ML20203Q014
| ML20203Q014 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 03/26/1986 |
| From: | GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20203Q012 | List: |
| References | |
| NUDOCS 8605080521 | |
| Download: ML20203Q014 (29) | |
Text
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GENER AL $ ELECTRIC Director - ONMSS March 26, 1986 ATTACHMENT 2 REVISION 14 DATED 3/26/86 J
TO PART I OF APPLICATION APPROVED BY CONDITION 9 OF NRC LICENSE SNM-1097, DOCKET #70-1113 1
TPW:bsd 8605080521 860326 PDR ADOCK 07001113 PDR
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REVISIONS BY PAGE Ef'fective Effective Effective ~
Page Date Page Date
,Page Date TABLE OF CONTENTS CHAPTER 2 I-3.11 3/14/84-I-3.12 1
10/23/84 I-2.1 5/14/84 I-3.13 2
d I-2.2
'I-3.14 3
I-2.3 I-3.15 4
I-2.4 I-3.16 5
I-2.5 I-3.17 6
I-2.6 I-3.18 7
3/26/86 I-2.7 I-3.19 8
I-2.8 I-3.20 I-2.9 I-3.21 9
I-2.10 I-3.22 10 I-2.11 I-3.23 11 I-2.12 I-3.24 12 I-2.13 I-3.25 I-2.14 I-3.26 PART I I-2.15 I-3.27 I-2.16
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I-2.17 CHAPTER 1 I-2.18
'i I-2.19 CHAPTER 4 I-1.1 3/26/86 I-2.1; I-1.2 I-2.21 I-4.1 10/23/84 I-1.3 I-2.22 I-4.2 I-1.4 I-2.23 I-4.3 l
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I-2.24 I-4.4 i
I-4.5 1
CHAPTER 3 I-4.6 I-1.8 I-4.7-I-1.9 I-3.1 5/14/84 I-4.8 I-1.10 I-3.2 I-4.9 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 I-1.15 I-3.7 I-4.14 I-1.16 I-3.8 I-4.15 I-1.17 I-3.9 I-4.16 I-1.18 I-3.10 I-4.17 I-1.19 I-4.18 I-1.20 I-4.19 1
4 I-1.21 i
LICENSE SNM-1097 DATE 3/26/86 PAGE DOCKET 7 0 -1 1 i l,_
REVISION 14,
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REVISIONS BY PAGE t
Effective Effective Effective Page Date Page Date Page Date i
I-4.20 11/12/84 CHAPTER _6 I-4.21 11/20/84 I-4.22 I-6.1 6/20/84 I-4.23 I-4.24 I-4.25 I-4.26 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
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I-8.1 3/26/86 I-5.5 I-5.6 I-5.7 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
I-5.17 5/14/84 4
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
I-5.27 I-5.28 LICENSE SNM-1097 DATE 3/26/86 PAGE DOCKET 70-1113 REVISION 14 ;
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REVISIONS BY PAGE Ef'fective Effective Effective Page Date Page Date Page Date II-10.22.7/25/83 II-11.15 7/25/83 PART II II-10.23 II-11.16 II-10.24 II-11.17 II-10.25 II-11.18 CHAPTER 9 II-10.26 II-11.19 II-10.27 II-11.20 II-9.1 7/25/83 II-10.28 II-11.21 II-9.2 II-10.29 II-11.22 II-9.3 II-10.30 II-11.23 II-9.4 II-10.31 II-11.24 II-9.5 II-10.32 II-11.25 II-9.6 II-10.33 II-11.26 3
II-9.7 II-10.34 II-11.27 II-9.8 II-10.35 II-11.28 II-10.36 II-11.29 II-10.37 II-11.30 j
CHAPTER 10 II-10.38 II-11.31 II-10.39 II-11.32 II-10.1 7/25/83 II-10.40 II-11.33 II-10.2 II-10.41 II-11.34 II-10.3 II-10.42 II-11.35 II-10.4 II-11.36 II-10.5 II-11.37 II-10.6 CHAPTER 11 II-11.38 II-10.7 II-11.39 II-10.8 II-11.1 7/25/83 II-11.40 II-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 II-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-li.48 II-10.17 II-11.10 II-11.49 II-10.18 II-11.11 II-11.50 II-10.19 II-11.12 II-11.51 II-10.20 II-11.13 II-11.52 II-10.21 II-11.14 II-11.53 LICENSE SNM-1097 DATE 3/26/86 PAGE DOCKET 70-1113 REVISION 14 - -
1 REVISIONS BY PAGE Effective Effective Effective Page Date Page Date Page Date,
II-11.54 7/25/83 II-13.10 7/25/83 II-13.49 7/25/83 II-11.55 II-13.11 II-13.50 II-11.56 II-13.12 II-13.51 II-13.13 II-13.52 II-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.
