Text

Final Operating Exam (Sections a, B, and C) (Folder 3)
	ML15131A255
Person / Time
Site:	Peach Bottom
Issue date:	05/07/2015
From:	Reiner R; Exelon Generation Co
To:	Peter Presby; Operations Branch I
Shared Package
ML14254A311	List: IR 05000277/2015301; ML14302A020; ML15077A098; ML15103A132; ML15131A255; ML15131A256; ML15169A646; ML15169A648; ML15169A649; ML15169A651; ML15169A652; ML15169A654; ML15169A656; ML15174A053;
References
	TAC U01911
	Download: ML15131A255 (232)
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EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET II X 1111 Peach Bottom II Limerick II 1111 Common TYPE:

~ JPM D QUALIFICATION MANUAL D OJT MODULE PROGRAM: LICENSED OPERATOR TRAINING CODE#: PLOR-241C

.*.*.*. *~\

COURSE:. LICENSED OPERATOR REQUALIFICATION REV#:.*.

.. ..: . . ' 001 AUTHOR: F. J. Bruns TYPIST:

- ...; . jav TITLE: MANUALLY CALCULATE DRYWELL BULK AVERAGE TEMPERATURE -

ALTERNATE PATH (Failed Temperature Points)

APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: I I NAME: ISSUE DATE:

Last First M.I.

EMPLOYEE ID NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMS CODE:

LMS ENTRY:

Signature/Date PLOR241 C Rev 1 Page 1 of 4

EXELON NUCLEAR

PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2880130201 I PLOR-241C KIA: G2.1.45 URO: 4.3 SRO: 4.3 TASK DESCRIPTION: MANUALLY CALCULATE DRYWELL BULK AVERAGE TEMPERATURE -ALTERNATE PATH (Failed Temperature Points)

A. NOTES TO EVALUATOR:

1. An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JP Ms, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR241C Rev 1 Page 2 of 4

B. TOOLS AND EQUIPMENT

1. RT-0-40C-530-2, "Drywell Temperature Monitoring"

2. RT-0-40C-530-2, Data Sheet 1 with temperature values filled in with points 137 and 139 indicated as out of service and point 136 reading 132°F (AT2)

C. REFERENCES

1. RT-0-40C-530-2, Rev. 6, "Drywell Temperature Monitoring" D. TASK STANDARD

1. Satisfactory task completion is indicated when the operator has determined that Drywell Temperature requires entry into ON-120, High Drywell Temperature.

2. Estimated time to complete: 20 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to Monitor Drywell Temperatures using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Unit 2 is experiencing a small steam leak into primary containment.

2. Tl-80146, the drywell bulk average temperature indication, has failed.

3. Another operator has completed taking the temperatures required for Data Sheet 1 of RT-0-40C-530-2, "Drywell Temperature Monitoring".

G. INITIATING CUE The Control Room Supervisor directs you to perform RT-0-40C-530-2, "Drywell Temperature Monitoring", beginning with step 6.2.1 up through and including step 6.2.3, and report any required actions by documenting your results on the cue sheet in the space provided.

PLOR241 C Rev 1 Page 3 of 4

H. PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD

1 Review Data Sheet 1 and recognize that p Recognize that the calculation of Bulk all of the temperature points in Zone Average temperature is INVALID. Place Number 4 are out of service (Step 6.2.1 ). an N/A in step 6.2.1.

2 Record the instrument used on the blank p Record "Tl-2501, Point 136" in the provided in step 6.2.2.1. "Instrument Used" blank provided in step 6.2.2.1, then initial the step in the SAT column.

3 Record the value of Tl-2501, Point 136 in p Record "132" in the blanks provided the provided blanks in steps 6.2.2.1 and before the first "°F" in steps 6.2.2.1 and 6.2.2.2. 6.2.2.2.

4 Calculate approximate Drywell Bulk p Calculate 132°F + 10°F = 142°F. Record Average Temperature as indicated in step "142" in the blank provided in step 6.2.2.2. 6.2.2.2, then initial the step in the SAT column.

5 Complete verification of Drywell Bulk p Initial the UNSAT Black Box beside Step Average Temperature less than 140°F. 6.2.3.

6 Report ON-120 "High Drywell p Report to the CRS that ON-120 should be Temperature" entry condition. entered due to Approximate Drywell Bulk Average Temperature greater than 140°F.

7 As an evaluator, ensure that you have p Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When the candidate informs the Control Room Supervisor of the ON-120, "High Drywell Temperature", entry condition, the evaluator will then terminate the exercise.

PLOR241 C Rev 1 Page 4 of 4

TASK CONDITIONS/PREREQUISITES

1. Unit 2 is experiencing a small steam leak into primary containment.

2. Tl-80146, the drywell bulk average temperature indication, has failed.

3. Another operator has completed taking the temperatures required for Data Sheet 1 of RT 40C-530-2, "Drywell Temperature Monitoring".

INITIATING CUE The Control Room Supervisor directs you to perform RT-0-40C-530-2, "Drywell Temperature Monitoring",

beginning with step 6.2.1 up through and including step 6.2.3, and report any required actions by documenting your results on the cue sheet in the space provided.

RESULTS:

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

~ JPM D QUALIFICATION MANUAL D OJT MODULE PROGRAM: LICENSED OPERATOR REQUALIFICATION CODE#: PLOR-219C COURSE: LICENSED OPERATOR REQUALIFICATION REV#:: 004 AUTHOR: M. J. Kelly TYPIST: rja TITLE: Perform an APRM Scram Margin Check APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: I I NAME: ISSUE DATE:

Last First M.I.

EMPLOYEE ID NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMS CODE:

LMS ENTRY:

Signature/Date PLOR219C Rev 4 Page 1 of 6

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2150300101 I PLOR-219C KIA: G2.1.31 RO: 4.6 SRO: 4.3 TASK DESCRIPTION: Perform APRM Scram Margin Check A. NOTES TO EVALUATOR:

1. An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. This JPM requires performance using either the Simulator NUMAC drawers or the actual Control Room APRM NUMAC drawers. Due to the electronic displays, this JPM should not be "simulated". Normally, this "Control Room" JPM will be performed in the simulator however this JPM may be performed in the actual Control Room on a real APRM NU MAC drawer with no impact on plant operation under the supervision of the shift.

b. When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR219C Rev 4 Page 2 of 6

6. This JPM should be performed in the Simulator but may be performed in the actual Control Room with no impact on plant operation. Obtain Control Room Supervisor and Unit RO permission prior to performing this JPM and prior to entering the controls area.

7. The evaluator may also select a different APRM if desired (e.g., if APRM #1 NUMAC drawer is out of service).

B. TOOLS AND EQUIPMENT A copy of ST-0-001-200-2, Rev. 29, "Turbine Stop Valve Closure and EOC-RPT Functional",

with procedure steps marked up and completed up to and including step 6.1.1. The Examinee will continue the surveillance at step 6.1.2.

C. REFERENCES

1. SO 60A.7.C-2, Rev. 11 "APRM Scram Margin Check"

2. ST-0-001-200-2, Rev. 29, "Turbine Stop Valve Closure and EOC-RPT Functional" D. TASK STANDARD

1. Satisfactory task completion is indicated when the student determines the correct scram margin as recorded on SO 60A.7.C-2 Data Sheet 1 and has determined that there is sufficient scram margin to continue with the ST-0-001-200-2.

2. Estimated time to complete: 12 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to determine if there is adequate ARPM scram margin to perform Turbine Stop Valve Closure testing using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Unit 2 is at full power (approximately 100%).

2. ST-0-001-200-2, "Turbine Stop Valve Closure and EOC-RPT Functional", is in progress.

3. All APRM Channels are operable.

G. INITIATING CUE The Control Room Supervisor directs you to perform steps 6.1.2 and 6.1.3 of ST-0-001-200-2, "Turbine Stop Valve Closure and EOC-RPT Functional". Inform the Control Room Supervisor when the steps are completed and whether the surveillance can be continued.

PLOR219C Rev 4 Page 3 of 6

H. PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD 1 Obtain a copy of ST-0-001-200-2, p A marked up copy of ST-0-001-200-2, "Turbine Stop Valve Closure and EOG- "Turbine Stop Valve Closure and EOG-RPT Functional". RPT Functional" with steps complete up to and including step 6.1.1 is obtained.

(Cue: Provide the Examinee a marked up copy of ST-0-001-200-2, "Turbine Stop Valve Closure and EOC-RPT Functional" with steps complete up to and including step 6.1.1.)

2 Obtain a copy of procedure p A copy of procedure SO 60A.7.C-2, SO 60A.7.C-2, "APRM Scram Margin "APRM Scram Margin Check" is Check". obtained.

(Cue: The Lead Evaluator may approve handing the Examinee a blank copy of SO 60A.7.C-2, "APRM Scram Margin Check" for review prior to performing the JPM.)

3 Determine that the APRM Downscale p Observe APRM Downscale lights are is clear. NOT lit on Panel 20C05 and /or annunciator 211 C-2 "APRM DOWNSCALE" is clear.

4 Determine that Step 4.1 of p Select Step 4.1 of SO 60A.7.C-2 to SO 60A.7.C-2 is applicable for Mode 1 perform.

operation.

- - - NOTE****

Step 4.1 of SO 60A.7.C-2 directs the operator to determine Scram setpoints for all operable APRMs.

For this JPM, APRM #1 is the selected. A different APRM may be selected by the evaluator if desired (e.g., APRM #1 NUMAC is out of service, or If this JPM is being performed in the Control Room).

5 At selected APRM NUMAC display p At APRM #1 NUMAC display, depress (APRM #1 ), depress the "ETC" softkey the "ETC" softkey to obtain the "SHOW to obtain the "SHOW PARAMETERS" PARAMETERS" softkey.

softkey.

PLOR219C Rev 4 Page 4 of 6

STEP NO STEP ACT STANDARD 6 Depress "SHOW PARAMETERS" p Depress "SHOW PARAMETERS" softkey. softkey.

7 Under the "APRM RUN MODE p Record the value of "STP UPSCALE SETPOINTS" section, record the value TRIP (FLOW BIASED)" on Data Sheet of "STP UPSCALE TRIP (FLOW 1 under "APRM SCRAM SETPOINT".

BIASED)" on Data Sheet 1 under (NOTE: With simulator reset to IC14, "APRM SCRAM SETPOINT". this value should be 116.0%)

8 Depress "EXIT" softkey. p Depress "EXIT" softkey.

9 Record "STP (%)"value on Data Sheet p Record "STP (%)"value on Data Sheet 1 under "APRM CURRENT". 1 under "APRM CURRENT". (NOTE:

With simulator reset to IC14, this value should be 99.9%)

10 Determine SCRAM margin by p Correctly calculates APRM #1 Scram performing the following calculation Margin on Data Sheet 1:

AND recording the value on Data Sheet 1 under "SCRAM MARGIN": SCRAM MARGIN = APRM SCRAM SETPOINT - APRM CURRENT SCRAM MARGIN = APRM SCRAM SETPOINT - APRM CURRENT= = SP-C SP-C (NOTE: With simulator reset to IC14, the Scram Margin value should be 16.1%)

- - Note***

At this time the Evaluator should inform the Examinee that the remaining 3 APRM Scram Margin checks have been completed with the same results obtained.

- - Note***

Step 4.2 of so GOA.7.C-2 is not applicable for the reactor mode condition.

PLOR219C Rev 4 Page 5 of 6

11 Records the date, time, and Scram p The date, time, and Scram Margin Margin values in step 6.1.2 of ST values are filled in for step 6.1.2 of ST-001-200-2, "Turbine Stop Valve 0-001-200-2, "Turbine Stop Valve Closure and EOC-RPT Functional". Closure and EOC-RPT Functional". The step is initialed as satisfactory.

12 Verifies that the Scram Margin for each p ST-0-001-200-2, "Turbine Stop Valve APRM channel is acceptable to Closure and EOC-RPT Functional" step continue ST-0-001-200-2, "Turbine 6.1.3 is referenced. 15% Scram Margin Stop Valve Closure and EOC-RPT is required when reactor power is above Functional". 75%. Step 6.1.3 of ST-0-001-200-2, "Turbine Stop Valve Closure and EOC-RPT Functional" is initialed as satisfactory.

13 Inform Control Room Supervisor that p Task completion reported.

the Scram Margin is sufficient to continue the surveillance test.

(Cue: Control Room Supervisor acknowledges report.)

14 As an evaluator, ensure that you have p Positive Control Established.

positive control of all exam material provided to the examinees (Task Conditions/Prerequisites AND procedures.

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When the scram margin for APRM #1 has been determined in accordance with SO 60A.7.C-2 "APRM Scram Margin Check", and the determination of whether the ST-0-001-200-2, "Turbine Stop Valve Closure and EOC-RPT Functional" can be continued, the Evaluator may terminate the exercise.

PLOR219C Rev 4 Page 6 of 6

TASK CONDITIONS/PREREQUISITES

1. Unit 2 is at full power (approximately 100°/o).

2. ST-0-001-200-2, "Turbine Stop Valve Closure and EOC-RPT Functional", is in progress.

3. All APRM Channels are operable.

INITIATING CUE The Control Room Supervisor directs you to perform steps 6.1.2 and 6.1.3 of ST-0-001-200-2, "Turbine Stop Valve Closure and EOC-RPT Functional".

Inform the Control Room Supervisor when the steps are completed and whether the surveillance can be continued.

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

~ JPM D QUALIFICATION MANUAL D OJT MODULE PROGRAM: LICENSED OPERATOR TRAINING CODE#: PLOR-220C COURSE: LICENSED OPERATOR REQUALIFICATION REV#:: 001 AUTHOR: G. Zellmer TYPIST: Rja TITLE: Print Reading APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: I I NAME: ISSUE DATE:

Last First M.I.

EMPLOYEE l.D. NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMS CODE:

LMS ENTRY:

Signature/Date PLOR220C Rev 1 Page 1 of 7

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: PLOR-220 KIA: 2.2.41 URO: 3.5 SRO: 3.9 TASK DESCRIPTION: Ability to Obtain and Interpret Station Electrical and Mechanical Drawings A. NOTES TO EVALUATOR:

1. An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR220C Rev 1 Page 2 of 7

B. TOOLS AND EQUIPMENT

1. M-300 sheet 1, Rev. 48, "P&I Diagram Legend" print

2. M-300 sheet 2, Rev. 46, "P&I Diagram Legend" print

3. M-300 sheet 3, Rev. 01, "P&I Diagram Legend" print

4. M-333 Sheet 1, Rev. 57, "P&I Diagram Instrument Nitrogen" print

5. M-333 Sheet 2, Rev. 58, "P&I Diagram Instrument Nitrogen" print C. REFERENCES

1. M-300 sheet 1, Rev. 48, "P&I Diagram Legend" print

2. M-300 sheet 2, Rev. 46, "P&I Diagram Legend" print

3. M-300 sheet 3, Rev. 01, "P&I Diagram Legend" print

4. M-333 Sheet 1, Rev. 57, "P&I Diagram Instrument Nitrogen" print

5. M-333 Sheet 2, Rev. 58, "P&I Diagram Instrument Nitrogen" print

6. E-1670 sheet 3 Rev 5 "Electrical Schematic Diagram Instrument Nitrogen Compressor 3AK37" print

7. E-1670 sheet 4 Rev 4 "Electrical Schematic Diagram Instrument Nitrogen Compressor 3BK37" print D. TASK STANDARD

1. Satisfactory task completion is indicated when it has been determined that:

a. Solenoid Valve SV-5232A should be energized under the present conditions.

b. Solenoid Valve SV-5232A is currently closed.

c. Starting the 3BK037 Instrument Nitrogen Compressor will energize the SV-52328 Solenoid Valve after a time delay of 0.5 seconds.

2. Estimated time to complete: 15 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to determine the status of a degraded component in the Instrument Nitrogen System using the appropriate P&IDs. I will describe initial plant conditions and provide you access to the materials required to complete this task.

PLOR220C Rev 1 Page 3 of 7

F. TASK CONDITIONS/PREREQUISITES

1) Unit 2 and Unit 3 are at 100% power with the station in a normal line-up.

2) An Equipment Operator reports to the control room that Solenoid Valve SV-5232A is making a humming sound. The Solenoid Valve is located on the discharge of the Unit 3 Instrument Nitrogen Compressor 3AK037 (Between the 3A Instrument Nitrogen Compressor and the 3A Instrument Nitrogen Compressor Aftercooler). The 3AK037 compressor is currently running as the 'LEAD' compressor and the pressure in the Receivers (3AT109 and 3BT109) is rising.

3) No other equipment is out of service or in a degraded condition.

4) A copy of the latest approved versions of M-300 sheets 1, 2, & 3 as well as M-333 sheets 1

& 2 are being provided to you.

G. INITIATING CUE The Control Room Supervisor directs you to determine the following:

A) Should the Solenoid Valve SV-5232A be energized with the 3AK037 Compressor running?

B) What is the status of SV-5232A right now (is the valve open or closed)?

C) If the 3BK037 Instrument Nitrogen Compressor is (manually) started momentarily, will the equipment operator be able to compare the 'humming noise' of the SV-5232A Solenoid Valve with the operation of the SV-52328 Solenoid Valve?

PLOR220C Rev 1 Page 4 of 7

H. PERFORMANCE CHECKLIST STEP STEP ACT STANDARD NO NIA Note to evaluator: The sequence of steps NIA Provide trainee with a written list of 'Task not critical. Nor is it necessary to validate Conditions and Prerequisites' as well as the performance of each step individually. the 'Initiating Cue' When the trainee makes the correct Provide trainee with legible copies the determinations (either verbally or written), latest approved versions of:

that is sufficient to determine that the M-300 sheet 1 below steps have been completed M-300 sheet 2 satisfactorily. M-300 sheet 3 M-333 sheet 1 M-333 sheet 2 1 Locate the "SV-5232A" on M-333 sheet 2. p "SV-5232A" Solenoid Valve is located at coordinates 8-6 on M-333 Sheet 2.

2 Locate 'NOTE 4' on the 'Notes' section of p NOTE 4 is located at coordinates F-1 on M-333 sheet 1. M-333 Sheet 1.

3 Determine that the "SV-5232A" Solenoid p Solenoid Valve SV-5232A opens when Valve unloads the 3AK037 Compressor the coil is de-energized and allows the for starting (while Solenoid Valve is de- discharge of the 3AK037 Compressor to energized). flow directly to the Compressor Inlet (unloading the compressor).

4 Determine that SV-5232A Solenoid Valve p The electrical connection to the solenoid is designed to be energized (and closed) valve is associated with the compressor when the compressor is running. Hand Switch and the Auto Start features of the Compressor (solenoid is labeled N.E.).

5 Determine that the SV-5232A Solenoid p Compressor will not be able to develop Valve must be closed in order for the high discharge pressure if a direct flow compressor to load and function properly. path exists between the Compressor discharge and the Compressor suction.

6 Determine that SV-5232A has a time p The logic symbol for 'function time delay' delay that prevents the Solenoid Valve is identified (symbol is listed on M-300 from energizing for 0.5 seconds following sheet 1).

a start to the 3AK037 Compressor 7 Determine that SV-52328 Solenoid Valve p Logic lines and symbols used for the SV-is designed to work in the same manner 5232A Solenoid Valve are identical to the as SV-5232A. logic lines and symbols used for the SV-52328 Solenoid Valve.

PLOR220C Rev 1 Page 5 of 7

STEP STEP ACT STANDARD NO

8 Control Room Supervisor informed of the p Inform the Control Room Supervisor that status and determinations made (this may be done verbally or written -

concerning the Unit 3 Instrument Nitrogen response does not have to match the System. below listed standards word for word):

Solenoid Valve SV-5232A should (Cue: Acknowledge report.) be energized with the 3AK037 Compressor running

Solenoid Valve SV-5232A is currently closed (Valve is energized to close)

Starting the 3BK037 Compressor will allow a comparison of SV-5232A and SV-52328 provided the 3BK037 Compressor is run for longer than 0.5 seconds.

9 As an evaluator ensure that you have p Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites AND p roced u res/prints).

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When the trainee has provided his determinations to the questions given in the 'Initiating Cue',

then the evaluator may terminate this JPM session.

PLOR220C Rev 1 Page 6 of 7

TASK CONDITIONS/PREREQUISITES

Unit 2 and Unit 3 are at 100% power with the station in a normal line-up.

An Equipment Operator reports to the control room that Solenoid Valve SV-5232A is making a humming sound. The Solenoid Valve is located on the discharge of the Unit 3 Instrument Nitrogen Compressor 3AK037 (Between the 3A Instrument Nitrogen Compressor and the 3A Instrument Nitrogen Compressor Aftercooler). The 3AK037 compressor is currently running as the 'LEAD' compressor and the pressure in the Receivers (3AT109 and 3BT109) is rising.

No other equipment is out of service or in a degraded condition.

A copy of the latest approved versions of M-300 sheets 1, 2, & 3 as well as M-333 sheets 1 & 2 are being provided to you.

INITIATING CUE The Control Room Supervisor directs you to determine the following:

Should the Solenoid Valve SV-5232A be energized with the 3AK037 Compressor running?

What is the status of SV-5232A right now (is the valve open or closed)?

If the 3BK037 Instrument Nitrogen Compressor is (manually) started momentarily, will the equipment operator be able to compare the 'humming noise' of the SV-5232A Solenoid Valve with the operation of the SV-52328 Solenoid Valve?

PLOR220C Rev 1 Page 7 of 7

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE: [3J JPM D QUALIFICATION MANUAL D OJT MODULE PROGRAM: LICENSED OPERATOR TRAINING CODE#: PLOR-218C COURSE: LICENSED OPERATOR REQUALIFICATION REV#: 006 AUTHOR: M. J. Kelly TYPIST: mda TITLE: EVALUATE A P1 EDIT FROM 3D MONICORE AND TAKE CORRECTIVE ACTION FOR A THERMAL LIMIT VIOLATION APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE:

NAME: ISSUE DATE:

Last First M.I.

EMPLOYEE ID NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMS CODE:

LMS ENTRY:

Signature/Date PLOR218C Rev 7 Page 1 of 5

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2830150401 / PLOR-218C KIA: 2.1.7 SRO: 4.7 TASK DESCRIPTION: Resolution of Thermal Limit Violation A. NOTES TO EVALUATOR:

1. An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR218C Rev 7 Page 2 of 5

B. TOOLS AND EQUIPMENT

1. JPM Attachment 2, Prepared Official 3D P1 Edit on green colored paper C. REFERENCES

1. GP-13 Rev. 23, "Resolution of Thermal Limit Violations"

2. GP-5-3 Rev. 001, "Power Operations"

3. Technical Specification 3.2.2, "Minimum Critical Power Ratio (MCPR)"

D. TASK STANDARD

1. Satisfactory task completion is indicated when the examinee has determined that MFLCPR is above 1.000, a reactor power reduction using GP-5, "Power Operations" and entry into Technical Specification 3.2.2, "Minimum Critical Power Ratio (MCPR)"

are required.

2. Estimated time to complete: 10 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, review the initial 3D Monitor Case (P1) edit run following a recent Unit 3 power ascension. Identify any unsatisfactory data points and document any actions that are required. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Unit 3 reactor power is currently stable at 100%.

2. Reactor power was recently raised from 90% to 100% following a rod pattern adjustment in accordance with GP-5, "Power Operations."

3. A valid OFFICIAL 3D Monitor Case (P1) edit has just been run to assess the reactor power ascension.

4. The Plant Monitoring System (PMS) and 3D MONICORE were operable at the time the OFFICIAL 3D Monitor Case (P1) edit was run. The OFFICIAL 3D Monitor Case [P1] has no unexplained changes to its input parameters.

G. INITIATING CUE As the CRS, review the official Unit 3 3D Monitor Case (P1) edit provided.

On the cue sheet, list all unsatisfactory data points and document all actions/notifications that are required by applicable procedures or Technical Specifications I Technical Requirements Manual, and record what document I step number requires the action/notification.

PLOR218C Rev 7 Page 3 of 5

H. PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD

- - NOTE***

Provide examinee with the official Unit 3 30 Monitor Case (P1) Edit (Attachment 2 of this JPM).

Ensure it is printed on green paper.

1 Review the official 3D P1 edit. P Reviews 3D P1 edit to ensure Core Thermal Limits are within specified limits. Focuses on MFLCPR, MFLPD, MAPRAT and FLLP values toward the top of the page.

2 Determine MFLCPR is above 1.000 P States and I or records on the cue sheet that a in one location (19-20). MFLCPR value of 1.001 is listed at core location 19-20.

(Cue: As the Shift Manager, request the examinee to determine what actions, if any, need to be performed to resolve the thermal limit violation.)

3 Obtain and enter GP-13, "Resolution P Obtains and enters GP-13, "Resolution of of Thermal Limit Violations." Thermal Limit Violations."

4 Notify Shift Management and P States and I or records on the cue sheet that Reactor Engineers that MFLCPR is Shift Management and Reactor Engineering above 1.000. (GP-13, step 3.1) require notification of core thermal limit violation as required by GP-13, step 3.1.

(Cue: Acknowledge notifications.)

5 Determine that Reactor power must P States and I or records on the cue sheet that a be reduced with the assistance of GP-5 power reduction is required to restore Reactor Engineering in accordance MFLCPR to below 1.000 as required by GP-13, with GP-5, "Power Operations" to step 3.2.

restore MFLCPR to below 1.000.

(GP-13, step 3.2) 6 Examine the OFFICIAL 3D Monitor P As stated in the cue, the OFFICIAL 3D Monitor Case (P1) for unexplained changes Case [P1] has no unexplained changes to its to its input parameters. input parameters. This action is required by GP-13, step 3.5.

(GP-13, step 3.5)

- - NOTE***

For the following step the other unit, Unit 2, Tech Spec LCO applicability is ~ 23% RTP following EPU.

PLOR218C Rev 7 Page 4 of 5

STEP NO STEP ACT STANDARD

7 Determine that TS LCO 3.2.2 p Identifies TS LCO 3.2.2 is not met and MFLCPR "Minimum Critical Power Ratio must be restored to below 1.000 within (MCPR)" is not met and state the 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or thermal power must be reduced to associated action requirements a below 25% RTP within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

and b.

MFLCPR _::: 1.000 means that MCPR is restored to within limits of the Core Operating Limits Report (COLR) 8 Determine that a Condition Report p States and I or records on the cue sheet that a should be written to address the Condition Report should be written to address thermal limit violation. the thermal limit violation.

(GP-13, step 3.11) 9 As the evaluator, ensure that you p Positive control established.

have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites AND procedures).

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE:

When the examinee has reviewed the 3D Monitor Case (P1) edit and determined actions associated with the thermal limit violation, the evaluator may terminate the exercise.

PLOR218C Rev 7 Page 5 of 5

TASK CONDITIONS I PREREQUISITES

1. Reactor power was recently raised from 90% to 100% following a rod pattern adjustment in accordance with GP-5, "Power Operations."

2. Unit 3 reactor power is currently stable at 100%.

3. A valid OFFICIAL 30 Monitor Case (P1) edit has just been run to assess the reactor power ascension.

4. The Plant Monitoring System (PMS) and 30 MONICORE were operable at the time the OFFICIAL 30 Monitor Case (P1) edit was run. The OFFICIAL 30 Monitor Case [P1] has no unexplained changes to its input parameters.

INITIATING CUE As the CRS, review the official 30 Monitor Case (P1) edit provided.

On the cue sheet, list all Unit 3 unsatisfactory data points and document all actions/notifications that are required by applicable procedures or Technical Specifications I Technical Requirements Manual, and record what document I step number requires the action/notification Unsatisfactory data points (if any)

Required actions (if any)

Official 30 P1 Edit JPM Attachment 2

PB-3 CY-18 3DM/P11 SEQUENCE NO 4 CORE PARAMETERS 3DM/P11 (Current time/date minus 10 minutes) CALCULATED POWER MWT 3514 PERIODIC LOG (Current time/date) PRINTED POWER MWE 1170 AUTOMATIC CASE ID FMLS1020404155957 FLOW MLB/HR 91.380 CALC RE SULTS RESTART FMLS 1020404135957 FPAPDR 0.775 LPRM SHAPE - FULL CORE SUBC BTU/LB 29.02 KEFF 1.0000 PR PS la 1033.8 XE WORTH% -2.47 LOAD LINE

SUMMARY

CORE MWD/ST 27938.9 XE/RATED 1.12 CORE POWER 100.0%

CYCLE MWD/ST 12409.2 AVE VF 0.433 CORE FLOW 90.5%

MCPR 1.348 FLLLP 0.947 LOAD LINE 113.2%

CORRECTION FACTOR MFLCPR=1.000 MFLPD=1.000 MAPRAT=1.000 ZBB = 2.96 ft OPTION: ARTS 2 LOOPS ON MANUAL FLOW MCPRLIM = 1.350 FCBB = N/A MOST LIMITING LOCATIONS (NON-SYMMETRIC)

MFLCPR LOG MFLPD LOG MAPRAT LOG PCRAT LOG 1.001 19-20 0.729 25 5 0.978 27 5 0.695 25-52-5 0.978 29-52 0.724 53 5 0.931 51-28-5 0.695 51-26-6 0.888 25-52 0.720 25 5 0.925 17 5 0.691 19-50-5 0.881 27-50 0.711 51-26-6 0.924 19-52-5 0.689 49 5 0.881 35-26 0.711 19-50-5 0.922 51-20-5 0.683 25 5 0.879 25-44 0.707 49 5 0.920 49-18-5 0.683 17-52-5 0.879 49-28 0.694 49 5 0.904 43 5 0.679 35 5 0.877 43-30 0.694 35 5 0.903 41 5 0.678 51-18-5 0.875 51-32 0.694 17-52-5 0.894 49 5 0.678 41-20-6 0.874 43-26 0.692 41-20-6 0.888 23 5 0.677 53 5 SEQ. A-2 C=MFLCPR D=MFLPD M=MAPRAT P-PCRAT *=MULTIPLE CORE AVE AXIAL NOTCH REL PW LOG 0.147 25 00 0.350 24 59 02 0.679 23 L 04 0.852 22 55 D 06 0.963 21 51 08 1.067 20 L 10 1.129 19 47 14 36 14 12 1.134 18 43 14 1.093 17 L 16 1.120 16 39 14 00 14 18 1.114 15 35 20 1.097 14 L 22 1.130 13 31 36 00 00 36 24 1.151 12 27 26 1.156 11 L 28 1.184 10 23 14 00 14 30 1.225 09 19 c 32 1.243 08 L 34 1.235 07 15 14 36 14 36 1.256 06 11 38 1.250 05 L 40 1.188 04 07 42 1.086 03 03 L L L L L L L 44 0.811 02 02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 46 0.340 01 CORE AVERAGE RADIAL POWER DISTRIBUTION RING# 1 2 3 4 5 6 7 8 REL PW 1.020 1.229 1.092 1.261 1.097 1.257 1.070 0.523 JPM Attachment 2

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET

'TYPE:

~ JPM D QUALIFICATION MANUAL D OJT MODULE PROGRAM: LICENSED OPERATOR TRAINING CODE#: PLOR-279C COURSE: LICENSED OPERATOR REQUALIFICATION REV#: 002 AUTHOR: R. J. Artus TYPIST: rja TITLE: Evaluate Overtime Work Request APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE:

NAME: ISSUE DATE:

Last First M.I.

EMPLOYEE ID#: COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMS CODE:

LMS ENTRY:

Signature/Date PLOR279C Rev 2002 Page 1 of 6

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2991120301 - PLOR-279C KIA: G2.1.5 SRO: 3.9 TASK DESCRIPTION: Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

A. NOTES TO EVALUATOR:

1. An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR279C Rev 2002 Page 2 of 6

B. TOOLS AND EQUIPMENT

1. LS-AA-119 "Fatigue Management and Work Hour Limits"

2. OP-PB-101-111-1002, "Peach Bottom Operations Overtime Guidelines" C. REFERENCES

1. LS-AA-119, Rev. 11, "Fatigue Management and Work Hour Limits"

2. OP-PB-101-111-1002, Rev. 6, "Peach Bottom Operations Overtime Guidelines" D. TASK STANDARD

1. Satisfactory task completion is indicated when the candidate successfully assesses the work hour limits and documents findings on the cue sheet.

2. Estimated time to complete: 20 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to review the work history provided, determine whether or not you are able to cover the requested shift AND determine if any work hour limits have already been violated, using appropriate procedures. I will describe initial conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. The present time/date is 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months on 2/16.

2. In accordance with OP-PB-101-111-1002, "Peach Bottom Operations Overtime Guidelines", the Shift Manager has directed the WECS to review the availability of RO #1 to work Dayshift 2/16 for load drop coverage.

3. RO #1 was on vacation for two weeks, returning to work on Sunday, 2/3.

4. RO #1 work history for the previous two weeks is as follows, with all hours having been in posted Licensed Reactor Operator positions.

Sunday Monday Tuesday Wednesday Thursday Friday Saturday 2/3 214 215 2/6 217 2/8 2/9 Worked Worked OFF Worked Worked OFF OFF 1900 - 0700 1900 - 0700 1900 - 1100 1900 - 0700 Sunday Monday Tuesday Wednesday Thursday Friday Saturday 2/10 2/11 2/12 2/13 2/14 2/15 2/16 Worked Worked Worked Worked Worked Worked Request:

0700 - 1900 0700 - 1900 0700 - 1900 0700 - 1900 0700 - 1900 0700 - 1900 0700 to 1900 PLOR279C Rev 2002 Page 3 of 6

G. INITIATING CUE Using the work history provided:

1. Determine whether or not RO #1 is able to cover the required shift.

2. If applicable, document fill work hour limits that would be exceeded if RO #1 works on Saturday 2/16.

3. Determine whether or not RO #1 has already violated any work hour limits.

4. If applicable, document fill work hour limits that have already been exceeded.

5. Document your results on the Cue sheet provided.

PLOR279C Rev 2002 Page 4 of 6

H. PERFORMANCE CHECKLIST Evaluator Cue:

Along with the Cue Sheet, provide candidate with copy of procedures OP-PB-101-111-1002, "Peach Bottom Operations Overtime Guidelines AND LS-AA-119 "Fatigue Management and Work Hour Limits".

