices. SIM DRIVER Instructions: NA Indications Available: NA . . . " Comments " Time Pos. Expected S-3.2P, SWAPPING eves LETDOWN ORIFICES NOTE: The HCO will contact an AO. SIM DRIVER: as AO, acknowledge. HCO (Step 6.1.1) VERIFY DIVERT VLV CATION DEBOR DI, AOV-244 is in the BYPASS position. HCO (Step 6.1.2) IF required, THEN PLACE TCV-NOTE: Since TCV-130 is slow 130 to manual AND ADJUST as necessary to react, most operators will to maintain letdown temperature at desired take this controller to value. OTHERWISE, MARK this Step N/A. MANUAL. HCO (Step 6.1.3) PLACE PCV-135 to MANUAL AND ADJUST as necessary to control Low Pressure Letdown pressure at approximately 200 psig. HCO (Step 6.1.4) CLOSE one of the following 40 NOTE: The HCO will close gpm orifice valves, THEN IMMEDIATELY AOV-202A completely before OPEN L TDN ORIFICE AOV-202 (N/A 40 opening AOV-200. qpm orifice valve not operated).

• AOV-202
• AOV-200A
• AOV-200B HCO (Step 6.1.5) ADJUST PCV-135 UNTIL Pl-135 indicates aooroximatelv 250 psiq.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# _.;... _____ Page 9 Of _6;..;7 _ _.1 Event

Description:

Swap Letdown Orifice (40 gpm to 60 gpm) f:xpected Actions/Behavior ,, Time ,,, ,Pos. '" ,'. ,, comments ,, " HCO (Step 6.1.6) ENSURE PCV-135 controller NOTE: It will be desired to signal is nulled/balanced, THEN PLACE leave PCV-135 in AUTO PCV-135 to AUTO. control. HCO (Step 61.7) ADJUST the Charging Pump that is in manual UNTIL the speed of the operating pumps is approximately 1equal. HCO (Step 6.1.8) VERIFY Letdown temperature is NOTE: It will be desired to at desired value, THEN ENSURE TCV-130 is leave TCV-130 in AUTO in AUTO. control. HCO (Step 6.1.9) IF Charging/Letdown mismatch NOTE: Most operators will exist, THEN PLACE Charging Pumps in leave the A Charging Pump in manual AND ADJUST as necessary to Auto, and attempt to control maintain Charging/Letdown mismatch at the speed of the C Charging approximately

0. OTHERWISE, MARK this Pump speed in MANUAL. Step N/A. HCO/ (Step 6.1.10) LOCALLY ADJUST SEAL AO INJECTION INLET NEEDLE VLV TO RCP A, V-300A AND SEAL INJECTION INLET NEEDLE VLV TO RCP B, V-3008, as necessary to maintain labyrinth seal D/P between 30 and 40 inches. HCO (Step 6.1.11) MONITOR Letdown Temperature is controlling at desired value. HCO/ (Step 6.1.12) VERIFY local demin D/P less NOTE: The HCO will contact AO than 25 psid (DPl-100, DPl-101 ). an AO. SIM DRIVER: as AO, acknowledge, and report that the Demin D/P is 12 psid.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# ------Page 10 of 67 --..;1 Event

Description:

Swap Letdown Orifice (40 gpm to 60 gpm) Time*** Pos. . ... Expected.Actions/Behavior Comments

• • * ** .. .. HCO (Step 6.1.13) NOTIFY Shift Chemistry NOTE: The HCO will contact Technician.

Chemistry. SIM DRIVER: as Chemistry, acknowledge. Crew should initiate actions to complete Event #2 after this evolution is complete. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# Page 11 of 67 2 Event

Description:

Alternate EHC Supply Pumps After this, the operator will alternate the EHC Supply Pump alignment in accordance with P-17, Operations Control Room Operating Instructions, Attachment 12, CROl-12 Swapping Electro-Hydraulic Pumps. SIM DRIVER Instructions: NA Indications Available: NA Time Pos. Expected Actions/Behavior"

• • comments

.. P-17, OPERATIONS CONTROL ROOM OPERATING INSTRUCTIONS ATTACHMENT 12, CROl-12 SWAPPING ELECTRO-HYDRAULIC PUMPS NOTE: The CO will dispatch an AO. SIM DRIVER: as AO, acknowledge. co (Step 2.1) START EH System Supply Pump B. co (Step 2.2) STOP EH System Supply Pump A. co (Step 2.3) VERIFY EH Pump B is operating NOTE: The CO will contact the normally AND discharge pressure is between AO. 1600 and 2100 lbs as indicated on Pl-6055 SIM DRIVER: as AO, when loaded. acknowledge, report that EH Pump B discharge pressure is 1860 psig. co (Step 2.4) IF EH System Supply Pump Bis NOTE: The CO will recognize NOT maintaining system pressure between that this is NOT applicable 1600 to 2100 lbs as indicted on Pl-6054, THEN ..... co (Step 2.5) MONITOR AND MAINTAIN EH NOTE: The CO will contact the system temperature between 110 and 130°F. AO. SIM DRIVER: as AO, acknowledge, report that EH Pump B discharge temperature is 118°F. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# _2 _____ Page 12 of 67 Event

Description:

Alternate EHe Supply Pumps ..

• Pos. .. Expected Actions!Behayi9r

.Comments co (Step 3.0) MONITOR System operation for 15 minutes after pump swap to ENSURE stable system operation and normal parameters. NOTE: The CRS may notify the Wee. SIM DRIVER: as wees, acknowledge. NOTE: The CRS will likely conduct a Plant Status Brief. At the discretion of the Lead Examiner move to Event #3. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# 3 Page 13 of 67 Event

Description:

Power Range N41 Upper Detector fails LOW/Letdown Pressure Controller Failure Then, the N41 Power Ranger Upper Detector will fail Low. The operator will respond in accordance with AR-E-26, POWER RANGE CHANNEL DEV +/-2%, and/or AR-E-28, POWER RANGE ROD DROP ROD STOP -5%/5SEC, and then enter ER-NIS.3, PR Malfunction. The operator will address Technical Specification 3.3.1, Reactor Trip Instrumentation. While the CO is defeating the failed Power Range Channel, a failure of the Letdown Pressure Controller will cause PCV-135 to fail OPEN. The operator will need to take manual control of the failed controller, and control Letdown pressure manually. SIM DRIVER Instructions: Operate Trigger #1 (NIS06A, 0%) Indications Available:

• MCB Annunciator E-26, POWER RANGE CHANNEL DEV +/-2%
• MCB Annunciator E-28, POWER RANGE ROD DROP ROD STOP -5%/5SEC
• Nl-41 C, Power Range Flux indicating 25%
• Nl-41 B, Power Range Full Power indicating 25%
• Power Range Drawer, N41 A indicating 25%
• Power Range Drawer, Upper Detector Current indicating 0
• Power Range Drawer, Dropped Rod Rod Stop light is LIT Time Pos. , Expected

,JJ Jji>>JJJ

• 11 '"J" NOTE: The crew may enter ER-NIS.3 directly.

AR-E-26, POWER RANGE CHANNEL DEV +/-2% CRS (Step 1) Refer to ER-NIS.3. HCO (Step 2) Check alarm F-29 and power tilt indication on PPCS. HCO (Step 3) Monitor MRPI for Rod out of alignment. HCO (Step 4) Monitor incore thermocouples. AR-E-28, POWER RANGE ROD DROP ROD STOP -5%/5 SEC Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# _3 ____ Page 14 of _6_7_'""' 1 Event

Description:

Time POS;cc HCO/ co CRS CRS HCO HCO HCO HCO Power Range N41 Upper Detector fails LOW/Letdown Pressure Controller Failure Expected,Actions/Behavio:r

' Comments (Step 4.1) CHECK the Following for NOTE: The CRS will indication of a dropped or misaligned RCC recognize that AP-RCC.3 is NOT applicable.

• Power Range indications
• MRPI indication
• RCS Tavg
• Core Exit Thermocouples (Step 4.1.1) IF conditions indicate a dropped NOTE: There is no Dropped or or misaligned RCC THEN ..... Misaligned RCC. (Step 4.1.2) IF conditions indicate a malfunctioning Power Range THEN GO TO ER-NIS.3 POWER RANGE MALFUNCTION NOTE: The CRS will go to ER-NIS.3. ER-NIS.3, PR MALFUNCTION (Step 6.1) PLACE the Rod Control Bank NOTE: The HCO will place the Selector switch in M (MANUAL).

Rods in MANUAL. (Step 6.2) ADJUST Tavg Tref. (Step 6.3) IF hot leg streaming has been NOTE: Hot leg streaming has causing single channel runback NOT been causing single signals, ..... channel T runback signals -reactor power too low for this concern. (Step 6.4) DEFEAT the inoperable Power NOTE: The appropriate Range per appropriate attachment: Attachment is Attachment

1.

• Attachment 1, N-41 Defeat NOTE: The CRS will hand off the Attachment to the CO.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# _3 _____ Page 15 of 67 ---11 Event

Description:

,' Ti Ille Pos;"-'< co co co co Power Range N41 Upper Detector fails LOW/Letdown Pressure Controller Failure Expected Actions/Behavior ,', ,, 'Comments ER-NIS.3, PR MALFUNCTION ATTACHMENT 1, N-41 DEFEAT NOTE: The CO will conduct an Instrument Defeat Brief. (Step 1) IF the PPCS is operational, THEN delete NIS Channel 41 from processing by performing the following:

• SELECT "Group Update" display
• Select "List Server Groups"
• Select NIS1 from the pick list
• TURN "OFF" scan processing, then click the "Set Scan Processing" button
• ANSWER prompts (Step 2) VERIFY the ROD CONTROL BANK SELECTOR switch (MCB) is in the: M (MANUAL}

position. (Step 3) PLACE the DROPPED ROD MODE switch (Power Range N41 A drawer) to BYPASS AND VERIFY the following:

• DROPPED ROD BYPASS (local light) is ILLUMINATED.
• POWER RANGE-1 ROD DROP BYPASS (MCB BYPASS STATUS LIGHT} is ILLUMINATED.
• Annunciator (MCB) E-7, NIS TRIP BYPASS, is ILLUMINATED.

(Step 4) PLACE T/405E DELTA T DEFEAT NOTE: The CO will unlock and switch (RIL Insertion Limit Rack) to LOOP A open the RIL Insertion Limit UNIT 1 (Defeats the L'.l T Runback and Rack Cabinet, take the Rodstop for the failed channel AND removes required action, and then close the associated L'.l T input from the RIL and lock the cabinet door. computer-Annunciators F-30 AND F-31 will clear if lit). Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# _3 _____ Page 16 of 67 ---jl Event

Description:

. ,i .* Time POS;: CO/ HCO CO/ HCO co Power Range N41 Upper Detector fails LOW/Letdown Pressure Controller Failure * *** " Expected Actions/Behavior:' . ,,,, :' . ' Comments . .. (Step 5) Place the OVERTEMP TRIP NOTE: The CO will unlock and bistable (RED R-1 Protection Channel 1 open the RED R-1 Protection rack) proving switch to DEFEAT (UP) AND Channel 1 Rack Cabinet, take VERIFY the following: the required action, and then close and lock the cabinet door.

• Annunciator F-23, RCS OT AT CHANNEL ALERT, is ILLUMINATED.
• Proving light OFF if Tl-405B Tl-405A NOTE: Light is ON IF any proving light status is NOT correct, NOTE: The Proving Light THEN SUBMIT a Condition Report on the status is Correct.

discrepancy and continue with the channel defeat steps. (Step 6) PLACE the OVERPOWER TRIP bistable (Red R-1 Protection Channel 1 rack) proving switch to DEFEAT (UP) AND VERIFY the following:

• Annunciator F-32, RCS OPAT CHANNEL ALERT, is ILLUMINATED.
• Proving light OFF if Tl-405B Tl-405C NOTE: Light is ON IF any proving light status is NOT correct, NOTE: The Proving Light THEN SUBMIT a Condition Report on the status is Correct.

discrepancy and continue with the channel defeat steps. (Step 7) Verify the following bistabl,es are ILLUMINATED:

• TC405A OPAT Loop A
• TC405C OT AT Loop A IF any bistable above is NOT lit, THEN the AT channel(s) may not be in the tripped condition.

Further investigation is necessary to ensure ITS requirements are met. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# _3 _____ Page 17 of 67 Event

Description:

Power Range N41 Upper Detector fails LOW/Letdown Pressure Controller Failure Time Pos. ,'/::, Expected Actions/Behavior Comments'* i Examiner NOTE: This malfunction should be inserted while the CO is in the back of the MCB, defeating the Power Range Channel failure. If following the CO, continue with Step 8 of ER-NIS.3 on Page 18. SIM DRIVER Instructions: Operate T1rigger

1. 2 (CVC07 A, 100%, CVC23) NOTE: After operating Trigger #2, call up INSIGHT and set clds12 135 = 1.1. Indications Available:

• Letdown pressure will start to lower .
• Letdown flow (Fl-134) starts to oscillate

.

• A-19, LETDOWN LINE HI FLOW 70 GPM, will alarm .
• CNG-OP-1.01-1000, CONDUCT OF OPERATIONS NOTE: The CRS may contact the AO to investigate the status of PCV-135.

IF so, SIM DRIVER, as AO, report that the valve is FULLY OPEN, and that there are NO Air Leaks. HCO (Step 5.1 O.C.1) Use sound judgment when NOTE: The HCO will diagnose deciding to take manual actions a failure of the PCV-135 automatic actions in response to parameter Controller in AUTO, and place trends. Take manual actions when automatic the controller in MANUAL. actions do not occur. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# Page ------3 18 of 67 __ .,., Event

Description:

Time Pos .. HCO HCO co co co Power Range N41 Upper Detector fails LOW/Letdown Pressure Controller Failure Expected Actions/Behavior .. Comments (Step 5.1 O.C.2) Transients induced by the malfunction of an automatic system should be terminated by operator action to establish manual control with a proper demand signal. Unless an instrument indication or control action is demonstrated to be incorrect by checking multiple and diverse indications, the control shall remain in automatic. (Step 5.1 O.C.3) The need and intent to place NOTE: The HCO will a controller into manual operation should be communicate to the CRS that communicated to the CRS before taking this the PCV-135 controller is in action. MANUAL. ER-NIS.3, PR MAL.FUNCTION ATTACHMENT 1, N-41 DEFEAT Examiner NOTE: If following the CO, continue HERE. (Step 8) PLACE the UPPER SECTION DEFEAT switch (Detector Current Comparator-Miscellaneous Control & Indications drawer) to the PRN41 position AND VERIFY the following:

• Local light for CHANNNEL DEFEAT upper section is ILLUMINATED.

(Step 9) PLACE the LOWER SECTION DEFEAT switch (Detector Current Comparator-Miscellaneous Controls & Indications drawer) to PRN41 position AND VERIFY the following:

• Local light for CHANNEL DEFEAT lower section is ILLUMINATED.

(Step 10) PLACE the POWER MISMATCH BYPASS switch (Detector Current Comparator-Miscellaneous Controls & Indications drawer) to BYPASS PR N41 Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# Page 19 of 67 3 Event

Description:

Time(* Pos. co co co CO/ HCO Power Range N41 Upper Detector fails LOW/Letdown Pressure Controller Failure ,: E>e:pected Actions/Behavior comments (Step 11) PLACE the ROD STOP BYPASS switch (Detector Current Comparator-Miscellaneous Controls & Indications drawer) to BYPASS PR N41. (Step 12) PLACE the COMPARATOR CHANNEL DEFEAT switch (Comparator and Rate drawer) to N41 AND VERIFY the following:

• Local light for COMPARATOR DEFEAT is ILLUMINATED.

(Step 13) REMOVE the 118V 5A AC INSTR POWER fuses (Power Range N41 B drawer) AND VERIFY the following alarms (MCB) are ILLUMINATED:

• E-18, POWER RANGE LOSS OF DETECTOR VOLTAGE
• E-19, POWER RANGE HI RANGE CHANNEL ALERT 108%
• E-21, POWER RANGE OVERPOWER ROD STOP 103%A
• E-27, POWER RANGE LO RANGE NOTE: Normally LIT above CHANNEL ALERT 24% 24% power.
• E-28, POWER RANGE ROD DROP ROD STOP -5%/5 SEC (Step 13.1) VERIFY the following RED bistable lights (MCB) are ILLUMINATED:
• HI POW RANGE P-10 NC41M
• HI POW RANGE P-8 NC41N
• LO POW RANGE TRIP NC41P
• HI POW RANGE TRIP NC41R
• HI POW RANGE P-9 NC41S Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

4 Event# _3 _____ Page 20 of _6_7_""" Event

Description:

Time Pos. co co co co Power Range N41 Upper Detector fails LOW/Letdown Pressure Controller Failure **. ExpectedActions/Behavior IF any bistable above is NOT ILLUMINATED, THEN the channel may not be in the tripped condition. Further investigation is necessary to ensure ITS requirements are met. (Step 13.2) VERIFY the following status lights (Power Range N41 A drawer) are lit:

• CONTROL POWER ON
• LOSS OF DETECTOR VOLT
• OVERPOWER TRIP HIGH RANGE
• OVERPOWER ROD STOP
• OVERPOWER TRIP LOW RANGE
• POWER ABOVE PERMISSIVE P10
• POWER ABOVE PERMISSIVE P8
• POWER ABOVE PERMISSIVE P9
• ROD DROP
• DROPPED ROD BYPASS (Step 13.3) VERIFY the following status lights (Power Range N41 B drawer) are extinguished:
• INSTRUMENT POWER ON
• CHANNEL ON TEST (Step 14) NOTIFY l&C to INSTALL.jumpers NOTE: The CO may notify the across contacts 1-5 AND 4-8 of Power WCC/l&C.

Range relays NC 41 MX (both A train and B SIM DRIVER: as WCCS/l&C, train Protection Racks). This will remove N-acknowledge. Set REM 41 from the logic circuit for reinstating the PR NIS105 to INSTALLED to low power trip and the source ranges (P-10). complete jumper installation. (Step 15) INITIATE an A-52.4 on N-41. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# _3..__ ____ Page 21 of _6_7_-11 Event

Description:

Time Pos. co CRS co HCO co CRS Power Range N41 Upper Detector fails LOW/Letdown Pressure Controller Failure ,'"' ,'/,:iii I i ,, , I , <<, ' Expected Aptions/Behavior

Comments (Step 16) Go to step 6.5. NOTE

The CO will notify the CRS that Attachment N-41 Defeat is complete.

