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| | number = ML081010242 | | | number = ML081010242 |
| | issue date = 09/08/2008 | | | issue date = 09/08/2008 |
| | title = James A. Fitzpatrick Nuclear Plant Renewed Facility Operating License No. DPR-59 / Appendix a - Technical Specifications | | | title = Renewed Facility Operating License No. DPR-59 / Appendix a - Technical Specifications |
| | author name = | | | author name = |
| | author affiliation = NRC/NRR | | | author affiliation = NRC/NRR |
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| =Text= | | =Text= |
| {{#Wiki_filter:APPENDIX A TECHNICAL SPECIFICATIONS FOR JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 TABLE OF CONTENTS 1.0 USE AND APPLICATION | | {{#Wiki_filter:}} |
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| ===1.1 Definitions===
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| ...........................................................................................
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| 1.1-1 1.2 Logical Connectors
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| .............................................................................
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| 1.2-1 1.3 Completion Times ................................
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| I ..............................................
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| 1.3-1 1.4 Frequency
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| ...........................................................................................
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| 1.4-1 2.0 SAFETY LIMITS (SLs)2.1 SLs .....................................................................................................
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| 2.0-1 2.2 SL Violations
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| .......................................................................................
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| 2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY
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| ..................
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| 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY
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| ................................
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| 3.0-3 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM) ..............................................................
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| 3.1.1-1 3.1.2 Reactivity Anomalies
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| ..........................................................................
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| 3.1.2-1 3.1.3 Control Rod OPERABILITY
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| ..................................................................
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| 3.1.3-1 3.1.4 Control Rod Scram Times ..................................................................
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| 3.1.4-1 3.1.5 Control Rod Scram Accumulators
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| .....................................................
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| 3.1.5-1 3.1.6 Rod Pattern Control ............................................................................
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| 3.1.6-1 3.1.7 Standby Liquid Control (SLC) System ................................................
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| 3.1.7-1 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves ........ 3.1.8-1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) ...... 3.2.1-1 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR) ......................................
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| 3.2.2-1 3.2.3 LINEAR HEAT GENERATION RATE (LHGR) .........................................
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| 3.2.3-1 3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation
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| ..........................
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| 3.3.1.1-1 3.3.1.2 Source Range Monitor (SRM) Instrumentation
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| ................................
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| 3.3.1.2-1 3.3.2.1 Control Rod Block Instrumentation
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| ...................................................
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| 3.3.2.1-1 3.3.2.2 Feedwater and Main Turbine High Water Level Trip Instrumentation
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| ...................................................................
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| 3.3.2.2-1 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation
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| ............................
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| 3.3.3.1-1 3.3.3.2 Remote Shutdown System .................................................................
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| 3.3.3.2-1 3.3.4.1 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT)
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| Instrumentation
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| ...................................
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| 3.3.4.1-1 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation
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| ...............
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| 3.3.5.1-1 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation
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| ..........................................................................
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| 3.3.5.2-1 3.3.6.1 Primary Containment Isolation Instrumentation
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| ..............................
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| 3.3.6.1-1 3.3.6.2 Secondary Containment Isolation Instrumentation
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| .........................
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| 3.3.6.2-1 3.3.7.1 Control Room Emergency Ventilation Air Supply (CREVAS)System Instrumentation
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| .........................
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| ; .................................
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| .3.3.7.1-1 3.3.7.2 Condenser Air Removal Pump Isolation Instrumentation
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| ................
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| 3.3.7.2-1 3.3.7.3 Emergency Service Water (ESW) System Instrumentation
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| ..............
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| 3.3.7.3-1 (continued)
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| JAFNPP I Amendment 287 TABLE OF CONTENTS 3.3 3.3.8.1 3.3.8.2 3.4 3.4.1 3.4.2 3.4.3 3.4.4 3.4.5 3.4.6 3.4.7 3.4.8 3.4.9 3.5 3.5.1 3.5.2 3.5.3 3.6 3.6.1.1 3.6.1.2 3.6.1.3 3.6.1.4 3.6.1.5 3.6.1.6 3.6.1.7 3.6.1.8 3.6.1.9 3.6.2.1 3.6.2.2 3.6.2.3 3.6.2.4 3.6.3.1 3.6.3.2 3.6.4.1 3.6.4.2 3.6.4.3 INSTRUMENTATION (continued)
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| Loss of Power (LOP) Instrumentation
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| .......Reactor Protection System (RPS) Electric Power Monitoring
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| ...................REACTOR COOLANT SYSTEM (RCS)Recirculation Loops Operating
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| ............Jet Pumps ......................
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| Safety/Relief Valves (S/RVs) .............RCS Operational LEAKAGE ...............RCS Leakage Detection Instrumentation
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| ........RCS Specific Activity .......Residual Heat Removal (RHR) Shutdown Cooling.System -Hot Shutdown ...............Residual Heat Removal (RHR) Shutdown Cooling System- Cold Shutdown ..............RCS Pressure and Temperature (P/T) Limits ......EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM ECCS- Operating
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| ...................ECCS- Shutdown ....................RCIC System .....................
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| CONTAINMENT SYSTEMS Primary Containment
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| .................
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| Primary Containment Air Locks ...Primary Containment Isolation Valves (PCIVs).Drywell Pressure ...................Drywell Air Temperature
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| ...........Reactor Building-to-Suppression Chamber Vacuum Breakers Suppression Chamber-to-Drywell Vacuum Breakers ....Main Steam Leakage Collection (MSLC) System .....Residual Heat Removal (RHR) Containment Spray System .Suppression Pool Average Temperature
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| .........Suppression Pool Water Level .............Residual Heat Removal (RHR) Suppression Pool Cooling .Drywell-to-Suppression Chamber Differential Pressure .Primary Containment Oxygen Concentration
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| .......Containment Atmosphere Dilution (CAD) System .....Secondary Containment
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| ................Secondary Containment Isolation Valves (SCIVs) ....Standby Gas Treatment (SGT) System ..........3.3.8.1-1 3.3.8.2-1 3.4.1-1 3.4.2-1 3.4.3-1 3.4.4-1 3.4.5-1 3.4.6-1 3.4.7-1 3.4.8-1 3.4.9-1 3.5.1-1 3.5.2-1 3.5.3-1 3.6.1.1-1 3.6.1.2-1 3.6.1.3-1 3.6.1.4-1 3.6.1.5-1 3.6.1.6-1 3.6.1.7-1 3.6.1.8-1 3.6.1.9-1 3.6.2.1-1 3.6.2.2-1 3.6.2.3-1 3.6.2.4-1 3.6.3.1-1 3.6.3.2-1 3.6.4.1-1 3.6.4.2-1 3.6.4.3-1 3.7 3.7.1 3.7.2 PLANT SYSTEMS Residual Heat Removal Service Water (RHRSW) System .Emergency Service Water (ESW) System and Ultimate Heat Sink (UHS) ................
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| 3.7.1-1 3.7.2-1 (continued)
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| JAFNPP ii Amendment 274 TABLE OF CONTENTS 3.7 PLANT SYSTEMS (continued)
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| ====3.7.3 Control====
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| Room Emergency Ventilation Air Supply (CREVAS)System ..3.7.3-1 3.7.4 Control Room Air Conditioning (AC) System ..3.7.4-1 3.7.5 Main Condenser Steam Jet Air Ejector (SJAE) Offgas 3.7.5-1 3.7.6 Main Turbine Bypass System ..............3.7.6-1 3.7.7 Spent Fuel Storage Pool Water Level .........3.7.7-1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources-Operating
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| ................3.8.1-1 3.8.2 AC Sources-Shutdown
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| ....3.8.2-1 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air. .3.8.3-1 3.8.4 DC Sources- Operating
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| ................3.8.4-1 3.8.5 DC Sources- Shutdown .................3.8.5-1 3.8.6 Battery Cell Parameters
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| ...............3.8.6-1 3.8.7 Distribution Systems-Operating
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| ...........3.8.7-1 3.8.8 Distribution Systems-Shutdown
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| ............3.8.8-1 3.9 REFUELING OPERATIONS
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| ====3.9.1 Refueling====
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| Equipment Interlocks
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| ............3.9.1-1 3.9.2 Refuel Position One-Rod-Out Interlock
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| ........3.9.2-1 3.9.3 Control Rod Position .....3.9.3-1 3.9.4 Control Rod Position Indication
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| ...3.9.4-1 3.9.5 Control Rod OPERABILITY-Refueling
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| ..........3.9.5-1 3.9.6 Reactor Pressure Vessel (RPV) Water Level ......3.9.6-1 3.9.7 Residual Heat Removal (RHR) -High Water Level ....3.9.7-1 3.9.8 Residual Heat Removal (RHR)-Low Water Level .....3.9.8-1 3.10 SPECIAL OPERATIONS 3.10.1 Inservice Leak and Hydrostatic Testing Operation
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| ...3.10.1-1 3.10.2 Reactor Mode Switch Interlock Testing ........3.10.2-1 3.10.3 Single Control Rod Withdrawal -Hot Shutdown .....3.10.3-1 3.10.4 Single Control Rod Withdrawal -Cold Shutdown .....3.10.4-1 3.10.5 Single Control Rod Drive (CRD) Removal -Refueling
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| ..3.10.5-1 3.10.6 Multiple Control Rod Withdrawal-Refueling
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| ......3.10.6-1 3.10.7 Control Rod Testing-Operating
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| ...... .......3.10.7-1 3.10.8 SHUTDOWN MARGIN (SDM) Test- Refueling
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| ........3.10.8-1 4.0 DESIGN FEATURES 4.1 Site Location .4.0-1 4.2 Reactor Core .....................4.0-1 4.3 Fuel Storage. ...... 4.0-2 (continued)
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| JAFNPP iii Amendment 274 TABLE OF CONTENTS (continued)
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| ===5.0 ADMINISTRATIVE===
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| CONTROLS 5.1 Responsibility
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| ....................5.1-1 5.2 Organization
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| ..5.2-1 5.3 Plant Staff Qualifications.
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| 5.3-1 5.4 Procedures.
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| ..... 5.4-1 5.5 Programs and Manuals .................5.5-1 5.6 Reporting Requirements
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| ................5.6-1 5.7 High Radiation Area .................5.7-1 JAFNPP iv Amendment 274 Definitions 1.1 1.0 USE AND APPLICATION
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| | |
| ===1.1 Definitions===
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| The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)CHANNEL CALIBRATION CHANNEL CHECK The APLHGR shall be applicable to a specific planar height and is equal to the sum of the heat generation rate per unit length of fuel rod for all the fuel rods in the specified assembly at the specified height divided by the number of fuel rods in the fuel assembly at the height.A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors.
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| The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY and the CHANNEL FUNCTIONAL TEST.Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps.A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation.
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| This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.(continued)
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| JAFNPP 1.1-1 Amendment 274
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| ---Definitions 1.1 1.1 Definitions (continued)
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| CHANNEL FUNCTIONAL TEST CORE ALTERATION A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY.
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| The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps.CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel. The following exceptions are not considered to be CORE ALTERATIONS:
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| : a. Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement);
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| and b. Control rod movement, provided there are no fuel assemblies in the associated core cell.Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.CORE OPERATING LIMITS REPORT (COLR)DOSE EQUIVALENT I-131 The COLR is the plant specific document that provides cycle specific parameter limits for the current reload cycle. These cycle specific limits shall be determined for each reload cycle in accordance with Specification
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| ====5.6.5. Plant====
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| operation within these limits is addressed in individual Specifications.
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| DOSE EQUIVALENT I-131 shall be that concentration of 1-131 (microcuries/gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132. I-133. I-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in International Commission on Radiological Protection Publication 30 (ICRP-30)."Limits for Intake by Workers," or in NRC Regulatory Guide 1.109. Rev. 1, 1977.(continued)
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| JAFNPP 1.1-2 Amendment 274 Definitions 1.1 1.1 Definitions (continued)
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| ISOLATION INSTRUMENTATION RESPONSE TIME The ISOLATION INSTRUMENTATION RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its isolation initiation setpoint at the channel sensor until the isolation valve receives the isolation signal (e.g.. de-energization of the main steam isolation valve solenoids).
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| The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
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| In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.LEAKAGE LEAKAGE shall be: a. Identified LEAKAGE 1. LEAKAGE into the drywell, such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank: or 2. LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE;b. Unidentified LEAKAGE All LEAKAGE into the drywell that is not identified LEAKAGE;c. Total LEAKAGE Sum of the identified and unidentified LEAKAGE;d. Pressure Boundary LEAKAGE ,, _ _, _LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body.pipe wall, or vessel wall.(continued)
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| JAFNPP 1.1-3 Amendment 274 Definitions 1.1 1.1 Definitions (continued)
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| LINEAR HEAT GENERATION RATF II WRH3 LOGIC SYSTEM FUNCTIONAL TEST MINIMUM CRITICAL POWER RATIO (MCPR)The LHGR shall be the heat generation rate per unit length. o!fuei rod. !t the Integral of the heat flux over the heat transfer area associated with the unit length.A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all logic components required for OPERABILITY of a logic circuit, from as close to the sensor as practicable up to, but not Including, the actuated device, to verify OPERABILITY.
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| The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.The MCPR shall be the smallest critical power that exists in the core for each type of fuel. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
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| I MODE OPERABLE-OPERABILITY (continued)
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| JAFNPP 1.1-4 Amendment 287 Definitions 1.1 1.1 Definitions (continued)
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| RATED THERMAL POWER (RTP)REACTOR PROTECTION SYSTEM (RPS) RESPONSE TIME SHUTDOWN MARGIN (SDM)RTP shall be a total reactor core heat transfer rate to the reactor coolant of 2536 MWt.The RPS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its RPS trip setpoint at the channel sensor until de-energization of the scram pilot valve solenoids.
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| The response time may be measured by means of any series of sequential.
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| overlapping, or total steps so that the entire response time is measured.
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| In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.SDM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical assuming that: a. The reactor is xenon free: b. The moderator temperature is 68 0 F; and c. All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.
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| With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.STAGGERED TEST BASIS THERMAL POWER A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency.
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| so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.(continued)
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| JAFNPP 1.1-5 Amendment 274 Definitions 1.1 1.1 Definitions (continued)
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| TURBINE BYPASS SYSTEM The TURBINE BYPASS SYSTEM RESPONSE TIME consists RESPONSE TIME of two components:
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| : a. The time from initial movement of the main turbine stop valve or control valve until 80X of the assumed turbine bypass capacity is established:
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| and b. The time from initial movement of the main turbine stop valve or control valve until initial movement of the turbine bypass valve.The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.JAFNPP 1.1-6 Amendment 274 Definitions
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| | |
| ===1.1 Table===
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| 1.1-1 (page 1 of 1)MODES REACTOR MODE AVERAGE REACTOR MODE TITLE SWITCH POSITION COOLANT TEMPERATURE
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| (.F)1 Power Operation Run NA 2 Startup Refuel(a) or Startup/Hot NA Standby 3 Hot Shutdown(a)
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| Shutdown > 212 4 Cold Shutdown(a)
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| Shutdown s 212 5 Refueling(b)
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| Shutdown or Refuel NA (a) All reactor vessel head closure bolts fully tensioned.(b) One or more reactor vessel head closure bolts less than fully tensioned.
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| JAFNPP 1.1-7 Amendment 274 Logical Connectors 1.2 1.0 USE AND APPLICATION
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| ===1.2 Logical===
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| Connectors PURPOSE The purpose of this section is to explain the meaning of logical connectors.
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| Logical connectors are used in Technical Specifications (TS)to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies.
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| The only logical connectors that appear in TS are AND and OR. The physical arrangement of these connectors coRiiituteilogical conventions with specific meanings.BACKGROUND Several levels of logic may be used to state Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action). The successive levels of logic are identified by additional digits of the Required Action number and by successive indentions of the logical connectors.
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| When logical connectors are used to state a Condition, Completion Time, Surveillance, or Frequency.
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| only the first level of logic is used, and the logical connector is left justified with the statement of the Condition, Completion Time, Surveillance, or Frequency.
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| EXAMPLES The following examples illustrate the use of logical connectors.(continued)
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| JAFNPP 1.2-1 Amendment 274
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| --Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES (continued)
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| EXAMPLE 1.2-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Verify ...AND A.2 Restore ...In this example the logical connector AND is used to indicate that when in Condition A, bothiRequired Actions A.1 and A.2 must be completed.(continued)
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| JAFNPP 1.2-2 Amendment 274 Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES (continued)
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| EXAMPLE 1.2-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Trip ...OR A.2.1 Verify ..AND A.2.2.1 Reduce ...OR A.2.2.2 Perform ...OR A.3 Align ...This example represents a more complicated use of logical connectors.
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| Required Actions A.1. A.2. and A.3 are alternative choices, only one of which must be performed as indicated by the use of the logical connector OR and the left justified placement.
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| Any one of these three Actions may be chosen. If A.2 is chosen. then both A.2.1 and A.2.2 must be performed as indicated by the logical connector AND.Required Action A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical connector OR indicates that A.2.2.1 and A.2.2.2 are alternative cHoices. only one of which must be performed.
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| JAFNPP 1.2-3 Amendment 274
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| -Completion Times 1.3 1.0 USE AND APPLICATION
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| | |
| ===1.3 Completion===
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| Times PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.BACKGROUND Limiting Conditions for Operation (LCOs) specify minimum requirements for ensuring safe operation of the plant. The ACTIONS associated with an LCO state Conditions that typically describe the ways in which the requirements of the LCO can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Times(s).DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of discovery of a situation (e.g.. inoperable equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the plant is in a MODE or specified condition stated in the Applicability of the LCO. Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the plant is not within the LCO Applicability.
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| If situations are discovered that require entry into more than one Condition at a time within a single LCO (multiple Conditions), the Required Actions for each Condition must be performed within the associated Completion Time. When in multiple Conditions, separate Completion Times are tracked for each Condition starting from the time of discovery of the situation that required entry into the Condition.
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| Once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition, discovered to be inoperable or not within limits.will not result in separate entry into the Condition unless specifically stated. The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition.(continued)
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| JAFNPP 1.3-1 Amendment 274 Completion Times 1.3 1.3 Completion Times DESCRIPTION However, when a subsequent division, subsystem, component, (continued) or variable expressed in the Condition is discovered to be inoperable or not within limits, the Completion Time(s) may be extended.
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| To apply this Completion Time extension, two criteria must first be met. The subsequent inoperability:
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| : a. Must exist concurrent with the first inoperability; and b. Must remain inoperable or not within limits after the first inoperabi ity is resolved.The total Completion Time allowed for completing a Required Action to address the subsequent inoperability shall be limited to the more restrictive of either: a. The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours; or b. The stated Completion Time as measured from discovery of the subsequent inoperability.
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| The above Completion Time extension does not apply to those Specifications that have exceptions that allow completely separate re-entry into the Condition (for each division, subsystem, component or variable expressed in the Condition) and separate tracking of Completion Times based on this re-entry.
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| These exceptions are stated in individual Specifications.
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| The above Completion Time extension does not apply to a Completion Time with a modified "time zero." This modified"time zero" may be expressed as a repetitive time (i.e.."once per 8 hours," where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase"from discovery
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| ..." Example 1.3-3 illustrates one use of this type of Completion Time. The 10 day Completion Time specified for Condition A and B in Example 1.3-3 may not be extended.(continued)
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| JAFNPP 1.3-2 Amendment 274 Completion Times 1.3 1.3 Completion Times (continued)
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| EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.
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| EXAMPLE 1.3-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required B.1 Be in MODE 3. 12 hours Action and associated AND Completion Time not B.2 Be in MODE 4. 36 hours met.Condition B has two Required Actions. Each Required Action has its own separate Completion Time. Each Completion Time is referenced to the time that Condition B is entered.The Required Actions of Condition B are to be in MODE 3 within 12 hours AND in MODE 4 within 36 hours. A total of 12 hours is allowed for reaching MODE 3 and a total of 36 hours (not 48 hours) is allowed for reaching MODE 4 from the time that Condition B was entered. If MODE 3 is reached within 6 hours. the time allowed for reaching MODE 4 is the next 30 hours because the total time allowed for reaching MODE 4 is 36 hours.If Condition for reaching B is entered while in MODE 3, MODE 4 is the next 36 hours.the time allowed (continued)
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| JAFNPP 1.3-3 Amendment 274 Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
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| EXAMPLE 1.3-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pump A.1 Restore pump to 7 days inoperable.
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| OPERABLE status.B. Required B.1 Be in MODE 3. 12 hours Action and associated AND Completion Time not B.2 Be in MODE 4. 36 hours met.When a pump is declared inoperable.
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| Condition A is entered.If the pump is not restored to OPERABLE status within 7 days, Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start. If the inoperable pump is restored to OPERABLE status after Condition B is entered, Conditions A and B are exited, and therefore, the Required Actions of Condition B may be terminated.
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| When a second pump is declared inoperable while the first pump is still inoperable, Condition A is not re-entered for the second pump. LCO 3.0.3 is entered, since the ACTIONS do not include a Condition for more than one inoperable pump.The Completion Time clock for Condition A does not stop after LCO 3.0.3 is entered, but continues to be tracked from the time Condition A was initially entered.While in LCO 3.0.3. if one of the inoperable pumps is restored to OPERABLE status and the Completion Time for Condition A has not expired. LCO 3.0.3 may be exited and operation continued in accordance with Condition A.(continued)
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| JAFNPP 1.3-4 Amendment 274 Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-2 (continued)
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| While in LCO 3.0.3, if one of the inoperable pumps is restored to OPERABLE status and the Completion Time for Condition A has expired, LCO 3.0.3 may be exited and operation continued in accordance with Condition B. The Completion Time for Condition B is tracked from the time the Condition A Completion Time expired.On restoring one of the pumps to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first pump was declared inoperable.
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| This Completion Time may be extended if the pump restored to OPERABLE status was the first inoperable pump. A 24 hour extension to the stated 7 days is allowed, provided this does not result in the second pump being inoperable for> 7 days.(continued)
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| JAFNPP 1.3-5 Amendment 274 Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
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| EXAMPLE 1.3-3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Restore 7 days Function X Function X subsystem subsystem to AND inoperable.
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| OPERABLE status.10 days from discovery of failure to meet the LCO B. One B.1 Restore 72 hours Function Y Function Y subsystem subsystem to AND inoperable.
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| OPERABLE status.10 days from discovery of failure to meet the LCO C. One C.1 Restore 12 hours Function X Function X subsystem subsystem to inoperable.
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| OPERABLE status.AND OR One C.2 Restore 12 hours Function Y Function Y subsystem subsystem to inoperable.
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| OPERABLE status.(continued)
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| JAFNPP 1.3-6 Amendment 274 Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)
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| When one Function X subsystem and one Function Y subsystem are inoperable, Condition A and Condition B are concurrently applicable.
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| The Completion Times for Condition A and Condition B are tracked separately for each subsystem.
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| starting from the time each subsystem was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second subsystem was declared inoperable (i.e., the time the situation described in Condition C was discovered).
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| If Required Action C.2 is completed within the specified Completion Time, Conditions B and C are exited. If the Completion Time for Required Action A.1 has not expired.operation may continue in accordance with Condition A. The remaining Completion Time in Condition A is measured from the time the affected subsystem was declared inoperable (i.e., initial entry into Condition A).The Completion Times of Conditions A and B are modified by a logical connector, with a separate 10 day Completion Time measured from the time it was discovered the LCO was not met. In this example, without the separate Completion Time, it would be possible to alternate between Conditions A. B.and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO.The separate Completion Time modified by the phrase "from discovery of failure to meet the LCO" is designed to prevent indefinite continued operation while not meeting the LCO.This Completion Time allows for an exception to the normal"time zero" for beginning the Completion Time "clock". In this instance, the Completion Time "time zero" is specified as commencing at the time the LCO was initially not met, instead of at the time the associated Condition was entered.(continued)
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| JAFNPP 1.3-7 Amendment 274 Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
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| EXAMPLE 1.3-4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve(s) 4 hours valves to OPERABLE inoperable.
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| status.B. Required B.1 Be in MODE 3. 12 hours Action and associated AND Completion Time not B.2 Be in MODE 4. 36 hours met.A single Completion Time is used for any number of valves inoperable at the same time. The Completion Time associated with Condition A is based on the initial entry into Condition A and is not tracked on a per valve basis.Declaring subsequent valves inoperable, while Condition A is still in effect, does not trigger the tracking of separate Completion Times.Once one of the valves has been restored to OPERABLE status.the Condition A Completion Time is not reset, but continues from the time the first valve was declared inoperable.
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| The Completion Time may be extended if the valve restored to OPERABLE status was the first inoperable valve. The Condition A Completion Time may be extended for up to 4 hours provided this does not result in any subsequent valve being inoperable for > 4 hours.If the Completion Time of 4 hours (plus the extension) expires while one or more valves are still inoperable.
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| Condition B is entered.(continued)
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| JAFNPP 1.3-8 Amendment 274
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| ---Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
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| EXAMPLE 1.3-5 ACTIONS----------------------------
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| NOTE---------------------------
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| Separate Condition entry is allowed for each inoperable valve.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve to 4 hours valves OPERABLE status.inoperable.
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| B. Required B.1 Be in MODE 3. 12 hours Action and associated AND Completion Time not B.2 Be in MODE 4. 36 hours met.The Note above the ACTIONS Table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition.
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| the Note would appear in that Condition rather than at the top of the ACTIONS Table.The Note allows Condition A to be entered separately for each inoperable valve, and Completion Times tracked on a per valve basis. When a valve is declared inoperable.
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| Condition A is entered and its Completion Time starts. If subsequent valves are declared inoperable.
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| Condition A is entered for each valve and separate Completion Times start and are tracked for each valve.(continued)
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| JAFNPP 1.3-9 Amendment 274 Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-5 (continued)
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| If the Completion Time associated with a valve in Condition A expires, Condition B is entered for that valve.If the Completion Times associated with subsequent valves in Condition A expire, Condition B is entered separately for each valve and separate Completion Times start and are tracked for each valve. If a valve that caused entry into Condition B is restored to OPERABLE status. Condition B is exited for that valve.Since the Note in this example allows multiple Condition entry and tracking of separate Completion Times, Completion Time extensions do not apply.EXAMPLE 1.3-6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel A.1 Perform Once per inoperable.
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| SR 3.x.x.x. 8 hours OR A.2 Place channel in 8 hours trip.B. Required B.1 Be in MODE 3. 12 hours Action and associated Completion Time not met.(continued)
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| JAFNPP 1.3-10 Amendment 274 Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-6 (continued)
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| Entry into Condition A offers a choice between Required Action A.1 or A.2. Required Action A.1 has a "once per" Completion Time, which qualifies for the 25X extension, per SR 3.0.2. to each performance after the initial performance.
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| The initial 8 hour interval of Required Action A.1 begins when Condition A is entered and the initial performance of Required Action A.1 must be complete within the first 8 hour interval.
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| If Required Action A.1 is followed and the Required Action is not met within the Completion Time (plus the extension allowed by SR 3.0.2). Condition B is entered.If Required Action A.2 is followed and the Completion Time of 8 hours is not met, Condition B is entered.If after entry into Condition B. Required Action A.1 or A.2 is met. Condition B is exited and operation may then continue in Condition A.(continued)
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| JAFNPP 1.3-11 Amendment 274 Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
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| EXAMPLE 1.3-7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Verify affected 1 hour subsystem subsystem inoperable.
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| isolated.
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| AND Once per 8 hours thereafter AND A.2 Restore subsystem 72 hours to OPERABLE status.B. Required B.1 Be in MODE 3. 12 hours Action and associated AND Completion Time not B.2 Be in MODE 4. 36 hours met.Required Action A.1 has two Completion Times. The 1 hour Completion Time begins at the time the Condition is entered and each "Once per 8 hours thereafter" interval begins upon performance of Required Action A.1.If after Condition A is entered. Required Action A.1 is not met within either the initial 1 hour or any subsequent 8 hour interval from the previous performance (plus the extension allowed by SR 3.0.2). Condition B is entered. The Completion Time clock for Condition A does not stop after Condition B is entered, but continues from the time Condition A was initially entered. If Required Action A.1 is met after Condition B is entered, Condition B is exited (continued)
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| JAFNPP 1.3-12 Amendment 274 Completion Times 1.3', 1.3 Completion Times EXAMPLES EXAMPLE 1.3-7 (continued) and operation may continue in accordance with Condition A.provided the Completion Time for Required Action A.2 has not expired.IMMEDIATE When "Immediately" is used as a Completion Time, the COMPLETION TIME Required Action should be pursued without delay and in a controlled manner.JAFNPP 1.3-13 Amendment 274
| |
| --Frequency 1.4 1.0 USE AND APPLICATION
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| | |
| ===1.4 Frequency===
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| PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.
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| DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which the Surveillance must be met in order to meet the associated Limiting Condition for Operation (LCO). An understanding of the correct application of the specified Frequency is necessary for compliance with the SR.The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 3.0.Surveillance Requirement (SR) Applicability.
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| The "specified Frequency" consists of the requirements of the Frequency column of each SR. as well as certain Notes in the Surveillance column that modify performance requirements.
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| Sometimes special situations dictate when the requirements of a Surveillance are to be met. They are "otherwise stated' conditions allowed by SR 3.0.1. They may be stated as clarifying Notes in the Surveillance, as part of the Surveillance, or both.Situations where a Surveillance could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated LCO is within its Applicability, represent potential SR 3.0.4 conflicts.
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| To avoid these conflicts, the SR (i.e., the Surveillance or the Frequency) is stated such that it is only "required" when it can be and should be performed.
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| With an SR satisfied.
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| SR 3.0.4 imposes no restriction.
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| The use of "met" or "performed" in these instances conveys specific meanings.
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| A Surveillance is "met" only when the acceptance criteria are satisfied.
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| Known failure of the requirements of a Surveillance, even without a Surveillance specifically being "performed." constitutes a Surveillance not "met." "Performance" refers only to the requirement to specifically determine the ability to meet the acceptance (continued)
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| JAFNPP 1.4-1 Amendment 274 Frequency 1.4 1.4 Frequency DESCRIPTION (continued) criteria.
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| Some Surveillances contain notes that modify the Frequency of performance of the conditions during which the acceptance criteria must be satisfied.
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| For these Surveillances, the MODE entry restrictions of SR 3.0.4 may not apply. Such a Surveillance is not required to be performed prior to entering a MODE or other specified condition in the Applicability of the associated LCO if any of the following three conditions are satisfied:
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| : a. The Surveillance is not required to be met in the MODE or other specified condition to be entered: or b. The Surveillance is required to be met in the MODE or other specified condition to be entered, but has been performed within the specified Frequency (i.e.. it is current) and is known not to be failed; or c. The Surveillance is required to be met, but not performed, in the MODE or other specified condition to be entered, and is known not to be failed.Examples 1.4-3, 1.4-4, 1.4-5. and 1.4-6 discuss these special situations.
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| EXAMPLES The following examples illustrate the various ways that Frequencies are specified.
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| In these examples, the Applicability of the LCO (LCO not shown) is MODES 1, 2, and 3.(continued)
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| JAFNPP 1.4-2 Amendment 274 Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-1 (continued)
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| SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK. 12 hours Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours) during which the associated Surveillance must be performed at least one time.Performance of the Surveillance initiates the subsequent interval.
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| Although the Frequency is stated as 12 hours, an extension of the time interval to 1.25 times the interval specified in the Frequency is allowed by SR 3.0.2 for operational flexibility.
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| The measurement of this interval continues at all times, even when the SR is not required to be met per SR 3.0.1 (such as when the equipment is inoperable, a variable is outside specified limits. or the plant is outside the Applicability of the LCO). If the interval specified by SR 3.0.2 is exceeded while the plant is in a MODE or other specified condition in the Applicability of the LCO, and the performance of the Surveillance is not otherwise modified (refer to Examples 1.4-3 and 1.4-4). then SR 3.0.3 becomes applicable.
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| If the interval as specified by SR 3.0.2 is exceeded while the plant is not in a MODE or other specified condition in the Applicability of the LCO for which performance of the SR is required, the Surveillance must be performed within the Frequency requirements of SR 3.0.2 prior to entry into the MODE or other specified condition.
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| Failure to do so would result in a viol ation of SR 3.0.4.(continued)
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| JAFNPP 1.4-3 Amendment 274 A. --.Frequency 1.4 1.4 Frequency EXAMPLES (continued)
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| EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify flow is within limits. Once within 12 hours after 2 25% RTP AND 24 hours thereafter Example 1.4-2 has two Frequencies.
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| The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector "AND" indicates that both Frequency requirements must be meFT Each time reactor power is increased from a power level < 25% RTP to 2 25% RTP. the Surveillance must be performed within 12 hours.The use of "once' indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by "AND"). This type of Frequency does not qualify for the extension allowed by SR 3.0.2."Thereafter" indicates future performances must be established per SR 3.0.2, but only after a specified condition is first met (i.e.. the "once" performance in this example).
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| If reactor power decreases to < 25% RTP, the measurement of both intervals stops. New intervals start upon reactor power reaching 25% RTP.(continued)
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| JAFNPP 1.4-4 Amendment 274 A.'.* " .. -Frequency 1.4 1.4 Frequency EXAM PLES (continued)
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| EXAMPLE 1.4-3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY-NOTE-------------
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| Not required to be performed Until 12 hours after 25% RTP.Perform channel adjustment.
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| 7 days The interval continues whether or not the plant operation is < 25% RTP between performances.
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| As the Note modifies the required performance of the Surveillance, it is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is < 25% RTP, this Note allows 12 hours after power reaches 2: 25% RTP to perform the Surveillance.
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| The: Surveillance is still considered to be within the "specified Frequency." Therefore, if the Surveillance were not performed within the 7 day interval (plus the extension allowed by SR 3.0.2), but operation was < 25% RTP, it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not exceed 12 hours (plus the extension allowed by SR 3.0.2) with power > 25% RTP.Once the plant reaches 25% RTP, 12 hours would be allowed for completing the Surveillance.
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| If the Surveillance were not performed within this 12 hour interval (plus the extension allowed by SR 3.0.2), there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.(continued)
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| I JAFNPP 1.4-5 A Anendment
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| -Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-4 (continued)
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| SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY-------------
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| NOTE------------------
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| Only required to be met in MODE 1.Verify leakage rates are within limits. 24 hours Example 1.4-4 specifies that the requirements of this Surveillance do not have to be met until the plant is in MODE 1. The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1. However, the Note constitutes an "otherwise stated" exception to the Applicability of this Surveillance.
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| Therefore, if the Surveillance were not performed within the 24 hour interval (plus the extension allowed by SR 3.0.2).but the plant was not in MODE 1, there would be no failure of the SR nor failure to meet the LCO. Therefore, no violation of SR 3.0.4 occurs when changing MODES, even with the 24 hour Frequency exceeded, provided the MODE change was not made into MODE 1. Prior to entering MODE 1 (assuming again that the 24 hour Frequency were not met), SR 3.0.4 would require satisfying the SR.(continued)
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| JAFNPP 1.4-6 Amendment 274 Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-5 (continued)
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| SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY-.---------------
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| NOTE--................
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| Only required to be performed in MODE 1.Perform complete cycle of the valve. 7 days The interval continues, whether or not the plant operation is in MODE 1, 2, or 3 (the assumed Applicability of the associated LCO) between performances.
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| As the Note modifies the required performance of the Surveillance, the Note is construed to be part of the"specified Frequency." Should the 7 day interval be exceeded while operation is not in MODE 1, this Note allows entry into and operation in MODES 2 and 3 to perform the Surveillance.
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| The Surveillance is still considered to be performed within the "specified Frequency" if completed prior to entering MODE 1. Therefore, if the Surveillance were not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval, but operation was not in MODE 1. it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met.provided operation does not result in entry into MODE 1.Once the plant reaches MODE 1, the requirement for the Surveillance to be performed within its specified Frequency applies and would require that the Surveillance had been performed.
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| If the Surveillance were not performed prior to entering MODE 1. there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.(continued)
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| JAFNPP 1.4-7 Amendment 274
| |
| -Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-6 (continued)
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| SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY------------------
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| NOTE------------------
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| Not required to be met in MODE 3.........................................
