ML102220067

DC Cook, 2010 Initial License Exam, Admin JPMs

ML102220067
Person / Time
Site:	Cook
Issue date:	06/21/2010
From:	Division of Reactor Safety III
To:	Indiana Michigan Power Co
References
Download: ML102220067 (66)

Text

OPERATIONS JPM TRAINING PROGRAM INITIAL LICENSE TRAINING TIME: 10 MINUTES TITLE NUMBER AND NRC2010-A1a TITLE: Calculate Reactor Vessel Void Vent Time REVISION: 0 SCOPE OF Initial Issue.

REVISION From: Audit06-A1a DATE:

PREPARED BY: Name:

(Exam Writer)

Signature:

APPROVED BY: Name:

(Facility Reviewer)

Signature:

NRC2010-A1a Revision: 0 Calculate Reactor Vessel Void Vent Time NRC2010-A1a.doc Page 1 of 6

OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 1-OHP 4023 FR-I.3, R8 Response to Voids in Reactor Vessel K/A Number: EPE: 009 EA2.38 Ability to interpret existence of head bubble during SBLOCA.

2.1.25 Ability to obtain and interpret station reference materials. (CFR: 41.7 / 45.5 to 45.8)

K/A Imp.: RO: 3.9 SRO: 4.3 3.9 4.2 Task Number: EOP1090512 Mitigate the effects of voids in the reactor vessel TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS Task Briefing 1-OHP 4023 FR-I.3, Response to Voids in Reactor Vessel, Attachemnt A, Instructions For Determaining Venting Time 1-OHP 4023 FR-I.3, Response to Voids in Reactor Vessel, Figure 1, Hydrogen Flow Rate Versus RCS Pressure ATTACHMENTS None EVALUATION SETTINGS Classroom EVALUATION METHOD: PERFORM: SIMULATE:

NRC2010-A1a Revision: 0 Calculate Reactor Vessel Void Vent Time NRC2010-A1a.doc Page 2 of 6

OPERATIONS JPM SIMULATOR/LAB SETUP None 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 SRO from Unit 2.

The Unit 1 Control Room team is responding to a SBLOCA and is currently implementing ES-1.2, Post LOCA Cooldown and Depressurization. There has been significant voiding in the RCS.

The Unit Supervisor has implemented FR-I.3, Response to Voids in Reactor Vessel.

The Unit Supervisor directs you to determine the maximum vent time for the Reactor vessel using Attachment A of FR-I.3. You are to report the calculated vent time to the US.

The following containment parameters were noted on 1-SG-18, Containment Air Temperature Recorder:

Point # Point Id Noun Name Temperature (Deg F) 1 ETR-11 Upper Cont. 90 97 2 ETR-12 Upper Cont. 180 134 3 ETR-13 Upper Cont. 270 101 4 ETR-14 Upper Cont. 0 93 5 ETR-15 Lower Cont. Q1 173 6 ETR-16 Lower Cont. Q2 139 7 ETR-17 Lower Cont. Q3 129 8 ETR-18 Lower Cont. Q4 168 9 ETR-19 HV-CLV-1,4 Room 170 10 ETR-20 HV-CEQ-2 Room 151 11 ETR-21 HV-CLV-2,3 Room 146 12 ETR-22 INST Room 190 13 ETR-23 PZR Doghouse 367 RCS pressure is 1450 psig NRC2010-A1a Revision: 0 Calculate Reactor Vessel Void Vent Time NRC2010-A1a.doc Page 3 of 6

OPERATIONS JPM Containment hydrogen concentration is 0.8%.

NOTE Simulator Indications are NOT applicable to this JPM GENERAL STANDARDS/PRECAUTIONS Reactor Vessel Void Vent time is appropriately determined (+10% error) based upon initial conditions.

NRC2010-A1a Revision: 0 Calculate Reactor Vessel Void Vent Time NRC2010-A1a.doc Page 4 of 6

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

STANDARD: (CS) Determines Average Temp is 126 Deg F. (Points 2, 4,

& 10 as per note at bottom of page)

SAT: UNSAT:

STANDARD: Determine 586 Deg R SAT: UNSAT:

STANDARD: Determines1.041x106 ft3 SAT: UNSAT:

STANDARD: Determines 2.290x104. ft3 SAT: UNSAT:

STANDARD: (CS): Determines 3300 + 100 SCFM SAT: UNSAT:

STANDARD: (CS) Determines 6.94 (range of 6.7 - 7.2) minutes.

SAT: UNSAT:

JPM TERMINATION: Reports to US a vent time NRC2010-A1a Revision: 0 Calculate Reactor Vessel Void Vent Time NRC2010-A1a.doc Page 5 of 6

Task Briefing You are the extra SRO from Unit 2.

The Unit 1 Control Room team is responding to a SBLOCA and is currently implementing ES-1.2, Post LOCA Cooldown and Depressurization. There has been significant voiding in the RCS. The Unit Supervisor has implemented FR-I.3, Response to Voids in Reactor Vessel.

The Unit Supervisor directs you to determine the maximum vent time for the Reactor vessel using Attachment A of FR-I.3. You are to report the calculated vent time to the US.