1 Review work history, OP-PB-101-111- p Candidate reviews procedures for Work 1002, and LS-AA-119 to determine if able Hour limits and reviews work history to work requested shift. provided.

2 Determine that working the requested p Circles "Cannot" on the cue sheet for future shift will result in exceeding work question #1.

hour limits.

3 Identifies work hour limits exceeded if RO p Determines that working the requested

1 works on Saturday 2/16. shift would result in exceeding 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7-day period (Sunday, 2/10 through Friday, 2/15 shows 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months worked.

Working Saturday would result in exceeding 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in the 7-day period)

4 Determines whether or not RO #1 has p Circles "Yes" on the cue sheet for already violated any work hour limits. question #3.

5 Determine that the break between shifts p Documents less than a 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months break from Thursday 2/7 to Friday 2/8 was less between 2/7 to 2/8 on the cue sheet for than the required 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months . question #4.

6 Determine that shifts Thursday 2/7 to p Documents greater than 26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months worked Friday 2/8 were greater than 26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months (actual of 28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months ) in the 48-hour period worked in 48-hour period. over 2/7 to 2/8.

7 As an evaluator, ensure that you have p Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

Under "ACT" P - must perform PLOR279C Rev 2002 Page 5 of 6

I. TERMINATING CUE When review is complete and the cue sheet has been completed, the evaluator will terminate the exercise.

PLOR279C Rev 2002 Page 6 of 6

TASK CONDITIONS/PREREQUISITES

1. The present time/date is 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months on 2/16.

2. In accordance with OP-PB-101-111-1002, "Peach Bottom Operations Overtime Guidelines", the Shift Manager has directed the WECS to review the availability of RO #1 to work Dayshift 2/16 for load drop coverage.

3. RO #1 was on vacation for two weeks, returning to work on Sunday, 2/3.

4. RO #1 work history for the previous two weeks is as follows, with all hours having been in posted Licensed Reactor Operator positions.

Sunday Monday Tuesday Wednesday Thursday Friday Saturday 2/3 214 215 216 217 218 2/9 Worked Worked OFF Worked Worked OFF OFF 1900 - 0700 1900 - 0700 1900 - 1100 1900 - 0700 Sunday Monday Tuesday Wednesday Thursday Friday Saturday 2/10 2/11 2/12 2/13 2/14 2/15 2/16 Worked Worked Worked Worked Worked Worked Request:

0700 - 1900 0700 - 1900 0700 - 1900 0700 - 1900 0700 - 1900 0700 - 1900 0700 to 1900 INITIATING CUE Using the work history provided:

1. Determine whether or not RO #1 is able to cover the required shift.

Circle one: Can I Cannot

2. If applicable, document~ work hour limits that would be exceeded if RO #1 works on Saturday 2/16.

3. Determine whether or not RO #1 has already violated any work hour limits.

Circle one: Yes I No

4. If applicable, document~ work hour limits that have already been exceeded.

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

~ JPM D QUALIFICATION MANUAL D OJT MODULE PROGRAM: LICENSED OPERATOR TRAINING CODE#: PLOR-222C COURSE: LICENSED OPERATOR REQUALIFICATION REV#: 002 AUTHOR: M. J. Kelly TYPIST: mjk TITLE: REVIEW A TEMPORARY PROCEDURE CHANGE APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: I I NAME: ISSUE DATE:

Last First M.I.

EMPLOYEE ID#: COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMS CODE:

LMS ENTRY:

Signature/Date PLOR222C Rev 2 Page 1 of 5

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Senior Reactor Operator TASK-JPM DESIGNATOR: 3421130302 / PLOR-222C KIA: 2.2.6 SRO: 3.6 TASK DESCRIPTION: Knowledge of the process for making changes to procedures A. NOTES TO EVALUATOR:

1. An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR222C Rev 2 Page 2 of 5

B. TOOLS AND EQUIPMENT

1. ST-R-003-495-2 marked-up with a proposed Temporary Change to steps 5.8, 6.17.1.2, and Data Sheet 3 for changing the control rod insertion time criteria to position "36" from a maximum of 1.08 seconds to 1.15 seconds.

a. TC Form AD-PB-101-1003 F-01 should be on white colored paper

2. AD-PB-101-1003, Rev. 14, "Temporary Changes to Approved Documents and Partial Procedure Use"

3. AD-PB-101-1003-F-01, with first three sections filled out. See Attachment 2 of this JPM for an example.

C. REFERENCES

1. ST-R-003-495-2, Rev. 7 "CRD Scram Insertion Timing of Selected Control Rods During Hydro"

2. AD-PB-101-1003, Rev. 14, "Temporary Changes to Approved Documents and Partial Procedure Use" D. TASK STANDARD

1. Satisfactory task completion is indicated when the Shift Management review has been completed and it has been identified that the proposed temporary change results in change of intent and the Temporary Change is disapproved pending resolution of the problem.

2. Estimated time to complete: 10 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to review a Temporary Change to a procedure using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Unit 2 is in a refueling outage.

2. A Temporary Change has been prepared for ST-R-003-495-2, "CRD Scram Insertion Timing of Selected Control Rods During Hydro". Steps 5.8, 6.17, and Data Sheet 3 have been modified.

G. INITIATING CUE You have been assigned as the SRO Reviewer for the temporary change to the surveillance procedure. Review and approve the temporary change to ST-R-003-495-2, "CRD Scram Insertion Timing of Selected Control Rods During Hydro".

PLOR222C Rev 2 Page 3 of 5

H. PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD

- - Note***

Provide marked up procedure change AND a copy of procedure AD-PB-101-1003 to the Examinee.

1 Review ST-R-003-495-2 temporary p Review the procedure change and procedure change. compare it to the Change of Intent Screening criteria in AD-PB-101-1003.

2 Identify a change of intent due to: p Identify that the proposed change to steps 5.8, 6.17.1.2, and Data Sheet 3

a change to the acceptance criteria constitutes a "change of intent" in that decreases the margin of accordance with AD-PB-101-1003 step acceptance (step 3.2.1), 2.1 and 3.2.1 due to:

and/or

a change to the acceptance criteria that decreases the margin of

a change to technical specifications acceptance, (step 3.2.1) and/or

a change to technical specifications Either of the above choices is acceptable

3 Disapprove the procedure change. p Disapprove the temporary procedure change.

(Cue: Acknowledge the disapproval.)

4 As an evaluator, ensure that you have p Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

Under "ACT" P - must perform S - must simulate PLOR222C Rev 2 Page 4 of 5

I. TERMINATING CUE When the review of ST-R-003-495-2 has been completed, and the temporary procedure change is disapproved, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

PLOR222C Rev 2 Page 5 of 5

TASK CONDITIONS/PREREQUISITES

1. Unit 2 is in a refueling outage.

2. A Temporary Change has been prepared for ST-R-003-495-2, "CRD Scram Insertion Timing of Selected Control Rods During Hydro". Steps 5.8, 6.17, and Data Sheet 3 have been modified.

INITIATING CUE You have been assigned as the SRO Reviewer for the temporary change to the surveillance procedure.

Review and approve the temporary change to ST-R-003-495-2, "CRD Scram Insertion Timing of Selected Control Rods During Hydro".

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

~ JPM D QUALIFICATION MANUAL D OJT MODULE PROGRAM: LICENSED OPERATOR TRAINING CODE#: PLOR-256C COURSE: LICENSED OPERATOR REQUALIFICATION REV#: 002 AUTHOR: M. J. Kelly TYPIST: Jav TITLE: REVIEW AND APPROVE PRIMARY CONTAINMENT PURGENENT ISOLATION VALVE CUMULATIVE HOUR LOG APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE:

NAME: ISSUE DATE:

Last First M.I.

EMPLOYEE ID#: COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMS CODE:

LMS ENTRY:

Sig nature/Date PLOR256C Rev 2 Page 1 of 5

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2270140201 I PLOR-256C KIA: G2.3.13 SRO: 3.8 TASK DESCRIPTION: Perform Primary Containment PurgeNent Isolation Valve Cumulative Log.

A. NOTES TO EVALUATOR:

1. An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR256C Rev 2 Page 2 of 5

B. TOOLS AND EQUIPMENT

1. Calculator

2. Copy of ST-0-007-560-2, "Primary Containment PurgeNent Isolation Valve Cumulative Hour Log".

3. A calculation error made on Data Sheet 1 such that "Accumulated Total Time Since Beginning of Calendar Year" is greater than 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months , with the procedure completed to indicate total time is less than 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months (use Attachment 2 of this JPM for exact values).

C. REFERENCES

1. ST-0-007-560-2, Rev. 2, "Primary Containment PurgeNent Isolation Valve Cumulative Hour Log".

D. TASK STANDARD

1. Satisfactory task completion is indicated when the Shift Management review has been completed, the calculation error on Data Sheet 1 identified, and the total accumulated time a purge/vent valve is open has been determined to be greater than 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months .

2. Estimated time to complete: 15 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to review the Primary Containment PurgeNent Isolation Valve Cumulative Hour Log. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. The "Primary Containment PurgeNent Isolation Valve Cumulative Hour Log" for Unit 2 (ST-0-007-560-2) has been completed.

2. The "Accumulated Total Time Since Beginning of Year" is greater than 80 hours9.259259e-4 days 0.0222 hours 1.322751e-4 weeks 3.044e-5 months . Shift Management has been notified as required by Step 6.1.6.

G. INITIATING CUE You are the Work Control Supervisor. Perform the Plant Staff review and approval of ST-0-007-560-2, "Primary Containment PurgeNent Isolation Valve Cumulative Hour Log". Document all errors on procedure copy, if applicable.

PLOR256C Rev 2 Page 3 of 5

H. PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD 1 Cue: Hand the Examinee a completed copy of ST-0-007-560-2," Primary Containment PurgeNent Isolation Valve Cumulative Hour Log" with Data Sheets 1 and 2 data filled in by hand from Attachment 2 of this JPM.

2 Review ST-0-007-560-2 for p Verifies all procedure steps, Data Sheet completeness. 1, and Data Sheet 2 have been completed satisfactorily.

3 Verify calculations. p Performs all calculations that were done on Data Sheet 1 to verify they are correct and properly recorded.

4 Recognize calculation errors. p Recognizes the following calculation errors on Data Sheet 1:

1. Second row of the "Flow Path Open Total Time" column should be 17 Hr, 4 Min versus 5 Hr, 4 Min.

2. Fourth row of the "Accumulated Total Time Since Beginning of Calendar Year" column total is incorrect. .. one additional hour should be added.

NOTE: the "critical" part of this step is to recognize the first error and the fact that the accumulated total time has exceeded 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months .

5 Determines the "Accumulated Total Time p Determines the "Accumulated Total Time Since Beginning of Year" is beyond the Since Beginning of Year" is 93 Hr, 22 Min Acceptance Criteria specified in Step 5.0. versus 80 Hr, 22 Min.

6 Notify Shift Management of unsatisfactory p Reports to Shift Manager and/or Control test results. Room Supervisor that the "Accumulated Total Time Since Beginning of Year" is (Cue: Acknowledge report.) greater than 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months .

7 As an evaluator, ensure that you have p Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

PLOR256C Rev 2 Page 4 of 5

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When the review of ST-0-007-560-2 has been completed, the calculation error on Data Sheet 1 identified, and the total accumulated time a purge/vent valve is open has been determined to be greater than 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months , the evaluator will terminate the exercise.

PLOR256C Rev 2 Page 5 of 5

TASK CONDITIONS/PREREQUISITES

1. The "Primary Containment PurgeNent Isolation Valve Cumulative Hour Log" for Unit 2 (ST-0-007-560-2) has been completed.

2. The "Accumulated Total Time Since Beginning of Year" is greater than 80 hours9.259259e-4 days 0.0222 hours 1.322751e-4 weeks 3.044e-5 months .

Shift Management has been notified as required by Step 6.1.6.

INITIATING CUE You are the Work Control Supervisor.

Complete the Plant Staff review and approval of ST-0-007-560-2, "Primary Containment PurgeNent Isolation Valve Cumulative Hour Log".

Document all errors on procedure copy, if applicable.

Exelon Nuclear ST-0-007-560-2 Peach Bottom Rev. 2 Unit 2 Page 1 of 8 Routine Test HJM:hjm ST-0-007-560-2 PRIMARY CONTAINMENT PURGE/VENT ISOLATION VALVE CUMULATIVE HOUR LOG TEST FREQUENCY: Once/Shift (See Section 1.0)

TECH SPEC: 3.6.1.3 APPLICABILITY: None CHECK why this procedure is being performed:

II Schedule D OVF D Retest Due To Unsat Test D Other Reason:

Approved by SMgt: "N/A" I I Printed Name Time Date Initials INITIAL one of the following Test Results:

A: All R steps are SATISFACTORY B: One or More R steps are UNSATISFACTORY Refer to Section 9.0 for Corrective Action I I Performed By: I I Printed Name Time Date Initials RO/PRO Informed of Test Completion: "N/A" I I SMgt Informed of Test Results: I I UNSAT Notification:

SMgt Discretion: Plant Mgr or Others Notified By: I I IF other portions of the test did NOT function properly, OR other discrepancies were noted, THEN COMPLETE the following:

DESCRIBE discrepancies/actions taken: Issue or ETT#: - - - - -

Reviewed/Approved Plant Staff:

I I Printed Name Time Date Initials

ST-0-007-560-2 Rev. 2 Page 2 of 8

~URPOSE

~:his test tracks the total hours the 6" Containment Purge/Vent Isolation Valves and 18" Primary are open when Reactor pressure is greater than 100 PSIG, and Reactor is in Mode 1 or 2 or the calendar year for Tech Spec 3.6.1.3 Condition E. This test is issued weekly and performed once per shift. CM-1 EQUIPMENT Initial Initiation Review ENSURE procedure is current revision. -~-

IF this test is being performed for the first time this calendar year, THEN ENTER "0" on Data Sheet 1 the Total Hours to date in "Total Fwd" space AND N/A Step 3.2.3.

OTHERWISE, N/A this step.

Nii!

IV OBTAIN a copy of last performed ST-0-007-560-2 "Primary Containment Purge/Vent Isolation Valve Cumulative Hour Log" AND RECORD on Data Sheet 1 the Total Hours to date in "Total Fwd" space. -~

I. o/.

IV ent Configuration

.3.1 VERIFY the following conditions exists:

~eactor is in Mode 1 or 2. -~-

~~eactor RO pressure is greater than 100 PSIG. -~

RO Required Redundant Safety Related Equipment None

ST-0-007-560-2 Rev. 2

/ Page 3 of 8

~Approval to Start Test

~ OBTAIN RO Permission to begin. <Time :M/cD/~ -~-

Time Date RO IONS, LIMITATIONS, AND GENERAL INSTRUCTIONS Statement This does NOT impact plant availability in any manner. This test is only performed when Reactor pressure is greater than 100 PSIG AND Reactor is in Mode 1 OR 2.

Instructions IF any procedure step CANNOT be completed OR produces an unexpected response, THEN STOP the test AND RETURN the equipment to a safe condition AND NOTIFY the RO or SMgt.

IF any Black Box is initialed, THEN STOP the test AND RETURN the equipment to a safe condition AND NOTIFY the RO or SMgt.

IF procedure is aborted, THEN NOTIFY SMgt AND WRITE "TEST ABORTED" in Section 3 of Cover Page.

All persons who initial steps in Sections 3.0, 6.0, or 7.0 are responsible for completing Section 10.0.

All applicable R steps are identified immediately in front of the initials.

ACCEPTANCE CRITERIA The total accumulated time a purge or vent flow path exists when Reactor pressure is greater than 100 PSIG and Reactor is in Mode 1 or 2 is less than 90 hour0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months s/year.

ST-0-007-560-2 Rev. 2 Page 4 of 8 Initial Sat UnSat ata Acquisition All data and sign- the following steps are located on Data 1 and 2.

< At C trol Room Panel 20C003-03 >

INDICATE with a Check Mark 11 '1 11 flow path(s) used ORN/A for non-use AND INITIAL AND DATE once per shift on Data Sheet 2.

RECORD time any flow path is open AND Reactor pressure is GREATER than 100 PSIG AND Reactor is in Mode 1 or 2.

RECORD time all flow paths are closed OR Reactor pressure is LESS than 100 PSIG OR Reactor is in Mode 3, 4, or 5.

CALCULATE AND RECORD "Flow Path Open Total Time".

CALCULATE AND RECORD "Accumulated Total Time Since Beginning of Calendar Year".

NOTIFY SMgt once "Accumulated Total Time Since Beginning of Calendar Year" is greater than 80 hours9.259259e-4 days 0.0222 hours 1.322751e-4 weeks 3.044e-5 months .

VERIFY "Accumulated Total Time Since Beginning of Calendar Year" is less than 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months AND INITIAL block on Data Sheet 1.

IF NO calculations were performed then VERIFY "Accumulated Total Time Since Beginning of Calendar Year" is less than 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months . N/A IF calculations were performed. R_~-D

ST-0-007-560-2 Rev. 2 Page 5 of 8 URE COMPLETION Initial WHEN weekly data is collected, THEN VERIFY calculations are correct. N/A IF NO calculations were performed. I. o/.

IV Completion COMPLETE Section 2 of Cover Page (and Section 3 IF applicable). -~-

Tech Spec 3.6.1.3 Condition E.

CM-1, Req to Spec Accum Time for Purge/Vent Path to 90 HRS (T03820) mental Letter of Thomas Ippolito, NRC to Edward Bauer, Jr.,

PECO dated November 29, 1978.

This procedure supersedes RT-0-007-560-2.

ACTIONS IF corrective actions are necessary, THEN INITIATE an Issue to correct problems.

ST-0-007-560-2 Rev. 2 Page 6 of 8 10.0 PARTICIPANTS RECORD Printed Name Initials

~act Orr -~-

I mfie o/erif - o/. -

I.-

ST-0-007-560-2 Rev. 2 Page 7 of 8 DATA SHEET 1 6 11 AND 18" FLOW PATH TOTAL HOUR LOG Any 6" or 18" Flow Path All 6" or 18" Flow Path Flow Path Open Accumulated Total Time Accumulated Total Time OPEN AND Reactor CLOSED OR Reactor Total Time Since Beginning of Since Beginning of pressure GREATER than 100 PSIG AND Reactor in Mode 1or2.

100 PSIG OR pressure LESS than Mode 3, 4, or 5.

Reactor in Calendar Year (Note 1) Calendar Year< 90 hrs (Hours &

Initial TIME DATE TIME DATE Minutes) Total Fwd: _§ill__ Unsat 61 Hr, 28 Min 0131 03/19/13 0411 03/19/13 2 Hr, 40 Min 64 Hr, 8 Min R-~-CJ 0428 03/19/13 2132 03/19/13 5 Hr, 4 Min 69 Hr, 12 Min R-~-CJ 2147 03/19/13 2319 03/19/13 1Hr,32 Min 70 Hr, 44 Min R-~-CJ 0916 03/23/13 1706 03/23/13 7 Hr, 50 Min 77 Hr, 34 Min R_~-CJ 1154 03/24/13 1442 03/24/13 2 Hr, 48 Min 80 Hr, 22 Min R-~-CJ R_CJ R_CJ R_CJ R_CJ R_CJ R_CJ R_CJ R_CJ R_CJ NOTE 1: IF "Accumulated Total Time Since Beginning of Year" is greater than or equal to 80 hrs, THEN NOTIFY SMgt.

ST-0-007-560-2 Rev. 2 Page 8 of 8 DATA SHEET 2 DAY I SHIFT DATE FLOW PATHS USED Initial (See below) Sat Un sat 1 2 3 4 5 6 7 MON D 03/18/13 N/A N/A N/A N/A N/A N/A N/A

~o.

N N/A N/A -..j -..j -..j -..j N/A

" ~o.

TUE D 03/19/13 N/A N/A N/A -..j N/A -..j N/A

~o.

N " N/A N/A -..j -..j -..j -..j N/A

~o.

WED D 03/20/13 N/A N/A N/A N/A N/A N/A N/A

~o.

N " N/A N/A N/A N/A N/A N/A N/A

~o.

THUR D 03/21/13 N/A N/A N/A N/A N/A N/A N/A

~o.

N " N/A N/A N/A N/A N/A N/A N/A

~o.

FRI D 03/22/13 N/A N/A N/A N/A N/A N/A N/A

~o.

N " N/A N/A N/A N/A N/A N/A N/A

~o.

SAT D 03/23/13 N/A -..j N/A N/A -..j N/A N/A

~o.

N " N/A N/A N/A N/A N/A N/A N/A

~o.

SUN D 03/24/13 -..j -..j N/A N/A -..j -..j N/A

~o.

N " N/A N/A N/A N/A N/A N/A N/A

~o.

1. A0-2-078-2519 and A0-2-078-2520 OPEN in a Drywell N2 Purge Flowpath

2. A0-2-078-2519 and A0-2-078-25218 OPEN in a Torus N2 Purge Flowpath

3. A0-2-078-2505 and A0-2-078-2520 OPEN in a Drywell Purge Supply Flowpath

4. A0-2-078-2521A and A0-2-078-25218 OPEN in a Torus Purge Supply Flowpath

5. A0-2-078-2506 and A0-2-078-2507 OPEN in a Drywell Exhaust Flowpath

6. A0-2-078-2511 and A0-2-078-2512 OPEN in a Torus Exhaust Flowpath

7. Abnormal Flowpath.

==

Description:==

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

D Day Shift - 6:30a - 6:30p N Night Shift - 6:30p - 6:30a

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

~ JPM D QUALIFICATION MANUAL D OJT MODULE PROGRAM: LICENSED OPERATOR TRAINING CODE#: PLOR-153C COURSE: LICENSED OPERATOR REQUALIFICATION REV#:: 000 AUTHOR: R. J. Artus TYPIST: Rja TITLE: EAL CLASSIFICATION AND STATE/LOCAL NOTIFICATIONS FOR AN ALERT-INABILITY TO MAINTAIN PLANT IN COLD SHUTDOWN APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE:

NAME: ISSUE DATE:

Last First M.I.

EMPLOYEE ID NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMS CODE:

LMS ENTRY:

Signature/Date PLOR153C Rev 00 Page 1 of 7

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Senior Reactor Operator TASK-JPM DESIGNATOR: 2007510502 I PLOR-235C KIA: 2.4.41 SRO: 4.6 TASK DESCRIPTION: Classification of Emergencies and PARs A. NOTES TO EVALUATOR:

1. An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

c. Applicable JPM Work Practice Standards, TQ-JA-150-04 graded satisfactorily.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR153C Rev 00 Page 2 of 7

B. TOOLS AND EQUIPMENT

1. Ensure there are multiple copies of EP binders available that contain all the procedures listed below in the References Section C.

2. Copy of PMS Met Data screen that displays a wind direction of 75 degrees and a wind speed of 5 mph.

C. REFERENCES

1. EP-AA-111 Rev. 19, "Emergency Classification and Protective Action Recommendations"

2. EP-AA-111-F-08 Rev. G, "Limerick I Peach Bottom Plant Based PAR Flowchart"

3. EP-AA-112-100 Rev. 13, "Control Room Operations"

4. EP-AA-112-100-F-01 Rev. U, "Shift Emergency Director Checklist"

5. EP-AA-114-F-02 Rev A, "BWR Release in Progress Determination Guidance"

6. EP-MA-114-100 Rev. 20, "Mid-Atlantic State/Local Notifications"

7. EP-MA-114-1 OO-F-01 Rev 0, "State/Local Notification Form"

8. EP-AA-1007, ADDM 3 Rev. 000, "Exelon Nuclear Emergency Action Levels for Peach Bottom Atomic Power Station" D. TASK STANDARD

1. Satisfactory task completion is indicated when the plant conditions have been classified correctly and EP-MA-114-1 OO-F-01, "State/Local Event Notification Form" has been completed accurately.

(NOTE: The criteria for accurate Event Notification form completion were derived from EP-AA-125-1002 Rev. 8, "ERO Performance - Performance Indicators Guidance").

2. Estimated time to complete: Event Classification - 15 minutes: Time Critical State/Local Notification - 13 minutes: Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to make the EAL classification and complete the State/Local Event Notification form (if required). I will describe initial plant conditions and provide you access to the materials required to complete this task.

PLOR153C Rev 00 Page 3 of 7

F. TASK CONDITIONS/PREREQUISITES NOTE: This is a time critical JPM.

Unit 2 is operating at 100% power Unit 3 has just shut down for a refueling outage. The Reactor Head has been removed. Fuel moves have not begun.

A loss of Off-site power has occurred. The following conditions exist:

E-2 and E-3 D/G have started and are supplying power to their respective 4KV busses.

Unit 2 has scrammed automatically. RPV level is being controlled by RCIC at -127 inches.

Shut down cooling has been lost on Unit 3.

Unit 3 Reactor Coolant temperature is 215°F and rising

Unit 3 Reactor Building and Refuel Floor differential pressures are indicating +.05 on DPI 3003-1 & 2.

G. INITIATING CUE As the Emergency Director:

1. Make the EAL classification. Inform the Proctor when you have made a declaration.

2. Complete the State/Local Event Notification form. Inform the Proctor when you have completed the State/local Event Notification Form.

PLOR 153C Rev 00 Page 4 of 7

H. PERFORMANCE CHECKLIST STEP STEP ACT STANDARD NO

- - NOTE***

Record the time using the clock above the Full Core Display. Time =

1 Obtain procedures EP-AA-112-1 OO-F-01, p Procedures EP-AA-112-100-F-01 and "Shift Emergency Director Checklist" and EP-AA-1007 are obtained.

EP-AA-1007, "Radiological Emergency Plan Annex for PBAPS."

2 Determine the appropriate EAL IC. p The following sections of EP-AA-1007, CA5 Table PBAPS 3-1 are referenced:

(Cue: Classification is acknowledged.) MU1 is referenced due to the loss of Off-site power. This is a correct EAL classification but not the highest classification that exists.

CU5 is referenced. CU5 is a correct classification but not the highest classification.

CA5 is the correct EAL classification for Unit 3. The Reactor Head is removed which means that the RCS is not intact.

Primary containment is not intact because Reactor building differential pressure is positive therefore Secondary Containment is not established ..

3 Announce the event classification to the p Announces the event classification to the facility staff. Control Room crew.

- - NOTE***

WHEN the examinee completes the classification determination, THEN record the time using the clock above the Full Core Display. Time=

Determine if the elapsed time since the initiating cue exceeds 15 minutes.

This time will also be used as the starting time for the State/Local notification process.

- - NOTE***

Inform examinee that the Public Address announcement & ERO Notification are NOT required.

- - NOTE***

Follow-u~ Cue: Complete EP-MA-114-100-F-01, "State/Local Notification Form."

PLOR 153C Rev 00 Page 5 of 7

STEP STEP ACT STANDARD NO

- - NOTE***

The following steps are associated with EP-MA-114-1 OO-F-01, "State/Local Event Notification Form."

4 Check the call status. p "This is a drill" is checked in Block #1.

5 Check the affected station. p "Peach Bottom" is checked in Block #2.

6 Check the affected unit(s). event p Unit 3 is checked in Block #3.

classification.

7 Check the event classification. p "ALERT" classification is checked in Block #4.

8 Enter the time and date of the p Declaration time (in 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months clock declaration. nomenclature) and today's date are entered in Block #5. The declaration time should match the time the examiner entered in the note before JPM step 1.

9 Check the applicable change in p "Initial Declaration" is checked in Block classification status. #6.

10 Enter the EAL number declared. p EAL# CA5 is annotated in Block #7

11 Provide a brief non-technical description p Check box "F" Cold Shutdown/Refueling of the event. System Malfunction in Block #8.

12 Check the non-routine radiological p "No radiological release in-progress" release status. is checked in Block #9. EP-AA-114-F-02, "BWR Release In Progress Determination Guidance" may be referenced.

13 Enter the wind direction "Degrees from". p Wind direction of 75 degrees is obtained from either PMS Met data or Control (Cue: Wind direction is from 75 Room panel OOC767 and is entered in degrees.) Block #10. Minor discrepancy in parameter value is acceptable.

14 Enter the wind speed. p Wind speed of 5 mph is obtained from either PMS Met data or Control Room (Cue: Wind speed is 5 mph.) panel OOC767 and is entered in Block

10. Minor discrepancy in parameter value is acceptable.

15 Check the utility Protective Action p The "None" box is checked in Block #11.

Recommendation.

16 Enter Communication Information. p "This is a drill" is checked in Block #13.

17 Utility Message number and approve the p The Emergency Director enters "1" for event notification form. the Utility Message Number and signs the Event Notification form in the form's header area.

- - NOTE***

WHEN the examinee completes the Event Notification form, THEN record the time using the clock above the Full Core Display. Time=

Determine if the elapsed time since the classification exceeds 13 minutes.

PLOR153C Rev 00 Page 6 of 7

STEP STEP ACT STANDARD NO 18 As the evaluator, ensure that you have p Positive control established.

positive control of all exam material provided to the examinee (Task condition/Prerequisites) AND procedures.

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When plant conditions have been classified and EP-MA-114-100-F-O 1, "State/Local Event Notification Form" has been completed, the evaluator will then terminate the exercise.

PLOR153C Rev 00 Page 7 of 7

TASK CONDITIONS/PREREQUISITES NOTE: This is a time critical JPM.

1. Unit 2 is operating at 100°/o power

2. Unit 3 has just shut down for a refueling outage. The Reactor Head has been removed. Fuel moves have not begun.

3. A loss of Off-site power has occurred. The following conditions exist:

E-2 and E-3 DIG have started and are supplying power to their respective 4KV busses.

Unit 2 has scrammed automatically. RPV level is being controlled by RCIC at -127 inches.

Shut down cooling has been lost on Unit 3.

Unit 3 Reactor Coolant temperature is 215°F and rising

Unit 3 Reactor Building and Refuel Floor differential pressures are indicating +.05 on DPI 3003-1 & 2.

INITIATING CUE As the Emergency Director:

1. Make the EAL classification. Inform the Proctor when you have made a declaration.

2. Complete the State/Local Event Notification form. Inform the Proctor when you have completed the State/local Event Notification Form.

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

~ JPM D QUALIFICATION MANUAL D OJT MODULE PROGRAM: LICENSED OPERATOR TRAINING CODE#: PLOR-374CA COURSE: LICENSED OPERATOR REQUALIFICATION REV#:: 001 AUTHOR: R. J. Artus TYPIST: mda TITLE: Reactor Operator Actions On A Recirc Pump Trip (Alternate Path-Thermal Hydraulic Instabilities Exist Without Operable OPRMs)

APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: I I NAME: ISSUE DATE:

Last First M.I.

EMPLOYEE ID NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMS CODE:

LMS ENTRY:

Signature/Date PLOR374CA Rev 1 Page 1of7

EXELON NUCLEAR

PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2007200501 I PLOR-374CA KIA: 295001.AA 1.06 RO: 3.3 SRO: 3.4 TASK DESCRIPTION: Perform Actions for an Unexpected/Unplanned Change in Core Flow perOT-112 A. NOTES TO EVALUATOR:

1. An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

c. Applicable JPM Work Practice Standards, TQ-JA-150-04 graded satisfactorily.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR374CA Rev 1 Page 2 of 7

B. TOOLS AND EQUIPMENT None C. REFERENCES

1. SO 2D.7.B-2, Rev.22, "Recirculation MG Set Scoop Tube Lockup and Reset"

2. GP-9-2, Rev. 35, "Fast Reactor Power Reduction"

3. OT-112, Rev. 39, "Unexpected/Unexplained Change in Core Flow"

4. AO 60A.1-2 Rev 1, "Alternate Method to Detect and Suppress Thermal Hydraulic Instability (THI)"

D. TASK STANDARD

1. Satisfactory task completion is indicated when the trip of the 'A" reactor recirculation pump has been recognized, GP-9-2 control rod insertion was initiated, and the reactor has been scrammed upon recognition of Thermal Hydraulic Instability (THI).

2. Estimated time to complete:

1. 90 seconds to start insertion of GP-9-2 control rods upon recognition of 'A' recirculation pump trip,

2. 5 minutes from the onset of THI as defined in AO 60A.1-2, "Alternate Method to Detect and Suppress Thermal Hydraulic Instability (THI)".

E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to lockup the 2A Reactor Recirculation Pump. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Unit 2 is operating at 100% power.

3. The OPRM System is NOT operable.

2. The 2A Reactor Recirculation Pump M-G Set needs to have the scoop tube locked up for approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to support scheduled maintenance.

4. An Equipment Operator is standing by in the Unit 2 Reactor Recirculation M-G Set Room.

PLOR374CA Rev 1 Page 3 of 7

G. INITIATING CUE The Control Room Supervisor directs you, the Unit Reactor Operator, to lockup the 2A Reactor Recirculation Pump M-G Set using SO 20.7.B-2, "Recirculation MG Set Scoop Tube Lockup and Reset".

PLOR374CA Rev 1 Page 4 of 7

H. PERFORMANCE CHECKLIST STEP STEP ACT STANDARD NO 1 Obtain a copy of procedure SO 2D.7.B-2, p Copy of procedure SO 2D.7.B-2, "Recirculation MG Set Scoop Tube "Recirculation MG Set Scoop Tube Lockup and Reset" Lockup and Reset" is obtained.

2 Obtain a copy of procedure AO 60A.1-2, p Copy of AO 60A.1-2, "Alternate Method to "Alternate Method to Detect and Suppress Detect and Suppress Thermal Hydraulic Thermal Hydraulic Instability (THI)". Instability (THI)", is obtained.

