ML083540401
| ML083540401 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/10/2008 |
| From: | Kelly M Exelon Generation Co |
| To: | Todd Fish Operations Branch I |
| Hansell S | |
| Shared Package | |
| ML081060602 | List: |
| References | |
| TAC U01776 | |
| Download: ML083540401 (71) | |
Text
EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET APPROVALS:
Signature / Title Date Signature /Title Date Signature /Title Date Signature / Title Date APPROVED FOR USE:
Signature / Title Date EFFECTIVE DATE:
I I
II ISSUE DATE:
COMPLETION DATE:
NAME:
Last First SOC. SEC. NO.
COMMENTS:
Training Review for Completeness:
I PlMS CODE:
SignatureIDate I
ENTRY:
I1 I
I 2008 NRC JPM RO AD-CO1 (NEW-SGTS Lineup -AP) -1 Page I of 9
TEMPORARY CHANGE FORM LOG CODE NO.: PLOR-NEWCA REV. NO.: @
J TITLE:
Lineup Standby Gas Treatment Systeim for Automatic Operation - Alternate Path (Switches Are Out of Position) 7 TCf ##
TCF DATE CHANGED SEGYION ##
2008 NRC JPM RO AD-CO1 (NEW-SGTS Lineup -AP) -1 Page 2 of 9
EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:
TASK-JPM DESIGNATOR: 261 00301 01 - PLOR-NEWCA WA:
261000 G2.1.29 Unit Reactor OperatodSenior Reactor Operator URO: 4.1 SRO: 4.0 TASK D ESC R I PTI 0 N :
Knowledge of how to conduct system lineups, such as valves, breakers, switches, 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 SWt Management approval.
- 4.
Satisfactory performance of this JPM lis 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 tine (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.
- 2)
For time critical JPMs, clompletion within the estimated time (listed ip 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.
2008 NRC JPM RO AD-CO1 (NEW-SGTS Lineup -AP) -1 Page 3 of 9
B.
TOOLS AND EQUIPMENT 5 (A fan) 6 (B fan)
- 1.
Partial procedure COL 9A.1.A Standby Gas Treatment System Automatic Operation, Rev. IO. All steps are marked N/A except for step:
20 (A0 20469-01) 21 (A0 20469-02)
I 8 (A0 2507) 9 (A0 2512) 10 (A0 2514) 11 (A0 2510) 16 (A0 00475-01) 17 (A0 00475-02)
-~
I I
8 (AO 00476-01 j 19 (A0 00476-02)
C.
REFERENCES
- 1.
COL 9A.1.A Standby Gas Treatment System Automatic Operation, Rev. I O.
D.
TASK STANDARD
- 1.
Satisfactory task completion is indicated when the Unit 2 Main Control Room related steps of COL 9A. 1.A, A Standby Gas Treatment System Automatic Operation, are complete.
- 2.
Estimated time to complete: 10 minutes Non-Time Critical E.
DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to lineup the Unit 2 Main Control Room portion of the Standby Gas Treatment System using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.
F.
TAS K C 0 N D IT I 0 N SIP RE R EQ U I S ITE S
- 1.
A Unit 2 startup is in progress.
- 2.
Emergent maintenance was performed on various components of the Standby Gas Treatment System (SGTS).
- 3.
Shift Management directs that a lineup verification of the Unit 2 Main Control Room portion of the SGTS be performed.
- 4.
A partial of COL 9A. 1.A Standby Gas Treatment System Automatic Operation has been reviewed and approved for use.
2008 NRC JPM RO AD-CO1 (NEW-SGTS Lineup -AP) -1 Page 4 of 9
G.
INITIATING CUE The Control Room Supervisor directs you to perform a lineup verification of the Unit 2 Main Control Room portion of the SGTS using the approved partial of COL 9A.1.A Standby Gas Treatment System Automatic Operation.
=
2008 NRC JPM RO AD-CO1 (NEW-SGTS Lineup -AP) -1 Page 5 sf 9
H.
PERFORMANCE CHECKLIST I1 I
I I
STANDARD I ACT I STEP
- NOTE TO EVALUATOR****
Hand partial of COL 9A.1.A Standby Gas Treatment System Automatic Operation to the Examinee to start this JPM.
1
- 2 3
4 Verify Standby Gas Treatment Fan A (OAV020) control switch is in AUTO.
(Cue: Standby Gas Treatment Fan A (OAV020) control switch is in AUTO position)
Verify Standby Gas Treatment Fan 9 (OBV020) control switch is in AUTO.
(Cue: If notified that the Fan B (OBV020) control switch is NOT in AUTO position, acknowledge report. If needed repeat initiating cue to perform a lineup verification of the Unit 2 Main Control Room portion of the SGTS)
Verify AO-2507 Drywell Outboard 18 Vent is in CLOSED position.
(Cue: AO-2507 Drywell Outboard 18 Vent control switch is in CLOSED position)
Verify AO-2512 Torus Outboard 18 Vent is in CLOSED position.
(Cue: AO-2512 Torus Outboard 18 Vent control switch is in CLOSED position)
P P
On panel 20C012 verify Standby Gas Treatment Fan A (OAV020) control switch is in AUTO position.
Initial and date the check off list step.
On panel 20C012 recognize that the Standby Gas Treatment Fan 9 (OBV020) control switch is in the PULL-TO-LOCK position and NOT in AUTO position.
May report to the Control Room Supervisor that the switch is out of target position now or report all mispositionings after COL is completed.
Place switch in AUTO position.
Initial and date the check off list step.
On panel 2OCOO3-3 verify that AO-:2507 Drywell Outboard 18 Vent is in CLOSED position.
Initial and date the check off list step.
On panel 2OCOO3-3 verify that AO-2512 Torus Outboard 18 Vent is in CLOSED position.
Initial and date the check off list step.
2008 NRC JPM RO AD-CO1 (NEW-SGTS Lineup -AP) -1 Page 6 of 9
F=-
6
- 7
- 8 Verify AO-2514 Torus Outboard 2 Vent is in CLOSED position.
(Cue: AO-2514 Torus Outboard 2 Vent control switch is in CLOSED position)
Verify AO-2510 Drywell Outboard 2 Vent is in CLOSED position.
(Cue: AO-2510 Drywell Outboard 2 Vent control switch is in CLOSED position)
Verify AO-00475-01 Standby Gas Treatment A Filter Inlet is in AUTO position.
(Cue: AO-00475-01 Standby Gas Treatment A Filter Inlet is in CLOSE position)
Verify AO-00475-02 Standby Gas Treatment A Filter Outlet is in AUTO position.
(Cue: If notified that the AO-00475-02 Standby Gas Treatment A Filter Outlet is NOT in the AUTO position, acknowledge report. If needed repeat initiating cue to perform a lineup verification of the Unit 2 Main Control Room portion of the SGTS P
P On panel 20C484A verify that AO-2514 Torus Outboard 2 Vent is in CLOSED position.
Initial and date the check off list ste13.
On panel 20C484B verify that AO-2510 Drywell Outboard 2 Vent is in CLOSED position.
Initial and date the check off list step.
On panel 20C012 recognize that AO-00475-01 Standby Gas Treatment A Filter Inlet control switch is in the CLOSE position and NOT in AUTO position.
May report to the Control Room Supervisor that the switch is out of target position now or report all mispositionings after COL is completed.
Place switch in AUTO position.
Initial and date the check off list step.
On panel 20C012 recognize that AQ-00475-02 Standby Gas Treatment A Filter Outlet control switch is in CLOSE and NOT in the AUTO position.
May report to the Control Room Supervisor that the switch is out of target position now or report all mispositianings after COL is completed.
Place switch in AUTO position.
Initial and date the check off list ste;,
2008 NRC JPM RO AD-CO1 (NEW-SGTS Lineup -AP) -1 Page 7 of 9
10 11 12 13
)I
~~
~
~~
Verify AO-00476-0 1 Stand by Gas Treatment B Filter Inlet is in AUTO position.
(Cue: AO-00476-01 Standby Gas Treatment B Filter Inlet is in AUTO position)
Verify AO-00476-02 Standby Gas Treatment B Filter Outlet is in AUTO position.
