ML091030146

Draft - Operating Exam (Sections a, B & C) (Folder 2)

ML091030146
Person / Time
Site:	Oconee
Issue date:	03/31/2009
From:	D'Antonio J Operations Branch I
To:	Entergy Nuclear Operations
Hansell S
Shared Package
ML082600435	List: IR 05000293/2009301 ML083260506 ML090770042 ML091000641 ML091000643 ML091030146 ML091030488 ML091130218 ML091250545 ML091250549 ML091250552 ML091260229 ML091310110 ML091310567 ML091310586
References
50-293/09-301, ES-C-1, TAC U01744 50-293/09-301
Download: ML091030146 (191)

Text

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

Facility: PILGRIM Task No.:

Task

Title:

Verifv Recombiner O~eration JPM No.: 2009 NRC ROISRO JPM COO1 KIA

Reference:

2.1.25 2.8 / 3.1 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testinq:

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

Initial Conditions: The plant is operating at 50% power. High hydrogen concentration is suspected downstream of the AOG Recombiners.

Task Standard: Determines recombiner delta-temperature indicates recombiner is overheated.

Required Materials: N/A General

References:

PNPS 2.4.1 41 Initiating Cue: You have been directed to perform PNPS 2.4.141 "Abnormal Recombiner Operation" Section 4.2 and identify abnormal conditions, if any.

SRO ONLY - Take appropriate actions for abnormal conditions, if any.

Time Critical Task: NO Simulator Booth: TAKE SIMULATOR OUT OF FREEZE Validation Time:

2009 NRC ,IPM RO/SRO COO1

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

1. Initialize simulator to 50% power.

2. Insert Instructor Overrides on CP600 Hydrogen Recorder AR-R603 so that both channels indicate 1.80%

3. Turnoff CP-6OOL Alarms:

A-7 "H2 Analyzer A H2 CONC HI" B-7 "H2 Analyzer B H2 CONC HI" A-8 " After CNDSR LOOP SEAL LVL HILO"

4. Insert malfunction OG05 " Water In Offgas System". Allow the simulator to run until the Recombiner Exit temperature, Pt.5 on Recorder TR-9250, Lowers to c 425 degrees.

5. Freeze Simulator

6. Place Danger tags on the MO-9205 and MO-9204.

7 . Ensure Preheater exit temperature is >350 degrees ( procedure NOTE at step 4.2 ['I])

2009 NRC JPM ROISRO COO1

Appendix C Page 3 of 7 Form ES-C-1 PERFORMANCE INFORMATIOIV (Critical Steps denoted with a check (d) mark)

START TIME:

Performance Step: 1 Proceeds to PNPS 2.4.141 Section 4.2 - High Hydrogen Concentration Downstream of the Recombiners.

Standard: Enters PNPS 2.4.141 Section 4.2 Comment:

Performance Step: 2 Section 4.2 Step [I] - TRIP the ETS using "ETS SHUTDOWN" push button on Panel CP600.

Standard: Depresses "ETS SHUTDOWN" pushbutton Comment:

SIM BOOTH: Ensure Preheater exit temperature is ~ 3 5 degrees 0 NOTE Reducing Reactor power will reduce recombiner exit temperature by reducing hydrogen production. Preheater exit temperature should be greater than 350°F at f 00% power.

4 Performance Step: 3 Section 4.2 Step [2] - If both H2 analyzers are indicating greater than or equal to 4%....

Standard: Reviews above NOTE.

Determines that both H2 analyzers are not greater than 4%

Comment:

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION 4 Performance Step: 4 Section 4.2 [3] - Verify recombiner operation for the power level being maintained by referring to Att. 1 Att. 2 as applicable.

Standard: Evaluates recombiner delta-temperature utilizing Att. 1 and determines recombiner delta-temperature is in the questionable region of the graph.

Comment: NOTE The procedure step states t o use Att.1 Att.2. Prompt candidate t o evaluate using both graphs if only one is used.

4 Performance Step: 5 Evaluate recombiner delta-temperature utilizing Attachment 2 Standard: Determines recombiner delta-temperature is below the Low Limit of the graph Comment: Termination for RO ONLY, SRO continues t o next step Performance Step: 6 Direct placing the standby recombiner in service.

Standard: AOG will be directed to be bypassed IAW PNPS 2.2.106 while maintaining steam dilution and air purge through the recombiner and the charcoal beds Cue: If the standby recorr~bineris directed to be placed in service, "the

'B' recombiner i s unavailable" Direct maintaining steam dilution and air purge on the 'A' recombiner.

Cue: An operator has been assigned to initiate air purge on 'A' recombiner and the charcoal beds.

Evaluator Note: The candidate may indicate a power reduction is necessary when performing the following step. If so, it has been directed to the 905 operator.

4 Direct bypassing the AOG system IAW PNPS 2.2.106 Cue: An operator i s bypassing AOG IAW PNPS 2.2.106 2009 NRC JPM ROISRO COO1

Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 7 Step 4.2 [5]a,b,c - whenever the H2 concentration downstream of the recombiner is greater than or equal to 2% continuously monitor...

Standard: Continuously monitors parameters at step 4.2151 a,b,c at Panel CP 600.

Comment:

4 Performance Step: 8 Step 4.2 [5]d,e - whenever the H2 concentration downstream of the recombiner is greater than or equal to 2% continuously monitor...

Standard: Directs a field operator to continuously monitor the parameters for recombiner operations locally at Panel C75.

Comment: SRO termination.

Terminating Cue: This .lPM is complete.

STOP TIME:

2009 NRC JPM RO/SRO COO1

Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2009 NRC JPM ROISRO COO1 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2009 NRC .IPM ROISRO COO1

Page 7 of 7 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: The plant is operating at 50% power. High hydrogen concentration is suspected downstream of the AOG Recombiners.

INITIATING CUE: You have been directed to perform PNPS 2.4.141 "Abnormal Recombiner Operation" Section 4.2 and identify abnormal conditions, if any.

SRO ONLY - Take appropriate actions for abnormal conditions, if any.

2009 NRC JPM RO/SRO COO1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: PILGRIM Task No.:

Task

Title:

Perform Section of Control Room JPM No.: 2009 NRC RO JPM Readings PNPS 2.1.35 ATT.2 COO2 t

KIA

Reference:

2.1.18 3.6 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testina:

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

Initial Conditions: The plant is operating at 100% power Task Standard: Determines that 5 readings are OOS Required Materials: NIA General

References:

PNPS 2.1.35 Att.2 Initiating Cue: You are directed to complete the 0800 - 1200 control room readings IAW PNPS 2.1.35 Att.2.

Time Critical Task: NO Validation Time: 15 minutes 2009 NRC JPM RO COO2

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

1. Initialize simulator to IC14.

2. Using Instructor Overrides, set the following control room indications to the values below C905: CRD MTR CURRENT PUMP A - 39 amps C904: RWCU NON-REGEN OUTLET TEMP (PT #3) TI-1290 45 degrees C2: CONTROL OIL PRESS (PI-4405) - 205 PSI (Adjust Control Room Indication until it reads 205)

CST Tank level "A" Ll-3503 - 28.5, "B" Ll-3508 - 29 Execute LP #5, Control Room Log Readings (NRCO9 Config.)

2009 NRC JPM RO COO2

Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION (Critical Steps denoted with a check (d) mark)

START TIME:

Performance Step: 1 Reviews PNPS 2.1.35, Att.2 Standard: Obtains PNPS 2.1.35, Att.2 Comment: Provide candidate with 2.1.35 Att.2 4 Performance Step: 2 Records Control Room readings Standard: Determines that CST TANK A Ll-3503 is OOS low (28.5 Ft)

Comment:

4 Performance Step: 3 Records Control Room readings Standard: Determines that CST TANK A Ll-3508 is OOS low (29 Ft)

Comment:

4 Performance Step: 4 Records Control Room readirlgs Standard: Determines that C2: CONTROL OIL PRESS (PI-4405) - 205 PSI, is 00s Low 2009 NRC JPM RO COO2

Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION -

Comment:

.( Performance Step: 5 Records Control Room readings Standard: Determines that C905: CRD MTR CURRENT PUMP A - 39 amps, is OOS High Comment:

Performance Step: 6 Records Control Room readings Standard: Determines that C904: RWCU NON-REGEN OUTLET TEMP (PT #3) TI-1290 45 Degrees F, is OOS Low Comment:

.( Performance Step: 7 Reads Step on page 14 to perform a backpanel walkdown Standard: Determines that C904: RWCLl NON-REGEN OUTLET TEMP (PT #3) TI-1290-2 .- 45 Degrees F, is OOS Low CUE: Another operator will complete that task Terminating Cue: This JPM is complete.

STOP TIME:

2009 NRC JPM RO COO2

Appendix C Page 5 of 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2009 NRC JPM RO COO2 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2009 NRC JPM RO COO2

Appendix C Page 6 of 6 Form ES-C-I JPM CUE SHEET INITIAL CONDITIONS: The plant is operating at 100% power.

INITIATING CUE: You are directed to complete the 0800 - 1200 control room readings IAW PNPS 2.1.35 Att.2.

2009 IVRC JPM RO COO2

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: PILGRIM Task No.:

Task

Title:

Recirc Pump Speed &Jet Pump JPM No.: 2009 NRC RO JPM EC Operability Surveillance Check KIA

Reference:

2.2.12 3.7 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testina:

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

Initial Conditions: The plant is operating at 90% power following a reactor plant startup 2 days ago. Daily Log Tests 17 & 17A have not yet been completed.

Task Standard: Determines that Required Materials: NIA General

References:

PNPS 2.1.1 5 Daily Log Test 17 & 17A Initiating Cue: You are directed to perform PNPS 2.1.1 5 Daily Log Test 17 & 17A for Recirc Pump Speed and Jet Pump Operability and determine if acceptance criteria is met.

Time Critical Task: NO Validation Time: 15 minutes 2009 NRC JPM RO EC

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

1. Initialize simulator to IC14

2. Insert Malfunction RR19, Jet Pump Riser Failure

3. Allow Simulator to stabilize

4. Verify Epic is operating 2009 NRC JPM RO EC

Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION (Critical Steps denoted with a check (d) mark)

START TIME:

Performance Step: 1 Obtains PNPS 2.1.15 Daily Log Test 17 & 17A Standard: Reviews PNPS 2.1.15 Daily Log Test 17 & 17A Comment: Provide candidate with BLANK copy of PNPS 2.1.15 Daily Log Test 17 & 17A

.( Performance Step: 2 IAW Daily test # I 7- Log Pump speeds Standard: Determines acceptance criteria is met and no corrective action is required Comment: Refer To Key for Actual Values 4 Performance Step: 3 IAW Daily Test # I 7A - log pump speeds and flows. Determine if Recirc Pump Flow and Jet Pump Loop Flow are within predicted limits.

Standard: Records readings and, using tables, determines that actual jet pump loop flow is outside the predicted limits for the current recirc pump speed. Therefore Step #6 is UNSAT.

Comment: Refer to Key for Actual Values 2009 NRC JPM RO EC

Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 4 Determine the Recirc Pump Loop flow to Speed Ratio Standard: Determines that the ratio differs by >5% and marks Step #7(b) as FA1LED Reports results to CRS (evaluator)

Comment: Refer to Key for Actual Values Terminating Cue: This JPM is complete.

STOP TIME:

2009 NRC JPM RO EC

Appendix C Page 5 of 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2009 NRC JPM RO EC Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2009 NRC JPM RO EC

Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET IhllTlAL CONDITIONS: The plant is operatiqg at 90% power following a reactor plant startup 2 days ago. Daily Log Tests 17 & 17A have not yet been completed.

INITIATING CUE: You are directed to perform PNPS 2.1.1 5 Daily Log Test 17 & 17A for Recirc Pump Speed and Jet Pump Operability and determine if acceptance criteria is met.

2009 NRC JPM RO EC

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: PILGRIM Task No.: NEW Task

Title:

Determine Offsite Release Rate IAW JPM No.: 2009 NRC JPM RO RC PNPS 2.1.1 5 Daily Log Test #34.

KIA

Reference:

K/A: 2.3.11 (3.8)

Ability to control radiation releases.

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testina:

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: Plant conditions are as follows:

The plant is at 100% power.

Plant conditions are stable.

Task Standard:

Note:

Required Materials: PNPS 2.1 .I 5 Att.2 Page 109 of 150 General

References:

PNPS 2.1 . I 5 Att.2 Initiating Cue: You are directed to determine Offsite Release Rate IAW PNPS 2.1.1 5 Daily Log Test #34 2009 NRC JPM RO COO2

Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: NO Validation Time: 15 minutes 2009 NRC JPM RO COO2

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

1. Must set up values for Main Stack and Reactor Building Vent Monitors that exceed the ODCM limit as indicated on Graph Figure 4.

2009 NRC JPM RO COO2

Appendix C Page 4 of 8 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Performance Step: 1 Obtain and review PNPS 2.1.15 , Att.2 Daily Log Test #34 Standard: Obtains and reviews PNPS 2.1.15 , Att.2 Daily Log Test #34 Comment:

2009 NRC JPM RO COO2

Appendix C Page 5 of 8 Form ES-C-1 PERFORMANCE INFORMATION 2009 NRC JPM RO COO2

Appendix C Page 6 of 8 Form ES-C:

PERFORMANCE INFORMATION Performance Step: 10 Initial performed By and submit for review Standard: Initials performed By and submit for review Comment:

Terminating Cue: The JPM is complete after the candidate discusses their findings.

STOP TIME: TIME CRITICAL STOP TIME:

2009 NRC JPM RO COO2

Appendix C Page 7 of 8 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance.Measure No.: 2009 AUDIT JPM RO COO1 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2009 NRC JPM RO COO2

Appendix C Page 8 of 8 Form ES-C-1 JPM CUE SHEET -

Initial Conditions: Plant conditions are as follows:

The plant is at 100% power.

Plant conditions are stable.

Initiating Cue: You are directed to determine Offsite Release Rate IAW PNPS 2.1 . I 5 Daily Log Test #34 2009 NRC .IPM RO COO2

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: PILGRIM Task No.:

Task

Title:

Verifv Recorr~binerO~era'tion, JPM No.: 2009 NRC ROISRO JPM COO1 KIA

Reference:

2.1.25 2.8 I3.1 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testina:

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

Initial Conditions: The plant is operating at 50% power. High hydrogen concentration is suspected downstream of the AOG Recombiners.

Task Standard: Determines recombiner delta-temperature indicates recombiner is overheated.

Required Materials: N/A General

References:

PNPS 2.4.141 Initiating Cue: You have been directed to perform PNPS 2.4.141 "Abnormal Recombiner Operation" Section 4.2 and identify abnormal conditions, if any.

SRO ONLY - Take appropriate actions for abnormal conditions, if any.

Time Critical Task: NO Simulator Booth: TAKE SIMULATOR OUT OF FREEZE Validation Time:

2009 NRC JPM ROISRO COO1

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

1. Initialize simulator to 50% power.

2. Insert Instructor Overrides on CP600 Hydrogen Recorder AR-R603 so that both channels indicate 1.80%

3. Turnoff CP-6OOL Alarms:

A-7 "H2 Analyzer A H2 CONC HI" B-7 "H2 Analyzer B H2 CONC HI" A-8 " After CNDSR LOOP SEAL LVL HILO"

4. Insert malfunction OG05 " Water In Offgas System". Allow the simulator to run until the Recombiner Exit temperature, Pt.5 on Recorder TR-9250, Lowers to < 425 degrees.

5. Freeze Simulator

6. Place Danger tags on the MO-9205 and MO-9204.

7. Ensure Preheater exit terr~peratureis >350 degrees ( procedure NOTE at step 4.2 [I])

2009 NRC JPM ROISRO COO1

Page 3 of 7 Form ES-C-1 PERFORMANCE INFORMATION (Critical Steps denoted with a check (4mark)

START TIME:

Performance Step: 1 Proceeds to PNPS 2.4.141 Section 4.2 - High Hydrogen Concentration Downstream of the Recombiners.

Standard: Enters PNPS 2.4.1 4.1 Section 4.2 Comment:

Performance Step: 2 Section 4.2 Step [ I ] - TRIP the ETS using "ETS SHUTDOWN" push button on Panel CP600.

Standard: Depresses "ETS SHUTDOWN" pushbutton Comment:

SIM BOOTH: Ensure Preheater exit temperature is >350 degrees NOTE Reducing Reactor power will reduce recombiner exit temperature by reducing hydrogen production. Preheater exit temperature should be greater than 350°F at 100% power.

.\I Performance Step: 3 Section 4.2 Step [2] - If both H2 analyzers are indicating greater than or equal to 4%....

Standard: Reviews above NOTE.

Determines that both H2 analyzers are not greater than 4%

Comment:

2009 NRC JPM ROISRO COO1

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION 4 Performance Step: 4 Section 4.2 [3] - Verify recombiner operation for the power level being maintained by referring to Att. 1 Att. 2 as applicable.

Standard: Evaluates recombiner delta-temperature utilizing Att. 1 and determines recombiner delta-temperature is in the questionable region of the graph.

Comment: NOTE The procedure step states to use Att.1 Att.2. Prompt candidate to evaluate using both graphs if only one is used.

4 Performance Step: 5 Evaluate recombiner delta-temperature utilizing Attachment 2 Standard: Determines recombiner delta-temperature is below the Low Limit of the graph Comment: Termination for RO ONLY, SRO continues to next step Performance Step: 6 Direct placing the standby recombiner in service.

Standard: AOG will be directed to be bypassed IAW PNPS 2.2.106 while maintaining steam dilution and air purge through the recombiner and the charcoal beds Cue: If the standby recombiner is directed to be placed in service, "the

'B' recombiner is unavailable" Direct maintaining steam dilution and air purge on the 'A' recombiner.

Cue: An operator has been assigned to initiate air purge on 'A' recombiner and the charcoal beds.

Evaluator Note: The candidate may indicate a power reduction is necessary when performing the following step. If so, it has been directed to the 905 operator.

4 Direct bypassing the AOG system IAW PNPS 2.2.106 Cue: An operator is bypassing AOG IAW PNPS 2.2.106 2009 NRC JPM ROISRO COO1

Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMA1-ION Performance Step: 7 Step 4.2 [5]a,b,c - whenever the H2 concentration downstream of the recombiner is greater than or equal to 2% continuously monitor...

Standard: Continuously monitors parameters at step 4.2[5] a,b,c at Panel CP 600.

Comment:

Performance Step: 8 Step 4.2 [5]d,e - whenever the H2 concentration downstream of the recombiner is greater than or equal to 2% continuously monitor...

Standard: Directs a field operator to continuously monitor the parameters for recombiner operations locally at Panel C75.

Comment: SRO termination.

Terminating Cue: This JPM is complete.

STOP TIME:

2009 NRC JPM ROISRO COO1

Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2009 NRC JPM ROISRO COO1 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2009 NRC JPM ROISRO COO1

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

INITIAL CONDITIONS: The plant is operating at 50% power. High hydrogen concentration is suspected downstream of the AOG Recombiners.

INITIATING CUE: You have been directed to perform PNPS 2.4.141 "Abnormal Recombiner Operation" Section 4.2 and identify abnormal conditions, if any.

SRO ONLY - Take appropriate actions for abnormal conditions, if any.

2009 NRC .IPM ROISRO COO1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: PILGRIM Task No.:

Task

Title:

Perform &Assess requirements for a JPM No.: 2009 NRC SRO JPM Recirc Pump Start COO2 WA

Reference:

2.1.7 4.7 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testina:

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: "B" Recirc MG Set tripped 2 days ago and single loop operations were commenced.

The Recirc MG Set fault has been repaired and preparations are underway to restart the "B" Recirc MG set IAW Section 7.4 of 2.2.84 "Reactor recirculation System".

