ML063060357

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October 2006 Exam - Draft Section B Operating Exam (Folder 2)
ML063060357
Person / Time
Site: Oyster Creek
Issue date: 09/05/2006
From:
AmerGen Energy Co
To: D'Antonio J
Operations Branch I
Sykes, Marvin D.
References
Download: ML063060357 (107)
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Text

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Appendix C Job Performance Measure Form ES-C-1 WORKSHEET U Facility: Ovster Creek Task No: 2020601002 Task

Title:

ResDond to Power Oscillations (Recirc. Flow Oscillations) (Alternate Path)

Job Performance Measure No: NRC Siml (RO/SRO)

WA

Reference:

202002 A2.04 (RO 3.O/SRO 3.2)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testinq:

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

.\ - I performance measure will be satisfied.

Initial Conditions:

1. The Reactor is at 90% power.

Task Standard: The A Recirculation Pump has been tripped. The A Recirculation Pump suction valve has been closed and Electricians have been notified to close the A Recirculation Pump discharge valve IAW ABN-2.

Required Materials: None General

References:

ABN-2, Recirculation System Failures, Rev. 6 Initiating Cue: Power oscillations have been observed and attributed to fluctuations in reactor recirculation flow. Complete the applicable section of ABN-2, Recirculation System Failures.

Time Critical Task: No Validation Time: 21 minutes NRC Siml Page 1 of 8

-~

Appendix C Job Performance Measure Form ES-C-1 WORKS HEET

J Simulator Setup
1. IC65
2. Reduce power to approximately 90% with recirc. flow
3. Fail Recirc. Pump A discharge valve OPEN: VLV-NSSOOG to MECH SIEZE
4. Recirc. Pump A flow oscillations: MAL-RFC005A NRC Siml Page 2 of 8

Appendix C Form ES-C-1 Performance Information d

Denote critical steps with a check mark Performance Step: 1 JPM Start Time:

Standard: Provides repeat back of initiating cue. Evaluator acknowledges repeat back.

Comment:

Performance Step: 2 Standard: Obtain a copy of the reference procedure and reviewhtilize the correct section (Procedure ABN-2, Section 3.3).

Comment:

Performance Step: 3 Standard: Recognizes flow/speed fluctuations on the A Recirculation Pump (Panel 3F).

Comment:

NRC Siml Page 3 of 8

Appendix C Form ES-C-1 Performance Information

.v Performance Step: 4 (step 3.3.2.A)

Standard: At Panel 3F, depresses the AUTO/MAN pushbutton to transfer A Recirculation Pump speed control to MANUAL.

NOTE: speed control is NOT regained.

Comment:

J Performance Step: 5 (step 3.3.2.D.l)

Standard: Determines APRM oscillations are > 4.6% (Panel 4F) and generator load fluctuations are > 30 W e (Panel 8F/9F).

At Panel 3F, places the ARecirculation Pump Drive Motor Control switch to STOP.

CUE: APRM fluctuations are 5% peak to peak AND generator load fluctuations are 40 MWe peak to peak (if not physically present).

Comment:

Performance Step: 6 (step 3.3.2.D.2)

Standard: Refers to Step 3.1.2 of ABN-2 for a single recirculation pump trip when five loops were operating.

Comment:

IWC Siml Page 4 of 8

Appendix C Form ES-C-1 Performance Information

~~~ ~

Performance Step: 7 (step 3.1.2.A)

Standard: At Panel 3F, confirms A Recirc. Pump discharge bypass valve is open (red light ON; green light OFF).

Comment:

Performance Step: 8 (step 3.1.2.8)

Standard: At Panel 3F, places A Recirculation Pump discharge valve control switch to CLOSE. Notifies SRO of valve failure.

NOTE: The A Recirculation Pump discharge valve will not close v

Comment:

- Performance Step: 9 (step 3.1.2.D.1)

Standard: At Panel 3F, places ARecirculation Pump suction valve control switch to CLOSE (red light OFF; green light ON).

Comment:

NRC Siml Page 5 of 8

Appendix C Form ES-C-1 Performance Information L.l 4 Performance Step: 10 (step 3.1.2.D.2)

Standard: Refers to Attachment ABN-2-1; directs electrician to MCC 1A21A to close Recirc. Pump A discharge valve NG03A.

Comment:

Terminating Cue: A Recirculation Pump has been tripped. The ARecirculation Pump suction valve has been closed and Electricians have been notified to close the A Recirculation Pump discharge valve IAW ABN-2.

JPM Stop Time:

NRC Siml Page 6 of 8

Appendix C Form ES-C-1 Validation of Completion Job Performance Measure No. NRC Siml Examinees Name:

Examiners Name:

Date Performed:

FaciIity Eva1uator:

Number of Attempts:

Time to Complete:

Question:

--- Response:

~~

Result: Satisfactory/Unsatisfactory Examiners signature and date:

NRC Siml Page 7 of 8

Appendix C Form ES-C-1 STUDENT HANDOUT Initial Conditions:

1. The Reactor is at 90% power.

Task Cue:

Power oscillations have been observed and attributed to fluctuations in reactor recirculation flow. Complete the applicable section of ABN-2, Recirculation System FaiIures.

NRC Siml Page 8 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET u

Facility: Oyster Creek Task No: 2040101412 Task

Title:

Place a Second RWCU PumD in Service Job Performance Measure No: NRC Sim2 (RO/SRO)

WA

Reference:

204000 A4.01 (RO 3.1/SRO 3.0)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testinq:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read fo 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 iJ performance measure will be satisfied.

Initial Conditions:

1. The Reactor is at 95% power.
2. Reactor water level, power, and pressure are constant.
3. Reactor Water Cleanup Recirculation Pump A is in service with filter ND05A.
4. Chemistry samples show sulfates are out-of-spec high requiring two RWCU pump operation.
5. RBCCW is valved-in to the BCleanup Recirculation Pump.
6. An Equipment Operator is in the field and has been briefed on the evolution and has a copy of the procedure.

Task Standard: The second Cleanup Recirculation Pump is in service with system flow approximately 700 gpm.

Required Materials: None General

References:

Procedure 303, Reactor Cleanup Demineralizer System, Rev. 95 NRC Sim2 Page 1 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Initiating Cue: Place a second reactor water cleanup pump in service IAW Procedure 303, Section 22.0, and establish approximately 700 GPM system flow.

Step 22.3.1 has already been performed. When the second Cleanup Recirculation Pump is in service, another Operator will complete steps 22.3.14 through 22.3.17.

Time Critical Task: No Validation Time: 27 minutes Simulator Setup:

1. IC-65, with power reduced to 95% power, with recirculation flow.
2. Cleanup Pump A is in service.
3. LOA-RCU022 and LOA-RCU023 to 1to open the cleanup pumps min. flow valves.
4. LOA-RCU022 and LOA-RCU023 to 0 to close the cleanup pumps min. flow valves.
5. Adjust (raise) RBCCW to the NHRX HX NRC Sim2 Page 2 of 9

Appendix C Form ES-C-1 Performance Information

',--L Denote critical steps with a check mark Performance Step: 1 JPM Start Time:

Standard: Provides repeat back of initiating cue. Evaluator acknowledges repeat back.

Comment:

Performance Step: 2 Standard: Obtains a copy of the reference procedure and reviewhtilize the correct section (Procedure 303, Section 22).

Comment:

Standard: Verifies Prerequisites; Review Precautions and Limitations.

Comment:

NRC Si& Page 3 of 9

Appendix C Form ES-C-1 Performance Information Performance Step: 4 (step 22.3.2)

Standard: Places placards on Panel 3F for heat balance adjustment and on Letdown Flow Controller to not exceed 760 GPM flow.

Comment:

Performance Step: 5 (step 22.3.3)

Standard: Confirms B cleanup pump discharge valve (V-16-50) is closed (red light OFF; green light ON).

Comment:

- Performance Step: 6 (step 22.3.4)

Standard: Directs equipment operator to open minimum flow valves V-16-36 & V-16-37 (using the local toggle switches).

NOTE: Activate LOA-RCU022 and LOA-RCU023to 1 (OPEN). (Monitor and adjust RBCCW flow to CU system as required.)

CUE: As the EO, report that both minimum flow valves V-16-36 and V-16-37 are open.

Comment:

NRC Sim2 Page 4 of 9

Appendix C Form ES-C-1 Performance Information

.~

4 Performance Step: 7 (step 22.3.5)

Standard: Makes plant announcement for the pump start (not required for critical task).

At Panel 3F, places the B Cleanup Recirculation Pump control switch to START.

Comment:

J Performance Step: 8 (22.3.6)

Standard: Slowly opens B Cleanup Recirculation Pump discharge valve V-16-50 until a small increase in pump discharge pressure is noted on Panel 3F. To throttle this valve, place the valve to OPEN, then to the neutral position to hold the valve in place.

Comment:

Performance Step: 9 (step 22.3.7)

Standard: Slowly opens FCV-ND-16 to maintain original pump discharge pressure.

Comment:

NRC Sim2 Page 5 of 9

Appendix C Form ES-C-1 Performance Information Performance Step: 10 (step 22.3.8)

Standard: Adjusts PCV-ND11 to maintain system pressure at approximately 90 psig.

Comment:

Performance Step: 11 (step 22.3.9/22.3.10)

Standard: Directs EO to monitor:

Demineralizer strainer dP Demineralizer dP Filter dP CUE: As the Field EO, Report:

.*-- - Demineralizer strainer dP is 7 w i d e Demineralizer dP is 8 mid Filter dP is 18 w i d Comment:

Performance Step: 12 (step 22.3.1 1)

Standard: Continues to open the pump discharge valve while adjusting pressure and flow, until the discharge valve is full open (red light ON; green light OFF).

Comment:

NRC Si& Page 6 of 9

Appendix C Form ES-C-1 Performance Information

.u J Performance Step: 13 (step 22.3.12)

Standard: Increases flow with FCV ND-16 until flow is approximately 700 gpm, but does not exceed 760 gpm.

Comment:

Performance Step: 14 (step 22.3.13)

Standard: When flow exceeds 500 gpm, directs Equipment Operator to close minimum flow valves V-16-36 & V-16-37 using the local toggle switches.

NOTE: Activate LOA-RCU022 and LOA-RCU023 to 0 (CLOSED). (Monitor and adjust RBCCW flow to CU system as required.)

CUE: As the EO, report that both minimum flow valves V-16-36 and V-16-37 are closed.

Note: The candidate may request non-regenerationtemperature: Report 95 F.

Comment:

Terminating Cue: The second Cleanup Recirculation Pump is in service with system flow approximately 700 gpm.

JPM Stop Time:

NRC Sim2 Page 7 of 9

Appendix C Form ES-C-1 Validation of Completion Job Performance Measure No. NRC Sim2 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

W i Response:

Result: SatisfactoryAJnsatisfactory Examiners signature and date:

NRC Si& Page 8 of 9

Appendix C Form ES-C-1 STUDENT HANDOUT Initial Conditions:

1. The Reactor is at 95% power.
2. Reactor water level, power, and pressure are constant.
3. Reactor Water Cleanup Recirculation Pump A is in service with filter ND05A.
4. Chemistry samples show sulfates are out-of-spec high requiring two RWCU pump operation.
5. RBCCW is valved-in to the B Cleanup Recirculation Pump.
6. An Equipment Operator is in the field and has been briefed on the evolution and has a copy of the procedure.

Task Cue:

Place a second reactor water cleanup pump in service IAW Procedure 303, Section 22.0, and establish approximately 700 GPM system flow. Step 22.3.1 has already been performed. When the second Cleanup Recirculation Pump is in service, another Operator will complete steps 22.3.14 through 22.3.17.

NRC Sim2 Page 9 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Ovster Creek Task No: 2090101005 Task

Title:

Shutdown Core Smav After Inadvertent Initiation (Alternate Path)

Job Performance Measure No: NRC Sim3 (RO/SRO)

WA

Reference:

209001 A4.01 (RO 3.8/SRO 3.6)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Performance X CIassroom 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 Ll performance measure will be satisfied.

Initial Conditions:

1. The Reactor is at 100% power.
2. Reactor water level, power, and pressure are in the normal bands and are constant.
3. Low-Low Reactor Water Level Instrument RE02A has failed downscale.
4. Core Spray Systems 1 and 2 have initiated.
5. All other systems are operating properly.
6. The US has determined that adequate core cooling is assured.

Task Standard: Core Spray System I has been shutdown following automatic initiation.

Required Materials: None General

References:

Procedure 308, Emergency Core Cooling System Operation, Rev.

76 JWC Sim3 Page 1 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Initiating Cue: Secure Core Spray System 1 IAW Procedure 308, Section 5.0. Another

.-/+ Operator will secure Core Spray System 2.

Time Critical Task: No Validation Time: 20 minutes Simulator Setup:

1. IC-65
2. Fail RPV water level transmitter RE02A low (MAL-NSS007H to "85")
3. Fail control switch for Core Spray Booster Pump NZO1C in START (BKR-CSS001 to MECH SIEZE AFTER the core spray system is running)
4. To trip the Core Spray Booster Bump NZOlC breaker locally: BKR-CSS001 to TRIP NRC Sim3 Page 2 of 8

Appendix C Form ES-C-1 Performance Information

. I

\4 -

Denote critical steps with a check mark Performance Step: 1 JPM Start Time:

Standard: Provides repeat back of initiating cue. Evaluator acknowledges repeat back.

Comment:

Performance Step: 2 Standard: Obtains a copy of the reference procedure and reviewhtilize the correct section (Procedure 308, Section 5.0).

Comment:

.,-.-le Performance Step: 3 Standard: Verify Prerequisites; Review Precautions and Limitations.

Comment:

NRC Sim3 Page 3 of 8

Appendix C Form ES-C-1 Performance Information 4 Performance Step: 4 (step 5.3.2.1)

Standard: Overrides start logic for Core Spray Systems 1 and 2 by depressing RE02A OVERRIDE pushbutton located on the logic mimic on Panel 1F/2F. Observes amber OVERRIDE light is lit and the CH A ACTUATED light extinguishes.

Resets Core Spray start logic by depressing all ACTUATED pushbuttons located on the logic mimic on Panel 1F/ZF.

Comment:

Performance Step: 5 (step 5.3.3)

Standard: At Panel I F/2F, confirms Core Spray System I Parallel Isolation Valves V-20-15 and V-20-40 are closed by observing green CLOSED indicating lights illuminated and red OPEN indicating lights extinguished.

Comment:

NRC Sim3 Page 4 of 8

Appendix C Form ES-C-1

~~~~

Performance Information Performance Step: 6 (step 5.3.4)

NOTE: Core Spray System 1 Booster Pump NZ03A does not trip remotely.

Standard: At Panel 1F/2F, secures Core Spray System 1 Booster Pump NZ03A by placing its control switch to the STOP position. Observes the pump remains running based on no change in pump indications (red light ON; green light OFF; and discharge pressure unchanged)

Directs the EO to trip Core Spray Booster Pump NZ03A by opening its breaker at USS 1A2 located in the 480V Room.

CUE: As EO, acknowledge order to trip Booster Pump NZ03A. Input BKR-CSS001 to TRIP, and then report the breaker is tripped for Core Spray Booster Pump NZ03A.

Standard: Determines pump is tripped by observing pump status lights (red light OFF, green light ON) and pump discharge pressure and amps decrease.

.\. . Comment:

4 Performance Step: 7 (step 5.3.5)

Standard: At Panel 1F/2F, secures Core Spray System 1 Main Pump NZO1A by placing its control switch to the STOP position. (red light OFF; green light ON; lowering pump discharge pressure and amps).

Comment:

NRC Sim3 Page 5 of 8

Appendix C Form ES-C-1 Performance Information Performance Step: 8 (step 5.3.6k5.3.7)

Standard: Confirms the System is filled and vented.

Verify Core Spray System 1 is in Standby Readiness.

CUE: Another Operator will verify the Core Spray System I is filled and vented, and that the Core Spray System I is in Standby Readiness.

Comment:

Te rminating Cue: Core Spray System I has been shutdown following automatic initiation.

JPM Stop Time:

NRC Sim3 Page 6 of 8

Appendix C Form ES-C-1 STUDENT HANDOUT Initial Conditions:

1. The Reactor is at 100% power.
2. Reactor water level, power, and pressure are in the normal bands and are constant.
3. Low-Low Reactor Water Level Instrument RE02A has failed downscale.
4. Core Spray Systems 1 and 2 have initiated.
5. All other systems are operating properly.
6. The US has determined that adequate core cooling is assured.

