ML083190208

Final - Section B Operating Exam (Folder 3)

ML083190208
Person / Time
Site:	Limerick
Issue date:	12/05/2008
From:	Caruso J Operations Branch I
To:	Hunter J Exelon Generation Co
Hansell S
Shared Package
ML081060533	List: ML081840059 ML082890027 ML083181193 ML083181203 ML083181214 ML083181220 ML083190087 ML083190102 ML083190115 ML083190201 ML083190208 ML083190217 ML083220002 ML083520040 ML083650196 ML090260031
References
TAC U01745
Download: ML083190208 (93)

Text

NRC JPM A 2008 Limerick Operating Exam NRC JPM A - 2008 Limerick Operating Test

Appendix C Job Performance Measure Form ES-C-I

- Worksheet Facility: Limerick Task

Title:

Perform Reactor Startup Job Performance Measure: NRC JPM A K/A

Reference:

201001 A2.04 (3.8, 3.9)

Examinee: NRC Examiner:

Date:

Method of testins:

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:

Unit 1 is at 3% power and RPV pressure is 157 psig RPV level is 35 inches, being controlled by LIC-120 in automatic 0 A plant startup is in progress per GP-2, Appendix 1, Reactor Startup and Heatup Control rods are being withdrawn per Control Rod Move Sheet Sequence 1D: LGS Sim U-1.O on Step 17 The next rod move step is to withdraw Control Rod 10-43 There are no channel bow rods Initiating Cue:

You are the Reactor Operator. You have been directed to continue with the startup by withdrawing control rods in accordarice with the control rod move sheet.

Required Materials:

None General

References:

ON-107, CRD Problems ARC-MCR-108-F1, CRD Accumulator Trouble ARC-MCR-108-G4, CRD Drive Water Filter Hi Delta P ARC-MCR-108-H4, CRD Charging Water Low Pressure TS 3.1.3.5, Control Rod Scram Accumulators GP2 Appendix 1, Reactor Startup and Heatup, Revision 37 S46.6.C, Placing Alternate Control Rod Water Filter In Service, Revision 08 JPM Origination: New NRC JPM A - 2008 Limerick Operating Test 2 of 1 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard:

Address the loss of CRD flow per ON-107 and respond to the subsequent resulting failure of two scram accumulators by tripping the reactor.

Alternate Path: Yes Time Critical: No Validation Time: 15 minutes JPM Setup Instructions:

Summary Description of JPM:

The applicant will continue the startup by withdrawing control rods per the move sheets.

The CRD drive water hi d/p annunciator will alarm 2 minutes after first rod notch out. The applicant respond per ARC and ON-107 and will direct placing the alternate drive water filter in service. Subsequently, the alternate drive water filter will also clog. During troubleshootinglinitial response, alarms will be received for low CR accumulator pressure.

An EO will be dispatched and will report of low nitrogen pressure in the CR accumulator. A second accumulator will exhibit the same symptoms shortly thereafter. The applicant will respond per ON-I07 and ultimately initiate a manual reactor scram.

Simulator Setup:

1. Reset to a startup IC at RPV pressure of approximately 157 psig with 1A CRD Pump in operation.

2. Set up Trigger 1 to activate on depressing Control Rod Notch Out Pushbutton C1 I A -

S46 on 1OC603 Panel (WLCSWDR).

3. Set up a Manual Trigger 2 to time down for accumulator troubles.

4. Set up to actuate the drive water dip alarm (108 G-4) 1 minute after Trigger 1 is activated by closing the running CRD pump discharge valve using the remote function.

5. Set up Malfunction MRC0016C for CR 22-35 Accumulator at 1 minute after Trigger 2 is activated.

6. Set up Malfunction MRCOO16C for CR 46-19 Accumulator at 2minutes 45 seconds after Trigger 2 is activated.

NRC JPM A - 2008 Limerick Operating Test 3 OS11

Appendix C Job Performance Measure Form ES-C-1

- Worksheet Simulator Tables:

NRC JPM A - 2008 Limerick Operating Test 4efll

Appendix C 2 Form ES-C-1 Performance Information Critical steps denoted with an asterisk Step Element Standard Comment I SatlUnsat NOTCH withdraw control Notch withdraws CRs 10- Note:

rods per CR Move Sheet 43, xx-xx and xx-xx from Trigger 1 activates to start 1 Seq 1D: LGS Sim U - I .O. 04 to 06. CRD trouble timing when notch withdraw Dushbutton is dewessed.

Observes indications of Informs supervisor of high Note:

high d/p, clogged drive filter d/p and alarm. CRD Pump discharge water filter. valve is closed by remote 2 Cue: Report function on trigger to acknowledged. simulate drive water filter necessary, direct applicant clog.

to resDond to alarm.

Refers to ARC-MCR-108- Refers to ARC. Informs G4, CRD Drive Water Filter supervisor of direction to Hi Delta P enter ON-107.

3 Cue: When informed of ARC direction, hand copy of ON-107 to applicant and direct him/her to perform the actions of ON-107.

IF lA(B)P158, CRD Pump, Directs EO to place Booth operator:

is running but CRD drive alternate drive water filter Respond as EO, obtain flow is insufficient, in service per S46.6.C S46.6.C. After 1 minute, THEN PERFORM one of open discharge valve on the following as applicable: running CRD pump (to 1 PLACE alternate simulate valving in the 1B(A)F204, CRD Drive alternate drive water filter)

Water Filter, in service and report back that per S46.6. C. alternate drive water filter 2 PLACE alternate FV is in service.

4*

1F002B(A), CRD Flow Control Valve, in service Booth operator:

per S46.6. B Aft er another minute, reclose CRD pump discharge valve on ramp to simulate clogging of alternate drive water filter and initiate trigger to time down to accumulator alarms.

NRC JPM A - 2008 Limerick Operating Test 5 of11

Appendix C 2 Form ES-C-1 Performance Information Step Element Standard Comment I SatIUnsat Observes indications of Informs supervisor of high Booth operator:

high d/p, clogged drive filter d/p and alarm. Report that FIN team is water filter. aware of filter problem 5 and is expediting paperwork to replace the filter with hi d/p.

Responds to indications of Informs supervisor. Refers 6 1St failed accumulator. to ARC-MCR-108-F1, CRD Accumulator Trouble.

ARC Actions: Performs ARC actions: Booth operator:

1. Follow Tech. Spec If directed to investigate, 3.1.3.5, pertaining to Refers to TS report back as EO that control rod scram Dispatches EO to HCU cause of accumulator accumulators. 0 Investigates low N2 trouble is low nitrogen

2. Dispatch Operator to 0 Wtr not suspected pressure.

inspect HCU. 0 Chks spade connectors

3. IF Nitrogen pressure low THEN adjust per 547.8.8 AND investigate for leakage.

4. IF water is suspected 7 THEN blowdown instrument block using S47.8.B accumulator pressure reduction section as guidance.

5. IF HCU indications are normal THEN instruct operator to check spade connectors for looseness in HCU transponder box using S47.8.C Attachment 2 as a guide.

NRC JPM A - 2008 Limerick Operating Test 6nfll

Appendix C 2 Form ES-C-1 Performance Information Step Element Standard Comment I SatlUnsat (Responds to 1 Acc Alarm Informs CRS of required Note:

per ON-I 07) actions for single The ARC for accumulator 2.4 IF one CRD scram inoperable accumulator. trouble does not reference accumulator is inoperable, ON-I 07. However, ON-THEN PERFORM the Cue: 107 provides explicit following within 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />s: CRS acknowledges. guidance for addressing

1. RESTORE the accumulator inoperability.

inoperable accumulator The applicant is expected 8

to operable OR to perform ON-107 steps DECLARE associated based on training and the control rod inoperable. fact that the applicant is

2. IF step [I] is not already implementing the completed, THEN TAKE ON procedure for the action to be in at least drive water filter problem.

HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

(Responds to 2"dAcc Contacts EO for local Booth operator:

Alarm per ON-107): evaluation and refers to If directed to investigate, ON-I 07. report back as EO that 2.5 IF more than one cause of accumulator CRD scram accumulator is trouble is low nitrogen inoperable THEN pressure.

PERFORM the following:

2.5.1 DECLARE the Informs CRS to declare associated control rods CRD associated with 2nd inoperable. accumulator inoperable.

10 Cue:

CRS acknowledges.

NRC JPM A - 2008 Limerick Operating Test 7of11

Appendix C 2 Form ES-C-I Performance Information Step Element Standard Comment I Sat/Unsat 2.5.2 IF the control rod Attempts to insert a Note:

associated with any withdrawn control rod one The selected rod will NOT inoperable CRD scram notch. insert. This action is used accumulator is withdrawn, per procedure to define THEN immediately whether or not a CRD VERIFY at least one CRD pump is operating. If pump is operating: attempt is unsuccessful

1. INSERT a withdrawn (and it will be), then control rod one notch. applicant will understand OR NO CRD pumps are

2. IF loss of RMCS operating for the purpose prevents control rod of the subsequent 11 motion, THEN CHECK IFlTHEN step in ON-107.

charging water header pressure 1 1400 psig on Note:

PSH-46*N600, Applicant should p J base "CHARGING WATER hidher determination of PRESSURE" (PX) at CRD pump operating on

• OC603. the second part of this step because there is no loss of the RMCS.

However, a check of the charging water header pressure will reveal low pressure.

~ -~

2.5.3 IF no CRD pump is Not applicable. Reactor operating AND reactor pressure is < 900 psig.

pressure is greater than or equal to 900 psig, THEN PERFORM the following:

1. START at least one CRD pump within 20 minutes 12 OR manually SCRAM the reactor AND PLACE Reactor Mode Switch in

'ISHUTDOW N,"

AND ENTER T-I 00 OR T-101, as atmlicable.

NRC JPM A - 2008 Limerick Operating Test 8 of' 1 I

Appendix C 2 Form ES-C-I Performance Information Step Element Standard Comment I Sat/Unsat 2.5.4 IF no CRD pump is Depresses scram operating AND reactor pushbuttons.

pressure is less than 900 psig, PERFORM the following:

1. Manually SCRAM the

?3* reactor AND PLACE Reactor Mode Switch in "SHUTD0W N,"

AND ENTER T-100

-OR T-101, as a mlicable.

Cue: JPM is complete.

NRC JPM A - 2008 Limerick Operating Test 9 of11

Appendix C 3 Form ES-C-1 Verification of Completion Job Performance Measure: NRC JPM A Examinees Name: -

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Result: Satisfactory/Unsatisfactory Examiners signature and date:

N R C JPM A - 2008 Limerick Operating Test 10 o f 1 1

- Applicant JPM Cue Sheet Initial Conditions:

Unit 1 is at 3% power and RPV pressure is 151 psig RPV level is 60 inches, being controlled by LIC-120 in automatic A plant startup is in progress per GP-2, Appendix 1, Reactor Startup and Heatup Control rods are being withdrawn per Control Rod Move Sheet Sequence 1D LGS Sim U-I .O on Step 17 The next rod move step is to withdraw Control Rod 10-43 There are no channel bow rods Initiating Cue:

You are the Reactor Operator. You have been directed to continue with the startup by withdrawing control rods in accordance with the control rod move sheet.

