ML20135A894

Amend 6 to License SNM-1999 for Kerr Mcgee Corp,Revising License Conditions 11.K,11.F,11.D & 11.C as Listed

ML20135A894
Person / Time
Site:	07003073
Issue date:	02/12/1997
From:	Jim Hickey NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20135A891	List: ML20135A889 ML20135A894 ML20135A896 ML20135A900
References
NUDOCS 9702280013
Download: ML20135A894 (4)

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U.S. NUCLEAO CEGULATORY COnetelSSION PAGE 1 OF 3 DAGES y

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. ., MATERIALS LICBISE  !

l l Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public law 93-438), and Title 10, lg

] Code of Federal Regulations, Chapter I, Parts 30, 31, 32, 33,34, 35, 39,40 and 70, and in reliance on statements and representations heretofor g I

made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, sourc l I

nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below; to deliver or transfer such rnaterial I I

to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This license shall be dee

specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations and orders of the Nuclear l Regulatory Commission now or hereafter in effect and to any conditions specified below.

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I Kerr-McGee Corporation SNM-1999 )

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I 2' Kerr-McGee Center Oklahoma City, OK 73125

4. Expiration.date January 1, 1997 j)n l i S. Docket or

'l 70-3073 'n I Reference No Amendment No. 6 i I 6. Byproduct, murce, and/or I

7. Cherracal and/or physical - 6. Maximum amount that licensee l special nuclear material form i

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,may possess at any one time ll ender this license I  !

i A. Uranium Enriched A. Contaminated soil, I A. All residual contam- i n

I in U-235 sludge, sediment. ination which n i trash, building rubble, currently exists at I I {

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structures, and any the former Cushing jb

,I , other contaminated Refinery Site.

i material-. *' ~ u Jl g

! B. Thorium ~

B. Contaminated soil, '

B.N1residualcontam-I sludge, sediment... cination which i I

I trash, building rubble, ocurrently exists at itI structures, and any < the former Cushing l other contaminated A' Refinery Site. lj i material. ..

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l C. Natural Uranium and C. Contaminated soi,1, C. All residual contam- il I Depleted Uranium sludge, sediment, ination which I I

trash. building rubble, currently exists at E l structures, and any the former Cushing i other contaminated Refinery Site. l i material. ly I

I D. U-235 D. Calibration and D. No calibration or llI

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reference radioactive reference radioactive il.

l l sources containing source containing 88-235 U-235, shall exceed }

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9702280013 970212 i l

PDR ADOCK 07o03073 0 1 microcurie Per 1'1 C PDR source, 1

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9. Authorized Use: Licensed material shall be possessed and used in remediation I l activities leading to the decommissioning of the Cushing Site.

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1 l 10. Authorized Place of Use: The existing facilities of Kerr-McGee Corporation, i l Environmental Operations, Technology and Engineering Division, P.O. Box 89, Cushing, 1 1 OK 74023. Location: Two miles North - State Highway 18, 1/2 mile East - Deep Rock I I

Road. I l

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NR FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 2 OF 3 eAGes g Lbeme Number g u SNM-1999 a

. N MATERIALS LICENSE coan or gere,coce Number g g SUPPLEMENTADY SHEET 70-3073  :

N I g Amendment No. 6 g M E  !

N l l I p I 11. Conditions: g I I g A. Kerr-McGee shall submit by license amendment request before May 1. 1994, a g a Proposed Decommissioning Plan for the Cushing Site meeting the requirements ,

e of 10 CFR 70.38(c)(2)(iii). g i

I e y B. Kerr-McGee shall submit. by separate license amendment requests, or as a y l

g part of the Proposed Decommissioning Plan, detailed' descriptions of the g g methods for performing the following. activities, prior to beginning the g i activities:

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g i N I g 1. Prior to transferfing contaminated material to any of the three y q temporary , storage areas provide an analysis,0f s the ability of the three g g temporary, storage areas to effectively resist erosion f by wind and y l g water, and describe the measurement procedures ~to be used to control y l g the sorting of the contaminated material to be transferred to the g i y temporary storage areas. .