EPIC is not available.

Task Standard:

Required Materials: N/A General

References:

PNPS Initiating Cue: You are directed to perform PNPS 2.2.84 Att [5] Section B for temperature limits in preparation for the start of "B"Recirc Pump.

Report if the pump can be started or, if not, requirements not met and actions needed to place the pump in service.

Time Critical Task: NO 2009 NRC JPM SRO COO2

Appendix C Job Performance Measure Form ES-C-1 Worksheet Validation Time: 15 minutes 2009 NRC JPM SRO COO2

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

1. Initialize simulator to IC12

2. Trip "B" Recirc pump manually and close the discharge valve

3. Manipulate "A" Recirc & Rods such that:

Core Flow is between 27.6 and 36 mlbm/hr Core Operating Point is outside of the Buffer Region

4. Insert Instructor Overrides such that:

"B" Recirc Loop suction temp is 55 degrees less than the "A" Recirc Loop suction temp as indicated on TR-260-151 A/B Vessel Bottom head drain temp (Pt.3 on TR-263-104) is 170 degrees below current vessel saturation temperature

5. Shutdown EPIC using remote function

6. Ensure that operating recirc pump speed is <50%

6. Freeze the simulator 2009 NRC JPM SRO COO2

Appendix C Page 4 of 8 Form ES-C-1 PERFORMANCE INFORMATION START TIME:

Performance Step: 1 Obtains PNPS 2.2.84, Att.5 Standard: Reviews Limitations of PNPS 2.2.84, Att.5 Comment: Provide candidate with blank copy of PNPS 2.2.84 Attachment 5 Steps 4 Performance Step: 2 fa) RECORD the following data:

(1) Vessel Dome Pressure (2) Saturation Temperature (3) Bottom Head Drain Temperature (point 3 on TRU-263-104 or RXXOO6 )

(b) VERIFY Limitations Step B.[l](a) is met.

CRS lnit Standard: Records data & determines that limitations of Step B. [I](a) are NOT met.

(a) The Reactor Recirculation Pumps shall not be started UNLESS the coolant temperatures between the dome and the bottom head drain are within 145°F (Tech Spec 3.6.A.5).

Per Procedure Note:

If required, Bottom Head Drain temperature can be adjusted in accordance with PNPS 2.4.24, "Reactor Vessel Cold Water Stratification . Attachment 1 for Reactor coolant temperature N

References PNPS 2.4.24, Att.1 Step 3, and directs raising Bottom Head Flow to RWCU.

CUE: If the candidate begins to reference 2.4.24 and directs raisiug flow, State that another operator will perform that task and they should continue with this attachment Comment: Bottom Head drain temperature will be approximately 170 degrees below current vessel saturation temperature 2009 NRC JPM SRO COO2

Appendix C Page 5 of 8 Form ES-C-1 PERFORMANCE INFORMATION 4 Performance Step: 3 (c) RECORD the following data:

(1) required, PERFORM a controlled heatup of the idle loop in accordance with base document Step 7.4[4].

Initials (2) Recirculation loop temperature on idle pump OF (3) Recirculation loop temperature on operating pump OF (d) VERIFY Limitations Step B.[l](bf is met.

CRS lnit Standard: Records the data and determines that the limitations of Step B. 113 (b) are not met.

(b) The pump in an idie Recirculation Loop shall not be started UNLESS the temperature of the coolant within the idle RecirculationLoop is within 50°F of Reactor coolant temperature (Tech Spec 3.6.A.4 also meets the intent of FSAR Section 4.3.7).

References and directs step 7.4[4] for controlled heatup of idle loop (below)

[4] IF the pump to be started requires a controlled heat up lo ensure compliance with Technical Specifications Sections 3.6.A.4 and 3.6.A.5, ESTABLISH a heatup rate (not to exceed 5O0F/hour)as follows:

(a) RECORD initial data on Section C of Attachment 5 (OPER-19).

(b) CRACK OPEN MO-202-5A (B), Pump Disch Vlv.

(cf IF the heatup rate becomes excessive, REDUCE flow through the pump by throttling closing M0-2025A (B), Pump Disch Vlv.

(d) RECORD data every 15 minutes until temperature has stabilized for three consecutive readings on Section C of Attachment 5 (OPER-19).

CUE: If the candidate directs actions in 7.4, State that another operator will perform that task and they should continue with this attachment.

Comment: "B" Recirc Loop suction temp will be approximately 55 degrees less than the "A" Recirc Loop suction temp as indicated on TR-260-151 A/B 2009 NRC JPM SRO COO2

Appendix C Page 6 of 8 Form ES-C-1 PERFORMANCE INFORMATION 4 Performance Step: 4 (el VERIFY operating pump speed is less than 50%.

CRS lnit Standard: Verifies that operating pump speed is < 50%

Comment: See key for actual values Terminating Cue: This JPM is complete.

STOP TIME:

2009 NRC JPM SRO COO2

Appendix C Page 7 of 8 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2009 NRC JPM SRO COO2 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2009 NRC JPM SRO COO2

Appendix C Page 8 of 8 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: "B" Recirc MG Set tripped 2 days ago and single loop operations were commenced.

The Recirc MG Set fault has been repaired and preparations are undeway to restart the "B" Recirc MG set IAW Section 7.4 of 2.2.84 "Reactor recirculation System".

EPIC is not available.

INITIATING CUE: You are directed to perform PNPS 2.2.84 Att [5] Section B for temperature limits in preparation for the start of "B" Recirc Pump.

Report if the pump can be started or, if not, requirements not met and actions needed to place the pump in service.

2009 NRC ,IPM SRO COO2

Appendix C Page 1 of 5 Form ES-C-1 PERFORMANCE INFORMATION Facility: PILGRIM Task No.:

Task

Title:

Review RBCCW Pump " A System JPM No.: 2009 NRC SRO JPM Quarterly Operability PNPS 8.5.3.1 - -

EC Determine pump operability WA

Reference:

2.2.12 4.1 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

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

Initial Conditions: The RBCCW Pump "A" System Quarterly Operability Test - PNPS 8.5.3.1 -

has been completed.

All RBCCW System components are operable.

Task Standard:

Required Materials: N/A General

References:

PNPS Initiating Cue: Review the RBCCW Pump " A System Quarterly Operability Test -

PNPS 8.5.3.1 - Review Acceptance criteria and Determine pump operability Time Critical Task: NO Validation Time: 15 minutes

Appendix C Page 2 of 5 Form ES-C-1 PERFORMANCE INFORMATION SIMULATOR SETUP (Critical Steps denoted with a check ($ mark)

START TIME:

Performance Step: 1 Obtain RBCCW Pump "A" System Quarterly Operability Test - PNPS 8.5.3.1 Att.1A Standard: Obtains RBCCW Purnp "A" System Quarterly Operability Test - PNPS 8.5.3.1 Att.lA Comment: Provide completed surveillance to candidate.

Appendix C Page 3 of 5 Form ES-C-1 PERFORMANCE INFORMATION 4 Performance Step: 2 Reviews Acceptance Criteria P-202A - QUARTERLY AND BIENNIAL COMPREHENSIVE INSERVICE PUMP T t m S H t tI Hydraulic and vibration reference values were obta~nedduring conduct of PNPS 8 5 3 18 on M3M.

%% Mark as "NF" for 81-CompTest Xw Mark as " N F icu P u a M y Test CALCULATIONS:

TOTAL DYNAMIC HEAD.AT 2040 GPM (TDH)

TDH = (Disch Press at 2040 GPM - Running Sutiin Pressure) X 2.309 TDH = ( psig - psis) x 2.303 D~scharge SuCtKKl TDH = n Standard: 1. Determines that Total Dynamic Head Calculation is incorrect.

2. The correct calculation puts you in the Required Action Range.

3. TS 3.5.B.3 Action A.1. applies - 7 days Comment: All 3 items are Critical Steps - See Key 4 Performance Step: 3 Reviews Acceptance Criteria Standard: 4. Determines Pump Inboard Vertical Vibration is in the Alert Range Comment: Item is a Critical Step Terminating Cue: This JPM is complete.

STOP TIME:

Page 4 of 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2009 NRC .IPM SRO EC Examinee's Name:

Date Performed:

Facility Evaluator:

IVumber of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

Appendix C Page 5 of 5 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: The RBCCW Pump " A System Quarterly Operability Test - PNPS 8.5.3.1 - has been completed.

All RBCCW System components are operable.

INI'TIATING CUE: Review the RBCCW Pump " A System Quarterly Operability Test

- PNPS 8.5.3.1 - Review Acceptance criteria and Determine pump operability

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: PILGRIM Task No.: NEW Task

Title:

Perform Daily Log Test #31 - High JPM NO.: 2009 NRC JPM SRO Range Effluent Monitors -

RC KIA

Reference:

WA: 2.3.1 1 (3.8)

Ability to control radiation releases.

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testina:

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: Plant conditions are as follows:

The plant is at 100% power Plant conditions are stable.

Task Standard: Performs the test and determines that Reactior Building Vent Effluent rad Monitor is OOS and TS Table 3.2.F. Action (7) applies Evaluator Note: See attached copy of Test and Tech Spec Required Materials: PNPS 2.1.1 5 Daily Log test #31 General

References:

PNPS 2.1.15 Daily Log test #31 Initiating Cue: You are directed to perform Daily Log Test #31 - High Range Effluent Monitors and determine any required actions.

2009 NRC JPM SRO RC

Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: NO Validation Time: 15 minutes 2009 NRC JPM SRO RC

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

1. Must set up value for RBV Rad Monitor "RT-1001-609" to indicate <lo3 Rlhr when the switch is placed in "check.

2009 hlRC .IPM SRO RC

Appendix C Page 4 of 8 Form ES-C-1 PERFORMANCE INFORMATION START 'TIME:

Performance Step: 1 Obtain and review PNPS 2.1 .I 5 , Daily Log Test #31 Standard: Obtains and reviews PNPS 2.1.15 , Daily Log Test #31 Comment:

Dsilv Loq T e d M l - H~ahRange EMuent Mon~lors Performance Step: 2 Once each day perform an mtrumentcheck of the H h Ran EMumt M o n h on Panel CQlO and canpare the reiuitsto me ER- ~onltorRemder #k-IW E08.

(1) Note: Not requbwl to be openwe when in the Cdd Shutdown M. Refuel made to satisfy the requirements of Tables 3.2.Fand 4.2.F (Tech Spec Bases 32).

W a rnaltunclioninglnswmcni or recmder is suspected, &mil a Werk Rquesi (WR).

Dunng phnl operatitons, TE Ex Monltw and conerpond~n on recordar nuy not ndlcate fun aownwle due to detector mmlarea radIauon level ( 8 6n 8353)

Standard: Review the statements at the beginning of the test Comment:

2009 NRC JPM SRO RC

Appendix C Page 5 of 8 Form ES-C-1 PERFORMANCE INFORMATION '

2009 NRC .IPM SRO RC

Appendix C Page 6 of 8 Form ES-C-1 PERFORMANCE INFORMATION (7) With less t h a n the minimum number of operable instrument channels, r e s t o r e the f?

r e s t o r i n g the channela t o operable s i a t u s I:

Terminating Cue: The JPM is complete after the candidate discusses their findings.

STOP TIME: TIME CRI'TICAL STOP 'I'IME:

2009 NRC JPM SRO RC

Appendix C Page 7 of 8 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2009 AUDIT JPM SRO RC Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2009 hlRC ,IPM SRO RC

Appendix C Page 8 of 8 Form ES-C-1 JPM CUE SHEET Initial Conditions: Plant conditions are as follows:

The plant is at 100% power.

Plant conditions are stable.

Initiating Cue: You are directed to perform Daily Log Test #31 - High Range Effluent Monitors and determine any required actions.

2009 NRC JPM SRO RC

2009 NRC SRO JPM EP NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE (SRO Only)

TITLE: EMERGENCY PLAN IMPLEMENTATION OPERATOR: DATE: --

EVALUATOR: EVALUATOR SIGNATURE: --

CRI'TICAL TIME FRAME # I : Required Time (min): 15 Actual Time (min):

(Assessment and Declaration)

CRITICAL TIME FRAME #2: Required Time (min): 15 Actual Time (min):

(Notification of Off-Site Agencies) 1 PERFORMANCE TIME: Average Time (min): 20 Actual Time (min):

JPM RESULTS*: SAT UNSAT NEEDS IMPROVEMENT (Circle one) *Refer to Grading Instructions at end of JPM SYNOPSIS: The SRO will assess plant conditions using the information provided, compare plant conditions against the Emergency Action Level (EAL) criteria and declare the appropriate EAL. Following the initial declaration, the SRO will activate the PNPS Emergency Response Organization (ERO) and complete the notification of off-site agencies.

TASK The SRO will declare an Alert based on EAL 7.3.1.2, Aircraft crash on the facility STANDARD: affecting plant operation, within 15 minutes. Following initial declaration the SRO will activate the PNPS ERO and complete the notification of off-site agencies in accordance with EP-IP-100. Notification of off-site agencies shall be completed withiti 15 minutes of initial declaration.

EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant Simulate -x Simulator Control Room Prepared: Date: -

Reviewed: Date: -

Date: --

Approved: Superintendent, Operations Training (or Designee)

2009 NRC SRO JPM EP REVISION LOG Revision Number: 0 Date Originated: 11/20/2008 Pages Affected: All

Description:

New JPM

2009 NRC SRO JPM EP TASK

Title:

Task Number K&A SYSTEM: K&A RATING:

Classify events requiriqg Emergency 015-05-02-013 Generic 2.4.40 2.7 / 4.5 Plan implementation.

REFERENCES:

EP-IP-100 Emergency Classification and Notification SIMULATOR CONDITIONS:

1. The simulator may be initialized to any IC.

2. Using remote function MT22, set outside weather conditions to:

a) Wind direction on 220 foot met tower: 264 degrees b) Wind speed on 220 foot met tower: 13 mph

3. Allow simulator to run a sufficient amount of time to allow the 15 minute averages on the met tower display to stabilize.

4. The Digital Notification System is Operable and in the Training Configuration.

GENERAL TOOLS AND EQUIPMENT:

1. None CRITICAL ELEMENTS:

Critical elements are shaded in gray within the body of this document.

OPERATOR BRIEF:

1. State the following paragraph IF this is the first performance in this setting:

a) "All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task. When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will state the task conditions and answer any questions, then provide a cue to begin".

2009 NRC SRO JPM EP

2. Always state the following two paragraphs:

a) "The title of this JPM is: "Emergency Plan Implementation" b) "The task conditions are as follows:

Attachment 1 of this JPM includes the following information. Provide the operator a copy of Attachment 1.

i) PNPS was at full power when a load reject and loss of off-site power occurred.

ii) All control rods fully inserted.

iii) Both Emergency Diesel Generators Started and 4160 VAC buses A5 and A6 have been re-energized. All other 4160 VAC buses have de-energized.

iv) The security shift commander has called the control room and reported that a small aircra?

crashed into the switchyard and that three 345 KV ACBs have been severely damaged.

Smoke is issuing from the aircraft and off-site fire fighting assistance has been requested.

No PNPS equipment is currently engulfed by fire.

v) Following the scram, RPV Level lowered to - 47 inches. Both RClC and HPCl auto started and aligned for injection.

vi) HPCl was manually shifted to pressure control when RPV level recovered to the normal band.

vii) RPV level is currently stable at 20 inches being controlled by RClC viii) RPV pressure is currently 900 psig and slowly lowering with HPCl in pressure control.

ix) The Control Room Supervisor is coordinating overall plant response, including fire brigade response and notification of Plymouth Fire.

x) All containment parameters are normal, with the exception of Torus Water Temperature.

Torus Water Ternperature has just exceeded 80 degrees.

xi) The security shift commander has determined that this is not a security event and that plart access and egress has not been impacted.

xii) Weather conditions are as indicated on Panel MT1

3. Solicit and answer any questions the operator may have.

INITIATING CUE:

State the following:

"[Operator's name], you are the Third SRO on shift. The Shift Manager is incapacitated.

Implement the Emergency Plan as required.

2009 NRC SRO JPM EP PERFORMANCE:

Notes This task is covered in EP-IP 100, Emergency Classification and I\lotification. Notification of Off-site Agencies will be completed via the Digital Notification Network.

Attachment 2 of this .IPM contains the anticipated information to be enterecl for the initial notification to off-site agencies and may be used as an aid in evaluating the accuracy of the initial notification.

START TIME:

CRITICAL TIME FRAME #1 START TIME:

Procedure Step:

IProcedure steps and NOTE Attachments may be performed in parallel when appropriate to facilitate I

timelv notifications

[I] When indications of abnormal conditions are received, personnel will verify the symptoms/indications and then compare them with the Emergency Action Level ;

(EP-IP-100.1 Attachment 1, Emergency Action Levels).

Standard Operator refers to EP-IP-100 to commence the evaluation and concurrent reviews EP-IP-100.1, Attachment 1, Emergency Action Levels. --

Cue Notes EP-IP-100 is a "Reference Use" procedure. The operator may go directly t I the "EAL Chart" to determine the classification. This is acceptable.

Results SAT E l UNSAT n .-

2009 NRC SRO elPM EP 1 Procedure Step: 1 5.2 INITIAL DECLARATION OF AN EMERGENCY FROM THE CONTROL ROD^

7 I I [I] Announce to the Control Room operating staff I

I I (a) That an emergency has been declared; I

I1 I (b)

(c)

The emergency classification level; Who has assumed the role of Emergency Director.

I I

Standard Operator Announces that:

An Alert has been declared due to an Aircraft crash on the facility affecting plant operation at time (current time) and that helshe has assumed the role of the Emergency Director.

Cue -

Notes Expected format of the announcement is in the form of a 'Crew Update".

Exact verbiage above is not required provided the information is provided.

~4 Results SAT 0 UNSAT n -

CRITICAL TIME FRAME #1 END TIME:

2009 NRC SRO JPM EP CRITICAL TIME FRAME #2 START (Same as Critical Time Frame #I End Time)

TIME:

Procedure Step: f2] Conduct initial emergency notifications as follows:

(a) If the event involves a security compromise or security considerations, ther contactlconsult with the Security Shift Commander or Supervisor to determ ne whether ERO members should be directed to report to their respective Emergency Response Facilities or whether some alternate response is appropriate.

Standard Operator determines that event does not involve a security compromise or security considerations and continues to next step.

Cue Notes Initial conditions indicated that a security event was not in progress. -

Results SAT E l UNSAT 1 Procedure Step: (b) If the normal site egress/accesspoint is unavailable for site evacuation, the21 direct the Security Shift Commander or Security Supervisor to:

(1) Contact Maintenance to remove the vehicle barriers blocking either t , ~ e I&S or Shorefront gates.

(2) Dispatch Security personnel to unlock the appropriate gates.

(3) Redirect vehicles and wrsonnel as appropriate.

Standard Operator determines that normal site egress/access is available and continues to next step.

Cue Notes Initial conditions indicated that a security event site egress/access was not imlsacted bv the event.

Results SAT n UNSAT

I I

6.

I Procedure Step:

I (c) 2009 NRC SRO JPM EP If the GaiTronics is inoperative during notifications to Station personnel at a n time, then determine alternate means to disseminate information to plant personnel.

Standard ( Operator determines that GaiTronics is available and continues to the next Cue I

(

I I step.

Notes No indication has been provided to indicate that GaiTronics is unavailable.

Operator may do a brief test of the GaiTronics system.

-4

-1 I

Results SAT 0 UNSAT

7. Procedure Step: (d) fe)

For events which are classified as a General Emergency, complete the Genera Emergency Notification Checklist (Attachment 4).