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| Verify parameter is within limits. 24 hours Example 1.4-6 specifies that the requirements of this Surveillance do not have to be met while the plant is in MODE 3 (the assumed Applicability of the associated LCO is MODES 1. 2, and 3). The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1. However, the Note constitutes an "otherwise stated" exception to the Applicability of this Surveillance.
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| Therefore, if the Surveillance were not performed within the 24 hour interval (plus the extension allowed by SR 3.0.2), and the unit was in MODE 3, there would be no failure of the SR nor failure to meet the LCO.Therefore, no violation of SR 3.0.4 occurs when changing MODES to enter MODE 3. even with the 24 hour Frequency exceeded, provided the MODE change does not result in entry into MODE 2. Prior to entering MODE 2 (assuming again that the 24 hour Frequency were not met). SR 3.0.4 would require satisfying the SR.JAFNPP 1.4-8 Amendment 274 SLs 2.0 2.0 SAFETY LIMITS (SLs)2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10X rated core flow: THERMAL POWER shall be 25X RTP.2.1.1.2 With the reactor steam dome pressure 785 psig and core flow 2 10X rated core flow: MCPR shall be 2 1.07 for two recirculation loop operation or 2 1.09 for single recirculation loop operation.
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| 2.1.1.3 Reactor vessel water level shall be greater than the top. : of active irradiated fuel.2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be 5 1325 psig.2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hours: 2.2.1 Restore compliance with all SLs: and 2.2.2 Insert all insertable control rods.JAFNPP 2.0-1 Amendment 281 LCO Applicability 3.0 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.1 LCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LCO 3.0.2 and LCO 3.0.7.LC0 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5 and LCO 3.0.6.If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated.LCD 3.0.3 When an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the plant shall be placed in a MODE or other specified condition in which the LCO is not applicable.
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| Action shall be initiated within 1 hour to place the plant, as applicable, in: a. MODE 2 within 7 hours;b. MODE 3 within 13 hours; and c. MODE 4 within 37 hours.Exceptions to this Specification are stated in the individual Specifications.
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| Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 is not required.LCO 3.0.3 is only applicable in MODES 1, 2, and 3.LCO 3.0.4 When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made: a. When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time;(continued)
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| JAFNPP 3.0-1 Amendment 284 LCO Applicability 3.0 3.0 LCO APPLICABILITY LCO 3.0.4 (continued)
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| : b. After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition In the Applicability, and establishment of risk management actions, if appropriate; exceptions to this Specification are stated in the individual Specifications; or c. When an allowance is stated in the individual value, parameter, or other Specification.
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| This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.LCO 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment.
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| This is an exception to LCO 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.
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| LCO 3.0.6 When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered.Only the support system LCO ACTIONS are required to be entered.This Is an exception to LCO 3.0.2 for the supported system. In this event, an evaluation shall be performed in accordance with Specification 5.5.12, "Safety Function Determination Program (SFDP).t If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.When a support system's Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2.(continued)
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| JAFNPP 3.0-2 Amendment 284 LCO Applicability
| |
| | |
| ===3.0 LCOAPPLICABILITY===
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| (continued)
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| LCO 3.0.7 Special Operations LCOs in Section 3.10 allow specified Technical Specifications (TS) requirements to be changed to permit performance of special tests and operations.
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| Unless otherwise specified, all other TS requirements remain unchanged.
| |
| Compliance with Special Operations LCOs is optional.
| |
| When a Special Operations LCO is desired to be met but is not met, the ACTIONS of the Special Operations LCO shall be met. When a Special Operations LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with the other applicable Specifications.
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| JAFNPP 3.0-3 Amendment 284 SR Applicability 3.0 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY SR 3.0.1 SRs shall be met during the MODES or other specified conditions in the Applicability for individual LCOs, unless otherwise stated in the SR.Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LCO except as provided in SR 3.0.3. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.SR 3.0.2 The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.For Frequencies specified as "once,' the above Interval extension does not apply.If a Completion Time requires periodic performance on a "once per. ..' basis, the above Frequency extension applies to each performance after the initial performance.
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| Exceptions to this Specification are stated in the individual Specifications.
| |
| SR 3.0.3 If It is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance.
| |
| A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours and the risk impact shall be managed.If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.When the Surveillance is performed within the delay period and the Surveillance is not met, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.(continued)
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| JAFNPP 3.0-4 Amendment 284 SR Applicability 3.0 3.0 SR APPLICABILITY (continued)
| |
| SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an LCO shall only be made when the LCO's Surveillances have been met within their specified Frequency, except as provided by SR 3.0.3.When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4.This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.JAFNPP 3 .0-5 Amendment 284 SDM 3.1.1 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM)LCO 3.1.1 APPLICABILITY:
| |
| SDM shall be 2 0.38% Ak/k. with the highest worth control rod analytically determined.
| |
| MODES 1, 2. 3. 4, and 5.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limits A.1 Restore SDM to within 6 hours in MODE 1 or 2. limits.B. Required Action and B.1 Be in MODE 3. 12 hours associated Completion Time of Condition A not met.C. SDM not within limits C.1 Initiate action to Immediately in MODE 3. fully insert all insertable control rods.D. SDM not within limits D.1 Initiate action to Immediately in MODE 4. fully insert all insertable control rods.AND (continued)
| |
| JAFNPP 3.1.1-1 Amendment 274 SDM 3.1.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. (continued)
| |
| D.2 Initiate action to 1 hour restore secondary containment to OPERABLE status.AND D.3 Initiate action to 1 hour restore one standby gas treatment (SGT)subsystem to OPERABLE status.AND D.4 Initiate action to 1 hour restore isolation capability in each required secondary containment penetration flow path not isolated.E. SDM not within limits E.1 Suspend CORE Immediately in MODE 5. ALTERATIONS except for control rod insertion and fuel assembly removal.AND E.2 Initiate action to Immediately fully insert all insertable control rods in core cells containing one or more fuel assemblies.
| |
| AND (continued)
| |
| JAFNPP 3.1.1-2 Amendment 274
| |
| -SDM 3.1.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. (continued)
| |
| E.3 Initiate action to 1 hour restore secondary containment to OPERABLE status.AND E.4 Initiate action to 1 hour restore one SGT subsystem to OPERABLE status.AND E.5 Initiate action to 1 hour restore isolation capability in each required secondary containment penetration flow path not isolated.JAFNPP 3.1.1-3 Amendment 274
| |
| -SDM 3.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY t SR 3.1.1.1 Verify SDM is 2 0.38% Ak/k with the highest worth control rod analytically determined.
| |
| Prior to each in vessel fuel movement during fuel loading sequence AND Once within 4 hours after criticality following fuel movement within the reactor pressure vessel or control rod replacement JAFNPP 3.1.1-4 Amendment 274 Reactivity Anomalies 3.1.2 3.1 REACTIVITY CONTROL SYSTEMS 3.1.2 Reactivity Anomalies LCO 3.1.2 APPLICABILITY:
| |
| The reactivity difference between the measured rod density and the predicted rod density shall be within i 1X Ak/k.MODES 1 and 2.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Core reactivity A.1 Restore core 72 hours difference not within reactivity difference limit. to within limit.B. Required Action and B.1 Be in MODE 3. 12 hours associated Completion Time not met.JAFNPP 3.1.2-1 Amendment 274 Reactivity Anomalies 3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 4.SR 3.1.2.1 Verify core reactivity difference between the measured rod density and the predicted rod density is within +/- 1% Ak/k.Once within 24 hours after reaching equilibrium conditions following startup after fuel movement within the reactor pressure vessel or control rod replacement AND 1000 MWD/T thereafter during operations in MODE 1 JAFNPP 3.1.2-2 Amendment 274
| |
| -Control Rod OPERABILITY 3.1.3 3.1 REACTIVITY CONTROL SYSTEMS 3.1.3 Control Rod OPERABILITY LCO 3.1.3 APPLICABILITY:
| |
| Each control rod shall be OPERABLE.MODES 1 and 2.ACTIONS Separate Condition entry is allowed for each control rod.CONDITION REQUIRED ACTION COMPLETION TIME A. One withdrawn control ------------
| |
| NOTE-------------
| |
| rod stuck. Rod worth minimizer (RWM) may be bypassed as allowed by LCO 3.3.2.1, "Control Rod Block Instrumentation." if required, to allow continued operation.
| |
| .............................
| |
| A.1 Verify stuck control Immediately rod separation criteria met.AND A.2 Disarm the associated 2 hours control rod drive (CRD).AND (continued)
| |
| JAFNPP 3.1.3-1 Amendment 274 Control Rod Operability
| |
| | |
| ====3.1.3 ACTIONS====
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
| |
| A.3 Perform SR 3.1.3.2 for 24 hours from each withdrawn discovery of Condition OPERABLE control rod. A concurrent with THERMAL POWER greater than the low power setpoint (LPSP)of the RWM AND 72 hours A.4 Perform SR 3.1.1.1.B. Two or more withdrawn B.1 Be in MODE 3. 12 hours control rods stuck.C. One or more control rods C.1 NOTE -----inoperable for reasons RWM may be bypassed other than Condition A or B. as allowed by LCO 3.3.2.1, if required, to allow insertion of inoperable control rod and continued operation.
| |
| Fully insert inoperable 3 hours control rod.AND C.2 Disarm the associated CRD. 4 hours (continued)
| |
| I JAFNPP 3.1.3-2 Amendment 291 Control Rod OPERABILITY
| |
| | |
| ====3.1.3 ACTIONS====
| |
| (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME D. ---------NOTE---------
| |
| D.1 Restore compliance 4 hours Not applicable when with BPWS.THERMAL POWER> 10% RTP. OR......................
| |
| D.2 Restore control rod 4 hours Two or more inoperable to OPERABLE status.control rods not in compliance with banked position withdrawal sequence (BPWS) and not separated by two or more OPERABLE control rods.E. Required Action and E.1 Be in MODE 3. 12 hours associated Completion Time of Condition A, C. or D not met.OR Nine or more control rods inoperable.
| |
| JAFNPP 3.1.3-3 Amendment 274 Control Rod OPERABILITY
| |
| | |
| ====3.1.3 SURVEILLANCE====
| |
| | |
| REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Determine tie position of each control rod. .24 hours SR 3.1.3.2 --------------
| |
| NOTE----------------
| |
| Not required to be performed until 31 days after the control rod is withdrawn and THERMAL POWER is greater than the LPSP of the RWM.Insert each withdrawn control rod at least one notch. 31 days SR 3.1.3.3 Verify each control rod scram time from fully In accordance with withdrawn to notch position 04 is < 7 seconds. SR 3.1.4.1, SR 3.1.4.2, SR 3.1.4.3, and SR 3.1.4.4 SR 3.1.3.4 Verify each control rod does not go to the withdrawn Each time the overtravel position.
| |
| control rod iswithdrawn to "full out" position AND Prior to declaring control rod OPERABLE after work on control rod or CRD System that could affect coupling I JAFNPP 3.1.3-4 Amendment!291
| |
| -Control Rod Scram Times 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Control Rod Scram Times LCO 3.1.4 a. No more than 10 OPERABLE control rods shall be "slow." in accordance with Table 3.1.4-1: and b. No more than 2 OPERABLE control rods that are 'slow" shall occupy adjacent locations.
| |
| APPLICABILITY:
| |
| MODES 1 and 2.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Be in MODE 3. 12 hours LCO not met.SURVEILLANCE REQUIREMENTS
| |
| -------------------------------------
| |
| NOTE-------------------------------------
| |
| During single control rod scram time Surveillances, the control rod drive (CRD) pumps shall be isolated from the associated scram accumulator.
| |
| ...........
| |
| .............
| |
| ........................................
| |
| ..... ....SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify each control rod scram time is Prior to within the limits of Table 3.1.4-1 with exceeding reactor steam dome pressure k 800 psig. 40X RTP after each reactor shutdown k 120 days (continued)
| |
| JAFNPP 3.1.4-1 Amendment 274 Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.1.4.2 Verify, for a representative sample, each tested 200 days control rod scram time Is within the limits of cumulative Table 3.1.4-1 with reactor steam dome pressure operation In> 800 psig. MODE1 SR 3.1.4.3 Verify each affected control rod scram time Is within Prior to declaring the limits of Table 3.1.4-i with any reactor steam control rod dome pressure.
| |
| OPERABLE after work on control rod or CRD System that could affect scram time SR 3.1.4.4 Verify each affected control rod scram time is within Prior to exceeding the limits of Table 3.1.4-1 with reactor steam dome 40% RTP after fuel pressure > 800 psig. movement within the affected core cell AND Prior to exceeding 40% RTP after work on control rod or CRD System that could affect scram time I JAFNPP 3.1.4-2 Amendment 283 J Control Rod Scram Times 3.1.4 Table 3.1.4-1 (page I of 1)Control Rod Scram Times------- ------- -------------
| |
| NOTES--------------------------
| |
| : 1. OPERABLE control rods with scram times not within the limits of this Table are considered"slow.u 2. Enter applicable Conditions and Required Actions of LCO 3.1.3, "Control Rod OPERABILITY," for control rods with scram times > 7 seconds to notch position 04. These control rods are inoperable, in accordance with SR 3.1.3.3, and are not considered "slow." SCRAM TIMES (a) (b)when REACTOR STEAM DOME NOTCH POSITION PRESSURE >800 psig (seconds)46 0.44 36 1.08 26 1.83 06 3.35 (a). Maximum scram time from fully withdrawn position, based on de-energization of scram pilot valve solenoids at time zero.(b). Scram times as a function of reactor steam dome pressure, when< 800 psig, are within established limits.JAFNPP 3.1.4-3 Amendment 291 I Control Rod Scram Accumulators 3.1.5 3.1 REACTIVITY CONTROL SYSTEMS 3.1.5 Control Rod Scram Accumulators LCO 3.1.5 APPLICABILITY:
| |
| Each control rod scram accumulator shall be OPERABLE.MODES 1 and 2.ACTIONS-------------------------------------
| |
| NOTE -----------------------------------
| |
| Separate Condition entry is allowed for each control rod scram accumulator.
| |
| ..............................................................................
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. One control rod scram A.1 --------NOTE---------
| |
| accumulator inoperable Only applicable if with reactor steam the associated dome pressure control rod scram 2 900 psig. time was within the limits of Table 3.1.4-1 during the last scram time Surveillance.
| |
| .....................
| |
| Declare the 8 hours associated control rod scram time"slow.'OR A.2 Declare the 8 hours associated control rod inoperable.(continued)
| |
| JAFNPP 3.1.5-1 Amendment 274 Control Rod Scram Accumulators
| |
| | |
| ====3.1.5 ACTIONS====
| |
| (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME B. Two or more control rod scram accumulators inoperable with reactor steam dome pressure 2 900 psig.B.1 AND B.2.1 OR B.2.2 Restore charging water header pressure to z 940 psig...NOTE---------
| |
| Only applicable if the associated control rod scram time was within the limits of Table 3.1.4-1 during the last scram time Surveillance.
| |
| .........
| |
| ...................
| |
| .....Declare the associated control rod scram time"slow." Declare the associated control rod inoperable.
| |
| 20 minutes from discovery of Condition B concurrent with charging water header pressure< 940 psig 1 hour 1 hour C. One or more control C.1 Verify all control Immediately upon rod scram accumulators rods associated with discovery of inoperable with inoperable charging water reactor steam dome accumulators are header pressure pressure < 900 psig. fully inserted.
| |
| < 940 psig AND (continued)
| |
| JAFNPP 3.1.5-2 Amendment 274 Control Rod Scram Accumulators
| |
| | |
| ====3.1.5 ACTIONS====
| |
| CONDITION REQUIRED ACTION COMPLETION TIME C. (continued)
| |
| C.2 Declare the 1 hour associated control rod inoperable.
| |
| D. Required Action B.1 or D.1 ---NOTE---------
| |
| C.1 and associated Not applicable if all Completion Time not inoperable control met. rod scram accumulators are associated with fully inserted control rods.Place the reactor Immediately mode switch in the shutdown position.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify each control rod scram accumulator 7 days pressure is -940 psig.JAFNPP 3.1.5-3 Amendment 274 Rod Pattern Control 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Rod Pattern Control LCO 3.1.6 APPLICABILITY:
| |
| OPERABLE control rods shall comply with the requirements of the banked position withdrawal sequence (BPWS).MODES 1 and 2 with THERMAL POWER s 10% RTP.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more OPERABLE A.1 -------NOTE-........
| |
| control rods not in Rod worth minimizer compliance with BPWS. (RWM) may be bypassed as allowed by LCO 3.3.2.1. Control Rod Block Instrumentation."..........
| |
| ...................
| |
| __..._..Move associated 8 hours control rod(s) to correct position.OR A.2 Declare associated 8 hours control rod(s)inoperable.(continued)
| |
| JAFNPP 3.1.6-1 Amendment 274 Rod Pattern Control 3.1.6 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME B. Nine or more OPERABLE B.1 NOTE---------
| |
| control rods not in Rod worth minimizer compliance with BPWS. (RWM) may be bypassed as allowed by LCO 3.3.2.1.Suspend withdrawal of Immediately control rods.AND B.2 Place the reactor 1 hour mode switch in the shutdown position.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify all OPERABLE control rods comply 24 hours with BPWS.JAFNPP 3.1.6-2 Amendment 274 SLC System 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Standby Liquid Control (SLC) System LCO 3.1.7 Two SLC subsystems shall be OPERABLE.APPLICABILITY:
| |
| MODES 1 and 2.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SLC subsystem A.1 Restore SLC subsystem 7 days inoperable.
| |
| to OPERABLE status.B. Two SLC subsystems B.1 Restore one SLC 8 hours inoperable.
| |
| subsystem to OPERABLE status.C. Required Action and C.1 Be in MODE 3. 12 hours associated Completion Time not met.JAFNPP 3.1.7-1 Amendment 274 SLC System 3.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify available volume of sodium 24 hours pentaborate solution is within the limits of Figure 3.1.7-1.SR 3.1.7.2 Verify temperature of sodium pentaborate 24 hours solution is within the limits of Figure 3.1.7-2.SR 3.1.7.3 Verify temperature of pump suction piping 24 hours is within the limits of Figure 3.1.7-2.SR 3.1.7.4 Verify continuity of explosive charge. 31 days SR 3.1.7.5 Verify the concentration of sodium 31 days entaborate in solution is within the imits of Figure 3.1.7-1. AND Once within 24 hours after water or sodium pentaborate is added to solution AND Once within 24 hours after solution temperature is restored within the limits of Figure 3.1.7-2 (continued)
| |
| JAFNPP 3.1.7-2 Amendment 274 SLC System 3.1.7 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.1.7.6 Verify each SLC subsystem manual valve in 31 days the flow path that is not locked, sealed.or otherwise secured in position is in the correct position.
| |
| or can be aligned to the correct position.SR 3.1.7.7 Verify each pump develops a flow rate In accordance 2 50 gpm at a discharge pressure with the 1275 psig. Inservice Testing Program SR 3.1.7.8 Verify flow through one SLC subsystem from 24 months on a pump into reactor pressure vessel. STAGGERED TEST BASIS SR 3.1.7.9 Verify all heat traced piping between 24 months storage tank and pump suction is unblocked.
| |
| AND Once within 24 hours after piping temperature is restored within the limits of Figure 3.1.7-2 SR 3.1.7.10 Verify sodium pentaborate enrichment is Prior to 2 34.7 atom percent B-10. addition to SLC tank (continued)
| |
| JAFNPP 3.1.7-3 Amendment 274 SLC System 3.1.7 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.1.7.11 Verify sodium pentaborate enrichment in 24 months solution in the SLC tank is 2 34.7 atom percent B-10.JAFNPP 3.1.7-4 Amendment 274 SLC System 3.1.7 14 C 0 co a-C C 0 C-a)a-0 a-E 0 Cn 0)S._C LU I*.0 C ax 0.-W 13 12 11 10 9 (2200gal.
| |
| 13%)(4724gal, 13%)(4724gal, 10%)(2850gal, 10%)8 2000 3000 4000.Net Volume of Solution in Tank (gal)Figure 3.1.7-1 (page 1 of 1)Sodium Pentaborate Solution Volume Versus Concentration Requirements 5000 JAFNPP 3.1.7-5 Amendment 274 SLC System 3.1.7 100 90 CD a)a-a)a)N.E I-80 70 60 50 40 6 8 10 12 14 16 18 20 Concentration (Weight Percent Enriched Sodium Pentaborate)
| |
| Figure 3.1.7-2 (page 1 of 1)Sodium Pentaborate Solution Temperature Versus Concentration Requirements JAFNPP 3.1.7-6 Amendment 274 SDV Vent and Drain Valves 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves LCO 3.1.8 APPLICABILITY:
| |
| Each SDV vent and drain valve shall be OPERABLE.MODES 1 and 2.ACTIONS-.. ......... ........NOTES-..
| |
| ................1. Separate Condition entry is allowed for each SDV vent and drain line.2. An isolated line may be unisolated under administrative control to allow draining and venting of the SDV...............................................................................
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. One or more SDV vent A.1 Isolate the 7 days or drain lines with associated line.one valve inoperable.
| |
| B. One or more SDV vent B.1 Isolate the 8 hours or drain lines with associated line.both valves inoperable.
| |
| C. Required Action and C.1 Be in MODE 3. 12 hours associated Completion Time not met.JAFNPP 3.1.8-1 Amendment 274 SDV Vent and Drain Valves 3.1.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.8.1 -------------------
| |
| NOTE--------------------
| |
| Not required to be met on vent and drain valves closed during performance of SR 3.1.8.2.......................
| |
| .............................................................
| |
| ..Verify each SDV vent and drain valve is 31 days open.SR 3.1.8.2 Cycle each SDV vent and drain valve to the In accordance fully closed and fully open position.
| |
| with the Inservice Testing Program SR 3.1.8.3 Verify each SDV vent and drain valve: 24 months a. Closes in 5 30 seconds after receipt of an actual or simulated scram signal; and b. Opens when the actual or simulated scram signal is reset.JAFNPP 3.1.8-2 Amendment 274
| |
| -APLHGR 3.2.1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)LCO 3.2.1 APPLICABILITY:
| |
| All APLHGRs shall be less than or equal to the limits specified in the COLR.THERMAL POWER 2 25% RTP.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any APLHGR not within A.1 Restore APLHGR(s) to 2 hours limits. within limits.B. Required Action and B.1 Reduce THERMAL POWER 4 hours associated Completion to < 25X RTP.Time not met.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify all APLHGRs are less than or equal Once within to the limits specified in the COLR. 12 hours after 2 25X RTP AND 24 hours thereafter I JAFNPP 3.2.1-1 Amendment 274 MCPR 3.2.2 3.2 POWER DISTRIBUTION LIMITS 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR)LCO 3.2.2 All MCPRs shall be .greater than or equa operating limits specified in the COLR.1 to the MCPR APPLICABILITY:
| |
| THERMAL POWER 2 25% RTP.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any MCPR not within A.1 Restore MCPR(s) to 2 hours limits. within limits.B. Required Action and B.1 Reduce THERMAL POWER 4 hours associated Completion to < 25% RTP.Time not met.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify all MCPRs are greater than or equal Once within to the limits specified in the COLR. 12 hours after 2 25% RTP AND 24 hours thereafter (continued)
| |
| JAFNPP 3.2.2-1 Amendment 274 MCPR 3.2.2 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.2.2.2 Determine the MCPR limits. Once within 72 hours after each completion of SR 3.1.4.1 AND Once within 72 hours after each completion of SR 3.1.4.2 AND Once within 72 hours after each completion of SR 3.1.4.4 JAFNPP 3.2.2-2 Amendment 274
| |
| --LHGR 3.2.3 3.2 POWER DISTRIBUTION LIMITS 3.2.3 LINEAR HEAT GENERATION RATE (LHGR)LCO 3.2.3 All LHGRs shall be less than or equal to the limits specified in the COLR.APPLICABILITY:
| |
| THERMAL POWER 2 25X RTP.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any LHGR not within A.1 Restore LHGR(s) to 2 hours limits. within limits.B. Required Action and B.1 Reduce THERMAL POWER 4 hours associated Completion to < 25% RTP.Time not met.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify all LHGRs are less than or equal to Once within the limits specified in the COLR. 12 hours after 2 25% RTP AND 24 hours thereafter JAFNPP 3.2.3-1 Amendment 274 RPS Instrumentation 3.3.1.1 3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation LCO 3.3.1.1 APPLICABILITY:
| |
| The RPS instrumentation for each Function in Table 3.3.1.1-1 shall be OPERABLE.According to Table 3.3.1.1-1.
| |
| ACTIONS-------------------------------------
| |
| NOTE--...................................
| |
| Separate Condition entry is allowed for each channel.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Place channel in 12 hours channels inoperable.
| |
| trip.OR A.2 Place associated trip 12 hours system in trip.B. One or more Functions B.1 Place channel in one 6 hours with one or more trip system in trip.required channels inoperable in both OR trip systems.B.2 Place one trip system 6 hours in trip.(continued)
| |
| JAFNPP 3.3.1.1-1 Amendment 274 RPS Instrumentation 3.3.1.1 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME C. One or more Functions C.1 Restore RPS trip 1 hour with RPS trip capability.
| |
| capability not maintained.
| |
| D. Required Action and D.1 Enter the Condition Immediately associated Completion referenced in Time of Condition A. Table 3.3.1.1-1 for B. or C not met. the channel.E. As required by E.1 Reduce THERMAL POWER 4 hours Required Action D.1 to < 29% RTP.and referenced in Table 3.3.1.1-1.
| |
| F. As required by F.1 Be in MODE 2. 6 hours Required Action D.1 and referenced in Table 3.3.1.1-1.
| |
| G. As required by G.1 Be in MODE 3. 12 hours Required Action D.1 and referenced in Table 3.3.1.1-1.
| |
| H. As required by H.1 Initiate action to Immediately Required Action D.1 fully insert all and referenced in insertable control Table 3.3.1.1-1.
| |
| rods in core cells containing one or more fuel assemblies.
| |
| JAFNPP 3.3.1.1-2 Amendment 274 RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS
| |
| ----------------------------
| |
| NOTES------------------------------
| |
| : 1. Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.2. When a channel is placed in an Inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains RPS trip capability.
| |
| SURVEILLANCE FREQUENCY SR 3.3.1.1.1 Perform CHANNEL CHECK. 12 hours SR 3.3.1.1.2
| |
| ----------------
| |
| NOTE--------------
| |
| Not required to be performed until 12 hours after THERMAL POWER ; 25% RTP.Verify the absolute difference between the 7 days average power range monitor (APRM) channels and the calculated power is : 2% RTP while operating at > 25% RTP.SR 3.3.1.1.3
| |
| ---------------
| |
| NOTE--------------
| |
| Not required to be performed when entering MODE 2 from MODE I until 12 hours after entering MODE 2.Perform CHANNEL FUNCTIONAL TEST. 7 days SR 3.3.1.1.4 Perform a functional test of each RPS automatic 7 days scram contactor.(continued)
| |
| I JAFNPP 3.3.1-1-3 Amendment 287 RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.3.1.1.5 Verify the source range monitor (SRM) and Prior to fully intermediate range monitor (IRM) channels withdrawing overlap. SRMs SR 3.3.1.1.6
| |
| -----------------
| |
| NOTE-------------------
| |
| Only required to be met during entry into MODE 2 from MODE 1..........................................
| |
| Verify the IRM and APRM channels overlap. 7 days SR 3.3.1.1.7 Calibrate the local power range monitors.
| |
| 2000 MWD/T average core exposure SR 3.3.1.1.8 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.1.1.9
| |
| -----------------
| |
| NOTES---------------
| |
| : 1. Neutron detectors are excluded.2. For Functions 1.a and 2.a. not required to be performed when entering MODE 2 from MODE 1 until 12 hours after entering MODE 2.3. For Function 2.b, the recirculation loop flow signal portion of the channel is excluded..........................................
| |
| Perform CHANNEL CALIBRATION.
| |
| 92 days (continued)
| |
| I JAFNPP 3.3.1.1-4 Amendment 277 MAY 1 2003 RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.3.1.1.10 Calibrate the trip units. 184 days SR 3.3.1.1.11 Perform CHANNEL FUNCTIONAL TEST. 24 months SR 3.3.1.1.12
| |
| ---NOTE-------------------
| |
| For Function 2.b. all portions of the channel except the recirculation loop flow signal portion are excluded.... ........... .... .....Perform CHANNEL CALIBRATION.
| |
| 24 months SR 3.3.1.1.13 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months SR 3.3.1.1.14 Verify Turbine Stop Valve -Closure and 24 months Turbine Control Valve Fast Closure. EHC Oil Pressure-Low Functions are not bypassed when THERMAL POWER is 2 29X RTP.SR 3.3.1.1.15
| |
| ------------------
| |
| NOTES------------------
| |
| : 1. Neutron detectors are excluded.2. "n" equals 2 channels for the purpose of determining the STAGGERED TEST BASIS Frequency.
| |
| Verify the RPS RESPONSE TIME is within 24 months on a limits. STAGGERED TEST BASIS JAFNPP 3.3.1.1-5 Amendment 274
| |
| --RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 1 of 3)Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE 1. Intermediate Range Monitors a. Neutron Flux-High 2 3 G SR 3.3.1.1.1 s 120/125 SR 3.3.1.1.3 divisions of SR 3.3.1.1.4 full scale SR 3.3.1.1.5 SR 3.3.1.1.6 SR 3.3.1.1.9 SR 3.3.1.1.13 5 (a) 3 H SR 3.3.1.1.1 s 120/125 SR 3.3.1.1.3 divisions of SR 3.3.1.1.4 full scale SR 3.3.1.1.9 SR 3.3.1.1.13
| |
| : b. Inop 2 3 G SR 3.3.1.1.3 NA SR 3.3.1.1.4 SR 3.3.1.1.13 5 (a) 3 H SR 3.3.1.1.3 NA SR 3.3.1.1.4 SR 3.3.1.1.13
| |
| : 2. Average Power Range Monitors a. Neutron Flux-High.
| |
| 2 2 G SR 3.3.1.1.1 s 15t RTP (Startup)
| |
| SR 3.3.1.1.3 SR 3.3.1.1.4 SR 3.3.1.1.6 SR 3.3.1.1.7 SR 3.3.1.1.9 SR 3.3.1.1.13
| |
| : b. Neutron Flux-High 1 2 F SR 3.3.1.1.1 As specified (Flow Biased) SR 3.3.1.1.2 in the COLR SR 3.3.1.1.4 and s 117X RTP SR 3.3.1.1.7 SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.1.12 SR 3.3.1.1.13 SR 3.3.1.1.15 (continued)(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.
| |
| JAFNPP 3.3.1.1-6 Amendment 274 RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 2 of 3)Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE 2. Average Power Range Monitors (continued)
| |
| : c. Neutron Flux-High 1 2 F SR 3.3.1.1.1 s 120S RTP (Fixed) SR 3.3.1.1.2 SR 3.3.1.1.4 SR 3.3.1.1.7 SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.1.13 SR 3.3.1.1.15
| |
| : d. Inop 1.2 2 G SR 3.3.1.1.4 NA SR 3.3.1.1.7 SR 3.3.1.1.8 SR 3.3.1.1.13
| |
| : 3. Reactor 1.2 2 G SR 3.3.1.1.1 s 1080 psig Pressure -High SR 3.3.1.1.4 SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.12 SR 3.3.1.1.13 SR 3.3.1.1.15
| |
| : 4. Reactor Vessel Water 1.2 2 G SR 3.3.1.1.1 2 177 inches Level -Low (Level 3) SR 3.3.1.1.4 SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.12 SR 3.3.1.1.13 SR 3.3.1.1.15
| |
| : 5. Main Steam Isolation 1 8 F SR 3.3.1.1.4 s 15S closed Valve -Closure SR 3.3.1.1.8 SR 3.3.1.1.12 SR 3.3.1.1.13 SR 3.3.1.1.15
| |
| : 6. Drywell Pressure-High 1.2 2 G SR 3.3.1.1.1 s 2.7 psig SR 3.3.1.1.4 SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.12 SR 3.3.1.1.13 SR 3.3.1.1.15 (continued)
| |
| JAFNPP 3.3.1.1-7 Amendment 274 RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 3 of 3)Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE 7. Scram Discharge Volume Water Level -High a. Differential Pressure Transmitter/Trip Unit b. Level Switch 8. Turbine Stop Valve -Closure 1.2 5 (a)1.2 5 (a)2 29S RTP 2 2 2 2 4 G SR SR SR SR H SR SR SR SR G SR SR SR SR H SR SR SR SR E SR SR SR SR SR SR SR SR 3.3.1.1.1 3.3.1.1.4 3.3.1.1.9 3.3.1.1.13 3.3.1.1.1 3.3.1.1.4 3.3.1.1.9 3.3.1.1.13 3.3.1.1.4 3.3 .1.1.8 3.3.1.1.12 3.3.1.1.13 3.3.1.1.4 3.3.1.1.8 3.3.1.1.12 3.3.1.1.13 3.3.1.1.1 3.3.1.1.4 3.3.1.1.8 3.3.1.1.10 3.3.1.1.12 3.3.1.1.13 3.3.1.1.14 3.3.1.1.15 s 34.5 gallons s 34.5 gallons s 34.5 gallons s 34.5 gallons s 15? closed 9. Turbine Control Valve Fast Closure. EHC Oil Pressure -Low 10. Reactor Mode Switch -Shutdown Position 11. Manual Scram 2 29? RTP 1.2 5 (a)1.2 5 (a)2 1 1 1 1 E SR SR SR SR SR SR SR SR G SR SR H SR SR G SR SR H SR SR 3.3.1.1.1 3.3.1.1.4 3.3.1.1.8 3.3.1.1.10 3.3.1.1.12 3.3.1.1.13 3.3.1.1.14 3.3.1.1.15 3.3.1.1.11 3.3.1.1.13 3.3.1.1.11 3.3.1.1.13 3.3.1.1.8 3.3.1.1.13 3.3.1.1.8 3.3.1.1.13 a 500 psig and s 850 psig NA NA NA (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.
| |
| JAFNPP 3.3.1.1-8 Amendment 274
| |
| -.SRM Instrumentation 3.3.1.2 3.3 INSTRUMENTATION 3.3.1.2 Source Range Monitor (SRM) Instrumentation LCO 3.3.1.2 APPLICABILITY:
| |
| The SRM instrumentation in Table 3.3.1.2-1 shall be OPERABLE.According to Table 3.3.1.2-1.
| |
| ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore required SRMs 4 hours SRMs inoperable in to OPERABLE status.MODE 2 with intermediate range monitors (IRMs) on Range 2 or below.B. Three required SRMs B.1 Suspend control rod Immediately inoperable in MODE 2 withdrawal.
| |
| with IRMs on Range 2 or below.C. Required Action and C.1 Be in MODE 3. 12 hours associated Completion Time of Condition A or B not met.(continued)
| |
| JAFNPP 3.3. 1.2-1 Amendment 274 SRM Instrumentation 3.3.1.2 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME D. One or more required D.1 Fully insert all 1 hour SRMs inoperable in insertable control MODE 3 or 4. rods.AND D.2 Place reactor mode 1 hour switch in the shutdown position.E. One or more required E.1 Suspend CORE Immediately SRMs inoperable in ALTERATIONS except MODE 5. for control rod insertion.
| |
| AND E.2 Initiate action to Immediately fully insert all insertable control rods in core cells containing one or more fuel assemblies.
| |
| SURVEILLANCE REQUIREMENTS Refer to Table 3.3.1.2-1 to determine which SRs apply for each applicable MODE or other specified condition.(continued)
| |
| JAFNPP 3.3.1.2-2 Amendment 274 SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.3.1.2.2
| |
| ------------------
| |
| NOTES------------------
| |
| : 1. Only required to be met during CORE ALTERATIONS.
| |
| : 2. One SRM may be used to satisfy more than one of the following.