The following containment parameters were noted on 1-SG-18, Containment Air Temperature Recorder:

Point # Point Id Noun Name Temperature (Deg F) 1 ETR-11 Upper Cont. 90 97 2 ETR-12 Upper Cont. 180 134 3 ETR-13 Upper Cont. 270 101 4 ETR-14 Upper Cont. 0 93 5 ETR-15 Lower Cont. Q1 173 6 ETR-16 Lower Cont. Q2 139 7 ETR-17 Lower Cont. Q3 129 8 ETR-18 Lower Cont. Q4 168 9 ETR-19 HV-CLV-1,4 Room 170 10 ETR-20 HV-CEQ-2 Room 151 11 ETR-21 HV-CLV-2,3 Room 146 12 ETR-22 INST Room 190 13 ETR-23 PZR Doghouse 367 RCS pressure is 1450 psig Containment hydrogen concentration is 0.8%.

Revision: 0 NRC2010-A1a.doc Page 6 of 6

OPERATIONS JPM TRAINING PROGRAM INITIAL LICENSE TRAINING TIME: 30 MINUTES TITLE NUMBER AND NRC2010-A1b-RO TITLE: Determination Of Reactor Shutdown Margin REVISION: 0 SCOPE OF Initial Issue.

REVISION From: Audit08-A1b-RO DATE:

PREPARED BY: Name:

(Exam Writer)

Signature:

APPROVED BY: Name:

(Facility Reviewer)

Signature:

NRC2010-A1b-RO Revision: 0 Determination Of Reactor Shutdown Margin NRC2010-A1b-RO.doc Page 1 of 16

OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 2-OHP-4021-001-012, R16 Determination of Reactor Shutdown Margin Misc: Unit 2 Technical Data Book Cycle 18 K/A Number: SYS 001 A4.11 Ability to manually determine shutdown margin in the control room.

K/A Imp.: RO: 3.5 SRO: 4.1 Task Number: 0010010501 Calculate Reactor Shutdown Margin.

TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS Task Briefing 2-OHP-4021-001-012, R16 Determination of Reactor Shutdown Margin, Attachment 1, Manual Shutdown Boron Calculation for Modes 3, 4, or 5.

Copy of Unit 2 Technical Data Book curves (Section 1, 4, 8.3 series)

ATTACHMENTS None EVALUATION SETTINGS Classroom.

EVALUATION METHOD: PERFORM: SIMULATE:

NRC2010-A1b-RO Revision: 0 Determination Of Reactor Shutdown Margin NRC2010-A1b-RO.doc Page 2 of 16

OPERATIONS JPM SIMULATOR/LAB SETUP None.

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 Control Room Operator on Unit 2.

The Unit Supervisor has directed you to calculate the SHUTDOWN MARGIN using Attachment 1 of 02-OHP-4021-001-012, Determination of Reactor Shutdown Margin.

The reactor tripped from 100% steady state operations 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> ago. A Shutdown Margin Calculation Using Xenon Correction was performed to begin the cooldown.

You are to calculate the required Shutdown Boron Concentration for the CURRENT RCS conditions without use of the optional Xenon Correction.

• NERDS is NOT available.

• RCS Temperature is currently 215°F.

• PPC point U0035 indicates 8500 MWD/MTU

• RCS boron concentration is 1810 ppm per a chemistry sample taken 30 minutes ago.

• All Rods are fully inserted except Control Bank D Rod D-12 which indicates 105 steps.

NOTE Simulator Indications are NOT applicable to this JPM GENERAL STANDARDS/PRECAUTIONS The net excess shutdown margin has been determined.

NRC2010-A1b-RO Revision: 0 Determination Of Reactor Shutdown Margin NRC2010-A1b-RO.doc Page 3 of 16

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

ACTIONS:

Instructor Note: IF candidate states that the previous Shutdown Margin calculation is No longer valid (Since it used Xenon correction and it is now > 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />), THEN:

• Acknowledge that the Unit Supervisor will address that issue.

• Direct candidate to complete the Shutdown Margin as directed.

STANDARD: Records cycle number 18 from Technical Data Book.

SAT: UNSAT:

STANDARD: Enters Time and Date SAT: UNSAT:

NRC2010-A1b-RO Revision: 0 Determination Of Reactor Shutdown Margin NRC2010-A1b-RO.doc Page 4 of 16

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

N/A - Optional Xenon Correction NOT required.

PPC point U0035 reading of 8500 MWD/MTU is given in briefing.

STANDARD: Determines 8.5 GWD/MTU is burnup SAT: UNSAT:

N/A - Obtained from PPC NRC2010-A1b-RO Revision: 0 Determination Of Reactor Shutdown Margin NRC2010-A1b-RO.doc Page 5 of 16

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

STANDARD: Enters RCS Temperature of 215°F SAT: UNSAT:

STANDARD:P-11 and P-12 are blocked (Normal Cooldown Steps)

SAT: UNSAT:

STANDARD: Mode 4 so penalty applies SAT: UNSAT:

Step 4.5 is N/A - Unit is in Mode 4 Following a Trip NRC2010-A1b-RO Revision: 0 Determination Of Reactor Shutdown Margin NRC2010-A1b-RO.doc Page 6 of 16

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

Uses Figure 4.5 Curve for Mode 4 and 5 with Boron Penalty (Top Line)

STANDARD: (CS) Determines Uncorrected Boron Concentration is 1910 to 1930 PPM SAT: UNSAT:

NRC2010-A1b-RO Revision: 0 Determination Of Reactor Shutdown Margin NRC2010-A1b-RO.doc Page 7 of 16

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

Rod D-12 is stuck out at 105 steps.

