ML083540411
| ML083540411 | |
| 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: ML083540411 (90) | |
Text
EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET
-1 FICAT10N MANUA L OJT MODULE APPROVALS:
Signature /Title Date Signature /Title Dak Signature / Title Date Signature / Title Date 1 APPROVED FOR USE:
Signature I Title Date I EFFECTIVE DATE: I I NAME: ISSUE DATE:
Last First M.I.
SOC. SEC. NO. COMPLETION DATE:
COMMENTS:
Training Review for Completeness: PlMS CODE:
Signature/Date I ENTRY:
2008 NRC JPM CR-a(4) (PLOR309CA Rev011) Recirc Pp Start-I Page 1 of 7
TEMPORARY CHANGE FORM LOG CODE NO.: PLOR-309CA REV. NO.: 011 TITLE: STARTING A RECIRCULATION PUMP (ALTERNATE PATH - SCOOP TUBE LOCKUP)
TCF # TCF DATE CHANGED SECTION #
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2008 NRC JPM CR-a(4) (PLOR309CA Rev011) Recirc Pp Start-I Page 2 of 7
EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2020040101 / PLOR-309CA WA: 202001A4.01 RO: 3.7 SRO: 3.7 TAS K DESCRIPTI0N: STARTING A RECIRCULATION PUMP (ALTERNATE PATH - SCOOP TUBE LOCKUP)
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 approvaI.
- 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 JPhAs, 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 CR-a(4) (PLOR309CA Rev011) Recirc Pp Start-I Page 3 of 7
B. TOOLS AND EQUIPMENT None C. REFERENCES SO 2A.1.B-2, Rev. 45, Starting the Second Recirculation Pump D. TASK STANDARD
- 1. Performance Location: Simulator
- 2. Satisfactory task completion is indicated when the B Reactor Recirculation Pump has been started and subsequently tripped due to a scoop tube lockup.
- 3. Estimated time to complete: 14 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to start the B Reactor Recirculation Pump 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. The 2B Recirculation pump is being placed in service following a spurious trip.
- 2. All the prerequisite steps of SO 2A.1.B-2, Starting the Second Recirculation Pumphave been successfully performed.
- 3. Steps 4.1 through 4.25 of SO 2A.1.B-2, Starting the Second Recirculation Pump have been successfully performed.
- 4. ST-0-02B-510-2, Reactor Coolant Temperatures has been performed. Data from ten minutes ago showed reactor dome to bottom head drain DT is 80°F and the loop to loop DT is 23°F.
- 5. An Equipment Operator is in place to visually verify relays at Panel 2BC152.
G. INITIATING CUE The Control Room Supervisor directs you tcu start the B Reactor Recirculation Pump in accordance with SO 2A.1.B-2, Starting the Second Recirculation Pump, beginning at step 4.26.
2008 NRC JPM CR-a(4) (PLOR309CA RevOll) Recirc Pp Start-I Page 4 of 7
H. PERFORMANCE CHECKLIST I1 STEP I STEP I ACT I STANDARD NO 1 Obtain a copy of procedure SO 2A.l.B-2. A copy of procedure SO 2A.1.B-2 is r p obtained. ~
- NOTE ***
The next step is not applicable if the 'A' Recirc pump speed is already less than 50%. This will depend on simulator initial conditions used.
- 2 Lower "AI Recirc pump speed to less than P Manual control knob is turned 50% as read on SPI-2-02-184-016A. COUNTERCLOCKWISE until SPI-2-02-184-016A indicates 50% at (Cue: SPI-2-02-184-016A is lowering, FR- panel 20C004A.
2-02-154 is lowering, and reactor level is stable.) This step may not be applicable if initial conditions have the 'A' Recirc. Pump speed already less than 50%.
3 Verify the speed of the "AI Recirc pump is "AwRecirc pump speed is verified tcr be less than 50%. less than 50% on SPI-2-02-184-01;A at panel 20C004A.
(Cue: SPI-2-02-184-016A indicates 45%.)
- 4 Verify closed MO-2-02-053BI Recirc Pump MO-2-02-053B green light is verifieil ON at B Discharge Valve. panel 20C004A.
(Cue: MO-2-02-053B green light is on, red linht is off.)
- NOTE ***
Nhen ready to perform a plant announcement to start the Recirc. Pump, inform the Examinee to
@ make the announcement if another JPM is being conducted simultaneously in the simulator.
5 Verify reactor coolant temperatures stated P Verifies that ST-0-02B-510-2, "Reactor in step 4.17.1 and 4.17.2 are still valid. Coolant Temperatures" were perforlmed I within the last 15 minutes indicating that (Cue: ST-0-02B-510-2, "Reactor Coolant Reactor dome to bottom head drain DT is Temperatures" were performed c 145°F AND the loop to loop DT is 4 0 ° F .
satisfactorily I O minutes ago. Reactor dome to bottom head drain DT is 80°F
- 6 P "6"Recirc MG Set Drive Motor Breaker control switch is momentarily placed in the START position at panel 20C004A.
I flashing.) I 2008 NRC JPM CR-a(4) (PLOR309CA Rev011) Recirc Pp Start-I Page 5 of 7
STEP ACT STANDARD 7 Direct an operator to verify that relay 2-2A- P Equipment operator directed to verify relay KO15B is energized. 2-2A-KO15B is energized.
(Cue: Equipment operator acknowledges the direction and reports that relay 2-2A-K015B is eneraized.)
Direct an operator to verify that relay 2-2A- P Equipment operator directed to verify rela)
K022B energizes 20 seconds after the 2-2A-K022B energizes 20 seconds after drive motor starts. the drive motor starts.
(Cue: Equipment operator acknowledges the direction and reports that relay 2-2A-K022B energized 20 seconds after the drive motor start.)
Verify the "B" Recirc MG Set drive motor P "B" Recirc MG Set Drive Motor Breaker starts, generator speed reached 100% red light is verified ON, MG Set speed is and field breaker closes in 21 seconds. verified to increase to 100% on SPI-2-02-184-16B and the "B" Recirc MG (Cue: "B" Recirc MG Set Drive Motor Set Field Breaker red light is verified ON a Breaker red light is on, green light is off. panel 20C004A.
SPI-2-02-184-16B indicates an increase to 100%. 21 seconds later, "B" Recirc MG Set Field Breaker red light is on, green liaht is off.)
- NOTE ***
The next step may not be performed if the examinee decides to trip the '6' Recirc. Drive Motor first.
10 Direct an Equipment operator to verify that ' P Equipment operator directed to verify rela) relay 2-2A-KO15B de-energized 6 seconds 2-2A-KO15B de-energized 2 seconds after after the field breaker closes. the field breaker closes.
(Cue: Equipment operator acknowledges This step may not be performed if the the direction and reports that relay 2-2A- Examinee decides to immediately perform KO15B de-energized 2 seconds after the steps 11 & 12.
field breaker closes.)
- I1 When the field circuit breaker closes, the P Recognizes "B" RECIRC FLUID DFWE "B" RECIRC FLUID DRIVE SCOOP TUBE SCOOP TUBE LOCK and "B" RECjRC LOCK and "B" RECIRC FLUID DRIVE FLUID DRIVE SCOOP TUBE SCOOP TUBE POSITIONER TROUBLE POSITIONER TROUBLE annunciaiors art annunciators are recognized alarming. flashing at panels 213 C-3 and 214 J-I.
(Cue: As soon as the field circuit breaker closes, SPI-2-02-184-016B reading drops to 40% and annunciators 213 C-3 and 214 I J-I begin flashing.)
2008 NRC JPM CR-a(4) (PLOR309CA Rev011) Recirc Pp Start-I Page 6 of 7
STEP ACT STANDARD
- I2 Trip the "B" Recirc Pump Drive Motor "B" Recirc Pump Drive Motor breaker control switch is momentarily placed in the (Cue: "B" Recirc Pump Drive Motor STOP position at panel 20C004A.
breaker green light is on, red light is off.)
13 Inform Control Room Supervisor of the Receipt of the "B" RECIRC FLUID DRIVE receipt of the "B" RECIRC FLUID DRIVE SCOOP TUBE LOCK alarm and trip of the SCOOP TUBE LOCK alarm and trip of the "B" Recirc Pump reported to CRS.
"Bll Recirc Pump.
(Cue: Control Room Supervisor acknow-ledaes rePort.)
14 As evaluator ensure you have positive P Positive Control established.
control of all exam material provided to the examinee (Task Condition / Prerequisites)
AND procedures.
Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When the "B" Recirculation Pump has been started and subsequently tripped due to a scoop tube lockup, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.
2008 NRC JPM CR-a(4) (PLOR309CA RevOll) Recirc Pp Start-I Page 7 of 7
TASK CONDITIONS/PREREQUISlTES
- 1. The "2B" Recirculation pump is being placed in service following a spurious trip.
- 2. All the prerequisite steps of SO 2A.1.B-2, "Starting the Second Recirculation Pump" have been successfully performed.
- 3. Steps 4.1 through 4.25 of SO 2A.l.B-2, "Starting the Second Recirculation Pump" have been successfully performed.
- 4. ST-0-026-510-2, "Reactor Coolant Temperatures" has been performed. Data from ten minutes ago showed reactor dome to bottom head drain DT is 80°F and the loop to loop DT is 23°F.
- 5. An Equipment Operator is in place to visually verify relays at Panel 2BC152 INITIATING CUE The Control Room Supervisor directs you to start the "B" Reactor Recirculation Pump in accordance with SO 2A.l .B-2, "Starting the Second Recirculation Pump", beginning at step 4.26.
EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET APPROVALS: -
I Signature /Title Date Signature / Title Date
~
Signature I Title Date Signature / Title Date 1 APPROVED FOR USE:
Signature I Title Date I
1 :
EFFECTIVE DATE: I I NAME: Last First MI. ISSUE DATE:
SOC. SEC. NO. COMPLETION DATE: -
COMMENTS:
Training Review for Completeness: PlMS CODE:
SignatureIDate 2008 NRC JPM CR-b(1) (PLOR300CA RevOl3) HPCl PB Fails-I Page 1 of 7
TEMPORARY CHANGE FORM LOG CODE NO.: PLOR-300CA REV. NO.: 013 TITLE: Manually Initiate HPCl (Alternate Path - Manual Initiation Pushbutton Fails to Opt-&rate) 1.
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1 2008 NRC JPM CR-b(1) (PLOR300CA RevOl3) HPCl PB Fails-I :z of 7
EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2060050101 / PLOR-300CA WA: 295031EA1.02 URO: 4.5 SRO: 4.5 TASK DESCRIPTION: Manuallv Initiate HPCI (Alternate Path - Manual Initiation P u s h b u m Fails to Operate)
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.
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.
- 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 CR-b(1) (PLOR300CA Rev013) HPCI PB Fails-I 3 of 7
B. TOOLS AND EQUIPMENT I. None
- 2. REFERENCES
- 1. Satisfactory task completion is indicated when HPCl is injecting to the RPV at 5000 gpm.
- 2. Estimated time to complete: 5 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to manually initiate the HPCl system and inject to the Reactor vessel at a flow rate of 5000 gpm using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.
F. TAS K C0NDITI0NS/PREREQ UISITES
- 1. RPV Level is -25 inches and lowering slowly G. INITIATING CUE The Control Room Supervisor directs you to initiate the HPCl system using the HPCl Manual Initiation pushbutton and inject to the Reactor vessel at 5000 gpm using RRC 23.1-2HFCI System Operation During A Plant Event 2008 NRC JPM CR-b(1) (PLOR300CA RevOl3) HPCl PB Fails-I 4 of 7
H. PERFORMANCE CHECKLIST fi NO STEP ACT STANDARD 1 Obtain copy of RRC 23.1-2 "HPCI System P References Section A "HPCI Injection Operation During A Plant Event" Using Manual Initiation Push-buttotY.
