Text

Draft Operating Exam (Sections a, B, and C) (Folder 2)
	ML111870278
Person / Time
Site:	Oyster Creek
Issue date:	05/27/2011
From:	Todd Fish; Operations Branch I
To:	; Exelon Nuclear
	Hansell S
Shared Package
ML110030666	List: IR 05000219/2011301; ML111810110; ML111870186; ML111870261; ML111870267; ML111870274; ML111870278; ML112130525; ML112130528; ML112130534; ML112130541;
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Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: C00000044

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

Task

Title:

Week 4 Safety Related Equipment Verification Job Performance Measure No.: NRC Admin JPM1 (RO)

KIA

Reference:

_G.=2.:....:..1=.2:....:..9->.{_4._1L-)_ _ _ _ _ __

Examinee: 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 satis'fied.

Initial Conditions:

1. The plant is at rated power Task Standard: Three instances of improper EOP Jumper Bypass Plug placement have been identified. The Acceptance Criteria is declared UNSAT (not met)

Required Materials: None.

General

References:

1. 680.4.007, Safety Related Equipment Verification, Revision 14 Initiating Cue: Complete Section 6.4, Week Four Verification, lAW 680.4.007, Safety Related Equipment Verification, starting at Step 6.4.3.

Time Critical Task: No.

Validation Time: 10 Minutes ILT 10-1 NRC RO ADMIN JPM1 Page 1 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark '"

Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time: _ _ _ __

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

Comment:

SAT/UNSAT Performance Step: 2 Procedure Step: Verifies Prerequisites and reviews Precautions and Limitations.

Standard: Verifies Prerequisites and reviews Precautions and Limitations.

Comment:

SAT/UNSAT ILT 10-1 NRC RO ADMIN ..IPM1 Page 2 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Procedure Step: 6.4.3.1 Verify that the bypass plugs are positioned as follows:

1. EOP Bypass Plug Panel in rear of Panel 2R

Bypass plug in position BP1

Bypass plug in position BP2

No other plugs inserted Standard: Verifies that the bypass plugs are positioned as follows:

1. EOP Bypass Plug Panel in rear of Panel 2R

Bypass plug in position BP1

Bypass plug in position BP2

No other plugs inserted Comment:

SAT/UNSAT ILT 10-1 I\lRC RO ADMIN JPM1 Page 3 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 4 Procedure Step: 6.4.3.2 Verify that the bypass plugs are positioned as follows:

2. EOP Bypass Plug Panel in rear of Panel 3F

BP2, BP4, BP6, BP8, BP10, BP12, BP14

No other plugs inserted Standard: Verifies that the bypass plugs are positioned as follows:

2. EOP Bypass Plug Panel in rear of Panel 3F

BP2, BP4, BP6, BP8, BP10, BP12, BP14

No other plugs inserted

Reports that no plug is located in BP14 Cue: Acknowledge the report and tell the Candidate to continue (Leave the plugs in their current positions)

Comment:

SAT/UNSAT Performance Step: 5 Procedure Step: 6.4.3.3 Verify that the bypass plugs are positioned as follows

3. EOP Bypass Plug Panel in rear of Panel 6R

No plugs inserted Standard: VerHies that the bypass plugs are pOSitioned as follows

3. EOP Bypass Plug Panel in rear of Panel 6R

No plugs inserted Comment:

SAT/UNSAT ILT 10-1 NRC RO ADMIN JPM1 Page 4 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 6 Procedure Step: 6.4.3.4 Verify that the bypass plugs are positioned as follows

4. EOP Bypass Plug Panel in rear of Panel7R

1\10 plugs inserted Standard: Verifies that the bypass plugs are positioned as follows

4. EOP Bypass Plug Panel in rear of Panel7R

No plugs inserted Comment:

SAT/UNSAT Performance Step: 7 Procedure Step: 6.4.3.5 Verify that the bypass plugs are positioned as follows

5. EOP Bypass Plug Panel in rear of Panel 11 R

Bypass plug in position BP4

No other plugs installed Standard: Verifies that the bypass plugs are positioned as follows

5. EOP Bypass Plug Panel in rear of Panel 11 R

Bypass plug in position BP4

No other plugs installed

Reports that plug is installed in BP2 instead of BP4 Cue: Acknowledge the report and tell the Candidate to continue (Leave the plugs in their current positions)

Comment:

SAT/UNSAT ILT 10-1 NRC RO ADMIN JPM1 Page 5 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 8 Procedure Step: 6.4.3.6 Verify that the bypass plugs are positioned as follows

6. EOP Bypass Plug Panel inside of Panel 10XF

Bypass plug in position BP2

Bypass plug in position BP4

No other plugs installed Standard: Verify that the bypass plugs are positioned as follows

6. EOP Bypass Plug Panel inside of Panel 10XF

Bypass plug in position BP2

Bypass plug in position BP4

No other plugs installed

Reports that plug is installed in BP3 Cue: Acknowledge the report and tell the Candidate to continue (Leave the plugs in their current positions)

Comment:

SAT/UNSAT ILT 10-1 NRC RO ADMIN JPM1 Page 6 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 9 Procedure Step: 6.4.4 Compare results of this surveillance with Section 7.0, Acceptance Criteria. Record comments/discrepancies.

Standard: Reviews Acceptance Criteria and determines the Acceptance Criteria 7.1.3 is Unsat (has not been met)

Note: For failure of the acceptance criteria, the procedure then directs that the requirements of LS-OC-125 be followed. That procedure has been superseded by LA-AA-125, Corrective Action program, which would require generation of an IR or AR (incident report).

The Candidate may state generation of an IR is required. (Not required for critical step.) Writing comments in Step 6.4.4 is not required.

Comment:

SAT/UNSAT Terminating Cue: Three instances of improper EOP Jumper Bypass Plug placement have been identified. The Acceptance Criteria is declared UNSAT (not met)

JPM Stop Time: _ _ _ __

ILT 10-1 NRC RO ADMIN JPM1 Page 7 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC Admin JPM1 (RO)

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ __

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiner's Signature and Date:

ILT 10-1 NRC RO ADMIN JPM1 Page 8 of 10

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

1. This JPM can be performed at any power level

2. Remove EOP Bypass Plug in rear Panel 3F at position BP14

3. Remove EOP Bypass Plug in rear Panel 11 R from position BP4 and place in BP2

4. Place an additional EOP Bypass Plug in Panel inside Panel10XF in position BP3 ILT 10-1 NRC RO ADMIN JPM1 Page 9 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

1. The plant is at rated power Task Cue:

Complete Section 6.4, Week Four Verification, lAW 680.4.007, Safety Related Equipment Verification, starting at Step 6.4.3.

ILT 10-1 I\IRC RO ADMIN ..IPM1 Page 10 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 2000301402 Task

Title:

Perform Core Thermal Limits Verification Job Performance Measure No.: NRC Admin JPM 2 (RO)

KIA

Reference:

_G=2=.:....:,.1.::.;;..7_(L.:4-'--.4:...t..)_ _ _ _ _ _ __

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance - - - - - Actual Performance x Classroom --~--

X Simulator - - - - Plant Read to the Examinee:

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

Initial Conditions:

1. The plant is at rated power in 4-loop operation

2. Reactor Recirculation Pump A is isolated

3. Core Spray Main Pump NZ01A is inoperable

4. It is currently 0850 on 2126/11 Task Standard: A review the Reactor Core State Parameters printout reveals that MAPRAT and FLLLP are unacceptable and requires actions Required Materials: None General

References:

1. 202.1, Power Operations, revision 123 ILT 10-1 I\IRC RO Admin JPM2 Page 1 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Initiating Cue: Complete the Core Thermal Limits Verification lAW with Attachment 202.1-3, Core Checks/APRM Status ChecklHB Input Check Instructions, Section 1.0. After completing the Attachment, perform the following for each core thermal limit: 1) state the status of the core thermal limit (whether the core thermal limit is satisfactory I unsatisfactory); and 2) for those core thermal limits deemed unsatisfactory, if any, state the requirements which must be met or apply. Show how you have reached these conclusions.

Time Critical Task: No.

Validation Time: 10 Minutes ILT 10-1 NRC RO Admin JPM2 Page 2 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark ./

Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time: _ _ _ __

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

Comment:

SAT/UNSAT Performance Step: 2 Procedure Step 1.1 Obtain a "Screen Prinf' of PPC Reactor Core State Parameters display or 3D Monicore Monitor Case Summary (P1 Report).

Standard: Obtains a "Screen Prinf' of PPC Reactor Core State Parameters display or 3D lVIonicore Monitor Case Summary (P1 Report).

CUE: Provide the applicant the PPC Reactor Core State Parameters display (Handout).

Comment:

SAT/UNSAT ILT 10-1 NRC RO Admin JPM2 Page 3 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Procedure Step: 1.2 Compare the PPC Reactor Core State Parameters display to Attachment 1-5, Column C.

Standard: Compares the PPC Reactor Core State Parameters display to Attachment 1-5, Colurnn C, and notes the following:

MFLCPR is satisfactory lAW Column C of Attachment 202.1-5

<<1.00 with 4 or more Recirculation loops operating) o Note: The Candidate may report that actions are required lAW Column A (NOT required for the critical task)

MFLPD is satisfactory lAW Column C of Attachment 202.1-5

(<1.00 with 4 or more Recirculation loops operating)

MAPRAT is unsatisfactory lAW Column C of Attachment 202.1-5 (> 0.882 for an isolated recirculation loop and an inoperable Core Spray Pump with primary containment inerted) o Requirements of Tech Spec 3.10 applies o Notify Manager Reactor Engineering and Director Operations o Requirements of Tech Specs 3.3.F.2.a applies

FLLLP is unsatisfactory lAW Column C of Attachment 202.1-5

(>100%)

o Take action to restore (ie., insert control rods) o Notify Manager Reactor Engineering and Director Operations Note: Reviewing Tech Specs is not required.

Comment:

SAT/UNSAT ILT 10-1 NRC RO Admin JPM2 Page 4 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 4 Procedure Step: 1.3 (NOTE: Date/time of last monitor case is shown after "Last Model Calculation" on the PPC display and after "LATEST 3D MONICORE CASE" on the 3D Monicore Operator Window).

Review Screen Print or P1 Report for the current shift to ensure date/time of last monitor case is reasonable (within the past two hours unless 3D Monicore Monitor is INHIBITED per approved station procedure).

Standard: Determines the "Last Model Calculation" is within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of the given current time/date.

Comment:

SAT/UNSAT Performance Step: 5 Procedure Step: 1.4 Attach Screen Print or P1 Report to the Daily Summary Table (Attachment 202.1-4).

Standard: Attaches the Screen Print or P1 Report to the Daily Summary Table (Attachment 202.1-4).

CUE: The Screen Print is attached to the Daily Summary Table (Attachment 202.1-4)

Comment:

SAT/UNSAT Terminating Cue: Attachment 202.1-3 section 1.0 is complete. Determines MAPRAT and FLLLP are unacceptable.

JPM Stop Time: _ _ _ __

ILT 10-1 NRC RO Admin JPM2 Page 5 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC Admin JPM 2 (RO)

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiner's Signature and Date:

ILT 10-1 NRC RO Admin JPM2 Page 6 of 8

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

1. Have a copy of the Reactor Core State Parameters printout (Reactor Core State Admin 10-1 NRC2) available for Step 2.

2. Have a copy of 202.1 available for the applicant.

ILT 10-1 NRC RO Admin ...IPM2 Page 7 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

1. The plant is rated power in 4-loop operation

2. Reactor Recirculation Pump A is isolated

3. Core Spray Main Pump NZ01 A is inoperable

4. It is currently 0850 on 2/26/11 Task Cue:

Complete the Core Thermal Limits Verification lAW with Attachment 202.1-3, Core CheckslAPRM Status ChecklHB Input Check Instructions, Section 1.0.

After completing the Attachment, perform the following for each core thermal limit: 1) state the status of the core thermal limit (whether the core thermal limit is satisfactory 1 unsatisfactory); and 2) for those core thermal limits deemed unsatisfactory, if any, state the requirements which must be met or apply. Show how you have reached these conclusions.

ILT 10-1 NRC RO Admin JPM2 Page 8 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: -.:R:..:.:P_T:....;:0:..::.0-=-00=-.:5=--_ _ __

Task

Title:

Application of Radiation Exposure limits Job Performance Measure No.: NRC Admin JPM3 (RO)

KIA

Reference:

-=2::..;..-=-3.:....:.4~(.:.....:R-=O.-:;3;..:,:.2=)_ _ _ _ _ __

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance

Actual Performance x Classroom --.::....::---X Simulator - - - - Plant Read to the Examinee:

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

Initial Conditions:

1. The plant is at coasting down at the end of the cycle

2. Preparations are being made to use of the Shutdown Cooling System during the shutdown/cooldown

3. Each Shutdown Cooling Pump needs to have its oil changed and a valve lineup performed

4. Assume NO radiation exposure is received in transit to and from the job location.

Task Standard: Calculates the dose for each job and determines that all jobs can be performed without exceeding the administrative dose limit of 2000 mrem/yr.

Required Materials: Calculator General

References:

1. RP-AA-203. Exposure Control and Authorization, revision 3

2. RP-AA-300, Radiological Survey Program, revision 5 ILT 10-1 NRC RO Admin JPM3 Page 1 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Initiating Cue: Given supporting information, determine which jobs you can complete without exceeding your administrative dose limit. The jobs are to be performed in the order stated. Your current dose is 1915 mrem.

Time Critical Task: No.

Validation Time: 10 minutes ILT 10-1 NRC RO Admin JPM3 Page 2 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark ./

Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time: _ _ _ __

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

Comment:

SAT/UNSAT Note: Steps may be performed out of sequence .

./ Performance Step: 2 Procedure Step: Calculates dose for the jobs Note: The candidate may calculate the dose for all jobs and determine if there is enough dose remaining, or the candidate may calculate the dose for the first job and compare to remaining dose, and then the second job and so on. Step sequence is not important.

Standard: Dose for Job 1: (112 hour0.0013 days 0.0311 hours 1.851852e-4 weeks 4.2616e-5 months x 50 mrem/hr) = 25 mrem Dose for Job 2: (1/2 hour x 60 mrem/hr) =30 mrem Dose for Job 3: (1/2 hour x 80 mremlhr) =40 mrem Total Dose: 95 mrem Comment:

SAT/UNSAT ILT 10-1 NRC RO Admin JPM3 Page 3 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Procedure Step: Determines remaining dose Standard: Remaining dose: 2000 mrem - 1915 mrem = 85 mrem Comment:

SAT/UNSAT Performance Step: 4 Procedure Step: Determine that jobs 1 and 2 can be performed without exceeding the administrative dose limit.

Standard: Determine that jobs 1 and 2 can be performed without exceeding the administrative dose limit.

85 mrem remaining < 95 mrem left for the 3rd job (or 1915 mrem + 95 mrem =2010> 2000 mrem administrative limit)

Comment:

SAT/UNSAT Terminating Cue: Calculates the dose for each job and determines that only jobs 1 & 2 can be performed without exceeding the administrative dose limit of 2000 mrem/yr.

JPM Stop Time: _ _ _ __

ILT 10-1 NRC RO Admin JPM3 Page 4 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC Admin JPM 3 (RO)

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ __

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiner's Signature and Date:

ILT 10-1 NRC RO Admin JPM3 Page 5 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Simulator/JPM Setup

1. Prepared Radiation Contamination Diagram Sheet: SOC Map.ppt ILT 10-1 NRC RO Admin JPM3 Page 6 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

1. The plant is at coasting down at the end of the cycle

2. Preparations are being made to use of the Shutdown Cooling System during the shutdown/cooldown

3. Each Shutdown Cooling Pump needs to have its oil changed and a valve lineup performed

4. Assume NO radiation exposure is received in transit to and from the job location.

Task Cue:

Given supporting information, determine which jobs you can complete without exceeding your administrative dose limit. The jobs are to be performed in the order stated. Your current dose is 1915 mrem.

ILT 10-1 NRC RO Admin JPM3 Page 7 of 8

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

1. JOB 1

a. Drain SDC Pump A oil

b. Refill SDC Pump A with oil

i. Total time (for oil drain and refill): 15 minutes at the pump/motor

c. Perform valve lineup at SDC Pump A

i. Total time: 15 minutes at the pump/motor

2. JOB2

a. Drain SDC Pump B oil

b. Refill SDC Pump B with oil

i. Total time (for oil drain and refill): 15 minutes at the pump/motor

c. Perform valve lineup at SDC Pump B

i. Total time: 15 minutes at the pump/motor

3. JOB3

a. Drain SDC Pump C oil

b. Refill SDC Pump C with oil

i. Total time (for oil drain and refill): 15 minutes at the pump/motor

c. Perform valve lineup at SDC Pump C

i. Total time: 15 minutes at the pump/motor ILT 10-1 NRC RO Admin ..IPM3 Page 8 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 2000501406 Task

Title:

Determine Primary Containment Water Level Job Performance Measure No.: NRC Admin JPM 4 (RO)

KIA

Reference:

G2.4.21 (4.0)

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

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance -------

Actual Performance x Classroom --~--

X Simulator ----

Plant Read to the Examinee:

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

Initial Conditions:

1. The plant was at rated power when a LOCA occurred.

2. The TORUS WATER LEVEL recorders on Panel16R indicate upscale.

3. The RPV has been Emergency Depressurized.

4. Containment Spray System 1 is in operation in the Drywell Spray Mode.

Task Standard: Determines that Primary Containment water level is approximately 550 in.

Required Materials: None General

References:

1. EMG-SP38, Determining Primary Containment Water Level, revision 0 Initiating Cue: Determine Primary Containment water level lAW EMG-SP38, Determining Primary Containment Water Level.

Time Critical Task: No.

Validation Time: 5 Minutes ILT 10-1 NRC RO Admin JPM4 Page 1 of9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark -/

Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time: _ _ _ __

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

Comment:

SAT/UNSAT Performance Step: 2 Procedure Step 3.1.1 Record Torus pressure from one of the following:

P (Torus) =_____ psig

1. Digital indicator on Panel 4F

2. Computer Point ID PTIP12

3. PT-IP12 on Pane11F/2F Standard: Records Torus pressure as about 25 psig Comment:

SAT/UNSAT ILT 10-1 NRC RO Admin JPM4 Page 2 of9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Procedure Step: 3.1.2 Record Orywell pressure from PI-IP08 Panel 1F/2F P (OW) = psig Standard: Records Orywell pressure as about 17 psig Comment:

SAT/UNSAT Performance Step: 4 Procedure Step: 3.1.3 Calculate AP AP =P (Torus) - P (OW) = psid Standard: Calculates AP as approximately 8 psig Comment:

SAT/UNSAT ILT 10-1 NRC RO Admin JPM4 Page 30f9

AppendixC Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Note: Step 3.1.4 does not apply.

Performance Step: 5 Procedure Step: 3.1.5 If LlP is less than 16 psid, then determine Primary Containment Water Level using Figure SP-38-1.

Standard: Using Figure SP-38-1, calculates Primary Containment water level is approximately 550 in.

Comment:

SAT/UNSAT Terminating Cue: Determines that Primary Containment water level is approximately 550 in.

JPM Stop Time: _ _ _ __

ILT 10-1 NRC RO Admin JPM4 Page 4 of9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Figure EMG-SP38-1 Containment Water Level Determination Using OW Pressure Indication From Panel 1FI2F 800 j I I I

i II I i

775

./

i I I 750 725 v

/

700

/

675 i /

I V 650 /

/

i /

-c 625

~ 600 I

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fI)~

~ ~ 575

/ ---- -

~o::

~ 550 ......... . i**1-** - I- * ****

/

~

= !

I 525 500 I

Ii 475 . / I 450 V

I (4.7 psid. 461~ches)

I 425 - / I

i /

/ *

~

400 I I

/

V I 375

350 1I (1.3 pSid, 365 inches)

i I

o 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 P(Torus)-P(OW) (psid)

ILT 10-1 NRC RO Admin JPM4 Page 50f9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC Admin JPM 4 (RO)

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ __

Time to Complete:

Question:

Response

Result: Satisfactory/U nsatisfactory Examiner's Signature and Date:

ILT 10-1 NRC RO Admin JPM4 Page 6of9

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

1. Have a copy of EMG-SP38, Determining Primary Containment Water Level available.

ILT 10-1 NRC RO Admin JPM4 Page 7of9

AppendixC Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

1. The plant was at rated power when a LOCA occurred.

2. The TORUS WATER LEVEL recorders on Panel16R indicate upscale.

3. The RPV has been Emergency Depressurized.

4. Containment Spray System 1 is in operation in the Drywell Spray Mode.

Task Cue:

Determine Primary Containment water level lAW EMG-SP38, Determining Primary Containment Water Level.

ILT 10-1 NRC RO Admin JPM4 Page 80f9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT 8-0 t::

=

ILT 10-1 NRC RO Admin JPM4 Page 9 of9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: C0000030 Task

Title:

Review a Technical Specification Log Sheet Job Performance Measure No.: NRC JPM ADMIN SR01 (SRO)

KIA

Reference:

Generic 2.1.3 (SRO 3.9)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

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

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

Initial Conditions:

1. The plant is at rated power with all Recirculation Pumps on.

2. You are the oncoming Unit Supervisor after being off for the last 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

3. Your last shift was completed at 06:30:00AM on Tuesday, March 01,2011.

4. The current date/time is March 01, 2011 at 6:30:00PM.

5. There are no LCOs, ABNs, or EOPs have been entered on the previous shift or are currently in effect.

Task Standard: The Candidate has reviewed the Oyster Creek Technical Specification Log Sheet and determines that Tech Specs 3.3 and apply and the Primary Containment Control EOP requires entry due to High Drywell Temperature.

Required Materials: None.

General

References:

1. Oyster Creek Technical Specifications

2. Primary Containment Control EOP ILT 10-1 NRC SRO Admin JPM1 Page 1 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Initiating Cue: As the oncoming Unit Supervisor, review the Technical Specification Log Sheet, procedure 681.4.001 Attachment 1, sheets E1-1 and E1-2. Note any abnormalities, if any, and if abnormalities exist, state the required actions lAW Tech Specs and/or EOPs.

Time Critical Task: No.

Validation Time: 20 minutes ILT 10-1 NRC SRO Admin JPM1 Page 2 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark -/

Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time: _ _ _ __

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back. Provide the completed Turnover Sheet.

Comment:

SAT/UNSAT Note: The following steps may be performed in any order.

-/ Performance Step: 2 Procedure Step: Reviews the Technical Specification Log Sheet.

Standard: Reviews the Technical Specification Log Sheet and notes the following:

EDG Fuel Oil Tank Level is 13, 950 gal

Calculated UILR is approximately 5.2 gpm

Bulk DW temperature is 151.2 OF Comment:

SAT/UNSAT ILT 10-1 NRC SRO Admin ..IPM1 Page 3 of 7

Appendix C Job Performance Measure Form ES~C~1 WORKSHEET Performance Information Performance Step: 3 Procedure Step: Applies Tech Specs and EOPs.

Standard: I. Due to Reactor Coolant System Leakage (Unidentified Leak Rate) > 5 gpm, applies Tech Spec 3.3.D:

1. Reactor coolant system leakage shall be limited to:

a. 5 gpm unidentified leakage

b. 25 gpm total (identified and unidentified)

c. 2 gpm increase in unidentified leakage rate within any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period while operating at steady state power

2. With the reactor coolant system leakage greater than the limits in 3.3.D.1.a or b above, reduce the leakage rate to within the acceptable limits within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or place the reactor in the shutdown condition within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and be in the cold shutdown condition within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

II. Due to EDG Fuel Oil Tank level < 14,000 gal, both EDGs must be declared INOPERABLE lAW TS 3.7.C.4.A:

1. lAW TS 3.7.C.3, with both diesel generators INOPERABLE, the reactor shall be placed in the COLD SHUTDOWN condition (30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ).

III. Due to Drywell Temperature> 150F, commence a shutdown (lAW the TS Log Sheet) and enter the Primary Containment Control EOP (based on exceeding an entry condition).

Comment:

SAT/UNSAT JPM Stop Time: _ _ _ __

ILT 10-1 NRC SRO Admin JPM1 Page 4 of 7

Validation of Completion JPM Number: NRC Admin JPM1 (SRO)

Examinee's l'Jame:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiner's Signature and Date:

ILT 10-1 NRC SRO Admin JPM1 Page 5 of 7

JPM Setup

1. Have a copy of Tech Specs available (if requested)

2. Have a copy of the Primary Containment Control EOP available (if requested)

3. Have a copy of 681.4.004, Technical Specification Log Sheet, Attachment 1, sheets E1-1, marked up.

ILT 10-1 NRC SRO Admin JPM1 Page 6 of 7

STUDENT HAI\IDOUT Initial Conditions:

1. The plant is at rated power with all Recirculation Pumps on.

2. You are the oncoming Unit Supervisor after being off for the last 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

3. Your last shift was completed at 06:30:00AM on Tuesday, March 01,2011.

4. The current date/time is March 01, 2011 at 6:30:00PM.

5. There are no LCOs, ABNs, or EOPs have been entered on the previous shift or are currently in effect.

Initiating Cue:

As the oncoming Unit Supervisor, review the Technical Specification Log Sheet, procedure 681.4.001 Attachment 1, sheets E1-1 and E1-2. Note any abnormalities, if any, and if abnormalities exist, state the required actions lAW Tech Specs and/or EOPs.

