Term
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Definition
| That part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times. |
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Term
| DEFINE AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) |
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Definition
| Applicable to a specific planar height and is equal to the sum of the LHGRs for all fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the height. |
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Term
| DEFINE CHANNEL CALIBRATION |
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Definition
| "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. (see TS 1.1 for further guidance)" |
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Term
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Definition
| "The qualitative assessment, by observation, of channel behavior during operation. 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." |
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Term
| DEFINE CHANNEL FUNCTIONAL TEST |
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Definition
| "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. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps." |
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Term
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Definition
| The movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel. |
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Term
| DEFINE CORE OPERATING LIMITS REPORT (COLR) |
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Definition
| The unit 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 5.6.3. |
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Term
| DEFINE DOSE EQUIVALENT I-131 |
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Definition
| "That concentration of I-131 (microcuries/gram) that alone would produce the same dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I 135 actually present." |
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Term
| DEFINE Identified LEAKAGE |
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Definition
| "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 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." |
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Term
| DEFINE Unidentified LEAKAGE |
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Definition
| All LEAKAGE into the drywell that is not identified LEAKAGE. |
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Term
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Definition
| Sum of the identified and unidentified LEAKAGE. |
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Term
| DEFINE Pressure Boundary LEAKAGE |
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Definition
| "LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component, pipe wall, or vessel wall." |
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Term
| DEFINE LINEAR HEAT GENERATION RATE (LHGR) |
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Definition
| The heat generation rate per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length. |
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Term
| DEFINE LOGIC SYSTEM FUNCTIONAL TEST |
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Definition
| "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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Term
| DEFINE MINIMUM CRITICAL POWER RATIO (MCPR) |
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Definition
The smallest critical power ratio (CPR) that exists in the core for each class of fuel. NOTE: 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. |
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Term
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Definition
| "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." |
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Term
| DEFINE OPERABLE - OPERABILITY |
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Definition
| "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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Term
| DEFINE RATED THERMAL POWER (RTP) |
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Definition
| A total reactor core heat transfer rate to the reactor coolant of 1775 MWt |
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Term
| DEFINE REACTOR PROTECTION SYSTEM RESPONSE TIME |
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Definition
| "That time interval from initiation of any RPS channel trip to the de-energization of the scram pilot valve solenoids. 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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Term
| DEFINE SHUTDOWN MARGIN (SDM) |
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Definition
| "The amount of reactivity by which the reactor is subcritical or would be subcritical assuming that 1) the reactor is Xenon free, 2) Moderator temperature is 68 degrees F., 3) All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn. NOTE: with control rods not capable of being inserted, the reactivity worth of these control rods must be accounted for in the determination." |
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Term
| DEFINE STAGGERED TEST BASIS |
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Definition
| "The testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, 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." |
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Term
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Definition
| The total reactor core heat transfer rate to the reactor coolant. |
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Term
| DEFINE TURBINE BYPASS SYSTEM RESPONSE TIME |
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Definition
| That time interval from when the main turbine trip solenoid is activated until 80% of the turbine bypass capacity is established. |
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Term
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Definition
| That part of a Requirement that prescribes Required Actions to be taken under designated Conditions within specified Completion Times. |
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Term
| TRM DEFINITION: OPERABLE - OPERABILITY |
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Definition
| "A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified 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 function(s) are also capable of performing their related support function(s)." |
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Term
| Thermal Power Safety Limit with steam dome pressure < 785 psig OR core flow <10% rated core flow |
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Definition
| Core Thermal Power of less than or equal to 25% Rated Thermal Power |
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Term
| Two loop MCPR Safety limit with steam dome pressure greater than or equal to 785 psig AND core flow greater than or equal to 10% rated core flow. |
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Definition
| Greater than or equal to 1.15 |
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Term
| SINGLE LOOP MCPR Safety limit with steam dome pressure greater than or equal to 785 psig AND core flow greater than or equal to 10% rated core flow. |
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Definition
| Greater than or equal to 1.15 |
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Term
| Reactor Vessel water level Safety Limit |
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Definition
| Greater than the top of active irradiated fuel |
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Term
| "Reactor Coolant System Pressure Safety Limit (in other words, reactor steam dome pressure limit)" |
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Definition
| Less than or equal to 1332 psig |
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Term
| "With any safety limit violation, list the actions that SHALL be completed within 2 hours" |
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Definition
| 1) Restore compliance with all Safety Limits; 2) Insert all insertable control rods |
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Term
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Definition
| Title: Power operation; Reactor Mode Switch Position: Run; Temperature: N/A |
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Term
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Definition
Title: Startup Reactor Mode Switch Position: Refuel (with all reactor vessel head closure bolts fully tensioned) OR Startup/Hot Standby Temperature: N/A |
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Term
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Definition
| Title: Hot Shutdown (all reactor vessel head closure bolts fully tensioned); Reactor Mode Switch Position: Shutdown; Temperature: > 212 degrees |
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Term
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Definition
| Title: Cold Shutdown (all reactor vessel head closure bolts fully tensioned); Reactor Mode Switch Position: Shutdown; Temperature: less than or equal to 212 degrees. |
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Term
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Definition
| Title: Refueling (One or more reactor vessel head closure bolts less than fully tensioned); Reactor Mode Switch Position: Shutdown or refuel; Temperature: N/A |
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Term
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Definition
| Notices, Instructions and Reports to Workers: Inspection and Investigations |
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Term
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Definition
| Standards for Protection Against Radiation |
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Term
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Definition
| Domestic Licensing of Production and Utilization Facilities (Site License) |
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Term
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Definition
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Term
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Definition
| Physical Protection of Plants and Materials |
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Term
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Definition
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Term
| List the Tech Spec Requirements of 10CFR50 |
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Definition
Safety Limits, limiting safety system settings Limiting Conditions for Operation Surveillance Requirements Design Features Administrative Controls
6) Decommissioning; 7) Initial Notification; 8) Written Reports
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Term
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Definition
| Limiting Conditions for Operation: the lowest functional capability or performance levels of equipment required for safe operation of the facility. |
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Term
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Definition
| "A Tech Spec LCO must be established for each item meeting one or more of the following criteria: INSTALLED INSTRUMENTATION that is used to detect, and indicate in the control room, a significant, abnormal degradation of the reactor coolant pressure boundary." |
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Term
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Definition
A Tech Spec LCO must be established for each item meeting one or more of the following criteria: A process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. |
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Term
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Definition
| "A Tech Spec LCO must be established for each item meeting one or more of the following criteria: A structure, system or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier." |
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Term
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Definition
| "A Tech Spec LCO must be established for each item meeting one or more of the following criteria: a structure, system or component which operating experience or probablisitic risk analysis has shown to be significant to public health and safety." |
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Term
| Explain the acceptance criteria for ECCS |
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Definition
Peak cladding temperature: 2200º F Maximum cladding oxidation: shall nowhere exceed 0.17 times the total cladding thickness before oxidation Maximum hydrogen generation. The calculated total amount of hydrogen generated from the chemical reaction of the cladding with water or steam shall not exceed 0.01 times the hypothetical amount that would be generated if all of the metal in the cladding cylinders surrounding the fuel, excluding the cladding surrounding the plenum volume, were to react Coolable geometry Long-term cooling
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Term
| State the minimum Control Room staffing requirements for a single unit site |
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Definition
When operating: 2 SRO, 2 RO; When shutdown: 1 SRO, 1 RO. |
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