ML20235E544

Application for Amend to License SNM-1097,revising Part I to Condition 9 of License.Fee Paid

ML20235E544
Person / Time
Site:	07001113
Issue date:	05/22/1987
From:	Winslow T GENERAL ELECTRIC CO.
To:	NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
28237, NUDOCS 8707110111
Download: ML20235E544 (31)

Text

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c GENERALO ELECTRIC

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NUCLEAR FUEL & COMPONENTS MANUFACTURING GENERAL ELECTRIC COMPANY

• P.O. BOX 780

• WILMINGTON, NORTH CAROUNA 2B402 May 22, 1997 g

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Office of Nuclear Materials Safety & Safeguards q

U. S. Nuclear Regulatory Cornission ca 1+

Washington, D.

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l Attention:

Mr.

L. C. Rouse, Chief Fuel Cycle Safety Branch

Reference:

NRC License SNM-1097, Docket #70-1113

Subject:

LICENSE AMENDMENT REQUEST (REVISION #16) l GE Nuclear Fuel & Components Manufacturing hereby submits a requested revision to Part I of the application approved by

. Condition 9 of License SNM-1097. to this letter I

describes the requested revision and Attachment 2 contains the' l

revised pages.

j Pursuant to 10 CFR 170.31, a GE check for $150 for processing j

this amendment request will be forwarded under separate cover.

If you have any questions regarding this matter, please contact me.

Very truly yours, GENERAL ELECTRIC COMPANY

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Preston Winslow, Manager Licensing & Nuclear Materials Management l

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GENER AL $ ELECTRIC Director - ONMSS May 22, 1987 ATTACHMENT 1 DESCRIPTION OF REVISIONS Description Page 7 - 12 Revised to reflect revision to Chapter 1.

I-1.4

" Department General Manager" was changed to "Wilmington facility Manager" to reflect's title change.

I-1.5 In Section.1.7, references to 10 CFR Parts' 74 and 75 were added.

l I-1.17 Paragraph 1.8.9, " Posting", has beert inserted.

10 CFR 20.203(f) details the labeling requirements l

for containers of radioactive material.

Due to the impracticality of labeling certain types of individual containers (i.e., bundles, laboratory vials, etc.), NF&CM requests authorization to post areas containing these types of containers with a sign stating "Every container in this area may j

contain radioactive material" in lieu of individual container labeling.

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I GENER AL h ELECTRIC Director - ONMSS May 22, 1987 i

ATTACHMENT 2 REVISION 16 DATED 5/22/87 TO PART I OF APPLICATION j

APPROVED BY CONDITION 9 OF f

NRC LICENSE SNM-1097, DOCKET #70-1113 l

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REVISIONS BY PAGE l

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l Effective Effective Effective l

Page.

Date Page Date Page Date TABLE OF CONTENTS CHAPTER 2 I-3,11 5/14/84 I

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12 I-2.12 I-3.24 I-2.13 I-3.25 I-2.14 I-3.26 PART I I-2.15 I-3.27 l

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CEAPTER 1 I-2.19 CHAPTER 4 1

1 I-1.1 5/22/87 I-2.20 j

l I-1.2 I-2.21 I-4.1 10/23/84 i

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I-1,7 CHAPTER 3 I-4.6 I-1.8 I-4.7 i

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I-1.11 I-3.3 I-4.10 I-1.12 I-3.4 I-4.11 I-1.13 I-3.5 6/20/84 I-4.12 I-1.14 I-3.6 5/14/84 I-4.13 11/12/84 1

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LICENSE SNM-1097 DATE 5/22/87 PAGE DOCKET 70-1113 REVISION 16

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REVISIONS BY PAGE Effective Effective Effective Page Date Page __

Date Page Date 9

I-4.20 11/12/64 CHAPTER 6 I-4.21 11/20/84 I-4.22 I-621 6/20/84 I-4.23 I-4.24 I-4.25 I-4.25 CHAPTER 7 I-7.1 5/14/84 CHAPTER 5 I-5.1 5/14/84 I-5.2 CHAPTER 8 I-5. 3 I-5.4 I-8.1 8/25/86 I-5. 5 -

