ML19304B902

Attachment 2 - Chapter 1.0 General Information

ML19304B902
Person / Time
Site:	07001113
Issue date:	10/31/2019
From:	Global Nuclear Fuel
To:	Office of Nuclear Material Safety and Safeguards
Shared Package
ML19304B896	List: ML19304B898 ML19304B899 ML19304B902 ML19304B904
References
M190173
Download: ML19304B902 (23)

Text

Attachment 2 LICENSE SNM-1097 DATE 10/31/19 Page DOCKET 70-1113 REVISION 4

1.1 CHAPTER 1.0 GENERAL INFORMATION 1.1 FACILITY AND PROCESS DESCRIPTION The primary purpose of the Global Nuclear Fuel - Americas, L.L.C. facility in Wilmington, North Carolina (identified in this document as GNF-A) is the manufacture of fuel assemblies for commercial nuclear reactors. Nuclear materials enriched to less than or equal to 8 weight percent U-235 are utilized in the product manufacturing operations authorized by this license. The safety, environmental, quality assurance and emergency preparedness aspects of the manufacturing operations are managed and controlled as described in this license.

1.1.1 SITE DESCRIPTION AND LOCATION GNF-A is situated on a 1,664-acre tract of land, located on N.C. Highway 133 and approximately six miles north of the City of Wilmington, North Carolina in New Hanover County (refer to Figures 1.1 and 1.2). New Hanover County is situated in the southern coastal plains section of southeastern North Carolina, with the Atlantic Ocean on the east and the Cape Fear River on the west. The Atlantic Ocean lies approximately 10 miles east and 26.4 miles south of GNF-A. The surrounding terrain is low-lying, with an average elevation of less than 40 feet above mean sea level.

Castle Hayne, the nearest community, is approximately three miles north of GNF-A.

The region around the site is lightly settled with large areas of heavily timbered tracts of land. Farms, single-family dwellings and light commercial activities are located along N.C. Highway133. The Wilmington airport is located approximately 3.5 miles southeast of the site.

1.1.2 FACILITY DESCRIPTION The location and arrangement of buildings at GNF-A, and their relative distance from the site boundary are shown in Figure 1.3. Located on the property are the following major facilities: (1) the Aviation LICENSE SNM-1097 DATE 10/31/19 Page DOCKET 70-1113 REVISION 4

1.2 FIGURE 1.1 PLANT SITE - STATE AND COUNTY LOCATIONS

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LICENSE SNM-1097 DATE 10/31/19 Page DOCKET 70-1113 REVISION 4

1.3 FIGURE 1.2 NEW HANOVER COUNTY AND ADJACENT COUNTIES

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1.4 FIGURE 1.3 GLOBAL NUCLEAR FUEL - AMERICAS, L.L.C. (GNF-A)

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GLOBAL NUCLEAR FUEL -AMERICAS, L.L.C. (GNF-A)

SITE PLAN LEGEND LEGEND:

1. FUEL MANUFACTURING OPERATION (FMO)

19. *ocp* FACIUlY

2. FUEL COMPONENTS OPERATION (FCO) 3 AVIATION*OPERATIONt

20. FMO/FMOX SHIPPING WAREHOUSE

21. WILM FLO SVC CTR WAREHOUSE

4. SERVICES COMPONENTS OPERATION (SCO)

22. 10-WIDE MODULAR OFFICE

5. FINAL PROCESS LAGOONS

23. SANITARY BUILDING

6. WASTE TREATMENT FACILITY

24. HF FACILllY

7. INCINERATOR BUILDING

25. GE90 BLOC. (AVIATION>,

8. FILTER FACILllY

26. CAF2 PITS

9. DA BUILDING

27. STORAGE PADS

10. BOILER/SCRAP PACK FACIL11Y (SPF)

28. ENGINEERING BUILDING

11. BUILDING *J*

29. GE INSPECTION SERVICES

12. SITE MAINTENANCE

30. WILM FLO SVC CTR OFFICE

13. SITE WAREHOUSE/SOURCING

31. 1 3-WIDE MODULAR OFFICE

14. FMO STORAGE BUILDING

32. 1 4-WIDE MODULAR OFFICE 15 'FtTF.T.*O'R0W'T'H*'P'R0IT.r.TS* 'RT.nO *

33. GETTER TRAILER / GRANITE OFFICE

16. A.E. MAINTENANCE

34. 5-WIDE IT TRAILER

17. WASTE TREATMENT LAGOONS

35. WILM FLDS SVC CTR WAREHOUSE f 2

18. FUEL EXAMINATION TECHNOLOGY FACILllY LICENSE DOCKET SNM-1097 70-1113 DATE REVISION 10/31/19 4

Page 1.5

Attachment 2 LICENSE SNM-1097 DATE 10/31/19 Page DOCKET 70-1113 REVISION 4

1.6 facility which is not involved in the nuclear fuel manufacturing operation, (2) The GE Services Components Operation (SCO) facility where non-radioactive reactor components are manufactured, (3) the Fuel Components Operation (FCO) facility where non-radioactive components for reactor fuel assemblies are manufactured, and (4) the fuels complex containing the fuel manufacturing facility. The fuels complex, which includes the Fuel Manufacturing Operation and Dry Conversion Process (FMO/FMOX & DCP) buildings and supporting facilities, is enclosed by a fence with restricted access. This complex is called the Controlled Access Area (CAA).

Additionally, inside the CAA is the Wilmington Field Services Center (WFSC) operation which cleans and refurbishes contaminated and non-contaminated equipment used at reactor sites. This area is regulated by a North Carolina Division of Radiation Protection license.

1.1.3 FACILITY RESISTANCE TO ENVIRONMENTAL EVENTS In the coastal area of North Carolina where GNF-A is located, the greatest severe weather threat in this area is due to high winds from hurricanes and possible tornadoes. Facility construction meets or exceeds local codes (in effect when designed and constructed) for strength and, in the case of hurricanes, advance notice provides an opportunity for further mitigating actions. Since high winds could impact electrical power, key safety systems are protected with adequate back-up power supplies or fail safe features. Earthquakes are not considered a major threat because this section of the southern Atlantic Seaboard is an area of relatively low seismic activity.

The Fuel Manufacturing Operation building in which radioactive materials are processed and stored, is designed to provide for containment of material under adverse environmental conditions such as fire, wind, flooding or earthquake to the limits of the building code. The roof construction meets Factory Mutual requirements for fire hazard and wind resistance.

Detailed information regarding the facility resistance to the effects of potential credible accident sequences is contained in the facilities ISA Summaries submitted in accordance with 10 CFR 70.65(b).

1.1.4 PROCESS DESCRIPTION The product manufacturing operations authorized by this license consist of receiving low-enriched, (less than or equal to 8.0 weight percent U-235), uranium hexafluoride; converting the uranium hexafluoride to uranium dioxide powder; and LICENSE SNM-1097 DATE 10/31/19 Page DOCKET 70-1113 REVISION 4

1.7 processing the uranium dioxide through pelletizing steps, fuel rod loading and sealing, fuel assembly, storage and product shipment.

The manufacturing operations are served by support systems such as waste disposal, laboratory, and manufacturing technology development, which are also described in this license.

1.2 INSTITUTIONAL INFORMATION GNF-As NRC license number is SNM-1097 (Docket #70-1113).

1.2.1 IDENTITY AND ADDRESS This application for license renewal is filed by the Global Nuclear Fuel - Americas, L.L.C., a wholly-owned subsidiary of Global Nuclear Fuel Holding Co., L.L.C., in which General Electric holds a majority ownership interest. Global Nuclear Fuel -

Americas, L.L.C. is headquartered in Wilmington, North Carolina.

The full address is as follows: Global Nuclear Fuel - Americas, L.L.C., mailing address P.O. Box 780, Wilmington, NC 28402 or location address 3901 Castle Hayne Road, Wilmington, NC 28401.