(Cue: AO-00476-02 Standby Gas Treatment B Filter Outlet is in AUTO position)
Verify AO-20469-01 Standby Gas Treatment DNV Reactor Bldg Equipment Exhaust is in CLOSED position.
(Cue:AO-20469-01 Standby Gas Treatment DNV Reactor Bldg Equipment Exhaust is in CLOSED position)
Verify AO-20469-02 Standby Gas Treatment DNV Reactor Bldg Equipment Exhaust is in CLOSED position.
(C ue: AO-20469-02 Stand by Gas Treatment DNV Reactor Bldg Equipment Exhaust is in CLOSED position)
Verify AO-20470-01 Standby Gas Treatment Refuel Floor Exhaust is in CLOSED position.
(Cue:AO-20470-01 Standby Gas Treatment Refuel Floor Exhaust is in IC LO S E D posit ion)
P P
P P
P
~
~
On panel 20C012 verify that AO-00476-01 Standby Gas Treatment B Filter-Inlet is in AUTO position.
Initial and date the check off list step.
On panel 20C012 verify that AO-00476-02 Standby Gas Treatment B Filter Outlet is in AUTO position.
Initial and date the check off list step.
~~
~
~
~
On panel 20C012 recognize that AQ-20469-0 1 Stand by Gas Treatment DNV Reactor Bldg Equipment Exhaust is in the CLOSED position.
Initial and date the check off list step On panel 20C012 recognize that AO-20469-02 Standby Gas Treatment DNV Reactor Bldg Equipment Exhaust is in the CLOSED position.
Initial and date the check off list step On panel 20C012 recognize that AO-20470-01 Standby Gas Treatment Refuel Floor Exhaust is in the CLOSED position.
Initial and date the check off list step 2008 NRC JPM RO AD-CO1 (NEW-SGTS Lineup -AP) -1 Page 8 of 9
P-15 16 17 18 Verify AO-20470-02 Standby Gas Treatment Refuel Floor Exhaust is in CLOSED position.
(Cue:AO-20470-02 Standby Gas Treatment Refuel Floor Exhaust is in CLOSED position)
Verify PO-20465 Exhaust to Stand by Gas Treatment Equipment Cell is in CLOSED posit ion.
(Cue: PO-20465 Exhaust to Standby Gas Treatment Equipment Cell is in CLOSED position)
Verify PO-20466 Exhaust to Standby Gas Treatment Rx Bldg is in CLOSED position.
(Cue: PO-20466 Exhaust to Standby Gas Treatment Rx Bldg is in CLOSED position)
Inform Control Room Supervision of completion of partial SGTS lineup.
As an evaluator, ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.
P P
On panel 20C012 recognize that A3-20470-02 Standby Gas Treatment Refuel Floor Exhaust is in the CLOSED position.
Initial and date the check off list step On panel 20C012 recognize that PO-20465 Exhaust to Standby Gas Treatment Equipment Cell is in the CLOSED position.
Initial and date the check off list step On panel 20C012 recognize that PO-20466 Exhaust to Standby Gas Treatment Rx Bldg is in the CLOSED position.
Initial and date the check off list step Inform Control Room Supervision af completion of partial COL 9A.1.A. 14 lineup verification of the Unit 2 Main Control Room portion of the SGTS has been performed.
Positive control established.
Under ACT P - must perform S - must simulate I.
TERMINATING CUE When a lineup verification of the Unit 2 Main Control Room portion of the SGTS has been performed the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.
2008 NRC JPM RO AD-CO1 (NEW-SGTS Lineup -AP) -1 Page 9 crf 9
TASK CONDITIONS/PREREQUISlTES
- 1.
A Unit 2 startup is in progress.
- 2.
Emergent maintenance was performed on various components of the Standby Gas Treatment System (SGTS).
- 3.
Shift Management directs that a lineup verification of the Unit 2 Main Control Room portion of the SGTS be performed.
- 4.
A partial of COL 9A.I.A Standby Gas Treatment System Automatic Operation has been reviewed and approved for use.
INITIATING CUE The Control Room Supervisor directs you to perform a lineup verification of the Unit 2 Main Control Room portion of the SGTS using the approved partial of COIL 9A.I.A Standby Gas Treatment System Automatic 0 perat ion.
Inform the Control Room Supervisor when complete.
EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET IFCATION MANUAL OJT MODULE
'C DUE TO A LEAK APPROVALS:
Signature / Title Date Signature /Title Date Signature / Title Date Signature / Title Date APPROVED FOR USE:
~
Signature /Title Date EFFECTIVE DATE:
I I
NAME:
Last First M.I.
SOC. SEC. NO.
COMMENTS:
ISSUE DATE:
COMPLETION DATE:
Training Review for Completeness:
Sig natu re/Date PlMS CODE:
PlMS ENTRY:
2008 NRC JPM RO AD-C02 (PLORNEWC Rev000 - Isolating 2A TBCCW Pump) -1 Page 1 of 6
- ODE NO.: PLOR-NEWC REV. NO.:
TITLE:
ISOLATING THE 2A TBCCW PUMP DUE TO A LEAK I
I CHANGED SECTION # 7 TCF #
TCF DATE
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
- 10.
- 11.
- 12.
- 13.
- 14.
- 15.
I 2008 NRC JPM RO AD-C02 (PLORNEWC Rev000 - Isolating 2A TBCCW Pump) -1 Page 2 of 6
EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:
TASK-JPM DESIGNATOR: 2002300401 / PLOR-NEWC WA:
2.2.41 Unit Reactor Operatoi-/Senior Reactor Operator 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 Snift 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.
2008 NRC JPM RO AD-C02 (PLORNEWC Rev000 - Isolating 2A TBCCW Pump) -1 Page 3 of 6
B.
TOOLS AND EQUIPMENT
- 1.
P&ID M-316 sheet 2, Rev. 61 C.
REFERENCES
- 1.
P&ID M-316 sheet 2, Rev. 61
- 2.
SO 34.6.A-2 Placing the Standby TBCCW Pump In Service D.
TASK STANDARD
- 1.
Satisfactory task completion is indicated when the isolation points and vent path for the 2A TBCCW pump have been identified.
- 2.
Estimated time to complete: 15 minutes m - T i m e Critical E.
DIRECTIONS TO EXAMINEE When given the initiating cue, determine the isolation points and vent path necessary to !stop a TBCCW System leak located on the suction of the 2A TBCCW pump.
F.
TASK CONDITIONS/PREREQUISlTES I. A Turbine Building Closed Cooling Water (TBCCW) System leak has been identified at pressure tap PX-2221A on the suctiori of the 2A TBCCW Pump.
- 2.
The 2B TBCCW pump has been placed in service and the 2A TBCCW pump has been removed from service using SO 34.6.A-2 Placing Standby TBCCW System Pump In Service.
- 3.
The 2A TBCCW pump control switch has been placed in the OFF position.
G.
INITIATING CUE The Control Room Supervisor directs you to identify the isolation points and a vent path lo stop the TBCCW leak located at the suction of the 2A TBCCW Pump. Document your results on the cue sheet. Inform the Control Room Supervisor when complete.
2008 NRC JPM RO AD-C02 (PLORNEWC Rev000 - Isolating 2A TBCCW Pump) -1 Page 4 of 6
H.
PERFORMANCE CHECKLIST 1
STEP No I Locate the component that is leaking on the P&ID drawing.
(Cue: Provide the candidate with a copy of M-316 Sheet 2.)
- 2
- 3 ACT P
STANDARD Locate PX-2221A on M-316 sheet 2, (Coordinates G-7).
- N CITE****
Steps 2 and 3 to determine the isolation points can be performed in any order.
Close HV-2-34-24268A TBCCW 2AP144 Suction Block Valve.
(Cue: Acknowledge that isolation point has been selected.)
Close HV-2-34-2427 1 A TBCCW 2AP144 Discharge Block Valve.
(Cue: Acknowledge that isolation point has been selected.)
P P
Identifies that HV-2-34-24268A TECCW 2AP144 Suction Block Valve must: be CLOSED in order to isolate the leak at PX-222 1 A.
