ML100840755
| ML100840755 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/18/2008 |
| From: | Bielby M NRC/RGN-III/DRS/OLB |
| To: | Indiana Michigan Power Co |
| References | |
| Download: ML100840755 (170) | |
Text
NRC2008-A1a TITLE Boron Volume Determination REVISION 0 PROGRAM NRC License Exam TIME 30 Minutes Revision 0: Initial Issue DATE:
DEVELOPING Name: J. T. Conrad 3/14/2008 INSTRUCTOR: Signature:
OPERATIONS REVIEW: Name:
Signature:
Page 1 of 7
TITLE: NRC2008-A1a REVISION: 0 Boron Volume Determination REFERENCES Unit 2 Technical Data Book Cycle 17 02-OHP-4021-005-002 Rev 3 Operation of the Unit 2 Boric Acid Blender K/A Number: 2.1.43 Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc..
K/A IMPORTANCE: RO: 4.1 SRO: 4.3 Task Number: 0050080101 Borate the RCS.
EVALUATION SETTING Classroom or Office HANDOUTS Task Briefing Copy of 02-OHP-4021-005-002 Attachment 9 Boron or Dilution Volume Determination Copy of Unit 2 Technical Data Book curves (Sections 3, 4, 5, 6, and 7)
ATTACHMENTS None SIMULATOR SETUP None Page 2 of 7
TITLE: NRC2008-A1a REVISION: 0 Boron Volume Determination TASK OBJECTIVES The required Boron Addition has been determined.
TASK BRIEFING You are an extra Control Room Operator on Unit 2.
The Unit Supervisor has directed you to calculate the required Boration or Dilution to restore Tave to program using Attachment 9 of 02-OHP-4021-005-002, Operation of the Unit 2 Boric Acid Blender.
NERDS is NOT available. Engineering has provided the Missing NERD information.
Reactor Power 96.3%
Tave 574.2°F Tref 573°F Boron Concentration 1095 ppm BAST Concentration 6800 ppm Core Burnup 8000 MWD/MTU Effective Fuel Temperature 1183.7°F DTC -2.164 pcm/°F Calculate ONLY the amount of Boron or PW required to be added to the VCT. Another Operator will determine the effects of the fluid within the CVCS piping.
NOTE Simulator Indications are NOT applicable to this JPM Page 3 of 7
TITLE: NRC2008-A1a - Boron Volume Determination REVISION: 0 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
ACTIONS:
STANDARD: Determines that section 4.1.2 is applicable SAT: UNSAT:
Page 4 of 7
TITLE: NRC2008-A1a - Boron Volume Determination REVISION: 0 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: CS Determines that 1.2°F temperature Reduction is required (574.2 - 573 = 1.2)
SAT: UNSAT:
STANDARD: Determines 8000 MWD/MTU is burnup SAT: UNSAT:
STANDARD: Records 1095 ppm from given information.
SAT: UNSAT:
Page 5 of 7
TITLE: NRC2008-A1a - Boron Volume Determination REVISION: 0 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: CS Determines that MTC is -10.9 pcm/°F (Range -
10.8 to -11.0)
SAT: UNSAT:
STANDARD: Determines that the Effective Fuel Temperature is 1183.7°F SAT: UNSAT:
STANDARD: Determines that the DTC is -2.164 pcm/°F SAT: UNSAT:
STANDARD: CS Determines that TC is -13.064 pcm/°F (-10.9 + -
2.164) (Range -13.0 to -13.2)
SAT: UNSAT:
STANDARD: CS Determines that PCM change is -15.68 (-13.064 pcm/°F x 1.2°F) ( Range -15.6 to -15.84)
SAT: UNSAT:
STANDARD: CS Determines that DBW is -8.07 pcm/°F (-8.0 to -
8.1)
SAT: UNSAT:
STANDARD: CS Determines that Boron change is +1.94 ppm (-
15.68 pcm/-8.07 pcm/°F) ( Range +1.925 to +1.975)
SAT: UNSAT:
Page 6 of 7
TITLE: NRC2008-A1a - Boron Volume Determination REVISION: 0 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: CS Determines that Boron change is +22.3 gallons of Boric Acid (circle Boric Acid) ( Range +22.1 to +22.7)
SAT: UNSAT:
Evaluator: This JPM is complete.
Page 7 of 7
Task Briefing You are an extra Control Room Operator on Unit 2.
The Unit Supervisor has directed you to calculate the required Boration or Dilution to restore Tave to program using Attachment 9 of 02-OHP-4021-005-002, Operation of the Unit 2 Boric Acid Blender.
NERDS is NOT available. Engineering has provided the Missing NERD information.
Reactor Power 96.3%
Tave 574.2°F Tref 573°F Boron Concentration 1095 ppm BAST Concentration 6800 ppm Core Burnup 8000 MWD/MTU Effective Fuel Temperature 1183.7°F DTC -2.164 pcm/°F Calculate ONLY the amount of Boron or PW required to be added to the VCT. Another Operator will determine the effects of the fluid within the CVCS piping.
NOTE Simulator Indications are NOT applicable to this JPM NRC2008-A1a.doc Page 1 of 1
NRC2008-A1b-R TITLE Calculate QPTR with Inoperable Power Range REVISION 0 Instrument PROGRAM Initial Licensed Operator (ILT) TIME 15 Minutes SCOPE OF REVISION:
Initial Issue From Audit07-A1a DATE:
AUTHOR Name: John T Conrad Signature:
FACILITY Name:
REVIEWER Signature:
Facility Supervisor / Manager Page 1 of 6
NRC2008-A1b-R TITLE: REVISION: 0 Calculate QPTR with Inoperable Power Range Instrument REFERENCES 01-OHP-4030-114-032, Rev 0, Quadrant Power Tilt Calculation Task: 0130180201 Perform Quadrant Power Tilt Ratio Calculation K/A CROSS
REFERENCE:
2.1.7 Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrumentation interpretation K/A IMPORTANCE: RO 4.4 SRO 4.7 EVALUATION SETTINGS Classroom HANDOUTS Task Briefing 01-OHP-4030-114-032 and Data Sheet 3 ATTACHMENTS NI Calibration Data Card N41, N42, N43, and N44 Pictures SIMULATOR SETUP N/A Page 2 of 6
NRC2008-A1b-R TITLE: REVISION: 0 Calculate QPTR with Inoperable Power Range Instrument TASK OBJECTIVES/STANDARDS Correctly obtain values and calculates a Quadrant Power Tilt Ratio calculation with one power range channel out-of-service using 01-OHP-4030-114-032.
TASK BRIEFING You are an extra RO.
The following conditions exist:
- NI Channel N-42 has failed low
- Unit 1 is currently at 72% power.
- All actions of 01-OHP-4022-013-004, Power Range Malfunction have been completed
- The Plant Process Computer (PPC) is INOPERABLE The US directs you to perform a manual QPTR calculation per 01-OHP-4030-114-032, Quadrant Power Tilt Calculation.
The NI amp meters are set to display maximum resolution and the fluke readings confirm that the indicators are reading properly.
Page 3 of 6
NRC2008-A1b-R TITLE: REVISION: 0 Calculate QPTR with Inoperable Power Range Instrument EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator records Upper & Lower Detector blanks for N-41, 43 and 44 on Data Sheet 3.
SAT: UNSAT:
Instructor Note: See Page 3 For expected values (Spreadsheet program may be used to verify accuracy of candidate readings and calculations)
STANDARD: CS Operator records NI detector readings (within
+0.5) on a division mark and within the division marks for all others. (Enter data into spreadsheet for comparison)
SAT: UNSAT:
STANDARD: CS Operator enters data from cards provided.
SAT: UNSAT:
STANDARD: Operator divides respective NI channel with its 120%
value (from cards on channel 3 NI panel)
SAT: UNSAT:
STANDARD: Operator totals 3 channels of normalized values SAT: UNSAT:
STANDARD: CS: Operator determines upper and lower QPTR using data sheet 3 with an accuracy of .01 of Exam Team calculated value (Enter data into spreadsheet for comparison)
N/A SAT: UNSAT:
STANDARD: Operator enters the highest calculated QPTR (CS:
Covered on Page 6 of this section)
SAT: UNSAT:
Page 4 of 6
NRC2008-A1b-R TITLE: REVISION: 0 Calculate QPTR with Inoperable Power Range Instrument EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: CS Operator Determines that Acceptance Criteria is NOT Met (QPTR > 1.02) and Notifies SM & Reactor Engineering SAT: UNSAT:
CUE: SM Acknowledges that QPTR has Exceeded TS value and will address the required actions.
Page 5 of 6
NRC2008-A1b-R TITLE: REVISION: 0 Calculate QPTR with Inoperable Power Range Instrument EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) 41 98.8 135.4 .7297 43 98.4 134.4 .7321 Data entered on this page based on Simulator readings.
44 98.0 136.7 .7169 Enter data into QPTR calculation spreadsheet to determine 2.1787 accuracy of candidates calculation 41 91.8 135.6 .6770 43 98.2 134.7 .7290 44 97.3 136.2 .7144 2.1204 Reference Step 4.3.6 for criteria 1.0081 STANDARD: CS Operator enters the highest calculated QPTR of these 2 values 1.0314 STANDARD: Candidate marks N/A 1.0314 STANDARD: CS Operator Determines that Acceptance Criteria is N/A NOT Met (QPTR > 1.02) and Notifies SM & Reactor Engineering STANDARD: Candidate Signs, Dates, & enters Time Reports task completed.
CUE: SM Acknowledges that QPTR has Exceeded TS value and will address the required actions.
Evaluator: This JPM is complete.
Page 6 of 6
Task Briefing You are an extra RO.
The following conditions exist:
- NI Channel N-42 has failed low
- Unit 1 is currently at 72% power.
- All actions of 01-OHP-4022-013-004, Power Range Malfunction have been completed
- The Plant Process Computer (PPC) is INOPERABLE The US directs you to perform a manual QPTR calculation per 01-OHP-4030-114-032, Quadrant Power Tilt Calculation.
The NI amp meters are set to display maximum resolution and the fluke readings confirm that the indicators are reading properly.
NRC2008-A1b-R.doc Page 1 of 1
NRC2008-A1b-S TITLE Review QPTR with Inoperable Power Range REVISION 0 Instrument PROGRAM Initial Licensed Operator (ILT) TIME 15 Minutes SCOPE OF REVISION:
Initial Issue From Audit07-A1a DATE:
AUTHOR Name: John T Conrad Signature:
FACILITY Name:
REVIEWER Signature:
Facility Supervisor / Manager Page 1 of 7
NRC2008-A1b-S TITLE: REVISION: 0 Review QPTR with Inoperable Power Range Instrument References 01-OHP-4030-114-032, Rev 0, Quadrant Power Tilt Calculation Task: 0130180201 Perform Quadrant Power Tilt Ratio Calculation K/A CROSS
REFERENCE:
2.1.7 Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrumentation interpretation K/A IMPORTANCE: RO 4.4 SRO 4.7 Evaluation Setting Classroom Handouts Task Briefing Completed 01-OHP-4030-114-032 and Data Sheet 3 Attachments NI Calibration Data Card N41, N42, N43, and N44 Pictures Simulator Setup
- N/A Page 2 of 7
NRC2008-A1b-S TITLE: REVISION: 0 Review QPTR with Inoperable Power Range Instrument Task Objectives/Standards Review a Quadrant Power Tilt Ratio calculation with one power range channel out-of-service using 01-OHP-4030-114-032 and identify error and required TS Actions.
Task Briefing You are the Unit SRO.
The following conditions exist:
- NI Channel N-42 has failed low
- Unit 1 is currently at 72% power.
- All actions of 01-OHP-4022-013-004, Power Range Malfunction have been completed
- The Plant Process Computer (PPC) is INOPERABLE The SM directs you to Review the manual 01-OHP-4030-114-032, Quadrant Power Tilt Calculation.
The NI amp meters are set to display maximum resolution and the fluke readings confirm that the indicators are reading properly.
Page 3 of 7
NRC2008-A1b-S TITLE: REVISION: 0 Review QPTR with Inoperable Power Range Instrument EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) 41 98.8 135.4 .7297 43 98.4 134.4 .7321 44 98.0 136.7 .7169 2.1787 41 91.8 135.6 .6770 43 98.2 134.7 .7290 44 97.3 136.2 .7144 2.1204 1.0081 STANDARD: CS Operator identifies that value was incorrectly 1.0031 calculated. Should be 1.0314 resulting in excessive QPTR.
(Range of 1.030 to 1.032) 1.0081 SAT: UNSAT:
N/A STANDARD: CS Operator Determines that Acceptance Criteria is NOT Met (QPTR > 1.02) and Notifies SM SAT: UNSAT:
Page 4 of 7
NRC2008-A1b-S TITLE: REVISION: 0 Review QPTR with Inoperable Power Range Instrument EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: CS Operator Determines that Acceptance Criteria is NOT Met (QPTR > 1.02) and Notifies SM & Reactor Engineering SAT: UNSAT:
CUE: SM Acknowledges that QPTR has Exceeded TS value requests that you review the Required Technical Specification and determine the required Actions.
Page 5 of 7
NRC2008-A1b-S TITLE: REVISION: 0 Review QPTR with Inoperable Power Range Instrument EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
CUE: (If Required) Ask Operator to calculate the Technical Specification Power Limit that applies.
STANDARD: CS Determines that Power is limited to 3% for each 1% over 1.00 (3.14 x 3% = 9.42%) per LCO 3.2.4 Action A.1 -
(note power limit is from RTP - 90.58% is limit)
(Range of 9% to 9.6% reduction and 90.4% to 91% power limit)
SAT: UNSAT:
STANDARD: Also Determines that QPTR must be calculated C W every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, Verify F Q (Z ) is within limit., Verify F Q (Z ) is N
within limit, & Verify F h is within limits specified in the COLR.
SAT: UNSAT:
Page 6 of 7
NRC2008-A1b-S TITLE: REVISION: 0 Review QPTR with Inoperable Power Range Instrument EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Identify that safety analyses must be evaluated before raising power above 90.58%
SAT: UNSAT:
STANDARD: A.5 & A.6 required if power is raised above 90.58%
SAT: UNSAT:
Evaluator: This JPM is complete.
