ML14049A019: Difference between revisions
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{{#Wiki_filter:JPM RO A1a 1 OPERATOR: | {{#Wiki_filter:JPM RO A1a 1 OPERATOR: ________________________________ | ||
________________________________ | |||
RO DATE: | RO DATE: | ||
JPM NUMBER: | JPM NUMBER: | ||
RO | RO A 1a TASK NUMBER: | ||
Conduct of Operations | Conduct of Operations | ||
Line 33: | Line 32: | ||
. | . | ||
LOCATION OF PERFORMANCE: | LOCATION OF PERFORMANCE: | ||
Simulator | Simulator REFERENCES/PROCEDURES NEEDED: | ||
REFERENCES/PROCEDURES NEEDED: | |||
3-SR-2, Instrument Checks and Observations VALIDATION TIME: | 3-SR-2, Instrument Checks and Observations VALIDATION TIME: | ||
30 minutes | 30 minutes PERFORMANCE TIME: | ||
PERFORMANCE TIME: | |||
COMMENTS: | COMMENTS: | ||
__________________________________________________________ | __________________________________________________________ | ||
Line 67: | Line 62: | ||
JPM RO A1a 3 ******************************************************************************* | JPM RO A1a 3 ******************************************************************************* | ||
Simulator | Simulator ******************************************************************************* | ||
INITIAL CONDITIONS | INITIAL CONDITIONS | ||
: You are a Unit Operator assigned to Unit 3, and it is Friday morning at 0800. 3-SR-2, Instrument Checks and Observations, is being performed. | : You are a Unit Operator assigned to Unit 3, and it is Friday morning at 0800. 3-SR-2, Instrument Checks and Observations, is being performed. | ||
Line 77: | Line 71: | ||
All readings that are already completed are correct and need not be checked by you. | All readings that are already completed are correct and need not be checked by you. | ||
JPM RO A1a 4 START TIME | JPM RO A1a 4 START TIME | ||
******************************************************************************* | ******************************************************************************* | ||
Performance Step 1: Critical X Not Critical (1) Whenever there is fuel in the reactor vessel and the continuous conductivity monitor is inoperable, periodic analysis of reactor coolant samples are required by the Technical Requirements Manual. If the reactor coolant continuous conductivity monitor becomes inoperable, notify Chemistry to sample according to 3 | Performance Step 1: Critical X Not Critical (1) Whenever there is fuel in the reactor vessel and the continuous conductivity monitor is inoperable, periodic analysis of reactor coolant samples are required by the Technical Requirements Manual. If the reactor coolant continuous conductivity monitor becomes inoperable, notify Chemistry to sample according to 3 | ||
-SI-4.6.B.1-4. Standard: Records a Reactor Coolant Conductivity reading of .057 or .058 µmho. Initials under UO. | -SI-4.6.B.1-4. Standard: Records a Reactor Coolant Conductivity reading of .057 or .058 µmho. Initials under UO. | ||
SAT UNSAT N/A COMMENTS: | SAT UNSAT N/A COMMENTS: | ||
JPM RO A1a 5 ******************************************************************************* | JPM RO A1a 5 ******************************************************************************* | ||
Performance Step 2: Critical X Not Critical (1) The difference between readings of 3 | Performance Step 2: Critical X Not Critical (1) The difference between readings of 3 | ||
-LI-64-54A and 3 | -LI-64-54A and 3-LI-64-66 should not exceed 2 inches. Deviations greater than 2 inches should be investigated. | ||
-LI-64-66 should not exceed 2 inches. Deviations greater than 2 inches should be investigated. | |||
(2) The Technical Specification requirements for Suppression Pool Water Level are --1.0" with DW to Torus --1.0" without DW to Torus DP established. | (2) The Technical Specification requirements for Suppression Pool Water Level are --1.0" with DW to Torus --1.0" without DW to Torus DP established. | ||
Standard: | Standard: Records a Suppression Pool Level of (-) 2.75 inches; plus or minus 0.5 inches in both columns. Initials under UO. | ||
Records a Suppression Pool Level of ( | |||
-) 2.75 inches; plus or minus 0.5 inches in both columns. Initials under UO. | |||
SAT UNSAT N/A COMMENTS: | SAT UNSAT N/A COMMENTS: | ||
JPM RO A1a 6 ******************************************************************************* | JPM RO A1a 6 ******************************************************************************* | ||
Performance Step 3: Critical X Not Critical (1) The required observation of Bulk Volumetric Average Drywell Air Temperature may be obtained from ICS Pt TEST2500 OR 3 | Performance Step 3: Critical X Not Critical (1) The required observation of Bulk Volumetric Average Drywell Air Temperature may be obtained from ICS Pt TEST2500 OR 3 | ||
Line 100: | Line 88: | ||
(2) It may be necessary to have Instrument Maintenance turn on the "BULK VOLUMETRIC AVERAGE DRYWELL AIR TEMPERATURE" on 3 | (2) It may be necessary to have Instrument Maintenance turn on the "BULK VOLUMETRIC AVERAGE DRYWELL AIR TEMPERATURE" on 3 | ||
-TR-80-1 to allow the point to be displayed. | -TR-80-1 to allow the point to be displayed. | ||
Standard: | Standard: Records a Drywell Air Temperature from ICS of 1 04.1 °F; plus or minus 0.1 °F in the column under ICS Pt TEST2500. Initials under UO. | ||
Records a Drywell Air Temperature from ICS of 1 04.1 °F; plus or minus 0.1 °F in the column under ICS Pt TEST2500. Initials under UO. | |||
SAT UNSAT N/A COMMENTS: | SAT UNSAT N/A COMMENTS: | ||
JPM RO A1a 7 ******************************************************************************* | JPM RO A1a 7 ******************************************************************************* | ||
Line 109: | Line 96: | ||
- Suppression Chamber Differential pressure of 1.1 to 1.2 psid in both columns. Initials under UO. | - Suppression Chamber Differential pressure of 1.1 to 1.2 psid in both columns. Initials under UO. | ||
SAT UNSAT N/A COMMENTS: | SAT UNSAT N/A COMMENTS: | ||
JPM RO A1a 8 *************************************************************** | JPM RO A1a 8 *************************************************************** | ||
**************** | **************** | ||
Line 125: | Line 111: | ||
(4) If both the primary and secondary indication of any SRV tailpipe is inoperable, per Technical Requirements Manual 3.3.5, the Suppression Pool Water Temperature must be monitored at least once per shift to observe any unexplained temperature rise which might be indicative of an open SRV. | (4) If both the primary and secondary indication of any SRV tailpipe is inoperable, per Technical Requirements Manual 3.3.5, the Suppression Pool Water Temperature must be monitored at least once per shift to observe any unexplained temperature rise which might be indicative of an open SRV. | ||
Standard: | Standard: Records Suppression Pool Water Temperature of 87.5 °F; plus or minus 2.5 °F in all 4 -3. Initials under UO. | ||
Records Suppression Pool Water Temperature of 87.5 °F; plus or minus 2.5 °F in all 4 -3. Initials under UO. | |||
SAT UNSAT N/A COMMENTS: | SAT UNSAT N/A COMMENTS: | ||
JPM RO A1a 9 ******************************************************************************* | JPM RO A1a 9 ******************************************************************************* | ||
Performance Step 6: *Critical X Not Critical (1) Each pressure indicator provides indication of the discharge pressure for one RHR or Core Spray Loop. The instrument chec k will consist of observing that the instrument exhibits an expected reading for the given plant conditions. (2) The Technical Requirements Manual requires a minimum discharge pressure for OPERABLE subsystems. Refer To TRM Section 3.5.4. | Performance Step 6: *Critical X Not Critical (1) Each pressure indicator provides indication of the discharge pressure for one RHR or Core Spray Loop. The instrument chec k will consist of observing that the instrument exhibits an expected reading for the given plant conditions. (2) The Technical Requirements Manual requires a minimum discharge pressure for OPERABLE subsystems. Refer To TRM Section 3.5.4. | ||
CS Loop I PI-75-20 CS Loop II PI-75-48 RHR Loop I PI-74-51 48 psig RHR Loop II PI-74-65 35 | CS Loop I PI-75-20 CS Loop II PI-75-48 RHR Loop I PI-74-51 48 psig RHR Loop II PI-74-65 35 ps ig (3) MAX criteria is N/A for RHR/Core Spray subsystems in service or if keep fill aligned to CS & S. When a RHR/Core Spray subsystem is in a standby readiness condition the maximum discharge pressure is 100 psig. High discharge pressures with pumps secured may be indication of primary valve leakage. | ||
Standard: | Standard: *Records a CS Loop I Fill Pressure of 50 psig (+) 5 psig and for *CS Loop II Discharge Fill Pressure of 50 psig (+) 5 psig. *Records a RHR Loop I Discharge Fill Pressure of 40 psig; | ||
+) 5 psig and for *CS Loop II Discharge Fill Pressure of 50 psig ( | |||
+) 5 psig. *Records a RHR Loop I Discharge Fill Pressure of 40 psig; | |||
(+) 5 psig. Records NA or 270 psig for RHR Loop II because it is in Shutdown Cooling. Initials under UO. *Informs Unit Supervisor that RHR Loop I discharge pressure is less than the minimum required discharge pressure of 48 psig. | (+) 5 psig. Records NA or 270 psig for RHR Loop II because it is in Shutdown Cooling. Initials under UO. *Informs Unit Supervisor that RHR Loop I discharge pressure is less than the minimum required discharge pressure of 48 psig. | ||
SAT UNSAT N/A COMMENTS: | SAT UNSAT N/A COMMENTS: | ||
Line 143: | Line 124: | ||
(3) To be considered as In Service, RHR System and its associated Shutdown Cooling Subsystems must be in the Shutdown Cooling Mode alignment with RHR SD CLG FLOW LOW annunciator (3 | (3) To be considered as In Service, RHR System and its associated Shutdown Cooling Subsystems must be in the Shutdown Cooling Mode alignment with RHR SD CLG FLOW LOW annunciator (3 | ||
-XA-55-3D, Window 11) RESET. | -XA-55-3D, Window 11) RESET. | ||
Standard: | Standard: Places an X under RR Pump B for being in service and an X under RHR Shutdown Cooling Subsystem D for being in service. Records SAT in all data Column. Initials under UO. | ||
Places an X under RR Pump B for being in service and an X under RHR Shutdown Cooling Subsystem D for being in service. Records SAT in all data Column. Initials under UO. | |||
SAT UNSAT N/A COMMENTS: | SAT UNSAT N/A COMMENTS: | ||
JPM RO A1a 11 ******************************************************************************* | JPM RO A1a 11 ******************************************************************************* | ||
Performance Step 8: Critical X Not Critical Standard: | Performance Step 8: Critical X Not Critical Standard: Records Reactor Zone Exhaust Radiation Monitor readings of 1.0 mr/hr for both RM | ||
Records Reactor Zone Exhaust Radiation Monitor readings of 1.0 mr/hr for both RM | |||
--142 and RM | --142 and RM | ||
--143; plus or minus 0.5 mr/hr for Detector A and B. Records Refuel Zone Exhaust Radiation Monitor readings of 26.0 mr/hr for RM | --143; plus or minus 0.5 mr/hr for Detector A and B. Records Refuel Zone Exhaust Radiation Monitor readings of 26.0 mr/hr for RM | ||
Line 155: | Line 133: | ||
--141 records reading of 50 mr/hr; plus or minus 1 mr/hr for Detector A and B. Initials under UO. Informs Unit Supervisor that Refuel Zone Exhaust Radiation Monitors are outside the MAX deviation of 20 mr/hr. | --141 records reading of 50 mr/hr; plus or minus 1 mr/hr for Detector A and B. Initials under UO. Informs Unit Supervisor that Refuel Zone Exhaust Radiation Monitors are outside the MAX deviation of 20 mr/hr. | ||
SAT UNSAT N/A COMMENTS: | SAT UNSAT N/A COMMENTS: | ||
JPM RO A1a 12 ******************************************************************************* | JPM RO A1a 12 ******************************************************************************* | ||
Performance Step | Performance Step | ||
: *Critical X Not Critical (1) The instrument check will consist of observing that the instruments exhibit an expected reading for the given plant conditions. MAX will be the alarm (RHRSW/RCW EFFLUENT RADIATION HIGH 3-RA--132 (Panel 3 | : *Critical X Not Critical (1) The instrument check will consist of observing that the instruments exhibit an expected reading for the given plant conditions. MAX will be the alarm (RHRSW/RCW EFFLUENT RADIATION HIGH 3-RA--132 (Panel 3 | ||
--3, 3-XA-55-3A, Window 3)) setpoint for the respective monitor. Instrument Shop should be contacted for most current setpoints as required. | --3, 3-XA-55-3A, Window 3)) setpoint for the respective monitor. Instrument Shop should be contacted for most current setpoints as required. | ||
Standard: | Standard: Records NA for RM | ||
Records NA for RM | |||
--133 or a reading of 300 cpm. *Records a reading for RM | --133 or a reading of 300 cpm. *Records a reading for RM | ||
--134 of 300 cpm; plus or minus 10 cpm. *Records SAT in all data Column. *Initials under UO. | --134 of 300 cpm; plus or minus 10 cpm. *Records SAT in all data Column. *Initials under UO. | ||
Line 170: | Line 146: | ||
STOP TIME | STOP TIME | ||
JPM RO A1a 1 OPERATOR: | JPM RO A1a 1 OPERATOR: ________________________________ | ||
________________________________ | |||
RO DATE: | RO DATE: | ||
JPM NUMBER: | JPM NUMBER: | ||
RO | RO A 1a TASK NUMBER: | ||
Conduct of Operations | Conduct of Operations | ||
