ML19344E455
| ML19344E455 | |
| Person / Time | |
|---|---|
| Site: | Berkeley Research Reactor |
| Issue date: | 08/07/1980 |
| From: | Kaplan S CALIFORNIA, UNIV. OF, BERKELEY, CA |
| To: | |
| References | |
| NUDOCS 8009020040 | |
| Download: ML19344E455 (3) | |
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dNIVERSITY OF CALIFORNIA, BERKELEY (C @
BERKELEY
- DAY 15
- IRVINE
- LOS ANGELES
- RIVERSIDE
- SAN DIECO
- SAN FRANCISCO SANTA BARBARA
- SANTA CRtlZ COLLEGE OF ENGINEERINc BERKELEY, CALIFORNIA 94720 DEPARTEIENT Or NL' CLEAR ENGINEERLNc 3 ; August 7, 1980 L-
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Mr. James A. Miller, Chief'
/
Standardization and Special Project Branch Division of Licensing U.S. Nuclear Regulatory Cocunission Washington, D. C. 20555
Dear Mr. Miller:
We hereby request the following changes to the University of California TRIGA Mark III Berkeley Research Reactor, Docket No. 50-224, Amendment for Renewal of Facility Operating License, Amendment No. 2, License No.
R-101, effectiva date September 28, 1979, Section 2.B.2 page 2 from
" Pursuant to the Act and 10 CFR Part 70, "Special Nuclear Material," to receive, possess, and use up to 7.4 kilograms of contained uranium 235, in a homogeneous mixture of uranium-zirconium hydride, enriched to less than 20 percent and up to 240 grams of plutonium 239 in the form of sealed Pu-Be neutron sources (5 - 1 curie Pu-Be sources, 1 - 10 curie Pu-Be source),
both in connection with operation of the reactrar."
to read an follows:
" Pursuant to the Act and 10 CFR Part 70, "Special Nuclear Material," to receive, possess, and use up to 7.4 kilograms of contained uranium 235, in a homogeneous mixture of uranium-zirconium hydride, enriched to less than 20 percent, up te 25 grams of enriched uranium 235, both in connection with the operation of the reactor and up to 240 grams of plutonium 239 in the form of sealed Pu-Be neutron sources (5 - 1 curie Pu-Be sources, 1 - 10 curie Pu-Be source)."
This change will permit possession of enriched uranium other than fuel elements (e.g. in fission chambers) and, will permit use of the PuBe sources for acti-vities not in connection with operation of the reactor.
Also, we request the following changes to Appendix A of Facility License No.
R-101, Technical Specifications for the TRIGA Mark III Berkeley Research Reactor of the University of California Berkeley, California, Docket No.
O 50-224, effective date 9-28-79:
5 ID 80000209/88
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James A. Miller August 7, 1980 Section C 2.1.f page 19 from:
" Control rod drop times shall be verified to be less than one second.
If the rod drop time is found to be greater than one second, the rod shall not be considered operable."
to read as follows:
" Control rod drop times shall be verified to be less than two seconds.
If the rod drop ti=e is found to be greater than two seconds, the rod shall not be censidered operable."
This change will be consistent with the =aximum control rod drop time of 2 seconds given in Section 3.4.1 page 10 of this same document.
Sectxon 3.5, Table 1, page 12 line 6 or line 4 of the first colu=n, from:
" Safety (Power Level) 1 SCRAM @ 1.1. =egawatt X
X" to read as follows:
" Safety (Power Level) 1 SCRAM 9 110% of Safety Channel Meter X
X" This change will bring dercription into conformance with intent of the specification and with current practice.
Section 3.5. Table 1, page 12, line 29 or line 21 of the first column, from:
" Pool Water Level 1
2 feet above top of grid bridge plate X
X" to read as follows:
" Fool Water Level 1
2 feet above tcp of grid plate X
X" This change will bring description to conform to the accepted terminology, f
The requested changes were reviewed by the Reactor Hazards Cc=nittee and i
the Reactor Supervisor.
These changes do not constitute an unreviewed safety question in that:
(1)
It does not increase the probability of occurrence of an accident analy ed in the Safety Analysis Report.
(2)
It does not increase the consequences of an accident analyzed in the Safety Analysis Report.
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e James A. Miller August 7, 1980 (3)
It does not create the possibill.ty of occurrence of nuclear accident not previously analyzed in the Safety Analysis Report.
Sincerely yours,
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Selig N. Kaplan SNK: irs Reactor Administrator l