(Step 6.5) WHEN the appropriate channel defeat attachment is complete, THEN restore the following systems to AUTOMATIC as desired:

• STEAM DUMP
• ROD CONTROL NOTE: The HCO will place the Rods in AUTO.
• EH (Step 6.6) CHECK the following for required actions:
• Tech Spec Sections
• Section 3.3.1TABLE3.3.1-1 Functions 2a & b, 5, 6, 16b, 16c, 16d and 16e.
• Section 3.2.1 (SR 3.2.1.2)
• Section 3.2.2 (SR 3.2.2.2)
• Section 3.2.3 NOTE: N/A if< 50% power
• Section 3.2.4 NOTE: N/A if< 50% power
• TRM Sections
• Section 3.2.3 NOTE: N/A if< 50% power
• Section 3.2.4 NOTE: N/A if< 50% power TECHNICAL SPECIFICATION 3.3.1, REACTOR TRIP (RTS) INSTRUMENTATION CRS LCO 3.3.1 The RTS instrumentation for each Function (functions 2a, 2b, 5, 6, 1 Eib, 16c, 16d, 16e) in Table 3.3.1-1 shall be OPERABLE.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# 3 Page 22 of 67 ---11 Event

Description:

Time Pos. Power Range N41 Upper Detector fails LOW/Letdown Pressure Controller Failure ' l Expected Actions/Behavior

'<"'< ,,,: Comments APPLICABILITY According to Table 3.3.1-1.

CONDITION REQUIRED COMPLETION ACTION TIME A. One or more A.1 Enter the Immediately Functions Condition with one reference in channel Table inoperable. 3.3.1-1 for the channel(s). D. As required D.1 Place 6 hours by Required channel in Action A.1 trip. and referenced by Table 3.3.1-1. S. As required S.1 Verify 1 hour 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 likely conduct a Plant Status Brief. At the discretion of the Lead Examiner move to Event #4. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# 4 Page 23 of 67 ......;..____

---

;1 Event

Description:

PORV Leak/Block Valve Failure Subsequently, Pressurizer PORV-431 C will fail partially open. The operator will respond in accordance with AR-F-18, PRZR PORV OUTLET HI TEMP 145°F, and enter AP-PZR.1, Abnormal Pressurizer Pressure. When the operator attempts to isolate the PORV, the Block Valve will fail to shut fully resulting in a 2-5 gpm leak into the PRT. The crew may implement AP-RCS.1, Reactor Coolant Leak, and prepare to make a Containment entry. Ultimately, the crew will be directed to take the unit line. The operator will address Technical Specification 3.4.11, Pressurizer PORVs, 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits, as well as TRM 3.4.3, Anticipated Transients Without Scram (ATWS) Mitigation. Although the crew will address Technical Specification 3.4.13, RCS Leakage, it is likely that at the current leakrate, this specification will be met. SIM DRIVER Instructions: Operate Trigger #3 (PZROSB, 5%, Throttled back to 2% after the operator attempts to close the PORV Block Valve) Indications Available:

• MCB Annunciator F-19, PRZR PORV OUTLET HI TEMP 145°F
• MCB Annunciator F-18, PRZR SAFETY VAL.VE HI TEMP 145°F
• Pressurizer Pressure decreases slowly
• PRT Pressure (Pl-440A) increases
• PCV-431 Chas dual indication
• Time

..... l,;f coffiments.

. ; ,.1.1. AR-F-19, PRZR PORV OUTLET HI TEMP 145°F CRS (Step 1) IF Pressurizer pressure is lowering, NOTE: The HCO will .* THEN GO TO AP-PRZR.1, ABNORMAL recognize that Pzr Pressure PRESSURIZER PRESSURE. is lowering because of the Open PORV. HCO (Step 2) Check PRZR PORV outlet NOTE: The HCO may temperature, Tl-438. attempt to close PCV-431 C, in accordance with A-503.1 . Upon recognizing that PCV-431 C did NOT close, the HCO will attempt to close MOV-515. HCO (Step 3) Check PRT parameters. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# _4 _____ Page 24 of _6_7_1 Event

Description:

PORV Leak/Block Valve Failure Time

, Expected Actions/Behayior:

\' .* ** .. *.Comments p:, .. HCO (Step 4) Check Containment temperature. CRS (Step 5) Start OR swap Containment Recirc Fans per Shift Manager directions. CRS (Step 6) Refer to ITS LCO 3.4.11 and 3.4.13. NOTE: The CRS will go to AP-PRZR.1. SIM DRIVER Note: When the operator attempts to close the PORV Block Valve, Trigger #30 will activate, failing the valve at mid-position. Throttle PZR0513 back to 2°/o. Indications Available:

• PORV Block Valve Red status light LIT
• PORV Block Valve Green status light LIT
• Pressurizer Pressure continues to decreases slowly Examiner NOTE: If the crew enters AP-RCS.1 at any time, proceed to the actions on Page 28. AP-PRZR.1, ABNORMAL PRESSURIZER PRESSURE HCO (Step 1) Check PRZR Pressure:
• All 4 narrow range channels

-APPROXIMATELY EQUAL

• All 4 narrow range channels

-TRENDING TOGETHER HCO (Step 2) Check Reactor Power -ST ABLE HCO (Step 3) Check PRZR Pressure:

• Pressure

-LESS THAN 2235 PSIG

• Pressure

-GREATER THAN 2000 PSIG Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# 4 Page 25 of _67_-o Event

Description:

PORV Leak/Block Valve Failure Time .. ,Expected Actions/Behavior Comments r HCO (Step 4) Check PRZR heater Status:

• PRZR proportional heater breaker -CLOSED
• PRZR heater backup group -ON NOTE: All Pzr Heaters will be energized.

HCO (Step 5) Verify Normal PRZR Spray Valves -CLOSED

• AOV-431A
• AOV-4318 HCO (Step 6) Check PRZR Pressure Controller, 431 K, Demand -LESS THAN 50°/c, HCO (Step 7) Check PRZR PORVs:
• PORVs -CLOSED NOTE: PCV-431C will be in mid-position.
• (Step 7a RNO) Manually close PORVs NOTE: PORV will not close. IF any valve can NOT be closed, THEN manually close the associated block valve.
• MOV-515 for PCV-431 C NOTE: The HCO will attempt to close the Block Valve unsuccessfully (if not attempted earlier).

HCO * (Step 7 Continued) Annunciator F-19, NOTE: F-19 is LIT. PRZR PORV OUTLET HI TEMP 145°F -EXTINGUISHED

• (Step 7b RNO) IF PORV leakage is indicated, THEN perform the following:

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# _4 _____ Page 26 of 67 Event

Description:

PORV Leak/Block Valv1e Failure .* Expected .Actions/Behavior Time Pos .... ) *;, . . . . . )

• Close PORV block valv1es one at a time AND check if pressure stabilizes.
• MOV-515 NOTE: The HCO will attempt to close the Block Valve unsuccessfully (if not attempted earlier).

CRS * (Step ?c Go to step 9) HCO (Step 9) Check PRZR Safety Valves: Position indicator -LESS THAN 0.1 INCH Annunciator F-18, PRZR SAFETY VLV OUTLET HI TEMP 145°F -EXTINGUISHED Annunciator AA-13, PRESSURIZER SAFETY VAL VE POSITION -EXTINGUISHED HCO (Step 10) Check AUX Spray Valve, AOV-296 -CLOSED. HCO (Step 11) Check PRZR Pressure Control Restored:

• Pressure

-TRENDING TO PSIG NOTE: The Pressurizer Pressure is expected to be rising by this time. CRS

• Go to Step 16 . HCO (Step 16) Check PRT Indications:
• Level -BETWEEN 61 % AND 84%
• Pressure-APPROXIMATELY 1.5 PSIG NOTE: The PRT pressure AND STABLE will be rising.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# Page 27 of 67 4 Event

Description:

PORV Leak/Block Valve Failure *. *** '..:Expected Actions/B.ehavior

• .. Time Pos ... ,. Comments.
  • • @ I.* . '* .... HCO (Step 16.b RNO) Open PRT vent, AOV-527 NOTE: The HCO will until PRT 1.5 PSIG AND ST ABLE pressure attempt to control PRT is approximately 1.5 psig. IF PRT pressure pressure.

will NOT lower, THEN open PRT drain valve, AOV-526, to reduce pressure until PRT pressure is approximately 1.5 psig. HCO (Step 16.c) Temperature -AT CNMT AMBIENT TEMPERATURE AND STABLE HCO (Step 17) Establish PRZR Pressure Control In Auto:

• Verify 431 K in AUTO
• Verify PRZR spray valves in AUTO
• Verify PRZR heaters restored:
• PRZR proportional heaters breaker -CLOSED
• PRZR backup heaters breaker -RESET, IN AUTO CRS/ (Step 18) Evaluate MCB Annunciator Status HCO/ (Refer to AR Procedures) co CRS (Step 19) Notify Higher Supervision CRS (Step 20) Notify Reactor Engineer for NOTE: The CRS will call Transient Monitoring Program RE. SIM DRIVER: as RE, acknowledge.

NOTE: IF crew does not enter AP-RCS.1, then PROMPT (as Ops Management) that plant should be S/D per AP-TURB.5 at 1 %/minute. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# 4 -----Page 28 of 67 Event

Description:

PORV Leak/Block Valve Failure Time *eos .. Expected Action*s/Behavi9r

+ \. ..c Com.ments

.* * . .

• NOTE: The following steps assumes CRS enters AP-RCS.1.IF AP-TURB.5 entry, Move forward to Event 5. AP-RCS.1, REACTOR COOLANT LEAK HCO (*Step 1) Monitor PRZR Level -ST ABLE AT NOTE: The HCO may raise PROGRAM LEVEL Charging Pump Speed. HCO (Step 2) Check VCT Makeup System:
• Verify VCT level -GREATER THAN 5%
• Ensure the following:
• RMW mode selector switch in AUTO
• RMW control armed -RED LIGHT LIT
• Check VCT level:
• Level GREATER THAN 20% OR
• Level -STABLE OR RISING HCO (Step 3) Check If RCS Leakage In CNMT: NOTE: The leakage is into the PRT.
• Check CNMT radiation monitors

-NORMAL

• R-2
• R-7
• R-10A
• R-11
• R-12
• CNMT sump A pump run frequency-NORMAL (Refer to RCS Daily Leakage Log)

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# 4 -----Page 29 of 67 Event

Description:

PORV Leak/Block Valve* Failure Time* PC>s .. Expected Actions/Behavior ,,,; Comments' <> N' ' ' ,' < < < ' CRS (Step 4) Dispatch AO to AUX BLDG To NOTE: The CRS will Investigate For CVCS Leak (locked area dispatch an AO. keys required) SIM DRIVER: as AO, acknowledge. HCO (Step 5) Check For Leak To CC\N System: NOTE: The leakage is into the PRT.

• CCW surge tank level -APPROXIMATELY 50% AND STABLE
• CCW radiation

monitor, R-1-1 -NORMAL HCO (Step 6) Check CVCS Conditions:

NOTE: The leakage is into the PRT.

• Normal letdown -IN SERVICE
• Letdown indication:
• Letdown flow -APPROXIMATELY 40 GPM (60 GPM IF AOV-202 OPEN)
• Low pressure L TON pressure

-APPROXIMATELY 250 PSIG

• Letdown pressure control valve, PCV-135, demand APPHXIMATELY 35% OPEN (40% OPEN IF AOV-202 OPEN) HCO
• Charging indication:
• Seal injection flows -GREATER THAN 6 GPM AND STABLE
• RCP Labyrinth seal D/Ps -GREATER THAN 15 INCHES AND APPROXIMATELY EQUAL
• Charging pump discharge pressure

-GREATERTHAN RCS PRESSURE

• AUX BLDG radiation levels -NORMAL
• R-4
• R-9
• R-10B Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

4 Event# _4 _____ Page 30 of 67 Event

Description:

PORV Leak/Block Valve Faulure Time Pos. Expected Actions/Behavior / /, *Comments i"

• R-13
• R-14 HCO (Step 7) Check PRT Indications:

NOTE: The leakage is into the PRT.

• Level -BETWEEN 61 % AND 84%
• Pressure-APPROXIMATELY

'1.5 PSIG NOTE: PRT pressure is AND STABLE increasing.

• Temperature

-AT CNMT AMBIENT TEMPERATURE AND STABLE HCO (Step 7 RNO) Check tailpipe and valve NOTE: Tailpipe leakoff temperatures for the PRZR safety temperatures are high. valves and PORVs for indication of leakage. IF no PORV or safety valve leakage is NOTE: There is PORV indicated, THEN ....... leakage indicated into the PRT. HCO (Step 8) Check SIGs for Leakage:

• Air ejector radiation monitors

-NORMAL

• R-15
• R-47
• R-48
• SIG blowdown radiation monitor (R-19)-NORMAL
• Steamline radiation monitors

-NORMAL

• R-31
• R-32
• SIG sample activity

-NORMAL (Check with Chemistry Department for normal) HCO (Step 9) Check SI Accumulator Lev13ls -NOTE: The leakage is into STABLE the PRT. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# 4 Page 31 -----of 67 Event

Description:

PORV Leak/Block Valve Failure Time Pos. ** Expected Actions/Behavior

• *comments
  • ' ' v, HCO (Step 10) Check RCP Seal Leakoff Flows:
• Leakoff flows -WITHIN THE NORMAL OPERATING RANGE OF FIG-4.0, FIGURE RCP SEAL LEAKOFF
• Leakoffflows

-STABLE HCO (Step 11 ) check RCDT Leak Rate -NOTE: The leakage is into NORMAL (Refer to RCS Daily Leakage the PRT. Loq and PPCS point ID L 1003) HCO (Step 12) Check Valve Leakoff Temperatures -NORMAL (Refer to Pressurizer Valve Leak-Off Temperature Record HCO (Step 13) Check Normal or Excess Letdown NOTE: Normal Letdown is in -IN SERVICE service. HCO (Step 14) Establish Stable Plant Conditions:

• PRZR level -TRENDING TO PROGRAM IN AUTO CONTROL
• Check PRZR pressure

-TRENDING TO NOTE: Pressurizer Pressure 2235 PSIG IN AUTO is trending down. * (Step 14b RNO) Control PRZH pressure by one of the following:

• 431 Kin MANUAL
• Manual control of PRZR heaters and sprays
• IF pressure can NOT be controlled manually THEN refer to AP-PHZR.1, ABNORMAL PRESSURIZER PRESSURE.

HCO (Step 15) Establish Control Systems In Auto

• Verify 431 Kin AUTO Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

4 Event# 4 -----Page 32 of 67 Event

Description:

PORV Leak/Block Valve Failure Time/ *.*. Pos.* :*. Expected Actions/Behavior .. Comments ,, p >> ' ' ... * (Step 15a RNO) Place 431 K in AUTO, if desired.

• (Step 15 Continued)

Verify PRZR spray valves in AUTO

• Verify PRZR heaters restored:
• PRZZR proportional heaters breaker -CLOSED
• PRZR backup heaters breaker -RESET, IN AUTO
• Verify one charging pump in AUTO HCO/ (Step 16) Evaluate MCB Annunciator Status co (Refer to AR Procedures)

CRS (Step 17) Evaluate RCS Leakage:

• Leakage within limits (Refer to leakage NOTE: The leakage is > surveillance sheet and ITS section than that allowed by TS. 3.4.13) * (Step 17a RNO) IF leak NOT isolable, SIM DRIVER: As the Shift but PRZR level and seal injection can be Manager, direct the CRS to maintained, THEN shut the plant down shutdown the plant using (Refer to 0-2.1, NORMAL SHUTDOWN AP-TURB.5 at 1 %/minute.

TO HOT SHUTDOWN or AP-TURB.5, RAPID LOAD REDUCTION).

• (Step 17 Continued)

Leak location identified

• (Step 17b RNO) Return to Step 1 .

Appendix D Operator Action Form ES-D-2 Op Test No.: N2D14-301 Scenario# 4 Event# Page 33 -----4 of 67 Event

Description:

PORV Leak/Block Valve Failure Time Pos .. *** Expected Actions/Behavior .. ' ' ' . . Cpmments NOTE: The CRS will likely conduct a Plant Status Brief. NOTE: The CRS will go to AP-TURB.5. NOTE: The CO may notify the eENG Generation Dispatch. SIM DRIVER: as CENG Generation

Dispatch, acknowledge.

NOTE: The CO may notify the RG&E Eee. SIM DRIVER: RG&E ECC, acknowledge. NOTE: The CRS may notify the wee. SIM DRIVER: as wees, acknowledge. Examiner NOTE: The CRS may NOT check TS during the plant transient. If NOT, eRS Examiner check TS after the scenario is complete. TECHNICAL SPECIFICATION 3.4.1, RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING (DNB) LIMITS CRS RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits CRS LCO 3.4.1 RCS DNB parameters for NOTE: According to Section pressurizer

pressure, RCS average 2.10.1 of the COLR, the Przr temperature, and RCS total flow rate shall be Pressure shall be :2:2205 within the limits specified in the COLR. psig. APPLICABILITY:

MODE 1 ACTIONS Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# Page 34 -----4 of 67 Event

Description:

PORV Leak/Block Valve Failure Time< Pos., : ** r Conl"rnents x ... CONDITION REQUIRED COMPLETION ACTION TIME A. One or more A.1 Restore RCS 2 hours RCS DNB DNB parameters parameter(s) not within to within limit. limits. TECHNICAL SPECIFICATION 3.4.11, PRESSURIZER POWER OPERATED RELIEF VALVES (PORVs) CRS LCO 3.4.11 Each PORV and associated block valve shall be OPERABLE. CRS APPLICABILITY MODES 1, 2, and 3. CONDITION REQUIRED COMPLETION ACTION TIME C. One block C.1 Place 1 hour valve associated inoperable. PORVin manual control. AND C.2 Restore 7 days block valve to OPERABLE status. TECHNICAL SPECIFICATION 3.4.13, RCS OPERATIONAL LEAKAGE CRS LCO 3.4.13 RCS operational LEAK.AGE NOTE: The CRS will shall be limited: evaluate this Tech Spec but conclude the LCO is MET {Identified leakrate is 2-5 gpm).

• No pressure boundary LEAKAGE;
• 1 gpm unidentified LEAKAGE;
• 10 gpm identified LEAKAGE; and Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

4 Event# _4..-_________ Page 35 of 67 Event

Description:

PORV Leak/Block Valve Failure . Expected Actions/Behavior Comments Time Pos. .<

• 150 gallons per day primary to secondary LEAKAGE through any one steam generator (SG ). APPLICABILITY MODES 1, 2, 3, and 4. CONDITION REQUIRED COMPLETION ACTION TIME A. RCS A.1 Reduce 4 hours operational LEAKAGE LEAKAGE to within not within limits. limits for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE.

