Text

Draft Operating Exam (Section a, B, and C) (Folder 2)
	ML112620096
Person / Time
Site:	Three Mile Island
Issue date:	07/01/2011
From:	; Exelon Nuclear
To:	Caruso J; Operations Branch I
	JACKSON D RGN-I/DRS/OB/610-337-5306
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ML110030671	List: IR 05000289/2011301; ML110490206; ML112311224; ML112590501; ML112590507; ML112620074; ML112620096; ML112620102; ML112620105; ML112620125; ML113350223; TMI-11-034, Draft - Outlines (Folder 2);
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Exelon.

Nuclear THREE MILE ISLAND INITIAL LICENSE TRAINING CLASS 10-01 -.

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~\flo NRC EXAMINATION MATERIAL CONTROL lAW NUREG 1021 and TQ-AA-201 OPERATIONAL JPM's

Appendix Performance Measure Form Facility: TMI Unit 1 Task No.:

Task

Title:

JPM No.: 2011 NRC JPM RO Verify watch standing requirements A1-1

- Work-hour Rules KIA

Reference:

2.1.5 (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. Wheln you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

It is currently 1700 on Week 1, Day 6 of the current shift cycle.

Plant is at power.

PQS is not available.

Task Standard:

All critical steps evaluated as SAT.

Required Materials:

LS-AA-119, FATIGUE MANAGEMENT AND WORK HOUR LIMITS

Calculator General

References:

LS-AA-119, FATIGUE MANAGEMENT AND WORK HOUR LIMITS Handouts: A shift cycle with requested overtime days (Attachment 1)

Initiating Cue: You are the Third Reactor Operator on duty. To help fill empty spots for the rest of the shift cycle, you have been asked to stand overtime watches. Review the shift schedule and determine whether you are able to stand the requested additional watches, and if not give reason for any not able to be filled.

Time Critical Task: N/A Validation Time: 15 minutes TMI 2011 NRC JPM RO A1-1 NUREG 1021, Revision 9 Supp 1

Appendix Job Performance Measure Form SIMULATOR SETUP N/A TMI 2011 NRC JPM RO A1-1 NUREG 1021, Revision 9 Supp 1

Appendix Page 3 of 6 Form PERFORMANCE INFORMATION (Denote Critical Steps with a check)

Evaluator Cue: Provide the shift cycle with requested overtime days (Attachment 1)

~ Performance Step: 1 Determine whether the examinee can stand watch as requested on Week 1, Day 7 Standard: Examinee determines that he/she cannot stand the requested watch on Week 1, Day 7 as that would be 7 days in a row and therefore a violation of LS-AA-119, Section 5.1.1 (No more than 72 work hours in any 7-day (168-hour) period)

Comment:

~ Performance Step: 2 Determine whether the examinee can stand watch as requested on Week 3, Day 1 Standard: Examinee determines that he/she cannot stand the requested watch on Week 3, Day 1 as that would be >16 hours in a row and therefore a violation of LS-AA-119, Section 5.1.1 (No more than 16 work hours in any 24-hour period)

Comment:

Performance Step: 3 Determine whether the examinee can stand watch as requested on Week 5, Day 6 Standalrd: Examinee determines that he/she can stand the requested watch on Week 5, Day 6 as that would be < 2.5 days/week averaged over the shift cycle and therefore allowed per LS-AA-119, Section 5.1.2 (Minimum days off are averaged over the shift cycle, not to exceed 6 weeks: 2.5 days off/week for 12-hour shifts)

Comment:

Terminating Cue: When examinee has determined whether they can or cannot stand any of the 3 requested watches, JPM may be terminated.

TMI 2011 NRC JPM RO A1-1 NUREG 1021, Revision 9 Supp 1

Appendix 40f6 Form VERIFICATION OF COMPLETION Job Performance Measure No.: 2011 NRC JPM RO A1-1 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

TMI 2011 NRC JPM RO A1-1 NUREG 1021, Revision 9 Supp 1

Page 5 of 6 Form JPM CUE SHEET INITIAL CONDITIONS:

It is currently 1700 on Week 1, Day 6 of the current shift cycle.

Plant is at power.

PQS is not available.

INITIATING CUE: You are the Third Reactor Operator on duty. To help fill empty spots for the rest of the shift cycle, you have been asked to stand overtime watches. Review the shift schedule and determine whether you are able to stand the requested additional watches, and if not give reason for any not able to be filled.

TIME CRITICAL: No TMI 2011 NRC JPM RO A1-1 NUREG 1021, Revision 9 Supp 1

Appendix Page 6 of 6 Form ES-C-1 JPM CUE SHEET Attachment 1 Shift Cycle with Requested Overtime Days WEEK 1. CURRENT CYCLE DAY 1 I DAY 2 I DAY 3 DAY 1 DAY 2 DAY 6 I DAY?

Your Shift I 0'2 WEEK 5, CURRENT CYCLE WEEK 1, NEXT CYCLE DAY 1 DAY 2 DAY 3 DAY 4 DAYS DAY 6 DAY? DAY 1 DAY 2 DAY 3 DAY 4 DAYS DAY 6 DAY?

~§hlft r:~'llf:lijli-l5,> !.);~;

- - L;t!~(,*I*W!l* if" .l'l) 0(2) VAC VAC VAC VAC VAC VAC VAC Key:

D= Day shift N= Night shift (1)= Requested additional watches already stood (2)= Requested additional watches TMI2011 NRC JPM RO A1-1 NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Facility: TMI Unit 1 Task No.: GOP002003 Task

Title:

Calculate an Estimated Critical Rod JPM No.: 2011 NRC JPM RO Position. A 1-2 KIA

Reference:

2.1.37 (4.3) New for 2011 NRC Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

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

Initial Conditions:

A sequential trip of both main feedwater pumps resulted in a reactor trip 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ago.

The unit had been at 100% power for 150 days prior to the reactor trip.

Cycle Burnup is 450 EFPD.

TAVE 532"F

Final Measured Boron Concentration = 985 PPM

The FINAL MIXED BORON DEPLETION CORRECTION FACTOR as specified in the control room log is 0.95.

The Plant Process Computer is NOT available.

No reactor engineering personnel are on site.

A licensed operator has prepared OP-TM-300-403, ESTIMATED CRITICAL ROD POSITION, ATTACHMENT 7.1, Estimated Critical Position Calculation Data Sheet Task Standard: All critical steps evaluated as SAT.

Required Materials:

OP-TM-300-403, ESTIMATED CRITICAL ROD POSITION Rev 3

OP-TM-300-000, REACTIVITY AND POWER DISTRIBUTION CALCULATIONS Rev 2

Calculator

Straight Edge General

References:

OP-TM-300-403, ESTIMATED CRITICAL ROD POSITION

OP-TM-300-000, REACTIVITY AND POWER DISTRIBUTION CALCULATIONS TMI 2011 NRC JPM RO A1-2 NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Handouts: A completed OP-TM-300-403, ESTIMATED CRITICAL ROD POSITION, ATIACHMENT 7.1, Estimated Critical Position Calculation Data Sheet with faults. (Attachment 1)

Initiating Cue: You are the Unit Reactor Operator on duty. Perform an independent Estimated Critical Rod Position calculation using OP-TM-300-403, ESTIMATED CRITICAL ROD POSITION, ATIACHMENT 7.1, Estimated Critical Position Calculation Data Sheet.

Time Critical Task: N/A Validation Time: 30 minutes.

SIMULATOR SETUP TMI 2011 NRC JPM RO A 1-2 NUREG 1021, Revision 9 Supp 1

Appendix Page 3 of 9 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check)

Evaluator Cue: Provide completed ATTACH MENT 7.1, Estimated Critical Position Calculation Data Sheet with faults. (Attachment 1)

Perfol'mance Step: 1 CALCULATION IS FOR AN ECP AT DATE(TIME Standard: Examinee places the current date and time on the appropriate line of Attachment 7.1.

Comment:

Performance Step: 2 The reactor coolant temperature is assumed to be 532 +/-2F Standard: Examinee obtains T ave from the initial conditions and verifies this value on Line 1 of Attachment 7.1.

Comment:

Performance Step: 3 Cycle Burnup: From FIDMS Display 1 or the Hourly Log Standard: Examinee is given this number on the Initial Condition Sheet.

This number will be entered on Line 2 of Attachment 7.1.

Comment:

Performance Step: 4 Measured Boron Concentration: Obtain the latest measured boron concentration from the RCS chemistry analysis, and check the Control Room log to verify that no major boron concentration changes have been made since the analysis. If major boron concentration changes have been made since the latest sample, request a new RCS boron concentration measurement. Until the new boron concentration is available, use OP-TM-300-409, Final RCS Boron Concentration EstimatE~ Following RCS Feed and Bleed, to estimate the current boron concentration to calculate a preliminary ECB.

Standard: Examinee is given this number on the Initial Condition Sheet.

This number will be entered on Line 3a of Attachment 7.1.

Comrnent:

TMI 2011 NRC JPM RO Al-2 NU REG 1021, Revision 9 Supp 1

Appendix C Page 4 of 9 PERFORMANCE INFORMATION Evaluator Cue: If asked about the Control Room log reading, respond "The Control Room log reading agrees with the latest measured boron concentration."

Evaluator Cue: If requested to perform additional samples, respond "Two consecutive samples are indicating Boron concentration of 985 ppm."

Performance Step: 5 Boron Depletion Correction Factor: From PPC, Control Room Log, or Reactor Engineering.

Standard: Examinee is given this number on the Initial Condition Sheet.

This number will be entered on Line 3b of Attachment 7.1.

Comment:

.."j Performance Step: 6 Final Corrected Boron Concentration: Adjust the measured boron concentration to account for boron-1 0 depletion by multiplying the Measured Boron Concentration by the Boron Depletion Correction Factor.

Standard: Examinee calculates the final corrected boron concentration and enters between 935 -936 ppm on Line 3c of Attachment 7.1.

Comment:

.."j Performance Step: 7 Fuel Excess Reactivity: From OP-TM-300-000 Figure 2.

Standard: Examinee enters a value on Line 5 between: 9.0 %Ak/k and 9.2

%Ak/k on Line 5 of Attachment 7.1.

Comment:

.."j Performance Step: 8 Inverse Boron Worth: From OP-TM-300-000 Figure 8.

Standard: Examinee enters a value between: 134.5 ppmB/%Ak/k and 135.5 ppmB/%Ak/k on Line 7a of Attachment 7.1.

Comment:

.."j Performance Step: 9 Boron Reactivity Worth: Quotient of 3c and 7a.

Standard: Examinee enters a value between: -6.90 %Ak/k and -6.96 %Ak/k on Line 7b of Attachment 7.1.

Comment:

TMI 2011 NRC JPM RO A 1-2 NUREG 1021, Revision 9 Supp 1

Appendix C Page 5 of 9 PERFORMANCE INFORMATION Evaluator Cue: The Plant Process Computer Program and Nuclear Engineering are unavailable.

-v Performance Step: 10 Xenon Reactivity Worth: Obtain xenon worth using the PPC, FIDMS Display 22 or from program XENC# (where # is the current cycle number). Figure 13 may be used if the PPC and Reactor Engineering are unavailable, provided that power prior to shutdown was constant (+/- 2%FP) for at least 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months .

Standard: Examinee enters 0.4-0.5 %i1k/k on Line 8 of Attachment 7.1.

Comment:

-v Performance Step: 11 Samarium and Plutonium Buildup Reactivity Worth: Record the number of hours since 0% FP and obtain Sm and Pu worth per Figure 15. If startup at any time during the cycle is within 5 days of a previous startup, contact Reactor Engineering for the appropriate reactivity worth.

Standard: Examinee enters a time since last shutdown of 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months and a value between: -0.085 to -0.095 dk/k on Line 9 of Attachment

7.1. Comment

-v Performance Step: 12 Inserted CRG 5-7 Worth Required for Criticality: Add reactivity contributions from Lines 5 through 9.

Standard: Examinee enters a value between: -1.53 %i1k/k and -1.73

%i1k/k on Line 10 of Attachment 7.1.

Comment:

TMI 2011 NRC JPM RO A1-2 NU REG 1021, Revision 9 Supp 1

Appendix C Page 6 of 9 Form PERFORMANCE INFORMATION Evaluator Note: The following tolerance bands (JPM steps 13 and 14) are based on the maximum allowable error in the previous steps. The examiner shall verify, using OP-TM-300-000 Figure 5a, that the examinee has correctly interpolated the graphs to within an error of +/- 2% rod withdrawal based on the reactivity value recorded by the examinee in step 12 of the JPM.

.,j Performance Step: 13 Estimated Critical Rod Position: Rod position from Figure SA corresponding to the reactivity value from Line 10.

Standard: Examinee enters the value determined on Figure Sa between:

90% and 115% rod index on Line 11 of Attachment 7.1.

Comment:

.,j Performance Step: 14 CRITICAL ROD POSITION TOLERANCE BAND (FIG SA) 12a.

Circle One: O.S%f1k1k 0.8%f1k1k Use O.S%f1k1k for Steady State conditions if xenon (8) is 0.0 to 0.5%

Use 0.8%f1k1k for Transient conditions if xenon (8) is more negative than -O.S%f1k/k Standard: Circles O.S%f1k1k on Line 12a of Attachment 7.1 Comment:

Evaluator Note: These numbers can vary slightly due to the starting point that is determined in Step 13 of this JPM. The evaluator will have to determine the validity of all responses using appropriate Figures and calculations shown.

.,j Performance Step: 15 Critical Rod Position Tolerance Band: As noted on the Calculation Data Sheet. Combine the reactivity value from Line 10 with the tolerance value from Line 12a and find the corresponding rod positions on Figure SA.

Standard: Examinee enters a value on line 4.3 for Minimum and Maximum values between:

Minimum: 67% rod index +/- 8%.

AND Maximum: 176% rod index + 16% /- 9% (in overlap region) .

Comment:

Terminating Cue: When examinee has completed and signed calculation JPM may be terminated.

TMI2011 NRC JPM RO A1-2 NU.REG 1021, Revision 9 Supp 1

Appendix C Page 7 of 9 Form ES-C-1 PERFORMANCE INFORMATION CALCULATION IS FOR AN ECP AT DATE/TIME Today / NOW

1. TAVE (Assume TAVE = 532 +/- 2°F) ~oF

2. CYCLE BURNUP 450 EFPD

3. 3a. FINAL MEASURED BORON CONCENTRATION 985 ppmB 3b. BORON DEPLETION CORRECTION FACTOR 0.95 (PPC, Control Room Log, Reactor Engineering, Reactivity Datasheet) 3c. FINAL CORRECTED BORON CONCENTRATION (3.a) X (3.b) = 935.75 (935 to 936)ppmB

4. CRG 8 POSITION AT CRITICALITY 100 %WD

5. FUEL EXCESS REACTIVITY (FIG 2) 9.1 (9.0 to 9.2)% i1k/k

6. CRG 8 REACTIVITY WORTH o % i1k/k

7. 7a. INVERSE BORON WORTH (FIG 8) 135 (134.5 to 135.5)

_ _ _ppmB/% i1k/k 7b. BORON REACTIVITY WORTH (3c /7a) x (-1) = -6.93_{-6.90 to -6.96L% i1k/k

8. XENON REACTIVITY WORTH (PPC, REACTOR ENGR., FIG 13) -0.45 (-0.4 to -0.5L%

~0~fi~,~~~~'G[ru@Q [hJ&J@~s @[illQ

REACTIVITY DUE TO BUILDUP -0.09 (-0.85 to -0.95L%

i1k/k

10. INSERTED CRG 5-7 WORTH REQUIRED FOR CRITICALITY (IRW)

(5 + 6 + 7b + 8 + 9) x (-1) = -1.63 (-1.53 to -1.73)

_% i1k/k

11. ESTIMATED CRITICAL ROD POSITION (FIG SA) 105 (90 to 115L% ROD INDEX

12. CRITICAL ROD POSITION TOLERANCE BAND (FIG SA) 12a. Circle One: 0.5%6k/k 0.8%i1k/k Use 0.5%i1k/k for Steady State conditions if xenon (8) is 0.0 to -0.5%

Use 0.8%i1k/k for Transient conditions if xenon (8) is more negative than -0.5%6k/k 12b. MINIMUM ROD WITHDRAWAL LIMIT (10 -12a) = _-2.13 (-2.00to-2.30L %i1k/k => _67 (59 to 75) %ROD INDEX (FIG Sa) 12c. MAXIMUM ROD WITHDRAWAL LIMIT (10 + 12a) = -1.13 (-1.00 to -i.30) %i1k/k => _176 {i65 to 192L %ROD INDEX (FIG Sa)

13. If this is a transient Xenon startup, then record the interval that ECP is valid TMI 2011 NRC JPM RO A 1-2 NUREG 1021, Revision 9 Supp 1

Appendix Page 8 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2011 NRC JPM RO A 1-2 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

TMI 2011 NRC JPM RO A1-2 NUREG 1021, Revision 9 Supp 1

Appendix Page 9 of 9 Form JPM CUE SHEET Initial Conditions:

A sequential trip of both main feedwater pumps resulted in a reactor trip 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ago.

The unit had been at 100% power for 150 days prior to the reactor trip.

Cycle Burnup is 450 EFPD.

TAVE = 532"F

Final Measured Boron Concentration = 985 PPM

The FINAL MIXED BORON DEPLETION CORRECTION FACTOR as specified in the control room log is 0.95.

The Plant Process Computer is NOT available.

No reactor engineering personnel are on site.

A licensed operator has prepared OP-TM-300-403, ESTIMATED CRITICAL ROD POSITION, ATTACHMENT 7.1, Estimated Critical Position Calculation Data Sheet INITIATING CUE: You are the Unit Reactor Operator on duty. Perform an independent Estimated Critical Rod Position calculation using OP TM-300-403, ESTIMATED CRITICAL ROD POSITION, ATTACHMENT 7.1, Estimated Critical Position Calculation Data Sheet.

TIME CRITICAL: No TMI 2011 NRC JPM RO A 1-2 NUREG 1021, Revision 9 Supp 1

II Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND UNIT 1 Task No.: EQC00015 Task

Title:

Isolate a component for JPM No.: 2011 NRC ..IPM RO A2 maintenance KIA

Reference:

G 2.2.41 (3.5/3.9) New for 2011 NRC Exam Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

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

Initial Conditions: You are the Extra RO Plant is in a refueling outage with RCS level in the green band of the refueling canal.

A worker tag out is needed for a leaking flange on RCP Seal Return Line Relief MU-V-180.

The line is currently filled.

Task Standard: All critical steps evaluated as SAT.

Required Materials: 302-660, Makeup and Purification Flow Diagram, Rev 44 OP-TM-211-000, Makeup and Purification System, Rev 21 General Re,ferences:

Handout: 302-660, Makeup and Purification Flow Diagram, Rev 44 OP-TM-211-000, Makeup and Purification System, Rev 21 Initiating Cue: MU-V-180 Seal Return Relief Valve is to be removed for flange repair.

You are directed to identify the required points, and sequence, to isolate, drain, and vent the liquid side of the Relief Valve.

TMI 2011 NRC JPM A2 RO NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: No Validation Time: 20 minutes TMI 2011 NRC JPM A2 RD NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP N/A TMI 2011 NRC JPM A2 RO NUREG 1021, Revision 9 Supp 1

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

EVALUATOR NOTE: After candidate obtains appropriate diagram you may hand the candidate a copy they can mark up.

Performance Step: 1 Obtains 302-660 Makeup and Purification flow diagram.

Standard: Drawing obtained.

Comment:

Performance Step: 2 Locates MU-V-180 relief valve at coordinate 03 Standard: Relief Valve located.

Comment:

TMI 2011 NRC JPM A2 RO NUREG 1021, Revision 9 Supp 1

~!II!j-.M11IUf ( I' i ,

Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION

..J Performance Step: 3 Candidate determines isolation pOints.

Standard:

MU-V-25 closed. v j

MU-V-39 closed.

MU-V-38 closed.'

MU-V-33A closed.*

MU-V-33B closed.*

MU-V-33C closed.*

MU-V-33D closed.*

Anyone of the MU-V-179A through D valve uncapped ,/

and opened to vent.

MU-V-141 uncapped and open to drain. ~.

EYALUATOR NOTE:

An acceptable alternative would be to use a combination of MU-Y-177A-O, MU-Y-178A-O, and MU-Y-96A-O in lieu of MU-Y-33A-O. Verify the isolation points would be the same as the equivalent MU-Y-33.

Comment:

..J Performance Step: 4 Candidate determines sequence.

Standard: Isolation valves; MU-V-25, MU-V-39, MU-V-38 MU-V-33A (or equivalents), MU-V 33B (or equivalents), MU-V-33C (or equivalents), and MU-V-33D (or equivalents) are closed, before Vent / Drain valves MU-V-179 and MU-V-141 are open.

Comment:

Terminating Cue: When components and positions are identified on a print JPM may be terminated.

STOP TIME: TIME CRITICAL STOP TIME: N/A TMI 2011 NRC JPM A2 RO NUREG 1021, Revision 9 Supp 1

Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2011 NRC JPM RO A2 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

TMI 2011 NRC JPM A2 RO NUREG 1021, Revision 9 Supp 1

Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: You are the Extra RO Plant is in a refueling outage with RCS level in the green band of the refueling canal.

A worker tag out is needed for a leaking flange on RCP Seal Return Line Relief MU-V-180.

The line is currently filled.

INITIATING CUE: MU-V-180 Seal Return Relief Valve is to be removed for flange repair. You are directed to identify the required points, and sequence, to isolate, drain, and vent the liquid side of the Relief Valve.

TMI 2011 NRC JPM A2 RO NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Facility: TMI Unit 1 Task No.: EPAA101007 Task

Title:

Perform State and Local Event JPM No.: 2011 NRC JPM RO A4 Notification KIA

Reference:

G2.4.43 (3.2/3.8) Bank JPM TQ-TM-104EPAA-J002 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. Wheln you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

An Unusual Event, MU1, was declared at Three Mile Island Unit 1 at 1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months on October 2, 2010 after a loss of offsite power occurred.

It is currently 1303 hours0.0151 days 0.362 hours 0.00215 weeks 4.957915e-4 months on October 2, 2010.

Task Standard: All critical steps evaluated as SAT.

Required Materials:

EP-MA-114-100, Mid-Atlantic State/Local Notifications Rev 15

EP-MA-114-100-F-01 Rev J General

References:

EP-MA-114-100, Mid-Atlantic State/Local Notifications

EP-MA-114-100-F-01 Handouts:

EP-MA-114-100, Mid-Atlantic State/Local Notifications

EP-MA-114-1 00-F-01 , filled out with: 1. MU 1 for block 4a and an FU1 sticker for block 4b, 2. blocks 7a and 7b blank.

Initiating Cue: As the Emergency Director I am assigning you the task to perform the State and Local Notifications of the declaration of the Unusual Event, MU1.

Time Critical Task: Yes Validation Time: 5 minutes.

TMI 2011 NRC JPM RO A4 NUREG 1021, Revision 9 Supp 1

Appendix C Form ES-C-1 SIMULATOR SETUP N/A TMI 2011 NRC JPM RD A4 NUREG 1021, Revision 9 Supp 1

Appendix Page 3 of 8 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Time Critical Time starts with acknowledgement of CUE. Time _ __

Evaluator Cue: Provide EP-MA-114-1 00, Mid-Atlantic State/Local Notifications and EP-MA-114-1 00-F-01 , filled out with: 1. MU 1 for block 4a and an FU1 sticker for block 4b, 2. blocks 7a and 7b blank.

Performance Step: 1 Ensure that the number of the message is on the State and Local (S&L) Notification Form Standard: Examinee confirms that the "Utility Message No." blank is completed with the number "1".

Comment:

Evaluator Cue: If requested what time to use indicate current clock time may be used. Time may be filled in after all parties are on phone.

Performance Step: 2 Fills in block 2 of EP-MA-114-1 00-F-01.

Standard: Name filled in.

TMI checked.

Phone number filled in (TMI control room number)

Current time filled in (time message read).

Comment:

TMI 2011 NRC JPM RO A4 NUREG 1021, Revision 9 Supp 1

Appendix Page 4 of 8 Form ES-C-1 PERFORMANCE INFORMATION Evaluator Cue: If the examinee informs you that block 4 is wrong, apply the proper sticker, MU1.

If the examinee informs you that block 7 is wrong, place a check mark in block 7a and line out block 7b.

,j Performance Step: 3 Review the S&L Notification form for completeness.

Standard: Examinee detects discrepancies with blocks 4 and 7.

Comment:

Evaluator Cue: If the examinee selects the correct telephone and lifts the handset to his/her ear, inform the examinee that they hear a dial tone Performance Step: 4 Connect with S&L agencies using the NARS line Standard: Examinee selects the NARS labeled telephone and lifts the handset to his/her ear Comment:

Evaluator Cue: If the examinee dials the correct number ("44") inform the examinee that they are hearing the following: "PEMA online; Cumberland County online; Lebanon County online; Lancaster County online; York County online; Dauphin County online".

Performance Step: 5 Contact the S&L agencies using the NARS line Standard: Examinee dials "44" Comment:

TMI 2011 NRC JPM RO A4 NUREG 1021, Revision 9 Supp 1

Appendix C Page 5 8 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 6 Inform the agencies online that a notification message is about to be read Standard: Examinee states "This is Exelon Nuclear TMI-i. Please standby for a notification message".

Comment:

..j Performance Step: 7 Determine if all S&L Agencies are on-line .

Standard: Examinee conducts an initial roll call of the S&L Agencies and correctly records the time contacted in 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months clock time on page 3 of the S&L Notification form in the appropriate block for each agency.

Evaluator Note: Examinee must hear all S&L Agencies respond as on-line no later than 12 minutes after initiation of this JPM for a "Pass" evaluation.

Comment:

Time Critical End pOint, when roll call is acknowledged. Page 3 initial roll call completed may be used if completed accurately.

Time: _ _ __

..j Cue time - Time above < 12 Minutes SAT UNSAT Performance Step: 8 Notify the S&L Agencies of the declaration of an Unusual Event at TMI-i.

Standard: Using the Phonetic Alphabet for clarity, the Examinee reads each of the blocks one at a time from pages 1 and 2 of the S&L Event Notification Form.

Comment:

TMI 2011 NRC JPM RO A4 NUREG 1021, Revision 9 Supp 1

Appendix Page 6 of 8 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 9 Conduct final roll call Standard: Examinee conducts a final roll call for each agency and checks the agencies off as they respond.

Comment:

Evaluator Cue: If the examinee asks if there are any questions, inform him/here that there are none.

Performance Step: 10 Ask if there are any questions.

Standard: Examinee asks if there are any questions.

Comment:

Performance Step: 11 Terminate phone call.

Standard: Examine states: "This concludes the notification message."

Comment:

Terminating Cue: When examinee ends the S&L Notification phone call JPM may be terminated.

TMI 2011 NRC JPM RO A4 NUREG 1021, Revision 9 Supp 1

Appendix Page 7 8 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2011 NRC JPM RO A4 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

TMI 2011 NRC JPM RO A4 NUREG 1021, Revision 9 Supp 1

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

An Unusual Event, MU1, was declared at Three Mile Island Unit 1 at 1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months on October 2, 2010 after a loss of offsite power occurred.

It is currently 1303 hours0.0151 days 0.362 hours 0.00215 weeks 4.957915e-4 months on October 2, 2010.

INITIATING CUE: As the Emergency Director I am assigning you the task to perform the State and Local Notifications of the declaration of the Unusual Event, MU-1 .

TIME CRITICAL: Yes TMI 2011 NRC JPM RO A4 NUREG 1021, Revision 9 Supp 1

Exel ncr> EP-MA-114-100-F-01 Revision J Nuclear Page 1 of 3 STATE/LOCAL EVENT NOTIFICATION FORM (OR ELECTRONIC FACSIMILE)

UTILITY MESS~~() I VERIFIED WITH: EMERGENCY DIRECTOR APPROVAL:

PERFORM INITIAL CALL PRIOR TO TRANSMITTING - Refer to Page 3 of Form

1. CALL STATUS is: 2. This is I)<.] This is a DRILL. for [ ] LIMERICK / [ 1PEACH BOTTOM / [ 1TMI

[ 1This is an ACTUAL EVENT. My phone number is The current time is

[Communicator will provide his/her NAME, PHONE NUMBER, and CURRENT TIME (in 24-hour clock) when notification is read.]

3.a EMERGENCY CLASSIFICATION b. AFFECTED UNIT(S} is/are: d. THIS REPRESENTS AlAN:

D<l UNUSUAL EVENT f><l ONE [ ] TWO [ ] THREE [)() INITIAL DECLARATION

[ ] ALERT [ 1ESCALATION

[ ] SITE AREA EMERGENCY c. DECLARED AT: [ 1NO CHANGE

[ ] GENERAL EMERGENCY TIME: 13!:;10 (24-hr clock) [ 1REDUCTION

[ 1RECOVERY DATE: 10/0",,/112 -IN CLASSIFICATION STATUS

[ ] TERMINATION

4. a. EMERGENCY ACTION LEVEL (EAL} NO. is: M!.2 t

b. A BRIEF NON-TECHNICAL DESCRIPTION OF THE EVENT is as follows:

FUI There are indications of a loss or possible loss of containment integrity. Current plant conditions DO NOT threaten public safety.

5. NON-ROUTINE RADIOLOGICAL RELEASE STATUS is:

D<J. a. NO radiological release in-progress

[ 1b. AIRBORNE radiological release in-progress

[ 1c. LIQUID radiological release in-progress

[ ] d. Radiological release TERMINATED

6. METEOROLOGY is:

a. WIND DIRECTION is FROM: LSd (degrees)

b. WIND SPEED is: 7 (miles per hour)

Document Retention SRRS-ID - 5B.1 00

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Three Mile Island Task No.: OF1000005 Task

Title:

Maintain Minimum Shift Staffing, JPM No.: 2011 NRC JPM SRO Control Overtime A1-1 KIA

Reference:

2.1.5 (3.9) New for 2011 NRC Exam Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

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

Initial Conditions:

Plant is at 100% power with ICS in automatic

The time is 2300 on 8/30/11.

The shift is staffed as follows:

C. Six - Shift Manager

You -CRS

J. Kulasinsky - STA

A. Williams _. URO

H. Blunt - ARO

B. Dickinson - URO Under Instruction

The Shift Technical Advisor (STA), J. Kulasinsky, reports that his contact lenses have popped out and are lost. He reminds you that he has a license restriction that requires him to wear corrective lenses. His backup eyeglasses are missing and cannot be located, so he has requested to go home.

A licensed Senior Reactor Operator, J. Stubbs, is in the Turbine Building walking down a potential clearance with an NLO.

Task Standard: All critical steps evaluated as SAT.

2011 NRC JPM SRO A1-1 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Required Materials:

OP-TM-1 01-111-1 001, Shift Manning Requirements, Rev. 6

Tech Spec 6.2.2 and Table 6.2-1, Amendment 219.

LS-AA-119, Overtime Controls, Rev. 8

Shift Staffing Report prepared

LMS Qual Matrix Report

Over time list prepared General

References:

Technical Specifications Handout:

OP-TM-101-111-1001, Shift Manning Requirements, Rev. 6

LS-AA-119, Overtime Controls, Rev. 8

Shift Staffing Report prepared

LMS Qual Matrix Report

Over time list prepared Initiating Cue: When I tell you to begin, as the Control Room Supervisor, you are to PERFORM THE STEPS NECESSARY TO ENSURE THAT YOUR SHIFT IS APPROPRIATELY STAFFED.

Time Critical Task: N/A Validation Time: 10 minutes 2011 NRC JPM SRO A1-1 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP Exam Setup: IC N/A

N/A

MALFUNCTIONS:

N/A

OVERRIDES:

N/A 2011 NRC JPM SRO A1-1 NUREG 1021, Revision 9

Appendix C Page 4 of 11 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START '"IME:

Evaluators Note: Provide Examinee with OP-TM-101-111-1001, LS-AA-119, Shift Staffing Report, LMS Qual Matrix Report, and Overtime list Performance Step: 1 Examinee references Technical Specifications and/or OP-TM 101-111-1001, Shift Manning Requirements, to determine minimum shift manning requirements for current conditions.

Standard: Examinee determines that three SROs are required. One SRO is required to be in the Control Room.

- Except for the Shift Manager, shift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2.-1. This provision does not permit any shift crew position to be unmanned upon shift change due to an incoming shift crewman being late or absent.

Comment:

Evaluator'S Cue: If asked, state that there are no other licensed SROs on site.

Performance Step: 2 Examinee references Shift Staffing Report to determine current shift manning status.

Standard: Examinee references Shift Staffing Report and determines that current SRO staffing is unacceptable.

Comment:

2011 NRC ..IPM SRO A1-1 NUREG 1021, Revision 9

Appendix C Page 5 of 11 Form ES-C-1 PERFORMANCE INFORMATION

..J Performance Step: 3 Examinee initiates action to comply with Technical Specification requirements for three licensed SROs.

Standard: Action initiated by referring to Overtime list Comment:

Evaluator's Cue: If examinee tries to call scheduler, inform examinee Ops scheduler is UNAVAILABLE.

Performance Step: 4 Examinee seeks a replacement for the third licensed SRO position left vacant by the inability of the STA to meet requirements for the job.

Standard: Examinee calls the Operations Scheduler or directly references the Overtime Callout list to identify a replacement SRO to be called.

Comment:

Evaluator's Cue: If examinee calls OshaII or Stubbs to report to work, answer that you are on your way.

..J Performance Step: 5 Examinee references the provided materials to evaluate callout restrictions on candidates one and two.

Standard: Examinee skips first two candidates (Oshall, Stubbs) as they are inactive per the LMS Qual Matrix Report.

Comment:

2011 NRC ,-'PM SRO A 1-1 NUREG 1021, Revision 9

Appendix C Page 6 of 11 Form ES-C-1 PERFORMANCE INFORMATION Evaluator's Cue: As candidate three (Valent, Lewis, Carreras, or Parfitt),

report when called "I am making a self-declaration of fatigue and do not wish to report to work".

...J Performance Step: 6 Examinee references the provided materials to evaluate callout restrictions on candidate three.

Standard: Examinee initially informs candidate three to report to work immediately, then acknowledges self-declaration of fatigue and informs candidate three NOT to report at this time lAW LS-AA 119 Section 5.6.

Comment:

Evaluator's Cue: As candidate four (Valent, Lewis, Carreras, or Parfitt), report when called "I just had four beers at a friend's house. If you need me though, I'll come in as soon as I can"

...J Performance Step: 7 Examinee references the provided materials to evaluate callout restrictions on candidate four.

Standard: Examinee initially informs candidate four to report to work immediately, then acknowledges alcohol consumption and informs candidate four NOT to report at this time.

Comment:

2011 NRC JPM SRO A1-1 NUREG 1021, Revision 9

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

Appendix C Page 7 of 11 Form ES-C-1 PERFORMANCE INFORMATION

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

Evaluator'S Cue: As candidate five (Valent, Lewis, Carreras, or Parfitt), report when called "This is my one day off this week since I validated NRC exams in the simulator yesterday. If you need me though, 1'" come in as soon as I can"

~ Performance Step: 8 Examinee references the provided materials to evaluate callout restrictions on candidate five.

Standard: Examinee initially informs candidate five to report to work immediately, then informs candidate five NOT to report at this time due to LS-AA-119 Section 5.1.1 requirement.

Comment:

Evaluator's Cue: As candidate six (Valent, Lewis, Carreras, or Parfitt), report when called "I am on vacation, flying to Hawaii in the afternoon. If you need me though, 1'" come in as soon as I can"

~ Performance Step: 9 Examinee references the provided materials to evaluate callout restrictions on candidate six.

Standard: Examinee informs candidate six to report to work immediately.

Comment:

Terminating Cue: After examinee demonstrates ability to contact an SRO at home to have them report to work JPM may be terminated.

STOP TIME: TIME CRITICAL STOP TIME: N/A 2011 NRCJPMSROA1-1 NUREG 1021, Revision 9

Appendix C Page 8 of 11 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2011 NRC JPM SRO A1-1 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2011 NRC JPM SRO A1-1 NUREG 1021, Revision 9

Appendix C Page 9 of 11 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

Plant is at 100% power with ICS in automatic

The time is 2300 on 8/30/11.

The shift is staffed as follows:

C. Six - Shift Manager

You - CRS

J. Kulasinsky - STA

A. Williams - URO

H. Blunt - ARO

B. Dickinson - URO Under Instruction

The Shift Technical Advisor (STA). J. Kulasinsky, reports that his contact lenses have popped out and are lost. He reminds you that he has a license restriction that requires him to wear corrective lenses. His backup eyeglasses are missing and cannot be located, so he has requested to go home.

A licensed Senior Reactor Operator, J. Stubbs. is in the Turbine Building walking down a potential clearance with an NLO.

INITIATING CUE: When I tell you to begin, as the Control Room Supervisor, you are to PERFORM THE STEPS NECESSARY TO ENSURE THAT YOUR SHIFT IS APPROPRIATELY STAFFED.

2011 NRC JPM SRO A1-1 NUREG 1021, Revision 9

Appendix '-' Page 10 of 11 Form ES-C-1 JPM CUE SHEET Attachment #1 LMS Qual Matrix Report Date: 8/30/11 11 :00:00 PM Y Currently Qualified (will not expire in the next 60 days) 0 = Currently Qualified (due to expire in 60 days or less) N = Not qualified (expired) (blank) '" Qualification Never Assigned

.. ~-

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FOR TRAINI~G PURPOSES ONLYT*

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-I I I I Qualification 10 I Qualification Title Qualification Paren!

N-TM-OP-STA QUAL I TMI STA: SHIFT QUALIFIED =------' N Root Qual 0 0 YIY N_.J'J Y Y 0 N Y Y 0 0 N YIYIO 2011 NRC JPM SRO A1-1 NUREG 1021, Revision 9

Appendix I.." Page 11 of 11 Form ES-C-1 JPM CUE SHEET Attachment #2 OVERTIME CALLOUT FOR Ops Shift Schedule STARTING AT 8/30/2011 17:30:00 AND ENDING AT 8/31/2011 06:00:00 SRO # 2 STA QUALIFICATION Shift Technical Advisor REPORT CREATION DATE 8/30/2011 23:00:00 NOTES:

FOR TRAINING PURPOSES ONLY

~ . . Gre:=

l~urrentlY Working Shift Name Phone OT Hours Accept Refuse Comments NONE Oshall, D 0 j I I NONE Stubbs, J 0 I NONE- Valf:j/"lt.J 0

--- f------------

NONE -----

Lewis, D ---------

0 NONE Carreras, E 0 c NONE Parfitt, B 0 ~--.-.- ..... ~---

Note: List created by PQS lAW LS-AA-119 2011 NRC JPM SRO A1-1 NUREG 1021, Revision 9

AppendixC Job Performance Measure Form ES-C-1 Worksheet

------=-'----"-~'-'------------,-"~,---

Facility: TMI Unit 1 Task No.: GOP002003 Task

Title:

Review an Estimated Critical Rod JPM No.: 2011 NRC JPM SRO Position Calculation for approval, A1-2 identify any errors KIA

Reference:

2.1.37 (4.3/4.6) New 2011 NRC Exam Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

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

Initial Conditions:

A sequential trip of both main feedwater pumps resulted in a reactor trip 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ago.

The unit had been at 100% power for 150 days prior to the reactor trip.

Cycle Burnup is 450 EFPD.

