ML20128D402

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Partial Response to FOIA Request for Documents.Forwards App D Documents Which Are Being Made Available in PDR
ML20128D402
Person / Time
Site: Reed College
Issue date: 05/05/1992
From: Grimsley D
NRC OFFICE OF ADMINISTRATION (ADM)
To: Gold R
EUGENE PEACEWORKS
Shared Package
ML20126M891 List:
References
FOIA-92-35, RTR-REGGD-05.059, RTR-REGGD-5.059 NUDOCS 9212070264
Download: ML20128D402 (14)
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[<..%.y,V,pT RESPGNSE TO FREEDOM OF ~~FW* t '6P>a"at INFORMATC ACT (FOlA) REQUEST Eit

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- o oc i i Nusro m ofRmhY,we~i 5.19R kt uut bit M Richard Gold PAH11.- AGI NCY lti COftOS HI L1 A$t D cH NOT LOCAll D (See ther Anf hoan)

Nu epincy riuords aut>>ect to the twiunt have been kn sted No additennel egern y tw oede nutunI to the request have laen km atml Heowested ettoeds sie svedoble through another pubhc despiteution prog *am See Conunents section, Agetty twords tubint to the request that are klentified in Appetubairsi att already eveilable for pubhc intention trxi wpylng et the

_.NHC Pubhc Dot ument floom. Pl?o L Street, N W , Washington, DC, Agerry records substat to the request that are klentifkt in Apperuhalet)__ Q are 1,eing enade available for pubhc inspec tion and copying ,

)( et the NHC Pubhc Document Huom,7170 L htreet, N W., Washington, DC, m a fuktt t uvuter this F OIA nutnbet, T he nonproptictary version of the proposalta) that you agteed to er< ept in a teicphone conversation with a enember of my staf f is now being medt avadabic for pubhc inspm tion and copying at the NHC Pubhc Docunient itoom,2170 L Street, N.W., Wethington, oC,in a fokter undet this f OI A number, Agerty #words tut.im t to the requent that see identified in Appendialn) rney be mesh tal and topimf at the NHC Loca8 Pubhc Docurmt Hoorn identif,ed in the Cuie tnentt 6etlion.

I rw hismi is uifutmation on how you niay obtam su eu to and the haripUne topyhig reords located at the Nf tC Public Document hoom,7170 4. 6treet, i N W , Wasyr_gton, DC.  ;

)( Agenc y eM' orris subjnt to the request are entkened.

flecordt sulynt to the requnt have bNm refetted to another f ederal agmcybet) fut revis-w and thetti iMponte to you-l'oes You ndi be billed by the NHC for fees totahng $ ,_ _ _ _ _

J You will tm eive a refund from the NHC m the amount of $

i tn view of NHC'l fewonhe to this trquest, no further artton #6 feririg taken on apprat lettet dated __ . _

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PAlti 11. A+ tnt OHMAllON Yv11HHI LD i HOM PuttLIC OthCLO$UltL Certain informet6on in the teuvettent records is being wHhheld from putak dittlosure puttuent to the enempoons describe <t in erst for th testons steitswt in Part II, it, C, and D Any released portion 6 of the docuanents for whkh only part of the recont is being withhekt are t>eing rnaite svollable for pubik in.necuan .nd cousinon o NHC Pubhc Document Huom, NO L $9eet, N W., Washinen, DC in a fold t undet this f OIA number, COMMl Niti i

The NRC is continuing to review records subject to your f 01 A reauest. We vill ntify you upon completion of the review, 9212070264 92050D PDR FDIA

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Ret 'FOIA-92 APPENDIX D DOCUMENTS BEING PLACED IN THC PDR NUMBER DATE DESCRIPTIDM

1. 07/92/68 Document from Skovholt concerning The Reed Institute (13 pages)
2. 07/28/81 Letter from Tedesco to Church (2 pages)
3. 12/05/91 Letter from Pollock to Michaels (11 pages)
4. 03/17/92 Letter from Pollock to Martin (19 pages)
5. 03/31/92 Letter from Terdal to Quells (10 pages)

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( 1. This lleense applies to the TRICA Hark 1 type nuclear reactor '

(herein "the reactov'), owned by Road Col 4ege and located on its campus in Portland, Oregon, and which is described in the application for license dated April 15, 1967, and sgplements tiereto dated July 5 and August 22, 1967, and March 13 and April 26,1968 (herein referred to as "the application"), and authorized for construction by Construction Permit No. CPRR-101.

2. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Reed College A. Pursuant to Section 104 e of the Act and Title 10, Chapter 1, Part 50, " Licensing of Production and Utilization CFR[lities",

Fac to possess, use and operate the reactor as a utilization facility in accardance with the procedures and ,

limitations described in the application and in this license; B. Pursuant to the Act and Title 10, Chapter 1, CFR, Part 70, "Special Nuclear Material," to receive, possess and use up to 2500 grams of contained uranium-235 and a 1-curie plutonium-beryllium neutron source, all for use in connection with operation of the reactor; and C. Pursuant to- the Act and Title 10, Chapter 1, CFR, Part 30,

" Rules of General Applicability to Licensing of Byproduct to receive, possess and use a 1.Mocurie sealed Material",

americium- beryllium neutron source for reactor starrup;l and as to possess, but not to separate, such byproduct materia may be produced by operation of the reactor.

3. The license shall be deemed to contain and be subject to the conditions specified in Parc 20, Section 30.34 of Part 30, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70 of the Commission's regulations; is subject to all applicable provisions of the Act and rules, regulations and orders of the Commission now or hereafter in effect; tad is subject to the additional conditions specified or incorporated below:

A. Maximum _ Power Levd The licensee may operate the reactor at steady-state power levels up to a maximum of 250 kilowatts (thermal) .

3 B. Technical Specifications The Technical Specifications :Ontained in Appendix A to this license issued July 2,1968, and Change No.1 issued July 28, incorporated 1969, and Change No. 2 appended hereto, in this license as the Technical Specifications. are hereby(I lst sentence in 3-5 amended 10-3-72) The licensee a sa 1 operate The reactor in accordance with these Technical Specifications.

No changes shall be made in the Technical Specifications unless authorized by the Comission as provided in Section 50.59 of 10 CFR Part 50.

C. Records (This entire section deleted as per amendment _of 10-3-72.

See Section R of the Technical Specifications.)

D. Reports In addition to reports otherwise required by applicable regulations:

- (1) The licensee shall inform the Commission of any incident or condition relating to the operatiod of the reactor which prevented or could have prevented a nuclear system from performing its safety function as described in the Technical Specifications or in the safen analysis report.

Rood College shall promptly For each such occurrence,legraph notify y telephone or te the Director of the appropr ate Atomic Energy Commission Regional Compliance Office submitlisted withininten Ap(pendix D of 10)-days a 10 CFRinPart report 20 and writing shall te the Director, Division of Reactor Licensing (hereinafter,

" Director, DRL"), with a copy to the Regional Compliance Of fice .

(2) As promptly as practicable, but no later than sixty (60) davs after the initial criticality of the facility, need College shall submit a written report to the Director, DRL, cescribing the measured values of the operating conditione or characteristics listed below and evaluating any significant variation of a measured value from the corresponding predicted value:

not (a) Maximum excess reactivity of the facility including the worth of control rods or ot $er control devices such as burnable poison strips I or soluble poison, or any experiments; (b) Total control rod reactivity worth; ,

(c) Minimum shutdown margin both at room and operating i

temperatures;

i 4-(d) I-taximum worth of the single control rod of highest reactivity value; and (e) llaximum total and individual reactivity worth of any fixed er movable experiments inserted in the facility.

(3) The licensee shall report (> the Director, DRL, in writing within thirty (30) days of its occurrence any l substantial variance disclosed by operation of the reactor from performance specifications contained in the safety analysis report or in the Technical Specifications. -

(4) The licensee shall report to the Director, DPJ,, in writing within thirty (30) days of its occurrence, any significant change in the trantinnt or accident analysis, as described in the safety analysis report.