l 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-12.10 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 II-12.14 II-13.30 II-13.69 II-12.15 II-13.31 II-13.70 II-12.16 II-13.32 II-13.71 II-12.17 II-13.33 II-13.72 II-12.18 II-13.34 II-13.73 II-12.19 II-13.35 II-13.74 II-13.36 II-13.75 II-13.37 II-13.76 CHAPTER 13 II-13.38 II-13.77 II-13.39 II-13.78 II-13.1 7/25/83 II-13.40 II-13.79 II-13.2 II-13.41 II-13.80 II-13.3 II-13.42 II-13.81 II-13.4 II-13.43 II-13.82 II-13.5 II-13.44 II-13.93 II-13.6 II-13.45 II-13.84 II-13.7 II-13.46 II-13.85 II-13.8 II-13.47 II-13.86 II-13.9 II-13.48 II-13.87 LICENSE SNM-1097 DATE 3/26/86 PAGE DOCKET 70-1113 REVISION 14 10 -
1 REVISIONS BY PAGE Effective Effective Effective Page Date
,Page Date Page Date II-13.88 7/25/83 II-15.27 9/30/83 II-1,6.15 9/30/83 II-13.89 II-15.28 II-16.16 II-13.90 II-15.29 II-16 17 II-13.91 II-15.30 II-16.18 II-15.31 II-16.19 II-15.32 II-16.20 CHAPTER 14 II-15.33 II-16.21 II-15.34 II-16.22 II-14.1 7/25/83 II-15.35 II-16.23 II-15.36 II-16.24 II-15.37 II-16.25 CHAPTER 15 II-15.38 II-16.26 II,15.39 II-16.27 II-15.1 9/30/83 II-15.40 II-16.28 II-15.2 II-15.41 II-16.29 II-15.3 II-15.42 II-16.30 II-15.4 II-15.43 II-16.31 II-15.5 II-15.44 II-16.32 II-15.6 II-15.45 II-16.33 II-15.7 II-15.46 II-16.34 II-15.8 II-15.47 II-16.35 II-15.9 II-16.36 II-15.10 II-16.37 II-15.11 CHAPTER 16
.II-16.38 II-15.12 II-16.39 II-15.13 II-16.1 9/30/83 II-16.40 II-15.14 II-16.2 II-16.41 II-15.15 II-16.3 II-16.42 II-15.16 II-16.4 II-16.43 II-15.17 -
II-16.5 II-16.44 II-15.18 II-16.6 II-16.45 II-15.19 II-16.7 II-16.46 II-15.20 II-16.8 II-16.47 II-15.21 II-16.9 II-16.48 II-15.22 II-16.10 II-16.49 II-15.23 II-16.11 II-16.50 II-15.24 II-16.12 II-16.51 II-15.25 II-16.13 II-16.52 II-15.26 II-16.14 II-16.53 LICENSE SNM-1097 DATE 3/26/86 PAGE DOCKET 70-1113 REVISION 14 11 -
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Effective Effective Effective Page Date Page Date Page_
Date II-16.54 9/30/83 II-16.55 II-16.56 II-16.57 II-16.58 II-16.59 II-16.60 II-16.61 II-16.62 II-16.63 II-16.64 II-16.65 II-16.66 II-16.67 II-16.68 II-16.69 II-16.70 II-16.71 II-16.72 II-16.73 CHAPTER 17 II-17.1 7/25/83 1
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l LICENSE SNM-1097 DATE 3/26/86 PAGE DOCKET 70-1113 REVISION 14 12 -
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l CHAPTER 1 STANDARD CONDITIONS AND SPECIAL ' AUTHORIZATIONS 1.1 CORPORATE & FINANCIAL INFORMATION This licensing information document is filed by the Nuclear Fuel & Component Manufacturing facility of the General Electric Company, a New York corporation with a principal place of business at Schenectady, New York.