NRC JPM A - 2008 Limerick Operating Test

NRC JPM 6 2008 Limerick Operating Exam NRC JPM B - 2008 Limerick Operating Test

Appendix C Job Performance Measure Form ES-C-1

- Worksheet Facility: Limerick Task

Title:

Manually Initiate Core Spray Job Performance Measure: NRC JPM B WA

Reference:

295031 EAI.03 (4.4, 4.4)

Examinee: NRC Examiner:

Date:

Method of testins:

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:

0 A seismic event has occurred, resulting in a LOCA with a loss of all offsite power.

0 Reactor has scrammed, all rods inserted, all scram actions have been taken.

0 Reactor vessel water level is minus (-)'l40" on Fuel Zone and lowering.

0 Reactor pressure is 500 psig.

0 Drywell pressure is 17 psig and rising.

D11 and D13 Emergency Diesel Generators have tripped on ground fault.

0 Suppression pool level is 21 feet and slowly lowering.

0 Core spray has failed to automatically initiate.

Initiating Cue:

Shift Supervision directs you to manually initiate Core Spray System per S52.7.A. An additional RO is available to acknowledge alarms. Another RO has been briefed to perform SE-10 LOCA actions when the LOCA signal has been initiated.

Required Materials:

S52.7.A, Manual Initiation After Failure Of Automatic Injection During A LOCA S52.7.8, Core Spray Injection with a Single Operable Pump General

References:

S52.7.A, Manual Initiation After Failure Of Automatic Injection During A LOCA, Rev. 009 332.7.8, Core Spray Injection with a Single Operable Pump, Rev. 9 JPM Origination: Modified Limerick Bank JPM 128, Rev. 000 Task Standard:

NRC JPM B - 2008 Limerick Operating Test 2 ol' 10

-~

Appendix C Job Performance Measure Form ES-C-1 Worksheet Core spray manually initiated and throttled per S52.7.A.

Alternate Path: Yes Time Critical: No Validation Time: 8 minutes JPM Setup Instructions:

Summary Description of JPM:

A major seismic event has occurred, where Loop B Core Spray is the only available injection source during a small LOCA. Loop A LPCl and CS are unavailable due to loss of power to Buses D11 and 013. RHR is unavailable because Loop B RHR Injection Isolatiorl Valves F017B and F017D are jammed closed. A slow suppression pool leak has lowered pool level to less than 22 feet. A large LOCA occurs at the moment the applicant initiates a manual CS initiation signal. Core Spray Pump I D fails to auto start and trips shortly after it is manually started. RPV pressure is low enough (-200 psig) that Core Spray Pump B will be near runout conditions. Per S52.7.8, the applicant must throttle Loop B Core Spray Inboard Valve F037 to maintain core spray flow as close as possible to the maximum of 31 75 gpm while not exceeding the 3175 gpm limit in order to ensure pump runout (which could lead to pump damage) does not occur.

Simulator Setup:

1. Reset to normal at-power IC.

2, Insert the following malfunctions:

a. MHP447B HPCl Aux Oil Pump Trips

b. MRC466 inadvertent Trip of RClC Overspeed Mechanism

c. MSL559 SLC Injection Line Rupture Inside the Drywell

d. MFW244A Reactor Feed Pump A Trip

e. MFW245A Reactor Feed Pump B Trip

f. MFW246A Reactor Feed Pump C Trip

g. MV1237A Reference Leg 1D004A Level Defect at 60 severity

h. MV1237B Reference Leg 1D004B Level Defect at 60 severity

i. MV1237C Reference Leg 1DOO4C Level Defect at 60 severity

j. MV1237D Reference Leg 1D004D Level Defect at 60 severity

k. MCS183D Core Spray Pump I D Fails to Auto Start I. MCSl82D Core Spray Pump 1D Trips

m. MCS184A Core Spray Inboard Valve 1F005 Fails As Is

n. MRH174B RHR Injection Valve (F017B) Fails As Is 0 . MRH174D RHR Injection Valve (F017D) Fails As Is

p. MDG418A Diesel Generator D11 Trips

q. MDG418C Diesel Generator D13 Trips

r. MED261 Loss of Offsite Power

s. MPC257 Supp Pool Leak to Reactor Enclosure at 20,000 gpm severity

t. MRR440A Recirc Loop A Rupture at 2% severity

3. Override annunciators as needed to provide seismic event alarms.

4. Operate SRVs as needed to reduce and control pressure at approximately 500 psig.

5. When indicated RPV level is approximately minus (-)I 40, remove Malfunction MRR440A, Recirc Loop A Rupture.

NRC JPM B - 2008 Limerick Operating Test 3 Ot10

Appendix C Job Performance Measure Form ES-C-7 Worksheet

6. Reduce Malfunction MPC257 severity to 2,000 gpm when indicated suppression pool level is approx equal to 21 feet.

7. Set up Trigger 1 to activate on illumination of Core Spray Loop D LOCA Initiation indicating Lamp E21A-Sl7D on 10C601 Panel ( ZLOBl(7540) ).

8. Set up Malfunction MRR440A, Recirc Loop A Rupture at 50% severity on Trigger 1.

9. Set up Override on D124-G-D Supply Breaker Control Switch in CLOSE on Trigger 1 with 5 second delay to simulate operator performing SE-10 actions on LOCA initiation.

10. Set up Override on IOY202 Reset on Trigger 1 with 7 second delay to simulate operator performing SE-10 actions on LOCA initiation.

11. Acknowledge alarms and freeze simulator.

Simulator Tables:

114.?lfirricrrori Eicrrrrrury MallID MULID 1 Description ~ 2CUneniVdue 1 JavuslVd~~e ] Rmplime I Aclime I Dactime ] Tiig MHP447B HPCl Aux Oil Pump Trips True 000000 000000 000000 0 MRC466 Inadvertent Trip 01 RClC Dverspeed Mechanism True on0000 000000 000000 0 MSL553 SLC lnleclion Line Ruptrne Inside the DryweU True 000000 000000 000000 0 MFW244A Reactoi FeedpumpA Tiip Tiue oooooo oooooo uuueoo n MFW2454 Reactor FadDumD % TIID True 000000 000000 000000 0 MFW2464 Reactor Feedpump C Trip True 00 0000 00 0000 000000 0 MV1237A Releience Leg IDOOM Level Delecl 60 OD00 00 00 00 00 DUO000 G MV1237B Reference Leg lDOO4B Level Delwct 60 000000 000000 000000 0 MV1237C Reference Leg lDO04C Level Delect 60 woo00 0000orJ 000000 0 MVI237D Relererce Leg 1D004D Level Delect 60 0000 00 000000 u00000 0 MCSl83D Core Spray Pump 1D Fails toAuto Star1 1iue oooooo oomao 00000u 0 MCSlB4A Cote Spray lnlectionValva HV52 1F005 Fails CW I S True 00 00 00 00 00 00 000000 0 MAH174B RHR Valve HV51 1F0178 Fails As is True 00 00 00 000000 00Do00 0 MRH174D RHR Valve HV51 1F017D Fails As is True 00 00 00 00 00 oa 000000 0 MDG4184 Diesel Generator D11 Trips True 00 00 00 0000 DO 000000 0 MDG418C Diesel Generator 0 1 3 Trips True 000000 OD 0000 00WD0 0 MED261 Loss of Dflnite Power True 00 00 00 00 00 00 000000 0 MPC257 Leak F i m Suppression Pool (1 100 000 gprnl 2000 OD00 00 00 0000 OOOUOD 0 MRR440A Recirculation Loop4 Rupture 50 0000 00 0000 00 000000 1 MCS lB2D Core Spray Pump 1 D Trips 1iue 0000 00 00 00 00 000000 0 iictuaiwue 1 1 nmptln4c I A O V O I ~ ~ ~ ~ V ~ I U ~ ~ I

~ [Ioctltfis

~ 1 v l ~ ~ ~~ t ~

, 52 20224/CS Saieguaid Bus D124 G D Supply Bleakel Control Swltch CLOSE ON 000005 WOO00 52 20224/CS Saleguaid Bus 0124 G D Supply Breaker Control Switch NACLOSi OFF 000005 000000 1 52202241CS Saleguard Bus D124 G D Supply Breaker Control Switch NATRIP OFF 000005 000000 1 52 20224/CS Safeguard Bus D124 G D SuppC Breaker Contiol Switch TRIP OFF 000005 000000 1 43 22422/CS Bieakei Trip RESET IOI 120VAC Panel 1W202 RESET

__-__ ON 000007 000000 1 NRC JPM B - 2008 Limerick Operating Test 4 of 10

Appendix C 2 Form ES-C-I Performance Inf ormat ion Critical steps denoted with an asterisk t

Step Element Standard Comment I Sat/Unsat TURN collar of the Not applicable following MANUAL INITIATION pushbuttons to ARMED:

a. (INITIATION l ) E21- Rotates core spray manual Not critical since D11 de-S22A initiation pushbutton collar energized.

2 S22A clockwise to the ARMED Dosition.

b. (INITIATION 2) E21- Rotates core spray manual S22B initiation pushbutton collar 3 S22B clockwise to the ARMED Dosition.

C. (INITIATION 3) E21- Rotates core spray manual Not critical since D13 de-s22c initiation pushbutton collar energized.

4 S22C clockwise to the ARMED position.

d. (INITIATION 4) E21- Rotates core spray manual Not critical since CS S22D initiation pushbutton collar Pump D will not auto start 5 S22D clockwise to the on init signal. Must be ARMED position. manually started.

VERIFY the following Not applicable annunciator alarms:

DIV 1 CORE SPRAY DIV 1 and DIV 3 Core MANUAL INITIATION Spray manual initiation SWITCH ARMED switch armed annunciators AND are verified lit on 113 7 DIV 3 CORE SPRAY COOL A.

MANUAL INITIATION SWITCH ARMED, annunciator alarms on *I 3 COOL A DIV 2 CORE SPRAY DIV 2 and DIV 4 Core MANUAL INITIATION Spray manual initiation SWITCH ARMED switch armed annunciators AND are verified lit on 115 8 DIV 4 CORE SPRAY COOL B.

MANUAL INITIATION SWITCH ARMED, annunciator alarms on *I 5 NRC JPM B - 2008 Limerick Operating Test 5 o f 10

Appendix C 2 Form ES-C-1 Performance Information Step Element ~

Standard Comment / SatlUnsat DEPRESS AND RELEASE NIA all four of the following 9 MANUAL INITIATION pushbuttons to initiate Core Spray System: _-

a. (INITIATION 1) E21- Momentarilly depresses Not critical since D11 de-S22A and then releases energized.

10 MANUAL INITIATION pushbutton S22A.

b. (INITIATION 1 ) E21- Momentarilly depresses S22B and then releases 1I

• MANUAL INITIATION pushbutton S22B.

C. (INITIATION 1) E21- Momentarilly depresses Not critical since D13 de-s22c and then releases energized.

12 MANUAL INITIATION nushbutton S22C.

d. (INITIATION 1) E21- Momentarilly depresses Not critical since CS S22D and then releases Pump D will not auto start MANUAL INITIATION on init signal. Must be pushbutton S22D. manually started.

Cue:

13 If necessary, inform applicant that another RO has been directed to perform SE-10 actions upon LOCA signal initiation.