For events which are classified as a Site Area Emergency, complete the Site Area Emergency Notification Checklist (Attachment 3).

-7 ff) For events which are classified as an Alert, complete the Alert Notification Checklist (Attachment 2).

fg) For events which are classified as an Unusual Event, complete the Unusual Event Notification Checklist (Attachment 4).

I 1 /

Standard Operator continues utilizing Attachment 2 of EP-IP-100.

I Cue Notes

(

Results SAT n +

1 8. 1 Procedure Stew 1

I

~OmFccATioN OF STAnON PFRsONNFt -1 CAUnON M n g a trecurity threat, it may be advisable to sound an alarm.

Ensure appropriate m88ege content is prepared before a n m m e r r t .

Soundhave the Control Room sound the Operator Recall Alarm and make the following announcement over the public-address system TWICE:

, A. "Attention all personnel, attention all personnel: An Alert has been declared due to u f gfescri~tionof initiatina evenf). Members of the Emergency Response Organization (Choose one:)

(1) Remain in place; await further instructions.

' (2) Report to your assigned Emergency Response Facility.

(3) CRfrSClOSC staff report to Chiltonville staging area and EOFlMedia Center staff report to your assigned Emergency Response Facility.

All visitors, all nonessential contractor personnel, all declared pregnant females, an3 all petarons with disabilities - (Choose one:)

(1) Remain in place; await further instructions.

I (2) Please leave the s~teat this time." 11

2009 NRC SRO JPM EP 1 Standard Operator:

1. Sounds the Operator Recall Alarm

2. Makes the above announcement over ,the GaiTronics, specifying that tt-e ERO is to report to their assigned Emergency Response Facility.

3. Directs that all visitors, nonessential personnel, declared pregnant females and disabled personnel leave the site.

4. Repeats the announcement.

1 Cue -

L Notes Direction (1) and (3) to the ERO are only applicable during security events.

Direction (1) to nonessential personnel is only applicable during security events.

Results SAT n UNSAT

9. Procedure Step: 5. If there is a localized emergency (for example; high radiation, fire), announce its type and location and instruct personnel to stand clear of this area.

Standard Operator announces over the GaiTronics that there is a fire in the switchyard and that all unnecessary personnel should stay clear of the area.

I Cue Notes Results

10. Procedure Step: C. If there is a potential for an airborne radiological release, consider announcing that there will be no eating, drinking, or smoking until further notice.

Standard Operator determines that there is no potential for airborne release and continues to the next step.

I Cue Notes Results SAT n

2009 NRC SRO JPM EP 2009 NRC SRO JPM EP I EVALUATOR CAUTION: I 1 Following the process described below will actually ACTIVATE the pagers for the ERO PRIOR to the operator commencing CANS activation, CUE that CANS has been activated and that th 3 operator is toexplain the process that helshe would utilize. - _I Procedure Step: B. Contact CANS using one of the following:

1. Preprogrammed speed dial button located on the designated Control Room Notification telephone (phone located in E-Plan Cabinet):

2. Any touch-tone telephone line by calling 1-508-732-6687. 11 C. Listen for the CANS introductory message: "This is the remote activation module.

Please enter your scenario activation password followed by the # sign". 11 D. After hearing the CANS introductory message, implement one of the following:

1. Press the preprugrammed speed dial button for the scenario activation password on the designated Control Room Notification telephone; OR

2. Manually enter the nine-digit scenario activation password followed by the # sign. [ 1 E. After CANS accepts the scenario activation password, CANS will then state the following two verbal prompts:

1. 'To start a scenario, enter the scenario ID, followed by the # sign".

2. "Press # alone for more options." I]

F. Start scenario by entering the scenario ID (i.e., CANS activation code) as fofiows:

1. If a DRILL, enter "37455' followed by the CANS three-digit activation code and then the # sign.

2. If NOT A DRILL enter the CANS three-digit activation code followed by the

% sign. [ I G. After entering the CANS activation code, the CANS will state the following two verbal prompts:

1. "To start the scenario, press 3".

2. 'To return to main menu, press #. I1 H. Press 3 to start scenario and CANS will prompt you that "the scenarlo is building" and then immediately state the following verbal prompts:

1. "To start a scenario, press 1".

2. "To stop a scenario, press 2".

3. "To check scenario information, press 3".

4. "To enter a different scenario activation password, press 4 .

5. "To end this call, press # [ 1 Standard Operator locates the dedicated CANS telephone and accurately describes the activation process. -

I Cue EVALUATOR CAUTION:

Following the process described above will actually ACTIVATE the pager ;

for the ERO PRIOR to the operator commencing CANS activation, CUE that CANS ha; been activated and that the operator is to explain the process that helshe would utilize. --

I Notes I - -4 Results SAT 0 UNSAT 0 -

2009 NRC SRO JPM EP m

An initial nobjficcslionrto the C&mfnmwaerlth and lpeal wthorifies must be t r a m withim 15 minut s of the event classification.

A. Within 15 minutes of the event classification, transmit an Initial Notification Form to the Commonwealth and local authorities.

B. In the event the classification changes before the initial notification is transmitted, then implement one of the following actions:

1. If a revision CAN be completed within the original Ifiminute time limit from the previous classification. then revise the Initial NatificationForm with the most current event classificatior and transmit the information to the Commonwealth and local authorities.

2. If a revision CANNOT be comolete(! within the original 15-minute time limit, then transmit the original. unrevised Initial Notification Form within the 15-minute time period with a caveat (if possible or as time permits) that a change in classification is forthcoming and in addition prepare and transmit the notification for the change in classification within its 15-minute time limit.

1 1 C. Initlate DNN Initial Notification instructions as follows:

I 1 1 Record EAL number and time declared in space prov~ded.

EALNumber: . .- . 2 (Obtain from ED) Time Declared:

I Standard Operator records "7.3.1.2" and the time of declaration in the space provide 1 in the procedure. -

Cue I I

Notes I 1

I Results SAT UNSAT I

2 Open the "DNN" program (tcon available on "DNN" computer desktop) to fill out and transm~tthe ln~tlalNot~ficationForm. if the automated DNN system IS not available, then go to Attachment 7 and implement backup notification instructions

2009 NRC SRO JPM EP iete and obtain tD approval. Hard copy for kD signature -3 Cue: This completes this JPM.

CRITICAL TIME FRAME #1 END TIME:

STOP TIME:

2009 NRC SRO JPM EP JPM GRADING INSTRUCTIONS CRITERIA FOR SATISFACTORY EVALUATION

1. 100% of critical elements/steps identified in the JPM successfully completed.

2. Critical Time Frame is met if applicable

3. No actual safety violation (radiological or industrial) requiring evaluator intervention.

CRITERIA FOR UNSAT EVALUATION

1. Any critical elementJstepis graded as "UNSAT"

2. Critical Time Frame is not met if applicable. *

3. Actual safety violation (radiological or industrial) requiring evaluator intervention.

4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, I r otherwise reduced the level of safety of the plant CRITERIA FOR NEEDS IMPROVEMENT EVALUATION

1. One or more non-critical elements/ steps evaluated as UNSAT which indicate the need for remediation.

2. Any relevant Management Expectation/Standardmissed a majority of the opportunities.

ADMINISTRATIVE REQUIREMENTS Any performance deficiencies resulting in an UNSAT or NEEDS IMPROVEMENT evaluation shall be documented on the JPM comment sheet.

Documentation for Satisfactory evaluations need only consist of the cover sheet and any applicable comment sheet(s) provided that a Master Copy of the JPM is on file or captured.

Documentation for UNSAT evaluations shall consist of the entire, as administered JPM, with associated comment sheets.

Documentation for NEEDS IMPROVEMENT evaluations need only consist of the cover sheet and the associated comment sheet(s) describing the operator deficiencies noted, provided that a Master Copy of the JPM is on file or captured and the deficiencies are involving only management expectations. Otherwise, the entire JPM shall be retained.

2009 NRC SRO JPM EP JPM COMMENT SHEET REQUIREMENTS:

Any operator deficiencies resulting in an UNSAT or NEEDS IMPROVEMENT evaluation shall be documented.

Any follow-up questions asked and the operator's response must be documented.

Any operator deficiencies which, in themselves, would not result in an UNSAT evaluation of th s JPM but may, when coupled with pedormance on other JPMs, result in an OVERALL FAILING evaluation for the ,IPM exam should also be documented below.

Any other comments, positive or negative, that the evaluator determines is worth noting.

COMMENTS:

2009 NRC SRO JPM EP AlTACHMENT ONE i) PNPS was at full power when a load reject and loss of off-site power occurred.

ii) All control rods fully inserted.

iii) Both Emergency Diesel Generators Started and 4160 VAC buses A5 and A6 have been re energized. All other 4160 VAC buses have de-energized.

iv) The security shift commander has called the control room and reported that a small aircrafl crashed into the switchyard and that three 345 KV ACBs have been severely damaged.

The aircraft is on fire and off-site fire fighting assistance is recommended. No PNPS equipment is currently engulfed by the fire.

v) Following the scram, RPV Level lowered to - 47 inches. Both RClC and HPCl auto started and aligned for injection.

vi) HPCl was manually shifted to pressure control when RPV level recovered to the normal band.

vii) RPV level is currently stable at 20 inches being controlled by RClC viii) RPV pressure is currently 900 psig and slowly lowering with HPCl in pressure control.

ix) The Control Room Supervisor is coordinating overall plant response, including fire brigade response and notification of Plymouth Fire.

x) All containment parameters are normal, with the exception of Torus Water Temperature.

Torus Water Temperature has just exceeded 80 degrees.

xi) The security shift commander has determitied that this is not a security event and that plar t access and egress has not been impacted.

xii) Weather conditions are as indicated on Panel MT1

2009 NRC SRO JPM EP Attachment 2 Initial Notification Gradinq Aid

/Critical Elements are Shaded Grev)

PILGRlM NUCLEAR POWER STATION INITUL EMERGENCY NOTIFICA TION This is a Training Event Notification Number: 1 Description of Event:

Any of the following events occurring which affect plant operation:

--Aircraft crash on facility.

--Missile impact from any source on the facility.

--Entry of toxic or flammable gas into a plant process building atmosphere (includes significant Main Generator hydrogen leaks).

-- Explosion (unplanned).

Note: Computer Fills this in Automatically Note: Computer Fills this in Automatically Meteorological Data as of : on / / ,:

Wind Direction FROM 264 degrees TO 84 degrees at 13 miles per hour.

2009 NRC SRO JPM EP PNPS's Protective Action Recommendations:

NO Protective Actions Necessary.

Note: Computer Fills this in Automatically Notification initiated by at (not yet sent).

(ENTERGY.COM\ from NPI-DSHJHHFI)

This is a Training Event Approved by

PILGRIM 2009 NRC JPM S-1 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE (ROISRO)

TITLE: RESTORE A CRD PUMP TO SERVICE FOLLOWING A PUMP TRIP (ALTERNAIE PATH\

OPERATOR: DATE: --

EVALUATOR:

CRITICAL TIME FRAME:

PERFORMANCE TIME:

Required Time (min):

Average Time (min):

3 EVALUATOR SIGNATURE:

Actual Time (min):

1 JPM RESULTS*: SAT UNSAT (Circle one) *Refer to Grading Instructions at end of JPM COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for UNSAT, Needs Improvement or Follow-Up Questions)

SYNoPSIS:

The reactor is at power. The running CRD pump has just tripped. The operator will start the standby pump IAW 2.4.4, Loss of CRD Pumps. During the restoration of CRD system flow, the in-service CRD flow control valve will fail close. The operator s expected to diagnose the condition, and shift to the standby FCV IAW 2.4.11 .I and restore CRD system flow.

TASK The 'B' CRD Pump will be placed in-service and CRD system flow restored to norma.

STANDARD:

There CRD system shall be restored to normal operating conditions in accordance with all system precautions and limitations and without failure of any critical elements EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant Simulate X

- Simulator Control Room Prepared: Date: -

Reviewed: Date: -

Superintendent, Operations Training (or Date: . -

Designee)

PILGRIM 2009 NRC JPM S-I TASK

Title:

Task Number K&A SYSTEM: K&A RATING:

SHIFT CRD FLOW CONTROL 201-01-04-012 201001 3.213.1 A2.07 VALVE

REFERENCES:

PNPS 2.4.4, Loss of CRD Pumps 2.4.11 . I , CRD System Malfunctions SIMULATOR CONDITIONS:

1. Initialize the simulator to any IC

2. Insert a CRD pump trip on the running CRD pump RD05 CRD Hydraulic Pump A Trip

3. Insert the CRD Flow Control Valve Fails Close Malfunction for the in-service flow control valve.

Condition the malfunction to go active when the RED open indication for that valve is FALSE.

RD02 CRD Flow Control Valve 6AF Cue Off - 'A' FCV Red Light OFF

4. Acknowledge all alarms.

5. An IOS operator is standing by to support the operator in responding to the JPM.

GENERAL TOOLS AND EQLIIPMENT:

1. None CRITICAL ELEMENTS:

OPERATOR BRIEF:

1. State the following paragraph IF this is the first performance in this setting:

a) "All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task. Wheal a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will state the task conditions and answer any questions, then provide a cue to begin".

2. The task conditions are as follows:

i) The reactor is operating at power ii) CRD Pump A has just tripped.

iii) Off-normal procedure 2.4.4, Loss of CRD Pump Trip, has just been entered.

3. Solicit and answer any questions the operator may have.

PILGRIM 2009 NRC JPM S-1 INITIAL CONDITIONS:

The reactor is operating at power.

CRD Pump A has just tripped.

Off-normal procedure 2.4.4, Loss of CRD Pump Trip, has just been entered.

INITIKI'ING CUE:

Execute procedure 2.4.4, Loss of CRD Pump Trip and restore the CRD system to normal."

PILGRIM 2009 NRC JPM S-1 PERFORMANCE:

Notes This task is covered in 2.4.4. The actions for the Flow Control Valve failuac are addressed in procedure 2.4.11. l , section Attachment 5.

All controls are located on panel C905.

All critical steps must be performed in order written unless otherwise noted START TIME:

l. I Procedure Step: Operator obtains a copy of procedure 2.4.4 and reviews the immediate actic n; 3.0 IMMEDIATE OPERATOR ACTIONS I '

NOTE S e d i n 5.0 (Discussion) provides the definition of "immediate".

I

[I] IF at any time during this Procedure Reactor pressure is less than 950psig AND the following conditions occur, THEN MANUALLY SCRAM the Reactor CONCURRENTLY EXECUTE PNPS 2.1.6, "Reactor Scram".

(a) One or more inoperable control rod Scram accumulators exist, as indicated b:f the ACCUM Trouble lights on the full core disptay, concurrent with charging water pressure c 940 psig.

I -

AND I

(bf All control rods associated with inoperable control rod Scram accumulators cannot be verified to be filly inserted immediately.

Pressure is > 950 psig and that the immediate actions are not applicable, regardless of the status of accumulat3r alarms.

Notes Multiple RPV pressure indicators located irr~mediatelyabove the CRD

-3 system controls.

Results SAT

PILGRIM 2009 NRC clPM S-1

[I] TRANSFER CRD flow controller (FIC-340-1) to MANUAL CLOSE the Flow Control Valve by rotating the controller manual potentiometer fully counterclockw se.

I 3.

/

Procedure Step:

I

[21 VERIFY that the in-sewice FIOW Control Valve is dosed by observing the green C305 vaive position light for FLOW CONTROL VLV A(B) LFCV-302-6A(B)].

Standard Operator observes the valve position indication and notes that the Green 1 1 I close light is illuminated and the Red open light is extinguished.

I I I

4 I

I Cue Notes I

I 4

1 I

Results SAT

4. Procedure Step: 131 IF the CRD pumps have been lost due to a load shed signal required, THEN BYPASS the load shed signal for the applicable CRD pumpfs) in accordance with AttachmentI.

1 the CRD pump( ) is (a) a Scram signal exists, THEN CLOSE 301-25, CRD Charging Water Sup18iy Valve.

Standard Operator determines that this step is not applicable and proceeds to the ne~ct step.

Cue I I

1 1 Notes I Initial conditions stated that the reactor is at power. There are no indicatioris 1 I

I I in the control room indicating either a load shed or a reactor scram.

-1

PILGRIM 2009 NRC JPM S-1 PILGRIM 2009 NRC JPM S-1 Procedure Step: Operator notifies the control room supervisor that the valve has close l. -

Standard Operator notifies the supervisor. --

Cue Acknowledge the report and question the operator as to what helshe recommends. Assuming the operator recommends entry into 2.4.11. l , CU Z:

"Execute 2.4.11.1" --

Notes The sustained loss of CRD cooling flow may result in CRD high temperatur 2 alarms. If so, then ROLE Play as the CRS and inform the operator that another operator is monitoring CRD temperatures and to continue with system restoration.

The operator could also got to PNPS 2.2.87 "Control Rod Drive System" rather than 2.4.11.1. If this course is taken, Section 7.7.5.2 "Placing Flow Control valve b in service" applies. The SOP actions are more specific thail the Off-Normal but are essentially the same. -

Results SAT UNSAT n Procedure Step: Operator obtains a copy of 2.4.1 1.1 and reviews the immediate actiors.

3.0 IMMEDIATE OPERATOR ACTIONS None Standard Operator proceeds to the subsequent actions section of the procedure. - -

Cue --

Notes Results

PILGRIM 2009 NRC JPM S-1 o

I I l .

Procedure Step: 4.0 SUBSEQLIENT ACTIONS

[I] WHEN the type of malfunction which has occurred has been determined, r!IEN PERFORM the applicable Attachment listed below:

Attachment MaRunction EkE 1 Degraded Control Rod Motion 7 I I 2 3

RPlS Mailunction CRD High Temperature 15 17 I

4 CRD Flow Controller Failure 18 I I 5 CRD Flow Control Valve Failure 19 I

Standard I Operator continues on in the procedure utilizing Attachment 5.

I I

-4 I

Cue I

I

-4 I

Notes I

I Results SAT n UNSAT n -4

PILGRIM 2009 NRC JPM S-1 Procedure Step: [2] At Flow Control Valve Station.

-1 I I fa) SLOWLY OPEN standby flow control valve inlet valve 301-40A (B).

I I I (b) SLOWLY OPEN outlet valve 301-41A (8)from standby Row control valve.

I I I (c) CLOSE outlet valve 301-41A (8) from in-service flow control valve.

I (d) CLOSE inlet valve 301-40A (B) for the previously in-service flow control valv- '.

(e) On the local valve control panel, PERFORM the following:

(1) SWAP selector switch 3B-S1, for electrical signal to EIP unit, from val Ie I

in-service to standby valve position.

(2) SWAP valve 3-HO-301-29 from valve in-service position to that of star idby valve FCV-302-6A, Position 1 (FCV-302-6B, Position 2).

I (9 NOTIFY the Control Room that flow control valves have been swapped over locally.

Standard Operator contacts an equipment operator and directsicoordinatesthe performance of step [2].

Cue IOS Operator is to role play as necessary to support this step. IOS operator is to utilize remote functions as directed by the operator.

/ A Notes 1

Results SAT n UNSAT n

14. Procedure Step: At Panel C905,CHECK DRIVE WTR and COOLING WTR DlFF PRESS

~ a)

Indicatars, dPL-340-4 and dPI-340-5, AND. IF needed, ADJUST pressures Standard Operator checks pressures and determines that they are normal. -

I I Cue I 1 Notes Operator may determine that adjustments are required. However this is not expected. Note per, 2.1.35,Control room readings, CRD drive pressure is 150 to 250 psid. Cooling water pressure is normally 8-15 psid. -

I Results SAT UNSAT

PILGRIM 2009 NRC JPM S-1 Cue: This completes this JPM.

