T.S4 Flashcards
4 SURVEILLANCE REQUIREMENTS
- 1 Reactor Core Parameters
- 1.1 Steady State Operation
Specifications: The surveillance requirements for the reactor safety systems that monitor reactor power level are described in Section 4.2.3.
4.1.2 Pulse Mode Operation
Specification:
The surveillance requirements in this section may be postponed during periods of reactor shutdown. If the surveillance requirement occurs during a period of reactor shutdown the surveillance shall be completed upon resumption of reactor operation.
(1) The maximum safe allowable reactivity insertion shall be calculated annually for an existing core and prior to pulsing a new or modified core arrangement.
(2) The reactor shall be pulsed semiannually to compare fuel temperature measurements and peak power levels with previous pulses of the same reactivity.
4.1.3 Shutdown Margin
The surveillance requirements in this section may be postponed during periods of reactor shutdown. If the surveillance requirement occurs during a period of reactor shutdown the surveillance shall be completed upon resumption of reactor operation.
(1) The reactivity worth of each control rod and the shutdown margin shall be determined annually.
(2) The reactivity worth of each control rod and the shutdown margin shall be determined after a change to the type or location of fuel, reflector, or control rods in the reference core, or after any change to the reference core that results in or could result in a change of reactivity of $0.25 or more.
(3) The reactivity worth of an experiment shall be estimated or measured, as appropriate, before reactor operation with the experiment.
4.1.4 Maximum Excess Reactivity
Specifications: The core excess reactivity shall be determined annually or following a change to the core that causes a change in reactivity greater than $0.25. This surveillance requirement may be postponed during periods of reactor shutdown. If this surveillance requirement occurs during a period of reactor shutdown the surveillance shall be completed upon resumption of reactor operation.
4.1.5 Core Configuration Limitation
Specifications:
(1) Proposed changes in core configuration shall be analyzed to determine whether amendments to the reactor license or Technical Specifications are required.
(2) Changes in fuel configuration shall be documented by a Safety Analysis Report and recorded in a fuel inventory log.
(3) Each change to the core configuration shall be evaluated to determine the allowed locations for the Instrumented Fuel Element.
4.1.6 Fuel Parameters
Specifications:
(1) At least 20% of the fuel rods comprising the core shall be visually inspected annually for damage or deterioration and annually measured for bowing or elongation such that each fuel rod in the core is inspected at least once over a five year period.
(2) The failure of a single fuel element to pass inspection shall trigger a required inspection of all fuel elements in the reactor core.
- 2 Reactor Control and Safety System
4. 2.1 Control Rods
Specifications:
The surveillance requirements in this section may be postponed during periods of reactor shutdown. If the surveillance requirement occurs during a period of reactor shutdown the surveillance shall be completed upon resumption of reactor operation.
(1) The control rods shall be visually inspected at biennial intervals.
(2) The scram time shall be measured annually.
(3) The transient rod drive cylinder and associated air supply system shall be inspected, cleaned, and lubricated semiannually.
4.2.2 Reactor Measuring Channels
Specifications:
(1) A channel test of each of the required operable measuring channels listed in Table 3.1 for
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the intended mode of operation shall be performed before each day’s operation or before each operation extending more than one day.
(2) A channel check of the fuel rod temperature measuring channel shall be made each time the reactor is operated in the steady state mode by comparing the indicated instrumented fuel rod temperature with previous indicated temperature values for the same core configuration and power level.
4.2.3 Reactor Safety System
Specifications:
The surveillance requirements in this section may be postponed during periods of reactor shutdown. If the surveillance requirement occurs during a period of reactor shutdown the surveillance shall be completed upon resumption of reactor operation.
(1) A channel test of each of the safety channels listed in Table 3.2, except for the bulk primary coolant temperature, for the intended mode of operation (steady-state or pulse) shall be performed before each day’s operation or before each operation extending more than one day.
(2) A channel check of the bulk primary coolant temperature shall be performed before each day’s operation or before operation extending more than one day.
(3) A test of the interlocks in Table 3.3 for the intended mode of operation (steady-state or pulse) shall be performed before each day’s operation or before each operation extending more than one day.
(4) A channel calibration of the fuel rod temperature measuring channel shall be performed semiannually by the substitution of a thermocouple simulator in place of the instrumented fuel rod thermocouple.