2 Arm and depress the HPCl Manual P HPCl Manual Initiation Pushbutton collar Initiation Pushbutton 23A-SI 05. is rotated clockwise to the ARMED position and then the pushbutton is (Cue: Acknowledge pushbutton momentarily DEPRESSED at pane, operation.) 20C004B.
"3 Recognize that the Manual Initiation P Manual Initiation pushbutton failure to pushbutton did not function. function is recognized.
(Cue: HPCl discharge pressure, flow and speed indicate zero. Aux oil pump green light is on, red light is off.)
- NOTE****
IF NEEDED, REPEAT INITIATING CUE TO GET EXAMINEE TO CONTINUE The Control Room Supervisor directs you to initiate the HPCl system using the HPCl Manual lnitiation pushbutton and inject to the Reactor vessel at 5000 gpm using RRC 23.1-2 "HPCI System Operation During A Plant Event"
- NOTE****
Steps 4 through 11 can be performed by the Examinee using either RRC Section A "HPC Injection Using Manual Initiation Push-button" QB RRC Section B "HPCI Injection By Manual Component Operation".
- 4 Simultaneously start the Auxiliary Oil P Auxiliary oil pump control switch is placed Pump, 20P026 and open MO-2-23-014 in the START position while "Supply" va Ive. simultaneously placing MO-2-23-014 "Supply" control switch momentarily in the (Cue: Acknowledge control switch "OPEN" position at panel 20C004B.
operation.)
5 Verify the Auxiliary Oil Pump started. P Verify the Auxiliary Oil pump red light is ON at panel 20C004B or annunciator 222 (Cue: Auxiliary Oil pump red light is on D-5 is alarming at panel 20C204C.
green light is off and annunciator 222 D-5 is alarming, "HPCI AUXILIARY OIL PUMP RUNNING", Turbine Stop and Control valve red lights are on.)
I L 2008 NRC JPM CR-b(1) (PLOR300CA RevOl3) HPCl PI3 Fails-I 5 of 7
STEP ACT STANDARD 6 Verify MO-2-23-014, "Supply" valve is P VlO-2-23-14 red light verified ON, HPCl open. jischarge pressure (PI-2-23-109) alid i P C I speed (SPI-4505) rising at panel (Cue: MO-14 red light is on, green light is 20C004B.
off, HPCl discharge pressure and speed rise.)
- 7 Open MO-2-23-019, "To Feed Line" valve. MO-2-23-019 control switch is momentarily placed in the OPEN position (Cue: Acknowledge control switch at panel 20C004B.
operation.)
8 Verify MO-2-23-019, "To Feed Line" valve MO-2-23-019 red light is verified ON and is open. Flow (Fl-2-23-108) rising at panel 20C004B.
(Cue: MO-19 red light is on, green light is off, HPCl flow rise.)
9 Start the HPCl Gland Seal Condenser P HPCl Gland Seal Condenser Vacuum Vacuum Pump, 20K002. Pump control switch is placed in the START position at panel 20C004B (Cue: Vac pump red light is on, green light is off.)
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10 Verify pump flowrate of 5000 gpm. P A HPCl flowrate of approximately 5000 gpm is verified on Fl-2-23-108 at panel (Cue: Fl-2-23-108 indicates 5000 gpm.) 20COO4B.
11 Adjust HPCl flow controller to maintain P HPCl flow controller setpoint is adjusted level. as necessary to maintain vessel level 5 to 35 inches at panel 20C004B.
(Cue: Level is rising into 5 to 35" band.)
12 Inform Control Room Supervisor that P Task completion reported.
HPCl was manually started and is injectin{
into the RPV.
(Cue: Control Room Supervisor acknowledges report.)
2008 NRC JPM CR-b(1) (PLOR300CA RevOl3) HPCl PB Fails-I 6 of 7
13 As an evaluator ensure that you have P Positive control established.
positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.
Under ACT P - must perform S - must simulate I. TERMINATING CUE When HPCl is injecting into the Reactor vessel at a flow rate of 5000 gpm, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.
2008 NRC JPM CR-b(1) (PLOR300CA RevOl3) HPCl PB Fails-I 7 of 7
TASK CONDlTlONSlPREREQUlSlTES
- 1. RPV Level is -25 inches and lowering slowly.
INITIATING CUE The Control Room Supervisor directs you to initiate the HPCI system using the HPCI Manual Initiation pushbutton and inject to the Reactor vessel at 5000 gpm using RRC 23.1-2, HPCI System Operation During a Plant Event.
EXELON NUCLEAR Nuclear Generation Group OJTITPE MATERIAL COVERSHEET
-1FICATION MANUAL OJT MODULE lves After a GP I Isolation APPROVALS:
Signature /Title Date Signature / Title Date Signature / Title Date Signature / Title Date EFFECTIVE DATE: I I NAME: ISSUE DATE:
Last First M.I.
SOC. SEC. NO. COMPLETION DATE:
Training Review for Completeness: PlMS CODE:
Signature/Date I PlMS ENTRY:
2008 NRC JPM CR-c(2) (PLOR083C RevOO9) Reopen MSlVs after Grp 1-1 Page 1 of 7
EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2000800501 / PLOR-083C K/A: 239001A4.01 RO: 4.2 SRO: 4.0 TASK DESCRlPTION: Reopen the Main Steam Isolation Valves after a GP I Isolation 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 D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.
- 2) For time critical JPMs, c.ompletionwithin 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 CR-c(2) (PLOR083C RevOO9) Reopen MSlVs after Grp 1-1 Page 2 of 7
B. TOOLS AND EQUIPMENT None C. REFERENCES Procedure T-221-2, Rev. 8, Main Steam Isolation Vale Bypass D. TASK STANDARD
- 1. Satisfactory task completion is indicated when Inboard MSIVs are open.
- 2. Estimated time to complete: 10 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to reopen the MSIVs using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.
F. TAS K C0NDITI0NS/PREREQUIS ITES
- 1. Use of this procedure has been directed by the TRIP procedures.
- 2. Main Condenser is available.
- 3. RPV level is known.
- 4. There is no indication of gross fuel failure.
- 5. There is no indication of a Main Stearn Line break.
- 6. All T-221 Tool Packages have been obtained.
- 7. Inboard and Outboard MSlVs are closed.
- 8. Steps 4.1 thru 4.5 of T-221-2, Main Steam Isolation Valve Bypass are complete.
G. INITIATING CUE The Control Room Supervisor directs you to perform T-221-2, Main Steam Isolation Valve Bypass steps 4.6 through 4.12 in order to reopen the MSIVs.
2008 NRC JPM CR-c(2) (PLOR083C RevOO9) Reopen MSIVs after Grp 1-1 Page 3 of 7
H. PERFORMANCE CHECKLIST P
" STEP NO STEP ACT STANDARD 1 Obtain a copy of procedure T-221-2. P A copy of procedure T-221-2 is obtained.
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- 2 Open AO-2-02-086A "AI Outboard MSIV. P AO-2-02-086A control switch is placed in the "AUTO/OPEN" position at panel (Cue: Acknowledge control switch 2OCOO3-01.
operation.)
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3 Verify AO-2-02-086A "AvOutboard MSlV AO-2-02-086A red light is verified ON at is open. panel 2OCOO3-01.
(Cue: AO-2-02-086A red light is on, green light is off.)
- 4 Open AO-2-02-086B "B" Outboard MSlV AO-2-02-086B control switch is placed in the "AUTO/OPEN" position at panel (Cue: Acknowledge control switch 2OCOO3-01.
operation.)
5 Verify AO-2-02-0866 "6" Outboard MSlV AO-2-02-0866 red light is verified ON at is open. panel 2OCOO3-01.
(Cue: AO-2-02-086B red light is on, green light is off.)
- 6 Open AO-2-02-086C "C" Outboard MSIV. AO-2-02-086C control switch is placed in the "AUTO/OPEN" position at panel (Cue: Acknowledge control switch 2OCOO3-01.
operation .)
7 Verify AO-2-02-086C 'IC" Outboard MSlV P AO-2-02-086C red light is verified ON at is open. panel 2OCOO3-01.
(Cue: AO-2-02-086C red light is on, green light is off.)
- 8 Open AO-2-02-086D "D" Outboard MSIV. P AO-2-02-086D control switch is placed in the "AUTO/OPEN" position at panes (Cue: Acknowledge control switch 2OCOO3-01.
operation.)
2008 NRC JPM CR-c(2) (PLOR083C RevOO9) Reopen MSlVs after Grp 1-1 Page 4 of 7
STEP ACT STANDARD 9 Verify AO-2-02-086D "D" Outboard MSlV P AO-2-02-086D red light is verified C)N at IS open. panel 2OCOO3-01.
(Cue: AO-2-02-086D red light is on, green light is off.)
- I0 Open MO-2-02-077, Outboard Main P MO-2-02-077 control switch is Steam Drain valve. momentarily placed in the "OPEN" position at panel 2OCOO3-03.
(Cue: Acknowledge control switch operation.)
11 Verify M0-2-02-077, Outboard Main P MO-2-02-077 red light is verified ON at Steam Drain valve open. panel 2OCOO3-03.
(Cue: MO-77 red light is on, green light is off.)
- I2 Open MO-2-02-074, Inboard Main Steam P MO-2-02-074 control switch is Drain valve. momentarily placed in the "OPEN" position at panel 2OCOO3-03.
(Cue: Acknowledge control switch operation.)
13 Verify MO-2-02-074 Inboard Main Steam P MO-2-02-074 red light is verified ON at Drain valve is open. panel 2OCOO3-03.
(Cue: MO-74 red light is on, green light is Off.)
14 Close MO-2-02-079, Orifice Bypass to P MO-2-02-079 green light is verified ON at Main Cndr valve. panel 2OCOO3-03.
(Cue: MO-79 green light is on, red light is Off.)
- I5 Open MO-2-02-078, Downstream Drain P MO-2-02-078 control switch is valve. momentarily placed in the "OPEN" positior at panel 2OCOO3-03.
(Cue: MO-78 red light is on, green light is Off.)
2008 NRC JPM CR-c(2) (PLOR083C RevOO9) Reopen MSlVs after Grp 1-1 Page 5 cf 7
STEP ACT STANDARD 16 Verify MO-2-02-078 Downstream Drain MO-2-02-078 red light is verified 01"dat valve is open. panel 2OCOO3-03.
(Cue: MO-78 red light is on, green light is Off.)
17 Observe pressure differential across the Pressure differential across the Inboard Inboard MSIVs. MSlVs is determined using PI-2-06-090A(B)(C) at panel 20C005A, Determine the difference between Reactor and "Steam Line" PR-2865 at panel pressure on PI-2-06-090A(B)(C) and 20C008A.
"Steam Line" pressure on PR-2865 on panel 20C008A.
(Cue: PI-2-06-090A(B)(C) indicates 540 psig and "Main Steam Pressure A I and "Main Steam Pressure B" indicate 485 psig and rising slowly.)
18 Verify differential pressure across the P Differential pressure across the inboard inboard MSlVs is less than 150 psid. MSlVs is verified less than 150 psig on PI-2-06-090A(B)(C) at panel 20C005A, (Cue: PI-2-06-090A(B)(C) is 400 psig and and "Steam Line" PR-2865 at panel Main Steam Pressure is 300 psig.) 20C008A.
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- I9 Open AO-2-02-080A " A I Inboard MSIV. P AO-2-02-080A control switch is placed in the "AUTO/OPEN" position at panel (Cue: Acknowledge control switch 2OCOO3-01.
operation.)
20 Verify AO-2-02-080A "AI Inboard MSlV is P AO-2-02-080A red light is verified ON at open. panel 2OCOO3-01.
(Cue: AO-2-02-080A red light is on, green light is off.)