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I-5.8 6/20/84 I-5. 9 5/14/84 I-5.10 I-5.11 I-5.12 I-5.13 I-5.14 6/20/84 I-5.15 5/14/84 I-5.16 6/20/84 I-5.17 5/14/84 I-5.18 6/20/84 I-5.19 I-5.20 5/14/84 I-5.21 6/20/84 I-5.22 I-5.23 I-5.24 I-5.25 I-5.26 I-5.27 I-5.28 LICENSE SNM-1097 DATE 5/22/87 PAGE DOCKET 70-1113 REVISION 16 8-

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REVISIONS BV PAGE l

Effective Effective Effective Page Date Page Date Page Date II-10.22 7/25/83 II-11.15 7/25/83 l

PART II II-10.23 II-11.16 l

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II-10.25 II-11.18 I

CHAPTER 9 II-10.26 II-11.19 l

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11-9.2 II-10.29 II-11.22

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II-9.8 II-10.35 II-11.28 II-10.36 II-1 1. 29 j

II-10.37 II-11.30 CHAPTER 10 II-10.38 II-1 1. 31 II-10.39 II-11.32 1

l I I-10.1 7/25/83 I I-10. 4 0 II-11.33 II-10.2 II-10.41 II-11.34 l

II-10.3 II-10.42 II-11.35 II-10.d II-11.36 II-10.5 II-11.37

'II-10.6 CHAPTER 11 II-11.38 i

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I I-10. 9 II-11.2 II-11.41 II-10.10 II-11.3 II-11.42 II-10.11 II-11.4 II-11.43 II-10,12 II-11.5 II-11.44 I I-10.13 II-11.6 II-11.45 II-10.14 II-11.7 II-11.46 II-10.15 II-11.8 II-11.47 II-10.16 II-11.9 II-11.48 I I-10.17 II-11.10 II-11.49 II-10.18 II-11.11 II-11.50 I I-10.19 II-11.12 I I-1 1. 51 II-10.20 II-11.13 II-11.52 I I-10. 21 I I-1 1.14 II-1 1,53 LICENSE SNM-1097 DATE 5/22/87 PAGE DOCKET 70-1113 REVISION 16 l

REVISIONS BY PAGE Effective Effective Effective Page Date Page Date Page Date I

II-11.54 7/25/63 I I-13.10 7/25/83 II-13.49 7/25/83 l

II-11.55 II-13.11 II-13.50 II-11.56 I I-13,12 I I-13. 51 II-13.13 II-13.52 I I-13.14 II-13.53 CHAPTER 12 II-13.15 II-13.54 II-13.16 II-13.55 II-12.1 7/25/83 II-13.17 II-13.56 II-12.2 II-13.18 II-13.57 II-12.3 II-13.19 II-13.58 II-12.4 II-13.20 II-13.59 II-12.5 II-13.21 II-13.60 II-12.6 II-13.22 II-13.61 II-12.7 II-13.23 II-13.62 II-12.8 II-13.24 II-13.63 II-12.9 II-13.25 II-13.64 II-12 In II-13.26 II-13.65 II-12.11 II-13.27 II-13.66 II-12.12 II-13.28 II-13.67 II-12.13' II-13.29 II-13.68 l

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II-13.37 II-13.76 CHAPTER 13 II-13.3E II-13.77 II-13.39 II-13.78 II-13.1 7/25/63 II-13.40 II-13.79 II-13.2 II-13.41 II-13.80 II-13.3 II-13. 4 2 II-13.81 II-13.4 II-13.43 II-13.82 II-13.5 I I-13. 4 4 II-13.83 II-13.6 II-13.45 II-13.84 II-13.7 II-13.40 I.I-13. 8 5 II-13.8 II-13.47 IT-13.86 II-13.9 II-13.48 II-13.87 l