| |
| Verify an OPERABLE SRM detector is 12 hours located in: a. The fueled region;b. The core quadrant where CORE ALTERATIONS are being performed.
| |
| when the associated SRM is included in the fueled region; and c. A core quadrant adjacent to where CORE ALTERATIONS are being performed.
| |
| when the associated SRM is included in the fueled region.SR 3.3.1.2.3 Perform CHANNEL CHECK. 24 hours SR 3.3.1.2.4
| |
| ------------------
| |
| NOTE-------------------
| |
| Not required to be met with less than or equal to four fuel assemblies adjacent to the SRM and no other fuel assemblies in the associated core quadrant.Verify count rate is 2 3.0 cps with a 12 hours during signal to noise ratio 2 2:1. CORE ALTERATIONS AND 24 hours (continued)
| |
| JAFNPP 3.3.1.2-3 Amendment 274 SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.3.1.2.5
| |
| -----------------
| |
| *NOTE-------------------
| |
| The determination of signal to noise ratio is not required to be met with less than or equal to four fuel assemblies adjacent to the SRM and no other fuel assemblies in the associated core quadrant................
| |
| ...................................
| |
| ..........
| |
| Perform CHANNEL FUNCTIONAL TEST and 7 days determination of signal to noise ratio.SR 3.3.1.2.6
| |
| ------------------
| |
| NOTE-------------------
| |
| Not required to be performed until 12 hours after IRMs on Range 2 or below.............
| |
| ......................................
| |
| ... .........
| |
| ...........
| |
| Perform CHANNEL FUNCTIONAL TEST and 31 days determination of signal to noise ratio.SR 3.3.1.2.7
| |
| ------------------
| |
| NOTES------------------
| |
| : 1. Neutron detectors are excluded.2. Not required to be performed until 12 hours after IRMs on Range 2 or below...... ...........
| |
| .........................
| |
| Perform CHANNEL CALIBRATION.
| |
| 92 days JAFNPP 3.3.1.2-4 Amendment 274 SRM Instrumentation 3.3.1.2 Table 3.3.1.2-1 (page 1 of 1)Source Range Monitor Instrumentation APPLICABLE MODES OR OTHER REQUIRED SURVEILLANCE FUNCTION SPECIFIED CONDITIONS CHANNELS REQUIREMENTS
| |
| : 1. Source Range Monitor 2 (a) 3 SR 3.3.1.2.1 SR 3.3.1.2.4 SR 3.3.1.2.6 SR 3.3.1.2.7 3.4 2 SR 3.3.1.2.3 SR 3.3.1.2.4 SR 3.3.1.2.6 SR 3.3.1.2.7 5 2 (b)(c) SR 3.3.1.2.1 SR 3.3.1.2.2 SR 3.3.1.2.4 SR 3.3.1.2.5 SR 3.3.1.2.7 (a) With IRMs on Range 2 or below.(b) Only one SRM channel is required to be OPERABLE during spiral offload or reload when the fueled region includes only that SRH detector.(c) Special movable detectors may be used in place of SRMs if connected to normal SRM circuits.JAFNPP 3.3.1.2-5 Amendment 274
| |
| --Control Rod Block Instrumentation 3.3.2.1 3.3 INSTRUMENTATION 3.3.2.1 Control Rod Block Instrumentation LCO 3.3.2.1 APPLICABILITY:
| |
| The control rod block instrumentation for each Function in Table 3.3.2.1-1 shall be OPERABLE.According to Table 3.3.2.1-1.
| |
| ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One rod block monitor A.1 Restore RBM channel 24 hours (RBM) channel to OPERABLE status.inoperable.
| |
| B. Required Action and B.1 Place one RBM channel 1 hour associated Completion in trip.Time of Condition A not met.OR Two RBM channels inoperable.
| |
| C. Rod worth minimizer C.1 Suspend control rod Immediately (RWM) inoperable movement except by during reactor scram.startup.OR (continued)
| |
| JAFNPP 3.3.2.1-1 Amendment 274 Control Rod Block Instrumentation 3.3.2.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued)
| |
| C.2.1.1 Verify i 12 rods Immediately withdrawn.
| |
| OR C.2.1.2 Verify by Immediately administrative methods that startup with RWM inoperable has not been performed in the current calendar year.AND C.2.2 Verify movement of During control control rods is in rod movement compliance with banked position withdrawal sequence (BPWS) by a second licensed operator or other qualified member of the technical staff.D. RWM inoperable during D.1 Verify movement of During control reactor shutdown.
| |
| control rods is in rod movement compliance with BPWS by a second licensed operator or other qualified member of the technical staff.(continued)
| |
| JAFNPP 3.3.2.1-2 Amendment 274 Control Rod Block Instrumentation 3.3.2.1 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME E. One or more Reactor E.1 Suspend control rod Immediately Mode Switch-Shutdown withdrawal.
| |
| Position channels inoperable.
| |
| AND E.2 Initiate action to Immediately fully insert all insertable control rods in core cells containing one or more fuel assemblies.
| |
| SURVEILLANCE REQUIREMENTS
| |
| -------------------------------------
| |
| NOTES--..................................
| |
| : 1. Refer to Table 3.3.2.1-1 to determine which SRs apply for each Control Rod Block Function.2. When an RBM channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains control rod block capability.
| |
| SURVEILLANCE FREQUENCY SR 3.3.2.1.1 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.2.1.2
| |
| ------------
| |
| NOTE-------------------
| |
| Not required to be performed until 1 hour after any control rod is withdrawn at s 10X RTP in MODE 2.Perform CHANNEL FUNCTIONAL TEST. 92 days (continued)
| |
| JAFNPP 3.3.2.1-3 Amendment 274 Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.3.2.1.3-----------------
| |
| NOTE-----------------
| |
| Not required to be performed until 1 hour after THERMAL POWER is 10% RTP in MODE 1.... ..... ...... .. ...... ...Perform CHANNEL FUNCTIONAL TEST.92 days 1*SR 3.3.2.1.4------------------
| |
| NOTE----------------.
| |
| Neutron detectors are excluded.... ..... .. ... ........ .....................
| |
| .Verify the RBM is not bypassed: a. When THERMAL POWER is 2 30% RTP; and b. When a peripheral control rod is not selected.92 days SR 3.3.2.1.5------------------
| |
| NOTES------------------
| |
| : 1. Neutron detectors are excluded.2. For Function 1.a, the recirculation loop flow signal portion of the channel is excluded....P ..eror .HANL.ALBATO.
| |
| Perform CHANNEL CALIBRATION.
| |
| 92 days SR 3.3.2.1.6 Verify the RWM is not bypassed when 24 months THERMAL POWER is 10% RTP.(continued)
| |
| JAFNPP 3.3.2.1-4 Amendment 274 Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.3.2.1.7
| |
| ---NOTE-------------------
| |
| Not required to be performed until 1 hour after reactor mode switch is in the shutdown position..........................................
| |
| Perform CHANNEL FUNCTIONAL TEST. 24 months SR 3.3.2.1.8
| |
| -----------------
| |
| NOTE-------------------
| |
| For Function 1.a. all portions of the channel except the recirculation loop flow signal portion are excluded.....................
| |
| ................................
| |
| Perform CHANNEL CALIBRATION.
| |
| 24 months SR 3.3.2.1.9 Verify control rod sequences input to the Prior to RWM are in conformance with BPWS. declaring RWM OPERABLE following loading of sequence into RWM JAFNPP 3.3.2.1-5 Amendment 274 Control Rod Block Instrumentation 3.3.2.1 Table 3.3.2.1-1 (page 1 of 1)Control Rod Block Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS REQUIREMENTS VALUE 1. Rod Block Monitor a. Upscale (a) 2 SR 3.3.2.1.4 As specified in SR 3.3.2.1.5 the COLR SR 3.3.2.1.8 b. Inop (a) 2 SR 3.3.2.1.1 NA SR 3.3.2.1.4 c. Downscale (a) 2 SR 3.3.2.1.4 2 2.5/125 SR 3.3.2.1.5 divisions of full scale 2. Rod Worth Minimizer 1 (b)2 (b) 1 SR 3.3.2.1.2 NA SR 3.3.2.1.3 SR 3.3.2.1.6 SR 3.3.2.1.9 3. Reactor Mode Switch -Shutdown (c) 2 SR 3.3.2.1.7 NA Position (a)(b)(c)THERMAL POWER 2 301 RTP and no peripheral control rod selected.With THERMAL POWER s lOt RTP.Reactor mode switch in the shutdown position.JAFNPP 3.3.2.1-6 Amendment 274 Feedwater and Main Turbine High Water Level Trip Instrumentation 3.3.2.2 3.3 INSTRUMENTATION 3.3.2.2 Feedwater and Main Turbine High Water Level Trip Instrumentation LCO 3.3.2.2 APPLICABILITY:
| |
| Three channels of feedwater and main turbine high water level trip instrumentation shall be OPERABLE.THERMAL POWER 2 25% RTP.ACTIONS.---------------------.
| |
| NOTE-------------------------------------
| |
| Separate Condition entry is allowed for each channel.-------....-- ----------------------------CONDITION REQUIRED ACTION COMPLETION TIME A. One feedwater and main A.1 Place channel in 7 days turbine high water trip.level trip channel inoperable.
| |
| B. Two or more feedwater B.1 Restore feedwater and 2 hours and main turbine high main turbine high water level trip water level trip channels inoperable.
| |
| capability.(continued)
| |
| JAFNPP 3.3.2.2-1 Amendment 274 Feedwater and Main Turbine High Water Level Trip Instrumentation 3.3.2.2 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1- ---- NOTE-------
| |
| associated Completion Only applicable if Time not met. inoperable channel is the result of inoperable feedwater pump turbine or main turbine stop valve.... ..................
| |
| Remove affected stop 4 hours valve(s) from service.OR C.2 Reduce THERMAL POWER 4 hours to < 25% RTP.SURVEILLANCE REQUIREMENTS
| |
| ......---......---------------------
| |
| NOTE------------------------------------
| |
| When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided feedwater and main turbine high water level trip capability is maintained.
| |
| SURVEILLANCE FREQUENCY SR 3.3.2.2.1 Perform CHANNEL CHECK. 24 hours (continued)
| |
| JAFNPP 3.3.2.2-2 Amendment 274
| |
| ---Feedwater and Main Turbine High Water Level Trip Instrumentation 3.3.2.2 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.3.2.2.2
| |
| ------------------
| |
| NOTE-------------------
| |
| Only required to be performed when in MODE 4 for > 24 hours..... .......................
| |
| ........................................................
| |
| .Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.2.2.3 Perform CHANNEL CALIBRATION.
| |
| The 24 months Allowable Value shall be s 222.5 inches.SR 3.3.2.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST 24 months including valve actuation.
| |
| JAFNPP 3.3.2.2-3 Amendment 274 PAM Instrumentation 3.3.3.1 3.3 INSTRUMENTATION 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3.1 APPLICABILITY:
| |
| The PAM instrumentation for each Function in Table 3.3.3.1-1 shall be OPERABLE.MODES 1 and 2.ACTIONS Sep-arate Condition entry is aNOTE for-each-Function.
| |
| Separate Condition entry is allowed for each Function.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Restore required channel 30 days with one required to OPERABLE status.channel inoperable.
| |
| B. Required Action and B.1 Initiate action in Immediately associated Completion accordance with Time of Condition A not Specification 5.6.6.met.C. One or more Functions C.1 Restore one required 7 days with two required channel to OPERABLE channels inoperable.
| |
| status.(continued)
| |
| JAFNPP 3.3.3.1-1 Amendment 284 PAM Instrumentation 3.3.3.1 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C Table 3.3.3.1-1 for not met. the channel.E. As required by E.1 Be in MODE 3. 12 hours Required Action D.1 and referenced in Table 3.3.3.1-1.
| |
| F. As required by F.1 Initiate action in Immediately Required Action D.1 accordance with and referenced in Specification 5.6.6.Table 3.3.3.1-1.
| |
| SURVEILLANCE REQUIREMENTS
| |
| ------------------------------------
| |
| NOTE -----------------------------------
| |
| When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the other required channel in the associated Function is OPERABLE.SURVEILLANCE FREQUENCY SR 3.3.3.1.1 Perform CHANNEL CHECK of each required 31 days PAM instrument channel.(continued)
| |
| JAFNPP 3.3.3.1-2 Amendment 274 PAM Instrumentation 3.3.3.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.3.3.1.2 Perform CHANNEL CALIBRATION of each 24 months required PAM instrumentation channel.I JAFNPP 3.3.3.1-3 Amendment 280 PAM Instrumentation 3.3.3.1 Table 3.3.3.1-1 (page 1 of 1)Post Accident Monitoring Instrumentation CONDITIONS REFERENCED REQUIRED FROM REQUIRED FUNCTION CHANNELS ACTION D.1 1. Reactor Vessel Pressure 2 E 2. Reactor Vessel Water Level a. Fuel Zone 2 E b. Wide Range 2 E 3. Suppression Pool Water Level (Wide Range) 2 E 4. Drywell Pressure a. Narrow Range 2 E b. Wide Range 2 E 5. Containment High Range Radiation 2 F 6. Drywell Temperature 2 E 7. Penetration Flow Path PCIV Position 2 per penetrat E 8. Suppression Chamber Pressure 2 E 9. Suppression Pool Water Temperature 2 E 10. Drywell Water Level 2 E (a) Not required for isolation valves whose associated penetration flow path is isolated by at least one closed and deactivated automatic valve. closed manual valve, blind flange, or check valve with flow through the valve secured.(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.JAFNPP 3.3.3.1-4 Amendment 280 Remote Shutdown System 3.3.3.2 3.3 INSTRUMENTATION 3.3.3.2 Remote Shutdown System LCO 3.3.3.2 APPLICABILITY:
| |
| The Remote Shutdown System Functions shall be OPERABLE.MODES 1 and 2.ACTIONS--- ----- ------- --- ----------
| |
| NOTE -------------------------------
| |
| Separate Condition entry is allowed for each Function.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore required Function 30 days Functions inoperable, to OPERABLE status.B. Required Action and B.1 Be in MODE 3. 12 hours associated Completion Time not met.JAFNPP 3.3.3.2-1 Amendment 284 Remote Shutdown System 3.3.3.2 SURVEILLANCE REQUIREMENTS
| |
| -------------------------------------
| |
| NOTE- -----------------------
| |
| When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours..............................................................................................................
| |
| SURVEILLANCE FREQUENCY SR 3.3.3.2.1 Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.
| |
| SR 3.3.3.2.2 Verify each required control circuit and 24 months transfer switch is capable of performing the intended function.SR 3.3.3.2.3 Perform CHANNEL CALIBRATION for each 24 months required instrumentation channel.JAFNPP 3.3.3.2-2 Amendment 274
| |
| --ATWS-RPT Instrumentation 3.3.4.1 3.3 INSTRUMENTATION 3.3.4.1 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT)
| |
| Instrumentation LCO 3.3.4.1 Two channels per trip system for each ATWS-RPT instrumentation Function listed below shall be OPERABLE: a. Reactor Vessel Water Level- Low Low (Level 2); and b. Reactor Pressure-High.APPLICABILITY:
| |
| MODE 1.ACTIONS..- -------------------
| |
| NOTE-------------------------------------
| |
| Separate Condition entry is allowed for each channel... .. ..............
| |
| ...........................................
| |
| ........CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Restore channel to 14 days inoperable.
| |
| OPERABLE status.OR A.2 --------NOTE---------
| |
| Not applicable if inoperable channel is the result of an inoperable breaker.Place channel in 14 days trip.(continued)
| |
| JAFNPP 3.3.4.1-1 Amendment 274
| |
| ---ATWS-RPT Instrumentation 3.3.4.1 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME B. One Function with B.1 Restore ATWS-RPT trip 72 hours ATWS-RPT trip capability.
| |
| capability not maintained.
| |
| C. Both Functions with C.1 Restore ATWS-RPT trip 1 hour ATWS-RPT trip capability for one capability not Function.maintained.
| |
| D. Required Action and D.1 -------NOTE--*-------
| |
| associated Completion Only applicable if Time not met. inoperable channel is the result of an inoperable RPT breaker......................
| |
| Remove the affected 6 hours recirculation pump from service.OR D.2 Be in MODE 2. 6 hours JAFNPP 3.3.4.1-2 Amendment 274 ATWS-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS
| |
| ------NOTE------------------
| |
| When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains ATWS-RPT trip capability.
| |
| SURVEILLANCE FREQUENCY SR 3.3.4.1.1 Perform CHANNEL CHECK. 12 hours SR 3.3.4.1.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.4.1.3 Calibrate the trip units. 184 days SR 3.3.4.1.4 Perform CHANNEL CALIBRATION.
| |
| The 24 months Allowable Values shall be: a. Reactor Vessel Water Level -Low Low (Level 2): 2 105.4 inches; and b. Reactor Pressure-High: 1153 psig.SR 3.3.4.1.5 Perform LOGIC SYSTEM FUNCTIONAL TEST 24 months including breaker actuation.
| |
| JAFNPP 3.3.4.1-3 Amendment 274
| |
| ---ECCS Instrumentation 3.3.5.1 3.3 INSTRUMENTATION 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation LCO 3.3.5.1 APPLICABILITY:
| |
| The ECCS instrumentation for each Function in Table 3.3.5.1-1 shall be OPERABLE.According to Table 3.3.5.1-1.
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| ACTIONS-------------
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| NOTE-------------------------------------
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| Separate Condition entry is allowed for each channel.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Enter the Condition Immediately inoperable.
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| referenced in Table 3.3.5.1-1 for the channel.B. As required by B.1 --------NOTES--------
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| Required Action A.1 1. Only applicable and referenced in in MODES 1. 2.Table 3.3.5.1-1.
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| and 3.2. Only applicable for Functions 1.a. 1.b. 2.a.and 2.b......................
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| Declare supported 1 hour from feature(s) inoperable discovery of when its redundant loss of feature ECCS initiation initiation capability capability for is inoperable.
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| feature(s) in both divisions AND (continued)
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| JAFNPP 3.3.5.1-1 Amendment 274
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| -ECCS Instrumentation 3.3.5.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued)
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| B.2 --------NOTE-........
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| Only applicable for Functions 3.a and 3.b.Declare High Pressure 1 hour from Coolant Injection discovery of (HPCI) System loss of HPCI inoperable.
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| initiation capability AND B.3 Place channel in 24 hours trip.C. As required by C.1 --------NOTES--------
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| Required Action A.1 1. Only applicable and referenced in in MODES 1. 2.Table 3.3.5.1-1.
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| and 3.2. Only applicable for Functions 1.c, 1.d. 2.c.2.d. and 2.f..............
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| ............
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| ...Declare supported 1 hour from feature(s) inoperable discovery of when its redundant loss of feature ECCS initiation initiation capability capability for is inoperable.
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| feature(s) in both divisions AND C.2 Restore channel to 24 hours OPERABLE status.(continued)
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| JAFNPP 3.3.5.1-2 Amendment 274
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| -ECCS Instrumentation 3.3.5.1 ACTIONS (continued)
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| CONDITION REQUIRED ACTION COMPLETION TIME D. As required by D.1- --------NOTE ----Required Action A.1 Only applicable if and referenced in HPCI pump suction is Table 3.3.5.1-1.
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| not aligned to the suppression pool.Declare HPCI System 1 hour from inoperable.
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| discovery of loss of HPCI initiation capability AND D.2.1 Place channel in 24 hours trip.OR D.2.2 Align the HPCI pump 24 hours suction to the suppression pool.(continued)
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| JAFNPP 3.3.5.1-3 Amendment 274 ECCS Instrumentation 3.3.5.1 ACTIONS (continued)
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| CONDITION REQUIRED ACTION COMPLETION TIME E. As required by E.1 --------NOTES--------
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| Required Action A.1 1. Only applicable and referenced in in MODES 1. 2.Table 3.3.5.1-1.
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| and 3.2. Only applicable for Functions i.e. 1.f.and 2.g.Declare supported 1 hour from feature(s) inoperable discovery of when its redundant loss of feature ECCS initiation initiation capability capability for is inoperable.
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| subsystems in both divisions AND E.2 Restore channel to 7 days OPERABLE status.(continued)
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| JAFNPP 3.3.5.1-4 Amendment 274
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| --ECCS Instrumentation 3.3.5.1 ACTIONS (continued)
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| CONDITION REQUIRED ACTION COMPLETION TIME F. As required by F.1 Declare Automatic 1 hour from Required Action A.1 Depressurization discovery of and referenced in System (ADS) valves loss of ADS Table 3.3.5.1-1.
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| inoperable.
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| initiation capability in both trip systems AND F.2 Place channel in 96 hours from trip. discovery of inoperable channel concurrent with HPCI or reactor core isolation cooling (RCIC)inoperable AND 8 days G. As required by G.1 Declare ADS valves 1 hour from Required Action A.1 inoperable.
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| discovery of and referenced in loss of ADS Table 3.3.5.1-1.
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| initiation capability in both trip systems AND (continued)
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| JAFNPP 3.3.5.1-5 Amendment 274 ECCS Instrumentation 3.3.5.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME G. (continued)
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| G.2 Restore channel to 96 hours from OPERABLE status. discovery of inoperable channel concurrent with HPCI or RCIC inoperable AND 8 days H. Required Action and H.1 Declare associated Immediately associated Completion supported feature(s)
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| Time of Condition B. inoperable.
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| C, D, E. F, or G not met.JAFNPP 3.3.5.1-6 Amendment 274 ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS
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| ------------------------------
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| ------NOTES- .1. Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function.2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours for Functions 3.c. 3.f, and 3.g; and (b) for up to 6 hours for Functions other than 3.c, 3.f, and 3.g provided the associated Function or the redundant Function maintains ECCS initiation capability.
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| ... ..... ...................: -------- ------SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK. 12 hours SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.5.1.3 Perform CHANNEL CALIBRATION.
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| 92 days SR 3.3.5.1.4 Calibrate the trip units. 184 days SR 3.3.5.1.5 Perform CHANNEL CALIBRATION.
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| 24 months SR 3.3.5.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months JAFNPP 3.3.5.1-7 Amendment 274 ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 of 5)Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES REQUIRED REFERENCED OR OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE 1. Core Spray System a. Reactor Vessel Water Level -Low Low Low (Level 1)b. Drywell Pressure -High c. Reactor Pressure -Low (Injection Permissive)
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| : d. Core Spray Pump Start -Time Delay Relay e. Core Spray Pump Discharge Flow -Low (Bypass)f. Core Spray Pump Discharge Pressure -High (Bypass)1.2.3.4 (a), 5 (a)1,2,3 1.2.3 4 (a). 5 (a)1.2.3, 4 (a), 5 (a)1.2.3.4 (a), 5 (a)1.2.3.4 (a), 5 (a)4 (b)4 (b)4 4 1 per pump 1 per pump 1 per pump B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6 B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6 C SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6 B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6 C SR 3.3.5.1.5 SR 3.3.5.1.6 2 18 inches s 2.7 psig 2 410 psig and s 490 psig 2 410 psig and s 490 psig t 12.34 seconds 2 510 gpm and s 980 gpm 2 90 psig and S 110 psig E SR 3.3.5.1.5 SR 3.3.5.1.6 E SR 3.3.5.1.3 SR 3.3.5.1.6 2. Low Pressure Coolant Injection (LPCI) System a. Reactor Vessel Water Level -Low Low Low (Level 1)1.2.3.4 (a), 5 (a)4 (b)B SR SR SR SR SR 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 2 18 inches (continued)(a) When associated ECCS subsystems) are required to be OPERABLE per LCO 3.5.2. ECCS -Shutdown.(b) Also required to initiate the associated emergency diesel generator subsystem.
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| JAFNPP 3.3.5.1-8 Amendment 274 ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 2 of 5)Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES REQUIRED REFERENCED OR OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE 2. LPCI System (continued)
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| : b. Drywell 1.2.3 4 (b) B SR 3.3.5.1.1 s 2.7 psig Pressure -High SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6 c. Reactor Pressure -Low 1.2.3 4 C SR 3.3.5.1.1 z 410 psig (Injection Permissive)
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| SR 3.3.5.1.2 and SR 3.3.5.1.4 s 490 psig SR 3.3.5.1.5 SR 3.3.5.1.6 4 (a). 5 (a) 4 B SR 3.3.5.1.1 2 410 psig SR 3.3.5.1.2 and SR 3.3.5.1.4 s 490 psig SR 3.3.5.1.5 SR 3.3.5.1.6 d. Reactor Pressure-Low 1 (c), 2 (c). 4 C SR 3.3.5.1.1 2 295 psig (Recdrculation SR 3.3.5.1.2 Discharge Valve 3 (c) SR 3.3.5.1.4 Permissive)
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| SR 3.3.5.1.5 SR 3.3.5.1.6 e. Reactor Vessel Shroud 1.2.3 2 B SR 3.3.5.1.1 k 1.0 inches Level (Level 0) SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6 f. Low Pressure Coolant 1.2.3. 1 per pump C SR 3.3.5.1.5 Injection Pump SR 3.3.5.1.6 Start -Time Delay 4 (a). 5 (a)Relay Pumps A. D s 1.51 seconds Pumps B. C s 6.73 seconds (continued)(a) When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2.(b) Also required to initiate the associated emergency diesel generator subsystem.(c) With associated recirculation pump discharge valve open.JAFNPP 3.3.5.1-9 Amendment 274
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| --ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 3 of 5)Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS NODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE 2. LPCI System (continued)
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| : g. Low Pressure Coolant Injection Pump Discharge Flow -Low (Bypass)1.2.3.4 (a), 5 (a)1 per subsystem E SR 3.3.5.1.5 SR 3.3.5.1.6 2 1040 gpm and s 1665 gpm h. Containment Pressure -High 1.2.3 4 B SR 3.3.5.1.3 SR 3.3.5.1.6 2 1 psig and s 2.7 psig 3. High Pressure Coolant Injection (HPCI) System a. Reactor Vessel Water Level -Low Low (Level 2)b. Drywell Pressure -High c. Reactor Vessel Water Level -High (Level 8)d. Condensate Storage Tank Level -Low e. Suppression Pool Water Level -High f. High Pressure Coolant Injection Pump Discharge Flow -Low (Bypass)g. High Pressure Coolant Injection Pump Discharge Pressure -High (Bypass)1.2 (d). 3 (d)1.2(d).3(d)1.2 (d). 3 (d)1.2 (d). 3 (d)1.2 (d). 3 (d)1.2 (d). 3 (d)1.2 (d). 3 (d)4 4 2 4 2 B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6 B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6 C SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6 D SR 3.3.5.1.3 SR 3.3.5.1.6 2 126.5 inches s 2.7 psig s 222.5 inches 2 59.5 inches s 14.5 ft 2 475 gpm and S 800 gpm 2 25 psig and S 80 psig D SR 3.3.5.1.3 SR 3.3.5.1.6 1 E SR 3.3.5.1.5 SR 3.3.5.1.6 1 E SR 3.3.5.1.3 SR 3.3.5.1.6 (continued)(a) When the associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2.(d) With reactor steam dome pressure > 150 psig.JAFNPP 3.3.5.1-10 Amendment 274 ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 4 of 5)Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE 4. Automatic Depressurization System (ADS) Trip System A a. Reactor Vessel Water 1. 2 F SR 3.3.5.1.1 2 18 inches Level -Low Low Low d SR 3.3.5.1.2 (Level 1) 2 3 (d) SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6 b. Automatic
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| : 1. 1 G SR 3.3.5.1.5 s 134 seconds Depressurization SR 3.3.5.1.6 System Initiation 2 (d), 3 (d)Timer c. Reactor Vessel Water 1. 1 F SR 3.3.5.1.1 2 177 inches Level -Low (Level 3) (d SR 3.3.5.1.2 2 d) 3 (d) SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6 d. Core Spray Pump 1. 2 G SR 3.3.5.1.3 2 90 psig and Discharge 2 SR 3.3.5.1.6 s 110 psig Pressure -High 2 (d) 3 (d)e. Low Pressure Coolant 1. 4 G SR 3.3.5.1.3 2 105 psig Injection Pump d SR 3.3.5.1.6 and Discharge 2 3 (d) s 145 psig Pressure -High 5. ADS Trip System B a. Reactor Vessel Water 1. 2 F SR 3.3.5.1.1 2 18 inches Level -Low Low Low d SR 3.3.5.1.2 (Level 1) 2 3(d) SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6 b. Automatic
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| : 1. 1 G SR 3.3.5.1.5 s 134 seconds Depressurization SR 3.3.5.1.6 System Initiation 2 (d), 3 (d)Timer (continued)(d) With reactor steam dome pressure > 150 psig.JAFNPP 3.3.5.1-11 Amendment 274 ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 5 of 5)Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE 5. ADS Trip System B (continued)
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| : c. Reactor Vessel Water 1. 1 F SR 3.3.5.1.1 2 177 inches Level -Low (Level 3) d d SR 3.3.5.1.2 2 (d) 3 (d) SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6 d. Core Spray Pump 1. 2 G SR 3.3.5.1.3 2 90 psig Discharge SR 3.3.5.1.6 and Pressure-High 2 (d). 3 (d) S 1R .ps.g e. Low Pressure Coolant 1. 4 G SR 3.3.5.1.3 2 105 psig Injection Pump SR 3.3.5.1.6 and Discharge 2(d). 3(d) s 145 psig Pressure -High (d) With reactor steam dome pressure > 150 psig.JAFNPP 3.3.5.1-12 Amendment 274 RCIC System Instrumentation 3.3.5.2 3.3 INSTRUMENTATION 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation LCO 3.3.5.2 APPLICABILITY:
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| The RCIC System instrumentation for each Function in Table 3.3.5.2-1 shall be OPERABLE.MODE 1.MODES 2 and 3 with reactor steam dome pressure > 150 psig.ACTIONS-----------------------.-------------
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| NOTE- ------------------------------
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| Separate Condition entry is allowed for each channel.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Enter the Condition Immediately inoperable.
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| referenced in Table 3.3.5.2-1 for the channel.B. As required by B.1 Declare RCIC System 1 hour from Required Action A.1 inoperable.
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| discovery of and referenced in loss of RCIC Table 3.3.5.2-1.
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| initiation capability AND B.2 Place channel in 24 hours trip.C. As required by C.1 Restore channel to 24 hours Required Action A.1 OPERABLE status.and referenced in Table 3.3.5.2-1.(continued)
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| JAFNPP 3.3.5.2-1 Amendment 274 RCIC System Instrumentation 3.3.5.2 ACTIONS (continued)
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| _CONDITION REQUIRED ACTION COMPLETION TIME D. As required by D.1 --------NOTE---------
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| Required Action A.1 Only applicable if and referenced in RCIC pump suction is Table 3.3.5.2-1.
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| not aligned to the suppression pool.Declare RCIC System 1 hour from inoperable.
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| discovery of loss of automatic RCIC initiation capability AND D.2.1 Place channel in 24 hours trip.OR D.2.2 Align RCIC pump 24 hours suction to the suppression pool.E. Required Action and E.1 Declare RCIC System Immediately associated Completion inoperable.
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| Time of Condition B.C. or D not met.JAFNPP 3.3.5.2-2 Amendment 274
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| -.RCIC System Instrumentation 3.3.5.2 SURVEILLANCE REQUIREMENTS
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| ----------
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| NOTES------------------------
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| : 1. Refer to Table 3.3.5.2-1 to determine which SRs apply for each RCIC Function.2. When a channel is placed in an inoperable status solely for performance of required Surveillances.
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| entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours for Functions 2 and 4; and (b) for up to 6 hours for Functions 1 and 3 provided the associated Function maintains RCIC initiation capability.
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| SURVEILLANCE FREQUENCY SR 3.3.5.2.1 Perform CHANNEL CHECK. 12 hours SR 3.3.5.2.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.5.2.3 Perform CHANNEL CALIBRATION.
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| 92 days SR 3.3.5.2.4 Calibrate the trip units. 184 days SR 3.3.5.2.5 Perform CHANNEL CALIBRATION.
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| 24 months SR 3.3.5.2.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months JAFNPP 3.3.5.2-3 Amendment 274 RCIC System Instrumentation 3.3.5.2 Table 3.3.5.2-1 (page 1 of 1)Reactor Core Isolation Cooling System Instrumentation CONDITIONS REQUIRED REFERENCED CHANNELS FROM REQUIRED SURVEILLANCE ALLOWABLE FUNCTION PER FUNCTION ACTION A.1 REQUIREMENTS VALUE 1. Reactor Vessel Water 4 B SR 3.3.5.2.1 2 126.5 inches Level -Low Low (Level 2) SR 3.3.5.2.2 SR 3.3.5.2.4 SR 3.3.5.2.5 SR 3.3.5.2.6 2. Reactor Vessel Water 2 C SR 3.3.5.2.1 s 222.5 inches Level -High (Level 8) SR 3.3.5.2.2 SR 3.3.5.2.4 SR 3.3.5.2.5 SR 3.3.5.2.6 3. Condensate Storage Tank 4 D SR 3.3.5.2.3 2 59.5 inches Level -Low SR 3.3.5.2.6 4. Manual Initiation I C SR 3.3.5.2.6 NA JAFNPP 3.3.5.2-4 Amendment 274 Primary Containment Isolation Instrumentation 3.3.6.1 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment Isolation Instrumentation LCO 3.3.6.1 APPLICABILITY:
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| The primary containment isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.According to Table 3.3.6.1-1.
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| ACTIONS-------------------------------------
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| NOTES------------------------------------
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| : 1. Penetration flow paths may be unisolated intermittently under administrative controls.2. Separate Condition entry is allowed for each channel.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Place channel in 12 hours for channels inoperable.
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| trip. Functions 2.a.2.b. 2.d, 2.g.5.e. 5.f, 6.b.7.a, and 7.b AND 24 hours for Functions other than Functions 2.a, 2.b, 2.d.2.g. 5.e, 5.f, 6.b. 7.a, and 7.b B. One or more Functions B.1 Restore isolation 1 hour with isolation capability.
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| capability not maintained.(continued)
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| JAFNPP 3.3.6.1-1 Amendment 274 Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS (continued)
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| CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Enter the Condition Immediately associated Completion referenced in Time of Condition A Table 3.3.6.1-1 for or B not met. the channel.D. As required by D.1 Isolate associated 12 hours Required Action C.1 main steam line and referenced in (MSL).Table 3.3.6.1-1.
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| OR D.2.1 Be in MODE 3. 12 hours AND D.2.2 Be in MODE 4. 36 hours E. As required by E.1 Be in MODE 2. 6 hours Required Action C.1 and referenced in Table 3.3.6.1-1.
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| F. As required by F.1 Isolate the affected 1 hour Required Action C.1 penetration flow and referenced in path(s).Table 3.3.6.1-1.
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| G. As required by G.1 Isolate the affected 24 hours Required Action C.1 penetration flow and referenced in path(s).Table 3.3.6.1-1.(continued)
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| JAFNPP 3.3.6.1-2 Amendment 274 Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS (continued)
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| CONDITION REQUIRED ACTION COMPLETION TIME H. Required Action and H.1 Be in MODE 3. 12 hours associated Completion Time of Condition F or AND G not met.H.2 Be in MODE 4. 36 hours OR As required by Required Action C.1 and referenced in Table 3.3.6.1-1.
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| I. As required by 1.1 Declare associated 1 hour Required Action C.1 standby liquid and referenced in control subsystem Table 3.3.6.1-1. (SLC) inoperable.
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| OR I.2 Isolate the Reactor 1 hour Water Cleanup System.J. As required by J.1 Initiate action to Immediately Required Action C.1 restore channel to and referenced in OPERABLE status.Table 3.3.6.1-1.
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| OR J.2 Initiate action to Immediately isolate the Residual Heat Removal (RHR)Shutdown Cooling System.JAFNPP 3.3.6.1-3 Amendment 274 Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS
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| ...-------------------------
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| NOTES-----------------------------------
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| : 1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours for Functions 2.d, 2.g. 7.a, and 7.b: and (b) for up to 6 hours for Functions other than 2.d, 2.g, 7.a. and 7.b provided the associated Function maintains isolation capability.