- 2 1 Open AO-2-02-080B "6" Inboard MSlV P AO-2-02-0806 control switch is placed in the "AUTO/OPEN" position at panel (Cue: Acknowledge control switch 2OCOO3-01.
operation.)
22 Verify AO-2-02-080B "Bll Inboard MSlV is P AO-2-02-080B red light is verified ON at open. panel 2OCOO3-01.
(Cue: AO-2-02-080B red light is on, green L light is off.)
2008 NRC JPM CR-c(2) (PLOR083C RevOO9) Reopen MSIVs after Grp 1-1 Page 6 of 7
STEP ACT STANDARD
- 23 Open AO-2-02-080C "C" Inboard MSlV P AO-2-02-080C control switch is placed in the "AUTO/OPEN" position at panel (Cue: Acknowledge control switch 2OCOO3-01.
operation.)
24 Verify AO-2-02-080C "C" Inboard MSlV is P AO-2-02-080C red light is verified ON at open. panel 2OCOO3-01.
(Cue: AO-2-02-080C red light is on, green light is off.)
"25 Open AO-2-02-080D "D" Inboard MSIV. P AO-2-02-080D control switch is placed in the "AUTO/OPEN" position at panel (Cue: Acknowledge control switch 2OCOO3-01.
operation.)
26 Verify AO-2-02-080D "D" Inboard MSlV is P AO-2-02-080D red light is verified ON at open. panel 2OCOO3-01.
(Cue: AO-2-02-080D red light is on, green light is off.)
~~ ~~
Inform Control Room Supervisor of task P Task completion reported.
completion.
(Cue: Control Room Supervisor acknow-ledges report.)
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 P Positive control established.
1 I. TERMINATING CUE When the MSlVs have been reopened, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.
2008 NRC JPM CR-c(2) (PLOR083C RevOO9) Reopen MSlVs after Grp 1-1 Page 7 of 7
TASK CONDITIONS/PREREQUISlTES
- 1. Use of this procedure has been directed by the TRIP procedures.
- 2. Main Condenser is available.
- 3. RPV level is known.
- 4. There is no indication of gross fuel failure.
- 5. There is no indication of a Main Steam Line break.
- 6. All T-221 Tool Packages have been obtained.
- 7. Inboard and Outboard MSlVs are closed.
- 8. Steps 4.1 thru 4.5 of T-221-2, "Main Steam Isolation Valve Bypass" are complete.
INITIATING CUE The Control Room Supervisor directs you to perform T-221-2, "Main Steam Isolation Valve Bypass" steps 4.6 through 4.12 in order to reopen the MSIVs.
EXELON NUCLEAR Nuclear Generation Group OJTITPE MATERIAL COVERSHEET Signature / Title Date
~
Signature / Title Date Signature I Title Date APPROVED FOR USE: -
Signature / Title Date EFFECTIVE DATE: I I
- 8 NAME: ISSUE DATE:
Last First M.I.
SOC. SEC. NO. COMPLETION DATE:
~~
Training Review for Completeness: IPlMS CODE:
Signature/Date I PlMS ENTRY:
It I I 2008 NRC JPM CR-d(3) (NEW) Core Spray Test AP -1 Page 1 of 8
TEMPORARY CHANGE FORM LOG CODE NO.: PLOR-???CA REV. NO.: @
TITLE: PERFORM CORE SPRAY B PUMP CAPACITY TEST FOR IST (Alternate Path - _
Minimum Flow Valve Fails to Open)
TCF # TCF DATE CHANGED SECTION #
1.
2.
3.
4.
5.
6.
7.
a.
I I
t I I
i 9.
IO.
11.
I 12.
I - I 13.
14.
15.
2008 NRC JPM CR-d(3) (NEW) Core Spray Test AP -1 Page 2 of 8
EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2090140101 / PLOR-NEW1CA WA: 209001A4.04 URO: 2.9 SRO: 2.9 TASK DESCRIPTI0N: Ability to manually operate and/or monitor Core Spray minimal flow valves in the control room 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 exarriinee 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 JPhSs, 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 CR-d(3) (NEW) Core Spray Test AP -1 Page 3 c f 8
B. TOOLS AND EQUIPMENT
- 1. None C. REFERENCES
- 1. ST-0-014-212-2, Rev. 1, Core Spray B Pump Capacity Test for I S T D. TASK STANDARD
- 1. Satisfactory task completion is indicated when it is recognized that the Core Spray B Pump has no minimum flow protection, the pump is secured, and Core Spray 6 loop is returned to a normal standby lineup, as specified in the performance steps of ST-0-014-212-2, Section 6.0.
- 2. Estimated time to complete: 15 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to perform Core Spray 2B pump capacity test for IST using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.
F. TASK CONDIT10NSIPREREQUISITES 1I The plant is operating at 100% power.
- 2. An Equipment Operator is standing by in the 2B Core Spray Pump Room.
- 3. Communications are available between the Control Room, 2B Core Spray Pump Ftoom, B and D Core Spray Pump Triangle Room, and Cable Spreading Room.
- 4. Core Spray pump 2B oil level is between the minimum and maximum lines on the sightglass.
- 5. Core Spray pump 26 static pump suction pressure is 6 psig.
- 6. All data recording will be performed (simulated) by a second operator.
G. INITIATING CUE The Control Room Supervisor directs you to perform Core Spray 2B Pump Capacity Test for IST in accordance with ST-0-014-212-2 (provided).
Provide examinee a copy of ST-0-014-212-2 with the following items completed:
0 Section 1 of the cover page Procedure section 2.0, Test Equipment 0 Procedure section 3.0, Prerequisites
-I 2008 NRC JPM CR-d(3) (NEW) Core Spray Test AP -1 Page 4 of 8
H. PERFORMANCE CHECKLIST 7
STEP NO STEP ACT STANDARD 1 CLOSE MO-2-14-011B Core Spray MO-2-14-011B control switch is Outboard Disch. momentarily placed in CLOSE al Panel (Cue: Acknowledge control switch operation) 2 VERIFY CLOSED MO-2-14-011B Core P Verifies that MO-2-14-011B green light is Spray Outboard Disch. ON; red light is OFF at Panel 20C003.
(Cue: MO-2-14-011B green light is ON; red light is OFF.)
If this JPM is being performed in parallel with another JPM, direct candidate NOT to make the plant page announcement prior to starting 2 8 Core Spray pump.
3 START 2BP037 Core Spray B Pump. P Starting 2B Core Spray pump is announced on plant page prior to starting (Cue: Acknowledge control switch Core Spray pump 2B.
operation.)
2B Core Spray pump control switch is momentarily placed in the START position at Panel 20C003.
4 VERIFY Core Spray 2B Pump STARTS P 2B Core Spray pump green light is and is RUNNING by observing motor verified OFF, red light is verified ON.
current on 14A-MI B and discharge Pump motor amps on ammeter 14A-MI B pressure on PI-2-14-048B Core Spray and discharge pressure on PI-2-14-048B Disch P. are verified rising at Panel 20C003.
(Cue: Ammeter 14A-MIB indicates 40 amps, PI-2-14-048B indicates 350 psig.)
5 VERIFY MO-2-14-005B Core Spray B P MO-2-14-005B green light is verified Min Flow automatically OPENS. OFF; red light is verified ON at Panel 20C003.
(Cue: MO-2-14-005B green light is OFF; red light is ON.)
6 VERIFY 2DP037 Core Spray D Pump is P Directs Equipment Operator to verify NOT rotating. Core Spray D Pump is NOT rotating.
(Cue: When requested, report that the Core Spray D Pump is NOT rotating.)
2008 NRC JPM CR-d(3) (NEW) Core Spray Test AP -1 Page 5 of 8
/j STEP
~
STANDARD
~~ ~ ~ ~
- 7 OPEN MO-2-14-026B Core Spray Full MO-2-14-026B control switch is Flow Test. momentarily placed in OPEN at Panel 20C003.
(Cue: Acknowledge control switch operation)
VERI FYOPEN MO-2-14-026B Core P MO-2-14-026B green light is verified Spray Full Flow Test. OFF; red light is verified ON at Panel 20C003.
(Cue: MO-2-14-0266 green light is OFF; red light is ON)
VERIFY MO-2-14-0056 Core Spray B MO-2-14-005B green light is verified ON; Min Flow automatically CLOSES. red light is verified OFF at Panel 20C003.
(Cue: MO-2-14-005B green light is ON; red light is OFF.)
Time-compress by telling the examinee Core Spray B Pump has been running for !5 minutes.
Remind examinee that a second operator has successfully recorded all full flow test data on Data Sheet I.
~ ~ ~ ~~
- I 0 THROTTLE MO-2-14-026B Core Spray P MO-2-14-026B control switch is Full Flow Test to obtain Rated Flow of momentarily placed in CLOSE at Panel 3125 to 3175 gpm as read on computer 20C003. Red pushbutton is depressed to point H056. stop valve stroke. Valve control switch and red pushbutton are operated as (Cue: Acknowledge control switch and necessary to achieve 3125 to 3175 gpm red pushbutton operation. MO-2-14-026B as read on PMS computer point H056.
green light is ON; red light is OFF.
Computer point H056 indicates 0 gpm.) Recognizes that the MO-2-14-026E3 has ramped close unexpectedly and that the green closed light is ON and that the red open light is verified OFF at Panel 20C003.
Report to the CRS that the MO-2 026B full flow test valve for the 28 Core Spray Pump has failed to properly operate 2008 NRC JPM CR-d(3) (NEW) Core Spray Test AP -1 Page 6 of 8
STEP ACT STANDARD
~ ~~
11 VERIFY MO-2-14-005B Core Spray B P Recognizes that the MO-2-14-0053 green Min Flow automatically OPENS. light is ON; red light is OFF at Pariel 20C003. The Min. Flow Valve has not (Cue: MO-2-14-005B green light is ON; automatically opened.
red light is OFF.)
Report to the CRS that the minimum flow valve for the 2B Core Spray Pump has failed to properly operate.
- I2 SHUTDOWN 2BP037 Core Spray B P 2B Core Spray pump control switclh is Pump. momentarily placed in the STOP position at Panel 20C003.
(Cue: Acknowledge control switch operation. Core Spray B Pump green 2B Core Spray pump green light is light is ON; red light is OFF. Pump motor verified ON, red light is verified OFF.
amps and pump discharge pressure are Pump motor amps on ammeter 14,A-MI6 zero.) and discharge pressure on PI-2-14-048B are verified at zero at Panel 20C003.
As the Control room Supervisor, direct that the 2 6 Core Spray loop be returned to a normal lineup.
13 Open MO-2-14-011B Core Spray P MO-2-14-011B control switch is Outboard Disch. momentarily placed in OPEN at Panel 20C003.
(Cue: Acknowledge control switch operation) 14 VERIFY OPEN MO-2-14-011B Core P MO-2-14-011B green light is verified Spray Outboard Disch. OFF; red light is verified ON at Panel 20C003.
(Cue: MO-2-14-011B green light is OFF; red light is ON)
~ ~
15 Inform Control Room Supervisor of task P Control Room Supervisor notified F40 completion. 14-026B malfunction and test being aborted.
16 As an evaluator, ensure that you have P Positive control established.
positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AN D L procedures.
2008 NRC JPM CR-d(3) (NEW) Core Spray Test AP -1 Page 7 of 8
Under ACT P - must perform S - must simulate I. TERMINATING CUE When it is recognized that the Core Spray B Pump has no minimum flow protection, the pump is secured, and Core Spray B loop is returned to a normal standby lineup, as specified in the performance steps of ST-0-014-212-2, Section 6.0, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.
2008 NRC JPM CR-d(3) (NEW) Core Spray Test AP -1 Page 8 of 8
TASK CONDITIONS/PREREQUISlTES
- 1. The plant is operating at 100% power.