Task Cue:

Secure Core Spray System 1 IAW Procedure 308, Section 5.0. Another Operator will secure Core Spray System 2.

NRC Sim3 Page 8 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET l2' Facility: Ovster Creek Task No: 2120501402 Task

Title:

Bvpass RPS Scram Loaic Trim Job Performance Measure No: NRC Sim4 (RO/SRO)

WA

Reference:

295037 EA1.01 (RO 4.6/SRO 4.61 Examinee: NRC Examiner:

Facility Eva1uato r : Date:

Method of testinq:

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:

1. A small-break LOCA has resulted in a high drywell pressure condition.
2. A partial failure to scram has occurred.
3. There is a hydraulic lock on the scram discharge volume.

Task Standard: The RPS trips have been bypassed, a manual scram inserted, and all control rods are fully inserted.

Required Materials: 4 EOP Bypass Plugs General

References:

1. EMG-3200-016, RPV Control - With ATWS. Rev. 14
2. Support Procedure 21, Alternate Insertion of Control Rods, Rev. 14 Initiating Cue: Reset the scram and manually scram the reactor, IAW Support Procedure 21, Section 5.0.

Time Critical Task: No

'L-'

NRC Sim4 Page 1 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET c Validation Time: 15 minutes Simulator Setup:

1. IC-65
2. Hydraulic lock on control rods (partial):
3. Small break LOCA: MAL-NSS005D to 0.5O/0
4. Following the scram, place Mode switch in Shutdown
4. After RPV water level recovers, trip 2 FW pumps NRC Sim4 Page 2 of 8

Appendix C Form ES-C-1 Performance Information b,

Denote critical steps with a check mark Performance Step: 1 JPM Start Time:

Standard: Provide repeat back of initiating cue. Evaluator acknowledges repeat back.

Comment:

Performance Step: 2 Standard: Obtain a copy of the reference procedure and reviewhtilize the correct section (Support Procedure 21).

Comment:

-*-=

Performance Step: 3 (step 5.1 .l)

Standard: At Panel 4F, starts the standby CRD pump by placing its control switch to START (red light ON; green light OFF).

Comment:

NRC Sim4 Page 3 of 8

Appendix C Form ES-C-I Performance Information 4

4 Performance Step: 4 (step 5.1.2)

Standard: Bypasses ARI by placing the ARI NormaVBypass Switch in the BYPASS position in the rear of Panel 8R.

Comment:

4 Performance Step: 5 (step 5.1.3)

Standard: Resets ARI by depressing the ARI Manual reset pushbutton on Panel 4F.

Comment:

Performance Step: 6 (step 5.1-4)

Standard: 1) Obtains four (4) bypass plugs from the EOP toolbox.

2) Opens EOP BYPASS PLUGS panel in the rear of Panel 6R.

Inserts a bypass plug in position BP5.

Inserts a bypass plug in position BP6.

3) Opens EOP BYPASS PLUGS panel in the rear of Panel 7 R .

Inserts a bypass plug in position BP5.

Inserts a bypass plug in position BP6.

Comment:

NRC Sim4 Page 4 of 8

Appendix C Form ES-C-1 Performance Information

  • i 4 Performance Step: 7 (step 5.1 5)

Standard: At Panel 4F, places the SDV HI LVL BYPASS switch to the BYPASS position.

Comment:

4 Performance Step: 8 (step 5.1.6)

Standard: Resets the scram by depressing the Scram Reset pushbutton on Panel 4F.

NOTE: Delete the hydraulic fail-to-scram after the scram is reset.

Comment:

Performance Step: 9 (step 5.1.7)

Standard: At Panel 4F, confirms the SDV vent and drain valves indicate open.

Comment:

NRC Sim4 Page 5 of 8

Appendix C Form ES-C-1 Performance Information J Performance Step: 10 Standard: When the SDV LEVEL HI-HI alarms clear (H-1-b/H-2-b), depresses both manual scram pushbuttons at Panel 4F. Verifies all control rods inserted and notifies SRO of all control rods inserted (not required for critical task).

NOTE: All control rods will insert.

Comment:

Terminating Cue: The RPS trips have been bypassed, a manual scram inserted, and all control rods are fully inserted.

JPM Stop Time:

NRC Sim4 Page 6 of 8

Appendix C Form ES-C-1 Validation of Completion Job Performance Measure No. NRC Sim4 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

v-

Response

Result: SatisfactoryAJnsatisfactory Examiners signature and date:

NRC Sim4 Page 7 of 8

Appendix C Form ES-C-1 STUDENT HANDOUT Initial Conditions:

1. A small-break LOCA has resulted in a high drywell pressure condition.
2. A partial failure to scram has occurred.
3. There is a hydraulic lock on the scram discharge volume.

Task Cue:

Reset the scram and manually scram the reactor, IAW Support Procedure 21, Section 5.0.

NRC Sim4 Page 8 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Ovster Creek Task No: 2000501435 Task

Title:

Prepare the Torus for Ventina for Pressure Control Job Performance Measure No: NRC Sim5 (RO/SRO)

WA

Reference:

295024 EA1.19 (RO 3.3/SRO 3.4)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job

'cc performance measure will be satisfied.

Initial Conditions:

1. The reactor scrammed due to a LOCA.
2. The mode switch is in SHUTDOWN.
3. Drywell pressure is 28 psig.
4. Torus venting has been directed by the EOPs.

Task Standard: Preparations for venting the Torus are complete IAW Section 2.0 of Support Procedure 32.

Required Materials: 1 EOP Bypass Plug General

References:

1. EMG-3200-02,Primary Containment Control, Rev. 17
2. Support Procedure 32, Venting the Torus for Primary Containment High Pressure, Rev. 17 NRC Sim5 Page 1 of 10

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

~ ~~~ ~~

Initiating Cue: Prepare the torus for venting due to high Primary Containment pressure

- IAW Support Procedure 32, Section 2.0.

Time Critical Task: No Validation Time: 20 minutes Simulator Setup:

1. IC-65 2 Insert steam leak into Primary Containment so that DW pressure rises above the scram setpoint. (MAL-NSS005D to 1%)
3. Place Mode switch in Shutdown NRC Sim5 Page 2 of 10

Appendix C Form ES-C-1 Performance Information Denote critical steps with a check mark Performance Step: 1 JPM Start Time:

Standard: Provide repeat back of initiating cue. Evaluator acknowledges repeat back.

Comment:

Performance Step: 2 Standard: Obtain a copy of the reference procedure and reviewhtilize the correct section (Support Procedure 32).

Comment:

Performance Step: 3 (step 2.1)

Standard: At Panel 1FEF, verifies Torus water level is below 348 inches.

Comment:

NRC Sim5 Page 3 of 10

Appendix C Form ES-C-1

-v' Performance Information J Performance Step: 4 (step 2.2)

Standard: Evacuates the Reactor Building by performing the following:

Sounds the Reactor Building Evacuation Alarm by placing the switch to REACTOR BLDG EVAC.

Announces: "Primary containment venting will commence in approximately 5 minutes. All personnel evacuate the Reactor Building immediately. Stand clear of the stack and the Reactor Building fan pad" on the PAGING phone.

Comment:

Performance Step: 5 (step 2.3)

~u-'

Standard: Selects a SGTS train at Panel 11R and places its control switch in the HAND position (exhaust fan starts: red light ON, green light OFF; fan inlet and outlet valves open: red light ON, green light OFF; orifice valve closes: green light ON, red light OFF)

NOTE: One SGTS train should already be running. The candidate may select the SGTS train that is already running, but still must place the control switch for that train in HAND.

Comment:

NRC Sim5 Page 4 of 10

Appendix C Form ES-C-1 Performance Information

. j Performance Step: 6 (step 2.4)

Standard: Closes SGTS Crosstie at Panel 11R placing the SGTS crosstie valve V-28-48 in the CLOSED position (green light ON; red light OFF).