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| SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK. 12 hours SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.6.1.3
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| ------------------
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| NOTE------------------
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| For Functions 1.f and 2.f. radiation detectors are excluded....... ............
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| ..........Perform CHANNEL CALIBRATION.
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| 92 days SR 3.3.6.1.4 Calibrate the trip units. 184 days SR 3.3.6.1.5 Perform CHANNEL CALIBRATION.
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| 24 months SR 3.3.6.1.6 Calibrate the radiation detectors.
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| 24 months SR 3.3.6.1.7 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months (continued)
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| JAFNPP 3.3.6.1-4 Amendment 274 Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS (continued)
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| SURVEILLANCE FREQUENCY+SR 3.3.6.1.8... .------NOTE-----------------"n" equals 2 channels for the purpose of determining the STAGGERED TEST BASIS Frequency.
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| Verify the ISOLATION INSTRUMENTATION RESPONSE TIME is within limits.24 months on a STAGGERED TEST BASIS JAFNPP 3.3.6.1-5 Amendment 274 Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 1 of 6)Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE 1. Main Steam Line Isolation a. Reactor Vessel Water 1.2.3 2 D SR 3.3.6.1.1 2 18 inches Level -Low Low Low SR 3.3.6.1.2 (Level 1) SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 SR 3.3.6.1.8 b. Main Steam Line 1 2 E SR 3.3.6.1.1 2 825 psig Pressure-Low SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 SR 3.3.6.1.8 c. Main Steam Line 1.2.3 2 per D SR 3.3.6.1.1 s 125.9 psid Flow -High MSL SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 SR 3.3.6.1.8 d. Condenser Vacuum -Low 1. 2 D SR 3.3.6.1.1 2 8 inches SR 3.3.6.1.2 Hg vacuum 2 (a), 3 (a) SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 e. Hain Steam Tunnel Area 1.2.3 8 D SR 3.3.6.1.1 s 195'F Temperature
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| -High SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 f. Main Steam Line 1,2.3 2 F SR 3.3.6.1.1 s 3 times Radiation
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| -High SR 3.3.6.1.3 Normal Full SR 3.3.6.1.6 Power SR 3.3.6.1.7 Background (continued)(a) With any turbine stop valve not closed.(b) Not used.JAFNPP 3.3.6.1-6 Amendment 274 Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 2 of 6)Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE 2. Primary Containment Isolation a. Reactor Vessel Water 1.2.3 2 H SR 3.3.6.1.1 2 177 inches Level -Low (Level 3) SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 b. Drywell Pressure-High 1.2.3 2 H SR 3.3.6.1.1 s 2.7 psig SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 c. Containment 1.2.3 1 F SR 3.3.6.1.1 s 450 R/hr Radiation
| |
| -High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7 d. Drywell Pressure -High 1.2.3 2 (c) F SR 3.3.6.1.1 s 2.7 psig SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 e. Reactor Vessel Water 1.2.3 2 F SR 3.3.6.1.1 2 18 inches Level -Low Low Low SR 3.3.6.1.2 (Level 1) SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 f. Main Steam Line 1.2.3 2 F SR 3.3.6.1.1 s 3 times Radiation-High SR 3.3.6.1.3 Normal Full SR 3.3.6.1.6 Power SR 3.3.6.1.7
| |
| | |
| ===Background===
| |
| : g. Reactor Vessel Water 1.2.3 2 (c) F SR 3.3.6.1.1 2 177 inches Level -Low (Level 3) SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 (continued)(b) Not used.(c) Only one trip system provided for each associated penetration.
| |
| JAFNPP 3.3.6.1-7 Amendment 274 Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 3 of 6)Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE 3. High Pressure Coolant Injection (HPCI) System Isolation a. HPCI Steam Line* Flow -High 1.2.3 1 F SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5 3.3.6.1.7 s 168.24 inches of water dP b. HPCI Steam Supply Line Pressure -Low c. HPCI Turbine Exhaust Diaphragm Pressure -High d. HPCI Steam Line Penetration (Drywell Entrance)
| |
| Area Temperature
| |
| -High e. HPCI Steam Line Torus Room Area Temperature
| |
| -High f. RHR Heat Exchanger A Area Temperature
| |
| -High g. RHR Heat Exchanger B Area Temperature
| |
| -High h. RB Southwest Area of Elevation 272'Temperature
| |
| -High i. RB Southeast Area of Elevation 272'Temperature
| |
| -High 1.2.3 1.2.3 2 2 F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 F SR 3.3.6.1.3 SR 3.3.6.1.7 2 61 psig and 5 90 psig sc 9.9 psig, 1.2.3 1.2.3 1.2.3 1.2.3 1.2.3 1.2.3 F SR SR SR SR SR F SR SR SR SR SR F SR SR SR SR SR F SR SR SR SR SR F SR SR SR SR SR F SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5 3.3.6.1.7 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5 3.3.6.1.7 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5 3.3.6.1.7 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5 3.3.6.1.7 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5 3.3.6.1.7 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5 3.3.6.1.7 s 160-F s 160F s 170'F s 170'F s 144F s 144-F (continued)
| |
| JAFNPP 3.3.6.1-8 Amendment 274 Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 4 of 6)Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE 3. HPCI System Isolation (continued)
| |
| J. HPCI Equipment Area 1.2.3 2 F SR 3.3.6.1.1 s 144F Temperature
| |
| -High SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 4. Reactor Core Isolation Cooling (RCIC) System Isolation a. RCIC Steam Line 1.2.3 1 F SR 3.3.6.1.1 5 272.26 inches Flow -High SR 3.3.6.1.2 of water dP SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 b. RCIC Steam Supply 1.2,3 2 F SR 3.3.6.1.1 a 58 psig and Line Pressure -Low SR 3.3.6.1.2 s 93 psig SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 c. RCIC Turbine 1.2.3 2 F SR 3.3.6.1.3 s 5 psig Exhaust Diaphragm SR 3.3.6.1.7 Pressure -High d. RCIC Steam Line 1.2.3 1 F SR 3.3.6.1.1 s 160F Penetration (Drywell SR 3.3.6.1.2 Entrance)
| |
| Area SR 3.3.6.1.4 Temperature
| |
| -High SR 3.3.6.1.5 SR 3.3.6.1.7 e. RCIC Steam Line Torus 1.2.3 1 F SR 3.3.6.1.1 s 160'F Room Area SR 3.3.6.1.2 Temperature
| |
| -High SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 f. RCIC Equipment Area 1.2.3 2 F SR 3.3.6.1.1 s 144'F Temperature
| |
| -High SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 (continued)
| |
| JAFNPP 3.3.6.1-9 Amendment 274 Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 5 of 6)Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS NODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE S. Reactor Water Cleanup (RWCU) System Isolation a. RWCU Suction Line 1.2.3 1 F SR 3.3.6.1.3 s 144'F Penetration Area SR 3.3.6.1.7 Temperature
| |
| -High b. RWCU Pump Area 1.2.3 1 per F SR 3.3.6.1.3 i 165'F for Temperature -High room SR 3.3.6.1.7 Pump Room A and s 175'F for Pump Room B c. RWCU Heat 1.2.3 1 F SR 3.3.6.1.3 s 155F Exchanger Room Area SR 3.3.6.1.7 Temperature
| |
| -High d. SLC System Initiation 1.2 2 (d) I SR 3.3.6.1.7 NA e. Reactor Vessel Water 1.2.3 2 F SR 3.3.6.1.1 2 177 inches Level -Low (Level 3) SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 f. Drywell 1.2.3 2 F SR 3.3.6.1.1 s 2.7 psig Pressure -High SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 6. Shutdown Cooling System Isolation a. Reactor 1.2.3 1 F SR 3.3.6.1.3 s 74 psig Pressure -High SR 3.3.6.1.7 b. Reactor Vessel Water 3.4.5 2 (e) J SR 3.3.6.1.1 2 177 inches Level -Low (Level 3) SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 (continued)(d) SLC System Initiation only inputs into one of the two trip systems and only isolates one valve in the RWCU suction and return line.(e) Only one trip system required in MODES 4 and 5 when RHR Shutdown Cooling System integrity maintained.
| |
| JAFNPP 3.3 .6 .1-10 Amendment 274 Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 6 of 6)Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE 7. Traversing Incore Probe System Isolation a. Reactor Vessel Water 1.2.3 2 G SR 3.3.6.1.1 z 177 inches Level -Low (Level 3) SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 b. Drywell 1.2.3 2 G SR 3.3.6.1.1 s 2.7 psig Pressure -High SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 JAFNPP 3.3.6.1-11 Amendment 274 Secondary Containment Isolation Instrumentation 3.3.6.2 3.3 INSTRUMENTATION 3.3.6.2 Secondary Containment Isolation Instrumentation LCO 3.3.6.2 APPLICABILITY:
| |
| The secondary containment isolation instrumentation for each Function in Table 3.3.6.2-1 shall be OPERABLE.According to Table 3.3.6.2-1.
| |
| ACTIONS--..----------..
| |
| --.----..---.-----.-.
| |
| NOTE.....................................
| |
| Separate Condition entry is allowed for each channel.......- ----...- ---...- .................
| |
| -..- -..- -----....- ----....- -...-..-...-.......-
| |
| -..- -. .....................
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Place channel in 12 hours for inoperable.
| |
| trip. Functions 1 and 2 AND 24 hours for Functions 3 and 4 B. One or more Functions B.1 Restore secondary 1 hour with secondary containment isolation containment isolation capability.
| |
| capability not maintained.
| |
| C. Required Action and C.1.1 Isolate the 1 hour associated Completion associated secondary Time of Condition A containment or B not met. penetration flow path(s).OR (continued)
| |
| JAFNPP 3.3.6.2-1 Amendment 274 Secondary Containment Isolation Instrumentation 3.3.6.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued)
| |
| C.1.2 Declare associated 1 hour secondary containment isolation valves inoperable.
| |
| AND C.2.1 Place the associated 1 hour standby gas treatment (SGT) subsystem~s) in operation.
| |
| OR C.2.2 Declare associated 1 hour SGT subsystem(s) inoperable.
| |
| SURVEILLANCE REQUIREMENTS
| |
| --- -----------------
| |
| NOTES-------------------
| |
| : 1. Refer to Table 3.3.6.2-1 to determine which SRs apply for each Secondary Containment Isolation Function.2. When a channel is placed in an inoperable status solely for performance of required Surveillances.
| |
| entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains secondary containment isolation capability.
| |
| SURVEILLANCE FREQUENCY SR 3.3.6.2.1 Perform CHANNEL CHECK. 12 hours (continued)
| |
| JAFNPP 3.3.6.2-2 Amendment 274 Secondary Containment Isolation Instrumentation 3.3.6.2 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.3.6.2.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.6.2.3 Perform CHANNEL CALIBRATION 92 days SR 3.3.6.2.4 Calibrate the trip units. 184 days SR 3.3.6.2.5 Perform CHANNEL CALIBRATION.
| |
| 24 months SR 3.3.6.2.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months JAFNPP 3.3.6.2-3 Amendment 274 i, Secondary Containment Isojation Instrumentation 3.3.6.2 Table 3.3.6.2-1 (page 1 of 1)Secondary Containment Isolation Instrumentation APPLICABLE MODES OR REQUIRED OTHER CHANNELS SPECIFIED PER SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS TRIP SYSTEM REQUIREMENTS VALUE 1. Reactor Vessel Water 1.2.3. 2 SR 3.3.6.2.1 2 177 inches Level -Low (Level 3) (a) SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 SR 3.3.6.2.6 2. Drywell Pressure-High 1.2.3 2 SR 3.3.6.2.1 5 2.7 psig SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 SR 3.3.6.2.6 3. Reactor Building Exhaust 1.2.3. 1 SR 3.3.6.2.1 g 24.800 cpm Radiation
| |
| -High (a).(b) SR 3.3.6.2.3 SR 3.3.6.2.6 4. Refueling Floor Exhaust 1.2.3. 1 SR 3.3.6.2.1 s 24.800 cpm Radiation
| |
| -High (a).(b) SR 3.3.6.2.3 SR 3.2.6.2.6 (a)(b)During operations with a potential for draining the reactor vessel.During movement of recently irradiated fuel assemblies in secondary containment.
| |
| JAFNPP 3.3.6.2-4 Amendment 276 SEP 1 2 21x12
| |
| -l u R. EAS zob zem~ -:<>,- ;v ,~ i 37 .3.3 INSTRUMENTATION 3.3.7.1 Control Room Emergency Ventilaticn Air Supply (CREVAS)System Instrumentation LCO 3.3.7.1 APPLICABILITY:
| |
| The Control Room Air Inlet Radiation -High channel shall be OPERABLE.MODES 1. 2 and 3.During movement of recently irradiated fuel assemblies in the secondary containment.
| |
| During operations with a potential for draining the reactor vessel.I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Channel inoperable.
| |
| A.1 Place the CREVAS 1 hour System in the isolate mode of operation.
| |
| OR A.2 Declare both CREVAS 1 hour subsystems inoperable.
| |
| JAFNPP 3.3.7.1-1 Amendment 276 SEP 1 2 2W2 CREVAS System Instrumentation 3.3.7.1 SURVEILLANCE REQUIREMENTS N-------OTE------N--
| |
| NOTE.---------------------------------
| |
| When the channel is placed in an inoperable status solely for performance of required Surveillances, entry into the Condition and Required Actions may be delayed for up to 6 hours.SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK. 12 hours SR 3.3.7.1.2 Perform CHANNEL CALIBRATION.
| |
| The 92 days Allowable Value shall be s 4000 cpm.JAFNPP 3.3.7.1-2 Amendment 274 Condenser Air Removal Pump Isolation Instrumentation 3.3.7.2 3.3 INSTRUMENTATION 3.3.7.2 Condenser Air Removal Pump Isolation Instrumentation LCO 3.3.7.2 APPLICABILITY:
| |
| Four channels of the Main Steam Line Radiation-High Function for the condenser air removal pump isolation shall be OPERABLE.MODES 1 and 2 with any condenser air removal pump not isolated and any main steam line not isolated.ACTIONS-------------------------------------
| |
| NOTE--...................................
| |
| Separate Condition entry is allowed for each channel.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore channel to 24 hours channels inoperable.
| |
| OPERABLE status.OR A.2 --------NOTE---------
| |
| Not applicable if inoperable channel is the result of an inoperable isolation valve......................
| |
| Place channel or 24 hours associated trip system in trip.(continued)
| |
| JAFNPP 3.3.7.2-1 Amendment 274 Condenser Air Removal Pump Isolation Instrumentation 3.3.7.2 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME B. Condenser air removal B.1 Restore isolation 1 hour pump isolation capability.
| |
| capability not maintained.
| |
| C. Required Action and C.1 Isolate the condenser 12 hours associated Completion air removal pumps.Time of Condition A or B not met. OR C.2 Isolate the main 12 hours steam lines.OR C.3 Be in MODE 3. 12 hours SURVEILLANCE REQUIREMENTS
| |
| -----------------------------------
| |
| NOTE-----------------------------------
| |
| When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains condenser air removal pump isolation capability.
| |
| SURVEILLANCE FREQUENCY SR 3.3.7.2.1 Perform CHANNEL CHECK. 12 hours (continued)
| |
| JAFNPP 3.3.7.2-2 Amendment 274
| |
| .Condenser Air Removal Pump Isolation Instrumentation 3.3.7.2 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.3.7.2.2
| |
| -----------------
| |
| NOTE------------------
| |
| Radiation detectors are excluded.Perform CHANNEL CALIBRATION.
| |
| The 92 days Allowable Value shall be s 3 times Normal Full Power Background.
| |
| SR 3.3.7.2.3 Calibrate the radiation detectors.
| |
| 24 months SR 3.3.7.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST 24 months including isolation valve actuation.
| |
| JAFNPP 3.3.7.2-3 Amendment 274 Emergency Service Water (ESW) System Instrumentation 3.3.7.3 3.3 INSTRUMENTATION 3.3.7.3 Emergency Service Water (ESW) System Instrumentation LCO 3.3.7.3 APPLICABILITY:
| |
| Four channels of ESW pressure instrumentation shall be OPERABLE.MODES 1. 2 and 3.ACTIONS------------------------------------
| |
| NOTE------------------------------------
| |
| Separate Condition entry is allowed for each channel.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Place channel in 24 hours inoperable.
| |
| trip.B. Initiation capability B.1 Restore initiation 1 hour not maintained in both capability.
| |
| logic systems.C. Required Action and C.1 Declare associated Immediately associated Completion ESW subsystem(s)
| |
| Time of Condition A inoperable.
| |
| or B not met.JAFNPP 3.3.7.3-1 Amendment 274 Emergency Service Water (ESW) System Instrumentation 3.3.7.3 SURVEILLANCE REQUIREMENTS When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the ESW pressure instrumentation maintains initiation capability.
| |
| SURVEILLANCE FREQUENCY SR 3.3.7.3.1 Perform CHANNEL CALIBRATION.
| |
| The Allowable 92 days Value shall be -40 psig and 50 psig.SR 3.3.7.3.2 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months JAFNPP 3.3.7.3-2 Amendment 274 LOP Instrumentation 3.3.8.1 3.3 INSTRUMENTATION 3.3.8.1 Loss of Power (LOP) Instrumentation LCO 3.3.8.1 APPLICABILITY:
| |
| The LOP instrumentation for each Function in Table 3.3.8.1-1 shall be OPERABLE.MODES 1. 2, and 3, When the associated emergency diesel generator (EDG)subsystem is required to be OPERABLE by LCO 3.8.2. "AC Sources- Shutdown." ACTIONS.....------.----.-..-.-.-.-.-.-.----.
| |
| NOTE-------------------------------------
| |
| Separate Condition entry is allowed for each channel.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Place channel in 1 hour inoperable.
| |
| trip.B. Required Action and B.1 Declare associated Immediately associated Completion EDG(s) inoperable.
| |
| Time not met.JAFNPP 3.3.8.1-1 Amendment 274
| |
| -LOP Instrumentation 3.3.8.1 SURVEILLANCE REQUIREMENTS
| |
| -. ----NOTE----------'
| |
| Refer to Table 3.3.8.1-1 to determine which SRs apply for each LOP Function...............................................................................
| |
| SURVEILLANCE FREQUENCY SR 3.3.8.1.1 Perform CHANNEL CALIBRATION.
| |
| 24 months SR 3.3.8.1.2 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months JAFNPP 3.3.8.1-2 Amendment 274 LOP Instrumentation 3.3.8.1 Table 3.3.8.1-1 (page 1 of 1)Loss of Power Instrumentation REQUIRED CHANNELS SURVEILLANCE ALLOWABLE FUNCTION PER BUS REQUIREMENTS VALUE 1. 4.16 kV Emergency Bus Undervoltage (Loss of Voltage)a. Bus Undervoltage 2 SR 3.3.8.1.1 2 80.2 V and g 89.8 V SR 3.3.8.1.2 b. Time Delay 1 SR 3.3.8.1.1 2 2.4 seconds and SR 3.3.8.1.2 s 2.6 seconds 2. 4.16 kV Emergency Bus Undervoltage (Degraded Voltage)a. Bus Undervoltage 2 SR 3.3.8.1.1 z 109.8 V and SR 3.3.8.1.2 s 111.4 V b. Time Delay (LOCA) 1 SR 3.3.8.1.1 2 8.4 seconds and SR 3.3.8.1.2 s 9.5 seconds c. Time Delay (non-LOCA) 1 SR 3.3.8.1.1 2 41.0 seconds and SR 3.3.8.1.2 s 46.6 seconds JAFNPP 3.3.8.1-3 Amendment 274 RPS Electric Power Monitoring 3.3.8.2 3.3 INSTRUMENTATION 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring LCO 3.3.8.2 APPLICABILITY:
| |
| Two RPS electric power monitoring assemblies shall be OPERABLE for each inservice RPS motor generator set or alternate power supply.MODES 1 and 2.MODES 3, 4, and 5 with any control rod withdrawn from a core cell containing one or more fuel assemblies.
| |
| ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or both inservice A.1 Remove associated 72 hours power supplies with inservice power one electric power supply(s) from monitoring assembly service.inoperable.
| |
| B. One or both inservice B.1 Remove associated 1 hour power supplies with inservice power both electric power supply(s) from monitoring assemblies service.inoperable.
| |
| C. Required Action and C.1 Be in MODE 3. 12 hours associated Completion Time of Condition A or B not met in MODE 1 or 2.(continued)
| |
| JAFNPP 3.3.8.2-1 Amendment 274 RPS Electric Power Monitoring 3.3.8.2 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Initiate action to Immediately associated Completion fully insert all Time of Condition A insertable control or B not met in rods in core cells MODE 3. 4, or 5 with containing one or any control rod more fuel assemblies.
| |
| withdrawn from a core cell containing one or more fuel assemblies.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.8.2.1
| |
| ------------
| |
| NOTE-------------------
| |
| Only required to be performed prior to entering MODE 2 from MODE 3 or 4, when in MODE 4 for 2 24 hours..... ......................Perform CHANNEL FUNCTIONAL TEST. 184 days (continued)
| |
| JAFNPP 3.3.8.2-2 Amendment 274 RPS Electric Power Monitoring 3.3.8.2 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY 4.SR 3.3.8.2.2 Perform CHANNEL CALIBRATION of the electric power monitoring assemblies associated with the inservice RPS motor generator sets. The Allowable Values shall be: 24 months a. Overvoltage s 132 V. with time delay set to s 4 seconds.b. Undervoltage 2 112.5 V for RPS bus A and k 113.9 V for RPS bus B. with time delay set to s 4 seconds.c. Underfrequency k 57 Hz. with time delay set to s 4 seconds.SR 3.3.8.2.3 Perform CHANNEL CALIBRATION of the electric power monitoring assemblies associated with the inservice alternate power supplies.
| |
| The Allowable Values shall be: 24 months a. Overvoltage s 132 V. with time delay set to s 4 seconds.b. Undervoltage 2 109.9 V. with time delay set to s 4 seconds.c. Underfrequency
| |
| -57 Hz. with time delay set to i 4 seconds.SR 3.3.8.2.4 Perform a system functional test. 24 months JAFNPP 3.3.8.2-3 Amendment 274 Recirculation Loops Operating 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.1 Recirculation Loops Operating LCO 3.4.1 Two recirculation loops with matched flows shall operation and the reactor operating at core flow POWER conditions outside the Exclusion Region of to-flow map specified in the COLR.be in and THERMAL the power-OR One recirculation loop shall be in operation and the reactor operating at core flow and THERMAL POWER conditions outside the Exclusion Region of the power-to-flow map specified in the COLR with the following limits applied when the associated LCO is applicable:
| |
| : a. LCO 3.2.1.(APLHGR)." COLR;"AVERAGE PLANAR LINEAR HEAT GENERATION RATE single loop operation limits specified in the b. LCO 3.2.2. "MINIMUM CRITICAL POWER RATIO (MCPR)." loop operation limits specified in the COLR: single c. LCO 3.3.1.1, "Reactor Protection System (RPS)Instrumentation," Function 2.b (Average Power Range Monitors Neutron Flux- High (Flow Biased)), Allowable Value of Table 3.3.1.1-1 is reset for single loop operation; and d. LCO 3.3.2.1. "Control Rod Block Instrumentation." Function l.a (Rod Block Monitor-Upscale).
| |
| Allowable Value of Table 3.3.2.1-1 is reset for single loop operation.
| |
| APPLICABILITY:
| |
| MODES 1 and 2.JAFNPP 3.4.1-1 Amendment 274 Recirculation Loops Operating 3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or two A.1 Initiate action to Immediately recirculation loops in exit the Exclusion operation with core Region.flow and THERMAL POWER conditions within the Exclusion Region of the power-to-flow map.B. Requirements of the B.1 Satisfy the 24 hours LCO not met for requirements of the reasons other than LCO.Condition A.C. Required Action and C.1 Be in MODE 3. 12 hours associated Completion Time of Condition A or B not met.OR No recirculation loops in operation.
| |
| JAFNPP 3.4.1-2 Amendment 274 Recirculation Loops Operating 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 ------------------
| |
| NOTE---------------.-----
| |
| Only required to be performed in MODE 1.Verify reactor operating at core flow and 12 hours THERMAL POWER conditions outside the Exclusion Region of the power-to-flow map specified in the COLR.SR 3.4.1.2 --------------------
| |
| NOTE-------------------
| |
| Not required to be performed until 24 hours after both recirculation loops are in operation.
| |
| Verify recirculation loop jet pump flow 24 hours mismatch with both recirculation loops in operation is: a. s 10% of rated core flow when operating at < 70% of rated core flow: and b. s 5% of rated core flow when operating at 2 70% of rated core flow.JAFNPP 3.4.1-3 Amendment 274 Jet Pumps 3.4.2 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.2 Jet Pumps LCO 3.4.2 All jet pumps shall be OPERABLE.APPLICABILITY:
| |
| MODES 1 and 2.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more jet pumps A.1 Be in MODE 3. 12 hours inoperable.
| |
| JAFNPP 3.4.2-1 Amendment 274 Jet Pumps 3.4.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 ------------------
| |
| NOTES-------------------
| |
| : 1. Not required to be performed until 4 hours after associated recirculation loop is in operation.
| |
| : 2. Not required to be performed until 24 hours after > 25Z RTP.............
| |
| ..,.......................
| |
| Verify at least one of the following 24 hours criteria (a or b) is satisfied for each operating recirculation loop: a. Recirculation pump flow to speed ratio differs by 5X from established patterns, and recirculation loop jet pump flow to recirculation pump speed ratio differs by 5% from established patterns.b. Each jet pump diffuser to lower plenum differential pressure differs by & 20%from established patterns.JAFNPP 3.4.2-2 Amendment 274 S/RVs 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.3 Safety/Relief Valves (S/RVs)LCO 3.4.3 APPLICABILITY:
| |
| The safety function of 9 S/RVs shall be OPERABLE.MODES 1. 2. and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Be in MODE 3. 12 hours S/RVs inoperable.
| |
| AND A.2 Be in MODE 4. 36 hours JAFNPP 3.4.3-1 Amendment 274 S/RVs 3.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 Verify the safety function lift setpoint of In accordance the required S/RVs is 1145 i 34.3 psig. with the Following testing, lift settings shall be Inservice within i 1%. Testing Program SR 3.4.3.2 -------------------
| |
| NOTE--------------------
| |
| Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test............................................
| |
| Verify each required S/RV opens when 24 months on a manually actuated.
| |
| STAGGERED TEST BASIS for each valve solenoid JAFNPP 3.4.3-2 Amendment 274 RCS Operational LEAKAGE 3.4.4 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.4 RCS Operational LEAKAGE LCO 3.4.4 RCS operational LEAKAGE shall be limited to: a. No pressure boundary LEAKAGE;b. 5 gpm unidentified LEAKAGE;C. 5 25 gpm total LEAKAGE averaged over the previous 24 hour period: and d. s 2 gpm increase in unidentified LEAKAGE previous 24 hour period in MODE 1.within the APPLICABILITY:
| |
| MODES 1, 2. and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Unidentified LEAKAGE A.1 Reduce LEAKAGE to 4 hours not within limit. within limits.OR Total LEAKAGE not within limit.B. Unidentified LEAKAGE B.1 Reduce unidentified 4 h6urs increase not within LEAKAGE increase to limit. within limits.OR (continued)
| |
| JAFNPP 3.4.4-1 Amendment 274 RCS Operational LEAKAGE 3.4.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued)
| |
| B.2 Verify source of 4 hours unidentified LEAKAGE increase is not service sensitive type 304 or type 316 austenitic stainless steel.C. Required Action and C.1 Be in MODE 3. 12 hours associated Completion Time of Condition A AND or B not met.C.2 Be in MODE 4. 36 hours OR Pressure boundary LEAKAGE exists.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify RCS unidentified and total LEAKAGE 4 hours and unidentified LEAKAGE increase are within limits.JAFNPP 3.4.4-2 Amendment 274 RCS Leakage Detection Instrumentation 3.4.5 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.5 RCS Leakage Detection Instrumentation LCO 3.4.5 The following RCS leakage detection instrumentation shall be OPERABLE: a. Drywell floor drain sump monitoring system;b. One channel of the drywell monitoring system; and c. One channel of the drywell monitoring system.continuous atmospheric particulate continuous atmospheric gaseous APPLICABILITY:
| |
| MODES 1, 2, and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Drywell floor drain sump A.1 Restore drywell floor drain 30 days monitoring system sump monitoring system inoperable.
| |
| to OPERABLE status.B. One drywell continuous B.1 NOTE-------
| |
| atmospheric monitoring Not applicable when both system inoperable.
| |
| drywell continuous atmospheric monitoring systems are inoperable.
| |
| __________________
| |
| Perform SR 3.4.5.1. Once per 8 hours (continued)
| |
| I JAFNPP 3.4.5-1 Amendment 284 RCS Leakage Detection Instrumentation
| |
| | |
| ====3.4.5 ACTIONS====
| |
| (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME C. Both drywell continuous C.1 Analyze grab samples of Once per 12 hours atmospheric monitoring drywell atmosphere.
| |
| systems inoperable.
| |
| AND C.2 Restore one drywell 30 days continuous atmospheric monitoring system to OPERABLE status.D. Required Action and D.1 Be in MODE 3. 12 hours associated Completion Time of Condition A, B, or AND C not met D.2 Be in MODE 4. 36 hours E. All required leakage E.1 Enter LCO 3.0.3. Immediately detection systems inoperable.
| |
| JAFNPP 3.4.5-2 Amendment 284 RCS Leakage Detection Instrumentation
| |
| | |
| ====3.4.5 SURVEILLANCE====
| |
| | |
| REQUIREMENTS
| |
| -------------------------------------
| |
| NOTE-----.-.
| |
| When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the other required leakage detection instrumentation is OPERABLE.SURVEILLANCE FREQUENCY SR 3.4.5.1 Perform a CHANNEL CHECK of drywell 12 hours continuous atmospheric monitoring systems.SR 3.4.5.2 Perform a CHANNEL FUNCTIONAL TEST of 31 days required leakage detection instrumentation.
| |
| SR 3.4.5.3 Perform a CHANNEL CALIBRATION of required 92 days leakage detection instrumentation.
| |
| JAFNPP 3.4.5-3 Amendment 274 RCS Specific Activity 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.6 RCS Specific Activity LCO 3.4.6 APPLICABILITY:
| |
| The specific activity of the reactor coolant shall be limited to DOSE EQUIVALENT 1-131 specific activity 0.2 pCi/gm.MODE 1, MODES 2 and 3 with any main steam line not isolated.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reactor coolant specific ----- NOTE----------
| |
| activity > 0.2 pCi/gm and LCO 3.0.4.c is applicable.
| |
| 2.0 pCi/gm DOSE ------------------------
| |
| EQUIVALENT 1-131.A.1 Determine DOSE Once per 4 hours EQUIVALENT 1-131.AND A.2 Restore DOSE 48 hours EQUIVALENT 1-131 to within limits.B. Required Action and B.1 Determine DOSE Once per 4 hours associated Completion EQUIVALENT 1-131.Time of Condition A not met. AND OR B.2.1 isolate all main steam 12 hours lines.Reactor coolant specific activity > 2.0 pCi/gm OR DOSE EQUIVALENT 1-131.(continued)
| |
| I JAFNPP 3.4.6-1 Amendment 284
| |
| --RCS Specific Activity 3.4.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued)
| |
| B.2.2.1 Be in MODE 3. 12 hours AND B.2.2.2 Be in MODE 4. 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 ------------------
| |
| NOTE--------------------
| |
| Only required to be performed in MODE 1.Verify reactor coolant DOSE EQUIVALENT 7 days I-131 specific activity is s 0.2 pCi/gm.JAFNPP 3.4.6-2 Amendment 274 RHR Shutdown Cooling System-Hot Shutdown 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System-Hot Shutdown LCO 3.4.7 Two RHR shutdown cooling subsystems shall be OPERABLE.----------
| |
| --- ------- -NOTE -----------------------
| |
| One RHR shutdown cooling subsystem may be inoperable for up to 2 hours for the performance of Surveillances.
| |
| __________________________________._______________-
| |
| APPLICABILITY:
| |
| MODE 3, with reactor steam dome pressure less than the RHR cut In permissive pressure.ACTIONS-----------------------------
| |
| NOTE -------------------------------
| |
| Separate Condition entry is allowed for each RHR shutdown cooling subsystem.
| |
| _________________________________________________________________
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. One or two RHR A.1 Initiate action to restore Immediately shutdown cooling RHR shutdown cooling subsystems inoperable.
| |
| subsystem(s) to OPERABLE status.AND A.2 Verify an alternate
| |
| +/- hour method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem.
| |
| AND A.3 Be in MODE 4. 24 hours JAFNPP 3.4.7-1 Amendment 284 RHR Shutdown Cooling System -Hot Shutdown 3.4.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCYSR 3.4.7.1-----------------
| |
| NOTE--..................
| |
| Not required to be met until 2 hours after reactor steam dome pressure is less than the RHR cut in permissive pressure.Verify each required RHR shutdown cooling subsystem manual, power operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, is in the correct position, or can be aligned to the correct position.31 days JAFNPP 3.4.7-2 Amendment 274 RHR Shutdown Cooling System -Cold Shutdown 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System- Cold Shutdown LCO 3.4.8 Two RHR shutdown cooling subsystems shall be OPERABLE........................
| |
| -----NOTE--.............
| |
| .............
| |
| One RHR shutdown cooling subsystem may be inoperable for up to 2 hours for the performance of Surveillances.
| |
| .............................
| |
| ..........................................................................................
| |
| ..........
| |
| APPLICABILITY:
| |
| MODE 4.ACTIONS-------------------------------------
| |
| NOTE-------------------------------------
| |
| Separate Condition entry is allowed for each shutdown cooling subsystem.
| |
| ..... ......................
| |
| .... ..........
| |
| ...............................................