ILT 10-1 NRC SRO Admin ..IPM1 Page 7 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 3410102411 Task

Title:

Review a Completed Pre-Critical Checkoff lAW Procedure 201 Job Performance Measure No.: NRC Admin JPM2 (SRO)

KIA

Reference:

_G=2=.--'..1=.2=3->.(4=,--'..4.1-)_ _ _ _ _ __

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

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

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

Initial Conditions:

1. The plant has just completed all major activities during a refuel outage

2. Preparations are being made for a plant startup 3, The REACTOR MODE SELECTOR switch is in REFUEL

4. Attachment 201-2, Pre-Critical Checkoff has been completed and is awaiting review Task Standard: The plant is deemed NOT ready for an uninterrupted startup to rated power. The correct reasons and required actions are stated.

Required Materials: None General

References:

1. Procedure 201, Plant Startup, Revision 71

2. Tech Specs ILT 10-1 NRC SRO Admin JPM2 Page 1 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Initiating Cue: Perform Step 78 of the Pre-Critical Checkoff for Attachment 201-2 ONLY. From this review, determine if the plant is ready for an uninterrupted startup to rated power. If the plant is NOT ready, state why and what actions are required to be ready.

Time Critical Task: No.

Validation Time: 30 Minutes ILT 10-1 NRC SRO Admin JPM2 Page 2 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark -I' Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time: _ _ _ __

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

Comment:

SAT/UNSAT Note: The following steps can be performed in any order.

Performance Step: 2 Determines the plant is not ready for an uninterrupted startup to rated power for the following reasons:

Step 12.4.1 shows only 1 operable SRM. SRM 22 reads 30000, SRM 23 reads 2, and SRM 24 is bypassed.

TS 3.1.1.K requires a minimum of 2 operable SRMs to support the rodblock function.

Any inoperable SRM must be made operable to withdraw control rods.

Standard: Recognizes the Tech Spec applicability due to the inoperability of 3 SRMs. 2 SRMs must be operable to withdraw control rods.

Comment:

SAT/UNSAT ILT 10-1 NRC SRO Admin JPM2 Page 3 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Determines the plant is not ready for an uninterrupted startup to rated power for the following reasons:

Step 45.1 shows that MCC 1A24 is not operable.

Tech Spec 3.7 states that the reactor shall not be made critical unless all of the following requirements are satisfied: The listed buses or panel listed in the TS are energized, and this includes MCC 1A24.

Standard: Recognizes the Tech Spec applicability due to the inoperability of MCC 1A24. MCC 1A24 must be made operable prior to going critical.

Comment:

SAT/UNSAT ILT 10-1 NRC SRO Admin JPM2 Page 4 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 4 Determines the plant is not ready for an uninterrupted startup to rated power for the following reasons:

Step 73.1 shows that conductivity and chlorides are above the allowable limits.

TS 3.3.E.1 provides the following:

3.3.E.1: The reactor coolant quality during power operation with steaming rates to the turbine-condenser of less than 100,000 pounds per hour shall be limited to: conductivity 2 us!cm[s=mhos at 25°C (77°F); chloride ion 0.1 ppm.

TS 3.3.E.2 provides the following:

3.3.E.2: When the conductivity and chloride concentration limits given in 3.3.E.1 are exceeded, an orderly shutdown shall be initiated immediately, and the reactor coolant temperature shall be reduced to less than 212°F within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Standard: Recognizes the Tech Spec applicability due high conductivity and chloride values which must be reduced below the limits in TS 3.3.E.1.

Comment:

SAT/UNSAT Terminating Cue: The plant is deemed NOT ready for an uninterrupted startup to rated power. The correct reasons and required actions are stated.

JPM Stop Time: _ _ _ __

ILT 10-1 NRC SRO Admin JPM2 Page 5 of 8

Appendix C Job Performance lVIeasure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC SRO Admin JPM2 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ __

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiner's Signature and Date:

ILT 10-1 NRC SRO Admin JPM2 Page 6 of 8

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

1. Have Tech Specs available

2. Have a clean copy of procedure 201 available

3. Have a prepared copy of Attachment 201-2 ready ILT 10-1 NRC SRO Admin JPM2 Page 7 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

1. The plant has just completed all major activities during a refuel outage

2. Preparations are being made for a plant startup

3. The REACTOR MODE SELECTOR switch is in REFUEL

4. Attachment 201-2, Pre-Critical Checkoff has been completed and is awaiting review Task Cue:

Perform Step 78 of the Pre-Critical Checkoff for Attachment 201-2 ONLY.

From this review, determine if the plant is ready for an uninterrupted startup to rated power. If the plant is NOT ready, state why and what actions are required to be ready.

ILT 10-1 NRC SRO Admin JPM2 Page 8 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 3420302026

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

Task

Title:

Review Completed Surveillance Test Job Performance Measure No.: NRC SRO Admin JPM 3 KIA

Reference:

G2.2.12 (SRO 4.1)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance - - - - Actual Performance x Classroom --~--

X Simulator - - - - Plant Read to the Examinee:

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

Initial Conditions:

1. The plant is at rated power

2. Surveillance test 609.3.022, "An Isolation Condenser Isolation Test and Calibration - A 1 Sensors First, has just been completed for Isolation Condenser A Task Standard: The surveillance test has been reviewed. Isolation Condenser A has been declared inoperable and that TS Table 3.1.1 and TS 3.8 have been applied Required Materials: None.

General

References:

1. Surveillance procedure 609.3.022, revision 0

2. Tech Spec Table 3.1.1

3. Tech Spec 3.8 ILT 10-1 NRC SRO Admin JPM3 Page 1 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Initiating Cue: Review the acceptance criteria for the TEST DATA SHEET Attachment 609.S.022-2, sheets 1 & 2. Note any discrepancies or required actions, if any.

Time Critical Task: No.

Validation Time: 10 minutes ILT 10-1 NRC SRO Admin JPMS Page 2 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark .,

Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time: _ _ _ __

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

Comment:

SATIUNSAT Performance Step: 2 Procedure Step: Review completed surveillance test Standard: Reviews completed surveillance test Comment:

SAT/UNSAT ILT 10-1 NRC SRO Admin JPM3 Page 3 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Procedure Step: Determine that acceptance criteria 7.1 has not been met

The as-left trip pOints for IB011A1 and IB11A2 are>

allowed (23.5 - 24.5 psig)

Standard: Determines that acceptance criteria 7.1 has not been met

The as-left trip points for IB011A1 and IB11A2 are>

allowed (23.5 - 24.5 psig)

Comment:

SAT/UNSAT Performance Step: 4 Procedure Step: Comply with TS Table 3.1.1.H

Direct the Panel Operator to isolate Isolation Condenser A Standard: Complies with TS Table 3.1.1.H

Directs the Panel Operator to isolate Isolation Condenser A Comment:

SAT/UNSAT ILT 10-1 NRC SRO Admin JPM3 Page 4 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 5 Procedure Step: Declare Isolation Condenser A inoperable and apply TS 3.8.C Standard: Declares Isolation Condenser A inoperable and applies TS 3.8.C

If one isolation condenser becomes inoperable during the run mode the reactor may remain in operation for a period not to exceed 7 days provided the motor operated isolation and condensate makeup valves in the operable isolation condenser are verified daily to be operable.

May also state: 1) document the as-found failure in the CAP System; 2) Initiate an IR; Notify the Shift Manager (not required for credit)

Comment:

SAT/UNSAT Note: The candidate may also require the initiation of an IR and that upper management notifications be made.

Terminating Cue: The surveillance test has been reviewed. Isolation Condenser A has been declared inoperable and isolated, and that TS Table 3.1.1 and TS 3.8 have been applied JPM Stop Time: _ _ _ __

ILT 10-1 NRC SRO Admin JPM3 Page 5 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC Admin ..IPM 3 (SRO)

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiner's Signature and Date:

ILT 10-1 NRC SRO Admin JPM3 Page 6 of 8

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

1. Have a marked-up copy of surveillance test 609.3.002, Isolation Condenser Isolation Test and Calibration - A 1 Sensors First. Provide pages 32-33 (Acceptance Criteria), and Attachment 609.3.022-2 (filled out).

2. Have a copy of the entire procedure available

3. Have Tech Specs available

4. Have LS-AA-125 copy available

5. Have several full blank copies of surveillance test 609.3.002, Isolation Condenser Isolation Test and Calibration - A 1 Sensors First, in case the applicant requests to view the entire surveillance.

ILT 10-1 NRC SRO Admin ..IPM3 Page 7 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

1. The plant is at rated power

2. Surveillance test 609.3.002, Isolation Condenser Isolation Test and Calibration - A 1/81 Sensors First, has just been completed for Isolation Condenser A ONLY Task Cue:

Review the acceptance criteria for the TEST DATA SHEET Attachment 609.3.022-2, sheets 1 & 2. Note any discrepancies or required actions, if any.

ILT 10-1 NRC SRO Admin ..IPM3 Page 8 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 3420302008 Task

Title:

Authorize TI P Room Entry Job Performance Measure No.: NRC Admin JPM 4 (SRO)

KIA

Reference:

--=2=.-=-3.:..-'.1-=-3....>..(3=-:.-=-8)<--_ _ _ _ _ __

Examinee: Examiner:

Facility Evaluator: - - - - - - - - Date:

Method of Testing:

Simulated Performance -----

Actual Performance x Classroom X Simulator - - - - - Plant Read to the Examinee:

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

Initial Conditions:

1. The plant is at rated power

2. TIP machine 1 was used earlier today for LPRM calibrations

3. An event occurred when retracting the TIP to its shield position. The following indications were noted for TIP Machine 1:

The IN SHIELD light is extinguished

The IN CORE light is illuminated

The BALL VALVE OPEN light is illuminated and the BALL VALVE CLOSED light is extinguished

4. A clearance order has been applied to TIP Machine 1

5. It has been determined that an inspection in the TIP Room is required and inside the TIP Drive Mechanism 1 (RB 38')

6. Maintenance Planners expect that the TIP drive chain will not have to be disconnected

7. No entry into the TIP Room has been made over the last 2 months ILT 10-1 SRO Admin JPM4 Page 1 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Task Standard: Attachment 1 has been reviewed and routed to RPSS for signature, and Attachment 2 has been initiated Required Materials: A partially completed Attachment 1 to RP-AB-460.

General

References:

1. RP-AB-460, TIP Area Access Controls, revision 1

2. 405.1, Placing the TIP System is Stand-By Readiness, revision 16

3. 405.2, Operation of the TIP System, revision 27 Initiating Cue:

1. Review Attachment 1 of RP-AB-460, Initial TIP Room Entry Data Sheet. Sign for Operations Shift Manger if acceptable. If not acceptable, note any discrepancies and state the required actions.

2. Following your review of Attachment 1, complete RP-AB-460, Attachment 2, TIP Drive Mechanism Access Data Sheet, Sections I, II and III.

Time Critical Task: No.

Validation Time: 11 minutes ILT 10-1 SRO Admin JPM4 Page 2 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark ~

Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time: _ _ _ __

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

Comment:

SAT/UNSAT Note: The candidate may initiate Attachment 2 prior to reviewing Attachment 1.

This is allowed. Steps may be performed in any order.

Performance Step: 2 Procedure Step: Review Attachment 1, Initial TIP Room Entry Data Sheet Standard: Reviews Attachment 1, Initial TIP Room Entry Data Sheet Comment:

SAT/UNSAT ILT 10-1 SRO Admin JPM4 Page 3 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Note: Steps 3 and 4 may occur in any order Performance Step: 3 Procedure Step: Step 1.1 , Attachment 1 Report that "decay time since TIPs last run is > 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months " should state NO and that Attachment 1 is incorrectly annotates YES.

Standard: Report that "decay time since TIPs last run is> 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months " should state NO and that Attachment 1 is incorrectly annotates YES.

(The candidate should correct this on Attachment 1)

Comment:

SAT/UNSAT Performance Step: 4 Procedure Step: Step 1.2, Attachment 1 Report that TIP Detectors withdrawn into Shield" should state NO and that Attachment 1 is incorrectly annotates YES.

Standard: Report that TIP Detectors withdrawn into Shield" should state 1\10 and that Attachment 1 is incorrectly annotates YES.

(The candidate should correct this on Attachment 1)

Comment:

SAT/UNSAT ILT 10-1 SRO Admin ..IPM4 Page 4 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 5 Procedure Step: Report that since there is a NO in Section I, then the RPSS should first complete Section III.

Standard: Reports that since there is a NO in Section I, then the RPSS should first complete Section III.

Comment:

SAT/UNSAT Note: This completes the Attachment 1 activity.

Performance Step: 6 Procedure Step: Review Attachment 2 Standard: Reviews Attachment 2 Comment:

SAT/UNSAT Performance Step: 7 Procedure Step: I, Attachment 2 "Determine TI P Decay Time" as Still in core Standard: "Determines TIP Decay Time" as Still in core Comment:

SAT/UNSAT ILT 10-1 SRO Admin JPM4 Page 5 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 8 Procedure Step: II, Attachment 2 "Determine TIP Detector Location" as In Core Standard: "Determines TIP Detector Location" as In Core Comment:

SAT/UNSAT Performance Step: 9 Procedure Step: III, Attachment 2 Determine "TIP Drive Mechanism Clearance Order Applied" as YES Standard: Determines "TIP Drive Mechanism Clearance Order Applied" as YES Comment:

SAT/UNSAT Terminating Cue: Attachment 1 has been reviewed and routed to RPSS for signature (to complete Attachment III), and Sections /, II and III of Attachment 2 have been completed.

JPM Stop Time: _ _ _ __

ILT 10-1 SRO Admin JPM4 Page 6 of9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC Admin JPM 4 (SRO)

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ __

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiner's Signature and Date:

ILT 10-1 SRO Admin JPM4 Page 7 of 9

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

1. Marked-up copy of RP-AB-460, Initial TIP Room Entry Data Sheet, Attachment 1 and a blank copy of Attachment 2.

ILT 10-1 SRO Admin JPM4 Page 8 of 9

Appendix C Job Performance Measure Form ES~C~1 WORKSHEET STUDENT HANDOUT Initial Conditions:

1. The plant is at rated power

2. TIP machine 1 was used earlier today for LPRM calibrations

3. An event occurred when retracting the TIP to its shield position. The following indications were noted for TIP Machine 1:

The IN SHIELD light is extinguished

The IN CORE light is illuminated

The BALL VALVE OPEN light is illuminated and the BALL VALVE CLOSED light is extinguished

4. A clearance order has been applied to TIP Machine 1

5. It has been determined that an inspection in the TI P Room is required and inside the TIP Drive Mechanism 1 (RB 38')

6. Maintenance Planners expect that the TIP drive chain will not have to be disconnected

7. No entry into the TIP Room has been made over the last 2 months Task Cue:

1. Review Attachment 1 of RP-AB-460, Initial TIP Room Entry Data Sheet. Sign for Operations Shift Manger if acceptable. If not acceptable, note any discrepancies and state the required actions.

2. Following your review of Attachment 1, complete RP-AB-460, Attachment 2, TIP Drive Mechanism Access Data Sheet, Sections I, II and III.

ILT 10-1 SRO Admin ,JPM4 Page 9 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 2000501406 Determine Primary Containment Water Level and Determine Task

Title:

Corrective Actions Job Performance Measure No.: NRC Admin JPM 5 (SRO)

KIA

Reference:

_G_2_._4._2_1->-(4_._6}<---_ _ _ _ _ __

Examinee: Examiner:

Facility Evaluator: -------------- Date:

Method of Testing:

Simulated Performance --------

Actual Performance x Classroom

- - -X- - - Simulator

Plant Read to the Examinee:

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

Initial Conditions:

1. The plant was at rated power when a LOCA occurred.

2. The TORUS WATER LEVEL recorders on Panel16R indicate upscale.

3. The RPV has been Emergency Depressurized.

4. Containment Spray System 1 is in operation in the Drywell Spray Mode.

Task Standard: Determines that Primary Containment water level is approximately 385 in.

Required Materials: None General

References:

1. EMG-SP38, Determining Primary Containment Water Level, revision 0 Initiating Cue: Determine Primary Containment water level lAW EMG-SP38, Determining Primary Containment Water Level and state any actions required, if any, by the EOPs.

ILT 10-1 NRC SRO Admin JPM5 Page 1 of 10

AppendixC Job Performance Measure Form ES-C-1 WORKSHEET Time Critical Task: No.

Validation Time: 5 Minutes ILT 10-1 NRC SRO Admin JPM5 Page 2 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark .j' Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time: _ _ _ __

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

Comment:

SAT/UNSAT Performance Step: 2 Procedure Step 3.1.1 Record Torus pressure from one of the following:

P (Torus) =_____ psig

1. Digital indicator on Panel 4F

2. Computer Point ID PTIP12

3. PT-IP12 on Panel1F/2F Standard: Records Torus pressure as about 27 psig Comment:

SAT/UNSAT ILT 10-1 NRC SRO Admin JPM5 Page 3 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Procedure Step: 3.1.2 Record Drywell pressure from PI-IP08 Panel 1F/2F P (OW) = psig Standard: Records Drywell pressure as about 25 psig Comment:

SAT/UNSAT Performance Step: 4 Procedure Step: 3.1.3 Calculate dP dP = P (Torus) - P (OW) = psid Standard: Calculates 8P as approximately 2 psig Comment:

SAT/UNSAT ILT 10-1 NRC SRO Admin JPM5 Page 4 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Note: Step 3.1.4 does not apply.

./ Performance Step: 5 Procedure Step: 3.1.5 If dP is less than 16 psid, then determine Primary Containment Water Level using Figure SP-38-1.

Standard: Using Figure SP-38-1, calculates Primary Containment water level is approximately 385 in.

Comment:

SAT/UNSAT Performance Step: 6 Procedure Step: N/A From the Primary Containment Control EOP, Terminate Drywell Sprays if Primary Containment Water Level cannot be maintained below 348 in. (Torus Water Level Leg)

Standard: States that Drywell Sprays must be terminated.

Comment:

SAT/UNSAT Terminating Cue: Determines that Primary Containment water level is approximately 385 in. States that Drywell Sprays must be terminated.

JPM Stop Time: _ _ _ __

ILT 10-1 NRC SRO Admin JPM5 Page 5 of 10

AppendixC Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Figure EMG-SP38-1 Containment Water Level Determination Using DW Pressure Indication From Panel 1F/2F 800 i I i I i I i I I I I i i II :

775 I I I I 750 ~. I I I

I I /1I i I 725 .. -

I I

I

I I

V

/ I

I I

700 I I

/ I i

I I V i I

675 ~-

I I

I I / I I I I i I I /

/

~

650 I I I VI I I i I / i I

-~

c 625 600 I

i I

i i

/1 I I

I

(/)w IX: ~ 575 I

I

/ I_

elX: I i I I VI I I

~ 550 I I i I I I I I

~

I ill I I I

I I i I I :

525 Ii I I I I I 500

! I I i!

I i

1

! I I I I I ! I I I I

i 475 450 i

I I

Ii _I 1 (4.7 psid, 461 1 I I

I I i

I V I I I I

425 I L I iI . J I i I

I 400

/

I I I

I J I I I i 375 I I J ! I J 1(1 I

~ psid, 365 inches) i i ! i I I 350 o 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 P(Torus}-P(OW) (psid)

ILT 10-1 NRC SRO Admin JPM5 Page 6 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC Admin JPM 5 (SRO)

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ __

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiner's Signature and Date:

ILT 10-1 NRC SRO Admin JPM5 Page 7 of 10

AppendixC Job Performance Measure Form ES-C-1 WORKSHEET JPM Setup

1. Have a copy of EMG-SP38, Determining Primary Containment Water Level available.

2. Have a copy of the Primary Containment Control EOP available.

ILT 10-1 NRC SRO Admin JPM5 Page 8 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

1. The plant was at rated power when a LOCA occurred.

2. The TORUS WATER LEVEL recorders on Panel16R indicate upscale.

3. The RPV has been Emergency Depressurized.

4. Containment Spray System 1 is in operation in the Drywell Spray Mode.

Task Cue:

Determine Primary Containment water level lAW EMG-SP38, Determining Primary Containment Water Level and state any actions required, if any, by the EOPs.

ILT 10-1 NRC SRO Admin JPM5 Page 9 of 10

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

=- 60 g.

E- 50

~

-=-40 E

P 1=

=- 30 G

=

E- 20

~

e=- 10 E

1=

e- 0 t=

ILT 10-1 NRC SRO Admin JPM5 Page 10 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 2090201003 Perform Core Spray Surveillance with faulted Core Spray Task

Title:

Pump (Alternate Path)

Job Performance Measure No.: ILT 10-1 NRC Sim JPM1 (RO/SRO)

KIA

Reference:

2090001 A4.01 (RO/SRO 3.8/3.6)

Examinee: 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 plant is at rated power.

2. Core Spray Main Pump NZ01 C is tagged out of service due to an oil leak.

3. Core Spray Pump Operability Test, 610.4.002, is in progress and is complete up to and including Step 6.4 for Core Spray System A.

4. The testing is a normal surveillance for pumps NZ01 A and NZ03A only.

5. An Equipment Operator has been briefed on the evolution, and is standing-by with the procedure and a radio on RB 51'.

6. Plant announcements for the pump starts have already been made.

Task Standard: The Core Spray Booster Pump NZ03A is manually tripped after the Core Spray Pump NZ01 A trips.

Required Materials: None.

General

References:

1. Procedure 610.4.002, Core Spray Pump Operability Test, revision 49.

ILT 10-1 NRC SIM JPM1 Page 1 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Initiating Cue: Continue with surveillance test 610.4.002, Core Spray Pump Operability Test, beginning at Step 6.5.

Time Critical Task: No.

Validation Time: 8 minutes ILT 10-1 NRC SIM JPM1 Page 2 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark ./

Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time: _ _ _ __

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

Comment:

SAT/UNSAT Performance Step: 2 Procedure Step: Reviews Precautions and Limitations.

Standard: Reviews Precautions and Limitations.

Note: The candidate may state that annunciator B3d, KEEP FILL TROUBLE, will be an expected alarm. Acknowledge the report.

Comment:

SAT/UNSAT ILT 10-1 NRC SIM JPM1 Page 3 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Note: If annunciator C5e, TORUS LEVEL HIILO alarms, state that other operators will respond to this.

Performance Step: 3 Procedure Step: 6.5 Start Core Spray MAIN PUMP (control switch on 1F/2F) for Core Spray Main Pump NZ01 A.

Standard: Places Core Spray MAIN PUMP NZ01A control switch to START (red light ON, green light OFF, MAINS PUMP AIVIPS NZ01A rises, PUMP DISCH PRESS MAINS rises).

Comment:

SAT/UNSAT Performance Step: 4 Procedure Step: 6.5.1 Record Core Spray PUMP DISCH PRESS*- MAII\JS PIT-RV03A (1 F/2F) > 150 psig.

Standard: Records Core Spray PUMP DISCH PRESS - MAINS PIT-RV03A (1F/2F) > 150 psig.

Comment:

SAT/UNSAT ILT 10-1 NRC SIM JPM1 Page 4 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 5 Procedure Step: 6.6 If Core Spray PUMP DISCH PRESS - MAINS PIT-RV03A is >

100 psig, then start a Core Spray Booster Pump from the control switch on 1F/2F.

Standard: Verifies PUMP DISCH PRESS -MAINS PIT-RV03A is > 100 psig, then starts Core Spray Booster Pump NZ03A by placing BOOSTER PUMP NZ03A control switch to START (red light ON, green light OFF, PUMP DISCH PRESS - BOOSTERS rises).

Comment:

SAT/UNSAT Performance Step: 6 Procedure Step: 6.6.1 Verify alarm SYSTEM 1 FLOW PERMISSIVE (B2e) annunciates (if reactor press < 300 psig).

Standard: Recognizes reactor pressure is > 300 psig and that SYSTEM 1 FLOW PERMISSIVE (B2e) will not annunciate.

Comment:

SAT/UNSAT ILT 10-1 NRC SIM JPM1 Page 5 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Note: In the following step, when core spray flow reaches 4000 gpm, the Core Spray Main Pump NZ01 A will trip. This initiates the Alternate Path.

Performance Step: 7 Procedure Step: 6.7 Open V-20-27 and establish Core Spray flow by taking the keylock switch to OPEN (51' NW).

Standard: Directs the EO over the radio to open V-20*-27 and establish Core Spray flow by taking the keylock switch to OPEN. (Red light ON, green light OFF)

On the pump trip, verifies MAIN PUMP NZ01 A red light OFF, green light ON, MAINS PUMP AMPS NZ01 A at O.

Booth Cue: Acknowledge the report. Insert Trigger 2 (LOA-CSS016 from 0%

to 100%)

Note: When Core Spray System I flow exceeds 4000 GPM, Core Spray Main Pump NZ01 A will trip. Annunciator B4e will alarm.

The candidate may refer to the alarm response B4e and notify the SRO. If so notified, acknowledge the report.

Comment:

SAT/UNSAT ILT 10-1 NRC SIM ..IPM1 Page 6 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 8 Procedure Step: P&L 4.9 application Trips Core Spray Booster Pump NZ03A.

Standard: Trips Core Spray Booster Pump NZ03A by placing CORE SPRAY 1 BOOSTER PUMP NZ03A control switch to STOP (red light OFF; green light ON; PUMP DISCH PRESS BOOSTERS falls to 0).

Comment:

SAT/UNSAT Terminating Cue: The candidate has manually tripped Core Spray Booster Pump NZ03A.

