ML100840755

2008 D.C. Cook Initial License Examination Administered JPMs

ML100840755
Person / Time
Site:	Cook
Issue date:	08/18/2008
From:	Bielby M E 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: Name: J. T. Conrad 3/14/2008 DEVELOPING INSTRUCTOR:

Signature:

OPERATIONS REVIEW: Name: Signature:

Page 1 of 7

TITLE: NRC2008-A1a Boron Volume Determination REVISION: 0 Page 2 of 7 REFERENCES Unit 2 Technical Data Book Cycle 17 02-OHP-4021-005-002 Rev 3 O peration 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, su ch as reactor coolant system temperature, secondary plan t, 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 Atta chment 9 Boron or Dilut ion Volume Determination Copy of Unit 2 Technical Data Book cu rves (Sections 3, 4, 5, 6, and 7)

ATTACHMENTS

None SIMULATOR SETUP

None TITLE: NRC2008-A1a Boron Volume Determination REVISION: 0 Page 3 of 7 TASK OBJECTIVES The required Boron Addi tion 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, Operati on 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 Bor on or PW required to be added to the VCT. Another Operator will determine the effects of the fl uid within the CVCS piping.

NOTE Simulator Indications are NOT applicable to this JPM

TITLE: NRC2008-A1a - Boron Volume Determination REVISION: 0 Page 4 of 7 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

ACTIONS:

STANDARD: Determines that se ction 4.1.2 is applicable SAT: UNSAT:

TITLE: NRC2008-A1a - Boron Volume Determination REVISION: 0 Page 5 of 7 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:

TITLE: NRC2008-A1a - Boron Volume Determination REVISION: 0 Page 6 of 7 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 E ffective 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) ( Ra nge -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:

TITLE: NRC2008-A1a - Boron Volume Determination REVISION: 0 Page 7 of 7 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."

Task Briefing NRC2008-A1a.doc Page 1 of 1 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, Operati on 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 Bo ron or PW required to be added to the VCT. Another Operator will determine the effects of the fl uid within the CVCS piping.

NOTE Simulator Indications are NOT applicable to this JPM

Page 1 of 6

NRC2008-A1b-R

TITLE Calculate QPTR with Inoperable Power Range Instrument REVISION 0 PROGRAM Initial Licensed Operator (ILT)

TIME 15 Minutes

SCOPE OF REVISION:

Initial Issue

From Audit07-A1a

DATE: Name: John T Conrad AUTHOR Signature:

Name: FACILITY REVIEWER Signature:

Facility Supervisor / Manager

TITLE: NRC2008-A1b-R Calculate QPTR with Inoperable Power Range Instrument REVISION: 0 Page 2 of 6 REFERENCES 01-OHP-4030-114-032, Rev 0, Quadrant Power Tilt Calculation

Task: 0130180201 Perform Quadrant Po wer Tilt Ratio Calculation

K/A CROSS

REFERENCE:

2.1.7 Ability

to evaluate plant performance and make operational judgements based on operating characte ristics, reactor behavior, and in strumentation 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 TITLE: NRC2008-A1b-R Calculate QPTR with Inoperable Power Range Instrument REVISION: 0 Page 3 of 6 TASK OBJECTIVES/STANDARDS Correctly obtain values and calculates a Quadrant Power Tilt Ratio calcul ation 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 di splay maximum resolution and the fluke readings confirm that the indicators are reading properly.

TITLE: NRC2008-A1b-R Calculate QPTR with Inoperable Power Range Instrument REVISION: 0 Page 4 of 6 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 de tector readings (within +0.5) on a division mark and wit hin 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 res pective NI channel with its 120% value (from cards on channel 3 NI panel)

SAT: UNSAT:

STANDARD: Operator totals 3 c hannels of normalized values SAT: UNSAT:

STANDARD:

CS: Operator determines upper and lower QPTR

using data sheet 3 with an accu racy of .01 of Exam Team calculated value (Enter data into spreadsheet for comparison)

SAT: UNSAT:

STANDARD: Operator enters the hi ghest calculated QPTR (CS:

Covered on Page 6 of this section)

SAT: UNSAT: N/A TITLE: NRC2008-A1b-R Calculate QPTR with Inoperable Power Range Instrument REVISION: 0 Page 5 of 6 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

STANDARD:

CS Operator Determines that Acceptance Criteria is NOT Met (QPTR > 1.02) and Noti fies SM & Reactor Engineering SAT: UNSAT:

CUE: SM Acknowledges that QPTR has Exceeded TS value and will address the required actions.

TITLE: NRC2008-A1b-R Calculate QPTR with Inoperable Power Range Instrument REVISION: 0 Page 6 of 6 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

Data entered on this page based on Simulator readings.

Enter data into QPTR calculat ion spreadsheet to determine accuracy of candidate's calculation

Reference Step 4.3.6 for criteria

STANDARD:

CS Operator enters the highest calculated QPTR of

these 2 values

STANDARD: Candidate marks "N/A"

STANDARD:

CS Operator Determines that Acceptance Criteria is NOT Met (QPTR > 1.02) and Notifi es 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."

41 43 44 41 43 44 1.0081 1.0314 1.0314 N/A 98.8 135.4 .7297 98.4 134.4 .7321 98.0 136.7 .7169 2.1787 91.8 135.6 .6770 98.2 134.7 .7290 97.3 136.2 .7144 2.1204 NRC2008-A1b-R.doc Page 1 of 1 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 1 of 7

NRC2008-A1b-S

TITLE Review QPTR with Inoperable Power Range

Instrument REVISION 0 PROGRAM Initial Licensed Operator (ILT)

TIME 15 Minutes

SCOPE OF REVISION:

Initial Issue

From Audit07-A1a

DATE: Name: John T Conrad AUTHOR Signature:

Name: FACILITY REVIEWER Signature:

Facility Supervisor / Manager

TITLE: NRC2008-A1b-S Review QPTR with Inoperable Power Range Instrument REVISION: 0 Page 2 of 7 References

01-OHP-4030-114-032, Rev 0, Quadrant Power Tilt Calculation

Task: 0130180201 Perform Quadrant Po wer Tilt Ratio Calculation

K/A CROSS

REFERENCE:

2.1.7 Ability

to evaluate plant performance and make operational judgements based on operating characte ristics, reactor behavior, and in strumentation 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 TITLE: NRC2008-A1b-S Review QPTR with Inoperable Power Range Instrument REVISION: 0 Page 3 of 7 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 e rror 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-O HP-4030-114-032, Quadrant Powe r Tilt Calculation.