N N g 2. Prior to neutralizing the acidic contaminated sludge in Pit 4. describe g g the methods to be used. ,  ;

l 3. Prior to demolishing potentially contaminated structures, provide a l g description of the methods to be used. ,

Both the Initial Radworker Training and the Annual Radworker Requalification l

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Training, described in Item 8 of the application, shall include all of the y g

y topics described in 10 CFR 19.12. g l E l g D. Lapel air samplers will be issued when required by a special work permit or I g

at the direction of the health physics personnel. Lapel air samplers would I be issued when there is a reasonable probability that personnel may be y

exposed to airborne radioactive material. Lapel air samplers may be issued I y

at a minimum of one 3er work crew, or a maximum of one per individual.

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, E y depending on the wor ( scope and the potential for worker exposure. Downwind I y

area air sampling would be performed when work activities are being I y performed that would cause the potential of producing airborne E radioactivity, such as earthmoving.

Urine sampling and analysis for uranium isotopes will be performed for all I l workers in a crew, if either area air sample (s) or lapel air sample (s) I indicate the following: l h

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>40 DAC-hrs for a single air sample result.

lg >100 DAC-hrs /yr accumulated exposure for any one worker. l I

Fecal analysis will be performed in cases where thorium exposure is l suspected and either area air sample (s) or lapel air sample (s) indicate I

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y chronic or acute exposures in excess of 100 DAC-brs.

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NR FORM 374A U.S. NUCLEAR REGULATORY COMMISSION License Number PAGE 3 or 3 Pacts l g g g SNM-1999 g g

MATERIALS LICENSE Docket or Reference Number g g SUPPLEMENTARY SHEET 70-3073 g N N g Amendment No. 6 g E

4 N N g E. Notwithstanding statements in the a] plication. the limits listed in a p " Guidelines for Decontamination of racilities and Equipment Prior to Release g g for Unrestricted Use or Termination of Licenses for Byproduct. Source, or g g S)ecial Nuclear Material." Policy and Guidance Directive 83-23. August 1987. g g s1all be used as the criteria for the unrestricted release of equipment, y g material, and personnel. p p I y F. All radiation protection 3rogram procedures or revisions to these procedures y y shall be approved by the Radiation Safety Officer. All revisions to the y radiation safety plan shall be approved by the Radiation Safety Officer.

p g y Site Manager. Project Manager. and Project. Leader.

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R g G. All work in radioactiive Inaterials areas or r'stricted e areas, or work with y y

licensed material not located in radioactive materials or restricted areas, y y shall be in accor' dance with an approved radiation safety procedure. Work g g may be performed in the haul road corridor area.* except in fenced g g

radioactive materials areas located within the haul road corridor area, g y without implementing a radiation safety procedure. .

g Wastes disposed offsite shall be classified and meet waste form requirements l l, H.

of 10 CFR Part 61. meet applicable disposal site license conditions, and g g

meet Department of Transportation and 10 CFR Part 71 tr,ansportation g g

requirements. g I. The Radiation Safety Officer for this license is Mr. Terence Moore. l l

J. Licensee is exempt from the physical protection requirements of 10 CFR Part l lg 73 and the criticality accident requirements of 10 CFR 70.24. g N

K. Except as specifically provided otherwise in this license, the licensee l N shall conduct its program in accordance with statements, representations, g I and conditiw, contained in a letter dated September 25, 1992, as N N supplemented on December 18. 1992. January 14, 1993. February 23, 1993.

August 26, 1993. January 5. 1994, and February 9. 1996. l l N N FOR THE U.S. NUCLEAR REGULATORY COMMISSION N

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W Date: February 12, 1997 By:

U N ohn W. N. Hickey. Chief T 8 N Low-Level Waste and Decommitsioning I

W ' Projects Branch I 8 Division of Waste Management 8

N Office of Nuclear Material Safety and Safeguards l l N N

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• The haul road corridor area is considered to be defined as the aggregate of the g g

30. 1996. s 4 .33 survey units addressed in Kerr-McGee's letter to the NRC dated Maymm--m--m=============-===

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Enclosure 2