ML050830166

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Final - Section a Operating (Folder 3)
ML050830166
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 02/18/2005
From: Popielarski J
Exelon Generation Co
To: Conte R
NRC/RGN-I/DRS/OSB
Conte R
References
Download: ML050830166 (65)


Text

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET Signature I Tile Date I

Signature I Tile Date APPROVED FOR USE:

T Signature I Title Date EFFECTIVE DATE:

I I

COMMENTS:

ISSUE DATE:

COMPLETION DATE:

I Training Review for Completeness:

Signa tu re/Date I

I PlMS CODE:

PlMS ENTRY:

2005 RO TC INFIATION.d&

Page 1 of 7

.ODE NO.: PILT-ADMIN 000

11.
12.
13.
14.
15.

TEMPORARY CHANGE FORM LOG TITLE:

Initiate a Temporary Change.

REV. NO.: -

001

1.
2.
3.
4.
5.
6.
7.

1 I

2005 RO TC INITIATION.doc Page 2 of 7

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

TASK-JPM DESIGNATOR: X -

WA:

Generic 2.2.1 1 Unit Reactor Operator/Senior Reactor Operator URO: 2.5 SRO: 3.4 TASK DESCRIPTION:

Knowledge of the process for controlling Temporary Changes A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEP:

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 examine 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 (I shall be simulated (S).

b.

When performing ln-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 0.2) 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 b given to the examinee.

2005 RO TC INITIAT1ON.doc Page 3 of 7

B.

W.

D.

E.

F.

G.

L-TOOLS AND EQUIPMENT

1.

None REFERENCES

1.
2.

AD-PB-101-103, Temporary Changes to Procedures.

SO 52A. 1.B, Section 4.1, Diesel Generator Operations, Slow Start.

TASK STANDARD I. Satisfactory task completion is indicated when Temporary Change has been submitted to the SRO with Attachment 3, Part A completed, in accordance with the approved procedure.

2.

Estimated time to complete: 20 minutes Non-Time Critical DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to initiate a single use temporary change to SO 52A.1.B, Diesel Generator Operations, Slow Start, step 4.1.1.4, using AD-PB-101-1003, Temporary Changes to Procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

TASK CONDITIONS/PREREQUISlTES

1.

The Plant is operating at full power.

2.

A slow start of the E-1 Diesel Generator using SO 52A.1.B Diesel Generator Operations, is required today for performance monitoring by Predictive Maintenance.

3.

SO 52A.1.B Diesel Generator Operations has no existing Temporary Changes.

4.

The E-1 Diesel Generator Coolant Expansion Tank level indicating sightglass has a crack in it. The sightglass is isolated with an Equipment Status Tag (EST), but the tank is still available for use.

5.

Maintenance reports that the sightglass will be repaired tomorrow on dayshift under Work Order C0123456.

6.

The Control Room Supervisor has directed that the System Manager will determine and verify Coolant Expansion Tank level, then report it to the Control Room as part of the pre-start check of the E-I Diesel Generator.

INITIATING CUE The Control Room Supervisor directs you to initiate a single use temporary change to SO 52A. 1.B, Diesel Generator Operations, step 4.1.1.4, using AD-PB-101-1003, Temporary Changes to Procedures beginning with step 4.2.7.

2005 RO TC INITIATION.doc Page 4 of 7

H.

PERFORMANCE CHECKLIST STEP 1 STEP STANDARD NO 1

Obtain a copy of the reference procedure and reviewhtilize the correct section of the procedure.

CUE: Provide the Student with of this JPM.

P A copy of AD-PB-101-1003, Temporary Changes to Procedures is obtained.

Initiator responsibility is reviewed.

n*Note***

The Student may not classify the temporary change because single use was given to them in the initiating cue. It is necessary to provide this direction in the cue to ensure 2

3 4

  • 5 consistent imdeme Determine the temporary change classification.

Verify that the recommended change does not change the intent of the procedure.

Verify that there are no other TCs to this procedure.

(Cue: If the candidate asks a question, refer them back to the Task Conditions sheet.)

Complete the required mark-up of SO 52A.1.B, Diesel Generator Operations, Slow Start.

NOTE: The exact wording by the Student may vary from that of this JPM step. As long as the intent is clear the exact wording is not important.

atior P

P P

P for evaluation purposes.

Uses the information provided and determines that this temporary change is a SINGLE USE change in accordance with Step 4.2.7.

Check the list of items in Step 2.1 and verify that none of them matches this temporary change (which would indicate a change of intent.

Recognize that there are no previously existing TCs on the Diesel Procedure. This will be documented later on Attachment 1.

Completes the mark-up of SO 52A.1.B, Diesel Generator Operations, Slow Start by performing the following:

  • Draws a single line through each sentence of step 4.1.1.4 of SO 52A.1.B, Diesel Generator Operations, Slow Start.

0 *Inserts the following text as close to the affected step as possible; o The System Manager will verify and report Coolant Expansion tank level to the Control Room and will have coolant added as necessary.

Rev Bar. Initial and Date chanaes.

2005 RO TC INITIATION.doc Page 5 of 7

. p=

7 8

Complete Temporary Change Control Form, Attachment 1, Originator Section.

NOTE: This Diesel Generator procedure is common to both Units.

NOTE: The exact wording by the Student may vary from that of this JPM step. As long as the intent is clear the exact wording is not important.

Present the temporary change for review and approval.

CUE: Accept Attachment 3 and SO 52kl.B, Diesel Generator Operations, Slow Start from the Student as the SQR and SRO.

As an evaluator ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites)

AND procedures.

P P

P Completes the Temporary Change Form,, Originator Section, as follows:

  • Inserts SO-54A.l.B on the top line of the Temporary Change Control Form.
  • Writes 32 for the revision number.
  • Writes Common on the first line for common.
  • Places a check mark next to NO to the question related to whether this TC replaces existing TCs.
  • Places a check mark next to Single Use
  • Circles W/O and enters COl23456
  • Inserts 3 for Affected Pages.
  • Inserts System Manager will verify and report Coolant Expansion tank level to the Control Room and will have coolant added as necessary for the revision summary.

Prints name, initials, dates, writes their work group and extension on the Originator Line.

Presents Attachment 1 of AD-PB-101-1003, Temporary Changes to Procedures and the entire Diesel Generator Operation procedure SO 52A.1.B, Diesel Generator Operations, Slow Start with the marked up step 4.1.1.4 to the SQR and SRO for review and approval.

Positive control established.

2005 RO TC INITIATION.doc Page 6 of 7

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

When Attachment 3 of AD-PB-101-1003, "Temporary Changes to Procedures" and the entire Diesel Generator Operation procedure SO 52A. 1.B, "Diesel Generator Operations, Slow Start" with the marked up step 4.1.1.4 have been presented to the SQR and SRO for review and approval, the evaluator will terminate the exercise.

J.

SPECIAL INSTRUCTIONS:

None 2005 RO TC INITIATION.doc Page 7 of 7

AD-PB-101-1003 Revision 4 PaaelOof11 TEMPORARY CHANGE CONTROL FORM TC # ---___

Procedure/T&RM Number:

so S 2 A. t. G Revision:

32 Unit: G. v L bs this TC supende or (2 carmor If YES, ISt TCS to be DELETED and W m O V d h distribution:

replampxisting TCs?