JPM Stop Time: _ _ _ __

ILT 10-1 NRC SIM JPM1 Page 7 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: ILT 10-1 NRC SIM ...IPM1 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ __

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiner's Signature and Date:

ILT 10-1 NRC SIM ...IPM1 Page 8 of 10

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

1. Reset to full power IC (IC-115) or similar

2. Insert Remote LOA-CSS017 to FALSE

a. This will rack-in the breaker for Core Spray System I Test Valve, V-20-27

3. Insert LOA-CSS055 to RACKED OUT

a. This will rack-out the breaker for Core Spray Main Pump NZ01C

4. Insert the following:

a. Conditional Trigger pp_fitrv26a_1v.gt.4000 on Trigger 1

b. Malfunction MAL-CSS002a on Trigger 1 with a 20 second time delay

i. These two items will trip Core Spray Main NZ01 A when Core Spray System I flow exceeds 4000 GPM after 20 seconds

5. Have a surveillance test completed up through step 6.4 (610.4.002). N/A those steps for system C.

6. Place a tag on Core spray Main Pump NZ01 C.

7. At ..IPM completion, verify no marks in RAP-B4e.

8. Place on Trigger 2: LOA-CSS016 from 0% to 100% (This will open the core spray test valve V-20-27)

ILT 10-1 NRC SIM JPM1 Page 9 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

1. The plant is at rated power.

2. Core Spray Main Pump NZ01 C is tagged out of service due to an oil leak.

3. Core Spray Pump Operability Test, 610.4.002, is in progress and is complete up to and including Step 6.4 for Core Spray System A.

4. The testing is a normal surveillance for pumps NZ01A and NZ03A only.

5. An Equipment Operator has been briefed on the evolution, and is standing-by with the procedure and a radio on RS 51'.

6. Plant announcements for the pump starts have already been made.

Task Cue:

Continue with surveillance test 610.4.002, Core Spray Pump Operability Test, beginning at Step 6.5.

ILT 10-1 NRC SIM JPM1 Page 10 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 2180101402 Task

Title:

Shutdown of Auto Depressurization System Job Performance Measure No.: ILT 10-1 NRC Sim JPM 2 (RO/SRO)

KIA

Reference:

218000 A4.03 (4.214.2)

Examinee: 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 plant experienced an ATWS condition and the RPV Control - With ATWS EOP has been entered

2. The Primary Containment Control EOP has also been entered on high Drywell pressure

3. All control rods have since been inserted and RPV Control - No ATWS EOP has been entered

4. Drywell pressure has been restored to within the normal band

5. RPV pressure is 600 psig and lowering Task Standard: ADS is returned to a standby status Required Materials: None.

General

References:

1. Procedure 308, Emergency Core Cooling System Operation, Revision 88 Initiating Cue: Shutdown the ADS System lAW procedure 308, Emergency Core Cooling System Operation, starting at Step 10.3 ILT 10-1 NRC Sim JPM 2 Page 1 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Time Critical Task: No.

Validation Time: 5 minutes ILT 10-1 NRC Sim JPM 2 Page 2 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark ./

Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time: _ _ _ __

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

Comment:

SAT/UNSAT Performance Step: 2 Procedure Step: Reviews Prerequisites.

Standard: Reviews Prerequisites.

Comment:

SAT/UNSAT ILT 10-1 I\IRC Sim JPM 2 Page 3 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Procedure Step: 10.3.1 When the drywell high pressure signal clears, place the following keylock switches on Panel 1F/2F to the RESET position momentarily and return them to the AUTO pOSition

A Hi Drywell Pressure Switch

B Hi Drywell Pressure Switch Standard: Veri'fies Drywell pressure < 2.9 psig on Panel 1F/2F, or 4F indication or PPC. Places the following keylock switches on Panel 1F/2F to the RESET position momentarily and returns them to the AUTO position

A HI DRYWELL PRESSURE SWITCH

B HI DRYWELL PRESSURE SWITCH Comment:

SAT/UNSAT Performance Step: 4 Procedure Step: 10.3.2 Verify the following annunciators are clear:

B-3-h, ADS I NOT RESET

B-4-h, ADS II NOT RESET Standard: Verifies the following annunciators are clear:

B-3-h, ADS I NOT RESET

B-4-h, ADS II NOT RESET Comment:

SAT/UNSAT Note: Step 10.3.3 is NA ILT 10-1 NRC Sim JPM 2 Page 4 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 5 Procedure Step: 10.3.4 If in BYPASS, then place the channel A and B ADS TIMER keylock switches on Panel 1F/2F to the AUTO position Standard: Verifies ADS TIMER keylock switches in BYPASS. Places the channel A and B ADS TIMER keylock switches on Panel 1F/2F to the AUTO position.

Comment:

SAT/UNSAT Performance Step: 6 Procedure Step: 10.3.5 Verify the following annunciators are clear:

B-5-h, ADS BYPASSED I

B-6-h, ADS BYPASSED II Standard: Verifies the following annunciators are clear:

B-5-h, ADS BYPASSED I

B-6-h, ADS BYPASSED II Comment:

SAT/UNSAT ILT 10-1 NRC Sim JPM 2 Page 5 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 7 Procedure Step: 10.3.6 Verify the Electromatic Relief Valves close or are closed as indicated by the green lights on the individual valve controllers and by the acoustic monitoring system indications Standard: Verify the Electromatic Relief Valves close or are closed as indicated by the green lights on the individual valve controllers and by the acoustic monitoring system indications (all AUTO DEPRESS VALVE indications show red light OFF; green light ON; all EMRVs indicate in the VALVE CLOSED REGION)

Comment:

SAT/UNSAT Terminating Cue: ADS is returned to a standby status JPM Stop Time: _ _ _ __

ILT 10-1 NRC Sim JPM 2 Page 6 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion

..IPM Number: ILT 10-1 !\JRC Sim JPM 2 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ __

Time to Complete:

Question:

Response

Result: Sa tisfactoryIU nsatisfactory Examiner's Signature and Date:

ILT 10-1 NRC Sim JPM 2 Page 7 of 9

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

1. This ..IPM can be run in IC-115 or similar full power IC

2. Place the ADS Timer keylock switches to BYPASS

3. Have a copy of 308 marked-up including 10.1 & 10.2 ILT 10-1 NRC Sim JPM 2 Page 8 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

1. The plant experienced an ATWS condition and the RPV Control - With ATWS EOP had been entered

2. The Primary Containment Control EOP had also been entered on high Drywell pressure

3. All control rods have since been inserted and RPV Control - No ATWS EOP has been entered

4. Drywell pressure has been restored to within the normal band

5. RPV pressure is 600 psig and lowering Task Cue:

Shutdown the ADS System lAW procedure 308, Emergency Core Cooling System Operation, starting at Step 10.3 ILT 10-1 I\IRC Sim JPM 2 Page 9 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 200::....::0--=-5...:....01_4----"0_1_ _ _ __

Cool down the RPV using the Isolation Condenser tube side vents lAW SP-15, Alternate Pressure Control Systems - IC Task

Title:

Tube Side Vents (Alternate Path)

Job Performance Measure No.: ILT 10-1 NRC Sim JPM3 (RO/SRO)

KIA

Reference:

295021 AA1.04 (RO/SRO 3.7/3.7)

Examinee: 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 plant is shutdown and cooling down to COLD SHUTDOWN lAW RPV Control - no ATWS.

2. Isolation Condensers are not required to be isolated.

3. The Main Condenser is intact.

4. The Offsite radioactivity release rate is below that required for an Unusual Event.

5. Shutdown Cooling interlocks cannot be cleared.

6. All modes of pressure control for cooldown are unavailable except the Isolation Condenser Tube Side Vents.

7. The Isolation Condenser DC valves are isolated due to previous RPV level being> 180". RPV water level is currently 155 in and steady.

Task Standard: RPV is being cooled down using Isolation Condenser B Tube Side Vents.

ILT 10-1 NRC SIM JPM3 Page 1 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Required Materials: None.

General

References:

1. Support Procedure 15, Alternate Pressure Control Systems - IC Tube Side Vents, Revision O.

Initiating Cue: As the US, I am directing you to establish a 10F/hr cooldown rate lAW SP-15, Alternate Pressure Control Systems -IC Tube Side Vents.

Time Critica.l Task: No.

Validation Time: 12 minutes ILT 10-1 NRC SIM ..IPM3 Page 2 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark ../

Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time: _ _ _ __

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

Comment:

SAT/UNSAT Performance Step: 2 Procedure Step: 2.1.1 Verify Isolation Condensers are not required to be isolated.

Standard: Verifies Isolation Condensers are not required to be isolated.

Note: Initial Conditions state that Isolation Condensers are not required to be isolated.

Comment:

SAT/UNSAT ILT 10-1 NRC SIM JPM3 Page 3 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Procedure Step: 2.1.2 Verify Main Condenser is intact.

Standard: Verifies Main Condenser is intact.

Note: Initial Conditions state the Main Condenser is intact.

Comment:

SAT/UNSAT Performance Step: 4 Procedure Step: 2.1 .3 Verify Offsite radioactivity release rate is expected to remain below the release rate, which requires an Unusual Event.

Standard: Verifies Offsite radioactivity release rate is expected to remain below the release rate, which requires an Unusual Event.

Note: Initial Conditions state that Offsite radioactivity release rate is expected to remain below the release rate, which requires an Unusual Event.

Comment:

SAT/UNSAT ILT 10-1 NRC 81M ..IPM3 Page 4 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 5 Procedure Step: 2.2 Open the EOP BYPASS PLUGS panel inside of Pane110XF.

Standard: Opens the EOP BYPASS PLUGS panel inside of Panel 10XF.

Comment:

SAT/UNSAT Performance Step: 6 Procedure Step: 2.2.1 Remove the bypass plug from position BP2.

Standard: Removes the bypass plug from position BP2.

Comment:

SAT/UNSAT ILT 10-1 NRC SIM JPM3 Page 5 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 7 Procedure Step: 2.2.2 Insert a bypass plug into position BP1.

Standard: Inserts a bypass plug into position BP1.

Comment:

SAT/UNSAT Performance Step: 8 Procedure Step: 2.2.3 Remove the bypass plug from position BP4.

Standard: Removes the bypass plug from position BP4.

Comment:

SAT/UNSAT ILT 10-1 NRC SIM JPM3 Page 6 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 9 Procedure Step: 2.2.4 Insert a bypass plug into position BP3.

Standard: Inserts a bypass plug into position BP3.

Comment:

SAT/UNSAT Performance Step: 10 Procedure Step: 3.1 Verify that RPV Water Level is below 180 in.

Standard: Verifies that RPV Water Level is below 180 in.

CUE: If RPV water level has risen to > 180 in following the JPM setup, inform the applicant RPV water level is < 155 in and steady.

Comment:

SAT/UNSAT ILT 10-1 NRC 81M JPM3 Page 7 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 11 Procedure Step: 3.2 Confirm open the following Isolation Condenser Steam Inlet Valves for the Isolation Condenser A: (Panel 1F/2F)

V-14-30

V-14-31 Standard: Confirms open the following Isolation Condenser Steam Inlet Valves for the Isolation Condenser A: (Panel 1F/2F)

V-14-30

V-14-31 Note: Places the CLOSE-AUTO-OPEN switch for the valves to the OPEN position. Waits for valve indications to show red OPEN light lit and green CLOSED light extinguished.

Comment:

SAT/UNSAT ILT 10-1 NRC SIM JPM3 Page 8 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information NOTE: In the next step Isolation Condenser A vents will NOT open. This will initiate the Alternate Path.

Performance Step: 12 Procedure Step: 3.3 Open the following Isolation Condenser Vents for the Isolation Condensers to be used: (Panel 11 F)

V-14-5 / V-14-20 Standard: Opens the following Isolation Condenser Vents for the Isolation Condensers to be used: (Panel 11 F)

V-14-5 / V-14-20 Note: Isolation Condenser A vent valves V-14-5 and V-14-20 will not open. The applicant will re-perform SP-15 starting at step 3.2 for Isolation Condenser B.

CUE: The applicant may inform the US that Isolation Condenser A vent valves will not open. Direct the applicant to continue with Support Procedure 15. It is acceptable if the applicant establishes a coo Idown using the Isolation Condenser B vents without first consulting the US.

Comment:

SAT/UNSAT ILT 10-1 NRC SIM JPM3 Page 9 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 13 Procedure Step: 3.2 Confirm open the following Isolation Condenser Steam Inlet Valves for the Isolation Condenser B: (Panel 1F/2F)

V-14-32

V-14-33 Standard: Confirms open the following Isolation Condenser Steam Inlet Valves for the Isolation Condenser B: (Panel 1F/2F)

V-14-32

V-14-33 Note: Places the CLOSE-AUTO-OPEN switch for the valves to the OPEN position. Waits for valve indications to show red OPEN light lit and green CLOSED light extinguished.

Comment:

SAT/UNSAT ILT 10-1 NRC SIM JPM3 Page 10 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 14 Procedure Step: 3.3 Open the following Isolation Condenser Vents for the Isolation Condensers to be used: (Panel 11 F)

V 1 / V 19 Standard: Opens the following Isolation Condenser Vents for the Isolation Condensers to be used: (Panel 11 F)

V-14-1 / V-14-19 Note: Waits for valve indications to show red OPEN light lit and green CLOSED light extinguished.

CUE: Another operator will continue with and control the cooldown that is already established.

Comment:

SAT/UNSAT Terminating Cue: RPV cooldown is in progress using Isolation Condenser B tube side vents.

JPM Stop Time: _ _ _ __

ILT 10-1 NRC SIM JPM3 Page 11 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: ILT 10-1 NRC Sim JPM3 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts: ____________

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiner's Signature and Date:

ILT 10-1 NRC SIM JPM3 Page 12 of 14

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

1. Reset to IC-115 or any shutdown IC where the Primary Containment is NOT isolated

2. Insert a manual scram

3. Stabilize RPV pressure around 500 psig

4. Stabilize RPV level below 180 in

5. Shut the IC A & B vents

6. Insert VLV-ICS002 to CLOSE

Keeps IC A vent valve V-14-5 closed

7. Insert VLV-ICS004 to CLOSE

Keeps IC A vent valve V-14-20 closed

8. Have a copy of SP-15 for the applicant ILT 10-1 NRC SIM ...IPM3 Page 13 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

1. The plant is shutdown and cooling down to COLD SHUTDOWN lAW RPV Control- no ATWS.

2. Isolation Condensers are not required to be isolated.

3. The Main Condenser is intact.

4. The Offsite radioactivity release rate is below that required for an Unusual Event.

5. Shutdown Cooling interlocks cannot be cleared.

6. All modes of pressure control for cooldown are unavailable except the Isolation Condenser Tube Side Vents.

7. The Isolation Condenser DC valves are isolated due to previous RPV level being> 180". RPV water level is currently 155 in and steady.

Initiating Cue:

As the US, I am directing you to establish a 10F/hr cooldown rate lAW SP-15, Alternate Pressure Control Systems - IC Tube Side Vents.

ILT 10-1 NRC SIM JPM3 Page 14 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 2000501416 Task

Title:

Place the H2/02 Monitoring System in service Job Performance Measure No.: ILT 10-1 NRC Sim JPM4 (RO/SRO)

KIA

Reference:

500000 EA 1.01 (RO/SRO 3.413.3)

Examinee: 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. A LOCA is in progress.

2. The Primary Containment Control EOP has been entered.

Task Standard: Channel A H2I02 Monitoring System is in service.

Required Materials: None.

General

References:

1. Support Procedure 39, Placing the H2/02 Monitoring System In Service, Revision O.

Initiating Cue: As the US, I am directing you to place the H2I02 monitoring system in service lAW Support Procedure 39.

Time Critical Task: No.

Validation Time: 7 minutes ILT 10-1 NRC SIM .JPM4 Page 1 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark -./

Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time: _ _ _ __

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

Comment:

SAT/UNSAT Performance Step: 2 Procedure Step: 3.1.1 (For Channel A) Verify the Power switch is in the ON position Standard: Verifies the Power switch is in the ON position Comment:

SAT/UNSAT ILT 10-1 NRC SIM JPM4 Page 2 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Procedure Step: 3.1.2 Place switch for H2 Sample Supply V-38-37 to OPEN Standard: Places switch for H2 Sample Supply V-38-37 to OPEN Note: Verifies that the red OPEN light is lit and the green CLOSE light is extinguished.

Comment:

SAT/UNSAT Performance Step: 4 Procedure Step: 3.1.3 Place switch for H2 Sample Supply V-38-38 to OPEN Standard: Places switch for H2 Sample Supply V-38-38 to OPEN Note: Verifies that the red OPEN light is lit and the green CLOSE light is extinguished.

Comment:

SAT/UNSAT ILT 10-1 NRC SIM ..IPM4 Page 3 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 5 Procedure Step: 3.1 .4 Place switch for H2 Sample Supply V-38-39 to OPEN Standard: Places switch for H2 Sample Supply V-38-39 to OPEN Note: Verifies that the red OPEN light is lit and the green CLOSE light is extinguished.

Comment:

SAT/UNSAT Performance Step: 6 Procedure Step: 3.1.5 Place switch for H2 Sample Supply V-38-40 to OPEN Standard: Places switch for H2 Sample Supply V-38-40 to OPEN Note: Verifies that the red OPEN light is lit and the green CLOSE light is extinguished.

Comment:

SAT/UNSAT ILT 10-1 NRC SIM .JPM4 Page 4 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 7 Procedure Step: 3.1.6 Place switch for PUMP (P-38-5) in ENABLE position Standard: Places switch for PUMP (P-38-5) in ENABLE position Comment:

SAT/U NSAT Performance Step: 8 Procedure Step: 3.1.7 Depress Channel A ANALYZE PB to place Analyzer IT-1A in Analyze mode.

Standard: Depresses Channel A ANALYZE PB to place Analyzer IT-1A in Analyze mode.

Note: PB = Pushbutton Comment:

SAT/UNSAT ILT 10-1 NRC SIM JPM4 Page 5 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 9 Procedure Step: 3.1.8 Touch CRT Screen and VERIFY:

GAS MONITORING SYSTEM screen ILLUMINATES

GAS MONITORING SYSTEM screen does not indicate Stand-By mode.

Standard: Touches CRT Screen and VERIFY:

GAS MONITORING SYSTEM screen ILLUMINATES

GAS MONITORING SYSTEM screen does not indicate Stand-By mode.

Comment:

SAT/UNSAT ILT 10-1 NRC SIM JPM4 Page 6 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 10 Procedure Step: 3.1.9 Verify H~02 Recorder AR-0002 begins recording Standard: Verifies H2/0 2 Recorder AR-0002 begins recording CUE: Inform the applicant Channel A has begun recording and another operator will continue with the support procedure Comment:

SAT/UNSAT Terminating Cue: Channel A of the H2/02 monitoring system has been placed in service lAW SP-39.

JPM Stop Time: _ _ _ __

ILT 10-1 NRC SIM JPM4 Page 7 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM !\lumber: ILT 10-1 NRC Sim JPM4 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ __

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiner's Signature and Date:

ILT 10-1 NRC SIM ..IPM4 Page 8 of 10

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

1. Reset to any IC

2. Have a copy of SP-39 for the applicant ILT 10-1 NRC SIM JPM4 Page 9 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

1. A LOCA is in progress.

2. The Primary Containment Control EOP has been entered.

Initiating Cue:

As the US, I am directing you to place the H2I02 monitoring system in service lAW Support Procedure 39.

ILT 10-1 NRC SIM JPM4 Page 10 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 2620101002 Manual Transfer of the 4160 VAC Bus 1A from the Auxiliary Task

Title:

Transformer to the Startup Transformer (Alternate Path)

Job Performance Measure No.: ILT 10~1 NRC Sim JPM5 (RO/SRO)

KIA

Reference:

262001 K4.02 (RO/SRO 2.9/3.3)

Examinee: 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 plant is at rated power.

2. 4160 VAC Bus 1A Main Breaker needs to be removed from service.

3. All Prerequisites of 337, step 6.2.1, have been verified met.

Task Standard: 4160 VAC Bus 1A is powered from the S1A Startup Transformer and Main Breaker 1A has been manually tripped.

Required Materials: None.

General

References:

1. Procedure 337, 4160 Volt Electrical System, Revision 85.

Initiating Cue: As the US, I am directing you to transfer 4160 VAC Bus 1A to the Startup Transformer.

Time Critical Task: No.

Validation Time: 12 minutes ILT 10-1 NRC SIM JPM5 Page 1 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark ./

Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time: _ _ _ __

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

Comment:

SAT/UNSAT Performance Step: 2 Procedure Step: 6.2.2. Reviews Precautions and Limitations.

Standard: Reviews Precautions and Limitations.

CUE: If requested, any Prerequisites or Precautions and Limitations the applicant requests to verify that is outside of the Control Room can be acknowledged as being met.

Comment:

SAT/UNSAT ILT 10-1 NRC 81M JPM5 Page 2 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Procedure Step: 6.2.3.1 Adjust Bank 5 voltage regulator in accordance with Section 11.0.

Standard: Ensures Bank 5 voltage regulator is adjusted in accordance with Section 11.0.

CUE: Inform the applicant that the Bank 5 regulator is in service and is adjusted lAW Section 11.0. (NOTE: Section 11.0 is not provided to the applicants)

Comment:

SAT/UNSAT Performance Step: 4 Procedure Step: 6.2.3.2 Confirm the Bank 5 transformer oil pump is operating by placing the control switch in HAND.

Standard: Confirms the Bank 5 transformer oil pump is operating by placing the control switch in HAND.

CUE: The Bank 5 transformer oil pump is in HAND and running.

Comment:

SAT/UNSAT ILT 10-1 NRC SIM JPM5 Page 3 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 5 Procedure Step: 6.2.3.3 Confirm the Bank 5 transformer cooling fans are operating by placing the control switch in HAND.

Standard: Confirms the Bank 5 transformer cooling fans are operating by placing the control switch in HAND.

CUE: The Bank 5 transformer cooling fans are in HAND and running.

Comment:

SAT/UNSAT Performance Step: 6 Procedure Step: 6.2.3.4 Verify MAIN BREAKER 1A control switch is in the CLOSE position. (Panel BF/9F).

Standard: Verifies MAIN BREAKER 1A control switch is in the CLOSE position. (Panel BF/9F).

Comment:

SAT/UNSAT ILT 10-1 NRC SIM ..IPM5 Page 4 of 14

Appendix C Job Performance Measure Form ES-C*1 WORKSHEET Performance Information Performance Step: 7 Procedure Step: 6.2.3.S VERIFY MAIN BREAKER 1A CLOSED light is illuminated. (Panel SF/9F).

Standard: Verifies MAIN BREAKER 1A CLOSED light is illuminated. (Panel SF/9F).

Comment:

SAT/UNSAT Performance Step: S Procedure Step: 6.2.3.6 Verify STARTUP BREAKER S1A is racked in and open by observing the following at Panel SF/9F:

Green OPEN light illuminated

BKR UP light illuminated Standard: Verifies STARTUP BREAKER S1A is racked in and open by observing the following at Panel SF/9F:

Green OPEN light illuminated

BKR UP light illuminated Comment:

SAT/UNSAT ILT 10-1 NRC SIM JPMS Page S of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 9 Procedure Step: 6.2.3.7 Verify the 34.SKV breaker, feed to Bank S is closed by the red CLOSE light illuminated (Panel 12F-S).

Standard: Verifies the 34.SKV breaker, feed to Bank S is closed by the red CLOSE light illuminated (Panel 12F-S).

Comment:

SAT/U NSAT Performance Step: 10 Procedure Step: 6.2.3.S Insert the synchronizing key into the Synchroscope Switch for Startup Breaker S1A. (Panel BF/9F)

Standard: Inserts the synchronizing key into the Synchroscope Switch for Startup Breaker S1A. (PaneISF/9F)

Comment:

SAT/UNSAT ILT 10-1 NRC SIM JPMS Page 6 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 11 Procedure Step: 6.2.3.9 Place Synchroscope Switch to the ON position. (Panel SF/9F)

Standard: Places the Synchroscope Switch to the ON position. (Panel SF/9F)

Comment:

SAT/UNSAT Performance Step: 12 Procedure Step: 6.2.3.10 Verify power is synchronized across the S1 A breaker by comparing the following:

Voltage

Frequency Standard: Verifies power is synchronized across the S1A breaker by comparing the following:

Voltage

Frequency Note: The Synchroscope needle should be stationary and pointing at 12 o'clock with both Synchroscope lights extinguished.

Comment:

SAT/UNSAT ILT 10-1 NRC SIM JPM5 Page 7 of 14

Appendix C Job Performance Measure Form ES~C-1 WORKSHEET Performance Information Performance Step: 13 Procedure Step: 6.2.3.11 Places STARTUP BREAKER S1A control switch to the CLOSE position. (Panel SF/9F)

Standard: Places STARTUP BREAKER S1A control switch to the CLOSE position. (Panel SF/9F)

Comment:

SAT/UNSAT Performance Step: 14 Procedure Step: 6.2.3.12 Verify STARTUP BREAKER S1A red CLOSED light illuminated.

(Panel SF/9F)

Standard: Verifies STARTUP BREAKER S1A red CLOSED light illuminated.

(Panel SF/9F)

Comment:

SAT/UNSAT ILT 10-1 NRC SIM JPM5 Page S of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information NOTE: In step 15 the applicant will recognize that Breaker 1A did not trip. This initiates the Alternate Path.