TECHNICAL REQUIREMENT 3.4.3, ANTICIPATED TRANSIENTS WITHOUT SCRAM (ATWS) MITIGATION CRS TR 3.4.3 ATWS Mitigation shall be OPERABLE as follows:

• Each PORV shall be capable of automatic actuation and each block valve shall be open;
• Manual rod insertion shall be OPERABLE; and
• ATWS Mitigation System Actuation Circuitry (AMSAC) shall be OPERABLE.

APPLICABILITY MODE 1 > 45% RTP. CONDITION REQUIRED COMPLETION ACTION TIME Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# 4 ------Page 36 of 67 Event

Description:

PORV Leak/Block Valve Failure ' .* EXPE!£ted Actions/Behavior

• . *' comments

.. Ji me .. f>os. ' ' i'>> ' A. One or more A.1 Declare Immediately PORV ATWS automatic mitigating flow path capability inoperable. inoperable. When the crew starts the downpower move to Event #5 Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# 5 Page 37 -----of 67 Event

Description:

Downpower/Failure of Turbine Control/EHC The operator will take the unit off line in accordance with AP-TURB.5, Rapid Load Reduction During the downpower, the Main Turbine will fail in automatic

control, and shift to manual control.

The operator will identify that the load reduction has been stopped, and use manual control of the turbine to restart and continue the downpower. The remainder of the downpower will need to be accomplished using manual control of the Turbine. SIM DRIVER Instructions: NA Indications Available: NA . Time. Pos. :* Expected Actions/Behavior

<Comments

' . . . ,, c ; ' , . .. AP-TURB.5, RAPID LOAD REDUCTION Examiner NOTE: The crew may perform ATT-23.0 based on the Note prior to Step 1 of AP-TURB-5. If so, Examiner following CO continue, while other Examiners continue with Step 1 of AP-TURB.5 on Page 38. ATT-23.0, ATTACHMENT TRANSFER 4160V LOADS co (Step 1) Place Bus 12A-Bus 11A TIE SYNCHROSCOPE to ON. co (Step 2) Close BUS 12A -BUS 11 A TIE 4160V. co (Step 3) Place BUS 12A-BUS 11A TIE SYNCHROSCOPE to OFF. co (Step 4) Open BUS 11 A NORMAL FEED 4160V. co (Step 5) Place BUS 11 B -BUS 12B TIE SYNCHROSCOPE to ON. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# 5 -----Page 38 of 67 Event

Description:

Down power/Failure of Turbine Control/EHC ' Pos. , *. \t Expected Actions/Behavior Comn:ients

• * .. .. **. co (Step 6) Close BUS 11 B -BUS 12B Tl E 4160V. co (Step 7) Place BUS 11B -BUS 12B TIE SYNCHROSCOPE to OFF. co (Step 8) Open BUS 11 B NORMAL FEED 4160V. co (Step 9) Reset alarms L-20 AND L-28, locally NOTE: The BOP will contact in the Relay Room Addition.

the AO to perform this action. SIM DRIVER: as AO, acknowledge and will need to insert: REM-EDS49=RESET REM-EDS50=RESET AP-TURB.5, RAPID LOAD REDUCTION Examiners NOTE: Examiners following HCO and CRS, continue HERE. NOTE: The CRS will conduct a load reduction brief. HCO (Step 1) Initiate Load Reduction

• Verify rods in AUTO
• Reduce turbine load in Auto as follows:

co

• Place Turbine EH Control in OPER PAN., IMP PRESS IN, if desired.
• Select desired rate on thumbwheel NOTE: The CO will select 1%/Minute.
• Reduce the setter to the desired load
• Depress the GO button NOTE: The CO will start the load decrease.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# Page 39 -----5 of 67 Event

Description:

Downpower/Failure of Turbine Control/EHC Time Pos." , Expected Actions/Behavior Comments \,' ' ,, ' ' HCO

• Initiate boration at the rate determined in NOTE: The HCO will initiate OPG-REACTIVITY-CALC.

a 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
• Match Tavg and Tref
• Compensate for Xenon HCO (*Step 4) Monitor PRZR Pressure

-NOTE: Pressurizer Pressure TRENDING TO 2235 PSIG IN AUTO may be trending down. HCO (Step 4 RNO) Control PRZR pressure by one of the following:

• 431 Kin MANUAL
• Manual control of PRZR heaters and sprays If PRZR pressure can NOT be controlled NOTE: This procedure has manually, THEN refer to AP-PRZR.1, already been completed.

ABNORMAL PRESSURIZER PRESSURE. co (*Step 5) Monitor MFW Regulating Valves -RESTORING SIG LEVEL TO 52% IN AUTO HCO (*Step 6) Monitor PRZR Level -THENDING TO PROGRAM IN AUTO CONTROL Appendix D Operator Action Form ES-0-2 Op Test No.: N2014-301 Scenario# 4 Event# Page 40 -----5 of 67 Event

Description:

Downpower/Failure of Turbine Control/EHC Time Pos. ./ "., Expected Actions/Behavior Comments I 'o, ,, ',,, ,: SIM DRIVER Instructions: Operate Trigger#4 (TUR09D, 100%, OVR-TUROSO = OFF, OVR-TURSP =ON) Indications Available:

• Turbine Load decrease stops
• EH valve control status lights:
• OPER PAN -DARK
• IMP PRESS OUT -DARK
• TURB MANUAL -LIT
• MANUAL CONTROL VAL VE LOWER -LIT
• MANUAL CONTROL VALVE FAST-LIT
• MANUAL CONTROL VALVE RAISE-LIT
• Reference and Setter Control Valve Position are equalized NOTE: Based on the changing plant condition, the CRS may re-enter AP-TURB.5. AP-TURB.5, RAPID LOAD REDUCTION HCO (Step 1) Initiate Load Reduction
• Verify rods in AUTO
• Reduce turbine load in Auto as follows:

co * (Step 1 b RNO) IF Auto control is inoperable, THEN reduce turbine load in manual at the desired rate. At the discretion of the Lead Examiner move to Events #6-7. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# _6_&_7 ___ Page of _6_7_1 Event

Description:

Pzr Steam Space Water Return Isolation CIV Fails in AUTO When the plant is at approximately 40% power, the piping leading to the failed PORV will fail so that a vapor space Small Break LOCA occurs. The plant will trip and Safety Injection will be actuated, and the operator will enter E-0, Reactor Trip or Safety Injection. On the plant trip Containment Isolation Valve MOV-313, the Seal Water Return Line CIV, will fail to close automatically, requiring that the operator manually close this valve. The operator will transition from E-0 to E-1, Loss of Reactor or Secondary

Coolant, and then into ES-1.2 Post-LOCA Cooldown and Depressurization.

While in ES-1.2, an Orange Path may occur on the RCS Integrity Critical Safety Function Status Tree. The scenario will terminate at Step 14 of ES-1.2, after the crew has demonstrated the ability to evaluate/perform the SI flow reduction

sequence, or upon transition to FR-P.1, Response to Imminent Pressurized Thermal Shock Condition.

SIM DRIVER Instructions: Operate Trigger #5 (PZR07, 89,0000) Indications Available:

• Pressurizer Pressure decreases at a faster rate
• Pzr level initially decreases and then starts to rise
• PRT pressure increases rapidly and then equalizes with Containment Pressure

" Expected

• * *. " . Time
• . Comments' Examiner NOTE: RCS pressure will drop to within 210 psig [240 psig Adverse Containment]

of Maximum SG Pressure 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: E-0, REACTOR TRIP OR SAFETY INJECTION HCO (Step 1) Verify Reactor Trip: Immediate Action

• At least one train of reactor trip breakers

-OPEN

• Neutron flux -LOWERING
• MRPI indicates

-ALL CONTROL AND SHUTDOWN RODS ON BOTrOM Appendix D Operator Action Form ES-0-2 Op Test No.: N2014-301 Scenario# 4 Event# _6_&_7 ___ Page of _6_7_1 Event

Description:

Time Pos.'* co co HCO/ co HCO/ co HCO Pzr Steam Space Break/Seal Water Return Isolation CIV Fails in AUTO . 1Expected

• h Comme'nts

. : . (Step 2) Verify Turbine Stop Valves -Immediate Action CLOSED (Step 3) Verify Both trains of AC Emergency Immediate Action Buses

• Bus 14 and Bus 18
• Bus 16 and Bus 17 (Step 4) Check if SI is Actuated:

Immediate Action

• Any SI Annunciator

-LIT

• SI sequencing

-BOTH TRAINS STARTED Foldout Page NOTE: The crew will monitor these conditions throughout the performance of E-0. RCP TRIP CRITERIA NOTE: This condition is expected to be met.

• IF BOTH conditions listed below occur, THEN trip both RCPs: 0 SI pumps -AT LEAST TWO RUNNING 0 RCS pressure minus maximum SIG pressure

-LESS THAN 210 osi [240 psi adverse Cl\IMT] LOSS OF SW CRITERIA AFW SUPPLY SWITCHOVER CRITERION SFP COOLING CRITERIA (*Step 5) Verify CNMT Spray Not RBquired: NOTE: The Containment Pressure is expected to be ::::::2 psig and rising slowly.

• Annunciator A-27, CNMT SPRAY EXTINGUISHED Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

4 Event# _6_&_7 ___ Page of _6_7_1 Event

Description:

. Time: Pos. co Pzr Steam Space Break/S1eal Water Return Isolation CIV Fails in AUTO ExpectecfActions/Behavior

• 'Comments
• CNMT pressure

-LESS THAN 28 PSIG (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-0. Examiner following operator performing ATT-27.0 continue below. Examiner following operator NOT performing ATT-27.0 continue at page 47. E-0, REACTOR TRIP OR SAFETY INJECTION, ATTACHMENT 27.0, ATTACHMENT AUTOMATIC ACTION VERIFICATION HCO/ (Step 1) Verify SI and RHR Pumps Running: co

• All SI pumps -RUNNING
• Both RHR pumps -RUNNING HCO/ (Step 2) Verify CNMT RECIRC Fans co RUNNING:
• All fans RUNNING
• Charcoal filter dampers green status lights -EXTINGUISHED HCO/ (Step 3) Check If Main Steamlines Should Be co Isolated:
• Any MSIV -OPEN
• Check CNMT pressure

-LESS THAN 18 PSIG

• Check if ANY main should be isolated Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

4 Event# 6&7 Page 67 Event

Description:

rime Pos. HCOI co HCOI co HCOI co Pzr Steam Space Break/Seal Water Return Isolation CIV Fails in AUTO ;Expectea . . Comments .

• Low Tavg (545°F) AND high steam flow (0 .5x106 lb/hr) from either SIG OR
• High-High steam flow (4.4x106 lb/hr) from either SIG * (Step3c RNO) Go to Step 4 . (Step 4) Verify MFW Isolation:
• MFW pumps -TRIPPED
• MFW Isolation valves -CLOSED
• SIG A, AOV-3995
• SIG B, AOV-3994
• SIG blowdown and sample valves -CLOSED (Step 5) Verify At Least Two SW Pumps -RUNNING (Step 6) Verify Cl and CVI:
• Cl and CVI annunciators

-LIT

• Annunciator A-26, CNMT ISOLATION
• Annunciator A-25, CNMT VENTILATION ISOLATION
• (Step 6 Continued)

Verify Cl and CVI NOTE: MOV-313 Status valve status lights -BRIGHT light is NOT bright. * (Step 6b RNO) Manually close affected NOTE: The HCO will Cl and CVI valve(s). manually close MOV-313. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# _6_&_7 ___ Page _6_7 __ 11 Event

Description:

Time 1* .. Pos. Pzr Steam Space Break/Seal Water Return Isolation CIV Fails in AUTO _:--,", ,p' *. Comments IF valve(s) can NOT be closed from NOTE: MOV-313 can be the MCB, THEN ..... closed. CRITICAL TASK 2. Close the Seal Water Return Containment Isolation Valve before transition out of E-0. Safety Significance: Failure to close at least one Containment Isolation Valve on each critical penetration under the postulated conditions when it is possible to do so, constitutes mis-operation leading to degradation of the Containment Barrier. Failure to take this action leads to an unnecessary release of fission products to the auxiliary

building, increasing the potential for release to the environment, and reducing accessibility to vital equipment within the Auxiliary Building.

Higher radiation levels within the Auxiliary Building will result in a degradation of ALARA principles.

• (Step 6 Continued)

CNMT RECIRC fan coolers SW outlet valve status lights -BRIGHT

• FCV-4561
• FCV-4562
• Letdown orifice valves -CLOSED
• AOV-200A
• AOV-2008
• AOV-202 co (Step 7) Check CCW System Status:
• Verify CCW pump-AT LEAST ONE RUNNING co (Step 8) Verify SI And RHR Pump Flow:
• SI flow indicators

-CHECK FOR FLOW

• RHR flow indicator

-CHECK FOR FLOW Appendix D Operator Action Form ES-0-2 Op Test No.: N2014-301 Scenario# 4 Event# _6_&_7 ____ Page of Event

Description:

Pos.;"* co co co Pzr Steam Space Break/Seal Water Return Isolation CIV Fails in AUTO . .. ... .. .. . . . . . . . .. .. . .. .. comments .. Actions/Behayior* ...

• 1*** ... * (Step 8b RNO) IF RCS pressure less than 150 psig manually start pumps and align valves. IF NOT, THEN to Step 9. (Step 9) Verify SI Pump And RHR Pump Emergency Alignment:
• RHR pump discharge to Rx vessel deluge -OPEN
• MOV-852A
• MOV-8528
• Verify SI pump C -RUNNING
• Verify SI pump A -RUNNING
• Verify SI pump B -RUNNING
• Verify SI pump C discharge valves -OPEN
• MOV-817A
• MOV-8178 (Step 10) Verify GREATS Actuation:
• At least one damper in each flowpath

-CLOSED

• Normal Supply Air
• Normal Return Air
• Lavatory Exhaust Air
• GREATS fans-BOTH RUNNING (Step 11) Verify Cl and CVI During a Fire Event
• A confirmed fire has occurred in the control complex or cable tunnel (fire systems S05, S06, SOB, Z05, Z:18, or Z19).

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# _6_&_7 ___ Page of _6_7_1 Event

Description:

Time Pps .. co HCO HCO HCO Pzr Steam Space Break/Seal Water Return Isolation CIV Fails in AUTO ***.. .: * .Expegted Actions/Behavior ... Comments .. * (Step 11 RNO) Go to END E-0, REACTOR TRIP OR SAFETY INJECTION Examiner following operator NOT performing ATT-27.0 continue HERE. (Step 7) Verify Both MDAFW Pumps RUNNING (Step 7 RNO) Manually start both MDAFW NOTE: ONLY the A pumps. MDAFW Pump will be running. IF less than 2 MDAFW pumps are running, THEN manually open TDAFW pump steam supply valves.

• MOV-3505A
• MOV-3504A NOTE: The CO will start the TDAFW Pump. (Step 8) Verify AFW Valve Alignment:
• AFW flow-INDICATED TO BOTH SIG(s)
• AFW flow from each MDAFW pump LESS THAN 230 GPM (*Step 9) Monitor Heat Sink:
• Check SIG narrow range leved GREATER THAN 7% [25% adverse CNMT] in any SIG
• Check SIG narrow range level BOTH SIG LESS THAN 50%
• Control feed flow to maintain SIG narrow range level between 7% [25%. adverse CNMT] and 50%.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# _6.o...;..&_7 ___ Page of _6_7 __ 11 Event

Description:

" Time* HCO CRS HCO HCO co Pzr Steam Space Break/S1:tal Water Return Isolation CIV Fails in AUTO .. Expected Actions/Behavior .*.... Comments (Step 10) Check If TDAFW Pump Can Be Stopped:

• Both MDAFW pumps -RUNNING NOTE: ONLY the A MDAFW Pump will be running.

(Step 10 a RNO) Go to Step 11. (Step 11) Check CCW Flow to RCP thermal Barriers:

• Annunciator A-7. RCP 1A CCW RETURN HI TEMP OR LOW FLOW -EXTINGUISHED
• Annunciator A-15, RCP 1B CCW RETURN HI TEMP OR LOW FLOW EXTINGUISHED

(*Step 12) Monitor RCS Tavg -STABLE AT NOTE: Tavg is expected to OR TRENDING TO 547°F be less than 54 7°F and lowering. (Step 12 RNO) IF temperature less than 547°F and lowering, THEN perform the following:

• Stop dumping steam .
• Ensure reheater steam supply valves are closed.
• IF cooldown continues, THEN control NOTE: Adverse total feed flow between 200 gpm to 230 Containment may exist at gpm until narrow range level than this time. 7% [25% adverse CNMT] in at least one SIG.
• WHEN SIG level greater than 7% [25% adverse CNMT] in one SIG, THEN limit feed flow to that required to maintain level in at least one SIG.
• IF cooldown continues, THEN close both NOTE: The CO will CLOSE MS IVs. both MSIVs.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# _6_&_7 ___ Page _6_7---11 Event

Description:

Time <:eos. HCO HCO CRS Pzr Steam Space Break/Seal Water Return Isolation CIV Fails in AUTO :t:.<< Expected Actions/Beha:vior . Comments ... * *;:. (Step 13) Check PRZR PORVS And Spray Valves:

• PORVs -CLOSED NOTE: PCV-431 C is still OPEN. * (Step 13a RNO) IF PRZR pressure less than 2335 psig, THEN manually close PO RVs. IF any valve can NOT be closed, THEN manually close its block valve.
• MOV-516 for PCV-430
• MOV-515 for PCV-431 C NOTE: MOV-515 is still OPEN. IF block valve can NOT be closed, THEN go to E-1, LOSS OF REACTOR OR SECONDARY

COOLANT, Step 1. NOTE: The CRS will go to E-1. The CRS will conduct an alignment brief. E-1, LOSS OF REACTOR OR SECONDARY COOLANT HCO/ Foldout Page NOTE: The crew will co monitor these conditions throughout the performance of E-0. RCP TRIP CRITERIA NOTE: This condition is expected to be met.