NOAWS -

single Use (s) J TC Classification:

(Type)

Enter the acthrity No.

will restore stendcomponent and eliminate need for Conditional TC (Check One) Conditional (C) -

(Circie One) o&

CO 3 3 qrb Permanent Revision (R) -

Affected Pages:

3 Originator:

~~

Change of Intent Scmnfng:

If the proposed Temp Change invdves any of the fdkwing. than a TC Is inappropna

' teforthechange. Afulrevisknmustbepetformed

~~

Changes to the purpose w ofthe docwnent as defined n the 'Statement of Appiicabily 0r'Purpose'.

OYe6 O M wngesto

' sorcond~htheUFSARor~informationinanyofthefokwing:DedgnBasisDoarment O M (DBD), EP &

I

Fin, Bases, TRM & Bases?

Rogm. ISI Rogram, IST Progrem. ODCM 6 Bases. Tech Spec &

An unapproved setpoint or scaling change.

OYeS ON:

Change lo acceptance criteria that deaease the margin of acoeptance.

OYeS ON:

Change to technical speciRcation or other regulatoty related acceptance aiteria.

OYeS O k Change that eliminates QV hold points.

Modifications to any commitment to regulakm.

OYeS O k OYeS ON0 Print sign-

m.

SRO (procedures) or SFAM (l(LRMs) RinVSigWDate 14 DqSQR Approval

procedures only):

Date Disoplim or Org.

SFAM Authorization ApprovaUAuthorkatbn (TbRMs):

PrinVSi his TC will expire 90 days after the implementation date listed above or on the e@ration date listed above(i any). whichever comesfirst. Ta quest that the TC be m e d hwn Controlled Locations and cancelled earlier. ENTERthe new exphtion date here.

ORWARD this completed document to Records Management.

(procadures)

Date Cancel and Remove from Controlled Locations on (Date):

4.0 PERFORMANCE STEPS SO 52A.l.B Rev. 32 Page 3 of 31 NOTE The following sections may be performed individually without performing the entire procedure:

o Section 4.1, Diesel Generator Slow Start o Section 4. 2, Diesel Generator Synchronization and Loading o Section 4. 3, Diesel Generator Fast Start o Section 4.4, 4KV Switchgear Manual Transfer o Section 4.5, Diesel Generator Shutdown 4.1 Diesel Generator Slow Start 4.1.1 Direct the operator to perform the following as a pre-start inspection:

-72s 4.1.1.1 4. 1. 1. 2 4.1.1.3 4

Verify governor oil level LG-7575A(B) (C) (D) above the black line CM-7 below the top of the sightglass.

Check the engine crankcase lube oil level is between the t1U+311 and the "U-2" scribe marks on the dipstick.

Verify proper generator bearing oil level at M;-7568A(B) (C) (D). CM-7 Verify control rod pin is engaged with adjuster collar, on each fuel injection pump. (See Figure 1).

1.
2.
3.
4.
5.
6.

The Plant is operating at full power.

A slow start of the E-I Diesel Generator using SO 52A.l.B Diesel Generator Operations, is required today for performance monitoring by Predictive Maintenance.

SO 52A.l.B Diesel Generator Operations has no existing Temporary Changes.

The E-I Diesel Generator Coolant Expansion Tank level indicating sightglass has a crack in it. The sightglass is isolated with an Equipment Status Tag (EST), but the tank is still available for use.

Maintenance reports that the sightglass will be repaired tomorrow on dayshift under Work Order C0123456.

The Control Room Supervisor has directed that the System Manager will determine and verify Coolant Expansion Tank level, then report it to the Control Room as part of the pre-start check of the E-I Diesel Generator.

The Control Room Supervisor directs you to initiate a single use temporary change to SO 52A.1.B, Diesel Generator Operations, step 4.1.I

.4, using AD-PB-101-1003, Temporary Changes to Procedures beginning with Step 4.2.7.

ATTACHMENT 2 Provide the student a copy of the latest revision of procedure SO 52A.1.B, Diesel Generator Operations.

EXELON NUCLEAR Nuclear Generation Group OJTmPE MATERIAL COVERSHEET I

APPROVED FOR USE:

I EFFECTIVE DATE:

NAME:

Last First M.I.

ISSUE DATE:

SOC. SEC. NO.

COMPLETION DATE:

COMMENTS:

PlMS CODE:

PlMS ENTRY:

2005 RO - CALCULATE DW BULK AVE TEMP Page 1 of 5

TEMPORARY CHANGE FORM LOG CODE NO.: PILT-ADMIN 000 REV. NO.: 000 TITLE: MANUALLY CALCULATE DRYWELL BULK AVERAGE TEMPERATURE - ALTERNATE PATH (Failed Temperature Points)

1.
2.
3.
4.
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c.

3-

7.
8.
9.

1 1

10.

1 1

1 1

11.
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1 1

13.
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15.

2005 RO - CALCULATE DW BULK AVE TEMP Page 2 of 5

PECO NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

TASK-J PM DES I G NATOR:

Unit Reactor OperatorlSenior Reactor Operator PWG 2.1.7 URO: 3.7 SRO: 4.4 WA:

TASK DESCRIPTION:

MANUALLY CALCULATE DRYWELL BULK AVERAGE TEMPERATURE - ALTERNATE PATH (Failed Temperature Points)

A.

NOTES TO EVALUATOR:

1.
2.
3.
4.
5.

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.

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

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).

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

b.

Satisfactory performance of this JPM is accomplished if:

a.
b.

The task standard is met.

JPM completion time requirement is met.

I) 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.

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

2)

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

2005 RO - CALCULATE DW BULK AVE TEMP Page 3 of 5

B.

L C.

D.

E.

G.

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 132.4"F.

REFERENCES 1.

RT-0-40C-530-2, Drywell Temperature Monitoring, Rev. 5.

TASK STANDARD

1.

Satisfactory completion of this task 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. (Not time-critical)

DIRECTIONS TO EXAMINEE When given the initiating cue, use RT-0-40C-500-2 to determine whether an entry to ON-120, High Drywell Temperature is required. I will describe the initial conditions and provide you access to the materials required to complete this task.

TASK CONDITIONS/PREREQUISlTES

1. Unit 2 is experiencing a small steam leak into primary containment.
2. Tl-80146, the Drywell Bulk Average indication has failed.
3. Another operator has completed taking the temperatures required for Data Sheet 1 of RT-0-4OC-500-2, Drywell Temperature Monitoring.

INITIATING CUE The Control Room Supervisor has directed you to perform RT-04OC-530-2, Drywell Temperature Monitoring beginning with step 6.2.1 and report whether an entry condition exists for ON-120, High Drywell Temperature.

2005 RO - CALCULATE DW BULK AVE TEMP Page 4 of 5

NO 1

  • 2 3
  • 4
  • 5
  • 6
  • 7 8

STEP Review the-provided, partially complete, ST to determine where to begin in the ST Review Data Sheet 1 and recognize that all of the temperature points in Zone Number 4 are out of service (Step 6.2.1).

Record the instrument used on the blank provided in step 6.2.2.1.

Record the value of TI-2501, Point 136 in the provided blanks in steps 6.2.2.1 and 6.2.2.2.

Calculate approximate Drywell Bulk Average Temperature as indicated in step 6.2.2.2.

Complete verification of Drywell Bulk Average Temperature less than 140°F.

Report the status of ON-120, High Drywell Temperature entry condition.