Performance Step: 15 Procedure Step: 6.2.3.13 Verify MAIN BREAKER 1A trips by the associated green OPEN light being illuminated. (Panel 8F/9F)

Standard: Veri'fies MAIN BREAKER 1A trips by the associated green OPEN light being illuminated. (Panel 8F/9F). Recognized that MAl N BREAKER 1A did not trip and manually trips breaker with or without US direction.

NOTE: Applicant observes that Breaker 1A is still CLOSED. Observes annunciator for S-3-f, S1A BRKR OFF NORMAL.

CUE: Applicant may manually trip breaker 1A without guidance (automatic action that failed to occur). If the applicant requests guidance from the US, direct them to manually open breaker 1A.

Comment:

SAT/UNSAT Performance Step: 16 Procedure Step: 6.2.3.14 Place Synchroscope Switch for Startup Breaker S1A to the OFF position.

Standard: Places Synchroscope Switch for Startup Breaker S1A to the OFF position.

Comment:

SAT/UNSAT ILT 10-1 NRC SIM JPM5 Page 9 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 17 Procedure Step: 6.2.3.15 Remove the synchronizing key.

Standard: Removes the synchronizing key.

Note: Places synchronizing key in ED slot for storage.

Comment:

SAT/UNSAT Performance Step: 1B Procedure Step: 6.2.3.16 Place MAIN BREAKER 1A control switch to the TRIP position.

1. Verify the mechanical indication and the light indication match.

2. Verify MI'J BRKR 1A TRIP alarm clears (Panel BF/9F).

Standard: Places MAIN BREAKER 1A control switch to the TRIP position.

1. Verify the mechanical indication and the light indication match.

2. Verify MN BRKR 1A TRIP alarm clears (Panel BF/9F).

Note: The applicant may take credit for this step by actions performed in Performance Step 15 (procedure step 6.2.3.13)

Comment:

SAT/UNSAT ILT 10-1 NRC SIM JPM5 Page 10 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 19 Procedure Step: 6.2.3.17 Adjust 4160V bus voltage in accordance with Section 11.0.

Standard: Adjusts 4160V bus voltage in accordance with Section 11 .0.

CUE: If the applicant attempts to adjust 4160 VAC Bus Voltage, as the US, inform the applicant that 4160 VAC Bus 1A Voltage does not require any adjustments at this time. (!\JOTE: Section 11.0 is not provided to the applicants)

Comment:

SAT/UNSAT Terminating Cue: The applicant has closed Startup Breaker S1 A and manually tripped Main Breaker 1A.

JPM Stop Time: _ _ _ __

ILT 10-1 NRC SIM JPM5 Page 11 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: ILT 10-1 NRC Sim JPM5 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ __

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiner's Signature and Date:

ILT 10-1 NRC SIM JPM5 Page 12 of 14

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

1. Reset to full power IC (IC-115) or similar

2. Insert BKR-EDS022A to 3-FAIL AUT TRIP

This will result in 4160 VAC Main Breaker 1A failing to automatically trip.

3. Have a copy of procedure 337, sections 6.2.

ILT 10-1 NRC SIM JPM5 Page 13 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

1. The plant is at rated power.

2. 4160 VAC Bus 1A Main Breaker needs to be removed from service.

3. All Prerequisites of 337, step 6.2.1, have been verified met.

Initiating Cue:

As the US, I am directing you to transfer 4160 VAC Bus 1A to the Startup Transformer.

ILT 10-1 NRC SIM JPM5 Page 14 of 14

Appendix C Job Performance Measure WORKSHEET Facility: Oyster Creek Task No.: 2150201401 Task

Title:

Perform an APRM Gain Adjustment Job Performance Measure No.: ILT 10-1 NRC Sim JPM6 (RO/SRO)

KIA

Reference:

215005 A4.03 (RO 3.2/SRO 3.3)

Examinee: 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. Reactor Recirculation flow was just adjusted to attain 100% reactor power a short while ago.

2. Reactor power has been steady for the last 5 minutes.

3. Procedure 403 allows bypassing APRM 8.

4. The procedure revision, prerequisites and precautions and limitations have been verified by the Unit Supervisor.

5. APRM 8 is the ONLY APRM that requires an adjustment.

Task Standard: APRM 8 should indicate 100% +/- 1% of Core Thermal Power and APRM 8 has been UNBYPASSED on Panel4F.

Required Materials: None.

General

References:

1. 202.1-9, APRM Gain Adjustment From Heat Balance (Hard Card), revision 120 ILT 10-1 NRC SIM ..IPM5 Page 1 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Initiating Cue: Perform an APRM Gain Adjustment on APRM 8 lAW Attachment 202.1-9 starting at step 2.2.

Time Critical Task: No.

Validation Time: 5 minutes ILT 10-1 NRC SIM JPM5 Page 2 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Denote critical steps with a check mark ./

Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time: _ _ _ __

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

Comment:

SAT/UNSAT Performance Step: 2 Procedure Step: 1.0.

Reviews Procedure revision, Prerequisites, and Precautions and Limitations.

Standard: Acknowledges the Initial Conditions state that the procedure revision, prerequisites and precautions and limitations have been verified with the US.

CUE: This was given in the Initial Conditions and the student may initial the step in section 1.0 as completed.

Comment:

SAT/UNSAT ILT 10-1 !\JRC SIM JPM5 Page 3 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Step: 3 Procedure Step: 2.1 Allow reactor power to stabilize for at least 2 minutes.

Standard: The student verifies from the Initial Conditions that reactor power has been stabilized for at least 2 minutes.

CUE: The Initial Conditions state that reactor power has been stable for 5 minutes. The student may initial this step as complete.

Comment:

SAT/UNSAT Performance Step: 4 Procedure Step: 2.2 If allowed by 403, bypass APRM 8.

Standard: Verifies from the Initial Conditions that Bypassing APRM 8 is allowed by Procedure 403.

Bypasses APRM 8 on Panel4F by placing the APRM BYPASS joystick in the CH 8 position.

Comment:

SAT/UNSAT ILT 10-1 NRC SIM JPM5 Page 4 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Step: 5 Procedure Step: 2.3 Pull out the APRM 8 drawer.

Standard: Pulls out APRM Drawer 8 on Panel 5R to allow access to the R10 screw (Gain adjustment screw).

Comment:

SAT/UNSAT Performance Step: 6 Procedure Step: 2.4 Turn the gain adjustment pot with a small screwdriver (R10 on calibration and feedback unit) clockwise to raise gain or counterclockwise to lower gain while monitoring APRM output on the APRM 8 drawer.

Standard: Inserts small screwdriver and turns CCW or CW to change APRM power indication.

Comment:

SAT/UNSAT ILT 10-1 NRC SIM JPM5 Page 5 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Step: 7 Procedure Step: 2.5 When output on APRM 8 drawer matches required APRM setting within 1%, then stop gain adjustment and push in the APRM 8 drawer.

Standard: When output on APRM 8 drawer matches required APRM setting within 1%, then stops gain adjustment. With reactor power at 100%, APRM 8 should indicate 100% +/- 1% of Core Thermal Power.

Pushes in APRM drawer 8.

Comment:

SAT/UNSAT Performance Step: 8 Procedure Step: 2.6 Un-bypasses APRM 8.

Standard: Places the APRM 8 BYPASS joystick to the center position.

Comment:

SAT/UNSAT ILT 10-1 NRC SIM JPM5 Page 6 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Step: 9 Procedure Step: 2.7 If another APRM channel in the same drawer requires adjustment, then perform the APRM adjustment lAW steps 2.2 through 2.6.

Standard: Determines that no other APRM adjustments are required from the Initial Conditions.

CUE: Student will inform evaluator that APRM 8 Gain has been adjusted.

Comment:

SAT/UNSAT ILT 10-1 NRC SIM ..IPM5 Page 7 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: ILT 10-1 NRC SimJPM6 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ __

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiner's Signature and Date:

ILT 10-1 NRC SIM JPM5 Page 8 of 11

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

1. Reset the simulator to IC-115 or other rated power IC.

2. Change APRM 8 gain so that the APRM reads> 104%.

3. Have a blank copy of Attachment 202.1-9 rev 120, APRM Gain Adjustment From Heat Balance (Hard Card).

4. Ensure Heat Balance is displayed on PPC between Panel 3R and 4R.

5. Ensure APRMs 1 through 7 indicate 100%.

6. Ensure all APRM drawers are fully pushed in.

7. Have a copy of procedure 403 for the students to Bypass APRM 8.

8. Have a copy of Attachment 403-2 which shows APRM bypass is allowed.

ILT 10-1 NRC SIM JPM5 Page 9 of 11

Appendix C Job Performance Measure Form ES~C~1 WORKSHEET STUDENT HANDOUT Initial Conditions:

1. Reactor Recirculation flow was just adjusted to attain 100% reactor power a short while ago.

2. Reactor power has been steady for the last 5 minutes.

3. Procedure 403 allows bypassing APRM 8.

4. The procedure revision, prerequisites and precautions and limitations have been verified by the Unit Supervisor.

5. APRM 8 is the ONLY APRM that requires an adjustment.

Initiating Cue:

Perform an APRM Gain Adjustment on APRM 8 lAW Attachment 202.1-9 starting at step 2.2.

ILT 10-1 NRC SIM JPM5 Page 10 of 11

Exelonw OYSTER CREEK GENERATING STATION PROCEDURE Number 202.1 Nuclear Title Revision No.

Power Operation 120 ATTACHMENT 202.1-9 Page 1 of 1 APRM GAIN ADJUSTMENT FROM HEAT BALANCE {HARD CARD}

202.1, Section 4.13.2.1

~ RIFY with the Unit Supervisor that the following support use of the Hard Card:

Procedure revision [TB]

Prerequisites [TB]

Precautions and Limitations [TB]

~ M GAIN ADJUSTMENT ALLOW reactor to stabilize for at least 2 minutes. [TB]

IF allowed by Procedure 403, THEN BYPASS the APRM channel. [ ]

2.3 PULL out selected APRM drawer. [ ]

2.4 TURN the gain adjustment pot with a small screwdriver (R10 on calibration and feedback unit) clockwise to raise gain or counterclockwise to lower gain while monitoring APRM output on the selected drawer. [ ]

2.5 WHEN output on the selected drawer matches required APRM setting within 1%,

THEN STOP gain adjustment [ ]

AND PUSH in selected drawer when all APRM adjustments are cornplete. [ ]

2.6 LE the APRIVI channel was bypassed, THEN UNBYPASS the APRM channel. [ ]

2.7 IF another APRM channel in the same drawer requires adjustment, THEN PERFORM the APRM channel adjustment lAW steps 2.2 through 2.6 above. [ ]

3.0 REFER to Procedure 202.1 if problems are encountered. [ ]

E9-1

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 2860401403 Task

Title:

Inject Fire Water Via The Core Spray System During An ATWS Job Performance Measure No.: ILT 10-1 NRC Sim JPM 7 (RO/SRO)

KIA

Reference:

286000 A4.06 (RO 3.4/3.4)

Examinee: 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 crew is responding to an ATWS and LOCA.

2. The RPV has been Emergency Depressurized.

3. RPV water level is -15" and lowering.

4. Injecting water with Low Pressure Systems has been directed by the Emergency Operating Procedures.

5. The Fire Protection System is available.

Task Standard: Firewater is being injected into the RPV via the Core Spray System.

Required Materials: None.

General

References:

1. Procedure EMG-SP20, Low Pressure Injection During An ATWS, rev. 0 ILT10-11\IRCSimJPM7 Page 1 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Initiating Cue: As the US, I am directing you to lineup and inject firewater via Core Spray System 1 lAW SP-20, Low Pressure Injection During An ATWS.

Time Critical Task: No.

Validation Time: 12 minutes ILT 10-1 !\IRC Sim JPM 7 Page 2 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark 0/

Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time: _ _ _ __

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

Comment:

SAT/UNSAT Performance Step: 2 Procedure Step: 1.0 Injecting water with Low Pressure Systems has been directed by the Emergency Operating Procedures.

Standard: The student verifies from the Initial Conditions that injecting water with Low Pressure Systems has been directed by the Emergency Operating Procedures and initials this step as complete.

Comment:

SAT/UNSAT ILT 10-1 NRC Sim JPM 7 Page 3 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Procedure Step: 2.1 IF Core Spray activating signals are present, THEN OVERRIDE Core Spray initiation logic by performing the following: (Panel 1F/2F)

1. PRESS the OVERRIDE switches for all the sensors that are lit.

2. PRESS !ill ACTUATED switches, whether lit or unlit.

Standard: Overrides Core Spray initiation logic by performing the following: (Panel 1F/2F)

1. Presses the OVERRIDE switches for all the sensors that are lit.

2. Presses all ACTUATED switches, whether lit or unlit.

Comment:

SAT/UNSAT ILT 10-1 NRC Sim JPM 7 Page 4 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 4 Procedure Step: 2.2 IE Firewater is available, THEN DISPATCH an operator to the Firewater valves for the selected Core Spray System.

Standard: The student verifies from the Initial Conditions the fire protection system is available. The student dispatches an EO to Core Spray System 1 Firewater valves.

CUE: Report an EO has been dispatched and is standing by at the Core Spray System 1 Firewater valves.

Comment:

SAT/UNSAT Performance Step: 5 Procedure Step: 2.3 IF using Condensate Transfer for injection, THEN DISPATCH an operator to the Reactor Building with an MB-1 key.

Standard: Student initials or N/As this step since Condensate Transfer is not being used for injection.

Comment:

SAT/UNSAT ILT 10-1 NRC Sim ..IPM 7 Page 5 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 6 Procedure Step: 3.1 DETERMINE which RPV injection source is to be used as directed by the Unit Supervisor.

Standard: Student verifies from Initiating Cue that the Unit Supervisor directed injecting with Firewater via Core Spray System 1 and initials off this step.

Comment:

SAT/UNSAT Performance Step: 7 Procedure Step: 3.2.1 VERIFY Condensate Transfer is not being injected via Core Spray System 1.

Standard: Student verifies from Initiating Cue that the Unit Supervisor directed injecting with Firewater via Core Spray System 1 and initials off this step.

CUE: If the student asks, inform them Condensate Transfer is not being injected via Core Spray System 1.

Comment:

SAT/UNSAT ILT 10-1 NRC Sim ...'PM 7 Page 6 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 8 Procedure Step: 3.2.2 CONFIRM stopped Core Spray Booster Pump A and C.

Standard: The student confirms Core Spray Booster Pump A and Care stopped.

Comment:

SAT/UNSAT Performance Step: 9 Procedure Step: 3.2.3 CO~IFIRM stopped Core Spray Main Pump A and C.

Standard: The student confirms Core Spray Main Pump A and Care stopped.

Comment:

SAT/UNSAT ILT 10-1 NRC Sim JPM 7 Page 7 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 10 Procedure Step: 3.2.4 PLACE Core Spray System 1 Main Pump control switches in PULL-TO-LOCK position.

Standard: Places the control switches for Core Spray Main Pump A and C in PULL-TO-LOCK.

Comment:

SAT/UNSAT Performance Step: 11 Procedure Step: 3.2.5 CLOSE Tell-Tale Drain Valve, V-20-91. (RB 23 North or North Side RB outside)

Standard: Calls the Reactor Building EO and directs them to close Tell-Tale Drain Valve, V-20-91.

CUE: When requested as the RB EO, tell the student that Tell-Tale Drain Valve, V-20-91 is closed. (This valve is NOT modeled in the simulator).

Comment:

SAT/UNSAT ILT 10-1 NRC Sim JPM 7 Page 8 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 12 Procedure Step: 3.2.6 CONFIRM running all available Diesel Fire Pumps by placing their control switches in MAN position. (Panel 13R)

Standard: Places the control switches for Fire Diesel Pump 1 and 2 in MAN on Panel 13R.

Comment:

SAT/UNSAT Performance Step: 13 Procedure Step: 3.2.7 CONFIRM open Core Spray System 1 Discharge Valve, V-20-12. (PaneI1F/2F)

Standard: Confirms open Core Spray System 1 Discharge Valve, V-20-12. (Panel 1F/2F)

Comment:

SAT/UNSAT ILT 10-1 !\IRC Sim ..IPM 7 Page 9 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 14 Procedure Step: 3.2.8 CONFIRM closed Core Spray System 1 Test Flow Return Valve, V-20-27. (Panel 1F/2F)

Standard: Confirms closed Core Spray System 1 Test Flow Return Valve, V 20-27. (Panel 1F/2F)

Comment:

SAT/UNSAT Performance Step: 15 Procedure Step: 3.2.9 CLOSE the following Core Spray System 1 Pump Suction Valves: (Panel 1F/2F)

V-20-32

V-20-3 Standard: Places the control switch for V-20-32 and V-20-3 to the CLOSE position (one switch operates both valves)

Comment:

SAT/U NSAT ILT 10-1 I\IRC Sim JPM 7 Page 10 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 16 Procedure Step: 3.2.10 CONFIRM open either of the following Core Spray System 1 Parallel Isolation Valves:

V-20-1S

V-20-40 Standard: Confirms either V-20-1S or V-20-40 are OPEN.

Comment:

SAT/UNSAT Performance Step: 17 Procedure Step: 3.2.11 Slowly THROTTLE open Fire Water Supply Valve, V-20-83 to maintain RPV Level. (RS 23 North or North Side RS outside)

Standard: Directs the RS EO to slowly THROTTLE open Fire Water Supply Valve, V-20-83 to maintain RPV Level. (RS 23 North or North Side RS outSide)

CUE: As the RS EO, inform the student V-20-83 has been throttled open, Firewater is injecting into the RPV via Core Spray System 1, and another operator will continue with the Support Procedure.

Comment:

SAT/UNSAT Terminating Cue: Fire Water Supply Valve, V-20-83, has been throttled open and Firewater is injecting into the RPV via Core Spray System 1.

JPM Stop Time: _ _ _ __

ILT 10-1 !\IRC Sim JPM 7 Page 11 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: ILT 10-1 NRC Sim ..IPM 7 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ __

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiner's Signature and Date:

ILT 10-1 NRC Sim JPM 7 Page 12 of 14

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

1. Reset to IC-1S1 (password protected for ILT 10-1 NRC Exam).

a. This IC places the plant in a Hydraulic ATWS where ED has been completed.

2. Verify RPV pressure and level are stabilized before administration of the JPM.

ILT 10-1 NRC Sim JPM 7 Page 13 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

1. The crew is responding to an ATWS and LOCA.

2. The RPV has been Emergency Depressurized.

3. RPV water level is -15" and lowering.

4. Injecting water with Low Pressure Systems has been directed by the Emergency Operating Procedures.

5. The Fire Protection System is available.

Task Cue:

As the US, I am directing you to lineup and inject firewater via Core Spray System 1 lAW SP-20, Low Pressure Injection During An ATWS.

ILT 10-1 NRC Sim .JPM 7 Page 14 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 28801 1404 Startup of the Turbine Building Ventilation System (Alternate Task

Title:

Path)

Job Performance Measure No.: ILT 10-1 NRC Sim JPM 8 (RO/SRO)

KIA

Reference:

288000 A4.01 (3.1/2.9)

Examinee: 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 plant is shutdown

2. The Turbine Building Ventilation System has been secured

3. All prerequisites to start the Turbine Building Ventilation System have been verified Task Standard: The Turbine Ventilation System has been started utilizing Exhaust Fan 1-6 Required Materials: None.

General

References:

1. Procedure 328, Turbine Building Heating And Ventilation System, Revision 54 Initiating Cue: Start the Turbine Building Ventilation System lAW Procedure 328, Turbine Building Heating And Ventilation System, starting at Step 5.1.2 Time Critical Task: No.

ILT 10-1 NRC Sim JPM 8 Page 1 of 15

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation Time: 11 minutes ILT 10-1 NRC Sim JPM 8 Page 2 of 15

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark ""

Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time: _ _ _ __

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

Comment:

SAT/UNSAT Performance Step: 2 Procedure Step: Reviews Precautions and Limitations.

Standard: Reviews Precautions and Limitations.

Comment:

SAT/UNSAT ILT 10-1 I\IRC Sim JPM 8 Page 3 of 15

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Note: Exhaust Fan 1-7 will not start and initiates the Alternate Path.

Exhaust Fan 1-7 will not be re-started on the second attempt.

Performance Step: 3 Procedure Step: 5.1.2 Start EF-1-7 by placing EF-1-7 control switch to START.

Reports the fan does not start.

Standard: Starts EF-1-7 by placing EF-1-7 control switch to START.

Reports the fan will not start. (red light OFF; green light ON)

May contact EO to inspect the Fan.

Cue: As the SRO, acknowledge the fan will not start. As the EO, report that you see no obvious abnormalities with the fan.

Comment:

SAT/UNSAT Note: The step below may occur any time during the JPM.

Performance Step: 4 Procedure Step: 5.1.2.1.1 Caution Notify Radiation Protection anytime operating EF-1-6.

Standard: Notifies Radiation Protection anytime operating EF-1-6.

Cue: RP has been notified Comment:

SAT/UNSAT ILT 10-1 NRC Sim JPM 8 Page 4 of 15

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 5 Procedure Step: 5.1.2.1.1 Confirm closed Dampers DM-28-8, DM-28-3 and their associated limit switches are made up Standard: Directs the EO to confirm closed Dampers DM-2S-S, DM-2S-3 and their associated limit switches are made up Cue: Dampers DM-2S-S, DM-2S-3 are closed and their associated limit switches are made up Comment:

SAT/LINSAT Performance Step: 6 Procedure Step: 5.1.2.1.2 Confirm open DM-2S-4 and associated limit switches are made up.

Standard: Directs the EO to confirm open DM-2S-4 and associated limit switches are made up.

Cue: Damper DM-2S-4 is open and associated limit switches are made up.

Comment:

SAT/UNSAT ILT10-1 NRCSimJPMS Page 5 of 15

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 7 Procedure Step: 5.1 .2.1.3 Start EF-1-7 by placing EF-1-7 control switch to START Standard: Starts EF-1-7 by placing EF-1-7 control switch to START and recognizes the fan will not start (red light OFF; green light ON)

Comment:

SAT/UNSAT Performance Step: 8 Procedure Step: 5.1.2.1.4a If EF-1-7 fails to start on the second attempt, then place EF-1-6 in service as follows:

Open V-28-71 to drain any standing water from EF-1-6 Standard: Directs EO to Open V-28-71 to drain any standing water from EF-1-6 Cue: V-28-71 is open and a little water has drained out.

Comment:

SAT/UNSAT ILT 10-1 NRC Sim JPM 8 Page 6 of 15

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 9 Procedure Step: 5.1.2.1 Ab When water has stopped draining, then close V-28-71 Standard: Directs EO to close V-28-71 when water has stopped draining Cue: Water has stopped draining and V-28-71 is closed Comment:

SAT/UNSAT Performance Step: 10 Procedure Step: 5.1.2.1Ac Confirm closed DM-28-8 Standard: Directs EO to confirm closed DM-28-8 Cue: DM-28-8 is closed Comment:

SAT/UNSAT ILT 10-1 NRC Sim JPM 8 Page 7 of 15

Appendix C Job Performance Measure Form ES~C-1 WORKSHEET Performance Information Performance Step: 11 Procedure Step: 5.1.2.1.4d Close DM-28-4.

Standard: Directs EO to close DM~28-4 Cue: DM~28-4 is closed Comment:

SAT/UNSAT Performance Step: 12 Procedure Step: 5.1.2.1.4e Open DM-28-3 Standard: Directs the EO to open DM-28-3 Cue: DM-28~3 is open Comment:

SAT/UNSAT ILT 10-1 NRC Sim "IPM 8 Page 8 of 15

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 13 Procedure Step: 5.1 .2.1.4f Start Exhaust Fan EF-1-6 by placing EF-1-6 control switch to ON Standard: Starts Exhaust Fan EF-1-6 by placing EF-1-6 control switch to START (red light ON; green light OFF)

Comment:

SAT/UNSAT Performance Step: 14 Procedure Step: 5.1.3 Start Supply Fan SF-1-1 or SF-1-2 by placing Control Switch to ON Standard: Starts Supply Fan SF-1-1 or SF-1-2 by placing Control Switch to ON (red light ON; green light OFF)

Comment:

SAT/UNSAT ILT 10-1 NRC Sim JPM 8 Page 9 of 15

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 15 Procedure Step: 5.1.4 Start Supply Fan SF-1-3 or SF-1-4 by placing Control Switch to ON.

Standard: Starts Supply Fan SF-1-3 or SF-1-4 by placing Control Switch to ON. (red light ON; green light OFF)

Comment:

SAT/UNSAT Performance Step: 16 Procedure Step: 5.1.5 Start EF-1-33 by placing EF-1-33 control switch to ON.

Standard: Starts EF-1-33 by placing EF-1-33 control switch to OI\J. (red light ON; green light OFF)

Comment:

SAT/UNSAT ILT 10-1 NRC Sim JPM 8 Page 10 of 15

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 17 Procedure Step: 5.1 .6 Start SF-1-5 or SF-1-6 by placing the control switch to ON.