STANDARD: (CS) Enters 1 for 1 stuck rod SAT: UNSAT:

STANDARD: (CS) Determines worth of stuck rod is 590 to 610 pcm SAT: UNSAT:

STANDARD: (CS) Enters total stuck rod worth of 590 to 610 pcm SAT: UNSAT:

Step 4.8 is N/A - Per briefing, Xenon Correction is NOT used.

NRC2010-A1b-RO Revision: 0 Determination Of Reactor Shutdown Margin NRC2010-A1b-RO.doc Page 8 of 16

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

STANDARD: (CS) Enters total stuck rod worth of 590 to 610 pcm SAT: UNSAT:

STANDARD: Enters 0 for Xenon reactivity SAT: UNSAT:

STANDARD: (CS) Enters Combined Reactivity of 590 to 610 pcm SAT: UNSAT:

NRC2010-A1b-RO Revision: 0 Determination Of Reactor Shutdown Margin NRC2010-A1b-RO.doc Page 9 of 16

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

STANDARD: (CS) Uses figure 4.1.c since Combined Reactivity is >0 and RCS Temperature is 215°F SAT: UNSAT:

STANDARD: (CS) Uses MOC line at Boron Concentration of ~ 1920 PPM to obtain Differential Boron Worth of -9.15 to to -9.35 pcm/ppm.

SAT: UNSAT:

STANDARD: Enters Combined Reactivity of 590 to 610 pcm SAT: UNSAT:

STANDARD: Enters DBW of -9.15 to to -9.35 pcm/ppm.

SAT: UNSAT:

STANDARD: (CS) Calculates Delta Boron of -63.10 to - 66.67 ppm SAT: UNSAT:

NRC2010-A1b-RO Revision: 0 Determination Of Reactor Shutdown Margin NRC2010-A1b-RO.doc Page 10 of 16

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

STANDARD: Enters Uncorrected Boron Concentration is 1910 to 1930 ppm SAT: UNSAT:

STANDARD: Enters Delta Boron of -63.10 to - 66.67 ppm SAT: UNSAT:

STANDARD: (CS) Calculates Adjusted Boron Concentration of 1973.1 to 1996.67 ppm SAT: UNSAT:

STANDARD: (CS) Uses figure 4.1.c since Combined Reactivity is >0 and RCS Temperature is 215°F SAT: UNSAT:

STANDARD: (CS) Uses MOC line at Adjusted Boron Concentration of

~ 1984.9 ppm to obtain Differential Boron Worth of -9.1 to -9.3 pcm/ppm.

SAT: UNSAT:

NRC2010-A1b-RO Revision: 0 Determination Of Reactor Shutdown Margin NRC2010-A1b-RO.doc Page 11 of 16

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

STANDARD: Enters Combined Reactivity of 590 to 610 pcm SAT: UNSAT:

STANDARD: Enters DBW of -9.1 to -9.3 pcm/ppm SAT: UNSAT:

STANDARD: (CS) Calculates Delta Boron of -63.4 to -67.0 ppm SAT: UNSAT:

STANDARD: Enters Uncorrected Boron Concentration is 1910 to 1930 ppm SAT: UNSAT:

STANDARD: Enters Delta Boron of -63.4 to -67.0 ppm SAT: UNSAT:

STANDARD: (CS) Calculates Adjusted Boron Concentration of 1973.4 to 1997.0 ppm SAT: UNSAT:

NRC2010-A1b-RO Revision: 0 Determination Of Reactor Shutdown Margin NRC2010-A1b-RO.doc Page 12 of 16

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

Step 4.10.1 is N/A - Correction for Stuck rod is required.

Step 4.10.2 is N/A - Concentration is < 2200 PPM STANDARD: (CS) Enters Required Boron Concentration of 1973.4 to 1997.0 ppm SAT: UNSAT:

NOTE: If Candidate determines Minimum Boron Concentration is NOT MET and Emergency Boration is required, the JPM may be terminated.

STANDARD: Enters Current RCS Boron Concentration of 1810 PPM SAT: UNSAT:

STANDARD: Enters sample time of Todays date and 30 minutes ago SAT: UNSAT:

NRC2010-A1b-RO Revision: 0 Determination Of Reactor Shutdown Margin NRC2010-A1b-RO.doc Page 13 of 16

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

STANDARD: (CS) Enters Required Boron Concentration of 1973.4 to 1997.0 ppm SAT: UNSAT:

STANDARD: Enters Current RCS Boron Concentration of 1810 ppm SAT: UNSAT:

STANDARD: Determines Difference is 163.4 to 187.0 ppm SAT: UNSAT:

STANDARD: (CS) Informs US that Shutdown Margin is NOT met and that Emergency Boration is Required.

SAT: UNSAT:

JPM TERMINATION: When operator Determines that Emergency Boration is required since the Shutdown Margin is NOT met, then JPM is Complete.

NRC2010-A1b-RO Revision: 0 Determination Of Reactor Shutdown Margin NRC2010-A1b-RO.doc Page 14 of 16

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

No actions required.

NRC2010-A1b-RO Revision: 0 Determination Of Reactor Shutdown Margin NRC2010-A1b-RO.doc Page 15 of 16

Task Briefing You are an extra Control Room Operator on Unit 2.