Start the 1D Core Spray Recognizes only 1B Core Pump trips on start.

Pump. Spray started. Informs However, step is critical supervisor and manually since required two-pump 14*

starts I D Core Spray operation could not be Pump. established without attempting a start.

ENSURE the following Determines F031A has no Core Spray Pump power.

minimum flow bypass valves are open: Verifies minimum flow 15 -HV-52-*FU31A, MIN valve HV-52-1F031B is FLOW closed as expected with

-HV-52-*FU31B, MIN flow greater than 775 gpm FLOW after 3 second delay.

NRC JPM B - 2008 Limerick Operating Test 6 of 10

Appendix C 2 Form ES-C-1 Performance Information Step Element Standard Comment I SaWnsat

~~ ~

WHEN Reactor Pressure is Determines following between 435 to 475 psig, actions are required l6 THEN VERIFY the because pressure is following: already less than 435 psig.

HV 52 *F005, Verifies HV-52-1F005 is OUTBOARD, open. open 17 Note: L.oop A pumps are not running so F005 position verification not imDortant.

HV 52 *F037, INBOARD Verifies HV-52-1F037 is l8 DISCHARGE. oDen. 013817.

NOTE: Recognizes only 1B CS Begins Alternate Path Two pump operation is Pump running. Refers to required to prevent pump S52.7.B.

damage due to run out.

IF only one Core Spray Pump in a loop is running, THEN GO TO S52.7.8, Core Spray Injection with a Single Operable Pump.

IF single operable Core Not applicable. CS Pump Spray Pump in loop is not operation is essential.

essential to maintain reactor level, 2o THEN PERFORM the following:

1. TRIP pump

2. EXIT procedure IF single operable Core Verifies pump has not run Note: SP level indicated Spray Pump in loop is > I hr. Verifies SP temp on L152-140A at 1OC626 essential to maintain ~ 1 9 8 ° F .Determines SP will continue to indicate reactor level, level is NOT > 22 feet. 23.6 due to the power THEN VERIFY all three of failures. Applicant will the following conditions for Informs supervisor that all need to realize this is not operation are satisfied: three conditions are NOT a valid indication based 21 1. Pump is run no longer met. Pool level is c22 feet. on LR55-115 at 10C648 than one hour. (20.8) and also plant

2. Suppression pool computer (21) temperature less than 198°F.

3. Suppression pool level greater than 22 feet.

NRC JPM B - 2008 Limerick Operating Test 7 of 10

-Appendix C 2 Form ES-C-?

Performance Information Step Element Standard Comment I Sat/Unsat IF all three conditions are Requests approval to not met, throttle HV-52-1 F037 to THEN OBTAIN SSV 3175 gpm on FI approval 1R6016, FL, at panel AND THROTTLE HV 52 1OC601.

• F005(A Loop)/HV -

AND

'** *F037(0Loop), Throttles flow to ~ 3 1 7 5 DISCHARGE to less than gpm.

3,775 gpm on FI 52

• RGOIA(B), FL, at panel [Acceptable range is 2900

• OC601. gpm to 3175 gpm]

Cue: JPM is comdete.

NRC JPM B - 2008 Limerick Operating Test 8 oil0

Appendix C 3 Form ES-C-?

Verification of Completion Job Performance Measure: NRC JPM B Examinee's Name:

Examiner's Name: --

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SatisfactorylUnsatisfactory Examiner's signature and date:

NRC JPM B - 2008 Limerick Operating Test 9 Of'lO

Applicant JPM Cue Sheet Initial Conditions:

A seismic event has occurred, resulting in a LOCA with a loss of all offsite power Reactor has scrammed, all rods inserted, all scram actions have been taken.

Reactor vessel water level is minus (-)140 on Fuel Zone and lowering.

Reactor pressure is 500 psig.

Drywell pressure is 17 psig and rising.

D11 and D I 3 Emergency Diesel Generators have tripped on ground fault.

Suppression pool level is 21 feet and slowly lowering.

Core spray has failed to automatically initiate.

Initiating Cue:

Shift Supervision directs you to manually initiate Core Spray System per S52.7.A.

An additional RO is available to acknowledge alarms. Another RO has been briefed to perform SE-10 LOCA actions when the LOCA signal has been initiated.

NRC JPM B - 2008 Limerick Operating Test

NRC JPM C 2008 Limerick Operating Exam NRC JPM C - 2008 Limerick Operating Test

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

Title:

Open An MSlV Job Performance Measure: NRC JPM C WA

Reference:

239001 A2.03 (4.0, 4.2)

Examinee: NRC Examiner:

Date:

Method of testing:

Simulat ed 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:

0 Unit 1 is at 35% power.

Outboard MSlV HV-41-1 F028B closed due to a rupture of the air exhaust line from the MSIV.

The MSlV air exhaust line has been repaired.

A second RO is available to monitor reactor power.

Initiating Cue:

You have been directed to open the MSlV per 541.3.8.

Required Materials:

None General

References:

S41.3.B, Reopening A Single Isolated MSIV, Revision 11 JPM Origination: New Task Standard:

Reopen a spuriously closed MSlV at power Alternate Path: No Time Critical: No Validation Time: 8 minutes JPM Setup Instructions:

NRC JPM C - 2008 Limerick Operating Test 2 of10

_ _ ~

Appendix C Job Performance Measure Form ES-C-1 Worksheet Summary Description of JPM:

The applicant will open the MSIV in accordance with 541.3.8.

Simulator Setup:

1. Reset to approximately 35% power.

2. Insert Malfunction MMS064B to fail closed Inboard MSIV HV-41-1F022B

3. Place HV-41-1F028B in TEST on 1OC601.

4. Remove Malfunction MMS064B.

5. Allow plant to stabilize.

6. Place simulator in Freeze.

NRC JPM C - 2008 Limerick Operating Test 3 of. 10

Appendix C

- 2 Form ES-C-1 Performance Information Critical steps denoted with an asterisk Step Element Standard Comment I SatlUnsat CAUTION Informs HP.

Steps 4.3.2 through 4.3.9 removes condensate from Cue:

Main Steam lines prior to HP has been notified.

opening MSlV @ l placing J

Main Steam line inservice, AND may change dose 1 rates in the vicinity.

(Step 4.3.1)

INFORM HP that the valves listed in step 4.3.2 will be operated AND another steam flow path is being established.

(Step 4.3.2)

ENSURE alignment of the 2 following Main Steam System valves at panel "OC601:

0 HV-C-41-*F020, Main Ensure HV-C-41-1F020 is Steam Line Pressure open.

3*

Equalizing Valve -

OPEN 0 HV-41-*42 Bypass Ensure HV- 41-142 is 4* Leakage Barrier Block open.

OPEN HV-41-*43 Bypass Ensure HV- 41-143 is 5* Leakage Barrier Block open.

OPEN NRC JPM C - 2008 Limerick Operating Test 4 01'10

Appendix C

- 2 Form ES-C-I Performance Information Step Element Standard Comment I SatlUnsat CAUTION Reactor power must be closely monitored while performing steps 4.3.3 through 4.3.12.

(Step 4.3.3)

ALIGN the following Main Steam System valves to drain condensate from upstream AND downstream piping around outboard MSlV at panel

• OC601:

HV-41-*F016, Main Opens HV-41-1F016.

7" Steam Drain -OPEN 0 HV-41-*FO19, Main Opens HV-41-1 FO19.

8*

Steam Drain - OPEN 0 HV-41-*F021, Main Opens HV-41-1 F021.

9 Steam Drain To Cond -

OPEN (Step 4.3.4) Opens HV-01-104 at Panel OPEN HV-01-*04, Main 1OC653.

IO* Steam Line Startup Drain (STARTUP DRAIN), at Dane1 *OC653.

NRC JPM C - 2008 Limerick Operating Test 5 o f 10

Appendix C 2 Form ES-C-'1 Performance Information Step Element Standard Comment I SatlUnsat NOTE Cue:

S06.1 .I U/*, Accessing If asked, inform applicant Information At The that MSlV was NOT Feedwater Level Control ' isolated IAW S41.3.C.

System Operator Station, provides directions on how to access screens at FWLCS Operator Station.

CAUTION

1. Only equipment associated with the main steam line with the MSlV 11 being reopened is to be operated.

2. MSIV's are designed to open with no more than 200 psid.

(Step 4.3.5)

IF MSlV was not isolated in accordance with S41.3.C, Isolation of One Main Steam Line at Power (i.e.

unplanned MSlV closure),

THEN PERFORM the following:

1. DEPRESS white Depresses SINGLE SINGLE pushbutton on pushbutton on LIC-MI-LIC-MI-*R600, Reactor 1R600 on 1OC603 12*

Level Controller (MASTER, LV), at panel

• OC603.

2. VERIFY white SINGLE Verifies SINGLE pushbutton is lit on LIC- pushbutton is lit.

M I -*R600, Reactor 13 Level Controller (MASTER, LV), at panel

• OC603.

3. MARK steps 4.3.6.1, Marks steps as NIA.

14 4.3.6.2 and 4.3.6.3 as N/A AND CONTINUE.

NRC JPM C - 2008 Limerick Operating Test 6 oS10

Appendix C 2 Form ES-C-1 Performance Information SteD Element Standard Comment I SatIUnsat (Step 4.3.6) Not applicable.

VERIFY MSlV Test Mode 15 is activated at FWLCS Operator Station as follows.. .

NOTE Closes HV-41-1F022B The outboard MSlV should (INBOARD) at Panel be opened soon after 1OC601.

inboard MSlV is fully closed.

16*

(Step 4.3.7)

CLOSE HV-41-*F022A(B, C, D), Inboard MSIV, at panel *OC601.

(Step 4.3.8) Places handswitch in OPEN HV-41-*F028A( B, C, AUTO for HV-41-1F028B 17* D), Outboard MSIV, at (OUTBOARD) at Panel panel *OC601. 1OC601 Observes valve open.

(Step 4.3.9) Cue:

WAIT 5 to 10 minutes 10 minutes have elapsed.

18 before proceeding to the next step to allow condensate to drain.

(Step 4.3.10) Places handswitch in OPEN HV-41-*F022A(B, C, AUTO for HV-41-1F022B 19* D), Inboard MSIV, at panel (INBOARD) at Panel

• OC601. 1OC601. Observes valve oDen.

(Step 4.3.1 1)

ALIGN the following Main Steam System drain 20 valves, unless otherwise directed by GP-2, Normal Plant Startup, at panel

• OC601:

0 HV-41-*F016, Main Closes HV-41-1F016.

21*

Steam Drain- CLOSED HV-41-*F019, Main Closes HV-41-1FO19.

22*

~

Steam -~Drain - CLOSED ~

0 HV-41-*F021, Main Closes HV-41-1 F021 23* Steam Drain To Cond -

~

CLOSED NRC JPM C - 2008 Limerick Operating Test

Appendix C 2 Form ES-C-1 Performance information Step Element Standard Comment I SatlUnsat (Step 4.3.12) Closes HV-01-104 at Panel CLOSE HV-01-*04, Main 1OC653.

24* Steam Line Startup Drain (STARTUP DRAIN), at panel *OC653.

NOTE S06.1.I U/*, Accessing Information At The Feedwater Level Control System Operator Station, provides directions on how to access screens at FWLCS Operator Station.