The NI amp meters are set to di splay maximum resolution and the fluke readings confirm that the indicators are reading properly.

TITLE: NRC2008-A1b-S Review QPTR with Inoperable Power Range Instrument REVISION: 0 Page 4 of 7 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

STANDARD:

CS Operator identifies that value was incorrectly

calculated. Should be 1.0314 resulting in excessive QPTR. (Range of 1.030 to 1.032)

SAT: UNSAT:

STANDARD:

CS Operator Determines that Acceptance Criteria is NOT Met (QPTR > 1.02) and Notifies SM

SAT: UNSAT: 41 43 44 41 43 44 1.0081 1.0031 1.0081 N/A 98.8 135.4 .7297 98.4 134.4 .7321 98.0 136.7 .7169 2.1787 91.8 135.6 .6770 98.2 134.7 .7290 97.3 136.2 .7144 2.1204 TITLE: NRC2008-A1b-S Review QPTR with Inoperable Power Range Instrument REVISION: 0 Page 5 of 7 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

STANDARD:

CS Operator Determines that Acceptance Criteria is NOT Met (QPTR > 1.02) and Notifi es 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.

TITLE: NRC2008-A1b-S Review QPTR with Inoperable Power Range Instrument REVISION: 0 Page 6 of 7 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 every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, Verify )(Z F C is within limit., Verify )(Z F W is within limit, & Verify Q Q F N his within limits specified in the COLR.

SAT: UNSAT:

TITLE: NRC2008-A1b-S Review QPTR with Inoperable Power Range Instrument REVISION: 0 Page 7 of 7 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."

NRC2008-A1b-S.doc Page 1 of 1 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-O HP-4030-114-032, Quadrant Powe r Tilt Calculation.

The NI amp meters are set to display maximum resolution and the fluke readings confirm that the indicators are reading properly.

Page 1 of 4

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: Name: John T Conrad AUTHOR Signature:

Name: FACILITY REVIEWER Signature:

Facility Supervisor / Manager

TITLE: NRC2008-A2 - SRO Review of Unit 1 LTOP Verification REVISION: 0 Page 2 of 4 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 fo r system operating param eters 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 Un it 1 are met per 01-OHP-4030-114-030, Daily and

Shiftly Surveillance Checks, Data Sheet 20A TITLE: NRC2008-A2 - SRO Review of Unit 1 LTOP Verification REVISION: 0 Page 3 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 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

Selector Cold Over-Pressure Block for

1-NRV-152 Cold Over Press 1-NRV-153 Control

Selector Cold Over-Pressure Block for

1-NRV-153 Cold Over Press 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

Drop 27 1-NRV-152 EMER AIR TANK

PRESSURE LOW NOT Lit Annunciator Panel 108

Drop 28 1-NRV-153 EMER AIR TANK

PRESSURE LOW Lit 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 185 o 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 400 o F 1-IMO-110, 120, 130, 140 SI Accumulator Is olation Valves Closed & De-Energized NOTE Simulator Indications are NOT applicable to this JPM TITLE: NRC2008-A2 - SRO Review of Unit 1 LTOP Verification REVISION: 0 Page 4 of 4 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)

X's in Circles are wrong, Empty Circles Should Have X's

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:

Instructor Note:

DataSheet 20B is for LCO 3.4.12.B when Both CCPs are available.

EVALUATOR:

"This JPM is complete."

N/A NRC2008-A2.doc Page 1 of 1 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

Selector Cold Over-Pressure Block for

1-NRV-152 Cold Over Press 1-NRV-153 Control

Selector Cold Over-Pressure Block for

1-NRV-153 Cold Over Press 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

Drop 27 1-NRV-152 EMER AIR TANK

PRESSURE LOW NOT Lit Annunciator Panel 108

Drop 28 1-NRV-153 EMER AIR TANK

PRESSURE LOW Lit 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 185 o 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 400 o F 1-IMO-110, 120, 130, 140 SI Accumulator Is olation Valves Closed & De-Energized NOTE Simulator Indications are NOT applicable to this JPM

NRC2008-A3 TITLE: Perform Containment Pressure Relief REVISION: 0 PROGRAM NRC License Exam TIME: 20 Minutes

From NRC2004-A3

DATE: Name: J. T. Conrad 3/14/2008 DEVELOPING INSTRUCTOR:

Signature:

OPERATIONS REVIEW: Name: Signature:

Page 1 of 14

REVISION: 0 TITLE: NRC2008-A3 Perform Containment Pressure Relief Page 2 of 14 REFERENCES 02-OHP 4021.028.004, Rev. 18 O peration of the Containment Pressure Relief System

TASK: 0280080101 Perform A Containment Pressure Relief K/A: 2.3.11 Ability to c ontrol radiation releases K/A IMPORTANCE: RO 3.8 SRO 4.3

Evaluation Setting

Unit 2 Simulator

Handouts Task Briefing

02-OHP 4021.028.004, Oper ation of the Cont ainment 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}

TITLE: NRC2008-A3 Perform Containment Pressure Relief REVISION: 0 Page 3 of 14 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 cha nnels are operable.

The Unit Supervisor directs you to perform a c ontainment pressure relie f 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.

REVISION: 0 TITLE: NRC2008-A3 - Perform Containment Pressure Relief Page 4 of 14 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.}

REVISION: 0 TITLE: NRC2008-A3 - Perform Containment Pressure Relief Page 5 of 14 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

Information in this note is typica lly 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 determi nes that ALL channels are OPERABLE SAT: UNSAT:

REVISION: 0 TITLE: NRC2008-A3 - Perform Containment Pressure Relief Page 6 of 14 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."

