ML20138P056
| ML20138P056 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 07/01/1985 |
| From: | Vaughan C GENERAL ELECTRIC CO. |
| To: | Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20138P058 | List: |
| References | |
| 25635, NUDOCS 8511060348 | |
| Download: ML20138P056 (47) | |
Text
,
G E N E R A L () E LE CTR I C NUCLEAR FUEL MANUFACTURING DEPARTMENT GENERAL ELECTRIC COMP ANY - P. O. BOX 780 - WILMINGTON. NORTH C AROLINA 28402 L/
vi July 1, 1985
,@ ff8,5 G=-
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Director b
Office of Nuclear Materials Safety & Safeguards U.S. Nuclear Regulatory Commission 93-Washington, D.C.
20555
,_in -
Attent' ion:
Mr. W. T.
Crow, Section Leader Uranium Process Licensing Section 00Carrco
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g M/S 396-SS USMc
Dear Sir:
8 I 2 1985 1.
2
""nss
Reference:
NRC License SNM-1097, Docket 70-1113 Unv 1
DOCKET citax g
Subject:
LICENSE AMENDMENT REQUEST - REVISION #9 q
p With reference to activities authorized by NRC License SNM-1097 (reference 1), General Electric hereby requests the following:
Special authorization, pursuant to the technical position paper SECY-81-576 dated 10/5/81, to dispose of industrial waste products by burial, which contain not more than 250 pCi/gm of uranium activity, of which no more than 100 pCi/g is soluble.
The soluble and insoluble uranium concentrations in these wastes are sufficiently low to prevent the associated radioactivity from posing a threat to public health or safety using disposal Option 2.
A specific example of the type of waste to be considered for disposal under Option 2 would be the calcium fluoride sludge produced as a result of the lime treatment of ammonium fluoride waste water.
(See Attachment 1.)
- is a revised Chapter 1 of Part I of the renewal application fo'r SNM-1097, which contains the requested authorization in paragraph 1.8.5.2.
For informational purposes, the following is the status of three of GE-NFMD current projects:
General Electric Company, Nuclear Fuel Manufacturi@ Deph tment o
requested and received NRC authorization in 1983 t% constructgi pilot plant for the Uranium Recovery from Lagoon S19dges g RLS) project.
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9 Construction has progressed to the poin that the stgucture is essentially comp] ci.e.an -
App scan cne equipment Lspartiallygnstaded.
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i GENER AL $ ELECTRIC Director - ONMSS July 1, 1985 Page 2 l
However, it has been necessary to defer completion of l
construction of this pilot facility until 1986.
o Concurrent with the URLS deferral, we are evaluating a desludging project for the nitrate waste lagoons.
While the details and schedule for this project are not firm at present, it. appears that we may need to use the URLS facility to support this work.
Project startup is currently estimated to be around January 1986.
We may also need to perform some pilot tests before 1986.
In any event these needs will be communicated separately.-
o With regard to this current special authorization request, we expect UPMP operations (authorized by Amendments 2 and 3 to SNM-1097) and the new operations which will produce option 2 material, to be ready for integrat.ed pilot testing within approximately one month.
Full routine operation is expected later this year.
Pursuant to 10 CFR 170.31, a GE check for $150 for processing this amendment request will be forwarded under separate cover.
If you have any questions regarding this special authorization request, please contact me.
Very truly yours, GENERAL ELECTRIC COMPANY Charles M. Vaughan, Manager
- Regulatory Compliance M/C J26
/sbm cc:
Virgil R. Autry - South Carolina DHEC L. C. Martin - South Carolina DHEC
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l GENERAL $ ELECTRIC Director - ONMSS July 1, 1985 - Page 1 ATTACHMENT 1 DESCRIPTION OF MATERIAL FOR DISPOSITION Conversion of uranium hexafluoride to uranium dioxide is one of the manuf acturing steps used in the production of nuclear fuel at the Wilmington, N.
C.,
facility of the General Electric Company.
The aqueous waste stream from this conversion must be chemically treated to remove impurities.
The treatment process used at this f acility for this waste stream is based on the addition of lime to precipitate insoluble impurities.
The ammonia content of the waste stream is recycled for reuse in the conversion operation.
The slurry, consisting of primarily calcium fluoride, calcium carbonate, excess lime and water, is directed to lagoons that are designed to provide for settling of the solid _ material.
The small quantities of uranium in the waste stream precipitate and accumulate with the other settled impurities.
These accumulated solids are generically referred to as calcium fluoride sludge.
The aqueous supernate is discharged to the N. E. Cape Fear River after additional treatment.
The calcium fluoride sludge produced to date is stored on site with the intent of future processing to recover the uranium in the sludge.
The advent of the Uranium Process Management Project (reference Amendments 2 and 3 to SNM-1097) has resulted in the capability to produce a new generation of calcium fluoride sludge with sufficiently low uranium concentration to make further uranium recovery operations uneconomical.