STOP TIME:

PILGRIM 2009 NRC JPM S-1 INITIAL CONDITIONS:

The reactor is operating at power.

CRD Pump A has just tripped.

Off-normal procedure 2.4.4, Loss of CRD Pump Trip, has just been entered.

INITIATING CUE:

Execute procedure 2.4.4, Loss of CRD Pump Trip and restore the CRD system to normal."

PILGRIM 2009 NRC JPM S-2 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE (RO/SRO)

TITLE: PLACING THE FIRST FEEDWATER REGULATING VALVE IN SERVICE OPERATOR: DATE: --

EVALUATOR: EVALUATOR SIGNATURE: --

c CRITICAL TIME FRAME: Required Time (min): N/A Actual Time (min):

PERFORMANCE 'TIME: Average Time (min): 12 Actual Time (min):

JPM RESULTS*: SAT UNSAT NEEDS IMPROVEMENT (Circle one) *Refer to Grading Instn~ctionsat end of JPM COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat, Needs Improvement or Follow-Up Questions)

SYNOPSIS: The reactor is in a normal startup configuration at -10% power and a main feed regulating valve needs to be placed in service to continue the startup.

TASK One Main Feed Reg. Valve is in service controlling vessel level with the startup STANDARD: regulator closed. Reactor water level will be maintained between the low level scram and main turbine trip setpoints. The system shall be operated in accordance with all applicable precautions and limitations. The system procedure shall be followed without failure of critical elements.

EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant Simulate X Simulator Control Room Prepared: Date: -

Reviewed: Date: -

Date: -

Approved: Superintendent, Operations Training (or Designee)

PILGRIM 2009 NRC JPM S-2 TASK

Title:

Task Number K&A SYSTEM: K&A RATING PLACE THE FEEDWATER 259-01-01-006 259002 3.813.6 A4.02 CONTROLS FROM MANUAL TO AUTO.

REFERENCES:

PNPS 2.2.82 SIMULATOR CONDITIONS:

1. Reset the simulator to a condition with Rx power at approximately 10 - 12% and level controlled or the startup regulator.

2. Simulator Conditions are consistent with PNPS 2.1.1 Rx Plant Startup Step[l1O](b)

3. Insert Malfunction FW06 Master Controller Fails High in Auto

4. Verify both downstream blocks are open

5. RNLC is aligned for single element control.

6. Adjust the setpoint tape adjust on the Master Controller to achieve a mismatch between actual level and the setpoint. Setpoint should be outside the + 25 to 30" band.

7. Verify EPIC is operating GENERAL TOOLS AND EQLIIPMENT:

1. None CRITICAL ELEMENTS:

OPERATOR BRIEF:

1. State the following paragraph this is the first performance in this setting:

a) "All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task. When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will state the task conditions and answer any questions, then provide a cue to begin".

2. The task conditions are as follows:

i) A plant startup is in progress IAW 2.1.l. Step[llO]

ii) The mode switch is in Run iii) Reactor power is approximately 10%

3. Solicit and answer any questions the operator may have.

PILGRIM 2009 NRC JPM S-2 INITIAL CONDITIONS:

A plant startup is in progress IAW 2.1 .I.

Step11101 The mode switch is in Run Reactor power is approximately 10%

INITIATING CUE:

IAW procedure 2.2.82 Section 7.1 .I, place the " A main feed reg valve in service and secure the startcrp feed reg valve. Inform me when you have completed this task."

The ATC operator will be standing by to monitor reactor power and adjust IRM Range Switches if required during the evolution.

PILGRIM 2009 NRC JPM S-2 PERFORMANCE:

EXAMINER NOTE: An ATC operator will be standing by to monitor reactor power and adjust IRM Range Switches if required during the evolution.

Notes This task is covered in 2.2.82, section 7.1 .l.

All components are located on 905 horizontal and vertical section unless otherwise noted.

All critical steps must be performed in order written unless otherwise notec.

START TIME:

Procedure Step:

If the piping between 1st Point Feedwater Heater Outlet Block Valves, MO 347913480, and Feedwater Regulating Valves, FV-642NB has been isolated for an extended period of time (as determined by the SMICRS), then the differential pressure between this piping and the RFP Discharge Header pressure shall be checked in accordance with Attachment 4 (Feedwater Piping Pressure Monitoring) prior to placing a Feedwater Regulating Valve into service.

I Standard 1 Operator questions the SMICRS~S to whether there is a concern with the 1 differential'pressure in the Feedwater discharge header.

Cue If asked cue: We have determined that the Feedwater piping pressure is equalized between the1st Point Feedwater Heater Outlet Block Valves and the Feedwater Regulating Valves using attachment 4.

1 Notes ( The operator may ask this question during- hislher procedure review prior tt I commencing the-evolution.

Results SAT n UNSAT n Procedure Step: VERIFY the following:

I 1 1 The MASTER LEVEL CONTROL in "MANUAL" and the Manual control knob 1 is turned FULLY COLINTERCLOCKWISE.

Standard Operator verifies:

control switch for the MASTER controller is aligned to Manual

-1 Manual control knob (knurled knob) is set to minimum by attempting to turr knurled knob counterclockwise. -

Cue 1 Notes I I Results SAT E l UNSAT El

PILGRIM 2009 NRC JPM S-2

4. Procedure Step: The control switch for LEVEL MODE SELECT is in the "1 ELEM" position.

Standard Operator verifies 1 I 3 element control is aligned to "1 ELEM" position. - '3 Cue Notes Switch is on vertical section on board, above the control switches for the I downstream block valves.

- i I Results / SAT n UNSAT n 7 1

5. Procedure Step: The bias adjustment on FIC-640-19A and FIC-640-196, FLOW CONTROL,7 VLVs, is set at zero.

Standard The bias adjust dial for both individual MIA stations is set at zero. (Bias the upper meter on the controller.)

Notes UNSAT

-1

6. Procedure Step: Each individual FLOW CONTROL VLV controller is in the MANUAL mode AND the Manual control knob is turned fully counterclockwise (FULLY CLOSED).

Standard Operator verifies:

Control switch for the "A" MIA controller is aligned to Manual Manual control knob (knurled knob) for the " A MIA controller is set to minimum by attempting to turn knurled knob counterclockwise.

Control switch for the "B"MIA controller is aligned to Manual Manual control knob (knurled knob) for the "B" MIA controller is set to minimum by attemptiqg to turn knurled knob counterclockwise -

Cue -

1 I Notes Manual control signal can also be verified by observing that the MIA output meter is at "zero". -

Results SAT n UNSAT T I

PILGRIM 2009 NRC JPM S-2

7. Procedure Step: The signal to the ~eedwatirRegulating Valve is a CLOSED signal as verified by the lower meter on the individual l'low controller indicating 0%.

-1 Cue is readirrg "zero".

Notes The upper meter on the controller will also indicate zero signal.

Results SAT n UNSAT n I

Standard Operator verifies that the control signal to the feed reg to be placed in serv ce

8. Procedure Step: WHEN ready to transfer to a FLOW CONTROL VLV, OPEN OR VERIFY OPEN MO-3479 AND M0.-3480.

-1 Standard Operator verifies MO-3479 AND MO-3480 OPEN by checking green light OFF, red light ON.

-1 Notes Results SAT UNSAT i

1 (located on top of the individual controllers) fo-the valve to be placed in service is balanced (needle on RED DOT). IF required, adjust the selected individual FLOW CONTROL VLV Manual control knob to achieve the balanced condition.

Standard Operator checks that the " A MIA is balanced by checking that needle deviation meter is on the red dot (upper meter). If not, then operator adjus s the Manual control (knurled knob) to balance the controller.

Cue Notes Results SAT UNSAT

PILGRIM 2009 NRC JPM S-2 PILGRIM 2009 NRC JPM S-2

13. Procedure Step: Respond to increasing RPV level andlor Annunciator C905R-C7 "Reactor Water Level High" 1

Cue: This completes the JPM.

STOP TIME:

PILGRIM 2009 NRC JPM S-2 INITIAL CONDITIONS:

A plant startup is in progress IAW 2.1.l.Step[l10]

The mode switch is in Run Reactor power is approximately 10%

INITIATING CUE:

IAW procedure 2.2.82 Section 7.1 .I, place the "A" main feed reg valve in service and secure the start ~p feed reg valve. Inform me when you have completed this task."

The ATC operator will be standing by to monitor reactor power and adjust IRM Range Switches if required during the evolution.

PILGRIM 2009 NRC JPM S-3 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE (ROISRO)

TITLE: RESTORATION OF POWER TO 4160 VAC BUS A-5 FROM THE STARTUP TRANSFORMER OPERATOR: DATE: --

EVALUATOR: EVALUATOR SIGNATURE: --

CRITICAL TIMEFRAME: Required Time @ i n )

PERFORMANCE TIME: Average Time (min): Actual Time (min):

JPM RESULTS*: SAT UNSAT NEEDS IMPROVEMENT (Circle one) *Refer to Grading Instructions at end of JPM COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat, Needs Improvement or Follow-Up Questions)

SYNOPSIS: Following an initial loss of Off-Site power both diesel generators have started and re-energized their respective safety buses. The operator will perform a dead bus transf ?r and transfer the A5 bus back to the startup transformer.

TASK Power is restored to 4160 VAC bus A-5 via the Startup Transformer. The system sha'l STANDARD: be operated in accordance with all applicable precautions and limitations. The procedure shall be followed without a failure of critical elements.

EVALUATION METHOD: EVALUKI'ION LOCATION:

X Perform Plant Simulate -

X Simulator Control Room Prepared: Date: -

Reviewed: Date: -

Approved: Date: -

Superintendent, Operations Training (or Designee)

PILGRIM 2009 NRC JPM S-3 TASK

Title:

Task Number K&A SYSTEM: K&A RATING:

Recover Off-Site Power Following 262-04-01-010 295003 AAI .01 3.713. 3 Initial Loss of Grid

REFERENCES:

PNPS 2.4.16 SIMULATOR CONDITIONS:

1. Initialize to IC14

2. Trip ACB 102 and 103 and Place in PTL

3. Insert a scram to cause the LOOP

4. Verify B6 is aligned to B2

5. Verify Open B1 to B6

6. Stabilize plant conditions as required.

7. Place all fast transfer switches to OFF

8. Place condensate transfer pumps in PTL

9. Re-close ACB 102 and 103

10. Re-energize A1 through A4 from the startup transformer

11. Re-open MO-3808 GENERAL TOOLS AND EQUIPMENT: None CRITICAL ELEMENTS:

OPERATOR BRIEF:

State the following paragraph IF this is the first performance in this setting:

a) "All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task. Whe.1 a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will state the task conditions and answer any questions, then provide a cue to begin".

The task conditions are as follows:

i) The plant had experienced a loss of off-site power ii) Both EDGs are powering the emergency buses (A5 & A6) iii) The Startup Transformer has been re-energized and buses A1 through A4 have been energized.

iv) The SM has determined that the grid is stable following discussions with REMVEC and the ISO.

v) A field operator is standing by to support you in any required actions iv) PNPS 2.4.16, ATT.ll "Restoration Of AC Power" is complete through Step[5]

3. Solicit and answer any questions the operator may have.

PILGRIM 2009 NRC JPM S-3 INITIAL CONDITIONS:

The plant had experienced a loss of off-site power Both EDGs are powering the emergency buses (A5 & A6)

The Startup Transformer has been re-energized and buses A1 through A4 have been energized.

The SM has determined that the grid is stable following discussions with REMVEC and the ISO.

A field operator is standing by to support you in any required actions PNPS 2.4.16, ATT.11 "Restoration Of AC Power" is complete through Step[5]

INITIATING CUE:

Restore power to the 416OVAC bus A-5 from the Startup Transformer per procedure 2.4.16, 1, starting at Step[6In.

PILGRIM 2009 NRC JPM S-3 PERFORMANCE:

Notes This task is covered in 2.4.16, Attachment 11, Step 6.

All components are located on C3 horizontal and vertical section unless otherwise noted.

All critical steps must be performed in order written unless otherwise notec .

START TIME:

Procedure Step:

I Coordinade resaoration of emergency buses beck b oR.sile powar swrc;es with ISO-NE, REMVEC, and BPSX. &e aware that miher loss of offaits p m w m y oaur duing gid mstoretim. I m E R 99.01'3

] Rsstoring 4 l W Bus A5 w A0 to SXartup TraneComer (a) 41mV Bus A5 (1) IF SBO Diesel Gemrator IS pwwing A5, m O QPNPS 22.146 la restore A5

a. VERIFY prncEA5 auto-transfer d k h in "OFF.

b. W81TlON tfie Startup Xfmr ta Bus A5 synch switch b "ON'.

c. MANUALLY CLOSE tfie Startup Xfrnr Bm&w to A5 3 JEErnqency D i d Genecator -A is pawering A5,

a. E 4 W V Bua. BBis b e i i fed from 480V E m 31 AND IF EQ is ENERGIZED, TRANSFER faed to 48W BUS82 (BEE

--I PNPS 2.2.7, VBOV AC w)

Standard Operator determines that A5 is being powered from the " A EDG and that 480V B6 is ~0weredfrom B2.

Cue Notes Results SAT 0 UNSAT 0 I 1 2. Procedure Step:

b. B2 is DE-ENERGFED.,THEN REMEW Step 5.Omin t offhis Pmcdum Wbsfsw prooeedEng.

b 1 Standard I Cue Operator recognizes that B6 has been transferred to B2. -1 Notes Results SAT UNSAT

PILGRIM 2009 NRC JPM S-3 1 3. 1 Procedure Step:

1 c Sinm the transfar of Bus Ad horn (hs Diesel (D the Startup Trensfomnar is a mbead-bus" $ansfer, SWITCH necessary lolads to 1 480V M C G 814 and 480V MCG 818.

Standard Operator notes loads shifted to MCC B14 and B18.

~

Cue "Loads have been shifted to 814 and B18 (as CRS)."

Notes Results SAT UNSAT i

4. Procedure Step: d. lEany mrnpormnt has had its I d shed signal bypa E E K B ~ P ng, REDTIORE ttre h d shed signal bo that wmpanent ssrq.

Standard Operator questions CRS as to whether any load shed signals have been 7 bypassed.

Cue "Load shed signals have not been bypassed (if asked as CRS)." -

Notes Results SAT UNSAT Standard I Operator verifies that Auto transfer switch is in "OFF".

Cue

-1 Notes Auto Transfer switches are already in OFF position per the initial steps of Results SAT procedure.

n UNSAT i

PILGRIM 2009 NRC JPM S-3 1 9. 1 I Procedure Step: VERlPl Bus A5 is ENERGIZED by observing bus VOLTAGE and bus ~ ~ 7 ' 1 meters.

Standard Operator observes bus loading.

-1

_I I 1 Cue I Notes

-1 Results SAT n UNSAT 1 10. 1 Procedure Stew 1 PLACE the STARTUP XFMR TO BUS A5 svnch switch to OFF. -1 I Standard I Operator turns synch switch off.

Cue

-3 Notes Results SAT El UNSAT

PILGRIM 2009 NRC JPM S-3

11. I Procedure Step:

2. cs4WWlab to "

8

"-my AC I --

Standard Operator reports to the CRS that the Diesel Generator needs to be placed in standby.

Another operator will perform that task --

Results SAT UNSAT Cue: This completes this JPM.

STOP TIME:

PILGRIM 2009 NRC JPM S-3 INITIAL CONDITIONS:

The plant had experienced a loss of off-site power Both EDGs are powering the emergency ~ (A5 I J S ~ S & A6)

The Startup Transformer has been re-energized and buses A1 through A4 have been energized.

The SM has determined that the grid is stable following discussions with REMVEC and thc ISO.

A field operator is standing by to support you in any required actions PNPS 2.4.16, ATT.11 "Restoration Of AC Power" is complete through Step[5]

INITIATING CUE:

Restore power to the 416OVAC bus A-5 from the Startup Transformer per procedure 2.4.1 6, 1, starting at Step[6Iv.

PILGRIM 2009 NRC JPM S-4 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE (ROISRO)

TITLE: TRANSFER PRESSLIRE REGULATION FROM MPR TO EPR WITH EPR FAILURE ( ALTERNATE PATH )

OPERATOR: DATE: --

EVALUATOR:

CRITICAL TIME FRAME:

PERFORMANCE TIME:

EVALUATOR SIGNATURE:

Required Time (min):

Average Time (min):

Actual Time (rnin):

~ 1 JPM RESULTS*: SAT LINSAT NEEDS IMPROVEMENT (Circle one) *Refer to Grading Instructions at end of JPM COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat, Needs Improvement c r Follow-Up Questions)

SYNOPSIS: With the reactor at full power, MHC pressure regulation is being controlled by the MPR following a failure of the EPR. Following repairs to the EPR, pressure regulation will be restored to the EPR. The operator will energize the EPR and place the EPR in service, when EPR is in service the EPR fails. Operator takes actions in accordance with 2.4.37.

TASK The EPR will be energized and placed in service IAW 2.2.99. The procedure should STANDARD: be followed with no failure of critical elements. There will be no unacceptable pressuee transients resulting from this transition (Rx scram, Bypass valve operation)

EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant Simulate -

X Simulator Control Room Prepared: Date: .-

Reviewed: Date: -

Approved: Superintendent, Operations Training (or Date: -

Designee)

PILGRIM 2009 NRC JPM S-4 TASK

Title:

Task Number K&A SYSTEM: K&A RATING:

RESPOND TO EPR-MPR 248-04-01-002 241000 A4.19 3.513.4 MALFLINCTION.

REFERENCES:

PNPS 2.2.99. Rev.46 SIMULATOR CONDITIONS:

1. Initialize to full power IC

2. Transfer MHC pressure regulation to the MPR IAW 2.4.37.

3. Adjust MPR so that RPV pressure is within the prescribed band of 2.4.37.

4. Take EPR power to off

5. Pend EPR oscillation failure (UT1EP-TCO6 when HwA2-A1_M3-GT 936)

6. When MPR set point is raised the EPR will fail.

GENERAL TOOLS AND EQUIPMENT:

1. None CRITICAL ELEMENTS:

OPERATOR BRIEF:

1. State the following paragraph IF this is the first performance in this setting:

a) "All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task. When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will state the task conditions and answer any questions, then provide a cue to begin".

2. The task conditions are as follows:

i) The plant is at rated power ii) Following a failure of the EPR, the MPR was placed in service IAW 2.4.37 iii) The EPR has been repaired

3. Solicit and answer any questions the operator may have.

PILGRIM 2009 NRC JPM S-4 INITIAL CONDI'I'IONS:

The plant is at rated power Following a failure of the EPR, the MPR was placed in service IAW 2.4.37 The EPR has been repaired INITIATING CUE:

IAW with 2.2.99, section 7.4.4, energize the EPR and restore pressure control to the EPR.

PILGRIM 2009 NRC JPM S-4 PERFORMANCE:

Notes This task is covered in 2.2.99, Section 7.4.4 All components are located on Panel C2 horizontal and vertical section unless otherwise noted All critical steps must be performed in order written unless otherwise notec START TIME:

2. Procedure Step: [2] WAIT 1 minute from the time EPR SETPT Indicator 21-3013reaches its maximum setpoint of 1010 psig. -

~

I Cue I

Standard Operator waits long enough for lndicator 21-3013 to go full scale.

I 1

I

-4 1

1 1 Notes I If operator does not wait long enough the EPR control switch will not respc nd I

~ I in the next step.

I I

Results SAT n UNSAT

-4

PILGRIM 2009 NRC JPM S-4 PILGRIM 2009 NRC JPM S-4 STOP TIME:

PILGRIM 2009 NRC JPM S-4 INITIAL CONDITIONS:

The plant is at rated power Following a failure of ,the EPR, the MPR was placed in service IAW 2.4.37 The EPR has been repaired INITIATING CUE:

IAW with 2.2.99, section 7.4.4, energize the EPR and restore pressure control to the EPR.