Standard: Starts SF-1-5 or SF-1-6 by placing the control switch to ON. (red light ON; green light OFF)

Comment:

SAT/UNSAT Performance Step: 18 Procedure Step: 5.1.7 Verify that EF-1-4 has started by observing the red indicating light Lit Standard: Verifies that EF-1-4 has started by observing the red indicating light Lit Comment:

SAT/UNSAT ILT 10-1 NRC Sim JPM 8 Page 11 of 15

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 19 Procedure Step: 5.1.8 Starts Feedwater Pump Room Supply Fan, SF-1-7, and Exhaust Fan, EF-1-1, by placing SF-1-7 and EF-1-1 control switch to ON Standard: Start Feedwater Pump Room Supply Fan, SF-1-7, and Exhaust Fan, EF-1-1, by placing SF-1-7 and EF-1-1 control switch to ON (red lights ON; green lights OFF)

Cue: Another Operator will continue with the procedure Comment:

SAT/UNSAT Terminating Cue: The Turbine Ventilation System has been started utilizing Exhaust Fan 1-6 JPM Stop Time: _ _ _ __

ILT 10-1 NRC Sim JPM 8 Page 12 of 15

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: ILT 10-1 NRC Sim JPM Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts: ____________

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiner's Signature and Date:

ILT 10-1 NRC Sim JPM 8 Page 13 of 15

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

1. IC-115. (but can be any IC)

2. Shutdown the TB Vent System lAW procedure 328, section 5.4

3. Insert the following:

a. LOA-TBS030 to OPEN

b. SWI-TBS017A to ON

c. These two malfunctions open the breaker to Exhaust Fan 1-7 but keeps the green light on

4. Insert AI\IN-L-2E to OFF

a. This keeps EF 7 TRIP annunciator off

5. Insert LOA-TBS011 to CLOSE (this closes DM-28-4)

6. Insert LOA-TBS012 to OPEN (this opens DM-28-3)

7. Insert LOA-TBS013 to OFF (stops SF 1-22)

8. Have a copy of 328, completed up to step 5.1.1 (for only section 5)

ILT 10-1 NRC Sim JPM 8 Page 14 of 15

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

1. The plant is shutdown

2. The Turbine Building Ventilation System has been secured

3. All prerequisites to start the Turbine Building Ventilation System have been verified Task Cue:

Start the Turbine Building Ventilation System lAW Procedure 328, Turbine Building Heating and Ventilation System, starting at Step 5.1.2 ILT 10-1 NRC Sim JPM 8 Page 15 of 15

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 2000501441 Task

Title:

Vent the Scram Air Header Job Performance Measure No.: ILT 10-1 NRC Plant ..IPM 1 (RO/SRO)

KIA

Reference:

295037 EA1.05 (RO 3.9/SRO 4.0)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance --~--

X Actual Performance Classroom - - - - - Simulator - - - - - Plant x Read to the Examinee:

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

Initial Conditions:

1. The plant was at rated power when an electric ATWS occurred Task Standard: The scram air header has been vented and then restored to normal Required Materials: None.

General

References:

1. EMG-SP21, Alternate Insertion of Control Rods, revision 0 Initiating Cue: Vent the scram air header lAW EMG-SP21 , section 4.3 Time Critical Task: No.

Validation Time: 2 minutes ILT 10-1 NRC Plant JPM 1 Page 1 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark ,(

Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time: _ _ _ __

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

Comment:

SAT/UNSAT Performance Step: 2 Procedure Step: 4.3.1 Close Scram Air Header isolation valve V-6-175 (RB 23 SE)

Standard: Closes Scram Air Header isolation valve V-6-175 (RB 23 SE) by rotating the valve operator CW until motion stops Cue: Scram Air Header isolation valve V-6-175 is closed Comment:

SAT/UNSAT ILT10-1 NRC PlantJPM 1 Page 2 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Procedure Step: 4.3.2 Open Scram Air Header drain valve V-6-409 (RS 23 SE)

Standard: Opens Scram Air Header drain valve V-6-409 (RS 23 SE) by rotating the valve operator CCW until motion stops Cue:

Scram Air Header drain valve V-6-409 is open and air is heard rushing out the vent

The Control Room notifies you that all control rods indicate full-in Comment:

SAT/UNSAT Performance Step: 4 Procedure Step: 4.3.3.1 When control rods are no longer moving in, then perform the following:

1. Close Scram Air Header drain valve V-6-409 (RS 23 SE)

Standard: Closes Scram Air Header drain valve V-6-409 (RS 23 SE) by rotating the valve operator CW until motion stops Cue: Scram Air Header drain valve V-6-409 is closed Comment:

SAT/UNSAT ILT 10-1 NRC PlantJPM 1 Page 3 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 5 Procedure Step: 4.3.3.2 When control rods are no longer moving in, then perform the following:

2. Open Scram Air Header isolation valve V-6-175 (RS 23 SE)

Standard: Opens Scram Air Header isolation valve V-6-175 (RS 23 SE) by rotating the valve operator CCW until motion stops Cue: Scram Air Header isolation valve V-6-175 is open Comment:

SAT/UNSAT Terminating Cue: The scram air header has been vented and then restored to normal JPM Stop Time: _ _ _ __

ILT 10-1 NRC Plant JPM 1 Page 4 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: ILT 1 NRC Plant JPM 1 Examinee's Name:

Examiner's I\lame:

Date Performed:

Facility Evaluator:

Number of Attempts: ____________

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiner's Signature and Date:

ILT 10-1 NRC Plant JPM 1 Page 5 of 7

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

..IPM Setup

1. Have a copy of EMG-SP21 for the applicant.

ILT 10-1 NRC PlantJPM 1 Page 6 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

1. The plant was at rated power when an electric ATWS occurred Task Cue:

Vent the scram air header lAW EMG-SP21, section 4.3 There will be no manipulations of plant c.ponents.

All mainuplations are to be simulated.

ILT 10-1 NRC Plant JPM 1 Page 7 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 2070501401 Adding Makeup to the Isolation Condensers with the Fire Task

Title:

Protection System Job Performance Measure No.: ILT 10-1 NRC Plant JPM 2 (RO/SRO)

KIA

Reference:

207000 K1.06 (3.3/3.7)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance

--- x -- Actual Performance Classroom - - - - - Simulator - - - - - Plant x Read to the Examinee:

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

Initial Conditions:

1. The plant scrammed due to an inadvertent MSIV isolation.

2. Both the Demineralized Water System and Condensate Transfer System are unavailable.

3. Isolation Condenser shell water levels indicate 7.2'.

4. The Isolation Condenser System is currently in Standby Task Standard: Isolation Condenser A shell water level is rising due to makeup from the Fire Protection System.

Required Materials: Keys to unlock plant valves.

General

References:

1. 307, Isolation Condenser System, revision 112 ILT 10-1 NRC Plant JPM 2 Page 1 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Initiating Cue: Raise Isolation Condenser A shell water level using the Fire Protection System, lAW 307, Isolation Condenser System, starting at step 7.3.3.2.

Time Critical Task: No.

Validation Time: 5 Minutes ILT 10-1 NRC Plant JPM 2 Page 2 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark ~

Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time: _ _ _ __

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

Comment:

SAT/UNSAT Note: The valves in the next steps may be inside a contaminated area. Dress-out and contaminated area entry is not required.

Performance Step: 2 Procedure Step: 7.3.3.2 Close V-11-41, Isolation Condensers Supply Isolation Valve. (Reactor Building 23' East)

Standard: Close V-11-41, Isolation Condensers Supply Isolation Valve by rotating the valve handwheel CWo Cue: V-11-41 is closed.

Comment:

SAT/UNSAT ILT 10-1 NRC Plant JPM 2 Page 3 of 9

Appendix C Job Performance Measure Form ES~C~1 WORKSHEET Performance Information Performance Step: 3 Procedure Step: 7.3.3.3 Close V-11-63, Makeup to Isolation Condenser Telltale Drain Valve. (Reactor Building 23' East)

Standard: Closes V-11-63, Makeup to Isolation Condenser Telltale Drain Valve by rotating the valve handwheel CWo Cue: V-11-63 is closed.

Comment:

SAT/UNSAT Performance Step: 4 Procedure Step: 7.3.3.4 Unlock and open V-9-2099, Fire Protection to Isolation Condenser Cross-Tie Isolation Valve. (Reactor Building 23' East)

Standard: Unlocks and opens V-9-2099, Fire Protection to Isolation Condenser Cross-Tie Isolation Valve, by rotating the valve handwheel CCW.

Cue: V-9-2099 is open.

Comment:

SAT/UNSAT ILT 10-1 NRC Plant JPM 2 Page 4 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 5 Procedure Step: 7.3.3.5 Open V-11-49, Fire Protection to Isolation Condenser Makeup Valve. (Reactor Building 23' East)

Standard: Opens V-11-49, Fire Protection to Isolation Condenser Makeup Valve, by rotating the valve handwheel CCW.

Cue: V-11-49 is open.

Comment:

SAT/UNSAT Performance Step: 6 Procedure Step: 7.3.3.6 Record initial shell level reading (PCS ID LTIG06A) on Attachment 307-15, Level Adjustments to Isolation Condenser.

Standard: Directs Control Room to record initial shell level reading Cue: Initial shell water level is 7.2'.

Comment:

SAT/UNSAT ILT 10-1 NRC Plant JPM 2 Page 5 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 7 Procedure Step: 7.3.3.7 Open V-11-36, Isolation Condenser Makeup Valve. (PaneI5F/6F)

Standard: Directs Control Room to open V-11-36, Isolation Condenser Makeup Valve.

Cue: V-11-36, Isolation Condenser Makeup Valve is open. Water level is rising and the Control Room will continue to monitor water level.

Comment:

SAT/UNSAT Terminating Cue: Isolation Condenser 'A' shell water level is rising due to makeup from the Fire Protection System.

JPM Stop Time: _ _ _ __

ILT 10-1 NRC Plant JPM 2 Page 6 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: ILT 10-1 NRC Plant JPM 2 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts: ____________

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiner's Signature and Date:

ILT 10-1 NRC Plant JPM 2 Page 7 of 9

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

1. Have a copy of Section 7.3.3 marked up to/including Step 7.3.3.1.

ILT 10-1 f\IRC Plant JPM 2 Page 8 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

1. The plant scrammed due to an inadvertent MSIV isolation.

2. Both the Demineralized Water System and Condensate Transfer System are unavailable.

3. Isolation Condenser shell water levels indicate 7.2'.

4. The Isolation Condenser System is currently in Standby.

Task Cue:

Raise Isolation Condenser A shell water level using the Fire Protection System, lAW 307, Isolation Condenser System, starting at step 7.3.3.2.

There will be no manipulations of plant components.

All mainuplations are to be simulated.

ILT 10-1 NRC PlantJPM 2 Page 9 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 3080401413 Operate Service Water Pump 1-2 from Local Shutdown Panel Task

Title:

LSP-1B3 Job Performance Measure No.: ILT 10-1 NRC Plant JPM 3 (RO/SRO)

KIA

Reference:

295016 AA 1.07 (RO 4.2ISRO 4.3)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance - - - - - Actual Performance x Classroom Simulator X* Plant

Simulated In-Plant and Performed on Simulator replica of LSP-1 B3 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 plant was at rated power when an event occurred resulting in a Control Room evacuation.

2. The Remote Shutdown Panel has been activated.

3. 4160 VAC Bus D is energized from EDG-2.

4. 125 VDC is available to USS 1B3.

5. Breaker 1B3P is closed.

6. All Service Water flow has been lost.

7. You have a set of Building Keys and a radio.

Task Standard: LSP-1 B3 has been activated and Service Water Pump 1-2 as been started.

Required Materials: None.

ILT 10-1 NRC Plant..IPM 3 Page 1 of 10

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

References:

1. Procedure 346, Operation of the Remote and Local Shutdown Panels, Revision 17 Initiating Cue: Start Service Water Pump 1-2 lAW Procedure 346, Operation of the Remote and Local Shutdown Panels, Section 9.0.

Time Critical Task: No.

Validation Time: 7 minutes ILT 10-1 NRC PlantJPM 3 Page 2 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark -/

Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time: _ _ _ __

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

Comment:

SAT/UNSAT Performance Step: 2 Procedure Step: 9.1 and 9.2 Verifies Prerequisites and Precautions and Limitations Standard: Verifies Prerequisites and Precautions and Limitations Note: Prerequisites are met from the Initial Conditions. Applicant may review Section 4.0, Precautions and Limitations.

Comment:

SAT/UNSAT ILT 10-1 I\IRC Plant.JPM 3 Page 3 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Procedure Step: 9.3.1 Establish communication between the LSP and the Remote Shutdown Panel.

Standard: Establish communication between the LSP and the Remote Shutdown Panel.

Cue: Communications have been established.

Comment:

SAT/UNSAT Performance Step: 4 Procedure Step: 9.3.2 Place Bypass Switch on Service Water Pump 1-2 breaker at USS 1B3 in BYPASS.

Standard: Places Bypass Switch on Service Water Pump 1-2 breaker at USS 1B3 in BYPASS.

Comment:

SAT/UNSAT ILT 10-1 NRC PlantJPM 3 Page 4 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 5 Procedure Step: 9.3.3 Rotate Keylock Control Transfer Switch to ALTERNATE.

Standard: Rotates Keylock Control Transfer Switch to ALTERNATE.

Comment:

SAT/UNSAT Performance Step: 6 Procedure Step: 9.3.4 Verify LSP-1 83 status lights are lit within 5 seconds.

Standard: Verifies LSP-1 83 status lights are lit within 5 seconds.

Note: The red CLOSED indication will be lit for 8KR 183M and the green OFF light will be lit for Service Water Pump 1-2.

Comment:

SAT/UNSAT ILT 10-1 NRC Plant JPM 3 Page 5 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 7 Procedure Step: 9.3.5 Confirm closed Main Breaker 1B3M at LSP-1 B3.

Standard: Confirms closed Main Breaker 1B3M at LSP-1 B3.

Note: Verifies the red CLOSED indication is lit for BKR 1B3M.

Comment:

SAT/UNSAT Performance Step: 8 Procedure Step: 9.3.6 Confirm closed Feeder Breaker to MCC 1B32 at USS 1B3.

Standard: Confirms closed Feeder Breaker to MCC 1B32 at USS 1B3.

CUE: If requested by an EO to verify the breaker position, report that feeder breaker MCC 1B32 is CLOSED on USS 1B3.

Comment:

SAT/UNSAT ILT 10-1 !\IRC Plant JPM 3 Page 6 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 9 Procedure Step: 9.3.7 Start Service Water Pump 1-2 by placing its switch in the START position.

Standard: Starts Service Water Pump 1-2 by placing its switch in the START position. Observes the red START light illuminate and the green STOP light extinguish. Reports to the Remote Shutdown Panel that Service Water Pump 1-2 is running.

Comment:

SAT/UNSAT Terminating Cue: LSP-183 has been activated and Service Water Pump 1-2 has been started.

JPM Stop Time: _ _ _ __

ILT 10-1 NRC Plant JPM 3 Page 7 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: ILT 10-1 NRC Plant JPM 3 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiner's Signature and Date:

ILT 10-1 NRC Plant JPM 3 Page 8 of 10

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

1. Reset to a shutdown IC (or IC-115 and manually scram the reactor).

2. Ensure Service Water Pump 1-2 is NOT running.

3. Silence Horns.

4. Have a copy of procedure 346 sections 4.0 and 9.0 for the applicant.

ILT 10-1 NRC Plant...IPM 3 Page 9 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

1. The plant was at rated power when an event occurred resulting in a Control Room evacuation.

2. The Remote Shutdown Panel has been activated.

3. 4160 VAC Bus D is energized from EDG-2.

4. 125 VDC is available to USS 1B3.

5. Breaker 1B3P is closed.

6. All Service Water flow has been lost.

7. You have a set of Building Keys and a radio.

Initiating Cue:

Start Service Water Pump 1-2 lAW Procedure 346, Operation of the Remote and Local Shutdown Panels, Section 9.0.

ILT 10-1 NRC PlantJPM 3 Page 10 of 10

ILT 10-1 NRG Scenario 2 (NEW)

ScenarIo Outline Facility: Oyster Creek Scenario No.: g Op Test No.: 10-1 NRC Examiners: Operators:

Initial Conditions:

97% power

Main Generator voltage control is in Manual Turnover:

Place the amplidyne in automatic service lAW 336.1, section 8

Raise reactor power to 100% with recirculation flow I Event No. Malt. No. Event Type" Event Description 1 NA N BOP Return the Amplidyne to service lAW 336.1.

Raise reactor power to 100% with recirculation flow 2 NA R ATC (REMA).

ICH- Respond to RPV High Pressure Instrument RE15 to 3 TS SRO NSS026A Isolation Condenser Initiation Logic Failing High.

MAL- I ATC 4 NIS021B Respond to APRM 2 failing INOP.

TS SRO MAL-5 MSSOO5A C Respond to trip of Steam Packing Exhauster 1.

C ATC Respond to the E EMRV lifting leading the crew to a MAL-6 BOP NSS025E TS manual scram.

SRO CAEP 7 ATWS M Crew Respond to an Electric ATWS.

PMP SLCOO1A 8 C Crew Respond to a Standby Liquid Control Pump shaft break.

PMp*

SLCOO2A

(N)onnal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor TranSient, (TS) Tech Specs ILT 10-1 I\JRG Scenario 2 Page 1 of 23

ILT 10-1 NRC Scenario 2 (NEW)

Simulator Summary Event Event Summary 1 The BOP will return the amplidyne to automatic service lAW 336.1.

The BOP will place the control switch in TEST, zero the amplidyne voltmeter, then place the control switch to ON. (BOP: Normal Evolution) 2 The ATC will raise reactor power to rated power (100%) with recirculation flow using the Master Recirc Speed Controller. (ATC:

Reactivity Manipulation) 3 RPV high pressure instrument RE15A to Isolation Condenser Initiation Logic fails high. No Isolation Condenser initiation will occur from this failure. The SRO will review and apply Tech Spec Table 3.1.1 part C.1. (SRO: Tech Specs) 4 The ATC will respond to an APRM HI-HI/INOP alarm and report that APRM 2 has failed INOP with a Y2 scram on RPS 1. The ATC will bypass APRM 2 lAW procedure 403 and reset the V2 scram. The SRO will review and apply Tech Spec Table 3.1.1. (ATC: Instrument Malfunction; SRO: Tech Specs) 5 The BOP will respond to the failure of the in-service steam packing exhauster. The BOP will start the standby Exhauster and throttle open its discharge valve to maintain the correct vacuum. (BOP:

Component Malfunction) 6 The ATC and BOP will respond to the E EMRV lifting lAW ABN-40, Stuck Open EMRV. The ATC will take manual control of the master feedwater controller. The BOP will cycle the E EMRV then disable it.

The ATC will return the master feedwater controller to automatic operation and insert a manual reactor scram. The SRO will review Tech Specs 3.4 for ADS operability and TS 3.5.A for Torus Temperature limits. (ATC: Component Malfunction; BOP:

Component Malfunction; SRO: Tech Specs) 7 The Crew will diagnose an electric ATWS and the SRO will direct entry into RPV Control- with ATWS EOP. The ATC will perform actions to insert control rods and the BOP will perform actions to control Torus water temperature and RPV water level. (Major Evolution) (PRA)

ILT 10-1 NRC Scenario 2 Page 2 of 23

ILT 10-1 NRC Scenario 2 (NEW) 8 Due to the Torus water temperature heating up from the E EMRV stuck open, Standby Liquid Control (SLC) injection will be directed.

The first SLC pump started will have a broken shaft and the Applicant will start the second SLC pump. (Component Failure After EOP)

Critical With reactor power> 2% during an ATWS, terminate and prevent Task 1 injection into the RPV to intentionally lower RPV water level which will lower reactor power.

Critical Crew directs the Reactor Building EO to vent the scram air header.

Task 2 (The Lead Examiner will direct the Booth to vent the scram air header at their discretion).

ES-301-4 Target Quantitative Actual Event Attributes Attributes Number(s)

1. Total malfunctions (5-8) 6 3,4,5,6,7,8

2. Malfunctions after EOP entry (1-2) 1 8

3. Abnormal events (2-4) 2 4,6

4. Major transients (1-2) 1 7

5. EOPs entered/requiring substantive 2 7 actions (1-2)

6. EOP contingencies requiring substantive 1 7 actions (O-2)

7. Critical tasks (2-3) 2 7 ILT 10-1 NRC Scenario 2 Page 3 of 23

ILT 10-1 NRC Scenario 2 (NEW)

Op-Test No.: 10-1 NRC Scenario No.: NRC Sim 2 Event No.: 1 Event

Description:

Return the Amglidyne to service lAW 336.1.

Initiation: Following shift turnover Cues: As directed by the SRO following shift turnover Time Position Applicant's Actions or Behavior SRO

Directs the BOP to shift from manual to automatic voltage regulation lAW 336.1, section 8 BOP

Shifts from manual to automatic voltage regulation lAW 336.1 , section 8 a Simultaneously places the AMPLIDYNE CONTROL 43CS switch in TEST and observes 4160 VAC Bus 1A ammeter for deflection a Confirms amplidyne motor start as indicated by ammeter deflection on Bus 1A a Directs EO to verify the amplidyne motor is running [ROLE PLAY]

ROLE PLAY:As the EO at the amplidyne, report a good start on the amplidyne motor.

a Zero the amplidyne voltmeter a Press and hold the AMPLIDYNE VOLTS PUSH FOR LOW RANGE pushbutton a Observe the AMPLIDYNE voltmeter for a zero or center-scale reading a If the needle is deflected, then adjust using the AMPLIDUNE ADJUST rheostat to reach center-scale a Release the AMPLIDYNE VOLTS PUSH FOR LOW RANGE pushbutton a Verify the AMPLIDYNE voltmeter reads zero or center-scale a Repeat if required to obtain zero or center-scale a Place the AMPLIDYNE CONTROL 43CS switch in ON ILT 10-1 NRC Scenario 2 Page 4 of 23

ILT 10~1 NRC Scenario 2 (NEW) o Removes VOLTAGE CONTROL IN MANUAL operator aids o May verify Terminal Voltage or Excitation are within the requirements of 336.1, section 5.0, on the PJM website.

[FLOOR ROLE PLAY]

FLOOR ROLE PLAY: If the applicant requests (or attempts to verify on the PJM website) that Terminal Voltage or MG Excitation (VARS) are within the limits of section 5.0, inform them that the requirements of section 5.0 are satisfactory.

o Verifies generator terminal voltage 23.3 to 24.7 KV o maintains a slight BUCK reading by adjusting EXCITER FIELD RHEOSTAT CONTROL 70M switch as needed, which ensures the Main Field will pick up control should the AMPLIDYNE trip o Reports the amplidyne is in automatic voltage control o May notify the Power team when in auto Terminus: The amplidyne is in automatic voltage control Notes/Comments ILT 1O~ 1 NRC Scenario 2 Page 5 of 23

ILT 10-1 NRC Scenario 2 (NEW)

Op-Test No.: 10-1 NRC Scenario No.: NRC Sim 2 Event No.: g Event

Description:

Raise reactor j20wer to rated lAW the ReMA Initiation: After the amplidyne is placed in automatic voltage control, or as directed by the Lead Examiner Cues: As directed by the SRO Time Position Applicant's Actions or Behavior SRO

Approves the ReMA and provides to the ATC

Directs the ATC to raise power to rated lAW the ReMA

Acts as the reactivity Manager

Provides a reactivity brief

May notify the Power team when at rated power ROLE PLAY: If Reactor Engineering is contacted inferring about the rate of power ascension, inform them there is no limit on the rate of power ascension.

ATC

Raises power lAW the ReMA o May review 202.1 , section 5.0, Raising Power o Rotates the MASTER RECIRC SPEED CONTROLLER manual knob CW o Monitors power, level, pressure o Reports to SRO when rated power is reached

Provides second check for the reactivity manipulation Terminus: Reactor power is at rated Notes/Comments ILT 10-1 NRC Scenario 2 Page 6 of 23

ILT 10-1 NRC Scenario 2 (NEW)

Op-Test No.: 10-1 NRC Scenario No.: NRC Sim 2 Event No.: ~

Event

Description:

Res~ond to RPV High Pressure Instrument RE15 to Isolation Condenser Initiation Logic Failing High !Trigger 1]

Initiation: Reactor power is at rated, or as directed by the Lead Examiner Cues: Annunciator C1a, LOGIC TRAIN 1 ACTUATED; E1a, ACTUATE A Time Position Applicant's Actions or Behavior BOP

Responds to Annunciator C1a, LOGIC TRAIN 1 ACTUATED; E1 a, ACTUATE A

Reports that Isolation Condensers did not initiate and no Recirc Pumps tripped

Investigates cause and discovers RE15A, RPV High Pressure Instrument to Isolation Condenser Initiation Logic Failed High SRO

Reviews Tech Specs Table 3.1.1, Section C.1

Determines that there is one operable and one tripped Trip Systems and that no further TS actions are required.

Notifies SMIWWM for investigation and repair Terminus: The SRO has reviewed and applied Tech Specs.

Notes/Comments ILT 10-1 NRC Scenario 2 Page 7 of 23

IlT 10-1 NRC Scenario 2 (NEW)

Op-Test No.: 10-1 NRC Scenario No.: NRC Sim 2 Event No.: .4 Event

Description:

ResQond to APRM 2 failing INOP rrrigger 3].