The Unit Supervisor has directed you to calculate the SHUTDOWN MARGIN using of 02-OHP-4021-001-012, Determination of Reactor Shutdown Margin.

The reactor tripped from 100% steady state operations 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> ago. A Shutdown Margin Calculation Using Xenon Correction was performed to begin the cooldown.

You are to calculate the required Shutdown Boron Concentration for the CURRENT RCS conditions without use of the optional Xenon Correction.

• NERDS is NOT available.

• RCS Temperature is currently 215°F.

• PPC point U0035 indicates 8500 MWD/MTU

• RCS boron concentration is 1810 ppm per a chemistry sample taken 30 minutes ago.

• All Rods are fully inserted except Control Bank D Rod D-12 which indicates 105 steps.

NOTE Simulator Indications are NOT applicable to this JPM Revision: 0 NRC2010-A1b-RO.doc Page 16 of 16

OPERATIONS JPM TRAINING PROGRAM INITIAL LICENSE TRAINING TIME: 30 MINUTES TITLE NUMBER AND NRC2010-A1b-SRO TITLE: SRO Review - Determination Of Reactor Shutdown REVISION: 0 Margin SCOPE OF Initial Issue.

REVISION From: Audit08-A1b-SRO DATE:

PREPARED BY: Name:

(Exam Writer)

Signature:

APPROVED BY: Name:

(Facility Reviewer)

Signature:

NRC2010-A1b-SRO Revision: 0 SRO Review - Determination Of Reactor Shutdown Margin NRC2010-A1b-SRO.doc Page 1 of 16

OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 2-OHP-4021-001-012, R16 Determination of Reactor Shutdown Margin Misc: Unit 2 Technical Data Book Cycle 18 K/A Number: SYS 001 A4.11 Ability to manually determine shutdown margin in the control room.

K/A Imp.: RO: 3.5 SRO: 4.1 Task Number: 0010010501 Calculate Reactor Shutdown Margin.

TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS Task Briefing 2-OHP-4021-001-012, R16 Determination of Reactor Shutdown Margin, Attachment 1, Manual Shutdown Boron Calculation for Modes 3, 4, or 5.

Copy of Unit 2 Technical Data Book curves (Section 1, 4, 8.3 series)

ATTACHMENTS None EVALUATION SETTINGS Classroom.

EVALUATION METHOD: PERFORM: SIMULATE:

NRC2010-A1b-SRO Revision: 0 SRO Review - Determination Of Reactor Shutdown Margin NRC2010-A1b-SRO.doc Page 2 of 16

OPERATIONS JPM SIMULATOR/LAB SETUP None.

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 Unit Supervisor on Unit 2. Per your direction, the extra Control Room Operator completed Attachment 2 of 02-OHP-4021-001-012, Determination of Reactor Shutdown Margin.

The reactor tripped from 100% steady state operations 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> ago.

The RO calculated the required Shutdown Boron Concentration for the CURRENT RCS conditions without use of the optional Xenon Correction.

• NERDS is NOT available.

• RCS Temperature is currently 215°F.

• PPC point U0035 indicates 8500 MWD/MTU

• RCS boron concentration is 1810 ppm per a chemistry sample taken 30 minutes ago.

• All Rods are fully inserted except Control Bank D Rod D-12 which indicates 105 steps.

Perform a complete review of the completed Attachment 1, noting all errors.

NOTE Simulator Indications are NOT applicable to this JPM.

GENERAL STANDARDS/PRECAUTIONS The net excess shutdown margin has been determined.

NRC2010-A1b-SRO Revision: 0 SRO Review - Determination Of Reactor Shutdown Margin NRC2010-A1b-SRO.doc Page 3 of 16

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

ACTIONS:

Instructor Note: IF candidate states that the previous Shutdown Margin calculation is No longer valid (Since it used Xenon correction and it is now > 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />), THEN:

• Acknowledge that the Unit Supervisor will address that issue.

• Direct candidate to complete the Shutdown Margin as directed.

STANDARD: Records cycle number 18 from Technical Data Book.

SAT: UNSAT:

STANDARD: Enters Time and Date SAT: UNSAT:

NRC2010-A1b-SRO Revision: 0 SRO Review - Determination Of Reactor Shutdown Margin NRC2010-A1b-SRO.doc Page 4 of 16

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

N/A - Optional Xenon Correction NOT required.

PPC point U0035 reading of 8500 MWD/MTU is given in briefing.

STANDARD: Determines 8.5 GWD/MTU is burnup SAT: UNSAT:

N/A - Obtained from PPC NRC2010-A1b-SRO Revision: 0 SRO Review - Determination Of Reactor Shutdown Margin NRC2010-A1b-SRO.doc Page 5 of 16

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

STANDARD: Enters RCS Temperature of 215°F SAT: UNSAT:

STANDARD:P-11 and P-12 are blocked (Normal Cooldown Steps)

SAT: UNSAT:

STANDARD: Mode 4 so penalty applies SAT: UNSAT:

Step 4.5 is N/A - Unit is in Mode 4 Following a Trip NRC2010-A1b-SRO Revision: 0 SRO Review - Determination Of Reactor Shutdown Margin NRC2010-A1b-SRO.doc Page 6 of 16

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

STANDARD: CS -Identified that Operator the incorrect curve.

SAT: UNSAT:

Figure 4.5 Curve for Mode 4 and 5 with Boron Penalty (Top Line)is signed for but Mode 3 curve was used.