4. This license is effective as of the date of issuance and shall expire at midnight, October 3, 2007.

FOR THE ATOMIC ENERGY C0ifiISSION Donald J. Skovholt Assistant Director for Reactor Operations Division of Reactor Licensing Date of Issuance: July 2, 1960.

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- Revised edition dated March 6,1974 to include Change No.1 issued I July 28, 1969, Change No. 2 issued October 3,1972, Change No. 3 issued August 22, 1973, and Change No. 4 issued January 17, 1974.

TECHNICAL SPECIFICATIONS FOR THE REED COLLEGE TRIGA MARK I REACTOR DATE: July 2, 1968 The dimensions, measurements', and other numerical values given in these specifications may differ from measured values owing to normal construction and manufactuiing tolerances, or normal accuracy of instrumentation.

A. Definitions

1. Shutdown The reactor, with fixed experiments in place, shall be considered to be shut down (not in operation) whenever all of the following conditions have been met: (a) the console key switch 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 r- 0.7% delta k/k cold, without xenon; (c) no work is in s, . progress involving fuel handling or refueling operations or maintenance of its control mechanisms.
2. Steadv-State Mode Steady-state mode shall mean operation of the reactor at power levels not to exceed 250 kilowatts utilizing the scrams in Table I and the interlocks in Table II. However, for the purpose of testing the 110% full power safety circuits, an exception shall be made to allow the reactor to be operated at power levels not to exceed 287.5 kilowatts during the testing period. .
3. Operable A sys tem or component shall be considered operable when it is capable of performing its intended functions in its normal manner.
4. Experimen t Experiment shall mean:

(a) Any apparatus, device, or material installed in the core or experimental facilities (except for underwater lights, fuel element storage racks and the like) which g, is not a normal part of these facilities.

(b) Any operation designed to measure reactor parameters or characteristics.

Technical Specifications- Page-2

. (--

5. Experimental Facilities Experimental facilities ~shall mean rotary specimeo rack, j vertical tubes,- pneumatic tranafer systems, central-thimble, and- in-pool irradiation- facilities.
6. Reactor Safetv circuits-

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Reactor safety circuits- shall mean those. circuits,--

including their asaocisted input eircuits, which are-designed to initiate a reactor scram.

B.3g The minimum distance from the center of the reactor pool to the boundary of_the exclusion area shall be 250 feet. C. Reactor Buildina

1. The reactor shall be housed in a closed room designed-to restrict-leakage. . The minime free volume in the -

p reactor room shall be 12,000 cubic feec.-

2. All air or other gas exhausted from the reactor room and C
  -i                    from associated experimental- facilities during the reactor operation shall be-released to the environment at a minimum of 12 feet above ground level.

D. Reactor Pool and Bridae

1. The reactor core shall be cooled by natural- convective:

water. flow. Corrective action- shall be taken if -during reactor operation the pool water -isiless thanul6 feet-above the tcp grid place. The bulk pool temperature-shall be monitored while- the reactor is in operation and-the reactor - shall be shut down if - the1 temperature exceeds 

                                                                      ~

120*F.

2. The pool water shall be sampled for conductivity at'least weekly. Conductivity averaged over a month shall not exceed 2 micrombos per centimeter.

Reactor Core-E. 

                  -1. The core shall be an assembly: of TRIGA Mark I aluminum clad and/or stainless-steel clad, fuel-moderator elements. arranged
                       -in a close-packed array' except for (1) replacement of single individual-elements with in= core irradiation facilities or-
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control rods ;--(2) . two separated experiment positionsL in the - c D- through E: rings, each occupying a maximum of.-three fuel. 

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element positions.. The reflector (axcluding experiments" and experimental facilities)-~ shall be water or a. combination of graphite'and water.; (As amended by Channe-No. 3)

Technical Specifications Page 3 f

2. The maximum available excess reactiviW above cold, critical, without xenon, shall be 2.25% delta k/h with experiments in place.
3. Each standard fuel element shall be visually inspected at least once every five years. At least 1/5 of all the fuel elements of the core shall be inspected at yearly intervals.