REVISION: 0 TITLE: NRC2008-A3 - Perform Containment Pressure Relief Page 7 of 14 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.}

REVISION: 0 TITLE: NRC2008-A3 - Perform Containment Pressure Relief Page 8 of 14 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

STANDARD: Initial Data Sheet 1

SAT: UNSAT:

N/A

N/A

REVISION: 0 TITLE: NRC2008-A3 - Perform Containment Pressure Relief Page 9 of 14 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.

REVISION: 0 TITLE: NRC2008-A3 - Perform Containment Pressure Relief Page 10 of 14 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 ar e 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 se cs) SAT: UNSAT:

N/A

STANDARD: Operator records start time in Section B

SAT: UNSAT:

REVISION: 0 TITLE: NRC2008-A3 - Perform Containment Pressure Relief Page 11 of 14 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 REVISION: 0 TITLE: NRC2008-A3 - Perform Containment Pressure Relief Page 12 of 14 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

NOTE: Included for information only.

REVISION: 0 TITLE: NRC2008-A3 - Perform Containment Pressure Relief Page 13 of 14 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

NOTE: Included for information only.

TITLE: NRC2008-A3 - Perform Containment Pressure Relief REVISION: 0 Page 14 of 14 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

NOTE: Included for information only.

Task Briefing NRC2008-A3.doc Page 1 of 1

Lower containment pressure has risen to approximately 0.19 psig due to atmospheric pressure

changes. All RMS cha nnels are operable.

The Unit Supervisor directs you to perform a c ontainment pressure relie f 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 1 of 5

NRC2008-A4-R

TITLE Complete EMD-32a Nuclear Plant Notification

Form REVISION 0 PROGRAM Initial Licensed Operator (ILT)

TIME 10 Minutes

SCOPE OF REVISION:

Initial Issue

From NRC2004-A4

DATE: Name: John T Conrad AUTHOR Signature:

Name: FACILITY REVIEWER Signature:

Facility Supervisor / Manager

TITLE: NRC2008-A4-R Complete EMD-32a Nuclear Plant Event Notification REVISION: 0 Page 2 of 5 REFERENCES Procedure: PMP-2080-EPP-108, Initial Dose Assessment Task: EPP 0030701 Perform Init ial 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 No tification (blank form)

ATTACHMENTS

None

SIMULATOR SETUP

None

TASK OBJECTIVES/STANDARDS

Complete the EMD-32a, Nuclear Plant Event Notifica tion form to notify of state/county agencies within 15 minutes.

TITLE: NRC2008-A4-R Complete EMD-32a Nuclear Plant Event Notification REVISION: 0 Page 3 of 5 TASK BRIEFING

You are an extra Control Room Operator on Unit 1.

At the beginning of your shift, Unit 1 was operat ing 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 - MI DAS Summary is provided.

NOTE Simulator Indications are NOT applicable to this JPM

TITLE: NRC2008-A4-R - Complete EMD-32a Nuclear Plant Event Notification REVISION: 0 Page 4 of 5 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.

TITLE: NRC2008-A4-R - Complete EMD-32a Nuclear Plant Event Notification REVISION: 0 Page 5 of 5 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."

NRC2008-A4-R.doc Page 1 of 2 Task Briefing

You are an extra Control Room Operator on Unit 1.

At the beginning of your shift, Unit 1 was operat ing 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 - MI DAS Summary is provided.

NOTE Simulator Indications are NOT applicable to this JPM

NRC2008-A4-R.doc Page 2 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 Page 1 of 3

NRC2008-A4-S

TITLE Emergency Plan Cla ssification With PAR REVISION 0 PROGRAM NRC License Exam TIME 15 Minutes Minor Revision: Updated from Audit06-A5 & SR-O-E008 with current revisions.

DATE: Name: J. T. Conrad 3/14/2008 DEVELOPING INSTRUCTOR:

Signature:

OPERATIONS REVIEW: Name: Signature:

NUMBER AND TITLE: NRC2008-A4-S Emergency Plan Cla ssification With PAR REVISION: 0 Page 2 of 8 REFERENCES Procedure: PMP-2080-EPP-101 Revision 12 Emergency Classification Task: EPP0020703 Classify an Emergency Condition

K/A: 2.4.41 Knowledge of the emer gency 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 emer gency 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 NUMBER AND TITLE: NRC2008-A4-S Emergency Plan Cla ssification With PAR REVISION: 0 Page 3 of 8 TASK OBJECTIVES/STANDARDS In accordance with procedures when an emergency ev ent 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 trip

s. Both SI pumps trip on over current and CTS actuates automatically with RCPs secu red by the RO shortly thereafter. The crew had transitioned to OHP-4023-E-1, Loss of Reactor or Secondary C oolant, 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 indicate s 44% and slowly lowering The MET data indicates no precipitati on 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 traffi c 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

NUMBER AND TITLE: NRC2008-A4-S Emergency Plan Cla ssification With PAR REVISION: 0 Page 4 of 8 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 determi nes POTIENTIAL LOSS of Containment based upon 3.7 (Next Page)

SAT: UNSAT:

STANDARD:

CS The classification for th is event is "General Emergency".

SAT: UNSAT:

STANDARD:

CS Record Classification Time ______________

(</= 15 minutes from Start)

SAT: UNSAT:

NUMBER AND TITLE: NRC2008-A4-S Emergency Plan Cla ssification With PAR REVISION: 0 Page 5 of 8 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

Candidate determines POTENTIA L LOSS of Containment based upon 3.7 (Continued)

NUMBER AND TITLE: NRC2008-A4-S Emergency Plan Cla ssification With PAR REVISION: 0 Page 6 of 8 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.