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. One or two RHR A.1 Verify an alternate 1 hour shutdown cooling method of decay heat subsystems inoperable.
| |
| removal is available AND for each inoperable RHR shutdown cooling Once per subsystem.
| |
| 24 hours thereafter JAFNPP 3.4.8-1 Amendment 274 RHR Shutdown Cooling System -Cold Shutdown 3.4.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify each RHR shutdown cooling subsystem 31 days manual, power operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position.is in the correct position, or can be aligned to the correct position.JAFNPP 3.4.8-2 Amendment 274
| |
| --RCS P/T Limits 3.4.9 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.9 RCS Pressure and Temperature (P/T) Limits LCO 3.4.9 APPLICABILITY:
| |
| RCS pressure, RCS temperature, RCS heatup and cooldown rates,'and the recirculation pump starting temperature requirements shall be maintained within limits.At all times.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ---------NOTE---------
| |
| A.1 Restore parameter(s) 30 minutes Required Action A.2 to within limits.shall be completed if this Condition is AND entered.......................
| |
| A.2 Determine RCS is 72 hours acceptable for Requirements of the continued operation.
| |
| LCO not met in MODE 1.2, or 3.B. Required Action and B.1 Be in MODE 3. 12 hours associated Completion Time of Condition A AND not met.B.2 Be in MODE 4. 36 hours (continued)
| |
| JAFNPP 3.4.9-1 Amendment 274
| |
| ---RCS P/T Limits 3.4.9 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME C. ---- NOTE---------
| |
| C.1 Initiate action to Immediately Required Action C.2 restore parameter(s) shall be completed if to within limits.this Condition is entered. AND C.2 Determine RCS is Prior to Requirements of the acceptable for entering MODE 2 LCO not met in other operation.
| |
| or 3 than MODES 1. 2.and 3.JAFNPP 3.4.9-2 Amendment 274 RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 -------------------
| |
| NOTE-------------------
| |
| Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.Verify: 30 minutes a. RCS pressure and RCS temperature are within the limits specified in Figure 3.4.9-1 or Figure 3.4.9-2. as applicable; and b. RCS temperature change averaged over a one hour period is: 1. s 100OF when the RCS pressure and RCS temperature are on or to the right of curve C of Figure 3.4.9-1 or Figure 3.4.9-2, as applicable.
| |
| during inservice leak and hydrostatic testing;2. 20 0 F when the RCS pressure and RCS temperature are to the left of curve C of Figure 3.4.9-1 or Figure 3.4.9-2. as applicable, during inservice leak and hydrostatic testing: and 3. s 100OF during other heatup and cooldown operations.(continued)
| |
| JAFNPP 3.4.9-3 Amendment 274 RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.4.9.2 Verify RCS pressure and RCS temperature are Once within within the criticality limits specified in 15 minutes Figure 3.4.9-1 or Figure 3.4.9-2. as prior to applicable.
| |
| control rod withdrawal for the purpose of achieving criticality SR 3.4.9.3 ---------NOTES-------------------
| |
| : 1. Only required to be met in MODES 1, 2.3. and 4 during recirculation pump startup.2. Not required to be performed if SR 3.4.9.4 is satisfied.
| |
| ........................................
| |
| Verify the difference between the bottom Once within head coolant temperature and the reactor 15 minutes pressure vessel (RPV) coolant temperature prior to each is 145 0 F. startup of a recircul ation pump SR 3.4.9.4 ------------------
| |
| NOTES--------------------
| |
| : 1. Only required to be met in MODES 1. 2.3. and 4 during recirculation pump startup.2. Not required to be met if SR 3.4.9.3 is satisfied.
| |
| ...................
| |
| .........................................
| |
| ....Verify the active recirculation pump flow Once within exceeds 40X of rated pump flow or the 15 minutes active recirculation pump has been prior to each operating below 40% rated flow for a period startup of a no longer than 30 minutes. recirculation pump (continued)
| |
| JAFNPP 3.4.9-4 Amendment 274 RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)
| |
| T SURVEILLANCE FREQUENCYSR 3.4.9.5---.-------------
| |
| NOTE-------------------
| |
| Only required to be met in MODES 1. 2, 3, and 4 during recirculation pump startup....- -..- --......-...-
| |
| -...- --....-...
| |
| ----.. ... .....- ----....- ------. ...Verify the difference between the reactor coolant temperature in the recirculation loop to be started and the RPV coolant temperature is s 50 0 F.Once within 15 minutes prior to each startup of a recirculation pump.1.SR 3.4.9.6 -------------------
| |
| NOTE--------------------
| |
| Only required to be performed when tensioning the reactor vessel head bolting studs.Verify, when the reactor vessel head bolting studs are under tension, reactor vessel flange and head flange temperatures are 2 90 0 F.30 minutes SR 3.4.9.7 -------------------
| |
| NOTE--------------------
| |
| Not required to be performed until 30 minutes after RCS temperature
| |
| & 1007F with any reactor vessel head bolting stud tensioned.
| |
| Verify, when the reactor vessel head bolting studs are under tension, reactor vessel flange and head flange temperatures are 2 90 0 F.30 minutes (continued)
| |
| JAFNPP 3.4.9-5 Amendment 274 RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.4.9.8-------------------
| |
| NOTE----------------.--
| |
| Not required to be performed until 12 hours after RCS temperature s 120OF with any reactor vessel head bolting stud tensioned.
| |
| .............
| |
| .................................
| |
| ..............
| |
| Verify, when the reactor vessel head bolting studs are under tension. reactor vessel flange and head flange temperatures are 2 90'F.12 hours JAFNPP 3.4.9-6 Amendment 274 RCS P/T Limits 3.4.9 1600 1400 1200 0 0.'U S 0 7, 1000 I-0 In1 0 S , 800 U Is E 600 n 40 0 0.400 T I I i i L i I i I I VALID TO 24 EFPY A -System Hydrotest Limit with Fuel in Vessel B -Non-Nuclear Heating Umit C -Nuclear (Core Critical)
| |
| Limit As, -System Hydrotest Umit with Fuel in Vessel -Bottom Head ANB -System Hydrotest Limit with Fuel in Vessel -Non-Bedtline BBH -Non-Nuclear Heating Limit Bottom Head I l .*I.ASH ANB BBS A B CI I a i-/H.I.I /i// / <,Vj L________ __ _ I B L;L LI NE ART =95'F I a1/ I/I S/L~ I I/' 'I /NON-BELTUNE
| |
| /RT 30 OF!l -_ ~~~~~~120!)
| |
| .31 95 2S_ _ _ _ _ _ _ _ _ __/ J -.S, I ! ,_ _ I _ _ _ _ _ _ _ _200 0 0 50 100 150 200 250 300 350 Minimum Reactor Vessel Metal Temperature
| |
| (°F)Figure 3.4.9-1 (page 1 of 1)Reactor Coolant System Pressure and Temperature Limits through 24 Effective Full Power Years (EFPY)JAFNPP 3.4.9-7 Amendment 274 RCS P/T Limits 3.4.9 1600 1400 1200 go U)-e I-lua a c Ec 6000 4 800 600-J S 0.400 200 0 0 50 100 150 200 250 300 350 Minimum Reactor Vessel Metal Temperature (OF)Figure 3.4.9-2 (page 1 of 1)Reactor Coolant System Pressure and Temperature Limits through 32 Effective Full Power Years (EFPY)JAFNPP 3.4.9-8 Amendment 274 ECCS-Operating 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1 ECCS-Operating LCO 3.5.1 APPLICABILITY:
| |
| ACTIONS Each ECOS injection/spray subsystem and the Automatic Depressurization System (ADS) function of six safety/relief valves shall be OPERABLE.MODE 1, MODES 2 and 3, except high pressure coolant injection (HPCI) and ADS valves are not required to be OPERABLE with reactor steam dome pressure 150 psig.----------
| |
| is-not-applicabNOTE to- -----LCO 3.O.4.b is not applicable to HPOI.CONDITION REQUIRED ACTION COMPLETION TIME A. One low pressure ECCS A.1 Restore low pressure 7 days injection/spray ECCS injection/spray subsystem inoperable.
| |
| subsystem(s) to OR OPERABLE status.One low pressure coolant injection (LPCI) pump in both LPCI subsystems inoperable.
| |
| B. Required Action and B.1 Be in MODE 3. 12 hours associated Completion Time of Condition A not AND met.B.2 Be in MODE 4. 36 hours (continued)
| |
| JAFNPP 3.5.1-1 Amendment 284 ECCS -Operating 3.5.1 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME C. HPCI System C.1 Verify by Immediately inoperable.
| |
| administrative means RCIC System is OPERABLE.AND C.2 Restore HPCI System 14 days to OPERABLE status.D. HPCI System D.1 Restore HPCI System 72 hours inoperable.
| |
| to OPERABLE status.AND OR Condition A entered. D.2 Restore low pressure 72 hours ECCS injection/spray subsystem(s) to OPERABLE status.E. One required ADS valve E.1 Restore required ADS 14 days inoperable.
| |
| valve to OPERABLE status.F. One required ADS valve F.1 Restore required ADS 72 hours inoperable.
| |
| valve to OPERABLE status.AND OR Condition A entered.F.2 Restore low pressure 72 hours ECCS injection/spray subsystem(s) to OPERABLE status.(continued)
| |
| JAFNPP 3.5.1-2 Amendment 274 ECCS -Operating 3.5.1 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME G. Required Action and G.1 Be in MODE 3. 12 hours associated Completion Time of Condition C. AND D. E, or F not met.G.2 Reduce reactor steam 36 hours OR dome pressure to_ s 150 psig.Two or more required ADS valves inoperable.
| |
| H. Two or more low H.1 Enter LCO 3.0.3. Immediately pressure ECCS injection/spray subsystems inoperable for reasons other than Condition A.OR HPCI System and one or more required ADS valves inoperable.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each ECCS injection/spray 31 days subsystem, the piping is filled with water from the pump discharge valve to the injection valve.(continued)
| |
| JAFNPP 3.5.1-3 Amendment 274 ECCS -Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.5.1.2 -------------
| |
| NOTE--------------------
| |
| Low pressure coolant injection (LPCI)subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam dome pressure less than the Residual Heat Removal (RHR) cut in permissive pressure in MODE 3, if capable of being manually realigned and not otherwise inoperable.
| |
| ...........................................
| |
| Verify each ECCS injection/spray subsystem manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.31 days SR 3.5.1.3 Verify ADS pneumatic supply header pressure 31 days is 2 95 psig.SR 3.5.1.4 Verify the RHR System cross tie valves are 31 days closed and power is removed from the electrical valve operator.SR 3.5.1.5 Cycle open and closed each LPCI motor 31 days operated valve independent power supply battery charger AC input breaker and verify each LPCI inverter output voltage is 2 576 V and s 624 V while supplying the respective bus.(continued)
| |
| JAFNPP 3.5.1-4 Amendment 274 ECCS -Operating
| |
| | |
| ====3.5.1 SURVEILLANCE====
| |
| | |
| REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY+SR 3.5.1.6 .- -----NOTE--------------------
| |
| Not required to be performed if performed within the previous 31 days.Verify each recirculation pump discharge valve cycles through one complete cycle of full travel or is de-energized in the closed position.Once each startup prior to exceeding 25% RTP SR 3.5.1.7 Verify the following ECCS pumps develop the specified flow rate against a system head corresponding to the specified reactor pressure above primary containment pressure.In accordance with the Inservice Testing Program SYSTEM FLOW RATE NO.OF PUMPS 1 1 SYSTEM HEAD CORRESPONDING TO A REACTOR PRESSURE ABOVE PRIMARY CONTAINMENT PRESSURE OF 2 113 psi 2 20 psi Core Spray LPCI 2 4265 gpm 2 7700 gpm SR 3.5.1.8 ------------------
| |
| NOTE--------------------
| |
| Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test.Verify, with reactor pressure s 1040 psig and 2 970 psig. the HPCI pump can develop a flow rate 2 3400 gpm against a system head corresponding to reactor pressure.In accordance with the Inservice Testing Program (continued)
| |
| JAFNPP 3.5.1-5 Amendment 274
| |
| ---ECCS -Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.5.1.9 -------------------
| |
| NOTE--------------------
| |
| Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test.Verify, with reactor pressure 165 psig, the HPCI pump can develop a flow rate 2 3400 gpm against a system head corresponding to reactor pressure.24 months SR 3.5.1.10-------------------
| |
| NOTES-------------------
| |
| : 1. For the HPCI System, not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test.2. Vessel injection/spray may be excluded.Verify each ECCS injection/spray subsystem actuates on an actual or simulated automatic initiation signal.24 months SR 3.5.1.11 -------------------
| |
| NOTE--------------------
| |
| Valve actuation may be excluded.Verify the ADS actuates on an actual or 24 months simulated automatic initiation signal.SR 3.5.1.12 Verify each LPCI motor operated valve 24 months independent power supply inverter capacity is adequate to supply and maintain in OPERABLE status the required emergency loads for the design duty cycle.(continued)
| |
| JAFNPP 3.5.1-6 Amendment 274 ECCS -Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.5.1.13 -------------------
| |
| NOTE--------------------
| |
| Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test.Verify each required ADS valve opens when manually actuated.24 months on a STAGGERED TEST BASIS for each valve solenoid JAFNPP 3.5.1-7 Amendment 274
| |
| -ECCS -Shutdown 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.2 ECCS -Shutdown LCO 3.5.2 APPLICABILITY:
| |
| Two low pressure ECCS injection/spray subsystems shall be OPERABLE.MODE 4, MODE 5, except with the spent fuel storage pool gates removed and water level 2 22 ft 2 inches over the top of the reactor pressure vessel flange.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required low A.1 Restore required low 4 hours pressure ECCS pressure ECCS injection/spray injection/spray subsystem inoperable.
| |
| subsystem to OPERABLE status.B. Required Action and B.1 Initiate action to Immediately associated Completion suspend operations Time of Condition A with a potential for not met. draining the reactor vessel (OPDRVs).C. Two required low C.1 Initiate action to Immediately pressure ECCS suspend OPDRVs.injection/spray subsystems inoperable.
| |
| AND C.2 Restore one required 4 hours low pressure ECCS injection/spray subsystem to OPERABLE status.(continued)
| |
| JAFNPP 3.5.2-1 Amendment 274 ECCS -Shutdown 3.5.2 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action C.2 D.1 Initiate action to Immediately and associated restore secondary Completion Time not containment to met. OPERABLE status.AND D.2 Initiate action to Immediately restore one standby gas treatment subsystem to OPERABLE status.AND D.3 Initiate action to Immediately restore isolation capability in each required secondary containment penetration flow path not isolated.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify, for each required low pressure 12 hours coolant injection (LPCI) subsystem, the suppression pool water level is 2 10.33 ft.(continued)
| |
| JAFNPP 3.5.2-2 Amendment 274 ECCS -Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.5.2.2 Verify, for each required core spray (CS) 12 hours subsystem, the: a. Suppression pool water level is 2 10.33 ft; or b. -------------
| |
| NOTE----------------
| |
| Only one required CS subsystem may take credit for this option during OPDRVs.The water level in each condensate storage tank is 2 324 inches.SR 3.5.2.3 Verify, for each required ECCS injection/
| |
| 31 days spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve.SR 3.5.2.4 -------------------
| |
| NOTE------------------
| |
| One LPCI subsystem may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable.
| |
| ....... ..................
| |
| .........
| |
| ... .Verify each required ECCS injection/spray 31 days subsystem manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.(continued)
| |
| JAFNPP 3.5.2-3 Amendment 274
| |
| --ECCS -Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued)
| |
| -SURVEILLANCE FREQUENCY SR 3.5.2.5 Verify each required ECCS pump develops the specified flow rate against a system head corresponding to the specified reactor pressure above primary containment pressure.In accordance with the Inservice Testing Program SYSTEM FLOW RATE CS 2 4265 gpm LPCI 2 7700 gpm NO.OF PUMPS 1 1 SYSTEM HEAD CORRESPONDING TO A REACTOR PRESSURE ABOVE PRIMARY CONTAINMENT PRESSURE OF 2 113 psi 2 20 psi SR 3.5.2.6 -------------------
| |
| NOTE ------------------
| |
| Vessel injection/spray may be excluded.................................
| |
| .. ................................................................
| |
| Verify each required ECCS injection/spray 24 months subsystem actuates on an actual or simulated automatic initiation signal.JAFNPP 3.5.2-4 Amendment 274 RCIC System 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.3 RCIC System LCO 3.5.3 The RCIC System shall be OPERABLE.APPLICABILITY:
| |
| MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig.ACTIONS-----------------------------
| |
| NOTE -------------------------------
| |
| LCO 3.0.4.b is not applicable to RCIC.CONDITION REQUIRED ACTION COMPLETION TIME A. RCIC System inoperable.
| |
| A.1 Verify by administrative Immediately means High Pressure Coolant Injection System is OPERABLE.AND A.2 Restore RCIC System to 14 days OPERABLE status.B. Required Action and B.1 Be in MODE 3. 12 hours associated Completion Time not met. AND B.2 Reduce reactor steam 36 hours dome pressure to S 150 psig.JAFNPP 3.5.3-1 Amendment 284
| |
| --RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the RCIC System piping is filled 31 days with water from the pump discharge valve to the injection valve.SR 3.5.3.2 Verify each RCIC System manual, power 31 days operated.
| |
| and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.SR 3.5.3.3 -------------------
| |
| NOTE--------------------
| |
| Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test.Verify, with reactor pressure s 1040 psig 92 days and 2 970 psig, the RCIC pump can develop a flow rate 2 400 gpm against a system head corresponding to reactor pressure.SR 3.5.3.4 ----------------
| |
| NOTE-----------------------
| |
| Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test.Verify, with reactor pressure 165 psig, 24 months the RCIC pump can develop a flow rate 2 400 gpm against a system head corresponding to reactor pressure.(continued)
| |
| JAFNPP 3.5.3-2 Amendment 274
| |
| ---RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.5.3.5 -----------
| |
| NOTES-------------------
| |
| : 1. Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test.2. Vessel injection may be excluded............................................
| |
| Verify the RCIC System actuates on an actual or simulated automatic initiation signal.24 months JAFNPP 3.5.3-3 Amendment 274 Primary Containment 3.6.1.1 3.6 CONTAINMENT SYSTEMS 3.6.1.1 Primary Containment LCO 3.6.1.1 APPLICABILITY:
| |
| Primary containment shall be OPERABLE.MODES 1, 2, and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Primary containment A.1 Restore primary 1 hour inoperable.
| |
| containment to OPERABLE status.B. Required Action and B.1 Be in MODE 3. 12 hours associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours JAFNPP 3.6.1.1-1 Amendment 274 Primary Containment 3.6.1.1 SURVEILLANCE REQUIREMENTS
| |
| __.SURVEILLANCE FREQUENCY SR 3.6.1.1.1 Perform required visual examinations and In accordance leakage rate testing except for primary with the containment air lock testing, in Primary accordance with the Primary Containment Containment Leakage Rate Testing Program. Leakage Rate Testing Program SR 3.6.1.1.2 Verify suppression chamber pressure 24 months increase is s 0.25 in. water gauge per minute over a 10 minute period with a AND drywell to suppression chamber differential pressure of 2 1 psi. -.... NOTE- ----Only required after two consecutive tests fail and continues until two consecutive tests pass 12 months JAFNPP 3.6.1.1-2 Amendment 274 Primary Containment Air Locks 3.6.1.2 3.6 CONTAINMENT SYSTEMS 3.6.1.2 Primary Containment Air Locks LCO 3.6.1.2 APPLICABILITY:
| |
| Two primary containment air locks shall be OPERABLE.MODES 1. 2, and 3.ACTIONS*-...--------.-----.--.-.-.-..----...NOTES--..................................
| |
| : 1. Entry and exit is permissible to perform repairs of the affected air lock components.
| |
| : 2. Separate Condition entry is allowed for each air lock.3. Enter applicable Conditions and Required Actions of LCO 3.6.1.1. "Primary Containment," when air lock leakage results in exceeding overall containment leakage rate acceptance criteria.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more primary ------------
| |
| NOTES------------
| |
| containment air locks 1. Required Actions A.1.with one primary A.2. and A.3 are not containment air lock applicable if both doors door inoperable.
| |
| in the same air lock are inoperable and Condition C is entered.2. Entry and exit is permissible for 7 days under administrative controls.A.1 Verify the OPERABLE 1 hour door is closed in the affected air lock.AND (continued)
| |
| JAFNPP 3.6.1.2-1 Amendment 274
| |
| ---Primary Containment Air Locks 3.6.1.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
| |
| A.2 Lock the OPERABLE 24 hours door closed in the affected air lock.AND A.3 --------NOTE---------
| |
| Air lock doors in high radiation areas or areas with limited access due to inerting may be verified locked closed by administrative means.Verify the OPERABLE Once per 31 days door is locked closed in the affected air lock.B. One or more primary ------------
| |
| NOTES------------
| |
| containment air locks 1. Required Actions B.1, with primary B.2, and B.3 are not containment air lock applicable if both doors interlock mechanism in the same air lock are inoperable.
| |
| inoperable and Condition C is entered.2. Entry into and exit from primary containment is permissible under the control of a dedicated individual.
| |
| B.1 Verify an OPERABLE 1 hour door is closed in the affected air lock.AND (continued)
| |
| JAFNPP 3.6.1.2-2 Amendment 274 Primary Containment Air Locks 3.6.1.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued)
| |
| B.2 Lock an OPERABLE door 24 hours closed in the affected air lock.AND B.3 -NOTE-........
| |
| Air lock doors in high radiation areas or areas with limited access due to inerting may be verified locked closed by administrative means.Verify an OPERABLE Once per 31 days door is locked closed in the affected air lock.C. One or more primary C.1 Initiate action to Immediately containment air locks evaluate primary inoperable for reasons containment overall other than Condition A leakage rate per or B. LCO 3.6.1.1, using current air lock test results.AND C.2 Verify a door is 1 hour closed in the affected air lock.AND C.3 Restore air lock to 24 hours OPERABLE status.(continued)
| |
| JAFNPP 3.6.1.2-3 Amendment 274 Primary Containment Air Locks 3.6.1.2 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 12 hours associated Completion Time not met. AND D.2 Be in MODE 4. 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.2.1
| |
| ------------
| |
| NOTES----------------
| |
| : 1. An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.2. Results shall be evaluated against criteria applicable to SR 3.6.1.1.1.
| |
| .... ... ... .... .. ..... .... .Perform required primary containment air In accordance lock leakage rate testing in accordance with the with the Primary Containment Leakage Rate Primary Testing Program. Containment Leakage Rate Testing Program SR 3.6.1.2.2 Verify only one door in the primary 24 months containment air lock can be opened at a time.JAFNPP 3.6.1.2-4 Amendment 274 PCIVs 3.6.1.3 3.6 CONTAINMENT SYSTEMS 3.6.1.3 Primary Containment Isolation Valves (PCIVs)LCO 3.6.1.3 APPLICABILITY:
| |
| Each PCIV. except reactor building-to-suppression chamber vacuum breakers, shall be OPERABLE.MODES 1, 2. and 3, When associated instrumentation is required to be OPERABLE per LCO 3.3.6.1, "Primary Containment Isolation Instrumentation." JAFNPP 3.6.1.3-1 Amendment 274 PCIVs 3.6.1.3 ACTIONS..................................
| |
| NOTES ....1. Penetration flow paths may be unisolated intermittently under administrative controls.2. Separate Condition entry is allowed for each penetration flow path.3. Enter applicable Conditions and Required Actions for systems made inoperable by PCIVs.4. Enter applicable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment," when PCIV leakage results in exceeding overall containment leakage rate acceptance criteria... .. .. ... .. ... .. ... .. .. ... .. ... .. ... .. .... .. .....CONDITION REQUIRED ACTION COMPLETION TIME A. ---------NOTE--------
| |
| A.1 Isolate the affected 4 hours except Only applicable to penetration flow path for main steam penetration flow paths by use of at least line with two or more one closed and PCIVs. de-activated AND.. ..... automatic valve, closed manual valve, 8 hours for main One or more blind flange, or steam line penetration flow paths check valve with flow with one PCIV through the valve inoperable for reasons secured.other than Conditions D and E. AND (continued)
| |
| JAFNPP 3.6.1.3-2 Amendment 274 PCIVs 3.6.1.3 ACTIONS CONDITION IREQUIRED ACTION I COMPLETION TIME A. (continued)
| |
| A.2------NOTES--------
| |
| : 1. Isolation devices in high radiation areas may be verified by use of administrative means.2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.Verify the affected penetration flow path is isolated.Once per 31 days for isolation devices outside primary containment AND Prior to entering MODE 2 or 3 from MODE 4. if primary containment was de-inerted while in MODE 4. if not performed within the previous 92 days, for isolation devices inside primary containment (continued)
| |
| JAFNPP 3.6.1.3-3 Amendment 274 PCIVs 3.6.1.3 ACTIONS (continued)
| |
| .CONDITION REQUIRED ACTION COMPLETION TIME B. -NOTE---------
| |
| B.1 Isolate the affected 1 hour Only applicable to penetration flow path penetration flow paths by use of at least with two or more one closed and PCIVs. de-activated
| |
| ...........
| |
| ....... automatic valve, closed manual valve, One or more or blind flange.penetration flow paths with two or more PCIVs inoperable for reasons other than Conditions D and E.C. ---------NOTE---------
| |
| C.1 Isolate the affected 4 hours except Only applicable to penetration flow path for excess flow penetration flow paths by use of at least check valves with only one PCIV. one closed and (EFCVs) and.... .... de-activated penetrations automatic valve, with a closed One or more closed manual valve, system penetration flow paths or blind flange.with one PCIV AND inoperable for reasons other than Conditions 72 hours for D and E. EFCVs and penetrations with a closed system AND (continued)
| |
| JAFNPP 3.6.1.3-4 Amendment 274 PCIVs 3.6.1.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued)
| |
| C.2 --NOTES--------
| |
| : 1. Isolation devices in high radiation areas may be verified by use of administrative means.2. Isolation devices that are locked.sealed, or otherwise secured may be verified by use of administrative means.Verify the affected Once per 31 days penetration flow path is isolated.D. One or more D.1 Restore leakage rate 8 hours penetration flow paths to within limit.with one or more MSIVs not within leakage rate limit.E. One or more E.1 Restore leakage rate 72 hours penetration flow paths to within limit.with LPCI System or CS System testable check valve leakage limit not met.(continued)
| |
| JAFNPP 3.6.1.3-5 Amendment 274 PCIVs 3.6.1.3 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action and F.1 Be in MODE 3. 12 hours associated Completion Time of Condition A, AND B. C. D. or E not met in MODE 1. 2, or 3. F.2 Be in MODE 4. 36 hours G. Required Action and G.1 Initiate action to Immediately associated Completion suspend operations Time of Condition A or with a potential for B not met for PCIV(s) draining the reactor required to be vessel.OPERABLE during MODE 4 or 5. OR G.2 Initiate action to Immediately restore valve(s) to OPERABLE status.JAFNPP 3.6.1.3-6 Amendment 274 PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 4 SR 3.6.1.3.1-----------------
| |
| NOTE-------------------
| |
| Not required to be met when the 20 inch and 24 inch primary containment vent and purge valves are open for inerting, de-inerting.
| |
| pressure control, ALARA or air quality considerations for personnel entry, or Surveillances that require the valves to be open, provided the full-flow line to Standby Gas Treatment (SGT)System is closed and one or more SGT System reactor building suction valves are open.Verify each 20 inch and 24 inch primary containment vent and purge valve is closed.l 31 days SR 3.6.1.3.2-..---------------
| |
| NOTES--................
| |
| : 1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.2. Not required to be met for PCIVs that are open under administrative controls.Verify each primary containment isolation manual valve and blind flange that is located outside primary containment and not locked, sealed or otherwise secured and is required to be closed during accident conditions is closed.31 days (continued)
| |
| JAFNPP 3.6.1.3-7 Amendment 274 PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.6.1.3.3------------------
| |
| NOTES.-------.--------
| |
| : 1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.2. Not required to be met for PCIVs that are open under administrative controls.Verify each primary containment manual isolation valve and blind flange that is located inside primary containment and not locked. sealed or otherwise secured and is required to be closed during accident conditions is closed.Prior to entering MODE 2 or 3 from MODE 4 if primary containment was de-inerted while in MODE 4. if not performed within the previous 92 days SR 3.6.1.3.4 Verify continuity of the traversing 31 days incore probe (TIP) shear isolation valve explosive charge.SR 3.6.1.3.5 Verify the isolation time of each power In accordance operated, automatic PCIV. except for with the MSIVs. is within limits. Inservice Testing Program SR 3.6.1.3.6 Verify the isolation time of each MSIV is In accordance 2 3 seconds and g 5 seconds. with the Inservice Testing Program (continued)
| |
| JAFNPP 3.6.1.3-8 Amendment 274 PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.6.1.3.7 Verify each automatic PCIV actuates to 24 months the isolation position on an actual or simulated isolation signal.SR 3.6.1.3.8 Verify each reactor instrumentation line In accordance EFCV actuates to the isolation position with the on a simulated instrument line break. Inservice Testing Program SR 3.6.1.3.9 Remove and test the explosive squib from 24 months on a each shear isolation valve of the TIP STAGGERED TEST System. BASIS SR 3.6.1.3.10 Verify combined main steam line leakage In accordance rate is 46 scfh when tested at 2 25 with the psig. Primary Containment Leakage Rate Testing Program SR 3.6.1.3.11 Verify the leakage rate of each air In accordance operated testable check valve associated with the with the LPCI and CS Systems vessel Primary injection penetrations is within limits. Containment Leakage Rate Testing Program I JAFNPP 3.6.1.3-9 Amendment 275 AUG 1 3 "W2 Drywell Pressure 3.6.1.4 3.6 CONTAINMENT SYSTEMS 3.6.1.4 Drywell Pressure LCO 3.6.1.4 APPLICABILITY:
| |
| Drywell pressure shall be s 1.95 psig.MODES 1. 2, and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Drywell pressure not A.1 Restore drywell 1 hour within limit. pressure to within lmit.B. Required Action and B.1 Be in MODE 3. 12 hours associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.4.1 Verify drywell pressure is within limit. 12 hours JAFNPP 3.6.1.4-1 Amendment 274
| |
| -Drywell Air Temperature 3.6.1.5 3.6 CONTAINMENT SYSTEMS 3.6.1.5 Drywell Air Temperature LCO 3.6.1.5 APPLICABILITY:
| |
| Drywell average air temperature shall be 135 0 F.MODES 1, 2, and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Drywell average air A.1 Restore drywell 8 hours temperature not within average air limit. temperature to within limit.B. Required Action and B.1 Be in MODE 3. 12 hours associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.5.1 Verify drywell average air temperature is 24 hours within limit.JAFNPP 3.6.1.5-1 Amendment 274 Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.6 3.6 CONTAINMENT SYSTEMS 3.6.1.6 Reactor Building-to-Suppression Chamber Vacuum Breakers LCO 3.6.1.6 APPLICABILITY:
| |
| Each reactor building-to-suppression chamber vacuum breaker shall be OPERABLE.MODES 1. 2. and 3.ACTIONS Separate Condition entry is allowed for each line................................................... ..........CONDITION REQUIRED ACTION COMPLETION TIME A. One or more lines with A.1 Close the open vacuum 72 hours one reactor building-breaker.to-suppression chamber vacuum breaker not closed.B. One or more lines with B.1 Close one open vacuum 1 hour two reactor building-breaker.to-suppression chamber vacuum breakers not closed.C. One line with one or C.1 Restore the vacuum 72 hours more reactor building-breaker(s) to to-suppression chamber OPERABLE status.vacuum breakers inoperable for opening.(continued)
| |
| JAFNPP 3.6.1.6-1 Amendment 274 Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.6 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME D. Two lines with one or D.1 Restore all vacuum 1 hour more reactor building-breakers in one line to-suppression chamber to OPERABLE status.vacuum breakers inoperable for opening.E. Required Action and E.1 Be in MODE 3. 12 hours Associated Completion Time not met. AND E.2 Be in MODE 4. 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.6.1
| |
| ------ ---- -NOTES--------------
| |
| : 1. Not required to be met for vacuum breakers that are open during Surveillances.
| |
| : 2. Not required to be met for vacuum breakers open when performing their intended function..........................................
| |
| Verify each vacuum breaker is closed. 14 days SR 3.6.1.6.2 Perform a functional test of each vacuum In accordance breaker. with the Inservice Testing Program (continued)
| |
| JAFNPP 3.6.1.6-2 Amendment 274 Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.6 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.6.1.6.3 Perform a CHANNEL CALIBRATION of each air 92 days operated vacuum breaker differential pressure instrument channel and verify the setpoint is s 0.5 psid.SR 3.6.1.6.4 Verify the opening setpoint of each self 24 months actuating vacuum breaker is s 0.5 psid.JAFNPP 3.6.1.6-3 Amendment 274 Suppression Chamber-to-Drywell Vacuum Breakers 3.6.1.7 3.6 CONTAINMENT SYSTEMS 3.6.1.7 Suppression Chamber-to-Drywell Vacuum Breakers LCO 3.6.1.7 APPLICABILITY:
| |
| Each suppression chamber-to-drywell vacuum breaker shall be OPERABLE.MODES 1, 2, and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One suppression A.1 Restore the vacuum 72 hours chamber-to-drywell breaker to OPERABLE vacuum breaker status.inoperable for opening.B. One suppression B.1 Close the open vacuum 2 hours chamber-to-drywell breaker.vacuum breaker not closed.C. Required Action and C.1 Be in MODE 3. 12 hours associated Completion Time not met. AND C.2 Be in MODE 4. 36 hours JAFNPP 3.6.1.7-1 Amendment 274 Suppression Chamber-to-Drywell Vacuum Breakers 3.6.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.7.1-----------------
| |
| NOTES------------------
| |
| : 1. Not required to be met for vacuum breakers that are open during Surveillances.
| |
| : 2. Not required to be breakers open when intended function.met for vacuum performing their Verify each vacuum breaker is closed.14 days SR 3.6.1.7.2 Perform a functional test of each vacuum In accordance breaker. with the Inservice Testing Program SR 3.6.1.7.3 Verify the opening setpoint of each 24 months vacuum breaker is 5 0.5 psid.JAFNPP 3.6.1.7-2 Amendment 274 MSLC System 3.6.1.8 3.6 CONTAINMENT SYSTEMS 3.6.1.8 Main Steam Leakage Collection (MSLC) System LCO 3.6.1.8 APPLICABILITY:
| |
| Two MSLC subsystems shall be OPERABLE.MODES 1, 2. and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One MSLC subsystem A.1 Restore MSLC 30 days inoperable.
| |
| subsystem to OPERABLE status.B. Two MSLC subsystems B.1 Restore one MSLC 7 days inoperable.
| |
| subsystem to OPERABLE status.C. Required Action and C.1 Be in MODE 3. 12 hours associated Completion Time not met. AND C.2 Be in MODE 4. 36 hours JAFNPP 3.6.1.8-1 Amendment 274 MSLC System 3.6.1.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.8.1 Verify each MSLC subsystem manual, power 31 days operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, is in the correct position or can be aligned to the correct position.SR 3.6.1.8.2 Perform a system functional test of each 24 months MSLC subsystem.
| |
| JAFNPP 3.6.1.8-2 Amendment 274 RHR Containment Spray System 3.6.1.9 3.6 CONTAINMENT SYSTEMS 3.6.1.9 Residual Heat Removal (RHR) Containment Spray System LCO 3.6.1.9 APPLICABILITY:
| |
| Two RHR containment spray subsystems shall be OPERABLE.MODES 1. 2, and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR containment A.1 Restore RHR 7 days spray subsystem containment spray inoperable.
| |
| subsystem to OPERABLE status.B. Two RHR containment B.1 Restore one RHR 8 hours spray subsystems containment spray inoperable.
| |
| subsystem to OPERABLE status.C. Required Action and C.1 Be in MODE 3. 12 hours associated Completion Time not met. AND C.2 Be in MODE 4. 36 hours JAFNPP 3.6.1.9-1 Amendment 274 RHR Containment Spray System 3.6.1.9 SURVEILLANCE REQUIREMENTS
| |
| ________SURVEI LLANCE FREQUENCY SR 3.6.1.9.1 Verify each RHR containment spray 31 days subsystem manual, power operated, and automatic valve in the flow path that is not locked. sealed, or otherwise secured in position, is in the correct position or can be aligned to the correct position.SR 3.6.1.9.2 Verify each required RHRjpump develops a In accordance flow rate of k 7750 gpm trough the with the associated heat exchanger while operating Inservice in the suppression pool cooling mode. Testing Program SR 3.6.1.9.3 Verify each spray nozzle is unobstructed.
| |
| 10 years JAFNPP 3.6.1.9-2 JAFNP 3.6..9-2Amendment 274 Suppression Pool Average Temperature 3.6.2.1 3.6 CONTAINMENT SYSTEMS 3.6.2.1 Suppression Pool Average Temperature LCO 3.6.2.1 Suppression pool average temperature shall be: a. 95 0 F with THERMAL POWER > 1% RTP and no testing that adds heat to the suppression pool is being performed;
| |
| : b. s 105 0 F with THERMAL POWER > 1% RTP and testing that adds heat to the suppression pool is being performed; and c. 110 0 F with THERMAL POWER 1% RTP.APPLICABILITY:
| |
| MODES 1. 2, and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Suppression pool A.1 Verify suppression Once per hour average temperature pool average> 95 0 F but s 110 0 F. temperature 110 0 F.AND AND THERMAL POWER A.2 Restore suppression 24 hours> 1% RTP. pool average temperature to AND s 95 0 F.Not performing testing that adds heat to the suppression pool.(continued)
| |
| JAFNPP 3.6.2.1-1 Amendment 274 Suppression Pool Average Temperature 3.6.2.1 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Reduce THERMAL POWER 12 hours associated Completion to s 1% RTP.Time of Condition A not met.C. Suppression pool C.1 Suspend all testing Immediately average temperature that adds heat to the> 105 0 F. suppression pool.AND THERMAL POWER> 1% RTP.AND Performing testing that adds heat to the suppression pool.D. Suppression pool D.1 Place the reactor Immediately average temperature mode switch in the> 110'F but 120 0 F. shutdown position.AND D.2 Verify suppression Once per pool average 30 minutes temperature 5 120'F.AND D.3 Be in MODE 4. 36 hours (continued)
| |
| JAFNPP 3.6.2.1-2 Amendment 274 Suppression Pool Average Temperature 3.6.2.1 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME E. Suppression pool E.1 Depressurize the 12 hours average temperature reactor vessel to> 120 0 F. < 200 psig.AND E.2 Be in MODE 4. 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1.1 Verify suppression pool average 24 hours temperature is within the applicable limits. AND 5 minutes when performing testing that adds heat to the suppression pool JAFNPP 3.6.2.1-3 Amendment 274 Suppression Pool Water Level 3.6.2.2 3.6 CONTAINMENT SYSTEMS 3.6.2.2 Suppression Pool Water Level LCO 3.6.2.2 Suppression pool water level shall be 2 13.88 ft and s 14 ft.------------
| |
| --NOTE -- ---..........
