ML20140B707
| ML20140B707 | |
| Person / Time | |
|---|---|
| Site: | Framatome ANP Richland |
| Issue date: | 08/31/1981 |
| From: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20140B699 | List: |
| References | |
| NUDOCS 8109140371 | |
| Download: ML20140B707 (90) | |
Text
{{#Wiki_filter:, . _ __ . _ -__ -. - - - __ _ _ _ . . ._ l.... 4 L i ENVIRONMENTAL IMPACT APPRAISAL EXXON NUCLEAR COMPANY j NUCLEAR FUEL FABRICATION PLA.'F ! RICHLAND, WASHINGTON i RELATED TO LICEf ~ ' RENEWAL OF SPECIAL NUCLEAR MATERIALS LICENSE NO. SNM-1227 DOCKET N0. 70-1257 - 1 i i 3 i PREPARED BY DIVISION OF FUEL CYCLE AND MATERIAL SAFETY , U. S. NUCLEAR REGULATORY COMMISSION i August 1981 8109140371 810813 PDR ADOCK 07001257 C PDR 4 v-* -v v e--.r-e-we-,. ,-,,----,ww--e r, w-,-- %--.-, - w+e,~,w-e.--,-..-www-*-y, , w-- -----w----ww----.-,.,--mm ==w,- ---wew-e- -e*rw-e-+---&-t -
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SUMMARY
The objective of this ret,or t is to assess the environmental impact of the proposed renewal of Exxon Nuclear Company's (ENC) license number SNM-1227. The assessment has been prepared in accordance with the CEQ Guidelines presented in the Code of Federal Regulations, Title 40, Chapter 1500 (40 CFR 1500) and the NRC Regulations presented in 10 CFR 51. Historically the effluents of ENC's plant have resulted in small impacts to the quality of the 4 cal environment. Furthermore, the effects associated with the continued operation are projected to result in small impacts to the environment. The findings of our assessment are sumarized in the following four points: o The radiological releases during normal operations of the ENC plant result in doses to the nearest resident that are a small percentage of the 25 mrem / year limit specified in 40 CFR 190. The future projected doses from normal operations are expected to be small. o Radiological assessments for a hypothetical accidental criticality and a larger UF6 release were performed using conservative assumptions. The resulting dcse levels at the nearest industrial site and the nearest residence show that there would be no significant consequences to humans or the environment. o The environmental monitoring program of test wells detected leakage from the lagoons. The investigative action limit specified in ENC's license was exceeded and action was taken. Investigation of the leakage found several possible causes of the leaks; and the containment system has been redesigned incorporating double liners for the lagoons as well as a leak detection system below and between the two liners. Continued monitoring of the test wells indicates that tha corrective action has had a positive effect on the concentrations of various contaminants in the groundwater. 'I
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l o Releases of fluorides under normal operations and for a large accidental UF 6 release have been assessed. The concentration of fluoride in vegetation is inconsistent with measurements of fluoride in the stack releases if the ENC plant is the source of the fluoride found in vegetation (see Section 3.3.2). The measurement of fluorides in the stacks is significantly different from the EPA recomended procedure. The staff requires that ENC modify their method for measuring total fluoride releases from the stacks (see Section 3.3.4).
TABLE OF CONTENTS Section Page 1.0 PURPOSE AND NEED FOR THE PROPOSED ACTION. . . . . . . . . . I
1.1 BACKGROUND
INFORMATION. . . . . . . . . . . . . . . . . . 1
2.0 INTRODUCTION
AND ORGANIZATION . . . . . . . . . . . . . . . 2 2.1 SCOPE . . . . . . . . . . . . . . . . . . . . . . . . . . 2 2.2 ASSESSMENT ACTIVITIES . . . . . . . . . . . . . . . . . . 2 2.3 ORGANIZATION. . . . . . . . . . . . . . . . . . . . . . . 2 3.0 CHANGES IN SITE AND FACILITY DESCRIPTIONS; ENVIRONMENTAL MONITORING PROGRAM OPERATIONAL DATA; AND ALTERNATIVE. . . . 3 3.1 SITE DESCRIPTILN. . . . . . . . . . . . . . . . . . . . . 3
)
3.1.1 Demography. . . . . . . . . . . . . . . . . . . . . . . 3 3.1.2 Meteorology and Climatology . . . . . . . . . . . . . . 3 3.1. 3 - Hydrology . . . . . . . . . . . . . . . . . . . . . . . 15 3.2 FACILITY DESCRIPTION. . . . . . . . . . . . . . . . . . . 15 3.3 ENVIRONMENTAL MONITORING AND OPERATIONAL DATA . . . . . . 17 3.1.1 Liquid Effluents. . . . . . . . . . . . . . . . . . . . 17 3.3.1.1 Process Cooling Water . . . . . . . . . . . . . . . . 17 i 3.3.1.2 Chemical Wastes . . . . . . . . . . . . . . . . . . . 22 3.3.1.3 Sanitary Wastes . . . . . . . . . . . . . . . . . . . 12 3.3.2 Gaseous Effluents . . . . . . . . . . . . . . . . . . . 35 3.3.3 Solid Wastes. . . . . . . . . . . . . . . . . . . . . . 44 I 3.3.4 Conclusions and Recommendations Environmental Monitoring Programs . . . . . . . . . . . . . . . . . . 44 3.4 ALTERNATIVE ACTION. . . . . . . . . . . . . . . . . . . . 45 i 3.4.1 No Action . . . . . . . . . . . . . . . . . . . . . . . 45 4.0 AFFECTED ENVIRONMENT 4.1 AFFECTED ENVIRONMENT OF THE PROPOSED ACTION . . . . . . . 46 4.1.1 Air Quality . . . . . . . . . . . . . . . . . . . . . . 46 4.1.2 Water Quality . . . . . . . . . . . . . . . . . . . . . 46 l 4.1.3 Te rre stri a l Qual i ty . . . . . . . . . . . . . . . . . . 47 4.2 AFFECTED ENVIRONMENT OF ALTERNATIVES . . . . . . . . . . 47 4.2.1 No Action, i.e. , Denial of any License denewal. . . . . 47 1 l
