Text

Final Operating Exam (Sections a, B, and C) (Folder 3)
	ML14141A107
Person / Time
Site:	Three Mile Island
Issue date:	04/01/2014
From:	Peter Presby; Operations Branch I
To:	; Exelon Generation Co
	Jackson D
Shared Package
ML13333A179	List: ML14093A016; ML14111A292; ML14111A293; ML14111A295; ML14111A296; ML14141A104; ML14141A105; ML14141A107; ML14143A127; TMI-14-002, Draft - Outlines (Folder 2);
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Appendix C Page 1 of 10 Form ES-C-1 PERFORMANCE INFORMATION Facility: TMI- Unit 1 Task No.: GOP002004 Task

Title:

Calculate an Estimated Critical JPM No.: TMI 2014 NRC ADM Boron Concentration JPM RO A1-1 KIA

Reference:

2.1.25 (3.9)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator ---

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

Initial Conditions:

A sequential trip of both main feedwater pumps resulted in a reactor trip yesterday at 1000.

The reactor is expected to return to critical at time T =+35 hours after the reactor trip.

Reactor Power was 80%

The unit had been on-line for 208 days.

The last down power was 21 days ago.

Cycle Burnup is 470 EFPD.

TAVE = 532°F

Current Boron Concentration = 1675 PPM

The Desired Critical Rod Position is: 85% WD on CRG-6.

The FINAL MIXED BORON DEPLETION CORRECTION FACTOR as specified in the control room log is .90

No DTSQA-approved software is available for calculations.

Task Standard: Calculate an Estimated Critical Boron Concentration.

Required Materials:

Calculator

Ruler General

References:

OP-TM-300-000, REACTIVITY AND POWER DISTRIBUTION CALCULATIONS, Rev. 5 OP-TM-300-402, ESTIMATED CRITICAL BORON CONCENTRATION, Rev. 3 TMI 2014 NRC ADM JPM RO A1-1 NUREG 1021, Revision 9 Supp 1

Appendix C Page 2 of 10 Form ES-C-1 PERFORMANCE INFORMATION Handouts: OP-TM-300-000, REACTIVITY AND POWER DISTRIBUTION CALCULATIONS, Rev. 5 OP-TM-300-402, ESTIMATED CRITICAL BORON CONCENTRATION, Rev. 3 Initiating Cue: You are the URO. A reactor startup is anticipated for this shift.

Calculate Estimated Critical Boron lAW OP-TM-300-402, ESTIMATED CRITICAL BORON CONCENTRATION.

Time Critical Task: No Validation Time: 30 minutes SIMULATOR SETUP N/A TMI2014 NRC ADM JPM RO A1-1 NUREG 1021, Revision 9 Supp 1

Appendix C Page 3 of 10 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

OP-TM-300-402 Step 3.0 Performance Step: 1 Locates/reviews procedure Limits and Precautions.

Standard: The Examinee reviews LIMITS AND PRECAUTIONS.

Evaluator Cue: Provide a clean copy of OP-TM-300-402 to the Examinee Comment:

OP-TM-300-402, Attachment 7. 1 Performance Step: 2 Open Attachment 7.1 and use the following to complete.

Standard: The Examinee obtains Attachment 7.1 Comment:

OP-TM-300-402 Attachment 7. 1 Step 1 Performance Step: 3 Verify the average reactor coolant temperature, TAVE, from the Initial Conditions.

Standard: The Examinee verifies TAVE on Initial Conditions equals 532+/-2°F Comment:

OP-TM-300-402 Attachment 7.1 Step 2 Performance Step: 4

Record Cycle Burnup.

Standard: The Examinee records 470 EFPD from Initial Conditions on Line 2 of Attachment 7.1.

Comment:

TMI2014 NRC ADM JPM RO A1-1 NUREG 1021, Revision 9 Supp 1

Appendix C Page 4 of 10 Form ES-C-1 PERFORMANCE INFORMATION OP- TM-300-402 Attachment 7. 1 Step 3 Performance Step: 5 Record Current Measure Boron Concentration Standard: The Examinee records 1675 ppm from Initial Conditions on Line 3 of Attachment 7.1.

Comment:

OP-TM-300-402 Attachment 7.1 Step 4 Performance Step: 6 Record the Desired Critical Rod Positions Standard: The Examinee records the following information on Line 4 of Attachment 7.1:

CRG 1-4 100%WD CRG5 100%WD CRG6 85%WD CRG7 10%WD Comment:

OP- TM-300-402 Attachment 7. 1 Step 5

-1 Performance Step: 7 Determine and record Fuel Excess Reactivity lAW Figure 2 of OP-TM-300-000 Standard: The Examinee interprets Figure 2 and records 9.4% to 9.6% .!lk/k on Line 5 of Attachment 7.1.

Comment:

OP-TM-300-402 Attachment 7. 1 Step 6

-1 Performance Step: 8 Determine and record the Desired Critical CRG 5-7 Reactivity Worth lAW Figure SA of OP-TM-300-000 Standard: The Examinee interprets Figure SA and records -1.0% to -1.2%

dklk on Line 6 of Attachment 7.1.

Comment:

TMI 2014 NRC ADM JPM RO A1-1 NUREG 1021, Revision 9 Supp 1

Appendix C Page 5 of 10 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-300-402 Attachment 7. 1 Step 7

"'./ Performance Step: 9 Determine and record the Xenon Reactivity Worth lAW Figure 13 of OP-TM-300-000.

Standard: The Examinee interprets Figure 13 and records -0.90% to -

0.95% dklk on Line 7 of Attachment 1.

Comment:

OP- TM-300-402 Attachment 7.1 Step 8

"'./ Performance Step: 10 Determine and record the Samarium and Plutonium Buildup lAW Figure 15 of OP-TM-300-000.

Standard: The Examinee interprets Figure 15 and records -0.07% to

-0.08% dklk on Line 8 of Attachment 7.1 Comment:

OP-TM-300-402 Attachment 7.1 Step 9

"'./ Performance Step: 11 Calculate and record the Boron Reactivity Worth For Criticality Calculation.

Standard: The Examinee records the value 7.175% to 7.535% dklk on Line 9 of Attachment 7.1 Comment:

OP- TM-300-402 Attachment 7. 1 Step 10

"'./ Performance Step: 12 Determine and record the Inverse Boron Worth lAW Figure 8 of OP-TM-300-000.

Standard: The Examinee interprets Figure 8 and records 133.5 to 134.5 ppmB I %dklk on Line 10 of Attachment 7.1 Comment:

TMI2014 NRC ADM JPM RO A1-1 NUREG 1021, Revision 9 Supp 1

Appendix C Page 6 of 10 Form ES-C-1 PERFORMANCE INFORMATION OP- TM-300-402 Attachment 7. 1 Step 11 a

-I Performance Step: 13 Calculate and record the Critical Boron Concentration Standard: The Examinee records 957.9 to 1013.5 ppmB on Line 11 a of Attachment 7.1.

Comment:

OP-TM-300-402 Attachment 7. 1 Step 11 b

-I Performance Step: 14 Record the Final Mixed Boron Depletion Correction Factor.

Standard: The Examinee records 0.9 from Initial Conditions on Line 11 b of Attachment 7.1 Comment:

OP-TM-300-402 Attachment 7. 1 Step 11 c

-I Performance Step: 15 Calculate and record the Estimated Measured Critical Boron Concentration Standard: The Examinee records 1064 to 1126 ppmB on Line 11 c of Attachment 7.1 Comment:

TMI 2014 NRC ADM JPM RO A1-1 NUREG 1021, Revision 9 Supp 1

Appendix C Page 7 of 10 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-300-402 Attachment 7. 1 Step 12 Performance Step: 16 If this is a transient Xenon startup, then RECORD the interval that ECB is valid. Use the Xe value from Line 7 and a plot or table of Xe behavior with time. Estimate when Xe worth will be more or less negative than the value in Line 7 by 0.5% 11klk.

Standard: The Examinee:

o Determines that this is a transient Xenon startup.

o Subtracts -0.5 11klk from -0.9 11klk. and comes up with

-1.4 11k/k.

o Interprets Figure 13 and determines that -1.4 11klk.

correlates with 28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months after shutdown (27-29).

o Determines that 28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months after shutdown is 1400 today

( 1300-1500) o Subtracts +0.5 11klk from -0.9 11klk. and comes up with

-0.4 11klk.

o Interprets Figure 13 and determines that 0.4 11klk.

correlates with 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after shutdown (46-50).

o Determines that 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after shutdown is 1000 tomorrow (0800-1200) o Records the following on Line 12 of Attachment 7.1:

o from" date as today.

o from" time as calculated above.

o "to" date as tomorrow.

o "to" time as calculated above.

Comment:

OP- TM-300-402 Attachment 7. 1 Performance Step: 17 Sign and add date/time Standard: The Examinee signs and adds the date and time at the bottom of Attachment 7.1.

Comment:

Terminating Cue: When the candidate returns the completed Attachment 7.1 to the examiner: This JPM is complete.

STOP TIME:

TMI2014 NRC ADM JPM RO A1-1 NUREG 1021, Revision 9 Supp 1

Appendix C Page 8 of 10 Form ES-C-1 PERFORMANCE INFORMATION ANSWER KEY- DO NOT PROVIDE TO EXAMINEE OP-TM-300-402 Revision 3 Page 3 of4 ATTACHMENT 7.1 Estimated Critical Boron Concentration Cak:.ulation Data Sheet Page 1 of1 NOTE: \RB'el" ro ~ 7 2 tJ ~ tl'!ils tb!.a Sheet. ~:lata l'fli)' be~ !n any~- S9Hll ~ ~ tbU*emered ii!i ~ ~al

~*IOO'Icatesan ~ ~*"

CALCu..AllOO F5 f<JIR liN EC5 AT DATE!TIME Current Date I Time

1. TA'lll (~ TA'III* 5J.2 ::1: :n=)

2. CYCLE BURNUP 470 .EFPD

3. CUflRBil. MEASURED EICflDN CONCEI'flRATION 1675 ppmB

CRG t-.4 ------'1=00'-*% WD

eRGS 100 %WD

eRGo 85 ~WD

CRG7 10 ~WD 5 FUEl EXCESS R£ACT1\111Y (HG 2) 9.4 to 9.6 ':ria M;.l};

6. DESIRED CRmCAL CRG* 5-7 REACTI'IIfN WORTH (FIG 5A) -1.0 to -1.2 %.&£~};

1. XE.NON REACTN!TY WORTH (PPC, REACTOR ENGR, AG u:1 -0.85 to -0.95 %&;;.!};

~IJM AND P~fUM Bl.II.OOP I:HG 15)

TIME SiNCE SHUT'DOWN 35 HRS

FI.EACTMTYDUE TO BUilDUP -0.07 to -0.08 ,'%Atlt

9. EICflDN RE.A.CTIVITY WOR1li FOR CRJTiiCALITY Cld..CUATK:JN i.S + 6 + 7 + 6)

7.175 to 7.535 %Atlt

!ti!JERSE BaftCNWOfmi (HG8l 133.5 to 134.5 ppm~ Ar.t.

CRn1CAl ElOfiDN CONCENT'RA.T()N 11a CArneAL ~CCNCENTRATION (9x: 1Cl)- 957.9 to 1013.5 .FPJiiB 111>. ftw.. MIXED BOftCN DEPlETION CORRECTION FACTOR 0.9

{PPC, COOIIJU Fl'.ollm Ulg,. ReadD' ~)

11c. ESliMAlED MEA:..~ CRITICAl BORON CONCBITRATION 1064 to 1126 ~

111115 ~a~ XB1loo! ~.then RECORD the t'lte!Ya! mt EC815 *va!fd Fram: oamrnme: Todav/1300-1500 To: Dalemme Tomorrow I 0800-1200 CALCUAlED BY: Signature DATEmME Current Date/ Time

~BY~SRO~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ OATEmME _ _ _ __

ANSWER KEY- DO NOT PROVIDE TO EXAMINEE TMI2014 NRC ADM JPM RO A1-1 NUREG 1021, Revision 9 Supp 1

Appendix C Page 9 of 10 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: TMI 2014 NRC ADM 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 2014 NRC ADM JPM RO A1-1 NUREG 1021, Revision 9 Supp 1

Appendix C Page 10 of 10 Form ES-C-1 JPM CUE SHEET Initial Conditions:

A sequential trip of both main feedwater pumps resulted in a reactor trip yesterday at 1000.

The reactor is expected to return to critical at time T =+35 hours after the reactor trip.

Reactor Power was 80%

The unit had been on-line for 208 days.

The last down power was 21 days ago.

Cycle Burnup is 470 EFPD.

TAVE = 532.F

Current Boron Concentration = 1675 PPM

The Desired Critical Rod Position is: 85% WD on CRG-6.

The FINAL MIXED BORON DEPLETION CORRECTION FACTOR as specified in the control room log is .90

No DTSQA-approved software is available for calculations.

INITIATING CUE: You are the URO. A reactor startup is anticipated for this shift.

Calculate Estimated Critical Boron lAW OP-TM-300-402, ESTIMATED CRITICAL BORON CONCENTRATION.

TIME CRITICAL: No TMI2014 NRC ADM JPM RO A1-1 NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Three Mile Island Task No.: AOP602001 Task

Title:

Perform OP-TM-300-202, JPM No.: TMI2014 NRC ADM QUADRANT POWER TILT AND JPM RO A1-2 CORE IMBALANCE USING THE OUT-OF-CORE DETECTOR SYSTEM.

KIA

Reference:

2.1.37 4.3 I 4.6 Facility Bank JPM 148 (Modified)

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 computer is not operational.

The computer has been off-line for 33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months .

lncore tilt was not exceeding the limits prior to the computer outage.

No associated computer alarms were in prior to the computer outage.

Recalibration of the Nl's is not and has not been required.

There are no dropped rods.

All OCD's are operable.

The following items are available for your use:

An Examinee Data Sheet containing the current Nl power level and last recorded set of valid, steady state Fulllncore System (FIS) and out-of-core detector (OCD) tilt measurements.

Calculator Task Standard: Calculate quadrant power tilt.

Required Materials:

COLR

Calculator TMI2014 NRC ADM JPM RO A1-2 NUREG 1021, Revision 9 Supp 1

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

References:

OP-TM-300-202, QUADRANT POWER TILT AND CORE IMBALANCE USING THE OUT-OF-CORE DETECTOR SYSTEM, Revision 2

COLA

Technical Specifications An Attachment 7.1, OCD-ICD Tilt Correlation, KEY is attached to this JPM for evaluator use/information. Ensure that the KEY is NOT provided to the applicants.

Handout:

OP-TM-300-202, QUADRANT POWER TILT AND CORE IMBALANCE USING THE OUT-OF-CORE DETECTOR SYSTEM

Examinees Data Sheet (attached behind the JPM CUE SHEET) containing the current Nl power level and recorded set of valid, steady state Fulllncore System (FIS) and out-of-core detector (OCD) tilt measurements.

Initiating Cue: Calculate quadrant power tilt lAW OP-TM-300-202, QUADRANT POWER TILT AND CORE IMBALANCE USING THE OUT-OF-CORE DETECTOR SYSTEM, based on the information provided.

Time Critical Task: No Validation Time: 25 minutes SIMULATOR SETUP N/A TMI2014 NRC ADM JPM RO A1-2 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:

EVALUATOR NOTE: Ensure that the KEY is NOT provided to the applicants.

OP-TM-300-202, Step 4.1 Performance Step: 1 IAAT the PPC, FIDMS, and FIS are all operable, then EXIT this procedure.

Standard: Determines from the given initial conditions that the PPC is not operable and continues.

Comment:

OP-TM-300-202, Step 4.2 Performance Step: 2 IF all OCDs are operable, THEN PERFORM the following:

(1) DETERMINE tilt lAW Step 4.5.

Standard: Examinee goes to Step 4.5 Comment:

PROCEDURE NOTE: Tilt calculation must be performed once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the tilt alarm is inoperable.

TMI 2014 NRC ADM JPM RO A 1-2 NUREG 1021, Revision 9 Supp 1

Appendix C Page 4 of 13 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-300-202, Step 4.5. 1. 1-4.5.1.2 Performance Step: 3 VERIFY computer alarms package for incore tilt was not in alarm immediately prior to loss of PPC, FIDMS, or FIS.

IF the alarms package was in the alarm state, THEN TAKE action as necessary to address the alarm before proceeding in this procedure.

Standard: Verifies the computer alarms package was not in an alarm state immediately prior to the loss of computer.

Comment:

OP-TM-300-202, Step 4.5. 1.3 Performance Step: 4 RECORD last set of valid, steady state incore (FISo) and out-of-core (OCD 0 ) tilt measurements and the date and time the data was obtained on Attachment 7.1.

Standard: Examinee obtains the date and time that the data was obtained from the given data sheet and enters the data on Line A 1 of Attachment 7.1.

Examinee obtains the FISo incore tilt measurements from the given data sheet and enters the following data on Line A2 of Attachment 7.1 :

Nl-5 (WX) +1.23 Nl-6 (YZ) +2.28 Nl-7 (XY) +0.04 Nl-8 (ZW) -0.63 Examinee obtains the OCD out-of-core tilt measurements from the given data sheet and enters the following data on Line A3 of Attachment 7.1 :

Nl-5 (WX) -0.88 Nl-6 (YZ) -0.06 Nl-7 (XY) +0.25 Nl-8 (ZW) -0.46 Comment:

TMI2014 NRC ADM JPM RO A1-2 NUREG 1021, Revision 9 Supp 1

Appendix C Page 5 of 13 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-300-202, Step 4.5. 1.4 Performance Step: 5 CALCULATE total tilt per Section B of Attachment 7.1 at least once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (T. S. 3.5.2.4.g)

Standard: Goes to Section B of Attachment 7 .1.

Comment:

PROCEDURE NOTE: This date must be less than 30 days from the reference date in A1.

OP-TM-300-202, Attachment 7.1, Step B. 1 Performance Step: 6 Date!rime of measurements.

Standard: Obtains the given Date and Time and enters the data on Line 8.1 of Attachment 7.1.

Comment:

OP-TM-300-202, Attachment 7. 1, Step B.2a Performance Step: 7 Present Nl power.

Standard: Obtains the given Present Nl power and enters the data on Line B.2a of Attachment 7.1.

Comment:

OP-TM-300-202, Attachment 7. 1, Step B.2b

--./ Performance Step: 8 Average Nl power (Sum of B2a/4) - same number in all 4 blanks.

Standard: Examinee calculates Average Nl power as follows:

{98.4 + 100.3 + 99.1 + 98.6) I 4 = 99.1 Examinee enters 99.1 four times on Line B.2b of Attachment 7.1.

Comment:

TMI 2014 NRC ADM JPM RO A1-2 NUREG 1021, Revision 9 Supp 1

Appendix C Page 6 of 13 Form ES-C-1 PERFORMANCE INFORMATION EXAMINER NOTE: See answer key for acceptable ranges.

OP-TM-300-202, Attachment 7. 1, Step 8.3

..J Performance Step: 9 Indicated Nl tilt ([NI power/Average Nl power]-1)*100 Standard: Examinee calculates Nl tilt for each Nl as follows:

Nl5: [(98.4 I 99.1) -1]

100 = -0.706 Nl6: [(1 00.3 I 99.1) - 1]

100 = + 1.210 Nl7: [(99.1 I 99.1) -1]

100 = 0.000 Nl8: [(98.6 I 99.1) - 1]

100 = -0.504 Examinee enters the above solutions on Line 8.3 of Attachment

7.1. Comment

EXAMINER NOTE: See answer key for acceptable ranges.

OP-TM-300-202, Attachment 7. 1, Step 8.4

..J Performance Step: 10 Change in indicated OCD tilt (83-A3)

Standard: Examinee calculates the change in indicated OCD tilt as follows:

Nl5: -0.706- -0.88 = +0.174 Nl6: + 1.210 - -0.06 =+ 1.270 Nl7: 0.000- +0.25 = -0.250 Nl8: -0.504 - -0.46 = -0.044 Examinee enters the above solutions on Line 8.4 of Attachment

7.1. Comment

TMI 2014 NRC ADM JPM RO A 1-2 NUREG 1021, Revision 9 Supp 1

Appendix C Page 7 of 13 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-300-202, Attachment 7. 1, Step 8.5 Performance Step: 11 Recalibration correction [REGAL from Attachment 7.2 (=0 if no recalibration has occurred)]

Standard: Determines from intial conditions that no recalibration has occurred and enters zero on Line 8.5 of Attachment 7.1.

Comment:

EXAMINER NOTE: See answer key for acceptable ranges.

OP-TM-300-202, Attachment 7.1, Step 8.6

..J Performance Step: 12 Power correction (If 81-A1<24 hrs and no Nl calibration has occurred, then power correction= 0, or =[0.7311(82bl100)])

Standard: Examinee calculates power correction as follows:

[0.731 I (99.1 I 100)] = 0.738 Examinee enters 0. 738 on Line 8.6 of Attachment 7 .1.

Comment:

EXAMINER NOTE: See answer key for acceptable ranges.

OP-TM-300-202, Attachment 7. 1, Step B. 7

..J Performance Step: 13 Total adjustments (84+85+86)

Standard: Examinee calculates the total adjustments as follows:

Nl5: +0.174 + 0.00 + 0.737 = 0.911 Nl6: +1.270 + 0.00 + 0.737 = 2.008 Nl7: -0.250 + 0.00 + 0.737 = 0.487 Nl8: -0.044 + 0.00 + 0.737 =0.692 Examinee enters the above solutions on Line 8.7 of Attachment

7.1. Comment

TMI2014 NRC ADM JPM RO A1-2 NUREG 1021, Revision 9 Supp 1

Appendix C Page B of 13 Form ES-C-1 PERFORMANCE INFORMATION Examiner's Note: See answer key for acceptable ranges.

OP-TM-300-202, Attachment 7.1, Step 8.8

" Performance Step: 14 OCD to lCD conversion factor [application (same factor applies for all quadrants) = 1.23*(87) for no dropped rod, = 1.61 *(87) if a dropped rod exists in any quadrant]

Standard: Examinee:

o Determines from the initial conditions that no dropped rod exists.

o Calculates the OCD to lCD conversion factor as follows:

o N15: 1.23

0.911 = 1.120 o Nl6: 1.23

2.007 = 2.469 o Nl7: 1.23

0.4B7 = 0.599 o NIB: 1.23

0.693 = O.B51 o Enters the above solutions on Line 8.B of Attachment 7.1.

Comment:

Examiner's Note: See answer key for acceptable ranges.

OP-TM-300-202, Attachment 7.1, Step 8.9

" Performance Step: 15 Total adjusted OCD tilt (A2+8B)

Standard: Examinee calculates the OCD to lCD conversion factor as follows:

Nl5: + 1.23 + 1.12 = 2.350 Nl6: 2.2B + 2.46B = 4.749 Nl7: 0.04 + 0.599 = 0.639 NIB: -0.63 + O.B52 = 0.221 Examinee enters the above solutions on Line 8.9 of Attachment

7.1. Comment

TMI 2014 NRC ADM JPM RO A1-2 NUREG 1021, Revision 9 Supp 1

Appendix C Page 9 of 13 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-300-202, Attachment 7.1, Step 8.10 Performance Step: 16 Fulllncore System Tilt limit per COLR Table 1.

Standard: Examinee reviews COLR Table 1 and determines that Full lncore System Steady State Limit for Power > 60% is 4.53 and enters 4.53 on Line 8.1 0 of Attachment 7 .1.

Comment:

Evaluator Note: OP-TM-300-202, Step 4.5.1.5 is N/A OP-TM-300-202, Step 4.5. 1.6 and/or OP-TM-300-202, Attachment 7. 1, Step C. 1

-.J Performance Step: 17 DETERMINE if the total adjusted OCD tilt exceeds the full incore limit lAW T.S. 3.5.2.4.b limit and COLR Table 1.

Standard: Examinee determines that N16 total adjusted OCD tilt exceeds the COLR full incore limit of Table 1 and circles NO on Line C.1 of Attachment 7.1.

Comment:

Terminating Cue: After the RO applicant has specified the tilt exceeds COLA limits: Evaluation on this JPM is complete.

STOP TIME:

TMI2014 NRC ADM JPM RO A1-2 NUREG 1021, Revision 9 Supp 1

Appendix C Page 10 of 13 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: TMI 2014 NRC JPM RO 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 2014 NRC ADM JPM RO A 1-2 NUREG 1021, Revision 9 Supp 1

Appendix C Page 11 of 13 Form ES-C-1 VERIFICATION OF COMPLETION ANSWER KEY- DO NOT PROVIDE TO EXAMINEE ATTACHMENT7.1 KEY A. REFERENCE TILT CONDITIONS A 1. Dateffime of last recorded set of valid, steady state Full lncore System (FIS) and out-of-core detector (OCD) tilt measurements:

Yesterday I_ t = -33 Hours .

Nl5 (WX) Nl6 (YZ) Nl7 (XY) Nl8 (ZW)

A2. FISO = lncore Detector Tilt 1.23 2.28 0.04 -0.63 at Dateffime per A 1 above.

A3. OCDO = Out-of-core Detector Tilt -0.88 -0.06 0.25 -0.46 at Dateffime per A 1 above.

B. TILT MEASUREMENT CALCULATION NOTE: This date must be less than 30 days from the reference date in A 1.

B1. Dateffime of measurements: *--------~~-----------

B2a. Present Nl power B2b. Average Nl power (Sum of B2a)/4-same number in all 4 blanks B3. Indicated Nl tilt (-0.70--0.71 )(1.20-1.21) 0.000 (-.50--.51}

=([NI Power /Average Nl Power]-1)*100 B4. Change in indicated OCD tilt B3-A3 (0.17-0.18} (1.26-1.27} -0.25 (-0.04--0.05}

B5. Recalibration correction Q Q Q Q REGAL from Attachment 7.2 (= 0 if no recalibration has occurred)

B6. Power correction (0.73-0.74)(0.73-0.74)(0.73-0.74)(0.73-0.74}

IF: B1 -A 1 < 24 hrs AND no Nl recalibration has occurred, THEN Power correction = 0, OR

= [0.731/(B2b/100)]

B7. Total adjustments= B4 + B5 + B6 NOTE: 87 Acceptable Ranges (.812-1.012) (1.908-2.108) (.388-.588)(.594-.794)

B8. OCD to lCD conversion factor application (0.9-1.2} (2.3-2.6) (0.4-0.7} (0.7-1.0}

= 1 .23 * (B7) for no dropped rod

= 1.61 * (B7) if a dropped rod exists in any quadrant (same factor applies for all quadrants)

B9. Total adjusted OCD tilt= A2 + B8 (2.2-2.5} (4.6-4.9} (0.5-0.8} (0.1-0.4)

B1 0. Full lncore System Tilt limit per COLR Table 1 4.53 C. EVALUATION C1. The maximum value of B9 is less than the FIS Tilt limits in the COLA. (Circle one) Yes 8 TMI2014 NRC ADM JPM RO A1-2 NUREG 1021, Revision 9 Supp 1

Appendix C Page 12 of 13 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

The plant computer is not operational.

The computer has been off-line for 33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months .

lncore tilt was not exceeding the limits prior to the computer outage.

No associated computer alarms were in prior to the computer outage.

Recalibration of the Nl's is not and has not been required.

There are no dropped rods.

All OCD's are operable.

The following items are available for your use:

An Examinee Data Sheet containing the current Nl power level and last recorded set of valid, steady state Full lncore System (FIS) and out-of-core detector (OCD) tilt measurements.

Calculator INITIATING CUE: Calculate quadrant power tilt lAW OP-TM-300-202, QUADRANT POWER TILT AND CORE IMBALANCE USING THE OUT-OF-CORE DETECTOR SYSTEM, based on the information provided.

TIME CRITICAL: No TMI2014 NRC ADM JPM RO A1-2 NUREG 1021, Revision 9 Supp 1

Appendix C Page 13 of 13 Form ES-C-1 JPM CUE SHEET EXAMINEE DATA SHEET FIS lncore Detector Tilt on: Date: Yesterday Time: 33 Hours Ago Nl-5 (WX) +1.23 Nl-6 (YZ) +2.28 Nl-7 (XY) +0.04 Nl-8 (ZW) -0.63 OCD Out-of-Core Detector Tilt on: Date: Yesterday Time: 33 Hours Ago Nl-5 (WX) -0.88 Nl-6 (YZ) -0.06 Nl-7 (XY) +0.25 Nl-8 (ZW) -0.46 PRESENT CORE POWER Date: TODAY Time: Now Nl-5 Core Power 98.4%

Nl-6 Core Power 100.3%

Nl-7 Core Power 99.1%

Nl-8 Core Power 98.6%

TMI2014 NRC ADM JPM RO A1-2 NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: TMI- Unit 1 Task No.: 22601001 Task

Title:

RCP Station Print Read JPM No.: 2014 NRC JPM RO A2 KIA

Reference:

2.2.41 (3.5) NewJPM Examinee: NRC Examiner:

Facility Examiner: Date:

Method of testing:

Simulated Performance: X Actual Performance:

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

Initial Conditions:

Reactor Power is 20%, 600 EFPD.

RC-P-1A is Out of Service, not expected to return to service until repairs can be made during the next outage.

RC-P-1 D was tripped manually 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months ago and is ready to be restarted with the following conditions:

The RC-P-1 D-69, RC-P-1 D Control Transfer Switch, has been placed in Bypass.

The 69 Selector Switch Contact #13 is stuck in the CLOSED position.

MU-V-33D, RC-P-1 D Seal #1 Leak Off Isolation Valve, is closed with a damaged valve stem.

Fuse FD78 (XCC Fuse associated with RC-P-1D) has blown.

All other systems and components are in their normal configuration.

Task Standard:

Determine RC-P-1 D will not start from the Control Room and locally at the breaker.

Required Materials:

Print 208-113, RC-P-1 D, Rev 16

Print SS-209-066, Aux Relays of MU-13-DPS1 ,2,3 & 4, Rev 4

Print SS-209-127, Neutron Above 30% RC Pump Interlock, Rev 3

Print D8032727, Reactor Control Sheet 2 of 2, Rev W

Print 302-660, Makeup & Purification, Rev 45

OP-TM-226-000, Reactor Coolant Pumps, Rev 8 2014 TMI NRC JPM RO A2 NUREG 1021, Revision 9, Supplement 1

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

References:

Print 208-113, RC-P-1 D, Rev 16

Print SS-209-066, Aux Relays of MU-13-DPS1 ,2,3 & 4, Rev 4

Print SS-209-127, Neutron Above 30% RC Pump Interlock, Rev 3

Print 08032727, Reactor Control Sheet 2 of 2, Rev W

Print 302-660, Makeup & Purification, Rev 45

Print 302-661, Make-up & Purification, Rev 60

Print 209-070, D.C. And Miscellaneous, Rev 7

Print 209-109, Aux. Relays for RC Pump A,B & D Instruments, Rev 0

Print SS-208-350, Nuclear Service Closed Cooling Water Pumps NS-P1A To C Interlocks, Rev 3

Print SS-209-065, Auxiliary Relays of: MU42-FS, Rev 8

Print SS-208-114, 6900V Switchgear- Reactor Plant Bus 1A (1 B)

Undervoltage Relays & Potential Circuits, Rev 8

OP-TM-226-000, Reactor Coolant Pumps, Rev 8 Handouts:

Print208-113, RC-P-10, Rev 16

Print SS-209-066, Aux Relays of MU-13-DPS1 ,2,3 & 4, Rev 4

Print SS-209-127, Neutron Above 30% RC Pump Interlock, Rev 3

Print 08032727, Reactor Control Sheet 2 of 2, Rev W

Print 302-660, Makeup & Purification, Rev 45 Initiating Cue: While addressing all bolded conditions above and explaining why or why not, determine if RC-P-1 D can be started either: a) from Console Center (using CS-1) or b) locally at its breaker. Fill in the provided table.

Time Critical Task: No Validation Time: 30 minutes SIMULATOR SETUP N/A 2014 TMI NRC JPM RO A2 NUREG 1021, Revision 9, Supplement 1

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

Start Time _ _ _ __

EXAMINER CUE: Hand Examinee the following:

Print 208-113, RC-P-1 D

Print SS-209-066, Aux Relays of MU-13-DPS1,2,3 & 4

Print SS-209-127, Neutron Above 30% RC Pump Interlock

Print 08032727, Reactor Control Sheet 2 of 2

Print 302-660, Makeup & Purification Examiner Note: RC-P-1 D-69 in Bypass is addressed in this FIRST STEP.

Refer to a marked up copy of the prints for contact positions.

Examiner Note: Bolded items below identify the critical portions of the step.

Performance Step: 1 Determine if the 69 Bypass switch will allow RCP start from either Console Center or Locally when in BYPASS.

~ Standard:

Using Print 208-113:

Examinee locates the 69 selector switch contact position table in section 5G and the 69 contacts located in various places on the print.

Examinee determines that, while the 69 Bypass switch is in the Bypass position, the RCP can be started from Console Center through 69 selector switch contacts 6 and 4 as long as all starting interlocks are met.

AND

Examinee determines that, while the 69 Bypass switch is in the Bypass position, the RCP can be started locally through 69 selector switch contacts 2, 3, and 4 as long as all starting interlocks are met.

Comment:

2014 TMI NRC JPM RO A2 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION Examiner Note: RC-P-10-69 Contact #13 is addressed in this SECOND STEP.

Refer to a marked up copy of the prints for contact positions.

Examiner Note: Bolded item below identifies the critical portion of the step.

Performance Step: 2 Determine if the 69 Bypass switch Contact #13 will allow RCP start from either Console Center or Locally when in BYPASS.

-.J Standard:

Using Print 208-113:

Examinee locates the 69 selector switch contact position table in section 5G.

Examinee determines that the 69 Bypass switch Contact #13 is a Spare Contact and has no effect on the circuitry.

Examinee determines that, while the 69 Bypass switch Contact #13 is closed, the RCP can be started from both Console Center and locally as long as all starting interlocks are met.

Comment:

2014 TMI NRC JPM RO A2 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION Examiner Note: MU-V-330 is addressed in this THIRD STEP. Refer to a marked up copy of the prints for contact positions.

Examiner Note: Bolded item below identifies the critical portion of the step.

Performance Step: 3 Determine the impact of MU-V-330 being closed on starting RC-P-10 .

...J Standard:

Using Print 302-660:

Examinee locates MU-V-330 in section1C.

Examinee determines that MU-13DPT-4 will read zero.

Using Print 208-113:

Examinee determines that a starting interlock contact associated with MU-13DPS-4 is found on sheet SS-209-066.

Using Print SS-209-066:

Examinee determines MU-13-DPS4 contact found in the far right branch of the main drawing will be open, deenergizing Relay 80XMU13-dPS4.

Examinee determines that the contact associated with 80XMU13-dPS4, found in the bottom right hand corner of the print, will be open. This is the same contact shown on Print 208-113.

Examinee determines that the RCP Starting Interlock is not met and it will prevent RC-P-1 D from starting from either location.

Comment:

2014 TMI NRC JPM RO A2 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION Examiner Note: Fuse FD78 is addressed in this FOURTH STEP. Refer to a marked up copy of the prints for contact positions.

Examiner Note: Bolded item below identifies the critical portion of the step.

Performance Step: 4 Determine the impact of Fuse FD78 being blown on starting RC-P-10 .

..J Standard:

Using Print SS-209-127:

Examinee locates FD78, found in the far right branch of the main drawing.

Examinee determines that Relay 90X/RCP1 D will be deenergized.

Examinee determines that the contact associated with 90X/RCP1 D, found in the bottom right hand corner of the print, will be open. This is the same contact shown on Print 208-113.

Examinee may refer to Print 08032727 to determine contact 86/NPL position.

Using Print 08032727:

Examinee determines that the contact 86/NPL opens when neutron power is >30%. This would be the same result as a blown fuse.

Examinee determines that, although less than 30%

reactor power, the RCP Starting Interlock is not met and it will prevent RC-P-1 D from starting from either location.

Comment:

Terminating Cue: When the examinee has addressed all four bolded conditions, JPM may be terminated.

STOP TIME:

2014 TMI NRC JPM RO A2 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 9 Form ES-C-1 PERFORMANCE INFORMATION ANSWER KEY DO NOT HAND TO STUDENTS RCP can or cannot be started RCP can or cannot be started Item from Console Center? locally at the RCP breaker?

RC-P-1 D-69 in The RCP can be started from The RCP can be started locally Bypass Console Center through 69 through 69 selector switch selector switch contacts 6 contacts 2, 3, and 4.

and 4.

69 Selector Switch 69 Bypass switch Contact 69 Bypass switch Contact #13 is Contact #13 stuck #13 is a Spare Contact and a Spare Contact and has no closed has no effect on the circuitry. effect on the circuitry.

Therefore, the RCP can be Therefore, the RCP can be started from Console Center. started locally.

MU-13-DPS4 contact will be MU-13-DPS4 contact will be open, deenergizing Relay open, deenergizing Relay MU-V-330 is closed 80XMU13-dPS4. 80XMU13-dPS4.

with a damaged The contact associated with The contact associated with valve stem 80XMU13-dPS4 will be open. 80XMU13-dPS4 will be open.

Therefore, the RCP Starting Therefore, the RCP Starting Interlock is not met and it will Interlock is not met and it will prevent RC-P-1 D from prevent RC-P-1 D from starting starting from Console Center. locally.

Relay 90X/RCP1 D will be Relay 90X/RCP1 D will be deenergized. deenergized.

The contact associated with The contact associated with 90X/RCP1 D will be open. 90X/RCP1 D will be open.

Fuse FD78 is blown Contact 86/NPL opens when Contact 86/NPL opens when neutron power is >30%. This neutron power is >30%. This would be the same result as a would be the same result as a blown fuse. blown fuse.

Therefore, although less than Therefore, although less than 30% reactor power, the RCP 30% reactor power, the RCP Starting Interlock is not met Starting Interlock is not met and it and it will prevent RC-P-1 D will prevent RC-P-1 D from from starting from Console starting locally.

Center.

2014 TMI NRC JPM RO A2 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2014 TMI NRC JPM RO A2 Examinee's Name:

Date Performed:

Facility Examiner:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2014 TMI NRC JPM RO A2 NUREG 1021, Revision 9, Supplement 1

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

Reactor Power is 20%, 600 EFPD.

RC-P-1 A is Out of Service, not expected to return to service until repairs can be made during the next outage.

RC-P-1 D was tripped manually 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months ago and is ready to be restarted with the following conditions:

The RC-P-1 D-69, RC-P-1 D Control Transfer Switch, has been placed in Bypass.

The 69 Selector Switch Contact #13 is stuck in the CLOSED position.

MU-V-330, RC-P-10 Seal #1 Leak Off Isolation Valve, is closed with a damaged valve stem.

Fuse FD78 (XCC Fuse associated with RC-P-10) has blown.

All other systems and components are in their normal configuration.

INITIATING CUE: While addressing all bolded conditions above and explaining why or why not, determine if RC-P-1 D can be started either: a) from Console Center (using CS-1) or b) locally at its breaker. Fill in the provided table.

TIME CRITICAL: No RCP can or cannot be started RCP can or cannot be started Item from Console Center? locally at the RCP breaker?

RC-P-1 D-69 in Bypass (include contact numbers) (include contact numbers) 69 Selector Switch Contact #13 stuck closed (include reason why) (include reason why)

MU-V-330 is closed with a damaged valve stem (include reason why) (include reason why)

Fuse FD78 is blown (include reason why) (include reason why) 2014 TMI NRC JPM RO A2 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: TMI- Unit 1 Task No.: OF01 0009 Task

Title:

ERO Notification JPM No.: 2014 NRC JPM RO A4 KIA

Reference:

2.4.39 (3.9) Modified JPM Examinee: NRC Examiner:

Facility Examiner: Date:

Method of testing:

Simulated Performance: X 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:

A General Emergency has been declared.

You are the Third Reactor Operator on shift.

Task Standard: Complete ERO notification via Everbridge system.

Required Materials: None General

References:

EP-AA-112-100-F-06, ERO NOTIFICATION OR AUGMENTATION, Revision Q.

Handouts: EP-AA-112-100-F-06, ERO NOTIFICATION OR AUGMENTATION, Revision Q.

Initiating Cue: You are directed to call out the Three Mile Island Emergency Response Organization lAW EP-AA-112-100-F-06, ERO Notification or Augmentation.

Time Critical Task: Yes Validation Time: 10 minutes 2014 TMI NRC JPM RO A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP Utilize the CAS workstation for this JPM. Ensure the computer has internet access and the phone used for the ERO Notification is set up in the Simulator and is UNPLUGGED.

2014 TMI NRC JPM RO A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 15 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Start Time _ _ _ __

Examiner Cue: When the examinee has located a copy of the procedure, then provide the Examinee a copy of EP-AA-112-100-F-06, ERO Notification or Augmentation.

Performance Step: 1 Locate the Simulator phone for ERO Notification.

Standard:

Examinee locates the Simulator phone for ERO Notification Phone at the CRS work station in the Simulator.

Examinee locates the local copy of EP-AA-112-1 00-F-06, ERO Notification or Augmentation.

Comment:

Procedure Note: The automated system will initiate the call out of management and bargaining unit personnel required to meet the ERO staffing requirements. Additional staffing of personnel shall be the responsibility of the individual Managers and Directors in the TSC I OSC I EOF I ENC IJIC following initial activation of those facilities.

Section 1 - Initiate Activation I Termination of Notification System using World Wide Web Section 2 - Initiate Activation I Termination of Notification System using live Everbridge Agent Section 3 - Initiate Activation I Termination of Notification System using a Standard Phone Section 4 - Initiate Alternate Pager Notification 2014 TMI NRC JPM RO A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 15 Form ES-C-1 PERFORMANCE INFORMATION EP-AA-112-1 00-F-06, Step 1. 1 CIRCLE the appropriate station specific Member ID and Station Performance Step: 2 Password number from the table below.

Standard: Examinee circles the following:

TMI under Station

730143311 under Member ID

730143311 under Password Comment:

EP-AA-112-1 00-F-06, Step 1.2 Performance Step: 3 CIRCLE the appropriate Activation I Termination Scenario Number for the event from the table below.

Standard: Examinee circles the following:

Scenario 1 - Actual Event Respond to Facility - For Alert, Site Area, or General Emergency, or Security Events with On Site ERO reporting Comment:

EP-AA-112-1 00-F-06, Step 1.3 Performance Step: 4 OPEN (double-click) the Everbidge Aware shortcut icon from your desktop computer. If shortcut Icon is not available or does not open, then ACCESS the World Wide Web and go to www.everbridge.net Standard: Examinee opens the Everbridge Aware shortcut from the desktop computer.

Comment:

2014 TMI NRC JPM RO A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 15 Form ES-C-1 PERFORMANCE INFORMATION EP-AA-112-1 00-F-06, Step 1.4 Performance Step: 5 ENTER the appropriate station specific Member 10 and Password from Step 1.1 and SELECT {click) Go.

Standard:

Examinee enters TMI as Station

Examinee enters 730143311 as Member 10

Examinee enters 730143311 as Password Comment:

EP-AA-112-100-F-06, Step 1.5 Performance Step: 6 VERIFY the appropriate Station Name is displayed.

Standard: Examinee verifies TMI is displayed Comment:

Examiner Note: If the examinee selects scenario 1, an actual ERO callout will occur.

DO NOT LET EXAMINEE SELECT SCENARIO 1.

INSTRUCT EXAMINEE TO SELECT SCENARIO 11.

EP-AA-112-100-F-06, Step 1.6 Performance Step: 7 SELECT (click) the appropriate scenario identified in Step 1.2.

Standard: Examinee selects Scenario 11 Comment:

EP-AA-112-1 00-F-06, Step 1. 7 Performance Step: 8 VERIFY the appropriate scenario is displayed.

Standard: Examinee verifies Scenario 11 is displayed.

Comment:

2014 TMI NRC JPM RO A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 15 Form ES-C-1 PERFORMANCE INFORMATION Examiner Note: Step 1.8 is N/A.

EP-AA-112-100-F-06, Step 1.9 Performance Step: 9 If the scenario displayed is correct, then SELECT (click) Send Message.

Standard: Examinee determines that the scenario displayed is correct and selects "Send Message".

Comment:

EP-AA-112-1 00-F-06, Step 1.10 Performance Step: 10 VERIFY "Active Scenario Broadcasts" is displayed.

Standard: Examinee verifies "Active Scenario Broadcasts" is displayed.

Comment:

EP-AA-112-1 00-F-06, Step 1.11 Performance Step: 11 RECORD the time of the scenario broadcast.

Standard: Examinee records current time.

Comment:

EP-AA-112-100-F-06, Step 1.12 Performance Step: 12 SELECT "Log Out to exit the Everbridge Aware Notification program.

Standard: Examinee selects "Log Out.

Comment:

2014 TMI NRC JPM RO A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 15 Form ES-C-1 PERFORMANCE INFORMATION EXAMINER CUE: State: "Ten minutes has elapsed and no call to the Control Room has been received".

EXAMINER NOTE: Step 1.13 is N/A EP-AA-112-1 00-F-06, Step 1. 14 Performance Step: 13 If a confirmation call is not received in the Control Room within 10 minutes confirming scenario activation, then proceed to Section 2, Initiate Activation I Termination of Notification System Using Live Everbridge Agent.

Standard: Examinee recognizes that a confirmation call has not been received and goes to Section 2.

Comment:

EXAMINER NOTE: In step 2.1, the examinee may circle more information on the TMI line, but it is not required.

EP-AA-112-1 00-F-06, Step 2.1 Performance Step: 14 CIRCLE the appropriate station specific Organization Name, Member ID, Response to Hint Question from the table below.

Standard: Examinee circles the following:

Exelon - Three Mile Island under Organization Name

730143311 under Member ID

Exelon under Response to Hint Question Comment:

2014 TMI NRC JPM RO A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 15 Form ES-C-1 PERFORMANCE INFORMATION EP-AA-112-100-F-06, Step 2.2 Performance Step: 15 CIRCLE the appropriate Activation I Termination Scenario Number for the event from the table below.

Standard: Examinee circles the following:

Scenario 1 - Actual Event Respond to Facility - For Alert, Site Area, or General Emergency, or Security Events with On Site ERO reporting.

Comment:

EXAMINER CUE: State: "You hear a busy signal" when the examinee attempts to make a phone call in the next two steps.

EP-AA-112-100-F-06, Step 2.3 Performance Step: 16 DIAL the ERO Notification System Activation phone number: 1-877-220- 4911.

Standard: Examinee dials 1-877-220-4911, recognizes that there is a busy signal, and continues on.

Comment:

EP-AA-112-100-F-06, Step 2.4 Performance Step: 17 If the number is busy or does not answer after a 2nd attempt, then PROCEED to Section 3 Initiate Activation I Termination of Notification System Using Standard Phone.

Standard: Examinee goes to Section 3.

Comment:

2014 TMI NRC JPM RO A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 9 of 15 Form ES-C-1 PERFORMANCE INFORMATION EP-AA-112-1 00-F-06, Step 3.1 Performance Step: 18 CIRCLE the appropriate station specific Member 10 and Station Password number from the table below.

Standard: Examinee circles the following:

TMI under Station

730143311 under Member ID

730143311 under Password Comment:

EP-AA-112-1 00-F-06, Step 3.2 Performance Step: 19 CIRCLE the appropriate Activation I Termination Scenario Number for the event from the table below.

Standard: Examinee circles the following:

Scenario 1 - Actual Event Respond to Facility - For Alert, Site Area, or General Emergency, or Security Events with On Site ERO reporting.

Comment:

EXAMINER CUE: When the examinee attempts to make a phone call in the next step, state: "Welcome to EverBridge Aware. Please enter member ID followed by the pound SIGN".

EP-AA-112-1 00-F-06, Step 3.3 Performance Step: 20 DIAL the Everbridge AWARE system activation phone number-1-888-440-4911 .

-./ Standard: Examinee dials 1-888-440-4911.

Comment:

2014 TMI NRC JPM RO A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 10 of 15 Form ES-C-1 PERFORMANCE INFORMATION EXAMINER NOTE: Steps 3.4 and 3.5 are N/A.

EXAMINER CUE: If the examinee enters a number other than 730143311 #,

then state: "Number not recognized".

EP-AA-112-100-F-06, Step 3.6 Performance Step: 21 When the System prompts "Please enter member ID followed by the #sign" then ENTER the member ID followed by the "#" sign.

v Standard: Examinee enters 730143311#

Comment:

EXAMINER CUE: State: "Please enter your password followed by the pound BUTTON".

EP-AA-112-100-F-06, Step 3.7 Performance Step: 22 When the system prompts "Please enter your Password followed by the # sign" then ENTER the Password followed by the "#"

button.

v Standard: Examinee enters 730143311 #

Comment:

EXAMINER CUE: State: "Press 3 to launch a broadcast scenario now".

EP-AA-112-100-F-06, Step 3.8 Performance Step: 23 When prompted, PRESS 3 to launch a broadcast scenario now.

v Standard: Examinee presses 3.

Comment:

2014 TMI NRC JPM RO A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 11 of 15 Form ES-C-1 PERFORMANCE INFORMATION EXAMINER CUE: State: "Press 1 to select your scenario number".

EP-AA-112-100-F-06, Step 3.9 Performance Step: 24 When prompted, PRESS 1 to select your scenario number

..J Standard: Examinee presses 1.

Comment:

EXAMINER CUE: State: "Please enter your scenario number followed by the pound KEY".

EP-AA-112-100-F-06, Step 3.10 Performance Step: 25 When the System states "Please enter your scenario number followed by the # key" A. For "Actual Event with Response to Facility" PRESS 1 Then#

B. For "Unusual Event ERO Notification Only PRESS 2 Then C. For "Actual Event Alternate Reporting Location" PRESS 3 Then#

D. For "Scenario Event Termination" PRESS 4 Then#

E. For "Scenario Activation Cancellation" PRESS 12 Then #

..J Standard: Examinee presses 1#

Comment:

2014 TMI NRC JPM RO A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 12 of 15 Form ES-C-1 PERFORMANCE INFORMATION EXAMINER CUE: If entered correctly, state: "You have selected Scenario 1, actual event with response to facility. If this is correct, press pound, otherwise press star".

If entered incorrectly, use performance step 25 to find the name of the scenario and state the name. The examinee should then press star and repeat performance step 25.

EP-AA-112-1 00-F-06, Step 3. 11 Performance Step: 26 If the event name is correct, then PRESS#.

-./ Standard: Examinee presses#.

Comment:

EXAMINER CUE: State: "To launch this scenario now, press 1. To return to the previous menu, press 9. To end this call, simply hang up".

EP-AA-112-1 00-F-06, Step 3. 12 Performance Step: 27 The System will state "To launch this scenario now, press 1, to return to the previous menu, PRESS 9, to end this call, simply hang up. PRESS 1."

-./ Standard: Examinee presses 1.

Comment:

2014 TMI NRC JPM RO A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 13 of 15 Form ES-C-1 PERFORMANCE INFORMATION EXAMINER CUE: State: "Your scenario will be launched momentarily, results for this broadcast can be obtained by logging into Everbridge".

EP-AA-112-100-F-06, Step 3.13 Performance Step: 28 When the activation is complete and the System states "Your scenario will be launched momentarily, results for this broadcast can be obtained by logging into Everbridge", then HANG UP the phone.

Standard: Examinee hangs up the phone Comment:

EP-AA-112-100-F-06, Step 3.14 Performance Step: 29 RECORD the time of the scenario broadcast Standard: Examinee records the current time.

Comment:

Terminating Cue: When the time of the scenario broadcast has been recorded, JPM may be terminated.

STOP TIME:

2014 TMI NRC JPM RO A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 14 of 15 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2014 NRC JPM RO A4 Examinee's Name:

Date Performed:

Facility Examiner:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2014 TMI NRC JPM RO A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 15 of 15 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

A General Emergency has been declared.

You are the Third Reactor Operator on shift.

INITIATING CUE: You are directed to call out the Three Mile Island Emergency Response Organization lAW EP-AA-112-100-F-06, ERO Notification or Augmentation.

TIME CRITICAL: Yes 2014 TMI NRC JPM RO A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: TMI- Unit 1 Task No.: GOP002004 Task

Title:

Review and approve an Estimated JPM No.: TMI2014 NRC ADM Critical Boron Concentration JPM SRO A1-1 Calculation KIA

Reference:

2.1.25 (4.2) Modified from Bank JPM: TMI08 NRC JPM A1-1SRO 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 yesterday at 1000.

The reactor is expected to return to critical at time T =+35 hours after the reactor trip.

Reactor Power was 80%

The unit had been on-line for 208 days.

The last down power was 21 days ago.

Cycle Burnup is 470 EFPD.

TAVE = 532°F

Current Boron Concentration = 1675 PPM

The Desired Critical Rod Position is: 85% WD on CRG-6.

The FINAL MIXED BORON DEPLETION CORRECTION FACTOR as specified in the control room log is .90

No DTSQA-approved software is available for calculations.

Task Standard: Calculate an Estimated Critical Boron Concentration and find errors.

Required Materials:

Calculator

Ruler TMI 2014 NRC ADM JPM SRO A1-1 NUREG 1021, Revision 9 Supp 1

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

References:

OP-TM-300-000, REACTIVITY AND POWER DISTRIBUTION CALCULATIONS, Rev. 5 OP-TM-300-402, ESTIMATED CRITICAL BORON CONCENTRATION, Rev. 3 Handouts: OP-TM-300-000, REACTIVITY AND POWER DISTRIBUTION CALCULATIONS, Rev. 5 OP-TM-300-402, ESTIMATED CRITICAL BORON CONCENTRATION, Rev. 3 Initiating Cue: You are the CAS. Review and Approve the calculated Estimated Critical Boron calculation lAW OP-TM-300-402, ESTIMATED CRITICAL BORON CONCENTRATION.

Time Critical Task: No Validation Time: 30 minutes SIMULATOR SETUP N/A TMI2014 NRC ADM JPM SRO A1-1 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:

EVALUATOR CUE: Provide a clean copy of OP-TM-300-402 and a filled out Attachment 7.1 (found as an attachment to this JPM) to the Examinee OP- TM-300-402 Step 3.0 Performance Step: 1 Locates/reviews procedure Limits and Precautions.

Standard: The Examinee reviews LIMITS AND PRECAUTIONS.

Comment:

OP-TM-300-402, Step 4.1 Performance Step: 2 Perform calculations per Attachment 7.1 or DTSQA-approved software.

Standard: The Examinee determines from the initial conditions that DTSQA-approved software is not available and goes to Attachment 7.1.

Comment:

OP-TM-300-402 Attachment 7. 1 Step 1 Performance Step: 3 Verify the average reactor coolant temperature, T AvE, from the Initial Conditions.

Standard: The Examinee verifies TAvE on Initial Conditions equals 532+/-2°F Comment:

TMI2014 NRC ADM JPM SRO A1-1 NUREG 1021, Revision 9 Supp 1

Appendix C Page 4 of 13 Form ES-C-1 PERFORMANCE INFORMATION OP- TM-300-402 Attachment 7. 1 Step 2 Performance Step: 4

Record Cycle Burnup.

Standard: The Examinee determines 470 EFPD from Initial Conditions and verifies correct value on Line 2 of Attachment 7.1.

Comment:

OP-TM-300-402 Attachment 7. 1 Step 3 Performance Step: 5 Record Current Measure Boron Concentration Standard: The Examinee determines 1675 ppm from Initial Conditions and verifies correct value on Line 3 of Attachment 7.1.

Comment:

OP-TM-300-402 Attachment 7. 1 Step 4 Performance Step: 6 Record the Desired Critical Rod Positions Standard: The Examinee determines the desired critical rod position to be 85% withdrawn on CRG 6 from the initial conditions and recognizes the group positions as follows:

CRG 1-4 100% WD CRG 5 100%WD CRG 6 85%WD CRG 7 10% WD The Examinee recognizes the following discrepancy on Line 4 of Attachment 7.1: Group 7 has incorrectly been recorded to be O%WD.

Comment:

OP-TM-300-402 Attachment 7. 1 Step 5 Performance Step: 7 Determine and record Fuel Excess Reactivity lAW Figure 2 of OP-TM-300-000

..J Standard: The Examinee interprets Figure 2 and verifies (between 9.4%

and 9.6%} ~k/k has been recorded on Line 5 of Attachment 7.1.

