ML20028F883
| ML20028F883 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 12/14/1982 |
| From: | Vaughan C GENERAL ELECTRIC CO. |
| To: | Evans L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 21757, NUDOCS 8302040586 | |
| Download: ML20028F883 (9) | |
Text
{{#Wiki_filter:~T)- ///3 . e GENER AL h ELECTRIC NUCLEAR ENERGY PRODUCTS DIVISION g WILMINGTON MANUF ACTURING D CASTLE H AYNE ROAD. P. O. BOX 780. WILMINGTON, N. C. 28402. (919) 343-m D ce er 14, 1989 Director Office of Nuclear Material Safety & Safeguards y h.g.C'f U. S. Nuclear Regulatory Commission p s a Washington, D. C. 20555
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'-\\ EbMns Attention: Mr. _W. --Tv-Crow Section Leader i DECgi,V352? 9 O L1 anium Process Licensing Section W g,faca M/S 396-SS W 4 / 4 n S o KETED Gentlemen: 4 ussac c -8 g JAN 101983 > :-
Reference:
NRC License SNM-1097, Docket #70-1113 Nvss
Subject:
URANIUM PROCESS MANAGEMENT PROJECT - MAIL SECTION O DocktictERx CONSTRUCTION & USE OF FACILITIES & EQUIPMENT N Application Amendment N-18/S-32 D ~ With reference to activities authorized by NRC License SNM-1097, General Electric Company hereby applies for authorization to allow the construction of uranium process management facilities and the operation of the facilities and associated equipment in accordance with information submitted in the attachment to this letter. The project relocates a number of current operations and re-arranges them with some new process equipment which improves general operating safety and further reduces environmental effluents. This projects also includes the construction of two minor adjunct structures attached to the current fuel manufacturing building with a total additional roofed area of approximately 4000 square feet. This project is consistent with and necessary to support the General Electric " Closure & Decommissioning Plan" dated 6/12/81 (Chapter 4.0) and approved by the NRC on 12/11/81. The project also results in a positive environmental impact related to currently approved operations as described in the attachment. General Electric's assessment is that this amendment is not specifically covered by the requirements of 10 CFR 51.5(a) or (b) and, therefore, no Environmental Impact Statement, Negative Declaration or Environmental Impact Assessment are required under the exclusion provisions of 10 CFR 51.5(d)(3) and (4). Applicant......,,h*(* * 'fg* " I Check No..oETp, 3, ^ml,""lQcam m.:i.e.p/W7 i D tc Check Re /,i,f *** 8302040586 821214 i R ece ive d B *
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1 i GENER AL $ ELECTRIC Director - ONMSS December 14, 1982 Page 2 The current schedule requires construction to begin no later than June 1,
- 1983, and operations involving nuclear material are identified to begin October 1,
1984. Our current licensing schedule indicates that we will be submitting detailed license and demonstration information for operational safety and safeguards requirements during the period of November 1983 through February 1984. In order that firm contracts and approvals for the construction phase of the project can be finalized in January 1983, General Electric needs to receive NRC concurrence for construction as soon as possible. Of course, NRC approval of the operating phase of the amendment will not be required until an appropriate time in 1984 and GE recognizes that significant additional information must be submitted in advance of this determination. GE will be working closely with the NRC to establish appropriate scope and schedules for the additional licensing information. Pursuant to 10 CFR 170.31, enclosed is a General Electric Company check for $41,500 for processing this amendment request. General Electric Company personnel would be pleased to discuss this matter with you and members of your staff as you may deem necessary. Very truly yours, GENERAL ELECTRIC COMPANY GM *t-Charles M. Vaughan, Manager Licensing & Nuclear Materials Management M/C J26 CMV:bsd NSD/SGD-L Enclosure Attachment