Identifies that HV-2-34-24271A TECCW 2AP144 Discharge Block Valve must be CLOSED in order to isolate the leak at PX-222 1 A.
- NOlTE****
For step 4, the examinee can open the pump vent valve, the suction line drain valve, or both.
- 4 Open HV-2-34-24270A TBCCW Pump 2AP144 Vent Valve AND /OR Open and uncap HV-2-34-24269A TBCCW Pump 2AP144 Suction Line Drain Valve (Cue: Acknowledge that isolation point has been selected.)
P Id en tif ies that HV-2-34-24270A TBCC W PUMP 2AP144 Vent Valve must be OPEN in order to VENT the isolated system volume and stop the leak at PX-222 1 A AND/OR HV-2-34-24269A TBCCW Pump 2AP144 Suction Line Drain Valve must be OPEN and UNCAPPED in order to VENT the isolated system volume and stop the leak at PX-2221A 2008 NRC JPM RO AD-C02 (PLORNEWC Rev000 - Isolating 2A TBCCW Pump) -1 Page 5 sf 6
6 Inform Control Room Supervisor of task completion.
(Cue: The Control Room Supervisor acknowledges the report.)
As an evaluator ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.
P P
The operator informs the Control R Supervisor of task completion.
Positive control established.
Under ACT P - must perform S - must simulate I.
TERMINATING CUE When the isolation points and vent path necessary to stop the leak have been identified, and the Control Room Supervisor informed, the evaluator will terminate the exercise.
2008 NRC JPM RO AD-C02 (PLORNEWC Rev000 - Isolating 2A TBCCW Pump) -1 Page 6 of 6
TASK CONDITIONS/PREREQUISlTES
- 1. A Turbine Building Closed Cooling Water (TBCCW System leak has been identified at pressure tap PX-2221A on the suction of the 2A TBCCW Pump.
- 2.
The 2B TBCCW pump has been placed in service and the 2A TBCCW pump has been removed from serv using SO 34.6.A-2 Placing Standby TBCCW System Pump In Service.
- 3.
The 2A TBCCW pump control switch has been placed in the OFF position.
INITIATING CUE The Control Room Supervisor directs you to identify the isolation points and a vent path to stop the TBCCW leak located at the suction of the 2A TBCCW Pump. Document your results on this cue sheet. Inform the Control Room Supervisor when complete.
EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET Siyinature /Title Date Signature / Title Date Signature I Title Date Signature / Title Date 11 APPROVED FOR USE:
Signature / Title Date EFFECTIVE DATE:
I I
I1 ISSUE DATE:
COMPLETION DATE:
NAME:
Last First SOC. SEC. NO.
COMMENTS:
Training Review for Completeness:
PlMS CODE:
Signature/Date 2008 NRC JPM RO AD-EC (Liq Radwaste Disch Rev000) -1 Page 1 of6
TEMPORARY CHANGE FORM LOG CODE NO.: Liquid Release JPM REV. NO.:
TITLE:
PRO Duties for a Liquid Radwaste Discharqe 3
TCF #
TCF DATE CHANGED SECTION #!
- 7.
- 1
- 8.
- 9.
I O.
- 11.
- 12.
- 13.
- 14.
- 15.
2008 NRC JPM RO AD-EC (Liq Radwaste Disch Rev000) -1 Page 2 of 6
PECO NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:
TASK-JPM DESIGNATOR: 27301 30202 / PLOR-NEW-C WA:
2.3.11 Unit Reactor Operator/Senior Reactor Operator URO: 3.8 SRO: 4 3 TASK D ESC RI PTI 0 N :
Abilitv to control radiation releases.
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 JPIVls, no equipment will be operated without Shift Management approval.
- 4.
Satisfactory performance of this JPM lis 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 no1 to be given to the examinee.
2008 NRC JPM RO AD-EC (Liq Radwaste Disch Rev000) -1 Page 3 of 6
- 6.
C.
D.
E.
F.
G.
TOOLS AND EQUIPMENT 1"
Copy of ST-C-095-805-2, Rev. 12, completed through step 6.12.8.
REFERENCES 1.
ST-C-095-805-2, Rev. 12, "Liquid Raclwaste Discharge".
TASK STANDARD
- 1.
Satisfactory task completion is indicated when section 6.13 has been completed in its entirety.
- 2.
DIRECTIONS TO EXAMINEE Estimated time to complete: 12 minutes Non-Time Critical When given the initiating cue, perform the necessary steps to set-up the plant in preparation for a Liquid Radwaste discharge. I will describe initial plant conditions and provide you access to the materials required to complete this task.
TASK CONDITIONS/PREREQUISlTES
- 1.
Both units are operating at 100% power.
- 2.
The Floor Drain Sample Tank (FDST) needs to be discharged.
- 3.
Chemistry and Shift Management have completed ST-C-095-805-2, "Liquid Radwaste Discharge" through step 6.12.8.
- 4.
Six Circulating Water Pumps are in operation.
- 5.
The discharge Canal-To-Intake Pond crosstie gate is closed.
- 6.
The PRO review and set-up has not been completed.
INITIATING CUE You are the PRO. Complete section 6.13 of ST-C-095-805-2 "Liquid Radwaste Discharge in preparation for a liquid radwaste discharge.
I 2008 NRC JPM RO AD-EC (Liq Radwaste Disch Rev000) -1 Page 4 of 6
H.
PERFORMANCE CHECKLIST STEP STEP ACT STANDARD NO 1
- 2
- 3 4
5 Record actual number of operating Circulating Pumps.
P Verifies six Circulating Pumps are operating from Task Conditions/Prerequisite information, record and initial step 6.13.1.
Set the HI Trip Setpoint.
P Manually adjust the HI Setpoint Po!
setting for RIS-0-17-350 to 5 4.18,,and record and initial step 6.1 3.2.
Manually adjust the HI HI Setpoint Pot setting for RIS-0-17-350 to 5 4.21, and record and initial step 6.13.3.
Set the HI HI Trip Setpoint.
Step 6.13.4 is reviewed and marked N/A.
Mark step 6.13.4 N/A Review PRO steps.
Visually verify all the PRO steps in section 6.13 are complete, and initial step 6.13.5 SAT.
Record your name and initials.
Print your name and initials in Sect on 10.0.
Forward the test.
P Forward this test to the Radwaste Operator, and initial step 6.13.6 SAT.
(Cue: Radwaste Operator has received the test.)
Inform Control Room Supervision of completion of task.
P Inform Control Room Supervision crf completion of section 6.13 of ST-C-095-805-2 Liquid Radwaste Discharge.
As an evaluator, ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.
P 9
Positive control established.
Under ACT P - must perform S - must simulate 2008 NRC JPM RO AD-EC (Liq Radwaste Disch Rev000) -1 Page 5 of 6
I.
TERMINATING CUE When Section 6.13 of ST-C-095-805-2 has been completed, terminate the exercise.
2008 NRC JPM RO AD-EC (Liq Radwaste Disch Rev000) -1 Page 6 of 6
TASK CONDlTlONSlPREREQUlSlTES
- 1.
Both units are operating at 100% power.
- 2.
The Floor Drain Sample Tank (FDST) needs to be discharged.
- 3.
Chemistry and Shift Management have completed ST-C-095-805-2, "Liquid Radwaste Discharge" through step 6.12.8.
- 4.
Six Circulating Water Pumps are in operation.
- 5.
The discharge Canal-To-Intake Pond crosstie gate is closed.
- 6.
The PRO review and set-up has not been com pleted.
INITIATING CUE You are the PRO. Complete section 6.13 of ST-C-095-805-2 "Liquid Radwaste Discharge".
EXELON NUCLEAR Nuclear Generation Group OJTITPE MATERIAL COVERSHEET Training Review for Completeness:
SFICATION MANUAL PONSE DATA SYSTEM APPROVALS:
Signature /Title Date PlMS CODE:
Signature /Title Date Signature /Title Date
~
Signature /Title Date 11 APPROVED FOR USE:
Signature I Title Date EFFECTIVE DATE:
I I
II ISSUE DATE:
COMPLETION DATE:
NAME:
Last First SOC. SEC. NO.
