ML20210N148
| ML20210N148 | |
| Person / Time | |
|---|---|
| Site: | 07003073 |
| Issue date: | 08/05/1999 |
| From: | Brown S NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Lux J KERR-MCGEE CORP. |
| Shared Package | |
| ML20210N155 | List: |
| References | |
| NUDOCS 9908110035 | |
| Download: ML20210N148 (6) | |
Text
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.'k UNITED STATES 1
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NUCLEAR REGULATORY COMMISSION I
C WASHINGTON, D.C. 205!$ 4001 44*****
,o August 5, 1999 l
Mr. Jeff Lux Kerr-McGee Corporation Kerr-McGee Center P.O. Box 25861 Oklahoma City, OK 73125
SUBJECT:
PROPOSED REVISIONS TO THE KERR-McGEE CORPORATION'S CUSHING, OKLAHOMA, REFINERY SITE MATERIALS LICENSE SNM-1999
Dear Mr. Lux:
In response to your letter dated August 17,1998, and supplemented by your letters dated June 4, June 15, and June 18,1999, in which you requested NRC to authorize remediation of the Cushing, Oklahoma, Refinery Site (Cushing) by license amendment, we are completing our review of your request and are considering revising Materials License SNM-1999 as follows:
1.
The requirements of License Condition 11.A. will be deleted.
I1.A. DELETED 2.
The requirements of License Condition 11.B. will be deleted.
h k(h hh I1.B. DELETED 3.
License Condition 11.M. will be revised to reflect the potential for disposal of Acid Pit 4 material, that is less than Option 1, in a new onsite industrial waste disposal cell by including reference to your letters dated June 15, and July 29,1999.
l 11.M. The licensee is authorized to remediate Acid Sludge Pit 4 in accordance with the i
methods and criteria prescribed in the licensee's letters dated November 26,1997, l
February 5,1998, March 3,1998, June 15, and July 29,1999.
4.
A new License Condition i 1.N., which will authorize remediation of the Cushing site.
(
- 11. N. The licensee is authorized to remediate the Cushing Refinery Site in accordance with methods and criteria prescribed in the licensee's Site Decommissioning Plan, h submitted by letter dated August 17,1998, and supplemented by letters dated
)'
June 4,1999, and June 18,1999.
t 9908110035 990805 PDR ADOCK 07003073 C
PDR j
9
' J. Lux The licensee shall use the unrestricted use criteria listed in the August 1987,
" Guidelines for Decontamination of Facilities 'md Equipment Prior to Release for Unrestricted Use or Termination of License for Byproduct, Source, or Special Nuclear Material" for surfaces of buildings and equipment; the February 13,1997,
" Method for Surveying and Averaging Concentrations of Thorium in Contaminated Subsurface Soil" for subsurface contaminated soil in RMA 11 and the Disposal Trench areas; and the Branch Technical Position, the October 23,1981, " Disposal or Onsite Storage of Thorium or Uranium Wastes from Past Operations," for soils.
Specific values are given below--
Soils:
Uranium 1.11 Becquerels per gram (Be/g) [30 pico Curies per gram (pCi/g)]
Thorium 0.37 Be/g (10 pCi/g)
Subsurface soil (RMA 11 and The licensee shall survey in accordance with Disposal Trench areas):
NRC's guidance paper," Method for Surveying and Averaging Concentrations of Thorium in Contaminated Subsurface Soil", as a minimum, but may collect samples on a smaller grid or at more frequent depth intervals. The subsurface soil concentration limits are the same as the soil concentration for uranium and thorium, above.
When multiple radionuclides are present, the sum of the ratios of the concentration of each radionuclide to its respective limit must not exceed 1.
Surfaces:
Uranium 5,000 disintegrations per minute (dpm)/100 square j
2 centimeter (cm ) average contamination level over 1 m or smaller area 2
15,000 dpm/100 cm maximum 2
1,000 dpm/100 cm removable 2
Thorium 1,000 dpm/100 cm average contamination level a
over 1 m or smaller area 2
3,000 dpm/100 cm maximum 2
200 dpm/100 cm removable Exposure rate: Soils 2.6 nanocoulombs per kilogram per hour (nC/kg/hr)
[10 microroentgen per hour (pR/hr)] above background at I meter (m)
Buildings and 1.3 nC/kg/hr (5 pR/hr) above background at I m Equipment:
4 J. Lux..
5.
A new License Condition 11.0., which will assure that the Cushing final survey and sampling program will be performed in accordance with NUREG/CR-5849.
I1.0. The licensee shall conduct a final survey and sampling program of the site in accordance with the December 1993, NUREG/CR-5849," Manual for Conducting Radiological Surveys in Support of License Termination." Radioactivity levels shall not exceed the averaging criteria in NUREG/CR-5849, except for subsurface material in RMA 11 and Disposal Trench areas. Subsurface material in RMA 11 and Disposal Trench areas shall not exceed the averaging criteria in the February 13,1997," Method for Surveying and Averaging Concentrations of Thorium In Contaminated Subsurface Soil." Material that exceeds these averaging criteria shall be removed and shipped off-site to a licensed low-level waste disposal site.