Comment:

TMI2014 NRC ADM JPM SRO A1-1 NUREG 1021, Revision 9 Supp 1

Appendix C Page 5 of 13 Form ES-C-1 PERFORMANCE INFORMATION OP- TM-300-402 Attachment 7. 1 Step 6 Performance Step: 8 Determine and record the Desired Critical CRG 5-7 Reactivity Worth lAW Figure SA of OP-TM-300-000

-1 Standard: The Examinee interprets Figure SA and verifies (between -1.0%

to -1.2%) dklk has been recorded on Line 6 of Attachment 7.1.

Comment:

OP-TM-300-402 Attachment 7. 1 Step 7 Performance Step: 9 Determine and record the Xenon Reactivity Worth lAW Figure 13 of OP-TM-300-000.

-1 Standard: The Examinee interprets Figure 13 and verifies (between -0.90%

to -0.95%) dklk has been recorded on Line 7 of Attachment 1.

The Examinee recognizes the following discrepancy on Line 7 of Attachment 7.1: Xenon Reactivity has incorrectly been recorded as -1 .15%.

Comment:

OP-TM-300-402 Attachment 7. 1 Step 8 Performance Step: 10 Determine and record the Samarium and Plutonium Buildup lAW Figure 15 of OP-TM-300-000.

-1 Standard: The examinee determines 35 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months since shutdown from initial conditions and verifies correct value on Line 8 of Attachment 7.1.

The Examinee interprets Figure 15 and verifies (between

-0.07% to -0.08%) dklk has been recorded on Line 8 of Attachment 7.1 Comment:

TMI2014 NRC ADM JPM SRO A1-1 NUREG 1021, Revision 9 Supp 1

Appendix C Page 6 of 13 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-300-402 Attachment 7. 1 Step 9 Performance Step: 11 Calculate and record the Boron Reactivity Worth For Criticality Calculation.

-! Standard: The Examinee adds Lines 5 + 6 + 7 + 8 and determines the value (between 7.175% to 7.535%) dklk should be recorded on Line 9 of Attachment 7.1 The Examinee recognizes the following discrepancy on Line 9 of Attachment 7.1: Boron Reactivity Worth has incorrectly been been recorded as + 11.82%.

Comment:

OP-TM-300-402 Attachment 7. 1 Step 10 Performance Step: 12 Determine and record the Inverse Boron Worth lAW Figure 8 of OP-TM-300-000.

-! Standard: The Examinee interprets Figure 8 and verifies (between 133.5 to 134.5) ppmB I %dk/k has been recorded on Line 10 of Attachment 7.1 Comment:

OP-TM-300-402 Attachment 7.1 Step 11 a Performance Step: 13 Calculate and record the Critical Boron Concentration

-! Standard: The Examinee multiplies lines 9 and 10 and determines (between 957.9 and 1013.5) ppmB should be recorded on Line 11 a of Attachment 7.1.

The Examinee recognizes the following discrepancy on Line 11 a of Attachment 7.1 : Critical Boron Concentration has incorrectly been recorded (due to error carried forward).

Comment:

OP-TM-300-402 Attachment 7. 1 Step 11 b TMI 2014 NRC ADM JPM SRO A 1**1 NUREG 1021, Revision 9 Supp 1

Appendix C Page 7 of 13 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 14 Record the Final Mixed Boron Depletion Correction Factor.

Standard: The Examinee determines 0.9 from Initial Conditions and verifies correct value on Line 11 b of Attachment 7.1 Comment:

OP-TM-300-402 Attachment 7. 1 Step 11 c Performance Step: 15 Calculate and record the Estimated Measured Critical Boron Concentration Standard: The Examinee divides line 11 a by line 11 b and determines (between 1064 and 1126) ppmB should be recorded on Line 11 c of Attachment 7.1 The Examinee recognizes the following discrepancy on Line 11 c of Attachment 7.1: Estimated Measured Critical Boron Concentration has incorrectly been recorded (due to error carried forward).

Comment:

OP-TM-300-402 Attachment 7. 1 Step 12 TMI2014 NRC ADM JPM SRO A1-1 NUREG 1021, Revision 9 Supp 1

Appendix C Page 8 of 13 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 16 If this is a transient Xenon startup, then RECORD the interval that ECB is valid. Use the Xe value from Line 7 and a plot or table of Xe behavior with time. Estimate when Xe worth will be more or less negative than the value in Line 7 by 0.5% ~klk.

Standard: The Examinee:

o Determines that this is a transient Xenon startup.

o Subtracts -0.5 ~klk from -0.9 ~klk. and comes up with

-1.4 ~klk.

o Interprets Figure 13 and determines that -1.4 ~klk.

correlates with 28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months after shutdown (27-29).

o Determines that 28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months after shutdown is 1400 today (1300-1500) o Subtracts +0.5 ~klk from -0.9 ~klk. and comes up with

-0.4 ~klk.

o Interprets Figure 13 and determines that 0.4 ~klk.

correlates with 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after shutdown (46-50).

o Determines that 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after shutdown is 1000 tomorrow (0800-1200) o Records the following on Line 12 of Attachment 7.1 :

o "from" date as today.

o from" time as calculated above.

o "to" date as tomorrow.

o "to" time as calculated above.

The Examinee recognizes the following discrepancy on Line 12 of Attachment 7.1: Line 12 has been N/A'd.

Comment:

OP-TM-300-402 Attachment 7. 1 Performance Step: 17 Sign and add date/time

.,; Standard: The Examinee does NOT sign and add the date and time at the bottom of Attachment 7.1.

Examinee returns the attachment unapproved.

Comment:

Terminating Cue: When the candidate returns the completed Attachment 7.1 to the examiner: This JPM is complete.

STOP TIME:

TMI 2014 NRC ADM JPM SRO A1-1 NUREG 1021, Revision 9 Supp 1

Appendix C Page 9 of 13 Form ES-C-1 VERIFICATION OF COMPLETION ANSWER KEY- DO NOT PROVIDE TO EXAMINEE OP-TM~2 Rec'lision 3 Page 3of-t ATTACHMENT 7.1 Estimai@d Critical Boron Concenlration Calculation Data Sheet Page 1 of 1 NOTE: Refer t1 ~ 1.2 t1 ~e.E tlit6 dlalla meet om l"la)' be~ 1n any~. ~~iiltbta~a&~ ~

~*~an~~*

CALCUt..A.llON ~ fOIRAN EC8 AT DAl'Eff!ME Current Date I Time TAW (~T>>JJI**~:Z:l'F) 532 "F CYCLE BURNtiP 470 EFPO CI..IRRENT MEASURED BCftJJH CONCBfTRATION 1675 pprnB

CRG 1,-4 -----'1'-=00"-*% 'l"'D

eRGS 100 % 'l"'D

CRGi 85 ~WD

*CRG7 Q-(10) ~'l"'D FUEl EXCESS FEACTIV'fTY (flG 2~ 9.4 to 9.6 %Mil DESIRED CRI.TICAL CRG 5-7 RE.ACTMTY WORTH fFIG SA) -1.0 to -1.2 %Mil X'.BKlN REACTMT't' WORTH J,PPC, REACTOR BNGR., F1G tl) ..:t-..t5 (-0.85 to -0.95) .% Mil

~UM AND PU.fi"Ct.lll.lM BULIJUP (AG 15)

TIUE SINCE SHLll'DOWN 35 HRS

REACTMrt IJUE lO BULIJUP -0.07 to -0.08 .% ~ll

'9.

{5+6+7+6)* +1-1-..Ba (7.175 to 7.535) %.~11:

!tNERSE B~ warn-! (fiG B} 133.5 to 134.5 ppT~Bt% Alll CRI.TICAl BCftJJH CONCEN'T'RATION (957 .9 to 1013.5) 11.a. *CRrnCAL BORON CCNCENTRATION 1:9 :t 10)

t583.9 111>. FDriAl MOO:O ~ DEPLEllON CORRECTION FACTOR 0.9 (PPC. ~ Room leg. Rea::lm ~)

(1064 to 1126) 11C. ESTIUA.TEDMEA...~RED CRITICAL~ OONCBHRATION (11 1759.9 ~

!f1flls ~a 1rana:mt: ~ eatl.ip0 tt's1 RECORD 1M~ l1at ECS 15 *waa Fram: O~lnme NIA Today 11300-1500 To: Da"Emme: NIA Tomorrow I 0800-1200 OATEffll'ltE. Today 11 Hr ago APPROVB:l BY ~SRO~ - - - - - - - - - - - - - - OATEmME _ _ _ __

ANSWER KEY- DO NOT PROVIDE TO EXAMINEE TMI2014 NRC ADM JPM SRO A1-1 NUREG 1021, Revision 9 Supp 1

Appendix C Page 10 of 13 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: TMI2014 NRC ADM 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:

TMI2014 NRC ADM JPM SRO A1-1 NUREG 1021, Revision 9 Supp 1

Appendix C Page 11 of 13 Form ES-C-1 JPM CUE SHEET Initial Conditions:

A sequential trip of both main feedwater pumps resulted in a reactor trip yesterday at 1000.

The reactor is expected to return to critical at time T =+35 hours after the reactor trip.

Reactor Power was 80%

The unit had been on-line for 208 days.

The last down power was 21 days ago.

Cycle Burnup is 470 EFPD.

TAVE = 532°F

Current Boron Concentration = 1675 PPM

The Desired Critical Rod Position is: 85% WD on CRG-6.

The FINAL MIXED BORON DEPLETION CORRECTION FACTOR as specified in the control room log is .90

No DTSQA-approved software is available for calculations.

INITIATING CUE: You are the CRS. Review and Approve the calculated Estimated Critical Boron calculation lAW OP-TM-300-402, ESTIMATED CRITICAL BORON CONCENTRATION.

TIME CRITICAL: No TMI2014 NRC ADM JPM SRO A1-1 NUREG 1021, Revision 9 Supp 1

Appendix C Page 12 of 13 Form ES-C-1 JPM CUE SHEET OP-TM-300-402 Re¥iision 3 Page 3 of4 AlTACHMEHT 7.1 Esti.mah!d Critical Boron Concentration Calct.dation Data Sh~t Page 1 of 1 NOTE: Refer tJ Attact"rnerl7 2b ~ tf'!J6 u.a &tteel Data ITiii)' be~ !fl any~. ~~iil~~iiil&~ ~al

~ lldcats5.an ~t~.

C/ILCl...llllliDN !:S FOR AN EC5 AT OA'IE!TI.AE Current Date /1 Hour ago

1. TA'lli ~TIM!!- 532 :2: TF) 5...'3,2 "F

2:. CYCLE BURMJP 470 EFPD

3. CURRENT MEASURED BORON CONICEKTFt!\T!ON 1675 ppmB 4 DESIREDCR.IT!CALROO~

CRG t-4 _ _...:,.100==-*% wo

eRGS 100 %WO

CRG6 85 ~wo

CRG7 0 ~WD FUEl Exc:ESS R.IEACTIVIT'f (FIG :2) 9.5 ti. DESIRED CR.mCAL CRG 5-7 REACTMTY WORTH !FIG SA) -1.1

7. ~ REACTMTY WORTH (PPC, R.IEACTOR ENGR, F'fG t3J -1.15 35 HRS

REACTMTf IJUE TO BUir...IJUP -0.075

'9. E!CRON R~ WORTH FOR CRIDCI!JJTY CALCIA.ATION

{5 + 15 + 7 + B) * + 11.82 111 IN\IERSE BORa\! WCRT:+i (flG 6~ 134.0 ppmB.I%Mll t 1. CRITICAL BORON CONCEN'TRAT!ON 11a CRJnc!IL ~ CCNCENTRATION (9 :( 10) - 1583.9 . J:PT15 1UJ. FINAL MIXED BOReN DEPLE:llON C.oRflECTION FACTOR 0.9

!P~C. ~Roof!"! log..~~

1H::_ ESTIMATEDME.ASURED CRITICAl BORONCONCENlRATION{11ad Hb) 1759.9 ~

12 I'I!Ui !& a 1~ Xenon~~ then RECOftD 1:tle! *fTiefVal l1at ECS IS val:i fi'Ql'Tl: ~ N/A To:~ N/A Current Date I CJ!LCIA.ATED BY: DATEfflME 1 Hour ago APPROVEDBY(SRO~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ DATI8TIME _ _ _ _ __

TMI2014 NRC ADM JPM SRO A1-1 NUREG 1021, Revision 9 Supp 1

Appendix C Page 13 of 13 Form ES-C-1 JPM CUE SHEET TMI2014 NRC ADM JPM SRO A1-1 NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: TMI- Unit 1 Task No.: AOP602001 Task

Title:

Review OP-TM-300-202, JPM No.: TM12014 NRC ADM QUADRANT POWER TILT AND JPM SRO A1-2 CORE IMBALANCE USING THE OUT-OF-CORE DETECTOR SYSTEM. Calculation KIA

Reference:

2.1.37 4.3 I 4.6 Facility Bank JPM 148 (Modified)

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 computer is not operational.

The computer has been off-line for 33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months .

lncore tilt was not exceeding the limits prior to the computer outage.

No associated computer alarms were in prior to the computer outage.

Recalibration of the Nl's is not and has not been required.

There are no dropped rods.

All OCD's are operable.

The following items are available for your use:

An Examinee Data Sheet containing the current Nl power level and last recorded set of valid, steady state Fulllncore System (FIS) and out-of-core detector (OCD) tilt measurements.

Calculator Task Standard: Calculate quadrant power tilt and identify critical errors.

TMI2014 NRC ADM JPM SRO A1-2 NUREG 1021, Revision 9

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

COLR

Calculator General

References:

OP-TM-300-202, QUADRANT POWER TILT AND CORE IMBALANCE USING THE OUT-OF-CORE DETECTOR SYSTEM, Revision 2

COLR

Technical Specifications An Attachment 7.1, OCD-ICD Tilt Correlation, KEY is attached to this JPM for evaluator use/information. Ensure that the KEY is NOT provided to the applicants.

Handout:

OP-TM-300-202, QUADRANT POWER TILT AND CORE IMBALANCE USING THE OUT-OF-CORE DETECTOR SYSTEM

Filled out attachment 7.1 (attached behind the JPM CUE SHEET)

Examinees Data Sheet (attached behind the JPM CUE SHEET) containing the current Nl power level and recorded set of valid, steady state Fulllncore System (FIS) and out-of-core detector (OCD) tilt measurements.

Initiating Cue: Review and approve the calculation for quadrant power tilt lAW OP-TM-300-202, QUADRANT POWER TILT AND CORE IMBALANCE USING THE OUT-OF-CORE DETECTOR SYSTEM, based on the information provided, and determine any applicable Tech Specs.

Time Critical Task: N/A Validation Time: 25 minutes SIMULATOR SETUP N/A TMI 2014 NRC ADM JPM SRO A 1-2 NUREG 1021, Revision 9

Appendix C Page 3 of 19 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

EVALUATOR NOTE: Ensure that the KEY is NOT provided to the applicants.

OP-TM-300-202, Step 4.1 Performance Step: 1 IAAT the PPC, FIDMS, and FIS are all operable, then EXIT this procedure.

Standard: Determines from the given initial conditions that the PPC is not operable and continues.

Comment:

OP-TM-300-202, Step 4.2 Performance Step: 2 IF all OCDs are operable, THEN PERFORM the following:

(1) DETERMINE tilt lAW Step 4.5.

Standard: Examinee goes to Step 4.5.

Comment:

TMI 2014 NRC ADM JPM SRO A 1-2 NUREG 1021, Revision 9

Appendix C Page 4 of 19 Form ES-C-1 PERFORMANCE INFORMATION PROCEDURE NOTE: Tilt calculation must be performed once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the tilt alarm is inoperable.

OP-TM-300-202, Step 4.5.1.1-4.5.1.2 Performance Step: 3 VERIFY computer alarms package for incore tilt was not in alarm immediately prior to loss of PPC, FIDMS, or FIS.

( 1) IF the alarms package was in the alarm state, THEN TAKE action as necessary to address the alarm before proceeding in this procedure.

Standard: Verifies the computer alarms package was not in an alarm state immediately prior to the loss of computer.

Comment:

TMI2014 NRC ADM JPM SRO A1-2 NUREG 1021, Revision 9

Appendix C Page 5 of 19 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-300-202, Step 4.5.1.3

"' Performance Step: 4 RECORD last set of valid, steady state incore (FISo) and out-of-core (OCD0 ) tilt measurements and the date and time the data was obtained on Attachment 7.1.

Standard: Examinee obtains the date and time that the data from the given data sheet and enters the data on Line A 1 of Attachment 7 .1.

Examinee obtains the FISo incore tilt measurements from the given data sheet and determines the following data should be recorded on Line A2 of Attachment 7.1:

Nl-5 (WX) +1.23 Nl-6 (YZ) +2.28 Nl-7 (XV) +0.04 Nl-8 (ZW) -0.63 Examinee obtains the OCD out-of-core tilt measurements from the given data sheet and determines the following data should be recorded on Line A3 of Attachment 7.1:

Nl-5 (WX) -0.88 Nl-6 (YZ) -0.06 Nl-7 (XY) +0.25 Nl-8 (ZW) -0.46 The Examinee recognizes the following discrepancy on Lines A2 and A3 of Attachment 7.1: FISo incore tilt measurements have been improperly entered on Line A3 and OCDo out-of-core tilt measurements have been improperly entered on Line A2.

Comment:

OP-TM-300-202, Step 4.5. 1.4 Performance Step: 5 CALCULATE total tilt per Section B of Attachment 7.1 at least once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (T. S. 3.5.2.4.g)

Standard: Goes to Section B of Attachment 7.1.

Comment:

TMI2014 NRC ADM JPM SRO A1 .. 2 NUREG 1021, Revision 9

Appendix C Page 6 of 19 Form ES-C-1 PERFORMANCE INFORMATION PROCEDURE NOTE: This date must be less than 30 days from the reference date in A1.

OP-TM-300-202, Attachment 7.1, Step B. 1 Performance Step: 6 Date!fime of measurements.

Standard: Determines the Date and Time and verifies the data has been recorded on Line 8.1 of Attachment 7 .1.

Comment:

OP-TM-300-202, Attachment 7. 1, Step B.2a Performance Step: 7 Present Nl power.

Standard: Examinee obtains the Present Nl power from the given data sheet and verifies the following data has been recorded on Line B.2a of Attachment 7.1 :

Nl-5 Core Power 98.4%

Nl-6 Core Power 100.3%

Nl-7 Core Power 99.1%

Nl-8 Core Power 98.6%

Comment:

OP-TM-300-202, Attachment 7. 1, Step B.2b Performance Step: 8 Average Nl power (Sum of B2a/4) - same number in all 4 blanks.

-./ Standard: Examinee calculates Average Nl power as follows:

(98.4 + 100.3 + 99.1 + 98.6) I 4 = 99.1 Examinee verifies 99.1 has been recorded four times on Line B.2b of Attachment 7.1.

Comment:

TMI2014 NRC ADM JPM SRO A1-2 NUREG 1021, Revision 9

Appendix C Page 7 of 19 Form ES-C-1 PERFORMANCE INFORMATION EXAMINER NOTE: See answer key for acceptable ranges.

OP-TM-300-202, Attachment 7. 1, Step 8.3 Performance Step: 9 Indicated Nl tilt ([NI power/Average Nl power]-1)*100 v Standard: Examinee calculates Nl tilt for each Nl as follows:

Nl5: [(98.4 I 99.1) -1]

100 = -0.706 Nl6: [(100.3 I 99.1) -1]

100 = +1.210 Nl7: [(99.1 I 99.1) -1]

100 = 0.000 Nl8: [(98.6 I 99.1)- 1]

100 = -0.504 The Examinee recognizes the following discrepancy on Line 83 of Attachment 7.1: The negative sign is missing from Nl8.

Comment:

EXAMINER NOTE: See answer key for acceptable ranges.

OP-TM-300-202, Attachment 7. 1, Step 8.4 Performance Step: 10 Change in indicated OCD tilt (83-A3) v Standard: Examinee calculates the change in indicated OCD tilt as follows:

Nl5: -0.706--0.88 = +0.174 Nl6: + 1.210 - -0.06 = + 1.270 Nl7: 0.000- +0.25 = -0.250 Nl8: -0.504 - -0.46 =-0.044 The Examinee recognizes the following discrepancy on Line 84 of Attachment 7.1: All four entries are wrong due to previous errors (Error carried forward).

Comment:

TMI2014 NRC ADM JPM SRO A1-2 NUREG 1021, Revision 9

Appendix C Page 8 of 19 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-300-202, Attachment 7. 1, Step 8.5 Performance Step: 11 Recalibration correction [REGAL from Attachment 7.2 (=0 if no recalibration has occurred)]

Standard: Determines from initial conditions that no recalibration has occurred and verifies zero has been recorded on Line 8.5 of Attachment 7.1.

Comment:

EXAMINER NOTE: See answer key for acceptable ranges.

OP-TM-300-202, Attachment 7.1, Step 8.6 Performance Step: 12 Power correction (If 81-A1<24 hrs and no Nl calibration has occurred, then power correction= 0, or =[0.7311(82bl100)])

..,J Standard: Examinee calculates power correction as follows:

[0.731 I (99.1 I 100)] = 0.738 Examinee verifies 0.738 has been recorded four times on Line 8.6 of Attachment 7.1.

Comment:

TMI 2014 NRC ADM JPM SRO A1-2 NUREG 1021, Revision 9

Appendix C Page 9 of 19 Form ES-C-1 PERFORMANCE INFORMATION EXAMINER NOTE: See answer key for acceptable ranges.

OP-TM-300-202, Attachment 7. 1, Step B. 7 Performance Step: 13 Total adjustments (84+85+86)

--.1 Standard: Examinee calculates the total adjustments as follows:

Nl5: +0.174 + 0.00 + 0. 737 = 0.911 Nl6: +1.270 + 0.00 + 0.737 =2.008 Nl7: -0.250 + 0.00 + 0. 737 =0.487 NIB: -0.044 + 0.00 + 0.737 = 0.692 The Examinee recognizes the following discrepancy on Line 87 of Attachment 7.1: All four entries are wrong due to previous errors (Error carried forward).

Comment:

TMI2014 NRC ADM JPM SRO A1-2 NUREG 1021, Revision 9

Appendix C Page 10 of 19 Form ES-C-1 PERFORMANCE INFORMATION EXAMINER NOTE: See answer key for acceptable ranges.

OP-TM-300-202, Attachment 7.1, Step 8.8 Performance Step: 14 OCD to lCD conversion factor [application (same factor applies for all quadrants) = 1.23*(87) for no dropped rod, = 1.61 *(87) if a dropped rod exists in any quadrant]

...J Standard: Examinee:

o Determines from the initial conditions that no dropped rod exists.

o Calculates the OCD to lCD conversion factor as follows:

o N15: 1.23

0.911 = 1.120 o Nl6: 1.23

2.007 = 2.469 o Nl7: 1.23

0.487 = 0.599 o Nl8: 1.23

0.693 = 0.851 The Examinee recognizes the following discrepancy on Line 88 of Attachment 7.1: All four entries are wrong due to previous errors (Error carried forward).

Comment:

TMI2014 NRC ADM JPM SRO A1-2 NUREG 1021, Revision 9

Appendix C Page 11 of 19 Form ES-C-1 PERFORMANCE INFORMATION EXAMINER NOTE: See answer key for acceptable ranges.

OP-TM-300-202, Attachment 7.1, Step 8.9 Performance Step: 15 Total adjusted OCD tilt (A2+88)

...J Standard: Examinee calculates the OCD to lCD conversion factor as follows:

Nl5: +1.23 + 1.12 =2.350 Nl6: 2.28 + 2.468 = 4.749 Nl7: 0.04 + 0.599 = 0.639 Nl8: -0.63 + 0.852 = 0.221 The Examinee recognizes the following discrepancy on Line 89 of Attachment 7.1: All four entries are wrong due to previous errors (Error carried forward).

Comment:

OP-TM-300-202, Attachment 7. 1, Step B. 10 Performance Step: 16 Fulllncore System Tilt limit per COLR Table 1.

...J Standard: Examinee reviews COLR Table 1 and determines that Fulllncore System Steady State Limit for Power > 60% is 4.53.

The Examinee recognizes the following discrepancy on Line 810 of Attachment 7.1: The wrong COLR limit has been recorded.

Comment:

TMI2014 NRC ADM JPM SRO A1-2 NUREG 1021, Revision 9

Appendix C Page 12 of 19 Form ES-C-1 PERFORMANCE INFORMATION EVALUATOR NOTE: OP-TM-300-202, Step 4.5.1.5 is N/A OP-TM-300-202, Step 4.5. 1.6 and/or OP-TM-300-202, Attachment 7. 1, Step C. 1 Performance Step: 17 DETERMINE if the total adjusted OCD tilt exceeds the full incore limit lAW T.S. 3.5.2.4.b limit and COLR Table 1.

-./ Standard: Examinee determines that NIB total adjusted OCD tilt exceeds the COLR full incore limit of Table 1 and that NO should be circled on Line C.1 of Attachment 7.1.

The Examinee recognizes the following discrepancy on Line C1 of Attachment 7.1: YES is circled (Error carried forward).

Comment:

TMI 2014 NRC ADM JPM SRO A 1-*2 NUREG 1021, Revision 9

Appendix C Page 13 of 19 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-300-202, Step 4.5. 7 Performance Step: 18 If the total adjusted OCD tilt of any quadrant exceeds the limits for the full incore system, then PERFORM action per T.S.

3.5.2.4.d, e, and f as applicable.

T.S. 3.5.2.4.d, e, and f:

d. Except for physics tests if quadrant tilt exceeds the tilt limit, allowable power shall be reduced 2 percent for each 1 percent tilt in excess of the tilt limit. For less than four pump operation, thermal power shall be reduced 2 percent below the thermal power allowable for the reactor coolant pump combination for each 1 percent tilt in excess of the tilt limit.

e. If quadrant power tilt exceeds the tilt limit then within a period of 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months , the quadrant power tilt shall be reduced to less than the tilt limit except for physics tests, or the following verifications and/or adjustments in setpoints and limits shall be made:

1. Verify FQ (Z) and F ~H are within limits of the COLR once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and restore OPT to s steady state limit within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or perform steps 2, 3, & 4 below.

2. The protection system reactor power/imbalance envelope trip setpoints shall be reduced 2 percent in power for each 1 percent tilt, in excess of the tilt limit, or when thermal power is equal to or less than 50% full power with four reactor coolant pumps running, set the nuclear overpower trip setpoint equal to or less than 60%

full power.

3. The control rod group withdrawal limits in the CORE OPERATING LIMITS REPORT shall be reduced 2 percent in power for each 1 percent tilt in excess of the tilt limit.

4. The operational imbalance limits in the CORE OPERATING LIMITS REPORT shall be reduced 2 percent in power for each 1 percent tilt in excess of the tilt limit.

f. Except for physics or diagnostic testing, if quadrant tilt is in excess of the maximum tilt limit defined in the CORE OPERATING LIMITS REPORT and using the applicable detector system defined in 3.5.2.4.a, b, and c above, reduce thermal power to S15% FP within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Diagnostic testing during power operation with a quadrant tilt is permitted provided that the thermal power allowable is restricted as stated in 3.5.2.4.d above.

..J Standard: Decides that power needs to be reduced Comment:

TMI 2014 NRC ADM JPM SRO A 1-2 NUREG 1021, Revision 9

Appendix C Page 14 of 19 Form ES-C-1 PERFORMANCE INFORMATION Terminating Cue: After the examinee has specified the tilt exceeds COLR limits and that T.S. 3.5.2.4.d, e, and f apply: Evaluation on this JPM is complete.

STOP TIME:

TMI 2014 NRC ADM JPM SRO A 1-2 NUREG 1021, Revision 9

Appendix C Page 15 of 19 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: TMI 2014 NRC ADM 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 2014 NRC ADM JPM SRO A 1-2 NUREG 1021, Revision 9

Appendix C Page 16 of 19 Form ES-C-1 VERIFICATION OF COMPLETION ANSWER KEY- DO NOT PROVIDE TO EXAMINEE NOTE: All 4 Nls must be operable to use this data sheet.

A. Reference Tilt Conditions A 1. Date/Time of last recorded set of valid, steady state Full lncore System (FIS) and out-of-core detector (OCD) tilt measurements:

Yesterday /_ t = -33 Hours .

Nl5 (WX) Nl6 (YZ) Nl7 (XY) NIB (ZW)

A2. FIS0 ~ 1.23 0.06 +2.28 0.25 +0.04 ..Q.A-9 -0.63 A3. OCD 0 ~-0.88 2.28 -0.06 G-:Q4 o.25 o.6a -0.46 B. Tilt Measurement Calculation NOTE: This date must be less than 30 days from the reference date in A 1.

81. Date/Time of measurements: - TODAY_ _/ _ NOW- -

B2a. Present Nl power 98.4 100.3 99.1 98.6 82b. Average Nl power (Sum of 82a)/4 - 99.1 99.1 99.1 99.1 same number in all4 blanks

83. Indicated Nl tilt (-0.70--+-0.71} (1.20--+ 1 .21} 0.000 0.504

=([NI Power /Average Nl Power]-1)*100 ( -.50--+-.51}

84. Change in indicated OCD tilt 83-A~~ 1.9:36 1.07 0.04 1.1:34 (0.17--+0.18} (1.26--+ 1.27} -0.25 (-0.04--+-0.05}

85. Recalibration correction 0 0 0 0 REGAL from Data Sheet 2 (= 0 if no recalibration has occurred)

86. Power correction (0.73--+0.74} (0.73--+0.74} (0.73--+0.74}(0.73--+0.74}

IF: 81 -A1 < 24 hrs AND no Nl recalibration has occurred, THEN Power correction= 0, OR

= [0.731/{82b/100)]

87. Total adjustments= 84 + 85 + 86 1.198 o.aa2 0.698 1.872 (0.9--+1.0) (1.9--+2.1) (0.4--+0.5) (0.6--+0.7)

88. OCD to lCD conversion factor 1.47 0.408 0.858 2.:30 Application (same factor applies ... ) (0.9--+1.2) (2.3--+2.6) (.=..0.:....:.4_--+__:::0'"'"7. -'-)_ _ (0. 7--+ 1 .0)

= 1.23 * {87) for no dropped rod

= 1.61 * {87) if a dropped rod exists in any quadrant

89. Total adjusted OCD tilt= A2 + 88 0.1 -0.468 1.108 1.84

(=2=.2'---+"'-=2=.5:..<}_ _(4.6--+4.9} (0.5--+0.8} (0.1--+0.4) 810. Fulllncore System Tilt limit per COLA Table 1 1.90 (4.53}

C. Acceptance Criteria C1. The maximum value of 89 is less than the FIS Tilt limits in the COLA. (Circle one)

C2. If the adjusted quadrant power tilt per C1 exceeds the limits in the COLA, then PERFORM action per T.S. 3.5.2.4d, e, and f as applicable.

TMI2014 NRC ADM JPM SAO A1-*2 NUREG 1021, Revision 9

Appendix C Page 17 of 19 Form ES-C-1 EXAMINEE SHEET INITIAL CONDITIONS:

You are the CRS .

The plant computer is not operational.

The computer has been off-line for 33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months .

lncore tilt was not exceeding the limits prior to the computer outage.

Recalibration of the Nl's is not and has not been required.

There are no dropped rods.

All OCD's are operable.

The following items are available for your use:

An Examinee Data Sheet containing the current Nl power level and last recorded set of valid, steady state Full lncore System (FIS) and out-of-core detector (OCD) tilt measurements recorded.

A Calculator INITIATING CUE: Review and approve the calculation for quadrant power tilt lAW OP-TM-300-202, QUADRANT POWER TILT AND CORE IMBALANCE USING THE OUT-OF-CORE DETECTOR SYSTEM, based on the information provided, and determine any applicable Tech Specs.

TIME CRITICAL: No TMI 2014 NRC ADM JPM SRO A 1-2 NUREG 1021, Revision 9

Appendix C Page 18 of 19 Form ES-C-1 EXAMINEE SHEET ATTACHMENT 7.1 OCD-ICD Tilt Correlation Page 1 of 1 NOTE: All 4 Nls must be operable to use this data sheet.

A. Reference Tilt Conditions A 1. Date!fime of last recorded set of valid, steady state Full lncore System (FIS) and out-of-core detector (OCD) tilt measurements:

Yesterday I_ t = -33 Hours Nl5 (WX) Nl6 (YZ) Nl7 (XY) NIB (ZW)

A2. FIS 0 -0.88 -0.06 0.25 -0.46 A3. OCD 0 1.23 2.28 0.04 -0.63 B. Tilt Measurement Calculation NOTE: This date must be less than 30 days from the reference date in A 1.

81. Date!Time of measurements: TODAY I NOW B2a. Present Nl power 98.4 100.3 99.1 B2b. Average Nl power (Sum of 82a)/4- 99.1 99.1 99.1 same number in all 4 blanks

83. Indicated Nl tilt -0.706 1.210 0.000

=([NI Power /Average Nl Power]-1)*100

84. Change in indicated OCD tilt B3-A3 -1.936 -1.07 -0.04

85. Recalibration correction Q Q Q Q REGAL from Data Sheet 2 (= 0 if no recalibration has occurred)

86. Power correction 0.738 0.738 0.738 IF: 81 -A1 < 24 hrs AND no Nl recalibration has occurred, THEN Power correction= 0, OR

= [0.731/(82b/100)]

87. Total adjustments= 84 + 85 + 86

88. OCD to lCD conversion factor -1.47 Application (same factor applies for all quadrants)

= 1.23 * (87) for no dropped rod

= 1.61 * (87) if a dropped rod exists in any quadrant

89. Total adjusted OCD tilt= A2 + 88 -0.1 810. Fulllncore System Tilt limit per COLA Table 1 1.90 C. Acceptance Criteria C1. The maximum value of 89 is less than the FIS Tilt limits in the COLA. (Circle one) ~No C2. If the adjusted quadrant power tilt per C1 exceeds the limits in the COLA, then PERFORM action per T.S. 3.5.2.4d, e, and f as applicable.

Calculated by: ~ Date!Time Todav!Now SAO Review by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. Date!Time_ _ _ _ _ __

TMI 2014 NRC ADM JPM SRO A1*-2 NUREG 1021, Revision 9

Appendix C Page 19 of 19 Form ES-C-1 EXAMINEE SHEET EXAMINEE DATA SHEET FIS lncore Detector Tilt on Date Yesterday Time 33 hrs ago Nl-5 (WX) +1.23 Nl-6 (YZ) +2.28 Nl-7 (XY) +0.04 Nl-8 (ZW) -0.63 OCD Out-of-Core Detector Tilt on Date Yesterday __ Time 33 hrs ago_

Nl-5 (WX) -0.88 Nl-6 (YZ) -0.06 Nl-7 (XY) +0.25 Nl-8 (ZW) -0.46 PRESENT CORE POWER Date TODAY Time_NOW __

Nl-5 Core Power 98.4%

Nl-6 Core Power 100.3%

Nl-7 Core Power 99.1%

Nl-8 Core Power 98.6%

TMI 2014 NRC ADM JPM SRO A 1-2 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: TMI- Unit 1 Task No.: 22601001 Task

Title:

RCP Station Print Read JPM No.: 2014 NRC JPM SRO A2 KIA

Reference:

2.2.41 {3.9) NewJPM Examinee: NRC Examiner:

Facility Examiner: 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 CRS on shift.

Reactor Power is 20%, 600 EFPD.

RC-P-1 A has been Out Of Service for 30 days, not expected to return to service until repairs can be made during the next outage.

RC-P-1 D was tripped manually 23 hours2.662037e-4 days 0.00639 hours 3.80291e-5 weeks 8.7515e-6 months ago and is ready to be restarted with the following conditions:

The RC-P-1 D-69, RC-P-1 D Control Transfer Switch, has been placed in Bypass.

The 69 Selector Switch Contact #13 is stuck in the CLOSED position.

MU-V-33D, RC-P-1 D Seal #1 Leak Off Isolation Valve, is closed with a damaged valve stem.

Fuse FD78 (XCC Fuse associated with RC-P-1D) has blown.

All other systems and components are in their normal configuration.

Task Standard:

Determine RC-P-1 D will not start from the Control Room and locally at the breaker and the applicable Tech Specs that apply.

2014 TMI NRC JPM SRO A2 NUREG 1021, Revision 9, Supplement 1

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

Print 208-113, RC-P-1 0, Rev 16

Print SS-209-066, Aux Relays of MU-13-DPS 1 ,2,3 & 4, Rev 4

Print SS-209-127, Neutron Above 30% RC Pump Interlock, Rev 3

Print 08032727, Reactor Control Sheet 2 of 2, Rev W

Print 302-660, Makeup & Purification, Rev 45

OP-TM-226-000, Reactor Coolant Pumps, Rev 8

Tech Specs General

References:

Print 208-113, RC-P-1 0, Rev 16

Print SS-209-066, Aux Relays of MU-13-DPS1 ,2,3 & 4, Rev 3

Print SS-209-127, Neutron Above 30% RC Pump Interlock, Rev 3

Print 08032727, Reactor Control Sheet 2 of 2, Rev W

Print 302-660, Makeup & Purification, Rev 45

Print 302-661, Make-up & Purification, Rev 60

Print 209-070, D.C. And Miscellaneous, Rev 7

Print 209-109, Aux. Relays for RC Pump A,B & 0 Instruments, Rev 0

Print SS .. 208-350, Nuclear Service Closed Cooling Water Pumps NS-P1 A To C Interlocks, Rev 3

Print SS-209-065, Auxiliary Relays of: MU42-FS, Rev 8

Print ss. 208-114, 6900V Switchgear - Reactor Plant Bus 1A ( 1 B)

Undervoltage Relays & Potential Circuits, Rev 8

OP-TM-226-000, Reactor Coolant Pumps, Rev 8

Tech Specs Handouts:

Print 208-113, RC-P-1 0, Rev 16

Print SS-209-066, Aux Relays of MU-13-DPS1 ,2,3 & 4, Rev 3

Print SS-209-127, Neutron Above 30% RC Pump Interlock, Rev 3

Print 08032727, Reactor Control Sheet 2 of 2, Rev W

Print 302-660, Makeup & Purification, Rev 45 Initiating Cue: While addressing all bolded conditions above and explaining why or why not, determine if RC-P-1 0 can be started either: a) from Console Center (using CS-1) or b) locally at its breaker. Address applicable Tech Spec concerns, if any. Fill in the provided table.

Time Critical Task: No Validation Time: 30 minutes SIMULATOR SETUP N/A 2014 TMI NRC JPM SRO A2 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 10 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Start Time _ _ _ __

EXAMINER CUE: Hand Examinee the following:

Print208-113, RC-P-10

Print SS-209-066, Aux Relays of MU-13-0PS1,2,3 & 4

Print SS-209-127, Neutron Above 30% RC Pump Interlock

Print 08032727, Reactor Control Sheet 2 of 2

Print 302-660, Makeup & Purification EXAMINER NOTE: RC-P-1 0-69 in Bypass is addressed in this FIRST STEP.

Refer to a marked up copy of the prints for contact positions.

EXAMINER NOTE: Bolded items below identify the critical portions of the step.

Performance Step: 1 Determine if the 69 Bypass switch will allow RCP start from either Console Center or Locally when in BYPASS .

..j Standard:

Using Print 208-113:

Examinee locates the 69 selector switch contact position table in section 5G and the 69 contacts located in various places on the print.

Examinee determines that, while the 69 Bypass switch is in the Bypass position, the RCP can be started from Console Center through 69 selector switch contacts 6 and 4 as long as all starting interlocks are met.

AND

Examinee determines that, while the 69 Bypass switch is in the Bypass position, the RCP can be started locally through 69 selector switch contacts 2, 3, and 4 as long as all starting interlocks are met.

Comment:

2014 TMI NRC JPM RO A2 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 10 Form ES-C-1 PERFORMANCE INFORMATION EXAMINER NOTE: RC-P-1 0-69 Contact #13 is addressed in this SECOND STEP.

Refer to a marked up copy of the prints for contact positions.

EXAMINER NOTE: Bolded items below identify the critical portions of the step.

Performance Step: 2 Determine if the 69 Bypass switch Contact #13 will allow RCP start from either Console Center or Locally when in BYPASS.

--./ Standard:

Using Print 208-113:

Examinee locates the 69 selector switch contact position table in section 5G.

Examinee determines that the 69 Bypass switch Contact #13 is a Spare Contact and has no effect on the circuitry.

Examinee determines that, while the 69 Bypass switch Contact #13 is closed, the RCP can be started from both Console Center and locally as long as all starting interlocks are met.

Comment:

2014 TMI NRC JPM RO A2 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 10 Form ES-C-1 PERFORMANCE INFORMATION EXAMINER NOTE: MU-V-330 is addressed in this THIRD STEP. Refer to a marked up copy of the prints for contact positions.

EXAMINER NOTE: Bolded items below identify the critical portions of the step.

Performance Step: 3 Determine the impact of MU-V-33D being closed on starting RC-P-1 D .

...j Standard:

Using Print 302-660:

Examinee locates MU-V-33D in section1C.

Examinee determines that MU-13DPT-4 will read zero.

Using Print 208-113:

Examinee determines that a starting interlock contact associated with MU-13DPS-4 is found on sheet SS-209-066.

Using Print SS-209-066:

Examinee determines MU-13-DPS4 contact found in the far right branch of the main drawing will be open, deenergizing Relay 80XMU13-dPS4.

Examinee determines that the contact associated with 80XMU13-dPS4, found in the bottom right hand corner of the print, will be open. This is the same contact shown on Print 208-113.

Examinee determines that the RCP Starting Interlock is not met and it will prevent RC-P-1 D from starting from either location.

Comment:

2014 TMI NRC JPM RO A2 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 10 Form ES-C-1 PERFORMANCE INFORMATION EXAMINER NOTE: Fuse FD78 is addressed in this FOURTH STEP. Refer to a marked up copy of the prints for contact positions.

EXAMINER NOTE: Bolded items below identify the critical portions of the step.

Performance Step: 4 Determine the impact of Fuse FD78 being blown on starting RC-P-10 .

..J Standard:

Using Print SS-209-127:

Examinee locates FD78, found in the far right branch of the main drawing.

Examinee determines that Relay 90X/RCP1 D will be deenergized.

Examinee determines that the contact associated with 90X/RCP1 D, found in the bottom right hand corner of the print, will be open. This is the same contact shown on Print 208-113.

Examinee may refer to Print 08032727 to determine contact 86/NPL position.

Using Print 08032727:

Examinee determines that the contact 86/NPL opens when neutron power is >30%. This would be the same result as a blown fuse.

Examinee determines that, although less than 30%

reactor power, the RCP Starting Interlock is not met and it will prevent RC-P-1 D from starting from either location.

Comment:

2014 TMI NRC JPM RO A2 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 10 Form ES-C-1 PERFORMANCE INFORMATION Examiner Note: Tech Specs are addressed in this FIFTH STEP.

Performance Step: 5 Determine applicable Tech Spec, if any.

..j Standard:

Examinee reviews Tech Spec 3.1.1.1: Reactor Coolant Pumps a) Pump combinations permissible for given power levels shall be as shown in Specification Table 2.3.1.

o Table 2.3.1: One Reactor Coolant Pump Operating in Each Loop (Nominal Operating Power- 49%}

b) Power operation with one idle reactor coolant pump in each loop shall be restricted to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . If the reactor is not returned to an acceptable RC pump operating combination at the end of the 24-hour period, the reactor shall be in a hot shutdown condition within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Examinee determines that current reactor power is not a Tech Spec violation.

Examinee determines that since it has been 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months that both RC-P-1 A and RC-P-1 D have been secured and it will be an additional12 hours until MU-V-330 will be repaired; a reactor shutdown to a Hot Shutdown condition must be commenced in the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Comment:

Terminating Cue: When the examinee has addressed all four bolded conditions and states whether a Tech Spec applies or not, JPM may be terminated.

STOP TIME:

2014 TMI NRC JPM RO A2 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 10 Form ES-C-1 PERFORMANCE INFORMATION ANSWER KEY DO NOT HAND TO STUDENTS RCP can or cannot be started from RCP can or cannot be started locally Item Console Center? at the RCP breaker?

RC-P-1 0-69 in The RCP can be started from The RCP can be started locally Bypass Console Center through 69 selector through 69 selector switch contacts switch contacts 6 and 4. 2, 3, and 4.

69 Selector 69 Bypass switch Contact #13 is a 69 Bypass switch Contact #13 is a Switch Contact Spare Contact and has no effect on Spare Contact and has no effect on

13 stuck closed the circuitry. the circuitry.

Therefore, the RCP can be started Therefore, the RCP can be started from Console Center. locally.

MU-13-0PS4 contact will be open, MU-13-0PS4 contact will be open, MU-V-330 is deenergizing Relay 80XMU13-dPS4. deenergizing Relay 80XMU13-dPS4.

closed with a The contact associated with The contact associated with damaged valve 80XMU13-dPS4 will be open. 80XMU13-dPS4 will be open.

stem Therefore, the RCP Starting Interlock Therefore, the RCP Starting Interlock is not met and it will prevent RC-P- is not met and it will prevent RC-P-1 0 from starting from Console 1 0 from starting locally.

Center.

Relay 90X/RCP1 0 will be Relay 90X/RCP1 0 will be deenergized. deenergized.

The contact associated with The contact associated with Fuse F078 is 90X/RCP1 0 will be open. 90X/RCP1 0 will be open.

blown Contact 86/NPL opens when neutron Contact 86/NPL opens when neutron power is >30%. This would be the power is >30%. This would be the same result as a blown fuse. same result as a blown fuse.

Therefore, although less than 30% Therefore, although less than 30%

reactor power, the RCP Starting reactor power, the RCP Starting Interlock is not met and it will prevent Interlock is not met and it will prevent RC-P-1 0 from starting from Console RC-P-1 0 from starting locally.

Center.

T.S. Applicability, if any:

Table 2.3.1: One Reactor Coolant Pump Operating in Each Loop (Nominal Operating Power-49%)

c) Power operation with one idle reactor coolant pump in each loop shall be restricted to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . If the reactor is not returned to an acceptable RC pump operating combination at the end of the 24-hour period, the reactor shall be in a hot shutdown condition within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

2014 TMI NRC JPM RO A2 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 9 of 10 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2014 TMI NRC JPM SRO A2 Examinee's Name:

Date Performed:

Facility Examiner:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2014 TMI NRC JPM SRO A2 NUREG 1021, Revision 9, Supplement 1

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

You are the CRS on shift.

Reactor Power is 20%, 600 EFPD.

RC-P-1 A has been Out Of Service for 30 days, not expected to return to service until repairs can be made during the next outage.

RC-P-1 D was tripped manually 23 hours2.662037e-4 days 0.00639 hours 3.80291e-5 weeks 8.7515e-6 months ago and is ready to be restarted with the following conditions:

The RC-P-1 D-69, RC-P-1 D Control Transfer Switch, has been placed in Bypass.

The 69 Selector Switch Contact #13 is stuck in the CLOSED position.

MU-V-33D, RC-P-1 D Seal #1 Leak Off Isolation Valve, is closed with a damaged valve stem.

Fuse FD78 (XCC Fuse associated with RC-P-1 D) has blown.

All other systems and components are in their normal configuration.

INITIATING CUE: While addressing all bolded conditions above and explaining why or why not, determine if RC-P-1 D can be started either: a) from Console Center (using CS-1) or b) locally at its breaker. Address applicable Tech Spec concerns, if any. Fill in the provided table.

TIME CRITICAL: No RCP can or cannot be started RCP can or cannot be started Item from Console Center? locally at the RCP breaker?

RC-P-1 D-69 in Bypass (include contact numbers) (include contact numbers) 69 Selector Switch Contact #13 stuck closed (include reason why) (include reason why)

MU-V-330 is closed with a damaged valve stem (include reason why) (include reason why)

Fuse FD78 is blown (include reason why) (include reason why)

T.S. Applicability, if any:

2014 TMI NRC JPM SRO A2 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: TMI- Unit 1 Task No.: SGT02002 Task

Title:

Implement the Requirements of JPM No.: 2014 NRC JPM SRO ODCM for RMS Operability A3 KIA

Reference:

2.3.15 (3.1) Modified from TMI08 NRC JPM A3 SRO Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

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

Initial Conditions:

You are the CRS.

The plant is at 100% power

RM-A-8 Gas Channel is OOS for replacement of the indicator.

CA-G-1A, Beckman H2/02 Gas Analyzer, is OOS, awaiting parts.

Waste Gas Tank WDG-T-1C is being released lAW 6610-4250-11, Releasing Radioactive Gaseous Effluents- Waste Gas Tanks AlB/C.

The .ARO informs you of the following reports:

RM-A-6 Gas channel has failed low.

120/208V AC Distribution Panel AB-3 (SS-201-149) has deenergized.

All other plant equipment is operating properly.

Task Standard: ODCM Requirements for RMS Operability identified.

Required Materials: None 2014 TMI NRC JPM SRO A3 NUREG 1021, Revision 9, Supplement 1

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

References:

CY-TM-170-300, Offsite Dose Calculation Manual (ODCM), Rev. 3 661 0-ADM-4250.11, Releasing Radioactive Gaseous Effluents- Waste Gas Tanks A/B/C, Rev. 14A 661 0-ADM-4250.1 0, Radiological Controls/Chemistry Actions When RMS Malfunctions, Rev 16.

1107-4, Electrical Distribution Panel Listing, Rev 225.

Handouts: CY-TM-170-300, Offsite Dose Calculation Manual (ODCM), Rev. 3 Initiating Cue: Identify actions required to be taken for the given conditions.

Time Critical Task: No Validation Time: 10 minutes SIMULATOR SETUP N/A 2014 TMI NRC JPM SRO A3 NUREG 1021, Revision 9, Supplement 1

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

START TIME:

Evaluator Cue: When/if asked for, provide a copy of:

ODCM 661 0-ADM-4250.11, Releasing Radioactive Gaseous Effluents- Waste Gas Tanks A/8/C 661 0-ADM-4250.1 0, Radiological Controls/Chemistry Actions When RMS Malfunctions 1107-4, Electrical Distribution Panel Listing Performance Step: 1 Identifies entry into the ODCM is required.

Standard: The Examinee determines entry into the ODCM is required.

Comment:

ODCM 2. 1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Performance Step: 2 Enters ODCM 2.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Standard: The Examinee recognizes applicability of section 2.1.2.b:

With less than the minimum number of radioactive gaseous process or effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in table 2.1-2. Exert best efforts to return the instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Effluent Release Report why the inoperability was not corrected in a timely manner.

Evaluator Cue: Acknowledge the report.

Comment:

2014 TMI NRC JPM SAO A3 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION ODCM Table 2.1-2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Performance Step: 3 The Examinee enters the ODCM Table 2.1-2 to determine operability requirements.

Standard: The Examinee determines:

That CA-G-1 B is inoperable when Distribution Panel AB-3 is deenergized.

That the Waste Gas Tank release may continue as long as a grab sample is collected and analyzed for H2 and 02 at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months lAW the Table Notation applicability and ACTION 30 associated with CA-G-1 A and CA-G-1 B being inoperable.

Table2.1*2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation MINIMUM CHANNEl OPERABLE APPUCAS!l!TY

1. Waste G.u holdup S')i$-t.em Z. W!Mire Gas Holdup Sy11tem E1..pl~~\'f' Gas ~tonr.Dffi~g System fl. Hydr.oge1~

t*. O>:yqer.

Momlor (CA-G-1/!.JB\

MOOib:lr\:CA-G-~A!B) :I ACTION 30 1. With the numl.ler of channels OPERABLE less than requtrea oy the Minimum Channels OPERABLE requirement, a grab sample shall be collected and analyzed for the inoperable gas channel(s) at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . With both channels inoperable, a grab sample shan be collected and analyzed for the inoperable gas channel(s)'.

(a) at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during degassing operations.

(b) at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during other operations (e.g_ Feed and Bleed).

2. If the inoperable gas channel{s) is not restored to service within 14 days, a special report shall be submitted to the Regional Administrator of the NRC Region 1Office and a copy to the Director, Office of Inspection and Enforcement Within 30 days of deciaring the channel(s) inoperable. The report shall describe {a) the cause of the monitor inoperabillty, {b) actiOn being taken to restore the instrument to service, and (c) action to be taken to prevent recurrence.

Comment:

2014 TMI NRC JPM SRO A3 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION ODCM Table 2.1-2 Performance Step: 4 Determine actions required for Auxiliary Building ventilation with RM-A-6G and RM-A-8G inoperable.

-1 Standard: The Examinee reviews the ODCM Table 2.1-2, ACTION 27 for RM-A-8G and RM-A-6G being inoperable and determines releases via the Auxiliary Building ventilation exhaust may continue provided that gas grab samples are taken at least once per twelve (12) hours, and that the initial sample is analyzed by gamma scan within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after the channel has been declared inoperable.

Table 2.1*2 (Confd)

Radioactive Gaseous Process and Effluent Monitoring Instrumentation M~NJMUM CHANNEL INSTRUMENT OPERABLE APPUCABILITY ,~CTION S Auxiliary and Fuel Handling: B-ui1dtng Ventlal!on System

.a. NolMe Gas ActrJity Momror {RM-A-$} -or {RM-Jl.-4 and RM-A-6) 27

b. lodifte Sampler (RM-A->3: or {RM-A-4 and RM-A-6-) 31

c. Partit:::uhate Samp~r (RM-A-8 Of {RM-A-4 and RM-A-S} 31 d Effluent System Flow* Rate Measu1ing Devic-es {AH-FR-149 and 26 AH-fR-150)

e. Samp~r F!Ow Rate Moort:or {RM-Ft-12'3:0 or RM-A-4\FI and RM-A-6\F!) 26 ACTION 27 With ttJe number of channels OPERABlE Jess than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and lhe initial samples are analyzed for gross activity (gamma scan) within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after the channel has been dedared inoperable. If RM-A-9 is declared inoperable, see also Technical Specification 3.5.1, Table 3-5.1,11em C.3J.

Comment:

Terminating Cue: When the Examinee completes the call on Auxiliary Building ventilation the JPM may be terminated.

STOP TIME: TIME CRITICAL STOP TIME: N/A 2014 TMI NRC JPM SRO A3 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2014 TMI 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:

2014 TMI NRC JPM SRO A3 NUREG 1021, Revision 9, Supplement 1

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

You are the CRS.

The plant is at 100% power

RM-A-8 Gas Channel is OOS for replacement of the indicator.

CA-G-1 A, Beckman H2/02 Gas Analyzer, is OOS, awaiting parts.

Waste Gas Tank WDG-T-1C is being released lAW 6610-4250-11, Releasing Radioactive Gaseous Effluents- Waste Gas Tanks AlB/C.

The ARO informs you of the following reports:

RM-A-6 Gas channel has failed low.

120/208V AC Distribution Panel AB-3 (SS-201-149) has deenergized.

All other plant equipment is operating properly.

INITIATING CUE: Identify actions required to be taken for the given conditions.

TIME CRITICAL: No 2014 TMI NRC JPM SRO A3 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: TMI Unit 1 Task No.: OF010009 Task

Title:

Given a set of conditions, determine JPM No.: 2014 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 2014 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:

T= 0700:

Plant is at 100% Power.

Weather: Rain. Temp: 60°F. Wind: from 120° at 6 mph.

T= 0701:

OBE Earthquake Alarm PRF-1-3 actuates.

An 11 gpm tube leak occurs in the "A" OTSG.

A 7 gpm tube leak occurs in the "8" OTSG.

T= 0703:

An aftershock occurs.

Turbine Trip with an ATWS, Manual Reactor Trip was NOT successful due to multiple stuck rods.

An RCS leak occurs at the suction of RC-P-1 C of 300gpm.

4 psig ES actuation occurs.

MS-V-4A (ADV) sticks open and the MS-V-15A (MS-V-4A isolation) handwheel breaks off while still open.

T = 0705 (current time):

Another aftershock causes the RCS leak to rise to 500gpm.

Containment Radiation levels on RM-A-22/23 indicate 2000 Rlhr in Containment.