1.2.2 TYPE, QUANTITY, AND FORM OF LICENSED MATERIAL Uranium normally will be used at GNF-A in the Controlled Access Area (CAA) only. Conversion and fabrication is conducted within the fuel manufacturing building (FMO/FMOX & DCP). Small quantities (i.e., less than one safe batch of uranium in a non-dispersible form) may be temporarily moved to other buildings or site locations outside of the CAA for special tests under special authorizations and controls.

The following types, maximum quantities, and forms of special nuclear materials are authorized:

LICENSE SNM-1097 DATE 10/31/19 Page DOCKET 70-1113 REVISION 4

1.8

1) ((

)) kilograms of U-235 contained in uranium enriched to a maximum enrichment of less than or equal to 8%, in any chemical or physical form,

2) ((

)) grams of U-235 at nominal enrichments >8% to <20% in any form for use in laboratory and process development operations,

3) ((

)) grams of U-235 in any form and at any enrichment for use in measurement and detection instruments, check sources and instrument response standards,

4) Plutonium - (( )) milligram in samples for analytical purposes, (( )) milligram as standards for checking the alpha radiation response of radiation detection instrumentation, and in nuclear fuel rods at a level of less than 1 x 10-6 gram of plutonium per gram of U235, and

5) ((

)) milligrams U-233 for analytical purposes.

1.2.3 ACTIVITY GNF-A complies with applicable parts of Title 10, Code of Federal Regulations, unless specifically amended or exempted by NRC staff.

Authorized activities at GNF-A include:

1.2.3.1 Product Processing Operations

UF6 Conversion - Conversion of uranium hexafluoride to uranium oxides by the ADU process and the Dry Conversion Process.

Fuel Manufacture - Fabrication of nuclear reactor fuel (powder, pellets, or assemblies) containing uranium.

Scrap Recovery - Reprocessing of uranium bearing material from GNF-A fuel fabrication activities and from other sources with nuclear safety characteristics not significantly different from GNF-As in-process materials.

Waste Recovery - Recovery of uranium from wet and dry material stored in on-site pits and basins. The recovered uranium will be returned to the fuel processing facility.

LICENSE SNM-1097 DATE 10/31/19 Page DOCKET 70-1113 REVISION 4

1.9 1.2.3.2 Process Technology Operations Development and fabrication of reactor fuel, fuel elements and fuel assemblies of advanced design in small amounts.

Development of scrap recovery processes.

Determination of interaction between fuel additives and fuel materials.

Chemical analysis and material testing, including physical and chemical testing and analysis, metallurgical examination and radiography of uranium compounds, alloys and mixtures.

Instrument research and calibration, including development, calibration and functional testing of nuclear instrumentation and measuring devices.

Conversion of UF6 to UO2 and other intermediate compounds using chemical and dry processes.

Other process technology development activities related to, but not limited by, the above.

1.2.3.3 Laboratory Scale Laser Enrichment Research and Development Operation of a laboratory scale research and development activity related to the enrichment of uranium using laser energy involving the extension of investigative findings and theories of a technical nature based on original work by Silex Limited.

Experimental production of slightly enriched uranium from natural uranium feed material to test models, devices, equipment, materials and processes for the sole purpose of developing a practical application of the technology.

Withdrawal of samples from the test-loop for the purpose of evaluating process performance.

Other enrichment technology development activities related to, but not limited by the above.

1.2.3.4 Laboratory Operations Chemical, physical or metallurgical analysis and testing of uranium compounds and mixtures, including but not limited to, preparation of laboratory standards.

1.2.3.5 General Services Operations LICENSE SNM-1097 DATE 10/31/19 Page DOCKET 70-1113 REVISION 4

1.10 Storage of unirradiated fuel assemblies, uranium compounds and mixtures in areas arranged specifically for maintenance of criticality and radiological safety.

Design, fabrication and testing of uranium prototype processing equipment.