COMMENTS:
Signature/Date I
ENTRY:
II 2008 NRC JPM RO AD-EP (PLOR186C Rev001-Emer Response Data System) -1 Page 1 of 6
TEMPORARY CHANGE FORM LOG TCF t JCF DATE CODE NO.: PLOR-186C REV. NO.: 002 TITLE:
Activate the Emerqency Response Data System CHANGED SECTION #
- 1.
- 2.
- 3.
- 4.
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 5.
- 6.
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IO.
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- 15.
_I 2008 NRC JPM RO AD-EP (PLOR186C Rev001-Emer Response Data System) -1 Page 2 of 6
EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:
TASK-JPM DESIGNATOR: 2007500501 / PLOR-186C WA:
2.4.39 Unit Reactor Operator/Senior Reactor Operator URO: 3.9 SRO: 3.8 TASK DESCRIPTION:
Knowledge of the ROs responsibilities in emergency plan implementation 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 f u nct io n i ng properly or p reven t s uccessf u I task co m p let ion.
- 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 JPhlls, 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, clompletion within the estimated time (listed ir 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.
2008 NRC JPM RO AD-EP (PLOR186C Rev001-Emer Response Data System) -1 Page 3 of 6
B.
TOOLS AND EQUIPMENT
- 1.
EP-MA-1 1 0-100-F-12, Rev. C, PBAPS ERDS Activation C.
REFERENCES
- 1.
EP-MA-110-100, Rev. 7 ERO Computer Applications
- 2.
EP-MA-110-100-F-12, Rev. C PBAPS ERDS Activation D.
TASK STANDARD
- 1.
Satisfactory task completion is indicated when the Emergency Director is informed that the ERDS link has been made.
- 2.
Estimated time to complete: 7 minutes NOT-Time Critical E.
DIRECTIONS TO EXAMINEE When given the initiating cue, perform the actions as the NRC Communicator for an Alest emergency classification. I will describe initial plant conditions and provide you access to the materials required to complete this task.
F.
TASK CONDITIONS/PREREQUISlTES
- 1.
An Alert has just been declared on Unit 2.
- 2.
You have been assigned to be the NRC Communicator G.
INITIATING CUE The Emergency Director directs you to initiate the ERDS link to the NRC via the Plant Monitoring System in accordance with EP-MA-1 IO-100-F-12. Inform the Emergency Director when the connection is made.
2008 NRC JPM RO AD-EP (PLOR186C Rev001-Emer Response Data System) -1 Page 4 of 6
NO STEP ACT STANDARD H.
PERFORMANCE CHECKLIST
" STEP I I
I Perform this JPM ONLY on a PMS terminal located in the simulator.
Performance on a PMS terminal outside of the simulator will result in initiating the ERDS link to the NRC.
1 Obtain a copy of procedure EP-MA-110-100-F-012.
A copy of procedure EP-MA-110-1 OO-F-012 is obtained.
P 2
Review EP-MA-110-100-F-012.
P EP-MA-110-100-F-012 is reviewed
- 3 Locate the PMS terminal.
P The operator locates the PMS terrriinal.
- 4
~
Select the EPDS Menu.
~~
At the PMS terminal, the operator selects the EPDS menu or types "EPD".
P (Cue: EPDS Menu selected.)
- 5 Select the NRC Link Activation.
P At the PMS terminal, the operator selects the NRC Link Activation, or types "NRC".
(Cue: NRC Link Activation selected.)
- 6 Activate the Link.
(Cue: "FI" selected.)
P At the PMS terminal, the operator selects "F 1 'I.
- 7 Select Unit 2.
(Cue: Unit 2 activated.)
P At the PMS terminal, the operator selects "FI" to activate Unit 2.
- a Enter the password.
(Cue: Password "USNRC" entered.)
P At the PMS terminal, the operator types the password "USNRC" and depresses return.
Confirm data is being transmitted.
Visually confirms that ERDS Status Window displays "Sending Data".
9 10 (Cue: ERDS Status Window displays "Sending Data")
Notify the Emergency Director.
~
~~~~
Verbally notify the Emergency Director that the ERDS link to the NRC has been completed.
(Cue: The ED acknowledges the report.)
2008 NRC JPM RO AD-EP (PLOR186C Rev001-Emer Response Data System) -1 Page 5 af 6
- 1) 11 Under ACT P - must perform S - must simulate As an evaluator ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.
P Positive control established.
I.
TERMINATING CUE When the ERDS link to the NRC has been completed and the Emergency Director informed, the evaluator will terminate the exercise.
2008 NRC JPM RO AD-EP (PLOR186C Rev001-Emer Response Data System) -1 Page 6 of 6
TASK CONDlTlONSlPREREQUlSlTES
- 1. An Alert has just been declared on Unit 2.
- 2.
You have been assigned to be the NRC Communicator.
INITIATING CUE The Emergency Director directs you to initiate the ERDS link to the NRC via the Plant Monitoring System in accordance with EP-MA-1 10-1 00-F-12.
Inform the Emergency Director when the connection is made.
EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET APPROVALS:
Signature I Title Date Signature / Title Date Signature / Title Date Signature / Title Date 11 APPROVED FOR USE:
Signature / Title Date EFFECTIVE DATE:
I I
ISSUE DATE:
MI. 1 NAME:
Last First SOC. SEC. NO.
COMPLETION DATE:
COMMENTS:
~
~~
Training Review for Completeness:
PlMS CODE:
SignaturelDate I
ENTRY:
2008 NRC JPM SRO AD-CO1 (NEW - Reactor Coolant Chemistry Limits) -1 Page 1 of 7
TEMPORARY CHANGE FORM LOG TCF #
- 1.
CODE NO.: PLOR-NEWC REV. NO.:
TITLE:
Review and Evaluate Reactor Coolant Chemistry Limits TCF DATE CHANGED SECTION ##
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
IO.
- 11.
- 12.
- 13.
- 14.
- 15.
2008 NRC JPM SRO AD-CO1 (NEW - Reactor Coolant Chemistry Limits) -1 Page 2 of 7
EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:
Senior Reactor Operator TASK-JPM DESIGNATOR: 34431 00402 / PLOR-NEWC WA:
2.1.34 SRO: 3.5 TASK DESC R I PTI ON :
Knowledge of primaw and secondary plant chemistry limits 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 io be given to the examinee.
2008 NRC JPM SRO AD-CO1 (NEW - Reactor Coolant Chemistry Limits) -1 Page 3 of 7
B.
TOOLS AND EQUIPMENT
- 1.
CH-10 chemistry Goals Fill out two separate CH-10-1 Chemistry Recommendation Forms using Attachment 2 of this JPM as a reference.
- 2.
ON-I 26 High Condensate Conductivity
- 3.
REFERENCES I. CH-10, Rev. 15, Chemistry Goals
- 2.
ON-I 26, Rev. 3, High Condensate Conductivity
- 3.
TASK STANDARD
- 1.
Satisfactory task completion is indicated when ON-I 26 High Condensate Conductivity reactor coolant chemistry actions and lechnical Requirements Manual (TRM) Action Levels are determined in response to a condenser tube leak.
- 2.
Estimated time to complete: 15 minutes Non-Time Critical L.
DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to determine immediate plant impact and compensatory measures, if any, for identified system chemistry limits using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.
F.
TASK CON DIT1 ON SPREREQU I SITES
- 1.
- 2.
Unit 2 has been at 100% power for 160 days.
The Hydrogen Water Chemistry Systeni is in service.
- 3.
Chemistry has generated two CH-10-1 Chemistry Recommendation Forms for Unit 2 condensate conductivity and Reactor Water chloride concentration.
- 4.
The CH-10-1 Forms are being brought to the Main Control Room.
- 5.
All the samples have been verified
- 6.
Chemistry has confirmed a severe conductivity intrusion.
2008 NRC JPM SRO AD-CO1 (NEW - Reactor Coolant Chemistry Limits) -1 Page 4 of 7
G.
INITIATING CUE The Shift Manager directs you to determine what immediate plant and/or regulatory actions, if any, exist for the above conditions using:
0 ON-1 26 High Condensate Conductivity, 0
CH-10 Chemistry Goals, 0 TRM 3.9, RCS Chemistry.
Document the results of your determination on the cue sheet.