6.
A new License Condition 11.P., which authorizes certain changes to the NRC-approved Site Decommissioning Plan, the Radiation Safety Plan, and associated procedures can be made without NRC's approval.
I1.P. The licensee is authorized to make certain changes to the NRC-approved Site Decommissioning Plan, the Radiation Safety Plan, and associated procedures without NRC's approval, if these changes are consistent with the as-low-as-reasonably-achievable (ALARA) principle and the decommissioning process. All changes shall be approved by the Cushing ALARA Review Committee (ARC),
subject to the following:
1.
The licensee may, without prior NRC's approval, and subject to the requirements specified in Parts 2 and 3 of this condition:
Make changes in the facility or process, as presented in the NRC-a.
approved Site Decommissioning Plan and Radiation Safety Plan; i
b.
Make changes in the procedures presented in the NRC-approved Site Decommissioning Plan, Radiation Safety Plan, or applicable license conditions; and j
Conduct tests or experiments not present in the NRC-approved Site c.
Decommissioning Plan or applicable license conditions.
l 2.
The licensee shall not be required to file an application for an amendment to the license when the following conditions are satisfied; The change, test, or experiment does not conflict with requirements a.
specifically stated in the license (excluding those aspects addressed L
8 m
J. Lux
-4 in Part 1 of this condition): or impair the licensee's ability to meet j
i all applicable NRC regulations; b.
There is no degradation in safety or environmental commitments i
addressed in the NRC-approved Site Decommissioning Plan or Radiation Safety Plan, or have a significant adverse affect on the quality of the work, the remediation objectives, or health and safety; and c.
The change, test, or experiment is consistent with the conclusions of actions analyzed in the Environmental Assessment (EA) dated (insert month and year when the EA for the Site Decommissioning Plan is approved).
3.
The licensee's determination shall be made by the ARC. The ARC shall consist of a minimum of three individuals employed by the licensee, of whom one shall be designated as the ARC chairman. One member of the ARC shall represent corporate (Oklahoma City office) management and shall be responsible for approval of managerial and financial changes.
One member shall represent site operations and shall have responsibility for implementing any changes. One member shall be the site Radiation Safety Officer or equivalent, with responsibility for assuring that changes conform to radiation safety requirements. Additional members may be included in the ARC, as appropriate, to address technical aspects, such as health physics, groundwater hydrology, surface-water hydrology, specific earth sciences, and other technical disciplines. Temporary or permanent members, other than three individuals who are required to be Kerr-McGee Corporation employees, may be consultants. The licensee's determinations as to whether the above conditions are met will be made by the ARC. All such determinations shall be documented, and the records kept until license termination. All such determinations shall be reported annually to 4
the NRC. The retained records shall include written safety and environmental evaluations, made by the ARC, that provide the basis for determining whether or not the above conditions are met.
)
7.
A new License Condition 11.Q., will confirm compliance with the requi,rements of 10 CFR Part 20, Appendix B for liquid and airborne effluents releases during remediation operations.
I1.Q. During the remediation operations, liquid and airborne effluents will be sampled and analyzed to ensure that releases meet the requirements of 10 CFR Part 20 Appendix B. Ifliquid waste radioactivity concentrations exceed the requirements in 10 CFR Part 20 and require processing, the licensee shall request NRC approval of the proposed processing system.
4 J. Lux' '
, 1
. 8.
( A new License Con'dition 11.R., will include what had been condition 11.N.
11.R. Except as specifically provided....
- If you have any questions or comments related to these proposed changes, please contact me at (301) 415-6605, within 5 working days from the date of this letter.
Sincerely, hd W"
Stewart W. Brown, Project Manger
- Decommissioning Branch Division of Waste Management Office of Nuclear Material Safety and Safeguards Docket No. 70-3073 License No. SNM-1999
Enclosure:
As stated cc w/encli Kerr-McGee, Cushing distribution list e
p.
')
I J. Lux 5-8.
A new License Condition 11.R., will include what had been condition 11.N.
I1.R. Except as specifically provided....
If you have any questions or comments related to these proposed changes, please contact me at (301) 415-6605, within 5 working days from the date of this letter.
l Sincerely,
[0RIGINAL SIGNED BY:]
Stewart W. Brown, Project Manger Decommissioning Branch Division of Waste Management Office of Nuclear Material Safety and Safeguards Docket No. 70-3073 License No. SNM-1999
Enclosure:
As stated cc w/ encl: Kerr-McGee, Cushing distribution list This docu t should /A- ::: / / be made available to the PUBLIC k 7/499.
Using this format will require the originator / supervisor to scratch one or the other, and initial.
DISTRIBUTION:
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1 NAME SBrowstv JCopeland BSpitzberg TCJohnson auiper 7M9 F M/99 f/499
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