- 2. An Equipment Operator is standing by in the 2 9 Core Spray Pump Room.
- 3. Communications are available between the Control Room, 2B Core Spray Pump Room, B and D Core Spray Pump Triangle Room, and Cable Spreading Room.
- 4. Core Spray pump 2 9 oil level is between the minimum and maximum lines on the sightglass.
- 5. Core Spray pump 2B static pump suction pressure is 6 psig.
- 6. All data recording will be performed (simulated) by a second operator.
INITIATING CUE The Control Room Supervisor directs you to perform Core Spray 2B pump capacity test for IST in accordance with ST-Q-014-212-2 (provided).
EXELON NUCLEAR Nuclear Generation Group OJTlTPE MATERIAL COVERSHEET Si'gnature/Title Date Signature I Title Date Segnature I Title Date (1 APPROVED FOR USE:
Signature I Title Date I EFFECTIVE DATE: I I NAME:
Last SOC. SEC. NO.
COMMENTS:
First
" ISSUE DATE:
COMPLETION DATE:
Training Review for Completeness: PlMS CODE:
SignatureIDate 1I PlMS ENTRY:
I -.
2008 NRC JPM CR-e(1) (PLOR024C Rev008) Grp 1 Reset -1 Page Iof 12
TEMPORARY CHANGE FORM LOG CODE NO.: PLOR-024C REV. NO.: 008 TITLE: Perform a Group I PClS Isolation Reset (GP-8A)
TCF 4 l TCF DATE C W G E D SECTION #
1.
9.
IO.
11.
12.
13.
14.
15.
2008 NRC JPM CR-e(1) (PLOR024C Rev008) Grp 1 Reset -1 Page 2 of 12
EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operat<rr/SeniorReactor Operator TASK-JPM DESIGNATOR: 2000490501 / PLOR-024C WA: 223002A4.03 URO: 3.6 SRO: 3.5 TASK DESCRIPTlON: Perform a Group I PClS Isolation Reset GP-8A)
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 approvaI.
- 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 irr 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 CR-e(1) (PLOR024C Rev008) Grp 1 Reset -1 Page 3 of 12
B. TOOLS AND EQUIPMENT Hand the Examinee a copy of C.O.L. GP-8.A with "As Found Position" column initials already filled in.
C. REFERENCES I. Procedure GP-8.A, Rev. 10, "PCIS Isolation - Group I"
- 2. C.O.L. GP-8.A, Rev. 8, "Group I Isolation" D. TASK STANDARD
- 1. Satisfactory task completion is indicated when the PClS Group I Isolation is reset.
- 2. Estimated time to complete: 8 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to reset the PClS Group I isolatioii using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.
F. TAS K C0NDITI0NS/PREREQ UISITES
- 1. The plant had been at 100% power.
- 2. A PClS Group I isolation has occurred and has been verified to be a result of Main Steam tunnel high temperature.
- 3. The cause of the PClS Group I isolation has been corrected.
- 4. The plant is in a safe, stable shutdown condition.
- 5. CAV (Crack Arrest Verification) System is in operation.
- 6. GP-8.A, "PCIS Isolation - Group I" steps 3.1 and 3.2 have been completed.
- 7. There is no indication of fuel damage.
- 8. There is no evidence of a steam leak.
2008 NRC JPM CR-e(1) (PLOR024C Rev008) Grp IReset -1 Page 4 of 12
G. INITIATING CUE The Control Room Supervisor directs you to reset the PClS Group I isolation logic per steps 4.1 through 4.4 of GP-8.A, "PCIS Isolation - Group I".
2008 NRC JPM CR-e(1) (PLOR024C Rev008) Grp 1 Reset -1 Page 5 of 12
H. PERFORMANCE CHECKLIST
~
STEP NO STEP 1 Obtain copies of procedures GP-8A P Copies of procedures GP-8A and and COL GP-8A. COL GP-8A are obtained.
I I I
- NOTE**
Provide examinee with the marked up COL GP-8A.
- 2 Place switch to "CLOSE" for P AO-2-02-080A control switch placed AO-2-02-080A. in the "CLOSE" position at panel 2OCOO3-01.
(Cue: Acknowledge control switch operation.)
3 Initial the AO-2-02-080A box in the P "CHECKED BY" column for "CHECKED BY" column on COL AO-2-02-080A initialed on COL GP-8A. GP-8A.
- 4 Place switch to "CLOSE" for P AO-2-02-080B control switch placed AO-2-02-0806. in the "CLOSE' position at panel 2OCOO3-01.
(Cue: Acknowledge control switch operation.)
5 Initial the AO-2-02-080B box in the P "CHECKED BY" column for "CHECKED BY" column on COL AO-2-02-080B initialed on COL GP-8A. GP-8A.
- 6 Place switch to "CLOSE" for P AO-2-02-080C control switch placed AO-2-02-080C. in the "CLOSE" position at panel 2OCOO3-01.
(Cue: Acknowledge control switch operation.)
7 Initial the AO-2-02-080C box in the P "CHECKED BY" column for "CHECKED BY" column on COL AO-2-02-080C initialed on COL GP-8A. GP-8A.
"8 Place switch to "CLOSE" for P AO-2-02-080D control switch placed AO-2-02-080D. in the "CLOSE" position at panel 2OCOO3-01.
(Cue: Acknowledge control switch operation.)
2008 NRC JPM CR-e(1) (PLOR024C Rev008) Grp 1 Reset -1 Page 6 of 12
STEP ACT STANDARD 9 Initial the AO-2-02-080D box in the P "CHECKED BY" column for "CHECKED BY" column on COL AO-2-02-080D initialed on COL GP-8A. GP-8A.
"10 Place switch to "CLOSE" for P AO-2-02-086A control switch placed AO-2-02-086A. in the "CLOSE" position at panel 2OCOO3-01.
(Cue: Acknowledge control switch operation.)
11 Initial the AO-2-02-086A box in the P "CHECKED BY" column for "CHECKED BY" column on COL AO-2-02-086A initialed on COL GP-8A. GP-8A.
- I2 Place switch to "CLOSE" for P AO-2-02-086B control switch placed AO-2-02-086B. in the "CLOSE" position at panel 2OCOO3-01.
(Cue: Acknowledge control switch operation.)
13 Initial the AO-2-02-086B box in the P "CHECKED BY" column for "CHECKED BY" column on COL AO-2-02-086B initialed on COL GP-8A. GP-8A.
"14 Place switch to "CLOSE" for P AO-2-02-086C control switch placed AO-2-02-086C. in the "CLOSE" position at panel 2OCOO3-01.
(Cue: Acknowledge control switch operation.)
15 Initial the AO-2-02-086C box in the P "CHECKED BY" column for "CHECKED BY" column on COL AO-2-02-086C initialed on COL GP-8A. GP-8A.
- I6 Place switch to "CLOSE" for P AO-2-02-086D control switch placed AO-2-02-086D. in the "CLOSE" position at panel 2OCOO3-01.
(Cue: Acknowledge control switch operation.)
~ ~~
17 Initial the AO-2-02-086D box in the P "CHECKED BY" column for "CHECKED BY" column on COL AO-2-02-086D initialed on COL GP-8A. GP-8A.
2008 NRC JPM CR-e(1) (PLOR024C Rev008) Grp 1 Reset -1 Page 7 of 12
STEP ACT STANDARD 18 Verify switch in "CLOSE" for P AO-2-02-039 control switch verified 40-2-02-039. in the "CLOSE" position at panel 20C004A.
(Cue: Switch in 'CLOSE.)
19 N/A or initial the AO-2-02-039 box in P "CHECKED BY" column for the "CHECKED BY" column on COL AO-2-02-039 N/A'd or initialed on GP-8A. COL GP-8A.
20 Verify switch in "CLOSE" for P AO-2-02-040 control switch verified AO-2-02-040. in the "CLOSE" position at panel 2OC004A.
(Cue: Switch in 'CLOSE".)
~ ~~
21 N/A or initial the AO-2-02-040 box in P "CHECKED BY" column for the "CHECKED BY" column on COL AO-2-02-040 NIAd or initialed on GP-8A. COL GP-8A.
22 Verify switch in "CLOSE" for AO-2-02-316 control switch verified AO-2-02-316. in the "CLOSE" position at panel 2OCOO3-03.
(Cue: Switch in 'CLOSE.)
23 N/A or initial the AO-2-02-316 box in "CHECKED BY" column for the "CHECKED BY" column on COL AO-2-02-316 N/Ad or initialed on GP-8A. COL GP-8A.
24 Verify switch in "CLOSE" for AO-2-02-317 control switch verified AO-2-02-3 I7. in the "CLOSE" position at panel 2OCOO3-04.
(Cue: Switch in 'CLOSE".)
25 N/A or initial the AO-2-02-317 box in "CHECKED BY" column for the "CHECKED BY" column on COL AO-2-02-317 N/Ad or initialed on GP-8A. COL GP-8A.
26 Verify MO-2-02-074 is CLOSED. P MO-2-02-074 green light verified ON at panel 2OCOO3-03.
(Cue: MO-2-02-074 green light is on, red light is off.)
27 N/A or initial the MO-2-02-074 box in P "CHECKED BY" column for the "CHECKED BY" column on COL MO-2-02-074 N/A'd or initialed on GP-8A. COL GP-8A.
2008 NRC JPM CR-e(1) (PLOR024C Rev008) Grp 1 Reset -1 Page 8 of 12
ACT STANDARD 28 Verify MO-2-02-077 is CLOSED. P MO-2-02-077 green light verified ON at panel 2OCOO3-04.
(Cue: MO-2-02-077 green light is on, red light is off.)
29 N/A or initial the MO-2-02-077 box in P "CHECKED BY" column for the "CHECKED BY" column on COL MO-2-02-077 N/Ad or initialed on GP-8A. COL GP-8A.
30 Verify switch in "CLOSE" for P AO-8098A control switch verified in AO-8098A. the "CLOSE" position at panel 2OCOO3-04.
(Cue: Switch in 'CLOSE.)
31 N/A or initial the AO-8098A box in P "CHECKED BY" column for AO-the "CHECKED BY" column on COL 8098A N/Ad or initialed on COL GP-8A. GP-8A.
32 Verify switch in "CLOSE" for AO-8098C control switch verified in AO-8098C. the "CLOSE" position at panel 2OCOO3-04.
(Cue: Switch in 'CLOSE.)
33 N/A or initial the AO-8098C box in "CHECKED BY" column for the "CHECKED BY" column on COL AO-8098C N/A'd or initialed on COL GP-8A. GP-8A.
34 Verify switch in "CLOSE" for AO-8099A control switch verified in AO-8099A. the "CLOSE" position at panel 2OCOO3-04.
(Cue: Switch in 'CLOSE".)
35 N/A or initial the AO-8099A box in "CHECKED BY" column for the "CHECKED BY" column on COL AO-8099A N/Ad or initialed on COL GP-8A. GP-8A.
36 Verify switch in "CLOSE" for P AO-8099C control switch verified in AO-8099C. the "CLOSE" position at panel 2OCOO3-04.
(Cue: Switch in 'CLOSE".)
37 N/A or initial the AO-8099C box in P "CHECKED BY" column for AO-the "CHECKED BY" column on COL 8099C N/A'd or initialed on COL GP-8A. GP-8A.
2008 NRC JPM CR-e(1) (PLOR024C Rev008) Grp 1 Reset -1 Page 9 of 12
STEP ACT STANDARD 38 Verify switch in "CLOSE" for P AO-8098B control switch verified in AO-8098B the "CLOSE" position at panel 2OCOO3-02.
(Cue: Switch in 'CLOSE'.)
~~~
39 N/A or initial the AO-8098B box in P "CHECKED BY" column for AO-the "CHECKED BY" column on COL 8098B N/A'd or initialed on COL GP-8A. GP-8A.