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TABLE OF CONTENTS (Continued) Section Page 5.0 ENVIRONMENTAL CONSEQUENCES. . . . . . . . . . . . . . . . . 48 5.1 E FFECTS OF OPERATIONS . . . . . . . . . . . . . . . . . . 48 - 5.2 ACCIDENTS AND EFFECTS . . . . . . . . . . . . . ... . . . 51 5.2.1 Analysis o f Large UF . Release . . . . . . . . . . . . . 51 5.2.2 Criticality Report. 6.................. 52 6.0 MATERIALS AND PLANT PROTECTION. . . . . . . . . . . . . . . 55 6.1 PHYSICAL PROTECTION AND MATERI AL ACCOUNTING . . . . . . . 55 APPENDIX A A.1 REFERENCES 11 l
b LIST OF FIGURES Figure Page 3.1 Exxon Nuclear Company Site Location . . . . . . . . . . . 4 3.2 Exxon Nuclear Company Site. . . . . . . . . . . . . . . . 5 3.3 Surrounding Development . . . . . . . . ......... 8 3.4 Wind Characteristics. . . . . . . . . . . . . . . . . . . 11 3.5 Isocies tic Lines. . . . . . . . . . . . . . . . . . . . . 16 3.6 Offsite Environmental Station Locations . . . . . . . . . 18
- 3.7 Liquid Effluent Discharge Routes. . . . . . . . . . . . . 21
! 3.8 Test Well Locations (Relative to ENC Lagoons) . . . . . . 24 3.9 Average Monthly Fluoride Concentrations (PPM) in Test Well No. 1. . . . . . . . . . . . . . . . . . . . . . . . 28 i 3.10 Average Monthly Fluoride Concentrations (PPM) in Test I Well No. 2. . . . . . . . . . . . . . . . . . . . . . . . 29 i 3.11 Average Monthly Fluoride Concentrations (PPM) in Test Well No. 3. . . . . . . . . . . . . . . . . . . . . . . . 30 3.12 Average Monthly Fluoride Concentrations (PPM) in Test Well No. 4. . . . . . . . . . . . . . . . . ... . . . . . 31 3.13 Sampling Head, Lagoon Leakage Monitor . . . . . . . . . . 33 3.14 Uranium Released from UO 2 Building Exhaust Stacks Per Ton of Throughput . . ................. 37 3.15 Fluoride Released from U0 Exhaust Stacks'Per Ton of Uranium Throughput. . . 2 ................ 40 i
i 111 l .
t LIST OF TABLES Table Page 3.1 Estimated Population Distribution (1980) Within 50 Miles of the Exxon Nuclear Site . . . . . . . . . . . . . . 6 3.2 Projected Population Distribution (1985) Within 50 Miles of the Exxon Nuclear Site . . . . . . . . . . . . . . 7 3.3 Industrial Population Distribution (1980) Within 5 Miles of the Exxon Nuclear Site . . . . . . . . . . . . . . 9 3.4 Comparison of 1980 Population Projections With 19C; Census 10 3.5 Joint Frequency Distribution (5) of Wind Speed, Wind Direction and Atmospheric Stability Applicable to the Exxon Nuclear Plant Si te. . . . . . . . . . . . . . . . . . 12 3.6 Annual Average Atmospheric Dilution Factors . . . . . . . . 14 3.7 Environmental Surveillance Program. . . . . . . . . . . . . 19 3.8 Quantity of Chemicals Discharged to the Lagoon. . . . . . . 23 3.9 Evaporation Lagoon System Test Well Results . . . . . . . . 25 3.10 Liquid Effluent Monitoring Program. . . . . . . . . . . . . 34
, 3.11 Public Sewage Treatment Plant Liquid Sample . . . . . . . . 36 3.12 Semiannual Radiological Liquid Effluent Releases to the Pu bl i c Sewe r . . . . . . . . . . . . . . . . . . . . . . . . 36 3.13 Semiannual Radiological Air Effluent Releases . . . . . . . 38 3.14 Micrograms Fluoride Per Gram Vegetation . . . . . . . . . . 41 3.15 Summary of Fluoride Content of Environmental Vegetation Samples . . . . . . . . . . . . . . . . . . . . . . . . . . 43 5.1 Dose Commitments Based Upon Normal Operating Gaseous Radiological Releases . . . . . . . . . . . . . . . . . . . 49 5.2 Estimated Doses (REM) From Postulated Accidents . . . . . . 53 iv
1.0 PURPOSE AND NEED FOR THE PROPOSED ACTION The action proposed is renewal of the Exxon Nuclear Company's (ENC) license for acquisition, storage, processing, and disposition of special nuclear materials (SNM). The action proposed would authorize the continued possession and use of up to 10,000 kg of U-235 (<5% enrichment) and possession of 100 kg of plutonium of which at least 90 kg is in encapsulated form. The purpose of the action proposed is to provide the enabling mechanism to permit the continuance of the manuf acture, by ENC, of low-enriched uranium fuel for light water reactors (LWR) to provide continuing ccqtribution to the maintenance of an ample supply of fuel for ENC's customers.
