ML16245A230

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Pillsbury, Winthrop, Shaw, Pittman, Llp, Submittal of Response to Request for Additional Information Regarding Opportunity to Supplement 2012 License Transfer Application
ML16245A230
Person / Time
Site: Aerotest
Issue date: 08/22/2016
From: Silberg J
Pillsbury, Winthrop, Shaw, Pittman, LLP
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC MF7221
Download: ML16245A230 (42)
v • d • e


Text

Pillsbury Winthrop Shaw Pittman LLP 1200 Seventeenth Street NW I Washington, DC 20036-3006 I tel 202.663.8000 I fax 202.663.8007 Jay E. Silberg tel: 202.663.8063 j ay.silberg@pills bury law .com August 22, 2016 ATTENTION: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 AEROTEST RADIOGRAPHY AND RESEARCH REACTOR DOCKET NO. 50~228/LICENSE NO. R-98 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RE; OPPORTUNITY TO SUPPLEMENT 2012 LICENSE TRANSFER APPLICATION (TAC NO. MF7221)

Ladies and Gentlemen:

Enclosed please find the response of Aerotest Operations, Inc. ("Aerotest")

and Nuclear Labyrinth LLC ("Nuclear Labyrinth") to the U.S. Nuclear Regulatory Commission's Request for Additional Information Re: Supplemented Application for Indirect License Transfer of Aerotest Radiography and Research Reactor, dated July 20, 2016, including supporting affidavits on behalf of both Aerotest and Nuclear Labyrinth.

The Commission's Request asked clarification "whether all current [Aerotest Radiography and Research Reactor] *personnel, including individuals responsible for licensed activities involving reactor operation and safety, will be offered employment by Nuclear Labyrinth." Nuclear Labyrinth will offer employment to the five current employees of Aerotest Operations, Inc.

  • The Commission's Request also asked that we provide "a proposed license amendment and technical specifications, based on your current license, marked up to clearly show all insertions, deletions and revisions." Based on discussions between the undersigned and Mr. Ed Helvenston, enclosed with this letter are the current pages of record of the License and Technical Specifications (provided by Mr. Helvenston) marked to show the insertions, deletions and revisions. Also enclosed, as requested by Mr. Helvenston, is a clean, Word version of the license amendment and Technical Specifications, with the changes indicated by margin bars.

www.pillsburylaw.com

..,*----- 4818-3699-3847.v2

/'-**

Page2 Should you have any questions or require additional information regarding this submission, please contact Jay Silberg, counsel to Aerotest at 202-663-8063 or jay.silberg@pillsburylaw.com.

Very truly yours, J9Jilb::~

Counsel for Aerotest Operations, Inc.

Enclosures

1. ARRR License and Technical Specification (pages of record) with changes
2. ARRR License Amendment and Technical Specifications (clean copy with margin bars) cc: U.S. NRC Office of Nuclear Reactor Regulation/NRLPO U.S. NRC Region IV, Regional Administrator NRC, NRR (Helvenston)

NRC, NRR (Adams)

NRC, OGC (Ghosh) www.pillsburylaw.com 4818-3699-3847.vl

STATE OF UTAH

TOWIT:

COUNTY OF SALT LAKE COUNTY I, Dr. David Michael Slaughter, state that I am the Chief Executive Officer of Nuclear Labyrinth LLC, and that I am duly authorized to execute and file this response on behalf of Nuclear Labyrinth LLC. To the best of my knowledge and belief, the statements contained in this document with respect to Nuclear Labyrinth LLC ar~=- ~ ~

Subscribed and sworn before rm~, a Notary Public in and for the State of Utah and County of Salt Lake, this ~ day of Augus{, 201'6. < * **

  • WITNE$S my Hand and Notarial Seal: ~---=-=-

~NOtfilYPUblic My Commission Expires:

Date l<lf;:l'fAIW 1$U!\ILIC NARCISO PASILLAS 682410 COMMISSION EXPIRES MARCH 30, 2019 STATE OF UTAH 4813-5228-9591.vl

STATE OF MICHIGAN

TOWIT:

COUNTY OF OAKLAND I, Anthony Nellis, state that I am the President of Aerotest Operations, Inc., and that I am duly authorized to execute and file this response on behalf of Aerotest Operations, Inc. To the best of my knowledge and belief, the statements contained in this document with respect to Aerotest Operations, Inc. are true and correct.

Subscribed ands~ before me, a Notary Public in and for the State of Michigan and County of Oakland, this . I day of August, 2016.

WITNESS my Hand and Notarial Seal:

My Commission Expires:

'Date RUTH A. WILKENING ...,..._.(

Notary Public, State of Michigan Counfy of Oakland I

My Commission Explr .ec , 0 i Aeling In the Coun~.(lf~**'"=--=-~.i 4849-9242-1175.vl

UNITED STATEs.**

.;..

  • u~.ENs~.

AUT:H~.R!.1Y *~lLE, .cop_r ATOMIC ENERGY COMMISSION WASHINGTON, D.C, .20545

..-.AEROTEST OPERATIONS, INC.

  • DOCI<ET .NO.. 50-.228

, AEROTEST RADIOGRAPHY AND RESEARCH REACTOR (ARRR)

.AMENDMENT*TO.FACILITY OPERATING.LICENSE

.Amendment *:No .* .a:-

License No. "R-98 iv"e.~. ,e'i,.k1"."t*,,~

1. The M;em;i.c ~~.Commiss~on (the* Commission) has found tbat::
  • 1111d1ru.t A. The application .forAtransfer of 11.c.ense *fi"led by 9fl*; Ine . .fsr-~~--

Aerotest Operations., *rll:c* (the licensee) ,.(comp ies -wit t e .a."d

  • standardfl and requirements of the .Atomic* Energy Act of :1954., .as IVw.c/e..,,.

,,-., * *. a:mended (the* Act)~ and the Commission's .rules and regtilations L<tliyri,. 'th~

I i ' i set* forth in *~o CFR Chapte~-i;

. r~c:.

-B. Construction of *the facility "has been substantially *completed

  • in cmiformity W:ith Cori.~truc.tLoti .Permit :No. CPR.R-86,* .and .the

. appli.cation, as amended, the provis"ions "of the .Act and *the *.r.ules and regulati9ns .of the Commiss;i.on-;

c. .The faC.i"lity will . operate in conformi~y with the app'lication., as amendea, the provisions of the Act., a~d the rU.l.es and :regulations

.of the* Connnission:;

D. There is :reasonable assurance.: (i.) .that the .activities authorized

~y tbis .op~rating license can .be conducted without endangering the health and safe~y of the public, *.and (ii) that .sucn activities will

  • be conducted .in compliance with *the rule~ and* .regulations *of the Commiss~on'.;

E. Aerotest Operations, Inc. is technically and -financially qualified to l:io*sse.ss, use, and operate "the fac.ili:ty in .accordance with the

)'.'.ules and regulations of *the Comrnissio~;

LICENSE AUTHO.Rl.I¥- fJL~ ~coex

f. The issuance of this o.pe.rating .license will not be inimical to

.the common defense and security or to the heal.th and safety of the*pulilic, and does not involve* a significant hazards con-*

sideration-;

G. 'The receipt, possession, and* use of byproduct .an~* special nuclear

. *material as- author.;Lzed *_by th:ts license will be in accordance with the Commission's regulations in 10 CFR Parts 30 and.70, including

  • Sec~ioris 30.* 33, 70. 23, and 70. 31; H. The licensee. is qua'lified to .'be the holde.r of *~he' license:; and I.

~

Th~transt'er :of the license is otherwise consistent with applicable provisions of law, regulations, and orders issued by '.the Commission pur.suant* .there to.

.2. Facility Operat*ing License Nb.; R-98., flt'eviei.:u;efiss~ed to krejet: MtmxalJ

Y- Get:p&ratien, ..is hereby t: ... a11sfo1rrea to Aerotest Operations., .Inc. aaa tf.ie liS9Ri1 ; s re?,ge;yer;l .iH it;s e.ft.t:i:rety t;e. X:QOIQ 8$ fol] ows-=- :> l:S he~b Md*~*t.-1-!J

-1/.~f~v'.,e.!. ~ N uc.l-UA

  • L4.b'J.A*Vl+A 1 :i:....c.. . *
  • A.. This "license applies .to .the Aerotest Radiography and !{esearch (ARRR) ., fL,re:gi ons 1 y eaJJ Ge ehe Aereje t:: Ge'fteral ~ltte'leat lft<:h:1s tdal.

-Re.aster (ASNIR:), a pool-type nuclear* reactor owned 'by the O~As Lie-.

'The facili*ty is located at the .Aerote~t Operations site near San

.Ramon, *California, and is described in the ap'plication dated

.September 14, 1964. (the applicati.on)., and' in supplements thereto,

.including* the application -for trans'fer of J.icense *dated April 24, .

