ML061290607
| ML061290607 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/01/2005 |
| From: | Operations Branch IV |
| To: | Southern California Edison Co |
| References | |
| 50-361/05-301, 50-362/05-301 | |
| Download: ML061290607 (162) | |
Text
Appendix D Scenario Outline Form ES-D-1 Facility: San Onofre Scenario No.: 1 Op Test No.: NRC Examiners: Operators:
Initial Conditions:
- Train A Component Cooling Water Pump (P-025) in service
- Train A Saltwater Cooling Pump (P-307) OOS
- Train A Low Pressure Safety Injection Pump (P-015) OOS
- Condenser Air Ejector Low Range Radiation Monitor (RM-7818) OOS Turnover: Maintain steady-state power conditions.
Critical Tasks: Transfer the Non-Critical Loop (SWC failure)
Isolate affected Steam Generator Reduce Thot to < 530°F Event No. Malf. No. Event Type* Event Description 1 SC01A C (ACO, CRS) SWC Pump trip P-112 (seized shaft).
+15 min TS (CRS) 2 RC24A C (CO, CRS) Spray valve fails open (PV-0100A @ 40%).
+30 min TS (CRS) 3 RX11A I (ACO, CRS) MFWP speed signal fails low (P-062 speed control).
+45 min 4 SG06A C (CO, CRS) SG tube leak on E-088 (~50 gpm).
+60 min TS (CRS) 5 R (CO) Rapid down power due to SG tube leak on E-088.
+70 min N (ACO, CRS) 6 SG06A M (ALL) SGTR on E-088.
+80 min 7 PG21 Unit output breaker fails to open.
+80 min 8 K403B I (CO) SIAS relay failure.
+80 min
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specifications Appendix D NUREG 1021 Revision 9
Appendix D Scenario Outline Form ES-D-1 SCENARIO
SUMMARY
- 1 The crew will assume the shift at 100% power and maintain steady-state conditions per SO23-5-1.7, Power Operations.
When turnover is complete a Saltwater Cooling Pump will trip due to a seized shaft. The crew will respond per SO23-2-17, Component Cooling System Operation and/or AOI SO23-13-7, Loss of Component Cooling Water (CCW) / Saltwater Cooling (SWC). The crew will align SWC & CCW Train B per pump configuration requirements. The SRO will be required to evaluate Technical Specifications.
When the CCW and SWC systems are properly aligned the Pressurizer Spray Valve will fail 40%
open. Crew will respond and stabilize primary plant using Annunciator Response Procedures (ARP) and Abnormal Operating Instruction (AOI) SO23-13-27, Pressurizer Pressure and Level Malfunction. The SRO will be required to evaluate Technical Specifications.
When plant is stable and the instrument card for the Pressurizer Spray Valve is pulled (valve closes) a Main Feed Water Pump speed signal will fail high. Crew will regain control of feedwater pump per Annunciator Response Procedures and AOI SO23-13-24, Feedwater Malfunctions.
Once stable, a small tube leak will occur. The SRO will be required to evaluate Technical Specifications and enter AOI SO23-13-14, Reactor Coolant System Leak. The SRO will determine that a rapid downpower per SO23-5-1.7, Power Operations is required. Once the power change is underway and the crew has demonstrated plant control during the power reduction, the leak will become a rupture and cause a plant trip. The crew performs SO23-12-1, Standard Post Trip Actions and diagnoses a SGTR and enters SO23-12-4, Steam Generator Tube Rupture (SGTR). The crew will be required to isolate the affected SG and reduce Thot to <
530°F. A Generator Output Breaker will fail to open on Turbine trip and actuate the Breaker Failure Local Backup (BFLBU). A SIAS relay failure will require the operator to position three (3)
Train B SIAS valves to their SIAS position.
Scenario is terminated when the affected SG is isolated, Thot is < 530°F, and plant conditions are stable.
Risk Significance:
- Failure of risk important system prior to trip: SWC Pump seizure
- Risk significant operator actions: Manually initiate SIAS Transfer the Non-Critical Loop Appendix D NUREG 1021 Revision 9
Appendix D Scenario Outline Form ES Facility: San Onofre Scenario No.: 2 Op Test No.: NRC Examiners: Operators:
Initial Conditions:
- Train A Component Cooling Water Pump (P-025) in service
- Train A Saltwater Cooling Pump (P-307) OOS
- Train A Low Pressure Safety Injection Pump (P-015) OOS
- Condenser Air Ejector Low Range Radiation Monitor (RM-7818) OOS Turnover: Boration and down power required for taking the Turbine off-line for planned maintenance.
Critical Tasks:
- Respond to ATWS by de-energize B15 & B16
- Start Component Cooling Water Pump following SDVS Event No. Malf. No. Event Type* Event Description 1 R (CO) Commence boration and down power following turnover at 15%/hour.
+15 min N (ACO, CRS) 2 TU10A C (ACO, CRS) Turbine Governor Valve fails closed (UV2200B).
+30 min 3 RC11A I, (CO, CRS) RCS Th Loop 1 TT-0111X1 fails HIGH to 625°F.
+40 min 4 PG22 C (ACO, CRS) Degraded grid to SDVS setpoint.
+50 min PG23 TS (CRS) 5 SEISMIC Seismic event without Feedwater Pump trip.
+55 min OBE w/o FWPT 6 RC03 C (CO, CRS) RCS leak requiring a plant shutdown (~30 gpm).
+65 min TS (CRS) 7 RC03 M (ALL) LOCA @ 500 gpm.
+75 min 8 RP03 C (ACO) Auto and manual Reactor trip failure (ATWS).
+75 min 9 MS03B M (ALL) ESDE on E-089 inside Containment.
+75 min 10 EC08DA C (CO) HPSI Pump (P-018) trip.
+75 min
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specifications Appendix D NUREG 1021 Revision 9
Appendix D Scenario Outline Form ES SCENARIO
SUMMARY
- 2 The crew will assume the shift with a boration required to remove the Turbine from service for pre-planned maintenance per SO23-5-1.7, Power Operations.
After the crew has demonstrated control of the power change an HP Turbine Governor Valve will fail closed. The crew will respond per the Annunciator Response Procedures (ARP) and SO23-10-3, Operation of the Turbine Control and Protection System.
With the plant in a stable condition a Thot instrument fails high and will require crew actions per the ARPs and Abnormal Operating Instruction (AOI) SO23-13-27, Pressurizer Pressure and Level Malfunction. This is followed by a frequency drop and grid voltage decrease to the Sustained Degraded Voltage Signal (SDVS) for 110 seconds that will require crew response and entry into AOI SO23-13-4, Operation during Major System Disturbances. The ACO will be required to maximize Generator MVARs and restart a CCW Pump. The CRS will evaluate Technical Specifications.
With plant conditions stable a seismic event will occur. The crew will perform actions in AOI SO23-13-3, Earthquake. Initially an RCS leak of about 30 gpm will require the crew to determine that a plant shutdown is required. After Technical Specifications have been evaluated, an aftershock will result in a loss of Coolant Accident and Steam Line Break along with an ATWS. The crew will respond to the ATWS by opening breakers to B15 and B16. The crew performs SO23-12-1, Standard Post Trip Actions and diagnoses a LOCA and an ESDE and transition to SO23-12-9, Functional Recovery.
During the Functional Recovery a HPSI Pump P-018 will trip. The CO will be required to manually start HPSI Pump P-017. The scenario is terminated when RCS temperature and pressure are stabilized while in the Functional Recovery procedure and associated Floating Steps.
Risk Significance:
- Risk significant operator actions: Manually trip Reactor on ATWS Start a CCW Pump on SDVS Appendix D NUREG 1021 Revision 9
Appendix D Scenario Outline Form ES-D-1 Facility: San Onofre Scenario No.: 3 Op Test No.: NRC Examiners: Operators:
Initial Conditions: * ~25% power - RCS Boron is 1123 ppm
- Train A Component Cooling Water Pump (P-025) in service
- Train A Saltwater Cooling Pump (P-307) OOS
- Train A Low Pressure Safety Injection Pump (P-015) OOS
- Condenser Air Ejector Low Range Radiation Monitor (RM-7818) OOS Turnover: Dilution and power increase in progress at 10% per hour.
Critical Tasks:
- Transfer Component Cooling Water for Non-Critical Loop.
- Energize Vital AC Buses A06 & B06 with G003.
Event No. Malf. No. Event Type* Event Description 1 R (CO) Dilution and power increase in progress.
+15 min N (ACO, CRS) 2 CV14 C (CO, CRS) Loss of Primary Water Makeup Pumps.
+25 min 3 RC22C TS (CRS) RCS Cold Leg Temperature Transmitter Failure to the Core Protection
+30 min Calculators.
4 CV19 I (CO, CRS) Letdown Temperature instrument fails low.
+40 min 5 ED07C C (ALL) Loss of Inverter Y003.
+50 min TS (CRS) 6 Severe weather (tornado watch).
+65 min 7 TU08 M (ALL) Turbine trip due to electric governor failure.
+65 min PG24 Loss of Off-site Power (+ 5 seconds).
8 EG08A C (ACO) Mechanical failure of EDG G002.
+65 min 9 EG07B C (ACO) EDG G003 AVR failure requires manual adjustment for breaker closure.
+70 min
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specifications Page 5 of 162
Appendix D Scenario Outline Form ES-D-1 SCENARIO
SUMMARY
- 3 The crew will assume the shift at approximately 25% power with a dilution in progress. The crew will raise power per SO23-5-1.7, Power Operations.
After the crew has demonstrated control of the power change, the Primary Water Makeup Pumps trip and are addressed per the Annunciator Response Procedures (ARP). A Tcold Protection Channel failure will occur on Plant Protection System Channel C. The crew will respond per the Annunciator Response Procedures, Abnormal Operating Instruction (AOI) SO23-13-18, Reactor Protection System Failure and the CRS will evaluate Technical Specifications.
With the plant stable the crew will respond to a Letdown Temperature Instrument Failure. This will require action per the Annunciator Response Procedures. A vital bus failure will cause the crew to enter AOI SO23-13-18, Loss of Vital Bus. The CRS will evaluate Technical Specifications and the bus will be re-energized from the alternate supply per SO23-6-17, 120 VAC Vital Bus Power Supply System Operation.
When the Vital Bus is restored, the crew will receive a tornado watch from the National Weather Service and will enter AOI SO23-13-8, Severe Weather. The crew will be required to prepare for the tornado watch by performing actions inside and outside the Control Room.
A Loss of Off-Site power will occur and the crew will respond to a plant trip per SO23-12-1, Standard Post Trip Actions and will transition to SO23-12-7, Loss of Forced Circulation / Loss of Off-Site Power. A mechanical failure of an emergency diesel generator coupled with an EDG breaker that fails to close due to the setting of the automatic voltage regulator will require the operator to adjust and manually close the output breaker.
Event termination will occur once an off-site line is restored, the crew has re-energized 2A03 or 2A07, and plant temperature and pressure are stable.
Risk Significance:
- Failure of risk important system prior to trip: Loss of Vital Inverter
- Risk significant core damage sequence: Failure to recover from LOOP
- Risk significant operator actions: EDG failure Page 6 of 162
Appendix D Scenario Outline Form ES-D-1 JPM INFORMATION SHEET JPM NUMBER SO-05 NRC RO JPM A.1.a INITIAL PLANT CONDITIONS Unit 2 is currently in Mode 3 at 545°F.
The plant was shutdown due to a fully stuck out and immovable CEA (#40).
Current core burnup is 250 EFPD. A cooldown to Mode 5 is required to evaluate the stuck CEA.
Current RCS boron concentration is 1500 ppm.
The BAMU Tanks are at a boron concentration of three (3) weight percent Boric Acid.
The Plant Monitoring System is unavailable for use.
TASK TO BE PERFORMED Determine the Target boron concentration for RCS Cooldown to Mode 5 per SO23-5-1.5, Plant Shutdown from Hot Standby to Cold Shutdown, Step 6.3.4 and determine the amount of Boric Acid required to raise RCS boron concentration to the Target boron concentration.
Page 7 of 162
Appendix D Scenario Outline Form ES-D-1 JOB PERFORMANCE MEASURE SO-05 NRC RO JPM A.1.a SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:
The operators performance was evaluated against the standards contained in this JPM and is determined to be:
SATISFACTORY:
UNSATISFACTORY:
Page 8 of 162
Appendix D Scenario Outline Form ES-D-1 DOCUMENTATION SO-05 NRC RO JPM A.1.a JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 20 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: ACO VISION ID: 185181 TASK DESCRIPTION Perform a plant shutdown from hot standby to cold shutdown.
KA NUMBER: 2.1.20 KA VALUES: RO 4.3 SRO 4.2 10CFR55.45 APPLICABILITY: 1
REFERENCES:
SO23-5-1.5, Plant Shutdown From Hot Standby to Cold Shutdown, Rev. 24 SO23-3-2.2, Makeup Operations, Rev. 18 M-38100, Operations Figure 2.3-1, Songs Unit 2 Cycle 13 (MOC) Minimum Boron Concentration for 5.15% Shutdown Margin, Rev. 49 Operations Web Page/References/Miscellaneous/Boration/Dilution Table AUTHOR: L. Zilli DATE: 02/24/05 OPERATIONS REVIEW: M. Jones DATE: 03/08/05 APPROVED BY: A. Hagemeyer DATE: 03/08/05 Page 9 of 162
Appendix D Scenario Outline Form ES-D-1 MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New - - -
1 Compared with SO23-5-1.5, Rev. 24 and LRZ 02/24/05 REV modified to include a stuck rod in the initial conditions. Also changed calculated value to reflect Cycle 13 MOC graph. Added requirement to calculate amount of boron required.
Page 10 of 162
Appendix D Scenario Outline Form ES-D-1 SET-UP Use any of the following as required throughout the JPM.
NOTE: Provide the Examinee with a copy of SO23-5-1.5, Plant Shutdown from Hot Standby to Cold Shutdown, SO23-3-2.2, Makeup Operations and the Boration/Dilution Tables from the OPS Web page.
Provide the examinee with a copy of Operations Figure 2.3-1, SONGS Unit 2 Cycle 13 (MOC)
Minimum Boron concentration for 5.15% Shutdown Margin.
CAUTION: Ensure that the curve is readable due to the six (6) different conditions addressed by the curve. Consider making copies directly from the Nuclear Database Management System to avoid this problem.
Page 11 of 162
JPM: SO-05 NRC RO A.1.a TITLE: Determine the Required Boron Concentration for Cooldown to Mode 5
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)
NOTE: Provide the examinee with a copy of SO23-5-1.5, Plant Shutdown from Hot Standby to Cold Shutdown, SO23-3-2.2, Makeup Operations and the Boration/Dilution Tables from the OPS Web page. Provide the examinee with a copy of Operations Figure 2.3-1, Songs Unit 2 Cycle 13 Minimum Boron Concentration for 5.15% Shutdown Margin.
1 Determine target boron concentration. Determines target boron concentration Start Time: _______
requires OPS Figure 2.3-1, SONGS Unit 2 Cycle 13 Minimum Boron Concentration for 5.15% Shutdown Margin.
2* Read OPS Figure 2.3-1, SONGS Unit Selects correct curve and locates boron 2 Cycle 13 Minimum Boron concentration using OPS Figure 2.3-1, Concentration for 5.15% Shutdown SDM 5.15% @ 200°F and Worst Rod Stuck Margin. Out (WRSO).
Calculates a value between 1650 ppm &
1750 ppm.
3* Calculate the amount of boron Calculates the amount of boron required to required to raise RCS boron raise RCS boron concentration from 1500 concentration from 1500 ppm to 1700 ppm to 1700 ppm using SO23-3-2.2, ppm using SO23-3-2.2 and the Attachment 10 and the Boration/Dilution Boration/Dilution Table. Table from the Operations Web Page.
Calculates a value of 3368 +/- 870 gallons.
TERMINATING CUE: Stop Time: _______
This JPM is complete.
Page 12 of 162
JPM: SO-05 NRC RO TITLE: Determine the Required Boron Concentration for A.1.a Cooldown to Mode 5
- Denotes a CRITICAL STEP JPM CHECKLIST
- 1. The JPM is:
- a. X Supported by facilitys job task analysis.
- b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).
- c. X Designed as either SRO only, or RO/SRO.
- 2. Each JPM includes:
- a. X Initial conditions.
- b. X Initiating cues.
- c. X References, including associated procedures.
- d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.
- e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.
- f. N/A Statements describing important actions or observations that should be made by the Examinee.
- g. X Criteria for successful completion.
- h. X Identification of the critical steps and their associated performance standards.
- i. X Validated time limits (average time allowed for completion).
- j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.
COMPLETED BY: L. Zilli DATE: 02/24/05 Page 13 of 162
JPM: SO-05 NRC RO TITLE: Determine the Required Boron Concentration for A.1.a Cooldown to Mode 5
- Denotes a CRITICAL STEP JPM INFORMATION SHEET JPM NUMBER SO-05 NRC RO JPM A.1.b INITIAL PLANT CONDITIONS Unit 2 is at 100% power. RCS Flow Rate must be determined to comply with Technical Specification Surveillance Requirement 3.4.1.3. The PMS computer is not available.
TASK TO BE PERFORMED The Control Room Supervisor directs you to perform SO23-3-3.3, RCS Flow Rate Determination, Attachment 2, RCP P Flow Calculation for SONGS Unit 2 and determine if Acceptance Criteria is met.