The anticipated uranium activity is also sufficiently low to allow consideration of disposal under the guidelines of Option 2, SECY 81-576 (i.e., less than 250 pCi/gm uranium activity, of which no more than 100 pCi/gm
.is soluble).
The composition of the calcium fluoride sludge would be expected to be relatively uniform and as follows:
GENER AL $ ELECTillC Director - ONMSS July 1, 1985 - Page 2 Calcium Fluoride Sludge Composition
- Values in weight %
Calcium Fluoride 45 Calcium Carbonate 2.5 Calcium Hydroxide 2.F Metals Plus Combined Ammonia & Nitrates 0.3 Total Solids 50.3 Water 49.7 Total 100
- Typical composition at 50% water content Metal & Combined Ammonia Parts per Nitrate Concentrations Million (Example at 50%
(Wet Basis)
Water Content)
< 25 Barium
< 25 Cadmium 5
Lead 5
< 50 Chromium - Trivalent 5
- Hexavalent 5
Nickel 8
Copper 5
Titanium 31 Aluminum 436 Iron 296 Manganese 8
Cobalt 5
Magnesium 1735 Combined Ammonia & Nitrates 408 Note:
The chemical and activity concentration of the uranium in the sludge will vary as functions of the effectiveness of uranium removal from the waste water stream, the enrichment and the percent solids in the sludge after filtration.
The information in Figure I
GENERAL $ ELECTRIC Director - ONMSS July 1, 1985 - Page 3 FIGURE 1 URANIUM ACTIVITY IN CaF SLUDGE 2
600 -
500 -
zo 5!
<w m o 400 -
PARAMETER zw BOUNDARIES ta o U C z
O E 300 -
3t 250 pCi/g gg p 8 200 -
l Ua l
1 EXPECTED OPERATING 100 -
RANGE 0
i i
i 0
1 2
3 4
ENRICHMENT, % U235
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~w
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GENER AL $ ELECTRIC Director - ONMSS July 1, 1985 - Page 4 portrays the effect of the interrelationship of these variables and indicates the projected operating parameters.
The calcium fluoride sludge is not classified as a hazardous waste under Resource Conservation & Recovery Act Regulations.
The pH is less than 12.5, e.g.,
12.2.
The EP toxicity values in the extract, when tested in accordance with 40 CPR 261.24, are:
Milligrams per Liter Maximum Allowable Test Contaminant Concentration Values Arsenic 5.0
< 0.05 Barium 100.0
< 0.8 Cadmium 1.0
< 0.04 Chromium 5.0
< 0.1 Lead 5.0
< 0.1 Mercury 0.2
< 0.002 Selenium 1.0
< 0.05 Silver 5.0
< 0.1 As expected, the uranium is present in an insoluble form.
Analysis of leachate developed in accordance with 40 CFR 261.24 showed a uranium concentration of less than 0.02 parts per million and 0.04 parts per million on tests run in duplicate.
PROPOSED MANNER & CONDITIONS OF DISPOSAL The calcium fluoride sludge will be'dewatered before loading into a transport for delivery to the GSX Corporation Facility near Pinewood, South Carolina for burial.
The GSX Corporation Facility was formerly operated by SCA Services, Inc.
The facility is operated as a hazardous waste burial facility under interim RCRA ID Number SCD 070375985 and South Carolina Permit Number IWP-145.
The Part B application for hazardous waste management was submitted in August 1983 for the Pinewood Facility.
It is currently in the review cycle.
GSX Corporation has confirmed their willingness to handle the material and initial discussions with South Carolina Department of
GENERAL $ ELECTRIC Director - ONMSS July 1, 1985 - Page 5 Health and Environmental Control (DHEC) personnel have not identified any problems.
A concern was raised by DHEC personnel that the adequacy of the transportation mode for preventing leakage would have to be established.
The specific truck trailer body design was chosen to address this concern.
This trailer design incorporates a cup concept thus eliminating the need for a tailgate and the potential leakage problems that can be associated with tailgates.
The final steps in the sludge dewatering process will be performed in a filter press.
The filter cake will be discharged into the over-the-road trailer body.
The trailers will be covered by tarpaulines enroute to and from the burial facility and will be sole use vehicles.
While it is anticipated that there will be no free water (as defined.
by EPA in 40 CFR 264.314(c) which references EPA publication No.
SW-846, " Test Methods for Evaluating Solid Wastes / Physical / Chemical Methods"), it is not yet known what the actual operating experience will be.
A small quantity of an approved solidification media will be added if necessary prior to transportation.
Similarly, actual over-t'ne-road experience will be necessary to determine whether the physical vibration of the filtered calcium fluoride sludge during transit may result in the occurrence of free water.
In this case, the sludge will be treated as necessary at the burial site to conform to South Carolina and U.
S. Environmental Protection Agency Regulations pertaining to free water.
In either case, our plans include the capability to address these options in an appropriate manner once we establish the characteristics of production quantities of the material.
