ML20236F944
| ML20236F944 | |
| Person / Time | |
|---|---|
| Site: | 07001201 |
| Issue date: | 06/25/1998 |
| From: | Elliott G FRAMATOME COGEMA FUELS (FORMERLY B&W FUEL CO.) |
| To: | Lamastra M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 9807060023 | |
| Download: ML20236F944 (10) | |
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F RAMATOM E COG EM A F U E LS June 25,1998 l
Mr. Michael A. Lamastra United States Nuclear Regulatory Commission Office of Nuclear Material Safety & Safeguards Division of Fuel Cycle Safety & Safeguards Licensing Branch, Licensing Section 2 Mail Stop T8D14 Two White Flint North 11555 Rockville Pike Rockville, MD 20852-2738
Dear Mr. Lamastra:
Reference:
Docket No. 70-1201, SNM-1168 Framatome Cogema Fuels (FCF) has a contract to fabricate lead test assemblies in the late fall of 1998 for the Tennessee Valley Authority using uranium that has been down-blended frem Department of Energy high enriched, reprocessed material. Chapter 1 of the License Conditions for the above referenced license has been revised to allow use of this material at the Lynchburg Manufacturing Facility. Section 1.4.11 of Chapter 1 has been modified to allow the receipt, rod loading, downloading, assembly, storage and shipment of enriched icprocessed uranium containing plutonium and other transuranic isotopes provided that the concentration of transuranic isotopes in such uranium be limited to 50Bq per gram of uranium. Upon
. evaluation of the use of this material, FCF determined that this modification will increase the specific activity at the LMF only by approximately 0.013 percent maximum. The increase in personnel exposure would be minimum due to this increase in transuranic isotope concentration. Presently, FCF's maximum exposed ind; 'idual is approximately 25% of the NRC limit and the average exposure to all individuals is less than 1%
of the NRC limit.
FCF requests that Safety Condition S-9, located on page 4 of the above referenced Materials License, be revised for consistency with Section 1.4.11 of Chapter 1 of the License Conditions.
FCF also requests that Safety Condition S-6, located on page 3 of the above referenced Materials License,
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be deleted. The present Manager of Fuel Manufacturing satisfies the education and experience requirements set forth in Section 2.1.2 of the License Conditions.
I Six copies of Chapter 1 of the License Conditions are included. The changes in the chapter are indicated by [
a side-bar and are detailed in Attachment 1.
J Should you require any further information, please contact me at (804) 832-5202 or Mr. C.F. Sanders at (804)
-832-5216. Thank you for your efforts.
i Sincerely, FRAMATOME COGEMA FUELS Lynchburg Manufacturing Facility 01 Y.
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PDR<
Gayle F. Elliott l
Manager, Safety & Licensing m
Frematome cogoma Fuels FRAMATOME e.o. eox tis 4s. Lynenburg. vA 2450s-is48 TECHHOLOOeEs Telephone: 804 832-5000 Fax: 804 832 5167
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'6 Page 1 of 1 Chaoter Pace Paragraoh Change TOC Changed revision and date of Chapter 1 to Revision 16 dated June 25,1998. Changed the last page for Chapter 11 from 11-32 to 11-21 (typographical error).
1 1-1 1.2 Changed Babcock and Wilcox NNFD and Nuclear Technology Center to BWX Technology.
1-2,1-3 1.4.11 Omitted reference to ASTM C996-90 and limited the concentration of plutonium and other transuranic isotopes in enriched reprocessed uranium to 50Bq per gram of uranium.
1-5 1.7.1 Changed 20.1904(e) to 20.1904(a) (typographical error).
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FRAMA TOME COGEMA FUELS - L YNCH:URG MANUFACTURING FA CILITY USNRC LICENSE SNM-1168, DOCKET 70-1201 TABLE OF CONTENTS PARTI CHAPTER LICENSE CONDITIONS PAGES REV.
