ML022970200
| ML022970200 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 09/23/2002 |
| From: | Alfonso M Exelon Nuclear |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-277/02-302, 50-278/02-302 | |
| Download: ML022970200 (77) | |
Text
EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:
Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:
2150300101 / PILT-ADMIN 000 K/A:
215005A1.04 RO: 4.1 SRO: 4.1 TASK DESCRIPTION:
Perform APRM Scram Margin Check A.
NOTES TO EVALUATOR:
- 1.
An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.
- 2.
System cues included in the performance checklist are to be provided to the examinee when no system response is available.
- 3.
JPM Performance
- a.
This JPM requires performance using either the Simulator NUMAC drawers or the actual Control Room APRM NUMAC drawers. Due to the electronic displays, this JPM should not be "simulated". Normally, this "Control Room" JPM will be performed in the simulator however this JPM may be performed in the actual Control Room on a real APRM NUMAC drawer with no impact on plant operation under the supervision of the shift.
- b.
When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.
- 4.
Satisfactory performance of this JPM is accomplished if:
- a.
The task standard is met.
- b.
JPM completion time requirement is met.
- 1)
For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.
- 2)
For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.
"5.
The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.
Page 3 of 6 RO AJPM 1 - Scram Margin Check.doc
- 6.
This JPM should be performed in the Simulator but may be performed in the actual Control Room with no impact on plant operation. Obtain Control Room Supervisor and Unit RO permission prior to performing this JPM and prior to entering the controls area.
- 7.
The procedure normally requires the operator to perform the scram check on all operable APRMs. For this JPM, only APRM #4 is directed since this task is repetitive.
The evaluator may also select a different APRM if desired (e.g., if APRM #4 NUMAC drawer is out of service).
B.
TOOLS AND EQUIPMENT None C.
REFERENCES
- 1.
Procedure SO 60A.7.C-2 Rev. 11 "APRM Scram Margin Check" D.
TASK STANDARD
- 1.
Satisfactory task completion is indicated when the student determines the correct scram margin as recorded on SO 60A.7.C-2 Data Sheet 1
- 2.
Estimated time to complete: 10 minutes Non-Time Critical DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to perform an ARPM scram margin check for APRM #4 using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.
F.
TASK CONDITIONS/PREREQUISITES
- 1.
Unit 2 startup and power ascension is in progress at approximately 60% power.
- 2.
All APRM Channels are Operable and in service.
G.
INITIATING CUE The Control Room Supervisor directs you to determine the scram margin for APRM #4 in accordance with SO 60A.7.C-2 "APRM Scram Margin Check".
RO AJPM I - Scram Margin check.doc Page 4 of 6 Page 4 of 6 RO AJPM 1 - Scram Margin Check.doc
H.
PERFORMANCE CHECKLIST STEP ACT STANDARD 1
Obtain a copy of procedure P
A copy of procedure SO 60A.7.C-2 is SO 60A.7.C-2.
obtained.
- 2 Student determines that Step 4.1 is P
Student selects Step 4.1 to perform.
applicable for Mode 1 operation.
Step 4.1 directs the operator to determine Scram setpoints for all operable APRMs. For this JPM, APRM
- 4 is the selected. A different APRM may be selected by the evaluator if desired (e.g., APRM #4 NUMAC is out of service). If this JPM is being performed in the Control Room 4
At selected APRM NUMAC display P
At APRM #4 NUMAC display, depress (APRM #4), depress the "ETC" softkey the "ETC" softkey to obtain the "SHOW to obtain the "SHOW PARAMETERS" PARAMETERS" softkey.
softkey.
5 Depress "SHOW PARAMETERS" P
Depress "SHOW PARAMETERS" softkey.
softkey.
Under the "APRM RUN MODE SETPOINTS" section, record the value of "STP UPSCALE TRIP (FLOW BIASED)" on Data Sheet I under "APRM SCRAM SETPOINT".
P Record the value of "STP UPSCALE TRIP (FLOW BIASED)" on Data Sheet 1 under "APRM SCRAM SETPOINT".
7 Depress "EXIT" softkey.
P Depress "EXIT" softkey.
8 Record "STP (%)" value on Data Sheet P
Record "STP (%)" value on Data Sheet 1 under "APRM CURRENT".
1 under "APRM CURRENT".
Note: Step 4.2 is not applicable for the reactor mode condition.
"*10 Determine SCRAM margin by P
Correctly calculates APRM #4 Scram performing the following calculation Margin on Data Sheet 1:
AND recording the value on Data Sheet 1 under "SCRAM MARGIN":
SCRAM MARGIN = APRM SCRAM SCRAM MARGIN = APRM SCRAM SETPOINT - APRM CURRENT SETPOINT - APRM CURRENT =
=
SP-C SP-C RO AJPM I - Scram Margin Check.doc Page 5 of 5 I STEP NO
I
7 STEP NO 13 STEP ACT STANDARD T
I Inform Control Room Supervisor of task completion.
(Cue: Control Room Supervisor acknowledges report.)
P Task completion reported.
a ______________________________
+/- _____
a _______________________________
Under "ACT" P - must perform S - must simulate TERMINATING CUE When SBGT system is running to support HPCI operation, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.
RO AJPM I - Scram Margin Check.doc Page 6 of 6 RO AJPM 1 - Scram Margin Check.doc Page 6 of 6
TASK CON DITIONS/PREREQUISITES Unit 2 Startup and power ascension is in progress at approximately 60% power.
All APRM Channels are Operable and in service.
INITIATING CUE The Control Room Supervisor directs you determine the scram margin for APRM #4 in accordance with SO 60A.7.C-2 "APRM Scram Margin Check".
EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:
Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:
X K/A:
Generic 2.2.11 URO: 2.5 SRO: 3.4 TASK DESCRIPTION:
Knowledge of the process for controlling Temporary Changes A.
NOTES TO EVALUATOR:
- 1.
An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.
- 2.
System cues included in the performance checklist are to be provided to the examinee when no system response is available.
- 3.
JPM Performance
- a.
"Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).
- b.
When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.
- 4.
Satisfactory performance of this JPM is accomplished if:
- a.
The task standard is met.
- b.
JPM completion time requirement is met.
- 1)
For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.
- 2)
For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.
- 5.
The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.
L>4t.
RO ADMIN JPM 2 - Initiation of a Temp Change ryoui iti r'age 3o o10*
RO ADMIN JPM 2 - Initiation of a Temnp Change
B.
TOOLS AND EQUIPMENT
- 1.
None
'-t.
REFERENCES
- 1.
AD-PB-1 01-1003 Rev. 1, Temporary Changes to Procedures.
- 2.
SO 52A.I.B Rev. 24, Section 4.1, Diesel Generator Operations, Slow Start.
D.
TASK STANDARD
- 1.
Satisfactory task completion is indicated when Temporary Change has been submitted to the SRO with Attachment 3, Part "A" completed, in accordance with the approved procedure.
- 2.
Estimated time to complete: 20 minutes Non-Time Critical E.
DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to initiate a "single use" temporary change to SO 52A.1..B, "Diesel Generator Operations, Slow Start", step 4.1.1.4, using AD-PB 101-1003, "Temporary Changes to Procedures". I will describe initial plant conditions and provide you access to the materials required to complete this task.
F.
TASK CONDITIONS/PREREQUISITES
- 1.
The Plant is operating at full power.
- 2.
A "slow start" of the E-1 Diesel Generator, per ST-O-052-201-2 "El Diesel Generator Slow Start and Full Load Test" and SO 52A.1..B "Diesel Generator Operations, Slow Start", is required for operability requirements.
- 3.
The E-1 Diesel Generator Coolant Expansion Tank level indicating sightglass has a crack in it. The sightglass is isolated with an Equipment Status Tag (EST), but the tank is still available for use.
- 4.
Maintenance reports that the sightglass will be repaired prior to the next scheduled run of the E-1 Diesel Generator.
- 5.
The Control Room Supervisor has directed that the System Manager will determine and verify Coolant Expansion Tank level, then report it to the Control Room as part of the pre-start check of the E-1 Diesel Generator.
G.
INITIATING CUE The Control Room Supervisor directs you to initiate a "single use" temporary change to SO 52A. 1.B, "Diesel Generator Operations, Slow Start", step 4.1.1.4, using AD-PB-101-1003, "Temporary Changes to Procedures".
RO ADMIN JPMV 2 - Initiation of a Temp Change Page 4 of 10
H.
PERFORMANCE CHECKLIST STEP STEP ACT STANDARD NO 1
Obtain a copy of AD-PB-101-1003, P
A copy of AD-PB-101-1003, "Temporary "Temporary Changes to Changes to Procedures" is obtained.
Procedures" and review/utilize the correct section of the procedure.
Initiator responsibility is reviewed.
2 Determine if a Temporary Change P
Uses Attachment 1 of AD-PB-101-1003, is valid for the conditions.
"Temporary Changes to Procedures" to determine that temporary change criteria are met.
CUE: Once the Student has determined that the temporary change criteria are met, provide him/her of this JPM "SO 52A.1.B, "Diesel Generator Operations, Slow Start".
- Note***
he Student may not classify the temporary change because "single use" was given to him/her in the initiating cue.
3 Determine the temporary change P
Uses the information provided and determines classification, that this temporary change is a SINGLE USE change.
- 4 Complete the required mark-up of P
Completes the mark-up of SO 52A.1..B, "Diesel SO 52A.1..B, "Diesel Generator Generator Operations, Slow Start" by performing Operations, Slow Start".
the following with BLACK ink:
"* Draws a single line through each sentence of step 4.1.1.4 of SO 52A.1..B, "Diesel Generator Operations, Slow Start".