All work with GSX Corporation requires prior authorization of intended activities via a South Carolina Department of Health and Environmental Control (DHEC) Authorization Request (see Exhibits 1 and 2).
Exhibit 1 discusses zirconium sludge previously disposed of at this facility under Option 1, SECY 81-576.
Exhibit 2 is a copy of the DHEC authorization request that will be supplied to GSX Corporation.
GSX will then utilize this information to coordinate authorization with DHEC prior to receiving and disposing of calcium fluoride sludge disposal.
GENER AL $ ELECTRIC Director - ONMSS July 1, 1985 - Page 6 i
PERTINENT INFORMATION A copy of the GENSTAR annual report for 1984 is attached as Exhibit 3.
Please note pages 11-13 which reference the GSX facility and operations at the Pinewood, S.
C.,
location.
As mentioned previously, the calcium fluoride sludge is not classified as a hazardous waste under RCRA regulations; nevertheless, the choice has been made to utilize a RCRA quality facility for disposal purposes.
The GSX burial facility is presently subject to the 40 CFR 265 requirements as a minimum and also applicable South Carolina requirements.
The burial facility will be subject to 40 CFR 264 requirements when the pending Part B permit' application is processed.
The present and future requirements address in detail the issues pertaining to containment of buried hazardous waste as defined in the Resource Conservation and Recovery Act and regulations pertaining thereto.
For example, 40 CFR 264.119 " Notice to Local Land Authority" details requirements after closure for surveying and marking the property and submitting to the local zoning authority and to the Regional Administrator records as to types, quantities and locations of wastes at the facility.
40 CFR 264.120 "Hotice in Deed to Property" details requirements for recording on a deed or other similar instrument, a notation that will in perpetuity notify any potential purchaser of the prior site of prior use, future use restrictions and the prior filing of the information required in 40 CFR 264.119.
The proposed work has been discussed extensively with GSX Corporation personnel.
GSX has quoted on performing the work and, by the content of their quotations, clearly demonstrates their understanding of the nature of the material and an ability to safely handle it.
Copies of thesa quotations are on file at General Electric for inspection.
Based on the radiological nature of the calcium fluoride sludge, the vendor's capabilities and procedures, and the procedures defined in this application, General Electric Company has determined that the calcium fluoride sludge can be disposed of without risk of unexpected or hazardous exposures.
The amendment request should therefore be granted since it does not impact public safety.
Further, these conclusions are in accordance with SECY S1-576 dated October 5, 1981.
GENERAL $ ELECTRIC Director - ONMSS July 1, 1985 - Page 7 SPECIFIC CONDITIONS OF LICENSE In accordance with Option 2 of SECY 81-576, " Disposal or Onsite Storage of Residual Thorium or Uranium (Either as Natural Ores or Without Daughters Present From Past Operations)", the following special authorization is requested:
Notwithstanding any requirements for state of local government agency disposal permits, General Electric is authorized to dispose of industrial waste treatment products without continuing NRC controls provided that the uranium concentration in the material shipped for disposal 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 will be at least four feet below the surface.
This request has been incorporated into Section 1.8.5.2 of Part I of the GE application for renewal of SNM-1097 and is included as.
C. M. Vaughan/WBS l
)
GENERAL $ ELECTRIC Director - ONMSS July 1, 1985 - Page 8 EXHIBIT 1 PRIOR DISPOSAL OF ZIRCONIUM SLUDGE Chemical etching of tubing and other zirconium reactor components is one of the manufacturing steps used in the production of nuclear fuel at the Wilmington, N.
C.,
facility of General Electric Company.
It had been the practice during 1972-1982 to treat the waste chemical etch solution with lime to precipitate impurities and to neutralize the acid.
The resulting precipitate, referred to as zirconium sludge, was accumulated in lined lagoons which from time to time had been used to treat other chemical wastes from the fuel manufacturing process.
A major portion of the accumulated zirconium sludge was removed from the lagoons, treated with a chemical fixation process and stored on the site during this time period.
A decision was made and implemented in 1982 to discontinue the on-site treatment of the waste etch acid and to dispose of both the chemically-fixed sludge stored on site and the zirconium sludge stored in the lagoon.
Even though this material was not a hazardous waste under the Resource Conservation & Recovery Act (RCRA) regulations, the F
decision was made to utilize the RCRA-quality facility at j
Pinewood, South Carolina for disposal.
The concurrence of the South Carolina Department of Health & Environmental Control was obtained prior to commencing this effort.
As the zirconium sludge contained low concentrations of uranium activity (i.e., less than 30 pCi per gram) concurrence was also requested and-obtained from the U.
S. Nuclear Regulatory Commission ~~for disposal at the Pinewood, S.
C.,
facility under Option '1 - of SECY 81-576.
Approximately 14,000 tons of. fixed zirconium sludge and 2,000 tons
'of unfixed sludge were disposed in this effort.