LICENSE SNM-1097 DATE 3/22/87 hkGE DOCKET 70-1113 REVISION 16 l l j

REVISIONS BY PAGE Effective Effective Effective P ag e Date__

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1I-15.22 II-16.10 I I-15. 49 II-15,. 2 3 1I-16.11 II-16.50 II-15.24 21-16.12 II-16.51 11-15.25 1I-16.11 II-16.52 11-15.26 II-16.14 II-16.53 LICENSE SNM-1097 DATE 5/22/8]

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CHAPTER 17 II-17.1 7/25/83 i

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LICENSE SNM-1097 DATE 5/22/37 PAGE j

DOCKET 70-1113 REVISION 16

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12 -

. CHAPTER 1 S,TANDARD COND.ITIONS AND SPECIAL AUTHORIZATIONS 1.1 CORPORATE & FINANCIAL INFORitATION This licensing information document is filed by the i

Nuclear Fuel & Component Manuf acturing f acility of the General Electric Company, a New York corporation with a principal place of business at Schenectady, New York.

1.2 LOCA, TION & GENERAL DESCRIPTION OF WILMINGTON PLANT l

The General Electric Company, Nuclear Fuel & Components Manufraturing (NF&CM) operates a nuclear fuel fabrication plant in Wilmington, North Carolir.a.

At this site, NF&CM occupies buildings for administrative, laboratcry and manuf acturing activitiec.

Fuel manuf acturing activities are conducted within the Fuel Manuf acturing area.

The f ull address is as follows:

General Electric Company, Nuclear Fuel & Components Manufacturing, ( nanie of person and mail code),

P.

O. Box 780, Nilming ton,, NC 08402.

l 1.3 LICENSE NUMBER The General Electric Compar'y Nuclear Fuel & Components Manufacturing NRC license number is SNM-1097 (Docket 70-1 1 1 11 :-=

LlCENSE SNM-1097 DATE 5/22/87 PAGE I

D0CKET 70-1113 REVISION 16 I-1.1

1 i

l In accordance wi,th the GE timely renewal request dated I

4/28/81 and subsequent, related submittals, General Electric hereby requests license renewal for a five year period commencing from the time that the Nuclear l

Regulatory Commission completes final action on this I

matter.

1 I

1.4 POSSESSION _ LIMITS 1

The following types, quantities, and forms of special l

nuclear materials are authorized:

1.4.1 Uranium-235, 50,000 kg s total Contained in uraniwn to a maximum, nominal enrichment.of G% in the form of UF6, 00 2,, U 08 and other solid and 3

liquid process intercrediates and products characteristic of LZU fuel fabrication and fuel fabrication development activities.

1.4.2 Uranium-235, 350 grams total In any form contained in uranium at any enrichment, for use in measurements, detection, research or development.

1.4.3 Uranium-235, 500 kg s Total i

i In any form, contained in uranium at a maximu:a nominal enrichment of 15% for use in laboratory and process technology development operations.

LICENSE SNM-1097 DATE 5/22/87 PAGE

. DOCKET 70-1113 REVISION 16 I-1.2 l

o 1.4.4 Plutonium I

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1 milligram in samples for analytical purposes 1 milligram as staridards for checking the alpha l

radiation respoitse of radiation detection l

instr umentation.

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20 grams as sealed neutron sources In nuclear fuel rods containing not more than 10-6 grams I

of plutonium per gram of U235,

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1.5 MATERIAL USE LOCATIONS Uranium normally will be used at the Wilming ton site in the Puel Manufacturing Area only.

Conversion and fabrication of SNM is conducted within the Puel Manuf acturing building.

Small quantitlen (i.e., less than one safe oatch of j

uranium in a non-dispensable form) may be temporarily f

moved to other buildings or site locations for special I

tests.

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1 1.6 DEFINITIONS Definitions as used in the license conditions are set forth below.