1.1 BACKGROUND
INFORMATION On September 14, 1971 ENC was granted an interim operating license for nuclear fuel manuf acturing at their Richland, Washington, site. In March 1974 the Fina EnvironmentalStatementrelatedtotheoperationoftheuraniumoxidefuelplant{ was published and in June of the same year the Final Envirpnmental Statement related to the operation of the mixed oxide fabrication plant was published. A full term license was issued April 22, 1974. The operations at ENC nuclear fuel manufacturing site have been in accord with the processing described in the two environmental statements. As the production capacity was increased, ENC twice requested (references 3,4), and was granted, license amendments to authorize the operation of expanded uranium fuel manufacturing capacity. At the present time, the operation involving the use of plutonium has ceased. If the licensee plans to resume such operation in the future, a license amendment will be required and an environmental impact assessment will be prepared by NRC, ! l
2.0 INTRODUCTION
AND ORGANIZATION 2.1 SCOPE This Environmental Assessment of a proposed operating license renewal for the Exxon Nuclear Company has been prepared in accordance with the Code of Federal Regulations, Title 10, Part 51 (10 CFR 51), " Licensing and Regulatory Policy and Procedures for Environmental Protection," and Sections 51.5, 51.7, 51.20, 51.21, 51.30, and 51.70 thereof. This assessment was made by preparing estimates of the eny fronmental consequences of continuing manufacture of low enriched uranium nuclear fuel and comoaring these estimated consequences with applicable Federal standards. The specific Federal standards used were (1) 10 CFR 20.105, " Permissible Levels of Radiation in Unrestricted Areas" (2) 10 CFR 20.106, " Radioactivity in Effluents in Unrestricted Areas" (3) 40 CFR 190.10, " Environmental Standards for the Uranium Fuel Cycle" and (4) 40 CFR 141.11, " Maximum Contaminant Levels For Inorganic Chemicals (National Interim Primary Drinking Water Regulations)". In addition, the concentrationr, of fluoride rgleases and fluoride in vegetation were compared to the Washington State Standards . Because the facility is an operating Mant and actual plant effluent releases have been monitored and are documented, this evaluation has addressed the most significant environmental indices. These relate to demography, site meteorology data, hydrology, control of effluents, environmental monitoring, and accident potential. 2.2 ASSESSMENT ACTIVITIES
- During assessment preparation, applicable Federal and State legislation and Federal guidelines were reviewed. Appropriate Federal and State ageticies were contacted in person, by phone and/or mail. Conferences were held with facility management and staff. A site visit, including surrounding areas, was conducted.
Data from the site visit and personnel contacts were collected, evaluated and analyzed for incorporation into the final report. 2.3 ORGANIZATION This assessment is organized according to the guidelines established by the President's Council on Environmental Quality (40 CFR 1506) and the U.S. Nuclear Regulatory Comission (10 CFR 51). Section 3.0 sumarizes the principal changes in the characteristics of the site and facility since the previous environmental statements and environmental monitoring programs. The operational data from the environmental monitoring are also presented in Section 3.0. In Section 4.0 the affected environment relative to the operation of the ENC plant is discussed. Section S.O addresses the environmental consequences of the Proposed Action. 2
3.0 CHANGES IN SITE AND FACILITY DESCRIPTIONS; ENVIRONMENTAL MONITORING PROGRAM OPERATIONAL DATA; AND ALTERNATIVE 3.1 SITE DESCRIPTION The Exxon Nuclear Company site coordinates are at 146 0 21' N and 1190 17' W, just inside the northern limit of the City of Richland, Washington, on a 6100-acre parcel of land known as the Horn Rapids Triangle (Figure 3.1). The site is square, consists of 160 acres and occupies the entire Southwest Quarter of Section 15 Township 10 North, Range 28 East, Willamette Meridian in Benton County, Washington . The facility process and ancillary buildings, storage lagoons, offices and parking accomodations occupy an area of approxima91y 26.4 acres in the northeast corner of the site. With exception of tne office buildings and parking areas, the entire facility is fenced with an eight-foot security fence (Figure 3.2). 3.1.1 Demography The City of Richland, in which the Exxon Nuclear Company is located, along with Pasco and Kennewick comprise a metropolitan area known as the Tri-Cities. In 1970 the Tri-Cities population was approximately 56,000. During the past ten l years, due mainly to the increased activities on the Hanford Reservation, the population of the Tri-Cities area has increased to 84,750, i.e., a 51% increase. Table 3.1 shows the 1980 population distribution within a 50-mile radius of the ENC by compass direction and radii interval. Projected population within 50 miles of ENC for 1985 is presented in Table 3.2. Tne developments within a five mile radius of the site are shown in Figure 3.3 and the industrial population distribution within five miles is shown in Table 3.3. The 1970 population within a 50-mile radius of the ENC was 184,294. Today's population within that radius has increased by 36% to 250,220. Table 3.4 compares the 1980 data to the projections made in 1974 (reference 2). It is evident from Table 