WBS f
GENERAL $ ELECTRIC Director - ONMSS July 1, 985 - Page 9 b
1 i
EXHIBIT 2 SOUTH CAROLINA DEPARTMENT OF HEALTH & ENVIRONMENTAL CONTROL AUTHORIZATION REQUEST FORM DHEC 1969 (7/84), 3 PAGES
'rf l
Amendment New X
Landfill R2 claim South Carolina Department of Health and Environmental Control Recycle incinerate Bureau of Solid and Hazardous Waste (803) 758 -5681 Landfarm Energy Recovery Other AUTHORIZATION REQUEST FORM ra-ility use only:
Authorization Number: I I-1 1-I I
2 To be entered
~
(1-11) by TSD Facility Generator Information:
Generator ID # I NCD050409150 I Namel GENEIML ELECTRIC OOMPANY (12-23) y Address I P.O. DoX 780 W C J26 WINNN I City I I
Statei I
Zip Code I.
NC 402 Official Contact! w.n. sMALLEY ITitle I MGR-EW NT ITelephone IC 919)343 - 5646 i l j
SC County Treatment, Storage, or Disposal Facility Information:
un inauw wner air)
Facility EPA 10 #Is c n o 7 0 3 7 s 9 8 s-I Narne I GSX CORPORATION I
(24-35)
Address i P.O. DOX 210799 I City l COLUMBIA I
Statei SC I Zip Codel 29221 g
Description of Hazardous Waste:
I CALCIUM FLUORIDE SLUDGE I
(36-95) 7777 EPA /DHEC Waste Codes: I I I I I I I I I i
(1-4)
(5-B)
(9-12)
(13-16)
(17-20)
Handling MethoddD3 II Volume: (Ibs/yr. only) 1 70oooooI (21-23)
(24-32)
Enter Quarter for One-Tirne Disposal: U /I I Qtr/yr.
(33-35)
If Multiple Shipments Enter Frequency Here: 1 250 i times /yr.
(36-39)
Physical State of Waste @ 70*F (40) :
Flash Point (cc) (41):
1.Lx_J solid
- 2. L_J liquid 3.L_J N/A
- 1. Lx_J none 2. L_J (60*F
- 3. l_] 60-140'F 4. L_I > 140*F -
(SFNT SOT.TD)
/
f For DHEC use Ody:
totes:
Date Received i II Ii 1
b'
- '40 DHEC 1969 (7/84) page1
rY AUTHORIZATION REQUEST FORM (con't).
6 s
Proper DOT Shipping Name/ Hazard Class / DOT ID'# I NOME - IUP CLASSIFIED AS A D0ff HAZARDOUS WASTE OR SUBSTANCEg
/
Process Producing Waste 1 00NVERS7p OF URANIUM HEXAFwoRIDE 'IO URANIUM DIOXIDE J Line 1 I
1 I in Drums (size)I' I
I X 1 in Bulk i
I Other Packaging for Shipment:
I Railroad tankeh I x Itruck i I Otheri I Specific Gravity: Ll s _1 Method of Transportation : I o
Viscosity @ 70*F: I ILow I
~ l Mediurn tilAl High Layering: I X l None i I Bilayered i I Multilayered
^
Suspended Solids: % by weight or volume, Specify exact %IN/Al Dissolved Solids: by % weight, Specify exact % IN/A l Thousands of Btu's/lb, Specify : IN/A I Organically Bound Sulfur (wt %): IN/A I Organically Bound Chloride:1N/Al Organically Bound Nitrogen (Wt %) l N/A I Toxicity: L_lHigh LX_lMedium L_.1LowL_1 Unknown Ash'%: I N/A~j ;
Affinity for Water: 1 xi I
I Hydrophilic Lipophilic pH (if hydrophilic): I a-12.4 l
Visual Description of waste: I GRAY SLUDGE l
Constituents: List specific constituents by name and corresponding percentage in waste stream.
Volatile Organics Non Volatile Organics %
Acid or Alkalis Salts & Inorganics* %
RANGE CAILIUM FLUORIDE 45 40-50 CAILIUM CARBONATE 2.5 2-5 CAICIUM HYDROXIDE 2.5 2-5 COMBINED AMMONIA 0.3 0.1-0.5 AND NITRATFE HATER 50 40-60
'IUPAL (VOwME %)
100 100
- EXAMPLE OF A TYPICAL COMPOSITION Water:
40 - 60 IN WEIGiff PERCENT. RANGES ARE AT 50% WATER CONTENT.
DHEC 1969 (7/84)
Page 2
s SPECfFIC INSTRUCT 10NS
- 13. 00T Proper Shipping Name/ Hazard Class /00T ID f: names and codes as found in Code of Federal Regulations (Transportation) Title 49.
Ex. Hazardous Waste Liquid, N.0.S., OR'4E, NA9189.
- 14. Process Producing Waste: briefly describe the process by which the waste is produced. Be Specific.
- 15. Packing for shipment: check one.
Indicate the size of the drum.
If (other), specify in blank space to the right of item.
- 16. Method of Transportation: check one. Please specify if (other).