2014 NRC JPM SRO A4 NUREG 1021, Revision 9

Appendix C Job Periormance Measure Form ES-C-1 Worksheet Task Standard: Identifies EAL and PAR.

Required Materials: Periorm in a location with:

o EAL Matrix o Shift Emergency Director Book General

References:

EP-AA-111, EMERGENCY CLASSIFICATION AND PROTECTIVE ACTION RECOMMENDATIONS, Revision 18

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

EP-AA-112-1 00-F-01, SHIFT EMERGENCY DIRECTOR CHECKLIST, RevisionS

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

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

EP-AA-1009 EXELON NUCLEAR RADIOLOGICAL EMERGENCY PLAN ANNEX FOR THREE MILE ISLAND (TMI) STATION Revision 21

EP-AA-112-100-F-06 ERO NOTIFICATION OR AUGMENTATION Revision Q.

EP-AA-114-F-01 PWR RELEASE IN PROGRESS DETERMINATION GUIDANCE, Revision E

EP-MA-114-100, MID-ATLANTIC STATE/LOCAL NOTIFICATIONS, Revision 20 Handouts:

EP-AA-112-100-F-01, SHIFT EMERGENCY DIRECTOR CHECKLIST, signed off for the declared alert.

Emergency Director Binder Initiating Cue:

You are the Shift Manager. I will act as your communicator.

Declare the appropriate EAL and respond in accordance with the EP-AA-112-1 00-F-01, SHIFT EMERGENCY DIRECTOR CHECKLIST.

Time Critical Task: Yes Validation Time: 20 minutes SIMULATOR SETUP N/A 2014 NRC JPM SRO A4 NUREG 1021, Revision 9

Appendix C Page 3 of 10 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check)

EVALUATOR CUE: The Time Critical Start Time is when the Cue is acknowledged.

1 Time Critical Start Time: _ _ _ __

Performance Step: 1 Compares conditions to the EAL Table.

Standard: Examinee:

Determines Fuel Clad has been lost based on Containment radiation (RM-G-22 or RM-G-23) reading > 1.95E+03 Rlhr.

Determines Reactor Coolant System has been lost based on Containment radiation (RM-G-22 or RM-G-23) reading > 25 Rlhr.

Determines Primary Containment Barrier has been lost based on Primary-to-Secondary leak rate > 10 gpm and UNISOLABLE steam release from affected S/G to the environment.

Determines conditions are met for GENERAL EMERGENCY EAL FG1.

Comment:

2014 NRC JPM SRO A4 NUREG 1021, Revision 9

Appendix C Page 4 of 10 Form ES-C-1 PERFORMANCE INFORMATION EP-AA-112-100-F-01 Performance Step: 2 Locate and Implement EP-AA-112-100-F-01 forGE.

Standard:

Examinee locates EP-AA-112-100-F-01.

Examinee determines that Section 1.4 is to be implemented for General Emergency Initial Actions.

Comment:

EP-AA-112-100-F-01, Step 1.4.A Performance Step: 3 Announce the event classification, possible escalation paths, and declaration time to the Control Room staff.

"./ Standard: Announces GE based on Loss of Fuel Clad, Loss of RCS, and a Loss of Containment.

Comment:

EVALUATOR NOTE: The #1 Time Critical Stop Time is when the General Emergency is declared.

1 Time Critical Stop Time: _ _ _ __

EVALUATOR NOTE: Time Critical #1 must be equal to or less than 15 minutes.

Time Critical #1 = (#1 Time start)

(Time of declaration)

- - - - mins 2014 NRC JPM SRO A4 NUREG 1021, Revision 9

Appendix C Page 5 of 10 Form ES-C-1 PERFORMANCE INFORMATION EP-AA-112-100-F-01, Step 1.4.8 Performance Step: 4 Record the EAL, threshold(s) (as applicable) and declaration time.

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

Examinee records thresholds FC7, RC7, and CT5 on EP-AA-112-100-F01.

Examinee records the time of declaration on EP-AA-112-1 OO-F01.

Comment:

EVALUATOR NOTE: Step 1.4C is N/A.

EVALUATOR CUE: Repeat any direction given to you with regards to EP-AA-112-F-09.

EP-AA-112-100-F-01, Step 1.4.0 Performance Step: 5 SELECT the Emergency Public Address Announcements from the form and DIRECT performance of the public address announcement within 15 minutes of event classification.

Standard: Examinee fills out EP-AA-112-F-09 (found at tab 1), section 4.2.8, and hands to communicator (NRC examiner) to make the announcement.

Comment:

2014 NRC JPM SRO A4 NUREG 1021, Revision 9

Appendix C Page 6 of 10 Form ES-C-1 PERFORMANCE INFORMATION EVALUATOR CUE: Repeat any direction given to you with regards to EP-AA-112-1 00-F-06.

EVALUATOR CUE: If requested to provide DAPAR information, then respond "Offsite dose projections are < 1 REM TEDE and < SREM CDE thyroid".

EP-AA-112-100-F-01, Step 1.4.E Performance Step: 6 If the ERO has not been activated, then DIRECT activation of the ERO Notification using Scenario 1, "Actual Event Respond to Facility," or Scenario 3, "Actual Event Alternate Reporting Location," as appropriate, per EP-AA-112-1 00-F-06.

Standard: Examinee hands out EP-AA-112-1 00-F-06 and directs activation of the ERP notification using Scenario 1.

Comment:

EP-AA-112-100-F-01, Step 1.4.F Performance Step: 7 Determine the PAR per the Emergency Classification and Protective Action Recommendations procedure. *

Emergency Classification and PAR Procedure: Tab 6

Plant Based PAR Flowchart: Tab 7

..J Standard: Examinee follows the flowchart of EP-AA-111-F-09 as follows:

Classification is a General Emergency?- Yes

Is this the Initial PAR?- Yes

Release via Controlled direct containment vent with a duration < 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ?- No

Is there a Hostile Action Event in progress?- No

Has the utility been informed by the State that there are impediments to evacuation?- No Examinee determines the following actions are required:

Evacuate 5 - mile radius.

Evaluate Dose Assessment results to determine if a PAR upgrade is required.

Comment:

2014 NRC JPM SRO A4 NUREG 1021, Revision 9

Appendix C Page 7 of 10 Form ES-C-1 PERFORMANCE INFORMATION EVALUATOR CUE: Repeat any direction given to you with regards to EP-MA-114-1 00-F-01.

EP-AA-112-100-F-01, Section 1.4.G Performance Step: 8 Direct performance of State/Local notifications within 15 minutes of the event classification as required per the Notifications procedure.

Notification Procedure (EP-MA-114-100): Tab 3 Notification Form (EP-MA-114-100-F-01): Tab 4 Release in Progress Determination Guidance (EP-AA-114-F-01 ):

Tab 21

,J Standard: Examinee fills out EP-MA-114-1 00-F-01 (while using EP-MA-114-100 and EP-AA-114-F-01 for guidance) as follows:

Utility Message No. 1

Verified With: N/A

Emergency Director Approval: signature

1 Call Status is X This is a DRILL.

3a Emergency Classification: X General Emergency

3b Affected Unit(s) is/are: X One

3c Declared at: declaration time and date

3d This represents a/an: Initial Declaration

4a Emergency Action level (EAL) No. is: FG-1

4b A Brief Non-Technical Description of the Event is as follows: FG-1 sticker placed in the space provided

5 Non-Routine Radiological Release Status is: X b.

Airborne radiological release in-progress.

6a Wind Direction is from 120 (degrees)

6b Wind Speed is_§ (miles per hour)

7b X Evacuate 360 degress from 0 miles to§. miles ...

8

Conclusion:

X This is a DRILL Examinee hands the filled out form to the communicator.

Comment:

2014 NRC JPM SRO A4 NUREG 1021, Revision 9

Appendix C Page 8 of 10 Form ES-C-1 PERFORMANCE INFORMATION EVALUATOR NOTE: The #2 Time Critical Stop Time is when the completed form, EP-MA-114-100-F-01, is handed to the Communicator.

2 Time Critical Stop Time: _ _ _ __

EVALUATOR NOTE: Time Critical #2 must be equal to or less than 15 minutes.

Time Critical #2= {Time of declaration

{#2 Critical Stop Time)

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

2014 NRC JPM SRO A4 NUREG 1021, Revision 9

Appendix C Page 9 of 10 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2014 NRC JPM 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:

2014 NRC JPM SRO A4 NUREG 1021, Revision 9

Appendix C Page 10 of 10 Form ES-C-1 JPM CUE SHEET Initial Conditions:

T= 0700:

Plant is at 100% Power.

Weather: Rain. Temp: 60°F. Wind: from 120° at 6 mph.

T= 0701:

OBE Earthquake Alarm PRF-1-3 actuates.

A 11 gpm tube leak occurs in the "A" OTSG.

A 7 gpm tube leak occurs in the "B" OTSG.

T= 0703:

An aftershock occurs.

Turbine Trip with an ATWS, Manual Reactor Trip was NOT successful due to multiple stuck rods.

An RCS leak occurs at the suction of RC-P-1 C of 300gpm.

4 psig ES actuation occurs.

MS-V-4A (ADV) sticks open and the MS-V-15A (MS-V-4A isolation) handwheel breaks off while still open.

T = 0705 (current time):

Another aftershock causes the RCS leak to rise to 500gpm.

Containment Radiation levels on RM-A-22/23 indicate 2000 Rlhr in Containment.

Initiating Cue: You are the Shift Manager. I will act as your communicator.

Declare the appropriate EAL and respond in accordance with the EP-AA-112-100-F-01, SHIFT EMERGENCY DIRECTOR CHECKLIST.

Time Critical Yes 2014 NRC JPM SRO A4 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND Task No.: 21101002 Task

Title:

Feed from the "C" RCBT and the JPM No.: 20141LT NRC JPM A BAMT KIA

Reference:

001 A4.02 4.1/3.9 New for 20141LT 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:

The Reactor is at 100% power.

A borated water addition is required to be made.

CA-P-1 A is OOS for repairs.

BAMT level is currently 69 inches.

High Feed Flow rates are not desired.

Level tracking is desired.

You are the Third RO.

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

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

ARO will be responsible for all alarms.

Task Standard: Calculate the correct BAMT level change, final level, injection time, and RCBT feed rate, then feed from the "C" RCBT and the BAMT.

Required Materials: OP-TM-211-458, Feed From One RCBT and the BAMT, Rev 0, filled out through Step 4.2.2.

OP-TM-211-455, Feed From RCBT, Rev 1, filled out through Step 3.3.

Calculator 20141LT NRC JPM A NUREG 1021, Revision 9 Supp 1

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

References:

OP-TM-211-458, Feed From One RCBT and the BAMT, Rev 0.

OP-TM-211--455, Feed From RCBT, Rev 1.

Initiating Cue: The Control Room Supervisor directs you to Feed from the BAMT and "C" RCBT lAW OP-TM-211-458, Feed From One RCBT and the BAMT.

Time Critical Task: N/A Validation Time: 20 minutes 2014 ILT NRC JPM A NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP Exam Setup: IC 16, (Temp IC 121)

Place an OOS tag on CA-P-1A

Insert the following:

MUR35 at 33 inches

WDR15 at 69 inches

Ensure the Pump "B" stroke counter is set at all "9"s.

Ensure OP-TM-211-458 is filled out through step 4.2.2.

o Step 4.2.1 will have 1102-4 as the procedure used.

o Step 4.2.2 will have:

A target rod index of 88%

"C" RCBT as the feed source

100 gallons required from the RCBT

150 gallons required from the BAMT

Ensure OP-TM-211-455 is filled out through step 3.3.3

Ensure the Batch Controller top window is set for Total Flow and the bottom window is set for Flow Rate and the Batch Controller is Reset.

This completes the setup for this JPM.

2014 ILT NRC JPM A NUREG 1021, Revision 9 Supp 1

Appendix C Page 4 of 13 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Evaluator's Cue: Provide a copy of OP-TM-211-458, Feed From One RCBT and the BAMT, Rev 0, filled out through Step 4.2.2 OP-TM-211-458 Step 4.2.3 Performance Step: 1 GO TO Step 4.4 Standard: Examinee reviews procedure through step 4.2.2 and then goes to Step 4.4 Comment:

OP-TM-211-458 Step 4.4.1

.V Performance Step: 2 If injection volume tracking using BAMT level is desired, then calculate final BAMT level as follows:

1. CALCULATE BAMT level change by dividing Required BAMT Addition Volume by 48.35 gal/inch:

_ _ _ _ _ _ gal I 48.35 gal/in = in Required BAMT BAMT ll Level Addition Volume Standard: Examinee:

1. Obtains Required BAMT Additional volume from Step 4.2.2 (150 gallons) and writes it on the appropriate line in Step 4.4.1.

2. Divides 150 by 48.35 and comes up with 3.1.

3. Writes 3.1 on the appropriate line in Step 4.4.1.

Comment:

20141LT NRC JPM A NUREG 1021, Revision 9 Supp 1

Appendix C Page 5 of 13 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-211-458 Step 4.4.2

-./ Performance Step: 3 CALCULATE final BAMT level by subtracting BAMT level change from current BAMT level:

_______ in - in= in Current BAMT Level BAMT !::. Level Final BAMT Level (PPC Pt A0475)

Standard: Examinee:

1. Obtains current BAMT level from PPC Point A0475 (69 inches) and writes it on the appropriate line in Step 4.4.2.

2. Obtains BAMT!::. Level from Step 4.4.1 (3.1 inches) and writes it on the appropriate line in Step 4.4.2.

3. Subtracts 3.1 inches from 69 inches and writes 65.9 on the appropriate line in Step 4.4.2.

Comment:

OP-TM-211-458 Step 4.5

-./ Performance Step: 4 CALCULATE Boric Acid Injection Time by dividing Required BAMT Addition Volume by 10 gpm:

_ _ _ _ _ gal I 10 gal/min = min BAMT Batch Size Boric Acid Injection Time Standard: Examinee:

1. Obtains BAMT Batch Size from Step 4.2.2 (150 gallons) and writes it on the appropriate line in Step 4.5.

2. Divides 150 by 10, comes up with 15, and writes it on the appropriate line in Step 4.5 Comment:

20141LT NRC JPM A NURE;G 1021, Revision 9 Supp 1

Appendix C Page 6 of 13 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-211-458 Step 4.6

...J Performance Step: 5 CALCULATE Maximum RCBT Feed Rate by dividing Required RCBT Addition Volume by Boric Acid Injection Time:

._ _ _ _ gal I min = gal/min Required RCBT Boric Acid Injection Maximum RCBT Addition Volume Time Feed Rate Standard: Examinee:

1. Obtains Required RCBT Additional Volume from Step 4.2.2 (1 00 gallons) and writes it on the appropriate line in Step 4.6.

2. Obtains Boric Acid Injection Time from Step 4.5 (15) and writes it on the appropriate line in Step 4.6.

~3. Divides 100 by 15, comes up with 6.67, and writes it on the appropriate line in Step 4.5 Comment:

Examiner Note: Step 4.7 is N/A OP- TM-211-458 Step 4.8 Performance Step: 6 If CA-P-1 B will be used, then perform the following:

1. VERIFY the BORIC ACID PUMP B CONTROL LOCATION SELECT switch is in the LWDS position. _

2. VERIFY CA-P-1 B Pump Stroke Counter is set at "999999."

Standard: Examinee verifies that the BORIC ACID PUMP B CONTROL LOCATION SELECT switch is in the LWDS position and that the CA-P-1 B Pump Stroke Counter is set at 999999 (LWDS Panel).

Comment:

Examiner Cue: When OP-TM-211-455 is located, hand the examinee a printed copy.

20141LT NRC JPM A NUREG 1021, Revision 9 Supp 1

Appendix C Page 7 of 13 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-211-458 Step 4.9 Performance Step: 7 Perform the following to initiate feed from the RCBT:

1. INITIATE OP-TM-211-455, "Feed from RCBT," using Required RCBT Addition Volume determined in this procedure as Required Addition Volume.

2. ENTER "N/A" in the following steps of OP-TM-211-455, "Feed from RCBT."

- Steps 4.1 through 4.4

- Steps 4.27 through 4.29 Standard: Examinee locates OP-TM-211-455 and enters N/A for steps 4.1-4.4 and 4.27-4.29.

Comment:

OP-TM-211-455 Step 3.0 Performance Step: 8 PRECAUTIONS, LIMITATIONS, AND PREREQUISITES.

Standard: Examinee reviews Precautions, Limitations, and Prerequisites.

Comment:

Procedure Note: Raising RCS boron concentration without a defined target may be appropriate during emergent conditions or when the effect on RCS boron concentration is insignificant.

Examiner Note: Steps 4.5-4.8 are N/A.

20141LT NRC JPM A NUREG 1021, Revision 9 Supp 1

Appendix C Page 8 of 13 Form ES-C-1 PERFORMANCE INFORMATION OP- TM-211-455 Step 4.9

....j Performance Step: 9 If feeding from "C" RCBT, then perform the following:

1. If WDL-P-6C is available, then perform the following:

A. POSITION Feed Tank select switch to T1 C.

B. POSITION Waste Transfer Pump select switch to P6C.

C. GO TO Step 4.1 0.

Standard: Examinee determines that WDL-P-6C is available, and:

1. Places the Feed Tank select switch to the T1 C position by rotating the switch in either direction until T1 C is selected (LWDS Panel).

2. Places the Waste Transfer Pump select switch to P6C position by rotating the switch in either direction until P6C is selected (LWDS Panel).

3. Goes to Step 4.1 0 Comment:

Examiner Note: Step 4.10 is N/A Examiner Note: Procedure Note: The batch size may be raised to allow manually securing transfer at the required size. This is accomplished by entering an amount at least 11 gallons greater than the Required Addition Volume.

OP- TM-211-455 Step 4.11

....f Performance Step: 10 Perform the following to enter desired quantity into the Batch Controller (MU12FZS/C/1) (CC):

1. PRESS BATCH SET.

2. ENTER desired batch volume.

3. PRESS ENTER.

Standard: Examinee:

1. Presses BATCH SET on the Batch Controller (CC).

2. Enters between 100-120 as the desired batch volume on the Batch Controller (CC).

3. Presses ENTER on the Batch Controller (CC).

Comment:

20141LT NRC JPM A NUREG 1021, Revision 9 Supp 1

Appendix C Page 9 of 13 Form ES-C-1 PERFORMANCE INFORMATION Procedure Note: Approximate VALVE SET positions vs. flow:

-10%::::::10 gpm

-20%::::::50 gpm

- 21% : : : 53 gpm : : : letdown flow @ 2155 psig Examiner Note: The Valve Set amount is not required to be precise at this time due to the fact that it will be adjusted correctly in OP-TM-211-458, Step 4.11.

OP-TM-211-455 Step 4.12 Performance Step: 11 Perform the following to enter desired valve position into the Batch Controller (MU12FZS/C/1):

1. PRESS VALVE SET.

2. ENTER desired percent valve setting.

3. PRESS ENTER.

Standard: Examinee:

1. Presses VALVE SET on the Batch Controller (CC).

2. Enters approximately 6 as the desired percent valve setting on the Batch Controller (CC).

3. Presses ENTER on the Batch Controller (CC).

Comment:

Examiner Note: Step 4.13 is a decision to be made by the examinee by preference.

OP-TM-211-455 Step 4.13 Performance Step: 12 SELECT desired displays for the upper and lower windows of the Batch Controller (MU12FZS/C/1):

-Batch size (4)

- Inventory total (5)

- Running total (7)

- Flow rate (8)

-Valve demand (CE)

Standard: Examinee selects a display for the upper and lower windows of the Batch controller from the selected choices in Step 4.13, as desired (CC).

Comment:

20141LT NRC JPM A NUREG 1021, Revision 9 Supp 1

Appendix C Page 10 of 13 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-211-455 Step 4.14

..J Performance Step: 13 PRESS RUN on the Batch Controller (MU12FZS/C/I).

Standard: Examinee presses RUN on the Batch Controller (CC)

Comment:

OP-TM-211-455 Step 4.15

..J Performance Step: 14 OPEN MU-V-10.

Standard: Examinee opens MU-V-10 and verifies Open by red open light lit, green closed light not lit (CC).

Comment:

OP-TM-211-455 Step 4.16

..J Performance Step: 15 START the Waste Transfer Pump selected on the Waste Transfer Pump select switch.

Standard: Examinee starts the "C" Waste Transfer Pump by rotating the control switch in the clockwise direction and releasing, observing red running light lit and green secured light not lit (LWDS panel).

Comment:

OP-TM-211-455 Step 4.17 Performance Step: 16 If Batch Controller is operable, then VERIFY flow is indicated on Batch Controller.

Standard: Examinee verifies that flow is indicated on the Batch Controller by observing gallons per minute indicated (CC).

Comment:

2014 ILT NRC JPM A NUREG 1021, Revision 9 Supp 1

Appendix C Page 11 of 13 Form ES-C-1 PERFORMANCE INFORMATION Examiner Note: Once flow is indicated on the Batch Controller, the examinee will return to OP-TM-211-458. Step 4.10 allows the examinee to continue.

OP-TM-211-458 Step 4.11

...J Performance Step: 17 SET RCBT feed flow rate to less than the "Maximum RCBT Feed Rate" lAW OP-TM-211-455, "Feed from RCBT."

Standard: If necessary, the Examinee adjusts RCBT feed rate lAW OP-TM-211-455, Step 4.19 as follows:

1. Presses Valve Set on the Batch Controller (CC).

2. Presses the "A" or "V" carrot button, as required, to establish RCBT feed flow rate to less than 6.67 gpm (the value established in OP-TM-211-458, Step 4.6) (CC).

Comment:

OP-TM-211-458 Step 4.12

...J Performance Step: 18 OPEN MU-V-51.

Standard: Examinee opens MU-V-51 by pressing the red open pushbutton and verifying that the valve is open by the red light being lit and the green light not being lit (CC).

Comment:

OP-TM-211-458 Step 4.13

...J Performance Step: 19 START one of the following Boric Acid Pumps:

- CA-P-1A

- CA-P-1 B Standard: Examinee starts CA-P-1 B by rotating the control switch in the clockwise direction and releasing, observing red running light lit and green secured light not lit (LWDS panel).

Comment:

Terminating Cue: After CA-P-1 B is running, evaluation on this JPM may be terminated.

STOP TIME:

20141LT NRC JPM A NUREG 1021, Revision 9 Supp 1

Appendix C Page 12 of 13 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 20141LT 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:

20141LT NRC JPM A NUREG 1021, Revision 9 Supp 1

Appendix C- Page 13 of 13 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

The Reactor is at 100% power.

A borated water addition is required to be made.

CA-P-1 A is OOS for repairs.

BAMT level is currently 69 inches.

High Feed Flow rates are not desired.

Level tracking is desired.

You are the Third RO.

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

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

ARO will be responsible for all alarms.

INITIATING CUE: The Control Room Supervisor directs you to Feed from the BAMT and "C" RCBT lAW OP-TM-211-458, Feed From One RCBT and the BAMT.

TIME CRITICAL: No 2014 ILT NRC JPM A NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND Task No.: 64101001 Task

Title:

Manually Initiate ESAS -Ait path JPM No.: 2014 ILT NRC JPM B KIA

Reference:

006 A2.12 4.5/4.8 Bank TQ-TM-1 04-642-J007 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 has just been tripped.

A small Break LOCA has occurred.

Guide 9 has been implemented through step C.7.

You are the URO.

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

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

Task Standard: Manually initiate Emergency Injection.

Required Materials:

OP-TM**EOP-010, Guide 9, RCS Inventory Control, signed through step C.8, Rev 16.

OP-TM-211-901, EMERGENCY INJECTION (HPI/LPI), Rev 7.

General

References:

OP-TM-EOP-010, Guide 9, RCS Inventory Control, Rev 16.

OP-TM-211-901, EMERGENCY INJECTION (HPI/LPI), Rev 7.

Initiating Cue: The Control Room Supervisor directs you to INITIATE HPIIAW OP-TM-211-901, "Emergency Injection HPI/LPI".

20141LT NRC JPM B NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: N/A Validation Time: 20 minutes 2014 ILT NRC JPM B NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP Exam Setup: IC 16, (Temp IC 122)

Trip the reactor

Insert the following:

A. Malfunction ES01 A Immediately B. Malfunction ES01 B Immediately

c. Malfunction ES02A Immediately D. Malfunction ES02B Immediately E. Malfunction ES04A Immediately F. Malfunction ES04B Immediately G. Malfunction TH06 to 0.03 Immediately H. WAAT Pressurizer level is> 100", then modify TH06 to 0.02 I. Override 02A4S66-ZDIPB1 RCA to OFF Immediately J. Override 02A4S67-ZDIPB1 RBA to OFF Immediately K. Override 03A4S01-ZDIPB1 RCB to OFF Immediately L. Override 03A4S02-ZDIPB1 RBB to OFF Immediately M. Ensure MUMMT=27000.0

3. Perform Guide 9 through step C. 7

a. Ensure MU-V-217 is OPEN

b. Ensure MU-V-3 is CLOSED

4. Freeze the Simulator.

5. 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.

6. This completes the setup for this JPM.

20141LT NRC JPM B NUREG 1021, Revision 9 Supp 1

Appendix C Page 4 of 17 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Evaluator's Cue: Provide a copy of OP-TM-211-901, EMERGENCY INJECTION (HPI/LPI).

Performance Step: 1 PRECAUTIONS, LIMITATIONS, AND PREREQUISITES.

Standard: Examinee reviews Precautions, Limitations, and Prerequisites.

Comment:

Procedure Note: There are special usage requirements for Section 4.1 and Attachments 7.1 , 7.2 and 7 .3. These actions are memory items (lAW OS 24) and performed from memory when required. The sequence of actuation and verification of ES is not train dependent. Either train may be performed first or trains may be performed in parallel.

Examiner Note: Step 4.1.1 is N/A.

OP-TM-211-901 Step 4.1.2 Performance Step: 2 If ESAS Train A "Load Seq Block 4" lights (PCR) are not BLUE, then PRESS "Manual ES Actuation" "1600 PSIG RC PRESS" (Train A CC).

Standard: Examinee verifies ESAS Train A "Load Seq Block 4" lights (PCR) are NOT blue, and presses "Manual ES Actuation" "1600 PSIG RC PRESS" (Train A CC).

Comment:

Procedure Note: PCR graphic display is equivalent to Attachment 7.1 2014 ILT NRC JPM B NUREG 1021, Revision 9 Supp 1

Appendix C Page 5 of 17 Form ES-C-1 PERFORMANCE INFORMATION Examiner Note: Examinee may attempt to initiate "8" Train ES prior to going to Section 4.2. This is allowed lAW OS-24.

OP-TM-211-901 Step 4.1.3 Performance Step: 3 If any of the components on Attachment 7.1 are not in the required condition, then INITIATE Section 4.2 Standard: Examinee recognizes that components are NOT in the required condition and initiates Section 4.2.

Comment:

Examiner Note: Step 4.1.4 is N/A.

OP- TM-211-901 Step 4.1.5 Performance Step: 4 If ESAS Train B "Load Seq Block 4" lights (PCR) are not BLUE, then PRESS "Manual ES Actuation" "1600 PSIG RC PRESS" (Train B CR).

Standard: Examinee recognizes ESAS Train B "Load Seq Block 4" lights (PCR) are NOT blue and presses "Manual ES Actuation" "1600 PSIG RC PRESS" (Train B CR).

Comment:

Procedure Note: PCR graphic display is equivalent to Attachment 7.2 OP-TM-211-901 Step 4.1.6 Performance Step: 5 If any of the components on Attachment 7.2 are not in the required condition, then INITIATE Section 4.2 Standard: Examinee recognizes that components are NOT in the required condition and initiates Section 4.2.

Comment:

Alternate Path Begins 20141LT NRC JPM B NUREG 1021, Revision 9 Supp 1

Appendix C Page 6 of 17 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-211-901 Step 4.2.1.1 Performance Step: 6 If MU-V-14A or MU-V-148 did not Open, then perform the following:

1. IAAT MU tank level< 18", then perform the following:

A. PLACE all of the following in Pull-to-lock.

MU-P-1A MU-P-18 MU-P-1C Standard: Examinee recognizes MU tank level is NOT <18" and continues on.

Comment:

Examiner Note: Step 4.2.1.2 is N/A.

Examiner Note: The student may choose to open both MU-V-14A and MU-V-148. This is allowed per OS-24 {manually performing an action due to the automatic action failing), and also applies at other points during this JPM.

OP-TM-211-901 Step 4.2.1.3

...J Performance Step: 7 If MU-V-14A or MU-V-148 did not Open, then perform the following:

ENSURE MU-V-14A or MU-V-148 is Open.

Standard: Examinee opens MU-V-14A and/or MU-V-148 by pressing the open pushbutton, observing the Open light is lit and the closed light is not lit (CC).

Comment:

20141LT NRC JPM 8 NUREG 1021, Revision 9 Supp 1

Appendix C Page 7 of 17 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-211-901 Step 4.2.2.1

...J Performance Step: 8 IAAT DC-P-1A or DC-P-1 B fails to start or is shut down unexpectedly, then perform the following:

1. If DC-P-1 A fails to start, then START DC-P-1 A Standard: Examinee starts DC-P-1 A by rotating the control switch in the clockwise direction, observing running light is lit and normal running amps (CC).

Comment:

Examiner Note: Step 4.2.2.2 is N/A.

OP-TM-211-901 Step 4.2.2.3

...J Performance Step: 9 IAAT DC-P-1 A or DC-P-1 B fails to start or is shut down unexpectedly, then perform the following:

3. If DC-P-1 B fails to start, then START DC-P-1 B Standard: Examinee starts DC-P-1 B by rotating the control switch in the clockwise direction, observing running light is lit and normal running amps (CR).

Comment:

OP-TM-211-901 Step 4.2.2.4 Performance Step: 10 IAAT DC-P-1A or DC-P-1 B fails to start or is shut down unexpectedly, then perform the following:

4. If DC-P-1 B is not operating then perform the following:

A. PLACE MU-P-1 C in PTL.

B. PLACE DH-P-1 Bin PTL.

C. PLACE BS-P-1 B in PTL.

D. INITIATE OP-TM-543-440 "Swapping MU-P-1C cooling toNS".

Standard: Examinee recognizes that DC-P-1 B is running and continues on.

Comment:

20141LT NRC JPM B NUREG 1021, Revision 9 Supp 1

Appendix C Page 8 of 17 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-211-901 Step 4.2.3.1.A Performance Step: 11 IAA T either ES selected MU pump fails to start or is shut down unexpectedly, then perform the following:

1. If Train A ES selected MU pump is not operating, then perform the following:

A. VERIFY 1 D 4160V bus is energized.

Standard: Examinee recognizes that MU-P-1A is not operating and verifies that 1D 4160V bus is energized.

Comment:

Examiner Note: Step 4.2.3.1.8 is N/A.

Booth Operator Cue: If contacted as an NLO, state that MU-P-3A is operating.

OP-TM-211-901 Step 4.2.3.1.C.1)

Performance Step: 12 IAAT either ES selected MU pump fails to start or is shut down unexpectedly, then perform the following:

1. If Train A ES selected MU pump is not operating, then perform the following:

C. If MU-P-1A is ES Selected, then perform the following:

1) VERIFY MU-P-2A or MU-P-3A is operating Standard: Examinee verifies MU-P-2A or MU-P-3A is operating by one or more of the following:

"RC Makeup Pump A Oil Pumps" light is lit MAP D-1-1 is clear Contacting an NLO Comment:

2014 ILT NRC JPM B NUREG 1021, Revision 9 Supp 1

Appendix C Page 9 of 17 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-211-901 Step 4.2.3.1.C.2)

...J Performance Step: 13 IAAT either ES selected MU pump fails to start or is shut down unexpectedly, then perform the following:

1. If Train A ES selected MU pump is not operating, then perform the following:

C. If MU-P-1A is ES Selected, then perform the following:

2) START MU-P-1A Standard: Examinee starts MU-P-1A by rotating the control switch in the clockwise direction, observing running light is lit and normal running amps (CC).

Comment:

Examiner Note: Steps 4.2.3.1.C.3) and 4.2.3.1.0 are N/A.

OP- TM-211-901 Step 4.2.3.2.A Performance Step: 14 IAAT either ES selected MU pump fails to start or is shut down unexpectedly, then perform the following:

2. If Train B ES selected MU pump is not operating, then perform the following:

A. VERIFY 1 E 4160V bus is energized.

Standard: Examinee recognizes that MU-P-1 Cis not operating and verifies that 1 E 4160V bus is energized.

Comment:

Examiner Note: Step 4.2.3.2.8 is N/A.

Booth Operator Cue: If contacted as an NLO, state that MU-P-3C is operating.

2014 ILT NRC JPM B NUREG 1021, Revision 9 Supp 1

Appendix C Page 10 of 17 Form ES-C-1 PERFORMANCE INFORMATION OP- TM-211-901 Step 4.2.3.2.C.1)

Performance Step: 15 IAAT either ES selected MU pump fails to start or is shut down unexpectedly, then perform the following:

2. If Train B ES selected MU pump is not operating, then perform the following:

C. If MU-P-1C is ES Selected, then perform the following:

1) VERIFY MU-P-2C or MU-P-3C is operating Standard: Examinee verifies MU-P-2C or MU-P-3C is operating by one or more of the following:

"RC Makeup Pump C Oil Pumps" light is lit MAP D-1-3 is clear Contacting an NLO Comment:

OP-TM-211-901 Step 4.2.3.2.C.2)

...J Performance Step: 16 IAAT either ES selected MU pump fails to start or is shut down unexpectedly, then perform the following:

2. If Train B ES selected MU pump is not operating, then perform the following:

C. If MU-P-1 Cis ES Selected, then perform the following:

2) START MU-P-1C Standard: Examinee starts MU-P-1 C by rotating the control switch in the clockwise direction, observing running light is lit and normal running amps (CR).

Comment:

Examiner Note: Steps 4.2.3.2.C.3), 4.2.3.2.0, and 4.2.3.3 are N/A.

20141LT NRC JPM B NUREG 1021, Revision 9 Supp 1

Appendix C Page 11 of 17 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-211-901 Step 4.2.4.1

....f Performance Step: 17 If any of the following did not Open MU-V-16A MU-V-168 MU-V-16C MU-V-160 then perform the following to ensure flow through all four HPI nozzles:

1. If two ES selected MU pumps are operating, then ENSURE one of the following pairs of valves are Open: (N/A steps not performed)

A. MU-V-16A and MU-V-168 B. MU-V-16A and MU-V-160 C. MU-V-168 and MU-V-16C D. MU-V-16C and MU-V-160 Standard: Examinee recognizes that MU-V-16A-D are closed and opens, at a minimum, a pair of MU-V-16's, verified by Open lights being lit and Closed lights not lit (CC/CR).

Comment:

Examiner Note: Steps 4.2.4.2, 4.2.4.3, and 4.2.4.4 are N/A.

Examiner Note: The combination of MU-V-16 valves opened in the previous step will determine whether valve manipulation takes place in the next two steps.

OP- TM-211-901 Step 4.2.5.1 Performance Step: 18 If MU-V-36 and MU-V-37 did not Close, then perform the following:

1. If MU-P-1A or MU-P-1 8-D is operating, then ENSURE MU-V-16A or MU-V-168 is Open Standard: Examinee recognizes that MU-V-36 and MU-V-37 are open and ensures MU-V-16A or MU-V-168 is open, verified by Open light being lit and Closed light not lit.

Comment:

2014 ILT NRC JPM 8 NUREG 1021, Revision 9 Supp 1

Appendix C Page 12 of 17 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-211-901 Step 4.2.5.2 Performance Step: 19 If MU-V-36 and MU-V-37 did not Close, then perform the following:

2. If MU-P-1 Cor MU-P-1 B-E is operating, then ENSURE MU-V-16C or MU-V-160 is Open Standard: Examinee recognizes that MU-V-36 and MU-V-37 are open and ensures MU-V-16C or MU-V-160 is open, verified by Open light being lit and Closed light not lit.

Comment:

OP-TM-211-901 Step 4.2.5.3

..,J Performance Step: 20 If MU-V-36 and MU-V-37 did not Close, then perform the following:

3. ENSURE MU-V-36 or MU-V-37 is Closed.

Standard: Examinee closes MU-V-36 and/or MU-V-37 by pressing the closed pushbutton and verifying that the closed light is lit and the open light is not lit (CC).

Comment:

OP-TM-211-901 Step 4.2.6

..,J Performance Step: 21 If MU-V-18 did not Close, then perform one of the following: (N/A step not performed)

1. ENSURE MU-V-18 is Closed.

2. ENSURE MU-V-17 and MU-V-217 are Closed Standard: Examinee closes MU-V-18 by pressing the close pushbutton and verifying that the closed light is lit and the open light is not lit (CC). The examinee may close MU-V-17 and MU-V-217 (CC).

Comment:

2014 ILT NRC JPM B NUREG 1021, Revision 9 Supp 1

Appendix C Page 13 of 17 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-211-901 Step 4.2.7.1

...J Performance Step: 22 IAAT DH-P-1 A or DH-P-1 B fails to start or is shut down unexpectedly (e.g., cavitation), then perform the following:

1. If DH-P-1 A failed to start, then perform the following:

A. VERIFY DC-P-1A is operating.

B. START DH-P-1A Standard: Examinee recognizes that DH-P-1A failed to start, verifies DC-P-1A is operating by the running light and normal running amps, and starts DH-P-1 A by rotating the control switch in the clockwise direction, observing running light is lit and normal running amps (CC).

Comment:

OP-TM-211-901 Step 4.2.7.2

...J Performance Step: 23 IAAT DH-P-1 A or DH-P-1 B fails to start or is shut down unexpectedly (e.g., cavitation), then perform the following:

2. If DH-P-1 B failed to start, then perform the following:

A. VERIFY DC-P-1 B is operating.

B. START DH-P-1 B Standard: Examinee recognizes that DH-P-1 B failed to start, verifies DC-P-1B is operating by the running light and normal running amps, and starts DH-P-1 B by rotating the control switch in the clockwise direction, observing running light is lit and normal running amps (CR).

Comment:

Examiner Note: Steps 4.2. 7 .3, 4.2.8.1.A(/B/C), and 4.2.8.2.A(/B/C) are N/A.

20141LT NRC JPM B NUREG 1021, Revision 9 Supp 1

Appendix C Page 14 of 17 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-211-901 Step 4.2.9

....j Performance Step: 24 If DH-V-4A or DH-V-48 is not Open, then perform the following:

1. VERIFY DH-P-1 A and DH-P-1 8 are operating

2. ENSURE both DH-V-4A and DH-V-48 are Open.

Standard: Examinee recognizes that DH-V-4A and DH-V-48 are closed, verifies that DH-P-1 A and DH-P-1 8 are operating by the running indicator lights and the normal running amps, and opens both DH-V-4A and DH-V-48 by pressing the open pushbuttons and verifying that the open lights are lit and the closed lights are not lit (CC/CR).

Comment:

OP-TM-211-901 Step 4.2.10

....j Performance Step: 25 If DR-P-1A is not operating or DR-V-1A is Closed, then perform the following:

1. START DR-P-1A

2. ENSURE DR-V-1A is Open Standard: Examinee recognizes that DR-P-1 A is not operating and/or that DR-V-1A is closed and starts DR-P-1A by rotating the control switch in the clockwise direction, observing running light is lit and normal running amps (CC). Examinee verifies DR-V-1A is open by verifying that the open light is lit and the closed light is not lit (CC).

Comment:

Examiner Note: Step 4.2.1 0.3 is N/A.

20141LT NRC JPM 8 NUREG 1021, Revision 9 Supp 1

Appendix C Page 15 of 17 Form ES-C-1 PERFORMANCE INFORMATION OP- TM-211-901 Step 4.2. 11

...J Performance Step: 26 If DR-P-1 8 is not operating or DR-V-1 8 is Closed, then perform the following:

1. START DR-P-1 8

2. ENSURE DR-V-1 8 is Open Standard: Examinee recognizes that DR-P-1 8 is not operating and/or that DR-V-1A is closed and starts DR-P-1 8 by rotating the control switch in the clockwise direction, observing running light is lit and normal running amps (CR). Examinee verifies DR-V-1 8 is open by verifying that the open light is lit and the closed light is not lit (CR).

Comment:

Examiner Note: The JPM may be terminated at this point. The following step is scripted as an action that may take place while DR-V-1 8 is travelling open.

Examiner Note: Steps 4.2.11.3 and 4.2.12 are N/A.

OP-TM-211-901 Step 4.2.13 Performance Step: 27 If NR-V-4A or NR-V-48 is not closed, then perform the following:

A. ENSURE NR-V-4A or NR-V-48 is Closed (PL).

Standard: Examinee recognizes that NR-V-4A and NR-V-48 are open and closes NR-V-4A or NR-V-48 by pressing the close pushbutton and verifying green closed light lit, red open light not lit (PL).

Comment:

Examiner Note: Steps 4.2.13.8 and 4.2.14 are N/A.

Terminating Cue: After DR-V-1 8 is open, evaluation on this JPM is complete.

STOP TIME: TIME CRITICAL STOP TIME: N/A 20141LT NRC JPM 8 NUREG 1021, Revision 9 Supp 1

Appendix C Page 16 of 17 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2014 ILT 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:

20141LT NRC JPM B NUREG 1021, Revision 9 Supp 1

Appendix C Page 17 of 17 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

The Reactor has just been tripped.

A small Break LOCA has occurred.

Guide 9 has been implemented through step C.7.

You are the URO.

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

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

INITIATING CUE: The Control Room Supervisor directs you to INITIATE HPIIAW OP-TM-211-901, "Emergency Injection HPI/LPI".

TIME CRITICAL: No 20141LT NRC JPM B NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND Task No.: AOP211 005 Task

Title:

Restore Seal Injection with a Loss of JPM No.: 20141LT NRC JPM C ICCW - Alternate Path KIA

Reference:

003 K6.02 2.7/3.1 New for 20141LT 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:

The Reactor is at 100% power.

MU-P-1 B has tripped and is not selected for ES from either power supply.

You are the URO.

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

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

Task Standard: Attempt to restore Seal Injection and trip the Reactor and Reactor Coolant Pumps when required.

Required Materials:

OP-TM-AOP-041, Loss Of Seal Injection, Rev 6.

General

References:

OP-TM-AOP-041, Loss Of Seal Injection, Rev 6.

OP-TM-EOP-001, Reactor Trip, Rev 12.

Initiating Cue: The Control Room Supervisor directs you to restore Seal Injection lAW OP-TM-AOP-041, Loss of Seal Injection.

2014 ILT NRC JPM C NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: N/A Validation Time: 20 minutes SIMULATOR SETUP Exam Setup: IC 16, (Temp IC 123)

1. Insert the following:

A. Remote MUR12 on Event #1 to open MU-V-76A&B B. Trigger #2 MU-P-1C>1.0 IMF CC04A 10 C. Override 03A4S22-ZDIICP1 8(4) to ON Immediately D. Override 03A4S22-ZDIICP1 8(1) to OFF Immediately E. Override 03A4S22-ZDIICP1 8(2) to OFF Immediately F. Override 03A4S22-ZDIICP1 8(3) to OFF Immediately G. Override 03A4S22-ZDIICP1 8(5) to OFF Immediately H. Override 02A5S71-ZDICSMUP1 A(1) to ON Immediately I. Override 02A5S71-ZDICSMUP1 A(2) to OFF Immediately J. Override 02A5S71-ZDICSMUP1 A(3) to OFF Immediately K. Override 02A5S71-ZDICSMUP1A(4) to OFF Immediately L. Override 02A5S71-ZDICSMUP1A(5) to OFF Immediately M. Malfunction RC36 Immediately N. Malfunction MU33A Immediately

0. Malfunction MU31 C Immediately

3. Freeze the Simulator.

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.

20141LT NRC JPM C NUREG 1021, Revision 9 Supp 1

Appendix C Page 3 of 12 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Evaluator's Cue: Provide a copy of OP-TM-AOP-041, Loss Of Seal Injection.

Evaluator's Note: Steps 3.1 and 3.2 are "If At Any Time" steps and are not applicable at this time.

OP- TM-AOP-041 Step 3.3

...J Performance Step: 1 ENSURE MU-V-32 is in HAND and Closed.

Standard: Examinee recognizes that MU-V-32 is in AUTO and open, and:

1. Presses the white HAND button on the MU-V-32 Bailey controller station, observing that the white HAND light is lit and the red AUTO light is not lit (CC).

2. Holds the toggle switch on the MU-V-32 Bailey controller station in the downward direction until MU-V-32 indicates closed by the indicator being at 0 (CC).

Comment:

OP- TM-AOP-041 Step 3.4 Performance Step: 2 When 1D or 1E 4160V bus is energized, then CONTINUE.

Standard: Examinee verifies 1D and/or 1E 4160V bus is energized and continues.

Comment:

OP- TM-AOP-041 Step 3.5 Performance Step: 3 VERIFY a makeup pump is operating (MU header pressure MU2-PI is above RCS pressure) and aligned to seal injection.

Standard: Examinee determines that a makeup pump is not operating by none of the three makeup pumps showing red running lights or amps (CC/CR) and goes to the RNO column.

Comment:

20141LT NRC JPM C NUREG 1021, Revision 9 Supp 1

Appendix C Page 4 of 12 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-AOP-041 Step 3.5, RNO 1 Performance Step: 4 ENSURE MU-V-3 is Closed.

Standard: Examinee closes MU-V-3 by pressing the green closed pushbutton and verifying that the red Open light is not lit and the green closed light is lit (CC).

Comment:

OP-TM-AOP-041 Step 3.5, RNO 2 Performance Step: 5 ENSURE MU-V-17 is Closed.

Standard: Examinee closes MU-V-17 by:

1. Presses the white HAND button on the MU-V-17 Bailey controller station, observing that the white HAND light is lit and the red AUTO light is not lit (CC).

2. Holds the toggle switch on the MU-V-17 Bailey controller station in the downward direction until MU-V-17 indicates closed by the indicator being at 0 (CC).

Comment:

OP-TM-AOP-041 Step 3.5, RNO 3 Performance Step: 6 VERIFY [MU tank level >40"] or [MU-V-14A orB is Open].

Standard: Examinee verifies that MU tank level is greater than 40" by observing the MU-T level indicator (CC)

Comment:

Examiner Note: Step 3.5, RNO 4 is N/A.

20141LT NRC JPM C NUREG 1021, Revision 9 Supp 1

Appendix C Page 5 of 12 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-AOP-041 Step 3.5, RNO 5 Performance Step: 7 If MU-V-77 A & Bare Open, then GO TO section 4.0.

Standard: Examinee recognizes that MU-V-77A&B are open by the plate indicator (CC) or by recognizing the initial conditions did not state anything to contradict normal lineups, and Goes To Section 4.0 Comment:

Examiner Note: Step 4.0 is N/A.

Booth Operator Note: If contacted as an NLO, reply that MU-P-1A has been verified as ES selected.

OP-TM-AOP-041 Step 4.1 Performance Step: 8 Ensure MU-P-1A is ES Selected. (CB 338: 10 4160V Bus Unit 7)

Standard: Examinee recognizes MU-P-1A is ES Selected from the initial conditions.

Comment:

OP- TM-AOP-041 Step 4.2 Performance Step: 9 VERIFY one of the following:

- MU-V-36 and 37 are Open MU-V-16A or 168 is Open Standard: Examinee verifies that MU-V-36 and MU-V-37 are open by the red open lights lit, green closed lights not lit (CC)

Comment:

20141LT NRC JPM C NUREG 1021, Revision 9 Supp 1

Appendix C Page 6 of 12 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-AOP-041 Step 4.3 Performance Step: 10 ENSURE DR-P-1A and DC-P-1A are operating.

Standard: Examinee:

1. Starts DR-P-1A by rotating the Control switch clockwise to the Start position, releasing to the Normal-After-Start position, and verifying red running light lit, green stop light not lit, and amps (CC).

2. Starts DC-P-1 A by rotating the Control switch clockwise to the Start position, releasing to the Normal-After-Start position, and verifying red running light lit, green stop light not lit, and amps (CC).

Comment:

OP-TM-AOP-041 Step 4.4 Performance Step: 11 START MU-P-1 A.

Standard: Examinee attempts to start MU-P-1A by rotating the Control switch clockwise to the Start position, releasing to the Normal-After-Start position, recognizes that MU-P-1A fails to start by red running light not lit, green stop and yellow mismatch lights lit, and no amps (CC).

Examinee Goes to RNO column.

Comment:

Examiner Note: Step 4.4, RNO 1 is N/A.

OP-TM-AOP-041 Step 4.4, RNO 2 Performance Step: 12 If MU-P-1 Cis available, then GO TO Section 6.0.

Standard: Examinee determines that MU-P-1C is available and Goes To Section 6.0.

Comment:

Booth Operator Cue: If contacted as an NLO to open MU-V-76A&B, acknowledge the direction and insert EVENT #1 to open MU-V-76A&B.

20141LT NRC JPM C NUREG 1021, Revision 9 Supp 1

Appendix C Page 7 of 12 Form ES-C-1 PERFORMANCE INFORMATION OP- TM-AOP-041 Step 6.0 Performance Step: 13 If MU-V-76A & Bare closed and HPI train A and Normal MU header piping is intact, then DISPATCH an operator to open MU-V-76 A & B. (AB 281: MU valve alley)

Standard: Examinee determines that MU-V-76A&B are closed by the plate indicator (CC) or by recognizing the initial conditions did not state anything to contradict normal lineups, and dispatches an NLO to open MU-V-76A and MU-V76B.

Comment:

OP-TM-AOP-041 Step 6.1 Performance Step: 14 Ensure MU-P-1C is ES Selected. (CB 338: 1 E 4160V Bus Unit 9)

Standard: Examinee recognizes MU-P-1 Cis ES Selected from the initial conditions.

Comment:

OP- TM-AOP-041 Step 6.2 Performance Step: 15 VERIFY one of the following:

- MU-V-36 and 37 are Open MU-V-16A or 16B is Open Standard: Examinee verifies that MU-V-36 and MU-V-37 are open by the red open lights lit, green closed lights not lit (CC)

Comment:

20141LT NRC JPM C NUREG 1021, Revision 9 Supp 1

Appendix C Page 8 of 12 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-AOP-041 Step 6.3

-./ Performance Step: 16 ENSURE DR-P-1 P and DC-P-1 8 are operating.

Standard: Examinee:

1. Starts DR-P-1 8 by rotating the Control switch clockwise to the Start position, releasing to the Normal-After-Start position, and verifying red running light lit, green stop light not lit, and amps (CR).

2. Starts DC-P-1 8 by rotating the Control switch clockwise to the Start position, releasing to the Normal-After-Start position, and verifying red running light lit, green stop light not lit, and amps (CR).

Comment:

OP-TM-AOP-041 Step 6.4

-./ Performance Step: 17 START MU-P-1 C.

Standard: Starts MU-P-1 C by rotating the Control switch clockwise to the Start position, releasing to the Normal-After-Start position, and verifying red running light lit, green stop light not lit, and amps (CR).

Comment:

Alternate Path Begins Booth Operator Cue: Ensure Event #2 is triggered when MU-P-1C is started. If not, then Insert Event #2.

OP-TM-AOP-041 Step 3.1.A Performance Step: 18 IAAT ICCW flow is< 550 GPM (IC-5 Fl) and Sl Flow< 22 GPM, then perform the following:

A. ENSURE the reactor is tripped.

Standard: Examinee recognizes that ICCW flow is< 550 GPM (CR) and Sl Flow < 22 GPM (CC) and performs the Immediate Manual Actions of OP-TM-EOP-001.

Comment:

20141LT NRC JPM C NUREG 1021, Revision 9 Supp 1

Appendix C Page 9 of 12 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-EOP-001, Step 2.1

-./ Performance Step: 19 PRESS both Reactor Trip and DSS pushbuttons.

Standard: Examinee presses the Reactor Trip pushbutton (CC) and the DSS pushbutton (CC).

Comment:

OP- TM-EOP-001, Step 2.2 Performance Step: 20 VERIFY REACTOR SHUTDOWN.

Standard: Examinee verifies the reactor is shutdown as defined in OS-24, Conduct of Operations During Abnormal and Emergency Events:

The reactor is shutdown when the heat generation by fission has been stopped. This condition can be confirmed immediately following a reactor trip as follows:

1) Power Range Nl's indicate less than 5%,

2) all control rods are inserted, or

3) source range count rate is continuously lowering.

Comment:

OP-TM-EOP-001, Step 2.3

..,J Performance Step: 21 PRESS Turbine Trip pushbutton.

Standard: Examinee presses the Turbine Trip pushbutton (CL)

Comment:

OP-TM-EOP-001, Step 2.4 Performance Step: 22 VERIFY the turbine stop valves are Closed.

Standard: Examinee verifies the Turbine Stop Valves are closed by observing the digital indications on CL.

Comment:

Examiner Note: The examinee may perform a symptom check at this time, but it is not required.

20141LT NRC JPM C NUREG 1021, Revision 9 Supp 1

Appendix C Page 10 of 12 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-AOP-041 Step 3.1.8

...J Performance Step: 23 IAAT ICCW flow is< 550 GPM (IC-5 Fl) and Sl Flow< 22 GPM, then perform the following:

B. ENSURE all RCPs are tripped.

Standard: Examinee secures RC-P-1 A by rotating the Control Switch (CC) counter-clockwise to the "Stop" position and releasing it to the "Normal-After-Stop" position, verifying the green light is lit, red light is not lit, and amps indicate zero (CC).

Examinee secures RC-P-1 B by rotating the Control Switch (CC) counter-clockwise to the "Stop" position and releasing it to the "Normal-After-Stop" position, verifying the green light is lit, red light is not lit, and amps indicate zero (CC).

Examinee secures RC-P-1 C by rotating the Control Switch (CC) counter-clockwise to the "Stop" position and releasing it to the "Normal-After-Stop" position, verifying the green light is lit, red light is not lit, and amps indicate zero (CC).

Examinee secures RC-P-1 D by rotating the Control Switch (CC) counter-clockwise to the "Stop" position and releasing it to the "Normal-After-Stop" position, verifying the green light is lit, red light is not lit, and amps indicate zero (CC).

Comment:

Terminating Cue: After RCP's are secured, evaluation on this JPM is complete.

STOP TIME:

20141LT 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.: 2014 ILT NRC JPM C Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

20141LT 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 at 100% power.

MU-P-1 8 has tripped and is not selected for ES from either power supply.

You are the URO.

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

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

INITIATING CUE: The Control Room Supervisor directs you to restore Seal Injection lAW OP-TM-AOP-041, Loss of Seal Injection.

TIME CRITICAL: No 20141LT NRC JPM C NUREG 1021, Revision 9 Supp 1

Appendix C Page 1 of 6 Form ES-C-1 PERFORMANCE INFORMATION Facility: TMI Unit 1 Task No.: 40101004 Task

Title:

Transfer Feedwater Pump From ICS JPM No.: 20141LT NRC JPM D to the Motor Speed Changer KIA

Reference:

059 A2.11 (3.0 I 3.3)

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 operating at 100% power with ICS in full automatic.

Maintenance is scheduled to be performed on the E/P converter for FW-P-1A.

An Auxiliary Operator is standing by FW-P-1A speed control cabinet with a radio to support Operations.

You are the ARO.

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

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

Task Standard: Transfer Feedwater Pump From ICS to the Motor Speed Changer.

Required Materials: None General

References:

OP-TM-401-472, Manual Control of FW-P-1 A, Rev. 3 Handouts: OP-TM-401-472, Manual Control of FW-P-1A, Rev. 3 Initiating Cue: Transfer speed control of FW-P-1A to its Motor Speed Changer in accordance with OP-TM-401-472.

Time Critical Task: No Validation Time: 10 Minutes 20141LT NRC JPM D NUREG 1021, Revision 9 Supp 1

Appendix C Page 2 of 6 Form ES-C-1 PERFORMANCE INFORMATION SIMULATOR SETUP

1. Reset the simulator to IC 16 or similar 100% IC

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.

2014 ILT NRC JPM D NUREG 1021, Revision 9 Supp 1

Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

OP-TM-401-472, Step 4.1

....; Performance Step: 1 If ICS HAND power is energized, then transfer the FW-P-1A to HAND as follows:

PLACE FW-P-1A (FP A TURBINE SPEED CONTROL) station in HAND.