CAUTION IF MSlV Test Mode is deactivated with an inboard 25 MSIVOR outboard MSlV closed, THEN an RPV level transient will occur.

(Step 4.3.13)

IF MSlV was not isolated in accordance with S41.3.C, Isolation of One Main Steam Line at Power (i.e.

unplanned MSlV closure),

THEN PERFORM the following:

1. DEPRESS white THREE Depresses THREE pushbutton on LIC-MI- pushbutton on LIC-MI-26* *R600, Reactor Level 1R600 on Panel 1OC603.

Controller (MASTER, LV), at panel *OC603.

2. VERIFY white THREE Verifies THREE pushbutton is lit on LIC- pushbutton is lit.

Ml-*R600, Reactor 27 Level Controller (MASTER, LV), at panel

• OC603.

3. MARK step 4.3.14 as Marks the step N/A.

28

~~ ~

N/A AND CONTINUE Cue: JPM is complete. -

NRC JPM C - 2008 Limerick Operating Test 8 oflo

Appendix C 3 Form ES-C-1 Verification of Cornplet ion Job Performance Measure: NRC JPM C Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

NRC JPM C - 2008 Limerick Operating Test 9 of10

- Applicant JPM Cue Sheet Initial Conditions:

0 Unit 1 is at 35% power.

0 Outboard MSlV HV-41-1F028B closed due to a rupture of the air exhaust line from the MSIV.

0 The MSlV air exhaust line has been repaired.

0 A second RO is available to monitor reactor power.

Initiating Cue:

You have been directed to open the MSlV per S41.3.B.

NRC JPM C - 2008 Limerick Operating Test

NRC JPM D 2008 Limerick Operating Exam NRC JPM D - 2008 Limerick Operating Test

Appendix C 2 Form ES-C-1 Performance Information Facility: Limerick Task

Title:

Manually Start HPCl Job Performance Measure: NRC JPM D WA

Reference:

206000 A2.06 (3.3, 3.5)

Examinee: NRC Examiner:

Date:

Method of testing:

SimuIated 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:

e Unit 1 is at 100% power e No equipment is out of service 0 Steam Leak Detection System is available e Suppression Pool Cooling is in service e HPCl Oil Reservoir is filled to high in the normal operating range on sightglass e HPCI is lined-up for automatic operation per S55.1 .A e Reactor Enclosure Equipment Compartment Exhaust is in service e ST-6-060-390-1 is currently being performed by the Reactor Operator e No maintenance has been performed on the Turbine oil system or governor control system e No water was drained from any part of the system e The Vibration Monitoring System is in service Initiating Cue:

You are directed by Shift Supervision to place Unit 1 HPCl in full flow test, CST to CST, with pump discharge pressure at least 120 psig greater than reactor pressure, using the manuai quick start method for a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> PMT per S55.1.D.

Required Materials:

S55.1 .D, HPCl System Full Flow Functional Test, Rev. 34, with prerequisites signed off.

GeneraI Refe ren ces :

S55.1.D, HPCI System Full Flow Functional Test, Rev. 34 HU-AA-104-101, Procedure Use and Adherence, Rev 03 NRC JPM D - 2008 Limerick Operating Test Page 2 of'9

Appendix C 2 Form ES-C-1 Performa nce Info rmation JPM Origination: Modified Limerick Bank JPM 19 Revision 008 Task Standard:

Starts HPCl in full flow test (CST to CST) lineup, with pump discharge pressure at least 120 psig greater than reactor pressure, using manual quick start method. Trips turbine within 3 minutes after start due to lack of min flow protection.

Alternate Path: Yes Time Critical: No Validation Time: 7 minutes JPM Setup Instructions:

Summary Description of JPM:

The applicant is directed to perform full flow HPCl test from CST back to CST. Helshe will partially align HPCl full flow path back to CST by opening Condensate Return Valve HV 1FOI 1. Min Flow Valve HV-55-1 F012 is in normal pre-start closed position, but is failed as-is, such that it will not open when demanded by pump discharge pressure >I25 psig and pump flow 6 5 0 gpm. The applicant will start the HPCl turbine and, per procedure, will attempt to open HPCl Test Loop Shutoff HV-55-1F008 to establish full flow conditions.

However, the valve is thermally bound and will not open. The applicant will announce unexpected indications and will attempt to open Min Flow Valve HV-55-1 F012. Per precautions, HPCl is not allowed to run without min flow protection for greater than 60 seconds. The applicant will recognize the challenge to this limitation and trip the HPCl turbine within 3 minutes from the time pump discharge pressure exceeds 125 psig.

The 3 minute time limit was established based on a response time of no more than 3 times the value stated in the precaution. A 3 minute response is reasonable as a maximum acceptable time, given the procedural emphasis on actions to attempt to open the F008 full flow line isolation valve. As soon as the applicant realizes F008 is not going to open, it is expected they will assess the pump alignment, determine the min flow valve is closed and trip the HPCl pump.

Simulator Setup:

1. Reset to a full power IC

2. Place Suppression Pool Cooling in service

3. Place B Loop ESW in service

4. Override HPCl Min Flow Valve HV55-1FO12 indicating lights (green-ON, red-OFF) to indicate valve closed.

5. Override HPCl Test Bypass to CST, HV55-1 F008 handswitch to PTS.

6. Override HPCl Pump Disch Pressure Indication (P155-1R601) to 1500 on trigger 1.

7. Activate trigger Ion HPCl speed 2 4500 (HPNT >= 4500).

8. Acknowledge alarms and freeze simulator.

NRC JPM D - 2008 Limerick Operating Test Page 3 o f 9

~

Appendix C 2 Form ES-C-1 Performance Information Critical steps denoted with an asterisk Step Element Standard Comment I SatlUnsat IF required to limit Not applicable Suppression Pool temperature anytime during this procedure, then refer to S51.8.A Suppression Pool Cooling Operation (Startup and Shutdown) and Level Control, and PLACE Suppression Pool Cooling Mode of RHR System in Service If Vibration Monitoring Not applicable System is available, then verify in service 2

Cue: Vibration Monitoring system is in service.

Ensure the following valves Verifies valves closed by are CLOSED: position indication:

HV-55-1F071, "HPCIIRCIC Green lights ON Flush Line to Suppression Red lights OFF Pool" (TEST OUTBOARD)

HV-55-1F008, "Test Loop 3 Shutoff" (TEST ISOL)

HV-55-1FOI 1, "HPCVRCIC Test Return to CST" (CONDENSATE RETURN) 0 HV-49-1 F022, "RCIC Test Loop Isolation"(TEST ISOL)

Open HV-55-*F011, Places handswitch in 4* Condensate Return. OPEN. Observes valve indicates full open.

START 1OP0216, Takes handswitch to start.

" Baromet r ic Condenser 10P216 indicates running.

Vacuum Pump" (VACUUM PUMP).

NRC JPM D - 2008 Limerick Operating Test Page 4 o f 9

Appendix C 2 Form ES-C-1 Performance Information Step Element Standard Comment / SatlUnsat Monitor Suppression Pool Not applicable.

temperature per ST-6-060-390-1, Suppression Pool Temperature Check.

6 Cue: ST-6-060-390-1 is being performed by an additional operator.

INFORM HP of changing HP notified HPCI start is 7 radiological conditions due imminent.

to HPCl System start.

ENSURE FIC-55-*R600, FIC-55-1R600 MIA selector "HPCI Pump Discharge switch in the "A" position.

8 Flow Controller" (FL), set Flow controller FlC to 5600 gpm in "AUTO" 1R600 set between 5,500 and 5,700 GPM.

Make Plant Announcement Plant Announcement for for HPCI startup. HPCl startup performed.

Simultaneously open HV- Simultaneously positions Examiner Note:

55-1FOOI, "HPCI Steam handswitches. HV Begin timer when FOO1 Supply" (INLET) AND Start IF001 is open and 10P213 handswitch is placed in lo* 1OP213, "Auxiliary Oil is running. OPEN.

Pump" (AUX OIL PUMP).

Start time:

When Sl-56-161, "Turbine Observes speed increase.

Speed" (S), starts to go up, Immediately opens F008 then immediately throttle Valve. Maintains speed >

open HV-55-1F008, "HPCI 2200 rpm.

1I

• Test Loop Shutoff" (TEST ISOL), until desired flow is obtained, while maintaining turbine speed greater than 2,200 rpm. -

NRC JPM D - 2008 Limerick Operating Test Page 5 01'9

Appendix C 2 Form ES-C-1 Performance Information Step Element Standard Comment I SatlUnsat Recognizes pump flow is Observes pump flow is not Note:

not increasing. increasing. Informs Will not be able to supervisor. establish flow because 1F008 is thermally bound Cue: Acknowledge report. and will not move.

Note:

HU-AA-104- 10 1 (Procedure Use and Adherence) Step 3.1.7 12 requires test procedure stopped at current step because procedure cannot be performed as written (cannot get flow to increase) and because continuation would result in an unsafe condition (running pump without min flow).

Attempts to open Min Flow Observes min flow valve Note:

Valve HV-55-1F012. F012 is not open. Informs F012 is failed closed, supervisor. Attempts to however by design it open HV-55-1F012. should automatically open at e550 gpm with disch 13* Cue: Acknowledge report. pressure > 125 psig.

S55.1 .D,Precaution 3.7 states in part, Operator action may be required to open HV-55-1 F012, MIN FLOW valve.

NRC JPM D - 2008 Limerick Operating Test Page 6 019

-~

Appendix C 2 Form ES-C-1 Performance Information Step Element Standard Comment I Sat/Unsat Trips the HPCl turbine. Trips the HPCl turbine Note:

within 3 minutes and 10 Do not allow HPCl to seconds after opening operate without min flow 1Fool Steam Supply protection for greater than Valve. 60 seconds. (S55.1.D, Step 3.7). Takes Cue: applicant approximately 10 seconds recommends tripping HPCl for HPCl discharge turbine, then acknowledge pressure to increase to >

report and direct the 125 psig following the applicant to trip the HPCl positioning of 1FOOI turbine. handswitch to open.

14* Examiner Note:

Stop time:

Elapsed time from 1Fool handswitch operation must be approximately 5 I 9 0 seconds (10 seconds for pump discharge pressure to increase 1 125psigand 180seconds to respond to the abnormal flow indications by tripping the HPCl pump).

NRC JPM D - 2008 Limerick Operating Test Page 7 o 9

Appendix C 3 Form ES-C-I Verification of Completion Job Performance Measure: NRC JPM D Examinees Name: -

Examiners Name: -

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

NRC JPM D - 2008 Limerick Operating Test Page 8 of9

Applicant JPM Cue Sheet Initial Conditions:

Unit 1 is at 100% power No equipment is out of service Steam Leak Detection System is available Suppression Pool Cooling is in service HPCl Oil Reservoir is filled to high in the normal operating range on sightglass HPCl is lined-up for automatic operation per S55.1 .A Reactor Enclosure Equipment Compartment Exhaust is in service ST-6-060-390-1 is currently being performed by the Reactor Operator No maintenance has been performed on the Turbine oil system or governor control system No water was drained from any part of the system The Vibration Monitoring System is in service Initiating Cue:

You are directed by Shift Supervision to place Unit 1 HPCl in full flow test, CST to CST, with pump discharge pressure at least 120 psig greater than reactor pressure, using the manual quick start method for a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> PMT per S55.1 .D.

