ML20211D596
| ML20211D596 | |
| Person / Time | |
|---|---|
| Site: | 07003073 |
| Issue date: | 08/23/1999 |
| From: | Camper L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20211D589 | List: |
| References | |
| NUDOCS 9908270096 | |
| Download: ML20211D596 (9) | |
Text
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NRC , FORM 374 U.S. NUCLEAR REGULATORY COMMISSION ___._}_ OF 0_ PAGES j' ~
,i MATERIALS LICENSE O Gi Amendment No. 10 i l wi
[9 Pursuant to the Atomic Energy Act of 1954. as amended, the Energy Reorganuation gl Federal RcFulations. Chapter I. Parts 10. 31. 32. 31,34,35. 36. 39. 40. and 70. and m rehance on stateme g) material
, by thedesignated hcensee. a license is hereby nsued authorizing the hcensee to recenc. acquire O below; to use such material for the purposets) and at the placeo.) designated below; to deliser or transfer such mater
%[ persons authorved to receive it in accordance with the reFulations of the apphcable Part(s). Thn licen specified in Section IM3 of the Atomic Energy Act of 1954, as amended, and is subject to all appbcable rules, regulations. and orders of the "
, l sj Nudcar Regulator) Commiwion now or hereaf ter in elfeet and to en) conditions specified below. i 9 ' '
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Kerr-McGee Corporation i
.?{1- 3 license Nurser SNM-1999
$n .i h 2 3! C d Kerr-McGee Center 4. inpiration oate January 1. 1997 hl M Oklahoma City. OK 73125 2 J 5. Docter or 70-3,073 g Reference No.
9]I 3 6. Byproduct. Source. and/or Ci
- 7. Chemical and/or Ph> sical Form
- 8. Maximum Amount that I.icensee 2 May Possess at Any One Time Q Under This 1.icense 2l 9 g$ l h A. Uranium Enriched A. Contaminated soil, sludge. A. All residual contamina-
%j in U-235 sediment, trash, building tion which currently %y l h rubble, structures, and any exists at the former 6l
$l other contaminated material. Cushing Refinery Site.
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2 E B. Thorium B. Contaminated soil, sludge. B. All residual contam- 2 M sediment, trash. building ination which j k
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rubble, structures, and currently exists at jl 5 any other contaminated the former Cushing 5l material.
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Refinery Site. g
- a. i E C. Natural Uranium and C. Contaminated soil. sludge. C. All residual contam- y
$ Depleted Uranium sediment, trash, building ination which
$ 3 rubble. structures, and currently exists at l any other contaminated the former Cushing Q material. Refinery Site.
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kp 9 D. Calibration and reference D. No calibration or 5 g
slD.U-235 radioactive sources reference radioactive jal containing U-235 source containing l l
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U-235. shall exceed 0.1 microcurie per source.
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SNM-1999 l W MATERIALS LICENSE t>.act or Reference Nurnber gl W SUPPLEMENTARY SHEET 70-3073 El W '
E N Amendment No. 10 g W s !
E p 9. Authorized Use: Licensed material shall be possessed and used in remediation h g
R. activities leading to the decommissioning of the Cushing Site. E
$ E l 10. Authorized Place of Use: The existing facilities, as defined in Figure 1 of an Ef November 6. 1998, letter, of Kerr-McGee Corporation. Safety and Environmental Affairs y
g Division, P.O. Box 89 Cushing. OK 74023. Location: Two miles North - State Highway gj f '
N 18, 1/2 mile East - Deep Rock Road. l W I I
5 11. Conditions: l 9
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A. DELETED.
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B B. DELETED. !!
N !l la 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 j topics described in 10 CFR 19.12. !l' i
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3 D. Lapel air samplers will be issued when required by a special work permit or !
l 3 at the direction of the health physics personnel. Lapel air samplers would '
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j l be issued when there is a reasonable probability that personnel may be exposed to airborne radioactive material. Lapel air samplers may be issued f y
at a minimum of one per work crew (either the maximum exposed individual or 3 the potentially maximum exposed individual). or a maximum of one per hq 3; individual. depending on the work scope and the potential for worker lil exposure. Downwind area air sampling shall be performed when work lSj3j activities would cause the potential of producing airborne radioactivity. lf H
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such as earthmoving.
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\$l Urine sampling and analysis for uranium isotopes will be performed for all H sl!