ADJUST FW-P-1A speed demand to maintain limits.

Standard:

Examinee verifies on PCL, ICS/NNI Power, Hand Power light is 'LIT".

Examinee presses White Hand PB on FW-P-1 A. White light is LIT.

Examinee adjusts FW-P-1A with toggle switch as necessary.

Comment:

Procedure Caution Ensure an operator is ready to adjust total FW flow as needed when FW pump speed is reduced. Fast Lower & Fast Raise positions on the governor control switch change FW pump Turbine speed rapidly.

OP-TM-401-472, Step 4.2.1

....; Performance Step: 2 If FW-P-1A speed control using MSC is required, then perform the following:

PLACE 1A FPT Governor control to Slow Lower or Fast Lower and LOWER FW-P-1A speed (FW-SR-6/7 or PPC A0320) approximately 100 rpm.

Standard:

Examinee rotates 1A FPT Governor control switch (CL) counter clockwise, until an approximate 100 rpm reduction in rpm is noted. 1A FPT Governor control switch is released.

Examinee verifies 1A FPT White "LOW' light is illuminated.

Comment:

2014 ILT NRC JPM D NUREG 1021, Revision 9 Supp 1

Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-401-472, Step 4.2.2

-.1 Performance Step: 3 PLACE FP A TURBINE Full Range Manual Speed control to ON.

Standard: FP A TURBINE Full Range Manual speed switch (CL) is rotated clockwise to 'ON'.

Comment:

OP-TM-401-472, Step 4.2.3

-.1 Performance Step: 4 ADJUST turbine speed with 1A FPT Governor to maintain limits.

Standard: Turbine speed adjusted as necessary to maintain limits.( -35 psid and equal flows on both Feed pumps)

Comment:

Terminating Cue: When candidate has demonstrated the ability to use the MSC to control feedwater flow, evaluation of this JPM is complete.

STOP TIME:

20141LT NRC JPM D NUREG 1021, Revision 9 Supp 1

Appendix C Page 5 of 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 20141LT 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:

2014 ILT NRC JPM D NUREG 1021, Revision 9 Supp 1

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

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

Maintenance is scheduled to be performed on the E/P converter for FW-P-1A.

An Auxiliary Operator is standing by FW-P-1A speed control cabinet with a radio to support Operations.

You are the ARO.

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

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

INITIATING CUE: Transfer speed control of FW-P-1A to its Motor Speed Changer in accordance with OP-TM-401-472.

TIME CRITICAL No 20141LT NRC JPM D NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND Task No.: 53401007 Task

Title:

Perform Emergency Operations of JPM No.: 2014 NRC JPM E Reactor Building Emergency Cooling Water- Alternate Path KIA

Reference:

022 A4.04 3.1 I 3.2 Modified from TQ-TM-1 04-534-J 100 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

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

Initial Conditions:

The Plant is at 100% power.

ICS is in full AUTO.

There is a small steam leak inside Containment.

The Operations Director is informed of the situation.

You are the ARO.

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

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

Task Standard: RB Emergency Cooling is initated with cooler pressure maintained 52-75 psig.

Required Materials: None General

References:

OP-TM-534-901 RB Emergency Cooling Operations, Rev. 12 Handout: OP-TM-534-901 signed off through Section 3.3.

Initiating Cue: The Control Room Supervisor has directed you to initiate Reactor Building Emergency Cooling using OP-TM-534-901, RB Emergency Cooling Operations.

2014 NRC JPM E NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: N/A Validation Time: 15 minutes SIMULATOR SETUP

IC-17 (Temporarily snapped in IC-252)

MALFUNCTIONS:

MS02A at 0.1% severity

MS02B at 0.1% severity

RWOB at 0% severity (to close RR-V-6)

03A4S46-ZDIRRV48(1) to OFF immediately

03A4S39-ZDIRRV48(2) to ON immediately

CCR32, NS-V-85 to close, on EVENT 1

Reduce power as necessary to maintain power less than 100%.

FREEZE the simulator.

2014 NRC JPM E NUREG 1021, Revision 9

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

START TIME:

Evaluator's Cue: Once OP-TM-534-901 is located, provide JPM copy.

Performance Step: 1 Locate OP-TM-534-901.

Standard: Locates procedure.

Comment:

Booth Operator Cue: When directed as an NLO to close NS-V-85, acknowledge the order, insert EVENT #1, and then report back that NS-V-85 is closed.

Evaluator's Note: Examinee does not have to wait for NS-V-85 to be closed to continue in the procedure.

OP-TM-534-901, Step 4.1. 1 Performance Step: 2 DISPATCH an operator to CLOSE NS-V-85 (IB 295: S of RR valve room).

Standard: Contacts AO to close NS-V-85.

Comment:

Procedure Note: The sequence of actuation and verification of ES is not train dependent. Either train may be performed first or trains may be performed in parallel.

2014 NRC JPM E NUREG 1021, Revision 9

Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-534-901, Step 4.1.2 Performance Step: 3 IAAT expected equipment response is not obtained when initiating the desired train(s) of R8EC, then INITIATE Section 4.2, Contingency Actions.

Standard: Examinee reads the statement and continues.

Comment:

OP-TM-534-901, Step 4.1.3

-,J Performance Step: 4 START or VERIFY running:

RR-P-1A

RR-P-1 8 Standard: Examinee starts RR-P-1A (CC) and RR-P-1 8 (CR) by rotating the Control Switch for each in the clockwise direction, observing the red "running" light is lit and the green "secured" light is not lit, and normal running amps indicated for each pump.

Comment:

OP-TM-534-901, Step 4.1.4

-,J Performance Step: 5 ENSURE OPEN:

RR-V-3A

RR-V-38

RR-V-3C Standard: Examinee opens RR-V-3A, RR-V-38 and RR-V-3C by pressing the respective OPEN pushbutton on CR.

Comment:

Alternate Path Begins 2014 NRC JPM E NUREG 1021, Revision 9

Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION Evaluator's Note: Once the examinee recognizes that RR-V-48 will not open, they may choose to immediately go to Section 4.2 or to continue with Section 4.1 prior to going to Section 4.2.

Either method is acceptable. This JPM continues in Section 4.1. Section 4.2 begins on Performance Step 8.

OP-TM-534-901, Step 4.1.5

--./ Performance Step: 6 ENSURE OPEN:

RR-V-4A

RR-V-48

RR-V-4C

RR-V-40

RR-V-1A

RR-V-1 8 Standard: Examinee opens RR-V-4A, RR-V-4C, RR-V-40, RR-V-1A AND RR-V-1 8 by pressing the respective OPEN pushbutton on CC and CR and observing the red "open" light lit and green "closed" light not lit.

Examinee recognizes that RR-V-48 will not open by the green "closed" light lit and red "open" light not lit (CR).

Comment:

OP-TM-534-901, Step 4.1.6 Performance Step: 7 VERIFY the coolers in service are controlled at 50- 75 psig:

RR-PI-224

RR-PI-225

RR-PI-226 Standard: Examinee determines that all coolers are greater than 75 psig and goes to Section 4.2.

Comment:

Evaluator's Note: Steps 4.2.1 through 4.2.6.1 are N/A.

2014 NRC JPM E NUREG 1021, Revision 9

Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-534-901, Step 4.2.6.2 Performance Step: 8 If RR-V-48 is not Open, then perform the following:

2. If RR-V-48 is not Open, then PLACE AH-E-1 8 in PTL.

Standard: Examinee determines that RR-V-48 cannot be opened and places AH-E-1 8 in PTL by rotating the Control Switch counter-clockwise and lifting until the Control Switch is captured in a lifted state (CR).

Comment:

Evaluator's Note: Steps 4.2. 7 through 4.2.13 are N/A.

Evaluator's Note: RR-PI-225 will not be in service due to RR-V-48 remaining closed. Therefore it will not get to less than 75 psig.

OP-TM-534-901, Step 4.2.14.1 Performance Step: 9 If any of the following are > 75 psig on coolers in service:

RR-PI-224

RR-PI-225

RR-PI-226 then perform the following:

OPEN RR-V-5.

Standard: Examinee verifies that the coolers are > 75 psig and opens RR-V-5 by pressing the red "open" pushbutton Comment:

2014 NRC JPM E NUREG 1021, Revision 9

Appendix C Page 7 of 9 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-534-901, Step 4.2.14.2

...J Performance Step: 10 If any of the following are > 75 psig on coolers in service:

RR-PI-224 RR-PI-225 RR-PI-226 then perform the following:

2. If< 52 psig on coolers in service, then JOG CLOSED RR-V-5 to maintain coolers in service> 52 psig.

Standard: Examinee presses the green "close", red "open", pushbuttons associated with RR-V-5, as appropriate, to ensure RR-PI-224 and RR-PI-226 indicate greater than 52 psig and less than 75 psig Comment:

Terminating Cue: When system pressure is stabilized using RR-V-5:

Evaluation on this JPM is complete.

STOP TIME:

2014 NRC JPM E NUREG 1021, Revision 9

Appendix C Page 8 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2014 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:

2014 NRC JPM E NUREG 1021, Revision 9

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

The Plant is at 100% power.

ICS is in full AUTO.

There is a small steam leak inside Containment.

The Operations Director is informed of the situation.

You are the ARO.

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

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

INITIATING CUE: The Control Room Supervisor has directed you to initiate Reactor Building Emergency Cooling using OP-TM-534-901, RB Emergency Cooling Operations.

TIME CRITICAL: No 2014 NRC JPM E NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND UNIT 1 Task No.: 73101010 Task

Title:

Return 1C 480V Bus to the Normal JPM No.: 2014 ILT NRC JPM F Power Supply KIA

Reference:

SYS 062 A4.01 3.3/3.1 NewJPM Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom

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

Initial Conditions:

A loss of offsite power occurred two hours ago, and has subsequently been restored.

1C 480V Bus is currently energized from the 1N Bus Cross Tie.

No loads were reduced on the 1N 480V Bus.

You are the ARO.

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

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

Task Standard: Return 1C 480V Bus to the Normal Power Supply.

Required Materials: None General

References:

OP-TM-731-901, ENERGIZE 1C 480V BUS USING 1N BUS CROSS TIE, Rev. 2 1107-11, TMI Grid Operations, Rev 30 Handout: OP-TM-731-901, ENERGIZE 1C 480V BUS USING 1N BUS CROSS TIE, Rev. 2, signed off through step 4.2.9 2014 ILT NRC JPM F NUREG 1021, Revision 9 Supp1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Initiating Cue: The SM/ED directs you to restore normal power to the 1C 480V Bus lAW OP-TM-731-901, ENERGIZE 1C 480V BUS USING 1N BUS CROSS TIE.

Time Critical Task: No Validation Time: 10 minutes 2014 ILT NRC JPM F NUREG 1021, Revision 9 Supp1

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

1. IC-16 (Temporarily snapped in IC-124)

a. Insert ED01 immediately. Once in, delete malfunction.

b. Perform OP-TM-AOP-020 through Step 5.3.1 (including Attachment 2)

c. Perform OP-TM-731-901 through Step 4.2.9

d. Ensure EDG Voltage is less than 50 V difference with A and D 4KV

e. Start SC-P-18 and place SC-P-1C in PTL

f. Place C1-02 in PTL.

g. Place 1C-02 in PTL.

h. 1OA 1S23-ZDILTCA43S(1) AUTO OFF

i. Ensure MUMMT=1 0000.0

j. FREEZE the simulation.

2. This completes the setup for this JPM.

20141LT NRC JPM F NUREG 1021, Revision 9 Supp1

Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark}

START TIME:

Evaluator Cue: Provide a copy of OP-TM-731-901, filled out through step 4.2.9 OP-TM-731-901 Step 5.1 Performance Step: 1 When 1A 4160V Bus is energized and SM/ED concurrence has been obtained to restore normal power to the 1C bus, then CONTINUE.

Standard: The Examinee verifies that the 1A 4160V Bus is energized and that SM/ED concurrence has been obtained Comment:

OP-TM-731-901 Step 5.2 Performance Step: 2 If 1A and 1D 4160 Volt bus voltage difference is greater than 50 volts, then

a. Place Aux Xfmr 1A load tap changer in manual lAW 1107-11.

b. Place Aux Xfmr 1B load tap changer in manual lAW 1107-11.

c. ADJUST Aux Xfmr LTC associated with the lower voltage to reduce the difference to less than 50 volts.

Standard: The Examinee observes that 1A and 1D 4160 Volt bus voltage difference is NOT greater than 50 volts and N/A's the step.

Comment:

OP-TM-731-901 Step 5.3 Performance Step: 3 VERIFY 1C-02 is OPEN.

Standard: Examinee VERIFIES 1C-02 is Open by the switch in PTL and no associated lights are lit.

Comment:

2014 ILT NRC JPM F NUREG 1021, Revision 9 Supp1

Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-731-901 Step 5.4

...J Performance Step: 4 ENSURE C1-02 is CLOSED.

Standard: Examinee observes that C1-02 is in Pull-to-Lock and closes C1-02 by pushing inward and then fully clockwise, verifying red light lit, green light not lit, and red flag indicated.

Comment:

OP-TM-731-901 Step 5.5 Performance Step: 5 ANNOUNCE "Restoring the 1C 480V bus to normal power source".

Standard: The Examinee announces "Restoring the 1C 480V bus to normal power source".

Comment:

Evaluator Note: The following two steps require two-handed operation.

OP-TM-731-901 Step 5.6

...J Performance Step: 6 HOLD 1C-02 extension control switch in the CLOSED position.

Standard: Examinee holds 1C-02 extension control switch in the CLOSED position.

Comment:

OP-TM-731-901 Step 5.7

...J Performance Step: 7 OPEN T2-C2.

Standard: The Examinee Opens T2-C2 while still holding 1C-02 extension control switch in the CLOSED position.

Comment:

20141LT NRC JPM F NUREG 1021, Revision 9 Supp1

Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-731-901 Step 5.8 Performance Step: 8 When 1C-02 is closed, then release 1C-02 extension control.

Standard: The Examinee VERIFIES 1C-02 is closed and then releases the 1C-02 extension control.

Comment:

OP-TM-731-901 Step 5.9 Performance Step: 9 OPEN 1N-12.

Standard: The Examinee Opens 1N-12 by rotating the Control Switch counter-clockwise and verifying green indicating flag and light.

Comment:

OP-TM-731-901 Step 5.10 Performance Step: 10 ENSURE both Aux. Transformer load tap changers are in AUTO.

1A Aux Transformer LTC in AUTO lAW 1107-11.

1B Aux Transformer LTC in AUTO lAW 1107-11.

Standard: The Examinee VERIFIES 1A and 1B Aux Transformers are in AUTO.

Comment:

OP-TM-731-901 Step 5.11 Performance Step: 11 If 1N Unit 1C was opened to reduce N bus load, then CLOSE 1N Unit 1C Standard: The Examinee determines from the initial conditions and/or Attachment 1 of OP-TM-731-901 that 1N Unit 1C was not opened and N/A's the step.

Comment:

20141LT NRC JPM F NUREG 1021, Revision 9 Supp1

Appendix C Page 7 of 9 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-731-901 Step 5.12 Performance Step: 12 PLACE the following in Normal-after-stop VA-P-1 A Main Vacuum Pump A VA-P-1C Main Vacuum Pump C SC-P-1 A Secondary Closed Cooling Pump A Standard: The Examinee places the following in Normal-after-Stop:

VA-P-1A Main Vacuum Pump A VA-P-1 C Main Vacuum Pump C SC-P-1A Secondary Closed Cooling Pump A Comment:

OP-TM-731-901 Step 5.13 Performance Step: 13 If SC-P-1 C is in PTL, then PLACE SC-P-1 C in Normal-After-Stop.

Standard: The Examinee determines SC-P-1C is in PTL and places SC-P-1C in Normal-After-Stop.

Comment:

OP- TM-731-901 Step 5.14 Performance Step: 14 ENSURE all breakers on Attachment 1 are CLOSED.

Standard: The Examinee determines that there are no breakers listed on Attachment 1.

Comment:

Terminating Cue: When OP-TM-731-901 Step 5.14 is completed, the JPM can be terminated.

STOP TIME: TIME CRITICAL STOP TIME: N/A 20141LT NRC JPM F NUREG 1021, Revision 9 Supp1

Appendix C Page 8 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2014 ILT 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:

20141LT NRC JPM F NUREG 1021, Revision 9 Supp1

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

A loss of offsite power occurred two hours ago, and has subsequently been restored.

1C 480V Bus is currently energized from the 1N Bus Cross Tie.

No loads were reduced on the 1N 480V Bus.

You are the ARO.

The instructor/examiner will act as the URO and CAS.

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

INITIATING CUE: The SM/ED directs you to restore normal power to the 1C 480V Bus lAW OP-TM-731-901, ENERGIZE 1C 480V BUS USING 1N BUS CROSS TIE.

TIME CRITICAL: No 20141LT NRC JPM F NUREG 1021, Revision 9 Supp1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: TMI Unit 1 Task No.: 66101004 Task

Title:

Respond lAW OP-TM-MAP-C0101 JPM No.: 2014 ILT NRC JPM G Alarm Response with Failure-Alternate Path KIA

Reference:

072 A3.01 (2.9 I 3.1) 2011 NRC JPM G 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 operating at 100% power with ICS in full automatic.

No Maintenance or surveillances are scheduled for this shift.

You are the ARO.

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

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

Task Standard: Place Control Building Ventilation in the Emergency Recirculation mode.

Required Materials: None General

References:

OP-TM-MAP-C0101, Radiation Level HI, Rev 2A OP-TM-826-901, CONTROL BUILDING VENTILATION SYSTEM RADIOLOGICAL RESPONSE OPERATIONS, Rev 2 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 2014 ILT NRC JPM G NUREG 1021, Revision 9 Supp 1

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

1. Reset the simulator to IC 16 (Temporarily snapped into IC-127}

2. Insert the following Malfunctions:

RM01 G, AH-E-17A fails to trip on interlock, insert immediately 13A6S06ZDICSAHE18B(5) str to OFF, AH-E-188 fails to start, insert immediately Create or Verify the following Batch File (RMA 1.bat)

NOTE: Current batch file has a ramp time of 1 min. This scenario requires a THREE (3) min ramp time so batch file must be changed for this scenario.

Set RMPASSWORD = 168 Set RM:NEWFILE =True Set RMRAMPIN = 3 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.

20141LT NRC JPM G NUREG 1021, Revision 9 Supp 1

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

START TIME:

Evaluator Note: The examinee may recognize that the Automatic actions of C-1-1 did not occur and may perform the actions lAW OS-24.

ICC Cue: When directed, type into expert command: bat RMA1.bat Evaluator Cue: Acknowledge condition and entry into OP-TM-MAP-C01 01.

OP-TM-MAP-C0101, Step 4.1 Performance Step: 1 ANNOUNCE alarm over plant page and radio.

Standard: Examinee announces RM-A-1 Hi Alarm over the plant page and radio.

Comment:

ICO Cue: Acknowledge, as RadPro, to verify the alarm and determine the source.

OP-TM-MAP-C0101, Step 4.2 Performance Step: 2 Notify Radiation Protection to verify the alarm and determine the source.

Standard: Examinee notifies Radiation Protection to verify the alarm and determine the source.

Comment:

20141LT NRC JPM G NUREG 1021, Revision 9 Supp 1

Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION Examiner's Note: The candidate will review the next step but it will not be applicable C-1-1 alarms with RM-A-1 in High Alarm.

Examiner's Note: If requested to evaluate donning SCBAs, report "No SCBAs are required".

If requested to evaluate EAL's, acknowledge the request.

OP-TM-MAP-C0101, Step 4.3 Performance Step: 3 IAAT High Alarm is Lit, then perform the following:

PERFORM OP-TM-826-901, " Control Building Ventilation System Radiological Response Operations":

EVALUATE donning SCBA's.

REQUEST SM to evaluate Emergency Action Levels (EALs).

Standard: Examinee verifies RM-A-1 High alarm is Lit (PRF), and goes to OP-TM-826-901.

Comment:

Examiner's Note: ALTERNATE PATH BEGINS OP-TM-826-901, Step 4. 1.2

~ Performance Step: 4 ENSURE the following fans are shutdown:

- AH-E-17A and AH-E-178

- AH-E-95A and AH-E-958

- AH-E-20A and AH-E-208 Standard: Examinee ensures AH-E-178, AH-E-95A/B, AH-E-20A/B are shutdown.

Examinee recognizes that AH-E-17A is running and secures AH-E-17 A, by rotating extension control in the counter-clockwise direction (H&V A).

Examinee recognizes that AH-E-20A is running and secures AH-E-20A, by rotating extension control in the counter-clockwise direction (H&V A).

Comment:

20141LT NRC JPM G NUREG 1021, Revision 9 Supp 1

Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION OP- TM-826-901, Step 4.1.3 Performance Step: 5 SHUTDOWN AH-E-19A and AH-E-19B.

Standard: Examinee 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: Examinee 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: Examinee places ext. controls for AH-E-93/94A and AH-E-93/94B to the OFF position on H& V Center.

Comment:

OP- TM-826-901, Step 4.1.6 Performance Step: 8 START AH-E-18B (A) if AH-E-17 A (B) was previously operating.

Standard: Examinee attempts to start AH-E-18B (H&V B), by rotating extension control to start and waiting for discharge damper to drive to the open position, recognizes it does not start.

Comment:

20141LT NRC JPM G NUREG 1021, Revision 9 Supp 1

Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION Evaluator Cue: When the candidate states that there is a 2 minute wait, announce "time compression is in effect and 2 minutes has elapsed".

OP-TM-826-901, Step 4.1.7

..J Performance Step: 9 If the opposite train of ventilation is unavailable, then WAIT 2 minutes after AH-E-17A (B) was shutdown and START AH-E-18A (B).

Standard: Examinee waits 2 minutes Examinee 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.

Comment:

OP-TM-826-901, Step 4.1.8 Performance Step: 10 ENSURE AH-E-19A orB is operating.

Standard: Examinee 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-95A or B is operating.

Standard: Examinee ensures AH-E-95A is operating by observing RED light H& V Center.

Comment:

ICO Cue: Acknowledge, as an NLO, to start AH-E-90 and AH-E-91.

2014 ILT NRC JPM G NUREG 1021, Revision 9 Supp 1

Appendix C Page 7 of 9 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-826-901, Step 4.1. 10 Performance Step: 12 START AH-E-90 and AH-E-91.

Standard: Examinee orders 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.

20141LT NRC JPM G NUREG 1021, Revision 9 Supp 1

Appendix C Page 8 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2014 ILT NRC JPM G Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

20141LT NRC JPM G NUREG 1021, Revision 9 Supp 1

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

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

No Maintenance or surveillances are scheduled for this shift.

You are the ARO.

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

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

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

TIME CRITICAL No 20141LT 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.: 82401001 Task

Title:

Initiate and Isolate a Reactor JPM No.: 20141LT NRC JPM H Building Purge -Alternate Path KIA

Reference:

SYS 029 K1.01 3.4/3. 7 Bank JPM, TMI08 NRC JPM G 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 in Hot Shutdown in preparation for a refueling outage.

Normal equipment lineups exist.

A Reactor Building Purge is being started lAW OP-TM-823-406, RB Purge- Containment Closed.

The maximum allowable flow per permit is 47,500 scfm.

You are the ARO.

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

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

An Auxiliary Operator is available to report AH-TI-6A and AH-TI-6B temperatures.

An Auxiliary Operator is available to adjust AH-PC-1146 as needed.

Task Standard: RB Purge is initiated and then isolated following an RM-G-9G High Radiation alarm.

Required Materials: Key #2 General

References:

OP-TM-823-406, RB Purge Containment Closed, Rev. 9 OP-TM-MAP-C0101, Radiation Level Hi, Rev. 2A 20141LT NRC JPM H NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet 661 0-ADM-4250.12, Releasing Radioactive Gaseous Effluents -

Reactor Building Purge, Rev 16, signed off through Step 3.3 Handout: OP-TM-823-406, RB Purge Containment Closed, Rev. 9, signed off through Step 4.6 and Step 4.22 is marked as N/A Initiating Cue: The CRS directs you to INITIATE a Reactor Building Purge lAW OP-TM-823-406, RB Purge Containment Closed, not to exceed a rate of 20,000 scfm.

Time Critical Task: No Validation Time: 30 minutes 20141LT NRC JPM H NUREG 1021, Revision 9

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

1. Initialize the Trainer to Temp IC 128, Hot Shutdown

a. INSERT MALFUNCTION RM01 L RM-A9 INTERLOCK FAILURE IMMEDIATELY.

b. PLACE MALFUNCTION RM04H RM-A-9G ATMOSPHERIC RAD MONITOR FAILS HIGH ON EVENT #1.

2. Complete OP-TM-823-406, RB Purge- Containment Closed, signed off through Step 4.6 and Step 4.22 is marked as N/A

3. FREEZE the simulation.

4. This completes the setup for this JPM.

20141LT NRC JPM H NUREG 1021, Revision 9

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

START TIME:

Procedure Note: Fan suction damper will open allowing fan to start when fully open.

Procedure Note: CAUTION: To prevent damage to makeup duct containing AH-D-225, do not operate the purge system if total purge flow (AH-FR-148A) minus RB exhaust flow (AH-FR-1488 or AH-FR-909) exceeds 36,000 SCFM.

OP-TM-823-406 Step 4.7

,J Performance Step: 1 START the following:

AH-E-7A AH-E-78 Standard: The Examinee starts AH-E-7A by rotating the control switch in the clockwise direction and releasing, observing red running light lit and green secured light not lit (PL).

The Examinee starts AH-E-78 by rotating the control switch in the clockwise direction and releasing, observing red running light lit and green secured light not lit (PL).

Comment:

Evaluator Cue: AH-PC-1146 is normally set at 39.5. Role play as Auxiliary Operator to locally adjust AH-PC-1146 to the desired position.

OP-TM-823-406 Step 4.8 Performance Step: 2 ENSURE AH-PC-1146 is set to 9.5 for single AH-E-7 operation or 39.5 for two AH-E-7 operation.

Standard: The Examinee ensures AH-PC-1146 is set to 39.5.

Comment:

20141LT NRC JPM H NUREG 1021, Revision 9

Appendix C Page 5 of 11 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-823-406 Step 4.9

.Y Performance Step: 3 OPEN AH-V-1A.

Standard: Examinee opens AH-V-1A by pressing the red open pushbutton and verifying that the valve is open by the red light being lit and the green light not being lit (PL).

Comment:

Evaluator Cue: When the examinee has located the Key locker near the LWDS panel, hand Key #2 to the examinee.

OP-TM-823-406 Step 4.10

.Y Performance Step: 4 PLACE lock key switch for AH-V-1 Bin OPENING PERMITTED.

Standard: The Examinee places the lock key switch for AH-V-1 Bin OPENING PERMITTED position by inserting Key #2 into the appropriate slot and turning it clockwise to the OPENING PERMITTED position (PL).

Comment:

OP-TM-823-406 Step 4.11

.Y Performance Step: 5 OPEN AH-V-1 B.

Standard: Examinee opens AH-V-18 by pressing the red open pushbutton and verifying that the valve is open by the red light being lit and the green light not being lit (PL).

Comment:

20141LT NRC JPM H NUREG 1021, Revision 9

Appendix C Page 6 of 11 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-823-406 Step 4.12 Performance Step: 6 PLACE lock key switch for AH-V-18 in OPENING DEFEATED.

Standard: The Examinee places the lock key switch for AH-V-1 8 in OPENING DEFEATED position by turning Key #2 counter-clockwise to the OPENING DEFEATED position and removing Key #2 from the appropriate slot (PL).

Comment:

Evaluator Note: Step 4.13 and 4.14 are N/A.

OP-TM-823-406 Step 4. 15 Performance Step: 7 If one of the following conditions exists:

Maximum permissible purge rate lAW Rad Permit is~

25,000 scfm.

Purge valves are limited to 30° open.

Only one purge exhaust fan is operating.

Only one purge supply fan is operable.

then START one purge supply fan, otherwise START both of the following:

AH-E-6A AH-E-68 Standard: The Examinee determines that purge valves are limited to 30° open and starts EITHER AH-E-6A or AH-E-68 by rotating the control switch in the clockwise direction and releasing, observing red running light lit and green secured light not lit (PL).

Comment:

OP-TM-823-406 Step 4.16

.V Performance Step: 8 OPEN AH-V-1D.

Standard: Examinee opens AH-V-1 D by pressing the red open pushbutton and verifying that the valve is open by the red light being lit and the green light not being lit (PL).

Comment:

20141LT NRC JPM H NUREG 1021, Revision 9

Appendix C Page 7 of 11 Form ES-C-1 PERFORMANCE INFORMATION OP- TM-823-406 Step 4.17

--./ Performance Step: 9 PLACE lock key switch for AH-V-1C in OPENING PERMITTED.

Standard: The Examinee places the lock key switch for AH-V-1C in OPENING PERMITTED position by inserting Key #2 into the appropriate slot and turning it clockwise to the OPENING PERMITTED position (PL).

Comment:

OP-TM-823-406 Step 4.18

--./ Performance Step: 10 OPEN AH-V-1C.

Standard: Examinee opens AH-V-1C by pressing the red open pushbutton and verifying that the valve is open by the red light being lit and the green light not being lit (PL).

Comment:

OP-TM-823-406 Step 4.19 Performance Step: 11 PLACE lock key switch for AH-V-1C in OPENING DEFEATED.

Standard: The Examinee places the lock key switch for AH-V-1 C in OPENING DEFEATED position by turning Key #2 counter-clockwise to the OPENING DEFEATED position and removing Key #2 from the appropriate slot (PL).

Comment:

Evaluator Note: Step 4.20 and 4.21 are N/A.

OP-TM-823-406 Step 4.22 Performance Step: 12 MARK FR-148 with start time, date, and release number.

Standard: This step is N/A since the recorder is now digital.

Comment:

20141LT NRC JPM H NUREG 1021, Revision 9

Appendix C Page 8 of 11 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-823-406 Step 4.23

.Y Performance Step: 13 ADJUST RB Purge Manual Loader Purge Rate (AH-D-8B-EX1) to establish desired purge rate (not to exceed maximum allowable purge rate) and maintain RB pressure near 0 psig.

Standard: The Examinee adjusts the RB Purge Manual Loader Purge Rate by dialing AH-D-8B-EX1 as necessary to establish desired flow rate of approximately 20,000 scfm, given in the initiating cue (H& V), while ensuring RB pressure is maintained near 0 psig by observing RB pressure meters (PC).

Comment:

Alternate Path Begins Booth Operator Cue: When directed by the examiner, Insert EVENT #1 Evaluator Note: The Examinee may immediately close AH-V-1A-D based on OS-24, section 4.3.5 Reactor "At Power" Protocol:

Any time an automatic control or interlock functions fails to perform as designed and there is no specific procedure direction, the reactor operator should take action to compensate directly for the failure.

Evaluator Cue: Acknowledge as Radiation Protection and/or the Shift Manager for possible notification/direction.

Evaluator Note: OP-TM-MAP-C0101 has an IAAT at step 4.6 that is applicable upon entry into the alarm response. The examinee may perform steps 4.1-4.5, but these are not necessary prior to step 4.6 20141LT NRC JPM H NUREG 1021, Revision 9

Appendix C Page 9 of 11 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-MAP-C0101, RM-A-9 Step 4.6.1

>I Performance Step: 14 IAAT high alarm is Lit, then perform the following:

If fuel handling is not in progress, then ENSURE the following are Closed:

AH-V-1A AH-V-18 AH-V-1C AH-V-10 Standard: The Examinee:

Closes AH-V-1A by pressing the green closed pushbutton and verifying that the red Open light is not lit and the green closed light is lit (PL).

Closes AH-V-1 B by pressing the green closed pushbutton and verifying that the red Open light is not lit and the green closed light is lit (PL).

Closes AH-V-1C by pressing the green closed pushbutton and verifying that the red Open light is not lit and the green closed light is lit (PL).

Closes AH-V-1 D by pressing the green closed pushbutton and verifying that the red Open light is not lit and the green closed light is lit (PL).

Comment:

Terminating Cue: When AH-V-1 A, AH-V-1 8, AH-V-1 C and AH-V-1 D are closed the JPM can be terminated.

STOP TIME:

20141LT NRC JPM H NUREG 1021, Revision 9

Appendix C Page 10 of 11 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 20141LT NRC JPM H Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

20141LT NRC JPM H NUREG 1021, Revision 9

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

The Reactor is in Hot Shutdown in preparation for a refueling outage.

Normal equipment lineups exist.

A Reactor Building Purge is being started lAW OP-TM-823-406, RB Purge - Containment Closed.

The maximum allowable flow per permit is 47,500 scfm.

You are the ARO.

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

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

An Auxiliary Operator is available to report AH-TI-6A and AH-TI-6B temperatures.

An Auxiliary Operator is available to adjust AH-PC-1146 as needed.

INITIATING CUE: The CRS directs you to INITIATE a Reactor Building Purge lAW OP-TM-823-406, RB Purge Containment Closed, not to exceed a rate of 20,000 scfm.

TIME CRITICAL No 20141LT NRC JPM H NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Three Mile Island Task No.: 73401002 Task

Title:

RETURN A BATTERY CHARGER JPM No.: 2014 NRC JPM I TO SERVICE KIA

Reference:

058 AA1.03 3.1 I 3.3 Bank TQ-TM-1 05-734-J001 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:

The Reactor is at 100% power.

1E battery charger is shutdown following maintenance.

The 1A battery charger has failed and is out of service with all of its associated breakers OPEN.

The 1 E battery charger is available to be placed in service.

You are the Third Reactor Operator (RO).

Task Standard: The 1E battery charger placed in-service to replace the 1A battery charger.

Required Materials: 1107-2C, Vital DC Electrical System, Revision 12 General

References:

1107-2C, Vital DC Electrical System, Revision 12 Handout: 1107-2C, Vital DC Electrical System, all steps signed off up to 3.1.3.1 Initiating Cue: The CRS has directed you to place the 1E battery charger in-service to replace the 1A battery charger in accordance with 1107-2C.

2014 NRC JPM I NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: N/A Validation Time: 25 minutes 2014 NRC JPM I NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP N/A 2014 NRC JPM I NUREG 1021, Revision 9

Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

EVALUATOR CUE: Provide a copy of 11 07-2C, Vital DC Electrical System EVALUATOR CUE: If Examinee establishes communications with the Control Room, role play as a Control Room Operator.

EVALUATOR CUE: If asked about prerequisites, state that" all Prerequisites have been completed and Shift Manager permission has been obtained as required".

Performance Step: 1 Locate 1E Battery Charger.

Standard: Examinee proceeds to the 1E Battery Charger in the Inverter Room on the 2nd floor of the Control Tower.

Comment:

EVALUATOR CUE: As required, simulate or state that the positions of the handles for both the AC and DC breakers on the front of the 1E battery charger, indicate down.

PROCEDURE NOTE: When placing a battery charger in standby operation, or placing it in service, it is important to follow the sequence exactly as written. This will prevent damage to the charger and prevent possible loss of a vital AC Bus.

2014 NRC JPM I NUREG 1021, Revision 9

Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION 1107-2C, Step 3.1.3.1 Performance Step: 2 Verify the AC and DC breakers on the front of the battery charger are OPEN.

Standard: Examinee verifies the "AC CKT BKR" and the "DC CKT BKR" switches are open (in the down position) on the front of the 1E Battery Charger.

Comment:

EVALUATOR CUE: When contacted as the Control Room as to which panel the charger should be started up to supply, state "A" DC panel unit #1.

1107-2C, Step 3.1.3.2 Performance Step: 3 IF the battery charger being returned to service is the 1E or 1F charger, THEN get direction from the CRS/SM as to which panel the charger should be started up to supply. (If not 1E or 1F then N/A)

- - - - D C Panel Standard: Examinee recognizes that the battery charger is the 1 E.

Examinee requests info from the Control Room and writes "A" DC panel unit #1 on the line.

Comment:

EVALUATOR CUE: As required, simulate or state that the position of the handle on #1 CL on 1A ES MCC is down (\).

When simulated closed, simulate or state that the position of the handle on #1 CL on 1A ES MCC is up (/).

2014 NRC JPM I NUREG 1021, Revision 9

Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION 11 07-2C, Step 3. 1.3.3

..,J Performance Step: 4 CLOSE the AC 480 volt supply breaker to the charger being started up, as listed below: (N/A those chargers not being started up.)

Standard: Examinee simulates closing the 480V AC Power Supply breaker for the 1E Station Battery Charger, #1 CL on 1A ES MCC and N/A's the other lines in this step.

Comment:

EVALUATOR CUE: As required, simulate or state that the position of the handles on "A" DC panel units #1 and #2 are down(\).

When simulated closed, simulate or state that the position of the handle on "A" DC panel unit #1 is up (/).

PROCEDURE NOTE: 1E and 1F battery chargers have two breakers each. Only one can be closed in at a time and the other breaker must be verified open prior to closing one.

1107-2C, Step 3.1.3.4

..,J Performance Step: 5 Close the DC switch on the DC Dist panel for the charger to be started up. (N/A those chargers not being started up.)

Standard: Examinee verifies "1 A" DC panel unit #2 is open and simulates closing "1A" DC panel unit #1. Examinee N/A's all other lines in this step Comment:

EVALUATOR CUE: When simulated closed, simulate or state that the position of DC breaker on the front of the 1E charger is closed.

EVALUATOR NOTE: Performing Steps 6 and 7 out of order could cause possible damage to the battery chargers and is grounds for JPM failure.

PROCEDURE NOTE: When starting up a battery charger, it is possible to damage the rectifier stack or blow the anode fuse if the DC breaker is not closed first.

2014 NRC JPM I NUREG 1021, Revision 9

Appendix C Page 7 of 9 Form ES-C-1 PERFORMANCE INFORMATION 1107-2C, Step 3.1.3.5

...J Performance Step: 6 CLOSE the DC circuit breaker on the front of the charger.

Standard: Examinee simulates closing the DC circuit breaker on the front of the 1E charger.

Comment:

EVALUATOR CUE: When simulated closed, simulate or state that the position of AC breaker on the front of the 1E charger is closed.

1107-2C, Step 3.1.3.6

...J Performance Step: 7 Close the AC circuit breaker on the front of the charger.

Standard: Examinee simulates closing the AC circuit breaker on the front of the 1E charger.

Comment:

Terminating Cue: After the AC circuit breaker is closed on the 1E battery charger: This JPM is complete.

STOP TIME:

2014 NRC JPM I NUREG 1021, Revision 9

Appendix C Page 8 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2014 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:

2014 NRC JPM I NUREG 1021, Revision 9

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

The Reactor is at 100% power.

1E battery charger is shutdown following maintenance.

The 1A battery charger has failed and is out of service with all of its associated breakers OPEN.

The 1E battery charger is available to be placed in service.

You are the Third Reactor Operator (RO).

INITIATING CUE: The CRS has directed you to place the 1E battery charger in-service to replace the 1A battery charger in accordance with 1107-2C.

TIME CRITICAL No 2014 NRC JPM I NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND UNIT 1 Task No.: 41101004 Task

Title:

Locally/Manually Operate a Turbine JPM No.: 2014 NRC JPM J Bypass Valve KIA

Reference:

041 A4.08 (3.0/3.1) Bank J PM TQ-TM-1 05-411-J 100 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 ICS Hand and Auto Power has occurred

The crew has entered OP-TM-AOP-025, Loss of ICS Hand and Auto Power.

The Reactor has been tripped and OP-TM-EOP-001 has been initiated.

FW-P-1A and FW-P-1 B have been tripped.

Emergency Feedwater has been initiated.

You are an extra Reactor Operator on shift.

Task Standard: Simulated MS-V-3C being controlled locally in Manual.

Required Materials: None General

References:

OP-TM-411-451, Manual Control of TBVs/ADVs, Revision 6 Handout: Attachment 7.1 of OP-TM-411-451 , Manual Control of TBVs/ADVs, Revision 6 2014 NRC JPM J NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Initiating Cue: Take local control of MS-V-3C lAW OP-TM-411-451, Attachment 7.1, Local Operation of the TBV's (MS-V-3s), and await further direction from the Control Room.

Time Critical Task: NO Validation Time: 15 Minutes SIMULATOR SETUP N/A 2014 NRC JPM J 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 CUE: Provide the candidate a copy of OP-TM-411-451, Attachment 7.1, Local Operation of TBVs (MS-V-3s).

EVALUATOR CUE: The sleeve for MS-V-3C will slide up/down as the handwheel is rotated in the direction of the arrow on the handwheel.

Performance Step: 1 Obtain/review procedure.

Standard: Candidate proceeds to TB 322' elevation, West side of Main Condenser and reviews OP-TM-411-451 , Attachment 7 .1.

Comment:

EVALUATOR CUE: If candidate correctly describes rotating the handwheel to align the holes in the sleeve and stem, state "the holes are aligned".

If candidate does not correctly describe rotating the handwheel to align the holes in the sleeve and stem, state "the holes are not aligned".

OP-TM-411-451, Attachment 7.1, Step 2 Performance Step: 2 Turn the handwheel to align the hole in the sleeve with the hole in the stem (either set of holes will work)

..J Standard: Candidate simulates rotating the handwheel to align the holes in the sleeve and the stem using either set of holes.

Comment:

EVALUATOR CUE: If candidate correctly describes inserting the pin, state "the pin is inserted".

If candidate does not correctly describe inserting the pin, state "the pin is not inserted".

2014 NRC JPM J NUREG 1021, Revision 9 Supp 1

Appendix C Page 4 of 8 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-411-451, Attachment 7.1, Step 3 Performance Step: 3 Insert pin (located on valve housing, attached to a chain)

-../ Standard: Candidate locates the pin and simulates inserting the pin into the holes of the sleeve and stem on the manual operator.

Comment:

PROCEDURE NOTE: Auto/Manual switch for MS-V-3s is located on side of positioner box.

EVALUATOR CUE: If candidate correctly describes positioning the switch, state "the switch is in manual".

If candidate does not correctly describe positioning the switch, state "the switch is in auto".

OP-TM-411-451, Attachment 7.1, Step 4 Performance Step: 4 Press and rotate Auto/Manual switch to the Manual position.

Switch is "Press to Turn"

Switch must be rotated 90 degrees counter clockwise.

-../ Standard: Candidate simulates pressing and rotating the Auto/Manual switch 90 degrees counter clockwise to the Manual position.

Comment:

EVALUATOR CUE: If candidate correctly describes opening the actuator equalizing valve, state "the actuator equalizing valve is open".

If candidate does not correctly describe opening the actuator equalizing valve, state "the actuator equalizing valve is closed".

2014 NRC JPM J NUREG 1021, Revision 9 Supp 1

Appendix C Page 5 of 8 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-411-451, Attachment 7.1, Step 5 Performance Step: 5 Open the actuator Equalizer valve (located near the valve operator and marked as Equalizing Valve).

" Standard: Candidate simulates opening the actuator equalizing valve by rotating the handwheel counter clockwise to the fully open position.

Comment:

OP-TM-411-451, Attachment 7.1, Step 6 Performance Step: 6 Maintain Header Pressure within limits by adjusting TBV/ADV handwheel. Position MS-V-3C as needed using handwheel.

Standard: Candidate contacts Control Room and informs them that MS-V-3C is in Manual and awaits instructions to position the valve.

Comment:

EVALUATOR CUE: When contacted, state "Main Header Pressure is too high.

Throttle MS-V-3C two and one half turns open".

EVALUATOR CUE: If candidate correctly describes OPENING MS-V-3C two and one half turns, then when they call it in to the ARO in the Control Room respond with "Main Header Pressure is responding".

If candidate does not correctly describe opening MS-V-3C two and one half turns, then when they call it in to the ARO in the Control Room respond with "Main Header Pressure is not responding".

OP-TM-411-451, Attachment 7.1, Step 6 Performance Step: 6 Throttle MS-V-3C two and one half turns open.

" Standard: Candidate simulates rotating the handwheel for MS-V-3C counter-clockwise two and one half turns.

Comment:

2014 NRC JPM J NUREG 1021, Revision 9 Supp 1

Appendix C Page 6 of 8 Form ES-C-1 PERFORMANCE INFORMATION Terminating Cue: After MS-V-3C is open two and one half turns, evaluation on this JPM is complete.

STOP TIME: TIME CRITICAL STOP TIME: N/A 2014 NRC JPM J NUREG 1021, Revision 9 Supp 1

Appendix C Page 7 of 8 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2014 NRC JPM J Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2014 NRC JPM J NUREG 1021, Revision 9 Supp 1

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

A loss of ICS Hand and Auto Power has occurred

The crew has entered OP-TM-AOP-025, Loss of ICS Hand and Auto Power.

The Reactor has been tripped and OP-TM-EOP-001 has been initiated.

FW-P-1A and FW-P-18 have been tripped.

Emergency Feedwater has been initiated.

You are an extra Reactor Operator on shift.

INITIATING CUE: Take local control of MS-V-3C lAW OP-TM-411-451, Attachment 7.1, Local Operation of the TBV's (MS-V-3s), and await further direction from the Control Room.

TIME CRITICAL: No 2014 NRC JPM J NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Three Mile Island Unit 1 Task No.: 21301002 Task

Title:

Pressurize the Core Flood Tanks JPM No.: 2014 NRC JPM K KIA

Reference:

006 A 1.13 (3.5/3. 7) Bank JPM TQ-TM-105-213-J100 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: X Actual Performance:

Classroom X

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

Initial Conditions:

The Plant is operating at 100% power.

"A" Core Flood Tank Pressure is low.

You are the Third Reactor Operator.

Task Standard: Nitrogen lined up to pressurize Core Flood Tank 1A.

Required Materials: None General

References:

OP-TM-213-473, Raising CF-T-1A Nitrogen Pressure, Rev 3 Handout: OP-TM-213-473, Raising CF-T-1 A Nitrogen Pressure, Rev 3, signed off through Step 4.1.3 and Step 4.1.4 is N/A.

Initiating Cue: As the CRS, I am directing you to raise Core Flood Tank Pressure using the Alpha Side Regulator lAW OP-TM-213-473, Raising CF-T-1A Nitrogen Pressure, starting at step 4.2.

Time Critical Task: No Validation Time: 35 minutes (includes time to sign on RWP) 2014 NRC JPM K NUREG 1021, Revision 9 Supp 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP N/A 2014 NRC JPM K NUREG 1021, Revision 9 Supp 1

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

START TIME:

EVALUATOR CUE: If candidate correctly describes rotating the handwheel to open CF-V-10, state "the valve is open".

If candidate does not correctly describes rotating the handwheel to open CF-V-1 0, state "the valve is closed".

EVALUATOR CUE: If candidate correctly describes rotating the handwheel to open NI-V-25, state "the valve is open".

If candidate does not correctly describes rotating the handwheel to open NI-V-25, state "the valve is closed".

OP-TM-213-473, Step 4.2.1 Performance Step: 1 Open the following:

CF-V-10

NI-V-25 Standard: Examinee locates CF-V-10 in the Auxiliary Building, 305' elevation, in the cubicle behind the Seal Injection Filters.

Examinee simulates opening CF-V-10 by turning the valve in a counterclockwise direction.

Examinee locates NI-V-25 in the Auxiliary Building, 305' elevation, along the wall just South of th 1A 480V ES Valves MCC.

Examinee simulates opening NI-V-25 by turning the valve in a counterclockwise direction.

Comment:

EVALUATOR NOTE: The Chemical Addition Room is the first door on the left when exiting the elevator in the Auxiliary Building, 3rd floor.

The Nitrogen bottles are to the left as you enter the room.

2014 NRC JPM K NUREG 1021, Revision 9 Supp 1

Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION EVALUATOR CUE: If candidate correctly describes rotating the handwheel to open NI-V-98A, state "the valve is open".

If candidate does not correctly describes rotating the handwheel to open NI-V-98A, state "the valve is closed".

EVALUATOR CUE: If candidate correctly describes rotating the handwheel to open NI-V-99, state "the valve is open".

If candidate does not correctly describes rotating the handwheel to open NI-V-99, state "the valve is closed".

OP-TM-213-473, Step 4.2.2 Performance Step: 2 Open the following:

NI-V-98A

NI-V-99 Standard: Examinee locates NI-V-98A in the Auxiliary Building, Chemical Addition Room, on the 650# Nitrogen Header.

Examinee simulates opening NI-V-98A by turning the valve in a counterclockwise direction.

Examinee locates NI-V-99 in the Auxiliary Building, Chemical Addition Room, on the 650# Nitrogen Header.

Examinee simulates opening NI-V-99 by turning the valve in a counterclockwise direction.

Comment:

2014 NRC JPM K NUREG 1021, Revision 9 Supp 1

Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION EVALUATOR CUE: If candidate correctly describes rotating the handwheel to open NI-V-81 A, state "the valve is open".

If candidate does not correctly describes rotating the handwheel to open NI-V-81A, state "the valve is closed".

If candidate begins to manipulate NI-V-81 B, state "Raise Core Flood Tank Pressure using the 'A' regulator".

OP-TM-213-473, Step 4.2.3 Performance Step: 3 Align High Pressure to one or both NI-V-80A/B, 650# Nitrogen regulators as follows (N/A regulator not used):

Open NI-V-81A and/or

Open NI-V-81 B Standard: Examinee locates NI-V-81A in the Auxiliary Building, Chemical Addition Room, on the 650# Nitrogen Header.

Examinee simulates opening NI-V-81A by turning the valve in a counterclockwise direction.

Examinee N/A's NI-V-81 B.

Comment:

EVALUATOR NOTE: NI-PI-1090 is the high side pressure gauge.

NI-PI-1 091 is the low side pressure gauge.

EVALUATOR CUE: If candidate correctly identifies NI-PI-1090 and NI-PI-1091, state "pressure indication has not changed".

If candidate does not correctly identify NI-PI-1090 and NI-PI-1091, state "pressure indication has not changed".

OP-TM-213-473, Step 4.2.4 Performance Step: 4 Observe high and low side regulator pressure gauges to ensure regulator is reducing Nitrogen to approximately 650 psig.

Standard: Examinee identifies the pressure gauges to see if the regulator is reducing Nitrogen and recognizes no change in pressure.

Comment:

2014 NRC JPM K NUREG 1021, Revision 9 Supp 1

Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION EVALUATOR CUE: State "the NI-V-138 handle is in-line with the pipe (or 'as shown')".

State "the NI-V-141 handle is 90 degrees to the left of the pipe".

EVALUATOR CUE: If candidate correctly describes NI-V-141 valve manipulation, state "the NI-V-141 handle is in-line with the pipe (or 'as shown')".

If candidate correctly describes valve manipulation, state "pressure has responded, low side pressure gauge indicates 650#".

If candidate does not correctly describe valve manipulation, state "pressure indication has not changed".

OP-TM-213-473, Step 4.2.5 Performance Step: 5 If Pressure does not come up on the high side gauge, then ensure open the following valves:

NI-V-138

NI-V-141 Standard: Examinee locates NI-V-138 in the Auxiliary Building, Chemical Addition Room.

Examinee determines NI-V-138 is open by the handle being in-line with the pipe.

Examinee locates NI-V-141 in the Auxiliary Building, Chemical Addition Room.

Examinee simulates opening NI-V-141 by turning the valve to be in-line with the pipe.

Comment:

2014 NRC JPM K NUREG 1021, Revision 9 Supp 1

Appendix C Page 7 of 9 Form ES-C-1 PERFORMANCE INFORMATION EVALUATOR CUE: If candidate correctly describes rotating the handwheel to open NI-V-1011, state "the valve is open".

If candidate does not correctly describes rotating the handwheel to open NI-V-1011, state "the valve is closed".

EVALUATOR CUE: If candidate correctly describes rotating the handwheel to open NI-V-79A, state "the valve is open".

If candidate does not correctly describes rotating the handwheel to open NI-V-79A, state "the valve is closed".

OP-TM-213-473, Step 4.2.6 Performance Step: 6 Align downstream side of one or both NI-V-80A/B, 650# Nitrogen Regulators, as follows (N/A regulator not used):

NI-V-80A Position

NI-V-1011 Open

NI-V-79A Open Standard: Examinee locates NI-V-1011 in the Auxiliary Building, Chemical Addition Room.

Examinee simulates opening NI-V-1 011 by turning the valve in a counterclockwise direction.

Examinee locates NI-V-79A in the Auxiliary Building, Chemical Addition Room.

Examinee simulates opening NI-V-79A by turning the valve in a counterclockwise direction.

Examinee N/A's NI-V-79B.

Comment:

Terminating Cue: After NI-V-1011 and NI-V-79A have been opened, evaluation on this JPM is complete.

STOP TIME:

2014 NRC JPM K NUREG 1021, Revision 9 Supp 1

Appendix C Page 8 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2014 NRC JPM K Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2014 NRC JPM K NUREG 1021, Revision 9 Supp 1

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

The Plant is operating at 100% power.

"A" Core Flood Tank Pressure is low.

You are the Third Reactor Operator.

INITIATING CUE: As the CRS, I am directing you to raise Core Flood Tank Pressure using the Alpha Side Regulator lAW OP-TM-213-473, Raising CF-T -1 A Nitrogen Pressure, starting at step 4.2.

TIME CRITICAL: No 2014 NRC JPM K NUREG 1021, Revision 9 Supp 1

Appendix 0 Scenario Outline Form ES-D-1 Facility: Three Mile Island Scenario No.: 1 Op Test No.: 289-2014-301 Examiners: Operators:

Initial Conditions: * (Temporary IC-241)

100% Power, MOL

SBO OOS For Maintenance, expected to return to service in 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months

Crane work is occurring on the West side of the Plant to stage new piping .

NRC Authorization Code for today is AB12 .

Turnover: Maintain 100% Reactor Power Critical Tasks:

Minimize SCM (CT-7)

Limit Uncontrolled Radiation Release (CT-21)

Reduce Steaming/Isolate Affected SGs (CT-22)

Event No. Malt. No. Event Type' Event Description 1 MSR01 CCRS MSIV Inadvertent Closure, entry into OP-TM-PPC-L2204.

CURO CARO (URO: Lowers power in ICS Auto, ARO: Opens MS-V-1A) 2 RW02C TSCRS NR-P-1 C Trips, NR-P-1 B Fails to Auto-Start, entry into OP-TM-MAP-B01 05, and OP-TM-MAP-B0205 CARO (ARO: Starts NR-P-1 B from CR) 3 MU19D CCRS Reactor Coolant Pump Seal Leakage, entry into OP-TM-AOP-040.

CURO (URO: Lower Reactor Power, ARO: Manually Control Feedwater Pumps)

CARO 4 ED09D TSCRS Loss of Vital Bus D, entry into OP-TM-AOP-018 CARO (ARO: Restore Control Building Ventilation) 5 IC20 ICRS Total FW Demand Fails to Zero Volts, ICS Transient, entry into OP-TM-AOP-070.

IURO (URO/ARO: Coordinate to stabilize plant in ICS HAND control)

IARO 6 TH17B TSCRS -30 gpm "B" OTSG Tube Leak (TS), entry into OP-TM-EOP-005 R URO (URO: Guide 9)

NARO 7 RC39A MCRS RC-P-1 B Trip, Reactor Trip, -500 gpm "B" OTSG Tube Rupture TH16B with an elevated offsite dose, entry into OP-TM-EOP-005 MURO MARO 8 MUR67 CCRS MU-V-36 Fails to Open MUR94 CURO (URO: Maintains HPI flow greater than 115 GPM)

(N)ormal, (R)eactivity, (l}nstrument, (C)omponent, (M)ajor Appendix D Scenario Outline Form ES-D-1 Three Mile Island NRC Scenario #1 Event #1: When the crew has accepted the watch, the Lead Examiner will cue the Closure of MS-V-1A. The crew will identify this by the green closed light lit, white test light lit (during travel) and the red open light not lit (after travel is complete) (CC). The crew will enter OP-TM-PPC-L2204, which will direct lowering power less than 90% and reopening MS-V1 A.

When MS-V-1A has been opened, the scenario can continue.