3 Review section 4.2 of SO 2D.7.B-2, p Section 4.2 of SO 2D.7.B-2, "Recirculation "Recirculation MG Set Scoop Tube MG Set Scoop Tube Lockup and Reset" Lockup and Reset" for guidance during for guidance during transients requiring transients requiring flow reductions. flow reductions is reviewed.

4 Note speed demand setting for the p Speed demand setting for the affected MG affected MG set on SPl-2-02-184-016A-1. set on SPl-2-02-184-016A-1 noted.

5 Note the current settings of variables 'S' p The current settings of variables 'S' and and 'V' of Moore Controller SPIC-2 'V' of Moore Controller SPIC-2-02-184-184-016A 016A are noted.

6 Place Scoop Tube Positioner Lockup p Scoop Tube Positioner Lockup Switch 2A-Switch 2A-S2A at Panel 20C004A to S2A at Panel 20C004A is taken "counter-

"LOCK". clockwise to "LOCK".

7 Verify annunciator 213 A-3, "A RECIRC p Verifies and acknowledges annunciator FLUID DRIVE SCOOP TUBE LOCK" in 213 A-3, "A RECIRC FLUID DRIVE alarm. SCOOP TUBE LOCK" in alarm.

8 Verify the "Scoop Tube Lockup" light is lit p Direct an Equipment Operator to verify the at Panel 2AC152 in MG Set Room. "Scoop Tube Lockup" light is lit at Panel 2AC152 in MG Set Room.

(CUE: If directed as an Equipment Operator, report that the Scoop Tube Lockup" light is lit at Panel 2AC152.)

9 Verify annunciator 214 E-2, "A Recirc p Verifies and acknowledges annunciator Scoop Tube Positioner Trouble" is in 214 E-2, "A Recirc Scoop Tube Positioner alarm. Trouble" is in alarm.

PLOR374CA Rev 1 Page 5 of 7

STEP STEP ACT STANDARD NO

- - NOTE***

The Alternate Path portion of the JPM begins with the next step

10 Recognize the trip of the "A" Recirc MG p Verifies the trip of the "A" Recirc pump by Set Drive Motor Breaker". monitoring the following:

Green light on for the "A" Recirc MG Set Drive Motor Breaker.

Drop in Reactor Power.

Rise in RPV level.

Recognize and acknowledge annunciator 214 C-3, "A RECIRC DRIVE MOTOR TRIP".

11 Obtain a copy of procedure GP-9-2, "Fast p A copy of procedure GP-9-2 is obtained.

Reactor Power Reduction".

Note The malfunction for THI will be entered either after the first Control Rod is driven or 3 minutes has elapsed since the trip of the recirculation pump, whichever occurs first.

12 Drive in the following GP-9-2, Appendix 1, p GP-9-2, Appendix 1, Table 1 control rods Table 1 control rods: are selected and driven in by depressing 22-23, the corresponding select matrix 38-39, pushbutton and placing 3A-S2, ROD 38-23, CONTROL switch OR 3A-S3, 22-39, EMERGENCY IN/ NOTCH OVERRIDE 30-15, switch in the IN position at panel 30-47, 20C005A.

14-31, Operations Management expects insertion 46-31, of GP-9-2 control rods to be performed 30-31. within 90 seconds of the trip of the recirculation pump. Doubling this (Cue: Rod Select matrix pushbuttons estimated time is acceptable provided the backlight for each selected rod, Full Core evaluator determines that the progress to Display rod position has green "00" on for completion is acceptable.

each inserted rod.)

13 Monitor for Thermal Hydraulic Instabilities p All APRM recorders are monitored for (THI) on the APRMs. noise level growing by two or more times or oscillations greater than 10% peak to (Cue: APRMs A, B, and D readings are peak on panel 20C005A.

swinging from 45% to 60%.)

14 Recognize Thermal Hydraulic Instabilities p Determine that the Power oscillations (THI). meet the criteria for TH I PLOR374CA Rev 1 Page 6 of 7

STEP STEP ACT STANDARD NO 15 Inform Control Room Supervisor of the p The presence of Thermal Hydraulic Thermal Hydraulic Instabilities and the Instabilities and the insertion of a manual insertion of a manual scram. scram reported.

(Cue: Control Room Supervisor acknowledges report.)

16 Place the Mode Switch in SHUTDOWN. p Mode Switch moved counterclockwise from "RUN" to "SHUTDOWN" position at (Cue: Annunciator 211 A-2 is alarming) panel 20C005A.

17 Verify that Control Rods are in the process p Rod positions verified "COUNTING of inserting. DOWN" on the full core display at panel 20C0058.

(Cue: All rod positions indicate inward rod movement.)

18 Verify all APRM Downscale Lights are lit p Individual APRM downscale lights verified ON at panel 20C005A.

19 Initial scram report made to Control Room p The following report is made to the Control Supervisor. Room Supervisor:

Mode switch is in SHUTDOWN (Cue: Control room supervisor

Control Rods are inserting acknowledges initial scram report.)

APRMs are downscale .

When the initial scram actions are complete, inform the examinee that the JPM is complete.

20 As an evaluator, ensure that you have p Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

Under "ACT P - must perform S - must simulate I. TERMINATING CUE When the Reactor has been manually scrammed due to the presence of thermal hydraulic instabilities and the initial scram actions are complete, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

PLOR37 4CA Rev 1 Page 7 of 7

TASK CONDITIONS/PREREQUISITES

1. Unit 2 is operating at 1OOo/o power.

2. The OPRM System is NOT operable.

3. The 2A Reactor Recirculation Pump M-G Set needs to have the scoop tube locked up for approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to support scheduled maintenance.

4. An Equipment Operator is standing by in the Unit 2 Reactor Recirculation M-G Set Room INITIATING CUE The Control Room Supervisor directs you, the Unit Reactor Operator, to lockup the 2A Reactor Recirculation Pump M-G Set using SO 20. 7.B-2, "Recirculation MG Set Scoop Tube Lockup and Reset".

SIMULATOR JPM INITIAL CONDITIONS JPM NO: PLOR-374CA TITLE: URO Actions on a Recirc Pump Trip (Alternate DATE: 3/15/15 Path - THI)

SIMULATOR INITIAL CONDITIONS IC NO: 14 TITLE: 100% Power Target Rod Pattern POWER: 100%

PRESSURE: 1030 psig MALF FINAL DELAY RAMP ACTIVE REMOTE EVENT No. TITLE SEV. TIME TIME TIME SWITCH AC DA NOTE APR02A APRM Channel 1 Average 100 Circuit Deviation

. APR02B APRM Channel 2 Average 100 Circuit Deviation

.:-:--::2c APRM Channel 3 Average 100 Circuit Deviation APR02D APRM Channel 4 Average 100 Circuit Deviation RRS08A Recirc M-G Drive Motor "A" Breaker Trip 1/0 OVERRIDE LIST (IOSI)

PAGE VALUE/ EVENT TIME PLANT ID No. TITLE STATUS AC I DA DELAY NOTE AN0205RA3 APRM/OPRM Hl-Hl-INOP ALARM_OFF I REMOTE FUNCTIONS (RFI)

RF ID# I PAGE NO. I TITLE I VALUE/STATUS I EVENT I NOTE SPECIAL NOTES

1. Enter the following 1/0 Override:

IOR AN0205RA3 ALARM_OFF "APRM/OPRM Hl-Hl-INOP"

2. Have a copy of the alternate Power/Flow map available

3. Start JPM.

4. WHEN the "A" M/G Set is locked up THEN enter the following Malfunction:

IMF RRS08A "Recirc M-G Drive Motor 'A' Breaker Trip".

5. When the Candidate has either driven the first Control Rod OR 3 minutes has elapsed since the recirc pump trip, THEN enter the following Malfunction:

APR02A 100, "APRM Channel 1 Average Circuit Deviation"

APR02B 100, "APRM Channel 3 Average Circuit Deviation"

APR02C 100, "APRM Channel 3 Average Circuit Deviation"

APR02D 100, "APRM Channel 4 Average Circuit Deviation"

6. Delete Malfunction DMF APR02 A-D when the reactor is scrammed.

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

~ JPM D QUALIFICATION MANUAL D OJT MODULE PROGRAM: Licensed Operator Training CODE#: PLOR-353CA COURSE: Licensed Operator Requalification REV#:: 001 AUTHOR: M. J. Kelly TYPIST: mda TITLE: Startup HPCI in the CST To CST Mode (Alternate Path - Turbine Exhaust Diaphragm High Pressure)

APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: I I NAME: ISSUE DATE:

Last First M.I.

EMPLOYEE ID NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMS CODE:

LMS ENTRY:

Signature/Date PLOR353CA Rev 1 Page 1 of 8

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2060480401 I PLOR-353CA KIA: 206000A3.07 RO: 3.9 SRO: 3.8 TASK DESCRIPTION: Startup HPCI in the CST to CST Mode (Alternate Path - Turbine Exhaust Diaphragm High Pressure)

A. NOTES TO EVALUATOR:

1. An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR353CA Rev 1 Page 2 of 8

B. TOOLS AND EQUIPMENT None C. REFERENCES

1. RRC 23.1-2, Rev. 6, "HPCI System Operation During a Plant Event"

2. ARC 221 (20C204B) E-3, Rev. 2, "HPCI Turb Exh Diaphram Hi Press" D. TASK STANDARD

1. Satisfactory task completion is indicated when the HPCI Turbine has been started, correctly placed in the CST-to-CST mode of operation, and then manually tripped due to receipt of Turbine Exhaust Diaphragm rupture alarm.

2. Estimated time to complete: 15 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to startup HPCI in the CST to CST mode using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Reactor is shutdown following an electrical transient.

2. RPV level is +20 inches and steady

3. The HPCI System is set up for operation in accordance with SO 23.1.A-2, "HPCI System Setup for Automatic or Manual Operation".

4. "B" loop of RHR is in the Torus Cooling mode in accordance with RRC 10.1-2, "RHR System Torus Cooling During a Plant Event".

5. SBGT is in service.

G. INITIATING CUE The Control Room Supervisor directs you to start up HPCI in the CST to CST Mode in accordance with RRC 23.1-2, "HPCI System Operation During a Plant Event" and lower reactor pressure to 500 psig.

PLOR353CA Rev 1 Page 3 of 8

H. PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD 1 Obtain a copy of procedure RRC 23.1-2, p A copy of procedure RRC 23.1-2 is "HPCI System Operation During a Plant obtained. Section D, HPCI System Startup Event". in "CST to CST" Mode, is selected.

2 Open M0-2-23-024, "Cond Tank Return". p M0-2-23-024 control switch is momentarily placed in the OPEN position at panel (Cue: Acknowledge control switch 20C004B.

operation.)

3 Verify M0-2-23-024, "Cond Tank Return" p M0-2-23-024 red light is verified ON at valve opened. panel 20C004B.

(Cue: M0-24 red light is ON, green light is OFF.)

4 Verify closed M0-2-23-019, "To Feed p M0-2-23-19 verified CLOSED at panel Line" 20C004B.

(Cue: M0-19 red light is OFF, green light is ON.)

5 Start the Gland Seal Condenser Vacuum p Gland Seal Condenser Vacuum Pump Pump 20K002. control switch is placed in the "START" position at panel 20C004B.

(Cue: Acknowledge control switch operation.)

6 Verify the Gland Seal Condenser Vacuum p 20K002 red light is verified ON at panel Pump 20K002 is running. 20C004B.

(Cue: 20K002 red light is ON and green light is OFF.)

7 Throttle open M0-2-23-021, "Full Flow p M0-2-23-021 control switch is momentarily Test" until the red "OPEN" indicating light placed in the OPEN position.

has been lit for 3 to 4 seconds. Approximately 3 to 4 seconds after the red light lit, the red stop travel pushbutton is (Cue: M0-21 green light is ON, red light depressed at the 20C004B panel.

has been ON for 3 to 4 seconds.)

PLOR353CA Rev 1 Page 4 of 8

STEP NO STEP ACT STANDARD

8 Simultaneously START the Auxiliary Oil p Auxiliary oil pump control switch is placed Pump, 20P026 and OPEN M0-2-23-014 in the START position while "Supply" valve. simultaneously placing M0-2-23-014 "Supply" control switch momentarily in the (Cue: Acknowledge control switch "OPEN" position at panel 20C004B.

operation.)

9 Verify the Auxiliary Oil pump started. p Auxiliary Oil Pump red light is verified ON at panel 20C004B.

(Cue: Auxiliary Oil pump red light is ON, green light is OFF and annunciator 222 D-5 is alarming.)

10 Verify M0-2-23-014, "Supply" valve p M0-2-23-14 red light verified ON and HPCI opened. speed, discharge pressure, and flow are verified at panel 20C004B. HPCI Aux Oil (Cue: M0-14 red light is ON, green light is Pump is verified to have turned itself OFF OFF, HPCI discharge pressure, flow, as the Attached Oil Pump ramps up.

speed and exhaust pressure rise, Aux. oil pump red light is OFF and green light is ON.)

11 Verify pump flow rate of 5000 gpm on p FIC-2-23-108 setpoint is adjusted to obtain Fl-2-23-108. 5000 gpm on Fl-2-23-108 at panel 20C004B.

(Cue: Fl-2-23-108 indicates 5000 gpm.)

12 Throttle M0-2-23-021 and adjust FIC p M0-2-23-021 control switch is closed to 23-108 to obtain desired system pressure raise pressure, opened to lower pressure and flow. and red stop travel pushbutton is depressed to obtain a pressure of 200 psig (Cue: Acknowledge control switch below reactor pressure on Pl-2-23-109 operation. Pl-2-23-109 reads about 800 while maintaining turbine speed greater psig, Fl-2-23-108 reads 5000 gpm.) than 2200 rpm at SPl-4505 at panel 20C004B.

FIC-2-23-108 set point control knob is adjusted clockwise or counter-clockwise as needed. This action should not be required as long as the FIC is functioning correctly in automatic.

PLOR353CA Rev 1 Page 5 of 8

STEP NO STEP ACT STANDARD

- - - NOTE: ****

The Alternate Path portion of this JPM begins with the next step.

13 Recognize HPCI Exhaust Diaphragm P Recognize annunciator 221 E-3 "HPCI rupture condition. TURBINE EXH DIAPHRAM HI PRESS" is flashing and consult Alarm Response Card (Cue: Annunciator 221 E-3 is alarming.) 221 E-3. Recognize that the condition requires HPCI turbine trip as Adequate Core Cooling is NOT in jeopardy.

- - - NOTE****

The following steps are scripted from Rapid Response procedure RRC 23.1-2, Section F, HPCI Shutdown with NO initiation Signal Present.

Based on direction from Alarm Response Card 221 E-3 "HPCI TURBINE EXH DIAPHRAM HI PRESS" the Examinee may go directly to steps 17 and 20 to immediately trip the HPCI turbine and close the steam supply valve M0-2-23-014.

14 Verify HPCI initiation pushbutton (23A- P HPCI Manual Initiation (23A-S105) collar is S105) collar is in "DISARM". verified in the "DISARM"

[counterclockwise] position on 20C004B or (Cue: HPCI initiation collar is in "DISARM" "HPCI IN TEST/ARMED" annunciator 221 and annunciator 221 B-2 is not lit.) B-2 is clear.

15 Verify the Aux oil pump (20P026) control P Aux oil pump (20P026) control switch is switch is in "START". verified in "START" at panel 20C004B.

(Cue: Aux oil pump control switch (20P026) is in "START".)

16 Verify Gland Seal Condenser Vacuum P Gland Seal Condenser Vacuum Pump Pump (20K002) is in "START". (20K002) control switch is verified in "START" at panel 20C004B.

(Cue: Vacuum pump switch is in "Start",

red light is on and green light is off.)

17 Depress and hold the HPCI System P Remote trip pushbutton is DEPRESSED "Remote Trip" pushbutton. AND HELD in until M0-2-23-014 indicates fully closed at panel 20C004B.

(Cue: Turbine speed drops and annunciator 221 B-1 is alarming "HPCI TURB TRIP".)

PLOR353CA Rev 1 Page 6 of 8

STEP NO STEP ACT STANDARD 18 Verify annunciator 221 B-1 "HPCI TURB p Recognizes that annunciator 221 B-1 TRIP" is in alarm. "HPCI TURB TRIP" is flashing and acknowledges alarm.

(Cue: Annunciator 221 B-1 "HPCI TURB TRIP" is alarminq.)

19 Verify HPCI Aux oil pump starts as turbine p HPCI Aux oil pump (20P026) red light is slows down (1200-1500 RPM). verified ON at panel 20C004B and/or "HPCI AUX OIL PUMP RUNNING" (Cue: HPCI Aux oil pump red light is lit annunciator 222 D-5 is verified lit.

and green light is off. Annunciator 222 D-5 is flashing.)

20 Close M0-2-23-014, "Supply" valve OR p M0-2-23-014 control switch is momentarily WAIT for the turbine shaft to stop rotating placed in the CLOSE position within 5 as indicated by SPl-4505 on Panel minutes of receiving annunciator 221 B-3 20C004B (or local visual indication) and at panel 20C004B.

place the Aux. Oil Pump control switch to the Pull-to-Lock (PTL) position. The operator may follow the ARC 221 E-3 guidance which directs the operator to trip (Cue: Acknowledge control switch the HPCI turbine. The operator may elect operation.) to place the Aux. Oil Pump control switch to PTL after the turbine shaft stops rolling and before releasing the trip pushbutton. If this option is chosen THEN steps 21-27 can be marked as "N/A".

21 Verify M0-2-23-014, "Supply" valve p M0-2-23-014 green light verified ON at closed. panel 20C004B.

(Cue: M0-14 green light is on red light is off. HPCI speed, discharge pressure, and exhaust pressure have dropped to 0.)

22 Verify closed the M0-2-23-019, "To Feed p M0-2-23-019 green light verified ON and Line" valve. red light verified OFF on panel 20C004B.

(Cue: M0-2-23-019 green light ON, red liQht OFF.)

23 When M0-2-23-14 is fully closed, release p Remote trip pushbutton is RELEASED at the HPCI system "Remote Trip" panel 20C004B.

pushbutton.

(Cue: Acknowledge pushbutton is released.)

PLOR353CA Rev 1 Page 7 of 8

STEP NO STEP ACT STANDARD 24 Depress 23A-S21 "Initiation Signal" reset p 23A-S21 "Initiation Signal" reset push-push-button. button is depressed on panel 20C004B.

(Cue: Acknowledge Control Switch Operator.)

25 Direct Equipment Operator to verify HPCI p Equipment Operator dispatched Turbine Shaft is stopped (Cue: Acknowledge direction, inform Candidate that the HPCI turbine shaft has stopped rotating) 26 Place the Aux oil pump (20P026) control p Aux oil pump (20P026) control switch is switch to "STOP" and verify it returns to placed in "STOP" and then verified to "AUTO". return to "AUTO" position at panel 20C004B.

(Cue: Aux oil pump control switch (20P026) is in "AUTO".)

27 Verify HPCI system flow controller FIC p FIC-2-23-108 should already be in "AUTO"23-108 is in "AUTO" and set for 5000 gpm. with the set point at 5000 gpm.

(Cue: FIC-2-23-108 is in "AUTO" and the set point indicates 5000 gpm.)

28 Inform Control Room Supervisor of p Exhaust Diaphragm rupture indications Exhaust Diaphragm rupture indications and HPCI Turbine trip reported.

and HPCI Turbine trip.

NOTE: This step may be performed at any (Cue: Control Room Supervisor point post-Alarm condition.

acknowledges report.)

29 As an evaluator ensure that you have p Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When the HPCI Turbine has been tripped due to Exhaust Diaphragm rupture indications, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

PLOR353CA Rev 1 Page 8 of 8

TASK CONDITIONS/PREREQUISITES

1. Reactor is shutdown following an electrical transient.

2. RPV level is +20 inches and steady

3. The HPCI System is set up for operation in accordance with SO 23.1.A-2, "HPCI System Setup for Automatic or Manual Operation".

4. "B" loop of RHR is in the Torus Cooling mode in accordance with RRC 10.1-2, "RHR System Torus Cooling During a Plant Event".

5. SBGT is in service.

INITIATING CUE The Control Room Supervisor directs you to start up HPCI in the CST to CST Mode in accordance with RRC 23.1-2, "HPCI System Operation During a Plant Event" and lower reactor pressure to 500 ps1g.

SIMULATOR JPM INITIAL CONDITIONS JPM NO: PLOR-353CA I TITLE: I Start HPCI in CST to CST Mode - Alternate Path I DATE: I 2/24/15 SIMULATOR INITIAL CONDITIONS IC NO: 14 TITLE: 100% Power, 60°F River Temp POWER: 100%

PRESSURE: 1042 psia MALFUNCTION LIST (MFSI)

MALF PAGE FINAL DELAY RAMP ACTIVE REMOTE EVENT No. No. TITLE SEV. TIME TIME TIME SWITCH AC DA NOTE 1/0 OVERRIDE LIST (IOSI)

PAGE VALUE/ EVENT TIME PLANT ID No. TITLE STATUS AC DA DELAY NOTE AN02048E3 HPCI TURB EXH DIAPH HI ALARM_ON 2 1:00 PRESSURE AN021481 UNIT 2 RB HI RAD ALARM_ON 2 1:15 ZAORMARM_2 ARM CH.2 (TORUS ROOM) 1000 2 1: 15 ZLORMHl_2 ARM HI LIGHT ON 2 1: 15 REMOTE FUNCTIONS (RFI)

RF ID# I PAGE NO. I TITLE I VALUE/STATUS EVENT NOTE I I I SPECIAL NOTES

1. Consider performing the following:

a. Place the 'B' RHR loop in Torus Cooling.

b. Place SBGT in service per SO 9A.1.B.

2. Run APP JPM 353CA or enter the Event Trigger and the 1/0 Overrides listed below to bring in Hi Exhaust Pressure alarm and Rad Indications :

TRG E2 HPCl_FLOW_GE_4950 IOR AN02048E3 (E2 1:00 0) ALARM_ ON IOR AN021481 (E2 1:15 0) ALARM_ON IOR ZAORMARM_2 (E2 1: 15 0) 1000 IOR ZLORMHl_2 (E2 1: 15 0) ON

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

~ JPM D QUALIFICATION MANUAL D OJT MODULE PROGRAM: LICENSED OPERATOR TRAINING CODE#: PLOR-381CA COURSE: LICENSED OPERATOR REQUALIFICATION REV#:: 000 AUTHOR: R. J. Artus TYPIST: Mda TITLE: Manual Startup of LPCI for Injection (Alternate Path-RHR Injection Valve Trips on Thermal Overload)

APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: I I NAME: ISSUE DATE:

Last First M.I.

EMPLOYEE ID NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMS CODE:

LMS ENTRY:

Signature/Date PLOR381CA Rev 0 Page 1 of 6

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2320350401 / PLOR-381CA KIA: 203000.A4.02 RO: 4.1 SRO: 4.1 TASK DESCRIPTION: Take Actions for System I RHR Injection Valves Overcurrent Alarm A. NOTES TO EVALUATOR:

1. An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

c. Applicable JPM Work Practice Standards, TQ-JA-150-04 graded satisfactorily.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR381CA Rev 0 Page 2 of 6

B. TOOLS AND EQUIPMENT None C. REFERENCES

1. RRC 10.2-2, Rev. 3, "RHR System LPCI Manual Start During a Plant Event"

2. ARC-226 D-3, Rev. 0, "System II RHR Injection Valves Overcurrent" D. TASK STANDARD

1. Satisfactory task completion is indicated when both loops of LPCI are injecting into the RPV.

2. Estimated time to complete: 15 minutes E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to inject both loops of RHR into the RPV using RRC 10.2-2, "RHR System LPCI manual Start During a Plant Event".

F. TASK CONDITIONS/PREREQUISITES

1. A loss of high pressure feed has occurred.

2. Reactor conditions:

Reactor is shutdown

RPV level is -140 inches and down slow.

RPV Pressure is 300 psig.

G. INITIATING CUE The Control Room Supervisor directs you, the Unit Reactor Operator, to inject both loops of RHR into the RPV using RRC 10.2-2, "RHR System LPCI Manual Start During a Plant Event".

PLOR381CA Rev 0 Page 3 of 6

H. PERFORMANCE CHECKLIST STEP STEP ACT STANDARD NO 1 Obtain a copy of procedure RRC 10.2-2, p A copy of procedure RRC 10.2-2 is "RHR System LPCI Manual Start During a obtained.

Plant Event".

2 Open M0-2-10-154A, "RHR Loop A p The control switch for M0-2-10-154A is Outboard Discharge Valve". taken to the OPEN position for a count of three.

(Cue: Control switch for M0-2-10-154A is taken to the OPEN position.)

3 Verify open M0-2-10-154A, "RHR Loop A p Verify that the Red light is ON and that the Outboard Discharge Valve". green light is OFF.

(Cue: When the M0-154A control switch is taken to OPEN then report that the red light is on and green light is out.)

4 Verify open M0-2-10-1548, "RHR Loop B p Verify that the Red light is ON and that the Outboard Discharge Valve". green light is OFF.

(Cue: Report that the red light is on and green light is out.)

5 Start RHR pumps 2AP035 and 2BP035. p Control Switches for RHR pumps 2AP035 and 2BP035 are taken to the START (Cue: Control Switches for RHR pumps position.

2AP035 and 2BP035 are taken to the START position.)

6 Verify the A and B RHR pumps are p Monitor pump light indication, discharge running. pressure and pump amps.

(Cue: Red light is on and green light is off, discharge pressure is rising, pump amps rise and then return to normal)

7 Start RHR pumps 2CP035 and 2DP035. p Control Switches for RHR pumps 2CP035 and 2DP035 are taken to the START (Cue: Control Switches for RHR pumps position.

2CP035 and 2DP035 are taken to the START position.)

8 Verify the C and D RHR pumps are p Monitor pump light indication, discharge running. pressure and pump amps.

(Cue: Red light is on and green light is off, discharge pressure is rising, pump amps rise and then return to normal)

PLOR381CA Rev 0 Page 4 of 6

STEP STEP ACT STANDARD NO 9 Verify Reactor pressure is less than 450 p Monitor RPV pressure and determine that psig. RPV pressure is 300 psig.

(Cue: When the operator monitors RPV pressure, report that RPV pressure is 300 psig.)

10 Open M0-2-10-25A,"RHR Loop A p The control switch for M0-2-10-25A is Outboard Discharge Valve". taken to the OPEN position for a count of three.

(Cue: Control Switch for M0-25A is taken to the open position and spring returns to normal) 11 Verify open M0-2-10-25A, "RHR Loop A p Verify that the Red light is ON and that the Outboard Discharge Valve". green light is OFF.

(Cue: When the M0-25A control switch is taken to OPEN then report that the red light is on and green light is out.)

The Alternate Path portion of the JPM begins with the next step 12 Open M0-2-10-258. p The control switch for M0-2-10-258 is taken to the OPEN position for a count of (Cue: Control Switch for M0-258 is taken three.

to the open position and spring returns to normal) 13 Verify open M0-258, "RHR Loop 8 p Recognize that M0-2-10-258 did not Outboard Discharge Valve". open.

(Cue: When the M0-2-10-258 control switch is taken to OPEN then report that the red light is off the green light is on and alarm 226 D-3 alarms) 14 Recognize alarm 226 D-3, "System II RHR p The Operator recognizes alarm 226 D-3.

Injection Valves Overcurrent".

(Cue: Alarm 226 D-3 is received when M0-258 is taken to open.)

15 Obtain a copy of procedure ARC-226 D-3, p A copy of procedure ARC 226 D-3 is "System I RHR Injection Valves obtained.

Overcurrent".

PLOR381CA Rev 0 Page 5 of 6

STEP STEP ACT STANDARD NO 16 Notify the CRS that M0-2-10-258 did not p Notify the CRS that M0-2-10-258 did not open due to a thermal overload trip. open due to a thermal overload trip.

(Cue: Acknowledge the report from the RO. Repeat the initiating cue to the operator.)

17 Hold the M0-2-10-258 control switch to p The control switch for M0-2-10-258 is the OPEN position until M0-2-10-258 is held in the OPEN position until the valve is open. fully open.

(Cue: When the control switch for M0 10-258 is taken to the OPEN position report the Red light is on and discharge pressure is risinQ 18 Verify open M0-2-10-258, "RHR Loop 8 p Verify that the Red light is ON and that the Outboard Discharge Valve". green light is OFF.

(Cue: Report that the red light is on and green light is out.)

19 Notify Shift Management of completion of p Verbally report completion of assigned assigned task. task to Control Room Supervisor.

(Cue: Acknowledge report.)

20 As an evaluator, ensure that you have p Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When both loops of RHR are injecting into the RPV, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

PLOR381CA Rev 0 Page 6 of 6

TASK CONDITIONS/PREREQUISITES A loss of high pressure feed has occurred on Unit 2.

Reactor conditions:

Reactor is shutdown

RPV level is -140 inches and down slow.

RPV Pressure is 300 psig.

INITIATING CUE The Control Room Supervisor directs you, the Unit Reactor Operator, to inject both loops of RHR into the RPV using RRC 10.2-2, "RHR System LPCI manual Start During a Plant Event".

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

~ JPM D QUALIFICATION MANUAL D OJT MODULE PROGRAM: LICENSED OPERATOR TRAINING CODE#: PLOR-321CA COURSE:. LICENSED OPERATOR REQUALIFICATION REV#:: 005 AUTHOR: J. T. Hanley TYPIST: rja TITLE: DRYWELL VENTING VIA THE 2" VENT - ALTERNATE PATH APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: I I NAME: ISSUE DATE:

Last First M.I.

Employee ID NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMS CODE:

LMS ENTRY:

Signature/Date PLOR321CA Rev 5 Page 1 of 7

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2230020101 / PLOR-321CA KIA: 223001A2.07 URO: 4.2 SRO: 4.3 TASK DESCRIPTION: Drywell Venting via the 2" Vent - Alternate Path A. NOTES TO EVALUATOR:

1. An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JP Ms, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR321CA Rev 5 Page 2 of 7

8. TOOLS AND EQUIPMENT None C. REFERENCES

1. OT-101, Rev. 14 "High Drywell Pressure"

2. SO 78.3.A-2, Rev. 17, "Containment Atmosphere Pressure Control and Nitrogen Makeup"

3. ARC 003 D-2, Rev. 11, "Main Stack Radiation High" D. TASK STANDARD

1. Performance Location: Simulator

2. Satisfactory task completion is indicated when drywell venting via the 2" vents has been initiated, maximized, and terminated due to high radioactive release levels.

3. Estimated time to complete: 12 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to initiate drywell venting via the 2" vent using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Drywell pressure is 1 psig and going up slowly.

2. The CRS has entered OT-101, "High Drywell Pressure".

3. The primary containment has been inerted in accordance with SO 78.1.A-2, "Containment Atmosphere lnerting".

4. Drywell and Torus Hydrogen/ Oxygen Sampling system is in operation in accordance with SO 7J.1.A-2, "Drywell and Torus H2/02 Sampling System Startup and Normal Operation CAC Mode".

5. Drywell Ventilation System is in operation in accordance with SO 40C.1.A-2, "Drywell Ventilation System Startup and Normal Operations".

6. S8GT is currently operating on the 'A' Fan and the 'A' Train. The "8" S8GT train is available.

7. The Drywell Radiation Monitors are in service and being monitored by the STA.

8. The Main Stack Radiation Monitors are in service and being monitored by the STA.

PLOR321CA Rev 5 Page 3 of 7

9. Stack Dilution fans are in operation in accordance with SO 8.7.A, "Off-Gas Dilution Fan Operation".

10. Primary Containment Isolation System is reset in accordance with GP-88, "PCIS Isolation - Group II & Ill".

11. Management has determined that COL 78.3.A-2, "Containment Atmosphere Pressure Control and Nitrogen Makeup", is not required.

G. INITIATING CUE The Control Room Supervisor directs you to maximize venting the drywell via the 2" vents in accordance with OT-101, Step 3. 7 "High Drywell Pressure" to lower drywell pressure to 0.70 psig.

PLOR321CA Rev 5 Page 4 of 7

H. PERFORMANCE CHECKLIST STEP STEP ACT STANDARD NO 1 Obtain a copy of procedure OT-101, "High p A copy of procedure OT-101. "High Drywell Drywell Pressure" Pressure" is obtained.

2 Verify Drywell Radiation Monitor Reading is p Verify that Drywell Radiation Monitor reading, less than 10*1 µCi/cc. indicated on PR/RR-4048 at panel 20C003 is reading less than 10*1 µCi/cc I (Cue: PR/RR-2-02-3-4048 is reading 2.5 E-6

µCi/cc.)

3 Verify the "Main Stack Radiation High" alarm p Verify that the Main Stack Radiation High at Panel 003 D-2 is clear. alarm at Panel 003 D-2 is NOT in alarm.

(Cue: 003 D-2 is NOT in alarm.)

4 Obtain a copy of procedure SO 78.3.A-2. p A copy of procedure SO 78.3.A-2 is obtained.

5 Verify open A0-2509, "Drywell Vent lnbd 2" p A0-2509 red light is verified on.

Vent".

(Cue: A0-2509 red light is lit, green light is out.)

6 Open A0-2510, "Drywell Vent Outbd 2" p A0-2510 switch is taken to open.

Vent".

(Cue: Acknowledge switch operation.)

7 Verify A0-2510 is open. p The A0-2510 red light is verified ON.

(Cue: A0-2510 red light is lit, green light is out.)

8 Open CV-4957, "Drywell Bleed Flow", using p HCS-4957 is used to fully open CV-4957 to manual control HCS-4957 to set the desired maximize venting via the 2" vents.

flowrate.