DATE j
1 Standard Conditions &
1-1 thru 1-6 16 06-25-98 Special Authorizations 2
Organization & Administrative 2-1 thru 2-11 9
11-24-97
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3 Radiation Protection 3-1 thru 3-10 5
11-24-97 4
Nuclear Criticality Safety 4-1 thru 4-21 9
11-24-97 5
Environmental Protection 5-1 thru 5-3 3
06-09-97 6
Special Processes 6-1 thru 6-5 4
06-09-97 7
Decommissioning Plan 7-1 5
06-09-97 8
Radiological Contingency Plan 8-1 6
06-09-97 PART ll CHAPTER SAFETY DEMONSTRATION PAGES
- REV, DAIE 9
General information 9-1 thru 9-10 4
06-09-97 10 Facility Description 10-1 thru 10-15 4.
12-30-96 11 Organization and Personnel 11-1 thru 11-21 10 06-09-97 12 Radiation Protection 12-1 thru 12-10 3
12-30-96 13 Environmental Safety 13-1 thru 13-4 2
12-30-96
- Radiological l
14 Nuclear Criticality Safety 14-1 thru 14-10 4
12-30-96 15 Process Description & Safety 15-1 thru 15-37 5
12-30-96 Analysis 16 Accident Analysis 16-1 thru 16-13 3
12-30-96 Table of Contents November 24,1997 L_ _ __ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _.
FRAMA TOME COGEMA FUELS - L YNCHBURG MANUFACTURING FACILITY j
USNRC LICENSE SNM-1168, DOCKET 70-1201 PARTI - CHAPTER 1 - STANDARD CONDITIONS & SPECIAL AUTHORIZA TIONS 1
l 1.1 Licensee Name Address, and Coroorate Information l
l Name and Address of Licensee Framatome Cogema Fuels Lynchburg Manufacturing Facility Rt. 726 Mt. Athos Road P. O. Box 11646 Lynchburg, Virginia 24506-1646 State of Incorporation Framatome Cogema Fuels is a partnership of Virginia Fuels, Inc. and Cogema Fuels, Inc. The partners and the resultant partnership are organized and exist under the laws of the State of Delaware.
Princioal Offices Framatome Cogema Fuels P. O. Box 10935 Lynchburg, Va. 24506-0935 Framatome Cogema Fuels Lynchburg Manufacturing Facility Rt. 726 Mt. Athos Road P. O. Box 11646 Lynchburg, Va. 24506-1646 1.2 Site Location The Framatome Cogema Fuels, Lynchburg Manufacturing Facility is located on a 76 acre site in Campbell County, Virginia approximately 4 miles from the Lynchburg City limits. The Lynchburg Manufacturing Facility is adjacent to the BWX Technology site. The physical layout of the Lynchburg Manufacturing Facility is as shown in Figure 9.1 which illustrates the principle features within the Lynchburg Manufacturing Facility perimeter fence.
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l FRAMA TOME COGEMA FUELS - L YNCHBURG MANUFA CTURING FACILITY l
USNRC LICENSE SNM-1168, DOCKET 70-1201 PARTI - CHAPTER 1 - STANDARD CONDITIONS & SPECIAL AUTHORIZATIONS 1.3 License Number and oeriod of License The Lynchburg Manufacturing Facility license is designated as SNM-1168, Docket 70-1201. The expiration date is September 30,2000.
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1.4 Nuclear and Bv-oroduct Materials Possession Limits 1.4.1 15,000 kilograms of 2asU contained in Special Nuclear Material of a pellet form and with a maximum 23sU enrichment of 5.1 % 23sU.
Chemical form to be uranium oxide.
1.4.2 100,000 kilograms of uranium as depleted or natural material in powder or pellet form and composed of uranium oxides.
1.4.3 1000 kilograms total of uranium but not to exceed 50 kilograms in a single container as natural UF for storage only.
l 1.4.4 Up to 10 curies of encapsulated by-product material contained in one or more sealed sources. Atomic numbers 3 to 83 inclusive.
1.4.5 Up to 6.0 grams of encapsulated plutonium contained in one or more sealed sources.
1.4.6 Up to 3.0 milligrams of Californium-252 contained in one or more sealed sources, i
1.4.7 Up to 350 grams 23sU without limit on chemical, physical, or isotopic composition, for analytical and laboratory purposes.