• IF BOTH conditions listed below occur, THEN trip both RCPs: 0 SI pumps -AT LEAST TWO RUNNING 0 RCS pressure minus maximum NOTE: Adverse SIG pressure

-LESS THAN 210 Containment is likely to exist psi [240 psi adverse CNMT] at this time. LOSS OF SW CRITERIA Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# _6_&_7 ___ Page of _6_7_1 Event

Description:

Time Pos. HCO Pzr Steam Space Break/Seal Water Return Isolation CIV Fails in AUTO eJ(pectecl Comments ,' , ,, ', SI REINITIATION CRITERIA SI TERMINATION CRITERIA SECONDARY INTEGRITY CRITERIA E-3 TRANSITION CRITERIA COLD LEG RECIRCULATION SWITCHOVER CRITERION AFW SUPPLY SWITCHOVER CRITERION (Step 1) Monitor RCP Trip Criteria:

• RCP status -ANY RCP RUNNING
• SI pumps-AT LEAST TWO RUNNING
• RCS pressure minus maximum SIG pressure

-LESS THAN 210 psi [240 psi adverse CNMT]

• Stop both RCPs NOTE: If the RCPs have ,,, NOT been stopped prior to this step, they will be stopped here. CRITICAL TASK 1. 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 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 Page 41 = minutes. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# _6_&_7 ___ Page of _6_7---t1 Event

Description:

Time HCOI co co HCO HCO Pzr Steam Space Break/Seal Water Return Isolation CIV Fails in AUTO Expected Actions/Befiavior ' . Comments'* .v (Step 2) Check If SIG Secondary Side Is Intact:

• Pressure in both SIGs -ST ABLE OR RISING
• Pressure in both SIGs -GREATER THAN 110 PSIG (*Step 3) Monitor Intact SIG 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% (Step 4) Monitor If Secondary Radiation Levels Are Normal
• Steamline radiation monitor and R-32)
• Request Chem Tech sample SIGs for NOTE: The CRS may activity contact Chemistry.

SIM DRIVER: as Chemistry, acknowledge. (*Step 5) Monitor PRZR PORV Status:

• Power to PORV block valves -AVAILABLE
• PORVs -CLOSED NOTE: PCV-431C is still OPEN. * (Step Sb RNO) IF PRZR pressure less than 2335 psig, THEN manua1lly close PO RVs.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# _6_&_7 ___ Page of _6_7_-11 Event

Description:

Time. Pos. : HCO HCO HCO co HCO/ co Pzr Steam Space Break/Seal Water Return Isolation CIV Fails in AUTO : : . ,, ,,.,,,, ,, ', ' ': ', ' :; ' ,, ' :,' Expected Actions/Behavior **, .. ,, IF any PORV can NOT be closed, THEN NOTE: MOV-515 is still manually close its block valve. IF block OPEN. valve can NOT be closed, THEN The CRS may dispatch an dispatch AO to locally check breaker. AO. SIM DRIVER: as AO, acknowledge.

• MOV-515, MCC D position 6C
• MOV-516, MCC C position 6C * (Step 5 Continued)

Block valves -AT LEAST ONE OPEN. (Step 6) Reset SI. (Step 7) Reset Cl:

• Depress Cl reset pushbutton
• Verify annunciator A-26, CNMT ISOLATION

-EXTINGUISHED (Step 8) Verify Adequate SW Flow:

• Check at least two SW pumps RUNNING
• Dispatch AO to establish normal NOTE: The CRS will shutdown alignment (Refer to ATT-17.0, dispatch an AO. ATTACHMENT SD-1) SIM DRIVER: as AO, acknowledge.

(Step 9) Establish IA to CNMT:

• Verify non-safeguards busses energized from offsite power
• Bus 13 normal feed -CLOSED OR
• Bus 15 normal feed -CLOSED Appendix D Operator Acltion Form ES-D-2 Op Test No.: N2014-301 Scenario#

4 Event# _6_&_7 ____ Page ::_ of _6_7_-11 Event

Description:

Tifne** Pos:. co HCO Pzr Steam Space Break/Seal Water Return Isolation CIV Fails in AUTO ; Expected .* ., Comme.tlts .. : .

• Verify turbine building SW isolation 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
• Reset both trains of XY relays for IA to CNMT AOV-5392
• Verify IA to CNMT AOV-5392

-OPEN (Step 10) Check Normal Power Available To Charging Pumps:

• Check Normal Power Available To Charging Pumps:
• Bus 14 normal feed breakm -CLOSED
• Bus 16 normal feed breaker -CLOSED
• Verify adequate Safeguards Bus capacity to run charging pumps (6 amps each)
• Station Service transformer 14 ammeter
• Station Service transformer 16 ammeter (Step 11) Check If Charging Flow Has Been Established:
• Charging pumps -ANY RUNNING NOTE: There are NO Charging Pumps running.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# 6&7 Page 67 Event

Description:

Time , I \',, ,: ' 'Pos:; HCO CRS HCO Pzr Steam Space Break/Seal Water Return Isolation CIV Fails in AUTO . *.; *; . . . c * ; f:xpected Act.1ons/Behavior comments* .. * (Step 11 a RNO) Perform the following:

• IF CCW flow is lost to any RCP NOTE: CCW flow to the thermal barrier OR any RCP #1 seal RCP has NOT been lost, nor outlet temperature greater than is any RCP #1 seal outlet 235°F, THEN ....... temperature greater than 235°F.
• Ensure HCV-142 open, demand at 0%. * (Step 11 Continued)

Charging pump suction aligned to RWST:

• LCV-112B

-OPEN

• LCV-1112C

-CLOSED * (Step 11 b RNO) manually align valves as necessary.

• (Step 11 Continued)

Start charging NOTE: The HCO will start pumps and adjust charging flow as one Charging Pump even necessary to restore PRZR level though Pzr Level is off-scale high. (Step 12) Check If SI Should Be Terminated:

• RCS pressure:
• Pressure-GREATER THAN 1650 NOTE: Adverse psig [1650 psig adverse CNMT] Containment is likely to exist at this time. RCS pressure is expected to be ::::1200 psig and stable.
• Pressure

-ST ABLE OR RISING * (Step 12a RNO) Do NOT stop SI pumps . Go to Step 13. (*Step 13) Monitor If CNMT Spray Should Be Stopped: Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# _6_&_7 ___ Page of Event

Description:

Time CRS HCO co Pzr Steam Space Break/Seal Water Return Isolation CIV Fails in AUTO : \, .Expeeted.Actions/Behavior: '. .' .*.

• CNMT spray pumps -ANY RUNNING NOTE: No CS pumps running.
• (Step 13a RNO) Go to Step 14 . (*Step 14) Monitor IF RHR Pumps Should Be Stopped:
• Check RCS pressure:
• Pressure

-GREATER THAN 300 NOTE: Adverse psig [350 psig adverse CNMT] Containment is likely to exist at this time.

• RCS pressure

-ST ABLE OR RISING

• RHR pumps -ANY RUNNING IN INJECTION MODE
• Stop RHR pumps and place in AUTO NOTE: The HCO will STOP the RHR Pumps.
• Dispatch AO to perform ATT-14.6, NOTE: The CRS will ATTACHMENT RHR PRESS dispatch an AO. REDUCTION, Part A. SIM DRIVER: as AO, acknowledge.

Use INSIGHT point t_p682a to provide RHR pump suction pressure. If asked, report RHR discharge pressure -100 PSIG, and pressure reduction is not necessary per this Att. (Step 15) Check RCS And S/G Pressures

• Check pressures in both S/Gs *-STABLE OR RISING
• Check pressures in both S/Gs --GREATER THAN 110 PSIG
• Check RCS pressure

-ST ABLE OR LOWERING Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# _6_&_7 ___ Page of _6_7_-11 Event

Description:

Time co co Pzr Steam Space Break/Seal Water Return Isolation CIV Fails in AUTO . Expected Actions/Behavior:

• .. . Comments F . . (Step 16) CHECK IF EMERGENCY DIGs Should Be Stopped:
• Verify Safeguards busses 14, 16, 17, and 18 voltage-GREATER THAN 440 VOLTS
• Verify Safeguards buss es 14, 16, 17, and 18 voltage energized by offsite power:
• Emergency DIG output breakers

-OPEN

• AC emergency bus normal feed breakers

-CLOSED

• Stop any unloaded emergency DIG and NOTE: Both DIGs are place in standby (Refer to ATT-8.1, running unloaded.

ATTACHMENT DIG STOP) NOTE: The CRS will hand this off to the CO. CRS/HCO Examiner continue on page 58. ATT-8.1, ATTACHMENT D/G STOP (Step A) Perform the following to STOP DIG A and restore to AUTO:

• 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 60Hz.
• Using DIG A AUTO VOLT AGE CONTROL rheostat adjust DIG A voltage to 480 volts.
• Place DIG A CONTROL switch to STOP AND immediately depress DIG A VOLT AGE SHUTDOWN button until voltage decays to zero.
• After -60 seconds, perform thH following:

Appendix D Operator Action Form ES-0-2 Op Test No.: N2014-301 Scenario# 4 Event# _6_&_7 ___ Page of _6_7_1 Event

Description:

Time *** .. Pos. co

• Pzr Steam Space Break/S*eal Water Return Isolation CIV Fails in AUTO * .. Expected

,Actions/BelJaVior ' ' ,' ' , ' ' Comments

• Depress DIG A FIELD RESET
• Depress DIG A RESET
• Verify DIG A AIR START SOLENOID lights -LIT
• Verify DIG A ST ART RELAY lights -LIT IF alternate cooling is being supplied to NOTE: Alternate Cooling is the DIG A ...... NOT being supplied.

(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 E>OHz.
• Using DIG B AUTO VOLTAGE CONTROL rheostat adjust DIG B voltage to 480 volts.
• Place DIG B CONTROL switch to STOP AND immediately depress DIG B VOLT AGE SHUTDOWN button until voltage decays to zero.
• After -60 seconds, perform the following:
• Depress DIG B FIELD RESET
• Depress DIG B RESET
• Verify DIG BAIR START SOLENOID lights -LIT
• Verify DIG b START RELAY lights -LIT
• IF alternate cooling is being supplied to NOTE: Alternate Cooling is the DIG B ...... NOT being supplied.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# ____ Page of Event

Description:

Pzr Steam Space Break/Seal Water Return Isolation CIV Fails in AUTO Time .Pos.* l.;c., Expected Actions/Behavior .* .. ' ,, ,,'<< . ' ' , ,< ,:: 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)
• Plant vent gas (R-14)
• CCW liquid monitor (R-H)
• L TON line monitor (R-9)
• CHG pump room (R-4)
• WHEN TSC is manned, THEN request NOTE: The TSC will NOT evaluation of sampling requirements.

be 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 HCO will refer to including required power supplies, ATT-14.5.

from Sump B and back to RCS available per ATT-14.5, ATTACHMENT RHR SYSTEM Appendix D Operator Adion Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# _6_&_7 ___ Page of _6_7_-11 Event

Description:

Pzr Steam Space Break/Seal Water Return Isolation CIV Fails in AUTO Time***** 1Pos. *,. .Expecte<;I Actions/BehaviC>r1 .1 .Comments+

• 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 basement for RHR system leakage (AUX dispatch an AO. BLDG sub-basement key may be SIM DRIVER: as AO, required) acknowledge (Report No Leaks). HCO (Step 19) Check If RCS Cooldown And Depressurization Is Required:
• RCS pressure-GREATER THAN 300 NOTE: Adverse psig (350 psig adverse CNMT) Containment is likely to exist at this time.
• Go To ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, Step 1 NOTE: The CRS will go to ES-1.2. ES-1.2, POST-LOCA COOLDOWN AND DEPRESSURIZATION Examiner NOTE: An Orange Path on RCS Integrity is expected during the steps taken in ES-1.2. If so, move forward to exam termination.

HCO/ Foldout Page NOTE: The crew will co monitor these conditions throughout the performance of E-0. LOSS OF SW CRITERIA SI REINITIATION CRITERIA SI TERMINATION CRITERIA SECONDARY INTEGRITY CRITERIA ! Appendix D Operator Action Form ES-D-2 Op Test No.: N2D14-3D1 Scenario# 4 Event# _6_&_7 ___ Page of _6_7_-;, Event

Description:

Time, Po:;.*',, HCO CRS co co Pzr Steam Space Break/Seal Water Return Isolation CIV Fails in AUTO Expected*,Actions/Behavi'or

' Comments

• • . . COLD LEG RECIRCULATION SWITCHOVER CRITERION AFW SUPPLY SWITCHOVER CHITERION E-3 TRANSITION CRITERIA

(*Step 1) Monitor If RHR Pumps Should Be Stopped:

• RHR pumps -ANY RUNNING IN NOTE: The RHR Pumps INJECTION MODE have previously been stopped.
• (Step 1 a RNO) Go to Step 2 . (Step 2) Monitor AC Bus Power:
• Verify Safeguards Susses 14, 16, 17, and 18 -GREATER THAN 440 VOL TS
• Monitor All AC Susses -SUSSES ENERGIZED BY OFFSITE POWER
• Normal feed breakers to all 480 volt busses -CLOSED
• Emergency DIG output breakers

-OPEN (Step 3) Check Power Availability To Charging Pumps:

• Check Normal Power Available To Charging Pumps:
• Bus 14 normal feed breaker -CLOSED
• Bus 16 normal feed breakHr -CLOSED
• Verify adequate Safeguards Bus capacity to run charging pumps (6 amps each)
• Station Service transformer 14 ammeter Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

4 Event# 6&7 Page _61_ of 67 Event

Description:

Time":,, HCO co co HCO Pzr Steam Space Break/Seal Water Return Isolation CIV Fails in AUTO Expected Actions/Behavior n,', Comments

• Station Service transformer 16 ammeter (Step 4) Establish 75 GPM Charging Flow:
• Charging pumps -ANY RUNNING NOTE: There are one or two Charging Pumps running.
• Align charging pump suction to RWST:
• LCV-1128

-OPEN

• LCV-112C

-CLOSED

• Start charging pumps as necessary (75 kw each) and establish 7fi gpm total charging flow
• Charging line flow
• Seal injection flow (Step 5) Establish Condenser Steam Dump Pressure Control:
• Verify condenser available:
• Any MSIV -OPEN NOTE: Both MSIVs are CLOSED. * (Step 4a RNO) Place SIG ARV controllers in AUTO at current SG pressure and go to Step 6. (*Step 6) Monitor Intact SIG Levels:
• Narrow range level -GREATER THAN NOTE: Adverse 7% [25% adverse CNMT] Containment is likely to exist at this time.
• Control feed flow to maintain narrow range level between 17% [25% adverse CNMT] and 50% (Step 7) Deenergize PRZR Heaters Appendix D Operator Action Form ES-D-2 Op Test No.: N2D14-301 Scenario#

4 Event# _6_&_7 ____ Page of _67_-l1 Event

Description:

Time .. Pos. co HCO HCO HCO Pzr Steam Space Break/Seail Water Return Isolation CIV Fails in AUTO *"' Expected Actions/Behavk>r Comments ..

• Place PRZR proportional heaters in PULL STOP
• Place PRZR backup heaters in OFF
• Consult TSC for a recommended NOTE: The TSC is NOT minimum indicated PRZR water level manned. that will ensure heaters are covered (Step 8) Initiate RCS Cooldown To Cold Shutdown:
• Establish and maintain cooldown rate NOTE: Current CID due to using CET's -BETWEEN 80°F/HR AND SI flow should be > 100°F/hr 100°F/HR
• Use RHR system if in service
• Dump steam to condenser from intact S/G(s) (Step 9) Check RCS Subcooling Based On NOTE: IF subcooling is Core Exit T/Cs -GREATER THAN 0°F indicated, crew should USING FIG-1.0, FIGURE MIN transition to FR-P .1 if entry SUBCOOLING conditions are reached.

(Step 10) Check SI and RHR Pump Status:

• SI pumps -ANY RUNNING OR
• RHR pumps -ANY RUNNING iN INJECTION MODE (Step 11) Depressurize RCS To Refill PRZR: NOTE: Pzr Level is off-scale HIGH.
• Depressurize using normal PRZR spray if available
• (Step 1 Oa RNO) Depressurize using one PRZR PORV.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# _6.;....;..&..;.7 ___ Page of Event

Description:

Time , Pos .. HCO HCO HCO Pzr Steam Space Break/Seal Water Return Isolation CIV Fails in AUTO *Expected Actions/Behavior . comments

• * (Step 10 Continued)

PRZR level -NOTE: Adverse GREATER THAN 20% [40% adverse Containment is likely to exist CNMT] at this time.

• Stop RCS depressurization (Step 12) Check If An RCP Should Be Started:
• Both RCPs -STOPPED NOTE: Both RCPs are stopped.
• RCS subcooling based on core exit T/Cs -GREATER THAN 0°F USING FIG-1.0, FIGURE MIN SUBCOOLING
• PRZR level-GREATER THAN 20% NOTE: Adverse (40% adverse CNMT) Containment is likely to exist at this time.
• Try to start an RCP
• Establish conditions for starting an RCP
• Bus 11 A or 11 B energized
• Refer to ATT-15.0, ATTACHMENT RCP START ATT-15.0, ATTACHMENT RCP START (Step A) The following are prerequisites for starting an RCP:
• MCC E energized
• RCP oil lift pump running (-2 minutes)
• RCP oil lift pressure white light -LIT (Step B) In addition, the following conditions should be met prior to starting an R:CP:
• Both PRZR spray valves closed -DEMANDATO%

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 4 Event# _6_&_7 ___ Page _6_7_-l1 Event

Description:

Time Pos. -----**. *< * * * * * * *

• Pzr Steam Space Break/Seal Water Return Isolation CIV Fails in AUTO Actions/Behavior*

-_. '"' *,,*, ,,;' , Comments. CCW in service to selected RCP(s) with flow and temperature alarms (A-7, A-15) extinguished. Selected RCP(s) seal inlet temperature -LESS THAN 135°F Selected RCP(s) motor bearing1 temperatures -LESS THAN 200°F Selected RCP(s) seal injection in service

• Seal injection flow -GREATER THAN 6 GPM
• Labyrinth seal D/P -GREATER THAN 15 INCHES OF WATER Selected RCP(s) #1 seal D/P -GREATER THAN 220 PSID Selected RCP(s) oil levels:
• Level alarms (A-24, A-32) -EXTINGUISHED
• Level indicators

-ON SCALE Selected RCP(s) seal return alignment

• RCP #1 seal outlet valve(s) open:
• AOV-270A for RCP A
• IF MOV-313, seal return NOTE: MOV-313 is Closed. isolation, open ......
• IF MOV-313 closed, THEN verify other RCP #1 seal parameters normal for selected RCP(s):
• RCP #1 seal inlet temperature

-LESS THAN 135°F

• RCP #1 seal D/P -GREATER THAN 220 PSID IF ES-0.2, ES-0.3 or ES-1.1 is in NOTE: These procedures effect ..... are NOT in effect. ES-1.2, POST-LOCA COOLDOWN AND DEPRESSURIZATION Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

4 Event# _6_&_7 ___ Page of Event

Description:

Time Pos. HCO HCO Pzr Steam Space Water Return Isolation CIV Fails in AUTO E><;pected ACtions/Behavior. ' . .* .*. *: ..* *comments

• (Step 12 Continued)

Start one NOTE: The HCO will RCP. START one RCP. (Step 13) Check If One Of Three SI Pumps Should Be Stopped:

• Three SI pumps -RUNNING
• RCS subcooling based on core exit T/Cs NOTE: Adverse -GREATER THAN 35°F [50°F adverse Containment is likely to exist CNMT] USING FIG-1.0, FIGURE MIN at this time. SUBCOOLING
• Check PRZR level -GREATER THAN NOTE: Adverse 20% [40% adverse CNMT] Containment is likely to exist at this time.
• Stop one SI pump NOTE: The HCO will STOP one SI pump. (Step 14) Check If One Of Two SI Pumps Should Be Stopped:
• Two SI pumps -RUNNING
• Determine required RCS subcooling from table:
• RCS subcooling based on core exit T/Cs NOTE: The HCO will NOT -GREATER THAN VALUE FROM be able to stop the second TABLE ABOVE USING FIG-1.0, SI Pump, due to Subcooling FIGURE MIN SUBCOOLING requirements NOT met. Terminate the Exam at the discrntion of the Lead Examiner SRO Examiner Perform Admin JPM A4 on CRS Core Age: MOL 48% Power, Equilibrium Xe Outside Air Temp= 45°F Water Temp= 45°F Boron: 1106 ppm BAST: 17,400 ppm RCS Activity:

Normal TURNOVER SHEET for NRC Exam Scenario

1. 4 Procedure in Use:

• S-3.2P, Swapping CVCS Letdown Orifices
• P-17, Operations Control Room Operating Instructions, Attachment 12, CROl-12 Swapping Electro-Hydraulic Pumps RCS LEAKAGE:

(gpm) Total: .021 Identified: .003 Unidentified: .018 ACTIONS/NOTES:

• The plant is at -48% power (MOL). Reactor power is below P-9.
• Power has been held at this level for approximately four days while corrective maintenance is performed on the A MFW Pump. Maintenance has just been completed.
• Chemistry has requested that Letdown flow be raised from 40 gpm to 60 gpm. The crew should be prepared to raise Letdown flow to 60 gpm by swapping to AOV-200 immediately after turnover.
• The crew should also plan to swap EHC Pumps per P-17 in preparation for performing maintenance on the A EHC supply pump after the letdown orifice flow has been adjusted.
• The B AFW Pump is OOS for Bearing Replacement.