PILGRIM 2009 NRC JPM S-5 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE (ROISRO)

Restoration of SDC LOOP A OPERATOR: DATE: --

EVALUATOR: EVALUATOR SIGNATURE: --

CRITICAL TIME FRAME: Required Time (min): NIA Actual Time (min):

PERFORMANCE TIME: Average Time (min): 15 Actual Time (min):

- J JPM RESULTS*: SAT UNSAT NEEDS IMPROVEMENT (Circle one) *Refer to Grading Instructions at end of JPM COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat, Needs Improvement c r Follow-IJp Questions)

SYNOPSIS: The reactor was shutdown four (4) hours ago. Shutdown cooling had already been established, but was terrr~inatedfor testing purposes. The tests have been complete 1 and 'A' loop RHR shutdown cooling needs to be re-established. When it is placed in service, a RHR leak will develop which should cause an auto PClS isolation, howeve*,

the auto action doesn't work and manual action is required by the operator to isolate the leak.

TASK The 'A' loop of RHR is placed in shutdown cooling. RHR shall be operated in STANDARD: accordance with all applicable system precautions and limitations. When it is placed In service, a RHR leak will develop which requires manual operator action to isolate dutl to a PClS failure. Procedure 2.2.19 shall be followed without deviation and with no failure of critical elements.

EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant Simulate X Simulator Control Room Prepared: Date: -

Reviewed: Date: -

Date: -

Approved: Superintendent, Operations Training (or Designee)

PILGRIM 2009 NRC JPM S-5 TASK

Title:

Task Number K&A SYSTEM: K&A RATING Restoration of SDC Loop A 205000 A4.02 3.6

13.5 REFERENCES

PNPS 2.2.19.1 Att.12 Examiners Note: PNPS 2.2.19.1 Rev 27, RESIDUAL HEAT REMOVAL SYSTEM- SHUTDOWN COOLING MODE OF OPERATION includes a typographical error. Attachment 12 Section 2.0, step [4] incorrectly identifies the 'C' RHR Torus Suction Valve as 'A'. The candidate will be provided with a corrected copy.

SIMULATOR CONDITIONS:

2. Secure Loop A SDC IAW PNPS 2.2.19.1 Att.12 Step [ I ]

3. Insert Malf. COP3, PClS Group 3 Isolation Bypass,

4. Insert Malf RHOS, Leak on RHR Pump A Disch Line at 4000 gpm. Condition malfunction on FI-1040-7, Greater than 1800 gpm.

GENERAL TOOLS AND EQUIPMENT:

NONE CRI'TICAL ELEMENTS:

OPERATOR BRIEF:

1. State the following paragraph IF this is the first performance in this setting:

a) "All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task. Whe 1 a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will state the task conditions and answer any questions, then provide a cue to begin".

2. The task conditions are as follows:

The reactor was shutdown four (4) hours ago. 'A' loop of RHR shutdown cooling needs tcj be re-established following a brief shutdown for testing.

3. Solicit and answer any questions the operator may have.

PILGRIM 2009 NRC JPM S-5 INITIAL CONDITIONS:

The reactor was shutdown four (4) hours ago. 'A' loop of RHR shutdown cooling needs to be re-established following a brief shutdown for testing.

INITIATING CUE:

Restore SDC using "A" RHR Pump IAW PNPS 2.2.19.1, Attachment 12, Section 2.0.

PILGRIM 2009 NRC JPM S-5 PERFORMANCE:

Notes START TIME:

1. Procedure Step: [ I ] CLOSENERIFY CLOSED MO-1001-28A, LPCl Inj Throttle Vlv #I.

Standard I Closes/verifies CLOSED MO-1001-28A, LPCl Inj Throttle Vlv #I.

-1

- 1 I Cue I I Notes Results SAT n UNSAT n

2. Procedure Step: [2] ENSURE an Operator is monitoring the Reactor water level.

1 Standard Ensures an Operator is monitoring the Reactor water level.

I Cue I Another operator is monitoring RPV Level

-1

-1 Notes Results SAT n UNSAT n i

3. Procedure Step:

Standard

[3] ISOLATENERIFY ISOLATED MO-1001-18A, RHR Pumps Loop A Minimum Flow Valve, control switch and breaker (81754).

-1 1 lsolates/verifies ISOLATED MO-1001-18A, RHR Pumps Loop A ~ i n i m u m1 I Flow Valve, control switch and breaker (B1754).

I Cue I Notes I 4I Results SAT 0 uNSAT 0 1

PILGRIM 2009 NRC JPM S-5 1 4. Procedure Step:

s!!!mN If at any trme dunng Step [4] an umqmted Reector water l e d drop rs observed.

Imamudlably dose the last vahm operated mER87-BNRC Bulktln 9-

[4] VERIFY the RHR Loop " A Shutdown Cooling flow path as follows:

CLOSENERIFY CLOSED MO-1001-7A, RHR Pump A Torus Suction Valve.

Standard Verifies the RHR Loop "A"Shutdown Cooling flow path as follows:

ClosesNerifies CLOSED MO-1001-7A, RHR Pump A Torus Suction i

Valve. -

I Cue I -

I Notes I 1 Results SAT n UNSAT n

5. 1 Procedure S t e ~ :I CLOSEIVERIFY CLOSED MO-1001-7C. RHR P u m C ~ Torus Suction ~ a l ~ 2 -

~tand&d ClosesNerifies CLOSED MO-1001-7C, RHR pump'c Torus Suction Valve Cue I 3

Notes I

~

Results SAT UNSAT n

8. Procedure Step: OPENNERIFY OPEN MO-1001-43C, Pump Suct Vlv.

Standard OpensNerifies OPEN MO-1001-43C, Pump Suct Vlv.

Notes Results SAT UNSAT n i

PILGRIM 2009 NRC JPM S-5

12. Procedure Step: OPEN/VERIFY OPEN MO-1001-16A, RHR HX A Byp Vlv.

Standard Opens MO-1001-16A, RHR HX A Byp Vlv.

Notes Results SAT n UNSAT n Regctor Vessel level wlll l mwrVl the start of an RHR Pump. The Intent ol Step [5] rs to prevent e law RWL lsalelonwhen starling an RHR Pump.

[5] VERIFY OR ADJUST Reactor water level to > +30n,(IF cavity level is flooded, ENTER "NIP".)

Standard Adjusts Reactor water level to > +3OV.

Cue Notes Results SAT n UNSAT

PILGRIM 2009 NRC JPM S-5 Procedure Step: [6] NOTIFY CRS to record.in the CRS logbook the date and time RHR is placed into SDC mode.

(a) NOTIFY Radiation Protection (RP) that RHR Pump A or C is about to b ?

returned to service in the SDC mode. RP should monitor the "A RHR Quadrant and the " A Valve Room for radiological changes. --

Standard Notifies CRS to record date and time RHR is laced in SDC in the CRS Notifies Radiation Protection (RP) that RHR Pump A or C is about to be returned to service in the SDC mode. RP should monitor the " A RHR Quadrant and the " A Valve Room for radiological changes. --

Cue --

Notes Results SAT UNSAT 0 0 I I

-1

15. 1 Proced~~reStep:

I - II NOTE Flaw lndlcators FI-1040-1A [B) and FI-ID40.2A [El) wil indicate r e r ~BcHv if the acPtml RHR I

flow is r, 1400 GPM When RHR flaw is r 1400 GPM, FR-1040-7will Indicate flaw. EPIC points RHROM and R H R W are also available far tMal lfow indlcatm.

Standard Reviews NOTE --

Cue --

Notes --

Results SAT UNSAT 0 0 --

PILGRIM 2009 NRC JPM S-5 Cue: This completes this JPM.

STOP TIME:

PILGRIM 2009 NRC JPM S-5 INITIAL CONDITIONS:

The reactor was shutdown four (4) hours ago. 'A' loop of RHR shutdown cooling needs to be re-established following a brief shutdown for testing.

INITIATING CUE:

Restore SDC using " A RHR Pump IAW PNPS 2.2.19.1 Section 2.0 of Attachment 12.

PILGRIM 2009 NRC JPM S-6 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE (ROISRO)

TITLE: INERTING THE CONTAINMENT OPERATOR: DATE: --

EVALUATOR: EVALUATOR SIGNATURE: --

I CRITICAL TIME FRAME: I Required Time (min): I N/A I Actual Time (min):

1 PERFORMANCE TIME: I Average Time (rnin): 1 15 1 Actual Time (min):

JPM RESLILTS*: SAT LINSAT NEEDS IMPROVEMENT (Circle one) *Refer to Grading Instructions at end of JPM COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat, Needs Improvement or Follow-Up Questions)

SYNOPSIS: The reactor is at about 5%. The operator will line up to inert containment IAW PNPS 2.2.70 Att.8 beginning at step 4.0[12]. A cooler will begin leaking causing an annunciator alarm (C7L-A5,6,7) requiring the operator to isolate the flowpath per Att.13 Step 3.0[2]

TASK lnerts containment IAW PNPS 2.2.70 Att.8. Isolates the system IAW PNPS 2.2.70 STANDARD: ATT.13 upon alarm indications of a cooler leak. Evolution shall be performed in accordance with all system precautions and limitations and without failure of any critical elements.

EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant Simulate X Simulator Control Room Prepared: Date: -

Reviewed: Date: -

Approved: Date: -

Superintendent, Operations Training (or Designee)

PILGRIM 2009 NRC JPM S-6 TASK

Title:

Task Number K&A SYSTEM: K&A RATING IIVERI-IIVG THE CONTAINMENT 223001 A4.10 3.2

13.2 REFERENCES

1. PNPS 2.2.70Att.8 & 13 SIMULATOR CONDITIONS:

1. IC with Reactor power at about 5%

2. PNPS 2.2.70Att.8 complete thru Step 4.0[1I]

3. At JPM Step 17 Inserts Alarms:

C7L-A5 and A6 "Cooler NNN leaking "

C904LC-B3 "C19AIB Trouble" GENERAL TOOLS AND EQUIPMENT:

1. None CRITICAL ELEMENTS:

OPERATOR BRIEF:

1. State the following paragraph this is the first performance in this setting:

a) "All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task. When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will state the task conditions and answer any questions, then provide a cue to begin".

2. The task conditions are as follows:

i) The reactor is at about 5% power ii) Containment inerting preparations have started IAW PNPS 2.2.70Att.8. The procedure is complete through Step 4.0[1I ]

3. Solicit and answer any questions the operator may have.

PILGRIM 2009 NRC JPM S-6 INITIAL CONDITIONS:

The reactor is at approximately 5% power Containment inerting preparations have started IAW PIIPS 2.2.70 Att.8. The procedure is complete through Step 4.0[11]

INITIATING CUE:

Line up SGTS A train to inert containment IAW PNPS 2.2.70 Att.8 begir~nirrgat step 4.0[12].

PILGRIM 2009 NRC JPM S-6 PERFORMANCE:

Notes START TIME:

Procedure Step: IF while purging, venting, OR inerting the containment, alarm is received which requires termination of the purging, venting, or inerting evolution, THEN EXIT this Attachment AND ENTER base document Section 7.1 0 (Isolation of Containment Purge Lines Upon Indication of Reactor Coolant Pressure Boundary Leakage). Alarms are listed below:

I I "SBGT DlSCH RAD HI" (C904LC-F41 1 I I "C19 A/B TROUBLE" (C904LC-B31 1 "DRYWELL EQPT DRAIN SUMP DlSCH HlGH TOTAL FLOW' (C20C)

"DRYWELL FLOOR DRAIN SUMP DlSCH HIGH TOTAL FLOW (C20C)

"DRYWELL EQPT DRAIN PUMP SUMP HlGH LEVEL" (twice within 30 4

minutes) (C20L)

"DRYWELL FLOOR DRAIN SUMP HlGH LEVEL" (twice within a 160-minute interval) (C20L) -

"COOLER 'NNN' LEAKING alarms, where 'NNN' is the specific cooler number (more than one unit in alarm) Panel C7L windows A5, A6, A7, B5, B6, B7, C5, and C6 O~eratorreviews alarms listed above.

1 Notes 1 I UNSAT n

Procedure Step: VERIFY the control switches for the following valves are in the "AUTO" position at Panel C904:

AO-5035A, DRYWELL PURGE SUPPLY ISOL VLV AO-5036A, TORUS PURGE SUPPLY ISOL VLV Standard Verifies the control switches for the following valves are in the "AUTO" 4

position at Panel C904: -

AO-5035A, DRYWELL PURGE SUPPLY ISOL VLV AO-5036A, TORUS PURGE SUPPLY ISOL VLV Cue Notes Results SAT 0 -1

PILGRIM 2009 NRC JPM S-6 Procedure Step: VERIFY CLOSED AO-5035A, DRYWELL PLIRGE SUPPLY ISOL VLV, fro~n Panel C7.

Standard Verifies Closed AO-5035A, DRYWELL PURGE SUPPLY ISOL VLV, from Panel C7. -

Cue I Notes I I Results SAT 0 UNSAT 0 1 Procedure Step: CLOSE the air supply block valve to AO-5035A, DRYWELL PURGE SLIPPLY ISOL VLV, located in the Drywell personnel air lock access.

Standard Closes the air supply block valve to AO-5035A, DRYWELL PLIRGE SLIPPI Y ISOL VLV, located in the Drywell personnel air lock access.

Evaluator Operator: Candidate contacts Field Operator to close Valve.

Cue: Evaluator responds.

-1 Notes UNSAT n

6. Procedure Step: VERIFY CLOSED AO-5035B, DRYWELL PURGE SUPPLY ISOL VLV.

Standard Verifies Closed AO-5035B, DRYWELL PURGE SUPPLY ISOL VLV.

-1 Cue Notes

PILGRIM 2009 NRC JPM S-6 Results SAT LlNSAT

7. Procedure Step: VERIFY CLOSED AO-50368, TORUS PURGE SUPPLY ISOL VLV.

-7 Cue Notes I

Standard Verifies Closed AO-5036B, TORUS PURGE SUPPLY ISOL VLV.

-1 Results SAT 0 LlNSAT Procedure Step: THROTTLE OPEN 9-HO-262, N2Supply to Drywell/Torus Purge Block Valve. (Rx Bldg El. 23')

Standard Throttles Open -HO-262, N, Supply to Drywell/Torus Purge Block Valve. - 1, Cue Candidate contacts Field Operator to open valve.

Evaluator Cue Evaluator responds as Field Operator that he opened the valve.

Notes Results SAT UNSAT

-4 0 0 -

Procedure Step: OPEN 9-HO-117, Primary Cntmt Atm Control N2Purge Supply Block Valve (Drywell Access, Rx Bldg El. 23')

Standard Opens 9-HO-117, Primary Cntrnt Atm Control NpPurge Supply Block V~IVE Cue Candidate contacts Field Operator to open valve.

Evaluator's Cue Responds as Field Operator that he opened the valve.

Notes Results SAT UNSAT 0 0

PILGRIM 2009 NRC JPM S-6

13. Procedure Step: AO-N-99, TRAIN A INLET DMPR, IS OPEN.

I Standard AO-N-99, TRAIN A INLET DMPR, IS OPEN.

-1

- A I cue I I 1 Notes I I Results SAT UNSAT 0 0 -

14. Procedure Step: AO-N-108, TRAIN A OUTL. DMPR, is OPEN.

Standard AO-N-108, TRAIN A OUTL. DMPR, is OPEN.

-1 Cue Notes I - -I

PILGRIM 2009 NRC JPM S-6

15. Procedure Step: VEX-210B, STANDBY GAS FAN B, is in "STANDBY.

Standard VEX-210~,STANDBY GAS FAN B, is in "STANDBY.

-1 Cue Sim Booth Evaluator Examiner's Note Notes Results SAT UNSAT 0 0

PILGRIM 2009 NRC JPM S-6

18. Procedure Step: IAW Att.13 Steps 13[1] & [2]

IF, while venting, purging, or inerting the containment during power

-1 operation, any of the following alarms are received:

"SBGT DlSCH RAD HI" (C904LC-F4) a "C19 AIB T R O L I B L E " ~ ( C ~ O ~ L C - ~ 3 )

a "DRYWELL EQPT DRAIN SUMP DlSCH HIGH TOTAL FLOW' (C20Cf --

a "DRYWELL FLOOR DRAIN SUMP DlSCH HIGH TOTAL FLOW (C20( - :)

"DRYWELL EQPT DRAIN PUMP SUMP HlGH LEVEL" (twice with 30 minutes) (C20L) --

a "DRYWELL FLOOR DRAIN SUMP HIGH LEVEL" (twice within a 2-hou.

40-minute interval) (C20L)

"COOLER 'NNN' LEAKING" ALARMS, WHERE 'NNN' is the specific:

cooler number (more than one unit in alarm) Panel C7L windows A5, A6, A7, 85, B6, B7, C5, and C6 Standard Responds to Annunciators

-7 Notes Ar~nunciatorsabove in BOLD will alarm Results SAT LlNSAT 0 0 Procedure Step: CLOSES OR VERIFIES CLOSED SV-5030A, N2Makeup Supply Block Valve.

1 I Standard Closes SV-5030A, N, Makeup Supply Block Valve. - A UNSAT n

20. Procedure Step: CLOSES OR VERIFIES CLOSED AO-5035A, Drywell Purge Supply lsol VI I .

Standard Closes AO-5035A, Drywell Purge Supply lsol Vlv.

Cue 1 1 Notes -

Results SAT UNSAT I E l -

Procedure Step: CLOSES OR VERIFIES CLOSED AO-5036A, Torus Purge Supply lsol Vlv.

I

PILGRIM 2009 NRC JPM S-6 Supply lsol Vlv.

UNSAT I Procedure Step: I CLOSES OR VERIFIES CLOSED AO-5041A, Torus Normal Exhaust lsol 1 I

Standard Closes AO-5041A, Torus Normal Exhaust lsol Vlv. - 1 Cue Notes Results SAT UNSAT

-4 0 0

23. Procedure Step: CLOSES OR VERIFIES CLOSED AO-50416, Torus Normal Exhaust lsol Vlv. 1 Standard Closes AO-5041B, Torus Normal Exhaust lsol Vlv.

Cue Notes UNSAT n

PILGRIM 2009 NRC JPM S-6 rG -Procedure Step:

-1 CLOSES OR VERIFIES CLOSED AO-5043A, Drywell Normal Exhaust Iso Vlv.

Standard Closes AO-5043A, Drywell Normal Exhaust lsol Vlv.

I I Notes 1 Results SAT 0

UNSAT 0 -1

27. 1 I Procedure Step: CLOSES OR VERIFIES CLOSED AO-5043B, Drywell Normal Exhaust 1s; 1 I

I Standard Closes A0-50438, Drywell Normal Exhaust lsol Vlv.

I Cue I I 1 Notes I I Results SAT UNSAT 0 0 I I Procedure Step: CLOSES OR VERIFIES CLOSED AO-5044A, Drywell Purge Exhaust lsol I I

Standard Closes AO-5044A, ~ G e lPurge l Exhaust lsol VE - AI I cue I 1 Notes I I Results SAT UNSAT 0 0

29. Procedure Step: CLOSES OR VERIFIES CLOSED AO-5044B, Drywell Purge Exhaust lsol Vlv.

Standard Closes AO-5044B, Drywell Purge Exhaust lsol Vlv.

Cue Notes I 41 Results SAT UNSAT 0 0 -

PILGRIM 2009 NRC JPM S-6 31.

I N-106, Train B Inlet Dmpr, to "AUTO".