3 fj workers in a crew, if either area air sample (s) or lapel air sample (s) indicate the following.
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>40 DAC-hrs for a single air sample result, h{l y >100 DAC-hrs /yr accumulated exposure for any one worker.
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3 Fecal analysis will be performed in cases where thorium exposure is pj l suspected and either area air sample (s) or lapel air sample (s) indicate the y W chronic or acute exposures in excess of 100 DAC-hrs.
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SNM-1999 El b
EI l MATERIALS LICENSE Docket or Reference Nun ll l SUPPLEMENTARY SHEET 4g!
I Amendment No. 10 EI I
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E I E. Notwithstanding statements in the application, the limits listed in E E
" Guidelines for Decontamination of Facilities and Equipment Prior to Release El l for Unrestricted Use or Termination of Licenses for Byproduct. Source, or g Special Nuclear Material." Policy and Guidance Directive 83-23. August 1987 l W shall be used as the criteria for the unrestricted release of equipment, gll g
N material, and personnel. E E
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All radiation protection program procedures or revisions to these procedures shall be approved by the Radiation Safety Officer (RS0). All revisions to I
1 g the Radiation Safety Plan (RSP) shall be approved by the RSO Site Manager. Ill W Project Manager, and Program Manager. Il R
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$ G. All work in radioactive materials areas or restricted areas, or work with l licensed material not located in radioactive materials or restricted areas, jlj g shall be in accordance with an approved radiation safety procedure. Il M
R H. Wastes disposed offsite shall be classified and meet waste form requirements N of 10 CFR Part 61, meet applicable disposal site license conditions, and lll lg meet Department of Transportation and 10 CFR Part 71 transportation requirements.
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The RSO for this license is Mr Terence Moore.
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B J. Licensee is exempt from the physical protection requirements of 10 CFR 5
Part 73 and the criticality accident requirements of 10 CFR 70.24.
k ly K. Construction and operation of the Radioactive Material Storage Area (RMSA) (lEl in accordance with the licensee's letters, dated September 2. 1997, and h
R M May 28. 1998, is authorized. b d 2
$ L. The licensee shall maintain liquid effluent releases from both the RMSA and l 9
9 the retention pond to an annual cumulative average less than 20 percent of i g! the effluent limits stipulated in Appendix B of 10 CFR Part 20. Liquid Ill d effluents shall be measured prior to discharge and during discharge using Il N
gross alpha and isotopic analytical techniques for all effluent samples.
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SNM-1999 gl g MATERIALS LICENSE IAx tet or Reference Number gf SUPPLEMENTARY SHEET 70-3073 El N l Amendment No. 10 gi l I El I El' l M. The licensee is authorized to remediate Acid Sludge Pit 4 in accordance with g I the methods and criteria prescribed in the licensee's letters dated E
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8 November 26. 1997. February 5.1998. March 3,1998. June 15.1999, and N l July 29, 1999.
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f p The licensee shall use the unrestricted use criteria listed in " Guidelines El' y,
$ for Decontamination of Facilities and Equipment Prior to Release for El N
Unrestricted Use or Termination of License for Byproduct. Source or Special , l l Nuclear Material" for surfaces of buildings and equipment, and the l y October 23, 1981. Branch Technical Position. " Disposal or Onsite Storage of l l
g Thorium or Uranium Wastes from Past Operations." for soils. l Rl l N Specific values are given below-- E!
W gl Soils: Depleted uranium ly 1.3 Bq/gm (35 pCi/gm) (total uranium) g Enriched uranium Thorium 1.1 Bq/gm (30 pCi/gm) (total uranium) 0.37 Bq/gm (10 pCi/gm) (total thorium) f,1 l W !
l B Equipment 1.000 dpm alpha /100 cm , average li 2
N and Building surfaces: contamination level over 1 m2 or 5 $
smaller area 5 ly 1.000 dpm beta-gamma /100 cm2 : average contamination level over l
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g 1 m2 or smaller area Ill B 3.000 dpm alpha /100 cm2 ; maximum over 100 cm2 ll I l
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5l 3.000 dpm beta-gamma /100 cm 2: maximum El
! over 100 cm2 l g 200 dpm alpha /100 cm2 . removable l 2
B 200 dpm beta-gamma /100 cm ; removable l W
Il Exposure rate: Soils 2.6 nC/kg/hr (10 uR/hr) average above ll background at 1 meter (m) p! Buildings 1.3 nC/kg/hr (SuR/hr) above background !