"* Inserts the following text as close to the affected step as possible; NOTE: The exact wording by the o "The System Manager will verify and Student may vary from report Coolant Expansion tank level to that of this JPM step. As the Control Room and will have long as the intent is clear coolant added as necessary."
the exact wording is not important.
Page 5 of 10 RO ADMIN JPMV 2 - Initiation of a Temp Change
STEP STEP ACT STANDARD NO Insert the following in the left margin of the NOTE: The Student may insert an affected step(s);
area for SQR/SRO review.
Normally this is performed 0 Initial/Date of SROA by the SQR/SRO.
o Initial/Date of SRO.
Complete Temporary Change Form, Attachment 3, Part A.
NOTE: This Diesel Generator procedure is common to both Units.
NOTE: This was determined in step #2 of this JPM from the given information.
CUE:
Inform Student that NO other Temporary Changes are in affect on this page of SO-54A.1.B.
NOTE: The exact wording by the Student may vary from that of this JPM step. As long as the intent is clear the exact wording is not important.
P
- 5 IL-J D.
Cz f in RO ADMIN JPM 2 - Initiation of a Temp Change Completes the Temporary Change Form,, Part A, as follows:
"* Places a check mark next to "Common" in step #1, "Unit Applicability".
"* Places a check mark next to "Single Use (S)" in step #2, "TC Classification".
"* Inserts SO-54A.1.B and current revision number in step #3, "Procedure Number".
"* Inserts Diesel Generator Operation in step
- 4, "Procedure Title".
"* Inserts 3 of 29 in step #5, "Pages Affected".
"* Place a check mark next to "NO" in step #6, "Does this TC supersede or replace existing TC's".
"* Inserts System Manager will verify and report Coolant Expansion tank level to the Control Room and will have coolant added as necessary in step #7, "TC Description".
"* Inserts Diesel Generator #1 Coolant Expansion tank level sightglass is broken, valved out and won't be fixed before the Diesel needs to be slow started in step #8, "Reason for TC".
I czaj W Ii
STEPI STEP ACTI STAN DARD NO 11 *6 Present the temporary change for review and approval.
CUE: Accept Attachment 3 and SO 52A.1.B, Diesel Generator Operations, Slow Start" from the Student as the SQR and SRO.
P Presents Attachment 3 of AD-PB-101-1003, "Temporary Changes to Procedures" and the entire Diesel Generator Operation procedure SO 52A.1.B, "Diesel Generator Operations, Slow Start" with the marked up step 4.1.1.4 to the SQR and SRO for review and approval.
As an evaluator ensure that you P
Positive control established.
have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites)
AND procedures.
Under "ACT" P - must perform S - must simulate TERMINATING CUE:
When Attachment 3 of AD-PB-101-1003, "Temporary Changes to Procedures" and the entire Diesel Generator Operation procedure SO 52A.1..B, "Diesel Generator Operations, Slow Start" with the marked up step 4.1.1.4 have been presented to the SQR and SRO for review and approval, the evaluator will terminate the exercise.
J.
SPECIAL INSTRUCTIONS:
None RO ADMIN JPM 2 - Initiation of a Temp Change rage (013/4)
RO ADMIN JPM 2 - Initiation of a Temnp Change Page 7 of -10
ATTACHMENT I
TASK CONDITIONSIPREREQUISITES
- 1.
The Plant is operating at full power.
- 2.
A "slow start" of the E-1 Diesel Generator, per ST-O-052-201-2 "El Diesel Generator Slow Start and Full Load Test" and SO 52A.1.B "Diesel Generator Operations, Slow Start", is required for operability requirements.
- 3.
The E-1 Diesel Generator Coolant Expansion Tank level indicating sightglass has a crack in it. The sightglass is isolated with an Equipment Status Tag (EST), but the tank is still available for use.
- 4.
Maintenance reports that the sightglass will be repaired prior to the next scheduled run of the E-1 Diesel Generator.
- 5.
The Control Room Supervisor has directed that the System Manager will determine and verify Coolant Expansion Tank level, then report it to the Control Room as part of the pre-start check of the E-1 Diesel Generator.
INITIATING CUE The Control Room Supervisor directs you to initiate a "single use" temporary change to SO 52A.1.B, "Diesel Generator Operations, Slow Start", step 4.1.1.4, using AD-PB-101-1003, "Temporary Changes to Procedures".
ATTACHMENT 2 SO 52A.1.B, DIESEL GENERATOR OPERATIONS
EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:
Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:
XI PLOR-172C K/A:
2.1.24 URO: 2.8 SRO: 3.1 TASK DESCRIPTION:
Familiarity and Use of P&IDs 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.
RO AJPM 3-PID USE.doc Page 3 of 7 RO AJPM 3 - PID USE.doc Page 3 of 7
B.
TOOLS AND EQUIPMENT
- 1.
M-315 Sheet 1, Rev. 64, "Emergency Service Water and High Pressure Service Water System" print
- 2.
M-315 Sheet 4, Rev. 50, "Emergency Service Water and High Pressure Service Water System" print
- 3.
M-330 Sheet 1, Rev. 33, "Emergency Cooling System" print C.
REFERENCES
- 1.
M-315 Sheet 1, Rev. 64, "Emergency Service Water and High Pressure Service Water System" print
- 2.
M-315 Sheet 4, Rev. 50, "Emergency Service Water and High Pressure Service Water System" print
- 3.
M-330 Sheet 1, Rev. 33, "Emergency Cooling System" print D.
TASK STANDARD
- 1.
Satisfactory task completion is indicated when it has been determined that following any start of the Diesel Generators the:
- a.
A and B ESW pump will automatically start and continue to run normally.
- b.
ECW pump will automatically start and shut down after 45 seconds.
- c.
ECW discharge valve (MO-0841) will remain closed.
- 2.
Estimated time to complete: 15 minutes Non-Time Critical E.
DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to determine the impact of a damaged instrument on cooling water operation using the appropriate P&IDs. I will describe initial plant conditions and provide you access to the materials required to complete this task.
F.
TASK CONDITIONS/PREREQUISITES An Equipment Operator reports to the control room that PS-0246B, mounted on the "B" Emergency Service Water Pump (OBP057) discharge pipe has been damaged by scaffolding such that it cannot sense high pressure.
RO AJPM 3-PID USE.doc Page 4 of 7 Page 4 of 7 RO AJPM 3 - PID USE.doc
G.
INITIATING CUE The Control Room Supervisor directs you to use P&IDs to determine the impact of the damaged PS-0246B on cooling water operation during a Diesel Generator start without additional operator actions.
RO AJPM 3-PlO USE.doc Page 5 of 7 Page 5 of 7 RO AJPM 3 - PID USE.doc
H.
PERFORMANCE CHECKLIST STEP STEP ACT STANDARD NO 1
Obtain M-315 Sh. 4, "P&I Diagram P
M-315 for ESW is located using the Emergency Service Water and High M-300 index. Sheet 4 is located as Pressure Service Water Sys's".
featuring the "B" ESW pump.
2 Locate the "B" ESW pump on M-315 Sh.
P "B" ESW is located at coordinates A-5 on
- 4.
M-315 Sh. 4.
- 3.
Locate PS-0246B on the discharge pipe P
PS-0246B is located at coordinates B-5 of the "B" ESW pump.
on M-315 Sh. 4.
- 4 Determine that the "B" ESW pump will P
Diesel Generator start is identified as a start on a Diesel Generator Start.
start signal from the logic illustrated on M-315 Sh. 4 coordinates B-5 OR from individuals knowledge base.
5 Determine that if a damaged PS-0246B is P
Logical outputs of "LOW" and "NOT unable to sense high pressure it will LOW" are located on M-315 Sh. 4 contribute a "LOW" to the logic, coordinates B-5. A logic output of "LOW" is determined.
6 Trace logic lines to M-315 Sh. 1 G-6.
Logic lines are traced to M-315 Sh.1 using continuation identifiers on M-315 Sh. 4 coordinates B-6.
7 Obtain M-315 Sh. 1, "P&I Diagram P
M-315 Sh. 1 is located using continuation Emergency Service Water and High identifiers on M-315 Sh. 4.
Pressure Service Water Sys's".
8 Determine that logic lines from M-315 Sh.
P Logic lines from M-315 Sh.4 are traced to 4 input to "AND" logic on M-315 Sh. 1 "AND" logic on M-315 Sh. 1 coordinates coordinates G-6.
G-6.
- 9 Determine that the "A" ESW pump will P
Diesel Generator start is identified as a start on a Diesel Generator start.
start signal from the logic illustrated on M-315 Sh. 1 coordinates G-5 OR from individuals knowledge base.
10 Determine that PS-0246A will contribute P
Logical outputs of "LOW" and "NOT a "NOT LOW" to the logic.
LOW" are located on M-315 Sh. 1 coordinates G-7. A logic output of "NOT LOW" is determined.
11 Determine that the "AND" logic will not be P
Logic lines from PS-0246A are traced to satisfied due to lack of "LOW" from "AND" logic on M-315 Sh. 1 coordinates PS-0246A and "LOW" from PS-0246B.
G-6. "AND" logic is not satisfied due to lack of "LOW" from PS-0246A.
12 Determine that the "OR" logic will be P
Logic lines from PS-0246A are traced to satisfied by PS-0246A "NOT LOW".
"OR" logic on M-315 Sh. 1 coordinates G-6. "OR" logic is satisfied by singular I input of "NOT LOW" from PS-0246A.
13 Trace logic lines to M-330 Sh. 1 P
Logic lines are traced to M-330 Sh. 1 coordinates G-3.
using continuation identifiers on M-315 Sh. 1 coordinates G-6.
14 Obtain M-330 Sh. 1 "P&I Diagram Emergency Cooling System".
P M-330 Sh. 1 is located using continuation identifier on M-315 Sh.1.