As an evaluator ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites AND procedures. )

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

ACT P

P P

P P

P P

P STANDARD Candidate reviews the ST and determines that all steps are signed off up to step 6.2.1.

Recognize that the calculation of Bulk Average temperature is INVALID. Place an N/A in step 6.2.1.

Record 7-2501, Point 136" in the "Instrument Used" blank provided in step 6.2.2.1, then initial the step in the SAT column.

Record "132.4" in the blanks provided before the first "OF" in steps 6.2.2.1 and 6.2.2.2.

Calculate 132.4"F + 10°F = 142.4"F.

Record "142.4" in the blank provided in step 6.2.2.2, then initial the step in the SAT column.

Initial the UNSAT Black Box beside Step 6.2.3.

Report to the CRS that ON-120 should be entered due to Approximate Drywell Bulk Average Temperature greater than 140°F.

Positive control established.

When the candidate informs the Control Room Supervisor of the ON-120, High Drywell Temperature entry condition, the evaluator will terminate the exercise.

2005 RO - CALCULATE DW BULK AVE TEMP Page 5 of 5

PECO NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET ESTABLISH COMPONENT CLEARANCE APPROVALS:

Signature I Title Date Signature /Title Date Signature I Title Date I

APPROVED FOR USE:

EFFECTIVE DATE:

I I

NAME:

Last First M.I.

ISSUE DATE:

SOC. SEC. NO.

COMPLETION DATE:

~

COMMENTS:

PlMS CODE:

2005 RO CLEARANCE POINT Rev000.doc Page 1 of 6

TEMPORARY CHANGE FORM LOG CODE NO.: Clearance Point JPM REV. NO.:

TITLE:

Establish ComDonent Clearance Points - 2A Fuel Pool SW Booster Pump I 1-

3.
4.
5.
6.
7.
a.

~~

~

~~

~

9.

IO.

11.
12.
13.

2005 RO CLEARANCE POINT Rev000.doc Page 2 of 6

PECO NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOBPERFORMANCEMEASURE POSITION TITLE:

TASK-JPM DESIGNATOR: 29907301 01 WA:

2.2.13 Unit Reactor ODeratorlSenior Reactor Operator URO: 3.6 SRO: 3.8 TASK DESC RI PTI ON:

Knowledse of taqsing and clearance 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 0.2) is required.

5.

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

~

~

2005 RO CLEARANCE POINT Rev000.doc Page 3 of 6

- B.

C.

D.

F.

G.

TOOLS AND EQUIPMENT

1.

P&ID M-314 sheet 3

2.

Electrical drawing E-178

3.

Electrical drawing E-1606 REFERENCES

1.

P&ID M-314 sheet 3

2.

Electrical drawing E-178

3.

Electrical drawing E-1606 TASK STANDARD

1.

Satisfactory task completion is indicated when the clearance points for the "2A" Fuel Pool Service Water Booster Pump have been identified.

2.

Estimated time to complete: 20 minutes m - T i m e Critical DIRECTIONS TO EXAMINEE When given the initiating cue, determine the clearance points necessary to perform work on the "2A" Fuel Pool Service Water Booster Pump.

TASK CON D IT1 0 N S/PRE REQ U I S ITES

1.

The "2A Fuel Pool Service Water Booster Pump is scheduled for maintenance that requires the pump to be isolated, vented, and drained.

INITIATING CUE The Control Room Supervisor directs you to identify the clearance points for isolation, venting, and draining of the "2A" Fuel Pool Service Water Booster Pump. Inform the Control Room Supervisor when the task is completed.

2005 RO CLEARANCE POINT Rev000.doc Page 4 of 6

H.

PERFORMANCE CHECKLIST STEP NO STEP Locate the component to be repaired on the P&ID drawing.

(Cue: Provide the candidate with a copy of M-314 Sheet 3.)

Locate the component to be repaired on electrical prints.

(Cue: Provide the candidate with a copy of E-I78 and E-1606.)

ACT P

P STANDARD Locate "2A Fuel Pool Service Water Booster Pump on M-314 sheet 3, (F-7).

Locate "2A" Fuel Pool Service Water Booster Pump on E-1 78 and E-1606.

NOTE:

The following step contains the expected blocking points to isolate, vent, and drain the"2A" Fuel Pool Service Water Booster Pump. Alternate points may be acceptable, evaluate the points to determine if they meet the requirements to isolate, vent, and drain the pump.

Isolation valves and at least one vent valve and one drain valve are required.

  • 3 4

L Determine the clearance points.

(Cue: Acknowledge the blocking point selections.)

Inform Control Room Supervisor of task

om pletion.

[Cue: The Control Room Supervisor xknowledges the

-e po rt. )

P P

The operator determines the following clearance points (critical points indicated by an asterisk) on the "2A" Fuel Pool Service Water Booster Pump:

Pump control switch OFF or STOP.

  • BKR 1 R4-R-8 (2564) OPEN or OFF

'HV 2-30-21 81 8A "Discharge Block VLV" - CLOSED

'HV 2-30-2 18 16A "Suction Block VLV" - CLOSED

  • HV 2-30-21 81 9A "Discharge Drain VLV" - OPEN
  • HV 2-30-2181 7A "Vent VLV" - OPEN The operator informs the Control Room Supervisor of task completion.

2005 RO CLEARANCE POINT Rev000.doc Page 5 of 6

.==TEF I

STEP I A C

STANDARD P

1 NO 5

Positive Control Established.

As an evaluator, ensure that you have positive control of all exam material provided to examinees (Task ConditionslPrerequisites I

B Under ACT P - must perform S - must simulate

1.

TERMINATING CUE When the clearance points have been identified, and the Control Room Supervisor informed, the evaluator will terminate the exercise.

~~

2005 RO CLEARANCE POINT Rev000.doc Page 6 of 6

TASK CONDlTlONSlPREREQUlSlTES The 2A Fuel Pool Service Water Booster Pump is scheduled for maintenance that requires the pump to be isolated, vented, and drained.

INITIATING CUE The Control Room Supervisor directs you to identify the clearance points for isolation, venting, and draining of the 2A Fuel Pool Service Water Booster Pump. Inform the Control Room Supervisor when the task is completed.

I

EXELON NUCLEAR Nuclear Generation Group OJTITPE MATERIAL COVERSHEET I

I APPROVED FOR USE:

EFFECTIVE DATE:

I I

Y NAME:

SOC. SEC. NO.

Last First M.I.

ISSUE DATE:

COMPLETION DATE:

~

COMMENTS:

1 PlMS CODE:

I PlMS ENTRY:

RO ADMIN - STATE-LOCAL NOTIFICATIONS Page 1 of 6

TEMPORARY CHANGE FORM LOG CODE NO.: PILT-ADMIN 000 REV. NO.: 000 TITLE: PERFORM STATE/LOCAL EVENT NOTIFICATIONS FOR A DECLARED EMERGENCY.

7.
a.
9.
10.
11.
12.
13.
14.
15.

RO ADMIN - STATE-LOCAL NOTIFICATIONS Page 2 of 6

PECO NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

TASK-J PM DES I G NATOR:

Unit Reactor Operator/Senior Reactor Operator 294001 G213 URO: 3.6 SRO: 3.8 WA:

TASK DESCRIPTION:

PERFORM STATE/LOCAL EVENT NOTIFICATIONS FOR A DECLARED EMERGENCY.