NRC JPM D - 2008 Limerick Operating Test

NRC JPM E 2008 Limerick Operating Exam NRC JPM E - 2008 Limerick Operating Test

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

Title:

Initiate Containment Spray Job Performance Measure: NRC JPM E WA

Reference:

226001 A4.03 (3.5, 3.4)

Examinee: NRC Examiner:

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:

e The reactor is shutdown due to a large steam leak inside primary containment.

e Reactor water level is being maintained by the RO using S/U level control.

Cooling water is not required to the Post LOCA Recombiners and the HV57-168A valve has been verified closed.

1A and 1B RHR Pumps have both tripped.

Initiating Cue:

You are directed by Shift Supervision to establish to initiate drywell spray using the fire protection system cross-tie per T-225.

Required Materials:

Copy of T-225, Startup And Shutdown Of Suppression Pool And Drywell Spray Operation General

References:

T-225, Startup And Shutdown Of Suppression Pool And Drywell Spray Operation, Rev. 20 JPM Origination: Modified Limerick Bank JPM 32, Rev. 005 Task Standard:

Establish Drywell Spray with Fire Water Alternate Path: No Time Critical: No Validation Time: 10 min JPM Setup Instructions:

NRC JPM E - 2008 Limerick Operating Test 2 of l?

Appendix C Job Performance Measure Form ES-C-1 Worksheet Summary Description of JPM:

The applicant is directed to spray the drywell using fire water. The applicant will perform Section 4.7 to align fire water for drywell spray. This JPM has applicant perform different actions than those performed during Part C scenarios. Use of fire water requires operation of the F0486, F003B and F004B valves and also includes fire protection system verifications.

Simulator Setup:

1. Reset the simulator to IC 17.

2. Insert Steam Leak in Drywell - Malfunction MMS067 at 2000 gprn.

3. The following actions should be taken:

a. Mode switch to SHUTDOWN

b. Insert SRMs & IRMs

c. Line up Condensate System to STARTUP level control with 138A in AUTO

d. Bypass and restore D/W Cooling

4. Reduce the steam leak to 300 gpm when drywell pressure reaches 25 psig.

NOTE: This will keep reactor pressure high enough to prevent the LOCA signal from coming in while the JPM is being performed.

5. Set up Malfunction MRHl71B to trip 1B RHR Pump on Manual Trigger 1.

6. Set up Remote RTR267 for YES to open FW cross-tie on Manual Trigger 2.

7. Acknowledge and reset Alarms and FREEZE the simulator.

Simulator Tables :

k4alf ID MMS067

, ~--,-

Mull ID I -~

Maffrrrrcrtorr Strrrirrwry -I^__-

Descfiplim

~ - - _ _ I -

Steam Leak m Diywell(0 5000 gpm)

~~?.i&t\l&r: --] T.ipetValue 300

-[Rmdime 00oow

] 4ctime- ]

000000 Dactime 000000 1 Trig 0

MRH1718 RHR Pump IS Trips True 0000Do 000000 000000 1 i a y a ,t ,v I im&e- I Acme ] Tiic RTR267 T 225 Fue Wale, Ciorslie to RHR -~ YES 000000 000000 2 NRC JPM E - 2008 Limerick Operating Test 3 of0

~

Appendix C 2 Form ES-C-1 Performance Information Critical steps denoted with an asterisk Ster, Element Standard Comment I SatlUnsat ENSURE the following Refers to Section 4.7 of T-1 valves closed: 225, Fire Water Crosstie.

HV-51-1F004B, 1B RHR Closes valve.

2* Pump Suction PClV (SUCTION B) e HV-51-1 F0068, 1B RHR Verifies valves closed.

Pp S/D Clg Suct Intertie Vlv (SUCTION B) e HV-51-1F015B, 1B Shutdown Clg Injection PClV (OUTBOARD) 3 e HV-51-1F016B, 1B RHR Cntmt Spray Line Outboard PClV (OUTBOARD)

HV-51-1 F017B, 1B RHR LPCl lnj PClV (OUTBOARD)

HV-51-1F024B, 1B RHR Closes valve.

Pp Full Flow Test 4* Return Vlv (SUPP POOL CLG B)

HV-51-1F027B, 1B RHR Verifies valve is closed Supp Pool Spray Line PClV (SUPP POOL SPRAY)

HV-51-1F0476, IB RHR Closes valve.

6* Htx Shell Side Inlet Vlv (INLET)

HV-51-1 F048B, 1B RHR Closes valve.

Htx Shell Side 7* Bypass Vlv (HEAT EXCH BYPASS) 051-1 F098, Cond Trans Fill Directs EO to verify valve lsol Vlv to closed.

8 1A & 1B RHR LOOPS(402-R11-253) Cue:

(ATTACHMENT 6) Valve is closed.

NRC JPM E - 2008 Limerick Operating Test 4of9

Appendix C 2 Form ES-C-1 Performance Info rmation Step Element Standard Comment I SatlUnsat PERFORM the following in Directs EO to perform Booth operator:

402-R16-253 local fire water alignment. Activate Manual Trigger #2 (ATTACHMENT 5): to locally align fire water.

1. CONNECT hose at 51-1 179, 1B RHR Fire Report back as EO that Protection Crosstie fire water aligned as Connection Drain directed.

Valve AND Route to drain THEN CYCLE 51-1 179 open AND closed to ensure piping vented.

2. CONNECT hose at 22-1 430, Fire Protection/RHR Interconnection Drain Valve AND Route to 9*

drain THEN CYCLE 22-1430 open AND closed to ensure piping vented.

3. CONNECT hose to fitting downstream of 22-1429, Fire Protection/RHR Interconnection Isolation Valve.

4. CONNECT other end of hose to 51-1 178, 1B RHR Fire Protection Crosstie Connection Isolation Valve.

5. OPEN 22-1429.

6. OPEN 51-1 178.

NRC JPM E - 2008 Limerick Operating Test 5 of9

-Appendix C 2 Form ES-C-I Performance Infor mation Step Element Standard Comment I SatlUnsat REQUEST SSV verify D/W pressure and Note:

drywell temperature AND temperature readings are Step is critical for SRO drywell pressure are on given to the CRS prior to applicants only.

SAFE side of Drywell Spraying and confirmation Spray Initiation Limit curve is received from the CRS per T-I 02, Primary that it is Safe to spray the Containment Control OR drywell.

SAMP-1, RPV and Primary Containment Flooding Cue for SRO Applicant:

Control. You are directed to 1o* determine if on safe side of Drywell Spray Initiation Curve.

Cue for RO Applicant:

Request drywell temperature and pressure.

After being given D/W temperature and pressure readings, state that it is safe to spray the drywell.

Trip Reactor Recirc Verifies pumps tripped.

Pumps.

REMOVE Drywell Cooling Turns fans OFF.

Fans from service 12* by placing all 16 Drywell Cooler Fan switches to OFF.

MONITOR Drywell Drywell pressure is l3 pressure. observed.

PERFORM the following to 14 initiate LOCA signal for B Loop:

Place E l 1A-S61B, Places switch in ARM.

INITIATION, switch for B 15* Loop operation at panel 1O?C601 (Main Control Room) to "ARM". ~~ ~

