ML20010E864

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Provides Outline of Requirements for Various Options Involved W/Removal of Argonaut-type Reactor from Operation. Alternatives to Continued Operation Include Mothballing, Standby Condition & Dismantling
ML20010E864
Person / Time
Site: 05000124
Issue date: 08/17/1981
From: Tedesco R
Office of Nuclear Reactor Regulation
To: Parkinson T
VIRGINIA POLYTECHNIC INSTITUTE & STATE UNIV., BLACKSB
References
NUDOCS 8109080396
Download: ML20010E864 (2)


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,3 AUG 17 1981 D

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5-D W f.8RC PDR Local PDR Docket No.:

50-124 TERA Q[!$7,

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I Dr. T. F. Parkinson R. Tedesco

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Sb 1 { [D Director, Nuclear Laboratory J. Miller g

9 Virginia Polytechnic Institute J. Stolz J!

and State University P. Erickson y

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Room 108 Robeson L. Tremper s

Blacksburg, Virginia 24061 J. Wilson

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Dear Dr. Parkinson:

Members of your reactor staff have requested that we furnish you with an outline of what the requirements would be for the various options involved with removing your Argonaut-type reactor from operation. Three alternatives to continued operation are possible: mothballing; standby condition; and dismantling. A brief discussion of the requirements associated with each option is presented below.

Mothballing Regulatory Guide 1.86 (Enclosure 1). describes our requirements for each of the decommissioning alternatives.

In' the mothballing alternative (possession-only license), the fuel may be left on-site for a period of time under the following conditions:

1) The fuel is removed from the reactor vessel and placed in safe secure storage with technical specifications for monitoring, access control, security and maintenance of storage facility.
2) The licensee provides plans for eventual disposition of fuel, including the use of licensed senior reactor operators for ha.7dling of fuel at the end of the on-site storage interval.

For all alternatives involving a possession-only license, the licensee must provide plans for eventual removal of residual radioactivity at the facility or plans for obtaining an operating license. Radiation levels acceptable for release of a reactor facility to unrestricted access are specified in the Enclosure No. 2.

An application for a re-issuance of an operating license would require:

1) sufficient testing of reactor equipment to assure that it would perform reliably and safely;
2) an adequate staff of licensed senior reactor operators and reactor operators; i
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Dr. T. F. Parkinson AUG 171981

3) qualified health physics personnel adequate for reactor operations;
4) upgrading of reactor systems to meet any new itRC requirements in effect at the time of application for operating license;
5) a comprehensive safety and environmental analysis of proposed reactor operation; Standby Condition Standby operations in which the operating license would continue, but reactor operations would be halted, would require that all maintenance and monitoring continue at the facility as required by the technical specifications. Any changes would require detailed analyses of why deletion of a particular maintenance or monitoring activity would not affect future safe operation of the reactor or the safety of the standby status of the reactor.

Information relative to the present request for renewal of operating license would have to be provided as requested by the flRC.

Any change in the technical specifications (TS) to allow a reduction in staff level during standby status would have to be justified by an analysis submitted with proposed changes to the TS.

Dismaritl ing A dismantling plan would need to be submitted to the NRC that demonstrates how all fuel, radioactive sources and residual radioactivity will be removed from the facility. The dismantling plan for the R-3 reactor at North Carolina State University, Raleigh is provided for your information (Enclosure 3).

It should be noted, however, that the criteria of Enclosure 2 was a requirement for that dismantling also. The licensee must also provide environmental information sufficient for us to write an Environmental Impact Appraisal on the proposed dismantling. Our authorization to dismantle the NC State R-3 reactor including our Environmental Impact Appraisal is provided for your information (Enclosure 4).

If you have any questions on the above alternatives, please feel free to call Mr. Pete Erickson (301) 492-9564.

Sincerely, m1GIUMIC#b M %*'lM'

[cr Robert L. Tedesco, Assistant Director for Licensing Division of Licensing Enclos c :_AL itated

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Decket No. 50-111 Dr. Joab L. Thomas, Chencellor North Carolina State University Box 5536 Raleigh,.1 orth Carolina 276 0 Cear Dr. Thomas:

By letters dated June 5,1950 and February 19, 1931 you requested authori:ati:n to dismantle your 10KW training and research reacter l

and terminate License No. R-63.

As discussed nith your staff, we have deterrined that you snould rev:se ycur criteria for release of the reactor facility to un-res trictec access.

The enclosure provides such criteria that wculd be accep;a:le for your R-3 reactor.

T erefore, f:r us ;c prcceed with authcrization for dis: antiine the R-3 rea:::r you sh:uld revise jour dis. an: ling plan in accordance i th the 3r.c :s ure.

A letter resp:nse -:uld :e satisf actory.