1
- 17. Specific Gravity: list the appropriate value.
- 18. Viscosi ty: check one.
- 19. Layering: check one.
- 20. Suspended solids: list exact value if known and circle correct indicator parameter either weight or volume.
- 21. Dissolveo solids by weight: list exact value if known.
- 22. Thousands of BTV's/lb: list exact value if known.
- 23. Organically bound sulfur: list exact value if known.
- 24. Organically bound chlorine: list exact value if known.
- 25. Organically bound nitrogen: list exact value if known.
- 26. To xicity: check appropriate toxicity for waste stream based on values found in various chemical references.
If no value can be found use reasonable judgement.
- 27. Ash 3: give a value in percentage.
- 28. Affinity for Water: check one. hydrophilic refers to having a strong affinity for bindings or absorbing water. Lipophilic refers to a strong affinity to fats.
- 29. pH:
If hydrophilic was checked previously, give exact value.
If lipophilic was checked previously, print N/A.
- 30. Visual Description of Waste: Give brief visual description of waste i
stream, include parameters, such as color, physical state, and similarities wi th conmonly known substances. Ex. Light-green dry pellets.
- 31. Consti tuents:
List specific constituents by name and corresponding percentage in waste stream. Values in percent must be listed for the following categories: " Volatile Organics", "Non Volatile Organics", " Acid or Al kalis", " Sal ts and Inorganics", and " Water". Values in ppm must be listed for the following categories found on page 3: " Metallic" and "Toxics".
Blank space is provided for those metals not listed on this fonn but found in the waste stream If there is not a suitable category for a specific iten other than metallics, found in the waste stream, list the item and the appropriate value (Percentage or ppm) under "Other Infonnation " found on page 3.
Ex.
Crushed Steel Drums 60% List any categories of chea1 cal compounds that the referenced waste stream will react with under "Other Information".
Speci fic values listed for constituents, must total to plus or minus 4% of the total vol uce. Constituent values may also be listed in a small range; in this case the minimum and maximum values as totalled are not required to be within plus or minus 4% of total volune.
AtJTHORIZATION REQlEST FORM (con't) 1 Metallic: (total metals not EP Toxicity Test)
(SAME BASIS AS EXAMPIE ON PG 2)
ToxicS:
As
<25 ppm Cr+3
<s ppm Ag
<5 ppm Fe 300 ppm Cyanide None ppm 4
Ba 2s ppm Cr
<5 ppm Ni a ppm Sb
-- ppm Pesticides None pprn Cd_ <s ppm Hd ppm Cu
<s ppm Mn
<10 ppm Carcinogens None ppm Pb
<s ppm Se
-- ppm Ti 31 ppm Co _ <s ppm Other Toxics None ppm Zn <so ppm A1 500 ppm Mg 2000 ppm ppm
- Low Enriched Uranium (< 6 w/o U235) activity not to exceeo ou pci/gtwa Other Information :
Certification :
I certify under penalty of law that this document and all attachments were prepared under my direction or supervision in accordance with a system designed to assure that qualified personnel properly gather and evaluate the information submitted. Based on my inquiry of the person or persons who manage the system, or those persons directly responsible for gathering the information, the information submitted is, to the best of my knowledge and belief, true, accurate, and complete. I am aware that there are significant penalties for submitting false information, including the possibility of fine and impriconment for knowing violations.
Signature :
Date Submitted :
Print Name :
Title :
TSO Facility Certification :
I certify that based on the information presented in this document this facility is permitted to accept the waste stream described hereon, and do hereby inform the generator listed hereon of acceptance of the waste for treatment, storage, and/or disposal in the manner designated, and in complicnce with the TSD Facility's standard terms and conditions.
Signature :
Date Submitted :
Print Name :
Title :
DHEC 1969 (7/84)
Page 3
SPECIFIC INSTRUCTIONS 32.
See page 2 under (" Constituents") for instructions on the listing of
" Metallic", "Toxics", and "Other Information" values.
- 33. Certification:
Must be signed by appropriate managers and personnel representing the company generating the waste stream referenced on this Form.
- 34. TSD Facility Certification:
Must be signed by appropriate managerial personnel representing the facility to treat, dispose, or store waste stream
'as referenced on this Fom 35.
Nomally once this Form is conpleted and signed by the correct parties, it may be submitted to The Department of Health and Environmental Control thru the facility.