'l.974). a"6 ~~ ~prl1<J1t'"" .f,,.., ~J~ef ./1~111-S~* d,,,hJ l1a 1 3o, '1.cD12..

B. Subject to *the conditions and*-requirements incorporated *herein, the .

Co~ission.hereby licenses Aerotest Operations,' Inc.:

. (1) :Pursuant to Section 1.04c of *the Act and 10 CFR Part 50, 11

.Licensing of Production and *Utilization Facilities", to possess, use, and operate t*he *reactor at the designated

.location *in* San Ramon, California, in accordan.ce -with the procedures and limitations set .forth .in thi~ .license;

.(2) Pursuant to the Act.and 10 CFRPart 70, 11 Spe~ial Nuclear "Material", to receive, possess,, and use up *to'5.0 kilograms of *contained uran*ium 235 in connection with operation of the reactor; and (3) Pursuant to* the Act and 10 *cFR Part 30,. 1.1Licensi,1g of Byproduct Material", (1) to receive, possess,. and use a

.2 curie americium-beryllium neutron startup source, and (2) to possess, but i:iot to separate, such byproduct material i ...

I as may be produced by op*eration of the reactor,

  • ...~. .{

- '3 -

c. This license shall be deemed to contain and is subject to the c~l)ditions specifio.~ in the fol:ldwing Commission regulations i~

10 . C.F.R .Chapter- I: Part 20*, Section 30.-34 "of Part 30; .SectioD$ 50. 54

.and' 50.59. of :Part;: 50, .*and Section. 70.:32 of Part 7.0.; iJ; .subject: to all. applicable provisions -of the Act* and to the_ *rules, re~lations, and orders *of the Commission now or* herea:fter .in effect;*:.and is subject 1to the additional* conditions specified or :incorporated*

below: *

(1) Mnximum 'Power Level The licensee is authorized to operate *th~ facility .at steady state J>P'W~r levels. not in excess. ot. *2sO :ki'lowa~tts (thePl!Ci1) ~

"~*...

  • (2) Tec:lmj.c."ai Sp!;!C'ifiC:a tions
  • A ,;.~t- ti 1. The *Technical Specific contained in "App~ndix A, *as revised*
  • through Amendment No~ . _, are hereby incorpor.~ted *in* *the license.~:.

. The licensee shall operate the faci'lity in accordan.ce with the.k l _, 2i .. g1 .Technica.l Speci fi catfons.

  • - {'3:) . P.h.ysical.Security Plan
  • ' ~- 'ffh-e**1;.ce~s*.ee shall mafotafo in *effect and *fully jmj;lement a11 * . ....",

'I

/ *~ * . provtsians of. the NRG-approved physical securit,r plan. 'including * .. ~.

-~* V\\ am~nd~en~s *and chan.~es *made purs.uant .to *t~e :a~thori_ty :~ ~lO . . .

~~

t'i"* 'l,\ . CfR. 5ecU.on. :50 *.S4(pJ. 'The approved security :plan con~1sts '

~~ ;\\\. of *the* d~c1:1ment *~ith~eld ,f:rom *public .:_d1sclosu_re pors~nt "tc! ~;:

\~ . \ 10 CFR 2. 7~0 (.d,), e~~1tl e.d n Aei:-ote7t Operations, Inc~ Secur~ty,;::,

Plan"* *dated .August 109 1976, subm1tted .by.letter dated. r;:c-

~~ob_er 4, 1976, as revised Janu_ary *16, "H79. --c:::-

D. Rcpo~ts

'In addition* to :repor.ts otherwise *required under this license .and applicable regu1ations:

(l)°' . The 'licensee shall rapo'J."'t 'in .wri.tii:ig to the Comrniss;ion vi.thin

  • 1.0...._d_ays of *i~s observed occurrence *any incident or condition
  • relating to *.the .operation of the facility which p.revented or.

could *have ,prevented a nuclear system from perfbrming i:ts

. saiecy function as described in the .Technical Spec.ificat;ipns or in toe Razetrds Summary Repo*rt. * *

(2) The *licensee shall report to the Commission .in writing l..-1..thin 30 days. of its o.bserved occurrence any substal\tial variance "d,isclosed by operation of the facility from perforn:ance spcci-

.ficatioris CC?nta.ined in the Hazards Summary Report or the

.J) Technical Sp~cifications *

.(3) !he licensee shall report to the Commission .in writing vi.thin 30 days of its occurrence any significnnt change in transient or* accident analysis, as .;iescribed in the Hazards 5111llm:'1cy

  • Report.

E. Records In addition to those otherwise required under this license and appli-cable regulations, the licensee shall ~eep the following:

  • **O**

...1 *...** ............_..._...

.(l)* Reactor operating rec:ords, _including power levels.

(2). Re.cords of in-:pile irradiations.

(3) Records .showing zadioactivity released or discharged ~nto t:he .air or water beyond the *effective control of the licensee as measured at*the point of such release or discharge ..

(4) Records *of emergency reac*tor scrams,. *including reasons for emergency shutdowns.

F. This wot.t.IJ ha.V.c.....e1mtt amended~cense e.J:pir~ ~~

is effedi~e as of th:-::e midn{ght April 16, 2005J b,,..t IS f * .

~1e.lst~a.;:.,ce and tL.. fl~,~ ~r..~w-.L Joct"/\.iv..._ ~1oocl 1,,o1 ill <;7.JV'_d~ /e.e.;~ca"'ii) .

Cot11l1111.\~ 1\1\ ~(feet. f>u..~'"1 /\.tSoli..o-fuiit ~R THE'~)r07rr£ EJEt\Jiit\CO~l:lHSS!O~~ .. -

of t~~ M.,.ew4--C. app/1e4':f,o~ . * . *

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S(Lfpl~w-.e111.".l.

is, 1oos- (/S g

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"1 29 rfi;~

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X.llrl R. Goller, Assis taut 1511 ectbr

. f<;?r OpQraT::iug Reaecors Iljrss~erate cf Lie~Rsiag

Attachment:

  • Change No * .,g. to the Technical Specifications Da-te of Issuance: C4:tebe:r 22, 1974

/

AEROTEST OPERATIONS, INC.

DOCKET NO. 50-228 AEROTEST RADIOGRAPHY AND RESEARCH REACTOR (ARRR)

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 5 License No. R-98

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

A. The application for indirect transfer of license filed by Aerotest Operations, Inc. (the licensee) and Nuclear Labyrinth, Inc. complies with the 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;

  • B. Construction of the facility has been substantially completed in conformity with Construction Permit No. CPRR-86, and the application, as amended, the provisions of the Act and the rules and regulations of the Commission; C. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; D. There is reasonable assurance: (i) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public, aiid (ii) that such activities will be conducted in compliance with the rules and regulations of the Commission; E. Aerotest Operations, Inc. is technically and financially qualified to possess, use, and operate the facility in accordance with the rules and regulations of the Commission; F. The issuance of this operating license will not be inimical to the common defense and security or to the health and safety of the public, and does not involve a significant hazards consideration; G. The receipt, possession, and use of byproduct and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30 and 70, including Sections 30.33, 70.23, and 70.31; H. The licensee is qualified to be the holder of the license; and I. The indirect transfer of the license is otherwise consistent with applicable provisions of law, regulations, and orders issued by the Commission pursuant thereto;
2. Facility Operating License No. R-98, issued to Aerotest Operations, Inc. is hereby indirectly transferred to Nuclear Labyrinth, Inc.

A. This license applies to the Aerotest Radiography and Research Reactor (ARRR), a pool-type nuclear reactor owned by Aerotest Operations, Inc. The facility is located at the Aerotest Operations site near San Ramon, California, and is described in the application dated September 14, 1964 (the application), and in supplements thereto, including the application for transfer of license dated April 24, 1974, and the

[ application for indirect transfer dated May 30, 2012.

B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Aerotest Operations, Inc.:

(1) Pursuant to Section 104c of the Act and 10 CFR Part 50, "Licensing of Production and Utilization Facilities," to possess, use, and operate the reactor at the designated location in San Ramon, California, in accordance with the procedures and limitations set forth in this license; (2) Pursuant to the Act and 10 CFR Part 70, "Special Nuclear Material", to receive, possess, and use up to 5.0 kilograms of contained uranium 235 in connection with operation of the reactor; and (3) Pursuant to the Act and 10 CFR Part 30, "Licensing of Byproduct Material", (1) to receive, possess, and use a 2 curie americium-beryllium neutron startup source, and (2) to possess, but not to separate, such byproduct material as may be * >

produced by operation of the reactor.

C. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The licensee is authorized to operate the facility at steady state power levels not in excess of 250 kilowatts (thermal).

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 5, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

2

(3) Physical Security Plan The licensee shall maintain in effect and fully implement all provisions of the NRC-approved physical security plan, including amendments and changes made pursuant to the authority of 10 CFR Section 50.54(p). The approved security plan consists of the document withheld from public disclosure pursuant to 10 CFR

2. 790(d), entitled "Aerotest Operations, Inc. Security Plan" dated August 10, 1976, submitted by letter dated October 4, 1976, as revised January 16, 1979.

