ML20206J279
| ML20206J279 | |
| Person / Time | |
|---|---|
| Site: | General Atomics |
| Issue date: | 11/18/1988 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206J274 | List: |
| References | |
| R-067-A-040, R-67-A-40, NUDOCS 8811280125 | |
| Download: ML20206J279 (8) | |
Text
- - - - -- _
p-
%, UNITED STATES 8 g NUCLEAR RECULATORY COMMISSION
,$ ,s WASHINGTON, D. C. 20506
%o.....
GA TECHNOLOGIES, INC.
DOCKET NO. 50-163 AMENOMENT TO FACILITY LICENSE Amendment No. 40 License No. R-67
- 1. The Nuclear Regulatory Comission (the Commission) has found that:
A. The application for amendment to Facility License No. R-67 {
filed by GA Technologies, Inc. (the licensee), dated December 22, 1987, of the At'omic Energycomplies with the Act of 1954, standards(the as amended andAct req)uirements , and the Commission's regulations as set forth in 10 CFR Chapter I; B. The facility will c?erate in conformity with the ap)lication, the provisions of che Act, and the regulatione of tie Commission; C. There is reasonable assurance: (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Cornission'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 licenseofthetypadescribedin10CFRSection2.106(a)(2).
$k $0 $ b!b Q3
l 1
. 2
- 2. Accordingly, the license is amended by changes to the Technical '
Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C.2. of License No. R-67 is hereby amended to read as follows:
- 2. Technical Specifications i The Technical Specifications contained in Appendix A, as revised through Amendmcnt No. 40, 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.
FOR THE NLICLEAR REGULATORY COMMIS$10N b ad. f. 9 d b Charle4 L. Miller, Acting Director Standardization and Non-Power Reactor Project Directorate 1 Division of Reactor Projects !!!, IV, (
V ansi Special Projects Office af Nuclear Reactor Regulation
Enclosure:
Appendix A Technical Specifications Changes i
Date of Issuance: November 18, 1988 i
i
L ENCLOSURE TO LICENSE AMENOMEN NO. 40 )i I FACILITY LICENSE NO. R-67 t 1
DOCKET NO. 50-163 ;
J Rep! ace the following pages of the Appendix A Techrical Specifications with (
the enclosed pages. The revised pages are identified by Amendment nus6er and ;
contain a vertical line indicating the area of c'sange. I i
Remove Pages Insert Pages l
' 3 3 i
' 7 7 l 7a .
14 14 i 14a [
1 l I h
i !
I 4 f f
)
I i
i 1
[
L i I 1
l t
t 4
1 0
i I
i T I l i !
I I
- t
e 2.0 SITE A minimum radius of 120 feet from the approximate center of the TRIGA reactor facility building shall define tie exclusion area.
3.0 REACTOR BUILDING 3.1 The reactor shall be housed in a closed room built to restrict leakage. The minimum free volume in the reactor room sN -l be 11,700 cubic feet.
3.2 Cont *ols for the ventilating system shall be located in the control room.
3.3 All air or other gas exhausted from the reactor room during reactor operati o shall be released to the environment at a minimum of 20 feet above ground level.
3.4 The reactor room ventilation system shall be separate from the rest of the building ventilation.
3.5 Adequate resistance to leakage of air from the reactor room shall be verified by measurement annually, (interval not to exceed 15 months) (
and anytime the roof hatch has been opened and reclosed, when a charcoal filter is required for reactor operations. The r to air leakage shall be at least 1//, where p = 6.38 x 10~gsistance m sec/kg.
%U REACTOR POOL 4.1 The reactor core shall be coolr' by natural convective water flow except as provided for in Sectio 10.0 covering experiments.
4.2 During reactor operation, the minimum level of the pool water shall be at least 16 feet above the top grid plate.
4.3 The pool water outlet pipe shall not extend more than 8 feet below the top of the reactor pool when fuel is in the core.
4.4 The pool water shall be sampled for conductivity at least weekly.
The conductivity of the coolant shall not exceed 5 micro-mhos per centimeter averaged over any one calendar month.
4.5 The reactor shall not be operated while the bulk pool temperature exceeds 65'C.
5.0 REACTOR CORE 5.1 The core shall be an assembly of uranium zirconium hydride fuel ele!nents placed in light water except for adjacent or non-adjacent positions occupied by startup sources, vertical thimbles, voids, control rods, in-core experiments, and rabbit facilities.
Amendment No. 40
4 6.2.3 The following monitoring systems shall be operable during reactor operation or when work is done on or around the reactor ~
core. (For periods of time for maintenance to the radiation monitoring cystems, the intent of this specification will be
! satisfied if the installed system is replaced as needed with I alternative or portable gama sensitive instruments having their own alarms or which shall be kept under visual observation).