RO AJPM 3-PID USE.doc Page 6 of 7 I
RO AJPM 3 - PID USE.doc Page 6 of 7
STEP STEP ACT STANDARD NO 15 Determine that the "AND" logic for the P
Logic lines from M-315 Sh. 1 G-6 are ECW pump will be satisfied by either traced to "AND" logic on M-330 Sh. 1, ESW pump A or B discharge pressure coordinates G-3. "AND" logic is "NOT LOW" and ECW pump not started determined to be satisfied with inputs manually when an auto start has existed from either the A or B ESW pump for 45 seconds.
discharge pressure "NOT LOW" and ECW not started manually when auto has existed for 45 seconds.
"*16 Determine that the ECW pump will trip 45 P
Logic line from "AND" is traced to ECW seconds after an ECW auto start signal "TRIP" when auto start signal has existed on Diesel Generator start.
for 45 seconds.
"*17 Determine that the "AND" logic for the P
Logic lines are traced to "AND" logic on ECW discharge valve MO-0841 will NOT M-330 Sh. 1 coordinates H-3.
be satisfied since ESW A AND B discharge pressure is NOT low. The ECW discharge valve will remain closed I following an ECW auto start signal.
18 Control Room Supervisor informed of P
Inform the Control Room Supervisor that plant impact of damaged PS-0246B on on a Diesel Generator start, the:
cooling water should a Diesel Generator o A and B ESW pumps will automatically start occur.
start and continue to run normally.
- ECW pump will automatically start and shutdown after 45 sec.
- A r*
ECW discharge valve (MO-0841) will (Cue: Acknowledge report.)
remain closed.
Under "ACT" P - must perform S - must simulate
- 1.
TERMINATING CUE When the impact of the damaged PS-0246B on ESW and ECW operation following a Diesel Generator start has been determined, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.
RO AJPM 3-PID USE.doc Page 7 of 7 Page 7 of 7 RO AJPM 3 - PID USE.doc
TASK CONDITIONS/PREREQUISITES An Equipment Operator reports to the control room that PS-0246B, mounted on the "B" Emergency Service Water Pump (OBP057) discharge pipe has been damaged by scaffolding such that it cannot sense high pressure.
INITIATING CUE The Control Room Supervisor directs you to use P&IDs to determine the impact of the damaged PS-0246B on cooling water operation during a Diesel Generator start without additional operator actions.
EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:
Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:
2730130202 K/A:
2.3.11 URO: 2.7 SRO: 3.2 TASK DESCRIPTION:
Ability to control radiation releases.
A.
NOTES TO EVALUATOR:
- 1.
An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.
- 2.
System cues included in the performance checklist are to be provided to the examinee when no system response is available.
- 3.
JPM Performance
- a.
"Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).
- b.
When performing "In-Plant" 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.
RO AJPM 4-PRO RAD RELEASE.doc Page 3 of 5 RO AJPM 4 - PRO PAD RELEASE.doc Page 3 of 5
B.
TOOLS AND EQUIPMENT
- 1.
Copy of ST-C-095-805-2, Rev. 9, completed through step 6.12.8.
"*C.
REFERENCES
- 1.
ST-C-095-805-2, Rev. 9, "Liquid Radwaste Discharge".
D.
TASK STANDARD
- 1.
Satisfactory task completion is indicated when section 6.13 has been completed in its entirety.
- 2.
Estimated time to complete: 12 minutes Non-Time Critical E.
DIRECTIONS TO EXAMINEE When given the initiating cue, perform the necessary steps to set-up the plant in preparation for a Liquid Radwaste discharge. I will describe initial plant conditions and provide you access to the materials required to complete this task.
F.
TASK CONDITIONS/PREREQUISITES
- 1.
Both units are operating at 100% power.
- 2.
The Floor Drain Sample Tank (FDST) needs to be discharged.
- 3.
Chemistry and Shift Management have completed ST-C-095-805-2, "Liquid Radwaste Discharge" through step 6.12.8.
- 4.
Six Circulating Water Pumps are in operation.
- 5.
The discharge Canal-To-Intake Pond crosstie gate is closed.
- 6.
The PRO review and set-up has not been completed.
G.
INITIATING CUE You are the PRO. Complete section 6.13 of ST-C-095-805-2 "Liquid Radwaste Discharge".
RO AJPM 4-PRO RAD RELEASE.doc I-'age '4 or
Page 4 OT 0 RO AJPM 4 - PRO RAD RELEASE.doc
H.
PERFORMANCE CHECKLIST I;TEP STEP ACT STANDARD NO 1
Record actual number of operating P
Visually verify six Circulating Pumps are Circulating Pumps.
operating, record and initial step 6.13.1.
- 2 Set the HI Trip Setpoint.
P Manually adjust the HI Setpoint Pot setting for RIS-0-17-350 to < 4.43, and record and initial step 6.13.2.
- 3 Set the HI HI Trip Setpoint.
P Manually adjust the HI HI Setpoint Pot setting for RIS-0-17-350 to < 4.46, and record and initial step 6.13.3.
4 Review PRO steps.
P Visually verify all the PRO steps in section 6.13 are complete, and initial step 6.13.5 SAT.
5 Record your name and initials.
P Print your name and initials in Section 10.0.
6 Forward the test.
P Forward this test to the Radwaste Operator, and initial step 6.13.6 SAT.
(Cue: Radwaste Operator has received the test.)
- NOTE ***
Terminate the exercise when the activities listed above are performed.
Under "ACT" P - must perform S - must simulate TERMINATING CUE When Section 6.13 of ST-C-095-805-2 has been completed, terminate the exercise.
RO AJPM 4 - PRO RAD RELEASE.doc Page 5 of 5
TASK CONDITIONS/PREREQUISITES
- 1.
Both units are operating at 100% power.
- 2.
The Floor Drain Sample Tank (FDST) needs to be discharged.
- 3.
Chemistry and Shift Management have completed ST-C-095-805-2, "Liquid Radwaste Discharge" through step 6.12.8.
- 4.
Six Circulating Water Pumps are in operation.
- 5.
The discharge Canal-To-Intake Pond crosstie gate is closed.
- 6.
The PRO review and set-up has not been completed.
INITIATING CUE You are the PRO. Complete section 6.13 of ST-C-095-805-2 "Liquid Radwaste Discharge".
EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:
Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:
3440230503 / PLOR-094C K/A:
2.4.43 URO: 2.8 SRO: 3.5 TASK DESCRIPTION:
Direct a Site Evacuation 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.
RO AJPM 5 - Site Evacuation.doc Page 3 of 9
B.
TOOLS AND EQUIPMENT None C.
REFERENCES ERP-130, Rev. 20, "Site Evacuation" D.
TASK STANDARD
- 1.
Satisfactory task completion is indicated when a site evacuation has been directed.
- 2.
Estimated time to complete: 18 minutes Non-Time Critical E.
DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to direct a site evacuation using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.
F.
TASK CONDITIONS/PREREQUISITES A Site Area Emergency has just been declared by the Emergency Director.
-G.
INITIATING CUE "The Emergency Director has directed you to implement ERP-130, "Site Evacuation" Step 2.2 in order to evacuate the site of non-essential personnel and have them report to the North Substation.
RO AJPM 5-Site Evacuation.doc Page 4 ot Y Page 4 of 9 RO AJPM 5 - Site Evacuation.doc
H.
PERFORMANCE CHECKLIST 3TEP STEP ACT STANDARD NO 1
Obtain a copy of procedure ERP-130.
P A copy of procedure ERP-130 is obtained.
- 2 Activate the Page Alert Tone system.
P Station Alert Tone system pushbutton is momentarily depressed at the Plant (Cue: Siren noise audible on Reactor Operators desk.
loudspeaker.)
- 3 Make evacuation announcement twice P
Depress and hold pushbutton on GAI over the Plant Public Address system.
Tronics handset while making evacuation announcement twice over the Plant Public "This is NOT a drill. This is NOT a drill.
Address System.
Attention all Personnel. This is a site evacuation notification. All non-essential personnel evacuate to the North Substation. All members of the Emergency Response organization report to your emergency response facility. This is NOT a drill. This is NOT a drill".
(Cue: Acknowledge announcement.)
- 4 Rotate "Evacuation Alarm/Mic selector" P
Mic/Siren Selector, switch 43 is placed in switch to position 6 (plant).
"POSITION 6" at panel 00C026B.
(Cue: Acknowledge control switch operation.)
- 5 Sound evacuation siren for approximately P
Mic/Siren Selector, switch 43 is PULLED 1 minute by pulling handle out.
OUT for approximately 1 minute at panel 00C026B.
(Cue: Acknowledge control switch operation.)
6 Push switch #43 on Diesel Panel IN.
P Mic/Siren Selector, switch 43 is PUSHED IN at panel 00C026B.
(Cue: Acknowledge control switch operation.)
RO AJPM 5 - Site Evacuation.doc Page 5 of 9 RO AJPM 5 - Site Evacuation.doc Page 5 of 9
STEP NO
- 7 STEP T
1*
Make evacuation announcement twice over the PLANT RADIO SYSTEM.
"This is NOT a drill. This is NOT a drill.
Attention all Personnel. This is a site evacuation notification. All non-essential personnel evacuate to the North Substation. All members of the Emergency Response organization report to your emergency response facility. This is NOT a drill. This is NOT a drill".
(Cue: Acknowledge announcement)
ACT P
STANDARD Depress the pushbutton on the radio system microphone while making evacuation announcement twice over the PLANT RADIO SYSTEM.
- 8 Rotate the "Evacuation Alarm/Mic P
Mic/Siren Selector, Switch 43, is placed in selector" switch, (while in the IN mode) to "POSITION 2", THEN handle is PULLED position 2, (microphone river speakers).