Page 7 of 7
Task Briefing You are the Unit SRO.
The following conditions exist:
- NI Channel N-42 has failed low
- Unit 1 is currently at 72% power.
- All actions of 01-OHP-4022-013-004, Power Range Malfunction have been completed
- The Plant Process Computer (PPC) is INOPERABLE The SM directs you to Review the manual 01-OHP-4030-114-032, Quadrant Power Tilt Calculation.
The NI amp meters are set to display maximum resolution and the fluke readings confirm that the indicators are reading properly.
NRC2008-A1b-S.doc Page 1 of 1
NRC2008-A2 TITLE SRO Review of Unit 1 LTOP Verification REVISION 0 PROGRAM Initial Licensed Operator (ILT) TIME 15 Minutes SCOPE OF REVISION:
Initial Issue.
Derived from NRC2004-A1b DATE:
AUTHOR Name: John T Conrad Signature:
FACILITY Name:
REVIEWER Signature:
Facility Supervisor / Manager Page 1 of 4
TITLE: NRC2008-A2 - SRO Review of Unit 1 LTOP REVISION: 0 Verification REFERENCES 01-OHP-4030-114-030 Rev. 15 Daily and Shiftly Surveillance Checks Task: STP0390201 Perform Shiftly Surveillance checks for MODE 5 & 6 K/A: 2.2.42 Ability to recognize indications for system operating parameters that are entry-level conditions for technical specifications.
K/A IMPORTANCE: RO 3.9 SRO 4.6 EVALUATION SETTING Classroom HANDOUTS Task Briefing Review copy of Completed 01-OHP-4030-114-030, Daily and Shiftly Surveillance Checks, Data Sheet 20A ATTACHMENTS None SIMULATOR SETUP N/A TASK OBJECTIVES/STANDARDS When directed by the Shift Manager, perform the SRO review of the completed LTOP Verification and determine if the LTOP Requirements for Unit 1 are met per 01-OHP-4030-114-030, Daily and Shiftly Surveillance Checks, Data Sheet 20A Page 2 of 4
TITLE: NRC2008-A2 - SRO Review of Unit 1 LTOP REVISION: 0 Verification TASK BRIEFING The SM directs you to perform the SRO review of the completed LTOP Verification 01-OHP-4030-114-030, Daily and Shiftly Surveillance Checks, Data Sheet 20A.
Equipment availability, as shown below:
Unit 1 Equipment Status COMPONENT NAME STATUS 1-NMO-152 PORV Block Valve Open & Energized 1-NMO-153 PORV Block Valve Open & Energized 1-NRV-152 Control Cold Over-Pressure Block for Cold Over Press Selector 1-NRV-152 1-NRV-153 Control Cold Over-Pressure Block for Cold Over Press Selector 1-NRV-153 1-IMO-128 Return from Hot Leg 2 Open & Energized 1-ICM-129 Return from Hot Leg 2 Open & Energized 1-SV-103 RHR Suction Relief Setpoint = 455 psig Annunciator Panel 108 1-NRV-152 EMER AIR TANK NOT Lit Drop 27 PRESSURE LOW Annunciator Panel 108 1-NRV-153 EMER AIR TANK Lit Drop 28 PRESSURE LOW 1-PP-50E East Centrifugal Charging Pump PTL (Racked Out) 1-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 PI-403 RCS Highest Reading Pressure 230 psig Both SI Pumps Safety Injection Pumps PTL (Racked Out) 1-NTA-251 Pressurizer Liquid Temp 400o F 1-IMO-110, 120, 130, 140 SI Accumulator Isolation Valves Closed & De-Energized NOTE Simulator Indications are NOT applicable to this JPM Page 3 of 4
TITLE: NRC2008-A2 - SRO Review of Unit 1 LTOP Verification REVISION: 0 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Instructor Note: Provide a Copy of Field Copy of 01-OHP-4030-114-030, Daily and Shiftly Surveillance Checks, Data Sheet 20. (If Required prompt SRO to identify TS and Correct the DS after determining the Error)
STANDARD: CS SRO Reviews Chart and determines that RHR Suction Relief In-Operable (one PORV is also in-operable)
Xs in Circles are wrong, Empty Circles Should Have Xs SAT: UNSAT:
CUE: (IF asked, then provide the following information for NRV-153 and 1-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.
SAT: UNSAT:
STANDARD: Informs Shift Manager that requirements are NOT Met and determines that Action F applies (Mode 5 - One required relief is In-operable)
SAT: UNSAT:
N/A Instructor Note: DataSheet 20B is for LCO 3.4.12.B when Both CCPs are available.
EVALUATOR: This JPM is complete.
Page 4 of 4
Task Briefing The SM directs you to perform the SRO review of the completed LTOP Verification 01-OHP-4030-114-030, Daily and Shiftly Surveillance Checks, Data Sheet 20A Equipment availability, as shown below:
Unit 2 Equipment Status COMPONENT NAME STATUS 1-NMO-152 PORV Block Valve Open & Energized 1-NMO-153 PORV Block Valve Open & Energized 1-NRV-152 Control Cold Over-Pressure Block for Cold Over Press Selector 1-NRV-152 1-NRV-153 Control Cold Over-Pressure Block for Cold Over Press Selector 1-NRV-153 1-IMO-128 Return from Hot Leg 2 Open & Energized 1-ICM-129 Return from Hot Leg 2 Open & Energized 1-SV-103 RHR Suction Relief Setpoint = 455 psig Annunciator Panel 108 1-NRV-152 EMER AIR TANK NOT Lit Drop 27 PRESSURE LOW Annunciator Panel 108 1-NRV-153 EMER AIR TANK Lit Drop 28 PRESSURE LOW 1-PP-50E East Centrifugal Charging Pump PTL (Racked Out) 1-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 PI-403 RCS Highest Reading Pressure 230 psig Both SI Pumps Safety Injection Pumps PTL (Racked Out) 1-NTA-251 Pressurizer Liquid Temp 400o F 1-IMO-110, 120, 130, 140 SI Accumulator Isolation Valves Closed & De-Energized NOTE Simulator Indications are NOT applicable to this JPM NRC2008-A2.doc Page 1 of 1
NRC2008-A3 TITLE: Perform Containment Pressure Relief REVISION: 0 PROGRAM NRC License Exam TIME: 20 Minutes From NRC2004-A3 DATE:
DEVELOPING Name: J. T. Conrad 3/14/2008 INSTRUCTOR: Signature:
OPERATIONS REVIEW: Name:
Signature:
Page 1 of 14
TITLE: NRC2008-A3 REVISION: 0 Perform Containment Pressure Relief REFERENCES 02-OHP 4021.028.004, Rev. 18 Operation of the Containment Pressure Relief System TASK: 0280080101 Perform A Containment Pressure Relief K/A: 2.3.11 Ability to control radiation releases K/A IMPORTANCE: RO 3.8 SRO 4.3 Evaluation Setting Unit 2 Simulator Handouts Task Briefing 02-OHP 4021.028.004, Operation of the Containment Pressure Relief System ATTACHMENTS None SIMULATOR SETUP
- 1. Reset the simulator to IC 35 .
- 2. Place simulator in RUN.
- 3. MRF CHR16 to 29.65 (barometric pressure)
- 4. Verify Lower Containment pressure at ~ 0.19-.20 psig.
- 5. Trigger 1 = RM02Q1 @ 0.48% with 30 sec delay {assign to trigger file CPR fan to start}
Page 2 of 14
TITLE: NRC2008-A3 REVISION: 0 Perform Containment Pressure Relief Task Objectives Perform a containment pressure relief as directed by procedure including correctly determining status of the relevant radiation monitors and correctly performing a flow estimate per 12-PMP-6010.OSD.001, Offsite Dose Calculation manual.
Task Briefing Lower containment pressure has risen to approximately 0.19 psig due to atmospheric pressure changes. All RMS channels are operable.
The Unit Supervisor directs you to perform a containment pressure relief to lower containment pressure to 0 psig in accordance with 02-OHP-4021-028-004, Operation of Containment Pressure Relief System. All initial conditions are satisfied.
Perform the containment pressure relief to lower containment pressure using the HIGHEST reading pressure channel.
Page 3 of 14
TITLE: NRC2008-A3 - Perform Containment Pressure Relief REVISION: 0 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
CUE: Procedure has been revision checked.
{NOTE: Not part of JPM.}
CUE: Precautions have been reviewed and discussed in the task briefing.
{NOTE: Not part of JPM.}
Page 4 of 14
TITLE: NRC2008-A3 - Perform Containment Pressure Relief REVISION: 0 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Information in this note is typically reviewed and discussed in task briefing.
NOTE: Not part of JPM.
CUE: None of the planned evolution activities are scheduled during the time we will be performing the pressure relief.
{NOTE: JPM starts here.}
STANDARD: Operator verifies that all listed monitors are functioning properly SAT: UNSAT:
CUE: If asked, AEO reports that 2-VFS-2521 is operating within the Normal range.
STANDARD: Operator determines that ALL channels are OPERABLE SAT: UNSAT:
Page 5 of 14
TITLE: NRC2008-A3 - Perform Containment Pressure Relief REVISION: 0 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
N/A N/A NOTE: This is typically reviewed and discussed as part of the task briefing.
CUE: Shift Manager deems NONE of these actions as necessary.
Page 6 of 14
TITLE: NRC2008-A3 - Perform Containment Pressure Relief REVISION: 0 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
NOTE: Data is recorded on Section A of Data Sheet 1 (FYI Page 13 of JPM)
STANDARD: Enter Next CPR number CUE: Next Containment Pressure Relief Number is 08-0058 SAT: UNSAT:
STANDARD: CS Record Vent Flow from 2-VFR-2510 or 2-VFR-315 on recorder 2-MR-54 and circles source SAT: UNSAT:
STANDARD: CS Record Containment Pressure SAT: UNSAT:
STANDARD: CS Record Radiation Monitor readings SAT: UNSAT:
STANDARD: CS Perform Source Check on 2-ERS-2305 SAT: UNSAT:
STANDARD: CS Perform Source Check on 2-ERS-2405 SAT: UNSAT:
N/A STANDARD: Verify all Trip block switches in NORMAL SAT: UNSAT:
{NOTE: 2300/2305 and 2400/2405 TRIP/BLOCK is performed by one switch action.}
Page 7 of 14
TITLE: NRC2008-A3 - Perform Containment Pressure Relief REVISION: 0 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Initial Data Sheet 1 SAT: UNSAT:
N/A N/A Page 8 of 14
TITLE: NRC2008-A3 - Perform Containment Pressure Relief REVISION: 0 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
NOTE: These contingencies may be reviewed by the Operator.
They will be used later in this JPM and are repeated when appropriate.
Page 9 of 14
TITLE: NRC2008-A3 - Perform Containment Pressure Relief REVISION: 0 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
CUE: If asked, 2-VFC-207 Containment Pressure Relief Flow controller is set at 500 cfm.
STANDARD: CS Places 2-VCR-107 to OPEN.
SAT: UNSAT:
STANDARD: CS Places 2-VCR-207 to OPEN and holds.
SAT: UNSAT:
CUE: After VCR-107 and VCR-207 are open, US directs you to start HV-CPR-1, CNTMT Pressure Relief Vent Unit.
STANDARD: CS 2-HV-CPR-1 Fan switch is placed in START.
{NOTE: Rad Alarm on VRS-2501 in ~30 secs)
SAT: UNSAT:
N/A STANDARD: Operator records start time in Section B SAT: UNSAT:
Page 10 of 14
TITLE: NRC2008-A3 - Perform Containment Pressure Relief REVISION: 0 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator reports HI Alarm on VRA-2501 SAT: UNSAT:
STANDARD: CS Operator places 2-HV-CPR-1 fan to STOP SAT: UNSAT:
STANDARD: CS Operator places 2-VCR-107 to CLOSE SAT: UNSAT:
STANDARD: CS Operator places 2-VCR-207 to CLOSE SAT: UNSAT:
STANDARD: Operator records unit vent flow rate SAT: UNSAT:
STANDARD: Operator request RP recalculate High alarm setpoint SAT: UNSAT:
EVALUATOR: JPM is COMPLETE Page 11 of 14
TITLE: NRC2008-A3 - Perform Containment Pressure Relief REVISION: 0 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
NOTE: Included for information only.
Page 12 of 14
TITLE: NRC2008-A3 - Perform Containment Pressure Relief REVISION: 0 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
NOTE: Included for information only.
Page 13 of 14
TITLE: NRC2008-A3 - Perform Containment Pressure Relief REVISION: 0 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
NOTE: Included for information only.
Page 14 of 14
Task Briefing Lower containment pressure has risen to approximately 0.19 psig due to atmospheric pressure changes. All RMS channels are operable.
The Unit Supervisor directs you to perform a containment pressure relief to lower containment pressure to 0 psig in accordance with 02-OHP-4021-028-004, Operation of Containment Pressure Relief System. All initial conditions are satisfied.
Perform the containment pressure relief to lower containment pressure using the HIGHEST reading pressure channel.
NRC2008-A3.doc Page 1 of 1
NRC2008-A4-R TITLE Complete EMD-32a Nuclear Plant Notification REVISION 0 Form PROGRAM Initial Licensed Operator (ILT) TIME 10 Minutes SCOPE OF REVISION:
Initial Issue From NRC2004-A4 DATE:
AUTHOR Name: John T Conrad Signature:
FACILITY Name:
REVIEWER Signature:
Facility Supervisor / Manager Page 1 of 5
TITLE: NRC2008-A4-R REVISION: 0 Complete EMD-32a Nuclear Plant Event Notification REFERENCES Procedure: PMP-2080-EPP-108, Initial Dose Assessment Task: EPP 0030701 Perform Initial Offsite Notification K/A: 2.4.39 Knowledge of RO responsibilities in emergency plan implementation K/A IMPORTANCE: SRO 3.9 RO 3.8 EVALUATION SETTING Classroom HANDOUTS Task Briefing & MIDAS Summary EMD-32a Nuclear Plant Event Notification (blank form)
ATTACHMENTS None SIMULATOR SETUP None TASK OBJECTIVES/STANDARDS Complete the EMD-32a, Nuclear Plant Event Notification form to notify of state/county agencies within 15 minutes.