40 Verify switch in "CLOSE" for AO-8098D control switch verified in AO-8098D. the "CLOSE" position at panel 2OCOO3-02.
(Cue: Switch in 'CLOSE.)
~
41 N/A or initial the AO-8098D box in P "CHECKED BY" column for AO-the "CHECKED BY" column on COL 8098D N/A'd or initialed on COL GP-8A. GP-8A.
42 Verify switch in "CLOSE" for P AO-8099B control switch verified in AO-8099B. the "CLOSE"position at panel 2OCOO3-02.
(Cue: Switch in "CLOSE".)
43 N/A or initial the AO-8099B box in P "CHECKED BY" column for AO-the "CHECKED BY" column on COL 8099B N/Ad or initialed on COL GP-8A. GP-8A.
44 Verify switch in "CLOSE" for P AO-8099D control switch verified in AO-8099D. the "CLOSE" position at panel 2OCOO3-02.
(Cue: Switch in 'CLOSE.)
~
45 N/A or initial the AO-8099D box in P "CHECKED BY" column for AO-the "CHECKED BY" column on COL 8099D N/Ad or initialed on COL GP-8A. GP-8A.
- NOTE,**
The C.O.L. steps for AO-2256 "Condenser Offgas to Mechanical Vacuum Pump (MVP)"
and the MVP are not required to be performed and can be marked as N/A.
2008 NRC JPM CR-e(1) (PLOR024C Rev008) Grp 1 Reset -1 Page 10 of 12
_ _ _ _ _ ~
derify isolation signal cleared. P The following Group I Isolation annunciators are verified not lit:
- Cue: The following annunciators are not lit: 227 B-2, 228 A-2, 228 E- 227 B-2 and 228 A-2, 3, 228 E-4)
OR 228 E-3 and 228 E-4 3R Verifies no alarms on Steam Leak Detection Panel (located on riverside back wall of simulator)
- 47 Place the Inboard PClS Reset P The Inboard PClS Reset Switch is Switch, 16A-S32, in the "GRP I" momentarily placed in the "GRP I" Dosition. position at panel 20C005A.
[Cue: Acknowledge reset switch Dperation.)
~~~ -.
- 48 Place the Outboard PClS Reset P The Outboard PClS Reset Switch is Switch, 16A-S33, in the "GRP I" momentarily placed in the "GRP I" position. position at panel 20C005A.
(Cue: Acknowledge reset switch Dperation.)
49 Verify "CHANNEL A and B GROUP I P The "CHANNEL A and B GROUP I ISOLATION RELAYS NOT RESET" ISOLATION RELAYS NOT RESET" annunciators clear. annunciators 21 1 H-I and 21 1 J-I are verified not lit.
(Cue: Annunciators 21 1 H-I and 21 1 J-I are not lit.)
50 Inform Control Room Supervisor of P Task completion reported.
task completion.
(Cue: Control Room Supervisor acknowledges report.)
2008 NRC JPM CR-e(1) (PLOR024C Rev008) Grp 1 Reset -1 Page 11 of 12
F- As an evaluator, ensure that you have positive control of all exam material provided to the examinee P Positive control established.
/I (Task ConditionslPrerequisites)AND procedures.
Under ACT P - must perform S - must simulate I. TERMINATING CUE When the PClS Group I isolation is reset, the Control Room Supervisor should be informed.
The evaluator will then terminate the exercise.
2008 NRC JPM CR-e(1) (PLOR024C Rev008) Grp 1 Reset -1 Page 12 of 12
TASK CONDITIONS/PREREQUISITES
- 1. The plant had been at 100% power.
- 2. A PCIS Group I isolation has occurred and has been verified to be a result of Main Steam tunnel high temperature.
- 3. The cause of the PCIS Group I isolation has been corrected.
- 4. The plant is in a safe, stable shutdown condition.
- 5. CAV (Crack Arrest Verification) System is not in operation.
6 . GP-8.A, "PCIS Isolation - Group I" steps 3.1 and 3.2 have been completed.
- 7. There is no indication of fuel damage.
- 8. There is no evidence of a steam leak.
INITIATING CUE:
The Control Room Supervisor directs you to reset the PCIS Group I isolation logic per steps 4.1 through 4.4 of GP-8.A, "PCIS Isolation -
Group I".
EXELON NUCLEAR Nuclear Generation Group OJTITPE MATERrAL COVERSHEET LIFlCAT1ON MANUAL OJT MODULE APPROVALS:
Signature /Title Date Signature / Title Date Signature / Title Date Signature / Title Date 1 APPROVED FOR USE:
Signature / Title Date EFFECTIVE DATE: I I NAME: ISSUE DATE:
Last First SOC. SEC. NO. COMPLETION DATE:
COMMENTS:
Training Review for Completeness: 1 PlMS CODE:
I PlMS ENTRY:
SignatureIDate 2008 NRC JPM CR-f(4) (PLOR031C Rev011) Excite Main Generator -1 Page 1 of 7
TEMPORARY CHANGE FORM LOG CODE NO.: PLOR-031C REV. NO.: Q I J
TITLE: EXCITING THE MAIN GENERATOR, TCF # TCF DATE CHANGED SECTION #
2008 NRC JPM CR-f(4) (PLOR031C Rev011) Excite Main Generator -1 Page 2 of 7
EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor OperatorISenior Reactor Operator TASK-JPM DESIGNATOR: 2370110101 / PLOR-031C K/A: 262001A4.04 RO: 3.6 SRO: 3.7 TASK DESCRIPTION: EXCITING THE MAIN GENERATOR 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 lime (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 CRf(4) (PLOR031C Rev011) Excite Main Generator -1 Page 3 i f 7
B. TOOLS AND EQUIPMENT None C. REFERENCES Procedure SO 50.1.A-2 Rev. 11, Main Generator Synchronizing and Loading (R)
D. TASK STANDARD
- 1. Performance Location: Simulator
- 2. Satisfactory task completion is indicated when the Main Generator is excited, generator terminal voltage is adjusted to 22 KV, and the automatic voltage regulator is in service.
- 3. Estimated time to complete: 10 minutes (A.5) Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to excite the Main Generator 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. Plant startup in progress with reactor power at approximately 18%.
- 2. All SO 50.1.A-2, Main Generator Synchronizing and Loading prerequisites are met.
- 3. The Power System Director has beer) notified.
G. INITIATING CUE The Control Room Supervisor directs you, the Plant Reactor Operator, to excite the Main Generator and place the automatic voltage regulator in service in accordance with steps 4.1 throuah 4.8 of SO 50.1.A-2. Main Generator Svnchronizina and Loadina.
2008 NRC JPM CR-f(4) (PLOR031C Rev011) Excite Main Generator -1 Page 4 (of 7
H. PERFORMANCE CHECKLIST
" STEP STEP ACT STANDARD NO 1 Obtain a CODV of SO 50.1.A-2. P 4 CODV of SO 50.1.A-2 is obtained 2 Verify "GENERATOR INSULATION OVER P 'GENERATOR INSULATION OVER HEATING" annunciator is clear. HEATING" annunciator is verified clear on alarm panel 206 L-2.
(Cue: Annunciator 206 L-2 is not lit.)
Verify the "Load Selector" pushbutton is P Load Selector REMOTE/AUTO light is selected to REMOTE/AUTO. verified ON at panel 20C008A.
(Cue: Load Selector REMOTElAUTO light is on.)
Verify "RegTTransfer" switch 43-0601 in P Regulator Transfer switch 43-0601 is MANUAL. verified in the MANUAL position at panel 20C009.
(Cue: "RegTTransfer" switch is in manual, green light is on, red light is off.)
5 Verify the Manual DC Volt Regulator Manual DC Voltage Regulator 70-Ci601 70-0601 set at minimum. green and amber lights are verified ON at Panel 20C009.
(Cue: Manual DC Volt Regulator green and amber lights are on, red light is off.)
6 Direct an Equipment Operator to Equipment Operator is directed to periodically monitor machine gas pressure periodically monitor machine gas pressure on PI-4356. on PI-4356.
(Cue: Equipment Operator reports PI-4356 indicates 75 Dsia.)
- 7 Close the "Alt Exc Fld Bkr" 41-0601. Alterrex Exciter Field Breaker control switch 41-0601 is momentarily placed in (Cue: Acknowledge control switch the CLOSE position at panel 20CQ09.
operation, Alt Exciter Field Breaker red light is on, green light is off.)
8 Verify Field Volts, Amps and Generator FIELD AMPS and VOLTS and Volts- rise and red deexcitation backup GENERATOR VOLTS are verified to RISE light lit. and DEEXCITATION backup red light is verified ON and green light OFF at panel (Cue: FIELD voltmeter indicates 100 volts, 20C009.
FIELD ammeter indicates 1400 amps, GENERATOR voltmeter indicates 17 kilovolts; DEEXCITATION backup red lighi is on, green light is off.)
2008 NRC JPM CR-f(4) (PLOR031C Rev011) Excite Main Generator -1 Page 5 of 7
c STEP Adjust GENERATOR output voltage to I ACT P
STANDARD Manual DC Voltage Regulator 70-0601 is Dbtain 21.5 - 22.5 KV using MAN. DC adjusted to obtain a GENERATOP output VOLT REGULATOR 70-0601. voltage between 20.9 and 23.1 Kb at panel 20C009.
(Cue: Generator voltmeter indicates 22 KV. Manual DC voltage regulator green light off, yellow light on.)
10 Verify GENERATOR output voltage is GENERATOR output voltage is verified between 21.5 - 22.5 KV. between 21.5 and 22.5 KV on GEPI VOLTMETER at panel 20C009.
(Cue: GENERATOR VOLTMETER indicates 22 KV.)
- I1 Adjust the "Auto Voltage Reg Auto Voltage Reg Rheostat 9OP is*
Rheostat"(9OP) to obtain a "Reg Man/Auto adjusted to obtain a reading within 2 volts Deviation" voltage of 0 VDC. of 0 on the Reg Man/Auto Deviation meter at panel 20C009.
(Cue: Acknowledge CLOCKWISE Rheostat oDeration.)
12 Verify "Reg Man/Auto Deviation voltage is P Reg Man/Auto Deviation voltage is verified 0 VDC. to be 0 VDC on the Reg Man/Auto Deviation voltmeter at panel 20C009.
(Cue: Reg Man/Auto Deviation meter indicates 0 VDC.)
I 13 Verify "GEN VOLT REG AUTO TO MAN "GEN VOLT REG AUTO TO MAN UNBALANCED~I annunciator is clear.. UNBALANCED" annunciator is verified clear on alarm panel 220 C-3.
(Cue: Annunciator 220 C-3 is not lit.)
- I4 Place the "RegTTransfer"
- switch 43-0601 Regnransfer switch 43-0601 is placed in in "AUTO". the AUTO position at panel 20C009.
(Cue: Acknowledge control switch operation.)
15 Verify the "ReglTransfer" lights indicate P Regnransfer red light is verified ON and auto regulation. green light verified OFF at panel 20C009.
(Cue: The ReglTransfer red light is on, green light is off.)
16 Inform the Control Room Supervisor of P Task completion reported.
task completion.
(Cue: Control Room Supervisor acknow-ledges report.)
17 As an evaluator, ensure that you have P Positive control established.
positive control of all exam material provided to the examinee (Task L Conditions/Prerequisites) AN D procedures.
-i 2008 NRC JPM CR-f(4) (PLOR031C Rev011) Excite Main Generator -1 Page 6 of 7
Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When the Main Generator exciter field breaker is closed and the automatic voltage regulator is in service, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.
2008 NRC JPM CR-f(4) (PLOR031C Rev011) Excite Main Generator -1 Page 7 of 7
TASK CONDITIONS/PREREQUISITES
- 1. Plant startup in progress with reactor power approximately 18YO .
- 2. All SO 50.1.A-2, Main Generator Synchronization and Loading prerequisites are met.