DEPRESS AND RELEASE Depresses and releases

~~~~~

16* E l 1A-S61B.

~

switch.

VERIFY LOOP B Verifies white light lit.

17 INJECTION white indicating light Lit.

NRC JPM E - 2008 Limerick Operating Test 6 of 0

Appendix C 2 Form ES-C-1 Performance Information Step Element Standard Comment I SatlUnsat OPEN HV-51-1F021B, I B Per Step 4.7.10, opens RHR Cntmt Spray Line va Ives .

Inboard PCIV, (INBOARD) 18* AND HV-51-1FO16B, 1 6 RHR Cntmt Spray Line Outboard PCIV, (OUTBOARD), at 10C601.

ENSURE OOP512, Motor Verifies Motor OR Diesel Driven Fire Pump, OR OOP511, Diesel Driven Fire Pump, running.

Driven Fire Pump running.

Cue: JPM is complete.

NRC JPM E - 2008 Limerick Operating Test

Appendix C 3 Form ES-C-1 Verification of Completion Job Performance Measure: NRC JPM E Examinees Name:

Examiners Name: -

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

ResuI t : Satisfa ct o ry! Unsat isf act o ry Examiners signature and date:

NRC JPM E - 2008 Limerick Operating Test 8 :Jf 9

Applicant JPM Cue Sheet Initial Conditions:

The reactor is shutdown due to a large steam leak inside primary containment.

Reactor water level is being maintained by the RO using S/U level control.

Cooling water is not required to the Post LOCA Recombiners and the HV57-168A valve has been verified closed.

0 1A and 1B RHR Pumps have both tripped Initiating Cue:

You are directed by Shift Supervision to establish to initiate drywell spray using the fire protection system cross-tie per T-225.

NRC JPM E - 2008 Limerick Operating Test

NRC JPM F 2008 Limerick Operating Exam NRC JPM F - 2008 Limerick Operating Test

Appendix C Job Performance Measure Form ES-C-1

- Worksheet Facility: Limerick Task

Title:

Transfer Loads to Unit Aux Trans Job Performance Measure: NRC JPM F K/A

Reference:

262001 A4.04 (3.6, 3.7)

Examinee: NRC Examiner:

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:

GP-2 is being performed on Unit 1.

0 1I and 12 Unit Auxiliary Busses are being powered from offsite sources.

Initiating Cue:

You are directed by Shift Supervision to transfer house loads for Unit 1 to the Unit Aux.

Transformer per S91.6.A.

Required Materials:

None General

References:

S91.6.A, Transferring House Loads To Unit Auxiliary Transformer, Rev. 15 JPM Origination: Limerick Bank JPM 25, Rev. 004 Task Standard:

11 and 12 Unit Auxiliary Busses being supplied by the Main Generator Alternate Path: No Time Critical: No Validation Time: 10 minutes JPM Setup Instructions:

Simulator Setup:

1. Reset simulator to any power IC.

2. Transfer 11 and 12 busses to offsite.

NRC JPM F - 2008 Limerick Operating Test 2 of 8

Appendix C Job Performance Measure Form ES-C-1

- Worksheet

3. Ensure that only one 13.2 kV aux bus is selected for fast transfer to a given offsite source.

NRC JPM F - 2008 Limerick Operating Test 3 ot 8

Appendix C 2 Form ES-C-?.-

Performance Inf ormat io n Critical steps denoted with an asterisk SteD Element Standard Comment / Sat/Unsat Obtain current revision of Current revision of S91.6.A S91.6.A. obtained.

Cue: Provide copy of S91.6.A to applicant after applicant demonstrates the ability to locate the current revision of the Procedure.

Determining section to Refers to Section 4.2.

perform.

Perform the appropriate section as follows:

1. Perform Section 4.2 to 2 transfer 11 Aux Bus

2. Perform Section 4.3 to transfer 12 Aux Bus.

3. Perform Section 4.4 to transfer 21 Aux. Bus.

4. Perform Section 4.5 to transfer 22 Aux Bus.

Place 225-101 13/SS Places Sync Switch to ON.

3" synchronization switch to ON.

Verify incoming voltmeter Observes that V/I-UAS and 4 AND running voltmeter VIR-UAS are both read approximately 11OV. approximately 11OV.

IF incoming / running Observes that V/I-UAS and voltages differ by greater V/R-UAS voltages are than 8 volts, THEN adjust within 8 volts of each other.

startup bus voltage to obtain less than 8 volts difference.

CLOSE and HOLD 252- Holds 252-1 01 13/CS in 101 13/CS, Aux Feed. CLOSE when incoming and running voltages are 6*

both approximately 110 and within 8 volts of each other.

NRC JPM F - 2008 Limerick Operating Test 4of8

Atmendix C 2 Form ES-C-1 Performance Information Step Element Standard Comment I SatlUnsat When 252-101 13/CS, A'ux Releases 252-101 13C Feed indicates closed, then when Aux. Feed indicates 7* release 252-10113C/CS. closed. Red light lit, green light out.

Verify 252-10102/CS, Verifies 10/11 and 20/11 10/11 Feed AND 252- feeds OPEN.

10106/CS, 20/11 Feed OPEN Acknowledge Alarm 175 Depresses alarm G E N l F1 acknowledge pushbutton.

Place 225-101 13/SS Sync Switch 225-101 13/SS 10 synchronization switch to handle OFF OFF.

Ensure 252-10102/CS, Verifies 252-10102/CS and 10/11 Feed AND 252- AND 252-10106/CS in 10106/CS, 20/11 Feed in NORMAL AFTER TRIP.

NORMAL AFTER TRIP Reset Alarm 125 GEN 1 Depresses Reset l2 F1 Pushbutton.

Place 243-101/CS, Fast Places 243-101/CS in I O -

Transfer Select to 10-11 11 position.

Place 225-10213/SS Refers to Section 4.4.

synchronization switch to ON. Inserts synch switch 14* handle and turns clockwise to ON position then releases.

Verify incoming voltmeter Observes that V/I-UAS and 15 and running voltmeter read V/R-UAS voltages are both approximately 11OV. approximately 1IOV.

Close and hold 252- Holds 252-10213/Cs in 10213/CS, Aux Feed. CLOSE when incoming and running voltages are 16*

both approximately 110 and within 8 volts of each other.

WHEN 252-1021 3/CS, Aux Releases 252-1021 3/CS 17* Feed indicates closed, then when AUX. FEED indicates release 252-1021 3/CS. closed.

Acknowledge alarm 125 Depress alarm l8 GEN 1 F-24. acknowledge pushbutton.

NRC JPM F - 2008 Limerick Operating Test 5of8

Appendix C 2 Form ES-C-q Performance Information Step Element Standard Comment I SatIUnsat

__ - ~~ __ ~

Verify 252-1 02021CS, Verifies 10112 and 20112 10112 Feed and 252- feeds open.

10206/CS, 20/12 Feed open.

Place 225-102131SS Places 225-10213/SS 20 Synchronization Switch to handle in OFF.

OFF.

Ensure 252-1 0202/CS, Verifies 252-10202/CS 10/12 Feed and 252- AND 252-102061CS in 21 10206/CS, 20112 Feed in NORMAL AFTER TRIP.

NORMAL AFTER TRIP.

~ ~ ~ ~ ~~

Place 243-1021CS, Fast Places 242-1021CS in 20-22* Transfer Select to 20-12 12 position.

Cue: JPM is complete.

NRC JPM F - 2008 Limerick Operating Test 6of8

_ _ _ - ~ ~ ~~~ ~

Appendix C 3 Form ES-C-I Verification of Completion Job Performance Measure: NRC JPM F Examinees Name:

Examiners Name: -_

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

NRC JPM F - 2008 Limerick Operating Test 7of8

- Applicant JPM Cue Sheet Initial Conditions:

0 GP-2 is being performed on Unit 1 0 11 and 12 Unit Auxiliary Busses are being powered from offsite sources Initiating Cue:

You are directed by Shift Supervision to transfer house loads for Unit 1 to the Unit Aux. Transformer per S91.6.A.

NRC JPM F - 2008 Limerick Operating Test

NRC JPM G 2008 Limerick Operating Exam NRC JPM G - 2008 Limerick Operating Test

Appendix C Job Performance Measure Form ES-C-I

- Worksheet Facility: Limerick Task

Title:

Align RECW For Drywell Cooling Job Performance Measure: NRC JPM G WA

Reference:

400000 K1.02 (3.2, 3.4)

E!xaminee: NRC Examiner:

Date:

Method of testing:

SimuIated Performa nce : 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:

0 DW Chilled Water has been lost due to trips on both Drywell Chiller Units.

0 The reactor was manually scrammed.

0 DW temperature is 148°F and rising.

0 DW pressure is 1.8 psig and rising.

0 The CRS has entered T - I 02, Primary Containment Control.

RWCU has been shutdown per S.44.2.A, Reactor Water Cleanup Shutdown.

Initiating Cue:

You are directed by Shift Supervision to align RECW operation to cool the drywell, using A Loop first per S13.6.D.

Required Materials:

None General

References:

T-I 02, Primary Containment Control Bases, Rev. 22 S13.6.D, RECW Operation with Loss of Drywell Chilled Water, Rev. 14 S44.2.A, Reactor Water Cleanup Shutdown, Rev. 23 ARC-MCR-118-H5, REAC ENCL COOLING WATER HEAD TANK HI/LO LEVEL JPM Origination: New NRC JPM G - 2008 Limerick Operating Test 2 of 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard:

Leaking DW Loop A is isolated from RECW. RECW is aligned to cool the drywell using DW Loop B.

Alternate Path: Yes Time Critical: No Validation Time: 10 minutes JPM Setup Instructions:

Summary Description of JPM:

Both drywell chiller units have tripped and efforts to restore have been unsuccessful. The reactor has been manually scrammed. Drywell temperature is 148°F and rising. The applicant is directed to align RECW to the A Loop of the drywell chill water system. When aligned, the Loop will begin leaking inside primary containment. The applicant will recognize multiple indications of RECW leakage and recognize the challenge to the RECW system.

The applicant will isolate Loop A Drywell Cooling from RECW and then align RECW to Loop B Drywell Chill Water. JPM is complete when the leak is isolated and the drywell is being cooled by RECW via the B Loop.

Simulator Setup:

1. Reset the simulator to any at-power IC

2. Insert Malfunctions MPC482A and MPC482B to trip DW Chillers

3. Manually scram the reactor, take immediate scram actions.

4. Trip both RRPs.

5. Allow DW temperature to rise to 148°F.

6. Shutdown RWCU per S44.2.A.

7. Set up [malfunctionshemotes to simulate DW Loop leak on RECW, automatically triggered off of switch actions described in S I 3.6.D Step 4.2.8 PLACE HSS 121A, Loop Drywell Water Source Mode Switch (LOOP), in RE CLG WTR]

a. Malfunction MPC500B, Drywell Chill Water Leak Loop B (30%) triggered when HSS-87-121A in RE CLG WTR.

b. Remote Function RCW034, RECW Head Tank Drain Valve to OPEN triggered when HSS-87-121A in RE CLG WTR.

C. Time delayed overrides on RECW Head Tank alarm and system pressure instrument, triggered when HSS-87-121A in RE CLG WTR position.

d. Time delayed override on pump motor indicating lights to indicate motor is running.

e. Time delayed override on pump handswitch to stop to simulate pump cavitating and no longer providing flow to system.

f. Malfunction MCW483A or B to trip the running RECW pump, as appropriate, and remove override on pump indicating lights.

8. Freeze simulator NRC JPM G - 2008 Limerick Operating Test 3 of 10

-Appendix C 2 Form ES-C-1 Performance 1nformat ion Critical steps denoted with an asterisk Step Element Standard Comment I Sat/Unsat Obtain a current revision of Obtains a current revision S I 3.6.D, RECW Operation of S I 3.6.0.

With Loss of Drywell Chilled Water Reviews precautions. Reviews precautions.

Cue:

If necessary, inform applicant that Precaution 3.1 does not apply to the 2

current plant condition.

Shift manager has confirmed that alignment of RECW cooling to the drywell is required by T-102.

(Step 4.2.1) Not applicable. RWCU SHUTDOWN RWCU system already shutdown.

system per S44.2.A, Reactor Water Cleanup Cue:

Shutdown. If necessary, inform applicant that RWCU has already been shutdown IAW S44.2.A.

(Step 4.2.2) Closes HV-13-102.

CLOSE HV-13-*02, 4* Cooling Water to Reactor BuiIding Isolation (SUPPLY ISOL).

(Step 4.2.3) Not applicable IF loss of instrument air prohibits closure of HV *02, SUPPLY ISOL,THEN CLOSE 13-*039, RECW Header Valve to RWCU Non-Regen Heat Exchanger.

NRC JPM G - 2008 Limerick Operating Test 4 of 10

Appendix C 2 Form ES-C-1 Performance Information Step Element Standard Comment / SatlUnsat (Step 4.2.4) Not applicable.

Block CLOSE the following sample point isolation Cue:

valves: If asked, a clearance is 6 being processed to block the sample point isolation.

You are directed to continue.

HV-51-*F080A, RHR Blocks HV-51-1 F080A Sample Line Downstream closed.

Isolation (SAMPLE OUTBOARD)

HV-51-*F080B, Main Blocks HV-51-1 F080B Steam Line Outboard closed.

Sample (SAMPLE OUTBOARD)

HV-41-*F085, RHR Blocks HV-41-1 F085 Sample Line Downstream closed.

Isolation (DRAIN SAMPLE OUTBOARD)

HV-43-*F020, Recirc Blocks HV-43-1 F020 10 Sample Line Outboard closed.

Isolation (SAMPLE) 023-1246, FW to Rx Sump Blocks 023-1246 closed.

l1 Is01 Vlv (Step 4.2.5) Directs EO to close Booth operator:

CLOSE the following following breakers: Close breakers locally breakers: D114-R-C-15 using Remote Function 12* D*14-R-C-15 (124A) D114-R-C-19 RPC306.

D*l4-R-C-19 (124B) D114-R-C-16 D*l4-R-C-I6 (125A) D114-R-C-20 Report breakers are D*l4-R-C-20 (1258) closed.

(Step 4.2.7) Not applicable.

13 IF required THEN BYPASS isolations Der GP-8.5.

NRC JPM G - 2008 Limerick Operating Test 5 of10

Appendix C 2 Form ES-C-11 Performance Information Step Element Standard Comment I SatlUnsat (Step 4.2.8) Places HSS-87-121A in RE Note:

PLACE HSS-87-*21A(B), CLG WTR position for The RECW leak into the Loop Drywell Water LOOP A. Verifies valves drywell through the Loop Source Mode Switch indicate flow path open A Drywell Cooling line will (LOOP), in "RE CLG WTR" from RECW and closed be simulated by initiating for loop to be supplied by from Chill Water. a Loop B (not Loop A)

RECW AND VERIFY the leak triggered when HSS-12* following: 87-121A is placed in RE 0 Red indicating lights CLG WTR position.

RECW IN AND RECW OUT Lit 0 Green indicating lights CHLD WTR IN AND CHLD WTR OUT Lit (Step 4.2.9) Verifies valves open:

VERIFY Drywell Isolation LOOP A HS-87-128 Loop A( B) (LOOP) red LOOP B HS-87-122 indicating lights DRYWELL 13 INLET AND DRYWELL OUTLET Lit for loop to be supplied by RECW.

LOOP A HS-87-*28 LOOP B HS-87-*22 (Step 4.2. I O ) Not applicable.

IF RECW flow is insufficient for adequate 14 cooling, THEN PLACE standby RECW Heat Exchanger in service AND Responds to RECW Head Refers to ARC for Alarm Note:

Tank level alarm. Panel 118 Window H-5, THIS BEGINS THE REAC ENCL COOLING ALTERNATE PATH.

WATER HEAD TANK HllLO LEVEL.

15 Cue:

If necessary, direct applicant to respond to alarms.

NRC JPM G - 2008 Limerick Operating Test 6 of 10

Awendix C 2 Form ES-C-I Performance I nformatio n Step Element Standard Comment I SatlUnsat

~

Verify RECW Head Tank Directs EO to check level Booth operator:

1OT201 level locally using locally. Report back as EO that LG-13-101. level is 11 inches and lowering approximately 6 16 inches every 30 seconds.

If asked, report that demin water supply valve LV 101 is fully opened.

~~ ~~ -

IF losing excessive water Directs EO to walkdown inventory, THEN have system looking for leaks.

Operator walkdown system to check for leaks. ~ __ ~ ~~~~

Recognizes likely leak Isolates the leak from Booth operator:

location is on Loop A of RECW by placing HSS Remove Malfunction for Drywell Cooling and 121A in the DWCW Loop B leak (MPC500B) isolates Loop A Drywell position. after handswitch is Cooling Loop from RECW. returned to DWCW Cue: position.

If necessary, CRS should ask applicant to identify the Booth operator:

18*

location of the leak and Report as EO, RECW take necessary actions to Head Tank level is rising.

isolate and to maintain the RECW system. Booth operator:

Restore normal RECW indications (Head Tank Level Alarm, system pressure).

NRC JPM G - 2008 Limerick Operating Test 7 of 10

Appendix C 2 Form ES-C-'I Performance I nf ormati on Step Element Standard Comment I Sat/Unsat (Step 4.2.11) Places HSS-87-121 B, IF other Drywell Chilled Loop Drywell Water Water loop is needed, Source Mode Switch THEN PLACE HSS (LOOP) in RE CLG WTR

• 21 B(A), Loop Drywell position and verifies proper Water Source Mode Switch indicating lights.

(LOOP), in RE CLG WTR AND VERIFY the following: Cue:

Red indicating lights If necessary, cue the RECW IN AND RECW applicant to proceed with 19" OUT Lit. establishing drywell cooling Green indicating lights by having the CRS ask CHLD WTR IN AND applicant to report the CHLD WTR OUT Lit. status of establishing Drywell Isolation Loop d rywelI cooling with B(A) (LOOP) red RECW.

indicating lights DRYWELL INLET & IfJ l necessary, direct DRYWELL OUTLET Lit. applicant to continue with

- LOOP A HS-87-*28 the procedure to establish

- LOOP B HS-87-*22 drywell cooling.

Cue: JPM is complete.

NRC JPM G - 2008 Limerick Operating Test 8 of 10

Appendix C 3 Form ES-C-I Verification of Completion Job Performance Measure: NRC JPM G Examinees Name: -

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

~~ ~ ~~ ~ ~~ ~ ~~

Result: SatisfactorylUnsatisfactory Examiners signature and date:

NRC JPM G - 2008 Limerick Operating Test 9 o f 10

- Applicant JPM Cue Sheet Initial Conditions:

0 DW Chilled Water has been lost due to trips on both Drywell Chiller Units.

The reactor was manually scrammed.

0 DW temperature is 148°F and rising.

0 DW pressure is 1.8 psig and rising.

0 The CRS has entered T-102, Primary Containment Control.

0 RWCU has been shutdown per S.44.2.A, Reactor Water Cleanup Shutdown.

Initiating Cue:

You are directed by Shift Supervision to align RECW operation to cool the drywell, using A Loop first per S I 3.6.0.

NRC JPM G - 2008 Limerick Operating Test

NRC JPM H 2008 Limerick Operating Exam NRC JPM H - 2008 Limerick Operating Test

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

Facility: Limerick Task

Title:

Control Room Ventilation High Radiation Reset Job Performance Measure: NRC JPM H KIA

Reference:

290003 A4.01 (3.2, 3.2)

Examinee: NRC Examiner:

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:

Manual Control Room ventilation high rad isolation was inhibited in response to instrument failure Repairs are complete and all rad alarms are clear Initiating Cue:

You are directed by Shift Supervision to reset the Control room HVAC high radiation isolations per S78.7.A Required Materials:

None General

References:

S78.7.A, Control Room HVAC system Restoration from an Isolation, Revision 14 JPM Origination: Limerick Bank JPM 74, Rev. 01 1 Task Standard:

Control room HVAC High Radiation isolation reset with CREFAS aligned for normal automatic operation Alternate Path: No Time Critical: No Validation Time: 15 minutes JPM Setup Instructions:

NRC JPM H - 2008 Limerick Operating Test 2of7

Appendix C Job Performance Measure Form ES-C-%

Worksheet Simulator Setup:

1. Place the HS-78-017A,B,C and D keylock switches to RESET

2. Rotate the arming collars for HSS-78-017A,B,C and D to RAD.

3. Place the HS-78-017A,B,C and S keylock switches to AUTO

4. Depress the pushbuttons on HSS-78-017A,B,C and D

5. Leave HSS-078-017A,B,C, and D collars in RAD

6. Ensure the HI RAD ISLN light lit and the CHLOR ISLN NOT lit for all four isolation channels.

7. Remove the four PA2235 keys from HS-78-017A,B,C and D.

8. Reset any annunciators that will reset NRC JPM H - 2008 Limerick Operating Test 3 of7

Appendix C 2 Form ES-C-I Performance Information Critical steps denoted with an asterisk Step Element Standard Comment I Sat/Unsat IF required THEN manually NIA ACKNOWLEDGE chlorine detectors locally at detector (625-08-350).

IF required, THEN RESET NIA toxic chemical alarms per S78.1.F, Alignment of Toxic Chemical Detection System for Normal Operation.

~ -

IF required, THEN NIA ACKNOWLEDGE radiation 3 condition by depres sing ACK on RM-11 console, MCR.

PLACE the following NIA control room Isolation Valve Reset keylock Switches to RESET:

HS-78-017C, RESET C Places HS-78-017C is in 4a

• RESET ~ ~~ ~~ ~~~~~

HS-78-017A, RESET A Places HS-78-017A is in 4b*

RESET HS-78-017B, RESET 6 Places HS-78-017B is in 4c*

RESET ~

HS-78-017D, RESET D Places HS-78-017D IS in 4d

• RESET ENSURE the following NIA Note: collar left in RAD control room Isolation valve per Main Rad Isolation 5 Trip Switches to NOR: procedure S78.8.A. Not critical to enable reset but required by procedure HSS-78-017C, TRIP C Places HSS-78-017C in 5a NOR HSS-78-017C, TRIP A Places HSS-78-017A in 5b NOR HSS-78-017C, TRIP B Places HSS-78-017B in 5c NOR NRC JPM H - 2008 Limerick Operating Test 4of7

Appendix C 2 Form ES-C-'I Performance Information SteD Element Standard Comment I Sat/Unsat HSS-78-017C, TRIP D Places HSS-78-017D in 5d NOR

~ ~~~~

PLACE the following N/A Control Room Isolation Valve Reset Keylock Switches to AUTO:

HS-78-017C, RESET C Places HS-78-017C in 6a AUTO HS-78-017C, RESET A Places HS-78-017A in 6b AUTO HS-78-017C, RESET B Places HS-78-0178 in 6c AUTO HS-78-017C, RESET D Places HS-78-017D in 6d