Line 187: | Line 162: | ||
: 2. Verify acceptance criteria are satisfied in accordance with notes and if not notification to Unit Supervisor is completed | : 2. Verify acceptance criteria are satisfied in accordance with notes and if not notification to Unit Supervisor is completed | ||
. LOCATION OF PERFORMANCE: | . LOCATION OF PERFORMANCE: | ||
Simulator REFERENCES/PROCEDURES NEEDED: | Simulator REFERENCES/PROCEDURES NEEDED: | ||
2-SR-2, Instrument Checks and Observations VALIDATION TIME: | 2-SR-2, Instrument Checks and Observations VALIDATION TIME: | ||
30 minutes | 30 minutes PERFORMANCE TIME: | ||
PERFORMANCE TIME: | |||
COMMENTS: | COMMENTS: | ||
__________________________________________________________ | __________________________________________________________ | ||
Line 214: | Line 187: | ||
The plant is in MODE 3. | The plant is in MODE 3. | ||
INITIATING CUE: The Unit Supervisor directs you as the Unit Operator to complete a portion of 2-SR-2 day shift checks and observations Attachment 2 Surveillance Procedure Data Package Modes 1, 2, and 3 (pages 1 8 of 90 to | INITIATING CUE: The Unit Supervisor directs you as the Unit Operator to complete a portion of 2-SR-2 day shift checks and observations Attachment 2 Surveillance Procedure Data Package Modes 1, 2, and 3 (pages 1 8 of 90 to 2 7 of 90) for Friday at 0800. | ||
All readings that are already completed are correct and need not be checked by you. | All readings that are already completed are correct and need not be checked by you. | ||
JPM RO A1a 3 ******************************************************************************* | JPM RO A1a 3 ******************************************************************************* | ||
Simulator | Simulator ******************************************************************************* | ||
INITIAL CONDITIONS | INITIAL CONDITIONS | ||
: You are a Unit Operator assigned to Unit 2, and it is Friday morning at 0800. 2-SR-2, Instrument Checks and Observations, is being performed. | : You are a Unit Operator assigned to Unit 2, and it is Friday morning at 0800. 2-SR-2, Instrument Checks and Observations, is being performed. | ||
Line 229: | Line 201: | ||
All readings that are already completed are correct and need not be checked by you. | All readings that are already completed are correct and need not be checked by you. | ||
JPM RO A1a 4 START TIME | JPM RO A1a 4 START TIME | ||
******************************************************************************* | ******************************************************************************* | ||
Performance Step 1: Critical X Not Critical (1) Whenever there is fuel in the reactor vessel and the continuous conductivity monitor is inoperable, periodic analysis of reactor coolant samples are required by the Technical Requirements Manual. If the reactor coolant continuous conductivity monitor becomes inoperable, notify the Chemistry to sample according to 2 | Performance Step 1: Critical X Not Critical (1) Whenever there is fuel in the reactor vessel and the continuous conductivity monitor is inoperable, periodic analysis of reactor coolant samples are required by the Technical Requirements Manual. If the reactor coolant continuous conductivity monitor becomes inoperable, notify the Chemistry to sample according to 2 | ||
-SI-4.6.B.1-4. Standard: | -SI-4.6.B.1-4. Standard: Records a Reactor Coolant Conductivity reading of | ||
Records a Reactor Coolant Conductivity reading of | |||
.057 or .058 | .057 or .058 | ||
µmho. Initials under UO | µmho. Initials under UO | ||
. SAT UNSAT N/A COMMENTS: | . SAT UNSAT N/A COMMENTS: | ||
JPM RO A1a 5 ******************************************************************************* | JPM RO A1a 5 ******************************************************************************* | ||
Performance Step 2: Critical X Not Critical (1) The difference between readings of 2 | Performance Step 2: Critical X Not Critical (1) The difference between readings of 2 | ||
-LI-64-54A and 2 | -LI-64-54A and 2-LI-64-66 should not exceed 2 inches. Deviations greater than 2 inches should be investigated. | ||
-LI-64-66 should not exceed 2 inches. Deviations greater than 2 inches should be investigated. | |||
(2) The Technical Specification requirements for Suppression Pool Water Level are --1.0" with DW to Torus --1.0" without DW to Torus DP established. | (2) The Technical Specification requirements for Suppression Pool Water Level are --1.0" with DW to Torus --1.0" without DW to Torus DP established. | ||
Standard: | Standard: Records a Suppression Pool Level of | ||
Records a Suppression Pool Level of | |||
(-) 1 to (-) 2 inches in both columns. | (-) 1 to (-) 2 inches in both columns. | ||
Initials under UO | Initials under UO | ||
Line 254: | Line 221: | ||
(2) It may be necessary to have Instrument Maintenance turn on the "BULK VOLUMETRIC AVERAGE DRYWELL AIR TEMPERATURE" on 2 | (2) It may be necessary to have Instrument Maintenance turn on the "BULK VOLUMETRIC AVERAGE DRYWELL AIR TEMPERATURE" on 2 | ||
-TR-80-1 to allow the point to be displayed. | -TR-80-1 to allow the point to be displayed. | ||
Standard: | Standard: Records a Drywell Air Temperature from ICS of 1 02.4 °F or 102.5 °F in the column under ICS Pt TEST2500. Initials under UO. | ||
Records a Drywell Air Temperature from ICS of 1 02.4 °F or 102.5 °F in the column under ICS Pt TEST2500. Initials under UO. | |||
SAT UNSAT N/A COMMENTS: | SAT UNSAT N/A COMMENTS: | ||
JPM RO A1a 7 ******************************************************************************* | JPM RO A1a 7 ******************************************************************************* | ||
Performance Step 4: Critical Not Critical X (1) Acceptance Criteria is not required to be met until 24 hours after THERMAL POWER is > 15% RTP following startup, TO 24 hours prior to reducing THERMAL POWER to | Performance Step 4: Critical Not Critical X (1) Acceptance Criteria is not required to be met until 24 hours after THERMAL POWER is > 15% RTP following startup, TO 24 hours prior to reducing THERMAL POWER to | ||
Line 263: | Line 228: | ||
(2) The Drywell | (2) The Drywell | ||
-Suppression Chamber Differential Pressure should not exceed 1.33 psid. | -Suppression Chamber Differential Pressure should not exceed 1.33 psid. | ||
Standard: | Standard: Records a Drywell - Suppression Chamber Differential pressure of 1.1 5 to 1.2 psid in both columns. Initials under UO | ||
Records a Drywell - Suppression Chamber Differential pressure of 1. | |||
. SAT UNSAT N/A COMMENTS: | . SAT UNSAT N/A COMMENTS: | ||
JPM RO A1a 8 ******************************************************************************* | JPM RO A1a 8 ******************************************************************************* | ||
Performance Step 5: Critical X Not Critical NOTES ARE ON THE FOLLOWING PAGE! | Performance Step 5: Critical X Not Critical NOTES ARE ON THE FOLLOWING PAGE! | ||
Line 280: | Line 243: | ||
-SR-3.6.2.1.1. | -SR-3.6.2.1.1. | ||
(4) If both the primary and secondary indication of any SRV tailpipe is inoperable, per Technical Requirements Manual 3.3.5, the Suppression Pool Water Temperature must be monitored at least once per shift to observe any unexplained temperature rise which might be indicative of an open SRV. | (4) If both the primary and secondary indication of any SRV tailpipe is inoperable, per Technical Requirements Manual 3.3.5, the Suppression Pool Water Temperature must be monitored at least once per shift to observe any unexplained temperature rise which might be indicative of an open SRV. | ||
Standard: | Standard: Records Suppression Pool Water Temperature of 8 7.5 °F; plus or minus 2 °F in all 4 columns under Panel 9 | ||
Records Suppression Pool Water Temperature of 8 7.5 °F; plus or minus 2 °F in all 4 columns under Panel 9 | |||
-3. Initials under UO. | -3. Initials under UO. | ||
SAT UNSAT N/A COMMENTS: | SAT UNSAT N/A COMMENTS: | ||
JPM RO A1a 10 ******************************************************************************* | JPM RO A1a 10 ******************************************************************************* | ||
Performance Step 6: *Critical X Not Critical (1) Each pressure indicator provides indication of the discharge pressure for one RHR or Core Spray Loop. The instrument check will consist of observing that the instrument exhibits an expected reading for the given plant conditions. | Performance Step 6: *Critical X Not Critical (1) Each pressure indicator provides indication of the discharge pressure for one RHR or Core Spray Loop. The instrument check will consist of observing that the instrument exhibits an expected reading for the given plant conditions. | ||
Line 290: | Line 251: | ||
(2) The Technical Requirements Manual requires a minimum discharge pressure for OPERABLE subsystems. Refer to TRM Section 3.5.4. | (2) The Technical Requirements Manual requires a minimum discharge pressure for OPERABLE subsystems. Refer to TRM Section 3.5.4. | ||
CS Loop I PI-75-20 39 psig CS Loop II PI-75-48 39 psig RHR Loop I PI-74-51 48 psig RHR Loop II PI-74-65 35 psig (3) MAX criteria are N/A for RHR/Core Spray subsystems in service or if keep fill aligned to CS & S. When a RHR/Core Spray subsystem is in a standby readiness condition the maximum discharge pressure is 100 psig. High discharge pressures with pumps secured may be indication of primary valve leakage. | CS Loop I PI-75-20 39 psig CS Loop II PI-75-48 39 psig RHR Loop I PI-74-51 48 psig RHR Loop II PI-74-65 35 psig (3) MAX criteria are N/A for RHR/Core Spray subsystems in service or if keep fill aligned to CS & S. When a RHR/Core Spray subsystem is in a standby readiness condition the maximum discharge pressure is 100 psig. High discharge pressures with pumps secured may be indication of primary valve leakage. | ||
Standard: | Standard: *Records a CS Loop I Fill Pressure of 50 psig (+) 5 psig and for *CS Loop II Discharge Fill Pressure of 4 5 psig (+) 5 psig. *Records a RHR Loop I Discharge Fill Pressure of 4 2.5 psig; plus 5 psig or minus 2.5 psig but less than 48 psig. Records NA or 270 psig for RHR Loop II because it is in Shutdown Cooling. Initials under UO. | ||
+) 5 psig and for *CS Loop II Discharge Fill Pressure of 4 5 psig (+) 5 psig. *Records a RHR Loop I Discharge Fill Pressure of 4 2.5 psig; plus 5 psig or minus 2.5 psig but less than 48 psig. Records NA or 270 psig for RHR Loop II because it is in Shutdown Cooling. Initials under UO. | |||
*Informs Unit Supervisor that RHR Loop I discharge pressure is less than the minimum required discharge pressure of 48 psig. SAT UNSAT N/A COMMENTS: | *Informs Unit Supervisor that RHR Loop I discharge pressure is less than the minimum required discharge pressure of 48 psig. SAT UNSAT N/A COMMENTS: | ||
JPM RO A1a 11 ******************************************************************************* | JPM RO A1a 11 ******************************************************************************* | ||
Performance Step 7: Critical X Not Critical (1) Technical Specification LCO 3.4.7 requires that two RHR Shutdown Cooling Subsystems be operable during this applicability. An operable Shutdown Cooling Subsystem consists of one RHR pump, associated heat exchanger, RHRSW pump capable of providing cooling water to its associated heat exchanger, associated piping and valves, all of which can be aligned in the Shutdown Cooling Mode for the removal of decay heat. | Performance Step 7: Critical X Not Critical (1) Technical Specification LCO 3.4.7 requires that two RHR Shutdown Cooling Subsystems be operable during this applicability. An operable Shutdown Cooling Subsystem consists of one RHR pump, associated heat exchanger, RHRSW pump capable of providing cooling water to its associated heat exchanger, associated piping and valves, all of which can be aligned in the Shutdown Cooling Mode for the removal of decay heat. | ||
Line 300: | Line 258: | ||
(3) To be considered as In Service, RHR System and its associated Shutdown Cooling Subsystems must be in the Shutdown Cooling Mode alignment with RHR SD CLG FLOW LOW annunciator (2 | (3) To be considered as In Service, RHR System and its associated Shutdown Cooling Subsystems must be in the Shutdown Cooling Mode alignment with RHR SD CLG FLOW LOW annunciator (2 | ||
-XA-55-3D, Window 11) is reset. | -XA-55-3D, Window 11) is reset. | ||
Standard: | Standard: Places an X under RR Pump B for being in service and an X under RHR Shutdown Cooling Subsystem D for being in service. Records SAT in all data Column. Initials under UO. | ||
Places an X under RR Pump B for being in service and an X under RHR Shutdown Cooling Subsystem D for being in service. Records SAT in all data Column. Initials under UO. | |||
SAT UNSAT N/A COMMENTS: | SAT UNSAT N/A COMMENTS: | ||
JPM RO A1a 12 ******************************************************************************* | JPM RO A1a 12 ******************************************************************************* | ||
Performance Step 8: Critical X Not Critical Standard: | Performance Step 8: Critical X Not Critical Standard: Records Reactor Zone Exhaust Radiation Monitor readings of 1.0 mr/hr for both RM 142 and RM 143; plus or minus 0.5 mr/hr for Detector A and B. Records Refuel Zone Exhaust Radiation Monitor readings of 26.0 mr/hr for RM 140; plus or minus 1.0 mr/hr for Detector A and B. For RM 141 records reading of 50 mr/hr; plus or minus 1 mr/hr for Detector A and B. Initials under UO. Informs Unit Supervisor that Refuel Zone Exhaust Radiation Monitors are outside the MAX deviation of 20 mr/hr. SAT UNSAT N/A COMMENTS: | ||