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Radiation Levels for Release Of Reac ce Facility to Unrastricted Access s

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RADIATION LEVELS FOR RELEASE OF P.EACTOR j

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l FACILITY TO UNRE3TRICTED ACCESS Surface Contamination Surfaces' must be decentaminated to levels consisten:.sith Table 1 of Reg. Guide 1.86.

Radicactive Material Other Than Surface Centaminatien (Co 50. Eu 152 Cs 137)

.Co 50, Eu 152 and Cs 137 that may exts: in concrete, cc xnents, structures, and soil must be removed su:h that :he raciatien levalI f :m these isetcpes is less than 5.:R/hr above natura'. background l as measured at one ceter fr:m surface.

General Site survey precedures ac:ep:able to cne NRC must be used F-I) Radiation from naturally occurring radioisotcpes as measured.at a comparable uncontaminated structure or exterior soil surface.

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June 1, 1981 Docket No. 50-111 Dr. Joab L. Thomas, Chancellor North Carolina State Univenity Box 5636 Raleigh, North Carolina 27650

Dear Dr. Thomas:

Tne Connission has issued the enclose.d Order that authorizes you to dismantle the North Carol:na State Univenity Training and Research Reactor in accordance with your application dated June 5,1980, as revised by letters dated February 19 and March 27, 1981. Tne dis-mantling plan replaces the Technical Specifications in their entirety.

Tne related Safety Evaluation, Environmental Impact Appraisal, and Negative-Ceclaration are also enclosed.

A copy of ne Order and Negative Declaration are being filed with the Office of the Federal Register for publication.

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John F. Stol:, Chief Ikerating Reacters Branch #4 Division of Licensing Enclos ures :

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Order Autnori:ing Dismantling 2.

Safety Evaluation 3.

Environmental Impact Appraisal 4

Negative Declaration cc w/encicsures: See next page 6

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_ DOCKET NO. 50-111 L

ORDER AUTHORIZIM CIS".'NTLING OF FACILITY AND DISPOSITIOri 0? COGCEiii PARTS By applicatien dated June 5,1980, as revised by letters dated February 19 and March 27, 1981, North Carolina State University (de licensee) requested

,authori:ation to dismantle the 10 Kw Research and Training Reactor (the facility), at North Carolina State University, Raleigh, North Carolina,

M to dispose of the component parts, in accordance with the plan submitted as part of the application.

A " Notice :f Proposed Issuance of Orders Author-iiing Dismantling of Facility, Dispositten of Cceponent Farts, and Temination cf Facility License" as published in the Fede"1 :ecister en Acril 3, ;931 (c5 ?. 203:3).

Ne request for a hear.ing er petiti:n fcr leave :: intervene i

-as filec fciicaing n:tice cf the proposed action.

Tne "uclear Regulater/ C.?.issi:n (the C:-issi: } has reviered the a: pit:atien in accordance aith the :revisicns cf the C:cmissicn's rules and regulations are nas fcund that the dismantling anc cis;0 sal of c:c:crent : arts in ac::rtance.sitn the licensee's ciscan:iing pian w:li ':e in 1:::rcance..ith I

the regulations in 10 CR Chapter I, and will not be inimical to the common I

defense and security or to the health and safety of the public.

ine basis for the findings is set forth in the concurrently issued Safety Evaluation by the Office of Nuclear Reactor Regulation.

The Cennission has' prepared an environmental impact appraisal for this action. Based on that appraisal, the Comission has determined that this l

action will not result,in any significant environmental impact and tnat an envimncental impact statement need not be prepared.

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T SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION Supp0RTING ORDER AUTHORIZING OISMANTLING OF FACILITY AND DISP 0SITION OF COMPONENT PARTS NORTH CAROLINA STATE UNIVERSITY,

DOCKET NO. 50-111

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Introduction By application dated June 5,1980, as revised by letters dated February 19 and March 27, 1981, the North Carolina State University at Raleigh (the licensee) equested authori:ation to dismantle the 10 Kw Research and Traini:g Reactor (the facility) and dispose of 1:s component parts in accordance with a proposed dismantling plan.

Discussion This 10 Kw reactor is a grapnite reflected, tank-type reactor which used 18 plate, MTR-tyoe fuel assemblies. The reactor cperated from 1960 to 1973 for a total of 52.5 megawatt hours. All irradiated fuel assemolies have been shipped to the U. S. Decar: ment of Enr.g Savannah River Plant for reprocessing. Th e

'our e aining unirradiated ?sel asse-clies and a remaining neutron source have teen ?cvec to tre it:ensee's PULSTAR reactor facili v for cry storage in accorcanca wi:n Amendment No. 5 to '_icense No R-123' da:ed September 17,1980.

!n additicn to removal of all fuel and radiaticn sources fem the rnctor, all reacter system nave been drained anc are dry.