J LICENSE SNM-1097 DATE 5/22/87 PAGE l

DOCKET 70-1113 REVISION 16 I-1.3 i

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1.6.1 Area Manager - The manager designated by the Wilmington facility Manager who is responsible for implementation of nucleat safety requirements in the area assigned.

The general title " Area Manager" does not necessarily refer to the title of any specific position in the General Electric system of organization and position nomenclature, i

i 1.6.2 Array - means two or more interacting accumulations of fissile material.

I 1.6.3 Criticality control - means the administrative and technical requirements established to minimize the I

possibility of achieving inadver tent criticality in the environment analyzed, j

I 1.6.4 Full Reflection - means the degree of reflection 1

equivalent to a tight fitting shell of 12 inches or more l

l of water.

1.6.5 Minimal Reflection - means the degree of reflection equivalent to a cloce-fitting shell of water, steel, al umin um, nickel or copper not greater than 1/8 inch in thickness.

1.6.6 Minimum Critical Dimension - means the smallest j

dimension which constitutes a critical system for a given geometry under conditions of full reflection and optimum moderation.

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l 1.6.7 Nominal U235 Enric hme nt - means the value of enrichment 1

aasigned to a quantity of material for convenience i

i LICENSE SNM-1097 DATE 5/22/87 PAGE i

DOCKET 70-1113 REVISION 16 I-1.4 1

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because the prec_ise value is not known due to process or measurement uncertainties.

1.6.8 Nuclear Safety - means both criticality and radiation safety.

1.6.9 Safe Batch - means an accumulation of special nuclear material which is 45% of the critical accumulation for U235 enrichments less than or equal to 6% and 33 1/3% of the critical accumulation for U235 enrichments greater than 6%, considering enrichment, full reflection, and optimum water moderation for the specific material form.

l 1.7 AUTHORIZED ACTIVITIES This application requests authorization to receive,.

possess, use, store and ship authorized special nuclear materials pursuant to 10 CFR Parts 70, 71,.73, 74 and 75.

1.7.1 Product Processing Operations

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1.7.1.1 UF6 Conversion - Conversion of uranium hexafluoride to j

uranium ox ides.

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1.7.1.2 Fuel Manufacture - Fabrication of nuclear reactor fuels l

1 containing uranium.

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I LICENSE SNM-1097 DATE 5/22/87 PAGE DOCKET 70-1113_

REVISION 16 I-1.5 I

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1.7.1.3 Scrap Recovery,

Reproc'essing of unirradiated scrap from NF&CM and from other sources with nuclear safety characteristics identical to NF&CM in-process materials.

i 1.7.2 Process Technology Operations 1.7.2.1 Development and f abrication of reactor fuel, fuel elements and fuel assemblies in small amounts or of advanced design.

1.7.2.2 Development of scrap recovery processes i

I 1.7.2.3 Determination of interaction between fuel additives and fuel materials.

I 1.7.2.4 Chemical analysis and material testing, including l

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

1.7.2.5 Ins tr ument research and calibration, including development, calibration and functional testing of nuclear instrumentation and measuring devices.

1.7.2.6 Other process technology development activities rela,ted to, but not limited by, the above.

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

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LICENSE SNM-1097 DATE 5/22/87 PAGE DOCKET 70-1113 REVISION 16 I-1.6

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'.7.4 General Services Operations 1

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1.7.4.1 Storage of unirradiated fuel assemblies, uranium j

compounds and mixtures in areas arranged specifically for maintenance of criticality and radiological safety.

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1.7.4.2 Design, f abrication and testing of uranium prototype processing equipment.

1.7.4.3 Maintenance and ' repair of uranium processing equipment and auxiliary systems.

1.7.4.4 Storage and nondestructive testing of fuel rods containing small amounts of plutonium.

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1.7.5 Waste Treatment and Disposal l

1.7.5.1 Treatment, storage and disposal and/or shipnent of I

liquid and solid wastes whose discharges are regulated.

l 1.7.5.2 Decontamination of non-combustible contaminated wastes to reduce uranium contamination levels, and subsequent l

shipment of such low-level radioactive wastes to licensed burial sites for disposal.

l 1.7.5.3 Treatment or disposal of combustible waste and scrap material by incineration pursuant to 10 CPR 20.302(a) l and 10 CPR 20.305.