Records Reactor Zone Exhaust Radiation Monitor readings of 1.0 mr/hr for both RM 142 and RM 143; plus or minus 0.5 mr/hr for Detector A and B. Records Refuel Zone Exhaust Radiation Monitor readings of 26.0 mr/hr for RM 140; plus or minus 1.0 mr/hr for Detector A and B. For RM 141 records reading of 50 mr/hr; plus or minus 1 mr/hr for Detector A and B. Initials under UO. Informs Unit Supervisor that Refuel Zone Exhaust Radiation Monitors are outside the MAX deviation of 20 mr/hr. | |||
SAT UNSAT N/A COMMENTS: | |||
JPM RO A1a 13 ******************************************************************************* | JPM RO A1a 13 ******************************************************************************* | ||
Performance Step 9: *Critical X Not Critical (1) The instrument check will consist of observing that the instruments exhibit an expected reading for the given plant conditions. MAX will be the alarm (RHRSW/RCW EFFLUENT RADIATION HIGH 2-RA-90-132 (Panel 2 3, 2-XA-55-3A, Window 3)) setpoint for the respective monitor. Instrument Shop should be contacted for most current setpoints as required. | Performance Step 9: *Critical X Not Critical (1) The instrument check will consist of observing that the instruments exhibit an expected reading for the given plant conditions. MAX will be the alarm (RHRSW/RCW EFFLUENT RADIATION HIGH 2-RA-90-132 (Panel 2 3, 2-XA-55-3A, Window 3)) setpoint for the respective monitor. Instrument Shop should be contacted for most current setpoints as required. | ||
Standard: | Standard: Records NA for RM 133 or a reading of 300 cpm. *Records a reading for RM 134 of 300 cpm; plus or minus 10 cpm. *Records SAT in all data Column. | ||
Records NA for RM 133 or a reading of 300 cpm. *Records a reading for RM 134 of 300 cpm; plus or minus 10 cpm | |||
. *Records SAT in all data Column. | |||
*Initials under UO. | *Initials under UO. | ||
SAT UNSAT N/A COMMENTS: | SAT UNSAT N/A COMMENTS: | ||
END OF TASK | END OF TASK | ||
STOP TIME | STOP TIME | ||
JPM RO A1b 1 OPERATOR: | JPM RO A1b 1 OPERATOR: ________________________________ | ||
________________________________ | |||
RO DATE: | RO DATE: | ||
JPM NUMBER: | JPM NUMBER: | ||
RO | RO A 1b TASK NUMBER: | ||
U-078-AB-01 TASK TITLE: | U-078-AB-01 TASK TITLE: | ||
Calculate Time to Reach Temperature Targets for Loss of Fuel Pool Cooling K/A NUMBER: | Calculate Time to Reach Temperature Targets for Loss of Fuel Pool Cooling K/A NUMBER: | ||
2.1.25 K/A RATING: RO 3.9 TASK STANDARD: | 2.1.25 K/A RATING: RO 3.9 TASK STANDARD: | ||
Complet e of SRM Operability surveillance and determine if core alterations may commence. | |||
LOCATION OF PERFORMANCE: | LOCATION OF PERFORMANCE: | ||
Simulator REFERENCES/PROCEDURES NEEDED: | Simulator REFERENCES/PROCEDURES NEEDED: | ||
2-AOI-78-1, Fuel Pool Cleanup System Failure VALIDATION TIME: | 2-AOI-78-1, Fuel Pool Cleanup System Failure VALIDATION TIME: | ||
10 minutes PERFORMANCE TIME: | 10 minutes PERFORMANCE TIME: | ||
Line 357: | Line 306: | ||
°F in accordance with 2-AOI-78-1 step 3.7 | °F in accordance with 2-AOI-78-1 step 3.7 | ||
. | . | ||
JPM RO | JPM RO A 1b 3 ******************************************************************************* | ||
Simulator | Simulator ************************************************************************ | ||
******* INITIAL CONDITIONS | ******* INITIAL CONDITIONS | ||
: You are a Reactor Operator on Unit 2. The RBCCW sectionalizing valve has failed closed. The Unit Supervisor has entered 2 | : You are a Reactor Operator on Unit 2. The RBCCW sectionalizing valve has failed closed. The Unit Supervisor has entered 2 | ||
Line 370: | Line 318: | ||
. | . | ||
JPM RO | JPM RO A 1b 4 START TIME | ||
********************************************** | ********************************************** | ||
********************************* | ********************************* | ||
Performance Step 1: Critical Not Critical X 2-AOI-78-1 Fuel Pool Cleanup System Failure | Performance Step 1: Critical Not Critical X 2-AOI-78-1 Fuel Pool Cleanup System Failure | ||
[3.7] ESTIMATE the time for the fuel pool temperature to rise to 125°F, 150°F, and 200°F using the heat up rates as provided on Attachment 1, Table 1 at least once per shift UNTIL Fuel Pool cooling is restored: | [3.7] ESTIMATE the time for the fuel pool temperature to rise to 125°F, 150°F, and 200°F using the heat up rates as provided on Attachment 1, Table 1 at least once per shift UNTIL Fuel Pool cooling is restored: | ||
Standard: | Standard: Proceeds to attachment 1 of 2-AOI-78-1 SAT UNSAT N/A COMMENTS: | ||
Proceeds to attachment 1 of 2-AOI-78-1 SAT UNSAT N/A COMMENTS: | |||
************************************************* | ************************************************* | ||
****************************** | ****************************** | ||
Line 386: | Line 331: | ||
-up Rate at Normal Fuel Pool Level NOTE Determine time to reach target temperatures of 125°F, 150°F and 200°F using the mos t conservative Heat | -up Rate at Normal Fuel Pool Level NOTE Determine time to reach target temperatures of 125°F, 150°F and 200°F using the mos t conservative Heat | ||
-up Rate (the highest rate) for days that fall between the dates listed on Table 1. Target Temperature 125 °F Actual fuel pool temp(°F) | -up Rate (the highest rate) for days that fall between the dates listed on Table 1. Target Temperature 125 °F Actual fuel pool temp(°F) | ||
- °F Standard: | - °F Standard: Records Actual Fuel Pool Temperature of 96.3 °F, can record 96 °F to 97 °F under each of the Target Temperatures (3 places). | ||
Records Actual Fuel Pool Temperature of 96.3 °F, can record 96 °F to 97 °F under each of the Target Temperatures (3 places). | |||
SAT UNSAT N/A COMMENTS: | SAT UNSAT N/A COMMENTS: | ||
JPM RO A 1b 5 ******************************************************************************* | |||
JPM RO | Performance Step 3: Critical X Not Critical Difference Standard: Calculates the difference 125 | ||
Performance Step 3: Critical X Not Critical Difference Standard: | |||
Calculates the difference 125 | |||
- actual temperature recorded; can record any of the following temperatures 28 °F to 29 °F. | - actual temperature recorded; can record any of the following temperatures 28 °F to 29 °F. | ||
SAT UNSAT N/A COMMENTS: | SAT UNSAT N/A COMMENTS: | ||
*************************************************** | *************************************************** | ||
**************************** | **************************** | ||
Performance Step 4: Critical X Not Critical Heat up rate from Table 1 | Performance Step 4: Critical X Not Critical Heat up rate from Table 1 | ||
÷ °F/hr Standard: | ÷ °F/hr Standard: Records the Heat up rate from Table 1 of 1.37 °F under each of the Target Temperatures (3 places) SAT UNSAT N/A COMMENTS: | ||
Records the Heat up rate from Table 1 of 1.37 °F under each of the Target Temperatures (3 places) SAT UNSAT N/A COMMENTS: | |||
******************************************************************************* | ******************************************************************************* | ||
Line 408: | Line 347: | ||
TIME (in hours) For FUEL POOL TO REACH Target Temperature | TIME (in hours) For FUEL POOL TO REACH Target Temperature | ||
= hrs Standard: | = hrs Standard: Divides the difference by 0.99 and calculates a time to reach 125 °F of one of the following 20.4 hours to 21.2 hours. | ||
Divides the difference by 0.99 and calculates a time to reach 125 °F of one of the following 20.4 hours to 21.2 hours. | |||
SAT UNSAT N/A COMMENTS: | SAT UNSAT N/A COMMENTS: | ||
JPM RO | JPM RO A 1b 6 *********************************************************************** | ||
******** Performance Step 6: Critical X Not Critical Difference | ******** Performance Step 6: Critical X Not Critical Difference | ||
Standard: | Standard: Calculates the difference 150 | ||
Calculates the difference 150 | |||
- actual temperature recorded; can record any of the following temperatures 53 °F to 54 °F. | - actual temperature recorded; can record any of the following temperatures 53 °F to 54 °F. | ||
SAT UNSAT N/A COMMENTS: | SAT UNSAT N/A COMMENTS: | ||
******************************************************************************* | ******************************************************************************* | ||
Performance Step 7: Critical X Not Critical TIME (in hours) For FUEL POOL TO REACH Target Temperature | Performance Step 7: Critical X Not Critical TIME (in hours) For FUEL POOL TO REACH Target Temperature | ||
= hrs Standard: | = hrs Standard: Divides the difference by 1.37 and calculates a time to reach 150 °F of one of the following 38.7 hours to 39.4 hours. | ||
Divides the difference by 1.37 and calculates a time to reach 150 °F of one of the following 38.7 hours to 39.4 hours. | |||
SAT UNSAT N/A COMMENTS: | |||
******************************************************************************* | ******************************************************************************* | ||
Line 435: | Line 369: | ||
Difference | Difference | ||
Standard: | Standard: Calculates the difference 200 | ||
Calculates the difference 200 | - actual temperature recorded; can record any of the following temperatures 10 3 °F to 10 4 °F. SAT UNSAT N/A COMMENTS: | ||
- actual temperature recorded; can record any of the following temperatures | JPM RO A 1b 7 ******************************************************************************* | ||
JPM RO | |||
Performance Step 9: Critical X Not Critical TIME (in hours) For FUEL POOL TO REACH Target Temperature | Performance Step 9: Critical X Not Critical TIME (in hours) For FUEL POOL TO REACH Target Temperature | ||
= hrs Standard: | = hrs Standard: | ||
Divides the difference by 1.37 and calculates a time to reach 200 °F of one of the following 75.2 hours to 75.9 hours. | Divides the difference by 1.37 and calculates a time to reach 200 °F of one of the following 75.2 hours to 75.9 hours. | ||
SAT UNSAT N/A COMMENTS: | SAT UNSAT N/A COMMENTS: | ||
END OF TASK | END OF TASK | ||
Line 451: | Line 382: | ||
STOP TIME | STOP TIME | ||
JPM RO A1b 1 OPERATOR: | JPM RO A1b 1 OPERATOR: ________________________________ | ||
________________________________ | |||
RO DATE: | RO DATE: | ||
JPM NUMBER: | JPM NUMBER: | ||
RO | RO A 1b TASK NUMBER: | ||
U-078-AB-01 TASK TITLE: | U-078-AB-01 TASK TITLE: | ||
Calculate Time to Reach Temperature Targets for Loss of Fuel Pool Cooling K/A NUMBER: | Calculate Time to Reach Temperature Targets for Loss of Fuel Pool Cooling K/A NUMBER: | ||
2.1.25 K/A RATING: RO 3.9 TASK STANDARD: | 2.1.25 K/A RATING: RO 3.9 TASK STANDARD: | ||
Complet e of SRM Operability surveillance and determine if core alterations may commence. | |||
LOCATION OF PERFORMANCE: | LOCATION OF PERFORMANCE: | ||
Simulator REFERENCES/PROCEDURES NEEDED: | Simulator REFERENCES/PROCEDURES NEEDED: | ||
3-AOI-78-1, Fuel Pool Cleanup System Failure VALIDATION TIME: | 3-AOI-78-1, Fuel Pool Cleanup System Failure VALIDATION TIME: | ||
10 minutes PERFORMANCE TIME: | 10 minutes PERFORMANCE TIME: | ||
Line 490: | Line 420: | ||
-AOI-78-1 step 3.7 | -AOI-78-1 step 3.7 | ||
. | . | ||
JPM RO | JPM RO A 1b 3 ******************************************************************************* | ||
Simulator | Simulator *********************************************************************** | ||
******** INITIAL CONDITIONS | ******** INITIAL CONDITIONS | ||
: You are a Reactor Operator on Unit 3. The RBCCW sectionalizing valve has failed closed. The Unit Supervisor has entered 3 | : You are a Reactor Operator on Unit 3. The RBCCW sectionalizing valve has failed closed. The Unit Supervisor has entered 3 | ||
Line 503: | Line 432: | ||
. | . | ||
JPM RO | JPM RO A 1b 4 START TIME | ||
********************************************* | ********************************************* | ||
********************************** | ********************************** | ||
Performance Step 1: Critical Not Critical X 3-AOI-78-1 Fuel Pool Cleanup System Failure | Performance Step 1: Critical Not Critical X 3-AOI-78-1 Fuel Pool Cleanup System Failure | ||
[3.7] ESTIMATE the time for the fuel pool temperature to rise to 125°F, 150°F, and 200°F using the heat up rates as provided on Attachment 1, Table 1 at least once per shift UNTIL Fuel Pool cooling is restored: | [3.7] ESTIMATE the time for the fuel pool temperature to rise to 125°F, 150°F, and 200°F using the heat up rates as provided on Attachment 1, Table 1 at least once per shift UNTIL Fuel Pool cooling is restored: | ||
Standard: | Standard: Proceeds to attachment 1 of 3 | ||
Proceeds to attachment 1 of 3 | -AOI-78-1 SAT UNSAT N/A COMMENTS: | ||
-AOI-78-1 SAT UNSAT N/A COMMENTS: | |||
************************************************ | ************************************************ | ||
******************************* | ******************************* | ||
Line 524: | Line 450: | ||
Target Temperature 125 °F Actual fuel pool temp(°F) | Target Temperature 125 °F Actual fuel pool temp(°F) | ||