2008 NRC JPM SRO AD-CO1 (NEW - Reactor Coolant Chemistry Limits) -1 Page 5 of 7
NO If this JPM is performed in the simulator:
STEP ACT STANDARD clave a copy of procedure CH-10 Chemistry Goals available in case it is not available in the simulator.
Procedure ON-126 High Condensate Conductivity, (and TRM 3.9 RCS Chemistry, will be in the simulator.
f this JPM is performed outside of the simulator:
Drovide all three documents to the Examinee at the start of the JPM.
- NOTE TO EVALUATOR****
The following steps can be performed in any order.
1
- 2
- 3 Review the two CH-10-1 Chemistry Recommendation Forms for Unit 2.
(Cue: Hand the Examinee the two CH 1 Chemistry Recommendation Forms which are Attachment 2 of this JPM.)
Enter ON-126 High Condensate Conductivity.
Determine that a plant shutdown per GP-3 Normal Plant Shutdown is required.
P P
P Review both CH-10-1 Chemistry Recommendation Forms.
Review CH-10 Chemistry Goals.
Recognize that condensate pump discharge conductivity > 0.4 pS/cm is a symptom for entry into ON-126.
Recognize the chemistry change as a severe conductivity intrusion (condenser tube leak) and ON-126 directs a plant shutdown using GP-3.
2008 NRC JPM SRO AD-CO1 (NEW - Reactor Coolant Chemistry Limits) -1 Page 6 of 7
4
- 5 6
7 I
STEP Determine that the 2A condenser waterbox needs to be removed from service.
Verify, immediately, by administrative methods that Reactor Coolant System chloride concentration has not been > 0.2 ppm for > 2 weeks in the last calendar year.
(Cue: if asked to assist with administrative check of chloride concentration, reply as the Chemistry Manager and report that chloride concentration has been c 0.2 ppm for the last calendar year.
Communicate to the Shift Manager that the review is complete.
As an evaluator, ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.
nder ACT P - must perform S - must simulate ACT P
P P
P STANDARD Determines that ON-126, step 2.4, cirects isolation of the source of the high conductivity. Using the CH-10-1 Chemistry Recommendation Forms the examinee determines that conductivity is high on the discharge of the 2C condensate pump which is tied to the 2A waterbox.
Recognize that Reactor Coolant System chloride concentration is > 0.2 ppm (actual is 0.22 ppm) limit in TRM Table 3.9-1, therefore, TRM 3.9.B applies.
Document on the CH-10-1 Form that TRM 3.9.B applies and that Reactor Coolant System chloride concentration has not been > 0.2 ppm for > 2 weeks in the last calendar year.
When plant impact and regulatory actions review is complete, the examinee reports the completion to the Shift Manager and hands over the documented results.
Positive control established.
I.
TERMINATING CUE When it is communicated to the Shift Manager that the review is complete and the determination of what immediate plant and/or regulatory actions, if any, exist, the evaluator will then tern-inate the exercise.
2008 NRC JPM SRO AD-CO1 (NEW - Reactor Coolant Chemistry Limits) -1 Page 7 of 7
TASK CONDITIONS/PREREQUISlTES
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
Unit 2 has been at 100% power for 160 days.
The Hydrogen Water Chemistry System is in service.
Chemistry has generated two CH-10-1 Chemistry Recommendation Forms for Unit 2 condensate conductivity and Reactor Water chloride concentration.
The CH-10-1 Forms are being brought to the Main Control Room.
All the samples have been verified.
Chemistry has confirmed a severe conductivity intrusion.
INITIATING CUE The Shift Manager directs you to determine what immediate plant and/or regulatory actions, if any, exist for the above conditions using:
ON-I 26 High Condensate Conductivity, CH-10 Chemistry Goals, TRM 3.9, RCS Chemistry.
Document the results of your determination on this cue sheet.
(Continue on back of sheet if necessary)
CH-10, Rev. 15 Page 11 of 17 FROM :
TO :
SUBJECT :
ATTACHMENT CH 1 EXAMPLE ONLY CHEMISTRY RECOMMENDATION (CR)
CR #3659-08 CHEMISTRY SHIFT SUPERVISOR CHEMISTRY RECOMMENDATION SECTION A ** COMPLETED BY SHIFT CHEMIST **
i DATE/TIME I
SYSTEM PARAMETER i LIMITS i VALUE i
1................................................................ i........................................................... :...
I To-da-y /
- Unit 2 12C Condensate Pump i 0.4 I Now
. Condensate I Discharge Conductivity pS/cm fpS/cm IS THIS CR A FOLLOW-UP TO A VERBAL NOTIFICATION?
YES a IF YES, DATE/TIME AND PERSON NOTIFIED.
N/A DATE / TIME N/A PERSON NOTIFIED
,ORRECTIVE ACTION REQUIRED: Confirmed a severe condensate conductivity intrusion due to a main condenser tube rupture. Investigate and identifp which waterbox is leaking.
SECTION B
- COMPLETED BY SHIFT OPERATIONS PERSONNEL **
THE FOLLOWING CORRECTIVE ACTION WAS TAKEN:
DATE / TIME CORRECTIVE ACTION TAKEN:
SHIFT OPERATOR VERBALLY NOTIFY CHEMISTRY AFTER CORRECTIVE ACTION IS COMPLETED DATE /T IME
~-
PERSON NOTIFIED:
- RETURN THIS SHEET TO CHEMISTRY *****
CHEMISTRY REVIEW:
DATE
CH-10, Rev. 15 Page 11 of 17 ATTACHMENT CH-10-1 EXAMPLE ONLY CHEMISTRY RECOMMENDATION (CR)
CR #3660-08 FROM :
CHEMISTRY TO :
SHIFT SUPERVISOR
SUBJECT:
CHEMISTRY RECOMMENDATION SECTION A ** COMPLETED BY SHIFT CHEMIST **
SYSTEM i
PARAMETER I
LIMITS I VALUE I FOUND I DATE/TIME I
I To-da-y /
U n i t 2 I C h l o r i d e s I <
- - 0.2 ppm j 0.22 ppm I Now i R e a c t o r I C o o l a n t
/ C o n d u c t i v i t y / < 1. 0 pS/cm. 0. 9 7 ps/cm I IS THIS CR A FOLLOW-UP TO A VERBAL NOTIFICATION?
YES IF YES, DATE/TIME AND PERSON NOTIF-TED.
N/A DATE / TIME N/A PERSON NOTIFIED CORRECTIVE ACTION REQUIRED: C o n f i r m e d a severe condensate conductivity intrusion due to a m a i n condenser tube rupture. Investigate and identify w h i c h w a t e r b o x i s leaking.
SECTION B
- COMPLETED BY SHIFT OPERATIONS PERSONNEL **
THE FOLLOWING CORRECTIVE ACTION WAS TAKEN:
DATE / TIME CORRECTIVE ACTION TAKEN:
SHIFT OPERATOR VERBALLY NOTIFY CHEMISTRY AFTER CORRECTIVE ACTION IS COMPLETED PERSON NOTIFIED:
DATE/TIME
- RETURN THIS SHEET TO CHEMISTRY *****
CHEMISTRY REVIEW:
DATE
EXELON NUCLEAR Nuclear Generation Group II OJT/TPE MATERIAL COVERSHEET I
APPROVALS:
Signature /Title Date Signature / Title Date ll Signature I Title Date II Signature I Title Date II 11 APPROVED FOR USE:
Signature I Title Date EFFECTIVE DATE:
I I
ISSUE DATE:
M.I.
~
NAME:
Last First SOC. SEC. NO.
COMPLETION DATE:
COMMENTS:
11 Training Review for Completeness:
I PlMS CODE:
II Signature/Date I
ENTRY:
2008 NRC JPM SRO AD-C02 (NEW - Determine PPE for Racking Out a 480 Volt Breaker)
Page 1 of 5
TEMPORARY CHANGE FORM LOG TCF #
- 1.
CODE NO.: PLOR-NEW REV. NO.:
TITLE:
Determine Personal Protective Equipment for Rackinn Out a 480 Volt Breaker TCF DATE CHANGED SECTION #
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
IO.
- 11.
- 12.