| |
| Not required to be met for up to 4 hours during Surveillances that cause suppression pool water level to be outside the limit.APPLICABILITY:
| |
| MODES 1, 2. and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Suppression pool water A.1 Restore suppression 2 hours level not within pool water level to limits. within limits.B. Required Action and B.1 Be in MODE 3. 12 hours associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.2.1 Verify suppression pool water level is 24 hours within limits.JAFNPP 3.6.2.2-1 Amendment 274 RHR Suppression Pool Cooling 3.6.2.3 3.6 CONTAINMENT SYSTEMS 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling LCO 3.6.2.3 APPLICABILITY:
| |
| Two RHR suppression pool cooling subsystems shall be OPERABLE.MODES 1. 2, and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR suppression A.1 Restore RHR 7 days pool cooling subsystem suppression pool inoperable.
| |
| cooling subsystem to OPERABLE status.B. Two RHR suppression B.1 Restore one RHR 8 hours pool cooling suppression pool subsystems inoperable.
| |
| cooling subsystem to OPERABLE status.C. Required Action and C.1 Be in MODE 3. 12 hours associated Completion Time not met. AND C.2 Be in MODE 4. 36 hours JAFNPP 3.6.2.3-1 Amendment 274 RHR Suppression Pool Cooling 3.6.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.3.1 Verify each RHR suppression pool cooling 31 days subsystem manual, power operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, is in the correct position or can be aligned to the correct position.SR 3.6.2.3.2 Verify each required RHR pump develops a In accordance flow rate 2 7700 gpm through the with the associated heat exchanger while operating Inservice in the suppression pool cooling mode. Testing Program JAFNPP 3.6.2.3-2 Amendment 274 Drywell-to-Suppression Chamber Differential Pressure 3.6.2.4 3.6 CONTAINMENT SYSTEMS 3.6.2.4 Drywell-to-Suppression Chamber Differential Pressure LCO 3.6.2.4 The drywell pressure shall be maintained
| |
| ? 1.7 psi above the pressure of the suppression chamber.----------------------------
| |
| NOTE----------------------------
| |
| Not required to be met for 4 hours during Surveillances that cause or require the drywell-to-suppression chamber differential pressure to be outside the limit.APPLICABILITY:
| |
| MODE 1 during the time period: a. From 24 hours after THERMAL POWER is > 15% RTP following startup, to b. 24 hours prior to reducing THERMAL POWER to < 15% RTP prior to the next scheduled reactor shutdown.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Drywell-to-suppression A.1 Restore differential 8 hours chamber differential pressure to within pressure not within limit.limit.B. Required Action and B.1 Reduce THERMAL POWER 12 hours associated Completion to s 15% RTP.Time not met.JAFNPP 3.6.2.4-1 Amendment 274 Drywell-to-Suppression Chamber Differential Pressure 3.6.2.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.4.1 Verify drywell-to-suppression chamber 12 hours differential pressure is within limit.JAFNPP 3.6.2.4-2 Amendment 274
| |
| --Primary Containment Oxygen Concentration 3.6.3.1 3.6 CONTAINMENT SYSTEMS 3.6.3.1 Primary Containment Oxygen Concentration LCO 3.6.3.1 APPLICABILITY:
| |
| The primary containment oxygen concentration shall be< 4.0 volume percent.MODE 1 during the time period: a. From 24 hours after THERMAL POWER is > 15X RTP following startup, to b. 24 hours prior to reducing THERMAL POWER to < 15% RTP prior to the next scheduled reactor shutdown.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Primary containment A.1 Restore oxygen 24 hours oxygen concentration concentration to not within limit. within limit.B. Required Action and B.1 Reduce THERMAL POWER 8 hours associated Completion to s 15% RTP.Time not met.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1.1 Verify primary containment oxygen 7 days concentration is within limits.JAFNPP 3.6.3.1-1 Amendment 274 CAD System 3.6.3.2 3.6 CONTAINMENT SYSTEMS 3.6.3.2 Containment Atmosphere Dilution (CAD) System LCO 3.6.3.2 APPLICABILITY:
| |
| Two CAD subsystems shall be OPERABLE.MODES I and 2.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CAD subsystem A.1 Restore CAD subsystem 30 days inoperable.
| |
| to OPERABLE status.B. Two CAD subsystems B.1 Verify by administrative 1 hour inoperable.
| |
| means that the hydrogen control AND function is maintained.
| |
| Once per 12 hours thereafter AND 6.2 Restore one CAD 7 days subsystem to OPERABLE status.C. Required Action and C.1 Be in MODE 3. 12 hours associated Completion Time not met.JAFNPP 3.6.3.2-1 Amendment 284 CAD System 3.6.3.2 SURVEILLANCE REQUIREMENTS
| |
| -SURVEILLANCE FREQUENCY SR 3.6.3.2.1 Verify 2 1400 gal of liquid nitrogen are 31 days contained in each CAD subsystem.
| |
| SR 3.6.3.2.2 Verify each CAD subsystem manual. power 31 days operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position or can be aligned to the correct position.JAFNPP 3.6.3.2-2 Amendment 274 Seconaarv i orn:ei r,,,en:.. 1 3.6 CONTAINMENT SYSTEMS 3.6.4.1 Secondary Containment LCO 3.6.4.1 APPLICABILITY:
| |
| The secondary containment shall be OPERABLE.MODES 1, 2, and 3.During movement of recently irradiated fuel assemblies in the secondary containment.
| |
| During operations with a potential for draining the reactor vessel (OPDRVs).I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Secondary containment A.1 Restore secondary 4 hours inoperable in MODE 1, containment to 2, or 3. OPERABLE status.B. Required Action and B.1 Be in MODE 3. 12 hours associated Completion Time of Condition A AND not met.B.2 Be in MODE 4. 36 hours C. Secondary containment C.1 NOTE .--.-inoperable during LCO 3.0.3 is not movement of recently applicable.
| |
| irradiated fuel .....................
| |
| assemblies in the secondary containment Suspend movement of Immediately or during OPDRVs. recently irradiated fuel assemblies in the secondary containment.
| |
| AND (continued)
| |
| JAFNPP 3.6.4.1-1 Amendment 276 SEP 1 2 200
| |
| : 3. 6.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued)
| |
| C.2 Initiate action to Immediately suspend OPDRVs.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify secondary containment vacuum is 24 hours 2 0.25 inch of vacuum water gauge.SR 3.6.4.1.2 Verify all secondary containment 31 days equipment hatches are closed and sealed.SR 3.6.4.1.3 Verify one secondary containment access 31 days door in each access opening is closed.SR 3.6.4.1.4 Verify the secondary containment can be 24 months on a maintained 2 0.25 inch of vacuum water STAGGERED TEST gauge for 1 hour using one SGT subsystem BASIS for each at a flow rate 6000 cfm. SGT subsystem I JAFNPP 3.6.4.1-2 Amendment 276 SEP 1 2 M S.- I VS-.2s 3.6 CONTAINMENT SYSTEMS 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)LCO 3.6.4.2 Each SCIV shall be OPERABLE.APPLICABILITY:
| |
| MODES 1, 2. and 3.During movement of recently irradiated the secondary containment.
| |
| During operations with a potential for vessel (OPDRVs).fuel assemblies in draining the reactor I ACTIONS.....-----------
| |
| ---- NOTES -------------------------
| |
| : 1. Penetration flow paths may be unisolated intermittently under administrative controls.2. Separate Condition entry is allowed for each penetration flow path.3. Enter applicable Conditions and Required Actions for systems made inoperable by SCIVs.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Isolate the affected 8 hours penetration flow paths penetration flow path with one SCIV by use of at least inoperable.
| |
| one closed and de-activated automatic valve, closed manual valve, or blind flange.AND (continued)
| |
| JAFNPP 3.6.4.2-1 Amendment 276 SEP 12 2012 SCIVs 3.6.4.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
| |
| A.2 --------NOTES--------
| |
| : 1. Isolation devices in high radiation areas may be verified by use of administrative means.2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.Verify the affected Once per 31 days penetration flow path is isolated.B. ---------NOTE---------
| |
| B.1 Isolate the affected 4 hours Only applicable to penetration flow path penetration flow paths by use of at least with two isolation one closed and valves. de-activated
| |
| ....... ... .. automatic valve.closed manual valve, One or more or blind flange.penetration flow paths with two SCIVs inoperable.
| |
| C. Required Action and C.1 Be in MODE 3. 12 hours associated Completion Time of Condition A AND or B not met in MODE 1, 2, or 3. C.2 Be in MODE 4. 36 hours (continued)
| |
| JAFNPP 3.6.4.2-2 Amendment 274
| |
| -4 I f-.-..c ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 --NOTE.-------
| |
| associated Completion LCO 3.0.3 is not Time of Condition A applicable.
| |
| or B not met during .....................
| |
| movement of recently irradiated fuel Suspend movement of Immediately assemblies in the recently irradiated secondary containment fuel assemblies in or during OPDRVs. the secondary containment.
| |
| AND D.2 Initiate action to Immediately suspend OPDRVs.JAFNPP 3.6.4.2-3 Amendment 276 SEP 1 2 2M2
| |
| -SCIVs 3.6.4.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.2.1
| |
| ----------
| |
| NOTES------------------
| |
| : 1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.2. Not required to be met for SCIVs that are open under administrative controls.Verify each secondary containment 31 days isolation manual valve and blind flange that is not locked. sealed. or otherwise secured and is required to be closed during accident conditions is closed.SR 3.6.4.2.2 Verify the isolation time of each power 92 days operated, automatic SCIV is within limits.SR 3.6.4.2.3 Verify each automatic SCIV actuates to 24 months the isolation position on an actual or simulated actuation signal.JAFNPP 3.6.4.2-4 Amendment 274 v .: I 3.6 CONTAINMENT SYSTEMS 3.6.4.3 Standby Gas Treatment (SGT) System LCO 3.6.4.3 Two SGT :ubsystems shall be OPERABLE.APPLICABILITY:
| |
| MODES 1. 2. and 3.During movement of recently irradiated the secondary containment.
| |
| During operations with a potential for vessel (OPDRVs).fuel assemblies in draining the reactor I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SGT subsystem A.1 Restore SGT subsystem 7 days inoperable.
| |
| to OPERABLE status.B. Required Action and B.1 Be in MODE 3. 12 hours associated Completion Time of Condition A AND not met in MODE 1, 2.or 3. B.2 Be in MODE 4. 36 hours C. Required Action and --.----.----
| |
| NOTE.-----------
| |
| associated Completion LCO 3.0.3 is not applicable.
| |
| Time of Condition A ............................
| |
| not met during movement of recently C.1 Place OPERABLE SGT Immediately irradiated fuel subsystem in assemblies in the operation.
| |
| secondary containment or during OPDRVs. OR (continued)
| |
| JAFNPP 3.6.4.3-1 Amendment 276 SEP 1 2 2002
| |
| , z -" m S : 2--:I 3 -' -^ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued)
| |
| C.2.1 Suspend movement of Immediately recently irradiated fuel assemblies in secondary containment.
| |
| AND C.2.2 Initiate action to Immediately suspend OPDRVs.D. Two SGT subsystems D.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1.2, or 3.E. Two SGT subsystems E.1 --NOTE- ----inoperable during LCO 3.0.3 is not movement of recently applicable.
| |
| irradiated fuel ...assemblies in the secondary containment Suspend movement of Immediately or during OPDRVs. recently irradiated fuel assemblies in secondary containment.
| |
| AND E.2 Initiate dction to Immediately suspend OPDRVs.I JAFNPP 3.6.4.3-2 Amendment 276 SEP 1 2 2M2 SGT System 3.6.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each SGT subsystem for 31 days 2 10 continuous hours with heaters operating.
| |
| SR 3.6.4.3.2 Perform required SGT filter testing in In accordance accordance with the Ventilation Filter with the VFTP Testing Program (VFTP).SR 3.6.4.3.3 Verify each SGT subsystem actuates on an 24 months actual or simulated initiation signal.SR 3.6.4.3.4 Manually cycle each SGT subsystem filter 24 months cooling cross-tie valve.JAFNPP 3.6.4.3-3 Amendment 274 RHRSW System 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Residual Heat Removal Service Water (RHRSW) System LCO 3.7.1 APPLICABILITY:
| |
| Two RHRSW subsystems shall be OPERABLE.MODES 1. 2. and 3.ACTIONS .CONDITION REQUIRED ACTION COMPLETION TIME A. One RHRSW pump A.1 Restore RHRSW pump to 30 days inoperable.
| |
| OPERABLE status.B. One RHRSW pump in each B.1 Restore one RHRSW 7 days subsystem inoperable, pump to OPERABLE status.C. One RHRSW subsystem
| |
| -----NOTE-------------
| |
| inoperable for reasons Enter applicable Conditions other than and Required Actions of LCO Condition A. 3.4.7. "Residual Heat Removal (RHR) Shutdown Cooling System-Hot Shutdown." for RHR shutdown cooling made inoperable by RHRSW System..............................
| |
| C.1 Restore RHRSW 7 days subsystem to OPERABLE status.(continued)
| |
| JAFNPP 3.7.1-1 Amendment 274 RHRSW System 3.7.1 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME D. Both RHRSW subsystems
| |
| --NOTE--.----
| |
| inoperable for reasons Enter applicable Conditions other than and Required Actions of LCO Condition B. 3.4.7 for RHR shutdown cooling made inoperable by RHRSW System..............................
| |
| D.1 Restore one RHRSW 8 hours subsystem to OPERABLE status.E. Required Action and E.1 Be in MODE 3. 12 hours associated Completion Time not met. AND E.2 Be in MODE 4. 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.1 Verify each RHRSW manual, power operated.
| |
| 31 days and automatic valve in the flow path. that is not locked, sealed, or otherwise secured in position, is in the correct position or can be aligned to the correct position.JAFNPP 3.7.1-2 Amendment 274 ESW System and UHS 3.7.2 3.7 PLANT SYSTEMS 3.7.2 Emergency Service Water (ESW) System and Ultimate Heat Sink (UHS)LCO 3.7.2 APPLICABILITY:
| |
| Two ESW subsystems and UHS shall be OPERABLE.MODES 1. 2, and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One ESW subsystem
| |
| ------------
| |
| NOTE-------------
| |
| inoperable.
| |
| Enter applicable Conditions and Required Actions of LCO 3.8.1. "AC Sources-Operating." for emergency diesel generator subsystem made inoperable by ESW.A.1 Restore the ESW 7 days subsystem to OPERABLE status.B. One division of B.1 Restore the division of 7 days required deicing deicing heaters to heaters inoperable.
| |
| OPERABLE status.AND UHS temperature 37 0 F.(continued)
| |
| JAFNPP 3.7.2-1 Amendment 274 ESW System and UHS 3.7.2 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 12 hours associated Completion Time not met. AND OR C.2 Be in MODE 4. 36 hours Both ESW subsystems inoperable for reasons other than Condition A.OR UHS inoperable for reasons other than Condition B.SURVEILLANCE REQUIREMENTS
| |
| .SURVEILLANCE FREQUENCY SR 3.7.2.1 Verify the water level in the ESW pump 24 hours screenwell is 2 236.5 ft mean sea level.SR 3.7.2.2 Verify the average water temperature of UHS 24 hours is 85 0 F.(continued)
| |
| JAFNPP 3.7.2-2 Amendment 274
| |
| -ESW System and UHS 3.7.2 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.7.2.3 ------------------
| |
| NOTE--------------------
| |
| Not required to be met if UHS temperature is > 37 0 F....... ................
| |
| .. ....Verify the required deicing heater feeder 7 days current is within limits for each division of deicing heaters.SR 3.7.2.4 -------------------
| |
| NOTE--------------------
| |
| Isolation of flow to individual components does not necessarily render ESW System inoperable.
| |
| .. .................. ..... ..Verify each ESW subsystem manual, power 31 days operated, and automatic valve in the flow paths servicing safety related systems or components, that is not locked, sealed, or otherwise secured in position, is in the correct position.SR 3.7.2.5 -------------------
| |
| NOTE--------------------
| |
| Not required to be met if UHS temperature is > 37 0 F... ...... .....-- ---- -----Verify the required deicing heater power is 6 months within limits for each division of deicing heaters.(continued)
| |
| JAFNPP 3.7.2-3 Amendment 274 ESW System and UHS 3.7.2 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.7.2.6 ------------------
| |
| NOTE--------------------
| |
| Not required to be met if UHS temperature is > 37 0 F..........
| |
| .........................
| |
| ........Verify the required deicing heater 12 months resistance to ground is within limits for each division of deicing heaters.SR 3.7.2.7 Verify each ESW subsystem actuates on an 24 months actual or simulated initiation signal.JAFNPP 3.7.2-4 Amendment 274 CREVAS System 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Control Room Emergency Ventilation Air Supply (CREVAS) System ICO 3.7.3 Two CREVAS subsystems shall be OPERABLE--------------N O T E ---------------The control room envelope (CRE) boundary may be opened intermittently under administrative control.APPLICABILITY:
| |
| MODES 1, 2, and 3 During movement of recently irradiated fuel assemblies in the secondary containment During operations with a potential for draining the reactor vessel (OPDRVs).ACTIONS______________________
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. One CREVAS subsystem A-l. Restore CREVAS 7 days inoperable for reasons subsystem to OPERABLE other than Condition B. status.B. One or more CREVAS B.1 Initiate action to Immediately subsystems inoperable implement mitigating due to inoperable CRE actions.boundary in MODE 1, 2, or 3. AND B.2 Verify mitigating actions 24 hours ensure CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.AND B.3 Restore CRE boundary to 90 days OPERABLE status.(continued)
| |
| JAFNPP 3.7.3-1 JAFNP 3..3-1Amendment 289 CREVAS SYSTEM 3.7.3 ACTIONS (continued)
| |
| _______________________
| |
| CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 12 hours associated Completion TIime of, Condition A or B iAND not met in MODE 1, 2, or 3. C.2 Be in MODE 4. 36 hours D. Required Action and--------------NOTE
| |
| ----------
| |
| associated Completion LCO, 3.0.3 is not applicable.
| |
| Time of Condition.
| |
| A not -- ------- -----met during movement of recently irradiated fuel D.1 Place OPERABLE .Immediately assemblies in the CREVAS subsystem in secondary containment isolate mode.or during OPDR Vs.OR 0.2.1 Suspend movement of Immediately recently irradiated fuel assemblies in the secondary containment.
| |
| AND D.2.2 Initiate action to suspend Immediately OPDRVs.E. Two CREVAS subsystems E.1 Enter LCO 3.0.3 Immediately inoperable in MODE 1, 2, or 3 for reasons other then Condition B.(continued)
| |
| JAFNPP 3.7.3-2 JAFNP 3..3-2Amendment 289 CREVAS SYSTEM 3.7.3 ACTIONS (continued)________________________
| |
| CONDITION REQUIRED ACTION COMPLETION TIME F. Two CREVAS subsystems------------NOTE
| |
| ----------
| |
| inoperable during LCO 3.0.3 is not applicable.
| |
| movement of recently ----- ---------irradiated fuel assemblies in the F.1 Suspend movement of Immediately secondary containment recently irradiated fuel or during OPDRVs. assemblies in the secondary containment.
| |
| OR AND One or more CREVAS subsystems inoperable F.2 Initiate action to suspend Immediately due to an inoperable CRE OPDRVs.boundary during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs.SURVEILLANCE REQUIREMENTS_________
| |
| SURVEILLANCE FREQUENCY SR 3.7.3.1 Operate each CREVAS subsystem for 2t 15 92 days minutes.S R 3.7.3.2 Perform required CREVAS filter testing in In accordance with accordance with the Ventilation Filter Testing the VFTP Program (VFTP)(continued)
| |
| JAFNPP 3.7.3-3 JAFNP 3..3-3Amendment 289 CREVAS SYSTEM 3.7.3 SURVEILLANCE REQUIREMENTS (continued)__________
| |
| SURVEILLANCE FREQUENCY SR 3.7.3.3 Perform required CR E unfiltered air in-leakage In accordance with testing in accordance with the Control Room the Control Room Envelope Habitability Program. Envelope Habitability Program JAFNPP 3.7.3-4 JAFNP 3..3-4Amendment 289 Control Room AC System 3.7.4 3..7 PLANT SYSTEMS 3.7.4 Control Room Air Conditioning (AC) System LCO 3.7.4 APPLICABILITY:
| |
| Two control room AC subsystems shall be OPERABLE.MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One control room AC A.1 Restore control room AC 30 days subsystem inoperable, subsystem to OPERABLE status.B. Two control room AC B.1 Verify control room area Once per 4 hours subsystems inoperable, temperature
| |
| < 90 OF.AND B.2 Restore one control 72 hours room AC subsystem to OPERABLE status.C. Required Action and C.1 Be in MODE 3. 12 hours associated Completion Time of Condition A or B AND not met in MODE 1, 2, or 3. C.2 Be in MODE 4. 36 hours (continued)
| |
| I I I JAFNPP 3.7.4-1 Amendment 290.
| |
| Control Room AC System 3.7.4 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and -----------
| |
| NOTE ----------
| |
| associated Completion LCO 3.0.3 is not applicable.
| |
| Time of Condition A not --------------------------
| |
| met during movement of recently irradiated fuel D.1 Place OPERABLE Immediately assemblies in the control room AC secondary containment or subsystem in during OPDRVs. operation.
| |
| OR D.2.1 Suspend movement of Immediately recently irradiated fuel assemblies in the secondary containment.
| |
| AND D.2.2 Initiate action to Immediately suspend OPDRVs.E. Required Action and -----------
| |
| NOTE--------
| |
| associated Completion LCO 3.0.3 is not applicable.
| |
| Time of Condition B not --------------------------
| |
| met during movement of recently irradiated fuel E.1 Suspend movement of Immediately assemblies in the recently irradiated fuel secondary containment or assemblies in the during OPDRVs. secondary containment.
| |
| AND E.2 Initiate action to Immediately suspend OPDRVs.I JAFNPP 3.7.4-2 Amendment 290 Control Room AC System 3.7.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify each control room AC subsystem has the 24 months capability to remove the assumed heat load.JAFNPP 3.7.4-3 Amendment 2 9 0 Main Condenser SJAE Offgas 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Main Condenser Steam Jet Air Ejector (SJAE) Offgas LCO 3.7.5 The gross gamma activity rate of the noble gases measured at the discharge of the SJAE (prior to dilution and/or discharge) shall be s 600,000 pCi/second.
| |
| APPLICABILITY:
| |
| MODE 1.MODES 2 and 3 with steam jet air any main steam ejector (SJAE)line not isolated and in operation.
| |
| ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Gross gamma activity A.1 Restore gross gamma 72 hours rate of the noble activity rate of the gases not within noble gases to within limit. limit.B. Required Action and B.1 Isolate all main 12 hours associated Completion steam lines.Time not met.OR B.2 Isolate SJAE. 12 hours OR B.3.1 Be in MODE 3. 12 hours AND B.3.2 Be in MODE 4. 36 hours JAFNPP 3.7.5-1 Amendment 274 Main Condenser SJAE Offgas 3.7.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1-------------------
| |
| NOTE--------------------
| |
| Not required to be performed until 31 days after any main steam line not isolated and SJAE in operation.
| |
| Verify the gross gamma activity rate of the noble gases is s 600,000 pCi/second.
| |
| 31 days AND------NOTE-----Only required when gross gamma activity rate is 2 5.000 pCi/second
| |
| ..........
| |
| ...........
| |
| .Once within 4 hours after a 2 50% increase in the nominal steady state fission gas release after factoring out increases due to changes in THERMAL POWER level JAFNPP 3.7.5-2 Amendment 274 Main Turbine Bypass System 3.7.6 3.7 PLANT SYSTEMS 3.7.6 Main Turbine Bypass System LCO 3.7.6 The Main Turbine Bypass System shall be OPERABLE.OR The following limits are made applicable:
| |
| : a. LCO 3.2.2. "MINIMUM CRITICAL POWER RATIO (MCPR)," for an inoperable Main Turbine Bypass System, as specified in the COLR: and limits b. LCO 3.2.3. "LINEAR HEAT GENERATION RATE (LHGR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR.APPLICABILITY:
| |
| THERMAL POWER 2 25% RTP.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Satisfy the 2 hours LCO not met. requirements of the LCO.B. Required Action and B.1 Reduce THERMAL POWER 4 hours associated Completion to < 25% RTP.Time not met.JAFNPP 3.7.6-1 Amendment 274 Main Turbine Bypass System 3.7.6 SURVEILLANCE REQUIREMENTS
| |
| _SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify one complete cycle of each required Prior to main turbine bypass valve. entering MODE 2 or 3 from MODE 4 SR 3.7.6.2 Perform a system functional test. 24 months SR 3.7.6.3 Verify the TURBINE BYPASS SYSTEM RESPONSE 24 months TIME is within limits.JAFNPP 3.7.6-2 Amendment 274
| |
| -.Spent Fuel Storage Pool Water Level 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Spent Fuel Storage Pool Water Level LCO 3.7.7 The spent fuel storage pool water level shall be 2 21 ft 7 inches over the top of irradiated fuel seated in the spent fuel storage pool racks.assemblies APPLICABILITY:
| |
| During movement of irradiated fuel assemblies in the spent fuel storage pool.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel storage A.1 NOTE---------
| |
| pool water level not LCO 3.0.3 is not within limit. applicable.
| |
| .....................
| |
| Suspend movement of Immediately irradiated fuel assemblies in the spent fuel storage pool.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 Verify the spent fuel storage pool water 7 days level is 2 21 ft 7 inches over the top of irradiated fuel assemblies seated in the spent fuel storage pool racks.JAFNPP 3.7.7-1 Amendment 274 AC Sources-Operating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources-Operating LCO 3.8.1 The following AC electrical power sources shall be OPERABLE: a. Two qualified circuits between the offsite transmission network and the plant Class lE AC Electrical Power Distribution System; and b. Two emergency diesel generator (EDG) subsystems.
| |
| APPLICABILITY:
| |
| MODES 1, 2, and 3.ACTIONS----------
| |
| is-not-applicabNOTE to-----subsystems.
| |
| LCO 3.O.4.b is not applicable to EDG subsystems.
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. One offsite circuit A.1 Perform SR 3.8.1.1 for 1 hour inoperable.
| |
| OPERABLE offsite circuit AND Once per 8 hours thereafter AND A.2 Declare required 24 hours from feature(s) with no discovery of no offsite power available offsite power to inoperable when the one division redundant required concurrent with feature(s) are inoperability of inoperable.
| |
| redundant required feature(s)
| |
| AND (continued)
| |
| JAFNPP 3.8.1-1 Amendment 284 AC Sources -Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
| |
| A.3 Restore offsite 7 days circuit to OPERABLE status. AND 21 days from discovery of failure to meet LCO B. One EDG subsystem inoperable.
| |
| B.1 AND B.2 AND B.3.1 OR B.3.2 Perform SR 3.8.1.1 for OPERABLE offsite circuit(s).
| |
| Declare required feature(s), supported by the inoperable EDG subsystem, inoperable when the redundant required feature(s) are inoperable.
| |
| Determine OPERABLE EDG subsystem is not inoperable due to common cause failure.Perform SR 3.8.1.2 for OPERABLE EDG subsystem.
| |
| 1 hour AND Once per 8 hours thereafter 4 hours from discovery of Condition B concurrent with inoperability of redundant required feature(s) 24 hours 24 hours (continued)
| |
| AND JAFNPP 3.8.1-2 Amendment 274 AC Sources -Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued)
| |
| B.4 Restore EDG subsystem 14 days to OPERABLE status.AND 21 days from discovery of failure to meet LCO C. Two offsite circuits C.1 Declare required 12 hours from inoperable.
| |
| feature(s) inoperable discovery of when the redundant Condition C required feature(s) concurrent with are inoperable.
| |
| inoperability of redundant required feature(s)
| |
| AND C.2 Restore one offsite 7 days circuit to OPERABLE status.D. One offsite circuit ------------
| |
| NOTE-------------
| |
| inoperable.
| |
| Enter applicable Conditions and Required Actions of AND LCO 3.8.7, "Distribution Systems -Operating." when One EDG subsystem Condition D is entered with inoperable.
| |
| no AC power source to any division.D.1 Restore offsite 12 hours circuit to OPERABLE status.OR (continued)
| |
| JAFNPP 3.8.1-3 Amendment 274 AC Sources -Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. (continued)
| |
| D.2 Restore EDG subsystem 12 hours to OPERABLE status.E. Two EDG subsystems E.1 Restore one EDG 2 hours inoperable.
| |
| subsystem to OPERABLE status.F. Required Action and F.1 Be in MODE 3. 12 hours associated Completion Time of Condition A. AND B, C, D, or E not met.F.2 Be in MODE 4. 36 hours G. Three or more AC G.1 Enter LCO 3.0.3. Immediately sources inoperable.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and 7 days indicated power availability for each offsite circuit.(continued)
| |
| JAFNPP 3.8.1-4 Amendment 274 AC Sources -Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.8.1.2 ---------------
| |
| NOTE--------------------
| |
| All EDG subsystem starts may be preceded by an engine prelube period and followed by a warmup period prior to loading............................................
| |
| Verify each EDG subsystem starts from 31 days standby conditions, force parallels.
| |
| and achieves: a. In 10 seconds, voltage 2 3900 V and frequency 2 58.8 Hz; and b. Steady state voltage 2 3900 V and 4400 V and frequency 2 58.8 Hz and 61.2 Hz.SR 3.8.1.3 -------------------
| |
| NOTES----------------
| |
| : 1. EDG loadings may include gradual loading as recommended by the manufacturer.
| |
| : 2. Momentary transients outside the load range do not invalidate this test.3. This Surveillance shall be conducted on only one EDG subsystem at a time.4. This SR shall be preceded by and immediately follow, without shutdown.a successful performance of SR 3.8.1.2..............
| |
| .................................................
| |
| Verify each EDG subsystem is paralleled 31 days with normal, reserve, or backfeed power and each EDG is loaded and operates for 2 60 minutes at a load 2 2340 kW and 2600 kW.(continued)
| |
| JAFNPP 3.8.1-5 Amendment 274 AC Sources -Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.8.1.4 Verify each day tank contains 2 327 gal of 31 days fuel oil.SR 3.8.1.5 Check for and remove accumulated water from 31 days each day tank.SR 3.8.1.6 Verify that each EDG fuel oil transfer 31 days system operates to automatically transfer fuel oil from its storage tank to the associated day tank.SR 3.8.1.7 ------------------
| |
| NOTE---------------------
| |
| Only required to be met for each offsite circuit that is not energizing its respective 4.16 kV emergency bus.Verify automatic and manual transfer of 24 months plant power supply from the normal station service transformer to each offsite circuit.(continued)
| |
| JAFNPP 3.8.1-6 Amendment 274 AC Sources -Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| ..SURVEILLANCE FREQUENCY 4 SR 3.8.1.8 --------------
| |
| NOTE---------------------
| |
| If performed with the EDG subsystem paralleled with normal, reserve, or backfeed power, it shall be performed within the power factor limit. However, if grid conditions do not permit. the power factor limit is not required to be met.Under this condition, the power factor shall be maintained as close to the limit as practicable.
| |
| Verify each EDG subsystem rejects a load greater than or equal to its associated single largest post-accident load. and following load rejection, the frequency is s 66.75 Hz.24 months (continued)
| |
| JAFNPP 3.8.1-7 Amendment 274 AC Sources -Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.8.1.9 ------....-----
| |
| NOTE--------------------.
| |
| All EDG subsystem starts may be preceded by an engine prelube period.....................
| |
| ...........Verify on an actual or simulated loss of 24 months power signal: a. De-energization of emergency buses: b. Load shedding from emergency buses: and c. EDG subsystem auto-starts from standby condition, force parallels, and: 1. energizes permanently connected loads in s 11 seconds, 2. energizes auto-connected shutdown loads, 3. maintains steady state voltage 2 3900 V and s 4400 V.4. maintains steady state frequency 2 58.8 Hz and s 61.2 Hz. and 5. supplies permanently connected and auto-connected shutdown loads for 2 5 minutes.(continued)
| |
| JAFNPP 3.8.1-8 Amendment 274 AC Sources -Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.8.1.10 --------------
| |
| NOTE--------------------
| |
| All EDG subsystem starts may be preceded by an engine prelube period.Verify on an actual or simulated Emergency 24 months Core Cooling System (ECCS) initiation signal each EDG subsystem auto-starts from standby condition, force parallels, and: a. In s 10 seconds after auto-start and during tests, achieves voltage i 3900 V. frequency k 58.8 Hz;b. Achieves steady state voltage ; 3900 V and 4400 V and frequency e 58.8 Hz and 61.2 Hz: c. Operates for k 5 minutes: d. Permanently connected loads remain energized from the offsite power system; and e. Emergency loads are auto-connected in the prescribed sequence from the offsite power system.(continued)
| |
| JAFNPP 3.8.1-9 Amendment 274 AC Sources -Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.8.1.11 -------NOTES-------------------
| |
| : 1. Momentary transients outside the load and power factor ranges do not invalidate this test.2. If grid conditions do not permit. the power factor limit is not required to be met. Under this condition, the power factor shall be maintained as close to the limit as practicable.
| |
| ..............................
| |
| .............................................................
| |
| Verify each EDG subsystem operating within 24 months the power factor limit operates for 2 8 hours: a. For 2 2 hours each EDG loaded 2 2730 kW and 2860 kW; and b. For the remaining hours of the test each EDG loaded 2 2340 kW and 2600 kW.(continued)
| |
| JAFNPP 3.8.1-10 Amendment 274 AC Sources -Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.8.1.12....---------------
| |
| NOTE--..................
| |
| All EDG subsystem starts may be preceded by an engine prelube period......................
| |
| ............................................
| |
| .........Verify, on an actual or simulated loss of power signal in conjunction with an actual or simulated ECCS initiation signal: a. De-energization of emergency buses: b. Load shedding from emergency buses;and c. EDG subsystem auto-starts from standby condition, force parallels, and: 1. energizes permanently connected loads in s 11 seconds, 2. energizes auto-connected emergency loads in the prescribed sequence.3. achieves steady state voltage 2 3900 V and s 4400 V.4. achieves steady state frequency 2 58.8 Hz and s 61.2 Hz, and 5. supplies permanently connected and auto-connected emergency loads for 2 5 minutes.24 months SR 3.8.1.13 Verify interval between each sequenced load 24 months block is greater than or equal to the minimum design load interval.JAFNPP 3.8.1-11 Amendment 274 h o ;,orces -'~~''3 8 2 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources- Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE: a. One qualified circuit between the offsite transmission network and one division of the plant Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8. "Distribution Systems- Shutdown";
| |
| : b. One qualified circuit. which maybe the same circuit required by LCO 3.8.2.a. between the offsite transmission network and the other division of the plant Class 1E AC electrical power distribution subsystems.
| |
| when a second division is required by LCO 3.8.8: and c. One emergency diesel generator (EDG) subsystem capable of supplying one division of the plant Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8.APPLICABILITY:
| |
| MODES 4 and 5.During movement of recently irradiated fuel assemblies in the secondary containment.
| |
| I JAFNPP 3.8.2 1 Amendment 276 SEP 1 2 2I02 A;< jer,,res -Fr u. Ivn , 3.3.2 ACTIONS Y). --------------.-------.--
| |
| --- ---- -NOTE ----.-.-..........................
| |
| LCO 3.0.3 is not applicable.