TAVE = 532"F

Final Measured Boron Concentration = 985 PPM

The FINAL MIXED BORON DEPLETION CORRECTION FACTOR as specified in the control room log is 0.95.

The Plant Process Computer is NOT available.

No reactor engineering personnel are on site.

A licensed operator has prepared OP-TM-300-403, ESTIMATED CRITICAL ROD POSITION, ATTACHMENT 7.1, Estimated Critical Position Calculation Data Sheet Task Standard: All critical steps evaluated as SAT.

Required Materials:

OP-TM-300-403, ESTIMATED CRITICAL ROD POSITION

OP-TM-300-000, REACTIVITY AND POWER DISTRIBUTION CALCULATIONS

Calculator

Straight Edge General

References:

OP-TM-300-403, ESTIMATED CRITICAL ROD POSITION Rev 3

OP-TM-300-000, REACTIVITY AND POWER DISTRIBUTION CALCULATIONS Rev 2 TMI 2011 NRC JPM SRO A1-2 NUREG 1021, Revision 9 Supp 1

tt r Appendix C Job Performance Measure Form ES-C-1

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

Worksheet

"-'-=..:..:..:;.;..;..;:;....::...::--- --------

Handouts: A completed OP-TM-300-403, ESTIMATED CRITICAL ROD POSITION, ATTACHMENT 7.1, Estimated Critical Position Calculation Data Sheet with faults. (Attachment 1)

Initiating Cue: You are the Control Room Supervisor on duty.

Perform an Estimated Critical Rod Position calculation.

Then approve the supplied Estimated Critical Rod Position Calculation in accordance with OP-TM-300-403, ESTIMATED CRITICAL ROD POSITION, ATTACHMENT 7.1, Estimated Critical Position Calculation Data Sheet.

Time Critical Task: N/A Validation Time: 30 minutes.

SIMULATOR SETUP TMI 2011 NRC JPM SRO A 1-2 NUREG 1021, Revision 9 Supp 1

Appendix C Page 3 of 11 Form PERFORMANCE INFORMATION (Denote Critical Steps with a check)

Evaluator Cue: Provide completed AITACH MENT 7.1, Estimated Critical Position Calculation Data Sheet with faults. (Attachment 1)

Performance Step: 1 CALCULATION IS FOR AN ECP AT DATE/TIME Standard: Examinee places the current date and time on the appropriate line of Attachment 7.1.

Comment:

Performance Step: 2 The reactor coolant temperature is assumed to be 532 +/-2F Standard: Examinee obtains T ave from the initial conditions and verifies this value on Line 1 of Attachment 7.1.

Comment:

Performance Step: 3 Cycle Burnup: From FIDMS Display 1 or the Hourly Log Standard: Examinee is given this number on the Initial Condition Sheet.

This number will be entered on Line 2 of Attachment 7.1.

Comment:

Performance Step: 4 Measured Boron Concentration: Obtain the latest measured boron concentration from the RCS chemistry analYSis, and check the Control Room log to verify that no major boron concentration changes have been made since the analysis. If major boron concentration changes have been made since the latest sample, request a new RCS boron concentration measurement. Until the new boron concentration is available, use OP-TM-300-409, Final RCS Boron Concentration Estimate Following RCS Feed and Bleed, to estimate the current boron concentration to calculate a preliminary ECB.

Standard: Examinee is given this number on the Initial Condition Sheet.

This number will be entered on Line 3a of Attachment 7.1.

Comment:

TMI 2011 NRC JPM SRO A1-2 NUREG 1021, Revision 9 Supp 1

Appendix Page 4 11 PERFORMANCE INFORMATION Evaluator Cue: If asked about the Control Room log reading, respond "The Control Room log reading agrees with the latest measured boron concentration."

Evaluator Cue: If requested to perform additional samples, respond "Two consecutive samples are indicating Boron concentration of 985 ppm."

Performance Step: 5 Boron Depletion Correction Factor: From PPC, Control Room Log, or Reactor Engineering.

Standard: Examinee is given this number on the Initial Condition Sheet.

This number will be entered on line 3b of Attachment 7.1.

Comment:

,f Performance Step: 6 Final Corrected Boron Concentration: Adjust the measured boron concentration to account for boron-1 0 depletion by multiplying the Measured Boron Concentration by the Boron Depletion Correction Factor.

Standard: Examinee calculates the final corrected boron concentration and enters between 935 -936 ppm on line 3c of Attachment 7.1.

Comment:

.j Performance Step: 7 Fuel Excess Reactivity: From OP-TM-300-000 Figure 2.

Standard: Examinee enters a value on line 5 between: 9.0 %Llk/k and 9.2

%Llk/k on line 5 of Attachment 7.1.

Comment:

.j Performance Step: 8 Inverse Boron Worth: From OP-TM-300-000 Figure 8.

Standard: Examinee enters a value between: 134.5 ppmB/%Llk/k and 135.5 ppmB/%Llk/k on line 7a of Attachment 7.1.

Comment:

.j Performance Step: 9 Boron Reactivity Worth: Quotient of 3c and 7a.

Standard: Examinee enters a value between: -6.90 %Llk/k and -6.96 %Llk/k on line 7b of Attachment 7.1.

Comment:

TMI 2011 NRC JPM SRO A1-2 NUREG 1021, Revision 9 Supp 1

Appendix C Page 5 of 11 PERFORMANCE INFORMATION Evaluator Cue: The Plant Process Computer Program and Nuclear Engineering are unavailable.

>j Performance Step: 10 Xenon Reactivity Worth: Obtain xenon worth using the PPC, FIDMS Display 22 or from program XENC# (where # is the current cycle number). Figure 13 may be used if the PPC and Reactor Engineering are unavailable, provided that power prior to shutdown was constant (+/- 2%FP) for at least 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months .

Standard: Examinee enters 0.4-0.5 %Ak/k on Line 8 of Attachment 7.1.

Comment:

.,j Performance Step: 11 Samarium and Plutonium Buildup Reactivity Worth: Record the number of hours since 0% FP and obtain Sm and Pu worth per Figure 15. If startup at any time during the cycle is within 5 days of a previous startup, contact Reactor Engineering for the appropriate reactivity worth.

Standard: Examinee enters a time since last shutdown of 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months and a value between: -0.085 to -0.095 dk/k on Line 9 of Attachment

7.1. Comment

.,j Performance Step: 12 Inserted CRG 5-7 Worth Required for Criticality: Add reactivity contributions from Lines 5 through 9.

Standard: Examinee enters a value between: -1.53 %Ak/k and -1.73

%Ak/k on Line 10 of Attachment 7.1.

Comment:

TMI 2011 NRC JPM SRO A 1-2 NU REG 1021, Revision 9 Supp 1

n -liilk .7 Appendix Page 6 of 11 Form PERFORMANCE INFORMATION Evaluator Note: The following tolerance bands (JPM steps 13 and 14) are based on the maximum allowable error in the previous steps. The examiner shall verify, using OP-TM-300-000 Figure 5a, that the examinee has correctly interpolated the graphs to within an error of +/- 2% rod withdrawal based on the reactivity value recorded by the examinee in step 12 of the JPM.

-v Performance Step: 13 Estimated Critical Rod Position: Rod position from Figure 5A corresponding to the reactivity value from Line 10.

Standard: Examinee enters the value determined on Figure 5a between:

90% and 115% rod index on Line 11 of Attachment 7.1.

Examinee Identifies discrepancy with the completed ECP.

Comment:

~ Performance Step: 14 CRITICAL ROD POSITION TOLERANCE BAND (FIG 5A) 12a.

Circle One: 0.5%.6.klk 0.8%.6.klk Use 0.5%.6.klk for Steady State conditions if xenon (8) is 0.0 to 0.5%

Use 0.8%.6.klk for Transient conditions if xenon (8) is more negative than -0.5%.6.k/k Standard: Circles 0.5%.6.klk on Line 12a of Attachment 7.1 Examinee identifies discrepancy with the completed ECP.

Comment:

Evaluator Note: These numbers can vary Slightly due to the starting point that is determined in Step 13 of this JPM. The evaluator will have to determine the validity of all responses using appropriate Figures and calculations shown.

-V Performance Step: 15 Critical Rod Position Tolerance Band: As noted on the Calculation Data Sheet. Combine the reactivity value from Line 10 with the tolerance value from Line 12a and find the corresponding rod positions on Figure 5A.

Standard: Examinee enters a value on line 4.3 for Minimum and Maximum values between:

Minimum: 67% rod index +/- 8%.

AND Maximum: 176% rod index + 16% / - 9% (in overlap region).

Examinee identifies discrepancy with the completed ECP.

Comment:

TMI 2011 NRC JPM SRO A1-2 NUREG 1021, Revision 9 Supp 1

Appendix C Page 7 of 11 Form ES-C-1 PERFORMANCE INFORMATION

...J Performance Step: 16 Notes that anomalies exist between the two calculations and states that the ECP will not be approved.

Standard: Examinee notifies the Shift Manager to evaluate the discrepancy and does not sign the CRO's ECP.

Comment:

Terminating Cue: When examinee has completed step 12 of the ECP and notified the Examiner that the ECP will not be signed due to the anomalies with the calculations, this JPM may be terminated.

TMI 2011 NRC ,JPM SRO A 1-2 NUREG 1021, Revision 9 Supp 1

__4WS...._

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, r.... ' _ w ~ ( _ w._ _ _ _ _....._ _

1 Appendix C Page 8 of 11 Form ES-C-1 PERFORMANCE INFORMATION CALCULATION IS FOR AN ECPAT DATErrlME Today I NOW

1. TAVE (Assume T AVE = 532 +/- 2°F) 532 of

2. CYCLE BURNUP 450 EFPD

3. 3a. FINAL MEASURED BORON CONCENTRATION 985 ppmB 3b. BORON DEPLETION CORRECTION FACTOR 0.95 (PPC, Control Room Log, Reactor Engineering, Reactivity Datasheet) 3c. FINAL CORRECTED BORON CONCENTRATION (3.a) X (3.b) = 935.75 (936 to 936)ppmB

4. CRG 8 POSITION AT CRITICALITY 100 %WD

5. FUEL EXCESS REACTIVITY (FIG 2) 9.1 (9;~t~ 9.2)% Ak/k

6. CRG 8 REACTIVITY WORTH o % Ak/k

7. 7a. INVERSE BORON WORTH (FIG 8)

_ _ _ppmB/% Ak/k 7b. BORON REACTIVITY WORTH (3c / 7a) x (-1) =

8. XEI\JON REACTIVITY WORTH (PPC, REACTOR ENGR., FIG 13) -0.45(~O.4'to"O.5L%

~~~~I~~~~~IG~@~ [hj@@~s @(ill~

REACTIVITY DUE TO BUILDUP Ak/k

10. INSERTED CRG 5-7 WORTH REQUIRED FOR CRITICALITY (IRW)

(5 + 6 + 7b + 8 + 9) x (-1) = -1.63 (~1.53tQ.-1.73)

_% Ak/k

11. ESTIMATED CRITICAL ROD POSITION (FIG 5A) 105 (OOto1lsL% ROD INDEX

12. CRITICAL ROD POSITION TOLERANCE BAND (FIG 5A) 12a. Circle One: IH3%Aklk ,~A~

Use 0.5%Ak/k for Steady State conditions if xenon (8) is 0.0 to -0.5%

Use 0.8%Ak/k for Transient conditions if xenon (8) is more negative than -0.5%Ak/k 12b. MINIMUM ROD WITHDRAWAL LIMIT (10 -12a) = _-2.13 (t2.00to ~2,~OL %Ak/k => _67 (~;(to75) %ROD INDEX (FIG 5a) 12c. MAXIMUM ROD WITHDRAWAL LIMIT (10 + 12a) = -1.13 H;OO;tct:~l}30) %Ak/k => _176 (165)ID't92L %ROD INDEX (FIG 5a)

13. If this is a transient Xenon startup, then record the interval that ECP is valid C.,ndJOat4l . ,naul

~lmQmWJt cerrected.

TMI 2011 NRC .JPM SRO A1-2 NUREG 1021, Revision 9 Supp 1

Appendix C Page 9 11 Form VERIFICATION OF COMPLETION Job Performance Measure No.: 2011 NRC JPM SRO A1-2 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

TMI 2011 NRC JPM SRO A1-2 NUREG 1021, Revision 9 Supp 1

Appendix Page 10 of 11 Form JPM CUE SHEET INITIAL CONDITIONS:

A sequential trip of both main feedwater pumps resulted in a reactor trip 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ago.

The unit had been at 100% power for 150 days prior to the reactor trip.

Cycle Burnup is 450 EFPD.

TAVE =532"F

Final Measured Boron Concentration = 985 PPM

The FINAL MIXED BORON DEPLETION CORRECTION FACTOR as specified in the control room log is 0.95.

The Plant Process Computer is NOT available.

No reactor engineering personnel are on site.

A licensed operator has prepared OP-TM-300-403, ESTIMATED CRITICAL ROD POSITION, ATTACHMENT 7.1, Estimated Critical Position Calculation Data Sheet INITIATING CUE: You are the Control Room Supervisor on duty.

Perform an Estimated Critical Rod Position calculation.

Then approve the supplied Estimated Critical Rod Position Calculation in accordance with OP-TM-300-403, ESTIMATED CRITICAL ROD POSITION, ATTACHMENT 7.1, Estimated Critical Position Calculation Data Sheet.

TIME CRITICAL: No TMI 2011 !\IRC JPM SRO A 1-2 NUREG 1021, Revision 9 Supp 1

Appendix Page 1 11 Form JPM CUE SHEET CALCULATION IS FOR AN ECPAT DATEmME Today / NOW

1. TAVE (Assume TAVE = 532 +/- 2°F) 532 of

2. CYCLE BURNUP 450 EFPD

3. 3a. FINAL MEASURED BORON CONCENTRATION 985 ppmB 3b. BORON DEPLETION CORRECTION FACTOR 0.95 (PPC, Control Room Log, Reactor Engineering, Reactivity Datasheet) 3c. FINAL CORRECTED BORON CONCENTRATION (3.a) X (3.b) = 935.75 ppmB

4. CRG 8 POSITION AT CRITICALITY ---1..lliL%WD

5. FU EL EXCESS REACTIVITY (FIG 2) ~%l\k/k

6. CRG 8 REACTIVITY WORTH _0_% l\k/k

7. 7a. INVERSE BORON WORTH (FIG 8) .....1Q§. ppmB/% l\k/k 7b. BORON REACTIVITY WORTH (3c /7a) x (-1) = -6.93 % llk/k

8. XENON REACTIVITY WORTH (PPC, REACTOR ENGR., FIG 13) -0.45 % llk/k

9. SAMARIUM AND PLUTONIUM BUILDUP (FIG 15)

TIME SINCE LAST SHUTDOWN 1L.HRS

REACTIVITY DUE TO BUILDUP -0.09 % l\k/k

10. INSERTED CRG 5-7 WORTH REQUIRED FOR CRITICALITY (lRW)

(5+6+7b+8+9)x(-1) -1.63 %l\k/k

11. ESTIMATED CRITICAL ROD POSITION (FIG 5A) ~% ROD INDEX

12. CRITICAL ROD POSITION TOLERANCE BAND (FIG 5A) 12a. Circle One: 0.5%l\k/k ~~

Use 0.5%l\k/k for Steady State conditions if xenon (8) is 0.0 to -0.5%

Use 0.8%l\k/k for Transient conditions if xenon (8) is more negative than -0.5%llk/k 12b. MINIMUM ROD WITHDRAWAL LIMIT (10 -12a)::;; -0.83 %l\k/k => 205 %ROD INDEX (FIG 5a) 12c. MAXIMUM ROD WITHDRAWAL LIMIT (10 + 12a) -2.43 %llk/k => --..1L %ROD INDEX (FIG 5a)

13. If this is a transient Xenon startup, then record the interval that ECP is valid From: Date/Time: Time of Calc To: Date/Time 3 Hours after Calc CALCULATED BY: =G"",,re~g,-,-H=o=e.!.!..k_ _ _ _ _ _ _ _ _ _ _ _ _ _ DATE/TIME Today T-30 APPROVED BY (SRO): DATE/TIME TMI 2011 NRC JPM SRO A 1-2 NUREG 1021, Revision 9 Supp 1

",\OWit ~1ii>'iIIoi ~ . , _ _ ,_ _*S_*_ _.........

_ ,_ _ _'.'fi '_tqil_._---_:Ufi

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

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND UNIT 1 Task No.: EQC02014 Task

Title:

Approve Isolation points for a JPM No.: 2011 NRC JPM SRO component for maintenance A2 KIA

Reference:

G 2.2.41 (3.5/3.9) New for 2011 NRC Exam Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

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

Initial Conditions: You are the Duty SRO.

Plant is in a refueling outage with RCS level in the green band of the refueling canal.

A worker tag out, for the liquid portion only, has been prepared for a leaking flange on RCP Seal Return Line Relief MU-V-180.

The line is currently filled.

Task Standard: All critical steps evaluated as SAT.

Required Materials: None General

References:

302-660, Makeup and Purification Flow Diagram Rev 44 OP-TM-211-000, Makeup and Purification System Rev 21 Handout: Attached Worker Tag out Initiating Cue: You are directed to review the Worker Tag Out for accuracy and sign as Operations Authorization.

TMI 2011 NRC JPM A2 SRO NUREG 1021, Revision 9 Supp 1

_____~--.------------------------------------'--I#_**_*-,----------

Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: No Validation Time: 15 minutes TMI 2011 NRC JPM A2 SRO NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP N/A TMI 2011 NRC JPM A2 SRO NUREG 1021, Revision 9 Supp 1

.. 'J Appendix C Page 4 of 11 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

EVALUATOR NOTE: After candidate obtains appropriate diagram you may hand the candidate a copy they can mark up.

Performance Step: 1 Obtains 302-660 Makeup and Purification flow diagram.

Standard: Drawing obtained.

Comment:

Performance Step: 2 Locates MU-V-180 relief valve at coordinate 03 Standard: Relief Valve located.

Comment:

...; Performance Step: 3 Candidate reviews isolation pOints.

Standard:

Identifies MU-V-38 breaker needs to be added (open)

Should add info tag to control switch for MU-V-38.

Comment:

...; Performance Step: 4 Candidate reviews isolation pOints.

Standard:

Identifies MU-V-39 breaker needs to be added (open)

Should add info tags to control switch for MU-V-39.

Comment:

TMI 2011 NRC JPM A2 SRO NUREG 1021, Revision 9 Supp 1

___ IiInWh.II_'~'_ _ _ _ _ ' ' ' _'iIIa 'ia'_'_ _ _ _ . - - - - - - - - - - - -

Appendix C Page 5 of 11 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 5 Candidate reviews restoration points.

Standard:

Identifies MU-V-38 and MU-V-39 breakers need to be added (closed)

Should add line to remove info tags from control switches for MU-V-38 and MU-V-39 to be (close MU-V-38) and (Auto Close MU-V-39)

MU-V-33A, B, C, D Breakers to be ON Comment:

Performance Step: 6 Candidate returns application for correction.

Standard: Candidate identifies that Worker Tag Out can not be approved as is.

Evaluator Cue: If candidate determines error in Worker Tag Out but does not correct the errors request, "Please correct Worker Tag Out to condition where it could be approved."

Comment:

Terminating Cue: When candidate has identified and corrected errors with Worker Tag Out JPM may be terminated.

STOP TIME: TIME CRITICAL STOP TIME: N/A TMI 2011 NRC JPM A2 SRO NUREG 1021, Revision 9 Supp 1

Appendix C Page 6 of 11 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2011 NRC "IPM SRO A2 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

TMI 2011 NRC JPM A2 SRO NUREG 1021, Revision 9 Supp 1

Appendix \,. Page 7 of 11 Form ES-C-1 Answer key do not hand out Non- Power Plant Work: 0 Worker Tagout Log # EXAM-1 0-1 Attachment 19 Power Plant Work: Worker Tagout Clearance Form Operations Authorization Required (Operations Authorization may [gj Page 1 of2 Prior to starting Worker Tagout: [gj be required) 1 System: 211 Equipment Tag: MU-V-180

Description:

RCP SEAL RETURN LINE VALVE TO RCD Description of work: REPLACE FLANGE GASKET Lead worker: MARINKOV 8593 Extension: Pager: _ _ f TAG TAG TAG TAG VERIF. RTS RTS RTS VERIF.

ISOLATION POINT Ea. TAG /EaUIPMENT NAME SEa TYPE POSITION BY BY SEa POSITION BY BY MUN-3&-EX1,Mtl..y ... :OPEHIL.OQ'l'USHBUTTONS 1 INF CLO 23 CL.O MON49-1$1l(1;~~~ OPiSt4AeLOSElOFF CONTROL SWIT¢H :2 ~Nf; AU~ 22 ~

MU-V-2S-EX1 MU-V-2S OPEN/CLOSE/OFF CONTROL SWITCH 3 INF AUC 21 AUC MU-V-33A-EX1 MU-V-33A OPEN CLOSE PUSHBUTTONS 4 INF CLO 20 OPN MU-V-33B-EX1 MU-V-33B OPEN CLOSE PUSHBUTTONS S INF CLO 19 OPN MU-V-33C-EX1 MU-V-33C OPEN CLOSE PUSHBUTTONS 6 INF CLO 18 OPN MU-V-33D-EX1 MU-V-330 OPEN CLOSE PUSH BUTTONS 7 INF CLO 17 OPN MU-V-2S-BK 1A ES VALVES MCC UNIT 40 8 OGR OFF 16 ON MU-V-39-'BK:1AESVALVES MCCUNJll~1) 9 DBR OFF 15 ON SPECIAL INSTRUCTIONS: c2016175 COMMENTS (E. G. THROTTLED VALVE NOTES): OP-TM-211-000, 302-660 TAGOUT PREPARER: DATE: 06/24/2011 SUPERVISOR APPROVAL: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ DATE: _ _ _ __

TMI 2011 NRC JPM A2 SRO NUREG 1021, Revision 9 Supp 1

Appendix '- Page 8 of 11 Form ES-C-1 Answer key do not hand out OPERATIONS AUTHORIZATION (IF REQUIRED): _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ DATE: _ _ _ __

2'° OPERATIONS AUTHORIZATION (IF REQUIRED): _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ DATE: _ _ _ __

OP-MA-1 09-1 01 Revision 5 Page 125 of 135 Attachment 19 Worker Tagout Clearance Form Page 2 of 2 I TAG TAG TAG TAG VERIF. RTS i RTS i RTS i VERIF.I ISOLATION POINT EQ. TAG /EQUIPMENT NAME SEQ _...TYPE POSITION BY BY SEQ POSITION BY BY MU*V*~1B RAOWASTE: MCC UMI!&A fO QtlR OFF 14 OFF MU-V-33A-BK 1A RADWASTE MCC UNIT 5B 11 DGR OFF 13 ON MU-V-33B-BK 1A RADWASTE MCC UNIT 5C 12 OGR OFF 12 ON r** -------- --------- ~ ... --------- ...... ..... .._---_.

MU-V-33C-BK lA RADWASTE MCC UNIT 50 13 DGR OFF 11 ON MU-V-330-BK 1A RADWASTE MCC UNIT 7B 14 OGR OFF 10 ON MU-V-33A RC-P-1AII1 SEAL LEAK-OFF ISOLATION VALVE 15 OGR HWT 9 TAO

....- -------- _ . . . . _---_ . ..... ~ -------

MU-V-33B RC-P-1B III SEAL LEAK-OFF ISOLATION VALVE 16 DGR HWT 8 TAO MU-V-33C RC-P-1C III SEAL LEAK-OFF ISOLATION VALVE 17 OGR HWT 7 TAO MU-V-33D RC-P-1D #1 SEAL LEAK-OFF ISOLATION VALVE 18 OGR HWT 6 TAO MU-V-25 CONTAINMENT ISOLATION RCP SEAL RETURN VLV OP 19 DGR HWT 5 TAO MU-V-38 RCP SEAL #1 BYPASS CONTROL VALVE OPERATOR 20 DGR HWT 4 TAO MU-V-39 RCP STANDPIPE FILL ISOL VALVE OPERATOR 21 DGR HWT 3 TAO MU-V-141 MU-V-25 LEAK RATE TEST AND DRAIN VALVE 22 INF OTD 2 CAC

[MU-V-179A RC-P-1 A SEAL LEAK OFF FLOW METER VENT 23 INF OPN 1 CAC Note: Additional copies of this sheet may be used if additional isolation pOints are required.

TMI 2011 NRC JPM A2 SRO NUREG 1021, Revision 9 Supp 1

Appendix C Page 9 of 11 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: You are the Duty SRO Plant is in a refueling outage with RCS level in the green band of the refueling canal.

A worker tag out, for the liquid portion only, has been prepared for a leaking flange on RCP Seal Return Line Relief MU-V-180.

The line is currently filled.

INITIATING CUE: You are directed to review the Worker Tag Out for accuracy and sign as Operations Authorization.

TMI 2011 NRC JPM A2 SRO NUREG 1021, Revision 9 Supp 1

Appendix ~ Page 10 of 11 Form ES-C-1 JPM CUE SHEET May be handed out to Candidate Non- Power Plant Work: D Worker Tagout Log # EXAM-1 0-1 Attachment 19 Power Plant Work: Worker Tagout Clearance Form Operations Authorization Required (Operations Authorization may [g] Page 1 of 2 Prior to starting Worker Tagout: [g]

be required)

Unit: .L System: 211 Equipment Tag: MU-V-180

Description:

RCP SEAL RETURN LINE VALVE TO RCD Description of work: REPLACE FLANGE GASKET Lead worker: MARINKOV 8593 Extension: Pager: _ _

~~~~~~~~~~

TAG TAG TAG TAG VERIF. RTS RTS RTS VERIF.

ISOLATION POINT EQ. TAG /EQUIPMENT NAME POSITION BY BY SEQ TYPE POSITION BY BY SEQ MU-V-25-EX1 MU-V-25 OPEN/CLOSE/OFF CONTROL SWITCH 1 INF AUC 19 AUC MU*V*33A*EX1 MU-V-33A OPEN CLOSE PUSHBUTTONS 2 INF CLO 18 OPN MU*V-33B-EX1 MU-V-33B OPEN CLOSE PUSHBUTTONS 3 INF CLO 17 OPN MU-V-33C-EX1 MU-V-33C OPEN CLOSE PUSHSUTTONS 4 INF CLO 16 OPN MU-V-330-EX1 MU-V-330 OPEN CLOSE PUSH BUTTONS 5 INF CLO 15 OPN MU-V-25*SK 1A ES VALVES MCC UNIT 40 6 OGR OFF 14 ON MU-V*33A-BK 1A RAOWASTE MCC UNIT 5S 7 OGR OFF 13 OFF MU-V-33B-BK 1A RAOWASTE MCC UNIT 5C 8 OGR OFF 12 OFF MU-V-33C-BK 1A RAOWASTE MCC UNIT 50 9 DGR OFF 11 OFF SPECIAL INSTRUCTIONS: c2016175 COMMENTS G. THROTTLED VALVE NOTES): OP-TM-211-000, 302-660 TAGOUT PREPARER: G. Hoek DATE: 06/24/2011 SUPERVISOR APPROVAL: Megill Maintenance DATE: _Exam Day__

OPERATIONS AUTHORIZATION (IF REQUIRED): _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ DATE: _ _ _ _ __

2 NO OPERATIONS AUTHORIZATION (IF REQUIRED): _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ DATE: _ _ _ __

TMI 2011 NRC JPM A2 SRO NUREG 1021, Revision 9 Supp 1

Appendix ~ Page 11 of 11 Form ES-C-1 JPM CUE SHEET May be handed out to Candidate OP-MA-109-101 Revision 5 Page 125 of 135 Attachment 19 Worker Tagout Clearance Form Page 2 of 2

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

-~~-~

-~

TAG TAG TAG TAG VERIF. RTS RTS RTS VERIF.

ISOLATION POINT EQ. TAG IEQUIPMENT NAME BY SEQ TYPE POSITION BY BY SEQ POSITION BY MU-V-33D-BK 1A RADWASTE MCC UNIT 7B 10 DGR OFF I 10 I OFF I

MU-V-33A RC-P-1A#1 SEAL LEAK-OFF ISOLATION VALVE 11 DGR HWT 9 TAO

-~~--

~-~ ~-~

MU-V-33B RC-P-1B #1 SEAL LEAK-OFF ISOLATION VALVE 12 DGR HWT 8 TAO

~~~~ ~-~~

~-~ ~-- -~

MU-V-33C RC-P-1C #1 SEAL LEAK-OFF ISOLATION VALVE 13 DGR HWT 7 TAO

-~~~ ~-

MU-V-33D RC-P-10 #1 SEAL LEAK-OFF ISOLATION VALVE 14 DGR HWT 6 TAO

-~~-~

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

MU-V-25 CONTAINMENT ISOLATION RCP SEAL RETURN VLV OP 15 OGR HWT 5 TAO MU-V-38 RCP SEAL #1 BYPASS CONTROL VALVE OPERATOR 16 DGR HWT 4 TAO

~--~~-~

~-~

MU-V-39 RCP STANDPIPE FILL (SOL VALVE OPERATOR 17 DGR HWT 3 TAO

-~~-~ r--~~-~

MU*V-141 MU-V-25 LEAK RATE TEST AND DRAIN VALVE 18 INF OTD 2 CAC