Maintenance and repair of uranium processing equipment and auxiliary systems.

Storage and nondestructive testing of fuel rods containing trace amounts of plutonium as authorized in the license.

1.2.3.6 Waste Treatment and Disposal Treatment, storage and disposal and/or shipment of liquid and solid wastes whose discharges are regulated.

Decontamination of non-combustible contaminated wastes to reduce uranium contamination levels, and subsequent shipment of such low-level radioactive wastes to licensed burial sites for disposal or as authorized by the NRC.

Treatment or disposal of combustible waste and scrap material by incineration pursuant to 10 CFR 20.2002 and 10 CFR 20.2004.

1.2.3.7 Off-site Activities Testing, demonstration, non-destructive modification and storage of materials and devices containing uranium, provided that such materials and devices shall be under GNF-As control at all times.

1.2.3.8 Possession of Classified Matter Authorization to use, possess, store, reproduce, transmit, handle and transport classified matter under conditions specified in the standard Practice and Procedures Plan (SPPP) submitted and approved in accordance with 10 CFR Part 95 requirements. The licensee is to maintain the SPPP in accordance with 10 CFR 95.19.

LICENSE SNM-1097 DATE 10/31/19 Page DOCKET 70-1113 REVISION 4

1.11 1.3 SPECIAL AUTHORIZATIONS AND EXEMPTIONS 1.3.1 AUTHORIZATIONS TO MAKE CHANGES TO LICENSE COMMITMENTS 1.3.1.1 Changes Requiring Prior NRC Approval GNF-A will not make changes to the site, structures, processes, systems, equipment, components, computer programs or personnel activities unless those changes are authorized in accordance with10 CFR 70.72 and/or this license. Requests for amendment of the license will be made in accordance with 10 CFR 70.34 and 10 CFR 70.65.

1.3.1.2 Changes Not Requiring Prior NRC Approval GNF-A is authorized to make changes to the site, structures, processes, systems, equipment, components, computer programs and activities of personnel without prior NRC approval provided the changes do not:

Create new types of accident sequences that, unless prevented or mitigated, would exceed the performance requirements of 10 CFR 70.61, and that have not previously been described in the ISA Summary Use new processes, technologies or control systems for which GNF-A has no prior experience Remove, without at least an equivalent replacement of the safety function, an item relied on for safety (IROFS) that is listed in the ISA Summary and is necessary for compliance with the performance requirements of 10 CFR 70.61.

Alter any IROFS, listed in the ISA Summary, that is the sole IROFS preventing or mitigating an accident sequence that would be expected to exceed the performance requirements of 10 CFR 70.61 Violate any other NRC regulation, license condition or order.

1.3.1.3 On-Site Documentation GNF-A shall maintain records of changes to its facilities carried out under 10 CFR 70.72. These records will contain an evaluation that provides the basis for the determination that the changes do not require prior NRC approval.

LICENSE SNM-1097 DATE 10/31/19 Page DOCKET 70-1113 REVISION 4

1.12 These records will be maintained until the termination of the license.

For changes covered by 10 CFR 70.72, the affected on-site documentation is updated promptly not to exceed 3-months from the approval of the change.

1.3.1.4 Annual Reporting of Changes For changes not requiring pre-approval by the NRC, GNF-A shall submit annually, within 30-days after the end of the calendar year during which the change occurred, a brief summary of all the changes to the records required by 10 CFR 70.62 (a) (2).

For all changes that affect the ISA Summary, GNF-A shall submit annually, within 30-days after the end of the calendar year during which the change occurred, revised ISA Summary pages.

1.3.2 AUTHORIZED GUIDELINES FOR CONTAMINATION-FREE ARTICLES Authorization to use the guidelines, contamination and exposure rate limits specified at the end of this Section, "Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material," US NRC, April 1993 for decontamination and survey of surfaces or premises and equipment prior to abandonment or release for unrestricted use.