- 13.
- 14.
- 15.
2008 NRC JPM SRO AD-C02 (NEW - Determine PPE for Racking Out a 480 Volt Breaker)
Page 2 of 5
EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:
Senior Reactor Opera-TASK-JPM DESIGNATOR: 2991 780301 / PLOR-NEW WA:
2.1.26 SRO: 3.6 TASK DESCRIPTION:
Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydroqen).
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 lis 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 tiine (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.
2008 NRC JPM SRO AD-C02 (NEW - Determine PPE for Racking Out a 480 Volt Breaker)
Page 3 cf 5
B.
C.
D.
E.
F.
G.
TOOLS AND EQUIPMENT
- 1.
SA-AA-129 "Electrical Safety"
- 2.
Tablet or booklet for Examinee to document results of determination.
REFERENCES
- 1.
SA-AA-129, Rev. 4, "Electrical Safety
TASK STANDARD
- 1.
Satisfactory task completion is indicated when the minimum required proper persainal protective equipment (PPE) has been determined for racking out a 480 Volt breaker using SA-AA-129 "Electrical Safety".
- 2.
Estimated time to complete: 15 minutes Non-Time Critical DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to determine the minimum required personal protective equipment (PPE) using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.
TASK CON D IT1 0 N S/PRE REQ U IS ITES
- 1.
The breaker for the 2A EHC pump needs to be racked out in support of scheduled maintenance.
- 2.
The 2A EHC pump is powered from 480 volt reactor area load center 1 R4.
INITIATING CUE As the Work Execution Control Supervisor, determine the minimum personal protective equipment (PPE) required for racking out the! 2A EHC pump breaker using SA-AA-129 "Electrical Safetv". Document vour determination on the cue sheet.
2008 NRC JPM SRO AD-C02 (NEW - Determine PPE for Racking Out a 480 Volt Breaker)
Page 4 cIf 5
H.
PERFORMANCE CHECKLIST Determine that eye protection is required.
STEP NO P
1 Inform evaluator of completion of the task.
- 2 P
- 3 As an evaluator, ensure that you have positive control of all exam material provided to the examinee (Task Cond itions/Prerequ isites) AND procedures.
- 4 P
- 5 6
7 STEP Review SA-AA-129 "Electrical Safety".
(Cue: Hand the Examinee a copy of SA-M - I 29 "Electrical Safety".)
Determine that Class 2 clothing is required.
P Determine that a face shield is required.
Determine that a hard hat is required.
STANDARD Reviews SA-AA-129 "Electrical Satsty".
References ATTACHMENT 4 - Electrical Safe Work Practices Hazard Assessment.
Uses ATTACHMENT 4 - Electrical Safe Work Practices Hazard Assessmelit, of SA-AA-129, Item 2, for racking in/oA a 480 Volt load center breaker.
Uses ATTACHMENT 4 - Electrical Safe Work Practices Hazard Assessmert, of SA-AA-129, Item 2, for racking i n h t a 480 Volt load center breaker.
Uses ATTACHMENT 4 - Electrical Safe Work Practices Hazard Assessment, of SA-AA-129, Item 2, for racking idout a 480 Volt load center breaker.
Uses ATTACHMENT 4 - Electrical Safe Work Practices Hazard Assessment, of SA-AA-129, Item 2, for racking inlout a 480 Volt load center breaker.
Communicate that the task has been completed.
Positive control established.
Under "ACT" P - must perform S - must simulate I.
TERMINATING CUE When the minimum personal protective equipment (PPE) for racking out a 480 Volt breaKer using SA-AA-129 "Electrical Safety" has been determined, the evaluator will then terminate the exercise.
2008 NRC JPM SRO AD-C02 (NEW - Determine PPE for Racking Out a 480 Volt Breaker)
Page 5 of 5
TASK CONDlTlONSlPREREQUlSlTES I. The breaker for the 2A EHC pump needs to be racked out in support of scheduled maintenance.
- 2.
The 2A EHC pump is powered from 480 volt reactor area load center 1R4.
INITIATING CUE As the Work Execution Control Supervisor, determine the minimum personal protective equipment (PPE) required for racking out the 2A EHC pump breaker using SA-AA-129 "Electrical Safety". Document your determination on this cue sheet.
EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET IFICATION MANUAL OJT MODULE JRE CHANGE APPROVALS:
Signature I Title Date Signature I Title Date Signature I Title Date Signature / Title Date 11 APPROVED FOR USE:
Signature I Title Date EFFECTIVE DATE:
I I
II ISSUE DATE:
COMPLETION DATE:
NAME:
Last First SOC. SEC. NO.
COMMENTS:
Training Review for Completeness:
I PlMS CODE:
I I PlMS ENTRY:
Sig nat u re/Da te 2008 NRC JPM SRO AD-EC (PLOR222C Approve Temp Change) -1
TEMPORARY CHANGE FORM LOG CODE NO.: PLOR-222C REL!. NO.: 001 TITLE:
REVIEW A TEMPORARY PROCEDURE CHANGE I
7 TCF #
TCF DATE CHANGED SECTION #
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
IO.
- 11.
- 12.
- 13.
- 14.
- 15.
2008 NRC JPM SRO AD-EC (PLOR222C Approve Temp Change) -1 Page 2 crf 6
EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:
Senior Reactor OperaiBr TASK-JPM DESIGNATOR: 3421 130302 / PLOR-222C K/A:
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 iri paragraph D.2) is required.
- 5.
The estimated time to complete this JPM, though listed in the task standard, is no to be given to the examinee.
Page 3 of 6 2008 NRC JPM SRO AD-EC (PLOR222C Approve Temp Change) -1
B.
TOOLS AND EQUIPMENT 1
I ST-0-080-520-2 marked-up with a proposed Temporary Change to step 6.1.2 for reactor vessel flange and head flange to be greater than 65 degrees F
- 2.
AD-PB-101-1003, Rev. 8, Temporary Changes to Approved Documents and Partial Procedure Use
- 3. of AD-PB-101-1003. with first three sections filled out.
C.
REFERENCES
- 1.
ST-0-080-520-2, Rev. 3 Reactor Vessel Head Flange Temperature Surveillance
- 2.
AD-PB-101-1003, Rev. 8, 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, the errors in the procedure have been identified and the Temporary Change is disapproved pending resolution of the problems.
- 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/PREREQUISlTES
- 1.
A refuel outage is in progress on Unit 2.
- 2.
Refueling has been completed and reactor vessel reassembly is in progress.
- 3.
An industry notification has been sent to Peach Bottom concerning the accuracy and range of temperature elements associated with the reactor vessel head flange.
- 4.
I&C has contacted operations with this concern and has recommended allowing vessel flange and head flange temperature indications to go as low as 65 degrees F to account for these inaccuracies.
- 5.
A Temporary Change has been prepared for ST-0-080-520-2 Reactor Vessel Head Flange Temperature Surveillance step 6.1.2, to ensure reactor vessel flange and head flange temperature is greater than 65 degrees F.
2008 NRC JPM SRO AD-EC (PLOR222C Approve Temp Change) -1 Page 4 :If 6
G.
INITIATING CUE The Control Room Supervisor directs you, as; the SRO Reviewer, to review and approve The temporary change to ST-0-080-520-2 "Reactor Vessel Head Flange Temperature Surveillance".
E 2008 NRC JPM SRO AD-EC (PLOR222C Approve Temp Change) -1 Page 5 of 6
H.
PERFORMANCE CHECKLIST STEP 7
STEP NO 1
- 2 ACT
- 3 Identify a change of intent.
Note: this is a change to the acceptance criteria in the test.
4 P
Disapprove the procedure change.
(Cue: Acknowledge the disapproval.)
Review ST-0-080-520-2 temporary procedure change.
P P
As an evaluator, ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.
STANDARD Review the procedure change and compare it to the Change of Intent Screening criteria in AD-PB-101-1003.
Identify that the proposed change to step 6.1.2 constitutes a change of intent in accordance with AD-PB-1 01 -1 003 !step 2.1.
Disapprove the temporary procedure change.
Positive control established.
Under ACT P - must perform S - must simulate I.