OUT at panel 00C026B.
Activate microphone by pulling handle OUT.
(Cue: Acknowledge control switch operation.)
- 9 Make evacuation announcement twice P
Key microphone at panel 00C026B while over the Pond Paging system.
making evacuation announcement twice over Pond Paging System.
"This is NOT a drill. This is NOT a drill.
Attention all Personnel. This is a site evacuation notification. All non-essential personnel evacuate to the North Substation. All members of the Emergency Response organization report to your emergency response facility. This is NOT a drill. This is NOT a drill".
(Cue: Acknowledge announcement.)
10 Push switch #43 selector switch on Diesel P
Mic/Siren Selector, Switch 43 is PUSHED Generator Panel IN.
IN at panel 00C026B.
(Cue: Acknowledge control switch operation.)
RO AJPM 5 - Site Evacuation.doc Page 6 of9 I
RO AJPM 5 - Site Evacuation.doc Page 6 of 9
STEP STEP ACT STANDARD NO
- 11 Activate the Page Alert Tone system.
P Station Alert Tone system pushbutton is momentarily depressed at the Plant (Cue: Siren noise audible on Reactor Operator's desk.
loudspeaker.)
"*12 Make evacuation announcement twice P
Depress and hold pushbutton on GAI over the Plant Public Address system.
Tronics handset while making evacuation announcement twice over the Plant Public "This is NOT a drill. This is NOT a drill.
Address System.
Attention all Personnel. This is a site evacuation notification. All non-essential personnel evacuate to the North Substation. All members of the Emergency Response organization report to your emergency response facility. This is NOT a drill. This is NOT a drill".
(Cue: Acknowledge announcement.)
"*13 Rotate "Evacuation Alarm/Mic selector" P
Mic/Siren Selector, switch 43 is placed in switch to position 6 (plant).
"POSITION 6" at panel 00C026B.
(Cue: Acknowledge control switch operation.)
"*14 Sound evacuation siren for approximately P
Mic/Siren Selector, switch 43 is PULLED 1 minute by pulling handle out.
OUT for approximately 1 minute at panel 00C026B.
(Cue: Acknowledge control switch operation.)
15 Push switch #43 on Diesel Panel IN.
P Mic/Siren Selector, switch 43 is PUSHED IN at panel 00C026B.
(Cue: Acknowledge control switch operation.)
RO AJPM 5 - Site Evacuation.doc Page 7 of 9 RO AJPM 5 - Site Evacuation.doc Page 7 of 9
STEP Make evacuation announcement twice over the PLANT RADIO SYSTEM.
"This is NOT a drill. This is NOT a drill.
Attention all Personnel. This is a site evacuation notification. All non-essential personnel evacuate to the North Substation. All members of the Emergency Response organization report to your emergency response facility. This is NOT a drill. This is NOT a drill".
(Cue: Acknowledge announcement)
ACT
- 1-4 P
STANDARD Depress the pushbutton on the radio system microphone while making evacuation announcement twice over the PLANT RADIO SYSTEM.
"*17 Rotate the "Evacuation Alarm/Mic P
Mic/Siren Selector, Switch 43, is placed in selector" switch, (while in the IN mode) to "POSITION 2", THEN handle is PULLED position 2, (microphone river speakers).
OUT at panel 00C026B.
Activate microphone by pulling handle OUT.
(Cue: Acknowledge control switch operation.)
"*18 Make evacuation announcement twice P
Key microphone at panel 00C026B while over the Pond Paging system.
making evacuation announcement twice over Pond Paging System.
"This is NOT a drill. This is NOT a drill.
Attention all Personnel. This is a site evacuation notification. All non-essential personnel evacuate to the North Substation. All members of the Emergency Response organization report to your emergency response facility. This is NOT a drill. This is NOT a drill".
(Cue: Acknowledge announcement.)
19 Push switch #43 selector switch on Diesel P
Mic/Siren Selector, Switch 43 is PUSHED Generator Panel IN.
IN at panel 00C026B.
(Cue: Acknowledge control switch operation.)
I STEP NO
"*16 RO AJPM 5 - Site Evacuation.doc Page 8 of 9
STEP STEP ACT STANDARD NO 20 Inform Emergency Director of task P
Task completion reported.
completion.
(Cue: Emergency Director acknowledges report.)
Under "ACT" P - must perform S - must simulate TERMINATING CUE When a site evacuation has been performed per ERP-1 30 the Emergency Director should be informed. The evaluator will then terminate the exercise.
RO AJPM 5 - Site Evacuation.doc h'age or u Page 9 or RO AJPM 5 - Site Evacuation.doc
TASK CONDITIONS/PREREQUISITES A Site Area Emergency has just been declared by the Emergency Director.
INITIATING CUE The Emergency Director has directed you to implement ERP-130, "Site Evacuation" Step 2.2 in order to evacuate the site of non-essential personnel and have them report to the North Substation.
EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:
Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:
X K/A:
Generic 2.1.4 URO: 2.3 SRO: 3.4 TASK DESCRIPTION:
Knowledge of shift staffing requirements.
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.
SRO ADMIN JPM I - Evaluate Shift Staffing Page 3 of 11 Page 3 of 11 SRO ADMIN JPM 1 - Evaluate Shift Staffing
B.
TOOLS AND EQUIPMENT
- 1.
None
"-C.
REFERENCES
- 1.
OP-PB-101-111 Rev. 2, Peach Bottom Operations Department
- 2.
OP-AA-105-101 Rev. 1, Administrative Process for NRC License and Medical Requirements
- 3.
A-C-40 Rev. 1, Working Hour Limitations
- 4.
A-C-40-1 Rev. 2, Working Hours Limitation Deviation Form
- 5.
OPM-P-40 Rev. 0, Peach Bottom Operations Overtime Policy
- 6.
OPM-P-30 Rev. 0, Operations Policy Manual Reactor Operator Staffing Policy D.
TASK STANDARD
- 1.
Satisfactory task completion is indicated when the Shift Manager has chosen an appropriately qualified individual that will not exceed overtime requirements to replace the disqualified operator, in accordance with approved procedures.
- 2.
Estimated time to complete: 15 minutes Non-Time Critical E.
DIRECTIONS TO EXAMINEE When given the initiating cue, perform the steps necessary to ensure that your shift is appropriately staffed. I will describe initial plant conditions and provide you access to the materials required to complete this task.
F.
TASK CON DITIONS/PREREQUISITES
- 1.
The Plants are operating at full power conditions.
- 2.
Unit #2 is expected to do a "load drop" later this morning to facilitate investigation of air inleakage on the Main Condenser.
- 3.
PS06 has just assumed the watch and you, as the Shift Manager, are reviewing the daily line-up Sheet.
- 4.
The Shift is staffed as indicated on the "Shift Lineup Sheet" and the "Shift Attendance Briefing Sheet".
G.
INITIATING CUE As the PS06 Shift Manager (SM), using appropriate procedures and Shift Line-up Sheets, determine if Shift manning requirements are being met.
SRO ADMIN JPM 1 - Evaluate Shift Staffing Page 4 of 11 SRO ADMIN JPM 1 - Evaluate Shift Staffing Page 4 of 11
H.
PERFORMANCE CHECKLIST I'STEP STEP ACT STANDARD NO CUE: Provide the Student with the Attachment #2 to this JPM.
CUE: When the Student has had time to review Attachment
- 2 of this JPM, tell him that you are with Regulatory Services and that you have just been informed that D.
Paul's NRC Medical examination expired yesterday.
Obtain a copy of the procedure and P
Obtains a copy of OP-AA-1 05-101, review/utilize the correct section of "Administrative Process for NRC License and the procedure.
Medical Requirements".
- 2 Evaluate the impact of D. Paul's P
Using OP-AA-105-101, "Administrative Process medical qualification expiring, for NRC License and Medical Requirements",
step 4.5 determines:
"* D. Paul has to be removed from licensed duties, and
"* Remain that way until such time as the medical exam is completed.
- 3 Determine if Shift Staffing P
May refer to OPM-P-30, "Reactor Operator Requirements are met.
Staffing Policy" and/or a copy of Technical Specification 5.2.
Directs the fourth RO to relieve D. Paul as the PRO.
Determines the minimum staffing requirements are now met with three (3) Reactor Operators.
Page 5 of 5 SRO AJPM 1 - Evaluate Shift Staffing.doc
STEP STEP ACT STANDARD NO CUE: As the Unit #2 CRS state that for the impending load drop, four (4) Reactor Operators are needed in the Control Room and no more are available on shift.
3 Call-out of a qualified Reactor P
May refer to the following procedures:
Operator.
OPM-P-40, Peach Bottom Operations Overtime Policy.
"* A-C-40, Working Hour Limitations.
"* A-C-40-1, Working Hour Limitation Deviation Form.
Requests from the SOAISSV a copy of the RO off-shift callout list.
CUE: As the SOA/SSV hand the Student Attachment 3 of this JPM, the Off-Shift RO call-out list.
- 4 Determine which of the qualified P
May refer to Technical Specification 5.2, A-C-40, Reactor Operators on the list is and A-C-40-1:
available without exceeding A-C-40 limitations.
Determines that Booker, T is the only Reactor Operator on the supplied list that can be called out for the full twelve (12) hours without exceeding procedural and Technical Specification limitations.
May also determine that Garlic, T and Hook, U could be called out for up to eight (8) hours each but would have to use them in combination with each other to cover the entire shift.
5 As an evaluator ensure that you P
Positive control established.
have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites)
AND procedures.
lSRO ADINP I
I vlaeSitSafigPg f1 SRO ADMIN JPM 1 - Evaluate Shift Staffing Page 6 of 11
Under "ACT" P - must perform S - must simulate TERMINATING CUE:
When the Shift Manager determines the status of the individuals on the Call-Out List in respect to the A-C-40 requirements, the evaluator will terminate the exercise.