Please check with the facility on specific instructions concerning disposal procedures.
e 9
I
GENERAL $ ELECTRIC Director - ONMSS
- July 1.,
1985 - Page 10 r
, f/
EXHIBIT 3
.p_4 GENSTAR ANNUAL REPORT - 1984 f
REFERENCS PAGES 11-13 i
9 L
s
'l GENERAL $ ELECTRIC Director - ONMSS
- July 1, 1985 1
ATTACHMENT 2 REVISED CHAPTER 1 OF PART I DATED 7/01/85
. OF APPLICATION TO RENEW SNM-1097 WITH APPLICABLE INDEX PAGES CHANGES ARE NOTED BY A-ASTERISK IN THE RIGHT MARGIN V1
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REVISIONS BY PAGE O
Effective Effective Effective Pace Date Page Date Pace Date TABLE OF CONTENTS CHAPTER 2 I-3.11 5/14/84 I-3.12 1
10/23/84 I-2.1 5/14/84 I-3.13 2
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
7/01/85 I-2.7 I-3.19 8
I-2.8 I-3.20 9
I-2.9 I-3.21 10 I-2.10 I-3.22 11 I-2.11 I-3.23 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 I-2.16 I-2.17
/~'l T
CHAPTER 1 I-2.18
\\~
I-2.19 CHAPTER 4 I-1.1 7/01/85 I-2.20 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 I-1.5 I-2.24 I-4.4 I-1.6 I-4.5 I-1.7 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-3.7 I-4.14
.15 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 I-1.21 E
LICEtISE SNM-1097 DATE 7/01/85 PAGE DOCKET 70-1113 REVISION I
9
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REVISIONS BY PAGE Effective Effective Effective Page Date Page Date Page Date 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 I-8.1 9/24/84 I-5.5 I-5.6 I-5.7
(~s I-5.8 6/20/84 (s)
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 llh LICENSE SNM-1097 DATE 7/01/85 PAGE DOCKET 70-1113 REVISION
/
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REVISIONS BY PAGE i
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Effective Effective Effective Page Date Pace 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 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 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 i
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-11.48 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 l.
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RE"ISIONS BY PAGE Effective Effective Effective Page Date Page Date Pace 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 4
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 l
II-12.3 II-13.19 II-13.58 II-12.4 II-13.20 II-13.59 i
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
(/T II-12.12 II-13.28 II-13.67 L
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 4
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 I; -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-13.83 II-13.6 II-13.45 II-13.84 IT-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 h
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REVISIONS BY PAGE C) a Effective Effective Effective Page Date Page Date Page Date II-13.88 7/25/83 II-15.27 9/30/83 II-16.15 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-16.2)
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 e
II-15.5 II-15.44 II-16.32
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II-15.6 II-15.45 II-16.33
()5 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 '6.39 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 h
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Effective Effective Effective Page Date Pace Date Pace 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 4
II-16.65 II-16.66 II-16.67 II-16.68 II-16.69 II-16.70 II-16.71 Q(>
II-16.72 II-16.73 4
CHAPTER 17 J
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CHAPTER 1
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STANDARD CONDITIONS AND SPECIAL AUTHORIZATIONS 1.1 CORPORATE & FINANCIAL INFORMATION This licensing information document is filed by the Nuclear Fuel Manufacturing Department 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 Manufacturing Department (NFMD) operates a nuclear fuel fabrication plant in Wilmington, North Carolina.
At this site, NFMD
(])
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 Manufacturing Department, (name of person and mail code),
P. O. Box 780, Wilmington, NC 28402.
i 1.3 LICENSE NUMBER The General Electric Company Nuclear Fuel Manufacturing Department NRC license number is SNM-1097 (Docket 70-1113).
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l llh LICENSE SNM-1097
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as In accordance with the GE timely renewal request dated
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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 Regulatory Commission completes final action on this matter.
i 1.4 POSSESSION LIMITS The following types, quantities, and forms of special nuclear materials are authorized:
1.4.1 Uranium-235, 50,000 kas total Contained in uranium to a maximum, nominal enrichment of 6% in the form of UF UO U0 and other solid and 6,
2, 3 8
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liquid process intermediates and products characteristic of LEU 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 kas Total In any form, contained in uranium at a maximum nominal enrichment of 15% for use in laboratory and process technology development operations.
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1.4.4 Plutonium I ()
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l milligram in samples for analytical purposes 1 milligram as standards for checking the alpha radiation response of radiation detection to instrumentation.
1,
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20 grams as sealed neutron sources i
In nuclear fuel rods containing not more than 10-6 grams I
of plutonium per gram of U235,
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l 1.5 MATERIAL USE LOCATIONS i
1 Uranium normally will be used at the Wilmington site
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in the Puel Manufacturing Area only.
Conversion and 1
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fabrication of SNM is conducted within the Fuel Manufe.eturing building.
i Small quantities (i.e., less than one safe batch of f
uranium in a non-dispersable form) may be temporarily moved to other buildings or site locations for special I
tests.
1.6 DEFINITIONS 3
i Definitions as used in the license conditions are set forth below.
I ()
I LICENSE SNM-1097 DATE i 7/3?/8 PAGE DOCKET 70-1113 REVISION I
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i.6.1 Area Manaaer - The manager designated by the Department
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G1 General Manager who is responsible for implementation of nuclear 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.
1.6.2 Array - means two or more interacting accumulations of fissile material.
1.6.3 Criticality Control - means the administrative and technical requirements established to minimize the possibility of achieving inadvertent criticality in the environment analyzed.