LICENSE SNM-1097 DATE 10/31/19 Page DOCKET 70-1113 REVISION 4

1.13 1.3.3 AUTHORIZED TRANSFER OF CONTAMINATION-FREE LIQUIDS 1.3.3.1 Transfer of Hydrofluoric Acid (HF) for Testing Authorization to transfer test quantities of HF to potential buyers/customers or laboratories for the purpose of analyzing, examination or evaluation, without continuing NRC controls as described in a letter to the NRC dated February 27, 1996.

Test quantities may not contain more than 3 PPM uranium with an enrichment not to exceed 8% U-235.

The recipients will be advised that this material is not a nuclear hazard, but will be advised that the material should be handled carefully and in such a manner so as not to be consumed by humans nor used in products used on or in the body or in the food chain.

1.3.3.2 Transfer of Hydrofluoric Acid as Product Authorization, pursuant to 10 CFR 70.42(b)(3), to transfer liquid hydrofluoric acid to any commercial chemical company/supplier without either company possessing an NRC or Agreement State license for special nuclear material, provided that the concentration of uranium does not exceed three parts per million by weight of the liquid and the enrichment is less than or equal to 8 weight percent U-235.

The hydrofluoric acid is transferred and used in such a manner that the minute quantity of uranium does not enter into any food, beverage, cosmetic, drug or other commodity designated for ingestion or inhalation by, or application to, a human being such that the uranium concentration in these items would exceed that which naturally exists. Additionally, the acid is used in a process which will not release the low levels of radioactivity to the atmosphere as airborne material and whose residues will remain in a wastewater or other treatment system.

Prior to shipment, each transfer is sampled and measured to assure that the concentration does not exceed three parts per million of uranium (3 ppmU).

LICENSE SNM-1097 DATE 10/31/19 Page DOCKET 70-1113 REVISION 4

1.14 GNF-A shall maintain records under this condition of license including, as a minimum, the date, uranium concentration and quantity of hydrofluoric acid transferred.

1.3.3.3 Transfer of Nitrate-Bearing Liquids Authorization to transfer nitrate-bearing liquids, provided that the uranium concentration does not exceed a 30-day average of 5 parts per million by weight of the liquids and the enrichment is less than or equal to 8 weight percent U-235 by transport to an off-site liquid treatment system located at International Paper, Riegelwood, North Carolina (or similar commercial paper operation), in which decomposition of the nitrates will occur and from which the denitrified liquids will be discharged in the effluent from the system.

Environmental samples will be taken periodically to monitor effluent releases.

1.3.4 AUTHORIZATION TO TRANSFER TEST QUANTITIES OF CALCIUM FLUORIDE Authorization to transfer test quantities of calcium fluoride (CaF2) to potential buyers for the purpose of their examination and evaluation as described in a letter to the NRC dated September 24, 1992.

Test quantities may not contain more than 30 pCi per gram on a dry weight basis and are limited to 1 gram U-235 at each off-site location.

Test activities and end uses of the material will be limited to those that do not allow chemical separation of the uranium or entry of the product into the food chain.

1.3.5 AUTHORIZATION TO TRANSFER CALCIUM FLUORIDE (CAF2) TO VENDORS FOR BENEFICIAL REUSE Authorization to transfer quantities of industrial waste treatment products (primarily CaF2) to commercial firms, for the purpose of briquette manufacturing and use as a steel flux forming material in the production of steel as described in a letter to the NRC dated December 20, 1989.

LICENSE SNM-1097 DATE 10/31/19 Page DOCKET 70-1113 REVISION 4

1.15 Measurements are made using a sample plan to provide at a 95% confidence level that the population mean for each shipment is less than 30pCi of uranium per gram of material on a dry weight basis.

Activities and end use of the material will be limited to those that do not allow chemical separation of the uranium or entry of the product into the food chain.