a GEN ER ALh ELECTRIC Director - ONMSS-December 14, 1982 Attachment - Page 1 -URANIUM PROCESS MANAGEMENT PROJECT (UPMP) PURPOSE The purpose of this project is' to integrate the recovery and recycle of uranium from waste streams and scrap into the normal process operations for the current fuel fabrication facility.. l LOCATION The location of the facility modifications are identified on the attached figure. The shaded area of the existing fuel manufacturing building annotated "1" will be modified to incorporate most of the integrated operations. The addition annotated "2" will be a high profile structure which will blend with the existing fuel manuf acturing building architecture. The-structure annotated "3" will be primarily a chemical make-up area with assorted tanks w'.ch, will support the nuclear manufacturing activities bat will r... contain nuclear material. BUILDING CONSTRUCTION The majority of the construction will involve modification and rearrangement of space within the fuel manufacturing building as shown in the attached _ figure. Additional process and support areas will be housed in attachments to the existing primary structure. The high-profile, structural extension to the north will add less than 1,000 square feet of roofed area and will be similar to the current construction of the fuel manufacturing building. The single-level, structural extension to the west will have a roofed. area of less than 3,000 square feet. The design will i I adhere to the standard Metal Building Manufacture Association i guidelines and internal GE building standards. All major utilities and support services for the operations will E -be supplied from or supported by existing systems which are used and installed in the - fuel manuf acturing build ing. An add itional i L
~ GENER AL h ELECTRIC Director - ONMSS December 14, 1982 Attachment - Page 2 exhaust system will be provided for gaseous ef fluents of less than 20,000 cubic feet per minute. Existing land areas to be occupied by the appendages to the existing building are presently paved. No additional areas exceeding one-half acre will be cleared of natural vegetation and the present drainage area flow pattern will be maintained or improved within the construction boundary area. All construction will be in accordance with all State and local building, fire and safety codes. BUILDING USE Currently, waste treatment, recycle and certain recovery operations are conducted at various locations within the facility as defined in the current license. Some scrap recovery operations are performed offsite by nuclear vendors. The new construction and modification to a section of the fuels manufacturing building will allow consolidation and integration of these operations within the current process. Add it ionally, it will allow the installation of improved technology and make possible a more self-sufficient operating capability for the facility. This project consists of three basic process elements to be installed. Each is briefly described below: (1) Advanced Waste Treatment Each of the present three uranium-bearing waste streams will be treated to recover uranium prior to release of the waste streams to the current waste treatment facilities and to the subsequent lagoon systems. The proposed uranium recovery processes will represent an environmental improvement by recovering and recycling valuable uranium which would otherwise be disposed of as waste. (2) Uranium Scrap Recycle This project element includes uranium scrap pre-treatment, ~ scrap dissolution, and solvent extraction facilities to
GENER AL & ELECTRIC Director - ONMSS December 14, 1982 Attachment - Page 3 recover uranium from scrap and sludges and to produce pure uranyl nitrate. (3) Uranyl Nitrate Conversion The existing uranium purification system (UPS) operation will be modified as part of this project. RADIOLOGICAL SAFETY Since the majority of the operations planned in the new/ modified manufacturing area are similar to those currently performed in the
- facility, the radiological safety procedures and programs will remain the same as those defined in the current operating license.
Implementation of these operations will be controlled to the same criteria currently required by license and regulations. In
- summary, no significant radiolog ical safety problems are expected.
NUCLEAR CRITICALITY SAFETY Nuclear criticality safety for this project will be treated in accordance with the General Electric currently licensed criteria. While the project will require an extensive volume of criticality safety
- analysis, General Electric currently has available qualified analytical codes for performing the calculations.
