ML12244A525

2012 Donald C. Cook Nuclear Power Plant Initial License Examination Administered Operating Test

ML12244A525
Person / Time
Site:	Cook
Issue date:	08/15/2012
From:	Operations Branch III
To:	American Electric Power
Shared Package
ML11354A196	List: ML12244A525 ML12244A531
References
Download: ML12244A525 (287)

Text

OPERATIONS JPM NUMBER: 2012 NRC-A1a-RO TIME: 15 MINUTES TITLE: Perform a Thermal Power Calculation REVISION: 0 Revision: 0 2012 NRC-A1a-RO Page 1 of 26

OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 2-OHP-4030-214-029 REACTOR THERMAL POWER K/A Number: 2.1.43 K/A Imp.: RO: 4.1 SRO: 4.3 Task Number: STP0030201 Determine Reactor Thermal Power (STP.029).

STP0040201 Determine Reactor Thermal Power based on Feedwater Indications.

TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS

• Task Briefing sheet

• 2-OHP-4030-214-029, Attachment 2, PPC Derived RTP Evaluation-Loss of LEFM

• Handout 1 - PPC Thermal Power History Data

• Handout 2 - PPC Feedwater Temperature Data

• Handout 3 - Power Range NIs Readings

• Calculator ATTACHMENTS

• Handout 1 - PPC Thermal Power History Data

• Handout 2 - PPC Feedwater Temperature Data

• Handout 3 - Power Range NIs Readings EVALUATION SETTINGS Classroom EVALUATION METHOD: PERFORM: SIMULATE:

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OPERATIONS JPM SIMULATOR/LAB SETUP N/A EVALUATOR INSTRUCTIONS

1. Initial the Prerequisites of Attachment 2.

2. Brief the operator (May be performed by giving out Task Briefing sheet).

3. Announce start of the JPM.

4. Perform evolution.

5. At completion of evolution, announce the JPM is complete.

6. Document evaluation performance.

TASK BRIEFING You are the BOP in Unit 2.

It is currently 0700 (TODAY).

The Unit Supervisor (US) has requested a Thermal Power Calculation in accordance with 2-OHP-4030-214-029, Reactor Thermal Power, Attachment 2, PPC Derived Reactor Thermal Power Evaluation-Loss of LEFM. The LEFM has been out of service for about 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and is not expected to be returned to service until the next shift. A pre-job brief has been conducted with the US. All prerequisites for Section 2 are met.

Perform the Thermal Power Calculation using the provided data from the Unit 2 PPC and Control Panels (Handouts 1, 2, and 3).

Additional Data:

• 2-SG-9, Point 26, Feedwater Heater 6A & 6B Outlet Temp. is reading 427°F.

• RCS Delta-T (UO485) is 99.75% with a GOOD quality reading.

TASK STANDARDS Perform a Reactor Thermal Power Calculation in Mode 1 with the LEFM not available and determine NI gain adjustment is required.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Verifies ALL prerequisites completed.

SAT: UNSAT:

CUE: If asked, state that all prerequisites have been met.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Reviews ALL precautions and limitations.

SAT: UNSAT:

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Enters 427°F (as provided in the Task Briefing).

SAT: UNSAT:

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Determines Step 4.1.1.a.2.a is N/A.

SAT: UNSAT:

Determines Step 4.1.1.a.2.b is N/A.

SAT: UNSAT:

Determines Step 4.1.1.a.3 is N/A.

SAT: UNSAT:

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Determines Step 4.1.1.b is N/A.

SAT: UNSAT:

Records Feedwater Inlet Temperatures to SGs from Handout 2 for 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> TODAY:

• T0418A: 429.0°F

• T0438A: 429.4°F

• T0458A: 428.7°F

• T0478A: 429.4°F SAT: UNSAT:

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

CS: Determines that all Feedwater Inlet Temperatures to SGs are within limits. YES checked (x 4).

SAT: UNSAT:

Determines Step 4.1.4.a & b is N/A.

SAT: UNSAT:

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Note: The Operator will need to determine the last time BOTH the LEFM and Venturi readings were valid - 1720 YESTERDAY Uses Handout 1 to determine that last valid RTP using LEFM was 99.59% from 1720 hrs YESTERDAY (U0601DL).

SAT: UNSAT:

Uses Handout 1 to determine that corresponding RTP using Venturi was 98.60% from 1720 hrs on YESTERDAY (U0601DV).

SAT: UNSAT:

CS: Determines that correction factor is 1.01.

SAT: UNSAT:

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Enters current Venturi RTP reading of 98.74.

SAT: UNSAT:

CS: Determines that corrected Venturi RTP is 99.73% (+ 0.1%).

SAT: UNSAT:

Enters readings for Power Range NIs (+ 0.5%):

• N41: 101.1%

• N42: 99.3%

• N43: 99.0%

• N44: 98.3%

SAT: UNSAT:

Determines difference between the corrected venturi RTP of 99.73% and actual NIs (+ 0.5%):

• N41 = +1.37

• N42 = -0.43

• N43 = -0.73

• N44 = -1.43 SAT: UNSAT:

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

CS: Calculates the average Power Range NIs of 99.43% (+ 0.5%).

SAT: UNSAT:

CS: Determines average Power Range NIs less than corrected Venturi RTP) and checks YES block SAT: UNSAT:

CS: Determines that greater than 1% deviation exists between actual NIs and corrected Venturi RTP and checks YES block SAT: UNSAT:

Determines that all NIs are within 2% of corrected Venturi RTP and checks NO block.

SAT: UNSAT:

CS: Determines that N41 is reading greater than 100.5% and checks YES block.

SAT: UNSAT:

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

CS: Determines that NIs need adjusting in accordance with Attachment 6.

SAT: UNSAT:

CUE: When operator determines NIs need adjusting in accordance with Attachment 6, then JPM is complete.

Revision: 0 2012 NRC-A1a-RO Page 14 of 26

OPERATIONS JPM Task Briefing You are the BOP in Unit 2.

It is currently 0700 (TODAY).

The Unit Supervisor (US) has requested a Thermal Power Calculation in accordance with 2-OHP-4030-214-029, Reactor Thermal Power, Attachment 2, PPC Derived Reactor Thermal Power Evaluation-Loss of LEFM. The LEFM has been out of service for about 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and is not expected to be returned to service until the next shift. A pre-job brief has been conducted with the US. All prerequisites for Section 2 are met.

Perform the Thermal Power Calculation using the provided data from the Unit 2 PPC and Control Panels (Handouts 1, 2, and 3).

Additional Data:

• 2-SG-9, Point 26, Feedwater Heater 6A & 6B Outlet Temp. is reading 427°F.

• RCS Delta-T (UO485) is 99.75% with a GOOD quality reading.

Task Briefing Revision: 0 2012 NRC-A1a-RO Page 15 of 26

OPERATIONS JPM DC Cook Point # : Point Name Database Point Type Point Description Point 1 : U2_U0601DL PPC2 Analog Input LEFM PCT RTP 10 MIN AVG Point 2 : U2_U0601DV PPC2 Analog Input VENT PCT RTP 10 MIN AVG DATE TIME U2_U0601DL U2_U0601DV YESTERDAY 07:00:00.000 99.81 GOOD PC 99.50 GOOD PC YESTERDAY 07:10:00.000 99.80 GOOD PC 99.49 GOOD PC YESTERDAY 07:20:00.000 99.77 GOOD PC 99.45 GOOD PC YESTERDAY 07:30:00.000 99.79 GOOD PC 99.44 GOOD PC YESTERDAY 07:40:00.000 99.80 GOOD PC 99.44 GOOD PC YESTERDAY 07:50:00.000 99.78 GOOD PC 99.45 GOOD PC YESTERDAY 08:00:00.000 99.76 GOOD PC 99.43 GOOD PC YESTERDAY 08:10:00.000 99.80 GOOD PC 99.47 GOOD PC YESTERDAY 08:20:00.000 99.82 GOOD PC 99.47 GOOD PC YESTERDAY 08:30:00.000 99.87 GOOD PC 99.53 GOOD PC YESTERDAY 08:40:00.000 99.83 GOOD PC 99.51 GOOD PC YESTERDAY 08:50:00.000 99.84 GOOD PC 99.53 GOOD PC YESTERDAY 09:00:00.000 99.84 GOOD PC 99.47 GOOD PC YESTERDAY 09:10:00.000 99.91 GOOD PC 99.54 GOOD PC YESTERDAY 09:20:00.000 99.90 GOOD PC 99.55 GOOD PC YESTERDAY 09:30:00.000 99.82 GOOD PC 99.52 GOOD PC YESTERDAY 09:40:00.000 99.84 GOOD PC 99.53 GOOD PC YESTERDAY 09:50:00.000 99.85 GOOD PC 99.50 GOOD PC YESTERDAY 10:00:00.000 99.85 GOOD PC 99.51 GOOD PC YESTERDAY 10:10:00.000 99.83 GOOD PC 99.47 GOOD PC YESTERDAY 10:20:00.000 99.86 GOOD PC 99.50 GOOD PC YESTERDAY 10:30:00.000 99.82 GOOD PC 99.48 GOOD PC YESTERDAY 10:40:00.000 99.87 GOOD PC 99.53 GOOD PC YESTERDAY 10:50:00.000 99.84 GOOD PC 99.50 GOOD PC YESTERDAY 11:00:00.000 99.83 GOOD PC 99.50 GOOD PC YESTERDAY 11:10:00.000 99.81 GOOD PC 99.46 GOOD PC YESTERDAY 11:20:00.000 99.81 GOOD PC 99.47 GOOD PC YESTERDAY 11:30:00.000 99.81 GOOD PC 99.47 GOOD PC YESTERDAY 11:40:00.000 99.80 GOOD PC 99.45 GOOD PC YESTERDAY 11:50:00.000 99.80 GOOD PC 99.45 GOOD PC YESTERDAY 12:00:00.000 99.79 GOOD PC 99.45 GOOD PC YESTERDAY 12:10:00.000 99.75 GOOD PC 99.44 GOOD PC YESTERDAY 12:20:00.000 99.76 GOOD PC 99.41 GOOD PC YESTERDAY 12:30:00.000 99.77 GOOD PC 99.40 GOOD PC YESTERDAY 12:40:00.000 99.71 GOOD PC 99.39 GOOD PC YESTERDAY 12:50:00.000 99.71 GOOD PC 99.40 GOOD PC YESTERDAY 13:00:00.000 99.77 GOOD PC 99.44 GOOD PC YESTERDAY 13:10:00.000 99.73 GOOD PC 99.40 GOOD PC YESTERDAY 13:20:00.000 99.72 GOOD PC 99.36 GOOD PC YESTERDAY 13:30:00.000 99.73 GOOD PC 99.41 GOOD PC YESTERDAY 13:40:00.000 99.71 GOOD PC 99.38 GOOD PC YESTERDAY 13:50:00.000 99.70 GOOD PC 99.39 GOOD PC YESTERDAY 14:00:00.000 99.72 GOOD PC 99.39 GOOD PC HANDOUT-1 Revision: 0 2012 NRC-A1a-RO Page 16 of 26

OPERATIONS JPM DATE TIME U2_U0601DL U2_U0601DV YESTERDAY 14:10:00.000 99.68 GOOD PC 98.56 GOOD PC YESTERDAY 14:20:00.000 99.64 GOOD PC 98.63 GOOD PC YESTERDAY 14:30:00.000 99.66 GOOD PC 98.64 GOOD PC YESTERDAY 14:40:00.000 99.68 GOOD PC 98.57 GOOD PC YESTERDAY 14:50:00.000 99.73 GOOD PC 98.61 GOOD PC YESTERDAY 15:00:00.000 99.71 GOOD PC 98.64 GOOD PC YESTERDAY 15:10:00.000 99.72 GOOD PC 98.60 GOOD PC YESTERDAY 15:20:00.000 99.75 GOOD PC 98.61 GOOD PC YESTERDAY 15:30:00.000 99.77 GOOD PC 98.64 GOOD PC YESTERDAY 15:40:00.000 99.69 GOOD PC 98.60 GOOD PC YESTERDAY 15:50:00.000 99.71 GOOD PC 98.58 GOOD PC YESTERDAY 16:00:00.000 99.70 GOOD PC 98.59 GOOD PC YESTERDAY 16:10:00.000 99.72 GOOD PC 98.59 GOOD PC YESTERDAY 16:20:00.000 99.70 GOOD PC 98.57 GOOD PC YESTERDAY 16:30:00.000 99.70 GOOD PC 98.57 GOOD PC YESTERDAY 16:40:00.000 99.67 GOOD PC 98.64 GOOD PC YESTERDAY 16:50:00.000 99.70 GOOD PC 98.67 GOOD PC YESTERDAY 17:00:00.000 99.66 GOOD PC 98.64 GOOD PC YESTERDAY 17:10:00.000 99.59 GOOD PC 98.60 GOOD PC YESTERDAY 17:20:00.000 99.59 GOOD PC 98.60 GOOD PC YESTERDAY 17:30:00.000 99.59 GOOD PC 98.38 BAD PC YESTERDAY 17:40:00.000 99.57 GOOD PC 94.44 BAD PC YESTERDAY 17:50:00.000 99.56 GOOD PC 96.44 BAD PC YESTERDAY 18:00:00.000 99.58 GOOD PC 99.44 BAD PC YESTERDAY 18:10:00.000 99.63 GOOD PC 96.40 BAD PC YESTERDAY 18:20:00.000 99.60 GOOD PC 94.46 BAD PC YESTERDAY 18:30:00.000 99.57 GOOD PC 95.43 BAD PC YESTERDAY 18:40:00.000 99.55 GOOD PC 96.39 BAD PC YESTERDAY 18:50:00.000 99.57 GOOD PC 99.45 BAD PC YESTERDAY 19:00:00.000 99.65 GOOD PC 99.41 BAD PC YESTERDAY 19:10:00.000 99.56 GOOD PC 99.45 BAD PC YESTERDAY 19:20:00.000 99.55 GOOD PC 99.39 BAD PC YESTERDAY 19:30:00.000 99.58 GOOD PC 95.40 BAD PC YESTERDAY 19:40:00.000 99.63 GOOD PC 95.38 BAD PC YESTERDAY 19:50:00.000 99.64 GOOD PC 99.31 BAD PC YESTERDAY 20:00:00.000 99.63 GOOD PC 95.20 BAD PC YESTERDAY 20:10:00.000 99.62 GOOD PC 98.99 BAD PC YESTERDAY 20:20:00.000 99.61 GOOD PC 93.93 BAD PC YESTERDAY 20:30:00.000 99.59 GOOD PC 94.60 BAD PC YESTERDAY 20:40:00.000 99.15 BAD PC 95.61 BAD PC YESTERDAY 20:50:00.000 99.03 BAD PC 98.58 BAD PC YESTERDAY 21:00:00.000 99.00 BAD PC 97.56 BAD PC YESTERDAY 21:10:00.000 79.60 BAD PC 98.83 BAD PC YESTERDAY 21:20:00.000 29.28 BAD PC 98.64 GOOD PC YESTERDAY 21:30:00.000 88.99 BAD PC 98.65 GOOD PC YESTERDAY 21:40:00.000 48.40 BAD PC 98.04 GOOD PC YESTERDAY 21:50:00.000 57.95 BAD PC 98.61 GOOD PC YESTERDAY 22:00:00.000 27.49 BAD PC 99.13 GOOD PC YESTERDAY 22:10:00.000 77.11 BAD PC 98.61 GOOD PC YESTERDAY 22:20:00.000 87.02 BAD PC 98.60 GOOD PC YESTERDAY 22:30:00.000 97.04 BAD PC 98.62 GOOD PC YESTERDAY 22:40:00.000 17.04 BAD PC 98.61 GOOD PC YESTERDAY 22:50:00.000 27.05 BAD PC 98.62 GOOD PC YESTERDAY 23:00:00.000 47.08 BAD PC 98.55 GOOD PC HANDOUT-1 Revision: 0 2012 NRC-A1a-RO Page 17 of 26

OPERATIONS JPM DATE TIME U2_U0601DL U2_U0601DV YESTERDAY 23:10:00.000 96.98 BAD PC 96.66 GOOD PC YESTERDAY 23:20:00.000 27.22 BAD PC 96.89 GOOD PC YESTERDAY 23:30:00.000 36.97 BAD PC 96.59 GOOD PC YESTERDAY 23:40:00.000 47.07 BAD PC 96.73 GOOD PC YESTERDAY 23:50:00.000 16.88 BAD PC 96.53 GOOD PC TODAY 00:00:00.000 87.03 BAD PC 96.70 GOOD PC TODAY 00:10:00.000 36.77 BAD PC 96.42 GOOD PC TODAY 00:20:00.000 47.12 BAD PC 96.81 GOOD PC TODAY 00:30:00.000 56.87 BAD PC 96.54 GOOD PC TODAY 00:40:00.000 16.75 BAD PC 96.43 GOOD PC TODAY 00:50:00.000 96.95 BAD PC 96.62 GOOD PC TODAY 01:00:00.000 36.81 BAD PC 96.50 GOOD PC TODAY 01:10:00.000 56.94 BAD PC 96.60 GOOD PC TODAY 01:20:00.000 57.17 BAD PC 96.85 GOOD PC TODAY 01:30:00.000 17.73 BAD PC 97.39 GOOD PC TODAY 01:40:00.000 37.94 BAD PC 97.60 GOOD PC TODAY 01:50:00.000 17.94 BAD PC 97.63 GOOD PC TODAY 02:00:00.000 18.07 BAD PC 97.74 GOOD PC TODAY 02:10:00.000 48.43 BAD PC 98.12 GOOD PC TODAY 02:20:00.000 38.80 BAD PC 98.49 GOOD PC TODAY 02:30:00.000 48.91 BAD PC 98.59 GOOD PC TODAY 02:40:00.000 18.96 BAD PC 98.66 GOOD PC TODAY 02:50:00.000 29.12 BAD PC 98.78 GOOD PC TODAY 03:00:00.000 79.24 BAD PC 98.89 GOOD PC TODAY 03:10:00.000 99.48 BAD PC 98.87 GOOD PC TODAY 03:20:00.000 89.65 BAD PC 98.82 GOOD PC TODAY 03:30:00.000 39.77 BAD PC 98.94 GOOD PC TODAY 03:40:00.000 69.87 BAD PC 98.85 GOOD PC TODAY 03:50:00.000 19.95 BAD PC 98.88 GOOD PC TODAY 04:00:00.000 49.91 BAD PC 98.89 GOOD PC TODAY 04:10:00.000 99.86 BAD PC 98.92 GOOD PC TODAY 04:20:00.000 29.88 BAD PC 98.93 GOOD PC TODAY 04:30:00.000 69.92 BAD PC 98.98 GOOD PC TODAY 04:40:00.000 39.97 BAD PC 98.92 GOOD PC TODAY 04:50:00.000 19.91 BAD PC 98.87 GOOD PC TODAY 05:00:00.000 29.82 BAD PC 98.79 GOOD PC TODAY 05:10:00.000 49.88 BAD PC 98.82 GOOD PC TODAY 05:20:00.000 19.82 BAD PC 98.80 GOOD PC TODAY 05:30:00.000 89.86 BAD PC 98.92 GOOD PC TODAY 05:40:00.000 79.87 BAD PC 98.96 GOOD PC TODAY 05:50:00.000 69.87 BAD PC 98.85 GOOD PC TODAY 06:00:00.000 29.90 BAD PC 98.88 GOOD PC TODAY 06:10:00.000 79.98 BAD PC 98.91 GOOD PC TODAY 06:20:00.000 69.92 BAD PC 98.89 GOOD PC TODAY 06:30:00.000 59.95 BAD PC 98.82 GOOD PC TODAY 06:40:00.000 39.87 BAD PC 98.83 GOOD PC TODAY 06:50:00.000 59.85 BAD PC 98.78 GOOD PC TODAY 07:00:00.000 49.88 BAD PC 98.74 GOOD PC HANDOUT-1 Revision: 0 2012 NRC-A1a-RO Page 18 of 26

OPERATIONS JPM DC Cook Point #  : Point Name Database Point Type Point Description Point 1  : U2_T0418A PPC2 Analog Input SG 1 FEEDWATER TEMPERATURE FTQ-210 Point 2  : U2_T0438A PPC2 Analog Input SG 2 FEEDWATER TEMPERATURE FTQ-220 Point 3  : U2_T0458A PPC2 Analog Input SG 3 FEEDWATER TEMPERATURE FTQ-230 Point 4  : U2_T0478A PPC2 Analog Input SG 4 FEEDWATER TEMPERATURE FTQ-240 DATE TIME U2_T0418A U2_T0438A U2_T0458A U2_T0478A YESTERDAY 07:00:00.000 429.0 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 07:10:00.000 429.1 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 07:20:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 07:30:00.000 429.0 GOOD DEGF 429.0 GOOD DEGF 428.3 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 07:40:00.000 428.9 GOOD DEGF 429.0 GOOD DEGF 428.2 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 07:50:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.3 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 08:00:00.000 429.0 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 08:10:00.000 429.0 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 08:20:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 08:30:00.000 429.2 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 08:40:00.000 429.0 GOOD DEGF 429.0 GOOD DEGF 428.4 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 08:50:00.000 429.2 GOOD DEGF 429.3 GOOD DEGF 428.4 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 09:00:00.000 429.0 GOOD DEGF 429.3 GOOD DEGF 428.4 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 09:10:00.000 429.2 GOOD DEGF 429.3 GOOD DEGF 428.6 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 09:20:00.000 429.2 GOOD DEGF 429.3 GOOD DEGF 428.6 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 09:30:00.000 428.9 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 09:40:00.000 429.2 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 09:50:00.000 429.1 GOOD DEGF 429.3 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 10:00:00.000 429.1 GOOD DEGF 429.3 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 10:10:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.4 GOOD DEGF YESTERDAY 10:20:00.000 429.1 GOOD DEGF 429.3 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 10:30:00.000 429.2 GOOD DEGF 429.3 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 10:40:00.000 429.2 GOOD DEGF 429.3 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 10:50:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 11:00:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 11:10:00.000 428.9 GOOD DEGF 429.2 GOOD DEGF 428.2 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 11:20:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.2 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 11:30:00.000 429.1 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.3 GOOD DEGF HANDOUT-2 Revision: 0 2012 NRC-A1a-RO Page 19 of 26

OPERATIONS JPM DATE TIME U2_T0418A U2_T0438A U2_T0458A U2_T0478A YESTERDAY 11:40:00.000 428.9 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 11:50:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.3 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 12:00:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 12:10:00.000 428.9 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 12:20:00.000 428.9 GOOD DEGF 429.2 GOOD DEGF 428.3 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 12:30:00.000 428.9 GOOD DEGF 429.2 GOOD DEGF 428.3 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 12:40:00.000 428.9 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 12:50:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.3 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 13:00:00.000 428.9 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 13:10:00.000 428.9 GOOD DEGF 429.3 GOOD DEGF 428.3 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 13:20:00.000 428.9 GOOD DEGF 429.2 GOOD DEGF 428.2 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 13:30:00.000 428.9 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 13:40:00.000 428.9 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.0 GOOD DEGF YESTERDAY 13:50:00.000 428.9 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 14:00:00.000 428.9 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 14:10:00.000 428.9 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 14:20:00.000 428.8 GOOD DEGF 429.0 GOOD DEGF 428.3 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 14:30:00.000 428.8 GOOD DEGF 429.0 GOOD DEGF 428.2 GOOD DEGF 429.0 GOOD DEGF YESTERDAY 14:40:00.000 429.0 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 14:50:00.000 429.0 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 15:00:00.000 429.0 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 15:10:00.000 429.0 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 15:20:00.000 428.9 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 15:30:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 15:40:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 15:50:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 16:00:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 16:10:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 16:20:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 16:30:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 16:40:00.000 428.8 GOOD DEGF 429.0 GOOD DEGF 428.3 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 16:50:00.000 428.9 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 17:00:00.000 428.9 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 17:10:00.000 429.1 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 17:20:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 17:30:00.000 429.0 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 17:40:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 17:50:00.000 429.1 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 18:00:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 18:10:00.000 429.0 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF HANDOUT-2 Revision: 0 2012 NRC-A1a-RO Page 20 of 26

OPERATIONS JPM DATE TIME U2_T0418A U2_T0438A U2_T0458A U2_T0478A YESTERDAY 18:20:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 18:30:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 18:40:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 18:50:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 19:00:00.000 429.0 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 19:10:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 19:20:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 19:30:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 19:40:00.000 428.9 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 19:50:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 20:00:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 20:10:00.000 429.0 GOOD DEGF 429.0 GOOD DEGF 428.3 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 20:20:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.3 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 20:30:00.000 429.0 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 20:40:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.3 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 20:50:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 21:00:00.000 428.9 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 21:10:00.000 428.7 GOOD DEGF 428.9 GOOD DEGF 428.0 GOOD DEGF 429.0 GOOD DEGF YESTERDAY 21:20:00.000 428.5 GOOD DEGF 428.6 GOOD DEGF 427.9 GOOD DEGF 428.9 GOOD DEGF YESTERDAY 21:30:00.000 428.2 GOOD DEGF 428.3 GOOD DEGF 427.5 GOOD DEGF 428.3 GOOD DEGF YESTERDAY 21:40:00.000 427.5 GOOD DEGF 427.8 GOOD DEGF 427.0 GOOD DEGF 427.8 GOOD DEGF YESTERDAY 21:50:00.000 427.3 GOOD DEGF 427.5 GOOD DEGF 426.7 GOOD DEGF 427.6 GOOD DEGF YESTERDAY 22:00:00.000 426.8 GOOD DEGF 426.9 GOOD DEGF 426.2 GOOD DEGF 427.0 GOOD DEGF YESTERDAY 22:10:00.000 426.7 GOOD DEGF 426.8 GOOD DEGF 426.1 GOOD DEGF 427.0 GOOD DEGF YESTERDAY 22:20:00.000 426.7 GOOD DEGF 426.8 GOOD DEGF 426.0 GOOD DEGF 427.0 GOOD DEGF YESTERDAY 22:30:00.000 426.7 GOOD DEGF 426.9 GOOD DEGF 426.2 GOOD DEGF 426.9 GOOD DEGF YESTERDAY 22:40:00.000 426.7 GOOD DEGF 426.9 GOOD DEGF 426.2 GOOD DEGF 427.0 GOOD DEGF YESTERDAY 22:50:00.000 426.5 GOOD DEGF 426.7 GOOD DEGF 426.0 GOOD DEGF 426.9 GOOD DEGF YESTERDAY 23:00:00.000 426.3 GOOD DEGF 426.4 GOOD DEGF 425.8 GOOD DEGF 426.6 GOOD DEGF YESTERDAY 23:10:00.000 427.0 GOOD DEGF 427.1 GOOD DEGF 426.3 GOOD DEGF 427.1 GOOD DEGF YESTERDAY 23:20:00.000 426.7 GOOD DEGF 426.8 GOOD DEGF 426.1 GOOD DEGF 427.0 GOOD DEGF YESTERDAY 23:30:00.000 426.4 GOOD DEGF 426.6 GOOD DEGF 425.9 GOOD DEGF 426.7 GOOD DEGF YESTERDAY 23:40:00.000 426.7 GOOD DEGF 426.7 GOOD DEGF 425.9 GOOD DEGF 426.9 GOOD DEGF YESTERDAY 23:50:00.000 426.4 GOOD DEGF 426.5 GOOD DEGF 425.8 GOOD DEGF 426.7 GOOD DEGF TODAY 00:00:00.000 426.6 GOOD DEGF 426.8 GOOD DEGF 426.1 GOOD DEGF 426.7 GOOD DEGF TODAY 00:10:00.000 426.5 GOOD DEGF 426.9 GOOD DEGF 425.9 GOOD DEGF 426.7 GOOD DEGF TODAY 00:20:00.000 426.7 GOOD DEGF 426.7 GOOD DEGF 425.9 GOOD DEGF 427.0 GOOD DEGF TODAY 00:30:00.000 426.4 GOOD DEGF 426.6 GOOD DEGF 425.9 GOOD DEGF 426.6 GOOD DEGF TODAY 00:40:00.000 426.7 GOOD DEGF 427.0 GOOD DEGF 426.2 GOOD DEGF 426.8 GOOD DEGF TODAY 00:50:00.000 427.0 GOOD DEGF 427.1 GOOD DEGF 426.3 GOOD DEGF 427.2 GOOD DEGF HANDOUT-2 Revision: 0 2012 NRC-A1a-RO Page 21 of 26

OPERATIONS JPM DATE TIME U2_T0418A U2_T0438A U2_T0458A U2_T0478A TODAY 01:00:00.000 426.6 GOOD DEGF 426.7 GOOD DEGF 425.9 GOOD DEGF 426.9 GOOD DEGF TODAY 01:10:00.000 426.6 GOOD DEGF 426.7 GOOD DEGF 426.1 GOOD DEGF 426.8 GOOD DEGF TODAY 01:20:00.000 427.1 GOOD DEGF 427.2 GOOD DEGF 426.5 GOOD DEGF 427.3 GOOD DEGF TODAY 01:30:00.000 427.4 GOOD DEGF 427.7 GOOD DEGF 426.9 GOOD DEGF 427.7 GOOD DEGF TODAY 01:40:00.000 427.6 GOOD DEGF 427.7 GOOD DEGF 427.0 GOOD DEGF 427.7 GOOD DEGF TODAY 01:50:00.000 427.4 GOOD DEGF 427.8 GOOD DEGF 427.0 GOOD DEGF 427.8 GOOD DEGF TODAY 02:00:00.000 427.8 GOOD DEGF 428.0 GOOD DEGF 427.2 GOOD DEGF 428.0 GOOD DEGF TODAY 02:10:00.000 427.9 GOOD DEGF 428.1 GOOD DEGF 427.3 GOOD DEGF 428.1 GOOD DEGF TODAY 02:20:00.000 428.3 GOOD DEGF 428.4 GOOD DEGF 427.8 GOOD DEGF 428.6 GOOD DEGF TODAY 02:30:00.000 428.3 GOOD DEGF 428.5 GOOD DEGF 427.8 GOOD DEGF 428.5 GOOD DEGF TODAY 02:40:00.000 428.4 GOOD DEGF 428.5 GOOD DEGF 427.8 GOOD DEGF 428.7 GOOD DEGF TODAY 02:50:00.000 428.6 GOOD DEGF 428.7 GOOD DEGF 428.0 GOOD DEGF 428.7 GOOD DEGF TODAY 03:00:00.000 428.8 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.0 GOOD DEGF TODAY 03:10:00.000 428.8 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.1 GOOD DEGF TODAY 03:20:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF TODAY 03:30:00.000 429.2 GOOD DEGF 429.3 GOOD DEGF 428.6 GOOD DEGF 429.3 GOOD DEGF TODAY 03:40:00.000 429.2 GOOD DEGF 429.3 GOOD DEGF 428.6 GOOD DEGF 429.3 GOOD DEGF TODAY 03:50:00.000 429.1 GOOD DEGF 429.3 GOOD DEGF 428.6 GOOD DEGF 429.4 GOOD DEGF TODAY 04:00:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF TODAY 04:10:00.000 429.2 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF TODAY 04:20:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF TODAY 04:30:00.000 429.1 GOOD DEGF 429.3 GOOD DEGF 428.5 GOOD DEGF 429.4 GOOD DEGF TODAY 04:40:00.000 429.3 GOOD DEGF 429.4 GOOD DEGF 428.6 GOOD DEGF 429.4 GOOD DEGF TODAY 04:50:00.000 429.1 GOOD DEGF 429.3 GOOD DEGF 428.5 GOOD DEGF 429.2 GOOD DEGF TODAY 05:00:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.3 GOOD DEGF TODAY 05:10:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF TODAY 05:20:00.000 429.1 GOOD DEGF 429.3 GOOD DEGF 428.6 GOOD DEGF 429.3 GOOD DEGF TODAY 05:30:00.000 429.2 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF TODAY 05:40:00.000 429.1 GOOD DEGF 429.3 GOOD DEGF 428.7 GOOD DEGF 429.4 GOOD DEGF TODAY 05:50:00.000 429.2 GOOD DEGF 429.3 GOOD DEGF 428.5 GOOD DEGF 429.4 GOOD DEGF TODAY 06:00:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.4 GOOD DEGF TODAY 06:10:00.000 429.2 GOOD DEGF 429.4 GOOD DEGF 428.6 GOOD DEGF 429.4 GOOD DEGF TODAY 06:20:00.000 429.2 GOOD DEGF 429.3 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF TODAY 06:30:00.000 429.2 GOOD DEGF 429.3 GOOD DEGF 428.6 GOOD DEGF 429.4 GOOD DEGF TODAY 06:40:00.000 429.1 GOOD DEGF 429.3 GOOD DEGF 428.6 GOOD DEGF 429.3 GOOD DEGF TODAY 06:50:00.000 429.2 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF TODAY 07:00:00.000 429.0 GOOD DEGF 429.4 GOOD DEGF 428.7 GOOD DEGF 429.4 GOOD DEGF HANDOUT-2 Revision: 0 2012 NRC-A1a-RO Page 22 of 26

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OPERATIONS JPM NUMBER: 2012 NRC-A1a-SRO TIME: 15 MINUTES TITLE: Review a Thermal Power Calculation REVISION: 0 Revision: 0 2012 NRC-A1a-SRO Page 1 of 28

OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 2-OHP-4030-214-029 REACTOR THERMAL POWER 2.1.43 K/A Number:

K/A Imp.: RO: 4.1 SRO: 4.3 Task Number: ADM0090302 Review completed Operation Department procedures STP0030201 Determine Reactor Thermal Power (STP.029).