LCO 3.7.5 was entered 24 hours ago. Estimated return to service is within 48 hours.

• Steam Flow channel FT-475 is OOS. The channel has been defeated per
• The following Alarms are in: o E-4, POWER RANGE UPPER DETECT FLUX DEV OR AUTO DEFEAT(<

50% Power) o E-12, POWER RANGE LOWER DETECT FLUX DEV OR AUTO DEFEAT (< 50% Power) o J-25, SAFEGUARDS EQUIPMENT LOCKED OFF (B MD AFW Pump OOS)

• Protected equipment IAW OPG Protected Equipment.

TURNOVER SHEET for NRC Exam Scenario

1. 4 EquiQ.ment Problems/OOS:

Planned Activities for Shift: Electrical System OQerator Declarations See NOTES

• Shift Letdown from 60 gpm to 40 gpm . None in effect
• Swap EHC Pumps per P-17 BAST RWST 151 hour dilution stabilization 2nd hour dilution stabilization (gal) (gal) (gal RMW) (gal RMW) 10% at 1 % per minute 52 545 77 51 10% at 10% per hour 48 503 77 52 50% at 1 % per minute 229 2482 558 314 50% at 10% oer hour 173 1860 296 98 A-52.4 EQUIPMENT DATE/TIME 005 LCO TITLE EXP DATE ECO 'B' MDAFW Pump Yesterday, 24hrs ago 3.7.5.B AFW system 7 days 2 days from now AM FT-475 Today,0200 3.3.2 4.d/4.e ESFAS Instrumentation Indefinite 3 Days A-52.12 EQUIPMENT DATE/TIME 005 TRM/ODCM TITLE EXP DATE ECO PROGRAM:

Ginna Operations Training MODULE: 2014 Initial License Operator Training Class TOPIC: NRC Simulator Exam Scenario N2014-301-5

REFERENCES:

1. 0-1.2, Plant Startup From Hot Shutdown to Full Power Load, Rev 20101 2. T-16A, Turbine Pre-Startup, Rev 09400 3. A-503.1, Emergency and Abnormal Operatin1;:i Procedures Users Guide, Rev 04409 4. AR-L-8, 480V GROUND, Rev 8 5. AR-A-22, CCW PUMP DISCHARGE LO PRESS 60 PSI, Rev 12 6. AP-CCW.2, Loss of CCW During Power Operation, Rev 02201 7. Technical Specification

3. 7. 7, CCW System, Amendment 80 8. AR-E-9, IR N-35 LOSS OF COMPENSATING

VOLTAGE, Rev 4 9. ER-NIS.2, IR MALFUNTION, Rev 00501 10. AR-L-23, BUS18 UNDER VOLTAGE SAFEGUARDS, Rev 01102 11. AP-ELECT.17/18, Loss of Safeguards Bus 1 "7/18, Rev 00802 12. AP-SW.2, Loss of Service Water, Rev 00801 13. Technical Specification 3.8.1, AC Sources -Modes 1, 2, 3, and 4, Amendment 109 14. Technical Specification 3.8.9, Distribution Systems -Modes 1, 2, 3,and 4, Amendment 80 15. Technical Specification

3. 7.8, Service Water System, Amendment 102 16. AR-A-11, LETDOWN LINE HI PRESS 400 PSI, Rev 4 17. E-0, Reactor Trip and Safety Injection, Rev 04602 18. ATT-27.0, Attachment Automatic Action Verification, Rev 00300 19. E-2, Faulted Steam Generator Isolation, Rev 01301 20. E-3, Steam Generator Tube Rupture, Rev 04800 21. ECA-3.1, SGTR with Loss of Reactor Coolant, Subcooled Recovery

Desired, Rev 03401 22. FR-P.1, Response to Imminent Pressurized Thermal Shock Condition, Rev 03200 Validation Time: 98 Minutes Author: David Lazarony, Essential Training

& Consulting, LLC Facility Review: Rev. 110714 Scenario Event Description NRC Scenario 5 Facility: Ginna Scenario No.: 5 Op Test No.: N2014-301 Examiners: Operators: (SRO) (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 A MFW Pump in accordance with 0-1.2, Plant Startup From Hot Shutdown to Full Power Load, Step 6.3.4 and beyond. The area has experienced thunderstorms over the last 6 hours, and this is expected to continue for the next 6 hours. Turnover: The following equipment is Out-Of-Service: The B Condensate Pump is OOS for Bearing Replacement. Event Malf. Event Type* Event No. No. Description 1 NA R-RO Raise Power to POAH N-SRO 2 NA N-BOP Testing of the MFW Oil Pumps N-SRO 3 CLG10 C-RO 480VAC Ground/A CCW Pump trips w/B CCW Pump failure to CLG02A C(TS)-SRO start in AUTO A-EDS33 4 EDS04D C-BOP Fault on 480V Bus 18/SW Pump D fails to start CLG01D C(TS)-SRO 5 CVCO?A C-RO PCV-135 fails CLOSED C-SRO 6 NISOSA C-BOP Loss of Compensating Voltage to Intermediate Range N35 C{TS)-SRO 7 STM04D M-RO B ARV fails CLOSED/B SG Safety Valve Lifts and fails OPEN STM09A M-BOP M-SRO 8 RP SOSA C-RO Failure of Reactor to Trip in AUTO only RP SO SB C-SRO 9 SGN04B C-BOP B Steam Generator Tube Rupture/1 % Failed Fuel RCS16 C-SRO * (N)ormal, (R)eactivity, (I )nstrument, ( C )om ponent, (M)ajor Ginna 2014 NRC Scenario

1. 5 Scenario Event Description 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 0-11.2, Plant Startup From Hot Shutdown to Full Power Load, Step 6.3.4 and beyond. The area has experienced thunderstorms over the last 6 hours, and this is expected to continue for the next 16 hours. 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 Load. The operator will raise reactor power and stabilize reactor power at 0.5-1.0%; and then control Tavg at 547°F. After this, the operator will conduct the oil pump chHcks on the A Main Feedwater (MFW) Pump accordance with Attachment 5, Main Feed Pump A Startup of 0-1.2, Plant Startup From Hot Shutdown to Full Load, in preparation for starting the A MFW Pump. 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 A 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, 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 and/or AR-L-5, SAFEGUARD BUS MAIN BREAKER OVERCURRENT TRIP and enter 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 EOG running or trip it within AP-ELECT.17 /18, but in either case align Alternate Cooling to the EOG. 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 operator will respond in accordance with AR-A-11, LETDOWN LINE HI PRESS 400 PSI, and take manual control of the valve. Shortly afterwards, 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. After this, the B ARV will inadvertently close, and one SG Safety valve will open and stick open. The reactor will fail to trip automatically, and the operator will need to manually trip the reactor and enter E-0, Reactor Trip or Safety Injection. On the trip approximately 1 % failed fuel will occur. The operator will proceed through E-0, and then transition to E-2, Faulted Steam Generator Isolation. Scenario Event Description NRC Scenario 5 While in E-2 a large Steam Generator Tube Rupture will develop on the B Steam Generator, and the operator will transition to E-3, Steam Generator Tube Rupture. Because the B Steam Generator is both Ruptured and Faulted, the operator will transition to ECA-3.1, SGTR with Loss of Reactor Coolant, Subcooled Recovery Desired. Also, while in E-2, it is expected that high temperatures will occur on the RCPs due to low service water flow, requiring the crew to stop these pumps. Because of this the NC condition of the RCS will tend to lower loop Tcold temperatures causing an Orange/Red condition on RCS Integrity. If so, the operator may need to transition to FR-P.1, Response to Imminent Pressurized Thermal Shock Condition. The scenario will terminate at Step 15 of ECA-3.1, after the crew has monitored conditions for continuing with the Subcooled Recovery procedure, or upon transition to FR-P.1. Critical Tasks: 1. Manually trip the reactor prior to transition to FR-5.1, "Response to Nuclear Generation/ A TWS." 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. 2. 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 otherwisB 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). D D Bench Mark Prior to Crew Briefing Scenario Event Description NRC Scenario 5 SIMULATOR INSTRUCTIONS ACTIVITY DESCRIPTION Reset to Temp l/C 175. (Built on IC-7) 0% power BOL T=Qi: RUN Place B Condensate Pump is Pull-Stop. Vacuum Priming Pump A ON CND06, Vacuum Priming Pump B ON ENSURE that the A CCW Pump is ON and the B CCW Pump is in STANDBY. ENSURE that Steam Generator Levels are stabilized. Insert MALF CLG10 (Auto start failure of standby CCW pump on low pressure) Insert MALF RPS05A, MAN AVAIL (Reactor trip breaker A failure) Insert MALF RPS05B, MAN AVAIL (Reactor trip breaker B failure) Insert MALF CLG01 D (SWP D Trip) MALF CLG02A, on T-1, A CCW Pump Trip ANl\I A-EDS33, ON, on T-1, 480 VAC Ground (15 Seconds delayed, clears in 20 seconds) MAL.F EDS04D, on T-2, Fault on Bus 18 MAL.F CVC07A, 0%, 0 Ramp, MAN AVAIL, on T-3, PCV-135 Fails CLOSED MALF NIS05A, 1 E-8 amps, 0 Ramp, on T-4, Loss of Compensating Voltage in N35 MAL.F STM04D, 0%, 0 Ramp, on T-5 MAL.F STM09A, 40%, 30 second delay, 15 second Ramp, on T-5 MALF SGN04B, 60% [600 gpm], 0 Ramp, on T-6 MALFRCS16=1%, 0 Ramp, on T-6, 1% failed fuel

• Hang Protective Tags per OPG-Protective Equipment.
• Place Black Dot on J-17
• a Critical Parameter Marker on SG Narrow Range level at 52+/-7%.

D D D D D Bench Mark Scenario Event Description NRC Scenario 5 *ACTIVITY Crew Briefing

• Assign Crew Positions based on evaluation requirements
• Review the Shift Turnover Information with the crew. 1. Provide crew with Reactivity Plan for the startup.

DESCRIPTION

2. Hand out 0-1.2, Step 6.3 and substeps (p24-216), 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 1st Bullet -Record 100, Initialed
• Step 6.3.3.2.b 2nd Bullet -Record D, Initialed
• Step 6.3.3.2.c 1st Bullet -Record 110, Initialed
• Step 6.3.3.2.c 2nd Bullet -Record D, Initialed
• Step 6.3.3.2.d

-Record 2094, Initialed

• Step 6.3.3.2.e

-Record 547, Initialed

• Step 6.3.3.2.f

-Initialed

• Step 6.3.6 -Initialed
• Step 6.3.7 -Initialed
• Step 6.3.8 -NA
• All other Steps blank 3. Provide a Blank Copy of Attachment

5. 4. Low Power Attachment of 0-1.2 should be covered in the Pre-Job Briefing.

T-0 At direction of examiner At direction of examiner At direction of examiner Begin Familiarization Period Event1 Event2 Event3 Trigger#1 A-EDS33 CLG02A CLG10 (T=O) Raise power to POAH Testing of the MFW Oil Pumps 480VAC Ground/A CCW Pump trips w/B CCW Pump failure to start in AUTO ON, (Simulates simultaneous 480V ground). Alarm will clear 20 seconds after alarm. NOTE: This Malfunction is inserted in the IC at T=:O. Bench Mark D At direction of examiner D At direction of examiner D At direction of examiner D At direction of examiner D Continued from Event 7 D Upon Entry into E-2 D Scenario Event Description NRC Scenario 5 ACTIVITY DESCRIPTION Event 4 Loss of Emergency Bus: 480V Bus 18/SW Pump D Trigger #2 fails to start EDS04D CLG01 D (T=O) NOTE: This Malfunction is inserted in the IC at T :: 0. Event 5 PCV-135 fails Closed Trigger #3 O°/i, (MAN AVAIL), No Ramp CVC07A Event 6 Loss of Compensating Voltage to Intermediate Trigger#4 Range N35 NIS05A 1 E--8 amps, No Ramp Event 7 B ARV fails CLOSED/B SG Safety Valve Lifts and Trigger#5 fails OPEN STM04D (0%) STM09A (40%) 30 seconds delay, 15 second ramp Event 8 Failure of Reactor to Trip in AUTO only RPS05A (T=O) NOTE: This Remote is inserted in the IC at T = RPS05B (T=O) 0. Event 9 B Steam Generator Tube Rupture/1 % Failed Fuel Trigger#6 SGN04B (600 gpm) RCS16 (1%) Terminate the scenario upon direction of Lead Examiner Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# Page ------8 of 57 Event

Description:

Raise Power to POAH 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 Load. The operator will raise reactor power and stabilize reactor power at 0.5-1.0%; and then control Tavg at 547°F. ' SIM DRIVER Instructions: NA Indications Available: NA Time Pos. ,,Expected Actions/Behavior

• **comments.**

0-1.2, PLANT STARTUP FROM HOT SHUTDOWN TO FULL LOAD NOTE: The CRS will conduct an alignment brief. HCO (Step 6.3.4) WITHDRAW controlling bank of NOTE: The HCO will raise Rods and raise Reactor Power to the point of Reactor power. adding heat without exceeding the capacity of one AFW Pump. CO/ (Step 6.3.5) VERIFY one of the following is CRS operating to control RCS Tavg AND MARK component NOT controlling Tavg N/A.

• SGARVs
• 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 NOTE: The CRS will hand Attachment 5 off to the CO.
• Attachment 6, Main Feedwater Pump B NOTE: The CRS will likely conduct a Plant Status Brief. At the discretion of the Lead Examiner move to Event #2.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# 2 Page 9 of 57 Event

Description:

Testing of the MFW Oil Pumps After this, the operator will conduct the oil pump checks on the A Main Feedwater (MFW) Pump accordance with Attachment 5, Main Feed Pump A Startup of 0-1.2, Plant Startup From Hot Shutdown to Full Load, in preparation for starting the A MFW Pump. SIM DRIVER Instructions: NA Indications Available: NA Time Expected Actions/Beliavior

• . .... *. :(. .. Pos .. .comments

. .. NOTE: The CO will contact and coordinate with the Secondary AO to complete this Attachment. SIM DRIVER: Acknowledge as AO as appropriate. 0-1.2, PLANT STARTUP FROM HOT SHUTDOWN TO FULL LOAD ATTACHMENT 5, MAIN FEE:DWATER PUMP A co (Step 1.0) PERFORM the following to align and start MFW Pump A: co (Step 1.1) PLACE Feedwater Pump A Oil Pump in service as follows: co (Step 1.1.1) START a FEEDWATER PUMP A AC OIL PUMP AND MARK the Oil Pump NOT started N/ A.

• 1A1
• 1A2 co (Step 1 .1.2) PERFORM the following to ensure the FEEDWATER PUMP A DC OIL PUMP starts on low oil pressure:
• PLACE FEEDWATER PUMP A DC OIL PUMP in AUTO.
• SLOWLY SELECT standby NOTE: The CO will need to FEEDWATER PUMP A AC OIL PUMP. move the Select Switch slowly.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# _2 _____ Page 10 of _5_7_1 Event

Description:

Testing of the MFW Oil Pumps .***Time*. t.eos; * < ,. Expected .. * .* .Comments <' ' ' ..

• VERIFY FEEDWATER PUMP A DC OIL PUMP starts. NOTE: MCB Annunciator J-31 may alarm when the DC Oil Pump is started.

Based on this alarm, the CRS may contact maintenance to evaluate the DC Distribution System. If so, SIM DRIVER: Acknowledge as Maintenance, and report that the alarm will clear when the DC Oil Pump is stopped; and that it is appropriate to continue with the test. co

• VERIFY MCB Alarm H-12, FEED PUMP DC OIL PUMP AUTO START, is ILLUMINATED.
• VERIFY MCB Alarm H-4, MAIN FEED PUMP OIL SYSTEM, is ILLUMINATED.
• STOP FEEDWATER PUMP A DC OIL PUMP.
• VERIFY MCB Alarm H-12, FEED PUMP DC OIL PUMP AUTO ST ART 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 original 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, is ILLUMINATED.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# _2;;..._ ____ Page 11 of _5_7_-11 Event

Description:

Testing of the MFW Oil Pumps Time .. Pos.** ,, i;xpected Actions/Behavior .. .