(Cue: Acknowledge controller operation.

HCS-4957 is indicating full open)

- - Note***

If the examinee monitors drywell pressure on PR-2508, cue him that:

Drywell pressure is 0.95 psig and down slow.

After 2 minutes, update examinee that OW pressure is 0.90 psig, down slow.

PLOR321CA Rev 5 Page 5 of 7

STEP STEP ACT STANDARD NO 9 Inform Control Room Supervisor that Drywell p Drywell Venting is reported.

Venting is in progress.

(Cue: Control Room Supervisor acknowledges report.)

- - Notes***

Once drywell venting is in progress, PR/RR-2-02-3-4048 will slowly rise and 003 D-2 "Main Stack Radiation High" will alarm. Examinee may terminate Drywell venting by performing step 10 OR step 12 (or both).

The ALTERNATE PATH portion of this JPM begins with the next step.

1 O Terminate Drywell Venting by closing p Upon either Drywell Radiation Monitor A0-2510 on panel 20C484B. exceeding 1ON1 µC/cc, or receipt of annunciator 003 D-2, terminate Drywell (Cue: Acknowledge switch operation.) Venting per OT-101 by taking A0-2510 control switch to close.

11 Verify A0-2510 is closed. p The A0-2510 Green light is verified ON.

(Cue: A0-2510 green light is lit, red light is out.)

12 Terminate Drywell Venting by closing p HCS-4957 is used to close CV-4957 to CV-4957, "Drywell Bleed Flow", using manual terminate drywell venting via the 2" vents.

control HCS-4957.

(Cue: Acknowledge switch operation. HCS-4957 is indicating closed.)

13 Inform Control Room supervisor that Drywell p Drywell Venting termination is reported.

Venting has been terminated.

(Cue: Control Room supervisor acknowledges report.)

14 As an evaluator ensure that you have p Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE PLOR321 CA Rev 5 Page 6 of 7

When drywell venting via the 2" vents has been terminated, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

PLOR321CA Rev 5 Page 7 of 7

TASK CONDITIONS/PREREQUISITES

1. Drywell pressure is 1 psig and going up slowly.

2. The CRS has entered OT-101, "High Drywell Pressure".

3. The primary containment has been inerted in accordance with SO 78.1.A-2, "Containment Atmosphere lnerting".

4. Drywell and Torus Hydrogen/ Oxygen Sampling system is in operation in accordance with SO 7J.1.A-2, "Drywell and Torus H2/02 Sampling System Startup and Normal Operation CAC Mode".

5. Drywell Ventilation System is in operation in accordance with SO 40C.1.A-2, "Drywell Ventilation System Startup and Normal Operations".

6. S8GT is currently operating on the 'A' Fan and the 'A' Train. The "8" S8GT train is available.

7. The Drywell Radiation Monitors are in service and being monitored by the STA.

8. The Main Stack Radiation Monitors are in service and being monitored by the STA.

9. Stack Dilution fans are in operation in accordance with SO 8.7.A, "Off-Gas Dilution Fan Operation".

10. Primary Containment Isolation System is reset in accordance with GP-88, "PCIS Isolation - Group II & 111".

11. Management has determined that COL 78.3.A-2, "Containment Atmosphere Pressure Control and Nitrogen Makeup", is not required.

INITIATING CUE The Control Room Supervisor directs you to maximize venting the drywell via the 2" vents in accordance with OT-101, Step 3. 7 "High Drywell Pressure" to lower drywell pressure to 0.70 psig.

SIMULATOR JPM INITIAL CONDITIONS JPM NO: PLOR-321CA I TITLE: I Drywell Venting via the 2" Vent - Alternate Path I DATE: I 2/23/15 SIMULATOR INITIAL CONDITIONS IC NO: 14 TITLE: 100% Power, 60°F River POWER: 100%

PRESSURE: 1043 MALFUNCTION LIST (MFSI)

MALF PAGE FINAL DELAY RAMP ACTIV REMOTE EVENT E

No. No. TITLE SEV. TIME TIME TIME SWITCH AC DA NOTE MSS01 Steam Leakage 0.5 See Inside Primary special Containment notes below 1/0 OVERRIDE LIST (IOSI)

PAGE VALUE/ EVENT TIME PLANT ID No. TITLE STATUS AC DA DELAY NOTE ZAORMRR023404B OW Activity Meter (4048) .75 1 5 min. ramp AN0214D2 Stack Gas Hi Rad ALARM - 1 1 min. Alarm 003 ON D-2 ZAORM14RR1751A_ 1 Stack Gas Recorder AOs .55 1 1 min.

ZAORM14RR1751B_ 1 Stack Gas Recorder AOs .55 1 1 min.

REMOTE FUNCTIONS (RFI)

RF ID# PAGE NO. TITLE VALUE/STATUS EVENT NOTE SPECIAL NOTES

1. Any IC.

2. Remove drywell fans from service to raise drywell pressure to 1.0 psig.

3. Place 'A' SBGT filter and 'A' SBGT fan in-service per SO 9A.1. B.

4. Assign the following Event Trigger to E1: A02510_RED_LIGHT_ON (ZLOPC484BA02510_2==True)

5. Load overrides per list above.

6. Insert malfunction IMF MSS01 0.5 until drywell pressure is 1.0 psig, then reduce the value of MSS01 to 0.01.

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

~ JPM D QUALIFICATION MANUAL D OJT MODULE PROGRAM: LICENSED OPERATOR TRAINING CODE#: PLOR-373CA COURSE: LICENSED OPERATOR REQUALIFICATION REV#:: 001 AUTHOR: R. J. Artus TYPIST: mda TITLE: LOAD DIESEL GENERATOR TO 500 KW (ALTERNATE PATH DIFFERENTIAL/GROUND)

APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: I I NAME: ISSUE DATE:

Last First M.I.

EMPLOYEE ID NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMS CODE:

LMS ENTRY:

Signature/Date PLOR373CA Rev 1 Page 1 of 9

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2640630401 I PLOR-373CA KIA: 264000A4.04 RO: 3.7 SRO: 3.7 TASK DESCRIPTION: Take Actions for E-4 Diesel Generator Differential and Ground A. NOTES TO EVALUATOR:

1. An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph 0.2) is required.

c. Applicable JPM Work Practice Standards, TQ-JA-150-04 graded satisfactorily.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR373CA Rev 1 Page 2 of 9

B. TOOLS AND EQUIPMENT None C. REFERENCES

1. SO 52A.1.B Rev 51, "Diesel Generator Operations"

2. ARC 005 F-1 Rev 4, "Diesel Generator Differential and Ground" D. TASK STANDARD

1. Satisfactory task completion is indicated when the E-4 Diesel Generator is synchronized to the E-43 bus and then shutdown following receiving alarm 005 F-1 "Diesel Generator Differential and Ground".

2. Estimated time to complete: 10 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, synchronize the E-4 Diesel to the E-43 bus and pick up 500 KW for testing purpose using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. E-4 Diesel Generator has been "SLOW" started in accordance with Section 4.1 of SO 52A.1.B, "Diesel Generator Operations".

2. E-4 Diesel Generator is running at rated frequency and voltage.

3. E-43 Bus is being supplied by 2SUE.

4. The ESW system is supplying D/G cooling water.

G. INITIATING CUE The Control Room Supervisor directs you to synchronize the E-4 Diesel to the E-43 Bus and pick up 500 KW in accordance with Section 4.2 of SO 52A.1.B, "Diesel Generator Operations".

PLOR373CA Rev 1 Page 3 of 9

H. PERFORMANCE CHECKLIST STEP STEP ACT STANDARD NO 1 Obtain a copy of procedure SO 52A.1.B, p A copy of procedure SO 52A.1.B is "Diesel Generator Operations". obtained.

2 Verify the E-4 Diesel is running in p Verify the following (OOC026D panel):

accordance with Section 4.1 of SO --The E4 DIG "101-DG12" red "RUN" light 52A.1.B. is lit

--The E4 D/G is running at rated (Cue: E-4 diesel Generator is running frequency (58.8 -7 61.2 hz) as normally.) indicated on the E4 D/G "FREQ" meter.

--The E4 EOG is running at rated voltage (4.16 -7 4.40 KV) as indicated on the E4 DIG "V" meter (and/or PMS computer E038).

OR Check JPM Task Conditions/Prerequisites

3 Place the E43 Breaker "BKR SYNC" p Synchronizing Switch Handle is inserted switch in the "ON" position. into the "E43 BKR SYNC" Switch. The "E43 BKR SYNC" Switch handle is then (Cue: The syncroscope is rotating.) rotated in the clockwise direction until the handle position indicates that the switch is in the "ON" position.

4 Operate the "GOVERNOR" control switch p Raise E4 D/G speed by momentarily for the E4 EOG to "RAISE" frequency to taking the E4 D/G "GOVERNOR" Control 0.5 Hz above the initial value. Switch "165-DG12" to "RAISE" at panel OOC026D. The E4 D/G "FREQ" meter (Cue: When the governor control switch is should change indication from -60 hz to taken to raise, the Diesel Generator -60.5 hz.

frequency rises to 60.5 hz.)

5 Operate the "GOVERNOR" control switch p Lower E4 DIG speed by momentarily for the E4 EOG to "LOWER" frequency to taking the E4 DIG "GOVERNOR" Control 0.5 Hz below the initial value. Switch "165-DG12" to "LOWER" at panel OOC026D. The E4 DIG "FREQ" meter (Cue: When the governor control switch is should change indication from -60.5 hz to taken to lower, the Diesel Generator -59.5 hz.

frequency rises to 59.5 hz.)

PLOR373CA Rev 1 Page 4 of 9

STEP STEP ACT STANDARD NO 6 Operate the "GOVERNOR" control switch p Raise E4 DIG speed by momentarily for the E4 EOG to "RAISE" frequency to taking the E4 DIG "GOVERNOR" Control return to initial value. Switch "165-DG12" to "RAISE" at panel OOC026D. The E4 DIG "FREQ" meter (Cue: When the governor control switch is should change indication from -59.5 hz to taken to raise, the Diesel Generator -60 hz.

frequency rises to 60 hz.)

7 Operate the "AUTO VOLT REG" control p Raise the E4 DIG output voltage by switch for the E4 EOG to "RAISE" voltage momentarily taking the E-4 DIG "AUTO to 50 volts above the initial value. VOLT REG" Control Switch "90-DG14" to "RAISE" at panel OOC026D. The voltage (Cue: When the voltage control switch is indicated on the E4 DIG "V" meter should taken to raise, the Diesel Generator change from -4.2 KV to -4.3 KV.

voltage rises to 4.25 KV.)

8 Operate the "AUTO VOLT REG" control p Lower the E4 DIG output voltage by switch for the E4 EOG to "LOWER" momentarily taking the E-4 DIG "AUTO voltage to 50 volts below the initial value. VOLT REG" Control Switch "90-DG14" to "LOWER" at panel OOC026D. The voltage (Cue: When the voltage control switch is indicated on the E4 DIG "V" meter should taken to lower, the Diesel Generator change from -4.3 KV to -4.1 KV.

voltage rises to 4.15 KV.)

9 Operate the "AUTO VOLT REG" control p Raise the E4 DIG output voltage by switch for the E4 EOG to "RAISE" voltage momentarily taking the E-4 DIG "AUTO to return to initial value. VOLT REG" Control Switch "90-DG14" to "RAISE" at panel OOC026D. The voltage (Cue: When the voltage control switch is indicated on the E4 DIG "V" meter should taken to raise, the Diesel Generator change from -4.1 KV to -4.2 KV.

voltage rises to 4.2 KV.)

10 Check both synchronizing lights for proper p Verify proper operation of the operation. synchronizing lights (at the OOC026C panel) as follows:

(Cue: Both lights "ON" when synchroscope -- Both lights "ON" when synchroscope is is at "Bottom Dead Center". at "Bottom Dead Center".

-- Both lights "OFF" when synchroscope is -- Both lights "OFF" when synchroscope is at "Top Dead Center".) at "Top Dead Center".

PLOR373CA Rev 1 Page 5 of 9

STEP STEP ACT STANDARD NO 11 Adjust diesel generator speed, using the p Raise or lower E4 D/G speed by "GOVERNOR" control switch for the E4 momentarily taking the "GOVERNOR" EOG, to make the synchroscope rotate control switch "165-DG12" to the "RAISE" 1 revolution/5 to 10 seconds in the "FAST" and/or "LOWER" position as appropriate direction. (at the OOC026D panel).

(Cue: Syncscope is rotating slow in the NOTE: The synchroscope must rotate fast direction.) 1 revolution/5 to 10 seconds in the "FAST" direction to satisfy this step. Use of a stopwatch, the digital control room clock, or a wristwatch are acceptable means of timing the action of the synchroscope.

- - Note***

The following step may be marked N/A if the INCOMING voltage is already slightly higher than the RUNNING voltage.

12 Adjust diesel generator "INCOMING" p Raise or lower the E4 DIG output voltage voltage so that it is slightly higher than by taking the E-4 DIG "AUTO VOLT REG" "RUNNING" bus voltage by using the Control Switch "90-DG14" to the "RAISE" "AUTO VOLT REG" control switch for the and/or "LOWER" position as appropriate E4 D/G. (at the OOC026D panel).

(Cue: Incoming voltage is 50 volts higher than running voltage.)

13 Verify the synchroscope is still rotating p Verify the synchroscope is rotating 1 revolution/5 to 10 seconds in the "FAST" 1 revolution/5 to 10 seconds in the "FAST" direction. direction (at the OOC026C panel).

(Cue: Syncscope is rotating slow in the NOTE: Use of a stopwatch, the digital fast direction.) control room clock, or a wristwatch are acceptable means of timing the action of the synchroscope.

PLOR373CA Rev 1 Page 6 of 9

STEP STEP ACT STANDARD NO

14 WHEN the diesel generator is p The E43 Breaker is closed by taking the synchronized with the 4KV emergency control switch "E43 BKR" momentarily to bus, THEN close the E43 Breaker. the "CLOSE" position when the following conditions are met:

(Cue: The red light is on and the green light is off for the E-43 breaker. The --Diesel generator "INCOMING" voltage syncscope has stopped rotating.) slightly higher than "RUNNING" bus voltage.

--Synchroscope rotating 1 revolution/ 5 to 10 seconds in the "FAST" direction.

--Synchroscope within 13 degrees of "Top Dead Center".

- - Note***

The following two steps may be marked N/A if no load or VAR adjustments are required.

15 Pickup 200 to 300 kW of load on the diesel p Raise E4 DIG load by momentarily taking generator by turning the E4 DIG the E4 DIG "GOVERNOR" control switch "GOVERNOR" control switch to "RAISE". 165-DG12 to "RAISE" at panel OOC026D as required to raise diesel loading as (Cue: When the governor control switch is indicated on the E4 DIG 'W' meter.

taken to raise, diesel generator load rises to 250 KW.) NOTE: This step must be performed immediately following the previous step.

NOTE: Loading the diesel generator shall proceed at a rate NOT to exceed 300 KW/min.

16 Ensure -100 KVAR on the EOG by turning p Verify 100 KVAR on the E4 DIG by the E4 DIG "AUTO VOLT REG" control momentarily taking the E-4 DIG AUTO switch to "RAISE" or "LOWER" as VOLT REG. Control Switch 90-DG14 to required. "RAISE" or "LOWER" at panel OOC026D as required to place -100 KVAR on the E4 (Cue: When the voltage control switch is DIG as indicated on the E4 DIG 'VAR' operated, diesel generator VARs rise to meter.

100 KVAR.)

NOTE: The KVAR value must not exceed 75% of the KW value, to assure that the generator 0.8 power factor will NOT be exceeded. For a DIG load of 300 KW, the allowable KVAR load is less than or equal to 225 KVAR.

PLOR373CA Rev 1 Page 7 of 9

STEP STEP ACT STANDARD NO

- - - NOTE:****

The Alternate Path portion of this JPM begins with the next step.

17 Recognize "E-4 Diesel Generator p Scan the alarm panel and acknowledge Differential and Ground" alarm. the "E-4 Diesel Generator Differential and Ground" alarm.

(Cue: Alarm 005 F-1 is in alarm) 18 Obtain a copy of ARC-005 F-1 "E-4 Diesel p A copy of ARC-005 F-1 "E-4 Diesel Generator Differential and Ground" alarm. Generator Differential and Ground" alarm is obtained.

NOTE It is acceptable for the Operator to trip the Diesel Generator then verify the 43 breaker is tripped. If the Diesel Gene~ator is tripped before the E-43 breaker then the E-43 breaker will automatically trip.

19 Trip the E-43 breaker p The control switch for the E-43 breaker is taken to the trip position.

(Cue: When the E-43 Breaker is taken to trip, green light above the E-43 breaker is lit and the red light is out.)

20 Trip the E-4 Diesel Generator. p The control switch for the E-4 Diesel generator is taken to trip position.

(Cue: When the Diesel generator is tripped, the green light is lit and the red light is out 21 Inform Control Room Supervisor that the p Control Room Supervisor is informed of E-4 diesel generator was tripped due to a the Diesel Generator differential and Differential and Ground alarm. ground condition.

(Cue: Control Room Supervisor acknow-ledges report.)

22 As an evaluator ensure that you have p Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

PLOR373CA Rev 1 Page 8 of 9

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When the E-4 diesel generator is tripped due to the differential and ground condition the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

PLOR373CA Rev 1 Page 9 of 9

TASK CONDITIONS/PREREQUISITES

1. E-4 Diesel Generator has been "SLOW" started in accordance with Section 4.1 of SO 52A.1.B, "Diesel Generator Operations".

2. E-4 Diesel Generator is running at rated frequency and voltage.

3. E-43 Bus is being supplied by 2SUE.

4. The ESW system is supplying D/G cooling water.

INITIATING CUE The Control Room Supervisor directs you to synchronize the E-4 Diesel to the E-43 Bus and pick up 500 KW in accordance with Section 4.2 of SO 52A.1.B, "Diesel Generator Operations".

SIMULATOR JPM INITIAL CONDITIONS JPM NO: PLOR-373CA TITLE: LOAD DIESEL GENERATOR TO 500 DATE: 3/17/15 KW (ALTERNATE PATH DIFFERENTIAL/GROUND)

SIMULATOR INITIAL CONDITIONS ICNO:

TITLE:

POWER:

PRESSURE:

MALFUNCTION LIST (MFSI)

MALF PAGE FINAL DELAY RAMP ACTIVE REMOTE EVENT No. No. TITLE SEV. TIME TIME TIME SWITCH AC DA NOTE 1/0 OVERRIDE LIST (IOSI)

PAGE VALUE/ EVENT TIME PLANT ID No. TITLE STATUS AC DA DELAY NOTE AN0226DF1 E-4 Diesel Gen Diff and Ground ALARM-ON AN0226DB4 E-43Bus Diff or Overcurrent ALARM -

Relays ON REMOTE FUNCTIONS (RFI)

RF ID# I PAGE NO. TITLE I VALUE/STATUS I EVENT I NOTE I I I I SPECIAL NOTES

1. Ensure 2SU XFMR (OOX003) is supplying the 2SUE Bus.

2. Manually start E-4 DIG by simultaneously placing the START MODE switch to "MAN" and the START-STOP switch to "START".

3. After 3.5 minutes, perform the following:

Shutdown the "B" ESW pump .

Acknowledge and reset annunciators .

4. Begin the JPM.

5. When the examinee has raised load on the E-4 Diesel Generator, THEN enter 1/0 Overrides

IOR AN0226DF1 ALARM_ON "E-4 Diesel Gen Diff and Ground",

IOR AN0226D84 ALARM_ON "E-43 Bus Diff or Overcurrent Relays"

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

~ JPM D QUALIFICATION MANUAL D OJT MODULE PROGRAM: LICENSED OPERATOR TRAINING CODE#: PLOR-366C COURSE: LICENSED OPERATOR REQUALIFICATION REV#:: 001 AUTHOR: J. E. McClintock TYPIST: mda TITLE: ROD WORTH MINIMIZER SYSTEM INITIALIZATION APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: I I NAME: ISSUE DATE:

Last First M.I.

Employee ID NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMS CODE:

LMS ENTRY:

Signature/Date PLOR366C Rev 11 Page 1 of 6

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2010010101 I PLOR-366C KIA: 201006A3.01 URO: 3.2 SRO: 3.1 TASK DESCRIPTION: INITIALIZE THE RWM A. NOTES TO EVALUATOR:

1. An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR366C Rev 11 Page 2 of 6

B. TOOLS AND EQUIPMENT Ensure that all RWM alarm messages are cleared on the RWM screen prior to JPM starting C. REFERENCES SO 62A.1.A-2, Rev 10, "Rod Worth Minimizer System Initialization" D. TASK STANDARD

1. Satisfactory task completion is indicated when:

a. The Rod Worth Minimizer has been initialized and a system diagnostic completed in accordance with SO 62A.1.A-2

b. Allotted time to complete: 12 minutes (A.5) Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to initialize the RWM. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Unit 2 is shutdown with all control rods inserted.

2. There are no substitute rod positions or inoperable rod position indications on Unit 2

3. The RWM is energized G. INITIATING CUE(S)

The Shift Supervisor directs you, the unit 2 Reactor Operator, to initialize the RWM, using SO 62A.1.A-2.

PLOR366C Rev 11 Page 3 of 6

H. PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD 1 Obtain a copy of procedure p A copy of procedure SO 62A.1.A-2 is obtained.

SO 62A.1.A-2, "Rod Worth Minimizer System Initialization".

2 Notify the RO that alarm 211 F-5 will p Expected alarm communication made to the annunciate unit RO.

(Cue: Acknowledge report)

3 Initiate the RWM System Initialization p The "System Initialize" pushbutton (located by pressing and momentarily holding in beneath the RWM monitor) is PRESSED and the System Initialization" pushbutton. momentarily HELD until the initialization commences.

(Cue: The "System Initialize" pushbutton "clicks" when depressed and momentarily back lights RED) 4 Monitor the initialization routine for the p The RWM screen and pushbuttons are "RWM INOP" indicator to CLEAR monitored during the initialization routine and within 2 minutes. timed to determine when the RWM INOP indicator clears.

(Cue: Acknowledge monitoring, RWM INOP indicator clears in one minute) 5 Press "FULLCORE" p The RWM touch screen "FULLCORE" button is identified and pressed.

(Cue: The FULLCORE screen is displayed.)

6 Verify there are not rod position p The operator verifies that no rod positions indicators indicating "-99". indicate "-99" by reviewing the rod positions.

(Cue: No rod positions indicate "-99".)

7 Select the "RWM MAIN" screen by p The RWM touch screen "RWM Main" button is pressing the touch screen "RWM identified and pressed.

Main" button.

(Cue: The RWM Main screen is displayed.)

PLOR366C Rev 11 Page 4 of 6

8 Verify the RWM has latched to a rod p The operator verifies that the RWM has group appropriate for current plant latched to the appropriate rod group by conditions. monitoring rod position and comparing that to the RWM.

(Cue: The RWM is latched to the correct rod group.)

9 Acknowledge all RWM messages p The RWM touch screen is used to select and acknowledge all of the RWM messages one at (Cue: the RWM messages are a time OR by double tapping "acknowledge" selected and acknowledged) 10 Notify the RO that alarm 211 F-5 will p Expected alarm communication made to the annunciate unit RO.

(Cue: Acknowledge report)

11 Initiate the RWM System Diagnostic p The "System Diagnostic" pushbutton (located routine by pressing and momentarily beneath the RWM monitor) is PRESSED and holding in the "System Diagnostic" momentarily HELD until the diagnostic routine pushbutton. commences.

(Cue: the "System Diagnostic" pushbutton "clicks" when depressed and back lights RED) 12 Verify "System Diagnostic" pushbutton p The "System Diagnostic" pushbutton is remains lit after being released. observed after being released to determine if the back light remains lit after the pushbutton is (Cue: "System Diagnostic" pushbutton released.

is lit.)

13 Verify the "Insert Block" and "Withdraw p The "Insert Block" and "Withdraw Block" Block" indicator lights under the RWM indicator lights are observed to determine if the console go ON and then OFF. light and then extinguish.

(Cue: "Insert Block" and "Withdraw Block" lights go ON and then OFF) 14 Verify that the RWM insert p The RWM insert block/insert permissive block/permissive indication cycles indication on the RWM screen is observed to between "Insert Block" and "Insert verify that the indication cycles between "Insert Permissive" Block" and "Insert Permissive" (Cue: Indication on the RWM console cycles between "Insert Block" and "Insert Permissive")

PLOR366C Rev 11 Page 5 of 6

15 Verify that the RWM withdraw p The RWM withdraw block/withdraw permissive block/permissive indication cycles indication on the RWM screen is observed to between "Withdraw Block" and verify that the indication cycles between "Withdraw Permissive" "Withdraw Block" and "Withdraw Permissive" (Cue: Indication on the RWM console cycles between "Withdraw Block" and "Withdraw Permissive")

16 Terminate the RWM System p The "System Diagnostic" pushbutton (located Diagnostic routine by pressing and beneath the RWM monitor) is PRESSED and momentarily holding in the System momentarily HELD Diagnostic" pushbutton.

(Cue: the "System Diagnostic" pushbutton "clicks" when depressed and back lights extinguish) 17 Verify "System Diagnostic" pushbutton p The "System Diagnostic" pushbutton is light goes OFF after being released. observed after being released to determine if the back light goes OFF after the pushbutton is (Cue: "System Diagnostic" pushbutton released.

light is OFF) 18 Inform Shift Supervisor of task p Task completion reported.

completion.

(Cue: Shift Supervisor acknowledges report.)

19 As an evaluator, ensure that you have p Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When the RWM has been successfully initialized, the Shift Supervisor should be informed.

The evaluator will then terminate the exercise.

PLOR366C Rev 11 Page 6 of 6

TASK CONDITIONS/PREREQUISITES

1. Unit 2 is shutdown with all control rods inserted.

2. There are no substitute rod positions or inoperable rod position indications on Unit 2

3. The RWM is energized INITIATING CUE(S)

The Shift Supervisor directs you, the unit 2 Reactor Operator, to initialize the RWM, using SO 62A.1.A-2.

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

~ JPM D QUALIFICATION MANUAL D OJT MODULE PROGRAM: LICENSED OPERATOR TRAINING CODE#: PLOR-270C COURSE: LICENSED OPERATOR REQUALIFICATION REV#: 003 AUTHOR: J. A. Verbillis TYPIST: Rja TITLE: ECW System Makeup to Tower Using a HPSW Pump APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: I I NAME: ISSUE DATE:

Last First M.I.

EMPLOYEE ID NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMS CODE:

LMS ENTRY:

Signature/Date PLOR270C Rev 33 Page 1 of 9

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2770040101 I PLOR-270C KIA: 400000 A4.01 URO: 3.1 SRO: 3.0 TASK DESCRIPTION: ECW System Makeup to Tower using a HPSW Pump A. NOTES TO EVALUATOR:

1. An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JP Ms, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR270C Rev 33 Page 2 of 9

B. TOOLS AND EQUIPMENT None C. REFERENCES

1. SO 48.7.A Rev 008, "Emergency Cooling Water System Makeup To Tower Using A High Pressure Service Water Pump"

2. SO 32.1.A-2 Rev 019, "High Pressure Service Water System Startup And Normal Operations"

3. SO 32.2.A-2 Rev 011, "High Pressure Service Water System Shutdown" D. TASK STANDARD

1. Satisfactory task completion is indicated when:

Emergency Cooling Tower level is at or about 18 Ft 3 In, and Emergency Service Water is returned to a standby lineup.

2. Estimated time to complete: 15 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to makeup to the Emergency Cooling Tower with the High Pressure Service Water system using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Emergency Cooling Water tower level is 17 ft.

2. All 4 KV busses are receiving power from the off-site startup sources.

3. Power available to the HPSW System per SO 54 and SO 56E.

4. The HPSW System is lined up for normal operation in accordance with COL 32.1.A-2 "High Pressure Service Water System" and SO 32.1.A-2 "High Pressure Service Water System Startup And Normal Operations"

5. Emergency Cooling Water (ECW) System is lined for normal standby operation in accordance with COL 48.1.A, "Emergency Cooling Water System (Units 2 and 3)".

6. High Pressure Service Water Radiation Monitoring System is lined up for normal operation in accordance with SO 63H.1.A-2, High Pressure Service Water Radiation Monitoring System Startup and Normal Operations.

PLOR270C Rev 33 Page 3 of 9

7. Outside air temperature is 50°F.

8. One HPSW System has been declared INOPERABLE and appropriate TSA entries have been made per SO 48.7.A Precaution 3.1.

G. INITIATING CUE:

The Control Room Supervisor directs you to makeup to the Emergency Cooling Tower to a level of 18 ft 3 in, then restore to a normal lineup, using the "2A" HPSW Pump I Heat Exchanger IAW SO 48.7.A "Emergency Cooling Water System Makeup To Tower Using A High Pressure Service Water Pump" PLOR270C Rev 33 Page 4 of 9

H. PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD 1 Obtain a copy of procedure SO 48.7.A, p Procedure SO 48.7.A obtained.

"Emergency Cooling Water System Makeup To Tower Using A High Pressure Service Water Pump".

2 Obtain a copy of SO 32.1.A-2, "High p Procedure SO 32.1.A-2 is obtained Pressure Service Water System Startup And Normal Operations", for starting the HPSW pump.

3 Direct Equipment Operator to verify "A" p EO directed to verify Oil Level HPSW Pump motor oil level at STAND STILL level (Cue: Report as EO that "A" HPSW Pump motor oil level at STAND STILL level) 4 Direct Equipment Operator to verify Area p EO directed to verify Fan alignment Ventilation Fans are aligned as follows:

HPSW + ESW Pump Room Supply Fan 2BV060 should be in "AUTO" AND 2AV060 should be in "AUTO STBY" on Panel 20C139.

HPSW + ESW Pump Room Exhaust Fans 2AV083 AND 2BV083 should be in "AUTO" on Panel 20C139.

(Cue: Report as EO that fans aligned as above) 5 Notify Chemistry that the "A" RHR Heat p Chemistry notified Exchanger will be placed in service and appropriate samples are required (Cue: As Chemistry, acknowledge the report) 6 Monitor "A" HPSW motor bearing p PMS used for bearing temperature temperatures on PMS monitoring PLOR270C Rev 33 Page 5 of 9

STEP NO STEP ACT STANDARD

7 Open MO 2 10 089A HPSW Hx Out p Correct valve opened (Cue: Red Light On, Green Light Off

8 Start the "A" HPSW Pump. p "A" HPSW pump control switch (Cue: Acknowledge control switch manipulated.

operation.)

9 Verify "A" HPSW Pump operating as p HPSW pump parameters verified to be in expected. expected range.

(Cue: Red Light On, Pump amps initially peg high then settle at about 110 amps, discharge pressure is 270 psig.)

10 Throttle MO 2 10 089A to establish 3300 p System Flow verified in band provided in to 5300 gpm flow on Fl 2 10 132A on SO.

Panel 20C003.

(Cue: System Flow is 4500 gpm) 11 Direct Equipment Operator to perform SO p EO directed to perform routine inspection.

32.8.A 2, "High Pressure Service Water Candidate should NOT wait for EO report System Routine Inspection". of completion.

(Cue: EO acknowledges.)

12 Open MO 2 32 2803, "Unit 2 HPSW Disch p At Panel OOC 123 (MCR Emergency to Clg Tower" Cooling Tower Panel), candidate opens (Cue: Red light ON, Green light OFF) MO 2803, "Unit 2 HPSW Disch to Clg Tower" 13 Verify TSA log entries are completed for p Candidate acknowledges requirement for one HPSW subsystem inoperable. TSA log entry (Cue: TSA log entry will be made by Supervisor)

PLOR270C Rev 33 Page 6 of 9

STEP NO STEP ACT STANDARD

- - Note***

The following step will need to be coordinated with the Simulator Operator.

14 Close breaker 5442 at E234-D-A "U/2 p Direct an Equipment Operator to close HPSW Return to Discharge Pond MO- breaker 5442 at E234-D-A "U/2 HPSW 2486". Return to Discharge Pond M0-2486".

{Cue: When requested inform the operator that breaker 5442 for M0-2486 is closed.)

15 Close M0-2-32-2486, "Unit 2 HPSW p At Panel OOC123 (MCR Emergency Disch to Pond" Cooling Tower Panel), candidate closes (Cue: Red light OFF, Green light ON) M0-2486, "Unit 2 HPSW Disch to Pond"

- - NOTE***

In the following step, ECT level rise, as indicated on Ll-0503, WILL BE TIME COMPRESSED.

16 Monitor ECT reservoir level. p Observe level indicator Ll-0503, "Clg Twr" on Panel OOC123.

(Cue: ECT reservoir level is slowly rising.)

(Cue: Inform candidate that ECT level is now 18 feet, 3 inches.)

17 Obtain a copy of SO 32.2.A, "High p A copy of SO 32.2.A is obtained Pressure Service Water System Shutdown", for shutting down the HPSW pump

18 Shutdown the running HPSW pump. p Running HPSW Pump control switch taken to OFF.

(Cue: Acknowledge switch operation.)

19 Verify "A" HPSW Pump shutdown as p HPSW pump parameters verified to be as expected. expected for shutdown pump.

(Cue: Red light OFF, Green light ON, Pump amps 0, discharge pressure is 0 psig.)

PLOR270C Rev 33 Page 7 of 9

STEP NO STEP ACT STANDARD 20 Close M0-2-10-089A "HPSW Hx Out" p Correct valve closed (Cue: Red light OFF, Green light ON) 21 Direct Equipment Operator to verify CHK- p Check Valve verified closed 2-32-502A "HPSW 2A P042 Discharge Check Valve" is closed (Cue: As Equipment Operator, report that CHK-2-32-502A is CLOSED) 22 Direct Equipment Operator to verify Area p EO directed to verify Fan alignment Ventilation Fans are aligned as follows:

HPSW + ESW Pump Room Supply Fan 2BV060 should be in "AUTO" AND 2AV060 should be in "AUTO STBY" on Panel 20C139.