1.2 LOCATION & GENERAL DESCRIPTION OF WILMINGTON PLANT The General Electric Company, Nuclear Fuel & Components Manufacturing (NF&CM) operates a nuclear fuel fabrication plant in Wilmington, North Carolina.
At this site, NF&CM occupies buildings for administrative, laboratory and manufacturing activities.
Fuel manufacturing activities are conducted within the Fuel Manufacturing area.
The full address is as follows:
General Electric Company, Nuclear Fuel & Components Manufacturing, (name of person and mail code),
P. O. Dox 780, Wilmington, NC 28402.
1.3 LICENSE NUMBER The General Electric Company Nuclear Fuel & Components Manufacturing NRC license number is SNM-1097 (Docket 70-1113).
LICENSE SNM-1097 DATE 3/26/86 PAGE DOCKET 70-1113 REVISION 14 y_),)
In accordance with the.GE timely renewal request dated 4/28/81 and subsequent, related submittals, General Electric hereby requests license renewal for a five year period commencing from the time tht? the Nuclear Regulatory Commission completes final action on this i
matter.
4 1.4 POSSESSION LIMITS l
The following types, quantities, and forms of special i
nuclear materials are authorized:
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1.4.1 Uranium'235, 50,000 kgs total 4
Contained in uranium to a maximum, nominal enrichment of 6% in the form of UF 00 UO and other solid and 6,
2, 3 g l
liquid process intermediates and products characteristic of LEU fuel fabrication and fuel fabrication development activities.
1.4.2 Uranium-235, 350 grams total a
In any form contained in uranium at any enrichment, for use in measurements, detection, research or development.
j 1.4.3 Uranium-235, 500 k,s Total In any form, contained in uranium at a maximum nominal enrichment of 15% for use in laboratory and process technology development operations.
LICENSE SNM-1097 DATE 3/26/86 PAGE 3
j DOCKET 70-1113 REVISION 14 1-1.2 i
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o 1.4.4 Plutonium 1 milligram in samples for analytical purposes 1 milligram as standards for checking the alpha radiation response of radiation detection instrumentation.
20 grams as sealed neutron sources In nuclear fuel rods containing not more than 10- 6 grams of plutonium per gram of U 235, 1.5 MATERIAL USE LOCATIONS Uranium normally will be used at the Wilmington cite in the Fuel Manufacturing Area only.
Conversion and fabrication of SNM is conducted within the Fuel Manufacturing building.
Small quantities (i.e.,
less than one safe batch of uranium in a non-dispersable form) may be temporarily moved to other buildings or site locations for special tests.
1.6 DEFINITIONS Definitions as used in the license conditions are set forth below.
LICENSE SNM-1097 DATE 3/26/86 PAGE DOCKET 70-1113 REVISION 14 I-1.3
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1.6.1 Area Manager - The manager designated by the Department General Manager who is responsible for implementation of I
nuclear safety requirements in the area assigned.
The ge'neral title " Area Manager" does not necessarily refer j.
to the title of any specific position in the General l
Electric system of organization and position nomenclature.
