ML20203G896

Amend 7 to License SNM-1999 for Kerr-McGee Corp,Approving Const of Radioactive Matl Storage Area Design

ML20203G896
Person / Time
Site:	07003073
Issue date:	12/12/1997
From:	Jim Hickey NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20203G872	List: ML20203G867 ML20203G896 ML20203G908 ML20203G957
References
NUDOCS 9712180255
Download: ML20203G896 (5)

Text

[ NIM _MD 'M7/*TN4f'TfTI1/'If4f4'Mh<W I- U.S. NUCLEAR REGULATORY COMMISSION "3

ki4 1 l[ ' SI ATERI Al.S I.lCENSE lf' Punuant to the Atomic Energ) Act of 1954. as amended. the l>cip) Reorgani/ation Act of 1974 (Pubbe I aw 9h4 jl

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lI federal Sepulations. Chapter L Path 30. 3 L 32. 33. 34. 35. 36. 39 Ji), and 70. and in reliance on statemenu and representatiorn heretofore l

i by the hcensee a facense b hereby bsued authoritism the licensee to tetene, acqune, powew and transfer by product, source, and special nuclear Ci l i snateri.d de.ignated below; lo use such material for the pt;;posent and at the piacen) designated below; to deliser er tansfer i4 penons authorired to recene it in accordance w ith .he segulations of the apphcable Parth). Tbn heens til be deemed to wntain the conditions N i l$ *pec6 tied in Setiton IN3 of the Atomic Energ) Att of 1954, as amended. and is subject *~ f.i applicable rulei regulations. and orden of the [l j ; Nucle.ir Regulatory Commiumn now or hereatler m clIect and to any wnduions specified below. l l > P q g

$ Licensee y 3 Kerr-McGee Corporation SNM-1999 h

• j%L 3. Ucense Number  %

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l Kerr-McGee Center l n$1 Oklahoma City, OK 73125 J8iluary '1. 1W7 X@

$ 4. Ihpiration Date y

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[gl Reference No. Amendment No. 7 .g l2 6. II)pmduct. Source, and/or 7. Chemical and/or Ph> sical 8. Masimum Amount that Licensee 'A l2 Special Nuclear Material Form May Powew at Any One Time L Under This License a' lQ a ,

3 A. Uranium Enriched A. Contaminated soil. A. All residual contam-  ;

h in U-235 sludge, sediment. ination which .

trash, building rubble. currently exists at lt i r li'i structures, and any the former Cushing g i other contaminated Refinery Site, ,

5 material.

W i B. Thorium B. Contaminated soil. B. All residual contam- [

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v sludge, sediment.

trash, building rubble, ination which currently exists at structures, and any the former Cushing Il

1. other contaminated material.

Refinery Site.  !

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2 C. Natural Uranium and C. Contaminated soil. C. All residual contam- '

1. ! Depleted Uranium sludge, sediment, ination which L i trash, building rubble, currently exists at '

l- structures, and any the former Cushing >

d other centaminated Refinery Site.  !

W material. (%

4' D. U-235 D. Calibration and' O. No calibration or Q q' reference radioactive reference radioactive @l

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sources containing source containing Ql 97121so255 9712to U-235 U-235. shall exceed W M PDR .ADOCK 07003073 0.1 microcurie per  ! l PD8 W c -

source. p s 9, Authorized Use: Licensed material shall be possessed and used in remediation  !

I activities leading to the decommissioning of the Cushing Site.

1. ! 10. Authorized Place of Use: The existing facilities of Kerr-McGee Corporation.

4' Environmental Operations. Technology and Engineering Division. P.O. Box 89. Cushing.!

M OK 74023. -Location: Two miles North - State Highway 18, 1/2 mile East - Deep Rock '

ef Road.

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M = = = = u.WUUUUUBLW_WJHLEUROUUEUNUELN.WJEUWUWWWWWJELEUELWJULWUWJBLNJEUUURLMELBUILE NRC FORM 374A U.S. NUCLEAR REQULATORY COMMISSION PAGE -- , 2 C7 3 races . g L6:ense Numter SNM-1999

( M ATERIALS LICENSE occi or Reference Numher p SUPPLEMENTARY SHEET 70-3073 .-

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y Amendment No. 7 N

N rju f: 11. -Conditions; f 5

A. Xerr-McGee shall submit by license amendment request, before May 1. 1994, a y h- -Proposed Decommissioning Plan for the Cushing Site meeting the requirements of 10 CFR 70.38(c)(2)(iii). ly g

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$ -B. Kerr-McGee shall submit, by separate licene,e amendment requests or as a k N

i part of the Proposed Decommissioning Plan, detailed descri)tions_of the methods for performing the following activities, prior to )eginning the f

!g activities: ,

k 1. Construction of the Radioactive Material Storage Area (RMSA) in ik Nj accordance with the licensee's letter dated September 2. 1997, is I~

N authorized, however NRC approval of the RMSA liquid effluent monitoring 8 program must be obtained prior to transferring any contaminated material into the RMSA, f

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

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

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C. Both the Initial Radworker-Training and the Annual Radworker Requalification lE Training, described in Item 8 of the application shall include all of the iE topics described in 10 CFR 19.12. lE D. Lapel air samplers will be issued when required by a special work permit or l1E at the direction of the health physics personnel. Lapel air samplers would 4E be issued when there is a reasonable probability that personnel may be I exposed to airborne radioactive material. Lapel air samplers may be issued lEE p at a minimum of one 3er work crew, or a maximum of one per individual. N pI depending on the wort scope and the potential for worker exposure. Downwind H N area air sampling would be performed when work activities are being 4 a performed that would cause the potential of producing airborne q p , radioactivity-, such as earthmoving, g N E y tirine sampling and analysis for uranium isotopes will be performed for all y p workers in a crew. if either area air sample (s) or lapel air sample (s) g g- indicate the following: ig t