Comment:

Performance Step: 7 (step 2.5)

Standard: Confirms RB Supply Fans secured at Panel 11R (RB Supply Fans Off: green light ON, red light OFF) u Comment:

Performance Step: 8 (step 2.6)

Standard: Confirm RB Exhaust Fans secured at Panel 11R (RB Exhaust Fans Off: green light ON, red light OFF)

Comment:

NRC Sim5 Page 5 of 10

Appendix C Form ES-C-1 Performance lnformation Performance Step: 9 (step 2.7)

Standard: At Panel 4F, verifies the Mode Switch is NOT in RUN.

Comment:

~~ ~~ ~ ~ ~

4 Performance Step: 10 (step 2.8)

Standard: Obtains one (1) bypass plug from the EOP toolbox in the Control Room.

Comment:

4 Performance Step: 11 (step 2.9.1)

Standard: Opens EOP BYPASS PLUGS panel at the rear of Panel lOXF,and inserts bypass plug into position BP5.

Comment:

NRC Sim5 Page 6 of 10

Appendix C Form ES-C-1 Performance Information J Performance Step: 12 (step 2.10)

Standard: Opens EOP BYPASS PLUGS panel at the rear of Panel 1 1R, removes bypass plug from position BP4 and inserts bypass plug into position BP1.

Comment:

4 Performance Step: 13 (step 2.1 1)

Standard: At Panel 11F, places the TORUS/ DRYWELL ISOLATION VALVE BYPASS PERMISSIVE keylock switch in the TORUS position.

NOTE: This switch is not labeled, but does have the following annotation above the keylock switch: Ensure Air Sample Taken Before Purging Drywell or Torus.

Comment:

4 Performance Step: 14 (step 2.12)

Standard: At Panel 11F, places the TORUS/DW VENT AND PURGE ISOL VLVS HI RAD BYP keylock switches for Channels 1 and 2 in the BYPASS position.

Comment:

NRC Sim5 Page 7 of 10

Appendix C Form ES-C-1 Performance Information i

u Performance Step: 15 (step 2.13)

Standard: Reports to the SRO that the Torus venting preparations are complete.

CUE: Acknowledge the report.

Comment:

Terminating Cue: Preparations for venting the Torus are complete IAW Section 2.0 of Support Procedure 32.

JPM Stop Time:

NRC Sim5 Page 8 of 10

Appendix C Form ES-C-1 Validation of Completion Job Performance Measure No. NRC Sim5 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

\.-

I

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

NRC Sim5 Page 9 of 10

Appendix C Form ES-C-1 STUDENT HANDOUT Initial Conditions:

1. The reactor scrammed due to a LOCA.
2. The mode switch is in SHUTDOWN.
3. Drywell pressure is 28 psig.
4. Torus venting has been directed by the EOPs.

Task Cue:

Prepare the torus for venting due to high Primary Containment pressure IAW Support Procedure 32, Section 2.0.

NRC Sim5 Page 10 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Ovster Creek Task No: 2640201003 Task

Title:

Perform the Emeraencv Diesel Generator Load Test (Alternate Path)

Job Performance Measure No: NRC Sim6 (RO/SRO)

WA

Reference:

264000 A4.04 (RO 3.7/SRO 3.7)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testinq:

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:

1. The Reactor is at 100% power, with all systems normally aligned.
2. All items listed in Prerequisite Section 3.0 of Procedure 636.4.003, Diesel Generator #I Load Test, have been verified.
3. Steps 6.1 through 6.5 of Procedure 636.4.003 have been completed.
4. The System Dispatcher has been contacted and grid conditions are stable.
5. An EO has been briefed, has a copy of the procedure and is stationed at EDG #1 with a radio.

Task Standard: Following startup/loading of EDGl for surveillance, EDGl has been shutdown by the Candidate.

Required Materials: Prepared copy of procedure 636.4.003 (up through step 6.5).

General

References:

1. Procedure 636.4.003, Diesel Generator #1 Load test, Rev. 74 NRC Sim6 Page 1 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Initiating Cue: Beginning with step 6.6, perform Diesel Generator #I Load Test IAW

.LJ' Procedure 636.4.003 for scheduled surveillance.

Time Critical Task: No Validation Time: 22 minutes Simulator Setup:

1. IC-65
2. Annunciator T3b, EDGl OV/GND: ANN-T-3B to ON during the EDG run (step 12)
3. Locally trip EDG1: LOA-DGN003 to STOP during the EDG run (step 13)
4. Setup EDG on the PPC NRC Sim6 Page 2 of 9

Appendix C Form ES-C-1 Performance Information Denote critical steps with a check mark Performance Step: 1 JPM Start Time:

Standard: Provide repeat back of initiating cue. Evaluator acknowledges repeat back.

Comment:

Performance Step: 2 Standard: Obtain a copy of the reference procedure and reviewhtilize the correct section (Procedure 636.4.003, Section 6.0).

Comment:

u Performance Step: 3 Standard: Verify Prerequisites, review Precautions and Limitations.

NOTE: All prerequisites have been verified, as outlined in the Initial Conditions.

Comment:

NRC Sim6 Page 3 of 9

Appendix C Form ES-C-1 L/ Performance Information Performance Step: 4 (step 6.6)

Standard: Confirms EDG lineup: At Panel 8F/9F:

UNIT START and UNIT IDLE lights are extinguished All EDG 1 alarms in their normal state (no alarms)

The EDG 1 MODE SELECTOR switch is in the PEAKING position Comment:

Performance Step: 5 (step 6.7)

Standard: Verifies an EO at EDG 1 prior to starting EDG 1.

CUE: As the EO, report that you are at EDG 1 standing-by.

Comment:

Performance Step: 6 (step 6.9)

Standard: To start the EDG At Panel 8F/9F, momentarily places EDG 1 NORMAL START switch to the START position.

NOTE: EDG will idle for approximately 90 seconds then accelerate to 900 RPM. EDG will then automatically synchronize, the breaker will close, and it will automatically achieve rated load (2750 KW).

Comment:

NRC Sim6 Page 4 of 9

Appendix C Form ES-C-1 Performance Information v

Performance Step: 7 (step 6.1 0)

Standard: Verifies EDG start at Panel 8F/9F, by observing UNIT START and UNIT IDLING lights illuminate.

Comment:

Performance Step: 8 (step 6.1 1)

Standard: Verifies proper creepy crank operation with the EO.

CUE: As the EO, report proper creepy crank operation.

Comment:

Performance Step: 9 (step 6.12)

Standard: Verifies EDG 1 automatically comes up to speed, automatically synchronizes with the line, EDG 1 load breaker closes (red light ON, green light OFF) and begins to pickup load (DG KW, KVAR, Amps rise on Panel 8F/9F)

Comment:

NRC Sim6 Page 5 of 9

~~

Appendix C Form ES-C-1 Performance Information ii/

Performance Step: 10 (step 6.13)

Standard: Observes EDG load rises automatically to approximately 2750 KW and records the initial full load achieved (acceptable range is 2600-2800 KW).

CUE: EDGl load is 2550 KW. (Load will be adjusted in the next step.)

Comment:

Performance Step: 11 (step 6.14.1 / 6.14.2)

Standard: 1) Places EDG 1 MODE SELECTOR switch to TRANSFER position.

2) Adjusts load to 2600-2800 KW using the EDGl GOVERNOR CONTROL switch to RAISE.

CUE: (after the initial adjustment:) EDG1 load is 2750 KW.

Note: Procedure steps 6.15 and 6.16 are not applicable.

Comment:

Performance Step: 12 (step 6.17)

Standard: Records time that load level of 2600-2800 KW was attained.

Comment:

NRC Sim6 Page 6 of 9

Appendix C Form ES-C-1 Performance Information Performance Step: 13 (step 6.18)

Standard: Adjusts KVAR load by adjusting the VOLTAGWKVAR CONTROL switch to obtain approximately +lo00 KVAR (lagging) (acceptable range is +200 to

+2000 KVAR lagging).

NOTE: KVAR load should be within the acceptable range of +200 to +2000. The Candidate may/may not adjust from within this range to attain +lo00 KVAR.

Comment:

J Performance Step: 14 NOTE: Input ANN-T-6-b, EDGl ENG TEMP HI, at this time.

u Standard: Responds to annunciator T6b: EDGl ENG TEMP HI

1) Directs NLO to verify proper louver operation.
2) Trips the EDG by placing the NORMAL START switch to the STOP position (KW, KVAR, amps lower; EDGl breaker opens [red light OFF, green light ON]).