NUMBER AND TITLE: NRC2008-A4-S Emergency Plan Cla ssification With PAR REVISION: 0 Page 7 of 8 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:

NUMBER AND TITLE: NRC2008-A4-S Emergency Plan Cla ssification With PAR REVISION: 0 Page 8 of 8 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 Re commendation 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 NRC2008-A4-S.doc Page 1 of 1 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 trip

s. Both SI pumps trip on over current and CTS actuates automatically with RCPs secu red by the RO shortly thereafter. The crew had transitioned to OHP-4023-E-1, Loss of Reactor or Secondary C oolant, 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 indicate s 44% and slowly lowering The MET data indicates no precipitati on 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 traffi c 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-Sim01

TITLE Dilute the RCS (ALT)

REVISION 0 PROGRAM Initial Licensed Operator (ILT)

TIME 15 Minutes

SCOPE OF REVISION:

Initial Issue

DATE: Name: John T Conrad AUTHOR Signature:

Name: FACILITY REVIEWER Signature:

Facility Supervisor / Manager

Page 1 of 9

TITLE: NRC2008-Sim01 (ALT)

Dilute the RCS.

REVISION: 0 Page 2 of 9 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.

TITLE: NRC2008-Sim01 (ALT)

Dilute the RCS.

REVISION: 0 Page 3 of 9 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 Blen der using Normal Dilute Mode.

TASK BRIEFING

You are the extra RO.

The following conditions exist:

• Unit is in Mode 3 preparing for startup.

• RCS Boron concentration is1517 ppm.

• 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 gall ons 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.

TITLE: NRC2008-Sim01 - Dilute the RCS. (ALT)

REVISION: 0 Page 4 of 9 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 Attach ment 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 Di lutions are NOT expected.

TITLE: NRC2008-Sim01 - Dilute the RCS. (ALT)

REVISION: 0 Page 5 of 9 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 not ifies the Unit Supervisor.

SAT: UNSAT:

CUE: When notified, inform operator that the 100 gal. dilution is still desired and ask for a recomme ndation. If required, the Unit

Supervisor informs the operator to return the blender to AUTO and then perform an Alternate Dilution for 100 GPM.

TITLE: NRC2008-Sim01 - Dilute the RCS. (ALT)

REVISION: 0 Page 6 of 9 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

STANDARD: Operator verifies Blend Control Switch is in STOP SAT: UNSAT:

STANDARD: Operator verifies co ntrollers 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 1, 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:

TITLE: NRC2008-Sim01 - Dilute the RCS. (ALT)

REVISION: 0 Page 7 of 9 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 Attach ment 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.

TITLE: NRC2008-Sim01 - Dilute the RCS. (ALT)

REVISION: 0 Page 8 of 9 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:

TITLE: NRC2008-Sim01 - Dilute the RCS. (ALT)

REVISION: 0 Page 9 of 9 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

CUE , if required: It is NOT de sired 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 Attach ment 1 Must be performed (Next page)

CUE: .Another operator will align the blender of AUTO.

EVALUATOR: "This JPM is Complete"

Task Briefing NRC2008-Sim01.doc Page 1 of 1 You are the extra RO.

The following conditions exist: Unit is in Mode 3 preparing for startup. RCS Boron concentration is1517 ppm. 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 gall ons 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 1 of 15

NRC2008-Sim02

TITLE Raise SI Accumulator Level (with Faulted

Pressure Relief Valve)

REVISION 0 PROGRAM Initial Licensed Operator (ILT)

TIME 15 Minutes

SCOPE OF REVISION:

Initial Issue

Developed from N02-02, JPM m odified from RO-O-NO66 rev 4

DATE: Name: John T Conrad AUTHOR Signature:

Name: FACILITY REVIEWER Signature:

Facility Supervisor / Manager

COURSE NUMBER AND TITLE:

NRC2008-Sim02 Raise SI Accumulator Level (with Faulted Pressure Relief Valve)

REVISION: 0 Page 2 of 15 REFERENCES 02-OHP-4021-008-004, Rev 20 Adjusting level of an Accumulator 02-OHL-4030-SOM-042, Rev 20 Unit 2 T ours - 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 Attach ment 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 FT 3 Ensure any caution tags have been removed from the Accum. Drain Valves Restore drain lineup to normal, adjus t 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.

COURSE NUMBER AND TITLE:

NRC2008-Sim02 Raise SI Accumulator Level (with Faulted Pressure Relief Valve)

REVISION: 0 Page 3 of 15 TASK OBJECTIVES/STANDARDS Performs a fill on #1 Accumulator, observing all applicable precautions and lim itations 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 f ill 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 candida te to distribute Attachment 5)

Given the following: You are the "extra" RO brought in to perform this task.

Chemistry inadvertently drained #1 accu mulator 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 th rough 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 st ep 4.9 of 02-OHP-4021-008-004 Attachment 3.

All procedure prerequisites, precaut ions and limitations have been met.

COURSE NUMBER AND TITLE: NRC2008-Sim02 Raise SI Accumulator Level (with Faulted Pressure Relief Valve) REVISION: 0 Page 4 of 15 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

Notes To Evaluator

This Alt Path JPM evaluates candidate's 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:

COURSE NUMBER AND TITLE: NRC2008-Sim02 Raise SI Accumulator Level (with Faulted Pressure Relief Valve) REVISION: 0 Page 5 of 15 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

(Pages included for review purposes)

JTC JTC X COURSE NUMBER AND TITLE: NRC2008-Sim02 Raise SI Accumulator Level (with Faulted Pressure Relief Valve) REVISION: 0 Page 6 of 15 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

Operator reviews steps 4.1 through 4.8 are complete

(Pages included for review purposes)

JTC JTC JTC N/A COURSE NUMBER AND TITLE: NRC2008-Sim02 Raise SI Accumulator Level (with Faulted Pressure Relief Valve) REVISION: 0 Page 7 of 15 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

Operator reviews steps 4.1 through 4.8 are complete

(Pages included for review purposes)

JTC S P JTC JTC JTC S P COURSE NUMBER AND TITLE: NRC2008-Sim02 Raise SI Accumulator Level (with Faulted Pressure Relief Valve) REVISION: 0 Page 8 of 15 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:

COURSE NUMBER AND TITLE: NRC2008-Sim02 Raise SI Accumulator Level (with Faulted Pressure Relief Valve) REVISION: 0 Page 9 of 15 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 prio r 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:

COURSE NUMBER AND TITLE: NRC2008-Sim02 Raise SI Accumulator Level (with Faulted Pressure Relief Valve) REVISION: 0 Page 10 of 15 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 Noti fication 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.