Event #2: The Lead Examiner will cue the trip of the "C" Nuclear River Pump. "B" Nuclear River Pump fails to auto-start in standby, leaving only one (1) Nuclear River Pump running. One Nuclear River Pump may not be sufficient to cool both the Nuclear Service Closed Cooling System (NSCCW) and the Intermediate Closed Cooling System (ICCW).

It is considered a loss of NSCCW if NSCCW temperatures reach 100°F, and the following Critical Safety Functions are affected:

CSF 4, Core Heat Removal: Provide the capability to remove core heat production at all times: Loss of Nuclear Services cooling function: RC pumps must shutdown. Natural Circulation will be used RCS heat removal.

CSF 8, Auxiliary Emergency Systems: Provide equipment cooling (closed cooling and ventilation), and other support requirements to accomplish the other Critical Safety Functions. Provide Instrument Air for operation of EFW, ADVs, RCP Support Systems, and some containment isolation valves: Loss of Nuclear Services cooling function: Other CSFs are affected as follows: (1) the reliability of safety related power sources and instrumentation system is degraded by the loss of the control building chillers and (2) the reliability of the decay closed pump motors and emergency feed pump motors is degraded by the loss of cooling to the area ventilation coolers.

CSF 10, Chemistry Control: Provide the means to monitor and control primary and secondary water chemistry in order to ensure the long term reliability of plant systems and limit the potential release of radioactive materials: Loss of Nuclear Services cooling function would result in the loss of the capability to obtain an RCS or OTSG sample.

It is considered a loss of ICCW if ICCW temperatures reach 120°F, and the following Critical Safety Functions are affected:

CSF 1, Reactivity and Reactor Power Control: Maintain control of the fission process, maintain the capability to shutdown the reactor and the capability to maintain the reactor in a shutdown condition. Control energy production and reactor power distribution based on design limits and current core heat removal capability. Loss of Intermediate Component Cooling: The reactor is tripped in the event of loss of cooling to the CAD stators in order to prevent stator damage.

Appendix D Scenario Outline Form ES-D-1 Loss of CRD stator cooling would not prevent CRD insertion on RPS actuation.

Maintaining reactor shutdown is not affected by loss of IC component cooling.

CSF 3, RCS Integrity: Maintain the capability to control heatup and cooldown rates and control RCS pressure prevent reactor vessel brittle fracture or LTOP events. Maintain RCP seal cooling to prevent excessive loss of RCS inventory through RCP seals. Loss of Intermediate Component Cooling: One of two RCP seal cooling methods is lost. Loss of seal injection would require RCP shutdown.

If Sl is lost, overheating of RCP seals is likely. If seal injection maintained, solid operation may be required due to the loss of letdown.

The crew will diagnose the trip of NR-P-1 C by an amber disagreement light on the NR-P-1 C control switch and Annunciator alarms A-1-5 and A-2-5. The ARO will manually start "B" Nuclear River Pump to provide sufficient cooling for NSCCW and ICCW. The CRS will identify and declare the following Tech Spec: 3.3.2.

When NR-P-1 B is running and the Tech Spec has been declared, the scenario can continue.

Event #3: The Lead Examiner will cue the Reactor Coolant Pump Seal Leak on RC-P-1D. lAW OP-TM-AOP-040, RCP #1 SEAL FAILURE, Basis Document:

The objective is to shutdown the RCP before any further significant RCP damage occurs. The goal is to attempt to reduce power to allow stopping pump without having to trip the reactor. If tripping the RCP would challenge RPS, then the reactor will be tripped, the IMAs and symptom check performed and then the affected RCP tripped.

These actions should be performed promptly. If seal leakoff flow exceeds 8 gpm or temperature exceeds limits at seal water to radial bearing or #1 seal inlet, the RCP must be shutdown immediately. Once an RCP is tripped, #1 seal return is isolated (close MU-V-33) and the #2 seal becomes the primary seal.

The crew will diagnose the #1 Seal Leak on RC-P-1 D by the PPC alarm, the digital recorder (PC), and Lab Seal D/P indicated abnormal (CC). The CRS will announce entry into OP-TM-AOP-040 and will determine that, based on Seal Leakage being greater than 6 gpm but less than 8 gpm, a power reduction will be made in order to secure the RCP.

The URO will have to reduce power with ICS in AUTO to secure the RCP.

Once the "D" Reactor Coolant Pump is tripped, then the scenario can continue.

Event #4: The Lead Examiner will cue the Loss of Vital Bus "D".

The effects of a loss of VBD which are significant to plant safety or operation are numerous. For each effect the required compensatory action is described in OP-TM-AOP-018.

Appendix D Scenario Outline Form ES-D-1 This procedure stabilizes the plant and performs compensatory actions for equipment failures. It is considered a loss of Vital Bus "D" if the OTSGs are being used for RCS heat removal and an unplanned deenergization of VBD has occurred, and the following Critical Safety Functions are affected:

CSF 1, Reactivity and Reactor Power Control: Maintain control of the fission process, maintain the capability to shutdown the reactor and the capability to maintain the reactor in a shutdown condition. Control energy production and reactor power distribution based on design limits and current core heat removal capability. Loss of VBD: Nl-4 and Nl-8 are lost, but the remaining channels of nuclear instrumentation and incore detectors provide sufficient information to control power level and reactor power distribution.

CSF 6, Radiation Control and Control Room Habitability: Monitor and control the release of radiation to the environment. Maintain access to critical plant equipment and use of the Control Room. Loss of VBD: RM-L-6, RM-A-7, RM-A-4, and RM-A-6 are deenergized. Compensatory actions will be taken lAW ODCM requirements. Access to plant equipment and Control Room is not affected.

CSF 7, Electrical Power: Provide electrical power as required to accomplish the other Critical Safety Functions. Provide AC and DC power for emergency equipment operation and instrumentation systems. Loss of VBD: VBD is deenergized. Ability to accomplish other Critical Safety Functions is not compromised.

CSF 8, Auxiliary Emergency Systems: Provide equipment cooling {closed cooling and ventilation), and other support requirements to accomplish the other Critical Safety Functions. Provide Instrument Air for operation of EFW, ADVs, RCP Support Systems and some containment isolation valves. Loss of VBD:

Ventilation will be lost to CB 322' Battery Rooms, Inverter Rooms, ES 480V Switchgear Rooms, and Remote Shutdown Area. Compensatory actions will be performed lAW OP-TM-AOP-034, "Loss of Control Building Cooling." Instrument air is not affected.

CSF 9, Fire Protection and Remote Shutdown Capability: Maintain means to prevent, detect and suppress fires, as well as the capability to perform a plant shutdown without access to the Control Room. Loss of VBD: Loss of PRF annunciators disables alarms PRF-5-1, Relay Room Fire, PRF-7-1, IWFS!TS Bldg Fire, PRF-7-6, UPS Fire, and PRF-7-7, Process Center Fire. HVB-4-10 remains available to annunciate a fire in the Relay Room, and Relay Room C02 fire suppression remains operable. Sprinkler systems remain operable in IWFS!TS Bldg, UPS room, and Processing Center.

The crew will diagnose the loss of Vital Bus "D" by the "D" Reactor Protection System Cabinet being deenergized, Nl-8 indication deenergized (CC), Multiple annunciator alarms, including one for a failed inverter, "D" powered HSPS lights lit, and a loss of the right monitor of the Position Monitor Panel.

Appendix D Scenario Outline Form ES-D-1 The ARO will place Radiation Monitor Interlock switches to Defeat, and restore Control Building, Auxiliary Building, and Fuel Handling Building Ventilation. The CRS will identify and declare the following Tech Spec: 3.5.5.2.

When the radiation monitor interlock switches are in defeat, ventilation is running and the Tech Spec has been declared, the scenario can continue.

Event #5: The Lead Examiner will cue Total FW Demand Fails to Zero Volts. This will cause an ICS transient, which if not responded to swiftly, will cause a Reactor Trip. The crew will diagnose the ICS failure by a rapid change in RCS pressure, multiple annunciator alarms, and/or changes in indications at multiple ICS stations. Entry into OP-TM-AOP-070, PRIMARY TO SECONDARY HEAT TRANSFER UPSET will be required based on RCS pressure not being controlled in ICS AUTO. "RCS pressure is not being controlled" requires the operator to make a subjective determination, based on their skills, training, and experience. A determination that RCS pressure is being controlled should include the following elements: 1) The reason for the transient is understood 2) RCS pressure response is consistent with the expected response for the event 3) Automatic or manual control in accordance with normal operating procedures is effectively controlling RCS pressure. A conservative assessment (i.e. concluding that RCS pressure is not being controlled) is appropriate when the three conditions above cannot be satisfied. ICS failures are one class of events that can lead to an upset in primary to secondary heat transfer. Most ICS failures can be mitigated by use of the appropriate manual control normal operating procedures.

This entry into OP-TM-AOP-070 is different from the others because FeedWater will lower significantly and the crew will need to establish ICS controls in manual. Once the plant is stabilized in ICS HAND control, the scenario can continue.

Event #6: The Lead Examiner will cue the "B" OTSG Tube Leak. Any OTSG tube leak causes an abnormal increase in the release of radioactive materials to the environment.

The most fundamental objective is to minimize this release. The prioritized objectives of this procedure are:

Maintain core cooling.

Minimize the activity release to the atmosphere (minimize release duration, rate and concentration of radioisotopes, particularly iodine)

Minimize the integrated tube leakage 30 seconds of MSSV actuation can release 75% of the iodine for the entire event. The main condenser provides for iodine removal due to the ability of water to absorb the iodine (at least temporarily} through the condensers 104 "partitioning factor". This phenomenon reduces off site does consequences to the point that the radiation limits listed in the EOP can not be reached regardless of the tube leak size and the number of fuel pin leaks. MSSV actuation provides an opportunity for failure resulting in an unisolable path for reactor coolant directly to the environment.

Appendix D Scenario Outline Form ES-D-1 The crew will diagnose an OTSG tube leak based on RM-G-27, RM-A-5, and RM-A-15 indications (PR}, Annunciator C-1-1 in alarm, and/or pressurizer level lowering (CC).

The CAS will announce entry into OP-TM-EOP-005, OTSG TUBE LEAKAGE. This is a reactivity manipulation event. The URO will perform reactor shutdown with ICS in HAND. The ARO may lineup to feed to the RCS from the "B" RBCT for inventory control.

The CAS will evaluate and declare Tech Spec 3.1.6.3 When sufficient reactivity manipulation has been observed, the scenario can continue.

Event #7/8: The Lead Examiner will cue the RC-P-1 B trip immediately followed by the Reactor tripping and the "B" OTSG Tube leakrate rising to approximately 500 gpm. The CAS will enter OP-TM-EOP-001 and direct the Immediate Manual Actions and then continue in OP-TM-EOP-005, OTSG Tube Leak.

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-?0F, but as close to 30F as possible. The ARO will preferentially steam the "B" OTSG:

Upon receiving the elevated offsite dose projections, the CAS should invoke 10CFR 50.54x and raise the cooldown rate lAW OP-TM-EOP-005, Step 3.31.

Upon throttling HPI, the URO will recognize that MU-V-36, one of two Makeup Pump Recirculation path Valves (in series), will not open. The URO will maintain minimum Makeup/HPI flow via alternative methods lAW Rule 2 in order to avoid Makeup Pump damage.

The scenario can be terminated the "B" OTSG has been isolated and SCM has been minimized.

Appendix D Scenario Outline Form ES-D-1 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.

- Minimizing SCM outside of the following limits should be considered grounds for failure of the critical task:

- Do not allow SCM to fall below 25F.

- Do not allow SCM to rise above ?OF sustained.

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 flP. The reason for minimizing RCS-SG flP 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 Appendix D Scenario Outline Form ES-D-1 B&W Unit EOP Critical Task Description Document, 47-1229003-04:

CT Limit Uncontrolled Radiation Release- During SGTR mitigation:

- Attempt to control PZR level such that it does not continually decrease by increasing MU or HPI flow and reducing letdown flow

- If the reactor has not tripped, then perform controlled shutdown to prevent lifting MSSVs.

- Isolate non-essential steam loads from affected SG(s).

- If required to prevent exceeding [SG overfill setpoint] or [radiation limit], use emergency cooldown rate limit to 500'F.

The typical plant design allows for 40 cycles of an emergency cooldown to 500'F Thot at 240°F/hr. This rate is allowed for any SGTR event. However, it is recommended that the use of this emergency cooldown rate be limited to situations where:

a) the affected SG level(s) will reach the SG level limit before the SG can be isolated using the normal cooldown rate, including the use of SG drains if available, or b) activity release rates are projected to reach the integrated limit before 500°F Thot at the normal cooldown rate.

The emergency cooldown rate is recommended for the two cases noted because several large SGTRs and/or a relatively high percentage of failed fuel already exist.

In these cases, it is most important to prevent liquid discharge through the MSSVs and limit the duration of high activity release rates.

- Limiting Uncontrolled Radiation Release outside of the following limits should be considered grounds for failure of the critical task:

- Do not allow affected OTSG MSSV's to lift.

- Do not allow affected OTSG to go dry.

Safety Significance: If pressurizer level can be controlled, then the operator's ability to perform a controlled shutdown is greatly enhanced. Whenever possible power should be reduced as quickly as possible, but in a controlled manner, to well within the turbine bypass system capacity before tripping the reactor to prevent lifting of the MSSVs. This includes cases where maximum MU or HPI flow and letdown isolation are required to keep up with the tube leak and maintain pressurizer level. Power reduction is intended to minimize atmospheric radiation releases due to SG safety valve operation. Also, if a reactor trip can be averted through controlled operations, then ability to mitigate the transient is expected to be enhanced as normal transition from power operations to a controlled cooldown occurs.

Cues:

1. Main steam line radiation alarm

2. SG high level alarm

3. Pressurizer low level alarm

4. Verbal alert by plant staff that a SGTR is occurring and the reactor has not tripped Appendix D Scenario Outline Form ES-D-1 B&W Unit EOP Critical Task Description Document, 47-1229003-04:

CT-21 -Limit Uncontrolled Radiation Release (cont)

Performance Indicators:

1. Operation of MU/HPI pump controls

2. Operation of MU/HPI valve controls

3. Operation of letdown valve controls

4. Operation of TBV/ADV controls Feedback:

1. Pressurizer level

2. Letdown flow

3. MU/HPI flow

4. RCS temperature

5. Verbal alert by plant staff of pressurizer level status

6. Verbal alert by plant staff of RCS cooldown rate Appendix D Scenario Outline Form ES-D-1 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].

- Isolating Affected SGs outside of the following limits should be considered grounds for failure of the critical task:

- Do not allow isolation to occur with RCS pressure > 1000 psi g.

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

<1 000 PSI G. 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 PSI G. 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 PSI G.

Once this initial cooldown and RCS depressurization to <1 000 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 <1 000 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 Appendix D Scenario Outline Form ES-D-1 B&W Unit EOP Critical Task Description Document, 47-1229003-04:

CT Reduce Steaming/Isolate Affected SGs (includes use of SG drains) (cont)

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 Scenario Outline Form ES-D-1 Industry Experience:

TMI Reactor Trip {11/2/06) Main Steam Safety Valves remained open longer than expected. (IR 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)

Appendix D Scenario Outline Form ES-D-1 Event Description Procedure Support Initial Set-up. 100% Power, MOL MSIV Inadvertent Closure OP-TM-PPC-L2204 1

1102-4, Power Operations NR-P-1C Trips, NR-P-18 OP-TM-MAP-80105, 480V ES MOTOR TRIP Fails to Auto-Start OP-TM-MAP-80205, 480V ES MOTOR 2

OVERLOAD Tech Spec 3.3.2 Reactor Coolant Pump Seal OP-TM-AOP-040, RCP 1 Seal Failure Leakage 3 11 02-4, Power Operations OP-TM-226-154, Shutdown RC-P-1 D Loss of Vital Bus D OP-TM-AOP-018, Loss of VBD 4

Tech Spec. 3.5.5.2 Total FW Demand Fails to Zero Volts, ICS Transient OP-TM-AOP-070, Primary to Secondary Heat 5

Transfer Upset

-30 gpm "B" OTSG Tube OP-TM-EOP-005, OTSG Tube Leak Leak (TS)

OP-TM-EOP-01 0, Emergency Procedure Rules, 6

Guides and Graphs 11 02-4, Power Operations RC-P-1 B Trip, Reactor Trip, OP-TM-EOP-001, Reactor Trip

-500 gpm "B" OTSG Tube OP-TM-EOP-01 0, Emergency Procedure Rules, 7 Rupture with an elevated offsite dose Guides and Graphs OP-TM-EOP-005, OTSG Tube Leak MU-V-36 Fails to Open OP-TM-EOP-01 0, Emergency Procedure Rules, 8 Guides and Graphs OP-TM-211-901, Emergency Injection (HPI/LPI)

Appendix D Scenario Outline Form ES-D-1 ACTION COMMENTS I INSTRUCTIONS DESCRIPTION Initialization IC-241 100% HFP ICS full AUTO Equilibrium XENON Remote MSR01 Value: 0 MSIV Inadvertent Closure When: EVENT 1 TRIGGER 11 Value: DRF MSR01 MSIV Inadvertent Closure When: RATPW<92 Malfunction RW02C Value: INSERT NR-P-1 C Trips When: EVENT 2 Malfunction MU19D Value: 20 Reactor Coolant Pump Seal When: EVENT 3 Leakage Malfunction ED09D Value: INSERT Loss of Vital Bus D When: EVENT 4 Malfunction IC20 Value: INSERT Total FW Demand Fails to When: EVENT 5 Zero Volts Malfunction TH17B Value: 0.2 "B" OTSG Tube Leak When: EVENT 6 Malfunction RC39A Value: Insert RC-P-1 B trip When: EVENT 7 Malfunction RD29 Value: Insert Reactor Trip When: EVENT 7 Malfunction TH16B Value: 3.5 Delay 20 seconds "B" OTSG Tube Rupture When: EVENT 7 Trigger 7 Value: DMF TH17B Delete OTSG Tube Leak When: EVENT 7 Trigger 8 Value: Insert MU-V-36 Fails to Open When: dhndhp1 a > 0.9 Override 02A5S80- Value: On MU-V-36 Fails to Open ZDISSMUV36{1) When: Event 8 Remote MSR66 Value: Insert Initiate Aux Boilers When: EVENT12 Remote FWR80 Value: MAN MS-V-13B Manual Control When: EVENT14 Remote FWR81 Value: 0 MS-V-13B Closed Position When: EVENT14 Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # Page 15rJ of 5311

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Event

Description:

MSIV Inadvertent Closure Time J Position I Applicant's Actions or Behavior Booth Instructions: When directed by the Lead Examiner INITIATE Event 1.

Indications Available: PPC-L2204 in alarm, MS-V-1A indicates closed on CC, "A" OTSG Pressure/Level rise.

Booth Cue: If contacted as maintenance, inform the crew that "I see no damage to MS-V-1A and the valve may be reopened when Ops is ready to open it" Direct entry into OP-TM-PPC-L2204, MAIN STEAM ISOL CRS MS-V1A.

Examiner's Note: Step 4.1 is N/A.

Procedure Note The following steps are designed to prevent an overpressure condition that could challenge the RC-RV-2 (PORV) and to prevent operation in an unbalanced steam flow condition.

OP-TM-PPC-L2204, MAIN STEAM ISOL MS-V1 A Step 4.2: REDUCE reactor power to less than 90% power lAW CRS 1102-4, "Power Operation".

Examiner's Note: The CRS will determine that the power reduction is a forced reduction, and will INITIATE Attachment 2A.

11 02-4, Power Operation Step 3.3.2.A.1: PERFORM Enclosure 2A (for an emergency CRS (forced) power reduction INITIATE Enclosure 2A).

I Footnote: 1- MS-V-1A: MAIN STEAM ISOL OF "A" OTSG "A" LINE Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario# 1 Event# - - - ' - - - - - - Page 16rJ of .....;5::..:3:..:::u:.....__ _,

Event

Description:

MSIV Inadvertent Closure Time I Position I Applicant's Actions or Behavior Examiner's Cue: Acknowledge as the personnel listed in the next step, or acknowledge as Shift Manager to notify the personnel listed in the next step. Also acknowledge Logging the notifications.

Step 3.3.2.A.2: If power change is greater than 10 MWe, then perform the following:

a) NOTIFY the following:

CRS

- Power Team

- TSO

- NDO b) LOG notifications to Power Team, TSO, and NDO in Control Room Log.

Procedure Note: S0-3-3, H2 Flow Trouble, is an expected alarm. The cooling of main generator hydrogen during a power reduction causes hydrogen flow to exceed the alarm setpoint of 1000 SCF/D.

Step 3.3.2.A.3.a: MAINTAIN Generator Reactive Load lAW ARO OP-TM-301-472.

Step 3.3.2.A.3.b: If SG/REACTOR DEMAND is in AUTO, then REDUCE reactor power as follows:

URO

1. ENSURE ULD is in HAND by observing White HAND light lit, red AUTO light not lit (CC).

Examiner's Note: The Load Rate of Change adjustment knob does not read in

"%". If the CAS directs a 1%/Min load rate of change, the URO will dial the adjustment knob to 10. If the CAS directs a 3%/Min load rate of change, the URO will dial the adjustment knob to 30.

l Footnote: 1- ULD: Unit Load Demand.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario# 1 Event# Page 1711 of 531 i

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Event

Description:

MSIV Inadvertent Closure Time I Position I Applicant's Actions or Behavior Step 3.3.2.A.3.b: If SG/REACTOR DEMAND is in AUTO, then REDUCE reactor power as follows:

2. SET ULD LOAD RATE OF CHANGE to-::; 1 %/minute URO for PLANNED reductions or at a rate determined by CRS for Forced power reductions by changing the Load Rate of Change adjustment knob in the clockwise direction until the corresponding value is achieved.

Examiner's Note: The URO will decide MWe corresponding to the power level directed by the CRS by looking at the placard next to the ULD.

Step 3.3.2.A.3.b: If SG/REACTOR DEMAND is in AUTO, then REDUCE reactor power as follows:

3. SET ULD Target Load Demand to desired setpoint by URO placing the ULD Control Station toggle switch in the down direction until the target MWe is targeted by the indicator.

Examiner's Note: Once Reactor Power is below 90%, the CRS will continue in OP-TM-PPC-L2204, MAIN STEAM ISOL MS-V1A.

OP-TM-PPC-L2204, MAIN STEAM ISOL MS-V1 A Step 4.3 RE-OPEN MSIV as soon as possible by pressing the red open pushbutton and observing all three lights lit during ARO travel, and only the red open light lit (green and white lights not lit) at the end of valve travel.

Examiner's Note: Once MS-V-1A is open, Go to Event 2.

Footnotes: 1 - ULD: Unit Load Demand.

2- MS-V-1A: MAIN STEAM ISOL OF "A 11 OTSG "A,. LINE Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 2 Page 181 of 531

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Event

Description:

NR-P-1 C Trips, NR-P-1 B Fails to Auto-Start Time j Position I Applicant's Actions or Behavior Booth Instructions: When directed by the Lead Examiner INITIATE Event 2.

Indications Available: MAP B-1-5 and B-2-5 in alarm, NR-P-1C amber disagreement light lit on CR, PPC alarm.

Examiner's Note: Crew may decide to start NR-P-1 B upon discovery of it not auto-starting lAW OS-24, Section 4.3.5.A:

Any time an automatic control or interlock functions fails to perform as designed and there is no specific procedure direction, the reactor operator should take action to compensate directly for the failure. The Reactor Operator should verbalize the actions taken to inform the Control Room team of the condition and actions taken.

Examiner's Note: The crew may choose to enter OP-TM-541-452, Remove NR-P-1C From Service, which provides direction toES select NR-P-1B on the 1T 480V ES bus and also to close NR-V-1C.

Booth Cue: If directed, as an Auxiliary Operator and/or Maintenance, to investigate NR-P-1 C and its breaker, acknowledge the order.

Nothing will be found at the pump or breaker.

Diagnose the trip of NR-P-1 C and the failure of NR-P-1 B to CRS automatically start on standby and direct entry into OP-TM-MAP-80105, 480V ES MOTOR TRIP Examiner's Note: OP-TM-MAP-B0105, Step 1 is N/A Footnotes: 1- NR-P-1C:. Nuclear Services River Water Pump (usually "B" Train ES selected).

2- NR..,P-18: Nuclear Services River Water Pump (usually notES selected, "swing" pump).

3- NR-V-1C: "C" Nuclear Services River Water Pump discharge valve.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario# 1 Event# 2 Page 191 of 5311

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Event

Description:

NR-P-1 C Trips, NR-P-1 B Fails to Auto-Start Time I Position I Applicant's Actions or Behavior OP-TM-MAP-801 05, 480V ES MOTOR TRIP Step 2: Starts NR-P-1 B by turning the Control Switch (CR)

ARO clockwise, observing red indicating light and normal running amps after initial start.

Examiner's Note: The crew may match flags for NR-P-1C (place pump in Off or Pull-to-Lock to clear overhead alarm.

Examiner's Note: OP-TM-MAP-80105, Steps 3 and 4 are N/A Step 5: Recognizes that Nuclear River header pressure is ARO within the acceptable pressure band (OP-TM-541-461 ).

Examiner's Note: OP-TM-MAP-80105, Step 6 is N/A Booth Cue: If directed, as an Auxiliary Operator and/or Maintenance, to ES select NR-P-1 Bon the 1T 480V ES bus, repeat the order but do not ES select the pump.

CRS Step 7: Declares a 3.3.2 (72 Hour) Tech Spec clock.

Footnotes: 1- NR-P-1C: Nuclear Services River WaterPump (usually "B" Train ES selected).

2 - NR-P-1 B: Nuclear Services River Water Pump (usually not ES selected "swing" pump).

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 2 Page 201 of 53L

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Event

Description:

NR-P-1 C Trips, NR-P-1 B Fails to Auto-Start Time I Position I Applicant's Actions or Behavior Examiner's Note: T.S. 3.3.2 Maintenance or testing shall be allowed during reactor operation on any component(s) in the makeup and purification, decay heat, R8 emergency cooling water, R8 spray, 8WST level instrumentation, or cooling water systems which will not remove more than one train of each system from service. Components shall not be removed from service so that the affected system train is inoperable for more than 72 consecutive hours. If the system is not restored to meet the requirements of Specification 3.3.1 within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , the reactor shall be placed in a HOT SHUTDOWN condition within six hours.*

I I Examiner's Note: Once the TS call is made, NR-P-1 8 is operating and sufficient time has been given for the direction to ES select NR-P-1 8, Go to Event 3.

Footnotes: 1- NR-P~.1 B: Nuclear Services River Water Pump (usually not ES.selected, "swing" pump).

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario# 1 Event # _3;;.....__ _ _ _ Page 211 of ....;5::;.;:3~1-~

Event

Description:

Reactor Coolant Pump Seal Leakage Time I Position I A_pplicant's Actions or Behavior Booth Instructions: When directed by the Lead Examiner INITIATE Event 3.

Indications Available: MAP Annunciator F-1-3 RCP SEAL #1 LEAK OFF FLOW HI/LO actuates, RC-P-1 D Seal Leak Off flow indicates 6.2 gpm on the recorder on PC and on the computer.

Diagnoses the failure of RC-P-1 D #1 seal based on seal leak URO off flow indication.

Determines the entry conditions for AOP-040 are met:

- RC Pump #1 seal leakoff flow > 6 gpm on any RCP CRS and thermal barrier cooling or seal injection is in service.

Directs entry into OP-TM-AOP-040, RCP #1 Seal Failure Examiner's Note: OP-TM-AOP-040, Step 1 is N/A.

Procedure Note: Seal injection flow can be adjusted with MU-V-32 in HAND or by adjusting H/A station setpoint.

OP-TM-AOP-040, RCP #1 Seal Failure Step 3.2: Maximizes seal injection flow not to exceed 60 gpm by placing the MU-V-32 Control Station in HAND (presses White HAND pushbutton and verifies white light lit, red light not URO lit) and then placing the toggle switch in the up direction until either 60 gpm seal injection is attained or MU-V-32 is 100%

open. URO may also dial the H/A/ setpoint instead to achieve the same results.

Footnotes: 1- RC*P-1D: "D" Reactor Coolant Pump 2- MU-V-32: RCP Seal Injection Control Valve Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # _3_ _ _ _ _ Page 221 of .....;5=3=11_ _,

Event

Description:

Reactor Coolant Pump Seal Leakage Time Position Applicant's Actions or Behavior Procedure Note: Power reduction should be performed at a rate that supports RCP shutdown in less than 30 minutes.

Step 3.3: INITIATE a power reduction using 1102-4 to within the appropriate limits (Reactor and MWe) based on shutdown of the RCP:

RCPs Rx Left Power MWe CRS Running Limit

(%}

3 < 75 < 665 1/loop < 49 < 445 0 in any 0 0 loop 11 02-4, Power Operation Step 3.3.2.A.1: PERFORM Enclosure 2A (for an emergency CRS (forced) power reduction INITIATE Enclosure 2A).

Examiner's Cue: Acknowledge as the personnel listed in the next step, or acknowledge as Shift Manager to notify the personnel listed in the next step. Also acknowledge logging the notifications.

Step 3 . 3.2.A.2: If power change is greater than 10 MWe, then perform the following:

c) NOTIFY the following:

- Power Team CRS

- TSO

- NDO d) LOG notifications to Power Team, TSO, and NDO in Control Room Log.

Procedure Note: S0-3-3, H2 Flow Trouble, is an expected alarm. The cooling of main generator hydrogen during a power reduction causes hydrogen flow to exceed the alarm setpoint of 1000 SCF/0.

Appendix D Operator Action Form ES-D-2 I Op Test No., NRC Scenario # 1 Event # 3

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Page 231 of 531

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' Event

Description:

Reactor Coolant Pump Seal Leakage Time I Position _j Applicant's Actions or Behavior Step 3.3.2.A.3.a: MAINTAIN Generator Reactive Load lAW ARO OP-TM-301-472.

Step 3.3.2.A.3.b: If SG/REACTOR DEMAND is in AUTO, then REDUCE reactor power as follows:

URO

4. ENSURE ULD is in HAND by observing White HAND light lit, red AUTO light not lit (CC).

Examiner's Note: The Load Rate of Change adjustment knob does not read in

%. If the CRS directs a 1%/Min load rate of change, the URO will dial the adjustment knob to 10. If the CRS directs a 3%/Min load rate of change, the URO will dial the adjustment knob to 30.

Step 3.3.2.A.3.b: If SG/REACTOR DEMAND is in AUTO, then REDUCE reactor power as follows:

5. SET ULD LOAD RATE OF CHANGE to:::; 1 %/minute URO for PLANNED reductions or at a rate determined by CRS for Forced power reductions by changing the Load Rate of Change adjustment knob in the clockwise direction until the corresponding value is achieved.

Examiner's Note: The URO will decide MWe corresponding to the power level directed by the CRS by looking at the placard next to the ULD.

Step 3 . 3.2.A.3.b: If SG/REACTOR DEMAND is in AUTO, then REDUCE reactor power as follows:

6. SET ULD Target Load Demand to desired setpoint by URO placing the ULD Control Station toggle switch in the down direction until the target MWe is targeted by the indicator.

Examiner's Note: Once Reactor Power is below 75%, the CRS will continue in OP-TM-AOP-040, RCP 1 Seal Failure.

I Footnote: 1 - ULD: Unit Load Demand.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario# 1 Event# 3 Page 241 of 531.

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Event

Description:

Reactor Coolant Pump Seal Leakage Time I Position I Applicant's Actions or Behavior OP-TM-AOP-040, RCP #1 Seal Failure Step 3.4: When power (Reactor and Turbine) is within limits to support RCP shutdown, then perform the following to shutdown CAS the affected RCP:

- OP-TM-226-154 (D RCP)

Procedure Note: A 211 RCP combination with OTSG levels > LLLs will require a re-ratio (70% I 30%) of Feedwater flow to A I B OTSG.

OP-TM-226-154, Shutdown RC-P-1 D Step 4.2: Recognizes that Reactor power is > 20%, and CRS determines the expected FW Flow requirements for new RCP combination to minimize effects on Delta Tc.

Examiner's Note: If asked, time is not available for Electrical Maintenance to monitor RC-P-1 D vibrations.

Step 4 . 4: Starts RC-P-2D-1, Oil Lift Pump AC HP or RC-P-2D-2, Oil Lift Pump DC HP by placing one of the control switches ARO clockwise and verifying red running light lit, green secured light not lit, and red indicating flag displayed (CC).

Step 4.4: Starts RC-P-3D-1, Backstop Oil Pump #1 or RC-P-3D-2, Backstop Oil Pump #2 by placing one of the control ARO switches clockwise and verifying red running light lit, green secured light not lit, and red indicating flag displayed (CC).

Footnotes: 1 - RC-P-1 D: "D" Reactor Coolant Pump 2- RC-P-20-1: RC-P-1 D AC High Pressure Oil Lift Pump 3- RC-P-20-2: RC-P-10 DC High Pressure Oil Lift Pump 4 - RC-P-30-1 : RC-P-1 D AC Backstop Oil Pump #1 5- RC-P-30-1: RC-P-10 AC Backstop Oil Pump #2 6 - LLL: Low Level Limits Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 3 Page 25L of 53L

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Event

Description:

Reactor Coolant Pump Seal Leakage Time Position Applicant's Actions or Behavior Step 4.5: Places RC-P-1 Din Pull-To-Lock by rotating the Control Switch counter-clockwise while pulling away from the URO console, ensuring no lights lit, black indicating flag is displayed, and the handle is locked in the extended position.

Procedure Note: Vibration levels at a low value with the absence of change indicates 0 rQm.

Step 4.6: Verify the following:

Crew

- RC-P-1 D not rotating backwards.

- Vibration readings (PLF) indicate RC-P-1 D has reached 0 rpm.

Step 4.7: Place the following in Pull-To-Lock:

- RC-P-30-1, Backstop Oil Pump #1 by rotating the Control Switch counter-clockwise while pulling away from the console, ensuring black indicating flag is displayed, and the handle is locked in the extended URO position.

- RC-P-30-2, Backstop Oil Pump #2 by rotating the Control Switch counter-clockwise while pulling away from the console, ensuring black indicating flag is displayed, and the handle is locked in the extended position.

Footnotes: 1 - RC-P-1 0: 11 0" Reactor Coolant Pump 2 - RC-P-20-1: RC*P-1 D AC High Pressure Oil Lift Pump 3- RC-P-20-2: RC-P-10 DC High Pressure Oil Lift Pump Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 3 Page 261. of 53c

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' Event

Description:

Reactor Coolant Pump Seal Leakage I Time I Position Applicant's Actions or Behavior Step 4.8: Place the following in Pull-To-Lock:

RC-P-20-1, Oil Lift Pump AC HP by rotating the Control Switch counter-clockwise while pulling away from the console, ensuring black indicating flag is displayed, and the handle is locked in the extended URO position.

RC-P-20-2, Oil Lift Pump DC HP by rotating the Control Switch counter-clockwise while pulling away from the console, ensuring black indicating flag is displayed, and the handle is locked in the extended position.

OP-TM-AOP-040, RCP #1 Seal Failure Step 3.5: When affected RCP stops rotating, then promptly close the following for the affected RCP by pressing the close pushbutton and verifying the green closed light is lit and the red open light is not lit:

URO Examiner's Note: Once MU-V-330 is Closed, Go to Event 4.

Footnotes: 1 - RC-P-30-1: RC*P-1 D AC Backstop Oil Pump #1 2 - RC-P-30-1: RC-P-1 0 AC Backstop Oil Pump #2 3- MU-V-33A: RC-P-1A Seal #1 Leakoff Isolation Valve 4- MU-V-33B: RC-P-1B Seal #1 Leakoff Isolation Valve 5- MU-V-33C: RC-P-1C Seal #1 Leakoff Isolation Valve 6 - MU* V-330: RC-P-1 0 Seal #1 Leakoff Isolation Valve Appendix D Operator Action Form ES-D-2 I Op Test No.: NRC Scenario# 1 Event# 4 Page 271 of 531J I ---------- ~=-~

Event

Description:

Loss of Vital Bus D Time .I Position I Applicant's Actions or Behavior Booth Instructions: When directed by the Lead Examiner INITIATE Event 4.

Examiner's Note: Attachment 1 of OP-TM-AOP-018, Loss of VBD, listing the effects of a loss of VBD, is listed on page 54 of this SEG.

Indications Available: Multiple Main Annunciator Panel Alarms illuminated, "D" RPS Cabinet deenergized, 1 of 2 Control Rod Position Indication Panels deenergized, 1 Row of HSPS lights lit.

Crew Diagnosis a loss of Vital Bus "D".

CRS Direct entry into OP-TM-AOP-018, Loss of VBD.

OP-TM-AOP-018, Loss of VBD Step 3.1: Announces entry into OP-TM-AOP-018, "Loss of ARO VBD," over the plant page and radio.

Examiner's Note: OP-TM-AOP-018, Steps 3.2-3.5 are N/A. If asked, as Shift Manager, state "there are no fuel movements in progress".

Procedure Note: Loss of power to RM-A-1 G trips AH-E-17 AlB, AH-E-20A/B, AH-E-21, AH-E-26, AH-E-93A/B, AH-E-94A/B & AH-E-95A/B, closes AH-D-28 and AH-D-617.

Footnotes: 1 - RM-A-1 G: Control Tower Air-In Gas, Radiation Monitor.

2- AH-E-17A/B: AlB Control Building Normal Supply Fans.

3 - AH-E-20A/B: AlB CB and Fuel Handling Building 1st Floor Exhaust Fans 4- AH-E-21: Control Building Kitchen Exhaust Fan.

5 - AH-E-26: Machine Shop and Chemical Hoods Supply Fan.

6- AH-E-93A/B, AH-E-94A/B: AlB CB Hallway Supply/Exhaust Fans.

7 - AH-E-95A/B: AlB CB 2"d Floor Booster Fans.

8- AH-0-28/AH-D-617: CB 1st Floor Isolation Damper/Backup Damper.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario# 1 Event# 4 Page 28r- of 53U

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Event

Description:

Loss of Vital Bus D Time I Position I Af:)plicant's Actions or Behavior Step 3.6: Places RM-A-1 G interlock switches in the DEFEAT ARO position by turning the interlock defeat switch to the defeat p_osition and verifying that Main Annunciator C-2-1 is in alarm.

Step 3.7: Restores Control Tower ventilation lAW 1104-19, ARO "Control Building Ventilation System."

Examiner's Note: 1104-19 has no direct section to recover from an RMS interlock. Section 3.7.2 is scripted below. Validators also used Section 3.4 which had the same steps in order as scripted below.

1104-19, Control Building Ventilation System Step 3.7.2.2.1: Makes a Plant Page Announcement ATTENTION Plant Personnel, Starting Control Building ARO Ventilation, use caution when opening or closing Control Building doors due to the potential for high differential pressures to exist.

Step 3. 7.2.2.2: Verifies that fire alarms are clear for Control ARO Tower and Air Intake Tunnel (AIT) on Heating and Ventilation Panels H& V AlB and PL A/B.

Examiner's Note: The ARC may secure AH-E-19A to imitate an initial lineup.

This is not required however.

Step 3.7.2.2.3: Verifies AH-E-19A is running by observing the ARO red light lit and green light not lit.

Examiner's Note: The ventilation fan controls are set up such that they must be held in the Start position longer than other Control switches. This is normal and expected.

Footnotes: 1- RM-A-1G: Control Tower Air-In Gas, Radiation Monitor.

2 - AH-E-19A: A CB Return Air Fan.

Appendix D Operator Action Form ES-D-2 I Op Test No.: NRC Scenario # 1 Event # 4

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Page 291 of 531 i

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Event

Description:

Loss of Vital Bus D Time l Position I Applicant's Actions or Behavior Step 3.7.2.2.4: Starts AH-E-17A by turning the Control Switch ARO in the clockwise direction, and observing the red light lit and green light not lit.

Procedure Note: Expect HVA-4-5 to come in and HVA-3-8 to come in and clear.

Step 3.7.2.2.5: Verifies AH-E-95A has automatically started by ARO observing the red light lit and green light not lit.

Examiner's Note: The next step is a Two-hand operation.

Step 3.7.2.2.6/7: Presses "AH-D-28/617 RESET PB" on H&V PANEL and holds it in while Starting AH-E-20A by turning the Control Switch in the clockwise direction and observing the red ARO light lit and green light not lit. Releases "AH-D-28/617 RESET PB" on H&V PANEL when AH-D-28/617 are OPEN as indicated by ESAS indication on PCR or white open light on H&V Panel.

Procedure Note: Expect HVA-6-5 and HVA-4-5 to come in and clear.

Step 3 . 7.2.2.8: Verifies AH-E-93A/94A selected for operation at ARO H&V PANEL by switch position pointing to AH-E-93A/94A.

Footnotes: 1- AH-E-17A: A Control Building Normal Supply Fan.

2- AH-E-20A: A CB and Fuel Handling Building 1st Floor Exhaust Fan.

3 - AH-E-93A: .. A CB Hallway Supply Fan.

4 - AH-E-94A: A CB Hallway Exhaust Fan.

5 - AH-E-95A: A CB 2"d Floor Booster Fan.

6- AH-D-28/AH-D-617: CB 1st Floor Isolation Damper/Backup Damper.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario# 1 Event# _4..;....___ _ _ _ Page 30r of ....;5:..::3;;..;r1_-1 Event

Description:

Loss of Vital Bus D Time I Position I Applicant's Actions or Behavior Booth Cue: If directed as an Auxiliary Operator to:

1. START AH-E-21, then, after a pause, report back that "AH-E-21 is running".

2. SECURE AH-E-90 and 91 fans from FH Bldg. 305 OR to report the status of AH-E-90 and AH-E-91 , then after a pause, report back that "AH-E-90 and 91 are secured".

3. START AH-E-26, then, after a pause, report back that "AH-E-26 is running".

Examiner's Note: The following steps are not required for the scenario to continue but are scripted to give the CAS time to make the Tech Spec call.

OP-TM-AOP-018, Loss of VBD Procedure Note: Loss of power fails AH-D-30A-G and AH-D-31A-G closed, resulting in loss of ventilation to Control Building 322' Battery Rooms, Inverter Rooms, ES 480V Switchgear Rooms, and Remote Shutdown Area.

Step 3.8: Initiates OP-TM-AOP-034, "Loss of Control Building CRS Cooling."

Step 3.9: Select the desired groups {1-4 or 5-7) on CRD-FPM-ARO A (left side PI Panel).

Footnotes: 1 - AH-D-30A*G: AlB Battery Charger Room Inlet Dampers.

2- AH-D-31A-G: AlB Battery Charger Room Outlet Dampers.

3 - AH-E-21: Control Building Kitchen Exhaust Fan.

4 - AH-E-90: Primary Sample Hood Recirc/Exhaust Fan.

5 - AH-E-91: Control Building 1st Floor Recirc Fan.

6 - AH-E-26: Machine Shop and Chemical Hoods Supply Fan.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario# 1 Event# _ 4 ' - - - - - - Page 31 r- of ~5::..=3~11_--1 Event

Description:

Loss of Vital Bus D Time l Position I Applicant's Actions or Behavior 1

Procedure Note:

I Loss of power to RM-A-6G will trip AH-E-11. Loss of power to RM-A-4G and RM-G-9 will trip AH-E-1 0 and close dampers AH-D-120, AH-D-121, and AH-D-122.

Step 3.10: Places the following radiation monitor interlock switches in the DEFEAT position (PCR):

ARO

RM-A-4G

RM-A-6G

RM-G-9 Step 3.11: Restores Auxiliary Building and Fuel Handling ARO Building ventilation lAW 11 04-15A, "Auxiliary and Fuel Handling Building Supply and Exhaust System."

1104-15A, Auxiliary and Fuel Handling Building Supply and Exhaust System Step 3.3.2.1 /2: Verifies AH-E-14B/D are running by observing ARO the red lights lit and green lights not lit (H&V Panel).

Step 3.4.2.1.A.1: Ensures open FH BLDG Isolation Dampers, ARO AH-D-120, 121,122 (H& V Panel), by turning the Control Switch clockwise and verifying the red light is lit, green light not lit.

Step 3.4.2.1.A.2: Starts AH-E-1 0 by turning the Control Switch ARO in the clockwise direction and observing the red light lit and green light not lit.

Footnotes: 1 - RM-A-4G: Fuel Handling Building Exhaust Air - Gas, Area Radiation Monitor.

2- RM-A-6G: Auxiliary Building Exhaust Air- Gas, Area Radiation Monitor.

3- RM-G-9: Spent Fuel Bridge Radiation Monitor.

4 - AH-E-1 0: Fuel Handling Building Supply Fan.

5- AH-E-11: Auxiliary Building Supply Fan.

6 - AH-D-120, AH-D-121, and AH-D-122: Fuel Handling Building 348 Elevation Supply Dampers.

7- AH-E-14B/D: 8/D Aux Building I Fuel Handling Building Exhaust Fans.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario# 1 Event# 4 Page 32L of 531 !

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Event

Description:

Loss of Vital Bus D Time I Position I Applicant's Actions or Behavior Step 3.4.2.1.B: Starts AH-E-11 by turning the Control Switch in the clockwise direction and observing the red light lit and green ARO light not lit. Observes flows trending upward on AH-FR-149, 150, and 151 (H& V Panel)

Booth Cue: If directed to select instruments in HSPS Cabinet lAW AOP-018 Step 3.12, then INSERT EVENT #12, then report the instruments as selected.

OP-TM-AOP-018, Loss of VBD Step 3.13: Directs an Auxiliary Operator to select the following instruments in HSPS Cabinet Section A2 Rack 4 for EF-V-30B and EF-V-30D control:

CRS

LT-1042

LT-1040

LT-1050

LT-1 048 Declares a 3.5.5.2 (7 Day) Tech Spec clock, based on RM-G-CRS 26 or RM-G-22.

Footnotes: 1- AH-FR-149: Fuel Handling Building Exhaust Flow Recorder.

2- AH-FR-150: Auxiliary Building Exhaust Air Flow Recorder.

3- AH-FR-151: Aux Bldg/Fuel Handling Bldg Total Exhaust Flow Recorder.

4- AH-E-11: Auxiliary Building Supply Fan.

5- EF-V-308: EFW Control Valve to "B" OTSG.

6- EF-V-300: EFW Control Valve to "A" OTSG.

7- RM-G-22: High Range Containment Area Monitor.

8 - RM-G-26: "A" OTSG Turbine Bypass Line Radiation Monitor.

9- LT-1040: "/!~:' OTSG Operating Range Level Transmitter.

10- LT-1042: "A" OTSG Startup Range Level Transmitter.

11 - LT-1048: "B" OTSG Operating Range Level Transmitter.

12 - LT -1050: "B" OTSG Startup Range Level Transmitter.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 4 Page 331 of 531

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Event

Description:

Loss of Vital Bus D Time I Position l Applicant's Actions or Behavior I I Examiner's Note: T.S. 3.5.5.2: The channels identified for the instruments specified in Table 3.5-3 shall be OPERABLE. With the number of instrumentation channels Jess than required, restore the inoperable channel(s} to OPERABLE in accordance with the action specified in Table 3.5-3.

Table 3.5-3, Action A: With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirements:

1. either restore the inoperable channel(s} to OPERABLE status within 7 days of the event, or

2. prepare and submit a Special Report within 30 days following the event outlining action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

J I Examiner's Note: A 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Tech Spec (3.5.1.9} does exist if the alternate instruments are not selected for HSPS.

I I Examiner's Note: A Tech Spec does exist for PORV Position Monitors, also a 7 day clock, but can be exited by closing the PORV Block Valve.

l I Examiner's Note: Once Control Building ventilation has been restored and the Tech Spec call made, Go to Event 5.

I Footnote: 1 - PORV: Pressurizer Pilot Operated Relief Valve.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # _5;:;.__ _ _ _ Page 341 of _5;;..;;3;.;;;:c_ _

Event

Description:

Total FW Demand Fails to Zero Volts, ICS Transient Time I Position I Applicant's Actions or Behavior Booth Instructions: When directed by the Lead Examiner INITIATE Event 5 Indications Available: RCS Pressure transient, RCS Temperature transient, Reactor Power lowers rapidly and continuously, Multiple Annunciators in alarm.

Diagnoses the Total FW Demand Failure and/or the severe ICS Crew transient.

DIRECTS entry into OP-TM-AOP-070, PRIMARY TO CRS SECONDARYHEATTRANSFERUPSET OP-TM-AOP-070, PRIMARY TO SECONDARY HEAT TRANSFER UPSET Step 2.1 (IMA): Places the Diamond Station in Manual by URO pressing the Manual/Auto pushbutton on the Diamond Panel, observing the Manual light is lit and the Auto light is not lit (CC).

Step 2.2 (IMA): Places SG "A" FW Demand and SG "8" FW Demand ICS Stations in HAND by pressing the HAND URO/ARO pushbuttons on each ICS Station, verifying the white HAND lights are lit and the red AUTO lights are not lit on each (CC).

Step 2.3 (IMA): Verifies Turbine Header Pressure is between ARO 835 and 935 psig as read on the Turbine Header Pressure digital indication (CL).

Step 2.4 (IMA): Verifies RCS Pressure is lowering and/or less than 2205 PSIG by observing RCS pressure meters (CC/PC).

If RCS Pressure is >2205 psig, URO places RC-V-1 control in URO Manual (CC), opens RC-V-1 fully by pressing the open pushbutton and observing the red open light lit and the green closed light not lit, then places RC-V-1 control back to AUTO.

I Footnote: 1 - RC-V-1: Pressurizer Spray Control Valve.

Appendix D Operator Action Form ES-D-2

\ Op Test No.: NRC Scenario# 1 Event# 5 Page 35r of 531'

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Event

Description:

Total FW Demand Fails to Zero Volts, ICS Transient Time I Position I Applicant's Actions or Behavior Examiner's Note: OP-TM-AOP-070, steps 3.1 and 3.2 are IAAT's that should not be applicable during this Event.

Step 3.3: Verifies the Main Turbine is reset by observing it on-CRS line (CL).

Step 3.4: Assigns manual control responsibilities and control CRS bands as follows:

INSERT or WITHDRAW rods to maintain Reactor power URO within 1% of current power level by operating the Control Rod switch on the Diamond Panel as applicable (CC).

Adjust FW Flow to maintain Tavg within 2°F of current temperature by adjusting SG A and SG B FW Demand Station toggle switches as applicable (CC).

ARO Maintain Turbine Hdr Pressure within 10 psig of current pressure by adjusting Turbine Load Set Station demand as applicable (CC).

Examiner's Note: OP-TM-AOP-070, step 3.5 is N/A.

Step 3.6: Ensures SG/Reactor Demand, Reactor Demand, and SG AlB Load Ratio Demand Stations are in HAND by pressing each HAND pushbutton and observing white HAND lights are lit URO/ARO and red AUTO lights are not lit for each station. Observes that the ULD ICS Station is already in HAND by the white HAND light being lit.

Step 3.7: Verifies that MFW Pumps are controlling FW Valve CRS dP greater than 30 psid (CL) and that Reactor Power is greater than 75% (CC).

Examiner's Note: OP-TM-AOP-070, step 3.8 is N/A and 3.9 has already been verified.

Appendix 0 Operator Action Form ES-0-2 I Op Test No.: NRC Scenario # 1 Event # _5;....__ _ _ _ Page 361 of 531 1 i Event

Description:

Total FW Demand Fails to Zero Volts, ICS Transient I Time Position A licant's Actions or Behavior Step 3.10 and 3.11: Maintains RCS pressure between 2105 and 2205 psig, controls RCS Tavg 578 to 580 °F, and controls RCS ARO 6.Tc < 5° F by adjusting SG "A" and SG "B" FW Demand Station toggle switches as applicable.

Examiner's Note: OP-TM-AOP-070, steps 3.12 and 3.13 are N/A.

Examiner's Note: Once AOP-070 Actions are complete, and the plant is stable, Go to Event 6.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario# 1 Event# 6 Page 37r- of 531 i

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Event

Description:

-30 gpm "B" OTSG Tube Leak Time I Position I Applicant's Actions or Behavior Booth Instructions: When directed by the Lead Examiner INITIATE Event 6.

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 Step 3.1: NOTIFY "Shift Dose Assessor" to begin offsite dose CRS assessment.

ARO Step 3.2: Announce OTSG TUBE LEAK.

INFO Step 3.3: INITIATE Guide 9, "RCS Inventory Control.

OP-TM-EOP-01 0, GUIDE 9, RCS Inventory Control URO Step C.1: Verify MU Pump is operating.

URO Step C.2: Verify MU-V-5 is closed.

Step C.3: Verify MU24-FI >20 gpm URO RNO: Ensure MU-V-18 is Open by pressing the Open Pushbutton (CC), verifying the valve open light is lit and the valve closed light is not lit.

Footnotes: 1- RM-A-5115: Main Condenser Offgas Radiation Monitors.

2 - RM-G-27: "B" OTSG Turbine Bypass Line Radiation Monitor.

3- MU-V-5: Letdown Flow Control Bypass Valve.

4- MU-V-18: Normal Makeup Reactor Building Isolation Valve.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # _6.;....__ _ _ _ Page 38l of _5_3_l___,

Event

Description:

-30 gpm "B" OTSG Tube Leak Time I Position I Applicant's Actions or Behavior URO Step C.4: Ensure MU-V-17 is open.

URO Step C.5: Verify Pressurizer level is being restored.

OP-TM-EOP-005, OTSG Tube leakage Booth Cue: When directed to fire both Auxiliary Boilers, insert Event

13.

Step 3.4: INITIATE the following procedures to start both Auxiliary Boilers:

ARO

- OP-TM-414-401, "Starting AS-B-1A".

- OP-TM-414-402, "Starting AS-B-1 B".

CRS Step 3.5: VERIFY the reactor is critical.

Step 3.6: IAAT pressurizer level < 150 inches and reactor power > 25%, then perform the following:

N/A 1. INITIATE HPJ.

2. TRIP the reactor.

3. GO TO EOP-001 Step 3. 7: IAAT the turbine trips, and reactor power > 15%, then perform the following:

N/A

1. TRIP the reactor

2. GO TO EOP-001 Procedure Note: 1102-4, "Power Operation" actions to perform plant power reduction should be completed as resources permit. The rate of power reduction should be selected to maintain control and avoid lifting MSSVs.

Footnotes: 1- MU-V-17: Normal Makeup to RCS Control Valve.

2 - AS-8-1 A: "A" Auxiliary Boiler.

3 - AS-B-1 B: "8" Auxiliary Boiler.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6

__.;;_ ____ Page 391 of 531 ,

! Event

Description:

-30 gpm "B" OTSG Tube Leak Time Position Applicant's Actions or Behavior Step 3.8: RNO: REDUCE power at a rate within manual URO control limitations lAW OP-TM-621-471 "ICS Manual Operations".

Examiner's Note: The following step may have been performed previously and therefore is a condition met.

Step 3.9: PLACE both FW-P-1A and FW-P-1 8 in HAND lAW the following procedures:

- OP-TM-401-472, "Manual Control of FW-P-1A" by pressing the white "Hand" pushbutton (CC), verifying that the white "Hand" light is lit and the red "Auto" N/A light goes out.

- OP-TM-401-473, "Manual Control of FW-P-18" by pressing the white "Hand" pushbutton (CC), verifying that the white "Hand" light is lit and the red "Auto" light goes out.

Examiner's Note: The following step is a manual reactivity manipulation.

OP-TM-621-471, ICS Manual Operations Step 4.2.4: If necessary to maintain reactor power or control rods within limits or if a power change is being conducted lAW 1102-4, then ADJUST SG/REACTOR DEMAND as follows:

1. If maintaining stable reactor power or a slow planned power change, then RAISE or LOWER in discrete steps to keep neutron error between +2%

URO and -2%.

2. If rapid power reduction is required, then LOWER as necessary to achieve desired reactor power level and ENSURE FW flow controlled within limits by lowering and/or raising on the SG/REACTOR DEMAND toggle switch (CC) as necessary.

Footnotes: 1- FW-P-1A: "A'j Main Feedwater Pump.

2- FW-P-18: "8" Main Feedwater Pump.

3 - ULD: Unit Load Demand.

