Tech Specs

Triga fuel that contains a nominal 30 weight percent of uranium with a U-235 enrichment of < 20%, and erbium, a burnable poison

A time interval of 12 months, not to exceed 15 months

A quantitative examination of records, procedures or other documents after implementation from which appropriate recommendations are made

A time interval of 24 months, not to exceed 30 months

(1) change that is shown to alter the dose vs. depth profile of the fast neutron, thermal neutron, or gamma rays as sensed by the calibration check and

(2) to a change that has the potential to increase the amount of activation products in the BNC facility

a boron neutron capture experiment which utilizes the BNC facility, including neutron irradiation of biological cells that have been enriched with boron

boron neutron capture facility that includes the BNC neutron beam, bridge moving system, beam monitoring equipment, beam shielding room, access door and experimental area viewing equipment

the process of measuring intensity and energy spectrum of a BNC neutron beam

total fluence of neutrons and gamma radiation that is emitted by the BNC facility beam

any position of the research reactor greater than 4 feet away from the BNC beam port

a combination of sensor, line, amplifier, and output devices that are connected for the purpose of measuring the value of a parameter

an adjustment of a channel such that its output corresponds with acceptable accuracy to known values of the parameter that the channel measures, encompassing the entire channel and requiring a channel test

a qualitative verification of acceptable performance by observation of channel behavior, or other independent measure systems

the introduction of a signal into the channel to verify that it is operable

the reactor is critical with the fuel and pool at ambient temperature

an enclosure of the facility that is designed to limit the release if effluents between the enclosed area and its external environment through controlled or defined pathways

a device fabricated from neutron-absorbing material that is used to initiate neutron flux changes and to compensate for reactivity changes

a low-worth control rod fabricated from stainless, primarily used to maintain an intended power level and does not have scram capabilty

a control rod with scram capability and is capable of providing rapid reactivity insertion to produce a pulse. Positioned by controlled movement of a pneumatic cylinder

any control rod that has a scram capability, and is used to vary the reactivity of the core. Positioned by means of an electric motor operated positioning system

the number, type, or arrangement of fuel rods, reflector elements and regulating, transient or standard control rods occupying the core grid

the specific location in the WSU reactor core. A grid consisting of rows A through G and columns 1 through 9

that amount of reactivity added if all reactivity control devices were moved to the maximum reactive condition from the point at which the reactor is exactly critical at reference core conditions

any operation, hardware, or target which is designed to investigate non-routine reactor characteristics or is intended for irradiation within the pool, beam port, or irradiation facility

an experiment of which part or all of it is intended to be moved in or near the core or into and out of the reactor while the reactor is operating

held in a stationary position relative to the reactor by mechanical means or by gravity and is not readily movable

a cluster of three or four fuel rods fastened together in a square array by a top handle and a bottom grid plate adapter

a single TRIGA-type fuel rod of either standard or 30/20 fuel

any in-pool experimental facility which is not a normal part of the core and which is used to irradiate devices and materials

a fuel rod in which the thermocouples have been embedded for the purpose of measuring the fuel temperature during reactor operation

written authorization, the responsible authority, or an individual or organization to carry out the duties or responsibilities with a personal position, material or facility requiring licensing

part of the research facility building which is subject to the requirements of the WSU license R-76: reactor pool room (201) and the beam room

and individual or organization holding a license

the settings for automatic protective devices related to those variables having significant safety functions

the value of a parameter as it appears on the output of a measuring channel

the combination of a sensor, interconnecting cables or lines, amplifiers, and output devices that are connected for the purpose of measuring the value of a parameter

a core arrangement containing standard and 30/20 fuels

a time interval of 30 days, not to exceed 45

any location which is outside the site boundary

and location which is within the site boundary

a component or system is capable of performing its intended function

a test to determine whether a component or system is capable of performing its intended function

a component or system is performing its intended funtion

any arrangement of TRIGA fuel that is capable of operating within the maximum licensed power level and that satisfies all the requirements of the Tech Specs

the combination of fans, dampers, filters, ductwork and controls the provides controlled movement of air into and out of the reactor pool room

the initiation of a signal or the operation of equipment within the reactor safety system in response to a parameter or condition of the reactor facility having reached a specific limit

operation of the reactor with the mode selector switch in the pulse position

a time interval of three months, not to exceed four months

the structure that spans the research reactor pool to provide a support structure from which the research reactor is suspended

the value of the reactivity change which results from the experiment being inserted into or removed from its position

The reactor is not secured or shut down

an individual who is licensed to manipulate the controls of the reactor

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

When:

Either: there is insufficient moderator available in the reactor to attain criticality or there is insufficient fissible material present in the reactor to attain criticality under optimum available conditions of moderation and reflection;

Or:

(a) the reactor is shutdown

(b) all control rods fully inserted

(c) console key switch is in the off position and key removed from lock

(d) no work is in progress involving core fuel, core structure, installed control rods, or control rod drives unless they are physically decoupled from the control rods

(e) no experiments are being moved or serviced that have a reactivity worth equal to or greater that $1.00

it is subcritical by at least $1.00 in reference core condition with the reactivity worth of all installed experiments included

it is at ambient temperature (cold) and the reactivity worth of xenon is less than $0.30

(1) violation of a safety limit;

(2) release of fission product into the environment;

(3) release of radioactivity from the site above limits established by 10 CFR 20 or tech specs

(4) operation with actual safety system settings for required systems less conservative that specified in the tech specs;

(5) operation in violation of a Limiting Operating Condition listed in Section 3;

(6) operation with a required reactor or experiment safety system component in an inoperative or failed condition which renders or could render the system incapable of performing its intended safety function;

(7) an unanticipated or uncontrolled change in reactivity >$1.00;

(8) significant degradation in reactor fuel or cladding, or both, coolant boundary or confinement boundary;

(9) an observed inadequacy in the implementation of either 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

a device designed to support a self-sustaining neutron chain-reaction for research, development, education, training, or experimental purposes and that may have the provisions for the production of radioisotopes

all areas within which the owner or operator directs authorized activities associated with the reactor

a review is a qualitative examination and evaluation of records, procedures or other documents prior to implementation from which appropriate recommendations are made

a measuring channel in the reactor safety system

limits upon important process variables that are found to be necessary to reasonably protect the integrity of certain of the physical barriers that guard against the uncontrolled release of radioactivity

the elapsed time between the initiation of a scram signal and complete insertion of the slowest control rod

a time interval of 6 months, not to exceed 7.5 months

an individual licensed to direct the activities of reactor operators

respectively denoting: requirement, recommendation, and permission

TRIGA fuel containing a 8.5 weight% uranium with an enrichment of < 20%

any operation of the reactor with the mode selector switch in the manual or auto position

the actual value of a parameter

any location that is off-site

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 operations, not including shutdowns that occur during testing or checkout

a core grid position which does not have a fuel assembly, reflector, or experimental apparatus installed in the grid position

a time interval of 7 days, not to exceed 10 days