~~~~--

'-- c------~ ~-~ ~---~--~

MU*V-179A RC-P-1A SEAL LEAK OFF FLOW METER VENT 19 INF OPN 1 CAC

--~~-

,. -~

-~

~~~~ ~- i--~~ ~---~ f-~~

~-

-~

~- ~~~~-~

~---

~-~

~-~ ~--~

~--'---~ ~--~-~

~_~ ~_~c~~~_~

~ ~- ~--~~

--~

Note: Additional copies of this sheet may be used if additional isolation points are required.

TMI 2011 NRC JPM A2 SRO NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form Facility: TMI Unit 1 Task No.: EPAA101014 Task

Title:

JPM No.: 2011 NRC JPM SRO Authorize emergency personnel A3 radiation exposure in excess of 5 REM KIA

Reference:

2.3.4 (3.7) New for 2011 NRC Exam Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

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

Initial Conditions:

You are the Shift Emergency Director.

A large break LOCA occurred; including significant fuel damage.

The TSC is manning but has not been activated.

A missing operator has been located. He is seriously injured, conscious, but unable to move and laying in an uncontaminated area where the general radiation level is 300 R/hr.

It is estimated that four people using a stretcher can move him out of the area in a maximum of 10 minutes.

Six people all between 50 and 60 years of age, have volunteered to perform the task. Pertinent information is provided below.

No radiation management personnel have arrived on site.

The rescue team must traverse through a high contamination area to perform the rescue.

TMI 2011 NRC ...IPM SRO A3 NU REG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 VOLUNTEER DATA CURAI;NT / N-:ANrHR-NAME << SSN ANNUAL PA$'fWORK H1S"fQRY MEOICAl;.2RESPIRATOR EXPOSURE <<

QUALIFIED Volunteer 123-45-6789 300 mRem None No I #1 Volunteered in Chernobyl Volunteer 234-56-7890 250 mRem - received 30 Rem acute Yes

2 dose TEDE Volunteer 345-67-8901 150 mRem None Yes

3 Volunteered in Japan Volunteer 456-78-9012 400 mRem received 5 Rem acute Yes

4 dose TEDE Volunteered in TMI-2 Volunteer 567-89-0123 200 mRem - received 2 Rem acute Yes

5 dose TEDE Volunteer I 678-90-1234 100 mRem None Yes

6 i

I Task Standard: All critical steps evaluated as SAT.

Required Materials:

EP-M-113 REV 10, Personnel Protective Actions

EP-M-113-F-02 REV B, Authorization for Emergency Exposure

Calculator General

References:

EP-M-113 REV 10, Personnel Protective Actions

EP-M-113-F-02 REV B, Authorization for Emergency Exposure Handouts:

EP-M-113 REV 10, Personnel Protective Actions

EP-M-113-F-02 REV B, Authorization for Emergency Exposure Initiating Cue:

You are the Emergency Director. Perform the required actions prior to dispatching the team of volunteers to rescue the injured man.

Time Critical Task: N/A Validation Time: 10 minutes TMI 2011 NRC JPM SRO A3 NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 SIMULATOR SETUP N/A TMI 2011 NRC JPM SRO A3 NUREG 1021, Revision 9 Supp 1

Appendix Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check)

Evaluator Cue: Provide EP-M-113, Personnel Protective Actions Evaluator Cue: If asked, inform the examinee that the plan was approved when it was determined that the individual could be moved by four people in 10 minutes, or less.

-J Performance Step: 1 ASSURE that the emergency exposure is for a bona fide emergency involving risk of life or limb, or the destruction of valuable property.

A. PLAN emergency operations prior to entry.

B. WEAR respiratory protection and protective clothing to reduce contamination where possible.

Standard: Examinee determines emergency exposure is for a bonafide emergency. And discusses the requirement to wear respiratory protection and protective clothing.

Examinee determines that Volunteer # 1 can not be used for the rescue efforts Comment:

Performance Step: 2 DETERMINE if emergency exposure limits in excess of 5 Rem TEDE (EPA-400 lower limits) are required for Exelon emergency workers.

Standard: Examinee determines that maximum stay time would result in >5 Rem TEDE.

Comment:

TMI 2011 NRC JPM SRO A3 NUREG 1021, Revision 9 Supp 1

Appendix Page 5 7 Form ES-C-1 PERFORMANCE INFORMATION Evaluator Cue: When requested, provide 4 copies of EP-AA-113-F-02.

Evaluator Cue: If candidate discusses obtaining volunteers acknowledgment that they have volunteered and they are aware of associated risks involved: "All volunteers verbally acknowledge they understand they have volunteered and are aware of the risks associated with Attachment 1" Performance Step: 3 For exposures at or above 5 Rem TEDE {EPA-400 lower limits},

COMPLETE an Authorization for Emergency Exposure (EP-AA 113-F- 02).

Standard: Examinee:

Completes EP-AA-113-F-02 for each volunteer.

Checks Block 3 (Authorized to receive greater than 25 Rem TEDE)

Informs the volunteers and obtains their acknowledgment that the task is voluntary and they're aware of the risks.

Have volunteer sign after reviewing Attachment 1, EMERGENCY WORKER EXPOSURE LIMITS AND ASSOCIATED RISKS.

Signs as Station Emergency Director.

Comment:

-J Performance Step: 4 All emergency exposures in excess of 25 Rem TEDE shall be voluntary and shall be limited to once in a lifetime. Persons who may receive exposures greater than 25 Rem TEDE shall be fully aware of the risks involved.

Standard: Examinee determines emergency exposure in excess of 25 Rem TEDE shall be limited to once in a lifetime and identifies Volunteer #2 can not be used for the rescue efforts.

Comment:

Terminating Cue: After candidate identifies Volunteer #s 1 and 2 can not be used for the rescue efforts, this JPM is complete.

TMI 2011 NRC JPM SRO A3 NUREG 1021, Revision 9 Supp 1

Appendix 6 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2011 NRC JPM SRO A3 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

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

TMI 2011 NRC JPM SRO A3 NUREG 1021, Revision 9 Supp 1

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

You are the Shift Emergency Director.

A large break LOCA occurred; including significant fuel damage.

The TSC is manning but has not been activated.

A missing operator has been located. He is seriously injured, conscious, but unable to move and lying in an uncontaminated area where the general radiation level is 300 R/hr.

It is estimated that four people using a stretcher can move him out of the area in a maximum of 10 minutes.

Six people all between 50 and 60 years of age, have volunteered to perform the task. Pertinent information is provided below.

No radiation management personnel have arrived on site.

The rescue team must traverse through a high contamination area to perform the rescue.

VOLUNTEER DATA

./ ......

CURRENT b_~= . . . N:-AN-HR- .1 I NAME SaN'.

~N,~~~E" RA8TW~RKHISrORY

<" 'i'ti __ '

ME;OlCALijE$PtRATOR .

QU~t..IFIED . . I RE

@/'/'<

I ..... .. EXP ...

Volunteer I 123-45-6789 300 mRem ! None No

1 Volunteered in Chernobyl Volunteer 234-56-7890 250 mRem - received 30 Rem acute Yes

2 I dose TEDE Volunteer 345-67-8901 I 150 mRem None Yes

3 Volunteered in Japan Volunteer 456-78-9012 400 mRem - received 5 Rem acute Yes

4 dose TEDE Volunteered in TMI-2 Volunteer 567 0123 200 mRem - received 2 Rem acute Yes

5 dose TEDE I

I Volunteer 678-90-1234 100 mRem None Yes

6 I INITIATING CUE: You are the Emergency Director. Perform the required actions prior to dispatching the team of volunteers to rescue the injured man.

TIME CRITICAL: No TMI 2011 NRC JPM SRO A3 NUREG 1021, Revision 9 Supp 1

10'1 fl IUL iwwU Appendix C Job Performance Measure Form ES-C-1 Facility: TMI Unit 1 Task No.: EPAA101006 Task

Title:

Given a set of conditions, determine JPM No.: 2011 NRC JPM SRO the Emergency Action Level (EAL) A4 and make a Protective Action Recommendation (PAR) lAW the facility Emergency Plan.

KIA

Reference:

2.4.44 (4.4) New for 2011 NRC JPM To be conducted one on one.

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

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

Initial Conditions: The plant was at 100% power.

15:00 - Large Break LOCA resulting in ESAS actuations, 4#RB, 30#

RB, 1600psig RCS, 500psig RCS.

Reactor Coolant Pumps were manually tripped based on indication of 5°F superheat.

An Alert was declared FA1 based on 1 barrier lost (Coolant)

Current Conditions;

Time 15:30

Reactor Building Pressure is 32 psig lowering very slowly.

RM-*G-6 is reading 10 R/hr rising slowly.

RM-*G-22 is reading 4.6 E +03 R/hr steady.

RM-G-23 is reading 3.9 E +03 R/hr steady.

Outside temperature is 49 'F.

The wind is from 120* at 8 MPH.

Task Standard: All critical steps evaluated as SAT.

Required Materials: Perform in a location with:

EAL Matrix

Shift Emergency Director Book 2011 NRC JPM SRO A4 NUREG 1021, Revision 9

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

References:

EP-AA-111, EMERGENCY CLASSIFICATION AND PROTECTIVE ACTION RECOMMENDATIONS, Revision 16

EP-AA-111-F-09, TMI PLANT BASED PAR FLOWCHART, Revision D

EP-AA-112-100-F-01, SHIFT EMERGENCY DIRECTOR CHECKLIST, Revision L

EP-AA-112-F-09, EMERGENCY PUBLIC ADDRESS ANNOUNCEMENTS, Revision C

EP-MA-114-100-F-01, STATE/LOCAL EVENT NOTIFICATION FORM, Revision J

EP-AA-1009 EXELON NUCLEAR RADIOLOGICAL EMERGENCY PLAN ANNEX FOR THREE MILE ISLAND (TMI) STATION Revision 17

EP-AA-112-100-F-07 MID-ATLANTIC ERO NOTIFICATION OR AUGMENTATION Revision F.

Handouts: EP-AA-112-1 00-F-01, SHIFT EMERGENCY DIRECTOR CHECKLIST, signed off for the declared alert.

Initiating Cue: You are the Shift Manager. Respond in accordance with the EP-AA 112-100-F-01, SHIFT EMERGENCY DIRECTOR CHECKLIST.

Time Critical Task: Yes Validation Time: 20 minutes SIMULATOR SETUP N/A 2011 NRC JPM SRO A4 NUREG 1021, Revision 9

Appendix C Page 3 of 9 Form ES-C-1 PERFORMANCE INFORMATION Start Time: _ _ _ _ (When Cue is acknowledged - this is also Time Critical Start Time)

(Denote Critical Steps with a check)

Performance Step: 1 Compares updated conditions to the EAL Table.

Standard:

Determines Primary Containment Barrier has been potentially lost. 3c1

Determines Reactor Coolant System has been lost. 2a 1

Determines Fuel clad has been lost. 1c1.

Determines conditions are met for GENERAL EMERGENCY EAL FG1.

Evaluator Cue: Inform candidate Time Critical time starts with acknowledgement of CUE.

Comment:

EP-AA-112-1 00-F-01, SHIFT EMERGENCY DIRECTOR CHECKLIST Performance Step: 2 Implement EP-AA-112-100-F-01 for GE.

Standard: Refers to Section 1.4.

Comment:

2011 NRC JPM SRO A4 NUREG 1021, Revision 9

Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION EP-AA-112-1 00-F-01, Section 1.4.A

.y Performance Step: 3 Announce Event Classification to the Control Room staff.

Standard: Announces GE based on Loss of two barriers FUEL and RCS with a potential loss of CONTAINMENT.

Comment:

.y Time Critical #1 Time start _ _ _ - Time of declaration _ _ _ = _ __

Standard: Less than 15 minutes.

EP-AA-112-1 OO-F-01, Section 1.4.B Performance Step: 4 Record the EAL and Declaration threshold{s) (as applicable).

Standard: Records EAL FG1 on EP-AA-112-100-F01.

Records thresholds 3c1 and 2a1 and 1c1.

Comment:

EP-AA-112-1 00-F-01, Section 1.4.C Performance Step: 5 For Security events - - - .

Standard: N/A - not a security event.

Comment:

2011 NRC JPM SRO A4 NUREG 1021, Revision 9

Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION EP-AA-112-1 00-F-01, Section 1.4. D

" Performance Step: 6 USE the Emergency Public Address Announcements form to select and direct the appropriate public address announcement for a General Emergency within 15 minutes of event classification.

Standard:

Fills out EP-AA-112-F-09 found at tab 1 and hands to communicator (NRC examiner) to make announcement.

Comment:

EP-AA-112-1 00-F-01, Section 1.4. E Performance Step: 7 If the ERO has NOT already been activated, then, PERFORM the "ERO Response Required" steps of the ERO Notification or Augmentation form.

Standard: N/A ERO full augmentation was made at Alert.

Comment:

2011 NRC JPM SRO A4 NUREG 1021, Revision 9

."_. _ . _ _ .,_ _ _ _ _ _ _... MW_-Ifl!:.~_MIl!_U;_'

w~_' '._-x.-'_ _ _ __

Appendix Page 6 of 9 Form PERFORMANCE INFORMATION EP-AA-112-1 00-F-01, Section 1.4. F

~ Performance Step: 8 DETERMINE the correct plant-based PAR per the Emergency Classification and Protective Action Recommendations procedure and the appropriate site**specific PAR flowchart:

Classification and PAR Procedure TAB 6 Plant Based PAR Flowchart TAB 7 Standard: Determine PAR lAW EP-AA-111-F-09; GE - Yes Release - Yes Projection - Yes Shelter 5 - mile radius Recommend KI for sheltered areas Advise remainder of EPZ to monitor EAS Messages.

Evaluator Cue: If Shift Dose Assessor is requested to provide DAPAR information respond "Offsite dose projections are < 1 REM TEDE and < 5REM CDE thyroid".

Comment:

2011 NRC JPM SRO A4 NUREG 1021, Revision 9

Appendix C Page 7 of 9 Form ES-C-1 PERFORMANCE INFORMATION EP-AA-112-1 00-F-01 , Section 1 .4. F

" Performance Step: 9 INITIATE required State/Local notifications within 15 minutes of the event classification (including initial PAR) as required per the Notifications procedure.

Notification Procedure (EP-MA-114-1 00)

Notification Form (EP-MA-114-1 00**F-01)

Release in Progress Determination Guidance (EP-AA-114-F-01)

Standard: Fills out EP-MA-114-1 00-F-01 using EP-MA-114-1 00 and EP AA-114-F-01 as guidance, hands to communicator (NRC Examiner).

Evaluator Note:

Minimum requirements on ENF to meet critical task:

3.a GENERAL EMERGENCY 3.d ESCALATION 4.a EMERGENCY ACTION LEVEL NO. is FG1 7.b PAR Evacuate 360 checked, 5 miles filled in.

Record TIME to be used as stop time for second critical time.

Time above - Time of Declaration =

_ _ _ _< 15 minutes for second critical time.

Comment:

Terminating Cue: When the candidate hands the completed Emergency Notification Form to the Communicator: Evaluation on this JPM is complete.

2011 NRC JPM SRO A4 NUREG 1021, Revision 9

Appendix C Page 8 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2011 NRC . . 'PM SRO A4 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2011 NRC JPM SRO A4 NUREG 1021, Revision 9

Appendix Page 9 of 9 JPM CUE SHEET Initial Conditions: The plant was at 100% power.

15:00 - Large Break LOCA resulting in ESAS actuations, 4#RB, 30#

RB, 1600psig RCS, 500psig RCS.

Reactor Coolant Pumps were manually tripped based on indication of 5°F superheat.

An Alert was declared FA1 based on 1 barrier lost (Coolant)

Current Conditions;

Time 15:30

Reactor Building Pressure is 32 psig lowering very slowly.

RM-G-6 is reading 10 R/hr rising slowly.

RM-G-22 is reading 4.6 E +03 R/hr steady.

RM-G-23 is reading 3.9 E +03 R/hr steady.

Outside temperature is 49 'F.

The wind is from 120' at 8 MPH.

Initiating Cue: You are the Shift Manager. Respond in accordance with the EP AA-112-100-F-01, SHIFT EMERGENCY DIRECTOR CHECKLIST.

Time Critical Yes 2011 NRC JPM SRO A4 NUREG 1021, Revision 9

~"'_~_ . . . ._. _ _

.,,¢l _ _ _ _ . _.

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

-~<<--<--

Facility: THREE MILE ISLAND UNIT 1 Task No.: EOP001001 Task

Title:

Respond to an Abnormal Transient JPM No.: 2011 NRC JPM A Without Reactor Trip. with fault KIA

Reference:

007 EA2.04 (4.4/4.6) New ILT 10-1 Alt path Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance:

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

Initial Conditions:

For this event you are assigned the duties of the Unit RO.

The instructor/examiner will act as the ARO and CRS.

The ICO will act as Auxiliary Operators in the plant as needed.

The Reactor is operating at 100% power with ICS in full automatic.

No Maintenance or surveillances are scheduled for this shift.

Task Standard: All critical steps evaluated as SAT.

Required Materials: None General

References:

OP-TM-EOP-001, REACTOR TRIP, Rev. 10 Handout: None Initiating Cue: Respond to the cues and indications given by the simulator as well as any input from the CRS.

Time Critical Task: NO Validation Time: 5 minutes 2011 NRC JPM A NUREG 1021, Revision 9 Supp 1

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

100% IC16 (Temporarily snapped into IC-231)

1. Insert the following Malfunctions:

TC()1, Turbine Trip, on Event #1 RD:27 A, Reactor Manual Trip Block, immediately RD27B, DSS Manual Trip Block, immediately RD28, Reactor Auto Trip Block, immediately RD32, DSS Auto Actuation Failure, immediately

2. When the above steps are completed for this and other JPMs to be run concurrently then validate, if not previously validated, the concurrently run JPMs using the JPM Validation Checklist.

3. This completes the setup for this JPM.

2011 NRC JPM A NUREG 1021, Revision 9 Supp 1

Appendix C Page 3 of 7 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

ICO CUrE: When directed by the Evaluator, insert EVENT 1 OP-TM-EOP-001, Step 2.1 Performance Step: 1 PRESS both Reactor Trip and DSS push buttons Standard: Announces reactor trip and entry into OP-TM-EOP-001.

Recognizes that RPS has failed to trip the Reactor and depresses the Reactor Trip and DSS push buttons on CC.

CommE~nt:

Evaluator Cue: As CRS, acknowledge reactor trip and entry into EOP-001 OP-TM-EOP-001, Step 2.2 Performance Step: 2 VERIFY REACTOR SHUTDOWN Standard: Verifies one or more of the following: Power Range Nls are NOT less than 5% power as indicated on Console Center, all control rods are NOT inserted, Source Range count rate is NOT continuously lowering.

Comment:

Alternate Path begins. OP-TM-EOP-001, Step 2.1 RNO Step 1 2011 NRC JPM A NUREG 1021, Revision 9 Supp 1

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-EOP-001, Step 2.2 RNO Step 1

'1/ Performance Step: 3 TRIP both

'1/ 1L-02 and Standard: Operates the 1L-02 control switch handle to the trip position on Panel Right.

Comment:

OP-TM-EOP-001, Step 2.2 RNO Step 1

.J Performance Step: 4 TRIP

.J 1G-02 Standard: Operates the 1G-02 control switch handle to the trip position on Panel Rig ht.

Comment:

OP-TM-EOP-001, Step 2.2 RNO Step 2 Performance Step: 5 If the REACTOR is SHUTDOWN, then GO TO step 2.3 Standard: Verifies one or more of the following: Power Range Nls are less than 5% power as indicated on Console Center, all control rods are inserted, Source Range count rate is continuously lowering.

Comment:

OP-TM-EOP-001, Step 2.3 Performance Step: 6 PRESS Turbine Trip pushbutton Standard: Depresses Turbine Trip pushbutton on Panel CL.

Comment:

2011 NRC JPM A NUREG 1021, Revision 9 Supp 1

Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-EOP-001, Step 2.4 Performance Step: 7 VERIFY the turbine stop valves are Closed Standard:

Observes indications on Panel el, TG-KI-0001 through TG KI-0004, to verify Turbine Stop Valves are CLOSED.

Announces that the Reactor is shutdown and OP-TM-EOP 001 IMAs have been completed, Comment:

Terminating Cue: When candidate announces Immediate Actions (IMAs) of EOP-001 are complete JPM may be terminated.

STOP TIME: TIME CRITICAL STOP TIME: N/A 2011 NRC JPM A NUREG 1021, Revision 9 Supp 1

Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: TMI 2011 NRC JPM A Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2011 NRC JPM A NUREG 1021, Revision 9 Supp 1

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

For this event you are assigned the duties of the Unit RO.

The instructor/examiner will act as the ARO and CRS.

The ICO will act as Auxiliary Operators in the plant as needed.

The Reactor is operating at 100% power with ICS in full automatic.

No Maintenance or surveillances are scheduled for this shift.

INITIATING CUE: Respond to the cues and indications given by the simulator as well as any input from the CRS.

TIME CRITICAL: No 2011 NRC JPM A NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND UNIT 1 Task No.: 22301010 Task

Title:

Respond to a Loss of Pressurizer JPM No.: 2011 NRC ..IPM B Level Control with Failures KIA

Reference:

011 A2.03 (3.8/ 3.9) New ILT 10-1 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance:

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

Initial Conditions:

For this event you are assigned the duties of the Unit RO.

The instructor/examiner will act as the ARO and CRS.

The ICO will act as Auxiliary Operators in the plant as needed.

The Reactor is operating at 100% power with ICS in full automatic.

No Maintenance or surveillances are scheduled for this shift.

Task Standard: All critical steps evaluated as SAT.

Required Materials: None General

References:

OP-TM-MAP-G0205, PZR Level HI/LO

OP-TM-EOP-010, EMERGENCY PROCEDURE RULES, GUIDES AND GRAPHS, Guide 9 RCS Inventory Control Handout: None Initiating Cue: Respond to the cues and indications given by the simulator as well as any input from the CRS.

Time Critical Task: NO 2011 NRC JPM B NUREG 1021, Revision 9 Supp 1

aliliit Appendix C Job Performance Measure Form ES-C-1 Worksheet Validation Time: 10 minutes 2011 NRC JPM B NUREG 1021, Revision 9 Supp 1

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

100% IC16 (Temporarily snapped into IC-232)

1. Insert the following Malfunctions:

RC04, RC1-LT1 RC PZR LVL Trans failure @ 0%, on Event #1

2. Insert the following Overrides:

02A5S22-ZOIPBCMUV18 MU-V-18 Close Pushbutton ON assign to EVENT 2 02A5S21-ZDIPBOMUV18 MU-V-18 Open Pushbutton OFF IMMEDIATELY 02A5A10-ZAIMU3MIC FLO MU-V-5 Letdown Flow control AI assign 0

3. Create the following Trigger:

HLORC1L1C(2)==1&&MUVMUV17>O.01 as trigger 2

4. When the above steps are completed for this and other JPMs to be run concurrently then validate, if not previously validated, the concurrently run JPMs using the JPM Validation Checklist.

5. This completes the setup for this JPM.

2011 NRC JPM B NUREG 1021, Revision 9 Supp 1

Appendix C Page 4 of 11 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

ICO CUE: When directed by the Evaluator, insert EVENT 1 OP-TM-MAP-G0205, Step 4.1-1

~ Performance Step: 1 PLACE MU-V-17 in Hand and controi PZR level.

Standard: Announces Pressurizer level lowering and failed level instrument.

Presses MU-V-17 Hand Control pushbutton, verifies red auto light out, white hand light lit.

Raises on MU-V-17 controller to restore Pressurizer level.

Comment:

Evaluator Cue: As CRS, acknowledge condition and entry into OP-TM-MAP G0205 OP-TM-MAP-G0205, Step 4.1-2 Performance Step: 2 SELECT a valid level signal.

Standard: Selects RC-1 LT -3 instrument by pressing pushbutton on Console Center.

Comment:

2011 NRC JPM B NUREG 1021, Revision 9 Supp 1

Appendix C Page 5 of 11 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-MAP-G0205, Step 4.1-3 Performance Step: 3 PLACE MU-V-17 in AUTO.

Standard: Presses MU-V-17 Auto Control pushbutton, verifies red auto light lit, white hand light out.

Comment:

ICO Cue: When MU-V-17 placed in Auto, ensure MU-V-18 has closed.

OP-TM-MAP-G0205, Step 4.2 Performance Step: 4 If PZR level can not be restored with automatic or manual control of MU-V-17, then INITIATE OP-TM-EOP-010, Guide 9 Standard: Recognizes that MU-V-18 is closed and/or Pressurizer level is not being restored and enters Guide 9.

Comment:

Alternate Path starts here when candidate leaves MAP G0205 and enters Guide 9.

GUIDE 9, RCS INVENTORY CONTROL Step A.1 Performance Step: 5 VERIFY MU Tank Level> 55 inches and ESAS HPI is not actuated.

Standard: Verifies MU Tank level is >55 inches and ESAS HPI is not actuated.

Comment:

2011 NRC JPM B NUREG 1021, Revision 9 Supp 1

Appendix C Page 6 of 11 Form ES-C-1 PERFORMANCE INFORMATION GUIDE 9, RCS INVENTORY CONTROL Step A.2 Performance Step: 6 VERIFY MU Tank Level < 96 inches.

Standard: Verifies MU Tank Level < 96 inches. On Digital (CG).

Comment:

GUIDE 9, RCS INVENTORY CONTROL Step C.1 Performance Step: 7 VERIFY MU pump is operating.

Standard: Verifies a MU pump is operating, by observation of Discharge pressure, or flow. May use Red light on at MU-P-1 B extension control (CL).

Comment:

GUIDE 9, RGS INVENTORY CONTROL Step C.2 Performance Step: 8 VERIFY MU-V-5 is Closed.

Standard: Verifies MU-V-5 closed by observation of MU-V-5 controller potentiometer on (CC).

Comment:

GUIDE 9, RCS INVENTORY CONTROL Step C.3 Performance Step: 9 VERIFY MU24-FI > 20 gpm Standard: Looks at MU24-FI on (CG) upper section, observes flow is NOT

>20 gpm.

Comment:

2011 NRC JPM B NUREG 1021, Revision 9 Supp 1

Appendix C Page 7 of 11 Form ES-C-1 PERFORMANCE INFORMATION GUIDE 9, RCS INVENTORY CONTROL Step C.3 RNO Performance Step: 10 ENSURE MU-V-18 is Open.

Standard: Observes MU-V-18 is closed by Green light lit, and attempts to open MU-V-18 by pressing OPEI\I Pushbutton. May call to have NLO OPEN MU-V-18 locally.

Comment:

ICO Cue: When sent to open MU-V-18 locally, report in that the stem is stuck and MU-V-18 cannot be opened locally.

GUIDE 9, RCS INVENTORY CONTROL Step CA Performance Step: 11 ENSURE MU-V-17 is Open.

Standard: Ensures MU-V-17 is Open. MU-V-17 will NOT Open.

Comment:

GUIDE 9, RCS INVENTORY CONTROL Step C.5 Performance Step: 12 VERIFY PZR level is being restored.

Standcllrd: Recognizes MU24-FI is NOT> 20 gpm Comment:

2011 NRC JPM B NUREG 1021, Revision 9 Supp 1

Appendix C Page 8 of 11 Form ES-C-1 PERFORMANCE INFORMATION GUIDE 9, RCS INVENTORY CONTROL Step C.5 RNO Performance Step: 13 THROTTLE MU-V-217.

Standard: Throttles OPEN on MU-V-217 on (CC) by pressing OPEN PB then STOP PB to attempt to establish a flow of > 20 gpm on MU24-FI. If throttling full open, the examinee will not press the STOP PB.

Comment:

Examiner Note Examinee may state that step will not be taken as MU-V-18 being failed closed will prevent success. Examinee should then continue. If Examinee requests permission 'from SRO to skip step grant permission under a variance.

GUIDE 9, RCS INVENTORY CONTROL Step C.B Performance Step: 14 VERIFY MU24-FI > 20 gpm Standard: Recognizes MU24-FI is NOT> 20 gpm Comm4:mt:

GUIDE 9, RCS INVENTORY CONTROL Step C.B RNa

~ Performance Step: 15 THROTTLE MU-V-1BB or MU-V-1BD.

Standard: Throttles MU-V-1BB, by pressing Open PB then STOP PB on (CC), while observing FI-1127 for indication of> 20 gpm.

Comment:

2011 NRC JPM B NUREG 1021, Revision 9 Supp 1

Appendix C Page 9 of 11 Form ES-C-1 PERFORMANCE INFORMATION GUIDE 9, RCS INVENTORY CONTROL Steps C.7 and C.B Performance Step: 16 VERIFY PZR level is being restored.

Standard: Recognizes PZR level is being restored, by indications of flow>

20 gpm and rising level on Pressurizer Digital or Recorder indicators on (CG).

Comment:

Terminating Cue: JPM may be terminated when Examinee recognizes Pressurizer level is being restored by MU-V-16B.

STOP TIME: TIME CRITICAL STOP TIME: N/A 2011 NRC JPM B NUREG 1021, Revision 9 Supp 1

Appendix C Page 10 of 11 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No,: TMI 2011 NRC JPM B Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2011 NRC JPM B NUREG 1021, Revision 9 Supp 1

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

For this event you are assigned the duties of the Unit RO.

The instructor/examiner will act as the ARO and CRS.

The ICO will act as Auxiliary Operators in the plant as needed.

The Reactor is operating at 100% power with ICS in full automatic.

No Maintenance or surveillances are scheduled for this shift.

INITIATING CUE: Respond to the cues and indications given by the simulator as well as any input from the CRS.

TIME CRITICAL: No 2011 NRC ,JPM B NUREG 1021, Revision 9 Supp 1

_ _ _"_'__ )!l~_IM>'I'l_"_' __i>>._",*,dol\\lli"lP"iri__ ,*!I!:IiIWJid ~ ____ * **

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_ '_ _ _.....,. ._ ,_ ,- _ _ _,_'_ _...._'11-_._M,Jl_*'_lI!\j,..**_#iili_iJi1t_U1Ji_ _ _....

- aiI_ _ _ _ _ __

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND UNIT 1 Task No.: EOP001001 Task

Title:

Transfer to Reactor Building Sump JPM No.: 2011 NRC JPM C Recirculation KIA

Reference:

011 EA 1.05 (4.3 / 3.9) Bank JPM # TQ-TM-104-G21-J002 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

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

Initial Conditions:

The Reactor is shutdown with a LOCA in progress.

OP-TM-EOP-001 and OP-TM-EOP-006 are in progress.

OP-TM-EOP-010, Guide 20 has been completed.

BWST level has dropped below 15 feet and is continuing to lower.

Task Standard: All critical steps evaluated as SAT.

Required Materials: l\Jone General

References:

OP-TM-EOP-010, Guide 21, Rev 11 OP-TM-EOP-010, Rule 2, Rev 11 OP-TM-211-901, Rev 5 Handout: None Initiating Cue: The Control Room Supervisor has directed you to transfer the reactor building sump to recirculation mode lAW OP-TM-EOP-010, Guide 21.

2011 NRC JPM C NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: NO Validation Time: 17 minutes 2011 NRC JPM C NUREG 1021, Revision 9 Supp 1

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

100% IC1S (Temporarily snapped into IC-233)

1. InsE~rt the following:

Insort Malfunction TH07, LOCA on 'A' RCP discharge, at 50% severity InsE~rt remote DHR05 IN to energize CF-V-1A Breaker Insert remote DHROS IN to energize CF-V-1 B Breaker Insert remote DHR18 IN to energize DH-V-2 Breaker Insert remote DHR11 at 100% to open DH-V-S4 Insert remote DHR14 to OPEN to open DH-V-64 on EVENT 1 to open DH-V-38A/B Insert remote DHR32 at 20 to adjust BWST level Insert EXPERT COMMAND: dhvdhv6b > 0.01 on EVENT 2 "Command" irf dhr25 out. This will cause the breaker for DH-V-68 to trip when the examinee attempts to open DH-V-68.

2. Place the simulator in RUN.

Using OP-TM-EOP-001 and OP-TM-EOP-OOS, control and monitor plant conditions.

Complete all steps of Guide 20.

When BWST level is approximately 9.5 feet and the RB Flood Level is about 53 inches, place the Simulator in FREEZE.

3. When the above steps are completed for this and other JPMs to be run concurrently then validate, if not previously validated, the concurrently run JPMs using the JPM Validation Checklist.

4. This completes the setup for this JPM.

2011 NRC JPM C NUREG 1021, Revision 9 Supp 1

Appendix C Page 4 of 12 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

EVALU.ATOR CUE: When a laminated copy is located by the Examinee, provide a copy of OP-TM-EOP-010, Guide 21.

Performance Step: 1 Obtain copy of OP-TM-EOP-010, Guide 21.

Standard: Examinee obtains laminated copy of Guide 21.

Comment:

OP-TM-EOP-010, GUIDE 21, Step 1 Performance Step: 2 ANNOUNCE initiation of RB sump recirculation over the page and radio Standard: Examinee announces initiation of RB sump recirculation over plant page and radio.

Comment:

2011 NRC JPM C NUREG 1021, Revision 9 Supp 1

Appendix C Page 5 of 12 Form ES-C-1 PERFORMANCE INFORMATION EVALUATOR NOTE: Reactor Building Flood Level will be reading about 50 to 52 inches at this time, which is where it should be for this event.

OP-TM-EOP-010, GUIDE 21, Step 2 Performance Step: 3 VERIFY RB Flood Level> 29 inches Standard: Examinee will read Reactor Building Flood level indication on Panels CC and CR to verify that levels are greater than 29 inches.

Comment:

OP-TM-EOP-010, GUIDE 21, Step 3 Performance Step: 4 VERIFY either DH-V-38A or DH-V-38B is Closed Standard: Contacts AO via radio to verify either DH-V-38A or DH-V-38B is Closed.

BOOTH OPERATOR Respond as AO and report back that both DH-V-3SA and DH CUE: V-3SB are Closed.

Comment:

OP-TM-EOP-010, GUIDE 21, Step 4

-v Performance Step: 5 THROTTLE both DH-V-4A and DH-V-4B to the maximum controllable flow s 3000 gpm in each line Standard: Examinee throttles DH-V-4A and DH-V-4B using the OPEN, CLOSE, and STOP pushbuttons on Panels CC and CR to achieve max controllable flows of s 3000 gpm in each line.

Comment:

2011 NRC JPM C NUREG 1021, Revision 9 Supp 1

Appendix C Page 6 of 12 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-EOP-010, GUIDE 21, Step 5

" Performance Step: S When BWST level reaches 9.5 ft., or RB Flood Level> 56 inches, then by depressing Open P.B. (CC) and (CR)

" OPEN DH-V-6A OPEN DH-V-6B Standard: Examinee observes BWST level and Reactor Building Flood level on Panels CC and CR. When BWST level drops below 9.5 feet (which will happen prior to RB Flood level reaching 56 inches) examinee will attempt to OPEN DH-V-6A and DH-V-6B by depressing the OPEN pushbutton for each on Panels CC and CR respectively.

WHEN the pushbutton for DH-V-6B is depressed the breaker for this valve will trip, leaving the valve in the CLOSED position.

The examinee should announce that the breaker for DH-V-6B has tripped, and may request an AO to investigate the tripped breaker.

Examinee enters RNO section, announces same to CRS.

EVALUATOR CUE: As CRS acknowledge report of breaker trip for DH-V-SB and entry into RNO section.

BOOTH OPERATOR If asked, role-playas AO and respond to request to CUE: investigate tripped breaker (1B ESV unit 3B).

Comment:

2011 NRC JPM C NUREG 1021, Revision 9 Supp 1

Appendix C Page 7 of 12 Form ES-C-1 PERFORMANCE INFORMATION EVALUATOR NOTE: ALTERNATE PATH BEGINS OP-TM-EOP-010, GUIDE 21, Step 5 RNO

..,j Performance Step: 7 RNO:

PLACE affected DH pump in PTL

PLACE affected BS pump in PTL

INITIATE contingency actions for one DH pump lAW OP-TM 211-901, "Emergency Injection HPIILP'"

Standard: Examinee places extension control for DH-P-1 Bon (CR) in PTL.

Examinee places extension control for BS-P-1 B on (CR) in PTL.

Examinee obtains copy of OP-TM-211-901 and announces entry into procedure.

EVALUATOR CUE: Acknowledge entry into OP-TM-211-901 if/When announced.

EVALUATOR NOTE: Provide copy of OP-TM-211-901 Comment:

OP-TM-211-901 Performance Step: 8 Review precautions, limitations, & prerequisites.

Continue at step 4.2.7 under Contingency Actions Standard: Examinee reviews precautions, limitations, & prerequisites and determines, upon procedure review, that he/she needs to initiate contingency step 4.2.7.

Comment:

2011 NRC JPM C NUREG 1021, Revision 9 Supp 1

Appendix C Page 8 of 12 Form ES-C-1 PERFORMANCE INFORMATION EVALUATOR NOTE: OP-TM-211-901 Steps 4.2.7.1 - 4.2.7.3.A are N/A BOOTH OPERATOR Role-playas AO and if requested, report back that it has CUE: been determined that both DH-V-38A and B are accessible.

OP-TM-211-901, Step 4.2.7.3.B.1)

,j Performance Step: 9 If DH-V-38A and B are accessible, then perform the following:

CLOSE DH-V-4 on the train with the inoperable DH pump Standard: Examinee closes DH-V-4B on Panel by depressing Close P.B.

on (CR), Green light on Red light off.

Comment:

OP-TM-211-901, Step 4.2.7.3.B.2)

Performance Step: 10 OPEN DH-V-38A and DH-V-38B (Aux Bldg 281' el.)

Standard: Requests AO to open DH-V-38A and DH-V-38B.

Boon'l OPERATOR Role-playas AO, respond when requested to open DH-V-38A CUE: and DH-V-38B and report back that both valves are open.

Remote function DHR14 opens both valves (Event 1).

Comment:

2011 NRC ,JPM C NUREG 1021, Revision 9 Supp 1

Appendix C Page 9 of 12 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-211-901, Step 4.2.7.3.8.3)

Performance Step: 11 THROTTLE DH-V-4A and DH-V-48 to balance LPI flow lAW Rule 2 Standard: Examinee obtains laminated copy of Rule 2, LPI Throttling.

Announces performance of Rule 2.

EVALUATOR CUE: Acknowledge performance of Rule 2 for LPI throttling EVALUATOR NOTE: Provide copy of Rule 2 Comment:

OP-TM-EOP-010, RULE 2, Step 8.1 Performance Step: 12 VERIFY both DH-V-6A and DH-V-68 Closed Standard: Examinee determines that DH-V-6A is OPEN and DH-V-68 is CLOSED.

Examinee performs RNO section of Rule 2 for LPI throttling.

Comment:

OP-TM-EOP-010, RULE 2, Step 8.1 RNO Step 2

...J Performance Step: 13 RNO: If both DH-V-38A and DH-V-388 are Open, then THROTTLE both trains for balanced total flow s 2800 gpm Standard: Examinee throttles DH-V-4A and DH-V-48 using the OPEN, CLOSE, and STOP push buttons on Panels (CC) and (CR),

respectively, to achieve a balanced total LPI flow of: 2500-2800 gpm with a minimum of 1250 gpm in each loop as indicated on DH-FI-802A and DH-FI-803A.

Comment:

2011 NRC JPM C NUREG 1021, Revision 9 Supp 1

Appendix C Page 10 of 12 Form ES-C-1 PERFORMANCE INFORMATION Terminating Cue: When examinee reports balanced LPI total flow S 2800 gpm JPM may be terminated.

STOP TIME: TIME CRITICAL STOP TIME: N/A 2011 NRC JPM C NUREG 1021, Revision 9 Supp 1

Appendix C Page 11 of 12 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: TMI 2011 NRC JPM C Examinee's Name:

Date Performed:

Facility Eva.luator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2011 NRC JPM C NUREG 1021, Revision 9 Supp 1

Appendix C Page 12 of 12 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