STP0040201 Determine Reactor Thermal Power based on Feedwater Indications.

TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS

• Task Briefing sheet

• 2-OHP-4030-214-029, Attachment 2, PPC Derived RTP Evaluation-Loss of LEFM

• Handout 1 - PPC Thermal Power History Data

• Handout 2 - PPC Feedwater Temperature Data

• Handout 3 - Power Range NIs Readings

• Calculator ATTACHMENTS

• Handout 1 - PPC Thermal Power History Data

• Handout 2 - PPC Feedwater Temperature Data

• Handout 3 - Power Range NIs Readings EVALUATION SETTINGS Classroom EVALUATION METHOD: PERFORM: SIMULATE:

Revision: 0 2012 NRC-A1a-SRO Page 2 of 28

OPERATIONS JPM SIMULATOR/LAB SETUP N/A EVALUATOR INSTRUCTIONS

1. Fill out Attachment 2 per the JPM.

2. Brief the operator (May be performed by giving out Task Briefing sheet).

3. Announce start of the JPM.

4. Perform evolution.

5. At completion of evolution, announce the JPM is complete.

6. Document evaluation performance.

TASK BRIEFING It is currently 0720 (TODAY).

You are the Unit Supervisor in Unit 2.

The LEFM has been out of service for about 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> and is not expected to be returned to service until the next shift. A Thermal Power Calculation was performed by the RO in accordance with 2-OHP-4030-214-029, Reactor Thermal Power, Attachment 2, PPC Derived Reactor Thermal Power Evaluation - Loss of LEFM.

Review the Thermal Power Calculation using the provided data from the Unit 2 PPC and Control Panels, noting all errors if any.

Additional Data:

• 2-SG-9, Point 26, Feedwater Heater 6A & 6B Outlet Temperature is reading 427°F.

TASK STANDARDS Review a Reactor Thermal Power Calculation in Mode 1 with the LEFM not available, determines Acceptance Criteria is NOT met and NI gain adjustment is required.

Revision: 0 2012 NRC-A1a-SRO Page 3 of 28

OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Developer Note: Complete Attachment 2 using information in BLUE.

CUE: All mistakes are circled in red.

O O General Standard:

Verifies all appropriate steps are completed as required.

SAT: UNSAT:

O Ensures ALL prerequisites are met.

SAT: UNSAT:

TW TW TW TW Latest Rev Checked ______

TW Date ______

TODAY 0

No. of CS: _______

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OPERATIONS JPM TW TW TW TW TW Ensures ALL precautions and limitations met.

O SAT: UNSAT:

O Revision: 0 2012 NRC-A1a-SRO Page 5 of 28

OPERATIONS JPM O

O O

Veifies 427ºF entered (as provided in the Task Briefing).

427 SAT: UNSAT:

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OPERATIONS JPM Concurs that Step 4.1.1.a.2 is N/A.

SAT: UNSAT:

N/A N/A N/A Concurs that Step 4.1.1.a.3 is N/A.

SAT: UNSAT:

N/A N/A Revision: 0 2012 NRC-A1a-SRO Page 7 of 28

OPERATIONS JPM Concurs that Step 4.1.1.b is N/A.

SAT: UNSAT:

N/A N/A N/A 429.0 Verifies Feedwater Inlet Temperatures to SGs from Handout 2 for 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> TODAY:

429.4

• T0418A: 429.0°F 428.7

• T0438A: 429.4°F 429.4 TW

• T0458A: 428.7°F

• T0478A: 429.4°F SAT: UNSAT:

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OPERATIONS JPM Verifies that all Feedwater Inlet Temperatures to SGs are within limits and the YES boxes are checked (x4).

SAT: UNSAT:

429.0 427 +2.0 427 427 X TW 429.4 427 +2.4 427 X TW 428.7 427 +1.7 427 X TW 429.4 427 +2.4 427 X TW Concurs that Step 4.1.4 is N/A.

SAT: UNSAT:

N/A N/A Revision: 0 2012 NRC-A1a-SRO Page 9 of 28

OPERATIONS JPM O Note: The Operator used the last time BOTH the LEFM and Venturi readings were valid - 1720 YESTERDAY O

Uses Handout 1 to determine that last valid RTP using LEFM was 99.59% from 1720 hrs on YESTERDAY (U0601DL).

SAT: UNSAT:

X 99.59 1720 TW Uses Handout 1 to determine that corresponding RTP using Venturi was 98.60% from 1720 hrs YESTERDAY (U0601DV).

X SAT: UNSAT:

98.60 1720 TW 99.59 98.60 1.01 Verifies that correction factor is 1.01.

TW SAT: UNSAT:

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OPERATIONS JPM Verifies current Venturi RTP reading of 98.74.

SAT: UNSAT:

X 98.74 TW Verifies that corrected Venturi RTP is 99.73% (+ 0.1%).

SAT: UNSAT:

98.74 1.01 99.73 TW Verifies readings for Power Range NIs were entered:

• N41: 100.1% - Determines transposition error, should be 101.1

• N42: 99.3%

100.1

• N43: 99.0%;

• N44: 98.3%

99.3 SAT: UNSAT:

99.0 98.3 TW Verifies the difference between corrected Venturis RTP of 99.73% and actual NIs.

SAT: UNSAT:

+0.37 CS: Determines transposition error, should be 101.1.

100.1 99.73 SAT: UNSAT:

99.3 99.73 -0.43 99.0 99.73 -0.37 CS: Determines math error, should be -0.73.

SAT: UNSAT:

98.3 99.73 -1.43 TW Revision: 0 2012 NRC-A1a-SRO Page 11 of 28

OPERATIONS JPM Checks RO calculation for average Power Range NI of 99.18% (+ 0.5).

Note Previous Error for N41 reading carries through (Should have been 99.43)

SAT: UNSAT:

Determines average Power Range NIs less than corrected Venturi RTP and the YES box should have been checked.

SAT: UNSAT:

X 100.1 99.3 99.0 98.3 396.7 Determines that greater than -1.0% deviation exists between actual NIs 396.7 4 99.18 and corrected Venturi RTP and the YES box should have been checked.

SAT: UNSAT:

X X Concurs that all NIs are within 2% of corrected Venturi RTP and the NO box is checked.

SAT: UNSAT:

X Determines that N41 is reading greater than 100.5% and the YES box should have been checked.

SAT: UNSAT:

Revision: 0 2012 NRC-A1a-SRO Page 12 of 28

OPERATIONS JPM Revision: 0 2012 NRC-A1a-SRO Page 13 of 28

OPERATIONS JPM N/A CS: Determines that NIs are in need of adjusting (in accordance with Attachment 6) and that Step 4.6 should have been done due to Step N/A 4.5 conditions.

SAT: UNSAT:

N/A N/A N/A N/A Revision: 0 2012 NRC-A1a-SRO Page 14 of 28

OPERATIONS JPM X

666642289 0650 TODAY T. Willians 0701 TODAY N/A Determines Step 7.1 should have had Comments reporting the need to do NI adjustments.

SAT: UNSAT:

X X

Determines Step 7.2 should have caught Acceptance Criteria NOT met..

SAT: UNSAT:

P. Jones 0715 TODAY Revision: 0 2012 NRC-A1a-SRO Page 15 of 28

OPERATIONS JPM CS: Candidate determines that the surveillance is NOT ACCEPTABLE.

SAT: UNSAT:

CUE: Once the candidate has determined the surveilance is NOT ACCEPTABLE, then the JPM is complete.

Revision: 0 2012 NRC-A1a-SRO Page 16 of 28

OPERATIONS JPM Task Briefing It is currently 0720 (TODAY).

You are the Unit Supervisor in Unit 2.

The LEFM has been out of service for about 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> and is not expected to be returned to service until the next shift. A Thermal Power Calculation was performed by the RO in accordance with 2-OHP-4030-214-029, Reactor Thermal Power, Attachment 2, PPC Derived Reactor Thermal Power Evaluation - Loss of LEFM.

Review the Thermal Power Calculation using the provided data from the Unit 2 PPC and Control Panels, noting all errors if any.

Additional Data:

• 2-SG-9, Point 26, Feedwater Heater 6A & 6B Outlet Temperature is reading 427°F.

Task Briefing Revision: 0 2012 NRC-A1a-SRO Page 17 of 28

OPERATIONS JPM DC Cook Point # : Point Name Database Point Type Point Description Point 1 : U2_U0601DL PPC2 Analog Input LEFM PCT RTP 10 MIN AVG Point 2 : U2_U0601DV PPC2 Analog Input VENT PCT RTP 10 MIN AVG DATE TIME U2_U0601DL U2_U0601DV YESTERDAY 07:00:00.000 99.81 GOOD PC 99.50 GOOD PC YESTERDAY 07:10:00.000 99.80 GOOD PC 99.49 GOOD PC YESTERDAY 07:20:00.000 99.77 GOOD PC 99.45 GOOD PC YESTERDAY 07:30:00.000 99.79 GOOD PC 99.44 GOOD PC YESTERDAY 07:40:00.000 99.80 GOOD PC 99.44 GOOD PC YESTERDAY 07:50:00.000 99.78 GOOD PC 99.45 GOOD PC YESTERDAY 08:00:00.000 99.76 GOOD PC 99.43 GOOD PC YESTERDAY 08:10:00.000 99.80 GOOD PC 99.47 GOOD PC YESTERDAY 08:20:00.000 99.82 GOOD PC 99.47 GOOD PC YESTERDAY 08:30:00.000 99.87 GOOD PC 99.53 GOOD PC YESTERDAY 08:40:00.000 99.83 GOOD PC 99.51 GOOD PC YESTERDAY 08:50:00.000 99.84 GOOD PC 99.53 GOOD PC YESTERDAY 09:00:00.000 99.84 GOOD PC 99.47 GOOD PC YESTERDAY 09:10:00.000 99.91 GOOD PC 99.54 GOOD PC YESTERDAY 09:20:00.000 99.90 GOOD PC 99.55 GOOD PC YESTERDAY 09:30:00.000 99.82 GOOD PC 99.52 GOOD PC YESTERDAY 09:40:00.000 99.84 GOOD PC 99.53 GOOD PC YESTERDAY 09:50:00.000 99.85 GOOD PC 99.50 GOOD PC YESTERDAY 10:00:00.000 99.85 GOOD PC 99.51 GOOD PC YESTERDAY 10:10:00.000 99.83 GOOD PC 99.47 GOOD PC YESTERDAY 10:20:00.000 99.86 GOOD PC 99.50 GOOD PC YESTERDAY 10:30:00.000 99.82 GOOD PC 99.48 GOOD PC YESTERDAY 10:40:00.000 99.87 GOOD PC 99.53 GOOD PC YESTERDAY 10:50:00.000 99.84 GOOD PC 99.50 GOOD PC YESTERDAY 11:00:00.000 99.83 GOOD PC 99.50 GOOD PC YESTERDAY 11:10:00.000 99.81 GOOD PC 99.46 GOOD PC YESTERDAY 11:20:00.000 99.81 GOOD PC 99.47 GOOD PC YESTERDAY 11:30:00.000 99.81 GOOD PC 99.47 GOOD PC YESTERDAY 11:40:00.000 99.80 GOOD PC 99.45 GOOD PC YESTERDAY 11:50:00.000 99.80 GOOD PC 99.45 GOOD PC YESTERDAY 12:00:00.000 99.79 GOOD PC 99.45 GOOD PC YESTERDAY 12:10:00.000 99.75 GOOD PC 99.44 GOOD PC YESTERDAY 12:20:00.000 99.76 GOOD PC 99.41 GOOD PC YESTERDAY 12:30:00.000 99.77 GOOD PC 99.40 GOOD PC YESTERDAY 12:40:00.000 99.71 GOOD PC 99.39 GOOD PC YESTERDAY 12:50:00.000 99.71 GOOD PC 99.40 GOOD PC YESTERDAY 13:00:00.000 99.77 GOOD PC 99.44 GOOD PC YESTERDAY 13:10:00.000 99.73 GOOD PC 99.40 GOOD PC YESTERDAY 13:20:00.000 99.72 GOOD PC 99.36 GOOD PC YESTERDAY 13:30:00.000 99.73 GOOD PC 99.41 GOOD PC YESTERDAY 13:40:00.000 99.71 GOOD PC 99.38 GOOD PC YESTERDAY 13:50:00.000 99.70 GOOD PC 99.39 GOOD PC YESTERDAY 14:00:00.000 99.72 GOOD PC 99.39 GOOD PC HANDOUT-1 Revision: 0 2012 NRC-A1a-SRO Page 18 of 28

OPERATIONS JPM DATE TIME U2_U0601DL U2_U0601DV YESTERDAY 14:10:00.000 99.68 GOOD PC 98.56 GOOD PC YESTERDAY 14:20:00.000 99.64 GOOD PC 98.63 GOOD PC YESTERDAY 14:30:00.000 99.66 GOOD PC 98.64 GOOD PC YESTERDAY 14:40:00.000 99.68 GOOD PC 98.57 GOOD PC YESTERDAY 14:50:00.000 99.73 GOOD PC 98.61 GOOD PC YESTERDAY 15:00:00.000 99.71 GOOD PC 98.64 GOOD PC YESTERDAY 15:10:00.000 99.72 GOOD PC 98.60 GOOD PC YESTERDAY 15:20:00.000 99.75 GOOD PC 98.61 GOOD PC YESTERDAY 15:30:00.000 99.77 GOOD PC 98.64 GOOD PC YESTERDAY 15:40:00.000 99.69 GOOD PC 98.60 GOOD PC YESTERDAY 15:50:00.000 99.71 GOOD PC 98.58 GOOD PC YESTERDAY 16:00:00.000 99.70 GOOD PC 98.59 GOOD PC YESTERDAY 16:10:00.000 99.72 GOOD PC 98.59 GOOD PC YESTERDAY 16:20:00.000 99.70 GOOD PC 98.57 GOOD PC YESTERDAY 16:30:00.000 99.70 GOOD PC 98.57 GOOD PC YESTERDAY 16:40:00.000 99.67 GOOD PC 98.64 GOOD PC YESTERDAY 16:50:00.000 99.70 GOOD PC 98.67 GOOD PC YESTERDAY 17:00:00.000 99.66 GOOD PC 98.64 GOOD PC YESTERDAY 17:10:00.000 99.59 GOOD PC 98.60 GOOD PC YESTERDAY 17:20:00.000 99.59 GOOD PC 98.60 GOOD PC YESTERDAY 17:30:00.000 99.59 GOOD PC 98.38 BAD PC YESTERDAY 17:40:00.000 99.57 GOOD PC 94.44 BAD PC YESTERDAY 17:50:00.000 99.56 GOOD PC 96.44 BAD PC YESTERDAY 18:00:00.000 99.58 GOOD PC 99.44 BAD PC YESTERDAY 18:10:00.000 99.63 GOOD PC 96.40 BAD PC YESTERDAY 18:20:00.000 99.60 GOOD PC 94.46 BAD PC YESTERDAY 18:30:00.000 99.57 GOOD PC 95.43 BAD PC YESTERDAY 18:40:00.000 99.55 GOOD PC 96.39 BAD PC YESTERDAY 18:50:00.000 99.57 GOOD PC 99.45 BAD PC YESTERDAY 19:00:00.000 99.65 GOOD PC 99.41 BAD PC YESTERDAY 19:10:00.000 99.56 GOOD PC 99.45 BAD PC YESTERDAY 19:20:00.000 99.55 GOOD PC 99.39 BAD PC YESTERDAY 19:30:00.000 99.58 GOOD PC 95.40 BAD PC YESTERDAY 19:40:00.000 99.63 GOOD PC 95.38 BAD PC YESTERDAY 19:50:00.000 99.64 GOOD PC 99.31 BAD PC YESTERDAY 20:00:00.000 99.63 GOOD PC 95.20 BAD PC YESTERDAY 20:10:00.000 99.62 GOOD PC 98.99 BAD PC YESTERDAY 20:20:00.000 99.61 GOOD PC 93.93 BAD PC YESTERDAY 20:30:00.000 99.59 GOOD PC 94.60 BAD PC YESTERDAY 20:40:00.000 99.15 BAD PC 95.61 BAD PC YESTERDAY 20:50:00.000 99.03 BAD PC 98.58 BAD PC YESTERDAY 21:00:00.000 99.00 BAD PC 97.56 BAD PC YESTERDAY 21:10:00.000 79.60 BAD PC 98.83 BAD PC YESTERDAY 21:20:00.000 29.28 BAD PC 98.64 GOOD PC YESTERDAY 21:30:00.000 88.99 BAD PC 98.65 GOOD PC YESTERDAY 21:40:00.000 48.40 BAD PC 98.04 GOOD PC YESTERDAY 21:50:00.000 57.95 BAD PC 98.61 GOOD PC YESTERDAY 22:00:00.000 27.49 BAD PC 99.13 GOOD PC YESTERDAY 22:10:00.000 77.11 BAD PC 98.61 GOOD PC YESTERDAY 22:20:00.000 87.02 BAD PC 98.60 GOOD PC YESTERDAY 22:30:00.000 97.04 BAD PC 98.62 GOOD PC YESTERDAY 22:40:00.000 17.04 BAD PC 98.61 GOOD PC YESTERDAY 22:50:00.000 27.05 BAD PC 98.62 GOOD PC YESTERDAY 23:00:00.000 47.08 BAD PC 98.55 GOOD PC HANDOUT-1 Revision: 0 2012 NRC-A1a-SRO Page 19 of 28

OPERATIONS JPM DATE TIME U2_U0601DL U2_U0601DV YESTERDAY 23:10:00.000 96.98 BAD PC 96.66 GOOD PC YESTERDAY 23:20:00.000 27.22 BAD PC 96.89 GOOD PC YESTERDAY 23:30:00.000 36.97 BAD PC 96.59 GOOD PC YESTERDAY 23:40:00.000 47.07 BAD PC 96.73 GOOD PC YESTERDAY 23:50:00.000 16.88 BAD PC 96.53 GOOD PC TODAY 00:00:00.000 87.03 BAD PC 96.70 GOOD PC TODAY 00:10:00.000 36.77 BAD PC 96.42 GOOD PC TODAY 00:20:00.000 47.12 BAD PC 96.81 GOOD PC TODAY 00:30:00.000 56.87 BAD PC 96.54 GOOD PC TODAY 00:40:00.000 16.75 BAD PC 96.43 GOOD PC TODAY 00:50:00.000 96.95 BAD PC 96.62 GOOD PC TODAY 01:00:00.000 36.81 BAD PC 96.50 GOOD PC TODAY 01:10:00.000 56.94 BAD PC 96.60 GOOD PC TODAY 01:20:00.000 57.17 BAD PC 96.85 GOOD PC TODAY 01:30:00.000 17.73 BAD PC 97.39 GOOD PC TODAY 01:40:00.000 37.94 BAD PC 97.60 GOOD PC TODAY 01:50:00.000 17.94 BAD PC 97.63 GOOD PC TODAY 02:00:00.000 18.07 BAD PC 97.74 GOOD PC TODAY 02:10:00.000 48.43 BAD PC 98.12 GOOD PC TODAY 02:20:00.000 38.80 BAD PC 98.49 GOOD PC TODAY 02:30:00.000 48.91 BAD PC 98.59 GOOD PC TODAY 02:40:00.000 18.96 BAD PC 98.66 GOOD PC TODAY 02:50:00.000 29.12 BAD PC 98.78 GOOD PC TODAY 03:00:00.000 79.24 BAD PC 98.89 GOOD PC TODAY 03:10:00.000 99.48 BAD PC 98.87 GOOD PC TODAY 03:20:00.000 89.65 BAD PC 98.82 GOOD PC TODAY 03:30:00.000 39.77 BAD PC 98.94 GOOD PC TODAY 03:40:00.000 69.87 BAD PC 98.85 GOOD PC TODAY 03:50:00.000 19.95 BAD PC 98.88 GOOD PC TODAY 04:00:00.000 49.91 BAD PC 98.89 GOOD PC TODAY 04:10:00.000 99.86 BAD PC 98.92 GOOD PC TODAY 04:20:00.000 29.88 BAD PC 98.93 GOOD PC TODAY 04:30:00.000 69.92 BAD PC 98.98 GOOD PC TODAY 04:40:00.000 39.97 BAD PC 98.92 GOOD PC TODAY 04:50:00.000 19.91 BAD PC 98.87 GOOD PC TODAY 05:00:00.000 29.82 BAD PC 98.79 GOOD PC TODAY 05:10:00.000 49.88 BAD PC 98.82 GOOD PC TODAY 05:20:00.000 19.82 BAD PC 98.80 GOOD PC TODAY 05:30:00.000 89.86 BAD PC 98.92 GOOD PC TODAY 05:40:00.000 79.87 BAD PC 98.96 GOOD PC TODAY 05:50:00.000 69.87 BAD PC 98.85 GOOD PC TODAY 06:00:00.000 29.90 BAD PC 98.88 GOOD PC TODAY 06:10:00.000 79.98 BAD PC 98.91 GOOD PC TODAY 06:20:00.000 69.92 BAD PC 98.89 GOOD PC TODAY 06:30:00.000 59.95 BAD PC 98.82 GOOD PC TODAY 06:40:00.000 39.87 BAD PC 98.83 GOOD PC TODAY 06:50:00.000 59.85 BAD PC 98.78 GOOD PC TODAY 07:00:00.000 49.88 BAD PC 98.74 GOOD PC HANDOUT-1 Revision: 0 2012 NRC-A1a-SRO Page 20 of 28

OPERATIONS JPM DC Cook Point #  : Point Name Database Point Type Point Description Point 1  : U2_T0418A PPC2 Analog Input SG 1 FEEDWATER TEMPERATURE FTQ-210 Point 2  : U2_T0438A PPC2 Analog Input SG 2 FEEDWATER TEMPERATURE FTQ-220 Point 3  : U2_T0458A PPC2 Analog Input SG 3 FEEDWATER TEMPERATURE FTQ-230 Point 4  : U2_T0478A PPC2 Analog Input SG 4 FEEDWATER TEMPERATURE FTQ-240 DATE TIME U2_T0418A U2_T0438A U2_T0458A U2_T0478A YESTERDAY 07:00:00.000 429.0 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 07:10:00.000 429.1 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 07:20:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 07:30:00.000 429.0 GOOD DEGF 429.0 GOOD DEGF 428.3 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 07:40:00.000 428.9 GOOD DEGF 429.0 GOOD DEGF 428.2 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 07:50:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.3 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 08:00:00.000 429.0 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 08:10:00.000 429.0 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 08:20:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 08:30:00.000 429.2 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 08:40:00.000 429.0 GOOD DEGF 429.0 GOOD DEGF 428.4 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 08:50:00.000 429.2 GOOD DEGF 429.3 GOOD DEGF 428.4 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 09:00:00.000 429.0 GOOD DEGF 429.3 GOOD DEGF 428.4 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 09:10:00.000 429.2 GOOD DEGF 429.3 GOOD DEGF 428.6 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 09:20:00.000 429.2 GOOD DEGF 429.3 GOOD DEGF 428.6 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 09:30:00.000 428.9 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 09:40:00.000 429.2 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 09:50:00.000 429.1 GOOD DEGF 429.3 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 10:00:00.000 429.1 GOOD DEGF 429.3 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 10:10:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.4 GOOD DEGF YESTERDAY 10:20:00.000 429.1 GOOD DEGF 429.3 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 10:30:00.000 429.2 GOOD DEGF 429.3 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 10:40:00.000 429.2 GOOD DEGF 429.3 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 10:50:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 11:00:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 11:10:00.000 428.9 GOOD DEGF 429.2 GOOD DEGF 428.2 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 11:20:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.2 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 11:30:00.000 429.1 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.3 GOOD DEGF HANDOUT-2 Revision: 0 2012 NRC-A1a-SRO Page 21 of 28

OPERATIONS JPM DATE TIME U2_T0418A U2_T0438A U2_T0458A U2_T0478A YESTERDAY 11:40:00.000 428.9 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 11:50:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.3 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 12:00:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 12:10:00.000 428.9 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 12:20:00.000 428.9 GOOD DEGF 429.2 GOOD DEGF 428.3 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 12:30:00.000 428.9 GOOD DEGF 429.2 GOOD DEGF 428.3 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 12:40:00.000 428.9 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 12:50:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.3 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 13:00:00.000 428.9 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 13:10:00.000 428.9 GOOD DEGF 429.3 GOOD DEGF 428.3 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 13:20:00.000 428.9 GOOD DEGF 429.2 GOOD DEGF 428.2 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 13:30:00.000 428.9 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 13:40:00.000 428.9 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.0 GOOD DEGF YESTERDAY 13:50:00.000 428.9 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 14:00:00.000 428.9 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 14:10:00.000 428.9 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 14:20:00.000 428.8 GOOD DEGF 429.0 GOOD DEGF 428.3 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 14:30:00.000 428.8 GOOD DEGF 429.0 GOOD DEGF 428.2 GOOD DEGF 429.0 GOOD DEGF YESTERDAY 14:40:00.000 429.0 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 14:50:00.000 429.0 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 15:00:00.000 429.0 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 15:10:00.000 429.0 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 15:20:00.000 428.9 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 15:30:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 15:40:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 15:50:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 16:00:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 16:10:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 16:20:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 16:30:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 16:40:00.000 428.8 GOOD DEGF 429.0 GOOD DEGF 428.3 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 16:50:00.000 428.9 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 17:00:00.000 428.9 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 17:10:00.000 429.1 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 17:20:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 17:30:00.000 429.0 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 17:40:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 17:50:00.000 429.1 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 18:00:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 18:10:00.000 429.0 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF HANDOUT-2 Revision: 0 2012 NRC-A1a-SRO Page 22 of 28

OPERATIONS JPM DATE TIME U2_T0418A U2_T0438A U2_T0458A U2_T0478A YESTERDAY 18:20:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 18:30:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 18:40:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 18:50:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 19:00:00.000 429.0 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 19:10:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 19:20:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 19:30:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 19:40:00.000 428.9 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 19:50:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 20:00:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF YESTERDAY 20:10:00.000 429.0 GOOD DEGF 429.0 GOOD DEGF 428.3 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 20:20:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.3 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 20:30:00.000 429.0 GOOD DEGF 429.1 GOOD DEGF 428.4 GOOD DEGF 429.1 GOOD DEGF YESTERDAY 20:40:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.3 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 20:50:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 21:00:00.000 428.9 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.2 GOOD DEGF YESTERDAY 21:10:00.000 428.7 GOOD DEGF 428.9 GOOD DEGF 428.0 GOOD DEGF 429.0 GOOD DEGF YESTERDAY 21:20:00.000 428.5 GOOD DEGF 428.6 GOOD DEGF 427.9 GOOD DEGF 428.9 GOOD DEGF YESTERDAY 21:30:00.000 428.2 GOOD DEGF 428.3 GOOD DEGF 427.5 GOOD DEGF 428.3 GOOD DEGF YESTERDAY 21:40:00.000 427.5 GOOD DEGF 427.8 GOOD DEGF 427.0 GOOD DEGF 427.8 GOOD DEGF YESTERDAY 21:50:00.000 427.3 GOOD DEGF 427.5 GOOD DEGF 426.7 GOOD DEGF 427.6 GOOD DEGF YESTERDAY 22:00:00.000 426.8 GOOD DEGF 426.9 GOOD DEGF 426.2 GOOD DEGF 427.0 GOOD DEGF YESTERDAY 22:10:00.000 426.7 GOOD DEGF 426.8 GOOD DEGF 426.1 GOOD DEGF 427.0 GOOD DEGF YESTERDAY 22:20:00.000 426.7 GOOD DEGF 426.8 GOOD DEGF 426.0 GOOD DEGF 427.0 GOOD DEGF YESTERDAY 22:30:00.000 426.7 GOOD DEGF 426.9 GOOD DEGF 426.2 GOOD DEGF 426.9 GOOD DEGF YESTERDAY 22:40:00.000 426.7 GOOD DEGF 426.9 GOOD DEGF 426.2 GOOD DEGF 427.0 GOOD DEGF YESTERDAY 22:50:00.000 426.5 GOOD DEGF 426.7 GOOD DEGF 426.0 GOOD DEGF 426.9 GOOD DEGF YESTERDAY 23:00:00.000 426.3 GOOD DEGF 426.4 GOOD DEGF 425.8 GOOD DEGF 426.6 GOOD DEGF YESTERDAY 23:10:00.000 427.0 GOOD DEGF 427.1 GOOD DEGF 426.3 GOOD DEGF 427.1 GOOD DEGF YESTERDAY 23:20:00.000 426.7 GOOD DEGF 426.8 GOOD DEGF 426.1 GOOD DEGF 427.0 GOOD DEGF YESTERDAY 23:30:00.000 426.4 GOOD DEGF 426.6 GOOD DEGF 425.9 GOOD DEGF 426.7 GOOD DEGF YESTERDAY 23:40:00.000 426.7 GOOD DEGF 426.7 GOOD DEGF 425.9 GOOD DEGF 426.9 GOOD DEGF YESTERDAY 23:50:00.000 426.4 GOOD DEGF 426.5 GOOD DEGF 425.8 GOOD DEGF 426.7 GOOD DEGF TODAY 00:00:00.000 426.6 GOOD DEGF 426.8 GOOD DEGF 426.1 GOOD DEGF 426.7 GOOD DEGF TODAY 00:10:00.000 426.5 GOOD DEGF 426.9 GOOD DEGF 425.9 GOOD DEGF 426.7 GOOD DEGF TODAY 00:20:00.000 426.7 GOOD DEGF 426.7 GOOD DEGF 425.9 GOOD DEGF 427.0 GOOD DEGF TODAY 00:30:00.000 426.4 GOOD DEGF 426.6 GOOD DEGF 425.9 GOOD DEGF 426.6 GOOD DEGF TODAY 00:40:00.000 426.7 GOOD DEGF 427.0 GOOD DEGF 426.2 GOOD DEGF 426.8 GOOD DEGF TODAY 00:50:00.000 427.0 GOOD DEGF 427.1 GOOD DEGF 426.3 GOOD DEGF 427.2 GOOD DEGF HANDOUT-2 Revision: 0 2012 NRC-A1a-SRO Page 23 of 28

OPERATIONS JPM DATE TIME U2_T0418A U2_T0438A U2_T0458A U2_T0478A TODAY 01:00:00.000 426.6 GOOD DEGF 426.7 GOOD DEGF 425.9 GOOD DEGF 426.9 GOOD DEGF TODAY 01:10:00.000 426.6 GOOD DEGF 426.7 GOOD DEGF 426.1 GOOD DEGF 426.8 GOOD DEGF TODAY 01:20:00.000 427.1 GOOD DEGF 427.2 GOOD DEGF 426.5 GOOD DEGF 427.3 GOOD DEGF TODAY 01:30:00.000 427.4 GOOD DEGF 427.7 GOOD DEGF 426.9 GOOD DEGF 427.7 GOOD DEGF TODAY 01:40:00.000 427.6 GOOD DEGF 427.7 GOOD DEGF 427.0 GOOD DEGF 427.7 GOOD DEGF TODAY 01:50:00.000 427.4 GOOD DEGF 427.8 GOOD DEGF 427.0 GOOD DEGF 427.8 GOOD DEGF TODAY 02:00:00.000 427.8 GOOD DEGF 428.0 GOOD DEGF 427.2 GOOD DEGF 428.0 GOOD DEGF TODAY 02:10:00.000 427.9 GOOD DEGF 428.1 GOOD DEGF 427.3 GOOD DEGF 428.1 GOOD DEGF TODAY 02:20:00.000 428.3 GOOD DEGF 428.4 GOOD DEGF 427.8 GOOD DEGF 428.6 GOOD DEGF TODAY 02:30:00.000 428.3 GOOD DEGF 428.5 GOOD DEGF 427.8 GOOD DEGF 428.5 GOOD DEGF TODAY 02:40:00.000 428.4 GOOD DEGF 428.5 GOOD DEGF 427.8 GOOD DEGF 428.7 GOOD DEGF TODAY 02:50:00.000 428.6 GOOD DEGF 428.7 GOOD DEGF 428.0 GOOD DEGF 428.7 GOOD DEGF TODAY 03:00:00.000 428.8 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.0 GOOD DEGF TODAY 03:10:00.000 428.8 GOOD DEGF 429.1 GOOD DEGF 428.3 GOOD DEGF 429.1 GOOD DEGF TODAY 03:20:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.2 GOOD DEGF TODAY 03:30:00.000 429.2 GOOD DEGF 429.3 GOOD DEGF 428.6 GOOD DEGF 429.3 GOOD DEGF TODAY 03:40:00.000 429.2 GOOD DEGF 429.3 GOOD DEGF 428.6 GOOD DEGF 429.3 GOOD DEGF TODAY 03:50:00.000 429.1 GOOD DEGF 429.3 GOOD DEGF 428.6 GOOD DEGF 429.4 GOOD DEGF TODAY 04:00:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF TODAY 04:10:00.000 429.2 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF TODAY 04:20:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF TODAY 04:30:00.000 429.1 GOOD DEGF 429.3 GOOD DEGF 428.5 GOOD DEGF 429.4 GOOD DEGF TODAY 04:40:00.000 429.3 GOOD DEGF 429.4 GOOD DEGF 428.6 GOOD DEGF 429.4 GOOD DEGF TODAY 04:50:00.000 429.1 GOOD DEGF 429.3 GOOD DEGF 428.5 GOOD DEGF 429.2 GOOD DEGF TODAY 05:00:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.4 GOOD DEGF 429.3 GOOD DEGF TODAY 05:10:00.000 429.0 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF TODAY 05:20:00.000 429.1 GOOD DEGF 429.3 GOOD DEGF 428.6 GOOD DEGF 429.3 GOOD DEGF TODAY 05:30:00.000 429.2 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF TODAY 05:40:00.000 429.1 GOOD DEGF 429.3 GOOD DEGF 428.7 GOOD DEGF 429.4 GOOD DEGF TODAY 05:50:00.000 429.2 GOOD DEGF 429.3 GOOD DEGF 428.5 GOOD DEGF 429.4 GOOD DEGF TODAY 06:00:00.000 429.1 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.4 GOOD DEGF TODAY 06:10:00.000 429.2 GOOD DEGF 429.4 GOOD DEGF 428.6 GOOD DEGF 429.4 GOOD DEGF TODAY 06:20:00.000 429.2 GOOD DEGF 429.3 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF TODAY 06:30:00.000 429.2 GOOD DEGF 429.3 GOOD DEGF 428.6 GOOD DEGF 429.4 GOOD DEGF TODAY 06:40:00.000 429.1 GOOD DEGF 429.3 GOOD DEGF 428.6 GOOD DEGF 429.3 GOOD DEGF TODAY 06:50:00.000 429.2 GOOD DEGF 429.2 GOOD DEGF 428.5 GOOD DEGF 429.3 GOOD DEGF TODAY 07:00:00.000 429.0 GOOD DEGF 429.4 GOOD DEGF 428.7 GOOD DEGF 429.4 GOOD DEGF HANDOUT-2 Revision: 0 2012 NRC-A1a-SRO Page 24 of 28

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OPERATIONS JPM NUMBER: 2012 NRC-A1b TIME: 15 MINUTES TITLE: Determine Ultimate Heat Sink REVISION: 0 Temperature Revision: 0 2012 NRC-A1b Page 1 of 14

OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 02-OHL-4030-SOM-043 Unit 2 Tours - U2 CR M5, 6 & D Shift Checks K/A Number: 2.1.7 K/A Imp.: RO: 4.4 SRO: 4.7 Task Number: STP0390201 Perform Shiftly Surveillance Checks for Modes 5 & 6 TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS

• Task Briefing sheet

• 02-OHL-4030-SOM-043, Sequence 112-124, Pages 53-59

• Calculator (If requested, provide OP-2-5119A, CW System - Drawing of Main Condenser Water Boxes)

• Calculator EVALUATION SETTINGS Classroom EVALUATION METHOD: PERFORM: SIMULATE:

SIMULATOR/LAB SETUP N/A EVALUATOR INSTRUCTIONS

1. Initial the Prerequisites of Attachment 2.

2. Brief the operator (May be performed by giving out Task Briefing sheet).

3. Announce start of the JPM.

4. Perform evolution.

5. At completion of evolution, announce the JPM is complete.

6. Document evaluation performance.

Revision: 0 2012 NRC-A1b Page 2 of 14

OPERATIONS JPM TASK BRIEFING Given the following conditions on Unit 2:

• Unit is in Mode 6.