HPSW + ESW Pump Room Exhaust Fans 2AV083 AND 2BV083 should be in "AUTO" on Panel 20C139.

(Cue: Report as EO that fans aligned as above) 23 Open MO 2 32 2486, "Unit 2 HPSW Disch p At Panel OOC 123 (MCR Emergency to Pond" Cooling Tower Panel), candidate opens (Cue: Red light ON, Green light OFF) MO 2486, "Unit 2 HPSW Disch to Pond" 24 EXIT TSA one HPSW subsystem p Candidate acknowledges requirement for inoperable. TSA status change (Cue: TSA status entry will be made by Supervisor) 25 Close MO 2 32 2803, "Unit 2 HPSW Disch p At Panel OOC 123 (MCR Emergency to Clg Tower" Cooling Tower Panel), candidate closes (Cue: Red light OFF, Green light ON) MO 2803, "Unit 2 HPSW Disch to Clg Tower" PLOR270C Rev 33 Page 8 of 9

STEP NO STEP ACT STANDARD

- - Note***

The following step will need to be coordinated with the Simulator Operator.

26 Open breaker 5442 at E234-D-A "U/2 p Direct an Equipment Operator to open HPSW Return to Discharge Pond MO- breaker 5442 at E234-D-A "U/2 HPSW 2486". Return to Discharge Pond M0-2486".

(Cue: When directed, inform the operator that breaker 5442 at E234-D-A "U/2 HPSW Return to Discharge Pond M0-2486" is open.)

27 Inform Control Room Supervisor of task p Task completion reported.

completion.

(Cue: Control Room Supervisor acknowledges report.)

28 As an evaluator ensure that you have p Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When the lineup for making up to the Emergency Cooling Tower is secured, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

PLOR270C Rev 33 Page 9 of 9

TASK CONDITIONS/PREREQUISITES

1. Emergency Cooling Water tower level is 17 ft.

2. All 4 KV busses are receiving power from off-site startup sources.

3. Power available to the HPSW System per SO 54 and SO 56E.

4. The HPSW System is lined up for normal operation in accordance with COL 32.1.A-2 "High Pressure Service Water System" and SO 32.1.A-2 "High Pressure Service Water System Startup And Normal Operations"

5. Emergency Cooling Water (ECW) System is lined for normal standby operation in accordance with COL 48.1.A, "Emergency Cooling Water System (Units 2 and 3)".

6. High Pressure Service Water Radiation Monitoring System is lined up for normal operation in accordance with SO 63H.1.A-2, High Pressure Service Water Radiation Monitoring System Startup and Normal Operations.

7. Outside air temperature is 50°F.

8. One HPSW System has been declared INOPERABLE and appropriate TSA entries have been made per SO 48. 7.A Precaution 3.1.

INITIATING CUE The Control Room Supervisor directs you to makeup to the Emergency Cooling Tower to a level of 18 ft 3 in, then restore to a normal lineup, using the "2A" HPSW Pump I Heat Exchanger IAW SO 48.7.A "Emergency Cooling Water System Makeup To Tower Using A High Pressure Service Water Pump"

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

~ JPM D QUALIFICATION MANUAL D OJT MODULE PROGRAM: LICENSED OPERATOR TRAINING CODE#: PLOR-018C COURSE: LICENSED OPERATOR REQUALIFICATION REV#:: 014 AUTHOR: J. R. Felice TYPIST: mda TITLE: MANUALLY PLACE SBGT ON EQUIPMENT CELL EXHAUST APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: I I NAME: ISSUE DATE:

Last First M.I.

EMPLOYEE l.D. NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMS CODE:

LMS ENTRY:

Signature/Date PLOR018C Rev 14 Page 1 of 8

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2610070101 I PLOR-018C KIA: 295017AA1 .09 RO: 3.6 SRO: 3.8 TASK DESCRIPTION: Manually Place SBGT on Equipment Cell Exhaust A. NOTES TO EVALUATOR:

1. An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR018C Rev 14 Page 2 of 8

B. TOOLS AND EQUIPMENT None C. REFERENCES

1. Procedure SO 9A.7.G Rev. 13, "SBGT Manual Startup on Equipment Cell Exhaust" (R)

2. ST-0-09A-500-2 Rev. 5, "SBGT Filter Train Operation Log" (A)

D. TASK STANDARD

1. Satisfactory task completion is indicated when SBGT operating on Equipment Cell Exhaust.

2. Estimated time to complete: 9 minutes (A.5) Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to place SBGT on Equipment Cell Exhaust using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Standby Gas Treatment System lined up for automatic operation per SO 9A.1.A, "Standby Gas Treatment System Lineup for Automatic Operation"

2. Operator stationed at Reactor Building Vent Panel 20C132.

3. Standby Gas Treatment Filter Train "A" has the least amount of run-hours.

G. INITIATING CUE The Control Room Supervisor directs you to place SBGT on Equipment Cell Exhaust using SO 9A.7.G, "Standby Gas Treatment System Manual Startup on Equipment Cell Exhaust".

PLOR018C Rev 14 Page 3 of 8

H. PERFORMANCE CHECKLIST STEP STEP ACT STANDARD NO 1 Obtain a copy of procedure SO 9A.7.G. p A copy of procedure SO 9A.7.G is obtained.

2 p Health Physics notified that SBGT is to Notify Health Physics that SBGT is to be started on Unit 2 Equipment Cell be started on Unit 2 Equipment Cell Exhaust. Exhaust.

(Cue: Health Physics acknowledges notification.)

3 Open P0-20465, Exh To SBGT Equip p P0-20465 control switch placed in the Cell Damper. OPEN position at panel 20C012.

(Cue: Acknowledge control switch operation.)

4 p P0-20465 red light verified ON at panel Verify P0-20465, Exh To SBGT Equip Cell Damper is open. 20C012.

(Cue: P0-20465 red light is on, green light is off.)

5 Open A0-20469-1, SBGT OW Rx Bldg p A0-20469-1 control switch placed in the Exh Damper. OPEN position at panel 20C012.

(Cue: Acknowledge control switch operation.)

(Evaluator Note: This step is critical IF A0-20469-2 is NOT opened.)

6 p A0-20469-1 red light verified ON at panel Verify A0-20469-1, SBGT OW Rx Bldg Exh Damper is open. 20C012.

(Cue: A0-20469-1 red light is on, green light is off.)

PLOR018C Rev 14 Page 4 of 8

STEP STEP ACT STANDARD NO

7 Open A0-20469-2, SBGT OW Rx Bldg p A0-20469-2 control switch is placed in Exh Damper. the OPEN position at panel 20C012.

(Cue: Acknowledge control switch operation.)

(Evaluator Note: This step is critical IF A0-20469-1 is NOT opened.)

8 Verify A0-20469-2, SBGT OW Rx Bldg p A0-20469-2 red light verified ON at panel Exh Damper is open. 20C012.

(Cue: A0-20469-2 red light is on, green light is off.)

9 Open A0-00475-1, SBGT "A" Filter Inlet p A0-00475-1 control switch is placed in Damper. the OPEN position at panel 20C012.

(Cue: Acknowledge control switch operation.)

10 Verify A0-00475-1, SBGT "A" Filter Inlet p A0-00475-1 red light verified ON at panel Damper is open. 20C012. Acknowledges annunciator 216 A-5 "SBGT Filters Not in Auto".

(Cue: A0-0475-1 red light is on, green light is off.)

11 Open A0-00475-2, SBGT "A" Filter p A0-00475-2 control switch is placed in Outlet Damper. the OPEN position at panel 20C012.

(Cue: Acknowledge control switch operation.)

12 Verify A0-00475-2, SBGT "A" Filter p A0-00475-2 red light verified ON at panel Outlet Damper is open. 20C012.

(Cue: A0-00475-2 red light is on, green light is off.)

13 Start "A" SBGT Fan. p "A" SBGT Fan control switch is placed in the RUN position at panel 20C012.

(Cue: Acknowledge control switch operation.)

PLOR018C Rev 14 Page 5 of 8

STEP STEP ACT STANDARD NO 14 Verify the "A" SBGT Fan Start. p SBGT Flow rises to approx. 6000 SCFM on FR-20008, "A" SBGTs Filter i0.P rises (Cue: Flow rises to approx. 6000 SCFM to 1" HzO on DPl-20001 and "A" SBGT on FR-20008 and "A" SBGTs Filter i0.P Fan red light verified ON at panel rises to 1" H2 0 on DPl-20001 "A" SBGT 20C012.

Fan red light is on, green light is off.)

15 Wait 3 to 5 seconds after "A" SBGT fan p A0-20467 is closed more than 3 seconds starts to close A0-20467. after "A" SBGT fan is started.

16 Close A0-20467, Ventilation Exhaust p A0-20467 control switch is placed in the Equip Cell Damper. CLOSE position at panel 20C012.

(Cue: Acknowledge control switch operation.)

17 Verify A0-20467, Ventilation Exhaust p A0-20467 green light verified ON at Equip Cell Damper is closed. panel 20C012.

(Cue: A0-20467 green light is on, red light is off.)

18 Close A0-20468, Ventilation Exhaust p A0-20468 control switch is placed in the Equip Cell Damper. CLOSE position at panel 20C012.

(Cue: Acknowledge control switch operation.)

19 Verify A0-20468, Ventilation Exhaust p A0-20468 green light verified ON at Equip Cell Damper is closed. panel 20C012. Acknowledges annunciator 216 L-1.

(Cue: A0-20468 green light is on, red light is off.)

PLOR018C Rev 14 Page 6 of 8

STEP STEP ACT STANDARD NO 20 Direct Equipment Operator to verify p Equipment Operator directed to verify the Equipment Cell Exhaust Fans 2AV18 and Equipment Cell Exhaust Fans not running 2BV18 are not running and verify the and Fan control switches in "OFF".

control switches for both of the Equipment Cell Exhaust Fans are in "OFF".

(Cue: Equipment Operator reports 2AV18 and 2BV18 are not running and both of the Equipment Cell Exhaust Fan control switches are in "OFF".)

21 Verify proper operation of the SBGT p The "A" SBGT Filter DP is verified to be system. in Expected Performance Region of Figure 1 of SO 9A.7.G and SBGT System (Cue: SBGT Filter DP is in the Expected flow is verified to be between 2000 and Performance Region of SO 9A.7.G, 9000 SCFM on FR-20008.

Figure 1.)

22 Verify Unit 2 Reactor Building differential p Reactor Building DPl-20003-01 indicates pressure between -.1 and -.4" H20 as between -.1 and -.4" H20. Equipment indicated on DPl-20003-01. Operator is directed to adjust differential pressure between -.1 to -.4 inches of (Cue: Reactor Building DP is between - water as necessary.

0.1 and -0.4" H20.)

23 Verify Unit 2 Refuel Floor differential p Equipment Operator is directed to verify pressure between -.1 and -.4" H20 as Refuel Floor DPl-20003-02 indicates indicated on DPl-20003-02. between -.1 and -.4" H20 .. Equipment Operator is directed to adjust differential pressure between -.1 to -.4 inches of (Cue: Refuel Floor DP is between -0.1 water as necessary.

and -0.4" H20.)

24 Log start time in the SBGT Filter Train p Logs start time in ST-0-09A-500-2, Data Run Log in accordance with ST-0-09A- Sheet 1.

500-2.

(Cue: Start time is logged in ST-0-09A-500-2.)

PLOR018C Rev 14 Page 7 of 8

STEP STEP ACT STANDARD NO 25 Inform Control Room Supervisor of task p Task completion reported.

completion.

(Cue: Control Room Supervisor acknowledges report.)

26 As an evaluator ensure you have positive p Positive control established.

control of all exam material provided to the examinee (Task Conditions I Prerequisites) AND procedures.

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When Equipment Cell Exhaust is placed on Standby Gas Treatment, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

PLOR018C Rev 14 Page 8 of 8

TASK CONDITIONS/PREREQUISITES

1. Standby Gas Treatment System lined up for automatic operation per SO 9A.1.A, "Standby Gas Treatment System Lineup for Automatic Operation"

2. Operator stationed at Reactor Building Vent Panel 20C132.

3. Standby Gas Treatment Filter Train "A" has the least amount of run-hours.

INITIATING CUE The Control Room Supervisor directs you to place SBGT on Equipment Cell Exhaust using SO 9A.7.G, "Standby Gas Treatment System Manual Startup on Equipment Cell Exhaust".

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

~ JPM D QUALIFICATION MANUAL D OJT MODULE PROGRAM: LICENSED OPERATOR TRAINING CODE#: PLOR-105P COURSE: LICENSED OPERATOR REQUALIFICATION REV#:: 011 AUTHOR: M. J. Kelly TYPIST: mda TITLE: ALTERNATE RPV INJECTION USING THE SBLC TEST TANK APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE:

NAME: ISSUE DATE:

Last First M.I.

EMPLOYEE l.D. NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMS CODE:

LMS ENTRY:

Signature/Date PLOR105P Rev 11011 Page 1 of 7

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2005410599 / PLOR-105P KIA: 295031EA1.08 URO: 3.8 SRO: 3.9 TASK DESCRIPTION: Alternate RPV Injection Using the SBLC Test Tank A. NOTES TO EVALUATOR:

1. An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR105P Rev 11011 Page 2 of 7

8. TOOLS AND EQUIPMENT

1. T-244-2, Tool Package

2. One 50 Foot Length of Air Hose

3. Unit 2 Locked Valve Key

4. EOP Tool Locker Key C. REFERENCES

1. T-244-2, Rev. 6, "Alternate Injection Using the SBLC Test Tank" D. TASK STANDARD

1. Performance Location: Plant

2. Satisfactory task completion is indicated when the SBLC Test Tank is aligned for alternate RPV injection per T-244-2.

3. Estimated time to complete: 20 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to align the SBLC system for alternate RPV injection using T-244-2, "Alternate Injection Using the SBLC Test Tank". I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Use of T-244-2 "Alternate Injection Using the SBLC Test Tank" has been directed by TRIPs.

2. All rods are fully inserted.

3. SBLC pump(s) are available.

4. Demineralized water is available to the SBLC system.

5. A loss of power event is NOT in progress.

G. INITIATING CUE The Control Room Supervisor directs you, the Equipment Operator, to perform T-244-2, "Alternate Injection Using the SBLC Test Tank" up to and including Step 4.6.

PLOR105P Rev 11011 Page 3 of 7

H. PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD

- - NOTE***

IF this is the first in-plant JPM then the license candidate is required to go to the EOP Tool Locker. For subsequent in-plant JPMs it is not necessary to have the candidate go to the Tool Locker for JPMs that require material from the locker. Describing where the locker is located, how to access key to unlock it, and what procedure packages/material would be obtained is sufficient for subsequent JPMs.

1 Obtain the key for the Emergency S Emergency Operating Procedure (EOP)

Operating Procedure Tool Locker. Tool Locker Key requested from WECS (Cue: When examinee requests EOP Tool OR examinee identifies the location of the Locker key from WECS OR examinee WECS key box and its associated key.

identifies the location of the WECS key box and its associated key then evaluator should provide the EOP Tool Locker key.)

2 Obtain a Unit 2 Locked Valve Key. S Examinee identifies the location of the U-2 Lock Valve key located in the WECS key (Cue: When the examinee identifies the box OR examinee produces a personal location of the U-2 Lock Valve key located copy of Lock Valve key.

in the WECS key box OR examinee produces a personal copy of Lock Valve key, then the evaluator should state that the examinee has obtained a Unit 2 Locked Valve key.

3 Open Emergency Operating Procedure S, P EOP Tool Locker located on Radwaste Tool Locker and obtain T-244-2 Tool Kit Building El. 165' is unlocked, opened and and 50 foot length of air hose. T-244-2 Tool Kit and is located.

(Cue: Equipment obtained.) The required 50 foot length of air hose is located in a separate locker nearby.

- - NOTE***

When examinee locates tool kit and air hose, inform him that he now has the tools to perform the procedure. Provide the examinee with a copy of the T-200 procedure which corresponds to the tool kit that has been chosen. DO NOT allow tools to be removed from the locker. Relock the locker before leaving the area.

PLOR105P Rev 11011 Page 4 of 7

STEP NO STEP ACT STANDARD 4 Verify closed HV-2-11-28, "SBLC Test s HV-2-11-28 valve handwheel Tank 20T017 Inner Drain Valve". (RB 195' CLOCKWISE turning is attempted to verify El. below the tank) it will not close further.

(Cue: [CLOCKWISE] Valve handwheel turned, valve handwheel will not turn.)

5 Verify closed HV-2-11-29 "SBLC Test s HV-2-11-29 valve handwheel Tank 20T017 Demin Water Hose CLOCKWISE turning is attempted to verify Connection". (RB 195' El. East wall) it will not close further.

(Cue: [CLOCKWISE] Valve handwheel turned, valve handwheel will not turn.)

6 Connect the 50 foot length of air hose to s The 50 foot length of air hose has been HV-2-11-29, "SBLC Test Tank 20T017 connected to HV-2-11-29 via the quick Oemin Water Hose Connection". disconnect.

(Cue: 50 ft. air hose is connected to HV 11-29.)

7 Connect the 50 foot length of air hose to s The 50 foot length of air hose has been HV-2-380-29, "Oemin Water Hose Block connected to HV-2-380-29 via the quick Viv for Stby Liq Ctrl Tnk 20T017" (RB 195' disconnect.

El. West wall).

(Cue: 50 ft. air hose is connected to HV 380-29.)

8 Open HV-2-380-29, "Oemin Water Hose s HV-2-380-29 handwheel is turned Block Viv for Stby Liq Ctrl Tnk 20T017". COUNTERCLOCKWISE until resistance of the valve backseat is felt.

(Cue: Valve handwheel turned

[COUNTERCLOCKWISE] until stem length above valve yoke increases 2 inches then will not turn.)

9 Verify no leakage from the demineralized s Oemineralized water hose connection is water hose connection. visually inspected for leakage.

(Cue: There is no leakage from the hose connection.)

PLOR105P Rev 11011 Page 5 of 7

STEP NO STEP ACT STANDARD

10 Open HV-2-11-29, "SBLC Test Tank s HV-2-11-29 Handwheel is turned 20T017 Demin Water Hose Connection", COUNTERCLOCKWISE until the to fill the SBLC Test Tank. resistance of the valve backseat is felt.

(Cue: Valve handwheel is turned

[COUNTERCLOCKWISE], stem length above valve yoke increases 2" then will not turn.)

11 Observe LG-2797 "SBLC Test Tank Level" p LG-2797 is observed on the side of the rising. SBLC Test Tank.

(Cue: LG-2797 indication is rising "out of sight" high.)

12 WHEN the SBLC Test Tank is full, THEN s HV-2-38D-29 handwheel is turned close HV-2-38D-29 " Demin Wtr Hose Blk CLOCKWISE until resistance of the valve Viv for SBLC Test Tank 20T017". seat is felt.

(Cue: Valve handwheel is turned

[CLOCKWISE] until it will turn no further.)

13 Unlock HV-2-11-41 "SBLC Test Tank s The locked valve key is inserted into the 20T017 Outlet to SBLC Pump Suction lock, the lock is unlocked and the chain is Hdr". removed from HV-2-11-41 handwheel.

(Cue: Locking device is unlocked and removed.)

14 Open HV-2-11-41 "SBLC Test Tank s HV-2-11-41 handwheel is turned 20T017 Outlet to SBLC Pump Suction COUNTERCLOCKWISE until resistance Hdr". of valve backseat is felt.

(Cue: Valve handwheel is turned

[COUNTERCLOCKWISE] until stem length above valve yoke increases 4 inches and then will not move.)

15 Unlock HV-2-11-11, "SBLC Tank 20T018 s The locked valve key is inserted into the Outlet Block to Pumps 2AP040 and lock, the lock is unlocked and the chain is 2BP040". removed from HV-2-11-11 handwheel.

(Cue: Locking device is unlocked and removed.)

PLOR105P Rev 11011 Page 6 of 7

STEP NO STEP ACT STANDARD

16 Close HV-2-11-11 "SBLC Tank 20T018 s HV-2-11-11 handwheel turned Outlet Block to Pumps 2AP040 and CLOCKWISE until valve will not turn 2BP040". further.

(Cue: Valve handwheel is turned

[CLOCKWISE], stem length above yoke decreases until it will not turn further.)

17 Inform Main Control Room that task is s Task completion reported using hand held completed. radio or GAl-TRONICS page system.

(Cue: The Control Room acknowledges report.)

18 As an evaluator ensure you have positive p Positive control established.

control of all exam material provided to the examinee (Task Conditions/Prerequisites)

AND procedures.

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When the SBLC system has been aligned for alternate RPV injection, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

PLOR105P Rev 11011 Page 7 of 7

TASK CONDITIONS/PREREQUISITES

1. Use of T-244-2 "Alternate Injection Using the SBLC Test Tank" has been directed by TRIPs.

2. All rods are fully inserted.

3. SBLC pump(s) are available.

4. Demineralized water is available to the SBLC system.

5. A loss of power event is NOT in progress.

INITIATING CUE The Control Room Supervisor directs you, the Equipment Operator, to perform T-244-2, "Alternate Injection Using the SBLC Test Tank" up to and including Step 4.6.

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

~ JPM D QUALIFICATION MANUAL D OJT MODULE PROGRAM: Licensed Operator Training CODE#: PLOR-093P COURSE: Licensed Operator Requalification REV#:: 000 AUTHOR: R. J. Artus TYPIST: Rja TITLE: RPV venting During Containment Flooding (T-252-3)

APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: I I NAME: ISSUE DATE:

Last First M.I.

EMPLOYEE ID NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMS CODE:

LMS ENTRY:

Signature/Date PLOR093P Rev 0 Page 1 of 6

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2002300504 I PLOR-093P KIA: 206000 K1 .01 RO: 3.8 SRO: 3.9 TASK DESCRIPTION: RPV Venting During Containment Flooding A. NOTES TO EVALUATOR:

1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR093P Rev 0 Page 2 of 6

B. TOOLS AND EQUIPMENT

1. T-252 Tool Package (A)

C. REFERENCES

1. Procedure T-252-3, Rev. 8, "RPV Venting During Containment Flooding" (R)

D. TASK STANDARD

1. Satisfactory task completion is indicated when the required interlocks have been defeated to allow RAPV venting while flooding the containment.

2. Estimated time to complete: 24 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to allow for RPV vent during Primary Containment flooding using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Alternate RPV depressurization is required by T-112.

2. Pneumatic supply and power is available to the HPCI and RCIC Steam Line Drain Valves.

3. HPCI System is shutdown.

4. RCIC System is shutdown.

G. INITIATING CUE The Control Room Supervisor directs you, the Equipment Operator, to perform sections 4.3.and 4.4 of T-252-3, "RPV Venting During Containment Flooding" to setup the HPCI and RCIC Steam Line Drain flow paths.

PLOR093P Rev 0 Page 3 of 6

H. PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD

- - NOTE***

IF this is the first in-plant JPM then the license candidate is required to go to the EOP Tool Locker. For subsequent in-plant JPMs it is not necessary to have the candidate go to the Tool Locker for JPMs that require material from the locker. Describing where the locker is located, how to access key to unlock it, and what procedure packages/material would be obtained is sufficient for subsequent JPMs.

1 Obtain the key for the Emergency S Examinee identifies the location of the Operating Procedure Tool Locker. WCS keybox and its associated key.

(Cue: Examinee locates the EOP Tool Locker key.)

2 Open EOP Tool Locker and obtain T-252-3 P EOP Tool Locker is unlocked, opened Tool Kit. and T-252-3 Tool Kit is located.

(Cue: Equipment obtained.)

- - - NOTE****

When examinee locates tool kit, inform him that he now has the tools to perform the procedure. Provide the examinee with a copy of the T-200 procedure which corresponds to the tool kit that has been chosen. DO NOT allow equipment to be removed from the locker. Relock the locker before leaving the area.

3 In the back of Panel 30C32, on Terminal S Using fuse pullers, fuses F5 (23A-F17)

Block BB, pull the following fuses: and F6 (23A-F18) are pulled on Terminal F5 (23A-F17) Block BB in the back of Panel 30C32.

F6 (23A-F18)

(Cue: Fuses are pulled.)

4 In the back of Panel 30C39, on Terminals S Using fuse pullers, fuses F1 (23A-F1) and Block BB, pull the following fuses: F2 (23A-F2) are pulled on Terminal Block F1 (23A-F1) BB in the back of Panel 30C39 are pulled.

F2 (23A-F2)

(Cue: Fuses are pulled.)

5 Verify closed M0-3-23-016 "Steam lsol" at P Due to the Cable Spreading Room being panel 30C04B. a radio free area, the Examinee calls the Main Control Room Unit 3 Reactor Operator via telephone to verify M0-3 (Cue: Unit 3 Reactor Operator reports 016 is CLOSED.

that M0-3-23-016 is CLOSED).

PLOR093P Rev 0 Page 4 of 6

STEP NO STEP ACT STANDARD 6 Open M0-3-23-015 "Steam lsol" at Panel p Due to the Cable Spreading Room being 30C04B. a radio free area, the Examinee calls Main Control Room Unit 3 Reactor Operator via telephone to verify M0-3 (Cue: Unit 3 Reactor Operator reports 015 is OPEN.

that M0-3-23-015 is OPEN).

7 Inform Shift Management that HPCI p Due to the Cable Spreading Room being Steam Line Drain flow path is set up. a radio free area, the Examinee informs Shift Management via telephone that the HPCI Steam Line Drain flow path is (Cue: Acknowledge as Shift setup.

management the report that the HPCI Steam Line Drain flow path is setup).

8 In the back of Panel 30C33, on Terminal s Using fuse pullers, fuses F5 (13A-F21)

Block BB, pull the following fuses: and F6 (13A-F22) are pulled on Terminal F5 (13A-F21) Block BB in the back of Panel 30C33.

F6 (13A-F22)

(Cue: Fuses are pulled.)

9 In the back of Panel 30C34, on Terminal s Using fuse pullers, fuses F1 (13A-F1) and Block BB, pull the following fuses: F2 (13A-F2) are pulled on Terminal Block F1 (13A-F1) BB in the back of Panel 30C34.

F2 (13A-F2)

(Cue: Fuses are pulled.)

10 Verify closed M0-3-13-016 "Steam lsol" at p Due to the Cable Spreading Room being panel 30C004C. a radio free area, the Examinee calls the Main Control Room Unit 3 Reactor Operator via telephone to verify M0-3 (Cue: Unit 3 Reactor Operator reports 016 is CLOSED.

that M0-3-13-016 is CLOSED).

11 Open M0-3-13-015 "Steam lsol" at Panel p Due to the Cable Spreading Room being 30C04C. a radio free area, the Examinee calls the Main Control Room Unit 3 Reactor Operator via telephone to verify M0-3 (Cue: Unit 3 Reactor Operator reports 015 is OPEN.

that M0-3-13-015 is OPEN).

12 Inform Shift Management that RCIC p Due to the Cable Spreading Room being Steam Line Drain flow path is set up. a radio free area, the Examinee informs Shift Management via telephone that the RCIC Steam Line Drain flow path is setup (Cue: Acknowledge as Shift Management the report that the RCIC Steam Line Drain flow path is setup).

PLOR093P Rev 0 Page 5 of 6

STEP NO STEP ACT STANDARD 13 As an evaluator, ensure that you have p Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

Under "ACT' P - must perform S - must simulate I. TERMINATING CUE When the required steps have been completed to setup the HPCI and RCIC Steam Line Drain flow paths, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

PLOR093P Rev 0 Page 6 of 6

TASK CONDITIONS/PREREQUISITES

1. Alternate RPV depressurization is required by T-112.

2. Pneumatic supply and power is available to the HPCI and RCIC Steam Line Drain Valves.

3. HPCI System is shutdown.

4. RCIC System is shutdown.

INITIATING CUE The Control Room Supervisor directs you, the Equipment Operator, to perform sections 4.3.and 4.4 of T-252-3, "RPV Venting During Containment Flooding" to setup the HPCI and RCIC Steam Line Drain flow paths.

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

~ JPM D QUALIFICATION MANUAL D OJT MODULE PROGRAM: Licensed Operator Training CODE#: PLOR-096P COURSE: Licensed Operator Requalification Training REV#:: 016 AUTHOR: J. R. Felice TYPIST: Mda TITLE: Loss of RBCCW (Plant Actions for the Instrument Nitrogen System)

APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: I I NAME: ISSUE DATE:

Last First M.I.

EMPLOYEE l.D. NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMS CODE:

LMS ENTRY:

Signature/Date PLOR096P Rev016 Page 1 of 5

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2000200401 I PLOR-096P KIA: 295018AA1.01 RO: 3.3 SRO: 3.4 TASK DESCRIPTION: LOSS OF RBCCW (PLANT ACTIONS FOR THE INSTRUMENT NITROGEN SYSTEM)

A. NOTES TO EVALUATOR:

1. An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR096P Rev016 Page 2 of 5

B. TOOLS AND EQUIPMENT None C. REFERENCES Procedure ON-113, Rev. 18, "Loss of RBCCW" D. TASK STANDARD

1. Satisfactory task completion is indicated when

a. The Instrument Air System is supplying the Instrument Nitrogen System.

b. The Instrument Nitrogen Compressors have been shutdown.

2. Estimated time to complete: 17 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to lineup the Unit 2 Instrument Air System to supply the Instrument Nitrogen System and trip the Instrument Nitrogen Compressors, using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. RBCCW has been lost on Unit 2.

2. ON-113, "Loss of RBCCW" is in progress.

G. INITIATING CUE The Control Room Supervisor directs you, the Equipment Operator, to perform steps 2.10 and 2.11 of ON-113, "Loss of RBCCW" on Unit 2.

PLOR096P Rev016 Page 3 of 5

H. PERFORMANCE CHECKLIST STEP STEP ACT STANDARD NO 1 Obtain a copy of procedure ON-113. p A copy of procedure ON-113 is obtained.

2 Open A0-4230A "A" Instrument Air s SV-4230A control switch is placed in the Backup to "A" Instrument N2 Header valve. OPEN position at the local control station, 2AC839 on Reactor Building 135' (Cue: Acknowledge control switch Elevation near the Scram Discharge operation.) Instrument Volume area.

3 Verify A0-4230A "A" Instrument Air p A0-4230A red light is verified ON at the Backup to "A" Instrument N2 Header valve local control station, 2AC839 on Reactor is open. Building 135' Elevation near the Scram Discharge Instrument Volume area.

(Cue: A0-4230A red light is on, and green light is off.)

- - NOTE***

For the next 2 steps, after the examinee identifies the location of the control station for the A0-42308 on the TIP Room Roof, have them demonstrate required actions back on the control station for the A0-4230A since it is more accessible.

4 Open A0-4230B "B" Instrument Air s SV-4230B control switch is placed in the Backup to "B" Instrument N2 Header valve. OPEN position at the local control station, 2BC839 on Reactor Building 135' (Cue: Acknowledge control switch Elevation. (TIP Room Roof) operation.)

5 Verify A0-4230B "B" Instrument Air p A0-4230B red light is verified ON at the Backup to "B" Instrument N2 Header valve local control station, 2BC839 on Reactor is open. Building 135' Elevation. (TIP Room Roof)

(Cue: A0-4230B red light is on, and green light is off.)

6 Shutdown the "A" Instrument Nitrogen s "A" Instrument Nitrogen Compressor Compressor. control switch (HS-2-16-4225) is placed in the OFF position at the local control (Cue: Acknowledge control switch station, 2AC268 on Reactor Building 195' operation.) Elevation.

PLOR096P Rev016 Page 4 of 5

STEP STEP ACT STANDARD NO 7 Verify the "A" Instrument Nitrogen p "A" Instrument Nitrogen Compressor OFF Compressor is shutdown. (green) light is ON at the local control station, 2AC268 on Reactor Building 195' Cue: The "A" Instrument Nitrogen Elevation.

Compressor control switch is in OFF and green light is on.)

8 Shutdown the "B" Instrument Nitrogen s "B" Instrument Nitrogen Compressor Compressor. control switch (HS-2-16-4121) is placed in the OFF position at the local control (Cue: Acknowledge control switch station, 2BC268 on Reactor Building 195' operation.) Elevation.

9 Verify the "B" Instrument Nitrogen p "B" Instrument Nitrogen Compressor OFF Compressor is shutdown. (green) light is ON at the local control station, 2BC268 on Reactor Building 195' (Cue: The "B" Instrument Nitrogen Elevation.

Compressor control switch is in OFF and green light is on.)

10 Inform Control Room Supervisor of task s Task completion reported using telephone, completion. hand held radio, or GAl-TRONICS page system.

(Cue: Control Room Supervisor acknowledges report.)

11 As an evaluator ensure that you have p Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND p raced ures.

Under "ACT' P - must perform S - must simulate I. TERMINATING CUE When the Instrument Air backup valves to Instrument Nitrogen, A0-4230A and A0-4230B, are open and the Instrument Nitrogen Compressors have been shutdown, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

PLOR096P Rev016 Page 5 of 5

TASK CONDITIONS/PREREQUISITES

1. RBCCW has been lost on Unit 2.

2. ON-113, "Loss of RBCCW" is in progress.

INITIATING CUE The Control Room Supervisor directs you, the Equipment Operator, to perform steps 2.10 and 2.11 of ON-113, "Loss of RBCCW" on Unit 2.

Appendix D Scenario Outline ES-D-1 Simulation Facility Peach Bottom Scenario No. #1 Op Test No. 2015 NRC Examiners Operator _ _ _ _ _ _ _ CRS (SRO)

- - - - - - URO (ATC)

PRO (BOP)

Scenario The scenario begins with the reactor at approximately 3% power during a reactor Summary startup.