The Reactor is shutdown with a LOCA in progress.

OP-TM-EOP-001 and OP-TM-EOP-006 are in progress.

OP-TM-EOP-01 0, Guide 20 has been completed.

BWST level has dropped below 15 feet and is continuing to lower.

INITIATING CUE: The Control Room Supervisor has directed you to transfer the reactor building sump to recirculation mode lAW OP-TM-EOP 010, Guide 21.

TIME CRITICAL: No 2011 NRC JPM C NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND UNIT 1 Task No.: 41101011 Task

Title:

Restore TBVs and ADVs to ICS JPM No.: 2011 NRC JPM D Auto Control KIA

Reference:

041 A4.06 (2.9/3.1) Bank TQ-TM-1 04-411-J001 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

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

Initial Conditions:

For this event you are assigned the duties of the Assistant RO.

The reactor is tripped due to a loss of Main Condenser vacuum.

OP-TM-EOP-001 Immediate Manual Actions (IMA's) and Vital System Status Verifications (VSSV's) are complete

. Condenser vacuum has been restored.

OTSG's are being fed from the Emergency Feedwater (EFW) system. OTSG levels are relatively steady.

OTSG pressure is being controlled at approximately 875 psig with the Atmospheric Dump Valves (ADVs) using the Backup loaders.

Task Standard: All critical steps evaluated as SAT.

Required Materials: None General

References:

OP-TM-411-451, MANUAL CONTROL OF TBVs/ADVs, Rev. 6 Handout: OP-TM-411-451, MANUAL CONTROL OF TBVs/ADVs, signed off through section 4.4 Initiating Cue: Restore the Turbine Bypass Valves and Atmospheric Dump Valves to ICS AUTO control per OP-TM-411-451.

2011 NRC JPM D NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form Worksheet Time Critical Task: NO Validation Time: 16 minutes 2011 NRC JPM D NUREG 1021, Revision 9 Supp 1

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

100% IC16 (Temporarily snapped into IC-234)

1. Trip the reactor.

2. Trip both FWPs.

3. Set MS:TBVRST to FALSE to simulate a Loss of Main Condenser Vacuum.

4. Select MS-V-4A/4B control to the B/U Loaders and stabilize Header Pressure at 880 890 psig.

5. Set Turbine Header setpoint to 30.

6. Control Primary Inventory while performing setup.

7. Use EFW to raise OTSG levels up to about 70" so they can steam down thereby ensuring EFW does NOT interfere with B/U loader control.

8. When the above steps are completed for this and other JPMs to be run concurrently then validate, if not previously validated, the concurrently run JPMs using the JPM Validation Checklist.

9. This completes the setup for this JPM.

2011 NRC JPM D NUREG 1021, Revision 9 Supp 1

Appendix C Page 4 of 11 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

EVALUATOR CUE: Hand Examinee OP-TM-411-4S1, MANUAL CONTROL OF TBVs/ADVs, signed off through section 4.4 EVALUATOR CUE: If asked, Local-Manual control of TBVs/ADVs was not performed.

Steps 5.1.1 - 5.1.4 Performance Step: 1 If MS-V-3A-F POWER 'RESET' light on CC is Off, then restore controls as follows:

Verify:

Main Condenser vacuum ~ 25" Hg vacuum

Two or more CW pumps operating

ICS Auto and ICS Hand power are available Ensure:

ADV control is on BU Loader Standard: Examinee Verifies:

MS-V-3A-F POWER 'RESET' light on CC is not lit

Main Condenser vacuum ~ 25" Hg vacuum on CL (PI 340)

Two or more CW pumps operating (PLF)

ICS Auto and ICS Hand power are available (PC)

Examinee Ensures:

ADV control is on BU Loader, verified by MS-V-4NB control 'B/U LOADER' light on CC is lit.

Comment:

2011 NRC JPM D NUREG 1021, Revision 9 Supp 1

Appendix C Page 5 of 11 Form ES-C-1 PERFORMANCE INFORMATION Steps 5.1.5 - 5.1.6

.y Performance Step: 2 Ensure:

MS-V-3D, E, For 4A station in HAND at zero percent demand

MS-V-3A, B, C or 4B station in HAND at zero percent demand Standard: Examinee adjusts, if necessary, MS-V-3D, E, For 4A station (CC) in HAND to zero percent demand and MS-V-3A, B, C or 4B station (CC) in HAND to zero percent demand. No adjustment should be necessary at this time.

Comment:

Steps 5.1.7 - 5.1.8 PROCEDURE NOTE: Following step will unlatch TBVs

.y Performance Step: 3 Press MS-V-3 A-F POWER 'RESET' pushbutton on ee.

Verify white backlight lit.

Standard: Examinee presses MS-V-3 A-F POWER 'RESET' pushbutton on ec and verifies white backlight is lit.

Comment:

2011 NRC JPM D NUREG 1021, Revision 9 Supp 1

Appendix C Page 6 of 11 Form ES-C-1 PERFORMANCE INFORMATION PROCEDURE NOTE: Steps 5.2 and 5.3 may be performed in parallel.

EVALUATOR NOTE: Steps 5.2.1 through 5.2.2.2 are N/A Step 5.2.2.3 Performance Step: 4 If Main Turbine load < 150 MWe, then perform the following:

OBTAIN CRS concurrence to place OTSG A TBVs/ADV control to ICS Auto.

Standard: Examinee:

Obtains CRS concurrence to place OTSG A TBVs/ADV control to ICS Auto.

EVALUATOR CUE: If asked, give permission as the CRS to take TBV/ADV control to ICS Auto.

Comment:

Steps 5.2.2.4 - 5.2.2.6 j Performance Step: 5

PLACE MS-V-3D, E, For 4A station indicator to STEAM PRESS ERROR position.

If STEAM PRESS ERROR is not 0%, then ADJUST TURBINE HDR PRESSURE Setpoint knob to obtain zero error (- 50% scale).

PLACE MS-V-3D, E, For 4A station indicator to POSITION DEMAND position.

Standiard: Examinee:

Places MS-V-3D, E, For 4A station indicator to STEAM PRESS ERROR position.

Ensures STEAM PRESS ERROR is 0 % error (- 50%

scale) by adjusting Turbine Hdr Press setpoint knob (CG).

Places MS-V-3D, E, For 4A station indicator to POSITION DEMAND position.

Comment:

2011 NRC JPM D NUREG 1021, Revision 9 Supp 1

~ lIdi VY&#'.--.

Appendix C Page 7 of 11 Form ES-C-1 PERFORMANCE INFORMATION Steps 5.2.2.7 - 5.2.2.8

."f Performance Step: 6

PLACE MS-V-3D, E, For 4A station in AUTO, By depressing RED Auto PB on (CG).

VERIFY AUTO light Lit.

Standard: Examinee places MS-V-3D, E, For 4A station in AUTO and verifies AUTO light Lit.

Comment:

EVALUATOR NOTE: Step 5.2.2.9 is N/A Steps 5.3.1 Performance Step: 7 OBTAIN CRS concurrence to place OTSG B TBVs/ADV control to ICS Auto.

Standard: Examinee obtains CRS concurrence to place OTSG B TBVs/ADV control to ICS Auto.

EVALUATOR CUE: If asked, give permission as the CRS to take TBV/ADV control to ICS Auto.

Comment:

EVALUATOR NOTE: Steps 5.3.2 through 5.3.3.2 are N/A, step 5.3.3.3 is the same as Performance Step #7 above.

2011 NRC JPM D NUREG 1021, Revision 9 Supp 1

Appendix C Page 8 of 11 Form ES-C-1 PERFORMANCE INFORMATION Steps 5.3.3.4 - 5.3.3.6

. Performance Step: 8

PLACE MS-V-3A, B, C or 4B station indicator to STEAM PRESS ERROR position.

If STEAM PRESS ERROR is not 0%, then ADJUST TURBINE HDR PRESSURE Setpoint knob to obtain zero error (- 50% scale).

PLACE MS-V-3A, B, C or 4B station indicator to POSITION DEMAND position.

Standlard: Examinee:

Places MS-V-3A, B, Cor 4B station indicator to STEAM PRESS ERROR position.

Ensures STEAM PRESS ERROR is 0 % error (- 50%

scale), if necessary, by adjusting Turbine Hdr Press setpoint knob (CC). Should not be necessary at this time.

Places MS-V-3A, B, C or 48 station indicator to POSITION DEMAND position.

Comment:

Steps 5.3.3.7 - 5.3.3.8

" Performance Step: 9

PLACE MS-V-3A, B, C or 4B station in AUTO.

VERIFY AUTO light Lit.

Standard: Examinee places MS-V-3A, B, Cor 4B station in AUTO by depressing RED Auto PB on (CC) and verifies AUTO light Lit.

Comment:

2011 I\IRC .JPM 0 NUREG 1021, Revision 9 Supp 1

.. t Appendix C Page 9 of 11 Form ES-C-1 PERFORMANCE INFORMATION PROCEDURE NOTE: Selecting "ICS" transfers MS-V-4A and MS-V-4B from B/U loaders to ICS control.

Steps 5.4.1 - 5.4.2

f Performance Step: 10 If ADV control is via B/U Loaders, then

ENSURE MS-V-4A and MS-V-4B Closed.

PRESS ICS pushbutton (CC).

Standard:

Examinee ensures that MS-V-4A and MS-V-4B are closed by adjusting MS-V-4A Backup CTRL knob (CC) and MS-V-4B Backup CTRL knob (CC), and presses ICS pushbutton (CC), observing white backlight lit and B/U Loader red backlight out.

Comment:

Terminating Cue: When candidate announces Turbine Bypass Valves and Atmospheric Dump Valves are in ICS AUTO Control, JPM may be terminated.

STOP TIME: TIME CRITICAL STOP TIME: N/A 2011 NRC JPM D NUREG 1021, Revision 9 Supp 1

Appendix C Page 10 of 11 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: TMI 2011 NRC JPM D Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2011 NRC JPM D NUREG 1021, Revision 9 Supp 1

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

For this event you are assigned the duties of the Assistant RO.

The reactor is tripped due to a loss of Main Condenser vacuum. OP-TM-EOP-001 Immediate Manual Actions (IMA's) and Vital System Status Verifications (VSSV's) are complete

Condenser vacuum has been restored.

OTSG's are being fed from the Emergency Feedwater (EFW) system. OTSG levels are relatively steady.

OTSG pressure is being controlled at approximately 875 psig with the Atmospheric Dump Valves (ADVs) IJsing the Backup loaders.

INITIATING CUE: Restore the Turbine Bypass Valves and Atmospheric Dump Valves to ICS AUTO control per OP-TM-411-451.

TIME CRITICAL: No 2011 NRC JPM D NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND UNIT 1 Task No.: 22601012 Task

Title:

RCP #1 Seal Failure JPM No.: 2011 NRC JPM E KIA

Reference:

003 A2.01 (3.5 / 3.9) New for 2011 NRC Exam 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. WhEln you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

For this event you assigned the duties of the assistant Reactor Operator (ARO)

The plant is at 68% power, with FW-P-1 B secured Task Standard: All critical steps evaluated as SAT.

Required Materials: OP-TM-226-153 Rev 1 (Available)

OP-TM-AOP-040 Rev 0 (Available)

General

References:

OP-TM-MAP-F0103 (RCP Seal #1 Leak-Off Hi I Lo) Rev 1 OP-TM-AOP-040, RCP #1 Seal Failure Rev 0 OP-TM-MAP-F0106, RC Pump Lab Seal DIP Lo Rev 2 OP-TM-226-153, Shutdown RC-P-1C Rev 1 Handout: None Initiating Cue: Respond to cues or indications I or the simulator gives you.

Time Critical Task: NO Validation Time: 10 minutes 2011 NRC JPM E NUREG 1021, Revision 9 Supp 1

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

100% IC16 (Temporarily snapped into IC-235)

Recluce power per 1102-4 to 68% power secure FW-P-1 B

Create the Following Events o Event 1 IMF MU19C 10 o Event 2 MMF MU19C 14 2011 NRC JPM E NUREG 1021, Revision 9 Supp 1

Appendix C Page 3 of 13 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Booth Operator When directed enter Event 1.

Performance Step: 1 Responds to alarms and indications.

Standard: Enters OP-TM-MAP-F01 03 (RCP Seal #1 Leak-Off Flow Hi / La)

Identifies RC-P-1 C as affected pump.

Comment:

OP-TM-MAP-F01 03, Step 4.0/4.1 Performance Step: 2 Manual Actions required:

If Seal Number 1 Leak-off Flow (SLO) is 2: 5 gpm, then Perform the following:

IAAT Seal Number 1 Leak-off Flow (SLO) is> 6 gpm, then GO TO OP-TM-AOP-040, RC Pump Seal Failures.

Standard: Using PPC point A0950 or recorder MU-43-FR (PC), determines Seal Leak-off is < 6 gpm and continues in OP-TM-MAP-F0103.

Comment:

2011 NRC ,JPM E NUREG 1021, Revision 9 Supp 1

Appendix C Page 4 of 13 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-MAP-F0103 Performance Step~ 3 Trend the following Parameters:

Seal Number 1 Leak-off Flow (SLO) (MU-43-FR)(PC)

RCP Seal and Bearing Water Temperatures

Lab Seall1P, RC-18-DPI-1/2/4 (CC)

Standard: May use RCP Group on Plant Process Computer (PPC) May Trend temperatures on computer and use console for Lab Seal, and use Panel Center Recorder for Flows.

Evaluator Cue: If STA is requested to trend data, "STA is unavailable".

Comment:

OP-TM-MAP-F01 03, Step 4.1

.,J Performance Step: 4 Raise Seal Injection flow, as necessary to attempt to maintain lab seal DP positive on each RC pump. Adjust SI Flow H/A station setpoint or place MU-V-32 in manual. If lab seal DP indication is not available, then MAXIMIZE seal injection flow. Do not exceed 60 gpm.

Standard: Places MU-V-32 (CC) in hand by depressing White pushbutton on Console Center and raises 'flow by pushing toggle switch away to MAXIMIZE Seal Injection flow (RC-P-1C has no seal injection l1P gage). MU-V-32 opened to 100% demand as indicated on controller gage.

Alternately may leave in AUTO and dial 100% on demand by rotating clockwise.

Comment:

NOTE: Alternate Path Starts here. With entry of the next event, the previous "If At Any Time (IAAT)" step applies and the alarm response is exited (a GO TO step is exit criteria per OS-24). AOP OP-TM-AOP-040 is entered. Alternate path decision is that a previously identified condition is now met and mitigation strategy must change from alarm response manual to AOP.

2011 NRC JPM E NUREG 1021, Revision 9 Supp 1

Appendix C Page 5 of 13 Form ES-C-1 PERFORMANCE INFORMATION Booth Operator When Seal Injection is maximized (MU-V-32 at 100%) and with Lead Evaluator concurrence, insert EVENT 2.

OP-TM-MAP-F01 03 IAAT Performance Step: 5 Monitors seal leak-off flow in accordance with IAAT statement and determines it has exceeded 6 gpm.

Standard: Announces need to transition to OP-TM-AOP-040 Evaluator Cue: After candidate announces AOP-040 entry criteria, hand them OP-TM-AOP-040, and direct them to PERFORM.

Comment:

OP-TM-AOP-040 Step 1.0 Performance Step: 6 Reviews entry criteria and determines entry met.

Standard: Continues in procedure.

Comment:

2011 NRC JPM E NUREG 1021, Revision 9 Supp 1

Appendix C Page 6 of 13 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-AOP-040 Step 3.1 Performance Step: 7 IAAT any of the following exists:

- RC Pump #1 seal leakoff flow> 8 gpm

.. Seal water temperature at radial bearing (A0521 through A0524) > 225°F

.. #1 seal inlet temperature (A0525 thru A0528) > 235 OF then perform the following:

A. Verify Reactor power will not challenge RPS limit when RCP is shutdown.

B. Trip affected RCP.

C. Go To step 3.5.

Standard: Determines none of the above apply at this time leaves step open.

Comment:

OP-TM-AOP-040 Step 3.2 Performance Step: 8 MAXIMIZE seal injection flow not to exceed 60 gpm.

Standard: Recognizes condition is met from Alarm response, continues in procedure.

Comment:

OP-TM-AOP-040 Step 3.3 Performance Step: 9 Initiate a power reduction using 1102-4 to within the appropriate limits (Reactor and MWe) based on shutdown of RCP {3 pumps = 75 % RTP 665 MWe}

Standard: Determines Reactor Power and Generated Mega Watts are already below limits.

Comment:

2011 NRC JPM E NUREG 1021, Revision 9 Supp 1

Appendix C Page 7 of 13 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-AOP-040 Step 3.4 Performance Step: 10 When power (Reactor and Turbine) is within limits to support RCP shutdown, then PERFORM the following to shutdown affected RCP:

- OP-TM-226-153 (C RCP)

Standard: Obtains OP-TM-226-153.

Evaluator Cue: When candidate shows they can locate OP-TM-226-1S3 provide an exam copy.

Comment:

OP-TM-226-153 Steps 1.0 through 4.1 Performance Step: 11 Reviews Purpose, Limits and Precautions, first step of Main Body.

Standard: May discuss above, recognizes

Pump is in operating mode

Reactor power is low enough

Turbine power is low enough

A re-ratio of feedwater will occur Evaluator NOTE: If candidate discusses the re-ratio need, inform them 3rd Reactor Operator is to handle feedwater.

Procedure NOTE: NOTE: A 2 / 1 Rep combination with OTSG levels> LLLs will require are-ratio (:::::70% /30%) of Feedwater flow to A / B OTSG.

Comment:

2011 NRC ,JPM E NUREG 1021, Revision 9 Supp 1

Appendix C Page 8 of 13 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-226-153 Step 4.2 Performance Step: 12 If Reactor power is > 20%,

Evaluate expected FW Flow requirements for new RCP combination, to minimize effects on delta Te.

Standard: May evaluate re-ratio flows (approximately 4.8 Mlb/hr "A" loop and 2.1 Mlb/hr "8" loop).

Evaluator Cue: If requested the 3rd Reactor Operator is responsible for feedwater flows.

Comment:

OP-TM-226-153 Step 4.3 Performance Step: 13 If desired and time is available, then NOTIFY Electrical Maintenance to monitor RC-P-1 C vibrations.

Standard: Determines time is not available.

Evaluator Cue: If CRS is requested to determine if vibrations are required respond no.

Comment:

2011 NRC ,JPM E NUREG 1021, Revision 9 Supp 1

ill Hi 1i Appendix C Page 9 of 13 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-226-153 Step 4.4 Performance Step: 14 Place at least one each of the following in Normal-After-Start:

- RC-P-2C-1, Oil Lift Pump AC HP (CC),

or RC-P-2C-2, Oil Lift Pump DC HP (CC)

- RC-P-3C-1, Backstop Oil Pump #1 (CC),

or RC-P-3C-2, Backstop Oil Pump #2 (CC)

Standard: Rotates extension control clockwise observing red light on green light off for at least:

1 backstop

1lift pump Comment:

OP-TM-226-153 Step 4.5

--J Performance Step: 15 Place RC-P-1C in Pull-To-Lock.

Standard: Rotates extension control counter-clockwise and pulls, observes Amps go to zero, red light off, green light on.

May also observe plant feedwater re-ratio (not part of JPM)

Comment:

OP-TM-226-153 Step 4.6 Performance Step: 16 Verify the following:

- RC-P-1C not rotating backwards (PPC L2877, RC-P-1C Reverse Rotation not in alarm).

Standard: Observes lack of alarm on Plant Process Computer.

Comment:

2011 NRC JPM E NUREG 1021, Revision 9 Supp 1

Appendix C Page 10 of 13 Form ES-C-1 INFORMATION OP-TM-226-153 Step 4.7 Performance Step: 17 Place the following in Pull-To-Lock:

- RC-P-3C-2, Backstop Oil Pump #2

- RC-P-3C-1 , Backstop Oil Pump #1 Standard: Rotates extension control counter-clockwise and pulls, observes red light off, green light on (CC).

Comment:

OP-TM-226-153 Step 4.8 Performance Step: 18 Place the following in Pull-To-Lock:

- RC-P-2C-2, Oil Lift Pump DC HP

,. RC-P-2C-1, Oil Lift Pump AC HP Standard: Rotates extension control counter-clockwise and pulls, observes red light off, green light on (CC).

Comment:

OP-TM-226-153 Step 4.9 Performance Step: 19 Record RC-P-1C (226) is in Standby Mode in the CR Log.

Standard: N/A Evaluator Cue: Inform candidate that another crew member is making the log entry.

Comment:

2011 NRC JPM E NUREG 1021, Revision 9 Supp 1

Appendix C Page 11of 13 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-AOP-040 Step 3,5

...J Performance Step: 20 When affected RCP stops rotating, then promptly CLOSE the following for the affected RCP: {MU-V-33C}

Standard: Observes low vibration of Reactor Coolant Pump "G" vibration meters on Panel Left Front (PLF), then presses MU-V-33C close pushbutton on CC. Observes Red light off Green Light on.

Comment:

Terminating Cue: After the candidate closes MU-V-33C the JPM may be terminated.

STOP TIME: TIME CRITICAL STOP TIME: N/A 2011 NRC JPM E NUREG 1021, Revision 9 Supp 1

Appendix C Page 12 of 13 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: TMI 2011 NRC JPM E Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2011 NRC JPM E NUREG 1021, Revision 9 Supp 1

Appendix C Page 13 of 13 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

Initial Conditions:

For this event you assigned the duties of the assistant Reactor Operator (ARO)

The plant is at 68% power, with FW-P-1 B secured Initiating Cue: Respond to cues or indications I or the simulator gives you.

TIME CRITICAL: No 2011 NRC JPM E NUREG 1021, Revision 9 Supp 1

un t "fj- I

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

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Three Mile Island Unit 1 Task No.: 86101011 Task

Title:

Restore 1D Sus from SSO JPM No.: 2011 NRC JPM F Operations KIA

Reference:

SYS 064 A2.09 (3.1 I 3.3) New 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. Wht3n you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

You are the Assist Reactor Operator (ARO).

Loss of 1D 4160 volt bus occurred.

EG-Y-1A failed to start.

"D" 4160 volt bus is being fed from the SSO diesel.

OP-TM-864-901 is in progress.

Task Standard: All critical steps evaluated as SAT.

Required Materials: None General

References:

Have 1107-11 Rev 24 available.

Handout: OP-TM-864-901, SSO DIESEL GENERATOR (EG-Y-4) OPERATIONS

- Revision 9A, Signed off up to section 5.0 Initiating Cue: The CRS has directed you to restore normal power to the 1D 4160 volt bus lAW OP-TM-864-901.

Time Critical Task: No Validation Time: 25 Minutes 2011 TM' NRC JPM F NUREG 1021, Revision 9 Supp 1

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

1. Reset the simulator to Temp IC 236.

NOTE: It is okay to use a similar Ie to the Ie listed above, provided the Ie actually used is verified to be compatible with this and other "IPMs that are scheduled to be run concurrently.

INSERT MALFUNCTION EG01A EG-Y-1A failure.

Place 1SA-D2 and 1SB-D2 in NORM-AFT-TRIP Start FS-P-2 Use OP-TM-864-901 to place SBO on "0" bus lAW section 4.1

2. When the above steps are completed for this and other JPMs to be run concurrently, then validate the concurrently run JPMs using the JPM Validation Checklist.

3. This completes the setup for this JPM.

2011 TMI NRC JPM F NUREG 1021, Revision 9 Supp 1

_ _ _,,,,,,_.._ " _ _ ~ __III 11_8"_,_ _ _ '_lih Appendix C Page 3 of 11 Form ES-C-1 PERFORMANCE INFORMATION (Denote C,'itical Steps with a check mark)

START TIME:

OP-TM-864-901 Step 5.0 Performance Step: 1 NOTE 1 Section 5.1 or 5.2 is used only as a transition to offsite power when a reliable source of offsite power is available.

NOTE 2 If the SBO is loaded on 1C 4160V bus parallel operation with offsite power is not used. The transition to offsite power will require a dead bus transfer.

Standard:

Determines Section 5,1 will apply as offsite power is reliably carrying all other busses.

Determines Note does NOT apply.

Comment:

op-TM-864-901, Step 5.1.1 Performance Step: 2 Verify 1B Auxiliary Transformer has been energized.

Standard:

Determines 1B Auxiliary transformer is energized by noting "C" 4160 volt bus energized from 1B or 1B 7 kV energized from 1B auxiliary transformer.

Evaluator Cue:

If asked: as CRS confirm all problems with 10 bus were repaired.

Comment:

op-TM-864-901, Step 5.1.2

.J Performance Step: 3 ENSURE synch switch for 1SB-D2 is "ON" Standard:

Inserts synch switch handle and rotates to "ON" position, may observe lights below synch meter to verify "ON".

Comment:

2011 TMI NRC JPM F NUREG 1021, Revision 9 Supp 1

Appendix C Page 4 of 11 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-864-901, NOTE after Step 5.1.2 Performance Step: 4 If any adjustments to auxiliary transformer LTC settings are required, these adjustments are performed lAW 1107-11 or OP-TM-AOP-020 depending on whether power is available to LTC.

Standard:

Determines 1107-11 will be used if needed due to power available.

Comment:

OP-TM-864-901, Step 5.1.3 Performance Step: 5 VERIFY Auxiliary Transformer 1S output "system kilovolts" is between 4000 and 4300 V.

Standard: Verifies voltage in the band of 4000-4300 on Console Right (CR)

System kV meter.

Comment:

OP-TM-864-901, Step 5.1.4

~ Performance Step: 6 PLACE the "UNIT/PARALLEL" switch in PARALLEL position Standard:

Calls AO at SSO to have switch placed in parallel.

ICO NOTE: Use Remote Function EGR23 to PARALLEL Comment:

OP-TM-864-901, Step 5.1.5 Performance Step: 7 ADJUST "SPEED DROOP" to 70% in increments of 10% or less.

Standard: e Calls AO at SSO to have "SPEED DROOP" adjusted in increments of 10% or less to 70%.

ICO NOTE: SLOWLY adjust Speed Droop using REMOTE FUNCTION EGR22 to 70%, follow candidate instructions 10% at a time using 3-way communications worked well in validation.

Comment:

2011 TMI NRC JPM F NUREG 1021, Revision 9 Supp 1

Appendix C Page 5 of 11 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-864-901, Step 5.1.6

..J Performance Step: 8 ADJUST SSO "GOVERNOR" to maintain frequency between 59 and 61 Hz.

Standard:

Uses Governor Control Switch (CR) to raise speed, compensating for lowering speed due to adjustment of Droop.

Comment:

OP-TM-864-901, Step 5.1.7 Performance Step: 9 ENSURE "EXCITER" control in manual.

Standard:

Verifies "EXCITER" control on (CR) is in manual.

Comment:

OP-TM-864-901, Step 5.1.8

..J Performance Step: 10 PLACE Auxiliary Transformer 1 S LTC in MANUAL lAW 1107-11.

Standard:

Places control switch 1 S LTC to manual on (PR)

Comment: 1107-11 does not work well here as 1D bus is not connected to transformer LTC adjustments do not affect 1D bus.

Evaluator Cue:

If asked: provide 1107-11.

OP-TM-864-901, Step 5.1.9 Performance Step: 11 ADJUST "Manual Voltage Controller" to maintain "generator kilovolts" between 0 and 50 volts above "system kilovolts",

Standard:

Rotates manual voltage controller clockwise to raise SSO voltage to be 0 to 50 volts higher than 1D incoming voltage.

Using Generator and System Kilovolt indicators on (CR).

Comment: (no adjustment required during validation) 2011 TMI NRC JPM F NUREG 1021, Revision 9 Supp 1

Appendix C Page 6 of 11 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-864-901, Step 5.1.10

~ Performance Step: 12 ADJUST SBO "GOVERNOR" to get synchroscope rotating SLOWLY (less than 1 rotation in 15 seconds) in the CLOCKWISE direction.

Standard:

Adjusts SBO "GOVERNOR" on (CR) to get synchroscope rotating SLOWLY (less than 1 rotation in 15 seconds) in the CLOCKWISE direction. By raising/lowering as necessary.

Comment:

OP-TM-864-901, Step 5.1.11

~ Performance Step: 13 When synchroscope is between "5 to 12" and "12 o'clock", then CLOSE 1SB-02.

Standard:

When synchroscope is between "5 to 12" and "12 o'clock",

closes 1SB-02 on (CR) by rotating clockwise and observing RED light on GREEN Light OFF.

Comment:

OP-TM-864-901, Step 5.2.12 Performance Step: 14 ADJUST "Manual Voltage Controller" to maintain reactive load between zero and +2.25 MVAR Standard:

Adjusts manual controller on (CR) as necessary.

Comment:

OP-TM-864-901, Step 5.2.13 Performance Step: 15 PLACE synch switch at 1SB-02 to "OFF" Standard:

Turns synch switch on (CR) to off.

Comment:

OP-TM-864-901, Step 5.2.14 2011 TMI NRC JPM F NUREG 1021, Revision 9 Supp 1

Appendix C Page 7 of 11 Form ES-C-1 PERFORMANCE INFORMATION

" Performance Step: 16 PLACE the following control switches in Normal-After-Stop (Le.

return to STANDBY) or as directed by CRS.

A. BS-P-1A B. The ES selected MU pump: MU-P-1A or MU-P-1 B-D.

C. DH-P-1A D. RR-P-1A EF-P-2A Standard: Places the following control switches in Normal-After-Stop by pushing down on extension control and rotating clockwise until "green flagged" A. BS-P-1A (CC)

B. MU-P-1A (CC)

C. DH-P-1A (CC)

D. RR-P-1A (CC)

E. EF-P-2A (Cl)

Comment:

OP-TM-864-901, Step 5.1.15 Performance Step: 17 GO TO Section 5.3 Standard:

Goes to section 5.3 of procedure.

Comment:

OP-TM-864-901, Step 5.3.1 Performance Step: 18 ENSURE Fire Service pressure> 80 psig.

Standard:

Verifies fire service pressure on (Pl).

Comment:

oP-TM-864-901 , Step 5.3.2 Performance Step: 19 ADJUST Governor to maintain EG-Y-410ad < 3000kW.

Standard:

No Adjustment should be required.

Comment:

2011 TMI NRC JPM F NU REG 1021, Revision 9 Supp 1

Appendix C Page 8 of 11 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-864-901, Step 5.3.3 Performance Step: 20 ADJUST Voltage control as needed to maintain reactive load between zero and +2.25 MVAR or less than Capability Limit per Figure 1 of 1107-9.

Standard:

No Adjustment should be required.

Comment:

OP-TM-864-901, Step 5.3.4 Performance Step: 21 ENSURE AH-E-197A or AH-E-198 are Operating.

Standard:

Calls AO at SBO to ensure fans operating.

ICO NOTE: Report AH-E-197A is operating normally.

Comment:

OP-TM-864-901, Step 5.4.2 (Step 5.4.1 is N/A)

Performance Step: 22 If EG-Y-4 is supplying an ES 4160V bus, then

1. Verify RELIABLE OFFSITE power is available to the ES 4160V bus.

2. VERIFY 1SB-D2 or 1SA-E2 is closed.

Standard:

Determines reliable power is available as all other busses are on OFFSITE POWER.

Verifies 1SB-D2 is closed.

Comment:

Evaluator Cue:

If asked: Offsite power is reliable OP-TM-864-901, Step 5.4.3 (Step 5.4.1 is N/A)

Performance Step: 23 If G2-12 is CLOSED, then gradually REDUCE GOVERNOR to

-0.3MW.

Standalrd:

Reduces load by rotating Governor Control Switch in the counter clockwise direction (several times if necessary) to reduce load while monitoring MWe for about 0.3.

Comment:

2011 TMII'JRC JPM F NUREG 1021, Revision 9 Supp 1

Appendix C Page 9 of 11 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-864-901, Step 5.4.4

-Y Performance Step: 24 OPEN G2-12 and PLACE switch in Normal-After-Trip position.

Standard:

Rotates G2-12 switch on (CR) counterclockwise to Stop and releases switch.

Comment:

OP-TM-864-901, Step 5.4.5 Performance Step: 25 ENSURE the following breaker extension controls are in Pull-To Lock.

1. T1-D2 is in Pull-To-Lock.

2. T1-E2 is in Pull-To-Lock.

Standalrd: T1-D2 on (CR) is rotated counterclockwise and pulled to place in Pull-To-Lock.

T1-E2 is verified by observation to be in Pull-To-Lock.

Terminating Cue: When T1-D2 is placed in PulI-To-Lock the JPM may be terminated.

STOP TIME:

2011 TMI I'JAC JPM F NUREG 1021, Revision 9 Supp 1

Appendix C Page 10 of 11 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure 1\10.: TMI 2011 NRC JPM F Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2011 TMI NRC JPM F NUREG 1021, Revision 9 Supp 1

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

You are the Assist Reactor Operator (ARO).

Loss of 1D 4160 volt bus occurred.

EG-Y-1A failed to start.

"D" 4160 volt bus is being feed from the SBO diesel.

OP-TM-864-901 is in progress.

You are the Assist Reactor Operator (ARO).

INITIATING CUE: The CRS has directed you to restore normal power to the 1D 4160 volt bus lAW OP-TM-864-901.

2011 TMI NRC JPM F NUREG 1021, Revision 9 Supp 1

Appendix C Page 1 of 8 PERFORMANCE INFORMATION Facility: TMI Unit 1 Task No.: 66101004 Task

Title:

Respond lAW OP-TM-MAP-C0101 JPM No.: 2011 NRC JPM G Alarm Response with Failure KIA Refen~nce: 072 A3.01 (2.9 / 3.1) Modified from 2007 NRC exam Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

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

Initial Conditions:

For this event you are assigned the duties of the Assistant RO.

The instructor/examiner will act as the URO and CRS.

The ICO will act as Auxiliary Operators in the plant as needed.

The Reactor is operating at 100% power with ICS in full automatic.

No Maintenance or surveillances are scheduled for this shift.

Task Standard: All critical steps evaluated as SAT.

Required Materials: None General

References:

OP-TM-MAP-C01 01, Radiation Level HI OP-TM-826-901, CONTROL BUILDING VENTILATION SYSTEM RADIOLOGICAL RESPONSE OPERATIONS Handouts: None Initiating Cue: Respond to the cues and indications given by the simulator as well as any input from the CRS.

Time Critical Task: No Validation Time: 10 Minutes 2011 NRC JPM G NU REG 1021, Revision 9 Supp 1

an Appendix Page 2 of 8 Form ES-C-1 PERFORMANCE INFORMATION SIMULATOR SETUP

1. Reset the simulator to IC 16 (Temporarily snapped into IC-237)

2. Insert the following Malfunctions:

RM01 G, AH-E-17 A fails to trip on interlock, insert immediately 13A6S06ZDICSAHE18B(5} str to OFF, AH-E-18B fails to start, insert immediately Create or Verify the following Batch File (RMA1.bat)

Set RMPASSWORD = 168 Set RM:NEWFILE = True Set RMRAMPIN = 1 Set RMARMA 1Gnew = 3000 Set RMARMA 1 Pnew = 4020

3. When the above steps are completed for this and other JPMs to be run concurrently then validate, if not previously validated, the concurrently run JPMs using the JPM Validation Checklist.

4. This completes the setup for this JPM.

2011 NRC JPM G NUREG 1021, Revision 9 Supp 1

Appendix Page 3 of 8 Form PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TiME:

ICO Cue: When directed by the Evaluator, type into expert command RMA1.bat OP-TM-MAP-C01 01, Step 4.1 Performance Step: 1 ANNOUNCE alarm over plant page and radio.

Standard:

Announces RM-A-1 Hi Alarm over the plant page and radio.

Evaluator Cue: As CRS, acknowledge condition and entry into OP-TM-MAP C0101.

Comment:

OP-TM-MAP-C01 01, Step 4.2 Performance Step: 2 NOTIFY Radiation Protection to verify the alarm and determine the source.

Standard:

Notifies Radiation Protection to verify the alarm and determine the source.

ICO Cue: Acknowledge, as RadPro to verify the alarm and determine the source.

Comment:

OP-TM-MAP-C01 01, Step 4.3.1 Performance Step: 3 IAAT High alarm is Lit, then PERFORM OP-TM-826-901, "

Control Building Ventilation System Radiological Response Operations":

Standard:

Verifies RM-A-1 High alarm is Lit (PRF), and goes to OP TM-826-901.

Comment:

2011 NRC JPM G NUREG 1021, Revision 9 Supp 1

Appendix Page 4 of 8 PERFORMANCE INFORMATION OP-TM-826-901, Step 4.1.2

,.j Performance Step: 4 ENSURE the following fans are shutdown:

- AH-E-17A and AH-E-17B

- AH-E-95A and AH-E-95B

- AH-E-20A and AH-E-20B Standard:

Ensures AH-E-17B, AH-E-95A/B, AH-E-20NB are shutdown.

Recognizes that AH-E-17A is running and secures AH-E 17A, by rotating extension control in the counter-clockwise direction (H&V A).

Comment:

OP-TM-826-901 , Step 4.1.3 Performance Step: 5

SHUTDOWN AH-E-19A and AH-E-19B.

Standard:

Verifies AH-E-19B secure and secures AH-E-19A by rotating extension control in the counter-clockwise direction (H&V A).

Comment:

OP-TM-826-901, Step 4.1.4 Performance Step: 6

ENSURE AH-D-28 or AH-D-617 are CLOSED.

Standard:

Ensures AH-D-28 or AH-D-617 is CLOSED by observation of indication on H&V Center and/or PCR.

Comment:

OP-TM-826-901, Step 4.1.5 Performance Step: 7

PLACE ext. control for AH-E-93/94A and AH-E-93/94B to the OFF position.

Standard:

Places ext. controls for AH-E-93/94A and AH-E-93/94B to the OFF position on H&V Center.

2011 NRC JPM G NUREG 1021, Revision 9 Supp 1

Appendix Page 5 of 8 Form PERFORMANCE INFORMATION Comment:

OP-TM-826-901, Step 4.1.6 Performance Step: 8

START AH-E-188 (A) if AH-E-17A (8) was previously operating.

Standard:

Attempts to start AH-E-188 (H&V 8), by rotating extension control to start and waiting for discharge damper to drive to the open position, recognizes it does not start.

Comment:

Alternate Path begins here. The opposite train from the operating will not start.

Opposite train is used to prevent reverse rotation of fan. Student must recognize and identify the need to allow five minute coast down of AH-E-18A and then proceed with "A" train vice expected "8" train.

OP-TM-826-901, Step 4.1.7

..J Performance Step: 9

If the opposite train of ventilation is unavailable, then WAIT 5 minutes after AH-E-17A (8) was shutdown and START AH-E-18A (8).

Standard:

Waits 5 minutes

Starts AH-E-18A by rotating extension control on H&V A clockwise and holding until the discharge damper travels and the RED light comes on indicating AH-E-18 contactor picked up.

Evaluator Cue: When the candidate states that there is a 5 minute wait, announce "time compression is in effect and 5 minutes has elapsed".

Comment:

OP-TM-826-901, Step 4.1.8 Performance Step: 10

ENSURE AH-E-19A or 8 is operating.

2011 NRC JPM G NUREG 1021, Revision 9 Supp 1

Appendix Page 6 of 8 Form PERFORMANCE INFORMATION Standard:

Ensures AH-E-19A is operating, by observing RED light (H&V A).

Comment:

OP-TM-826-901 , Step 4.1.9 Performance Step: 11 ENSURE AH-E-9SA or B is operating.

Standard:

Ensures AH-E-9SA is operating by observing RED light H&V Center.

Comment:

GUIDE 9, RCS INVENTORY CONTROL Step C.S RNO Performance Step: 12 START AH-E-90 and AH-E-91 .

Stand.:ud:

Orders an NLO to START AH-E-90 and AH-E-91.

ICO Cue: Acknowledge, as an NLO, to start AH-E-90 and AH-E-91.

Comment:

Terminating Cue: When AH-E-18A has been started and the order has gone out to an NLO to start AH-E-90/91: Evaluation on this JPM is complete.

2011 NRC JPM G NUREG 1021, Revision 9 Supp 1

Appendix 7 8 Form VERIFICATION OF COMPLETION Job Performance Measure No.:

Examinee~'s Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2011 NRC JPM G NUREG 1021, Revision 9 Supp 1

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

For this event you are assigned the duties of the Assistant RO.

The instructor/examiner will act as the URO and CRS.

The ICO will act as Auxiliary Operators in the plant as needed.

The Reactor is operating at 100% power with ICS in full automatic.

No Maintenance or surveillances are scheduled for this shift.

INITIATING CUE: Respond to the cues and indications given by the simulator as well as any input from the CRS.