• The reactor was shutdown 130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br /> ago.

• Fuel Movement is in Progress.

• A South and C North condenser Waterboxes are Out Of Service & Isolated.

MTI reports Circ Water (CW) temperature transmitters are not functioning properly due to a power supply problem. Therefore, the CW Temp Recorder SG-21 and PPC address U0200 are Out Of Service.

The Unit Supervisor directs you to perform Unit 2 Tours sequence 112 through 124 of 02-OHL-4030-SOM-043, pages 53 to 59, to ensure all Acceptance Criteria are met for the current CW System configuration.

An AEO has already recorded the following temperature readings from the Unit 2 CW Inlets:

Condenser A Condenser B Condenser C WTX-106 (S) = 69.8 WTX-206 (S) = 77.8 WTX-306 (S) = 77.7 WTX-107 (S) = 69.8 WTX-207 (S) = 77.4 WTX-307 (S) = 77.6 WTX-108 (S) = 69.2 WTX-208 (S) = 77.5 WTX-308 (S) = 77.6 WTX-102 (N) = 77.6 WTX-202 (N) = 77.5 WTX-302 (N) = 69.2 WTX-103 (N) = 77.7 WTX-203 (N) = 77.5 WTX-303 (N) = 70.9 WTX-104 (N) = 77.6 WTX-204 (N) = 77.7 WTX-304 (N) = 69.3 Temperature readings were obtained using Instrument ID CNP-147, Make/Model FLUKE -51 with Calibration Current (Next Due Cal. Date is 01/12/2013).

TASK STANDARDS The Candidate correctly identifies that the South Waterbox for A Condenser and the North Waterbox for the C Condenser are isolated which invalidates their associated temperatures.

The Candidate identifies that CW Temperature is > 77.5 F And Fuel Movement Revision: 0 2012 NRC-A1b Page 3 of 14

OPERATIONS JPM must be stopped until the reactor has been shutdown for >148 hours.

Revision: 0 2012 NRC-A1b Page 4 of 14

OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

CUE: If requested, then provide OP-2-5119A, CW Drawing.

CUE: If asked, then say You are on DAYS.

CS: Records YES due to reactor was shutdown 130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br /> ago.

SAT: UNSAT:

Revision: 0 2012 NRC-A1b Page 5 of 14

OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Records FLUKE for the method used to obtain temperatures (SG-21 and PPC are unavailable).

SAT: UNSAT:

Determines step is N/A.

Revision: 0 2012 NRC-A1b Page 6 of 14

OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Records Instrument ID CNP-147 from briefing sheet.

SAT: UNSAT:

Records Instrument Make/Model FLUKE 51 from briefing sheet.

SAT: UNSAT:

Records YES that calibration is current from briefing sheet.

SAT: UNSAT:

Revision: 0 2012 NRC-A1b Page 7 of 14

OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

CS: Records ONE of the A North Waterbox Points from the unisolated condenser:

• WTX-102

• WTX-103

• WTX-104 SAT: UNSAT:

CS: Records the (ONE) temperature corresponding to the A North Waterbox Point listed in the previous step:

• WTX-102 = 77.6

• WTX-103 = 77.7

• WTX-104 = 77.6 SAT: UNSAT:

Revision: 0 2012 NRC-A1b Page 8 of 14

OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

CS: Records ONE of the B Waterbox Points:

• WTX-206

• WTX-207

• WTX-208

• WTX-202

• WTX-203

• WTX-204 SAT: UNSAT:

CS: Records the (ONE) temperature corresponding to the B Waterbox Point listed in the previous step:

• WTX-206 = 77.8

• WTX-207 = 77.4

• WTX-208 = 77.5

• WTX-202 = 77.5

• WTX-203 = 77.5 Revision: 0 2012 NRC-A1b Page 9 of 14

OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

• WTX-204 = 77.7 SAT: UNSAT:

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

CS: Records ONE of the C South Waterbox Points from the unisolated condenser:

• WTX-306

• WTX-307

• WTX-308 SAT: UNSAT:

CS: Records the (ONE) temperature corresponding to the C South Waterbox Point listed in the previous step:

• WTX-306 = 77.7

• WTX-307 = 77.6

• WTX-308 = 77.6 SAT: UNSAT:

Note: The candidate may announce that the C Waterbox temperature is too high and fuel movement must be stopped (See CS on next page).

Revision: 0 2012 NRC-A1b Page 11 of 14

OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

CS: Records average of the three temperatures entered in the boxes above (value should be between 77.53ºF -

77.73ºF).

SAT: UNSAT:

CS: Candidate informs SRO that the C Waterbox temperature is greater than 77.5 ºF and fuel movement must be stopped since the reactor has been shutdown less than 148 hours0.00171 days <br />0.0411 hours <br />2.44709e-4 weeks <br />5.6314e-5 months <br />.

SAT: UNSAT:

CUE: JPM IS COMPLETE.

Revision: 0 2012 NRC-A1b Page 12 of 14

OPERATIONS JPM B Condenser South Inlet Temp WTX-206 77.8 B Condenser South Inlet Temp WTX-207 77.4 B Condenser South Inlet Temp WTX-208 77.5 B Condenser North Inlet Temp WTX-202 77.5 B Condenser North Inlet Temp WTX-203 77.5 B Condenser North Inlet Temp WTX-204 77.7 All Temperatures are valid A Condenser South Inlet Temp WTX-106 69.8 C Condenser South Inlet Temp WTX-306 77.7 A Condenser South Inlet Temp WTX-107 69.8 C Condenser South Inlet Temp WTX-307 77.6 A Condenser South Inlet Temp WTX-108 69.2 C Condenser South Inlet Temp WTX-308 77.6 A Condenser North Inlet Temp WTX-102 77.6 C Condenser North Inlet Temp WTX-302 69.2 A Condenser North Inlet Temp WTX-103 77.7 C Condenser North Inlet Temp WTX-303 70.9 A Condenser North Inlet Temp WTX-104 77.6 C Condenser North Inlet Temp WTX-304 69.3 North Temperatures are valid South Temperatures are valid Revision: 0 2012 NRC-A1b Page 13 of 14

Task Briefing Given the following conditions on Unit 2:

• Unit is in Mode 6.

• The reactor was shutdown 130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br /> ago.

• Fuel Movement is in Progress.

• A South and C North condenser Waterboxes are Out Of Service & Isolated.

MTI reports Circ Water (CW) temperature transmitters are not functioning properly due to a power supply problem. Therefore, the CW Temp Recorder SG-21 and PPC address U0200 are Out Of Service.

The Unit Supervisor directs you to perform Unit 2 Tours sequence 112 through 124 of 02-OHL-4030-SOM-043, pages 53 to 59, to ensure all Acceptance Criteria are met for the current CW System configuration.

An AEO has already recorded the following temperature readings from the Unit 2 CW Inlets:

Condenser A Condenser B Condenser C WTX-106 (S) = 69.8 WTX-206 (S) = 77.8 WTX-306 (S) = 77.7 WTX-107 (S) = 69.8 WTX-207 (S) = 77.4 WTX-307 (S) = 77.6 WTX-108 (S) = 69.2 WTX-208 (S) = 77.5 WTX-308 (S) = 77.6 WTX-102 (N) = 77.6 WTX-202 (N) = 77.5 WTX-302 (N) = 69.2 WTX-103 (N) = 77.7 WTX-203 (N) = 77.5 WTX-303 (N) = 70.9 WTX-104 (N) = 77.6 WTX-204 (N) = 77.7 WTX-304 (N) = 69.3 Temperature readings were obtained using Instrument ID CNP-147, Make/Model FLUKE -

51 with Calibration Current (Next Due Cal. Date is 01/12/2013).

Revision: 0 2012 NRC-A1b Page 14 of 14

Unit 2 Open Items Summary Open Item # Component Noun System Open Item Entered 2-2012-0594 2-VTR-300 Control Room Air Temperature VCRAC Tuesday, May 22, 2012 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.7.11 2012-13357 Condition Description Notes 12-IHP-5021-IMP-001 (55384995-01) Temperature Instrument Calibration Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2012-0600 2-NTR-12 CORE EXIT THERMOCOUPLE LOCATION F-15 NI Monday, July 23, 2012 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.3.3 A Modes 1, 2, 3, and 4 Condition Description Notes Failed TC Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2012-0601 2-NRV-153 PRESSURIZER PORV NRV-153 PZR Monday, July 23, 2012 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.4.12 F N/A Modes 5 & 6 3.4.12 E N/A Mode 4 3.4.11 A N/A Modes 1, 2, and 3 Condition Description Notes Emergency Air Tank is depressurized and Isolated due to air leak at pressure connection Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2012-0602 2-IMO-110 Safety Injection Accumulator Discharge Valve ECCS Monday, July 23, 2012 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.1 B A Modes 1, 2 and 3 > 1000 psig Condition Description Notes Valve is tagged closed to prevent Injection Required for SR 3.4.12.3 Procedure Title Drop Dead Date Monday, July 23, 2012 Page 1 of 3

Open Item # Component Noun System Open Item Entered 2-2012-0603 2-IMO-120 SAFETY INJECTION ACCUMULATOR DISCHARGE VALVE ECCS Monday, July 23, 2012 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.1 B A Modes 1, 2 and 3 > 1000 psig Condition Description Notes Valve is tagged closed to prevent Injection Required for SR 3.4.12.3 Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2012-0604 2-IMO-130 SAFETY INJECTION ACCUMULATOR DISCHARGE VALVE ECCS Monday, July 23, 2012 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.1 B B Modes 1, 2 and 3 > 1000 psig Condition Description Notes Valve is tagged closed to prevent Injection Required for SR 3.4.12.3 Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2012-0605 2-IMO-140 SAFETY INJECTION ACCUMULATOR DISCHARGE VALVE ECCS Monday, July 23, 2012 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.1 B B Modes 1, 2 and 3 > 1000 psig Condition Description Notes Valve is tagged closed to prevent Injection Required for SR 3.4.12.3 Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2012-0606 2-PP-26N NORTH SAFETY INJECTION PUMP ECCS Monday, July 23, 2012 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.2 A A Modes 1, 2, and 3 Condition Description Notes SI Pumps Tagged to Prevent Injection Required for SR 3.4.12.1 Procedure Title Drop Dead Date Monday, July 23, 2012 Page 2 of 3

Open Item # Component Noun System Open Item Entered 2-2012-0607 2-PP-26S SOUTH SAFETY INJECTION PUMP ECCS Monday, July 23, 2012 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.2 A B Modes 1, 2, and 3 Condition Description Notes SI Pumps Tagged to Prevent Injection Required for SR 3.4.12.1 Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2012-0608 2-SV-103 RHR Suction Line Relief Valve RHR Monday, July 23, 2012 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.4.12 E N/A MODE 4 when any RCS cold leg temperature is 299°F 3.4.12 F N/A Modes 5 and 6, when the vessel head is on 5.5.6 Condition Description Notes RHR Suction Line Relief Valve failed to lift at required setpoint Valve did not Open Until 460 psig.

Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2012-0609 2-PP-50E East CCP ECCS Monday, July 23, 2012 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.2 A A Modes 1, 2, 3 Condition Description Notes CCP Tagged Out to Prevent Injection Required for SR 3.4.12.2 Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2012-0610 2-SRA-2900 SJAE Radiation Monitor RMS Saturday, June 23, 2012 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 8.3.8 C Condition Description Notes RP has not completed Operability recommendation checks following I & C board replacement under WOT 55403403 Procedure Title Drop Dead Date Monday, July 23, 2012 Page 3 of 3

OPERATIONS JPM NUMBER: 2012 NRC-A2-RO TIME: 15 MINUTES TITLE: Perform Unit 2 LTOP Verification REVISION: 0 Revision: 0 2012 NRC-A2-RO.doc Page 1 of 9

OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 2-OHP-4030-214-030 Daily and Shiftly Surveillance Checks K/A Number: 2.2.37 K/A Imp.: RO: 3.6 SRO: 4.6 Task Number: STP0390201 Perform Shiftly Surveillance checks for MODE 5 & 6 TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS

1. Task Briefing sheet

2. Work Management Listing (Open Items) - 2 pages

3. Unit 2 Technical Specifications

4. 2-OHP-4030-214-030, Daily And Shiftly Surveillance Checks:

• Data Sheet 20,LTOP Verification

• Data Sheet 20A, LTOP Verification LCO 3.4.12.A

• Data Sheet 20B, LTOP Verification LCO 3.4.12.B ATTACHMENTS None EVALUATION SETTINGS Classroom.

EVALUATION METHOD: PERFORM: SIMULATE:

Revision: 0 2012 NRC-A2-RO.doc Page 2 of 9

OPERATIONS JPM SIMULATOR/LAB SETUP None.

EVALUATOR INSTRUCTIONS

1. Brief the operator (May be performed by giving out Task Briefing sheet).

2. Announce start of the JPM.

3. Perform evolution.

4. At completion of evolution, announce the JPM is complete.

5. Document evaluation performance.

TASK BRIEFING The US directs you to determine whether the Unit 2 LTOP Requirements are met per 2-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20.

To determine equipment status, use the Work Management Listing (Open Items - attachment) and the Equipment Availability Table, as shown below:

Equipment Availability Table COMPONENT I.D.: DESCRIPTION: STATUS:

2-NMO-152 PORV Block Valve Open & Energized 2-NMO-153 PORV Block Valve Open & Energized 2-NRV-152 Control Selector Cold Over-Pressure Block for Cold Over Press 2-NRV-152 2-NRV-153 Control Selector Cold Over-Pressure Block for Cold Over Press 2-NRV-153 2-IMO-128 Return from Hot Leg 2 Open & Energized 2-ICM-129 Return from Hot Leg 2 Open & Energized Annunciator Panel 208 2-NRV-152 EMER AIR TANK NOT Lit Drop 27 PRESSURE LOW Annunciator Panel 208 2-NRV-153 EMER AIR TANK Lit Drop 28 PRESSURE LOW 2-PP-50E East Centrifugal Charging Pump PTL (Racked Out) 2-PP-50W West Centrifugal Charging Pump Running (Racked In)

Loop 2 WR Cold Leg Temp RCS Lowest Cold Leg Temperature 185o F Revision: 0 2012 NRC-A2-RO.doc Page 3 of 9

OPERATIONS JPM RCS WR Pressure RCS Highest Reading Pressure 230 psig 2-NPS-121 2-PP-26N North Safety Injection Pump PTL (Racked Out) 2-PP-26S South Safety Injection Pump PTL (Racked Out) 2-NTA-251 Pressurizer Liquid Temp 400o F 2-IMO-110, 120, 130, 140 SI Accumulator Isolation Valves Closed & De-Energized GENERAL STANDARDS/PRECAUTIONS When directed by the Unit Supervisor, determine if LTOP Requirements for Unit 2 are met per 2-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20.

Revision: 0 2012 NRC-A2-RO.doc Page 4 of 9

OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

General CUES:

Provide a copy of the following handouts:

1) Work Management Listing (Open Items) - 3 pages.

2) 2-OHP-4030-214-030, Daily and Shiftly Surveillance Checks:

• Data Sheet 20

• Data Sheet 20A

• Data Sheet 20B CS: Determines based on Task Briefing information that Data Sheet 20A, LTOP Verification LCO 3.4.12.A is applicable.

SAT: UNSAT:

Note: Data Sheet 20B is for LCO 3.4.12.B when Both CCPs are available.

Note: Candidate should complete Data Sheet 20A, per following page prior to completing the remainder of Data Sheet 20.

Revision: 0 2012 NRC-A2-RO.doc Page 5 of 9

OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

CS: Marks page as shown [at Xs] (only one PORV is operable and RHR Suction Relief In-Operable).

SAT: UNSAT:

Note: RHR Suction Relief is In-Operable because of failed relief setpoint (See Work Management Listing - Page 2).

CS: Determines that LTOP Requirements are NOT Met.

SAT: UNSAT:

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Completes Section 3 based on Task Brief information, Work Management Listing, and Data Sheet 20A:

SAT: UNSAT:

• Accumulators Isolated (Yes)

• RHR Suctions Isolations Open (Yes)

• PORV Block Valves Open (Yes)

• Data Sheet 20A is Met (NO)

• Data Sheet 20B is met (N/A)

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

CS: Informs US/SM that LTOP Requirements are NOT Met.

SAT: UNSAT:

CUE: Acknowledge Test Results. When candidate documents FINAL CONDITIONS in step 4.1, then JPM is Complete.

Revision: 0 2012 NRC-A2-RO.doc Page 8 of 9

Task Briefing The US directs you to determine whether the Unit 2 LTOP Requirements are met per 2-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20.

To determine equipment status, use the Work Management Listing (Open Items - attachment) and the Equipment Availability Table, as shown below:

Equipment Availability Table COMPONENT I.D.: DESCRIPTION: STATUS:

2-NMO-152 PORV Block Valve Open & Energized 2-NMO-153 PORV Block Valve Open & Energized 2-NRV-152 Control Selector Cold Over-Pressure Block for Cold Over Press 2-NRV-152 2-NRV-153 Control Selector Cold Over-Pressure Block for Cold Over Press 2-NRV-153 2-IMO-128 Return from Hot Leg 2 Open & Energized 2-ICM-129 Return from Hot Leg 2 Open & Energized Annunciator Panel 208 2-NRV-152 EMER AIR TANK NOT Lit Drop 27 PRESSURE LOW Annunciator Panel 208 2-NRV-153 EMER AIR TANK Lit Drop 28 PRESSURE LOW 2-PP-50E East Centrifugal Charging Pump PTL (Racked Out) 2-PP-50W West Centrifugal Charging Pump Running (Racked In)

Loop 2 WR Cold Leg Temp RCS Lowest Cold Leg Temperature 185o F RCS WR Pressure RCS Highest Reading Pressure 230 psig 2-NPS-121 2-PP-26N North Safety Injection Pump PTL (Racked Out) 2-PP-26S South Safety Injection Pump PTL (Racked Out) 2-NTA-251 Pressurizer Liquid Temp 400o F 2-IMO-110, 120, 130, 140 SI Accumulator Isolation Valves Closed & De-Energized Revision: 0 2012 NRC-A2-RO.doc Page 9 of 9

OPERATIONS JPM NUMBER: 2012 NRC-A2-SRO TIME: 15 MINUTES TITLE: Perform Unit 2 LTOP Verification REVISION: 0 Revision: 0 2012 NRC-A2-SRO.doc Page 1 of 6

OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 2-OHP-4030-214-030 Daily and Shiftly Surveillance Checks K/A Number: 2.2.42 K/A Imp.: RO: 3.9 SRO: 4.6 Task Number: STP0390201 Perform Shiftly Surveillance checks for MODE 5 & 6 TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS

• Task Briefing sheet

• Work Management Listing (Open Items) - 2 pages

• Copy of Completed 2-OHP-4030-214-030, Data Sheet 20 (fill in Sections 3 & 4)

• Copy of Completed 2-OHP-4030-214-030, Data Sheet 20A (attached)

ATTACHMENTS None EVALUATION SETTINGS Classroom.

EVALUATION METHOD: PERFORM: SIMULATE:

SIMULATOR/LAB SETUP None.

EVALUATOR INSTRUCTIONS

1. Brief the operator (May be performed by giving out Task Briefing sheet).

2. Announce start of the JPM.

3. Perform evolution.

4. At completion of evolution, announce the JPM is complete.

5. Document evaluation performance.

Revision: 0 2012 NRC-A2-SRO.doc Page 2 of 6

OPERATIONS JPM TASK BRIEFING The Shift Manager directs you to perform the SRO review of the completed LTOP Verification 2-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20A.

To determine equipment status, use the Open Items Summary (attachment) and the Equipment Availability Table, as shown below:

Equipment Availability Table COMPONENT I.D.: DESCRIPTION: STATUS:

2-NMO-152 PORV Block Valve Open & Energized 2-NMO-153 PORV Block Valve Open & Energized 2-NRV-152 Control Cold Over-Pressure Block for Cold Over Press Selector 2-NRV-152 2-NRV-153 Control Cold Over-Pressure Block for Cold Over Press Selector 2-NRV-153 2-IMO-128 Return from Hot Leg 2 Open & Energized 2-ICM-129 Return from Hot Leg 2 Open & Energized Annunciator Panel 208 2-NRV-152 EMER AIR TANK NOT Lit Drop 27 PRESSURE LOW Annunciator Panel 208 2-NRV-153 EMER AIR TANK Lit Drop 28 PRESSURE LOW 2-PP-50E East Centrifugal Charging Pump PTL (Racked Out) 2-PP-50W West Centrifugal Charging Pump Running (Racked In)

Loop 2 WR Cold Leg Temp RCS Lowest Cold Leg Temperature 185o F RCS WR Pressure RCS Highest Reading Pressure 230 psig 2-NPS-121 2-PP-26N North Safety Injection Pump PTL (Racked Out) 2-PP-26S South Safety Injection Pump PTL (Racked Out) 2-NTA-251 Pressurizer Liquid Temp 400o F 2-IMO-110, 120, 130, 140 SI Accumulator Isolation Valves Closed & De-Energized GENERAL STANDARDS/PRECAUTIONS Perform the SRO review of the completed LTOP Verification and determine if LTOP Requirements for Unit 2 are met per 2-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20A.

Revision: 0 2012 NRC-A2-SRO.doc Page 3 of 6

OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

General CUES:

• If requested, provide a Copy of 2-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20.

• If required prompt the candidate to identify Tech Spec and correct Data Sheet 20A after determining the error.

CS: Reviews Data Sheet 20A and determines that the RHR Suction Relief is In-Operable (Xs in Circles are wrong, Empty Circles Should Have Xs).

SAT: UNSAT:

Note: RHR Suction Relief is In-Operable because of failed relief setpoint (See Work Management Listing - pg 2).

CS: Determines that LTOP Requirements are NOT Met.

SAT: UNSAT:

Informs Shift Manager that LTOP Requirements are NOT met and determines that Tech Spec LCO 3.4.12, Action F applies (Mode 5 - One required relief is In-Operable).

N/A SAT: UNSAT:

CUE: This JPM is complete.

Revision: 0 2012 NRC-A2-SRO.doc Page 4 of 6

Task Briefing The Shift Manager directs you to perform the SRO review of the completed LTOP Verification 2-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20A.

To determine equipment status, use the Open Items Summary (attachment) and the Equipment Availability Table, as shown below:

Equipment Availability Table COMPONENT I.D.: DESCRIPTION: STATUS:

2-NMO-152 PORV Block Valve Open & Energized 2-NMO-153 PORV Block Valve Open & Energized 2-NRV-152 Control Cold Over-Pressure Block for Cold Over Press Selector 2-NRV-152 2-NRV-153 Control Cold Over-Pressure Block for Cold Over Press Selector 2-NRV-153 2-IMO-128 Return from Hot Leg 2 Open & Energized 2-ICM-129 Return from Hot Leg 2 Open & Energized Annunciator Panel 208 2-NRV-152 EMER AIR TANK NOT Lit Drop 27 PRESSURE LOW Annunciator Panel 208 2-NRV-153 EMER AIR TANK Lit Drop 28 PRESSURE LOW 2-PP-50E East Centrifugal Charging Pump PTL (Racked Out) 2-PP-50W West Centrifugal Charging Pump Running (Racked In)

Loop 2 WR Cold Leg Temp RCS Lowest Cold Leg Temperature 185o F RCS WR Pressure RCS Highest Reading Pressure 230 psig 2-NPS-121 2-PP-26N North Safety Injection Pump PTL (Racked Out) 2-PP-26S South Safety Injection Pump PTL (Racked Out) 2-NTA-251 Pressurizer Liquid Temp 400o F 2-IMO-110, 120, 130, 140 SI Accumulator Isolation Valves Closed & De-Energized Revision: 0 2012 NRC-A2-SRO.doc Page 5 of 6

- FOR TRAINING USE ONLY -

Revision: 0 2012 NRC-A2-SRO.doc Page 6 of 6

GASEOUS WASTE RELEASE WORKSHEET Release Source Unit 1 CP Release No. G-12-06 SAMPLE IDENTIFICATION Chem Lab Sample Number(#) Sample Date/Time Decay Tank Unit 1 CP TODAY / 03:29:00 AM Instrument Room: 2-2012-07-23-001,3-2012-07-23-0003 7/23/2012 0150 Upper Ctmt: 2-2012-07-23-001,3-2012-07-23-0003 7/23/2012 0450 Lower Ctmt: 2-2012-07-23-001,3-2012-07-23-0003 7/22/2012 2315 Other:

INITIAL ESTIMATED RELEASE 9

Tank Pressure: 0.0 psig.

Source Flow Rate: 6000 cfm.

Source Volume: 1240000 ft3.

Estimated Duration of Release (Source Volume) 1240000 ft3 = 3.44 hr (60)min/hr x (source Flow Rate) 6000 cfm Unit Conversion (Source Flow Rate) 6000. cfm x (2.83E+04) cc/ft3 =2.80E+06 cc/sec (60) sec/min Page 1 of 7

TOTAL BODY DRDF Release No. G-12-06 Noble Gas Concentration Flow Rate Release Rate Total Body Total Body Nuclide (uCi/cc) x (cc/sec) = (uCi/sec) x DCF = DRDF KR-85 2.05E-05 x 2.80E+06 = 5.74E+0l x 1.61E+0l = 9.24E+02 XE-133 3.67E-08 x 2.80E+06 = 1.03E-01 x 2.94E+02 = 3.02E+01 Sum Total Body DRDF = 9.54E+02 Page 2 of 7

SKIN DRDF Release No. G-12-06 Noble Gas Concentration Flow Rate Release Rate Skin Total Skin Nuclide (uCi/cc) x (cc/sec) = (uCi/sec) x DCF = DRDF KR-85 2.05E-05 x 2.80E+06 = 5.74E+0l x 1.36E+03 = 7.81E+04 XE-133 3.67E-08 x 2.80E+06 = 1.03E-01 x 6.94E+02 = 7.15E+01 Sum Skin DRDF = 7.82E+04 Page 3 of 7

Release No. G-12-06 Conc. x Filtr. = Filtered x Flow = Release x DCF = Any Nuclide Factor Conc. Rate Rate Organ (uCi/cc) (uCi/cc) (cc/sec) (uCi/sec) DRDF H-3 9.37E-06 x N/A = N/A x 2.80E+06 =2.62E+01 x 1.12E+03 =2.94E+04 Sum Any Organ DRDF = 2.94E+04 Page 4 of 7

Release No. G-12-06 Dose Rate of Release Dose Rate Dose Rate DRDF x X/Q = of Release Limit mrem/yr Total Body 9.54E+02 x 2.04E-05 = 1.95E-02 500 mrem/yr Skin 7.82E+04 x 2.04E-05 = 1.60E+00 3,000 mrem/yr Any Organ 2.94E+04 x 2.04E-05 = 6.00E-01 1,500 mrem/yr Estimated Dose of Release Dose Rate Est. Duration Est. Dose Dose Limit of Release x of Release x Conv Fac = of Release of Release Total Body x 3.44 x 1.14E-4 Yr/Hr = 7.63E-06 5 mrem Skin x 3.44 x 1.14E-4 Yr/Hr = 6.26E-04 10 mrem Any Organ x 3.44 x 1.14E-4 Yr/Hr = 2.35E-04 7.5 mrem REDUCED FLOW RATE CALCULATIONS Individual Reduced Flow Rates Total Body:

(Source Flow Rate, cfm) x (500) mrem/yr = cfm (Calculated Total Body DR) mrem/yr Skin:

(Source Flow Rate, cfm) x (3,000) mrem/yr = cfm (Calculated Skin DR) mrem/yr Any Organ:

(Source Flow Rate, cfm) x (1,500) mrem/yr = cfm (Calculated Any Organ DR) mrem/yr Increased Duration of Release ft3 (source volume) = hr 60 min/hr x cfm (lowest available)

Page 5 of 7

GASEOUS WASTE RELEASE WORKSHEET Release No. G-12-06 Dose Rate Limit/Dose Rate of Release Ratio Total Body:

(500) mrem/yr = 2.56E+04 (DR Ratio)

(Calculated DR) 1.95E-02 mrem/yr Skin:

(3,000) mrem/yr = 1.88E+03 (DR Ratio)

(Calculated DR) 1.60E+00 mrem/yr Any Organ:

(1,500) mrem/yr = 2.50E+03 (DR Ratio)

(Calculated DR) 6.00E-01 mrem/yr Most Limitimg (smallest) DR Ratio = 1.88E+03 FINAL RELEASE DATA Source Volume .................. 1240000 ft3 Source Flow Rate................ 6000. cfm Unit Vent Stack Flow Rate....... 1.43E+05 cfm Duration of Release............. 3.44 hour Total Noble Gas Concentration .... 2.05E-05 uCi/cc High Alarm Setpoint Calculation Most Total Est. Source Limiting Noble Gas Conc. Flow Rate MRP DR Ratio uCi/cc cfm SP = (.9) x 4.10E-01 x 1 . 8 8 E + 0 3 x 2.05E-05 6000. = 5.73e-04 (uCi/cc) 6000. + 1.43E+05 Source Flow Rate (cfm) Unit Vent Flow Rate (cfm)

Page 6 of 7

GASEOUS WASTE RELEASE WORKSHEET Release No. G-12-06 Release Flow Rate 6000. + 1.43E+05 = 1.49E+05 cfm Source Flow Rate Unit Vent Flow Rate Release Flow Rate High Unit Vent Flow Rate Setpoints High Limit Flow Rate: 1.49E+05 x 1.1 = 1.63E+05 Release Flow Rate (cfm) (cfm)

Alert Alarm Setpoint 5.73e-04 x 0.8 = 4.58E-04 High Alarm Setpoint (uCi/cc) (uCi/cc)

COMMENTS:

APPROVAL SECTION Performed by: TODAY 0432 (Date) (Time)

Reviewed by: TODAY 0455 (Date) (Time)

Page 7 of 7

OPERATIONS JPM NUMBER: 2012 NRC-A3 TIME: 30 MINUTES TITLE: Perform a Containment Purge Release REVISION: 0 (Unit 1) 2012 NRC-A3 Page 1 of 21

OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 1-OHP-4021-028-005 Operations of the Containment Purge System K/A Number: 2.3.11 K/A Imp.: RO: 3.8 SRO: 4.3 Task Number: 0280090101 Perform a Containment Purge TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS

• Task Briefing sheet

• Annotated 1-OHP-4021-028-005, Procedure

• Annotated 1-OHP-4021-028-005, Data Sheet 1

• Release Paperwork EVALUATION SETTINGS Simulator EVALUATION METHOD: PERFORM: SIMULATE:

SIMULATOR/LAB SETUP Reset to IC 909 (Mode 3)

Revision: 0 2012 NRC-A3 Page 2 of 21

OPERATIONS JPM TASK BRIEFING You are an Extra RO in Unit 1.