Page 2 of 5
TITLE: NRC2008-A4-R REVISION: 0 Complete EMD-32a Nuclear Plant Event Notification TASK BRIEFING You are an extra Control Room Operator on Unit 1.
At the beginning of your shift, Unit 1 was operating at 100% rated power with the turbine-driven auxiliary feed water pump tagged out for maintenance.
A loss of heat sink has occurred leading to the implementation of 01-OHP-4023-FR-H.1, Response to Loss of Secondary Heat Sink. Operators have been dispatched to remove the clearance on the turbine-driven auxiliary feed water pump.
The Shift Manager has just declared a SITE AREA EMERGENCY per initiating condition System Malfunction S-5, Loss of Hot SD Sys. The plant is currently STABLE.
Classification Time is (Use Current Time _________ & have candidate enter on briefing handout)
THIS IS A TIME CRITICAL JPM The Shift Manager directs you as the Plant Communicator to complete EMD-32a, Nuclear Plant Event Notification form for approval.
All radiation monitors are indicating normal activity / expected levels. There are NO radiation alarms.
Meteorological Data - MIDAS Summary is provided.
NOTE Simulator Indications are NOT applicable to this JPM Page 3 of 5
TITLE: NRC2008-A4-R - Complete EMD-32a Nuclear Plant Event Notification REVISION: 0 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
All items should be completed on the form prior to submitting to the Site Emergency Coordinator for approval.
STANDARD: Drill box marked (for purposes of this JPM Actual Event is also acceptable)
SAT: UNSAT:
STANDARD:
- 1 entered as Plant Message Number since this is the initial notification (1CR is also acceptable)
- Candidate enters name as Plant Communicator
- Control Room box marked
- CUE: If asked, Time of Commuication is current time.
SAT: UNSAT:
STANDARD: CS
- SITE AREA EMERGENCY box MUST be marked
- Current date and time of Classification (Given during the briefing) MUST be filled in SAT: UNSAT:
STANDARD: CS
- System Malfunction box marked
- S-5 MUST be filled in SAT: UNSAT:
CONTINUED ON NEXT PAGE.
Page 4 of 5
TITLE: NRC2008-A4-R - Complete EMD-32a Nuclear Plant Event Notification REVISION: 0 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: CS None box MUST be marked SAT: UNSAT:
STANDARD: CS No box MUST be marked SAT: UNSAT:
STANDARD: Stability Class D filled in SAT: UNSAT:
STANDARD: CS Wind from 312 to 132 filled in SAT: UNSAT:
STANDARD: Precipitation Yes box marked SAT: UNSAT:
STANDARD: CS Wind speed 8 mph filled in SAT: UNSAT:
STANDARD: CS Candidate reports complete and ready for SEC/SM approval. Completion Time _________ (</= 15 minutes)
SAT: UNSAT:
EVALUATOR: This JPM is complete.
Page 5 of 5
Task Briefing You are an extra Control Room Operator on Unit 1.
At the beginning of your shift, Unit 1 was operating at 100% rated power with the turbine-driven auxiliary feed water pump tagged out for maintenance.
A loss of heat sink has occurred leading to the implementation of 01-OHP-4023-FR-H.1, Response to Loss of Secondary Heat Sink. Operators have been dispatched to remove the clearance on the turbine-driven auxiliary feed water pump.
The Shift Manager has just declared a SITE AREA EMERGENCY per initiating condition System Malfunction S-5, Loss of Hot SD Sys. The plant is currently STABLE.
Classification Time is (Enter Current Time _________ )
THIS IS A TIME CRITICAL JPM The Shift Manager directs you as the Plant Communicator to complete EMD-32a, Nuclear Plant Event Notification form for approval.
All radiation monitors are indicating normal activity / expected levels. There are NO radiation alarms.
Meteorological Data - MIDAS Summary is provided.
NOTE Simulator Indications are NOT applicable to this JPM NRC2008-A4-R.doc Page 1 of 2
Meteorological Data - MIDAS Summary Delta Temperature - Main Tower -0.4°F Wind Direction 10M - Main Tower 312° Wind Speed 10M - Main Tower 8 mph Precipitation - Main Tower Rain Wind Direction 10M - Backup Tower 318° Wind Speed 10M - Backup Tower 10 mph Wind Direction 60M - Main Tower 321° Wind Speed 60M - Main Tower 11 mph Standard Deviation 10M Main 0° Standard Deviation 10M Backup 0° Standard Deviation 10M Main 0° Pasquill Category D Outside Temperature 50.2°F Lake Breeze NA NRC2008-A4-R.doc Page 2 of 2
NRC2008-A4-S TITLE Emergency Plan Classification With PAR REVISION 0 PROGRAM NRC License Exam TIME 15 Minutes Minor Revision: Updated from Audit06-A5 & SR-O-E008 with current revisions.
DATE:
DEVELOPING Name: J. T. Conrad 3/14/2008 INSTRUCTOR: Signature:
OPERATIONS REVIEW: Name:
Signature:
Page 1 of 3
NUMBER AND NRC2008-A4-S TITLE: REVISION: 0 Emergency Plan Classification With PAR REFERENCES Procedure:
PMP-2080-EPP-101 Revision 12 Emergency Classification Task: EPP0020703 Classify an Emergency Condition K/A: 2.4.41 Knowledge of the emergency action level thresholds and classifications K/A IMPORTANCE: SRO 4.6 RO 2.9 Procedure:
PMP-2080-EPP-100 revision 11 Emergency Response Task EPP0120703 Develop a Protective Action Recommendation K/A: 2.4.44 Knowledge of the emergency plan protective action recommendations K/A IMPORTANCE: SRO 4.4 RO 2.4 EVALUATION SETTING Classroom or office HANDOUTS Task Briefing ATTACHMENTS None SIMULATOR SETUP None Page 2 of 8
NUMBER AND NRC2008-A4-S TITLE: REVISION: 0 Emergency Plan Classification With PAR TASK OBJECTIVES/STANDARDS In accordance with procedures when an emergency event has occurred or changed, the operator will be able to:
- 1. Classify an Emergency Condition
- 2. Develop a Protective Action Recommendation TASK BRIEFING You are the Shift Manager.
Unit 1 was at 100% power with the West CCP on clearance for pump overhaul when a Small Break LOCA event occurs and the Unit automatically trips. Both SI pumps trip on over current and CTS actuates automatically with RCPs secured by the RO shortly thereafter. The crew had transitioned to OHP-4023-E-1, Loss of Reactor or Secondary Coolant, and was working their way through the procedure, when the STA reported a RED CSFST indication on Core Cooling. The crew then transitioned to OHP-4023-FR-C.1, Response to Inadequate Core Cooling, which has been implemented for 20 minutes without restoring core cooling.
The following plant conditions exist:
CETC readings of the five highest temperatures indicate 860 °F and rising RCS pressure is 750 psig and slowly rising Containment pressure is 2 psig and slowly lowering Containment radiation is 250 R/hr and slowly rising Narrow range RVLIS indicates 44% and slowly lowering The MET data indicates no precipitation with the wind from 220° at 8 mph and NO offsite release is occurring.
The weather forecast is Sunny with a high of 75°F. No major traffic conditions exist.
THIS JPM IS TIME CRITICAL Record Start Time __________________
Inform the examiner of the Emergency Classification of this event and any applicable Protective Action Recommendations.
NOTE Simulator Indications are NOT applicable to this JPM Page 3 of 8
NUMBER AND NRC2008-A4-S Emergency Plan Classification With PAR REVISION: 0 TITLE:
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
The trainee should refer to PMP-2080-EPP-101, Emergency Classification, Attachment 1.
STANDARD: Candidate determines LOSS of Fuel Clad Barrier based upon 1.1 and/or 1.2 SAT: UNSAT:
STANDARD: Candidate determines LOSS of RCS Barrier based upon 2.1 and/or 2.3 SAT: UNSAT:
STANDARD: Candidate determines POTIENTIAL LOSS of Containment based upon 3.7 (Next Page)
SAT: UNSAT:
STANDARD: CS The classification for this event is General Emergency.
SAT: UNSAT:
STANDARD: CS Record Classification Time ______________
(</= 15 minutes from Start)
SAT: UNSAT:
Page 4 of 8
NUMBER AND NRC2008-A4-S Emergency Plan Classification With PAR REVISION: 0 TITLE:
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Candidate determines POTENTIAL LOSS of Containment based upon 3.7 (Continued)
Page 5 of 8
NUMBER AND NRC2008-A4-S Emergency Plan Classification With PAR REVISION: 0 TITLE:
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Candidate determines PAR recommendations:
NOTE: A General Emergency requires a protective action recommendation be made to the state.
Next page.
Page 6 of 8
NUMBER AND NRC2008-A4-S Emergency Plan Classification With PAR REVISION: 0 TITLE:
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
CUE, If asked,: No Dangerous Road/Travel conditions STANDARD: CS Even though there is NO offsite release occurring, a protective action recommendation is still required based on the General Emergency classification.
SAT: UNSAT:
Page 7 of 8
NUMBER AND NRC2008-A4-S Emergency Plan Classification With PAR REVISION: 0 TITLE:
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Wind is from 220°.
SAT: UNSAT:
STANDARD: Downwind sector is C and adjacent sectors are sectors B and D.
SAT: UNSAT:
STANDARD: CS Protective Action Recommendation is to Evacuate areas 1, 2 and 3.
SAT: UNSAT:
Student informs examiner that this event is classified as a General Emergency with a Protective Action Recommendation to Evacuate areas 1, 2 and 3.
STANDARD: Record PARS Time ______________ (</= 15 minutes from Classification Time)
SAT: UNSAT:
JPM IS COMPLETE Page 8 of 8
Task Briefing You are the Shift Manager.
Unit 1 was at 100% power with the West CCP on clearance for pump overhaul when a Small Break LOCA event occurs and the Unit automatically trips. Both SI pumps trip on over current and CTS actuates automatically with RCPs secured by the RO shortly thereafter. The crew had transitioned to OHP-4023-E-1, Loss of Reactor or Secondary Coolant, and was working their way through the procedure, when the STA reported a RED CSFST indication on Core Cooling. The crew then transitioned to OHP-4023-FR-C.1, Response to Inadequate Core Cooling, which has been implemented for 20 minutes without restoring core cooling.
The following plant conditions exist:
CETC readings of the five highest temperatures indicate 860 °F and rising RCS pressure is 750 psig and slowly rising Containment pressure is 2 psig and slowly lowering Containment radiation is 250 R/hr and slowly rising Narrow range RVLIS indicates 44% and slowly lowering The MET data indicates no precipitation with the wind from 220° at 8 mph and NO offsite release is occurring.
The weather forecast is Sunny with a high of 75°F. No major traffic conditions exist.
THIS JPM IS TIME CRITICAL Record Start Time __________________
Inform the examiner of the Emergency Classification of this event and any applicable Protective Action Recommendations.
NOTE Simulator Indications are NOT applicable to this JPM NRC2008-A4-S.doc Page 1 of 1
NRC2008-Sim01 TITLE Dilute the RCS (ALT) REVISION 0 PROGRAM Initial Licensed Operator (ILT) TIME 15 Minutes SCOPE OF REVISION:
Initial Issue DATE:
AUTHOR Name: John T Conrad Signature:
FACILITY Name:
REVIEWER Signature:
Facility Supervisor / Manager Page 1 of 9
TITLE: NRC2008-Sim01 (ALT) REVISION: 0 Dilute the RCS.
REFERENCES 02-OHP 4021-005-002, Rev. 3, Operation of the Unit 2 Boric Acid Blender Task: 0050090101 Dilute the RCS K/A: SYS 004 A4.12 CVCS - Ability to manually operate Boration/Dilution batch control K/A IMPORTANCE: RO: 3.3 SRO 3.8 EVALUATION SETTINGS Simulator HANDOUTS Task Brief Copy of 02-OHP 4021-005-002 Body & Attachments 1,4, 5,10, & 11 ATTACHMENTS
- 1. NONE SIMULATOR SETUP
- 1. Initialize to IC 971 (Mode 3)
- 2. Verify ZGI101QRV451 overide to CLOSE
- 3. Set the PW totalizer to a random value (Not = 100)
- 4. Freeze the simulator.
Page 2 of 9
TITLE: NRC2008-Sim01 (ALT) REVISION: 0 Dilute the RCS.
TASK OBJECTIVES/STANDARDS Add 100 gallons of primary water to the RCS in accordance with 02-OHP-4021-005-002, Operation of the Unit 2 Boric Acid Blender using Normal Dilute Mode.
TASK BRIEFING You are the extra RO.
The following conditions exist:
- Unit is in Mode 3 preparing for startup.
- BAST Boron concentration is 6600 ppm.
- Makeup control set for auto.
- The makeup line is full of primary water.
The US directs you to add 100 gallons of primary water to the RCS in accordance with 02-OHP-4021-005-002, Operation of the Unit 2 Boric Acid Blender using Normal Dilute Mode.
You are to restore the blender alignment for Auto makeup.
Page 3 of 9
TITLE: NRC2008-Sim01 - Dilute the RCS. (ALT) REVISION: 0 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
CUE: The Prerequisites, Precautions and Limitations have been met.
STANDARD: Operator verifies Blender Aligned for Automatic Operation (May reference Attachment 1 of this procedure)
SAT: UNSAT:
CUE: Reactor Engineer has requested and the SRO has verified the need to Dilute the RCS by adding 100 gallons of pure water.
STANDARD: Places switch to STOP SAT: UNSAT:
STANDARD: CS Places switch to DILUTE SAT: UNSAT:
STANDARD: CS PW batch counter set to 100 gallons (using Pre A P/B)
SAT: UNSAT:
STANDARD: PW flow can be set to any non-zero value.
SAT: UNSAT:
CUE: If required, Acknowledge as US Expected Alarm STANDARD: CS Places switch to START (See next page for Automatic Actions)
SAT: UNSAT:
CUE, if required: Multiple Dilutions are NOT expected.
Page 4 of 9
TITLE: NRC2008-Sim01 - Dilute the RCS. (ALT) REVISION: 0 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
NOTE: Automatic Actions listed are from Precautions &
Limitations Section. Operator may continue with Attachment 4 as shown on next page.