1.7.6 Of f site Ac tiv ities Non-destructive modification, testing, demonstration and storage of materials and de stees containing unirradiated 5/2E/8,'1 PAGE l

LICENSE SNM-1097 DATE 1

DOCKET 70-1113 REVISION 16 I-1.7 l

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1 uranium, prov ided that such materials and devices shall be in General Electric control at all times.

l 1.8 EXEMPTIONS & SPECIAL AUTHORIZATIONS 1.8.1 Requirements for Prior Authorization of Activities by License Amendment Prior authorization by license amendment shall be required for the following activities:

l 1.8.1.1 Major changes or additions to existing processes which may involve a significant increase in potential or actual environmental impact resulting from utilizing l

such changes or additions.

1.8.1.2 Major process changes or additions which involve a new process techno' logy for which a criticality safety demonstration has not been previously submitted to the I

Commis s ion.

In det'ermining whether a new process technology requires such prior authorization by license amendment, the following f actors will be considered:

(1) type of equipment utilized, (2) chemical reactions involved and (3) potential and/or actual environmental impact.

1.8.1.3 Proposed activities for which specific application and prior approval are required by Commission regulations.

LICENSE SNM-1097 DATE 5/22/87 PAGE DOCKET 70-1113 REVISION 16 I-1.8

1.8.2 Contamination-Free Articles See " Annex A, Guidelines for Decontamination of Facilities & Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or l

t Special Nuclear Material," US NRC, 12/30/82, pages I-l 1.18 through I-1,21.

I 1.8.3 Disposal of Contamination-Free Liquids 1.8.3.1 Hydrogen Fluoride Solutions i

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Authorization, pursuant to 10 CPR 70.4 2( b) (3 ), to transfer liquid hydrofluoric acid to Brush Wellman,

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Elmore, Ohio, through the chemical supplier, Consolidated Chemical Company, Kansas City, Missouri, without either company possessing a NRC or Agreement y

State license for special nuclear material, provided that the concentration of uranium does not exceed three j

parts per million by weight of the liquid and the i

nominal enrichment does not exceed 6%.

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l The hydrofluoric acid is transferred and used in such a manner that the minute quantity of uranium does not f

enter into any food, beverage, cosmetic, drug or oth,er commodity designated for ingestion or inhalation by, or application to, a human being such that the uranium l

concentration in these items would exceed that which i

naturally exists.

Add i tionally, the acid is us ed in a process which will not release the low levels of I

radioactivity to the atmosphere as airborne material and whose residues will remain in a lagoon system.

i LICENSE SNM-1097 DATE 5/22/87 PAGE j

DOCKET 70-1113 REVISION 16 j

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Prior to shipmen,t, each transfer is-sampled and measured to assure that the concentration does not exceed ' three -

parts - per. million of uranium.

.l General Electric shall maintain records.under this

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condition of. license including, as a minimum, the'date, uranium concentration and quantity of all hydrofluoric

. acid transferred.

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l 1.8.3.2 Nitrate-Bearing Liquids Authorization, pursuant to 10 CFR 20.302( a), to dispose of 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 nominal enrichment does not exceed 6 weight percent j

U235, by transport to an offsite liquid-treatment system located at Federal Paper Board Corporation, Riegelwood, North Carolina, in which decomposition of the nitrates will occur and from which the denitrified liquids will be discharged in the effluent from the system.

The environmental monitoring program' as described in Section 5.1.4.2 is used to control these activities.

1.8.4 Use of Materials at Of f-Site Locations l

1.8.4.1 Authorization to use up to 15 grams of U235 at other

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sites within the limits of the United States and at temporary job sites of the licensee anywhere in the United States where the Nuclear Regulatory Commission maintains jurisdiction for regulating the use of licensed material.