Appendix D Operator Action Form ES-D-2 OpTest No.: NRC Scenario# 1 Event# 6 Page 401 of 531

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

Event

Description:

-30 gpm "B" OTSG Tube Leak Time l Position I Applicant's Actions or Behavior Examiner's Cue: Acknowledge as the personnel listed in the next step, or acknowledge as Shift Manager to notify the personnel listed in the next step. Also acknowledge to evaluate EAL's.

OP-TM-EOP-005, OTSG Tube leakage Step 3.10: REQUEST SM to:

- Evaluate Emergency Action Levels CRS - NOTIFY Power Team

- NOTIFYTSO

- NOTIFY NDO.

CRS Step 3.11: IDENTIFY the affected OTSG:

Booth Cue: When directed to place the MS-V-138 handwheel in the closed position, insert Event #14 and then report the action complete.

Step 3.12: IAAT all of the following conditions exist:

- The affected OTSG is identified

- EF-P-1 is not running ARO

- Either Motor Driven EFW Pump is Operable then Place the Handwheel of the affected MS-V-13, in the CLOSED position.

CRS Declares a 3.1.6.2 and 3.1.6.3 (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) Tech Spec clock.

Examiner's Note: Technical 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.

Examiner's Note: After the Tech Spec call is made and sufficient reactivity manipulation has occurred, GO TO Event 7.

j Footnote: 1 - MS-V-138: Main Steam Supply to EF-P-1 from "B" OTSG.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7/8 Page 411 of 53l~

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Event

Description:

RC-P-1 B Trip, Reactor Trip, -500 gpm "B" OTSG Tube Rupture with an elevated offsite dose, MU-V-36 fails to open Time I Position I Applicant's Actions or Behavior Booth Instructions: When directed by the Lead Examiner INITIATE Event 7.

Indications Available: RC-P-1 B Green light lit, All Control Rod bottom lights, various annunciators, Pressurizer level lowering, RCS Pressure lowering, "B" OTSG level rising Examiner's Note: The CRS will direct the IMAs of OP-TM-EOP-001, Reactor Trip and following the Symptom Check he should re-enter OP-TM-EOP-005, OTSG Tube Leakage. Based on the reactor being tripped, previous actions have already been taken and the event picks up at step 3.24. The crew may or may not have made it through step 3.23, but those steps are not applicable once the reactor is tripped.

The URO will continue in Guide 9, RCS Inventory (This Page).

Crew Diagnoses RC-P-1 B trip and the Reactor trip.

OP-TM-EOP-001, REACTOR TRIP URO Step 2.1 {IMA): Presses Both Reactor Trip and DSS pushbuttons (CC).

URO Step 2.2 (IMA): Verifies that the reactor is shutdown by one of the following:

Power Range Nuclear Instrumentation indicates less than 5% (CC)

All control rods are inserted (PC)

Source Range count rate is continuously lowering (CC)

URO Step 2.3 (IMA): Presses the Turbine Trip pushbutton (CL}

URO Step 2.4 (IMA): Verifies the Turbine Stop valves are closed by observing the indication on CL.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario# 1 Event# 7/8 Page 42L of 53c

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

Event

Description:

RC-P-1 B Trip, Reactor Trip, -500 gpm "B" OTSG Tube Rupture with an elevated offsite dose, MU-V-36 fails to open Time Position Applicant's Actions or Behavior AAO Performs a Symptom Check, and identifies the "B" OTSG tube leak, and informs the CAS.

Diagnoses the "B" OTSG Tube leak rate increasing by lowering UAO Pressurizer level and ACS pressure, and informs the CAS.

OP-TM-EOP-01 0, GUIDE 9, RCS Inventory Control Step C.S: Verify Pressurizer Level is being restored.

RNO:

UAO Throttle MU-V-217 by pressing the open pushbutton (CC),

verifying valve open light is lit and valve closed light not lit.

UAO Step C.6: Verify MU24-FI > 20gpm Step C.7: Verify Pressurizer Level is being restored.

RNO:

UAO Close MU-V-3 by pressing the close pushbutton (CC), verifying valve closed light is lit and valve open light not lit.

Step C . 8: Verify Pressurizer Level is being restored.

RNO:

UAO INITIATE HPI lAW OP-TM-211-901, "Emergency Injection HPI/LPI" by pressing manual ES pushbuttons (CC and CA)

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7/8 Page 431 of 53Ci

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Event

Description:

RC-P-1 B Trip, Reactor Trip, -500 gpm "B" OTSG Tube Rupture with an elevated 1

offsite dose, MU-V-36 fails to open I T;me Position Applicant's Actions or Behavior OP-TM-EOP-005, OTSG Tube Leakage.

Step 3.24: Verify control rod groups 1 through 7 are fully URO inserted.

Examiner's Note: Step 3.25 has already been performed. The CRS should continue in OP-TM-EOP-005. This event picks up at step 3.29. The crew may or may not have made it through step 3.28. Those are listed in the ous events ARO Step 3.26: Ensure announcement of reactor trip.

ARO Step 3.27: Dispatch an operator to check MSSV status.

ARO Step 3.28: Ensure performance of an alarm review.

Step 3.29: IAAT OTSG A (B) pressure approaches, or is greater than 1000 psig, then perform the following:

ARO ENSURE MS-V-2A (MS-V-2B) is Open.

OPEN MS-V-30, E, F (MS-V-3A, B, C) to maintain OTSG ressure < 1000 Examiner's Note: Cooldown rate is 100°F/hr per Guide 11 until 10CFR 50.54x is invoked.

Step 3.30: IAAT OTSG level is rising due to tube leakage in an AVAILABLE OTSG, then preferentially STEAM to maintain CT-21 ARO OTSG level< 85% by adjusting the toggle switches for MS-V-3A/B/C u rd/downward as necessa Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7/8 Page 441 of 53l:

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Event

Description:

RC-P-1 B Trip, Reactor Trip, -500 gpm "B" OTSG Tube Rupture with an elevated offsite dose, MU-V-36 fails to open Time I Position I Applicant's Actions or Behavior Procedure Note: If exceeding RCS or Pressurizer Tech Spec cooldown rate limits is needed to permit isolation of an OTSG, then 10CFR 50.54x entry should be evaluated.

Examiner's Note: Step 3.31 is N/A at this time.

Step 3.32: IAAT all of the following exist:

- RCS pressure < 1750 psig,

- SCM> 25 °F,

- RCS pressure is being controlled, URO then BYPASS 1600 psig ESAS lAW 1105-3 by pressing the appropriate bypass/defeat pushbuttons (CC and CR) and verifying that the appropriate bypass/defeat lights are lit.

Step 3.33: MINIMIZE SCM lAW Guide 8, "RCS Pressure INFO Control".

Examiner's Note: The upper band for minimizing Subcooling Margin is found is OS-24, Conduct of Operations During Abnormal and Emergency Events, Section 3.9:

An intentional reduction of RCS pressure, to minimize SCM, when SCM is > 70 degF. Actions to minimize SCM are described in Guide 8.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7/8 Page 451 of 531:

~=-~

Event

Description:

RC-P-1 8 Trip, Reactor Trip, -500 gpm "8" OTSG Tube Rupture with an elevated offsite dose, MU-V-36 fails to open Time l Position I Applicant's Actions or Behavior OP-TM-EOP-01 0 Guide 8, RCS Pressure Control IAAT REACTOR is SHUTDOWN and SCM> 25 °F, 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 all RCPs are OFF and OTSG TUBE LEAKAGE does not exist, then MAINTAIN pressure above "Head bubble" limit (Fig 1 and 1A).

Examiner's Note: HPI Throttling lAW Rule 2 is described on the next page.

INFO Step B.1: ENSURE HPI/LPI is throttled per Rule 2 Examiner's Note: Guide 8 Step 8.2 has already been performed and Step 8.3 is not expected to occur.

URO Step B.4: Ensure Pressurizer heaters are off by rotating the Control Switches for all heater banks to the OFF position (CRJ Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 718 Page 46L of 53c

~~------ ~=-~

Event

Description:

RC-P-1 B Trip, Reactor Trip, -500 gpm "B" OTSG Tube Rupture with an elevated offsite dose, MU-V-36 fails to open Time Position Applicant's Actions or Behavior URO Step 8.5/6: Perform the following:

A. Verify an RCP is on by red running light, red indicator flag, and amps.

B. Ensure RC-V-3 is open by red open light lit, green closed light not lit.

c. Throttle open RC-V-1 by placing the Auto-Manual Control switch in Manual and then pressing down on CT-7 the Open pushbutton until the desired throttle position. Tweaks in the other direction may be required.

When the desired pressure and/or SCM is achieved, close RC-V-1 by pressing the closed pushbutton until the closed light is lit and the open light is not lit or by placing the Control Switch in the Auto position and then verifying the lights indicate closed.

Examiner's Note: OP-TM-EOP-01 0, RULE 2, Steps A.1 through A.3 conditions are met.

OP-TM-EOP-01 0, RULE 2, HPI THROTTLING Step A.4: Determines that SCM > 25F and HPI COOLING is URO not required, and throttles HPI lAW OP-TM-211-901, EMERGENCY INJECTION (HPI/LPI).

OP-TM-211-901, EMERGENCY INJECTION {HPIILPI)

Att. 7.3, Step 1: Defeats ESAS signals by pressing the defeat URO pushbuttons (manual and/or automatic signals as required).

Examiner's Note: Step 2 condition is met.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario# 1 Event# 718 Page 47L of 53L

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Event

Description:

RC-P-1 B Trip, Reactor Trip, -500 gpm "B" OTSG Tube Rupture with an elevated offsite dose, MU-V-36 fails to open Time Position Applicant's Actions or Behavior Att. 7.3, Step 3/4: WAAT HPI throttling is permitted lAW RULE 2 and prior to reducing any MU pump flow to less than 115 GPM, then perform the following:

Obtains CAS concurrence to throttle HPI.

Determines that DH-V-7A and DH-V-78 are closed, and URO opens MU-V-37 by pressing the open pushbutton and observing the open light lit and the closed light not lit (CC).

Determines that MU-V-36 will not open by observing the open light not lit and the closed light lit (CC) and maintains MU Pump flow greater than 115 GPM.

Examiner's Note: OP-TM-211-901, Step 5 will be performed, but is not the priority. Guide 9 is initiated already, so the step is met, but it is important to move on and terminate HPI to avoid lifting the PORV.

Att. 7.3, Step 7: Closes two MU-V-16 valves to establish flow through one valve on each train and retain HPI flow through four RCS nozzles (e.g., MU-V-16A and MU-V-16D) by pressing the URO closed pushbutton for two MU-V -16 valves and verifying that the closed light is lit and the open light is not lit for each of the two valves.

Att. 7.3, Step 8: Throttle open the MU-V-16 opposite of MU and Sf (MU-V-16C or MU-V-16D) by pressing the close, open, and URO stop pushbuttons as necessary to provide adequate HPI makeup flow.

Foptnote$: .f- I).H-;V~lA: "k.:ge~v.Heatc=oofer Quti~t. to M'q~eump:SuQ~n*~alve.

. :~~~~~tf~~i~~;i~~~~~~ve.

4 ~M~v<~r~'.,~-P:*1~B1Q. Jsollti()n .\tpfve.

. . 5*****i:'...>-. PbR~

';*-) . .... :;.. .. .

~Jtessud~erP,iJdi

'"<??"' ~

j :, : ; <~*"' *x .* ;'.

o@er~ted. R$lte! Valv~\.

.** ;. **'('~~-~*. . ' <"*'

6,it4tJi..V**J.,§A: * *~*~* HPI;Cont,oiVa{ve.

7**~ ~~~V:~,jb~l.:~~e:***~~}S,~Co~.!~~::valvel't1r MV- \l;.'f$0: 0 .HP1' ConttfJI Vafve.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario# 1 Event# 718 Page 48c of 53r,

~~------ ~~~

Event

Description:

RC-P-1 B Trip, Reactor Trip, -500 gpm "B" OTSG Tube Rupture with an elevated offsite dose, MU-V-36 fails to open Time I Position l AQQiicant's Actions or Behavior Examiner's Note: The following steps to throttle HPI will only be performed if HPI flow is still excessive and is not required prior to scenario termination.

Att. 7.3, Step 9: If two MU pumps are operating, then when flow is reduced to one MU-V-16:

2. If two MU pumps are operating, then SHUTDOWN the ES URO selected pump and PLACE Control Switch in Normal-After-Stop (MU-P-1 C) by rotating the Control Switch counter-clockwise, observing that the green indicator flag is visible, the green off light is lit, the red running light is not lit, and amps are zero (CR}_

Examiner's Note: Step 10 is N/A.

Att. 7.3, Step 11:

THROTTLE MU-V-16 parallel to MU and Sl (MU-V-16A or MU-URO V-168) by pressing the close, open, and stop pushbuttons as necessary to provide adequate HPI makeup flow.

Examiner's Cue: Role play as Shift Manager, as requested, and give permission to open MU-V-18.

Att. 7.3, Step 12: Upon obtaining Shift Manager concurrence, determines that OP-TM-244-901 requirements are met and URO opens MU-V-18 by pressing the open pushbutton and observing the open light lit and the closed light not lit (CC).

Footnotes: 1 - MU*P-1C: "C' Makeup Pump.

2- MU-V-16A: "A" HPI Control Valve.

3- MU-V-168: "B" HPI Control Valve.

4 - MU-V-18: Normal Makeup Reactor Building Isolation Valve.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # _7_18_ _ _ _ Page 491 of ....:5:....:::3....:1~--t Event

Description:

RC-P-1 B Trip, Reactor Trip, -500 gpm "B" OTSG Tube Rupture with an elevated offsite dose, MU-V-36 fails to open Time I Position I A!-!1-!licant's Actions or Behavior OP-TM-EOP-005, OTSG Tube Leakage.

Step 3.34: IAAT OTSG level> 85% Operate Range, then perform the following:

_1. When RCS pressure< 1000 psig, then INITIATE Attachment 1A or 1B to isolate the OTSG.

N/A

_ 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 "RCS Stabilization".

Step 3.35: IAAT both OTSGs are available, and projected or actual offsite integrated dose approaches 500 mRem TEDE or 1500 mRem CDE (thy}, then perform the following:

Crew

1. When RCS pressure< 1000 psig, then INITIATE Attachment 1A or 1B to isolate the most affected OTSG.

2. When the affected OTSG TBVs and ADVs are closed, then PERFORM Guide 12 "RCS Stabilization".

Booth Cue: When Subcooling Margin has been minimized and when directed by the Lead Examiner, call in as the shift dose assessor and report that "projected Off-Site Integrated Dose is 1.6R thyroid".

Examiner's Note: Step 3.31 is an IAAT step that now has conditions met.

Once RCS pressure is less than 1000 psig, Attachment 1B will be entered.

Procedure Note: If exceeding RCS or Pressurizer Tech Spec cooldown rate limits is needed to permit isolation of an OTSG, then 10CFR 50.54x entry should be evaluated.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario# 1 Event# 7/8 Page 501_ of 53LJ

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Event

Description:

RC-P-1 B Trip, Reactor Trip, -500 gpm "B" OTSG Tube Rupture with an elevated offsite dose, MU-V-36 fails to open Time I Position l Applicant's Actions or Behavior Step 3.31: IAAT 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 Crew RCS 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.

OP-TM-EOP-005, ATTACHMENT 18, OTSG 8 Isolation Ensure Closed the following valves (Control Room):

ARO - MS-V-1C by pressing the close pushbutton, verifying that the green closed light is lit, and the red open and white test lights are not lit (CC).

- MS-V-1 D by pressing the close pushbutton, verifying ARO that the green closed light is lit, and the red open CT-22 and white test lights are not lit (CC).

- FW-V-178 by placing the ICS Control Station to HAND by pressing the white HAND pushbutton, verifying white HAND light lit, red AUTO light not lit, ARO then ensuring that the valve is closed by moving the toggle switch in the down direction until closed is indicated (if necessary) (CC).

- FW-V-58 by ensuring the green closed light is lit and ARO the red open light is not lit (CC).

Footnotes: 1- MS-V-1C: Main Steam Isolation Valve of 8" OTSG "C" Line.

2- MS-V-1 D: Main Steam Isolation Valve of "B" OTSG "D" Line.

3- FW-V-178: lfB" Main Feedwater Control Valve.

4- FW-V-58: "B" Main Feedwater Block Valve.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7/8 Page 5H of 53U

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Event

Description:

RC-P-1 B Trip, Reactor Trip, -500 gpm "B" OTSG Tube Rupture with an elevated offsite dose, MU-V-36 fails to open Time I Position I AQQiicant's Actions or Behavior

- FW-V-168 by placing the ICS Control Station to HAND by pressing the white HAND pushbutton, verifying white HAND light lit, red AUTO light not lit, ARO then ensuring that the valve is closed by moving the toggle switch in the down direction until closed is indicated (if necessary) (CC).

- FW-V-928 by ensuring the green closed light is lit ARO and the red open light is not lit (CC).

CT-22 Ensure Closed the following valves (Control Room):

- EF-V-308 by placing the Control Station in Manual ARO by pressing the Manual pushbutton and ensuring that Manual is lit and Auto is not lit, then by locking the dial tab in the full left position (CC).

- EF-V-30C by placing the Control Station in Manual by pressing the Manual pushbutton and ensuring ARO that Manual is lit and Auto is not lit, then by locking the dial tab in the full left position (CC).

Footnotes: 1- FW-V-168: "8" Feedwaterstartup Control Valve.

2- FW-V-928: "8" OTSG Startup Feedwater Block Valve.

3- EF-V-308: EFW Control Valve to "B" OTSG.

4- EF-V-30C: EFW Control Valve to "B" OTSG.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario# 1 Event# 718 Page 52r of 531.

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

Event

Description:

RC-P-1 B Trip, Reactor Trip, -500 gpm "B" OTSG Tube Rupture with an elevated offsite dose, MU-V-36 fails to open Time I Position I Applicant's Actions or Behavior

- MS-V-3A, MS-V-38, MS-V-3C, and MS-V-48 by placing the ICS Control Station to HAND by pressing the white HAND pushbutton, verifying white HAND CT-22 ARO light lit, red AUTO light not lit, then ensuring that the valve is closed by moving the toggle switch in the down direction until closed is indicated (if necessary)

(CC).

- Verifying that MS-V-138 and CA-V-48 or CA-V-58 ARO are already closed by the green closed light lit and red open light not lit (CC and PCR).

Examiner's Note: Scenario can be terminated when HPI has been throttled, SCM has been minimized, and the "8" OTSG has been isolated.

Follow-up question: What was the highest event entered during scenario?

FA1 - OTSG Tube Rupture requiring ESAS Actuation Footnotes: 1 - MS-V-3A/8/C: Turbine Bypass Valves from the "8" OTSG.

2- MS-V-48: Atmospheric Dump Valve for the "8" OTSG.

3- MS-V-138: Main Steam Supply Valve to EF-P-1 from "8" OTSG.

4- CA-V-48: "B OTSG Feedwater Sample Valve.

5- CA-V-48: "B OTSG Feedwater Sample Isolation Valve Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7/8 Page 53r- of 53r

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Event

Description:

RC-P-1 B Trip, Reactor Trip, -500 gpm "B" OTSG Tube Rupture with an elevated offsite dose, MU-V-36 fails to open Time I Position I Applicant's Actions or Behavior OP-TM-AOP-018 ATTACHMENT 1 EFFECTS OF LOSS OF VBD Page 1 of 1 One channel of CRD Trip Confirm wiD de-energize to its actuate state but the other channel remains operable. Turbine will not trip and FW-V-SAIB will not close.

"D" RPS channel de-energ1zes. CRD-CB-10 open. "D" RPS channel trip signal is sent to all other RPS cabinets. (TS Table 3.5-1 )

RCPPM-10&20 de-energize. RC-P-10 tripped signal is sent to RPS Channels A, B, and C, and HSPS EFW Initiation Train A & Train B.

ES Relay Cabinet 38 de-energizes: 1 channel tripped in all ES actuations, B train only.

HSPS Channel IV de-energizes. HSPS Channel IV tripped signal sent to HSPS Trains A & B.

Mudtiple SASS transfers occur due to loss of HSPS Channel IV instruments.

Annunciator SER B de-energizes. MAP annunciator power remains on VBC. Annunciator Panel Pl transfers to backup power from TRA. All Annunciators on PRF and PRF1 fail.

Loss of power to RM-L-6 will close WDL-V-257.

Loss of power to RM-A-6G will trip AH-E-11.

Loss of power to RM-A-4G will trip AH-E-10 and close dampers AH-0-120, AH-0-121, and AH-D-122.

Loss of power to RM-A-7G will close WDG-V-47.

Loss of power to RM-A-1 G trips AH-E-17AIB, AH-E-20AIB, AH-E-21, AH-E-26, AH-E-93AIB, AH-E-94AIB & AH-E-95AI8, doses AH-D-28 and AH-D-617. I Loss of power to RM-G-9 TripsAH-E-10 and closes AH-0-120, AH-D-121, and AH-0-122.

AH-D-30A-G and AH-D-31A-G fail closed, resulting in loss of ventilation to A&B Battery Rooms, A&B Inverter Rooms, 1P & 1S 4SOV ES Switchgear Rooms, and Remote Shutdown Area.

Control room radio on Computer Console, P.E.M.A radio, and Scanner will be inoperable.

Control room radio on CRS desk will remain operable.

Scenario Event Description NRC Scenario 2 Facility: Three Mile Island Scenario No.: 2 Op Test No.: 12-01 NRC Examiners: Operators:

Initial Conditions: * (Temporary IC-242)

100% Power, MOL

SBO OOS For Maintenance, expected to return to service in 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months

Crane work is occurring on the West side of the Plant to stage new piping .

NRC Authorization Code for today is AB12 .

Turnover: Maintain 100% Power Operations Critical Tasks:

Isolate Possible RCS Leak Paths (CT-3}

Natural Circulation RCS Flow (CT-12)

Turbine Trip (CT-18)

Event No. Malt. No. Event Type* Event Description 1 DHR32 TSCRS BWST level lowers, entry into OP-TM-MAP-E0204 2 MS19A C CRS lsolable Steam Leak in Turbine Bldg, entry into OP-TM-AOP-051.

C ARO (ARO: Isolate Steam Leak) 3 IC23 I CRS SG/RX Demand Station fails to 0 Volts, Entry into OP-TM-AOP-070 IURO (URO/ARO: Coordinate to stabilize plant in ICS HAND control}

IARO 4 TU01D NCRS High Vibrations on Main Turbine, entry into OP-TM-MAP-K0201 and 1102-4.

R URO (URO/ARO: Power reduction with ICS in Manual)

NARO 5 ZDIPB1 TSCRS Inadvertent 1600# ESAS Signal, entry into OP-TM-AOP-046.

RCA IURO IARO (URO:Immediate Manual Actions, ARO: Restores Letdown) 6 ED05D TSCRS Loss of 1D 4Kv Bus, entry into OP-TM-AOP-013.

C ARO (ARO: Places LO-P-6 in PTL) 7 EG04A I CRS Loss of Stator Coolant Pumps, Main Turbine fails to automatically runback and trip EG04B I URO (URO: Trip Reactor, ARO: Adjust Main Feedwater) 8 ED01 MCRS Loss of Offsite Power, entry into OP-TM-AOP-020.

MURO MARO 9 EG07A CCRS EG-Y-1 B Trips, Station Blackout CURO (URO: Isolates Cooling paths to RCP's)

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 2 Three Mile Island NRCScenario #2 Event #1: When the crew has accepted the watch, the Lead Examiner will cue the lowering level of the BWST due to a crane piercing the tank at the 53.5 ft level.

The crew will diagnose the low level in the BWST by lowering level on the BWST level indicators (CC and CR) and annunciator E-3-4 in alarm. Although it initially drops rapidly, the crew will identify it as steady at approximately 54.5 ft. The CRS will review and declare the following Tech Spec: 3.3.1.1.a:

3.3.1.1 Injection Systems

a. The borated water storage tank (BWST) shall contain a minimum of 350,000 gallons of water having a minimum concentration of 2,500 ppm boron at a temperature not less than 40°F. If the boron concentration or water temperature is not within limits, restore the BWST to OPERABLE within 8 hrs. If the BWST volume is not within limits, restore the BWST to OPERABLE within one hour.

Specification 3.0.1 applies.

Once the Tech Spec has been declared, the scenario can continue.

Event #2: The Lead Examiner will cue the lsolable Steam Leak in the Turbine Building.

The operators will diagnose a Secondary Side Steam Leak based on a lowered efficiency of the Secondary Plant (Megawatts, Header Pressure, OTSG pressures, etc.)

Upon a Steam Leak in the Turbine Building, the following Critical Safety Functions are affected:

CSF 1, Reactivity and Reactor Power Control: Maintain control of the fission process, maintain the capability to shutdown the reactor and the capability to maintain the reactor in a shutdown condition. Control energy production and reactor power distribution based on design limits and current core heat removal capability. A secondary side steam leak will bypass steam away from the Turbine. If the steam leak is large enough, electrical generation will lower. ICS will raise reactor power to raise MWe back up to ICS demanded MW. If the steam leak causes Tave to lower, ICS will also try to raise reactor power to recover Tave.

CSF 7, Electrical Power: Provide electrical power as required to accomplish the other Critical Safety Functions. Provide AC and DC power for emergency equipment operation and instrumentation systems. A Steam Leak may affect power to non-safety related equipment in the Turbine Building.

CSF 9, Fire Protection and Remote Shutdown Capability: Maintain means to prevent detect and suppress fires, as well as the capability to perform a plant shutdown without access to the Control Room . A Steam Leak may cause fire alarms to actuate. This could be the first indication of a Steam Leak to the Control Room. May cause sprinkler systems to actuate or fire dampers to close.

Scenario Event Description NRC Scenario 2 The crew will diagnose the Steam Leak and the CRS will enter OP-TM-AOP-051, Secondary Side High Energy Leak. OP-TM-AOP-051 is entered for Steam Leaks that affect large portions of the plant and therefore it is not obvious to the operator what needs to be done initially to isolate the leak.

The affected Building is determined and from there, OP-TM-AOP-051 systematically attempts to isolate the leak remotely from the Control Room while taking steps to minimize the adverse effects of a steam environment on safety related equipment. The OP-TM-AOP-051 mitigation strategy for a Steam Leak in the Turbine Building is as follows:

Attempt to isolate the leak from the Control Room.

Shutdown and Cooldown the plant in a controlled manner to minimize pressure surges that could make the leak worse. Shutdown may have to be done quickly or the plant may have to be tripped depending on the circumstances.

The ARO will isolate Steam Leak by closing the appropriate valve, MS-V-5B. This can be performed because the steam supplies to the Main Feedwater Pumps are as follows:

Below 25% power, Main Steam, only, supplies the Main Feedwater Pumps.

Between 25% and 40% power, Main Steam supplements Extraction Steam as supplies to the Main Feedwater Pumps.

Above 40% power, Extraction Steam, only, supplies the Main Feedwater Pumps.

Once the Steam Leak has been isolated, the scenario can continue.

Event #3: The Lead Examiner will cue the failure of the SG/RX Demand Station to Zero Volts.

This will cause an ICS transient, which if not responded to swiftly, will cause a Reactor Trip.

The crew will diagnose the ICS failure by a rapid change in RCS pressure, Reactor Power rising, multiple annunciator alarms, and/or changes in indications at multiple ICS stations. Entry into OP-TM-AOP-070, PRIMARY TO SECONDARY HEAT TRANSFER UPSET will be required based on RCS pressure not being controlled in ICS AUTO.

"RCS pressure is not being controlled" requires the operator to make a subjective determination, based on their skills, training, and experience. A determination that RCS pressure is being controlled should include the following elements: 1) The reason for the transient is understood 2) RCS pressure response is consistent with the expected response for the event 3) Automatic or manual control in accordance with normal operating procedures is effectively controlling RCS pressure. A conservative assessment (i.e. concluding that RCS pressure is not being controlled) is appropriate when the three conditions above cannot be satisfied. ICS failures are one class of events that can lead to an upset in primary to secondary heat transfer. Most ICS failures can be mitigated by use of the appropriate manual control normal operating procedures.

This entry into AOP-070 is unique from the other scenarios because Reactor Power will lower while RCS pressure rises. The URO will have to place the Diamond Panel in manual to control Reactor Power or RPS will trip the reactor on high RCS pressure.

Once the plant is stabilized in ICS HAND control, the scenario can continue.

Scenario Event Description NRC Scenario 2 Event #4: The Lead Examiner will cue the High Vibrations on Main Turbine.

The crew will diagnose the High Vibrations on Main Turbine by Annunciator K-2-1 in alarm, and multiple PPC points in alarm. The crew will commence a power reduction to < 45% with ICS in manual in order to trip the Main Turbine. This is the reactivity manipulation for the scenario.

Once sufficient reactivity manipulation has occurred, the scenario can continue.

Event #5: The Lead Examiner will cue the Inadvertent 1600# ESAS Signal. The crew must quickly recognize the condition and perform the required Immediate Manual Actions to minimize the RCS pressure transient and pressurizer in-surge due to HPI. Additionally, while at power, immediately reducing HPI also minimizes the possibility of a reactor trip on high RCS pressure.

The following Critical Safety Functions are affected by an inadvertent ESAS signal:

CSF 1, Reactivity & Reactor Power Control: Maintain control of the fission process, maintain the capability to shutdown the reactor and the capability to maintain the reactor in a shutdown condition. Control energy production and reactor power distribution based on design limits and current core heat removal capability. HPI Actuation will insert negative reactivity as borated water from the BWST will be injected into the RCS. ICS will pull control rods to maintain ULD demand and RCS Tave. Potential all rods out condition. As primary side power decreases, ICS cross limits will lower feedwater flow in an attempt to match primary to secondary heat removal.

CSF 2, Reactor Vessel Inventory Control: Provide the means to maintain the core covered with sub cooled water. HPI Actuation will isolate RCS letdown and normal makeup. HPI will cause pressurizer level to rise. MU tank level will lower (MUT level/pressure requirements). BWST level will lower (BWST TS level).

CSF 3, RCS Integrity: Maintain the capability to control heatup and cooldown rates and control RCS pressure to prevent reactor vessel brittle fracture or LTOP events. Maintain RCP seal cooling to prevent excessive loss of RCS inventory through RCP seals. HPI Actuation will cause RCS pressure to rise. Seal Injection is not affected by an ES actuation. AOP-046 has the operator secure the remaining MU pump if the MU-V-16s cannot be closed from the control room. This action immediately terminates HPI and seal injection. The thermal barrier heat exchangers provide adequate seal cooling when the Sl is secured. AOP-046 ensures adequate thermal barrier cooling prior to terminating seal injection. Once MU-V-36 and 37 are opened locally and the appropriate MU-V-16s are closed, a makeup pump is restarted and Sl is re-established.

CSF 4, Core Heat Removal: Provide the capability to remove core heat production at all times. HPI Actuation will inject cold BWST into the RCS. The RCS will also cool due to the negative reactivity insertion from the injected BWST water lowering core power.

Scenario Event Description NRC Scenario 2 CSF 5, Containment Integrity: Provide means to prevent or minimize fission product release to the environment. (1) Maintain containment pressure below design and (2)

Provide capability to isolate the containment when required. An inadvertent HPI Actuation will start the Reactor River system, and the RB cooling fans will be running in slow speed. Normal cooling to the RB cooling fans will be isolated. RB Temperature and pressure will lower due to the actuation of the RR system. The degree of temperature reduction would depend of river temperature. Building Spray System valves will open to align the BWST to the RB, but the BS pumps would not start unless a 30# signal is present. Closure of the containment isolation valves under the HPI signal would not adversely affect their associated systems.

CSF 7, Electrical Power: Provide electrical power as required to accomplish the other Critical Safety Functions. Provide AC and DC power for emergency equipment operation and instrumentation systems. An inadvertent HPI Actuation will start the emergency diesel generators unloaded.

CSF 8, Auxiliary Emergency Systems: Provide equipment cooling (closed cooling &

ventilation), and other support requirements to accomplish the other Critical Safety Functions. Provide Instrument Air for operation of EFW, ADVs, RCP Support Systems and some containment isolation valves. An inadvertent HPI Actuation will start support systems to support ECCS and RB cooling systems. The DC and DR pumps will start to support MUP and DHP cooling which would be running during an inadvertent actuation.

ES selected NS and NR pumps will start. Two NR and NS pumps are normally running.

There is a potential for three NS pumps running which would start an overcooling of the NS system.

CSF 9, Fire Protection & Remote Shutdown Capability: Maintain means to prevent, detect, and suppress fires, as well as the capability to perform a plant shutdown without access to the Control Room. An inadvertent HPI Actuation would trip FS-P-2.

The crew will diagnose the Inadvertent "A" 1600# ESAS Signal by multiple annunciators in alarm, "A" Train components in their ES actuated state, and/or "A" EDG running, while all primary indications appear steady or rising (RCS pressure not at 500#}.

The URO will perform the Immediate Manual Actions of OP-TM-AOP-046, INADVERTANT ESAS. The ARO will restore letdown lAW OP-TM-211-950 (performing the appropriate portion of the procedure when restoring from isolation following an ESAS signal).

Once the plant is stabilized and Letdown is restored, the scenario can continue.

Event #6: The Lead Examiner will cue the Loss of the 1D 4Kv Bus.

Upon a Loss of the 1D 4Kv Bus, the following Critical Safety Functions are affected:

CSF 1, Reactivity & Reactor Power Control: Maintain control of the fission process, maintain the capability to shutdown the reactor and the capability to maintain the reactor in a shutdown condition. Control energy production and reactor power distribution based on design limits and current core heat removal capability. A loss of the 1 D 4Kv bus will not affect reactor shutdown capability. Emergency boration must be performed using "B" Train as MU-V-14A, MU Pump Suction Valve from BWST, will be unavailable.

Scenario Event Description NRC Scenario 2 CSF 2, Reactor Vessel Inventory Control: Provide the means to maintain the core covered with sub cooled water. A loss of 1D 4Kv bus will cause Train A Emergency Core Cooling Systems (HPI and LPI) to be inoperable. Train B is unaffected.

CSF 3, RCS Integrity: Maintain the capability to control heatup and cooldown rates and control RCS pressure to prevent reactor vessel brittle fracture or LTOP events. Maintain RCP seal cooling to prevent excessive loss of RCS inventory through RCP seals. A loss of 1D 4Kv bus will cause RC-V-1, Pressurizer Spray Valve, and the Emergency power to Pressurizer Group 8 Heaters to be unavailable.

CSF 4, Core Heat Removal: Provide the capability to remove core heat production at all times. A loss of the 1D 4Kv bus will cause EF-P-2A and DHR Train A to be inoperable.

EF-P-2B, EF-P-1, and DHR Train Bare available.

CSF 5, Containment Integrity: Provide means to prevent or minimize fission product release to the environment. {1) Maintain containment pressure below design and (2)

Provide capability to isolate the containment when required. A loss of 1 D 4Kv bus causes Reactor Building Emergency Cooling Train A and Building Spray Train A to be unavailable. Train B is available as well as Normal Reactor Building Cooling.

CSF 7, Electrical Power: Provide electrical power as required to accomplish the other Critical Safety Functions. Provide AC and DC power for emergency equipment operation and instrumentation systems. A loss of the 1 D 4Kv bus due to a bus fault will prevent use of the Emergency Diesel Generators. Prolonged loss of AC increases the risk of a Loss of DC and Vital busses.

CSF 8, Auxiliary Emergency Systems: Provide equipment cooling (closed cooling &

ventilation), and other support requirements to accomplish the other Critical Safety Functions. Provide Instrument Air for operation of EFW, ADVs, RCP Support Systems and some containment isolation valves. A loss of the 1 D 4Kv bus will cause Train A of all emergency cooling support systems (Control Building cooling, Nuclear Services Closed Cooling Water cooling, Intermediate Closed Cooling water cooling, River Water Systems, Equipment ventilation, etc.) to be unavailable. Train B is unaffected.

CSF 9, Fire Protection & Remote Shutdown Capability: Maintain means to prevent, detect, and suppress fires, as well as the capability to perform a plant shutdown without access to the Control Room. A loss of the 1 D 4Kv bus will cause the Relay Room Cardox and Screen House detection systems to be inoperable. Fire watches will be initiated.

The operators will diagnose a Loss of the 1 D 4Kv Bus based on a loss of running equipment powered from the 1 D 4Kv bus (Secondary Closed Cooling Water Pumps, Secondary River Water Pumps, Intermediate Closed Cooling Water Pumps, etc.), LO-P-6 starting, and half of the Control Room lighting out.

Scenario Event Description NRC Scenario 2 The CRS will enter OP-TM-AOP-013, LOSS OF 1D 4160V BUS. The ARO will place the Control Switch for LO-P-6 to Pull-To-Lock to minimize loading on the Battery. The CRS will evaluate and declare Tech Spec 3.7.2.f:

T.S. 3.7.2- The reactor shall not remain critical unless all of the following requirements are satisfied:

o 3.7.2.f- The Engineered Safeguards bus, switchgear, load shedding, and automatic diesel start systems shall be operable except as provided in Specification 3.7.2.c above and as required for testing.

Once LO-P-6 is in Pull-To-Lock and the Tech Spec has been declared, then the scenario can continue.

Event #7: The lead examiner will cue the Loss of Stator Coolant Pumps, causing a lack of Main Generator Stator Cooling.

The crew will diagnose a Loss of Stator Cooling Pumps by Main Annunciators L-2-7, GEN STATOR STBY CLG PUMP RUN, and Main Annunciator L-1-7, GEN STATOR CLG LOSS RUNBACK, in alarm, and no operating Stator Coolant Pump indications on PCL.

The crew will enter OP-TM-MAP-L0107 and OP-TM-MAP-L0207. The ARO will attempt to start the standby pump from PCL and will identify that it will not start. The crew will identify that the Turbine Control Valves are not closing as expected and, if the condition continues for more than 3.5 minutes, that the Main Turbine did not automatically trip.

lAW OP-TM-MAP-L0107:

o Automatic Actions:

Turbine Control Valves close at 23.4% vmo/min.

Turbine trips after 2 minute time delay should turbine not runback to approximately 95% power.

Turbine trips after 3.5 minute time delay should turbine not runback to approximately 29.6% power.

The CRS will enter OP-TM-EOP-001, Reactor Trip. The URO will trip the reactor (CT-18). The Main Turbine will fail to automatically trip and the URO will trip it manually. The ARO will adjust Main Feedwater flow to avoid an overcooling event.

Once the Reactor and Main Turbine have been tripped and a symptom check has been performed, then the scenario can continue.

Event #8: The lead examiner will cue the Loss of Offsite Power.

The crew will diagnose a Loss of Offsite Power by the Control Room lighting going dark for 10 seconds, followed by half of the lights returning once the B Emergency Diesel Generator powers the 1E 4Kv bus, as well as several alarms indicating a loss of the 4 bus and 8 bus, and a loss of seal injection and letdown. The CRS will direct entry into OP-TM-AOP-020, Loss of Station Power.

Scenario Event Description NRC Scenario 2 OP-TM-AOP-020 addresses two types of Loss of Station Power events. (1) Loss of Offsite Power with one or both diesels supplying the ES 4160V busses and (2) a loss of offsite power with no diesels supplying the ES 4160V busses.

If one or both diesels are supplying the ES busses, the procedure walks the operators through ensuring RCS cooling and RCP seal cooling is established.

As long as one diesel is available, the reactor can be stabilized and the operators can methodically walk through powering additional busses and starting additional equipment.

The ARO will establish Natural Circulation by feeding the OTSG's lAW Rule 4 (CT-12) and verify that Natural Circulation exists lAW Guide 10, Natural Circulation.

lAW Guide 10:

o Natural Circulation exists when the following conditions exist:

RCS differential temperature develops and stabilizes <50F.

Thot < 600F.

lncore temperatures stabilize and track Thot indications.

Tcold reflects OTSG saturation temperature for the existing OTSG pressure.

Primary to Secondary heat transfer is demonstrated by steaming or feeding OTSGs.

Adequate SCM exists.

Once Natural Circulation has been established, then the scenario can continue.

Event #9: The lead examiner will cue the Loss of EG-Y-1 B.

The crew will diagnose a Loss of Offsite Power by the Control Room lighting going dark as well as several alarms indicating a loss of EG-Y-1B. The CRS will direct entry into OP-TM-AOP-020, Loss of Station Power, Section 4.0, Station Blackout.

OP-TM-AOP-020 addresses two types of Loss of Station Power events. (1) Loss of Offsite Power with one or both diesels supplying the ES 4160V busses and (2) a loss of offsite power with no diesels supplying the ES 4160V busses.

In a Station Blackout (no power to either 4160V ES bus), immediate attempts are made to energize the ES busses. Actions are taken to prevent inventory loss, including protecting the RCP seals. The operators take action to minimize DC loads to maximize station battery life.

The URO will place Intermediate Closed Cooling Water Pumps in Pull-To-Lock and ensure that RCP Seal Return and Seal Injection Valves are closed (CT-3).

The scenario can be terminated when the Main Turbine has been tripped, Natural Circulation has been established, Intermediate Closed Cooling Water Pumps have been placed in Pull-To-Lock, and RCP Seal Return and Seal Injection lines have been isolated.

Scenario Event Description NRC Scenario 2 B&W Unit EOP Critical Task Description Document, 47-1229003-04:

CT Isolate Possible RCS Leak Paths- All isolable leaks should be isolated, if possible. There are several possible leaks in the RCS which may be isolated by closing certain valves. These may include:

PORV and PORV Block Valve.

Pressurizer Spray Valve and Spray Block Valve

Pressurizer Vent Valves.

Pressurizer Sample Valves.

Hot Leg High Point Vent Valves.

Reactor Vessel Head Vent Valves.

Station Blackout procedures include provisions for minimizing primary inventory losses, including:

Isolating all Letdown flows.

Closing Seal Return Valves.

Isolating other known leak paths.

Protecting against RCP Seal LOCA outside of the following limits should be considered grounds for failure of the critical task:

Isolating Seal Return Lines while any Reactor Coolant Pump #1 seal inlet temperature > 235°F.

Isolating Intermediate Closed Cooling Water System while any Reactor Coolant Pump #1 seal inlet temperature > 235°F.

Safety Significance: Elevated RCP seal temperatures will result in increased seal leakage of approximately 21 gpm I pump. To avoid seal damage and excessive seal leakage, do not restore RCP seal injection.

To avoid water hammer, thermal barrier cooler damage, and RCS leakage to the ICCW system, do not restore RCP thermal barrier cooling.

Either Seal Injection restoration or Intermediate Closed Cooling Water restoration would lead to a reduction of RCS inventory.

Cues:

1. Computer indication for RCP #1 Seal Inlet Temperature Performance Indicators:

1. Operation of associated RCP Seal Valve controls.

2. Operation of associated RCP Seal Pump controls.

Feedback:

1. Indications of Valve status indications associated with RCP Seals.

2. Indications of Pump status indications associated with RCP Seals.

Scenario Event Description NRC Scenario 2 B&W Unit EOP Critical Task Description Document, 47-1229003-04:

CT Establish Natural Circulation RC Flow- Whenever forced RC flow is not available, NC flow should be established. Maintaining primary to secondary heat transfer via NC eliminates the need to add RC to the RB as would occur with the back up feed and bleed HPI core cooling mode.

o If primary to secondary heat transfer has been lost, then establish and maintain appropriate SG levels in accordance with Rule 4.0.

o Reduce SG pressure using the TBVs/ADVs to establish a positive primary to secondary side ~T of- 50°F.

o RCS pressure should be maintained constant or slightly increasing using MU or HPI. RCS pressure should not be increased if PTS guidance is invoked.

Trying to establish Natural Circulation RC flow outside of the following limits should be considered grounds for failure of the critical task:

Establish Emergency Feedwater flow lAW Rule 4 to each OTSG (less than 515 gpm total), with a target band of 50-85% in the Operating Range.

Establish Natural Circulation prior to transitioning into OP-TM-EOP-009, HPI Cooling.

Safety Significance: Enhances the transient mitigation capability of the plant by maintaining SGs operable and eliminates the need to add RC to the RB as with HPI Cooling.

Cues:

Low RC flow alarm

Verbal alert by plant staff that all RCPs have tripped

SCM monitor and associated alarms

P-T display and associated alarms Performance Indicators:

Operation of EFW/FW pump and valve controls

Operation of TBV/ADV controls

Operation of MU/HPI pump and valve controls Feedback:

Verbal verification that natural circulation has been established

SG pressure

RC temperature Scenario Event Description NRC Scenario 2 B&W Unit EOP Critical Task Description Document, 47-1229003-04:

CT Turbine Trip- Whenever conditions exist such that a reactor trip is required, then the normally redundant actions of tripping the reactor and main turbine should be accomplished immediately. Tripping the main turbine provides assurance of a redundant trip signal to the main turbine electro-hydraulic control unit.

Due to Excessive Heat Transfer concerns, tripping the Main Turbine outside of the following limit should be considered grounds for failure of the critical task:

Trip the Main Turbine to ensure that it does not cause a continuous excessive cooldown rate or Tcold to be less than 329°F.

Once the reactor is shutdown, prompt isolation of the turbine steam flow path is significant. Until the major steam flow path through the turbine to the condenser is isolated, RCS heat removal will be much larger than heat generation, and a rapid RCS cooldown will continue. (Source: OP-TM-EOP-0011)

Safety Significance: When the reactor is tripped (shutdown), steam flow to the main turbine must be stopped in order to maintain the appropriate primary to secondary heat balance. When the appropriate primary to secondary heat balance is established, the normal heat removal systems are available for plant control thus enhancing the transient mitigation capability of the plant. If the turbine steam flow path is not isolated after a rapid reduction in reactor heat generation (reactor trip), extremely rapid RCS cooldown is possible. Prompt operator action can minimize the extent of this overcooling and potential consequences to RCS pressure boundary. A prolonged rapid cooldown will complicate plant control and could challenge OTSG tube integrity or Reactor Vessel integrity.

Cues:

Visual indications {closed generator output and exciter breakers, main turbine stop and control valves are not closed)

P-T display and associated alarms

Verbal alert by plant staff that all main turbine stop and control valves are not closed immediately following actuation of a reactor trip signal

Verbal alert by plant staff that main alternator output/exciter breakers are not open immediately following actuation of a reactor trip signal Performance Indicators:

Operation of control room manual main turbine trip pushbutton

Main turbine trip alarm

Main turbine-generator exciter alarms

Main turbine-generator breaker status alarms Feedback:

RC temperature and pressure

SG level and pressure

Mega-Watt electric indication

Main turbine-generator breaker status indications

Verbal notification by plant staff of main turbine trip status Scenario Event Description NRC Scenario 2 Event Description Procedure Support Initial Set-up. 100% Power, MOL SBO Tagged OOS due to maintenance 1 BWST level lowers OP-TM-MAP-E0204, BWST Level Lo Tech Spec 3.3.1.1 a 2 lsolable Steam Leak in Turbine Building OP-TM-AOP-051 3 SGIRX Demand Station fails to OP-TM-AOP-070, Primary to Secondary Heat Zero Volts Transfer Upset 4 High Vibrations on Main OP-TM-MAP-K0201, MN TURB VIBRIECC HI Turbine 11 02-4, Power Operations 5 Inadvertent 1600# ESAS OP-TM-AOP-046, Inadvertent ESAS Actuation Tech Spec 3.5.1.1 6 Loss of 1D 4Kv Bus OP-TM-AOP-013, Loss of 1D 4Kv Bus T.S. 3.7.2.f OP-TM-861-901, Diesel Generator EG-Y -1 A Emergency Operations OP-TM-541-444, Swap NS-P-1 B to Alternate Power Supply 7 Generator Stator Cooling OP-TM-MAP-L01 07, Gen Stator Clg Loss Run back Runback I Reactor Trip OP-TM-EOP-001, Reactor Trip OP-TM-EOP-010, Emergency Procedure Rules, Guides and Graphs 8 Loss of Off-Site Power OP-TM-AOP-020, Loss of Station Power OP-TM-861-902, Diesel Generator EG-Y-1A Emergency Operations OP-TM-AOP-041, Loss of Seal Injection 9 EG-Y-1 B Trips I Electrical OP-TM-AOP-020, Loss of Station Power Blackout OP-TM-AOP-041, Loss of Seal Injection OP-TM-EOP-01 0, Emergency Procedure Rules, Guides and Graphs Scenario Set-up Cert Scenario 3 ACTION COMMENTS I INSTRUCTIONS DESCRIPTION Initialization IC-242 100% HFP ICS full AUTO Equilibrium XENON MOL Remote DHR32 Value: 85.5 Ramp 15 Seconds BWST Level Lowers When: EVENT 1 Malfunction MS19A Value: 1 Steam Line Break in the When: EVENT 2 Turbine Building Malfunction IC23 Value: Insert SIG RX Demand Fails to 0 When: EVENT 3 volts Malfunction TU01D Value: 50 Ramp 30 Seconds Turbine Bearing 4 High When: EVENT 4 Vibrations Override OSA4S66 Value: ON 1600# Manual ESAS SDIPB1RCA When: EVENT 5 Pushbutton Malfunction ED05D Value: Insert 1D 4160V Bus Fault When: EVENT 6 Malfunction EG04A Value: Insert "A" Stator Cooling Pump Trip When: EVENT 7 Malfunction EG04B Value: Insert "B" Stator Cooling Pump Trip When: EVENT 7 Malfunction TC09A Value: Insert Turbine Control Valve 1 When: EVENT 7 Failure Malfunction TC09B Value: Insert Turbine Control Valve 2 When: EVENT 7 Failure Malfunction TC09C Value: Insert Turbine Control Valve 3 When: EVENT 7 Failure Malfunction TC09D Value: Insert Turbine Control Valve 4 When: EVENT 7 Failure Malfunction ED01 Value: Insert Loss of Off-Site Power When: EVENT 8 Malfunction EG07B Value: Insert EG-Y-1 B trips When: EVENT 9 Remote MUR12 Value: OPEN MU-V-76A I B Open When: EVENT 20 Appendix D Operator Action Form ES-D-2 Op Test No.:

Event

Description:

Scenario #

- 2 BWST Level Lowers Event # ......;.._ _ _ _ Page 14 of _4.;..;;;2--1 Time I Position I Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Lead Examiner INITIATE EVENT 1.

Indications Available: Main Annunciator E-3-4 in alarm, BWST digital indicators (LI-808-AIB) lower until approximately 54', PPC Points A0486 and A0487 lower until approximately 54'.

Diagnoses a lowering of BWST level and stabilizing at Crew approximately 54'.

Directs entry into OP-TM-MAP-E0304, BWST TEMP/LVL CAS HI/LO.

Booth Cue: If directed, as an Auxiliary Operator and/or Maintenance, to investigate the BWST level lowering, report that "The crane working near the BWST has swung its' load into the BWST and pierced it. There is no visual indication of further water coming out of the hole in the BWST".

OP-TM-MAP-E0304, BWST TEMP/LVL HI/LO Step 4.1.1: Determines that console and computer level ARO indications are accurate. (A0486 and (A0487)

Step 4.1.5: Determines that BWST level indication is less than CAS 56.0 ft and Reactor is not shutdown, and declares entry into TS 3.3.1.1.a. {1 hour).

Examiner's Note: T.S. 3.3.1.1.a: The Borated Water Storage Tank (BWST) shall contain a minimum of 350,000 gallons of water having a minimum concentration of 2,500 ppm boron at a temperature not less than 40°F. If the boron concentration or water temperature is not within limits, restore the BWST to OPERABLE within 8 hrs. If the BWST volume is not within limits, restore the BWST to OPERABLE within one hour.

Specification 3.0.1 applies.

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

-- Scenario # 2 Event # .....;...._ _ _ _ Page 15 of _4.;.;;2;..._-11 Event

Description:

BWST Level Lowers Time I Position I A_pplicant's Actions or Behavior CAS Briefs a Reactor Shutdown lAW 1102-4, Power Operations Examiner's Note: The crew may decide to commence with the power reduction lAW 1102-4. The steps are listed in the next Event since they are required to be performed there.

Examiner's Note: Once the Tech Spec is called, Go to Event 2.

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

-- Scenario # 2 Event # 2

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Page 16 of 42

-~

Event

Description:

lsolable Steam Leak in the Turbine Building Time I Position L Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Lead Examiner INITIATE EVENT 2.

Indications Available: Lowering Generated MWe, Lowering Tave, Reactor Power rising Booth Cue: Report, as Auxiliary Operator, "There is a large steam leak on the North Side of the Turbine Building. Specific location is unknown.

Crew Diagnoses the steam leak Announces entry into OP_ TM-AOP-051, Secondary Side High CRS Energy Leak.

OP-TM-AOP-051, Secondary Side High Energy Leak Step 3.1: ANNOUNCE entry into OP-TM-AOP-051, ARO "Secondary Side High Energy Leak" and to evacuate affected area over the plant page and radio.

URO Step 3.2: MAINTAIN reactor power< 100%.

Examiner's Note: Steps 3.3 through 3.5 are N/A CRS Step 3.6: REQUEST SM to evaluate EALs.

Examiner's Note: Steps 3.7 and 3.8 are N/A CRS Step 3.9: If leak is in Turbine Building, then GO TO Section 6.0 Appendix D Operator Action Form ES-D-2 Op Test No.:

-- Scenario # 2 Event # ...;2~---- Page 17 of _4;.;;;.2--11 Event

Description:

lsolable Steam Leak in the Turbine Building Time I Position J Applicant's Actions or Behavior SECTION 6.0, TURBINE BUILDING Step 6.1: CONSIDER evacuating the following:

CAS

Operations Office Building using the back stairwell.

Telephone Equipment Room in the Service Building .

Examiner's Note: The crew can perform isolation of A or B side of the Turbine Bldg Booth Cue: When requested by the Control Room to report the status of the steam leak following closure of MS-V-5A, report "The steam leak IS NOT isolated.

When requested by the Control Room to report the status of the steam leak following closure of MS-V-5B, report "The steam leak IS isolated".

Step 6.3: If power >40% or FW-P-1 B is tripped, then determine if leak is downstream of MS-V-5B by performing the following:

ARO

CLOSE MS-V-5B

If steam leak is isolated, then GO TO Section 7.0

OPEN MS-V-5B SECTION 7.0, RETURN TO NORMAL Step 7.1: If MS-V-1C and MS-V-10 are Closed, then perform the following:

NIA

Ensure Aux Boilers are operating lAW OP-TM-414-401 I 402, Starting AS-B-1 A I 1B

ENSURE Gland Seal System in Plant Shutdown Mode lAW OP-TM-314-000, Gland Seal System.

Footnotes: 1- FW-P-1A: Feedwater Pump 1A 2- MS-V-5B: Main Steam Supply to "B" Main Feed Pump Turbine 3- MS-V-1CI1D: Main Steam Isolation of "B" OTSG "C" I "D" Line 4- AS-B-1A/1 B: 1A/1 B Auxiliary Boilers Appendix D Operator Action Form ES-D-2 Op Test No.: _.....;__ Scenario # 2 Event # _.2~---- Page 18 of _4;.;;;.2--ll Event

Description:

lsolable Steam Leak in the Turbine Building Time I Position I Applicant's Actions or Behavior Step 7.2: EVALUATE T.S. implications of valves closed to CRS isolate the leak.

Step 7.3: ENSURE clearance or EST are applied to valves CRS manipulated to isolate the leak.

Step 7.4: REVIEW transient cycle logbook and LOG cycles as ARO required Step 7.5: ENSURE only one of the following is running:

ARO

AH-E-24A

AH-E-248 Examiner's Note: Once the leak is isolated and plant is stable, GO TO Event 3 IFootnotes: 1 - AH-E-24A I 248: Emergency Feed Pumps Cooling Fans Appendix D Operator Action Form ES-D-2 Op Test No.:

Event

Description:

Scenario # 2 Event # _3;;;_____ Page SG/RX Demand Station Fails to 0 Volts 19 of _4;.;;;.2----ll Time I Position I Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Lead Examiner INITIATE EVENT 3.

Indications Available: Power reduces quickly, Main Annunciators H-2-1, H-1-4, and H-3-2 in alarm, RCS Pressure reduces.

Crew Diagnoses an ICS transient.

