ML20197C370
| ML20197C370 | |
| Person / Time | |
|---|---|
| Site: | 07003073 |
| Issue date: | 09/03/1998 |
| From: | Jim Hickey NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20197C367 | List: |
| References | |
| NUDOCS 9809110144 | |
| Download: ML20197C370 (6) | |
Text
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f U.S. NUCLEAR REGULATORY COMMISSION ~
M ATERIAl.S I.ICENSE Amenoment No. 8 hl l
N l I Pursuant to the Atomic,linergy Act of 1954, as amended, the I:nergy Reorganization Act of 1974 (Public Law 93-4 M and Title 10. Co i ll l'ederal Regulations, Chapter 1. Parts 30,31,32. 33. 34, 35. 36. 39. 40, and 70, and in reliance on statements and representations heretofore made l,1 by the licensee, a license is hereby issued authorizing the licensee to receis e, acquire, possess. and transfer by product. source, arid special nucleary id material designated below; to use such material for the purpose (s) and at the place (s) designated below; to deiner or transfer such material to @,
h permns authorized to receise it in accordance nith the regulations of the applicable ParttsL Thn license shall be deemed t
% specified in Section 183 of the Atomic linergy Act of 1954. as amended, and is subject to all applicabj 3
$ Nui; lear Regulatory Commission now or herealter in effect and to any conditmns specified below.
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'6 1 9l Licensee B
3-Kerr-McGee Corporation 3. License Number l6 6, 6
SNM-1999 i 9 .
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6i Kerr-McGee Center 4. nxpiration oute January 1. 1997 jg 9 Oklahoma City. OK 73125 6
! '$erN No. 70-3073 3 6. ilyproduct. Source, and/or 7. Chemical and/or Physical 8. Maximum Amount that Licensee g,. Special Nuclea Material Form May Possess at Any One Time f Under This License Q-L d
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$ A. Uranium Enriched A. Contaminated soil, sludge. A. All residual co'.itamina- $
l in U-235 sediment, trash, building tion which currently d j rubble, structures, and any exists at the former Q t other contaminated material. Cushing Refinery Site. !g 9 I 6
5 B. Thorium B. Contaminated soil, sludge. B. All residual contam- 6 5 sediment, trash, building 6 ination which
! rubble, structures, and currently exists at Il,,
E any other contaminated the former Cushing s material. Refinery Site.
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! C. Natural Uranium and C. Contaminated soil, sludge, C. All residual contam- {
? Depleted Uranium sediment, trash, building ination which i l
j rubble. structures, and any other contaminated currently exists at the former Cushing
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p g material. Refinery Site.
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N D. U-235 D. Calibration and reference D. No calibration or lp radioactive sources containing U-235 reference radioactive source containing
}!)y U-235 shall exceed 0.1
,f s microcurie per source. %g B
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g y MATERIALS LICENSE IkxLet or Refer-nce Number lg l SUPPLEMENTARY SHEET 70-3073 y - -
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!g g' Amendment No. 8 I E
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- 9. Authorized Use:
l Licensed material shall be possessed and used in remediation l y activities leading to the decommissioning of the Cushing Site. !g g
N I E
N 10. Authorized Place of Use: The existing facilities of Kerr-McGee Corporation. Safety E E
and Environmental Affairs Division. P.O. Box 89. Cushing, OK 74023. Location: Two E l
N miles North - State Highway 18. 1/2 mile East - Deep Rock Road.
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El g 11. Conditions-
!g N
E R A. Kerr-McGee shall submit by license amendment request, before May 1. 1994, a E 5
Proposed Decommissioning Plan for the Cushing bite meeting the requirements E l
N of 10 CFR 70.38(c)(2)(iii). j 5
g B. Kerr-McGee shall submit, by separate license amendment requests, or as a g N part of the Proposed Decommissioning Plan, detailed descriptions of the N methods for performing the following activities, prior to beginning the kEi E
N activities: E E
N E y 1. DELETED. g N E N 2. DELETED. E N E N 3. Prior to demolishing potentially contaminated structures, provide a E description of the methods to be used.
l l N E l g C. Both the Initial Radworker Training and the Annual Radworker Requalification g M- Training, described in item 8 of the application, shall include all of the E N topics described in 10 CFR 19.12. E N E 1 l D. Lapel air samplers will be issued when required by a special work permit or at the direction of the health physics personnel. Lapel air samplers would lg g
q be issued when there is a reasonable probability that personnel may be E N exposed to airborne radioactive material. Lapel air samplers may be issuec' E N at a minimum of one per work crew (either the maximum exposed individual or E the potentially maximum exposed individual), or a maximum of one per l individual. depending on the work scope and the potential for worker lg y
g exposure. Downwind area air sampling shall be performed when work E N activities would cause the potential of producing airborne radioactivity. E, N such as earthmoving. E' i
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SNM-1999 f !
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g MATERIALS LICENSE IMet or Refen nce Numba l l
g SUPPLEMENTARY SHEET 70-3073 i l
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Urine sampling and analysis for uranium isotopes will be performed for all workers in a crew, if either area air sample (s) or lapel air sample (s) il G
g indicate the following: s N 5 W ,
>40 DAC-hrs for a single air sample result. E f
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>100 DAC-hrs /yr accumulated exposure for any one worker.