~~~ ~

AUTO VERIFY status of N/A 7 OA(B)VI 27, EMERGENCY AIR FAN A (B) as follows If a single subsystem N/A isolation remains, THEN 7a verify OAVl27 or OB127 is running as appropriate If all subsystems reset, OAVl27 and OBVl27 are THEN verify OAVl27 and not running.

OB127 are NOT running 7b (Cue: you can stop here.

You have met the termination criteria for this JPM)

NRC JPM H - 2008 Limerick Operating Test 5of7

Appendix C 3 Form ES-C-1 Verification of Completion Job Performance Measure: NRC JPM H Examinees Name: -

Examiners Name: -

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

ResuIt: Satisfactory/ U nsat isf acto ry Examiners signature and date:

NRC JPM H - 2008 Limerick Operating Test 6 of7

Applicant JPM Cue Sheet Initial Conditions:

Manual Control Room ventilation high rad isolation was inhibited in response to instrument failure Repairs are complete and all rad alarms are clear Initiating Cue:

You are directed by Shift Supervision to reset the Control room HVAC high radiation isolations per S78.7.A. All prerequisites are met.

NRC JPM H - 2008 Limerick Operating Test

NRC JPM I 2008 Limerick Operating Exam NRC JPM I - 2008 Limerick Operating Test

Appendix C Job Performance Measure Form ES-C-I Worksheet _-

Facility: Limerick Task

Title:

Alt Injection From The Fire System Job Performance Measure: NRC JPM I K/A

Reference:

295031 EA1.08 (3.8, 3.9)

Examinee: NRC Examiner:

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 t simulate or di uss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

Unit 2 reactor level is low and injection is being established Reactor pressure is 50 psig The Motor Driven Fire Pump is out of service and unavailable Initiating Cue:

Shift Supervision directs you to perform T-244 to supply Fire Water to increase Unit 2 reactor level.

Required Materials:

BL-840 Key for T-225 Hose Storage Cabinet (475-R17-253)

General

References:

T-244, Alternate Injection from the Fire System, Rev. 14 JPM Origination: Limerick Bank JPM 260, Rev. 006 Task Standard:

Backup Diesel Driven Fire Pump started locally.

Alternate Path: No Time Critical: No Validation Time: 23 min JPM Setup Instructions:

NRC JPM I - 2008 Limerick Operating Test 2 of6

Appendix C 2 Form ES-C-1"_

Performance Information Critical steps denoted with an asterisk Step Element Standard Comment / SatlUnsat Obtain current revision of Current revision of Unit 2 1

Unit 2 T-244. T-244 obtained.

Obtain necessary Necessary tools/equipment Tools/Equipment from Unit obtained.

2 T-225 Hose Storage Cabinet(475-R17-253), BL-2 840 key required.

Cue: You have the necessary tools/equipment in your possession.

CONNECT hose at 51- Connects hose at 51-2179 21 79 2A RHWFire AND routes to drain.

Protection Interconnection 51-2179 cycled to vent Drain Vlv. AND ROUTE to pipe.

drain THEN CYCLE 51-3*

2179 open AND closed to ensure pipe vented.

Cue: Connected as described.

CONNECT hose at 22- Connects hose at 22-2430 2430 Fire Protection/RHR AND routes to drain.

Interconnection Isolation 22-2430 cycled to vent Vlv AND ROUTE to drain pipe.

THEN CYCLE 22-2430 4* open AND closed to ensure pipe vented.