3.4 that the area, particularly within 20 miles of the plant, has exceeded the growth projections. The large growth is due primarily to increased activities on the Hanford site, including the location of several new power plants adjacent to the Hanford site. 3.1.2 Meteorology and Climatology Measurements of the wind characteristics in the vicinity of the Exxon Nuclear site are sumarized by Figure 3.4 and Table 3.5. The annual average X/Q values for the ENC site are tabulated on Table 3.6. The prevailing wind at the Exxon Nuclear site is from the southwest along the Yakima River corridor, which enters the Columbia Basin near the site. Secondary direction frequency maxima are from the northwest and the southeast along the axis of the Columbia River Valley, and the lowest frequencies are from the east and northeast. This pattern holds most of the year, with the exception of a few months in the fall and early winter, when the wind directi:n is predominantly from the north and northwest. 3
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Table 3.1 Estimated Population Distribution (1980) Within 50 Miles of the Exxon Nuclear Site (8y Compass Sector and Distance) Compass Miles Sector 0-5 5-10 l'0i 26 26~30 30-40 40-50 TOTAL N 0 O 140 520 1,350 1,050 3,060 NNE O 20 250 530 4,450 1,420 6,670 NE O 130 700 1,500 1,220 550 4,100 ENE 50 150 500 180 270 250 1,400 E 100 200 250 250 150 550 1,500 ESE 120 2,700 4,260 420 650 900 9,050 SE 2,730 3,780 48,880 2,600 1,160 690 59,840 SSE 13,750 13,030 15,160 410 1,920 1,900 46,170 S 13,710 5,680 4,550 4,670 11,680 3,030 43,320 SSW 960 320 450 260 2,600 1,200 5,790 SW 1,120 240 880 510 320 410 3,480 WSW 170 1,750 1,360 6,200 10,240 810 20,530 W 250 430 1,020 1,650 15,450 17,510 36,310 WNW 0 0 0 1,280 1,300 2,670 5,250 NW 0 0 0 110 590 1,160 1,860 NNW 0 0 O_ 10 300 1,580 1,890 TOTAL 32,960 28,430 78,400 21.100 53,650 35,680 250,220 j
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-a SE 4,250 5,300 58,600 3,100 1,450 720 73,420 SSE 16,000 15,500 18,200 500 2,020 2,000 54,220 S 16,500 6,600 5,300 5,850 13,300 3,400 50,950 SSW 1,750 340 54 0 350 2,750 1,280 7,010 SW 1,200 250 950 600 330 430 3,760 WSW 170 2,000 1,500 7,600 10,550 830 22,650 W 260 450 1, 080 1,750 16,800 18,800 39,140 WNW 0 0 0 1,650 1,330 2,800 5,780 NW 0 0 0 110 620 1,200 1,930 NNW 0 0 0 10 320 1,660 1,990 TOTAL 40,630 34,040 92,810 25,120 58,170 38,140 288,910
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Table 3.5 Joint Frequency Distribution (5) of Wind Speed, Wind Direction and Atmospheric Stability Applicable to the Exxon Nuclear Plant Site Pasquill Wind Direction Wind Speed Stability NE E SE $ SW W NW N Total [ Calm G .10 .11 .26 .14 .12 .058 .097 .20 (presumed F .10 .11 .26 .14 .12 .058 .097 .20 0-0.5 mph) D .033 .035 .087 .046 .042 .019 .032 .065 C .10 .11 .26 .14 .12 .058 .097 .20 All .33 .35 .87 .46 .42 .19 .32 .65 3.59% 0.5-3 mph G .66 .69 1.71 .90 .81 .38 .63 1.28 F .66 .69 1.71 .90 .81 .38 .63 1.28 D .22 .23 .57 .30 .27 .13 .21 .43 C .66 .69 1.71 .90 .81 .38 .63 1.28 All 2.19 2.30 5.71 2.99 2.72 1.26 2.11 4.28 23.56% 4-7 mph F 1.08 1.17 3.49 2.36 3.26 2.12 2.84 2.64 0 .18 .19 .58 .39 .54 .35 .47 .44 C .54 .58 1.75 1.18 1.63 1.06 1.12 1.32 All 1.80 1.95 5.82 3.94 5.43 3.53 4.73 4.40 31.60% 8-12 mph F .38 .24 .97 .95 2.76 2.18 2.96 .94 0 .063 .04 .16 .16 .46 .36 .49 .16 C .19 .12 .49 .47 1.38 1.09 1.48 .47 All .63 .40 1.61 1.58 4.60 3.63 4.93 1.57 18.95% 13-19 mph F .16 .19 .52 2.09 .93 1.47 .29 D .027 .032 .087 .35 .16 .25 .048 C .082 .097 .26 1.04 .46 .74 .14 All .27 .32 .87 3.48 1.55 2.45 .48 9.42% 19-24 mpi: F .24 1.00 .26 .60 0 .039 .17 .043 .10 i C .12 .50 .13 .30 All .39 1.67 .43 1.00 3.49% 25-31 mph F .095 .42 .043 .34 D .016 .070 .007 .057 C .047 .21 .021 .17 . All .16 .70 .072 .57 1.50% 32-38 mph F .18 D .031 i C .092 All .31 .31% 1 l 12 l
- .- . , _ . . -. - - - . . . - . _- . . - -. - - .._ , , -- . . 2
Table 3.5 (Cont'd) Pasquill Wind Direction i Wind Speed. S tability NE E SE S SW W NW N Total 3 Varioble* G .13 .14 .35 .18 .16 .076 .13 .26 0-3 mph F .13 .14 .35 .18 .16 .076 .13 .26 0 .044 .046 .12 .060 .055 .025 .043 .086 , C .13 .14 .35 .18 .16 .076 .13 .26 . All .44 .46 1.15 .60 .55 .25 .43 .86 4.74% Variable # F .067 .072 .22 .15 .20 .13 .18 .16 4-7 mph D .011 .012 .035 .024 .034 .022 .029 .027 C .033 .036 .11 .073 .10 .065 .088 .082 All .11 .12 .35 .24 .34 .22 .29 .27 1.94% !
- Direction frequency distributed proportional to distribution within 0-3 mph class.
# Direction frequency distributed proportional to distribution within 4-7 mph class.
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3.1.3 Hydroloay The local groundwater hydrology at the ENC site vas investigated in late 1977 and early 1978 because of the leakage in the lagoons. As part of this investigation the elevation of groundwater in 15 test wells was determined. From this information isopiestic lines were calculated and their positions shown on Figure 3.5. Water elevation information is presented below for the respective test wells. Test Water Test Water Well Elevation Well Elevation No, MSL (ft)* No. MSL(ft)* 1 353.36 9 353.29 2 353.33 10 353.35 3 353.39 11 353.50 4 353.45 12 353.45 5 353.45 13 353.48 6 353.46 14 353.06 7 353.42 15 353.06 8 353.56
- Average of 10 measurements each for test wells 1 through 13 between March 3, 1980 and January 21, 1981; average of 5 measurements each for test wells 14 and 15 between September 15, 1980 and January 21, 1981. (Test wells are about 25 ft deep.)