TIME CRITICAL No 2011 NRC JPM G NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND UNIT 1 Task No.: 53101011 Task

Title:

Cross Connect the Secondary River JPM No.: 2011 NRC JPM H Water System to the Nuclear River Water System KIA

Reference:

026 M2.02 (2.9/3.6) Modified Bank TQ-TM-1 04-531 J001 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

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

Initial Conditions:

For this event you are assigned the duties of the Unit RO.

NR-P-1 B is tagged out for maintenance, 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in to a 36-hour outage.

NR-P-1 C tripped 6 minutes ago.

OP-TM-AOP-031, LOSS OF NUCLEAR SERVICES COMPONENT COOLING, was entered due to NS cooler outlet temperature approaching 100°F. Progression through step 3.8 has just been completed.

Task Standard: All critical steps evaluated as SAT.

Required Materials: None General

References:

OP-TM-EOP-001, REACTOR TRIP, Rev. 10 OP-TM-AOP-031, LOSS OF NUCLEAR SERVICES COMPONENT COOLING, Rev. 4 OP-TM-541-901, CROSS-TIE SECONDARY RIVER TO SUPPLY NUCLEAR RIVER, Rev. 0 2011 NRC JPM H NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Handout: OP-TM-AOP-031, LOSS OF NUCLEAR SERVICES COMPONENT COOLING, Rev. 4, signed off through Step 3.8 Initiating Cue: The CRS has directed you to Cross-Tie Secondary River to supply Nuclear River lAW OP-TM-541-901.

Time Critical Task: NO Validation Time: 25 minutes 2011 NRC JPM H NUREG 1021, Revision 9 Supp 1

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

100% ICi6 (Temporarily snapped into IC-238)

1. Ensure NR-P-1 NC are running.

2. Place NR-P-1 B extension controls in PTL on CC and CR. Hang information tags on both switches.

3. Insert remote function RWR10 to OUT, to rack out breaker for NR-P-1 B

4. Open NR-V-4A and NR-V-4B on PL. (note, NR-V-4A is a jog control valve therefore opening requires the switch to be held down until only the open light is on.)

5. InsElrt malfunction RW02C to trip NR-P-1 C.

6. Insert LO Overrides to illuminate NR-V-4NB closed lights:

04A2S04-ZLONRV4BG GRN NR-V-4BG Value - ON

04A2S08- ZLONRV4BR RED NR-V-4BR Value - OFF

04A2S11-ZLONRV4AG GRN NR-V-4AG Value - ON

04A2S15-ZLONRV4AR RED NR-V-4AR Value - OFF

08A1S40-ZLOPCRNRV4A(1) BLU Value - ON

08A1S40-ZLOPCRNRV4A(2) AMBValue - OFF

08A3S17-ZLOPCRNRV4B(1) BLU Value - ON

08A3S17-ZLOPCRNRV4B(2) AMBValue - OFF

7. Perform OP-TM-EOP-001 IMA's and execute OP-TM-AOP-031 up through Step 3.8

8. Raise River Water temperature high enough to result in NS cooler outlet temperature>

100°F

Insert Remote Function RWR14 at 100°F (It takes - 6 minutes in run for NS Cooler Outlet Temperatures to exceed 100°F)

9. Adjust MUT level for current plant conditions (MUMMT to 27500) 2011 NRC JPM H NUREG 1021, Revision 9 Supp 1

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

10. Set Event 1 to close the following breakers:

RWR19 1A ES SHMCC Unit 28 (NR-V-3) Value - CLOSE

RWR20 1A ESV MCC Unit 80 (NR-V-5) Value - CLOSE

RWR21 18 ESV MCC Unit 100 (NR-V-6) Value - CLOSE 11 . Place the simulator in FREEZE

12. When the above steps are completed for this and other JPMs to be run concurrently then validate, if not previously validated, the concurrently run JPMs using the JPM Validation Checklist.

13. This completes the setup for this JPM.

2011 NRC JPM H NUREG 1021, Revision 9 Supp 1

Appendix C Page 5 of 12 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

EVALUATOR CUE: When OP-TM-S41-901 has been located, provide a copy of OP-TM-S41-901.

OP-TM-541-901, PRECAUTIONS, LIMITATIONS, AND PREREQUISITES Performance Step: 1 Precautions - None Limitations - To prevent SR pump motor overload, maintain secondary river header pressure (as read on SR-PI-134) greater than 21 psig.

Prerequisites - VERIFY one of the following conditions:

Reactor is shutdown

TS 3.0.1 action statement has been entered Standard: Examinee verifies the reactor is shutdown.

Comment:

EVAL.UATOR NOTE: Step 4.1 is N/A op- TM-541-901 , Step 4.2 Performance Step: 2 ENSURE NR-V-4A or NR-V-4B is Closed.

Standard: Notes both NR-V-4A and NR-V-4B are Closed as indicated by Green lights on PL or Blue lights on (PCR).

Comment:

2011 NRC JPM H NUREG 1021, Revision 9 Supp 1

Appendix C Page 6 of 12 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-541-901, Step 4.3 Performance Step: 3 ENSURE discharge valves are Closed on all NR or SR pumps which are shutdown.

Standard: Examinee closes the discharge valves on all non-running NR and SR pumps, by depressing close PB NR-V-1C on (CR) and close PB SR-V-1C (CL).

Comment:

OP-TM-541-901, Step 4.4 Perforrnance Step: 4 DISPATCH an Operator to Close the following breakers:

1A ES SCREEN HOUSE MCC UNIT 2B (NR-V-3)

1A ES VALVES MCC UNIT 8D (NR-V-5)

1B ES VALVES MCC UNIT 10D (NR-V-6)

Standcud: Examinee contacts an AO and directs closing of the breakers for NR-V-3, NR-V-5, NR-V-6.

BOOTH OPERATOR When requested to close the breakers for NR-V-3, NR-V-S, CUE: and NR-V-6:

Acknowledge the request.

Insert Event 1. Ensure RWR19, RWR20, RWR21 inserted.

Report that the breakers for NR-V-3, NR-V-S, and NR V-6 are closed Comment:

2011 NRC JPM H NUREG 1021, Revision 9 Supp 1

Appendix C Page 7 of 12 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-541-901, Step 4.5 Performance Step: 5 IAAT NR piping between NR-V-3 and NR-V-5 is ruptured or blocked, then CLOSE the following valves:

NR-V-3

NR-V-5 Standard: Determines no rupture in piping, leaves the step open (IAAT).

Comment:

OP-TM-541-901, Step 4.6

" Performance Step: 6 ENSURE the third Secondary River pump is operating.

Standard: Starts the third SR pump SR-P-1 C by rotating extension control clockwise (CL) observes RED light on GREEN light off.

Comment:

OP-TM-541-901, Step 4.7

" Performance Step: 7 ENSURE SR pump discharge valves are OPEN.

Standard: Opens the discharge valve for SR-P-1C, SR-V-1C by depressing Open PB. Notes GREEN light out, RED light lit.

Comment:

2011 NRC JPM H NUREG 1021, Revision 9 Supp 1

Appendix C Page 8 of 12 Form ES-C-1 PERFORMANCE INFORMATION EVALUATOR NOTE: Alternate Path begins, with report of rupture. Normal cross connect path must be abandoned and the alternate bypass path used.

BOOTH OPERATOR As the Outbuildings AO, contact the Control Room and CUE: inform the Examinee:

"/ am on my Screen House rounds and I've noticed there is a pipe rupture in the line just downstream of NR-V-3. I am exiting the Screen House."

OP-TM-S41-901, Step 4.S IAAT NR piping between NR-V-3 and NR-V-S is ruptured or

" Performance Step: 8 blocked, then CLOSE the following valves:

NR-V-3

NR-V-S Standard: Presses the CLOSE pushbuttons for NR-V-3 and NR-V-S (CG).

Notes green light lit, red light out.

Comment:

OP-TM-S41-901, Step 4.8

" Performance Step: 9 OPEN NR-V-2.

Standard: Presses the OPEN pushbutton for NR-V-2 (CG). Notes green light out, red light lit.

Comment:

2011 NRC JPM H NUREG 1021, Revision 9 Supp 1

Appendix C Page 9 of 12 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-541-901, Step 4.9

" Perfolrmance Step: 10 OPEN NR-V-7.

Standard: Presses the OPEN pushbutton for NR-V-7 (CG). Notes green light out, red light lit.

Comment:

OP-TM-541-901, Step 4.10 Performance Step: 11 WAAT 1B ES VALVES MCC UNIT 10D is CLOSED, then OPEN NR-V-B.

Standard: Presses the OPEN pushbutton for NR-V-B. Notes green light out, red light lit.

Comment:

OP-TM-541-901, Step 4.11 Performance Step: 12 THROTTLE SR-V-2 to maintain Secondary River discharge pressure (SR-PI-134) above 21 psig.

Standard: If necessary, Examinee throttles SR-V-2 to maintain Secondary River discharge pressure (SR-PI-134) above 21 psig.

Comment:

OP-TM-541-901, Step 4.12 Performance Step: 13 THROTTLE OPEN NR-V-1BA, B, C, D to maintains NS cooler outlet temperature less than 95 oF.

Standard: Informs AO to throttle open NR-V-1BA, B, C, D to maintains NS cooler outlet temperature less than 95 OF.

BOOTH OPERATOR When requested, acknowledge to throttle open NR-V-1SA, B, CUE: C, 0 to maintains NS cooler outlet temperature less than 95°F 2011 NRC JPM H NUREG 1021, Revision 9 Supp 1

Appendix C Page 10 of 12 Form ES-C-1 PERFORMANCE INFORMATION Comment:

OP-TM-541-901, Step 4.13

.J Performance Step: 14 THROTTLE OPEN NR-V-15A, B to maintain IC cooler outlet temperature less than 100 OF.

Standard: Examinee throttles NR-V-15A, Bon (CR) by pressing open PB for short periods of time, to maintain IC cooler outlet temperature less than 100 OF.

Comment:

Terminating Cue: When candidate has throttled NR-V-15A/B as necessary and has control of outlet temperatures (a lowering trend), JPM may be terminated.

STOP TIME: TIME CRITICAL STOP TIME: N/A 2011 NRC JPM H NUREG 1021, Revision 9 Supp 1

Appendix C Page 11 of 12 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: TMI 2011 NRC JPM H Examinee's Name:

Date Perfmmed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2011 NRC JPM H NUREG 1021, Revision 9 Supp 1

Appendix C Page 12 of 12 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

For this event you are assigned the duties of the Unit RO.

NR-P-1 B is tagged out for maintenance, 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in to a 36 hour4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months outage.

NR-P-1 C tripped 6 minutes ago.

OP-TM-AOP-031 , LOSS OF NUCLEAR SERVICES COMPONENT COOLING, was entered due to NS cooler outlet temperature approaching 100°F. Progression through step 3.8 has just been completed.

INITIATING CUE: The CRS has directed you to Cross-Tie Secondary River to supply Nuclear River lAW OP-TM-S41-901.

TIME CRITICAL: No 2011 NRC ..'PM H NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Three Mile Island Unit 1 Task No.: EOPG15001 Task

Title:

Manually Operate MU-V-20 and JPM No.: 2011 NRC JPM I IC-V-4 KIA

Reference:

015/017 AA1.07 (3.5/3.4) Bank TO-TM-1 05-852-J002 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: x Actual Performance:

Classroom Simulator ___ Plant .--=-.X::..-_

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

Initial Conditions:

A Loss of Instrument Air has occurred

OP-TM-AOP-028 has been entered

The reactor has been tripped and OP-TM-EOP-001 actions have been completed

An Auxiliary Operator has been directed to block open IC-V-3.

Task Standard: A" critical steps evaluated as SAT.

Required Materials: None General

References:

OP-TM-AOP-028, Loss of Instrument Air OP-TM-541-429, Manual Operation of IC-V-4 Locally Posted Instructions Handout: None Initiating Cue: The In-Plant supervisor has directed you to place MU-V-20 and IC-V-4 in the BLOCKED OPEN position to prevent the loss of Reactor Coolant Pump Seal Injection and Intermediate Closed Cooling Water.

Time Critical Task: No 2011 NRC JPM I NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Validation Time: 28 minutes 2011 NRC JPM I NUREG 1021, Revision 9 Supp 1

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

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

SIMULATOR SETUP N/A 2011 NRC "IPM I NUREG 1021, Revision 9 Supp 1

Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION

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

(Denote Critical Steps with a check mark)

START TIME:

Evaluator Note: When examinee identifies that a "locked valve" key is needed, simulate handing the examinee a "locked valve" key Performance Step: 1 Obtain a locked key valve Standard:

Examinee obtains a locked key valve Comment:

Evaluator Note: Either MU-V-20 2! IC-V-4 may be operated first.

Performance Step: 2 Go to MU-V-20 and establish communications with the Control Room Standard:

Locates MU-V-20 and simulates establishing communications with the Control Room.

Evaluator Cue: Role-playas the Control Room Operator for communications.

Comment:

"1/ Performance Step: 3 Unlock MU-V-20 handwheel Standard:

Examinee simulates unlocking and removing the chain from the MU-V-20 handwheel.

Evaluator Cue: After the simulation is performed correctly, inform the examinee that MU-V-20 is unlocked and the chain removed.

Comment:

2011 NRC JPM I NUREG 1021, Revision 9 Supp 1

Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION

,j Performance Step: 4 Rotate the MU-V-20 handwheel in the OPEN direction (counter clockwise) until upper local indicator is at the OPEN position (full down).

Standard:

Examinee simulates rotating the MU-V-20 handwheel in the OPEN direction (counter-clockwise) until upper local indicator is at the OPEN position (full down).

Evaluator Cue: After the simulation is performed correctly, inform the examinee that the upper local indicator is at the "FULL DOWN" position.

Comment:

Evaluator Note: Either MU-V-20 .Q! IC-V-4 may be operated first.

Performance Step: 5 Go to IC-V-4 and establish communications with the Control Room Stanciard:

Locates IC-V-4 and simulates establishing communications with the Control Room.

Evaluator Cue: Role-playas the Control Room Operator for communications.

Comment:

Performance Step: 6 Verify IC-V-4 is open.

Standard:

Examinee verifies IC-V-4 is open.

Comment:

2011 NRC JPM I NUREG 1021, Revision 9 Supp 1

Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION

,j Performance Step: 7 Loosen bolt in the 10% stop plate Standmd:

Examinee simulates loosening the bolt in the 10% stop plate, bolt is behind valve against wall to left as viewed from room.

Evaluator Cue: After the simulation is performed correctly, inform the examinee that the bolt is loosened.

Comment:

,j Performance Step: 8 Slide Stop Plate up IC-V-4 shaft Standard:

Examinee simulates sliding Stop Plate up IC-V-4 shaft Evaluator Cue: After the simulation is performed correctly, inform the student that the stop plate has been moved up the shaft.

Comment:

,j Performance Step: 9 Align bolt hole in 10% stop plate with bolt hole in valve shaft Standard:

Examinee aligns in 10% stop plate bolt with bolt hole in valve shaft Evaluator Cue: After the simulation is performed correctly, inform the student that the 10% stop plate bolt is aligned with bolt hole in valve shaft Comment:

,j Performance Step: 10 Tighten bolt. IC-V-4 travel will now be limited to 10%

Standard:

Candidate simulates tightening bolt.

Evalualtor Cue: After the simulation is performed correctly, inform the student that the bolt is tightened.

Comment:

2011 NRC JPM I NUREG 1021, Revision 9 Supp 1

Appendix C Page 7 of 9 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 11 Report to the Control Room that MU-V-20 AND IC-V-4 are in the Blocked Open position.

Standard:

Examinee reports to the Control Room that MU-V-20 AND IC-V-4 are in the Blocked Open position.

Comment:

Terminating Cue: JPM may be terminated when the examinee informs the Control Room that MU-V-20 AND IC-V-4 are in the Blocked Open position STOP TIME:

2011 NRC JPM I NUREG 1021, Revision 9 Supp 1

Appendix C Page 8 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2011 NRC JPM I Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2011 NRC JPM I NUREG 1021, Revision 9 Supp 1

Appendix C Page 9 of 9 Form ES-C-1 JPM CUE SHEET Initial Conditions:

A Loss of Instrument Air has occurred

OP-TM-AOP-028 has been entered

The reactor has been tripped and OP-TM-EOP-001 actions have been completed

An Auxiliary Operator has been directed to block open IC-V-3.

Initiating Cue: The In-Plant supervisor has directed you to place MU-V-20 and IC-V-4 in the BLOCKED OPEN position to prevent the loss of Reactor Coolant Pump Seal Injection and Intermediate Closed Cooling Water.

2011 NRC JPM I NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Three Mile Island Unit 1 Task No.: 86104001 Task

Title:

Local Start of EG-Y-1 B and Loading JPM No.: 2011 NRC JPM J of 1E 4160V bus KIA Referemce: 068 AA1.10 (3.7/3.9) New for 2011 NRC JPM Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: x Actual Performance:

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

Initial Conditions:

You are the Assistant RO.

Due to a fire an immediate evacuation of the control room was required.

All OP-TM-EOP-001 Reactor Trip IMA's were complete.

OP-TM-EOP-020 Cooldown From Outside the Control Room is in progress all steps through and including 3.2 are complete.

Attachment 12 actions, "Control Tower 3rd Floor Actions to Establish Control at Remote Shutdown Panels" has been completed.

Report has been received that EF-P-1 has tripped and can not be reset.

Power to the 1E bus has just been lost.

Task Standard: All critical steps evaluated as SAT.

Required Materials: None General

References:

OP-TM-EOP-020, COOLDOWN FROM OUTSIDE THE CONTROL ROOM Rev 12.

Handout: OP-TM-EOP-020, COOLDOWN FROM OUTSIDE THE CONTROL ROOM Attachment 9.

2011 NRC JPM J NUREG 1021, Revision 9 Supp 1

11, hi! j b P Appendix C Job Performance Measure Form ES-C-1 Worksheet Initiating Cue: The Shift Manager directs you to perform Attachment 9, Starting EG-Y 1B and Loading 1E 4160V bus, determination has been made that SCBAs are NOT required.

Time Critical Task: No Validation Time: 15 minutes 2011 NRC JPM J I'JU REG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP N/A 2011 NRC JPM J NUREG 1021, Revision 9 Supp 1

Appendix C Page 4 of 9 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Evaluator Note: Provide Candidate with a copy of OP-TM-EOP-020 attachment 9.

EOP-020 Att. 9 step 1.1 Evaluator Cue: If candidate indicates they are smelling for the indication of Wintergreen odor, tell them "No wintergreen odor is detected" Performance Step: 1 Trip the following breakers on the 1 E 4160V bus:

1SA-E2(Unit1E14)

RR-P-1 B (Unit 1 E11)

BS-P-1 B (Unit 1 E1 0)

DH-P-1 B (Unit 1E7)

T1-E2 (Unit 1E2)

1SB-E2(Unit1E1)

Standard: At the 336 elevation control tower, on the green 1E 4160V bus the candidate may trip each by depressing PB or if checked will find green lights on for each;

1SA-E2 (Unit 1 E14)

RR-P-1B (Unit 1E11)

BS-P-1 B (Unit 1 E1 0)

DH-P-1 B (Unit 1 E7)

T1-E2 (Unit 1E2)

1SB-E2 (Unit 1 E1)

Evaluator NOTE: Attachment 12 would have been performed by the ARO/STA previously therefore; All breakers above have had their locks unlocked and are positioned to emergency.

If candidate tries to unlock "69" switch tell them it is unlocked and indicate the handle is pOinted to emergency (Except BS-P-1 B is in bypass, as it has no emergency)

Evaluator Cue: For each breaker indicate the green light is on the red light is off.

2011 NRC JPM J NUREG 1021, Revision 9 Supp 1

Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION Comment:

EOP-020 Att. 9 Step 1.2.1 & 1.2.2

,j Performance Step: 2 Push START for EG-Y-*IB.

Verify READY light is lit.

Standard: * <") At the output breaker on 1E bus Examinee presses START PB.

Verifies ready to load light on front of breaker.

Evaluator Cue: After the PB is depressed and a 10 second time delay indicate Ready to load light (Green) is lit.

Comment:

EOP-020 Att. 9 Step 1.2.3 & 1.2.4

,j Performance Step: 3 <..,j) UNLOCK and PLACE FEEDER TRANSFER 69 switch in EMERGENCY Notify operator at RSD panel that EG-Y-1 B will be loaded.

Standard:

Examinee simulates unlocking and placing in emergency FEEDER TRANSFER 69, by inserting key in 69 switch on the front of the diesel output breaker and rotating clockwise until it won't turn any further (it is now captured), then rotating handle clockwise to emergency position.

Evaluator Cue: When described properly indicate the pointer is pointing toward EMERGENCY.

If the handle is attempted to be turned without the key being inserted / rotated indicate handle would not turn.

Acknowledge as Remote Shutdown panel operator that the Diesel will be started.

Comment:

2011 NRC JPM J NUREG 1021, Revision 9 Supp 1

Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION EOP-020 Att. 9 Step 1.2.5 I

'\I Performance Step: 4 PUSH "CLOSE" for G11-02.

Standard:

Examinee simulates pressing close PB for G11-02 on the front of the output breaker.

Evalucltor Cue: If the steps above for the 69 switch were correct indicate a closing noise was heard, and Red light is ON Green light is OFF.

NOTE: If the 69 switch is not in emergency the breaker will not close. (Green light remains lit.)

Comment:

EOP-020 Att. 9 Step 1.3 1/ Performance Step: 5 Perform the following to re-energize 'B' ES power train.

1. NOTIFY operator at RSD panel that the "B" ES power train will be reenergized.

2. (1/) PUSH CLOSE for S1-02 (Unit 1E6).

3. ("') PUSH CLOSE for T1-02 (Unit 1 E12)

Standard:

Candidate contacts RSD panel operator by radio or red page.

Candidate presses CLOSE PB on front of S1-02 breaker.

Candidate presses CLOSE PB on front of T1-02 breaker.

Evaluator Cue: Acknowledge report "8 Train power is being restored" Indicate Red light on green light off on front of S1-02.

Indicate Red light on green light off on front of T1-02.

Comment:

2011 NRC JPM J NUREG 1021, Revision 9 Supp 1

Appendix C Page 7 of 9 Form ES-C-1 PERFORMANCE INFORMATION EOP-020 Att. 9 Step 1.3.1

,J Performance Step: 6 IF EF-P-1 is not operating then perform the following to start EF P-2B:

1 , NOTIFY operator at RSD panel that EF-P-2B will be started.

2. ('>/) PUSH CLOSE for EF-P-2B (UNIT 1E5)

Standard:

Candidate Notifies RSD operator via radio or RED phone.

Candidate pushes close PB on front of EF-P-2B breaker.

Evaluator Cue: Acknowledge report.

If candidate tries to insert key in 69 lock, lock has key and is in emergency.

When candidate indicates close PB is pushed, red light is lit and green light is out.

Comment:

Terminating Cue: JPM may be terminated when the the breaker for EF-V-2B is closed.

STOP TIME:

2011 NRC JPM J NUREG 1021, Revision 9 Supp 1

Appendix C Page 8 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2011 NRC JPM J Examinee's Name:

Date Performed:

Facility Evaluator:

Number 01 Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2011 NRC ..IPM J NUREG 1021, Revision 9 Supp 1

Appendix C Page 9 of 9 Form ES-C-1 JPM CUE SHEET Initial Conditions:

You are the Assistant RO.

Due to a fire an immediate evacuation of the control room was required.

All OP-TM-EOP-001 Reactor Trip IMA's were complete.

OP-TM-EOP-020 Cooldown From Outside the Control Room is in progress all steps through and including 3.2 are complete.

Attachment 12 actions, "Control Tower 3rd Floor Actions to Establish Control at Remote Shutdown Panels" has been completed.

Report has been received that EF-P-1 has tripped and can not be reset.

Power to the 1E bus has just been lost.

Initiating Cue: The Shift Manager directs you to perform Attachment 9, Starting EG-Y 1B and Loading 1E 4160V bus, determination has been made that SCBAs are NOT required.

2011 NRC JPM J NUREG 1021, Revision 9 Supp 1

Appendix Job Performance Measure Form ES-C-1 Worksheet Facility: Three Mile Island Unit 1 Task No.: EOPG15001 Task

Title:

Respond to a failure of EF-P-2A to JPM No.: 2011 NRC JPM K start. and EF-V-30D to close.

KIA

Reference:

061 A2.04 (3.4 / 3.8) Modified for 2011 NRC Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: X Actual Performance:

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

Initial Conditions:

Post trip with EFW Actuation and you are the operator responding to EFW Actuation.

EF-P-2B OOS prior to the event.

EF-P-2A is running and has failed to develop discharge pressure.

Task Standard: All critical steps evaluated as SAT.

Required Materials: None General

References:

OP-TM-424-901 Emergency Feedwater Handout: OP-TM-424-901 Emergency Feedwater Initiating Cue: The CRS has given you OP-TM-424-901, and requests you to investigate for possible steam binding lAW section 4.2.3.

Time Critical Task: No Validation Time: 13 minutes 2011 NRC JPM K NUREG 1021, Revision 9 Supp 1

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

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

SIMULATOR SETUP N/A 2011 NRC JPM K NUREG 1021, Revision 9 Supp 1

Appendix C Page 3 of 8 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Evaluator Note: If requested provide the following EF-P-2A status when on scene Discharge pressure is still approximately 400 psig, the pump is running, 10 4Kv bus is 4160 volts.

OP-TM-424-901 4.2.3 Discharge temperature Perfor'mance Step: 1 Determine discharge piping temperature of EF-P-2A Standard:

Locates and reads strap on gage on discharge of EF-P-2A.

Evaluator Cue:

When gage is located point to 230°F (middle of the orange zone) and indicate that is what it is reading.

Comment:

OP-TM-424-901 4.2.3.3 & (A) & (8)

Performance Step: 2 Reports temperature to Control Room and requests they perform steps "A" and "8" defeating start signals and placing pump in pull to lock.

Standard:

Communicates with Control Room status of temperature and request that they complete the next two steps.

Evaluator Cue: Acknowledge temperature reported and after three-way communication inform candidate HSPS is defeated and EF P-2A is in PTL.

Comment:

2011 NRC JPM K NUREG 1021, Revision 9 Supp 1

Appendix C Page 4 of 8 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-424-901 4.2.3.3 (C)

,j Performance Step: 3 Open EF-V-1 024 to drain condensate through the pump.

Standard:

Proceeds to EF-V-1024 west wall by base of pump, simulates opening EF-V-1024 by rotating counter clockwise.

Evaluator Cue:

After a period of steam vapor venting from pipe end a steady stream of water is now seen.

Comment:

OP-TM-424-901 4.2.3.3 (D)

,j Perfol'mance Step: 4 Verifies temperature is below 200°F on strap on gage on discharge of EF-P-2A, then closes EF-V-1024.

Standard:

Verifies temperature on gage

Simulates closing EF-V-1024 by rotating handwheel clockwise.

Evaluator Cue:

When gage is looked at indicate 100°F on gage face.

When valve is correctly simulated closed indicate flow from pipe stopped Comment:

OP-TM-424-901 4.2.3.3 (E)

Performance Step: 5 Reports status of venting to Control Room and requests that Control Start EF-P-2A.

Standard:

Contacts Control Room and report pump vented and requests Control Room Complete 4.2.3.3 (E)

Evalucltor Cue:

Acknowledge Cue and report pump is now operating with excessive flow to "A" OTSG EF-V-30A and EF-V-30 D have been closed but flow continues, Report positions of EF-V-30A and EF-V-30D.

Comment:

2011 NRC JPM K NUREG 1021, Revision 9 Supp 1

Appendix C Page 5 of 8 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-424-901 Performance Step: 6 Candidate verifies Valve position of EF-V-30A and EF-V-30D.

Standard:

Valve position of EF-V-30A and EF-V-30D verified by valve position indicator on side of valve.

Evaluator Cue:

When EF-V-30A is verified pOint to the full closed position, when EF-V-30D is verified point to the full open position.

Comment:

OP-TM-424-901 Performance Step: 7 Candidate reports positions of EF-V-30A and EF-V-30D to Control Room.

Standard:

Valve position of EF-V-30A reported as CLOSED and EF-V 300 reported as OPEN.

Evaluator Cue:

Acknowledge report Request candidate stop flow through the "D" EFW line lAW section 4.3.

Comment:

OP-TM-424-901 4.3.2 (1)

j Performance Step: 8 Close EF-V-52D to isolate EF-V-30D Standand:

Candidate simulates closing EF-V-30D by turning hand wheel clockwise Evaluator Cue:

If candidate simulates closing EF-V-30D correctly and reports It closed to Control Room then report; Control room has control of EFW.

If candidate closes incorrect valve or does not properly simulate closing EF-V-S2D and reports it closed to Control Room then report; High Flow continues to "An OTSG.

Comment:

2011 NRC JPM K NUREG 1021, Revision 9 Supp 1

Appendix C Page 6 of 8 Form ES-C-1 PERFORMANCE INFORMATION Terminating Cue: ..IPM may be terminated when EF-V-52D is closed.

STOP TIME:

2011 NRC JPM K NUREG 1021, Revision 9 Supp 1

Appendix C Page 7 of 8 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2011 NRC JPM K Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to C()mplete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2011 NRC JPM K NUREG 1021, Revision 9 Supp 1

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

Post trip with EFW Actuation and you are the operator responding to EFW Actuation.

EF-P-2B OOS prior to the event.

EF-P-2A is running and has failed to develop discharge pressure.

Initiating Cue: The CRS has given you OP-TM-424-901, and requests you to investigate for possible steam binding lAW section 4.2.3.

2011 NRC JPM K NUREG 1021, Revision 9 Supp 1

'f ~ ~ Exelon~

y Nuclear THREE MILE ISLAND INITIAL LICENSE TRAINING CLASS 10-01 NRC EXAMINATION MATERIAL CONTROL lAW NUREG 1021 and TQ-AA-201 OPERATIONAL SCENARIOS

o Scenario Outline Form ES-D-1 Facility: Three Mile Island Scenario No.: 2 Op Test No.: 28a-2011-~01 Examiners: Operators:

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

Initial Conditions: * (Temporary IC-52)

100% Power, MOL

._---------- --.--~--. ~ .

r---.--.--.----~---------

EF-P-1 OOS for bearing replacement, 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months into a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months clock T.S. 3.4.1.1 (2)

Turnover: Maintain 100% Power Operations r--'--

Critical Tasks:

1--

Establish FW Flow and Feed SG(s} (CT-10)

~

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

r---~----'-~--~'~--'~--'-~'

Electrical Power Alignment (CT-8)

Event No. Malt No. Event Type* Event Description 1 MU01B CCRS MU-P-1 B Trips (TS), entry into OP-TM-AOP-041 CURO (URO: ensures MU-V-32 is in HAND and closed, ARO: Starts MU P-1A)

CARO TSCRS 2 ED18B CCRS Loss of the 8 Bus (TS) with EG-Y-1 B failing to start, entry into OP TM-AOP-014 CARO (ARO: Starts the SBO)

TSCRS 3 NI27A I CRS . Narrow Range Pressure Instrument Fails high with SASS failure to actuate, entry into OP-TM-MAP-G0308 IC48 IURO (URO: Closes Spray Valve, selects Alternate Pressure Instrument, IARO ARO: Manual control of Pressurizer Heaters) 4 FW15B NCRS Loss of FW-P-1 B, entry into OP-TM-MAP-M01 07, Runback Fails RURO to Occur, Power Reduction Performed, entry into OP-TM-MAP H0101 and 1102-4 i NARO 5 RD0230 'TS CRS Stuck Rod (TS), entry into OP-TM-AOP-062 6 ED18A MCRS Loss of Offsite Power (tripping SBO output breaker), entry into OP MURO TM-AOP-020,OP-TM-EOP-001 MARO 7 EG01A CCRS "A" EDG fails to start, manual start required. (URO)

. CURO 8 ICR02 CCRS EFW Valves for "An OTSG fail to 0% in Auto, manual control ICR04 required. (ARO)

CARO

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

- 1

Scenario Event Description NRC Scenario 2 Three Mile Island NRC Scenario #2 When the crew has accepted the watch, the Lead Examiner can cue the trip of MU-P-1 B, which will cause Seal Injection Flow Low, to alarm. The crew will enter OP-TM-AOP-041 and will take action to restore letdown using MU-P-1A. When letdown is restored, the scenario can continue.

When letdown flow is restored, the Lead Examiner can cue the initiation of Loss of 8 Bus with EG-Y -1 B failing to start. The operators will diagnose the Loss of 8 Bus and EG-Y -1 B failure on alarms, heM of the CR lighting going out, and lost equipment. The CRS will enter OP-TM-AOP 014, LOSS OF 1E 4160v Bus, and direct the operators to take actions. The ARO will place the 1E 4Kv bus on the SBO lAW OP-TM-864-901. The CRS will review T.S. and declare 3.7.2.b,c,d. Once the T.S. call is made and 1E 4Kv bus is energized, the scenario can continue.

When the Tech Spec call is made and 1E 4Kv bus is energized from the SBO, the Lead Examiner can cue the Narrow Range Pressure Instrument Failure. As the instrument failure is at a severity to open the Spray Valve, but not the PORV, the URO will close the spray valve lAW OP-TM-PPC-G0308 to mitigate Pressure drop and will select the alternate instrument. The ARO will take manual control of pressurizer heaters. When the alternate instrument is selected, the scenario can continue.

When the alternate instrument is selected, the Lead Examiner can cue the Loss of FW-P-1 B.

The runback does not occur and a power reduction must be performed by the crew. When the Lead Examiner has seen sufficient reactivity manipulation, the scenario can continue.

When the Lead Examiner has seen sufficient reactivity manipulation, the Lead Examiner can cue the stuck rod. Crew will enter OP-TM-MAP-G0201, CRD PATTERN ASYMMETRIC, for >7" difference and OP-TM-AOP-062, INOPERABLE ROD, for >9" and/or control rod cannot be exercised. CRS will declare T.S. 3.5.2.2.b.

Once the T.S. call has been made, the Lead Examiner can cue the Loss of Offsite power, which will result in a reactor trip and the crew will have to respond lAW OP-TM-EOP-001, Reactor Trip and OP-TM-AOP-020, Loss of Offsite Power. The way Offsite Power is lost will trip the SBO Diesel Generator lAW electrical schematics.

(CT-8) UA" EDG will fail to automatically start and the URO will manually start it lAW OS-24 and OP-TM-861-901, thereby energizing the 1D 4kV bus. The crew may also choose to repower the 1E 4kV bus with the SBO Diesel Generator lAW OS-24 and OP-TM-864-901. Failure criteria would be considered if a class 1E bus is not energized within 10 minutes (FSAR 8.4).

(CT-10) EFW valves for the "A" OTSG fail in auto to 0%. The ARO will take manual control and feed the "A" OTSG to 75-85% in the operating range. This avoids drying out of the "An OTSG and ensures primary to secondary heat transfer is maintained in the "An OTSG. The targeted level is set to enhance the establishment of natural circulation of the RCS. Failure criteria would be considered if the "An OTSG goes dry. Choosing a level other than 75-85% is not failure criteria as it will still establish Natural Circulation, although at a slower rate.

The ARO will feed and steam the OTSGs to establish Natural Circulation lAW OP-TM-EOP-010, Guide 10.

The URO will Emergency borate lAW Rule 5 to compensate for the stuck rod.

Scenario Event Description

!\IRC Scenario 2 The scenario can be terminated when Natural Circulation is verified, power is restored to a 4kv bus, and emergency boration is established.

B&W Unit EOP Critical Task Description Document, 47-1229003-04:

CT Electrical Power Alignment - If station auxiliary power is not available, then perform the following:

Initiate proper operation of emergency AC supply.

In the event that no emergency AC supply (or alternate AC source) is available, then perform [SBO procedure] and continue attempts to restore AC power.

Safety Significance: Plant electrical power is necessary for the operation of normal and emergency plant equipment. Therefore, it is important that the plant operator provide normal AC power, usually supplied through the station auxiliary transformer(s). If normal AC power cannot be supplied, then actions are necessary to initiate operation of the emergency AC source(s) including alternate AC supplies, if applicable. If both normal and emergency AC power are lost, then a station blackout has occurred. For such eVl9nts, station blackout procedures provide plant specific actions which are to be taken while efforts are being made to restore AC power. Providing normal AC power greatly enhances the transient mitigation capability of the plant, e.g., normal RCS make up systems remain operational.

Cues:

1. Auxiliary and emergency bus voltage low alarms

2. Verbal indication by plant staff that auxiliary and emergency AC bus voltage is low

3. Overhead lights turn off Performance Indicators:

1. Operation of auxiliary/emergency AC power source controls (EG-Y-1NSBO)

Feedback:

1. Auxiliary/emergency bus voltage normal

2. Verbal indication by plant staff of auxiliary/emergency AC power equipment status

-3

Scenario Event Description 1\1 RC Scenario 2 B&W Unit EOP Critical Task Description Document, 47-1229003-04:

CT Establish EFW Flow and Feed SG(s) (Rule 4) - Failure to accomplish either this or HPI/PORV cooling and allowing the plant to heatup into a Loss of Subcooling would jeopardize fuel clad and should be considered failure to met the critical task. Primary to secondary cooling is preferred over HPI/PORV cooling due to:

More stable

Does not challenge RCS integrity

Does not fill the Reactor Building with RCS water Safety Significance: The normal method of core cooling is by transferring core heat to the RC, then transferring the heat from the RC to the secondary side steam system via the SGs. This mode of heat transfer requires that adequate inventory of feedwater be supplied to the SGs, either as a liquid level, liquid flowrate or both. In the event all feedwater is lost HPI cooling can provide backup cooling of the core; however, this mode causes degradation of the RB. It is the intention of the GEOG bases to maintain appropriate FW flow, including trickle feed, to the SGs if at all possible. This includes use of approved plant specific alternate FW sources (e.g., service water, fire water systems, etc.).