- °F Standard: | - °F Standard: Records Actual Fuel Pool Temperatur e of 97.7 °F, can record 97 °F to 98 °F under each of the Target Temperatures (3 places) | ||
Records Actual Fuel Pool Temperatur e of 97.7 °F, can record 97 °F to 98 °F under each of the Target Temperatures (3 places) | |||
. SAT UNSAT N/A COMMENTS: | . SAT UNSAT N/A COMMENTS: | ||
JPM RO A 1b 5 ******************************************************************************* | |||
JPM RO | |||
Performance Step 3: Critical X Not Critical Difference | Performance Step 3: Critical X Not Critical Difference | ||
Standard: | Standard: Calculates the difference 125 | ||
Calculates the difference 125 | |||
- actual temperature recorded; can record any of the following temperatures 28 °F to 29 °F. | - actual temperature recorded; can record any of the following temperatures 28 °F to 29 °F. | ||
SAT UNSAT N/A COMMENTS: | SAT UNSAT N/A COMMENTS: | ||
*********** | *********** | ||
******************************************************************** | ******************************************************************** | ||
Performance Step 4: Critical X Not Critical Heat up rate from Table 1 | Performance Step 4: Critical X Not Critical Heat up rate from Table 1 | ||
÷ °F/hr Standard: | ÷ °F/hr Standard: Records the Heat up rate from Table 1 of 0.99 °F under each of the Target Temperatures (3 places). SAT UNSAT N/A COMMENTS: | ||
Records the Heat up rate from Table 1 of 0.99 °F under each of the Target Temperatures (3 places). SAT UNSAT N/A COMMENTS: | |||
******************************************************************************* | ******************************************************************************* | ||
Line 547: | Line 467: | ||
TIME (in hours) For FUEL POOL TO REACH Target Temperature | TIME (in hours) For FUEL POOL TO REACH Target Temperature | ||
= hrs Standard: | = hrs Standard: Divides the difference by 0.99 and calculates a time to reach 125 °F of one of the following 2 7.2 hours to 2 8.3 hours. SAT UNSAT N/A COMMENTS: | ||
Divides the difference by 0.99 and calculates a time to reach 125 °F of one of the following | |||
JPM RO | JPM RO A 1b 6 ******************************* | ||
************************************************ | ************************************************ | ||
Performance Step 6: Critical X Not Critical Difference | Performance Step 6: Critical X Not Critical Difference | ||
Standard: | Standard: Calculates the difference 150 | ||
Calculates the difference 150 | - actual temperature recorded; can record any of the following temperatures 5 2 °F to 5 3 °F. SAT UNSAT N/A COMMENTS: | ||
- actual temperature recorded; can record any of the following temperatures 5 2 °F to | |||
******************************************************************************* | ******************************************************************************* | ||
Performance Step 7: Critical X Not Critical TIME (in hours) For FUEL POOL TO REACH Target Temperature | Performance Step 7: Critical X Not Critical TIME (in hours) For FUEL POOL TO REACH Target Temperature | ||
= | = hr s Standard: Divides the difference by 0.99 and calculates a time to reach 150 °F of one of the following 5 2.5 hours to 53.5 hours. | ||
Divides the difference by 0.99 and calculates a time to reach 150 °F of one of the following | SAT UNSAT N/A COMMENTS: | ||
SAT UNSAT N/A COMMENTS: | |||
********************************************************* | ********************************************************* | ||
********************** | ********************** | ||
Line 571: | Line 486: | ||
Difference | Difference | ||
Standard: | Standard: Calculates the difference 200 | ||
Calculates the difference 200 | |||
- actual temperature recorded; can record any of the following temperatures 102 °F to 103 °F. | - actual temperature recorded; can record any of the following temperatures 102 °F to 103 °F. | ||
SAT UNSAT N/A COMMENTS: | SAT UNSAT N/A COMMENTS: | ||
JPM RO | JPM RO A 1b 7 ******************************************************************************* | ||
Performance Step 9: Critical X Not Critical TIME (in hours) For FUEL POOL TO REACH Target Temperature | Performance Step 9: Critical X Not Critical TIME (in hours) For FUEL POOL TO REACH Target Temperature | ||
= hrs Standard: | = hrs Standard: | ||
Divides the difference by 0.99 and calculates a time to reach 200 °F of one of the following 103 hours to 104 hours. | Divides the difference by 0.99 and calculates a time to reach 200 °F of one of the following 103 hours to 104 hours. | ||
SAT UNSAT N/A COMMENTS: | SAT UNSAT N/A COMMENTS: | ||
END OF TASK | END OF TASK | ||
Line 588: | Line 501: | ||
STOP TIME | STOP TIME | ||
JPM RO A2 1 OPERATOR: | JPM RO A2 1 OPERATOR: ________________________________ | ||
________________________________ | |||
RO DATE: | RO DATE: | ||
JPM NUMBER: | JPM NUMBER: | ||
Line 596: | Line 508: | ||
TASK NUMBER: | TASK NUMBER: | ||
S-000-AD-55 TASK TITLE: | S-000-AD-55 TASK TITLE: | ||
P S C Head Tank Pump 2B Clearance Boundary K/A NUMBER: | |||
2.2.13 K/A RATING: | 2.2.13 K/A RATING: | ||
RO 4.1 TASK STANDARD: | RO 4.1 TASK STANDARD: | ||
Determine the clearance boundary for P | Determine the clearance boundary for P S C Head Tank Pump 2B LOCATION OF PERFORMANCE: | ||
Class Room | Class Room | ||
/ Unit 2 Simulator REFERENCES/PROCEDURES NEEDED: | / Unit 2 Simulator REFERENCES/PROCEDURES NEEDED: | ||
2-47E814-1, 2-45E779-19, 2-47E610- | 2-47E814-1, 2-45E779-19, 2-47E610-7 5-1, 2-45E2750-4, and 2-4 5E751-3 and 5, NPG-SPP 10.2 VALIDATION TIME: | ||
30 minutes | 30 minutes | ||
Line 610: | Line 522: | ||
__________________ | __________________ | ||
___________________________________________________ | ___________________________________________________ | ||
___________________________ | |||
__________________________________________________________________ | __________________________________________________________________ | ||
______________ | ______________ | ||
Line 620: | Line 531: | ||
DATE: ___________ | DATE: ___________ | ||
__ | __ | ||
EXAMINER JPM RO A2 1 OPERATOR: | EXAMINER JPM RO A2 1 OPERATOR: ________________________________ | ||
________________________________ | |||
RO DATE: | RO DATE: | ||
JPM NUMBER: | JPM NUMBER: | ||
Line 628: | Line 538: | ||
TASK NUMBER: | TASK NUMBER: | ||
S-000-AD-55 TASK TITLE: | S-000-AD-55 TASK TITLE: | ||
P S C Head Tank Pump 2B Clearance Boundary K/A NUMBER: | |||
2.2.13 K/A RATING: | 2.2.13 K/A RATING: | ||
RO 4.1 TASK STANDARD: | RO 4.1 TASK STANDARD: | ||
Determine the clearance boundary for P | Determine the clearance boundary for P S C Head Tank Pump 2B LOCATION OF PERFORMANCE: | ||
Class Room | Class Room | ||
/ Unit 2 Simulator REFERENCES/PROCEDURES NEEDED: | / Unit 2 Simulator REFERENCES/PROCEDURES NEEDED: | ||
2-47E814-1, 2-45E779-19, 2-47E610- | 2-47E814-1, 2-45E779-19, 2-47E610-7 5-1, 2-45E2750-4, and 2-4 5E751-3 and 5, NPG-SPP 10.2 VALIDATION TIME: | ||
30 minutes | 30 minutes | ||
Line 642: | Line 552: | ||
__________________ | __________________ | ||
___________________________________________________ | ___________________________________________________ | ||
___________________________ | |||
__________________________________________________________________ | __________________________________________________________________ | ||
______________ | ______________ | ||
Line 655: | Line 564: | ||
INITIAL CONDITIONS | INITIAL CONDITIONS | ||
: Preventative maintenance is scheduled for the | : Preventative maintenance is scheduled for the P S C Head Tank Pump 2B Motor. Given: NPG Request for Clearance Page one of Completing Clearance form, NPG-SPG 10.2, Clearance Procedure to Safely Control Energy, Appendix B | ||
INITIATING CUES | INITIATING CUES | ||
: The Unit Supervisor directs you as a Reactor Operator to write a clearance to allow uncoupling the | : The Unit Supervisor directs you as a Reactor Operator to write a clearance to allow uncoupling the P S C Head Tank Pump 2B in support of preventative maintenance on the motor. ESOMs is not currently working, use the Completing Clearance, Appendix B (page 8 of 11). On Appendix B (page 8 of 11) complete columns 18, 20, 21, and 22 for each identified component. | ||
JPM RO A2 3 ******************************************************************************* | JPM RO A2 3 ******************************************************************************* | ||
Line 673: | Line 582: | ||
ESOMs is not currently working, use the Completing Clearance, Appendix B (page 8 of 11). On Appendix B (page 8 of 11) complete columns 18, 20, 21, and 22 for each identified component. | ESOMs is not currently working, use the Completing Clearance, Appendix B (page 8 of 11). On Appendix B (page 8 of 11) complete columns 18, 20, 21, and 22 for each identified component. | ||
JPM RO A2 4 START TIME | JPM RO A2 4 START TIME | ||
****************************************************************** | ****************************************************************** | ||
************* | ************* | ||
Performance Step 1: Critical Not Critical X | Performance Step 1: Critical Not Critical X | ||
Review print s to determine required isolation boundary: | Review print s to determine required isolation boundary: | ||
2- | 2-47E81 4-1 , 2-45E779-19, 2-47E610-7 5-1, 2-45 E 27 50-4, and 2-4 5E751-3 and 5. Standard: | ||
Locates and reviews print s for PSC Head Tank Pump 2B. SAT UNSAT N/A COMMENTS: | |||
Locates and reviews print s for PSC Head Tank Pump 2B. SAT UNSAT N/A COMMENTS: | |||
******************************************************************************* | ******************************************************************************* | ||
Line 688: | Line 594: | ||
Determines Isolation boundary | Determines Isolation boundary | ||
. Standard: | . Standard: *Determines at least one of the following components will need to be tagged to prevent pump rotation: | ||
2-75-SHV-603 Pump Discharge Valve | 2-75-SHV-603 Pump Discharge Valve | ||
, Closed, Danger Tag | , Closed, Danger Tag | ||
Line 696: | Line 601: | ||
Tag placement sequence will generally be after the electrical tag placement. NOT critical. | Tag placement sequence will generally be after the electrical tag placement. NOT critical. | ||
SAT UNSAT N/A COMMENTS: | SAT UNSAT N/A COMMENTS: | ||
JPM RO A2 5 ******************************************************************************* | JPM RO A2 5 ******************************************************************************* | ||
Line 702: | Line 607: | ||
Determines Isolation boundary | Determines Isolation boundary | ||
. Standard: | . Standard: *2-HS-75-7 6A Control Room Handswitch, Danger Tag, Pull to Lock | ||
. | . | ||
Tag placement sequence will generally be one or two. NOT critical. | Tag placement sequence will generally be one or two. NOT critical. | ||
SAT UNSAT N/A COMMENTS: | SAT UNSAT N/A COMMENTS: | ||
******************************************************************************* | ******************************************************************************* | ||
Line 713: | Line 616: | ||
Determines Isolation boundary | Determines Isolation boundary | ||
. Standard: | . Standard: *2B Pump Power Supply, 480 Volt RMOV Board 2B, Breaker 11D, Danger Tag, O ff. | ||
Tag placement sequence will generally be one or two. NOT critical. | Tag placement sequence will generally be one or two. NOT critical. | ||
SAT UNSAT N/A COMMENTS: | SAT UNSAT N/A COMMENTS: | ||
JPM RO A2 6 ******************************************************************************* | JPM RO A2 6 ******************************************************************************* | ||
Performance Step 5: Critical__ Not Critical X | Performance Step 5: Critical__ Not Critical X | ||
Determines Isolation Boundary | Determines Isolation Boundary | ||
. Standard: | . Standard: | ||
The following circuits may be identified but are not critical for personnel protection | The following circuits may be identified but are not critical for personnel protection | ||
: 2-FU-075-076B Control Circuit 2-FU-075- | : 2-FU-075-076B Control Circuit 2-FU-075-076 A Indicating Light SAT UNSAT N/A COMMENTS: | ||
END OF TASK | END OF TASK | ||
Line 730: | Line 630: | ||
STOP TIME | STOP TIME | ||
JPM A3 1 OPERATOR: ________________________________ | JPM A3 1 OPERATOR: ________________________________ | ||
RO SRO DATE: | RO SRO DATE: | ||
JPM NUMBER: | JPM NUMBER: | ||
Line 743: | Line 643: | ||
LOCATION OF PERFORMANCE: | LOCATION OF PERFORMANCE: | ||
Class Room REFERENCES/PROCEDURES NEEDED: | Class Room REFERENCES/PROCEDURES NEEDED: | ||
Handout RWP and Survey Map | Handout RWP and Survey Map , NPG-SPP 5.1 VALIDATION TIME: 15 minutes | ||
, NPG-SPP 5.1 VALIDATION TIME: 15 minutes | |||
PERFORMANCE TIME: | PERFORMANCE TIME: | ||
Line 779: | Line 678: | ||
: n. Assume a total travel dose of 25 mrem will be received. | : n. Assume a total travel dose of 25 mrem will be received. | ||
INITIATING CUES: Given the survey map and RWP, determine the following: | INITIATING CUES: Given the survey map and RWP, determine the following: | ||