5 (a) An area radiation monitoring system capable of activating the evacuation alarm.
l (b) A continuous monitoring system for airborne ridioactivity 4
having a readout and audible alarm which can be heard in both j the reactor and control rooms.
! (c) Themonitoringsystemsin(a)and(b)shallbecalibrated i annually and their set points verified weekly.
! 6.2.4 The reactor safety systems shall be verified to be operable I at least once each day the reactor is operated, unless the operation j extends continuously beyond one day, in which case the opera)ility 1
of the reactor safety system need only be verified prior to the extended operatien. (
1 6.2.5 The reactor power measuring channels shall be calibrated by the calorimetric or heat balance method semiannually but at intervals not to exceed seven and one-half (71) months.
I 6.2.6 When an activated charcoal filter is required for the testing of thermionic devices, its blower shall be verified to be operable
- j. atleastonceeachweek(intervalnottoexceedtendays). A sample of the activated charcoal shall be tested semiannually (at intervals not to exceed 71 months) to confirm acceptable low levels of water /
l
- humidity content. The filter flow rate shall be verified annually l to be at least 460 cfm (interval not to exceed 15 months).
6.3 Following maintenance or modification of the control or reactor safety j systems, the affected system shall be verified to be operable before
! comencing reactor operation.
4 l
7.0 FUEL STORAGE 7.1 All fuel elements or fueled devices shall be stored in a safe geometry (k,ff less than 0.8 under all conditions of moderation),
7.2. Irradiated fuel elements and fueled experiments shall be stored in f an array which will permit sufficient natural convection cooling by water or air such that the temperature of the fuel element or fueled device will not exceed design values.
I Amendment No. 40
. - 7a -
8.0 ADMINISTRATIVE REQUIREMENTS 8.1 The facility shall be under the supervision of the Physicist-in.
Charge or his designated alternate, who shall be a licensed senior operator of the facility. He shall be responsible to a Vice President whose duties include responsibility for research and developrnent, or his designated alternate, for safe operation of the retctor and its associated equipment. The Criticality Safeguards Comittee shall review and approve safety standards associated with operation and use of the facility. The Criticality Safeguards Comittee or.a Subcomittee thereof must audit reacter operations at least quarterly.
Amendrnent No. 40
i
. 14 (d) The irradiation tine for any one device shall not exceed 40,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.
(e) The reactor shall not be placed on a positive period of less than one second while any direct conversion device is present in the core.
(f) The experiment safety systems and the associated instruments necessary to provide the followina au+,omatic scrams shall be operable:
(1) when devices are present in the core and reactor pcwer exceeds 5 kilowatts (scram bypass is pernissible during scram reset or maintenance operation):
(i) Reactor scram if the temperature of the primary containment tube exceeds 1000'C.
(ii) Reactor scram if the bus bar water coolant flow rate fallt below that required to remove the resistance heat from the water cooled part of the bus bars and maintain the water coolant temperature below boiling. (This scram is applicable only where such cooling is required.)
(2) when devices are present in the core regardless of reactor (
power level:
(1) Reactor scram if the reactor room continuous air monitor registers 50,000 counts per minute or more (scram bypat.s is permissible during scram test or maintenance operations provided the reactor operator shall initiate a manual scram upon the occurrence of an equivalent signal from a specified alternative radiation monitor).
(g) The following reactor room personnel warning systems, which if tripped require innediate personnel evacuation, shall be operable when devices having a purgeable secondary containment are present in the core:
(1) a pressure sensing device capable of indicating a leak in the purgeable secondary centdament.
(2) a radiation monitor capable of indicating a gross leakage of fission products into the purgeable secondary containment.
(h) Thereactorshallbeshutdownifthedoserateeither(a)outside any wall of the reactor room resulting fron direct conversion experirents, or (b) in the control room due to all experiments, exceeds (1) a maximum of 20 mr/hr, or (2) 2.5 mr/hr continuously for more than one hour.
(1) When irradiated thermionic devices are present in the reactor room, a high efficiency activated charcoal filter having a minirnum flow rate capacity of 460 cfm shall be available in the reactor room.
The site boundary shall be 100 m. This paragraph is effective upon initial operability of the charcoal filter system.
Amendment No. 40
- - Ida -
10.2.7 If an experiment fails and releases material which, in the judgement of the Physicist-in-Charge or his designated alternate, could damage the reactor fuel or structure by corrosion or other means, physical inspection shall be performed to determine the consequences and i
need for corrective action. The results of the inspection and any 4 corrective action taken shall be reviewed by the Criticality Safeguards j Committee and determined to be satisfactory before reactor operation is resumed.
i u
1 I
l i
)
i .
(
4 I
l l
i i
1 f,
i l.
i l
}
Anendment No. 40 1
.- - - - -_,- --- - - . _ , - - - - - - - , - , - - . , - , , , . -,