- 3. The Power System Director has been notified.
INITIATING CUE The Control Room Supervisor directs you, the Plant Reactor Operator, to excite the Main Generator and place the automatic voltage regulator in service in accordance with I steps 4.1 through 4.8 of SO 50.1.A-2, Main Generator Synchronization and Loading.
EXELON NUCLEAR Nuclear Generation Group OJTlTPE MATERIAL COVERSHEET IFlCATlON MANUAL OJT MODULE c\
J APPROVALS:
Signature / Title Date Signature / Title Date
~
Signature /Title Date Signature /Title Date j/ APPROVED FOR USE:
Signature I Title Date
~
- I EFFECTIVE DATE: I 1 NAME: ISSUE DATE:
Last First SOC. SEC. NO. COMPLET10N DATE:
COMMENTS:
Training Review for Completeness: PlMS CODE:
Signature/Date I PlMS ENTRY:
2008 NRC JPM CR-g(2) (PLOR004C Rev011) Reset Scram - 1 Page 1 crf 7
EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor OperatorlSenior Reactor Operator TASK-JPM DESIGNATOR: 2120090101 / PLOR-004C WA: 212000A4.14 RO: 3.8 SRO: 3.8 TASK DESCRIPTION: SCRAM RESET 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.
2008 NRC JPM CR-g(2) (PLOR004C Rev011) Reset Scram - 1 Page 2 of 7
- 6. TOOLS AND EQUIPMENT Key for Scram Discharge Volume High Level Bypass Switch.
C. REFERENCES GP-11.E, Rev. 21 Reactor Protection System - Scram and ARI Reset D. TASK STANDARD
- 1. Satisfactory task completion is indicated when the Reactor Protection System is reset and the Scram Discharge Volume Vent and Drain valves are open.
- 2. Estimated time to complete: 19 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to reset a scram and begin draining the Scram Discharge Volume using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.
F. TASK C0NDITI0NS/PREREQUISITES
- 1. A Main Turbine trip has caused a reactor scram.
- 2. Plant conditions have stabilized with RPV level at 23 inches.
- 3. RPV pressure is being maintained below 1050 psig with Bypass Valves.
- 4. T-100, Scram is complete.
- 6. A CRD pump is operating.
- 7. Both RPS buses are energized.
- 8. The Reactor Mode switch is in SHUTDOWN.
- 9. ARI was NOT initiated.
IO. No fuel damage is suspected.
G. INITIATING CUE The Control Room Supervisor directs you to reset the scram in accordance with GP-11.E, Reactor Protection System - Scram and ARI Reset and begin draining the Scram Discharge Vol ume.
7 2008 NRC JPM CR-g(2) (PLOR004C Rev011) Reset Scram - 1 Page 3 of 7
H. PERFORMANCE CHECKLIST
[I STEP NO STEP ACT STANDARD
~ ~~~~
1 Obtain a copy of GP-11.E, "Reactor P A copy of GP-11.E, "Reactor Protection Protection System - Scram and ARI System - Scram and ARI Reset is Reset". obtained.
2 Verify scram initiating signal clear or P "TURBINE STOP VLV. CLOSURE AND bypassed. CONTROL VLV. FAST CLOSURE SCRAM BYPASS" annunciator is verified (Cue: Annunciator 210 A-2 is lit.) lit on alarm panel 210 A-2.
- 3 Place Scram Discharge Volume High P Key is obtained from CRS keybox, Water Level Bypass Keylock Switch to inserted into the Scram Discharge Volume "BYPASS". High Water Level Bypass Keylock Switch 5A-S8 and placed in the "BYPASS" (Cue: Annunciator C-2 on alarm panel position at panel 20C005A.
210 is alarming.)
4 Acknowledge the "SCRAM DISCHARGE P The annunciator "ACKNOWLEDGE" VOLUME HI WATER LEVEL SCRAM pushbutton is depressed on panel BYPASS" annunciator. 20C005A.
(Cue: Annunciator 210 C-2 is lit solid.)
5 Prior to resetting a full scram, notify P Contacts Rad. Protection personnel via Radiation Protection. radio, phone, or plant page.
(Cue: Evaluator responds as Rad.
Protection management and acknowledges notification.
- 6 Place Scram Reset switch in Group 1 and P Scram Reset switch 5A-S9 is takeri to the 4 position then Group 2 and 3 position. "GROUP 1 & 4", and then "GROUP 2 & 3" positions at panel 20C005A.
(Cue: Acknowledge reset switch operation.)
7 Verify the four scram group white lights P All scram group white lights verified LIT on are lit on both the RPS cabinets. panels 20C015 and 20C017.
(Cue: All of the scram group white lights are lit on both 20C015 and 20C017.)
2008 NRC JPM CR-g(2) (PLOR004C Rev011) Reset Scram - 1 Page 4 of 7
STEP ACT STANDARD
- ~
8 Verify "A CHANNEL AUTO SCRAM" and P "A CHANNEL REACTOR AUTO SCRAM" "B CHANNEL AUTO SCRAM" and "B CHANNEL REACTOR AUTO annunciators are clear. SCRAM" annunciators are verifiect clear on alarm panels 21 1 B-I and 21 1 12-1.
(Cue: Annunciators 211 B-I and 211 C-I are not lit.)
~
9 Monitor Scram Air header pressure. P Scram air header pressure is verified to be approximately 70 psig on Pl-2-3-3*I 2 on (Cue: Pl-2-3-312 indicated 73 psig.) panel 20C205R.
10 Verify "SCRAM VALVE PILOT AIR P "SCRAM VALVE PILOT AIR HEADER HEADER PRESS HI-LOWgannunciator is PRESS HI-LOW' annunciator is verified clear. clear on alarm panel 21 1 D-2.
(Cue: Annunciator 21 1 D-2 is not lit.)
11 Verify blue scram lights are off. P All blue scram lights are verified OFF on the Full Core Display.
(Cue: All of the blue scram lights are off on the Full Core Display.)
12 Verify "ACCUMULATOR TROUBLE" lights P AI I "ACCUMULATOR TRO UBLE" B ights are clear. are verified clear on the Full Core Display.
(Cue: All of the "ACCUMULATOR TROUBLE" lights are clear on the Full Core Display.)
13 Verify "CRD ACCUMULATOR LO PRESS P "CRD ACCUMULATOR LO PRESS HI HI LEVEL" annunciator is clear. LEVEL" annunciator is verified clear on alarm panel 21 1 E-2.
(Cue: Annunciator 211 E-2 is not lit.)
- NOTE **
Step 14 will take approximately 5 minutes to complete.
14 Verify CRD System Cooling Water flow is P CRD System Cooling Water flow is 55 - 65 gpm. verified to be 55 - 65 gpm on FI-2-03-306 on panel 20C005A.
(Cue: Fl-2-03-306 indicates 60 gpm.)
2008 NRC JPM CR-g(2) (PLOR004C RevOll) Reset Scram - 1 Page 5 of 7
STEP ACT STANDARD 15 Place the Rod Drift Alarm Reset switch to P Rod Drift Alarm Reset switch 3 A 4 7 is the "Reset" position. momentarily placed to the "RESET" position and then released at pane I (Cue: Acknowledge reset switch 20C005A.
operation.)
16 Verify the rod drift alarm lights are clear. P All of the rod drift alarm lights are verified clear on the Full Core Display.
(Cue: All of the rod drift alarm lights are clear on the full core display.)
~
17 Verify "ROD DRIFT annunciator is clear P "ROD DRIFT annunciator is verified clear on alarm panel 21 1 D-4.
(Cue: Annunciator 21 1 D-4 is not lit.)
- I8 Place SDV Inboard Vent and Drain Valves P The SDV Inboard Vent and Drain Valve Switch, 5A-S14A, in "OPEN". control switch 5A-SI4A is momentarily placed in the "OPEN" position and then (Cue: Acknowledge control switch released at panel 20C005A.
operation.)
19 Verify the SDV Inboard Vent and Drain P SDV Inboard Vent and Drain Valves red Valves indicate open. lights are verified ON at panel 20C005A.
(Cue: SDV Inboard Vent and Drain Valves red lights are on, green lights are Off.)
- 20 Place SDV Outboard Vent and Drain P The SDV Outboard Vent and Drain Valve Valves Switch, 5A-S14B, in "OPEN". control switch 5A-SI4B is momentarily placed in the "OPEN" position and then (Cue: Acknowledge control switch released at panel 20C005A.
operation.)
21 Verify the SDV Outboard Vent and Drain P SDV Outboard Vent and Drain Valves red Valves indicate open. lights are verified ON at panel 20CQ05A.
(Cue: SDV Outboard Vent and Drain Valves red lights are on, green lights are Off.)
22 Inform Control Room Supervisor of task P Task completion reported.
completion.
(Cue: Control Room Supervisor acknowledges report.)
L 2008 NRC JPM CR-g(2) (PLOR004C Rev011) Reset Scram - 1 Page 6 of 7
STEP NO STEP ACT STANDARD Positive control established.
control of all exam material provided to the examinee (Task Conditions /
Under ACT P - must perform S - must simulate I. TERMINATING CUE When the scram is reset and the Scram Discharge Volume Vents and Drains are open, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.
2008 NRC JPM CR-g(2) (PLOR004C Rev01 1) Reset Scram - 1 Page 7 of 7
TASK CONDlTlONSlPREREQUlSlTES
- 1. A Main Turbine trip has caused a reactor scra
- 2. Plant conditions have stabilized with RPV l e v d at 23 inches.
- 3. RPV pressure is being maintained below 1050 psig with Bypass Valves.
- 4. T-100, "Scram" is complete.
- 6. A CRD pump is operating.
- 7. Both RPS buses are energized.
- 8. The Reactor Mode switch is in "SHUTDOWN".
- 9. ARI was -NOT initiated.
I O . No fuel damage is suspected.
INITIATING CUE The Control Room Supervisor directs you to reset the scram in accordance with GP-11.E, "Reactor Protection System - Scram and ARI Reset" and beain draining the Scram Discharge Volume.
EXELON NUCLEAR Nuclear Generation Group OJTlTPE MATERIAL COVERSHEET APPROVALS: ,~
Signature I Title Date Siignature I Title Date Signature I Title Date Signature I Title Date 1 APPROVED FOR USE:
Signature I Title Date EFFECTIVE DATE: I I NAME: ISSUE DATE:
Last First M.I.
SOC. SEC. NO. COMPLETION DATE: .-
Training Review for Completeness: PlMS CODE:
PlMS ENTRY:
Signatu re/Date 2008 NRC JPM CR-h(3) (2005 NRC Exam) DWCW-RBCCW -1 Page 1 of 6
TEMPORARY CHANGE FORM LOG CODE NO.: PLOR-NEW REV. NO.:
TITLE: Verify Isolation of D w e l l Chilled Water and RBCCW TCF ## TCF DATE CHANGED SECTION #
9.
IO.
11.
12.
13.
14.
15.
L 2008 NRC JPM CR-h(3) (2005 NRC Exam) DWCW-RBCCW -1 Page 2 i>f6
EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2130220401/ PLOR-NEW WA: 295024EA1.07 URO: 3.8 SRO: >3.9 TASK DESCRIPTION: Verify Isolation of D w e l l Chilled Water and RBCCW 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 %-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 JRM, though listed in the task standard, is no1 to be given to the examinee.
2008 NRC JPM CR-h(3) (2005 NRC Exam) DWCW-RBCCW .-1 Page 3 of 6
B. TOOLS AND EQUIPMENT None C. REFERENCES GP-8.6, Rev. 18, PCIS Isolation - Groups II and 111 (R)
D. TASK STANDARD
- 1. Satisfactory task completion is indicated when the RBCCW to Drywell isolation valves MO-2373 and MO-2374 are closed AND both Recirculation Pumps are tripped.