D. Reports In addition to reports otherwise required under this license and applicable regulations:

(1) The licensee shall report in writing to the Commission within 10 days of its observed occurrence any incident or condition relating to the operation of the facility which prevented or could have prevented a nuclear system from performing its safety function as described in the Technical Specifications or in the Hazards Summary Report.

(2) The licensee shall report to the Commission in writing within 30 d~ys of its*

"-'1 observed occurrence any substantial variance disclosed by operation of the facility - .. ~

from performance specifications contained in the Hazards Summary Report or the Technical Specifications.

(3) The licensee shall report to the Commission in writing within 30 days of its occurrence any significant change in transient or accident analysis,:.as described in the Hazards Summary Report.

E. Records In addition to those otherwise required under this license and applicable regulations, the licensee shall keep the following:

(1) Reactor operating records, including power levels.

(2) Records of in-pile irradiations.

(3) Records showing radioactivity released or discharged into the air or water beyond the effective control of the licensee as measured at the point of such release or discharge.

(4) Records of emergency reactor scrams, including reasons for emergency shutdowns.

F. This amended license is effective as of the date of issuance and would have expired at midnight April 16, 2005, but is subject to the timely renewal doctrine and will 3

continue in effect pending resolution of the renewal application filed on February 28, 2005 as supplemented.

FOR THE NUCLEAR REGULATORY COMMISSION r

Attachment:

Change No._ to the Technical Specifications Date of Issuance:

4

=- '1'1-ems.=lljl S~Hgq~lj.-B&IYetl &-"3:7--~

Do f~ot Remo~i~

  • f *APPENDIX A LICENSE NO. R-98
  • TECHNICAL SPECIFICATIONS FUR THE

. 1!firmrn-1~ Mr/CfIJF/~CfS'-tIMtrf~ /JiFblchtdrt !f/Pl<iJiJIFl.'I Na:m~hYged t9-I* Aerotest Radiography and Research Reactor (ARRR)---Y@- 22 "il4

l. 0 Defini.tions
1. 1 Shutdown "The reactor, with fixed e~periments in.place, *shall be con-

.side:i;-ed to be shut dpwn {not in operation) whenever ail o.f the foll,owing conditions.have been met: (-a) the cc;>n.sole

. key is in t~~ "off" ,po~itiOn. an4 thtii, key is ,removed from ..

  • the consoie ~hd under .the' control* of a licensed ope~ator

'(or stored in a locked storage area); (b) sufficient .control rods are inserted .so as to assur~ *the .reac*tor is subcritical by a margin greater than O. 7% delta k/k cold, .clean critical condition; (c) no work:is .in-progress *involving *refueling

  • operations .o~ *maintenance of its control .rod.,me(:.hanisms.

1.:2

  • Reactor Operation l

Reactor operation shall *mean any condition wherein the reactor is not .shut down.

1. 3. Operable A system or com,ponent .shall be consiClered operable* when ii:

.1$ capa~le :of performing i.ts .required function .~n its normal manner.*

1.4 Operating_

A component or system is operating *if it i.s performing 'its

.required :function in its' normal. manner.*

1. 5 * 'Exoeriment Experiment shall mean any apparatus, device, or material
  • installed in *the core or experimental facilities (except for underwater lights, fuel storage .racks and the like) which is *not a normai' part of these *facilities .*

I I

i

2 -

1.6 Experimental Facilities

.. Exper.imentai facilities shall me.aJ;J. Glory Hole; vertical . tubes, pneumatic transfer systems, central thimble, beam tubes, thermal column, and in-pool irradiatic;m facilities.

1. 7 Reactor Safety Circuits*

_l.\eracrto.r-_ safety.circuits shall mean those circuits, including ~

their associated input circuits, which are designed to initiate a reactor scram.

2.* 0 Reactor Site 2.1 The reac.tor .and associated equipment is* located within an exclusion area. at the tror&Jg-f.leoe~ *~.,. -* fi.=RilDlG>a-

  • ~ Q~'--'J", 8~ I 0 -r9-0l - 7 '( ~

. 2 .2 .A steel, .locked *perimeter fence shall surround the~

ARRR.]~g:lf fm~;i.lity, 'forming an exclusion area. The minimum distance from*the center of the reactor.pool to the boundai::y of the exclus.ion area fencing shall be 50 fe~t. .Th~ *restricted area,

,. as defined in 10 CFR 20, shall consist of the entir~ *exclusion

-- . " area.

2.3 *The. principal activities carried on within the exclusion area . /

shall be those associated with the op~ration of the:~ARRR 1 reactor and the use of a hot cell and chemistry laboratory.

3.0 Reactor Building 3 .1 The reactor shall be housed in a steel building capable of meeting the following functional requirements:

3.1. l all circulating fans and .air *condl.:t:!oning systems .except the system which supplies air to the control room .

shall have the capability to be shut off *from a s:i_ngle control in the control room, 3.1.2 ventilation shall be achieved by gravity ventilators located on the roof of the building, and 3.1;3 a positive air pressure shall be maintained in the control room with respect to the reactor room.

(-~*'\.13.2 An alarm system shall be installed to detect unau-thorized entry*into the reactor building. The alarm

.system shall be monitored constantly and its annun-

-** ciation shall be tested monthly.~

/

, .4.0 Reactor Pool (Primary System) *

    • ..... 4.1 The Jllinimum depth of water above the top of the* ac.tive core shall be i6 ft. The maximum ~ulk water temperature shall be 130°F and the minimum 60°F *

. 4 *. 2 l'he_ pli and conductivity of the prima.ry coolant shall *be measured at* least once*"each month. Corrective action shall be taken to avoid ex~eeding a pH of 7 .5* or .a conc:iucUvity of 5 umho/cm.

5.0 .Reactor Core

~

5.1 . Fuel Elementi{: ~'.

5.1.l The reactor shall contain*:no ...mone:!*than~;. ,;;:: 90 TRIGA type =:filer elements. l'he core shall be loaded wi.th not* *mor~g.than 3*.30 kg of **U-235.

'  :. "; ~-

.5.1.2 The *maximum exeess reactivity a,bove cold~ clean critical, with.. or. without expetjments .i~ place~ shali be 3 dollars

  • 5.1. 3 The batlf'temperature coefficient and the prompt fuel tempe~at;ure coeff.ic:i.ent shall be negative at all operattng temperatures *:*and the minimum reactivity '/ I
  • decrement at .full power shall *be 80 cents when measured with *.tespe~t to source. p~*er level.
5. L 4 'The coolikt void coefficient shall* be .negative across the *active core. MB.xi~':liii'*in-cere *operating void".shall be 10% *of the coolant ~'ore volumes as defined by a .

cylini;ler..:.bounded by th~ g:i:-id plates, 5.2 Reflector *Elements 5.2.1' The everalt' reflector elements' dimensions shall be the same as the fuel t?lemen'ts.

5.3 Control Elements

. il 5.3.1 The reactor shall' be sub~ritical by a minimum ~argin of 0.50 dollar.:* when 'the maximum worth rod is fully withdrawn from the core.

5.3.2 The maximum rate of reactivity addition for the control rods shall be 11 cents/second*~ Ther~ shall be a mini-mum of three ~perable contr.ol elements.

,_.--*- -""'"--""~--""'- ~--""'-**-",..."--** _,,_ - ___,_,,._.,_. ..._,._,~ ...... -- __ _,__ --*-'~- ---- -- --"------- ----*- _____ .....,,_ -- ------------- --~ - .... -- - -

.5.JoJ The tatal time for insertion of the 'control rods fol-lowing receipt of a.scram signal by the safety*system shall be a maximum of *600 milliseconds.

6.0 Reactor Safety* Systems 6.1 The reactor safety system shall include sensing devices and associated circuits which automat:l.cally actuate visual and audible alarms and, when certain pr*e-set limits are e;x-

.ceede~., ~cram the r~actor. .TP,e systems shall l;Je fail-.safe

'(de-energizing shall cause a. scram). Tab.le 1 describes .the*

minimum xequirements of* the safety system, 6.2 The nuclear, process and radiatian monitoring instrumentation shall provide the functions and have *the set point *range*s and associated annunciations listed in Table 2 of these

.specificatlons.

6. 3
  • The. safety system shall be desig.ned such that no single ,.

component *failure or circuit fault shall simultaneously

./ .....

/ .,

6.4 Reactor sequences, interlocks and safety circuits shal1

..... remain operable while fuel is in the core except that one channet *may be removed for maintenance purposes when the reactor is shut down.

6.5 Interlocks sha~l _prev~nt safety rod withdrawal unless all of the foliowing. conditions exist:

6.5.l The master switch is in *the ON position; 605.2 The safety system 'has been reset;'-~  :.. *: :*

.6.5.3 All four nuclear instruments channels. are in the OPERATE mode;

  • 6.5.4 The startup channel count rate is greater than 2 cps.