) !E g >40 DAC-brs _for a single air sample result. Ig g >100 DAC-hrs /yr accumulated exposure for any one worker. I n

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Fecal analysis will be performed in cases where thorium exposure is -

y suspected and either area air sample (s) or lanel air sample (s) indicate the 4 chronic or acute exposures in excess of 100 DAC-hrs. 'g' N 4 g 4 N E N E_

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SNM-1999 q p M ATERI AI,S 1.ICENSE iweux Reference samter a p SUPPLEMENTARY SHEET 70-3073 -g E

Amendment No. 7 g 9

E. Notwithstanding statements in the a) plication, the limits listed in

" Guidelines for Decontamination of racilities and Equipment Prior to Release l

g for Unrestricted Use or Termination of Licenses for Byproduct. Source, or .g S)ecial Nuclear Material." Policy and Guidance Directive 83-23. August 1987. g gi g' s1all be used as the criteria for the unrestricted release of equipment, y material, and personnel. g F. All radiation protection 3rogram procedures or revisions to these procedures k shall be approved by the Radiation Safety Officer. All revisions to the ih g

radiation safety plan shall be approved by the Radiation Safety Officer, g Site Manager, Project Manager, and Project Leader. g N

G. All work in radioactive materials areas or restricted areas, or work with b Nl I licensed material not. located in radioactive materials or restricted areas, i.%

N shall be in accordance with an approved radiation safety procedure. Work j' Nl i may be performed in the haul road corridor area,* except in fenced iEi Nj 'adioactive materials areas located within the haul road corridor area, iE' sithout implementing a radiation safety procedure.

N H. Wastes dis)osed offsite shall be classified and meet waste form requirements lE N of 10 CFR 3 art 61, meet applicable disposal site license conditions, and I E

N meet Department of Transportation and 10 CFR Part 71 transportation ja E

N requirements, iE' n

h I. The Radiation Safety Officer for this license is Mr. Terence Moore. lE E

,E h J. Licensee is exempt from the physical protection requirements of 10 CFR Part E N 73 and the criticality accident requirements of 10 CFR 70.24 lE b E N K. Except as specifically provided otherwise in this license, the licensee E p shall conduct its program in accordance with statements, representations. ;E p and conditions contained in a letter dated September 25, 1992, as iE y supplemented on December 18. 1992. January 14, 1993. February 23. 1993, tu a August 26. 1993, January 5. 1994. and. February 9. 1996. E l E p!

p FOR THE U.S. NUCLEAR REGULATORY COMMISSION E W E N E  :

y Date: December 12, 1997 By: / k g g n W. N. Hickey, Chief > g

j Low-Level Waste and Decommissioning g a Projects Branch E y Division of Waste Management e p Office of Nuclear Material Safety n d and Safeguards 'g E!

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N El N The haul road corridor area is considered to'be defined as the aggregate of the E R 33 survey units addressed in Kerr-McGee's letter to the NRC dated May 30. 1996. E kwarmwarm a m a siarrm n rm m m m m m m m m m m m m m

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. . 3 3 SNM-1999 70-3073 Amendment No. 7 E. Notwithstanding statements in the application, the limits listed in

" Guidelines for Decontamination of Facilities and Equipment Prior to Re hase for Unrestricted Use or Termination of Licenses for Byproduct. Source.

Saecial Nuclear Material." Policy and Guidance Directive 83-23. August 1987.

51all be used as the criteria for the unrestricted release of Equipment.

material, and personnel .

F. All radiation protection arogram procedures or revisions to these procedures shall be approved by the Radiation Safetv Officer. All revisions to the radiation safety plan shall be approved by the Radiation Safety Officer.

Site Manager. Project Manager, and Project Leader G. All work in radioactive materials creas e restricted areas. or work with licensed material not located in radioactive materials or restricted areas.

shall be in accordar.ce with an approved radiation safety procedure. Work may be performed in the haul road corridor area.* except in fenced radioactive materials areas located within the haul road corridor area, without implementing a radiation safety procedure.

H. Wastes dis)osed offsite shall be classified and meet waste form requirements of 10 CFR 3 art 61, meet applicable disposal site license condit'ons, and meet Department of Transportation and 10 CFR Part 71 transportation requirements.

1. The Radiation Safety Officer for this license is Mr. Terence Moore.

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

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

August 26, 1993. January 5. 1999, and February 9, 1996.

FOR THE NUCLEAR REGULATORY COMMISSION Date: 12/12/97 By:

John W. N. Hickey. Chief Low-level Waste and Decommissioning Projects Branch Division of Waste Management Office of Nuclear Material Safety and Safeguards DISTRIBUTION: [*w/ or **w/o encl or att]

Central File PUBLIC LLDP r/f NMSS r/f BEid BSpitzberg/RIV PSobel j OFC LLDP m LLDP RJb,v LLD6 LLDV ;t/ GC NAME SM M pd aYd IECarr.on TMvT6ii Jdckey ##

F.fws.ee DATE .y/N/97 # /.2f/97 il/Z4/97 //h597 /d/Q /97 e.2./1/97 The haul road corridor area is considered to be defined as the aggregate of the 33 survey units addressed in Kerr-McGee's letter to the NRC dated May 30, 1996.

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