Initiation: The SRO has reviewed and applied Tech Specs, or as directed by the lead Examiner Cues: Annunciator G1f, APRM HI-HI/INOP; G1d, CHANNEL I; G1C, SCRAM CONTACTOR OPEN, APRM 2 DN SCl OR INOP light is lit Time Position Applicant's Actions or Behavior ATC

Responds to annunciators G2f, APRM HI-HI/INOP; G2d, CHANNEL II; G1C, SCRAM CONTACTOR OPEN and APRM 2 DN SCl OR INOP light lit 0 Reports Y2 scram RPS system 1 0 Reports APRM 2 DN SCl OR INOP light is ON and other APRMs indicate normal

Bypasses APRM 2 by placing APRM BYPASS in CH 2 position

Resets Y2 scram by depressing SCRAM SYSTEM RESET pushbutton

Reports APRM bypassed and Y2 scram reset I

Completes Attachment 403-2 BOP

Makes a plant announcement for the Y2 scram

Checks APRM 2 on Panel 3R and reports its INOP light is lit SRO

Directs bypassing APRM 2 lAW procedure 403 and resetting Y2 scram

May request Attachment 403-2 updated

May review TS 3.1 (no action required)

Notifies SMIWWM for APRM 2 repair BOOTH: AFTER the crew has reset the Y2 scram on RPS 1, insert ATWS.CAE Terminus: APRM 2 is bypassed and Y2 scram reset IlT10-1 NRC Scenario 2 Page 8 of 23

ILT 10-1 NRC Scenario 2 (NEW)

Notes/Comments ILT10-1 NRC Scenario 2 Page 9 of 23

ILT 10-1 NRC Scenario 2 (NEW)

Op-Test No.: 10-1 NRC Scenario No.: NRC Sim 2 Event No.: § Event

Description:

Resgond to trig of Steam Packing Exhauster 1 rrrigger 5]

Initiation: APRM 2 is bypassed and Y2 scram reset, or as directed by the Lead Examiner Cues: Annunciator Q8c, EXHAUSTER TRIP Time Position Applicant's Actions or Behavior BOP

Responds to annunciator Q8c, EXHAUSTER TRIP o Reports Exhauster Blower 1 has tripped o Verifies gland steam pressure o Closes Exhauster Blower 1 Valve V-7-38 o Starts Exhauster Blower 2 and verifies the red light on o Throttles open Exhauster Valve 2 V-7-39 o Adjusts Exhauster Valve 2 V-7-39 to maintain GLAND STM HEADER VACUUM at 15 - 17.5 inches of water o Reports Exhauster Blower 2 is in service

Directs EO to investigate the trip of Exhauster Blower 1 [Role Play]

As the EO sent to investigate the trip of Exhauster Blower 1, report there ROLE PLAY are indications of an overload on the breaker SRO

Notifies SMIWWM for repair

May direct condenser vacuum as key parameter Terminus: Exhauster Blower 2 has been started and proper gland steam header vacuum is established ILT 10-1 NRC Scenario 2 Page 10 of 23

ILT 10-1 NRC Scenario 2 (NEW)

Notes/Comments ILT 10-1 NRC Scenario 2 Page 11 of 23

ILT 10-1 NRC Scenario 2 (NEW)

Op-Test No.: 10-1 NRC Scenario No.: NRC Sim 2 Event !\lo.: § Event

Description:

Resgond to a stuck ogen EIVIRV fTrigger 7]

Initiation: Exhauster Blower 2 has been started and proper gland steam header vacuum is established, or as directed by the Lead Examiner Cues: Annunciator B4g, SV/EMRV NOT CLOSED; EMRV NR1 OBE tailpipe temperature rising; Torus water temperature rising; EMRV NR10BE indicates in the VALVE OPEN REGION Time Position Applicant's Actions or Behavior BOP

Responds to Annunciator B4g, SV/EMRV NOT CLOSED o Checks RPV pressure, ADS and determines SV/EMRV status o Determines an EMRV is open (NR1 OBE)

Performs ABN-40 actions o Verifies EMRV open conditions o Dispatches an EO to read EMRV tailpipe temperatures locally [ROLE PLAY]

ROLE PLAY: When directed as the EO to read EMRV tailpipe temperatures locally, report the following: 'E' EMRV tailpipe indicates 330 of and steady, All other EMRV tailpipe temperatures indicate normal.

o Places the AUTO DEPRESS VALVE NR10BE switch in OFF position o Determines EMRV still open o Cycles the AUTO DEPRESS VALVE NR10BE switch from OFF to MAN to OFF o Determines EMRV still open o Cycles the AUTO DEPRESS VALVE NR10BE switch from OFF to MAN to OFF 3-5 times o Determines EMRV still open o Places the EMRV NORMAUDISABLE keylock switch for EMRV NR1 OBE in DISABLE (rear of 1F/2F) o Determines EMRV still open SRO

Directs entry into ABN-40, Stuck Open EMRV ILT 10-1 NRC Scenario 2 Page 12 of 23

ILT 10-1 NRC Scenario 2 (NEW) o With the EMRV not closed, directs the ATe to manually scram the reactor lAW ABN-1 (An ATWS will occur leading to the next Event)

ATC

Performs ABN-40 actions o Places Feedwater Level Control in manual by depressing the AUTO/MAN pushbutton on the MASTER FEEDWATER CONTROLLER

Verifies the red manual LED is illuminated

ADJUST MASTER FEEDWATER CONTROLLER as required to control RPV water level within the normal band of 155-165" T AF o Places Feedwater Level Control in the AUTO mode as follows:

Selects the P display digital readout on the MASTER FEEDWATER LEVEL CONTROLLER using the CHNG DISP button

Selects the S display on the MASTER FEEDWATER LEVEL CONTROLLER

Raise or lower the S display digital readout to match the P display digital readout on the MASTER FEEDWATER LEVEL CONTROLLER

When the S display and P display digital readouts are equal, then places the MASTER FEEDWATER LEVEL CONTROLLER in AUTO by depressing the AUTO/MAN pushbutton.

Verifies the green AUTO light is illuminated

Monitors RPV water level and feedwater flow

Maintains Reactor level at 160 inches TAF or as directed by the US by adjusting the MASTER FEEDWATER LEVEL CONTROLLER setpoint

Manually scrams the reactor lAW ABI'J-1 o Depresses both MANUAL SCRAM pushbuttons o Places the REACTOR MODE SELECTOR switch in SHUTDOWN o Reports there is a failure to scram

Initiates ARI

Places ROPS in BYPASS

Places recirculation flow to minimum

Reports Immediate Failure to Scram Actions are Complete ILT 10-1 NRC Scenario 2 Page 13 of 23

ILT 10-1 NRC Scenario 2 (NEW) o Inserts SRMs o Inserts IRMs Terminus: The Crew has determined that EMRV NR1 08E could not be closed and have inserted a manual scram, and have recognized ATWS conditions Notes/Comments ILT 10-1 NRC Scenario 2 Page 14 of 23

ILT 10-1 NRC Scenario 2 (NEW)

Op-Test No.: 10-1 NRC Scenario No.: NRC Sim 2 Event No.: 7/8 Event

Description:

Respond to an ATWS with reactor power> 2%: Failure of SLC Pump Initiation: The Crew has determined that EMRV NR1 08E could not be closed and have inserted a manual scram, and have recognized ATWS conditions Cues: The reactor has failed to scram and is in an electrical ATWS condition Time Position Applicant's Actions or Behavior ATC

Reports reactor power

Determines the ATWS is electric

Performs SP-22 o Starts the selected SLC Pump by placing the STANDBY LIQUID CONTROL Keylock in either the FIRE SYS 1 or FIRE SYS 2 position o Verifies the following:

PUMP ON light for selected system illuminated

SQUIBS light for selected system illuminated

PUMP DISCH PRESS greater than Rx pressure

FLOW ON Alarm annunciates

SQUIB VALVE OPEN Alarm annunciates

Recognizes/reports failure of the first SLC Pump and starts the second pump

Performs SP-21 to insert control rods o Determines electrical ATWS o Vent the Scram Air header (Success Path)

Directs the EO to vent the scram air header [ROLE PLAY]

ROLE PLAY: As the eo directed to vent the scram air header, acknowledge the request. Venting the header is the success path to be performed at a later time.

CRITICAL TASK 2 ILT 10-1 NRC Scenario 2 Page 15 of 23

ILT 10-1 NRC Scenario 2 (NEW)

Places the ROD WORTH MINIMIZER keylock in BYPASS

Closes CRD DRIVE WATER PRESSURE CONTROL NC18 to maximize CRD drive water differential pressure

Inserts Control Rods as directed by the US [BOOTH]

BOOTH: After the ATC has inserted a few control rods, fail the CRD FCV closed: insert MAL-CRD001 A to O.

o De-energize the Scram Solenoids (Not Successful)

With the MSIVs open:

Places the following Sub channel Test Keylocks in the TRIP position:

RPS Sub Channel 1A Keylock

RPS Sub Channel 1B Keylock

RPS Sub Channel 2A Keylock

RPS Sub Channel2B Keylock

When the control rods are no longer moving in, then places the RPS Channell and II Sub channel Test Keylocks in the NORMAL position o Open Individual Scram Test Switches (Not Successful)

Confirms all available CRD pumps are running

Confirms open SDV vent and drain valves

Obtains Key for 6XR Rod Scram Test Panel

Opens Rod Scram Test Panel

Individually OPEN the scram test toggle switch for a control rod not inserted as follows:

Attempt to insert Cram Array Control Rods first

Then insert any other Control Rod as directed by the US

Monitors Reactor Building airborne radiation levels

When the control rod stops moving, then CLOSE the scram test toggle switch

Repeat to insert other control rods

Reports when control rods start moving inward (from scram air header venting)

Reports all control rods in ILT 10-1 NRC Scenario 2 Page 16 of 23

ILT 10-1 NRC Scenario 2 (NEW)

SRO

Directs entry into RPV Control - With ATWS EOP o Confirms ARI initiated o Directs ROPS bypassed o Directs all Recirculation Pumps tripped o Directs SLC initiated lAW SP-22, Initiating the Liquid Poison System o Directs ATC to insert control rods lAW SP-21 , Alternate Insertion of Control Rods o Directs SP-1, Confirmation of Automatic Initiation and Isolations o Di rects ADS bypassed o Directs SP-16, Bypassing MSIV Lo-Lo Level Isolation Interlocks and the RBCCW Interlocks o Waits until MSIV isolations are bypassed, then directs terminate and prevent RPV injection lAW SP-17 CRITICAL TASK 1 o Directs RPV water level below -20" to 30" lAW SP-19, Feedwater/Condensate and CRD Operation [BOOTH]

Enters Primary Containment Control EOP on Torus high water temperature (95 OF) o Directs Torus Cooling lAW Support Procedure 25

Enters RPV Control - No ATWS EOP when all control rods are inserted o Directs RPV water level 138" -- 175" using SP-2 (FW)

BOP

Trips all Recirculation Pumps when directed with the DRIVE MOTOR switches to STOP

Performs SP-1

Places ADS TIMERS to BYPASS

Performs SP-16 o Obtains four (4) bypass plugs o Opens the EOP BYPASS PLUGS panel in the rear of Panel6R

INSERT a bypass plug in position BP1 ILT 10-1 NRC Scenario 2 Page 17 of 23

ILT 10-1 NRC Scenario 2 (NEW)

INSERT a bypass plug in position BP2 o Opens the EOP BYPASS PLUGS panel in the rear of Panel7R

INSERT a bypass plug in position BP1

INSERT a bypass plug in position BP2 o Places the ISOL SIGNAL BYPASS V-6-395 switch in the BYPASS position o Informs the Unit Supervisor that the MSIV LO-LO Level Isolation Interlock has been bypassed o Verifies that the RBCCW System is not isolated due to hjgh Drywell pressure/low RPV water level conditions o Opens the EOP BYPASS PLUGS panel in the rear of Panel2R

Removes the bypass plug from position BP1

Removes the bypass plug from position BP2

Performs SP-17 o Terminates and prevents the Core Spray System injection into the RPV by performing the following:

Presses the OVERRIDE switches for all the sensors that are lit

Presses all ACTUATED switches, whether lit or unlit

Confirms Core Spray Parallel Isolation Valves closed

Confirms Core Spray Booster Pumps tripped

Confirms Core Spray Main Pumps that are not being used to provide makeup water to the torus per SP37 are in the PULL-TO-LOCK position o Terminates and prevents Condensate and Feedwater injection by performing the following:

Trips all operating Feedwater Pumps

Confirms only one Condensate Pump running

Places all individual FRV Controllers in MAN position

Closes all Feedwater Regulating Valves

Closes the Low Flow Valves o Reports RPV injection has been terminated and prevented

Monitors RPV water level and controls Feedwater to maintain desired band -20" to 20" lAW SP-19 o Confirms only one Condensate Pump and only one Feedwater Pump operating o Controls RPV Water level using the following:

Feedwater Regulating Valves ILT 10-1 NRC Scenario 2 Page 18 of 23

ILT 10-1 NRC Scenario 2 (NEW)

Feed Regulating Valve Block Valves

Feedwater Low Flow Valves

Heater Bank Outlet Isolation Valves

Feedwater and Condensate Pumps o Reports RPV water level in band

Performs SP-25 when directed (Torus cooling) o Confirm the SYSTEM MODE SELECT switch is in the TORUS COOLING position o Start an ESW Pump o Place and hold the System Pump Start Permissive Keylock for the selected pump in the appropriate position o Start the selected Containment Spray Pump using its control switch Terminus: Control rods have been fully inserted and RPV water level is rising towards the prescribed band as directed in the RPV Control- No ATWS EOP Notes/Comments ILT 10-1 NRC Scenario 2 Page 19 of 23

ILT 10-1 NRC Scenario 2 (NEW)

Procedures Used Event Procedure 1

None 2

None 3

TS Table 3.1.1 4

RAP-G1f

RAP-G2d

RAP-G1c

403 5

RAP-Q8c 6

RAP-B4g

ABN-40

ABN-1 7

RPV Control - With ATWS EOP

SP-16

SP-17

SP-21

SP-1

SP-19 8

SP-22

SP-25

RPV Control- No ATWS EOP

Primary Containment Control EOP ILT 10-1 NRC Scenario 2 Page 20 of 23

ILT 10-1 NRC Scenario 2 (NEW)

Simulator Setup

1. Reset to IC-115

2. Lower reactor power to 97% with recirc flow

3. Remove the Amplidyne from service lAW 336.1, section 7

4. Have copy of 336.1 (complete procedure) for applicants; mark step 8.1.1 and 8.1.2 complete

5. Have a copy of REMA NRC Sim2 for students

6. Have a blank copy of Attachment 403-2 in the 403 binder Event Trigger Malfunction 1 NA 2 NA 3 T1 -t ICH-NSS087 A to 1200 psig

Causes RE15A to fail upscale 4 T3 -t MAL-I\IIS021 B

APRM 2 fails INOP 5 T5-t MAL-MSS005A

Trips Steam Packing Blower 1 6 Trigger 7-t MAL-NSS025E to 100%

This inserts a 100% leak on EMRV NR108E

This leak will not be stopped 7 WAIT: SEE Activate ATWS.CAE file WHEN EVENT #4-t DIRECTED BY EVENT #4

This inserts an electric ATWS, not to be inserted until after the crew resets the Y2 scram from Event #4.

ILT 10-1 NRC Scenario 2 Page 21 of 23

ILT 10-1 NRC Scenario 2 (NEW) 8 PRESETS -+ PMP-SLC001A (SLC Pump 1)

PMP-SLC002A (SLC Pump 2)

This inserts a shaft break on each SLC Pump PRESETS -+ Insert the following Event Trigger (1) and Command (2) on Trigger 9:

1) hwx030266b.eq.1

2) DMF PMP-SLCOO2A

This will DELETE the shaft break on SLC Pump 2 if the SLC system 1 keylock is placed in FIRE SYS 1.

Insert the following Event Trigger (1) and PRESETS -+ Command (2) on Trigger 11 :

1) hwx030266d.eq.1

2) DMF PMP-SLC001 A

This will DELETE the shaft break on SLC Pump 1 if the SLC system 2 keylock is placed in FIRE SYS 2.

Trigger 13-+ LOA-CAS021 to 0

This closes the scram air header air isolation valve V-6-175 LOA-CAS022 to 1

This opens the scram air header vent valve to vent the header ILT 10-1 NRC Scenario 2 Page 22 of 23

ILT 10-1 NRC Scenario 2 (NEW)

Shift Turnover Current plant conditions:

97% power

Main Generator voltage control is in Manual Shift Activities:

Place the amplidyne in automatic service lAW 336.1, section 8, starting on step 8.1.3

Raise reactor power to 100% with recirculation flow ILT 10-1 NRC Scenario 2 Page 23 of 23

ILT 10-1 NRC Scenario 3 (NEW)

Scenario Outline Facility: Oyster Creek Scenario No.: ~ Op Test No.: 1()"1 NRC Examiners: Operators:

Initial Conditions:

75% power

TBCCW Pump 2 is tagged out of service Turnover:

Lower power to 70% using recirculation flow lAW 1001.22-3, Core Maneuvering Daily Instruction Sheet

Backwash the Main Condenser Half B South Ir; ..... No. Event Type* Event Description 1 NA R ATC Lower reactor power to 70% using recirculation flow 2 NA N BOP Continue backwashing Main Condenser Half B South BKR- C ATC 3 CRDOO2 Respond to a CRD Pump A trip TS SRO MAL-4 TCS010 I BOP Respond to the EPR setpoint failing low SWI TBS027C C BOP 5 Respond to a trip of Control Room Vent Fan B ANN-L4f TS SRO MAL- I ATC Respond to a variable leg leak in the A and C GEMAC 6 NSS012E TS SRO RPV level indicators ID13A and ID13C BKR-7 CRDOO1 M Crew Respond to a loss of all CRD Flow MAL-8 NSS016A M Crew Respond to a Safety Valve lifting post scram MAL- Respond to a trip of the operating Containment Spray 9 CNS004A* C Crew 0 Pump

(N)ormal, (R)eactivity, (I}nstrument, (C)omponent, (M)ajor Transient, (TS) Tech Specs ILT 10-1 NRC Scenario 3 Page 1 of 28

ILT 10-1 NRC Scenario 3 (NEW)

Simulator Summary Event Event Summary 1 The ATC will lower reactor power to approximately 70% with recirculation flow using the Master Recirc Speed Controller. (ATC:

Reactivity Manipulation) 2 The BOP will backwash condenser B South lAW procedure 323.6, Backwashing Condensers. This will require several switch manipulations by the BOP. (BOP: Normal Evolution) 3 The ATC will respond to a trip of CRO Pump A lAW RAP H-1-c. The ATC will start CRO Pump B. The SRO will review and apply Tech Spec 3.4.0.2. (ATC: Component Malfunction; SRO: Tech Specs) 4 The BOP will respond to the EPR setpoint failing low (indicating 890 psig) lAW ABN-9, Electric Pressure Regulator Malfunction. The BOP will transfer RPV pressure control to the MPR and secure power to the EPA. The BOP will then raise RPV pressure as directed by the SRO. (BOP: Instrument Malfunction)

S The Control Room HVAC Fan B will trip. The SRO will direct the BOP to place Control Room HVAC System A in service lAW 331.1, Control Room and Old Cable Spreading Room Heating, Ventilation, and Air Conditioning System. The SRO will apply Tech Spec 3.17.B. (BOP:

Component Malfunction; SRO: Tech Specs) 6 The ATC will diagnose a rising RPV water level. Indications of actual RPV water level will rise on Panel4F and Panel SF/6F Yarway indications. The ATC will perform actions to stabilize RPV water level lAW ABN-17, Feedwater System Abnormal Conditions. The ATC will take manual control of RPV water level and swap Feedwater Level Control to the alternate water level instrument 1013B. The increased Primary Containment leakage will result in a rise in unidentified leak rate and the SRO will review and apply Tech Spec 3.3.0.2. (ATC:

Instrument Malfunction; SRO: Tech Specs) 7 CRO Pump B will trip on overload and the Crew will respond to a loss of all CRO flow lAW RAP H-2-c. Upon receipt of two HCU accumulator alarms, the Crew will manually scram the reactor perform post scram actions. (Major Evolution) (PRA) 8 Post scram, the crew will respond to a Safety Valve lifting. This will result in rising drywell pressure and temperature requiring Orywell Sprays lAW the Primary Containment Control EOP. (Major Evolution)

ILT 10-1 NRC Scenario 3 Page 2 of 28

ILT 10-1 NRC Scenario 3 (NEW) 9 When initiating Containment Spray lAW the Primary Containment Control EOP, the Containment Spray pump in the system the Crew starts will trip after 30 seconds. The Crew must initiate containment spray using an alternate Containment Spray Pump. (Component Failure After EOP)

Critical The Crew must manually scram the reactor following a loss of all CRD Task 1 pumps. With no CRD flow at high power, damage to the CRD drive mechanisms will occur potentially inhibiting the ability to successfully scram.

Critical When Drywell or Torus pressure exceeds 12 psig, OR before Drywell Task 2 bulk temperature is determined it cannot be maintained below 281°F, spray the drywell lAW SP-29, Initiation of the Containment Spray System for Drywell Sprays.

ES-301-4 Target Quantitative Actual Event Attributes Attributes Number(s}

1. Total malfunctions (5-8) 7 3,4,5,6, 7, 8,9

2. Malfunctions after EOP entry (1-2) 2 8,9

3. Abnormal events (2-4) 2 4,6

4. Major transients (1-2) 2 7,8

5. EOPs entered/requiring substantive 1 8 actions (1-2)

6. EOP contingencies requiring substantive 0 N/A actions (0-2)

7. Critical tasks (2-3) 2 7,9 ILT 10-1 NRC Scenario 3 Page 3 of 28

ILT 10-1 NRC Scenario 3 (NEW)

Op-Test No.: 10-1 NRC Scenario No.: NRC Sim 3 Event No.: 1 Event

Description:

Lower reactor Qower to 70% using recirculation flow Initiation: Following srlift turnover Cues: As directed by the SRO following shift turnover Time Position Applicant's Actions or Behavior SRO

Approves the ReMA and provides to the ATC

Directs the ATC to lower power to 95% lAW the Core Maneuvering Daily Instruction Sheet

Acts as the reactivity Manager

Provides a reactivity brief

May notify the Power team when at 95% power ATC

Lowers power lAW the Core Maneuvering Daily Instruction Sheet o May review 202.1, section 6.0, Power Reductions o Rotates the MASTER RECIRC SPEED CONTROLLER manual knob CW o Monitors power, level, pressure o Reports to SRO when rated power is reached BOP

Provides second check for the reactivity manipulation Terminus: Reactor power is approximately 70%

Notes/Comments ILT 10-1 NRC Scenario 3 Page 4 of 28

ILT 10-1 NRC Scenario 3 (NEW)

Op-Test No.: 10-1 NRC Scenario No.: NRC Sim 3 Event No.: g Event

Description:

Continue backwashi09 Main Condenser Half B South Initiation: Reactor power is approximately 70%, or as directed by the Lead Examiner Cues: As directed by the SRO Time Position Applicant's Actions or Behavior SRO

Directs BOP to continue the main condenser backwash lAW procedure 323.6, starting at step 5.1.6.1 BOP

Performs backwash of condenser half B South lAW procedure 323.6, starting at step 5.1 .6.1 o Verifies the following:

All condenser valves are in the normal position

The inlet & outlet valves for each condenser half are open

The backwash valves and the cross connect valves for each condenser are closed

May verify the EO is aware of which valves will be operated [ROLE PLAY]

o Places the COND B SOUTH BACKWASH CONTROL switch to BACKWASH o After about 10 seconds, places the COND B SOUTH CIRC WATER INLET & OUTLET switch to CLOSE o Verifies the following:

V-3-15, COND B SOUTH CIRC WATER INLET valve closed

V-3-30, COND B SOUTH CIRC WATER OUTLET valve closed

V-3-21, COND B SOUTH BACKWASH CONTROL valve open

V-3-25, COND B CROSS CONNECT valve open

V-3-29, COI\ID B NORTH CIRC WATER OUTLET valve closed

V-3-14, COND B NORTH CIRC WATER INLET valve ILT 10-1 NRC Scenario 3 Page 5 of 28

ILT 10-1 NRC Scenario 3 (NEW) open

V-3-20, COND B NORTH BACKWASH CONTROL valve closed o Backwashes for about 3-S minutes o Monitors the following during backwash:

Condenser Hotwell Level

Turbine Exhaust Hood Temperature

Condenser Vacuum o Places the COND B SOUTH CIRC WATER INLET &

OUTLET switch to OPEN o After about 10 seconds, places the COND B SOUTH BACKWASH CONTROL switch to CLOSE o Verifies the following:

V-3-1S, COND B SOUTH CIRC WATER INLET valve open

V-3-30, COND B SOUTH CIRC WATER OUTLET valve open

V-3-21, COND B SOUTH BACKWASH CONTROL valve closed

V-3-14, COND B NORTH CIRC WATER INLET valve open

V-3-29, COND B NORTH CIRC WATER OUTLET valve open

V-3-20, COND B NORTH BACKWASH CONTROL valve closed

V-3-2S, COND B CROSS CONNECT valve open o Reports condenser backwash is complete When told as the EO which backwash valves will be operated, ROLE PLAY acknowledge the report Terminus: Main condenser backwash is complete ILT 10-1 NRC Scenario 3 Page 6 of 28

ILT 10-1 NRC Scenario 3 (NEW)

Notes/Comments ILT 10-1 NRC Scenario 3 Page 7 of 28

ILT 1O~1 NRC Scenario 3 (NEW)

Op~Test No.: 10~1 NRC Scenario No.: NRC Sim 3 Event No.: ~

Event

Description:

CRD Pumg A trigs reguiring Tech Sgec LCO entIY rTrigger 1]

Initiation: Main condenser backwash is complete or as directed by the Lead Examiner Cues: Annunciator H1c, PUMP A OL; H7c, CHARG WTR PRESS LO; COOLING WATER FLOW, CLG WTRlREACTOR 6P, DRV WTRlREACTOR 6P indicate downscale; CRD Pump A breaker open Time Position Applicant's Actions or Behavior ATC

Responds to annunciator H1c, PUMP A TRIP o Reports CRD Pump A tripped o Dispatches EO to investigate pump/breaker [ROLE PLAY]

o Starts CRD Pump B by placing CRD PUMP NC08B switch to START o Reports CRD Pump B running with CRD indications return to normal SRO

Declares CRD Pump A inoperable

Reviews and applies Tech Spec 3.4.0.2 o If one CRD hydraulic pump becomes inoperable when the reactor water temperature is above 212 QF, the reactor may remain in operation for a period not to exceed 7 days provided the second CRD hydraulic pump is operating and is checked at least once every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . If this condition cannot be met, the reactor water temperature shall be reduced to less than 212 QF

Notifies SMlWWM about the pump trip As the EO investigating the CRD Pump A trip, wait 2 minutes and report ROLE PLAY the pump tripped on overload.