Dress-out requirements for entry to perform your assigned task Whether you can complete the assigned task in the area without exceeding your TVA administrative dose limit Whether you can complete the assigned task in the area without exceeding the RWP dose entry limits both rate and total dose, i.e. will you receive an MG alarm (Electronic Dosimeter) | Dress-out requirements for entry to perform your assigned task Whether you can complete the assigned task in the area without exceeding your TVA administrative dose limit Whether you can complete the assigned task in the area without exceeding the RWP dose entry limits both rate and total dose, i.e. will you receive an MG alarm (Electronic Dosimeter). | ||
. | |||
JPM A3 4 START TIME | |||
******************************************************************************* | ******************************************************************************* | ||
Performance Step 1: Critical X Not Critical | Performance Step 1: Critical X Not Critical | ||
Determines Dress Out requirements Standard: | Determines Dress Out requirements Standard: Shoe covers - one pair, Coveralls - one pair, Face Shield, Gloves - rubber - two pair, cloth inserts, Booties - plastic - 2 pair , Rain suit, and Hood SAT UNSAT N/A COMMENTS: | ||
Shoe covers - one pair, Coveralls - one pair, Face Shield, Gloves - rubber - two pair, cloth inserts, Booties - plastic - 2 pair, Rain suit, and Hood SAT UNSAT N/A COMMENTS: | |||
******************************************************************************* | ******************************************************************************* | ||
Line 796: | Line 692: | ||
Calculates RWCU HX venting dose. | Calculates RWCU HX venting dose. | ||
Standard: | Standard: | ||
35 minutes in a 250 mrem/hr area = 145 to 146 mrem SAT UNSAT N/A COMMENTS: | |||
35 minutes in a 250 mrem/hr area = 145 to 146 mrem SAT UNSAT N/A COMMENTS: | |||
******************************************************************************* | ******************************************************************************* | ||
Line 804: | Line 699: | ||
Calculates 69-2 valve work dose Standard: | Calculates 69-2 valve work dose Standard: | ||
50 minutes in a 100 mrem/hr area = | 50 minutes in a 100 mrem/hr area = | ||
83 to 84 mrem SAT UNSAT N/A COMMENTS: | 83 to 84 mrem SAT UNSAT N/A COMMENTS: | ||
JPM A3 5 ******************************************************************************* | JPM A3 5 ******************************************************************************* | ||
Line 812: | Line 706: | ||
Calculates total dose received Standard: | Calculates total dose received Standard: | ||
25 mrem travel + 146 mrem venting + 83 mrem 69 | 25 mrem travel + 146 mrem venting + 83 mrem 69 | ||
-2 = 254 mrem SAT UNSAT N/A COMMENTS: | -2 = 254 mrem SAT UNSAT N/A COMMENTS: | ||
******************************************************************************* | ******************************************************************************* | ||
Line 821: | Line 714: | ||
Calculates total dose for quarter Standard: | Calculates total dose for quarter Standard: | ||
750 mrem + 254 mrem = 1004 mrem SAT UNSAT N/A COMMENTS: | |||
750 mrem + 254 mrem = 1004 mrem SAT UNSAT N/A COMMENTS: | |||
******************************************************************************* | ******************************************************************************* | ||
Line 829: | Line 721: | ||
* Critical X Not Critical | * Critical X Not Critical | ||
Verifies RWP MG Setpoints Standard: | Verifies RWP MG Setpoints Standard: MG setpoints: for Dose Rate alarm of 500 mrem/hr will not be exceeded and | ||
MG setpoints: for Dose Rate alarm of 500 mrem/hr will not be exceeded and | |||
*Dose alarm of 200 mrem will be exceeded. | *Dose alarm of 200 mrem will be exceeded. | ||
SAT UNSAT N/A COMMENTS: | SAT UNSAT N/A COMMENTS: | ||
JPM A3 6 ******************************************************************************* | JPM A3 6 ******************************************************************************* | ||
Line 838: | Line 729: | ||
Verifies dose limits for quarter and RWP Standard: | Verifies dose limits for quarter and RWP Standard: | ||
Verifies will have a total dose of greater than 1000 mrem which is above the TVA administrative limit. | Verifies will have a total dose of greater than 1000 mrem which is above the TVA administrative limit. | ||
SAT UNSAT N/A COMMENTS: | SAT UNSAT N/A COMMENTS: | ||
END OF TASK STOP TIME | END OF TASK STOP TIME | ||
BROWNS FERRY NUCLEAR PLANT Unit: 3 Permit Number: Training | BROWNS FERRY NUCLEAR PLANT Unit: 3 Permit Number: Training | ||
Page: 1 RADIOLOGICAL WORK PERMIT BRIEFING REQUIRED EVERY ENTRY GENERAL DESCRIPTION Status: Active Start Date: 01 | Page: 1 RADIOLOGICAL WORK PERMIT BRIEFING REQUIRED EVERY ENTRY GENERAL DESCRIPTION Status: Active Start Date: 01 | ||
-Jan-This year End Date: 01 | -Jan-This year End Date: 01 | ||
-Jan-Next year Type: SPECIFIC MAP ID: Outage: Y Name: Task: ROUTINE PLANT MAINTENANCE PSE: N HP CONTINUOUS Authorization Type: INDIVIDUAL ALARA Review Number: 0A-0010 Primary Work Doc: | -Jan-Next year Type: SPECIFIC MAP ID: Outage: Y Name: Task: ROUTINE PLANT MAINTENANCE PSE: N HP CONTINUOUS Authorization Type: INDIVIDUAL ALARA Review Number: 0A-0010 Primary Work Doc: | ||
Person-mrem Estimate: 1904 Person | Person-mrem Estimate: 1904 Person | ||
-Hrs Estimate: 1082 Dose Alarm: 200 Dose Rate Alarm: 500 | -Hrs Estimate: 1082 Dose Alarm: 200 Dose Rate Alarm: 500 | ||
Line 860: | Line 750: | ||
DOSIMETRY REQUIREMENTS ELECTRONIC DOSIMETER TLD BRIEFING REQUIREMENTS PRE-JOB BRIEFING | DOSIMETRY REQUIREMENTS ELECTRONIC DOSIMETER TLD BRIEFING REQUIREMENTS PRE-JOB BRIEFING | ||
WORK STEPS 1 MANAGEMENT / WO WALKDOWN 2 3-CI-412 3 OPS VALVE LINEUP OI-69 & HX VENTING 4 07-712928-000 5 06-722560-000 6 06-727133-000 7 06-722556-000 8 06-722559-000 9 06-718308-002 10 06-722558-000 BROWNS FERRY NUCLEAR PLANT Unit: 3 Permit Number: Training | WORK STEPS 1 MANAGEMENT / WO WALKDOWN 2 3-CI-412 3 OPS VALVE LINEUP OI-69 & HX VENTING 4 07-712928-000 5 06-722560-000 6 06-727133-000 7 06-722556-000 8 06-722559-000 9 06-718308-002 10 06-722558-000 BROWNS FERRY NUCLEAR PLANT Unit: 3 Permit Number: Training | ||
Page: 1 RADIOLOGICAL WORK PERMIT BRIEFING REQUIRED EVERY ENTRY WORKER INSTRUCTIONS 1 DRESSOUT CODE APPLICATIONS | Page: 1 RADIOLOGICAL WORK PERMIT BRIEFING REQUIRED EVERY ENTRY WORKER INSTRUCTIONS 1 DRESSOUT CODE APPLICATIONS | ||
Line 884: | Line 774: | ||
APPROVAL Prepaired by: TJFRANK Approved by: MJHAZEL Final Approval: JWSMITH3 End of RWP | APPROVAL Prepaired by: TJFRANK Approved by: MJHAZEL Final Approval: JWSMITH3 End of RWP | ||
JPM RO A2 1 OPERATOR: | JPM RO A2 1 OPERATOR: ________________________________ | ||
________________________________ | |||
RO DATE: | RO DATE: | ||
JPM NUMBER: | JPM NUMBER: | ||
Line 892: | Line 781: | ||
TASK NUMBER: | TASK NUMBER: | ||
S-000-AD-55 TASK TITLE: | S-000-AD-55 TASK TITLE: | ||
P S C Head Tank Pump 2B Clearance Boundary K/A NUMBER: | |||
2.2.13 K/A RATING: | 2.2.13 K/A RATING: | ||
RO 4.1 TASK STANDARD: | RO 4.1 TASK STANDARD: | ||
Determine the clearance boundary for P | Determine the clearance boundary for P S C Head Tank Pump 2B LOCATION OF PERFORMANCE: | ||
Class Room | Class Room | ||
/ Unit 2 Simulator REFERENCES/PROCEDURES NEEDED: | / Unit 2 Simulator REFERENCES/PROCEDURES NEEDED: | ||
2-47E814-1, 2-45E779-19, 2-47E610- | 2-47E814-1, 2-45E779-19, 2-47E610-7 5-1, 2-45E2750-4, and 2-4 5E751-3 and 5, NPG-SPP 10.2 VALIDATION TIME: | ||
30 minutes | 30 minutes | ||
Line 906: | Line 795: | ||
__________________ | __________________ | ||
___________________________________________________ | ___________________________________________________ | ||
___________________________ | |||
__________________________________________________________________ | __________________________________________________________________ | ||
______________ | ______________ |
Revision as of 16:16, 13 July 2018
ML14049A019 | |
Person / Time | |
---|---|
Site: | Browns Ferry |
Issue date: | 02/18/2014 |
From: | NRC/RGN-II |
To: | Tennessee Valley Authority |
References | |
Download: ML14049A019 (97) | |
Text
JPM RO A1a 1 OPERATOR: ________________________________
RO DATE:
JPM NUMBER:
RO A 1a TASK NUMBER:
Conduct of Operations
TASK TITLE:
3-SR-2, Mode 3 Operator Rounds, Table 1.12 through 1.2 2
K/A NUMBER:
2.1.7 K/A RATING:
RO 4.4 TASK STANDARD:
Perform Operator logs in accordance with SR
-2 Instrument Checks and Observations for log tables 1.1 3 through 1.2
- 2. Verify acceptance criteria are satisfied in accordance with notes and if not notification to Unit Supervisor is completed
.
LOCATION OF PERFORMANCE:
Simulator REFERENCES/PROCEDURES NEEDED:
3-SR-2, Instrument Checks and Observations VALIDATION TIME:
30 minutes PERFORMANCE TIME:
COMMENTS:
__________________________________________________________
______________________
__________
______________________________________
________________________________
______________________________________
Additional comment sheets attached? YES
___ NO ___
RESULTS: SATISFACTORY
____ UNSATISFACTORY
____
SIGNATURE:
____________________
______ DATE: __________
EXAMINER
INITIAL CONDITIONS
- You are a Unit Operator assigned to Unit 3, and it is Friday morning at 0800. 3-SR-2, Instrument Checks and Observations, is being performed.
The plant is in MODE 3.
INITIATING CUE: The Unit Supervisor directs you as the Unit Operator to complete a portion of 3-SR-2 day shift checks and observations Attachment 2 Surveillance Procedure Data Package Modes 1, 2, and 3 (pages 17 of 88 to 26 of 88) for Friday at 0800.
All readings that are already completed are correct and need not be checked by you.
JPM RO A1a 3 *******************************************************************************
Simulator *******************************************************************************
INITIAL CONDITIONS
- You are a Unit Operator assigned to Unit 3, and it is Friday morning at 0800. 3-SR-2, Instrument Checks and Observations, is being performed.
The plant is in MODE 3.
INITIATING CUE
- The Unit Supervisor directs you as the Unit Operator to complete a portion of 3-SR-2 day shift checks and observations Attachment 2 Surveillance Procedure Data Package Modes 1, 2, and 3 (pages 17 of 88 to 26 of 88) for Friday at 0800.
All readings that are already completed are correct and need not be checked by you.
Performance Step 1: Critical X Not Critical (1) Whenever there is fuel in the reactor vessel and the continuous conductivity monitor is inoperable, periodic analysis of reactor coolant samples are required by the Technical Requirements Manual. If the reactor coolant continuous conductivity monitor becomes inoperable, notify Chemistry to sample according to 3
-SI-4.6.B.1-4. Standard: Records a Reactor Coolant Conductivity reading of .057 or .058 µmho. Initials under UO.
SAT UNSAT N/A COMMENTS:
JPM RO A1a 5 *******************************************************************************
Performance Step 2: Critical X Not Critical (1) The difference between readings of 3
-LI-64-54A and 3-LI-64-66 should not exceed 2 inches. Deviations greater than 2 inches should be investigated.
(2) The Technical Specification requirements for Suppression Pool Water Level are --1.0" with DW to Torus --1.0" without DW to Torus DP established.
Standard: Records a Suppression Pool Level of (-) 2.75 inches; plus or minus 0.5 inches in both columns. Initials under UO.
SAT UNSAT N/A COMMENTS:
JPM RO A1a 6 *******************************************************************************
Performance Step 3: Critical X Not Critical (1) The required observation of Bulk Volumetric Average Drywell Air Temperature may be obtained from ICS Pt TEST2500 OR 3
-TI-82 OR 3-TR-80-1. Only one of the two methods is required to be logged and the other method may be N/A'd.
(2) It may be necessary to have Instrument Maintenance turn on the "BULK VOLUMETRIC AVERAGE DRYWELL AIR TEMPERATURE" on 3
-TR-80-1 to allow the point to be displayed.
Standard: Records a Drywell Air Temperature from ICS of 1 04.1 °F; plus or minus 0.1 °F in the column under ICS Pt TEST2500. Initials under UO.
SAT UNSAT N/A COMMENTS:
JPM RO A1a 7 *******************************************************************************
Performance Step 4: Critical Not Critical X (1) The Drywell
-Suppression Chamber Differential Pressure should not exceed 1.33 psid.
Standard: Records a Drywell
- Suppression Chamber Differential pressure of 1.1 to 1.2 psid in both columns. Initials under UO.
SAT UNSAT N/A COMMENTS:
JPM RO A1a 8 ***************************************************************
Performance Step 5: Critical X Not Critical (1) Limits:
adds heat to the suppression pool is being performed.
suppression pool is being performed; and
(2) This value is recorded to further validate the Suppression Pool Bulk Water Temperature indications when RHR Suppression Pool Cooling is not in service. If the Control Room Suppression Pool Bulk Water Temperature indications deviate more than 5°F from one another or if 3
-TI Suppression Pool Cooling may be required to be placed in service to obtain valid Suppression Pool Bulk Water Temperature readings (may indicate a potential thermal stratification problem, Refer To site response to GE SIL 106). Deviations in excess of 5°F for the MCR instruments is also an indication of a potential inoperable instrumen t; the Suppression Pool Bulk Water Temperature instruments affect LCO 3.3.3.1, "PAM Instruments" (CHANNEL CHECK surveillance requirement) and 3
-TI-64-55B affects LCO 3.3.3.2, "Backup Control System.