• c .. .** . * . . pmments . .
• VERIFY MCB Alarm H-4, MAIN FEED PUMP OIL SYSTEM, is ILLUMINATED.
• STOP FEEDWATER PUMP A DC OIL PUMP.
• VERIFY MCV Alarm H-12, FEED PUMP DC OIL PUMP AUTO ST ART, is EXTINGUISHED.
• VERIFY MCB Alarm H-4, MAIN FEED PUMP OIL SYSTEM, is EXTINGUISHED.
• ENSURE FEEDWATER PUMP A DC OIL PUMP in AUTO. At the discretion of the Lead Examiner move to Event

1. 3.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# _3 _____ Page 12 of Event

Description:

480VAC Ground/A CCW Pump trips w/B CCW Pump failure to start in AUTO 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 A 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. SIM DRIVER Instructions: Operate Trigger #1 (CLG02A, A-EDS33 (ON)) Indications Available:

• MCB Annunciator L-8, 480V GROUND
• MCB Annunciator, CCW PUMP DISCHARGE LO PRESS 60 PSIG
• A CCW Pump Green Breaker Status Light LIT
• A CCW Pump White Breaker Status Light LIT
• B CCW Pump Green Breaker Status Light LIT Time Pos.* .. .. **Expected Actions/Behavior

. i: *:i *comments*

i. 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. SIM DRIVER: as AO, acknowledge. CRS (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). SIM DRIVER: as SS, acknowledge. CRS (Step 3) IF necessary, THEN refer to ITS LCO 3.8.1 OR 3.8.2. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# _3 _____ Page 13 of 57 ---11 Event

Description:

Time: CRS CRS HCO HCO CRS 480VAC Ground/A CCW Pump trips w/B CCW Pump failure to start in AUTO Expected Actions/Behavic:>r ....... * *. *: * .. I* ** Comme11ts

• .. (Step 4) IF necessary, THEN notify the NOTE: The CRS may notify following:

the WCC/Electricians. SIM DRIVER: as WCCS/Electricians, acknowledge, and after 3 Minutes report that the A CCW has tripped.

• Electricians
• Electric Planner AR-A-22, CCW PUMP DISCHARGE LO PRESS 60 PSI (Step 1) GO TO the applicable AP-CCW procedure:
• AP-CCW.2, LOSS OF CCW DURING POWER OPERATION (Step 2) Notify AO to check CCW pumps. NOTE: The CRS may direct the AO to check the CCW Pumps. If so, SIM DRIVER acknowledge as AO, and report A CCW Pump Motor Hot to Touch. (Step 3) IF CCW pump cavitation is evident NOTE: The CRS may direct with normal CCW surge tank level as the AO to check the CCW indicated on Ll-618,.

... Pumps. If so, SIM DRIVER acknowledge as AO, and report no evidence of cavitation exists on any CCW Pump. (Step 4) Refer to ITS LCO 3.4.6, 3.4.7, 3.4.8, 3.7.7, 3.9.4 and 3.9.5. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# _3 ________ Page 14 of 57 Event

Description:

Time . . .< Pos. ,* 480VAC Ground/A CCW Pump trips w/B CCW Pump failure to start in AUTO Expected Actions/Behavior.

• ,comments*

.* 7 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 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 18. AP-CCW.2, LOSS OF CCW DURING POWER OPERATION Examiner NOTE: If the B CCW Pump is started already upon entry into this procedure, move on to Event 4 and the discretion of the Lead Examiner, and address TS Evaluation upon completion of the scenario. HCO (Step 1) Check CCW Pump Status:

• Both CCW pump breaker with lights -NOTE: The A CCW Pump 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.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# Page ------3 15 of 57 ---11 Event

Description:

Time <<,' Posl' HCO HCO HCO HCO HCO/ CO/ AO 480VAC Ground/A CCW Pump trips w/B CCW Pump failure to start in AUTO '" Expected 'Acth::ms/Behavior '\ ;: *col11111ents '* 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. (*Step 2) Monitor CCW Surge Tank Level -APPROXIMATELY 50% AND STABLE (PPCS Point L0618) (*Step 3) Monitor CCW Hx Temperature (MCB rear or PPCS point ID T0621)
• CCW Hx Outlet temperature-LESS THAN 120°F (*Step 4) Monitor RCP Indications:
• Annunciator A-7 (A-15), RCP 1A (18) 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-20.t\

recorder) -$ 200°F. (*Step 5) Monitor If Letdown Should Be Isolated:

• Check annunciator A-12, Non-Regen Hx Letdown Out Hi Temp 145°F -EXTINGUISHED
• Check Excess letdown temperature

-LESS THAN 195°F (Step 6) Check CCW Valve Alignment -NORMAL Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# 3 Page 16 of 57 Event

Description:

• Time* Pos. HCO/ AO HCO HCO HCO 480VAC Ground/A CCW Pump trips w/B CCW Pump failure to start in AUTO Expected Actions/Behavior

.* Comments

• Check MCB CCW valves (Refer to ATT-NOTE: The CRS will hand off 1.0, ATTACHMENT AT POWER CCW ATT-1.0 to the HCO or CO. ALIGNMENT)
• Direct AO to check local flow indications NOTE: The CRS may dispatch per ATT-1.1, ATTACHMENT NORMAL an AO. CCW FLOW SIM DRIVER: as AO, acknowledge, and after 5 Minutes, report that ATT-1.1.

is complete. (Step 7) Locally Check Seal Water Hx CCW NOTE: The CRS may dispatch Outlet Flow -NORMAL an AO. SIM DRIVER: as AO, acknowledge, and report after 2 Minutes that flow is 96 gpm. (Step 8) check For CCW Leakage In CNMT:

• Check CNMT sump A level:
• Level -ST ABLE
• Sump A pumps -OFF
• RCP oil levels -ST ABLE (Step 9) Check for CCW Leakage lln AUX BLDG:
• Start frequency of AUX BLDG sump pump(s)-NORMAL (Refer to RCS daily leakage log)
• Waste holdup tank level -STABLE OR NOTE: The CRS may contact RISING AS EXPECTED an AO. SIM DRIVER: as AO, acknowledge, and report that the WHUT Level is stable. (Step 10) Verify CCW System Leak -IDENTIFIED Appendix D Operator Action Form ES-0-2 Op Test No.: N2014-301 Scenario#

5 Event# _3 _____ Page 17 of 57 ---11 Event

Description:

Time** io Pos. HCO HCO HCO HCO/ co CRS CRS 480VAe Ground/A eew Pump trips w/B eew Pump failure to start in AUTO ........

• • • • • • • . . . **. ;. ;
• Expected Actions/Behavi.or

.. *; .* Comments

• 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 MATERIAL/WASTE there is no leak. (Step 11) Check Normal or Excess Letdown NOTE: Normal letdown is in -IN SERVICE service. (Step 12) Check CCW System Leak Isolated

• Surge tank level-APPROXIMATELY 50%
• Surge tank level -ST ABLE (Step 13) Direct RP To Sample CCW System NOTE: The CRS may NOT For Chromates take this action, knowing that there is no leak. (Step 14) Evaluate MCB Annunciator Status (Refer to AR Procedures)

(Step 15) Evaluate Plant Conditions:

• CCW system malfunction

-IDENTIFIED AND CORRECTED

• CCW system status adequate for power operation (Refer to ITS Section 3.7.7). (Step 16) Notify Higher supervision NOTE: The CRS may notify the wee. SIM DRIVER: as wees, acknowledge.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# _3_________ Page 18 of 57 ----11 Event

Description:

Time Pos.**. CRS 480VAC Ground/A CCW Pump trips w/B CCW Pump failure to start in AUTO

• Expected Actions/Behavior

> < Comments.

• .. * (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 CRS LCO 3.7.7 Two CCW trains, two CCW heat NOTE: CRS should recognize exchangers, and the CCW loop header shall escalating MODE change to be OPERABLE.

>5% power cannot occur with LCO not met. AAPLICABILITY: MODES 1, 2, 3, and 4. CRS CONDITION REQUIRED COMPLETION ACTION TIME A. OneCCW A.1 Restore 72 hours train CCW train inoperable. to OPERABLE status. NOTE: The CRS will likely conduct a Plant Status Brief. At the discretion of the Lead Examiner move to Event #4. Appendix D Operator Actiori Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# _4 ____ Page 19 of _5_7_1 Event

Description:

Fault on 480V Bus 18/SW Pump D fails to start Shortly after this, 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 and/or AR-L-5, SAFEGUARD BUS MAIN 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 EOG running or trip it within AP-ELECT.17 /18, but in either case align Alternate Cooling to the EOG. 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. SIM DRIVER Instructions: Operate Trigger #2 (EDS04D) Indications Available:

• MCB Annunciator L-23, BUS 18 UNDER VOLTAGE SAFEGUARDS
• MCB Annunciator L-5, SAFEGUARD BUS MAIN BREAKER OVERCURRENT TRIP
• Multiple MCB Annunciators
• Bus 18 Volts indicating O
• Bus 18 amperage indicating 0
• A EOG starts, voltage at 480 VAC, but will not load on Bus 18. Time Pos *. *
• Expe<?ted ActiOns/Behavior

". ,'!!,,-\ '" <<, ' ,::::!,,:;'

• • • Lin Comments
      • . ' : ,' NOTE: The crew may enter AP-ELECT.17/18 directly.

AR-L-23, BUS 18 UNDER VOLTAGE SAFEGUARDS CRS (Step 4.1) IF either L-20, 12A XFMH OR 12A NOTE: These annunciators BUS TROUBLE OR L-28, 12B XFMR OR are NOT LIT. 12B BUS TROUBLE-IS LIT, THEN ..... CRS (Step 4.2) IF D/G A ties onto Bus 1 B NOTE: D/G A will NOT tie THEN .... onto Bus 18. CRS (Step 4.3) IF D/G does not start THEN ..... NOTE: D/G A will start. AR-L-13, SAFEGUARDS BUS D/G BREAKER OVERCURRENT TRIP Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# _4 _____ Page 20 of 57 Event

Description:

Fault on 480V Bus 18/SW Pump D fails to start . Pos,c** Expected Actions/Behavior ,.,. *Comments .. ',, ,, ' ' " ( ,)' CRS (Step 1) Notify Electricians. CRS (Step 2) Investigate overcurrent condition. 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 applicable breaker. NOTE: The CRS will go to AP-ELEC.17118. AP-ELECT.17/18, LOSS OF SAFEGUARDS BUS 17/18 co (Step 1) Verify Emergency DIG Associated NOTE: The A DIG is With Affected Bus -RUNNING RUNNING, but its breaker is NOT Closed.

• Bus 18-DIG A co (Step 2) Verify Both trains Of AC Emergency Busses Energized To At Least 440 VOLTS:
• Bus 14 and Bus 18 NOTE: Bus 18 is de-energized.
• Bus 16 and Bus 17 co (Step 2 RNO) IF Bus 14 AND Bus 16 are NOTE: Bus 16 is energized.

deenergized, THEN ..... IF one train deenergized, THEN perform the following:

• Ensure DIG aligned for unit operation
• Mode switch in UNIT
• Voltage control selector in AUTO
• Check DIG running .

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# 4 Page 21 of 57 Event

Description:

Fault on 480V Bus 18/SW Pump D fails to start Time Pos. 1:./ .. ExpeCted Actions/Behavior

• • .......

. ' ": j ' ' "'i ' ' .. IF NOT, THEN ..... NOTE: The A D/G is RUNNING, but its breaker is NOT Closed.

• Adjust DIG voltage to approximately 480V.
• Adjust D/G frequency to approximately 60 Hz. co (Step 3) Verify Service Water System Operation:
• SW pumps -AT LEAST ONE RUNNING NOTE: The D SW Pump IN EACH LOOP has failed to Start, ONLY the B SW Pump is RUNNING.
• A or B pump in Loop A
• C or D pump in Loop B NOTE: The CRS may address AP .SW .1, SW Leak, however this procedure will NOT address the low flow condition.

co (Step 3a RNO) Perform the following:

• Manually start SW pump as necessary NOTE: The CO may attempt (357 kw each). to START the D SW Pump, but it will fail.
• IF adequate cooling can NOT be NOTE: The CRS will have to supplied to a running D/G. decide whether or not 1 SW Pump is adequate cooling.

IF NOT, the CRS will direct that the A D/G be stopped, and address ER-D/G.2 for Alternate Cooling. If 50, CRS will continue as scripted.

• IF no SW pumps can be operated, 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. NOTE: The CRS will go to AP-SW.2.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# _4 _____ Page 22 of 57 Event

Description:

Fault on 480V Bus 18/SW Pump D fails to start Time Pos.

• Actions/Behavior.

Comments ';.'* .* AP-SW.2, LOSS OF SERVICE WATER co (Step 1) Verify 480V AC Emergency Susses NOTE: Bus 18 is de-17 and 18 -ENERGIZED energized. co (Step 1 RNO) Ensure associated D/G(s) running and attempt to manually load busses 17 and/or 18 onto their respective D/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 D pump in loop B NOTE: Both C and D SW Pumps are OFF. co * (Step 2a RNO) Perform the following:
• Manually start SW pumps as NOTE: The CO may attempt necessary (257 kw each). to START the D SW Pump, but it will fail.
• IF adequate cooling can NOT be NOTE: The CRS will direct supplied to a running D/G" action based on whether or THEN ...... NOT one SW Pump can adequately cool the D/G.
• IF no SW pumps can be operated, NOTE: The B SW Pump is THEN ....... RUNNING.

CRS

• IF only one SW pump can be operated, THEN go to Step 3. co (Step 3) Align Alternate Cooling To One DIG (Refer to ER-D/G.2, ALTERNATE COOLING FOR EMERGENCY D/Gs):

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# _4 _____ Page 23 of 57 Event

Description:

Fault on 480V Bus 18/SW Pump D fails to start Time Pos. ActionsfBehavio.r

• IF B or D SW Pump is operating, THEN align alternate cooling to DIG A per D/G.2. 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, ATTACHMENT SW ISOLATION CO (Step 5) Monitor Plant Equipment Cooled By SW-TEMPERATURES STABLE
• Exciter
• MFP oil coolers
• Instrument air compressors
• Bus duct coolers
• Seal Oil unit
• Turbine lube oil cooler
• CCW Hx
• SFP Hx
• AFPs
• Condensate Pumps . * ...

NOTE: The CRS will dispatch an AO. SIM DRIVER: as AO, acknowledge, and use REM-GEN21 =OPEN. Report after 3 Minutes that ATT-2.2 is complete. NOTE: The CRS will dispatch an AO. SIM DRIVER: as AO, acknowledge, and report after 3 Minutes that ATT-2.2 is complete. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# Page 24 -----4 of 57 Event

Description:

Fault on 480V Bus 18/SW Pump D fails to start Time Po.s. Expected Actions/Behayior

• Comments
• Secondary sample coolers (Step 6) Notify Higher Supervision NOTE: The CRS may notify theWCC. SIM DRIVER: as wees, acknowledge.

co (Step 7) Check SW System Status:

• Check SW loop header pressures:
• PPCS SW low pressure alarm status -NOT LOW
• PPCS point ID P2160
• PPCS point ID P2161
• Pressure in both loops STABLE OR RISING
• Check SW loop header pressures

-NOTE: The SW System GREATER THAN 40 PSIG pressures are< 40 psig. CO/ * (Step ?a RNO) Locally isolate selected NOTE: The CRS will AO SW loads as desired (Refer to ATT 2.2, dispatch an AO. ATIACHMENT 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 D pump in loop B NOTE: Both C and D SW Pumps are OFF. * (Step 7b RNO) Perform the following:
• Continue efforts to start at least one SW pump in each loop.
• IF at least two SW pumps can be NOTE: Two SW Pumps operated, THEN, ...... cannot be operated.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# 4 Page 25 of 57 Event

Description:

Fault on 480V Bus 18/SW Pump D fails to start Time .Pos .. 1 Expected Actions/Behavior

. . Comments

. : o', '<:",'

• IF NOT, THEN return to Step 3 . NOTE: The CRS will continue efforts to restore the SW System. TECHNICAL SPECIFICATION 3.8.1, AC: SOURCES -MODES 1, 2, 3 AND 4 CRS LCO 3.8.1 The following AC electrical sources shall be OPERABLE:
• One qualified independent offsite power circuit connected between th1e offsite transmission network and each of the onsite 480 V safeguards busies required by LCO 3.8.9, "Distribution Subsystems

-MODES 1, 2, 3, and 4"; and

• Two emergency diesel generators (DGs) capable of supplying their respective onsite 480 V safeguards busies 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 hour inoperable. 3.8.1.1 for AND the offsite Once per 8 circuit. hours thereafter B.2Declare 4 hours from required discovery of feature(s) Condition B supported by concurrent with the inoperable inoperability of DG inoperable n;idundant when its required required feature(s). redundant feature(s) is inoperable. AND Appendix D Operator Action Form ES-D-2 Op Test No.: N2D14-301 Scenario# 5 Event# Page 26 ------4 of 57 Event

Description:

Fault on 480V Bus 18/SW Pump D fails to start TJme Pos. Expected Actions/Behavior . Comments ' B.3.1 24 hours Determine OPERABLE DG is not inoperable due to common cause failure. OR B.3.2 24 hours Perform SR 3.8.1.2 for OPERABLE DG. AND B.4 Restore DG 7 cjays to OPERABLE status. TECHNICAL SPECIFICATION 3.8.9, DISTRIBUTION SYSTEMS -MODES 1, 2, 3 AND4 CRS LCO 3.8.9 Train A and Train B of the following electrical power distribution subsystems shall be OPERABLE:

• AC power . CRS APPLICABILITY:

MODES 1, 2, 3, and 4. CRS ACTIONS CRS CONDITION REQUIRED COMPLETION ACTION TIME A. OneAC A.1 Restore AC 8 hours electrical electrical power power distribution distribution train train to inoperable OPERABL E status. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# _4 _____ Page 27 of 57 Event

Description:

Fault on 480V Bus 18/SW Pump D fails to start Time *Pos/ , ' 'Expected Actions/Behav\or: Comments 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. CRS APPLICABILITY: MODES 1, 2, 3, and 4. CRS CONDITION REQUIRED COMPLETION ACTION TIME A. One SW A. 1 Restore SW 14 days pump pump to inoperable OPERABLE status. At the discretion of the Lead Examiner move to Event #5. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# 5 Page 28 of 57 -----Event

Description:

PCV-135 fails CLOSED During the recovery, Letdown Pressure Control Valve PCV-135 will fail closed causing 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. SIM DRIVER Instructions: Operate Trigger #3 (CVC07 A (0%)) Indications Available:

• PCV-135 Controller output goes to 100
• MCB Annunciator A-11, LETDOWN LINE HI PRESS 400 PSI
• Letdown flow drops to 0 . ,,, Expected

.Actions/Behavior . *. .. * .*** . Time Pos. Com merits <, AR-A-11, LETDOWN LINE HI PRESS 400 PSI HCO (Step 1) Adjust PCV-135 controlleir 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 is NOTE: The CRS may notify consistent with letdown orifice in service. theWCC. SIM DRIVER: as WCCS, acknowledge. NOTE: The CRS will likely conduct a Plant Status Brief. At the discretion of the Lead Examiner move to Event #6. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# _6 _____ Page of Event

Description:

Loss of Compensating Voltage to Intermediate Range N35 Shortly afterwards, 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. SIM DRIVER Instructions: Operate Trigger #4 (NISOSA (1 E-8%)) Indications Available:

• MCB Annunciator E-9, IR N-35 LOSS OF COMPENSATING VOLTAGE Time Expected Actions/Behavior
• Comments AR-E-9, IR N-35 LOSS OF COMPENSATION VOLTAGE CRS (Step 1) Refer to ER-NIS.2 NOTE: The CRS will go to ER-NIS.2.