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1.6.2 Array - means two or more interacting accumulations of fissile material.
l 1.6.3 Criticality Control - means the administrative and 4
technical requirements established to minimize the i
possibility of achieving inadvertent criticality in the 1
l environment analyzed.
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j 1.6.4 Full Reflection - means the degree of reflection f
equivalent to a tight fitting shell of 12 inches or more of water.
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1.6.5 Minimal Reflection - means the degree of reflection 1
i equivalent to a close-fitting shell of water, steel, a
l aluminum, nickel or copper not greater than.1/8 inch in j
thickness.
l 1.6;6 Minimum Critical Dimension - means the smallest dimension which constitutes.a critical system for a i
given geon,$try under conditions of full reflection ~ and optimum moderation.
I 1.6.7 Nominal U 235 Enrichment - means the value of enrichment i
assigned to a quantity of material for convenience LICENSE.
.DATE 3/26/86 PAGE t
DOCKET 70-1113 REVISION 14 y_j,4 i
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because the precise value is not known due to process or measurement uncertainties.
t 1.6.8 Nuclear Safety - means both criticality and radiation safety.
I 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 (f 23 5 enrichments greater Man 6%, considering enrichment, full reflection, and optimum water moderation for the specific material form.
i 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 and 73.
i 1.7.1 Product Processing Operations 1.7.1.1 UF Conversion - Conversion of uranium hexafluoride to 6
uranium oxides.
i 1.7.1.2 Fuel Manufacture - Fabrication of nuclear reactor fuels containing uranium.
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1.7.1.3 Scrap Recovery -
Reprocessing of unirradiated scrap from NF&CM and from other sources with nuclear safety characteristics identical to NF&CM in-process materials.
LICENSE SNM-1097 DATE 3/26/86 PAGE DOCKET 70-1113 REVISION 14 I-1.5
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1 1.7.2 Process Technology Operations 1.7.2.1 Development and fabrication of reactor fuel, fuel el'ements and fuel assemblies in small amounts or of advanced design.
1.7.2.2 Development of scrap recovery processes 1.7.2.3 Determination of interaction between~ fuel additives and fuel materials.
1.7.2.4 Chemical analysis and material testing, including i
physical and chemical testing and analysis, metallurgical examination and radiography of uranium compounds, alloys and mixtures.
i 1.7.2.5 Instrument research and calibration, including development, calibration and functional testing of nuclear instrumentation and measuring devices.
1.7.2.6 Other process technology development activities related 3
to, but not limited by, the above.
j 1.7.3 Laboratory Operations Chemical, physical or metallurg. cal analysis and testing of uranium compounds and mixtures, including but not limited to, preparation of laboratory standards.
I LICENSE SNM-1097 DATE 3/26/86 PAGE DOCKET 70-1113 REVISION 14 I-1.6
1.7.4 General Services Operations 1.7.4.1 Storage of unirradiated fuel assemblies, uranium compounds and mixtures in areas arranged specifically for maintenance of criticality and radiological safety.
1.7.4.2 Design, fabrication 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.
1.7.5 Waste Treatment and Disposal 1.7.5.1 Treatment, storage and disposal and/or shipment of liquid and solid wastes whose discharges are regulated.
1.7.5.2 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.
1.7.5.3 Treatment or disposal of combustible waste and scrap material by incineration pursuant to 10 CPR 20.302(a) and 10 CFR 20.305.
1.7.6 Offsite Activities l
Non-destructive modification, testing, demonstration and storage of materials and devices containing unirradiated LICENSE SNM-1097 DATE 3/26/86 PAGE DOCKET 70-1113 REVISION 14 y_),7
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uranium, provided that such materials and devices shall be in General Electric control at all times.
1.8 EXEMPTIONS & SPECIAL AUTHORIZATIONS 1.8.1 Requirements for Prior Authorization of Activities iy License Amendment Prior authorization by license amendment shall be required for the following activities:
i 1.8.1.1 Major changes or additions to existing processes 661ch may involve a significant increase in potential or actual environmental impact resulting from utilizing i
such changes or additions.