Cues:

1. Low FW flow alarms

2. SG low level alarms

3. Low SG pressure alarms

4. SPDS displays and associated alarms

5. Verbal alert by plant staff that all FW flow has been lost and/or SG(s) level is inappropriate for current plant conditions Performance Indicators:

1. Operation of associated EFW valve controls.

Feedback:

1. EFWflow

2. SG level and pressure

3. RCS pressure and temperature

4. Verbal alert by plant staff of FW flow and/or SG(s) level status

-4

Scenario Event Description NRC Scenario 2 Industry Experience:

FW-P-1A Coupling Failure (TMI CR-00189457)

Harris Nuclear Plant Manual Scram Due to Loss of Feedwater (12/14/99)

Oconee 1 Loss of Feedwater (5/26/00)

Low System Grid Voltage at TMI on 7/6/99 (Control Room Log)

Fort St. Vrain Loss of all AC Power (Blackout) (10/27/83)

SOER 99-1 Loss of Grid (12/99)

PRA

Feedwater Transient (Initiating Event)

Loss of Offsite Power (Initiating Event)

Diesel Generator 1A loss (Risk Increase Factor)

-5

Scenario Event Description NRC Scenario 2 I

Event Description Procedure Support Initial Set-up.

100% Power, MOL i EF-P-1 Tagged OOS due to bearing replacement 1 MU-P-1 B Trips OP-TM-AOP-041, LOSS OF SEAL INJECTION i

2 I Loss of the 8 bus with EG-Y-, B l' OP-TM-AOP-OI4. LOSS OF 1E 4160V BUS failing to start

. OP-TM-864-90 1, "SBO Diesel Generator (EG-Y -4)

. Operations T.S. 3.7.2.b, 3.7.2.c, 3.7.2.d 3 Narrow Range Pressure Fails

OP-TM-MAP-G0205, PZR LVL HI/LO High i 4 Loss of FW-P-1 B, Power 1102-4, POWER OPERATIONS Reduction due to Runback

. Failure OP-TM-MAP-M0107, FW-P-1B TRIP OP-TM-MAP-H01 01, RUNBACK OP-TM-621-471 ICS Manual Operations 5 Stuck Rod OP-TM-MAP-G0201, CRD PATTERN

. ASYMMETRIC I

OP-TM-AOP-062, INOPERABLE ROD OP-TM-621-471 ICS Manual Operations T.S. 3.5.2.2.b.

i 6 Loss of Offsite Power OP-TM-EOP-001, Reactor Trip OP-TM-AOP-020, Loss of Offsite Power 7 "A" EDG fails to start, manual OP-TM-861-901, Diesel Generator EG-Y -1 A start required. Emergency Operations 8 EF-V-30A/D fail to 0% in auto.

OP-TM-424-901, Emergency Feedwater II

- 6

Scenario Set-up NRC Scenario 2 ACTION COMMENTS /INSTRUCTIONS DESCRIPTION Initialization IC-52 100% HFP ICS full AUTO Equilibrium XENON Console Center EF-P-1 Tagged OOS EF-P-1 Scenario Support Malfunction FW17 Value: Insert EF-P-1 Scenario Support When: Immediately Main Console Robust Barriers applied lAW EF-P-1 Scenario Support Protected Equipment Tracking Sheet Remote FWR78 Value: Manual EF-P-1 Scenario Support When: Immediately Remote FWR79 Value: 0 EF-P-1 Scenario Support When: Immediately Remote FWR80 Value: Manual EF-P-1 Scenario Support When: Immediately

Remote FWR81 Value: 0 EF-P-1 Scenario Support I When: Immediately !

Malfunction IC16 Value: Insert Failure to Runback Scenario When: Immediately Support Malfunction EG01 A Value: Insert EG-Y-1 A Fails to Auto Start When: Immediately I Malfunction EG01 B Value: Insert EG-Y -1 B Fails to Auto Start I When: Immediately I Remote ICR02 Value: 0 EF-V-30A/D fail in auto When: Immediately Remote ICR04 Value: 0 EF-V-30B/C fail in auto When: Immediately Malfunction MUO" B Value: Insert MU-P-1 B Trip When: EVENT #1 Malfunction ED18B Value: Insert Loss of 8 Bus When: EVENT #2

Malfunction NI27A Value: Severity 85 Ramp 30 Narrow Range Pressure When: EVENT #3 Instrument Fails Hi, SASS Fails to actuate Malfunction FW15B Value: Insert Loss of FW-P-1 B When: EVENT #4 Malfunction RD0230 Value: Insert Stuck Control Rod When: EVENT #5 I Malfunction ED18A Value: Insert Loss of Off-Site Power I When: EVENT #6 Trigger #7 Value: ZDIDGSTRT(1)==1 Allows manual start of "A" Command: DMF EG01A EDG

- 7

Scenario Set-up NRC Scenario 2 ACTION COMMENTS /INSTRUCTIONS DESCRIPTION 03A8S03 Value: On Trips SBO ZDIDGSBOG212(4) When: EVENT #6 Trigger #10 Value: ZDI86BP41 ==1 Allows manual closure of Command: DOR G2-12 (SBO output breaker)

I ZDIDGSBOG212(4)

I

-8

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

Scenario # 2 Event # Page 9 of 35

~-------- ~~

Event

Description:

MU-P-1 B Trips, Loss of Seal Injection TimEl II Position I: Applicant's Actions or Behavior i BOOTH OPERATOR: When directed by the Lead Examiner INITIATE EVENT 1.

I .~

I Indications Available: Zero amps on MU-P-1B, Yellow disagreement light MlI-P-1B, i MAP Annunciator.

I Crew Diagnoses the loss of MU-P-1 B.

i CRS Announces entry into OP-TM-AOP-041 , Loss of Seal injection.

i OP-TM-AOP-041, Loss of Seal Injection IAAT ICCW flow is < 550 GPM (IC-5 FI) and SI Flow < 22 GPM, then perform the following:

N/A

- A. ENSURE the reactor is tripped.

. _ B. ENSURE all RCPs are tripped.

IAAT ICCW flow < 550 GPM and #1 seal inlet temperature>

i 235°F, then perform the following:

N/A - A. CLOSE MU-V-20.

i

- B. GO TO OP-TM-226-901, "Loss of All RCP Seal Cooling".

.i" .t;NS.UF1E.~lJ-Y-32i~tnHA~Dpy'fessinq..~ttewhit~. "Hanel"

pu~hbutton (CQ},*.verifying thy_th~ Wbite "ri~n9" .fight .isU~~od the red "Au£(l"U~ht goesoutfitng Closed bYil~~&ring9nthEf i ...*

.*i .**.i 'j *.* * .:* :* *

loggle.$Witch (CC}to a valutlof'zero .., < " .. :

i CRS When 1D or 1E 4160V bus is energized, then CONTINUE.

Appendix 0 Operator Action Form ES-D-2 Op Test No.: .....;....

Scenario # 2 Event # Page 10 of 35

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

Description:

MU-P-1 B Trips, Loss of Seal Injection TimE~ II Position II Applicant's Actions or Behavior VERIFY a makeup pump is operating (MU .header pressure MU2-PI is above RCS pressure) and aligned to seal injection.

RNO:

ENSURE MU-V-17 is Closed by pressing the white "Hand" pushbu~on(CC), verifying that the white "Hand" light is lit and the red "Auto" Hghtgoes out and Closed by lowering on the LIRO toggle switch (CC) to a value of zero VERIFY[MU-T-1 pressure and level are in the unrestricted operating region} or [MU-V44A orB is Open).

If MU tank level was < 18" at any time, then PERFORM OP-TM-211-271 to vent the MU pumps.

If MU-V-77A & B are Open, then GO TO Section 4.

If MU-V-77A & B are Closed and HPI train B and Normal MU N/A header piping is intact, then DISPATCH an operator to open MU-V-77A & B. (AB 281: MU valve alley)

ENSURE MU-P-1A is ES Selected. (CB 338: 10 4160V Bus URO Unit 7)

VERIFY one of the following:

URO _ MU-V-36 and 37 are Open

_ MU-V-16A or 16B is Open ENSURE DR-P-1A and DC-P-1A are operating by rotating the ARO control switch for each pump (CC) clockwise, observing red light lit, green light out, and indicated amps appear normal.

START MU*P-1A by rotating the control switch (CC) clockwise, ARO observing red light lit, green light out, and indicated amps appear normal.

VERIFY a makeup pump is operating (MU header pressure ARO MU2-PI is above RCS pressure) and aligned to seal injection.

Appendix 0 Operator Action Form ES-O-2 Op Test No.:

-- Scenario # 2 Event # --.;..._ _ _ _ Page 11 of ....,;3;..;;.5--11 Event

Description:

MU-P-1 B Trips, Loss of Seal Injection Position A licant's Actions or Behavior ARO

VERIFY #1 seal temperatures are < 235°F.

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

ARO VERIFY MU-V-20 is Open.

$J~ly A..OJt)J! MtJ"V732'~~~~~~~finl~rtiol1flow.tar~te

.ttlil.Vfitt: liJr)ft>8~t;?f'a~r~ COp.!doWJlJ~ttt:< 1?F/mif'lby rai~Il~,on.UletDQ9;le sWitch ( lIntil 38 gpm inciicatedseaJ i ~tiollflow.~* . . ~

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

~n RESTOR~ffJzrj~yjtJ~Ul ra,te '.~'

consrstertt~RCS. ..... . . recpntr't;)t QY;laising. 9n. th~toggfe

,;.----''__~~__-~'--__I__~,witch.(eclUntilipre~ri~erJevelis**r~ored;*"

NOTE TO EXAMINER: MU-V-32 and MU-V-17 to AUTO control is at the discretion of the Examiner. The scenario may continue prior to the next two actions.

NOTE TO EXAMINER:

Table 3.5-4 (Remote Shutdown System Instrumentation and Controls)

MU-P-1B Required number of Functions: 1

3.5.7 Specification

The minimum number of functions identified in Table 3.5-4 shall be OPERABLE. With the number of functions less than the minimum required, restore the required function to OPERABLE status within 30 days or be i in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within I an additional 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

I I I NOTE TO EXAMINER: When Pressurizer level is being restored and after the Tech Spec call has been made, GO TO Event 2.

Appendix D Operator Action Form ES-D-2 Op Test No.: --:..._ Scenario # 2 Event # 2 Page 12 of 35

~-------- ~~I Event DElscription: Loss of 8 Bus, EG-Y-1 B fails to start Time I Position I Applicant's Actions or Behavior BOOTti OPERATOR: When directed by the Lead Examiner INITIATE EVENT 2.

Indications Available: Loss of half of CR lighting, MAP alarms, loss of multiple loads.

NOTE TO EXAMINER: The crew may enter OP-TM-AOP-034, Loss of Control Building Cooling, if cooling is lost for> 15 minutes.

BOOTti OPERATOR: If contacted as the dispatcher for information of the 8 bus, inform the caller that you don't have any information as to the cause or expected timeframe and that you will call as soon as you get some information. No call back will be required throughout the scenario.

~ Crew Diagnoses the Loss of 1E 4160v Bus.

CRS Directs entry into OP-TM-AOP-014, "Loss of 1E 4160V Bus".

OP-TM-AOP-014, "Loss of 1E 4160V Bus" Announce entry into OP-TM-AOP-014, "Loss of 1E 4160V Bus" ARO over the plant page and radio.

Initiate OP-TM-861-902 "Diesel Generator EG-Y-1 B ARO Emergency Operations".

URO Verify RCP seal injection flow> 22 gpm.

BOOTH OPERATOR: If directed to throttle SR-V-6, acknowledge order only (was not manipulated during validation).

Dispatch an operator to throttle SR-V-6 to approximately 30 ARO degrees OPEN

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # _2~_ _ _ _ Page 13 of __3....

5--11

. Event DElscription: Loss of 8 Bus, EG-Y-1 B fails to start

Time II Position !I Applicant's Actions or Behavior I i

I . . .. .. m---l I BOOTH OPERATOR: If directed to go to NR-V-1SA or NR-V-1SB, acknowledge order (manipulation was not needed during validation) .

r- ARO If MU-V-3 is open, then dispatch an operator to open NR-V-15A or NR-V-15B to maintain ICCW temperature <1 OOF IAAT SR-P-1A is shutdown, and GB1-02 or GP1-12 is closed, then PERFORM the following:

1. If reactor power >45%, then

a. TRIP the reactor, N/A

b. PERFORM EOP-01 IMA,

2. If reactor power <45%, then TRIP the turbine.

3. INITIATE OP-TM-AOP-033,"Loss of Secondary Component Cooling".

i INITIATE reactor power reduction lAW 1102-4 to maintain N/A

. secondary closed system temperature <95°F (A0322).

IAAT the Reactor is shutdown, then PERFORM the following:

_CLOSE FW-V-17B in HAND, N/A

_PERFORM OP-TM-732-902 "Energize 1S 480V Bus Using ES Bus Cross Tie".

r-------~------_r--------

URO . ENSURE IC-P-1A is operating.

r-------~------~-

URO i ENSURE NR-P-1A is operating.

ARO INITIATE OP-TM-541-443 to swap NR-P-1 B to 1R 480V bus.

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 2 Event # ...;2;;;.....____ Page 14 of ...,;3;;.;;,5---"1

---=--

Event DElscription: Loss of 8 Bus, EG-Y-1B fails to start Time II Position II Applicant's Actions or Behavior IAAT EG-Y-1 B is not available, then INITIATE OP-TM-864-901, ARO "SBO Diesel Generator (EG-Y-4) Operations".

OP-TM-864-901, SBO Diesel Generator (EG-Y-4) Operations ARO VERIFY 1E 4160V bus is de-energized.

ARO ENSURE 1SA-E2 and 1SB-E2 are OPEN.

VERIFY one of the following is TRUE.

ARO A. FS-P-1, FS-P-2 or FS-P-3 is operating.

B. FS-P-2 is operable except that power is not available.

ENSURE the following control switches are in PTL:

A. BS-P-1 B by turning the control switch (CR) counter clockwise and pulling up until the handle is in the PTL position, verifies all lights are not lit B. The ES selected MUpump: MU-P-1C or MU*P-1 B-E by turning the;)controlswitch (CR) counter-clockwise and pulling upuntiJ the handle;) is !nthe .PTL position. verifies all tights are not lit.

ARO C. DH-P-1 B by turnillg the;) control switch (CR) counter clockwise and pulling up until the handle;) is in the PTL position, verifies all lights are not lit.

D. RR-P-1 B by turning the control switch (CR) counter clockwise and pulling up until the handle is in the PTL pOSition, verifies all lights are not lit.

E. EF-P-2B by turning the control switch (CC) counter clockwise and pulling up until the handle is in the PTL position, verifies all lights are not lit PRESS and HOLD for approx. 8 seconds SBO DIESEL ARO GENERATOR START PB.

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 2 Event # .....;2~_ _ _ _ Page 15 of .....;;3=5---!1

~-

Event

Description:

Loss of 8 Bus, EG-Y-1 B fails to start Time Position A licant's Actions or Behavior If generator voltage is not between 4.1 and 4.3 kV, then N/A ADJUST Unit Volta e Rheostat.

If generator frequency is not between 59 and 61 Hz, then N/A ADJUST governor.

ENSU~'ij~1J~02 is i{l~~J'=L~~:~turning theqontrJll. switch (CR) counter~cilo" " .pulling up until the. handle is 1n the PTL position, ver * *~~tlit .

PLACET1-C2 *inP-T~ ~flicigth~:COn~~witch<f?R) counter-cl?:ck~i~~. i . . . . . pyrtil theb~~leJs il1:tmeBTL position, verif~~~Ili9hts.&n9tlit.

CLOStE~g-12:~G~V-4AAwut ~teak$J'jby ttJr.~~99 the control s\\'itch(C~}c~~isel~rifiesthe* closed IIgPlt\.itilf!t.,nd* the open IighUs*riot.~:"* . '. .

tlr~~fltrol switC~'§~}r~e,verifies . *Slosed~Mi~tis lit and WleQP.e,n ligntls not ."<\ :';

OP-TM-AOP-014, "loss of 1E 4160V Bus".

1MT 1E 4160 V bus is energized, then Go TO Section 4.0 CRS "Return to Normal".

Log entry into TS 3.7.2.b action statement. Reactor operation CRS in this condition is limited to 30 days.

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 2 Event # ,..;2;;;....._ _ _ _ Page 16 of 35 Event

Description:

Loss of 8 Bus, EG-Y-1 B fails to start Time II Position Ii Applicant's Actions or Behavior NOTE TO EXAMINER:

3.7.2.b: Both 230/4.16 kV unit auxiliary transformers shall be in operation except that within a period not to exceed eight hours in duration from and after the time one Unit 1 auxiliary transformer is made or found inoperable, two diesel generators shall be operable, and one of the operable diesel generator will be started and run continuously until both unit auxiliary transformers are in operation. This mode of operation may continue for a period not exceeding 30 days.

3.7.2.d: If one unit auxiliary transformer Is inoperable and a diesel generator becomes inoperable, the unit will be placed in HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

If one of the above sources of power is not made operable within an additional 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the unit will be placed In COLD SHUTDOWN within an additional 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter.

I I NOTE TO EXAMINER: After the Tech Spec call is made and the SBO is powering the 1E 4Kv bus, GO TO Event 3.

Appem:lix D Operator Action Form ES-D-2 Op Test No.: .....;...._ Scenario # 2 Event # ....;3~_ _ _ _ Page 17 of .....;3;;.;;;,5---11 Event

Description:

Narrow Range Pressure Instrument Fails High. SASS Fails to Actuate Time I Position II Applicant's Actions or Behavior

, BOOTH OPERATOR: When directed by the Lead Examiner INITIATE EVENT 3.

I

. Indications: MAP G0308 and H0302 alarms, Spray Valve opens, ICS Transient, Pressurizer heaters deenergize.

I I

Examiner Note: The crew may decide to perform OP-TM-AOP-070. Those steps can be found on page 33 of this scenario.

I i Diagnoses the failure of the selected Crew

, Instrument.

I CRS I Directs entry into OP-TM-MAP-G0308. RC PRESS NARROW

, RNG HI/LO.

OP-TM-MAP-G0308, RC PRESS NARROW RNG HI/LO

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

If RC-RV-2 PORV is Open and RCS pressure <2400 psig, then N/A CLOSE RC-V-2.

$~9'1C~\(~1~zRSpr$.yCOntr~1 \(alVebY.. .

pressin clo~;pu~ttQ~*(C~);verif}109\ialve cl~~d light f----'-"""-'-~-'-'__f----'-"~_ _ __i__is.::.-l-"it....:.a-nd--va-lv--'fiI.

- 9pen:lf,lrrnotUt; .

- PLAC.~.'1,.q,,\l+flirr~TO.(if.!"t~tdonem:~viouSlY, by pressing tneAutopushbUtt91t . verifYingtnatthe white.i:Hand" Hght is not lit ~the red:.: light is lit. . ~

. If failure of RC-V-1 is suspected, then CLOSE RC-V-3 N/A Pressurizer Spray Line Isol Valve as required.

N/A IAAT Spray Line LlT approaches 250°F, then

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

- - Scenario # 2 Event # ...;3:...-____ Page 18 of .....3......

5--1 Event

Description:

Narrow Range Pressure Instrument Fails High, SASS Fails to Actuate Time II Position il Applicant's Actions or Behavior If Pressurizer level is ~ 80 inches, then ENSURE Pressurizer ARO heaters are energized.

If RC-V-1 and RC-V-3 are Open, then:

1. RESET Thermal Overload for RC-V-1 1A ES MCC Unit 9B.

2. ATTEMPT to Close RC-V-1.

N/A

3. Prior to RPS actuation in low pressure, A. TRIP the Reactor.

B. SHUTDOWN RC-P-1A and RC-P-1B.

C. SHUTDOWN RC-P-1 C or RC-P-1 D.

If pressurizer heater capacity is inadequate to maintain RCS N/A pressure, then GO TO OP-TM-AOP-043, "Loss Of Pressurizer".

N/A If RC-V-3 is Closed, then PLACE an EST on RC-V-3.

i CRS Directs entry into OP-TM-MAP-H0302, SASS ACTUATION.

op-TM-MAP-H0302 If plant control is not stable or Validity of selected instrument is unknown or suspect, then PLACE affected stations in Hand INFO lAW associated manual operations procedures to balance plant arameters.

I OP-TM-220-503, Manual Control of Pressurizer Pressure.

Appendix D Operator Action Form ES-D-2 Op Test No.: -:...-_ Scenario # 2 Event # ...,;3;;;...._ _ _ _ Page 19 of"";;';;;'--11 Event

Description:

Narrow Range Pressure Instrument Fails High, SASS Fails to Actuate A licant's Actions or Behavior IfIC,S *.handpo'~7ii;.mt.itabfe;~tt\.mai~nRe$ipr~~$Ure wilfljnlimits ~".0~}~'* ... :':i'~> ... .. j .**..*..*

. ,:1", Place P~ ~sure~8~;ifl WAND by pressing

....... the white "Hand!lI)U.~9n(C~lf~~~githat the white "Hand"'ight is lit and the red <<.Autd"1i9htgoes out,<

.Pressurizer heater demand for Banks 1 through3

.the toggle switch$l~thePressurizer Pressure

.i;v/Station(q~l~.* '..,

If manual operation of RC-V-1 is desired, then perform the following:

1. Place RC-V-1 AUTO/MAN select switch (RC-V-EX2 CC)

URO in MAN.

2. Cycle RC-V-1 Open or Closed as necessary to maintain RCS pressure within limits.

op-TM-MAP-H0302 URO DETERMINE which input is bad.

INFO I ~~SURE valid instrument selected lAW OP-TM-621-4S1,

!'-----+----T- lecting Alternate Instrument Inputs to ICS.

OP-TM-621-4S1, Selecting Alternate Instrument Inputs to les ENSURE ULD in HAND lAW OP-TM-621-473, "ULD Manual URO Control".

COMPARE alternate inputs (using Attachment 7.3 of OP-TM 621-000, Integrated Control System or table in OP-TM-MAP H0302 as necessary) and VERIFY both of the following:

- Difference between affected and alternate channels are less URO than "SASS Setpoint t::.s" as listed in OP-TM-MAP-H0302 Table.

- Selecting alternate instrument will not affect ICS control or plant stability.

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 2 Event # _3_______ Page 20 of ....,;3;;.;;,5--11

~-

Event

Description:

Narrow Range Pressure Instrument Fails High, SASS Fails to Actuate Position A licant's Actions or Behavior

. SELECT alternat$ in$ttument(s) with consol~.PB bY.. Pf~sing

'the pushbu~on fo~thevalid NR Pressure irn;trl,lmentinput to LlRO *ICS (eq, \l~rjfyingthatvalid NR Pressureseleqted ~n~trlJment light is lit and the invalid NR Pressure selected instrument light is not lit.

URO VERIFY plant stable.

I NOTE TO EXAMINER: When the alternate Narrow Range Pressure instrument is selected, GO TO Event 4.

Appendix D Operator Action Form ES-D-2

. Op Test No.: Scenario # 2 Event # _4..:...._ _ _ _ Page 21 of .....;3;.;;;,5---11

~-

Event

Description:

FW-P-1 B trips, Runback fails to occur, Power reduction performed Time Ii Position I Applicant's Actions or Behavior I BOOTH OPERATOR: When directed by the Lead Examiner INrnATE EVENT 4.

I Indications Available: MAP M-1-7 actuates, LO-P-8 starts, FW-P-18 RPMs go to i _ z e r o , Rods do not travel as expected for the run back.

I I Examiner Note' The crew may decide to perform OP TM AOP 070 Those steps can be found on page 33 of this Scenario.

I I

i OP-TM-MAP-M0107, FWP 18 Trip ARO ENSURE plant runback and determine cause of trip.

I ARO ENSURE LO-P-S8 running.

ARO ENSURE FW-V-1 8 Closed.

I OP-TM-MAP-H0101, ICS Runback ENSURE NI power is reduced to below the limit for the runback URO condition.

INFO INITIATE 1102-4 for power reduction.

1102-4, Power Operation PERFORM Enclosure 2A (for an emergency (forced) power CRS reduction INITIATE Enclosure 2A).

Examiner Note: ULD will go in "Track" mode when the Runback fails to occur and therefore the URO will not be able to control reactivity with the ULD. Control will be taken at the SG/REACTOR DEMAND STATION for the reactivit y mani pulation.

URO ENSURE ULD is in HAND.

Appendix 0 Operator Action Form ES-D-2 Scenario # 2 Event # _4,.;,..-_ _ _ _ Page 22 of .....;3=5---11 FW-P-1 B trips, Runback fails to occur, Power reduction performed Time Position A licani's Actions or Behavior ARO i MAINTAIN Generator Reactive Load lAW OP-TM-301-472.

If SG/REACTOR DEMAND is in HAND, then REDUCE reactor INFO ower lAW OP-TM-621-471 niCS Manual 0 erations".

OP-TM-621-471 "Ies Manual Operations" URO I ENSURE ULD in HAND.

PbAC6 ~rt)Ro~:E~~D~t.i<mif\HAND~tg,r~Sing the whit.~d*'pushb~on,~CC)f verifyingJi;lst thewbite "Hand"lighti$fitst)d*.theJ9Q*"Auto'!lightgoe~Qut .

r-~--~t~~~~~~------~

URO ENSURE control rod position does not change.

URO . VERIFY alarm H-2-1 niCS in Track" In.

If neC$~$arYt(). roaintair1rea$t9rpower\orC . rpds.Wittiin limits or if,. power cns tlilelJADJWST $G/A~

btipg QOhd'-:l . / . lAW 110?--4,.

A [)J:SMAt~Oi) a~,~lIowS:

(" ,"

If~r.~f:fg .bl~~ea .fPo\'Ver Qr:;;a>~l~~ 'plan~PQw~r

~ari~~,th,.n~~E~ k . . *. . . . . EJ1

io dl~retestefl$:tQ ~eep

,"neutronerror betW~*;+2%.and+2%,*

~ .. ~*ra~~w..r~~~i~JeqUirEicf".~n.LOWEJ1.~~>

" . *.,ac~~~W*:~~jFedre~ptQr3QQ.er levefWlg

/.~~" ~Jiltr~ .Wi~JirnltSiJY l~eringand/or'

. ra e 9G/R~t~ OEM,AJf4pt9ggl.e SVlttei\(CC) asne~sa:.,

1102-4, Power Operation INFO PERFORM the actions per Enclosure 28.

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

Event DElscription:

Scenario # 2 Event # _4_ _ _ _ _ _ Page 23 PlY*P-1 B trips, Runback fails to occur, Power reduction performed of ....,;3;,;;.5--l.

A licanfs Actions or Behavior 1102-4, Power Operation, Enclosure 28

.*;;.. i;j.~~j~*":':**.** **Prior to FW-U-1A speed <4000rpm (between 100%-90%

.<~~actor power as a guide): .. .

ARO

<: Start LO-P-1Aby:tUmtngthe cont~olswitch (Cl.)clookwise,

' n~" " 'verifying the red.lijnt is lit and the green light is I')~tl\t NOTE TO EXAMINER: Event 5 must be in prior to 85% power in order to get the expected results.

NOTE TO EXAMINER: When the reactivity manipulation is satisfied, and prior to 85% power, GO TO Event 5.

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

-- Scenario # 2 Event # .,.;5::..-_ _ _ _ Page 24 of ...,;3;.;:;,5---11 Event

Description:

Stuck Control Rod I Time IL Position I Applicant's Actions or Behavior

'''Tii OPERATOR: When directed by the Lead Examiner INITIATE EVENT 5.

I i

I Indications Stuck rod indication on the PI Panel, MAP alarm G0201 i

I Crew Diagnoses the stuck control rod. I i

CRS i Directs entry into OP-TM-AOP-062, Inoperable Rod.

OP-TM-AOP-062, Inoperable Rod.

CRS RECORD time of discovery of inoperable rod.

If a rod group has dropped, then TRIP the reactor and GO TO N/A OP-TM-EOP-001.

IAAT more than one safety or regulating rod is inoperable, then perform the following:

A. INITIATE a plant shutdown to Hot Shutdown lAW 11 02-4 and 11 02-1 O.

B. Perform the following within one hour: (TS 3.5.2.2.a)

N/A 1. PERFORM a shutdown margin calculation lAW 1103-15A Section 3.2, "Calculation of shutdown margin with Tave;;:: 530°F."

2. If SDM is not more negative than -1 % ~K/K, then INITIATE Emergency Boration.

C. EXIT this procedure.

N/A IAAT all control rods are operable, then GO TO Section 4.0.

i CRS REQUEST duty reactor engineer to report to vuntrul I i i URO VERIFY reactor power> 5 %.

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

Event DE3scription:

Scenario #

Stuck Control Rod Event # .,..;5;;....._ _ _ _ Page 25 of ...,;3;;.;;;.5_

1 Tim A licant's Actions or Behavior F URO VERIFY safety group Out Limit (Diamond panel) is LIT.

VERIFY the inoperable rod is fully inserted.

RNO:

1. If any regulating or safety rods are inoperable, then perform the following within one hour: (TS 3.5.2.2.b,c).

A. INITIATE 1103-15A section 3.2, "Calculation of shutdown margin with Tave 2: 530°F." (TS 3.5.2.2.c).

B. If shutdown margin less negative than - 1% AK/K then INITIATE boration to achieve required shutdown CRS margin.

2. If one of the following is true:

rod does not meet trip insertion time rod can not be exercised rod can not be located then INITIATE OP-TM-622-201 Control Rod Movement to verify the operability of other rods, and GO TO step 3.11.

(TS 3.5.2.2.b).

If all of the following are satisfied:

The misaligned rod is latched and in Group 7 Rod group overlap can be satisfied with group adjusted to the affected rod position Rod insertion limits can be satisfied with the group URO adjusted to the affected rod position.

. then perform the following:

- A. TRANSFER all rods in Group 7 except the affected rod to the aux power supply lAW OP-TM-622-451.

B. ADJUST RCS boron concentration to trim Group 7 position to within 9" of the affected rod.

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

-- Scenario # 2 Event # _5~____ Page 26 of ...,;3;..;.,5---1\

Event

Description:

Stuck Control Rod Time II Position 'I Applicant's Actions or Behavior NOTE 'TO EXAMINER:

3.S.2.2.b Specification: If a control rod in the regulating and/or safety rod banks is declared inoperable in the withdrawn position as defined in Specification Paragraph 4.7.1.1 and 4.7.1.3, an evaluation shall be initiated immediately to verify the existence of one percent Aklk hot shutdown margin. Boration may be initiated to increase the available rod worth either to compensate for the worth of the inoperable rod or until the regulating banks are fully withdrawn, whichever occurs first. Simultaneously a program of exercising the remaining regulating and safety

. rods shall be initiated to verify operability.

I i

I I EXAMINER: When the Tech spec call has been declared and prior to placing rods on the Aux power supply, GO TO Event 6.

Appendix D Operator Action Form ES-D-2 Op Test No.: ____ Scenario # .2..- Event # ....;6;;.:..7:..J.,8~_ _ _ Page 27 of ....,;3;..;;;,5---11

. Event

Description:

Loss of Offsite Power. Reactor and Turbine Trip. SBO trip. "An EDG fails to auto start, EFW valves fail to 0% in auto.

A licant's Actions or Behavior I BOOTH OPER~TOR: . . When directed by the Lead Examiner INITIATEEVENT 6. I

!lndiCatiOnS Available: Loss of half of ell lighting, MAP alarms, loss of loads, Reactor and Turbine Trip.

m~. I Crew Diagnose the loss of offsite power, reactor and turbine trips.

CRS Directs entry into OP-TM-EOP-001, Reactor Trip.

~

OP-TM-EOP-001, Reactor Trip VERIFY REACTOR SHUTDOWN.

URO VERIFY the turbine stop valves are Closed.

OS-24

~~P~~J~G~ V,,,,,A d(~1,hot8tat't.f')~ $tattE~~Y-1~:tly'<

)?r:' e S1;. t;tDn, V&(ifYing.runniOfJIig.nt.i~ lit,. .. . . '

"~f!..... ..er¥tl~' hertzl"~Qbserving~;ofmEl Control.

i=toorncl are lifafter a 10 second dela . t i i NOTE TO EXAMINER: MU-P-1A, DC-P-1A and DR-P-1A are secured when the loss of offsite power occurs. Upon starting EDG-Y-1A and i energizing the 1D 4kV bus, MU-P-1A will restart but DC-P 1A and DR-P-1A will not.

(Qtatif'lg.th~~~t(OI*.~o~Jar rvf l1 gred Ugpblit,green 1\36t normal. '0

Appendix D Operator Action Form ES-D-2

! Op Test No.: 1 Scenario # 2 Event # _6.;.L,7;;..z.,,;;;..8_ _ _ Page 28 of ...3;.,;.5--11

. Event

Description:

Loss of Offsite Power, Reactor and Turbine Trip, SBO trip, "A" EDG fails to auto start, EFW valves fail to 0% in auto.

Time II Position II Applicant's Actions or Behavior i OP-TM-EOP-001, Reactor Trip I Performs a Symptom Check and declares Lack of Transfer based on:

ARO Incore temperatures rising and ReS circulation can not be

conflfmed.

Directs entry into OP-TM-EOP-004, Lack of Primary to CRS Secondary heat Transfer.

r-------~------~--

OP-TM-EOP-004, Lack of Primary to Secondary Heat Transfer.

CRS ENSURE no more than one RCP operating per loop.

ARO INITIATE OP-TM-424-901, "Emergency Feedwater".

OP-TM-424-901, Emergency Feedwater Recognizes no flow to A or B OTSGs.

4.1.3 1MT steps 4.1 .4, 4.1.5, or 4.1.6 are not satisfied, then initiate Section 4.2 "Contingency Actions",

ARO 4.1.5: Verify A OTSG level is above setpoint lAW Rule 4, or Emergency Feedwater flow is established.

4.1.6: Verify B OTSG level is above setpoint lAW Rule 4, or Emergency Feedwater flow i~_e_s_ta_b_li_s_he_d_'__________---1

.;*4.2.. 1,tfthjf~i~ nOeFVvflowan"le~~li~,<setpoint,then

'perfQrmJhelolfowing: ~ .

':,;,<'/:'_... -- ,.-~.,.:\,.,

.1.:,;'OPen ~n_Ef;'M~>toeactrQf$Gt() m~ntain requtf!ed level by the Man~~1 pus;~l.Itt~rys (CO tnd.CL).Cind '

toggle svvitCtlti in.~~~!()~1l directipn. ARO may t ,_Je switch~sJn~fuU~pen positiol1~'_ _~-'-"-_--,

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

Scenario # 2 Event # _6;;.:.,7;..:.,8.;;....._ _ _ Page 29 of ....;3;;,;;.5---11 Event

Description:

Loss of Offsite Power, Reactor and Turbine Trip, SSO trip, "A" EDG fails to auto start, EFW valves fail to 0% in auto.

A licant's Actions or Behavior NOTE 'TO EXAMINER: ARO may choose to open all EF-V-30 valves (A-D) lAW OS-24:

Licensed operators may take action without procedural guidance, and without taking a variance under the following conditions.

Action taken to directly compensate for the failure of an automatic system.

OP-TM-EOP-004, Lack of Primary to Secondary Heat Transfer.

ENSURE announcement of reactor trip.

VERIFY both 1 D and 1E 4160V buses are energized from auxiliary transformers.

URO RNO:

If offsite power has been lost, then INITIATE OP-TM-AOP-020, "Loss of Station Power".

Directs entry into OP-TM-AOP-020, Loss of Station Power CRS simultaneous with EOP-004.

OP-TM-AOP-020, Loss of Station Power ARO INITIATE "Emergency Feedwater".

INITIATE both OP-TM-861-901, "EG-Y-1A Emergency ARO Operations" and OP-TM-861-902, "EG-Y-1 B Emergency Operations".

NOTE TO EXAMINER: The crew mayor may not pursue reenergizing the 1E 4kV bus with the SBO diesel generator.

Appendix D Operator Action Form ES-D-2

Op Test No.: -.;..._ Scenario # 2 Event # _6;;.:,,7.;..,:,,;;;.8_ _ _ Page _.

30 of Event

Description:

Loss of Offsite Power, Reactor and Turbine Trip, SBa trip, "A" EDG fails to auto start, EFW valves fail to 0% in auto.

Ti A licant's Actions or Behavior VERIFY 1D 4160V and 1E 4160V bus are energized.

RNO:

ARO If only one ES 4160V bus is energized, then initiate OP-TM 864-901, "SBO Diesel Generator (EG-Y-4) Operations" to energize the affected ES 4160V bus.

BOOTH OPERATOR: If asked to investigate the SBO diesel generator, report back that you found nothing wrong with the SBO diesel generator.

Verify one of the following pumps operating:

URO - IC-P-1A

- IC-P-1 B CRS VERIFY seal injection flow> 22 gpm.

CRS Request SM evaluate Emergency Action Levels (EALs).

Directs the ARO to verify natural circulation flow exists lAW CRS OP-TM-EOP-01 0, Guide 10, Natural Circulation. I OP-TM-EOP-010, Guide 10, NATURAL CIRCULATION IAAT all RCPs are off, then If all of the following conditions exist, then adequate natural circulation is present:

- RCS THOT minus TCOLD stabilizes at less than 50 of.

- THOT < 600 of.

ARO - Incore temperature stabilizes and tracks THOT.

- Cold leg temperatures approach saturation temperature for secondary side pressure.

- OTSG heat removal is indicated by feeding or steaming with stable OTSG pressure.

-SCM> 25 F.

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

Scenario # 2 Event # _6;;.1,,7;;...:,8~_ _ _ Page 1L of 35 Event Description; Loss of Offsite Power, Reactor and Turbine Trip, SBO trip, "A" EOG fails to auto start, EFW valves fail to 0% in auto.

Time II Position II Applicant's Actions or Behavior OP-TM-EOP-004, Lack of Primary to Secondary Heat Transfer.

IAAT primary-to-secondary heat transfer (PSHT) has been N/A established, then GO TO step 3.20.

When primary to secondary heat transfer (PSHT) has been CRS restored, then CONTINUE.

10, Rule 5 "Emergency Boration" WAAT one of the following conditions exist:

- 1% dk/k SHUTDOWN has been achieved for the expected plant condition lAW Figure 1 of 1103-4, "Soluble Poison Concentration Control", or 11 03-15A, "SDM and Reactivity Balance".

N/A

- LPI > 1250 gpm per line.

- Tavg > 525F and stable or rising and all Control Rods are inserted, and Neutron flux is lowering as expected.

then emergency boration may be terminated.

URO Verify a MU pump is operating.

',),**, fi)erforrn.aJ'{$O!thefoflawing: \ ," ';

- OPEN MU-V-14A by pressing theo,R~1'l pushbutton (CC) *

."erifying valve open. light is lit andvalV~closedUghtnot lit.

URO;;i' . <;OPENMU-V:c14BbY pressing the, open pushbutton (CC),

~~ifyingvalve. t,')~rijigt\t is lit and valve closed light n()~ljt.

i~~ j: .eel fp'z\i':; . PERf20fVliti~ide1, "Emergency Borationeatpkup

".' ,i } i , Metttoda"':

URO Verify Total Injection (MU, SI and HPI) > 50 gpm.

Appendix D Operator Action Form ES-D-2 Op Test No.: .....;...._ Scenario # 2 Event # 6,7,8 Page 32 of 35

~~------- -~~I Event DE~scription: Loss of Offsite Power, Reactor and Turbine Trip, SBO trip, "A" EDG fails to auto start, EFW valves fail to 0% in auto.

Time II Position I Applicant's Actions or Behavior Stop any activities which may be diluting RCS boron N/A concentration.

If SCM> 25F and neutron flux indication is rising, then N/A STABALIZE RCS temperature.

NOTE 'TO EXAMINER: The scenario can be terminated when Natural Circulation flow is established.

I ITERMINATE the scenario.

Follow-up question highest event entered during scenario?

Answer: MU1 Loss of Offsite Power to Essential Busses for Greater Than 15 Minutes

Appendix D Operator Action Form ES-D-2 OpTest No.: --.;....

Scenario # 2 Event # 3 (All. actions) Page 33 of ....;3;..;;.5~1 Event D4~scription: Narrow Range Pressure Instrument Fails High, SASS Fails to Actuate Time II Position I Applicant's Actions or Behavior Examiner Note: The crew may decide to perform OP-TM-AOP-070 for Events 3 and/or 4.

OP-TM-AOP-070 E~sure Di~d,

.pOshbutto Jv1anualli~ht Utan

.*~asne~s~a

. and for, 9,r()~sbalal1cewttf? t~t~!

both $GA&BFW DEMANI:).in'tfANIJ by pressing "Ha .. tton (CC), vertfyipg.that the,while

':~aRcf'liglim.. . .' . re,d"Al.Jto"{j$.,* . . . .outa,1ld AQJUST FW.Flow .to $tte.a¥g~the~rrel1t. S*t~mpera~.

Verify Turbine Header Pressure is between 835 and 935 psig.

URO (MAP H-2-3 is not in alarm).

URO VERIFY ReS pressure is lowering or less than 2205 psig.

IAAT RPS setpoint is reached or Reactor trips, then GO TO N/A EOP-001.

IAAT MU Tank Level is approaching 55", then perform the following:

1. INITIATE OP-TM-EOP-010 Guide 9, Section A, "MU N/A Tank Level Control".

_ _ 2. If control rod index approaching 300%, then LOWER reactor ower to achieve desired control rod band.

ARO VERIFY Main Turbine is RESET.

Appendix D Operator Action Form ES-D-2 Op Test No.: --:..._ Scenario # 2 Event # 3 (All. actions) Page .2i.. of .-.,;3;.;;;,5---11 Event

Description:

Narrow Range Pressure Instrument Fails High, SASS Fails to Actuate TimE! II Position :1 Applicant's Actions or Behavior ASSIGN manual control responsibilities and control bands:

- INSERT or WITHDRAW rods to maintain Reactor power within 1% of current power level.

- ADJUST FW Flow to maintain Tavg within 2°F of current temperature.

CRS

- MAINTAIN Turbine Hdr Pressure within 10 psig of current pressure.

-If Main Generator Breakers are CLOSED, then ADJUST Turbine Load Set.

- If Main Generator Breakers are OPEN, then ADJUST TBVs.

If Reactor power has been reduced> 3%, then INITIATE 1102 URO 4, "Power 0 erations," actions for ower reduction.

~,~$~U~~ are 1~~flANO;,"

'1':aGt~~~oem~ndbY pr~~lhEJ~~e "~nd" PIJ~~~a. ,*'~.th$t thewn~""t1al1~"Hgbthlllt.and