CUE: The EDGl louvers are full open.

Comment:

Terminating Cue: Following startup/loading of EDGl for surveillance, EDGl has been shutdown by the Candidate.

JPM Stop Time:

NRC Sim6 Page 7 of 9

Appendix C Form ES-C-1 Val idation of Completion Job Performance Measure No. NRC Sim6 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

-\1

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

NRC Sim6 Page 8 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET u-Facility: Ovster Creek Task No: 2180401001 Task

Title:

Perform EMRV ODerabilitv Test w/ Stuck ODen EMRV (Alternate Path)

Job Performance Measure No: NRC Sim7 (RO/SRO)

WA

Reference:

239002 A2.03 (RO4.1/SRO 4.21 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

-L---.

performance measure will be satisfied.

Initial Conditions:

1. A reactor startup is in progress.
2. Reactor power is less that 5%.
3. Reactor water level, power, and pressure are constant.
4. RPV water level control is in manual, and will be controlled by another Operator
5. EMRV Operability Testing is required for valve NR-108A only.
6. Procedure steps 6.1 through 6.24 of 602.4.003, Electromatic Relief Valve Operability Test, have been completed for EMRV NR-108A.

Task Standard: The EMRV has been closed when the NR-108A EMRV Normal/Disable keylock switch has been placed in DISABLE.

NRC Sim7 Page 1 of 9

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

.-- , Required Materials:

1. Stopwatch
2. Prepared copy of 602.4.003 (completed up through step 6.24)

General

References:

1. 602.4.003, Electromatic Relief Valve Operability Test, Rev. 29
2. ABN-40, Stuck Open EMRV, Rev. 2 Initiating Cue: Complete procedure 602.4.003, Electromatic Relief Valve Operability Test for EMRV NR-108A1beginning at step 6.25.

Time Critical Task: No Validation Time: 23 minutes Simulator Setup:

1. Low power IC (about 5% power)
2. FW Control in manual
3. EMRV 108A control switch stuck in the MAN position (open) AFTER the valve is

..--- . opened: SWI-ADS001C to ON NRC Sim7 Page 2 of 9

Appendix C Form ES-C-1 Performance Information

.-4 Denote critical steps with a check mark Performance Step: 1 JPM Start Time:

Standard: Provide repeat back of initiating cue. Evaluator acknowledges repeat back.

Comment:

Performance Step: 2 Standard: Obtain a copy of the reference procedure and reviewhtilize the correct section (602.4.003).

Comment:

Performance Step: 3 Standard: Reviews Precautions and Limitations.

Comment:

NRC Sim7 Page 3 of 9

Appendix C Form ES-C-1 Performance Information 4 Performance Step: 4 (step 6.25)

CUE: Tell the Candidate that you will record the valve stroke times for him.

Standard: At Panel 1F/2F, places the control switch for EMRV NR-108A in the MAN position and starts the stopwatch (red light ON; green light OFF).

Comment:

Performance Step: 5 (step 6.26)

Standard: When annunciator SV/EMRV NOT CLOSED (B-4-g) alarms, stop the stopwatch; records time on Attachment 602.4.003-1 (See CUE in Step 4).

At Panel 1F/2F, verifies:

Red light is lit and green light is extinguished for EMRV NR-108A.

Acoustic valve monitor is in the valve open region.

Annunciator EMRV OPEN (B-3-g) is in alarm.

Comment:

NRC Sim7 Page 4 of 9

Appendix C Form ES-C-1 Performance Information

--J, Performance Step: 6 (step 6.27)

NOTE: The EMRV will NOT close at this time and remains open.

Standard: At Panel 1F/2F, 5 seconds after opening NR-l08A, places its control switch in the AUTO position and starts the stopwatch.

ReporWrecognizes EMRV will not close (red light ON, green light OFF; acoustic monitor still shows in the Valve Open Region (red); annunciators still in alarm), and enters ABN-40, Stuck Open EMRV.

Comment:

Performance Step: 7 (step 3.1 of ABN-40)

Standard: Verifies EMRV open (by any of the following): red light ON, acoustic monitor shows valve open (red region), EMRV discharge temperature high.

CUE: If requested to verify EMRV tailpiece temperature on RB 23',report the temperature is about 320" F.

Comment:

IWC Sim7 Page 5 of 9

Appendix C Form ES-C-1 Performance Information

--+-

Performance Step: 8 (step 3.2)

Standard: Verifies Feedwater Control in Manual CUE: Another Operator has confirmed Manual Control on the Master Controller and will be controlling feedwater.

Comment:

Performance Step: 9 (step 3.2.3/3.2.4)

Standard: At Panel 1F/2F, places EMRV NR-108A control switch in the OFF position; recognizes EMRV is still open (acoustic monitor still in the RED area; valve red light still ON; annunciators still lit; tailpiece temperature still high).

Comment:

Performance Step: 10 (step 3.2.5/3.2.6)

Standard: At Panel 1F/2F, cycles EMRV NR-108A control switch from OFF to MAN to OFF another 3-5 times in an attempt to close the EMRV; recognizes EMRV is still open (acoustic monitor still in the RED area; valve red light still ON; annunciators still lit; tailpiece temperature still high).

Comment:

NRC Sim7 Page 6 of 9

Appendix C Form ES-C-1 NOTE:

Performance Information Performance Step: 11 (step 3.2.7)

When the Normal/Disable keylock switch is placed in DISABLE, red/green position indication lights for the valve are lost on Panel 1FEF.

Standard: In the rear of Panel 1FEF, places NR-108A EMRV NormaVDisable keylock switch in DISABLE. Verifies EMRV closes (acoustic monitor in the Valve Closed Region (white); tailpiece temperature lowering).

Reports that the EMRV is closed (not required for critical task).

CUE: Acknowledge the report.

Note: This action will close the EMRV.

Comment:

-. .- Terminating Cue: The EMRV has been closed when the NR-108A EMRV NormaVDisable keylock switch has been placed in DISABLE.

JPM Stop Time:

NRC Sim7 Page 7 of 9

Appendix C Form ES-C-1 Validation of Completion Job Performance Measure No. NRC Sim7 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: SatisfactoryAJnsatisfactory Examiners signature and date:

NRC sim7 Page 8 of 9

Appendix C Form ES-C-1 STUDENT HANDOUT Initial Conditions:

1. A reactor startup is in progress.
2. Reactor power is less that 5%.
3. Reactor water level, power, and pressure are constant.
4. RPV water level control is in manual, and will be controlled by another Operator.
5. EMRV Operability Testing is required for valve NR-108A only.
6. Procedure steps 6.1 through 6.24 of 602.4.003, Electromatic Relief Valve Operability Test, have been completed for EMRV NR-108A.

Task Cue:

Complete procedure 602.4.003, Electromatic Relief Valve Operability Test for EMRV NR-l08A, beginning at step 6.25.

NRC Sim7 Page 9 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET l-/,

Facility: Ovster Creek Task No: 2610101006 Task

Title:

Reset SGTS After Auto Initiation (RO/SRO)

Job Performance Measure No: NRC Sim8 WA

Reference:

261000 A4.03 (RO 3.O/SRO 3.0)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job

+ performance measure will be satisfied.

Initial Conditions:

1. The Reactor is at 100% power.
2. Reactor water level, power, and pressure are in the normal bands.
3. SGTS 1 is operating due to a spurious initiation signal from the Reactor Building Vent Manifold Chl.
4. The cause of the false initiation has been corrected.

Task Standard: The Standby Gas Treatment System 1 has been secured following an automatic initiation.

Required Materials: None.

General

References:

Procedure 330, Standby Gas Treatment System, Rev. 43 Initiating Cue: Secure SGTS IAW Procedures 330, Standby Gas Treatment System.

Another Operator is currently reviewing the procedure to restore normal RB HVAC.