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.

L-L RO ADMIN - STATE-LOCAL NOTIFICATIONS Page 3 of 6

B.

C.

D.

E.

F.

G.

TOOLS AND EQUIPMENT I. EP-MA-114-100, Mid-Atlantic State/Local Notifications, Rev. 5.

REFERENCES

1.

EP-MA-114-100, Mid-Atlantic State/Local Notifications, Rev. 5.

TASK STANDARD

1.

Satisfactory completion of this task is indicated the State/Local Event Notifications have been properly completed.

2.

Estimated time to complete: 15 minutes. (Time-critical)

DIRECTIONS TO EXAMINEE When given the initiating cue, make StatelLocal Notifications in accordance with EP-MA-114-100, Mid-Atlantic State/Local Notifications. I will describe the initial conditions and provide you access to the materials required to complete this task.

TASK CON DIT1 ONS/PRE REQU I SITES

1. A transient has occurred on Peach Bottom Unit 2.
2. The Shift Manager, acting as the Station Emergency Director, has completed the initial classification of the event and prepared the State/Local Notification Form.
3. The event is classified as a Site Area Emergency.
4. Another operator has been assigned to fax the StateILocal Notification Form to the TSC and the OF.

INITIATING CUE As the communicator, complete the required State and Local Isminute Notifications in accordance with Step 4.2 of EP-MA-114-100, Mid-Atlantic State/Local Notifications using the provided STATE/LOCAL NOTIFICATION FORM.

RO ADMIN - STATE-LOCAL NOTIFICATIONS Page 4 of 6

H.

PERFORMANCE CHECKLIST STEP STEP ACT STANDARD NO NOTE:

When the cue is provided to the candidate, then WRITE the "DECLARED AT TIME" on the live it to the candidate.

State/Local Event Notification form and Obtain a copy of EP-MA-114-100, Mid-P Atlantic State/Local Notifications.

Candidate obtains a copy of EP-MA-114-100, Mid-Atlantic State/Local Notifications.

(Cue: this procedure may be provided by the examiner).

Ensure that "Utility Message No." has been assigned using a sequential number.

P Candidate verifies that the "Utility Message No." blank is filled in with the number "1 ".

Candidate notes the Shift Manager signature in the ED approval blank.

Verify "Emergency Director Approval" signature has been entered.

P Review form for completeness.

P Candidate reviews form to ensure that appropriate blanks are filled in.

5 Candidate picks up phone and listens for dial tone.

(Cue: When candidate picks up receiver, tell them that thev hear a dial tone.)

  • 6 Dial the appropriate CODE (CAN No.)

listed for the affected station.

PIS Candidate dials CAN Number 833 into the phone.

(Cue: acknowledge dialing of number).

Repeat the required message while t

allowing agencies to come on line.

  • 7 Candidate states: "This is the Exelon Nuclear Peach Bottom Control Room.

Please standby for a notification messaae. "

(Cue: acknowledge message.)

After 10-15 seconds, read the required message.

P Candidate states: "This is the Exelon Nuclear Peach Bottom Control Room.

Please standby to receive a notification message and respond as the roll is called.

  • 8
  • 9 (Cue: acknowledge message.)

Conduct an initial roll call for the agencies listed on the State/Local Event Notification Form.

P Call out each agency on the Peach Bottom 15 minute notification list on page 2 of the StatelLocal Event Notification Form.

Write the time on the form as each agency responds.

(Cue: respond with "here" or "present" or another suitable term as each agency is called.)

RO ADMIN - STATE-LOCAL NOTIFICATIONS Page 5 of 6

STEP STEP ACT STANDARD NO NOTE:

Completion of the Initial Roll Call is required to be completed within 15 minutes of the initial classification. AFTER the JPM is complete, compare the DECLARED AT TIME to the roll call

[

II complete time to ensure th, completed.

  • 10 I Enter the time that the roll call was
  • 11 Read the blocks from the approved notification form.

I 12 Repeat the roll call.

(Cue: respond with here or present or another suitable term as each agency is called.)

Ask if there are any questions.

13 (Cue: respond with no questions.)

14 Read the required statement.

(Cue: acknowledge statement.)

Report to the Shift ManagedEmergency 15 II I

Director that notifications-have been completed.

(Cue: acknowledge report.)

As an evaluator, ensure that you have positive control of all exam material provided to examinees (Task Condition s/Prerequ isites AND procedures).

16 it is IC P

P P

P P

P P

s than 15 minutes.

Enter the time the roll call was completed in the box on the bottom of the roll call box on page 2 of the form. This time is reauired to be less than 15 minutes.

Read each of the notification form blocks one at a time using the Phonetic Alphabet and speaking slowly and clearly Call the roll for each agency and check the final roll call box as each agency responds.

Ask if there are any questions and wait for a response.

Read the following: This concludes the notification message.

Report that State/Local Notifications have been completed.

Positive Control Established.

Under ACT P - must perform S - must simulate TERMINATING CUE:

When the candidate reports that the StateILocal Event Notifications are complete, the evaluator will be notified. The evaluator will then terminate the exercise.

RO ADMIN - STATE-LOCAL NOTIFICATIONS Page 6 of 6

TASK CONDlTlONSlPREREQUlSlTES

1. A transient has occurred on Peach Bottom Unit
2.

2.The Shift Manager, acting as the Station Emergency Director, has completed the initial classification of the event and prepared the S ta te/Loca I Not if icat ion Form.

3.The event is classified as a Site Area Emergency.

4. Another operator has been assigned to fax the State/Local Notification Form to the TSC and the EOF.

INITIATING CUE As the communicator, complete the required State and Local 15-minute Notifications in accordance with Step 4.2 of EP-MA4 14-1 00, MidlAtlantic State/Local Notifications using the provided STATE/LOCAL NOTIFICATION FORM.

EXELON NUCLEAR Nuclear Generation Group OJTmPE MATERIAL COVERSHEET APPROVALS:

[ APPROVED FOR USE:

EFFECTIVE DATE:

J J

I NAME:

SOC. SEC. NO.

Last First M.I.

ISSUE DATE:

COMPLETION DATE:

COMMENTS:

PlMS CODE:

PlMS ENTRY:

2005 SRO - CONTROL ROD SEQUENCE DEVIATION Page 1 of 6

TEMPORARY CHANGE FORM LOG

2.
3.
4.
5.
6.

- 7.

a.
9.

CODE NO.: PILT-ADMIN 000 REV. NO.: 000 TITLE: REVIEW AND AUTHORIZE A ROD SEQUENCE DEVIATION

11.
12.
13.
14.
15.

2005 SRO - CONTROL ROD SEQUENCE DEVIATION Page 2 of 6

PECO NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

TASK-JPM DESIGNATOR:

KIA:

Unit Reactor Operator/Senior Reactor Operator PWG 2.2.11 URO: 2.5 SRO: 3.4 TASK DESCRIPTION:

REVIEW AND AUTHORIZE A ROD SEQUENCE DEVIATION 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).

L

b.

When performing "ln-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 0.2) 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.

2005 SRO - CONTROL ROD SEQUENCE DEVIATION Page 3 of 6

B.

C.

D.

E.

F.

G.

TOOLS AND EQUIPMENT

1.

Prepare a Rod Sequence Deviation for Control Rod 14-27 stuck at position 42 during a reactor startup.

REFERENCES

1.