STANDARD: (CS) Determines Uncorrected Boron Concentration is 1910 to 1930 PPM SAT: UNSAT:

NRC2010-A1b-SRO Revision: 0 SRO Review - Determination Of Reactor Shutdown Margin NRC2010-A1b-SRO.doc Page 7 of 16

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

Rod D-12 is stuck out at 105 steps.

STANDARD: (CS) Enters 1 for 1 stuck rod SAT: UNSAT:

STANDARD: (CS) Determines worth of stuck rod is 590 -610 pcm SAT: UNSAT:

STANDARD: (CS) Enters total stuck rod worth of 590 -610 pcm SAT: UNSAT:

Step 4.8 is N/A - Per briefing, Xenon Correction is NOT used.

NRC2010-A1b-SRO Revision: 0 SRO Review - Determination Of Reactor Shutdown Margin NRC2010-A1b-SRO.doc Page 8 of 16

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

STANDARD: (CS) Enters total stuck rod worth of 590 -610 pcm SAT: UNSAT:

STANDARD: Enters 0 for Xenon reactivity SAT: UNSAT:

STANDARD: (CS) Enters Combined Reactivity of 590 -610 pcm SAT: UNSAT:

NRC2010-A1b-SRO Revision: 0 SRO Review - Determination Of Reactor Shutdown Margin NRC2010-A1b-SRO.doc Page 9 of 16

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

STANDARD: (CS) Uses figure 4.1.c since Combined Reactivity is >0 and RCS Temperature is 215°F SAT: UNSAT:

STANDARD: CS - Identifies that Boron Worth & Delta Boron values are Incorrect. (Note this carries through the remainder of the calculation Step 4.9, 4.10, & 4.12)

STANDARD: (CS) Uses MOC line at Boron Concentration of ~ 1920 PPM to obtain Differential Boron Worth of -9.15 to to -9.35 pcm/ppm.

SAT: UNSAT:

STANDARD: Enters Combined Reactivity of 590 -610 pcm SAT: UNSAT:

STANDARD: Enters DBW of -9.15 to to -9.35 pcm/ppm.

SAT: UNSAT:

STANDARD: (CS) Calculates Delta Boron of -63.10 to - 66.67 ppm SAT: UNSAT:

NRC2010-A1b-SRO Revision: 0 SRO Review - Determination Of Reactor Shutdown Margin NRC2010-A1b-SRO.doc Page 10 of 16

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

STANDARD: Enters Uncorrected Boron Concentration is 1910 to 1930 ppm SAT: UNSAT:

STANDARD: Enters Delta Boron of -63.10 to - 66.67 ppm SAT: UNSAT:

STANDARD: (CS) Calculates Adjusted Boron Concentration of

-1973.1 to - 1996.67 ppm SAT: UNSAT:

STANDARD: (CS) Uses figure 4.1.c since Combined Reactivity is >0 and RCS Temperature is 215°F SAT: UNSAT:

STANDARD: (CS) Uses MOC line at Adjusted Boron Concentration of

~ 1984.9 PPM to obtain Differential Boron Worth of -9.1 to -9.3 pcm/ppm.

SAT: UNSAT:

NRC2010-A1b-SRO Revision: 0 SRO Review - Determination Of Reactor Shutdown Margin NRC2010-A1b-SRO.doc Page 11 of 16

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

STANDARD: Enters Combined Reactivity of 590 - 610 pcm SAT: UNSAT:

STANDARD: Enters DBW of -9.1 to -9.3 pcm/ppm SAT: UNSAT:

STANDARD: (CS) Calculates Delta Boron of -63.4 to -67.0 ppm SAT: UNSAT:

STANDARD: Enters Uncorrected Boron Concentration is 1910 to 1930 ppm SAT: UNSAT:

STANDARD: Enters Delta Boron of -63.4 to -67.0 ppm SAT: UNSAT:

STANDARD: (CS) Calculates Adjusted Boron Concentration of 1973.4 to 1997.0 ppm SAT: UNSAT:

NRC2010-A1b-SRO Revision: 0 SRO Review - Determination Of Reactor Shutdown Margin NRC2010-A1b-SRO.doc Page 12 of 16

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

Step 4.10.1 is N/A - Correction for Stuck rod is required.

Step 4.10.2 is N/A - Concentration is < 2200 PPM STANDARD: (CS) Enters Required Boron Concentration of 1973.4 to 1997.0 ppm SAT: UNSAT:

NOTE: If Candidate determines Minimum Boron Concentration is NOT MET and Emergency Boration is required, the JPM may be terminated.

STANDARD: Enters Current RCS Boron Concentration of 1810 PPM SAT: UNSAT:

STANDARD: Enters sample time of Todays date and 30 minutes ago SAT: UNSAT:

NRC2010-A1b-SRO Revision: 0 SRO Review - Determination Of Reactor Shutdown Margin NRC2010-A1b-SRO.doc Page 13 of 16

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

STANDARD: (CS) Enters Required Boron Concentration of 1973.4 to 1997.0 ppm SAT: UNSAT:

STANDARD: Enters Current RCS Boron Concentration of 1810 PPM SAT: UNSAT:

STANDARD: Determines Difference is 163.4 to 187.0 ppm SAT: UNSAT:

STANDARD: (CS) Informs US that Shutdown Margin is NOT met and that Emergency Boration is Required.