NRC Sim8 Page 1 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Time Critical Task: No Validation Time: 13 minutes Simulator Setup:

1. IC-65.
2. Confirm that SGTS 1 is lead.
3. Perform trip check of RB Vent Manifold Channel 1 to initiate SGTS.

W NRC Sim8 Page 2 of 8

Appendix C Form ES-C-1 Performance Information 4

Denote critical steps with a check mark

~~~

Performance Step: 1 JPM Start Time:

Standard: Provides repeat back of initiating cue. Evaluator acknowledges repeat back.

Comment:

Performance Step: 2 Standard: Obtains a copy of the reference procedure and review/utilize the correct section (Procedure 330, Section 6.0).

Comment:

-4 Performance Step: 3 Standard: Verify Prerequisites, review Precautions and Limitations.

CUE: All prerequisites have been met.

Comment:

NRC Sim8 Page 3 of 8

Appendix C Form ES-C-1 u Performance Information 4 Performance Step: 4 (step 6.3.1.2)

Standard: At Panel 2R, depresses RESET pushbutton on the Indicator and Trip Unit for Reactor Building Vent Manifold CH 1 (the HIGH amber light extinguishes).

Comment:

Performance Step: 5 (step 6.3.1.3)

Standard: Verifies proper system lineup at Panel 11R:

e Exhaust Fan EF-1 off (green light ON; red light OFF)

Exhaust fan EF-1 off (green light ON; red light OFF)

-e' SGTS I inlet valve V-28-23 -closed (green light ON; red light OFF)

SGTS I orifice valve V-28 closed (green light ON; red light OFF)

SGTS I outlet valve V-28 closed (green light ON; red light OFF)

SGTS I I inlet valve V-28 closed (green light ON; red light OFF)

SGTS II orifice valve V-28 closed (green light ON; red light OFF)

SGTS II outlet valve V-28 closed (green light ON;red light OFF)

SGTS crosstie valve V-28 open (red light ON; green light OFF)

Reactor Building Isolation reset indication - double indication (red TRIP light ON; green RESET light ON)

Comment :

NRC Sim8 Page 4 of 8

Appendix C Form ES-C-1 Performance Information Performance Step: 6 (step 6.3.1.4)

Standard: At Panel 11R, depresses Reactor Building Ventilation isolation RESET button (red TRIP light OFF; green RESET light ON). Restarts RB Ventilation IAW procedure 329.

CUE: Another Operator will restart normal RB ventilation IAW Procedure 329 momentarily.

NOTE: The Candidate may stop here since normal RB ventilation is not yet running, as required by the current procedure step. This is allowed.

Comment:

Performance Step: 7 (step 6.3.1.5)

.-,' Standard: Directs EO to reset the strip heaters at local panel ATC-P-15, and to verify both green lights are illuminated.

CUE: As the EO, report: The strip heaters at panel ATC-P-15 have been reset and both green lights are illuminated.

Comment:

Performance Step: 8 (6.3.1.6)

Standard: At Panel 11R, verifies control switch for SGTS Crosstie valveV-28-48 is in the AUTO position (red light ON; green light OFF).

Comment:

NRC Sim8 Page 5 of 8

Appendix C Form ES-C-1 Performance Information Terminating Cue: The Standby Gas Treatment System 1 has been secured following an automatic initiation.

JPM Stop Time:

NRC Sim8 Page 6 of 8

Appendix C Form ES-C-1 Validation of Completion Job Performance Measure No. NRC Sim8 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

-.-d-

~ ~ ~ ~~~

Result: Satisfactory/Unsatisfactory Examiners signature and date:

NRC Sim8 Page 7 of 8

AmerGen.

An freba Coqipany 1 I

OYSTER CREEK GENERATING STATION PROCEDURE 1I I

Number 330 Title Usage Level I Revision No.

Standby Gas Treatment System 1 43 This Revision Changes the Valve Lineup Yes X No Prior Revision 42 incorporatedthe This Revision 43 incorporates the following Temporary Changes: following Temporary Changes:

N/A N/A List of Pages 1.0 to 28.0 E l - I to El-6 E2-1 to E2-2 1.o

AmerGen. OYSTER CREEK GENERATING STATION PROCEDURE Number AP f x t h Company 329 W

Title Usage Level Revision 51 Reactor Building Heating, Cooling and Ventilation System 1 THIS PROCEDURE CONTAINS A CHANGE TO THE VALVE LINEUP YES X NO Prior Revision 50 incorporatedthe This Revision 51 incorporatesthe following Temporary Changes: following Temporary Changes:

-N/A -N/A List of Pages 1.Oto 32.0 E l - I to El-I2 E2-1 to E2-2 E3-1 to E3-2 4-1 to E4-2 E5-1 to E5-2 E6-1 E7-1 to E7-7 E8-I E9-1 1.o

AmerGenw OYSTER CREEK GENERATING Number A n idebn Company STATION PROCEDURE 329

=d Title Revision No.

Reactor Building Heating, Cooling and Ventilation System 51 3.3 Startup and Operatinq Instructions 3.3.1 CONFIRM Reactor Building Heating, Cooling and Ventilation System is lined up in accordance with the following (As determined by the OS):

Attachment 329-1, Valve Check-Off List for Reactor Bldg HVAC System 0 Attachment 329-2, Electrical Check-Off List for Reactor Bldg HVAC System 0 Attachment 329-3, Damper Check-Off List Reactor Bldg Ventilation System 3.3.2 CONFIRM control switch for V-28-21 and V-28-22 in the OPEN position (Panel 11R).

3.3.3 CONFIRM all Reactor Building Heating, Cooling, and Ventilation System trips are reset by depressing the RESET button (Panel I 1R).

3.3.4 CONFIRM red open indication for valves V-28-21 and V-28-22 (Panel 11R).

3.3.5 CONFIRM control switch for V-28-42 and V-28-43 in the CLOSE position (Panel 11R).

3.3.6 CAUTION Both Reactor Building Supply Fans should be immediately started (Step 3.3.8) after starting the Reactor Building Exhaust Fan to preclude damage to the ventilation system ducts.

IF Exhaust Fan EF-1-5 is to be started, THEN PERFORM the following:

1. CONFIRM DM-28-006 is OPEN.
2. CONFIRM DM-28-008 is CLOSED.
3. START Exhaust Fan EF-1-5 by placing control switch to START (Panel 1IR).

10.0

=J Title AmerGen, An Cxclon Company I OYSTER CREEK GENERATING STATION PROCEDURE I bJu~ber 329 Revision No.

Reactor Building Heating, Cooling and Ventilation System 51 3.3.7 I NOTE Water drained from EF-1-6 shall be treated as potentially contaminated.

IF

- Exhaust Fan EF-1-6 is to be started, THEN PERFORM the following:

1. DRAIN any standing water from EF-1-6 by setting up the draining rig and opening V-28-71. [ I
2. WHEN water has stopped draining, THEN CLOSE V-28-71 and SECURE the drain rig. [ I
3. CONFIRM DM-28-006 is CLOSED. [ I
4. CONFIRM DM-28-008 is OPEN [ I
5. CONTACT NRW Control Room to confirm the NRW Exhaust Fans are running prior to starting EF-1-6. [ I
6. START Exhaust Fan EF-1-6 by placing control switch to START (Panel 11R). [ I 3.3.8 START two of the following Supply Fans by placing the appropriate two control switches to the START position and VERIFY red ON indication (Panel 11R): [ I SF-1-12 SF-1-13 SF-1-14 11.0

'\/' Title AmerGen, An fxeaonCompany OYSTER CREEK GENERATING STATION PROCEDURE 1 bJumber 329 Revision No.

Reactor Building Heating, Cooling and Ventilation System 51 3.3.9 CONFIRM the following Reactor Building Ventilation System Isolation Valves have red open indication (Panel 11R):

Valve Function I v-28-1 V-28-2 Fuel Pool [ I V-28-3 Reactor cavity, steam dryer and V-28-4 separator storage well [ I v-28-5 V-28-6 Reactor Building El. 95' [ I 1 v-28-7 V-28-8 Reactor Building El. 95' [ I v-28-9 V-28-10 Reactor Building El. 75' [ I v-28-1 V-28-12 Reactor Building El. 75' [ I v-28-13 V-28-14 Reactor Building El. 51' and 23' [ I v-28-15 V-28-16 Reactor Building El. 51' and 23' [ I V-28-36 Reactor cavity, steam dryer and V-28-37 separator storage well [ I v-28-38 V-28-39 Fuel Pool [ I 3.3.10 If drywell is being purged with fresh air, THEN PLACE control switch for V-28-42 and V-28-43 to OPEN and VERIFY red open indication (Panel 11R). [ ]

12.0

-J Title AmerGen-An Cxeh?~Company OYSTER CREEK GENERATING STATION PROCEDURE I hJumber 329 Revision No.

Reactor Building Heating, Cooling and Ventilation System 51 3.3.11 NOTE Reactor Building pressure adjustments can be made by manipulating Supply Fan Outlet dampers and Exhaust Fan Vortex dampers (See Attachment 329-3).

CHECK Reactor Building pressure is being maintained at approximately negative 0.25 in WG pressure (Panel 11R).

3.3.12 CHECK Reactor Building temperature is being maintained at equal to or greater than 40°F by one_ of the following methods:

3.3.12.1 VERIFY supply air temperature to the Reactor Building is greater than 40°F as indicated on the plant computer system (33 elevation temperature).

3.3.12.2 VERIFY general area temperatures on all elevations, except 119, are greater than 40°F using local temperature indicators within the Reactor Building listed on Attachment 329-9. [ I 3.3.13 USE the following guidelines to avoid the negative consequences of cold weather:

1. Attachment 329-7.1, Normal Reactor Building Ventilation Operating: Heating Available. [ I
2. Attachment 329-7.2, Normal Reactor Building Ventilation Operating: Heating Out Of Service. [ I
3. Attachment 329-7.3, SBGT System Operating:

No Additional Heating. [ I 13.0

Form ES-C-1 STUDENT HANDOUT Initial Conditions:

1. The Reactor is at 100% power.
2. Reactor water level, power, and pressure are in the normal bands.
3. SGTS 1 is operating due to a spurious initiation signal from the Reactor Building Vent Manifold Chl .
4. The cause of the false initiation has been corrected.

Task Cue:

Secure SGTS IAW Procedures 330, Standby Gas Treatment System. Another Operator is currently reviewing the procedure to restore normal RB HVAC.

NRC Sim8 Page 8 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET v

Facility: Ovster Creek Task No: 2090501403/2090504401 Task

Title:

Alian the Core Sway Svstem to the Condensate Storaae Tank for Emeraencv Operations Job Performance Measure No: NRC Plantl (RO/SRO)

WA

Reference:

295030 G2.1.30 (RO 3.7/SRO 4.4)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testinq:

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:

1. The Reactor is shutdown.
2. Reactor water level is being maintained at 160 inches with feedwater.
3. Drywell pressure is 1.1 psig and stable.
4. Torus water level is 140 inches and lowering due to a leak.
5. The Reactor Building is accessible.
6. Core Spray System 1 is operable and available.

Task Standard: Making-up to the Torus from the CST via Core Spray System 1 in accordance with Support Procedure 37.

Required Materials: MB-1 and PA-2235 keys (simulated)

General

References:

Support Procedure 37 of EMG-3200.02, Primary Containment Control, Rev. 17 NRC Plantl Page 1 of 8

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

~ ~~ ~~ ~ ~~

Initiating Cue: Line up and add makeup to the torus from the CST via Core Spray System

'-. 1 in accordance with Support Procedure 37.

Time Critical Task: No Validation Time: 40 minutes

?e.

NRC Plant1 Page 2 of 8

Appendix C Form ES-C-1 Performance Information Denote critical steps with a check mark Performance Step: 1 JPM Start Time:

Standard: Provides repeat back of initiating cue. Evaluator acknowledges repeat back.

Comment:

Performance Step: 2 Standard: Obtains a copy of the reference procedure, Support Procedure 37, and reviewshtilizes the correct section.

. Comment:

Performance Step: 3 Standard: Verifies Prerequisites.

Comment:

NRC Plant1 Page 3 of 8

Appendix C Form ES-C-1

--..-/ Performance Information Performance Step: 4 (step 3.2.4.1)

CUE: Report that the following steps have been completed:

0 System 1 Core Spray Main Pumps and Booster Pumps are stopped (step 3.2.1) 0 Core Spray System suction valves V-20-3 and V-20-32 are closed (step 3.2.2) 0 Core Spray System 1 Parallel Isolation valves V-20-15 and V-20-40 are closed (step 3.2.3)

Standard: Places the Core Spray pump suction valve breakers in OFF:

V-20-3 (MCC 1A21A RB 23 SW)

V-20-32 (MCC 1821A RB 23 NE)

CUE: The breakers for valve V-20-3 and V-20-32 are in the OFF position.

Comment:

J Performance Step: 5 (step 3.2.4.2)

Standard: Using MB-1 key, unlocks and opens the following CST valves:

0 V-20-1 (NW corner Room)

V-20-5 (NW corner Room)

V-20-34 (NW corner Room)

CUE: Valves V-20-1, V-20-5, and V-20-34 are unlocked and open.

NOTE: If the Candidate does not have the proper keys, ask where they can be obtained:

the Controlled Key Locker in the Shift Managers Office. (Not required to go get the key)

Comment:

NRC Plant1 Page 4 of 8

Appendix C Form ES-C-1 Performance Information 1

Performance Step: 6 (step 3.2.4.3)

Standard: Calls the Control Room to start Core Spray System 1 main pump NZOlA or NZOl C.

CUE: Acknowledge the report. State that Core Spray Pump NZOlA has been started and is running.

Comment:

J Performance Step: 7 (step 3.2.6)

Standard: Using the MB-1 key, unlocks and places the breaker for V-20-27 in the ON position (MCC 1A21B RB 23 E).

J

,-. CUE: V-20-27 breaker is ON.

Comment:

4 Performance Step: 8 (step 3.2.7)

Standard: On RB 51 NW, uses the PA-2235 key to open Torus Test Flow Return valve V-20-27 by placing upper keylock switch to the OPEN position (red light ON).

CUE: Valve V-20-27 indicates full open (red light on). (See comment regarding KEYS in Step 5)

Comment:

NRC Plant1 Page 5 of 8