Page 14 of 162
JPM: SO-05 NRC RO TITLE: Determine the Required Boron Concentration for A.1.a Cooldown to Mode 5
- Denotes a CRITICAL STEP JOB PERFORMANCE MEASURE SO-05 NRC RO JPM A.1.b SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:
The operators performance was evaluated against the standards contained in this JPM and is determined to be:
SATISFACTORY:
UNSATISFACTORY:
Page 15 of 162
JPM: SO-05 NRC RO TITLE: Determine the Required Boron Concentration for A.1.a Cooldown to Mode 5
- Denotes a CRITICAL STEP DOCUMENTATION SO-05 NRC RO JPM A.1.b JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 20 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CO TASK SYS ID: 179879 TASK DESCRIPTION Perform an RCS Flow Rate Determination.
KA NUMBER: 2.1.19 KA VALUES: RO 3.0 SRO 3.0 10CFR55.45 APPLICABILITY: 12
REFERENCES:
SO23-3-3.3, RCS Flow Rate Determination, Rev. 6, Attachment 2, RCP P Flow Calculation Technical Specification 3.4.1 AUTHOR: L. Zilli DATE: 04/05/05 OPERATIONS REVIEW: M. Jones DATE: 04/08/05 APPROVED BY: A. Hagemeyer DATE: 04/08/05 Page 16 of 162
JPM: SO-05 NRC RO TITLE: Determine the Required Boron Concentration for A.1.a Cooldown to Mode 5
- Denotes a CRITICAL STEP MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 2 Compared against SO23-3-3.3, Rev. 6 LRZ 04/05/05 REV and modified calculations to conform with new RCP Curves and procedure changes.
Page 17 of 162
JPM: SO-05 NRC RO TITLE: Determine the Required Boron Concentration for A.1.a Cooldown to Mode 5
- Denotes a CRITICAL STEP SET-UP Obtain a copy of SO23-3-3.3 and markup Attachment 2, complete up to Step 3.1.2 with the following data:
Step 3.1.1:
Ch. A TC1 RAW Avg. - 542°F TC2 RAW Avg. - 541°F Ch. B TC1 RAW Avg. - 540°F TC2 RAW Avg. - 539°F Ch. C TC1 RAW Avg. - 539°F TC2 RAW Avg. - 538°F Ch. D TC1 RAW Avg. - 538°F TC2 RAW Avg. - 539°F Step 3.1.2:
P001 P AVG - 102 psid P002 P AVG - 105 psid P003 P AVG - 103 psid P004 P AVG - 104 psid Page 18 of 162
JPM: SO-05 NRC RO JPM A.1.b TITLE: Perform an RCS Flow Rate Determination
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)
NOTE: Provide the candidate with a copy of SO23-3-3.3 completed to Step 3.1.2 of Attachment 2.
CUE: Steps 3.1.1 and 3.1.2 of Attachment 2 were completed last shift.
1 Calculate Average RCS Cold Leg Calculates TC1 using the data from Start Time: ______
Temperature TC1. Attachment 2, Step 3.1.1.
TC1 = 539.75°F TC1 = (Sum all CPC Ch. TRC1 RAW) / 4 2 Calculate Average RCS Cold Leg Calculates TC2 using the data from Temperature TC2. Attachment 2, Step 3.1.1.
TC2 = 539.25°F TC2 = (Sum all CPC Ch. TRC2 RAW) / 4 3 Determine density TC1 for RCS Cold Determines TC1, using TC1 and Attachment Leg Temp TC1. 12.
TC1 = 47.4947 4 Determine density TC2 for RCS Cold Determines TC2, using TC2 and Attachment Leg Temp TC2. 12.
TC2 = 47.5545 Page 19 of 162
JPM: SO-05 NRC RO JPM A.1.b TITLE: Perform an RCS Flow Rate Determination
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)
NOTE: The Formula for the next step:
Pc = Pavg (Step 3.1.2) x (46.654 lbm/ft3 ) / TC1 (Step 3.1.4) 5 Calculate Pc, the Compensated Pump Calculates Pc for RCP P001 using TC1 and Average P for RCP P001. the data from Steps 3.1.2 & 3.1.4.
Pc = 100.2 +/- 0.1 psid NOTE: The Formula for this step:
Pc = Pavg (Step 3.1.2) x (46.654 lbm/ft3 ) / TC2 (Step 3.1.5) 6 Calculate Pc, the Compensated Pump Calculates Pc for RCP P002 using TC2 and Average P for RCP P002. the data from Steps 3.1.2 & 3.1.5.
Pc = 103.1 +/- 0.1 psid NOTE: The Formula for this step:
Pc = Pavg (Step 3.1.2) x (46.654 lbm/ft3 ) / TC1 (Step 3.1.4) 7 Calculate Pc, the Compensated Pump Calculates Pc for RCP P003 using TC1 and Average P for RCP P003. the data from Steps 3.1.2 & 3.1.4.
Pc = 101.2 +/- 0.1 psid Page 20 of 162
JPM: SO-05 NRC RO JPM A.1.b TITLE: Perform an RCS Flow Rate Determination
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)
NOTE: The Formula for this step:
Pc = Pavg (Step 3.1.2) x (46.654 lbm/ft3 ) / TC2 (Step 3.1.5) 8 Calculate Pc, the Compensated Pump Calculates Pc for RCP P004 using TC2 and Average P for RCP P004. the data from Steps 3.1.2 & 3.1.5.
Pc = 102 +/- 0.1 psid 9 Determine the flow for RCP P001. Determines the flow for RCP P001 using Pc and Attachment 3.
P001 flow = 112,500 +/- 2500 gpm 10 Determine the flow for RCP P002. Determines the flow for RCP P002 using Pc and Attachment 4.
P002 flow = 108,750 +/- 2500 gpm 11 Determine the flow for RCP P003. Determines the flow for RCP P003 using Pc and Attachment 5.
P003 flow = 114,000 +/- 2500 gpm 12 Determine the flow for RCP P004. Determines the flow for RCP P004 using Pc and Attachment 6.
Page 21 of 162
JPM: SO-05 NRC RO JPM A.1.b TITLE: Perform an RCS Flow Rate Determination
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)
P004 flow = 112,500 +/- 2500 gpm Page 22 of 162
JPM: SO-05 NRC RO JPM A.1.b TITLE: Perform an RCS Flow Rate Determination
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)
NOTE: The Formula for next step: Qt = P001 gpm + P002 gpm + P003 gpm + P004 gpm 13* Calculate the total RCS volumetric flow Calculates the total RCS volumetric flow rate (Qt). rate (Qt) by summing the flow for each RCP.
Qt = 447,750 gpm +/- 10,000 gpm CUE: Another operator will independently verify the calculations.
14* Verify Acceptance Criteria per Verifies Acceptance Criteria of 396,000 Technical Specifications. gpm is met per Technical Specifications.
TERMINATING CUE: Stop Time: ______
This JPM is complete.
Page 23 of 162
JPM: SO-05 NRC RO TITLE: Perform an RCS Flow Rate Determination JPM A.1.b
- Denotes a CRITICAL STEP JPM CHECKLIST
- 1. The JPM is:
- a. X Supported by facilitys job task analysis.
- b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).
- c. X Designed as either SRO only, or RO/SRO.
- 2. Each JPM includes:
- a. X Initial conditions.
- b. X Initiating cues.
- c. X References, including associated procedures.
- d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.
- e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.
- f. X Statements describing important actions or observations that should be made by the Examinee.
- g. X Criteria for successful completion.
- h. X Identification of the critical steps and their associated performance standards.
- i. X Validated time limits (average time allowed for completion).
- j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.
COMPLETED BY: L. Zilli DATE: 02/24/05 Page 24 of 162
JPM: SO-05 NRC RO TITLE: Perform an RCS Flow Rate Determination JPM A.1.b
- Denotes a CRITICAL STEP JPM INFORMATION SHEET JPM NUMBER SO-05 NRC RO JPM A.2 INITIAL PLANT CONDITIONS Unit 2 is operating at 100% power, Annunciator 53A46, 2nd POINT HEATER LEVEL HI/LO, has been coming in repeatedly for the last 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. An investigation has revealed that 2LSHL-3157 and 2LSHL-3103 (2ME-038 and 2ME-039 Second Point Heater HI/LO Level Switches) are both defective.
TASK TO BE PERFORMED The SRO Operations Supervisor has determined that this is a nuisance alarm. Perform appropriate actions to disable the annunciator using approved procedures.
Page 25 of 162
JPM: SO-05 NRC RO TITLE: Perform an RCS Flow Rate Determination JPM A.1.b
- Denotes a CRITICAL STEP JOB PERFORMANCE MEASURE SO-05 NRC RO JPM A.2 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:
The operators performance was evaluated against the standards contained in this JPM and is determined to be:
SATISFACTORY:
UNSATISFACTORY:
Page 26 of 162
JPM: SO-05 NRC RO TITLE: Perform an RCS Flow Rate Determination JPM A.1.b
- Denotes a CRITICAL STEP DOCUMENTATION SO-05 NRC RO JPM A.2 JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 20 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: ACO VISION ID: 141341 TASK DESCRIPTION Disable a nuisance annunciator.
KA NUMBER: 2.2.13 KA VALUES: RO 3.6 SRO 3.8 10CFR55.45 APPLICABILITY: 3
REFERENCES:
SO23-6-29, Operation of Annunciators and Indicators, Rev. 14 SO-23-15-53.A, 53A46, 2nd POINT HEATER LEVEL HI/LO, Rev. 9-1 AUTHOR: L. Zilli DATE: 02/24/05 OPERATIONS REVIEW: M. Jones DATE: 03/09/05 APPROVED BY: A. Hagemeyer DATE: 03/09/05 Page 27 of 162
JPM: SO-05 NRC RO TITLE: Perform an RCS Flow Rate Determination JPM A.1.b
- Denotes a CRITICAL STEP MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New - - -
1 Compared to SO23-6-29, Rev. 14 and LRZ 02/24/05 REV revised due to adding the alarm link location and new Compensatory Actions.
Page 28 of 162
JPM: SO-05 NRC RO TITLE: Perform an RCS Flow Rate Determination JPM A.1.b
- Denotes a CRITICAL STEP SET-UP NOTE: Provide the examinee with a copy of SO23-6-29, Operation of Annunciators and Indicators and SO23-15-53.A, 53A46 - 2nd POINT HEATER LEVEL HI/LO, when requested.
Page 29 of 162
JPM: SO-05 NRC RO JPM A.2 TITLE: Disable a Nuisance Annunciator
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)
NOTE: When located, provide the examinee with a copy of SO23-6-29, Operation of Annunciators and Indicators and a copy of SO23-15-53.A, 53A46 2nd Point Heater Level HI/LO.
1 Locate the Step in SO23-6-29 that Locates Step 6.3.4 in SO23-6-29. Start Time: ________
applies to this alarm.
2 Discuss the Compensatory Actions Identifies the Compensatory Actions for from the associated ARP with the 53A46 to monitor 2nd Point Heater levels at responsible operator. least twice per shift.
3* Disable the alarm inputs. Identifies alarm links 929 through 932 for Unit 2 per the ARP.
4* Identify location of links. Identifies location of links for 53A46 at 2L-040 on Panel 03F and describes sliding all four (4) links to the open position.
CUE: The annunciator inputs have been disabled.
TERMINATING CUE: Stop Time: ________
This JPM is complete.
Page 30 of 162
JPM: SO-05 NRC RO JPM A.2 TITLE: Disable a Nuisance Annunciator
- Denotes a CRITICAL STEP JPM CHECKLIST
- 1. The JPM is:
- a. X Supported by facilitys job task analysis.
- b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).
- c. X Designed as either SRO only, or RO/SRO.
- 2. Each JPM includes:
- a. X Initial conditions.
- b. X Initiating cues.
- c. X References, including associated procedures.
- d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.
- e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.
- f. X Statements describing important actions or observations that should be made by the Examinee.
- g. X Criteria for successful completion.
- h. X Identification of the critical steps and their associated performance standards.
- i. X Validated time limits (average time allowed for completion).
- j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.
COMPLETED BY: L. Zilli DATE: 2/24/05 Page 31 of 162
JPM: SO-05 NRC RO JPM A.2 TITLE: Disable a Nuisance Annunciator
- Denotes a CRITICAL STEP JPM INFORMATION SHEET JPM NUMBER SO-05 NRC RO JPM S-1 INITIAL PLANT CONDITIONS The reactor has just tripped from full power. The CRS has directed the crew to carry out the Standard Post Trip Actions and report.
TASK TO BE PERFORMED Perform the Control Operators portion of the Standard Post Trip Actions. Provide feedback to the Control Room Supervisor, as appropriate.
THIS IS A TIME CRITICAL JPM Page 32 of 162
JPM: SO-05 NRC RO JPM A.2 TITLE: Disable a Nuisance Annunciator
- Denotes a CRITICAL STEP JOB PERFORMANCE MEASURE SO-05 NRC RO JPM S-1 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:
The operators performance was evaluated against the standards contained in this JPM and is determined to be:
SATISFACTORY:
UNSATISFACTORY:
Page 33 of 162
JPM: SO-05 NRC RO JPM A.2 TITLE: Disable a Nuisance Annunciator
- Denotes a CRITICAL STEP DOCUMENTATION SO-05 NRC RO JPM S-1 JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 4 minutes TIME CRITICAL JPM: NO CRITICAL TIME: 10 minutes POSITION: CO TASK SYS ID: 192836 TASK DESCRIPTION Respond to a reactor trip by performing Standard Post Trip Actions.
KA NUMBER: 007 EA1.06 KA VALUES: RO 4.4 SRO 4.5 10CFR55.45 APPLICABILITY: 5 and 6
REFERENCES:
SO23-12-1, Standard Post Trip Actions, Rev. 19 AUTHOR: R. Whitehouse DATE: 09/02/04 OPERATIONS REVIEW: M. Jones DATE: 09/02/04 APPROVED BY: A. Hagemeyer DATE: 09/07/04 Page 34 of 162
JPM: SO-05 NRC RO JPM A.2 TITLE: Disable a Nuisance Annunciator
- Denotes a CRITICAL STEP MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New - - -
0-1 Modified Set-up page. RCW 09/16/04 N/A 0-2 Modified Initial Plant Conditions and RCW 09/28/04 MRN Task To Be Performed to indicate that the crew is performing the second pass through the SPTAs, and should feed information back to the CRS.
0-3 Compared to SO23-12-1, Rev. 19 with LRZ 02/24/05 AHH minor valve wording changes required.
Page 35 of 162
JPM: SO-05 NRC RO JPM A.2 TITLE: Disable a Nuisance Annunciator
- Denotes a CRITICAL STEP SET-UP Use IC-137 for the 2005 NRC Exam. Otherwise use any full power IC that has Train B CCW in service, as well as Charging Pump P-191 aligned to Train B, and perform the following:
Hang on OOS tag on P174.
Trip the Reactor.
Insert the following malfunctions:
- RD0602 and RD1302 (2 stuck CEAs on the trip).
- CV17A = FAILURE (P174 pump failure).
- CV17B = FAILURE (P175 pump failure).
Insert the following Overrides:
- 2HS-9242-1-CR58-L01 = OFF (P174 red light off).
- 2HS-9242-1-CR58-L02 = OFF (P174 green light off).
- 2HS-9242-1-CR58-L03 = OFF (P174 double brilliant green light off).
- 2HS-9242-1-CR58-L04 = OFF (P174 white light off).
- 2HS-9242-1-CR58-L04 = OFF (P174 white light off).
- 2HS-9242-1-CR58-S01 = OUT (P174 START pushbutton)
- 58A46 = NO_ALARM (P174 overcurrent annunciator).
Page 36 of 162
JPM: SO-05 NRC RO JPM S-1 TITLE: Perform the Control Operator actions of the Standard Post Trip Actions
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)
CUE: Perform Standard Post Trip Actions for Reactivity Control.
1 VERIFY Reactor Trip Circuit Breakers Observes REACTOR TRIP STATUS, Start Time: _______
(8) are open. 2UI-9157 green lights illuminated for reactor trip breakers.
2 VERIFY a maximum of one full length Observes CEA ROD BOTTOM CEA NOT fully inserted. INDICATION, 2ZI-9133, and or CEA Operator Module 2UI-9134 and determines that two full length CEAs are NOT fully inserted.
3 Initiate Emergency Boration. Determines that Emergency Boration is required.
4 VERIFY that at least one Charging Observes at least one Charging Pump START Pump is available. light is illuminated for 2P-191, and/or 2P-192 with proper discharge pressure displayed on 2PI-0212 and flow displayed on 2FI-0212.
5 OPEN 2HV-9247, Emergency Boration Opens 2HV-9247, Emergency Boration Block Block Valve. Valve.
6 START either BAMU Pump. Determines that Boric Acid Makeup Pump, 2P-174 (E) or Boric Acid Makeup Pump, 2P-175 (W) are both not available.
7 INITIATE Emergency Boration using Goes to RNO column to initiate Emergency Gravity Feed. Boration using Gravity Feed.
Page 37 of 162
JPM: SO-05 NRC RO JPM S-1 TITLE: Perform the Control Operator actions of the Standard Post Trip Actions
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 8 CLOSE 2HV-9247, Emergency Closes 2HV-9247, Emergency Boration Block Boration Block Valve. Valve.
9* OPEN 2HV-9240, BAMU Tank 2T-071 Opens 2HV-9240, BAMU Tank 2T-071 Gravity Feed Valve. Gravity Feed Valve.
10* OPEN 2HV-9235, BAMU Tank 2T-072 Opens 2HV-9235, BAMU Tank 2T-072 Gravity Feed Valve. Gravity Feed Valve.