- 2. Estimated time to complete: 10 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps of GP 8.B PCIS Isolation - Groups II and 111. I will describe initial plant conditions and provide you access to the materials required to complete this task.
F. TASK CONDlTlONSlPREREQUlSlTES
- 1. The Reactor has just been scrammed.
- 3. DWCW Return Header pressure as read on PI-20262 is 32 psig.
- 4. Drywell pressure is approximately 24 psig.
G. INITIATING CUE The Control Room Supervisor directs you, the Plant Reactor Operator, to perform step 5.5 of GP-8.B, PCIS Isolation - Groups II and 111.
2008 NRC JPM CR-h(3) (2005 NRC Exam) DWCW-RBCCW -1 Page 4 of 6
H. PERFORMANCE CHECKLIST NO STEP ACT STANDARD 1 Obtain a copy of procedure GP-8.B. P A copy of procedure GP-8.B is obtained.
2 Verify MO-20245 AND MO-20246 aligned P MO-20245 AND MO-20246 red "CHILLED in the "CHILLED WATER" position. WATER" lights are lit. MO-20245 AND MO-20246 red "RX BLDG CLG WATER" (Cue: MO-20245 AND MO-20246 red lights are out at Panel 20C005A.
"CHILLED WATER" lights are lit. MO-20245 AND MO-20246 red "RX BLDG CLG WATER' lights are out.)
- 3 Calculate corrected RBCCW pressure P Indicated RBCCW pressure is checked, (CRP) by taking indicated RBCCW then 25 psig is subtracted to determine a pressure on PI-2350 minus 25 psig. CRP of approximately 15 psig.
(Cue: PI-2350 is indicating 40 psig.)
P Recognize that DWCW Return Header Return Header pressure. pressure is greater than Drywell prga assure (Cue: Comparison acknowledged) and DWCW isolation is not required and not performed.
- 5 Compare Drywell pressure to Corrected P Corrected RBCCW Pressure (CRP) is RBCCW Pressure (CRP) to determine determined to be less than PR-2508 or which pressure is greater. PR-4805 or PR-8102A(B) at panels 20C003/ 20C004C.
(Cue: PR-2508 indicates 24 psig.)
/1 *6 ITrip BOTH Recirc pumps. P The control switches for the Drive Motor Breakers on both A and B Recirc "DRIVE (Cue: Both Recirc pumps breaker green MOTOR" breakers are placed in TRIP at lights are on and red lights are off. panel 20C004A.
Annunciators 214 C-3 and H-3 are lit.)
7 Verify BOTH Recirc pumps are tripped. P A and B Recirc "DRIVE MOTOR" breaker green lights are verified to be ON at panel (Cue: Both Recirc pumps breaker green 20C004A.
lights are on and red lights are off.)
- 8 Close MO-2373, RBCCW Isolation valve. P MO-2373 control switch is momentarily placed in the "CLOSE" position at panel (Cue: Acknowledge control switch 20c012.
operation.)
2008 NRC JPM CR-h(3) (2005 NRC Exam) DWCW-RBCCW -1 Page 5 of 6
ACT STANDARD P MO-2373 green light is verified OM red light is verified OFF at panel 2C P MO-2374 control switch is moment placed in the "CLOSE" position at 20c012.
(Cue: Acknowledge control switch 11 Verify the MO-2374, the RBCCW Isolation P MO-2374 green light is verified ON valve is closed. red light is verified OFF at panel 2C (Cue: MO-2374 green light is on, red light is off.)
12 Inform Control Room Supervisor of task P Task completion reported.
completion.
ledges report.)
13 As an evaluator, ensure that you have P Positive control established.
positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND Drocedures.
Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When step 3.5 of GP-8.B has been completed, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.
2008 NRC JPM CR-h(3) (2005 NRC Exam) DWCW-RBCCW -1 Page 6 of 6
TASK CONDlTlONSlPREREQUlSlTES
- 1. The Reactor has just been scrammed.
- 2. DWCW Return Header pressure as read on PI-20262 is 32 psig.
- 3. Drywell pressure is 24 psig.
INITIATING CUE The Control Room Supervisor directs you, the Plant Reactor Operator, to perform step 3.5 of GP-8.B, PCIS Isolation - Groups II and 111.
EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET
-I FlCAT1ON MANUAL OJT MODULE APPROVALS: -.
Signature / Title Date Signature I Title Date Signature / Title Date Signature /Title Date IAPPROVED FOR USE:
Signature / Title Date EFFECTIVE DATE: I I NAME:
Last First M.I.
1 ISSUE DATE:
SOC. SEC. NO. 1 COMPLETION DATE: -"
COMMENTS:
~ _ _
~~
Training Review for Completeness: PIMS CODE:
PlMS ENTRY:
Signature/Date 2008 NRC JPM IP (i) (PLOR074P RevOl3) Vent Scram Header Page 1 af 6
TEMPORARY CHANGE FORM LOG CODE NO.: PLOR-074P REV. NO.: 013 TITLE: ISOLATING AND VENTING SCRAM AIR HEADER - UNIT 3 (T-214-3)
TCF # TCF DATE CHANGED SECTION #
7 9.
IO.
11.
12.
13.
14.
r 15.
2008 NRC JPM IP (i)(PLOR074P Rev013) Vent Scram Header Page 2 e4 6
EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2003810599 / PLOR-074P WA: 295037EA1.03 RO: 4.1 SRO: 4.1 TASK DESCRIPTION: ISOLATING AND VENTING SCRAM AIR HEADER - UNIT 3 (T-214-3)
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.
2008 NRC JPM IP (i) (PLOR074P RevOl3) Vent Scram Header Page 3 of 6
B. TOOLS AND EQUIPMENT
- 1. EOP Locker Key
- 2. T-214-3 Tool Package C. REFERENCES Procedure T-214-3, Rev. 7, Isolating and Venting the Scram Air Header D. TASK STANDARD
- 1. Satisfactory task completion is indicated when the Unit 3 scram air header has been isolated and vented.
- 2. Estimated time to complete: 8 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to isolate and vent the Unit 3 scram air header 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 I. A partial loss of feed flow on Unit 3 results in RPV level dropping below the scram setpoint.
- 2. Control Rods did NOT insert.
- 3. Blue scram lights on the Full Core Display are NOT lit.
G. INITIATING CUE The Control Room Supervisor directs you, the Equipment Operator to perform T-214-3, Isolating and Venting the Scram Air Header on Unit 3.
2008 NRC JPM IP (i)(PLOR074P Rev013) Vent Scram Header Page 4 c f 6
H. PERFORMANCE CHECKLIST
" STEP STEP ACT STANDARD NO
- I Obtain the key for the Emergency S Emergency Operating Procedure Tool Operating Procedure Tool Locker. Locker Key requested from WECS OR examinee identifies the location of the (Cue: When examinee requests EOP WECS keybox and its associated key.
Tool Locker key from WECS OR Produces own copy of Tool Locker Key.
examinee identifies the location of the WECS keybox and its associated key then evaluator should provide the EOP Tool Locker key. Examinee may produce their c o w of Tool Locker Kev.)
- 2 Open Emergency Operating Procedure P Tool Locker located on Radwaste IE3uilding Tool Locker and obtain T-214 Tool Kit. El. 165' is unlocked, opened and T-214 Tool Kit located.
(Cue: Equipment obtained.) I
- NC 'E****
When examinee locates tool kit, inform him that he now has the tools to perform the procedure. Provide the examinee with a copy of the T-200 procedure which corresponds to the tool kit that has been chosen. DO NOT allow tools to be removed from the locker.
Relock the locker before leavina the area.
- 3 Close HV-3-3-123, lnstr Air Header Block S HV-3-3-123 handwheel is turned Vlv to Scram Pilot Valve Header. CLOCKWISE until resistance of valve seal is felt. (Located on RB Unit 3 135' CRD (Cue: Valve handwheel is turned Valve Nest.)
[CLOCKWISE] until stem length above valve yoke lowers 1 inch then handwheel will not turn.)
4 Verify closed IDV-3-3-312, PS-3-03-230 + S IDV-3-3-312 handwheel movement is PS-3-03-229 Instrument Drain Valve. attempted in the CLOCKWISE direction.
(Cue: [CLOCKWISE] Valve handwheel did not move and stem length above valve voke did not move.)
- 5 Remove the cap from IDV-3-3-312. S Pipewrench from Tool Kit is placed on IDV-3-3-312 pipe cap and is turned (Cue: Pipe cap is turned COUNTERCLOCKWISE until pipe cap is
[COUNTERCLOCKWISE] until cap is removed from pipe.
removed.)
- 6 Open IDV-3-3-312. S IDV-3-3-312 is turned COUNTER-CLOCKWISE until resistance of valve (Cue: Valve is turned [COUNTER- backseat is felt.
CLOCKWISE] until stem length above valve yoke raises % inch then will not turn, flow noise can be heard as valve is L opened.
2008 NRC JPM IP (I) (PLOR074P Rev013) Vent Scram Header Page 5 of 6
STANDARD Task completion reported using tet hand held radio, or GAI-TRONICS system.
Positive control established Under ACT P - must perform S - must simulate I. TERMINATING CUE When the Unit 3 scram air header has been isolated and vented, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.
2008 NRC JPM IP (i) (PLOR074P RevOl3) Vent Scram Header Page 6 clf 6
TASK CONDITIONS/PREREQUISITES
- 2. Control Rods did NOT insert.
- 3. Blue scram lights on the Full Core Display are NOT lit.
INITIATING CUE The Control Room Supervisor directs you, the Equipment Operator to perform T-214-3, Isolating and Venting the Scram Air Header on Unit 3.
EXELON NUCLEAR Nuclear Generation Group OJTlTPE MATERIAL COVERSHEET Valve Auto Open Signal APPROVALS: -~
Signature I Title Date Signature I Title Date
~
Siiy~atureI Title Date Signature I Title Date
/ APPROVED FOR USE:
Signature / Title Date EFFECTIVE DATE: I I NAME: ISSUE DATE:
Last First M.I.
SOC. SEC. NO. - I COMPLETION DATE:
COMMENTS:
Training Review for Completeness: PlMS CODE:
~
PlMS ENTRY:
Sig nature/Date 2008 NRC JPM IP(j) (NEW) RClC Defeat Suct Auto Open Page 1 of 6
TEMPORARY CHANGE FORM LOG CODE NO.: PLOR-000C REV. NO.: @
TITLE: Defeat of RClC Torus Suction Valve Auto Open Signal TCF # TCF CSATE CHANCED SECTfOlrl#
2008 NRC JPM IP(j) (NEW) RClC Defeat Suct Auto Open Page 2 of 6
EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2170280401 / PLOR-000C K/A: 217000A2.04 URO: 3.0 SRO: 3.0 TASK DESCRIPTION: Defeat of RClC Torus Suction Valve Auto Open Signal A. NOTES TO EVALUATOR:
- 1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL S EPS 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 no! to be given to the examinee.
2008 NRC JPM IP(j) (NEW) RClC Defeat Suct Auto Open Page 3 of 6
B. TOOLS AND EQUIPMENT
- 1. Two (2) electrical boots for HFA relay contacts
- 2. Two blank Equipment Status tags C. REFERENCES
- 1. A 0 13.3-2, Rev. 1, RCIC Torus Suction Valves, Defeat of Auto Open Signal D. TASK STANDARD
- 1. Satisfactory task completion is indicated when the Unit 2 RClC Torus suction valve auto open signal has been defeated.
- 2. Estimated time to complete: 15 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to defeat the Unit 2 RClC Torus suction valve auto open signal using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.
F. TASK CONDIT1ONS/PREREQUISITES
- 1. Shift Management has given permission to perform this task.
- 2. The Unit 2 Reactor Operator has given permission to perform this task.