SAT: UNSAT:

JPM TERMINATION: When operator Determines that Emergency Boration is required since the Shutdown Margin is NOT met, then JPM is Complete.

NRC2010-A1b-SRO Revision: 0 SRO Review - Determination Of Reactor Shutdown Margin NRC2010-A1b-SRO.doc Page 14 of 16

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

No actions required.

NRC2010-A1b-SRO Revision: 0 SRO Review - Determination Of Reactor Shutdown Margin NRC2010-A1b-SRO.doc Page 15 of 16

Task Briefing You are the Unit Supervisor on Unit 2. Per your direction, the extra Control Room Operator completed Attachment 2 of 02-OHP-4021-001-012, Determination of Reactor Shutdown Margin.

The reactor tripped from 100% steady state operations 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> ago.

The RO calculated the required Shutdown Boron Concentration for the CURRENT RCS conditions without use of the optional Xenon Correction.

• NERDS is NOT available.

• RCS Temperature is currently 215°F.

• PPC point U0035 indicates 8500 MWD/MTU

• RCS boron concentration is 1810 ppm per a chemistry sample taken 30 minutes ago.

• All Rods are fully inserted except Control Bank D Rod D-12 which indicates 105 steps.

Perform a complete review of the completed Attachment 1, noting all errors.

NOTE Simulator Indications are NOT applicable to this JPM.

Revision: 0 NRC2010-A1b-SRO.doc Page 16 of 16

OPERATIONS JPM TRAINING PROGRAM INITIAL LICENSE TRAINING TIME: 15 MINUTES TITLE NUMBER AND NRC2010-A2 TITLE: Perform Unit 2 LTOP Verification REVISION: 0 SCOPE OF Initial Issue.

REVISION From: Audit07-A1b-R DATE:

PREPARED BY: Name:

(Exam Writer)

Signature:

APPROVED BY: Name:

(Facility Reviewer)

Signature:

NRC2010-A2 Revision: 0 Perform Unit 2 LTOP Verification NRC2010-A2.doc Page 1 of 9

OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 2-OHP-4030-214-030, R14 Daily and Shiftly Surveillance Checks K/A Number: 2.2.37 Ability to determine operability and/or availability of safety related equipment.

(CFR: 41.7 / 43.5 / 45.12)

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 Task Briefing Unit 2 TS 3.4.12 2-OHP-4030-214-030, R14, 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:

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OPERATIONS JPM SIMULATOR/LAB SETUP None.

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 The US directs you to determine whether the Unit 2 LTOP Requirements are met per 02-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20 Equipment availability, as shown below and on the attached Work Management (Open Items)

Listing:

Unit 2 Equipment Status COMPONENT NAME 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 NRC2010-A2 Revision: 0 Perform Unit 2 LTOP Verification NRC2010-A2.doc Page 3 of 9

OPERATIONS JPM 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 NOTE Simulator Indications are NOT applicable to this JPM GENERAL STANDARDS/PRECAUTIONS When directed by the Unit Supervisor, determine if the LTOP Requirements for Unit 2 are met per 02-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20.

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

General Instructions:

Provide a copy of 2-OHP-4030-214-030, Daily and Shiftly Surveillance Checks:

• Data Sheet 20

• Data Sheet 20A

• Data Sheet 20B STANDARD: (CS) Operator determines based on Task Briefing information that Data Sheet 20A, LTOP Verification LCO 3.4.12.A is applicable.

SAT: UNSAT:

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

Instructor Note: Operator will complete Data Sheet 20A, per following page prior to completing the remainder of Data Sheet 20.

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

STANDARD: (CS) Student Marks page as shown [Xs] (one PORV is operable, RHR Suction Relief In-Operable)

CUE: IF asked, THEN provide the following information for 2-NRV-153 and 2-NRV-152:

Both PZR PORVs passed their required stroke time test. Normal and Backup air supplies are available. Setpoints are within the functional testing criteria.

STANDARD: (CS) Determines that LTOP Requirements are NOT Met.

STANDARD: Informs Unit Supervisor/Shift Manager That requirements are NOT Met.

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

STANDARD: Operator completes Section 3 based in Task Brief information 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)

NRC2010-A2 Revision: 0 Perform Unit 2 LTOP Verification NRC2010-A2.doc Page 7 of 9

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

STANDARD: Operator completes Section 4.1.

SAT: UNSAT:

CUE: When reported, Acknowledge Test Results.

STANDARD: (CS) Operator completes and signs Step 4.2, including Reason for Test (Surveillance) and checking Test is complete and acceptance criteria bas NOT been met, with appropriate reason.

SAT: UNSAT:

JPM TERMINATION: When operator reports Acceptance Criteria is NOT met in section 4.2, then JPM is Complete.

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Task Briefing The US directs you to determine whether the Unit 2 LTOP Requirements are met per 02-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20 Equipment availability, as shown below and on the attached Work Management (Open Items) Listing:

Unit 2 Equipment Status COMPONENT NAME 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 RCS Lowest Cold Leg 185o F Temp Temperature 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, SI Accumulator Isolation Valves Closed & De-Energized 140 NOTE Simulator Indications are NOT applicable to this JPM Revision: 0 NRC2010-A2.doc Page 9 of 9

OPERATIONS JPM TRAINING PROGRAM INITIAL LICENSE TRAINING TIME: 15 MINUTES TITLE NUMBER AND NRC2010-A3 TITLE: Perform Monthly Rad Liquid And Gaseous Monitor REVISION: 0 Source Checks SCOPE OF Initial Issue.

