ML20113A160
| ML20113A160 | |
| Person / Time | |
|---|---|
| Site: | University of Texas at Austin |
| Issue date: | 06/06/1996 |
| From: | TEXAS, UNIV. OF, AUSTIN, TX |
| To: | |
| Shared Package | |
| ML20113A104 | List: |
| References | |
| NUDOCS 9606240139 | |
| Download: ML20113A160 (2) | |
Text
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t Revision 1 Technical Specifications '
5.0 DESIGN FEATURES l l 5,1 Site and Facility Description i
5.1.1 Location Specification (s) 1 I
- a. The site location is in the northeast corner of The University l of Texas at Austin J.J. Pickle Research Campus. I
- b. The TRICA reactor is installed in a designated room of a building constructed as a Nuclear Engineering Teaching Laboratory.
- c. The reactor core is assembled in an above ground shield and pool structure with horizontal and vertical access to the core.
- d. License areas of the facility for reactor operation shall consist of the room enclosing the reautor shield and pool structure, and the adj acent area for reactor control. (room 1.104, corridor 3.200; and rooms 3.202, 3.204, and 3.208) 5.1.2 Confinement Specification (s) I
- a. The reactor room shall be designed to restrict leakage and will have a minimum enclosed air volume of 4120 cubic meters.
- b. Ventilation system should provide two air changes per hour and shall isolate air in the reactor area upon detection of a limit signal related to the radiation level.
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- c. An air purge system should exhaust experiment air cavities and l shall be filtered by high efficiency particulate absorption filters,
- d. All exhaust air from the reactor area enclosure shall be ejected vertically upward at a point above the facility roof level.
5.1.3 Safety Related Systams 5.pecifications Any modifications to the air confinement or ventilation system, the reactor shield, the pool or its penetrations, the pool coolant system, l
the core and its associated support structure, the rod drive mechanisms or the reactor safety system shall be made and tested in accordance with the specifications to which the systems were l originally designed and fabricated. Alternate specifications may be l approved by the Nuclear Reactor Committee. A system shall not be )
considered operable until after it is tested successfully, i 9606240139 960606 PDR ADOCK 05000602 P PM l 12/90 Amended 6/96 Page 24
l Revision 1 Technical Specifications
= a l 3.2 Reactor Control and Safety System 1
1 3.2.1 Control Assemblies I l
Specification (s) 1
- The reactor shall not be operated unless the control rods are operable, and
- a. Control rods shall not be operable if damage is apparent to the rod or drive assemblies.
l b. The scram time measured from the instant a simulated signal reaches the value of a limiting safety system setting to the instant that the slowest scrammable control rod reaches its fully inserted position shall not exceed 1 second.
- c. Maximum reactivity insertion rate of a standard control rod l shall be less than 0.2% Ak/k per second. !
3.2.2 Reactor Control System Specification (s) l The reactor shall not be operable unless the minimum safety interlocks !
are operable. The following control system safety interlocks shall be l
operable: !
Control Rod Drive Number Effective Mode
- Interlock Function Operable Control Rod M A S P
- a. Startup Withdrawal - 3 Standard rods X X prevent rod up movement 1 Transient rod X X X X if startup signal is less than 2 counts per second
- b. Simultaneous Withdrawal - 3 Standard rods X prevent rod up movement 2 Shim rods X for two or more rods 1 Transient rod X X
- c. Non pulse condition - 1 Transient rod X X prevent air actuation if rod drive is not down
- d. Pulse Withdrawal - 3 Standard rods X X prevent withdrawal of non pulse rods
- e. Transient Withdrawal - 1 Transient rod X X prevent air actuation if linear power is more than 1 kilowatt l
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- Modes are: (M) Manual, (A) Auto, (S) Square Wave, and (P) Pulse 12/90 Amended 6/96 Page 14 l
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