(3) Suppression pool average temperature must be verified within the applicable limits and logged every 5 minutes when performing testing that adds heat to the suppression pool, accomplished by 3
-SR-3.6.2.1.1.
(4) If both the primary and secondary indication of any SRV tailpipe is inoperable, per Technical Requirements Manual 3.3.5, the Suppression Pool Water Temperature must be monitored at least once per shift to observe any unexplained temperature rise which might be indicative of an open SRV.
Standard: Records Suppression Pool Water Temperature of 87.5 °F; plus or minus 2.5 °F in all 4 -3. Initials under UO.
SAT UNSAT N/A COMMENTS:
JPM RO A1a 9 *******************************************************************************
Performance Step 6: *Critical X Not Critical (1) Each pressure indicator provides indication of the discharge pressure for one RHR or Core Spray Loop. The instrument chec k will consist of observing that the instrument exhibits an expected reading for the given plant conditions. (2) The Technical Requirements Manual requires a minimum discharge pressure for OPERABLE subsystems. Refer To TRM Section 3.5.4.
CS Loop I PI-75-20 CS Loop II PI-75-48 RHR Loop I PI-74-51 48 psig RHR Loop II PI-74-65 35 ps ig (3) MAX criteria is N/A for RHR/Core Spray subsystems in service or if keep fill aligned to CS & S. When a RHR/Core Spray subsystem is in a standby readiness condition the maximum discharge pressure is 100 psig. High discharge pressures with pumps secured may be indication of primary valve leakage.
Standard: *Records a CS Loop I Fill Pressure of 50 psig (+) 5 psig and for *CS Loop II Discharge Fill Pressure of 50 psig (+) 5 psig. *Records a RHR Loop I Discharge Fill Pressure of 40 psig;
(+) 5 psig. Records NA or 270 psig for RHR Loop II because it is in Shutdown Cooling. Initials under UO. *Informs Unit Supervisor that RHR Loop I discharge pressure is less than the minimum required discharge pressure of 48 psig.
SAT UNSAT N/A COMMENTS:
JPM RO A1a 10 *******************************************************************************
Performance Step 7: Critical X Not Critical (1) Technical Specification LCO 3.4.7 requires that two RHR Shutdown Cooling Subsystems be operable during this applicability. An operable Shutdown Cooling Subsystem consists of one RHR pump, associated heat exchanger, RHRSW pump capable of providing cooling water to its associated heat exchanger, associated piping and valves, all of which can be aligned in the Shutdown Cooling Mode for the removal of decay heat.
(2) An "X" shall be placed in the associated Column for the In Service Pump or Subsystem.
(3) To be considered as In Service, RHR System and its associated Shutdown Cooling Subsystems must be in the Shutdown Cooling Mode alignment with RHR SD CLG FLOW LOW annunciator (3
-XA-55-3D, Window 11) RESET.
Standard: Places an X under RR Pump B for being in service and an X under RHR Shutdown Cooling Subsystem D for being in service. Records SAT in all data Column. Initials under UO.
SAT UNSAT N/A COMMENTS:
JPM RO A1a 11 *******************************************************************************
Performance Step 8: Critical X Not Critical Standard: Records Reactor Zone Exhaust Radiation Monitor readings of 1.0 mr/hr for both RM
--142 and RM
--143; plus or minus 0.5 mr/hr for Detector A and B. Records Refuel Zone Exhaust Radiation Monitor readings of 26.0 mr/hr for RM
--140; plus or minus 1.0 mr/hr for Detector A and B. For RM
--141 records reading of 50 mr/hr; plus or minus 1 mr/hr for Detector A and B. Initials under UO. Informs Unit Supervisor that Refuel Zone Exhaust Radiation Monitors are outside the MAX deviation of 20 mr/hr.
SAT UNSAT N/A COMMENTS:
JPM RO A1a 12 *******************************************************************************
Performance Step
- *Critical X Not Critical (1) The instrument check will consist of observing that the instruments exhibit an expected reading for the given plant conditions. MAX will be the alarm (RHRSW/RCW EFFLUENT RADIATION HIGH 3-RA--132 (Panel 3
--3, 3-XA-55-3A, Window 3)) setpoint for the respective monitor. Instrument Shop should be contacted for most current setpoints as required.
Standard: Records NA for RM
--133 or a reading of 300 cpm. *Records a reading for RM
--134 of 300 cpm; plus or minus 10 cpm. *Records SAT in all data Column. *Initials under UO.
SAT UNSAT N/A COMMENTS:
END OF TASK
STOP TIME
JPM RO A1a 1 OPERATOR: ________________________________
RO DATE:
JPM NUMBER:
RO A 1a TASK NUMBER:
Conduct of Operations
TASK TITLE:
2-SR-2, Mode 3 Operator Rounds, Table 1.1 3 through 1.2 2
K/A NUMBER:
2.1.7 K/A RATING:
RO 4.4 TASK STANDARD:
Perform Operator logs in accordance with SR
-2 Instrument Checks and Observations for log tables 1.1 3 through 1.2
- 2. Verify acceptance criteria are satisfied in accordance with notes and if not notification to Unit Supervisor is completed
. LOCATION OF PERFORMANCE:
Simulator REFERENCES/PROCEDURES NEEDED:
2-SR-2, Instrument Checks and Observations VALIDATION TIME:
30 minutes PERFORMANCE TIME:
COMMENTS:
__________________________________________________________
_____________________
___________
______________________________________
________________________________
______________________________________
Additional comment sheets attached? YES
___ NO ___
RESULTS: SATISFACTORY
____ UNSATISFACTORY
____
SIGNATURE:
___________________
_______ DATE: __________
EXAMINER
INITIAL CONDITIONS
- You are a Unit Operator assigned to Unit 2, and it is Friday morning at 0800. 2-SR-2, Instrument Checks and Observations, is being performed.
The plant is in MODE 3.
INITIATING CUE: The Unit Supervisor directs you as the Unit Operator to complete a portion of 2-SR-2 day shift checks and observations Attachment 2 Surveillance Procedure Data Package Modes 1, 2, and 3 (pages 1 8 of 90 to 2 7 of 90) for Friday at 0800.
All readings that are already completed are correct and need not be checked by you.
JPM RO A1a 3 *******************************************************************************
Simulator *******************************************************************************
INITIAL CONDITIONS
- You are a Unit Operator assigned to Unit 2, and it is Friday morning at 0800. 2-SR-2, Instrument Checks and Observations, is being performed.
The plant is in MODE 3.
INITIATING CUE
- The Unit Supervisor directs you as the Unit Operator to complete a portion of 2-SR-2 day shift checks and observations Attachment 2 Surveillance Procedure Data Package Modes 1, 2, and 3 (pages 18 of 90 to 27 of 90) for Friday at 0800.
All readings that are already completed are correct and need not be checked by you.
Performance Step 1: Critical X Not Critical (1) Whenever there is fuel in the reactor vessel and the continuous conductivity monitor is inoperable, periodic analysis of reactor coolant samples are required by the Technical Requirements Manual. If the reactor coolant continuous conductivity monitor becomes inoperable, notify the Chemistry to sample according to 2
-SI-4.6.B.1-4. Standard: Records a Reactor Coolant Conductivity reading of
.057 or .058
µmho. Initials under UO
. SAT UNSAT N/A COMMENTS:
JPM RO A1a 5 *******************************************************************************
Performance Step 2: Critical X Not Critical (1) The difference between readings of 2
-LI-64-54A and 2-LI-64-66 should not exceed 2 inches. Deviations greater than 2 inches should be investigated.
(2) The Technical Specification requirements for Suppression Pool Water Level are --1.0" with DW to Torus --1.0" without DW to Torus DP established.
Standard: Records a Suppression Pool Level of
(-) 1 to (-) 2 inches in both columns.
Initials under UO
. SAT UNSAT N/A COMMENTS:
JPM RO A1a 6 *******************************************************************************
Performance Step 3: Critical X Not Critical (1) The required observation of Bulk Volumetric Average Drywell Air Temperature may be obtained from ICS Pt TEST2500 or 2
-TR-80 or 2-TI-82 Value. Only one of the three methods is required to be logged and the other method may be N/A'd.
(2) It may be necessary to have Instrument Maintenance turn on the "BULK VOLUMETRIC AVERAGE DRYWELL AIR TEMPERATURE" on 2
-TR-80-1 to allow the point to be displayed.
Standard: Records a Drywell Air Temperature from ICS of 1 02.4 °F or 102.5 °F in the column under ICS Pt TEST2500. Initials under UO.
SAT UNSAT N/A COMMENTS:
JPM RO A1a 7 *******************************************************************************
Performance Step 4: Critical Not Critical X (1) Acceptance Criteria is not required to be met until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after THERMAL POWER is > 15% RTP following startup, TO 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to reducing THERMAL POWER to
< 15% RTP prior to the next scheduled reactor shutdown.)
(2) The Drywell
-Suppression Chamber Differential Pressure should not exceed 1.33 psid.
Standard: Records a Drywell - Suppression Chamber Differential pressure of 1.1 5 to 1.2 psid in both columns. Initials under UO
. SAT UNSAT N/A COMMENTS:
JPM RO A1a 8 *******************************************************************************
Performance Step 5: Critical X Not Critical NOTES ARE ON THE FOLLOWING PAGE!
that adds heat to the suppression pool is being performed; hannel is > 70 on Range 7 and testing that adds heat to the suppression pool is being performed; and
(2) This value is recorded to further validate the Suppression Pool Bulk Water Temperature indications when RHR Suppression Pool Cooling is not in service. If the Control Room Suppression Pool Bulk Water Temperature indications deviate more than 5°F from one another or the 2
-TI-64-55B is greater than or equal to 95 deg F, RHR Suppression Pool Cooling may be required to be placed in service to obtain a valid Suppression Pool Bulk Water Temperature readings (may indicate a potential thermal stratification problem, REFER TO site response to GE SIL 106). Deviations in excess of 5°F for the MCR instruments is also an indication of a potential inoperable instrument; the Suppression Pool Bulk Water Temperature instruments affect LCO 3.3.3.1, "PAM Instruments" (CHANNEL CHECK surveillance requirement) and 2
-TI-64-55B affects LCO 3.3.3.2, "Backup Control System. Failure of an Analog (Pen), channel to track due to sticking or servo failure, contributing to the channel exceeding the Max Delta Limits or not, results in the channel being Inoperable.
(3) Suppression pool average temperature must be verified within the applicable limits and logged every 5 minutes when performing testing that adds heat to the suppression pool, accomplished by 2
-SR-3.6.2.1.1.
(4) If both the primary and secondary indication of any SRV tailpipe is inoperable, per Technical Requirements Manual 3.3.5, the Suppression Pool Water Temperature must be monitored at least once per shift to observe any unexplained temperature rise which might be indicative of an open SRV.
Standard: Records Suppression Pool Water Temperature of 8 7.5 °F; plus or minus 2 °F in all 4 columns under Panel 9
-3. Initials under UO.
SAT UNSAT N/A COMMENTS:
JPM RO A1a 10 *******************************************************************************
Performance Step 6: *Critical X Not Critical (1) Each pressure indicator provides indication of the discharge pressure for one RHR or Core Spray Loop. The instrument check will consist of observing that the instrument exhibits an expected reading for the given plant conditions.
(2) The Technical Requirements Manual requires a minimum discharge pressure for OPERABLE subsystems. Refer to TRM Section 3.5.4.
CS Loop I PI-75-20 39 psig CS Loop II PI-75-48 39 psig RHR Loop I PI-74-51 48 psig RHR Loop II PI-74-65 35 psig (3) MAX criteria are N/A for RHR/Core Spray subsystems in service or if keep fill aligned to CS & S. When a RHR/Core Spray subsystem is in a standby readiness condition the maximum discharge pressure is 100 psig. High discharge pressures with pumps secured may be indication of primary valve leakage.
Standard: *Records a CS Loop I Fill Pressure of 50 psig (+) 5 psig and for *CS Loop II Discharge Fill Pressure of 4 5 psig (+) 5 psig. *Records a RHR Loop I Discharge Fill Pressure of 4 2.5 psig; plus 5 psig or minus 2.5 psig but less than 48 psig. Records NA or 270 psig for RHR Loop II because it is in Shutdown Cooling. Initials under UO.
- Informs Unit Supervisor that RHR Loop I discharge pressure is less than the minimum required discharge pressure of 48 psig. SAT UNSAT N/A COMMENTS:
JPM RO A1a 11 *******************************************************************************
Performance Step 7: Critical X Not Critical (1) Technical Specification LCO 3.4.7 requires that two RHR Shutdown Cooling Subsystems be operable during this applicability. An operable Shutdown Cooling Subsystem consists of one RHR pump, associated heat exchanger, RHRSW pump capable of providing cooling water to its associated heat exchanger, associated piping and valves, all of which can be aligned in the Shutdown Cooling Mode for the removal of decay heat.
(2) An "X" shall be placed in the associated Column for the In Service Pump or Subsystem.
(3) To be considered as In Service, RHR System and its associated Shutdown Cooling Subsystems must be in the Shutdown Cooling Mode alignment with RHR SD CLG FLOW LOW annunciator (2
-XA-55-3D, Window 11) is reset.
Standard: Places an X under RR Pump B for being in service and an X under RHR Shutdown Cooling Subsystem D for being in service. Records SAT in all data Column. Initials under UO.