The following conditions exist:

• Unit 1 is in Mode 3 preparing for a startup.

• No Waste Gas Decay Tanks are being released.

• Due to an inadvertent lifting of a Pressurizer Safety Valve, the PRT rupture disc has blown and needs to be replaced.

• Engineering prefers that the repair be completed in Mode 3 to minimize cyclic temperature stresses on the RCS.

The Unit Supervisor has requested that you place the Containment Purge System in service in the Cleanup Mode for Lower Containment only to prepare the containment environment for the required PRT rupture disc replacement. Purge paperwork (Data Sheet 1) has already been initiated.

TASK STANDARDS Perform a Containment Purge IAW 1-OHP-4021-028-005.

Revision: 0 2012 NRC-A3 Page 3 of 21

OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

CUE: All prerequisites have been satisfied.

Revision: 0 2012 NRC-A3 Page 4 of 21

OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Reviews the Precautions and Limitations.

SAT: UNSAT:

CUE: RP approval was obtained 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago.

CUE: It is day shift. The Shift Manager has requested that purge be in service ASAP.

CUE: All logging will be performed by another operator.

CUE: This is the first recorded Containment Purge for the year.

Revision: 0 2012 NRC-A3 Page 5 of 21

OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Reviews the Precautions and Limitations on this page.

Revision: 0 2012 NRC-A3 Page 6 of 21

OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Reviews the Precautions and Limitations on this page.

Revision: 0 2012 NRC-A3 Page 7 of 21

OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Step 4.1 is N/A.

Verifies Data Sheet 1, Sections 1.0 and 2.0 are complete.

Verifies Data Sheet 1, Section 3.0 is complete.

SAT: UNSAT:

Revision: 0 2012 NRC-A3 Page 8 of 21

OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Reviews conditional steps.

Revision: 0 2012 NRC-A3 Page 9 of 21

OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Note: The Candidate may source check all of these channels except VRS-1505 from the Surv./Source Check Screen.

The monitors may also be individually Source Checked.

CS: Performs Source Check on all Radiation Monitors:

• VRS-1101

• VRS-1201

• VRS-1505

• ERS-1301

• ERS-1305

• ERS-1401

• ERS-1405 SAT: UNSAT:

Revision: 0 2012 NRC-A3 Page 10 of 21

OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

CS: Places all TRIP/BLOCK switches in NORMAL position:

• VRS-1101

• ERS-1300

• VRS-1201

• ERS-1400 SAT: UNSAT:

Reviews Section 4 of Data Sheet 1.

CUE: RP checks VRS-1505 and VFR-1510 setpoints.

Add RP Initial and Final values??????????????

CUE: Setpoint for VRS-1505 has been changed as required.

CUE: Setpoint for VFR-1510 does NOT need to be changed.

Revision: 0 2012 NRC-A3 Page 11 of 21

OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

FIX Handout????????????? & Cue Revision: 0 2012 NRC-A3 Page 12 of 21

OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Determines Step 4.5.4.c is N/A.

SAT: UNSAT:

Determines Step 4.6 is N/A.

SAT: UNSAT:

CUE: Winterization is NOT in effect Determines Step 4.7.1.a is N/A.

SAT: UNSAT:

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Step 4.7.1.b is N/A.

Requests AEO to check that Inlet Volume Dampers are open.

SAT: UNSAT:

CUE: Report as AEO that 1-HV-CPS-VD-1 & 2 Containment Purge Supply Inlet Volume Dampers are open.

Determines Step 4.7.3 is N/A.

SAT: UNSAT:

CUE: If required, Outside Air Temperature is 55°F.

Verifies containment status.

SAT: UNSAT:

CUE: Upper Containment Equipment Hatch is installed and both Containment Airlocks are closed.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Step 4.7.5 is N/A.

Step 4.7.5.b is N/A.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Step 4.7.5.c is N/A.

Step 4.7.6 is N/A.

Step 4.7.6.b is N/A.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Step 4.7.6.c is N/A.

Step 4.7.7 is N/A.

Step 4.7.7.b is N/A.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Step 4.7.7.c is N/A.

Verifies Closed Supply & Exhaust Valves.

SAT: UNSAT:

Determines Step 4.7.8.b is N/A.

SAT: UNSAT:

Verifies Closed VCR-105 & VCR-205.

SAT: UNSAT:

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

CS: Opens the following valves:

• VCR-103

• VCR-104

• VCR-203

• VCR-204 SAT: UNSAT:

Determines Step 4.7.9.a is N/A.

SAT: UNSAT:

Step 4.7.9.b is N/A.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Note: Based on Figure 2, Step 1.1, either 1 or 2 PAIRs (Supply & Exhaust) of fans are required to be operated.

CUE: If required, Only 1 pair of fans needs to be started.

CS: Starts 1 OR 2 Exhaust Fans.

SAT: UNSAT:

Determines Step 4.8.1.a (third box) is N/A.

SAT: UNSAT:

Determines Step 4.8.1.b is N/A.

SAT: UNSAT:

CS: Starts 1 or 2 Supply Fans SAT: UNSAT:

Determines Step 4.8.1.c (third box) is N/A.

SAT: UNSAT:

CUE: THIS JPM IS COMPLETE.

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Task Briefing You are an Extra RO in Unit 1.

The following conditions exist:

• Unit 1 is in Mode 3 preparing for a startup.

• No Waste Gas Decay Tanks are being released.

• Due to an inadvertent lifting of a Pressurizer Safety Valve, the PRT rupture disc has blown and needs to be replaced.

• Engineering prefers that the repair be completed in Mode 3 to minimize cyclic temperature stresses on the RCS.

The Unit Supervisor has requested that you place the Containment Purge System in service in the Cleanup Mode for Lower Containment only to prepare the containment environment for the required PRT rupture disc replacement. Purge paperwork (Data Sheet 1) has already been initiated.

Revisio 2012 NRC-A3 Page 21 of 21

OPERATIONS JPM NUMBER: 2012 NRC-A4-SRO TIME: 25 MINUTES TITLE: Prepare Prompt NRC Notification Worksheet REVISION: 0 2012 NRC-A4-SRO.doc Page 1 of 12

REFERENCES/NRC KA/TASKS Procedure: PMP-7030-001-001 Prompt NRC Notification 10 CFR 50.72 Immediate Notification Requirements NUREG-1022 Event Reporting Guidelines K/A Number: 2.4.30 K/A Imp.: RO: 2.7 SRO: 4.1 Task Number: ADM1250303 Make a prompt NRC notification.

TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS

• Task Briefing sheet

• Copy of procedure PMP-7030-001-001

• Unit 2 Technical Specifications ATTACHMENTS None EVALUATION SETTINGS Classroom EVALUATION METHOD: PERFORM: SIMULATE:

2012 NRC-A4-SRO.doc Page 2 of 12

SIMULATOR/LAB SETUP None EVALUATOR INSTRUCTIONS

1. Brief the operator (May be performed by giving out Task Briefing Sheet)

2. Announce start of the JPM

3. Perform evolution

4. At completion of evolution, announce the JPM is complete.

5. Document evaluation performance.

TASK BRIEFING You are the extra SRO.

The Shift Manager (SM) directs you to determine if a NRC notification is required. If notification is required, prepare an event notification worksheet (Data Sheet 1) for prompt NRC NOTIFICATION in accordance with PMP-7030-001-001.

The following conditions exist on Unit 2:

• Current time is 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />.

• The unit is currently at 100% power (and has been at 100% for 2 months).

• A Reactor Coolant System (RCS) leak was identified at 1215 hours0.0141 days <br />0.338 hours <br />0.00201 weeks <br />4.623075e-4 months <br /> and 2-OHP-4022-002-020, Excessive Reactor Coolant Leakage procedure was immediately entered and is currently in progress.

• An UNIDENTIFIED RCS leak (PRESSURE BOUNDARY Suspected) exists of 5.0 gpm and has been confirmed using 2-OHP-4030-102-016, RCS Leak Test.

• Leakage is inside the missile barrier.

• The SM has directed a unit shutdown IAW 2-OHP-4021-001-003, Power Reduction.

• Pressurizer level is currently being controlled in manual at program level (stable).

• Present RCS conditions are at normal operating temperature and pressure.

• RCS activity levels are 1.12e-04 µCi/gm I-131 with gross activity .005 µCi/gm.

• Containment pressure is 0.7 psig and stable.

• All other plant conditions are normal and there is no detectable radiation release in progress.

• The SM has determined that NO Emergency Classification is required per PMP-2080-EPP-101 and the Duty Operations Manager has been informed of the situation.

• The NRC Resident has been notified.

GENERAL STANDARDS/PRECAUTIONS Determine NRC notification requirements and prepare an event notification worksheet.

2012 NRC-A4-SRO.doc Page 3 of 12

EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

General Notes:

• NO CRITERIA ON THIS PAGE APPLY TO THE STATED PLANT CONDITIONS.

• However, the candidate may refer to this page as the applicable section 3.1 Reporting - Notification starts here.

2012 NRC-A4-SRO.doc Page 4 of 12

Note: NO CRITERIA ON THIS PAGE APPLY TO THE STATED PLANT CONDITIONS.

2012 NRC-A4-SRO.doc Page 5 of 12

Note: NO CRITERIA ON THIS PAGE APPLY TO THE STATED PLANT CONDITIONS.

2012 NRC-A4-SRO.doc Page 6 of 12

CS: Identifies that a Plant Shutdown per Tech Specs requires a report within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SAT: UNSAT:

Observes reference to Step 3.2.5.a (in the procedure text) that provides information or clarification of this flow chart determination.

SAT: UNSAT:

2012 NRC-A4-SRO.doc Page 7 of 12

CS: Refers to step in procedure text for clarification of flow chart results.

SAT: UNSAT:

Note: Once determination is made using Figure 1, return to Step 3.1.1.f to fill out Data Sheet 1.

2012 NRC-A4-SRO.doc Page 8 of 12

CS: Goes to NRC Form 361 (Data Sheet 1).

SAT: UNSAT:

CUE: The SM will notify the NRC.

2012 NRC-A4-SRO.doc Page 9 of 12

x Fill in applicable data to include:

CS: Notification Time / Facility or Organization / Unit NOTE: Data in () Parenthesis is NOT Critical.

CUE: If asked, the current time is 1310.

SAT: UNSAT:

Caller / Call Back Number (Can be any plant extension).

SAT: UNSAT:

CS: Event Time & Zone / Date / Power-Mode (Before and After).

SAT: UNSAT:

(>1300) COOK 2 (Candidate Name) (Any Ext.)

1215 EDT (Todays Date) 100% / MODE 1 100%/

CS: Event Classification (50.72 Non-Emergency).

SAT: UNSAT:

X X CS: 4 Hr Classification (TS Required S/D).

SAT: UNSAT:

Description (brief summary of condition).

SAT: UNSAT:

A Reactor Coolant System pressure boundary leak of 5.0 gpm has been identified. Abnormal Operating Procedure has been entered and a unit Notifications (Resident and NRC).

shutdown is planned. All other plant conditions are normal and there is SAT: UNSAT:

no detectable radiation release in progress.

Other Information CUE: Estimated restart is unknown.

UNKNOWN X X X

X X SAT: UNSAT:

X X UNKNOWN UNKNOWN X 2012 NRC-A4-SRO.doc Page 10 of 12

Note: NO CRITERIA IN THIS SECITION APPLY TO THE STATED PLANT CONDITIONS.

CS: Leakrate (5) Units (gpm), TS (1 Unidentified and/or No PB)

RCS Leakage inside Containment SAT: UNSAT:

5 GPM 1 Unidentified Started suddenly TODAY 1215 .

1.12e-04 µCi/gm I-131, gross 005 µCi/gm CS: Date, Time & RCS activity SAT: UNSAT:

CUE: When Data Sheet is submitted for review, then JPM is complete.

2012 NRC-A4-SRO.doc Page 11 of 12

Task Briefing You are the extra SRO.

The Shift Manager (SM) directs you to determine if a NRC notification is required. If notification is required, prepare an event notification worksheet (Data Sheet 1) for prompt NRC NOTIFICATION in accordance with PMP-7030-001-001.

The following conditions exist on Unit 2:

• Current time is 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />.

• The unit is currently at 100% power (and has been at 100% for 2 months).

• A Reactor Coolant System (RCS) leak was identified at 1215 hours0.0141 days <br />0.338 hours <br />0.00201 weeks <br />4.623075e-4 months <br /> and 2-OHP-4022-002-020, Excessive Reactor Coolant Leakage procedure was immediately entered and is currently in progress.

• An UNIDENTIFIED RCS leak (PRESSURE BOUNDARY Suspected) exists of 5.0 gpm and has been confirmed using 2-OHP-4030-102-016, RCS Leak Test.

• Leakage is inside the missile barrier.

• The SM has directed a unit shutdown IAW 2-OHP-4021-001-003, Power Reduction.

• Pressurizer level is currently being controlled in manual at program level (stable).

• Present RCS conditions are at normal operating temperature and pressure.

• RCS activity levels are 1.12e-04 µCi/gm I-131 with gross activity .005 µCi/gm.

• Containment pressure is 0.7 psig and stable.

• All other plant conditions are normal and there is no detectable radiation release in progress.

• The SM has determined that NO Emergency Classification is required per PMP-2080-EPP-101 and the Duty Operations Manager has been informed of the situation.

• The NRC Resident has been notified.

2012 NRC-A4-SRO.doc Page 12 of 12

OPERATIONS JPM NUMBER: 2012 NRC-INP01 TIME: 10 MINUTES TITLE: Locally Control VCT Makeup Valve REVISION: 0 (2-QRV-400)

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OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 2-OHP-4025-R-12-18 COMPONENT RESTORATION K/A Number: APE 068.AA1.08 K/A Imp.: RO: 4.2 SRO: 4.2 Task Number: APR0030604 Locally control air operated isolation valves.

TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS

• Task Briefing sheet

• 2-OHP 4025-R-12-18 ATTACHMENTS None EVALUATION SETTINGS In-Plant (U2)

EVALUATION METHOD: PERFORM: SIMULATE:

SIMULATOR/LAB SETUP None Revision: 0 2012 NRC-INP01 Page 2 of 7

OPERATIONS JPM EVALUATOR INSTRUCTIONS

1. Brief the candidate (may be performed by giving out Task Briefing sheet).

2. Announce start of JPM.

3. Perform evaluation.

4. When evaluation is complete, announce end of JPM.

5. Document evaluation (may be delayed until the end of a series of JPMs).

TASK BRIEFING The Shift Manager (SM) has implemented Emergency Remote Shutdown procedure 2-OHP-4025-001-001. Unit 2 is in mode 3 with Control Air available.

The SM directs you to establish local control capability for 2-QRV-400, Blender to CHG Pump Suction, then OPEN the valve in accordance with 2-OHP-4025-12, Section R-12-18, Local Control of Air Operated Isolation Valves.

GENERAL STANDARDS/PRECAUTIONS Establish local control and open 2-QRV-400, Blender to CHG Pumps Suction, in accordance with approved procedure and demonstrate proper operation of the valve.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Identifies 2-QRV-400 in Table 2.

SAT: UNSAT:

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Verifies that the valve number on flex hose matches number on emergency connections.

SAT: UNSAT:

CS: Pulls back retaining collar, then inserts hose and ensures retaining ring snaps back into place.

SAT: UNSAT:

CUE: You hear a click when the hose is connected.

CS: Simulates opening emergency control air supply valve.

SAT: UNSAT:

CUE: States resistance is felt when simulating opening control air valve.

CUE: When operator informs SM that 2-QRV-400 is open state SM directs operator to close QRV-400, Blender to Charging Pump Suction.

CS: Simulates closing emergency control air supply valve and then removes hose from emergency air station.

SAT: UNSAT:

CUE: A brief hiss of air can be heard when disconnecting hoses. Air flow can be continuous if control air isolation is not closed before removing the flex hose.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

CUE: When report is made that 2-QRV-400, Blender to Charging Pump Suction, is closed, then, This JPM is complete.

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Task Briefing The Shift Manager (SM) has implemented Emergency Remote Shutdown procedure 2-OHP-4025-001-001. Unit 2 is in mode 3 with Control Air available.

The SM directs you to establish local control capability for 2-QRV-400, Blender to CHG Pump Suction, then OPEN the valve in accordance with 2-OHP-4025-12, Section R-12-18, Local Control of Air Operated Isolation Valves.

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OPERATIONS JPM NUMBER: 2012 NRC-INP02 TIME: 17 MINUTES Restore an N Train Battery Charger TITLE: REVISION: 0

- U1 (Alt. Path)

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REFERENCES/NRC KA/TASKS Procedure: 1-OHP-4024-115, Drop 57 Trains A & B N Battery CHG De-energized 1-OHP-4021-082-015 Operation of the N Train Battery System K/A Number: APE 058 AA1.01 K/A Imp.: RO: 3.4 SRO: 3.5 Task Number: 0820080504 Reset the N-train Battery Charger 0820160104 Switch N-Train Battery Chargers.

TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS

• Task Briefing sheet

• 1-OHP-4024-115, Drop 57, Trains A & B N Battery CHG De-energized

• 1-OHP-4021-082-015, Operation of the N Train Battery System ATTACHMENTS None EVALUATION SETTINGS In-Plant (U1)

EVALUATION METHOD: PERFORM: SIMULATE:

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EVALUATOR INSTRUCTIONS

1. Brief the candidate (may be performed by giving out Task Briefing sheet).

2. Announce start of JPM.

3. Perform evaluation.

4. When evaluation is complete, announce end of JPM.

5. Document evaluation (may be delayed until the end of a series of JPMs).

TASK BRIEFING Unit 1 is in Mode 3 following a Reactor Trip with a Safety Injection.

You are an Extra Operator.

The Unit Supervisor directs to locally restore the Unit 1 N-Train Battery Charger to service in accordance with Annunciator Panel #115, Drop 57, Step 3.2.

You are to review the subsequent actions of this Annunciator Response Procedure and restore an N-Train battery charger to service.

The Train A Charger is currently aligned for service on the Unit 1 N-Train Battery system.

GENERAL STANDARDS/PRECAUTIONS Demonstrate the ability to place an N-Train Battery Charger in service following the loss of the N-Train battery on a Safety Injection and/or load shed condition.

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EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

NOTE: Candidate understands that the N-Train battery charger must be manually reset following a Safety Injection and Load Shed on bus T11B or T11D.

CUE: If asked, (at Train A Control Box) WHITE light is LIT and the GREEN / RED lights are NOT lit.

CS: Simulates resetting the in-service battery charger by placing the control switch to OFF and then back to the AUTO position.

SAT: UNSAT:

CUE: If asked, no change in control box light indication.

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EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

CUE: The control room reports that Annunciator Panel 115 Drop 57 alarm has NOT cleared [NOTE: Operator must open Breaker Cabinet to access the thermal overload reset. Provide a copy of Breaker Cabinet drawing during attempt to reset thermal overload.]

CUE: If asked, breaker switch is in the TRIPPED position.

Dons proper PPE, simulates opening breaker 1-AM-D-4A cabinet door, then attempts to reset thermal overload.

SAT: UNSAT:

NOTE: May inform control room thermal overload is reset.

CUE: Control room informs you the alarm will NOT reset.

May simulate re-closing the breaker.

SAT: UNSAT:

CUE: Breaker fails to the TRIPPED position.

May inform control room of breaker failure.

SAT: UNSAT:

CUE: Control room acknowledges breaker failure and directs you to place Train B charger in service.

Enters 1-OHP-4021-082-015 to restore Train B N-Train Battery Charger to service.

SAT: UNSAT:

CUE: Provide a copy of 1-OHP-4021-082-015 upon recognition that the procedure will be entered.

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EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

CUE: If asked, US directs you to place Train B charger in service.

CUE: Per procedure prerequisites, MCC 1-AM-D & 1-ABD-B are energized and one battery exhaust fan is operating.

Step 4.2.1 is N/A. CUE: When asked, the Train B charger was in service yesterday with operating parameters within normal limits.

SAT: UNSAT:

Verifies the 1-BC-B-CB1 is OFF. CUE: 1-BC-B-CB1 is OFF.

SAT: UNSAT:

Verifies GREEN light LIT. CUE: When checked, the GREEN light on the standby battery charger control box is LIT.

SAT: UNSAT:

Step 4.2.3.a. is N/A. (Breaker is located in 1AB EDG room - Turb.

Bldg.). CUE: When asked, breaker 1-ABD-B-2A is closed.

SAT: UNSAT:

Step 4.2.4 is N/A. CUE: There was no Loss of Offsite Power.

SAT: UNSAT:

CS: Simulates closing 1-DCN CKT 4 breaker.

SAT: UNSAT:

CUE: Breaker is in the ON position.

CS: Simulates closing 1-BC-B-CB2 breaker.

SAT: UNSAT:

CUE: Breaker is in the ON (UP) position.

CS: Simulates closing 1-BC-B-CB1 breaker.

SAT: UNSAT:

CUE: Breaker is in the ON (UP) position.

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EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

CS: Simulates placing 1-BC-B control switch in AUTO.

SAT: UNSAT:

CUE: Control switch is in the AUTO position - GREEN light ON and RED light OFF.

CUE: THIS JPM IS COMPLETE.

Revision: 0 2012 NRC-INP02 Page 7 of 8

Task Briefing Unit 1 is in Mode 3 following a Reactor Trip with a Safety Injection.

You are an Extra Operator.

The Unit Supervisor directs to locally restore the Unit 1 N-Train Battery Charger to service in accordance with Annunciator Panel #115, Drop 57, Step 3.2.

You are to review the subsequent actions of this Annunciator Response Procedure and restore an N-Train battery charger to service.

The Train A Charger is currently aligned for service on the Unit 1 N-Train Battery system.

2012 NRC-INP02 Page 8 of 8

OPERATIONS JPM NUMBER 2012 NRC-INP03 TIME: 30 MINUTES TITLE: Respond to Waste Gas Panel Alarm REVISION: 0 (Alt. Path)

Revision: 0 2012 NRC-INP03 Page 1 of 10

OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 12-OHP-4021-023-001 Operation of the Waste Gas System 1-OHP-4024-128 Annunciator #128 Response: Boron Recycle and Waste Gas K/A Number: 071 A4.14 K/A Imp.: RO: 2.8 SRO: 3.0 Task Number: 0230020104 Place a Gas Decay Tank In Service TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS

• Task Briefing sheet

• 1-OHP-4024-128, Ann. #128 Response: Boron Recycle & Waste Gas; Drops 19 and 20

• 12-OHP-4021-023-001, Operation of the Waste Gas System- Attachment #2 ATTACHMENTS None EVALUATION SETTINGS In-Plant EVALUATION METHOD: PERFORM: SIMULATE:

Revision: 0 2012 NRC-INP03 Page 2 of 10

OPERATIONS JPM SIMULATOR/LAB SETUP

1. None EVALUATOR INSTRUCTIONS

1. Brief the operator (May be performed by giving out Task Briefing Sheet)

2. Announce start of the JPM

a. Initially ONLY provide a copy of 12-OHP-4024, Annunciator Panel 128, Drops 19 and 20, to the operator.

b. Once operator determines that another GDT must be placed in service, then provide a copy of 12-OHP-4021-023-001, Operation of the Waste Gas System- Attachment #2, Aligning a GDT as the In Service GDT.

3. Perform evolution

4. At completion of evolution, announce the JPM is complete.

5. Document evaluation performance.

TASK BRIEFING You are an extra Operator.

The WASTE DISPOSAL SYS ABNORMAL alarm was received in Unit 1 control room. You have been dispatched by the Unit Supervisor to investigate the alarm.

Annunciator Panel #128 (1-OHP-4024-128) Drops 19 and 20 are in alarm when you arrive at the WDS panel. You are to respond as procedurally directed.

Initial Conditions are as follows:

GDTs #1, #2, #5, and #6 have clearances hung for maximum decay time.

1. 3 GDT is at 75 psig and aligned for cover gas.

1. 4 GDT is at 100 psig and selected for FILL.

1. 8 GDT is at 50 psig and selected for STANDBY.

1. 7 GDT is at 40 psig and was just released last shift.

GENERAL STANDARDS/PRECAUTIONS Number 7 GDT has been aligned for fill (in service) in accordance with 12-OHP-4021-023-001.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Annunciator 128, Drop 19 GENERAL CUES:

1. 4 GDT pressure is at 100 psig.

1. 4 GDT Inlet (RRV-341) red light LIT, green light NOT LIT .

1. 8 GDT Inlet (RRV-381) green light LIT, red light NOT LIT.

CS: Determines Automatic Actions did NOT occur and manually swaps tanks (place GDT #8 to INLET position). DUPLICATE ACTION TO ANNUNCIATOR 128, DROP 20.

SAT: UNSAT:

CUE: If the candidate places GDT #8 Control Switch (C/S) to the INLET position, then provide the following information:

RRV-341 green light is LIT; red light is NOT LIT.

RRV-381 red light is LIT; green light is NOT LIT.

Determines that another Gas Decay Tank (GDT) should be aligned per 12-OHP-4021-023-001.

SAT: UNSAT:

CUE: If asked, report that GDT #4 will be isolated for decay time by another operator.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Annunciator 128, Drop 20 GENERAL CUES:

There is no alarm on the Alternate Waste Gas Oxygen Analyzer.

1. 4 GDT pressure is at 100 psig.

1. 4 GDT Inlet (RRV-341) red light LIT, green light NOT LIT .

1. 8 GDT Inlet (RRV-381) green light LIT, red light NOT LIT.

If asked, GDT Standby Selector is in the 8 position.

CS: Determines Automatic Actions did NOT occur and manually swaps tanks (place GDT #8 to INLET position). DUPLICATE ACTION AND CUE TO ANNUNCIATOR 128, DROP 19.

SAT: UNSAT:

CUE: If the candidate places GDT #8 C/S to the INLET position, then provide the following information:

RRV-341 green light is LIT; red light is NOT LIT.

RRV-381 red light is LIT; green light is NOT LIT.

Determines that another GDT tank should be aligned per 12-OHP-4021.023.001.

SAT: UNSAT:

CUE: Unit Supervisor requests that #7 GDT be placed in service and #8 GDT be returned to standby status.

CUE: When candidate determines which attachment to use, provide copy of 12-OHP-4021-23-001, Attachment #2, Aligning a GDT as the In Service GDT.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

CUE: If asked, report that GDT #4 will be isolated for decay time by another operator.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Select Attachment 2 to align a GDT as the In Service tank.

SAT: UNSAT:

CUE: If asked, inform candidate that #7 GDT will be placed in service and #8 GDT will be returned to standby status.

Note: Step 4.1 and 4.2 (and all of their sub-steps) are N/A.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Enters 7 for GDT #7 SAT: UNSAT:

Locates 12-WD-230-7 and verifies closed and sealed.

SAT: UNSAT:

CUE: Valve is closed with seal in place.

Locates each ,of 6, valves and verifies they are closed.

SAT: UNSAT:

CUE: All the valves (for Step 4.5.1) are closed.

Verifies 12-NS-440-7 open.

SAT: UNSAT:

CUE: Valve is open.

CS: Simulates opening 12-WD-227-7 (at tank).

SAT: UNSAT:

CUE: Valve is initially closed, stem rises as you turn it counter-clockwise.

CS: Simulates opening 12-WD-229-7 (at tank).

SAT: UNSAT:

CUE: Valve is initially closed, stem rises as you turn it counter-clockwise.

CS: Simulates opening 12-RRV-371 (at control panel).

SAT: UNSAT:

CUE: Red light LIT, green light NOT LIT .

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

CUE: When candidate opens 12-RRV-371 (#7 GDT Aligned for service), then, JPM is complete.

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Task Briefing You are an extra Operator.

The WASTE DISPOSAL SYS ABNORMAL alarm was received in Unit 1 control room. You have been dispatched by the Unit Supervisor to investigate the alarm.

Annunciator Panel #128 (1-OHP-4024-128) Drops 19 and 20 are in alarm when you arrive at the WDS panel. You are to respond as procedurally directed.

Initial Conditions are as follows:

GDTs #1, #2, #5, and #6 have clearances hung for maximum decay time.

1. 3 GDT is at 75 psig and aligned for cover gas.

1. 4 GDT is at 100 psig and selected for FILL.

1. 8 GDT is at 50 psig and selected for STANDBY.

1. 7 GDT is at 40 psig and was just released last shift.

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OPERATIONS JPM NUMBER; 2012 NRC-SIM01 TIME: 15 MINUTES TITLE: Perform RCCA Operability Check REVISION: 0 Revision: 0 2012 NRC-SIM01.doc Page 1 of 6

OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 1-OHP-4030-112-015 Full Length Control Rod Operability Test K/A Number: SYS 014 A4.02 K/A Imp.: RO: 3.4 SRO: 3.2 Task Number: 0120130201 Perform Full Length Control Rod Operability Test TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS

• Task Briefing sheet

• Copy of 1-OHP-4030-112-015 (annotated to perform selected Control Rod Bank)

ATTACHMENTS None EVALUATION SETTINGS Unit 1 Simulator EVALUATION METHOD: PERFORM: SIMULATE:

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OPERATIONS JPM SIMULATOR/LAB SETUP

1. Initialize the Simulator to IC-113 (any at-power IC).

2. Reset Control Rods, check Step Counters and verify Rod Bank Update is complete EVALUATOR INSTRUCTIONS

1. Ensure simulator setup is complete

2. Brief the operator (May be performed by giving out Task Briefing Sheet)

3. Announce start of the JPM

4. Perform evolution

5. At completion of evolution, announce the JPM is complete.

6. Document evaluation performance.

TASK BRIEFING You are the RO.

MTI has completed maintenance on the step counters for Control Bank A.

