ML19275A818
| ML19275A818 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 09/03/1979 |
| From: | Dipiazza R WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| References | |
| WRD-LS&S-831, NUDOCS 7910190146 | |
| Download: ML19275A818 (8) | |
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WRD-LS&S-831 S
U. S. Nuclear Regulatory Cctrmission i
Office of Nuclear Material Safety & Safeguards Division of Fuel Cycle & Material Safety 1
Washington, D. C.
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Attention:
Mr. L. C. Pouse, Chief
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Fuel Processing & Fabrication Branch l
Gentlemen:
Transmittal of Acolication for Amendment to Construct and Use 1
a Waste Storage Building, License SNM-1107, Docket 70-1151 1
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The Westinghouse Electric Corpration hereby requests an amendment to License SNM-1107 to authorize construction and use of a Waste Storage Building in j
accordance with the infor: ration described in the enclosure to this letter.
1 The purpose of this structure is to provide a sheltered enclosure for storage 1
of low level contamnated wastes and equIpent and to serve as a staging area i
for dis;osal of solid wastes. The material consists of contarinated equipent, pipes, valves, etc. primarily from the Controlled Areas that ray be contarirated a
with uranium. The itcms are cleaned prior to being taken to the Waste Storage Building.
i Since radioactive waste handling ard storage are described in the existing i
license, no changes to Sections 2, 3, or 4 are required as a result of this j
request. Attached are changed pages 8,16.1 and 18 which describe the appro-j priate changes to Section 1 of the license.
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Page 16.1 has been modified to clarify the fact that the building and areas j
shown in Figure 1.3.2.1 (page 18) are those used to bandle and/or store licensed j
raterials. A reference to Figure 1.3.2.1 and the revised Subparagraph 1.3.3 j
wuld appear sufficient to describe the authorized places of use of licensed i
materials.
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In su. rnary, the construction of the proposed Waste Storage Building represents I
an overall enviromental improvement since rany of the activitie.s now conducted i
outside will now be perfonned within an enclosure.
1 Jj Construction of the Waste Storage Building is expected to begin in October 1979; y
consequently, we muld appreciate your timely attention to this application.
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U. S. Nuclea:. Regulatory Ca mission Page 2 Septauber 3,1979 Enclosed is a check for $1,400.00 to cover the cost of a minor safety and en-virormental license amendment.
If you have any questions regarding this matter, please write to me at the above address or telephone ne on (412) 373-4652.
Very truly yours, NESTINGHOUSE ELECURIC CORP.
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1180 157
ENCTOSURE TO TPANS?'ITTAL OF SEPTEMBER 3,1979 SNM - 1107, DOCKER 70-1151 WASTE STOPAGE BUILDIt.G i
PURPOSE The purpose of the Waste Storage Building is to provide a sheltered enclosure for storage of low level contaminated wastes and to serve as a staging area for disposal of solid wastes. These activities are currently performed in the open without the benefit of protection frcm the weather.
IOCATION The Building location is shown on revised Figure 1.3.2.1 which also shows the proposed Waste Treatment Building and the new location of the adjacent access road.
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BUIIDING 00NSTRUCTION The bii1 Ming is a " Butler" design, which measures approximately 120 ft. long by 44 ft. wide, and will rest on a concrete slab. The sides of the building i
will be partially open, i.e. the metal sides extend down to approximately 12 ft. from the concrete slab. Ventilators on the roof ridge provide natural l
vmtilation to the structure.
1 The concrete slab has a curb approximately six (6) inches high around the peri-meter of the building and two sumps which drain to the adjacent lagoon. A concrete slab will extend approximately 15 ft. fran the north end of the biilding to facilitate loading and unloading of vehicles.
BUILDING USE Ioa level contaminated solid materials are currently stored in an outside area i
unprotected from the weather. This material m nsists of equi pent, pipes, valves, flanges, containers, etc. which may be contarunated with uranium. Approx 1nutely one half of the building will be used for storage of such itss.
The other half of the biilaing will te used as a staging area for disposal of solid wastes. This will consist of activities associated with waste disposal and maintenance such as container handling, loading of containers, surveillance, vehicle loading and imim ing, etc.
a No uraniun in dispersible form will be permitted in this area. Cbntaminated itens will be suitably protected or containerized to prevent dispersion.
PADIOIDGICAL SAFEIY Itms stcred in this b1i1 Ming typically originate in the bhnufacturing Plant. The radiological safety controls which apply to these materials are described in sub-paragraph 1.3.3 of the existing license and include survey arxi release by the radia-tion function and containerization of the matarial as appropriate to prevent the spread of centamination.
Frcm a radiological standpoint, the Waste Storage Building rept v an
- e-ment over existing operations since container deterioration shch
//80 /S~8'
RADIOIDGICE SATTY (CCNr.)
Besides the surveys described above, the radiation protection function will conduct ruttine surveillance to assess the effectiveness of contamination ccntrol practices, including fixed and smcarable alpha surveys and air sampling if airborne particulates are posssible.
In sumary, no significant radiological safety problans are emed. ~ Any its such as a drum or piece of equi rent which requires raintenance which may cause l
significant contamination will te returned to the Manufacturing Plant where the work can be performed under controlled conditions.
NIX 1 EAR CRITICEITY SAmrY Contaminated itens will be visually inspeed to assure that no significant acct. -
lation of radioactive material is present. Consequently, it will not be necessary to control storage of such iters frcm a nuclear criticality viewpoint.
Containerized materials will be limited to a maximum of 350 grams U-235 per con-tainer and a maximum concentration of 5 grams U-235 per cubic foot.