Startup Control Rod Sequence

2.

NF-AB-720, Control Rod Sequence Package Preparation, Review, Revision, and Implementation.

TASK STANDARD

1.

Satisfactory completion of this task is indicated when emrs in the Control Rod Sequence Deviation have been identified and the request disapproved.

2.

Estimated time to complete: 20 minutes. (Not time-critical)

DIRECTIONS TO EXAMINEE When given the initiating cue, review the Control Rod Sequence Deviation for authorization. I will describe the initial conditions and provide you access to the materials required to complete this task.

TASK CONDITIONS/PREREQUISlTES

1. A Reactor Startup is in progress on Unit 2.
2. While being moved from position 12 to position 48, Control Rod 14-27 stuck at position 42.
3. No other Control Rods are slow or inoperable.
4. The QNE has determined that a deviation is appropriate for these conditions based on the guidance contained in NF-AB-720-1000. Startup, Shutdown, and Target Rod Pattern Sequence Development Package.
5. The QNE has evaluated the deviation to ensure that the requirements of the ReMA will be met. The current ReMA will be used for the continued startup, but then a new ReMA with the change will be issued.
6. Reactor Engineering has prepared a deviation from the approved sequence.

INITIATING CUE As the Control Room Supervisor, review the Control Rod Sequence Deviation for authorization.

2005 SRO - CONTROL ROD SEQUENCE DEVIATION Page 4 of 6

H.

PERFORMANCE CHECKLIST NOTES:

The following steps may be done in a different order as long as all steps are completed prior to placing the UNIT SUPERVISOR AUTHORIZED signature on the Control Rod Sequence Review and Approval Sheet.

This Control Rod Sequence Deviation should be REJECTED by the candidate.

Reference section 4.4, Deviation from an Approved Sequence, of NF-AB-720, Control Rod Sequence Package Preparation, Review, Revision, and Implementation.

Determines that a deviation is appropriate based on the NOTE after step 4.4.

Determines that the deviation is consistent with the requirements of NF-AB-720-1 000.

Determines that the QNE has performed an evaluation to ensure that the deviation meets the requirement of the ReMA.

Verifies that the Target Rod Position for Rod 14-27 is changed from '48" to '42".

qerifies that Sequence Step 6, Control Eiod 14-27 has an appropriate entry in the

'Comment/Problem Column".

derifies that other occurrences of Control 3od 14-27 movement are indicated 3ppropriately.

'Cue: Acknowledae items identified).

P The operator references section 4.4, located on page 23 of NF-AB-720.

P The operator checks the NOTE after step 4.4 and determines that these conditions are acceptable for a deviation.

P The operator recognizes from the initial task conditions that this has already been verified.

P The operator recognizes from the initial task conditions that this has been eva I uated.

Verifies that on Sequence Step 6, the target position of "48" is crossed out for control rod 14-27 and replaced with a "42".

P P

Verifies that the "Comment/Problem" column has 'Skip" and "Control Rod Stuck at Position 42" indicated. Verify that each change has two sets of initials (QNE and Second Verifier).

P Operator recognizes that Sequence Steps 3 and 4 also contain Control Rod 14-27 steps that should have "Skip" indicated beside them.

2005 SRO - CONTROL ROD SEQUENCE DEVIATION Page 5 of 6

STEP ACT STANDARD NOTE The Operator may indicate that "SKIP" should be written in the Control Rod Insert Columns for the RO initials and 2"d Verifier initials

  • 8 9

I or Control Rod 14-27 because this is a co Operator indicates authorization status of the Control Rod Deviation.

(Cue: Acknowledge candidate comments.)

As an evaluator, ensure that you have positive control of all exam material provided to examinees (Task Conditions/

Prerequisites AND procedures.

ider "ACT" P - must perform S - must simulate non p P

P xtice. It is not, however required.

Operator indicates that the Control Rod Sequence Deviation cannot be approved as written due to the administrative errors.

Positive Control Established.

TERMINATING CUE:

When the candidate informs the evaluator that he can NOT authorize the Control Rod Deviation as written, the evaluator will terminate the exercise L

2005 SRO - CONTROL ROD SEQUENCE DEVIATION Page 6 of 6

TASK CONDITIONS/PREREQUISlTES

1. A Reactor Startup is in progress on Unit 2.
2. While being moved from position 12 to position 48, Control Rod 14-27 stuck at position 42.
3. No other Control Rods are slow or inoperable.
4. The QNE has determined that a deviation is appropriate for these conditions based on the guidance contained in NF-AB-720-1000, Startup, Shutdown, and Target Rod Pattern Sequence Development Package.
5. The QNE has evaluated the deviation to ensure that the requirements of the ReMA will be met.

The current ReMA will be used for the continued startup, but then a new ReMA with the change will be issued.

6. Reactor Engineering has prepared a deviation from the approved sequence.

INITIATING CUE As the Control Room Supervisor, review the Control Rod Sequence Deviation for authorization.

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET 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:

Last First M.I.

ISSUE DATE:

SOC. SEC. NO.

COMPLETION DATE:

COMMENTS:

PlMS CODE:

PlMS ENTRY:

2005 SRO ADMlN - HEAT BALANCE.dOC Page 1 of 6

TEMPORARY CHANGE FORM LOG CODE NO.: Manual Heat Balance JPM TITLE:

Perform a Manual Heat Balance REV. NO.:

I I

I

1.
2.
3.

r

'I 9.

11.
12.
13.
14.
15.

I I

2005 SRO ADMIN - HEAT BALANCE.dOC Page 2 of 6

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

TASK-J PM DES I G NATOR:

WA:

2.120 Unit Reactor Operator/Senior Reactor Operator URO: 4.3 SRO: 4.2 TASK DESCRIPTION:

Perform a Manual Heat Balance 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 ln-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 0.2) 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.

\\-.

2005 SRO ADMlN - HEAT BALANCE.dOC Page 3 of 6

B.

TOOLS AND EQUIPMENT

1.

Calculator

-. C.

REFERENCES

1.

RE-C-05, Manual Heat Balance D.

TASK STANDARD

1.

Satisfactory task completion is indicated when Steps 6.3 and 6.4 of RE-C-05, Manual Heat Balance, have been completed and recorded.

2.

Estimated time to complete: 20 minutes m - T i m e Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform the necessary steps to calculate a manual heat balance using the appropriate procedure. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F.

TASK C 0 N D I T I ON S/PRE R EQ U IS I TE S

1.

You have been directed to perform a manual heat balance.

2.

The Manual Heat Balance procedure RE-C-05, is in progress and is complete through step 6.2.

3.

The Reactor Engineer has determined that Data Sheet #I (PMS Computer Data) is to be used for plant data.

G.

INITIATING CUE Complete Step 6.3, Preliminary Calculations, and Step 6.4, Data Sheet 3, of RE-C-05, Manual Heat Balance.

2005 SRO ADMIN - HEAT BALANCE.doc Page 4 of 6

H.

PERFORMANCE CHECKLIST STEP STANDARD ACT STEP Obtain a copy of procedure RE-C-05.

NO 1

  • 2 P

A copy of procedure RE-C-05 is obtained

~

Complete the Preliminary Calculations Worksheet item #16 for feedwater flow.

Calculate feedwater flow as 10.26 MLB/HR by adding Data Sheet #1 items 1,2, and 3.