If indication of apparent deterioration or distortion is found, the fuel element (s) shall be removed from the core. (As amended by Changes No. _1 and No. 4)

4. Any fuel element which exhibits a clad break as indicated by a measurable release of fission products shall be located and removed from service before resumption of reactor operation.

F. Control and Safe ty Sys tems

1. The cuatrol elements shall have scram capability and the poison section shall contain borated graphite, B4C powder, or boron and its compounds in solid form as a poison in an aluminum clad.
2. The control elements shall be visually inspected at least

( once every two years. If indication of significant distortion or deterioration is found, the element (s) will be replaced.

3. The minimum shutdown margin (with fixed experiments in place) provided by operable control elements in the cold condition, without xenon, with the most reactive of the operable control elements withdrawn shall be 0.4% delta k/k.
4. The maximum rate of reactivity insertion associated with movement of a standard rod shall be no greater than 0.12% delta k/k sec.
5. The type and minimum number of safety circuits which shall be operable for reactor operation are shown in Table I.
6. The type and mini. mum number of interlocks which shall be operable for reactor operation are shown in Table II. ,
7. The reactor instrumentation channels and safety circuits as listed in Table I shall be verified to be operable at least once each day dhe reactor is operated unless the l operation extends continuously beyond one day, in which case their operability need only be verified prior to i beginning the extended operation.

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8. Following maintenance or modification of the control or safety systeam, it shall be verified that the affected system is operable before reaccor operation is resumed.

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Technical Specifications. Page.4 - m

9. The' tests listed'below shall'be performed at least once '

semi-annually, with the exception that if - the reactor 'is: the tests shall-be performed after . operating tse first shutdown if t occurs more than six months continuously,his ' after the previous teses:

a. Verification that all-control element drop times ere- i less than one second. If drop time is found to be greater than this, the element shall not be considered operable,
b. A functional test of the ventilation system interlo'cks.
10. The linear power level channel shall be calibrated at least annually by thermal pcNer calibration.

G. Radistion Monitorina

1. The radiation levels within the reactor. laboratory shall be monitored by at least one area radiation monitor-during-reactor operation or when work is done on or around the reactor core or experimental facilities. The-m W tor 7 hall have a readout and provide a signal which actuatar at: .
      ~                             evacuation alarm. During short periods of repair to this
  • monitor, reactor operations may continue while .a portable -

gamma-sensitive-ion chamber is utilized as a temporary substitute.

2. A continuous air monitor with readout and audible alarm shall be operable in the reactor room when the reactor is operating.
3. The alarm set points for the above radiation monitoring instrumentation shall be verified at least once a week.

This instrumentation ~shall be calibrated at least once-a year. H. Fuel Storage ! 1. All- fuel elements or fueled devices shall be- rigidly L supported during storage in a safe- geometry (k gf _less I than 0.8 under all conditions of moderation) . . ~ l- 2. Irradiated- fuel elemente and fuel- devices shall be stored-in an array which will-permit sufficient natural convection-( cooling such that the fuel element or fuel device tempera-- L L ture w111 not axceed design values. L 

     ,,..               I. _ Administrative Reouirements
l. The facility shall-be under the direct control of the Facility Director. He shall be responsible to the President ,

of Reed College-for safe operating and maintenance-of the reactor and its associated equipment. His staff shall I i--. x . - , . . .: -_ u. 

 . -               _ - .        -     - _ . _ _      _--          - _    - - - - - -         - _ - . - ~ .

Tecnnical Specifications Page 5 include a reactor supervisor, senior reactor operators, and reactor operators. He (or his appointee) shall review and approve all experiments and experimental procedures prior to their use in the reactor. He shall enforce rules for the protection of personnel against radiation.