Cue: Connected as described.

CONNECT hose to fitting Connects one end of hose downstream of 22-2429, to downstream side of 22-Fire ProtectiodRHR 2429.

Interconnection Isolation 5* Valve.

Cue: Connected as described.

NRC JPM I - 2008 Limerick Operating Test 3 of6

Appendix C 2 Form ES-C Performance I nf ormat ion Step Element Standard Comment I SatlUnsat CONNECT other end of Connects other end of hose to 51-2178, 2A RHR hose to 51-2178.

Fire Protection Crosstie 6* Connection kolat ion Va Ive.

Cue: Connected as described.

OPEN 22-2429 Turns 22-2429 handwheel f uIIy counterclockwise.

Cue: Valve handwheel 7* turns in the counter-clockwise direction and StODS.

UNLOCK AND OPEN 51- Turns 51-2178 handwheel 21 78 fully counterclockwise.

8* Cue: Handwheel turns in counterclockwise direction and stops.

START available Fire Not Applicable Pump: ~ ~~ ~- ~~~ - -

IF starting OOP512, Motor Recognize from task Driven Fire Pump, THEN conditions that the Motor DEPRESS HS-22-002-1 at Driven Fire Pump is OOC650 (Main Control unavailable and proceed to 10 Room) AND VERIFY pump Step 4.2.2.

starts.

Cue: If asked, reply that MDFP is not available.

IF starting OOP511, Diesel Contacts main control Driven Fire Pump, THEN room and requests start of DEPRESS HS-22-6-1 at DDFP.

OOC650 (Main Control Room) AND VERIFY pump is running.

Cue: MCR reports the Diesel Driven Fire Pump is running Cue: JPM is complete.

NRC JPM I - 2008 Limerick Operating Test 4 of 6

Appendix C 3 Form ES-C-1.-

Verification of Completion Job Performance Measure: NRC JPM I Examinees Name: -

Examiners Name: -

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

NRC JPM I - 2008 Limerick Operating Test 5 of6

Applicant JPM Cue Sheet Initial Conditions:

0 Unit 2 reactor level is low and injection is being established 0 Reactor pressure is 50 psig 0 The Motor Driven Fire Pump is out of service and unavailable Initiating Cue:

Shift Supervision directs you to perform T-244 to supply Fire Water to increase Unit 2 reactor level.

NRC JPM I - 2008 Limerick Operating Test

NRC JPM J 2008 Limerick Operating Exam NRC JPM J - 2008 Limerick Operating Test

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

Facility: Limerick Task

Title:

Transfer RWST to CST Job Performance Measure: NRC JPM J KIA

Reference:

203000 A2.04 (3.5, 3.6)

Examinee: NRC Examiner:

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 station blackout has occurred. Procedure E-I, Loss of All AC Power (Station Blackout), is being implemented.

Initiating Cue:

You are directed to initiate gravity feed from the RWST to #I CST in accordance with E - I ,

Step 3.20. There is sufficient RWST inventory for this transfer.

Required Materials:

Pages from E-I, Loss of All AC Power (Station Blackout) containing Step 3.20.

General

References:

E-I, Loss of All AC Power (Station Blackout), Rev. 033 JPM Origination: New Task Standard:

Initiate gravity feed from the U1 RWST to the U1 CST.

Alternate Path: No Time Critical: No Validation Time: 5 min JPM Setup Instructions:

None NRC JPM J - 2008 Limerick Operating Test 2of5

Appendix C 2 Form ES-C-'1 Performa nce I nf or mation Critical steps denoted with an asterisk Step Element Standard Comment / SatlUnsat

~

ENSURE 08-0008 closed. Verifies 08-0008 is closed.

1 Cue: Valve is closed.

ENSURE 08-0029 closed. Verifies 08-0029 is closed.

2 Cue: Valve is closed. _-

ALIGN the following Not applicable 3

valves:

1. 08-0001, Tie Between Opens 08-0001.

RWST and Manifold -

4* OPEN Cue: Valve is open.

2. 08-0003, Tie Between Opens 08-0003.

1. I CST and Manifold 5* - OPEN Cue: Valve is open.

3. 08-0004, Manifold Opens 08-0004.

Stop Valve - OPEN 6*

Cue: Valve is open. You hear flow noise.

Inform control room that Informs control room.

gravity feed has been initiated from RWST to #I CST. Cue: JPM is comdete.

NRC JPM J - 2008 Limerick Operating Test 3 of 5

Appendix C 3 Form ES-C-I Verification of Completion Job Performance Measure: NRC JPM J Examinees Name: --

Examiners Name: --

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

NRC JPM J - 2008 Limerick Operating Test 4of.

Applicant JPM Cue Sheet Initial Conditions:

A station blackout has occurred. Procedure E - I , Loss of All AC Power (Station Blackout), is being implemented.

Initiating Cue:

You are directed to initiate gravity feed from the RWST to #I CST in accordance with E-I , Step 3.20. There is sufficient RWST inventory for this transfer.

NRC JPM J - 2008 Limerick Operating Test

NRC JPM K 2008 Limerick Operating Exam NRC JPM K - 2008 Limerick Operating Test

Appendix C Job Performance Measure Form ES-C-I Worksheet Facility: Limerick Task

Title:

Supply Emer Power to RClC Isolation Job Performance Measure: NRC JPM K WA

Reference:

600000 AK3.04 (2.8, 3.4)

Examinee: NRC Examiner:

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.

InitiaI Conditions:

0 A fire in the Main Control Room has required evacuation and control of the plant from the RSP.

0 Division 3 power is not available.

0 RClC is required but has failed to inject.

0 HV-49-2F007, RClC Main Steam Supply Inboard PClV has NO position indication.

Personnel are stationed at the RSP.

Initiating Cue:

You are directed to supply Div 1 power to HV-49-2F007, in preparation for placing Unit 2 RClC in service from the RSP in accordance with SE-1, Section 4.3.8 Reactor Level Control.

Required Materials:

SE-1, Remote Shutdown, Pages 14 & 15, Step 4.3.8 General

References:

SE-1, Remote Shutdown, Rev. 59 JPM Origination: Limerick Bank JPM 0250, Rev. 007 Task Standard:

Division 1 power supplied to HV-49-2F007, RClC Main Steam Supply Inboard PClV Alternate Path: No Time Critical: No Validation Time: 5 min NRC JPM K - 2008 Limerick Operating Test 20f8

Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM Setup Instructions:

Inform Unit 2 Main Control Room that Terminal Box 20TB49-2F007will be opened for training. Ensure locked valve entry is made.

NRC JPM K - 2008 Limerick Operating Test 3 of8

Appendix C 2 Form ES-C-1 Performance Information Critical steps denoted with an asterisk Step Element Standard Comment / Sat/Unsat

~~ ~

Obtain current revision of Not applicable SE-1, Remote Shutdown.

1 Cue:

Provide a copy of SE-1 CAUTION Steps 4.3.8.1 through 4.3.8.7 are Prompt Actions, requiring completion within 14 minutes.

NOTE Step 4.3.8 indicates HV-49-*F007 has failed closed.

IF the following conditions exist:

Div 3 power has been disrupted RClC fails to inject on manual auto start signal HV-49-*F007 has no position indication THEN PERFORM the following to supply Div 1 power to HV-49-2F007, AND PLACE RClC in service:

(Step 4.3.8.1) Opens D234-R-E-13 (Unit OPEN D*34-R-E-13. (Unit 2: 475-R13-253) 3* 1: 402-R15-253, Unit 2:

475-R13-253). Cue:

D234-R-E-13 is 0136317.

NRC JPM K - 2008 Limerick Operating Test 4of8

Atmendix C 2 Form ES-C-1 Performance Information Step Element Standard Comment I SatlUnsat NOTE Obtains a screwdriver and Note:

A screwdriver AND LV-*00 LV-200 key. SIMULATES Normal power is de-key are required for step unlocking and opening energized (the reason for 4.3.8.2. Terminal Box 20TB49- the task) and the alternate 2F007 (Unit 2: 475-R14- power supply breaker has (Step 4.3.8.2) 253). not been closed yet). The UNLOCK AND OPEN lamps indicate the status 4* terminal box *OTB49- Cue: of power just upstream of

• F007 Terminal box is unlocked the molded case breakers (Unit 1: 402-R15-253, Unit and opened. in the cabinet.

2: 475-R14-253).

Cue:

If asked, inform applicant that both lamps are out in the cabinet.

(Step 4.3.8.3) Places 43-CB22313, Note:

PLACE 43-CB22313, Manual Transfer Switch in USE PHOTO of cabinet.

Manual Transfer Switch EMERGENCY. Applicant Do not open cabinet.

(located in terminal box simulates pulling down on

• OTB491*F007), the red handle lever.

in EMERGENCY.

5* Cue:

Switch is in the DOWN position.

Cue:

If asked, lights remain OUT.

(Step 4.3.8.4) Unlocks and closes D214-UNLOCK R-C-31, RClC Main Steam AND CLOSE D*14-R-C-31, Inboard PClV RClC Main Steam lnbd (EMERGENCY POWER) 6* PClV (EMERGENCY (Unit 2: 580-R17-283)

POWER). (Unit 1: 506-R11-283 Unit 2: 580-R17- Cue:

283) D214-R-C-31 is closed.

(Step 4.3.8.5) Calls operator at 20C201 OPEN HV-49-*F007 and directs him to open (INBOARD) at *OC201 HV-49-2F007.

7*

Cue:

Operator reports HV 2F007 is open.

N R C JPM K - 2008 Limerick Operating Test 5of8

Appendix C 2 Form ES-C-I Performance Information Step Element Standard Comment I SatlUnsat (Step 4.3.8.6) Locks open D214-R-C-31 LOCK OPEN D*14-R-C-3II 8*

Cue:

D214-R-C-31 is open.

(Step 4.3.8.7) Returns 43-CB22313, RETURN 43-CB22313, Manual Transfer Switch, to Manual Transfer Switch, NORMAL.

to NORMAL.

Cue:

9* 43-CB22313, Manual Transfer Switch is in the UP position.

Cue:

Both lights are still out.

(Step 4.3.8.8) Informs operator at RSP PLACE RCIC in service that procedure directs lo* per step 4.3.3 placing RCIC in service per Step 4.3.3.

Cue: JPM is complete.

NRC JPM K - 2008 Limerick Operating Test 6of8

Appendix C 3 Form ES-C-1 Verification of Completion Job Performance Measure: NRC JPM K Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

- ~ ~~

Response

- ~ ~ ~ ~ ~~ ~~

Result: Satisfactory/Unsatisfactory Examiners signature and date:

NRC JPM K - 2008 Limerick Operating Test 7 of8

Applicant JPM Cue Sheet Initial Conditions:

0 A fire in the Main Control Room has required evacuation and control of the plant from the RSP.

0 Division 3 power is not available.

0 RClC is required but has failed to inject.

0 HV-49-2F007, RClC Main Steam Supply Inboard PClV has NO position indication.

0 Personnel are stationed at the RSP.

Initiating Cue:

You are directed to supply Div 1 power to HV-49-2F007, in preparation for placing Unit 2 RClC in service from the RSP in accordance with SE-1, Section 4.3.8 Reactor Level Control.

NRC JPM K - 2008 Limerick Operating Test