B at 1 m !ll 5
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ly Equipment 0.05 uC/kg/hr (0.2 mR/hr) at 1 cm {j for beta radiation Il g 0.26 uC/kg/hr (1.0 mR/hr) at 1 cm t for gamma radiation Wl
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SNM-1999 g{I g
b MATERIALS LICENSE Dtaket tw Reference Numter l SUPPLEMENTARY SHEET 70-3073 'l l b i l Amendment No. 10 g!
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N g N. The licensee is authorized to remediate the Cushing Refinery Site in g I accordance with methods and criteria prescribed in the licensee's Site g b Decommissioning Plan (SDP), submitted by letter dated August 17, 1998, and E I supplemented by letters dated January 15, 1999. June 4. 1999, and June 18. E I 1999. E' b
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g The licensee shall use the unrestricted use criteria listed in the August El ]
g B. 1987. " Guidelines for Decontamination of Facilities and Equipment Prior to E
$ Release for Unrestricted Use or. Termination of License for Byproduct. i N
Source, or Special Nuclear Material" for surfaces of buildings and fE E I equipment; the February 13. 1997. " Method for Surveying and Averaging g Concentrations of Thorium in Contaminated Subsurface Soil" for subsurface (f g
H contaminated soil in RMA-3. RMA-11. Skull Creek RMA-10. Block 102. Blocks !l N 60 or 72, and potential trench east of RMA-11: and the Branch Technical l Position, the October 23, 1981. " Disposal or Onsite Storage of Thorium or N
Uranium Wastes from Past Operations." for soils. lll l jj N
g Specific values are given below-- !l l
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ll N Soils: Uranium 1.11 Bq/g (30 pCi/g)(total uranium) 5 Thorium 0.37 Be/g (10 pCi/g)(total thorium) ll N
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! Subsurface The licensee shall survey in f
j soil (for the areas accordance with NRC's guidance paper. !l g listed above): " Method for Surveying and Averaging l 2 Concentrations of Thorium In Lll Ml Contaminated Subsurface Soil." as a lE f
gl minimum, but may collect samples on a smaller grid or at more frequent depth
{l il l gl intervals. The subsurface soil Il s concentration limits are the same as Il N the soil concentration for uranium !l 5
and thorium, above. When multiple h l
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radionuclides are present, the sum of the ratios of the concentration of
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l gI each radionuclide to its respective Ill p limit must not exceed 1.
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NRC FORM 374A U.S. NUCLEAR REOULATORY COMMi3SION 6 0 PAGES ' l
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P.t.GE OF twense sumner SNM-1999 g MATERIALS LICENSE hket or Reference Number l l SUPPLEMENTARY SHEET 70-3073 !g!
g l
I Amendment No. 10 f
5 l Equipment and Uranium 5.000 disintegrations per minute g Building surfaces: (dpm)/100 square centimeter (cm2 ) average l g
I contamination level over 1 m2 or smaller g I area I N 15.000 dpm/100 cm 2maximum E l 1.000 dpm/100 cm2 removable El y
a Thorium 1.000 dpm/100 cm 2 average contamination level over 1 m or smaller area 2 f
,l N 3.000 dpm/100 cm 2maximum !gl E
W 200 dpm/100 cm2 removable E N
El i y
l Exposure rate: Soils 2.6 nanocoulombs per kilogram per hour 4
E (nC/kg/hr) [10 microroentgen per hour i!g p (gR/hr)] above background at 1 m Ils N Buildings 1.3 nC/kg/hr (5 R/hr) above background at 1 m !!