11* CLOSE 2LV-0227B, VCT Tank Outlet Pushes the MANUAL pushbutton, and closes Block Valve. 2LV-0227B, VCT Tank Outlet Block Valve.
12 ENSURE charging flow greater than 40 Observes charging flow greater than 40 gpm gpm. on 2FI-0212.
TERMINATING CUE: Stop Time: _______
This JPM is complete.
Page 38 of 162
JPM: SO-05 NRC RO JPM S-1 TITLE: Perform the Control Operator actions of the Standar
- Denotes a CRITICAL STEP JPM CHECKLIST
- 1. The JPM is:
- a. X Supported by facilitys job task analysis.
- b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).
- c. X Designed as either SRO only, or RO/SRO.
- 2. Each JPM includes:
- a. X Initial conditions.
- b. X Initiating cues.
- c. X References, including associated procedures.
- d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.
- e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.
- f. X Statements describing important actions or observations that should be made by the Examinee.
- g. X Criteria for successful completion.
- h. X Identification of the critical steps and their associated performance standards.
- i. X Validated time limits (average time allowed for completion).
- j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.
COMPLETED BY: L. Zilli DATE: 02/24/05 JPM INFORMATION SHEET JPM NUMBER Page 39 of 162
JPM: SO-05 NRC RO JPM S-1 TITLE: Perform the Control Operator actions of the Standar
- Denotes a CRITICAL STEP SO-05 NRC RO JPM S-1 INITIAL PLANT CONDITIONS The reactor has just tripped from full power. The CRS has directed the crew to carry out the Standard Post Trip Actions and report.
TASK TO BE PERFORMED Perform the Control Operators portion of the Standard Post Trip Actions. Provide feedback to the Control Room Supervisor, as appropriate.
THIS IS A TIME CRITICAL JPM Page 40 of 162
JPM: SO-05 NRC RO JPM S-1 TITLE: Perform the Control Operator actions of the Standar
- Denotes a CRITICAL STEP JOB PERFORMANCE MEASURE SO-05 NRC RO JPM S-1 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:
The operators performance was evaluated against the standards contained in this JPM and is determined to be:
SATISFACTORY:
UNSATISFACTORY:
Page 41 of 162
JPM: SO-05 NRC RO JPM S-1 TITLE: Perform the Control Operator actions of the Standar
- Denotes a CRITICAL STEP DOCUMENTATION SO-05 NRC RO JPM S-1 JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 4 minutes TIME CRITICAL JPM: NO CRITICAL TIME: 10 minutes POSITION: CO TASK SYS ID: 192836 TASK DESCRIPTION Respond to a reactor trip by performing Standard Post Trip Actions.
KA NUMBER: 007 EA1.06 KA VALUES: RO 4.4 SRO 4.5 10CFR55.45 APPLICABILITY: 5 and 6
REFERENCES:
SO23-12-1, Standard Post Trip Actions, Rev. 19 AUTHOR: R. Whitehouse DATE: 09/02/04 OPERATIONS REVIEW: M. Jones DATE: 09/02/04 APPROVED BY: A. Hagemeyer DATE: 09/07/04 Page 42 of 162
JPM: SO-05 NRC RO JPM S-1 TITLE: Perform the Control Operator actions of the Standar
- Denotes a CRITICAL STEP MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New - - -
0-1 Modified Set-up page. RCW 09/16/04 N/A 0-2 Modified Initial Plant Conditions and RCW 09/28/04 MRN Task To Be Performed to indicate that the crew is performing the second pass through the SPTAs, and should feed information back to the CRS.
0-3 Compared to SO23-12-1, Rev. 19 with LRZ 02/24/05 AHH minor valve wording changes required.
Page 43 of 162
JPM: SO-05 NRC RO JPM S-1 TITLE: Perform the Control Operator actions of the Standar
- Denotes a CRITICAL STEP SET-UP Use IC-137 for the 2005 NRC Exam. Otherwise use any full power IC that has Train B CCW in service, as well as Charging Pump P-191 aligned to Train B, and perform the following:
Hang on OOS tag on P174.
Trip the Reactor.
Insert the following malfunctions:
- RD0602 and RD1302 (2 stuck CEAs on the trip).
- CV17A = FAILURE (P174 pump failure).
- CV17B = FAILURE (P175 pump failure).
Insert the following Overrides:
- 2HS-9242-1-CR58-L01 = OFF (P174 red light off).
- 2HS-9242-1-CR58-L02 = OFF (P174 green light off).
- 2HS-9242-1-CR58-L03 = OFF (P174 double brilliant green light off).
- 2HS-9242-1-CR58-L04 = OFF (P174 white light off).
- 2HS-9242-1-CR58-L04 = OFF (P174 white light off).
- 2HS-9242-1-CR58-S01 = OUT (P174 START pushbutton)
- 58A46 = NO_ALARM (P174 overcurrent annunciator).
Page 44 of 162
JPM: SO-05 NRC RO JPM S-1 TITLE: Perform the Control Operator actions of the Standard Post Trip Actions
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)
CUE: Perform Standard Post Trip Actions for Reactivity Control.
1 VERIFY Reactor Trip Circuit Breakers Observes REACTOR TRIP STATUS, Start Time: _______
(8) are open. 2UI-9157 green lights illuminated for reactor trip breakers.
2 VERIFY a maximum of one full length Observes CEA ROD BOTTOM CEA NOT fully inserted. INDICATION, 2ZI-9133, and or CEA Operator Module 2UI-9134 and determines that two full length CEAs are NOT fully inserted.
3 Initiate Emergency Boration. Determines that Emergency Boration is required.
4 VERIFY that at least one Charging Observes at least one Charging Pump START Pump is available. light is illuminated for 2P-191, and/or 2P-192 with proper discharge pressure displayed on 2PI-0212 and flow displayed on 2FI-0212.
5 OPEN 2HV-9247, Emergency Boration Opens 2HV-9247, Emergency Boration Block Block Valve. Valve.
6 START either BAMU Pump. Determines that Boric Acid Makeup Pump, 2P-174 (E) or Boric Acid Makeup Pump, 2P-175 (W) are both not available.
7 INITIATE Emergency Boration using Goes to RNO column to initiate Emergency Gravity Feed. Boration using Gravity Feed.
Page 45 of 162
JPM: SO-05 NRC RO JPM S-1 TITLE: Perform the Control Operator actions of the Standard Post Trip Actions
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 8 CLOSE 2HV-9247, Emergency Closes 2HV-9247, Emergency Boration Block Boration Block Valve. Valve.
9* OPEN 2HV-9240, BAMU Tank 2T-071 Opens 2HV-9240, BAMU Tank 2T-071 Gravity Feed Valve. Gravity Feed Valve.
10* OPEN 2HV-9235, BAMU Tank 2T-072 Opens 2HV-9235, BAMU Tank 2T-072 Gravity Feed Valve. Gravity Feed Valve.
11* CLOSE 2LV-0227B, VCT Tank Outlet Pushes the MANUAL pushbutton, and closes Block Valve. 2LV-0227B, VCT Tank Outlet Block Valve.
12 ENSURE charging flow greater than 40 Observes charging flow greater than 40 gpm gpm. on 2FI-0212.
TERMINATING CUE: Stop Time: _______
This JPM is complete.
Page 46 of 162
JPM: SO-05 NRC RO JPM S-1 TITLE: Perform the Control Operator actions of the Standar
- Denotes a CRITICAL STEP JPM CHECKLIST
- 1. The JPM is:
- a. X Supported by facilitys job task analysis.
- b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).
- c. X Designed as either SRO only, or RO/SRO.
- 2. Each JPM includes:
- a. X Initial conditions.
- b. X Initiating cues.
- c. X References, including associated procedures.
- d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.
- e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.
- f. X Statements describing important actions or observations that should be made by the Examinee.
- g. X Criteria for successful completion.
- h. X Identification of the critical steps and their associated performance standards.
- i. X Validated time limits (average time allowed for completion).
- j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.
COMPLETED BY: L. Zilli DATE: 02/24/05 JPM INFORMATION SHEET JPM NUMBER Page 47 of 162
JPM: SO-05 NRC RO JPM S-1 TITLE: Perform the Control Operator actions of the Standar
All systems are OPERABLE.
Maintenance is scheduled for the Unit Auxiliary Transformer feeder breaker to 6.9 kV Bus 2A01.
TASK TO BE PERFORMED Manually transfer 6.9 kV Bus 2A01 from the Unit Auxiliary Transformer (2XU2) to the Reserve Auxiliary Transformer (2XR3).
Page 48 of 162
JPM: SO-05 NRC RO JPM S-1 TITLE: Perform the Control Operator actions of the Standar
- Denotes a CRITICAL STEP JOB PERFORMANCE MEASURE SO-05 NRC RO JPM S-2 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:
The operators performance was evaluated against the standards contained in this JPM and is determined to be:
SATISFACTORY:
UNSATISFACTORY:
Page 49 of 162
JPM: SO-05 NRC RO JPM S-1 TITLE: Perform the Control Operator actions of the Standar
- Denotes a CRITICAL STEP DOCUMENTATION SO-05 NRC RO JPM S-2 JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 5 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: ACO TASK SYS ID: 186193 TASK DESCRIPTION Manually transfer a 6.9 kV bus from the Unit Auxiliary Transformer to the Reserve Auxiliary Transformer.
KA NUMBER: 062 A4.07 KA VALUES: RO 3.1 SRO 3.1 10CFR55.45 APPLICABILITY: 2, 6
REFERENCES:
SO23-6-1, Transferring 6.9 kV Buses, Rev. 6 AUTHOR: S. Hollinger DATE: 09/16/92 OPERATIONS REVIEW: J. Salinger DATE: 10/08/93 APPROVED BY: M. Kirby DATE: 10/14/93 Page 50 of 162
JPM: SO-05 NRC RO JPM S-1 TITLE: Perform the Control Operator actions of the Standar
- Denotes a CRITICAL STEP MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 1 New format. SW 07/07/93 MJK 1-1 Changed setup page; changed HJW 03/22/94 N/A estimated time from 6 to 5 minutes based on history; minor editorial changes to standards for clarity.
1-2 Compared against SO23-6-1, TCN 3-4 HJW 09/21/94 N/A with no changes required.
1-3 Compared against SO23-6-1, TCN 3-4 RCW 09/09/98 N/A with no changes required.
1-4 Compared against SO23-6-1, TCN 4-1 JJM 10/01/99 WLL with no changes required. Deleted two cues that are not necessary when JPM is performed on the simulator.
Updated KA designation and changed old task number to VISION SYS ID.
1-5 Compared against SO23-6-1, Revision JJM 09/14/00 WLL 5 and reordered JPM steps to match the wording of the procedure.
1-6 Compared against SO23-6-1, Revision LRZ 05/11/01 WLL 5 and corrected nomenclature for procedure to JPM consistency.
1-7 Compared against SO23-6-1, Revision JJM 07/25/02 N/A 6 with no changes required.
1-8 Updated Vision Task ID. RCW 08/09/04 AHH 1-9 Compared against SO23-6-1, Revision LRZ 02/15/05 AHH 6 with no changes required.
Page 51 of 162
JPM: SO-05 NRC RO JPM S-1 TITLE: Perform the Control Operator actions of the Standar
- Denotes a CRITICAL STEP SET-UP Use any at power IC.
NOTE: Provide the examinee with a copy of SO23-6-1, Transferring 6.9 kV Buses when identified.
Page 52 of 162
JPM: SO-05 NRC RO JPM S-2 TITLE: Manually Transfer 6.9kV Bus 2A01 from the UAT to the RAT
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 1 Locate procedure SO23-6-1, Locates a current copy of SO23-6-1, Start Time: _______
Transferring 6.9kV Buses and review Transferring 6.9kV Buses and reviews Limitations and Specifics LS-1.3. Limitations and Specifics LS-1.3.
NOTE: When the correct procedure is located provide a copy to the examinee.
2 VERIFY ENERGIZED 2XR3 Observes 2XR3 Transformer is energized by Transformer. visually checking the alignment of power to 2XR3.
3 ENSURE OPEN 3A0105 Res Aux Ensures 3A0105 Res Aux XFMR 2XR3 FDR XFMR 2XR3 FDR Breaker. Breaker open.
CUE: Unit 3 bus tie breaker is open (3A01 is not being fed from 2XR3).
4* PLACE IN MANUAL 2HS-1613B Res Places 2HS-1613B, Res Aux Xfmr 2XR3 Aux XFMR 2XR3 FDR Bkr 2A0102 FDR Bkr 2A0102 Mode Selector switch to Mode Selector. MANUAL.
5* PLACE IN SERVICE 2/3HS-1627A Places key operated 2/3HS-1627A NON-ESF NON-1E Sync Master CNTRL. SYNC MASTER CNTRL TO ON.
6* DEPRESS 2A0102 Res Aux XFMR Depresses SYNC pushbutton on 2HS-1613A, 2XR3 FDR Breaker SYNC pushbutton Res Aux Xfmr 2XR3 FDR Breaker 2A0102.
to place the synchronizing circuit in service.
7 Verify Breaker SYNC light Observes SYNC light on 2HS-1613A, Res ILLUMINATED. Aux Xfmr 2XR3 FDR Breaker 2A0102 is illuminated.
Page 53 of 162
JPM: SO-05 NRC RO JPM S-2 TITLE: Manually Transfer 6.9kV Bus 2A01 from the UAT to the RAT
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 8 Verify SYNC IN MODE light Observes SYNC IN MODE light on the Non-ILLUMINATED. ESF Sync Master switch is illuminated.
9 Verify SYNC RELAYS TROUBLE Observes SYNC RELAYS TROUBLE light light EXTINGUISHED. on the Non-ESF Sync Master switch is extinguished.
10 Verify INCOMING and RUNNING Observes meters 2/3EI-1627A, Running voltage and frequencies matched. Volts, and 2/3EI-1627B, Incoming Volts; 2/3SI-1627C, Running Hertz, and 2/3SI-1627D, Incoming Hertz to ensure they are matched.
11 Verify Synchroscope moves to straight Observes Synchroscope 2/3SI-1627A moves up (12 oclock) position. to straight up (12 oclock) position.
12* CLOSE 2A0102, Res Aux XFMR Depresses CLOSE pushbutton 2HS-1613A, 2XR3 FDR Breaker, paralleling 2XU2 Res Aux Xfmr 2XR3 FDR Breaker 2A0102.
and 2XR3.
13 VERIFY OPEN 2A0104, Unit Aux Observes Trip light illuminated on 2HS-1614, XFMR 2XU2 FDR Breaker. Unit Aux Xfmr 2XU2 FDR Breaker 2A0104.
14 DEPRESS 2A0102 Res Aux XFMR Depresses 2HS-1613A Res Aux XFMR 2XR3 2XR3 FDR Breaker SYNC pushbutton FDR Breaker 2A0102 SYNC pushbutton.
to remove the synchronizing circuit from service.
Page 54 of 162
JPM: SO-05 NRC RO JPM S-2 TITLE: Manually Transfer 6.9kV Bus 2A01 from the UAT to the RAT
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 15 PLACE in OFF 2/3HS-1627A. Places key operated Non-ESF Sync Master switch HS-1627A to OFF.
TERMINATING CUE: Stop Time: _______
This JPM is complete.
Page 55 of 162
JPM: SO-05 NRC RO TITLE: Manually Transfer 6.9kV Bus 2A01 from the JPM S-2 UAT to the RAT
- Denotes a CRITICAL STEP JPM CHECKLIST
- 1. The JPM is:
- a. X Supported by facilitys job task analysis.
- b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).
- c. X Designed as either SRO only, or RO/SRO.
- 2. Each JPM includes:
- a. X Initial conditions.
- b. X Initiating cues.
- c. X References, including associated procedures.
- d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.
- e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.
- f. X Statements describing important actions or observations that should be made by the Examinee.
- g. X Criteria for successful completion.
- h. X Identification of the critical steps and their associated performance standards.
- i. X Validated time limits (average time allowed for completion).
- j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.
COMPLETED BY: L. Zilli DATE: 02/15/05 JPM INFORMATION SHEET Page 56 of 162
JPM: SO-05 NRC RO TITLE: Manually Transfer 6.9kV Bus 2A01 from the JPM S-2 UAT to the RAT
- Denotes a CRITICAL STEP JPM NUMBER SO-05 NRC RO JPM S-3 INITIAL PLANT CONDITIONS Unit 2 was operating at 100% power when a Steam Line break occurred inside Containment.
Containment Spray Actuation System (CSAS), failed to automatically actuate. Up to this point, all attempts to manually actuate CSAS have been unsuccessful. Containment pressure is rising.
TASK TO BE PERFORMED The Control Room Supervisor directs you to perform Floating Step 12, Monitor Containment Pressure, of SO23-12-11, EOI Supporting Attachments.
Page 57 of 162
JPM: SO-05 NRC RO TITLE: Manually Transfer 6.9kV Bus 2A01 from the JPM S-2 UAT to the RAT
- Denotes a CRITICAL STEP JOB PERFORMANCE MEASURE SO-05 NRC RO JPM S-3 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:
The operators performance was evaluated against the standards contained in this JPM and is determined to be:
SATISFACTORY:
UNSATISFACTORY:
Page 58 of 162
JPM: SO-05 NRC RO TITLE: Manually Transfer 6.9kV Bus 2A01 from the JPM S-2 UAT to the RAT
- Denotes a CRITICAL STEP DOCUMENTATION SO-05 NRC RO JPM S-3 JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 10 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CO TASK SYS ID: 184570 TASK DESCRIPTION Initiate Containment Temperature and Pressure Control Recovery by CSAS.