~~~ ~

Appendix C Form ES-C-1

&d Performance Information Performance Step: 9 Standard: Calls the Control Room to report the lineup is complete to makeup to the torus from the CST is in progress.

CUE: (As Reactor Operator) repeat back the operators report.

Comment:

Terminating Cue: Making-up to the Torus from the CST via Core Spray System 1 in accordance with Support Procedure 37.

JPM Stop Time:

NRC Plant1 Page 6 of 8

Appendix C Form ES-C-1

~~ ~

Validation of Completion

---a Job Performance Measure No. NRC Plantl Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

NRC Plantl Page 7 of 8

Appendix C Form ES-C-1 STUDENT HANDOUT Initial Conditions:

1. The Reactor is shutdown.
2. Reactor water level is being maintained at 160 inches with feedwater.
3. Drywell pressure is 1.1 psig and stable.
4. Torus water level is 140 inches and lowering due to a leak.
5. The Reactor Building is accessible.
6. Core Spray System 1 is operable and available.

Task Cue:

Line up and add makeup to the torus from the CST via Core Spray System 1 in accordance with Support Procedure 37.

'La--

NRC Plant1 Page 8 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET iv-Facility: Ovster Creek Task No: 2630101003/2630104009 Task

Title:

Shift Battew Charaers Job Performance Measure No: NRC Plant2 (RO/SRO)

WA

Reference:

263000 K1.02 (RO 3.2/SRO 3.3)

Examinee: NRC Examiner:

FaciIity Eva1uator: Date:

Method of testinq:

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

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

Initial Conditions:

1. Static Charger C1 is currently in service supplying DC-C.
2. Electricians need to perform scheduled maintenance on Static Charger C1 while still energized from its AC source.
3. Static Charger C2 has been verified to be in standby readiness.
4. Isolation Condenser valves V-14-33 and V-14-35 have been declared inoperable and the appropriate Tech Spec LCOs have been entered by the Control Room SRO.

Task Standard: Static Charger C1 is removed from service and Static Charger C2 is in service.

Required Materials: None General

References:

Procedure 340.3, 125 Volt DC Distribution System C, Rev. 27 Initiating Cue: Transfer operation from Static Charger C1 to Static Charger C2 IAW Procedure 340.3, 125 Volt DC Distribution System C, Section 6.0.