'<,,' ...erec:f,~'A~ ','," " "., and.AQJOSTF;W:ffowtQ;;$tabiHze Tavgat~C\Jr~~J!lt;

,\,.y>.'> "" ': ,,' >~)', '

timperstt#"""

" ; /.

';0/

Pf~ngtl1ewhi.te"HSnd" the wI1$"Hand" light is lilan" Jt3Sl'tFW FIoV\l.t9~~aQifi~e

~re. " ' , ," "'"

VERIFY both of the following:

- Operating MFW Pumps are controlling FW Valve dP ARO greater than 30 psid.

- Reactor ower is reater than 75%.

Appendix D Operator Action Form ES-D-2

Op Test No.: Scenario # 2 Event # 3 (Alt. actions) Page 35 of .....;3;.;;,5---1

~-

Event

Description:

Narrow Range Pressure Instrument Fails High. SASS Fails to Actuate TimE~ II Position I Applicant's Actions or Behavior

If Main Turbine is in ICS HAND control, then PERFORM the following:

I _ _ 1. MAINTAIN Tavg stable using FW control and slowly ARO ADJUST Main Turbine to control header pressure between 865 and 905 psig.

- - 2. INITIATE OP-TM-301-471. "Manual Control of Main Turbine."

MAINTAIN RCS pressure between 2105 and 2205 psig and ARO slowly ADJUST feedwater flow to control RCS Tavg 578 to 580 I of.

I MAINTAIN RCS Tavg 578 to 580°F and slowly ADJUST loop ARO feedwater flows to control RCS I!:. Tc < 5° F. I If FW valves are in HAND, then INITIATE OP-TM-421-451 ARO (452), "Manual Control of Feed Flow to A (B) OTSG." I i

If TBVs are in Hand, then INITIATE OP-TM-411-451, "Manual ARO

. Control of TBVs/ADVs."

Appendix D Scenario Outline Form ES-O-1 Facility: Three Mile Island Scenario No.: 3 Op Test No.: 289-2011-301 Examiners: Operators:

Initial Conditions: * (Temporary IC-54)

100% Power, MOL i----

EF-P-1 OOS for bearing replacement, 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months into a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months clock T.S. 3.4.1.1 (2)

I Turnover: Maintain 100% Power Operations i

Critical Tasks:

i--.

Reduce Steaming/Isolate Affected SGs (includes use of SG drains) (CT-22)

Minimize SCM {CT-7}

nt No. Malf. No. Event Type* Event Description 1 03A4S01 ICRS Inadvertent ES Actuation, "B" Train (TS), entry into OP-TM-AOP

- luRO 046 ZDIPB1R IARO (URO: Defeats signal, ARO: Opens MU-V-2A/B)

CBON TSCRS 2 RcoeB ICRS Tc Instrument Fails High, SASS Fails to Actuate, entry into OP IC51 IURO TM-AOP-070 IARO (LlRO: Manual control of Control Rods, ARO: Manual control of Feedwater) 3 TH17B CCRS -30 gpm "B" OTSG Tube Leak (TS), entry into OP-TM-EOP-005 CURO (URO: Guide 9)

TSCRS 4 N/A NCRS Power Reduction lAW 1102-4 R URO I

. NARO 5 CC04A CCRS Loss of ICCW, entry into OP-TM-AOP-032, OP-TM-EOP-001 CC04B CURO (URO: Trips Reactor) 6 TH168 MCRS -800 gpm "B" OTSG Tube Rupture, entry into OP-TM-EOP-005 MURO I MARO I

7 MS09A CCRS "B" TBV's fail closed, entry into OP-TM-421-451 MS09B CARO (ARO: Places ADV on Backup Loader)

MS09C I

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

Scenario Event Description NRC Scenario 3 Three Milte Island NRC Scenario #3 When the crew has accepted the watch, the Lead Examiner can cue Event #1, "8" Train Inadvertent ESAS Actuation (1600# Manual HPI). The operators will diagnose the Inadvertent ESAS based on RCS Pressure, RCS Temperature, and R8 Pressure. The CRS will enter OP TM-AOP-046, Inadvertent ESAS Actuation, and direct the operators to take the actions. URO will defeat the signal to avoid overpressure of the RCS and Reactor Trip. The CRS will review T.S. and declare 3.3.2, 3.5.1.1, 3.5.1.3, and Table 3.5-1. Once the T.S. has been declared, the scenario can continue.

When OP-TM-AOP-046 has been performed and the Tech Spec calls are made, the Lead Examiner can cue the Tc Instrument Failure (High) with SASS failing to actuate. Crew will take manual control of ICS and coordinate to stabilize the plant. When plant is stable, the URO will select the alternate instrument. Once ICS is in manual control and the plant is stable, the scenario can continue.

When ICS is in manual control and the plant is stable, the Lead Examiner can cue the "8" OTSG Tube Leak. The CRS will enter OP-TM-EOP-005. The URO will initiate Guide 9, opening MU-V-18 to reestablish Makeup flow to the Pressurizer, making up for losses due to the tube leak. The CRS will review T.S. and declare 3.1.6.2.

A reactor shutdown will commence lAW 1102-4, POWER OPERATIONS, with the ULD in HAND. The crew may perform this with ICS as is (currently in Manual control) or choose to place ICS in auto prior to commencing a reactor shutdown. When the Lead Examiner has seen sufficient reactivity manipulation and the T.S. has been declared, the scenario can continue.

When sufficient reactivity manipulation has occurred and the T.S. has been declared, the Lead Examiner can cue the Loss of ICCW. The crew will enter OP-TM-AOP-031. The URO will trip the reactor and perform the Immediate Manual Actions of OP-TM-EOP-001. The ARO will perform a symptom check, confirming an OTSG tube leak as the highest priority. Once the symptom check is complete, the scenario may continue.

Once a Symptom Check has been performed, the Lead Examiner can cue the "8" OTSG Tube Rupture. The CRS will continue in OP-TM-EOP-005, OTSG Tube Leak.

(CT-7) ThE~ URO will minimize SCM to lower pressure and therefore lower the OTSG tube leak rate. Guide 8 and OS-24 give direction to maintain SCM 30-70F, but as close to 30F as possible. Failure criteria would be considered if SCM is <25F at any time, as LSCM procedure would be invoked.

(CT-22) The ARO will preferentially steam the "8" OTSG. The preferred method, opening the Turbine 8ypass Valves, will not work, requiring the ARO to use the "8" ADV on the backup loader. The ARO should steam only enough to maintain OTSG level relatively constant. Over steaming would result in more dose released to the public than is necessary. Under-steaming would result in rising OTSG level and complications from possible emergency cooldown and/or isolation of the OTSG. Failure criteria would be considered if improper steaming lead to a loss of Pressurizer level (over-steaming) or if OTSG level reached 85% in the operating range (under-steaming).

The scenario can be terminated when the "8" OTSG has been preferentially steamed using the ADV's and SCM has been minimized.

Scenario Event Description NRC Scenario 3 B&W Unit EOP Critical Task Description Document, 47-1229003-04:

CT Minimize SCM - HPI must be throttled to minimize SCM while maintaining margin> 30°F this minimizes primary to secondary leakage and reduces dose on the secondary side of the plant as well as minimizing release to the public. If HPI is allowed to raise OTSG pressure above 1000 psig after OTSG is full, a liquid RCS release to atmosphere would occur. Task failure would be to not throttle and challenge this.

Safety Significance: Except when RCP NPSH limits are applicable and are more restrictive, RCS pressure should be maintained close to, but above, the minimum SCM to minimize RCS-SG ~P. The reason for minimizing RCS-SG ~P is to reduce the leak flowrate from primary to secondary to as low as possible. Therefore, this procedure (minimizing SCM) is desirable whenever possible during SGTR mitigation.

Reducing the leak flowrate from the RCS to the secondary side of a SG reduces RCS losses and when accomplished with an impaired steam system (e.g., weeping MSSV and MSL leak) should reduce integrated radiation releases from the impaired system. If the level of the leaking SG can be maintained within normal operating limits, then the SG will remain available for continued use during the cooldown, thus enhancing the transient mitigation capability of the plant.

Cues:

1. SCM monitor

2. SPDS displays and associated alarms

3. P-T display and associated alarms Performance Indicators:

1. Operation of MU/HPI pump and valve controls

2. Operation of normal or auxiliary spray valve controls Feedback:

1. SCM meter and/or plant SPDS and/or P-T display

2. RCS pressure and temperature

3. MU/HPI pump and valve status indications

4. Normal and auxiliary spray valve status indications

Scenario Event Description NRC Scenario 3 B&W Unit EOP Critical Task Description Document, 47-1229003-04:

CT Reduce Steaming/Isolate Affected SGs (includes use of SG drains) - Steam affected SGs to maintain level < [overfill setpoint]. If steaming alone cannot prevent SG fill, then use SG drains (if available) to maintain SG level below [overfill setpoint]. Isolate SG(s) if steaming and draining cannot prevent overfill and maintain RCS and isolated SG pressures < 1000 PSIG by use of [primary and secondary relief paths].

Safety Significance: The more probable tube rupture scenario is a tube leak in one SG with both SGs available. The preferred mitigation strategy is therefore isolation of the affected SG following the initial cooldown and depressurization to <1000 PSIG. This limits the radiological consequences of the event, but does require cooldown to DHRS operation using one SG.

Both SGs are always used in the initial cooldown and depressurization to < 1000 PSIG.

Prevention of MSSV lift on the affected SG(s) is integral to the goal of minimizing off-site release, and assurance requires RCS temperatures at or below 500°F in order to maintain SCM when RCS pressure is < 1000 PSIG. Once this initial cooldown and RCS depressurization to

<1000 PSIG is completed, then SG isolation can be considered.

There are limitations on continued steaming of a SG with a SGTR. These limitations consider the overriding concerns of SGTR transients that dictate the isolation of the SG(s) and initiation of HPI cooling, if necessary. These limits are based on integrated radiation dose reaching predetermined values and SG filling due to tube leakage despite steaming to achieve maximum allowable cooldown rate.

SGs isolated due to SG fill criteria pose concerns related to liquid passing through MSSVs.

MSSVs should be prevented from passing liquid, since their failure to reseat becomes more probable. For this reason, RCS and SG pressures are maintained <1000 PSIG by use of

[primary and secondary relief paths]. These relief paths may include such things as letdown, PZR vents, HPVs, the PORV, TBVs and ADVs.

Cues:

1. Rising OTSG level

2. Rad Monitor Alarms

3. Lowering Pressurizer level

4. Lowering RCS Pressure

5. Automatic initiation of HPI Performance Indicators:

1. Operation of TBV/ ADV controls Feedback:

1. SG(s) level and pressure

2. RCS pressure

3. MFW/EFW flow

4. MFW/EFW pump and valve status indication

5. TBV/ADV status indication

Appendix D Operator Action Form ES-D-2

_ _ _ _ _ Page of 32 !I Op Test No.: --.;...

Scenario # 3 Event # 9 Event

Description:

Inadvertent Manual ESAS Actuation Time i Position I Applicant's Actions or Behavior I SOOnt OPERATOR: When directed by the Lead Examiner INITIATE EVENT 1.

Indications Available: 'B' Train ESAS Actuation indications on PCR and CR, MU-P*

1C running, HPI flow to the RCS indicated, RB Emergency Cooling in operation, MAP alarms.

. Diagnoses the Inadvertent ES using RCS pressure and RS Crew

~ pressure indications.

entry into OP*TM-AOP-046, i OP-TM-AOP-046. Inadvertent ESAS IMAs

. THROTTLE MU-V-16s with HPI flow to minimize and maintain URO

! MU PUMP FLOW> 115 gpm.

OP-TM-AOP-046, Inadvertent ESAS, Followup Actions ANNOUNCE entry into OP-TM-AOP-046, "Inadvertent ESAS ARO Actuation" over the plant page and radio r-------~------~

1MT ICCW flow < 550 gpm (lC5-FI) and SI flow < 22 gpm (MU42-FI1), then perform the following:

N/A

1. ENSURE the reactor is tripped.

2. ENSURE all RCPs are tripped.

Scenario Event Description NRC Scenario 3 Industry Experience:

TMI Reactor Trip (11/2/06) Main Steam Safety Valves remained open longer than expected.

(lR 552591)

Indian Point 2 (2/15/00) - Steam Generator Tube Failure (380 litres per minute)

Palo Verde 2 (3/14/93) - Steam Generator Tube Leak ranged between 11 and 39 litres per day, suddenly turned to 900 litres per minute tube rupture.

PRA

Steam Generator Tube Rupture (Initiating Event)

Scenario Event Description NRC Scenario 3 ent Description Procedure Support Initial Set-up. 100% Power, MOL EF-P-1 Tagged OOS due to bearing replacement 1 Inadvertent ES Actuation OP-TM-AOP-046, Inadvertent ES Actuation T.S. 3.3.2, 3.5.1.1,3.5.1.3, and Table 3.5-1 2 . Tc Instrument Fails High, OP-TM-AOP-070, Primary to Secondary Heat i SASS fails to actuate Transfer Upset OP-TM-621-471, ICS Manual Control 3 i "B" OTSG Tube Leak OP-TM-EOP-005, OTSG Tube Leakage i T.S. 3.1.6.3 4 Power Reduction 1102-4, Power Operations 5 Loss of ICCW OP-TM-EOP-001, Reactor Trip OP-TM-AOP-031, Loss of ICCW 6 "B" OTSG Tube Rupture OP-TM-EOP-005, OTSG Tube Leakage OP-TM-EOP-010, Guide 8 7 MS-V-3 NB/C Fail Closed OP-TM-421-451, MANUAL CONTROL OF TBVs/ADVs

Scenario Set-up NRC Scenario 3 ACTION COMMENTS / INSTRUCTIONS DESCRIPTION Initialization IC-54 100% HFP ICS full AUTO I Equilibrium XENON i EF-P-1 Tagged DOS EF-P-1 Scenario Support !

I Console Center

Malfunction FW17 Value: Insert EF-P-1 Scenario Support When: Immediately Main Console Robust Barriers applied lAW EF-P-1 Scenario Support Protected Equipment TrackinQ Sheet I Remote FWR78 Value: Manual EF-P-1 Scenario Support I

When: Immediately

Remote FWR79 Value: 0 EF-P-1 Scenario Support When: Immediately Remote FWR80 Value: Manual EF-P-1 Scenario Support When: Immediately I

Remote FWR81 Value: 0 EF-P-1 Scenario Support I I When: Immediately Remote MSR67 Value: 1006 "A" MSSVs setpoint When: Immediately change I/O Override 03A4S01 Value: On Inadvertent ESAS ZDIPB1 RCB ON When: EVENT #1 Actuation Malfunction RC08B Value: 100 Ramp 30 secs Tc Instrument Failure/

When: EVENT #2 SASS Failure

Malfunction IC51 I Value:

When:

Insert EVENT #2 Tc Instrument Failure/

SASS Failure Malfunction TH17B . Value: Severity 0.2 "B" OTSG Tube Leak I When: EVENT #3 Malfunction CC04B Value: Insert . Loss of ICCW When: EVENT #5 Malfunction CC04A Value: Insert Loss of ICCW I When: EVENT #5 I Malfunction TH 16B Value: Severity 5.5 "B" OTSG Tube Rupture When: EVENT #6 I Malfunction MS09A Value: 0 I MS-V-3A Fails closed When: EVENT #6 Malfunction MS09B Value: 0 I MS-V-3B Fails closed When: EVENT #6 Malfunction MS09C Value: 0 ' MS-V-3C Fails closed When: EVENT #6 I/O Overridl9 02A4A29 Value: On TBV/ADV ICS Control ZDIICS12BMCS(4) LO When: Immediately . failure I

I

Scenario Set-up NRC Scenario 3 ACTION COMMENTS / INSTRUCTIONS DESCRIPTION I/O Override 02A4A29 Value: Off TBV/ADV ICS Control

ZDIICS12BMCS(1) When: EVENT #6 failure AUT I/O Override 02A4A29 Value: Off TBV/ADV ICS Control

ZDIICS12BMCS(2) When: EVENT #6 failure

, MAN I I/O Override 02A4A29 Value: Off TBV/ADV ICS Control I I ZLOICS1 ~~BMCS(1) When: EVENT #6 failure RED I

I/O Override 02A4A29 Value: Off TBV/ADV ICS Control ZLOICS 12BMCS(2) When: EVENT #6 failure GRN

Appendix D Operator Action Form ES-D-2 I Op Test No.: _1~_ Scenario # 3 Event # _1"--_ _ _ _ Page 10 of ....;3=2----11 I, Event

Description:

Inadvertent Manual ESAS Actuation Time Position A licant's Actions or Behavior URO ENSURE MU-V-36 is Open.

Q~):t~PLl$bbyn(m af:l~,thfl!{£ya've

"'y.::;',,""",

If seal injection flow was adjusted, then ENSURE seal injection N/A flow - 38 m.

IMT RCP #1 seal inlet temp> 235°F (A0525 to A0528) or L

N/A RCP seal water temp at radial bearing> 225°F, (A0521 to A0524) then SHUTDOWN the affected RCP lAW OP-TM-226

. _--,-_ _ _-+-_15c_1-"-,_1-'-5~2,'___1_"5_=_3_'_,0.;;...;r_154

--C. _ _._ _ _ _ _ _ _ . . .- - - - - - - - l IMT all RCP seal cooling is lost and any RCP #1 seal inlet temperature can not be verified less than 235°F (A0525 to N/A A0528), then INITIATE OP-TM-226-901. "Loss of All RCP Seal Coolin ".

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

1MT all the following conditions exist:

- MU-V-16s with HPI can not be controlled from CR

- Pressurizer level > 100"

- Adequate IC cooling water supply to RCPs N/A available, then perform the following:

1. ENSURE IC-P-1A and IC-P-1B are running.

2. ENSURE all Makeu Pum s are Shutdown.

URO VERIFY MU-V-36 and MU-V-37 are Open.

If MU-V-77A&B are Open, then perform the following:

N/A

ENSURE MU-V-16A is Closed.

ENSURE MU-V-16B is Closed.

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

Event Dl9scription:

1 Scenario # 3 Event #

Inadvertent Manual ESAS Actuation

--.;..____ Page 11 of ...,;3=2--11 Time II Position II Applicant's Actions or Behavior If MU-V-76A&B are Open, then perform the following:

N/A

ENSURE MU-V-16C is Closed.

ENSURE MU-V-16D is Closed.

If all Makeup Pumps are Shutdown, then perform the following:

1. INITIATE AOP-041, "Loss of Seal Injection".

2. When seal injection flow has been established, then N/A CONTINUE.

3. If ICCW System available and both IC pumps are running, then PLACE one Intermediate Closed Pump in Normal-After-Sto IAAT control rods are above desired band, then LOWER URO reactor power to the desired control rod band.

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

If at power, then ENSURE two Secondary River pumps ARO running.

ARO INITIATE an alarm review.

ARO INITIATE OP-TM-211-950, "Restoration of Letdown Flow."

IAAT Makeup Tank level >96", then initiate OP-TM-211-462, N/A "Lowering RCS/MU Volume - Bleed" r-------+--------+------- -------------------~

op-TM-211-950, Restoration of Letdown Flow

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

Scenario # 3 Event # Page 12 of 32

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

Description:

Inadvertent Manual ESAS Actuation

'I Time II Position I Applicant's Actions or Behavior Limitation To prevent letdown cooler leakage caused by thermal stress, the rate of change of letdown flow should be limited to 2.5 GPM/Min. If letdown flow indication is not available, then ARO maximum open position of MU-V-5 is 50% or MU-V-98 % turn .

Open valve from closed to the maximum open position gradually over at least a 20 minute period.

t= ARO Prerequisites VERIFY ICCW flow> 550 GPM.

VERIFY the following valves are Open:

-IC-V-2 ARO

-IC-V-3

-IC-V-4 VERIFY any of the following:

- ESAS defeated.

URO

- ESAS did not actuate.

- AOP-046 was entered.

URO VERIFY ICCW cooler outlet temperature < 100°F.

VERIFY all CRD stator temperatures < 160°F or reactor is URO shutdown.

OP-TM-211-950, "Restoration of Letdown Flow." Section 4.5

, ENSURE the following valves are Closed:

- MU-V-3 ARO

-- MU-V-4

- MU-V-5 or MU-V-97A (AB 281: MU Valve Alley)

ENSURE the following are Open:

ARO - MU-V-1A

-MU-V-1B

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

Scenario # 3 Event # ....:.._ _ _ _ Page 13 of ...,;3;;,;;2--11 Event Dt:lscription: Inadvertent Manual ESAS Actuation Time II Position Applicant's Actions or Behavior ren'l0tely. *tben;~iACEMH~V~5at'10%

!int~p ~~Os .1~~Q(:Iende£fland (COl

~'- '.':," ,<- : : " ",:'::,><<:-':;';;:---'-""',""" ,.":'::'::">':'.

,n.~Y pr~I~~~~;O~~'El~~~~Q~~dn

. . **Gpenllgnt~JiH;;I,1:I:lre*iyalVe

'7;f'A"" -','>>'>>Y

'/'J;",,~ _./ ~s ':

None CONTROL ICCW temperature lAW OP-TM-541-461.

r-----~~------+- ----------~

None MAINTAIN letdown temperature <125°F.

~

~V:f:~t <2ig gpm/mint(j~jf$dfJOV:f:asfqJtpws:

~*~~HP.the . . a,llfl~he. OPtl~ttf~mand OP.TM*AOP*046, Inadvertent ESAS CRS REVIEW Tech Specs for ES operability impact.

Reviews Tech Spec 3.5.1.1,3.5.1.3 and Table 3.5-1 For ESAS CRS Operability requirements.

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

Scenario # 3 Event # Page 14 of 32

~-------- ~~I Event DE~scription: Inadvertent Manual ESAS Actuation Time =::JI Positionll Applicant's Actions or Behavior NOTE TO EXAMINER:

Table :3.5-1 (Instruments Operating Conditions)

C. En!~ineered Safety Features Functional Unit L Min O~erable Channels L Min Degree of Redundanc~

Manual Pushbutton/ 2 / N/A (g) The Operability requirement is for the manual actuation switch for the specified feature on each train to be OPERABLE.

1. If the manual actuation switch on one train is inoperable, restore the switch to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

NOTE TO EXAMINER: After the Tech Spec call is made and MU-V-5 is ~20%

DEMAND go to Event 2.

Appendix D Operator Action Form ES-D-2

.....;2~_ _ _ _ of .....;3=2~1 Op Test No.: ---:..... Scenario # 3 Event # Page 15 Event

Description:

Tc Instrument Fails High, SASS Fails to Actuate TimE~ II Position ~ Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Lead Examiner INITIATE EVENT 2.

Indications Available: Tc indication offscale high, Digital Tave indicator rising, multiple MAP alarms, Control Rod movement inward.

I I Examiner Note: The crew may decide to perform OP-TM-MAP-H0302. Those steps can be found on page 32 of this Scenario.

Crew Diagnoses the Tc Instrument failure.

Directs entry into OP-TM-AOP-070, PRIMARY TO CRS SECONDARY HEAT TRANSFER UPSET OP-TM-AOP-070, PRIMARY TO SECONDARY HEAT TRANSFER UPSET Ensure Diamond Station .in .MAN by pressing the "Auto/Manual" pushbutton (CC) on the diamondpanef and observing the URO Manual

.. light

. lit and the auto light not lit, and INSERT control

. rods as necessary to reduce power below Reactor power limit ari(j'for gross balance with total FW flow. .

ENSURE~both.SG A & BFW DEMAND in HAND by pressing the white "Hand" pushbutton (CC) , verifying thatthe white ARO "Hand" light is lit and the red "Auto" light goes out and ADJUST FW. Flow to stabilize Tavg at the current ReS temperature..

Verify Turbine Header Pressure is between 835 and 935 psig.

URO (MAP H-2-3 is not in alarm)

URO VERIFY RCS pressure is lowering or less than 2205 psig.

IAAT RPS setpoint is reached or Reactor trips, then GO TO N/A EOP-001.

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 3 Event # ..,:2=--____ Page 16 of ...,;3_2_......,

Event

Description:

Tc Instrument Fails High. SASS Fails to Actuate Time I Position II Applicant's Actions or Behavior IAAT MU Tank Level is approaching 55", then perform the following:

1. INITIATE OP-TM-EOP-01 0 Guide 9, Section A, "MU N/A Tank Level Control".

_ _ 2. If control rod index approaching 300%, then LOWER reactor ower to achieve desired control rod band.

ARO VERIFY Main Turbine is RESET.

ASSIGN manual control responsibilities and control bands:

- INSERT or WITHDRAW rods to maintain Reactor power within 1% of current power level.

- ADJUST FW Flow to maintain Tavg within 2°F of current temperature.

CRS

- MAINTAIN Turbine Hdr Pressure within 10 psig of current pressure.

-If Main Generator Breakers are CLOSED, then ADJUST Turbine Load Set.

-If Main Generator Breakers are OPEN, then ADJUST TBVs.

If Reactor power has been reduced> 3%, then INITIATE 1102 URO 4, "Power 0 erations," actions for ower reduction.

.wt;>,.-SG}~~,ctor .d bY.,~r~~$ingt~;whit~i"~nd".'.

. ~~'tl~""ttQ...t~), . . . . . . ........thatttieWhite\i;H~.pd~Hgt:lti~ liland '.

- lfl~r~d*"A;~/tight.goe&~

'taVO';Qtthllt~rrent RCS tem

,;\". "-::<---,~<:, " <ff~'*;',.

.wbit!.:*l1~~

l'Hc:J,rid" light is .Iitan~

.fW Flow to~li:ze

Appendix D Operator Action Form ES-D-2 Op Test No.: --=-_ Scenario # 3 Event # ....;2=--____ Page 17 of ...,;3;.;;;;,2__

1 Event

Description:

Tc Instrument Fails High, SASS Fails to Actuate A licant's Actions or Behavior

! VERIFY both of the following:

- Operating MFW Pumps are controlling FW Valve dP ARO greater than 30 psid.

I - Reactor power is greater than 75%.

If Main Turbine is in ICS HAND control, then PERFORM the following:

_ _ 1. MAINTAIN Tavg stable using FW control and slowly ARO ADJUST Main Turbine to control header pressure between 865 and 905 psig.

- - 2. INITIATE OP-TM-301-471, "Manual Control of Main Turbine."

MAINTAIN RCS pressure between 2105 and 2205 psig and ARO slowly ADJUST feedwater flow to control RCS Tavg 578 to 580 of.

MAINTAIN RCS Tavg 578 to 580°F and slowly ADJUST loop ARO I feedwater flows to control RCS ATc < 5° F.

If FW valves are in HAND, then INITIATE OP-TM-421-451 ARO (452), "Manual Control of Feed Flow to A (B) OTSG."

If TBVs are in Hand, then INITIATE OP-TM-411-451, "Manual ARO Control of TBVs/ADVs."

I NOTE TO EXAMINER: Ensure Pressurizer level is >160 inches prior to moving on to Event 3.

I I

[ NOTE TO EXAMINER: When the alternate Tc Instrument has been selected, ICS Is in manual control, and the plant is stable, GO TO Event 3.

Appendix D Operator Action Form ES-D-2 ScenaJio #

3 Event # ...;3:::..,...,:.4_ _ _ _ Page 18 of ...,;3=2......."

30 gpm "8" OTSG Tube Leak, Power Reduction Position A licant's Actions or Behavior I BOOTH OPERATOR: When directed by the Lead Examiner and if Pressurizer level is> 160 inches, INITIATE EVENT 3.

I Indications Available: MAP Annunciator C-1-1 actuates, RM-A-5/15/RM-G-27 counts rise.

Crew Diagnoses the "B" OTSG Tube leak.

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

CRS Announces entry into OP-TM-EOP-005, OTSG Tube leakage OP-TM-EOP-005, OTSG Tube leakage CRS NOTIFY "Shift Dose Assessor" to begin offsite dose

~ __~______-4~a~s,~se~s~s~m~e~n=t.__________________~ ____________~

ARO ANNOUNCE OTSG TUBE LEAK.

INFO INITIATE Guide 9, "RCS Inventory Control.

OP-TM-EOP-010, GUIDE 9, RCS Inventory Control URO VERIFY MU pump is operating.

URO VERIFY MU-V-5 is Closed.

URO ENSURE MU-V-17 is Open.

URO VERIFY PZR level is being restored.

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 3 Event # _3;;.1.*.. .;.4_ _ _ _ Page 19 of _3_2_1

~-

Event

Description:

30 gpm "8" OTSG Tube Leak, Power Reduction Position A licant's Actions or Behavior OP-TM-EOP-005, OTSG Tube leakage INITIATE the following procedures to start both Auxiliary Boilers:

ARO

- OP-TM-414-401, "Starting AS-B-1A".

- OP-TM-41 "Starti AS-B-1 B".

CRS VERIFY the reactor is critical.

IAAT pressurizer level < 150 inches and reactor power> 25%,

then perform the following:

N/A 1. INITIATE HPI.

2. TRIP the reactor.

3. GO TO EOP-001 IAAT the turbine trips, and reactor power> 15%, then perform the following:

N/A

1. TRIP the reactor,

2. GO TO EOP-001 VERIFY SG/REACTOR DEMAND is in Auto.

1. ENSURE ULD is in HAND.

2. SET ULD LOAD RATE OF CHANGE as directed by CRS.

URO 3. SET ULD Target Load Demand to 0%.

RNO: REDUCE power at a rate within manual control limitations lAW OP-TM-621-471 "ICS Manual

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

ScenaJio # 3 Event # ....;3:;.:.*...;.4_ _ _ _ Page 20 of ...B~I Event

Description:

30 gpm "8" OTSG Tube Leak. Power Reduction licant's Actions or Behavior OP-TM-621-471 "Ies Manual Operations", Step 4.2.4 nn~IIIAr or control rods within f'hgnnA is~ll}g conducted .tAW 1102~4;

'lRi~fii~QR De~ as.follows=

OP-TM-EOP-005, OTSG Tube leakage REQUEST SM to Evaluate Emergency Action Levels CRS NOTIFY Power Team NOTIFYTSO NOTIFY NDO.

CRS IDENTIFY the affected OTSG:

1MT all of the following conditions exist:

- The affected OTSG is identified

- EF-P-1 is not running N/A

- Either Motor Driven EFW Pump is Operable then Place the Handwheel, of the affected MS-V-13, in the CLOSED nl"":,,,1"'l"\n

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

Scenario # 3 Event # _3;;.i"....;,4_ _ _ _ Page ll. of ....;;3;,;;.2__

1 Event

Description:

30 gpm "8" OTSG Tube Leak, Power Reduction A licant's Actions or Behavior NOTE TO EXAMINER:

Specification 3.1.6.2:

! If unidentified reactor coolant leakage (excluding normal evaporative losses) exceeds one gpm or if any reactor coolant leakage is evaluated as unsafe, the reactor shall be placed in hot shutdown within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of detection.

I I NOTE TO EXAMINER: After the Tech Spec call is made and sufficient power reduction has occurred, GO TO Event 5.

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

~-

Scenario #

-3 Event # _5;......_ _ _ _ Page 22 of .....;3=2--1i Event DI~scription: Loss of ICCW, Reactor Trip

Time I Position II Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Lead Examiner INITIATE EVENT 5.

Indications Available: MAP Annunciators alarm, ICCW Pump off Indications, rising temperatures on ICCW-cooled components.

Crew Diagnoses loss of ICCW Announces entry into OP-TM-AOP-032, LOSS OF INTERMEDIATE COOLING, based on approaching the following entry conditions:

The OTSGs are being used for RCS heat removal, and at least one secondary river or nuclear river pump is available, and any CRS of the following:

-IC cooler outlet temperature (IC6-TI) approaching 120°F

- ICCW CRD flow (IC10-FI) < 100 GPM and any CRD stator I temperature> 180 of

- No ICCW flow in RS and reactor is shutdown

- IC surge tank level < 8 in. (IC-Ll-802/ 803) and lowering OP-TM-AOP-032, LOSS OF INTERMEDIATE COOLING ANNOUNCE the following over the plant page and radio: I ARO "Entering AOP-032, Loss of Intermediate Component Cooling.

Tri.Qping the reactor." i CRS INITIATE EOP-001, "Reactor Trip".

NOTE TO EXAMINER: The CRS may continue with OP-TM-AOP-032, LOSS OF INTERMEDIATE CLOSED COOLING simultaneous to the actions listed below. The AOP-032 steps continue on page 22.

OP-TM.EOP-001, "Reactor Trip" .

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 3 Event # 5 Page 23 of 32

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

Description:

Loss of ICCW, Reactor Trip Position A licant's Actions or Behavior URO VERIFY REACTOR SHUTDOWN. I i i i ......***.*........ > d~":

r:.**JJFl6~ ... **~n$*t~i>mpt;l~bbttttoniQk)~ i.

.* iii************ ..** I i

I URO ~RIFY the turbine stop valves are Closed.

Performs a symptom check and announces OTSG tube leak, B OTSG based on:

ARO A valid unexpected alarm from offgas or steam line radiation monitors (RM-A-5, RM-A-15, RM-G-26, RM-G-27)

IAAT a symptom exists, then GO TO the symptom response procedure using the following priority:

1. EOP-002, "Loss of 25 OF Subcooling Margin",

N/A

2. EOP-003, "Excessive Primary to Secondary Heat Transfer",

3. EOP-004, "Lack of Primary to Secondary Heat Transfer",

4. EOP-005, "OTSG Tube Leakage".

Announces re-entry into OP-TM-EOP-005, OTSG Tube CRS Leakage.

NOTE TO EXAMINER: The CRS should re-perform the steps of OP-TM-EOP-005 that were completed previously. The crew mayor may not have made it through step 3.12. Those steps are listed in the previous event.

OP-TM-EOP-005, OTSG Tube Leakage.

CRS Re-performs steps 3.1-3.5, 3.10-3.12 ARO INITIATE Attachment 2, "Radiological Controls".

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 3 Event # _5~_ _ _ _ Page 24 of ...,;3;.;;;.2__1 Event

Description:

Loss of ICCW, Reactor Trip A licanfs Actions or Behavior IAAT Aux. Steam is available, then perform the following:

1. OPEN AS-V-8 (TB 355' south of 6th stage drain collection tank).

ARO 2. CLOSE GS-V-4

3. Transfer operating FW pumps to Auxiliary Steam as follows:

OPEN AS-V-5A (TB 322: 7' W of FW-P-1A 2' up).

- OPEN AS-V-5B (TB 322: 7' W of FW-P-1 B 2' up).

I ARO ENSURE announcement of reactor trip.

F ARO DISPATCH an Operator to check MSSV status.

ARO ENSURE performance of an alarm review.

OP-TM-AOP-032, LOSS OF INTERMEDIATE COOLING IAAT either condition exists:

- IC surge tank level < 8 in. and lowering

- No ICCW flow in RB N/A then PLACE ICCW pumps in PTL:

- IC-P-1A IC-P-1B WAAT all the following conditions exist:

- An IC pump is available

- ES/UV lockouts are Reset

-*IC surge tank level> 8 in.

- RCP#1 seal inlet temp < 235 OF or IC-V-79NB/C/D are N/A Closed then START either ICCW pump:

- IC-P-1A IC-P-1 B URO ENSURE MU-V-3 is Closed.

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

Scenario # 3 Event # 5

~________

Page 25 of 32

~~i Event

Description:

Loss of ICCW, Reactor Trip Time, Position A licant's Actions or Behavior URO VERIFY Seal injection> 22 gpm. !

i WMT IC flow in RS > 550 GPM, and IC cooler outlet N/A ! temperature < 110°F, then GO TO Section 4.0, "Return To I

i Normal".

ARO PLACE WDL-P-8 (RCDT pump) in PTL.

I I NOTE TO EXAMINER: After Reactor is tripped and EOP-OOS has been re entered, GO TO Event 6.

Appendix D Operator Action Form ES-D-2 II Op Test No.: -.:.. Scenario # 3 Event # _6;;.:.,..;.7_ _ _ _ Page 26 of .....;3=2---'1 Event

Description:

800 gpm "8" OTSG Tube Rupture, "8" T8V/ADV ICS Control fails Time II Position II Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Lead Examiner INITIATE EVENT 6. i Indications Available: Pressurizer level lowering, ReS Pressure lowering, "8" OTSG level rising I I NOTE TO EXAMINER: The CRS should continue in OP-TM-EOP-oOS. This event picks up at step 3.29. The crew mayor may not have made it through step 3.28. Those steps are listed in the previous events Crew Diagnoses the "8" OTSG Tube Rupture.

- - >iogiihe9P$n t is lit and valve r~~r *. Levelis,.betng,~~$t()f~d.*. .;.

" ': "~;~<~,;:~,~ -, , -" y>~ 'v -" ,. '~

.*. hbuttQ~{ecj;V$rifVirtg Ii htnotlib . ;..

NOTE TO EXAMINER: The URO may press 4# ES manual pushbuttons due to the inadvertent 1600# "8" ES manual pushbuttons being faulted. The result is the same, 4# initiates 1600# ES.

Appendix D Operator Action Form ES-D-2

! Op Test No.:

Scenario # 3 Event # 6, 7

~..;...----

Page 27 of 32 I: Event

Description:

800 gpm "B" OTSG Tube Rupture, "8" TBV/ADV ICS Control fails Time Position A licant's Actions or 8ehavior NOTE TO EXAMINER: The ARO will have to control ADV's on the backup loader (8 side only).

1MT OTSG isolation criteria may be challenged prior to reducing RCS pressure < 1000 psig, then perform the following:

1. INITIATE RCS cooldown to 500°F at a rate within RCS N/A inventory control capability and < 240 of/hr.

__.2. ENSURE RC-V-2 is Open.

3. CYCLE the PORV to reduce SCM to approximately 30°F.

tfiIQ!li~~.*e}(ist:

. re<1150;psig'te

Appendix D Operator Action Op Test No.: Scenario # 3 Event # ....;6::.:"..;..7_ _ _ _ Page 28 of ...,;3;.,;;;2_11

~-

Event

Description:

800 9pm "8" OTSG Tube Rupture, "8" T8V/ADV ICS Control fails Ti A licant's Actions or 8ehavior INFO MINIMIZE SCM lAW Guide 8, "RCS Pressure Control".

OP-TM-EOP-010 Guide 8, "RCS Pressure Control",

IAAT REACTOR is SHUTDOWN and SCM> 25 of, and pressurizer has a steam bubble, then CONTROL RCS pressure as follows:

1. MAINTAIN RCS pressure within the limits of Figure 1 and 1A

2. If it is required to MINIMIZE SCM, then LOWER RCS pressure lAW Section B. Steps should be performed sequentially until RCS Press is lowering at the desired rate.

Pressure may be lowered until one of the following limits is INFO approached:

- MAINTAIN SCM> 30°F,

-If an RCP is ON, then MAINTAIN RCS pressure above RCP NPSH limits (1102-11 Fig 1 and 1A, or OP-TM 226-000),

-If a\l RCPs are OFF and OTSG TUBE LEAKAGE does not exist, then MAINTAIN pressure above "Head i bubble" limit (Fig 1 and 1A). j INFO . ENSURE HPI/LPI is throttled per Rule 2 I OP-TM-EOP-010 RULE 2, HPI THROTTLING I

i URO VERIFY MU PUMP FLOW:so 515 gpm/pump.

URO VERIFY SCM < 250°F.

I URO VERIFY an RCP is ON.

When any of the following conditions exist:

- SCM> 25°F and HPI COOLING is not required,

- SCM> 25°F and HPI COOLING is required and incore temperature is lowering, INFO

- Incore temperature < 25°F superheat and BWST level < 15 ft and LPI > 1250 gpm in each line, i then HPI may be THROTTLED lAW OP-TM-211-901, I I "Emergency Injection (HPI/LPI)".

Appendix D Operator Action Form ES-D-2 Op Test No.: ......:-_ Scenario # 3 Event # ...,;6.,.;..7_ _ _ Page 29 of ..,;;3:.:;,2--11 Event

Description:

800 gpm "B" OTSG Tube Rupture, "B" TBV/ADV ICS Control fails I Time I Position II Applicant's Actions or Behavior Op*TM*EOP*010 RULE 2, HPI THROTTLING IAAT all of the following exist:

RCS Press is being controlled

SCM> 25°F

CRS concurrence is obtained URO then perform the following:

If RCS pressure is < 1750 psig then BYPASS 1600 psig

-ESAS If RCS pressure is < 900 psig then BYPASS 500 psig

-ESAS

~,\\, ::'::'>, : " ';

,'77 ".l,~.+¥c::n**l~at't.Re~J$ON

"~i.'V~$"JS;Q~n;.*,,~."**

~ " , " , ,'/ ':'" ,: :, .,' '--:::~~-, -----:--~-::,'-,'-, -'"'>::>; '< '. "," : ,,' ""

....... e~l'fiROTTLEO~~N"AC;;Vl ,b),plaelwgthe Sp_~~l_~,~..??

aut<r/rJJ~ryy~ISWitdl tce) in the manual position and pr$ssing

- .*....**th.~~a~M'lI"e open pushbutton, verifying* the valve *openligtlt

.it:;.lit~(j.tl'l~valve closed light is not li~. . .

OP*TM*EOP*005, OTSG Tube Leakage.

IAAT OTSG level> 85% Operate Range, then perform the

following:

_ 1 . When RCS pressure < 1000 psig, then INITIATE N/A Attachment 1A or 1B to isolate the OTSG.

_ 2. If both OTSGs are being isolated, then GO TO EOP-009

_ 3. When affected OTSG's TBVs and ADVs are closed, then PERFORM Guide 12 "ReS Stabilization".

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 6,7 Page 30 of 32 ,I Event Dl9scription: 800 gpm "B" OTSG Tube Rupture, "B" TBV/ADV ICS Control fails Time Position il Applicant's Actions or Behavior