DIRECTS entry into OP-TM-AOP-070, PRIMARY TO CRS SECONDARY HEAT TRANSFER UPSET OP-TM-AOP-070, PRIMARY TO SECONDARY HEAT TRANSFER UPSET Step 2.1 (IMA): ENSURE diamond station in MAN and INSERT control rods as necessary to reduce power URO below Reactor power limit and for gross balance with total FW flow.

Step 2.2 (IMA): ENSURE both SG A & B FW DEMAND in ARO HAND and ADJUST FW Flow to stabilize Tavg at the current RCS temperature.

Step 2.3 (IMA): VERIFY Turbine Header Pressure is between URO 835 and 935 _psig_. (MAP H-2-3 is not in alarm)

Step 2 . 4 (IMA): VERIFY RCS pressure is lowering or less than 2205 psig.

As required, if RCS Pressure is >2205 psig, URO places RC-V-URO 1 control in Manual (CC), opens RC-V-1 fully by pressing the open pushbutton and observing the red open light lit and the green closed light not lit (CC), and then places RC-V-1 control back to AUTO.

I Footnotes: 1 - RC-V-1: Pressurizer Spray Valve Appendix D Operator Action Form ES-D-2 Op Test No.:

Event

Description:

Scenario #

-2 Event # _3;......_ _ _ _ Page SG/RX Demand Station Fails to 0 Volts 20 of _4;..;;;.2---11 Time I Position I Applicant's Actions or Behavior Examiner's Note: OP-TM-AOP-070, Steps 3.1 and 3.2 are IAAT's that should not be applicable during this Event.

CRS Step 3.3: VERIFY Main Turbine is RESET Step 3.4: Assigns manual control responsibilities and control CRS bands as follows:

INSERT or WITHDRAW rods to maintain Reactor power within URO 1% of current power level by operating the Control Rod switch on the Diamond Panel as applicable (CC).

Adjust FW Flow to maintain Tavg within 2 °F of current temperature by adjusting SG A and SG B FW Demand Station toggle switches as applicable (CC).

ARO Maintain Turbine Hdr Pressure within 10 psig of current pressure by adjusting Turbine Load Set Station demand as applicable (CC).

Step 3.6: ENSURE the following ICS stations are in HAND.

SG/Reactor Demand URO

Reactor Demand

SG AlB Load Ratio

ULD Step 3.7: VERIFY both of the following:

CRS

Operating MFW Pumps are controlling FW Valve dP greater than 30 psid.

Reactor power is greater than 75% .

Examiner's Note: OP-TM-AOP-070, Step 3.8 is N/A and 3.9 has already been verified.

I Footnote: 1 - ULD: Unit Load Demand Appendix D Operator Action Form ES-D-2 Op Test No.:

Event

Description:

Scenario # 2 Event # 3

~--------

Page 21 of 42

--~

SG/RX Demand Station Fails to 0 Volts Time I Position I Applicant's Actions or Behavior Step 3.10: MAINTAIN RCS pressure between 2105 and 2205 ARO psig and slowly ADJUST feedwater flow to control RCS Tavg 578 to 580°F.

Step 3.11: MAINTAIN RCS Tavg 578 to 580°F and slowly ARO ADJUST loop feedwater flows to control RCS f1Tc <5° F.

Examiner's Note: OP-TM-AOP-070, Steps 3.12 and 3.13 are N/A.

Examiner's Note: Once the Plant has been stabilized, GO TO Event 4.

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

-- Scenario # 2 Event # _4......__ _ _ _ Page 22 of _4;..;;;.2~

Event

Description:

High Vibrations on Main Turbine Time J Position I Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Lead Examiner INITIATE EVENT 4.

Indications Available: Main Annunciator K-2-1 in alarm, Multiple PPC alarms.

Crew Diagnosis High Vibrations on Main Turbine.

CAS Directs entry into OP-TM-MAP-K0201, MN TURB VIBR/ECC HI Booth Cue: If contacted as Electrical Maintenance and/or the Maintenance Director, acknowledge directions.

OP-TM-MAP-K0201, MN TURB VIBRIECC HI Step 4.2: Determines that the unit is at power and vibrations ARO are > 6 Mils, and notifies Electrical Maintenance and the Maintenance Director.

Step 4.3: Determines that the unit is at power, and directs the CAS URO to reduce load to s 45 percent.

Examiner's Note: OP-TM-MAP-K0201, Steps 4.3-4.9 are N/A.

11 02-4, Power Operations Step 3.3.2.A.1: PERFORM Enclosure 2A (for an emergency CAS (forced) power reduction INITATE Enclosure 2A).

Step 3.3.2.A.2.a: If power change is greater than 10 MWe, then NOTIFY the following:

CAS

Power Team

TSO

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

Event

Description:

Scenario #

- 2 Event #

High Vibrations on Main Turbine

_4_ _ _ _ _ Page 23 of _4_2~

1 Time I Position I Applicant's Actions or Behavior Step 3.3.2.A.3.c: If SG/REACTOR DEMAND is in HAND, then CRS REDUCE reactor power lAW OP-TM-621-471 "ICS Manual Control".

OP-TM-621-471, ICS Manual Control Step 4.6.3: If necessary to maintain reactor power or control URO rods within limits or if a power change is being conducted lAW 1102-4, then INSERT or WITHDRAW control rods.

OP-TM-AOP-070, PRIMARY TO SECONDARY HEAT TRANSFER UPSET Step 3.10 and 3.11: Maintains RCS pressure between 2105 and 2205 psig, controls RCS Tavg 578 to 580 °F, and controls ARO RCS ~Tc <5° F by adjusting SG A and SG B FW Demand Station toggle switches as applicable.

Examiner's Note: Once sufficient reactivity manipulation is observed and RCS pressure is low in the band, Go to Event 5.

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

~--

Scenario #

2 Event # _s...______ Page 24 of _4;.;;;.2--1 Event

Description:

Inadvertent 1600# ESAS Actuation Time I Position I A_Qplicant's Actions or Behavior BOOTH OPERATOR: When directed by the Lead Examiner INITIATE EVENT 5.

Indications Available: Multiple Main Annunciator Panel Alarms illuminated, MU-P-1A running, ES positions indicated on PCR for "A" Train components.

Crew Diagnoses an lnadvertant ES Actuation, "A Train 1600#.

Direct entry into OP-TM-AOP-046, lnadvertant ESAS CAS Actuation.

OP-TM-AOP-046, lnadvertant ESAS Actuation Step 2.1 (IMA): Defeats invalid ESAS signals by pressing "Defeat I Enable" pushbuttons for each of three channels, UROIARO verifying that the amber "Defeat" light is lit for each channel and the blue Block load lights are not lit for each channel (PCR).

Step 2.2 (IMA): Determines that MU-P-1A is not required for seal injection and secures it by rotating the Control Switch in URO the counter-clockwise direction and verifying the green flag indicator is visible, and that the green Off light is lit and the red Running light is not lit.

Examiner's Note: Once MU-P-1A is secured, MU-V-16A and MU-V-168 will have flow based on MU-P-1 8 operating.

Step 2.3 (IMA): Throttles MU-V-16A I 168 with HPI flow to URO maintain MU-P-1 B flow> 115 gpm.

Step 3.1: Announces entry into OP-TM-AOP-046, "Inadvertent ARO ESAS Actuation" over the plant page and radio.

Footnotes: 1 - MU-P-1 A: Makeup Pump 1A 2- MU-V-16A: "A" High Pressure Injection Control Valve 3- MU-V-168: "B" High Pressure Injection Control Valve Appendix D Operator Action Form ES-D-2 Op Test No.: .......__ Scenario # -2 Event # _5;.......____ Page 25 of _4;..;;;..2---1 Event

Description:

Inadvertent 1600# ESAS Actuation Time I Position 1 Applicant's Actions or Behavior Step 3.3: Ensures MU-V-36 is Open by pressing the open pushbutton and verifying the red open light is lit and the green URO closed light is not lit (CC). MU-V-37 is already open, evidenced by red open light lit and green closed light not lit (CC}.

Examiner's Note: Steps 3.4 through 3.8 are N/A Step 3.9: If Mu-V-77A & 778 are OPEN, then perform the following:

URO

ENSURE MU-V-16A is Closed

ENSURE MU-V-168 is Closed Examiner's Note: Steps 3.10 and 3.11 are N/A Step 3.12: Ensures MU-V-14A is Closed by pressing the close pushbutton and verifying the green closed light is lit and the red URO open light is not lit (CC). MU-V-148 is already closed, evidenced by green closed light lit and red open light not lit (CC).

Examiner's Note: Step 3.13 is N/A Step 3.14: If at power, then ENSURE two Secondary River ARO pumps are running.

Footnotes: 1- MU-V-36: Makeup Pump Recirc Valve 2- MU-V-37: Makeup Pump Recirc Valve 3- MU-V-77A: MU-P-1N8 Discharge Header Cross-Connect Valve 4- MU-V-778: MU-P-1N8 Discharge Header Cross-Connect Valve 5- MU-V-16A: "A" High Pressure Injection Control Valve 6- MU-V-168: 8" High Pressure Injection Control Valve 7- MU-V-14A: Makeup Pump Suction Valve from 8WST 8- MU-V-148: Makeup Pump Suction Valve from 8WST Appendix D Operator Action Form ES-D-2 Op Test No.:

Event

Description:

Scenario # 2 Event #

Inadvertent 1600# ESAS Actuation 5

~--------

Page 26 of 42

~

Time II Position II Applicant's Actions or Behavior ARO Step 3.15: INITIATE an alarm review.

Step 3.16: Initiates OP-TM-211-950, "Restoration of Letdown ARO Flow."

CAS Step 3.18: REVIEW Tech Specs for ES operability impact.

OP-TM-211-950, Restoration of Letdown Flow Section 3.0: Reviews Precautions, Limitations, and ARO Prerequisites.

Booth Cue: If contacted to verify integrity of Letdown Line, state " The integrity of the Letdown Line to MU-T-1 has been assessed and the Letdown line is intact".

Examiner's Note: Steps 4.1 through 4.4 are N/A.

Step 4.5: Ensures:

MU-V-3 is closed by observing green closed light lit, red open light not lit.

ARO

MU-V-4 is closed by pressing the green closed light, observing green closed light lit, red open light not lit.

MU-V-5 is closed by pressing the Control Station toggle switch in the downward direction, observing the carrot position indicator is pointing to zero.

Step 4.7: Verifies MU-V-1A and MU-V-1 Bare Open by the ARO indicating lights for each being red (not green) (CC)

Footnotes: 1- MU-V-3: RCS Letdown Reactor Bldg Isolation Valve 2- MU-V-4: Letdown Orifice Isolation Valve 3- MU-V-5: Letdown Flow Control Bypass 4- MU-V-1A: "A" Letdown Cooler Inlet Isolation Valve 5- MU-V-1 B: "B" Letdown Cooler Inlet Isolation Valve Appendix D Operator Action Form ES-D-2 Op Test No.: _;....._ Scenario # 2 Event # 5 Page 27 of 42

~-------- -=~

Event

Description:

Inadvertent 1600# ESAS Actuation Time ~ Position I Applicant's Actions or Behavior Step 4.8.2: Verifies MU-V-2A and MU-V-2B are Open by the ARO indicating lights for each being red (not green) (CC)

Step 4.9.2: Throttles MU-V-5 to 10% open by operating the ARO dial on the MU-V-5 Control Station to the 10 position.

Step 4.10: Verifies MU-V-8 is aligned to the Thru position by ARO the indication Thru to filters lit and Bleed indication not lit (CC}

Step 4.11: Opens MU-V-3 by pressing the open pushbutton ARO and observing the red open light lit and the green closed light not lit (CC)

Step 4.14: Raises letdown flow at < 2.5 gpm/min to desired ARO flow by operating the dial on the MU-V-5 Control Station in the clockwise direction to o_p_en MU-V-5 gradually.

CRS Declares a 3.5.1.1 (72 Hours) Tech Spec LCO time clock.

Footnotes: 1- MU-V-3: ReS Letdown Reactor Bldg Isolation Valve 2- MU-V-5: Letdown Flow Control Bypass Valve 3- MU-V-2A: "A" Letdown Cooler Outlet Valve 4- MU-V-28: "B" Letdown Cooler Outlet Valve 5- MU-V-8: Letdown Split Valve to MU-T-1 or RCBT 6- MU-T-1: Makeup Tank 7 -RCBT: Reactor Coolant Bleed Tank Appendix D Operator Action Form ES-D-2 Op Test No.:

Event

Description:

Scenario # 2 Event #

Inadvertent 1600# ESAS Actuation

_5....__ _ _ _ Page 28 of _4.;.;;.2---<<

Time I Position I Applicant's Actions or Behavior Examiner's Note: Tech Spec 3.5.1.1 The reactor shall not be in a startup mode or in a critical state unless the requirements of Table 3.5-1, Column "A" and "B" are met, except as provided in Table 3.5-1, Column "C". Specification 3.0.1 applies.

TABLE 3.5-1 INSTRUMENTS OPERATING CONDITIONS C. Engineered Safety Features (C)

Operational (A) (B)

Action if Functional Minimum Minimum Conditions of Unit Operable Degree of Column A Channels Redundancy and B Cannot Be Met Engineered Safety Features: 2 N/A (g) 1.c: Manual Pushbutton (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 .

2 If both manual actuation switches for that feature are inoperable, then place the reactor in HOT SHUTDOWN in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

I Examiner's Note: Once Letdown has been restored, Go to Event 6.

Appendix D Operator Action Form ES-D-2 Op Test No.: ......;....._ Scenario # 2 Event # _6...___ _ _ _ Page 29 of _4=2---t Event

Description:

Loss of 1D 4160VAC Bus Time I Position I Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Lead Examiner INITIATE EVENT 6.

Indications Available: Equipment lost, PPC alarms, MAP alarms, Y2 of Control Room lighting going out, EG-Y-1A running, 10 4Kv Over-current alarms.

BOOTH Cue: The crew may contact an NLO and/or maintenance to investigate 1 D 4KV bus. If so, no response will be given (delay as necessary).

URO Diagnoses the loss of 1D 4Kv Bus.

CRS Directs entry into OP-TM-AOP-013, Loss of 1D 4Kv Bus.

OP-TM-AOP-013, Loss of 1 D 4Kv Bus.

Determines the entry conditions are met based on:

All of the following:

CRS

1D 4160V bus is deenergized or recovered by EG-Y -1 A

At least one auxiliary transformer is energized

The OTSGs are being used for RCS heat removal OP-TM-AOP-013, Loss of 1 D 4Kv Bus, Section 3.0 Step 3.1: Announce entry into OP-TM-AOP-013, "Loss of 1D ARO 4160V Bus" over the "RED" plant page and radio.

Step 3.2: Initiate OP-TM-861-901, "Diesel Generator EG-Y -1 A ARO Emergency Operations".

URO Step 3.3: Verify seal injection flow >22 gpm.

I Footnote: 1- EG-Y-1A: "A" Emergency Diesel Generator Appendix D Operator Action Form ES-D-2 Op Test No.: ...;..._ Scenario # 2 Event # _6..__ _ _ _ Page 30 of _4=2--t Event

Description:

Loss of 1D 4160VAC Bus Time I Position I Applicant's Actions or Behavior Examiner's Note: Steps 3.4 through 3.6 are N/A URO Step 3.7: ENSURE IC-P-1 8 is operating.

ARO Step 3.8: ENSURE NS-P-1C is operating.

Examiner's Cue: If the crew initiates OP-TM-541-444, it may be performed but is not required to continue in the scenario.

Step 3.9: INITIATE OP-TM-541-444 "Swap NS-P-1 B to ARO alternate power supply".

Step 3.10: ENSURE the following NR pumps operating as required for NS or IC temperature control:

ARO

NR-P-18-T,

NR-P-1C .

Step 3.12: ENSURE the following SC pumps operating:

ARO

SC-P-1A,

SC-P-1 B.

Step 3.13: ENSURE the following SR pumps are operating:

ARO

SR-P-1 8,

SR-P-1C .

Footnotes: 1 - IC-P-1 8: "B" Intermediate Closed Cooling Water Pump 2- NS-P-18: "B" Nuclear Service Closed Cooling Water Pump 3- NS-P-1C: "C" Nuclear Service Closed Cooling Water Pump 4- NR-P-1 8: "B Nuclear Service River Water Pump 5- NR-P-1C: "C" Nuclear Service River Water Pump 6- SC-P-1A: "A" Secondary Service Closed Cooling Water Pump 7- SC-P-18: "B" Secondary Service Closed Cooling Water Pump 8- SR-P-18: "8" Secondary Service River Water Pump 9- SR-P-1 C: "C" Secondary Service River Water Pump Appendix D Operator Action Form ES-D-2 Op Test No.:

Event

Description:

Scenario # 2 Event #

Loss of 1D 4160VAC Bus

_6;.__ _ _ _ Page 31 of _4;.;;;.2---il Time I Position I Ap~licant's Actions or Behavior ARO Step 3.14: INITIATE an alarm review.

Step 3.15: REQUEST SM evaluate Emergency Action Levels CRS (EALs).

Step 3.16: If the main turbine is "on line", then PLACE LOP-6 ARO in "PTL".

Examiner's Note: Tech Spec 3.7.2.f The engineered safeguards electrical bus, switchgear, load shedding, and automatic diesel start systems shall be operable Examiner's Note: After the Tech Spec call is made, go to Event 7.

I Footnote: 1 - LO-P-6: Main Turbine Emergency Bearing Oil Pump Appendix D Operator Action Form ES-D-2 Op Test No.:

-- Scenario # 2 Event# 7

~-------

Page 32 of 42

-=~

Event

Description:

Loss of Stator Coolant Pumps I Reactor Trip Time II Position I Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Lead Examiner INITIATE EVENT 7.

Indications Available: Stator Cooling Pump Trip, PPC alarms for Stator Temperatures, MAP alarms L-1-7 and L-2-7 actuated.

CREW Announce "Generator Stator Coolant Runback" ARO Identifies the trip of GN-P-5A, Stator Water Cooling Pump.

OP-TM-MAP-L-2-7, GEN STATOR STBY CLG PUMP RUN Step 4.0: Ensure standby pump started (pump indication lights ARO on PLF)

ARO Reports the standby Stator Water Cooling pump failed to start.

Examiner's Note: The following Automatic Actions would normally occur:

Turbine control valves Close at 23.4% vwo/min .

Turbine control trips to HAND on ICS station and ICS goes into track.

Turbine trips after 2 minute time delay should turbine not run back to average generator current <

25,474 amps (approx plant load of 95% power).

Turbine trips after 3.5 minute time delay should turbine not runback to average generator current<

9322 amps (approx plant load of 29.6% power).

However, the Turbine Control Valves DO NOT Close in this scenario.

MAP L-1-7, GEN STATOR CLG LOSS RUNBACK Step 4.1: IAAT Reactor power is > 45% and the Turbine trips, CRS then GO TO OP-TM-EOP-001, "Reactor Trip".

Step 4.2: IAAT Reactor power is < 45% and the Turbine trips, ARO then GO TO OP-TM-MAP-K01 01.

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

Event

Description:

-- Scenario # 2 Event # 7

~-------

Loss of Stator Coolant Pumps I Reactor Trip Page 33 of 42

--~

Time I Position I Applicant's Actions or Behavior CRS INITIATE 1102-4, Power Operations Examiner's Note: The ARO may report that Main Turbine Control Valves are not closing or based on ICS in Hand Control during a turbine run back and an upset of the Primary to Secondary parameters, the CRS may direct the Reactor and Main Turbine tripped.

ARO Reports Main Turbine Control valves are not closing.

Directs the URO to manually trip the Reactor and perform CRS IMA's of OP-TM-EOP-001, Reactor Trip.

OP-TM-EOP-001, Reactor Trip Step 2.1 (IMA): PRESS both Reactor Trip and DSS URO push buttons.

URO Step 2.2 (IMA): Verify Reactor Shutdown CT-18 URO Step 2.3 (IMA): PRESS Turbine Trip pushbutton.

URO Step 2.4 (IMA): VERIFY the turbine stop valves are Closed Step 3.1: Performs a Symptom Check and reports "Symptom URO Check is Negative".

Examiner's Note: After Symptom Check is performed, GO TO Event 8 Appendix D Operator Action Form ES-D-2 Op Test No.: _.;...._ Scenario # 2 Event # 8 Page 34 of 42

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

Event

Description:

Loss of Off-Site Power Time I Position I Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Lead Examiner INITIATE EVENT 8.

Indications Available: Control Room lights go out, Makeup Pump 1B trips, loss of Makeup, and Seal Injection flows.

CRS Diagnoses the loss of offsite power.

CRS Directs entry into OP-TM-AOP-020, Loss of Station Power.

OP-TM-AOP-020, Loss of Station Power ARO Step 3.1: INITIATE "Emergency Feedwater.

Step 3.2: INITIATE OP-TM-861-901, "EG-Y-1A Emergency ARO Operations" and OP-TM-861-902, "EG-Y-18 Emergency Operations".

Step 3.3: VERIFY 1D 4160Vand 1E 4160V bus are energized.

URO RNO: 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.

Step 3.4: VERIFY one of the following pumps operating:

URO

IC-P-1A

IC-P-1 8 Step 3.5: VERIFY seal injection flow> 22 gpm.

CRS RNO: INITIATE OP-TM-AOP-041, "Loss of Seal Injection".

Footnotes: 1 - EG-Y-1 A: "A" Emergency Diesel Generator 2 - EG-Y -1 8: "8" Emergency Diesel Generator 3 - EG-Y-4: Station Blackout Diesel Generator 4 -IC-P-1A: 1'A" Intermediate Closed Cooling Water Pump 5- IC-P-1 B: "B" Intermediate Closed Cooling Water Pump Appendix D Operator Action Form ES-D-2 Op Test No.:

-- Scenario #

-2 Event #

8 Page 35 of 42

--~

Event

Description:

Loss of Off-Site Power Time I Position I Ap~icant's Actions or Behavior Examiner's Note: Details of OP-TM-AOP-041 are on Page 37.

Step 3.6: REQUEST SM evaluate Emergency Action Levels CRS (EALs)

Step 3.7: Initiate OP-TM-EOP-010 Guide 10, Natural URO Circulation Examiner's Note: Specific details of Guide 10 are on Page 39.

Step 3.8: CONTACT system dispatcher to get an estimate for CRS when to expect offsite power restoration.

Step 3.9: IAAT Tcold < 525°F, then INITIATE Emergency URO boration ~er Rule 5.

Examiner's Note: Step 3.10 is N/A Step 3.11: INITIATE OP-TM-220-901 to transfer Grp 8 or 9 ARO pressurizer heaters to ES power.

Step 3.12: VERIFY LO-P-6 Emergency Bearing Oil Pump or ARO LO-P-5 Turning Gear Oil Pump is operating.

Examiner's Note: Step 3.13 requires no action.

Step 3.14: VERIFY GN-P-2 Emergency DC Seal Oil Pump is ARO operating.

Footnotes: 1 - LO-P-6: Main Turbine Emergency Bearing Oil Pump 2 - GN-P-2: Emer enc Seal Oil Pum Appendix D Operator Action Form ES-D-2 Op Test No.: ....;.._ Scenario # 2 Event # 8 Page 36 of 42

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

Event

Description:

Loss of Off-Site Power Time l Position I Applicant's Actions or Behavior Step 3.15: INITIATE action to break vacuum in the main and auxiliary condensers, and isolate Gland Steam by performing the following:

OPEN VA-V-8 ARO

OPEN VA-V-4A

OPEN VA-V-4B

PLACE all VA-P-1 s in PTL

PLACE all VA-P-2s in PTL

When condenser vacuum < 1Oin Hg vac then CLOSE MS-V-7 URO Step 3.16: INITIATE generator hydrogen vent to atmosphere.

Step 3.17: IAAT 1D 4160V bus cannot be energized then URO

INITIATE OP-TM-732-901, "Energize 1P 480V Bus using ES Bus Cross Tie".

INITIATE OP-TM-AOP-023 "A" DC System Failure .

Examiner's Note: Step 3.18 is N/A at this time.

ARO Step 3.19: START AH-E-24A or AH-E-24B Step 3.20: INITIATE 1104-19, "Control Building Ventilation ARO System" section "Emergency Operation After Station Blackouf'.

Footnotes: 1- VA-V-8: Main Condenser Vacuum Breaker Valve 2- VA-V-4A: "A" Aux Condenser Vacuum Breaker Valve 3- VA-V-4B: "B" Aux Condenser Vacuum Breaker Valve 4- VA-P-1's: Main Condenser Vacuum Pumps 5 - VA-P-2's: Aux Condenser Vacuum Pumps 6- MS-V-7: Main Steam to Gland Steam System Isolation Valve 7 - AH-E-24A : "A" Emergency Feed Pump Air Handling Fan 8 - AH-E-24B: "B" Emergency Feed Pump Air Handling Fan Appendix D Operator Action Form ES-D-2 Op Test No.: __,;,.._ Scenario # 2 Event # _8=------- Page 37 of _4_2---t Event

Description:

Loss of Off-Site Power Time I Position I Applicant's Actions or Behavior OP-TM-AOP-041, Loss of Seal Injection Step 3.2: IAAT ICCW flow< 550 GPM and #1 seal inlet temperature> 235°F, then perform the following:

URO

CLOSE MU-V-20 .

GO TO OP-TM-226-901, "Loss of All RCP Seal Cooling".

URO Step 3.3: ENSURE MU-V-32 is in HAND and Closed.

Step 3.5: Determines that a Makeup Pump is not running and lAW the RNO, performs the following:

ENSURE MU-V-3 is Closed .

ENSURE MU-V-17 is Closed .

VERIFY [MU tank level >40"] or [MU-V-14A or 8 is URO Open].

If MU tank level was < 18" at any time, then PERFORM OP-TM-211-271 to vent the MU pumps.

If MU-V-77 A & 8 are Open, then GO TO section 4.0 .

If MU-P-1C is unavailable, then GO TO Section 5.0 .

GO TO Section 6.0 .

Booth Cue: When directed as an Auxiliary Operator to Open MU-V-76A and MU-V-768, Insert Event 20 and then report that MU-V-76A and MU-V-768 are OPEN Footnotes: 1- MU-V-20: RCP Seal Injection R8 Isolation Valve 2- MU-V-32: RCP Seal Injection Control Valve 3- MU-V-3: RCS Letdown R8 Isolation Valve 4- MU-V-17: Normal Makup to RCS Control Valve 5- MU-V-77A: MU-P-1A/8 Discharge Header Cross-Connect Valve 6- MU-V-778: MU-P-1A/8 Discharge Header Cross-Connect Valve 7- MU-V-14A: Makeup Pump Suction Valve from 8WST 8- MU-V-148: Makeup Pump Suction Valve from 8WST 9 - MU-P-1 C: "C" Makeup Pump 10- MU-V-76A: MU-P-1 8/C Discharge Header Cross-Connect Valve 11 - MU-V-768: MU-P-1 8/C Discharge Header Cross-Connect Valve Appendix D Operator Action Form ES-D-2 Op Test No.: _;...._ Scenario # 2 Event # ....:8=------ Page 38 of _4.;.;;.2--fl Event

Description:

Loss of Off**Site Power Time I Position I Applicant's Actions or Behavior Step 6.0: Determines that MU-V-76A and MU-V-768 are closed as well as HPI train A and Normal MU header piping is URO intact, and then directs an Auxiliary Operator to open MU-V-76A and MU-V-768.

Step 6.1 I 6.2: Verifies MU-P-1 C is ES selected and that MU-URO V-36 and MU-V-37 are open.

Step 6.3:

Starts DR-P-1 8 by rotating the Control Switch clockwise, verifying red flag indicated, red running light URO lit, green secured light not lit. (CC)

Starts DC-P-1 8 by rotating the Control Switch clockwise, verifying red flag indicated, red running light lit, green secured light not lit. (CC)

Step 6.4: Starts MU-P-1 C by rotating the Control Switch URO clockwise, verifying red flag indicated, red running light lit, green secured light not lit. (CC)

URO Step 3.6: VERIFY #1 seal temperatures are< 235°F.

URO Step 3.7: VERIFY MU-V-20 is Open Footnotes: 1- MU-V-76A: MU-P-1 8/C Discharge Header Cross-Connect Valve 2- MU-V-768: MU-P-18/C Discharge Header Cross-Connect Valve 3 - MU-P-1 C: "C" Makeup Pump 4- MU-V-36: Makeup Pump Recirc Valve 5- MU-V-37: Makeup Pump Recirc Valve 6- DR-P-1 8: "8" Decay River Water Pump 7- DC-P-1 8: "8" Decay Closed Cooling Water Pump 8- MU-V-20: RCP Seal Injection R8 Isolation Valve Appendix D Operator Action Form ES-D-2 Op Test No.: .......;......_ Scenario # 2 Event #

8 Page 39 of 42

--~

Event

Description:

Loss of Off**Site Power Time l Position ~ Applicant's Actions or Behavior Step 3.8: Slowly adjusts MU-V-32 for 38 gpm seal injection URO flow rate, while limiting RCP radial bearing cooldown rate to less than 1oF/minute.

OP-TM-EOP-01 0 Guide 10, Natural Circulation If all of the following conditions exist, then adequate Natural Circulation is present:

RCS THOT minus TCOLD stabilizes at less than 50°F .

THOT < 600°F CT-12 ARO

lncore temperature stabilizes and tracks THOT .

Cold let temperatures approach saturation temperature for secondary side pressure.

OTSG heat removal is indicated by feeding or steaming with stable OTSG pressure.

SCM< 25°F Examiner's Note: When Natural Circulation has been established, Go to Event 9.

I Footnote: 1- MU-V-32: RCP Seal Injection Control Valve Appendix D Operator Action Form ES-D-2 Op Test No.: _;..__ Scenario # 2 Event # 9 Page 40 of 42

~------- --~

Event

Description:

Loss of EG-Y-1 B I Station Blackout Time I Position I Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Lead Examiner, INITIATE EVENT 9 Indications Available: EG-Y-1B tripped, Loss of Control Room Lighting, various MAP alarms, Loss of all RCP's.

Crew Diagnoses the loss of EG-Y-1 B I Station Blackout Announces reentry into OP-TM-AOP-020, Loss of Station CRS Power Examiner's Note: Steps 3.1 and 3.2 have been previously performed.

Step 3.3: VERIFY 1D 4160V and 1E 4160V bus are energized.

CRS/

ARO RNO: If neither ES 4160V bus is energized, then GO TO Section 4.0 STATION BLACKOUT.

Section 4.0 - Station Blackout Examiner's Note: Steps 4.1 and 4.2 are N/A Step 4.4: PLACE the following in PTL:

CT-3 URO

IC-P-1A,

IC-P-1 B.

Footnotes: 1 - EG-Y -1 B: "B" Emergency Diesel Generator 2 -IC-P-1A: "A" Intermediate Closed Cooling Water Pump 3 -IC-P-18: "B" Intermediate Closed Cooling_ Water Pump Appendix D Operator Action Form ES-D-2 Op Test No.:

Event

Description:

Scenario # 2 Event #

Loss of EG-Y-1 B I Station Blackout

__;9;....._____ Page 41 of _4.;.;;;.2---ll Time I Position I Applicant's Actions or Behavior Step 4.4: ENSURE the following CLOSED:

URO

MU-V-3

MU-V-20

MU-V-26 Examiner's Note: If the above CT-3 actions are not completed prior to RCP seal temperatures rising above 235F, then give the crew EG-Y-1 8 back and allow them to restore the 1E 4kV bus.

Examiner's Note: After IC-P-1A/1B are in Pull to Lock and Seal Injection Isolation Valves are Closed OR the 1E 4kV bus has been restored, scenario may be terminated.

Follow-up question highest event entered during scenario?

Answer: MS1

Loss of all Off-Site and all On-Site AC power to emergency busses for 15 minutes or longer.

Footnotes: 1 - EG-Y-1 B: "B" Emergency Diesel Generator 2 -IC-P-1A: "A" Intermediate Closed Cooling Water Pump 3- IC-P-1 B: "B" Intermediate Closed Cooling Water Pump 4- MU-V-3: RCS Letdown RB Isolation Valve 5- MU-V-20: Reactor Coolant Pump Seal Water Isolation 6- MU-V-26: Reactor Coolant Pumg Seal Return RB Isolation Appendix D Operator Action Form ES-D-2 Op Test No.: .....;...._ Scenario # 2 Event # N/A Page 42 of 42

~~----- --~

Event

Description:

Effects of Loss of 1D 4160V bus Time I Position I Applicant's Actions or Behavior ATTACHMENT 2 Effects of loss of 10 4160V bus loss of EF-P-2A loss of cooling fans in ESAS cabinets:

1A, 2A, 3A, 4A, 4B, 4C and 40.

loss of BS Train A PM-1 transfers to EG-Y-38 Loss of PM-2 transfers to EG-Y-3A RRTrain A RR-V-3A, RR-V4A loss of Group 8 Pressurizer heaters ES AH-E-1A power SllPJNY loss of DH, DC and DR Train A A, C, and E Inverters transfer to "A" Battery loss ofSC-P-1C loss of RC-V-1 {Presst.JJizef" spray valve) loss of SR-P-1A loss of "Grey"' plant page phone system loss of NR-P-1 A and NR-P-1 B-R, NS-P-1A and NS-P-1 B-P loss of sample pumps on:

RM-A-12 (Piimary lab Air Monftor),

loss of fCP-1A RM-A-4, RM-A-6, RM-A-9 loss of SF-P-1A and AH-E-8A 1C ES Valves MCC transfers to 1S oos loss of CA-P-1A and BAMT heater loss of MU-P-1A and MU-P-18-D loss FW-V-SA and FW-V-92A loss of MU-P-2B (MU-P-113 Aux Ota Pump) loss of AH-E-9A loss of lO-P-S auto starts LO-P-6 loss of AH-E-27A loss of Relay Room CO:! Cootroi power loss of:

AH-E-20A, AH-E-2013, Loss of River WateT Chern Treabnent Sys.

AH-E-26, AH-E-~m, AH-E- 91, AH-E-92 loss of Screen Hoose Fire Detection System and 1h of Screen Hoose lighting loss of power to "A" ESF ventilmion loss of WT-P-33A loss of ..A"' side Contrrn Building chi lief &

ventilation fans loss of SR-S-2A, SR-S-2C Bar Rakes loss of all Control Building heating loss of SR-S-3A, SR-S..JC Traveling Screens Appendix D Scenario Outline Form ES-D-1 Facility: Three Mile Island Scenario No.: 4 Op Test No.: 289-2014-301 Examiners: Operators:

Initial Conditions: * (Temporary IC-244)

85% Power, MOL

I&C Maintenance is occurring on HSPS, Train B, currently testing EF-V-308 .

SBO OOS for Maintenance, expected to return to service in 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months .

Crane work is occurring on the West side of the Plant to stage new piping .

NRC Authorization Code for today is AB12 .

Turnover: Maintain 85% Reactor Power Critical Tasks:

PORV Control for Heat Transfer (CT-13) (If conditions are met)

Shutdown Reactor- ATWS (CT-24)

Restore Feed to a Dry OTSG (CT-26)

Event No. Malt. No. Event Type* Event Description 1 IA08 TSCRS Instrument Air Leak Requiring Isolation of "A" Side 2-Hour Air and "A" EFW Valves, entry into OP-TM-AOP-028 (ARO:Start IA-P-1 A/B)

CARO 2 IC38B CCRS Invalid "B" OTSG Low Level, "B" EFW inadvertent actuation.

CARO (ARO: defeats invalid signal, secures EF-P-28) 3 RD10B ICRS Uncontrolled Inward Rod Motion.

IURO IARO (URO: Assumes Manual Control of Control Rods) 4 TSCRS MU-V-18 Fails Closed, entry into Guide 9.

CURO (URO: Controls Pressurizer Level with HPI valve) 5 FW15A CCRS "A" Main Feed Pump Trips, Manual runback required.

RURO NARO (URO: Runback in Manual, ARO: Runback in Manual) 6 TH18B CCRS Sheared Shaft on RC-P-1 B C URO CARO (URO: Secures RC-P-1 B, ARO: re-ratios Main Feedwater) 7 RD28 MCRS "B" Main Feed Pump Runs to 0 rpm, ATWS, Lack of Primary to Secondary RD32 Heat Transfer.

MURO MARO 8 CCRS EFW Control Valves fail to operate, EF-V-52A-D Closed CARO (ARO: Establish PSHT via Condensate Booster Pump flow) 9 CCRS MU-P-1 A/C will not start, MU-P-1 B trips.

CURO (URO: Establish PORV control for Heat Transfer)

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Scenario Set-up NRC Scenario 4 Three Mile Island NRC Scenario #4 Event #1: When the crew has accepted the watch, the Lead Examiner will cue the Loss of Instrument Air.

The operators will diagnose the Loss of Instrument Air based on a report from the field and slightly lower lA pressure.

Upon a Loss of Instrument Air, the following Critical Safety Functions are affected:

CSF-1, Reactivity & Reactor Power Control: Maintain control of the fission process, maintain the capability to shutdown the reactor and the capability to maintain the reactor in a shutdown condition. Control energy production and reactor power distribution based on design limits and current core heat removal capability. Loss of lA: If lA pressure < 60 psig, then the reactor will be tripped. At above 60 psig, lA will be sufficient for plant control and proper reactivity management. Reactor trip capability is not impacted by loss of lA.

Emergency boration can be performed via BWST or by local operation of MU-V-51 when emergency berating from BAMT. Emergency boration via the RBAT is inoperable (several air operated valves w/o handwheel). DC-V-20A

& B are closed to prevent flooding new fuel storage area with non-borated water.

CSF-3, RCS Integrity: Maintain the capability to control heatup and cooldown rates and control RCS pressure prevent reactor vessel brittle fracture or LTOP events. Maintain RCP seal cooling to prevent excessive loss of RCS inventory through RCP seals. Loss of lA: Normal RCS pressure control (spray &

heaters) is not affected by loss of lA. Loss of lA will result in a loss of letdown.

This will eventually cause problems with RCS pressure control (i.e., with seal injection and no letdown, pressurizer level will increase until solid ops is required). This is mitigated by providing a method to restore letdown without lA lAW OP-TM-211-950. Emergency pressure control functions (PORV & ES powered heaters) are not affected by loss of lA. Both methods (ICCW to thermal barrier & seal injection) of RCP seal cooling are adversely affected by loss of lA.

IC-V-3, IC-V-4, and MU-V-20 fail closed on loss of air (after depletion of local air reservoir). Local operator action to block OPEN IC-V-3, 4, and MU-V-20 is needed to maintain redundant means of seal cooling. Loss of ICCW more than 10 minutes after loss of seal injection, or Loss of Seal Injection for more than 10 minutes without ICCW will result in unacceptable RCP seal & thermal barrier temperatures which will preclude restoration of RCP seal cooling. (Reference 6.1) Therefore, the Loss of lA procedure is designed to ensure that both Sl and ICCW are not lost.

Scenario Set-up NRC Scenario 4 CSF-4, Core Heat Removal: Provide the capability to remove core heat production at all times. Loss of lA: With lA pressure > 60 psig, main FW and main turbine (or turbine bypass) operation will not be adversely affected. If lA pressure is< 60 psig, the reactor will be shutdown and normal FW and TBV control will be utilized. If BUIA does maintain these functions, then EFW and ADVs will be used. The safety grade 2 HR air system should maintain the capability for remote control of these functions from the control room. If necessary, local operation of EF-V-30s or MS-V-4s will be utilized. EF-P-1 will start if air to IBis lost. MS-V-13A & B fail open. The pump will remain operating until lA pressure is restored. EF-P-1 remains operable during a loss of lA event.

CO-V-13 is closed at less than 60 psig to prevent loss of EFW inventory caused by dumping the CSTs to the hotwell. CO-V-8 and hotwell makeup level control is supplied by BUIA.

CSF-5, Containment Integrity: Provide means to prevent or minimize fission product release to the environment. (1) Maintain containment pressure below design and (2) Provide capability to isolate the containment when required.

Loss of lA: Containment cooling. Industrial cooler operation will be degraded.

RBEC will be initiated lAW MAP N-1-6 if RB air temperature is high.

The CRS will enter OP-TM-AOP-028, LOSS OF INSTRUMENT AIR. The ARO will start IA-P-1A and/or IA-P-1 B from the Control Room prior to Instrument Air reaching 60psig (setpoint below which a manual Reactor Trip must occur). The CAS will determine isolation points and order the appropriate valves to be closed. The CAS will evaluate and declare T.S. 3.4.1.1.a.(2) based on the following LimiVPrecaution in 1104-25, Instrument and Control Air System:

Both "A" and "B" trains of two-hour BUIA must be pressurized and inservice prior to exceeding 250°F in RCS. (Tech. Spec. Definition of OPERABLE (1.3} applied to EFW.)

T.S. 3.4.1.1.a.(2) Three independent Emergency Feedwater (EFW) Pumps and two redundant flowpaths to each Once Through Steam Generator (OTSG) shall be OPERABLE with:

(2) With one EFW Pump or any EFW flowpath inoperable, restore the inoperable pump or flowpath to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in COLD SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

When IA-P-1A and/or IA-P-1 Bare/is running, the air leak has been isolated and the Tech Spec has been declared, the scenario can continue.

Event #2: The Lead Examiner can cue the Inadvertent Low Level Signal on the "B" OTSG with EFW actuation.

The crew will diagnose the Inadvertent Low Level Signal by EF-P-2B and EF-P-1 running with no valid reason (OTSG level is greater than 10" in the Startup Range and OTSG pressure is greater than 600 psig).

Scenario Set-up NRC Scenario 4 The ARO will respond per OP-TM-424-901, and defeat the HSPS signal, secure the running EFW pump (EF-P-28), and re-enable HSPS.

When HSPS is re-enabled, the scenario can continue.

Event #3: The Lead Examiner will cue the Uncontrolled Inward Rod Motion. This will cause an ICS transient.

The crew will diagnose the uncontrolled inward rod motion by an inward signal shown on the Diamond panel and the Position Indication Panel, Reactor Power lowering, RCS pressure and temperature lowering.

Note: OP- TM-AOP-064, UNCONTROLLED ROD MOTION, was deleted when the Digital Control Rod System was installed, and so the only way to address the situation is with OP- TM-AOP-070, PRIMARY TO SECONDARY HEAT TRANSFER UPSET.

Entry into OP-TM-AOP-070, PRIMARY TO SECONDARY HEAT TRANSFER UPSET will be required based on RCS pressure lowering.

"RCS pressure is not being controlled" requires the operator to make a subjective determination, based on their skills, training, and experience. A determination that RCS pressure is being controlled should include the following elements:

1) The reason for the transient is understood

2) RCS pressure response is consistent with the expected response for the event

3) Automatic or manual control in accordance with normal operating procedures is effectively controlling RCS pressure.

A conservative assessment (i.e. concluding that RCS pressure is not being controlled) is appropriate when the three conditions above cannot be satisfied.

ICS failures are one class of events that can lead to an upset in primary to secondary heat transfer. Most ICS failures can be mitigated by use of the appropriate manual control normal operating procedures.

This entry into AOP-070 is unique from the other scenarios because Reactor Power will lower due to a rod insertion signal, and not due to a failed ICS input.

Once the plant is stabilized in ICS HAND control, the scenario can continue.

Event #4: The Lead Examiner will cue the Closure of MU-V-18.

The crew will diagnose MU-V-18 closing by the green closed light lit and the red open light not lit (CC), lowering Pressurizer level indications (CC), and if left unattended long enough, MAP G-2-5, Pressurizer Level Hi/Lo in alarm.

Scenario Set-up NRC Scenario 4 The URO will establish Pressurizer Makeup manually via HPI Control Valve, MU-V-16B lAW OP-TM-EOP-010, Guide 9, RCS Inventory Control:

If normal makeup flow has not been established via MU-V-17 or MU-V-217 and through MU-V-18 (i.e. MU24-FI < 20 GPM), then MU-V-16B (or MU-V-16D) is used for normal MU flow. MU-V-16D is only used when the MU discharge cross connects are not in the normal lineup.

The CRS will evaluate and declare T.S. 3.5. 7:

3.5.7 REMOTE SHUTDOWN SYSTEM 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 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 an additional 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

TABLE 3.5-4 REMOTE SHUTDOWN SYSTEM INSTRUMENTATION AND CONTROLS Function/Instrument or Control Parameter uired Number of Functions MU-V-18 1 Once Pressurizer level is being restored, Makeup is being controlled manually, and the Tech Spec call has been declared, the scenario can continue.

Event #5: The Lead Examiner will cue the Loss of the "A" Main Feedwater Pump.

The crew will diagnose the Loss of FW-P-1A by an immediate drop in Feedwater flow, OTSG level decreasing rapidly, steam header pressure increasing, a neutron cross-limit alarm coming in, and the remaining feedwater pump speed increases causing feedwater flow to recover somewhat.

OP-TM-MAP-H01 01, Plant Run back, will be entered and a manual run back will be performed to lower Reactor Power to approximately 68%. this will require coordination between the URO and ARO, ensuring that the Control Rods and Feedwater are run back in symphony. This is the reactivity manipulation for the scenario.

Once sufficient reactivity manipulation has been observed, the scenario can continue.

Event #6: The Lead Examiner will cue the Sheared Shaft on RC-P-1 B.

The crew will diagnose the sheared shaft on RC-P-1 B by MAP alarm F-3-1 in alarm and zero amps indicated on RC-P-1 B.

OP-TM-MAP-F0301, RC LOOP FLOW LO, and OP-TM-226-152, Shutdown RC-P-1B, will be entered to secure RC-P-1 B and to re-ratio Main Feedwater.

Scenario Set-up NRC Scenario 4 The URO will secure RC-P-1 Band the ARO will re-ratio Main Feedwater due to the "A" and "B" Feed flow master ICS control stations being in HAND.

Once sufficient reactivity manipulation has been observed, the scenario can continue.

Event #7/8/9: The Lead Examiner will cue the "B" Main Feed Pump Lowering to 0 rpm.

The crew will diagnose the loss of Main Feedwater by an immediate drop in Feedwater flow, OTSG level decreasing rapidly, and a rapid rise inn RCS pressure and temperature. The URO will identify that an ATWS has occurred and will perform the Immediate Manual Actions of OP-TM-EOP-001, REACTOR TRIP.

Memorized operator action is appropriate because operator response time can significantly alter the consequences of an ATWS or a failure of the turbine to trip when required.

The reactor protection system is designed to prevent fuel clad or RCS pressure boundary failure. If RCS conditions are outside of the RPS envelope and RPS fails to de-energize the control rod drive mechanisms, prompt operator response can minimize the potential for fuel damage or an RCS pressure boundary failure EOP-001 is the primary entry point to the EOP network. This procedure is designed to address or direct procedures to address events from a reactor trip with no adverse plant conditions or equipment failures as well as events which challenge the fission product barriers.

The first priority (with the exception of entry into OP-TM-EOP-005 at power to mitigate an OTSG tube leak) to mitigate the consequences of a significant plant upset is to ensure the reactor is shutdown. Success of all subsequent EOP action is based on reducing core heat generation to reactor decay heat generation rates.

- Once the reactor is shutdown, prompt isolation of the turbine steam flow path is significant. Until the major steam flow path through the turbine to the condenser is isolated, RCS heat removal will be much larger than heat generation, and a rapid RCS cooldown will continue.

-When the turbine steam flow path is isolated, plant conditions are evaluated to determine if any symptoms of a core cooling upset are present.

Based on a symptom of low subcooling margin, excessive heat transfer, lack of primary to secondary heat transfer or primary to secondary leakage, rule based actions and entry into other sections of the EOP network is performed.

Scenario Set-up NRC Scenario 4 The crew will identify a Lack of Heat Transfer based on the following definition from OS-24, Conduct of Operations During Abnormal and Emergency Events:

LOHT is the inability of either OTSG to remove sensible heat from the RCS.

LOHT can be confirmed if one of the following sets of conditions exists:

lncore temperatures or That rising above 580°F and at least one RC Pump operating

lncore temperatures rising and NO FEEDWATER available

lncore temperatures rising and RCS circulation can not be confirmed The CRS will direct entry into OP-TM-EOP-004, LACK OF PRIMARY TO SECONDARY HEAT TRANSFER.

RCP philosophy lAW the GEOG and the OP-TM-EOP-004 Basis Document:

One or two RCPs (one in each loop) should be left running to reduce heat input to the RCS yet provide for heat transfer as soon as FW is restored to either OTSG.

The step intent is to reduce heat input to the RCS while maintaining forced flow in both RC loops.

Impact to pressurizer spray flow should be considered when selecting RCPs for shutdown.

Although one RCP is allowed, our procedure directs one RCP in each loop to allow for even flow between the loops (avoiding the reverse directional flow in the opposite loop),

and to prevent a loss of forced RCS flow if the only running RCP were to trip.

The ARO will recognize that EFW control valves are inoperable and report that feedwater is not available.

If feedwater is NOT available, then efforts to establish EFW should continue. If this event occurs when the condensate booster pumps could provide a continuous feedwater supply, then the booster pumps may be used alone to feed the OTSGs.

HPI COOLING will be initiated (EOP-009) when RCS pressure approaches the PORV setpoint. After initiating HPI COOLING, actions to restore feedwater (main or emergency) should continue.

Additionally, when the conditions are met during the scenario the CRS will direct entry into OP-TM-EOP-009, HPI COOLING.

HPI will not be adequate, which will force the URO to manually control the PORV to maintain RCS pressure while minimizing inventory losses until Primary to Secondary Heat Transfer exists.

Scenario Set-up NRC Scenario 4 A report from the field will inform the control room that EF-V-52A-D are closed. These valves are the downstream isolations to the EF-V-30A-D, Emergency Feedwater Flow Control Valves. The Auxiliary Operator will be directed to open the EF-V-52A-D valves and report that only the EF-V-52D will open. EF-V-52D will be opened and the ARO will feed the "A" OTSG lAW OP-TM-EOP-010 Guide 13, Feeding a Dry or Depressurized OTSG.

Termination: The scenario can be terminated when the Reactor is shutdown, and Primary to Secondary Heat Transfer has been established with Emergency Feedwater.

Scenario Set-up NRC Scenario 4 B&W Unit EOP Critical Task Description Document, 47-1229003-04:

CT PORV Control for Heat Transfer- During action to restore primary to secondary heat transfer, RCS pressure must be continually controlled. RCS pressure is controlled by manually opening and closing the PORV. This prevents excessive PORV cycling which could occur if the PORV were allowed to operate automatically.

During mitigation of LHT, manually cycle the PORV as necessary to maintain RCS pressure between the PORV setpoint or RV P-T limit and minimum SCM (if subcooled) or 1600 PSIG (if saturated).

Performing PORV Control for Heat Transfer outside of the following limit should be considered grounds for failure of the critical task:

PORV automatically lifts three {3) times.

Safety Significance: During mitigation of LHT the PORV should be manually cycled to control RCS pressure between the PORV setpoint or RV P-T limit and 1600 PSIG if the RC is saturated or minimum allowable SCM if the RC is subcooled. The PORV opening values prevent challenges to the pressurizer safety valves and the RV P-T limit while the PORV closing values maintain a positive primary to secondary side AT (SGs remain heat sinks).

Cues:

1. High RCS pressure alarm

2. SCM monitor and associated alarms

3. SPDS displays and associated alarms

4. P-T display and associated alarms

5. Verbal alert by plant staff that RCS pressure has reached the PORV setpoint Performance Indicators:

1. Operation of PORV and PORV block valve controls Feedback:

1. PORV and PORV block valve status indication

2. RCS pressure and temperature

3. Verbal indication by plant staff that PORV flow has been initiated Scenario Set-up NRC Scenario 4 B&W Unit EOP Critical Task Description Document, 47-1229003-04:

CT Shutdown Reactor- ATWS- Actuation of the manual reactor trip pushbutton, to backup the automatic trip and/or provide the necessary reactor trip, anytime the reactor trips or should have tripped. In the event the reactor fails to trip, in response to automatic and manual demands, then perform the following: Deenergize CRDMs

Shutting down the reactor due to an ATWS outside of the following limit should be considered grounds for failure of the critical task:

Not deenergizing the CRDM power supplies:

1G-02

1L-02 Safety Significance: Without taking the proper actions, there exists a potential challenge to the Reactor Coolant System pressure boundary due to high RCS pressure.

An ATWS could occur due to a failure of the RPS to initiate a reactor trip signal upon one of the reactor trip parameters reaching its trip limit or the control and safety rods failing to insert once the RPS trip signal is given automatically or manually. A Diverse Scram System (DSS) is provided, independent of the RPS, to minimize the potential for an ATWS event. However, the operator must recognize and react to any of the reactor trip parameters that exceeds its limit but does not cause a reactor trip.

In this situation, the manual reactor trip button has been actuated but reactor power is not less than the plant specific reactor power level for verification of a reactor trip. Therefore, the reactor has not been shut down and there has been a failure of all or most of the control and safety rods to insert into the reactor core.

Given that RPS, DSS and the manual reactor trip have failed to trip the reactor, then immediate actions to shut down the reactor by the alternate methods should be initiated. These methods include trip of CRDM breakers and maximum rate of boron addition to the RCS. Once the control and safety rods are successfully tripped into the core, or sufficient boric acid has been added to provide an adequate shutdown margin, the reactor will be shut down.

This should be achieved prior to taking additional mitigating actions because post-trip transient mitigation, from this point forward, is based on the assumption that the reactor is shutdown (subcritical}.

Scenario Set-up NRC Scenario 4 B&W Unit EOP Critical Task Description Document, 47-1229003-04:

CT Shutdown Reactor- ATWS- Continued Cues:

1. RPS channel alarms

2. RCS Power, Pressure and Temperature indications

3. P-T display and associated alarms

4. Verbal alert by plant staff that reactor shutdown requirements have not been met Performance Indicators:

1. Operation of control rod drive feeder breakers Feedback:

1. Nuclear Instruments

2. Control rod status indication

3. Control rod drive breaker status indication

4. Verbal indication from plant staff of reactor shutdown status Scenario Set-up NRC Scenario 4 B&W Unit EOP Critical Task Description Document, 47-1229003-04:

CT Restore Feed to a Dry OTSG- If a RCP is running, establish FW to the SG(s) and control FW flow to maintain RCS cooldown rate within limits. EFW flow is established at less than 450 GPM total flow and MFW flow is established at less than 200,000 LBM/HR total flow.

Restoring Feed to a Dry OTSG (sustained) outside of the following limits should be considered grounds for failure of the critical task:

To minimize OTSG stress, do not exceed MFW flow greater than than 200,000 LBM/HR total flow (sustained).

To ensure the main feedwater nozzles remain full and to prevent cavitation type damage to the Main Feedwater nozzles if they are not full of subcooled fluid, do not fall below less than 160,000 LBM/HR total flow (sustained).

Safety Significance:

If it is decided to perform the cooldown by using trickle feeding, it will be necessary to control the rate of FW addition to the SGs to maintain RCS cooldown limits. The FW flow rate should be adjusted to get the desired cooldown rate. If possible EFW should be used to limit SG thermal stresses. If MFW is used with the MFW nozzles, it will only be effective with forced flow.

Once heat transfer is restored in the SG, feed rates can be adjusted as necessary to control the cooldown and SG tube-to-shell L1T.