STANDARD: Verifies PW pump starts SAT: UNSAT:
STANDARD: Verifies 2-QRV-422 Throttles Open SAT: UNSAT:
STANDARD: CS Determines that 2-QRV-451 DOES NOT Open and stops the dilution, then notifies the Unit Supervisor.
SAT: UNSAT:
CUE: When notified, inform operator that the 100 gal. dilution is still desired and ask for a recommendation. If required, the Unit Supervisor informs the operator to return the blender to AUTO and then perform an Alternate Dilution for 100 GPM.
Page 5 of 9
TITLE: NRC2008-Sim01 - Dilute the RCS. (ALT) REVISION: 0 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator verifies Blend Control Switch is in STOP SAT: UNSAT:
STANDARD: Operator verifies controllers 2-RU-34 & 2-RU-33 in TRK (AUTO)
SAT: UNSAT:
STANDARD: Operator verifies setpoint is set to 21.3 (+ 0.5) for 1517 ppm in RCS.
CUE: The US directs you to determine the 2-RU-33 setting per Attachment 11, Section 4.1.2 SAT: UNSAT:
STANDARD: Operator verifies the following valves in AUTO
- QRV-400
- QRV-421
- QRV-422
- QRV-451 SAT: UNSAT:
STANDARD: CS Places switch to AUTO SAT: UNSAT:
STANDARD: CS Places switch to START SAT: UNSAT:
Page 6 of 9
TITLE: NRC2008-Sim01 - Dilute the RCS. (ALT) REVISION: 0 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
CUE: Precautions and Limitations have been met.
STANDARD: Operator verifies Blender Aligned for Automatic Operation (May reference Attachment 1 of this procedure)
SAT: UNSAT:
CUE: Reactor Engineer has requested and the SRO has verified the need to Dilute the RCS by adding 100 gallons of pure water.
STANDARD: Places switch to STOP SAT: UNSAT:
STANDARD: CS Places switch to ALT DILUTE SAT: UNSAT:
STANDARD: CS PW batch counter set to 100 gallons (using Pre A P/B)
SAT: UNSAT:
STANDARD: PW flow can be set to any non-zero value.
SAT: UNSAT:
STANDARD: QRV-451 is left closed (OOS).
SAT: UNSAT:
STANDARD: CS Places switch to START (See next page for Automatic Actions)
SAT: UNSAT:
CUE, if required: Multiple Dilutions are NOT expected.
Page 7 of 9
TITLE: NRC2008-Sim01 - Dilute the RCS. (ALT) REVISION: 0 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
NOTE: Automatic Actions listed are from Precautions &
Limitations Section. Operator may continue with Attachment 5 as shown on next page.
STANDARD: Verifies PW pump starts SAT: UNSAT:
STANDARD: Verifies 2-QRV-422 Throttles Open SAT: UNSAT:
STANDARD: Verifies 2-QRV-400 Opens SAT: UNSAT:
STANDARD: Verifies the following
- Verifies PW pump stops
- Verifies 2-QRV-422 Closes
- Verifies 2-QRV-400 Closes SAT: UNSAT:
Page 8 of 9
TITLE: NRC2008-Sim01 - Dilute the RCS. (ALT) REVISION: 0 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
CUE, if required: It is NOT desired to Divert Letdown.
Note: Constant dilution is NOT Performed STANDARD: CS PW flow is stopped automatically or manually once 100 gallons (+10 gallons)
SAT: UNSAT:
CUE: Another dilution is not desired.
Operator Determines that Attachment 1 Must be performed (Next page)
CUE: .Another operator will align the blender of AUTO.
EVALUATOR: This JPM is Complete Page 9 of 9
Task Briefing You are the extra RO.
The following conditions exist:
- Unit is in Mode 3 preparing for startup.
- BAST Boron concentration is 6600 ppm.
- Makeup control set for auto.
- The makeup line is full of primary water.
The US directs you to add 100 gallons of primary water to the RCS in accordance with 02-OHP-4021-005-002, Operation of the Unit 2 Boric Acid Blender using Normal Dilute Mode.
You are to restore the blender alignment for Auto makeup.
NRC2008-Sim01.doc Page 1 of 1
NRC2008-Sim02 TITLE Raise SI Accumulator Level (with Faulted REVISION 0 Pressure Relief Valve)
PROGRAM Initial Licensed Operator (ILT) TIME 15 Minutes SCOPE OF REVISION:
Initial Issue Developed from N02-02, JPM modified from RO-O-NO66 rev 4 DATE:
AUTHOR Name: John T Conrad Signature:
FACILITY Name:
REVIEWER Signature:
Facility Supervisor / Manager Page 1 of 15
COURSE NUMBER NRC2008-Sim02 Raise SI Accumulator Level REVISION: 0 AND TITLE: (with Faulted Pressure Relief Valve)
REFERENCES 02-OHP-4021-008-004, Rev 20 Adjusting level of an Accumulator 02-OHL-4030-SOM-042, Rev 20 Unit 2 Tours - U2 CR M3 & 4 SHIFT CHKS Task: 0080240101: Increase an Accumulator level in Modes 1, 2, or 3 K/A CROSS
REFERENCE:
006 A4.07 K/A IMPORTANCE: RO: 4.4 SRO: 4.4 EVALUATION SETTINGS Simulator HANDOUTS Task Briefing Copy of 02-OHP-4021-008-004 Attachment 3 annotated for #1 Accumulator fill w/ Lineup Sheet 2 Copy of 02-OHL-4030-SOM-042 Unit 2 Tours - U2 CR M3 & 4 SHIFT CHKS Copy of 02-OHP-4021-008-004 Attachment 5 (if candidate elects to lower accumulator level)
ATTACHMENTS None SIMULATOR SETUP Initialize to IC 971 (IC with normal temperature and pressure & the following Setup.)
- Drain #1 Accumulator until Panel 206 Drop 16 alarm is IN and NR level is 925 FT3
- Ensure any caution tags have been removed from the Accum. Drain Valves
- Restore drain lineup to normal, adjust Accumulator pressure to 620 PSIG
- Fail #1 Accumulator Vent valve (2-IRV-112) closed with Override ZGI101IRV112
- Start the South SI pump per 2-OHP-4021-008-007.
Note: Booth operator should be prepared to open 2-IRV-60 (MRF SIR12) when requested.
Page 2 of 15
COURSE NUMBER NRC2008-Sim02 Raise SI Accumulator Level REVISION: 0 AND TITLE: (with Faulted Pressure Relief Valve)
TASK OBJECTIVES/STANDARDS Performs a fill on #1 Accumulator, observing all applicable precautions and limitations and procedure steps.
In addition, due a faulted condition with the selected Accumulator Vent valve, the operator should recognize the inability to vent accumulator during fill evolution, determine the operational implications and mitigate system conditions by terminating fill or lowering level to restore accumulator pressure and level within Tech Spec LCO limits.
TASK BRIEFING NOTE: (Wait until requested by candidate to distribute Attachment 5)
Given the following:
- You are the extra RO brought in to perform this task.
- Chemistry inadvertently drained #1 accumulator below the T.S. level limit.
- The ACCUMULATOR 1 LEVEL HIGH OR LOW alarm is lit.
The US directs you to raise #1 accumulator level to 950 cu. Ft IAW 02-OHP-4021-008-004 . The RO has completed steps 4.1 through 4.8. The South SI pump is running and the Starting Team reports all parameters are normal per 02-OHP-4021-008-007, Operation of the Safety Injection Pump. You are to begin at step 4.9 of 02-OHP-4021-008-004 Attachment 3.
All procedure prerequisites, precautions and limitations have been met.
Page 3 of 15
COURSE NUMBER NRC2008-Sim02 Raise SI Accumulator Level (with Faulted Pressure Relief REVISION: 0 AND TITLE: Valve)
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Notes To Evaluator This Alt Path JPM evaluates candidates operational control during a routine evaluation. During refill of the accumulator, a failure of the vent valve to open prevents venting of the accumulator as level rises.
The candidate is successful if the task is performed IAW the procedure AND final accumulator level and pressure is within Tech Spec LCO limits and Surveillance Notification Limits (NL).
STANDARD: Operator reviews Precautions and Limitations SAT: UNSAT:
Page 4 of 15
COURSE NUMBER NRC2008-Sim02 Raise SI Accumulator Level (with Faulted Pressure Relief REVISION: 0 AND TITLE: Valve)
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator reviews Precautions and Limitations (Continued)
SAT: UNSAT:
Operator reviews steps 4.1 through 4.8 are complete JTC X (Pages included for review purposes)
JTC Page 5 of 15
COURSE NUMBER NRC2008-Sim02 Raise SI Accumulator Level (with Faulted Pressure Relief REVISION: 0 AND TITLE: Valve)
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
JTC JTC Operator reviews steps 4.1 through 4.8 are complete (Pages included for review purposes)
JTC N/A Page 6 of 15
COURSE NUMBER NRC2008-Sim02 Raise SI Accumulator Level (with Faulted Pressure Relief REVISION: 0 AND TITLE: Valve)
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
JTC SP JTC Operator reviews steps 4.1 through 4.8 are complete (Pages included for review purposes)
SP JTC JTC Page 7 of 15
COURSE NUMBER NRC2008-Sim02 Raise SI Accumulator Level (with Faulted Pressure Relief REVISION: 0 AND TITLE: Valve)
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: CS Operator closes 2-IMO-270 or 2-IMO-275 SAT: UNSAT:
CUE: IMO-270 (IMO-275) dual verification is complete.
STANDARD: CS Operator Enters time & Date that Tech Spec 3.5.2 Condition D is entered.
SAT: UNSAT:
STANDARD: Operator directs AEO to OPEN 2-IRV-60 (Located on CAS Panel) Booth operator open 2-IRV-60 when requested.
CUE: 2-IRV-60 is OPEN SAT: UNSAT:
STANDARD: CS Operator declares the Accum 21 INOPERABLE and enters Tech Spec.
SAT: UNSAT:
STANDARD: CS Operator opens 2-IRV-111 (Not Critical - Enters N/A for remaining valves)
SAT: UNSAT:
Page 8 of 15
COURSE NUMBER NRC2008-Sim02 Raise SI Accumulator Level (with Faulted Pressure Relief REVISION: 0 AND TITLE: Valve)
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: CS Operator attempts to open IRV-112 and determines that valve will NOT open.
SAT: UNSAT:
NOTE: Operator may stop fill prior to the desired level but within the Tech Spec Limits, with pressure still within the band. If so, then Attachment 5 is not required to be performed and JPM will be complete once Step 4.18 has been completed.
CUE: If Required, The US directs you to fill the Accumulator to a level and pressure that are still within Notification Limits.
STANDARD: CS Operator closes 2-IRV-111 (NOTE: Operator also checks the position of all other valves as required, which is NOT a CS)
SAT: UNSAT:
Page 9 of 15
COURSE NUMBER NRC2008-Sim02 Raise SI Accumulator Level (with Faulted Pressure Relief REVISION: 0 AND TITLE: Valve)
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
CUE: An extra Operator has Independently Verified all valves in Step 4.14 in correct position.
STANDARD: Operator ask AEO to close 2-IRV-60 (Located on the CAS Panel)
CUE: IRV-60 position has been closed by AEO and Independently Verified.
SAT: UNSAT:
STANDARD: Verifies Accum. 21 Narrow Range Level and Pressure and within TS and Surveillance Notification Limits (NL)
- TS: Level Limit (>921 AND <971 Ft3)
- TS: Level Limit with Inst Uncertainty (>927.5 AND <965 Ft3)
- NL: Level Limit <932.5 OR >962.5 Ft3.
- TS: Pressure Between (595 AND 650 psig)
- NL: Pressure <600 OR >640 psig.
SAT: UNSAT:
STANDARD: Operator declares Accum 21 OPERABLE (Not applicable if pressure is outside Notification Limit, and draining is required to return pressure to normal)
SAT: UNSAT:
CUE: If pressure or level is outside Notification Limit, then request operator to restore the parameter as required. (Drain Accum. 21 to within Level and Pressure Limits per Attachment 5.)
EVALUATOR: If level and pressure are within limits then, This JPM is COMPLETE. Otherwise continue to next page.
Page 10 of 15
COURSE NUMBER NRC2008-Sim02 Raise SI Accumulator Level (with Faulted Pressure Relief REVISION: 0 AND TITLE: Valve)
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Evaluator Note: If required, use the following operator actions to restore accumulator pressure within Tech Spec limits (595 - 650 psig) by draining the accumulator.
CUE: The Unit Supervisor directs you to adjust Accumulator #1 to within Tech Spec limits/Notification Limits of per 02-OHL-4030-SOM-041.
STANDARD: Operator determines that the Unit is in Mode 1.
SAT: UNSAT:
STANDARD: Operator reviews Precautions and Limitations SAT: UNSAT:
Page 11 of 15
COURSE NUMBER NRC2008-Sim02 Raise SI Accumulator Level (with Faulted Pressure Relief REVISION: 0 AND TITLE: Valve)
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator checks Accum. 21 SAT: UNSAT:
STANDARD: Operator declares Accum 21 INOPERABLE (maybe be carried over from Attachment 3 Time/Date)
CUE: Another operator will make the control room log.
SAT: UNSAT:
STANDARD: Operator checks RCDT and RCDT pump status.
CUE: The RCDT and both RCDT pumps are available.
STANDARD: Operator enters N/A step 4.4 (2-IRV-112 is OOS and level is being lowered to lower pressure)
SAT: UNSAT:
Page 12 of 15
COURSE NUMBER NRC2008-Sim02 Raise SI Accumulator Level (with Faulted Pressure Relief REVISION: 0 AND TITLE: Valve)
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: CS Operator opens 2-IRV-110 for #1 Accumulator.
SAT: UNSAT:
STANDARD: Operator ensures that RCDT level and pressure are maintained per operating procedures.
CUE: WDS operator reports RCDT level and pressure are within normal limits.
SAT: UNSAT:
STANDARD: CS Operator closes 2-IRV-110 when Accum 21 when desired level is reached.