- 3. Annunciator 222 (A-5) LOGIC POWER BUS LOST is in alarm.
- 4. Shift Management has changed A 0 13.3-2, Attachment 1 steps 4.1.3 and 4.1.4, from required double verification (DV) to concurrent verification (CV).
G. INITIATING CUE The Control Room Supervisor directs you, the Equipment Operator, to defeat the auto open signal to MO-2-13-39 and MO-2-13-41, RCIC Torus suction valves, by performing steps 4.1.3 throuah 4.1.6 of A 0 13.3-2. RCIC Torus Suction Valves. Defeat of Auto ODen Sianal.
2008 NRC JPM IP(j) (NEW) RClC Defeat Suct Auto Open Page 4 of 6
H. PERFORMANCE CHECKLIST GF NO STEP ACT STANDARD
~ ~~
I Obtain a copy of procedure A 0 13.3-2, P A copy procedure A 0 13.3-2, RCIC: Torus RClC Torus Suction Valves, Defeat of Suction Valves, Defeat of Auto Open Auto Open Signal. Signal is obtained.
(Cue: When the Examinee requests the in-progress copy of A 0 13.3-2 OR identifies how to obtain a controlled copy of the procedure, provide a hardcopy of procedure A 0 13.3-2, RClC Torus Suction Valves, Defeat of Auto Open Signal with Attachment 1 steps 4.1 . I and 4.1.2, for Shift Management and URO signoffs, already filled in AND steps 4.1.1 and 4.1.2 checked complete).
2 Obtain two electrical HFA relay contact P The Examinee obtains two electrical relay boots and two blank Equipment Status contact boots and two Equipment Status tags. tags from the Main Control Room area or an alternate area such as an equipment (Cue: two electrical relay contact boots cage or I&C instrument cage.
AND two blank Equipment Status tags are obtained).
E****
Prior to booting the contacts in the next steps the examinee may have to open the back of Panel 20C034 in order to verify the appropriate relay contact locations.
- 3 Boot contacts 1-2 of relay 13A-K55. S In the Cable Spreading Room, panel 20C034, the cover of relay 13A-K55 is (Cue: Contacts 1-2 of relay 13A-K55 are removed. A single electrical boot is slid booted) over contacts 1-2 (first relay finger from the right).
4 Signoff Attachment 1 step 4.1.3. P A 0 13.3-2 Attachment 1 step 4.1.3 is signed off on the Initial line.
(Cue: A 0 13.3-2 Attachment 1 step 4.1.3 is signed off on the Initial line) 5 Attach an Equipment Status tag to the S Equipment Status tag with string is placed boot on contacts 1-2 of relay 13A-K55. on boot of contacts 1-2 of relay 13AK55.
L (Cue: Equipment Status tag is attached to boot on contacts 1-2 of relay 13A-K55).
l l 2008 NRC JPM IP(j) (NEW) RClC Defeat Suct Auto Open Page 5 of 6
Boot contacts 3-4 of relay 13A-K55. S A single electrical boot is slid over contacts 3-4(second relay finger from the (Cue: Contacts 3-4 of relay 13A-K55 are right).
booted) 7 Signoff Attachment 1 step 4.1.4. P A 0 13.3-2 Attachment 1 step 4.1.4 is signed off on the Initial line (Cue: A 0 13.3-2 Attachment 1 step 4.1.4 is signed off on the Initial line)
~~
8 Attach an Equipment Status tag to the S Equipment Status tag with string is placed boot on contacts 3-4 of relay 13A-K55. on boot of contacts 3-4 of relay 13A-K55.
9 Inform Control Room Supervisor of task P Task completion reported using either the completion. telephone or the plant page systerri.
10 As an evaluator, ensure that you have P Positive control established.
positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.
Under ACT P - must perform S - must simulate I. TERMINATING CUE When Attachment 1 of A 0 13.3-2 has been completed, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.
2008 NRC JPM IP(j) (NEW) RClC Defeat Suct Auto Open Page 6 of 6
TASK CONDlTlONSlPREREQUlSlTES
- 1. Shift Management has given permission to perform this task.
2.The Unit 2 Reactor Operator has given permission to perform this task.
- 3. Annunciator 222 (A-5) LOGIC POWER BUS LOST is in alarm.
- 4. Shift Management has changed A 0 13.3-2, Attachment 1 steps 4.1.3 and 4.1.4, from required double verification (DV) to concurrent verification (CV).
INITIATING CUE The Control Room Supervisor directs you, the Equipment Operator, to defeat the auto open signal to MO-2-13-39 and MO-2-13-41, RCIC Torus suction valves, by performing steps 4.1.3 through 4.1.6 of A 0 13.3-2, RCIC Torus Suction Valves, Defeat of Auto Open Signal
EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET APPROVALS:
Signature / Title Date Signature / Title Date Signature / Title Date II Signature / Title Date APPROVED FOR USE:
Srgnature I Title Date 1I 1
EFFECTIVE DATE: I I NAME: Last First M I. ISSUE DATE:
SOC. SEC. NO. COMPLETION DATE:
COMMENTS:
Training Review for Completeness: I PlMS CODE: I Signature/Date I PlMS ENTRY:
2008 NRC JPM IP(k) (NEW) DWCW Low Level -AP Page 1 of 6
TEMPORARY CHANGE FORM LOG CODE NO.: PLOR-NEWPA REV. NO.:
TITLE: D w e l l Chilled Water Low Level (Alternate Path - Manual Makeup to D w e l l Chill&
Water System) 1.
TCF # TCF DATE I CHANGED SECTION # 7 2.
3.
4.
5.
6.
7.
8.
9.
IO.
11.
12.
13.
14.
15.
2008 NRC JPM IP(k) (NEW) DWCW Low Level -AP Page 2 of 6
EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2200020401 / PLOR-NEWPA K/A: 295028EA1.03 URO: 3.9 SRO: 3.9 TASK DESCRIPTION: Take Actions For Drvwell Chilled Water Low Level 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 std?ps(P) shall be simulated (S).
- b. When performing %-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 deterrnines 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 ncst to be given to the examinee.
2008 NRC JPM IP(k) (NEW) DWCW Low Level -AP Page 3 of 6
B. TOOLS AND EQUIPMENT
- 2. T-223 Drywell Cooler Fan Bypass D. TASK STANDARD
- 1. Satisfactory task completion is indicated when the drywell chilled water system has been restored to normal presuure.
- 2. Estimated time to complete: 15 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to restore the drywell chilled water system to normal pressure. I will describe initial plant conditions and provide you access to the materials required to complete this task.
F. TASK C0NDITIONS/PREREQUISITES
- 1. Unit 2 was manually scrammed due to rising drywell pressure.
- 2. Drywell pressure is 2.1 psig and rising slowly.
- 3. Drywell bulk average temperature is 146 degrees F and rising slowly.
- 4. T-223 Drywell Cooler Fan Bypass is in progress.
- 5. Annunciator 217 H-5 DRYWELL CHILLED WATER LO LEVEL has alarmed and Ihe condition needs to be cleared to support restoring drywell cooling.
G. INITIATING CUE The Control Room Supervisor directs you, the Equipment Operator, to perform Operator Action
- 3 of ARC 217 H-5 DRYWELL CHILLED WATER LO LEVEL the annunciator is reset.
2008 NRC JPM IP(k) (NEW) DWCW Low Level -AP Page 4 of 6
H. PERFORMANCE CHECKLIST STEP ACT STANDARD NO 1 Obtain a copy of ARC 217 H-5 P A copy of procedure ARC 217 H-5 is DRYWELL CHILLED WATER LO LEVEL. obtained.
(Cue: Hand the Examinee a copy of ARC 217 H-5 DRYWELL CHILLED WATER LO LEVEL) 2 Check drywell chilled water expansion P Locate Pl-20265 for Drywell Chilled tank pressure at Pl-20265 Chilled Water Water Expansion Tank 20T036 located Expansion Tank. on Turbine Building 165 elevation near the drywell chillers. Verify Pl-20265 is (Cue: Pl-20265 Chilled Water Expansion reading 22 psig.
Tank is indicating 20 psig and lowering slowIy)
- 3 Verify SV-20265 is OPEN. P Locate SV-20265 Solenoid Operated Makeup to Chilled Water System.
(Cue: SV-20265 is cold to the touch, Attempt to verify that SV-20265 is there is no humming noise, and there is energized by listening for humming noise, no flow noise. Pl-20265 Chilled Water feeling that the SV is warm to the touch, Expansion Tank is indicating 19 psig and and listening for system flow.
continues to lower.)
- NO E****
During the performance of the following steps, if the examinee performs a system kalk search, cue that no leaks were identified.
- 4 OPEN HV-2-44A-23539 Demineralized Obtain a locked valve key (every Water Makeup Bypass To Chilled Water Equipment Operator in a posted position System. has a locked valve key).
(Cue: The lock and chain have been Unlock the lock on the valve and remove removed. HV-2-44A-23539 has been the chain.
turned in the fully counter-clockwise direction and will no longer turn. System Turn HV-2-44A-23539 in the counter-flow noise is heard.) clockwise direction until the valve handle no longer turns.
- 5 Locate Pl-20265 for Drywell Chilled pressure is 28 to 40 psig. Water Expansion Tank 20T036 located on Turbine Building 165 elevation near (Cue: Pl-20265 is indicating 30 psig and the drywell chillers. Verify Pl-20265 is rising) reading 28 psig to 40 psig.
L 2008 NRC JPM IP(k) (NEW) DWCW Low Level -AP Page 5 of 6
CLOSE HV-2-44A-23539 Demineralized S Turn HV-2-44A-23539 in the clockkvise Water Makeup Bypass To Chilled Water direction until the valve handle no onger System. turns.
(Cue: HV-2-44A-23539 has been turned Verify system pressure on PI-20265 for in the fully clockwise direction and will no Drywell Chilled Water Expansion l a n k longer turn. System flow noise has 20T036 stopped. PI-20265 is indicating 35 psig and steady.)
7 LOCK HV-2-44A-23539 Demineralized S Reinstall the lock and chain on thevalve.
Water Makeup Bypass To Chilled Water System.
(Cue: The lock and chain have been reinstalled.)
8 Contact main control room and ask if S Request using hand held radio, plant annunciator 217 H-5 DRYWELL page system, or telephone.
CHILLED WATER LO LEVEL is reset.
(Cue: Annunciator 217 H-5 DRYWELL CHILLED WATER LO LEVEL is reset.)
9 Inform Control Room of task completion. S Task completion reported using hand held radio, plant page system, or (Cue: Control Room acknowledges telephone.
report.) ~ ~ _ _
10 As an evaluator ensure you have positive P Positive control established.
control of all exam material provided to the examinee (Task ConditionslPrerequisites) AND Drocedures Under ACT P - must perform S - must simulate I. TERMINATING CUE When HV-2-44A-23539 has been closed after restoring the Drywell Chilled Water System to normal pressure, and the Control Room reports that Annunciator 217 H-5 is reset, the evaluator will then terminate the exercise.
2008 NRC JPM IP(k) (NEW) DWCW Low Level -AP Page 6 of 6
TASK CONDlTlONSlPREREQUlSlTES
- 1. Unit 2 was manually scrammed due to rising drywell pressure.
- 2. Drywell pressure is 2.1 psig and rising slowly.
- 3. Drywell bulk average temperature is 146 degrees F and rising slowly.
- 4. T-223 Drywell Cooler Fan Bypass is in progress.
- 5. Annunciator 217 H-5 DRYWELL CHILLED WATER LO LEVEL has alarmed and the condition needs to be cleared to support restoring drywell cooling.
INITIATING CUE The Control Room Supervisor directs you, the Equipment Operator, to perform Operator Action #3 of ARC 217 H-5 DRYWELL CHILLED WATER LO LEVEL until the annunciator is reset.