LICENSE SNM-1097 DATE 5/22/87 PAGE DOCKET 70-1113 REVISION 16 I-1.10 l

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The manager of the radiation safety function shall establish the safety criteria.for material being used at offsite locations.

It is also his responsibility to.

designate the individual who will be responsible to carry out these criteria.

1.8.4.2 Authorization to store at nuclear reactor sites, uranium fully packaged as for transport in any Fissile C1' ass I l

package,- in accordance with the conditions of a. license authorizing delivery of such containers to a carrier for Fissile Class I transport, at locations in the United States providing such' locations are controlled by the General Electric Company, with provision to minimize the severity of potential accident conditions to be no greater.than those in-the-design bases for the containers during transportation.,

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Provisions for compliance with applicable.10 CFR 7,3 requirements.are described'in the NRC-approved General Electric Company, Nuclear Fuel & Components Manuf acturing, Wilmington, N.

C.,

Physical Security Plan dated October 26, 1981, as currently revised in-l accordance with regulatory provisions.

Storage at nuclear reactor sites is subject to the financial protection and indemnity provision of 10 CFR l

i 140 and is limited to possessicn for urposes of e

delivery to a carrier for transport.

The requirements of 10 CFR 70.24 are waived insofar as this section applies to the materials contained in Fissile Class I packages.

LICENSE SNM-1097

DATE, 5/22/87 PAGE l

DOCKET 70-1113 REVISION 16 I-1.11 1

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3 1.8.4.3 Authorization to, store at nuclear reactor sites, arrays -

of finished reactor fuel rods'and/or assemblies in any of the inner metal containers of the RA-series shipping package described in package certificate USA /4986/AF, at

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locations in the United States providing. such locations are controlled by the General Electric Company' 'with provision to minimize the severity of potential accident conditions to. be no greater than those in the design i

bases for the containers during transportation.

Arrays.can be constructed without limit to the number of containers so stored, except that each array shall be stacked to a height of no more than 4 containers high with each container separated by nominal 2 inch wooden I

studs, and with the width and length for each array and separation between arrays determined only by container' l

handling requirements.

Provisions for compliance with applicable 10 CFR 73 requirements are described in the NRC-approved GE-NF&CM Physical Security Plan dated October 26, 1981, as l

currently revised in accordance with regulatory provisions.

Storage at nuclear reactor sites is subject to the financial protection and indemnity provision of 10 CPR 140 and is limited to possession for purposes of delivery to a carrier for transport.

The requirements of 10 CFR 70.24 are waived insof ar as this section applies to the materials contained in any of the inner LICENSE SNM-1097 DATE 5/22/87 PAGE DOCKET 70-1113 REVISION 16 I-1.12

1 metal containers, of the RA-series shipping package.

j

( Reference Section 1.8.7).

i 1.8.4.4 Authorization to transfer,. possess, use and store unirradiated reactor fuel of General Electric Company i

manufacture at nuclear. reactor sites, for purposes of inspection, fuel bundle disassembly and assembly, including fuel rod replacement, provided that the i

following conditions are met.

l 1.8.4.4.1 A valid NRC license has been issued to the reactor licensee, which authorizes receipt, possession and I

storage of the fuel at the reactor site, and that General Electric Company possesses the fuel only within the indemnified location.

I 1.8.4.4.2 Not more than one f uel assembly and 30 unassembled fuel l

l rods of the types described in NRC Certificate of l

Compliance USA /4986/AF, are possessed.by General Electric Company at any one reactor site at any one time, except when the f uel has been packaged for l-I transport.

1.8.4.4.3 All operations involving the fuel are conducted by or under the direct supervision of a member of the General Electric staf f who shall be responsible for all work, on the fuel element assembly.

The person shall be knowledgeable and shall have access to all applicable procedures and license conditions at the reactor site and the appropriate actions that are to be taken in the event of emergencies at the site.