1.8.1.2 Major process changes or additions which involve a new process technology for which a criticality safety demonstration has not been previously submitted to the Commission.
In determining whether a new process technology requires such prior authorization by license amendment, the following factors will be considered:
j (1) type of equip.nent utilized, (2) chemical reactions involved and (3) potential and/or actual environmental impact.
4 1.8.1.3 Proposed activities for which specific application and prior approval are required by Commission regulations.
LICENSE SNM-1097 DATE 3/26/86 PAGE DOCKET 70-1113 REVISION 14 I-1.8 4
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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 Special Nuclear Material," US NRC, 12/30/82, pages I-1.18 through I-1.21.
1.8.3
, Disposal of Contamination-Free Liquids 1.8.3.1 Hydrogen Fluoride Solutions Authorization, pursuant to 10 CFR 70.42(b)(3), to transfer liquid hydrofluoric acid to Brush Wellman, Elmore, Ohio, through the chemical supplier, Consolidated Chemical Company, Kansas City, Missouri, I
without either company possessing a 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 nominal enrichment does not exceed 6%.
i The hydrofluoric acid is transferred and used in such a manner that the minute quantity of uranium does not i
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 lagoon system.
LICENSE SNM-1097 DATE 3/26/86 PAGE DOCKET 70-1113 REVISION 14 I_1,9 s
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- o Prior to shipment, each transfer is sampled and measured to assure that the concentration does not exceed three parts per million of uranium.
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i General Electric shall maintain records under this j
condition of license including, as a minimum, the date, j
uranium concentration.and quantity of all hydrofluoric acid transferred.
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1.8.3.2 Nitrate-Bearing Liquids Authorization, pursuant to 10 CFR 20.302(a), to dispose-l of' nitrate-bearing liquids, provided that the uranium l
concentration does not exceed a-30-day. average of 5' l
parts per million by weight of the liquids and the I
nominal enrichment does not exceed.6 weight percent 1-U235, by transport to an offsite liquid treatment system 1
j located at Federal Paper Board Corporation, Riegelwood, North Carolina, in which decomposition of the nitrates l
will occur and from which the denitrified liquids will be discharged in the effluent from.the system.
i 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 Off-Site Locations j
1.8.4.1 Authorization to use up to 15 grams of U 2 3 5 at - other j
sites within the limits'of the United States and at temporary job sites of the licensee anywhere in the l
United States where the Nuclear Regulatory Commission maintains jurisdiction for regulating the use of j
licensed material.
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LICENSE SNM-1097 DATE 3/25/86 PAGE DOCKET 70-1113 REVISION 14 I-1.10 t
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The manager of the radiatio \\n safety function shall establish the safety criteria for material ~be,ing used at offsite locations.
It is alsc his responsibility to i
designate the individual who)will be responhible 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 Class I 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.
Provisions for compliance with applicable 10 CFR 73 requirements are described in the NRC-approved General Electric Company, Nuclear Fuel & Components Manufacturing, Wilmington, N.
C., Physical Security Plan dated October 26, 1981, as, currently revised in accordance with regulatory provisions.
Storage at nuclear reac' tor sites is subject to the financial protection and indemnity provision of 10 CFR 140 and is limited to possession for purposes of delivery to a carrier for transport.
The requirements of 10 CFR 70.24 are walved insofar as this section I
applies to the naterials contained in Fissile Class I packages.
I LICENSE SNM-1097 DATE 3/26/86 PAGE 4
DOCKET 70-1113 REVISION 14 7_j,jj 5
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 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.
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 studs, and with the width and length for each array and separation between arrays determined only by container i
handling requirements.
f 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 currently revised in accordance with regulatory provisions.
i Storage at nuclear reactor sites is subject to the financial protection and indemnity provision of 10 CPR i
140 and is limited to possession for purposes of delivery to a carrier for transport.