SAT: UNSAT:
Page 13 of 15
COURSE NUMBER NRC2008-Sim02 Raise SI Accumulator Level (with Faulted Pressure Relief REVISION: 0 AND TITLE: Valve)
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator enters N/A step 4.8 (Nitrogen was not added)
SAT: UNSAT:
Page 14 of 15
COURSE NUMBER NRC2008-Sim02 Raise SI Accumulator Level (with Faulted Pressure Relief REVISION: 0 AND TITLE: Valve)
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Verifies Accum. 21 Narrow Range Level and Pressure and within TS and Surveillance Notification Limits (NL)
- TS: Level Limit (>921 AND <971 Ft3)
- TS: Level Limit with Inst Uncertainty (>927.5 AND <965 Ft3)
- NL: Level Limit <932.5 OR >962.5 Ft3.
- TS: Pressure Between (595 AND 650 psig)
- NL: Pressure <600 OR >640 psig.
SAT: UNSAT:
STANDARD: Declares Accum. 21 OPERABLE.
SAT: UNSAT:
EVALUATOR: This JPM is complete.
Page 15 of 15
Task Briefing Given the following:
- You are the extra RO brought in to perform this task.
- Chemistry inadvertently drained #1 accumulator below the T.S. level limit.
- The ACCUMULATOR 1 LEVEL HIGH OR LOW alarm is lit.
The US directs you to raise #1 accumulator level to 950 cu. Ft IAW 02-OHP-4021-008-004 . The RO has completed steps 4.1 through 4.8. The South SI pump is running and the Starting Team reports all parameters are normal per 02-OHP-4021-008-007, Operation of the Safety Injection Pump. You are to begin at step 4.9 of 02-OHP-4021-008-004 Attachment 3.
All procedure prerequisites, precautions and limitations have been met.
NRC2008-Sim02.doc Page 1 of 1
NRC2008-Sim03 TITLE Depressurize the RCS to Refill the Pressurizer REVISION 0 (ALT)
PROGRAM Initial Licensed Operator (ILT) TIME 15 Minutes SCOPE OF REVISION:
Initial Issue DATE:
AUTHOR Name: John T Conrad Signature:
FACILITY Name:
REVIEWER Signature:
Page 1 of 6
NRC2008-Sim03 - Depressurize the RCS to Refill the Pressurizer (ALT) REVISION: 0 TITLE:
REFERENCES 2-OHP-4023-ES-1.2, Rev. 13 Post LOCA Cooldown and Depressurization TASK ID: EOP0670512, Cooldown and Depressurize the RCS following a loss of Coolant Inventory.
K/A Statement: EPE 009 EA1.01, Ability to operate and monitor the RCS Temperature and Pressure as it applies to a Small Break LOCA:
K/A Importance: RO: 4.4 SRO: 4.3 EVALUATION SETTINGS Simulator HANDOUTS 2-OHP-4023-ES-1.2, Post LOCA Cooldown and Depressurization ATTACHMENTS None SIMULATOR SETUP
& Block Closed for Leakage, Clearance Tag NRV-151 & NMO151
- Insert Global Malfunctions 101NRV151, 101NRV152, 101NRV 153 & 101NMO151
- Trg 1 - NMO153 to Open (ZGI101NMO153 == 3), IMF 101NMO153
- OOS Tag NRV & NMO 151, Caution Tag NMO 153
- Insert ZGI CCVAB79 NRV-151, power OFF.
Page 2 of 6
NRC2008-Sim03 - Depressurize the RCS to Refill the Pressurizer (ALT) REVISION: 0 TITLE:
TASK OBJECTIVES/STANDARDS Perform RCS Depressurization to Refill the Pressurizer using Aux Spray during a SB LOCA.
TASK BRIEFING You are the RO in Unit 2.
Unit 2 is responding to a Small Break LOCA. All RCPs have been stopped and the crew is implementing, Post LOCA Cooldown and Depressurization.
The Unit Supervisor requests you to perform step 13 of 2-OHP-4023-ES-1.2, to Depressurize the RCS to Refill the Pressurizer.
Page 3 of 6
NRC2008-Sim03 - Depressurize the RCS to Refill the Pressurizer (ALT) REVISION: 0 TITLE:
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator determines that PRZ Level is less than 37%.
SAT: UNSAT:
CUE: If Asked, Containment is NOT Adverse.
Instructor Note: (Not to be provided to student) Adverse Containment is defined as:
- Containment Pressure >5 psig
- Radiation >105 R/Hr
- Intergated Radiation >106 R Page 4 of 6
NRC2008-Sim03 - Depressurize the RCS to Refill the Pressurizer (ALT) REVISION: 0 TITLE:
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator determines that Normal Spray is NOT available (RCPs are not running).
SAT: UNSAT:
STANDARD: Operator attempts to open NRV-152 (only unisolated PORV) and determines that NRV-152 is NOT available.
SAT: UNSAT:
Instructor Note: Operator may attempt to open NRV-153 block valve but breaker will trip before valve opens.
STANDARD: Operator determines that Aux Spray is required.
SAT: UNSAT:
STANDARD: Operator verifies that at least one SI and one CCP are in operation.
SAT: UNSAT:
STANDARD: CS Operator resets and opens QMO-225/226.
SAT: UNSAT:
STANDARD: CS Operator closes BIT Inlet Valves.
SAT: UNSAT:
STANDARD: CS Operator closes BIT Outlet Valves.
SAT: UNSAT:
STANDARD: Operator closes normal spray valves.
SAT: UNSAT:
Page 5 of 6
NRC2008-Sim03 - Depressurize the RCS to Refill the Pressurizer (ALT) REVISION: 0 TITLE:
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: CS Operator closes QRV-61/62.
SAT: UNSAT:
STANDARD: Operator opens 2-QRV-251 SAT: UNSAT:
STANDARD: Operator opens 2-QRV-200 SAT: UNSAT:
STANDARD: CS Operator opens QRV-51.
SAT: UNSAT:
STANDARD: CS Operator opens 2-QMO-200/201 SAT: UNSAT:
CUE: US/BOP are continuing with other steps in procedure during the depressurization.
STANDARD: CS Operator depressurizes RCS until the PRZ Level is greater that 37%.
SAT: UNSAT:
STANDARD: CS Operator closes 2-QRV-51 SAT: UNSAT:
EVALUATOR: This JPM is complete.
Page 6 of 6
Task Briefing You are the RO in Unit 2.
Unit 2 is responding to a Small Break LOCA . All RCPs have been stopped and the crew is implementing, Post LOCA Cooldown and Depressurization.
The Unit Supervisor requests you to perform step 13 of 2-OHP-4023-ES-1.2, to Depressurize the RCS to Refill the Pressurizer.
NRC2008-Sim03.doc Page 1 of 1
NRC2008-SIM04 TITLE Start a Reactor Coolant Pump (ALT) REVISION 0 PROGRAM Initial Licensed Operator (ILT) TIME 20 Minutes SCOPE OF REVISION:
Initial Issue DATE:
AUTHOR Name: John T Conrad Signature:
FACILITY Name:
REVIEWER Signature:
Facility Supervisor / Manager Page 1 of 13
COURSE NUMBER NRC2008-SIM04 AND TITLE: REVISION: 0 Start a Reactor Coolant Pump (ALT)
REFERENCES 02-OHP-4023-SUP-007, Rev 1a Restoration of RCP Cooling 02-OHP-4023-SUP-010, Rev 3 Starting Reactor Coolant Pumps TASK: 0020030501 Restore RCP Support Systems following Containment Isolation 0020040501 Start an RCP KA
REFERENCE:
SYS 003 A4.08 K/A IMPORTANCE: RO: 3.2 SRO: 2.9 EVALUATION SETTINGS
- 1. Simulator HANDOUTS
- 1. Task Briefing
- 2. Copy of 02-OHP-4023-SUP-010
- 3. Copy of 02-OHP-4023-SUP-007 ATTACHMENTS
- 1. NONE SIMULATOR SETUP
- 1. Initialize simulator to IC 973 (from IC 35 with RC10D @70% perform E-0, E-1, ES-1.2 through Step 14) with:
- Verify/Close valves 2-CCM-458 and 2-CCM-451
- Verify RVLIS Upper > 85 or PRZ Level >87.
- Verify all SG NR levels above 27%.
Page 2 of 13
COURSE NUMBER NRC2008-SIM04 AND TITLE: REVISION: 0 Start a Reactor Coolant Pump (ALT)
TASK OBJECTIVES/STANDARDS Start RCP #23 as directed per 02-OHP-4023-SUP-010 after restoring CCW Cooling per 02-OHP-4023-SUP-007 while observing all applicable precautions and limitations and procedure steps.
EVALUATOR INSTRUCTIONS Note: Do NOT distribute 02-OHP-4023-SUP-007 until requested.
You are the RO in Unit 2.
Unit 2 is responding to a Small Break LOCA . All RCPs have been stopped and the crew is implementing step 14 of 2-OHP-4023-ES-1.2, Post LOCA Cooldown and Depressurization.
The Unit Supervisor requests you to start RCP 23, using 2-OHP-4023-SUP-010, Starting Reactor Coolant Pumps.
Page 3 of 13
COURSE NUMBER NRC2008-SIM04 AND TITLE: REVISION: 0 Start a Reactor Coolant Pump (ALT)
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Determines that RCP 2D is energized.
SAT: UNSAT:
STANDARD: CS Determines that RCP CCW Flow is NOT NORMAL & Enters RNO action go to SUP-007.
SAT: UNSAT:
Instructor Note: Supply Operator with copy of 02-OHP-4023-SUP-007.
Page 4 of 13
COURSE NUMBER NRC2008-SIM04 AND TITLE: REVISION: 0 Start a Reactor Coolant Pump (ALT)
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator verifies Panel 207 Drop 74 NOT LIT CUE: All RCP alarms currently standing are the only ones that have been in alarm.
SAT: UNSAT:
STANDARD: Operator verifies 2-QTI-230 is less than 225ºF SAT: UNSAT:
CUE: If Asked, Lower bearing temperatures have NOT exceeded 150ºF.
Page 5 of 13
COURSE NUMBER NRC2008-SIM04 AND TITLE: REVISION: 0 Start a Reactor Coolant Pump (ALT)
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator verifies Panel 207 Drop 68 NOT LIT CUE: All RCP alarms currently standing are the only ones that have been in alarm.
SAT: UNSAT:
Instructor Note: Ann. 207 panel alarms for CCW flow mismatch and Low Cooling Flow to RCP Bearings may alarm/clear when restoring CCW flow to RCPs.
STANDARD: CS Operator places 2-CCM-458 CS to OPEN SAT: UNSAT:
STANDARD: Operator verifies 2-CCM-458 & 2-CCM-459 are OPEN with red light lit SAT: UNSAT:
STANDARD: Operator verifies 2-CCM-453 & 2-CCM-454 are OPEN with red light lit SAT: UNSAT:
STANDARD: CS Operator places 2-CCM-451 CS to OPEN SAT: UNSAT:
STANDARD: Operator verifies 2-CCM-451 & 2-CCM-452 are OPEN (red light lit)
SAT: UNSAT:
Page 6 of 13
COURSE NUMBER NRC2008-SIM04 AND TITLE: REVISION: 0 Start a Reactor Coolant Pump (ALT)
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Checks Both CCP pumps running SAT: UNSAT:
STANDARD: Verifies RCP Seal Injection to 6-12 gpm SAT: UNSAT:
STANDARD: Returns to 02-OHP-4023-SUP-010 Step 2.
SAT: UNSAT:
Page 7 of 13
COURSE NUMBER NRC2008-SIM04 AND TITLE: REVISION: 0 Start a Reactor Coolant Pump (ALT)
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Verifies RCP #23 CCW flows are Acceptable.
SAT: UNSAT:
Page 8 of 13
COURSE NUMBER NRC2008-SIM04 AND TITLE: REVISION: 0 Start a Reactor Coolant Pump (ALT)
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator verifies RCP Seal Injection to 6-12 gpm SAT: UNSAT:
STANDARD: Operator verifies Panel 207 Drop 67 is NOT LIT for RCP #23.
SAT: UNSAT:
STANDARD: Operator verifies No. 1 Seal DP for RCP #23 is greater than 200.
SAT: UNSAT:
Page 9 of 13
COURSE NUMBER NRC2008-SIM04 AND TITLE: REVISION: 0 Start a Reactor Coolant Pump (ALT)
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator verifies RCP #23 seal leakoff flow above minimum value.
SAT: UNSAT:
STANDARD: Operator verifies RVLIS Upper Plenum greater than 92%.
SAT: UNSAT:
Page 10 of 13
COURSE NUMBER NRC2008-SIM04 AND TITLE: REVISION: 0 Start a Reactor Coolant Pump (ALT)
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: CS Operator places the #23 RCP Bearing Lift Pump CS to RUN SAT: UNSAT:
(Evaluator may time compress once 2 minute run time is mentioned).
STANDARD: Operator verifies SI NOT actuated (Already Reset/Blocked).
SAT: UNSAT:
Page 11 of 13
COURSE NUMBER NRC2008-SIM04 AND TITLE: REVISION: 0 Start a Reactor Coolant Pump (ALT)
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator verifies All SG levels above 27%.
SAT: UNSAT:
Page 12 of 13
COURSE NUMBER NRC2008-SIM04 AND TITLE: REVISION: 0 Start a Reactor Coolant Pump (ALT)
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator verifies both PZR Spray valves are CLOSED SAT: UNSAT:
STANDARD: CS Operator places the RCP #23 CS to RUN.
SAT: UNSAT:
STANDARD: Operator verifies UV alarms Panel 221 Drop 67 & 68 are NOT LIT.
CUE: Panel 221 Drops 67 & 68 are NOT LIT SAT: UNSAT:
STANDARD: Operator places the #23 RCP Bearing Lift Pump CS to STOP SAT: UNSAT:
STANDARD: Operator reports the No 23 RCP is running.
SAT: UNSAT:
EVALUATOR: This JPM is Complete.
Page 13 of 13
Task Briefing You are the RO in Unit 2.
Unit 2 is responding to a Small Break LOCA . All RCPs have been stopped and the crew is implementing step 14 of 2-OHP-4023-ES-1.2, Post LOCA Cooldown and Depressurization.
The Unit Supervisor requests you to start RCP 23, using 2-OHP-4023-SUP-010, Starting Reactor Coolant Pumps.