The Unit Supervisor directs you to perform a Full Length Operability test on Control Bank A in accordance with procedure 1-OHP-4030-112-015, Attachment 1, Step 4.8.

Reactor Engineering has determined that reactivity effects will be negligible.

PPC turn on code for Rod Position Screen is RSVANN.

TASK STANDARDS Performs an Operability Test on Control Rod Bank A in accordance with 1-OHP-4030-112-015, Attachment 1, while observing all applicable precautions, limitations and procedural steps.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Expected Initial Rod Positions:

(Gp 1 Dem) 228 (E3) 229 (C11) 229 (L13) 222 (N5) 229 (Gp 2 Dem) 228 (C5) 226 (E13) 230 (N11) 227 (L3) 230 Records initial position of Control Band (CB) A on Data Sheet (DS) 1.

SAT: UNSAT:

Determines required rod movement (for CB A) on DS 1.

SAT: UNSAT:

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

CS: Places FULL LENGTH BANK SELECTOR switch in CBA position.

SAT: UNSAT:

Monitors reactor power and RCS temperature.

CS: Inserts CB A at least 8 steps SAT: UNSAT:

Verifies RODS INSERTING lamp LIT and CB A rod movement.

SAT: UNSAT:

Ensures rods in CB A have moved > 8 steps & records position on DS 1.

SAT: UNSAT:

CS: Withdraws CB A to initial position.

SAT: UNSAT:

Records final position of CB A on Data Sheet (DS) 1.

SAT: UNSAT:

Verifies Allowed Rod Misalignment (ARM) using Tech Data Book Unit 1 Figure 13.1 or Operator Aid on Flux Panel.

SAT: UNSAT:

Verifies alarm clear.

SAT: UNSAT:

Verifies test results are met and reports CB A test is complete.

SAT: UNSAT:

CUE: JPM is complete. Another operator will restore Rods to AUTO.

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Task Briefing You are the RO.

MTI has completed maintenance on the step counters for Control Bank A.

The Unit Supervisor directs you to perform a Full Length Operability test on Control Bank A in accordance with procedure 1-OHP-4030-112-015, Attachment 1, Step 4.8.

Reactor Engineering has determined that reactivity effects will be negligible.

PPC turn on code for Rod Position Screen is RSVANN.

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OPERATIONS JPM NUMBER: 2012 NRC-SIM02 TIME: 15 MINUTES TITLE: Isolate SI (Safety Injection) Accumulators REVISION: 0 Revision: 0 2012 NRC-SIM02.doc Page 1 of 5

OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 1-OHP-4023.ES-1.2 Post LOCA Cooldown and Depressurization K/A Number: 006 A4.02 K/A Imp.: RO: 4.0 SRO: 3.8 Task Number: 0080020101 Isolate Accumulators TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS

• Task Briefing

• Copy of 1-OHP-4023.ES-1.2, Post LOCA Cooldown and Depressurization, Step 26 ATTACHMENTS None EVALUATION SETTINGS Unit 1 Simulator EVALUATION METHOD: PERFORM: SIMULATE:

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OPERATIONS JPM SIMULATOR/LAB SETUP

1. Post Trip conditions with IC-910 (~926 PSIG, ~436 0F CETCs, ES 1.2 step 25)

2. Malfunction: RC10B (severity 40%) ~600 GPM SBLOCA (run for ~ 40 minutes to be in ES-1.2)

U1_RC10B

3. Note: The Booth Operator is required to delete global malf. 101IMO110, 101IMO120, 101IMO130 and 101IMO140 when directed.

EVALUATOR INSTRUCTIONS

1. Ensure simulator setup is complete

2. Brief the operator (May be performed by giving out Task Briefing Sheet)

3. Announce start of the JPM

4. Perform evolution

5. At completion of evolution, announce the JPM is complete.

6. Document evaluation performance.

TASK BRIEFING You are an extra RO.

The Unit has experienced a Small Break LOCA. The crew has transitioned from E-1, Loss of Reactor or Secondary Coolant to ES-1.2, Post LOCA Cooldown and Depressurization.

Containment Pressure has remained less than 2.8 psig.

Containment Radiation has remained less than 100R/Hr.

The Unit Supervisor directs you to perform Step 26 of ES-1.2 to check if accumulators should be isolated.

GENERAL STANDARDS/PRECAUTIONS Operator has successfully isolated ALL four accumulators per procedure ES-1.2 step 26.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Checks RCS subcooling >40°F.

SAT: UNSAT:

Checks pressurizer level >21%.

SAT: UNSAT:

CS: Directs AEO to restore power to accumulator isolation valves (4).

SAT: UNSAT:

CUE: AEO will restore power as directed.

CUE: Booth Operator delete global malf 101IMO110, 101IMO120 101IMO130 and 101IMO140.

U1_101IMO110 U1_101IMO120 U1_101IMO130 U1_101IMO140 CUE: Report back to Operator that all breakers are closed.

CS: Closes IMO-110 - GREEN light LIT.

SAT: UNSAT:

CS: Closes IMO-120 - GREEN light LIT.

SAT: UNSAT:

CS: Closes IMO-130 - GREEN light LIT.

SAT: UNSAT:

CS: Closes IMO-140 - GREEN light LIT.

SAT: UNSAT:

CUE: JPM is complete.

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Task Briefing You are an extra RO.

The Unit has experienced a Small Break LOCA. The crew has transitioned from E-1, Loss of Reactor or Secondary Coolant to ES-1.2, Post LOCA Cooldown and Depressurization.

Containment Pressure has remained less than 2.8 psig.

Containment Radiation has remained less than 100R/Hr.

The Unit Supervisor directs you to perform Step 26 of ES-1.2 to check if accumulators should be isolated.

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OPERATIONS JPM NUMBER: 2012 NRC-SIM03 TIME: 10 MINUTES Perform SG (Steam Generator) Stop TITLE: REVISION: 0 Valve Dump Valve Test Revision: 0 2012 NRC-SIM03.doc Page 1 of 10

OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 1-OHP-4030-151-018 Steam Generator Stop Valve Dump Valve Surveillance Test K/A Number: 039 K4.05 K/A Imp.: RO: 3.7 SRO: 3.7 Task Number: ADM1190301 Stroke a valve for Post Maintenance operability TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS

• Task Briefing sheet

• 1-OHP-4030-151-018 (marked)

• Stopwatch (with current cal due date sticker)

• If requested, OHI-4016, Data Sheet 2, Immediate Valve Retest Data ATTACHMENTS None EVALUATION SETTINGS Unit 1 Simulator EVALUATION METHOD: PERFORM: SIMULATE:

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OPERATIONS JPM SIMULATOR/LAB SETUP

1. Initialize simulator to IC-113 (Any Mode 1-3 IC).

2. FREEZE the simulator.

3. Stop Watch Required with Calibration Sticker EVALUATOR INSTRUCTIONS

1. Ensure simulator setup is complete

2. Brief the operator (May be performed by giving out Task Briefing Sheet)

3. Announce start of the JPM

4. Perform evolution

5. At completion of evolution, announce the JPM is complete.

6. Document evaluation performance.

TASK BRIEFING You are the Balance of Plant Operator.

Steam Generator Stop Valve Dump Valve Surveillance Test is required for 1-MRV-210 following a conduit repair. The Unit Supervisor directs you to perform 1-OHP-4030-151-018 on 1-MRV-210 (Section 4.1).

All personnel have been briefed and are locally standing by for the test of 1-MRV-210 Dump Valves.

GENERAL STANDARDS/PRECAUTIONS Perform 1-OHP-4030-151-018, Steam Generator Stop Valve Dump Valve Surveillance Test on 1-MRV-210.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

General CUES:

CUE: Provide candidate marked up copy of 1-OHP-4030-151-018, Steam Generator Stop Valve Dump Valve Surveillance Test (marked to perform section 4.1).

CUE: If requested, provide candidate with a copy of OHI-4016, Data Sheet 2, Immediate Valve Retest Data.

CUE: If asked, all procedure prerequisites have been met and an AEO has been briefed and is stationed at 1-MRV-210 and in communication.

CUE: If asked, US acknowledges 1-MRV-210 is inoperable for testing.

SW-002 12-25-2012 Note: Primary Stop Watch Data is already entered.

N/A Secondary stopwatch data is N/A.

N/A N/A Revision: 0 2012 NRC-SIM03.doc Page 4 of 10

OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

CUE: If asked, all procedure Precautions and Limitations have been met.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

CUE: If asked, all procedure Precautions and Limitations have been met.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Verifies local operator stationed at stop valve.

CUE: If asked, per task brief an operator is stationed at stop valve.

CS: Places AND holds MMO-210 switch to the POS A position.

SAT: UNSAT:

Verifies MMO-210 POS A light is LIT.

SAT: UNSAT:

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Verifies neon lamps for MRV-211 are DARK. (Starts Stopwatch)

SAT: UNSAT:

Records OPEN time from Stopwatch. (Stops Stopwatch when GREEN light goes DARK and RED light is LIT)

SAT: UNSAT:

0 2 CUE: AEO reports pressure indicates 0 psi on MPI-211.

CS: Places MMO-210 switch to the NORM position.

SAT: UNSAT:

Verifies MRV-211 GREEN light is LIT.

SAT: UNSAT:

Verifies MMO-210 NORMAL light is LIT.

SAT: UNSAT:

(CS) Places AND holds MMO-210 switch to the POS B position.

SAT: UNSAT:

Verifies MMO-210 POS B light is LIT.

SAT: UNSAT:

Verifies neon lamps for MRV-212 are DARK. (Starts Stopwatch)

SAT: UNSAT:

Records OPEN time from Stopwatch. (Stops Stopwatch when GREEN light 0 2 goes DARK and RED light is LIT)

SAT: UNSAT:

CUE: AEO reports pressure indicates 0 psi on MPI-212.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

CS: Places MMO-210 switch to the NORM position.

SAT: UNSAT:

Verifies MRV-212 GREEN light is LIT SAT: UNSAT:

Verifies MMO-210 NORMAL light is LIT.

SAT: UNSAT:

Reports testing complete on MRV-210.

SAT: UNSAT:

CUE: JPM is complete.

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Task Briefing You are the Balance of Plant Operator.

Steam Generator Stop Valve Dump Valve Surveillance Test is required for 1-MRV-210 following a conduit repair. The Unit Supervisor directs you to perform 1-OHP-4030-151-018 on 1-MRV-210 (Section 4.1).

All personnel have been briefed and are locally standing by for the test of 1-MRV-210 Dump Valves.

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OPERATIONS JPM NUMBER: 2012 NRC- SIM04 TIME: 15 MINUTES TITLE: Place Hydrogen Recombiner In Service REVISION: 0 Revision: 0 2012 NRC-INP01 Page 1 of 8

OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 01-OHP-4023-SUP-005 Placing Hydrogen Recombiners in Service K/A Number: 028 A4.01 K/A Imp.: RO: 4.0 SRO: 4.0 Task Number: 0340180501 Place Hydrogen Recombiner in service TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS

• Task Briefing sheet

• 01-OHP-4023-SUP-005, Placing Hydrogen Recombiners in Service ATTACHMENTS None EVALUATION SETTINGS SIMULATOR (U1)

EVALUATION METHOD: PERFORM: SIMULATE:

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OPERATIONS JPM SIMULATOR/LAB SETUP

1. Initialize the Simulator to IC-910.

2. Overide PACHMS Meters to ~ 2.0% H2 indication:

• IAO ZAO2CPA_U1[1] to 2% ZAO2CPA_U1[1]

• IAO ZAO2CPB_U1[1] to 2% ZAO2CPB_U1[1]

• IAO ZAO2CPA_U1[2] to 2% ZAO2CPA_U1(2)

• IAO ZAO2CPB_U1[2] to 2% ZAO2CPB_U1(2)

EVALUATOR INSTRUCTIONS

1. Brief the candidate (may be performed by giving out Task Briefing sheet).

2. Announce start of JPM.

3. Perform evaluation.

4. When evaluation is complete, announce end of JPM.

5. Document evaluation (may be delayed until the end of a series of JPMs).

TASK BRIEFING You are an extra operator.

A LOCA occurred 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> ago on Unit 1. The Unit Supervisor directs you to place the Hydrogen Recombiners in service as per 01-OHP-4023-SUP-005, Placing Hydrogen Recombiners in Service.

Containment pressure is 0.5 psig.

GENERAL STANDARDS/PRECAUTIONS Places Hydrogen Recombiners in Service IAW 01-OHP-4023-SUP-005.

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EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

General CUES:

1. Provide candidate a copy of 01-OHP-4023-SUP-005.

2. If asked, all procedure prerequisites have been met.

CUE: Reactor Tripped 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> ago.

Verifies power is available to BOTH H2 Recombiners.

SAT: UNSAT:

Checks CEQ Fans BOTH running SAT: UNSAT:

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EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Checks dampers open.

SAT: UNSAT:

Checks valves open.

SAT: UNSAT:

CUE: Current EDG loading is as follows: DG1AB@2600 KW, DG1CD is Shutdown - CD Buses from Offsite power.

Note: Annun. Panel #103, Drops 46/48, H2 RECOMBINER 1/2 POWER LOW will alarm.

Checks power adjusters set at 000 (BOTH recombiners).

SAT: UNSAT:

CS: Place control switches to RUN (BOTH recombiners).

SAT: UNSAT:

CS: Raise power adjusters to 5 KW (BOTH recombiners).

SAT: UNSAT:

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EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Note: Only 1 Recombiner should be raised above 10KW, The second is left in standby @ 10 KW (Step 4.c).

CUE: Ten Minutes have passed.

CS: Raise power adjusters to 10 KW (BOTH recombiners).

SAT: UNSAT:

CUE: Ten Minutes have passed.

CS: Raise Power adjuster to 20 KW (ONE recombiner).

SAT: UNSAT:

CUE: Five Minutes have passed.

CUE: Containment Pressure is 0.5 psig.

CS: Determines the required KW @ 0.5 psig containment pressure for either recombiner is 46-47.

SAT: UNSAT:

CS: Raise power adjuster to KW determination from previous step (ONE recombiner) 46-47 KW.

SAT: UNSAT:

Logs final conditions on Att. A (Final Conditions: one recombiner should be left at the desired power with the second at ~ 10KW).

CUE: JPM IS COMPLETE.

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EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Note: Candidate must use Figure 1 of 01-OHP-4023-SUP-005, to determine required KW per step 4.b.4.

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Task Briefing You are an extra operator.

A LOCA occurred 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> ago on Unit 1. The Unit Supervisor directs you to place the Hydrogen Recombiners in service as per 01-OHP-4023-SUP-005, Placing Hydrogen Recombiners in Service.

Containment pressure is 0.5 psig.

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NUMBER; 2012 NRC-SIM05 TIME: 20 MINUTES TITLE: Restore RCP Bus 1A Power to Bus T11A REVISION: 0 Revision:

2012 NRC-SIM05.doc Page 1 of 9

REFERENCES/NRC KA/TASKS Procedure: 1-OHP 4023-SUP-002 Restoration of Reserve Power to 4KV Buses K/A Number: SYS 062 A4.07 K/A Imp.: RO: 3.1 SRO: 3.1 Task Number: EOP0390501 Restore Offsite Power to all AC buses using SUP 002.

TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS

• Task Briefing sheet

• Copy of Attachment G of 1-OHP 4023-SUP-002 ATTACHMENTS None EVALUATION SETTINGS Unit 1 Simulator EVALUATION METHOD: PERFORM: SIMULATE:

SIMULATOR/LAB SETUP

1. Reset to an IC-910 .

2. Verify that T11A and T11B are fed from 1AB EDG.

3. Open CB12AB - TR101AB transformer breaker prior to/following Trip & Then Reclose (Must Also Close Unit 2 Breaker on Soft Panel).

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EVALUATOR INSTRUCTIONS

1. Ensure simulator setup is complete

2. Brief the operator (May be performed by giving out Task Briefing Sheet)

3. Announce start of the JPM

4. Perform evolution

5. At completion of evolution, announce the JPM is complete.

6. Document evaluation performance.

TASK BRIEFING You are the extra operator.

The crew is recovering from a station blackout. The AB Emergency Buses are energized by the Emergency Diesel Generators. Offsite power has been restored to the AB RCP Buses.

The US directs you to load the T11A Bus to the RCP bus in accordance with 1-OHP-4023-SUP-002, Attachment G.

TASK STANDARDS Load the T11A Bus to the RCP Bus in accordance with 1-OHP-4023-SUP-002.

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EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Checks for lights, voltage, and/or amps on 4kV Bus 1A.

SAT: UNSAT:

Checks DG1AB running with Output Breaker to T11A closed.

SAT: UNSAT:

Places both Voltmeters to OFF position.

SAT: UNSAT:

CS: Places DG1AB 4KV CB T11A9 Synch Selector switch in MANUAL.

SAT: UNSAT:

CS: Adjusts DG1AB (START) voltage 2-3 volts higher than Bus 1A (RUN) voltage.

SAT: UNSAT:

NOTE: Must use auto Voltage Adjust POT.

CS: Adjusts speed so the Synchroscope is rotating SLOWLY in the FAST direction.

SAT: UNSAT:

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EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

CS: Closes DG1AB 4KV CB T11A9 control switch at 11:00.

SAT: UNSAT:

Verifies WHITE light permissive is LIT.

SAT: UNSAT:

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EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

CS: Places DG1AB Synchronize Master Close Switch in CLOSE at 11:00.

SAT: UNSAT:

Checks Breaker T11A9 CLOSED.

SAT: UNSAT:

Instructor Note: Ann. 119, Drop 76, 4KV BUS T11A PARALLEL OPERATION, will alarm when both supply breakers are closed.

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EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

CS: Adjusts DG1AB load to greater than 0 kw.

SAT: UNSAT:

CS: Places DG1AB 4KV CB T11A9 Synch Selector switch in OFF.

SAT: UNSAT:

Adjusts DG1AB voltage as required.

SAT: UNSAT:

CS: OPENS breaker T11A11.

SAT: UNSAT:

CUE: US acknowledges tripping open the T11A11 breaker.

Recognized that Bus T11B is still energized by DG1AB and leaves DG1AB running.

SAT: UNSAT:

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CUE: When a transition is made back to Supplement Body, Step 5, JPM is COMPLETE.

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TASK BRIEFING You are the extra operator.

The crew is recovering from a station blackout. The AB Emergency Buses are energized by the Emergency Diesel Generators. Offsite power has been restored to the AB RCP Buses.

The US directs you to load the T11A Bus to the RCP bus in accordance with 1-OHP-4023-SUP-002, Attachment G.

Revision:

2012 NRC-SIM05.doc Page 9 of 9

OPERATIONS JPM NUMBER: 2012 NRC-SIM06 TIME: 15 MINUTES TITLE: Unit 1 CR Vent Alignment for Unit 2 SI REVISION: 0 Revision: 0 2012 NRC-SIM06.doc Page 1 of 6

OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 1-OHP-4021-028-014 Operation of Control Room AC and Pressurization/Cleanup/Filter System 072.A3.01 K/A Number:

K/A Imp.: RO: 2.9 SRO: 3.1 Task Number: EOP0230501 Verify proper equipment response following Safety Injection actuation.

0280010501 Perform Control Room Pressurization System checks following an automatic actuation.

TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS

• Task Briefing sheet

• Copy of 1-OHP-4021-028-014, Attachment 13 ATTACHMENTS None EVALUATION SETTINGS Unit 1 Simulator EVALUATION METHOD: PERFORM: SIMULATE:

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OPERATIONS JPM SIMULATOR/LAB SETUP

1. Initialize simulator to IC-113 (MODE 1 IC with the following Actions taken).

EVALUATOR INSTRUCTIONS

1. Ensure simulator setup is complete

2. Brief the operator (May be performed by giving out Task Briefing Sheet)

3. Announce start of the JPM

4. Perform evolution

5. At completion of evolution, announce the JPM is complete.

6. Document evaluation performance.

TASK BRIEFING You are the Extra RO A Safety Injection (SI) has occurred on Unit 2.

The US directs you to verify that the Unit 1 Control Room Ventilation system is aligned for the Unit 2 SI signal by performing Attachment 13 of 1-OHP-4021-028-014.

TASK OBJECTIVES/STANDARDS:

Align the Unit 1 CR AC and Pressurization system for a Unit 2 SI signal, observing procedure steps and precautions and limitations of 1-OHP-4021-028-014.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Note: The Unit 2 SI signal did not result in the expected realignment of the Unit 1 CRAC and Pressurization system. The Operator will place all Unit 1 equipment in the required condition.

CS: Starts only 1 pressurization fan.

SAT: UNSAT:

CS: Closes both intake dampers.

SAT: UNSAT:

CS: Places 1 damper to partial open.

Note: The other damper remains closed.

SAT: UNSAT:

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Verifies damper open SAT: UNSAT:

Verifies hatch closed by Panel 101, Drop 69 alarm clear -OR- simulates verifying hatch closed in back of Control Room SAT: UNSAT:

CUE: If the candidate walks toward the back of the control room, say the Control Room Cable Vault Hatch is CLOSED.

CUE: JPM is COMPLETE Revision: 0 2012 NRC-SIM06.doc Page 5 of 6

Task Briefing You are the Extra RO.

A Safety Injection (SI) has occurred on Unit 2.

The US directs you to verify that the Unit 1 Control Room Ventilation system is aligned for the Unit 2 SI signal by performing Attachment 13 of 1-OHP-4021-028-014.

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NUMBER; 2012 NRC-SIM07 TIME: 15 MINUTES TITLE: Respond to a Unit 2 Plant Air Header REVISION: 0 Leak (Alt. Path)

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OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 1-OHP-4022-064-001 Control Air Malfuction K/A Number: 078 A3.01 K/A Imp.: RO: 3.1 SRO: 3.2 Task Number: 0640150101 Operate the Plant or Control Air Compressors TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS Copy of:

• Task Briefing sheet

• 1-OHP-4024-122, Plant Service

• 1-OHP-4022-064-001, Control Air Malfuction ATTACHMENTS None EVALUATION SETTINGS Unit 1 Simulator EVALUATION METHOD: PERFORM: SIMULATE:

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OPERATIONS JPM SIMULATOR/LAB SETUP

1. Initialize simulator to IC-912.

2. Block Auto Start of U1 CAC U1_PPS3

3. Block Auto Close of PRV10 & 11 U1_PPS11

4. Set Up Trigger to reduce CAC Load when PRV-10 & 11 Are Closed PRV10 & PRV 11 Closed U1_IA04A U1_IAR09

5. Insert U2 PA leaks on Trigger 9 U2_IA02A U1_IA04A U1_IAR09

6. Activate Trigger 9 to start the leaks when briefing starts.

Activate Trigger 9 EVALUATOR INSTRUCTIONS

1. Ensure simulator setup is complete

2. Brief the operator (May be performed by giving out Task Briefing Sheet)

3. Announce start of the JPM

4. Perform evolution

5. At completion of evolution, announce the JPM is complete.

6. Document evaluation performance.

TASK BRIEFING You are an extra operator. Unit 1 is in Mode 3.

When I tell you to begin, you are to respond to the Annunciator Panel #122 alarm(s).

You may use any approved reference material that is normally available in the Control Room.

The Unit Supervisor directs you to respond to the Annunciator Panel #122 alarm(s).

TASK STANDARDS Respond to a lowering Unit 1 Control Air Header pressure by starting the Unit 1 Control Air Compressor and closing the Plant Air Header Crosstie Valves to Unit 2 per 1-OHP-4022-064-001, Control Air Malfunction procedure.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Note: Annun. Panel #122, Drops 16 and 23 are expected alarms. The candidate should perform expected actions per Annun. Panel #122, Drop 23.

Note: If the candidate contacts Unit 2 control room, then report the Unit 2 Plant Air Compressor (PAC) has automatically started and an operator has been dispatched to check it out.

Dispatches an operator to locally check XPI-100.

SAT: UNSAT:

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Goes to 1-OHP-4022-064-001.

SAT: UNSAT:

CUE: Provide a copy of 1-OHP-4022-064-001.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Checks XPI-100 greater than 80 psig.

SAT: UNSAT:

Dispatches an operator -OR- calls Unit 2 control room, to ensure that Unit 2 PAC is running and loaded.

SAT: UNSAT:

Note: If the candidate contacts Unit 2 control room, then report the Unit 2 Plant Air Compressor (PAC) has automatically started and an operator has been dispatched to check it loaded to the header.

Dispatch an operator to start the Backup PAC.

SAT: UNSAT:

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Checks XPI-100 and recognizes it is less than 90 psig.

SAT: UNSAT:

Goes to Step 6.

SAT: UNSAT:

CS: Starts Unit 1 Control Air Compressor (CAC).

SAT: UNSAT:

CS: Closes the following valves:

• 1-PRV-10

• 1-PRV-11 SAT: UNSAT:

CUE: JPM is COMPLETE Revision: 0 2012 NRC-SIM07.doc Page 7 of 8

TASK BRIEFING You are an extra operator. Unit 1 is in Mode 3.

When I tell you to begin, you are to respond to the Annunciator Panel #122 alarm(s). You may use any approved reference material that is normally available in the Control Room.

The Unit Supervisor directs you to respond to the Annunciator Panel #122 alarm(s).

Revision:

2012 NRC-SIM07.doc Page 8 of 8

NUMBER; 2012 NRC-SIM08 TIME: 15 MINUTES TITLE: Respond to R-19 SG Blowdown RMS Hi REVISION: 0 Alarm (Alternate Path)

Rev 2012 NRC-SIM08.doc Page 1 of 6

OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 1-OHP-4024-138, Drop 15 RMS Electro-larm - R19 SG Blowdown Sampling K/A Number: 068 A2.04 K/A Imp.: RO: 3.3 SRO: 3.3 Task Number: 0130300801 Respond to a RMS High Alarm TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS Copy of:

• Task Briefing sheet

• 1-OHP-4024-123, Circulating Water

• 1-OHP-4024-138, RMS Electro-larm ATTACHMENTS None EVALUATION SETTINGS Unit 1 Simulator EVALUATION METHOD: PERFORM: SIMULATE:

SIMULATOR/LAB SETUP Revision: 0 2012 NRC-SIM08.doc Page 2 of 6

OPERATIONS JPM

1. Initialize the Simulator to IC-113 (any at-power IC).

2. Block Auto Actions and alarms from R19 ZGI101R19BLCK_U1 Block OFF ZLO101R19BLCK_U1[1] ARM ON ZLO101R19BLCK_U1[2]

3. Simulate actual R19 Alarms U1_RM02D AN23_U1(046)

4. Place R19 Electro-Alarm in Alarm position EVALUATOR INSTRUCTIONS

1. Ensure simulator setup is complete

2. Brief the operator (May be performed by giving out Task Briefing Sheet)

3. Announce start of the JPM

4. Perform evolution

5. At completion of evolution, announce the JPM is complete.

6. Document evaluation performance.

TASK BRIEFING You are an extra operator.

When I tell you to begin, you are to respond to the Annunciator Panel #123 alarm. You may use any approved reference material that is normally available in the Control Room.

The Unit Supervisor directs you to respond to the Annunciator Panel #123 alarm.

TASK STANDARDS Isolate Steam Generator Blowdown IAW 1-OHP-4024-138, Drop 15, R19 SG Blowdown Sampling.

Operator has verified automatic actions associated with R-19 Westinghouse Radiation Monitor.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Identifies that R-19 is in Alarm.

SAT: UNSAT:

Refers to 1-OHP-4024-138.

SAT: UNSAT:

CUE: Provide a copy of 1-OHP-4024-138.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

May notify Radiation Protection and/or Unit Supervisor (US) of High Alarm On R19.

SAT: UNSAT:

CUE: If required, "The US directs you to perform the automatic actions.

CS: Dispatches an operator to close 1-DRV-350 (on the Waste Disposal System [WDS] Panel - 587 Aux. Bldg.)

SAT: UNSAT:

CUE: If requested, as the AEO 1-DRV-350 has been CLOSED CS: Closes the following valves:

• DCR-310

• DCR-320

• DCR-330

• DCR-340 SAT: UNSAT:

CS: Places NUCLEAR SMPLG ISOL VAVES control switch to ISOLATE -OR- dispatches operator/chemist, to close:

(All [4] in Nuc. Sampling Rm. - 587 Aux. Bldg.)

• DCR-301 U1_WDR10

• DCR-302 U1_WDR11

• DCR-303 U1_WDR12

• DCR-304 U1_WDR13 SAT: UNSAT:

CUE: JPM is COMPLETE Revision: 0 2012 NRC-SIM08.doc Page 5 of 6

TASK BRIEFING You are an extra operator.

When I tell you to begin, you are to respond to the Annunciator Panel #123 alarm. You may use any approved reference material that is normally available in the Control Room.

The Unit Supervisor directs you to respond to the Annunciator Panel #123 alarm.

Revision: 0 2012 NRC-SIM08.doc Page 6 of 6

Appendix D Scenario Outline Form ES-D-1 Facility: _Cook Plant Unit 1 & Unit 2_ Scenario No: NRC2012-01 Op-Test No.: Crews 1, 2, & 3 Examiners: _________________ Operators: ___________________

Initial Conditions: IC- 522, 1% pwr, 1205 ppm boron, 10 GWD, 549°F Tavg, CBD @136 steps, 0 MW.

Turnover: Start the Middle Condensate Booster Pump, Raise Power to 3% for MFW Pump Start-up (Extra-RO will start the MFP), Rods in MANUAL, SG on MDAFPs.

Event No. Malf. No. Event Event Type* Description 1 N-BOP Start the Middle Condensate Booster Pump.

2 R-RO Raise Power to 3% Power.

3 QLC451 @ 100 I-RO VCT Level Transmitter (QLC-451) Fails HIGH.

TS 4

ED07A C-RO PZR HTR Transformer Fails (11PHA Fails).

TS 5 CLC10 to 0% I-BOP Hotwell Level Transmitter CLC-10 Fails LOW.

6 RX11D @100% C-BOP SG PORV Controller Failure.

TS 7 ED01 M Loss of All AC Power.

ED25 ED03A 1CD EDG Trip.

EG06B 8 EG08A C-BOP 1AB EDG Speed Governor Failure.

9 FW48C C-BOP TD AFW Pump Fails to AUTO start.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Cook Plant Unit 1 & 2 Page 1 of 15

Event Summary (NRC 2012-01)

The BOP is directed to start the Middle Condensate Booster Pump (CBP). The operator will place the Middle CBP in service in accordance with the normal operating procedure.

The Crew is directed to raise power to 3-4% for MFW Pump Start-up.

The third event will involve the VCT Level instrument (QLC-451) failing HIGH. This will result in the VCT High Level alarm. The RO will be required to perform a manual makeup to the RCS. The Crew will be required to implement AOP actions to stabilize the plant and trip bistables.

A failure of the PZR HTR Bus 11PHA will occur. The PZR SCR heater control will need to be transferred to 11PHC. The crew should also refer to Technical Specifications.

Then the Hotwell Level Transmitter CLC-10 fails LOW. The low failure will cause the Condensate Makeup valve (CRV-55) to fully open and the Condensate Letdown Valve (CRV-155) to fully close causing a rise in actual hotwell level. The BOP will be required to take manual control of the Hotwell Level Controller and return hotwell level to a normal band. The non failed hotwell level input may be selected for subsequent auto control.

The next event will involve the failure of the SG #14 PORV Controller. The controller will fail causing PORV 1-MRV-243 to fully open. This will also cause Reactor power to slightly rise. The BOP will need to take manual action to close the PORV and the US will need to declare the associated radiation monitor inoperable.

The Major event is a loss of all AC power. The reactor will trip. Failure of the EDGs will require entry into ECA-0.0 actions. Failure of the TDAFW Pump to auto start will require a manual start to restore feedwater flow. The crew will be required to take actions to restore Emergency Power (EP). The crew should transition to ECA-0.1 once power has been restored to one Safeguards Bus. The scenario will terminate when the crew has restored emergency power and transitioned to ECA-0.1 or ECA-0.2.

Critical Tasks Establish AFW (Start TDAFWP)

Restore Emergency Power to Safeguards Bus Procedures E-0, Reactor Trip or Safety Injection ECA-0.0, Loss of All AC Power Cook Plant Unit 1 & 2 Page 2 of 15

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Crews 1, 2, & 3 Scenario No.: NRC2012-01 Event No.: 1 Event

Description:

Start the Middle Condensate Booster Pump Time Position Applicant's Actions or Behavior US Directs actions of 1-OHP-4021-054-001, Attachment 2, Operation of Hotwell (HW) and Condensate Booster (CB) Pumps to start the Middle CB Pump.

US Directs the following actions to realign condensate system:

• Start the Middle CB pump.