1.6.4 Full Reflection - means the degree of reflection equivalent to a tight fitting shell of 12 inches or more
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of water.
1.6.5 Minimal Reflection - means the degree of reflection equivalent to a close-fitting shell of water, steel, aluminum, nickel or copper not greater than 1/8 inch in thickness.
i 1.6.6 Minimum Critical Dimension - means the smallest dimension which constitutes a critical system for a given geometry under conditions of full reflectica and optimum moderation.
1.6.7 Nominal U235 Enrichment - means the value of enrichment assigned to a quantity of material for convenience i
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because the precise value is not known due to process or
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measurement uncertainties.
1.6.8 Nuclear Safety - means both criticality and radiation safety.
1.6.9 Safe Batch - means an accumulation of special nuclear matcria' 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.
1.7 AUTHORIZED ACTIVITIES This application requests authorization to receive,
(")T possess, use, store and ship authorized special nuclear materials pursuant to 10 CFR Parts 70, 71 and 73.
1.7.1 Product Processing Operations 1.7.1.1 UF i
Conversion - Conversion of uranium hexafluoride to 6
uranium oxides.
l 1.7.1.2 Fuel Manufacture - Fabrication of nuclear reactor fuels containing uranium.
1.7.1.3 Scrap Recovery -
Reprocessing of unirradiated scrap from NFMD and from other sources with nuclear safety characteristics identical to NFMD in-process materials.
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1.7.2 Process Technology Operations
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1.7.2.1
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Development and fabrication of reactor fuel, fuel elements 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, i
I 1.7.2.4 Chemical analysis and material testing, including 1
4 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
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nuclear instrumentation and measuring devices.
1.7.2.6 Other process technology development activities related to, but not limited by, the above.
l 1.7.3 Laboratory Operations r
,i Chemical, physical or metallurgical analysis and testing i
of uranium compounds and mixtures, including but not limited to, preparation of laboratory standards.
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4 1.7.4 General Services Operations
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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 Discosal 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.
l 1.7.5.3 Treatment or disposal of combustible waste and scrap I
material by incineration pursuant to 10 CPR 20.302(a) and 10 CFR 20.305.
1.7.6 Offsite Activities j
Non-destructive modification, testing, demonstration and i
storage of materials and devices containing unirradiated l
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uranium, provided that such materials and devices shall
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be in General Electric control at all times.
1.8 EXEMPTIONS & SPECIAL AUTHORIZATIONS j
1.8.1 Requirements for Prior Authorization of Activities by 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 which may involve a significant increase in potential or actual environmental impact resulting from utilizing 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:
(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.
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LICENSE-SNM-1097 DATEi 7/01/85 PAGE oOCKET 7,1-1113 REVISION I
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1.8.2 Contamination-Free Articles 4
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-i 1.18 through I-1.21, 1.8.3 Disposal of Contamination-Free Liouids 1.8.3.1 Hydrocen 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,
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)
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%.
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 lagoon system.
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Prior to shipment, each transfer is sampled and measured
()
to assure that the concentration does not exceed three parts per million of uranium.
General Electric shall maintain records under this condition of license including, as a minimum, the date, uranium concentration and quantity of all hydrofluoric acid transferred.
r 1.8.3.2 Nitrate-Bearino Liouids 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 1
nominal enrichment does not exceed 6 weight percent l
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 Off-Site Locations 1.8.4.1 Authorization to use up to 15 grams of U 235 at other j
sites within the limits of the United States except where the material is subject to licensing by an Agreement State as defined in 10 CPR 150.
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The manager of the radiation safety function shall
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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 the storage warehouse located in Greenville, S.
C., and at nuclear reactor sites, 4
uranium fully packaged as for transport in any Fissile Class I package, in accordance with the conditions of a j
license authorizing delivery of such containers to a i
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 4
bases for the containers during transportation.
1
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Provisions for compliance with applicable 10 CFR 73 requirements are described in the NRC-approved General i
Electric Company, Nuclear Fuel Manufacturing Department, Wilmington, N.
C., Physical Security Plan dated October 26, 1981, as currently revised in accordance with regulatory provisions.
l Storage at nuclear reactor 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 waived insofar as this section applies to the materials contained in Fissile Class I packages.
1 lll LICENSE SNM-1097 D ATg ;
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1.8.4.3 Authorization to store, at the storage warehouse located
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at Greenville, S.
C., and 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 tb2 width and length for each array and separation betwc>
arrays determined only by container
()
handling requirements.
Provisions for compliance with applicable 10 CFR 73 requirements are described in the NRC-approved GE-NFMD Physical Security Plan dated October 26, 1981, 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 and is limited to possession for purposes of 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 any of the inner
$hI LICEMSE SNM-1097 DATE 7/01/85 PAGE DOCKET 70-1113 REVISION 9
I-1.12
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 that 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 fuel 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.