Terminus: CRD Pump B is in service and the SRO has addressed Tech Specs Notes/Comments ILT 10~1 NRC Scenario 3 Page 8 of 28

ILT 10-1 NRC Scenario 3 (NEW)

ILT 10-1 NRC Scenario 3 Page 9 of 28

ILT 10-1 NRC Scenario 3 (NEW)

Op-Test No.: OC 2008 Scenario No.: NRC SIM3 Event No.: 1 Event

Description:

ResQond to Electronic Pressure Regulator {EPR} Failure !Trigger 3]

Initiation: CRD Pump B is in service, or as directed by the Lead Examiner.

Cues: RPV Pressure and MWe drop (and stabilize at a lower value); EPR RELAY SETPOINT indicates 890 psig Time Position Applicant's Actions or Behavior ATC

Reports PRY pressure lowering

Monitors RPV pressure BOP

Reports EPR RELAY SETPOINT is low/changed

Performs ABN-9, Electronic Pressure Regulator Malfunction

[PANEL 7F]

o Slowly lowers the MPR setpoint by placing the MPR RELAY POSITION switch in the t% position using 1 second bumps until the MPR position indicator moves in the direction of and reaches the EPR setting and the MPR takes control o Verifies MPR CONTROLLING light is ON o Verifies the EPR CONTROLLING light is OFF o Places the EPR POWER switch to OFF o Verifies alarm Q6a, EPR PWR LOST alarm is received o Slowly raises RPV pressure to the previous pressure by placing MPR RELAY POSITION switch in the ~ % position o Refers to Procedure 202.1 for limitations with one pressure regulator out of service (no actions required)

Reports MPR in control and RPV pressure back to its previous pressure SRO

Directs entry into ABN**9, Electronic Pressure Regulator Malfunction

Notifies SMIWWM about the EPR failure Terminus: The EPR is off and the MPR is in control, and RPV pressure has been re established.

ILT 10-1 NRC Scenario 3 Page 10 of 28

ILT 10-1 NRC Scenario 3 (NEW)

Notes/Comments ILT 10-1 NRC Scenario 3 Page 11 of 28

ILT 10-1 NRC Scenario 3 (NEW)

Op-Test No.: 10-1 NRC Scenario No.: NRC Sim 3 Event No.: § Event

Description:

Trip of Control Room Vent System B [Trigger 5]

Initiation: The EPR is off and the MPR is in control, and RPV pressure has been re established, or as directed by the Lead Examiner Cues: Annunciator L4f, CONTROL RM HVAC SYS B TROUBLE; CR HVAC System B is shutdown.

Time Position Applicant's Actions or Behavior BOP

Responds to annunciator L4f, CONTROL RM HVAC SYS B TROUBLE o Reports that CR HVC B has shutdown o Dispatches NLO to Panel ER-S26-134 to determine cause of trip [ROLE PLAy]

ROLE PLAY: As the NLO, when requested to check Panel ER-S26-134, report that there are indications the fan blower has tripped. As the Lead Examiner, direct the BOP to place CR HVAC System A in service lAW 331.1. Hand the BOP a marked up copy of 331.1.

For time compression, tell them to start at step 5.3.4. When the get to step 5.3.8, tell the steps 5.3.S - 5.3.10 have been completed SAT.

Starts CR HVAC System A lAW procedure 331.1, section 5.0 (Startup shown below) o Momentarily places CONTROL ROOM HVAC A SYSTEM BYPASS in RESET o Verifies CONTROL ROOM HVAC A SYSTEM MODE switch in NORM o Start HVAC A Fan FN-S26-00SA by placing CONTROL ROOM HVAC A SYSTEM INITIATION switch in ON o Verifies isolation dampers open:

DM-826-042

DM-826-043 o Verifies CR HVAC Fan A FN-826-008A is running o Verifies System A operational mode is as selected by observing the NORM light lit ILT 10-1 NRC Scenario 3 Page 12 of 28

ILT 10-1 NRC Scenario 3 (NEW) o Notifies NLO to close refrigeration compressor breakers on the side of air conditioning unit 1-826-001 A as required

[ROLE PLAy]

ROLE PLAY: As the EO, when requested to close refrigeration compressor breakers 1, 2, and 3, report breakers are closed.

o Reports CR HVAC System A is in service SRO

Directs CR VHAC System A started lAW procedure 331.1

Declares CR HVAC System B inoperable

Reviews TS 3.17.B o With one control room HVAC system determined inoperable: 1. Verify once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the partial recirculation mode of operation for the operable system, or place the operable system in the partial recirculation mode; and 2. Restore the inoperable system within 7 days, or prepare and submit a special report to the Commission in lieu of any other report required by Section 6.9, within the next 14 days, outlining the action taken, the cause of the inoperability and the plans/schedule for restoring the HVAC system to operable status.

Notifies WWM/SM for repair/investigation

Briefs the Crew Terminus: I CR HVAC System A is in service and the SRO has reviewed/applied the Tech Specs.

l\Jotes/Comments ILT 10-1 NRC Scenario 3 Page 13 of 28

ILT 10-1 NRC Scenario 3 (NEW)

Op-Test No.: 10-1 NRC Scenario No.: NRC Sim 3 Event No.: § Event

Description:

Responds to a leak in the common variable leg to RPV water level instruments ID13A and ID13C !Trigger 71 Initiation: CR HVAC System A is in service, or as directed by the Lead Examiner Cues: ID13A and ID13C indication lowers; Other RPV water level indicators rising; Drywell pressure, temperature, unidentified leakage rising Time Position Applicant's Actions or Behavior ATC

Reports Indicated RPV water level lowering on NR GEMACs ID13A and ID13C, with RPV water level rising on all other available RPV water level instruments

Reports small rise in Drywell pressure, temperature and Drywell unidentified leak rate

Performs ABN-17, Feedwater System Abnormal Conditions o Places the MASTER FEEDWATER LEVEL CONTROLLER in manual by pressing the AUTO/MAN pushbutton o Confirms Feedwater flow is approximately equal to steam flow

Lowers feedwater flow by turning the manual knob on the MASTER FEEDWATER LEVEL CONTROLLER CCW to match TOTAL STEAM FLOW and TOTAL FEEDWATER FLOW o Places the LEVEL TRANSMITTER SELECTOR to the B position o Selects the S display on the MASTER FEEDWATER LEVEL CONTROLLER o Matches the S display to the P display by turning the manual knob on the MASTER FEEDWATER LEVEL CONTROLLER o When the deviation = 0 (S = P; Y = 0), then places the turning the manual knob on the MASTER FEEDWATER LEVEL CONTROLLER in AUTO o Monitors RPV water level and Feedwater flow o Maintains RPV water level at 160" or as directed by the US

Reports RPV water level transmitters swapped, Feedwater in auto and controlling.

ILT10-1 NRC Scenario 3 Page 14 of 28

ILT 10*1 NRC Scenario 3 (NEW)

BOP

May perform Drywell venting lAW attachment 312.11-10, if directed o Opens Torus vent valve V-28-47 o Opens Torus vent valve V-28-18 o Monitors DW pressure

May perform Drywall venting lAW attachment 312.11-12, if directed o Opens Drywell vent valve V-23-21 o Opens Drywell vent valve V-23-22 o Monitors DW pressure SRO

Directs entry into ABN-17, Feedwater System Abnormal Conditions

Notifies SMIWWM for repair/investigation of RPV water level instruments ID13A and ID13C

May direct Drywell venting lAW 312.11-10 or 312.11-12

Enters Tech Spec 3.3.D.1 for 2 gpm increase in unidentified leakage in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period o With the reactor coolant system leakage greater than the limits in 3.3.D.1.a or b above, reduce the leakage rate to within the acceptable limits within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or place the reactor in the shutdown condition within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

and be in the cold shutdown condition within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Terminus: RPV water level transmitters have been swapped, Feedwater is in auto and is controlling, and the SRO has reviewed/applied the Tech Specs Notes/Comments ILT 10-1 NRC Scenario 3 Page 15 of 28

ILT 10-1 NRC Scenario 3 {NEW}

Op-Test No.: 10-1 NRC Scenario No.: NRC Sim 3 Event No.: Z Event

Description:

ResQond to a loss of all CRD flow !Trigger 9]

Initiation: RPV water level transmitters have been swapped, Feedwater is in auto and is controlling, or as directed by the Lead Examiner Cues: Annunciator H2c, PUMP B OL; H7c, CHARG WTR PRESS LO; COOLING WATER FLOW, CLG WTRlREACTOR LlP, DRV WTR/REACTOR LlP indicate downscale; CRD Pump B breaker open Time Position Applicant's Actions or Behavior ATC

Responds to annunciator H2c, PUMP B OL

Recognizes/reports all CRD flow is lost. lAW RAP H2c, waits until two accumulator alarms are received then inserts a manual scram 0 NOTE: Two accumulator alarms are represented by annunciators H8c, ACCUMULATOR PRESS LO/LEVEL HI; and H7a, ROD BLOCK

Manually scrams the reactor lAW ABN-1 CRITICAL TASK 1 o Depresses both MANUAL SCRAM pushbuttons o Places the REACTOR MODE SELECTOR switch in SHUTDOWN o Reports all immediate scram actions are complete o Inserts SRMs o Inserts IRMs

Performs SP-1 when directed

May direct closure of CRD Charging header valve V-15-52

[ROLE PLAY]

Directs Chemistry to perform post-scram analysis of reactor water If directed as the EO to close CRD Charging header valve V-15-52, ROLE PLAY insert LOA-CRD024 to O. When done, report V-15-52 is closed SRO

Directs the ATC to manually scram the reactor lAW ABN-1, Reactor Scram CRITICAL TASK 1

Directs entry into RPV Control- No ATWS EOP o Directs the BOP to control RPV water level 138"-175" lAW ILT 10-1 NRC Scenario 3 Page 16 of 28

ILT 10-1 NRC Scenario 3 (NEW)

SP-2 (Feedwater) and SP-3 (CRD) o Directs RPV pressure 800 - 1000 psig with Turbine Bypass Valves (may be lower band) o Directs SP-1, Confirmation of Automatic Initiations and Isolations BOP

May have EO investigate B CRD Pump [ROLE PLAY]

ROLE PLAY: If asked to investigate B CRD Pump trip, wait 2 minutes and report that B CRD Pump tripped on overload.

Reports RPV water level 138" - EOP entry

Controls RPV water level initially lAW ABN-1 o When RPV water level begins to rise following the scram, performs the following:

Selects one Feedwater Pump and trips the other two Feedwater Pumps

Places all MFRVs in MANUAL

Closes all MFRVs

Performs SP-2 (Feedwater) o Controls RPV water level 138"-175" using the following as necessary:

Feedwater Regulating Valves

Main Feed Regulating (MFRV) Block Valve

Feedwater Low Flow Valves

Heater Bank Outlet Isolation Valves

Feedwater and Condensate Pumps o Reports RPV water level in band

Performs SP-3 (CRD) (i'f required) o Verifies running all available CRD Pumps Terminus: ABN-1 scram actions are complete and RPV water level is in/near the prescribed band ILT 10-1 NRC Scenario 3 Page 17 of 28

ILT 10-1 NRC Scenario 3 (NEW)

Notes/Comments ILT 10-1 NRC Scenario 3 Page 18 of 28

ILT 10-1 NRC Scenario 3 (NEW)

Op-Test No.: 10-1 NRC Scenario No.: NRC Sim 3 Event No.: 8/9 Event

Description:

Respond to Safety Valve lifting with a failure of one Containment Spray system to start Initiation: ABN-1 scram actions are complete and RPV water level is inlnear the prescribed band, or as directed by the Lead Examiner (Note: The leak will start 3 minutes after the Mode Switch is placed in SHUTDOWN from Event 7)

Cues: (RPV leak) Annunciator B4g, SV/EMRV NOT CLOSED; C3f, DW PRESS HI/LO; C8h, DW TEMP HI; Drywell pressure, temperature and leak rate rising Time Position Applicant's Actions or Behavior Crew

Monitor RPV water level and primary Containment temperature and pressure and report as required:

o RPV water level 138" - EOP entry o RPV water Level 90" RPV water level Lo-Lo o RPV water level at TAF o Drywell pressure 3.0 psig - EOP entry o Drywell temperature 150 of - EOP entry o Drywell pressure 12 psig o Drywell temperature as it approaches 281°F

Responds to annunciator B4g, SV/EMRV NOT CLOSED and C3f, DW PRESS HIILO o Reports Drywell pressure, temperature and leak rate rising o Reports a Safety Valve has lifted o Reports Drywell high pressure - EOP entry

Performs SP-3 (CRD) o Confirms both CRD Pumps running o Directs EO to close CRD Charging Header Supply valve V-15-52 [ROLE PLAy]

o Directs EO to open CRD Bypass valve V-15-237 o Directs EO to monitor CRD flow o Directs EO to throttle open CRD Bypass valve V-15-30 to not exceed 150 G PM o Reports SP-3 complete ILT 10-1 NRC Scenario 3 Page 19 of 28

ILT 10-1 NRC Scenario 3 (NEW)

Performs SP-7 (Liquid Poison) o Inserts a key in the STANDBY LIQUID CONTROL Keylock and places to FIRE SYS 1 or FIRE SYS 2 position o Verifies the following:

PUMP ON light on

SQUIBS light on

PUMP DISCH PRESS> RPV pressure

FLOW ON annunciator in alarm (G1b)

SQUIB VALVE OPEN annunciator in alarm (G2b) o Reports SP-7 complete

Places ADS TIMERs in BYPASS

Performs SP-9 (Core Spray) o Confirms Core Spray Suction valves open (V-20-32, V-20-3, V-20-33, & V-20-4) o Confirms Core Spray Test valves (V-20-27 & V-20-26) o Confirms one Core Spray Main Pump operating in each system o Confirms one Core Spray Booster Pump operating in each system o Confirms Core Spray Discharge valves open (V-20-12 &

V-20-18) o When RPV pressure is below 305 psig, then confirms at least one Core Spray Parallel Isolation valve in each system opens

Performs SP-4 (when RPV water level is recovering >61")

o Overrides Core Spray logic by pressing lit OVERRIDE pushbuttons and all ACTUATED pushbuttons o Restores/maintains the directed RPV water level band by cycling the Core Spray Parallel Isolation valves

Confirms Isolation Condensers initiated, but may remove from service after

Lowers RPV pressure to allow low pressure systems to inject by (any): initiating Isolation Condensers and/or opening EMRVs

Emergency Depressurization actions o Places ROPS in BYPASS o Opens all EMRVs by placing the associated control switches to MAN o Reports all EMRVs open ILT 10-1 NRC Scenario 3 Page 20 of 28

ILT 10-1 NRC Scenario 3 (NEW)

Performs SP-29 (Drywell Sprays)

CRITICAL TASK 2 o Confirms all Reactor Recirculation Pumps tripped o Confirms all Drywell Recirc Fans tripped o When directed, initiates Drywell Sprays

Places the SYSTEM MODE SELECT switch for the selected system in the DW SPRAY position

Verifies the Torus CLG Discharge valve closes

Verifies the DW Spray Discharge valve opens

Starts an ESW Pump

Selects a Containment Spray Pump

Places and holds the System Pump Start Permissive keylock for the selected in the appropriate position

Starts the selected Containment Spray Pump

[BOOTH]

BOOTH: 30 seconds after the applicant starts a Containment Spray Pump (or as directed by the Lead Examiner), trip the pump by inserting it's associated trigger:

Trigger 15: Cont. Spray Pump 51 A (System 1)

Trigger 17: Cont. Spray Pump 51B (System 1)

Trigger 19: Cont. Spray Pump 51 C (System 2)

Trigger 21: Cont. Spray Pump 51 D (System 2)

NOTE: CREW notices the Containment Spray Pump that was placed in service has tripped and starts another Containment Spray Pump

Monitors system and Drywell parameters

Confirms the following RBCCW valves closed

V-5-147, V-5-148, V-5-166, & V-5-167

Starts an additional Containment Spray Pump if required

Reports Drywell Sprays in**service o Before DrywelifTorus pressure lowers to 4 psig, secure Drywell Sprays:

Place the SYSTEM MODE SELECT switch in TORUS CLG position

Verifies the OW Spray Discharge valve closed

Verifies the Torus CLG Discharge valve opens

Reports EOP entry on high Torus water temperature (95 OF)

ILT 10-1 NRC Scenario 3 Page 21 of 28

ILT 10-1 NRC Scenario 3 (NEW)

SRO

Directs entry into Primary Containment Control EOP on high Drywell pressure and/or temperature, and re-entry into RPV Control - No ATWS EOP on high Drywell pressure

RPV Control - 1\10 ATWS EOP o May direct RPV pressure band 500-600 psig due to the leak with Turbine Bypass Valves o Directs SP-3 (CRD System Operation) o Directs SP-7 (Liquid Poison Injection) o Directs placing ADS Timers in Bypass (RPV water level <

61")

o Directs confirming the Isolation Condensers have initiated o Directs SP-9 (Core Spray) o Confirms low pressure systems have the capacity for restoring and maintaining RPV water level o Directs lowering RPV pressure to allow low pressure systems to inject o Directs SP-4 (Core Spray) o If RPV water level lowers to 0", directs entry into Emergency Depressurization - No ATWS EOP

Directs Emergency Depressurization - No ATWS EOP (if necessary on 0" RPV water level) o Directs ROPS bypassed o Verifies Torus water level> 90" o Directs all EMRVs open o When RPV water level rises to above 61", directs SP-4 (Core Spray) and to maintain RPV water level 100 - 175"

Primary Containment Control EOP o Directs SP-1, Confirmation of Automatic Initiations and Isolations o Directs line up of Drywell Sprays lAW SP-29 o Directs initiation of Drywell Sprays when either:

CRITICAL TASK 2

Drywell or Torus pressure exceeds 12 psig

It has been determined that bulk Drywell temperature is approaching 281°F Terminus: RPV water level is in the band or rising toward the band, and the Drywell Sprays has been initiated ILT 10-1 NRC Scenario 3 Page 22 of 28

ILT 10-1 NRC Scenario 3 (NEW)

Notes/Comments ILT 10-1 NRC Scenario 3 Page 23 of 28

ILT 10*1 NRC Scenario 3 (NEW)

Procedures Used Event Procedure 1

REMA (handed out) 2

323.6 (handed out) 3

RAP-H1c

RAP-H7c 4

ABN-9 5

RAp*L4f

331 .1 (handed out) 6

ABN-17

Tech Specs 3.5.0

Hardcard 312.11*10 or -12 7/8/9

ABN*1

PCC EOP

RPVC - no ATWS EOP

SP*2

SP-3

SP-1

ED-noATWS I

SP-29 I

ILT 10-1 NRC Scenario 3 Page 24 of 28

ILT 10-1 NRC Scenario 3 (NEW)

Simulator Setup

1. Reset to IC-115

2. Lower reactor power to 75% using recirc flow

3. Adjust reactor pressure to approximately 1000 psig

4. Have copy of 323.6 for applicants

5. Have a marked up copy of 331.1

6. Applicants can use the laminated copy of 1001.22-3, Core Maneuvering Daily Instruction Sheet, in the simulator to lower recirc flow Event Trigger Malfunction 1 NA None 2 NA None 3 T1-- BKR-CRD002 to TRIP

This trips CRD Pump A 4 T3-- MAL-TCS01 0 to 890

This causes the EPR setpoint to fail low and indicate 890 psig 5 T5-- SWI-TBS027C to ON SWI-TBS027A to OFF SWI-TBS023A to OFF STL-TBS006A to OFF STL-TBS006C to OFF

This trips the CR HVAC Fan Band extinguishes all indicating lights on Panel 9XR for CR HVAC B T5- I ANN-L-4f to ON

This brings in CONTROL RM HVAC SYS B TROUBLE alarm I

ILT 10-1 NRC Scenario 3 Page 25 of 28

ILT 10-1 NRC Scenario 3 (NEW) 6 T7 MAL- NSS012E to 2% over a 15-minute ramp

This places a leak in the common variable leg to NR GEMAC water level instruments ID13A and ID13C (this also inputs into FWLC).

7 T9 BKR-CRD001 to TRIP

This will trip CRD Pump NC08B T9 MAL-CRD010_0219 with a 2-minute time delay T9 MAL-CRD010_0223 with a 4-minute time delay

These will result in HCU accumulator trouble alarms 8/9 Preset Insert the following Event Trigger on Trigger 11: hwx03i271 n.lt.1

This activates Trigger 11 when the Reactor Mode switch is taken out of RUN T11 MAL-NSS016A on a 3 minute time delay

This will open Safety Valve NR28D T13 LOA-CRD024 to 0 (to close V-15-52)

LOA-CRD057 to 1 (to open V-15-237)

LOA-CRD051 to 1 (to open V-15-30)

This isolates CRD charging header and allows CRD flow on the bypass I

I ILT 10-1 NRC Scenario 3 Page 26 of 28

ILT 10-1 NRC Scenario 3 (NEW)

T15~ MAL-CNSOO4A

Trips Containment Spray Pump 51 A in System 1 T17~

MAL-CNSOO48 Trips Containment Spray Pump 518 in System 1 MAL-CNSOO4C T19~

Trips Containment Spray Pump 51 C in System 2 T21 ~

MAL-CNSOO4D Trips Containment Spray Pump 51 Din System 2 ILT 10-1 NRC Scenario 3 Page 27 of 28

ILT 10-1 NRC Scenario 3 (NEW)

Shift Turnover Current plant conditions:

The plant is at 75% power

TBCCW Pump 2 is tagged out of service Shift activities

Lower power to 70% using recirculation flow lAW 1001.22-3, Core Maneuvering Daily Instruction Sheet

Backwash Main Condenser Half B South starting at step 5.1.6.1 ILT 10-1 NRC Scenario 3 Page 28 of 28

ILT 10-1 NRC Scenario 4 (NEW)

Scenario Outline Facility: Oyster Creek Scenario No.: !! op Test No.: 10-1 NRC Examiners: Operators:

Initial Conditions:

100% power

Dilution pump 2 is tagged out of service Turnover:

No evolutions are planned during this shift Event N . o. Event Type* Event Description 1 Respond to CRD Flow Control Valve failed closed.

2 Respond to a leak in Isolation Condenser Shell A.

IND* R Condensate Pump A experiences high amps requiring a 3 CFW018 ATC ANN-K-2B C BOP rapid power reduction and securing of Condensate Pump.

MAL*

RCPOO3D C BOP 4 Respond to Recirculation Pump D total seal failure.

TS SRO 5 Respond to multiple drifting control rods.

Respond to a Torus Leak requiring entry into Primary 6

Containment Control.

Respond to Core Spray system suction valves being 7

mechanically seized when lining up the CST to the Torus.

Respond to a Torus leak increase requiring the crew to 8

Emergency Depressurize.

(N}ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient, (TS) Tech Specs ILT 10-1 NRC Scenario 4 Page 1 of 24

IlT 10-1 NRC Scenario 4 (NEW)

Simulator Summary Event Event Summary 1 The ATC will respond to in-service CRD Flow Control Valve failing closed. The ATC will swap Flow Control Valves lAW procedure 302.1, Control Rod Drive System. (ATC: Component Malfunction) 2 The BOP will respond to lowering level in Isolation Condenser A shell lAW RAP-C6a. The BOP will fill the IC shell from Panel 5F/6F. The IC shell level will not recover above the required point of 7.3 ft and the SRO will declare IC A inoperable and apply Tech Spec 3.8.C. (BOP:

Component Malfunction; SRO: Tech Specs) 3 Condensate Pump A will experience rising motor amps.The crew will receive annunciator K-2-f, CONDENSATE PUMP B Ol, and the BOP will diagnose the Condensate Pump A current indication in the Control Room is high. The field operator (on request) will report loud noise coming from Condensate Pump A. The SRO will direct the ATC to perform a rapid power reduction and the BOP to remove one Feedwater Pump and the affected Condensate Pump from service.

(ATC: Reactivity Manipulation; BOP: Component Malfunction) 4 The BOP will respond to a leak in Recirculation Pump D outer seal, followed by a leak in the inner seal. The SRO will direct entry into ABN-2, Recirculation System Failures, to trip Recirculation Pump D and Isolate the D Recirculation loop. The SRO will review and apply Tech Specs 3.3.D and 3.3.F for unidentified leak rate and recirculation loop operability. (BOP: Component Malfunction; SRO: Tech Specs) 5 The ATC will identify/report multiple drifting control rods into the core and lAW ABN-6, Control Rod Malfunctions, manually scram the reactor lAW ABN-1, Reactor Scram. (ATC: Component Malfunction) (PRA) 6 A leak in the Torus will develop requiring the crew to enter the Primary Containment Control EOP. The crew will commence makeup to the Torus lAW SP-37, Makeup To The Torus Via Core Spray System. (Major Evolution) 7 When the crew attempts to line up Core Spray System to make up to the Torus, Core Spray suction valve for System 1(2) V-20-3(4)and V 20-32(33), Core Spray System 1(2) suction valves will not close. The crew will place the alternate Core Spray Pump System in service.