Ii: shall not be po~sible to withdraw more than the-safety ro~ until it has reached *the upper limit interlock, at which time either the shim ~r regulating rod may be moved, but only one at a time, I

/' "**

i'. ___ )

Ii

.I I

-*---~- ---*- ~**-**--* _____ ..:-., ________ . -~- --------~------- ~**

5

©

~~ ~~=~~g 0

a critical experiment.,Jsubcritical mult'iplication

~ shall be obtained from at least three instrumentation *- -* -

chap.nels.. These* channels may be used in addition to the normal oper~ting ins.trumentation in Table 1.

6.7 Process instru;nentation with readout in the control room shall be ~pe.rat:ing to permit continuous indication of pool water temperature and conductivity.. Alarms shall be pper-abted. _to indicate* low water flow low pool water and improper

.location of the crane bridge. '

7.0 -Radiation Monitoring ----- -~----*-- -

~ .. l"T"A7=~f7i='='xe~d==g=a=mm==a~m~o~n~iQt=o=r=e=m=p=l~~~~y=~~*:-n=-=g;G~e:::;-i~*g=;er;;;:;;tu~b~e;;;:d=e==te==c=to=r=s::::;:::::~==t:::::~~..-;;:

shall be located on the wall connecting the control ./

room and the reactor room. This monit:or shall .serve .  : *f .!&

  • as both an area*radiation.monitor and a criticality* vcc..Hca ,1,{' 10 alarm and will annunciate through an automatic ()\\l,
  • i>
  • monitoring* system to th_e San Ramo~Galiforzxil!'l Fire * () . \ }'

and actuate a siren within the reactor ~

building on high radiation level. The monitor shall have a minimum range of 0 to 20*mr/hr. The annun-cia.tion and the siren actuation shall be tested t .. 0 riC:k.t&t-'f"5 mo_nt_~ly -~ ~e.e. 3 rY I aA fJ {)

7.. 2 During reactor operation, a gas sample shall be continuously /

withdrawn irom the roof vent above .the reactor, or from the .-.,

vicinity of .the reactor bridge and glory hole over the *reactor core, and _pumped *through a radioactive gas detection chamber.*

~he gas chamber shall be _monitored by a beta-gamma detector which .shall have? a continuous readout in the control *room *

. An annunciator shall indicate whe~- the gas exceeds 2 mr/hr.

7 .3 A fission. _product water monitor shall be attached to .the process water cleanup system loop adjacent to the deminer-

-alizer .and shall provide continuous indication :in the control room. High radiation levels within the demineralizer or

=pool water shall annunciate an audible alarm on the reactor console. The range of the monitor shall be *from O. l to *100 mr/hr.

7.4 Portable survey instruments for measuring beta-gamma dose rates *in- the range of 0.01 mr/hr *to 50 r/hr.shall be ..

available at the facility.

7.5 Portable instruments for measuri~g fast and thermal neutron dose rates from 0.1 mrem/hr to 1.0 rem/hr *shall bet1.1 *:*!

  • avai-lable .. at the facility.

... t.

I I

..- 6 7.6 Radiation detector packets.containing a series of threshold detectors shall be placed at several locations within *the reactor buil~ing for post-accident radiation analyses.

8.0 Experimental Facilities*

  • 8.1 Large-Component Irradiation Box 8.1.1 A large-component irradiation box.shall have a maximum volume of 20 cu. feet.* The box shall enc*ompass not more than 120° arc of the cor~ and shall be design~d*

so that it c~n be placed no* closer than 5 cm to the outer.row*df active fuel elements.

8.1.2 . The platform shall be positioned remotely relative to *the reactor core by a positive drive and *shall be f* ' !.:

cap~iye to *the stand which is bolted to the*floor ,of the tank. Positive mechanical stops shall *pr.event moving the experiment box into the active reactor ccre. 1 C~ .shall be used far plirging and. to maintain

  • a slight pasitive pressure in:;the box relative to* th~
  • pool water* pressure.

~. ,

8.1.3 To remove or install the experiment box, *the platform ~.. ;*_

shall be moved two or more feet away.from the _reactor core *. The box shall. then be lowered onto -1:he platform arid l?olted in place with remote handling equipment.

The vo.ided box shall be purged of air prior to* exposure to neutrons.

8.2 *Pneumatic Transfer Facility; 8.2.1 A pneumatic *transfer facility may be" located in any reactor core pos~tion. The facility shall be operated with dry C02 and exhausted through a fdilt~r.: .. :.: ..:::_ .;~.c ventilation system, which is monitored fol;" ra~ioactivity *

.8.2.2 The i.n-core 'portion of the transfer facility shall have a maximum.void.volume of 34 cu. in. in the active fuel .region. A manual control sball be pravided which is capable of overriding the automatic timer control *

.\

I

'i 1*

I 8.3 Glory Hole Facility 8.~.l A dry glory hole facility may be located* in any reactor core position. The glory hole shall accept capsules to a maximum of 1.35 in. in diameter.

8.3.2 . The glory hole shall be purged with co to prevent 2

formation of excessive.amounts of argon~41. Gas samples shall be taken near the pool when the glory hole f~cility is operated without a shield plug to insure adequate

.monitoring of radioactive gases.

8.4 Neutron .Radiogra?h}I"; Facility 8.4.l The beam tube shall consist of a two-section tapered tube having a rectanKular cross section. The upper r,'

and lower sections of the tube shall be equipped with a fill and drain line.

\

8.4.2. All.components contacting the pool water shall be fabricated from aluminum or stainless steel. *

~liiiii"""'=""-------------------~---;,.. *(o

! ,_-s.4.3 Th'e beam catche:::- shield shall consist of a movable **ri~e: 0 C- ,,,1 7

radiation shield~

= 1'"'

  • 8. 5 Thermal Column
  • I 8.5.l The thermal column shall be positioned remotely on steel locating pins immediately adjacent to the react~r
  • core.

8.5.2 The thermal column shall be composed of a three-foot cube of g,raphite encas~d in aluminum containing five rows of 1.5 in. diameter irradiation holes. The rows shall be placed 6 inches apart and contain seven holes per row.

Slotted beams shall :.,be provided to allow experiments to be attached directly_ ~o the thermal column.

8.6 Vertical Tube '.,,.****** *P-",."**:*' I 8.~ 6. l Vertical irradiation tubes, having diameters up ~o 6 in .*

may be attached* to the thermal column.

l 8.6.2 The ve"rtical tube shall be *purged with co2 to prevent*'

the formation of excess amounts of argon-41.

I

/

- 8

\

8.7 Other Irradiation Facilities 8.7~1 The central .7 fuel elements of the reactor may be removed from the core and a central irra~iation facility installed provided the cross-szctional area-of the facility does not exceed 16 in

  • 8~ 7 .2 Two triang.ular exposure facilities are available which shall allow the insertion of circular experiments to
  • a maximum of 2.35 :in *.diameter or triangular experiments to a maximum of 3.* 0 in. on a* side.

8.7.3 Irradiation capsules in the shape of dummy fuel elements shall have a maximum inner void volume of .34 cu. in.

in the active fuel region.

9.0 Ex2eriment Limitations 9.1* Experiments 'shall be evaluated in the most reactive condition.

9. 2. The documentation of experiments, which shall be reviewed and I

I approv.ed prior to insertion in the reac~or, shall include at-least:

9.2.1 The purpose of the experiment;-

9 .* 2.* 2 A dese:ri.ption of the experiment; and .

9.2.3 An analysis of th'e *possible haza::rds assodated* with the performance of *the experim~nt.

9.3 The value of .the.. reactivity worth of any single independent experiment sl;lall not exceed 2 d.ollars. .If such experiment~

are connected or otherwise related so that their combined reactivity could be added to the core simultaneously, their combined reactivity shall not exceed 2 dollar~.

  • 9.4 ';rhe reactivity worth of any single independent experiment not.rigidly* fixed in place shall not exceed 1 dollar~ If
  • such experiments are connected or otherwise related so t.hat their combined reactivi'ty could be added to the core simul-taneously, their combined reactivity worth.shall not exceed 1 dollar.

r

.r*-**,. \

- 9 9.5 No experiment shall be installed .~n the reactor in such a manner that it could shadow the nuclear instrumentation.

system monitors.

9.6 No experiment shall be installed in the reactor in such a manner that a failure could in:terfere with the insertion *

  • of. a reaict;or control e1ement.

9.7 No experiment shall be performed involvf~1g materials which coul~:

'9.7.1 Contaminate the reactor pool causing corrosive action on the reactor components or experimeµts; 9.7.2 Cause excessive p-roduction of airborne rad~oactivity; or 9.7.3 Produce an uncontained violent chemical reaction.

9.8 Experiments shall not *be perforined involving eq!-Jipment whose failure could result in fuel element damage.

9*, 9 The amount of special nuclear material contained in an experi-ment shall be *limited to 5 grams in the form of solid samples or 3 g*~ams in the form .of liquid.