According to the ENC staff, these data show that the groundwater elevation at test well no. 8 is higher than that at any of the other test wells, thus supporting the concept of generally easterly flow; also, the groundwater elevations at the test wells west of the lagoon system are higher than those at test wells east of the lagoons . Further, these data support the concept of localized northwardly flow of the groundwater in the vicinity of the lagoon system. ENC staff further state that, based on the chemical characteristics of water in the test wells, groundwater flows in a direction which parallels lines between test wells 1 to 14 and 2 to 15. 3.2 FACILITY DESCRIPTION Tne operations at the Exxon Company's facility consist the development and f abrication of fuels for nuclear reactors. The particular operations have been previously described in References 1 and 2. The U02 fuel manuf acturing process is unchanged from the process described in Refarence 1, only the capacity has changed. The ENC requested and was granted NRC authorization to increase the capacity from 1.4 to 2 tons per day. Included in the licensing actions were requests to expand the storage lagoon system. Authorization was granted to 15
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expand the storage lagoon system. Presently the lagoon system consists of four lagoons (see Figure 3.5) measuring 228 x 201, 235 x 107, 346 x 208 and 244 x 202 feet. 3.3 ENVIRONMENTAL MONITORING AND OPERATIONAL DATA The effluents from the Exxon nuclear plant consist of liquid, gaseous, and solid products, both radiological and non-radiological. The liquid effluents are sanitary wastes, process cooling water, and chemical wastes. Methods used to monitor these liquid effiuents are briefly discussed below and the operational data tabulated in Section 3.3.1. The gaseous effluent is discharged via the stacks. The monitoring methods and operational data are presented in Section 3.3.2. In addition to stack monitoring samples a number of environmental monitoring stations are used to collect additional air samples as well as vegetation samples for various analyses. Data from the vegetation samplings are also presented in Section 3.3.2. Solid waste effluents are discussed in Section 3.3.3. The locations of off-site environmental monitoring stations are shown on Figure 3.6. The environmental surveillance program characteristics, type of sample, frequency of collection and analysis, etc., for the various environmental ampling stations are sumarized in Table 3.7. 3.3.1 Liquid Effluents Liquid effluents from the plant consist primarily of process cooling water, chemical waste liquids, and sanitary wastewater. A schematic representation of the sources of and discharge routes for liquid effluents is shown in Figure 3.7. 3.3.1.1 Process Coolina Water. Process cooling water is the largest component of the liquid effluents. This effluent is normally not contaminated with radioactive material. The tnermal load of the cooling water system is generated by exothermic chemical reactions and heated process equipment. The heat from all of the U02 fue1 manufacturing operations and ancillary systems is equivalent to about 1.2 x 107 Btu per day. The thermal load in cooling water is dissipated in storage. Cooling water discharges average abou t 178,000 gallons per day. During process chemical make-up which is about twice each week, the rate of cooling water discharge is increased to the maximum projected daily volume of cooling water flow which is about 688,000 gallons. All flow into the liquid effluent retention tanks is through a single line from which a :mple stream is continuously withdrawn and composited. The plant design offers alternatives to discharge of process cooling water to the sanitary sewer. The system provides three options fcr disposal of process cooling water: to the chemical process waste storage lagoon, to the Exxon Nuclear property irrigation system or to the Richland Municipal Sewage System. The composite sample, which represents the composition of the full tank, is submitted to a laboratory for analysis before the contents of the tank are pumped to the sewer line. The sample is analyzed for uranium, fluoride, nitrates, 17
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11 N- / E IN MILES \l Plant Ezzon Nuclear Environmental Stations Station No. Direction from Site Distance from Site 1A, 13 NE 450, 2000 ft. 2A, 23 W 450, 2000 ft. 3A, 33 SW 450, 2000 ft. y 4A, 4B SE 450, 2000 ft. 3 NE 1 alle 11 SE 1 mile 12 E 3/4 mile 13 SSE 3 miles i t figure 3.6 Offsite Environmental Station Locations f 18 i
TABLE 3.7 Environmental Surveillance Program Sample Type of Collection Analysis Analyzed Min. Detection Station Samole Frequency Frequency For Level 1-A Air Continuous Monthly Fluoride 0.02 pob Soil Quarterly Quarterly Uranium 0.01 ppm Vegetation Monthly III Monthly Uranium & 0.01 ppm Fluoride 1 ppm 1-B Air Continuous Monthly Fluoride 0.02 ppb Soil Quarterly Quarte-ly Uranium 0.01 ppm Vegetation Monthly (I} Monthly Uranium & 0.01 ppm Fluoride 1 ppm 2-B Air Coatinuous Monthly Fluoride 0.02 ppb Soil Quarterly (Held) --- --- 3-B Air Continuous Monthly Fluoride 0.02 ppb Soil Quarterly (Held) --- --- 4-B Air Continuous Monthly Fluoride 0.02 ppb Soil Quarterly (Held) --- --- 5 Air Continuous Monthly Fluoride 0.02 ppb Soil Quarterly (Held) --- --- Vegetation Quarterly (I) Quarterly Fluoride 1 ppm 11 Air Continuous Monthly Fluoride 0.02 ppb Soil Quarterly (Held) --- --- Vegetation Quarterly (li Quarterly Fluoride 1 ppm 12 Air Continuous Monthly Fluoride 0.02 ppb Vegetation Monthly (I) Monthly Fluoride i ppm 13 Air Continuous Monthly Fluoride 0.02 ppb Soil Quarterly (Held) --- --- Vegetation Quarterly (I) Quarterly Fluoride 1 ppm ENC-City Lift Station (see Table 3.10) STP(2) Liquid Daily Monthly Uranium 0.1 ppm Sludge Quarterly Quarterly Uranium 0.01 ppm Yakima River (3) Liquid Monthly Monthly Uranium, 0.1 ppm Fluoride, 0.1 ppm Nitrate, 0.1 ppm Arrnon!a , 0.1 ppm Sulphates & 1 ppr pH 0.1 unit 19