Following shift turnover, the PRO will secure the Drywell Purge lineup.

A Primary Containment Isolation valve will fail open. The failed valve will require the CRS to evaluate the situation in Tech Specs and determine that the penetration must be isolated within four hours.

The URO will continue the startup by raising reactor power to > 4% by withdrawing control rods in accordance with the approved startup sequence until 3 main turbine bypass valves are open with reactor pressure at 915 psig using procedure GP-2-2, "Normal Plant Startup".

A control rod will become mispositioned due to a Reactor Manual Control System timer failure, requiring the crew to execute ON-122, "Mispositioned Control Rod" to return the control rod to the correct target position.

Following the mispositioned Control Rod, the steam supply valve for the in-service Steam Jet Air Ejector fails closed due to a loss of its normal air supply. The loss of steam to the air ejector will cause main condenser vacuum to get worse. The crew should recognize the lowering vacuum condition and enter procedure OT-106 "Condenser Low Vacuum". The CRS should direct the crew to place the steam supply valve alternate air supply in service and restore the air ejector to normal service and thereby reestablishing normal main condenser vacuum. The CRS might direct the PRO to swap Air Ejectors using SO 8A.6.A-2, "Placing the Standby SJAE In Service and Placing the In-Service SJAE in Standby".

Once main condenser vacuum is normal there will be a spurious start of the "A" loop of Core Spray. Following the spurious start a leak will occur in the "A" Core Spray pump discharge piping. The leak will continue until the Crew secures the pumps and isolated the suction for the "A" Core Spray pump. The CRS should reference Technical Specifications for required actions with the "A" Core Spray pump inoperable.

When the CRS has determined the Tech Spec action, the startup level control system will experience a control signal failure resulting in the startup level control valve failing closed. The valve closure will halt any makeup to the RPV and subsequently RPV level will lower. The crew should recognize the lowering RPV level and enter procedure OT-100 "Reactor Level Low". Placing the startup level control valve controller into manual will not return control of the makeup valve. The URO will need to establish RPV level control using the "C" RFP discharge valve and RFP speed.

2015 NRC Scenario #1 D-1 Rev 1

Appendix D Scenario Outline ES-D-1 Once RPV level is stabilized, a steam leak will develop in the primary containment with a stuck open Torus to Drywell vacuum breaker. The crew should recognize the rise in drywell temperature and pressure and enter procedure OT-101 "High Drywell Pressure". OT-101 actions include maximizing drywell cooling and isolating steam supply valves in the drywell in order to identify the possible leak location.

When drywell pressure reaches 1.2 psig the crew should attempt to scram the reactor. When the mode switch is placed in shutdown no control rods will insert due to an electric ATWS. The crew should enter procedure T-101 "RPV Control" to respond to the ATWS condition. The control rods will fully insert and the ATWS will be terminated when Alternate Rod Insertion is initiated using Rapid Response Card RRC 38.1-2 "ARI During a Plant Event". (Critical Task; Insert all control rods using ARI)

When drywell pressure reaches 2 psig the crew will enter procedure T-102 "Primary Containment Control" to respond to the degrading condition. The crew should spray the primary containment using procedure T-204 "Initiation of Containment Sprays Using RHR" to maintain below the Pressure Suppression Pressure Limit. (Critical Task; Spray the Drywell before the Pressure Suppression Pressure Limit Curve is exceeded) When Drywell Sprays are placed in-service, the RHR pump will trip and another RHR will need to be placed in-service. The scenario will be terminated when Primary Containment pressure is stable due to spraying containment.

Initial IC-71 Approximately 3% power Conditions Turnover Unit 2 startup is in progress.

Drywell purge needs to be secured. The extra RO will begin inerting Containment shortly after turnover.

Reactor Power is approximately 3% with direction to continue to raise Reactor power with control rods using GP-2-2 2015 NRG Scenario #1 D-1 Rev 1

Appendix D Scenario Outline ES-D-1 Event Malfunction Event Event No. No. Type* Description 1 See Scenario Guide N PRO Secure the Drywell Purge Lineup CRS 2 See Scenario Guide TS CRS Failure of a Primary Containment isolation valve 3 See Scenario Guide R URO Raise reactor power by withdrawing control rods until 2 main CRS turbine bypass valves are open with reactor pressure at 915 psig 4 See Scenario Guide c URO A control rod becomes mispositioned, requiring execution of CRS ON-122 "Mispositioned Control Rod" 5 See Scenario Guide c PRO Steam supply valve for in-service Steam Jet Air Ejector fails CRS closed I lowering main condenser vacuum 6 See Scenario Guide c PRO "A" Core Spray loop spurious start. "A" Core Spray suction TS CRS line break/flooding (Tech Spec) 7 See Scenario Guide c URO Startup level control valve fails closed I lowering RPV level CRS 8 See Scenario Guide M ALL Reactor coolant leak inside the drywell I Torus to Drywell vacuum breaker fails open 9 See Scenario Guide c URO A TWS I Control rods inserted using Alternate Rod Insertion CRS 10 See Scenario Guide c PRO RHR pump running in Torus Spray trips CRS

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor, (TS) Tech Spec 2015 NRC Scenario #1 D-1 Rev 1

SIMULATOR OPERATOR INSTRUCTIONS FOR NRC SCENARIO #1 GENERAL REQUIREMENTS

Recorders will be rolled prior to the scenario and paper from selected recorders will be retained for the examination team as requested.

All procedures, flow charts, curves, graphs, etc. will be in their normal storage places.

All markable procedures, boards, etc. will be erased.

All paper used by the Crew will be retained for the examination team as requested.

The simulator operators will keep a log of all communications during the scenario as requested by the examination team.

SCENARIO SOURCE HISTORY

This scenario is a new scenario written for the 2015 NRC exam.

INITIAL SETUP Initial Conditions

IC-9, 8% power (IC-71 for the 2015 exam)

OR

Insert Control Rods to lower Reactor power to 3%.

AND

Ensure recorder power is on; roll recorders as required

Ensure annunciator horns are active

"A" RFP M/A Station is at 0.

Blocking Tags

None Activate APP NRC 1 or insert the following:

Event Triggers TRG E3 =FALSE TRG E4 =FALSE TRG E5 =FALSE TRG E6 =FALSE 1

Malfunctions IMF CSS02A (E3 1 :00 0) 100 "CS Pmp A Discharge Line Break Before the Check Valve" IMF FWC01 D (ES) S "LCV 8091 Controller Failure" IMF MSS01 (E6) 1S 30:00 "Steam leakage Inside the Primary Containment" IMF PCS03A (E6) "Torus-Drywell Vacuum Breaker 'A' Fails Open" Overrides IOR ZYP12A1S1018 (E3) ARMED "CS SYS I Manual lnit PB" IOR ZYP12A1S101A (E3) ON "CS SYS I Manual lnit PB" IOR ZLOPC03A02S06_2 (E4) ON "OW 18" Vent Valve AO 2506 (Red)"

IOR ZLOPC03A02S06GRP_2 (E-4) ON "OW 18"Vent Valve A0-2506 (Red)"

IOR AN0203BA3 (E4) ALARM_ON "Drywell Vent valves Open (225 A3)"

IOR AN0206LH1 (ES) ALARM_ON "Feedwater Field Inst Trouble"(201 H1)

Trip Overrides MRF RPS01TO OVERRIDE "RPS Auto Scram CH A-1" MRF RPS02TO OVERRIDE "RPS Auto Scram CH A-2" MRF RPSOSTO OVERRIDE "RPS Auto Scram CH A-3" Remote Functions None Expert Commands Turnover Procedures GP-2-2, "Normal Plant Startup" completed up to step 6.2.53 with the exception of step 6.2.49 to secure purge.

Control Rod sequence sheets marked up through Sequence Step 14 Group 8 rod 10-19 is the next Control Rod to be withdrawn.

ReMA for the plant startup with guidance for Control Rod withdrawal described on page 6 of this scrnario.

2

SIMUAL TOR OPERATOR DIRECTIONS EVENT 1 Secure the Drywell Purge Lineup - Support the Crew as necessary to allow the PRO to secure the Drywell Purge lineup.

If directed to close and lock HV-2-36B-23840A and HV-2-36B-23840D, wait approximately 4 minutes and report that HV-2-36B-23840A and HV 36B-23840D are locked and closed.

EVENT 2 Failure of a Primary Containment Isolation Valve - When the operator begins to secure SGBT or at the direction of the Lead Examiner, initiate ET 4 (ZLOPC03A02506_2, ZLOPC03A02506GRP _2 & AN0203BA2) to fail the boot seal on the OW 18" Vent Valve A0-2506.

!E directed to check the Instrument Air Supply and Backup Nitrogen Supply pressures for the A0-2506, THEN WAIT approximately 4 minutes and report that Instrument Air Supply pressure and the Backup N2 Supply pressure is approximately 50 psig and that the valve appears to be closed.

EVENT 3 Control Rod Withdraw - Support the crew as necessary during Control Rod withdraw.

EVENT 4 Mispositioned Control Rod -When Control Rod 42-35 is withdrawn, the Control Rod will move beyond the expected position and be mispositioned.

Before Control Rod 42-35 is withdrawn, enter APP-NRC_ 1_1 or insert the following:

TRG E1 =ON 122 (Activates when the green light above the rod movement control switch is energized.)

TRG E2 = ON122A (Activates when the settle light is energized.)

IOR ZAP02A4503 NOTCH OVERRIDE "Emergency In/Notch Override Switch"

IOR ZLORD05A3ADS6 OFF "Emergency In/Notch Override switch yellow light"

IOR ZYP02A4509 (E1 0 8) OUT NOTCH "Rod Movement Control Switch"

TRG E2 = DOR ZYP02A4503

TRG E2 = DOR ZLORD05A3ADS6 At the completion of the movement verify the ET-2 has deleted ZYP02A4S03 and ZLORD05A3ADS6.

3

SIM UAL TOR OPERA TOR DIRECTIONS EVENT 5 Loss of Main Condenser Vacuum - When Control Rod 42-35 is returned to positon 12 or at the direction of the Lead Examiner, enter MRF MSS05A CLOSE '"A' SJAE Stm Isolation Valve AO 2466A".

The steam supply to the "A" Air Ejector will go closed. Steam Supply can be restored by using the Alternate Instrument Air Supply control switch.

EVENT 6 Core Spray Spurious Start and Room Leak - At the direction of the Lead Examiner, initiate ET 3 (ZYP12A1S1018, ZYP12A1S101A, CSS02A) to spuriously start the A and C Core Spray pumps and cause a leak on the "A" Core Spray pump discharge piping.

If directed to investigate the Core Spray pump starts, wait approximately 3 minutes and report that you don't know why the Core Spray pumps started.

If directed to investigate the room flood alarm report that there is water in the "A" Core Spray pump room and that the level is rising. Continue to report that the water is rising until the "A" Core Spray suction valve is fully closed. Modify the report of leak rate based on the status of the Core Spray Pumps.

If directed to rack out the "A" Core Spray pump breaker, then perform the following:

IOR ZLOCS032AP37_1 OFF, "2A Core Spray Pump (Green)"

IOR ZLOCS032AP37 _2 OFF, "2A Core Spray Pump (Red)"

IOR ZYP12A1S07 STOP, "2A Core Spray Pump (Stop/Start)"

EVENT 7 Startup Level Controller Fails Low -At the direction of the Lead Examiner, initiate ET-5 (FWC01D &AN0206LH1). The Startup level controller will fail in the closed direction. RPV level control will be with the "C" RFP discharge valve and RFP speed.

If directed to investigate the feedwater trouble as l&C, wait approximately 10 minutes and report that you cannot determine an issue with the startup level controller but will continue to look.

If the crew does not recover RPV level and the Reactor scrams, then move onto event 8.

4

SIM UAL TOR OPERA TOR DIRECTIONS EVENT 8 Steam Leak in the Drvwell - At the direction of the Lead Examiner initiate ET-6 (MSS01 and PCS03A). The steam leak will cause Primary Containment parameters to deteriorate and require a Reactor scram. The failed open Torus to Drywell Vacuum Breaker will require the Crew to spray containment in-order to prevent an Emergency Slowdown (exceeding the Pressure Suppression Pressure limit).

If directed to raise chiller loading to 100%, wait approximately 4 minutes and report the "C" chiller load has been raised to 100%.

If directed to report Drywell Chilled Water Return Header pressure, wait approximately 5 minutes and report that Drywell Chilled Water Return Header pressure is 26 psig.

If directed to place the Drywell fans in slow speed wait approximately 10 minutes and report that the fan control switches are in slow speed.

EVENT 9 A TWS, Control Rods Will Insert with ARI - When the Crew scrams the Reactor the Control Rods will not insert. Control Rods will insert when ARI is initiated.

EVENT 10 RHR Pump Trips -When Drywell Sprays are placed in service, trip the operating RHR pump by inserting Malfunction IMF RHR01A-D.

If directed to determine the cause of the RHR pump trip, wait approximately 3 minutes and report that the RHR pump tripped on instantaneous overcurrent.

TERMINATION The scenario may be terminated when Primary Containment pressure is stable due to spraying containment.

5

SHIFT TURNOVER PLANT CONDITIONS:

A Unit 2 startup is in progress at approximately 3% Reactor power.

INOPERABLE EQUIPMENT/LCOs:

None SCHEDULED EVOLUTIONS:

Continue the Reactor startup in accordance with GP-2-2.

Secure the Drywell purge lineup using SO 7B.4.A-2, "Containment Atmosphere De-lnerting and Purging Via SBGT System" steps 4.22.1-4.22.12.

SURVEILLANCES DUE THIS SHIFT:

None ACTIVE CLEARANCES:

None GENERAL INFORMATION:

When the Crew assumes the shift, secure the Drywell Purge lineup. GP-2-2 is complete up to step 6.2.53 with the exception of step 6.2.49 to secure purge. A Reactivity Briefing was already completed and you are ready to begin withdrawing rods at the beginning of Rod Group 8, Control Rod 10-19, to achieve 2 bypass valves open.

An unexpected slow response was observed by the Reactor Operator when rods 18-35, 42-27, 42-35 and 18-27 were moved from position 8 to position 12. Because of this the Reactor Engineers will be performing special testing prior to the movement of these Control Rods. These Control Rods are the first 4 Control Rods to be withdrawn in Sequence 15. Prior to withdrawing these Control Rods the Reactor Operator will:

1. Ensure the Reactor Engineers are ready to monitor Control Rod withdrawal.

2. Notch out the Control Rod from position 12 to position 14.

3. Verify proper operation of the Control Rod with the Reactor Engineer.

4. Withdraw the selected Control Rod to position 48.

6

CRITICAL TASK LIST

1. Insert all control rods using ARI. (T-101-2)

2. Spray the Drywell before the Pressure Suppression Pressure (PSP) Limit Curve is exceeded. (T-102-?a) 7

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 1 Event No. 1 Page: 1 of 18 Event

Description:

Secure the Drywell Purge Lineup using SO 78.4.A-2, "Containment Atmosphere De-lnerting and Purging Via SBGT System" Cause: N/A Effect: N/A Time Position Applicant's Actions or Behavior PRO Place the standby Drywell Purge fan in OFF.

Stop the running Drywell Purge fan.

Acknowledge and report alarm 220 G-4, "LOW DRYWELL TO TORUS DIFFERENTIAL PRESSURE". (Expected alarm for securing the purge lineup.)

Shutdown the SBGT system:

Take the SBGT fan control switch to STOP then to AUTO.

Close '"A' filter Inlet A0-00475-1 Valve" then place the control switch to AUTO.

Close '"A' filter Outlet A0-00475-2 Valve" then place the control switch to AUTO.

Acknowledge and report alarm 216 A-5, "STANDBY GAS TREATMENT FILTERS NOT IN AUTO". (Expected alarm for moving the control switch back to the AUTO position.)

Close A0-20459 "D/W Purge" on panel 20C012.

Close A0-20460 "D/W Purge" on panel 20C012.

Verify HCS-00522-1 is open on panel OBC452.

Close the following valves:

A0-2505, "D/W Air Purge Inlet Valve"

A0-2520, "D/W Air & N2 Purge Valve"

A0-2506, "Drywell Ventilation INBD 18" Vent Valve"

A0-2507, "Drywell Ventilation OUTBD 18" Vent Valve"

A0-2521A, "Torus Air Purge Outboard Valve"

A0-2521 B, "Torus Air & N2 Purge INBD Valve"

A0-2511, 'Torus Ventilation INBD 18" Vent Valve"

A0-2512, "Torus Ventilation OUTBD 18" Vent Valve

A0-20469-1, "D/W Rx BLDG Equip Exh"

A0-20469-2, "D/W Rx BLDG Equip Exh" Direct an Equipment Operator to close and lock HV-2-36B-23840A (Step 4.22.11) and HV-2-36B-23840D (Step 4.22.12).

8

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 1 Event No. 1 Page: 2of18 Event

Description:

Secure the Drywell Purge Lineup using SO 78.4.A-2, "Containment Atmosphere De-lnerting and Purging Via SBGT System" (continued)

Time Position Applicant's Actions or Behavior URO Continue to monitor RPV level and power.

Provide peer checks to the PRO as directed.

CRS Monitor PRO actions.

9

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 1 Event No. 2 Page: 3of18 Event

Description:

Failure of a Primary Containment isolation valve Cause: Valve A0-2506 boot seal fails Effect: Tech spec required entry for a failed PCIV Time Position Applicant's Actions or Behavior PRO When the Operator begins to secure SBGT by securing the SGBT fan, recognize by reporting the "DRYWELL VENT VALVES OPEN" alarm (225 A-3).

Enter and execute ARC 225 A-3.

Recognize by reporting that A0-2506, "Drywell INBD 18" Vent" indicates mid position.

Direct an Equipment Operator to monitor boot seal pressure.

Verify the A0-2507, "Drywell OTBD 18" Vent Valve" is closed to isolate the Primary Containment penetration.

CRS Enter and execute ARC 225 A-3.

Determine that A0-2506, "Drywell INBD 18 Vent" is INOP.

Enter Tech Specs 3.6.1.3, PCIVs and determine that 3.6.1.3.A applies and the penetration must be isolated within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Verify the A0-2507 "Drywell OTBD 18" Vent Valve" is closed to isolate the Primary Containment penetration.

10

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 1 Event No. 3 Page: 4of18 Event

Description:

Power ascension with Control Rods Cause: N/A Effect: Raise power above 4% for T-101 entry and ATWS response in events 8 and 9.

Time Position Applicant's Actions or Behavior CRS Direct the URO to commence rod withdrawal in accordance with the Startup REMA and the Startup Sequence beginning with Rod Group 8, control rod 10-19 to achieve 2 bypass valves open.

URO Withdraw the following Control Rods 10-19, 18-51, 42-11, 42-51, and 18-11.

Withdraw control rods selecting the rod on the matrix and then using the Single Notch Withdrawal switch to withdraw control rods to position 10 then position 12.

Monitor nuclear instrumentation and reactor power during control rod withdrawal.

Withdraw Control Rod 18-35 to position 14 then to position 48.

Withdraw Control Rod 42-27 to position 14 then to position 48.

Withdraw Control Rod 42-35 to position 14. (When Control Rod 42-35 is notched out to position 14, Event 4 will occur.)

PRO Monitor balance of plant conditions during rod withdrawal.

Peer Check rod motion as directed by CRS.

11

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 1 Event No. 4 Page: 5of18 Event

Description:

Mispositioned Control Rod (ON-122, "Mispositioned Control Rod")

Cause: RMCS timer failure Effect: Control rod 42-35 will withdraw from the core beyond the expected single notch.

Time Position Applicant's Actions or Behavior URO Recognize by reporting the mispositioned control rod.

Recognize the mispositioned rod as a symptom for entry into ON-122, "Mispositioned Control Rod".

Halt all control rod motion and power changes not directed by ON-122.

Notify Shift Management.

Move Control Rod 42-35 back to position 12.

Notify the Reactor Engineers of the mispositioned Control Rod CRS Enter and execute ON-122, "Mispositioned Control Rod".

Notify the Reactor Engineers of the mispositioned Control Rod.

PRO Peer Check rod movement as directed by the CRS.

12

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 1 Event No. 5 Page: 6of18 Event

Description:

Steam Supply valve for the in-service Air Ejector fails closed (PRA)

Cause: Failure of the normal air supply to steam valve A0-2466A.

Effect: Air Ejector Supply pressure goes to 0 psig Main Condenser Vacuum begins to drop slowly Time Position Applicant's Actions or Behavior PRO/URO Recognize by reporting the following alarms 204 D-5, "SJAE DISCHARGE HI/LO PRESSURE".

201 H-3, "H2 WATER CHEMISTRY SYSTEM TROUBLE".

003 E-3, "2 UNIT OFF GAS RECOMBINER TROUBLE".

218 E-2, AIR EJECTOR DISCHARGE RADIATION HIGH".

Recognize by reporting the drop in Man Condenser vacuum.

Recognize the drop in Main Condenser Vacuum as an entry into OT-106, "Condenser Low Vacuum".

Enter and execute OT-106.

CRS Enter and execute OT-106 Direct the PRO to perform step 3.8 of OT-106 to place the Alternate air supply in-service.

PRO Place control switch "Alt Instr Air A0-2-08A-2466A" to OPEN.

Verify A0-2-08A-2466A indicates open at Panel 20C006B.

Place PIC-2239A, "A Steam Press" in MANUAL.

Restore SJAE steam supply pressure to between 115 and 125 psig.

The Crew may elect to restore the Air Ejector system using SO BA.6.A-2, "Placing the Standby SJAE in Service and Placing the In-Service SJAE in Standby" instead of OT-106, "Condenser Low Vacuum". If that is the case then the crew will perform the below steps.

CRS Direct the PRO to place the "B" SJAE in-service with SO 8A.6.A-2, "Placing the Standby SJAE in Service and Placing the In-Service SJAE in Standby".

13

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 1 Event No. 5 Page: 7of18 Event

Description:

Steam Supply valve for the in-service Air Ejector fails closed (PRA) (continued)

Time Position Applicant's Actions or Behavior PRO Verify M0-21048, "SPE 8 Isolation" is OPEN.

Verify M0-21058, "SJAE 8 Isolation" is OPEN.

Verify PIC-22398 is in MANUAL at panel 20C007A.

Verify PIC-22398 'S' setpoint is at 120 psig.

Verify PIC-22398 'V' Output Valve signal is at the MINIMUM positon.

Open A0-2244/45/478, "Air Ejector Inlet 8 2nd Stage".

Direct an Equipment Operator to adjust HCS-2-BA-24668, "Main Steam Isolation Valve to SJAE 28" to 35 to 40 psig.

Verify PIC-22398 is in MANUAL and slowly raise the output valve signal 'V' on PIC-22398 to slowly open CV-2-BA-22398.

Observe rising pressure on Pl-24728 on panel 20C0068.

Raise pressure slowly in 20 psig increments over several minutes until steam pressure is 115 to 125 psig.

Verify process 'P' and setpoint 'S' vertical bars matched and place PIC-22398 in "AUTO".

In necessary, then lower SJAE steam supply pressure as necessary on PIC-22398 to reduce SJAE steam supply pressure when 2nd stage vacuum for Standby SJAE is indicated on Pl-22468.

When SJAE 2nd Stage vacuum is greater than 13 inches Hgv on Pl-22468 at panel 20C0068 for the Standby SJAE, then OPEN A0-2238D/E/F, "Air Ejector Inlet 8 1st Stage" and A0-25408, "Air Ejector Inter Cdsr Drain".

When steam pressure reaches 115 to 125 psig, then place the control switch for A0-2236D/E/F, "Air Ejector Off-Gas Inlet 8" in "AUTO" 14

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 1 Event No. 6 Page: 8of18 Event

Description:

Spurious start of A and C Core spray and a leak of the discharge of the "A" Core Spray pump Cause: Short in the manual initiation pushbutton logic Effect: Start of the A and C Core Spray pumps A Core Spray pump Room Flood Alarm Time Position Applicant's Actions or Behavior PRO Recognize and Report alarms

223 A-5, "SYSTEM I CORE SPRAY TEST I ARMED".

223 A-1, "A CORE SPRAY PUMP AUTO START'.

224 A-1, "C CORE SPRAY PUMP AUTO START'.

223 D-5, "A CORE SPRAY PUMP ROOM FLOOD".

Enter and execute ARCs

223 A-5, "SYSTEM I CORE SPRAY TEST I ARMED".

223 A-1, "A CORE SPRAY PUMP AUTO START'.

224A-1, "C CORE SPRAY PUMP AUTO START'.

223 D-5, "A CORE SPRAY PUMP ROOM FLOOD".

Direct an Equipment Operator to investigate the "A" Core Spray Pump Room for Flooding.

URO Recognize by reporting the following alarms:

217 B-4, "A COOL TWR FANS TROUBLE".

217 C-4, "B COOL TWR FANS TROUBLE".

217 D-4, "C COOL TWR FANS TROUBLE".

Recognize by reporting that the Cooling Towers are out of service.

15

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 1 Event No. 6 Page: 9of18 Event

Description:

Spurious start of A and C Core spray and a leak of the discharge of the "A" Core Spray pump (continued)

Time Position Applicant's Actions or Behavior CRS Enter and execute T-103 "Secondary Containment Control" Direct an Equipment Operator to monitor "A" Core Spray Pump room water level.

Monitor Torus water level on PMS or at panel 20C003-3.

Direct the PRO to secure the Core Spray pumps and close the "A" Core Spray Suction Valve (M0-2-14-007A).

Evaluate Tech Specs 3.5.1, "ECCS Operating" 3.5.1.A, determine that the "A" Core Spray loop must be returned to operable within 7 days.

The CRS may consider racking out the "A" Core Spray pump breaker using SO 54.7.C, "4KV Breaker Rack-out/Rack-in". If so, then direct the PRO to rack out the "A" Core Spray pump breaker.

PRO Monitor Torus water level on PMS or at panel 20C003-3.

When directed secure the A and C Core Spray pumps.

When directed close M0-2-14-007A, '"A' Core Spray Pump Suction"' by inserting and turning a key for the suction valve control.

If directed to rack out the "A" Core Spray pump breaker, then direct an Equipment Operator to perform SO 54.7.C, "4KV Breaker Rack-out/Rack-in".

16

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 1 Event No. 7 Page: 10of18 Event

Description:

Startup level control valve fails closed (PRA)

Cause: Failure of the control signal cable Effect: RPV level will begin to lower Time Position Applicant's Actions or Behavior URO Recognize by reporting alarm 201 H-1, "FEEDWATER FIELD INSTRUMENT TROUBLE".

Recognize by reporting the lowering RPV level.

Recognize the lowering RPV level as an entry into OT-100, "Reactor Low level".

Enter and execute OT-100.

Recognize the failure of the Startup Level Controller.

Place the Startup Level controller in manual.

Recognize that the Startup level control valve will not control in manual.

Stabilize RPV level using the "C" RFP discharge valve and RFP speed.

CRS Enter and execute OT-100.

Direct the URO to place the Startup Level Controller in manual to control level if not already completed.

PRO Provide peer checks as directed by the CRS.

17

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 1 Event No. 8 Page: 11 of 18 Event

Description:

Steam Leak in the Drywell with a failed open Torus to Drywell Vacuum Breaker Cause: An unidentified steam leak occurs in the Drywell.

A Torus to Drywell Vacuum Breaker sticks when it opens and will not rec lose.

Effect: Containment pressure will rise. The suppression capability of the Drywell will not function allowing Drywell pressure to continue to rise. If Containment sprays are not placed in-service the Pressure Suppression Capability of the Drywell will be lost.

Time Position Applicant's Actions or Behavior URO/PRO Recognize by reporting the following alarms:

225 A-4, "DRYWELL HI/LO PRESS"

210 F-2, "DRYWELL HI/LO PRESS" Recognize drywell pressure is rising and announce entry into OT-101 "High Drywell Pressure".

Trend the drywell pressure rise.

CRS Enter/direct actions in accordance with OT-101 "High Drywell Pressure":

Verify drywell inerting is not in progress.

Direct Maximizing drywell cooling using RRC 44A.1-2 "Maximize Drywell Cooling".

Direct actions to monitor components e.g., RRP seals.

Direct Crew to isolate and restore systems IAW OT-101 to stop the source of the leak, including:

RWCU, HPCI and RCIC (i.e. close HPCI M0-15 steam supply valve, close RCIC M0-15 steam supply valve ... ).

When Drywell pressure cannot be maintained below 1.2 psig, direct a GP-4, "Manual Reactor Scram".

18

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 1 Event No. 8 Page: 12of18 Event

Description:

Steam Leak in the Drywell with a failed open Torus to Drywell Vacuum Breaker (continued)

Time Position Applicant's Actions or Behavior PRO Perform OT-101 actions as directed:

Monitor drywell pressure and plant parameters.

If directed, verify drywell inerting is not in progress.

If directed, maximize drywell cooling using RRC 44A.1-2 "Maximize Drywell Cooling".

Start the 2C DWCW pump by taking the control switch to RUN.

Start the 2C Drywell Chiller by taking the control switch to RUN.

If Drywell pressure is above .75 psig then direct an Equipment Operator to place the speed control switches for all of the Drywell Cooler Fans that are not running to SLOW speed.

Direct an Equipment Operator to raise the load setting on the "C" Drywell Chiller.

Place all Drywell Cooler Fan control switches to RUN.

Monitor components for abnormal indications as directed by the CRS.

Isolate plant systems, including RWCU, HPCI, and RCIC, as directed by the CRS IAW OT-101 (i.e. close HPCI M0-15 steam supply valve, close RCIC M0-15 steam supply valve ... ).

URO Perform GP-4 "Manual Reactor Scram" actions:

Place the mode switch to "Shutdown".

Verify control rods inserting.

Verify APRMs are downscale.

Report to the CRS that control rods have not inserted and that the APRMs are not downscale.

19

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 1 Event No. 8 Page: 13of18 Event

Description:

Steam Leak in the Drywall with a failed open Torus to Drywall Vacuum Breaker (continued)

Time Position Applicant's Actions or Behavior PRO Perform scram actions per RRC 94.2-2 "Plant Reactor Operator Scram Actions".

Verify all isolations.

Restore Instrument Nitrogen to the drywell when directed by the CRS using RRC 94.2-2 "Plant Reactor Operator Scram Actions".

Recognize and respond to 2 psig drywell pressure and announce entry into T-101 "RPV Control" and T-102 "Primary Containment Control".

CRS Enter and execute T-101, "RPV Control".

May enter T-117, "Level Power Control" if Control Rods are not inserting with ARI before the entry step for T-117 is reached in T-101.

Enter and Execute T-101, RPV Control and T-102, Primary Containment Control when Drywell pressure reaches 2 psig.

Verify adequate RPV level control and direct the PRO to secure HPCI.

If entered, exit T-117, "Level Power Control" when control rods are inserted with ARI.

Verify adequate RPV level control and direct the PRO to secure the RHR and Core Spray pumps.

Direct URO/PRO to perform T-223 "Drywell Cooler Fan Bypass" to bypass and restore drywell ventilation.

20

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 1 Event No. 8 Page: 14 of 18 Event

Description:

Steam Leak in the Drywell with a failed open Torus to Drywell Vacuum Breaker (continued)

Time Position Applicant's Actions or Behavior URO/PRO Recognize and verify Group 11/111 isolations.

Recognize and report the HPCI auto start at 2 psig Drywell pressure.

Trend and report containment parameters.

Recognize and verify Diesel Generators start at 2 psig Drywell pressure and have cooling water.

Recognize and report Core Spray and RHR pumps auto start when Drywell pressure reaches 2 psig and Reactor pressure is less than 450 psig.

Perform T-223:

Verify T-223 requirements.

Verify operation on the safe side of Figure 1 "DWCW Saturation Curve".

Place all Drywell Cooler Control Switches in "OFF".

Momentarily place "D/W Cooler Fans 43-S-J165" control switch in "BYPASS" and allow it to spring return to "NORMAL".

o Verify the Amber light above the "D/W Cooler Fans 43-S-J 165" control switch is lit.

o "DRYWELL COOLER FAN TRIP BYPASS" alarm in up on panel 207 B-2.

Direct EO to place drywell fans in slow.

Operate the Drywell Cooler Fans, as necessary to reduce Drywell pressure and temperature.

21

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 1 Event No. 8 Page: 15 of 18 Event

Description:

Steam Leak in the Drywell with a failed open Torus to Drywell Vacuum Breaker (continued)

Time Position Applicant's Actions or Behavior PRO Perform isolation or shutdown of HPCI as directed by the CRS.

For isolation, depress the HPCI isolation pushbutton and verify that HPCI shuts down and the HPCI Steam Line Isolation Valves close.

For a HPCI shutdown:

o Place the HPCI aux oil pump control switch to start.

o Depress and hold the HPCI trip pushbutton.

o Verify that the HPCI aux oil pump starts as HPCI turbine speed drops.

o When the indication for HPCI sped reached 0 RPM then place the HPCI Aux Oil Pump in Pull-to-Lock and release the HPCI trip pushbutton.

Shutdown Core Spray and RHR pumps as directed by the CRS.

22

ES-D-2 Operator Actions OP Test No. Scenario No. 1 Event No. 9 Page: 16of18 Event

Description:

ATWS Cause: Failure of the Automatic and Manual scram logic.

Effect: Control Rods will not insert using the manual scram pushbuttons or with the mode switch Control Rods will insert with ARI Time Position Applicant's Actions or Behavior CRS Direct the URO to initiate ARI UROCT Initiate ARI using RRC 38.1-2 "Alternate Rod Insertion During a Plant Event" when directed:

Rotate the Arming collar clockwise for the "A" and "B" ARI initiation pushbuttons.