COURSE NUMBER AND TITLE: NRC2008-Sim02 Raise SI Accumulator Level (with Faulted Pressure Relief Valve) REVISION: 0 Page 11 of 15 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 yo u to adjust Accumulator #1 to within Tech Spec limits/Notificati on 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:

COURSE NUMBER AND TITLE: NRC2008-Sim02 Raise SI Accumulator Level (with Faulted Pressure Relief Valve) REVISION: 0 Page 12 of 15 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 st ep 4.4 (2-IRV-112 is OOS and

level is being lowered to lower pressure)

SAT: UNSAT:

COURSE NUMBER AND TITLE: NRC2008-Sim02 Raise SI Accumulator Level (with Faulted Pressure Relief Valve) REVISION: 0 Page 13 of 15 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:

COURSE NUMBER AND TITLE: NRC2008-Sim02 Raise SI Accumulator Level (with Faulted Pressure Relief Valve) REVISION: 0 Page 14 of 15 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

STANDARD: Operator enters N/

A step 4.8 (Nitrogen was not added)

SAT: UNSAT:

COURSE NUMBER AND TITLE: NRC2008-Sim02 Raise SI Accumulator Level (with Faulted Pressure Relief Valve) REVISION: 0 Page 15 of 15 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

STANDARD: Verifies Accum. 21 Narrow Range Level and

Pressure and within TS and Surveill ance 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.

NRC2008-Sim02.doc Page 1 of 1 Task Briefing Given the following:

You are the "extra" RO brought in to perform this task.

Chemistry inadvertently drained #1 accu mulator 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 th rough 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 st ep 4.9 of 02-OHP-4021-008-004 Attachment 3.

All procedure prerequisites, precaut ions and limitations have been met.

Page 1 of 6

NRC2008-Sim03

TITLE Depressurize the RCS to Refill the Pressurizer

(ALT) REVISION 0 PROGRAM Initial Licensed Operator (ILT)

TIME 15 Minutes

SCOPE OF REVISION:

Initial Issue

DATE: Name: John T Conrad AUTHOR Signature:

Name: FACILITY REVIEWER Signature:

TITLE: NRC2008-Sim03 - Depressurize the RCS to Refill the Pressurizer (ALT) REVISION: 0 Page 2 of 6 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 oper ate and monitor the RC S 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

1. Reset to an IC972 (from IC 35 with RC10D @

70% perform E-0, E-1, ES-1.2 through Step 13) with: A SB LOCA in progress and ready to depressurize RCS to refill PRZ in ES-1.2, RCPs Stopped Close PRZ PORV Block Valves NMO151 &

NMO153, PORV NRV-151, Caution Tag NRV 153

& Block Closed for Leakage, Cle arance Tag NRV-151 & NMO151 Insert Global Malfunctions 101NRV151, 101NRV152, 101NRV 153 & 101NMO151 Trg 1 - NMO153 to Open (Z GI101NMO153 == 3), IMF 101NMO153 OOS Tag NRV & NMO 151, Caution Tag NMO 153 Insert ZGI CCVAB79 NRV-151, power OFF.

TITLE: NRC2008-Sim03 - Depressurize the RCS to Refill the Pressurizer (ALT) REVISION: 0 Page 3 of 6 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.

TITLE: NRC2008-Sim03 - Depressurize the RCS to Refill the Pressurizer (ALT) REVISION: 0 Page 4 of 6 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 >10 5 R/Hr Intergated Radiation >10 6 R TITLE: NRC2008-Sim03 - Depressurize the RCS to Refill the Pressurizer (ALT) REVISION: 0 Page 5 of 6 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 t hat 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: UNS AT:

TITLE: NRC2008-Sim03 - Depressurize the RCS to Refill the Pressurizer (ALT) REVISION: 0 Page 6 of 6 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 ot her 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."

NRC2008-Sim03.doc Page 1 of 1 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 1 of 13

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: Name: John T Conrad AUTHOR Signature:

Name: FACILITY REVIEWER Signature:

Facility Supervisor / Manager

COURSE NUMBER AND TITLE: NRC2008-SIM04 Start a Reactor Coolant Pump (ALT)

REVISION: 0 Page 2 of 13 REFERENCES 02-OHP-4023-SUP-007, Rev 1a Re storation 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 wit h RC10D @70% perform E-0, E-1, ES-1.2 through Step 14) with: A SB LOCA in progress and ready to restart an RCP 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%.

COURSE NUMBER AND TITLE: NRC2008-SIM04 Start a Reactor Coolant Pump (ALT)

REVISION: 0 Page 3 of 13 TASK OBJECTIVES/STANDARDS Start RCP #23 as directed per 02-OHP-4023-SUP-010 after restori ng CCW Cooling per 02-OHP-4023-SUP-007 while observing all applicable prec autions 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.

COURSE NUMBER AND TITLE: NRC2008-SIM04 Start a Reactor Coolant Pump (ALT)

REVISION: 0 Page 4 of 13 CUES/STANDARDS ("

CS" Indicates Critical Standard) EXPECTED ACTIONS

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.

COURSE NUMBER AND TITLE: NRC2008-SIM04 Start a Reactor Coolant Pump (ALT)

REVISION: 0 Page 5 of 13 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 te mperatures have NOT exceeded 150ºF.

COURSE NUMBER AND TITLE: NRC2008-SIM04 Start a Reactor Coolant Pump (ALT)

REVISION: 0 Page 6 of 13 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 fo r 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:

COURSE NUMBER AND TITLE: NRC2008-SIM04 Start a Reactor Coolant Pump (ALT)

REVISION: 0 Page 7 of 13 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

STANDARD: Checks Both CCP pumps running

SAT: UNSAT:

STANDARD: Verifies RCP Se al Injection to 6-12 gpm

SAT: UNSAT:

STANDARD: Returns to 02-O HP-4023-SUP-010 Step 2.