LICENSE SNM-1097 DATE 5/22/87 PAGE DOCKET 70-1113 REVISION 16 I-1,13 l

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l

e 1.8.4.4.4 All operations ipvolving the fuel are conducted in locations that have been selected to preclude mechanical damage and flooding.

1 1.8.4.4.5 Loose rods are stored only in RA-series inner metal c

l containers.

1 l

1.8.4.4.6 Fuel is handled in accordance with pertinent prov isions I

I of the reactor license and in accordance with written j

and approved General Electric Company procedures.

The i

procedures shall define the radiation and contamination f

surveys that are to be performed and the frequency of the surveys.

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l 1.8.4.4.7 Written administrative procedures are jointly prepared and approved by General Electric and the reactor licensee, to provide for the nuclear and radiation safety of the operations to be performed.

j 1.8.4.4.8 Records of the operation, including evaluations,

l procedures used, audits performed, and performance reports are maintained at the Wilming ton, North Carolina, plant.

1.8.5 Disposal of Industrial Waste Treatment Products

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Notwithstanding any requirements for state or local i

government agency disposal permits, General Electric is authorized to dispose of industrial waste treatment products without continuing NRC controls provided that i

either of the two following conditions are met:

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LICENSE SNM-1097 DATE 5/22/87 PAGE DOCKET 70-1113 REVISION 16 I-1.14 1

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1.8.5.1 All freestanding liquid shall be removed prior to shipment.

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

1 The licensee shal] possess authorization from

)

appropriate state officials prior to disposing of the waste material delineated in this amendment.

The l

authorization shall be available for inspection at the l

Wilmington f acility.

1 1.8.5.2 The uranium concentration in the material shipped for disposal only at the RCRA hazardous waste burial facility in Pinewood, S.

C.

(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 gre. :

i shall be soluble.

The minimum. burial depth shall be at least four feet below the surface.

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1.8.6 Dilution Factor for Airborne Effluents I

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Authorization to utilize a dilution f actor to the measured stack discharges for the purpose of evaluating the airborne radioactivity at the closest site boundary of' stack discharges from the uranium processing f acilities.

For purposes of control, this dilution l

factor shall be no greater than 100.

For other l

purposes, specific dilution f actors, which consider dispersion model parameters, may be calculated and used.

LICENSE SNM-1097 DATE 5/22/87 PAGE DOCKET 70-1113 REVISION 16 I-1.15 l

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1.8.7 Monitor System Exemption i

l Authorization for exemption from the requirements of l

1 10 CFR 70.24 for each area in which there is' not more than:

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, er equal to or less than 75% of a minimum critical k

l number under conditions in which double batching is not credible, or l

l The number and type of finished reactor fuel rods j

and/or assemblies authorized for delivery to a carrier for transport as a Fissile Class I shipment l

in the model RA-series shipping package described in

)

package certificate USA /4986/AF, without limit on the l

number of such stored containers, provided the storage locations preclude mechanical damage and flooding, or The quantity of ur,anium authorized for delivery to a carrier for transport as a Fissile Class I package 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 LICENSE SNM-109,7 DATE 5/22/87 PAGE DOCKET 70-1113 REVISION 16 I-1.16

Arrays of finished reactor fuel rods and/or l

assemblies in any.of the -inner metal containers of the RA-series shipping package described in package

]

certificate USA /4986/AF, under storage conditions described.in Chapter 1.8.4.3.

1.8.8 Incinerator Operation 1

1 Authorization, pursuant' to 10 CFR 20.302(a) and 10 CFR 20.305, to treat or dispose.of waste and scrap material containing special nuclear -material by incineration.

1.8.9 Posting l

I Por those areas within the Controlled Access Area in which radioactive materials are processed, used, or l

stored, where it is deemed impractical to label individual containers pursuant to 10 CFR 20.203(f), a sign stating "Every container in this area may contain radioactive material" shall be posted.

LICENSE SNM-1097 DATE 5/22/87 PAGE DOCKET 70-1113 REVISION.