NRC2008-Sim04.doc Page 1 of 1
NRC2008-Sim05 TITLE Perform Steam Generator Stop Valve Dump REVISION 0 Valve Surveillance Test PROGRAM Initial Licensed Operator (ILT) TIME 10 Minutes SCOPE OF REVISION:
Initial Issue From Audit07-Sim07& Audit06-Sim02 DATE:
AUTHOR Name: John T Conrad Signature:
FACILITY Name:
REVIEWER Signature:
Facility Supervisor / Manager Page 1 of 6
TITLE: NRC2008-Sim05 - Perform Steam Generator Stop Valve REVISION: 0 Dump Valve Surveillance Test REFERENCES 2-OHP-4030-251-018 Rev 2 Steam Generator Stop Valve Dump Valve Surveillance Test Task ADM1190301 Stroke a valve for Post Maintenance operability Number:
K/A Number: 039 K4.05 Knowledge of the Main Steam System design features which provide for automatic isolation of the steam line K/A IMPORTANCE: RO: 3.7 SRO: 3.7 EVALUATION SETTINGS Simulator HANDOUTS Task Briefing 2-OHP-4030-251-018 Stopwatch (with current cal due date sticker)
ATTACHMENTS
- 1. NONE SIMULATOR SETUP
- 2. FREEZE the simulator.
- 3. Stop Watch Required with Calibration Sticker Page 2 of 6
TITLE: NRC2008-Sim05 - Perform Steam Generator Stop Valve REVISION: 0 Dump Valve Surveillance Test TASK OBJECTIVES/STANDARDS Perform 02 OHP 4030-251-018, Steam Generator Stop Valve Dump Valve Surveillance Test on 2-MRV-210.
TASK BRIEFING You are the Balance of Plant Operator.
Steam Generator Stop Valve Dump Valve Surveillance Test is required for 2-MRV-210 following a conduit repair. The Unit Supervisor directs you to perform 02 OHP 4030-251-018 on 2-MRV-210 (Section 4.2).
All personnel have been briefed and are locally standing by for the test of 2-MRV-210 Dump Valves.
Page 3 of 6
TITLE: NRC2008-Sim05 - Perform Steam Generator Stop Valve Dump Valve Surveillance Test REVISION: 0 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
General CUES:
Provide candidate marked up copy of 02-OHP-4030-251-018, Steam Generator Stop Valve Dump Valve Surveillance Test, (Marked to perform section 4.2).
Instructor Note: Primary Stop Watch Data is already entered.
Secondary stopwatch data is N/A.
SW-002 12-25-2008 N/A N/A Page 4 of 6
TITLE: NRC2008-Sim05 - Perform Steam Generator Stop Valve Dump Valve Surveillance Test REVISION: 0 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
CUE: If asked, all procedure prerequisites have been met and an AEO is stationed at the Valve and in communication STANDARD: Operator declares MRV-210 inoperable for testing (Step 3.8/3.12).
CUE: US acknowledges 2-MRV-210 is inoperable for testing.
SAT: UNSAT:
STANDARD: CS Operator places AND holds 2-MMO-210 switch to the POS A position.
SAT: UNSAT:
STANDARD: Operator verifies POS A light is LIT.
SAT: UNSAT:
STANDARD: Verifies neon lamp for 2-MRV-211 is dark. (Starts Stopwatch)
SAT: UNSAT:
STANDARD: Records OPEN time from Stopwatch (Stops Stopwatch when Green Light goes Dark & the RED light is lit)
SAT: UNSAT:
CUE: AEO reports pressure indicates 0 psi on 2-MPI-211.
0 2 STANDARD: CS Operator places 2-MMO-210 switch to the NORM position.
SAT: UNSAT:
Page 5 of 6
TITLE: NRC2008-Sim05 - Perform Steam Generator Stop Valve Dump Valve Surveillance Test REVISION: 0 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator verifies 2-MRV-211indicates CLOSED.
SAT: UNSAT:
STANDARD: Operator verifies NORMAL light is LIT.
SAT: UNSAT:
STANDARD: CS Operator places AND holds 2-MMO-210 switch to the POS B position.
SAT: UNSAT:
STANDARD: Operator verifies
- POS B light is LIT
- Neon lamp for 2-MRV-212 is dark. (Starts Stopwatch).
SAT: UNSAT:
STANDARD: Records OPEN time from Stopwatch (Stops Stopwatch when Green Light goes Dark & the RED light is lit)
SAT: UNSAT:
0 2 CUE: AEO reports pressure indicates 0 psi on 2-MPI-212.
STANDARD: CS Operator places 2-MMO-210 switch to the NORM position.
SAT: UNSAT:
STANDARD: Operator verifies
- 2-MRV-212indicates closed.
- NORMAL light is LIT SAT: UNSAT:
STANDARD: Operator reports testing complete on 2-MRV-210.
SAT: UNSAT:
EVALUATOR: This JPM is complete Page 6 of 6
Task Briefing You are the Balance of Plant Operator.
Steam Generator Stop Valve Dump Valve Surveillance Test is required for 2-MRV-210 following a conduit repair. The Unit Supervisor directs you to perform 02 OHP 4030-251-018 on 2-MRV-210 (Section 4.2).
All personnel have been briefed and are locally standing by for the test of 2-MRV-210 Dump Valves.
NRC2008-Sim05.doc Page 1 of 1
NRC2008-Sim06 TITLE Restore RCP Bus 2A Power to AC Bus T21A REVISION 0 Emergency Bus(T21A on EDG)
PROGRAM Initial Licensed Operator (ILT) TIME 20 Minutes SCOPE OF REVISION:
Initial Issue DATE:
AUTHOR Name: John T Conrad Signature:
FACILITY Name:
REVIEWER Signature:
Facility Supervisor / Manager Page 1 of 8
COURSE NUMBER NRC2008-Sim06 - Restore RCP Bus 2A Power to REVISION: 0 AND TITLE: AC Bus T21A Emergency Bus(T21A on EDG)
REFERENCES 02-OHP 4023-SUP-002, Rev. 6 Restoration of Reserve Power to 4KV Buses Task: EOP0390501 Restore Offsite Power to all AC buses using SUP 002.
K/A CROSS
REFERENCE:
SYS 062 A4.07 K/A IMPORTANCE: RO 3.1 SRO 3.1 EVALUATION SETTINGS Simulator HANDOUTS Task Brief Copy of Attachment G to 02-OHP 4023-SUP-002 ATTACHMENTS
- 1. NONE SIMULATOR SETUP
- Verify that T21A and T21B are fed from 2AB EDG (Open TR201AB transformer breaker following Trip & Then Reclose)
Page 2 of 8
COURSE NUMBER NRC2008-Sim06 - Restore RCP Bus 2A Power to REVISION: 0 AND TITLE: AC Bus T21A Emergency Bus(T21A on EDG)
TASK OBJECTIVES/STANDARDS Load the T21A Bus to the RCP Bus in accordance with 2-OHP-4023-SUP-002.
TASK BRIEFING You are an extra operator on Unit 2.
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 T21A Bus to the RCP bus in accordance with 2-OHP-4023-SUP-002, Restoration of Reserve Power to 4KV Buses.
Page 3 of 8
COURSE NUMBER NRC2008-Sim06 - Restore RCP Bus 2A Power to AC Bus T21A Emergency REVISION: 0 AND TITLE: Bus(T21A on EDG)
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator checks for voltage on 4kV Bus 2A SAT: UNSAT:
STANDARD: Operator checks DG2AB running with Output Breaker to T21A closed.
SAT: UNSAT:
STANDARD: Operator places both Voltmeters to OFF position SAT: UNSAT:
STANDARD: CS Operator places DG2AB 4KV CB T21A9 Synch Selector switch in MANUAL SAT: UNSAT:
STANDARD: CS Operator adjusts DG2AB (START) voltage 2-3 volts higher than Bus 2A (RUN) voltage.
SAT: UNSAT:
Instructor Note: Ann. 219, Drop 40, 4KV BUS T21A OVERVOLTAGE, may alarm when adjusting bus voltage.
STANDARD: CS Operator adjusts speed so the Synchroscope is rotating SLOWLY in the FAST direction.
SAT: UNSAT:
Page 4 of 8
COURSE NUMBER NRC2008-Sim06 - Restore RCP Bus 2A Power to AC Bus T21A Emergency REVISION: 0 AND TITLE: Bus(T21A on EDG)
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Page 5 of 8
COURSE NUMBER NRC2008-Sim06 - Restore RCP Bus 2A Power to AC Bus T21A Emergency REVISION: 0 AND TITLE: Bus(T21A on EDG)
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: CS Operator closes DG2AB 4KV CB T21A9 control switch at appropriate time.
SAT: UNSAT:
STANDARD: Operator verifies WHITE light permissive is LIT SAT: UNSAT:
Page 6 of 8
COURSE NUMBER NRC2008-Sim06 - Restore RCP Bus 2A Power to AC Bus T21A Emergency REVISION: 0 AND TITLE: Bus(T21A on EDG)
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: CS Operator places DG2AB Synchronize Master Close Switch in CLOSE at appropriate time.
SAT: UNSAT:
STANDARD: Operator verifies Breaker T21A9 CLOSED.
SAT: UNSAT:
Instructor Note: Ann. 219, Drop 76, 4KV BUS T21A PARALLEL OPERATION, will alarm when both supply breakers are closed.
Page 7 of 8
COURSE NUMBER NRC2008-Sim06 - Restore RCP Bus 2A Power to AC Bus T21A Emergency REVISION: 0 AND TITLE: Bus(T21A on EDG)
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: CS Operator adjusts DG2AB load to greater than 0 kw.
SAT: UNSAT:
STANDARD: CS Operator places DG2AB 4KV CB T21A9 Synch Selector switch in OFF SAT: UNSAT:
STANDARD: Operator adjusts DG2AB voltage as required.
SAT: UNSAT:
STANDARD: CS Operator OPENS breaker T21A11 SAT: UNSAT:
CUE: US acknowledges tripping open the T21A11 breaker.
STANDARD: Operator recognized that Bus T21B is still energized by DG2AB and leaves DG2AB running.
SAT: UNSAT:
Page 8 of 8
COURSE NUMBER NRC2008-Sim06 - Restore RCP Bus 2A Power to AC Bus T21A Emergency REVISION: 0 AND TITLE: Bus(T21A on EDG)
EVALUATOR: When transition is made back to Steps 5, JPM is COMPLETE Page 9 of 8
TASK BRIEFING You are an extra operator on Unit 2.
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 T21A Bus to the RCP bus in accordance with 2-OHP-4023-SUP-002, Restoration of Reserve Power to 4KV Buses.
NRC2008-Sim06.doc Page 1 of 1
NRC2008-Sim07 TITLE Energize SR Detectors and Audio Count Rate REVISION 0 PROGRAM Initial Licensed Operator (ILT) TIME 15 Minutes SCOPE OF REVISION:
Initial Issue Developed from Audit07-Sim06 DATE:
AUTHOR Name: John T Conrad Signature:
FACILITY Name:
REVIEWER Signature:
Facility Supervisor / Manager Page 1 of 7
TITLE: NRC2008-Sim07 - Energize SR Detectors and REVISION: 0 Audio Count Rate REFERENCES 02-OHP-4023-ES-1.2, Rev. 13 Post LOCA Cooldown And Depressurization 02-OHP-4021-013-005, Rev. 9 Visual Audio Count Rate Channel (NIS)
Tasks:
0130010501: Energize Source Range NIS 0130140101: Energize the Audio Count Rate Channel K/A CROSS
REFERENCE:
015 A2.02 K/A IMPORTANCE: RO 3.1 SRO 3.5*
EVALUATION SETTINGS Simulator HANDOUTS
- 1. Task Briefing
- 2. Copy of 02-OHP-4023-ES-1.2 Step 30
- 3. Copy of 02-OHP-4021-013-005 (Attachment 1)
ATTACHMENTS None SIMULATOR SETUP Reset to an IC972 (from IC 35 with RC10D @70% perform E-0, E-1, ES-1.2 through Step 13) with Malfunction NI07A (severity 0%) N-35 failed high due to under compensated.
Verify Scaler Timer Gate Light - NOT LIT (Depress STOP button between evals if needed)
Page 2 of 7
TITLE: NRC2008-Sim07 - Energize SR Detectors and REVISION: 0 Audio Count Rate TASK OBJECTIVES/STANDARDS Manually energize the Source Range Detectors and Audio Count Rate, observing all applicable precautions and limitations and procedure steps.
TASK BRIEFING NOTE: Wait until Candidate asks for 2-OHP-4021-013-005 before presenting to the candidate.
Thirty (30) minutes ago a reactor trip and safety injection were actuated in response to a RCS LOCA inside containment.
The US has determined that the Source Range Detectors have failed to automatically energize due to Intermediate Range N-35 being undercompensated.
The Unit Supervisor directs you to manually energize the Source Range detectors and verify proper operation per 2-OHP-4023-ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, starting at step 30b.
Page 3 of 7
NRC2008-Sim07 REVISION: 0 TITLE:
Energize SR Detectors and Audio Count Rate EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Evaluator Note:
Since the Reactor tripped occurred ~30 minutes ago, both Source Range detectors should have auto energized. The under compensation malfunction on N-35 IR results in the channel reading high, while the unaffected IR Channel will indicate
<6 X 10-11 AMPS and the 2/2 (P-6) logic NOT satisfied.
STANDARD: CS Operator momentarily places either SOURCE RANGE TRIP BLK & RESET switch to UNBLOCK position to re-energize the Source Range NIs.
SAT: UNSAT:
STANDARD: Operator places either or both Red pen and Blue pen Neutron Flux Recorder Selector Switches to SR1 and/or SR2 position(s)
SAT: UNSAT:
STANDARD: Operator obtains copy of 02-OHP-4021-013-005 CUE: Provide Operator with copy of 02-OHP-4021-013-005.