\\

I \\,

1MT EF-P-2A or EF-P-2B are running. then perform th~ ,

following:

1. PLACE both trains of each EFW actuation in "DEFEATil.

ARO (Eight switches)

2. CLOSE Main Steam supply valves to EF-P-1:

- MS-V-13A i - MS-V-13B i NOTE TO EXAMINER: The scenario can be terminated when HPI has been throttled, SCM has been minimized, and the "8" OTSG Level has been controlled.

TERMINATE the scenario.

Follow-*up question highest event entered during scenario?

Answer: FS1 due to 1) Primary to Secondary leakage>10 gpm with an unisolable steam release from the affected OTSG to the environment and a Steam Generator Tube Rupture requiring ESAS actuation.

Appendix D Operator Action Form ES-D-2 Op Test No.: ....;...._ Scenario # 3 Event # 2 (AI!. Actions) Page 31 of ...,;3;;,:2---l Event Dt3SCription: Tc Instrument Fails High, SASS Fails to Actuate (Alt. Actions)

I Time II Position I Applicant's Actions or Behavior Examiner Note: The crew may decide to perform OP-TM-MAP-H0302 for Event 2.

OP-TM-MAP-H0302 If plant control is not stable or Validity of selected instrument is unknown or suspect, then PLACE affected stations in Hand INFO lAW associated manual operations procedures to balance plant arameters.

OP-TM-621-471, ICS Manual Control

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

URO ENSURE ULD in HAND.

If SG/REACTOR Station is being placed in HAND to support a L1RO planned activity, then VERIFY reactor power is less than 2558 MWth 99.6%.

[)lit~Ji.ing

~..~

.out.

L1RO ENSURE control rod position does not change.

URO

VERIFY alarm H-2-1 "ICS in Track" In.

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

Scenario # 3 Event # 2 (All. Actions) Page 32 of ~~

Event D!:lscription: Tc Instrument Fails High, SASS Fails to Actuate (Alt. Actions)

Position licant's Actions or Behavior I

op-TM-MAP-H0302 URO DETERMINE which input is bad.

~------~-------r-ENSURE valid instrument selected lAW OP-TM-621-451, INFO Selecting Alternate Instrument Inputs to ICS.

OP-TM-621-451, Selecting Alternate Instrument Inputs to ICS ENSURE ULD in HAND lAW OP-TM-621-473, "ULD Manual URO Control".

COMPARE alternate inputs (using Attachment 7.3 of OP-TM 621-000, Integrated Control System or table in OP-TM-MAP H0302 as necessary) and VERIFY both of the following:

- Difference between affected and alternate channels are URO less than "SASS Setpoint L\s" as listed in OP-TM-MAP*

H0302 Table.

-- Selecting alternate instrument will not affect ICS control or plant stability.

Appendix D Scenario Outline Form ES-D-1 Facility: Three Mile Island Scenario No.: 4 Op Test No.: NRC Examiners: Operators:

Initial Conditions:

(Temporary IC-55)

5% Power, MOL I

EF-P-1 OOS for bearing replacement I Continue with Power escalation .1 Critical Tasks:

Control HPI (CT-5)

_.

Isolate Overcooling SGs (CT-17)

Event No. Malf. No. Event Type* Event Description 1 N/A N CRS Raise Reactor Power from 5% to 10%

RURO 2 IC37A CCRS Invalid "Au OTSG Low Level (TS), "Au EFW actuation, entry into OP-TM-424-90 1 IC4iA CARO (ARO: defeats invalid signal, secures EF-P-2A)

TSCRS 3 IA07 CCRS Loss of Instrument Air, entry into OP-TM-AOP-028 IAOiC CARO (ARO: Starts IA-P-1A or B) 4 MS02B CCRS Steam Leak into the Reactor Building, entry into OP-TM-AOP-051 I CURO RR-P-1 B Fails to start (TS)

CARO (URO: Initiate Plant Shutdown, ARO: Initiate RB Emergency Cooling)

TSCRS 5 THOa CCRS PORV fails open, entry into OP-TM-MAP-G0106 CURO (URO: Closes PORV Block Valve) 6 RD03C CCRS Uncontrolled outward rod motion, group 7, entry into OP-TM-AOP 064 CURO (URO: Selects Sequence Override) 7 MS02B MCRS Steam Rupture in Reactor Building, entry into OP-TM-EOP-001, Excessive Heat Transfer, isolate "8" OTSG, entry into OP-TM MURO EOP-003, OP-TM-EOP-Oi0, Rule 3 MARO 8 MUR67 CCRS MU-V-36 breaker opens, Valve fails closed. Alternative minimum flow path for Makeup Pump established.

MUR94 CURO

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

-1

Scenario Event Description NRC Scenario 4 Three Mile Island NRC Scenario #4 When the crew has accepted the watch, the Lead Examiner can cue the raising power from 5%

to 10%. When the Lead Examiner has seen sufficient reactivity manipulation, the scenario can continue.

When sufficient reactivity manipulation has occurred, the Lead Examiner can cue the Inadvertent low level signal on the "An OTSG with EFWactuation. The ARO will respond per OP-TM-424-901, and defeat the HSPS signal, secure the running EFW pump (EF-P-2A), and re-enable HSPS. The CRS will review T.S. and declare Table 3.5-1.D.(a). When the T.S. call is made and HSPS is re-enabled, the scenario can continue.

When the T.S. call is made and HSPS is re-enabled, the Lead Examiner can cue the Loss of Instrument Air. The operators will diagnose the Loss of Instrument Air based on IA-P-4 trip and lowering IA pressure. The CRS will enter OP-TM-AOP-028, LOSS OF INSTRUMENT air. ARO will start IA-P-1 A or IA-P-1 B from the Control Room prior to Instrument Air reaching 60psig (setpoint below which a manual Reactor Trip must occur).

When OP*TM-AOP-028 has been performed and IA-P-1 A or B is running, the Lead Examiner can cue the Steam Leak in the Reactor Building. The CRS will enter OP-TM-AOP-051, Steam Leak. The URO will commence a reactor shutdown. The ARO will perform OP-TM-861-901, RB Emergency Cooling. RR-P-1 B fails to start and only 1 train of cooling will be in service. The CRS will review T.S. for failure of RR-P-1 B to start and declare 3.3.1.3.a. Once the Tech Spec has been made and RB Emergency Cooling is in service ("A" Train), the scenario can continue.

When RB Emergency Cooling ("An Train) is in service and the Tech Spec call is made, the Lead Examiner can cue the PORV failing open. The crew will diagnose a faulted signal (comparison with actual plant pressure) and the URO will close the PORV block valve lAW OP-TM-MAP G0106. Once the PORV Block Valve is closed, the scenario can continue.

When the PORV Block Valve is closed, the Lead Examiner can cue the Uncontrolled Rod Motion on Group 7. The crew will enter OP-TM-AOP-064. The LlRO will perform the IMA's and rod motion will not stop, leading to a manual reactor trip and entry into OP-TM-EOP-001.

When OP-TM-AOP-064 and OP-TM-EOP-001 IMA's have been completed, the Lead Examiner can cue the Steam Rupture in the Reactor Building. A symptom check performed by the ARO will reveal Excessive Heat Transfer. The CRS will enter OP-TM-EOP-003, Excessive Heat Transfer. lAW OP-TM-EOP-003 IMA's, the ARO will perform Rule 3 and isolate the "B" OTSG (CT-17). Once the "B" OTSG has been isolated, the URO will throttle HPI to avoid raisill{;l pressure to the point of lifting a safety (PORV was blocked in an earlier event) (CT-S).

Additionally, the URO will minimize subcooling margin (Guide 8) and Emergency Borate (Rule 5). The ARO will use the "A" TBV's to commence a cooldown of 100F/hr (Guide 11).

MU-V-36 breaker will trip open and the valve will be failed closed. Upon termination of HPI, the URO will maintain> 40 gpm Makeup flow to avoid damaging a Makeup Pump, by using an alternative method, either throttling HPI valve MU-V-16B or placing MU-V-32 in HAND and adjusting for >40 gpm seal injection flow, either option lAW Rule 2.

The scenario can be terminated when "B" OTSG is isolated, HPI has been throttled, and a cooldown rate is in progress lAW Guide 11.

-2

Scenario Event Description NRC Scenario 4 B&W Unit EOP Critical Task Description Document, 47*1229003-04:

CT Control HPI- MUlHPI flow MUST be THROTTLED to prevent overpressurizing the RCS when SCM exists by keeping the RC pressure below the RV P-T limit. HPI flow must be maintained within acceptable operational bounds. This requires maintaining HPI flow greater than the minimum allowable pump flow rate and less than the pump runout flow rate.

Safety Significance: The only requirement to allow throttling of HPI is the existence of SCM. Throttling means to reduce the HPI flow rate below full flow rate. In general, HPI flow may be throttled anytime SCM exists as indicated by the incore TICs. HPI flow must not be throttled when SCM is lost.

If the PORV is not maintained open (Le., allowed to cycle) during HPI cooling, the RC will continue to heat up as the PORV is opened and closed either automatically or manually to control pressure. This heatup will continue until SCM is lost or HPI mass flow starts removing more energy than is being added to the RC. Full HPI flow must always be maintained when SCM does not exist. In addition, while the PORV is being cycled, full HPI flow must be maintained until the core outlet temperature is decreasing.

This criteria ensures that full HPI flow will be maintained if the PORV is permitted to cycle; therefore, throttling the HPI flow cannot be permitted until the HPI flow is sufficient to remove decay heat.

MU/HPI flow MUST be THROTTLED to prevent overpressurizing the RCS when SCM exists by keeping the RC pressure below the RV P-T limit. HPI flow must be maintained within acceptable operational bounds. This requires maintaining HPI flow greater than the minimum allowable pump flow rate and less than the pump runout flow rate Cues:

1. SPDS displays and associated alarms

2. SCM monitor and associated alarms

3. P-T display and associated alarms

4. RCS pressure and temperature (incore TICs)

Performance Indicators:

1. Operation of HPI pump controls

2. Operation of HPI valve controls Fel!dback:

1. HPI pump status indications

2. HPI valve status indications

3. HPI Flow

4. RCS pressure and temperature (incore TICs)

-3

Scenario Event Description NRC Scenario 4 S&W Unit EOP Critical Task Description Document, 47-1229003-04:

CT*17,* Isolate Overcooling SGs - This is a critical task in that continued feeding of an OTSG with a steam break will continue to overcoot the ReS, which could result in emptying the Pressurizer and causing a loss of subcooling margin. This would significantly change the mitigation strategy of the event o Critical task (CT-17) is to isolate the affected OTSG prior to emptying the, pressurizer. Alternately if HPI held pressurizer level, cooldown below ~29°F with HPI on would violate TS. Either condition should be considered grounds for failing critical task.

Safety Significance: If the overcooling SG has been identified then that SG should be isolated, otherwise both SGs should be isolated. Isolating a SG means to stop all FW flow (MFW and AFW) and steam flow (e.g., close TSVs, ADVs, steam supply to FW pumps, MSIVs etc.). FW flow should be maintained to the unaffected SG and cooling stabilized using the unaffected SG.

Isolation of a SG or both SGs should always follow a logical progression of increasingly more drastic attempts to isolate the SG. For example, if the overcooling is not severe it may be possible to close both the TSVs and ADVs as well as the auxiliary steam valves thus isolating the SG. If this does not work, then for those plants which have main steam isolation valves, the main steam isolation valve should then be closed. For severe oVE~rcooling situations, [secondary plant protection system] will likely actuate.

Inappropriate mitigative actions can cause loss of both SGs even if only one SG is faulted; such a situation would cause degradation of the transient mitigation capability of the plant.

Cues:

1. SPDS displays and associated alarms

2. P-T display and associated alarms

3. Rising RS Pressure and Temperature

4. RS Fire/Heat alarms Performance Indicators:

1. Operation of HIPI/MU pump start switches

2. Operation of associated FW pump and valve controls (affected OTSG)

3. Operation of associated steam valve (included TSVs/ADVs) controls (affected OTSG)

4. Operation of MSIV's (affected OTSG)

Feedback:

1. RC temperature and pressure

2. SG level and pressure

3. MSIV status indication

4. MFW/AFW pump and valve status indications

4

Scenario Event Description NRC Scenario 4 Industry Experience:

Rod Control Direction Error (TMI CR-008513201)

AH,-E-1 C Tripped During ES Testing (TMI CR-00778856)

SEI=t 1-05 Hope Creek Steam Leak and scram (10/10/04)

PRA

Secondary Line Breaks (Initiating Event)

PORV RC-RV-2 (Risk Increase Factor)

-5

Scenario Event Description NRC Scenario 4 i

Event I Description Procedure Support Initial Set-up. 5% Power, MOL EF-P-1 Tagged OOS due to bearing replacement 1 Raise Reactor Power from 5% 1102-4 I

to 10%

2 :I,nvalid "A" OTSG Low Level, Ii OP-TM-424-901 IL\" EFW actuation Ii 3 . Loss of Instrument Air OP-TM-AOP-028, Loss of Instrument Air I

OP-TM-PLB-01 06 4 Steam Leak into the RB, RR-P-. OP-TM-AOP-051, Steam Leak i 1B fails to auto-start OP-TM-861-901, RB Emergency Cooling T.S. 3.3.1.3.a 5 PORV fails open OP-TM-MAP-G01 06 6 Uncontrolled outward rod OP-TM-AOP-064, Uncontrolled Rod Motion motion, group 7 T.8. 3.5.2.5.a 7 Steam Rupture in RB, OP-TM-EOP-001, Reactor Trip Excessive Heat Transfer.

OP-TM-EOP-003, Excessive Primary to Secondary

. Heat Transfer I I

i OP-TM-EOP-010, RULE 3 OP-TM-EOP-010, RULE 5 OP-TM-EOP-010, GUIDE 11 r-8 MU-V-36 breaker opens, Valve OP-TM-EOP-010, RULE 2 fails closed. Alternative

minimum flow path for Makeup i Pump established.

- 6

Scenario Set-up NRC Scenario 4 ACTION Il:JiOMMENTS / INSTRUCTIONS [ DESCRIPTION Initialization IC-55 5% HFP ICS full AUTO Equilibrium XENON PPC Point A0602 Value: Delete From Monitor Scenario Support When: Immediately PPC Point A0603 Value: Delete From Monitor Scenario Support When: Immediately PPC Point A0604 Value: Delete From Monitor Scenario Support When: Immediately PPC Point A0605 Value: Delete From Monitor Scenario Support When: Immediately Malfunction PRF-2-8 Value: Off Scenario Support When: Immediately Console Center EF-P-1 Tagged OOS EF-P-1 Scenario Support Protected Equipment Tracking Sheet Malfunction FW17 Value: Insert EF-P-1 Scenario Support When: Immediately Main Console Robust Barriers applied lAW EF-P-1 Scenario Support Protected Equipment Tracking Sheet Remote FWR78 Value: Manual EF-P-1 Scenario Support When: Immediately Remote FWR79 Value: 0 EF-P-1 Scenario Support When: Immediately Remote ANR80 Value: Manual EF-P-1 Scenario Support When: Immediately Remote ANR81 Value: 0 EF-P-1 Scenario Support When: Immediately Remote ANR94 Value: Open Scenario Support When: Immediately Remote IAR01 Value: Off Loss of Instrument Air When: Immediately Scenario Support Remote IAR02 Value: Off Loss of Instrument Air When: Immediately Scenario Support Remote IAR03 Value: Off Loss of Instrument Air When: Immediately Scenario Support Remote IA.R04 Value: Off Loss of Instrument Air When: Immediately Scenario Support I/O Override 03A6S06 Value: Off Scenario Support ZDIRRPIB(2) STR CR When: Immediately RR-P-1 B Control Sw Malfunction IC37A Value: Insert Invalid "A" OTSG Low Level, When: EVENT #2 "An EFW actuation

- 7

Scenario Set-up NRC Scenario 4 ACTION COMMENTS / INSTRUCTIONS DESCRIPTION Malfunction IC41 A Value: Insert Invalid "A" OTSG Low Level, When: EVENT #2 "A" EFW actuation Malfunction IA07 Value: Severity 10, Ramp 30 Loss of Instrument Air When: EVENT #3 Malfunction IA01 C IA Value: Insert Loss of Instrument Air P4 When: EVENT #3 Malfunction MS02B Value: Severity 0.2 Steam Leak in the Reactor When: EVENT #4 Building Malfunction TH08 Value: Severity 10% PORV Fails Open When: EVENT #5 Malfunction RC26 Value: Severity 100 PORV Fails Open When: EVENT #5 Malfunction RD03C Value: 100% Outward Rod Motion Group 7 When: EVENT #6 Trigger Value: mmf MS02B 20 Steam Rupture in the Reactor When: Trjgger 7 Building Trigger Value: Event 8 MU-V-36 breaker opens, When: FWNEFP2B>0.5 Valve fails closed.

Remote MUR67 Value: OPEN MU-V-36 breaker opens, When: EVENT #8 Valve fails closed.

Remote MUR94 Value: 0 MU-V-36 breaker opens, I When: EVENT #8 Valve fails closed.

I/O Override 02A5A03 Value: 40 MU-V-36 breaker opens, ZAIMU42FIC FLO When: EVENT #8 Valve fails closed.

Note: Original Value is 48.6839 Remote CCR32 Value: Closed Close NS-V-85 When: EVENT 10

- 8

Appendix D Operator Action Form ES-D-2 OpTest No.: --.;..._ Scenario # 4 Event # _1,;"...-____ Page 9 of 32 Event DE~scription: Power Ascension From 5% to 10%

Time It Position II '~':. Actionl)or BehClVIUI

. NOTE TO EXAMINER: There are no malfunctions to set for event #1.

1102-2 Plant Startup, Section 3.2.15

.RJ}ISE .reactO£;*~Vl~r.at**~. * ~te:~~nj~"m~per>EncIO$~e . 4.to 1QQ$**by. W~t,tlc.ti,o'f~~ntr()I~~9~tJ~* $equ~nc~1Qy.rn,()¥jnQ.the

. .lnser:YW~rpaJsw~(~C)tothe; Withdrawal .

. ~~rifY.fl8~motiOrJwl':llte.'ightis lit,and roo motion is

,---'" ,','('<' ";;:Y' ',',",' -,"-'.': ,,"" -, ---,

When Tavg is 579 +/- .5°F, then

1. Verify SG FW A & B DEMAND are in AUTO.

2. ADJUST setpoint on REACTOR DEMAND station to obtain zero error on T-AV ERROR indicator.

URO 3. VERIFY Tavg calibrating integral (A5016) is between -10.0 and +10.0 volts and stable.

4. PLACE REACTOR DEMAND in AUTO.

5. ADJUST SG/REACTOR DEMAND to control reactor power

6. Slowly ADJUST Tavg setpoint to 579°F (in parallel with SUbsequent actions).

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

Scenario # 4 Event # --:...____ Page 10 of ....;3;;';;;;;"'--,1 Event

Description:

Power Ascension From 5% to 10%

Tim Position A licant's Actions or Behavior When the REACTOR DEMAND is in AUTO and feedwater demand is above LLL, then URO 1. OBTAIN CRS concurrence.

2. VERIFY SG/REACTOR DEMAND HAND MINUS AUTO indication is at 50%.

3. PLACE SG/REACTOR DEMAND to AUTO.

I------t----r-W-h-e-n-S-G-I-R-E-A-C-T~R DEMAND is in AUTO, then--1 URO 1. SET ULD LOAD RATE OF CHANGE for ~ 0.5 %/minute I AND consistent with MMR (Enclosure 1).

2. SET ULD Target Load Demand to desired setpoint.

1102-2 Plant Startup, Enclosure 2 When FW-V-16A is between 50% and 80% OPEN ARO VERIFY FW-V-17A is closed.

OPEN FW-V-5A. i I

When FW-V-16A is between 50% and 80% OPEN ARO - - - VERIFY FW-V-17A is closed.

OPEN FW-V-5A.

I NOTE TO EXAMINER: When sufficient Reactivity Manipulation has occurred and FW-V-5A/B are open, GO TO Event 2.

Appendix D Operator Action Form ES-D-2 Op Test No.: --.;.._ Scenario # 4 Event # .....;2~ ____ Page 11 of ~

Event

Description:

Invalid "A" OTSG Low Level, Inadvertent "A" EFW actuation. .

T:i:m:;:e:::::p:O~S=iti:on:::::::::::::::::A:P:P:lica~n:t:'S:A::ct=io:ns:o~r:B:eh:a:vl:'o:r:::::::::::::,1 OPERATOR: When directed by the Lead Examiner INITIATE EVENT 2.

i Indications Available: "A" ?TSG Low Level alarm clears, EF-P-2A Indicates runmng.

I Crew i Diagnosis inadvertent EFW actuation, "A" side. :

I i I

CRS i Directs entry into OP-TM-424-901, Emergency Feedwated i

I

, OP-TM-424-901, Emergency Feedwater Ilf EFW actuation . was cause dyan b 'Invard'I signa or con Itlon, INFO i then GO TO section 5.

I ARO Obtain CRS concurrence to shutdown EFW.

N/A If incore temperature <200F then GO TO step 5.5. I I

When all of the following conditions exist:

SCM> 25°F.

Main Feedwater flow is available to each OTSG AVAILABLE.

INFO At least one reactor coolant pump is operating.

OTSG level >20" in each available OTSG.

RB pressure < 2 psig.

I Continue. i I I

Appendix 0 Operator Action Form ES-O-2 Op Test No.: .....;...

Scenario # 4 Event # 2 Page 12 of 32

~~I

Event DElscription: Invalid "An OTSG Low Level. Inadvertent "An EFW actuation.

Time Ii Position I Applicant's Actions or Behavior

.th~:F~.cOntrol*va~~~***ID.~~aJ:.c .

t;f1\{;.~~~y.preSsi~.fJJ~"an

."'~rl1yiQg~t1e;.~v~at 'ligtjtJslit*.

lit. '. ",::>"f 0

** .... . ...... *i;:,}. 0 .

SF-V-. Manual p4~f;lbutton*(CC).*

..jC~~~t tisJit, andthEj~tJtolight is hot lit. '. . ;.~*

~Si.:~*JJ¥if$Sing.ttte~Q~I~sQbytton . (~C),

.... ,the Manual"N islit!and~~utolight is not i~~~.(t~) . ~~.!!itJ3)eJ;,~l!bY.

switches<counterc)o~~ise. to.!be Closes bothEF,:~,,8f}A~~~**.SF,.V,$3QOJ)yacfju~tifl~*thetQggJe * *.

s ..(CL)iot6ts..** '. ...n./~ROmay*pin the toggle .

s es in thefulf c J O ! l e d ' ..

If OTSG A is available, then ensure level is maintained with ARO Main Feedwater.

Closes both EF-V-30B and EF-V-30C by adjusting the toggle ARO switches (CC) in the closed direction. ARO may pin the toggle switches in the full closed nnC'ITIT".n If OTSG B is available, then ensure level is maintained with ARO Main Feedwater.

Appendix 0 Operator Action Form ES-D-2 1Op Test No.: ~-

Scenario # 4 Event # 2

~------

Page 13 of 32

~=-~

Event

Description:

Invalid "An OTSG Low Level, Inadvertent "A" EFW actuation.

Time Ii Position I Applicant's Actions or Behavior F>1$~'4~~". .....o'BCPs.~ndMi~Jt1 folloWS;. ..... '.' R~Pr~u~~¥1:eNA~~!as

- *s~rElif)A Los~QfRGJi"s iniEN~~ee!W(iotatin3,lle" .'

'sWitqh(~~);dQ~~ totl'leENAE\l;;~;posjtfon.

" ' " , ofRcPsin.E~ASLe.bYl9tatin~ th~

$... . ; '..* *. . . . CI?CkWj~j~t?~eE:N~t3k~;posjtjO~i

,itf~in ~Mi~~.6Spress~raif:1'FN~Bli'\*~.:f:o~nQthe

.~9h (CL}.;i:!()~se.to tn~;IiN~'LEposltiqn.

"M.V.", ".-.c ____, _ _ ",' ,'" -,,~ " j . ." , ' .",.

p¥.rotatingthe

~lion.

If~!least.~~¥~pump~[res~~thenplacel..DS$ ofFWPs in 5~~l;.E"as fon~~ ..

A""~"'...* *TffliD.~1.~~<9f.;J;Wf3tJm~/j~f2NA8LEb¥irotatirlg the

,,;;q

i f _*..*

.**. ~SWjtch}~)*~J9~ise t~*!~*~NABLEpO$ltion.

'J\rilinS.~:~t*~ Pum";ifli~~E3l.E . . . ...~Irrg thEil sWitch (~)'9Iockwise~the'Iit4AB~E po. *;~n..., .~-=---"--'1 If9TS(SA level?,"~:jl}C~~ ah~jpT$4l ele"el~<tQinCtles then place Lo-~&'gT~ .LeV~.ItJENAf3LE~fz~ottows: . . . . . . . .

N _ TrainA;~90rSG~vti)fIOr:NJ\fFlLEb¥*.r()tafing the) switcb 'lockwiSEttoltaeENABLEPOSifiim,

-" Tr~i~B:~~W>t)TS~LeV;liri>~ABLl;bY ro~ngthe

.f s.witch(eeicroc~wis~to theENABLf::Position.

, "'v/'

Close AS-V-4

Ensure MS-V-1 OA is Closed N/A Close MS-V-13A

. Ensure MS-V-10B is Closed r-----~~------~.

Close MS-V-13B

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

~--------

Page 14 of 32

-=~

Event

Description:

Invalid "A" OTSG Low Level. Inadvertent "A" EFW actuation.

Time Position A licant's Actions or Behavior I NOTE TO EXAMINER: The crew may decide t~ maintain EF-V-30A and EF-V-30D in

manual control due to a faulted signal being present.

.,> ~

Q. t~AlAto<~~t(

lls<l~atldfhe ..

0" _ ,

~tQ r5u~t1ltOh (eL),

~J1ldth*'Mam..~Jiiflbt*i!;not

, ;>~,

NOTE TO EXAMINER:

Table 3.5-1 (Instruments Operating Conditions)

D. Heat Sink Protection System Functional Unit I Min Operable Channels I Min Degree of Redundancy OTSG Low Level / 2 I 1 (a) Re!store the conditions of Column (A) and Column (8) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or place the unit in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

NOTE TO EXAMINER: After EF-V-30's have been placed in AUTO control and the Tech Spec call has been made, GO TO Event 3.

Appendix D Operator Action Form ES-D-2 OpTest No.: Scenario # 4 Event # _3~_ _ _ _ Page 15 of ~~I

~-

Event

Description:

Loss of Instrument Air I BOOTH OPERATOR: When directed by the Lead Examiner INrnATE EVENT 3.

I Indications Available: Lowering Instrument Air pressure, IA-P-4 trip indication, PLF annunciator alarms.

Crew Diagnoses the Loss of Instrument Air.

NOTE TO EXAMINER: The crew may go to PRF alarm response before AOP-02S.

The alarm response will lead to AOP-02S.

ICO N()TE: If directed to go to IA-P-1A/B, delay calling back until the ARO starts IA-P-1 A or B.

CRS Announces entry into OP-TM-AOP-028, Loss of Instrument Air.

OP-TM-AOP-02S, Loss of Instrument Air ANNOUNCE loss of instrument air over plant page and radio.

ARO (AO response per OS-24 Attachment E).

IAAT IA pressure is < 60 psig (PI-222 or PI-1403), then PERFORM the following:

_ A. If SI Flow> 22 gpm, then DISPATCH an operator to block Open MU-V-20 (AS 305: behind MU-F-4A/B).

N/A _ B. If ICCW Flow> 550 gpm, then DISPATCH an operator to block Open IC-V-4 (AS 305: W of RB wall) and IC-V-3 (AS 281: A shielded area).

_ C. ENSURE reactor is tripped.

D. GO TO Section 4.0.

I BOOTH OPERATOR: If asked, IA-PI-491 Reads SO psig.

I I

Appendix D Operator Action Form ES-D-2 Op Test No.: --.;..._ Scenario # 4 Event # ....;3~_ _ _ _ Page 16 of ...,;3;.;;.2---11 Event

Description:

Loss of Instrument Air Time II Position II Applicant's Actions or Behavior

. BOOTH OPERATOR: If asked, IA-P-1A1B filter and dryer DP reads 10 psld.

BOOTIH OPERATOR: If asked, IA-P-4 filter and dryer DP reads 10 psld.

i i 1 I NOTE TO ~MINER: i Alter IA-P-1A or 1B is started, GO TO Event 4.

Appendix D Operator Action Form ES-D-2 Op Test No.: ...;..._ Scenario # ~ Event # _4...:..-____ Page 17 of 32

Event DElscription: Steam Leak into RB, RR-P-1 B fails to start.

A licant's Actions or Behavior I BOOTH OPERATOR: When directed by the Lead Examiner INITIATE EVENT 4.

,__.,,_11;:>> .

Available' Rising RB Pressure, Lowered Megawatts, Fire alarm in RB * !

I Crew I Diagnoses the steam leak in the RB.

i i I I Announces entry into OP-TM-AOP-051, SECONDARY SIDE

! I CRS I HIGH ENERGY LEAK.

OP-TM-AOP-oS1, SECONDARY SIDE HIGH ENERGY LEAK ANNOUNCE entry into OP-TM-AOP-051, "Secondary Side I ARO High Energy Leak" and to evacuate affected area over the plant .

page and radio.

i I

URO MAINTAIN reactor power < 100%.

i IAAT leak can be isolated, then ISOLATE the leak and GO TO N/A i Section 7.0.

i N/A IAAT leak is isolated, then GO TO Section 7.0.

N/A IAAT XHT or LOHT exists, then GO TO EOP-001.

I I CRS i REQUEST SM to evaluate EALs.

I i

CRS If leak is in Reactor Building, then GO TO Section 4.0.

I t=

i

,IAAT RB pressure greater than 2 psig, then TRIP the reactor N/A and GO TO EOP-001.

I I .

INITIATE OP-TM-534-901, "RB Emergency Cooling L INF

......L-_ _ O~~peratlons" .

Appendix D Operator Action Form ES-D-2

. Op Test No.: --.;...

Scenario # 4 Event #

4 Page 18 of 32

~~;

. Event

Description:

Steam Leak into RB, RR-P-1 B fails to start.

Time Position A licant's Actions or Behavior OP*TM-534-901, "RB Emergency Cooling Operations".

Prerequisites:

VERIFY Reactor Building Emergency River Water System was in ES standby lAW OP-TM-534-000, "Reactor Building Emergency Cooling Water System".

ARO VERIFY 1600 psig ES actuation, RB pressure is approaching 2 psig or Emergency Director or Shift Manager has authorized use of RBEC.

D or 1E 4160V Bus is ener ized.

, BOOTH OPERATOR: When directed to close NS-V-85, insert CCR32 closed (Event #10) and report NS*V-85.

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

ARO DISPATCH an operator to CLOSE NS-V-85 (18295: S of RR

\-- _ _ _ _ _i - -_ _ _-t-'-V~lve Room).

8tl\RTor ~8lF~running; ...*. . '.

<r:', , ': : : .: ,:':., --">,,, :-'," :" ftc': ---:-:,::,:'i'-~' > :-:':,~>("--;- ',:, :.. :. '- -:---- -' .-:- ,-:-"-_;:-'--_~::':\: '::~:-y::',:--- "

Re~p-1 A*.by r~~ti~.the,cQ~v~r§~~!or ~i~~~rc~f!1J)(cC}

- cto~se.yerifriAlt~;fl'etttligIiUs.t;~nl'J .the:g.~~ri/ligbtis not .

"Tit,; '.~ ~.. .' . . ..Y ...** ... . :." .. :e*;.;; ....;:.. .';

'Ji~':A"1B ARO Announces RR-P-1 B will not start.

ENgORE0'~Ni; "

'<j' :",',,'

~Ft-V~:3Aby , utton (Gft) .\$rifyiJ'lQvaJye

'oe~n* Jj~~~" n~}(~ht~~ fnotlit RB,'"V -3a:,~Migptnot perfGtrT!)* , .'. .. ..,

. RR:f\l:.a~***** "~$hbuttOl'leivR~ijVerifyingvahte '

~_ _-t--~~,_ _~,-,o.J)9nl!tdIi9,htROtlit_*.~,~.-""-~~_~~

Appendix D Operator Action Form ES-D-2 Op Test No.: .....;...._ Scenario # 4 Event # _4..:...-_ _ _ _ Page 19 of .....;3=2--11 i

. Event

Description:

Steam Leak into RB, RR-P-1 B fails to start.

Position A licant's Actions or Behavior

~jon .(~};,v~r,litng:valve

\notlit.

ARO ENSURE NS-V-85 is Closed OP*TM-534*901, "RB Emergency Cooling Operations" Section 4.2, Contingency Actions If RR-P-1 B is not operating and 1E 4160V bus is energized, then perform the following: _

N/A A START RR-P-1 B.

B, If RR-V-10B and RR-V-1B are Closed, then OPEN RR-V-1B.

CRS Declare TS for RR-P-1 B non-operational.

NOTE TO EXAMINER: Reactivity manipulation has already been observed and is not required or desired prior to moving to Event 5.

OP.TM*AOP*051, SECONDARY SIDE HIGH ENERGY LEAK I URO

INITIATE Plant Shutdown lAW 1102-4, "Power Operation", and C_---'-____ .L1_11.02-10, "Plant Shutdown_"'_ _ _.

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # _4.;......_ _ _ _ Page 20 of ..,;3;;.;;;,2--"1 Steam Leak into RB, RR-P-1 B fails to start.

A licant's Actions or Behavior NOTE TO EXAMINER:

3.3.1.3 Specification: The following components must be OPERABLE:

a. Two reactor building spray pumps and their associated spray nozzles headers and two reactor building emergency cooling fans and associated cooling units (one in each train. Specification 3.0.1 applies.

I I NOTE TO EXAMINER: When RB Emergency Cooling is in effect and the T.S.

call is made, GO TO Event 5

Appendix D Operator Action Form ES-D-2 Op Test No.: -:..._ Scenario # 4 Event # _5;;;...-_ _ _ _ Page 21 of ...,;;3;.:,2__

1 Event De,scription: PORV Fails Open Time I Position I Applicant's Actions or Behavior Boon.. OPERATOR: When directed by the Lead Examiner INITIATE EVENT 5.

Indications Available: MAP Annunciator G0106, RCS Pressure lowering.

Crew Diagnoses PORV has failed open with an invalid signal.

CRS Directs entry into MAP Alarm Response G01 06.

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

OP-TM-MAP-G01 06

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

OBSERVE l1P indication on DPI 921, 922, or 923 (CC) to determine which valve is OPEN. Alarm G-1-6, PZR SAFETY OR PORV OPEN (DP) and tailpipe differential temperatures may also be used.

URO

- RC-V-1A tailpipe delta temp (A0518)

- RC-V-1 B tailpipe delta temp (A0519)

- RC-RV-2 tailpipe delta temp (A0517)

NOTE TO EXAMINER: After RC-V-2 is closed GO TO Event 6.

Appendix D Operator Action Form ES-D-2 Op Test No.: -.:.... Scenario # 4 Event # _6=--_ _ _ _ Page 22 of ...,;3;;;;;,2_

1 Event

Description:

Uncontrolled outward rod motion, Group 7, manual Reactor Trip Time II Position II Applicant's Actions or Behavior

[ BOOTH OPERATOR: When directed by the Lead Examiner INITIATE EVENT 6.

I Indications Available: MAP Annunciator alarms for Excessive Group overlap,

. Outward rod motion on group 7.

URO Diagnoses uncontrolled rod motion on group 7.

Announces entry into OP-TM-AOP-064, UNCONTROLLED CRS ROD MOTION.

OP-TM-AOP-OS4, UNCONTROLLED ROD MOTION

~--~~~~~~~

i$ifl ""~UAL by pressing

.. ,. ~ingt~~tttre i$:.t'lQIUt.

URO ENSURE GROUP and SINGLE SELECT switches are OFF.

A..J:~ip~~> .*itlij.~ft:l~. react()r trip al1d' DSS

.> ,,,.pu$@Utfon .

.... S. GO TO Op*TM;;~jE';~001.

CRS Directs entry into OP-TM-EOP-001, Reactor Trip.

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

Event Doscription:

Scenario # 4 Event # _6_ _ _ _ _ _ Page Uncontrolled outward rod motion, Group 7, manual Reactor Trip 23 of ...,;3=2----li Time I Position Ie Applicant's Actions or Behavior OP-TM-EOP-001, Reactor Trip IMAs URO VERIFY REACTOR SHUTDOWN.

~i-... ~*":""(Cl..), <i" .

.\JRO ...... PRi8ST:: .; !l'rip r\l .' ...

URO VERIFY the turbine stop valves are Closed.

i NOTE TO EXAMINER: After the EOP-001 IMA's are completed, GO TO Event 7.

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

Scenario # 4 Event # _7;..:.,.;;.8_ _ _ _ Page 24 of ...,;3;.;;;,2--"'1 Event

Description:

Steam Rupture in RB, Excessive Heat Transfer, MU-V-36 Fails Closed Time II Position I Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Lead Examiner INITIATE EVENT 7.

Indications Available: R~ Pressure rises rapidly, 4# ES signal, Lowered Megawatts, MAP annunciator alarms.

Crew Diagnose the Steam rupture.

Performs a Symptom Check, Announces Excessive Primary to Secondary Heat Transfer based on:

All of the following conditions:

ARO

RCS average temperature below 540°F.

Uncontrolled lowering of RCS temperature.

Tsat for OTSG pressure is less than Tcold on affected oTSGs.

ANNOUNCE Entry into OP-TM-EOP-003, Excessive Primary to CRS Secondary Heat Transfer.

OP-TM-EOP-003, Excessive Primary to Secondary Heat Transfer ARO

PERFORM Rule 3, XHT.

OP-TM-EOP-010, Rule 3, XHT.

ARO VERIFY OTSG level < 97.5%.

I i

ARO VERIFY primary to secondary heat transfer is excessive.

i ARO PERFORM Phase 1 Isolation of the affected OTSG{s).

Appendix 0 Operator Action Form ES-O-2 Op Test No.: --.;...

Scenario # 4 Event # 8 _ _ _ Page

....,;7.,.... 25 of ....,;3=2---11 Event

Description:

Steam Rupture in RB, Excessive Heat Transfer, MU*V*36 Fails Closed I Time II Position II Applicant's Actions or Behavior

'hbutton.,~),. '.,'

anQi;tg~~Jye'<:l~ligtlt

/;~;#"" '/i;<

.~~M....i2iQl.~y!;~~~etO$~(fPU$ti6J~qn(cc)~

verifying that.~.~;QIOsedJightj.s lit an~.lt1;e~~~eopen light

~1'1()tl,lt! ,'t"" . . ..... ".

" FW-V-16B by I toggJ~ switch (CC).

"~~if!l!7V.;.~ ~~'~'¥. 19werlng ~~d/qi/i~itlgQtJ.~f). FW.y-17B toDfe SWi~ (09),'/' ....... ' J '

"/,c<" .

,,";//,;

.Itg~ fOf~jnjrnumFWblP~f.lflQ¥i FW"V..aSB (lnterm8Idg..32!')...,

BOOTH OPERATOR: When directed to close FW-V-85B, close FW-V-85 and report it closed.

ARO PERFORM Phase 2 Isolation of the affected OTSG(s).

Appendix D Operator Action Form ES-D-2

! Op Test No.: Scenario # 4 Event # .....;7-",;;..8_ _ _ Page 26 of .....3=2--1i

~-

Event

Description:

Steam Rupture in RB, Excessive Heat Transfer, MU-V-36 Fails Closed A licant's Actions or Behavior theM~~y,tp~sht>'ttRrt(6Cl,' ..

'I~:~~ Alifolilhli$** JlQflitand

.. swi~9,bl$(gL) inth$l'cl~d tQggleSwncliesinthe.. fwh:~lo~

<')$:"" -,/ . . " , " , ,',",

d.~usflb~li~(CC) ,ver~ing

. . tpevalye,openUght is nofUt.

",,/., .. ", .

~ If una~~~Qse an e~=\)~t~enClpS~~i~ssw~ted ...*

EF~V-52 valve lA"OP~"TIM';lf:24"9Il';"Emet* ellC. FQ.edwater'*.**

THROTTLE EFW lAW Rule 4, "Feedwater Control" (maintain ARO OTSG level> 25" Startu Ran e Level usin Main or EFW.

ARO VERIFY OTSG level and pressure stabilizes.

ARO INITIATE Guide 12, "RCS Stabilization" .

. OP-TM-EOP-003, Excessive Primary to Secondary Heat Transfer URO INITIATE Guide 9, "RCS Inventory Control".

~-------r-------~-

OP-TM-EOP-010, Guide 9, "RCS Inventory Control"

Appendix D Operator Action Form ES-D-2

. Op Test No.:

Event

Description:

Scenario # 4 Event # 7,8

---'----- Page 27 Steam Rupture in RB, Excessive Heat Transfer, MU-V-36 Fails Closed of Time A licant's Actions or Behavior i

i URO VERIFY MU Tank Level < 96 inches. i i

URO VERIFY MU pump is operating.

URO VERIFY MU-V-5 is Closed.

URO VERIFY MU24-FI > 20 gpm. !

URO ENSURE MU-V-17 is Open.

VERIFY PZR level is being restored.

RNO: THROTTLE MU-V-217.

URO RNO: CLOSE MU-V-3.

RNO: INITIATE HPI lAW OP-TM-211-901, "Emergency Injection HPI/LPI".

op*TM-EOP-003, Excessive Primary to Secondary Heat Transfer 1MT RCS temperature reduction has been terminated, N/A then PERFORM Guide 12, "RCS Stabilization".

I ARO ENSURE announcement of reactor trip.

VERIFY primary to secondary heat transfer is being i ARO established .

VERIFY RCS Tcold > 525 of.

i URO RNO: INITIATE Rule 5, "Emergency Boration".

L INITIATE Rule 6 "Pressurized Thermal Shock".

ARO ENSURE performance of an alarm review.

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # _7;..l.,..;;.8_ _ _ _ Page 32 of -:;3;.;;;,2---'1

~-

Event

Description:

Steam Rupture in RB, Excessive Heat Transfer, MU-V-36 Fails Closed Time I Position II Applicant's Actions or Behavior II IAAT Containment pressure exceeds 2 psig, then perform the following.

_1. INITIATE OP-TM-534-901, RS Emergency Cooling.

__ 2. DETERMINE source of elevated Containment pressure by observing the following:

- Radiation Monitors, ARO - OTSG pressures,

- OTSG feed rates.

__ 3. If Containment pressure source is a secondary side leak (either FW or MS), then PERFORM EOP-001 Attachment 1, "OTSG Isolation" for the affected OTSG.

- 4. If an OTSG is isolated, then INITIATE EOP-010 Guide 2, "OTSG Isolation From Condenser".

I ARO VERIFY PRF1-3-5 "Intermed Bldg Flooding" alarm is Clear. I N/A i IAAT PRESSURIZER LEVEL can not be MAINTAINED WITHOUT HPI, then GO TO EOP-OOB. I I

I NOTE TO EXAMINER: The scenario may be terminated when the "B" OTSG is isolated and HPI is terminated. I I i . I

. NOTE TO EXAMINER. Terminate the scenario Follow-up question highest event entered during scenario?

Answer: None (unless overcooling results in Loss of Sub-cooling Margin LSCM would be an Alert FA1.

v t e Letter Sequence Draft Other
TAC:U01829, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML112620102, ML112620105, ML112620125, TMI-10-095, (TMI-1) Renewed Operating License No. DPR-50 Docket No. 50-28 - Revision of Scheduling Operator Examinations
MONTHYEAR2011-07-26 [Table View]

ML112620096

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