  • Liquid .'special "nuclear
    • ma~eri< ls shall be doubly encapsulated *

.9. 10* *Experin. *in ts having moving parts shall be designed to have*

reactiv'ty insertion rates less *than 10 cents/sec except that mo:* ing parts* worth *1*ess than 5 .cents may be oscillated oi; removed at hig~er .£requencies.

eo.- ,. _ _ _ _ _ _ _ ------....-:.---------------~--------

. _>-"'9.11*. Solid e:. plosive materials may be brought into* the fac.ilit;y for the.purpose of being radiograplied in the neutron *radio.graphy facilities located above the .pool, prm.rided that the following conditions are met:

9al. l Individual explosive devices shall be limited*

to 1000 grains equivalent TNT encased in metallic s~eathing.

9.11.2 . The maximum quantity of explosive material that*may be possessed at.one time shall be limited to 50 pounds*equivalent TNT.

Sxplosive material shall be stored* in ..I

, ._ _.,.: ._..:*--,-----:-'---.'.I 9 .11.}

f~ *-* .-:esignated areas within the reactor facility. *I I

" ~---"----_ ',I ,a li

' 9 .11. 3.1 Only the explosive devi~es to be radiographed within 4 hrs, not to- r1

  • exceed a maximum of ten pounds ~
  • I )* "*

,/lL~*1.1tf't.*_., 'l_.r1.~!*.

equivalent TNT, may.be removed from the storage area at one time for radiographing, including. preparation but excluding packa_ged shipments,

~rvt ~r~

1 9.11.3.2 An accountability log shall be maintained to show the amount of explosive material in the reactor f ac.ili ty a't all times, ah*d. shall con ta in ___.*- -.....

a description of the explosive, and  :.; 4 .J 1oy11-.r'...1. .

the location within the *f*aei1ity . ~ *

(e.g., storage;*

  • acility, or shipping-dock).

9.11.4

  • The maximum amount of e:xp:los-ive *material contained in devices that .may "be placed in the radiography *facili.ties a.t .a .time shall be limited to five pounds equivalent TNT.

Explosive material in the radiation

~

r 9.11.4.1 f .\ '. field at one time shall be limited:*

. -~** to 1 pound equivalen:t 'rNT .

9.11.* 4.2 Explosive material cot tained . il1-

-1ong device(s) shall b ~ limited to 0,5 pound. equivalen TNT*per.

  • foot.~
  • .-------------===-=------------.------~-- ---------~---- .

......____,,.. . . . " .12. Personnel handlin_g the explosiv~ devices sha-11 be trained and familiar with the devices being radiographtd. ~

. . I.I*

9.12.l Personnel handling the"* explosive device~ shall cH .

use *special equ.ipment, such as no~sparking .tools.* itV 11 and shoes,* protective clothin_g, safety shields (Y.' 1-~ 1 and *.grounded benches as :required for. the ~- .

explosives being handled.

9.12.2 Pnshielded high frequency generating e~uipment shall not be operated within .50 feet of any e ..;:plosive device.

i  !

.JJJ

'I  : -=--=-

I

~

I ; r'0, (.

(~

9 .12

  • 3 .The explosivi; dev:'.ces shall be subjected to a total exposure no:: to exceed 3 x 1011 neutrons/ cm 2

. , .- ~

9.12.4

  • and 3 x *10 3 roent;:.ens of gammas *

~ ~

Explosive dev:t.ces that, upon "ignition, have or provide a thrus.t ~:n a ~efini~e di5ection shall be positioned *so as :.:o be, aimed a';Na"j from the reactor and components.~ ~ *

,j

" ~

r:>~q~IJ~h' pfu .

{

~

.J 10.0* General Operating Limitations 10,l Reactor operation shall be per:aitted only when two or more personn~l are io the reactor t~ilding, at least one of whom is a licensed Ope.rator;

.10. 2 The reac**i:;;-s-hall not be op er; ::cd wherever there are: significant defects in fuel elements, control rods or control circuitry.

1 *~** 10.3 1.Ipon occurrence of abnormal opr~~i.on of the* reactor,* including its controls, safaty systems .:;:1d auxiliary systems, action shall be. taken immediately *to secure the safety of the facility and determine the cause of *th* ab.normal behavior. I ll. 0 *Fuel St*orage and Transfer ll.l The fuel sto.rage pits located *.n the floor of .the .reactor room shall accommodate a maxir:. *m of 19 fuel elements (700 gm U~235) in storage racks dry or flooded *With water. The fuel storage pits shall be sec?. red with a lock and chain except during fuel transfer '?f *,rations.

11 .2 Additional fuel storage racks may be located in the rea~tor tank. Each of these storage facilities shall be so designed thatpfor ~11 conditions of moderation keff ~h~ll not exceed a value of 0.8.

  • ~

l I

ll. 3 A fuel. handling *tool shall be u~ed in transferring fuel ele-

! ments. *of low radioactivity bet;..*een ::he storage .pits and the reactor; a shielded fuel tr!lnf f~r cask shall be used for *the . .

\ transfer of highly radioactive. fuel elements. The fuel handiing l d e.v i'c.e.

tool shall pemain in a locked *.:&iaet un er e cognizance of the Reactor Supervisor when nc.t authorized for use.*

Amendment. No. 4

- ----~---*

. J.:ij'i

!"l ~ n ~ *1Q8"

.;.. .... ~ J r

(

12 - .

ll.4 All fuel transfers in tank shall be co~ducted by.

a minimum staff o.f three , and shall include a licensed Senior Operator and a licensed Operator. The staff members shall monitor t~e. operation using appropr.iate radiation monitoring instrumentation. F.uel transfers outside *the reactor tank but wi'thin the facility shall be supervised by a* licensed