SAT: UNSAT:
Page 4 of 7
NRC2008-Sim07 REVISION: 0 TITLE:
Energize SR Detectors and Audio Count Rate EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator verifies scaler timer POWER toggle switch in the UP position SAT: UNSAT:
STANDARD: Operator verifies lights lit SAT: UNSAT:
STANDARD: Operator verifies Channel Selector switch in SRN31 or SRN32 position SAT: UNSAT:
STANDARD: Operator verifies Scaler Timer Polarity switch is in the (-) position SAT: UNSAT:
Page 5 of 7
NRC2008-Sim07 REVISION: 0 TITLE:
Energize SR Detectors and Audio Count Rate EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator verifies sampling mode switch in COUNT/SEC position SAT: UNSAT:
STANDARD: Operator verifies VOLUME switch in any position SAT: UNSAT:
STANDARD: Operator checks thumbwheels set to 00600 SAT: UNSAT:
STANDARD: Operator verifies sampling mode toggle switch in AUTO position SAT: UNSAT:
STANDARD: Operator depresses the STOP and RESET pushbuttons SAT: UNSAT:
STANDARD: CS Depresses the START pushbutton SAT: UNSAT:
STANDARD: Operator verifies gate light lit SAT: UNSAT:
STANDARD: Operator adjusts audio multiplier switch to produce a distinguishable gap in audio output SAT: UNSAT:
Page 6 of 7
NRC2008-Sim07 REVISION: 0 TITLE:
Energize SR Detectors and Audio Count Rate EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator determines Containment is N/A SAT: UNSAT:
STANDARD: Reports task completed.
SAT: UNSAT:
Evaluator: This JPM is complete.
Page 7 of 7
Task Briefing Thirty (30) minutes ago a reactor trip and safety injection were actuated in response to a RCS LOCA inside containment.
The US has determined that the Source Range Detectors have failed to automatically energize due to Intermediate Range N-35 being undercompensated.
The Unit Supervisor directs you to manually energize the Source Range detectors and verify proper operation per 2-OHP-4023-ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, starting at step 30b.
NRC2008-Sim07.doc Page 1 of 1
NRC2008-SIM08 TITLE Switching CCW Pumps REVISION 0 PROGRAM Initial Licensed Operator (ILT) TIME 20 Minutes SCOPE OF REVISION:
Initial Issue: Derived from NRC2007-SIM06 & Audit06-Sim04 DATE:
AUTHOR Name: John T Conrad Signature:
FACILITY Name:
REVIEWER Signature:
Facility Supervisor / Manager Page 1 of 6
COURSE NUMBER NRC2008-SIM08 REVISION: 0 AND TITLE:
Switching CCW Pumps REFERENCES 02-OHP-4021-016-003 Rev. 21, Operation of the CCW System during System Startup and Power Operation Task: 0160140101: Switch operating CCW pumps K/A CROSS
REFERENCE:
008 A4.01 K/A IMPORTANCE: RO 3.3 SRO 3.1 EVALUATION SETTINGS Simulator HANDOUTS Task Briefing Copy of 02-OHP-4021-016-003 Attachment 2 ATTACHMENTS None SIMULATOR SETUP Initialize any IC with CCW in normal operation aligned as follows:
- East CCW Pump - In Service
- West CCW Pump - In Standby Verify prerequisites of controlling procedure are met Page 2 of 6
COURSE NUMBER NRC2008-SIM08 REVISION: 0 AND TITLE:
Switching CCW Pumps TASK OBJECTIVES/STANDARDS Performs switching of the CCW pumps, observing all applicable precautions and limitations and procedure steps.
TASK BRIEFING You are an Extra Operator The US directs you to switch the running CCW Pumps and Heat Exchangers per 02-OHP-4021-016-003, Operation of the CCW System Startup and Power Operation Attachment 2 Step 4.2.
The CCW System is currently Operable.
Page 3 of 6
COURSE NUMBER NRC2008-SIM08 REVISION: 0 AND TITLE:
Switching CCW Pumps EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
General CUES:
- 1. Provide an annotated copy of 02-OHP-4021-016-003 Attachment 2 to perform switch of CCW pumps.
- 2. Inform candidate the West CCW pump is operable STANDARD: Operator determines this is the correct step to begin SAT: UNSAT:
CUE: If required, The Shift manager has determined that Step 4.2 may be used since the Plant is in Mode 3.
CUE: Unit Supervisor determines that steps 4.2.1, and 4.2.2 are not required. The RO is monitoring RCP and Letdown temperature affects of this evolution.
Page 4 of 6
COURSE NUMBER NRC2008-SIM08 REVISION: 0 AND TITLE:
Switching CCW Pumps EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Verifies 2-WMO-736 is open (red light lit)
SAT: UNSAT:
STANDARD: CS Throttles valve open (no specific initial intermediate position)
Instructor Note: Throttling ESW return form CCW Heat Exchangers may cause high/low CCW temperature alarms (Ann. Panel 204, Drop 85/95) on associated CCW trains until load on Hx is adjusted as required.
SAT: UNSAT:
STANDARD: Operator verifies each valve is OPEN in any order SAT: UNSAT:
STANDARD: Operator verifies 2-CMO-420 is CLOSED SAT: UNSAT:
CUE: Starting Team has verified West CCW pump is ready for start STANDARD: CS Operator starts West CCW pump SAT: UNSAT:
STANDARD: CS Operator opens 2-CMO-420 SAT: UNSAT:
STANDARD: Operator verifies pump flow and amps have stabilized.
CUE: Starting Team reports normal pump running parameters SAT: UNSAT:
STANDARD: CS Operator closes at least one valve.
SAT: UNSAT:
Page 5 of 6
COURSE NUMBER NRC2008-SIM08 REVISION: 0 AND TITLE:
Switching CCW Pumps EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator determines step - N/A (West CCW Pump is OPERABLE)
SAT: UNSAT:
STANDARD: CS Operator closes valve 2-CMO-410 Note: Operator may declare East CCW Train Inoperable based on Step 3.4 (Step 4.2.9 & 4.2.11 meet action Level)
SAT: UNSAT:
STANDARD: CS Operator stops East CCW pump SAT: UNSAT:
STANDARD: CS Operator verifies valves OPEN Note: whichever valve(s) was/were closed in step 4.2.9, must be manually reopened SAT: UNSAT:
STANDARD: Operator places control switch to AUTO SAT: UNSAT:
STANDARD: Operator verifies flow meets Precaution 3.3 Reports task completed.
SAT: UNSAT:
CUE: US determines these steps are NOT desired EVALUATOR: This JPM is complete Page 6 of 6
Task Briefing You are an Extra Operator The US directs you to switch the running CCW Pumps and Heat Exchangers per 02-OHP-4021-016-003, Operation of the CCW System Startup and Power Operation Attachment 2 Step 4.2.
The CCW System is currently Operable.
NRC2008-Sim08.doc Page 1 of 1
NRC2008-INP01 TITLE Local Operation of IRV-310, RHR Hx Outlet Valve REVISION 0 PROGRAM Initial Licensed Operator (ILT) TIME 15 Minutes SCOPE OF REVISION:
Initial Issue: Derived from Audit07-Inp02 & AE-O-E259 Revision 2:
DATE:
AUTHOR Name: John T Conrad Signature:
FACILITY Name:
REVIEWER Signature:
Facility Supervisor / Manager Page 1 of 6
TITLE: NRC2008-INP01 REVISION: 0 Local Operation of IRV-310, RHR Hx Outlet Valve REFERENCES 02-OHP 4025.R-12-16 Rev.4 Local Control of Air Operated Isolation Valves Task APR0010604 Locally control RHR and CVCS air operated regulating valves.
KA IMPORTANCE: SYS 005 A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the RHRS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: RHR valve malfunction KA VALUE: RO 2.9 SRO 2.9 EVALUATION SETTINGS In Plant HANDOUTS Task Briefing 02-OHP 4025.R-12-18, Section R-12-16 ATTACHMENTS
- 1. None SIMULATOR SETUP Not Applicable Page 2 of 6
TITLE: NRC2008-INP01 REVISION: 0 Local Operation of IRV-310, RHR Hx Outlet Valve TASK OBJECTIVES/STANDARDS Terminal Objective: When directed by the SM/US, establish local control of RHR air operated regulating valve IRV-310, RHR Hx Outlet valve, in accordance with the procedure and within a reasonable time.
TASK BRIEFING A fire has resulted in a control room evacuation and implementation of the Emergency Remote Shutdown Procedure. The control room crew has activated the Local Shutdown Stations. A cooldown was in progress using the East Train of RHR prior to the fire.
Unit 2 is in MODE 4.
Control air is available.
You are the auxiliary tour operator The Unit Supervisor directs you to establish local control of the East Residual Heat Removal heat exchanger Outlet flow control valve 2-IRV-310 and provides you with Section R-12-16 of 02-OHP 4025-R-12. You are to report back to the US once local control has been established.
Page 3 of 6
TITLE: NRC2008-INP01 REVISION: 0 Local Operation of IRV-310, RHR Hx Outlet Valve EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
General Standards:
- 1. Ensure correct Local Control Station located.
- 2. STAR performance should be observed.
General Feedback:
Valve full travel should be acknowledged by stating resistance is felt in that direction STANDARD: Operator proceeds to Auxiliary Building Elevator 609 STANDARD: The tag 2-IRV-310 on the EPT end of the flex hose is compared to the emergency connection tag "Emergency Control Air Supply Connection for 2-IRV-310. Operator verifies that the valve number on flex hose matches number on emergency connections.
Page 4 of 6
TITLE: NRC2008-INP01 REVISION: 0 Local Operation of IRV-310, RHR Hx Outlet Valve EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Full valve closure is simulated.
SAT: UNSAT:
STANDARD: CS Operator simulates pulling back retaining collar, then pulling hose free.
CUE: A brief hiss of air can be heard when disconnecting hoses.
Air flow may be continuous if control air isolation is not closed before removing the flex hose.
SAT: UNSAT:
STANDARD: CS Operator simulates pulling back retaining ring, then inserting hose.
SAT: UNSAT:
STANDARD: CS Operator simulates opening emergency control air supply valve.
SAT: UNSAT:
STANDARD: Operator notifies the US that he has taken local control of 2-IRV-310 E RHR Hx Outlet valve.
SAT: UNSAT:
CUE: US directs that IRV-310 is to be throttled closed. Indicate that IRV-310 air regulator pressure indicator shows 0 psig.
STANDARD: CS Operator adjusts air pressure regulator to throttle 2-IRV-310.
CUE: Indicate that Air regulator pressure indicator shows rising pressure as the regulator control handle is turned. Provide rising pressure indication up to 15 psig.
SAT: UNSAT:
EVALUATOR: When report is made state, This JPM is complete.
Page 5 of 6
TITLE: NRC2008-INP01 REVISION: 0 Local Operation of IRV-310, RHR Hx Outlet Valve EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Air Hose disconnected here.
Air Hose reconnected here.
Page 6 of 6
Task Briefing A fire has resulted in a control room evacuation and implementation of the Emergency Remote Shutdown Procedure. The control room crew has activated the Local Shutdown Stations. A cooldown was in progress using the East Train of RHR prior to the fire.
Unit 2 is in MODE 4.
Control air is available.
You are the auxiliary tour operator The Unit Supervisor directs you to establish local control of the East Residual Heat Removal heat exchanger Outlet flow control valve 2-IRV-310 and provides you with Section R-12-16 of 02-OHP 4025-R-12. You are to report back to the US once local control has been established.
NRC2008-INP01.doc Page 1 of 1
NRC2008-INP02 TITLE Modify, Relatch and Locally Start TDAFP REVISION 0 PROGRAM Initial Licensed Operator (ILT) TIME 10 Minutes SCOPE OF REVISION:
Initial Issue DATE:
AUTHOR Name: John T Conrad Signature:
FACILITY Name:
REVIEWER Signature:
Facility Supervisor / Manager Retention Requirements: Quality Page 1 of 10 1/080306/rs/ss
COURSE NUMBER NRC2008-INP02 AND TITLE: REVISION: 6 Modify, Relatch and Locally start TDAFP REFERENCES Procedures
2-OHP-4025-001-001 Sections LS 2-3 and LS 2-4 Tasks
- 0560030504 Locally start a TDAFP.
- 0560200204 Locally reset and latch the TDAFP Trip and Throttle Valve.
- 0560270604 Locally relatch TDAFP after remote controls fail.
KA IMPORTANCE: APE068 AA1.02 KA VALUE: RO: 4.3 SRO: 4.5 EVALUATION SETTINGS In Plant HANDOUTS Task Briefing 2-OHP 4025.LS-2, Sections LS2-3 and LS2-4 ATTACHMENTS
- 1. None SIMULATOR SETUP Not Applicable Retention Requirements: Quality Page 2 of 10 2/080306/rs/ss
COURSE NUMBER NRC2008-INP02 AND TITLE: REVISION: 6 Modify, Relatch and Locally start TDAFP TASK OBJECTIVES/STANDARDS Terminal Objective:
When directed by the Unit Supervisor Reset and Startup the Turbine Driven Auxiliary Feedwater Pump.
Enabling Objectives:
- 1. Locally reset and latch the TDAFP Trip and Throttle Valve after remote controls fail.
- 2. Locally startup the TDAFP .
TASK BRIEFING The Unit 2 Control Room has been evacuated due to heavy smoke from a fire in the control board panels. Neither Motor Driven AFW pump was capable of being started. You are a member of the Emergency Remote Shutdown (ERS) Team assembled in the Unit 1 Control Room.
You have been directed to relatch and start the TDAFP locally in accordance with 2-OHP 4025.LS-2-3, Relatch TDAFP, and LS-2-4, Start TDAFP.
Retention Requirements: Quality Page 3 of 10 3/080306/rs/ss
COURSE NUMBER NRC2008-INP02 AND TITLE: REVISION: 6 Modify, Relatch and Locally start TDAFP EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator reviews purpose and equipment requirements for performing LS.2-3 and LS.2-4 SAT: UNSAT:
Evaluator Note: Equipment lockers are located in various areas throughout the plant. A toolbox is located in the AFW Hallway for this task.
STANDARD: Operator obtains tools, keys, and protective clothing as specified Evaluator Note: The evaluator may ensure the operator knows what protective equipment is required and where it is located in-lieu of actually obtaining the protective equipment.
SAT: UNSAT:
Page 4 of 10
COURSE NUMBER NRC2008-INP02 AND TITLE: REVISION: 6 Modify, Relatch and Locally start TDAFP EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator verifies Valves open CUE: The US reports 2-MCM-221 and 231 are open at the Hot Shutdown Panel (HSD).