Equipment 0.05 uC/kg/hr (0.2 mR/hr) at 1 cm E
for beta radiation ll il l 0.26 uC/kg/hr (1.0 mR/hr) at I cm
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g for gamma radiation N !jl EI N 0. The licensee shall conduct a final status survey and sampling program of the 'E l fg E
site in accordance with the December 1993. NUREG/CR-5849 " Manual for
- Conducting Radiological Surveys in Support of License Termination."
j Radioactivity levels shall not exceed the averaging criteria in NUREG/CR-ll g 5849, except for subsurface contaminated soil in RMA-3 RMA-11. Skull Creek. !'
s RMA-10. Block 102 Blocks 60 or 72, and potential trench east of RMA-11: Il RMA-11 and Disposal Trench areas. Subsurface contaminated soil in these
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gl areas shall not exceed the limit calculated in accordance with the criteria in the February 13, 1997. " Method for Surveying and Averaging Concentrations f g!
l of Thorium In Contaminated Subsurface Soil." Material that exceeds these qEl i
g g averaging criteria shall be removed and shipped off-site to a licensed low-W level waste disposal site. W@l w I E
lg P. The licensee is authorized to make certain changes to the NRC-approved SDP and RSP without NRC's approval, if these changes are consistent with the as-lll 4
l low-as-reasonably-achievable (ALARA) principle and the decommissioning g
l process. All changes shall be approved by the Cushing ALARA Review Committee lg s'
N
- (ARC), subject to the following
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- 1. The licensee may, without prior NRC approval, and subject to the g! requirements specified in Parts 2 and 3 of this condition: f
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El l a. Make changes in the facility or process, as presented in the g NRC-approved SDP and RSP: and l g
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b b. Conduct tests or experiments not present in the NRC-approved SDP El 1
or applicable license conditions. E; b
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- 2. The licensee shall not be required to file an application for an g
y ll amendment to the license when the following conditions are satisfied: !l; R
!l 5 a. The change, test, or experiment does not conflict with EI N
requirements specifically stated in the license (excluding those !
l aspects addressed in Part 1 of this condition), or impair the jl!
y licensee's ability to meet all applicable NRC regulations: ll W
N b. There is no degradation in safety or environmental commitments I
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addressed in the NRC-approved SDP or RSP. or have a significant adverse effect on the quality of the work, the remediation fll lg objectives, or health and safety; and jj il R-N b. The change, test, or experiment is consistent with the
'l N conclusions of actions analyzed in the Environmental Assessment
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'l M (EA) dated August 1999.
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$ 3. The licensee's determination shall be made by the ARC. The ARC shall l jl consist of a minimum of three individuals employed by the licensee, of gl whom one shall be designated as the ARC chairman. One member of the l 3
M ARC shall represent corporate (Oklahoma City office) management and shall be responsible for approval of managerial and financial changes.
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f One member shall represent site operations and shall have responsibility for implementing any changes. One member shall be the fl j
j site RSO or equivalent, with responsibility for assuring that changes ll l
5 conform to radiation safety requirements. Additional members may be l B
included in the ARC. as appropriate, to address technical aspects. l 5
such as health physics. ground-water hydrology, surface-water l f
gl hydrology, specific earth sciences, and other technical disciplines.
Temporary or permanent members. Other than three individuals who are l ll M! ll m'! !l N
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U.S. NUCLEAR REZULATORY COMMISSION PAGE OF PAGES !
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SNM-1999 ll
.i N MATERIALS LICENSE !!
p SUPPLEMENTARY SHEET IMM or RdereAt NuNr-3073 !l l Amendment No. 10 m !!I 3
required to be Kerr-McGee Corporation employees, may be consultants. k!
The licensee's determinations as to whether the above conditions are .!!
g met will be made by the ARC. The licensee shall provide in an annual j 3 report to NRC describing all such determinations made pursuant to the y condition, including a summary of the safety and environmental 4 evaluations of each such action. As part of this annual report, the jl licensee shall include any SDP and RSP pages revised pursuant to this condition. The records of each determination shall be retained until }l g
!l 3 license termination. The retained records shall include written l l
5 safety and environmental evaluations, made by the ACR. that provide l 3: the basis for determining whether the above conditions are met. l 3 [l@
fj! Q. During the remediation operations, liquid and airborne effluents will be sampled and analyzed to ensure that releases meet the requirements of 10 CFR I
!l 3 Part 20. Appendix B. !l 3 !!
3 R. Except as specifically provided otherwise in this license the licensee shall L j 3
conduct its program in accordance with statements representations. and ;lll '
! conditions contained in a letter dated September 25. 1992, as supplemented on gj jI December 18, 1992, and August 26, 1993. gl 3 2l sf w
FOR THE U.S. NUCLEAR REGULATORY COMMISSION l5l o
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Date: 38k y:
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Camper.Chfe'f g sj scom,issioning Branch 3 3
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Office of Nuclear Material Safety and Safeguards
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