TERMINATING CUE When the review of ST-0-080-520-2 has been completed, and the temporary procedure change is disapproved, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.
2008 NRC JPM SRO AD-EC (PLOR222C Approve Temp Change) -1 Page 6 of 6
TASK CONDlTlONSlPREREQUlSlTES
- 1.
- 2.
- 3.
- 4.
- 5.
A refuel outage is in progress on Unit 2.
Refueling has been completed, and reactor vessel reassembly is in progress.
An industry notification has been sent to Peach Bottom concerning the accuracy and range of temperature elements associated with the reactor vessel head flange.
I&C has contacted operations with this concern and has recommended allowing vessel flange and head flange temperature indications to go as low as 65 degrees F to account for these inaccuracies.
A Temporary Change has been prepared for ST-0-080-520-2 "Reactor Vessel Head Flange Temperature Surveillance" step 6.1 2, to ensure reactor vessel flange and head flange temperature is greater than 65 degrees F.
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-O-080-520-2 "Reactor Vessel Head Flange Temperature S u rve i I lance".
EXELON NUCLEAR Nuclear Generation Group OJTlTPE MATERIAL COVERSHEET Last First M.I.
SOC. SEC. NO.
APPROVALS:
COMPLETION DATE:
Signature / Title Date Signature /Title Date Signature I Title Date Last First M.I.
SOC. SEC. NO.
Signature / Title Date II COMPLETION DATE:
APPROVED FOR USE:
Signature I Title Date
/I EFFECTIVE DATE:
I I
11 NAME:
I ISSUE DATE:
COMMENTS:
Training Review for Completeness:
I1 PlMS CODE:
Signature/Date I
ENTRY:
1 2008 NRC JPM SRO AD-RC (NRC 2007 Exam - 90 Hour Log) -1 Page 1 cf 6
TEMPORARY CHANGE FORM LOG CODE NO.: PLOR-NEWC RE\\/. NO.: 001 TITLE:
REVIEW AND APPROVE PRIMARY CONTAINMENT PURGENENT ISOIATIOM~
VALVE CUMULATIVE HOUR LOG TCF #
TCF DATE CHANGED SECTION #
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
I O.
- 11.
- 12.
- 13.
- 14.
- 15.
2008 NRC JPM SRO AD-RC (NRC 2007 Exam - 90 Hour Log) -1 Page 2 of 6
EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMA,NCE MEASURE POSITION TITLE:
Senior Reactor Opera-TASK-JPM DESIGNATOR:
2270140201 / PLOR-NEWC WA:
2.3.13 SRO: 3.8 TASK DESCRIPTION:
Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, 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 JPIVls, 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 ir 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.
2008 NRC JPM SRO AD-RC (NRC 2007 Exam - 90 Hour Log) -1 Page 3 of 6
B.
TOOLS AND EQUIPMENT
- 1.
Calculator
- 2.
Copy of ST-0-007-560-2 Primary Containment PurgeNent Isolation Valve Cumulative Hour Log.
0 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 <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br />, with the procedure completed to indicate total time is less than 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> (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 accumulaited time a purgehent valve is open has been determined to be greater than 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br />.
- 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 arid provide you access to the materials required to complete this task.
F.
TASK CON D IT1 0 N SIPRE REQ U IS ITES
- 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 <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. 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 007-560-2 Primary Containment PurgeNent Isolation Valve Cumulative Hour Log.
2008 NRC JPM SRO AD-RC (NRC 2007 Exam - 90 Hour Log) -1 Page 4 of 6
H.
PERFORMANCE CHECKLIST 7
STEP NO 1
2 3
- 4
- 5 6
7 STANDARD I ACT I STEP Sue:
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.
Review ST-0-007-560-2 for completeness.
Verify ca Icu lat ions.
Recognize calculation errors.
Determines the Accumulated Total Time Since Beginning of Year is beyond the Acceptance Criteria specified in Step 5.0.
Notify Shift Management of unsatisfactory test results.
(Cue: Acknowledge report.)
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
P P
P Verifies all procedure steps, Data Sheet 1, and Data Sheet 2 have been completed satisfactorily.
Performs all calculations that were done on Data Sheet 1 to verify they are correct and properly recorded.
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 <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br />.
Determines the Accumulated Total Time Since Beginning of Year is 93 Hr, 22 Min versus 80 Hr, 22 Min.
Reports to Shift Manager and/or Control Room Supervisor that the Accumulated Total Time Since Beginning of Year is greater than 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br />.
Positive control established.
2008 NRC JPM SRO AD-RC (NRC 2007 Exam - 90 Hour Log) -1 Page 5 af 6
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 tiheet 1 identified, and the total accumulated time a purgehent valve is open has been determined to be greater than 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br />, the evaluator will terminate the exercise.
2008 NRC JPM SRO AD-RC (NRC 2007 Exam - 90 Hour Log) -1 Page 6 c4 6
TASK CONDlTlONSlPREREQUlSlTES
- 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 <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. 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.
DATA SHEET 1 6" AND 18" FLOW PATH TOTAL HOUR LOG Any 6" or 18" ALL 6" or 18" Flow Flow Path Accumulated Total Time Flow Path OPEN AND Path CLOSED OR Open Total Since Beginning of Reactor pressure GREATER Reactor pressure LESS Time Calendar Year (Note 1) than 100 PSlG AND Reactor in Mode 1 or2 than 100 PSlG OR Reactor in Modes 3,4, or5 (Hours &
Minutes)
TIME DATE TIME DATE Total Fwd 61 Hr, 28 Min 0131 1 1 11 9108 041 1 1111 9/08 2 Hr, 40 Min 64 Hr 8 Min 0428 11119/08 2132 11119108 5 Hr 4 Min 69 Hr, 12 Min 2147 1111 9/08 2319 1 111 9/08 1 Hr, 32 Min 70 Hr, 44 Min 0916 11123108 1706 11123108 7 Hr, 50 Mtn 77 Hr, 34 Min 1154 1 1/24/08 1442 11/24/08 2 Hr, 48 Min 80 Hr, 22 Min NOTE: 1:
I F "Accumulated Total Tim(: Since Beginning Accumulated Total Time Since Beginning of Calendar Year 90 hrs Initial Sat Unsat R-U -
R-U -
R-n R-U -
R-n I
R-R-n R-U R-n R-n R-n R-U R-D -
R-U of Year" is
DATA SHEET 2 FLOW PATHS USED I n i t i a 1 (See below)
S a t --
Un s a t DAY / SHIFT DATE 3 1 4 1 5 1 6 1 7 1 1
N /A 2
N/A 3
4 5
6 7
~
-~
N/A N/A N/A N/A N/A d
4 N/A 11/18/08
~
-~
N/A N/A N/A N/A N/A d
4 N/A N
TUE D
1 1 /I 9/08 N
1 1120108 WED D
N N /A N/A
~
N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A
~-
~
-~
THUR D
1 1/21 108 N /A N
N /A N /A FRI D
11/22/08 N
II N/A SAT D
11/23/08 d
~
-~
N/A N/A d
N/A N/A N/A N/A N/A N/A N/A N/A N / A 4
4 N/A N/A N/A N/A N/A N/A
-~
~
-~
N N/A 4
N /A SUN D
11/24/08 N
II
- 1. AO-2-07B-2519 and AO-2-07B-2520 OPEN in d Drywell N2 Purge Flowpath
- 2. AO-2-07B-2519 and AO-2-07B-2521B OPEN in a Torus N2 Purge Flowpath
- 3. AO-2-07B-2505 and AO-2-07B-2520 OPEN in a Drywell Purge Supply Flowpath
- 4. AO-2-07B-2521A and AO-2-07B-2521B OPEN in a Torus Purge Supply Flowpath
- 5. AO-2-07B-2506 and AO-2-07B-2507 OPEN in a Drywell Exhaust Flowpath
- 6. AO-2-07B-2511 and AO-2-07B-2512 OPEN in d Torus Exhaust Flowpath
- 7. Abnormal Flowpath.
~.