Evalcation

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University personnel completed radiation measuremens of core conocnents (fuel removed).

In June 1978, the maximum radiation from core components was found to be 61 mR/hr on contact.

In June 1976, radiation measurements were taken at the beam corts nearest the core. The maximum exposure rate was found to be 20 mR/hr.

Swi e tests in th beam ports indicated removable contanination to be less than 120 dpm per 100 cn The activated core components will be disposed of as radioactive material.

Also, the bottom section of the reactor tank and some concrete from the biological shield may have to be disposed of as radioactive material because of activation.

All disnantling work will be supervised by the licensee's Nuclear Reactor Pro-gram. Qualified health physics personnel from the adjacent PULSTAR reactor facility will be responsib_le for health, physics control of dismarltling _ opera-tions. The low levels of radiation involved corroined with good balth physics practices will assure that exposures to personnel are as low as reasonably achievable and well within 10 CFR Part 20 requirements.

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ENVIRONMENTAL IMPACT APPRAISAL SUPPORTING ORDER AUTHORIZIM DISPANTLING OF FACILITY AND DISPOSITION OF COMPO*iENT PARTS NORTH CAROL INA STATE UNIVERSITY DOCXET NO. 50-111

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Introduction By letter dated June 5,1980, as revised by letters dated Februarv 19 and

. March 27,1981, the North Carolina State University (the licensee) applied for authord:ation to dismantle the 10 Kw Research and Training Reactor (the facility), _, pose of its component carts, and teminate the facility license.

This evaluation deals with those features and characteristics of reactor dis-mantling and disposition of component parts which may affect the environment.

Discussion of Facility Oismantline The facility is a 10 Kw, graphite reflected, pool-type reactor that used MTR-tyoe fuel elements. The core lattice is a 5x5 array of 21 fuel assemblies and 4 grapnite assemblies. The reactor was operated from 1960 to 1973. Operations were then teminated and License No. R-63 amended to "Pessess-but-not-cperate" s:atus.

All fuel nas been removed from the reactor facility. The irradiated fuel has been. shipped to the Cepartment of Energy (COE) Savannah River Plant for re-crocessing.

The remaining fuel, a unirradiated fuel assemblies, have been transferred to the licensee's Pu"uSTAR reactor facility 'or dry storage. Amend-ment No. 5 dated Septe ::er 17, 1980, to License No. R-120 authorized the trans-fer of the 4 unused fuel assemblies to the PULSTAR reactor.

These 4 assemolies will remain at tne PULSTAR facility until they are shipped to another licensed reactor facility for reuse or to a Federal reprocessing facility.

The facility accumulated a total of 52.5 megawatt hour: of operation.

Calcu-lations by the licensee indicate that the total residual activity in all reactor conconents and structures is less than 0.5 curies.

Environmental Considerations Radioactive material produced during the dismantling process will be sent to a licensed burial ground. The reactor will be dismantled in accordance with the licensee's dismantling plan, as revised. Dismantling will consist primarily of removal of activated reactor intemal components, beam tubes and the pool liner. Only minor decontaminatien effort is expected because of the low level of activity in the cooling water during reactor operation.

If any decontamination licuids are generated they will be handled in accordance with 10 CFR Part 20 requirements and procedures presently in existence at the adjacent PULSTAR reactor. All reactor systems of the 10 Kw reactor are now dry, hence there are no existing liquids for disposal.

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NORTH CAROLINA STATE UNIVE?.SITY RESEARCH AND TRAINING REACTOR DCCKET NO. 50-111 The U. 5. Nuclear Regula:Ory Cornission (the Commissi n) has considered the order authorizing dismantling of facility and dispcsition 'of component parts for the North Carolina State University (the licensee) Resear:h and Training Reac cr operated under Facility License No. R-63.

The order authorizes the. licensee to disassemble the reactor which :perated at ;cwer levels up 5o 10 N (. thermal)., and to dispese of the coeponent parts.

The U, S. Nuclear Regula:Ory Comissien, Office of Nuclear Reac:cr Regu-latien, has prepared an environmental impact aptraisal fer this research rea:ter.

On the basis cf this appraisal, the C: mission has c:ncluded that an envi-:nmental impact statement f r this : articular action is 7:: warranted because there will be 70 significant envir:n:, ental'impR: attributable to ne f

pr:p: sed 2;; ion.

The enyirennental :, pac 1:praisai is available f:r ; :lic ins;ecti:n a: the Cetnissien's Public Document ?. ca a: 1717 H Street, N. ".,"

'lashingt:n, C. C.

I Cated a: Bethesda,.'iaryland, this 1st day of June 1931.

FOR THE NUCLEAR REGULATORY COMMISSION ej u h4L ir il Jof F Stol:, Chief G erating Reactors Bra'.ch !4 Division of Licensing G

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