LICCNSE SNM-1097 DATE 7/01/25 PAGE DOCKET 7,0-1113 REVISION 9
I-1.13
i i
l 1.8.4.4.4 All operations involving the fuel are conducted in
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locations that have been selected to preclude mechanical j
damage and flooding.
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1.8.4.4.5 Loose rods are stored only in RA-series inner metal containers.
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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 j
and approved by General Electric and the reactor licensee, to provide for the nuclear and radiation a
)
safety of the operations to be performed.
1.8.4.4.8 Records of the operation, including evaluations, procedures used, audits performed, ar.d performance reports are maintained at the Wilmington, North i
Carolina, plant.
l 1.8.5 Disposal of Industrial Waste Treatment Products 1
1 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 following conditions are met:
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1.8.5.1 All freestanding liquid shall be removed prior to
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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 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 shall not exceed 250 pCi per gram of uranium activity, of which no more than 100 pCi per gram shall i
be soluble.
The minimum burial depth shall be at least four feet below the surface.
O 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 l
purposes, specific dilution factors, which consider j
dispersion model parameters, may be calculated and
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used.
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1.8.7 Monitor System Exemption
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m 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 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 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
( w) the number of such stored containers, provided on the storage locations preclude mechanical damage and flooding, or The quantity of uranium 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 lhh LICENSE SNM-1097 DArg 7/01/85 PAGE DOCKET 70-1113 REVISION 9
L-1.16
Arrays of finished reactor fuel rods and/or
(
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assemblies in any of the inner metal containers of m
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 CFR 20.302(a) and 10 CFR 20.305, to treat or dispose of waste and scrap material containing special nuclear material by incineration.
(
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DEC 3 01932
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ANNEX A GUIDELINES FOR DECO:iTAMINATION OF FACILITIES AND EQUIPMENT PRIGR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSES FOR SYPRODUCT, SO'JRCE, OR SPECIAL NUCLEAR MATERIAL
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i U. 5. Nuclear Reculatory Comission i
Division of Fuel Cycle and Material Safety Washington, D.C.
20555 July 1982 LICC'ISE SNM-1097 DATS 7/01/85 PAGE DOCKET 70-1113 REVISION 9
I I-1.18
r'T, The instructions in this guide, in conjunction.with Table 1, specify the
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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'l 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 belcw 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-inaticn at these locations is likely to be representative of centamination on the interior of the pipes, drain lines, or 7-ductwork. Surfaces of premises, equipment, or scrap which are
(,j 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.
Up:n request, the Comnission 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 radicactive 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 the premises, equipment or scrap, are unlikely to result in an unreasonable risk to the health and safety of the public.
i LICENSE SNM-1097 DATE:
7/01/85 p;,c t l
DOCKET 70-1113 REVIstoN
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9 I-1.19 l
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5.
Prior to release of premises for unrestricted use, the licensee
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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 P.aterial Safety, USNRC, Washington, D.C.
20555, and also the Administrator of the NRC Regional Office having jurisdiction.
The report shoul( be filed at least 30 days prior to the planned date of abar. dor. ment.
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.
Folicwing review of the report, the NRC will consider visi. ting the facilities to confirm the survey.
,mb LICE *lSE Stim-1097 DATE 7/01/85 PAGE DOCKET 70-1113 RtvIs 10;;
9 I-1.20
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O Inua.. e ACCEPTABLE SURFACE C0fiTAfilflATI0ti LEVELS f.UCLICE5 AVERAGEbcf MAXIMutibdf REMOVADLEbef 8
U-na t U-235, LI-238, and 2
2 2
associated decay products 5,000 dpm a/100 cm 15,000 dpm a/100 cm 1,000 dpm a/100 cm Transuranics Ra-226. Ra-228, Th-230. Th-228 Pa-231, 100 dpm/100 cm2 300 dpm/100 cm2 20 dpm/100 cm2 Ac-227, 1-125, 1-129 I
Ra-223. Ra-221, U-232, 1-126, 1000 dpm/100 cm2 3000 dpm/100 cm2 200 dpm/100 cm 1-131, 1-133 Deta-gama emitters (nuclides with decay codes other than
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1000 dpm sy/100 cm2 alpha emission or spontaneous 5000 dpm sy/100 cm 15,000 dpm sy/100 cm fission) except Sr-90 and others noted above.
- there surface contamination by both alpha-and beta-gamma-emitting nuclides exists, the limits established for alpha-and beta-ganna-emitting nuclides should apply independently.
b s used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material as detemined by correcting the A
counts per minute observed by an appropriate detector for background, ef ficiency, and geometric factors associated with the instrumentation.
CMeasurements of average contaminant should not be averaged over more than I 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 amodnt of removable radioactive material per 100 cm2 of surface area should be determined by wiping that area with dry filter or sof t 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.
fih2 average and maximum radiation levels associated with surface contamination resulting from beta-gamma emitters should not exceed 0.2 c. rad /hr at I cm and 1.0 mrad /hr at I cm, respectively, measured through not more than 7 milligrams per square centimeter of total absorber.
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