The process systems to be evaluated appear to be generally the same as those currently evaluated for the current operation. Details of the nuclear criticality safety demonstration for the project will be provided later in the cycle. ENVIRONMENTAL Construction Phase: The modifications to the existing fuel manuf acturing building will be accomplished using conventional construction techniques. This
GENERAL $ ELECTRIC Director - ONMSS December 14, 1982 Attachment - Page 4 facility is already in use for industrial applications. The modifications will not change the current environmental impact of l the facility. The two minor additions (maximum of 4,000 square feet) to the fuel mar uf acturing building ate to be constructed on land which is s a)ceady evaluated as acceptable for industrial use and is within tne current fuel manufacturing complex. Conventional construction practices are to be utilized and all local codes will be adhered to. This minor new construction will have a minimal impact to the environment. The modifications and new construction are consistent with the land use and environmental evaluations conducted and reported in the General Electric " Environmental Report," NEDO-20197, January 1974. Oyerational Phase: The project is projected to have a positive environmental impact with respect to the facility's currently approved operations and with respect to the entire fuel cycle operation. Key positive impacts are as follows: (1) Approximately 90% reduction in uranium discharged to the environment through liquid discards. (2) Approximately 30% reduction in fluoride discharged to the environment through liquid discards. (3) The quantity of sludge produced per kilogram fuel manufactured will decrease. (4) The radioactive concentration of future generation calcium fluoride sludge and its characteristics are expected to be such that it can be disposed of in accordance with Options 1 and 2 of SECY 81-576. ( 5) Climinates the transport of scrap and purified uranyl nitrate on public highways.
GENER AL $ ELECTRIC Director - ONMSS December 14, 1982 Attachment - Page 5 (6) Eliminates risks of hydrogen peroxide in current operations. (7) Provides the capability necessary to adequately decommission the facility in accordance with GE's approved " Closure & Decommissioning Plan." (8) Decreases the current environmental impact of the vaste treatment lagoon system. (9) Atmospheric discharges will remain unchanged and potentially will be reduced. (10) The volume of waste nitrate liquid fuel produced per kilogram decreases. The only potential for a negative impact would be from additional nitrate liquid generated at the GE site offset by the elimination of nitrate emissions at a vendor scrap recovery site. Nitrate discharges will remain the same or only very slightly increased. In summary, the project will result in a positive environmental impact for General Electric fuel manufacturing operation. Minor modifications to the site environmental monitoring program may be required and, if
- required, all such modifications will be transmitted along with the demonstration information later in the cycle.
I l CM Vaughan
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. _ _ _ _ = _ _ - - .o i GENER AL $ ELECTRIC { Director - ONMSS December 14, 1982 Attachment - Page 6 MAIN FLOOR - FUELS MANUFACTURING BUILDING l I i l l m I i D C3 I, o i i INI ~ k.~ lll _U = i ~ l s I i l z s: L li e a I l l M n i $ h ll [l l 7]I l "a r 2 -g d' ,J Q{! i [ 4r l =#-I l 'i i j i ), I C t 118 i i 2 311 l q.. ill li I
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'd 3 QNk'$N kk li__d-l Y T'-' I M lono M t4RC LICENSE SNM-1097 OATE 5/27/81 PAGE DOCKET #70-1113 REVISION I-1.7
.a.a - -. ~ = -. m &. b r,. a '" LICENSE AMENDMENTS" Docket No. 7D -M 3 .4 William O. Miller, License Fee Management Branch, ADM @d MATERIALS LICENSE AMENDMENT CLASSIFICATION $b!h ms g y Applicant: /9 c W A &< he ic License No: SA> A4 / o f 7 Fee Category: 18 y -{ jTg Application Dated: it-N - F u Received: TC -12 + 1 OfSq Applicant's Classification:' mb ali gm J 4 %q The above application for amendment has been reviewed by NMSS in d M accordance with 5170.31 of part 170, and is classified as follows: I N ';( 1. Safety and Environmental Amendments to Licenses in Fee .x ";j Cateoories'1A throuch 1H, 2A, 2B,~2C, and 4A {'.f! (a) / Major safety and environmental (b) Nino.r safety and environmental (c) Safety and environmental (Categories ID through 1G only) (d) Administrative' 2 Justification for reclassification: 3. The application was filed (a) pursuant to written NRC request and the amendment is being issued for the convenience of the Conmission, or (b) Other (State reason): Signature /fsv/ Division of Fuel Cycle & Material Safety I 2?lff-Date / p,,. [#$. / ~ __x __~_____ = ~__= _____ _- - -
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