The requirements of 10 CPR 70.24 are waived insofar as this section applies to the materials contained in any of the inner i
LICENSE SNM-1097 DATE 3/26/86 PAGE I
DOCKET 70-1113 REVISION 14 I_t,12
metal containers of the RA-series shipping package.
(Reference Section 1.8.7).
1.8.4.4 Authorization to transfer, possess, use and store unirradiated reactor fuel of General Electric Company manufacture at nuclear reactor sites, for purposes of inspection, fuel bundle disassembly and assembly, including fuel rod replacement, provided thst the following conditions are met.
1.8.4.4.1 A valid NRC license has been issued to the reactor licensee, which authorizes receipt, possession and storage of the fuel at the reactor site, and that General Electric Company possesses the fuel only within the indemnified location.
1.8.4.4.2 Not more than one fuel assembly and 30 unassembled fuc1 rods of the types described in NRC Certificate of Compliance USA /4986/AF, are possessed by General Electric Company at any one reactor site at any one time, except when the fuel has been packaged for 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 staff 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.
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LICENSE SNM-1097 DATE 3/26/86 PAGE DOCKET 70-1113 REVISION 14 I-1.13
1.8.4.4.4 All operations involving the fuel are conducted in locations that have been selected to preclude mechanical damage and flooding.
1.8.4.4.5 Loose rods are stored only in RA-series inner metal containers.
1.8.4.4.6 Fuel is handled in accordance with pertinent provisions of the reactor license and in accordance with written and approved General Electric Company procedures.
The procedures shall define the radiation and contamination surveys that are to be performed and the frequency of the surveys.
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.
1.8.4.4.8 Records of2the operation, including evaluations, procedures used, audits performed, and performance reports are maintained at the Wilmington, North Carolina, plant.
1.8.5 Disposal of Industrial Waste Treatment Products Notwithstanding any requirements for state or local government agency disposal permits, General Electric is authorized to dispose of industrial waste treatment products without continuing NRC controls provided that either of the two folicwing conditions are met:
LICENSE SNM-1097 DATE 3/26/86 PAGE DOCKET 70-1113 REVISION 14 I_j,14
l 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.
The licensee shall possess authorization from appropriate state officials prior to disposing of the 1
waste material delineated in this amendment.
The authorization shall be available for inspection at the Wilmington facility.
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 gram shall be soluble.
The minimum burial depth shall be at least four feet below the surface.
1 1.8.6 Dilution Factor for Airborne Effluents Authorization to utilize a dilution factor 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 facilities.
For purposes of control, this dilution factor shall be no greater than 100.
For other purposes, specific dilution factors, which consider dispersion model parameters, may be calculated and used.
LICENSE SNM-1097 DATE 3/26/86 PAGE DOCKET 70-1113 REVISION 14 I-1.15
o 1.8.7 Monitor System Exemption
~ Authorization for exemption from the requirements of 10'CFR 70.24 for each area in which there is not more than:
A quantity of finished reactor fuel rods equal to or e
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 e
The number and type of finished reactor fuel rods and/or assemblies authorized for delivery to a carrier for transport as a Fissile Class I shipment in the model RA-series shipping package described in package certificate USA /4986/AF, without limit on the number of such stored containers, provided the storage locations preclude mechanical damage and flooding, or The quantity of uranium authorized for delivery to a o
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-1097 DATE 3/26/86 PAGE DOCKET 70-1113 REVISION 14 I-1.16 i
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, under storage conditions described in Chapter 1.8.4.3.
1.8.8 Incinerator Operation Authorization, pursuant to 10 CPR 20.302(a) and 10 CFR 20.305, to treat or dispose of waste and scrap material containing special nuclear material by incineration.
6 LICENSE SNM-1097 DATE 3/26/86 PAGE DOCKET 70-1113 REVISION 14 I-1.17 n
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DEC 3 01982 ANtlEX A GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION,0F LICENSES FOR BYPRODUCT, SOURCE,
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OR SPECIAL NUCLEAR PATERIAL
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Division of Fuel Cycle and Material Safety Washington, D.C.