0 + 5.13 + 5.13 = 10.26 MLB/HR P

P P

P

~

Calculate feedwater temperature as 360 deg. F by completing the Feedwater Temperature Equation.

(360+360)0 + (360+360)5.13 +

(360+360)5.13 All divided by 10.26. All times 1/2 = 360

  • 3 Complete the Preliminary Calculations Worksheet item #17 for feedwater tem pera t u re.

Complete the Preliminary Calculations Worksheet item #23 for total Reactor Water Cleanup (RWCU) flow.

Calculate RWCU flow as.144 MLB/HR by adding Data Sheet #1 items 12 & 13.

.072 +.072 =.144 MLB/HR

  • 4
  • 5
  • 6 7

Determine CRD flow as.030 MLBlHR by inputting the computer point value for item #7.

Complete the Preliminary Calculations Worksheet item #24 for CRD flow.

P Calculate RX pressure as 1000 psia by adding 14.7 psi to Data Sheet # l item #9.

14.7 + 985.3 = 1000 psia Complete the Preliminary Calculations Worksheet item #9A for reactor pressure.

Sign the Preliminary Calculation Worksheet complete.

Initial and date step 6.3.

P P

P

  • 8 Complete the Steam Table Data sheet item #18.

Calculate feedwater Enthalpy hh as 333.57 BTU/LB by plotting feedwater temperature (item #17) and RX Pressure (item #9A) on Appendix B.

  • 9 Complete the Steam Table Data sheet item #19.

Determine that the Enthalpy of Saturated Steam at 1000 psig is approximately 1192 BTU/lbm (acceptable range 1186 -

1 193).

Calculate the Enthalpy of Reactor Water Cleanup (RWCU) h,,

from the core as 499.69 BTU/LB, by plotting RWCU inlet temp. (item #14) and RX Pressure (item

  1. 9A) on Appendix B
  • 10 Complete the Steam Table Data sheet item #20.

P L

2005 SRO ADMIN - HEAT BALANCE.dOC Page 5 of 6

Complete the Steam Table Data sheet item #21.

Complete the Steam Table Data sheet item #22.

Sign the Steam Table Data sheet complete.

As an evaluator, ensure that you have positive control of all exam material provided to the examinees (Task Conditions/Prerequisites AND procedures.

P P

P P

Calculate the Enthalpy of Reactor Water Cleanup (RWCU) hmi into the core as 375.96 BTU/LB, by plotting RWCU inlet temperature (item #15) and RX Pressure (item #9A) on Appendix B.

Calculate the Enthalpy of CRD herd as 80.57 BTU/LB, by plotting RWCU inlet temp. (item #8) and RX Pressure (item

  1. 9A) on Appendix B.

Initial and Date step 6.4.

Positive Control Established.

Under ACT P - must perform S - must simulate TERMINATING CUE

\\

When Step 6.4 of the ST has been completed, the evaluator will then terminate the exercise.

2005 SRO ADMIN - HEAT BALANCE.dOC Page 6 of 6

TASK CONDlTlONS/PREREQUISlTES I. You have been directed to perform a manual heat balance.

2.

The Manual Heat Balance procedure RE-C-05, is in progress and is complete through step 6.2.

3.

The Reactor Engineer has determined that Data Sheet #I (PMS Computer Data) is to be used for plant data.

INITIATING CUE Complete Step 6.3, Preliminary Calculations, and Step 6.4, Data Sheet 3, of RE-C-05, Manual Heat Balance.

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET rPPROVED FOR USE:

EFFECTIVE DATE:

I I

NAME:

SOC. SEC. NO.

Last First M.I.

ISSUE DATE:

1 COMPLETION DATE:

COMMENTS:

PlMS CODE:

I PlMS ENTRY:

Page 1 of 6 2005 SRO - REVIEW AND AUTHORIZE A CLEARANCE

TEMPORARY CHANGE FORM LOG CODE NO.: PILT-ADMIN 000 TITLE: REVIEW AND AUTHORIZE A CLEARANCE REV. NO.: 000

1.
2.
3.
6.
7.
8.
9.
10.
11.
12.
13.
14.

4 2005 SRO - REVIEW AND AUTHORIZE A CLEARANCE Page 2 of 6

PECO NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

TASK-J PM DES I G NATOR:

Unit Reactor Operator/Senior Reactor Operator Generic 2.2.1 3 URO: 3.6 SRO: 3.8 WA:

TASK DESCRIPTION:

REVIEW AND APPROVE A CLEARANCE 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 ln-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 0.2) 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.

5.

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

2005 SRO - REVIEW AND AUTHORIZE A CLEARANCE Page 3 of 6

B.

C.

D.

E.

F.

G.

TOOLS AND EQUIPMENT

1.

Prepare a Clearance Request that is complete ready for approval and authorization to hang tags. Include errors associated with the blocking points for the pump breaker.

Copy of M-363, Sheet 1 with Clearance Points highlighted.

Copy of E-329 with Clearance Points highlighted.

Copy of E-1606 with Clearance Points highlighted.

2.
3.
4.

REFERENCES

1. M-363, Sheet 1, System P&ID.
2. E-329, Electrical Print.
3. E-1606, Electrical Print.

TASK STANDARD

1.

Satisfactory completion of this task is indicated when errors in the Clearance Request have been identified and the request disapproved.

2.

Estimated time to complete: 20 minutes. (Not time-critical)

DIRECTIONS TO EXAMINEE When given the initiating cue, review the Clearance Request for approval. I will describe the initial conditions and provide you access to the materials required to complete this task.

TASK CONDITIONS/PREREQUISlTES

1. The B Fuel Pool Cooling Pump is shutdown and requires a Clearance to permit preventive maintenance on the pump coupling and motor.
2. The A Fuel Pool Cooling Pump is in service.
3. The Work Order, Clearance and Prints will be submitted to you for review.

INITIATING CUE The clearance for the B Fuel Pool Cooling Pump has just been prepared. The Shift Manager directs you, the Work Execution Center (WEC) Supervisor, to review the clearance for approval and immediate application and inform the Control Room Supervisor (CRS) when complete.

2005 SRO - REVIEW AND AUTHORIZE A CLEARANCE Page 4 of 6

H.

PERFORMANCE CHECKLIST 5TEP NO

  • 4 5

6 i.-

STEP ACT STANDARD NOTE:

The following steps may be done in a different order as long as they are performed prior to placing the APPROVED BY signature on the Clearance.

This Clearance should be REJECTED by the candidate.

Verify the Component ID, Component Description and Clearance Description are correct.

(Cue: Acknowledge verification of the Data.)

Check Comment Section to verify impact of Clearance is accurate and complete.

(Cue: Acknowledge Clearance impact.)

Verify Instructions are adequate for the Clearance.

(Cue: Acknowledge the verification of instructions.)

Verify Clearance Points to determine if they are correct and adequate for the work to be performed under this Clearance.

(Cue: Acknowledge the incorrect Clearance Points. )

Notify the Control Room Supervisor of the incorrect Clearance Points and the return of the Clearance without Approval.

(Cue: The Control Room Supervisor acknowledges the report.)

As an evaluator, ensure that you have positive control of all exam material provided to the examinees (Task Conditions/Prerequisites AND procedures).

nder ACT P - must perform S - must simulate P

P P

P P

P The operator verifies the Component ID, Component Description and the Clearance Description are correct.