1.3.6 AUTHORIZATION TO DISPOSE OF INDUSTRIAL WASTE TREATMENT PRODUCTS Notwithstanding any requirements for state or local government agency disposal permits, GNF-A is authorized to dispose of industrial waste treatment products without continuing NRC controls provided that either of the two following conditions are met:

1.3.6.1 Free-standing liquid shall be removed prior to shipment.

The uranium concentration in the material shipped for disposal shall not exceed 30 pCi per gram after free-standing liquid has been removed.

The licensee shall possess authorization from appropriate state officials prior to disposing of the waste material. The authorization shall be available for inspection at GNF-A.

1.3.6.2 The uranium concentration in the material shipped for disposal only at approved facilities such as Pinewood, South Carolina (licensed by the State of South Carolina), shall not exceed 250 pCi per gram of uranium activity, of which no more than 100 pCi per gram shall be soluble.

1.3.7 AUTHORIZATION TO STORE SANITARY SLUDGE PENDING FINAL DISPOSAL Dried sanitary sludge is collected and disposed of at approved offsite facilities in LICENSE SNM-1097 DATE 10/31/19 Page DOCKET 70-1113 REVISION 4

1.16 accordance with Section 1.3.6. Authorization to store treated sanitary sludge containing trace amounts of uranium in the sanitary sludge land application area pending final disposal.

1.3.8 AUTHORIZATION FOR THE USE OF MATERIALS AT OFF-SITE LOCATIONS 1.3.8.1 Authorization to store at nuclear reactor sites, uranium fully packaged for transport in any NRC approved package, in accordance with the conditions of a license authorizing delivery of such containers to a carrier for NRC approved transport, at locations in the United States providing such locations minimize the severity of potential accident conditions to be no greater than those in the design bases for the containers during transportation.

Provisions for compliance with applicable 10 CFR 73 requirements are described in the NRC-approved GNF-As Physical Security Plan as currently revised in accordance with regulatory provisions.

Storage at nuclear reactor sites is subject to the financial protection and indemnity provision of 10 CFR 140. Storage of the fuel is under the direct supervision of a member of the GNF-A or GE Nuclear staff. This person shall comply with applicable reactor license and procedural requirements as directed by the reactor site representative.

1.3.8.2 Authorization to transfer, possess, use and store unirradiated reactor fuel of GNF-As manufacture or procured to GNF-As specification at nuclear reactor sites, for purposes of inspection, fuel bundle disassembly and assembly, including fuel rod replacement, provided that the following conditions are met:

A valid NRC license has been issued to the reactor licensee, which authorizes receipt, possession and storage of the fuel at the reactor site. GNF-A possesses the fuel only within the indemnified location.

For dry fuel reconstitution, not more than 99 (9x9 or 10x10 lattices) or 88 (8x8 lattices) unassembled fuel rods may be possessed by GNF-A at any one reactor site at any one time, except when the fuel has been packaged for transport.

LICENSE SNM-1097 DATE 10/31/19 Page DOCKET 70-1113 REVISION 4

1.17 For underwater fuel reconstitution, not more than one fuel assembly plus unassembled fuel rods so that the total number of rods, including the assembly, possessed by GNF-A at any one reactor site at any one time does not exceed 99 (9x9 or 10x10 lattices) or 88 (8x8 lattices), except when the fuel has been packaged for transport or as described in Section 1.3.8.2.

Operations involving the fuel are conducted by or under the direct supervision of a GNF-A authorized person who shall be responsible for work on the fuel element assembly. The person shall comply with applicable reactor license and procedure requirements as directed by reactor site representatives, including appropriate actions that are to be taken in the event of emergencies at the site.

Loose rods are stored in RA-series inner metal containers.

Fuel is handled in accordance with pertinent provisions of the reactor license, and also in accordance with applicable GNF-A or GE Nuclear procedures which are jointly verified by GE and the reactor licensee.

Records of the operation, including the procedures used, are maintained at GNF-A.

1.3.9 AUTHORIZATION TO USE A DILUTION FACTOR FOR AIRBORNE EFFLUENTS Pursuant to 10 CFR 20.1302, GNF-A is authorized to utilize a dilution factor of 100 to the measured stack discharges for the purpose of evaluating the airborne radioactivity at the closest site boundary.