'16 I-1.17 i

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DEC U 01982 ANNEX A GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE l

OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE, j

OR SPECIAL NUCLEAR MATERIAL I

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U. S. Nuclear Regulatory Com;nission Division of Fuel Cycle and Material Safety Washington, D.C.

20555 July 1982 9

LICENSE SNM-1097 DATE 5/22/87 PAGE j

DOCKET 70-1113 REVISION 16 I-1.18

I j

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 lim:ts in Table 1 do not apply to premises, equipment, or scrap containing induced radio-activity for which the radiological considerations pertinent to their use may be differ,ent. 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 residt.al 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 ce 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!contam-l ination at these locations is likely to be representative of contamination on the interior of the pipes, drain lines, or ductwork.

Surfaces of premises, equipment, c 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 l

the limits.

4.

Up:n request, the Comission 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 cf 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 l

the premises, equipment or scrap, are unlikely to result in an j

unreasonable risk to the health and safety of the public.

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LICENSE SNM-1097 DATE 5/22/87 PAGE i

l DOCKET 70-1113 REVISION 16 I-1.19 l

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l 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 and Material Safety, USNRC, Washington, D.C.

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 l

of abandonment. The survey report shall:

a.

Identify the premises.

b.

Show that reasonable effort has been made to eliminate

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residual contamination.

c.

Describe the scope of the survey and general procedures followed.

d.

State the findings of the survey in vr.its specified in the instruction.

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

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t' 1

l LICENSE SNM-1097 DATE 5/22/87 PAGE I

DOCKET 70-1113 REVISION 16 I-1.20 i

s

• e j

mus. e ACCIPTABLE SUR' FACE CONTAAINAfl0N LCVEL5 huCL10[5*

AV[RACEbCf MAllMUMbdf R[MOVADLEbef J nat U 235. U 230

a. d 2

associated occay products 5,000 dpm e/100 ce 15,000 dpa e/10 cm*

1,000 dpa e/100 cm2 Iransuranics, Ra-226. Ra 228, in 230. Th 228, pa-231, 100 dpm/100 cm2 300 dpm/100 ca.I 20 dpe/100 cm2 Ac.222,1-125.1 129 th-nat. Th 232, 3r-90, I

Ha-223. Ra 224 U-232,1 126, 10M.us/100 cm2 3000Jpm/100 cm2 200 dpa/100 cm2 l*13I, 1-133 Deta gava emitters (nuclides with decay rodes other than I

alcLa emisstan or spontaneous 5000 dpm pr/100 cm2 15.000 dpa sy/100 cm2 1000 dpa pr/100 cm2 i

fisston) encept $r-90 and i

others nated above.

a nere ssrf ace contamination by both alpha-and beta-gamma-emitting nuclides exists, the limits established for alpha-and beta-gama emitting etclides should apply independently.

DAs used in this table, dom (disintegrations per minute) means the rate of emission by radioactive material as cetermined by correcting the counts per minute observed by an appropriate detector for background, ef ficiency, and geometr'ic factors associated with the instrumentation.

CMaasurements of average contaminant should not be averaged over more than I $4uare meter, for objects of less surface area, the aorage snevid be cerived for eaca sucn object.

d ng,j,:,um contamination level applies to an area of not more than 100 cm2 i

'ibe amount of removable radioactive material per 100 4,m2 of surface area should be determined by wiping that area with dry filter or soft l

esorbent taper. applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of q

kra.,n ef f iciency. knen removatile contamination on objects of less surface area is determined, the pertinent levels should be reduced pr portionally and tre entire swrface should be wiped.

o f lhe average and swalmum radiation levels associated with suiface contamination resulttag from beta-gama emitters should not esceed 0.2 mead /hr at I cm and 1.0 mrad /hr at I cm. respectively, meas'ured through not more than 7 ellligrams per sqaare centimeter of i

total absorter.

LICENSE SNM-1097 DATE 5/22/87 FAGE DOCKET 70-1113 REVISION 16 I-1.21 i

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