J.
SPECIAL INSTRUCTIONS:
None SRO ADMIN JPM I - Evaluate Shift Staffing rage I UT I I rage i of *II SRO ADMIN JPM 1 - Evaluate Shift Staffing
ATTACHMENT 1
TASK CONDITIONS/PREREQUISITES
- 1.
The Plants are operating at full power conditions.
- 2.
Unit #2 is expected to do a "load drop" later this morning to facilitate investigation of air inleakage on the Main Condenser.
- 3.
PS06 has just assumed the watch and you, as the Shift Manager, are reviewing the daily line-up Sheet.
- 4.
The Shift is staffed as indicated on the "Shift Lineup Sheet" and the "Shift Attendance Briefing Sheet".
INITIATING CUE As the PS06 Shift Manager (SM), using appropriate procedures and Shift Line-up Sheets, determine if Shift manning requirements are being met.
ATTACHMENT 2 Shift Lineup Sheet and Shift Attendance Briefing Sheet
Shift Attendance Briefing Sheet Monday-July 29,2002 D
Report Date 11Ime: 81110214:24 Shift managers SM Shift Supervisors 92 CBS 113 CRS STA WCS FS IA Reactor Operators Pro U2 U3 4th Staff Scheduler Equipment Operators R2 T2 R3 T3 RW WI Sub Station OIS Extra #8 Safe S/0 Extra #9 Shift Chemist BOP Chemist Shift Tech 2 Shift Tech 1 HPSuperviser SHIFT P. Jones B. Smith J. Johnson T. Olsen T. Olsen W. Thompson D. Paul B. Johns M. Life M. Marks H. Hooper A. Dees B. King D. Duck S. Clause J. Cats J. Stone K. Mart T. Bones M. Enam 630a-230p 230p-630p lox Adams Jefferson Sate Shutdown ED's 1 B. King R2 2 S. Clause R3 3 M. Marks 4thROI8x H. Hooper 4th Re14x FIRE BRIGADE IC D. Duck T2 I K. Mart WT 2 j. Cats T3 3 J. Stone 1W 4 M. Enam xLra#8 OTHER S. Hills rPS Spt ILT / EOT P. Pans 3p-11n D. Towers30-11p R. Rogers 3p-l1p T. Sawyer 3p-11p V. Shell EO OJT/8x R. Paper Eto OJT/x P. Show to OlT/12x UTILITY C. Bore 2R14 PreP R. Clocks SelfAsmt D. Soul SelfAsmt H. Hooper SelfAsmti/D4 J. Wayne A. Aunts SelfAsmi D. Admiral Project D. Harris Substation D. Hughes Substation B. Which LabelingllOx M. Dew 2R14Prep G. Glass SelfAsmt M. Ball SelfAsmt
COM SdO NI-A INW/I=IIHS JAO (ZOM) lUOddns SdO ONNI 03 E)NUI ON EM11 OUS
- 060 74 'WEU3 i squoe
,A,:Pevq 9uojS
++,r sleo
- S 'esnelo poUllent) dH++
- 0 'ýona
'Ei 'BuIN SHOlVd3dO
,-H 'jadOOH 474 S)PEN
.*N 'Gin pe4!lenC) OM,,
Suqor
'InEd 011/03
'ueslo pailileno ViS*,L
-PPRU 4 ASS squor U3E)VNVW IAIHS BUJI IJIHS =1=10 (9060) S33IMBS
ýZM lZ6C6 133HS dn3NI-I I:JIHS
ATTACHMENT 3 RO Off-Shift Call-Out List
RO Off-Shift Call-out List Work Date:
Work Shift:
Task:
Name Phone Authorized By:
Date:
Reason:
Attempt Made Resu~lt Result Il Pay Schedules List Reset 1
Garlic, T (717) 555-1212 2
Booker, T (717) 549-6969 3
Hook, U (410)111-2222 F--q
~E I
r-LI-I LI-I L] [Iq
~IZ Work Hours for the Last Seven (7) Days:
LEGEND:
N D
18:30- 06:30 06:30- 18:30 2
Unit #2 URO 3
Unit #3 URO 4
Fourth RO C
PRO (Chief)
Call-out Order Call-out Order Monday Tuesday Wednesday Thursday Friday Saturday Sunday 1
OFF D 2 D 2 OFF OFF D 4 8x D 4 12x 4x 2D 3
D 3
D 3 OFF OFF D C D C 3
OFF N C N
C N C N C 4x OFF D2 Phone Result /
Result 9 Pa Schedules List Reset (M
EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:
Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:
2830150401 K/A:
Generic 2.1.7 URO: 3.7 SRO: 4.4 TASK DESCRIPTION:
Perform GP-13, "Resolution of Thermal Limit Violations."
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.
Page 3 of 12 SRO ADMIN JPM 2 - Resolution of Thermal Limit Violation Administrative actions on a Thermal Limit Violation.
B.
TOOLS AND EQUIPMENT
- 1.
None
"-C.
REFERENCES
- 1.
GP-13 Rev. 17, Resolution of Thermal Limit Violations
- 2.
RE-C-01 Rev. 4, Appendix 7, Control Rod Movement and Core Flow Change Guidelines D.
TASK STANDARD
- 1.
Satisfactory task completion is indicated when the SRO has authorized a power reduction using control rods only, in accordance with the approved procedure.
- 2.
Estimated time to complete: 15 minutes Non-Time Critical E.
DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to review the initial 3D P1 edit following the previous shift's power ascension. I will describe initial plant conditions and provide you access to the materials required to complete this task.
F.
TASK CONDITIONS/PREREQUISITES
- 1.
Reactor Power is currently stable at 100%.
- 2.
During the previous shift, Reactor Engineering had requested and received a Reactor Power ascension using Control Rods.
- 3.
Reactor Power was raised from 90% to 100% during this evolution.
- 4.
Shift turnover has been completed, all required log entries have been completed and you have assumed the duties to the Control Room Supervisor.
- 5.
The official 3D P1 edit is being run at this time to assess the recently completed Reactor Power ascension.
G.
INITIATING CUE As the Control Room Supervisor, review the official 3D P1 edit to ensure Reactor Core limits have been controlled during the recent power ascension.
SRO ADMIN JPM 2 - Resolution of Thermal Limit Violation Administrative actions on a Thermal Limit Violation.
Page 4 of 12
H.
PERFORMANCE CHECKLIST STEP STEP ACT STANDARD NO CUE: Provide the Student with the official 3D P1 edit, which is Attachment 2 of this JPM.
- Note***
The out of limit parameter for this JPM is the Fraction of Limiting Load Line Power (FLLLP). Please note that this is NOT a thermal limit as specified in Technical Specification, however, per GP-1 3 "Resolution of Thermal Limit Violations", it is to be treated as though it is one.
Review the Official 3D P1 Edit to P
Reviews the Official 3D P1 Edit.
ensure Core Thermal Limits.
- 2 Recognize the condition of the Core P
Recognizes the following concerning the as indicated on the official 3D P1 condition of the Core:
edit.
e The Core FLLLP has exceeded the specified limit.
CUE: Role Play as necessary.
(All other Core parameters are within their specified limits.)
- GP-13 is required to be entered to address the thermal limit violation.
3 Obtain a copy and enter GP-13 P
Reviews GP-13 prerequisites.
"Resolution of Thermal Limit Violations".
Reviews procedure "NOTE" prior to step 3.1 of GP-1 3.
- 4 Make immediate notification of Core P
Immediately informs the following:
conditions.
Shift Management Reactor Engineers Reports that FLLLP limit has been exceeded CUE: Role Play as necessary.
and that if it cannot be restored within two (2) hours that Reactor Power will have to be reduced to less than 25 % within the next four (4) hours.
SRO ADMIN JPM 2 - Resolution of Thermal Limit Violation Administrative actions on a Thermal Limit Violation.
Page 5 of 12
STEP ACT STANDARD Also reports to Reactor Engineering the intent to reduce power using Control Rods ONLY.
Requests Reactor Engineering assistance with returning FLLLP to below its limit.
CUE: Role Play as the Reactor Engineer, provide the Student with RE-C-01, Appendix 7, Attachment 1.
CUE: As the Reactor Engineer state that:
"RE-C-01, Appendix 7 has been completed through step 6.1.4. Your review and approval is required on. We recommend reversing the rod sequence and inserting Group 17."
Review and approve Attachment 1 P
Performs the following:
of RE-C-01, Appendix 7.
9 Reviews the Control Rod movement recommendation, AND e Approves by initialing the appropriate block of Attachment 1.
Inform evaluator of Task completion.
NOTE: When the Student has approves RE-C-01, the JPM is terminated.
P Informs the evaluator that the Task has been completed.
7 As an evaluator ensure that you P
Positive control established.
have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites)
AND procedures.
SRO ADMIN JPM 2 - Resolution of Thermal Limit Violation Administrative actions on a Thermal Limit Violation.
Page 6 of 12 STEP NO 6
Under "ACT" P - must perform S - must simulate TERMINATING CUE:
When the CRS has authorized a reduction in Reactor power by Control Rods ONLY in accordance with GP-5 AND RE-C-01, the evaluator will terminate the exercise.
J.
SPECIAL INSTRUCTIONS:
Page 7 of 12 SRO ADMIN JPM 2 - Resolution of Thermal Limit Violation Administrative actions on a Thermal Limit Violation.
ATTACHMENT 1
TASK CONDITIONS/PREREQUISITES
- 1.
Reactor Power is currently stable at 100%.
- 2.
During the previous shift, Reactor Engineering had requested and received a Reactor Power ascension using Control Rods.
- 3.