HWIRhm The environmental impact will involve the follcwing: (1) excavation of an approxi-nately 6000 ft2 area for the Waste Storage Building, (2) relocation of the access road to approximately 20 ft. east from its present location. Refer to Figure 1.3.2.1 for exact locations.
Most of this ground has already been mmited to the existing contaminated equip-ment storage area and to tne existing access road. The Waste Storage Building will be constructed on this ccnmited area. The only environmntal.ur. pact of this construction will involve preparation for installatien of the poured concrete slab.
Conventional aanstruction techniques will be used.
The relocated a ess road will be of dirt construction identical to the existing road. Again, conventional construction techniques will be used.
The total cannited land area renains well below that estirated in the 1975 Westing-1 ruse Environmental Evaluation.
As indicated above, the operations will be controlled to assure that airborne con-centrations are well below MPC for unrestricted areas as listed in 10 CFR 20 Appendix B, Table II. Any water accumulation on the concrete slab will be drained to the two sumps and then to the adjacent storage lagoon.
1180 159
SNM-1107 FEVISION RECORD Revision Date of No.
Revision Pages Revised Revision Reason 9
6-12-79 18 Md locations of process area within plant expansion.
9 6-12-79 194c Md Docket No., Dates and Revision No.
to bottan of page.
9 6-12-79 194i Provide additional information on steps -
to be taken on systen loading.
9 6-12-79 194j tdify ash container limit to correspond to MPV fran Figure 2.3.2.1.
9 6-12-79 194k Mdition of a statement referencing the autcmatic shutdown provisions of sub-paragraph 2.2.12.
9 6-12-79 122a Md identification for each process.
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6-12-79 194ad Correct geanetry fornula, K ff reference, e
l and solid angle values.
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6-12-79 122b New Figure 1.9.4.1 with V1082 as the center elenent.
10 9-3-79 18 Md locations of Waste Storage Building, Fixed Calcitrn Fluoride Storage Area, HF/
UNH Mixing Building ard the proposed M-Vanced Waste Treatment Building 10 9-3-79 16.1 Md a description of the Waste Storage Building.
10 9-3-79 16 Delete description of storage of low-level contaminated wastes.
n' 1180 160 f
Docket 70-1151 Octo: 8-24-74 Revision No.10 Date: 9-3-7 9 Page 8
SNM-1107 i
1.3 Site Description 1.3.1 Geocrachical Location and Topocraphy The Westinghouse NFD Columbia Site is located approximately 10 miles southeast of Columbia, South Carolina, just off
- t S.C. Route 48, in a semi-rural area.
It consists of a plot of approximately 1156 acres which is nearly level.
The licensed facility is on a knoll approximately 40 feet above the water level of the nearby Congaree River.
j Figure 1.3.1.1 shows the geographical location of the site.
1.3.2 Location of Buildincs Within the Site Figure 1,3.2.1 shows the relative locations of the buildings on the site.
All existing buildings are occupied by the Manufacturing Department of the i
Nuclear Fuel Division.
l.3.3 Description of NFD Buildines The building in which NFD-Manufacturing operations are conducted consists mainly of high-bay manufacturing areas.
It is constructed with a structural steel framework and cast concrete curtain walls.
Adjoining the east side, j
of the building is a two-story office building.
All significant quantities of material authorized under this license are received, processed and stored within the i
Manufacturing NFD areas.
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1180 161 x
Docket 70-ll51Date: 8-24-74 Revision No.10 Dofe:
9-3-79 Page 16
SM4-1107 1.3.3 (mntinued)
Iow-level contaminated wastes are stored in the Waste Storage Building located to the south of the Manufacturing Building as shown in Figure 1.3.2.1.
Prior to transfer to this area, contaminated itans are visually inspected to ensure that no accuaulation of radioactive material is pre-sent, and then surveyed and released by the radiation protection function in accordance with the following contamination limits: (1) 25,000 dpVdm2_
-fixed alpha and (2) 2500 dpVdm2-retovable alpha. Contaminated itms which exceed either of these limits, or contain inaccessible surfaces or areas where radioactive material a m w L,tions could exist, are bagged and taped or otherwise containerized as appropriate to prevent the spread of contamination.
The specific buildings and areas in which licensed materials may be handled and/or stored are shown on Figure 1.3.2.1.
In addition to these locations, miscellaneous liunsed materials may be stored in various areas within the perimeter chain linP. fence. These include (1) T6 cylinders awaiting trans-fer into the Manufacturing Building, (2) centainerized SNM within covered trailers, (3) shipping containers or equivalent awaiting transport or trans-fer to other areas, (4) miscellaneous drun storage (egty UNH contaminated drurs, contaminated waste oil, etc.). Existing license conditicns are used to control outside storage of SNM with regard to nuclear criticality safety and contamination control.
1180 162 Docket 70-ll5Date:
8-24-74 Revision No. 10 Dofe:
9-3-79 Page 16.1
SNM-1107 El$ECTRICSUB-STATION
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TANK TARM CALCIUM FLUORIDE LAGOCN 62 CALCIUM FLUORIDE LAC 00N #1 WAT1:R 1 At4K PUMP IIOUSE STORM RUNOFF TO FIXED CALCIUM UPPER SUNS::T LAKE i,
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SCALE OF FEET COLUMBIA SITE BUILDING LOCATIONS PLANT ENTRANCE FIGURE 1.3.2.1 4 /' 4 *'" A Docket 7 0-1151 Date:
8-24-74 Revision No.10 Date:
9-3-79 page T8