SAT: UNSAT:

COURSE NUMBER AND TITLE: NRC2008-SIM04 Start a Reactor Coolant Pump (ALT)

REVISION: 0 Page 8 of 13 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

STANDARD: Verifies RCP #23 CCW flows are Acceptable.

SAT: UNS AT:

COURSE NUMBER AND TITLE: NRC2008-SIM04 Start a Reactor Coolant Pump (ALT)

REVISION: 0 Page 9 of 13 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

STANDARD: Operator verifies RCP Seal Injection to 6-12 gpm

SAT: UNSAT:

STANDARD: Operator verifies Pa nel 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:

COURSE NUMBER AND TITLE: NRC2008-SIM04 Start a Reactor Coolant Pump (ALT)

REVISION: 0 Page 10 of 13 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:

COURSE NUMBER AND TITLE: NRC2008-SIM04 Start a Reactor Coolant Pump (ALT)

REVISION: 0 Page 11 of 13 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:

COURSE NUMBER AND TITLE: NRC2008-SIM04 Start a Reactor Coolant Pump (ALT)

REVISION: 0 Page 12 of 13 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

STANDARD: Operator verifies All SG levels above 27%.

SAT: UNSAT:

COURSE NUMBER AND TITLE: NRC2008-SIM04 Start a Reactor Coolant Pump (ALT)

REVISION: 0 Page 13 of 13 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."

NRC2008-Sim04.doc Page 1 of 1 Task Briefing You are the RO in Unit 2.

Unit 2 is responding to a Small Break LO CA . All RCPs have been stopped and the crew is implementing step 14 of 2-OH P-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-Sim05

TITLE Perform Steam Generator Stop Valve Dump

Valve Surveillance Test REVISION 0 PROGRAM Initial Licensed Operator (ILT)

TIME 10 Minutes

SCOPE OF REVISION:

Initial Issue From Audit07-Sim07& Audit06-Sim02

DATE: Name: John T Conrad AUTHOR Signature:

Name: FACILITY REVIEWER Signature:

Facility Supervisor / Manager

Page 1 of 6

TITLE: NRC2008-Sim05 - Perform St eam Generator Stop Valve Dump Valve Surveillance Test REVISION: 0 Page 2 of 6 REFERENCES 2-OHP-4030-251-018 Rev 2 Steam G enerator Stop Valve Dump Valve Surveillance Test Task Number: ADM1190301 Stroke a valve for Post Maintenance operability 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

1. Initialize simulator to IC 971 (Any Mode 1-3 IC)

2. FREEZE the simulator.

3. Stop Watch Required with Calibration Sticker

TITLE: NRC2008-Sim05 - Perform St eam Generator Stop Valve Dump Valve Surveillance Test REVISION: 0 Page 3 of 6 TASK OBJECTIVES/STANDARDS Perform 02 OHP 4030-251-018, Steam Generator Stop Valve Dump Va lve Surveillance Test on 2-MRV-210.

TASK BRIEFING

You are the Balance of Plant Operator.

Steam Generator Stop Valve Dump Valve Surveillance Test is r equired 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 te st of 2-MRV-210 Dump Valves.

TITLE: NRC2008-Sim05 - Perform Steam Generator Stop Valve Dump Valve Surveillance Test REVISION: 0 Page 4 of 6 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

General CUES:

Provide candidate marked up c opy of 02-OHP-4030-251-018, Steam Generator Stop Valve Du mp Valve Surveillance Test, (Marked to perform section 4.2).

Instructor Note:

Primary Stop Watch Data is already entered.

Secondary stopwatch data is N/A.

N/A N/A 12-25-2008 SW-00 2 TITLE: NRC2008-Sim05 - Perform Steam Generator Stop Valve Dump Valve Surveillance Test REVISION: 0 Page 5 of 6 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 verifi es POS A light is LIT.

SAT: UNSAT:

STANDARD: Verifies neon lamp fo r 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.

STANDARD:

CS Operator places 2-MMO-210 switch to the

NORM position.

SAT: UNSAT: 0 2 TITLE: NRC2008-Sim05 - Perform Steam Generator Stop Valve Dump Valve Surveillance Test REVISION: 0 Page 6 of 6 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: 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 te sting complete on 2-MRV-210.

SAT: UNSAT: EVALUATOR: "This JPM is complete" 0 2 Task Briefing NRC2008-Sim05.doc Page 1 of 1 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 te st of 2-MRV-210 Dump Valves.

Page 1 of 8

NRC2008-Sim06

TITLE Restore RCP Bus 2A Power to AC Bus T21A Emergency Bus(T21A on EDG)

REVISION 0 PROGRAM Initial Licensed Operator (ILT)

TIME 20 Minutes

SCOPE OF REVISION:

Initial Issue

DATE: Name: John T Conrad AUTHOR Signature:

Name: FACILITY REVIEWER Signature:

Facility Supervisor / Manager

COURSE NUMBER AND TITLE: NRC2008-Sim06 - Restore RCP Bus 2A Power to AC Bus T21A Emergency Bus(T21A on EDG)

REVISION: 0 Page 2 of 8

REFERENCES 02-OHP 4023-SUP-002, Rev. 6 Restorati on 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

1. Reset to an IC972 (from IC 35 with RC10D @

70% perform E-0, E-1, ES-1.2 through Step 13) Verify that T21A and T21B are fed fr om 2AB EDG (Open TR201AB transformer breaker following Trip & Then Reclose)

COURSE NUMBER AND TITLE: NRC2008-Sim06 - Restore RCP Bus 2A Power to AC Bus T21A Emergency Bus(T21A on EDG)

REVISION: 0 Page 3 of 8

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 blackou

t. 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 t he RCP bus in accordance with 2-OHP-4023-SUP-002, Restoration of Reserve Power to 4KV Buses.