Reactor Power was raised from 90% to 100% during this evolution.
- 4.
Shift turnover has been completed, all required log entries have been completed and you have assumed the duties to the Control Room Supervisor.
- 5.
The official 3D P1 edit is being run at this time to assess the recently completed Reactor Power ascension.
INITIATING CUE As the Control Room Supervisor, review the official 3D P1 edit to ensure Reactor Core limits have been controlled during the recent power ascension.
ATTACHMENT 2 Official 3D P1 Edit
PEACH BOTTOM-2 CY-14SEQUENCE NO 8 CORE PARAMETERS POWER MWT POWER MWE FLOW MLB/HR FPAPDR SUBC BTU/LB PR PSIA CORE MWD/ST CYCLE MWD/ST MCPR 3463.
3D MONICORE PERIODIC LOG 11399.
91.380 CALC RESULTS 0.775 29.02 KEFF 1033.8 XE WORTH %
27938.9 XE/RATED 12409.2 FLLLP 1.598 1.0000
-2.47 1.12 (Current time/date minus 10 minutes) CALCULATED (Current lime/date) PRINTED CASE ID FMLS1020404155957 RESTART FMLS1020404135957 LPRM ABSOLUTE - FULL CORE LOAD LINE
SUMMARY
CORE POWER 1.002 CORE FLOW LOAD LINE 100.0%
100.5%
115.23%
CORRECTION FACTOR:
OPTION:
ARTS MFLCPR 0.891 0.889 0.888 0.881 0.881 0.879 0.879 0.877 0.875 0.874 LOC 19-20 29-52 25-52 27-50 35-26 2544 49-28 43-30 51-32 43-26 MFLCPR=1.000 MFLPD=1.000 MAPRAT=1.000 DUAL LOOP MANUAL FLOW MCPRLIM = 1.350 MOST LIMITING LOCATIONS (NON-SYMMETRIC)
MFLPD 0.729 0.724 0.720 0.711 0.711 0.707 0.694 0.694 0.694 0.692 LOC 25-54-5 53-26-5 25-52-5 51-26-6 19-50-5 49-20-5 49-28-5 35-26-5 17-52-5 41-20-6 MAPRAT 0.832 0.831 0.825 0.824 0.822 0.820 0.804 0.803 0.794 0.788 C=MFLCPR D=MFLPD M=MAPRAT P-PCRAT
- =MULTIPLE D
14 14 36 00 36 00 14 14 00 00 C
14 14 36 14 CORE AVE AXIAL NOTCH R
00 02 04 06 08 10 12
,EL PW LOC 0.147 25 0.350 24 0.679 23 0.852 22 0.963 21 1.067 20 1,129 19 1.134 18 14 1.093 16 1.120 18 1.114 20 1.097 22 1.130 24 1.151 26 1.156 28 1.184 30 1.225 32 1.243 34 1.235 36 1.256 38 1.250 40 1.188 42 1.086 44 0.811 46 0.340 36 14 L
L L
L L
L L
02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 17 16 15 14 13 12 11 10 09 08 07 06 05 04 03 02 01 CORE AVERAGE RADIAL POWER DISTRIBUTION RING #
1 2
3 4
5 6
7 8
1.020 1.229 1.092 1.261 1.097 1.257 1.070 0.523 ZBB = 2.96 t FCBB = N/A SEQ. A-2 LOC 27-52-5 51-28-5 17-50-5 19-52-5 51-20-5 49-18-5 43-28-5 41 5 49-26-5 23-52-5 PCRAT 0.695 0.695 0.691 0.689 0.683 0.683 0.679 0.678 0.678 0.677 LOC 25-52-5 51-26-6 19-50-5 49-20-5 25-54-5 17-52-5 35-26-5 51-18-5 41 6 53 5 L
L 51 47 43 39 35 31 27 23 19 15 11 07 03 L
L L
L L
REL PW
ATTACHMENT 3 RE-C-01, Appendix 7, Control Rod Movement and Core Flow Change Guidelines
PECO NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:
Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:
K/A:
294001G213 URO: 3.6 SRO: 3.8 TASK DESCRIPTION:
REVIEW AND APPROVE A CLEARANCE A.
NOTES TO EVALUATOR:
- 1.
An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.
- 2.
System cues included in the performance checklist are to be provided to the examinee when no system response is available.
- 3.
JPM Performance
- a.
"Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).
- b.
When performing "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.
SRO Admin 3 - Review and Approve a Clearance Page 3 of 3 Page 3 of 3 SRO Admin 3 - Review and Approve a Clearance
B.
TOOLS AND EQUIPMENT
- 1.
Prepare a Clearance Request that is complete but is lacking SRO approval. Include errors associated with the blocking points.
- 2.
Copy of M-314, Sheet 3, Rev. 64, Service Water System, with Clearance Points highlighted.
- 3.
Copy of E-178, Rev. 10, Fuel Pool Booster Pump 480 VAC Starter, with Clearance Points highlighted.
- 4.
Copy of E-1606, Rev 45 Single Line Meter and Relay Diagram with Clearance Points highlighted.
C.
REFERENCES
- 1.
Clearance and Tagging Manual, Rev. 6.
- 2.
M-314, Sheet 3, Rev. 64, Service Water System.
- 3.
E-1 78, Rev. 10, Fuel Pool Booster Pump 480 VAC Starter.
- 4.
E-1 606, Rev 45, Single Line Meter and Relay Diagram.
D.
TASK STANDARD
- 1.
Satisfactory completion of this task is indicated when errors in the Clearance Request have been identified and the request disapproved.
- 2.
Estimated time to complete: 20 minutes.
(Not time-critical)
E.
DIRECTIONS TO EXAMINEE When given the initiating cue, review the Clearance Request for approval. I will describe the initial conditions and provide you access to the materials required to complete this task.
F.
TASK CONDITIONS/PREREQUISITES
- 1. The "A" Service Water Booster Pump is shutdown and requires a Clearance to permit inspection of the pump internals.
- 2. The "B" Service Water Booster Pump is in service.
- 3. The "C" Service Water Booster Pump is available.
- 4. The Work Order, Clearance and Prints will be submitted to you for review.
G.
INITIATING CUE The Clearance request for the "A" Service Water Booster Pump has just been prepared and requires approval for immediate application. The Shift Manager directs you to review and approve the request, and inform the Control Room Supervisor when complete.
Page 4 of 4 SRO Admin 3 - Review and Approve a Clearance
H.
PERFORMANCE CHECKLIST
-STEP STEP ACT STANDARD
'NO NOTE:
The following steps may be done in a different order as long as all steps are completed prior to placing the APPROVED BY signature on the Clearance. This Clearance should be REJECTED by the candidate.
Verify the Component ID, Component P
The operator verifies the Component ID, Description and Clearance Description Component Description and the are correct.
Clearance Description are correct.
(Cue: Acknowledge verification of the Data.)
2 Check Comment Section to verify impact P
The operator checks the Comments of Clearance is accurate and complete.
Section and verifies the impact of the Clearance to be the 2A FP Service Water (Cue: Acknowledge Clearance impact.)
Booster Pump will be OOS.
3 Verify Instructions are adequate for the P
The operator verifies the Instructions to Clearance.
ensure 2BP145 and/or 2CP1 45 in service are adequate for the Clearance.
(Cue: Acknowledge the verification of instructions.)
- 4 Verify clearance Points to determine if P
The operator reviews the adequacy and they are correct and adequate for the accuracy of the Clearance Points and work to be performed under this identifies the valves identified for the 'B' Clearance.
pump:
0 HV-2-30-21818B Discharge Valve (Cue: Acknowledge the verification of HV-2-30-21816B Suction Valve Clearance Points and the identification of HV-2-30-21819B Drain Valve HV-2-30-21818B and HV-2-30-21816B HV-2-30-21817B Vent Valve as incorrect points.)
are INCORRECT Clearance Points for the 'A' Pump.
5 Notify the Control Room Supervisor of the P
The operator notifies the Control Room incorrect Clearance Points and the return Supervisor of the incorrect Clearance of the Clearance without Approval.
Points and of the return of the Clearance without Approval.
(Cue: The Control Room Supervisor 1 acknowledges the report.)
I 1__1 Under "ACT" P - must perform S - must simulate SRO Admin 3-Review and Approve a clearance Page 5 of 5 SRO Admin 3 - Review and Approve a Clearance Page 5 of 5
TERMINATING CUE:
When the tagging request review is complete, inform the Control Room Supervisor. The evaluator will then terminate the exercise SRO Admin 3-Review and Approve a Clearance Page 6 of 6 SRO Admin 3 - Review and Approve a Clearance Page 6 of 6
TASK CONDITIONS/PREREQUISITES
- 1. The "A" Service Water Booster Pump is shutdown and requires a Clearance to permit inspection of the pump internals.
- 2. The "B" Service Water Booster Pump is in service.
- 3. The "C" Service Water Booster Pump is available.
- 4. The Work Order, Clearance and Prints will be submitted to you for review.
INITIATING CUE The Clearance request for the "A" Service Water Booster Pump has just been prepared and requires approval for immediate application. The Shift Manager directs you to Review and Approve the request, and inform the Control Room Supervisor when complete.