BOP Performs the following to swap CB Pumps as directed:

1. Places the following switches in NEUTRAL:

• Standby CB Pump

• Standby HW Pump

• Standby TACW Pump

2. Starts the Middle CB Pump.

3. Directs operator to verify CRV-224 closed.

4. Places the following switches in AUTO:

• Standby CB Pump

• Standby HW pump

• Standby TACW pump Note: If desired, crew may remove power from 1-CRV-202, Middle CBP Emergency Leak-Off.

Note: Ann. 116, Drop 73, CNDST BOOSTER PUMP DISCH PRESSURE LOW may annunciate during this evolution.

Cook Plant Unit 1 & 2 Page 3 of 15

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:Crews 1, 2, & 3 Scenario No.: : NRC2012-01 Event No.: 2 Event

Description:

Raise Power to 3-4% Power Time Position Applicant's Actions or Behavior RO Briefs crew on reactivity plan for power rise.

US Reviews reactivity plan.

US Directs RO to commence Power Escalation in accordance with 1-OHP-4021-001-006, Power Escalation procedure.

RO Commences power rise by pulling rods or dilution.

US Acts as reactivity manager.

Cook Plant Unit 1 & 2 Page 4 of 15

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:Crews 1, 2, & 3 Scenario No.: NRC2012-01 Event No.: 3 Event

Description:

VCT Level Transmitter (QLC-451) fails HIGH Time Position Applicant's Actions or Behavior RO Recognizes indication of VCT Level problem and reports annunciator:

• Panel #109, Drop 47.

US Directs operator action per 1-OHP-4022-013-017, VCT Instrument Malfunction:

• Restores Divert Valve (QRV-303) to VCT position.

• Trip Interposing Relay in accordance with Attachment A.

RO Recognizes and reports failure of VCT Level Transmitter (QLC-451).

• Place Divert Valve (QRV-303) in VCT position.

• Perform MANUAL blend operation to maintain VCT level in band, as required.

• Requests Caution Tags (Yellow) on QRV-303 and Makeup Controls.

US Refers to the Technical Requirements Manual (TRM):

• TRM 8.1.1 Boration System - Operating Condition A.1 - Restore to operable within 72 Hours (RWST to CVCS auto swapover)

Cook Plant Unit 1 & 2 Page 5 of 15

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:Crews 1, 2, & 3 Scenario No.: NRC2012-01 Event No.: 4 Event

Description:

Pressurizer Heater Transformer (TR11PHA) Fails Time Position Applicant's Actions or Behavior RO Recognizes and reports annunciators on Panel 108, Drops 41 and 50, indicative of a pressurizer (PRZ) heater power supply failure.

US/RO Reenergizes PRZ control (cycling) group heaters per 1-OHP-4024-108, Drop 41 annunciator response, as follows:

• Opens breaker CB11PHA6

• Closes breaker CB11PHC6 (Drop 50 clears)

RO Monitors PRZ pressure response and ensures normal PRZ heater operations for PHC supplied heaters.

US Refers to Tech Specs (TS):

• TS 3.4.9.b Pressurizer - (Condition B.1) due to a loss of 1 train of pressurizer heaters. Restore B/U heaters to operable within &2 Hours Cook Plant Unit 1 & 2 Page 6 of 15

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:Crews 1, 2, & 3 Scenario No.: NRC2012-01 Event No.: 5 Event

Description:

Hotwell Level Transmitter CLC-10 fails Low Time Position Applicants Actions or Behavior BOP Acknowledges and reports alarms on Ann. Panel 116 as applicable:

• Drop 1, CONDENSER A HOTWELL LEVEL HIGH

• Drop 11, CONDENSER B HOTWELL LEVEL HIGH

• Drop 21, CONDENSER C HOTWELL LEVEL HIGH BOP Identifies that Hotwell Level Controller CLC-10 is failed as indicated by:

• Condensate Makeup Valve (CRV-55) fully open

• Condensate Letdown Valve (CRV-155) fully closed

• Rising hotwell level on CLC-30 BOP Places Hotwell Level Controller in MANUAL and adjusts controller output to maintain normal hotwell level.

US/BOP Performs one of the following:

• Maintains Hotwell level in MANUAL.

-OR-

• May select CLC-30 as the controlling channel and places the HW Level Controller back to AUTO.

Cook Plant Unit 1 & 2 Page 7 of 15

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Crews 1,2,& 3 Scenario No.: NRC2012-01 Event No.: 6 Event

Description:

SG PORV Controller Failure Time Position Applicant's Actions or Behavior BOP Recognize and reports Annunciator #114 Drop 24 that indicates SG #4 PORV MRV-243 has opened.

US Direct operator actions to close SG #4 PORV and monitor Reactor Power.

BOP Place SG PORV #4 in MANUAL and closes SG #4 PORV.

US Declares the SG #4 PORV Radiation Monitor MRA-1602 inoperable.

US Refers to the following Tech Specs (TS) / Tech Requirements Manual (TRM):

• TS 3.7.4, SG PORVs - (Note: Only Manual Ops Required) - N/A

• TRM 8.3.8. Radiation Monitoring Instrumentation, Condition C.1-Restore channel/monitor to operable status within 7 Days (PORV must be able to auto open for Radiation Monitor but not PORV safety Function.)

Cook Plant Unit 1 & 2 Page 8 of 15

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:Crews 1, 2, & 3 Scenario No.: : NRC2012-01 Event No.: 7/8/9 Event

Description:

Complete Loss of All AC Power - 1AB/CD Emergency Diesel Generator Failure; Turbine Driven AFW Pump Fails to Auto Start Time Position Applicant's Actions or Behavior CREW Identifies the need for a Reactor Trip and trips the reactor manually.

US Directs RO/BOP to perform the immediate actions of 1-OHP-4023-E-0 (E-0), Reactor Trip or Safety Injection.

RO Performs the (primary) immediate actions of E-0:

1. Verifies reactor trip

2. Checks safety injection status BOP Performs the (secondary) immediate actions of E-0:

1. Checks turbine trip

2. Checks power to AC emergency buses:

• Reports that NO AC emergency buses are energized Note: Crew may enter ECA-0.0, Loss Of All AC Power, directly.

US Announces transition (or entry) to 1-OHP-4023-ECA-0.0 (ECA-0.0), Loss Of All AC Power and directs RO/BOP to perform immediate actions for ECA-0.0.

US Announces RX Trip over Executone RO/BOP Performs the immediate actions of ECA-0.0:

• Checks reactor trip

• Checks turbine trip US Ensures immediate actions are completed and directs subsequent actions of ECA-0.0.

RO Checks RCS isolated:

1. Checks PRZ PORVs closed (NRV-151, 152 and 153)

2. Checks letdown isolation valves closed (QRV-111 and 112)

3. Checks excess letdown isolation valves closed (QRV-113 and 114)

BOP Checks AFW flow > 240,000 PPH:

1. Manually starts the Turbine Driven AFW (TDAFW) Pump Critical Task 2. May throttle TDAFW FMOs to establish > 240,000 PPH but heat sink

1. 1 requirements are met with SG Levels.

Cook Plant Unit 1 & 2 Page 9 of 15

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:Crews 1, 2, & 3 Scenario No.: : NRC2012-01 Event No.: 7/8/9 Event

Description:

Complete Loss of All AC Power - 1AB/CD Emergency Diesel Generator Failure; Turbine Driven AFW Pump Fails to Auto Start Time Position Applicant's Actions or Behavior US Identifies that:

• NEITHER EDG (AB nor CD) is available

• NEITHER the T11A nor the T11D bus is energized US Identifies Emergency Power (EP) source is AVAILABLE.

US Directs Restoration of 4KV Power From EP using Attachment D.

RO/BOP Directs AEO to manually isolate RCP Seals by closing :

• 1-CS-311N

• 1-CS-311S

• 1-CS-307

• 1-QCM-350 (locally)

BOP/US Places the following equipment in Pull-To-Lock:

• MDAFPs

• CCPs

• RHR Pumps

• SI Pumps

• CTS Pumps

• CCW Pumps

• ESW Pumps

• NESW Pumps

• PRZ Heaters BOP/US Identifies that the EITHER Train - Load Conservation lights are NOT LIT and that the Offsite Emergency Power is supplying the EP bus.

BOP Energizes EITHER emergency bus (T11A or T11D) from EP as directed:

Critical Task 1. Checks bus - not faulted

1. 2 2. Places EDG supply to bus in pull to lock

3. Places Load Conservation Switch in LOAD CON

4. Closes 4KV EP supply to bus and energizes bus RO/BOP Isolates Seal Return and RCP CCW Return line from Thermal Barrier:

• QCM-350 OR QCM-250 - CLOSED

• CCM-454 OR CCM-453 - CLOSED Cook Plant Unit 1 & 2 Page 10 of 15

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:Crews 1, 2, & 3 Scenario No.: : NRC2012-01 Event No.: 7/8/9 Event

Description:

Complete Loss of All AC Power - 1AB/CD Emergency Diesel Generator Failure; Turbine Driven AFW Pump Fails to Auto Start Time Position Applicant's Actions or Behavior BOP Energizes emergency bus (T11B or T11C) from EP as directed:

1. Checks bus - not faulted

2. Places DG supply to bus in pull to lock

3. Closes 4KV EP supply to bus and energizes bus RO/BOP Checks RCS Temperature stable or trending to 547ºF.

RO/BOP Realigns Equipment following power restoration:

• Start ESW Pump and verifies discharge valve opens.

• Return Load Conservation Switch to NORMAL.

• Reset and start one Control Room AHU.

US Based on RCS subcooling and PRZ level, announces transition to:

• ECA-0.1, Loss Of All AC Power Recovery Without SI Required

-OR-

• ECA-0.2, Loss Of All AC Power Recovery With SI Required if Subcooling is < 40 ºF OR Pressurizer level is < 21%.

TERMINATE SCENARIO Cook Plant Unit 1 & 2 Page 11 of 15

Critical Task Summary (NRC2012-01)

Task Elements Results

1. 1 Cueing: SAT / UNSAT

• Check AFW FlowVerify TDAFP Running (ECA-0.0, Manually Starts Step 4, RNO)

Turbine Driven AFW Pump Performance Indicators:

Establish AFW flow before SG dryout occurs (<15% WR level):

• Manually starts the TDAFP from the control room.

Performance Feedback:

• TDAFP speed rising

• AFW flow indications

1. 2 Cueing: SAT / UNSAT

• Restore AC Power (ECA-0.0)

Restore Emergency

• T11 A, B, C, D Energized Lights - NOT Lit Power Performance Indicators:

Power should be restored prior to depressurizing intact SGs to 190 psig (ECA-0.0, Step 19):

• Restores emergency power (EP) to at least one 4KV emergency (pump) bus (i.e., T11A or T11D).

Performance Feedback:

• T11A or T11D bus energized

• Power available to safeguards equipment.

Cook Plant Unit 1 & 2 Page 12 of 15

Simulator Instructions (NRC2012-01)

Setup:

1. Reset to IC-522.

2. Reset control rods and check group step counters.

3. Place Master Annunciator Silence pushbutton lockout ring in LOCKOUT position.

4. Set Up PPC Digital Display to Point U0485 (Delta T Power)

5. Advance chart recorder paper & clear chart recorder memory.

6. Verify/Activate the following (pre-load) malfunctions:

• IMF EG08A, AB EDG Speed Governor Failure U1_EG08A

• IMF FW48C, TD AFW pump fails to AUTO start U1_FW48C

• IMF SFR401, SJAE Flow to Maintain Steady Low Power Values U1_SFR401

7. Assign the following Event Trigger 9:

• IMF ED01, Delay 10 secs, Loss of 345 KV Bus 1 U12_ED01

• IMF ED25, Delay 12 secs, Loss of 765/345 KV Transformer Bank No. 4 U12_ED25

• IMF E03A, Delay 15 secs, Loss Of Reserve Auxiliary Transformer TR-101AB U1_ED03A

• EG06B Delay 30 secs, CD EDG Trip U1_EG06B Cook Plant Unit 1 & 2 Page 13 of 15

Simulator Instructions (NRC2012-01)

Scenario:

EVENT #1 Report as AEO as required:

• Starting Party is standing-by, the Middle CB Pump is ready for start. Maintenance verified the oil pump is primed and has added oil IAW 1-OHP-4021-054-001.

• Oil Pressure is 5 psig after pump start.

• 1-CRV-224 is closed Report as required to other departmental requests.

If asked to remove power from 1-CRV-202, insert ZDIVDAB13_U1 to OFF C 202 (May need to use Soft Panel for VDAB)

EVENT #2 NOTE: Ensure 1-OHP-4021-001-006, Power Escalation procedure is sign-off thru step 4.8 and steps have been completed on the simulator.

EVENT #3 After the crew has performed a power escalation, then insert ICF U1_QLC451, final value 100 over 2 sec (QLC-451 fails HIGH).

U1_QLC451 If directed to energize interposing relay for QLC-451 then use:

• Remote Function RPR157 to Trip LBX-112B U1_RPR157 NOTE: Ensure Crew has Caution Tags (> 2).

EVENT #4 After the crew has responded to the VCT level failure, insert IMF ED07A (PZR heater transformer fails). U1_ED07A As AEO, report T11A6 tripped on Overload/Overcurrent.

Cook Plant Unit 1 & 2 Page 14 of 15

Simulator Instructions (NRC2012-01)

EVENT #5 When the PRZ heater transformer failure is inserted, also insert ICF U1_CLC10, Final Value 0, to fail Hotwell Level Transmitter (CLC-10) Low.

U1_CLC10 Note: Takes ~12 minutes before alarms come in.

Monitor u1_msxcla10_inp for Hotwell level - alarms at 588.333 EVENT #6 After the crew has responded to the Hotwell level transmitter failure, then insert RX11D, final value 100 (SG PORV Controller failure). U1_RX11D EVENT #7 - 9 After the crew has responded to the SG PORV failure, insert Event Trigger 9.

Activate Trigger 9

• IMF ED01, Delay 10 secs, Loss of 345 KV Bus 1

• IMF ED25, Delay 12 secs, Loss of 765/345 KV Transformer Bank No. 4

• IMF E03A, Delay 15 secs, Loss Of Reserve Auxiliary Transformer TR-101AB

• EG06B Delay 30 secs, CD EDG Trip If directed to locally close seal injection valves (1-CS-311N, 311S and 307) then activate remote functions:

• IRF CVR20, Final Value 0 (CLOSE) U1_CVR20

• IRF CVR21, Final Value 0 (CLOSE) U1_CVR21 If directed to locally isolate RCP Seal Water Return Valve (1-QCM-350) then activate remote function:

• IRF CVR77, Final Value 0 (CLOSE) U1_CVR77 When Directed to Trip Bus 2 Main Breaker 12-CCB-5C then activate remote function:

• IRF U2_SWR88, TRIP 12-CCB-5C Main Breaker Cook Plant Unit 1 & 2 Page 15 of 15

Appendix D Scenario Outline Form ES-D-1 Facility: Cook Plant Unit 1 & Unit 2 Scenario No.: NRC2012-02 Op-Test No.: Crews 1, 4, & 5 Examiners: _________________ Operators: ___________________

Initial Conditions: IC-115,100% pwr, 797 ppm boron, 10 GWD, 556°F Tavg, CBD @ 217 steps, 1145 MWe.

Turnover: Lower SI Accumulator Pressure and then lower power to 95% for water box cleaning.

Event Malf. No. Event Event No. Type* Description 1 N Lower SI Accumulator #3 Pressure to Within BOP Notification Limits.

2 R Lower Turbine and Reactor Power.

RO 3 NLP151 @ I-RO Controlling Pressurizer Level Channel (NLP-151) Fails 0% LOW.

TS 4 RH09B C-BOP West RHR Pump Suction Strainer Cap Leak.

TS 5

RC17C to C-RO Pressurizer PORV NRV-153 Opens.

50% TS 6 FFC220 @ I-BOP SG #2 Feed Flow Instrument (FFC-220) Fails HIGH.

4E6 TS 7 RC01D to M Loop 4 Cold Leg Primary Coolant System Leak Inside 20% over 5 Containment.

min ramp 8 101ICM305 C-ALL Loss of Recirc Sump Capability.

9 RP13A C-BOP Phase A Train A & B Fails to Automatically Actuate.

RP13B Phase A Train A Fails to Manually Actuate.

RP14A

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Cook Plant Unit 1 & 2 Page 1 of 20

Event Summary (NRC2012-02)

The BOP is directed to Lower SI Accumulator Pressure to within limits. After the SI Accumulator Pressure has been restored, the crew is required to respond to various events.

If required, the crew will be directed by the Shift Manager to lower power.

While reducing power, the controlling Pressurizer Level channel NLP-151 fails LOW. Charging flow control valve (QRV-251) opens to raise charging flow which causes actual pressurizer level to rise. Pressurizer water level low alarm comes in, a letdown isolation occurs, and all pressurizer heaters will de-energize. The RO will need to take manual control of the Pressurizer Level controller and restore level. The crew should implement the AOP, stabilize the plant, trip bistables, select an operable channel, and restore level control to auto.

While the RO is restoring letdown, leakage on the RHR pump suction piping will require the BOP to isolate the RHR pump.

After the Crew has addressed the Tech Specs for RHR, the Pressurizer PORV NRV153 will fail partially open. This results in Actual RCS pressure lowering. The RO will be required to take manual actions to isolate the PORV (close block valve) and restore normal pressure conditions.

When the RCS Pressure has been restored a HIGH failure of #2 Steam Generator Feed Flow instrument (FFC-220) will occur. This will result in a lowering feedwater flow to #2 SG with corresponding SG level lowering. The BOP will be required to take manual control of FRV-220. Crew will be required to implement AOP actions to stabilize the plant and trip bistables.

When the SG level has stabilized, a Large Break LOCA will occur requiring a Reactor Trip and SI. On the Trip, the breaker for ICM-305 will be discovered to be without power, resulting in a Loss of Emergency Coolant Recirculation capability. On the SI, the auto Phase A Isolation will also fail requiring manual alignment of Phase A equipment. The crew should progress through E-0, E-1, and ECA-1.1. The scenario will terminate once a transition has been made back to E-1.

Critical Tasks Initiate/Isolate Phase A Isolate RWST Outflow Procedures E-0 Reactor Trip or Safety Injection E-1 Loss of Reactor or Secondary Coolant ECA-1.1, Loss of Emergency Coolant Recirculation Cook Plant Unit 1 & 2 Page 2 of 20

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Crews 1, 4, & 5 Scenario No.: NRC2012-02 Event No.: 1 Event

Description:

Restore SI Accumulator #3 pressure to within Notification Limits.

Time Position Applicant's Actions or Behavior BOP Reviews procedural requirements for raising SI Accumulator pressure per 1-OHP-4021-008-006, Adjusting Pressure in an Accumulator BOP Aligns valves (OPENS) to LOWER Accumulator #3 pressure:

• IRV-132

• GRV-341 BOP Monitor Accumulator pressure lowering.

BOP Isolate valves when Accumulator #3 desired pressure is reached:

• GRV-341

• IRV-132 Cook Plant Unit 1 & 2 Page 3 of 20

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Crews 1, 4, & 5 Scenario No.: NRC2012-02 Event No.: 2 Event

Description:

Reduce Turbine Load / Reduce Reactor Power Time Position Applicant's Actions or Behavior RO Calculates boric acid addition per 1-OHP-4021-005-002, Attachment 9, Boration or Dilution Volume Determination.

RO Briefs crew on reactivity plan for power reduction.

US Reviews reactivity plan.

RO Energize Pressurizer Backup Heaters US Directs RO to commence Power Reduction in accordance with 1-OHP-4021-001-003.

RO Performs BORATION:

Place RC Makeup Blend Control Switch in STOP.

Place RC Makeup Blend Control Mode Selector Switch in BORATE.

Set desired batch on BA Flow Totalizer.

Adjust BA Flow Ctrl (RU-33) to desired flow.

Place RC Makeup Blend Control Switch in START.

RO Commences power reduction:

• Lowers turbine load (reactor power) using HMI.

• Maintains Tavg/Tref deviation within limits by boration and turbine load adjustments.

• Ensures Axial Flux Difference (AFD) is maintained within target band by manual control rod movement as needed.

BOP/RO Acts as peer checker for RO during blender operations and RO verifies appropriate reactivity feedback.

BOP Monitors main electrical generator temperatures.

Cook Plant Unit 1 & 2 Page 4 of 20

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Crews 1, 4, & 5 Scenario No.: NRC2012-02 Event No.: 3 Event

Description:

Pressurizer Level Channel (NLP-151) Fails Low Position Applicants Actions or Behavior RO Recognizes and reports annunciators on Panel #108 (Drops 4, 5 and 50) indicative of a pressurizer (PRZ) level instrument failure.

RO Places QRV-251, Charging Flow Controller OR PRZ Level Controller to manual and manually adjusts output to minimize charging header flow and seal injection to normal.

US Enters and directs actions of 1-OHP-4022-013-010, Pressurizer Level Instrument Malfunction procedure.

1. Performs the following actions as directed:

RO/BOP 2. Restores PRZ level using QRV-251 or level controller

3. Reports NLP-151 has failed

4. Ensures PRZ level control is in manual

5. Places PRZ Level CTRL selector switch 459D in Ch. 2 & 3 position

6. Places PRZ Level REC selector switch 459E in Ch. 2 or 3 position

7. Restores normal letdown per 1-OHP 4021.003.001 Attachment 13 as:

a. Places QRV-302 in divert position

b. Verifies orifice isolations closed (QRV-160, 161 and 162)

c. Adjusts CRV-470 controller to 50%

d. Verifies open letdown isolation valves:

o QCR-300 and QCR-301 o QRV-111 and QRV-112

e. Adjusts QRV-301controller to 50%

f. Checks/adjusts charging flow to > 75 gpm

g. Opens QRV-161 or 162

h. Adjusts QRV-301 to maintain 160 - 350 psig and places QRV-301 in auto

i. Nulls and returns CRV-470 controller to auto

8. Adjusts charging flow as required to maintain PRZ level

9. Places PRZ level control in automatic (if desired)

10. Places QRV-302 in normal (demineralizer) position when letdown temperature is stable.

11. Reset PRZ Heaters to restore pressure control

12. Nulls and returns QRV-251 and PRZ Level Controller back to auto US Refers to Tech Specs (TS) :

• TS 3.3.1, Reactor Trip System (RTS) Instrumentation (Table 3.3.1-1)

• Function 9, Pressurizer Water Level - High.

• Condition A - Refer to Table

• Condition D - 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to trip bistables

• TS 3.3.3 Post Accident Monitoring (Minimum channels are met) - N/A.

• TS 3.3.4 Remote Shutdown Instrumentation Condition A - 30 Days to restore to operable US Initiates actions to trip bistables associated with NLP-151 PZR Level Failure per Attachment A of 1-OHP-4022-013-010.

Cook Plant Unit 1 & 2 Page 5 of 20

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Crews 1, 4, & 5 Scenario No.: NRC2012-02 Event No.: 4 Event

Description:

West RHR Pump Startup Suction Strainer Flange Leak Time Position Applicant's Actions or Behavior BOP/RO Recognizes and reports RHR Room Sump annunciator on Panel 106 indicative of Leakage (Drop 39).

BOP Dispatch Operator to check for sump blockage or RHR leakage.

BOP Isolate W RHR pump to stop leakage

• Place West RHR pump in PTL

• Close IMO-320 West RHR Pump Suction.

BOP May verify RWST level still within Technical Specifications (TS) Limits.

BOP Place Clearance (OOS) tags on RHR Pump, Suction, & Miniflow SRO Declares 1W RHR Pump inoperable and refers to:

• TS 3.5.2, ECCS - Operating Condition A - Restore RHR Train in 72 Hours Cook Plant Unit 1 & 2 Page 6 of 20

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Crews 1, 4, & 5 Scenario No.: NRC2012-02 Event No.:5 Event

Description:

Pressurizer PORV (NRV-153) Fails Open Time Position Applicant's Actions or Behavior RO Recognizes and reports annunciators on Panel #108 (Drop 23, 24, indicative of a pressurizer PORV opening. (Drops 8, 29, 34, 39, &

45 may also alarm).

US/RO Isolates failed open PORV per 1-OHP-4024-108, Drop 23:

• Attempts to manually close NRV-153, PRZ PORV.

• Manually closes NMO-153, NRV-153 PRZ PORV Block Valve.

US Declares NRV-153 inoperable, refers to Tech Spec 3.4.11 PORVs and complies with Condition B:

• Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> close and remove power from the PORV block valve (NMO-153).

May enter Technical Specification 3.4.1 RCS Pressure, Temperature, and Flow DNB Limits if Pressure lowers to <2050 psig. (Restore within 2 Hours)

Note: Crew may refer to 1-OHP-4022-002-009, Leaking Pressurizer Power Operated Relief Valve. Continue with next event while crew performs actions of this procedure.

RO Monitors PRZ pressure control system and ensures pressure returns to normal conditions (~2085 psig).

Cook Plant Unit 1 & 2 Page 7 of 20

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Crews 1, 4, & 5 Scenario No.: NRC2012-02 Event No.: 6 Event

Description:

SG 2 Feedwater Flow Transmitter (FFC-220) Fails HIGH Time Position Applicant's Actions or Behavior BOP Recognizes and reports annunciators on Ann. Panel 113 indicative of the Feed Flow Transmitter failure (Drops 33 and 43).

BOP Performs the following:

• Verifies FRV-220, SG 2 MFW Reg. Valve controller in manual.

• Raises controller output and restores SG 2 level to program.

US Enters and directs actions of 1-OHP-4022-013-015, Feedwater Flow Instrument Malfunction procedure.

BOP Performs the following actions as directed:

1. Restores SG 2 level using manual control of FRV-220.

2. Reports FFC-220 has failed.

3. Places FS-520-C selector switch in channel 2 position.

4. Nulls and returns FRV-220 controller to auto.

US Refers to Tech Specs (TS) and Tech Requirements Manual (TRM):

• TS 3.3.1 Reactor Trip System (RTS) Instrumentation (Table 3.3.1-1) o Function 15, SG Water Level - Low (per SG), Coincident with Steam Flow/Feedwater Flow Mismatch (per SG).

o Condition A - Refer to Table o Condition D - 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to trip bistables

• TRM 8.3.6 ATWS Mitigation System Actuation Circuitry (AMSAC) - Not applicable

• TRM 8.7.14 Leading Edge Flow Meter (Mode 1 > 3250 applicability) -

Not applicable US Initiates actions to trip bistables associated with FFC-220 FW Flow Failure per Attachment B-1 of 1-OHP-4022-013-015.

Cook Plant Unit 1 & 2 Page 8 of 20

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Crews 1, 4, & 5 Scenario No.: NRC2012-02 Event No.: 7/8/9 Event

Description:

Large Break LOCA inside Containment Loss of Recirc Sump Capability Containment Isolation Phase A - Auto & Manual Failure Time Position Applicant's Actions or Behavior RO/US Acknowledge Ann. 122, Drop 83 ICE CONDENSER DOORS OPEN.

Determines that a loss of reactor coolant is occurring based on the following:

• Pressurizer and VCT level change.

• Charging and letdown flow mismatch.

• Containment radiation monitoring trend.

• Containment pressure rise.

• Containment sump level rise.

US Directs RO/BOP to verify/trip the reactor and perform the immediate actions of E-0, Reactor Trip or Safety Injection.

RO/BOP Performs the immediate actions of E-0:

1. Checks reactor trip.

2. Checks turbine trip.

3. Checks power to AC emergency buses.

4. Checks safety injection status.

US Ensures immediate actions of E-0 are completed US Directs subsequent actions of E-0.

RO/BOP Reviews E-0 Foldout Page Criteria.

US Announces RX Trip over Executone Cook Plant Unit 1 & 2 Page 9 of 20

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Crews 1, 4, & 5 Scenario No.: NRC2012-02 Event No.: 7/8/9 Event

Description:

Large Break LOCA inside Containment Loss of Recirc Sump Capability Containment Isolation Phase A - Auto & Manual Failure Time Position Applicant's Actions or Behavior CREW Determines that Containment Pressure requires Steamline Isolation, Phase B Isolation, and CTS Actuation.

• Verifies Steamlines Isolated.

• Verifies CTS Actuation.

• Aligns Lower Cont. Vent Fans.

CREW Manually stops all Reactor Coolant Pumps (RCPs) due to Phase B Isolation and/or RCS pressure lowering below 1300 psig.

BOP Manually controls AFW flow to maintain SG narrow range levels 14% - 50%

once one SG narrow range level is > 14%.

RO Reports that 1W RHR Pump is NOT running - 1W RHR Pump off due to previous failure.

RO/BOP Performs manual actions of E-0 Attachment A (for Containment Phase A).

• Align CCW Valves - Close CCR -455, 456, 462 valves

• Place DIS in Service - Turn on Igniters

• Stop one Control Room Pressurization fan.

• Reset Bypass switches for PACHMS Crew Manually Actuates Containment Isolation - Phase A.

Critical Task -OR-

1. 1 Manually align valves to establish at least one train of isolation

• QCM-250

• BD sample Valves Closed.

CREW Completes all actions of E-0 through step 19 (Check If RCS Is Intact).

US Announces transition to E-1, Loss Of Reactor Or Secondary Coolant (at step 19 of E-0).

US Identifies Red Path on Intergrity.

Enter 1-OHP-4023-FR-P.1, Response To Imminent Pressurized Thermal Shock Condition, and then exits once RHR flow is verified.

Note: The Crew may transition to 1-OHP-4023-ES-1.3, Transfer to COLD Leg Recirculation if the RWST is low enough prior to the E-1 transition point (See Page 13 For actions).

Cook Plant Unit 1 & 2 Page 10 of 20

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Crews 1, 4, & 5 Scenario No.: NRC2012-02 Event No.: 7/8/9 Event

Description:

Large Break LOCA inside Containment Loss of Recirc Sump Capability Containment Isolation Phase A - Auto & Manual Failure Time Position Applicant's Actions or Behavior RO/BOP Reviews E-1 Foldout Page Criteria.

US Directs actions of E-1, Loss Of Reactor Or Secondary Coolant.

BOP Maintains SG narrow range levels 20% - 50%.

BOP Performs the following:

Resets Containment Isolation Phase A.

Notifies Chemistry to sample SGs for activity.

US Checks if SI Termination Criteria is MET:

RCS Subcooling >40°F.

3 Secondary Heat Sink (AFW Flow >240x10 or SG >14% [28%

ADVERSE]).

RCS Pressure rising or stable.

Pressurizer Level >21% [25%ADVERSE].

Crew Secures CTS Injection - May be secured in ES-1.3 or ECA-1.1:

Critical Task

• Resets CTS Actuations and Phase B.

1. 2

• Stops CTS Pumps.

• Closes CTS Pump Discharge Valves.

RO/BOP Performs the following as directed:

1. Resets both trains of Safety Injection.

2. Stops running Emergency Diesel Generators (EDG).

3. Dispatches operator to secure EDG jacket water pumps.

US/RO Determines that COLD Leg Recirculation Capability has been lost:

• ICM-305, Recirc Sump to East RHR/CTS pumps - NOT Lit.

• W RHR Pump OOS and Isolated.

US Announces transition to ECA-1.1, Loss of Emergency Coolant Recirculation (at step 11 RNO of E-1).

ES-1.3, Transfer To Cold Leg Recirculation.

actions on Page 13.

Cook Plant Unit 1 & 2 Page 11 of 20

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Crews 1, 4, & 5 Scenario No.: NRC2012-02 Event No.: 7/8/9 Event

Description:

Large Break LOCA inside Containment Loss of Recirc Sump Capability Containment Isolation Phase A - Auto & Manual Failure Time Position Applicant's Actions or Behavior Applicants actions or behavior associated with ECA-1.1, Loss of Emergency Coolant Recirculation.

RO/BOP Reviews ECA-1.1 Foldout Page Criteria.

US Directs actions of ECA-1.1, Loss of Emergency Coolant Recirculation.

US/RO Dispatch personnel to investigate ICM-305 failure.

US Direct CTS pumps shutdown to conserve RWST level.

Crew Secures CTS Injection - May be secured in E-1 or ES-1.3 Critical Task

• Resets CTS Actuations and Phase B.

1. 2

• Stops CTS Pumps.

• Closes CTS Pump Discharge Valves.

US Directs Operators to begin make-up to RWST.

Note: The following steps of ECA-1.1 will be performed depending on when ICM-305 is restored.

BOP Maintains SG narrow range levels 20% - 50% per ECA-1.1.

US Directs actions to begin Cooldown per ECA-1.1.

