ML20062K126
| ML20062K126 | |
| Person / Time | |
|---|---|
| Site: | Berkeley Research Reactor |
| Issue date: | 11/19/1980 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20062K124 | List: |
| References | |
| R-101-A-003, R-101-A-3, NUDOCS 8012010564 | |
| Download: ML20062K126 (6) | |
Text
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Ja* *'49 ff fo, UNITED STATES g $ c,(,g NUCLEAR REGULATORY COMMISSION
,;.g. A A.. C WASHING TON. D. C. 20$55 o
U'i!YERSITY OF CALIFORNIA AT SERYELEY DOCKET NO. 50-22%
A"E!O*4ENT TO FACILITY OPERATING LICENSE Amendment No. 3 License No. R-101 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the University of California at Berkeley (the licensee) dated August 7,1980, complies with ti.e standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; 3.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendme t 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; 3.
The issuance of this amendment will not be inimical to the common defense and security or to the haalth and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission'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).
2.
Accordingly, the license is amended by changes to the Technical Specific-ations as indicated in the attachment to this license amendment, and paragrapns 2.B.2 and 2.C.2 of Facility License Operating No. R-101 are hereby amended to read as follows:
2.3.2 Pursuant to the Act and 10 CFR Part 70, "Special Nuclear Material," to receive, possess, and use up to 7.4 kilo-grams of contained uranium 235, in a homogeneous mixture of uranium-zirconium hydride, enriched to less than 20 percent; uo to 25 grams cf enriched uranium 235, both in connection with the operation of the reactor; and up to
'8 01 g 0 3 o gg
2-240 grams of plutonium 239 in the form of sealed Pu-Be neutron sources (5-1 curie Pu-Be sources,1-10 c.rie Pu-Be source).
2.C.2 Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 3, 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 the date of its issuance.
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FOR THE NUCLEAR REGULATORY COMMISSION
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James R. Miller, Chief Standardization and Special Projects Branch Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: November 19, 1980
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ATTACHMENT TO LICENSE AMENDMENT NO. 3 FACILITY LICENSE NO. R-101 DOCKET NO. 50-224 Revise Apper. dix A as follows:
Remove Pages Add Pages 10 10 12 12 19 19 O
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3.4 cO!. ?.OI.
O SA.TI Y SYSTZ*.
3.4.1 S :a= Time
- abilitv A:=18:
-his specificatien applies to the ti e required for the scram-
=able control rods to be fully inserted from the instant that a safety channel variable reaches the Safety System Setting.
CM eetive
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The ehjective is to achieve ;:c=pt sh::devn of the reactor a preven: fuel da=agt Soccification I
The scram time measured from the instant a simulated signal reaches the value as described in Table 1 to the instant that the control rod reaches its fully inserted position shall be 1 second for the shim, safety and regulating rods, which are electromagnetically, controlled, and 2 seconds for the transient rod, which is pneumatically controlled.
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1 asis 2.is specifica:ica assures that the rea:::: vill be p:c=p:1y shut d=w. when a scra= signal !s ini:iated. Ixperience and analysis have indicated that fer the range of trar.sients anti-cipated !c: a ~?::A reac ::, t.e specified scra: L:e is yv adequate to assure d.e safety cf the reae:cr.
3.4.2 Reae:c Safety Svstem A:=licability O.is specificati=n applies to the reac :: safety system cha.nels.
(1) *'. T: leff, " Analysis o' h--'al Refue11.9 vi:h 12 v-a Ura 1:= ruel fe a
2.e Berkeley Resear:h Reacter", P.S Thesis, apart. ment of Neelear Engineering, l
University of Calif:..nia, Zerkeley, 19-.
I Amendment No. 3
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TA22.I 1 F.inir.:n Keae:c: Sa'ferv Cha.nels f....
UC bt:
E!!eetLve y.ofe Safe:v Cha=nel C= era =1e
?unc-len s.s.
?: se se,y,
=
- .inear 1
SCPM @ 110::
I X
(Power Level)
Safety (?ower tevel) 1 SC3.AM 0110% Safety Channe1X X
Meter Console Scra:n Button 1 SCFM I
I I
I,og Power 1
SC3.AM 6 < 3 seconds X
X X
X
- .inear and Safety 1
SC?M en less of "
3etects:
supply voltage Pcwer Supply Preset Tir.e:
1 "ransient red scrz=
X 15 see nds c: less after pulse
'Starte: Chann.el 1
Prevent red vi hdrasal '
X at less than two neu-tren induced ceu..:s per see:nd
=_'
.=
[
.,=g ?cwer 1
Prevent pulsing X
"above 1 kW ransien 'kd i
?: event a-eli:anica,
X r.
of air unless fully Pesi ica L=se: ed l
Md :h-ive Cen cl 1
Prevent withdrawal X
of any rod except I
transient rod r
Tu el I le:se'n :
1 Alarm 6 500*C I
I
~
~e=perature Zar hg:ake Detector i
SC?M X
X X
yagnes Curren:
1 SC.W.
X X
X Xey Switch I
Peo1 *Ja:a Level 1
2 feet above :cp ci I
I X
grid plate Rod Drive Centrol 1
?: event si=ul:aneous X
I i
_anual vi:hdrava*. of g.r.m. =.._.
7......
seen.W.
?cci 3ulk k*a:e 1
Ala:= 3 > 120 * :
A X
X
- pera:ure e
i Amendment No. 3. -,..
, - _ +
d.
-ho ::annign: od driva cylinder and asreciated al supply system shall be inspe::ed, cleaned, and lubricated as necessary se=i-annually at intervals ac: s exceed 8 months Che reacter shall be pulsed se=i-annually to e== pare fuel e.
tenperature measure =ents and peak pcwer levels with those
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of ; evicus pulses of the same reactivity value..
f.
Control rod drop time shall be verified at least semiannually.
If the rod drop time is found to be greater than that specified in Secticn 3.4.1, the rod shall not be co,nsidered operable.
Bases The reae:1vi:7 worth of the control rods is measured to assure tha the required shu:down margin is available and to provide an accurata
=eans for de:er ining the reactivity worths of experiments inserted in the core. ?as: experience with the 3RR TRIGA ". ark III reactors gives assurance that naasu:ement of the reactivity verth on a bi-annual basis is adequate to insure no significant changes in the shutdown margin.
Tne visual inspection of the centrol rods is made :o evaluate corrosion end wear characteristics caused by operation in the reac:ce. The reactor is pulsed a:. suitable inter-tals and a c:=; arisen nade with previous sinilar pu'.ses to dete: r.ine if chances. fa fuel c core characteris-
-ics are taking place.
4.2.2 C----~'
and Safe:v Svstem Ae:11cahiliev TF hese specifications apply to the surveillance require =e. s for nessure=ents, tests, and calibra:icns of the con :01 and safety syste=s.
ch,ective he objec-ive is to verify the perf::=ance and cperability of these systa=s and ce=penents which are dire :17 : elated to reac== safety.
?:ecifications a.
Che scra= ti:ne shall be measured annually but at intervals
=c. :o exceed 14 menths.
h.
A Channel Cest of each cf the reae::: safety syste= cha.nels with scra= capability f== -he intended nede cf operation shall he perf::=ed prior to each day's operatien c pric: to each cperati:n extending nere than ene day.
A Channel Calibratien shall be made cf the cwer level =eni-
- ing channels by the cal:ri=e::i: sthed a..nually but at inte:-tals no: to exceed.14 ncnths.
d.
A fune:1cnal check shall be =ade of all reac:c ::::rol and :eac::: pesi:ica
..75 in:ericeks dese:1hed in Table 1.
Amendment No. 3
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