ER-NIS.2, IR MALFUNCTION co (Step 6.1) 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 position. CRS (Step 6.2) NOTIFY l&C to repair the faulty NOTE: The CRS may notify channel. the WCC/l&C. SIM DRIVER: as WCCS/l&C, acknowledge. CRS (Step 6.3) 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.: N2014-301 Scenario# 5 Event# _6 _____ Page of Event

Description:

Loss of Compensating Voltage to Intermediate Range N35 Time r " J .* exi)ected . :. Comments Pos. .'* .. . NOTE: The CRS will evaluate Technical Specifications and determine that per Condition E, reactor SID is required to reduce power to <SE-11 amps (can't raise power> 5% due to CCW pump failure and Mode Change requirements). 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. CRS APPLICABILITY: According to Table 3.3.1-1. CRS ACTIONS CONDITION REQUIRED COMPLETION ACTION TIME A. One or more A.1 Enterthe Immediately Functions Condition with one referenced channel in Table inoperable. 3.3.1-1 for OR the Two source channel(s). range channels inoperable. NOTE: The CRS will E. As required E.1 Reduce 2 hours recognize that Function 3 by Required THERMAL requires ACTION E.1, and ActionA.1 POWER to that No mode change with and < 5E-11 referenced amps. CCW pump inoperable. by Table OR Power must be reduced to< 3.3.1-1. SE-11 amps. E.2 Increase 2 hours THERMAL POWER to RTP. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# _6 _____ Page l!..._ of _5_7_"""' Event

Description:

Loss of Compensating Voltage to Intermediate Range N35 Time Pos. Expected Actions/Behavior I Comments S. As required S.1 Verify 1 hour by Required interlock is NOTE: The CRS will Action A.1 in required recognize that Function 16.a and state for referenced existing requires ACTION S.1. 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 S/D is required to reduce power to <5E-11 amps. At the discretion of the Lead Examiner move to Events #7-9. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# _7_._8_&_9 ___ Page ::___of _5_7_1 Event

Description:

B ARV fails CLOSED/B SG Safety Valve Lifts and fails OPEN/ Failure of Reactor to Trip in AUTO only/B Steam Generator Tube Rupture/1% Failed Fuel After this, the B ARV will inadvertently close, and one SG Safety valve will open and stick open. The reactor will fail to trip automatically, and the operator will need to manually trip the reactor and enter E-0, Reactor Trip or Safety Injection. On the trip approximately 1 % failed fuel will occur. operator will proceed through E-0, and then transition to E-2, Faulted Steam Generator Isolation. While in E-2 a large Steam Generator Tube Rupture will develop on the B Steam Generator, and the operator will transition to E-3, Steam Generator Tube Rupture. Because the B Steam Generator is both Ruptured and Faulted, the operator will transition to ECA-3.1, SGTR with Loss of Reactor Coolant, Subcooled Recovery Also, while in E-2, it is expected that high temperatures will occur on the RCPs du1e to low service water flow, requiring the crew to stop these pumps. Because of this the NC condition of the RCS will tend to lower loop Tcold temperatures causing an Orange/Red condition on RCS Integrity. If so, the operator may need to transition to FR-P.1, Response to Imminent Pressurized Thermal Shock Condition. The scenario will terminate at Step 15 of ECA-3.1, after the crew has monitored conditions for continuing with the Subcooled Recovery procedure, or upon transition to FR-P.1. SIM DRIVER Instructions: Operate Trigger #5 (STM05B (0%) and STM09B (40%)) Indications Available:

• The B ARV closes.
• The B SG pressure rises and Safety Valve(s) lift.
• One SG Safety Valve in the B SG sticks open causing SG/RCS pressure to lower. , ... Time ... 1* Pos 1* IC . Expected Actions/Beh'aviof.
• .. ***. ,. Comments

_,. ... . <- ' ', .,, E-0, REACTOR TRIP OR SAFETY INJECTION HCO (Step 1) Verify Reactor Trip: Immediate Action 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 CONTHOL AND SHUTDOWN RODS ON BOTTOM HCO/ (Step 1 RNO) Manually trip reactor. Immediate Action co Appendix 0 Operator Action Form ES-0-2 Op Test No.: N2014-301 Scenario# 5 Event# _1 .......... s_&_9,___ __ Page of _5_7_..;i Event

Description:

' I Time Pos ..* B ARV fails CLOSED/B SG Safety Valve Lifts and fails OPEN/ Failure of Reactor to Trip in AUTO only/B Steam Generator Tube Rupture/1 % Failed Fuel ', Expected Actions/Behavior Comments IF reactor trip breakers NOT open, THEN perform the following:

• Open Bus 13 and Bus 15 normal feed breakers.
• Verify rod drive MG sets tripped .
• Close Bus 13 and Bus 15 normal feed breakers.
• Reset lighting breakers

. IF the reactor will NOT trip ......... NOTE: De-energizing Bus 13 and 15 causes the Rods to insert. CRITICAL TASK 1. Manually trip the reactor prior to transition to FR-S.1, "Response to Nuclear Generation/ A TWS." 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 recoQnize a failure of the automatic actuation of the RPS. co (Step 2) Verify Turbine Stop Valves -Immediate Action CLOSED co (Step 3) Verify Both Trains of AC Emergency Immediate Action Busses Energized to at Least 440 VOLTS:

• Bus 14 and Bus 18 NOTE: Bus 18 is de-energized.
• Bus 16 and Bus 17 Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

5 Event# _7_.,_8_&_9___ Page .:::...__ of _57_-11 Event

Description:

Time Pos. HCO HCO HCOI co HCOI co B ARV fails CLOSED/B SG Safety Valve Lifts and fails OPEN/ Failure of Reactor to Trip in AUTO only/B Steam Generator Tube Rupture/1 % Failed Fuel

• Actions/Beha"\ilor

. Comments (Step 3 RNO) Attempt to start any failed Immediate Action emergency DIG to restore power to all AC NOTE: The A DIG breaker emergency busses. has previously failed, and actions taken will be dependent upon how this was mitigated previously. IF Bus 14 AND Bus 16 are deenergized, NOTE: Susses 14 and 16 THEN go to ........ are both energized. (*Step 4) Check if SI is Actu.ated: Immediate Action NOTE: SI may or may NOT have actuated at this point. If it has, continue with Step 5. * (Step 4a RNO) IF any of the following conditions are met, THEN manually actuate SI and Cl:

• 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
• IF SI is NOT required,

..... * (Step 4b) SI sequencing -BOTH NOTE: The SG Safety Valve TRAINS STARTED. being stuck OPEN will eventually require that SI be actuated. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# _7_.,_8_&_9 ___ Page of _5_7_-11 Event

Description:

. *. Tame .. Pos. HCO/ co HCO/ co HCO CRS B ARV fails CLOSED/B SG Safety Valve Lifts and fails OPEN/ Failure of Reactor to Trip in AUTO only/B Steam Generator Tube Rupture/1% Failed Fuel E;>cpected Actions/Behavior; Comments

. *. (Step 4b RNO) Manually actuate SI and Cl. Foldout Page NOTE: The crew will monitor these conditions throughout the performance of E-0. RCP TRIP CRITERIA LOSS OF SW CRITERIA AFW SUPPLY SWITCHOVER CRITERION SFP COOLING CRITERIA NOTE: The CRS may dispatch an AO to address the status of the SFPCS. If so, SIM DRIVER acknowledge as AO, and report in 5 Minutes that the SFPCS is operating normally.

(*Step 5) Verify CNMT Spray Not Required:

• Annunciator A-27, CNMT SPRAY -EXTINGUISHED
• CNMT pressure

-LESS THAN 28 PSIG (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-0. Examiner following operator performing ATT-27.0 continue below. Examiner following operator NOT performing ATT-27.0 continue at Page 39. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# _7 ......... a .... &_9 ___ Page of Event

Description:

Time Pos. B ARV fails CLOSED/B SG Safety Valve Lifts and fails OPEN/ Failure of Reactor to Trip in AUTO only/B Steam Generator Tube Rupture/1% Failed Fuel Expected Actions/Behavior '.: Comments . ,. E-0, 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 HCOI (Step 2) Verify CNMT RECIRC Fans co Running:
• All fans -RUNNING
• Charcoal filter dampers green status lights -EXTINGUISHED HCOI (Step 3) Check If Main Steamlines Should Be co Isolated:
• Any MSIV -OPEN NOTE: B MSIV is CLOSED, Both MSIVs may be Closed.
• Check CNMT pressure-LESS THAN 18 PSIG
• Ensure BOTH MSIVs closed and go to Step 4. HCOI (Step 4) Verify MFW Isolation:

co

• MFW pumps -TRIPPED
• MFW Isolation valves -CLOSED
• SIG A, AOV-3995
• SIG B, AOV-3994
• SIG Blowdown and sample valves -CLOSED Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

5 Event# _.7._8_&_9 ___ Page of _5_7_-11 Event

Description:

Time** Pos. HCO/ co HCO/ co HCO/ co HCO/ co B ARV fails CLOSED/B SG Safety Valve Lifts and fails OPEN/ Failure of Reactor to Trip in AUTO only/B Steam Generator Tube Rupture/1 % Failed Fuel . . . . *. . : . Comments .Expected Actions/Behavior (Step 5) Verify At Least Two SW Pumps -RUNNING (Step 6) Verify Cl and CVI:

• Cl and CVI annunciators

-LIT

• Annunciator A-26, CNMT ISOLATION
• Annunciator A-25, CNMT VENTILATION ISOLATION
• Verify Cl 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 (Step 7) Check CCW System Status:
• Verify CCW pump-AT LEAST ONE RUNNING (Step 8) Verify SI and RHR Pump Flow:
• SI flow indicators

-CHECK FOR FLOW

• RHR flow indicator

-CHECK FOR FLOW Appendix D Operator Action Form ES-0-2 Op Test No.: N2014-301 Scenario# 5 Event# _7_.,_8_&_9 ___ Page of _5_7_-11 Event

Description:

Time HCO/ co HCO/ co HCO/ co B ARV fails CLOSED/B SG Safety Valve Lifts and fails OPEN/ Failure of Reactor to Trip in AUTO only/B Steam Generator Tube Rupture/1 % Failed Fuel ,,,, , , , , , ,, Actions/Behavior,* ,: Comments (Step ?b RNO) IF RCS pressure less than NOTE: RCS Pressure is > 150 psig ....... 150 psig. (Step 9) Verify SI Pump and RHR Pump Emergency Alignment:

• RHR pump discharge to Rx vessel deluge -OPEN
• MOV-852A
• MOV-8528
• Verify SI pump C -RUNNING
• Verify SI pump A -RUNNING
• Verify SI pump B -RUNNING
• Verify SI pump C discharge valves -OPEN
• MOV-871A
• MOV-8718 (Step 10) Verify GREATS Actuation:
• At least one damper in each flowpath

-CLOSED

• Normal Supply Air
• Normal Return Air
• Lavatory Exhaust Air
• GREATS fans-BOTH RUNNING (Step 11) Verify Cl and CVI During a Fire Event A confirmed fire has occurred in the' control complex or cable tunnel (fire systems S05, S06,S08,Z05,Z18,orZ19).

Go to END , Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# _7_.,_8_&_9 ___ Page ::.._ of _5_7_..;1 Event

Description:

Time Pos. HCO/ co HCO/ co co CO/ HCO B ARV fails CLOSED/B SG Safety Valve Lifts and fails OPEN/ Failure of Reactor to Trip in AUTO only/B Steam Generator Tube Rupture/1% Failed Fuel Expected Actions/Behavior Comments E-0, REACTOR TRIP OR SAFETY INJECTION Examiner following operator NOT performing ATT-27.0 continue HERE. (Step 7) Verify Both MDAFW Pumps Running (Step 8) Verify AFW Valve Alignment:

• AFW flow-INDICATED TO BOTH S/G(s)
• AFW flow from each MDAFW pump -LESS THAN 230 GPM (*Step 9) Monitor Heat Sink: NOTE: The A SG is likely > 7%, and the crew will stop AFWflow.
• Check SIG narrow range level -GREATER THAN 7% [25% ADVERSE CNMT] in any SIG
• Check SIG narrow range level BOTH SIG LESS THAN 50%
• Control feed flow to maintain SIG narrow range level between 7% [25cVo adverse CNMT] and 50%. (Step 10) Check If TDAFW Pump Can Be Stopped:
• Both MDAFW pumps -RUNNING
• PULL STOP TDAFW pump steam supply valves
• MOV-3504A
• MOV-3505A Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

5 Event# _7_.,_8_&_9 ___ Page _5_7_-u Event

Description:

Time Pos. HCO HCO HCO HCO B ARV fails CLOSED/B SG Safety Valve Lifts and fails OPEN/ Failure of Reactor to Trip in AUTO only/B Steam Generator Tube Rupture/1 % Failed Fuel ' Expected Actions/Behavior Co"'ments (Step 11) Check CCW Flow to RCP Thermal Barriers:

• Annunciator A-7, RCP 1A CCW RETURN HI TEMP OR LO FLOW EXTINGUISHED
• Annunciator A-15, RCP 1 B CCVV RETURN HI TEMP OR LOW FLOW -EXTINGUISHED

(*Step 12) Monitor RCS Tavg -STABLE AT NOTE: A cooldown is in OR TRENDING TO 547°F progress through the SG Safety Valve. (Step 12 RNO) If temperature less than 547°F 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 SIG.
• WHEN SIG level greater than /'% [25% adverse CNMT] in one SIG, THEN limit feed flow to that required to maintain level in at least one SIG.
• IF cooldown continues, THEN close both MS IVs. (Step 13 ) Check PRZR PORVs and Spray Valves:
• PORVs -CLOSED
• Auxiliary Spray Valve (AOV-2916)

-CLOSED Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# _7 __ ,_8_&_9 ___ Page _41_ of _57_-11 Event

Description:

Time .. I* HCO CRS co CRS B ARV fails CLOSED/B SG Safety Valve Lifts and fails OPEN/ Failure of Reactor to Trip in AUTO only/B Steam Generator Tube Rupture/1% Failed Fuel ... *. . . Comments Expected .Actions/Behavior

• Check PRZR pressure

-LESS THAN 2260 PSIG

• Normal PRZR spray valves -CLOSED
• PCV-431A
• PCV-431 B (Step 14) Monitor RCP Trip Criteria:
• RCP status -ANY RCP RUNNING
• SI pumps -AT LEAST TWO RUNNING
• RCS pressure minus maximum SIG pressure

-LESS THAN 210 psi [240 psi adverse CNMTJ (Step 14c RNO) Go to Step 15. (Step 15) Check If SIG Secondary Side Is NOTE: The B SG is Intact: depressurizing in an

• Pressure in both SIGs-ST ABLE OR uncontrolled manner. RISING
• Pressure in both SIGs-GREATER THAN 110 PSIG (Step 15 RNO) IF any SIG pressure lowering in an uncontrolled manner OR completely depressurized, THEN go to E-2, FAUL TED STEAM GENERATOR ISOLATION, Step 1. NOTE: The CRS will go to E-2. NOTE: The CRS will likely conduct an Alignment Brief. SIM DRIVER Instructions:

Operate Trigger #6 (SGN04B (60%)/RCS16 (1%)) Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# _7 .... _8_&_9 ___ Page Event

Description:

B ARV fails CLOSED/B SG Safety Valve Lifts and fails OPEN/ Failure of Reactor to Trip in AUTO only/B Steam Generator Tube Rupture/1% Failed Fuel . . . Time Pos ... * .. ... .* Expected Actions/Behavior Indications Available:

• The B SG wide range level starts to rise.
• The RCS pressure starts to lower.
• R-32 alarms E-2, FAUL TED STEAM GENERATOR ISOLATION HCO/ Foldout Page co LOSS OF SW CRITERIA CO (Step 1) Check MSIV of Faulted S/G(s) -CLOSED CO (Step 2) Check If Any SIG Secondary Side Is Intact:
• Check pressure in S/G A-STABLE OR RISING OR
• Check pressure in S/G B -ST ABLE OR RISING CO (Step 3) Check Faulted S/G Status:
• Faulted S/G pressure

-LOWERING IN AN UNCONTROLLED MANNER OR

• Faulted S/G -COMPLETELY DEPRESSURIZED CO (Step 4) Isolate Feed Flow to Faulted S/G:
• Close or verify closed the following valves: NOTE: The crew will monitor these conditions throughout the performance of E-2. NOTE: BOTH MSIVs are CLOSED. NOTE: The A SG is intact. NOTE: The B SG is de pressurized.

Appendix D Operator Action Form ES-0-2 Op Test No.: N2014-301 Scenario# 5 Event# _7 ..... _8_&_9 ___ Page of _5_7_-11 Event

Description:

Time ; Pos. co *

• B ARV fails CLOSED/B SG .Safety Valve Lifts and fails OPEN/ Failure of Reactor to Trip ini AUTO only/B Steam Generator Tube Rupture/1

% Failed Fuel .

• Actions/Behavior Comments
• Faulted SIG MDAFW pump discharge valve
• SIG B, MOV-4008
• Faulted SIG MFW valve and bypass valve -CLOSED
• SIG B, HCV-476 and HCV-481
• MFW isolation valves -CLOSED
• SIG B, AOV-3994
• MDAFW pump crosstie valves -BOTH CLOSED
• MOV-4000A
• MOV-40008
• Faulted SIG SAFW pump discharge valve
• SIG B, MOV-97048 Pull stop faulted SIG MDAFW pump Close faulted SIG TDAFW flow control valve
• SIG B, AOV-4298 NOTE: If Feed flow has NOT been isolated previously, it will be isolated here. CRITICAL TASK: 2. 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 lnteqritv, Subcriticalitv (if cooldown is allowed to continue uncontrollably). co (Step 5) Isolate Steam Flow From Faulted SIG:

• Verify faulted SIG ARV -CLOSED Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

5 Event# _7_.,_8_&_9 ___ Page of Event

Description:

T" .* . . 1me Pos. co HCO co B ARV fails CLOSED/B SG Safety Valve Lifts and fails OPEN/ Failure of Reactor to Trip in AUTO only/B Steam Generator Tube Rupture/1% Failed Fuel ' Expected Actions/Behavior ' Comments

• SIG B, AOV-3410
• Close faulted SIG TDAFW pump steam supply valve and place in PULL STOP
• SIG B, MOV-3504A
• Verify faulted SIG blowdown and sample valves -CLOSED
• SIG B, AOV-5737 and AOV-5736
• Dispatch AO to complete faulted SIG NOTE: The CRS will isolation (Refer to ATT-10.0, dispatch an AO. ATTACHMENT FAULTED Sl1G) SIM DRIVER: as AO, acknowledge and After 3 Minutes report that the Attachment is complete.