REVISION From: Audit06-A1a DATE:

PREPARED BY: Name:

(Exam Writer)

Signature:

APPROVED BY: Name:

(Facility Reviewer)

Signature:

NRC2010-A3 Revision: 0 Perform Monthly Rad Liquid And Gaseous Monitor Source Checks NRC2010-A3.doc Page 1 of 6

OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 1-OHP-4030-114-030, R18 Daily And Shiftly Surveillance Checks K/A Number: 2.3.5 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

(CFR: 41.11 / 41.12 / 43.4 / 45.9)

SYS 073 A4.03 Ability to manually operate and/or monitor in the control room:

(CFR: 41.7 / 45.5 to 45.8)

Check source for operability demonstration K/A Imp.: RO: 2.9 SRO: 2.9 4.3 4.0 Task Number: 0130310201 Perform monthly source checks on Westinghouse radiation monitors.

TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS Task Briefing 1-OHP-4030-114-030, R18, Daily And Shiftly Surveillance Checks. Data Sheet 12, Monthly Rad Liquid And Gaseous Monitor Source Checks ATTACHMENTS None EVALUATION SETTINGS Classroom/Simulator EVALUATION METHOD: PERFORM: SIMULATE:

NRC2010-A3 Revision: 0 Perform Monthly Rad Liquid And Gaseous Monitor Source Checks NRC2010-A3.doc Page 2 of 6

OPERATIONS JPM SIMULATOR/LAB SETUP Unit 1 SG Blowdown is removed from service.

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 from Unit 1.

The Unit Supervisor has requested that you perform the monthly radiation monitor source checks in accordance with 1-OHP-4030-114-030, Daily And Shiftly Surveillance Checks,. Data Sheet 12, for scheduled surveillance.

Unit 1 SG Blowdown has been removed from service.

GENERAL STANDARDS/PRECAUTIONS Perform Monthly Rad Liquid And Gaseous Monitor Source Checks.

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

General Source Check Instructions: Westinghouse Rad Monitor

1) Switch to Source Check

2) Observe upscale reading

3) Reset

4) Place switch in Operate General Source Check Instructions: Eberline Rad Monitor

1) Choose Start Check Source

2) Observe upscale reading

3) Observe monitor back to Normal

4) Optional review of Source Check Report STANDARD: Operator verifies SG Blowdown has been removed from service (Or N/As step if desired).

SAT: UNSAT:

STANDARD: (CS) Operator performs successful source check of 1-R-20 on Westinghouse Rad Monitor Drawer.

SAT: UNSAT:

STANDARD: (CS) Operator performs successful source check of 1-R-28 on Westinghouse Rad Monitor Drawer.

SAT: UNSAT:

STANDARD: (CS) STANDARD: (CS) Operator performs successful source check of 1-VRS-1505 on the Eberline Rad Monitor Terminal.

SAT: UNSAT:

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

STANDARD: (CS) Operator performs successful source check of 1-R-19 on Westinghouse Rad Monitor Drawer.

SAT: UNSAT:

STANDARD: (CS) Operator performs successful source check of 1-R-24 on Westinghouse Rad Monitor Drawer.

SAT: UNSAT:

STANDARD: (CS) Operator performs successful source check of 1-DRS-3101 on the Eberline Rad Monitor Terminal.

SAT: UNSAT:

STANDARD: (CS) Operator performs successful source check of 1-DRS-3201 on the Eberline Rad Monitor Terminal.

SAT: UNSAT:

STANDARD: Operator completes step 3.1 included: WO/PMQR (N/A),

Start/Stop Time, Test Completed by section, Any Comments.

SAT: UNSAT:

JPM TERMINATION: When Data Sheet 12 has been signed at step 3.2, the JPM is Complete.

NRC2010-A3 Revision: 0 Perform Monthly Rad Liquid And Gaseous Monitor Source Checks NRC2010-A3.doc Page 5 of 6

Task Briefing You are the RO from Unit 1.

The Unit Supervisor has requested that you perform the monthly radiation monitor source checks in accordance with 1-OHP-4030-114-030, Daily And Shiftly Surveillance Checks, Data Sheet 12, for scheduled surveillance.

Unit 1 SG Blowdown has been removed from service.

Revision: 0 NRC2010-A3.doc Page 6 of 6

OPERATIONS JPM TRAINING PROGRAM INITIAL LICENSE TRAINING TIME: 25 MINUTES TITLE NUMBER AND NRC2010-A4 TITLE: Prepare Prompt NRC Notification Worksheet REVISION: 0 SCOPE OF Initial Issue.

REVISION From: N06-SRO-e DATE:

PREPARED BY: Name:

(Exam Writer)

Signature:

APPROVED BY: Name:

(Facility Reviewer)

Signature:

NRC2010-A4 Revision: 0 Prepare Prompt NRC Notification Worksheet NRC2010-A4.doc Page 1 of 13

OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: PMP-7030-001-001, R11 Prompt NRC Notification 10 CFR 50.72 Notification of NRC NUREG-1022 Recent Reporting Guidelines K/A Number: 2.4.30 Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. l (CFR: 41.10 / 43.5 / 45.11)

K/A Imp.: RO: 2.7 SRO: 4.1 Task Number: ADM1250304 Make a prompt NRC notification TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS Task Briefing Copy of procedure PMP-7030-001-001 ATTACHMENTS None EVALUATION SETTINGS Classroom EVALUATION METHOD: PERFORM: SIMULATE:

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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 You are the extra SRO.