2. A Radiation Safety Committee shall review and approve safety standards associated with operation and use of the facilin. It shall report directly to the President of Reed College. Its med)ership shall consist of faculty members and individuals from outside organizations not connected with operation of the reactor facility. It shall meet at least twice yearly to review safety aspects of facility operations. (b st sentence I-2 amended 10-3-72)
3. A Reactor Operations Committee shall be composed of a minimum of four members of the faculty and facility staff, including the reactor supervisor and a qualified health physicist. It shall review facility operations at least twice yearly and shall meet as required to review all questions of safety of operation and scheduling of work of a non-routine nature. (Sentence 2. I-3, amended 10-3-72)
     -                       It shall review all experiments of the following types:

(a) Any experiment involving fissionable material. (b) Any new experiment of a type not previously reviewed by the committee. (c) /.ny experiment involving a change of core configuration or change in equipment associated with the reactor. The Committee shall be responsible for determining whether a proposed change, test or experiment would constitute an unreviewed safety question or a change in technical specifications, as required by 10 CFR 50.59. The Committee shall establish written procedures regarding quorums, sub-committees, review of experiments and operations and others as appropriate. l

4. Any additions, modifications, or maintenance to the core and its associated support structure, the pool structure, and rod drive mechanisms, or 'the reactor safety system, l

shall be made and tested in accordance with the specifi-l cations to which the systems or components were originally designed and fabricated, or to specifications approved by the Reactor Operations Comnittee as suitable and not involvin+ an unreviewed safety question. The reactor shall not be pIaced in operation until the affected system has been verified to be operable. I 

                                 . _ _ . . ~ _ . _ _
           -       Technical Specifications                                                                                                                      Page--6
5. Written instructions shall- be in effect for, but not-- '

limited to: (a) Checkout and calibration of reactor operating instrumentation and control,-control-rod drives, .. and area radiation monitors-and air particulate. monitors. (b) Reactor startup,- routine operation ar.d resctor shutdown. (c) Emergency and abnormal conditions, including evacuations,- reentry and recovery. (d) Fuel loading'or unloading. (e) Control rod removal and replacement. (f) Maintenance operations which may affect reactor safety. J. Experiments

1. Prior to performing any new reactor experiment, the proposed experiment shall be evaluated by a person or persons appointed by the Facility Director to be responsible. for -

reactor safety. He shall consider the experiment in terms (- of its effect on reactor operation and the possibility.-and where-significant, cmsequence consideration of ofchemical its failure, including,hysica1' reactions, p integrity, design life, proper cooling, interaction-with core com-ponents, and reactivity effects He shall determine whether,. in his judgment, the experiment by. virtue of its: nature , and/or design does not constitute a significant threat to the integrity of the core or .co the . safety of personnel. Following a favorable determination and prior to conducting an experiment, he must sign an- authorization form containing the basis for the favorable determination.-

2. No experiment shall- be performed if failure of such exper-ment could lead to a- failure of. a fuel element or of other experiments and these associated failures could resule in a measurable increase in reactivity or a measurable release of radioactivity.
3. No new experiment shall be isirformed until the proposed--

experimental. procedure for that experiment or: type of experiment has been reviewed by the Reactor Operations Connittee. I 4. The following limitations on reactivity shall: apply to all experiments: {, 

                                      ..(a)                                                              individual in-core The. reactivity experiment   shall   worth             of any $1.35.

not exceed y 

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Page 7 Technical Spacifications (b) ne total reactivity worth of in-core exaeriments shall not exceed $2.00. B is includes n e potential reactivity which might result from experimental malfunction, experiment flooding or voiding and removal or insertion of experiments. (c) Experiments having reactivity worths greater than 

                                                                        $1.00 shall be securely located or fastened to prevent inadvertent movement during reactor operations.
5. Experiments containing materials corrosive to reactor components, compounds highly reactive with water, and liquid fissionaile materials shall be doubly encapsulated. 1
6. Explosive materials shall not be irradiated in the reactor. _
7. Experiment materials, except fuel materials, which could off-gas, sublime, voletilize or produce aerosols under (a) normal operating conditions of the experiment or reactor, (b) credible accident gonditions in the reactor, or (c) possible accident conditions in the experiment shall be limited in activity such that if 1007. of the gaseous activity or radioactive aerosols produced escaped to the reactor room or the atmosphere, the airborne con-centration of re.dioactivity averaged over a year would not exceed the limits of Appendix B of 10 CFR Part 20.
8. The following assumptions shall be used in calculations regarding experiments:

(a) If the effluent from an ex?eriment facility exhausts through a holdup tank whici closes automatically on high radiation 1cvel,107, of the gaseous activity or aerosols produced will escape. (b) If the effluent from an experiment facility exhausts through a filter installation designed for greater , than 997, efficiency for 0.3 micron particles,107. of the aerosols produced will escape. (c) For macerials whose boiling point is above 130' F and where vapors formed by boiling this material could escape only through an undisturbed column of water above the core,107, of these vapors will escape.

9. Each fueled experiment shall' be controlled such that the total inventory of iodine isotopes 131 through 135 in the experiment is no greater than 1.5 curies and the maximum strontium-90 inventory is no greater than 5 millicuries.
10. If a capsule fails and releases material which could damage the reactor fuel or structure by corrosion or other means, C- physical inspection shall be performed to determine consequences and need for correctiva action. The results the of the inspection and any corrective action taken shall be reviewed by the Facility Director and d formined e to be satisfactory before operation of the reactor is resumed.

Technical Specifications Page 8 jr-K. Plant Op3 rating Rgcords (New section K, amended 10-3-72) In addition to the requirements of applicable regulations and records and logs of the in no way substituting therefor, following items, as a minimum shall be kept in a manner convenient for review sud shall be retained as indicated:

1. Records to be retained for a period of at least five (5) years:

(a) reactor operations, including unscheduled shutdowns; (b) principal maintenance activities and the reasons therefor; (c) shipments of radioactive materials; (d) equipment and components surveillance activities; (e) experiments performed with the reactor.

2. Records to be retained for the life of the facility:

(a) gaseous and liquid radioactive waste released C,- to the environs; (b) off-site environmental monitoring surveys; (c) facility radiation and contamination surveys; (d) fuel inventories and transfers; (e) updated, corrected and as-built facility drawings.

4 Technical Specifications Page 9 TABLE I 

                           .KGiidM REACTOR SAFETY SYSTEM SCRAMS Originating Channel                   .

Set Point

1. Linear 110% of full power
2. Percent Power 110% of full power
3. Scram button on console Manual TABLE II

( MINIMUM INTERLOCKS Action Prevented

1. Control element withdrawal with less than two neutron induced counts per second on the startup channel.
2. Simultaneous manual withdrawal of two control elements, r- . .

1

EUGENE PEACEWORKS 454 WILLAMETTE ST. EUGENE, OR. 97401 343-8548 JANUARY 16,1992 FREEDOMOFINRDRMADONACTREQUEST TRl[ DOM 0F INFORMATION ACT REQUEST-To: Office Of Chairperson $ JA -f/ #5 Nuclear Regulatory Commission 11555 Rockvillo Pike MY/~22 Rockville, Maryland 20852 Re: FOIA Roquest concerning experimental Nuclear Facility at Rood College Portland, Orogon.

Dear NRC,

I am a voluntoor member of Eupone PoaceWorks a non-profit public organization whose mornbors are interosted and concerned about the spread of Nucle.1 technology and waste in our stato. We are currently organizing a public forum in Eugeno and will continue to organize other public forums on the state of the Nuclear industry in Orogon. One of our members found an interesting recent (Docomber 1991)' article in our local paper, lho Rogistor-Guard, about a Nuclear accident at an Experimental Nuclear Facility at Road College, Portland, Oregon. Could you send copies of any and all documents you have regarding this facility within 10 (ton) days. Would you also send a description (including map with location if available)? Wo will share this information with the public and make oursolvos available for interviews with local news agenclos concerning this issue of critical importance to all Oregonians. We will also donate this material to our local public library. Sincerely, l lb Richard Gold 

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