The operator checks the Comments Section and verifies the impact of the Clearance to be the 2B Fuel Pool Cooling Pump will be 00s.

The operator verifies the Instructions are adequate for the Clearance.

The operator reviews the adequacy and accuracy of the Clearance Points and identifies the breaker identified is for the wrong (A) pump making the following points incorrect:

0 Breaker 1R4-R-B (2544) 0 Key for lock for Breaker 2544 HV-2-19-14B, FPC Pump Discharge Valve must also be blocked closed.

The operator notifies the Control Room Supervisor of the incorrect Clearance Points and of the return of the Clearance without Approval.

Positive Control Established.

2005 SRO :REVIEW AND AUTHORIZE A CLEARANCE Page 5 of 6

TERMINATING CUE:

When the tagging request review is complete and the Control Room Supervisor has been informed of its disapproval, the evaluator will terminate the exercise 2005 SRO - REVIEW AND AUTHORIZE A CLEARANCE Page 6 of 6

TASK CON DITIONS/PREREQUISITES

1. The 6 Fuel Pool Cooling Pump is shutdown and requires a Clearance to permit preventive maintenance on the pump coupling and motor.
2. The A Fuel Pool Cooling Pump is in service.
3. The Work Order, Clearance and Prints will be submitted to you for review.

INITIATING CUE The clearance for the 6 Fuel Pool Cooling Pump has just been prepared. The Shift Manager directs you, the Work Execution Center (WEC) Supervisor, to review the clearance for approval and immediate application and inform the Control Room Supervisor (CRS) when complete.

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

V I

1 APPROVED FOR USE:

EFFECTIVE DATE:

I I

NAME:

Last First M.I.

ISSUE DATE:

~~

COMMENTS:

SOC. SEC. NO.

COMPLETION DATE:

PlMS CODE:

I PlMS ENTRY:

2005 SRO ADMIN AUTHORIZE AN EMERGENCY EXPOSURE Page 1 of 7

TEMPORARY CHANGE FORM LOG CODE NO.: PILT-ADMIN 000 REV. NO.: 000 TITLE: REVIEW AND AUTHORIZE AN EMERGENCY EXPOSURE

5.
6.
7.
8.
9.
10.
11.
12.
13.
14.

1

15.

2005 SRO ADMlN AUTHORIZE AN EMERGENCY EXPOSURE Page 2 of 7

PECO NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

TASK-J P M DES I G N ATOR:

Unit Reactor Operator/Senior Reactor Operator 2940016213 URO: 3.6 SRO: 3.8 WA:

TASK DES CR I PT IO N :

REVIEW AND AUTHORIZE AN EMERGENCY EXPOSURE 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.

5.

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

2005 SRO ADMIN AUTHORIZE AN EMERGENCY EXPOSURE Page 3 of 7

B.

L C.

D.

E.

F.

TOOLS AND EQUIPMENT

1.

EP-AA-113, Personnel Protective Actions

2., Authorization for Emergency Exposure Forms completed for Worker One and Worker Two with the exception of the Station Emergency Director authorization.
3.

Worker One and Worker Two history descriptions.

REFERENCES

1.

EP-AA-113, Personnel Protective Actions TASK STANDARD

1.

Satisfactory completion of this task is indicated when the Emergency Director has reviewed the worker histories, Authorization for Emergency Exposure Forms, and made decisions on the Emergency Exposure Requests.

2.

Estimated time to complete: 20 minutes. (Not time-critical)

DIRECTIONS TO EXAMINEE When given the initiating cue, review the worker histories and Authorization for Emergency Exposure Forms and make the decision as to whether to authorize the Emergency Exposure.

I will describe the initial conditions and provide you access to the materials required to complete this task.

TASK CONDITIONS/PREREQUISlTES

1. Peach Bottom is experiencing a major plant transient.
2. A General Emergency has been declared.
3. It is necessary for two specially trained individuals to enter an area with extremely high radiation levels to prevent a major release that would cause significant radiation sickness to the general public in the area. The release would also result in long-term somatic and genetic effects for the public.
4. Only two individuals at Peach Bottom have the required training and experience to be successful in preventing the release.
5. Worker One and Worker Two are available and have volunteered for the assignment.
6. EP-AA-113, Attachment 2, Authorization for Emergency Exposure Forms have been completed for both individuals and require Emergency Director review and authorization.

2005 SRO ADMIN AUTHORIZE AN EMERGENCY EXPOSURE Page 4 of 7

7. A description of each workers history has been attached to the Emergency Authorization Forms.

G.

INITIATING CUE As the Emergency Director, review the Authorization for Emergency Exposure Forms (EP-AA-1 13, Attachment 2) for authorization.

2005 SRO ADMIN AUTHORIZE AN EMERGENCY EXPOSURE Page 5 of 7

H.

PERFORMANCE CHECKLIST EEF NO 1

2 3

4 5

6 STEP ACT STANDARD NOTES:

The following steps may be done in a different order as long as all steps are completed prior to signing STATION EMERGENCY DIRECTOR (Authorization) on the Authorization for Emergency Exposure Form (EP-AA-113, Attachment 2).

Locate the correct section of EP-AA-113, Personnel Protective Actions.

Evaluate the task to determine if it is worthy of authorizing Emergency Exposure.

Evaluate Worker Ones Authorization for Emergency Exposure Form.

Evaluate Worker Ones History.

Authorize Worker One to receive the Emergency Exposure.

Evaluate Worker Twos history and Authorization for Emergency Exposure Form.

P P

P P

P P

The operator references section 4.3 of EP-AA-113.

Determine that the task has an acceptable basis to authorize necessary emergency exposure. May reference EP-AA-113, Attachment 3, Emergency Worker Exposure Limits and Associated Risks.

Review Worker OnesAuthorization for Emergency Exposure Form and note that it is completed correctly and signed by Worker One and Rad. Protection Management.

Review Worker Ones History and determine that it is acceptable for Worker One to receive the Emergency Exposure.

Indicate the authorization for Emergency Exposure by signing the Station Emergency Director signature block on the Emergency Exposure Authorization Form.

Review Worker Twos Authorization for Emergency Exposure Form and note that it is completed correctly and signed by Worker One and Rad. Protection Management.

2005 SRO ADMIN AUTHORIZE AN EMERGENCY EXPOSURE Page 6 of 7

8 9

r I

STEP Evaluate Worker Twos History.

Do NOT authorize Worker Two to receive the Emergency Exposure.

Inform the evaluator of the results of his reviews.

As an evaluator, ensure that you have positive control of all exam material provided to the examinees (Task Conditions/Prerequisites, Worker Histories, and procedure copies.

nder ACT P - must perform S - must simulate ACT P

P P

P STANDARD Review Worker Twos History and recognize that he has received an Emergency Exposure in the past.

Determine that since Worker Two has previously received an Emergency Exposure, he is not permitted to receive another Emergency Exposure. This is based on the CAUTION in EP-AA-113 just after Step 4.3.3 which states that All Emergency Exposures in excess of 25 Rem TEDE shall be voluntary and shall be limited to once in a lifetime.

The operator must NOT sign Worker Twos Emergency Exposure Form (Attachment 2).

The operator informs the evaluator that Worker One may be authorized to perform the task, but that Worker Two is NOT eligible for the Emergency Exposure.

Positive Control Established.

TERMINATING CUE:

When the Emergency Exposure Authorization Review is complete, the operator will inform the Evaluator and the exercise will be terminated.