  • Operator.
11. 5 Not *. mor~ than one fuel element shal.l be :allowed in the facility
  • which .is not in storage* or in the core lattice.

~~~~~-:---

.12.0 Administrative Reauirements VJ~ o sJi4.{/ ~~ M~('tm 8 '/,t._

~ rlw. ffl,(s1W 1 AJ/lo~+

12 .1 Organization. f>p.kc.:ho'"s~ Tne, 12".1.J The. Reactqr Superviso.r shall have 'l:e pons.ibility of the reactor. facility. In all matters _pertaining to 4, reactor operations and to these Techn"cal.Specificatfons, .f ~~ *'

.,___ _-r......., the Reactor Supervisot shall be respo risible to the * ~li--f /}\'!Jr.*. !

~-----.....--- :Pres+/-eiezr.t, Aerotcist Operations, Inc .. ,. u\A.{> i

( oo'Bsiel:iar.,- ef E.{p1osive 'feeffi:;islegy; ~ The President, u Aerotest Op~rations, Inc. shal1 report to the Board of

.Directors of Aerotest Operations, Inc .* wflieh .ineh14es .1 t..fte P:i: !::!!ident3 0£ eatfl: GEA, Irre. uud £.<;;plush e TeehHeleg;+ ..

-inc." -

I

'12.1.2* The Radiological Safety Officer .shall review and ~(.. RSo approve all procedures and experiments involving

  • 1 radiological saf~ty, shall. enforce .rules,

.. regulation~. and procedures r:lating. to. radio-

  • logical sarety > conduct routine radiation sur-. ~~

\.. r~*r

?~

/

c,., l veys. a~d i:.,;esponsible to the hanager, Aero test L..:' e_, ~ 1-l'i;,;.,.

. - --- --- --- - - -- Operations. * ...}" c,.h ...

12. l.3 The Reactor Safeguards Committee shall be composed of not. less than five members, of whom no mo.re th.an three are members of th.e operating organization. The committee **s a l meet on call -of the chairman and t:hey shall meet at -least annually, .The committee shall be
  • responsible for, but not limited to the fo.llowing:

12~1.3.l Reviewing and approving nuclear safety standards associated.with the use of the facility;

{

\.

12 .1. 3. 2. Reviewing and approving all proposed exp er~ -

rnents and procedures and changes thereto, and modifications to the reactor and its

. as~ociated components;

1*

- 13 II 12.~.3.3 Determining whether proposed experiments, proced~res or modifications involve unreviewed S.

<C-f loll'\ *-

safety questions; as defined in *10 CFR 50,

)-Paff 50.59(c), and are in accordance. with th~se Technical Specifications; 12.1.3.4 Conducting periodic audits of procedures, reactor operations '.'ind maintenance, equipment performance, and records; 12.l.3.5 Reviewing all reported abnormal occurrences . .., ( ,:

arid violations .qf these Tecl:).nical Specifications, \.. *'f A

f,; :I evaluating the causes of suc.h events and the ~~-/ ~'l.'

.] '"'"' li corrective action taken and recommending . ~~PO measures to prevent reoccurrence and; ':l.i1l *

}

12 .1.3 .6 Reporting* their findings and re*commendations r;:Ja e.--5* .

concerning the above* to the Manager, .Aerotest jf;J..7+-*:J.0:10 Operations~ . * * *

. ;I

12. l. 4 The Reactor Supervisor shall have a Bachelor 1 s degree

. (_ ---- in Engineering or Physical Science and. shall have a 1.is.i minimum of .4 years experience in the operation of a nuclear facility ur ng whichiAe shall have demonstrated =l comP.etence .. in. supervision and reactor operations. ~ 1'k. ~Jn..

shall ..hold a Senior Reactor Operator license for the /

facility.

12 .* 1..-5 The Radiological .Safety Officer shall have a Bachelor's degree in "Biological or Physical .Science and shall have a minimum of 2 years experience in personnel an4 environmental radiation monitoring programs at a nuclear facility. Certification as a Health Physicist by the Health Physics Society is acceptable in lieu of the education and experience requirements given above.

12.2 Procedures 12.2.1 Detailed written procedures shall be provided and followed for the following reactor operations:

12.2.1.l Normal startup, op~ration and shutdown of the complete facility and of *au* systems and components involving nuclear safety of the **

facility.

~*

(-*,

)

~ ... --~/

("*-*-.

14 -

12 ~ 2 .1. 2 Refueling operations.

........ -~* ~ ....,.~* .....::; : ..

  • 12.2.1.3 Actions to be taken to correct specific and foreseen potentiai malfunctions of systems or components, including responses to alarms, suspected primary system leaks and abnormal
  • reac tivi ty changes.
  • 12.2.1.5 Preventive or corrective maintenance opera-tions which could.have an effect on the safety of the reactoJ:'..

.-** . I*

12.2.2 Temporary procedures which do not .change the iIJ.tent of previously approved procequres may be utilized' on:approval by a licensed Senior Reactor Operator and one other qualified individual. Such procedures shall be.subsequently reviewed by the Reactor Safe-guards Committee.

12.3 ~cords 1:-. In ad4ition to *those records required u:nder the facility

, \.

license and applicable regulations, the following rec.ords shall. be kept when explosive mater.ialS are to be irradiated or radiographed: .

12.3.1 '.the type and quantity of material ir;r:adiated.

12.3.2 ~ate, time of day, and length of exposure.

12.3~3 Total neutron and gamma exposure level *

... ~***

\.1

)

TABI.E .l NUCLEAR INSTRUMENTATION Channel Detector Minimum Info:rmation Mii1imum. Range *rn.fotma t;ion to (No.) Sensitivity Logic Element

.. .. .. (scram) .

Startup ~ 6crton-l1ne4* . 4.s counts/sec per Neutron f~ux 1 source lev.~l to Perio.d ~.Ct'Cim; (a)*

(1) Proportional n/cm2 -sec *. pericid

  • 1 watt low -**coun.t rate Counter scran Log N Compensated 4 x io-14 amp/n/ Pm~et level, io-~ watts to Period scram (2) ion chamber cm2 -sec period- 120% full pow.er.

'Linear Uncompensated 4.4 -~ lo-14 amp/* Power*level 30 *watts to. High Cnd low Levei ion chamber n/cro -sec 120% f_ull power level b) scrams Safety (3) .. **- I.

Linear Compensated 4.4 x 10-14 amp/ Power* level 10-l watts-to High and* low Level ion chamber n/cm 2 -sec " 120% .full power level *scram Safety (4)

{a) Scram8 on Channel 1 are by-passed wheti' signal on Channel .2* exceeds a fixed *setting similarly the

  • high voltage *is removed from the detector and* the detector is shqrted~ ~-,,.,...

(b) Low level scram is bypassed o.n Channel 3 and* 4 when Channel 2 is below**ii fixed setting.

~

.:.i

~

16 - j.

'I i

TABLE 2 .r ...

"*: SAFETY SYSTEM FUNCTIONS.

No. o; Switches An~unciator aid . -. Annunc:.iator and Sensor or Tri Device

  • or Sensors Scram Set Poi,. t Alarm Set Point 2:.

- High Neutron Flux * '.

2 3 sec *.

r r*.

level; Chs.* 3, 4 2 ~ 9s'7. ~£ *"fu*u scale and not

  • greater than.1201.

full power *

  • High Temperature of '
  • -Cootan*t Water l Low Pool Water Level l <1 ft max decrease Seismic Disturbance IV *on modified
  • Mercalli Sc;ile
  • i r:o . max. 1*

(, '

_) Bridge *Crane Location l When-located off

  • storage position i I

Loi1  :~eutron Detector

. Voltage; Chs. 2, 3, 4 3- ) 500 volts- r

(

Low* Source .Level; Ch. l* 1 I i:f. 2 cps I.

Loss *of Instrument Power; I  !*

  • *. Ch. 2, i* x  !

Low Neutron Flux; Ch. 3 -~57. of fuli

& 4 "2 . *-scale

.jJ I

Are.a Radiation Monitor 1 S, 10 mr/hr Water Radioactivity. 1

  • S20 mr/hr

.Demineralizer W~ter Flow 1 ~4 gpm Building Gas Effluent Monitor 1 ~ 2 mr/hr Master Key Switch 1 Not on "ON

!* position

\_

Manual Scram Button i'. Button Dep~essed

!t I*

.,. .... 1.."..:..!..~.i.iA\li". ** ~~ .....:.--~~"!i..t:-~~. ',\;o- * * * "'.-. . ,

I

'**~**!'-~

Appendix A License No. R-98 Technical Specifications for the

/ Aerl[)test Radiography and Research Reactor (ARRR) 1.0 Definitions 1.1 Shutdown The reactor, with fixed experiments in place, shall be considered to be shutdown (not in operation) whenever all of the following conditions have been met: (a) the console key is in the "off' position and the key is removed from the console and under the control of a licensed operator (or stored in a locked storage area); (b) sufficient control rods are inserted so as to assure the reactor is subcritical by a margin greater than 0.7% delta k/k cold, clean critical condition; (c) no work is in progress involving refueling operations or the maintenance of its control rod mechanisms.

1.2 Reactor Operation Reactor operation shall mean any condition wherein the reactor is not shutdown.

1.3 Operable A system or component shall be considered operable when it is capable of performing its required function in its normal manner.

1.4 Operating A component or system is operating if it is performing its required function in its normal manner.

1.5 Experiment Experiment shall mean any apparatus, device, or material installed in the core or experimental facilities (except for underwater lights, fuel storage racks and the like) which is not a normal part of these facilities.

1.6 Experimental Facilities Experimental facilities shall mean Glory Hole, vertical tubes, pneumatic transfer systems, central thimble, beam tubes, thermal column, and in-pool irradiation facilities.

1. 7 Reactor Safety Circuits Reactor safety circuits shall mean those circuits, including their associated

input circuits, which are designed to initiate a reactor scram.

2.0 Reactor Site 2.1 The reactor and associated equipment is located within an exclusion area.

2.2. A steel, locked perimeter fence shall surround the ARRR facility, forming an exclusion area.

The minimum distance from the center of the reactor pool to the boundary of the exclusion area fencing shall be 50 feet. The restricted area, as defined in 10 CFR 20, shall consist of the entire exclusion area.

2.3. The principal activities carried on within the exclusion area shall be those associated with the operation of the ARRR reactor and the use of a hot cell and chemistry laboratory.

3.0 Reactor Building 3 .1 The reactor shall be housed in a steel building capable of meeting the following functi01.rnl requirements:

3 .1.1. All circulating fans and air conditioning systems except the system which supplies air to the control room shall have the capability to be shut off from a single control in the control room.

3 .1.2. Ventilation shall be achieved by gravity ventilators located in the roof bf the building, and 3 .1.3. A positive air pressure shall be maintained in the control room with respect t9 the reactor room.

3 .2 An alarm system shall be installed to detect unauthorized entry into the reactor building. The alarm system shall be monitored constantly and its annunciation shall be tested monthly.

4.0 Reactor Pool (Primary System) 4.1. The minimum depth of water above the top of the active core shall be 16 ft. The maximum bulk water temperature shall be 130°F and the minimum 60°F.

4.2. The pH and conductivity of the primary coolant shall be measured at least once each month.