WORK ORDER ACTIVITY NUMBER
- 92 STATUS
- HOLD 02AUG02 ORDER
- C0151434 STATUS
- PLNNED 18NOV94 DES PAGE: 01 CRIPTIO W/O DESCRIPTION ACT DESCRIPTION PERFORMING ORG COMPONENT ID EQUIPMENT LOCAT CLR NUMBER WO RESP ORG DATE/SHIFT FOREMAN SSV AUTH ORG-INSP/HOLD ACT TYPE PREPARED BY HOLDS BARRIER PERMIT IRE RPROTECTIOIN ZARD BARRIER SYSTEM BREACH HWP REQ MULTIPLE WORK I HP REQD
- "PLANNING USE ONLY" SEE C0182906FOR TEMPLATES S:
SYSTEM-94 CLEAN /
INSPECT / LUBE COUPLING
- PMM
- PB 2
94 F
MISC SYSTEM-94
'ION:_*
DAP PUNCH LISTED UNDER REVIEW
- PMM WORK STANDARD
- N/A
- __FACTS CHARGE WORK CTR 94202
_DATE
- N/A
- C SUPPORT DATES: N/A N/A
- NULL, JIM DATE 05JUN99
- MODE PARTS N
CHEM + RAD Y
CLR Y
PLAN SCH
===SAFETY/PLANT IMPACT CONSIDERATIONS--.---
RQD: N CHEMICAL HAZARD-: N CSP REQ
- N
- N SECURITY
- N FSI REQ
- _N
- N /
CH*F*4AND RAD DATA
- _N INSULATION REQUIRED: N
- N SCAFFOLDING REQD
- N TECH SPEC:
,OC : N MAP NBR: UNIT 2 REACTOR BLDG 1 165' ELEV.
- A ADVANCED RAD WORKER ACTIVITY SCHEDULING DATA:
PREMIS ID START DATE
- 14JUL99 CLEARANCE REQD : Y SCHED ID/WIN PB
.EST DUR (HRS) 8 INITIAL REVIEWS=---------
ASME/ISI REVIEW QC PLAN REVIEW APPROVED BY WORK INSTRUCTION ASME XI R&R:
MSG/MCKELVEY,JM MAINT ENGR:
DATE: N/A DATE: N/A DATE: 02AUG02 DATE: N/A PRINT NAME AND WRITE INITIALS OF ALL PERSONNEL WHO INITIALED THIS ACTIVITY FOR INFO ONLY XXX FOR INFO ONLY XXX FOR INFO ONLY XXX W
FOR INFO ONLY XXX FOR INFO ONLY XXX FOR INFO ONLY XXX FOR INFO ONLY XXX FOR INFO ONLY XXX FOR INFO ONLY XXX FOR INFO ONLY XXX FOR INFO ONLY XXX FOR INFO ONLY XXX
WOR ORDER NUMBER STATUS do" ORDER ACTIVITY
- 92
- HOLD 02AUG02
- C0151434
- PLNNED 18NOV94 PAGE: 02 ACTIVITY P L
IST ACTIVITY FOLLOWER DESCRIPTION STEP DESCRIPTION NBR C'
INITIAL/DATE OMPLT INSP
- 1. PURPOSE:
A.
- 1) CLEAN INSPECT COUPLING INTERNALS,
- 2) REPLENISH GREASE, AND
- 3) VERIFY ALIGNMENT/SOFT FOOT IS SAT.
- 2.
SPECIAL CLEARANCE REQUIREMENTS A.
SCT BLOCKING IS REQUESTED TO RUN THE
- PUMP, TO TAKE VIBRATION DATA AND TEMPS.
- 3.
SUPPORT INFORMATION A.
EQUIPMENT LOCATIONS:
- 1) IR4-R-B (2564)
MCU FOR 2BP145-DR UNIT 2 REACTOR BLDG I 135' ELEVATION NEAR DRYWELL EQUIPMENT ACCESS DOOR IN MCC 20B025
- 2) 2AP145...
2'A' FUEL POOL CLG WTR PUMP UNIT 2 REACTOR BLDG I 165' ELEVATION B. LUBRICATION REQUIREMENTS:
WORK ORDER ACTIVITY NUMBER
- 92 STATUS
- HOLD 02AUG02 RK ORDER
- C0151434 STATUS
- PLNNED 18NOV94 ACTIVITY FOLLOWER DESCRIPTION STEP DESCRIPTION NBR PAGE: 03 INITIAL/DATE COMPLT INSP
- 1) PUMP BEARINGS...
HARMONY 100
- 2) MO.TOR BEARINGS...
EP-2 GREASE
- 3) COUPLING, FAST...
KOPPERS GREASE
- 4. JOB SCOPE A.
COUPLING INSPECTION:
- 1) REMOVE THE COUPLING GUARD.
- 2) OPEN THE COUPLING.
- 3) CLEAN OUT THE OLD GREASE AND EXAMINE FOR ANY METALIC SUBSTANCE AND ABNORMALITIES OR HARDNESS.
- CRACKS, OR ANY DEFECTS NOT MENTIONED.
REWORK AS REQUIRED.
- 5)
LUBE AND MAKE-UP COUPLING
- 6) ALIGN MOTOR TO PUMP USING M-C-700-315
- NOTE:
IF THE COUPLING OR ALIGNMENT REQUIRED REWORK OR CORRECTION; THE
- PMT, (STEP C),
WILL BE REQUIRED.
- 7)
LUBRICATE THE COUPLING WITH NEW GREASE AND CLOSE.
- 8) REINSTALL THE COUPLING GUARD.
S
- 4. JOB SCOPE
WORI( ORDER NbMBER STATUS SATUJS ACTIVITY
- 92
- HOLD 02AUG02
- C0151434
- PLNNED 18NOV94 ACTIVITY FOLLOWER DESCRIPTION STEP DESCRIPTION NBR PAGE: 04 INITIAL/DATE COMPLT INSP B. MOTOR MAINTENANCE:
- 1) CLEAN THE MOTOR'S EXTERIOR AND ITS VENTILATION PORTS.
C. POST MAINTENANCE TESTING:
- 1) SEE ACTIVITY 02 FOR CONTINGENT P.M.T.
NOTE: ACT 02 P.M.T.
IS TO BE PERFORMED,
- ONLY, IF PARTS WERE REPLACED OR IF THE ALIGNMENT REQUIRED CORRECTION S*
> END JOB SCOPE<
S
WORIC ORDER ACTIVITY NUMBER
- 92 STATUS
- HOLD 02AUG02 I
B RDE
- C0151434 STATUS
- PLNNED 18NOV94 PAGE: 05
- SUMARYCOMMENTS:
U CAUSE CODE:
REPAIR CODE:
ADDITIONAL PAGES ATTACHED ?
ETT REMOVED ?
================-MEASUREMENT AND TEST EQUIPMENT===================
ID NUMBER DATE USED DESCRIPTION ADDITIONAL PAGES ATTACHED ?
FINAL REV
.INT QC OTHER IEWS=------------------------------------
DATE :
DATE :
DATE :
m
WORK ORDER ACTIVITY NUMBER
- 92 STATUS
- HOLD 02AUG02 RKORDER ER
- C0151434 STATUS
- PLNNED 18NOV94 PAGE: 06 MEASURM4ENT AND TEST EQUIPMENT ACTIVITY ID NUMBER DATE USED DESCRIPTION
PECO NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:
Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:
27301300202 K/A:
2.3.6 URO: 2.1 SRO: 3.1 TASK DESCRIPTION:
Knowledge of the requirements for reviewing and approving release permits.
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.
P'age.3 OT b3 SRO AJPM 4 - Radwaste Liq Disch.doc
B.
TOOLS AND EQUIPMENT S
- 1.
Calculator
- 2.
Copy of ST-C-095-805-2 "Liquid Radwaste Discharge", Rev. 9, completed through step 6.11.
- 3.
A calculation error made in step 6.10.1.2.
C.
REFERENCES
- 1.
ST-C-095-805-2, Rev. 9, "Liquid Radwaste Discharge".
D.
TASK STANDARD
- 1.
Satisfactory task completion of this task is indicated when the Shift Management review has been completed, the errors in the procedure have been identified and the release is disapproved pending resolution of the problems.
- 2.
Estimated time to complete: 15 minutes Non-Time Critical E.
DIRECTIONS TO EXAMINEE When given the initiating cue, perform the necessary steps to review a Liquid Radwaste discharge, using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.
F.
TASK CONDITIONS/PREREQUISITES
- 1.
Unit 2 is operating at 100% power.
- 2.
The Floor Drain Sample Tank (FDST) needs to be discharged.
- 3.
Chemistry has completed ST-C-095-805-2, "Liquid Radwaste Discharge" through step 6.11.
- 4.
RIS-0-1 7-350 "Radwaste Effluent" Radiation Monitor is operable.
- 5.
FS-0-20-493 "RWS Low Purity Waste" High Flow Trip Set Pot and the associated flow control valve are operable.
- 6.
The discharge Canal-To-Intake Pond crosstie gate is closed.
- 7.
The Shift Management review and approval has not been completed.
SRO AJPM 4-Radwaste Liq Disch.doc Page 4 of 6 SRO AJPM 4 - Radwaste Liq Disch.doc Page 4 of 6
G.
INITIATING CUE As the Control Room Supervisor, complete Section 6.12 of ST-C-095-805-2, "Liquid Radwaste Discharge".
SRO AJPM 4 - Radwaste Liq Disch.doc Page 5 of 6 SRO AJPM 4 - Radwaste Liq Disch.doc Page 5 of 6
H.
PERFORMANCE CHECKLIST I STEP STEP ACT STANDARD
-NO 1
Review ST-C-095-805-2 for P
Visually verify all CT actions in steps 6.1 completeness.
through 6.11 have been completed satisfactorily and initial step 6.12.1 SAT.
2 Verify calculations.
P Perform all calculations that were done in section 6.8 and 6.10 and verify they are correct and recorded on Data Sheet 3 &
- 4.
- 3 Recognize Calculation error.
P Recognize error in step 6.10.1.2 for High Flow Discharge setting. Initial step 6.12.2 UNSAT.
- 4 Disapprove the Radwaste Discharge.
P Disapprove the discharge and return the paperwork to the Chemistry Department.