Depress the "A" and "B" ARI initiation pushbuttons.

Recognize by reporting that the scram air header is depressurizing.

Recognize by reporting that the control rods are inserting.

Report that all of the control rods are inserted.

23

ES-D-2 Operator Actions OP Test No. Scenario No. 1 Event No. 10 Page: 17 of 18 Event

Description:

RHR pump in Drywall Spray trips Cause: Instantaneous overcurrent trip of the RHR pump selected for Containment Spray Effect: Containment Spray will be lost, requiring the crew to realign Containment Sprays with a different RHR pump.

Time Position Applicant's Actions or Behavior CRS When Torus pressure exceeds 2 psig, direct the PRO to spray the Torus using T-204, "Initiation of Containment Sprays using RHR".

Direct the PRO to start a different RHR pump to reestablish Torus Sprays.

When plant conditions permit, direct the PRO to spray the Drywall using T-204, "Initiation of Containment Sprays using RHR".

PRO When directed, perform Torus Sprays IAW T-204 "Initiation of Containment Sprays using RHR":

Place keylock switch 10A-S18A(B), Containment Spray Override 2/3 Core Coverage" in MANUAL OVERRIDE

Momentarily place the S17A/B switch in "MAN".

Open M0-39A(B) "Torus Hdr. Valve".

Open M0-89C(D) "HPSW Outlet Valve"

Start a HPSW pump in the respective loop.

Start an RHR pump in the respective loop.

Throttle open M0-38A(B) to obtain 1000 gpm on Fl-2 136A(B).

CT When directed, perform Drywall Sprays IAW T-204 "Initiation of Containment Sprays using RHR":

Verify both Recirc pumps are off.

Verify all Drywall Cooling fan Switches are in Off

Open M0-31A(B), "D/W Spray Inboard".

Open M0-26A(B), "D/W Spray Outboard"

Monitor Torus and Drywall pressure.

Report the drop in Primary Containment pressure.

Recognize by reporting the trip of the RHR pump.

When directed, spray containment using another RHR pump or the other loop.

24

ES-D-2 Operator Actions OP Test No. Scenario No. 1 Event No. 10 Page: 18of18 Event

Description:

RHR pump in Drywell Spray trips Time Position Applicant's Actions or Behavior PRO Spray Containment with the other RHR pump in the same loop as follows:

Close M0-2-10-034A(B), "Full Flow Test".

Close M0-2-10 89A(B, C, D), "HPSW HX Out".

Close M0-2-10-031A(B), "D/W Spray Inboard".

Close M0-2-10-026A(B), "D/W Spray Outboard".

Open M0-2-10-89A(B, C, D), "HPSW HX Out"

Start 2A,(B, C, D) HPSW pump.

Start the other RHR pump.

Throttle open M0-38A(B) to obtain 1000 gpm on Fl-2 136A(B).

Open M0-31A(B), "D/W Spray Inboard".

Open M0-26A(B), "D/W Spray Outboard"

Monitor Torus and Drywell pressure.

Report the drop in Primary Containment pressure.

OR Spray Containment with the other RHR loop as follows:

Place keylock switch 10A-S18A(B), Containment Spray Override 2/3 Core Coverage" in MANUAL OVERRIDE

Momentarily place the S17A/B switch in "MAN".

Open M0-39A(B) "Torus Hdr. Valve".

Open M0-89C(D) "HPSW Outlet Valve"

Start a HPSW pump in the respective loop.

Start an RHR pump in the respective loop.

Throttle open M0-38A(B) to obtain 1000 gpm on Fl-2 136A(B).

Open M0-31A(B), "D/W Spray Inboard".

Open M0-26A(B), "D/W Spray Outboard"

Monitor Torus and Drywell pressure.

Report the drop in Primary Containment pressure.

TERMINATION CRITERIA:

The scenario may be terminated when Primary Containment pressure is stable due to spraying containment.

25

Appendix D Scenario Outline ES-D-1 Simulation Facility Peach Bottom Scenario No. #2 Op Test No. NRC Examiners Operator - - - - - - - CRS (SRO)

- - - - - - URO (ATC)

_ _ _ _ _ _ PRO (BOP)

Scenario The scenario begins with the reactor at 100% power with the 'B' Electrohydraulic Summary Control (EHC) pump and the E-332 breaker are blocked out of service for scheduled maintenance.

After taking the shift, the Crew will perform the Master Trip Solenoid Valve Routine Test RT-0-01 D-402-2.

Shortly after this, the E-4 diesel generator will inadvertently start, requiring the Crew to shut down the E-4 diesel generator from the main control room and apply Technical Specifications for an inoperable diesel generator.

Following the diesel generator inoperability there will be a loss of the 250 VDC bus that supplies power to the RCIC system. The Crew must recognize the loss of DC power and apply Technical Specifications for the inoperable DC power supply.

Following the 250 VDC bus inoperability, the in-service Turbine Building Closed Cooling Water (TBCCW) pump trips on overload and the standby TBCCW pump fails to automatically start. The Crew should place the standby pump in service by placing its control switch to start and monitor the system pressure and temperature.

Shortly after the TBCCW system is restored the Crew should recognize and respond to lowering main condenser vacuum caused by air in-leakage. The Crew will be able to stabilize the plant with the existing air in-leakage by entering OT-106 "Condenser Low Vacuum" and reducing reactor power in accordance with GP-9-2 "Fast Power Reduction". During the power reduction a reactor feed pump will not automatically respond requiring the Crew to take manual control and reduce feed pump flow to avoid a main turbine trip on high reactor water level.

Following the power reduction, a high vibration condition for the main turbine will occur, requiring the Crew to scram the reactor and trip the main turbine. A CRD hydraulic malfunction will result in an ATWS, requiring the Crew to execute T-101 "RPV Control" and T-117 "Level/Power Control."

A failure of the only available EHC pump will cause the turbine bypass valves to close, requiring the Crew to utilize SRVs for reactor pressure control. The Crew should perform T-220 "Driving Control Rods During Failure to Scram" and T-216 "Control Rod Insertion by Manual Scram or Individual Scram Test Switches" to insert control rods. (Critical Task; Attempt to shutdown the reactor by performing one or more of the following: T-216 "Control Rod Insertion by Manual Scram or Individual Scram Test Switches", T-220 "Driving Control Rods During Failure to Scram", T-246, "Maximizing CRD Flow to the Reactor Vessel", "Initiating Standby Liquid Control before Torus temperature 2015 NRC Scenario #2 D-1 Rev 2

Appendix D Scenario Outline ES-D-1 exceeds 110°F"). The scenario may be terminated when the Crew has control of RPV power and level using T-240 "Termination and Prevention of Injection into the RPV" and the Crew is inserting control rods. (Critical Task; Before violating the Heat Capacity Temperature Limit (HCTL) curve,, perform T-240 "Terminating and Preventing Injection Into the RPV" to protect Primary Containment until: Reactor power is below 4% or RPV level reaches -172 inches or All SRVs remain closed and Drywell pressure is below 2 psig.)

Initial IC-14, 100% power Conditions Turnover Reactor power is 100% power.

'B' Electrohydraulic Control (EHC) pump blocked out of service for scheduled maintenance.

E-332 breaker is blocked out of service for scheduled maintenance.

Perform the Master Trip Solenoid Valve Routine Test RT-0-01 D-402-2.

2015 NRC Scenario #2 D-1 Rev 2

Appendix D Scenario Outline ES-D-1 Event Malfunction Event Event No. No. Type* Description 1 See Scenario Guide N PRO Perform the master trip solenoid valve routine test CRS 2 See Scenario Guide I PRO E4 diesel generator spurious start I diesel generator manual TS CRS shutdown (Tech Spec) 3 See Scenario Guide TS CRS Loss of 250 VDC bus I RCIC becomes unavailable (Tech Spec) 4 See Scenario Guide c PRO In service Turbine Building Closed Cooling Water (TBCCW)

CRS pump trips on overload I Failure of standby TBCCW pump to automatically start 5 See Scenario Guide R URO Main condenser air in-leakage causes lowering condenser vacuum I GP-9 fast power reduction (with Recirc) 6 See Scenario Guide c URO Reactor feed pump does not respond to lowering power change I must place in manual to control 7 See Scenario Guide c URO Main turbine high vibration I reactor scram CRS 8 See Scenario Guide M ALL ATWS (hydraulic) 9 See Scenario Guide c PRO Remaining EHC pump trips causing loss of main turbine bypass valves I control reactor pressure with HPCI and/or SRVs

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor, (TS) Tech Spec 2015 NRC Scenario #2 D-1 Rev 2

SIMULATOR OPERATOR INSTRUCTIONS FOR 2015 NRC SCENARIO #2 GENERAL REQUIREMENTS

Recorders will be rolled prior to the scenario and paper from selected recorders will be retained for the examination team as requested.

All procedures, flow charts, curves, graphs, etc. will be in their normal storage places.

All markable procedures, boards, etc. will be erased.

All paper used by the crew will be retained for the examination team as requested.

The simulator operators will keep a log of all communications during the scenario as requested by the examination team.

SCENARIO SOURCE HISTORY

This scenario is modified from the 2009 cert exam.

INITIAL SETUP Initial Conditions

IC-14 100% Power

Ensure that Reactor Recirc pump speeds are less than 1665 rpm

Ensure recorder power is on; roll recorders as required

Ensure annunciator horns are active Blocking Tags

Apply Information Tag to the 28 EHC Pump control switch

Apply Information Tag to Annunciator 205 K-3 EHC STANDBY PUMP NOT IN AUTO

Apply Information Tag to the E-332 breaker control switch.

Activate APP "2015_NRC_SCN2" or insert the following:

Event Triggers TRG 1 FALSE TRG 2 FALSE TRG 3 FALSE TRG 4 FALSE TRG 5 FALSE TRG 6 RPV_LEVEL_L T_ -60 TRG 7 REACTOR_MODE_SWITCH_NOT_IN_RUN

Malfunctions IMF IPM03 98 "Hydraulic ATWS" IMF FWC01A 73 "'A' Local Controller Failure" IMF TBW048 "B' TBCCW pump fails to auto-start" IMF DCD01A (E2) "RCIC 250 VDC failure" IMF TBW01A (E3) "'A' TBCCW pump trip" IMF CAR01 (E4) 2 "Main Condenser air in-leakage" at 2% severity IMF MTA02B (E5) 100 10:00 "Main Turbine bearing 'B' high vibration" IMF MTA02C (E5) 100 10:00 "Main Turbine bearing 'C' high vibration" IMF EHH04A (E6 2:00 0) "2A EHC pump trip" 2 minutes after RPV level < -60 inches IMF EHH02A (E6 4:00 0) "'A' Bypass valves fail closed" 4 minutes after RPV level < -60" IMF EHH02B (E6 4:00 0) '"B' Bypass valves fail closed" 4 minutes after RPV level < -60" IMF EHH02C (E6 4:00 0) "'C' Bypass valves fail closed" 4 minutes after RPV level < -60" IMF EHH02D (E6 4:00 0) "'D' Bypass valves fail closed" 4 minutes after RPV level < -60" IMF EHH02E (E6 4:00 0) "'E' Bypass valves fail closed" 4 minutes after RPV level < -60" IMF EHH02F (E6 4:00 0) '"F' Bypass valves fail closed" 4 minutes after RPV level < -60" IMF EHH02G (E6 4:00 0) "'G' Bypass valves fail closed" 4 minutes after RPV level < -60" IMF EHH02H (E6 4:00 0) "'H' Bypass valves fail closed" 4 minutes after RPV level< -60" IMF EHH021 (E6 4:00 0) "'I' Bypass valves fail closed" 4 minutes after RPV level < -60" Overrides IOR ZLOTC08A2BP17_1 OFF (Block 2B EHC pump green light)

IOR ZYP01A6S39 STOP (Block 2B EHC pump control switch)

IOR ZLOED6C21521701_1 OFF (E-332 BKR Lights (Green)

IOR ZYP04A6S01 TRIP (E-332 BKR Control Switch)

IOR ZYP04A8S04 (E1 0 2) START (E-4 DG QUICK START pushbutton)

Trip Overrides None Expert Command TRG 7 = DMF IPM03 Turnover Procedures

RT-0-01 D-402-2 "Master Trip Solenoid Valves Operability Test" 2

SIMULA TOR OPERATOR DIRECTIONS EVENT 1 Master Trip Solenoid Valves Routine Test - Support the crew as necessary for the Master Trip Solenoid Valves Routine Test.

EVENT 2 E4 Diesel Generator Spurious Start - Following completion of the Master Trip Solenoid Valves RT, or when directed by the Lead Examiner, initiate ET1 (IOR ZYP04A8S04 START) to cause a spurious start of diesel generator E4.

After the E4 diesel starts, verify override ZYP04A8S04 is deleted.

If asked to perform a running inspection on the E4 Diesel Generator, wait approximately 1O minutes and report that the E4 diesel is running but that there is a fuel oil leak and recommend that the DIG be secured.

If directed to trip the fuel racks for the E-4 Diesel Generator, wait approximately 1 minute and enter IMF DGA01 D "Diesel Generator "D" Fails to Start" and report that the fuel racks are triped.

With the concurrence of the Lead Examiner and acting as the Shift Manager, prompt the CRS to remove the E-4 diesel generator from service if progress is not being made by the Crew to remove the Diesel Generator from service.

EVENT 3 Loss of 250 VDC - When the CRS completes the Tech Spec determination or at the direction of the Lead Examiner, initiate ET2 (IMF DCD01A) to cause a trip of the RCIC 250 voe bus.

Support the crew in responding ARC 209 (C-2) "2 DA RCIC 250 VDC BUS LO VOLTAGE" When directed to perform ARC 209 (C-2):

Wait approximately 2 minutes and report that Battery chargers 2AD003 and 2CD003 output voltage is 135 VDC,

Wait approximately 10 minutes and report that there are blown bus feed fuses at Panel 2AD018. Request Maintenance assistance.

3

SIMULA TOR OPERATOR DIRECTIONS EVENT 4 Loss of "A" TBCCW Pump - After the Tech Spec determination has been made, or as directed by the Lead Examiner, initiate ET3 (IMF TBW01A) to trip the 2A TBCCW pump. A pre-inserted failure (TBW04B) will prevent auto-start of the 28 TBCCW pump.

If directed to investigate the problems with the TBCCW pumps wait approximately 2 minutes and report that you don't know why the "B" TBCCW pump did not auto start.

Wait approximately another 2 minutes and report that the "A" TBCCW pump has tripped on overload and the pump motor smells like burnt insulation.

EVENT 5 Main Condenser Air In-leakage - When TBCCW flow is restored or at the direction of the Lead Examiner, initiate ET4 (IMF CAR01) to cause Main Condenser air in-leakage.

Support the crew for GP-9, "Fast Power Reduction". Role-play as the Transmission System Operator and Generation Dispatch Power System Director when called.

As soon as the crew begins to reduce reactor power, MMF CAR01 1 1 :00 0 to reduce the severity of the condenser in-leakage to 1% severity.

EVENT 6 "A" RFP Does Not Respond - "A" RFP will not respond in Auto during the power drop. The "A" RFP will not respond when control is transferred to Manual at the M/A station. RFP control will need to transferred to MSC control.

EVENT 7 After power is reduced, or as directed by the Lead Examiner, initiate ET5 (IMF MTA02B & IMF MTA02C).

If directed to investigate the Main Turbine, wait approximately five minutes and when# 2 bearing is above 225°F, report that oil flow to the #2 bearing is normal.

4

SIMULA TOR OPERA TOR DIRECTIONS EVENT 8 Hydraulic A TWS - Hydraulic A TWS occurs when the crew scrams the reactor.

When the mode switch is placed in SHUTDOWN (i.e., not in RUN), verify trigger ETS (DMF IPM03) deletes the ATWS malfunction.

When RPV level is lowered to -60 inches, verify trigger ET6 (IMF EHH04A) initiates a trip of the 'A' EHC pump 2 minutes later.

When requested to install jumpers to bypass ARI and RPS per T-216 steps 4.1 &

4.2, enter the following overrides:

MRF ARI01TO OVERRIDE "ARIA4-ARIA Relay Trip Override"

MRF ARI02TO OVERRIDE "ARIA4-ARIB Relay Trip Override" WAIT approximately 10 minutes and report to the MCR by phone or in person that jumpers for ARI (step 4.1) have been installed.

Enter the malfunction IMF RPSOS "RPS Automatic Scram Circuit Failure" WAIT approximately 5 minutes and report to the MCR by phone or in person that jumpers for RPS (step 4.2) have been installed.

When requested to T-221 step 4.1, enter the following Remote Function: T221_ 1 DEFEAT "Remove Low RPV Level/GP1 Isolation".

WAIT approximately 3 minutes and report to the MCR by phone or in person that jumpers T-221 (step 4.1) have been installed.

If directed to perform T-247, "Aligning CST Bottom Suction to Main Condenser Hotwell and CRD Pumps', wait approximately 7 minutes and report that the lineup is complete.

EVENT 9 Bypass Valves Fail Closed - Bypass valves fail closed due to a loss of EHC pressure.

When RPV level is lowered to -60 inches, verify trigger ET6 (IMF EHH04A) initiates a trip of the "A' EHC pump 2 minutes later.

TERMINATION The scenario may be terminated when the crew has:

Control of RPV power and level using T-240 "Termination and Prevention of Injection into the RPV" Control of RPV pressure with SRVs Torus cooling in-service Made attempts to shut down the Reactor with SBLC or Control Rods.

5

SHIFT TURNOVER PLANT CONDITIONS:

Unit 2 is at 100% power INOPERABLE EQUIPMENT/LCOs:

28 EHC pump is blocked OOS for micron filter replacement

E-332 breaker is blocked OOS for preventive maintenance of breaker cubicle SCHEDULED EVOLUTIONS:

Perform RT-0-01 D-402-2 "Master Trip Solenoid Valves Operability Test" SURVEILLANCES DUE THIS SHIFT:

None ACTIVE CLEARANCES:

28 EHC pump

E-332 breaker GENERAL INFORMATION:

None 6

CRITICAL TASK LIST

1. Before violating the Heat Capacity Temperature Limit (HCTL) curve, perform T-240 "Terminating and Preventing Injection into the RPV" to protect Primary Containment:

Reactor power is below 4%, OR

RPV level reaches -172 inches, OR

All SRVs remain closed and drywell pressure is below 2 psig.

(T-117-2)

2. Attempt to shutdown the reactor by performing one or more of the following:

T-216 "Control Rod Insertion by Manual Scram or Individual Scram Test Switches".

T-220 "Driving Control Rods During Failure to Scram".

T-246, "Maximizing CRD Flow to the Reactor Vessel".

Initiating Standby Liquid Control before torus temperature exceeds 110°F.

(T-101-4) 7

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 2 Event No.: 1 Page: 1of12 Event

Description:

Main turbine master trip solenoid valves routine test Cause: NIA Effects: N/A Position Applicant's Actions or Behavior CRS Direct PRO to perform RT-0-01 D-402-2 "Master Trip Solenoid Valves Operability Test".

PRO Perform RT-0-01 D-402-2 "Master Trip Solenoid Valves Operability Test":

Review RT

Place the Master Trip Test Selector switch to TRIP A

Verify "Test A" lamp if OFF

Release and place Master Trip Test Selector switch to RESET

Verify "Test A" lamp if ON

Place the Master Trip Test Selector switch to TRIP B

Verify "Test B" lamp if OFF

Release and place Master Trip Test Selector switch to RESET

Verify "Test B" lamp if ON

Complete RT paperwork CRS Review RT for completeness/satisfactory results.

URO Monitor plant parameters/assist as directed.

8

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 2 Event No.: 2 Page: 2of12 Event

Description:

E4 diesel generator spurious start Cause: Spurious automatic start signal Effects: 1. Alarm 005 F-4 "E4 Diesel Running".

2. The diesel will continue to run until manually shutdown .. .it should not be left running for long periods unloaded due to accumulation of oil in the exhaust manifold.

Time Position Applicant's Actions or Behavior PRO Acknowledge and report alarm 005 F-4 "E4 DIESEL RUNNING" and enter corresponding Alarm Response Card.

Recognize the E4 diesel is running unloaded.

Red flag the breaker for the E4 diesel.

Verify diesel automatic response using SO 528.1.8 "Diesel Generator Automatic Start".

Verify an ESW pump started.

Red-flag the ESW pump to remain in service.

Shutdown the remaining ESW pump.

Direct an Equipment Operator to perform a running inspection of the E-4 diesel generator.

CRS Per SO 528.1.8 (step 4.7), direct a shutdown of the E-4 diesel generator IAW the applicable steps of section 4.5 of SO 52A.1.8 "Diesel Generator Operations".

(May) direct placing the E4 diesel in Pull-to-Lock.

PRO Shutdown the E4 diesel IAW SO 52A.1.8:

Place the E4 diesel generator control switch to "STOP".

Shutdown the running ESW pump in accordance with SO 33.2.A.

Direct the Equipment Operator to continue with the E4 diesel shutdown in accordance with SO 52A.1.8, section 4.5.

Place the E4 diesel in Pull-to-Lock, as directed.

CRS Declare the E-4 diesel inoperable.

Review Tech Spec 3.8.1 and determine Condition 8 applies:

Verify alignment/availability of the Conowingo tie line immediately.

Verify breaker alignment for operable offsite circuits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Restore the E-4 diesel generator to operable status within 14 days.

9

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 2 Event No.: 3 Page: 3of12 Event

Description:

RCIC 250 VDC bus failure Cause: Blown RCIC 250 VDC bus fuses Effects: 1. Alarm 209 C-2 "2 DA RCIC 250 VDC Bus LO Voltage"

2. RCIC is inoperable and unavailable for operation Position Applicant's Actions or Behavior URO Reference ARC 209 (C-2) "2 DA RCIC 250 VDC BUS LO VOLTAGE" Dispatch Equipment Operator to perform ARC Operator Actions:

Check operation of battery chargers 2AD003 and 2CD003 (output voltage)

Check bus feed fuses at Panel 2AD018.

CRS Enter SE-13 "Loss of a 125 or 250 VDC Safety Related Bus" (there are no specific actions required by SE-13 for this event).

Refer to Tech Spec 3.8.7 D for RCIC 250 VDC Distribution System.

Determine that DC power must be restored in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

While not required the CRS may refer to TS 3.5.3 for RCIC and TS 3.6.1 for PCIS.

While not required, the Crew may test annunciators.

Request assistance for troubleshooting/investigation from Shift Manager.

10

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 2 Event No.: 4 Page: 4of12 Event

Description:

TBCCW pump trips with failure of the standby pump to auto-start Cause: Overload of 2A TBCCW pump due to excessive motor bearing friction Failure of PS-2131 to actuate on low TBCCW system pressure Effects: 1. Alarm: 217 C-5 "TURB BLDG COOLING WATER SUPPLY LO PRESS"

2. Loss of cooling to TBCCW loads Position Applicant's Actions or Behavior PRO Recognize annunciator 217 C-5 "TURB BLDG COOLING WATER SUPPLY LO PRESS" and report trip of 2A TBCCW pump. Respond IAW Alarm Response Card.

Place 2A TBCCW pump control switch to "OFF".

Recognize failure of 28 TBCCW pump to auto start after 20 seconds.

Start the 28 TBCCW pump as part of verifying automatic actions.

CRS Enter ON-118 "Loss of TBCCW" (may direct 28 TBCCW pump start from ARC 217 C-5 and not enter ON-118).

Direct starting the 28 TBCCW pump.

Direct follow-up use of SO 34.6.A-2 "Placing Standby TBCCW System Pump In Service".

Direct troubleshooting.

PRO Place 28 TBCCW pump control switch to "RUN".

Verify placing standby TBCCW pump in service IAW SO 34.6.A-2 "Placing Standby TBCCW System Pump In Service".

URO Monitor plant parameters/assist as necessary.

11

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 2 Event No.: 5 Page: 5of12 Event

Description:

Condenser air in-leakage I fast power reduction (w/ recirc)

Cause: Crack in condenser weld joint Effects: 1. Alarm 206 D-2, "Condenser Lo Vacuum"

2. Lowering main condenser vacuum, requiring a fast power reduction Time Position Applicant's Actions or Behavior URO/PRO Acknowledge, report alarms *and enter corresponding Alarm Response Card for the following alarms:

206 D-2, "CONDENSER LO VACUUM" Recognize and report lowering main condenser vacuum.

003 E-3, "2 UNIT OFF GAS RECOMBINER TROUBLE" Enter and execute OT-106, "Condenser Low Vacuum".

CRS Enter and execute OT-106, "Condenser Low Vacuum".

Direct the URO to reduce reactor power in accordance with GP-9-2, "Fast Power Reduction" until vacuum stops lowering.

URO Perform a fast power reduction in accordance with GP-9-2:

Lower recirculation flow as required to a value of 61.5 Mlbs/hr as read on Fr-2-02-3-095 at panel 20C05A.

Stop power reduction when main condenser vacuum stops lowering and/or begins to improve.

PRO Notify the Transmission System Operator and Generation Dispatch of the required power change.

12

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 2 Event No.: 6 Page: 6of12 Event

Description:

"A" Reactor Feedpump will not respond to changes in Reactor power Cause: Failure of the control signal Effects: The "A" RFP will not respond as Reactor power is reduced for the lower man condenser vacuum. The "8" and "C" RFPs will try to adjust for failure of the "A" RFP.

Time Position Applicant's Actions or Behavior URO Recognize by reporting alarm 201 H-1, "FEEDWATER FIELD INSTRUMENT TROUBLE" Enter and execute ARC 201 H-1 Recognize the failure of the "A" RFP to respond to lowering Reactor power.

Transfer control of the "A" RFP to manual on the M/A station using SO 6C.1.D-2, "Reactor Feedwater Automatic Level Control".

Recognize that the "A" RFP will not respond in manual control.

Transfer the "A" RFP to MSC control:

Press MSC select

Adjust speed using the raise/lower pushbuttons until the speeds are matched between the "A" RFP and the "B" and "C" RFPs.

CRS Enter and execute ARC 201 H-1 Direct that control of the "A" RFP be transferred to MSC if the URO has not already selected MSC.

PRO Peer check as directed by the CRS.

13

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 2 Event No.: 7 Page: 7of12 Event

Description:

Main turbine high vibration I reactor scram Cause: Failure of the #2 main turbine bearing Effects:

Alarm 205 A-2, "Turbine Vibration I Thrust High" Turbine bearing vibrations will rise.

Time Position Applicant's Actions or Behavior URO/PRO Recognize and report alarm 205 A-2, "TURBINE VIBRATION/THRUST HIGH.

Enter and execute ARC 205 A-2.

Check turbine lube oil temperature on TR-2401, and increase cooling water to lube oil coolers, if necessary.

Check vibration of the affected bearing on VR-2657.

Dispatch operator to check for proper oil flow and local temperature at the affected bearing.

CRS Direct operator actions IAW ARC 205 A-2, TURBINE VIBRATION/THRUST HIGH".

Direct the reduction of turbine load IAW GP-9-2, "Fast Power Reduction" (the CRS may go directly to GP-4 "Manual Reactor Scram").

URO Perform a GP-9-2 "Fast Power Reduction" as directed.

Perform a GP-4, "Manual Reactor Scram" as directed.

CRS When bearing vibration rises to 10 mils, then direct a manual scram IAW GP-4 "Manual Reactor Scram" (see next event).

14

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 2 Event No.: 8 Page: 8of12 Event

Description:

A TWS - hydraulic Cause: Control rods insert to various positions due to limited Scram Discharge Volume Effects: Requires the crew to take actions to terminate the ATWS, as well as control RPV level/power Position Applicant's Actions or Behavior URO Perform GP-4 "Manual Reactor Scram":

Reduce recirc flow controllers to minimum (20% demand)

Place the mode switch to "SHUTDOWN".

Verify control rods are inserting.

Report an ATWS is in progress with reactor power> 4% (T-101 entry condition).

PRO Perform GP-4 "Manual Reactor Scram":

Transfer 13 KV house loads using RRC 53.1-2.

Verify Group II & Ill isolations and SGTS initiation.

Verify HWC isolated.

CRS Enter/direct actions for T-101 "RPV Control":

Verify URO/PRO scram actions.

Direct tripping of the Main Turbine.

Direct RPV pressure stabilized below 1050 psig using EHC, SRVs and/or HPCI.

Following the PCIS GP II & Ill isolation, direct drywell instrument nitrogen restored.

Direct actions for the ATWS (see next page).

15

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 2 Event No.: 8 Page: 9of12 Event

Description:

ATWS - hydraulic (continued)

Position Applicant's Actions or Behavior PRO Trip the Main Turbine by depressing the "TRIP" pushbutton.

Stabilize reactor pressure below 1050 psig as directed.

Following the PCIS GP II & Ill isolation, bypass and restore drywell instrument nitrogen IAW RRC 16.1-2, "Bypass and Restore Instrument N2 Supply to the Drywell".

Place A0-2969A control switch to "CLOSE" on panel 20C03C.

Place A0-2969B control switch to "CLOSE" on panel 20C03C.

Place Drywell Instrument Nitrogen Bypass Switch 16A-S 100 in the "BYPASS" position on panel 20C05A.

Place Drywell Instrument Nitrogen Bypass Switch 16A-S99 in the "BYPASS" position on panel 20C05A.

Place A0-2969A control switch to "OPEN" at panel 20C03C.

Place A0-2969A control switch to "OPEN" at panel 20C03C.

CRS Direct T-101, actions:

Initiation of ARI

Trip recirc pumps at least 10 seconds apart OR verify the Recirc pumps are tripped (ARI or 13 KV fast transfer).

CT

SLC Injection

Enter T-117, "Level/Power Control CT

T-216, "Control Rod Insertion by Manual Scram or Individual Scram Test Switches" CT

T-220 "Driving Control Rods during Failure to Scram"

T-247, "Aligning CST Bottom Suction to Main Condenser Hotwell and CRD Pumps" 16

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 2 Event No.: 8 Page: 10of12 Event

Description:

ATWS- hydraulic (continued)

Time Position Applicant's Actions or Behavior URO Perform T-101, RC/Q actions:

Initiate ARI; report the scram air header is depressurized.

Trip Recirc pumps at least 10 seconds apart OR verify the Recirc pumps are tripped (ARI or 13 KV fast transfer).

CT

Initiate SLC by starting either SLC pump.

CT

Direct an Equipment Operator to perform T-216 steps 4.1and4.2 (install jumpers in Cable Spreading Room and Main Control Room to defeat ARI Initiation Logic and bypass all RPS Auto Scram signals).

CT

Per T-216 (on the 20C05A panel) o Reset ARI by placing ARI 'A' & '8' manual pushbutton collars in "Disarm".

o Depress the A & B ARI reset pushbuttons.

o Place the Scram Reset switch 5A-S9 to the "Group 1&4" and "Group 2&3" positions.

o Open Scram Discharge Volume inboard and outboard vents and drains.

CT

Perform T-220 "Driving Control Rods During Failure To Scram".

CRS Direct T-117 actions:

Inhibit ADS.

T-221 "Main Steam Isolation Valve Bypass".

CT

T-240 "Termination And Prevention Of Injection Into The RPV".

17

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 2 Event No.: 8 Page: 11 of 12 Event

Description:

ATWS- hydraulic (continued)

Position Applicant's Actions or Behavior URO/PRO Perform T-117 actions:

Inhibit ADS.

Direct Equipment Operator to perform T-221.

CT

Perform T-240: terminate and prevent injection from all injection sources; control RPV level below -60 inches and within the specific RPV level band directed by the CRS.

o Place HPCI Aux Oil Pump in the "Pull-to-Lock" position.

o Press "Emergency Stop" for all reactor feed pumps.

o Close reactor feed pump discharge valves M0-2149A, B, C.

o Verify closed M0-8090 "C RFP Discharge Bypass".

o Direct an Equipment Operator to secure ECCS Stayfull (considered to be complete when the direction is given).

When RPV level is below -60 inches, restore injection and maintain RPV level between -60 and -195 inches as follows:

Using Feedwater:

o Place LIC-8091 in "MAN" and close the valve.

o Open M0-8090 "C RFP Bypass".

o Raise RFP speed until discharge pressure is75-100 psig above RPV pressure.

o Control RPV injection by adjusting RFPT speed, OR LIC8091 setting, OR M0-2149C "RFP C Discharge" valve position.

Using HPCI (manual initiation):

o Arm and depress the "HPCI Manual Initiation" pushbutton.

o Verify M0-2-23-014 "Supply" opens.

o Verify the aux oil pump starts.

o Verify M0-2-23-019 "To Feed Line" opens.

o Verify vacuum pump starts.

o Verify A0-2-23-042 and A0-2-23-043 "Drain lsol to Mn Cndr" close.

o Adjust HPCI flow controller setpoint to the desired RPV injection rate.

18

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 2 Event No.: 9 Page: 12of12 Event

Description:

'A' EHC pump trips/ loss of turbine bypass valves Cause: 'A' EHC pump trips on overcurrent condition Effects: Complete loss of Turbine EHC System, which causes a turbine trip (if not already tripped) and closure of all bypass valves Time Position Applicant's Actions or Behavior URO/PRO Recognize loss of only available EHC Pump.

/CRS Recognize complete loss of EHC System and eventual loss of turbine bypass valves for RPV pressure control.

CRS Direct RPV pressure control using SRVs.

URO/PRO Control RPV pressure using SRVs to stay below 1050 psig, OR to stay on safe side ofT-102 Curve T/L-1 "SRVTail Pipe Limit", as applicable.

URO/PRO Place Torus cooling in service using RRC 10.1-2 (at panel 20C03)

Open M0-2-10-39A(B)

Open M0-2-32-89A (B, C, or D)

Start a HPSW Pump

Start an RHR Pump

Open M0-2-10-34A(B)

Place additional pumps in service as required TERMINATION CRITERIA:

The scenario may be terminated when the crew has:

Control of RPV power and level using T-240 "Termination and Prevention of Injection into the RPV" Control of RPV pressure with SRVs Torus cooling in-service Made attempts to shut down the Reactor with SBLC or Control Rods.