SAT: UNSAT:
STANDARD: Operator reviews notes prior to step 2 SAT: UNSAT:
STANDARD: CS Operator locates Panel 2-DCN and (simulates) places breaker Ckt. 6 in OFF position CUE: Initially breakers are in ON position (Evaluator may elect to locate panel at a different time to avoid extra trips into the Aux Bldg)
SAT: UNSAT:
STANDARD: CS Operator locates MCC 2-AM-A and (simulates) places breaker 2-AM-A-1B in OFF position SAT: UNSAT:
STANDARD: CS Operator locates MCC 2-AM-D and (simulates) places breaker 2-AM-D-R6C in OFF position CUE: Breakers are in OFF position SAT: UNSAT:
STANDARD: CS Operator locates panel VCC-2-AB-N cubicle 2-QT-506, simulates opening cubicle door and describes process of pulling fuses for 2-AB-N-3B (Picture provided for reference.)
CUE: Door is open and fuses pulled SAT: UNSAT:
Page 5 of 10
COURSE NUMBER NRC2008-INP02 AND TITLE: REVISION: 6 Modify, Relatch and Locally start TDAFP EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Evaluator Note: Emergency modification equipment box is located in the AFW pump area.
STANDARD: CS Operator locates Subpanel 2-TFP and identifies that this action is to be performed inside the subpanel.
Evaluator Note: Opening door to subpanel is not required. (Picture provided for reference.)
CUE: The wires have been lifted on Terminal Block TCE and Terminal Block TCF SAT: UNSAT:
Page 6 of 10
COURSE NUMBER NRC2008-INP02 AND TITLE: REVISION: 6 Modify, Relatch and Locally start TDAFP EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator identifies that this action is to be performed inside subpanel 2-TFP.
CUE: A Jumper has been placed between points 14A and 15 on Terminal Block TCF SAT: UNSAT:
STANDARD: CS Operator Returns to panel 2-DCN and (simulates) closes circuit 6 Evaluator Note: Evaluator may ask location of panel 2-DCN in-lieu of returning to the panel or locate the panel at a different time - same breaker as in step 2.a.)
CUE: Circuit 6 is in ON position SAT: UNSAT:
Page 7 of 10
COURSE NUMBER NRC2008-INP02 AND TITLE: REVISION: 6 Modify, Relatch and Locally start TDAFP EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: CS Operator checks TTV latched CUE: Latching mechanism is not engaged SAT: UNSAT:
STANDARD: CS Operator (simulates) performs RNO: TTV Clutch pushed in downward direction to engage handwheel CUE: Clutch lever lowers and will not move any further SAT: UNSAT:
STANDARD: CS Operator (simulates) turns TTV handwheel clockwise until latching lever raises to RESET position CUE: Latching mechanism is engaged in the reset position SAT: UNSAT:
STANDARD: Operator reports TDAFP is latched.
CUE: I understand that the TDAFP is latched, start the TDAFP in accordance with LS-2-4.
SAT: UNSAT:
Page 8 of 10
COURSE NUMBER NRC2008-INP02 AND TITLE: REVISION: 6 Modify, Relatch and Locally start TDAFP EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator acknowledges that LS-2-3 is complete SAT: UNSAT:
STANDARD: CS Operator (simulates) slowly turns TTV handwheel counterclockwise until speed indications stops rising then fully opens TTV CUE: As TTV is opened, operator hear sound of TDAFP coming up to spped. (Operator may determine rising TDAFP speed and stabilization by sound of TDAFP as it comes up to speed.)
If needed provide rising speed indications until turbine speed is at 4110 rpm and then stops rising. After speed stabilizes, operator continues to turn TTV handwheel in CCW direction SAT: UNSAT:
STANDARD: Operator Checks for proper operation CUE: No unusual noise, no excessive vibrations, and no oil leaks SAT: UNSAT:
STANDARD: Reports task complete SAT: UNSAT:
EVALUATOR: This JPM is complete.
Page 9 of 10
COURSE NUMBER NRC2008-INP02 AND TITLE: REVISION: 6 Modify, Relatch and Locally start TDAFP Describe observable elements. Do Not Provide Cues such as Trip lever is in the reset position.
Standard:
CT Operator moves the lever toward the outboard housing Standard:
CT Operator engages handwheel, manually opens TTV and ensures latch-up lever catches in trip hook Standard:
Operator verifies valve is latched.
NOTE: After completion, have operator actuate the manual overspeed trip and close the TTV Page 10 of 10
COURSE NUMBER NRC2008-INP02 AND TITLE: REVISION: 6 Modify, Relatch and Locally start TDAFP TASK BRIEFING The Unit 2 Control Room has been evacuated due to heavy smoke from a fire in the control board panels. Neither Motor Driven AFW pump was capable of being started. You are a member of the Emergency Remote Shutdown (ERS) Team assembled in the Unit 1 Control Room.
You have been directed to relatch and start the TDAFP locally in accordance with 2-OHP 4025.LS-2-3, Relatch TDAFP, and LS-2-4, Start TDAFP.
Page 1 of 1
NRC2008-INP03 TITLE Perform an Authorized Gaseous Release REVISION 0 PROGRAM Initial Licensed Operator (ILT) TIME 25 Minutes SCOPE OF REVISION:
Initial Issue DATE:
AUTHOR Name: John T Conrad Signature:
FACILITY Name:
REVIEWER Signature:
Facility Supervisor / Manager Page 1 of 3
COURSE NUMBER NRC2008-INP03 - Perform an Authorized REVISION: 0 AND TITLE: Gaseous Release REFERENCES 12-OHP-4021.023.002, Release of Radioactive Waste From Gas Decay Tanks Task: 0230120104; Release a Gas Decay Tank to atmosphere K/A CROSS
REFERENCE:
071 A4.26 K/A IMPORTANCE: RO 3.1 SRO 3.9 Evaluation Setting In-Plant (573 elevation Aux Building)
Handouts Task Briefing Gas Release Package (attachments listed below)
ATTACHMENTS
- 1. 12-OHP 4021.023.002, Attachment 2 completed through step 4.5.
- 2. 12-OHP 4021.023.002, Data Sheet 1, completed through Section 3.0
- 3. 12-OHP 4021.023.002, Figure 1 SIMULATOR SETUP N/A Page 2 of 3
COURSE NUMBER NRC2008-INP03 - Perform an Authorized REVISION: 0 AND TITLE: Gaseous Release Task Objectives/Standards Release the contents of #1 Gas Decay Tank to the vent header in accordance with the release procedure.
Task Briefing
- 1 Gas Decay Tank has been isolated, sampled, and approved for release. 12-OHP 4021.023.002, Release Of Radioactive Waste From Gas Decay Tanks, Attachment 2, Release of Radioactive Gaseous Waste From Gas Decay Tanks, has been completed up through step 4.5. Data Sheet 1, Gas Decay Tank Release Permit, is complete up through section 3.0. All support equipment and instrumentation required for this release is in service and properly calibrated.
The US has directed you to perform a Gaseous Waste Release from #1 Gas Decay Tank beginning with step 4.6.
Meteorological and Ventilation Data is as follows for time of release:
Wind Speed: 6.2 mph Wind Direction: 200 Temp Diff: - 1 Vent Stack Flow: 9.25E4 scfm; Initial Tank Pressure: 97 psig Page 3 of 3
COURSE NUMBER NRC2008-INP03 - Perform an Authorized Gaseous Release REVISION: 0 AND TITLE:
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Evaluator Note: Valves on this page located on 573 of Aux. Bldg.
STANDARD: Operator verifies 12-CS-531 closed CUE: Indicator pin is in CLOSE position SAT: UNSAT:
STANDARD: Operator verifies 12-CS-532 closed CUE: (Handwheel on chan in bomb box) Movement when pulled in the closed direction.
SAT: UNSAT:
STANDARD: Operator verifies 12-CS-533 closed CUE: Indicator pin is in CLOSE position SAT: UNSAT:
Page 1 of 10
COURSE NUMBER NRC2008-INP03 - Perform an Authorized Gaseous Release REVISION: 0 AND TITLE:
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Evaluator Notes: Following valves located on 587 of Aux. Bldg.
All valves for GDT #1 are initially closed STANDARD: Operator verifies 12-NS-440-1 Closed Checks and initials CUE: No handwheel movement when turned in the closed direction (stem is in).
SAT: UNSAT:
Page 2 of 10
COURSE NUMBER NRC2008-INP03 - Perform an Authorized Gaseous Release REVISION: 0 AND TITLE:
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator verifies 12-WD-227-1 Closed Checks and initials CUE: No handwheel movement when turned in the closed direction (stem is in).
SAT: UNSAT:
Page 3 of 10
COURSE NUMBER NRC2008-INP03 - Perform an Authorized Gaseous Release REVISION: 0 AND TITLE:
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator verifies 12-WD-231-1 Closed Checks and initials CUE: No handwheel movement when turned in the closed direction. (stem is in)
SAT: UNSAT:
Page 4 of 10
COURSE NUMBER NRC2008-INP03 - Perform an Authorized Gaseous Release REVISION: 0 AND TITLE:
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: CS Operator (simulates) opens 12-WD-229-1 Checks and initials CUE: Handwheel turns when operated in the open direction then stops when fully open. (stem is out)
SAT: UNSAT:
Page 5 of 10
COURSE NUMBER NRC2008-INP03 - Perform an Authorized Gaseous Release REVISION: 0 AND TITLE:
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Evaluator Notes: All WD-230 valves are initially closed.
STANDARD: Operator verifies 12-WD-230-1 Closed CUE: No handwheel movement when turned in the closed direction (stem is in)
SAT: UNSAT:
STANDARD: Operator verifies 12-WD-230-2 Closed CUE: No handwheel movement when turned in the closed direction (stem is in)
SAT: UNSAT:
STANDARD: Operator verifies 12-WD-230-3 Closed CUE: No handwheel movement when turned in the closed direction (stem is in)
SAT: UNSAT:
STANDARD: Operator verifies 12-WD-230-4 Closed CUE: No handwheel movement when turned in the closed direction (stem is in)
SAT: UNSAT:
Page 6 of 10
COURSE NUMBER NRC2008-INP03 - Perform an Authorized Gaseous Release REVISION: 0 AND TITLE:
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator verifies 12-WD-230-5 Closed CUE: No handwheel movement when turned in the closed direction (stem is in)
SAT: UNSAT:
STANDARD: Operator verifies 12-WD-230-6 Closed CUE: No handwheel movement when turned in the closed direction (stem is in)
SAT: UNSAT:
STANDARD: Operator verifies 12-WD-230-7 Closed CUE: No handwheel movement when turned in the closed direction (stem is in)
SAT: UNSAT:
STANDARD: Operator verifies 12-WD-230-8 Closed CUE: No handwheel movement when turned in the closed direction (stem is in)
SAT: UNSAT:
Page 7 of 10
COURSE NUMBER NRC2008-INP03 - Perform an Authorized Gaseous Release REVISION: 0 AND TITLE:
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: CS Operator (simulates) opens 12-WD-230-1 Checks and initials CUE: Handwheel turns when operated in the open direction then stops when fully open (stem is out)
SAT: UNSAT:
STANDARD: CS Operator (simulates) opens 12-WD-298 and initials CUE: Handwheel turns when operated in the open direction then stops when fully open (stem is out)
SAT: UNSAT:
Page 8 of 10
COURSE NUMBER NRC2008-INP03 - Perform an Authorized Gaseous Release REVISION: 0 AND TITLE:
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Evaluator Note: 12-WD-297 seal must be broken to open valve.
STANDARD: CS Operator (simulates) opens 12-WD-297 CUE: Handwheel turns when rotated in the open direction (stem is out).
SAT: UNSAT:
STANDARD: Operator checks reading on 12-MR-57 (12-RFR-300)
CUE: 12-MR-57 (12-RFR-300) reads 0 scfm.
SAT: UNSAT:
STANDARD: CS Operator records Initial Data in Section 4 (Provided in Task Brief)
SAT: UNSAT:
STANDARD: Operator verifies 12-RRV-305 set for 4 - 5 psig SAT: UNSAT:
STANDARD: Operator determines 12-RRV-306 position (98 -
100%)
SAT: UNSAT:
Page 9 of 10
COURSE NUMBER NRC2008-INP03 - Perform an Authorized Gaseous Release REVISION: 0 AND TITLE:
EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: CS Operator (simulates) opens 12-RRV-306 while observing flow on RFR-300 CUE: Flow is rising as valve is simulated being opened (red light lit). Flow is 120 scfm with valve fully open.
SAT: UNSAT:
STANDARD: Operator records 120 scfm for Release Flow Data in Section 4 SAT: UNSAT:
CUE: If asked, no alarms on VRS-1505 and VRS-2505 CUE: Source flow rate: 120 scfm; GDT discharge pressure: 4.5 psig; Unit vent flow: 9.25E4 scfm; GDT #1 pressure 94 psig (and lowering 3 psig/min.)
STANDARD: Operator determines that no adjustments are necessary SAT: UNSAT:
Evaluator Note: Time compression may be used to lower GDT pressure to desired value CUE: Gas Decay Tank #1 pressure is 12 psig STANDARD: CS Operator stops release, by (simulates) closing 12-RRV-306, prior to lowering GDT pressure below 10 psig CUE: Flow is lowering as valve is simulated being closed (green light lit). Flow is 0 scfm with valve fully closed.
SAT: UNSAT:
Evaluator: This JPM is complete.
Page 10 of 10
Task Briefing
- 1 Gas Decay Tank has been isolated, sampled, and approved for release. 12-OHP 4021.023.002, Release Of Radioactive Waste From Gas Decay Tanks, Attachment 2, Release of Radioactive Gaseous Waste From Gas Decay Tanks, has been completed up through step 4.5. Data Sheet 1, Gas Decay Tank Release Permit, is complete up through section 3.0. All support equipment and instrumentation required for this release is in service and properly calibrated.
The US has directed you to perform a Gaseous Waste Release from #1 Gas Decay Tank beginning with step 4.6.
Meteorological and Ventilation Data is as follows for time of release:
Wind Speed: 6.2 mph Wind Direction: 200 Temp Diff (T): -1F Vent Stack Flow: 9.25E4 scfm; Initial Tank Pressure: 97 psig NRC2008-INP03.doc Page 1 of 1