(5) A channel calibration shall be made of the power level monitoring channels annually or after a core configuration change, by the calorimetric method.
4.2.4 Pool Level Alarm
Specification: The reactor pool level alarm shall be monthly tested for operability.
4.3 Primary Coolant Conditions
Specifications:
(1) The conductivity of the primary coolant water shall be measured at least once every two weeks.
(2) The radionuclide content of the reactor pool water shall be monitored monthly. Steps shall be taken to isolate the source of the radioactivity and to mitigate the problem if the radionuclide content of the pool water in the reactor pool exceeds one-third (1/3) of the 10 CFR 20 Appendix B, Table 3 value.
4.4 Ventilation System
Specifications:
(1) The operation of the pool room ventilation system shall be checked monthly by cycling the system from the “normal” to the “isolate” and “dilution” modes of operation. The positions of the associated dampers, indicator display, and fan operation shall be visually checked to ensure correspondence between the device performance and selected mode of operation
(2) The pressure drop across the absolute filter in the pool room ventilation system shall be measured semiannually.
(3) The air flow rates in the ventilation system shall be measured biennially.
- 5 Radiation Monitoring System and Effluents
4. 5.1 Radiation Monitoring System
Specifications:
(1) All radiation monitoring systems shall be verified to be operable by a monthly channel test.
(2) The following surveillance activities shall be performed on an annual basis:
(a) The reactor bridge and beam room radiation monitoring system shall be calibrated using a certified radioactive source.
(b) A calibration shall be performed on the continuous air monitor in terms of counts per unit time per unit of radioactivity using calibrated beta-particle emitting sources.
(c) A calibration of the exhaust gas monitor system shall be done using at least two different calibrated gamma-ray sources.
4.5.2 Effluents
Specifications:
(1) The level of 41Ar in the effluent gas shall be continuously monitored during operation of the reactor.
(2) The environmental radiation monitoring program required by Section 3.5.2(2) shall measure the integrated radiation exposure in and around the Dodgen Research Facility on a quarterly basis.
(3) The radiation levels determined by the environmental monitoring program shall be tabulated and examined annually.
(4) The annual discharge of 41Ar shall be calculated annually.
(5) The continuous air monitor shall be continuously monitored during operation of the reactor.
(6) Before discharge, the facility liquid effluents collected in the holdup tanks shall be analyzed for their radioactivity content.
4.6 Limitations on Experiments
Specifications:
(1) The reactivity worth of moveable experiments shall be shown by measurement, testing, calculation, or comparison to other experiments, to be less than $1.00. This surveillance requirement shall be considered to be satisfied for subsequent movable experiments that exhibit the same characteristics as a previously analyzed moveable experiment.
(2) The reactivity worth of a secured experiment shall be shown by measurement, testing, calculation, or comparison to other experiments, to be less than $2.00. This surveillance requirement shall be considered to be satisfied for subsequent secured experiments when a measurement of an initial secured experiment is applied to subsequent secured experiments that are the same as the initially analyzed secured experiment.
(3) The sum of absolute values of all individual experiments shall be shown to be less than $5.00.
(4) The following surveillance requirements apply to use of explosive materials in experiments:
(a) The quantity of explosive materials (if any) used in an experiment shall be documented and shown to be less than 25 mg.
(b) Testing of explosive material encapsulation shall be documented and shown to be in accordance with Section 3.6 (4).
(5) A safety analysis shall document conformance to the requirements of Section 3.6(5).
(6) A safety analysis shall document conformance to the requirements of Section 3.6(6).
(7) A safety analysis shall document that the total radioactive inventory of the iodine isotopes 131 through 135 in a fueled experiment is less than 1.5 Ci.
(8) The results of an inspection and any corrective action taken following a sample failure that releases material that could damage reactor fuel or the reactor structure shall be reviewed by the facility Director and the Reactor Safeguards Committee and shall be determined to be satisfactory before operation of the reactor is resumed.
(9) Minor modifications to a reviewed and approved experiment may be made at the discretion the Reactor Supervisor, provided that the hazards associated with the modifications have been reviewed and a determination has been made and documented that the modifications do not create a significantly different, a new, or a greater hazard than the originally approved experiment.
