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 hl M ATERIAl.S I.ICENSE Amenoment No. 8 N
l 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. Coi 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 applicab 3
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$ Nui; lear Regulatory Commission now or herealter in effect and to any conditmns specified below.
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6, 3-Kerr-McGee Corporation
- 3. License Number SNM-1999 6
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9 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 Q
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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
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rubble, structures, and any exists at the former t
other contaminated material.
Cushing Refinery Site.
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B. Thorium B. Contaminated soil, sludge.
B. All residual contam-6 5
sediment, trash, building ination which 6
rubble, structures, and currently exists at Il,,
E any other contaminated the former Cushing Ql s
material.
Refinery Site.
E C. Natural Uranium and C. Contaminated soil, sludge, C. All residual contam-
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Depleted Uranium sediment, trash, building ination which i
l rubble. structures, and currently exists at
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Refinery Site.
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N D. U-235 D. Calibration and reference D. No calibration or l
radioactive sources reference radioactive p
containing U-235 source containing y
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%g U-235 shall exceed 0.1 s
microcurie per source.
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MATERIALS LICENSE IkxLet or Refer-nce Number lg l
SUPPLEMENTARY SHEET 70-3073
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g' Amendment No. 8 I
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9.
Authorized Use:
Licensed material shall be possessed and used in remediation l
y activities leading to the decommissioning of the Cushing Site.
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- 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 miles North - State Highway 18. 1/2 mile East - Deep Rock Road.
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11.
Conditions-
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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 of 10 CFR 70.38(c)(2)(iii).
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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 k
N methods for performing the following activities, prior to beginning the Ei E
activities:
E N
E N
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1.
DELETED.
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E N
2.
DELETED.
E N
E N
3.
Prior to demolishing potentially contaminated structures, provide a E
l description of the methods to be used.
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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
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D.
Lapel air samplers will be issued when required by a special work permit or l
g at the direction of the health physics personnel.
Lapel air samplers would 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
l the potentially maximum exposed individual), or a maximum of one per l
y individual. depending on the work scope and the potential for worker g
g exposure.
Downwind area air sampling shall be performed when work E
N activities would cause the potential of producing airborne radioactivity.
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such as earthmoving.
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g N,R F;ORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE OF PAGES p
u<ense sumb" SNM-1999 f
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g MATERIALS LICENSE IMet or Refen nce Numba g
SUPPLEMENTARY SHEET 70-3073 i
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Amendment No. 8
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Urine sampling and analysis for uranium isotopes will be performed for all il g
workers in a crew, if either area air sample (s) or lapel air sample (s)
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indicate the following:
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>40 DAC-hrs for a single air sample result.
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>100 DAC-hrs /yr accumulated exposure for any one worker.
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ui 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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Notwithstanding statements in the application, the limits listed in Ill
" Guidelines for Decontamination of Facilities and Equipment Prior to Release l
j for Unrestricted Use or Termination of Licenses for Byproduct. Source, or
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Special Nuclear Matcrial," Policy and Guidance Directive 83-23, August 1987.
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shall be used as the criteria for the unrestricted release of equipment, E
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material, and personnel.
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F.
All radiation protection program procedures or revisions to these procedures j
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shall be approved by the Radiation Safety Officer (RS0). All revisions to l
g the radiation safety plan shall be approved by the RSO. Site Manager, l ll N
Project Manager, and Program Manager.
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G.
All work in radioactive materials areas or restricted areas, or work with
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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.
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8 H.
Wastes disposed offsite shall be classified and meet waste form requirements j
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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.
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33 survey units addressed in Kerr-McGee's letter to the NRC dated May The haul road corridor area is considered to be defined as the aggregate of the 30, 1996.
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I RM 374A U.S. NUCLEAR REGULATORY COMMISSION Q
PAGE OF PAGES g p
< g uunse None SNM-1999 E
N N
p MATERIALS LICENSE Docket or Reference Number g
g SUPPLEMENTARY SHEET 70-3073 l;g l
Amendment No. 8 N
lEl N
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.
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N 5i M.
The licensee is authorized to remediate Acid Sludge Pit 4 in accordance with l
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the method and criteria prescribed in the licensee's letters dated gl N
November 26, 1997. February 5. 1998, and March 3. 1998.
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N The licensee shall use the unrestricted use criteria listed in " Guidelines I
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l for Decontamination of Facilities and Equipment Prior to Release for if y
Unrestricted Use or Termination of License for Byproduct. Source or Special
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Nuclear Material" for surfaces of buildings and equipment, and the Branch
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g Technical Positica. " Disposal or Onsite Storage of Thorium or Uranium Wastes lE N
from Past Operations." for soils.
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l Specific values are given below--
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Soils:
E N
E N
Depleted uranium 1.3 Bq/gm (35 pCi/gm) (total uranium)
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Enriched uranium 1.1 Bq/gm (30 pCi/gm) (total uranium) l l
Thorium 0.37 Bq/gm (10 pCi/gm) (total thorium) g E
N N
N E
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Lwense sumser l
SNM-1999 p
MATERIALS LICENSE N ket or Reference Number g
p.
SUPPLEMENTARY SHEET 70-3073 g
f Amendment No.
8 N
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lE N
Equipment and surfaces:
- E N
'E 2
2 y
1.000 dpm alpha /100 cm : average contamination level over 1 m or g
l smaller area l
1.000 dpm beta-gamma /100 cm : average contamination level over j j 2
l-l 2
B 1 m or smaller area p
3.000 dpm alpha /100 cm : maximum over 100 cm
!l 2
2 l
3.000 dpm beta-gamma /100 cm : maximum over 100 cm g
2 2
l 200 dpm alpha /100 cm : removable l
2 N
200 dpm beta-gamma /100 cm : removable E
2 N
E N
lE N
Exposure rate:
E B
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Soils 2.6 nC/kg/hr (10 uR/hr) average above j
y background at 1 meter 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 l
August 26, 1993. January 5. 1994, and February 9. 1996.
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FOR THE U.S. NUCLEAR REGULATORY COMMISSION g
B E
N E
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Date:
September 3, 1998 By:
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p ohn W. N. Hickey! Chief
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Low-Level Waste and Decommissfoning E'
E Projects Branch E
l Division of Waste Management l
g Office of Nuclear Material Safety g
p and Safeguards E
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