SAT UNSAT N/A COMMENTS:
JPM RO A1a 12 *******************************************************************************
Performance Step 8: Critical X Not Critical Standard: Records Reactor Zone Exhaust Radiation Monitor readings of 1.0 mr/hr for both RM 142 and RM 143; plus or minus 0.5 mr/hr for Detector A and B. Records Refuel Zone Exhaust Radiation Monitor readings of 26.0 mr/hr for RM 140; plus or minus 1.0 mr/hr for Detector A and B. For RM 141 records reading of 50 mr/hr; plus or minus 1 mr/hr for Detector A and B. Initials under UO. Informs Unit Supervisor that Refuel Zone Exhaust Radiation Monitors are outside the MAX deviation of 20 mr/hr. SAT UNSAT N/A COMMENTS:
JPM RO A1a 13 *******************************************************************************
Performance Step 9: *Critical X Not Critical (1) The instrument check will consist of observing that the instruments exhibit an expected reading for the given plant conditions. MAX will be the alarm (RHRSW/RCW EFFLUENT RADIATION HIGH 2-RA-90-132 (Panel 2 3, 2-XA-55-3A, Window 3)) setpoint for the respective monitor. Instrument Shop should be contacted for most current setpoints as required.
Standard: Records NA for RM 133 or a reading of 300 cpm. *Records a reading for RM 134 of 300 cpm; plus or minus 10 cpm. *Records SAT in all data Column.
- Initials under UO.
SAT UNSAT N/A COMMENTS:
END OF TASK
STOP TIME
JPM RO A1b 1 OPERATOR: ________________________________
RO DATE:
JPM NUMBER:
RO A 1b TASK NUMBER:
U-078-AB-01 TASK TITLE:
Calculate Time to Reach Temperature Targets for Loss of Fuel Pool Cooling K/A NUMBER:
2.1.25 K/A RATING: RO 3.9 TASK STANDARD:
Complet e of SRM Operability surveillance and determine if core alterations may commence.
LOCATION OF PERFORMANCE:
Simulator REFERENCES/PROCEDURES NEEDED:
2-AOI-78-1, Fuel Pool Cleanup System Failure VALIDATION TIME:
10 minutes PERFORMANCE TIME:
COMMENTS:
__________________________________________________________
________________________________
______________________________________
________________________________
______________________________________
Additional comment sheets attached? YES
___ NO ___
RESULTS: SATISFACTORY
____ UNSATISFACTORY
____ SIGNATURE:
__________________________
DATE: __________
EXAMINER
INITIAL CONDITIONS
- You are a Reactor Operator on Unit 2. The RBCCW sectionalizing valve has failed closed. The Unit Supervisor has entered 2-AOI-70-1, Loss of Reactor Building Closed Cooling Water and 2-AOI-78-1, Fuel Pool Cleanup System Failure.
INITIATING CUES
- The Unit Supervisor directs you to estimate the time for the fuel pool temperature to rise to 125 °F, 150 °F, and 200
°F in accordance with 2-AOI-78-1 step 3.7
.
JPM RO A 1b 3 *******************************************************************************
Simulator ************************************************************************
- INITIAL CONDITIONS
- You are a Reactor Operator on Unit 2. The RBCCW sectionalizing valve has failed closed. The Unit Supervisor has entered 2
-AOI-70-1, Loss of Reactor Building Closed Cooling Water and 2
-AOI-78-1, Fuel Pool Cleanup System Failure.
INITIATING CUES
- The Unit Supervisor directs you to estimate the time for the fuel pool temperature to rise to 125 °F, 150 °F, and 200
°F in accordance with 2
-AOI-78-1 step 3.7
.
Performance Step 1: Critical Not Critical X 2-AOI-78-1 Fuel Pool Cleanup System Failure
[3.7] ESTIMATE the time for the fuel pool temperature to rise to 125°F, 150°F, and 200°F using the heat up rates as provided on Attachment 1, Table 1 at least once per shift UNTIL Fuel Pool cooling is restored:
Standard: Proceeds to attachment 1 of 2-AOI-78-1 SAT UNSAT N/A COMMENTS:
Performance Step 2: Critical X Not Critical Attachment 1 (Page 2 of 2)
Spent Fuel Pool Heat
-up Rate at Normal Fuel Pool Level NOTE Determine time to reach target temperatures of 125°F, 150°F and 200°F using the mos t conservative Heat
-up Rate (the highest rate) for days that fall between the dates listed on Table 1. Target Temperature 125 °F Actual fuel pool temp(°F)
- °F Standard: Records Actual Fuel Pool Temperature of 96.3 °F, can record 96 °F to 97 °F under each of the Target Temperatures (3 places).
SAT UNSAT N/A COMMENTS:
JPM RO A 1b 5 *******************************************************************************
Performance Step 3: Critical X Not Critical Difference Standard: Calculates the difference 125
- actual temperature recorded; can record any of the following temperatures 28 °F to 29 °F.
SAT UNSAT N/A COMMENTS:
Performance Step 4: Critical X Not Critical Heat up rate from Table 1
÷ °F/hr Standard: Records the Heat up rate from Table 1 of 1.37 °F under each of the Target Temperatures (3 places) SAT UNSAT N/A COMMENTS:
Performance Step 5: Critical X Not Critical
TIME (in hours) For FUEL POOL TO REACH Target Temperature
= hrs Standard: Divides the difference by 0.99 and calculates a time to reach 125 °F of one of the following 20.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to 21.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
SAT UNSAT N/A COMMENTS:
JPM RO A 1b 6 ***********************************************************************
- Performance Step 6: Critical X Not Critical Difference
Standard: Calculates the difference 150
- actual temperature recorded; can record any of the following temperatures 53 °F to 54 °F.
SAT UNSAT N/A COMMENTS:
Performance Step 7: Critical X Not Critical TIME (in hours) For FUEL POOL TO REACH Target Temperature
= hrs Standard: Divides the difference by 1.37 and calculates a time to reach 150 °F of one of the following 38.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> to 39.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SAT UNSAT N/A COMMENTS:
Performance Step 8: Critical X Not Critical
Difference
Standard: Calculates the difference 200
- actual temperature recorded; can record any of the following temperatures 10 3 °F to 10 4 °F. SAT UNSAT N/A COMMENTS:
JPM RO A 1b 7 *******************************************************************************
Performance Step 9: Critical X Not Critical TIME (in hours) For FUEL POOL TO REACH Target Temperature
= hrs Standard:
Divides the difference by 1.37 and calculates a time to reach 200 °F of one of the following 75.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to 75.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />.
SAT UNSAT N/A COMMENTS:
END OF TASK
STOP TIME
JPM RO A1b 1 OPERATOR: ________________________________
RO DATE:
JPM NUMBER:
RO A 1b TASK NUMBER:
U-078-AB-01 TASK TITLE:
Calculate Time to Reach Temperature Targets for Loss of Fuel Pool Cooling K/A NUMBER:
2.1.25 K/A RATING: RO 3.9 TASK STANDARD:
Complet e of SRM Operability surveillance and determine if core alterations may commence.
LOCATION OF PERFORMANCE:
Simulator REFERENCES/PROCEDURES NEEDED:
3-AOI-78-1, Fuel Pool Cleanup System Failure VALIDATION TIME:
10 minutes PERFORMANCE TIME:
COMMENTS:
__________________________________________________________
________________________________
______________________________________
________________________________
______________________________________
Additional comment sheets attached? YES
___ NO ___
RESULTS: SATISFACTORY
____ UNSATISFACTORY
____ SIGNATURE:
__________________________
DATE: __________
EXAMINER
INITIAL CONDITIONS
- You are a Reactor Operator on Unit 3. The RBCCW sectionalizing valve has failed closed. The Unit Supervisor has entered 3
-AOI-70-1, Loss of Reactor Building Closed Cooling Water and 3
-AOI-78-1, Fuel Pool Cleanup System Failure.
INITIATING CUES
- The Unit Supervisor directs you to estimate the time for the fuel pool temperature to rise to 125 °F, 150 °F, and 200
°F in accordance with 3
-AOI-78-1 step 3.7
.
JPM RO A 1b 3 *******************************************************************************
Simulator ***********************************************************************
- INITIAL CONDITIONS
- You are a Reactor Operator on Unit 3. The RBCCW sectionalizing valve has failed closed. The Unit Supervisor has entered 3
-AOI-70-1, Loss of Reactor Building Closed Cooling Water and 3
-AOI-78-1, Fuel Pool Cleanup System Failure
. INITIATING CUES
- The Unit Supervisor directs you to estimate the time for the fuel pool temperature to rise to 125 °F, 150 °F, and 200
°F in accordance with 3
-AOI-78-1 step 3.7
.
Performance Step 1: Critical Not Critical X 3-AOI-78-1 Fuel Pool Cleanup System Failure
[3.7] ESTIMATE the time for the fuel pool temperature to rise to 125°F, 150°F, and 200°F using the heat up rates as provided on Attachment 1, Table 1 at least once per shift UNTIL Fuel Pool cooling is restored:
Standard: Proceeds to attachment 1 of 3
-AOI-78-1 SAT UNSAT N/A COMMENTS:
Performance Step 2: Critical X Not Critical Attachment 1 (Page 2 of 2)
Spent Fuel Pool Heat
-up Rate at Normal Fuel Pool Level NOTES 1) To determine time to reach target temperatures of 125°F, 150°F, and 200°F USE the following formulas.
- 2) Use the most conservative heat up rate (the highest rate) for days that fall between the
dates listed on Table 1.
Target Temperature 125 °F Actual fuel pool temp(°F)
- °F Standard: Records Actual Fuel Pool Temperatur e of 97.7 °F, can record 97 °F to 98 °F under each of the Target Temperatures (3 places)
. SAT UNSAT N/A COMMENTS:
JPM RO A 1b 5 *******************************************************************************
Performance Step 3: Critical X Not Critical Difference
Standard: Calculates the difference 125
- actual temperature recorded; can record any of the following temperatures 28 °F to 29 °F.
SAT UNSAT N/A COMMENTS:
Performance Step 4: Critical X Not Critical Heat up rate from Table 1
÷ °F/hr Standard: Records the Heat up rate from Table 1 of 0.99 °F under each of the Target Temperatures (3 places). SAT UNSAT N/A COMMENTS:
Performance Step 5: Critical X Not Critical
TIME (in hours) For FUEL POOL TO REACH Target Temperature
= hrs Standard: Divides the difference by 0.99 and calculates a time to reach 125 °F of one of the following 2 7.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to 2 8.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. SAT UNSAT N/A COMMENTS:
JPM RO A 1b 6 *******************************
Performance Step 6: Critical X Not Critical Difference
Standard: Calculates the difference 150
- actual temperature recorded; can record any of the following temperatures 5 2 °F to 5 3 °F. SAT UNSAT N/A COMMENTS:
Performance Step 7: Critical X Not Critical TIME (in hours) For FUEL POOL TO REACH Target Temperature
= hr s Standard: Divides the difference by 0.99 and calculates a time to reach 150 °F of one of the following 5 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> to 53.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
SAT UNSAT N/A COMMENTS:
Performance Step 8: Critical X Not Critical
Difference
Standard: Calculates the difference 200
- actual temperature recorded; can record any of the following temperatures 102 °F to 103 °F.
SAT UNSAT N/A COMMENTS:
JPM RO A 1b 7 *******************************************************************************
Performance Step 9: Critical X Not Critical TIME (in hours) For FUEL POOL TO REACH Target Temperature
= hrs Standard:
Divides the difference by 0.99 and calculates a time to reach 200 °F of one of the following 103 hours0.00119 days <br />0.0286 hours <br />1.703042e-4 weeks <br />3.91915e-5 months <br /> to 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br />.
SAT UNSAT N/A COMMENTS:
END OF TASK
STOP TIME
JPM RO A2 1 OPERATOR: ________________________________
RO DATE:
JPM NUMBER:
A2 Equipment Control
TASK NUMBER:
S-000-AD-55 TASK TITLE:
P S C Head Tank Pump 2B Clearance Boundary K/A NUMBER:
2.2.13 K/A RATING:
RO 4.1 TASK STANDARD:
Determine the clearance boundary for P S C Head Tank Pump 2B LOCATION OF PERFORMANCE:
Class Room
/ Unit 2 Simulator REFERENCES/PROCEDURES NEEDED:
2-47E814-1, 2-45E779-19, 2-47E610-7 5-1, 2-45E2750-4, and 2-4 5E751-3 and 5, NPG-SPP 10.2 VALIDATION TIME:
30 minutes
PERFORMANCE TIME:
COMMENTS:
____________________________________________________________
__________________
___________________________________________________
___________________________
__________________________________________________________________
______________
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY
_____ UNSATISFACTORY_____
SIGNATURE: ____________________________
DATE: ___________
__
EXAMINER JPM RO A2 1 OPERATOR: ________________________________
RO DATE:
JPM NUMBER:
A2 Equipment Control
TASK NUMBER:
S-000-AD-55 TASK TITLE:
P S C Head Tank Pump 2B Clearance Boundary K/A NUMBER:
2.2.13 K/A RATING:
RO 4.1 TASK STANDARD:
Determine the clearance boundary for P S C Head Tank Pump 2B LOCATION OF PERFORMANCE:
Class Room
/ Unit 2 Simulator REFERENCES/PROCEDURES NEEDED:
2-47E814-1, 2-45E779-19, 2-47E610-7 5-1, 2-45E2750-4, and 2-4 5E751-3 and 5, NPG-SPP 10.2 VALIDATION TIME:
30 minutes
PERFORMANCE TIME:
COMMENTS:
____________________________________________________________
__________________
___________________________________________________
___________________________
__________________________________________________________________
______________
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY
_____ UNSATISFACTORY_____
SIGNATURE: ____________________________
DATE: ___________
__
EXAMINER
INITIAL CONDITIONS
- Preventative maintenance is scheduled for the P S C Head Tank Pump 2B Motor. Given: NPG Request for Clearance Page one of Completing Clearance form, NPG-SPG 10.2, Clearance Procedure to Safely Control Energy, Appendix B
INITIATING CUES
- The Unit Supervisor directs you as a Reactor Operator to write a clearance to allow uncoupling the P S C Head Tank Pump 2B in support of preventative maintenance on the motor. ESOMs is not currently working, use the Completing Clearance, Appendix B (page 8 of 11). On Appendix B (page 8 of 11) complete columns 18, 20, 21, and 22 for each identified component.