RO/BOP Receives report and verifies that ICM-305, Recirc Sump to East RHR/CTS pumps - LIT, power has been restored.

US Announces transition to procedure and step previously in effect.

Cook Plant Unit 1 & 2 Page 12 of 20

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Crews 1, 4, & 5 Scenario No.: NRC2012-02 Event No.: 7/8/9 Event

Description:

Large Break LOCA inside Containment Loss of Recirc Sump Capability Containment Isolation Phase A - Auto & Manual Failure Time Position Applicant's Actions or Behavior Applicants actions or behavior associated with ES-1.3, Transfer To Cold Leg Recirculation.

US Announces transition to ES-1.3, Transfer To Cold Leg Recirculation when RWST level < 30% per:

• E-0, Foldout Page, Criteria 3

• E-1, Foldout Page, Criteria 5

• E-1, Step 13 US Directs actions of ES-1.3, Transfer To Cold Leg Recirculation.

RO/BOP Resets both trains of Safety Injection.

RO/BOP Checks CCW return flow on each RHR Hx at 3000-3500 gpm.

(may only perform for the East CCW HX)

RO/BOP Checks the following prior to switching over to cold leg recirc:

• RWST level < 20%

• Cntmt water level > MIN RECIRC LEVEL US/RO Directs/Performs switchover as follows:

NOTE: If RWST level < 9% then stop CCPs and SI pumps.

1. Stops and locks out East CTS pump

2. Stops and locks out East RHR pump

3. Checks East CTS and East RHR pumps stopped

4. Initiates valve closure:

• IMO-310, East RHR pump suction

• IMO-215, East CTS pump suction from RWST

5. Stops and locks out West CTS pump

6. Stops and locks out West RHR pump (OOS)

7. Checks West CTS and West RHR pumps stopped

8. Initiates valve closure:

• IMO-320, West RHR pump suction

• IMO-225, West CTS pump suction from RWST Cook Plant Unit 1 & 2 Page 13 of 20

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Crews 1, 4, & 5 Scenario No.: NRC2012-02 Event No.: 7/8/9 Event

Description:

Large Break LOCA inside Containment Loss of Recirc Sump Capability Containment Isolation Phase A - Auto & Manual Failure Time Position Applicant's Actions or Behavior Actions if ECA-1.1 has NOT yet been performed.

ES-1.3 Completion Actions Continued Below US/RO Determines that COLD Leg Recirculation Capability has been lost:

• ICM-305, Recirc Sump to East RHR/CTS pumps - NOT Lit.

• W RHR Pump OOS and Isolated.

US Announces transition to ECA-1.1, Loss of Emergency Coolant Recirculation ECA-1.1, Loss of Emergency Coolant Recirculation Actions on Page 12 if not previously performed.

ES-1.3, Transfer To Cold Leg Recirculation COMPLETION following performance of ECA-1.1 US/RO Restore Control Power to ICM-305 Open ICM-305, Recirc Sump to East RHR/CTS pumps US/RO Start East RHR Pump TERMINATE SCENARIO Cook Plant Unit 1 & 2 Page 14 of 20

CRITICAL TASK

SUMMARY

(NRC2012-02)

Task Elements Results

1. 1 Cueing: SAT / UNSAT

• Phase A Actuated Status PPC Screen - STANDBY Manually Initiate * (Train A AND Train B) (Not Actuated nor Complete)

Phase A Isolation

• Phase A Valves Closed Lights - NOT LIT

• Check Containment Vent and Phase A - Actuated on Both trains (E-0 Attachment A).

Performance Indicators:

• Manually Actuate at least one train of Phase A - OR -

• Manually align valves to establish at least one train of Isolation.

• Must be performed while in E-0 before transitioning (before completion of Attachment A).

Performance Feedback:

• Phase A Actuated Status PPC Screen -COMPLETED (Train A or Train B)

1. 2 Cueing: SAT / UNSAT

• *RWST Level Lowering Secure RWST Outflow * *RHR Room Sump Annunciator Panel 106 Drop 39 (Leakage and CTS

• ECA-1.1 flow)

Performance Indicators:

• *West RHR Suction Flowpath Isolated - IMO-320

• Manually stop all CTS pumps directed

• Manually Close CTS pump discharge valves when directed by procedures

• CTS must be stopped prior to RWST lowering below 11%

Performance Feedback:

• CTS ammeters - zero current

• CTS discharge flow meters - 0 gpm

• Rate of RWST level loss - lowering

• =May be performed prior to Trip Cook Plant Unit 1 & 2 Page 15 of 20

SIMULATOR INSTRUCTIONS (NRC2012-02)

Setup:

1. Reset to IC-115

2. Raise Accumulator #3 Pressure until High Pressure alarm is received. Set csms1gas(40) to 1180. Verify containment N2 header is pressurized by cycling GCR-314 open for 30 seconds.

3. Reset control rods and check group step counters.

4. Place Master Annunciator Silence pushbutton lockout ring in LOCKOUT position.

5. Advance chart recorder paper & clear chart recorder memory.

6. Go to RUN and acknowledge/clear alarms.

7. Activate the following pre-load malfunctions:

• RP13A (Failure of Train A Phase A Auto Actuation). U1_RP13A

• RP13B (Failure of Train B Phase A Auto Actuation). U1_RP13B

• RP14A (Failure of Train A Phase A Manual Actuation). U1_RP14A

• Assign RX Trip to Trigger 1 : U1_ReactorTripBreaker on TRG 1 o IMF 101ICM305 on Trg 1 (open ICM 305 breaker on trip)

U1_101ICM305 Cook Plant Unit 1 & 2 Page 16 of 20

SIMULATOR INSTRUCTIONS (NRC2012-02)

Scenario Events:

EVENT #1 Report as required:

• No personnel are in Unit 1 Lower Containment.

• You have the concurrence of the Safety Department Supervisor to lower Accumulator pressure without purge in service.

EVENT #2 No Additional Actions EVENT #3 After appropriate power change, insert ICF U1_NLP151, to 0% over 3 Seconds, Pressurizer Level Channel 1 (NLP-151) fails LOW. U1_NLP151 If directed to trip bistables for NLP-151 use:

• Override ZLOSTMC2[6] to ON to simulate opening cabinet door ZLOSTMC2_U1[6]

• (Override Lights/Relays - RX Flux panel)

Remote Bistable RPR041 U1_RPR041 LS-459A

• Override ZLOSTMC2[1] to ON to simulate lifting Test Rack ZLOSTMC2_U1[1]

• Delete Override ZLOSTMC2[6] to simulate closing cabinet Door ZLOSTMC2_U1[6]

Cook Plant Unit 1 & 2 Page 17 of 20

SIMULATOR INSTRUCTIONS (NRC2012-02)

EVENT #4 After the crew responds to the pressurizer level channel failure, insert IMF U1_RH09B, final value 5 (West RHR Suction Leak) while the RO is restoring letdown (So BOP Responds). U1_RH09B When dispatched to investigate RHR pump leakage, report that leakage is from startup suction strainer flange that appears to be stripped (will not tighten). Report that the pump must be isolated before this can be repaired. (If asked, leakage approximately 5-10 gpm).

If requested to investigate CAS Panel Alarm, report back that Annunciator #124, Drop 51, AUX BLDG SUMP LEVEL HIGH alarm is in.

If required, Prompt crew as Shift Manager for crew to make a decision on the course of action. (note pump needs to be isolated with Clearance for remainder of scenario)

When Dispatched to place OOS (Clearance) on RHR use the following to isolate the W RHR Pump:

• Rack out West RHR Pump Breaker U1_RHR17 RO. U1_RHR17

• RHR Pump From Recirc Sump RH104W U1_RHR07. U1_RHR07

• RHR Pump Manual Discharge RH113W U1_RHR21. U1_RHR21

• RHR Pump Recirc 1-IMO-322 (power). U1_101IMO322 EVENT #5 After the crew responds to the RHR leak, insert IMF RC17C, final value 50 (PRZ PORV NRV153 fails OPEN). U1_RC17C If contacted to remove power from 1-NMO-153, then activate global malfunction (YG) 101NMO153 for breaker 1-EZC-D-3D. U1_101NMO153 Cook Plant Unit 1 & 2 Page 18 of 20

SIMULATOR INSTRUCTIONS (NRC2012-02)

EVENT #6 After the crew responds to the PRZ PORV leak, insert ICF U1_FFC220, Final Value 4.0 E6 over 10 seconds to fail SG 2 Feed Flow Channel (FFC-220) HIGH.

U1_FFC220 If directed to trip bistables for FFC-220 use:

• Override ZLOSTMC2[6] to ON to simulate opening cabinet door open.

ZLOSTMC2_U1[6]

• (Override Lights/Relays - FW panel):

Remote Bistable RPR023 U1_RPR023 FS-520A RPR024 U1_RPR024 FS-520B

• Override ZLOSTMC2[1] to ON to simulate lifting Test Rack.

ZLOSTMC2_U1[1]

• Delete Override ZLOSTMC2[6] to simulate closing cabinet door.

ZLOSTMC2_U1[6]

Cook Plant Unit 1 & 2 Page 19 of 20

SIMULATOR INSTRUCTIONS (NRC2012-02)

EVENTS #7/8/9 After the crew responds to the Feed Flow Ch failure, insert IMF RC01D to 20 over 5 minutes (LB LOCA). U1_RC01D (Note: Auto Phase A actuation is already inserted, ICM-305 Will lose power when RX is tripped due to the wrong breaker being de-energized for RHR OOS)

When dispatched to investigate the failure/loss of power to ICM-305, report back that the breaker is off and OOS (Clearance) due to an incorrect tagging error. Delay report back if CTS pumps are to be shutdown in ECA-1.1.

Delete 101ICM305 to restore power to ICM-305 (Breaker 1-ABV-D-1B).

U1_101ICM305 Local actions after entry into E-0:

• Locally stop U1 Ice Condenser AHUs MRF CHR01 to OFF.

U1_CHR01

• Aux Tour will monitor Spent Fuel Pool Level and Temperatures

• Place PACHMAS in service - MRF CHR02 or 03 with 10 min delay.

U1_CHR02 OR U1_CHR03 (both have 10 minute delay built in.)

• U2 has aligned CR vent for U1 SI, Fan 2-HV-AS-2 is running.

If directed to secure EDG jacket water pumps select OFF then AUTO:

Remote OFF AUTO EGR 03A U1_EGR03A U1_EGR03A EGR 03B U1_EGR03B U1_EGR03B EGR 04A U1_EGR04A U1_EGR04A EGR 04B U1_EGR04B U1_EGR04B Cook Plant Unit 1 & 2 Page 20 of 20

Appendix D Scenario Outline Form ES-D-1 Facility: Cook Plant Unit 1 & Unit 2 Scenario No.: NRC2012-03 Op-Test No.: Crews 2, 4, & 5 Examiners: _________________ Operators:___________________

Initial Conditions: IC-113, 80% pwr, 841 ppm Boron, 10 GWD, 554°F Tavg, CBD @ 197 steps, 909 MW Turnover: Swap TACW Pumps, West CCP is OOS for Oil Change this shift. West CCP has been OOS for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Event Malf. No. Event Event No. Type* Description 1 N-BOP Swap Turbine Aux Cooling Water (TACW) Pumps.

2 NTP240 @ 620 I-RO RCS Cold Leg Temperature Instrument (NTP-240) Fails HIGH.

TS 3 MFC131 @ 4E6 I-BOP #3 SG Steam Flow Transmitter (MFC-131) Fails HIGH.

over 20 sec TS 4

101BAP1 C-RO Boric Acid Pump Fails.

TS 5 R-RO Lower Reactor Power and Turbine Load (Optional).

6 FW05A C-BOP East Main Feed Pump Trip.

7 FW05B M West Main Feed Pump Trip.

8 MS01C @ 20 M Steam Line Break Inside Containment (#3 SG).

2 min Ramp 9a RP16B C-RO West CTS (Train B) - Fails to Actuate (AUTO/MANUAL).

RP17B 9b RP19J C-RO RPS Relay K626-X3 Failure (East CTS Pump Fails to Start).

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Cook Plant Unit 1 & Unit 2 Page 1 of 21

Event Summary (NRC2012-03)

The Crew is directed to start West TACW pump and stop East TACW Pump.

The RCS Loop 4 Cold Leg Temperature instrument (NTP-240) fails HIGH. This will result in the AUTO insertion of control rods and a lower trip setpoint value for OPT and OTT. The RO will be required to take manual control of rods to stop insertion. The Crew will be required to implement AOP actions to stabilize the plant and trip bistables.

After the crew has addressed the RCS temperature instrument, the #3 SG Steam Flow instrument (MFC-131) fails HIGH. This will result in the opening of #3 SG FWRV (FRV-230) to raise feedwater flow. The BOP will be required to take manual control and regulate FRV-230. The Crew will be required to implement AOP actions to stabilize the plant and trip bistables.

The running Boric Acid Pump Breaker will trip. This results in a temporary loss of VCT make-up capability.

The RO will be required to take manual actions to align the standby Boric Acid Pump and start it in slow speed.

Next a rapid power reduction is performed based on a report of an Oil leak on the East Main feed Pump.

(Optional if reactivity change is required - note next event also involves a reactivity change which may be combined with this reactivity change)

A trip of the East Main Feed Pump will result in a rapid power reduction to less than 60% (if not already performed.) The RO will be required to control reactivity while the BOP monitors SG levels.

The main event will involve a trip of the remaining MFW pump. A Steam Line Break will cause SG #3 to blow down inside Containment. The BOP will be required to isolate the main steam lines. A SSPS failure results in failure of Train B (West) CTS and a failure of the K626-X3 relay which prevents the auto start of the East CTS pump. The crew will perform the actions of E-0 to verify the SI actions and then transition to E-2. The scenario will terminate when the crew has completed isolation of the faulted SG in E-2.

Critical Tasks Actuate Containment Spray Isolate the Faulted Steam Generator Procedures E-0, Reactor Trip or Safety Injection E-2, Faulted Steam Generator Isolation Cook Plant Unit 1 & Unit 2 Page 2 of 21

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Crews 2, 4 & 5 Scenario No.: NRC2012-03 Event No.: 1 Event

Description:

Swap TACW Pumps (Start West and Stop East)

Time Position Applicant's Actions or Behavior US Directs actions of 1-OHP-4021-058-002, Operation of TACW System.

BOP Performs the following to swap TACW pumps as directed:

• Start Standby (West) TACW Pump.

• Stop running (East) TACW Pump.

• Place East TACW Pump in AUTO.

Cook Plant Unit 1 & Unit 2 Page 3 of 21

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Crews 2, 4 & 5 Scenario No.: NRC2012-03 Event No.: 2 Event

Description:

Loop 4 RCS Cold Leg Temperature Transmitter (NTP-240) Fails High Time Position Applicant's Actions or Behavior RO Recognizes and reports annunciators on Ann. Panel #111 which are indicative of an RCS RTD failure.

Note: Based on the response time of the crew, an auto makeup may occur for the VCT due to letdown / charging mismatch due to erroneous auctioneered high Tavg (which feeds program PRZ level) indication.

RO Places rod control in MANUAL after verifying no turbine runback in progress.

US Enters and directs actions of 1-OHP-4022-012-003, Continuous Control Bank Movement procedure, if rods moved.

RO If 1-OHP-4022-012-003 is entered, then performs the following as directed:

1. Checks for no turbine runback.

2. Ensures control rods are in MANUAL with no rod motion.

3. Checks rod position above low-low Rod Insertion Limit (RIL).

Note: Delta-T failure may affect RIL Setpoint - Must use Core Operating Limits Report (COLR) or manually calculate.

4. Checks Axial Flux Difference (AFD) within target band.

5. Initiates restoration of equilibrium conditions using either:

• Control rod movement.

• Turbine load adjustment.

6. Identifies failed RTD channel.

US Enters and directs actions of 1-OHP-4022-013-007, RCS RTD Instrument Malfunction procedure.

RO 1. Ensures control rods are in MANUAL.

2. Reports Loop 4 as failed RCS temperature channel and aligns the following switches:

• Tavg defeat switch to Loop 4 position.

• T defeat switch to Loop 4 position.

• T/OPT/OTT recorder switch to Loop 1, 2, or 3.

EVENT NO. 2 CONTINUED ON NEXT PAGE Cook Plant Unit 1 & Unit 2 Page 4 of 21

Op-Test No.: Crews 2, 4 & 5 Scenario No.: NRC2012-03 Event No.: 2 Event

Description:

Loop 4 RCS Cold Leg Temperature Transmitter (NTP-240) Fails High Time Position Applicant's Actions or Behavior US Refers to the following Tech Specs (TS):

• TS 3.3.1, Reactor Trip System (RTS) Instrumentation

• Condition A - Refer to Table 3.3.1-1 o Function 6, Overtemperature T. Condition D - Trip Bistables in 6 Hours o Function 7, Overpower T. Condition D - Trip Bistables in 6 Hours

• TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS)

Instrumentation

• Condition A - Refer to Table 3.3.2-1 o Function 4e, Steam Line Isolation - High Steam Flow in Two Steam Lines (per steam line), Coincident with Tavg - Low Low Condition D -

Trip Bistables in 6 Hours o Function 8c, ESFAS Interlocks - Tavg - Low Low, P-12. Condition D -

Trip Bistables in 6 Hours May enter the following TS if Pressure lowers to <2050 psig during the transient:

• TS 3.4.1, RCS Pressure, Temperature, and Flow DNB Limits.

• Condition A - Restore within 2 Hours May Refer to Technical Requirements Manual (TRM)

• TRM 8.7.14 LEFM Thermal Power - Not Applicable @ 80%

US Initiates actions to trip bistables associated with RCS loop 4 RTD failure per Attachment D of 1-OHP-4022-013-007.

Cook Plant Unit 1 & Unit 2 Page 5 of 21

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Crews 2, 4 & 5 Scenario No.: NRC2012-03 Event No.: 3 Event

Description:

SG #3 Main Steam Flow Transmitter (MFC-131) Fails High Time Position Applicant's Actions or Behavior BOP Recognizes and reports annunciators on Panel #114 (Drops 11, 13, and 2) which are indicative of a steam flow instrument failure.

BOP Places FRV-230, SG 3 MFW Reg. Valve controller to MANUAL, lowers controller output and restores SG 3 level to program.

US Enters and directs actions of 1-OHP-4022-013-014, Steam Flow Instrument Malfunction procedure.

BOP Performs the following actions as directed:

1. Restores SG 3 level using MANUAL control of FRV-230.

2. Places MFP P controller in MANUAL and maintains pressure.

3. Reports MFC-131 has failed high.

4. Places 1-FS-532C selector switch in channel 2 position.

5. Nulls and returns FRV-230 controller to AUTO.

6. Returns MFP P controller to AUTO.

US Directs actions to trip bistables associated with 1-MFC-131 Steam Flow Failure per Attachment C-1 of 1-OHP-4022-013-014.

US Refers to the following Tech Specs (TS):

TS 3.3.1 RTS Instrumentation (Table 3.3.1-1)

Condition A - Refer to Table Function 15 Condition D - Trip Bistables in 6 Hours TS 3.3.2 ESFAS Instrumentation (Table 3.3.2-1)

Condition A - Refer to Table Function 4e Condition D - Trip Bistables in 6 Hours US Initiates actions to trip bistables associated with MFC-131 failure per Attachment C-1 of 1-OHP-4022-013-014.

Cook Plant Unit 1 & Unit 2 Page 6 of 21

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Crews 2, 4 & 5 Scenario No.: NRC2012-03 Event No.:4 Event

Description:

Boric Acid Pump Trips Time Position Applicant's Actions or Behavior RO Recognizes and reports annunciator on Panel #109 (Drops 35) which is indicative of a #1 boric acid transfer (BAT) pump trip.

RO Dispatches an operator to investigate cause of pump trip.

May dispatch an operator to Unit 1 Hot Shutdown Panel (HSDP) to check BAT pump #1 transfer switch position.

RO Ensures #2 BAT pump is aligned to the N Boric Acid Storage Tank and starts the #2 BAT pump per 12-OHP-4021-005-001.

US Refers to the following Tech Requirement Manual (TRM) Item:

TRM 8.1.1 Boration System - Operating - Restore within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Cook Plant Unit 1 & Unit 2 Page 7 of 21

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Crews 2, 4 & 5 Scenario No.: NRC2012-03 Event No.: 5 Event

Description:

Reduce Turbine Load / Reduce Reactor Power Time Position Applicant's Actions or Behavior Note: If desired the next event (MFW Pump Trip) may be initiated prior to commencing the Rapid Power reduction.

CREW Determines that a Rapid Power reduction is required based on the East MFW Pump Oil Leak.

Load Reduction per 1-OHP-4022-001-006, Rapid Power Reduction Response procedure.

US Directs RO to commence Rapid Power Reduction in accordance with 1-OHP 4022-001-006.

RO Performs (Att. D) NORMAL BORATION:

• Verify charging is > 75 gpm

• CLOSE 1-QMO-225, EAST CCP Mini-Flow (CCP ELO)

• Place RC Makeup Blend control switch in STOP.

• Place RC Makeup Blend Control Mode switch in BORATE.

• Adjust BA Controller/Totalizer to the desired flow rate and amount.

• Place RC Makeup Blend control switch in START.

• May take QRV-303 to MANUAL/OPEN (as required) to maintain VCT level and pressure.

1-OHP 4022-001-006 Attachment D Table

-OR-Continued Next Page Cook Plant Unit 1 & Unit 2 Page 8 of 21

Op-Test No.: Crews 2, 4 & 5 Scenario No.: NRC2012-03 Event No.: 5 Event

Description:

Reduce Turbine Load / Reduce Reactor Power Time Position Applicant's Actions or Behavior Performs (Att. E) EMERGENCY BORATION:

• Verify charging is > 75 gpm.

• CLOSE 1-QMO-225, EAST CCP Mini-Flow (CCP ELO)

• Place #2 BAT pump to FAST speed.

• Open QMO-410, Emergency Boration To CHG Pump Suction valve.

• Verify QFI-410, Emergency Boration Flow.

• May take QRV-303 to MANUAL/OPEN (as required) to maintain VCT level and pressure.

1-OHP 4022-001-006 Attachment E Table RO Commences power reduction:

• Verify all PRZ backup heaters ON.

• Lowers turbine load using HMI.

• Ensures control rods in AUTO.

BOP Acts as peer checker for RO and verifies appropriate reactivity feedback.

Cook Plant Unit 1 & Unit 2 Page 9 of 21

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Crews 2, 4 & 5 Scenario No.: NRC2012-03 Event No.: 6 Event

Description:

East Main Feed Pump Trip Time Position Applicant's Actions or Behavior BOP Recognizes indication of MFP trip and reports Ann. Panel #115 (Drop 1).

US Directs immediate operator actions per 1-OHP-4022-055-001, Loss of One MFP.

RO/BOP Perform immediate actions of 1-OHP-4022-055-001:

1. Verify Turbine Load is automatically reduced to ~ 625Mw.

2. Check rods in AUTO OR operate MANUALLY due to previous failure.

3. Close East MFW Pump ELOs (FRV-251 & 252).

4. Start Standby Hotwell & Condensate Booster Pumps (if required).

5. Start AFW pumps (if required).

6. Adjust West FW Pump speed as required.

US Direct subsequent operator actions per 1-OHP-4022-055-001(as required).

RO Perform the following actions:

• Ensures boration.

• Restore AFD to required band.

• Reset Steam Dump Load Rejection.

BOP Perform the following actions:

• Checks feedwater flow restores SG levels.

• Returns W MFP to DP control per attachment A

• Lowers FW Pump Speed If Required and selects Manual DP

• Lowers Manual DP target until Auto Transfer Button Available -

Selects auto

• Stop AFW pumps and aligns for standby.

• Complete E MFW pump shutdown.

• Align Condensate system for current plant conditions.

Note: Crew may enter TS 3.4.1 for RCS DNB if Pressurizer Pressure lowers to < 2050 psig.

(Condition A - Restore in 2 Hours)

Cook Plant Unit 1 & Unit 2 Page 10 of 21

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Crews 2, 4 & 5 Scenario No.: NRC2012-03 Event No.: 7/8/9 Event

Description:

West Main Feed Pump Trip Steam Line Break - I.C.

West CTS Pump Fails to Start (Auto or Manual)

RPS Relay Failure - East CTS Fails to Auto Start Time Position Applicant's Actions or Behavior RO/US Determines that a loss of feedwater is occurring based on the following:

• Both MFW pumps tripped.

• SG level change.

• Feedwater & steam flow mismatch.

US Directs RO/BOP to manually trip the reactor and perform the immediate actions of 1-OHP-4023-E-0 (E-0), Reactor Trip or Safety Injection.

RO/BOP Performs the immediate actions of E-0:

1. Checks reactor trip.

2. Checks turbine trip.

3. Checks power to AC emergency buses.

4. Checks safety injection status.

RO/BOP Report immediate actions complete and review foldout pages.

US Announces RX Trip over Executone US Ensures immediate actions of E-0 are completed.

US Directs Actions of E-0 to verify equipment is aligned as required and determine if SI is valid.

CREW Determines that Steam Line Pressures are lowering from steam line break.

Cook Plant Unit 1 & Unit 2 Page 11 of 21

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Crews 2, 4 & 5 Scenario No.: NRC2012-03 Event No.: 7/8/9 Event

Description:

West Main Feed Pump Trip Steam Line Break - I.C.

West CTS Pump Fails to Start (Auto or Manual)

RPS Relay Failure - East CTS Fails to Auto Start Time Position Applicant's Actions or Behavior CREW Verify all Main Steam Isolation (SG Stop) valves are closed CREW Manually aligns/starts ONE train of CNTMT Spray:

• Verifies CTS Pump Discharge Valves OPEN.

Critical Task #1

• Verifies Spray Additive Tank Outlet Valves OPEN.

• STARTS ONE Containment Spray Pump.

US Identifies that Containment Pressure is > 2.8 psig and directs actions to Stop RCPs and align containment systems as required per Step 6 RNO of E-0.

RO Stops all Reactor Coolant Pumps.

RO/BOP

• Places lower Cntmt vent unit fans in OFF.

• Places CRDM fans in STOP.

RO/BOP Performs manual actions of E-0 Attachment A as directed by US.

• Place DIS in Service - Turn on Igniters

• Stop one Control Room Pressurization fan.

• Reset Bypass switches for PACHMS

• Align CCW Valves - Close CCR -454, 452, 459 valves Cook Plant Unit 1 & Unit 2 Page 12 of 21

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Crews 2, 4 & 5 Scenario No.: NRC2012-03 Event No.: 7/8/9 Event

Description:

West Main Feed Pump Trip Steam Line Break - I.C.

West CTS Pump Fails to Start (Auto or Manual)

RPS Relay Failure - East CTS Fails to Auto Start Time Position Applicant's Actions or Behavior RO/BOP Manually controls AFW flow to maintain SG narrow range levels 14% - 50%

once one SG narrow range level is greater than 14%.

RO/BOP

• Verifies FW isolation.

• Isolates RCS Cooldown Paths.

CREW Completes all actions of E-0 through step 17 (Check If SG Secondary Pressure Boundaries Are Intact).

If Containment pressure is > 2.8 psig a transition to FR-Z.1 may be made.

See Page 15 for Z.1 Actions US Announces transition to E-2, Faulted Steam Generator Isolation, for a SG depressurized (at step 17 of E-0).

US Directs actions of 1-OHP-4023-E-2 (E-2), Faulted Steam Generator Isolation.

BOP Checks closed - SGSV Dump valves.

CREW Identifies #3 SG as FAULTED.

(If not previously performed in Z.1)

CREW Isolate the faulted SG:

• FMO-231, TDAFP discharge Critical

• FMO-232, MDAFP discharge Task #2

• MCM-231, TDAFP steam supply NOTE: The following should be checked closed (not part of Critical Task -

Already Closed):

• FRV-230, feedwater reg. valve

• FMO-203, feedwater isolation valve

• MRV-230, SG Stop Valve

• MRV-233, PORV

• DCR-330, Blowdown valve

• DCR-303, Blowdown sample valve Cook Plant Unit 1 & Unit 2 Page 13 of 21

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Crews 2, 4 & 5 Scenario No.: NRC2012-03 Event No.: 7/8/9 Event

Description:

West Main Feed Pump Trip Steam Line Break - I.C.

West CTS Pump Fails to Start (Auto or Manual)

RPS Relay Failure - East CTS Fails to Auto Start Time Position Applicant's Actions or Behavior BOP Closes DRV-407, SG stop valve drain valve RO/BOP Performs the following as directed:

• Resets containment isolation Phase A.

• Directs chemistry to sample all SGs for activity.

CREW Determines that ECCS flow should be reduced.

US Announces transition to 1-OHP-4023-ES-1.1 (ES-1.1) SI Termination (at step 8 of E-2).

US Directs actions of 1-OHP-4023-ES-1.1 (ES-1.1) SI Termination RO/BOP Reset SI RO/BOP Restore IA to Containment

• Close Pressurizer Spray Valves ( Zero Demand)

• Check Air Pressure

• Open IA Isolation Valves RO/BOP Isolate BIT

• Open QMO-225 CCP ELO

• Close BIT Inlet and Outlet Valevs RO/BOP Establish Charging Flow

• Close QRV-200, Charging header pressure control valve

• Open QMO-200 & 201Charging to Regen HX

• Establish minimum charging flow with QRV-251 & QRV-200 TERMINATE SCENARIO Cook Plant Unit 1 & Unit 2 Page 14 of 21

Op-Test No.: Crews 2, 4 & 5 Scenario No.: NRC2012-03 Event No.: 7/8/9 Event

Description:

West Main Feed Pump Trip Steam Line Break - I.C.

West CTS Pump Fails to Start (Auto or Manual)

RPS Relay Failure - East CTS Fails to Auto Start Time Position Applicant's Actions or Behavior FR-Z.1 Actions if Entered Crew Checks Containment Ventilation and Phase A Isolation Complete US Identifies that Containment Pressure is > 2.8 psig and directs actions to Stop RCPs and align containment systems as required per Step 3 of FR-Z.1.

(If not previously performed)

CREW Manually aligns/starts ONE train of CNTMT Spray:

• Verifies CTS Pump Discharge Valves OPEN.

Critical Task #1

• Verifies Spray Additive Tank Outlet Valves OPEN.

• STARTS ONE Containment Spray Pump.

RO Identifies and reports Phase B - Containment Isolation Actuation RO Stops all Reactor Coolant Pumps RO/BOP Places lower Cntmt vent unit fans in OFF Places CRDM fans in STOP Check CEQ Fans Operating Align DIS CREW Verify all Main Steam Isolation (SG Stop) valves are closed BOP Checks closed - SGSV Dump valves CREW Identifies #3 SG as FAULTED.

CREW Isolate the faulted SG:

• FMO-231, TDAFP discharge Critical

• FMO-232, MDAFP discharge Task #2

• MCM-231, TDAFP steam supply NOTE: The following should be checked closed (not part of Critical Task -

Already Closed):

• FRV-230, feedwater reg. valve

• FMO-203, feedwater isolation valve

• MRV-230, SG Stop Valve

• MRV-233, PORV

• DCR-330, Blowdown valve

• DCR-303, Blowdown sample valve US Determines that FR-Z.1 is complete and return to E-1 is required.

Cook Plant Unit 1 & Unit 2 Page 15 of 21

CRITICAL TASK

SUMMARY

(NRC2012-03)

Task Elements Results

1. 1 Cueing: SAT / UNSAT Containment pressure > 2.8 psig:

Actuate

• CNTMT SPRAY ACTUATED alarm.

Containment Spray

• LOWER CNTMT PRESS HI-HI alarm.

• E-0, step 5, Check CTS not required.

Performance Indicators:

• Manually start Train A (EAST) CTS Pump.

• One train of CTS must be in service prior to exceeding a Red Path on the Containment (Z)

CSFST (containment pressure of 12 psig).

Performance Feedback:

• Flow is indicated on at least one train of Containment Spray.

1. 2 Cueing: SAT / UNSAT

• SG AFW Valves - NOT Closed.

Isolate Faulted

• Steam generator pressure lowering.

Steam Generator

• RCS temperature lowering.

Performance Indicators:

• Isolate SG 3 completely. (AFW)

• SG 3 must be isolated before transitioning out of E-2.

Performance Feedback:

• RCS cooldown stops.

• Depressurization of all SGs stop.

• Feedwater flow to affected SG stops.

