ML20008E601

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Order Requiring Mod of License SNM-791.Licensee Must Develop & Submit Radiological Contingency Plan & Application for License Amend to Incorporate Plan as Condition of License within 240 Days
ML20008E601
Person / Time
Site: 07000854
Issue date: 02/11/1981
From: Cunningham R
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
ISOTOPIC ANALYSIS, INC.
Shared Package
ML20008E600 List:
References
NUDOCS 8103090261
Download: ML20008E601 (6)


Text

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UNITED STATES OF AMERICA NUCLEAR REGULATORY CCMMISSION In the Matter of

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Docket No.70-854

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Special Nuclear Material Isotopic Analysis, Inc.

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License No. SNM-791 P.O. Box 35622

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Tulsa, Oklahoma 74135

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ORDER TO MODIFY EICENSE I

Isotopic Analysis, Incorporated of Tulsa, Oklahoma ("the licensee") is tne holder of Special Nuclear Material License No. SNM-791 issued by the Nuclear Regulatory Commission ("the Commission").

The license includes authori-

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ation for the possession ant' use of 200 gms of '~~U, 3 gms of Pu and 10 gms 23"'U in unsealed form. The license is currently active and is due to be

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of renewed on Novemcer 30, 1931.

II Before issuance of a license to operate, staff review of the application determined that the licensee can operate the facility in a safe manner.

Nonetheless, based on the lessons learned from tne accident at Three Mile Island and new perspectives on emergency preparedness and planning, tne Commission has reevaluated the emergency preparecness requirements for its fuel cycle and materials licensees. The Commission has decided tnat significant imcrovements neec to be mace promptly to ensure that acequate onsite emergency response actions will be taken by licensees with major coerations in cases I

where, even though unlikely, potentially serious radiation accicenta could occur. The operations licensed to be carried out pursuant to Scecial Nuclear I

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Material License No. SNM-791 a; ear to fall in :nis category anc recuire tne deve1coment of a ccmcrenensive ensite raciological contingency plan.

5:ecifically, consicerations are neeced to ensure (1) tnat One lant c:ntains acequate engineered safety features and is etnerwise cesigned to limit releases of racicactive matcrials and raciation ex:csures in ne event of an accicent, (2)

nat a ca:acility exists for measuring and assessing tne significance of accidental reiseses of radicactive meterials, (3) :nat a recriate emergency equipment and planning are proviced ensite :: protect workers against radiation ha: arcs that signt be encountered folicwing an accicent, (a) tnat notif cations are mace Orczctly to feceral, state, anc local government agenciet, anc (5) tnat necessary recovery actions are taken in a timely f asnic. :: return :ne plant to a safe c:ncition folicwing an accident.

The information to be cevelccec and docu=ented is cescri:ed in tne enciesec "Stancarc Fermat anc Content for Raciclegical Contingency ?lars for Fuel Cycle

-anc Materials Facilities" (Enclesure 1).

In su= mary, the informatien to be suomitted to NRC for_ review incluces a (1) cescription of plant systems i=:crtant to safety; (2) cnaracterization of classes of crecible emergencies that sign:

cccur; (3) cescri: tion of radiclegical c:ntingency measures for eacn class of emergency; (a) cesignation of autnerities anc rescensibilities of key incividuals anc greu:s em:10yed by the licensee; anc (5) a descri tien of ecui: ent anc facilities designated for use curing raciatien emergencies. The :lan is to be directed toward mitigating the c:nsequences of raciolcgical emergencies and providing reasonacle assurance tnat a: recriate measures will te taken curing an emergency to assure protection of tne :ublic anc minimi:e acverse enviren-mental i : acts.

In pre:aring the plan, c:nsiceration sncuid be given := a set r

  • 3 of credible accioents ranging from almost everycay occurrences of small conse-quence tnrougn hignly improbacle, but not impossible, accidents such as those resulting from severe natural phenomena, human error, and multiple equipment failures, and sabotage.

III In addition to onsite radiological contingency planning, as discussec in l

Section II above, offsite emergency response planning is also nighly imcortant.