(Component Failure After EOP)

IlT 10-1 NRC Scenario 4 Page 2 of 24

ILT 10-1 NRC Scenario 4 (NEW) 8 After the Crew places Core Spray Pump/System 2 in service to makeup to the Torus, the Torus leak will increase leading the crew to Anticipate Emergency Depressurization and/or Emergency Depressurize the RPV. (Major Evolution)

Critical The ATC will manually scram the reactor following control rods drifting Task 1 into the core. There is no manual scram associated with this casualty and the core is not analyzed for the resultant abnormal rod configuration.

Critical The crew will Emergency Depressurize the RPV prior to Torus Level Task 2 reaching 110 inches.

ES-301-4 Target Quantitative Actual Event Attributes Attributes Number(s)

1. Total malfunctions (5-8) 7 1, 2, 3,4,5, 6, 7

2. Malfunctions after EOP entry (1-2) 2 7,8

3. Abnormal events (2-4) 3 1,4,5

4. Major transients (1-2) 2 6,8

5. EOPs entered/requiring substantive 2 5,6 actions (1-2)

6. EOP contingencies requiring substantive 1 8 actions (0-2)

7. Critical tasks (2-3) 2 5,8 ILT 10-1 NRC Scenario 4 Page 3 of 24

ILT 10-1 NRC Scenario 4 (NEW)

Op-Test No.: 10-1 NRC Scenario No.: NRC Sim 4 Event No.: 1 Event

Description:

Respond to CRD Flow Control Valve failed closed [Trigger 11 Initiation: Following shift turnover, or as directed by the Lead Examiner.

Cues: Annunciator H5c, CRD HIGH TEMP; DRIVE WATER FLOW, COOLING WATER FLOW, CLG WTRlREACTOR tlP, & DRIVE WTRlREACTOR tlP go downscale Time Position Applicant's Actions or Behavior ATC

Responds to annunciator H5c, CRD HIGH TEMP, and abnormal CRD indications.

Reports abnormal CRD indications.

Reports the CRD FCV (NC30A) indicates closed.

Directs the EO to investigate the failed CRD FCV [ROLE PLAY 1].

Enters ABN-6, Control Rod Malfunctions, section 13, Flow Control Valve NC-30AlB Fails Closed.

Places CRD FCV NC30B in service lAW procedure 302.1, section 6.3.3.

o Places the CRD FLOW CONTROLLER in MAN.

o Directs the EO to open the standby FCV inlet/outlet valves

[ROLE PLAY 2].

o Directs the EO to place the 4-Way Valve in position to supply both controllers [ROLE PLAY 3].

o Places the CRD FLOW CONTROL VALVES switch to the B position.

o Directs the EO to place the 4-Way Valve in position to supply the in-service controller [ROLE PLAY 4].

o Verifies normal CRD indications.

o Places the CRD FLOW CONTROLLER in AUTO.

o Directs the EO to close the failed FCV inlet/outlet valves

[ROLE PLAY 5].

!. Reports the standby CRD FCV is in service and indications are normal.

BOP

Announces entry into ABN-6, Control Rod Malfunctions, due to CRD FCV NC30A failing closed.

i

May check CRD Temperatures on Panel SR and report there ILT 10-1 NRC Scenario 4 Page 4 of 24

ILT 10-1 NRC Scenario 4 (NEW) are several control rods with high temperatures.

SRO

Directs entry into ABN-6, Control Rod Malfunctions, due to CRD FCV NC30A failing closed.

Directs swapping CRD FCVs lAW procedure 302.1, section 6.3.3.

Notifies the SMIWWM about the failed CRD FCV.

ROLE 1. When/if asked as the EO to investigate the in-service CRD FCV (NC30A),

PLAY report that it is closed, was leaking air badly, and that you have isolated the air supply to the valve.

2. (Step 6.3.3.1.1.2.b) When/if asked as the EO to open the standby CRD FCV inleVoutlet valves, insert Trigger 3 and report the valves OPEN (V 15-18, V-15-19).

3. (Step 6.3.3.1.1.3) When/if asked as the EO to place the 4-Way Valve in position to supply both controllers, state it is in the position to supply both controller (NO booth actions are required).

4. (Step 6.3.3.1.1.5) When/if asked as the EO to place the 4-Way Valve in position to supply the in-service controller state it is in the position to supply NC30B (NO booth actions are required).

5. (Step 6.3.3.1.1.8.a) When/if asked as the EO to close the failed FCV inleVoutlet valves, state the valves are closed (Insert LOA-CRD009 and LOA-CRD010 to 0) (closes V-15-16, V-15-17).

Terminus: CRD FCV NC30B is in service and CRD parameters indicate normal.

Notes/Comments ILT 10-1 NRC Scenario 4 Page 5 of 24

ILT 10-1 NRC Scenario 4 (NEW)

Op-Test No.: 10-1 NRC Scenario No.: NRC Sim 4 Event No.: g Event

Description:

Resgond to a leak in Isolation Condenser Shell A rrrigger 5]

Initiation: CRD FCV NC30B is in service and CRD parameters indicate normal, or as directed by the Lead Examiner.

Cues: Annunciator C6a, SHELL A LVL HI/LO; ISOL CONDENSER A LEVEL indicates lower than normal Time~ Applicant's Actions or Behavior BOP

Responds to annunciator C6a, SHELL A LVL HI/LO .

0 Reports Isolation Condenser shell level and trend.

0 Restores shell water level lAW procedure 307, Isolation Condenser System, section 7.3.1, using Demineralized Water.

Records initial shell water level on Attachment 307-15

Opens V-11 ..36 on Panel 5F/6F.

Veri'fies annunciator K6d is received.

Commences filling isolation condenser until shell level indicates between 7.3 and 7.7 feet.

0 After shell level makeup has been initiated, reports Isolation Condenser Shell level is not rising.

0 May direct the EO to investigate Isolation Condenser A.

[ROLE PLAY]

ROLE PLAY: When asked as the EO to investigate, report IC-A shell level is 6.6 ft. and slowly lowering. There is water on the floor under the ICs, the water is contained, and no equipment is affected.

0 If directed to isolate Isolation Condenser A, places the following switches in CLOSE:

AC V-14-30 (steam)

DC V-14-31 (steam)

DC V-14-34 (condensate return)

AC V-14-36 (condensate return)

SRO

Declares Isolation Condenser A inoperable and applies Tech Spec 3.B.B, C.

ILT 10-1 NRC Scenario 4 Page 6 of 24

ILT 10-1 NRC Scenario 4 (NEW) 0 The shell side of each condenser shall contain a minimum water volume of 22,730 gallons. If the minimum volume cannot be maintained or if a source of makeup water is not available to the condenser, the condenser shall be considered inoperable.

0 If one isolation condenser becomes inoperable during the run mode the reactor may remain in operation for a period not to exceed 7 days provided the motor operated isolation and condensate makeup valves in the operable isolation condenser are verified daily to be operable.

Notifies SMIWWM about Isolation Condenser A .

May direct the BOP to isolate Isolation Condenser A.

Terminus: Isolation Condenser A is declared inoperable and the SRO has applied Tech Specs.

Notes/Comments ILT 10-1 NRC Scenario 4 Page 7 of 24

ILT 10-1 NRC Scenario 4 (NEW)

Op-Test No.: 10-1 NRC Scenario No.: NRC Sim 4 Event No.: ~

Event

Description:

Condensate PumQ A eXQeriences high amQs reguiring a raQid Qower reduction and the securing of the Condensate PumQ fTrigger 7].

Initiation: Isolation Condenser A is declared inoperable and the SRO has applied Tech Specs., or as directed by the Lead Examiner Cues: Annunciator K2b, CONDENSATE PUMP A OL alarms; Condensate Pump A current indication rises Time Position Applicant's Actions or Behavior BOP

Responds to K2b, PUMP A OL and Condensate Pump A high amps.

0 May have the Turbine Building EO investigate Condensate Pump A [ROLE PLAY 1].

0 Verifies pump amps> 160 amps and rising.

0 Reports the RAP requires a Rapid Power Reduction lAW ABN-17, Feedwater System Abnormal Conditions.

Following the rapid power reduction (at the direction of the SRO), trips the A Condensate Pump [ROLE PLAY 2].

BOOTH ACTIONS ROLE PLAY 1: If requested to investigate Condensate Pump A, report there a loud noise and an acrid odor coming from Condensate Pump A's motor. No smoke or fire is observed.

ROLE PLAY 2: When the Applicant trips Condensate Pump A, delete the malfunction IND-CFW018. This will allow the pump ammeter to indicate normal.

SRO

Directs the ATC to perform a rapid power reduction to < 70%

Reactor Power.

Directs the Condensate Pump A be tripped or secured.

Informs the SMIWWM about Condensate Pump A failure.

ATC

Performs a rapid power reduction to < 70% power and ILT 10-1 NRC Scenario 4 Page 8 of 24

ILT 10-1 NRC Scenario 4 (NEW) verifies feed pump suction pressure is> 60 psig and steady.

Announces entry into ABN-17 (may be performed by BOP) .

Terminus: Reactor power is < 70% and Condensate Pump A is secured.

Notes/Comments ILT 10-1 NRC Scenario 4 Page 9 of 24

ILT 10-1 NRC Scenario 4 (NEW)

Op-Test No.: 10-1 I\JRC Scenario No.: NRC Sim 4 Event No.: 1:

Event

Description:

ResQond to Recirculation PumQ D total seal failure !Trigger 9].

Initiation: Reactor power is < 70% and Condensate Pump A is secured, or as directed by the Lead Examiner.

Cues: Rising unidentified leak rate; Recirculation Pump D seal indications are trending downscale; Drywell Pressure and Temperature slowly rising Time Position Applicant's Actions or Behavior BOP

Recognizes and reports Recirculation Pump D seal indications are trending downscale and unidentified leak rate rising.

Enters ABN-2 and performs actions for a Total Seal Failure for Recirculation Pump D.

0 Stops the affected recirculation pump.

0 Closes the following Valves for the affected loop:

Pump DISCHARGE valve.

Pump SUCTION valve.

Pump DISCHARGE BYPASS valve.

0 Vents the Drywell in accordance with 312.11 if required.

0 Verifies that the core is operating at less than the MAPRAT limits specified in Procedure 202.1-5.

0 Directs the Racking-out of MG-Set motor breaker of the affected recirculation pump lAW Procedure 337, Section 7.0.

0 Tags the MG-Set Motor breaker for the affected recirculation pump lAW Procedure OP-MA-1 09-1 01.

0 Informs US to refer to Technical Specifications 3.3.F.2.a and 3.3.F.2.b.

0 Refers to OP-AA-1 06-1 01, Significant Event Reporting.

ATC

Reports Drywell Pressure and Temperature are rising.

Announces entry into ABN-2 SRO

Directs entry into ABN-2

Refer to Technical Specifications 3.3.F.2.a and 3.3.F.2.b. for ILT 10-1 NRC Scenario 4 Page 10 of 24

ILT 10-1 NRC Scenario 4 (NEW)

Recirculation Loop Operability. Determines that the reactor may remain in operation with ONE isolated recirculation loop.

Informs SMIWWM Terminus: Recirculation Loop D is isolated and the SRO has referred to Tech Specs.

Notes/Comments ILT 10-1 NRC Scenario 4 Page 11 of 24

ILT 10-1 !\JRC Scenario 4 (NEW)

Op-Test No.: 10-1 NRC Scenario No.: NRC Sim 4 Event No.: § Event

Description:

ResQond to a mUltiQle rod drift rrrigger 11]

Initiation: Recirculation Loop D is isolated and the SRO has referred to Tech Specs, or as directed by the Lead Examiner Cues: Annunciator H6a, ROD DRIFT; Indications of multiple control rods drifting into the core Time Position Applicant's Actions or Behavior ATC

Responds to annunciator H6a, ROD DRIFT.

Recognizes/reports multiple control rods drifting and intention to manually scram.

CRITICAL TASK 1

Manually scrams the reactor lAW ABN-1, Reactor Scram 0 Depresses both MANUAL SCRAM pushbuttons 0 Places the REACTOR MODE SELECTOR switch in SHUTDOWN 0 Verifies all control rods are fully inserted 0 Reports that all 'Immediate scram actions are complete 0 Inserts SRMs 0 Inserts IRMs

Notifies Chemistry to sample Reactor Coolant for activity

Monitors Off-Gas activity and Main Steam Line radiation levels

Informs US to refer to Tech Spec section 3.2, Reactor Coolant SRO

Directs the ATC to enter ABN-6, Control Rod Malfunctions

Directs the ATC to manually scram the reactor lAW ABN-1, CRITICAL TASK 1 Reactor Scram

Directs entry into RPV Control - No ATWS o Directs the Crew to maintain RPV water level 138" - 175" if MSIVs are open, or 138" - 160" using SP2 (Cond/FW) and/or SP3 (CRD) o Directs the Crew to maintain RPV pressure (approximately) 800 - 1000 pSig using Turbine Bypass ILT 10-1 NRC Scenario 4 Page 12 of 24

ILT 10-1 NRC Scenario 4 (NEW)

I Valves, the Isolation Condensers (SP-11) and/or EMRVs (SP-12)

BOP

Controls RPV water level as directed following the scram o Reports entry into RPV Control - No ATWS on low RPV water level o When RPV level begins to rise following the scram, then performs the following:

o Trips 2 Feed Pumps with their control switches o Places all MFRVs in MANUAL o Closes all MFRVs o Directs the EO to close CRD Supply Water Valve to Charging Water Header valve V-1S-S2 [ROLE PLAy]

I ROLE PLAY: As the EO directed to close CRD Supply Water Valve to Charging Water Header valve V-15-52, insert Trigger 13. Report when complete.

o Enters SP-2 (Cond/FW) when directed o Controls RPV water level using the following as necessary:

o Feedwater Regulating valves o Main Feed Regulating Valve (MFRV) Block valves o Feedwater Low Flow valves o Heater Bank Outlet Isolation valves o Feedwater and Condensate pumps o Performs SP-1 as directed o Makes plant announcement for reactor scram Terminus: i The reactor is scrammed, and RPV water level and pressure are under I contra/.

Notes/Comments ILT 10-1 NRC Scenario 4 Page 13 of 24

ILT 10-1 NRC Scenario 4 (NEW)

Op-Test No.: 10-1 NRC Scenario No.: NRC Sim 4 Event No.: 6/7 Event

Description:

ResQond to a minor Torus Leak reguiring entIY into Primary Containment Control, Core SQra~ S~stem 2 suction valves mechanicall~ seized fTrigger 151.

Initiation: The reactor is scrammed, and RPV water level and pressure are under control, or as directed by the Lead Examiner.

Cues: Torus water level trending down; Annunciator CSe, TORUS LEVEL HIILO Time Position Applicant's Actions or Behavior ROLE PLAY: 3 minutes after inserting Trigger 15, call the control room as the Radwaste Operator and report the 1-7 Sump Hi Level alarm is in.

Crew

Responds to Torus water level trending down and annunciator C5e, TORUS LEVEL HIILO.

Dispatches Equipment Operators to investigate reactor building corner rooms for water [ROLE PLAY].

ROLE PLAY: 3 minutes after requesting the Equipment Operators to investigate the reactor building corner rooms for water, report there is no water in the corner rooms themselves but water noise can be heard coming from inside the water tight doors in the NE corner room.

Performs actions of SP-37 to makeup to the Torus with Core Spray System 1 .

0 If Core Spray actuating signals are present, overrides the Core Spray initiation logic.

0 Confirms Core Spray System 1 Main and Booster Pumps are stopped.

0 Closes Core Spray System 1 suction valves V-20-3 and V-20-32. NOTE: These valves are mechanically seized.

Informs the SRO V-20-3 and V-20-32 will not close and Core Spray System 1 is not available for Torus makeup.

Performs actions of SP-37 to makeup to the Torus with Core Spray System 2.

0 If Core Spray actuating signals are present, overrides the Core Spray initiation logic.

ILT 10-1 NRC Scenario 4 Page 14 of 24

ILT 10-1 NRC Scenario 4 (NEW) o Confirms Core Spray System 2 Main and Booster pumps are stopped.

o Closes the Core Spray System 2 suction valves V-20-4 and V-20-33.

o Confirms closed Parallel Isolation Valves V-20-21 and V 20-41.

o Requests the Equipment Operator to open the breakers for Core Spray Parallel Isolation Valves V-20-21 and V 20-41 [ROLE PLAY].

i I

ROLE PLAY: When requested to open the breakers for V-20-21 and V-20-41 (step 3.3.4 of SP-37), insert Trigger 17. Report the breakers for V-20-21 andV-20-41 are open (or that step 3.3.4 of SP-37 is complete).

o Requests the Equipment Operator place the breakers for Core Spray Pump Suction Valves V-20-4 and V-20-33 in OFF [ROLE PLAY].

ROLE PLAY: When requested to place the breakers for Core Spray Pump Suction ValvesV-20-4and V-20-33 in OFF (step 3.3.4.1 ofSP-37), insert Trigger 19. Report the breakers for V-20-4 and V-20-33 are in OFF (or step 3.3.4.1 is complete).

o Requests the Equipment Operator unlock and open the CST supply valves V-20-1, V-20-2, and V-20-35 [ROLE PLAY].

I ROLE PLAY: When requestc;:td to unlock and open CST supply valves V-20-1 , V-20-2, and V-20-35 (step 3.3.4.2 of SP-37), insert Trigger 21. Report CST supply valves V-20 1, V-20-2, and V-20-35 are unlocked and open (or step 3.3.4.2 is complete).

o Starts Core Spray System 2 Main Pump B or D [ROLE PLAY]

ROLEPLAY: If requested to verify all personnel are standing clear of Core Spray MaIn Pu~:p B orOtirep0r1 all personnel are clear of, the pump.' If requested to verify proper operation (or good start) Of Core Spray Main Pump B or D, report that there was a good start on Core Spray Main Pump B or D.

o Requests the Equipment Operator place the breaker for the Test Flow Return Valve V-20-26 in the ON position ILT 10-1 NRC Scenario 4 Page 15 of 24

ILT 10-1 NRC Scenario 4 (NEW) and Open V-20-26 [ROLE PLAY].

ROLE PLAY: When requested to place the breaker for the Test Flow Return Valve V 20-26 in the ON position and Open V-20-26 (step 3.3.6 and 3.3.7 of SP-37), insert Trigger 23. Report that the breaker for the Test Flow Return Valve V-20-26 in the ON position and V-20-26 in open (or step 3.3.6 and 3.3.7 are complete).

SRO

Directs entry into the Primary Containment Control EOP .

Directs the crew perform SP-37 to make-up to the Torus with the CST via the Core Spray System Terminus: SP-37 is complete and Core Spray System 2 is making up to the Torus.

Notes/Comments ILT 10-1 NRC Scenario 4 Page 16 of 24

ILT 10-1 NRC Scenario 4 (NEW)

Op-Test No.: 10-1 NRC Scenario No.: NRC Sim 4 Event No.: §.

Event

Description:

Resgond to a Torus leak increase reguiring the crew to Emergenc~

Degressurize [Change severitll of MAl-PCN007 to 20000].

Initiation: SP-37 is complete and Core Spray System 2 is making up to the Torus, or as directed by the Lead Examiner.

Cues: Torus leak rises beyond the makeup capacity of Core Spray System 2 that was lined up to makeup to the Torus lAW SP-37.

Time Position Applicant's Actions or Behavior Crew

Recognizes Torus leak rises beyond the makeup capacity of Core Spray System 2 that was lined up to makeup to the Torus lAW SP-37.

May Anticipate Emergency Depressurization with Turbine Bypass Valves or Isolation Condensers.

Performs Emergency Depressurization - No ATWS EOP.

CRITICAL TASK 2 0 Places ROPS in BYPASS when directed.

0 Places all EMRV switches to MAN.

Secures Core Spray lAW SP-10 as directed.

SRO

May direct Anticipating Emergency Depressurization .

CRn"leAl TASK 2

Directs entry into Emergency Depressurization - No ATWS EOP.

o Directs ROPS bypassed.

o Verifies Torus water level> 90".

o Directs RO to manually open all EMRVs.

o Directs securing Core Spray lAW SP-1 0 if not required for adequate core cooling.

Terminus: All EMRVs are OPEN and Emergency Depressurization has been commenced.

ILT 10-1 NRC Scenario 4 Page 17 of 24

ILT 10-1 NRC Scenario 4 (NEW)

Notes/Comments ILT 10-1 NRC Scenario 4 Page 18 of 24

ILT 10-1 NRC Scenario 4 (NEW)

Procedures Used Event Procedures ::J.

1

RAP-H5c

ABN-6

302.1 2

RAP-6G8

307, section 7 and Attachment 307-15

TS 3.8 3

RAP-K2b

ABN-17

"'t

ABN-2 5

ABN-6 6/7/8

RAP-G5e

RPV Gontrol- no ATWS

peG EOP

SP-37

SP-2

SP-3

ED noATWS ILT 10-1 1\1 RG Scenario 4 Page 19 of 24

ILT 10-1 NRC Scenario 4 (NEW)

Simulator Setup

1. Reset to IC-115

2. Place a tag on Dilution Pump #2 Event Trigger Malfunction N/A Preset ~ LOA-CWS043 to RACKED OUT

Racks out the breaker for Dilution Pump #2 1 T1 ~ MAL-CRD001 A to 0

This closes CRD FCV NC30A T3~ LOA-CRD012 to 1 LOA-CRD011 to 1

This opens the alternate FCV NC30B inleVoutlet valves.

2 T5~ ICH-ICS001A from 7.2' to 6.8' over a 2 minute ramp

This will cause IC A shell water level indication to lower to 7' over a 2-minute period. Note that this malfunction set to lower to 6.8' will give an indication on Panel 1F/2F of 7'.

3 T7~ IND-CFW018 from 160 to 200 over a 3 minute ramp

This makes Condensate Pump A amp meter read 160 amps and trend toward 200 amps.

NOTE: Delete this malfunction when Condensate Pump A is tripped.

ILT 10-1 NRC Scenario 4 Page 20 of 24

ILT 10-1 I\JRC Scenario 4 (NEW)

T7 ANN-K-2B to ON

This makes Condensate Pump A overload annunciator (PUMP B OL) alarm.

Insert the following Event Trigger (1) and Preset Command (2) on Trigger 25:

1) hwx040087g

2) DOR IND-CFW018

This will DELETE the malfunctions for high current on the 'A' Condensate Pump when the crew trips the pump.

4 T9 MAL-RCP003D to 100% over 15 minutes

This inputs a failure of Recirculation Pump D's inner seal.

MAL-RCP004D to 100% over 15 minutes

This inputs a failure o'f Recirculation Pump D's outer seal.

5 T11 MAL-CRD006_1835, _3451, and _4207

This will cause Control Rods 18-35, 35 51, and 42-07 to drift into the core.

T13 LOA-CRD031 to 0 6/7/8 Preset

'. This will close CRD Bypass V-15-52 VLV-CSS001 to MECH SZ VLV-CSS009 to MECH SZ

This will mechanically seize Core Spray System 1 suction valves V-20-3 and V-20-32.

I ILT 10-1 NRC Scenario 4 Page 21 of 24

ILT 10-1 NRC Scenario 4 (NEW)

Preset -- Insert the following Event Trigger on Trigger 15: hwx03i2?1 n.lt.1

This activates Trigger 15 when the Reactor Mode switch is taken out of RUN T15- MAL-PCNOO? to 5000

This will cause a Torus bottom leak.

NOTE: When Core Spray System 2 is placed in service to make-up to the Torus, raise MAL-PCNOO? to 20000.

T17-- LOA-CSS014 to TRUE

Racks out the breaker for Core Spray System 2 Parallel isolation valve V-20 21 T17-LOA-CSS02? to TRUE

Racks out the breaker for Core Spray System 2 Parallel isolation valve V-20 41 T19- VLV-CSS002 to CNT FUSE VLV-CSS010 to CNT FUSE

Places the Core Spray Pump suction valves V-20-4 and V-20-33 in OFF.

T21- LOA-CSS001 to 1 T21- LOA-CSS002 to 1 T21- LOA-CSS023 to 1

Opens CST supply valves V-20-1, V 20-2, and V-20-35.

T23-- LOA-CSS019 to FALSE

Places the breaker for the Test Flow Return Valve V-20-26 in ON.

I I I ILT 10-1 NRC Scenario 4 Page 22 of 24

ILT 10-1 NRC Scenario 4 (NEW)

T23-- I LOA-CSS018 to 100

This manually opens Test Flow Return Valve V-20-26.

ILT 10-1 NRC Scenario 4 Page 23 of 24

ILT 10-1 NRC Scenario 4 (NEW)

Shift Turnover Current plant conditions:

The plant is at rated power

Dilution Pump 2 is tagged out of service Shift Activities

No shift activities are scheduled ILT 10-1 NRC Scenario 4 Page 24 of 24

v t e Letter Sequence Draft Other
TAC:U01831, (Open)
Initiation Acceptance Administration Questions Answers Results Approval... Other: ML112130525, ML112130528, ML112130534, ML112490353
MONTHYEAR2011-06-27 [Table View]

ML111870278

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