NRC Plant2 Page 1 of 8

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

.u' Time Critical Task: No

~~

Validation Time: 16 minutes NRC Plant2 Page 2 of 8

Appendix C Form ES-C-1 Performance Information

-=

Denote critical steps with a check mark

~~~ ~ ~~ ~

Performance Step: 1 JPM Start Time:

Standard: Provides repeat back of initiating cue. Evaluator acknowledges repeat back.

Comment:

Standard: Obtains a copy of the reference procedure, Procedure 340.3, 125 Volt DC Distribution System C, and reviewshtilizes the correct section (Section 6.0).

Comment:

w Performance Step: 3 Standard: Verifies Prerequisites and reviews Precautions and Limitations.

Comment:

NRC Plant2 Page 3 of 8

Appendix C Form ES-C-1

~~ ~~

Performance Information

-k 4 Performance Step: 4 (step 6.3.3.1)

Standard: Places the DC output breaker for Charger C1 (at charger cabinet) in the OFF position.

CUE: The DC output breaker for Charger C1 is in the OFF position.

Comment:

4 Performance Step: 5 (step 6.3.3.2)

Standard: Places the breaker for Charger C1 on DC-C (in 4160V Room) in the OFF position.

<J' CUE: The breaker for Charger C1 on DC-C (in 41 60V Room) in the OFF position.

Comment:

- Performance Step: 6 (step 6.3.4.1)

Standard: Places the breaker for Charger C2 on DC-C (in 4160V Room) in the ON position.

CUE: The breaker for Charger C2 on DC-C (in 41 60V Room) in the ON position.

Comment:

NRC Plant2 Page 4 of 8

~~

Appendix C Form ES-C-1 Performance Information Performance Step: 7 (step 6.3.4.2)

Standard: Checks Charger C1 voltage against Battery Bus voltage.

CUE: Charger output voltage and battery bus voltage both indicate 133 volts (no adjustments are required).

Comment:

~~~ ~

4 Performance Step: 8 (step 6.3.4.3)

Standard: Places the DC output breaker for Charger C2 (at charger cabinet) in the ON position.

- ., CUE: The DC output breaker for Charger C2 (at charger cabinet) in the ON position.

Comment:

Performance Step: 9 (step 6.3.5)

Standard: Checks Battery Bus voltage to maintain DC System voltage 130.2 - 135 volts.

CUE: DC Battery Bus voltage indicates 133 volts (no adjustments are required).

Comment:

NRC Plant2 Page 5 of 8

Appendix C Form ES-C-1 Performance Information Performance Step: 10 (steps 6.3.6, 6.3.7, and 6.3.8)

Standard: Calls the Control Room to report Static Charger C2 is supplying DC-C.

Requests they declare V-14-33 and V-14-35 operable and exit the applicable Tech Specs.

CUE: (As the Control Room) V-14-33 and V-14-35 have been declared operable; Tech Spec 3.7.D. 1, 3.8.C and 3.8.E have been exited.

Comment:

Terminating Cue: Static Charger C1 has been removed from service and Static Charger C2 has been placed into service.

JPM Stop Time:

NRC Plant2 Page 6 of 8

Appendix C Form ES-C-1 Validation of Completion Job Performance Measure No. NRC Plant2 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: SatisfactoryAJnsatisfactory Examiners signature and date:

NRC Plant2 Page 7 of 8

Appendix C Form ES-C-1 STUDENT HANDOUT Initial Conditions:

1. Static Charger C1 is currently in service supplying DC-C.
2. Electricians need to perform scheduled maintenance on Static Charger C1 while still energized from its AC source.
3. Static Charger C2 has been verified to be in standby readiness.
4. Isolation Condenser valves V-14-33 and V-14-35 have been declared inoperable and the appropriate Tech Spec LCOs have been entered by the Control Room SRO.

Task Cue:

Transfer operation from Static Charger C1 to Static Charger C2 IAW Procedure 340.3, 125 Volt DC Distribution System C, Section 6.0.

MANIPULATIONS OF P NRC Plant2 Page 8 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET 4

Facility: Oyster Creek Task No: 2860401402/2070501401/2070504401 Task

Title:

LineuD Fire Protection to the Isolation Condensers Job Performance Measure No: NRC Plant3 (RO/SRO)

WA

Reference:

286000 G2.4.35 1RO 3.3/SRO 3.5)

Examinee: NRC Examiner:

FaciI ity Eva1uator: Date:

Method of testinq:

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

Initial Conditions:

1. The Reactor is scrammed and isolated.
2. Condensate transfer pump A is out of service.
3. Condensate transfer pump B has failed.
4. Isolation Condenser A has initiated from the standby readiness condition.
5. The Fire Water System is operable and available.

Task Standard: Fire Protection System lined up to Isolation Condenser A Required Materials: Fire Protection key (simulated)

General

References:

Procedure 307, Isolation Condenser System, Rev. 92 Initiating Cue: Lineup the Fire Protection System to makeup to Isolation Condenser A in accordance with Procedure 307, Isolation Condenser System, Section 7.0.

Notify the Control Room when the line-up is complete.

NRC Plant3 Page 1 of 7

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

~ ~

Time Critical Task: No Validation Time: 16 minutes Note: Some simulated valve manipulations occur in a contaminated area. The Candidate is NOT to reach across the contamination barrier.

NRC Plant3 Page 2 of 7

Appendix C Form ES-C-1 Performance Information Denote critical steps with a check mark Performance Step: 1 JPM Start Time:

Standard: Provide repeat back of initiating cue. Evaluator acknowledges repeat back.

Comment:

Performance Step: 2 Standard: Obtain a copy of the reference procedure and reviewhtilize the correct section (Procedure 307, Section 7.0).

Comment:

Performance Step: 3 Standard: Verify Prerequisites and reviews Precautions and Limitations.

CUE: All prerequisites have been met, Comment:

NRC Plant3 Page 3 of 7

Appendix C Form ES-C-1 Performance Information

d 4 Performance Step: 4 (step 7.3.2.1)

Standard: Closes Isolation Condenser Supply Isolation Valve V-11-41 on Reactor Building 23' elevation East.

CUE: Valve V-11-41 is closed.

Comment:

Performance Step: 5 (step 7.3.2.2)

Standard: Closes Makeup to Isolation Condenser Telltale Drain Valve V-11-63 on Reactor Building 23' elevation East.

L X '

CUE: Valve V-11-63 is closed.

Comment:

Performance Step: 6 (step 7.3.2.3)

Standard: Using the Fire Protection key, unlocks and opens Fire Protection to Isolation Condenser Cross-Tie Isolation Valve V-9-2099 on Reactor Building 23' elevation East.

CUE: Valve V-9-2099 is unlocked and open. Note: If the Candidate does not have the key to unlock this valve, ask where the appropriate key can be obtained: the key can be obtained from the Controlled Key Locker in the Shift Manager's Office (NOT required to go back for the key).

L- '

NRC Plant3 Page 4 of 7

Appendix C Form ES-C-1

~ ~~ ~~~

Performance Information

-d Comment:

Performance Step: 7 (step 7.3.2.4)

Standard: Opens Fire Protection to Isolation Condenser Makeup Valve V-11-49 on Reactor Building 23 elevation East.

CUE: Valve V-11-49 is open.

NOTE: This completes the in-plant lineup for CST to Isolation Condenser A. The Candidate should report in this step or next, that the in-plant lineup is complete.

Comment:

Performance Step: 8 (step 7.3.2.5)

Standard: Requests Control Room record initial isolation condenser shell level.

CUE: Shell water level will be recorded.

Comment:

Terminating Cue: Fire Protection System is lined up to Isolation Condenser A JPM Start Time:

NRC Plant3 Page 5 of 7

Appendix C Form ES-C-1 Validation of Completion Job Performance Measure No. NRC Plant3 Examinees Name:

Examiners Name:

Date Performed:

FaciIity Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

NRC Plant3 Page 6 of 7

Appendix C Form ES-C-1 STUDENT HANDOUT Initial Conditions:

1. The Reactor is scrammed and isolated.
2. Condensate transfer pump A is out of service.
3. Condensate transfer pump B has failed.
4. Isolation Condenser A has initiated from the standby readiness condition.
5. The Fire Water System is operable and available.

Task Cue:

Lineup the Fire Protection System to makeup to Isolation Condenser A in accordance with Procedure 307, Isolation Condenser System, Section 7.0. Notify the Control Room when the line-up is complete.

NRC Plant3 Page 7 of 7

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