Standard 1 NIA - 6 was not runnina

-1 Procedure Step: IF "B" SGTS was running, THEN at Panel C7, PLACE control switch for A( b-1 Cue Notes Results SAT UNSAT 0 0 CUE: JPM is complete STOP TIME:

PILGRIM 2009 NRC JPM S-6 INITIAL CONDITIONS:

The reactor is at approximately 5% power Containment inerting preparations have started IAW PNPS 2.2.70 Att.8. The procedure is complete through Step 4.0[11]

INITIATING CUE:

Line up SGTS A train to inert containment IAW PNPS 2.2.70 Att.8 beginning at step 4.0[12].

PILGRIM 2009 NRC JPM S-7 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE (RO/SRO)

TITLE: RECOVER RBCCW LOOP B' WITH AN ELEVATED DRYWELL TEMPERATURE OPERATOR: DATE: --

EVALUATOR: EVALUATOR SIGNATURE: --

CRITICAL TIME FRAME: Required Time (min): N/A Actual Time (min):

PERFORMANCE TIME: Average Time (min): 20 Actual Time (min):

JPM RESULTS*: SAT UNSAT NEEDS IMPROVEMENT (Circle one) *Refer to Grading Instructions at end of JPM COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat, Needs Improvement o p Follow-Up Questions)

SYNOPSIS: A non-LOCA event occurred that caused a reactor scram. Subsequent power and equipment failures have rendered RBCCW Loop '3' inoperable, causing drywell temperature to exceed 250°F. Electrical faults have been corrected, and it is desired to restore RBCCW Loop 'B' system flow.

TASK The RBCCW Loop 'B' will be restored without causing condensation-induced water STANDARD: hammer due to elevated drywell temperature. Procedure 2.4.42 shall be carried out without failure of any critical elements.

EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant Simulate X Simulator Control Room Prepared: Date: . -

Reviewed: Date: .-

Date: -

Approved: Superintendent, Operations Training (or Designee)

PILGRIM 2009 NRC JPM S-7 TASK

Title:

Task Number K&A SYSTEM: K&A RATING Respond to High Drywell Temperature 200-05-01-021 400000 AA4.01 3.113.2 (EOP-03)

REFERENCES:

PNPS 2.4.42 SIMULATOR CONDITIONS:

1. Initialize to any at power IC

2. Place HPCl Aux. Oil Pump in PTL.

3. Place all Loop "B" RBCCW Pumps in PTL

4. When the Reactor Scrams, carry out PNPS 2.1.6

5. Stabilize RPV Pressure and Level

6. Allow Drywell Temperature to rise to greater than 250 degrees GENERAL TOOLS AND EQUIPMENT: None CRITICAL ELEMENTS:

OPERATOR BRIEF:

1. State the following paragraph this is the first performance in this setting:

a) "All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task. Wheci a second checker is called for, the evaluator will perform ,the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will state the task conditions and answer any questions, then provide a cue to begin".

2. The task conditions are as follows:

i) A loss of B14 has occurred resulting in a loss of "B" loop RBCCW pumps ii) RBCCW could not be cross-tied due to the inability to open a cross connect valve.

iii) The HPCl Aux Oil Pump is in PTL.

iv) The reactor was scrammed and the actions of PNPS 2.1.6 carried out.

V) EOP-03 has been entered on high drywell temperature vi) The fault on B-14 has been cleared vii) SSW pumps have been started IAW PNPS 2.4.43 viii) "B" Loop RBCCW pumps are in PTL in preparation for restoring 814 IAW 2.4.42.

ix) Drywell temperature has exceeded 250 degrees for the past 8 minutes

3. Solicit and answer any questions the operator may have.

PILGRIM 2009 NRC JPM S-7 INITIAL CONDITIONS:

A loss of 814 has occurred resulting in a loss of "B" loop RBCCW pumps RBCCW could not be cross-tied due to the inability to open a cross connect valve.

The HPCl Aux Oil Pump is in P-TL.

The reactor was scrammed and the actions of PNPS 2.1.6 carried out.

EOP-03 has been entered on high drywell temperature The fault on B-14 has been cleared SSW pumps have been started IAW PNPS 2.4.43 "B" Loop RBCCW pumps are in PI-L in preparation for restoring B14 IAW 2.4.42.

Drywell temperature has exceeded 250 degrees for the past 8 minutes INITIATING CUE:

B14 has been re-energized. Restore RBCCW Loop 'B' IAW PNPS 2.4.42 Section 4.2. Inform me when you have completed the task."

PILGRIM 2009 NRC JPM S-7 PERFORMANCE:

Notes This task is covered in 2.4.42, Section 4.2.

All critical steps must be performed in order written unless otherwise noted START TIME:

1. Procedure Step: 4.2 RECOWRY OF RBCCW LOOP "B"WITH AN ELEVATED DRWELL TEMPERATURE [NRC GL96-061 CAUTION

-1 if Drywell temperatures exceed 250'F and the RBCCW Loop "B" pumps are not funntnq, 1% te possible for boiling to occur tn the Drywell Coolers that may resuit tn a candensation-mduced 11 water hammer when the RBCCW Pumps are started or the loopsare cross-bed, unless the RBCCW noneasenbalblock vajves are dosed first. WRC GL9&W]

41 1 111 (a) IF indcabons of a malor LOW\ east, TIIEN PERFORM Step m.

1 Cue p) NO indicattons uf a m a p LOCA exist, THEM PERFURM Step [3j.

Standard Operator enters Step 3 of the procedure.

Notes Initial Conditions described Non-LOCA conditions.

Results SAT n UNSAT n

-4

PILGRIM 2009 NRC JPM S-7 ion Pool temperature is

PILGRIM 2009 NRC JPM S-7 IF Maxtm~zedTorus Cooling, Toms S w y , Drywell Spray, LPCl tnj~tron With Maxrmtzed Cooling m& ISrequrred, THEN MAXIMIZE RBCCW C;mlinq n accordance wrfh PNPS 2 2 19 5 Attachment f ahla ALIGN the RHR Sydem fc the requ~redmode rn accordance with PNPS 2.2.19.5 Attachment 3, 4, 5, C Standard Operator questions CRS as to need to align systems for maximized coolin_< I Cue "The ECCS operator has placed RBCCW and torus cooling in service usinti loop " A systems. Continue restoration of "B" loop RBCCW." - -

Notes --

Results SAT 0 UNSAT 0 - -

NOTE Dlywell(:ooler Motor Operated Supply Valves MO-4038A M04039A MO-4040A MO-40388 M040398 MO4040B M0-40386 MO-4039C MP-4041A M0-4038D MO-4039D MO-40418 MO-4038E MO4039E M04038F MO-4039f

PILGRIM 2009 NRC JPM S-7 PILGRIM 2009 NRC JPM S-7 8.

I I Procedure Step:

I (g)

- plant condlttons ~ndrcate THEN ISOLATE the RBCGVV flaw to the Drywelt by closing; M0-4009A, RBCCW Loop "B" Nonessential Loop Inlet Valve

-1I a breach in the D m l l RBCCW w i m g pip~r3, MO-4009B, RBCCW Loop " B Nunessential Loop Outlet Valve - -

i=Ge Standard Operator determines that there is no break in RBCCW cooling piping in DPV.

Role Play as required to provide indication that RBCCW loop "B" has not been breached if operator requests information from field Notes The operator can make this determination in several ways, includirrg the following:

Operator can use steady pressure indication on RBCCW loop "6"and /or Absence of RBCCW loop "B" surge tank alarm and/or Request field operator to verify steady surge tank level. Etc.

Results SAT 0 UNSAT 0 I

9. Step: (h) PERFORM PNPS 2.2.19 5 Attachments t (Maximize RBCCW Cooling) and 2 1 (Maxim~reDrywelt Cooling) as necessary. 1 Standard Cue "This concludes the JPM." -3 i

Notes Results SAT El uNSAT E l STOP TIME:

PILGRIM 2009 NRC JPM S-7 INITIAL CONDITIONS:

A loss of B14 has occurred resulting in a loss of "B" loop RBCCW pumps RBCCW could not be cross-tied due to the inability to open a cross connect valve.

The HPCl Aux Oil Pump is in PTL.

The reactor was scrammed and the actions of PNPS 2.1.6 carried out.

EOP-03 has been entered on high drywell temperature The fault on B-14 has been cleared SSW pumps have been started IAW PNPS 2.4.43 "B" Loop RBCCW pumps are in PTL in preparation for restoring B14 IAW 2.4.42.

Drywell temperature has exceeded 250 degrees for the past 8 minutes INITIATING CUE:

814 has been re-energized. Restore RBCCW Loop 'B' IAW PNPS 2.4.42 Section 4.2. Inform me when you have completed the task."

PILGRIM 2009 NRC JPM S-8 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE TITLE: APRM "B"FUNCTI0NAL TEST OPERATOR: DATE: --

EVALUATOR: EVALUATOR SIGNATURE: --

CRITICAL TIME FRAME:

PERFORMANCE TIME:

JPM RESULTS*:

Required Time (min):

Average Time (min):

SAT UNSAT N/A 20 Actual Time (min):

Actual Time (min):

NEEDS IMPROVEMENT

-1 N/il (Circle one) *Refer to Grading Instructions at end of JPM COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat, Needs Improvement c r Follow-Up Questions)

SYNOPSIS: A plant startup is in progress. The operator will perform the APRM 'B" functional test IAW 8.M.1-3 Att.2 Steps [6] thru [ I 71 TASK APRM B Functional Test complete IAW 8.M.1-3, Attachment 2 thru step 17 and APR'd STANDARD: B out of Bypass. Task is performed in accordance with all system precautions and limitations and without failure of any critical elements.

EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant Simulate X Simulator Control Room Prepared: Date: -

Reviewed: Date: -

Date: -

Approved: Superintendent, Operations Training (or Designee)

PILGRIM 2009 NRC JPM S-8 TASK

Title:

Task Number K&A SYSTEM: K&A RATING APRM FUNCTIONAL TEST 215005 A4.03 3.2

13.2 REFERENCES

PNPS 8.M.1-3 Att.2 SIMULATOR CONDITIONS:

1. IC18.

GENERAL TOOLS AND EQUIPMENT:

1. None CRITICAL ELEMENTS:

OPERATOR BRIEF:

1. State the following paragraph IF this is the first performance in this setting:

a) "All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task. W h e i a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will state the task conditions and answer any questions, then provide a cue to begin".

2. The task conditions are as follows:

i) The plant is starting up.

ii) APRM "B" Functional Test has begun IAW 8.M.1-3, Attachment 2, and is complete through Step [51

2. Solicit and answer any questions the operator may have.

PILGRIM 2009 NRC JPM S-8 INITIAL CONDITIONS:

A plant startup is in progress APRM "B" Functional Test has begun IAW 8.M.1-3.1, Attachment 2, and is complete through Step [51 INITIATING CUE:

Perform APRM "B" Functional Test in accordance with 8.M.1-3, Attachment 2. Begin at procedure Sttap

[GI.

PILGRIM 2009 NRC JPM S-8 PERFORMANCE:

Notes START TIME:

1. Procedure Step: VERIFY the APRM "B" BYPASS indication lights as Panels C905 are ON.

Standard Verifies the APRM "B" BYPASS indication lights as Panels C905 are ON.

-7 Cue Notes UNSAT n 1 2.

I Procedure Step: VERIFY the following:

The SET DOWN white light for APRM " B channel at Panel C937 is OM.

CRD Scram Solenoid Group 1-4 liqhts at Panels C915 and C917 are ON.1 I

Standard Verifies the following:

The SET DOWN white light for APRM "B" channel at Panel C937 is I CRD Scram Solenoid G r o u 1-4

~ liahts at Panels C915 and C917 are ON.

-41 Cue Notes Results SAT n UNSAT n 1

PILGRIM 2009 NRC JPM S-8 Procedure Step: PERFORM Attachment 9 ~ R P S Reset Verification).

RPS RESET VERIFICATION

[I] VERIFY that the backup Scram valve relays are reset as follows:

Steps (a) through (e) verify that all RPS "A" and "B" contacts associated with the backup Scram valves are open priir to initiating a half-Scram. The normal indication is approximatet voltmeters. (Reference Drawing MIN22-8.) -

(a) VERIFY vdtage indicator El-302-19AA on 1 Panel C915 reads approximately 62.5 volts DC. - -

Initial:

(b) VERIFY voltage indicator El-302-19AB on I Panel C915 reads approximately 62.5 volts DC.

fc) VERIFY voltage indicator 1 -302-1 9BB on Panel C917 reads approximately 62.5 volts DC. - -

Initial?

(d) VERIFY voltage indicator El-302-19BA on Panel C917 reads approximately 62.5 volts DC. --

Initials I

CAUTION If any of the voltages verified in Steps fa) through (d) are approximately 125V DC or OV DC, P

then IMMEDIATELY STOP PERFORMANCE of this Procedure and report to the Shift Manager. Continuation of this Procedure could result in a full Reactor Scram.

fe) any of the voltages verified in Steps (a) through (d) were NOT approximately 62.5V DC, THEN STOP this Procedure AND NOTIFY the Shift Manager. the voltages were acceptable, ENTER "NIP". --

Initials

[2] Reviews:

I I Performed by:

Name (print) Initials Date SRO Review:

Name (print) Initials Date Standard Verifies the above voltages Cue Notes NONE will be OOS Results SAT 0 UNSAT n

PILGRIM 2009 NRC JPM S-8 Procedure Step: VERIFY that all LPRM card switches are in the "OP" position. IF LPRM ca-d switches are in the " B Y position due to a faulty detector or other trouble, they will remain in the " B Y position (RECORD LPRMs found in BYPASS below).

I Standard I Records .that no LPRMs were found in BYPASS. i I Cue I I Notes Results SAT 0 UNSAT n

PILGRIM 2009 NRC JPM S-8

7. Procedure Step: VERIFY APRM "6"local INOP light is ON AND APRM " B meter indicates correct number of operable LPRM inputs. RECORD value below:

Standard Verifies APRM "6"local INOP light is ON AND APRM "6"meter indicates

/ correct number of operable LPRM inputs.

--I

-4 I

I Cue Candidate records value af 50%. - 1 Notes Results SAT 0 UNSAT

9. Procedure Step: VERIFY APRM "B' local lNOP light is OFF. -1 Standard Verifies APRM "B" local INOP light is OFF.

-1 Cue Notes Results SAT UNSAT

PILGRIM 2009 NRC JPM S-8

14. 1 Procedure Step: RECORD the 'As-Found" value of power. The setpoint for the HlGH or rod

~ block function is 11 (10.5 to 11.5) percent power.

Standard Records the "As-Found" value of power. The setpoint for the HlGH or rod block function is 11 (10.5 to 11.5) percent power. -1 Cue i 1 Notes I 1 Results SAT UNSAT

PILGRIM 2009 NRC JPM S-8

16. Procedure Step: RECORD the "As-Found" value of power. The setpoint for the HIGH-HIGI-or Scram function is 13 (12.5 to 13.5) percent power.

Standard Records the "As-Found" value of power.

Cue Notes Results SAT

-4

PILGRIM 2009 NRCJPM S-8 20.

(3.0 to 4.0) percent power, decreasing.

-1 Procedure Step: RECORD the "As-Found" value of power. The setpoint for downscale is 3.3 Notes Results SAT I 1 22.

Procedure Step: RESET the APRM "B" channel trip functions.

VERIFY local alarms are CLEAR.

Standard Resets the APRM "B" channel trip functions.

Verifies local alarms are CLEAR.

-1 Cue Notes Results SAT UNSAT

,I PILGRIM 2009 NRC JPM S-8 STOP TIME:

PILGRIM 2009 NRC JPM S-8 INITIAL CONDITIONS:

A plant startup is in progress APRM "B" Functional Test has begun IAW 8.M.1-3, Attachment 2, and is complete through St ?p 151 INITIATING CUE:

Perform APRM "B" Functional Test in accordance with 8.M.1-3, Attachment 2. Begin at procedure St ap

[GI.

PILGRIM 2009 NRC EXAM IN-PLANT JPM P-1 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE TITLE: CROSS-TIE RBCCW COOLING LOOPS OPERATOR: DATE: --

I EVALUATOR:

CRITICAL TIME FRAME:

PERFORMANCE TIME:

EVALUATOR SIGNATURE:

Required Time (min):

Average Time (min): , Actual Time (min):

I JPM RESULTS*: SAT LINSAT NEEDS IMPROVEMENT (Circle one) *Refer to Grading Instructions at end of JPM COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat, Needs Improvement c~r Follow-Up Questions)

SYNOPSIS: With the plant at full power, a loss of 4160 VAC bus A5 occurred. Procedure 2.4.A.5 directs that RBCCW loops be cross-tied.

TASK The 'A' and 'B' Reactor Building Closed Cooling Water loops are cross-tied. The STANDARD: Reactor Building Closed Cooling Water System shall be operated in accordance with all applicable system precautions and limitations. The system procedure shall be followed without failure of any critical elements.

EVALUATION METHOD: EVALUATION LOCATION:

Perform X Plant X Simulate Simulator Control Room Prepared: Date: -

Reviewed: Date: -

Approved: Date: -

Superintendent, Operations Training (or Designee)

PILGRIM 2009 NRC EXAM IN-PLANT JPM P-1 TASK

Title:

Task Number K&A SYSTEM: K&A RATING Cross-Tie RBCCW Cooling Loops 200-05-04-075 295018 AA1.01; 3.3/3.,i.

REFERENCES:

PMPS 2.4.42, Attachment 5 SIMULATOR CONDITIONS:

GENERAL TOOLS AND EQUIPMENT:

1. None CRITICAL ELEMENTS:

OPERATOR BRIEF:

1. State the following paragraph this is the first performance in this setting:

a) "All actions associated with this job performance measure are to be simulated. You will be provided access to any tools or equipment you determine necessary to perform the task. When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will state the task conditions and answer any questions, then provide a cue to begin".

2. The task conditions are as follows:

i) The plant was operating at 100% power when bus A5 locked out due to a ground fault and is unavailable.

ii) As a result, the RBCCW loop 'A' pumps have been lost.

iii) Off-normal procedure 2.4.A5, Loss of A5, has been entered.

3. Solicit and answer any questions the operator may have.

PILGRIM 2009 NRC EXAM IN-PLANT JPM P-1 INITIAL CONDITIONS:

The plant was operating at 100% power when bus A5 locked out due to a ground fault and is unavailable.

As a result, the RBCCW loop 'A' pumps have been lost.

Off-normal procedure 2.4.A5, Loss of A5, has been entered.

INITIATING CUE:

Cross-tie Reactor Building Closed Cooling Water with the 'B' loop supplying. Inform me when you have completed this task.

PILGRIM 2009 NRC EXAM IN-PLANT JPM P-I PERFORMANCE:

Notes This task is covered in 2.4.42, Attachment 5.

Operator reviews .the applicable section of the procedure.

All critical steps must be simulated in order written unless otherwise noted.

2.4.42 Attachment 5 includes a CAUTION which states in part, "RBCCW shall NOT be cross-tied if Torus Temp is greater than or equal to 130F."

Operator may ask for Torus Temperature. Respond "75 degrees F" START TIME:

1. Procedure Step: [I]PLACE/VERIFY sufficient RBCCW pumps in service in the active loop 1

Standard Operator calls Control Room.

Cue Control Room reports that, "RBCCW pumps are in service in the active loop."

Notes Results SAT 0 UNSAT 0 -

2. 1 Procedure Step: 1 [2] SECURE any running RBCCW pump(s) in the idle loop from Panel C<-

I 7I I

Standard Operator calls Control Room.

I 1 I

Cue Control Room reports, "There are no pumps running on Loop "A."