This conservative dilution factor is derived using standard diffusion models and conservative assumptions regarding physical and atmospheric characteristics of the site. Records of the derivation of this factor are maintained on site for inspection.

1.3.10 AUTHORIZATION FOR WORKPLACE AIR SAMPLING ADJUSTMENTS Authorization to adjust Derived Air Concentration (DAC) limits and Annual Limit of Intake (ALI) values in process areas to reflect chemical and physical characteristics of the airborne uranium.

LICENSE SNM-1097 DATE 10/31/19 Page DOCKET 70-1113 REVISION 4

1.18 1.3.11 EXEMPTION TO CRITICALITY MONITORING SYSTEM REQUIREMENTS Authorization that it is not necessary to maintain the criticality accident monitoring system requirements of 10 CFR 70.24 when it is demonstrated that a credible criticality risk does not exist for:

1.3.11.1 A quantity of finished reactor fuel rods equal to or less than 45% of a minimum critical number under conditions in which double batching is credible, or equal to or less than 75% of a minimum critical number under conditions in which double batching is not credible, or 1.3.11.2 The quantity of uranium authorized for delivery to a carrier when fully packaged as for transport according to a valid NRC authorization for such packages without limit on the number of such packages, provided storage locations preclude mechanical damage and flooding, or 1.3.11.3 Individual areas where there is negligible risk of criticality due to the amount or configuration of fissile material.

In these areas, an evaluation has determined the risk of criticality is very low such that no credible accident sequence can be identified that results in criticality.

1.3.12 EXEMPTION TO POSTING REQUIREMENTS Authorization to post areas within the Controlled Access Area in which radioactive materials are processed, used, or stored, with a sign stating Every container in this area may contain radioactive material in lieu of the labeling requirements of 10 CFR 20.1904.

1.3.13 EXEMPTION TO EXTREMITY DOSE DETERMINATION REQUIREMENTS Authorization to use a skin thickness of 38 milligrams/cm2 in the assessment of worker fingertip doses from uranium and for determining compliance to NRC extremity dose limits.

LICENSE SNM-1097 DATE 10/31/19 Page DOCKET 70-1113 REVISION 4

1.19 1.3.14 UNRESTRICTED RELEASE OF THE NORTHWEST CAF2 STORAGE AREA Pursuant to the CaF2 Survey and Release Plan dated 3/27/96 as amended, and the Final Status Survey Report for the Northwest CaF2 Storage Area, dated October 1999, the area described as the Northwest CaF2 Storage Area has been adequately remediated, and therefore meets the unrestricted release criteria.

1.3.15 AUTHORIZATION TO USE ICRP 68 DAC and ALI values based on dose coefficients published in ICRP Publication No.

68 will be used in lieu of the values in Appendix B of 10 CFR Part 20 in accordance with internal procedures.

LICENSE SNM-1097 DATE 10/31/19 Page DOCKET 70-1113 REVISION 4

1.20 GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE, OR SPECIAL NUCLEAR MATERIAL U.S. Nuclear Regulatory Commission Division of Fuel Cycle Safety and Safeguards Washington, DC 20555 April 1993 LICENSE SNM-1097 DATE 10/31/19 Page DOCKET 70-1113 REVISION 4

1.21 The instructions in this guide, in conjunction with Table 1, specify the radionuclides and radiation exposure rate limits which should be used in decontamination and survey of surfaces or premises and equipment prior to abandonment or release for unrestricted use. The limits in Table 1 do not apply to premises, equipment, or scrap containing induced radioactivity for which the radiological considerations pertinent to their use may be different. The release of such facilities or items from regulatory control is considered on a case-by-case basis.

1.

The licensee shall make a reasonable effort to eliminate residual contamination.

2.