Offsite planning requirements for fuel cycle and materials facilities are being developed separately anc will te considered in a procosed rulemaking to be publisned in the coming months. Witnin the framework of tnat rulemaking, NRC will carry out extensive coordination with state governments and the Feceral Emergency Management Agency (FEMA) concerning apolica:le recuirements.

IV The Commission believes tnat it is prudent and necessary to require the licensee to develop and submit within 240 da/s of the effective date of this Orcer, or before, an onsite radiological contingency plan, as discussed in Section II acove, acplicable to ocerations licensed pursuant to Scecial Nuclear Material License No. SMM-791. Suca a plan can te ceveloced and effectively imolemented acart rom offsite emergency resconse clanning, wnica necessarily involves state anc local government emergency planning actions. The onsite radiological contingency plan is a necessary extension of protective actions taken by tne licensee during normal ocerations. Suca planning is essential to ensure that proper plans are made by the if censee to protect the oublic from accicents that coulc result frem the licensed ocerations. A lesson learned

from the Three Mile Island accicent is that accidents thougn: to ce hignly imorobacle can and will occur, and that procer emergency precarecness is recaired to mitigate radiological consecuences.

The reporting and recorc '<ee:ing : art of :nis onsite raciological contingency plan is subject to clearance sy the General Accounting Office. GA0 review and clearance wi'l not stay the effective date of this Order as regards the require-ment that the licensee ceveloo the plan. Unless advised to the contrary, GA0 clearance will be effective within 45 days from the date of this Orcer.

V Accordingly, pursuant to sections 161b anc 161o of the Atomic Er.ergy Act of 1954, as amended, is70.32(a)(3), 70.32(b)(2), and 70.32(b)(5) of 10 CFR

? art 70, and $2.204 Of 10 CFR ? art 2, IT IS HERE3Y CRDERED THAT within 240 days of the effective date of this Order, the licensee snall submit:

1.

A radiological contingency plan in accordance with Enclosure 1 of th.

Order, " Standard Format anc Content for Raciological Contingency

?lans for Fuel Cycle anc Materials Facilities,* anc an acolication for license amendnent to incor orate suca plan as accroved as a condition of the license; or alternatively, 2.

An acplication for license amencment to reduce the possession limits for radioactive materials below those scecified in Enclosure 2 of this Orcer.

5 VI Tne licensee or any person wncse interest may te affected by this Order may, within 20 days of the cate of the Ordte, recuest a hearing with respect to all or part of the Order. A request for a hearing snail be acdressed to the Secretary of the Commission, U.S.N.R.C., Washington, D.C.

20555.

A cocy of tne hearing recuest shall also be sent to the Executive Legal Director, U.S.N.R.C., Wasnington, D.C.

20555. If a persen other than the licensee requests a hearing, that person shall set forth with particularity the nature of his or her interest and the manner in whien his or her interest may be affected by this Order in accordance with 10 C.:R 32.71a(a)(2) of tne Ccemission's Rules of Practice.

If a hearing is reques* ad by the licensee or a person.no has an interest affected by this Orcer, tne 'camission will issue an order designating the time and place of the hearin.

If no hearing is requested, this Order will beccme effective 20 days from the date of the Order.

If a hearing is requested, this Order will become effective en the date scecified in an order made foilcwing the hearing.

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VII If a hearing is held, the issue to be censidered at the hearing snall be whether the licensee (1) shall sucmit a radiological contingency plan which comolies with Encicsure 1 of tnis Order, " Standard Format and Content for Raciological Contingency Plans for Fuel Cycle and Materials.:acilities," cr (2) if a clan is not sucmitted as recuired in Section V (i) of the Orcer, l

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6 should an acclication for a license amencment to reduce its possession limits for radioactive materials below those specified in Enclosure 2 of this Order be submittec.

FOR THE NUCLEAR REGULATORY CCMMISSICN

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Ricnard E. Cunningna, Director Division of Fuel Cycle and Material Safety Dated at Silver Soring, Maryland this 11 th day of February,1981

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