KA NUMBER: 009 EA1.07 KA VALUES: RO 3.7 SRO 3.9 10CFR55.45 APPLICABILITY: 5, 6
REFERENCES:
SO23-12-11, EOI Supporting Attachments, FS-12, Monitor Containment Pressure, Revision 2 AUTHOR: L. Zilli DATE: 02/15/05 OPERATIONS REVIEW: M. Jones DATE: 03/09/05 APPROVED BY: A. Hagemeyer DATE: 03/09/05 Page 59 of 162
JPM: SO-05 NRC RO TITLE: Manually Transfer 6.9kV Bus 2A01 from the JPM S-2 UAT to the RAT
- Denotes a CRITICAL STEP MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 1 Reviewed SO23-12-5, Rev. 16 and LRZ 07/05/00 WLL modified as required.
1-1 Compared against SO23-12-5, Rev. 16 LRZ 08/29/01 WLL with no changes required.
2 Revised to reflect new procedure and LRZ 02/15/05 REV Floating Step number SO23-12-11, EOI Supporting Attachments, Rev. 2, Floating Step 12. Added steps required by procedure revision. New VISION ID.
Page 60 of 162
JPM: SO-05 NRC RO TITLE: Manually Transfer 6.9kV Bus 2A01 from the JPM S-2 UAT to the RAT
Enter malfunctions to disable CSAS automatic and manual actuation of Containment Spray and Containment Spray Pump P012 to start.
Insert the malfunction for a Steam Line Break inside Containment and allow the Simulator to run until Containment pressure reaches approximately 15 psig. Choose the severity such that pressure is rising about 1 psig/min then freeze the simulator.
MS03A @ 10% for ~1 minute then 0.9%
RP01M - CS Pump P012 Failure to Start RPL104 = Fail energized (ON) = True for the following items:
Schematic pages for CSAS = RPL104 CSAS = RP_CSAS_MI1_Fail RP_CSAS_MI2_Fail RP_CSAS_MI3_Fail RP_CSAS_MI4_Fail RP_CSAS_SSR1_Fail RP_CSAS_SSR2_Fail RP_CSAS_SSR3_Fail RP_CSAS_SSR4_Fail NOTE: Provide the Examinee with a copy of SO23-12-11, EOI Supporting Attachments, Floating Step 12, Monitor Containment Pressure.
NOTE: Ensure DAS alarms are reset.
Page 61 of 162
JPM: SO-05 NRC RO JPM S-3 TITLE: Initiate Containment Temperature and Pressure Control Recovery by CSAS
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)
NOTE: Provide the Examinee with a copy of SO23-12-11, EOI Supporting Attachments, Floating Step 12, Monitor Containment Pressure. Ensure the DAS alarms are reset.
1 VERIFY Containment pressure less Verifies Containment pressure Narrow Range Time Start: _______
than 3.4 psig. indications 2PI-0351-1, 2, 3, 4 or Wide Range indications 2PI-0352-1, 2, 3, 4, greater than 3.4 psig and enters the RNO.
2 ENSURE SIAS actuated. Verifies SIAS actuated by observing annunciators 57A01 SIAS TRAIN A ACTUATION and 57B01 SIAS TRAIN B ACTUATION.
NOTE: The Examinee may choose to start Containment Spray Pump 2P-012 at this point or later in the Floating Step.
3 Recognizes that Containment Spray Starts Containment Spray Pump P-012 by Pump 2P-012 is not running. depressing the START pushbutton, 2HS-9395-1.
4 ENSURE CCAS actuated. Verifies CCAS actuated by observing annunciators 57A07 CCAS TRAIN A ACTUATION and 57B07 CCAS TRAIN B ACTUATION.
5 ENSURE CRIS actuated. Verifies CRIS actuated by observing annunciator 60B07 CRIS ACTUATION.
Page 62 of 162
JPM: SO-05 NRC RO JPM S-3 TITLE: Initiate Containment Temperature and Pressure Control Recovery by CSAS
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 6 ENSURE CIAS actuated. Verifies CIAS actuated by observing annunciators 57A02 CIAS TRAIN A ACTUATION and CIAS TRAIN B ACTUATION and/or CFMS page 342.
CUE: If CFMS page 342 is accessed, state all CIAS valves are closed.
7 VERIFY Containment Area Radiation Verifies Containment Area Radiation Monitors - NOT alarming or trending to Monitors are not alarming or trending to alarm alarm. using the DAS Home Page or DAS Containment page.
8 VERIFY Containment High Range Area Verifies Containment High Range Area Radiation Monitors - reading less than Radiation Monitors reading less than 40R/hr 40R/hr. using the DAS Home Page or DAS Containment page.
9 VERIFY Containment pressure less Verifies Containment Pressure Wide Range than 14 psig. indications 2PI-0352-1, 2, 3, or 4 greater than 14 psig and enters the RNO.
Page 63 of 162
JPM: SO-05 NRC RO JPM S-3 TITLE: Initiate Containment Temperature and Pressure Control Recovery by CSAS
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 10 ENSURE CSAS actuated. Observes CSAS not actuated:
- Annunciators 57A03 CSAS TRAIN A ACTUATION and 57B03 CSAS TRAIN B ACTUATION.
- Containment Spray Pump 2P012, 2HS-9395-1, did not start.
- 2HV-9367, Containment Spray Header 1 Control Valve, did not open.
- 2HV-9368, Containment Spray Header 2 Control Valve, did not open.
11 MANUALLY actuate CSAS. Attempts to actuate CSAS by pressing at least any two of four CSAS initiation pushbuttons, 2HS-9139-1, 2, 3, 4.
CUE: An ARO has been sent to L-034 and L-035 and CSAS actuation has been unsuccessful..
NOTE: The Containment Spray Pump 2P012 may already have been started in Step 3.
12* START Containment Spray Pump Starts Containment Spray Pump P-012 by P-012. depressing the START pushbutton, 2HS-9395-1.
Page 64 of 162
JPM: SO-05 NRC RO JPM S-3 TITLE: Initiate Containment Temperature and Pressure Control Recovery by CSAS
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 13 VERIFY Containment Spray Pump Verifies Containment Spray Pump P-012 has P-012 started. started by observing:
- Red START light illuminates on 2HS-9395-1.
- Pump amps at a normal no flow value of about 25 amps on 2HS-9395-1.
- Discharge pressure rises to approximately 250 psig on 2PI-0303-1.
14* OPEN 2HV-9367, Containment Spray Opens 2HV-9367, CNTMT Spray Header 1 Header Isolation Valve. Control Valve, by depressing and holding the JOG OPEN pushbutton and observing the red JOG OPEN light illuminates and the green JOG CLOSED light extinguishes.
15 VERIFY Containment Spray Pump Verifies Containment Spray Pump P-013 has P-013 started. started by observing:
- Red START light illuminates on 2HS-9396-2.
- Pump amps at a normal no flow value of about 25 amps on 2HS-9396-2.
- Discharge pressure is approximately 250 psig on 2PI-0303-2.
16* OPEN 2HV-9368, Containment Spray Opens 2HV-9368, CNTMT Spray Header 2 Header Isolation Valve. Control Valve by depressing and holding the JOG OPEN pushbutton and observing the red JOG OPEN light illuminates and the green Page 65 of 162
JPM: SO-05 NRC RO JPM S-3 TITLE: Initiate Containment Temperature and Pressure Control Recovery by CSAS
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)
JOG CLOSED light extinguishes.
17 CLOSE CCW to/from Letdown Heat Closes CCW CLA LTDN HX 2E062 Exchanger Valves for Train A and Supply/Return Valve 2HV-6293B/A..
Train B.
18 ENSURE each Containment Spray Verifies Containment Spray flow is header flow - greater than 1625 GPM. satisfactory by observing:
- 2FI-0338-1, Train A Containment Spray Flow, greater than 1625 gpm.
- 2FI-0348-2, Train B Containment Spray Flow, greater than 1625 gpm.
TERMINATING CUE: Stop Time: _______
This JPM is complete.
Page 66 of 162
JPM: SO-05 NRC RO JPM S-3 TITLE: Initiate Containment Temperature and Pressure Contr
- Denotes a CRITICAL STEP JPM CHECKLIST
- 1. The JPM is:
- a. X Supported by facilitys job task analysis.
- b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).
- c. X Designed as either SRO only, or RO/SRO.
- 2. Each JPM includes:
- a. X Initial conditions.
- b. X Initiating cues.
- c. X References, including associated procedures.
- d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.
- e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.
- f. X Statements describing important actions or observations that should be made by the Examinee.
- g. X Criteria for successful completion.
- h. X Identification of the critical steps and their associated performance standards.
- i. X Validated time limits (average time allowed for completion).
- j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.
COMPLETED BY: L. Zilli DATE: 02/26/05 JPM INFORMATION SHEET JPM NUMBER Page 67 of 162
JPM: SO-05 NRC RO JPM S-3 TITLE: Initiate Containment Temperature and Pressure Contr
- Denotes a CRITICAL STEP SO-05 NRC RO JPM S-4 INITIAL PLANT CONDITIONS A small Steam Generator Tube leak has developed in SG 2E-088. The leak rate is approximately 32 gallons per day (gpd) and increasing very slowly. On the DAS LEAK RATE page the Hi-Hi alarm is present for Condenser Air Ejector WRGM, RE-7870.
The Shift Manager has directed that RE-7870s Hi-Hi Alarm setpoint be raised to a new value of 60 gpd in order to alert the crew if the leak is trending to 75 gpd.
TASK TO BE PERFORMED Reset the Hi-Hi Alarm setpoint on the DAS LEAK RATE page for Condenser Air Ejector Wide Range Gas Monitor, RE-7870 to a new value of 60 gpd per SO23-3-2.36, Radiation Monitoring Data Acquisition System (DAS).
Page 68 of 162
JPM: SO-05 NRC RO JPM S-3 TITLE: Initiate Containment Temperature and Pressure Contr
- Denotes a CRITICAL STEP JOB PERFORMANCE MEASURE SO-05 NRC RO JPM S-4 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:
The operators performance was evaluated against the standards contained in this JPM and is determined to be:
SATISFACTORY:
UNSATISFACTORY:
Page 69 of 162
JPM: SO-05 NRC RO JPM S-3 TITLE: Initiate Containment Temperature and Pressure Contr
- Denotes a CRITICAL STEP DOCUMENTATION SO-05 NRC RO JPM S-4 JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 5 minutes TIME CRITICAL JPM: N/A CRITICAL TIME: N/A POSITION: RO VISION ID: 191191 TASK DESCRIPTION Verify, acknowledge, and bypass alarms using DAS.
KA NUMBER: 073 A4.02 KA VALUES: RO 3.7 SRO 3.7 10CFR55.45 APPLICABILITY: 9
REFERENCES:
SO23-3-2.36, Radiation Monitor Data Acquisition System (DAS), Rev. 3-2 AUTHOR: J. Marron DATE: 02/18/03 OPERATIONS REVIEW: P. Sandberg DATE: 02/19/03 APPROVED BY: S. Whitley DATE: 02/19/03 Page 70 of 162
JPM: SO-05 NRC RO JPM S-3 TITLE: Initiate Containment Temperature and Pressure Contr
- Denotes a CRITICAL STEP MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New JPM 0-1 Compared against SO23-3-2.36, LRZ 02/24/05 AHH Revision 3-2, with no changes required. New VISION ID.
Page 71 of 162
JPM: SO-05 NRC RO JPM S-3 TITLE: Initiate Containment Temperature and Pressure Contr
From any full power initial condition, insert malfunction SG01A at a severity level of 0.03.
When the leak rate increases to 20 gpd, verify that the Condenser Air Ejector WRGM, RE-7870 LEAKRATE page indicates the Hi-Hi Alarm and lower the leakrate to 0.001 (32 gpd).
Place the simulator in FREEZE until the examinee is ready to proceed with the task then place the simulator in RUN.
NOTE: Provide the Examinee with a copy of SO23-3-2.36.
CAUTION: Ensure the DAS Home Page is being displayed on the flat screen monitor on the Control Operators Desk.
Ensure RE-7870 alarm is reset to 30 gpd.
Page 72 of 162
JPM: SO-05 NRC RO JPM S-4 TITLE: Changing the Alarm Setpoint on the DAS LEAK RATE Page
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)
CAUTION: ENSURE the DAS Home Page is being displayed on the flat screen monitor on the Control Operators Desk. ENSURE RE-7870 alarm is reset to 30 gpd.
1 CONFIRM that the setpoint has been Determines from the Examiner the status of Start Time: _______
changed in RE-7870 Radiation Monitor. the setpoint change in Condenser Air Ejector WRGM, RE-7870.
CUE: The setpoint has been changed in the Condenser Air Ejector Radiation WRGM, RE-7870 by Radiation Monitoring I&C.
2 GO TO the DAS Home Page. Observes that the DAS Home Page is currently being displayed.
3 SELECT the Unit 2 LEAK RATE Uses the mouse to click on the U2 LEAK Button at the top of the display screen. RATE button at the top of the Home Page.
4 NAVIGATE to the applicable monitor Determines the correct Leak Rate Page is Leak Rate Page. displayed by its title, RE-7870.
5* DOUBLE CLICK the Hi-Hi Alarm Double clicks the Hi-Hi Alarm Setpoint Setpoint parameter to cause the keypad parameter and causes the keypad pop-up pop-up window to appear. window to appear on the screen.
6* ENTER the new value in the keypad Enters the new value for the Hi-Hi Alarm pop-up window by clicking on the Setpoint in the keypad pop-up window by numerals 6 then 0. clicking on the numerals 6 then 0 or type in the new setpoint using the keyboard.
Page 73 of 162
JPM: SO-05 NRC RO JPM S-4 TITLE: Changing the Alarm Setpoint on the DAS LEAK RATE Page
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 7* SELECT the ENTER button. Selects the ENTER button by clicking on the ENTER button on the keypad pop-up window or depresses the ENTER key on the keyboard.
8* SELECT OK to confirm. Selects OK to confirm by clicking on the OK button on the keypad pop-up window or depresses the ENTER key on the keyboard.
9 Observe that the new value of the Hi-Hi Observes that the value of the Hi-Hi Alarm Alarm Setpoint is now being displayed. Setpoint has been set to 60.
CUE: Another operator will perform the UPDATE SCADA task.
TERMINATING CUE: Stop Time: _______
This JPM is complete.
Page 74 of 162
JPM: SO-05 NRC RO TITLE: Changing the Alarm Setpoint on the DAS LEAK JPM S-4 RATE Page
- Denotes a CRITICAL STEP JPM CHECKLIST
- 1. The JPM is:
- a. X Supported by facilitys job task analysis.
- b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).
- c. X Designed as either SRO only, or RO/SRO.
- 2. Each JPM includes:
- a. X Initial conditions.
- b. X Initiating cues.
- c. X References, including associated procedures.
- d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.
- e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.
- f. X Statements describing important actions or observations that should be made by the Examinee.
- g. X Criteria for successful completion.
- h. X Identification of the critical steps and their associated performance standards.
- i. X Validated time limits (average time allowed for completion).
- j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.
COMPLETED BY: L. Zilli DATE: 02/24/05 JPM INFORMATION SHEET Page 75 of 162
JPM: SO-05 NRC RO TITLE: Changing the Alarm Setpoint on the DAS LEAK JPM S-4 RATE Page
- Denotes a CRITICAL STEP JPM NUMBER SONGS-05 NRC RO JPM S-5 INITIAL PLANT CONDITIONS The plant is in Mode 4 (~365 psia and 255°F) on the Shutdown Cooling System when a Loss of Offsite Power occurs. Vital Bus 2A06 did not transfer due to a bus fault. The running Shutdown Cooling Pump on Train A has tripped on an overcurrent/ground. RCS level is stable (NOT lowering).
Prior to the loss of offsite power, SBCS was in service assisting with the cooldown. The Steam Generator Pressure Channels in use were 2PI-1023A4 for E088 and 2PI-1013A4 for E089.
TASK TO BE PERFORMED The Control Room Supervisor directs you to perform Attachment 5, Alternate Reactor Core Cooling, Step 2.1 per SO23-13-15, Loss or Shutdown Cooling System.
The CRS also directs you to maximize RCS heat removal with the Steam Generators in order to promote natural circulation.
Page 76 of 162
JPM: SO-05 NRC RO TITLE: Changing the Alarm Setpoint on the DAS LEAK JPM S-4 RATE Page
- Denotes a CRITICAL STEP JOB PERFORMANCE MEASURE SO-05 NRC RO JPM S-5 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:
The operators performance was evaluated against the standards contained in this JPM and is determined to be:
SATISFACTORY:
UNSATISFACTORY:
Page 77 of 162
JPM: SO-05 NRC RO TITLE: Changing the Alarm Setpoint on the DAS LEAK JPM S-4 RATE Page
- Denotes a CRITICAL STEP DOCUMENTATION SO-05 NRC RO JPM S-5 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 10 minutes TIME CRITICAL JPM: N/A CRITICAL TIME:
POSITION: ACO VISION ID: 188158 TASK DESCRIPTION Respond to a Loss of Shutdown Cooling.