1.4.8 Up to 1000 curies of by-product material (including transuranic elements) as contamination associated with field service activities, with operations to support nuclear plants, and/or as waste.
1.4.9 Up to 5.0 curies of Americium-241 in one or more sealed sources.
1.4.10 Up to 1 microcurie of standard samples for instrument calibration purposes. Atomic numbers 3 to 96 inclusive.
1.4.11 Receive, rod-load, download, assemble, store and ship enriched reprocessed uranium containing plutonium and other transuranic isotopes provided that the concentration of transuranic isotopes in Page: 1-2 June 25,1998 Revision: 16 l
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FRAMA TOME COGEMA FUELS - LYNCHBURG MANUFACTURING FACILITY
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USNRC LICENSE SNM-1168, DOCKET 70-1201 PARTI - CHAPTER 1 - STANDARD CONDITIONS & SPECIAL AUTHORIZATIONS l
cuch uranium be limited to 50Bq per gram of uranium. Framatome Cogema Fuels shall obtain shipper certification the uranium containing plutonium and other transuranic isotopes is limited to 50Bq per gram of uranium.
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1.5 Authorized Activities 1.5.1 Fabrication of nuclear power fuel assemblies starting by inserting i
fuel pellets into rods, through fuel assembly bundling, packaging and delivery of fuel assemblies to a carrier for transport, and repair j
of returned assemblies.
l 1.5.2 Disposal of various solid, liquid, and airborne wastes resulting from the authorized activities excluding onsite burial.
1.5.3 Laboratory operations such as but not limited to chemical analysis, metallographic analysis and testing.
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1.5.4 Field Operations activities involving equipment, processes, laboratory operations and areas contaminated with authorized quantities of by-product materials to include decontamination, l
maintenance, refurbishment, storage, transportation, and testing of contaminated equipment, tooling and components.
1.5.5 Storage of nuclear materials in various forms and facilities appropnate to safety.
1.5.6 Activities of a process and product development nature.
1.5.7 Maintenance of the facilities and equipment under adequate control to assure safety.
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1.5.8 Possession of authorized by-product, source, and special nuclear materials in packages approved pursuant to 10 CFR 71 for the l
purpose of delivery to a carrier for transport, and in private carriage l
between NRC licensed facilities within the United States.
l 1.6 Glosserv of Terms - The following definitions apply to terms used within this license.
Page: 1-3 June 25,1998 Revision: 16
FRAMA TOME COGEMA FUELS - L YNCHBURG MANUFACTURING FACILITY USNRC LICENSE SNM-1168, DOCKET 70-1201 PARTI - CHAPTER 1 - STANDARD CONDITIONS & SPECIAL AUTHORIZATIONS 1.6.1 Bafflina/Shieldina - When used in the context of moderation control, a technique for secondary containment and control in the event of a water pipe rupture.
1.6.2 Calculated Safe Arrav - A calculated safe array is defined for nuclear safety purposes as having a K,,10.87 for normal operating conditions and a K,,10.95 under assumed accident conditions.
The K.,, values for these calculated safe array will also consider statistical and methodological limits of error.
1.6.3 Calculated Safe Unit - A calculated safe unit is defined in terms of nuclear safety as having a K.,,10.87 for normal operating conditions and a K,,10.95 under assumed accident conditions.
The statistical and methodologicallimits of error will be considered when determining K,,,.
1.6.4 Controlled Area - An area that has the potential for radio contaminants above the unrestricted release limits specified in 1.7.4 of this document.
1.6.5 Fuel Assembiv/Assembiv - A grouping of fuel rods into a rigidly l
restrained configuration suitable for use in reactors.
1 1.6.6 Fuel Pellet / Pellet - Right circular cylinders of uranium oxide that have been compacted. They may be sintered or unsintered.
1.6.7 Fuel Rod / Rod - Tubing that has been loaded with fuel pellets.
1.6.8 Geometrically Safe Containet - A container with a dimension of 9 5/8 inches ID x 11 inches high, or other cylinder demonstrated to be safe, authorized for uranium in any form.