19

Tech Spec Error from NRC Exam Scenario 2 It was discovered during performance of NRC Scenario 2 that the Tech Spec determination for a loss of 250 VDC was wrong. The scenario described the Tech Spec decision as a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months required action per Tech Spec 3.8.7.D.

The scenario described the blown fuses as those providing power to the RCIC 250 VDC bus. In order for Tech Spec 3.8.7.d to be correct the blown fuses would have had to been for the 250 VDC distribution bus that connects the two 125 VDC battery chargers to the two 125 VDC batteries.

With the loss of power to the RCIC 250 VDC bus the correct Tech Specs should have been 3.5.3 for RCIC being INOP and 3.6.1.3 for INOP Primary Containment Isolation Valves. This was determined to be the correct course of actions by the Operation's Representative and the Shift Operations Superintendent.

Appendix D Scenario Outline ES-D-1 Simulation Facility Peach Bottom Scenario No. #4 Op Test No. 2015 NRC Examiners Operator - - - - - - - CRS (SRO)

URO (ATC)

PRO (BOP)

Scenario The scenario begins with the reactor at 100% power with the 'B' Emergency Summary Service Water (ESW) Pump in service for an evaluation of flow through the Emergency Diesel Generator heat exchangers.

Shortly after taking the shift the Crew will swap Electrohydraulic Control (EHC)

Pumps using procedure SO 1D.6.A-2 "Placing the EHC Oil System Standby Pump in Service". The 'B' EHC pump will be started and the 'A' EHC pump will be shut down.

Once the "B" EHC pump is in service, an Equipment Operator will report a Core Spray snubber is INOP. The CRS will review the TRM and Tech Spec and determine that the Core Spray loop is INOP.

After the Tech Spec determination is made, a high temperature condition will occur on the in-service RWCU pump. With the standby pump out of service the Crew will be required to remove the RWCU system from service.

After the RWCU system is removed from service a leak will develop on the discharge of the running 'B' ESW Pump requiring the Crew to recognize the condition and secure the 'B' ESW pump. The CRS should reference Technical Specifications for the inoperable ESW pump and also for inoperable fire barriers due to doors being intentionally left open in response to the flooding.

Once the Technical Specification determinations have been made, the running RBCCW pump will trip and the standby pump will fail to start, resulting in a complete loss of RBCCW. The Crew should reduce reactor power as directed by ON-113 "Loss of RBCCW." The Crew should reduce power using procedure GP-9 "Fast Power Reduction". As a result of the loss of RBCCW the 'B' Recirculation Pump will experience a mechanical seal failure which is the source of a steam leak into the primary containment. The Crew should enter procedure OT-101 "Drywell High Pressure". Temperatures on the recirculation pump will rise requiring the Crew to remove the pump from service and they should enter procedure OT-112 "Unexpected/Unexplained Change in Core Flow". When primary containment pressure reaches 1.2 psig the Crew will shut down the reactor using procedure GP-4 "Scram". When the Crew places the mode switch in shut down the control rods will not insert due to a failure of the reactor mode switch. Depressing the manual scram pushbuttons will insert the control rods.

(Critical Task; Shutdown the Reactor by depressing the Manual Scram Pushbuttons.)

The steam leak worsens. The Crew should execute proceduresT-101 "RPV Control" and T-102 "Primary Containment Control". The Crew should spray the primary containment using procedure T-204 "Initiation of Containment Sprays 2015 NRC Scenario #4 D-1Rev2

Appendix D Scenario Outline ES-0-1 Using RHR". (Critical Task; Spray the Drywell to (restore and) maintain Drywell Bulk Average Temperature below 281°F.) A Drywell Chilled Water system to RBCCW system leak will develop allowing steam to leak into the RBCCW Room outside of the primary containment. The Crew will need to isolate the RBCCW system using procedure GP-8.B "PCIS Isolation - Groups 2 and 3".

(Critical Task; Isolate RBCCW from the Drywell in the Control Room.)

The scenario may be terminated when the reactor is shut down with RPV level is under control, Primary Containment sprays are in service, and the RBCCW leak is isolated.

Initial IC-14, 100% power Conditions Turnover Unit 2 is at 100% power.

"B" RWCU pump is out of service.

There is a leak in the RBCCW system that requires the head tank to be filled every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The head tank was last filled 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ago.

The "B" ESW pump is in-service to do a flow evaluation of flow through the DIG heat exchangers. The test is expected to be completed within the hour.

Following turnover the PRO will be directed to place the "B" EHC pump in-service and secure the "A" EHC pump.

2015 NRC Scenario #4 D-1 Rev 2

Appendix D Scenario Outline ES-D-1 Event Malfunction Event Event No. No. Type* Description 1 See Scenario Guide N PRO Swap EHC Pumps CRS 2 See Scenario Guide TS CRS INOP Core Spray pump discharge snubber 3 See Scenario Guide c PRO RWCU pump motor high winding temperature, secure CRS RWCU.

4 See Scenario Guide c PRO 'B' ESW Room flood I secure the 'B' ESW Pump (Tech Spec)

TS CRS 5 See Scenario Guide R URO Loss of RBCCW I fast reactor power reduction (w/ recirc and CRS rods) 6 See Scenario Guide c URO 'B' Recirculation Pump seal failure I Steam leak in primary CRS containment 7 See Scenario Guide c URO Failure of the Recirc suction valve "M0-2-02-0438" to close CRS 8 See Scenario Guide I URO Failure to automatically scram (manual scram pushbuttons CRS are required to scram the reactor) 9 See Scenario Guide M ALL Steam leak worsens 10 See Scenario Guide M ALL Drywell to RBCCW leak I Steam leak in RBCCW Room outside of primary containment

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor, (TS) Tech Spec 2015 NRC Scenario #4 D-1 Rev 2

SIMULATOR OPERATOR INSTRUCTIONS FOR NRC SCENARIO #4 GENERAL REQUIREMENTS

Recorders will be rolled prior to the scenario and paper from selected recorders will be retained for the examination team as requested.

All procedures, flow charts, curves, graphs, etc. will be in their normal storage places.

All markable procedures, boards, etc. will be erased.

All paper used by the Crew will be retained for the examination team as requested.

The simulator operators will keep a log of all communications during the scenario as requested by the examination team.

SCENARIO SOURCE HISTORY

This scenario is a new scenario developed for the 2015 NRC exam.

INITIAL SETUP Initial Conditions

IC-14, 100% power

Start the "B" ESW pump.

Ensure recorder power is on; roll recorders as required

Ensure annunciator horns are active Blocking Tags

Block the "B" RWCU pump Activate NRC4 or insert the following:

Event Triggers ET1 False ET2 False ET3 False ET4 False ET5 OW- PRESSURE- GT- 16.4- ABSOLUTE ET6 OW- PRESSURE- GT 18 ABSOLUTE

Malfunctions IMF RBW01 A "RBCCW Pump "A" Trip" IMF RBW01 B (E3) "RBCCW Pump 'B' Trip" IMF RRS14B (E4) "Recirc Pump #2B Seal Failure" IMF RRS138 (E4) "Recirc Pump #1B Seal Failure" IMF MSS02 (E5) 2 15:00 0 "MSL Rupture Inside Primary Containment" IMF ARM01_11 (E6 10:00 0) 1 "RBCCW Room 116' Elev" IMF H112(EG10:000)100 "PMS Rad Level-RB 116' Elev RBCCW Pump Room" Overrides IOR ZYP02A4501 RUN "Reactor Mode Switch" IOR ZYP03A2523 OPEN "PMP Suction VLV (Loop B)"

IORZLOCU04ABP49_1 OFF "CU Recirc Pump B (Green)"

IOR AN0204RA1 (E1) ALARM_ON '"A' Clean-up Recirc Pump MTR WDG Temp High" IOR AN0226CA4 (E2) ALARM_ON "' B' ESW Pump Room Flooded".

IOR AN0212RG5 (E5) ALARM_ON "Reactor Building Cooling Water Header Tank Hi Lo Level" IOR ZAOSW12Pl2350 (E5) 0 "Reactor Building Cooling Water Heat Exchanger Outlet Header Pressure" Remote Functions MRF DGA06 Fail "DG Cooling water valve A0-33-0241 'A' Air Failure" Trip Overrides MRF RPS01 TO OVERRIDE, "RPS Auto Scram Ch A 1" MRF RPS02TO OVERRIDE, "RPS Auto Scram Ch A2" MRF ARI01 TO OVERRIDE, "ARIA4-ARIA Relay Trip Override" MRF ARI02TO OVERRIDE, "ARIA4-ARIB Relay Trip Override" Batch Files None Turnover Procedures None 2

SIMULATOR OPERATOR DIRECTIONS EVENT 1 Placing the "B" EHC Pump ln-serivce - Support the Crew as needed to place the "B" EHC pump in service and remove the "A" EHC pump from service using SO 1D.6.A-2, "Placing the Electrohydraulic Control Oil System Standby Pump In-Service".

If directed as an Equipment Operator to verify Pl-4403, "EHC Fluid Pump B Discharge Pressure" indication is less than 100 psig at the EHC skid, report that pressure is 75 psig.

If directed as an Equipment Operator to perform Step 4.3.4 to adjust the B EHC pump pressure compensator, wait approximately 2 minutes and report that local pressure indication has raised 2 psig.

If asked as the Equipment Operator to provide local discharge pressure, report that discharge pressure is 1555 psig.

If directed as an Equipment Operator to verify that the Micron filter element indicator, report that the indicator indicates green.

EVENT 2 Core Spray Snubber INOP - When the "B" EHC pumps is in-service or at the direction of the Lead Examiner, report to the control room as the Reactor Building Equipment Operator and report that you are in the 28 Core Spray Pump Room on elevation 116' and that all of the hydraulic fluid has leaked out of the 28 Core Spray pump discharge pipe snubber. Also report that you have isolated the oil leak and it has not gotten into any drains. If asked for a snubber identification number report it is 14-GB-5-33.

!Ethe Station Duty Manager is requested to support an operability determination for the 28 Core Spray loop, THEN report that the determination will require several hours to complete.

3

SIMULATOR OPERATOR DIRECTIONS EVENT 3 "A" RWCU Pump High Winding Temperature - When the Tech Spec determination is complete or at the direction of the Lead Examiner, initiate ET 1 (AN0204RA 1).

If directed to investigate the "A" RWCU Pump High Winding Temperature, wait approximately 3 minutes and report that the winding temperature is 140°F and rising.

If directed to determine the cause for the high temperature condition, wait approximately 5 minutes and report that you cannot find a reason for the high temperature condition.

If the Crew does not trip the "A" RWCU pump within 10 minutes of receiving the alarm, enter Malfunction IMF RWC01A, "RWC Pump

'A' Trip" and 1/0 Override, IOR AN0204RA2 ALARM_ON, "'A' Clean-up Recirc Pump Mtr Wdg Temp High-High".

4

SIMULATOR OPERA TOR DIRECTIONS EVENT 4 "B" ESW Room Flooding - When a RWCU is isolated or as directed by the Lead Examiner, initiate events on ET2. (AN0226CA4)

If directed to check the "B" ESW pump room, then wait approximately 4 minutes and report that there is a lot of water in the room; you cannot see the bottom step and the water level is above the bottom of the MCC (i.e., into the MCC). In addition, report you believe there is a shock hazard and you do not want to go any further into the room until the water is removed.

Report the source of the leak appears to be from the 'B' ESW pump discharge piping on the pump side of the discharge check valve and that water has sprayed onto the "B" ESW pump motor.

If the 'B' ESW pump is not tripped within 10 minutes of the flooding report, trip the pump using malfunction IMF ESW01 B.

If asked to identify the MCC in the area, report that it is E-124-P-A.

When directed, wait approximately 2 minutes and report that the door directed by the crew is open.

If directed to close the diesel generator cooling water lineup then wait approximately 6 minutes and MRF DGA06 NORM, and report that the cooling water lineup is returned to normal.

If the Crew directs an Equipment Operator to remove the feed for the "B" ESW pump, enter IOR ZLOSW26COBP57_1 OFF "C010 Emerg SW Pump 'B' (Green Light)" and IOR ZYP04A6S20 STOP "C010 Emerg SW Pump 'B' Control Switch" then report back that the feed has been removed.

EVENT 5 Loss of RBCCW Cooling - When the CRS has determined the Tech Spec and TRM requirements for the ESW flooding condition or at the direction of the Lead Examiner, initiate ET3 (RBW01 B).

If sent to check the "B" RBCCW pump, wait approximately 5 minutes then report that it smells like the motor windings have burned.

If sent to check the "A" RBCCW pump, wait approximately 5 minutes and report that you cannot determine why the "A" RBCCW pump will not start.

5

SIMULA TOR OPERA TOR DIRECTIONS EVENT 6 Failed Seals on the "8" Recirc Pump - When the URO has reduced Reactor power with Recirc flow per GP-9 or when directed by the Lead Examiner, initiate ET4 (RRS138 and RRS148).

If the Crew askes for Drywell Chilled Water Return Header pressure, wait approximately 3 minutes and report that DWCW return header pressure is 26 psig.

EVENT 7 28 Recirc Suction Valve Fails to Close - When the Crew attempts to isolate the Recirc seal leakage the Recirc Suction valve M0 02-0438 will not close. This will allow the steam leak in Containment to continue and not be isolable.

EVENT 8 Failure of Auto Scram and Reactor Mode Switch -When the Crew scrams the Reactor; the mode switch will fail to change position and will stay in Run. If the Crew is slow to scram the Reactor and an automatic scram signal is generated, the control rods will not insert. Then Control Rods will insert using the Scram Pushbuttons.

EVENT 9 When Drywell pressure reaches 1.7 psig, VERIFY Pending Events on trigger ET5 (IMF MSS02). This will make the steam leak worse and require the crew to spray Primary Containment.

EVENT10 Drywell to R8CCW Leak - As Drywell pressure continues to rise, Drywell pressure will exceed R8CCW pressure and require the Crew to perform the GP-88 manual isolations.

When Drywell pressure reaches 1.7 psig, VERIFY Pending Events on trigger ET5.

IOR AN0212RG5 (E5 0 0) ALARM_ON R8CCW Tank Hi-Lo Level

IOR ZAOSW12Pl2350 (E5 0 0) 0 R8CCW Heat Exchanger Outlet Header Pressure When M0-2373 and M0-2374 are closed then clear the following Malfunctions:

DMF ARM01 11 "R8CCW Room 116' Elev"

DMF H112 "PMS - R8CCW Room 116' Elev" 6

SIMULATOR OPERATOR DIRECTIONS TERMINATION End the scenario when M0-2373 and M0-2374 are closed and Primary Containment parameters are under control.

7

SHIFT TURNOVER PLANT CONDITIONS:

Unit 2 is at a 100% power.

"B" RWCU is blocked for Motor Repairs

There is a leak in the RBCCW system that requires the head tank to be filled every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . It was filled 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ago.

The 'B' ESW pump is in service using A0-33.2, "ESW System Manual Startup and Operation" to do a flow evaluation of flow through the DIG heat exchangers. The test is expected to be completed within the hour.

INOPERABLE EQUIPMENT/LCOs:

None SCHEDULED EVOLUTIONS:

Place the "B" EHC pump in-service and the "A" EHC pump in Off for maintenance using SO 1D.6.A-2, "Placing the Electrohydraulic Control Oil System Standby Pump In-Service". The is an Equipment Operator standing by at the EHC skid.

SURVEILLANCES DUE THIS SHIFT:

None ACTIVE CLEARANCES:

"B" RWCU pump for motor repairs GENERAL INFORMATION:

8

CRITICAL TASK LIST

1. Shutdown the Reactor by depressing the manual Scram pushbuttons. (T-101-1b)

2. Spray the Drywell to (restore and) maintain Drywell Bulk Average Temperature below 281°F. (T-102-7c)

3. Isolate RBCCW from the Drywell in the Control Room.

9

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 4 Event No. 1 Page: 1of14 Event

Description:

Placing the "B" EHC pump in-service and the "A" EHC pump in Stop.

Cause: N/A Effect: N/A Time Position Applicant's Actions or Behavior PRO Place the "B" EHC pump in-service using SO 1D.6.A-2, "Placing the Electrohydraulic Control Oil System Standby Pump In-Service".

On Panel 20C008A, verify 2AP017, "Turbine Gen EHC Pump A" is in service.

On Panel 20C008A, verify 2BP017, "Turbine Gen EHC Pump B" is available to be placed in service.

Direct an Equipment Operator to verify Pl-4403, "EHC Fluid Pump B Discharge Pressure" indication is less than 100 psig at the EHC skid.

Start 2BP017, "Turbine Gen EHC Pump B" by placing the control switch to "Run" on Panel 20C008A.

Direct an Equipment Operator to perform Step 4.3.4 to adjust the B EHC pump pressure compensator.

Verify Pl-4403, EHC Fluid Pump B Discharge Pressure" is at least 1550 psig locally or Computer point T051.

Direct an Equipment Operator to verify that the Micron filter element indicator indicates green.

On Panel 20C008A, place 2AP017, "Turbine Gen EHC Pump A" to "Stop".

Acknowledge the expected alarm for 205 K-3, "EHC STANDBY PUMP NOT IN AUTO".

10

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 4 Event No. 2 Page: 2of14 Event

Description:

Report that there is no oil in the "B" Core Spray pump discharge piping snubber.

Cause: Damaged snubber Effect: N/A Time Position Applicant's Actions or Behavior CRS Recognize that a Technical Requirement is not met.

Consult TRM 3.16.A to determine the Required Actions.

Determine that the 28 Core Spray pump is inoperable immediately and enter required action for Tech Spec 3.5.1.A "ECCS -

Operating." Restore the Core Spray subsystem to operable status within 7 days.

11

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 4 Event No. 3 Page: 3of14 Event

Description:

"A" RWCU Pump High Winding Temperature Cause: Overheating condition on the "A" RWCU pump Effect: Crew should secure the RWCU system.

Time Position Applicant's Actions or Behavior PRO Recognize by reporting the "A" CLEAN-UP RECIRC PUMP MOTOR WINDING TEMPERATURE HIGH" alarm (ARC 215 A-1).

Enter and execute ARC 215 A-1.

Direct an Equipment Operator to determine the cause of the High Winding Temperature.

Shutdown RWCU, at panel 20C04A, when directed:

Shutdown the "A" RWCU pump.

Close M0-2-12-068, "RWCU Outlet".

Close M0-2-12-018, "RWCU Outboard lsol".

May close M0-2-12-15, "RWCU Inboard lsol" but it is not required.

CRS Enter and execute ARC 215 A-1.

Direct the PRO to perform a rapid shut down of RWCU using SO 12.2.A-2, "Reactor Water Cleanup System Shutdown" URO Provide peer checks as directed by the CRS.

12

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 4 Event No. 4 Page: 4of14 Event

Description:

"8" ESW Room Flooding Cause: The source of the leak is from the '8' ESW pump discharge piping on the pump side of the discharge valve and that water has sprayed onto the "B" ESW pump motor.

Effect: Room Flood.

If the Crew does not secure the ESW pump it will trip.

Time Position Applicant's Actions or Behavior PRO Recognize by reporting the "'B' ESW PUMP ROOM FLOODED" alarm (004 A-4).

Enter and execute the Alarm Response Card for the "' B' ESW PUMP ROOM FLOODED" alarm.

Direct an Equipment Operator to investigate the ESW Pump Room flood alarm.

When directed, trip the 'B' ESW pump.

Direct the Equipment Operator to open watertight door #C02 OR #C03.

Direct the Equipment Operator DO NOT OPEN watertight door #C09.

Direct the Equipment Operator to open watertight door #C02 OR #C03 which ever door was not opened in the above step.

CRS Enter and execute the Alarm Response Card for the "' B' ESW PUMP ROOM FLOODED" alarm.

Direct the PRO to trip the 'B' ESW pump.

Notify Security of the ESW Pump Room door status.

Post a Fire Watch within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per TRM 3.14.8.

Enter TRM 3.14.8 and determine that a continuous fire watch is required until the smoke detectors can be verified operable.

Recognize that a Tech Spec LCO is not met.

Consult Technical Specifications 3.7.2 to determine the Required Actions.

Determine that the "B" ESW pump must be restored within 7 days.

Direct an Equipment Operator to remove the feed for the "B" ESW pump.

May direct the Shift Manager to review EALs for the flooding condition.

13

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 4 Event No. 5 Page: 5of14 Event

Description:

Loss of RBCCW (PRA)

Cause: The "B" RBCCW pump will trip and the "A" RBCCW pump will not start.

Effect: Complete loss of cooling to components supplied by RBCCW including Recirc pumps and RWCU Time Position Applicant's Actions or Behavior URO/PRO Recognize by reporting the loss of RBCCW.

Recognize by reporting the loss of RBCCW as a symptom for entry into ON-113 "Loss of RBCCW" procedure.

Enter and execute ON-113 "Loss of RBCCW".

Monitor the Recirc pump temperatures.

Direct an Equipment Operator to determine why the "A" RBCCW pump did not start.

Recognize by reporting the following alarms:

214 A-5, "A RECIRC PUMP COOLING WATER LO FLOW"

214 F-5, "B RECIRC PUMP COOLING WATER LO FLOW" PRO Verify the start of the "A" RBCCW pump.

Recognize by reporting the failure of the "A" RBCCW pump to start.

Verify RWCU is isolated.

Recognize by reporting alarm 228 E-2, "NITROGEN COMPRESSOR A OR B TROUBLE". (May occur if a compressor starts following the loss of RBCCW flow.)

CRS Enter and execute ON-113 "Loss of RBCCW".

Direct the PRO to verify RWCU is isolated.

Direct the URO to lower Reactor power in accordance with GP-9-2 "Fast Power Reduction".

Direct the PRO to monitor Recirc pump temperatures.

URO When directed, reduce Reactor power in accordance with GP-9-2 "Fast Power Reduction".

14

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 4 Event No. 6 Page: 6of14 Event

Description:

"B" Recirc pump seal failure Cause: The loss of cooling to the Recirc pump seals due to the loss of RBCCW causes the seals to fail.

Effect: Drywell pressure will begin to rise.

Temperatures on the Recirc will begin to rise and will reach the point requiring the "B" Recirc pump be removed from service.

Time Position Applicant's Actions or Behavior URO/PRO Recognize by reporting the following alarms:

214 F-1, "B RECIRC PUMP SEAL STAGE 2 HI FLOW"

214 F-2, "B RECIRC PUMP SEAL STAGE 2 LO FLOW"

213 B-3, "RECIRC PUMP MOTOR HI TEMP" Recognize by reporting the seal failures on the "B" Recirc pump.

Recognize by reporting the "RECIRC PUMP MOTOR HI TEMP" alarm.

Enter and execute the ARC 214 F-1, 214 F-2 and 213 B-3.

Recognize by reporting the rise in Drywell pressure.

Enter and execute OT-101, "High Drywell Pressure".

When the Recirc pump is secured, recognize by reporting an entry condition to OT-112, "Unexpected I Unexplained Change in Core Flow."

Enter and execute OT-112.

PRO Maximize D/W cooling per RRC 44A.1 "Maximize Drywell Cooling".

Start the 2C DWCW pump by taking the control switch to RUN.

Start the 2C Drywell Chiller by taking the control switch to RUN.

If Drywell pressure is above .75 psig then direct an Equipment Operator to place the speed control switches for all of the Drywell Cooler Fans that are not running to SLOW speed.

Direct an Equipment Operator to raise the load setting on the "C" Drywell Chiller.

Place all Drywell Cooler Fan control switches to RUN.

15

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 4 Event No. 6 Page: 7of14 Event

Description:

"B" Recirc pump seal failure (continued)

Time Position Applicant's Actions or Behavior CRS Enter and execute the ARC 214 F-1 and F-2 Enter and execute OT-101, "High Drywell Pressure".

When the Recirc pump motor temperatures exceed the ARC limits, direct the URO to trip the "B Recirc pump.

Enter and execute OT-112.

Verify position on the Power to Flow map.

When Drywell pressure cannot be maintained below 1.2 psig, direct the Crew to perform GP-4 "Manual Reactor Scram".

16

ES-0-2 Operator Actions OP Test No. 1 Scenario No. 4 Event No. 7 Page: 8of14 Event

Description:

"8" Recirc pump suction valve, "M0-2-02-0438" failure to isolate Cause: Contacts fail to makeup to close the suction valve.

Effect: Seal leakage cannot be isolated; drywell pressure will continue to rise.

Time Position Applicant's Actions or Behavior URO Trip the M/G set drive motor breaker for the "8" Recirc pump When directed, close M0-2-02-0438, "Recirc Pump Suction Valve".

Recognize by reporting that M0-2-02-0438 will not close.

Secure seal purge by closing MO 80298, "Seal Purge".

When directed, close M0-2-02-0538 "Recirc Pump Discharge Valve".

Continue inserting GP-9-2 Appendix 1 control rods.

Report that there are no thermal hydraulic instabilities.

17

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 4 Event No. 8 Page: 9of14 Event

Description:

Failure to auto scram and failure of the Mode Switch in Run. (PRA)

Scram Actions Cause: Mode Switch contacts will remain in Run even when the URO takes the Mode Switch to Shutdown. The "A" channel auto scram will fail to operate.

Effect: The URO must use the Manual Scram Pushbuttons to insert the control rods.

When the crew begins to depressurize the Reactor, a Group I isolation will occur because the Mode Switch logic is still in Run.

Time Position Applicant's Actions or Behavior URO Perform GP-4 "Manual Reactor Scram" actions:

Place the Reactor mode switch to "Shutdown".

Recognize by reporting the failure of the Mode Switch to initiate a Reactor Scram.

CT

Use the Scram Pushbuttons to insert the Control Rods.

Verify control rods inserting.

Verify APRMs are downscale.

Report to the CRS that the mode switch is in Shutdown but that it did not cause the Reactor to scram, the APRMs are downscale and control rods have inserted.

Establish RPV level control with feedwater.

Maintain RPV level between 5 to 35 inches.

Verify RPV pressure, trend, and the status of EHC.

Report the following to the CRS per RRC 94.1-2:1 "URO Scram Reports":

a. RPV level, trend, and status of Feedwater.

b. RPV pressure, trend, and status of EHC.

c. All control rods are inserted.

18

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 4 Event No. 8 Page: 10of14 Event

Description:

Failure to auto scram and failure of the Mode Switch in Run.

Scram Actions (continued)

PRO Perform scram actions per RRC 94.2-2 "Plant Reactor Operator Scram Actions".

Transfer House loads.

Trip the Main Turbine

Verify the Generator Lockout

Start all of the Main Turbine lift pumps

Verify Group I, II, and Ill isolations and SGTS initiation, as applicable.

Verify Scram Discharge Volume vents and drains are closed.

Verify Hydrogen Water Chemistry is isolated.

Verify the "A" Recirc Pump speed has runback to 30%.

Monitor Instrument Air header pressure and Drywell pressure.

Report the following when the CRS is ready per RRC 94.2-2: 1 "PRO Scram Reports":

House loads are transferred.

Main Turbine is tripped.

Main Generator is locked out.

PCIS Group II and Ill isolations are complete and SBGT was manually started.

SDV vents and drains are closed.

Hydrogen Water Chemistry is isolated.

"A" Recirc Pump speed is 30% and the "B" Recirc Pump is tripped.

Instrument Air header pressure is greater than Drywell pressure.

When Directed, bypass and restore Drywell Instrument Nitrogen per RRC 94.2-2 "Plant Reactor Operator Scram Actions".

CRS Enter and execute T-101, "RPV Control".

Direct the PRO to bypass and restore Drywell Instrument Nitrogen.

19

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 4 Event No. 9 Page: 11 of 14 Event

Description:

Steam leak into Primary Containment Worsens Cause: Recirc pump seal completely fails.

Effect: Drywell pressure will rise requiring the crew to Spray Primary Containment.

Time Position Applicant's Actions or Behavior URO/PRO When Drywell temperature reaches 140°F recognize by reporting the rise in Drywell temperature as a symptom for entry into ON-120, "High Drywell Temperature".

Enter and execute ON-120, "High Drywell Temperature".

Recognize by reporting the event as an entry condition for T-102 "Primary Containment Control" procedure. (Drywell pressure 2 psig and Drywell Temperature 145°F)

Recognize by reporting the event as an entry condition for T-101 "RPV Control" procedure.

Report the HPCI auto start on 2 psig Drywell pressure.

CRS Enter and execute ON-120, "High Drywell Temperature".

Enter and execute T-102 "Primary Containment Control".

Enter and execute T-101 "RPV Control" Direct the PRO to secure HPCI when it is not required for level makeup.

Direct the PRO to place Torus Sprays in-service when Drywell temperature cannot be maintained below 200°F.

Direct T-223 "Drywell Cooler Fan Bypass" be performed.

Direct the URO to begin a depressurization In accordance with T-101, "RPV Control.

If Drywell Bulk Average Temperature is above 281°F the CRS may decide to perform a T-112, "Emergency Slowdown".

Verify condensate injection is controlled by monitoring the Reactor Feedpump Discharge valve positions.

Verify Torus level is above 7 Feet.

Direct the PRO to open all ADS valves.

20

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 4 Event No. 9 Page: 12of14 Event

Description:

Steam leak into Primary Containment Worsens (continued)

Time Position Applicant's Actions or Behavior PRO When directed, secure HPCI in accordance with RRC 23.1 "HPCI System Operation During a Plant Transient".

Verify 20P026, "Aux Oil Pump" control switch in "START"

Place 20K002, "Vac Pump" control switch in "START"

DEPRESS and hold "Remote Trip" pushbutton.

Verify H0-4513, "HPCI Turbine Stop" is closed.

When turbine speed reaches approximately ORPM as indicated on SPl-4505, then place 20P026, "Aux Oil Pump" control switch to "PULL TO LOCK" position.

Release the "Remote Trip" pushbutton.

Verify HPCI Flow controller in "AUTO" and set for 5000 gpm.

When directed, perform Torus Sprays IAW T-204 "Initiation of Containment Sprays using RHR":

Place keylock switch 1OA-S1 SA(B), Containment Spray Override 2/3 Core Coverage" in MANUAL OVERRIDE

Momentarily place the S 17A/B switch in "MAN".

Open M0-39A(B) "Torus Hdr. Valve".

Open M0-89C(D) "HPSW Outlet Valve"

Start a HPSW pump in the respective loop.

Start an RHR pump in the respective loop.

Throttle open M0-38A(B) to obtain 1000 gpm on Fl-2 136A(B).

CT When directed, perform Drywell Sprays IAW T-204 "Initiation of Containment Sprays using RHR":

Verify both Recirc pumps are off.

Verify all Drywell Cooling fan Switches are in Off

Open M0-31A(B), "D/W Spray Inboard".

Open M0-26A(B), "D/W Spray Outboard"

Monitor Torus and Drywell pressure.

Report the drop in Primary Containment pressure.

21

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 4 Event No. 9 Page: 13of14 Event

Description:

Steam leak into Primary Containment Worsens (continued)

Time Position Applicant's Actions or Behavior PRO When directed, perform T-223 "Drywell Cooler Fan Bypass".

Verify operation on the safe side of Figure 1, "DWCW Saturation Curve", prior to starting or restarting any Drywell Cooler Fan Unit.

Verify cooling water is available to the Drywell Cooler Fan Units.

Place all Drywell Cooler Fan control switches on "OFF" at panel 20C012.

Momentarily place "D/W Cooler Fans, 43-S-J-165" control switch in "BYPASS" and allow it to spring return to "NORMAL" at panel 20C005A.

Verify the following:

o Amber light above the "D/W Cooler Fans, 43-S-J165" control switch is lit at panel 20C005A.

o "DRYWELL COOLER FAN TRIP BYPASS" alarm in up on panel 207 B-2.

Direct an Equipment Operator to place the Drywell Cooler Fan speed control switches in "SLOW".

Operate the Drywell Cooler Fans as necessary to reduce Drywell pressure and temperature.

When directed open all ADS valves.

URO When directed, begin a depressurization with SRVs.

22

ES-D-2 Operator Actions OP Test No. 1 Scenario No. 4 Event No. 10 Page: 14 of 14 Event

Description:

Steam leak into the RBCCW room Cause: Drywell pressure exceeds RBCCW pressure do the leak in the RBCCW due to the system leak and the failure of the RBCCW pumps.

Effect: Conditions in the RBCCW will deteriorate. The ARM in the RBCCW room will alarm.

Temperatures in the RBCCW room will rise.

Time Position Applicant's Actions or Behavior CRS Direct the PRO to perform GP-8.B "PCIS Isolations - Groups II and Ill" for high Drywell pressure.

When conditions permit, the CRS should direct the PRO to spray the Drywell.

Evacuate the RBCCW Room using GP-15 "Local Evacuation".

(This step will be N/A if the isolation valves are closed.)

PRO CT When directed perform GP-8B"PCIS Isolations - Groups II and Ill".

Trip the "A" Recirc pump on panel 20C04A.

Close M0-2373 and M0-2374 on panel 20C12.

Recognize by reporting the RBCCW Room ARM alarm is clear and radiation levels have returned to normal. This step will be N/A if the isolation valves are closed.

URO/PRO Recognize by reporting the RBCCW Room ARM in alarm. This step will be NIA if the isolation valves are closed.

TERMINATION CRITERIA:

End the scenario when M0-2373 and M0-237 4 are closed and Primary Containment parameters are under control.

23

v t e Letter Sequence Other
TAC:U01911, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML15131A255, ML15131A256, ML15169A646, ML15169A648, ML15174A053
MONTHYEAR2015-03-13 [Table View]

ML15131A255

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