Cook Plant Unit 1 & Unit 2 Page 16 of 21

SIMULATOR INSTRUCTIONS (NRC2012-03)

Setup:

1. Reset to IC-113.

2. Reset control rods and check group step counters.

3. Place Master Annunciator Silence pushbutton lockout ring in LOCKOUT position.

4. Advance chart recorder paper and clear chart recorder memory.

5. Go to RUN and acknowledge/clear alarms.

6. Place QMO-226 to CLOSE.

7. Activate the following to place W CCP OOS:

• W CCP W CCP Brkr T11A8

• W CCP Lube Oil Pump 1W CCP LO Brkr

• QMO-226 QMO226 Power

8. Place RED clearance tags on the following switches positioned as indicated:

• W CCP - PTL

• W CCP Lube Oil Pump - STOP

• QMO-226 - CLOSED

9. Activate the following (pre-load) malfunctions:

U1_RP19J

• RP19J (RPS Relay K626-X3 failure) (E CTS fails to start).

• RP16B (Failure of Phase B - Auto). U1_RP16B

• RP17B (Failure of Phase B - Manual Train B). U1_RP17B

10. Activate the following (pre-load) malfunctions on Trigger E7:

• FW05B (West MFP trip). U1_FW05B

• MS01C (SG #3 Steam Line Break) @ 20% over 2 Min. U1_MS01C Cook Plant Unit 1 & Unit 2 Page 17 of 21

SIMULATOR INSTRUCTIONS (NRC2012-03)

EVENT #1 If asked, a Starting Party is standing by to observe swap of the TACW Pumps.

EVENT #2 After the TACW Pumps have been swapped, insert ICF NTP240, final value 620 (NTP-240 fails HIGH). U1_NTP240 If directed, to trip bistables for NTP-240 use:

• IOR ZLOSTMC2[9] to ON to simulate opening cabinet door.

ZLOSTMC2_U1[9]

• Override Lights/Relays - RX Flux panel:

Remote Bistable RPR137 U1_RPR137 TS/441G RPR139 U1_RPR139 TS/442D RPR135 U1_RPR135 TS/441C RPR138 U1_RPR138 TS/441H RPR140 U1_RPR140 TS/442G RPR136 U1_RPR136 TS/441D

• IOR ZLOSTMC2[4] to ON to simulate lifting Test Rack.

ZLOSTMC2_U1[4]

• DOR ZLOSTMC2[9] to simulate closing cabinet door.

ZLOSTMC2_U1[9]

Cook Plant Unit 1 & Unit 2 Page 18 of 21

SIMULATOR INSTRUCTIONS (NRC2012-03)

EVENT #3 After crew has stabilized the plant from the RCS temperature failure, insert ICF MFC131, final value 4E6 ramped over 20 seconds (MFC-131 fails HIGH).

U1_MFC131 If directed, to trip bistables for MFC-131 use:

• IOV ZLOSTMC2[6] to ON to simulate opening cabinet door.

ZLOSTMC2_U1[6]

• Override Lights/Relays - RX Flux panel):

Remote Bistable RPR033 U1_RPR033 FS/532B RPR029 U1_RPR029 FS/530A RPR030 U1_RPR030 FS/530B

• IOV ZLOSTMC2[1] to ON to simulate lifting Test Rack.

ZLOSTMC2_U1[1]

• DOV ZLOSTMC2[6] to simulate closing cabinet door ZLOSTMC2_U1[6]

Cook Plant Unit 1 & Unit 2 Page 19 of 21

SIMULATOR INSTRUCTIONS (NRC2012-03)

EVENT #4 After crew has stabilized the plant from the Steam Flow failure, insert ICF U1_101BAP1, to cause the #1 BA Pump Trip (Global).

U1_101BAP1 If asked, #1 BAT Pump is hot to the touch and Breaker 1ABD-1D thermal overload is tripped (will not reset).

If requested, #2 BAT is aligned as required.

Present completed lineup sheet 6 of 12-OHP-4021-005-001 if requested.

1. 2 BAT Pump flow is ~5 gpm when started and flow rises as recirc is opened.

EVENT #5 (Optional - Planned Reactivity Change)

When crew has recovered from the BA Pump failure:

• Call control room and report oil spray (unisolable) coming from East MFP oil pump of approximately 10 gpm. (Feed pump needs to be removed within the hour.)

Note: If desired the next event (East MFP Trip) may be initiated prior to commencing the Rapid Power Reduction.

EVENT #6 When the crew has changed power 2-3% or as directed by the lead examiner, insert IMF FW05A (East MFP trip).

U1_FW05A Cook Plant Unit 1 & Unit 2 Page 20 of 21

SIMULATOR INSTRUCTIONS (NRC2012-03)

EVENT #7,8,9 After the Crew has stabilized following the East MFP Trip, activate trigger ET-7 (West MFP Trip and Steam Line Break).

Activate Trg 7 Local actions after entry into E-0:

• Locally stop U1 Ice Condenser AHUs MRF CHR01 to OFF U1_CHR01

• Aux Tour will monitor Spent Fuel Pool Radiation, Level and Temperatures

• Place PACHMAS in service - MRF CHR02 or 03 with 10 min delay.

U1_CHR02 OR U1_CHR03 (both have 10 minute delay built in)

• U2 has aligned CR vent for U1 SI, Fan 2-HV-AS-2 is running.

If directed to secure EDG jacket water pumps select OFF then AUTO Remote OFF AUTO EGR 03A U1_EGR03A U1_EGR03A EGR 03B U1_EGR03B U1_EGR03B EGR 04A U1_EGR04A U1_EGR04A EGR 04B U1_EGR04B U1_EGR04B Cook Plant Unit 1 & Unit 2 Page 21 of 21

Appendix D Scenario Outline Form ES-D-1 Facility: Cook Plant Unit 1 & Unit 2 Scenario No.: NRC2012-04 Op-Test No.: Crews 3 & 4 Examiners: _________________ Operators:___________________

Initial Conditions: IC-523, 50% pwr; 933 ppm boron, 10 GWD, 551°F Tavg, CBD @ 174 steps, 485 MW Turnover: Complete shutdown of East MFW Pump for repairs. NRV-153, PZR PORV is isolated for leakage.

Event Malf. No. Event Event No. Type* Description 1 N-BOP Complete Shutdown of Idle (East) MFW Pump.

2 NI10B to I-RO Power Range Channel NI-42 fails HIGH.

120%

TS 3 MPP240 to I-BOP SG Pressure Channel MPP-240 Fails HIGH.

1200 over 10 Sec TS 4 RC24D to C-RO SG No. 4 Tube Leak of 5 gpm Requiring Shutdown.

50%

TS 5 R-RO Shutdown the Reactor.

6 RX24G to C-BOP FRV-240 Feedwater Control Valve Controller Fails 99% OPEN in Auto.

7 RC23D to 60% (400 M SG No. 4 Tube Rupture.

gpm) Ramp Time 5:00 Min 8a 101XCR101 C-BOP Train B Instrument Air to Containment XCR-101 & XCR 101XCR103 103 Failure (Fail to Reopen After SI Reset).

Global 8b RC17B 0% - C-RO PZR PORV NRV-152 Fails to Open.

Preload

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Cook Plant Unit1 & Unit 2 Page 1 of 22

Event Summary (NRC2012-04)

The plant is at 50% power and the BOP is directed to complete the shutdown of the idle FW pump.

After the crew completed the FW pump shutdown, a failure of the Power Range NI-42 will occur. This will result in the AUTO insertion of control rods. The RO will be required to take manual control of rods to stop insertion. The RO should identify the NI-42 failure. The crew will need to address this failure with the Abnormal Operating Procedure and address Technical Specifications.

The next event will involve the SG Pressure Channel MPP-240 fails high. The BOP will be required to take manual control SG 4 Feedwater Regulating Valve FRV-240 to stabilize level. The crew will address the failure with the Abnormal Operating Procedure, address Technical Specifications, select an operable channel, and restore automatic control.

After the pressure channel; a SG 4 Tube Leakage of 5 gpm, will require a shutdown per the Abnormal Operating Procedure.

After the crew has begun the shutdown, the Feed Regulating Valve FRV-240 on SG 4 will fail to 99% in Auto. The BOP will need to take manual control and maintain SG level during the ramp.

The SG tube leak will become worse requiring a Reactor Trip and Safety Injection. The crew should manually trip the reactor and initiate SI. The crew will progress through E-0 and transition to E-3.

The crew will progress through E-3 and discover that Instrument Air can not be restored to Containment because the Train B Isolation Valves will not re-open. This will complicate the RCS Depressurization. The scenario will be terminated once the RCS has been depressurized and the SI pumps have been stopped.

Critical Tasks Isolate Ruptured SG RCS Cooldown Depressurize RCS Procedures E-0 Reactor Trip or Safety Injection E-3 Steam Generator Tube Rupture Cook Plant Unit1 & Unit 2 Page 2 of 22

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Crews 3 & 4 Scenario No.: NRC2012-04 Event No.: 1 Event

Description:

Complete Shutdown of Idle (East) MFW Pump Time Position Applicant's Actions or Behavior US Directs actions of 1-OHP-4021-055-004, Attachment 1, Removing East MFP From Service (Starting at Step 4.7).

Performs the following on the East MFP:

BOP 1. TRIPS the MFP.

2. Verify Turbine Drain (FPT Stop Valve Drains) valves OPEN.

3. Dispatch an operator to open local drain valves (1-HPD-133 and 1-HPD-104E).

4. Verifies following valves CLOSED:

• FMO-251

• AMO-1

• AMO-11

5. Verifies ARV-60 CLOSED.

6. Adjusts LO Temperature Controller to 80-90ºF.

7. Verify DC Emergency LO pump OFF and in AUTO.

8. Place MFP on turning gear:

• Verify Turning Gear Motor in RUN.

• Verify ELO valves CLOSED (FRV-251 and 252).

RO Monitors the plant during East MFP shutdown.

Cook Plant Unit1 & Unit 2 Page 3 of 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Crews 3 & 4 Scenario No.: NRC2012-04 Event No.: 2 Event

Description:

Power Range Channel (NI-42) Fails HIGH Time Position Applicant's Actions or Behavior RO Acknowledges and reports annunciator on Panel #110 which is indicative of a Power Range NI failure (Drop 18).

RO Places rod control in MANUAL after verifying no turbine runback in progress.

US Enters and directs actions of 1-OHP-4022-012-003, Continuous Control Bank Movement procedure, if rods moved.

RO If 1-OHP-4022-012-003 is entered, then performs the following as directed:

1. Checks for no turbine runback.

2. Ensures control rods are in MANUAL with no rod motion.

3. Checks rod position above low-low Rod Insertion Limit (RIL).

4. Checks Axial Flux Difference (AFD) within target band.

5. Identifies failed Power Range channel.

US Enters and directs actions of 1-OHP 4022-013-004, Power Range Malfunction procedure.

EVENT NO. 2 CONTINUED ON NEXT PAGE Cook Plant Unit1 & Unit 2 Page 4 of 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Crews 3 & 4 Scenario No.: NRC2012-04 Event No.: 2 Event

Description:

Power Range Channel (NI-42) Fails HIGH (Continued)

Time Position Applicant's Actions or Behavior RO/BOP Performs the following as directed:

1. Verifies Rods in MANUAL.

2. Restores equilibrium conditions (after bypassing rod stop).

3. Places the following switches to the NI-42 position:

• Rod stop bypass selector.

• Initiates restoration of equilibrium conditions using either:

• Control rod movement.

• Turbine load adjustment.

• Comparator channel defeat selector.

• Upper section detector current comparator defeat.

• Lower section detector current comparator defeat.

• Power mismatch bypass selector.

4. Checks Permissives (Ps) in proper states.

5. Checks AFD within target band.

6. Verifies following recorders selected to an unaffected channel:

• Delta T

• Overtemperature Delta T

7. Returns control rods in automatic (if desired)

US Refers to Tech Specs 3.3.1 RTS Instrumentation -

Condition A - Check Table 3.3.1-1 Functions:

• 2a. PR High Trip - Condition C -Trip Bistables in 6 Hours (QPTR if >75%)

• 2b. PR Low Trip - Condition D -Trip Bistables in 6 Hours

• 3. PR Rate Trip - Condition D -Trip Bistables in 6 Hours

• 6. OTDT 6, - Condition D -Trip Bistables in 6 Hours

• 18c,d. P-8 & P Condition L - Verify Correct State within 1 Hour US Initiates actions to trip bistables associated with Power Range N42 failure per Attachment B of 1-OHP-4022-013-004.

Cook Plant Unit1 & Unit 2 Page 5 of 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Crews 3 & 4 Scenario No.:RO27 Audit-03 Event No.: 3 Event

Description:

SG Pressure Channel MPP-240 Fails High Time Position Applicant's Actions or Behavior BOP Recognizes and reports annunciators on Panel 114 which are indicative of a steam generator #4 water level control / pressure instrument failure (Drops 14, 32, 43).

BOP Places FRV-240, SG 4 MFW Reg. Valve controller to MANUAL, lowers controller output and restores SG 4 level to program (may also place MFP P controller in MANUAL at this time).

US Enters and directs actions of 1-OHP-4022-013-012, Steam Generator Pressure Instrument Malfunction procedure.

BOP Performs the following actions as directed:

1. Restores SG 4 level using manual control of FRV-240.

2. Checks SG PORVs closed.

3. Places MFP P controller in MANUAL.

4. Reports MPP-240 has failed.

5. Places 1-FS-542C selector switch in channel 2 position.

6. Nulls and returns FRV-240 controller to AUTO.

7. Returns MFP P controller to auto.

US Refers to Tech Specs (TS):

• TS 3.3.1 RTS Instrumentation Condition A - Check Table 3.3.1-1 Function:

• Function 15 - Cond. D Trip Bistables in 6 Hours

• TS 3.3.2 ESFAS Instrumentation Condition A - Check Table 3.3.2-1 Functions:

• Function 1e(2) & 4e - Cond. D - Trip Bistables in 6 Hours

• TS 3.3.4 Remote Shutdown Instrumentation - Condition A - Restore within 30 Days US Initiates actions to trip bistables associated with MPP-240 per Attachment D-1 of 1-OHP-4022-013-012.

Cook Plant Unit1 & Unit 2 Page 6 of 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Crews 3 & 4 Scenario No.: NRC2012-04 Event No.:4 Event

Description:

SG 4 Tube Leak (5 gpm) requiring rapid shutdown Time Position Applicant's Actions or Behavior RO/BOP Acknowledges and reports secondary radiation alarms:

• SRA-1905, Steam jet air ejector vent monitor Note: Crew may enter 1-OHP-4022-002-020 Excessive RCS Leakage if it is noted that Pressurizer level is slowly lowering. This procedure has a transition at step 11 (RNO) for 1-OHP-4022-002-021, Steam Generator Tube Leak.

US Enters and directs actions of 1-OHP-4022-002-021, Steam Generator Tube Leak procedure.

RO Performs the following actions as directed:

• Maintains PRZ level stable or trending to program level.

• Maintains VCT level with Auto/Manual makeup as required.

BOP Performs the Attachment B actions as directed:

• Verifies Unit 2 has auxiliary steam loads.

• Dispatches operator to close 12-DRV-710.

• Directs chemistry to sample SGs and TRS compositor.

• Notifies RP to monitor Turb. Bldg. and main steam lines.

RO Determines RCS leak rate to be approximately < 10 gpm.

US Determines a controlled unit shutdown is necessary based on an RCS leakrate > 75 gpd (0.05 gpm) and < 50 gpm.

US Refers to Tech Specs 3.4.13 RCS Operational Leakage.

SG Leakage >150gpd/SG. Action D applies. - Be in Mode 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Cook Plant Unit1 & Unit 2 Page 7 of 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Crews 3 & 4 Scenario No.: NRC2012-04 Event No.:5 Event

Description:

Shutdown the Reactor Time Position Applicant's Actions or Behavior NOTE: May use 1-OHP 4022-001-006, Rapid Power Reduction Response procedure (to perform power reduction. See below)

US Directs RO to commence Power Reduction in accordance with 1-OHP-4021-001-003.

RO Performs BORATION addition:

• Place RC Makeup Bend control switch in STOP.

• Place RC Makeup Blend Control Mode switch in BORATE.

• Set desired batch on BA Flow Totalizer.

• Adjust BA Flow Ctrl (RU-33) to desired flow.

• Place RC Makeup Blend control switch in START.

RO Commences power reduction:

• Lowers turbine load (reactor power) using HMI.

• Maintains Tavg/Tref deviation within limits by boration and turbine load adjustments.

• Ensures Axial Flux Difference (AFD) is maintained within target band by manual control rod movement as needed.

BOP May as peer checker for RO during blender operations and verify appropriate reactivity feedback.

Load Reduction per 1-OHP-4022-001-006, Rapid Power Reduction Response procedure.

US Directs RO to commence Rapid Power Reduction in accordance with 1-OHP 4022-001-006.

Continued Next Page Cook Plant Unit1 & Unit 2 Page 8 of 22

Op-Test No.: Crews 3 & 4 Scenario No.: NRC2012-04 Event No.:5 Event

Description:

Shutdown the Reactor Time Position Applicant's Actions or Behavior RO Performs (Att. D) NORMAL BORATION:

• Verify charging is > 75 gpm

• CLOSE 1-QMO-225, EAST CCP Mini-Flow (CCP ELO)

• Place RC Makeup Blend control switch in STOP.

• Place RC Makeup Blend Control Mode switch in BORATE.

• Adjust BA Controller/Totalizer to the desired flow rate and amount.

• Place RC Makeup Blend control switch in START.

• May take QRV-303 to MANUAL/OPEN (as required) to maintain VCT level and pressure.

1-OHP 4022-001-006 Attachment D Table

-OR-Cook Plant Unit1 & Unit 2 Page 9 of 22

Op-Test No.: Crews 3 & 4 Scenario No.: NRC2012-04 Event No.:5 Event

Description:

Shutdown the Reactor Time Position Applicant's Actions or Behavior Performs (Att. E) EMERGENCY BORATION:

• Verify charging is > 75 gpm.

• CLOSE 1-QMO-225, EAST CCP Mini-Flow (CCP ELO)

• Place #2 BAT pump to FAST speed.

• Open QMO-410, Emergency Boration To CHG Pump Suction valve.

• Verify QFI-410, Emergency Boration Flow.

• May take QRV-303 to MANUAL/OPEN (as required) to maintain VCT level and pressure.

1-OHP 4022-001-006 Attachment E Table RO Commences power reduction:

• Verify all PRZ backup heaters ON.

• Lowers turbine load using HMI.

• Ensures control rods in AUTO.

BOP Acts as peer checker for RO and verifies appropriate reactivity feedback.

Cook Plant Unit1 & Unit 2 Page 10 of 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Crews 3 & 4 Scenario No.: NRC2012-04 Event No.:6 Event

Description:

Feedwater Control Valve (FRV-240) Controller Fails to 100% in Auto Time Position Applicant's Actions or Behavior BOP Acknowledges and reports Annunciator #114 (Drop 32).

US/BOP Places FRV-240 in MANUAL and lowers controller output to return SG 4 level to program.

BOP Maintains SG 4 level near program (44%) with FRV-240 in manual.

Cook Plant Unit1 & Unit 2 Page 11 of 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Crews 3 & 4 Scenario No.: NRC2012-04 Event No.:7/8a/8b Event

Description:

Steam Generator (4) Tube Rupture XCR-101 & XCR 103 Fails to Open PZR PORV NRV-152 Fails to Open Time Position Applicant's Actions or Behavior US Directs RNO actions of 1-OHP-4022-002-021, Steam Generator Tube Leak procedure based on indications that the primary to secondary leakrate has escalated.

RO Performs the actions of 1-OHP-4022-002-021 as directed:

• Maximize charging flow

• Reduces or isolates letdown US Directs RO/BOP to manually trip the reactor and initiate safety injection and perform the immediate actions of 1-OHP-4023-E-0 (E-0) Reactor Trip or Safety Injection (based on RCS leak rate beyond the capacity of one charging pump per 1-OHP 4022-002-021).

RO Performs the (primary) immediate actions of E-0:

1. Trips the reactor.

2. Actuates safety injection.

BOP Performs the (secondary) immediate actions of E-0:

1. Checks turbine trip.

2. Checks power to AC emergency buses.

US Ensures immediate actions of E-0 are completed.

US Announces RX Trip over Executone US Directs subsequent actions of E-0.

Cook Plant Unit1 & Unit 2 Page 12 of 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Crews 3 & 4 Scenario No.: NRC2012-04 Event No.: 7/8a/8b Event

Description:

Steam Generator (4) Tube Rupture XCR-101 & XCR 103 Fails to Open PZR PORV NRV-152 Fails to Open Time Position Applicant's Actions or Behavior RO/BOP Reviews E-0 Foldout Page Criteria.

BOP Performs the following actions as directed:

• Manually controls AFW flow to maintain SG narrow range levels 14% - 50% once one SG narrow range level is > 14%.

• Reports 4 SG level rising in an uncontrolled manner and isolates AFW to the ruptured SG when level is > 14%.

RO/BOP Performs actions of E-0, Attachment A, as directed by US.

• Place DIS in Service - Turn on Igniters

• Stop one Control Room Pressurization fan.

• Reset Bypass switches for PACHMS CREW Completes all actions of E-0 through Step 18 (Check If SG Tubes Are Intact).

US Announces transition to 1-OHP-4023-E-3 (E-3), Steam Generator Tube Rupture (at step 18 of E-0).

RO/BOP Reviews E-3 Foldout Page Criteria.

US Directs actions of E-3, Steam Generator Tube Rupture.

US/BOP Isolates flow to and from the ruptured SG:

1. Adjusts MRV-243 (PORV) controller setpoint to 1040 psig Critical ( items 2-5 Not Critical)

Task #1 2. Checks MRV-243 closed

3. Checks DCR-340 blowdown isolation valve closed

4. Checks DCR-304 blowdown sample valve closed

5. Places DRV-407 SGSV drain valve in close

6. Trips/verifies MRV-240 SGSV closed

7. Verifies SGSV dump valves closed:

• MRV-241

• MRV-242 Cook Plant Unit1 & Unit 2 Page 13 of 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Crews 3 & 4 Scenario No.: NRC2012-04 Event No.: 7/8a/8b Event

Description:

Steam Generator (4) Tube Rupture XCR-101 & XCR 103 Fails to Open PZR PORV NRV-152 Fails to Open Time Position Applicant's Actions or Behavior BOP Verifies 14 SG level > 14%:

• Ensures feed flow to SG 4 - isolated Critical Task #1 US Determines target cooldown CETC temperature (E-3 step 7 table) based on ruptured 4 SG pressure.

US/BOP Initiates RCS cooldown to target CETC temperature using either:

Critical

• Condenser steam dump (preferred if available).

Task #2

• Intact SG PORVs (if condenser unavailable).

BOP Performs the following during cooldown as directed:

1. Bypasses steam dump lo-lo Tavg interlock.

2. Blocks steam line break SI.

US/BOP Stops cooldown, establishes and maintains CETC temperatures below E-3 target temperature.

Critical Task #2 BOP Maintains intact SG levels >14% or >240 KPH (control band 20-50%).

RO Attempts to restore control air to containment as directed:

1. Resets SI

2. Resets Phase A

3. Attempts to open control air to containment valves:

• 1-XCR-100 and 1-XCR-102 open

• 1-XCR-101 and 1-XCR-103 will not open Cook Plant Unit1 & Unit 2 Page 14 of 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Crews 3 & 4 Scenario No.: NRC2012-04 Event No.: 7/8a/8b Event

Description:

Steam Generator (4) Tube Rupture XCR-101 & XCR 103 Fails to Open PZR PORV NRV-152 Fails to Open Time Position Applicant's Actions or Behavior RO Stops RHR pumps.

US/RO Depressurizes RCS using available PRZ PORV:

• Opens NMO-153, PRZ PORV block valve Critical

• Opens NRV-153, PRZ PORV until any of the following Task #3 conditions are satisfied:

1. RCS press < ruptured SG press and PRZ level >21%

2. PRZ level > 70%

3. RCS Subcooling < 40°F RO Stops the following ECCS pumps:

• Both SI pumps

• One CCP Isolate the BIT RO

• Reset and open CCP ELOs QMO-225 & 226

• Close BIT Inlet Valves IMO-255 & 256

• Close BIT Otlet Valves ICM-250 & 251 RO/BOP Establish Charging Flow

• Close QRV-200, Charging header pressure control valve

• Open QMO-200 & 201Charging to Regen HX

• Establish minimum charging flow with QRV-251 & QRV-200 TERMINATE SCENARIO Cook Plant Unit1 & Unit 2 Page 15 of 22

CRITICAL TASK

SUMMARY

(NRC2012-04)

Task Elements Results

1. 1 Cueing: SAT / UNSAT

• Isolate Flow From Ruptured SG (E-3, Isolates Flow To and Step 3)

From The Ruptured

• If Ruptured SG Then Close AFW Steam Generator Valves to Affected SG (E-0, Step 8),

RNO)

• Check Feed Flow To Ruptured SG Isolated (E-3, Step 4.b)

Performance Indicators:

• Isolates SG 4:

o Adjusts PORV setpoint at 1040 psig o Trips/verifies MRV-240 SGSV closed o Verifies SGSV dump valves closed, o MRV-241 and MRV-242 o Ensures feed flow isolated

• Must be performed prior to RCS cooldown to preclude transition to ECA-3.1, Loss of Reactor Coolant -

Subcooled Recovery Desired on low ruptured SG pressure < 250 psid above intact SG pressures.

Performance Feedback:

• Stable pressure in the ruptured SG.

• No feedwater flow to the ruptured SG.

Cook Plant Unit1 & Unit 2 Page 16 of 22

CRITICAL TASK

SUMMARY

(Cont.)

(NRC2012-04)

Task Elements Results

1. 2 Cueing: SAT / UNSAT

• Initiate RCS Cooldown (E-3, Step 7)

Establishes and Maintains RCS Target Temperature Performance Indicators:

• Performs RCS cooldown, establishes and maintains CETC temperatures below target temperature.

• Temperature must be maintained within limits to prevent transition from E-3 due to either:

• Loss of subcooling (high temp.)

• CSF transition (low temp.)

Performance Feedback:

• RCS temp. less than target temp.

1. 3 Cueing: SAT / UNSAT

• Depressurize RCS Using PRZ PORV Depressurize RCS Using (E-3, Step 18)

Available PRZ PORV Performance Indicators:

• Depressurizes RCS using available PRZ PORV (NRV-153).

• Final RCS conditions must meet SI termination criteria

• Ruptured SG inventory should not risk potential consequences of SG overfill Performance Feedback:

• RCS pressure lowering

• PRZ level rising Cook Plant Unit1 & Unit 2 Page 17 of 22

SIMULATOR INSTRUCTIONS (NRC2012-04)

Setup:

1. Reset to ~50% power IC-523 with East MFP Idle - Perform 1-OHP-4021-055-004, Attachment 1, Removing East MFP From Service (Up to Step 4.7). East MFP 3000-3500 rpm.

2. Reset control rods and check group step counters.

3. Place Master Annunciator Silence pushbutton lockout ring in LOCKOUT position.

4. Advance chart recorder paper & clear recorder memory.

5. Go to RUN and acknowledge/clear alarms.

6. Close NMO-153 and caution tag control switch.

7. Place NRV-153 to CLOSE and caution tag control switch (for leakage).

8. Activate the following pre-load malfunctions:

• RCR20, final value 10, (NRV-153 leaks 10 gpm). U1_RCR20

• RC17B, final value 0, (NRV-152 fails to open) U1_RC17B

• IMF SFR401, SJAE Flow to Maintain Steady Low Power Values U1_SFR401

9. Assign file U1_SafetyInjectionSignal to trigger 1 U1 SI Signal

10. Assign Global Malfunctions for IA valves to trigger 1 U1_101XCR101

• 101XCR101 Containment IA Isol Power loss

• 101XCR103 Containment IA Isol Power loss U1_101XCR103 Cook Plant Unit1 & Unit 2 Page 18 of 22

SIMULATOR INSTRUCTIONS (NRC2012-04)

EVENT #1 Provide Marked-Up copy of 1-OHP-4021-055-004, Attachment 1, Removing East MFP from Service (up to Step 4.7) to BOP.

If requested, report that HPD-133 and HPD-104E are OPEN As SM, tell the BOP that Extra RO will finish shutting down the East MFP (at Step 4.8).

EVENT #2 After crew removes the East MFP from service, inset IMF NI10B, final value 120 (NI-42 fails high) when crew has assumed the watch.

U1_NI10B If directed to trip bistables for NI-42 use:

• Override ZLOSTMC2[7] to ON to simulate opening cabinet door.

ZLOSTMC2_U1[7]

• Override Lights/Relays - RX Flux panel:

Remote Bistable RPR123 U1_RPR123 TS-421C RPR124 U1_RPR124 TS-421D

• Override ZLOSTMC2[2] to ON to simulate lifting Test Rack.

ZLOSTMC2_U1[2]

• Override ZLOSTMC2[7] to OFF to simulate closing cabinet door.

ZLOSTMC2_U1[7]

• MRF U1_NIR09 to Tripped to simulate Pulling P312 cable from the NI drawer U1_NIR09 Cook Plant Unit1 & Unit 2 Page 19 of 22

SIMULATOR INSTRUCTIONS (NRC2012-04)

EVENT #3 After crew responds to the NI failure, insert ICF U1_MPP240 final value 1200 over 10 seconds (MPP-240 fails high).

U1_MPP240 If directed, to trip bistables for MPP-240 use:

• IOV ZLOSTMC2[6] to ON to simulate opening cabinet door.

ZLOSTMC2_U1[6]

• Override Lights/Relays - RX Flux panel:

Remote Bistable RPR105 U1_RPR105 PS/534B RPR104 U1_RPR104 PS534A RPR035 U1_RPR035 FS/540A RPR036 U1_RPR036 FS/540B RPR039 U1_RPR039 FS/542B

• IOV ZLOSTMC2[1] to ON to simulate lifting Test Rack ZLOSTMC2_U1[1]

• DOV ZLOSTMC2[6] to simulate closing cabinet Door ZLOSTMC2_U1[6]

Cook Plant Unit1 & Unit 2 Page 20 of 22

EVENT #4 After crew responds to the SG Pressure failure, insert IMF RC24D, final value 50 (#14 SGTL of 5gpm) when crew has recovered from NI failure. U1_RC24D NOTE: It takes about 10 Minutes to reach Alert on Radiation Monitor.

1. If contacted as Radiation Protection, report that the requirements of 12-THP-6010-RPP-706, Gaseous Monitor Alarm Response have been met.

2. If contacted as Chemistry to evaluate SG Blowdown sample line activity per 12-THP-4030-002-208, Primary to Secondary Leakage - report back after some delay that leakage appears to be 5 GPM on the #4 SG.

3. If contacted as Duty Staff Supervisor to determine shutdown rate, then direct US to start power reduction at the rate required by procedure.

EVENT #5 If required prompt crew to begin power change (as the SM).

EVENT #6 During the power reduction, insert IMF RX24G, final value 100 (FRV-240 fails open in auto).

U1_RX24G EVENT #7 After crew responds FRV-240 failing open, insert IMF RC23D, final value 40, ramp 5:00

(#14 SGTR, 400 gpm, over 5 min.). U1_RC23D Cook Plant Unit1 & Unit 2 Page 21 of 22

SIMULATOR INSTRUCTIONS (NRC2012-04)

EVENT #8a/b When the SI occurs, verify/Trigger (TRG 1) the following malfunctions:

• 101XCR101 (control air valve fails to open)

• 101XCR103 (control air valve fails to open)

If contacted as Radiation Protection, report that the requirements of 12-THP-6010-RPP-706, Gaseous Monitor Alarm Response have been met.

If contacted as Chemistry to evaluate SG Blowdown sample line activity per 12-THP-4030-002-208, Primary to Secondary Leakage - report back after some delay that leakage appears to be > 50 GPM on the #4 SG.

Local actions after entry into E-0:

• Locally stop U1 Ice Condenser AHUs MRF CHR01 to OFF U1_CHR01

• Aux Tour will monitor Spent Fuel Pool Radiation, Level and Temperatures

• Place PACHMAS in service - MRF CHR02 or 03 with 10 min delay.

U1_CHR02 OR U1_CHR03 (both have 10 minute delay built in)

• U2 has aligned CR vent for U1 SI, Fan 2-HV-AS-2 is running.

• If required CCW Vent Fan 12-HV-ACCP-1 is NOT Running.

If directed to secure EDG jacket water pumps select OFF then AUTO Remote OFF AUTO EGR 03A U1_EGR03A U1_EGR03A EGR 03B U1_EGR03B U1_EGR03B EGR 04A U1_EGR04A U1_EGR04A EGR 04B U1_EGR04B U1_EGR04B Cook Plant Unit1 & Unit 2 Page 22 of 22