2055S July 1982 LICENSE SNM-1097 DATE 3/26/86 PAGE DOCKET 70-1113 REVISION 14 I-1.18 n
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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 radio-activity for which the radiological considerations pertinent to their use may be different. The release of such facilities or items from regulatory contro'1 is considered on a casc-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 contam-ination at these l'ocations 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.
Upcn 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 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 3/26/86 PAGE DOCKET 70-1113 REVISION 14 y_j,j9
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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 of abandonment. The survey report shall:
a.
Identify the premises.
b.
Show that reason'able 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 units specified in the instruction.
Following review of the report, the NRC will consider visiting the facilities to eenfirm the survey.
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LICENSE SNM-1097 DATE 3/26/86 PAGE DOCKET 70-1113 REVISION 14 I-1.20
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ACCEPTA8tt SUATACE CONTAMINATION LEYtts Mtl'I5*
AVERAGEbcf MI!P!UPtbdf REMOVA8ttbef Q-mat. U-235. U-233 and associated cecay products 5.000 dpa e/100 cat 15.000 dpa e/100 cm2 1.DC w s/100 ce:2 Transuranics. Ra-226.24-228 Th-230.14 228, pa 231 100 dpe/100 cm2 300 dpe/100 cut 20 dpa/100 c.2 Ac-2U.1-125. 1 123 Th-eat. Th-232. 3r-93 f
aa 223. Ra-221. U-232.1 125 1000 dps/100 cm2 3000Jpm/100 cm2 200 dpe/100 cm2 8 131. 1-133 J
Beta.gava enitters (nuclides
=tta decar r: des etter than atsha entsston or s:entanecas 5000 dpa 81/100 c.2 15.000 dpa 8v/100 cm2 1000 dpa 31/100 cm2 fisstant escent $r-53 and others noted above.
Ancre sarface contastnation by both alpha. and beta-gama-emitting nuclides entsts, the Ilmits established for alpha-and beta gama-emittlng nuclides snould apply independently.
bAs used in this table, d:wa (disintegrettons per minute) reans the rate of emission by radioactive eaterial as determined by correcting the counts per minute or, served by an appropriate detector for background. ef ficiency and geometric factors associated with the instrumentation.
creas,re,ents of average contaminant should not be averaged over more than I square meter. for objects of less surface area, the average snould be cerived far each such object.
IIhe maair a Contaelaation level applies to an area of not more than 100 cm2, w
'The amount of removable radioactive material per 100 cm2 of surface area should be determined by 'wfatng that area with dry filter or soft absorbent taper. applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate Instrument of snawn ef ficiency. knen removable contamination on objects of less surface area is catermined the pertinent levels should be reduced proportionally and the entire surface should be wiped.
IThe average and easimum radfation levels associated with surface contamination resultlag from beta-gamma emitters should not enceed 0.2 arad/hr at I cm and 1.0 mrad /hr at I cm. respectively, measured through not more than 2 milligrams per square centimeter of total absorber.
i LICENSE SNM-1097 DATE
,3/26/86 PAGE DOCKET 70-1113 REVISION 14 I-1.21
L CHAPTER 8 EMERGENCY PLAN General Electric Company Nuclear Fuel & CompentsManufactgggng facility she.ll maintain a capability for handling emergencies in accordance with the Radiological Contingency & Emergency Plan, submitted to the NRC on August 27, 1981, supplemented on January 14, 1982, approved by-the-NRC on -March '29, '1982, and as revised on April 4, 1984, Februar.y 25.,-1985 and-Novem6'er 8, 1985, in accordance with regulatory-provisions ^.'
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GE will make no changes to the Plan which would decrease its effectiveness without prior app.roval of_.the Commission.
A record of authorized changes will_bermaintained for a period of two years.
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C.,
20555., _,_,_.__,
The requirements of the Plan shall be implemented through approved written procedures mAi.ntained by the licensee.
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