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. One or both required offsite circuits inoperable.
| |
| -- ---- --NOTE ............
| |
| Enter applicable Condition and Required Actions of LCO 3.8.8, when any required division is de-energized as a result of Condition A.A. 1 Declare affected required feature(s), with no offsite power available.
| |
| inoperable.
| |
| OR A.2.1 Suspend CORE ALTERATIONS.
| |
| AND A.2.2 Suspend movement of recently irradiated fuel assemblies in the secondary containment.
| |
| Immediately Immediately Immediately I AND A.2.3 Initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs).I Immediately AND (continued)
| |
| JAFNPP 3.8.2-2 Amendment 276 SEP 1 2 2p1 bW.~-,~,-
| |
| ~ .'e :-- .- :' , ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
| |
| A.2.4 Initiate action to Immediately restore required offsite power circuit(s) to OPERABLE status.B. One required EDG B.1 Suspend CORE Immediately subsystem inoperable.
| |
| ALTERATIONS.
| |
| AND B.2 Suspend movement of Immediately recently irradiated fuel assemblies in secondary containment.
| |
| AND B.3 Initiate action to Immediately suspend OPDRVs.AND B.4 Initiate action to Immediately restore required EDG subsystem to OPERABLE status.I JAFNPP 3.8.2-3 Amendment 276 SEP 1 2 202 AC Sources -Shutdown 3.8.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1 -------------------
| |
| NOTES-------------------
| |
| : 1. The following SRs are not required to be performed:
| |
| SR 3.8.1.3. SR 3.8.1.8.SR 3.8.1.9. SR 3.8.1.11, SR 3.8.1.12, and SR 3.8.1.13.2. SR 3.8.1.10 and SR 3.8.1.12 are not required to be met when associated ECCS subsystems are not required to be OPERABLE per LCO 3.5.2."ECCS -Shutdown." For AC sources required to be OPERABLE the SRs of Specification
| |
| | |
| ====3.8.1. except====
| |
| SR 3.8.1.7. are applicable.
| |
| In accordance with applicable SRs JAFNPP 3.8.2-4 Amendment 274 Diesel Fuel Oil, Lube Oil. and Starting Air 3.8.3 3.8 ELECTRICAL POWER SYSTEMS 3.8.3 Diesel Fuel Oil, Lube Oil. and Starting Air LCO 3.8.3 APPLICABILITY:
| |
| The stored diesel fuel oil, lube oil, and starting air subsystem shall be within limits for each required emergency diesel generator (EDG).When associated EDG subsystem is required to be OPERABLE.ACTIONS-.........
| |
| -.......-.-. -NOTE--------------------.----------------
| |
| Separate Condition entry is allowed for each EDG.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more EDGs with A.1 Restore fuel oil 48 hours fuel oil level level to within< 32.000 gal and limits.> 28,000 gal in storage tank.B. One or more EDGs with B.1 Restore lube oil 48 hours lube oil inventory inventory to within< 168 gal and limits.> 144 gal.C. One or more EDGs with C.1 Restore stored fuel 7 days stored fuel oil total oil total particulates not particulates to within limit. within limit.(continued)
| |
| JAFNPP 3 .8.3-1 Amendment 274
| |
| ---Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME D. One or more EDGs with D.1 Restore stored fuel 30 days new fuel oil oil properties to properties not within within limits.lmits.E. One or more EDGs with E.1 Restore required 48 hours required starting air starting air receiver receiver pressure pressure to within< 150 psig and limits.2 110 psig.F. Required Action and F.1 Declare associated Immediately associated Completion EDG inoperable.
| |
| Time of Condition A, B. C. D, or E not met.OR One or more EDGs with diesel fuel oil, lube oil, or starting air subsystem not within limits for reasons other than Condition A, B. C, D, or E.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify each fuel oil storage tank contains 31 days 2 32.000 gal of fuel.(continued)
| |
| JAFNPP 3.8.3-2 Amendment 274 Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.8.3.2 Verify lube oil inventory of each EDG is 31 days 2 168 gal.SR 3.8.3.3 Verify fuel oil properties of new and In accordance stored fuel oil are tested in accordance with the Diesel with, and maintained within the limits of. Fuel Oil the Diesel Fuel Oil Testing Program. Testing Program SR 3.8.3.4 Verify each EDG required air start receiver 31 days pressure is 2 150 psig.SR 3.8.3.5 Check for and remove accumulated water from 31 days each fuel oil storage tank.JAFNPP 3.8.3-3 Amendment 274 DC Sources -Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources -Operating LCO 3.8.4 The following DC electrical power subsystems shall be OPERABLE, a. Two 125 VDC subsystems; and b. Two 419 VDC low pressure coolant Injection (LPCI) MOV Independent power supply subsystems.
| |
| APPLICABILITY.
| |
| MODES 1, 2, and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One battery charger on A.1 Restore battery terminal 2 hours One 125 VDC power voltage to greater than or subsystem Inoperable.
| |
| equal to the minimum established float voltage (127.8 VDC).AND A.2 Verify battery float current Once per 12 hours<S2 amps.AND A.3 Restore battery charger to 7 days OPERABLE status.(continued)
| |
| JAFNPP 3.8.4-1 Amendment 286 DC Sources -Operating 3.8.4 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME B. One 125 VDC electrical B.1 Restore 125 VDC electrical 8 hours power subsystem power subsystem to Inoperable for reasons OPERABLE status.other than Condition A.C. Required Action and C.i. Be In MODE 3. 12 hours associated Completion Time of Condition A or B not AND met.C.2. Be in MODE 4. 36 hours D. One or both 419 VDC LPCI D.1. Declare associated LPCI Immediately MOV Independent power subsystem(s)
| |
| Inoperable.
| |
| supply subsystems Inoperable.
| |
| I I JAFNPP 3.8.4-2 Amendment 286 DC Sources -Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage on float 7 days charge is: a. 'a 127.8 VDC for 125 VDC batteries, and b. __396.2 VDC for 419 VDC LPCI MOV independent power supply batteries.
| |
| SR 3.8.4.2 Verify each 125 VDC battery charger 24 months supplies > 270 amps at _> 128 VDC for 2t 4 hours.OR Verify each 125 VDC battery charger can recharge the battery to the fully charged state within 24 hours while supplying the largest combined demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state.SR 3.8.4.3 ----------------
| |
| NOTE ----------------
| |
| This Surveillance shall not normally be performed in MODE 1, 2, or 3 for the 125 VDC batteries.
| |
| However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced.
| |
| Credit may be taken for unplanned events that satisfy this SR.Verify battery capacity Is adequate to 24 months supply, and maintain in OPERABLE status, the required emergency loads for the design duty cycle when subjected to a battery service test or a modified performance discharge test.(continued)
| |
| JAFNPP 3.8.4-3 Amendment 286 DC Sources -Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY+SR 3.8.4.4---------------.
| |
| NOTE ----------------
| |
| This Surveillance shall not normally be performed in MODE 1, 2, or 3 for the 125 VDC batteries.
| |
| However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced.
| |
| Credit may be taken for unplanned events that satisfy this SR.Verify battery capacity is > 80% of the manufacturer's rating when subjected to a performance discharge test or a modified performance discharge test.60 months AND 12 months when battery shows degradation or has reached 85% of expected life with capacity < 100% of manufacturer's rating AND 24 months when battery has reached 85% of the expected life with capacity> 100% of manufacturer's rating JAFNPP 3.8.4-4 Amendment 286
| |
| _~u _ '__S --IOU---e -I s 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources -Shutdown LCO 3.8.5 APPLICABILITY:
| |
| One 125 VDC electrical power subsystem shall be OPERABLE to support one division of the plant Class IE DC Electrical Power Distribution System required by LCO 3.8.8,"Distribution Systems- Shutdown." MODES 4 and 5.During movement of recently irradiated fuel assemblies in the secondary containment.
| |
| I ACTIONS-.- --------------
| |
| -----NOTE -..-----------.---------------.-----
| |
| LCO 3.0.3 is not applicable.
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. Required DC electrical A.1 Declare affected immediately power subsystem required feature(s) inoperable.
| |
| inoperable.
| |
| OR A.2.1 Suspend CORE Immediately ALTERATIONS.
| |
| AND A.2.2 Suspend movement of Immediately recently irradiated fuel asse.,blies in the secondary containment.
| |
| AND (continued)
| |
| I JAFNPP 3.8.5-1 Amendment 276 SEP 1 2 axE DC Sources -Shutdown 3.8.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
| |
| A.2.3 Initiate action to Immediately suspend operations with a potential for draining the reactor vessel.AND A.2.4 Initiate action to Immediately restore required DC electrical power subsystem to OPERABLE status.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.5.1 ---------------
| |
| NOTE--------------------
| |
| The following'SRs are not required to be performed:
| |
| SR 3.8.4.2. SR 3.8.4.3, and SR 3.8.4.4................................
| |
| .......................................................
| |
| .....For DC electrical power subsystem required In accordance to be OPERABLE the following SRs are with applicable applicable:
| |
| SRs SR 3.8.4.1, SR 3.8.4.2. SR 3.8.4.3, and SR 3.8.4.4.JAFNPP 3.8.5-2 Amendment 274 Battery Cell Parameters 3.8.6 3.8 ELECTRICAL POWER SYSTEMS 3.8.6 Battery Cell Parameters LCO 3.8.6 Battery cell parameters for the 125 VDC and 419 VDC LPCI MOV independent power supply batteries shall be within the limits of Table 3.8.6-1.AND Battery cell average electrolyte temperature for the 125 VDC and 419 VDC LPCI MOV independent power supply batteries shall be within required limits.APPLICABILITY:
| |
| When associated DC electrical power subsystems are required to be OPERABLE.ACTIONS-..---------.-.-.--.--.--.----.-.-...
| |
| NOTE--...................................
| |
| Separate Condition entry is allowed for each battery.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more batteries A.1 Verify pilot cells 1 hour with one or more electrolyte level and battery cell float voltage meet parameters not within Table 3.8.6-1 Category A or B Category C limits.limits.AND A.2 Verify battery cell 24 hours parameters meet Table 3.8.6-1 AND Category C limits.Once per 7 days thereafter AND (continued)
| |
| JAFNPP 3.8.6-1 Amendment 274
| |
| -.Battery Cell Parameters
| |
| | |
| ====3.8.6 ACTIONS====
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
| |
| A.3 Restore battery cell 31 days parameters to Category A and B limits of Table 3.8.6-1.B. Required Action and B.1 Declare associated Immediately associated Completion battery inoperable.
| |
| Time of Condition A not met.OR One or more batteries with average electrolyte temperature of the representative cells not within limits.OR One or more batteries with one or more battery cell parameters not within Category C limits.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.1 Verify battery cell parameters meet 7 days Table 3.8.6-1 Category A limits.(continued)
| |
| JAFNPP 3.8.6-2 Amendment 274 Battery Cell Parameters
| |
| | |
| ====3.8.6 SURVEILLANCE====
| |
| | |
| REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.8.6.2 Verify battery cell parameters meet 92 days Table 3.8.6-1 Category B limits.SR 3.8.6.3 Verify average electrolyte temperature of 92 days representative cells is 65 0 F for each 125 VDC battery, and a 50 0 F for each 419 VDC LPCI MOV independent power supply battery.JAFNPP 3.8.6-3 Amendment 274 Battery Cell Parameters
| |
| | |
| ====3.8.6 Table====
| |
| 3.8.6-1 (page 1 of 1)Battery Cell Parameter Requirements CATEGORY A: LIMITS FOR EACH CATEGORY B: CATEGORY C: DESIGNATED PILOT LIMITS FOR EACH LIMITS FOR EACH PARAMETER CELL CONNECTED CELL CONNECTED CELL Electrolyte
| |
| > Minimum level > Minimum level Above top of Level indication mark, indication mark, plates, and not and s 4 inch above and s %, inch above overflowing maximum level maximum level indication mark(a) indication mark(a)Float Voltage 2 2.13 V 2 2.13 V > 2.07 V Specifi ~ k 1.195 k 1.195 Not more than GravityNb)(c) 0.020 below AND average of all connected cells Average of all connected cells AND> 1.205 Average of all connected cells 2 1.195 (a) It is acceptable for the electrolyte level to temporarily increase above the specified maximum level during and, for a limited time, following equalizing charges provided it is not overflowing.(b) Corrected for electrolyte temperature and level. Level correction is not required, however, when on float charge and battery charging current is < 2 amps for 125 VDC batteries and < 1 amp for 419 VDC LPCI MOV independent power supply batteries.(c) A battery charging current of < 2 amps for 125 VDC batteries and < 1 amp for 419 VDC LPCI MOV independent power supply batteries when on float charge is acceptable for meeting specific gravity limits following a battery recharge, for a maximum of 7 days. When charging current is used to satisfy specific gravity requirements, specific gravity of each connected cell shall be measured prior to expiration of the 7 day allowance.
| |
| JAFNPP 3.8.6-4 Amendment 274 Distribution Systems -Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems -Operating LCO 3.8.7 The Division 1 and power distribution Division 2 AC and 125 VDC electrical subsystems shall be OPERABLE.APPLICABILITY:
| |
| MODES 1, 2. and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more AC A.1 Restore AC electrical 8 hours electrical power power distribution distribution subsystems to AND subsystems inoperable.
| |
| OPERABLE status.16 hours from discovery of failure to meet LCO B. One 125 VDC electrical B.1 Restore 125 VDC 8 hours power distribution electrical power subsystem inoperable.
| |
| distribution AND subsystem to OPERABLE status. 16 hours from discovery of failure to meet LCO C. Required Action and C.1 Be in MODE 3. 12 hours associated Completion Time of Condition A or AND.B not met.C.2 Be in MODE 4. 36 hours (continued)
| |
| JAFNPP 3.8.7-1 Amendment 274 Distribution Systems -Operating 3.8.7 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME D. Two or more electrical D.1 Enter LCO 3.0.3. Immediately power distribution subsystems inoperable that result in a loss of function.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct breaker alignments and 7 days voltage to required AC and 125 VDC electrical power distribution subsystems.
| |
| JAFNPP 3.8.7-2 Amendment 274
| |
| ] I S .r :. 3 I; v .v , ' V S _,i- E.u I _ ..I ., 4 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Distribution Systems -Shutdown LCO 3.8.8 APPLICABILITY:
| |
| The necessary portions of the AC and 125 VDC electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE.MODES 4 and 5.During movement of recently irradiated fuel assemblies in the secondary containment.
| |
| I ACTIONS.-.---------.---.
| |
| -----NOTE-...............
| |
| LCO 3.0.3 is not applicable.
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Declare associated Immediately AC or 125 VDC supported required electrical power feature(s) distribution inoperable.
| |
| subsystems inoperable.
| |
| OR A.2.1 Suspend CORE Immediately ALTERATIONS.
| |
| AND A.2.2 Suspend movement of Immediately recently irradiated fuel aS-r- blies in the secondary containment.
| |
| AND (continued)
| |
| I JAFNPP 3.8.8-1 Amendment 276 SEP 1 2 2LWz Distribution Systems -Shutdown 3.8.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
| |
| A.2.3 Initiate action to Immediately suspend operations with a potential for draining the reactor vessel.AND A.2.4 Initiate actions to Immediately restore required AC and 125 VDC electrical power distribution subsystems to OPERABLE status.AND Immediately A.2.5 Declare associated required shutdown cooling subsystem~s) inoperable.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct breaker alignments and 7 days voltage to required AC and 125 VDC electrical power distribution subsystems.
| |
| JAFNPP 3.8.8-2 Amendment 274 Refueling Equipment Interlocks 3.9.1 3.9 REFUELING OPERATIONS
| |
| | |
| ====3.9.1 Refueling====
| |
| | |
| Equipment Interlocks LCO 3.9.1 APPLICABILITY:
| |
| The refueling equipment interlocks associated with the reactor mode switch in the refuel position shall be OPERABLE.During in-vessel fuel movement with equipment associated with the interlocks when the reactor mode switch is in the refuel position.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Suspend in-vessel Immediately refueling equipment fuel movement with interlocks inoperable.
| |
| equipment associated with the inoperable interlockts).
| |
| OR A.2.1 Insert a control rod Immediately withdrawal block.AND A.2.2 Verify all control Immediately rods are fully inserted.JAFNPP 3.9.1-1 Amendment 274 Refueling Equipment Interlocks
| |
| | |
| ====3.9.1 SURVEILLANCE====
| |
| | |
| REQUIREMENTS SURVEILLANCE FREQUENCY 4.SR 3.9.1.1 Perform CHANNEL FUNCTIONAL TEST on each of the following required refueling equipment interlock inputs: 7 days a. All-rods-in.
| |
| : b. Refuel platform position.c. Refuel platform fuel grapple, fuel loaded, d. Refuel platform fuel grapple not fully up, e. Refuel platform frame mounted hoist, fuel loaded, and f. Refuel platform trolley mounted (monorail) hoist, fuel loaded.JAFNPP 3.9.1-2 Amendment 274 Refuel Position One-Rod-Out Interlock 3.9.2 3.9 REFUELING OPERATIONS
| |
| | |
| ====3.9.2 Refuel====
| |
| Position One-Rod-Out Interlock LCO 3.9.2 The refuel position one-rod-out interlock shall be OPERABLE.APPLICABILITY:
| |
| MODE 5 with the reactor mode switch in the and any control rod withdrawn.
| |
| refuel position ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Refuel position one- A.1 Suspend control rod Immediately rod-out interlock withdrawal.
| |
| inoperable.
| |
| AND A.2 Initiate action to Immediately fully insert all insertable control rods in core cells containing one or more fuel assemblies.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Verify reactor mode switch locked in refuel 12 hours position.(continued)
| |
| JAFNPP 3.9.2-1 Amendment 274 Refuel Position One-Rod-Out Interlock 3.9.2 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.9.2.2 -------------------
| |
| NOTE--------------------
| |
| Not required to be performed until 1 hour after any control rod is withdrawn.
| |
| ...........................................
| |
| Perform CHANNEL FUNCTIONAL TEST. 7 days JAFNPP 3.9.2-2 Amendment 274 Control Rod Position 3.9.3 3.9 REFUELING OPERATIONS
| |
| | |
| ====3.9.3 Control====
| |
| Rod Position LCO 3.9.3 APPLICABILITY:
| |
| All control rods shall be fully inserted.When loading fuel assemblies into the core.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more control A.1 Suspend loading fuel Immediately rods not fully assemblies into the inserted.
| |
| core.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Verify all control rods are fully inserted.
| |
| 12 hours JAFNPP 3.9.3-1 Amendment 274 Control Rod Position Indication 3.9.4 3.9 REFUELING OPERATIONS
| |
| | |
| ====3.9.4 Control====
| |
| Rod Position Indication LCO 3.9.4 The control rod "full-in" position indication channel for each control rod shall be OPERABLE.APPLICABILITY:
| |
| MODE 5.ACTIONS-------------------------------------
| |
| NOTE-------------------------------------
| |
| Separate Condition entry is allowed for each channel.~~... ..... .... ..... ..... .... ... ........ ... ...CONDITION REQUIRED ACTION COMPLETION TIME A. One or more control A.1.1 Suspend in-vessel Immediately rod position fuel movement.indication channels inoperable.
| |
| AND A.1.2 Suspend control rod Immediately withdrawal.
| |
| AND A.1.3 Initiate action to Immediately fully insert all insertable control rods in core cells containing one or more fuel assemblies.
| |
| OR (continued)
| |
| JAFNPP 3.9.4-1 Amendment 274 Control Rod Position Indication
| |
| | |
| ====3.9.4 ACTIONS====
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
| |
| A.2.1 Initiate action to Immediately fully insert the control rod associated with the inoperable position indicator.
| |
| AND A.2.2 Initiate action to Immediately disarm the control rod drive associated with the fully inserted control rod.SURVEILLANCE REQUIREMENT SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify the channel has no "full-in" Each time the indication on each control rod that is not control rod is"full-in." withdrawn from the "full-in'position JAFNPP 3.9.4-2 Amendment 274 Control Rod OPERABILITY
| |
| -Refueling 3.9.5 3.9 REFUELING OPERATIONS
| |
| | |
| ====3.9.5 Control====
| |
| Rod OPERABILITY-Refueling LCO 3.9.5 APPLICABILITY:
| |
| Each withdrawn control rod shall be OPERABLE.MODE 5.ACTIONS .CONDITION REQUIRED ACTION COMPLETION TIME A. One or more withdrawn A.1 Initiate action to Immediately control rods fully insert inoperable.
| |
| inoperable withdrawn control rods.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 ------------------
| |
| NOTE---------------------
| |
| Not required to be performed until 7 days after the control rod is withdrawn.
| |
| Insert each withdrawn control rod at least 7 days one notch.SR 3.9.5.2 Verify each withdrawn control rod scram 7 days accumulator pressure is 2 940 psig.JAFNPP 3.9.5-1 Amendment 274 RPV Water Level 3.9.6 3.9 REFUELING OPERATIONS
| |
| | |
| ====3.9.6 Reactor====
| |
| Pressure Vessel (RPV) Water Level LCO 3.9.6 APPLICABILITY:
| |
| RPV water level shall be 2 22 ft 2 inches above the top of the RPV flange.During movement of irradiated fuel assemblies within the RPV, During movement of new fuel assemblies or handling of control rods within the RPV, when irradiated fuel assemblies are seated within the RPV.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RPV water level not A.1 Suspend movement of Immediately within limit. fuel assemblies and handling of control rods within the RPV.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify RPV water level is 2 22 ft 2 inches 24 hours above the top of the RPV flange.JAFNPP 3.9.6-1 Amendment 274
| |
| -RHR- High Water Level 3.9.7 3.9 REFUELING OPERATIONS
| |
| | |
| ====3.9.7 Residual====
| |
| Heat Removal (RHR)- High Water Level LCO 3.9.7 APPLICABILITY:
| |
| One RHR shutdown cooling subsystem shall be OPERABLE.MODE 5 with irradiated fuel in the reactor pressure vessel (RPV) and the water level 2 22 ft 2 inches above the top of the RPV flange.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required RHR shutdown A.1 Verify an alternate 1 hour cooling subsystem method of decay heat inoperable.
| |
| removal is available.
| |
| AND Once per 24 hours thereafter B. Required Action and B.1 Suspend loading Immediately associated Completion irradiated fuel Time of Condition A assemblies into the not met. RPV.AND B.2 Initiate action to Immediately restore secondary containment to OPERABLE status.AND (continued)
| |
| JAFNPP 3.9.7-1 Amendment 274 RHR- High Water Level 3.9.7 ACTIONS .CONDITION REQUIRED ACTION COMPLETION TIME B. (continued)
| |
| B.3 Initiate action to Immediately restore one standby gas treatment subsystem to OPERABLE status.AND B.4 Initiate action to Immediately restore isolation capability in each required secondary containment penetration flow path not isolated.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.7.1 Verify each required RHR shutdown cooling 31 days subsystem manual, power operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, is in the correct position, or can be aligned to the correct position.JAFNPP 3.9.7-2 Amendment 274 RHR- Low Water Level 3.9.8 3.9 REFUELING OPERATIONS
| |
| | |
| ====3.9.8 Residual====
| |
| Heat Removal (RHR) -Low Water Level LCO 3.9.8 APPLICABILITY:
| |
| Two RHR shutdown cooling subsystems shall be OPERABLE.MODE 5 with irradiated fuel in the reactor pressure vessel (RPV) and the water level < 22 ft 2 inches above the top of the RPV flange.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or two required A.1 Verify an alternate 1 hour RHR shutdown cooling method of decay heat subsystems inoperable.
| |
| removal is available AND for each inoperable required RHR shutdown Once per cooling subsystem.
| |
| 24 hours thereafter B. Required Action and B.1 Initiate action to Immediately associated Completion restore secondary Time of Condition A containment to not met. OPERABLE status.AND B.2 Initiate action to Immediately restore one standby gas treatment subsystem to OPERABLE status.AND (continued)
| |
| JAFNPP 3.9.8-1 Amendment 274 RHR- Low Water Level 3.9.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued)
| |
| B.3 Initiate action to Immediately restore isolation capability in each required secondary containment penetration flow path not isolated.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.8.1 Verify each RHR shutdown cooling subsystem 31 days manual, power operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, is in the correct position, or can be aligned to the correct position.JAFNPP 3.9.8-2 Amendment 274 Inservice Leak and Hydrostatic Testing Operation 3.10.1 3.10 SPECIAL OPERATIONS 3.10.1 Inservice Leak and Hydrostatic Testing Operation LCO 3.10.1 The average reactor coolant temperature specified in Table 1.1-1 for MODE 4 may be changed to "NA," and operation considered not to be in MODE 3; and the requirements of LCO 3.4.8, "Residual Heat Removal (RHR) Shutdown Cooling System -Cold Shutdown," may be suspended to allow reactor coolant temperature
| |
| > 212
| |
| * F:* For performance of an inservice leak or hydrostatlc test," As a consequence of maintaining adequate pressure for an inservice leak or hydrostatic test, or" As a consequence of maintaining adequate pressure for control rod scram time testing Initiated in conjunction with an Inservice leak or hydrostatic test, provided the following MODE 3 LCOs are met: a. LCO 3.3.6.2, "Secondary Containment Isolation Instrumentation," Functions 1, 3, and 4 of Table 3.3.6.2-1;
| |
| : b. LCO 3.6.4.1, "Secondary Containment';
| |
| : c. LCO 3.6.4.2, -Secondary Containment Isolation Valves (SCIVs)";and d. LCO 3.6.4.3, "Standby Gas Treatment (SGT) System." APPLICABIUTY:
| |
| MODE 4 with average reactor coolant temperature
| |
| > 212°F.JAFNPP 3.10.1-1 Amendment 288 Inservice Leak and Hydrostatic Testing Operation 3.10.1 ACTIONS-----------------------------------
| |
| NOTE-------------------------------------
| |
| Separate Condition entry is allowed for each requirement of the LCO.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 --------NOTE---------
| |
| above requirements not Required Actions to met. be in MODE 4 include reducing average reactor coolant temperature to s 212'F......................
| |
| Enter the applicable Immediately Condition of the affected LCO.OR A.2.1 Suspend activities Immediately that could increase the average reactor coolant temperature or pressure.AND A.2.2 Reduce average 24 hours reactor coolant temperature to s 212 0 F.JAFNPP 3.10.1-2 Amendment 274 Inservice Leak and Hydrostatic Testing Operation 3.10.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.1.1 Perform the applicable SRs for the required According to MODE 3 LCOs. the applicable SRs JAFNPP 3.10.1-3 Amendment 274 Reactor Mode Switch Interlock Testing 3.10.2 3.10 SPECIAL OPERATIONS 3.10.2 Reactor Mode Switch Interlock Testing LCO 3.10.2 The reactor mode switch position specified in Table 1.1-1 for MODES 3, 4. and 5 may be changed to include the run, startup/hot standby, and refuel position, and operation considered not to be in MODE 1 or 2. to allow testing of instrumentation associated with the reactor mode switch interlock functions, provided: a. All control rods remain fully inserted in core cells containing one or more fuel assemblies; and b. No CORE ALTERATIONS are in progress.APPLICABILITY:
| |
| MODES 3 and 4 with the reactor mode startup/hot standby, or refuel MODE 5 with the reactor mode switch startup/hot standby position.switch in the run, position.in the run or ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 Suspend CORE Immediately above requirements not ALTERATIONS except met. for control rod insertion.
| |
| AND A.2 Fully insert all 1 hour insertable control rods in core cells containing one or more fuel assemblies.
| |
| AND (continued)
| |
| JAFNPP 3.10.2-1 Amendment 274 Reactor Mode Switch Interlock Testing 3.10.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
| |
| A.3.1 Place the reactor 1 hour mode switch in the shutdown position.OR A.3.2 ---- NOTE---------
| |
| Only applicable in MODE 5.Place the reactor 1 hour mode switch in the refuel position.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.2.1 Verify all control rods are fully inserted 12 hours in core cells containing one or more fuel assemblies.
| |
| SR 3.10.2.2 Verify no CORE ALTERATIONS are in progress.
| |
| 24 hours JAFNPP 3.10.2-2 Amendment 274 Single Control Rod Withdrawal
| |
| -Hot Shutdown 3.10.3 3.10 SPECIAL OPERATIONS 3.10.3 Single Control Rod Withdrawal
| |
| -Hot Shutdown LCO 3.10.3 The reactor mode switch position specified in Table 1.1-1 for MODE 3 may be changed to include the refuel position, and operation considered not to be in MODE 2, to allow withdrawal of a single control rod, provided the following requirements are met: a. LCO 3.9.2. "Refuel Position One-Rod-Out Interlock":
| |
| : b. LCO 3.9.4. "Control Rod Position Indication";
| |
| : c. All other control rods are fully inserted; and d. 1. LCO 3.3.1.1, "Reactor Protection System (RPS)Instrumentation," MODE 5 requirements for Functions l.a. 1.b, 7.a. 7.b, 10, and 11 of Table 3.3.1.1-1, and LCO 3.9.5. "Control Rod OPERABILITY-Refueling," OR 2. All other control rods in a five by five array centered on the control rod being withdrawn are disarmed:
| |
| at which time LCO 3.1.1, SHUTDOWN MARGIN (SDM)," MODE 3 requirements, may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod.APPLICABILITY:
| |
| MODE 3 with the reactor mode switch in the refuel position.JAFNPP 3.10.3-1 Amendment 274
| |
| .-Single Control Rod Withdrawal
| |
| -Hot Shutdown 3.10.3 ACTIONS..- ----------------
| |
| NOTE--...................................
| |
| Separate Condition entry is allowed for each requirement of the LCO.CONDITION IREQUIRED ACTION [COMPLETION TIME A. One or more of the above requirements not met.A.1--------NOTES--------
| |
| : 1. Required Actions to fully insert all insertable control rods include placing the reactor mode switch in the shutdown position.2. Only applicable if the requirement not met is a required LCO.Enter the applicable Condition of the affected LCO.OR A.2.1 AND A.2.2 Initiate action to fully insert all insertable control rods.Place the reactor mode switch in the shutdown position.Immediately Immediately 1 hour JAFNPP 3.10.3-2 Amendment 274 Single Control Rod Withdrawal-Hot Shutdown 3.10.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.3.1 Perform the applicable SRs for the required According to LCOs. the applicable SRs SR 3.10.3.2 --------------
| |
| NOTE--------------------
| |
| Not required to be met if SR 3.10.3.1 is satisfied for LCO 3.10.3.d.1 requirements.
| |
| Verify all control rods, other than the 24 hours control rod being withdrawn, in a five by five array centered on the control rod being withdrawn, are disarmed.SR 3.10.3.3 Verify all control rods, other than the 24 hours control rod being withdrawn, are fully inserted.JAFNPP 3.10.3-3 Amendment 274 Single Control Rod Withdrawal
| |
| -Cold Shutdown 3.10.4 3.10 SPECIAL OPERATIONS 3.10.4 Single Control Rod Withdrawal-Cold Shutdown LCO 3.10.4 The reactor mode switch position specified in Table 1.1-1 for MODE 4 may be changed to include the refuel position, and operation considered not to be in MODE 2. to allow withdrawal of a single control rod, and subsequent removal of the associated control rod drive (CRD) if desired.provided the following requirements are met: a. All other control rods are fully inserted: b. 1. LCO 3.9.2, "Refuel Position One-Rod-Out Interlock." and LCO 3.9.4. "Control Rod Position Indication," OR 2. A control rod withdrawal block is inserted: c. 1. LCO 3.3.1.1, "Reactor Protection System (RPS)Instrumentation," MODE 5 requirements for Functions l.a. 1.b. 7.a, 7.b. 10, and 11 of Table 3.3.1.1-1, and LCO 3.9.5. "Control Rod OPERABILITY-Refueling," OR 2. All other control rods in a five by five array centered on the control rod being withdrawn are disarmed; at which time LCO 3.1.1. "SHUTDOWN MARGIN (SDM)." MODE 4 requirements.
| |
| may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod.APPLICABILITY:
| |
| MODE 4 with the reactor mode switch in the refuel position.JAFNPP 3.10.4-1 Amendment 274 Single Control Rod Withdrawal
| |
| -Cold Shutdown 3.10.4 ACTIONS......-----.-.-.--.....-.-....-.--...
| |
| NOTE--...................................
| |
| Separate Condition entry is allowed for each requirement of the LCO.CONDITION
| |
| [ REQUIRED ACTION COMPLETION TIME A. One or more of the above requirements not met with the affected control rod insertable.
| |
| A.1--------NOTES--------
| |
| : 1. Required Actions to fully insert all insertable control rods include placing the reactor mode switch in the shutdown position.2. Only applicable if the requirement not met is a required LCO.Enter the applicable Condition of the affected LCO.OR A.2.1 Initiate action to fully insert all insertable control rods.Immediately Immediately 1 hour AND A.2.2 Place the reactor mode switch in the shutdown position.(continued)
| |
| JAFNPP 3.10.4-2 Amendment 274 Single Control Rod Withdrawal-Cold Shutdown 3.10.4 ACTIONS (continued)
| |
| .CONDITION REQUIRED ACTION COMPLETION TIME B. One or more of the B.1 Suspend withdrawal of Immediately above requirements not the control rod and met with the affected removal of associated control rod not CRD.insertable.
| |
| AND B.2.1 Initiate action to Immediately fully insert all control rods.OR B.2.2 Initiate action to Immediately satisfy the requirements of this LCO.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.4.1 Perform the applicable SRs for the required According to LCOs. the applicable SRs SR 3.10.4.2 ------------
| |
| NOTE--------------------
| |
| Not required to be met if SR 3.10.4.1 is satisfied for LCO 3.10.4.c.1 requirements.
| |
| .. ..... ... ....... .. ..............
| |
| Verify all control rods. other than the 24 hours control rod being withdrawn, in a five by five array centered on the control rod being withdrawn, are disarmed.(continued)
| |
| JAFNPP 3.10.4-3 Amendment 274 Single Control Rod Withdrawal-Cold Shutdown 3.10.4 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.10.4.3 Verify all control rods, other than the 24 hours control rod being withdrawn, are fully inserted.SR 3.10.4.4 -------------------
| |
| NOTE-----------------
| |
| Not required to be met if SR 3.10.4.1 is satisfied for LCO 3.10.4.b.1 requirements.
| |
| ...........................................
| |
| Verify a control rod withdrawal block is 24 hours inserted.JAFNPP 3.10.4-4 Amendment 274 Single CRD Removal- Refueling 3.10.5 3.10 SPECIAL OPERATIONS 3.10.5 Single Control Rod Drive (CRD) Removal -Refueling LCO 3.10.5 The requirements of LCO 3.3.1.1, "Reactor Protection System (RPS) Instrumentation";
| |
| LCO 3.3.8.2. "Reactor Protection System (RPS) Electric Power Monitoring";
| |
| LCO 3.9.1,"Refueling Equipment Interlocks";
| |
| LCO 3.9.2. "Refuel Position One-Rod-Out Interlock";
| |
| LCO 3.9.4. "Control Rod Position Indication";
| |
| and LCO 3.9.5, "Control Rod OPERABILITY-Refueling," may be suspended in MODE 5 to allow the removal of a single CRD associated with a control rod withdrawn from a core cell containing one or more fuel assemblies, provided the following requirements are met: a. All other control rods are fully inserted: b. All other control rods in a five by five array centered on the withdrawn control rod are disarmed;c. A control rod withdrawal block is inserted and LCO 3.1.1, "SHUTDOWN MARGIN (SDM)," MODE 5 requirements.