I 1 Notes Results SAT UNSAT I

3. Procedure Step:

II

[3] PLACE all three control switches for RBCCW pumps in the idle loop to "PULL-TO-LOCK at Panel C1.

Standard Operator calls Control Room.

I-1 I 1 Cue Control Room reports that, "Pump switches are in P-T-L."

-4 Notes I

I I I

(

I Results SAT

-4

PILGRIM 2009 NRC EXAM IN-PLANT JPM P-I II 4.

1 Procedure Step: [4] For the idle RBCCW loop, UNLOCK AND CLOSE the RBCCW Surge I

I-4 Tank T-201A or T-201B Outlet Valve (30-HO-220 for Loop A OR 30-HO-2: 1 for Loop 6)to minimize backsurging and overflowing of tanks. -

Standard Operator locates, unlocks, and closes 'A' loop surge tank outlet, 30-HO-22 1.

I 1

Cue When the operator pushes the elevator call button, ask where he is going 1 I and state "The valve is unlocked and closed."

I I -1 I --I I

Notes (

I I

Results SAT

PILGRIM 2009 NRC EXAM IN-PLANT JPM P-I

9. ' Procedure Step:

d Standard Operator contacts the Control Room and informs them that the RBCCW A

loops have been cross-tied.

Cue "This completes the JPM."

Notes Results SAT E l STOP TIME:

PILGRIM 2009 NRC EXAM IN-PLANT JPM P-I INITIAL CONDI'I'IONS:

The plant was operating at 100% power when bus A5 locked out due to a ground fault and is unavailable.

As a result, the RBCCW loop 'A' pumps have been lost.

Off-normal procedure 2.4.A5, Loss of A5, has been entered.

INITIATING CUE:

Cross-tie Reactor Building Closed Cooling Water with the 'B' loop supplying. Inform me when you have completed this task.

PILGRIM 2009 NRC EXAM IN-PLANT JPM P-2 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE TITLE: RClC START FROM THE ALTERNATE SHUTDOWN PANELS OPERATOR: DATE: - -

EVALUATOR: EVALUATOR SIGNATURE: --

CRITICAL TIME FRAME: Required Time (min): 20 Actual Time (min): I -1 1 PERFORMANCE TIME: ( Average Time (min): 1 16 1 Actual Time (min):

JPM RESULTS*: SAT LINSAT NEEDS IMPROVEMENT (Circle one) *Refer to Grading Instructions at end of JPM COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat, Needs Improvement or Follow-Up Questions)

SYNOPSIS: The operator will place RClC in service from the alternate shutdown panels for level control following control room abandonment due to a fire.

TASK The RClC turbine will be in operation from the Alternate Shutdown Panels in the level STANDARD: control mode. The system shall be operated in accordance with all applicable precautions and limitations. The procedure shall be followed without failure of any critical elements.

EVALUATION METHOD: EVALUATION LOCATION:

Perform X Plant X Simulate Simulator Control Room Prepared: Date: -

Reviewed: Date: -

Approved: Date: -

Superintendent, Operations Training (or Designee)

PILGRIM 2009 NRC EXAM IN-PLANT JPM P-2 TASK

Title:

Task Number K&A SYSTEM: K&A RATING Manually Operate and Adjust RClC 217-02-01-006 295016 AA1.06 4.014:

System Flow With RClC Flow Controls At Alternate Shutdown Panel

REFERENCES:

PNPS 2.4.143 SIMULATOR CONDI'TIONS:

1. NIA GENERAL TOOLS AND EQUIPMENT:

1. Keys to Alternate Shutdown Panels C-154 and C-159 (ASP Key Ring CR-66 or CRA051).

CRI'TICAL ELEMENTS:

OPERATOR BRIEF:

1. State the following paragraph IF this is the first performance in this setting:

a) "All actions associated with this job performance measure are to be simulated. You will be provided access to any tools or equipment you determine necessary to perform the task. Whe 1 a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will state the task conditions and answer any questions, then provide a cue to begin".

2. The task conditions are as follows:

a) The control room has been evacuated due to a fire b) The reactor has been scrammed successfully c) RPV level control has not been established d) RClC must be started to accomplish RPV level control e) Communications have been established with the Shift Manager, who is standing by 'the level instrument rack 2205 and with an operator stationed at Rack 2258 with walkie-talkies or a cellular phone.

3. Solicit and answer any questions the operator may have.

PILGRIM 2009 NRC EXAM IN-PLANT JPM P-2 INITIAL CONDITIONS:

The control room has been evacuated due to a fire The reactor has been scrammed successfully RPV level control has not been established RClC must be started to accomplish RPV level control Communications have been established with the Shift Manager, who is standing by the level instrument rack 2205 and with an operator stationed at Rack 2258 with walkie-talkies or a cellular phone.

INITIATING CUE:

This JPM is TIME CRITICAL. Start RClC from the Alternate Shutdown Panels and place the system if1 the injection mode in accordance with PNPS procedure 2.4.143, Appendix B. Maintain reactor water level between +20 and +40. Water level is currently +30 and slowly lowering. Inform me when you have completed the assigned task."

PILGRIM 2009 NRC EXAM IN-PLANT JPM P-2 PERFORMANCE:

Notes This task is covered in 2.4.143, Appendix B, Sections 3.1 - 3.3.

All controls are located at the alternate shutdown panels (2154, C155 and C159 unless noted.

All critical steps must be performed in order written unless otherwise noted TIME CRITICAL START TIME NOTE: Start time begins once the RCA has been entered

3. Procedure Step:

1 [3] LOCALLY START the RClC Vawurn Pump P-222 in t h t q QuadmM.

Standard Operator starts personally or calls individual in quadrant start the vacuum L

Cue "The RClC vacuum pump is already running."

Notes It is not necessary to go to the Quadrant to accomplish this step. The operator may choose to call the operator stationed in the quad to start the pump. If not performed, note "NIA. -

PILGRIM 2009 NRC EXAM IN-PLANT JPM P-2 Results SAT UNSAT 0 -1 Valve MO-2301-15 may already be in use if HPCl is in operation. - A 1

switch to MO-2301-15 (HPCI/RCIC Test Return Valve) at ASP C155 (HPCI Quad entrance) to the pushed-in NORMAL position.

Standard Operator simulates pushing in the Contrd switch for MO-2301-15 Cue "The control switch is pushed in."

Notes Results SAT n 1 UNSAT 1

5. Procedure Step: [5] OPEN ASP C155.

CHECK OPEN valve MO-2301-15 from Standard Operator identifies correct switch and motions in the proper direGion.

1 Cue "The red light is on and the green light is off."

Notes Results SAT UNSAT Procedure Step: [6] PLACE switch 1 s - L S 1 at ASP C159 Standard Operator locates correct switch and simulates Cue "Switch 13A-LS1 is in local."

Notes Results SAT 0

PILGRIM 2009 NRC EXAM IN-PLANT JPM P-2

7. Procedure Step: [q PLACE all control switches (five valve control switches) in ASP C154 out of "PULL-TO-LOCK" and into the pushed-in NORMAL position:

MO-I 301-49, RClC Injection Valve #2 MO-1301-53, RClC Full Flow Test Valve MO-1301-60, RClC Pump Minimum Flow Valve MO-1301-61, RClC Turbine Steam Inlet Valve

• MO-1301-62, RClC Cooling Water Supply Valve Standard Operator simulates pushing in ail control switches.

Cue After each switch is pointed to, "The control switch is pushed in."

Notes Switches may be pushed in any order as long as all 5 get pushed in.

Results SAT UNSAT n

8. Procedure Step: ' [8] VERIFY/PtACE the power supply "ON at Power St~pply Panel N551, adjacent to C154 and C159.

JJ Standard Operator locates correct switch and simulates motion in proper direction.

'1 Cue "The switch is simulated in the ON position.

The red light is on, voltage indicates 120 volts, current indicates slightly above 0 amps."

Notes Results SAT UNSAT

PILGRIM 2009 NRC EXAM IN-PLANT JPM P-2 Control of RCIC components, which may be controlled at Panels C154 and C159, as well as control o the HPCIIRCIC common Full Flow Test Valve (MO-2301-15 at ASP 155), has now been transferred tc the ASPS. - 1

9. Procedure Step: [9] VERIFY that the amber lights on the front of Panels C154 and C159 are NOT tit.

Standard Operator verifies amber light is out on both panels.

Cue "The amber light is off (repeat for each panel)." 3 Notes Results SAT n UNSAT n 1

10. Procedure Step:

3.2 VALVE LINEUP I11 , -

IF mnn& AND availebb, REQUEST addgbnaii suppoi t fmm the OSC9TSC tioi assist in aibning and operating tPls RCXC System.

Standard Operator requests additional assistance.

Cue "The OSC/TSC is not yet sufficiently manned." -

Notes Results SAT 1 1 UNSAT T I NOTE The following lineup is for initial start of RCIC. It assumes that flow will be established to the TEST 1

I LINE. Subseauent flow adiustment and valve mani~ulationare at the direction of the SM.

11. Pmcedure Step: I21 VERiFY that Flow CuntroEIer FIC-1340-2on ASP C159 is "AUTO" and the $e@ointis 250 GPM.

Standard Operator verifies flow controller is in auto and the setpoint is 250 GPM.

Cue "Controller and setpoint tape is as you see them." -

Notes Results SAT n UNSAT n

PILGRIM 2009 NRC EXAM IN-PLANT JPM P-2

12. Procedure Step: [3] OPEN MO-1301-62, Cooling Water Supply Vlv, on ASP C1Y -

Standard Operator identifies the proper control switch and simulates rotation in the proper direction.

Cue "The red light is on and the green light is off."

Notes Results SAT UNSAT Procedure Step: 1 141 OPEWERlFY OPEN MO-2301-15HPCliRClt Test Relur I Valve, an ASP C 155.

Standard Operator simulates verifying indications and/or notes the valve has been - 1 checked open already.

Cue "The red light is on and the green light is off." -

Notes The operator may indicate that the position of the valve has already been 1 checked. In this case no cue is required.

Results SAT n UNSAT n 1 14. ( Procedure Step: 1 [5] JOG OPEN MO-1301-53, RClC Full Flow Test Valve, for 7 6 seconds.

Standard Operator locates and simulates opening of MO-1301-53 for six seconds.

Cue "The red and green lights are both on,"

Notes I Results SAT UNSAT

PILGRIM 2009 NRC EXAM IN-PLANT JPM P-2 CAUTION During normal operation, the turbine should not be run below 2000 RPM. Below 2000 RPM, 1 intermittent exhaust flow will cause water hammer in the exhaust line. If turbine operation below 200C RPM is required to achieve and/or maintain adequate core cooling, then the turbine should not be run below 1000 RPM. This will ensure adequate oil pressure to maintain the stop valve open and bearing P

lubrication. The time the turbine is run below 2000, RPM should be kept to a minimum.

15. Procedure Step: 3.3

[I]

TURBINE STARTUP AND SYSTEM OPEWTION OPEN M0-1301-61,RClC Turbine Supply Valve, from

-7 ASP Cl54 AND OBSERVE that the Turbine starts.

-problems are encountered, REFER TO Precaution 2.0[5]

IF of Appendix B.

Standard Operator identifies correct control switch and motions operations in proper direction.

Cue "The red light is on and the green light is off."

Notes Results SAT 1 1 UNSAT 1 1

16. Procedure Step:

Standard Operator verifies increase in turbine speed.

Cue "SI-1340-2 is rising and stabilizes at 2800 RPM." _1 Notes Results SAT UNSAT E l 0

17. Procedure Step:

Standard Operator verifies flow.

Cue "FI-1340-2 is rising and stabilizes at 250 GPM."

Notes Results SAT 1- LINSAT n

PILGRIM 2009 NRC EXAM IN-PLANT JPM P-2

18. Procedure Step: 121 OPERATE system as necxs8ar-yto control Reactor Vessel level and preswre.

(a) MONITOR system operation AND ADJUST FtC-4 340-2, lm~ectionF W Control, and/or

-1 MO-9 301-53,RCIC Full Flow Test Valve, an ASP C1E9 to obtain RCIC f bw rate as directed by the SM.

Standard Operator monitors system.

Cue As the SM, iiPlace RClC in the injection mode."

Notes Results SAT 0 UNSAT I -1 NOTE The next few steps will affect RClC discharge pressure and steam demand. FIC-1340-2 and MO-130 1 -

53 should be manipulated in tandem such that Reactor Vessel pressure and level are controlled as desired. RClC discharge pressure can be monitored at PI-1360-5 (Rack C2258) if desired. -

I CAUTION DO NOT bring RClC flow below 200 GPM when injecting to the Reactor Vessel (MO-1301-49 OPEN) .n the AUTO mode of control.

steps to swap over to injection:

(a) USE MO-1301-53, RClC Full FtowTest Valve, on i ASP C154 to adjust pump discharge pressure to less than Reactor pressure.

Standard Operator reviews Note and Caution then, simulates opening MO-1301-53 1 I and/or adjusts FIC-1340-2 until cued that discharge pressure is less than reactor pressure. -

Cue , As the operator at C2258, "Discharge pressure is below reactor pressure." -

Notes I The operator may call the operator at rack 2258 to determine reactor pressire and RC~C pump discharge pressure. -

Results SAT 1 - 1 UNSATI -

PILGRIM 2009 NRC EXAM IN-PLANT JPM P-2

20. Procedure Step:

/

(b) OPEN MO-1301-49 Injection Valve W2 on ASP C154.

-11 1 Standard Operator simulates taking the control switch for MO-1301-48 to the open position.

Cue "Red light is on, green light is off."

Notes -

Results SAT 0

1 Procedure Step:

(c) THROTTLE MO-1301-53, RCiC Full Flow Test Val ie, 1 on ASP C154 to obtain vessel level increase.

I Standard Operator simulates taking the control switch for MO-1301-5Fto the closed

~ositionmornentarilv.

Cue I As the SM, "RPV level is +25 inches and slowly rising."

Notes

- 3 Results SAT n UNSAT n

TlME CRITICAL STOP TlME Cue: This completes this JPM.

STOP TIME:

PILGRIM 2009 NRC EXAM IN-PLANT JPM P-2 INITIAL CONDITIONS:

The control room has been evacuated due to a fire The reactor has been scrammed successfully RPV level control has not been established RClC must be started to accomplish RPV level control Communications have been established with the Shift Manager, who is standing by the level instrument rack 2205 and with an operator stationed at Rack 2258 with walkie-talkies or a cellular phone.

INITIATING CUE:

This JPM is TIME CRITICAL. Start RClC from the Alternate Shutdown Panels and place the system it) the injection mode in accordance with PNPS procedure 2.4.143,Appendix B. Maintain reactor water level between +20 and +40. Water level is currently +30 and slowly lowering. Inform me when you have completed the assigned task."

PILGRIM 2009 NRC EXAM IN-PLANT JPM P-3 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE TITLE: LOCAL START AND FIELD FLASH OF AN EDG OPERATOR: DATE: --

EVALUATOR: EVALUATOR SIGNATURE: --

CRITICAL TIME FRAME: Required Time (min): N/A Actual Time (min):

PERFORMANCE 'TIME: Average Time (min): 8 Actual Time (min):

JPM RESULTS*: SAT UNSAT NEEDS IMPROVEMENT (Circle one) *Refer to Grading Instructions at end of JPM COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat, Needs Improvement or Follow-Up Questions)

SYNOPSIS: Following a loss of all AC power and loss of DC power to the A EDG, the operator is required to start the " A DG at the air start solenoids and then flash the field with two 12-volt batteries.

TASK The 'A' DG is running and ready to load. The system shall be operated in accordanct?

STANDARD: with all applicable precautions and limitations. The procedure shall be followed without failure of critical elements.

EVALUATION METHOD: EVALUATION LOCATION:

Perform X Plant X Simulate Simulator Control Room Prepared: Date: -

Reviewed: Date: -

Approved: Superintendent, Operations Training (or Date: -

Designee)

PILGRIM 2009 NRC EXAM IN-PLANT JPM P-3 TASK

Title:

Task Number K&A SYSTEM: K&A RATING, Local Start and Field Flash of an EDG 264-05-04-001 295004 AA1.03 3.413.t i Following a Loss of 125 VDC Power

REFERENCES:

PNPS 2.4.16 SIMULATOR CONDITIONS:

GENERAL TOOLS AND EQUIPMENT:

1. CR-155 Keys to 2.4.16 toolbox in 'B' EDG room.

CRITICAL ELEMENTS:

OPERATOR BRIEF:

1. State the following paragraph IF this is the first performance in this setting:

a) "All actions associated with this job performance measure are to be simulated. You will be provided access to any tools or equipment you determine necessary to perform the task. Whe.1 a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will state the task conditions and answer any questions, then provide a cue to begin".

2. The task conditions are as follows:

i) The plant has experienced a complete loss of AC power.

ii) DC control power to the " A EDG has also been lost resulting in the inability to start and load the "A" EDG.

iii) Procedure 2.4.16 is beivg executed.

2. Solicit and answer any questions the operator may have.

PILGRIM 2009 NRC EXAM IN-PLANT JPM P-3 INITIAL CONDI'TIONS:

The plant has experienced a complete loss of AC power.

DC control power to the " A EDG has also been lost resulting in the inability to start and lo2 d the " A EDG.

Procedure 2.4.16 is being executed.

INITIATING CUE:

Start the "A" EDG and flash the field in accordance with PNPS 2.4.16, Attachment 3. Inform me wher you have completed the assigned task."

PILGRIM 2009 NRC EXAM IN-PLANT JPM P-3 PERFORMANCE:

Notes This task is covered in 2.4.16, Attachment 3.

All controls are located on the A EDG unless otherwise noted.

All critical steps must be performed in order written unless otherwise noted START TIME:

Procedure Step: [I] Obtain KEY (CR-155) for jumper and equipment toolbox stationed in the Emergency Diesel Generator 'B' Room. -

Standard Operator states the need to obtain the key.

Cue Provide the Operator with the CR-155 key.

I 1 - .-- I Notes I 1 I Results SAT n UNSAT n -1

PILGRIM 2009 NRC EXAM IN-PLANT JPM P-3 I I

~ .

Procedure Step: FLASH FIELD

[2] Protective clothing (e.g., voltage rated gloves, arc face shield, antj appropriate protective clothing) shall be donned in accordance with EN-IS-123, "Electrical Safety".

Standard Operator mentions dor~ningprotective clothing and where it would be Cue obtained from. -1 Notes If Operator doesn't mention this, coach after JPM is completed and record comments section.

Results SAT UNSAT n

PILGRIM 2009 NRC EXAM IN-PLANT JPM P-3 1

cables as soon as voltage begins to indica7t t engine will now be under control of the electric governor, will reduce speed to about 900 RPM, and is ready 10 accept load automatically.

Standard Operator observes indication of field volts on field voltmeter at C101 and removes jumpers from terminals inside C101.

Cue As operator looks at field volts, "Voltage is increasing. The jumpers are removed. Engine speed is 900 RPM."

Notes Results SAT UNSAT Cue: This completes this JPM.

STOP TIME:

PILGRIM 2009 NRC EXAM IN-PLANT JPM P-3 INITIAL CONDI'TIONS:

The plant has experienced a complete loss of AC power.

DC control power to the " A EDG has also been lost resulting in the inability to start and lo^ d the " A EDG.

Procedure 2.4.16 is being executed.

INITIKI'ING CUE:

Start the "A" EDG and flash the field in accordance with PNPS 2.4.16, Attachment 3. Inform me when you have completed the assigned task."