KA NUMBER: 025-AA1.03 KA VALUES: RO 3.4 SRO 3.3 10CFR55.45 APPLICABILITY: 6, 7
REFERENCES:
SO23-13-15, Loss of Shutdown Cooling, Attachment 5, Alternate Reactor Core Cooling, Rev. 15 AUTHOR: L. Zilli DATE: 02/15/05 OPERATIONS REVIEW: M. Jones DATE: 03/09/05 APPROVED BY: A. Hagemeyer DATE: 03/09/05 Page 78 of 162
JPM: SO-05 NRC RO TITLE: Changing the Alarm Setpoint on the DAS LEAK JPM S-4 RATE Page
- Denotes a CRITICAL STEP MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New Page 79 of 162
JPM: SO-05 NRC RO TITLE: Changing the Alarm Setpoint on the DAS LEAK JPM S-4 RATE Page
- Denotes a CRITICAL STEP SET-UP Use IC #123 for the 2005 NRC Exam.
Obtain and insert the following Control Room keys:
- 13, 14, 15, and 19 for Train A LPSI
- 28, 29, 30, and 34 for Train B LPSI
- 21 and 22 for Train A SIT
- 35 and 36 for Train B SIT
- 38 for Train A CPC Bypass
- 42 for Train B CPC Bypass
- 46 for Train C CPC Bypass
- 50 for Train D CPC Bypass Perform the following if using Base IC #2:
Insert the following:
Malfunction EC08A - LPSI P015 Fault Malfunction ED03B - 2A06 Bus Fault Malfunction PG24 - Loss of Edison Grid Malfunctions SG03A/B/C/E/F/G - SG Pressure Instrument failure to 600 psia Perform the following:
Close the Main Steam Isolation Valves Start CCW Pump P025 NOTE: Provide the Examinee with a copy of SO23-13-15, Attachment 5, Alternate Reactor Core Cooling.
NOTE: The Machine Operator will setup the PMS monitor at the CO desk with the Natural Circulation display and the PMS monitor on the other side of the CO desk with the Shutdown Cooling System display.
Examiner NOTE: In order to establish the criteria for entry into this scenario an IC with Shutdown Cooling in service was used. In that IC, Steam Generator pressure indications (3 of 4) are artificially set higher than the MSIS setpoint to prevent inadvertent MSIS. This is a standard practice in the Control Room.
Identify the indication on each SG that is reading the actual value of SG pressure as stated in the Initial Conditions. This can be accomplished by covering those indications that are set higher (as done in the Control Room when on Shutdown Cooling) and placing yellow arrows on the one indication for each Steam Generator that is reading the correct value of SG pressure (~50 psia). This also is a standard practice in the Control Room.
Page 80 of 162
JPM: SO-05 NRC RO JPM S-5 TITLE: Alternate Reactor Core Cooling
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)
NOTE: Review the Setup page and ensure the PMS Monitors are properly aligned and the SG Pressure indications are correctly identified.
NOTE: The Simulator is frozen until just prior to the first manipulation. As soon as the Simulator is placed in RUN, RCS Subcooling will decrease as Thot rises. The examiner should verify that the candidate establishes core cooling by verifying that natural circulation conditions exist on at least one SG.
1 Initiate operating the AFW System. Initiates operating the AFW System. Start Time: _______
NOTE: Examinee may choose either of the two methods listed for initiating AFW flow.
2* Start AFW Pump P141. Starts AFW Pump P141 by depressing 2HS-4707-1 start pushbutton.
3 Verify 2HV-4731 AFW to SG 2E089 Verifies 2HV-4731, AFW to SG 2E089 ISO ISO VALVE is open. VALVE is open.
4* Commence feeding an available SG Commences feeding SG E089 by depressing using P141. OPEN/MODULATE on 2HV-4713 AFWP 2P141 to SG 2E089 DISCH VALVE.
NOTE: Steps 5 and 6 may not be performed by the examinee if they recognize that there is insufficient SG pressure to adequately feed the SGs.
5 Start AFW Pump P140. Starts AFW Pump P140 by depressing 2HV-4716 AFWPT 2K007 STEAM INLET VALVE open pushbutton.
Page 81 of 162
JPM: SO-05 NRC RO JPM S-5 TITLE: Alternate Reactor Core Cooling
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 6 Commence feeding an available SG Commences feeding SG by opening using P140. 2HV-4705 AFWP 2P140 to SG 2E088 DISCH VALVE and/or2HV-4706 AFWP 2P140 to SG 2E089 DISCH VALVE.
7 Initiate operating the SBCS and/or Initiates operating the Atmospheric Dump ADVs. Valves.
8* Prepare to open an Atmospheric Dump Depress OPEN/MODULATE on 2HV-8421 Valve. SG E089 ADV and/or 2HV-8419 SG E088 ADV.
9* Raise ADV Controller Output to open Depress SELECT push button on ADV valve. Controller 2PIC-8421-2 and/or 2PIC-8419-1 and raise OUTPUT to open valve.
NOTE: Any hesitation on the part of the Examinee to fully open the ADVs will delay in establishing natural circulation with the present RCS conditions.
10 Ensure one RCP is running per Identifies that no RCPs are running.
SO23-3.1.7. If forced circulation cannot be established, then provide natural circulation.
NOTE: Examinee may access Natural Circulation screen on CFMS to assess the following data.
11 Commence monitoring QSPDS Page Monitors QSPDS Page 622 and/or CFMS 622 and/or CFMS Page 312. Page 312.
12 Adjust steaming rate and feedwater Adjusts steaming rate and feedwater flow as flow to attain the following conditions: required.
13 Operating loop T - less than 58°F. Verifies operating loop T - less than 58°F.
Page 82 of 162
JPM: SO-05 NRC RO JPM S-5 TITLE: Alternate Reactor Core Cooling
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 14 Tcold and Thot - NOT rising. Verifies Tcold and Thot - NOT rising.
15 RX Vessel (Plenum) level - greater Verifies Reactor Vessel (Plenum) level -
than or equal to 100%. greater than or equal to 100%.
16 Core Exit Saturation Margin - greater Verifies Core Exit Saturation Margin -
than 20°F. greater than 20°F.
17 Operating loop Thot and REP CET - Verifies operating loop Thot and REP CET within 16°F. - within 16°F.
18 Maintain alternate RX Core cooling Maintains Alternate Reactor Core Cooling until SDC is restored. until SDC is restored.
TERMINATING CUE: Stop Time: _______
This JPM is complete.
Page 83 of 162
JPM: SO-05 NRC RO TITLE: Alternate Reactor Core Cooling JPM S-5
- Denotes a CRITICAL STEP JPM CHECKLIST
- 1. The JPM is:
- a. X Supported by facilitys job task analysis.
- b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).
- c. X Designed as either SRO only, or RO/SRO.
- 2. Each JPM includes:
- a. X Initial conditions.
- b. X Initiating cues.
- c. X References, including associated procedures.
- d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.
- e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.
- f. X Statements describing important actions or observations that should be made by the Examinee.
- g. X Criteria for successful completion.
- h. X Identification of the critical steps and their associated performance standards.
- i. X Validated time limits (average time allowed for completion).
- j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.
COMPLETED BY: L. Zilli DATE: 03/05/05 JPM INFORMATION SHEET Page 84 of 162
JPM: SO-05 NRC RO TITLE: Alternate Reactor Core Cooling JPM S-5
- Denotes a CRITICAL STEP JPM NUMBER SO-05 NRC RO JPM S-6 INITIAL PLANT CONDITIONS A Unit 2 Containment entry must be made to investigate an abnormal noise in a Reactor Coolant Pump. Prior to the entry, a Containment Mini-Purge is to be performed. 2RT-7828, Containment Purge Stack Radiation Monitor, is out-of-service.
TASK TO BE PERFORMED The Control Room Supervisor directs you to initiate a Containment Mini-Purge using SO23 4.2, Containment Purge and Recirculation Filtration System. , Operation of the Containment Mini-Purge System has been completed through Step 2.4.3.
2RT-7865, Plant Vent Stack/Containment Purge Stack Wide Range Gas Monitor, is aligned to the Containment Purge Stack.
Page 85 of 162
JPM: SO-05 NRC RO TITLE: Alternate Reactor Core Cooling JPM S-5
- Denotes a CRITICAL STEP JOB PERFORMANCE MEASURE SO-05 NRC RO JPM S-6 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:
The operators performance was evaluated against the standards contained in this JPM and is determined to be:
SATISFACTORY:
UNSATISFACTORY:
Page 86 of 162
JPM: SO-05 NRC RO TITLE: Alternate Reactor Core Cooling JPM S-5
- Denotes a CRITICAL STEP DOCUMENTATION SO-05 NRC RO JPM S-6 JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 20 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: ACO TASK SYS ID: 193205 TASK DESCRIPTION Startup the Containment Mini-Purge System.
Secure the Containment Mini-Purge System.
KA NUMBER: 103 A4.01 KA VALUES: RO 3.2 SRO 3.3 10CFR55.45 APPLICABILITY: 3, 8
REFERENCES:
SO23-1-4.2, Containment Purge and Recirculation Filtration System, Attachment 6, Rev. 27 SO23-15-61.A, Alarm Response Instruction for Panel 61A, Window 61A09, Rev. 13-1.
AUTHOR: K. Meagher DATE: 08/07/01 OPERATIONS REVIEW: W. Lyke DATE: 09/27/01 APPROVED BY: A. Hagemeyer DATE: 10/10/01 Page 87 of 162
JPM: SO-05 NRC RO TITLE: Alternate Reactor Core Cooling JPM S-5
- Denotes a CRITICAL STEP MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 2 Compared to SO23-1-4.2, Revision 24 KM 008/07/01 REV and SO23-15-61.A, Revision 10-2.
No changes required. Updated VISION system ID number. Verified KA number. Made into faulted JPM due to Rad. Monitor failure. Made into simulator JPM since this is performed in simulator. Made steps 3, 4, 5 and 6 critical steps since they are the steps to start the Mini-Purge.
2-1 Compared to SO23-1-4.2, Revision 27 LRZ 02/24/05 AHH with minor changes required. New VISION ID.
Page 88 of 162
JPM: SO-05 NRC RO TITLE: Alternate Reactor Core Cooling JPM S-5
- Denotes a CRITICAL STEP SET-UP SIMULATOR:
For April 2005 NRC Exam this JPM will be performed concurrent with S-2.
Use any IC.
- Plant Vent Stack Rad Monitor 2RT-7865 will need to be aligned to the Ctmt. Purge Stack.
INSTRUCTOR/MACHINE OPERATOR:
This is a faulted JPM. The fault is that Plant Vent Stack Rad Monitor 2-RT7865 fails after the mini-purge is initiated (JPM Step 9). This will require the examinee to stop the mini-purge.
Simulator RT-7828, Containment Purge Monitor, is presently out-of-service. ENSURE RT-7828 is failed on the Data Acquisition System. This necessitates 2RT-7865, PVS Wide Range Gas Monitor, being aligned to the Containment Purge Stack.
OBTAIN a copy of SO23-1-4.2, Containment Purge and Recirculation Filtration System and MARK-UP Attachment 6 as complete up through Step 2.4.3. This will make Section 2.5, Start Mini-Purge, as the next step to be performed.
A laminated copy of the DAS page for Unit 2 RT-7865, showing instrument failure is in the JPM folder for use at JPM Step 9.
VERIFY Containment Pressure is equal to or slightly above atmospheric pressure.
ALERT the Machine Operator that after the report to Chemistry (JPM Step 7) has been made, ANNUNCIATE 61A09 - Unit 2 AND COMMON INSTRUMENT FAILURE alarm.
CAUTION: ENSURE that 2HV-9825 and 2HV-9824 are open before starting this JPM.
Page 89 of 162
JPM: SO-05 NRC RO JPM S-6 TITLE: Perform a Containment Mini-Purge
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)
NOTE: Provide the Examinee with the marked-up copy of SO23-1-4.2, Containment Purge and Recirculation Filtration System completed through Step 2.4.3. Ensure that 2HV-9825 and 2HV-9824 are open before starting this JPM.
NOTE: It may be necessary to cue the Examinee that Containment pressure is greater than atmospheric pressure.
CUE: There is an ARO standing by to assist you in performing manipulations outside of the Control Room.
1 ENSURE OPEN HV-9825, Verify open 2HV-9825, CNTMT MINI PRG Time Start: _______
Containment Mini-Purge Exhaust EXH 2A-059 ISO Valve.
2 (3) MA-059 Isolation Valve. (Outside Containment) 2 ENSURE OPEN HV-9824, Verify open 2HV-9824, CNTMT MINI PRG Containment Mini-Purge Exhaust EXH 2A-059 ISO Valve.
2 (3) MA-059 Isolation Valve. (Inside Containment) 3* ENSURE OPEN HV-9823, Opens 2HV-9823, CNTMT MINI PRG SPLY Containment Mini-Purge Supply 2A-379 ISO Valve, by depressing the OPEN 2 (3) MA-379 Isolation Valve. (Inside pushbutton on 2HV-9823 and observing the Containment) red OPEN lamp illuminates.
4* ENSURE OPEN HV-9821, Opens 2HV-9821, CNTMT MINI PRG SPLY Containment Mini-Purge Supply 2A-379 ISO Valve, by depressing the OPEN 2 (3) MA-379 Isolation Valve. (Outside pushbutton on 2HV-9821 and observing the Containment) red OPEN lamp illuminated.
5* START 2 (3) MA-059, Mini-Purge Directs the ARO to START 2MA-059, Mini-Exhaust Unit. Purge Exhaust Unit.
Page 90 of 162
JPM: SO-05 NRC RO JPM S-6 TITLE: Perform a Containment Mini-Purge
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)
CUE: The ARO acknowledges and reports that 2MA-059, Mini-Purge Exhaust Unit is running.
6* START 2 (3) MA-379, Mini-Purge Directs the ARO to START 2MA-379, Mini-Supply Unit. Purge Supply Unit.
CUE: The ARO acknowledges and reports that 2MA-379, Mini-Purge Supply Unit is running.
7 Notify the Chemistry Division that a Contacts Chemistry and informs them that a purge is in progress. Containment Mini-Purge is in progress.
CUE: Chemistry acknowledges that the mini-purge is in service. Steps 2.5.8, 2.5.9, and 2.5.10 were completed by another operator.
NOTE: ALERT the Machine Operator that after the report to Chemistry has been made, ANNUNCIATE alarm 61A09 - UNIT 2 AND COMMON INSTRUMENT FAILURE.
8 Acknowledge annunciator 61A09, U2 Acknowledges 61A09, UNIT 2 AND AND COMMON INSTRUMENT COMMON INSTRUMENT FAILURE alarm, FAILURE. by depressing the Alarm Acknowledge button for Panel 61A.
NOTE: Provide the cue for JPM Step 9 as soon as the Examinee accesses DAS.
NOTE: A laminated copy of the DAS page for 2RT-7865, showing an instrument failure is given to the examinee.
9 Determine which instrument has failed. Accesses DAS or views 2L-405 to determine the instrument failure to be a channel failure of 2RT-7865.
CUE: If the examinee goes to 2L-405 to determine if an instrument failure has occurred, report that a channel failure is indicated for 2RT-7865, Plant Vent Stack/Containment Purge Stack Wide Range Gas Monitor.
Page 91 of 162
JPM: SO-05 NRC RO JPM S-6 TITLE: Perform a Containment Mini-Purge
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 10 STOP 2 (3) MA-379, Mini-Purge Directs the ARO to STOP 2MA-059, Mini-Supply Unit. Purge Supply Unit.
CUE: The ARO acknowledges and reports that 2MA-379, Mini-Purge Supply Unit is stopped.
11 STOP 2 (3) MA-059, Mini-Purge Directs the ARO to STOP 2MA-059, Mini-Exhaust Unit. Purge Exhaust Unit.
CUE: The ARO acknowledges and reports that 2MA-059, Mini-Purge Exhaust Unit is stopped.
NOTE: The Examinee need only perform JPM Step 12 or 13 and JPM Step 14 or 15 to meet the intent of isolating the Containment Mini-Purge.
12* CLOSE 2 (3) HV-9821, Containment Closes 2HV-9821, CNTMT MINI PRG SPLY Mini-Purge Supply MA-379 Isolation. 2A-379 ISO Valve, by depressing the CLOSE (Outside Containment) pushbutton for on 2HV-9821 and observing only the green CLOSE lamp illuminated.
13* CLOSE 2 (3) HV-9823, Containment Closes 2HV-9823, CNTMT MINI PRG SPLY Mini-Purge Supply MA-379 Isolation. 2A-379 ISO Valve, by depressing the CLOSE (Inside Containment) pushbutton on 2HV-9823 and observing only the green CLOSE lamp illuminated.
14* CLOSE 2 (3) HV-9824, Containment Closes 2HV-9824, CNTMT MINI PRG EXH Mini-Purge Exhaust MA-059 Isolation 2A-059 ISO Valve, by depressing the CLOSE Valve. (Inside Containment) pushbutton on 2HV-9824 and observing only the green CLOSE lamp illuminated.
Page 92 of 162
JPM: SO-05 NRC RO JPM S-6 TITLE: Perform a Containment Mini-Purge
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 15* Close 2 (3) HV-9825, Containment Closes 2 HV-9825, CNTMT MINI PRG EXH Mini-Purge Exhaust MA-059 Isolation 2A-059 ISO Valve, by depressing the CLOSE pushbutton on 2HV-9825 and Valve. (Outside Containment) observing only the green CLOSE lamp illuminated.
TERMINATING CUE: Stop Time: _______
Another operator will complete the procedure.
This JPM is complete.
Page 93 of 162
JPM CHECKLIST
- 1. The JPM is:
- a. X Supported by facilitys job task analysis.
- b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).
- c. X Designed as either SRO only, or RO/SRO.
- 2. Each JPM includes:
- a. X Initial conditions.
- b. X Initiating cues.
- c. X References, including associated procedures.
- d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.