| |
| may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod; and d. No other CORE ALTERATIONS are in progress.APPLICABILITY:
| |
| MODE 5 with LCO 3.9.5 not met.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 Suspend removal of Immediately above requirements not the CRD.met.AND (continued)
| |
| JAFNPP 3.10.5-1 Amendment 274 Single CRD Removal -Refueling 3.10.5 ACTIONS .CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
| |
| A.2.1 Initiate action to Immediately fully insert all control rods.OR A.2.2 Initiate action to Immediately satisfy the requirements of this LCO.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.5.1 Verify all control rods, other than the 24 hours control rod withdrawn for the removal of the associated CRD, are fully inserted.SR 3.10.5.2 Verify all control rods, other than the 24 hours control rod withdrawn for the removal of the associated CRD. in a five by five array centered on the control rod withdrawn for the removal of the associated CRD. are disarmed.SR 3.10.5.3 Verify a control rod withdrawal block is 24 hours inserted.SR 3.10.5.4 Perform SR 3.1.1.1. According to SR 3.1.1.1 (continued)
| |
| JAFNPP 3.10.5-2 Amendment 274
| |
| .Single CRD Removal -Refueling 3.10.5 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.10.5.5 Verify no other CORE ALTERATIONS are in 24 hours progress.JAFNPP 3.10.5-3 Amendment 274 Multiple Control Rod Withdrawal
| |
| -Refueling 3.10.6 3.10 SPECIAL OPERATIONS 3.10.6 Multiple Control Rod Withdrawal-Refueling LCO 3.10.6 The requirements of LCO 3.9.3. "Control Rod Position";
| |
| LCO 3.9.4, "Control Rod Position Indication";
| |
| and LCO 3.9.5."Control Rod OPERABILITY-Refueling," may be suspended.
| |
| and the "full-in" position indicators may be bypassed for any number of control rods in MODE 5, to allow withdrawal and removal of these control rods, removal of associated control rod drives (CRDs), or both, provided the following requirements are met: a. The four fuel assemblies are removed from the core cells associated with each control rod or CRD to be removed;b. All other control rods in core cells containing one or more fuel assemblies are fully inserted; and c. Fuel assemblies shall only be loaded in compliance with an approved spiral reload sequence.APPLICABILITY:
| |
| MODE 5 with LCO 3.9.3. LCO 3.9.4. or LCO 3.9.5 not met.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 Suspend withdrawal of Immediately above requirements not control rods and met. removal of associated CRDs.AND A.2 Suspend loading fuel Immediately assemblies.
| |
| AND (continued)
| |
| JAFNPP 3.10.6-1 Amendment 274
| |
| -Multiple Control Rod Withdrawal
| |
| -Refueling 3.10.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
| |
| A.3.1 Initiate action to Immediately fully insert all control rods in core cells containing one or more fuel assemblies.
| |
| OR A.3.2 Initiate action to Immediately satisfy the requirements of this LCO.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.6.1 Verify the four fuel assemblies are removed 24 hours from core cells associated with each control rod or CRD removed.SR 3.10.6.2 Verify all other control rods in core cells 24 hours containing one or more fuel assemblies are fully inserted.SR 3.10.6.3 -------------------
| |
| NOTE--------------------
| |
| Only required to be met during fuel loading.... .......................................................................
| |
| .Verify fuel assemblies being loaded are in 24 hours compliance with an approved spiral reload sequence.JAFNPP 3.10.6-2 Amendment 274
| |
| --Control Rod Testing- Operating 3.10.7 3.10 SPECIAL OPERATIONS 3.10.7 Control Rod Testing- Operating LCO 3.10.7 The requirements of LCO 3.1.6. "Rod Pattern Control." may be suspended to allow performance of SDM testing. control rod scram time testing, and control rod friction testing, provided: a. The banked position withdrawal sequence requirements of SR 3.3.2.1.8 are changed to require the control rod sequence to conform to the specified test sequence.OR b. The RWM is bypassed; the requirements of LCO 3.3.2.1."Control Rod Block Instrumentation," Function 2 are suspended; and conformance to the approved control rod sequence for the specified test is verified by a second licensed operator or other qualified member of the technical staff.APPLICABILITY:
| |
| MODES 1 and 2 with LCO 3.1.6 not met.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Suspend performance Immediately LCO not met. of the test and exception to LCO 3.1.6.JAFNPP 3.10.7-1 Amendment 274 Control Rod Testing -Operating 3.10.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 4 SR 3.10.7.1 -------------------
| |
| NOTE--------------------
| |
| Not required to be met if SR 3.10.7.2 satisfied.
| |
| Verify movement of control rods is in compliance with the approved control rod sequence for the specified test by a second licensed operator or other qualified member of the technical staff.During control rod movement SR 3.10.7.2 ----------------
| |
| NOTE----------------
| |
| Not required to be met if SR 3.10.7.1 satisfied.
| |
| Verify control rod sequence input to the Prior to RWM is in conformance with the approved control rod control rod sequence for the specified movement test.JAFNPP 3.10.7-2 Amendment 274 SDM Test -Refueling 3.10.8 3.10 SPECIAL OPERATIONS 3.10.8 SHUTDOWN MARGIN (SDM) Test -Refueling LCO 3.10.8 The reactor mode switch position specified in Table 1.1-1 for MODE 5 may be changed to include the startup/hot standby position, and operation considered not to be in MODE 2, to allow SDM testing, provided the following requirements are met: a. LCO 3.3.1.1, "Reactor Protection System Instrumentation," MODE 2 requirements for Functions 2.a and 2.d of Table 3.3.1.1-1:
| |
| : b. 1. LCO 3.3.2.1. "Control Rod Block Instrumentation." MODE 2 requirements for Function 2 of Table 3.3.2.1-1, with the banked position withdrawal sequence requirements of SR 3.3.2.1.8 changed to require the control rod sequence to conform to the SDM test sequence.OR 2. Conformance to the approved control rod sequence for the SDM test is verified by a second licensed operator or other qualified member of the technical staff;c. Each withdrawn control rod shall be coupled to the associated CRD: d. All control rod withdrawals during out of sequence control rod moves shall be made in notch out mode: e. No other CORE ALTERATIONS are in progress:
| |
| and f. CRD charging water header pressure ; 940 psig.APPLICABILITY:
| |
| MODE 5 with the reactor mode switch in startup/hot standby position.JAFNPP 3.10.8-1 Amendment 274
| |
| --SDM Test -Refueling 3.10.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ---- NOTE--------
| |
| -------------
| |
| NOTE------------
| |
| Separate Condition Rod worth minimizer may be entry is allowed for bypassed as allowed by each control rod. LCO 3.3.2.1. "Control Rod...................... .Block Instrumentation," if required, to allow insertion One or more of inoperable control rod and control rods not continued operation.
| |
| coupled to its ......associated CRD.A.1 Fully insert 3 hours inoperable control rod.AND A.2 Disarm the 4 hours associated CRD.B. One or more of the B.1 Place the reactor Immediately above requirements not mode switch in the met for reasons other shutdown or refuel than Condition A. position.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.8.1 Perform the MODE 2 applicable SRs for LCO According to 3.3.1.1, Functions 2.a and 2.d of Table the applicable 3.3.1.1-1.
| |
| SRs (continued)
| |
| JAFNPP 3.10.8-2 Amendment 274
| |
| .SDM Test -Refueling 3.10.8 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.10.8.2 --------- NOTE------------------
| |
| Not required to be met if SR 3.10.8.3 satisfied.
| |
| Perform the MODE 2 applicable SRs for According to LCO 3.3.2.1, Function 2 of Table 3.3.2.1-1.
| |
| the applicable SRs SR 3.10.8.3 -------------------
| |
| NOTE--------------------
| |
| Not required to be met if SR 3.10.8.2 satisfied.
| |
| Verify movement of control rods is in During control compliance with the approved control rod rod movement sequence for the SDM test by a second licensed operator or other qualified member of the technical staff.SR 3.10.8.4 Verify no other CORE ALTERATIONS are in 12 hours progress.(continued)
| |
| JAFNPP 3.10.8-3 Amendment 274 SDM Test -Refueling 3.10.8 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.10.8.5 Verify each withdrawn control rod does not Each time the go to the withdrawn overtravel position.
| |
| control rod is withdrawn to"full-out" position AND Prior to satisfying LCO 3.10.8.c requirement after work on control rod or CRD System that could affect coupling SR 3.10.8.6 Verify CRD charging water header pressure 7 days 2 940 psig.JAFNPP 3.10.8-4 Amendment 274 Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location 4.1.1 Site and Exclusion Area Boundaries The Site and Exclusion Area Boundaries coincide with each other and shall be as shown on Figure 4.1-1.4.1.2 Low Population Zone (LPZ)The LPZ shall be a 4 mile radius around the Nine Mile Point Nuclear Station Unit 1 stack.4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 560 fuel assemblies.
| |
| Each assembly shall consist of a matrix of Zircaloy or ZIRLO fuel rods with an initial composition of natural or slightly enriched uranium dioxide (U0 2) as fuel material, and water rods. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods. in accordance with approved applications of fuel rod configurations.
| |
| may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with NRC staff approved codes and methods and have been shown by tests or analyses to comply with all safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.4.2.2 Control Rod Assemblies The reactor core shall contain 137 cruciform shaped control rod assemblies.
| |
| The control material shall be boron carbide or hafnium metal as approved by the NRC.(continued)
| |
| JAFNPP 4.0-1 Amendment 274
| |
| -.Design Features 4.0 4.0 DESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with: a. Fuel assemblies having a maximum k-infinity of 1.32 in the normal reactor core configuration at cold conditions (20 0 C);b. ke 0.95 if fully flooded with unborated water.which includes an allowance for uncertainties as described in Section 9.3 of the UFSAR: and c. A nominal 6.625 inch center to center distance between fuel assemblies placed in the aluminum high density storage racks, and a nominal 6.355 inch center to center distance between fuel assemblies placed in the stainless steel high density storage racks.4.3.1.2 The new fuel storage racks are designed and shall be maintained with: a. Fuel assemblies having a maximum k-infinity of 1.31 in the normal reactor core configuration at cold conditions (20 0 C): b. keff s 0.90 if dry: c. kef, 0.95 if fully flooded with unborated water;and d. A nominal 6.625 inch center to center distance between fuel assemblies placed in storage racks.4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 344 ft 6 inches.(continued)
| |
| JAFNPP 4.0-2 Amendment 274 Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage (continued)
| |
| | |
| ====4.3.3 Capacity====
| |
| The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 3239 fuel assemblies.
| |
| JAFNPP 4.0-3 Amendment 274 Design Features 4.0 LAKE ONTARIO sit & xcw.SGI S7ARA wUOARY Figure 4.1-1 (page 1 of 1)Site and Exclusion Area Boundaries JAFNPP 4.0-4 Amendment 274 Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The plant manager shall be responsible for overall plant operation and shall delegate in writing the succession to this responsibility during his absence.The plant manager or his designee shall approve, prior to implementation, each proposed test, experiment, and modification to systems or equipment that affect nuclear safety.5.1.2 The shift supervisor (SS) shall be responsible for the control room command function.
| |
| During any absence of the SS from the control room while the plant is in MODE 1, 2, or 3. an individual with an active Senior Reactor Operator (SRO) license shall be designated to assume the control room command function.
| |
| During any absence of the SS from the control room while the plant is in MODE 4 or 5, an individual with an active SRO license or Reactor Operator license shall be designated to assume the control room command function.JAFNPP 5.1-1 Amendment 274 Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization
| |
| | |
| ====5.2.1 Onsite====
| |
| and Offsite Organizations Onsite and offsite organizations shall be established for plant operation and corporate management, respectively.
| |
| The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant.a. Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions.
| |
| These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.
| |
| These requirements, including the plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications, shall be documented in the UFSAR;b. The plant manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant;c. The chief nuclear officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety; and d. The individuals who train the operating staff, carry out radiation protection, or perform quality assurance functions may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures.
| |
| | |
| ====5.2.2 Plant====
| |
| Staff The plant staff organization shall include the following:
| |
| : a. At least one non-licensed operator shall be on site when the plant is in MODE 4 or 5. At least two non-licensed operators shall be on site when the plant is in MODE 1. 2.or 3.(continued)
| |
| JAFNPP 5.2-1 Amendment 274 Organization 5.2 5.2 Organization
| |
| | |
| ====5.2.2 Plant====
| |
| Staff (continued)
| |
| : b. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a and 5.2.2.f for a period of time not to exceed 2 hours in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.
| |
| : c. A radiation protection technician shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours, in order to provide for unexpected absence, provided immediate action is taken to fill the required position.d. Administrative procedures shall be developed and implemented to limit the working hours of personnel who perform safety related functions (e.g., licensed Senior Reactor Operators (SROs), licensed Reactor Operators (ROs). radiation protection technicians, auxiliary operators, and key maintenance personnel).
| |
| The controls shall include guidelines on working hours that ensure adequate shift coverage shall be maintained without routine heavy use of overtime.Any deviation from the working hour guidelines shall be authorized in advance by the plant manager or the plant manager's designee, in accordance with approved administrative procedures, and with documentation of the basis for granting the deviation.
| |
| Routine deviation from the working hour guidelines shall not be authorized.
| |
| Controls shall be included in the procedures to require a periodic independent review be conducted to ensure that excessive hours have not been assigned.e. The operations manager or assistant operations manager shall hold an SRO license.f. When the plant is in MODE 1, 2. or 3. an individual shall provide advisory technical support to the shift supervisor (SS) in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the plant. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift, published in the October 28. 1985 Federal Register (50 FR 43621).JAFNPP 5.2-2 Amendment 274 Plant Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Plant Staff Qualifications 5.3.1 Each member of the plant staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions except for the radiation protection manager, who shall meet or exceed the qualifications of Regulatory Guide 1.8, Revision 1. September 1975.5.3.2 For the purpose of 10 CFR 55.4. a licensed Senior Reactor Operator (SRO) and a licensed Reactor Operator (RO) are those individuals who, in addition to meeting the requirements of TS 5.3.1. perform the functions described in 10 CFR 50.54(m).JAFNPP 5.3-1 Amendment 274 Procedures 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Procedures
| |
| | |
| ====5.4.1 Written====
| |
| procedures shall be established, implemented.
| |
| and maintained covering the following activities:
| |
| : a. The applicable procedures recommended in Regulatory Guide 1.33, Appendix A. November 1972;b. The emergency operating procedures required to implement the requirements of NUREG-0737 and NUREG-0737.
| |
| Supplement
| |
| : 1. as stated in Generic Letter 82-33;c. Quality assurance program for radioactive effluent and radiological environmental monitoring;
| |
| : d. Fire Protection Program implementation; and e. All programs specified in Specification 5.5.JAFNPP 5.4-1 Amendment 274 Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs and manuals shall be established, implemented and maintained.
| |
| | |
| ====5.5.1 Offsite====
| |
| Dose Calculation Manual (ODCM)a. The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints.
| |
| and in the conduct of the radiological environmental monitoring program: and b. The ODCM shall also contain the radioactive effluent controls and radiological environmental monitoring activities and descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by Specification 5.6.2 and Specification 5.6.3.c. Licensee initiated changes to the ODCM: 1. Shall be documented and records of reviews performed shall be retained.
| |
| This documentation shall contain: (a) sufficient information to support the change(s)together with the appropriate analyses or evaluations justifying the change(s), and (b) a determination that the change(s) maintain the levels of radioactive effluent control required pursuant to 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a. and 10 CFR 50, Appendix I. and not adversely impact the accuracy or reliability of effluent, dose. or setpoint calculations;
| |
| : 2. Shall become effective after the approval of the plant manager; and 3. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by (continued)
| |
| JAFNPP 5.5-1 Amendment 274 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.1 Offsite Dose Calculation Manual (ODCM)(continued) markings in the margin of the affected pages. clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.
| |
| Primary Coolant Sources Outside Containment 5.5.2 This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable.
| |
| The systems include the Core Spray, High Pressure Coolant Injection, Residual Heat Removal, Reactor Core Isolation Cooling, Reactor Water Cleanup, process sampling, and Standby Gas Treatment.
| |
| The program shall include the following:
| |
| : a. Preventive maintenance and periodic visual inspection requirements; and b. Integrated leak test requirements for each system at 24 month intervals or less.The provisions of SR 3.0.2 and SR 24 month Frequency for performing 3.0.3 are applicable integrated leak test to the activities.
| |
| 5.5.3 Not Used (continued)
| |
| JAFNPP 5.5-2 Amendment SAY 1 6 278 2003
| |
| --Programs and Manuals 5.5 5.5 Programs and Manuals (continued)
| |
| | |
| ====5.5.4 Radioactive====
| |
| | |
| Effluent Controls Program This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable.
| |
| The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded.
| |
| The program shall include the following elements: a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM: b. Limitations on the concentrations of radioactive material released in liquid effluents from the site to unrestricted areas, conforming to 10 times the concentration values in Appendix B. Table 2, Column 2 to 10 CFR 20.1001-20.2402:
| |
| : c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM;d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from the site to unrestricted areas, conforming to 10 CFR 50. Appendix I;e. Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days.Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCM at least every 31 days.f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I: (continued)
| |
| JAFNPP 5.5-3 Amendment 274 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)
| |
| : g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the site boundary shall be in accordance with the following:
| |
| : 1. For noble gases: a dose rate s 500 mrem/yr to the whole body and a dose rate s 3000 mrem/yr to the skin, and 2. For iodine-131, iodine-133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: a dose rate s 1500 mrem/yr to any organ;h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from the site to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I;i. Limitations on the annual and quarterly doses to a member of the public from iodine-131.
| |
| iodine-133, tritium, and all radionuclides in particulate form with half-lives
| |
| > 8 days in gaseous effluents released from the site to areas at or beyond the site boundary, conforming to 10 CFR 50, Appendix I;j. Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190: and k. Limitations on venting and purging of the primary containment through the Standby Gas Treatment System to maintain releases as low as reasonably achievable.
| |
| The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluent Controls Program Surveillance Frequency.
| |
| | |
| ====5.5.5 Component====
| |
| | |
| Cyclic or Transient Limit This program provides controls to track the UFSAR Section 4.2, cyclic and transient occurrences to ensure that components are maintained within the design limits.(continued)
| |
| JAFNPP 5.5-4 Amendment 274 Programs and Manuals 5.5 5.5 Programs and Manuals (continued)
| |
| | |
| ====5.5.6 Primary====
| |
| Containment Leakage Rate Testing Program This program implements the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J. Option B. as modified by approved exemptions.
| |
| This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995, as modified by the following exceptions:
| |
| * NEI 94-01-1995.
| |
| Section 9.2.3: The first Type A test performed after the March 7. 1995 Type A test shall be performEd-no later than March 7. 2010.* Type C testing of valves not isolable from the containment free air space may be accomplished by pressurization in the reverse direction, provided that testing in this manner provides equivalent or more conservative results than testing in the accident direction.
| |
| If potential atmospheric leakage paths (e.g., valve stem packing) are not subjected to test pressure, the portions of the valve not exposed to test pressure shall be subjected to leakage rate measurement during regularly scheduled Type A testing. A list of these valves, the leakage rate measurement method. and the acceptance criteria, shall be contained in the Program.a. The peak primary containment internal pressure for the design basis loss of coolant accident, Pa. is 45 psig.b. The maximum allowable primary containment leakage rate, Las at Pa. shall be 1.5% of containment air weight per day.c. The leakage rate acceptance criteria are: 1. Primary containment leakage rate acceptance criteria is< 1.0 La. During plant startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the Type B and Type C tests, and < 0.75 La for the Type A tests.2. Air lock testing acceptance criteria are: (a) Overall air lock leakage rate is < 0.05 La when tested at 2 Pa; and (b) For each door seal, leakage rate is < 120 scfd when tested at > Pa.(continued)
| |
| JAFNPP 5.5-5 Amendment 279 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.6 Primary Containment Leakage Rate Testing Program (continued)
| |
| : d. The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.e. Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50.Appendix J.Inservice Testing Program 5.5.7 This program provides controls for inservice testing of certain ASME Code Class 1. 2. and 3 pumps and valves. The program shall include the following:
| |
| : a. Testing Frequencies specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda are as follows: ASME Boiler and Pressure Vessel Code and applicable Addenda terminology for inservice testing activities Required Frequencies for performing inservice testing activities Weekly Monthly Quarterly or every 3 months Semiannually or every 6 months Every 9 months Yearly or annually Biennially or every 2 years b. The provisions of SR required Frequencies activities:
| |
| At least once At least once per 7 days per 31 days At least once per 92 days At At At least least least once once once per 184 days per 276 days per 366 days At least once per 731 days 3.0.2 are applicable to the above for performing inservice testing c. The provisions of SR 3.0.3 are applicable to inservice testing activities:
| |
| and (continued)
| |
| JAFNPP 5.5-6 Amendment 274 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 Inservice Testing Program (continued)
| |
| : d. Nothing in the ASME Boiler and Pressure Vessel code shall be construed to supersede the requirements of any TS.5.5.8 Ventilation Filter Testing Program (VFTP)This program implements the following required testing of Engineered Safeguards filter ventilation systems.The tests described in Specifications 5.5.8.a and 5.5.8.b shall be performed:
| |
| Once per 24 months;After each complete or partial replacement of the HEPA filter train or charcoal adsorber filter or after removal of a charcoal sample;After any structural maintenance on the HEPA filter or charcoal adsorber housing that could affect the filter system efficiency; and Following painting, fire, or chemical release that could adversely affect the ability of the filter system to perform the intended function in any ventilation zone communicating with the system.The tests described in Specification 5.5.8.c shall be performed:
| |
| Once per 24 months: After 720 hours of system operation:
| |
| After any structural maintenance on the charcoal adsorber housing that could affect the filter system efficiency:
| |
| and Following painting, fire, or chemical release that could adversely affect the ability of the charcoal filter system to perform the intended function in any ventilation zone communicating with the system.The tests described in Specifications 5.5.8.d and 5.5.8.e shall be performed once per 24 months.(continued)
| |
| JAFNPP 5.5-7 Amendment 274 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Ventilation Filter Testing Program (VFTP) (continued)
| |
| The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test Frequencies.
| |
| : a. Demonstrate for each of the Engineered Safeguards systems that an inplace test of the HEPA filters shows a penetration and system bypass less than the value specified below when tested in accordance with Sections C.5.a and C.5.c of Regulatory Guide 1.52, Revision 2. and ASME N510-1980 at the system flowrate specified below.Engineered Safeguards Ventilation System Penetration and System Bypass Flowrate (scfm)Standby Gas Treatment System Control Room Emergency Ventilation Air Supply System 1. 0%1.0%5.400 to 6.600 900 to 1.100 b. Demonstrate for each of the Engineered Safeguards systems that an inplace test of the charcoal adsorber shows a penetration and system bypass less than the value specified below when tested in accordance with Sections C.5.a and C.5.d of Regulatory Guide 1.52, Revision 2. and ASME N510-1980 at the system flowrate specified below.Engineered Safeguards Ventilation System Penetration and System Bypass Flowrate (scfm)Standby Gas Treatment System Control Room Emergency Ventilation Air Supply System 1. 0%0.5X 5.400 to 6,600 900 to 1.100 (continued)
| |
| JAFNPP 5.5-8 Amendment 274 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Ventilation Filter Testing Program (VFTP) (continued)
| |
| : c. Demonstrate for each of the Engineered Safeguards systems that a laboratory test of a sample of the charcoal adsorber, when obtained as described in Section C.6.b of Regulatory Guide 1.52. Revision 2, shows the methyl iodide penetration less than the value specified below when tested in accordance with ASTM D3803-1989 at a temperature of 30 0 C (86 0 F) and the relative humidity specified below.Engineered Safeguards Penetration RH Ventilation System Standby Gas 5% 2 70%Treatment System Control Room 5% 9 95%Emergency Ventilation Air Supply System d. Demonstrate for each of the Engineered Safeguards systems that the pressure drop across the combined HEPA filters and the charcoal adsorbers is less than the value specified below when tested at the system flowrate specified below: Engineered Safeguards Delta P Flowrate (scfm)Ventilation System (inches wg)Standby Gas 5.7 5,400 to 6,600 Treatment System Control Room 5.8 900 to 1,100 Emergency Ventilation Air Supply System e. Demonstrate that the heaters for the Standby Gas Treatment System dissipate
| |
| > 29 kW when tested in accordance with ASME N510-1975.(continued)
| |
| JAFNPP 5.5-9 Amendment 274 Programs and Manuals 5.5 5.5 Programs and Manuals (continued)
| |
| | |
| ====5.5.9 Explosive====
| |
| | |
| Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the Main Condenser Offgas Treatment System and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks.The program shall include: a. The limits for concentrations of hydrogen and oxygen in the Main Condenser Offgas Treatment System and a surveillance program to ensure the limits are maintained.
| |
| Such limits shall be appropriate to the system's design criteria (i.e., whether or not the system is designed to withstand a hydrogen explosion);
| |
| and b. A surveillance program to ensure that the quantity of radioactivity contained in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, or walls, capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste System is less than the amount that would result in a concentration that is 10 times the concentration values in Appendix B. Table 2. Column 2, to 10 CFR 20.1001-20.2402 (excluding tritium and dissolved or entrained noble gases) at the nearest potable water supply and the nearest surface water supply beyond the site boundary, in the event of an uncontrolled release of the tanks' contents.The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program Surveillance Frequencies.
| |
| 5.5.10 Diesel Fuel Oil Testing Program This program implements required testing of both new fuel oil and stored fuel oil. The program shall include sampling and testing requirements, and acceptance criteria, all in accordance with applicable ASTM Standards.
| |
| The purpose of the program is to establish the following: (continued)
| |
| JAFNPP 5.5-10 Amendment 274 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.10 Diesel Fuel Oil Testing Program (continued)
| |
| : a. Acceptability of new fuel oil for use prior to addition to storage tanks by determining that the fuel oil has: 1. An API gravity or an absolute specific gravity within limits, 2. A flash point and kinematic viscosity within limits for ASTM 2D fuel oil, and 3. A clear and bright appearance with proper color: b. Within 31 days following addition of the new fuel oil to storage tanks verify that the properties of the new fuel oil, other than those addressed in Specification 5.5.10.a above, are within limits for ASTM 2D fuel oil; and c. Total particulate concentration of the fuel oil is s 10 mg/l when tested every 31 days in accordance with the applicable ASTM Standard, except that the specified filters may be replaced with filters up to 3.0 microns.The provisions of SR 3.0.2 and SR 3.0.3,are applicable to the Diesel Fuel Oil Testing Program test Frequencies.
| |
| 5.5.11 Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.
| |
| : a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.b. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:
| |
| : 1. A change in the TS incorporated in the license; or 2. A change to the UFSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.(continued)
| |
| JAFNPP 5.5-11 Amendment 274 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Technical Specifications (TS) Bases Control Program (continued)
| |
| : c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.d. Proposed changes that meet the criteria of Specification 5.5.11.b above shall be reviewed and approved by the NRC prior to implementation.
| |
| Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).5.5.12 Safety Function Determination Program (SFDP)This program ensures loss of safety function is detected and appropriate actions taken. Upon entry into LCO 3.0.6. an evaluation shall be made to determine if loss of safety function exists. Additionally, other appropriate limitations and remedial or compensatory actions may be identified to be taken as a result of the support system inoperability and corresponding exception to entering supported system Condition and Required Actions. This program implements the requirements of LCO 3.0.6.a. The SFDP shall contain the following:
| |
| : 1. Provisions for cross division checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected;
| |
| : 2. Provisions for ensuring the plant is maintained in a safe condition if a loss of function condition exists;3. Provisions to ensure that an inoperable supported system's Completion Time is not inappropriately extended as a result of multiple support system inoperabilities:
| |
| and 4. Other appropriate limitations and remedial or compensatory actions.b. A loss of safety function exists when, assuming no concurrent single failure, no concurrent loss of offsite power or no concurrent loss of emergency diesel generator (continued)
| |
| JAFNPP 5.5-12 Amendment 274 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Safety Function Determination Program (SFDP) (continued) subsystems, a safety function assumed in the accident analysis cannot be performed.
| |
| For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and: 1. A required system redundant to system(s) supported by the inoperable support system is also inoperable:
| |
| or 2. A required system redundant to system(s) in turn supported by the inoperable supported system is also inoperable:
| |
| or 3. A required system redundant to support system(s) for the supported systems (1) and (2) above is also inoperable.
| |
| The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program.the appropriate Conditions and Required Actions of the ECO in which the loss of safety function exists are required to be entered. When a loss of safety function is caused by the inoperability of a single Technical Specification support system, the appropriate Conditions and Required Actions to enter are those of the support system.5.5.13 Configuration Risk Management Program (CRMP)The CRMP provides a proceduralized risk-informed assessment to manage the risk associated with equipment inoperability.
| |
| The program applies to technical specification structures, systems, or components for which a risk-informed allowed outage time has been granted. The program is to include the following:
| |
| : a. Provisions for the control and implementation of a Level 1 at-power internal events PRA-informed methodology.
| |
| The assessment is to be capable of evaluating the applicable plant configuration.
| |
| : b. Provisions for performing an assessment prior to entering the plant configuration described by the Limiting Condition for Operation (LCO) Condition(s) for preplanned activities.
| |
| : c. Provisions for performing an assessment after entering the plant configuration described by the LCO Condition(s) for unplanned entry into the LCO Condition(s).(continued)
| |
| JAFNPP 5.5-13 Amendment 274 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.13 'Configuration Risk Management Program (CRMP) (continued)
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| : d. Provisions for assessing the need for additional actions after the discovery of additional equipm~ent-out-of-service conditions while in the plant configuration descri bed by the LCO Condition(s).
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| : e. Provisions for considering other applicable risk significant contributors such as level 2 issues and external events, qualitatively or quantitatively.
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| 5.5.14 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation Air Supply (CREVAS) System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge.
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| The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem whole body or its equivalent to any part of the body for the duration of the accident.
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| The program shall include the following elements: a. The definition of the CRE and the CRE boundary.ýb. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.
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| C. Requirements for (i) determining the unfiltered air inleakage past 'the CRE boundary into the CRE in accordance with the testing methods and at the J Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197,"Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.d. Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the isolate mode of operation by one subsystem of the CREVAS System, operating at the flow rate required by the VFrP, at a Frequency of 18 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 18 month assessment of the CRE boundary.(continued)
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| JAFNPP 5.5-1-4 JAFNPP5.5-14Amendment nF~
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| Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14. Control Room Envelo~e, Habitability Program (continued)
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| : e. The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c.The'unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences.
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| Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.f. The provisions of SIR 3.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.
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| JAFNPP 5.5-15 JAFNP 5.-15Amendment 289 Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 5D.4.5.6.1 Not Used 5.6.2 Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report covering the operation of the plant during the previous calendar year shall be submitted by Hay 15 of each year. The report shall include summaries, interpretations.
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| and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (00CM), and in 10 CFR 50. Appendix I. Sections IV.B.2, IV.B.3. and The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period at the locations specified in the table and figures in the ODCH, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1.November 1979. In the event that some individual results are not available for inclusion with the report. the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.5.6.3 Radioactive Effluent Release Report The Radioactive Effluent Release Report covering the operation of the plant during the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the plant. The material provided shall be consistent with the objectives outlined in the ODCK and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I, Section IV.B.1.(continued)
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| JAFNPP 5.6-1 Amendment 282 Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.4 Not Used f 5.6.5 CORE OPERATING LIMITS REPORT (COLR)a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
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| : 1. The AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)of Specification 3.2.1;2. The MINIMUM CRITICAL POWER RATIO (MCPR) of Specification 3.2.2;3. The LINEAR HEAT GENERATION RATE (LHGR) of Specification 3.2.3: 4. The Reactor Protection System (RPS) APRN Neutron Flux _High (Flow Biased) Function Allowable Value of Table 3.3.1.1-1;
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| : 5. The Rod Block Monitor _ Upscale Function Allowable Value of Table 3.3.2.1-1; and 6. The Power/Flow Exclusion Region of Specification 3.4.1.b. The analytical methods used to determine the core operating limits shall be those previously reviewed and a pproved by the NRC, specifically those described in the following document: 1. NEDE-24011-P-A, General Electric Standard Application for Reactor Fuel;2. NEDC-31317P, James A. FitzPatrick Nuclear Power Plant SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis; and 3. NEDO-31960-A, BWR Owners' Group Long-Term Stability Solutions Licensing Methodology.
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| The COLR will contain the complete identification for each of the Technical Specification referenced topical reports used to prepare the COLR (i.e.. report number. title, revision, date. and any supplements).(continued)
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| JAFNPP 5.6-2 Amendment 282 Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)
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| : c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits.core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.d. The COLR, including any mridcycle revisions or supplements.
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| shall be provided upon issuance for each reload cycle to the NRC.5.6.6 PAM Report When a report is required by Condition B or F of LCO 3.3.3.1,'Post Accident Monitoring (PAM) Instrumentation,'
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| a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.AAFNPP 5.6-3 Amendment282 High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 10 CFR Part 20: 5.7.1 High Radiation Areas with dose rates not exceeding 1.0 rem/hour at 30 centimeters from the radiation source or from any surface penetrated by the radiation:
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| : a. Each entrance or access point to such an area shall be barricaded (e.g., roped off) and conspicuously posted as a high radiation area, or be continuously guarded to prevent unauthorized personnel entry. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.
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| : b. Access to, and activities in, each such area shall be controlled by means of a Radiation Work Permit (RWP) or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.c. Individuals qualified in radiation protection procedures and personnel continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assigned duties provided they are following plant radiation protection procedures for entry to, exit from, and work in such areas.d. Each individual or group entering such an area shall possess: 1. A radiation monitoring device that continuously displays radiation dose rates in the area; or 2. A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with a pre-set alarm setpoint, or 3. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area, or (continued)
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| JAFNPP 5.7-1 Amendment 274 High Radiation Area 5.7 5.7 High Radiation Area 5.7.1 High Radiation Areas with dose rates not exceeding 1.0 rem/hour at 30 centimeters from the radiation source or from any surface penetrated by the radiation: (continued)
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| : 4. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and.(a) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (b) Be under the surveillance, as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.
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| : e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination.
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| knowledge, and pre-job briefing does not require documentation prior to initial entry.5.7.2 High Radiation Areas with dose rates greater than 1.0 rem/hour at 30 centimeters from the radiation source or from any surface penetrated by the radiation, but less than 500 rads/hour at I meter from the radiation source or from any surface penetrated by the radiation:
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| : a. Each entrance or access point to such an area shall be conspicuously posted as a high radiation area and shall be (continued)
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| JAFNPP 5.7-2 Amendment 274 High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with dose rates greater than 1.0 rem/hour at 30 centimeters from the radiation source or from any surface penetrated by the radiation, but less than 500 rads/hour at 1 meter from the radiation source or from any surface penetrated by the radiation: (continued) provided with a locked door or gate that prevents unauthorized entry, or be continuously guarded to prevent unauthorized personnel entry, and, in addition: 1. All such door and gate keys shall be maintained under the administrative control of the shift manager, radiation protection manager, or designee.2. Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.b. Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.c. Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided they are following plant radiation protection procedures for entry to, exit from, and work in such areas.d. Each individual or group entering such an area shall possess: 1. A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with a pre-set alarm setpoint.
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| or 2. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area, or (continued)
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| JAFNPP 5.7-3 Amendment 274 High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with dose rates greater than 1.0 rem/hour at 30 centimeters from the radiation source or from any surface penetrated by the radiation, but less than 500 rads/hour at 1 meter from the radiation source or from any surface penetrated by the radiation: (continued)
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| : 3. A self reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and.(a) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (b) Be under the surveillance, as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area, or, 4. In those cases where options 2 and 3, above, are impractical or determined to be inconsistent with the"As Low As is Reasonably Achievable' principle, a radiation monitoring device that continuously displays radiation dose rates in the area may be used.e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to entry.f. Such individual areas that are within a larger area where no enclosure exists for the purpose of locking and where no enclosure can reasonable be constructed around the individual area need not be controlled by a locked door or gate, nor conspicuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible flashing light shaI b4eaCtivatedjat.
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| thparpa a2 wa2rninn djelvir _ .- -----JAFNPP 5.7-4 Amendment 274}}
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