NRC ADMIN .IPM NOTES as of 1/23/09 General - Check/Revise all Answer Keys R-COO1 - add pre-heater exit temp - done 1/23 - revalidate in sim R-C002- add CST Tank level "A" LI-3503, "8"LI-3508 - level lo (28.5,29) - done 1/23 - revalidate in sim R-EC - state in initial conditions "plant startup "2 days ago" - done 1/23 S-COO1 - look at last 2 steps - SD added info in JPM 1/23, looks OK - revalidate in sim S-COO2 - provide complete copy of 2.2.84, add cues when completing each step that is unsat - done 1/23 S-EC - For Handout put in actual values for M&TE cal info, fill in TEST Equipment Info

, do not sign off Att.1 step 4.0[5](c) - NOT complete as of 1/23 S-RC - Need Key

Scenario Event Description ES-Dl Pilgrim 2009 NRC Scenario 1 Facility: PILGRIM Scenario No.: 1 Op Test No.: 2009 NRC I Examiners: Operators: SRO - I1 1 BOP - I1 I Initial Conditions: Reactor Power is 100% Il APRM C is bypassed while I & C replaces a power supply.

B RHR Pump will be OOS for maintenance. Currently in day 1 of a 7 day LC0 I1 B Feedwater Pump has a bad pump seal and must be secured and isolated. 1 Turnover: Reduce Reactor Power IAW 2.1 . I 4 Sections 7.11 & 7.9, continue power reduction with the RPR, then remove the B Feedwater Pump from service Critical Tasks: 1. Restore power to at least one ECCS bus by manually placing the SBO EDG in service.

I1 2. When RPV level cannot be restored and maintained above (-150 inches), 11 II Emergency Depressurization is directed and performed. 1

3. Restores RPV level above + I 2 inches using low-pressure ECCS pumps.

Event Malf. No. Event Event No. TYpe* Description 1 R-RO Power reduction required with RPR due to FW pump issue R-SRO N - BOP Secure Feedwater Pump "B" (PNPS 2.2.96)

N - SRO RD07 for in I - RO Rod drifts out of the core (Rod 10-27) sequence I- SRO AOP-2.4.11, Control Rod Positioning Malfunctions, Att 2 TS- SRO ANN C905L-A3 - Rod Drift TS - 3.3.B.l.C - LC0 to fully insert within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, disarm within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 NM21- APRM 'E' failure Downscale fails TS - SRO downscale TS 3.1.1 - action A. place in trip condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

Scenario Event Description Pilgrim 2009 NRC Scenario 1 5 HPOI - C-BOP HPCl Spurious Initiation C905R & C1L-F5 HPCl C-SRo inadvertently Enters AOP 2.4.35 step 4.0 [ I ] to secure HPCl TS-SRO starts TSs 3.5.A.3, 3.5.B.l.a, 3.5.C.3, 3.5.C.2 is most limiting Once HPCI shutdown/cooldown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is secured Add sirn booth note to prevent HPCl restartlreset 6 ED27- C - ALL Loss of all offsite power. Diesel B will not auto start, but can be loss of line started manually. Diesel A will tie on initially but will shortly trip 355 and lockout. SBO DG must be started.

DG03B &

DG02A (5 EOP-1 entry minutes Annunciators:

after loop) C3R-A8 - Line 355 Undervoltage B6 - ACB 105 trip C6 - ACB 102 Trip AOP-2.4.16 - DISTRIBUTION ALIGNMENT ELECTRICAL SYSTEM MALFUNCTIONS PNPS 2.2.146 7 PC01 - M -ALL Recirc leak in Drywell leads to Emergency Depressurization on 1500 gpm low RPV level.

Insert after SBO EOP Hi Drywell Pressure DG starts EOP Hi Drywell pressure OR if SBO DG is not started within 10 minutes of trip of DG

'A' 8 RHR04 C - BOP MO-1001-29B LPCl Injection Valve #2 fails to auto open C - SRO

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Scenario Event Description ES-Dl Pilgrim 2009 NRC Scenario 1 --

Pilgrim 2009 NRC Scenario #I The plant is operating at 100% power, End of Cycle. B RHR Pump will be OOS for maintenance and is under clearance. The crew must reduce power and remove the "B" Feedwater Pump from service due to a leaking pump seal.

When the Feedwater Pump is secured a control rod will begin to drift out. The RO will take action IAW AOP-2.4.11 to insert the rod. TS must be addressed and will require disarming the rod after insertion. APRM 'E' will then fail downscale requiring the SRO to address Technical Specification 3.1 . I . The RO will be required to insert a half scram on the affected channel.

Once the APRM actions are addressed, a spurious HPCl injection will occur requiring action by the BOP to secure HPCI. The SRO will address Technical Specifications for the system being inoperable.

A Loss of All Offsite Power will occur. The "6"Diesel will fail to auto start but can be started manually. The " A Diesel will start and tie to the bus initially but will shortly trip and lockout. The SBO DG must be started to supply the bus (Critical Task).

Once conditions stabilize following the reactor scram and restoration of power, a leak will occur in the Recirculation piping leading to increasing drywell pressure. The crew will continue taking actions in EOP-01 and enter EOP-03 due to high drywell pressure and other degrading containment parameters. The crew will place Suppression Pool Cooling and Spray in service as well as Drywell Spray as required by EOPs. Due to the unavailability of HPCl and the severity of the leak RPV level will continue to lower and the crew will take actions to Emergency Depressurize (Critical Task) and reflood the RPV with low pressure ECCS systems (Critical Task). Complicating the reflood effort will be the failure of LPCl Injection Valve MO-1001-29B to auto-open.

The scenario may be terminated when level has been restored to the required EOP band and containment parameters are improving.

EAL: Alert - 3.4.1.2 - Drywell Pressure >2.2 psig

Facility: PILGRIM Scenario No.: 2 Op Test No.: 2009 NRC Examiners: Operators: SRO -

RO -

BOP -

1 Initial Conditions: Power is -3.5 % reactor pressure - 960 psig APRM C is bypassed while I & C replaces a power supply.

RHR Pump 'B' OOS for maintenance - Day 1 of a 7 day LC0 has been entered.

1 RM-1805-3B Log Rad Monitor is tagged and is Out of Service. 1 Turnover: Place RWCU in service. KWCU was previously removed from service due to a filter demin holding pump trip. Filter demins have been backwashed and precoated. PNPS 2.2.83 Section 7.2 is complete through Step [4]. Continue at Step [5].

After RWCU is in service, continue the startup at PNPS 2.1.1 Step [103]

Critical Tasks: 1. Upon failure of RPS & Mode Switch, Actuates ARI to insert control rods

2. Emergency depressurizes when Torus Bottom Pressure cannot be maintained below PSP.

3. Performs Alternate RPV depressurization actions per Table T of EOP-17 when 4 SRVs do not open from the control room.

Event No.

1 Malf. No. Event Type*

N - BOP

- SRo Place RWCU in service Event Description 1

PNPS 2.2.83, Section 7.2 2 R- RO Continue withdrawing control rods to raise power R - SRO 3 RD09 - C- RO Stuck Rod 15 Control Rod C - SRO AOP 2.4.11.1 , Att.1 - CRD System Malfunctions 46-15 stuck Unsticks after drive pressure is raised.

4 RM RM- TS-SRO Air Ejector Off-Gas Process rad monitor RM-1705-3A Fails 1705-3A Detector ANN 600R-C4 Fails TS- ODCM 3.1-2 Action 4 - d

PC C - BOP RWCU isolates due to leak, inboard and outboard isolation valves RWCU C - SRO fail to auto close and must be manually closed from control room.

system leak ANN C904RC;-C2 - NON REGEN HX OUTLET TEMP HI PC-I5 MO-- ANN C904RC-A1 - RWCU Isolated 1201-5 auto EOP-4 entry isolation failure AOP 2.4.27 -. RWCU Malfunctions --

6 ED1 9- I - BOP Loss of power to Y-3 Y-3 Failure I - SRo AOP 5.3.18 - Loss of 120VAC Y-3 TS - SRO ANN C905L-B5 - Division 1 Panel Trouble Insert next event after TS 3.5.A - Cold Shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TS and 3.9.A, 3.9.B secondary containment are

- - addressed.

7 RP13,14- C - RO A loss of Turbine Lube oil will occur requiring a reactor scram.

RPS A & C - SRO When the reactor is scrammed a failure of RPS PB & Mode Switck Scram occurs. ARI functions.

Failure Auto

& Complete EOP-1 (in-out-in), EOP-2 (in-out)

Insert next event once EOP-2 is exited -

- - - - p -

8 MS17 - M - All Leaking Safety Valve, Downcomer break, Containment Safety Valve 4A Leak - 15 parameters degrade, ED required.

minute ramp EOP-3 entries to max severity PC21 - DW Downcomer Leak -

Initially at demanded value of 7.0 and ramped to max severity over 15 minutes g MS15 - SRV C - BOP ALL SRVs do not open during ED, Alternate Depressuriztion 3Cfailsto C-SRO Required open

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

P i l ~ r i m2009 NRC Scenario #2 The plant is at 3.5% power, reactor pressure is about 960 psig and a startup is in progress IAW GP-3. The BOP will place RWCU in service IAW plant operating procedures.

Once the startup continues, as the RO is withdrawing control rods, CR 46-15 will become stuck. The RO will enter the AOP and take actions to unstick the control rod.

Once the startup continues, an Air Ejector Off-Gas Process rad monitor will fail requiring the SRO to enter TS-ODCM 3.1.2 Action 4. Once TS are addressed, a RWCU leak will occur and the system will not fully isolate. The BOP will take action to isolate the system per the AOP. The SRO will enter EOP-04.

Then, a loss of 120 VAC Y-3 will occur. The crew will enter the AOP and take actions which include initiating a Reactor Building Isolation Signal and placing Standby Gas Treatment in service. Additionally, the SRO will enter Technical Specifications and determine the most limiting TS L C 0 is being in Cold Shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

After the loss of Y-3 has been addressed, a loss of turbine lube oil due to a trip of the aux oil pump will cause the Turbine Bypass Valves to close. When the reactor is scrammed, a failure of RPS and the mode switch will occur. The control rods will fully insert when the RO manually initiates ARI (Critical Task). The SRO will enter EOP-01 due to the scram.

Following the scram, a leaking SRV and downcomer break will result in a loss of pressure suppression. Containment pressure will rise resulting in EOP-03 entry. As torus bottom pressure rises drywell sprays will be required. Eventually containment pressure will exceed the pressure suppression pressure of EOP-03 requiring an emergency depressurization. The crew is expected to emergency depressurize (ED) the reactor IAW EOP-17 (Critical Task). All SRVs will not open during the ED requiring Alternate Depressurization methods (Critical Task).

The scenario may be terminated when the RPV is depressurized and containment parameters are improving.

EAL: SAE - 3.4.1.3 - Torus Bottom Pressure cannot be maintained below PSP.

Scenario Event Description NRC Scenario 3 I Facility: PILGRIM NRC Scenario No.: 3 Op Test No.: 2009 NRC Y Examiners: Operators:

Initial setup: B,C,D,E SSW pumps in service Initial Conditions: Reactor Power is 100%

APRM C is bypassed while I & C replaces a power supply.

'B' RHR Pump is OOS for maintenance. Today is day one of the LCO. 1 Turnover: Daily Screen Wash is in progress 41 Maintenance has requested that "B" Salt Service Water Pump be tagged out.

Start "A" SSW Pump and Place "B"SSW pump in PTL.

1 1 Critical Tasks: 1

1. Terminate and prevent injection except from Boron, RClC and CRD

2. Inject SBLC before Torus Water temperatures reaches the BllT

3. Insert Control Rods and achieve shutdown under all conditions

- 411 Event No. 1 Malf. No. Event TYpe*

N - BOP Event Description Shift Salt Service Water Pumps N - SRO Place "B" SSW pump in PTL and Start " A SSW pump IAW PNPS 2.2.32 Section 7.2 C- RO CRD Pump trip C - SRO ANN 905R - A5 - CRD Pump A Trip ANN 905R - (35 - Charging Water Pressure Low AOP 2.4.4 - Loss of CRD pumps I - BOP Loss of FW heating controllers - R- RO Power reduction required (Recirc then RPR array) Recirc to 43 LV3251 I - SRO mlbmlhr then RPR array LV3250 Ann C1C-A3 -- 1 Point Heater Level Hi AOP 2.4.150 - Loss of Feedwater Heating 4 CWOI- 'A' TS-SRO " A Salt Service Water Pump Trip -add cue that screens have SSW stopped turning, screen wash pumps have tripped on low pressure pump trip TS 3.5.8.4 - Restore SSW to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

Scenario Event Description NRC Scenario 3 MG Set " A requires transfer to alternate power.

RPS MG Set A Trip 2.2.79 - RPS Section 7.1.5 RM02 -

Refuel Refuel Floor Rad Monitor RM-1805-8A fails requiring entry to TS Floor Rad 3.2.D.1 - no recently irridated fuel movement unless SBGT is in Monitor service RM-1805-8A fails downscale MS SRV fails open, Scram required, A W S SRV 3B ANN 903L-B2, A2 Fails open AOP 2.4.29 --Stuck Open SRV LHWT EOPI, EOP 2 (East &

West SDlVs 99% full) 7 LPol A & B C - BOP SBLC fails to inject initially C - SRO

Scenario Event Description NRC Scenario 3 Pilgrim 2009 NRC Scenario #3 The plant is at 100% power, Maintenance has requested a clearance on Salt Service Water (SSW) Pump "B". The crew must start an SSW Pump " A and secure and isolate "B" SSW Pump.

Once those actions are completed, a trip will occur on the operating CRD pump and the crew will respond per the AOP. The RO will start the standby pump. Then, a loss of Feedwater Heating will occur due to I&C accidentally bumping into a transmitter rack.

The crew will enter the AOP and the RO will perform a power reduction as required. The BOP will restore the FW heater to service.

After the power reduction and plant conditions are stable, SSW pump 'A' will trip and the SRO will enter Technical Specification L C 0 3.5.8.4 - restore SW to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

The crew will then respond to a failure of the "A" RPS MG set requiring a transfer to alternate power. When that occurs the Refuel Floor Rad Monitor RM-1705-8A fails requiring the SRO to enter Technical Specification L C 0 3.2.D.1.

Once TS have been addressed, an SRV fails open and will not initially close requiring a reactor scram. When the manual scram is inserted numerous control rods will fail to insert and EOP-01 then EOP-02 must entered for the ATWS. The crew will be required to stop and prevent inject injection (except for CRD and SLC) to lower RPV water level (Critical Task) and bypass the MSlV isolation to preserve the Main Condenser as a heat sink. Actions will also be required to respond to an SBLC injection failure (Critical Task) and to insert control rods after level is lowered to maintain the reactor shutdown under all conditions (Critical Task).

The scenario can be terminated once the reactor is shutdown under all conditions.

EAL: SAE -2.3.1.3 - SBLC Injection

Facility: PILGRIM Scenario No.: 4 Op Test No.: 2009 NRC Examiners: Operators: SRO -

RO -

BOP -

Initial Conditions: Power is 100 %

APRM C is bypassed while I & C replaces a power supply.

RHR Pump 'B' OOS for maintenance - Day 1 of a 7 day LC0 has been entered Turnover: Place SBGT " A in service for I&C to check vibrations.

A control rod pattern adjustment is scheduled; the crew is directed to lower power to 90 %.

Critical Task: 1. Scram the reactor before one area exceeds max safe temperature

2. Emergency Depressurize when two areas exceed max safe temp Event Malf. No. Event Event No. TYpe* Description TS 3.7.A.2.B - Deactivate in isolated condition -Torus Vent A05041B fails in open position.

2 R - RO Lower power to 90% using Recirculation Flow R - SRO 3 Insert I - RO Recirc Flow Controller 'A' failure fails downscale.

Override I - SRO when operator is ANN 904RC-C7 MG 'A' Deviation High adjusting Recirc Pump AOP 2.4.20, 2.4.165 A Speed - TS 3.6.F.1. - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to have loop flows within 10%

Recirc Pump

'A' controller fails Downscale

4 Manual Stop C - BOP Spurious RClC injection (signal does not clear) - operators trip and Hold C - SRO RCIC.

RCIC TS - SRo initiation PB AOP 2.4.35, 2.2.22 Section 7.2 TS 3.5.D.2 - 14 days 5 RR11 - CRO Recirc pump 'A' High Vibration. Requires removing the 'A' Pump C -SRO Recirculation Pump from service. Trips Pump, Shuts discharge

'A' Hi Vibs valve ANN 904RC-.B6- Pump Motor A Vibration High AOP 2.4.17 Section 4.1 (End up in ExclusionIUnanalyzed Region, Insert CRs per RPR array).

TS 3.6.F.1 --

6 CW05- C - BOP RBCCW Pump Trips, Failure of Pump in Auto to start. Recirc RBCCW Pump trip C - SRO Pump 'B' inner seal failure. RWCU may isolate due to RBCCW TS - SRO loss.

RRI 3-Recirc Pump AOP 2.4.42 - Loss of RBCCW

'B' seal AOP 2.4.22 - Failure of a Recirc Pump inboard seal failure ANN 904RC-G6, 904R-G5 -Seal Cooling Flow Lo (A & B)

ANN 904R-D5 -Pump B Seal staging Flow Hi ANN C1R-A5 - Low Discharge pressure TS 3.5.B.3.A.l 7 Day L C 0 RBCCW.

7 RC06 - initial M - All RClC steam line break in the Secondary Containment, RClC ramp 15 in Steam line isolation valves fail to close which results in the need tc 20 minutes scram (1 area) and eventually 2 areas exceeding max safe OR requiring a E-Depress. EOP-04 for leak and EOP-01 for scram Overrides for individual area ANN 904L-A6 - Steam leakage area temp high temperatures ANN 903-A1- CRDIDrywell Misc Temp Hi Insert the next malfunction after scram and initial conditions stabilize 8 TFU-114 - C - BOP Failure of the Main Turbine to auto trip on reactor scram.

Main Turbine C - SRO Auto trip Failure

• (N)orrnal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Pilgrim 2009 NRC Scenario #4 The plant is at 100% power. The crew will place SBGT " A in service for I&C vibration checks. As the lineup for the evolution is being secured, a primary containment isolation damper will fail to close requiring a Technical Specification (TS) entry by the SRO, TS L C 0 3.7.A.2.B.

Once TS are addressed reactor power will be lowered to 90%. As power is being decreased, Recirc Flow Controller 'A' failure will fail low requiring a scoop tube lockup (AOP) by the RO. After plant conditions have stabilized, a spurious RClC initiation will occur, RClC must be tripped by the BOP operator. The RClC initiation will not reset (AOP). A TS entry will be required by the SRO, TS 3.5.D.2 - 14 day L C 0

'A' Recirc Pump will then experience high vibrations requiring removal from service.

Power to Flow may end up in the exclusion area and control rods must inserted by the RO. The SRO must address TS for Recirc Loop Flow Mismatch, TS 3.6.F.1. Once powerlflow and TS are addressed a RBCCW pump will trip and the pump in auto will fail to start requiring manual action (AOP) by the BOP operator. Additionally, the RO must diagnose one seal failure on the "B" Recirc Pump requiring entry to an AOP.

Then, a RClC steam line break in the Secondary Containment will occur. The RClC Steam line isolation valves fail to close resulting in increasing area temperatures and an EOP-04 entry. A reactor scram and entry to EOP-01 will be required before one area reaches its maximum safe operating value (Critical Task). The Main Turbine will fail to auto trip when the reactor scrams requiring manual action by the operator to trip the turbine. Eventually 2 areas will exceed safe operating values and an Emergency Depressurization will be required (Critical Task). The crew may anticipate ED and use bypass valves to reduce reactor pressure.

The scenario may be terminated when the ED is complete.

EAL: SAE - 6.2.2.3 - steam line break without isolation AND/OR 4.2.1.3 - 2 areas above max safe