- e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.
- f. X Statements describing important actions or observations that should be made by the Examinee.
- g. X Criteria for successful completion.
- h. X Identification of the critical steps and their associated performance standards.
- i. X Validated time limits (average time allowed for completion).
- j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.
COMPLETED BY: L. Zilli DATE: 02/25/05 JPM INFORMATION SHEET JPM NUMBER Page 94 of 162
SO-05 NRC RO JPM S-7 INITIAL PLANT CONDITIONS An ESDE and a LOCA has occurred on Unit 2. Vital Bus 2A06 was lost upon plant trip and HPSI Pump P-018 tripped on overcurrent. The Control Room Supervisor has entered SO23-12-9, Functional Recovery.
TASK TO BE PERFORMED The Control Room Supervisor has reviewed the RACs and directs you to perform SO23-12-9, Functional Recovery Attachment FR-4, PC Subcooled Pressure Control Recovery Actions, Step 9.
Page 95 of 162
JOB PERFORMANCE MEASURE SO-05 NRC RO JPM S-7 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:
The operators performance was evaluated against the standards contained in this JPM and is determined to be:
SATISFACTORY:
UNSATISFACTORY:
Page 96 of 162
DOCUMENTATION SO-05 NRC RO JPM S-7 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 10 minutes TIME CRITICAL JPM: N/A CRITICAL TIME:
POSITION: CO VISION ID: 192187 TASK DESCRIPTION Respond to a Loss of Coolant Accident.
KA NUMBER: EA1.3 KA VALUES: RO 3.6 SRO 3.8 10CFR55.45 APPLICABILITY: 6, 7
REFERENCES:
SO23-12-9, Functional Recovery, Attachment FR-4, Recovery - RCS Pressure Control, Rev. 23 SO23-12-11, EOI Supporting Attachments, FS-7, SI Throttle / Stop Criteria, Rev.2 AUTHOR: L. Zilli DATE: 02/15/05 OPERATIONS REVIEW: M. Jones DATE: 03/09/05 APPROVED BY: A. Hagemeyer DATE: 03/09/05 Page 97 of 162
MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New Page 98 of 162
SET-UP Use IC #125 for 2005 NRC Exam.
NOTE: Provide the Examinee with a copy of SO23-12-9, Functional Recovery, Attachment FR-4, Recovery - RCS Pressure Control and a copy of FS-7, SI Throttle/Stop Criteria from SO23-12-11, EOI Supporting Attachments.
NOTE: Examiner should have Control Room Key #20 in hand to expedite JPM.
NOTE: Examiner should wear a headset to be in communication with the Machine Operator.
Page 99 of 162
JPM: SO-05 NRC RO JPM S-7 TITLE: Subcooled Pressure Control Recovery Actions
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)
NOTE: Provide the Examinee with a copy of SO23-12-9, Functional Recovery, Attachment FR-4, Recovery -
RCS Pressure Control. Examiner should have Control Room Key #20 in hand to expedite JPM.
1 VERIFY RWST level - greater than Verifies RWST level greater than 19%. Start Time: _______
19%.
2 INITIATE FS-20, MONITOR RWST Initiates FS-20, Monitor RWST Level.
Level.
CUE: Another operator will perform FS-20, Monitor RWST Level.
3 ENSURE at least one RWST Outlet Verifies RWST Outlet Valve open on Train Valve - open: A, HV-9300.
Train A Train B HV-9300 HV-9301 4 VERIFY PZR pressure - less than Verifies PZR pressure less than 1500 PSIA.
1500 PSIA.
NOTE: Provide a copy of FS-7, SI Throttle/Stop Criteria to the examinee.
5 VERIFY FS-7, VERIFY SI Determines FS-7, SI Throttle/Stop Criteria -
Throttle/Stop Criteria - NOT satisfied. NOT satisfied due to Pressurizer level
< 30%.
CUE: Another operator will monitor FS-7, SI Throttle/Stop Criteria.
Page 100 of 162
JPM: SO-05 NRC RO JPM S-7 TITLE: Subcooled Pressure Control Recovery Actions
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 6 VERIFY at least two HPSI to RCS Verifies that only one (1) HPSI to RCS Cold Cold Leg Injection Valves on Leg Injection Valve, 2HV-9327 on HPSI operating HPSI train - open: Train A is open.
Train A Train B HV-9324 HV-9323 HV-9327 HV-9326 HV-9330 HV-9329 HV-9333 HV-9332 7 ESTABLISH HPSI Hot Leg Injection Establishes HPSI Hot Leg Injection for for operating HPSI trains: operating HPSI trains.
8 CLOSE applicable breakers: Directs an operator to close Train A breaker BY-29.
Train A Train B BY-29 BZ-39 NOTE: Direct Machine Operator to activate event for MCC Breaker BY-29 closed.
CUE: Breaker BY-29 is closed.
NOTE: Hand Control Room Key #20 to examinee when at the Key Locker.
9* OPEN applicable HPSI to RCS Hot Opens Train A HPSI to RCS Hot Leg Leg Injection Valves: Injection Valve HV-9420 by inserting the Train A Train B key and turning to the OPEN position.
HV-9420 HV-9434 Page 101 of 162
JPM: SO-05 NRC RO JPM S-7 TITLE: Subcooled Pressure Control Recovery Actions
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 10* ENSURE available HPSI Pumps - Starts Train A HPSI Pump P017 by operating. depressing START on 2HS-9392-1, HPSI PUMP 2P017 and verifies proper running pump amps (~40 to 50 amps).
TERMINATING CUE: Stop Time: _______
This JPM is complete.
Page 102 of 162
JPM: SO-05 NRC RO TITLE: Subcooled Pressure Control Recovery Actions JPM S-7
- Denotes a CRITICAL STEP JPM CHECKLIST
- 1. The JPM is:
- a. X Supported by facilitys job task analysis.
- b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).
- c. X Designed as either SRO only, or RO/SRO.
- 2. Each JPM includes:
- a. X Initial conditions.
- b. X Initiating cues.
- c. X References, including associated procedures.
- d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.
- e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.
- f. X Statements describing important actions or observations that should be made by the Examinee.
- g. X Criteria for successful completion.
- h. X Identification of the critical steps and their associated performance standards.
- i. X Validated time limits (average time allowed for completion).
- j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.
COMPLETED BY: L. Zilli DATE: 03/05/05 JPM INFORMATION SHEET Page 103 of 162
JPM: SO-05 NRC RO TITLE: Subcooled Pressure Control Recovery Actions JPM S-7
- Denotes a CRITICAL STEP JPM NUMBER SO-05 NRC RO/SRO JPM A.3 INITIAL PLANT CONDITIONS A LOCA has occurred on Unit 2. An operator has been seriously injured in the Train A Containment Spray Pump Room.
Extremely high radiation levels require a volunteer to attempt a rescue. The Emergency Coordinator has authorized a volunteer to attempt a rescue.
The estimated dose to the rescuer is 50 Rem.
The TSC and OSC have NOT yet been activated.
TASK TO BE PERFORMED The Emergency Coordinator has directed you to select a volunteer from the list of candidates available in accordance with SO23-VIII-30, Units 2/3 Operations Leader Duties.
Page 104 of 162
JPM: SO-05 NRC RO TITLE: Subcooled Pressure Control Recovery Actions JPM S-7
- Denotes a CRITICAL STEP JOB PERFORMANCE MEASURE SO-05 NRC RO/SRO JPM A.3 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:
The operators performance was evaluated against the standards contained in this JPM and is determined to be:
SATISFACTORY:
UNSATISFACTORY:
Page 105 of 162
JPM: SO-05 NRC RO TITLE: Subcooled Pressure Control Recovery Actions JPM S-7
- Denotes a CRITICAL STEP DOCUMENTATION SO-05 NRC RO/SRO JPM A.3 JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 10 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CO TASK SYS ID: 186266 TASK DESCRIPTION Implement exposure control in the control room during an emergency event.
KA NUMBER: 2.3.4 KA VALUES: RO 2.5 SRO 3.1 10CFR55.45 APPLICABILITY: 10
REFERENCES:
SO23-VIII-30, Units 2/3 Operations Leader Duties, Rev. 10 EPIP Form EP (123) 3, Emergency Exposure Authorization, Rev. 1 AUTHOR: Joseph G. Arsenault DATE: 10/28/03 OPERATIONS REVIEW: M. Jones DATE: 11/10/03 APPROVED BY: K. Rauch DATE: 11/10/03 Page 106 of 162
JPM: SO-05 NRC RO TITLE: Subcooled Pressure Control Recovery Actions JPM S-7
- Denotes a CRITICAL STEP MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New - - -
0-1 Compared against SO23-VIII-30, Rev. LRZ 04/05/05 AHH 9 with minor changes required.
Modified JPM to have the examinee select an appropriate volunteer.
Page 107 of 162
JPM: SO-05 NRC RO TITLE: Subcooled Pressure Control Recovery Actions JPM S-7
- Denotes a CRITICAL STEP SET-UP NOTE: Provide the examinee with copies of SO23-VIII-30, EPIP Form EP (123) 3 and the list of available volunteers.
Page 108 of 162
JPM: SO-05 NRC RO / SRO JPM A.3 TITLE: Provide Briefing for Emergency Exposure Authorization
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)
CUE: Provide examinee with a clean copy of SO23-VIII-30, EPIP Form EP (123) 3 and a list of available volunteers.
1 Refer to SO23-VIII-30 Section 6.7 and Refers to guidance in SO23-VIII-30 Section Start Time: _______
EPIP Form EP (123) 3. 6.7 and EPIP Form EP (123).
2* Determine if individual is a volunteer. Determines that all individuals have volunteered for Emergency Exposure.
3* Determine age of volunteer. Determines the desired age of the volunteer is
> 45 years old.
4* Determine if volunteer is pregnant. Determines that the ideal volunteer has not declared herself pregnant.
5* Determine if volunteer can read and Determines that the ideal volunteer can read understand the potential biological and understand the potential biological consequences. consequences.
6* Determine if volunteer is allergic to Determines ideal volunteer is NOT allergic to shellfish and has a shellfish and has NO history of thyroid history of thyroid disease.
disease.
7* Select a volunteer. Selects Volunteer C as the most appropriate candidate for Emergency Exposure.
TERMINATING CUE: Stop Time: _______
This JPM is complete.
Page 109 of 162
JPM: SO-05 NRC RO / TITLE: Provide Briefing for Emergency Exposure SRO JPM A.3 Authorization
- Denotes a CRITICAL STEP JPM CHECKLIST
- 1. The JPM is:
- a. X Supported by facilitys job task analysis.
- b. X Operationally important (meets threshold criterion of K/A 3.0 or greater). This task is ranked at 2.5 for the RO, however, these are duties that are required at SONGS for both ROs and SROs.
- c. X Designed as either SRO only, or RO/SRO.
- 2. Each JPM includes:
- a. X Initial conditions.
- b. X Initiating cues.
- c. X References, including associated procedures.
- d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.
- e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.
- f. X Statements describing important actions or observations that should be made by the Examinee.
- g. X Criteria for successful completion.
- h. X Identification of the critical steps and their associated performance standards.
- i. X Validated time limits (average time allowed for completion).
- j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.
COMPLETED BY: L. Zilli DATE: 04/04/05 Page 110 of 162
JPM: SO-05 NRC RO / TITLE: Provide Briefing for Emergency Exposure SRO JPM A.3 Authorization
- Denotes a CRITICAL STEP List of Available Volunteers
- 1. Volunteer A is a 35-year-old female who is trying to start a family.
- 2. Volunteer B is a 40-year-old male who recently qualified as a Primary PEO.
- 3. Volunteer C is a 48-year-old male with a lifetime exposure of 1.75 REM.
- 4. Volunteer D is a 52-year-old male with a lifetime exposure of 105 REM, including a Protecting Valuable Property dose of 9.5 REM at another facility.
- 5. Volunteer E is a 46-year-old female with sensitivity to shellfish.
- 6. Volunteer F is a 47-year-old female that tells you she is pregnant.
- 7. Volunteer G is a 60-year-old male that does not speak or read English.
JPM INFORMATION SHEET JPM NUMBER SO-05 NRC RO/SRO JPM P-1 INITIAL PLANT CONDITIONS The Unit 2 (3) CRS is performing RCS Pressure Control Recovery in SO23-12-9, Functional Recovery procedure. Normal Pressurizer spray is not available and the crew is directed to establish Pressurizer Auxiliary Spray. The NOA has provided key 2(3) AB for S2(3)1208MU084, Charging Line to Regenerative Heat Exchanger Block Valve and key 2(3)
CIV for S2(3)1208MU130, Auxiliary Spray Bypass Line.
Page 111 of 162
JPM: SO-05 NRC RO / TITLE: Provide Briefing for Emergency Exposure SRO JPM A.3 Authorization
- Denotes a CRITICAL STEP TASK TO BE PERFORMED As the Primary ACO, establish the alternate Auxiliary Spray flowpath using SO23-12-11, EOI Supporting Attachments, FS-31, Establish Manual Auxiliary Spray and control the rate of pressure reduction as directed by the Control Room Supervisor.
Page 112 of 162
JPM: SO-05 NRC RO / TITLE: Provide Briefing for Emergency Exposure SRO JPM A.3 Authorization
- Denotes a CRITICAL STEP JOB PERFORMANCE MEASURE SO-05 NRC RO/SRO JPM P-1 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:
The operators performance was evaluated against the standards contained in this JPM and is determined to be:
SATISFACTORY:
UNSATISFACTORY:
Page 113 of 162
JPM: SO-05 NRC RO / TITLE: Provide Briefing for Emergency Exposure SRO JPM A.3 Authorization
- Denotes a CRITICAL STEP DOCUMENTATION SO-05 NRC RO/SRO JPM P-1 JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 5 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: PPEO TASK SYS ID: 193333 TASK DESCRIPTION Locally operate Pressurizer Auxiliary Spray System under harsh environment conditions.
KA NUMBER: 010 A2.02 KA VALUES: RO 3.9 SRO 3.9 10CFR55.45 APPLICABILITY: 6, 12
REFERENCES:
SO23-12-11, EOI Supporting Attachments, FS-31, Establish Manual Auxiliary Spray, Revision 2 AUTHOR: L. Zilli DATE: 04/06/05 OPERATIONS REVIEW: M. Jones DATE: 04/08/05 APPROVED BY: A. Hagemeyer DATE: 04/08/05 Page 114 of 162
JPM: SO-05 NRC RO / TITLE: Provide Briefing for Emergency Exposure SRO JPM A.3 Authorization
- Denotes a CRITICAL STEP MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0-1 Compared against SO23-12-9, Rev. 21 LRZ 09/05/01 KR with minor changes required to allow JPM to be performed on either unit.
0-2 Changed reference to SO23-12-11, RCW 08/25/04 MRN Rev. 2. Added two cues. Updated Task Sys ID.
1 Compared against SO23-12-11, Rev. 2 LRZ 04/06/05 REV and modified to include the requirement to reduce pressure via valve manipulation.
Page 115 of 162
JPM: SO-05 NRC RO / TITLE: Provide Briefing for Emergency Exposure SRO JPM A.3 Authorization
- Denotes a CRITICAL STEP SET-UP NOTE: Provide the examinee with a copy of SO23-12-11, EOI Supporting Attachments, FS-31, Establish Manual Auxiliary Spray.
Page 116 of 162
JPM: SO-05 NRC RO/SRO JPM P-1 TITLE: Perform Manual Auxiliary Spray Actions
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)
NOTE: Provide the examinee with a copy of SO23-12-11, EOI Supporting Attachments, FS-31, Establish Manual Auxiliary Spray.
1 Ensure HV-9201 is closed. Ensures 2(3)HV-9201 is closed by contacting Start Time: _______
the Control Room and verifying 2(3)HV-9201 position.
CUE: The CRS reports that the PZR Auxiliary Spray Valve 2(3)HV-9201 is closed.
2* UNLOCK and OPEN 1208MU130, Simulates unlocking and opening PZR Auxiliary Spray Bypass Line S2(3)1208MU130, PZR Auxiliary Spray Isolation Valve (CIV Key Penetration Bypass Line Isolation Valve at Penetration 68 68). with CIV Key.
CUE: The valve is unlocked and open.
NOTE: Examinee should report to the Control Room that MU130 is open.
CUE: CRS directs you to throttle MU084 to 50% open.
3* UNLOCK and THROTTLE Simulates unlocking and throttling 1208MU084, PZR Charging Line Block S2(3)1208MU084, Charging Line Block Valve (AB Key Penetration 8), to Valve using AB Key at Penetration 8 to 50%
control spray flow to establish required open.
PZR pressure.
NOTE: MU084 is normally open, so the examinee should simulate throttling the valve in the closed direction (clock-wise).
CUE: The valve is unlocked and throttled.
Page 117 of 162
JPM: SO-05 NRC RO/SRO JPM P-1 TITLE: Perform Manual Auxiliary Spray Actions
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 4 Contact the Control Room to verify Contacts the Control Room to verify the rate correct valve position. of depressurization is acceptable.
CUE: CRS directs you to adjust MU084 to increase the rate of pressure reduction.
NOTE: Examinee should indicate that the valve should be throttled further in the closed direction.
5* Control Room requests that the operator Throttles closed MU084 and contacts the increase the rate of pressure reduction. Control Room to verify the rate of depressurization is acceptable.
CUE: CRS reports the rate of pressure reduction is acceptable (if the valve is throttled closed).
CRS reports the rate of pressure reduction is unacceptable (if the valve is throttled opened).
NOTE: Examinee should indicate that the valve should be throttled further in the closed direction.