(*Step 6) Monitor Intact SIG Levels:

• Narrow range level -GREATER THAN NOTE: The B SG has a 7% [25% adverse CNMT] SGTR.
• Control feed flow to maintain narrow range level between 17% [25% adverse CNMT] and 50% (Step 7) Check Secondary Radiation Levels -NORMAL
• Steamline radiation monitor (IR-31 and R-NOTE: R-32 will be in alarm. 32)
• Air ejector radiation monitor (R-15)
• SIG blowdown radiation monitor (IR-19)
• Request Chem Tech sample SIGs for NOTE: The CRS will activity request that Chemistry sample. SIM DRIVER: as chemistry, acknowledge.

(Step 7 RNO) IF steamline radiation monitors NOT available, THEN dispatch AO to locally check steamline radiation. Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# _7_,,,-.8_&_9._ __ Page of _5 ..... Event

Description:

' Time Pos. co HCO/ co CRS HCO B ARV fails CLOSED/B SG Safety Valve Lifts and fails OPEN/ Failure of Reactor to Trip in AUTO only/B Steam Generator Tube Rupture/1% Failed Fuel Expected

Actions/Behavior

.* .. . Comments IF abnormal radiation levels detected in any SIG, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1. NOTE: It is expected that A-7/A-15 will alarm because of limited SW flow to CCW. If so, the RCPs will need to be stopped due to hi temperatures. NOTE: The CRS will go to E-3. E-3, STEAM GENERATOR TUBE RUPTURE Foldout Page NOTE: The crew will monitor these conditions throughout the performance of E-3. LOSS OF SW CRITERIA SI REINITIATION CRITERIA SECONDARY INTEGRITY CRITERIA COLD LEG RECIRCULATION SWITCHOVER CRITERIA AFW SUPPLY SWITCHOVER CRITERION MULTIPLE S/G TUBE RUPTURE CRITERIA (Step 1) Dispatch an AO to standby at door NOTE: The CRS may direct 44 in the Turbine Building. the AO to standby at door 44 in the Turbine Building. If so, SIM DRIVER acknowledge as AO. (*Step 2) Monitor RCP Trip Criteria: Appendix D Operator Action Form ES-D-2 Op Test No.: N2D14-301 Scenario# 5 Event# ...... Page 57 Event

Description:

Time Pos. co co B ARV fails CLOSED/B SG Safety Valve Lifts and fails OPEN/ Failure of Reactor to Trip in AUTO only/B Steam Generator Tube Rupture/1 % Failed Fuel Expected Actions/Behavior Comments

• RCP status-ANY RCP RUNNING NOTE: It is likely that both RCPs are OFF due to high temperatures (Low SW flow).
• 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 1 c RNO) Go to step 3 (Step 3) Identify Ruptured SIG(s):

• Unexpected rise in either SIG narrow NOTE: The CO may report range level that there is an unexpected increase in B SG Level. OR
• High radiation indication on main steamline radiation monitor
• R-31 for SIG A
• R-32 for SIG B OR
• RP reports high radiation from SIG NOTE: The CRS will activity sample. request that RP assist the Chemistry sample. SIM DRIVER: as RP, acknowledge, and report that the B SG has high radioactivity.

(Step 4) Isolate Flow From Ruptured SIG(s): NOTE: B is ruptured

• Adjust ruptured SIG ARV controller to 1050 psig in AUTO
• Check ruptured SIG ARV -CLOSED
• Close ruptured SIG TDAFW pump steam supply valve and place in PULL STOP
• SIG A, MOV-3504A Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

5 Event# _7_,_8_&_9 ___ Page of _5_7 __ 11 Event

Description:

. Time Pos. * .. co co co B ARV fails CLOSEO/B SG Safety Valve Lifts and fails OPEN/ Failure of Reactor to Trip in AUTO only/B Steam Generator Tube Rupture/1% Failed Fuel Expected ACtions/Behavior Comments " < 'I '

• Verify ruptured S/G blowdown valve -CLOSED
• SIG B, AOV-5737 (Step 5) Complete Ruptured SIG Isolation:
• Close ruptured SIG MSIV -RUPTURED SIG MSIV CLOSED
• Dispatch AO to complete ruptured SIG NOTE: The CRS will isolation (Refer to ATT-16.0, dispatch an AO. ATTACHMENT RUPTURED S/G part A) SIM DRIVER: as AO, acknowledge, and perform all remotes associated with ATT-16.0 (Schedule File ATT16SGBpartA.sch

). (Step 6) Check Ruptured SIG Level:

• Narrow range level -GREATER THAN 7% [25% adverse CNMT] (Step 6a RNO) IF ruptured S/G NOT faulted, NOTE: The CRS will THEN ..... determine that the Ruptured SG is Faulted, and continue.
• Close MDAFW pump discharge valve to ruptured SIG
• SIG 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-40008 Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

5 Event# _7_,,_8_&_9 ___ Page _5_7--11 Event

Description:

Time Pos. co CRS B ARV fails CLOSED/B SG Safety Valve Lifts and fails OPEN/ Failure of Reactor to Trip in AUTO only/B Steam Generator Tube Rupture/1 % Failed Fuel *;,.* ' . . . Expected Actions/Behavior** Comments (Step 7) Verify Ruptured S/G Isolated:

• Check ruptured MSIV -CLOSED
• Check TDAFW pump steam supply from ruptured SIG -ISOLATED
• Ruptured S/G pressure

-GREATER NOTE: The B SG is less THAN 500 PSIG than 500 psig. (Step 7 RNO) Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -SUBCOOLED RECOVERY

DESIRED, Step 1. NOTE: The CRS will go to ECA-3.1.

ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED Examiner NOTE: It is expected that at some time during the performance of ECA-3.1, an Orange/Red Path may exist on RCS Integrity. If so, Terminate Exam at the discretion of the Lead Examiner. HCO/ Foldout Page NOTE: The crew will co monitor these conditions throughout the performance of ECA-3.1. LOSS OF SW CRITERIA SI REINITIATION CRITERIA SATURATED RECOVERY CRITERIA SECONDARY INTEGRITY CRITERIA COLD LEG RECIRCULATION SWITCHOVER CRITERIA AFW SUPPLY SWITCHOVER CRITERION Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# _7_..,_8_&_9 ___ Page of _5_7_-11 Event

Description:

Time Pos. HCO HCO co co CRS HCO/ co B ARV fails CLOSED/B SG Safety Valve Lifts and fails OPEN/ Failure of Reactor to Trip in AUTO only/B Steam Generator Tube Rupture/1 % Failed Fuel Expected Actions/Behavior.

• .. Comments

. (Step 1) Reset SI (Step 2) Reset Cl:

• Depress Cl reset pushbutton
• Verify annunciator A-26, CNMT ISOLATION

-EXTINGUISHED (Step 3) Verify Adequate SW Flow: * .Check at least two SW pumps. -RUNNING (Step 3.a RNO) Manually start SW pumps as power supply permits (257 kw each).

• IF less than two SW pumps running, NOTE: Only one SW Pump THEN perform the following:

is running.

• Ensure SW isolation

.

• Refer to AP-SW.2, LOSS OF NOTE: The CRS may refer SERVICE WATER to AP-SW .2, however, no additional SW Pumps can be started.
• Dispatch AO to establish normal NOTE: This task is already shutdown alignment (Refer to ATT-17.0, in progress.

ATTACHMENT SD-1) (Step 4) Establish IA to CNMT:

• Verify non-safeguards busses energized from offsite power
• Bus 13 normal feed -CLOSED OR
• Bus 15 normal feed -CLOSED
• Verify SW isolation valves to turbine NOTE: These valves are building

-OPEN closed. Appendix D Operator Action Form ES-0-2 Op Test No.: N2014-301 Scenario# 5 Event# _7_,,_8_&_9 ___ Page of _5_7 _ _,, Event

Description:

Time ', ,, ', Pos .. co co CRS B ARV fails CLOSED/B SG Safety Valve Lifts and fails OPEN/ Failure of Reactor to Trip in AUTO only/8 Steam Generator Tube Rupture/1 % Failed Fuei ' " ,',, :\,' ' " " Comments .Expected Actions/Bebavior . . . ,. . ,

• MOV-4613 and MOV-4fi70
• MOV-4614 and MOV-43664 (Step 4.b RNO) Perform the following:

Restore IA using Service Air Restore IA NOTE: The CRS will start using Service Air the Diesel SA Compressor.

• Verify adequate air compressor(s)-

RUNNING

• Check IA supply:
• Pressure

-GREATER THAN 60 PSIG

• Pressure

-ST ABLE OR RISING

• Reset both trains of XY relays for IA to CNMT AOV-S392
• Verify IA to CNMT AOV-S392

-OPEN (Step S) Monitor AC Bus Power:

• Verify Safeguards Busses 14, 16, 17, NOTE: Bus 18 is de-and 18-GREATER THAN 440 VOLTS energized.

(Step Sa RNO) Perform the following:

• Restore bus voltage (Refer to AP-ELEC.2, SAFEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW FREQUENCY)
• Continue with Step 6. WHEN bus voltage restored, THEN do Step Sb.
• Verify All AC Busses -BUSSES ENERGIZED BY OFFSITE POWER
• Normal feed breakers to all 480 volt busses -CLOSED Appendix D Operator Action Form ES-0-2 Op Test No.: N2014-301 Scenario#

5 Event# _7 ..... _8_&_9 ___ Page of _5_7_.,.1 Event

Description:

. TI me

• HCO HCO CRS co B ARV fails CLOSED/B SG Safety Valve Lifts and fails OPEN/ Failure of Reactor to Trip in AUTO only/B Steam Generator Tube Rupture/1%

Failed Fuel' Expected Actions/Behav.ior* Comments .

• Emergency DIG output breakers

-OPEN (Step 6) Deenergize PRZR Heaters

• Place PRZR proportional heaters in PULL STOP
• Place PRZR backup heaters to OFF
• Consult TSC for a recommended NOTE: The CRS will contact minimum indicated PRZR level that will the TSC. ensure heaters are covered.

SIM DRIVER: as TSC, acknowledge, indicate that TSC is NOT manned, and will call when active. (Step 7) Monitor If CNMT Spray Should Be Stopped:

• CNMT spray pumps -ANY HUNN ING NOTE: The CS Pumps are NOT running.
• (Step 7a RNO) Go to Step 8 . (Step 8) Check Ruptured SIG Level:
• Narrow range level -GREATER THAN 7% [25% adverse CNMT]
• Close MDAFW pump dischar9e valve to ruptured SIG
• SIG A, MOV-4007
• SIG B, MOV-4008
• Pull stop MDAFW pump for ruptured SIG
• Close TDAFW pump flow control valve to ruptured SIG
• SIG A, AOV-4297
• SIG B, AOV-4298 Appendix D Operator Action Form ES-0-2 Op Test No.: N2014-301 Scenario#

5 Event# _7_.,_8_&_9 ___ Page of Event

Description:

Time Pos. HCO CRS HCO CRS B ARV fails CLOSED/B SG Safety Valve Lifts and fails OPEN/ Failure of Reactor to Trip i11 AUTO only/B Steam Generator Tube Rupture/1 % Failed Fuel Actfons/Behavior Comments'

• Verify MDAFW pump crosstie valves -CLOSED
• MOV-4000A
• MOV-4000B

(*Step 9) Monitor If RHR Pumps Should Be Stopped:

• RHR pumps -ANY RUNNING IN NOTE: The RHR Pumps are INJECTION MODE BOTH running.
• Check RCS pressure:
• Pressure

-GREATER THAN 300 psiq f350 psiq adverse CNMTl

• Pressure

-ST ABLE OR RISING

• Stop RHR pumps and place in AUTO (Step 10) Evaluate Plant Status:
• Check auxiliary building radiation

-NORMAL

• Plant vent iodine (R-1 OB)
• Plant vent particulate (R-13)
• Plant vent gas (R-14)
• CCW liquid monitor (R-17)
• Letdown line monitor (R-9)
• CHC pump room (R-4)
• Direct Chem Tech to obtain following NOTE: The CRS may samples:

contact Chemistry. SIM DRIVER: as Chemistry, acknowledge.

• RCS boron
• RCS activity
• CNMT hydrogen
• CNMT sump boron Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario#

5 Event# _...7,._8_&_9 ___ Page of Event

Description:

Time .. . Pos. HCO HCO HCO/ co HCO B ARV fails CLOSED/B SG Safety Valve Lifts and fails OPEN/ Failure of Reactor to Trip in AUTO only/B Steam Generator Tube Rupture/1 % Failed Fuel . . . " .. . . . . : : .. : '.Expected Actions/Behavror

• Comments
• CNMTsump pH
• Verify adequate Rx head cooling:
• Verify at least one control rod shroud fan -RUNNING
• Verify one Rx compartment cooling fan -RUNNING (Step 10.c.2 RNO) Perform the following:
• Dispatch AO to locally reset UV NOTE: The CRS will relays at MCC C and MCC D. dispatch an AO. SIM DRIVER: as AO, acknowledge, and use EDS033 and 034 =RESET.
• Manually start one fan as power NOTE: The HCO starts one supply permits (23 kw) Rx Compartment Cooling Fan. (Step 11) Check Power Availability to Charging Pumps:
• Check Normal Power Available To Charging Pumps:
• Bus 14 normal feed breaker -CLOSED
• Bus 16 normal feed breaker -CLOSED
• Verify adequate Safeguard Bus capacity to run charging pumps (6 amps each)
• Station Service transformer 14 ammeter
• Station Service transformer 16 ammeter (Step 12) Establish 75 GPM Charging Flow:
• Charging pumps -ANY RUNNING
• Align charging pump suction to RWST:
• LCV-112B

-OPEN Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# 7, 8 & 9 Page 57 Event

Description:

Tirne Pos. co co co co B ARV fails CLOSED/B SG Safety Valve Lifts and fails OPEN/ Failure of Reactor to Trip in AUTO only/B Steam Generator Tube Rupture/1 % Failed Fuel Expected Actions/EJehavior. / Comments* .

• LCV-112C CLOSED
• Start charging pumps as necessary and establish 75 gpm total charging flow
• Charging line flow
• Seal injection (Step 13) Check If SIG Secondary Side Is NOTE: The A SG is intact. Intact:
• Pressure in both SIGs -ST ABLE OR RISING
• Pressure in both SIGs -GREATER THAN 110 PSIG (*Step 14) Monitor Intact SIG levels:
• Narrow range level -GREATER THAN 7% [25% adverse CNMT]
• Control feed flow to maintain narrow range level between 17% [251% adverse CNMT] and 50% (Step 15) Initiate RCS Cooldown To Cold Shutdown:
• Establish and maintain cooldown rate in RCS cold legs -LESS THAN 100°F/HR
• Use RHR system if in service
• Dump steam to condenser from intact SIG (*Step 16) Monitor Conditions For Subcooled Recovery:
• Check RWST level-GREATER THAN 56%
• Check ruptured SIG narrow level -LESS NOTE: If SG Level < 90%, THAN 90% [80% adverse CNMT] continue in ECA-3.1.

Appendix D Operator Action Form ES-D-2 Op Test No.: N2014-301 Scenario# 5 Event# _7_.,_8_&_9 ___ Page .=__ of Event

Description:

Time .. ** *.Pas .. .

• B ARV fails CLOSED/B SG Safety Valve Lifts and fails OPEN/ Failure of Reactor to Trip in AUTO only/B Steam Generator Tube Rupture/1

% Failed Fuel / . . . . . . . cc>mmellts Expected

• Actions/13ehavior.

. ' . (Step 15b RNO) Consult TSC to determine if recovery should be completed using ECA-3.2, SGTR WITH LOSS OF REACTOR COOLANT -SATURATED RECOVERY DESIRED. Terminate the Exam at the discretion of the Lead Examiner SRO Examiner Perform Admin JPM A4e on CRS Core Age: BOL 0%, Equilibrium Xe Outside Air Temp= 51°F Water Temp= 50°F TURNOVER SHEET for NRC Exam Scenario

1. 5 Procedure in Use: ACTIONS/NOTES:

• 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 an A MFW Pump failure.
• The repairs have been made and the plant is ready to be started back up.
• The crew is directed to pull rods to the point of adding heat ..,.. ______________________________

.... (POAH), and stabilize power between 0.5 and 1 %; and start Boron: 2094 ppm BAST: 17,400 ppm RCS Activity: Normal Equipment Problems!OOS: See NOTES 10% at 1% per minute 10% at 10% per hour 50% at 1 % per minute 50% at 10% per hour RCS LEAKAGE: (gpm) Total: .021 Identified: .003 Unidentified: .018 Planned Activities for Shift:

• Plant Startup BAST RWST (gal) (gal) 52 545 48 503 229 2482 173 1860 the A MFW Pump in accordance with 0-1.2, Plant Startup From Hot Shutdown to Full Power Load, Step 6.3.4.
• The crew is directed to test the MFW Lube Oil Pumps in accordance with 0-1.2, Plant Startup From Hot Shutdown to Full Power Load, Step 6.3.9.
• The area has experienced thunderstorms over the last 6 hours, and this is expected to continue for the next 6 hours.
• The B Condensate Pump is OOS for Bearing Replacement.
• The alarms on the MCB have been evaluated and are expected for the current plant conditions.
• Protected equipment IAW OPG Protected Equipment.

Electrical System Operator Declarations None in effect 151hour dilution stabfiization 2nd hour dilution stabilization (gal RMW) (gal RMW) 77 51 77 52 558 314 296 98 TURNOVER SHEET for NRC Exam Scenario

1. 5 A-52.4 EQUIPMENT DATE/TIME 005 LCO TITLE EXP DATE ECO A-52.12 EQUIPMENT DATE/TIME 005 TRM/ODCM TITLE EXP DATE ECO B Condensate Pump _/_/14, 0200 NA NA No Time Limit _/_/14, 0800}}