COURSE NUMBER AND TITLE: NRC2008-Sim06 - Restore RCP Bus 2A Power to AC Bus T21A Emergency Bus(T21A on EDG)

REVISION: 0 Page 4 of 8 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:

COURSE NUMBER AND TITLE: NRC2008-Sim06 - Restore RCP Bus 2A Power to AC Bus T21A Emergency Bus(T21A on EDG)

REVISION: 0 Page 5 of 8 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

COURSE NUMBER AND TITLE: NRC2008-Sim06 - Restore RCP Bus 2A Power to AC Bus T21A Emergency Bus(T21A on EDG)

REVISION: 0 Page 6 of 8 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:

COURSE NUMBER AND TITLE: NRC2008-Sim06 - Restore RCP Bus 2A Power to AC Bus T21A Emergency Bus(T21A on EDG)

REVISION: 0 Page 7 of 8 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.

COURSE NUMBER AND TITLE: NRC2008-Sim06 - Restore RCP Bus 2A Power to AC Bus T21A Emergency Bus(T21A on EDG)

REVISION: 0 Page 8 of 8 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 t hat Bus T21B is still energized by DG2AB and leaves DG2AB running.

SAT: UNSAT:

COURSE NUMBER AND TITLE: NRC2008-Sim06 - Restore RCP Bus 2A Power to AC Bus T21A Emergency Bus(T21A on EDG)

REVISION: 0 Page 9 of 8

EVALUATOR: When transition is made back to Steps 5, "JPM is COMPLETE"

NRC2008-Sim06.doc Page 1 of 1 TASK BRIEFING

You are an extra operator on Unit 2.

The crew is recovering from a station blackou

t. 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 t he RCP bus in accordance with 2-OHP-4023-SUP-002, Restoration of Reserve Power to 4KV Buses.

Page 1 of 7

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: Name: John T Conrad AUTHOR Signature:

Name: FACILITY REVIEWER Signature:

Facility Supervisor / Manager

TITLE: NRC2008-Sim07 - Energize SR Detectors and Audio Count Rate REVISION: 0 Page 2 of 7 REFERENCES 02-OHP-4023-ES-1.2, Rev. 13 Post LO CA 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)

TITLE: NRC2008-Sim07 - Energize SR Detectors and Audio Count Rate REVISION: 0 Page 3 of 7 TASK OBJECTIVES/STANDARDS Manually energize the Source Range Detectors and Audio Count Rate, observing all applicable precautions and limitati ons 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 in jection 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 energi ze the Source Range detectors and verify proper operation per 2-OHP-4023-ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, starting at step 30b.

TITLE: NRC2008-Sim07 Energize SR Detectors and Audio Count Rate REVISION: 0 Page 4 of 7 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 c opy of 02-OHP-4021-013-005 CUE: Provide Operator with copy of 02-OHP-4021-013-005.

SAT: UNSAT:

TITLE: NRC2008-Sim07 Energize SR Detectors and Audio Count Rate REVISION: 0 Page 5 of 7 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:

TITLE: NRC2008-Sim07 Energize SR Detectors and Audio Count Rate REVISION: 0 Page 6 of 7 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

STANDARD: Operator verifies sampling mode switch in

"COUNT/SEC" position

SAT: UNSAT:

STANDARD: Operator verifies "V OLUME" 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:

TITLE: NRC2008-Sim07 Energize SR Detectors and Audio Count Rate REVISION: 0 Page 7 of 7 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

STANDARD: Operator determi nes Containment is N/A SAT: UNSAT:

STANDARD: Reports task completed.

SAT: UNSAT:

Evaluator:

"This JPM is complete."

NRC2008-Sim07.doc Page 1 of 1

Task Briefing Thirty (30) minutes ago a reactor trip and safety in jection 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 energi ze 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 1 of 6

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: Name: John T Conrad AUTHOR Signature:

Name: FACILITY REVIEWER Signature:

Facility Supervisor / Manager

COURSE NUMBER AND TITLE: NRC2008-SIM08 Switching CCW Pumps REVISION: 0 Page 2 of 6 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 COURSE NUMBER AND TITLE: NRC2008-SIM08 Switching CCW Pumps REVISION: 0 Page 3 of 6 TASK OBJECTIVES/STANDARDS Performs switching of the CCW pumps, observing all applicable pr ecautions 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 Operat ion Attachment 2 Step 4.2.

The CCW System is currently Operable.

COURSE NUMBER AND TITLE: NRC2008-SIM08 Switching CCW Pumps REVISION: 0 Page 4 of 6 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 monito ring RCP and Letdown temperature affects of this evolution.

COURSE NUMBER AND TITLE: NRC2008-SIM08 Switching CCW Pumps REVISION: 0 Page 5 of 6 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 a ssociated 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 verifi es 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:

COURSE NUMBER AND TITLE: NRC2008-SIM08 Switching CCW Pumps REVISION: 0 Page 6 of 6 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" NRC2008-Sim08.doc Page 1 of 1 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 Operat ion Attachment 2 Step 4.2.

The CCW System is currently Operable.

Page 1 of 6

NRC2008-INP01

TITLE Local Operation of IR V-310, RHR Hx Outlet Valve REVISION 0 PROGRAM Initial Licensed Operator (ILT)

TIME 15 Minutes

SCOPE OF REVISION:

Initial Issue: Derived from A udit07-Inp02 & AE-O-E259 Revision 2:

DATE: Name: John T Conrad AUTHOR Signature:

Name: FACILITY REVIEWER Signature:

Facility Supervisor / Manager

TITLE: NRC2008-INP01 Local Operation of IRV-310, RHR Hx Outlet Valve REVISION: 0 Page 2 of 6 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 predicti ons, use procedures to correct, control, or mitigate the consequences of thos e 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 TITLE: NRC2008-INP01 Local Operation of IRV-310, RHR Hx Outlet Valve REVISION: 0 Page 3 of 6 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 evacuat ion and implementation of the Emergency Remote Shutdown Procedure. The control room crew has ac tivated 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 Se ction R-12-16 of 02-OHP 4025-R-12. You are to report back to the US once local control has been established.