Cues:

1. Low SG level alarms

2. Low SG pressure alarms

3. Verbal alert by plant staff that no SG is available for heat transfer Performance Indicators:

1. Operation of EFW/MFW pump controls

2. Operation of EFW /MFW valve controls Feedback:

1. EFW/MFW flow

2. SG level and pressure

3. RCS pressure and temperature

4. Verbal alert by plant staff of EFW/MFW flow status Scenario Set-up NRC Scenario 4 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)

PRA o Feedwater Transient (Initiating Event)

Scenario Set-up NRC Scenario 4 Event Description Procedure Support Initial Set-up 85% Power, MOL 1 Instrument Air Leak OP-TM-AOP-028, LOSS OF INSTRUMENT AIR Requiring Isolation of "A" Side 2-Hour Air T.S. 3.4.1.1.a.(2) 2 Invalid "B" OTSG Low Level OP-TM-424-901, Emergency Feedwater (TS), "B" EFW actuation 3 OP-TM-AOP-070, Primary to Secondary Heat Uncontrolled Inward Rod Transfer Upset Motion 11 02-4, Power Operations 4 OP-TM-EOP-01 0, Emergency Procedure Rules, MU-V-18 Fails Closed Guides and Graphs T.S. 3.5.7 5 "A" Main Feed Pump Trips, OP-TM-MAP-H01 01, Plant Run back Manual runback required OP-TM-621-471, ICS Manual Control 6 OP-TM-EOP-004, Lack of Primary to Secondary Sheared Shaft on RC-P-1 B Heat Transfer 7 OP-TM-EOP-001, Reactor Trip OP-TM-EOP-004, Lack of Primary to Secondary "B" Main Feed Pump Runs Heat Transfer to 0 rpm, ATWS, Lack of Primary to Secondary Heat OP-TM-EOP-01 0, Emergency Procedure Rules, Transfer Guides and Graphs OS-24, Conduct of Operations During Abnormal and Emergency Events 8 OP-TM-EOP-004, Lack of Primary to Secondary EFW Control Valves fail to Heat Transfer operate, EF-V-520 OP-TM-EOP-01 0, Emergency Procedure Rules, Guides and Graphs 9 MU-P-1 A/C will not start, OP-TM-EOP-009, HPI Cooling MU-P-1 B trips Scenario Set-up NRC Scenario 4 ACTION COMMENTS I INSTRUCTIONS DESCRIPTION Initialization IC-238 85% HFP ICS full AUTO Equilibrium XENON Malfunction RD28 Value: Insert ATWS Scenario Support When: Immediately Malfunction RD32 Value: Insert ATWS Scenario Support When: Immediately Malfunction MU31 C Value: Insert MU-P-1 A will not start When: Immediately Malfunction MU34C Value: Insert MU-P-1 C will not start 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 IAR04 Value: Off Loss of Instrument Air When: Immediately Scenario Support Remote FWR54 Value: MAN EF-V-30A Local Control When: Immediately Remote FWR55 Value: 0 EF-V-30A Control Set to 0 When: Immediately Remote FWR58 Value: MAN EF-V-30C Local Control When: Immediately Remote FWR59 Value: 0 EF-V-30C Control Set to 0 When: Immediately Remote FWR56 Value: MAN EF-V-308 Local Control When: Immediately Remote FWR57 Value: 50 EF-V-308 Control Set to 0 When: Immediately Malfunction lAOS Value: Severity 50 Loss of Instrument Air When: EVENT 1 Malfunction IC388 Value: Insert Invalid "8" OTSG Low Level, When: EVENT 2 "8" EFW actuation Annunciator J-1-4 Value: ON OTSG "8" EFW Actuated When: EVENT 2 Malfunction RD1 08 Value: Insert Uncontrolled Inward Rod When: EVENT 3 Motion Override Value: On MU-V-18 Fails Closed ZDIP8CMUV18 When: EVENT 4 Scenario Set-up NRC Scenario 4 ACTION COMMENTS I INSTRUCTIONS DESCRIPTION Malfunction FW15A Value: On FW-P-1A Trips When: EVENT 5 Malfunction TH 188 Value: On RC-P-1 B Sheared Shaft When: EVENT 6 Override Value: ON FW-P-1 BRuns to 0 RPM ZDIMSCB(1} When: EVENT 7 Override Value: OFF FW-P-1 BRuns to 0 RPM ZDIICS36BMCS{1) When: EVENT 7 Override Value: ON FW-P-1 BRuns to 0 RPM ZDIICS36BMCS(2} When: EVENT 7 Override Value: OFF FW-P-1 BRuns to 0 RPM ZDIICS36BMCS(3) When: EVENT 7 Override Value: OFF FW-P-1 BRuns to 0 RPM ZDIICS36BMCS(4) When: EVENT 7 Override Value: ON FW-P-1 BRuns to 0 RPM ZLOICS36BMCS(1} When: EVENT 7 Override Value: OFF FW-P-1 BRuns to 0 RPM ZLOI CS36BMCS(2) When: EVENT 7 Trigger 9 Value: Insert Triggers MU-P-1 B Trip When: dhndhp1 a > 0.9 Trigger 10 Value: mrf FWR57 0 Triggers EF-V-30 Failures When: Ratpw<20 Remote FWR60 Value: MAN EF-V-30D Local Control When: EVENT10 Remote FWR61 Value: 0 EF-V-30D Control Set to 0 When: EVENT10 Malfunction MU33A Value: INSERT MU-P-1 B trips When: EVENT 9 Delay: 10 SECONDS Trigger 20 Value: DMF IA08 Isolates Air Leak When: EVENT 20 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # Page 17l of 511'

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Event

Description:

Instrument Air Leak isolating "A" 2-Hour Air.

Time I Position I Applicant's Actions or Behavior Booth Operator: When directed by the Lead Examiner: Initiate Event 1 Indications Available: Lowering Instrument Air Pressure (PL), verbal report from the field, IA-P-1A and IA-P-1B may start.

Booth Cue: Report, as an Auxiliary Operator, that "I'm by the "A" 2-Hour Air bank and it looks like there is a small Instrument Air leak downstream of IA-V-1626A. The "A" 2-Hour Air bank pressure is 1000psig and lowering quickly."

Booth Cue: If contacted as I&C to suspend maintenance, acknowledge and state that you are backing out to a safe condition.

Crew Diagnoses the Loss of Instrument Air.

CRS Direct entry into OP-TM-AOP-028, Loss of Instrument Air.

OP-TM-AOP-028, Loss of Instrument Air Step 3.1: ANNOUNCE loss of instrument air over plant page ARO and radio.

Step 3.2: IAAT lA pressure is< 60 psig (PI-222 or Pl-1403),

N/A then PERFORM the following:

Booth Cue: If asked, IA-PI-491 Reads 80 psig.

Footnotes: 1 -IA-P-1A/1 B: Instrument Air Compressors.

2 -IA-V-1626A: "A" 2 Hour Air Distribution Supply Valve.

3- IA-PI-222: Instrument Air Pressure Indicator.

4 -IA-PI-1403: Turbine Building Instrument Air Pressure Indicator.

5- IA-PI-491: Instrument Air Dryer Inlet Pressure.

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # Page 181 of 511,

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Event

Description:

Instrument Air Leak isolating "A" 2-Hour Air.

Time I Position I Applicant's Actions or Behavior Step 3.3: If IA-PI-491 (18 295: upstream of pre-filters) < 85 psig and IA-P-1A and IA-P-18 are not loaded, then START IA-P-1A ARO or 18 from the Control Room by rotating the control switch for either pump (PL) clockwise, verifying the red light is lit, and the green light is not lit.

Examiner's Note: Steps 3.4 through 3.11 are N/A.

Step 3.12: When cause of loss of lA is known, then CONTINUE CRS in this procedure.

Examiner's Note: Step 3.13 is N/A.

Booth Cue: If asked, IA-P-1AIB filter and dryer DP reads 10 psid. (L\ of lA-Pl-491 and IA-PI-493)

Booth Cue: If asked, IA-P-4 filter and dryer DP reads 10 psid. (L\ of lA-PI-1408 and IA-PI-1411)

Step 3.14: VERIFY loss of Instrument Air was due to system CRS leak.

Step 3.15: DETERMINE leak isolation requirements and CRS possible effects.

CRS Step 3.16: ISOLATE leak.

Footnotes: 1 - IA-P-1 A/1 8: Instrument Air Compressors.

2- IA-PI-491: Instrument Air Dryer Inlet Pressure.

3 - IA-PI-493: Instrument Air Dryer Outlet Pressure.

4 -IA-PI-1408: IA-P-4 Dryer Inlet Pressure.

5 - IA-PI-1411: IA-P-4 Dryer Outlet Pressure.

6- IA-P-4: Main Instrument Air Compressor.

Appendix D Operator Action Form ES-D-2 Op Test No.: __;,__ Scenario # 4 Event # --'2:::..______ Page 191 of . . ;5: . . :1. .:. . 1- - - - 1 Event

Description:

Invalid "B" OTSG Low Level, "B" EFW inadvertent actuation.

Time I Position I Applicant's Actions or Behavior Examiner's Note: The minimum valves for isolation, as identified on drawing 302-273 (applicable portion can be found on Page 51 of this scenario), are as follows:

IA-V-1629A Booth Cue: If directed, as an Auxiliary Operator and/or Maintenance, to isolate the air leak (and the proper valves have been identified), then Insert Event 20, ensure that malfunction lAOS has been deleted and report that "the air leak has been isolated".

Declare TS for the 2-Hour Air portion of "A" side EFW being CRS non-operational.

Examiner's Note: T.S. 3.4.1.1.a.(2) Three independent Emergency Feedwater (EFW) Pumps and two redundant flowpaths to each Once Through Steam Generator (OTSG) shall be OPERABLE with:

(2) With one EFW Pump or any EFW flowpath inoperable, restore the inoperable pump or flowpath to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in COLD SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Examiner's Note: Once the air leak has been isolated and the TS call is made, Go to Event 2.

Footnotes: 1 - IA-P-1 A/1 B: Instrument Air Compressors.

2 -IA-V-1616A: "A" 2 Hour Air Bank Header Isolation Valve.

3 -IA-V-1629A: Normal Instrument Air to "A" 2 Hour Air Distribution Isolation Valve.

Appendix D Operator Action Form ES-D-2 Op Test No.: --'--- Scenario # 4 Event # _2_____ Page 20l of _;5::...;1~1:....'-----1 Event

Description:

Invalid "B" OTSG Low Level, "B" EFW inadvertent actuation.

Time I Position I Applicant's Actions or Behavior Booth Operator: When directed by the Lead Examiner: Initiate Event 2.

Indications Available: "B" OTSG Low Level alarm clears, EF-P-2B indicates running, MAP-J-1-4 in Alarm Crew Diagnosis inadvertent EFW actuation, "B" side.

CRS Directs entry into OP-TM-424-901, Emergency Feedwater.

Booth Note: Before the next message is delivered, ensure that Malfunction IC38B and Annunciator J-1-4 are removed.

Booth Cue: When contacted as I&C, state "A switch was bumped during maintenance. All switches have been inspected and are in their normal position. Maintenance has been suspended".

OP-TM-424-901, Emergency Feedwater Step 4.1.1: If EFW actuation was caused by an invalid signal or INFO condition, then GO TO section 5.

ARO Step 5.1: Obtain CRS concurrence to shutdown EFW.

N/A Step 5.2: If incore temperature <200F then GO TO step 5.5.

Step 5.3: 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 .

then Continue.

Footnote: 1 - EF-P-28: Emergency Feedwater Pump "B" Appendix D Operator Action Form ES-D-2 Op Test No.: ___:___ Scenario # 4 Event # .....:2=------ Page 21 1 of _5.;....1_1_

Event

Description:

Invalid "B" OTSG Low Level, "B" EFW inadvertent actuation.

Time I Position I Applicant's Actions or Behavior Step 5.3.1: Place the EFW control valves in Manual:

EF-V-30A by pressing the Manual pushbutton (CL},

verifying the Manual light is lit, and the Auto light is not lit.

EF-V-308 by pressing the Manual pushbutton (CC),

verifying the Manual light is lit, and the Auto light is not ARO lit.

EF-V-30C by pressing the Manual pushbutton (CC),

verifying the Manual light is lit, and the Auto light is not lit.

EF-V-30D by pressing the Manual pushbutton (CL),

verifying the Manual light is lit, and the Auto light is not lit.

Step 5.3.2: Ensure all EFW actuation switches (8) are in ARO DEFEAT by rotating the 8 EFW actuation switches counterclockwise to the DEFEAT position.

Step 5.3.3: Close both EF-V-30A and EF-V-30D by adjusting N/A the toggle switches (CL} in the closed direction. ARO may pin the toggle switches in the full closed position.

Step 5.3.4: If OTSG A is available, then ensure level is ARO maintained with Main Feedwater.

Step 5.3.5: Close both EF-V-308 and EF-V-30C by adjusting N/A the toggle switches (CC) in the closed direction. ARO may pin the toggle switches in the full closed position.

Footnotes: 1 - EF-V-30A: EFW Control Valve to "A" OTSG 2- EF-V-308: EFW Control Valve to "8" OTSG 3- EF-V-30C: EFW Control Valve to "8" OTSG 4- EF-V-30D: EFW Control Valve to "A" OTSG Appendix D Operator Action Form ES-D-2 Op Test No.: 4 Event # of ....;5::...:1...;;.;l~-----l

- - Scenario # -'2;;;...__ _ _ _ Page 22l Event

Description:

Invalid "B" OTSG Low Level, "B" EFW inadvertent actuation.

Time I Position I Applicant's Actions or Behavior Step 5.3.6: If OTSG B is available, then ensure level is ARO maintained with Main Feedwater.

Step 5.3.7: Place Loss of RCPs and High RB Pressure in ENABLE as follows:

Train A Loss of RCPs in ENABLE by rotating the switch (CL) clockwise to the ENABLE position.

ARO

Train B Loss of RCPs in ENABLE by rotating the switch (CC) clockwise to the ENABLE position.

Train A High RB Pressure in ENABLE by rotating the switch (CL) clockwise to the ENABLE position.

Train B High RB Pressure in ENABLE by rotating the switch (CC) clockwise to the ENABLE position.

Step 5.3.8: If at least one MFW pump is reset, then place Loss of FWPs in ENABLE as follows:

Train A Loss of FW Pumps in ENABLE by rotating the ARO switch (CL) clockwise to the ENABLE position.

Train B Loss of FW Pumps in ENABLE by rotating the switch (CC) clockwise to the ENABLE position.

Step 5.3.9: If OTSG A level> 20 inches and OTSG B level> 20 inches then place Lo-Lo OTSG Level in ENABLE as follows:

Train A Lo-Lo OTSG Level in ENABLE by rotating the ARO switch (CL) clockwise to the ENABLE position.

Train B Lo-Lo OTSG Level in ENABLE by rotating the switch (CC) clockwise to the ENABLE position.

Step 5.3.11: Place EF-P-2B in Normal-After-Stop by rotating ARO the Control Switch (CL) counter-clockwise, verifying the green light is lit, the red light is not lit, and amps indicate zero.

J Footnote: 1 - EF-P-2B: Emergency Feedwater Pump "B" Appendix D Operator Action Form ES-D-2 Op Test No.: _ _ Scenario # 4 Event # 2 Page 23L of 511

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Event

Description:

Invalid "B" OTSG Low Level, "B" EFW inadvertent actuation.

Time I Position I Applicant's Actions or Behavior N/A Step 5.3.12: CLOSE AS-V-4 ARO Step 5.3.13: ENSURE MS-V-10A is Closed.

Step 5.3.14: CLOSE MS-V-13A by pressing the close ARO pushbutton, verifying the green closed pushbutton is lit, red open pushbutton is not lit.

ARO Step 5.3.15: ENSURE MS-V-108 is Closed.

Examiner's Note: MS-V-138 is on a forty second delayed timer to open (to avoid the over-speeding of EF-P-1.

During validation, the faulted signal was removed prior to MS-V-138 opening, therefore it was not applicable.

The following step would be applicable if MS-V-138 has gone open.

N/A Step 5.3.16: Close MS-V-138.

Footnotes: 1 - AS-V-4: Auxiliary Steam Supply Valve to EF-P-1 2- MS-V-10A: "A" OTSG to EF-P-1 Throttle Valve.

3- MS-V-108: "8" OTSG to EF-P-1 Throttle Valve.

4- EF-P-1: Steam Driven Emergency Feedwater Pump.

5- MS-V-13A: "A" OTSG to EF-P-1 Main Steam Supply Valve.

6- MS-V-138: "8" OTSG to EF-P-1 Main Steam Supply Valve.

Appendix 0 Operator Action Form ES-0-2 Op Test No.: 4 Event # 2 Page 241 of 51l

- - Scenario # ~-------- ~~--~

Event

Description:

Invalid "B" OTSG Low Level, "B" EFW inadvertent actuation.

Time I Position I Applicant's Actions or Behavior Step 5 . 3.17: Place each of the following EFW control valves in AUTO and select REMOTE setpoint:

EF-V-30A by pressing the Auto pushbutton (CL),

verifying the Auto light is lit, and the Manual light is not lit.

EF-V-308 by pressing the Auto pushbutton (CC),

verifying the Auto light is lit, and the Manual light is not ARO lit.

EF-V-30C by pressing the Auto pushbutton (CC),

verifying the Auto light is lit, and the Manual light is not lit.

EF-V-300 by pressing the Auto pushbutton (CL),

verifying the Auto light is lit, and the Manual light is not lit.

Examiner's Note: After EF-V-30's have been placed in AUTO control, GO TO Event 3.

Footnotes: 1- EF-V-30A: EFW Control Valve to "A" OTSG 2- EF-V-308: EFW Control Valve to "8" OTSG 3- EF-V-30C: EFW Control Valve to "8" OTSG 4- EF-V-300: EFW Control Valve to "A" OTSG Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # _3:.__ _ _ _ Page 25r of .....:5~1..;..;1!_ __,

Event

Description:

Uncontrolled Inward Rod Motion.

Time 1 Position I Applicant's Actions or Behavior Booth Operator: When directed by the Lead Examiner: Initiate Event 3.

Indications Available: Rods indicating inward motion on the Position Indication Panel and the Diamond station, a rapid lowering of RCS pressure, Reactor Power lowering, and changes in indications at multiple ICS stations.

Examiner's Note: The crew may elect to place the SG/Rx Demand Station to Hand lAW OP-TM-621-471.

Crew Diagnoses uncontrolled inward rod motion.

DIRECTS entry into OP-TM-AOP-070, PRIMARY TO CAS SECONDARY HEAT TRANSFER UPSET OP-TM-AOP-070, PRIMARY TO SECONDARY HEAT TRANSFER UPSET Step 2.1 (IMA): Places the Diamond Station in Manual by pressing the Manual/Auto pushbutton on the Diamond Panel URO and observing the Manual light is lit and the Auto light is not lit (CC).

Step 2.2 (IMA): Places SG "A" FW Demand and SG "B" FW Demand ICS Stations in HAND by pressing the HAND URO/ARO pushbuttons on each res Station and verifying the white HAND lights are lit and the red AUTO lights are not lit on the selected ICS stations (CC).

Step 2.3 (IMA): Verifies Turbine Header Pressure is between URO 835 and 935 psig as read on the Turbine Header Pressure digital indication (CL)

Appendix D Operator Action Form ES-D-2 Op Test No.: __;___ Scenario # 4 Event # 3 Page 261 of 511:

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Event

Description:

Uncontrolled Inward Rod Motion.

Time I Position I Applicant's Actions or Behavior Step 2 . 4 (IMA): Verifies RCS Pressure is lowering and/or less than 2205 PSIG by observing RCS pressure meters (CC and PC).

URO As required, if RCS Pressure is >2205 psig, URO places RC-V-1 control in Manual (CC), opens RC-V-1 fully by pressing the open pushbutton and observing the red open light lit and the green closed light not lit (CC), and then places RC-V-1 control back to AUTO.

Examiner's Note: OP-TM-AOP-070, steps 3.1 and 3.2 are IAAT's that should not be applicable during this Event.

Step 3.3: Verifies the Main Turbine is reset by observing it on-CRS line (CL).

Step 3.4: Assigns manual control responsibilities and control CRS bands as follows:

Step 3.4: INSERT or WITHDRAW rods to maintain Reactor URO power within 1% of current power level by operating the Control Rod switch on the Diamond Panel as applicable (CC).

Step 3.4: Adjust FW Flow to maintain Tavg within 2 °F of current temperature by adjusting SG "A" FW Demand and SG ARO "8" FW Demand ICS Station toggle switches as applicable (CL and CC).

Footnotes: 1 - RC-V-1: Pressurizer Spray Control Valve.

2- FW-V-16A: "A" Main Feedwater Startup Control Valve.

3- FW-V-168: "8" Main Feedwater Startup Control Valve.

4- FW-V-17A: "A" Main Feedwater Control Valve.

5- FW-V-178: "8" Main Feedwater Control Valve.

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # 3 Page 271_ of 511 '

~~--~

Event

Description:

Uncontrolled Inward Rod Motion.

Time .I Position I Applicant's Actions or Behavior Step 3.4: Maintain Turbine Hdr Pressure within 10 psig of ARO current pressure by adjusting Turbine Load Set Station demand as applicable (CC).

CAS Step 3 . 5: Initiates 1102-4, Power Operations.

Step 3.6: Ensures SG/Reactor Demand Station is in HAND by URO pressing the HAND pushbutton and observing white HAND light is lit and red AUTO light is not lit.

Step 3.6: Ensures Reactor Demand Station is in HAND by URO pressing the HAND pushbutton and observing white HAND light is lit and red AUTO light is not lit.

Step 3.6: Ensures SG AlB Load Ratio Demand Station is in URO HAND by pressing the HAND pushbutton and observing white HAND light is lit and red AUTO light is not lit.

Step 3.6: Observes that the ULD ICS Station is already in URO HAND by the white HAND light being lit.

Examiner's Note: If Reactor Power is not greater than 75%, then the Feedwater Pumps will be placed in HAND lAW OP-TM-401-472 (473),

"Manual Control of FW-P-1A (B)", per Step 3.7 RNO.

Step 3. 7: Verifies that MFW Pumps are controlling FW Valve CAS dP greater than 30 psid (CL) and that Reactor Power is greater than 75% (CC).

Footnotes: 1 - FW-P-1A: "A" Main Feedwater Pump.

2- FW-P-1 8: "B" Main Feedwater Pump.

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # 3 Page 281 of 51r:

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Event

Description:

Uncontrolled Inward Rod Motion.

Time I Position I Applicant's Actions or Behavior 1 I Examiner's Note: OP-TM-AOP-070, step 3.8 is N/A and 3.9 has already been verified.

ARO Step 3.10: Maintains RCS pressure between 2105 and 2205 psig by adjusting SG "A" FW Demand and SG "8" FW Demand ICS Station toggle switches as applicable as applicable (CL and CC).

ARO Step 3.11: Maintains RCS Tavg 578 to 580 °F, and controls RCS flTc <so F by adjusting SG "A" FW Demand and SG "8" FW Demand ICS Station toggle switches as applicable as applicable (CL and CC).

Examiner's Note: OP-TM-AOP-070, steps 3.12 and 3.13 are N/A.

Examiner's Note: Once the appropriate stations from OP-TM-AOP-070 have been placed in HAND and the plant is stable, Go to Event 4.

Footnotes: 1- FW-V-16A: "A" Main Feedwater Startup Control Valve.

2- FW-V-168: "8" Main Feedwater Startup Control Valve.

3- FW-V-17A: "A" Main Feedwater Control Valve.

4- FW-V-178: "8" Main Feedwater Control Valve.

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # 4 Page 291 of 511

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Event

Description:

MU-V-18 Fails Closed Time J Position I Applicant's Actions or Behavior Booth Operator: When directed by the Lead Examiner: Initiate Event 4.

Indications Available: Lowering level on Pressurizer indicators (CC), MAP G-0205 in alarm (if Pressurizer level falls to 200"), green closed light lit on MU-V-18 (CC).

Crew Diagnoses MU-V-18 closed.

Examiner's Note: The CRS may enter alarm response based on "approaching" criteria, as described in OS-24:

3.2 APPROACHING

The parameter is trending toward the setpoint or limit, and based on its trend and plant conditions it is likely that the parameter will reach the setpoint or limit.

4.1.14 Guidance on using APPROACHING A. If it is clear that the plant trend is going to reach a setpoint requiring action, Shift Management may elect to perform the action before the setpoint is reached. This applies to EOP and AOP entry, safety system actuation, and the performance of emergency response procedure steps.

CRS Directs entry into OP-TM-MAP-G0205, PZR LEVEL HI/LO Examiner's Note: Step 4.1 is N/A.

OP-TM-MAP-G0205, PZR LEVEL HI/LO Step 4.2: If PZR level cannot be restored with automatic or CRS manual control of MU-V-17, then INITIATE OP-TM-EOP-010, Guide 9.

Footnotes: 1- MU-V-17: Normal Makeup to RCS Control Valve.

2- MU-V-18: Normal Makeup RB Isolation Valve.

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # 4 Page 301 of 511!

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Event

Description:

MU-V-18 Fails Closed Time I Position I Applicant's Actions or Behavior Examiner's Note: Sections A and 8 are N/A.

OP-TM-EOP-010, Guide 9, RCS Inventory Control Step C.1: Verifies MU-P-1 B is operating by observing red light lit, URO green light not lit, and amps in the green band of the ammeter (CC).

Step C.2: Ensures MU-V-5 is Closed by placing the MU-V-5 Bailey URO Controller toggle switch in the downward direction until the MU-V-5 indication is at zero (CC).

Examiner's Note: Steps C.3 through C.S are either not possible to accomplish (e.g. Open MU-V-18) or will be ineffective due to MU-V-18 being closed.

Examiner's Note: The URO will not use MU-V-160 to ensure makeup flow due to valve lineup within the Makeup System. MU-V-160 is a component in the "8" HPI Train and there is no associated pump running and no discharge path lined up for flow to get to the Pressurizer. The URO will therefore be required to throttle MU-V-168.

Step C.6 RNO: Throttles MU-V-16B by pressing the red open pushbutton, green close pushbutton, and white stop pushbutton URO associated with MU-V-16B (CC) as necessary to ensure proper makeup flow, as indicated on the HPJ flow indicator for MU-V-16B.

(CC).

Footnotes: 1 - MU-P-1 B: "B" Makeup Pump 2- MU-V-5: Letdown Flow Control Bypass Valve.

3- MU*V-18: Normal Makeup RB Isolation Valve.

4- MU*V-16B: HPJ Control Valve B.

5- MU-V-160: HPI Control Valve D.

Appendix 0 Operator Action Form ES-0-2 Op Test No.: Scenario # 4 Event # 4 Page 31 r_ of 51l:

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

Event

Description:

MU-V-18 Fails Closed Time I Position I Applicant's Actions or Behavior Step C. 7 and C.8: Verify PZR level is being restored by observing URO rising level on Pressurizer level indicators (CC) and/or the PPC.

CRS Identifies and declares Tech Spec 3.5.7.

Examiner's Note: T.S. 3.5.7:

3.5.7 REMOTE SHUTDOWN SYSTEM 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 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 an additional12 hours.

TABLE 3.5-4 REMOTE SHUTDOWN SYSTEM INSTRUMENTATION AND CONTROLS I Function/Instrument or Control Parameter I Required Number of Functions J I MU-V-18 I 1 J Examiner's Note: Once Pressurizer level is recovering, makeup flow is being controlled, and the Tech Spec call has been declared, Go to Event 5.

Appendix D Operator Action Form ES-D-2 Op Test No.: ......;....__ Scenario # 4 Event # 5 Page 321 of 51 c

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

Event

Description:

FW-P-1A Trips, Plant Runback with ICS in Manual.

Time I Position I Applicant's Actions or Behavior Booth Operator: When directed by the Lead Examiner: Initiate Event 5.

Indications Available: Main Annunciator Panel alarms M-1-1 and H-1-1 actuate, LO-P-8 starts, FW-P-1A indicate zero RPMs.

Diagnoses FW-P-1A tripped and that a manual runback is Crew required.

OP-TM-MAP-M01 01, FWP 1A Trip Examiner's Note: Crew will be required to run the plant back manually due to ICS being in HAND control. Those steps are listed on the next page.

ARO Step 4.2: Ensure plant runback and determine cause of trip.

Step 4.3: Ensure LO-P-8A running by the red running light lit, ARO green light not lit (CL).

Step 4.4: Ensure FW-V-1A Closed by the red closed light lit, ARO green open light not lit (CL).

OP-TM-MAP-H01 01, ICS Runback Step 4.1: Ensure Nl power is reduced to below the limit for the URO runback condition. If ICS manual control is required, then initiate OP-TM-621-471, ICS Manual Control.

Footnotes: 1- FW-P-1A: "A" Main Feed Pump 2- LO-P-8: FW-P-1A Turbine AC Oil Pump.

3- FW-V-1A: FW-P-1A Discharge Isolation Valve.

Appendix D Operator Action Form ES-D-2 Op Test No.: __;,__ Scenario # 4 Event # 5 Page 33l of 51l

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

Event

Description:

FW-P-1A Trips, Plant Runback with ICS in Manual.

Time I Position I Applicant's Actions or Behavior Examiner's Note: Crew will run the plant back to 560 MWe (::::: 68% Nl power} for a loss of 1 MFP. Actual reactor power may vary due to plant efficiencies.

INFO Step 4.2: INITIATE 1102-4 for power reduction.

1102-4, Power Operation Step 3.3.2.A.1: Perform Enclosure 2A (for an emergency CRS (forced) power reduction INITIATE Enclosure 2A).

Examiner's 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 Diamond Panel with Rod Control in Manual for the reactivity manipulation. If the crew elects earlier to place ICS in Hand lAW OP-TM-621-471, the SG/REACTOR DEMAND STATION will be used for the reactivity manipulation.

Step 3.3.2.A.2.a): MAINTAIN Generator Reactive Load JAW ARO OP-TM-301-472.

Examiner's Note: Step 3.3.2.A.2.b} is N/A.

Step 3.3.2.A.2.c): If SG/REACTOR DEMAND is in HAND, then CRS REDUCE reactor power JAW OP-TM-621-471 "JCS Manual Operations".

OP-TM-621-471 "ICS Manual Operations" Step 4.1: Ensure ULD in HAND by observing white HAND light URO lit (CC).

Examiner's Note: Steps 4.2.1 through 4.2.3 have already been accomplished in an earlier event.

Appendix D Operator Action Form ES-D-2 Op Test No.: ......:......._ Scenario # 4 Event # 5 Page 341 of 511

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

Event

Description:

FW-P-1A Trips, Plant Runback with ICS in Manual.

Time I Position I Applicant's Actions or Behavior Step 4.2.4: If necessary to maintain reactor power or control rods within limits or if a power change is being conducted lAW 1102-4, then ADJUST SG/REACTOR DEMAND as follows:

1. If maintaining stable reactor power or a slow planned power change, then RAISE or LOWER in discrete steps to keep URO/ARO neutron error between +2% and -2%.

2. If rapid power reduction is required, then LOWER as necessary to achieve desired reactor power level and Ensure FW flow controlled within limits by lowering and/or raising on the SG/REACTOR DEMAND toggle switch (CC) as necessary.

Examiner's Note: 11 02-4, Power Operation Step 3.3.2.A.2.d) is N/A.

11 02-4, Power Operation INFO Step 3.3.2.A.2.e): PERFORM the actions per Enclosure 28.

11 02-4, Power Operation, Enclosure 28 Prior to FW -U-1 A speed < 4000 rpm (between 100%-90%

reactor power as a guide):

N/A Start LO-P-8A by turning the control switch (CL) clockwise, verifying the red light is lit and the green light is not lit.

Examiner's Note: Once Sufficient reactivity manipulation has been observed and Reactor Power < 75%, Go to Event 6.

Footnotes: 1 - FW-U-1A: "A" Main Feed Pump Turbine.

2- LO-P-8: FW-P-1A Turbine AC Oil Pump.

Appendix D Operator Action Form ES-D-2 Op Test No.: _ _ Scenario # 4 Event # 6 Page 351 of 51lJ

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

Event

Description:

RC-P-1 B Shaft Shear Time I Position I Applicant's Actions or Behavior Booth Operator: When directed by the Lead Examiner: Initiate Event 6.

Indications Available: Main Annunciator Panel Alarm F-3-1 in alarm, RC-P-18 amps go to zero.

Diagnoses a sheared shaft on RC-P-1 B and will enter OP-TM-Crew MAP-F0301.

Examiner's Note: OP-TM-MAP-F0301 Steps 4.1 through 4.3 are N/A.

OP-TM-MAP-F0301, RC LOOP FLOW LO Step 4.4: Observe the following and determine the faulty RC Pump to be RC-P-1 8:

URO

- RC-P-1 A and RC-P-1 B Ammeters (CC)

- Bentley-Nevada for elevated vibrations (PLF)

Step 4.5.1: If faulty RC Pump is still in operation, then perform the following:

URO/ARO - Start at least one RC-P-2 pump by rotating either RC-P-28-1 or RC-P-28-2 control switch in the clockwise direction, ensuring that the red light is lit, green light is not lit (CC).

Footnotes: 1 - RC-P-1A: "A" Reactor Coolant Pump.

2- RC-P-1 8: "B" Reactor Coolant Pump.

3 - RC-P-28-1: RC-P-1 8 AC Oil Lift Pump.

4- RC-P-28-2: RC-P-1 B DC Oil Lift Pump.

Appendix D Operator Action Form ES-D-2 Op Test No.: __;__ Scenario # 4 Event # 6 Page 361 of 51 LJ

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

Event

Description:

RC-P-1 B Shaft Shear Time I Position I Applicant's Actions or Behavior Step 4.5.2: If faulty RC Pump is still in operation, then perform the following:

UROIARO - Start at least one RC-P-3 pump by rotating either RC-P-3B-1 or RC-P-3B-2 control switch in the clockwise direction, ensuring that the red light is lit, green light is not lit (CC).

Step 4.5.3: Perform OP-TM-226-150 series procedure to place CRS affected RCP in the Standby mode.

Examiner's Note: OP-TM-226-152 Step 4.1 is N/A.

Procedure Note: A 2 I 1 RCP combination with OTSG levels > LLLs will require a re-ratio (approximately 30% I 70%) of Feedwater flow to A I B OTSG.

OP-TM-226-152, SHUTDOWN RC-P-18 Step 4.2: If Reactor power is > 20%, then EVALUATE CRS expected FW Flow requirements for new RCP combination, to minimize effects on Delta Tc.

Examiner's Note: OP-TM-226-152 Step 4.3 is not required and step 4.4 has already been accomplished.

Step 4 . 5: Place RC-P-1 Bin Pull-To-Lock by rotating the Control Switch in the counter-clockwise direction while URO simultaneously pulling the Control Switch outward to lock it in a PTL position, observing the green light lit, red and amber lights not lit, and a black flag position. (CC).

Footnotes: 1 - RC-P-1 B: "B" Reactor Coolant Pump.

2 - RC-P-3B-1 : RC-P-1 B AC Backstop Oil Pump #1 .

3- RC-P-3B-2: RC-P-1 B AC Backstop Oil Pump #2.

Appendix D Operator Action Form ES-D-2 Op Test No.: .......:....__ Scenario# 4 Event# _6"------- Page 37r of ....;5:;;...;1-'-1_ ___,

Event

Description:

RC-P-1 B Shaft Shear Time I Position I Applicant's Actions or Behavior Re-ratio Main Feedwater by manipulating the toggle switches the for SG "A" FW Demand and SG "8" FW Demand ICS ARO Stations upward or downward, as necessary to achieve feed flows discussed in step 4.2.

Examiner's Note: Once Main Feedwater re-ratioing has been observed, Go to Event 7.

Appendix D Operator Action Form ES-D-2 Op Test No.: ___;___ Scenario # 4 Event # _7__,,..;;...8':..;;..9_ _ _ _ Page 38l of _;5::;..;1...;;.c_ _--l Event

Description:

Loss of Feedwater, ATWS, EFW Control Valves Fail, LOHT, HPI Pumps Fail Time .I Position I Applicant's Actions or Behavior Booth Operator: When directed by the Lead Examiner: Initiate Event 7.

Indications Available: FW-P-1 8 RPMs go to zero, Feedwater flow lowers to zero, RCS pressure and temperature rise, OTSG level lowers.

Crew Diagnoses a loss of Feedwater and ATWS.

Examiner's Note: The ARO may trip FW-P-1 8 which will automatically actuate Emergency Feedwater.

The URO will trip the reactor, as allowed by OS-24:

4.2 Actions Not Described in Procedures A. Licensed operators may take action without procedural guidance, and without taking a variance under the following conditions:

Initiating a manual reactor TRIP when a licensed operator believes the reactor is not in a safe condition.

Action taken to directly compensate for the failure of an automatic system.

Action to manually actuate a safety system when the automatic actuation setpoint is being approached.

OP-TM-EOP-001, REACTOR TRIP CT-24 URO Step 2.1 (IMA): Presses Both Reactor Trip and DSS pushbuttons (CC).

URO Step 2.2 (IMA): Verifies that the reactor is shutdown by one of the following:

- Power Range Nuclear Instrumentation indicates less than 5% (CC)

- All control rods are inserted (PC)

- Source Range count rate is continuously lowering (CC)

Footnote: 1 - FW-P-1 B: "B" Main Feed Pump.

Appendix D Operator Action Form ES-D-2 Op Test No.: .......;__ Scenario # 4 Event # _7.:....!.'.:::.!8,.::...9_ _ _ Page 391 of _5.;...1_1_1_ _

Event

Description:

Loss of Feedwater, ATWS, EFW Control Valves Fail, LOHT, HPI Pumps Fail Time I Position I Applicant's Actions or Behavior URO Step 2.3 (IMA): Presses the Turbine Trip pushbutton (CL)

URO Step 2.4 (IMA): Verifies the Turbine Stop valves are closed by observing the indication on CL.

ARO Performs a Symptom Check, recognizes a Lack of Primary-to-Secondary Heat Transfer based on NO Main Feedwater and NO Emergency Feedwater due to the EF-V-30 valves failing, and informs the CAS.

Examiner's Note: A Lack of Primary-to Secondary Heat Transfer will be identified based on the following definition found in OS-24:

One of the following sets of conditions :

lncore temperatures or THOT rising above 580°F and at least one RC Pump operating.

lncore temperatures rising and NO FEEOWATER available.

lncore temperatures rising and RCS circulation can not be confirmed.

Following a loss of all RC Pumps, incore temperatures will rise while building natural circulation. Time should be taken to allow for the building of natural circulation.

EF-V-30A and Care failed due to the Instrument Air leak isolation earlier in the scenario. EF-V-308 and 300 will have no flow because EF-V-528 I 520 which are the downstream isolation valves for EF-V-308 /300 are closed and are required to be opened to allow EFW flow to the OTSGs.

Announces entry into OP-TM-EOP-004, LACK OF PRIMARY CAS TO SECONDARY HEAT TRANSFER.

Appendix 0 Operator Action Form ES-0-2 Op Test No.: _;.__ Scenario # 4 Event # _7......,8--'-,9"'---- Page 401 of ....;5;;..;1...;.;.;1l_ _~

Event

Description:

Loss of Feedwater, ATWS, EFW Control Valves Fail, LOHT, HPI Pumps Fail Time I Position I Applicant's Actions or Behavior OP-TM-EOP-004, LACK OF PRIMARY TO SECONDARY HEAT TRANSFER Step 3 . 1: Ensure no more than one RCP operating per loop by shutting down RC-P-1 C or RC-P-1 0 by rotating the control URO switch for either pump clockwise, verifying the red light is lit, and the green light is not lit (CC).

Examiner's Note: Upon initiating OP-TM-424-901, the ARO will discover and announce that EF-V-30AIB/C/D will not open, and will announce it to the CAS. Any further actions contained in OP-TM-424-901 will be useless.

CRS Step 3.2: Initiate OP-TM-424-901, "Emergency Feedwater".

ARO Step 3.3: Announces the reactor trip.

Examiner's Note: Steps 3.4-3.7 are N/A.

Footnotes: 1 - RC-P-1C: "C" Reactor Coolant Pump.

2- RC-P-10: "0" Reactor Coolant Pump.

3- EF-V-30A: EFW Control Valve to "A" OTSG.

4- EF-V-308: EFW Control Valve to "8" OTSG.

5- EF-V-30C: EFW Control Valve to "8" OTSG.

6- EF-V-300: EFW Control Valve to "A" OTSG.

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # 789 Page 41L of 51L~

-- ~*~*~----- ~~~--~

Event

Description:

Loss of Feedwater, ATWS, EFW Control Valves Fail, LOHT, HPI Pumps Fail Time Position Applicant's Actions or Behavior Examiner's Note: If conditions are met for Step 3.8 the CRS will transition to OP-TM-EOP-009, HPI Cooling. These steps are located on Page 42 If conditions are met for Step 3.9 the crew will attempt to feed the OTSGs with a Condensate Booster Pump lAW Attachment 1 of OP-TM-EOP-004. The steps of Attachment 1 are located on Page 50 ARO Step 3.8: IAAT RCS pressure approaches 2450 psig (or 527 psig if < 329°F}, and feedwater is not available, then GO TO EOP 009 "HPI COOLING".

Step 3 . 9: If all of the following conditions are met:

- A Condensate Booster Pump is On

- At least one RCP is On CRS - An OTSG is intact; then PERFORM Attachment 1, "OTSG Feed Using a Condensate Booster Pump", to the ARO.

I Footnote: 1- RC-V-2: PORV Isolation Valve.

Appendix D Operator Action Form ES-D-2 Op Test No.: _ _ Scenario # 4 Event # --'7;..:..,8;;..:.,9.;.....____ Page 42l of .....;5;....;..1;..;.Ii _ ____,

Event

Description:

Loss of Feedwater, ATWS, EFW Control Valves Fail, LOHT, HPI Pumps Fail Time I Position I Aj>Qiicant's Actions or Behavior OP-TM-EOP-009, HPI COOLING URO IAAT SCM< 25°F, then perform the following:

1. PERFORM Rule 1

2. CONTINUE with EOP-009 URO Step 3 . 2: Ensure RC-V-2 is OPEN by the red light lit, green light not lit (CC).

URO Step 3.3: 4 psig ESAS has been initiated lAW OP-TM-642-902, "4 psig ESAS Actuation".

Booth Note: Ensure MU-P-1A and 1C do not start on 4 psig ESAS and that MU-P-1 B trips as soon as the ES signal is actuated.

Examiner's Note: Due to no Makeup Pumps operating, the crew will recognize that HPI is not adequate.

Step 3.4: Verify Adequate HPI.

URO RNO: Go to Section 4.0.

OP-TM-EOP-009, Section 4.0: Inadequate HPI CT-13 Step 4.2.1: IAAT RCS pressure approaches TS 3.1-1 limit or 2450 psig, then perform the following:

URO

- ENSURE the PORV block is open by the red light lit, green light not lit (CC).

Footnotes: 1 - RC-RV-2: Pressurizer Pilot Operated Relief Valve.

2- RC-V-2: PORV Isolation Valve.

3 - MU-P-1 A: "A" Makeup (HPI) Pump 4- MU-P-18: "8" Makeup (HPI) Pump 5 - MU-P-1 C: "C" Makeup (HPI) Pump Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # 789 Page 431 of 511',

--'--- ~*~*~----- -~----~

Event

Description:

Loss of Feedwater, ATWS, EFW Control Valves Fail, LOHT, HPI Pumps Fail Time I Position I Applicant's Actions or Behavior CT-13 Step 4.2.2: IAAT RCS pressure approaches TS 3.1-1 limit or 2450 psig, then perform the following:

URO - OPEN the PORV (RC-RV-2) by turning the Control Switch to the open position, verifying MAP alarms G01 06 and G01 07 are in alarm and flow is indicated on the CC meter.

CT-13 Step 4 . 2.3: IAAT RCS pressure approaches TS 3.1-1 limit or 2450 psig, then perform the following:

URO - When RCS pressure is reduced to -1750 psig, or approaches 25 oF SCM, then CLOSE the PORV.,

verifying MAP alarms G01 06 and G01 07 are not in alarm and no flow is indicated on the CC meter.

Examiner's Note: The URO will perform the above three steps, as necessary, each time the IAAT conditions are met.

Step 4.3: Ensure either the PORV or PORV block valve is URO Closed.

Step 4.4: Ensure the following RCS Vent Valves are CLOSED by observing the valve positions (PCR):

- RC-V-28 or RC-V-44 URO RC-V-40A or RC-V-41A

- RC-V-408 or RC-V-418

- RC-V-42 or RC-V-43 Footnotes: 1 -RC-V-28: Pressurizer Vent to RCDT Isolation Valve.

3- RC-V-40A: "A" Hot Leg Vent to RCDT and Atmosphere Valve.

4- RC-V-408: "8" Hot Leg Vent to RCDT and Atmosphere Valve.

5- RCN-41A: "A" Hot Leg Vent to RCDT and Atmosphere Valve.

6- RC-V-41 8: "8" Hot Leg Vent to RCDT and Atmosphere Valve.

7- RC-V-42: Reactor Vessel Head Vent to R8 Atmosphere Valve.

8- RC-V-43: Reactor Vessel Head Vent to R8 Atmosphere Valve.

9- RC-V-44: Pressurizer Vent Isolation Valve.

Appendix 0 Operator Action Form ES-0-2 Op Test No.: Scenario# 4 Event # ....;7;..:.;,8::.l-,9~--- Page 44r of _5;;;...;1~1;._*_ ___,

Event

Description:

Loss of Feedwater, ATWS, EFW Control Valves Fail, LOHT, HPI Pumps Fail Time l Position I Applicant's Actions or Behavior Booth Cue: Report to the Control Room as Secondary Auxiliary Operator, "I'm down at the EV-F-30 area and EF-V-528 and EF-V-52D are CLOSED. Do you want me to do anything with these valves?"

Examiner's Note: RC-P-1 B has already been secured.

Step 4 . 5: If SCM 2 25 oF then Shutdown all RC Pumps by rotating the control switch for either pump clockwise, verifying URO the red light is lit, and the green light is not lit for the remaining two RCP's (RC-P-1A and either RC-P-1C or RC-P-10) (CC}_.

Examiner's Note: The URO may deenergize the Pressurizer heaters by taking the Control switch for each bank to "OFF".

Step 4.6: Ensure all pressurizer heaters are de-energized by URO observing the Pressurizer heater indicating lights are not lit (CR).

Step 4.8: IAAT FEE OW ATEA is available to at least one CAS OTSG, then GO TO EOP-004 OP-TM-EOP-004, Lack of Primary to Secondary Heat Transfer Examiner's Note: Steps 3.1 to 3.3 were previously performed.

Step 3.4: IAAT primary-to-secondary heat transfer (PSHT) has CAS been established, then GO TO Step 3.19.

Footnotes: 1 - RC-P-1A: "A" Reactor Coolant Pump 2- RC-P-1 B: "B" Reactor Coolant Pump 3- RC-P-1C: "C" Reactor Coolant Pump Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # _7...~-,8...:..,9.;....__ _ _ Page 451 of ....;5;;...;1....;1- - - 1 Event

Description:

Loss of Feedwater, ATWS, EFW Control Valves Fail, LOHT, HPI Pumps Fail Time I Position I Applicant's Actions or Behavior Step 3.5: IAAT RCS is approaching 25°F SCM, then GO TO CRS EOP-009.

Step 3.6: IAAT RCS pressure approaches 2450 psig (or 592 psig if< 313°F) and FEEDWATER is available, then perform the following:

URO 1. ENSURE PORV block (RC-V-2) is Open.

2. OPEN the PORV (RC-RV-2).

3. When RCS pressure approaches 30°F SCM, or 1750 psig, then CLOSE the PORV.

Step 3.7: IAAT FEEDWATER is available, then GO TO Step CRS 3.10.

Step 3.11: IAAT OTSG pressure< 750 psig, then DEFEAT ARO HSPS Lo-Lo Pressure MFW Isolation.

Step 3.12: IAAT all RCPs are Off, then INITIATE Guide 7, URO "RCP Restart".

Step 3.13: REDUCE OTSG Pressure so that secondary Tsat is ARO 40 to 60°F lower than incore thermocouple temperature.

Examiner's Note: Step 3.14 is N/A Step 3.15: REDUCE OTSG Pressure so that secondary Tsat is ARO 90 to 100°F lower than incore thermocouple temperature.

CT-26 Step 3.16: RAISE OTSG level to 75 to 85% Operate Range ARO with EFW.

Footnotes: 1 - RC-V-2: PORV Isolation Valve.

2 - RC-RV-2: Pressurizer Pilot 0 erated Relief Valve.

Appendix D Operator Action Form ES-D-2 Op Test No.: _7;....:..,8;;..:.,9.;;....__ _ _ Page 46l of ....;5;;..;1....;11_ _--i

- - Scenario # 4 Event #

Event

Description:

Loss of Feedwater, ATWS, EFW Control Valves Fail, LOHT, HPI Pumps Fail Time I Position I Applicant's Actions or Behavior OP-TM-EOP-01 0, RULE 4, Feedwater Control Step 1: If EFW is actuated, then VERIFY two or more EFW pumps are running.

N/A RNO: If only EF-P-2A or EF-P-28 are operating, then MAINTAIN flow to OTSGs < 515 gpm.

Examiner's Note: SCM can only be determined by the PPC when the RCP's are secured and Natural Circulation has not been verified per OS-24, Conduct of Operations During Abnormal and Emergency Events:

If any of the following conditions exist:

o All RCPs are shutdown and natural circulation has not been verified in both loops o Tl-977 and Tl-978 are not valid o Tl-977 or Tl-978 {SCM indication) is less than 25F and hot leg temperature is changing rapidly (i.e.

immediately after a reactor trip or temperature lowering at greater than 900 F/HR),

then USE incore subcooling margin C4008 (or C4132).

Otherwise, USE the most conservative subcooling margin indicator on PCL (TI-977 or Tl-978).

Step 2: Verify SCM > 25°F or OTSG level between 75 to 85%

ARO Operating Range Level by observing that SCM is greater than 25°F on the PPC.

CT-26 Step 3: Verify the OTSG is not dry.

RNO: If Primary to Secondary Heat Transfer is not available to ARO either OTSG, then initiate FW as follows:

- If EFW is not available, then MAINTAIN MFW flow< 0.2 Mlb/HR I OTSG.

END Footnotes: 1 - EF-P-2A: "A" Motor Driven Emergency Feedwater Pump 2 - EF-P-28: "8" Motor Driven Emer enc Feedwater Pum Appendix D Operator Action Form ES-D-2 Op Test No.: ___;__ Scenario # 4 Event # 789 Page 471 of 51r

~*~*~----- ~~----~

Event

Description:

Loss of Feedwater, ATWS, EFW Control Valves Fail, LOHT, HPI Pumps Fail Time l Position I Applicant's Actions or Behavior Examiner's Note: The ARO should report to the CRS the status of Feedwater and direct the Auxiliary Operator to open one or both EF-V-52 valves and restore feedwater to at least one dry OTSG. The crew will continue in OP-TM-EOP-009 until they reach Step 4.8 at which time they verify feedwater is available and re-enter OP-TM-EOP-004.

With feedwater restored to an OTSG there is a possibility of losing Sub Cooling Margin. If this occurs the crew will take one of the following three paths based on procedural guidance:

If the crew is in OP-TM-EOP-004 when approaching loss of SCM, the procedure directs them to OP-TM-EOP-009.

If the crew is in OP-TM-EOP-009 at the time SCM is lost, the procedure directs them to perform OP-TM-EOP-01 0 Rule 1 and then remain in EOP-009.

If SCM is lost when the crew is in any other procedure or plant condition, they will enter OP-TM-EOP-002.

OP-TM-EOP-002, Loss of 25°F Subcooling Margin ARO Step 2.1: Perform Rule 1, LSCM OP-TM-EOP-01 0, Rule 1, LSCM Step 1: VERIFY it has been more than two minutes since RCP ARO start.

Step 2: ENSURE all RCPs are shutdown within one minute by performing the following:

IAAT a RCP cannot be secured from the Console, then de-energize 1A 6900v and 1B 6900v busses.

URO

ENSURE RC-P-1A is OFF .

ENSURE RC-P-1 B is OFF .

ENSURE RC-P-1C is OFF .

ENSURE RC-P-1 Dis OFF .

Footnotes: 1 - RC-P-1 A: "A" Reactor Coolant Pump 2 - RC-P-1 8: "B" Reactor Coolant Pump 3 - RC-P-1 C: "C" Reactor Coolant Pump 4- RC-P-1 D: "D" Reactor Coolant Pump Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # _7;....:.,8=*.;;...9_ _ _ Page 481 of ....;5;..;1...:....1- - - 1 Event

Description:

Loss of Feedwater, ATWS, EFW Control Valves Fail, LOHT, HPI Pumps Fail Time I Position J Applicant's Actions or Behavior Step 3: INITIATE 4 # ESAS Actuation lAW OP-TM-642-902 4#

URO ESAS Actuation.

Step 4: INITIATE OP-TM-424-901, "Emergency Feedwater" URO and FEED lAW Rule 4.

Examiner's Note: OP-TM-EOP-002Steps 3.1 through 3.5 will beN/A OP-TM-EOP-002, Loss of 25°F Subcooling Margin Step 3 . 6: REQUEST SM evaluate Emergency Action Levels CRS (EALs).

ARO Step 3 . 7: ENSURE performance of an alarm review.

URO Step 3.8: Verify all Reactor Coolant Pumps are shutdown.

Step 3.9: VERIFY one of the following exists:

SCM> 25 °F, CRS

ADEQUATE HPI.

RNO: GO TO Section 4.0, Rapid RCS Cooldown Examiner's Note: Steps 4.1 and 4.2 will not be performed during this scenario.

Step 4.3: IAAT OTSG pressure < 750 psig, then DEFEAT ARO HSPS Lo Lo Pressure MFW Isolation.

Step 4.4: RAISE OTSG Operate Range level to 75 to 85%

ARO using EFW.

Examiner's Note: The scenario can be terminated when an OTSG is being fed by feedwater to > 6" on Startup Range instruments.

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

Scenario# 4 Event# _7'-' -"-'8'"'-9_ _ _ _ Page 49l of _5;;...;1~1.'-*- - - 1 Event

Description:

Loss of Feedwater, ATWS, EFW Control Valves Fail, LOHT, HPI Pumps Fail Time I Position I Applicant's Actions or Behavior Follow-up question: What was the highest event entered during scenario?

Answer:

MA2 due to:

1. Automatic Reactor Trip was unsuccessful and Manual Reactor Trip was successful.

OR FA1 due to:

1. Loss of SCM or HPI/ PORV Cooling Used.

Appendix D Operator Action Form ES-D-2 Op Test No.: _ _ Scenario # 4 Event # 789 Page 50r of 51 [

~*~*~----- -~~--~

Event

Description:

Loss of Feedwater, ATWS, EFW Control Valves Fail, LOHT, HPI Pumps Fail Time I Position I Applicant's Actions or Behavior OP-TM-EOP-004, ATTACHMENT 1, OTSG feed using a Condensate Booster Pump N/A Step 1.: IAAT EFW is recovered, then perform: N/A Step 2: Ensures CLOSED the following:

ARO

- FW-V-16A by observing the FW-V-16A Bailey Station indicator at zero (CC).

- FW-V-16B by observing the FW-V-16B Bailey Station indicator at zero (CC).

ARO Step 3: Maintains TSDT lAW Guide 14 CT-26 Step 4: Opens FW-V-6 by pressing the red open pushbutton ARO and observing the red open pushbutton lit, green closed

_pushbutton closed (CL).

CT-26 Step 5: When OTSG Pressure < 750 psig, then defeats OTSG Lo-Lo Pressure MFW Isolation by pressing the Lo-Lo Pressure ARO MFW Isolation bypass pushbuttons and observing the amber lights for each are lit (CC and CL).

CT-26 ARO Step 6: When OTSG Press <600 psig, then Feeds lAW Rule 4.

Step 7: Throttle MS-V-3's to maintain OTSG Press 500-600 psig by adjusting the toggle switch on each Turbine Bypass ARO Valve Bailey Station in either the upward or downward direction, as necessary, to maintain proper OTSG pressure.

Step 8: IAAT FEEDWATER is not available, then perform the following:

N/A A. ENSURE CLOSED MS-V-3's.

B. ENSURE CLOSED MS-V-4's.

C. GO TO Step 3.5.

Footnotes: 1 - FW-V-16A: "A" Feedwater Startup Control Valve 2- FW-V-16B: "B" Feedwater Startup Control Valve 3- FW-V-6: Main Feedwater Pump Bypass 4- MS-V-3's: Turbine Bypass Valves 5- MS-V-4's: Atmospheric Dump Valves Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario# 4 Event# 7,8,9 Page 511 of 511 Event

Description:

Loss of Feedwater, ATWS, EFW Control Valves Fail, LOHT, HPI Pumps Fail Time I Position I Applicant's Actions or Behavior

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Initiation Acceptance Administration Questions Answers Results Approval... Other: ML14141A104, ML14141A107, ML14143A127
MONTHYEAR2014-03-04 [Table View]

ML14141A107

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