Corrective action shall be taken to avoid exceeding a pH of 7 .5 or a conductivity of 5 umho/cm.

5.0 Reactor Core 5 .1. Fuel Elements 5 .1.1. The reactor shall contain no more than 90 TRIGA type fuel elements. The core shall be loaded with not more than 3.30 kg ofU-235.

5 .1.2. The maximum excess reactivity above cold, clean critical, with or without experiments in place, shall be 3 dollars.

5 .1.3. The bath temperature coefficient and the prompt fuel temperature coefficient shall be negative at all operating temperatures and the minimum reactivity decrement at full power shall be 80 cents when measured with respect to source power level.

5 .1.4. The coolant void coefficient shall be negative across the active core. Maximum in-core operating void shall be 10% of the coolant core volume as defined by a cylinder bounded by the grid plates.

5 .2 Reflector Elements 5 .2.1. The overall reflector elements' dimensions shall be the same as the fuel elements.

5.3 Control Elements 5.3.1. The reactor shall be subcritical by a minimum margin of0.50 dollar when the maximum worth rod is fully withdrawn from the core.

5.3.2. The maximum rate ofreactivity addition for the control rods shall be 11 cents/second. There shall be a minimum of three operable control elements.

5.3.3. The total time for insertion of the control rods following receipt of a scram signal by the safety system shall be a maximum of 600 milliseconds.

6.0 Reactor Safety Systems 6.1. The reactor safety system shall include sensing devices and associated circuits which automatically actuate visual and audible alarms and, when certain pre-set limits are exceeded, scram the reactor. The systems shall be fail-safe (de-energizing shall cause a scram. Table 1 describes the minimum requirements of the safety system.

6.2. The nuclear, process and radiation monitoring instrumentation shall provide the functions and have the set point ranges and associated annunciations listed in Table 2 of these specifications.

6.3. The safety system shall be designed such that no single component failure or circuit fault shall simultaneously disable both the automatic and manual scram circuits.

6.4. Reactor sequence, interlocks and safety circuits shall remain operable while fuel is in the core except that one channel may be removed for maintenance purposes when the reactor is shut down.

6.5. Interlocks shall provide safety rod withdrawal unless all of the following conditions exist:

6.5.1. The master switch is in the ON position; 6.5.2. The safety system has been reset; 6.5.3. All four nuclear instrument channels are in the OPERATE mode; ..

6.5 .4. The startup channel count rate is greater than 2 cps; 6.5.5. It shall not be possible to withdraw more than the safety rod until it has reached the upper limit interlock, at which time either the shim or regulating rod may be moved, but only one at a time.

6.6 During a critical experiment a subcritical multiplication plot shall be obtained from at le,ast three instrumentation channels. These channels may be used in addition to the normal operating instrumentation in Table 1.

6.7. Process instrumentation with readout in the control room shall be operating to permit continuous indication of pool water temperature and conductivity. Alarms shall be operable to indicate low water flow, low pool water and improper location of the crane bridge.

7.0 Radiation Monitoring 7 .1. A fixed gamma monitor employing Geiger tube detectors shall be located on the wall connecting the control room and the reactor room. This monitor shall serve as both an area radiation monitor and criticality alarm and will annunciate through an automatic monitoring system to the San Ramon Valley Fire Protection District and actuate a siren within the reactor building on high radiation level. The monitor shall have a minimum range of 0 to 20 mr/hr. The annunciation and the siren actuation shall be tested monthly.

7.2. During reactor operation, a gas sample shall be continuously withdrawn from the roof vent above the reactor, or from the vicinity of the reactor core, and pumped through a radioactive gas detector chamber. The gas chamber shall be monitored by a beta-gamma detector which shall have a continuous readout in the control room. An annunciator shall indicate when the gas exceeds 2 mr/hr.

7.3. A :fission product water monitor shall be attached to the process water cleanup system loop adjacent to the demineralizer and shall provide continuous indication in the control room. High radiation levels within the demineralizer or pool water shall annunciate an audible alarm on the reactor console. The range of the monitor shall be from 0.1 to 100 mr/hr.

7.4. Portable survey instruments for measuring beta-gamma dose rates in the range of 0.01 mr/hr to 50 r/hr shall be available to the facility.

7 .5. Portable instruments for measuring fast and thermal neutron dose rates from 0.1 mrem/hr to 1.0 rem/hr shall be available at the facility.

7.6. Radiation detector packets containing a series of threshold detectors shall be placed at several locations within the reactor building for post-accident radiation analysis.

8.0 Experimental Facilities 8.1 Large-Component Irradiation Box 8.1.1. A large component irradiation box shall have a maximum volume of 20 cu. feet.

The box shall encompass not more than 120° arc of the core and shall be designed so that it can be placed no closer than 5 cm to the outer row of active fuel elements.

8.1.2. The platform shall be positioned remotely relative to the reactor core by a positive drive and shall be captive to the stand which is bolted to the floor of the tank. Positive mechanical stops shall prevent moving the experimental box into the active reactor core.

C02 shall be used for purging and to maintain a slight positive pressure in the box relative to the pool water pressure.

8.1.3. To remove or install the experiment box, the platform shall be moved two or more feet away from the reactor core. The box shall then be lowered onto the platform and bolted in place with remote handling equipment. The voided box shall be purged of air prior to exposure to neutrons.

8.2 Pneumatic Transfer Facility

8.2.1. A pneumatic transfer facility may be located in any reactor core position. The facility shall be operated with dry C02 and exhausted through a filter ventilation system, which is monitored for radioactivity.

8.2.2. The in-core portion of the transfer facility shall have a maximum void volume of 34 cu. in. in the active fuel region. A manual control shall be provided which is capable of overriding the automatic timer control.

8.3 Glory Hole Facility 8.3 .1. A dry glory hole facility may be located in any reactor core position. The glory hole shall accept capsules to a maximum of 1.35 in. in diameter.

8.3 .2. The glory hole shall be purged with C::02 to prevent formation of excessive amounts of argon-41. Gas samples shall be taken near the pool when the glory hole facility is operated without a shield plug to insure adequate monitoring of radioactive gases.

8.4 Neutron Radiography Facility 8.4.1 The beam tube shall consist of a two-section tapered tube having a rectangular cross section. The upper and lower sections of the tube shall be equipped with a fill and drain line.

8.4.2 All components contacting the pool water shall be fabricated from aluminum or 'J'1 stainless steel.

8 .4.3 The beam capture shield shall consist of a movable radiation shield.

8.5 Thermal Column 8.5 .1 The thermal column shall be positioned remotely on steel locating pins immediately adjacent to the reactor core.

8.5.2 The thermal column shall be composed of a three-foot cube of graphite encased in aluminum containing five rows of 1.5 in. diameter irradiation holes. The rows shall be placed 6 inches apart and contain 7 holes per row. Slotted beams shall be provided to allow experiments to be attached directly to the thermal column.

8.6 Vertical Tube 8.6.1 Vertical irradiation tubes, having diameters up to 6 in., may be attached to the thermal column.

8.6.2 The vertical tube shall be purged with C02 to prevent the formation of excess amounts of argon-41.

8.7 Other Irradiation Facilities

8. 7 .1 The central 7 fuel elements of the reactor may be removed from the core and a central irradiation facility installed provided the cross-section area of the facility does not exceed 16 in2
  • 8.7.2 Two triangular exposure facilities are available which shall allow the insertion of circular experiments to a maximum of 2.35 in. diameter or triangular experiments to a maximum of3.0 in. on a side.

8.7.3 Irradiation capsules in the shape of dummy fuel elements shall have a maximum inner void volume of 34 cu. in. in the active fuel region.

9 .0 Experiment Limitations 9 .1 Experiments shall be evaluated in the most reactive condition.

9 .2 The documentation of experiments, which shall be reviewed and approved prior to insertion "'}f.

in the reactor, shall include at least:

9 .2.1 The purpose of the experiment; 9.2.2 A description of the experiment; and 9.2.3 An analysis of the possible hazards associated with the performance of the experiment.

9.3 The value of the reactivity worth of any single independent experiment shall not exceed 2 dollars. If such experiments are connected or otherwise related so that their combined reactivity could be added to the core simultaneously, their combined reactivity shall not exceed 2 dollars.

9 .4 The reactivity worth of any single independent experiment not rigidly fixed in place shall not exceed 1 dollar. If such experiments are connected or otherwise related so that their combined reactivity could be added to the core simultaneously, their combined reactivity worth shall not exceed 1 dollar.

9.5 No experiment shall be installed in the reactor in such a manner that it could shadow the nuclear instrumentation system monitors.

9.6 No experiment shall be installed in the reactor in such a manner that a failure could interfere with the insertion of a reactor control element.

9.7. No experiment shall be performed involving materials which could:

9. 7 .1. Contaminate the reactor pool causing corrosive action on the reactor components or experiments; 9.7.2. Cause excessive production of airborne radioactivity; or 9.7.3 Produce an uncontained violent chemical reaction.

9.8 Experiments shall not be performed involving equipment whose failure could result in fuel element damage.

9.9 The amount of special nuclear material contained in an experiment shall be limited to 5 grams in the form of solid samples or 3 grams in the form of liquid. Liquid special nuclear materials shall be doubly encapsulated.

