ML20140C317
| ML20140C317 | |
| Person / Time | |
|---|---|
| Site: | General Atomics |
| Issue date: | 03/05/1986 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20140C309 | List: |
| References | |
| R-067-A-036, R-67-A-36, NUDOCS 8603250320 | |
| Download: ML20140C317 (4) | |
Text
o UNITED STATES
[
~,,
NUCLEAR REGULATORY COMMISSION o
5 j
WASHINGTON, D. C. 205. 5
\\...../
GA TECHNOLOGIES, INC.
DOCKET N0. 50-163 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 36 License No. R-67 1.
The Nuclear Regulatory Commission (the Comission) has found that:
j A.
The application for amendment to Facility Operating License No. R-67, filed by the GA Technologies, Inc. (the licensee),
j dated January 28, 1986, 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.
1 B.
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 reasonable assurance:
(i) 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 Commission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 i
license of the type described in 10 CFR Section 2.106(a)(2).
9603250320 860320 PDR ADOCK 05000163 P
PDR 4
2-2.
Accordingly, the license is amended by char.ges 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:
Technical Specifications The technical specifications contained in Appendix A, as revised through Amendment No. 36, 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 (f f.
A Herbert N. Berkow, Director Standardication and Special Projects Directorate Division of PWR Licensing-B, NRR
Attachment:
Appendix A Technical Specifications Changes Date of Issuance: March 5, 1986 1
i
.-.-----_,r.
_,-,.-,,,,,-,-,m--,
-=,
l e
1 ATTACHMENT TO LICENSE AMENDMENT NO. 36 i
FACILITY OPERATING LICENSE NO. R-67 DOCKET NO. 50-163 4
Revised Appendix A Technical Specifications are as follows:
Remove Page Add Page 14 14
'h i
The change on the revised page is identified by a marginal line.
]
4 a
l
]
'l 4
i
- 14 _
(d) The irradiation time for any cne device shall not exceed 20,000 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 pemissible 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 renove the resistance heat from the water cooled part of the bus bars and maintefn 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:
(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 screm upon the occurrence of an equivalent signal from a specified alternative radiationmonitor).
i (g) The following reactor room personnel warning systems, i
which if tripped require imediate 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.
i 1
(h) The reactor shall be shut down if the dose rate either (a) outside any wall of the reactor room resultion 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 iudoment 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 l
to determine the consequences and need for corrective action.
The results of the inspection.and any corrective action taken shall be reviewed by the Criticality Safeguards Committee and determined to be satisfactory before reactor operation is resumed.
Amendment No. 36
.