TERMINATING CUE: Stop Time: _______
This JPM is complete.
Page 118 of 162
JPM: SO-05 NRC RO/SRO TITLE: Perform Manual Auxiliary Spray Actions JPM P-1
- Denotes a CRITICAL STEP JPM CHECKLIST
- 1. The JPM is:
- a. X Supported by facilitys job task analysis.
- b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).
- c. X Designed as either SRO only, or RO/SRO.
- 2. Each JPM includes:
- a. X Initial conditions.
- b. X Initiating cues.
- c. X References, including associated procedures.
- d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.
- e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.
- f. X Statements describing important actions or observations that should be made by the Examinee.
- g. X Criteria for successful completion.
- h. X Identification of the critical steps and their associated performance standards.
- i. X Validated time limits (average time allowed for completion).
- j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.
COMPLETED BY: L. Zilli DATE: 02/24/05 JPM INFORMATION SHEET Page 119 of 162
JPM: SO-05 NRC RO/SRO TITLE: Perform Manual Auxiliary Spray Actions JPM P-1
- Denotes a CRITICAL STEP JPM NUMBER SO-05 NRC RO/SRO JPM P-2 INITIAL PLANT CONDITIONS A Blackout has occurred on Unit 2.
OFF-Site power has just been restored to Unit 3.
Buses 3A04 and 3B04 are energized from Off-Site power.
The Unit 2 Crew has determined that Bus 2B04 needs to be energized from Unit 3.
Declaration of 10CFR50.54(x) and (y) has been made.
MCC BS is required by SO23-12-11, Attachment 9, Control Building Ventilation Emergency Actions.
MCC BQ is currently aligned to Unit 2.
TASK TO BE PERFORMED Energize 1E 480V bus 2B04 from Unit 3 per SO23-12-11, Attachment 23. Use MCC BQ for the cross-connect. You have been issued an extra interlock key for MCC BQ.
Page 120 of 162
JPM: SO-05 NRC RO/SRO TITLE: Perform Manual Auxiliary Spray Actions JPM P-1
- Denotes a CRITICAL STEP JOB PERFORMANCE MEASURE SO-O5 NRC RO/SRO JPM P-2 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:
The operators performance was evaluated against the standards contained in this JPM and is determined to be:
SATISFACTORY:
UNSATISFACTORY:
Page 121 of 162
JPM: SO-05 NRC RO/SRO TITLE: Perform Manual Auxiliary Spray Actions JPM P-1
- Denotes a CRITICAL STEP DOCUMENTATION SO-05 NRC RO/SRO JPM P-2 JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 13 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: PEO TASK SYS ID: 188352 TASK DESCRIPTION Energize class 1E 4KV buses from the other unit during response to a station blackout.
KA NUMBER: 055 EA2.03 KA VALUES: RO 3.9 SRO 4.7 10CFR55.45 APPLICABILITY: 6, 12
REFERENCES:
SO23-12-11, EOI Supporting Attachments, Attachment 23, Revision 2 AUTHOR: L. Zilli DATE: 02/24/05 OPERATIONS REVIEW: M. Jones DATE: 03/09/05 APPROVED BY: A. Hagemeyer DATE: 03/09/05 Page 122 of 162
JPM: SO-05 NRC RO/SRO TITLE: Perform Manual Auxiliary Spray Actions JPM P-1
- Denotes a CRITICAL STEP MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New - - -
0-1 Compared against SO23-12-11, LRZ 2/24/05 AHH Rev. 2, Attachment 23 with minor changes required.
Page 123 of 162
JPM: SO-05 NRC RO/SRO TITLE: Perform Manual Auxiliary Spray Actions JPM P-1
- Denotes a CRITICAL STEP SET-UP NOTE: Provide the Examinee with a copy of SO23-12-11, EOI Supporting Attachments, 3, Cross Connecting Class 1E 480V Buses Between Units.
Page 124 of 162
JPM: SO-05 NRC RO JPM P-2 TITLE: Energize Class 1E 480V Bus B04 from Unit 3
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)
NOTE: Provide the Examinee with a copy of SO23-12-11, EOI Supporting Attachments, Attachment 23, Cross Connecting Class 1E 480V Buses Between Units.
1 Verify BS required by Attachment 9, Identified in Initial Conditions. Start Time:_______
Control Building Ventilation Emergency Action.
2 Verify A04 and B04 on other Unit Identified in Initial Conditions.
energized.
3 Verify A04 and B04 energized on other Identified in Initial Conditions.
Unit NOT supplied by Diesel Generator.
4* Open 2B04 4kV supply breaker Contact Unit 2 Control Room and request that 2A0420. they open breaker 2A0420.
CUE: The breaker is open.
5* Open 2B04 480V supply breaker Simulate opening 2B0401 by pressing the 2B0401. TRIP pushbutton.
CUE: The breaker is open.
6* Open all the breakers on affected unit Simulate opening all breakers on 2B04 by B04. pressing the TRIP pushbuttons.
NOTE: Trainee does not have to simulate opening each individual breaker. After trainee simulates opening the first breaker, and identifies he will open the remaining breakers, provide the Cue below.
CUE: All breakers on 2B04 are open.
Page 125 of 162
JPM: SO-05 NRC RO JPM P-2 TITLE: Energize Class 1E 480V Bus B04 from Unit 3
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 7 Ensure both MCC BQ supply breakers open:
- 2B0417 Verify 2B0417 is open by checking indicating flag in the breaker window (breaker was opened on previous step).
- 3B0417 Verify 3B0417 is open by checking indicating flag in the breaker window.
NOTE: Breaker is already open due to initial condition of BQ aligned to Unit 2.
CUE: 2B0417 and 3B0417 are open.
NOTE: The next three (3) steps can be done in any order.
8 Open all breakers on BE (affected unit). Simulate opening all breakers on MCC 2BE by pulling the breaker levers down to the OFF position.
NOTE: Examinee does not have to simulate opening each individual breaker. After examinee simulates opening the first breaker and identifies they will open the remaining breakers, provide the Cue below.
CUE: All breakers on MCC 2BE are open.
9 Open all breakers on BY (affected unit). Simulate opening all breakers on MCC 2BY by pulling the breaker levers down to the OFF position.
NOTE: Examinee does not have to simulate opening each individual breaker. After examinee simulates opening the first breaker and identifies they will open the remaining breakers, provide the Cue below.
Page 126 of 162
JPM: SO-05 NRC RO JPM P-2 TITLE: Energize Class 1E 480V Bus B04 from Unit 3
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)
CUE: All breakers on MCC 2BY are open.
10* Open all breakers on BQ. Simulate opening all load breakers on MCC by BQ by pulling the breaker levers down to the OFF position. (Unit 2 supply breaker BQ-01 is currently closed and does not have to be opened.)
NOTE: Examinee does not have to simulate opening each individual breaker. After examinee simulates opening the first breaker and identifies he will open the remaining breakers, provide the Cue below.
CUE: All load breakers on MCC 2BQ are open.
11 Obtain second MCC BQ power supply Key already obtained.
interlock key.
CUE: You have the interlock key.
12* Ensure Unit 2 power supply feeder Verify BQ-01 is closed by observing breaker BQ-01 to MCC BQ is closed. lever up in the ON position.
NOTE: If examinee opened BQ-01 in Step 10, they will have to re-close it here.
CUE: The breaker is closed.
13* Ensure Unit 3 power supply feeder BQ- Simulate opening the Kirk Key Panel door to 02 to MCC BQ is closed. the right of the BQ-02 supply breaker to expose the Kirk Key lock.
CUE: BQ-02 Kirk Key lock is empty.
Page 127 of 162
JPM: SO-05 NRC RO JPM P-2 TITLE: Energize Class 1E 480V Bus B04 from Unit 3
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 14* Ensure Unit 3 power supply feeder Simulate inserting the second Kirk Key into BQ-02 to MCC BQ is close. the BQ-02 Kirk Key lock.
Simulate turning the BQ-02 Kirk Key to unlock the breaker.
Simulate closing the MCC supply breaker BQ-02 by raising the breaker lever up to the ON position.
CUE: The breaker is closed.
15* Energize MCC BQ by closing supply Simulate closing 3B0417 by pressing the breaker from energized B04: CLOSE pushbutton.
- 3B0417 CUE: The breaker is closed.
16* Energize affected B04 by closing MCC Simulate closing 2B0417 by pressing the BQ supply breaker. CLOSE pushbutton.
CUE: The breaker is closed.
TERMINATING CUE: Stop Time: _______
Another operator will energize loads.
This JPM is complete.
Page 128 of 162
JPM: SO-05 NRC RO TITLE: Energize Class 1E 480V Bus B04 from Unit 3 JPM P-2
- Denotes a CRITICAL STEP JPM CHECKLIST
- 1. The JPM is:
- a. X Supported by facilitys job task analysis.
- b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).
- c. X Designed as either SRO only, or RO/SRO.
- 2. Each JPM includes:
- a. X Initial conditions.
- b. X Initiating cues.
- c. X References, including associated procedures.
- d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.
- e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.
- f. X Statements describing important actions or observations that should be made by the Examinee.
- g. X Criteria for successful completion.
- h. X Identification of the critical steps and their associated performance standards.
- i. X Validated time limits (average time allowed for completion).
- j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.
COMPLETED BY: L. Zilli DATE: 02/24/05 JPM INFORMATION SHEET Page 129 of 162
JPM: SO-05 NRC RO TITLE: Energize Class 1E 480V Bus B04 from Unit 3 JPM P-2
- Denotes a CRITICAL STEP JPM NUMBER SO-05 NRC RO/SRO JPM P-3 INITIAL PLANT CONDITIONS The Control Room has just been evacuated.
You have been to the Safe Shutdown Locker and have an emergency lantern, earplugs, and the ACO Keyset.
TASK TO BE PERFORMED Manually feed the Unit 2 (Unit 3) Steam Generators with the Steam Driven Auxiliary Feedwater Pump, P-140, in Local-Manual using SO23-13-2, Attachment 12, AFW Pump Local Manual Operation.
Page 130 of 162
JPM: SO-05 NRC RO TITLE: Energize Class 1E 480V Bus B04 from Unit 3 JPM P-2
- Denotes a CRITICAL STEP JOB PERFORMANCE MEASURE SO-05 NRC RO/SRO JPM P-3 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:
The operators performance was evaluated against the standards contained in this JPM and is determined to be:
SATISFACTORY:
UNSATISFACTORY:
Page 131 of 162
JPM: SO-05 NRC RO TITLE: Energize Class 1E 480V Bus B04 from Unit 3 JPM P-2
- Denotes a CRITICAL STEP DOCUMENTATION SO-05 NRC RO/SRO JPM P-3 JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 13 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: PPEO TASK SYS ID: 193557 TASK DESCRIPTION Perform AFW Pump local manual operations during a Plant shutdown from outside the Control Room.
KA NUMBER: 068 AA1.02 KA VALUES: RO 4.3 SRO 4.5 10CFR55.45 APPLICABILITY: 6, 8, 12
REFERENCES:
SO23-12-2, Shutdown from Outside the Control Room, Rev. 7-3 AUTHOR: S. Hollinger DATE: 09/16/92 OPERATIONS REVIEW: K. Eckman DATE: 10/21/93 APPROVED BY: M. Kirby DATE: 10/26/93 Page 132 of 162
JPM: SO-05 NRC RO TITLE: Energize Class 1E 480V Bus B04 from Unit 3 JPM P-2
- Denotes a CRITICAL STEP MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 1-1 Added step 11 per OPS comments. SW 10/26/93 MJK 1-2 Compared against SO23-13-2, HJW 01/18/94 N/A TCN 2-17; no changes required.
1-3 Changed setup page; minor editorial HJW 03/18/94 N/A corrections; changed time from 15 to 14 minutes based on history.
1-4 Compared against SO23-13-2, HJW 09/08/94 N/A TCN 2-18; changes made in steps for operation with governor out-of-service to match procedure.
1-5 Correct Position on Documentation HJW 02/09/95 N/A page.
1-6 Compared against SO23-13-2, HJW 04/17/95 N/A TCN 2-19; with no changes required.
1-7 Compared against SO23-13-2, HJW 05/03/95 N/A TCN 2-20; with no changes required.
1-8 Compared against SO23-13-2, Rev. 3 HJW 08/20/96 N/A with no changes required. Changed the time to 13 minutes.
1-9 Compared against SO23-13-2, Rev. 5. RCW 08/13/98 N/A Removed JPM step 3. Reversed the order of JPM steps 17 and 18 to match the order in the procedure.
1-10 Compared against SO23-13-2, JJM 09/30/99 WLL TCN 5-2. Changed verbs verify to ensure and changed cue following step 9. JPM can be performed on any unit.
1-11 Checked against SO23-13-2, Rev. 6-3 KM 08/03/01 KR with minor rewording required.
Added use of laser pointer to setup page.
1-12 Checked against SO23-13-2, Rev. 7-3 RCW 09/01/04 AHH with minor rewording required.
Page 133 of 162
JPM: SO-05 NRC RO TITLE: Energize Class 1E 480V Bus B04 from Unit 3 JPM P-2
- Denotes a CRITICAL STEP 1-13 Compared against SO23-13-2, LRZ 02/15/05 AHH Rev. 7-3 with no changes required.
SET-UP NOTE: Provide the Examinee with a copy of SO23-13-2, Shutdown from Outside the Control Room Attachment 12, AFW Pump Local Manual Operation.
NOTE: Circle the unit on the JPM Information Sheet on which this JPM will be performed and inform the Examinee.
A working flashlight will be required and a LASER pointer would be helpful in pointing out components at P140.
Page 134 of 162
JPM: SO-05 NRC RO/SRO JPM P-3 TITLE: Manually Feed the Steam Generators with the Steam Driven Aux.
Feedpump
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)
NOTE: Provide the Examinee with a copy of SO23-13-2, Shutdown from Outside the Control Room Attachment 12, AFW Pump Local Manual Operation.
1* Open DC to HV-4716 Disconnect inside Simulates opening the disconnect switch for Start Time: _______
Panel MS-4716 (west side of MP140). DC power to 2(3) HV-4716 inside panel 2(3)MS-4716.
CUE: The switch is open.
2* Manually close HV-4716. Simulates manually closing 2(3)HV-4716 by depressing the clutch lever and rotating the handwheel clockwise.
CUE: The valve is closed.
3 Ensure Trip Rod is pulled toward Simulates pulling Trip Rod toward HV-4716 and latched. 2(3)HV-4716 and verifying Trip Rod is latched into the gripper pawl.
CUE: The hook is latched with the gripper pawl.
4 Ensure the trip plunger is fully seated Simulates opening cover on shatter shield and the flat side is toward HV-4716. over the front standard. Locate the trip plunger and indicate the plunger would be fully seated with the flat side of the washer toward 2(3)HV-4716.
CUE: The plunger is fully seated with the flat side of the washer toward 2(3)HV-4716.
Page 135 of 162
JPM: SO-05 NRC RO/SRO JPM P-3 TITLE: Manually Feed the Steam Generators with the Steam Driven Aux.
Feedpump
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 5* Open HV-4716 1-1/2 turns to roll Simulates opening 2(3)HV-4716 by rotating turbine to approximately 1800 RPM on handwheel counter-clockwise. Observes SI-4732 (Panel L-298-C). turbine speed indication on 2(3)SI-4732, AFWPT K007 Tach. Indicator on Panel 2(3)L-298-C.
CUE: Turbine speed is 1800 rpm, as indicated on 2(3)SI-4732.
6* Continue opening HV-4716; Ensure Simulates continuing to open 2(3)HV-4716 by K-007 governor controls speed at rotating handwheel counter-clockwise.
approximately 3500 RMP on SI-4732. Observes turbine speed on 2(3)HV-4732, AFWPT K007 Tach. Indicator, monitoring for the governor to control speed at 3500 RPM on panel 2(3)L-298.
CUE: Turbine speed is erratic at approximately 3500 rpm.
7* Manually close HV-4716. Simulates manually closing 2(3) HV-4716 by rotating the handwheel in the clockwise direction.
CUE: 2(3)HV-4716 is closed.
8* Open DC to K007 Governor Disconnect Simulates opening DC to K007 Governor inside panel MS-4716. Disconnect switch inside panel 2(3)MS-4716.
CUE: The disconnect switch for DC to K007 governor is open.
Page 136 of 162
JPM: SO-05 NRC RO/SRO JPM P-3 TITLE: Manually Feed the Steam Generators with the Steam Driven Aux.
Feedpump
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 9 Ensure Trip Rod is pulled toward Simulates pulling Trip Rod toward HV-4716 and latched. 2(3)HV-4716 and verifying Trip Rod is latched into the gripper pawl.
CUE: The hook is latched with the gripper pawl.
10 Ensure the trip plunger is fully seated Simulates opening cover on shatter shield and the flat side is toward HV-4716. over the front standard. Locates the trip plunger and indicates the plunger would be fully seated with the flat side of the washer toward 2(3)HV-4716.
CUE: The plunger is fully seated with the flat side of the washer toward 2(3)HV-4716.
11* Slowly throttle open HV-4716, to raise Simulates slowly opening 2(3)HV-4716 by MP-140 discharge pressure to 1350 slowly rotating handwheel in the counter-PSIG on PI-4703L, East (West) side of clockwise direction. Observes 2(3)PI-4703L P140. to monitor pump discharge pressure.
CUE: 2(3)PI-4703L indicates pump discharge pressure of 1350 psig.
12* Open HV-4706, P140 Discharge to ME- Simulates manually opening 2(3)HV-4706 by 089. depressing the clutch lever and rotating the handwheel counter-clockwise.