Radioactivity on equipment or surfaces shall not be covered by paint, plating, or other covering material unless contamination levels, as determined by a survey and documented, are below the limits specified in Table 1 prior to the application of the covering. A reasonable effort must be made to minimize the contamination prior to use of any covering.

3.

The radioactivity on the interior surfaces of pipes, drain lines, or ductwork shall be determined by making measurements at all traps, and other appropriate access points, provided that contamination at these locations is likely to be representative of contamination on the interior of the pipes, drain lines, or ductwork. Surfaces of premises, equipment, or scrap which are likely to be contaminated but are of such size, construction, or location as to make the surface inaccessible for purposes of measurement shall be presumed to be contaminated in excess of the limits.

4.

Upon request, the Commission may authorize a licensee to relinquish possession or control of premises, equipment, or scrap having surfaces contaminated with materials in excess of the limits specified. This may include, but would not be limited to, special circumstances such as razing of buildings, transfer of premises to another organization continuing work with radioactive materials, or conversion of facilities to a long-term storage or standby status. Such requests must:

a.

Provide detailed, specific information describing the premises, equipment or scrap, radioactive contaminants, and the nature, extent, and degree of residual surface contamination.

b.

Provide a detailed health and safety analysis which reflects that the residual amounts of materials on surface areas, together with other considerations such as prospective use of the premises, equipment, or scrap, are unlikely to result in an unreasonable risk to the health and safety of the public.

LICENSE SNM-1097 DATE 10/31/19 Page DOCKET 70-1113 REVISION 4

1.22

5.

Prior to release of premises for unrestricted use, the licensee shall make a comprehensive radiation survey which establishes that contamination is within the limits specified in Table 1. A copy of the survey report shall be filed with the Division of Fuel Cycle Safety and Safeguards, U. S. Nuclear Regulatory Commission, Washington, DC 20555, and also the Administrator of the NRC Regional Office having jurisdiction. The report should be filed at least 30 days prior to the planned date of abandonment. The survey report shall:

a.

Identify the premises.

b.

Show that reasonable effort has been made to eliminate residual contamination.

c.

Describe the scope of the survey and general procedures followed.

d.

State the findings of the survey in units specified in the instruction.

Following review of the report, the NRC will consider visiting the facilities to confirm the survey.

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1.23 TABLE 1 ACCEPTABLE SURFACE CONTAMINATION LEVELS NUCLIDESa AVERAGEbcf MAXIMUMbdf REMOVABLEbef U-nat, U-235, U-238, and associated decay products 5,000 dpm /100 cm2 15,000 dpm /100 cm2 1,000 dpm /100 cm2 Transuranics, Ra-226, Ra-228, Th-230, Th-228, Pa-231, Ac-227, I-125, I-129 100 dpm/100 cm2 300 dpm/100 cm2 20 dpm/100 cm2 Th-nat, Th-232, Sr-90, Ra-223, Ra-224, U-232, I-126, I-131, I-133 1000 dpm/100 cm2 3000 dpm/100 cm2 200 dpm/100 cm2 Beta-gamma emitters (nuclides with decay modes other than alpha emission or spontaneous fission) except Sr-90 and others noted above.

5,000 dpm /100 cm2 15,000 dpm / 100 cm2 1,000 dpm /100 cm2 aWhere surface contamination by both alpha-and beta-gamma-emitting nuclides exists, the limits established for alpha-and beta-gamma-emitting nuclides should apply independently.

bAs used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, and geometric factors associated with the instrumentation.

cMeasurements of average contaminant should not be averaged over more than 1 square meter. For objects of less surface area, the average should be derived for each such object.

dThe maximum contamination level applies to an area of not more than 100 cm2.

eThe amount of removable radioactive material per 100 cm2 of surface area should be determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. When removable contamination on objects of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped.

fThe average and maximum radiation levels associated with surface contamination resulting from beta-gamma emitters should not exceed 0.2 mrad/hr at 1 cm and 1.0 mrad/hr at 1 cm, respectively, measured through not more than 7 milligrams per square centimeter of total absorber.