. . I TABLE 3.7 (continued)
Sample Type of Collection Analysis Analyzed Min. Detection Station Sample __ Frequency Frequency For Level Plant I#) Orinking Water Liquid Weekly Weekly Uranium, 0. l' ppm Fluoride. 0.1 ppm Nitrate. 0.1 pon Amonia. 0.1 ppm Sulphates & 1 ppm pH 0.1 unit Test Conductivity (5) Wells (15) Liquid Monthly Monthly 0.1 umhos/cm (1) Collected monthly during the normal growing season. (2) Richland Municipal Sewage Treatment Plant. (3) Washington State Department of Ecology requirement. (4) For purpose of background determinations. (5) See Section 3.4.4 of ENC's " Application for Renewal of Special Nuclear Material License No. SNM-1227", Document No. XN-2, for Lagoon Leak Action Guides based upon conductivity levels in Test Well water. It should be noted that ENC previously collected weekly samples from each Test Well and analyzed them for uranium, fi-uoride, nitrate, ammonia, sulphates and pH. 20 I
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ammonia, sulphates, sodium, and pH. If the concentrations of any of these constituents exceed criteria based on the range of concentrations for the site water supply, the content: of the retention tanks are quarantined and consigned to a licensed waste disposal contractor for burial. 3.3.1.2 Chemical Wastes. The Exxon Nuclear Company disposes of its process waters in four large evaporation i Sons. These lagoons are provided with impervious liners to prevent the en. tents from leaking into the ground and impacting the area groundwaters. The estimated quantities of chemicals discharged to the lagoon in pounds per day per ton uranium are listed in Table 3.8. The actual flow of chemical waste to the lagoons has varied with production levels and been consistently lower than the predicted values. The minimum liquid level in the lagoon is a death of one foot and this is maintained by diverting process cooling water, as required, from the flow to the municipal sewer system. The flow rate to the lagoon at maximum production levels is predicted to average 14,600 gallons of process chemical wastes per day. This volume is made up of the collected and neutralized process waste streams conveyed to the lagoon by the process sewer system. Measurements of concentrations of uranium, fluorides, nitrates and sulf ates in the evaporation lagoons, taken during 1978,1979 and 1980, show the average concentrations to be as follows': Uranium (U) 178 pom Fluoride (F-) 16,115 ppm Nitrate (NO3 and NH3 ) 19,735 ppm Sulfate (504) 8,052 ppm. Several test wells are used to monitor the groundwater near the lagooa. The locations of these wells are indicated on Figure 3.8. The test wells are sampled weekly. the samples are analyzed for following chemicals or ions: uranium, fluoride, NO3 , NH3 , and 50 4. The annual average concentrations of these chemicals and ions for 1977 through 1980 are suninarized in Table 3.9. During 1977, test wells 1, 2 and 3 were sampled for uranium. In 1978 analytis for uranium was ceased, or no longer recorded as historically the uranium conceni. ration had consistently been below the minimum detection level. New wells 9,10 and 11 were sampled twice for uraniur at commencement of their use. When wells 12 and 13 were put into operation, in 1979 they too were sampled and analysis for uranium was performec. ENC staff prepare plots of the average monthly concentration of the fluoride, nitrates and sulfates for each of the test wells. Plots of the fluoride concentration in test wells 1, 2, 3 and 4 are presented on Figures 3.9, 3.10, 3.11 and 3.12 respectively. Plots of the nitrate and sulf ate concentrations are presented in Appendix A for all test wells. On each plot the action level used w
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Table 3.9 Evaporation Lagoon Syster Test Well Results Element Ions in ppm U F- NO- (as N) 50] NH3 (as N) Test Well #1 1977 <.1 5.39 4'0.55 24.68 60 1978 5.6 72 0.88 597.4 1979 4.8 33.79 0.13 214.7 1980 6.3 50.9 8.7 69.8 Test Well #2 1977 <1. 41.5 145 995 1636.9 1978 84.6 120 261.5 1170 1979 27.7 76 187 819.5 1980 17.8 59.6 159 227.7 Test Well #3
*1977 <.1 4.8 14.4 39.4 479 1978 0.53 62 3.49 253 1979 1.05 35.7 0.12 67.9 1980 0.8 36.9 0.12 109 Test Well #4 1977 0.69 4.57 0.73 23.6 1978 0.54 7.9 1.49 24.9 1979 0.85 8.67 0.12 43.59 1980 0.77 13.8 4.27 163 Test Well #5 1977 1.09 6.67 0.67 25.5 1978 3.8 1.9 5.2 56.6 1979 0.48 2.06 1.47 44 1980 0.36 1.95 0.58 38.2 25
Table 3.9 (Cont'd) Evaporation Lagoon System Test Well Results Element Ions in ppm U F- NO- (as N) NH3 (as N) 50] Test Well 46 1977 0.67 1.74 1.73 27 1978 0.43 2.17 0.95 21.69 1979 0.67 6.5 1.97 58.75 1980 0.37 10.5 0.19 40 Test Well #7 1977 0.57 1.32 2.69 18.57 1978 0.54 1.8 3.24 13.86 1979 0.70 0.18 0.60 52.25 1980 0.43 3.29 0.15 45.14 Test Well 48 1977 0.63 2.12 4.04 13.25 1978 0.53 1.88 1.76 56.02 1979 0.73 1.48 4.85 12.38 1980 0.41 1.81 0.27 10.33 Test Well #9 1978 <.1* 14.9 70.9 68.8 404.8 1979 18.7 71.3 96.6 350.4 1980 18.8 70.5 127.7 286.7 Test Well #10 1978 <.1* C.409 3.7 0.87 32.3 1979 0.69 4.2 0.19 42 1980 0.47 9.1 0.19 51
*Two samples at commencement of operation.