CUE: 2(3)HV-4706 is open.
13 Open HV-4705, P140 Discharge to ME- No action required (see CUE below).
088 (inside West RWST vault).
Page 137 of 162
JPM: SO-05 NRC RO/SRO JPM P-3 TITLE: Manually Feed the Steam Generators with the Steam Driven Aux.
Feedpump
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)
CUE: Due to personal safety considerations, 2(3)HV-4705 will not be accessed. Assume 2(3)HV-4705 is open.
CUE: Communications are established with the CO.
CUE: The CO directs you to open 2(3)HV-4730 until flow is heard.
14* Manually Open HV-4730, AFW Simulates manually opening 2(3)HV-4730 by isolation valve. depressing the clutch lever and rotating the handwheel counter-clockwise.
CUE: You hear flow.
CUE: The CO directs you to open 2(3)HV-4715 until flow is heard.
15* Manually Open HV-4715, AFW Simulates manually opening 2(3)HV-4715 by isolation valve. depressing the clutch lever and rotating the handwheel counter-clockwise.
TERMINATING CUE: Stop Time: _______
This JPM is complete.
Page 138 of 162
JPM: SO-05 NRC RO/SRO TITLE: Manually Feed the Steam Generators with JPM P-3 the Steam Driven Aux. Feedpump
- Denotes a CRITICAL STEP JPM CHECKLIST
- 1. The JPM is:
- a. X Supported by facilitys job task analysis.
- b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).
- c. X Designed as either SRO only, or RO/SRO.
- 2. Each JPM includes:
- a. X Initial conditions.
- b. X Initiating cues.
- c. X References, including associated procedures.
- d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.
- e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.
- f. X Statements describing important actions or observations that should be made by the Examinee.
- g. X Criteria for successful completion.
- h. X Identification of the critical steps and their associated performance standards.
- i. X Validated time limits (average time allowed for completion).
- j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.
COMPLETED BY: L. Zilli DATE: 02/26/05 JPM INFORMATION SHEET Page 139 of 162
JPM: SO-05 NRC RO/SRO TITLE: Manually Feed the Steam Generators with JPM P-3 the Steam Driven Aux. Feedpump
- Denotes a CRITICAL STEP JPM NUMBER SO-05 NRC SRO JPM A.1.a INITIAL PLANT CONDITIONS Unit 2 is in Mode 1.
With ME-335 CCW aligned to Unit 3, the Unit 2 Containment Emergency Cooling System Monthly Test - Train B has just been completed IAW SO23-3-3.13, Containment Cooling
/Spray Monthly Tests, Attachment 2.
TASK TO BE PERFORMED Determine OPERABILITY of the Train B Containment Emergency Cooling Units by performing the SRO Operations Supervisor review.
Page 140 of 162
JPM: SO-05 NRC RO/SRO TITLE: Manually Feed the Steam Generators with JPM P-3 the Steam Driven Aux. Feedpump
- Denotes a CRITICAL STEP JOB PERFORMANCE MEASURE SO-05 NRC SRO JPM A.1.a SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:
The operators performance was evaluated against the standards contained in this JPM and is determined to be:
SATISFACTORY:
UNSATISFACTORY:
Page 141 of 162
JPM: SO-05 NRC RO/SRO TITLE: Manually Feed the Steam Generators with JPM P-3 the Steam Driven Aux. Feedpump
- Denotes a CRITICAL STEP DOCUMENTATION SO-05 NRC SRO JPM A.1.a JPM LEVEL: SRO Only ESTIMATED TIME TO COMPLETE: 15 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CRS TASK SYS ID: 187652 TASK DESCRIPTION Authorize, supervise, and review all surveillance tests performed on shift.
KA NUMBER: 2.1.12 KA VALUES: RO N/A SRO 4.0 10CFR55.45 APPLICABILITY: 12
REFERENCES:
SO23-3-3.13, Containment Cooling/Spray Monthly Tests, Rev. 9-1 AUTHOR: L. Zilli DATE: 02/25/05 OPERATIONS REVIEW: M. Jones DATE: 03/09/05 APPROVED BY: A. Hagemeyer DATE: 03/09/05 Page 142 of 162
JPM: SO-05 NRC RO/SRO TITLE: Manually Feed the Steam Generators with JPM P-3 the Steam Driven Aux. Feedpump
- Denotes a CRITICAL STEP MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New 0-1 Modified for different error. JGA 10/27/03 KR 1 Compared against SO23-3-3.13, LRZ 02/25/05 REV Revision 9-1 with no minor changes required. Modified JPM to change to Train B and CCW Chiller ME-335 with different errors inserted.
Page 143 of 162
JPM: SO-05 NRC RO/SRO TITLE: Manually Feed the Steam Generators with JPM P-3 the Steam Driven Aux. Feedpump
- Denotes a CRITICAL STEP SET-UP NOTE: Provide a marked-up copy of SO23-3-3.13, Containment Cooling/Spray Monthly Tests, .
Page 144 of 162
JPM: SO-05 NRC SRO JPM A.1.a TITLE: Authorize, Supervise, and Review all Surveillance Tests Performed On Shift
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)
NOTE: Proved a marked-up copy of SO23-3-3.13, Containment Cooling / Spray Monthly Tests, Attachment 2.
1 Perform final SRO review of the Reviews the surveillance procedure provided. Start Time: _______
surveillance procedure.
2* Discovers error at Step 2.4.1. Discovers that the wrong space was checked.
Should have checked off Other Unit in the Train B ME-335 Emergency Chiller Supply box.
3* Discovers error at Step 2.5.4. Discovers that the CCW flow rate requirements are not met for ME-335 being aligned to other Unit. Should have checked off Other Unit in the Train B ME-335 Emergency Chiller Supply box and flow should be 2265 gpm.
4 Perform the step required for Identifies the need to:
unsatisfactory results.
- Initiate LCOAR/EDMR.
- Realign ME-335 to Unit 2.
- Re-perform this Attachment.
- Indicate action taken in the Comment Section.
TERMINATING CUE: Stop Time: _______
This JPM is complete.
Page 145 of 162
JPM: SO-05 NRC SRO JPM A.1.a TITLE: Authorize, Supervise, and Review all Surveillance Tests Performed On Shift
- Denotes a CRITICAL STEP Page 146 of 162
JPM: SO-05 NRC SRO TITLE: Authorize, Supervise, and Review all JPM A.1.a Surveillance Tests Performed On Shift
- Denotes a CRITICAL STEP JPM CHECKLIST
- 1. The JPM is:
- a. X Supported by facilitys job task analysis.
- b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).
- c. X Designed as either SRO only, or RO/SRO.
- 2. Each JPM includes:
- a. X Initial conditions.
- b. X Initiating cues.
- c. X References, including associated procedures.
- d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.
- e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.
- f. X Statements describing important actions or observations that should be made by the Examinee.
- g. X Criteria for successful completion.
- h. X Identification of the critical steps and their associated performance standards.
- i. X Validated time limits (average time allowed for completion).
- j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.
COMPLETED BY: L. Zilli DATE: 02/25/05 JPM INFORMATION SHEET Page 147 of 162
JPM: SO-05 NRC SRO TITLE: Authorize, Supervise, and Review all JPM A.1.a Surveillance Tests Performed On Shift
- Denotes a CRITICAL STEP JPM NUMBER SO-05 NRC SRO JPM A.1.b INITIAL PLANT CONDITIONS Unit 2 is in Mode 4 HOT SHUTDOWN at 340°F. At 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> on Sunday, Train A Emergency Diesel Generator 2G002 was taken out of service for scheduled maintenance. All required Technical Specification surveillances are being tracked. Maintenance should be completed at 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br /> on Monday.
You are informed at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br /> on Monday that the Train B Emergency Diesel Generator 2G003 T-338 & T-341 air receivers are out of service (pressure is 130 psig) and T-337 pressure relief valve (2PSV-5921C) is leaking by (pressure is 135 psig) and cannot be gagged.
TASK TO BE PERFORMED Determine the required ACTION(s) per Technical Specifications for the problem associated with the Train B Emergency Diesel Generator 2G003, and Determine if a heatup can be completed to a Mode 3 temperature of 400°F at this time.
Page 148 of 162
JPM: SO-05 NRC SRO TITLE: Authorize, Supervise, and Review all JPM A.1.a Surveillance Tests Performed On Shift
- Denotes a CRITICAL STEP JOB PERFORMANCE MEASURE SO-05 NRC SRO JPM A.1.b SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:
The operators performance was evaluated against the standards contained in this JPM and is determined to be:
SATISFACTORY:
UNSATISFACTORY:
Page 149 of 162
JPM: SO-05 NRC SRO TITLE: Authorize, Supervise, and Review all JPM A.1.a Surveillance Tests Performed On Shift
- Denotes a CRITICAL STEP DOCUMENTATION SO-05 NRC SRO JPM A.1.b JPM LEVEL: SRO Only ESTIMATED TIME TO COMPLETE: 10 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CRS / SM TASK SYS ID: 192875 TASK DESCRIPTION Ensure compliance with Technical Specifications and other regulatory requirements.
KA NUMBER: 2.1.12 KA VALUES: RO N/A SRO 4.0 10CFR55.45 APPLICABILITY: 12
REFERENCES:
Technical Specifications 3.0.4 (page 3.0-5) and 3.8.1 (page 3.8-3).
Diesel Air Start P&ID 40110F, Revision 3 AUTHOR: L. Zilli DATE: 07/10/00 OPERATIONS REVIEW: M. Jones DATE: 08/02/00 APPROVED BY: W. Lyke DATE: 08/04/00 Page 150 of 162
JPM: SO-05 NRC SRO TITLE: Authorize, Supervise, and Review all JPM A.1.a Surveillance Tests Performed On Shift
- Denotes a CRITICAL STEP MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New - - -
0-1 Compared against current Technical LRZ 02/15/05 AHH Specifications with no changes required.
Page 151 of 162
JPM: SO-05 NRC SRO TITLE: Authorize, Supervise, and Review all JPM A.1.a Surveillance Tests Performed On Shift
- Denotes a CRITICAL STEP SET-UP NOTE: Provide the examinee with a copy of the Diesel Air Start P&ID (40110F). Ensure that Technical Specifications are available for the examinee to use.
Page 152 of 162
JPM: SO-05 NRC SRO JPM A.1.b TITLE: Determine Technical Specifications and Requirements for a Technical Specification Mode Change
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)
NOTE: Provide the examinee with a copy of Diesel Air Start P&ID (40110F).
NOTE: Examinee may reference Technical Specifications during performance of this JPM.
1* Determine the action required per Determines that both EDGs are inoperable Start Time: _______
Technical Specifications. and Technical Specification 3.8.1.E requires restoration of one EDG to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
2* Determine if a heatup can be completed Determines that a heatup can not be to a temperature of 400°F prior to completed prior to returning the EDGs to returning the EDGs to OPERABLE OPERABLE status per Technical status. Specification 3.0.4 which prohibits entry into another Mode when an LCO is not met.
TERMINATING CUE: Stop Time: _______
This JPM is complete.
Page 153 of 162
JPM: SO-05 NRC SRO TITLE: Determine Technical Specifications and JPM A.1.b Requirements for a Technical Specification Mode Change
- Denotes a CRITICAL STEP JPM CHECKLIST
- 1. The JPM is:
- a. X Supported by facilitys job task analysis.
- b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).
- c. X Designed as either SRO only, or RO/SRO.
- 2. Each JPM includes:
- a. X Initial conditions.
- b. X Initiating cues.
- c. X References, including associated procedures.
- d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.
- e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.
- f. X Statements describing important actions or observations that should be made by the Examinee.
- g. X Criteria for successful completion.
- h. X Identification of the critical steps and their associated performance standards.
- i. X Validated time limits (average time allowed for completion).
- j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.
COMPLETED BY: L. Zilli DATE: 02/15/05 JPM INFORMATION SHEET Page 154 of 162
JPM: SO-05 NRC SRO TITLE: Determine Technical Specifications and JPM A.1.b Requirements for a Technical Specification Mode Change
- Denotes a CRITICAL STEP JPM NUMBER SO-05 NRC SRO JPM A.2 INITIAL PLANT CONDITIONS The Boric Acid Makeup Pump 2MP174 has recently been overhauled and is ready to be aligned for return to service.
TASK TO BE PERFORMED The Shift Manager directs you to review the Return to Service WAM and report your finding when complete.
Page 155 of 162
JPM: SO-05 NRC SRO TITLE: Determine Technical Specifications and JPM A.1.b Requirements for a Technical Specification Mode Change
- Denotes a CRITICAL STEP JOB PERFORMANCE MEASURE SO-05 NRC SRO JPM A.2 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:
The operators performance was evaluated against the standards contained in this JPM and is determined to be:
SATISFACTORY:
UNSATISFACTORY:
Page 156 of 162
JPM: SO-05 NRC SRO TITLE: Determine Technical Specifications and JPM A.1.b Requirements for a Technical Specification Mode Change
- Denotes a CRITICAL STEP DOCUMENTATION SO-05 NRC SRO JPM A.2 JPM LEVEL: SRO only ESTIMATED TIME TO COMPLETE: 30 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: SM TASK SYS ID: 182220 TASK DESCRIPTION Manage the control of equipment status.
KA NUMBER: 2.2.13 KA VALUES: RO 3.6 SRO 3.8 10CFR55.45 APPLICABILITY: 13
REFERENCES:
SO123-XX-5, Work authorizations, Revision 13-1 SO23-3-2.2, Makeup Operations, Revision 18 Boric Acid Makeup P&ID #40125A, Revision 14 Boric Acid Makeup P&ID #40125B, Revision 17 480 V Load Center Bus 2BY One Line Diagram #30162, Revision 32 AUTHOR: R. Clement DATE: 09/02/00 OPERATIONS REVIEW: K. Rauch DATE: 09/04/00 APPROVED BY: W. Lyke DATE: 09/05/00 Page 157 of 162
JPM: SO-05 NRC SRO TITLE: Determine Technical Specifications and JPM A.1.b Requirements for a Technical Specification Mode Change
- Denotes a CRITICAL STEP MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New 0-1 Compared against SO123-XX-5, LRZ 03/14/05 AHH Revision 13-1 and the P&IDs with no changes required.
Page 158 of 162
JPM: SO-05 NRC SRO TITLE: Determine Technical Specifications and JPM A.1.b Requirements for a Technical Specification Mode Change
- Denotes a CRITICAL STEP SET-UP Prepare a Work Authorization Return to Service WAM that is complete up to the SRO review of the Return to Service WAM sheet. Include errors associated with the Return to Service WAM sheet.
Obtain P&IDs for:
- Boric Acid Makeup Pump #40125A
- Boric Acid Makeup Pump #40125B Obtain One-Line Diagram for:
- 480 V Load Center Bus 2BY #30162 The P&IDs should be prepared as follows:
- Highlight in BLUE the problem area(s)
- Highlight in YELLOW the Cleared line(s)
- Highlight in RED the isolation area(s)
The completed Return to Service List should be prepared as follows:
- Obtain a CLOSED Work Authorization Record (WAR). Use WAR 2-0400636.
- Modify the WAR to include errors as listed in the JPM body by cutting and pasting.
NOTE: Provide the examinee with a copy of SO123-XX-5, Work Authorizations, the applicable P&IDs and drawings, and the completed Work Authorization Record for the Boric Acid Makeup Pump S21218MP174.
Page 159 of 162
JPM: SO-05 NRC SRO JPM A.2 TITLE: Review the Return to Service WAM List of a Completed Work Authorization
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)
NOTE: The following steps may be performed in a sequence other than indicated below.
NOTE: Provide the examinee with a copy of SO123-XX-5, the completed Return to Service WAM List (with errors), SO23-3.2.2, Makeup Operations and copies of highlighted P&IDs and Electrical Print when located.
1 Check the Equipment ID, Equipment Checks the Equipment ID, Equipment Start Time: _______
Description and Work Description. Description and Work Description on the WAR to compare with the information on the Tagging List and the applicable drawings.
2 Check the Work Authorization Numbers Checks the Work Authorization Numbers match for each page of the Request. match on each page of the Request.
3* Examine the Return to Service (RTS) Examines the adequacy and accuracy of the WAM to determine if it is correct and RTS alignment and identifies:
adequate for system restoration.
- S21218MU036 should be LOCKED OPEN.
- S21218MU007 should be LOCKED OPEN.
- S21218MU040 should be OPEN.
Page 160 of 162
JPM: SO-05 NRC SRO JPM A.2 TITLE: Review the Return to Service WAM List of a Completed Work Authorization
- Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 4 Report to the Shift Manager the Reports to the Shift Manager the incorrect incorrect Return to Service alignment Return to Service alignment and returns the and return the WAM Installation Sheet WAM Installation Sheet without signature.
without signature.
TERMINATING CUE: Stop Time: _______
This JPM is complete.
Page 161 of 162
JPM CHECKLIST
- 1. The JPM is:
- a. X Supported by facilitys job task analysis.
- b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).
- c. X Designed as either SRO only, or RO/SRO.
- 2. Each JPM includes:
- a. X Initial conditions.
- b. X Initiating cues.
- c. X References, including associated procedures.
- d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.
- e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.
- f. X Statements describing important actions or observations that should be made by the Examinee.
- g. X Criteria for successful completion.
- h. X Identification of the critical steps and their associated performance standards.
- i. X Validated time limits (average time allowed for completion).
- j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.
COMPLETED BY: L. Zilli DATE: 03/11/05 Page 162 of 162