.~
==
Description:==
D = Day S h i f t - 6:30a - 6:30p N = N i g h t S h i f t - 6:30p - 6:30a
EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET
.I F I CATION MANUAL OJT MODULE I
- /LOCAL NOTIFICATIONS FOR ALERT - HIGH APPROVALS:
Signature /Title Date Signature /Title Date Signature / Title Date Signature / Title Date APPROVED FOR USE:
Signature I Title Date EFFECTIVE DATE:
/
/
"~
ISSUE DATE:
M.I. 1 NAME:
Last First
.~
SOC. SEC. NO.
COMPLETION DATE:
COMMENTS:
Training Review for Completeness:
PlMS CODE:
I' I
2008 NRC JPM SRO AD-EP (PLOR234C EAL - ALERT) -1 Page 1 cif 7
EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:
Senior Reactor Operim TASK-JPM DESIGNATOR: 20075 10502/PLOR-234C WA:
2.4.40 SRO: 4.5 TASK DESCRIPTION:
Knowledge of SRO responsibilities in emergency plan implementation.
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 Ma nag em en t a p prova I.
- 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.
2008 NRC JPM SRO AD-EP (PLOR234C EAL - ALERT) -1 Page 2 of 7
B.
TOOLS AND EQUIPMENT None C.
REFERENCES
- 1.
EP-AA-112-100, Rev 9, Control Room Operations (R)
- 2.
EP-AA-111, Rev. 14, Emergency Classification and Protective Action Recommendations (R)
- 3.
EP-MA-114-100, Rev. 12, Mid-Atlantic State/Local Notifications (R)
- 4.
EP-MA-114-100-F-01, Rev F, State / Local Event Notification Form (R)
- 5.
EP-AA-1007, Table PBAPS 3-1, Rev. 17 Emergency Action Level (EAL) Matrix (R)
- 6.
EP-AA-112-100-F-01, Rev. H, Shift Eimergency Director Checklist
- 7.
EP-AA-114-F-01, Rev C, Release In Progress Determination Guidance (R)
D.
TASK STANDARD
- 1.
Satisfactory task completion is indicated when the plant conditions have been classified correctly and EP-MA-114-IOO-F-OI, State/Local Event Notification Form has been completed accurately.
(NOTE: The criteria for accurate Event Notification form completion was derived.from EP-AA-125-1002, Rev. 4, ERO Performance - Performance Indicators Guidance!).
- 2.
Estimated time to complete: Event Classification - 15 minutes: Time Critical StateILocal 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.
2008 NRC JPM SRO AD-EP (PLOR234C EAL - ALERT) -1 Page 3 (of 7
F.
TASK CONDITIONS/PREREQUISlTES
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
Both Units were initially operating at 100% power.
Storm winds of 90 mph were reported on-site.
Neither the Unit 2 nor the Unit 3 Secandary Containment can be maintained negative.
Unit 2 and Unit 3 Reactor Building Vent Stacks are damaged.
Equipment on Unit 2 Reactor Building elevation 234 is reported to be damaged.
Equipment on Unit 3 Reactor Building elevation 195 is reported to be damaged.
Wind direction is from 20 degrees.
Average wind speed currently is 50 mph.
G.
INITIATING CUE As the Emergency Director, make the EAL classification and complete the State/Local Event Notification form (if required).
2008 NRC JPM SRO AD-EP (PLOR234C EAL - ALERT) -1 Page 4 of 7
H.
PERFORMANCE CHECKLIST NO ACT STANDARD II
- NOTE***
1 Record the time using the clock above the Full I Obtain a copy of procedures EP-AA-112-1 II I 100-F-01 and EP-AA-1007
(Cue: Classification is acknowledged.)
Announce the event classification to the II facilitv staff.
- 4
- 5
- 6 7
ore Di:
P Check the call status.
Check the affected station.
Check the event classification.
Check the affected unit.
P P
P P
This is a drill line is checked in Block #I.
Peach Bottom is checked in Block #2.
Alert classification is checked in E3lock
- 3a.
Units Two and Three are checked in Block #3b.
P P
A copy of procedures EP-AA-112-7 OO-F-01 and EP-AA-1007 are obtained.
The following sections of EP-AA-1 C107, Table PBAPS 3-1 are referenced: Natural and Destructive Phenomena Affecting the Protected Area (HU5), Natural and Destructive Phenomena Affecting the Plant Vital Area (HA5).
The event is classified as an Alert (HA5) due to meeting EALThreshold #2 (based on tornado or high winds > 87 mph within Protected Area resulting in visible damage to plant structures (Reactor Building Vent Stacks) or equipment in any Table H2 area (Reactor Building) or Control Room indication of degraded system performance (positive pressure in Reactor Building).
Announces the event classification to the Control Room crew.
- NOTE***
WHEN the examinee completes the classification determination, THEN record the time using the clock above the1 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 StatelLocal notification process.
- NOTE ***
Inform the examinee that the Public Address announcement and the ERO Notification are NOT reauired for this JPM.
- NOTE ***
The following steps are associated with completion of EP-MA-114-IOO-F-OI, State/Local Evept N o t if ica t io n Form.
2008 NRC JPM SRO AD-EP (PLOR234C EAL - ALERT) -1 Page 5 of 7
- 8 II 17 9
- I 0
- I 1 Positive control established.
As an evaluator, ensure that you have positive control of all exam material provided to the examinee (Task cond ition/Prerequisites) AND procedures.
- I 2
- I 3
- I4 15 16 STEP Enter the time and date of the declaration.
Check the applicable change in classification status.
Enter the EAL number declared AND/OR provide a brief non-technical description of event.
Check the non-routine radiological release status.
Enter the wind direction Degrees from.
(Cue: Wind direction is from 20 degrees.)
Enter the wind speed.
(Cue: Wind speed is 50 mph.)
Check the utility Protective Action Recommendation.
Check the appropriate conclusion.
Enter the Utility Message number and approve the event notification form.
- NC ACT P
P P
P P
E ***
STANDARD Declaration time (in 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> clock nomenclature) and todays date ara entered in Block #3c. The declaralion time should match the time the examiner entered in the note before JPM step 1.
Initial Declaration is checked in Block
- 3d.
EAL# HA5 is annotated in Block #4a AND/OR a simplified explanation for the event classification is provided in Ellock
- 4b. Acronyms, abbreviations or other terms that would not be recognized by state and local response agencies are avoided. The Offsite EAL Referenice Manual may be referred to, if necessary.
NO non-routine radiological release in progress is checked in Block #5. EP-AA-1 14-F-01, Release In Progress Determination Guidance may be referenced.
Wind direction is obtained from either PMS Met data or Control Room panel OOC767 and is entered as the wind direction degrees from in Block #ea.
Minor discrepancy in parameter value is acceptable.
Wind speed is obtained from either-PMS Met data or Control Room panel OOC767 and is entered in Block #6b. Minor discrepancy in parameter value is accedable.
The Not Applicable box is checked in Block #7a.
This is a drill line is checked in Block #8.
The Emergency Director enters I for the Utility Message Number and signs the Event Notification form in the forms header area.
WHEN the examinee completes the Event Notification form, THEN record the time using the clock above the Full Core Display. Time =
Determine if the elamed time since the classification exceeds 13 minutes.
2008 NRC JPM SRO AD-EP (PLOR234C EAL - ALERT) -1 Page 6 i>f 7
Under ACT P - must perform S - must simulate
- 1.
TERMINATING CUE When plant conditions have been classified and EP-MA-114-100-F-01, State/Local Event Notification Form has been completed, the evaluator will then terminate the exercise.
=
2008 NRC JPM SRO AD-EP (PLOR234C EAL - ALERT) -1 Page 7 c:f 7
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
TASK CONDITIONS/PREREQUISlTES Both Units were initially operating at 100% power.
Storm winds of 90 mph were reported on-site.
Neither the Unit 2 nor the Unit 3 Secondary Containment can be maintained negative.
Unit 2 and Unit 3 Reactor Building Vent Stacks are damaged.
Equipment on Unit 2 Reactor Building elevation 234 is reported to be damaged.
Equipment on Unit 3 Reactor Building elevation 195 is reported to be damaged.
Wind direction is from 20 degrees.
Average wind speed currently is 50 mph.
INITIATING CUE As the Emergency Director, make the EAL classification and complete the State/LocaI Event Notification form (if required).