26
Table 3.9 (Cont'd) Evaporation Lagoon System Test Well Results l Element Inns in ppm U F- 50 NO3 (as N) NH3 (as N) Test Well #11 1978 <.1* 0.43 3.98 2.98 143.86 1979 0.53 4.5 0.12 19.66 1980 0.52 1.48 0.68 27.38 Test Well d12 1979 <.1** 0.83 1.92 6.8 68.4 1980 0.59 2.38 19.35 100.6 Test Well 413 1979 <.1** 0.68 1.19 3.5 23.4 1980 0.43 1.93 0.99 29.2
- Two samples at commencement of operation.
** One sample at commencement of operation.
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by ENC are indicated. ENC staff have used these plots to identify leakages from the lagoons. For example, examination of Figure 3.10 shows a sharp rise in the fluoride concentration in test well 2 about mid-year 1973 and again late in 1977. The leaks in the lagoon liners have been investigated by ENC and causes assigned. Generally the causes were due to either some foreign object (e.g., a survey stake and rocks) or the failure of the Petromat liner. ENC staff's solution, since 1977, has been to install a double-Hypalon liner system. The double-Hypalon liner system consists of two layers of Hypalon material with a 4 to 6 inch thick intermediate layer of sand. Leak monitoring devices, like the one shown in Figure 3.13, are installed in the sand layer. There are presently 21,10, 35 and 26 leak monitoring devices installed in lagoons number 1, 2, 3, and 4 respectively. In addition to the between liner leak detection system ENC has installed a total of 8 leak monitoring devices that are under both liners. ENC staff states that this leak monitoring system works, as they have detected a leak in the upper Hypalon liner in lagoon number 2 during 1980. Examination of the concentration of sulfates and nitrates on test well 2 indicates the possibility of a downward trend beginning after 1977 and to a lesser extent in test well 9. ENC staff states that these apparent trends indicate that the problem of leaking lagoon liners has been solved. As part of the ENC license renewal application, ENC staff proposes to change the analyses performed on the test well water samples. ENC proposes a conductivity measurement, on a monthly basis, to replace the measurement for specific chemical concentrations. ENC proposes that the investigative action level be establishd when the conductivity of the samples reaches 2000 umhos/cm. ENC also proposes shutdown and corrective action levels be as follows: NO3 + NH3 (as N), 4000 ppm; F, 600 ppm; 504 ,100,000 ppm; and U, 2000 ppm. These proposed shutdown and correct action levels as wel.' as the corresponding present limits, generally exceed, or are comparable to, the average concentration of the corresponding chemical species in the lagoon liquid stated above. In practice the proposed measurement of conductivity would give less information about the composition of the groundwater since the lagoon liners have leaked and the contaminants from the liquid waste have been detected in the water taken from the test wells. The staff believes that the method of analysis should not be changed at this time. The proposed change of frequency of measurement, from weekly to monthly, was also considered. The staff concluded that the present method of analysis,with a monthly frequency for those wells with concentrations below the present investigative action levels and bi-weekly frequency of those wells with concentrations at or above the investigative action limits, is an adequate measuring program. 3.3.1.3 Sanitary Wastes. Sanitary wastes are discharged to the City of Richland sewage system. The municipal system provides a sewage treatment process and ultimately discharges into the Yakima River at its confluence with the Columbia River. ENC's liquid effluent monitoring program for the ENC-city lif t station is shown in Table 3.10. Composite samples are continuously collected from a sampling stream at the Exxon 32 l
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; e TABLE 3.10 Liquid Effluent Monitoring proaram Discharge Point: ENC-City Lif t Station Sampling Point: ENC-City Lift Station Sample Type: Liquid Sample Collection Frequency: Continuous Sample Analysis Frequency: Daily (Monday through Friday)
Samoles Analytical Minimum Investigate Shutdown & Analyzed For Method Sensi tivity Level Correct Level Uranium Fluorimetry 0.1 10.1 ppm > 0.1 ppm 1 ppm Fluoride Specific ion 0.1 10.1 ppr. 1 ppm 3 ppm Electrode Nitrate Specific ion 0.1 10.1 ppm 10 ppm -- Electrode (as N) Ammonia Colorimetry- 0.1 10.1 ppm 10 ppm -- Nessler Reagent (as N) Sulfates Turbidimetrically 1 1 1 ppm 50 ppm -- (as S04 ) pH pH meter 0 to 14 in 0.1 < 6.5 or < 5 or units > 8.5 > 10 34 -
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Nuclear - City of Richland lift station and submittad daily to an analytical laboratory for analysis. As discussed in Section 3.3.1.1 an analysis of process cooling water is made before each discharge to the sewage system. Furthermore, daily liquid grab samples are also collected from the discharge of the municipal sewage treatment plant, and are analyzed monthly. Additionally, sludge grab samples are collected and analyzed quarterly for uranium. The results of these analyses of sanitary waste liquid effluent are sumarized in Tables 3.11 and 3.12. 