1.6.9 Lvnchbura Manufacturing Facilitv-The manufacturing fuel plant of the Framatome Cogema Fuels Fuel Company.
1.6.10 Qualified Desionee - An individual who at the minimum possess the qualifications of the position that they are filling in for in the absence of the normally assigned individual.
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FRAMA TOME COGEMA FUELS - L YNCHBURG MANUFACTURING FACILITY
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USNRC LICENSE SNM-1168, DOCKET 70-1201 PARTI - CHAPTER 1 - STANDARD CONDITIONS & SPECIAL AUTHORIZATIONS 1.6.11 Radiation Worker - An employee whose job has a significant potential for exposure to radiation or who is required to handle SNM.
1.6.12 Removed From Servita - Process equipment which is removed from production for replacement repairs or mortifications which may affect safety related controls, or which is in " storage" for a period of 4 months or more whether or not modifications have been undertaken. " Removed from service" is not taken to include equipment which cemains on line but is infrequently used, or which is temporarily bypassed as a result of routine process requirements.
1.6.13 Safe Mass - The maximum safe mass, independent of geometry, degree of water moderation, and reflection is defined as 850 grams of U-235, 1.6.14 Safe Volume - Defined as 14-liter maximum capacity for 4.10 w/o uranium in any form.
1.6.15 Tube - Zircaloy or stainless steel tubing used as fuel pellet cladding.
1.6.16 Uncontrolled Area - An area where the contamination levels do not exceed the limits specified in 1.7.4.
1.7 Soecific Exemotions and Soecial Authorizations 1.7.1 Postinas A continued exemption is requested from the labeling and posting requirements of 10 CFR 20.1902(e) and 20.1904(a) because of the I
nature of our operation. The intent of this section is met by posting I
areas which house or temporarily store radioactive material with signs incorporating the radiation symbol and with the warning:
" CAUTION RADIOACTIVE MATERIAL; ANY AREA OR CONTAINER l
WITHIN THIS PLANT MAY CONTAIN RADIOACTIVE MATERIAL".
This exemption is based on practicality and/or experience and has been applied effectively at Lynchburg Manufacturing Facility for the past 25 years.
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FRAMA TOME COGEMA FUELS - L YNCHBURG MANUFACTURING FACILITY USNRC LICENSE SNM-1168, DOCKET 70-1201 PARTI - CHAPTER 1 - STANDARD CONDITIONS & SPECIAL AUTHORIZATIONS i
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1.7.2 Storace of UF Cvlinders 3
J UFe cylinders may be stored outside the main building in a planar array. This storage area is exempt from the criticality monitoring requirements of 10 CFR 70.24.
l 1.7.3 Storaae of Fuel Within Shionino Containers Fuel may be stored in NRC licensed shipping containers. They are i
l exempt from the criticality monitoring requirements of 10 CFR 70.24 provided:
The containers and contents have been subject to the inspections and determinations required by 10 CFR 71, l
Subpart D.
The containers are sealed, properly identified, and meet shipment requirements.
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A minimum of 38" edge-to-edge separation is maintained between the loaded container array and other accumulations of SNM.
The loaded container array has a minimum separation of 12 feet.
1.7.4 rree-Release Limits Framatome Cogema Fuels is authorized to release equipment and material from the controlled areas to the uncontrolled areas in accordance with " Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for By-Product, Source or Special Nuclear Material",
USNRC, August 1987.
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FCF requests a modification to License condition S-9 to allow the receipt of reprocessed uranium containing plutonium and other transuranic isotopes in exceed of the limit specified in ASTM Specification C996-90. We are requesting a limit of 50Bq per gram of Uranium.
Reasons that we think it is justified Increase in specific activity - 0.013 percent Maximum I
e M.uuumu auucase in uk.ml h. A.
Current exposures -Maximum exposed individual is -25% of the NRC limit and the average e
exposure to all individuals is less than 1% of the NRC limit j
'Ihe increase in personnel exposure would be minimum due to this increase in transuranic isotope concentration.
FCF has a contract to fabricate lead test assemblies for the TVA using uranium that has been down blended l
from DOE high enriched, reprocessed material.
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