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i Fecal analysis will be performed in cases where thorium exposure is W y suspected and either area air sample (s) or lapel air sample (s) indicate the lil1 W chronic or acute exposures in excess of 100 DAC-hrs.
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E. Notwithstanding statements in the application, the limits listed in I l,
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" Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct. Source, or l
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N Special Nuclear Matcrial," Policy and Guidance Directive 83-23, August 1987. '
B shall be used as the criteria for the unrestricted release of equipment, liE j ,
N material, and personnel. lE l N E i y
y F. All radiation protection program procedures or revisions to these procedures j g shall be approved by the Radiation Safety Officer (RS0). All revisions to l the radiation safety plan shall be approved by the RSO. Site Manager, l ll g
N Project Manager, and Program Manager. ,
l W E N
G. All work in radioactive materials areas or restricted areas, or work with 'E l licensed material not located in radioactive materials or restricted areas, h y shall be in accordance with an approved radiation safety procedure. Work j y may be performed in the haul road corridor area.* except in fenced E B radioactive materials areas located within the haul road corridor area, E N without implementing a radiation safety procedure. E' W
El 8
N y H. Wastes disposed offsite shall be classified and meet waste form requirements j g of 10 CFR Part 61, meet applicable disposal site license conditions, and g p' meet Department of Transportation and 10 CFR Part 71 transportation E N requirements. E N E N E N E l The haul road corridor area is considered to be defined as the aggregate of the g 33 survey units addressed in Kerr-McGee's letter to the NRC dated May 30, 1996. g N ( ll 4
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SUPPLEMENTARY SHEET 70-3073 l Amendment No. 8 l;g N
N lEl E
N I. The Radiation Safety Officer for this license is Mr. Terence Moore. E N E ,
E J. Licensee is exempt from the physical protection requirements of 10 CFR E l Part 73 and the criticality accident requirements of 10 CFR 70.24.
N K. Construction and operation of the Radioactive Material Storage Area (RMSA) l l
N in accordance with the licensee's letters, dated September 2. 1997, and l N May 28. 1998, is authorized. i l E
j l l L. The licensee shall maintain liquid effluent releases from both the RiiSA and g g the retention pond to an annual cumulative average less than 20 percent of g g the effluent limits stipulated in Appendix B of 10 CFR Part 20. Liquid E N effluents shall be measured prior to discharge and during discharge using E N gross alpha and isotopic analytical techniques for all effluent samples. E i
N E\
N 5i y M. The licensee is authorized to remediate Acid Sludge Pit 4 in accordance with l g the method and criteria prescribed in the licensee's letters dated lg gl N November 26, 1997. February 5. 1998, and March 3. 1998. ;E W jE N The licensee shall use the unrestricted use criteria listed in " Guidelines I Ei for Decontamination of Facilities and Equipment Prior to Release for l Unrestricted Use or Termination of License for Byproduct. Source or Special if
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y Nuclear Material" for surfaces of buildings and equipment, and the Branch !g '
g Technical Positica. " Disposal or Onsite Storage of Thorium or Uranium Wastes N from Past Operations." for soils. lE E
N jE l
l Specific values are given below--
f M E p Soils: E N E N Depleted uranium 1.3 Bq/gm (35 pCi/gm) (total uranium) W N Enriched uranium 1.1 Bq/gm (30 pCi/gm) (total uranium)
Thorium 0.37 Bq/gm (10 pCi/gm) (total thorium) l l g
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Lwense sumser SNM-1999 p MATERIALS LICENSE N ket or Reference Number lg
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SUPPLEMENTARY SHEET 70-3073 g N
Amendment No. 8 f
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N Equipment and surfaces: lE
- E N 'E 2
y 1.000 dpm alpha /100 cm : average contamination level over 1 m2 or g l smaller area 1.000 dpm beta-gamma /100 2cm : average contamination level over j l j B 1 m2 or smaller area
, l-l p 3.000 dpm alpha /100 cm2 : maximum over 100 cm2
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2 3.000 dpm beta-gamma /100 cm : maximum over 100 cm 2 g
200 dpm alpha /100 cm2 : removable l 2 l
N 200 dpm beta-gamma /100 cm : removable E N E N !
N Exposure rate: lE E
B jn '
ly Soils 2.6 nC/kg/hr (10 uR/hr) average above background at 1 meter j
y B E y Equipment and buildings: E N E N 1.3 nC/kg/hr (5uR/hr) E E
above background at 1 meter l
N E y N. Except as specifically provided otherwise in this license, the licensee g g shall conduct its program in accordance with statements, representations. E N and conditions contained in a letter dated September 25,1992, as E B supplemented on December 18. 1992. January 14. 1993. February 23. 1993. E August 26, 1993. January 5. 1994, and February 9. 1996.
l l N E y FOR THE U.S. NUCLEAR REGULATORY COMMISSION g B E N E N E Date: September 3, 1998 By: , / (
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ohn W. N. Hickey! Chief Low-Level Waste and Decommissfoning
\ E E'
E Projects Branch E Division of Waste Management l Office of Nuclear Material Safety lg g
p and Safeguards E N E ATm~nir= = = = = = = = =L= = = = = = = = =_m = = = = = = = =Ju = = = =-= = = = = = = = = = 5
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