TITLE: NRC2008-INP01 Local Operation of IRV-310, RHR Hx Outlet Valve REVISION: 0 Page 4 of 6 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.

TITLE: NRC2008-INP01 Local Operation of IRV-310, RHR Hx Outlet Valve REVISION: 0 Page 5 of 6 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 pr essure 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."

TITLE: NRC2008-INP01 Local Operation of IRV-310, RHR Hx Outlet Valve REVISION: 0 Page 6 of 6 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

Air Hose disconnected here.

Air Hose reconnected here.

NRC2008-INP01.doc Page 1 of 1 Task Briefing

A fire has resulted in a control room evacuat ion and implementation of the Emergency Remote Shutdown Procedure. The control room crew has ac tivated 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 Se ction R-12-16 of 02-OHP 4025-R-12. You are to report back to the US once local control has been established.

Retention Requirements: Quality 1/080306/rs/ss Page 1 of 10

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: Name: John T Conrad AUTHOR Signature:

Name: FACILITY REVIEWER Signature:

Facility Supervisor / Manager

COURSE NUMBER AND TITLE:

NRC2008-INP02 Modify, Relatch and Locally start TDAFP REVISION: 6 Retention Requirements: Quality 2/080306/rs/ss Page 2 of 10 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 COURSE NUMBER AND TITLE:

NRC2008-INP02 Modify, Relatch and Locally start TDAFP REVISION: 6 Retention Requirements: Quality 3/080306/rs/ss Page 3 of 10 TASK OBJECTIVES/STANDARDS Terminal Objective:

When directed by the Unit Supervisor Reset and St artup 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 asse mbled 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.

COURSE NUMBER AND TITLE:

NRC2008-INP02 Modify, Relatch and Locally start TDAFP REVISION: 6 Page 4 of 10 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:

COURSE NUMBER AND TITLE:

NRC2008-INP02 Modify, Relatch and Locally start TDAFP REVISION: 6 Page 5 of 10 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:

COURSE NUMBER AND TITLE:

NRC2008-INP02 Modify, Relatch and Locally start TDAFP REVISION: 6 Page 6 of 10 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:

COURSE NUMBER AND TITLE:

NRC2008-INP02 Modify, Relatch and Locally start TDAFP REVISION: 6 Page 7 of 10 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:

COURSE NUMBER AND TITLE:

NRC2008-INP02 Modify, Relatch and Locally start TDAFP REVISION: 6 Page 8 of 10 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:

COURSE NUMBER AND TITLE:

NRC2008-INP02 Modify, Relatch and Locally start TDAFP REVISION: 6 Page 9 of 10 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 Che cks 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."

COURSE NUMBER AND TITLE:

NRC2008-INP02 Modify, Relatch and Locally start TDAFP REVISION: 6 Page 10 of 10 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 COURSE NUMBER AND TITLE:

NRC2008-INP02 Modify, Relatch and Locally start TDAFP REVISION: 6 Page 1 of 1 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 asse mbled 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 3

NRC2008-INP03

TITLE Perform an Authorized Gaseous Release REVISION 0 PROGRAM Initial Licensed Operator (ILT)

TIME 25 Minutes

SCOPE OF REVISION:

Initial Issue

DATE: Name: John T Conrad AUTHOR Signature:

Name: FACILITY REVIEWER Signature:

Facility Supervisor / Manager

COURSE NUMBER AND TITLE:

NRC2008-INP03 - Perform an Authorized Gaseous Release REVISION: 0 Page 2 of 3 REFERENCES 12-OHP-4021.023.002, Release of Radioacti ve 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

COURSE NUMBER AND TITLE:

NRC2008-INP03 - Perform an Authorized Gaseous Release REVISION: 0 Page 3 of 3 Task Objectives/Standards Release the contents of #1 Gas Decay Tank to the vent header in accordance with the release procedure.

Task Briefing

1. 1 Gas Decay Tank has been isolated, sampled, and approved for release. 12-OHP 4021.023.002, Release Of Radioactive Waste From Gas Decay T anks, 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 releas e 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

û Temp Diff: -

1 Vent Stack Flow: 9.25E4 scfm; Initial Tank Pressure: 97 psig

COURSE NUMBER AND TITLE:

NRC2008-INP03 - Perform an Authorized Gaseous Release REVISION: 0 Page 1 of 10 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:

COURSE NUMBER AND TITLE:

NRC2008-INP03 - Perform an Authorized Gaseous Release REVISION: 0 Page 2 of 10 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:

COURSE NUMBER AND TITLE:

NRC2008-INP03 - Perform an Authorized Gaseous Release REVISION: 0 Page 3 of 10 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:

COURSE NUMBER AND TITLE:

NRC2008-INP03 - Perform an Authorized Gaseous Release REVISION: 0 Page 4 of 10 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:

COURSE NUMBER AND TITLE:

NRC2008-INP03 - Perform an Authorized Gaseous Release REVISION: 0 Page 5 of 10 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:

COURSE NUMBER AND TITLE:

NRC2008-INP03 - Perform an Authorized Gaseous Release REVISION: 0 Page 6 of 10 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:

COURSE NUMBER AND TITLE:

NRC2008-INP03 - Perform an Authorized Gaseous Release REVISION: 0 Page 7 of 10 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:

COURSE NUMBER AND TITLE:

NRC2008-INP03 - Perform an Authorized Gaseous Release REVISION: 0 Page 8 of 10 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:

COURSE NUMBER AND TITLE:

NRC2008-INP03 - Perform an Authorized Gaseous Release REVISION: 0 Page 9 of 10 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:

COURSE NUMBER AND TITLE:

NRC2008-INP03 - Perform an Authorized Gaseous Release REVISION: 0 Page 10 of 10 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."

NRC2008-INP03.doc Page 1 of 1 Task Briefing

1. 1 Gas Decay Tank has been isolated, sampled, and approved for release. 12-OHP 4021.023.002, Release Of Radioactive Waste From Gas Decay T anks, 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 releas e 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

û Temp Diff (T): -1ûF Vent Stack Flow: 9.25E4 scfm; Initial Tank Pressure: 97 psig