ML20245D332
| ML20245D332 | |
| Person / Time | |
|---|---|
| Site: | 05000192 |
| Issue date: | 04/21/1989 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245D329 | List: |
| References | |
| R-092-A-011, R-92-A-11, NUDOCS 8904280251 | |
| Download: ML20245D332 (6) | |
Text
p
- . i. , g
'o UNITED STATES g
L o- NUCLEAR REGULATORY COMMISSION
)8: ;$-
~*
WASHINGTON, D. C. 20666 -
b
, \ . . . . . ,o l.
THE UNIVERSITY OF TEXAS DOCKET NO. 50-192 AMENDMENTTOFACILITYOPERATINGLICENSE Amendment No. 11 License No. R-92 l
- 1. The Nuclear Regulatory Commission (the Comission) has found that:
A. The application for amendment to Facility Operating License No. R-92 filed by the University of Texas (the licensee), dated August 1, 1988, as supplemented on September 13,.1988 and March 9, 1989, complies with the standards and re Energy Act of 1954, as amended (the ,Act)quirements of the Atomic and the Commission's regulations as set forth in 10 CFR_ Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C. There is reasonable assurance: (1).thattheactivitiesauthorized by this amendment can be conducted without endangering the health I and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health'and safety of the public; E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied; and F. Publication of notice of this amendment is not required since it does not involve a significant hazards consideration nor amendment of a :
license of the type described in 10 CFR Section 2.106(a)(2). l 89042;O251 890421 4 i gDR ADOCK0500g2 i
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license 1 amendment, and paragraph 2.C.2. of License No. R-92 is hereby l amended to read as follows: !
- 2. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. II, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of its date of issuance. 3 FOR THE NUCLEAR REGULATORY COMMISSION ;
h YI Charles L. Miller, Director Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects Ill. ,
Y and Special Projects 1 Office of Nuclear Reactor Regulation j
Enclosure:
Appendix A Technical Specifications Changes l l
Date of Issuance: April 21, 1989 )
l l
l l
I L___-___-______--__-_.
- _ - - - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - __-. _ _ _ _ - . - _ . __ . _ _ _ _ - _ _ _ _ _ = _
, ~
ENCLOSURE TO LICENSE AMENDMENT NO. 11 FACILITY OPERATING LICENSE NO. R-92 DOCKET NO. 50-192 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
Remove Pages Insert Pages 1 1 20 20 21 21
e 1.0 DEFINITIONS 3,
REACTOR OPERATING CCNDITIONS 1.1 REACTOR SHUTDOW The reactor is shut down when the reactor is suberitical by at least ~one do11ar (0.7% 3.k/k) of reactivity.
1.2 Reactor Secure The reactor is secure when:
1.2.1 It contains insufficient fissile material or moderator present in the reactor, control rods or adjacent experiments, to attain criticality !
under optimum available conditions of moderation and reflection, or 1.2.2
- a. The minimum number of neutron absorbing control rods are fully inserted or other safety devices are in shutdown position, as required by technical specifications.
- b. The console key switch is in the off position and the key is removed from the lock.
- c. 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.
- d. No experiments in or near the reactor are being moved or sem iced that have, on movement, a reactivity worth exceeding the maximum allowed for a single experiment or one dollar which ever is smaller.
1.3 REACTOR OPERATION Reactor operation is any condition wherein the reactor is not secured.
l 1.4 COLD CRITICAL The reactor is in the cold critical condition when it is critical with the fuel and bulk water temperatures both
.below 40*C.
l 1.5 STEADY STATE MODE I
Steady state rade operation shall mean operation of the reactor with the m ue selector switch in the steady-state position.
1.6 Pp.SE MODE Pulse mode operation shall mean any operation of the reactor with the mode selector switch in the pulse positien.
1,7 SHUTDOW MARGIN Shutdown margin shall mean the minimum shutdown reactivity necessary to provide confidence that the reactor can be made suberitical by means of the control and safety systems, l starting from any permissible operating cenditions and that the reactor will re sin suberitical without further operator action.
1 Amendment No. 11
<r .
Specifications !
I
- a. The reactivity worth of each control rod and the shut- {
down margin shall be determined annually, but at intervals i not to exceed 14 months,
- b. The reactivity worth of an experiment shall be estimated !
or measured, as appropriate, before reactor 4.peration j with said experiment. l
- c. The control rods shall be inspected visually for deteriora- l tion at intervals not to exceed 2 years. ,
- d. The transient rod drive cylinder and associated air supply system shall be inspected, cleaned, and lubricated semi-annually, but at intervals not to exceed 8 months.
- e. The reactor shall be pulsed semiannually to compare fuel temperature measurements and peak power levels with those of previous pulses of the same reactivity value or the reactor shall not be pulsed until such comparative pulse measurements are performed.
- f. The reactor shall not be operable until the surveillance a-e of this section are complete. Surveillance intervals of this section with the exception of c may be extended if the reactor is not operable.
Bases Thr. reactivity worth of the control rods is measured to assure that the required shutdown margin is available and to provide an accurate means for determining the reactivity worths of experiments inserted in the core. l.ong term effects of TRIGA reactor operation are such that measurement of the reactivity worth on an annual basis is adequate to insure no significant changes in the shutdown margin. The visual inspection of the control rods is made to evaluate corrosion and wear characteristics caused by operation in the reactor.
The reactor is pulsed at suitable intervals and a comparison made with previous similar pulses to determine if changes in fuel or core characteristics are taking place.
4.2.2 Control and Safety System Applicability
]
)
These specifications apply to the surveillance requirements for measurements, tests, and calibrations of the control and safety systems.
Objective The objective is to verify the performance and operability of those systems and components which are directly related to reactor safety, i
20 Amendment No. 11 l i
____ _ _ _ _ _ _ __ _ J
Specifications
- a. The scram time shall be measured annually, but at intervals not to exceed 14 months.
- b. A channel test of each reactor safety . scram channel for the intended mode of non-shutdown operation shall be per-formed prior to each day's operation or prior to each operation extending more than one day.
- c. A functional check of all safety channels listed in section 3.4.3 shall be performed semiannually, but at intervals not to exceed 8 months.
- d. A Channel Calibration shall be made of the power level monitoring channels by the calorimetric method annually, but at intervals not to exceed 14 months.
- e. A test of the power level safety circuits shall be performed semiannually, but at intervals not to exceed 8 months. i
- f. The reactor shall not be operable until the surveillance a-e of this section are complete. Surveillance intervals for sections a-e of this section may be extended if the reactor is not operable.
Bases Measurement of the scram time on an annual basis is a check l not only of the scram system electronics, but also is an indication of the capability of the control rods to perform properly. The channel tests will assure that the safety system channels are operable on a daily basis or prior to an extended run. The power level channel calibration will assure that the reactor will be operated at the proper ,
power levels. Transient control rod checks and semiannual 1 maintenance insure proper operation of tMs control rod.
i 4.2.3 Radiation Monitoring System Applicability This specification applies to the surveillance requirements for the area radiation monitoring equipment and the continuous air monitoring system.
Objective 1
)
The objective is to assure that the radiation monitoring 1 equipment is operating and to verify the appropriate alarm settings. ,
I 21 Amendment No. 11 l 3