ML20235E981

Amend 38 to License R-67,authorizing Increase in Irradiation Time for Fueled Incore Thermionic Direct Conversion Devices W/Irradiation Time Not to Exceed 40,000 H for Any One Incore Thermionic Direct Conversion Device

ML20235E981
Person / Time
Site:	General Atomics
Issue date:	07/06/1987
From:	Berkow H Office of Nuclear Reactor Regulation
To:
Shared Package
ML20235E891	List: ML20235E890 ML20235E981 ML20235E998
References
R-067-A-038, R-67-A-38, NUDOCS 8707130158
Download: ML20235E981 (4)

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5~ :j g NUCLEAR REGULATORY COMMISSION

' WASHINGTON, D. C 20555

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GA TECHNOLOGIES, INC.

DOCKET NO. 50-163 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 38 License No. R-67

1. The Nuclear Regulatory Comission (the Comission) has found that:

A. The application for amendment to Facility Operating License No. R-67, filed by GA Technologies, Inc. (the licensee), dated April 30, 1987, complies with the standards and requirements of the Atomic Energy Act of'1954, as amended (the Act), and the Comission'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 Comission; 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 Comission'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).

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2. Accordingly, the license is amended by changes to'the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 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. 38, are hereby incorporated in the license. l The licensee shall operate the facility in accordance with the Technical Specifications.

3. The license amendment is effective upon date of issuance.  ;

FOR THE NUCLEAR REGULATORY COMMISSION I

h i Her ert N. Berkow, irector I St dardization and Non-Power Reactor Project Directorate Division of Reactor Projects, III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

Appendix A Technical Specifications Changes Date of Issuance:

')

4 ENCLOSURE TO LICENSE AMENDMENT NO. 38 FACILITY OPERATING LICENSE NO. R-67 DOCKET NO. 50-163 Replace the following page of the Appendix A Technical Specifications with the ,

enclosed page. The revised page is identified by Amendment number and contains a vertical line indicating the area of change.

Remove Insert i

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(d) The irradiation time for any one device shall not exceed 40,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. l (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 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 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 a where such cooling is required.)pplicable only (2) when devices are present in the core regardless of reactor power level:

(i) 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 scram upon the occurrence of an equivalent signal from a specified alternative i radiation monitor).

(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 releases 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. The results of the 4 inspection and any corrective action taken shall be reviewed by .

the Criticality Safeguards Committee and determined to be I satisfactory before reactor operation is resumed.

Amendment No. 38 Correction Letter of 3-20-80

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