JPM RO A2 3 *******************************************************************************
Class Room
INITIAL CONDITIONS:
Preventative maintenance is scheduled for the PSC Head Tank Pump 2B Motor.
Given: NPG Request for Clearance Page one of Completing Clearance form, NPG
-SPG 10.2, Clearance Procedure to Safely Control Energy, Appendix B
INITIATING CUES:
The Unit Supervisor directs you as a Reactor Operator to write a clearance to allow uncoupling the PSC Head Tank Pump 2B in support of preventative maintenance on the motor.
ESOMs is not currently working, use the Completing Clearance, Appendix B (page 8 of 11). On Appendix B (page 8 of 11) complete columns 18, 20, 21, and 22 for each identified component.
Performance Step 1: Critical Not Critical X
Review print s to determine required isolation boundary:
2-47E81 4-1 , 2-45E779-19, 2-47E610-7 5-1, 2-45 E 27 50-4, and 2-4 5E751-3 and 5. Standard:
Locates and reviews print s for PSC Head Tank Pump 2B. SAT UNSAT N/A COMMENTS:
Performance Step 2: *Critical X Not Critical
Determines Isolation boundary
. Standard: *Determines at least one of the following components will need to be tagged to prevent pump rotation:
2-75-SHV-603 Pump Discharge Valve
, Closed, Danger Tag
.
AND/OR 2-75-SHV-599 Pump Suction Valve, Closed, Danger Tag.
Tag placement sequence will generally be after the electrical tag placement. NOT critical.
SAT UNSAT N/A COMMENTS:
JPM RO A2 5 *******************************************************************************
Performance Step 3: *Critical X Not Critical
Determines Isolation boundary
. Standard: *2-HS-75-7 6A Control Room Handswitch, Danger Tag, Pull to Lock
.
Tag placement sequence will generally be one or two. NOT critical.
SAT UNSAT N/A COMMENTS:
Performance Step 4: *Critical X Not Critical
Determines Isolation boundary
. Standard: *2B Pump Power Supply, 480 Volt RMOV Board 2B, Breaker 11D, Danger Tag, O ff.
Tag placement sequence will generally be one or two. NOT critical.
SAT UNSAT N/A COMMENTS:
JPM RO A2 6 *******************************************************************************
Performance Step 5: Critical__ Not Critical X
Determines Isolation Boundary
. Standard:
The following circuits may be identified but are not critical for personnel protection
- 2-FU-075-076B Control Circuit 2-FU-075-076 A Indicating Light SAT UNSAT N/A COMMENTS:
END OF TASK
STOP TIME
JPM A3 1 OPERATOR: ________________________________
JPM NUMBER:
548 TASK NUMBER:
Radiation Control TASK TITLE: Locked High Radiation Entry
K/A NUMBER:
2.3.12 K/A RATING:
RO 3.2 TASK STANDARD: Determine dress out requirements and estimate dose to verify within RWP and quarterly limits.
Determines exceeds quarterly administrative dose limit of 1000 mRem and determines that the MG dose alarm will sound for a dose of greater than 200 mRem.
LOCATION OF PERFORMANCE:
Class Room REFERENCES/PROCEDURES NEEDED:
Handout RWP and Survey Map , NPG-SPP 5.1 VALIDATION TIME: 15 minutes
PERFORMANCE TIME:
COMMENTS:
__________________________________________________________
______________________________________________________________________
______________________________________________________________________
Additional comment sheets attached? YES
___ NO ___
RESULTS: SATISFACTORY
____ UNSATISFACTORY
____
SIGNATURE:
__________________________
DATE: __________
EXAMINER
INITIAL CONDITIONS: You are a Browns Ferry employee who has obtained an accumulative yearly dose of 750 mrem.
The job will require you to vent the RWCU Regenerative Hx and to manually close the 3-FCV-69-2 valve and place a mechanical restraining device on the valve. The RWCU Regenerative Hx will be vented from the scaffold at the south end of the Hx's (a scaffold has been erected to be used for venting - cannot leave scaffold while venting is in progress), and will require 3 5 minutes for venting. Then proceed to 3-FCV-69-2 valve to manually close and install the mechanical restraining device, it should require 25 minutes to close the valve and another 25 minutes to install the mechanical restraining device. Assume the 30cm reading will be the whole body dose received at each location. Assume a total travel dose of 25 mrem will be received.
INITIATING CUES: Given the survey map and RWP, determine the following:
Dress-out requirements for entry to perform your assigned task Whether you can complete the assigned task in the area without exceeding your TVA administrative dose limit Whether you can complete the assigned task in the area without exceeding the RWP dose entry limits both rate and total dose, i.e. will you receive an MG alarm (Electronic Dosimeter).
JPM A3 3 *******************************************************************************
Class Room
INITIAL CONDITIONS: You are a Browns Ferry employee who has obtained an accumulative yearly dose of 750 mrem.
The job will require you to vent the RWCU Regenerative Hx and to manually close the 3-FCV-69-2 valve and place a mechanical restraining device on the valve. The RWCU Regenerative Hx will be vented from the scaffold at the south end of the Hx's (a scaffold has been erected to be used for venting - cannot leave scaffold while venting is in progress), and will require 35 minutes for venting. Then proceed to 3-FCV-69-2 valve to manually close and install the mechanical restraining device, it should require 25 minutes to close the valve and another 25 minutes to install the mechanical restraining device. Assume the 30cm reading will be the whole body dose received at each locatio
- n. Assume a total travel dose of 25 mrem will be received.
INITIATING CUES: Given the survey map and RWP, determine the following:
Dress-out requirements for entry to perform your assigned task Whether you can complete the assigned task in the area without exceeding your TVA administrative dose limit Whether you can complete the assigned task in the area without exceeding the RWP dose entry limits both rate and total dose, i.e. will you receive an MG alarm (Electronic Dosimeter).
JPM A3 4 START TIME
Performance Step 1: Critical X Not Critical
Determines Dress Out requirements Standard: Shoe covers - one pair, Coveralls - one pair, Face Shield, Gloves - rubber - two pair, cloth inserts, Booties - plastic - 2 pair , Rain suit, and Hood SAT UNSAT N/A COMMENTS:
Performance Step 2: Critical X Not Critical
Calculates RWCU HX venting dose.
Standard:
35 minutes in a 250 mrem/hr area = 145 to 146 mrem SAT UNSAT N/A COMMENTS:
Performance Step 3: Critical X Not Critical
Calculates 69-2 valve work dose Standard:
50 minutes in a 100 mrem/hr area =
83 to 84 mrem SAT UNSAT N/A COMMENTS:
JPM A3 5 *******************************************************************************
Performance Step 4: Critical X Not Critical
Calculates total dose received Standard:
25 mrem travel + 146 mrem venting + 83 mrem 69
-2 = 254 mrem SAT UNSAT N/A COMMENTS:
Performance Step 5: Critical X Not Critical
Calculates total dose for quarter Standard:
750 mrem + 254 mrem = 1004 mrem SAT UNSAT N/A COMMENTS:
Performance Step 6:
- Critical X Not Critical
Verifies RWP MG Setpoints Standard: MG setpoints: for Dose Rate alarm of 500 mrem/hr will not be exceeded and
- Dose alarm of 200 mrem will be exceeded.
SAT UNSAT N/A COMMENTS:
JPM A3 6 *******************************************************************************
Performance Step 7: Critical X Not Critical
Verifies dose limits for quarter and RWP Standard:
Verifies will have a total dose of greater than 1000 mrem which is above the TVA administrative limit.
SAT UNSAT N/A COMMENTS:
END OF TASK STOP TIME
BROWNS FERRY NUCLEAR PLANT Unit: 3 Permit Number: Training
Page: 1 RADIOLOGICAL WORK PERMIT BRIEFING REQUIRED EVERY ENTRY GENERAL DESCRIPTION Status: Active Start Date: 01
-Jan-This year End Date: 01
-Jan-Next year Type: SPECIFIC MAP ID: Outage: Y Name: Task: ROUTINE PLANT MAINTENANCE PSE: N HP CONTINUOUS Authorization Type: INDIVIDUAL ALARA Review Number: 0A-0010 Primary Work Doc:
Person-mrem Estimate: 1904 Person
-Hrs Estimate: 1082 Dose Alarm: 200 Dose Rate Alarm: 500
DAC-Hrs Tracked: N Work Area
Description:
RWCU HX Room Unit 3 DESCRIPTION OF WORK TO BE PERFORMED Unit 3 Maintenance on RWCU (69) Systems (LHRA VARIOUS DRESS) 200 /
500 ANTI-CONTAMINATION CLOTHING REQUIREMENTS 1 LAB COAT 1,2 BOOTIES, CLOTH, ONE PAIR 1,2 GLOVES, RUBBER, ONE PAIR 1,2,3 CLOTH INSERTS 1,2,3 SHOE COVERS, ONE PAIR 1,2,3 MODESTY CLOTHING 1,2,3 NO PERSONAL OUTER CLOTHING 1,2,3 SURGEON'S CAP 2,3 COVERALLS, ONE PAIR 3 BOOTIES, PLASTIC, TWO PAIR 3 FACE SHIELD 3 RAIN SUIT 3 GLOVES, RUBBER, TWO PAIR 3,4 HOOD
DOSIMETRY REQUIREMENTS ELECTRONIC DOSIMETER TLD BRIEFING REQUIREMENTS PRE-JOB BRIEFING
WORK STEPS 1 MANAGEMENT / WO WALKDOWN 2 3-CI-412 3 OPS VALVE LINEUP OI-69 & HX VENTING 4 07-712928-000 5 06-722560-000 6 06-727133-000 7 06-722556-000 8 06-722559-000 9 06-718308-002 10 06-722558-000 BROWNS FERRY NUCLEAR PLANT Unit: 3 Permit Number: Training
Page: 1 RADIOLOGICAL WORK PERMIT BRIEFING REQUIRED EVERY ENTRY WORKER INSTRUCTIONS 1 DRESSOUT CODE APPLICATIONS
- 1) FLOOR LEVEL INSP, LOW TO MODERATE CONTAMINATION. 2) MINOR MAINTENANCE, NO PRIMARY SYSTEM BREACH.
- 3) PRIMARY SYSTEM BREACH, HEAT EXCHANGER VENTING.
- 4) ANY WORK ABOVE FLOOR LEVEL REQUIRES SAFETY BELT W/ LIFELINE. 5) REQUIRED TO WEAR HEADGEAR OTHER THAN PERSONAL HARDHAT.
2 MONITOR YOUR ED (DAD) FREQUENTLY, EXIT THE AREA PRIOR TO REACHING THE DOSE ALARM SET POINT OR UPON RECEIVING ANY UNEXPECTED ALARMS.
3 DO NOT EXCEED 2 00 mrem PER ENTRY OR DOSE MARGIN (RAD
-REMAINING ALLOWABLE DOSE).
4 REMOTE MONITORING , PEA , OR SIMILAR DEVICE REQUIRED.
5 ED (DAD) TO BE BAGGED (WRAPPED) AND WORN OUTSIDE OF C
-ZONE CLOTHING.
6 REVIEW PLANNED WORK OR INSPECTIONS WITH RAD PROTECTION PRIOR TO ENTRY.
7 UTILIZE TIME, DISTANCE, AND SHIELDING ALARA PRINCIPLES.
8 REVIEW APPROPRIATE SURVEY DATA PRIOR TO ENTRY. NOTE AND AVOID POSTED HOT SPOTS. LOCATE AND UTILIZE LOW DOSE WAITING AREAS.
9 RADWORKER SHALL ADHERE TO ANY SPECIAL INSTRUCTIONS (APR, ETC) ON WHICH HE/SHE HAS BEEN BRIEFED BY RAD PROTECTION.
10 NOTIFY RADCON PRIOR TO ANY SYSTEM BREACH.
11 RAD PROTECTION COVERAGE MAY BE PROVIDED FROM OUTSIDE THE C
-ZONE. 12 SECURE ALL HOSES, ELECTRICAL CORDS, WELDING LEADS AND OTHER SERVICES ENTERING THE C
-ZONE AT THE C-ZONE BOUNDRY AND NOTIFY RAD PROTECTION.
13 NOTIFY RAD PROTECTION OF ANY UNUSUAL RADIOLOGICAL CONDITIONS (FOR EXAMPLE: WATER, LEAKS, RADIATION MONITOR ALARMS).
14 RAD PROTECTION PERMISSION REQUIRED PRIOR TO WELDING, GRINDING, BUFFING OR OTHER SURFACE DISTURBING ACTIVITIES.
APPROVAL Prepaired by: TJFRANK Approved by: MJHAZEL Final Approval: JWSMITH3 End of RWP
JPM RO A2 1 OPERATOR: ________________________________
RO DATE:
JPM NUMBER:
A2 Equipment Control
TASK NUMBER:
S-000-AD-55 TASK TITLE:
P S C Head Tank Pump 2B Clearance Boundary K/A NUMBER:
2.2.13 K/A RATING:
RO 4.1 TASK STANDARD:
Determine the clearance boundary for P S C Head Tank Pump 2B LOCATION OF PERFORMANCE:
Class Room
/ Unit 2 Simulator REFERENCES/PROCEDURES NEEDED:
2-47E814-1, 2-45E779-19, 2-47E610-7 5-1, 2-45E2750-4, and 2-4 5E751-3 and 5, NPG-SPP 10.2 VALIDATION TIME:
30 minutes
PERFORMANCE TIME:
COMMENTS:
____________________________________________________________
__________________
___________________________________________________
___________________________
__________________________________________________________________
______________
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY
_____ UNSATISFACTORY_____
SIGNATURE: ____________________________
DATE: ___________
__
EXAMINER