ML20137X634
| ML20137X634 | |
| Person / Time | |
|---|---|
| Site: | General Atomics |
| Issue date: | 03/05/1986 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20137X632 | List: |
| References | |
| R-067-A-035, R-67-A-35, NUDOCS 8603110243 | |
| Download: ML20137X634 (4) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
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GA TECHNOLOGIES, INC.
DOCKET NO. 50-163 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 35 License No. R-67 1
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to Facility Operating License No. R-67, filed by the GA Technologies, Inc. dated January 28, 1986, complies with the standards and re Energy Act of 1954, as amended (the Act)quirements of the Atomic
, and the Comission'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 Comission; C.
There is rea.'nable assurance:
(i) that the activities I
authorized by this amendment can be conducted without g
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 Comission's regulations and all applicable requirements have been satisfied; and F.
Publication of notice of this amendment is not reouired 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).
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2-2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2 of facility Operating License No.
R-67 is hereby amended to read as follows:
2.
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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erbert N. Berkow, Director Standardization and Special Projects Directorate Division of PWR Licensing-8, NRR
Attachment:
Appendix A Technical Specification Changes Date of Issuance: March 5, 1986 o
ATTACHMENT TO LICENSE AMENDMENT NO. 35 FACILITY OPERATING LICENSE NO. R-67 DOCKET NO. 50-163 Revised Appendix A Technical Specifications are as follows:
Remove Page Add Page 14 14 The change on the revised page is identified by a marginal line.
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% (d) The irradiation time for any one device shall not exceed 20,000 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 reactor power exceeds 5 kilowatts (scram bypass'is permissible during scram reset or maintenance operations):
(1) Reactor scram if the temperature of the primary 0
containment tube exceeds 1000 C.
(ii) Reactor scram if the bus bar water coolant flow rate falls 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.)
f (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.
(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 cores (1) a pressure sensing device capable of indicating a leak in the purgeable secondary containment.
o (2) a radiation monitor capable of indicating a gross leakage of fission products into the purgeable secondary containment.
(h) The reactor shell 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 iue 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 releasse material which, in the judgment 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 need for corrective action, f
The results of the inspection and any corrective. action taken
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shall be reviewed by the Criticality gefeguards Committee and determined to be satisfactory before reactor operation is resumed.
l Amendment No. 35
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