9 .10 Experiments having moving parts shall be designed to have reactivity insertion rates less than 10 cents /sec except that moving parts worth less than 5 cents may be oscillated or removed at higher frequencies.

9 .11 Solid explosive materials may be brought into the facility for the purpose of being radiographed in the neutron radiography facilities located above the pool, provided that the following conditions are met:

9 .11.1 Individual explosive devices shall be limited to 1000 grains equivalent TNT encased in metallic sheathing.

9 .11.2 The maximum quantity of explosive material that may be possessed at one time shall be limited to 50 pounds equivalent TNT.

9 .11.3 Explosive material shall be stored in designated areas within the reactor facility.

9 .11.3 .1 Only the explosive devices to be radio graphed within 4 hrs. not to exceed a maximum often pounds equivalent TNT, may be removed from the storage area at one time for radiographing, including preparation but excluding packaged shipments.

9 .11.3 .2 An accountability log shall be maintained to show the amount of explosive material in the reactor facility at all times, and shall contain a description of the explosive, and the location within the facility (e.g., storage, radiography facility, or shipping dock).

9 .11.4 The maximum amount of explosive material contained in devices that may be placed in the radiography facilities at a time shall be limited to five pounds equivalent 1NT.

9 .11.4.1 Explosive material in the radiation field at one time shall be limited to 1 pound equivalent 1NT.

9.11.4.2 Explosive material contained in long device(s) shall be limited to 0.5 pound equivalent TNT per foot.

9 .12 Personnel handling the explosive devices shall be trained and familiar with the devices being radio graphed.

9.12.1 Personnel handling the explosive devices shall use special equipment, such as non-sparking tools and shoes, protective clothing, safety shields and grounded benches as required for the explosives being handled.

9.12.2 Unshielded high frequency generating equipment shall not be operated within 50 feet of any explosive device.

9.12.3 The explosive device shall be subjected to a total exposure not to exceed 3 x 10 11 neutrons/cm2 and 3 x 103 roentgens of gammas.

9.12.4 Explosive devices that, upon ignition, have or provide a thrust in a definite direction shall be positioned so as to be aimed away from the reactor and components.

10.0 General Operating Limits 10.1 Reactor operation shall be permitted only when two or more personnel are in the reactor building, at least one of whom is a licensed Operator.

10.2 The reactor shall not be operated whenever there are significant defects in fuel elements, control rods or control circuitry 10.3. Upon occurrence of an abnormal condition of the reactor, including its controls, safety systems and auxiliary systems, action shall be taken immediately to secure the safety of the facility and determined the cause of the abnormal behavior.

11.0 Fuel Storage and Handling 11.1. The fuel storage pits located in the floor of the reactor room shall accommodate a maximum of 19 fuel elements (700 g U-235) in the storage racks dry or flooded with water. The fuel storage pits shall be secured with a lock and chain except during fuel transfer operations.

11.2. Additional fuel storage racks may be located in the reactor tank. Each of these storage facilities shall be so designed that for all conditions of moderation Keffshall not exceed a value of 0.8.

11.3. A fuel handling tool shall be used in transferring fuel elements of low radioactivity between the storage pits and the reactor; a shielded fuel transfer cask shall be used for the transfer of highly radioactive fuel elements. The fuel handling tool shall be enclosed in a locked device under the cognizance of the Reactor Supervisor when not authorized for use.

11.4. All fuel transfers in the reactor tank shall be conducted by a minimum staff of three p~ople, and shall include a licensed Senior Operator and a licensed Operator. The staff members shall monitor the operation using appropriate radiation monitoring instrumentation. Fuel transfers outside the reactor tank but within the facility shall be supervised by a licensed Operator.

11. 5. Not more than one fuel element shall be allowed in the facility which is not in storage or in the core lattice.

12.0. Administrative Requirements 12.1. Organization 12.1.1. The reactor supervisor shall have responsibility of the reactor facility. In all matters pertaining to the reactor operations and to these Technical Specifications, the Reactor Supervisor shall be responsible to the General Manager, Aerotest Operations, Inc. who shall be responsible to the President, Aerotest Operations Inc. The President, Aerotest Operations, Inc. shall report to the Board of Directors of Aerotest Operations, Inc.

12.1.2. The Radiological Safety Officer shall review and approve all procedures and experiments involving radiological safety. The RSO shall enforce rules, regulations and procedures relating to radiological safety, conduct routine radiation surveys and is responsible to the Manager, Aerotest Operations.

12.1.3. The Reactor Safeguards Committee shall be composed of not less than five members, of whom no more than three are members of the operating organization. The committee

shall meet on the call of the chairman and they shall meet at least annually. The committee shall be responsible for, but not limited to the following:

12.1.3 .1. Reviewing and approving nuclear safety standards associated with the use of the facility; 12.1.3.2. Reviewing and approving all proposed experiments and procedures and changes thereto, and modifications to the reactor and its associated components; 12.1.3 .3. Determining whether proposed experiments, procedures or modifications involve unreviewed safety questions, as defined in 10 CPR 50, Section 50.59(c), and are in accordance with these Technical Specifications; 12.1.3 .4. Conducting periodic audits of procedures, reactor operations and maintenance, equipment performance, and records; 12.1.3.5. Reviewing all reported abnormal occurrences and violations of these Technical Specifications, evaluating the cause of such events and the correptive action taken and recommending measures to prevent recurrence <!-nd; 12.1.3.6. Reporting their findings and recommendations concerning the above to the Manager, Aerotest Operations.

12.1.4. The Reactor Supervisor shall have a Bachelor's degree in Engineering or Physical Science and shall have a minimum of 4 years experience in the operation of a nuclear facility during which the Reactor Supervisor candidate shall have demonstrated competence in supervision and reactor operations. The Reactor Supervisor shall hold a Senior Reactor Operator license for the facility.

12.1.5. The Radiological Safety Officer shall have a Bachelor's degree in Biological or Physical Science and shall have a minimum of 2 years experience in personnel and environmental radiation monitoring programs at a nuclear facility. Certification as a Health Physicist by the Health Physics Society is acceptable in lieu of the education and experience requirements given above.

12.2. Procedures 12.2.1. Detailed written procedures shall be provided and followed for the following reactor operations:

12.2.1.1. Normal startup, operation and shutdown of the complete facility and of all systems and components involving nuclear safety of the facility.

12.2.1.2. Refueling operations.

12.2.1.3. Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, including responses to alarms, suspected primary system leaks and abnormal reactivity changes.

12.2.1.4. Paragraph omitted.

12.2.1.5 Preventive or corrective maintenance operations which could have an effect on the safety of the reactor.

12.2.2. Temporary procedures which do not change the intent of previously approved procedures may be utilized on approval by a licensed Senior Reactor Operator and one other qualified individual. Such procedures shall be subsequently reviewed by the Reactor Safeguards Committee.

12.3 Records In addition to those records required under the facility license and applicable regulations, the following records shall be kept when explosive materials are to be irradiated or radiographed:

12.3.1 The type and quantity of material irradiated.

12 .3 .2 Date, time of day, and the length of exposure.

12.3.3 Total neutron and gamma exposure level.

Ta_ble 1 NUCLEAR INSTRUMENTATION Channel Detector Minimum Information Minimum Information to No. Sensitivity Range Logic Element (Scram)

Startup Boron-lined 4.5 counts/sec Neutron Source Level Period Scram;

( 1) Proportional per n/cm 2-sec flux, to 1 watt (a)

Counter Period Low Count Rate Scram LogN Compensated Ion 4x10- 14 Power 1o-.l watts to Period Scram 2

(2) Chamber amp/n/cm - Level, 120% of full sec Period power Linear Uncompensated 4.4 x 10- 14 Power 30 watts to High and Low Level Ion Chamber amp/n/cm2- Level 120% of full level (b) scrams Safety sec power

( 3)

Linear Compensated Ion 4.4 x 10- 14 Power 1o-I watts to High and Low Level Chamber amp/n/cm2- Level 120% of full level (b) scrams Safety sec power (4)

(a) Scrams on channel 1 are by-passed when signal on channel 2 exceeds a fixed setting similarly the high voltage is removed from the detector and the detector is shorted.

(b) Low level scram is bypassed on channel 3 and 4 when the Channel 2 is below a fixed setting.

Table 2 SAFETY SYSTEM FUNCTIONS Sensors or Trip Number of Annunciator and Scram Set Annunciator and Device Switches or Points Alarm Set Point Sensors Short Period; Chs 1, 2 2 ~ 3 seconds High Neutron Flux 2  :::; 98% of full scale and not Level; Chs. 3, 4 greater than 120% of full power High Temperature of 1  :::; 13 0 degrees F Coolant Water Low Pool Water 1  :::; 1 ft max decrease Level Seismic Disturbance 1 IV on modified Mercalli Scale max.

Bridge Crane 1 When located off Location storage position Low Neutron 3 ~ 500 volts Detector Voltage; Chs. 2,3,4 Low Source Level; 1 ~ 2 cps Ch. 1 Loss of Instrument 1 x Power; Ch. 2 Low Neutron Flux; 2 ~ 5% of full scale Ch. 3,4 Area Radiation 1  :::; 10 mr/hr Monitor Water Radioactivity 1  :::; 20 mr/hr Demineralizer Water 1 ~4gpm Flow Building Gas 1  :::; 2 mr/hr Effluent Monitor Master Kev Switch 1 Not on "ON" position Manual Scram Button 1 Button Depressed

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