_ _ _ _ C u e : A c k n o w le d g e th e d is a p p ro v a l.)_
- NOTE ***
Terminate the exercise when the activities listed above are performed.
Under "ACT" P - must perform S - must simulate I.
TERMINATING CUE When the review of ST-C-095-805-2 has been completed, and the release is disapproved, terminate the exercise.
SRO AJPM 4-Radwaste Liq Disch.doc Page 6 of 6 SRO AJPM 4 - Radwaste Liq Disch.doc Page 6 of 6
TASK CONDITIONS/PREREQUISITES
- 1.
Unit 2 is operating at 100% power.
- 2.
The Floor Drain Sample Tank (FDST) needs to be discharged.
- 3.
Chemistry has completed ST-C-095-805-2, "Liquid Radwaste Discharge" through step 6.11.
- 4.
RIS-0-17-350 "Radwaste Effluent" Radiation Monitor is operable.
- 5.
FS-0-20-493 "RWS Low Purity Waste" High Flow Trip Set Pot and the associated flow control valve are operable.
- 6.
The discharge Canal-To-Intake Pond crosstie gate is closed.
- 7.
The Shift Management review and approval has not been completed.
INITIATING CUE As the Control Room Supervisor, complete Section 6.12 of ST-C-095-805-2, "Liquid Radwaste Discharge".
EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:
Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:
2007510502 / PILT-ADMIN 000 K/A:
2.4.41 URO: 2.3 SRO: 4.1 TASK DESCRIPTION:
Reactor Power EAL Classification - Site Area Emergency A.
NOTES TO EVALUATOR:
- 1.
An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.
- 2.
System cues included in the performance checklist are to be provided to the examinee when no system response is available.
- 3.
JPM Performance
- a.
"Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).
- b.
When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.
- 4.
Satisfactory performance of this JPM is accomplished if:
- a.
The task standard is met.
- b.
JPM completion time requirement is met.
- 1)
For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.
- 2)
For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.
- 5.
The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.
\\\\
SRO Admin 5 - EAL Classification Page 3* OT
B.
TOOLS AND EQUIPMENT None C.
REFERENCES
- 1.
ERP-101, Rev. 23, "Classification of Emergencies" Table 2
- 2.
ERP-200, Rev. 18, "Emergency Director (ED)"
- 3.
ERP-200, Appendix 1, Rev. 6, "Emergency Director Checklist (MCR)"
- 4.
ERP-200, Appendix 3, Rev. 4, "Event Notification Form" D.
TASK STANDARD
- 1.
Satisfactory task completion is indicated when plant conditions have been classified as a Site Area Emergency in accordance with ERP-101 Table 2.2.3, and the appropriate steps of ERP-200, Appendix 1, "Emergency Director Checklist (MCR)" have been completed.
- 2.
Estimated time to complete: 15 minutes -Time Critical (To classify the Event) 15 minutes - Non-Time Critical To complete ERP-200, Appendix 1 actions)
- I.
DIRECTIONS TO EXAMINEE This is a 2-part JPM. When given the first initiating cue, perform necessary steps to classify the event using appropriate procedures. When the event is classified, I will give you an additional cue to perform Emergency Director actions for the same event. I will describe initial plant conditions and provide you access to the materials required to complete this task.
F.
TASK CONDITIONS/PREREQUISITES An open SRV resulted in a attempted manual reactor scram. The following is the current plant status:
- 1.
RPS failed to generate an automatic scram.
- 2.
The manual scram pushbuttons and ARI failed to insert control rods.
- 3.
Reactor power is 35% and steady.
- 4.
Torus temperature is 160 degrees F.
- 5.
Torus level is 15 feet.
- 7.
Reactor pressure is 1000 psig and steady.
- 8.
RPV level is being controlled between -120 inches and -150 inches.
SRO Admin 5 - EAL Classification Page 4 of 4
- 9.
There is NO radioactive release in progress and NO indication of fuel damage.
- 10.
The TSC and EOF are not yet activated.
INITIATING CUE As the Emergency Director, classify the event in accordance with ERP-1 01, "Classification of Emergencies" NOTE: When the event has been classified, give the following cue.
As the Emergency Director, complete the INITIAL ACTIONS of ERP-200 Appendix 1 "Emergency Director (ED) Checklist".
SRO Admin 5 - EAL Classification Page 5 of 5 G.
SRO Admin 5 - EAL Classification Page 5 of 5
H.
PERFORMANCE CHECKLIST 1LSTEP STEP ACT STANDARD NO
- NOTE***
Note the time when the Emergency Director receives the Task Conditions/Prerequisites. Step 1 and 2 below must be completed within 15 minutes.
1 Obtain a copy of procedure ERP-1 01.
P A copy of procedure ERP-101 is obtained.
- 2 Classify the event.
P ERP-1 01 Table 2.2.3, "Reactor Power" is referenced. The event is classified as a (Cue: Classification is acknowledged.)
Site Area Emergency.
- NOTE***
Ensure that Step 2 is completed within 15 minutes of the start of the JPM.
Hand the Emergency Director the second Task Conditions/Prerequisites Sheet.
3 Obtain a copy of procedure ERP-200.
P A copy of procedure ERP-200 is obtained.
4 Obtain copies of procedure ERP-200 P
Copies of procedure ERP-200 Appendix Appendix I and Appendix 3.
1 and Appendix 3 are obtained.
- 5 Perform the ED Initial Actions using the ERP 200 Appendix 1 Checklist:
"* NOTE: Classification steps have been performed previously in part 1 of this JPM.
"* Call the SAS Operator (Security) and S
Call the SAS Operator (281 or 4277) and direct activation of the ERO per ERP-direct activation of the ERO per ERP-140.
140.
"* Refer SAS Operator to the S
Refers the SAS Operator to Emergency Emergency Notification Binder.
Notification Binder (Cue: The SAS Operator acknowledges the direction.)
SRO Admin 5 - EAL Classification Page 6 of 6 SRO Admin 5 - EAL Classification Page 6 of 6
STEP STEP ACT STANDARD NO I
I II
= A
"* 6 Fax Completed Appendix 3 to the S
Fax Appendix 3 to the SAS at 3228.
SAS Operator.
"* Phones the SAS operator to confirm S
Phone the SAS Operator at 281 or 4277.
receipt of fax.
(Cue: The Fax has been sent to the SAS operator. SAS Operator confirms receipt of fax.)
Continues ERP-200 Appendix 1 ED Checklist:
"* Evaluates necessity to relocate the TSC per Appendix 9 or the OSC per Appendix 10.
P P
Determines there is no need to relocate TSC or OSC.
Determines no GE and no PAR required.
Directs NRC communicator actions.
SRO Admin 5 - EAL Classification Page 7 of 7 8
£ ________________________________
I ________________________________
SRO Admin 5 - EAL Classification Page 7 of 7 Complete the ERP-200, Appendix 3, "Event Notification Form",
"* Emergency Classification.
"* Unit, Time, Date.
- Initial Declaration.
Brief Non-Technical Description.
Non-Routine Radiological Release in Progress.
- Wind Direction and Speed.
(Cue: Acknowledges completion of Appendix 3.)
"Site Area Emergency" box checked.
Unit, "2", Current Time and Date.
"Initial Declaration" box checked Any paraphrase of conditions is acceptable.
"NO" Box checked.
Wind Direction 0 Wind Speed 10 P
P P
P P
P
Dirct NR Comnctr cine P
P Directs NRC Communicator actions per checklist.
Directs PA Announcement.
10 Evaluates the need for Dose P
Determines no need for Dose Assessment.
Assessment.
0 Include Accident Assessment in MCR P
Directs Accident Assessment information logs.
in logs.
(Acknowledges accident information to be recorded in control room logs.)
"*11 Directs Site Evacuation per ERP-1 30.
P Directs personnel to perform a Site Evacuation per ERP-130.
(Acknowledges direction to perform a Site Evacuation)
NOTE ***
PTerminate the exercise when the activities listed above are performed. A dose assessment, use of 1,CSAMPs and completion of the Turnover/Briefing form (App 7) are NOT required.
Under "ACT" P - must perform S - must simulate
- 1.
TERMINATING CUE When the event is classified, the Station Public Address Announcement is directed, the NRC Communicator has been assigned, and the Site Evacuation has been directed, the evaluator will then terminate the exercise.
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- WL L.iaSSITiCatIOn Page 8 of 8 5RQ*
Admln 5 - IEAL CJlasslifcation Page 8 of 8 V
"* Appoints NRC Communicator to:
Complete ENS Worksheet.
Activate ERDS.
Call the NRC on ENS phone.
(Acknowledges NRC Communicator actions directed.)
" Directs the PA Announcement for Site Area Emergency per Appendix 4.
(Acknowledges PA Announcement.)
TASK CONDITIONS/PREREQUISITES An open SRV resulted in an attempted manual scram. The following is the current plant status:
- 1.
RPS failed to generate a reactor scram.
- 2.
The manual scram pushbuttons and ARI failed to insert control rods.
- 3.
Reactor power is 35% and steady.
- 4.
Torus temperature is 160 degrees F.
- 5.
Torus level is 15 feet.
- 7.
Reactor pressure is 1000 psig and steady.
- 8.
RPV level is being controlled between -120 inches and -140 inches.
- 8.
There is NO radioactive release in progress and NO indication of fuel damage.
- 9.
The TSC and EOF are not yet activated.
INITIATING CUE Part I of 2 As the Emergency Director, classify the event in accordance with ERP-1 01, Classification of Emergencies".
TASK CONDITIONS/PREREQUISITES Conditions have not changed since the Emergency Classification.
INITIATING CUE Part 2 of 2 As the Emergency Director, complete the INITIAL ACTIONS of ERP-200 Appendix 1 "Emergency Director (ED) Checklist".
Attachment #2