L 2005 SRO ADMIN AUTHORIZE AN EMERGENCY EXPOSURE Page 7 of 7

TASK CONDITIONS/PREREQUlSlTES L-

1. Peach Bottom is experiencing a major plant transient.
2. A General Emergency has been declared.
3. It is necessary for two specially trained individuals to enter an area with extremely high radiation levels to prevent a major release that would cause significant radiation sickness to the general public in the area. The release would also result in long-term somatic and genetic effects for the public. It is estimated that each worker would receive 30 Rem of dose.
4. Only two individuals at Peach Bottom have the required training and experience to be successful in preventing the release.
5. Worker One and Worker Two are available and have volunteered for the assignment.
6. EP-AA-113, Attachment 2, Authorization for Emergency Exposure Forms have been completed for both individuals and require Emergency Director review and authorization.
7. A description of each workers history has been attached to the Emergency Authorization Forms.

As the Emergency Director, review the workers histories and Authorization for Emergency Exposure Forms (EP-AA-113, ) for authorization.

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET EFFECTIVE DATE:

I NAME:

Last First M.I.

ISSUE DATE:

SOC. SEC. NO.

COMPLETION DATE:

COMMENTS:

PlMS CODE:

PlMS ENTRY:

I I

2005 SRO ADMlN EP CLASSIFY AND COMPLETE STATE/LOCAL NOTIFICATION FORM Page 1 of 6

PECO NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

TASK-J P M DES I G NATOR:

Unit Reactor Operator/Senior Reactor Operator 294001 G213 URO: 3.6 SRO: 3.8 KIA:

TASK DESCRIPTION:

EMERGENCY CLASSIFICATION AND PREPERATION OF THE STATWLOCAL EVENT NOTIFICATION FORM.

A.

NOTES TO EVALUATOR:

1.
2.
3.

L

4.
5.

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.

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

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).

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

b.

Satisfactory performance of this JPM is accomplished if:

a.
b.

The task standard is met.

JPM completion time requirement is met.

1 )

For non-time critical JPMs, completion within double the estimated time (listed in paragraph 0.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

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

2)

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

2005 SRO ADMIN EP CLASSIFY AND COMPLETE STATEnOCAL NOTIFICATION FORM Page 3 of 6

B.

L-C.

D.

E.

~..

F.

G.

TOOLS AND EQUIPMENT

1.

Peach Bottom Atomic Power Station Emergency Action Level Matrix.

2.

EP-MA-114-100, Mid-Atlantic State/Local Notifications, Rev. 5.

REFERENCES

1.

Peach Bottom Atomic Power Station Emergency Action Level Matrix.

2.

EP-MA-114-100, Mid-Atlantic State/Local Notifications, Rev. 5.

TASK STANDARD

1.

Satisfactory completion of this task is indicated when event has been properly classified and the State/Local Event Notification Form has been completed.

2.

Estimated time to complete: 15 minutes. (Time-critical)

DIRECTIONS TO EXAMINEE When given the initiating cue, classify the event and complete the State and Local Notification Form. I will describe the initial conditions and provide you access to the materials required to complete this task.

TASK CONDITIONS/PREREQUISlTES

1. Unit 2 was operating at 100% power when a primary system leak developed in the drywell.
2. The operators are responding using:

0 ON-120, High Drywell Temperature 0

OT-101, High Drywell Pressure 0

T-I 01, RPV Control 0

T-I 02, Primary Containment Control

3. When a manual scram was attempted, the Reactor Protection System (RPS) and Alternate Rod Insertion (ARI) failed to insert the control rods.
4. Reactor Power is currently 17% with rod insertion in progress using T-220.
5. The Wind is coming from 270 degrees with a speed of 12 miles per hour.

INITIATING CUE Classify the event and complete the State/Local Notification Form in accordance with EP-MA-1 14-1 00, Mid-Atlantic State/Local Notifications.

2005 SRO ADMIN EP CLASSIFY AND COMPLETE STATULOCAL NOTIFICATION FORM Page 5 of 6

H.

PERFORMANCE CHECKLIST STEP STEP ACT STANDARD Evaluator:

Note the time when the cue is provided to the candidate. Start Time classifying the event.

Atomic Power Station Emergency Action accordance with MS-4 of the Peach Bottom Atomic Power Station Emergency Action Level Matrix.

  • 5 Indicate Call Status in Block I.

P Mark the box for "This is an Actual Plant Event" in box 1 of the form.

L

  • 6 Indicate the affected Station in Block 2.

P Mark the box before "PEACH BOTTOM" in Box 2.

  • 7 Indicate the Emergency Classification.

P For item 3.a., select "SITE AREA

  • 8 Indicate the affected unit.

P For item 3.b., select "lW0".

EMERGENCY".

  • 9 Indicate the Time and Date P

For item 3.c., indicate the current Time

  • I 0

Indicate what this represents.

P For item 3.d., select "INITIAL and Date.

DECLARATION".

  • I I Indicate the Emergency Action Level.

P For item 4.a., indicate "MS4".

2005 SRO ADMlN EP CLASSIFY AND COMPLETE STATULOCAL NOTIFICATION FORM Page 5 of 6

- *I 7

18 As an evaluator, ensure that you have positive control of all exam material provided to the examinees (Task Conditions/Prerequisites, Worker Histories, and procedure copies.

STEP ACT Provide a Brief Non-Technical P

Positive Control Established.

Description.

Indicate the status of a Radiological Release.

Indicate Meteorology Information.

ndicate the status of the PAR.

ndicate the conclusion Spprove the State/Local Notification

-arm.

P P

P P

P P STANDARD I

For item 4.b., indicate something similar to: "A Unit 2 shutdown was attempted due to a steam leak inside the primary containment. The Reactor Protection System, Manual Scram, and Alternate Rod Insertion Systems failed to shutdowr the reactor."

Note that the words for this description dc not have to match exactly.

For item 5, select "a. NO non-routine radiological release in progress."

For item 6.a., indicate that Wind Direct6 s FROM 270 (degrees).

=or item 6.b., indicate that Wind Speed is 12 (miles Der hour).

=or item 7, indicate that a PAR is "NOT 4PPLICABLE".

-or item 8, select "This is an Actual

vent".

sign the "EMERGENCY DIRECTOR 4PPROVAC" blank on the top of the form.

TERMINATING CUE:

When the classification and completion of the State/Local Event Notification Form is complete the evaluator will be notified. The evaluator will then terminate the exercise.

./

Page 6 of 6 2005 SRO ADMlN EP CLASSIFY AND COMPLETE STATWLOCAL NOTIFICATION FORM

TASK CONDlTlONS/PREREQUlSlTES

1. Unit 2 was operating at 100% power when a primary system leak developed in the drywell.
2. The operators are responding using:

ON-120, High Drywell Temperature OT-101, High Drywell Pressure T-101, RPV Control T-I 02, Primary Containment Control

3. When a manual scram was attempted, the Reactor Protection System (RPS) and Alternate Rod Insertion (ARI) failed to insert the control rods.
4. Reactor Power is currently 17% with rod insertion in progress using T-220.
5. The wind is coming from 270 degrees with a speed of 12 miles per hour.

INITIATING CUE Classify the event and complete the StateILocal Notification Form in accordance with EP-MA4 14-100, Mid-Atlantic State/Local Notifications.