ML20133K324
| ML20133K324 | |
| Person / Time | |
|---|---|
| Site: | General Atomics |
| Issue date: | 10/17/1985 |
| From: | Thomas C Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20133K322 | List: |
| References | |
| R-067-A-035, R-67-A-35, NUDOCS 8510210183 | |
| Download: ML20133K324 (6) | |
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/ jog UNITED STATES 8 o NUCLEAR REGULATORY COMMISSION g .j WASHINGTON,0. C. 20555 i
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GA TECHNOLOGIES, INC. o DOCKET NO. 50-163 AMENDMENT TO FACILITY OPERATING LICENSE _ I n ..
Amendment No. 35 License No. R-67 l
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- 1. The Nuclear Regulatory Comission (the Commission) has found that:
, A. :
The application No. R-67, filed byfor GA amendment Technologies, to Facility Inc. (Operating Licensethe licensee), ;
August 26 and September 24, 1985, complies with the standards and '
requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's Regulations as set forth in !
10 CFR Chapter I:
- 8. The facility will operate in conformity with the amended license, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance Ji) 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 Comission's regulations; 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 Commission's reculations and all applicable requirements have been satisfied; and F. Publication of notice of this amendment-is not required since it does f not involve a significant hazards consideration nor amendment of a license of the type described in 10 CFR Section 2.106(a)(2).
<,- 83 G h 163 gggo2 Cg O ppR PDR P
- 2. Accordingly, the license is amended by changes to the technical specifications as indicated in the attechment to this licens6 amendmert, and paragraph 2.C.2 of License No R-67 is hereby' amended to read as follows:
Technical Specifications The technical specifications contained in Appendix A, as revised through Amendment No. 35, 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 NUCLEAR REGULATORY COMMISSION
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Cecil 0. Thomas, Chief Standardization & Special Projects Branch Division of Licensing
Attachment:
Appendix A Technical Specifications Changes
- Date of Issuance: October 17, 1985 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 35 FACILITY OPERATING LICENSE NO. R-67 _
DOCKET NO. 50 163 -
Revised Appendix A technical specifications are as follows:
Renove Paoes Add Pages 6 6 7 7 c; ,,
14 14 Changes on the revised paces are identified by marginal lines.
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6.0 CONTROL AND SAFETY SYSTEMS 6.1 Control Systems .
6.1.1 The poison section of the control rods shall contain borated graphite or stainless steel, B C3 powder or boron or its compounds in solid forn, cadnium, dr the rare earth poisons in solid form clad with the materials authorized for fuel element cladding. The control rods may contain flux traps and may be equipped with fuel or non-fuel followers.
6.1.2 The rumber and position of operable control rods, at least one of which shall be a standard control rod, and their respective worths shall be such as to shut the reactor down by at least 10 cents when direct conversion experiments (section 10.2.6) are being conducted and by at least 50 cents at all other times, even with -
the most reactive rod stuck out. Period or rod drop measurements shall be used to verify minimum reactor shutdown when the estimated -
shutdown margin is less than 50 cents. -
6.1.3 The maximum scram time for any fully withdrawn rod shall be two seconds from time of initiation of scram signal to full insertion of the rod. Verification shall be carried out at least ,
semi-annually.
6.1.4 The control rods shall be visually inspected at least once every two years. If indication of significant deterioration or l distortion is found, the rod (s) affected shall be replaced.
6.1.5 On each day that pulse mode operation of the reactor is planned, a functional performance check of the transient (pulse) '
rod system shall be perfomed.
Semiannually, at intervals not to exceed eight months, the transient (pulse) rod drive cylinder and the associated air supply system -
shall be inspected, cleaned and lubricated as necessary.
6.2 Safety Systems 6.2.1 The reactor safety systems and the associated instruments necessary to provide the scrans listed in Table 1 shall be operable '
during reactor operation.
6.2.2 During reactor operation, the applicable interlocks shown in Table II shall be operable. ;
t Amendment No. 35
. -7 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 systems, the intent of this speciff. cation will be satisfied if the installed system is replaced as needed with alternative or portable gamma-sersitive instruments having their own alanns or which shall be kept under visual observa. tion).
(a) An area rediation monitoring system capable of activating the evacuation alarm.
(b) A continuous monitoring system for airborne radioactivity having a readout ard audible alarm which can be heard in both the reactor and control rooms.
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(c) The monitoring systems in (a)'and (b) shall be calibrated annually and their set points verified weekly.
6.2.4 The reactor safety systems shall be verified to be operable at least once each day the reactor is operated, unless the operation
% .- extends continuously beyond one day, in which case the operability -
of the reactor safety system need only be verified prior to the -
extended operation.
6.2.5 The reactor power measuring channels shall be calibrated by the calorimetric or heat balance method sentannually but at intervals not to exceed seven and one-half (7)) months.
6.3 Following maintenance or modification of the control or reactor safety systems, the effected system shall be verified to be operable befor~e comencing reactor operation.
7.0 FUEL STORAGE 7' 1 All fuel elements or fueled devices shall be stored in a safe geometry (k eff less than 0.8 under all conditions of moderation).
7.2 Irradiated fuel elements and fueled experiments shall be stored in an array which will permit sufficient natural convection
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cooling by water or air such that the temperature.cf the fuel -
element or fueled device will not exceed design values.
8.0 ADMINISTPATIVE RE0llIREMENTS 8.1 The faci.lity 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 respor.sibility for research and development, or his designated alternate, for safe operation of the reactor and its associated equipment. The Criticality Safeguards Committee shall review and approve safety standards associated with operation and use of the facility. The' Criticality Safeguards Committee or a Subcommittee thereof must audit reactor operations at least quarterly.
Amendment No. 35
- 14 (d) The irradiation time for any cre device shall not exceed 10,000 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 in-struments necessary to provide the following automatic scrams shall be operable:
(1) when devices are present in the core and reacter power exceeds 5 kilowatts (scram bypass is pemissible during scram reset or maintenance operation):
(i) Reactor scram if the temperature of the primary containnent tube exceeds 1000"C.
(ii) Reactor scram if the bus bar water coolant flow rate falls below that required to renove the resistance heat from the water cooled part of the
- bus bars and maintain the water coolant temperature -
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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 bypass is permissible during scram test or maintenance operations provided the reactor operator shall initiate a manual screm upon the occurrence
- of an equivalent signal from a specified alternative radiationmonitor).
(g) The following reactor room personnel warning systems, which if tripped require immediate 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 containment.
(2) a radiation monitor capable of indicating a gross leakage of fission products into the purgeable secondary containment.
(h) The reactor shall be shut down if the dose rate either (a) outside any wall of the reactor room resulting from direct conversion experiments, 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.
10.2.7 If an experiment fails and releeses material which, in the judoment of the Physici. st-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 need for corrective action.
l The results of the inspection and any corrective action taken l
shall be reviewed by the Criticality Safeguards Committee and l determined to be satisfactory before reactor operation is resumed.
l l Amendment No. 35 l
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