The Shift Manager directs you to determine the NRC notification requirements and prepare an event notification worksheet (Data Sheet 1) for prompt NRC NOTIFICATION in accordance with PMP-7030-001-001.

The following plant conditions exist as noted.

• Current time is 1400

• DC Cook Unit 1 was in MODE 3 at Operating Temperature and Pressure. The Shutdown and Control Rods were fully inserted with the Reactor Trip Breakers Open.

• At 1325 today, Steam Generator #12 Safety Valve has opened and did not reseat (remains partially open).

• The Unit 1 operation crew manually initiated Safety Injection due to uncontrolled lowering of RCS temperature / pressure, and Steam Generator #12 pressure continues to lower.

• The Unit 1 operating crew has completed E-0, Reactor Trip and Safety Injection, E-2 Faulted Steam Generator Isolation, and is currently in ES-1.1, SI Termination. SI flow has been terminated per ES-1.1.

• Present RCS conditions: RCS is stable in Mode 3; level in SG #12 is at 5% WR and slowly lowering; all other SGs are being maintained between 26% and 50% NR on auxiliary feedwater; and there is no detectable radiation release in progress.

• All other plant systems responded normally to the event.

• The SM has determined that NO Emergency Classification is required per PMP-2080-EPP-101.

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

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

STANDARD: (CS) Determine from conditions stated that the event is reportable per guidance provided in PMP 7030-001-001 SAT: UNSAT:

STANDARD: Refers to FIGURE 1 to identify reportability and the reference text section for information and clarification SAT: UNSAT:

Instructor Note: Step 3.1.1.f (Filling out Data Sheet 1) will be completed following the Reportability Determination using Figure 1.

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

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

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

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

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

STANDARD: (CS) Identifies that an unplanned ECCS actuation from valid signal (Manual SI) 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:

STANDARD: Observes note of the sections in the procedure text that provide information or clarification of this flow chart determination.

SAT: UNSAT:

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

NO STEPS ON THIS PAGE APPLY TO THE STATED PLANT CONDITIONS.

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

STANDARD: (CS) Refers to sections in procedure text for information of clarification of flow chart results SAT: UNSAT:

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

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

STANDARD: (CS) Goes to Data Sheet 1 SAT: UNSAT:

CUE: The SM will notify the NRC.

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

STANDARD: Fill in applicable data to include:

• (CS) Notification of Time / Facility or organization / Unit

• CUE: Use Current time for Notification time SAT: UNSAT:

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

SAT: UNSAT:

1400 DC COOK 1 (Candidate Name) (Any Ext.)

• (CS) Event Time & Zone/ Date / Power-Mode(Before and After) 1325 EDT 6/21/10 0% / MODE 3 0%/ MODE 3 SAT: UNSAT:

• (CS) Event Classification X SAT: UNSAT:

X

• (CS) 4 hr Classification (ECCS Discharge to RCS)

SAT: UNSAT:

• Description SAT: UNSAT:

Manual ECCS Actuation on lowering RCS Temp & Pressure from steam release through SG #12 safety valve that opened and failed to reseat. RCS stable in mode three, SI terminated per ES-1.1, SI Termination, SG #12 has blown down and all other

• Notifications (NRC)

SGs are stable at 26% to 50% NR level. SAT: UNSAT:

• Other Information X

X X

• CUE: Estimated restart is 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

X X SAT: UNSAT:

X M3 (+72 hrs) X X

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

NO ITEMS ON THIS PAGE ARE APPLICABLE JPM TERMINATION: When Data Sheet is submitted for review, then JPM is complete.

NRC2010-A4 Revision: 0 Prepare Prompt NRC Notification Worksheet NRC2010-A4.doc Page 12 of 13

Task Briefing You are the extra SRO.

The Shift Manager directs you to determine the NRC notification requirements and prepare an event notification worksheet (Data Sheet 1) for prompt NRC NOTIFICATION in accordance with PMP-7030-001-001.

The following plant conditions exist as noted.

• Current time is 1400

• DC Cook Unit 1 was in MODE 3 at Operating Temperature and Pressure. The Shutdown and Control Rods were fully inserted with the Reactor Trip Breakers Open.

• At 1325 today, Steam Generator #12 Safety Valve has opened and did not reseat (remains partially open).

• The Unit 1 operation crew manually initiated Safety Injection due to uncontrolled lowering of RCS temperature / pressure, and Steam Generator #12 pressure continues to lower.

• The Unit 1 operating crew has completed E-0, Reactor Trip and Safety Injection, E-2 Faulted Steam Generator Isolation, and is currently in ES-1.1, SI Termination. SI flow has been terminated per ES-1.1.

• Present RCS conditions: RCS is stable in Mode 3; level in SG #12 is at 5% WR and slowly lowering; all other SGs are being maintained between 26% and 50% NR on auxiliary feedwater; and there is no detectable radiation release in progress.

• All other plant systems responded normally to the event.

• The SM has determined that NO Emergency Classification is required per PMP-2080-EPP-101.

Revision: 0 NRC2010-A4.doc Page 13 of 13