| A | B |
|---|
| Bottomed | A control rod is bottomed if it is resting on the carrier plate in the hydraulic buffer at the bottom of the core |
| Channel | A channel is the combination of sensor, line, amplifier, and output devices that are connected for the purpose of measuring the value of a parameter |
| Channel calibration | A channel calibraiton is an adjustment of the channel such that its output corresponds with acceptable accuracy to known values of the parameter that the channel measures. Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip, and shall be deemed to include a channel test |
| Channel check | A channel check is a qualitative verificaiton of acceptable performance by observation of channel behavior, or by comparison of the channel with other independent channels or systems measuring the same parameter |
| Channel test | A channel test is the introduciton of a signal into the channel for verification that it is operable. |
| Control rod | A control mechanism consisting of a stainless steel basket that houses two absorber sections, one above the other. These absorber sections contain boron in iron clad in stainless steel. All are the same dimensions, nominally 2.6 inches square, with their poisons uniformly distributed. When the control rods are bottomed the absorbers shall extend above the top and to within one inch of the bottom of the fueled portion of the core. |
| Core configuration | the core configuration includes the numbe,r type, and arrangement of fuel elements, and control rods occupying the core grid |
| Excess reactivity | Excess reactivity is that amount of reactivity that would exist if all reactivity control devices and movable experiments were moved to and moderator temperature changed to the maximum reactive condition from the point where the reactor is exactly critical (keff =1) at ambient temperature |
| Experiment | Any operation, hardware, or target (excluding devices such as detectors, foils, etc.) that is designed to investigate reactor characteristics or that is intended for irradiation within the reactor |
| Fail | A component or experiment has failed if it is no longer able to perform its intended function or causes the unintentional addition or removal or reactivity |
| Fully inserted | a contorl rod is fully inserted if it is within one inch of being bottomed. |
| Known core | A core configuration for which the power indicating instrumentaiton has been calibrated in accordance with surveillance procedures and the following parameters have been measured: 1. excess reactivity, 2. shutdown reactivity, all rods bottomed and one rod stuck in the full out position, 3. reactivity worth of most reactive fuel pin. |
| License | The written authorization, by the NRC, for an individual or organizaiton to carry out the duties and responsibilities associated with a personnel position, material, or facility requiring licensing |
| Measured value | The measured value is the value of a parameter as it appears ont he output of a channel |
| Movable experiment | a movalbe experiment is one where it is intended that all or part of the experiment may be moved in or near the core or into and out of the reactor while the reactor is operationg |
| Operable | Operable means a component or system is capable of performing its intended fuciton |
| Operating | Operating means a component or system is performing its intended fuciton |
| Protective action | The initiation of a singal or the operation of equipment withink the reactor safety system in response to a parameter or condition of the reactor facility having reached a specified limit |
| Reactivity worth of an experiment | The reactivity worth of an experiment is the value of the reactivity change that results from the experiment being inserted into or removed from its intended position |
| Reactor operating | The treactor is operating whenever the reactor tank contains moderatior and any fuel, and any contorl rod is not bottomed |
| Reactor operator (RO) | An individual who is deemed capable and qualified by the SRO on duty to manipulate the contorls of the reactor. The individual may be the SRO on duty, another SRO or someone without a Senior Reactor Operator License. |
| Reactor safety systems | Reactor safety systems are those systems, including their associated input channels, which are designed to initiate automatic reactor protection or to provide information for initiation of manual protective action. |
| Reactor secured | The reactor is secured when: 1 Either their is insufficient moderator available in the reactor to attain criticaility, all control rods are bottomed, and the console keys are removed, 2. Or all fuel pins have been removed form the reactor. |
| Reactor shutodwn | The reactor is shutdown if all contorl rods are bottomed and it is subcritical by at least 1.00 $ in the reference core condition with the reactivty worth of all installed experiments included |
| readily available on call | An operator is readily available on call if within 60 minutes normal travel time and 25 miles of the facility and personnel at the facility can readily contact the individual. |
| reference core condition | The condition of the core when it is at ambient temperature (cold) and the control rods are bottomed. |
| reportable occurrences | 1. Release of radioactivity from the facility above allowed limits; 2. Discovery of loose surface contamination, excluding contamination due to naturally occurring radionuclides such as radon daughters; 3. Operation with actual safety system setting less conservative than the limiting safety system settings; 4. Operation in violation of limiting conditions for operation; 5. Any reactor safety system component malfunction that could render the safety system incapable of performing its intended function; 6. An unanticipated or uncontrolled change in reactivity greater than 60 cents; or 7. An observed inadequacy in the implementation of administrative or procedural controls such that the inadequacy causes or could have caused the existence or development of an unsafe condition with regard to reactor operations. |
| review and approve | The reviewing group or persons shall carry out a review of the matter in question and may either approve or disapprove it. Before it can be implemented, the matter in question must receive approval from the reviewing group or persons. |
| safety channel | A channel in the reactor safety system. |
| scram time | Scram time is the elapsed time between the initiation of a scram signal and indication that the control rod has been at least fully inserted.. |
| secured experiment | A secured experiment is any experiment, experimental apparatus, or component of an experiment that is held in a stationary position relative to the reactor by mechanical means. The restraining forces must be substantially greater than those to which the experiment might be subjected by hydraulic, pneumatic, buoyant, or other forces that are normal to the operating environment of the experiment, or by forces that can arise because of credible malfunctions. |
| secured shutdown | The reactor is secured and the facility administrative requirements are met for leaving the facility with no licensed operators present.rted.. |
| senior reactor operator (SRO) | An individual who is licensed to direct the activities of reactor operators at the RCF. |
| shall, should, and may | The word "shall" is used to denote a requirement; the word "should" is used to denote a recommendation; and the word "may" is used to denote permission, neither a requirement nor a recommendation.� |
| shutdown marginn | Shutdown margin is the minimum shutdown reactivity necessary to provide confidence that the reactor can be made subcritical by means of the control and safety systems starting from any permissible operating condition and with the most reactive rod in the most reactive position, and that the reactor will remain subcritical without further operator action. |
| shutdown reactivitymay | The amount of reactivity the reactor is subcritical by given a specific set of conditions.3 |
| surveillance frequency | Unless otherwise stated in these specifications, periodic surveillance tests, checks, calibrations, and examinations shall be performed within the specified surveillance intervals. In cases where the elapsed interval has exceeded 100% of the specified interval, the next surveillance interval shall commence at the end of the original specified interval. Allowable surveillance intervals, as defined in ANSI/ANS 15.1 (2007) shall not exceed the following: 1. Annual (interval not to exceed 15 months). 2. Semiannual (interval not to exceed seven and one-half months). 3. Quarterly (interval not to exceed 4 months). 4. Monthly (interval not to exceed 6 weeks). 5. Daily prior to the first reactor startup of the day.c |
| surveillance intervaly | The surveillance interval is the calendar time between surveillance tests, checks, calibrations, and examinations to be performed upon an instrument or component when it is required to be operable. |
| true value | The true value is the actual value of a parameter. |
| unknown coreginn | Any core configuration that is not a known core. |
| unscheduled shutdownly | An unscheduled shutdown is defined as any unplanned shutdown of the reactor caused by actuation of the reactor safety system, operator error, equipment malfunction, or a manual shutdown in response to conditions that could adversely affect safe operation, not including shutdowns that occur during testing or checkout operations.ut |