3.3.2 Gaseous Effluents With one exception, all building air and proc.ess offgases are passed through two stages of MEPA filters in series before release through stacks approximately 50 feet above ground level (20 feet above roof level). The single gaseous effluent exception is the burner exhaust from the calciner furnace. Calciner burner offgas consisting of propane combustion products is discharged directly to the atmosphere because it is in a closed system isolated from the process with no potential for release of radionuclides. The HEPA filters are certified by the .. manufacturer to be at least 99.97% efficient for the removal of 0.3 micron particles. Liquid scrubber systems followed by dryers are used to remove the corrosive offgases from the UF conversion process and the acid etch tank ventilation exhaustandtoprotechtheHEPAfilters. Airbcrne alpha activity is continuously sampled after each stage of HFPA filtration. Additionally, a single sampling probe, designed to operate isoKinetically, is located in the exhaust stack and continuously samples the exhaust stack. Each statior, draws a representative sample of air through a Gelman Type E glass fiber filter, which is assayed weekly for alpha activity. The senpOitivity of the airborne effluent monitoring system is estimated to be 3 x 10' uCi/mi of alpha activity. The isokinetic stack exhaust sample is analyzr.d weakly for urarium. Results of these analyses are plotted on Figure 3.14 and they are sur, " ?.ed on a semi-annual basis and tabulated in Table 3.13. The high value,11c.38 uCi uranium, for the last part of 1978 is attributed, by ENC, to the startup of the second UF6 to U02 conversion line. The sharp peak in 1976 was caused by a broken UF6 transfer line that resulted in the estimated release of 40 kilograms of uranium inside the UO2 building. An estimated 2.3 grams of uranium were released from the building in the 1976 release. i The principal process chemical airborne wastes released from the Exxon Nuclear UO2 fuels plant are amonium fluoride and hydrogan . fluoride which are generated during the conversion of UF6 to U02 . Fluoride is removed from the conversion process by the process offgas systems. These offgases are liquid scrubbed to remove the fluoride from the air exhausted through the exhaust stacks. Despite the scrubbing system, fluorides are released to the air. The stack exhaust from the UF6 - U02 conversion process is continuously sampled for fluoride and analyzed at weekly intervals. Figure 3.15 shows the measured quantity of fluoride released per 1,000 kilograms of uranium processed. Additicnslly, the plant environmental surveillance program includes the collection of filter paper samples for fluoride analysis at selected locations 35
Table 3.11 Public Sewage Treatment Plant Liquid Sample pCi/ liter Concentration ppm Year Pu* U I NO3 (as N) SO NH3 (as N) 4 1977 <13.5 <1 0.48 7.56 13.23 40.8 1978 <13.5 <.1 1.21 9.2 18.0 311.75 1979 <13.5 <.1 0.539 16.08 13.87 304.2 1980 <13.5 <.1 0.595 3.55 38.33 42
*bse of plutonium at ENC c. discontinued in July 1980.
Table 3.12 Semiannual Radiological Liquid Effluent Releases to the Public Sewer Period Uranium (mci) July - Dec. 1976 1.64 Jan. - June 1977 0.61 July - Dec. 1977 2.05 Jan. - June 1978 1.87 July - Dec. 1978 ~0.88 Jan. - June 1979 2.66 36
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a...... . . , U Releasad (u Ci/ Ton) 37
Table 3.13 Semiannual Radiological Air Effluent Releases Period U,ranium (uC1) Plutonium (uCi) July - Dec. 1C76 7.99 0.28 j Jan. - June 1977 3.91 0.04 July - Dec. 1977 10.64 0.17 Jan. - June 1978 12.78 0.09 July - Dec. 1978 112.38 0.06 Jan. - June 1979 20.68 0.03*
- Subsequently the use of plutonium at the Exxon Nuclear Company has been discontinued.
38
. . l o on-site and off-site. The filter papers, treated with Na2 C03 , are exposed for 30 days with analyses performed monthly. The treated filter oaper method 6f sample collection is passive. No sample of air is drawn through the filter paper;thus the principal form of fluoride deposited on the papers would be the particulate forms. The data presented on Figure 3.15 indicates that the measured fluoride in the offgases is a maximum of about 12 grams and an average of about 6 grams per 1000 kg of uranium processed. *nformation provided by ENC indicates the scrubber efficiencies used in the UF6 t- U02 conversion operations to be 80 to 98%. Rough estimates indicate that the praduction of 1 ton of uranium per day would require about 1.5 tonsof UF6 as raw material and during the processing of UF 6 , 480 kg of fluoride would be released. Assuming that the released fluoride during tne procassing is contained in the building and is scrubbed with water prior to release to the environment through stacks, it is estimated that the overall system, scrubber and f'!ters, would have to have a removal efficiency of 99.998%
in order to limit the final fluoride emission to 6 grams per ton of uranium processed. Based upon the efficiency of the offgas scrubber systems, this 6 gram average valua appears to be small. An indirect measurement of the fluoride releases is the measurement of fluoride in vegetation samples. Vegetation samples are usually collected quarterly for fluoride analysis. , Results of the analysis of vegetation for fluoride are presented in Table 3.14 and sumarized in Table 3.15. Table 3.14 shows the fluoride accumulation, measured monthly, at sampling stations 1A,1B, 5,11 and 12. This data indicates that on occasions concentrations of fluorides have exceeded 40 parts per million and during the sumer of 1978 exceeded 60 parts per miliion for three consecutive months. Table 3.15 shows that during 1979, at four sampling stations 1A,1B, 5, and 11, was at least 40 ppm the entire year. 7 The National Academy of Sciences study of the effects of fluorid indicates that exposure of forage to an ambient air concentration of 0.5 ugm/m of HF for 30 days would result in an accumulation of 40 ppm or more fluoride. The monthly average for 1980 at station IB is 37 ppm. Station IB is at a distance of 2000 ft. northeast of t The annual average X/Q value for this location is approximately 10 y m ENC
/m gite.
Using this X/Q value and an ambient air concentration of 0.5 ugm/m3 a release rate of 0.05 gm/sec fluoride is calculated. This release rate would correspond to 4,320 gm/ day or, issuming that the ENC plant operates at the 2 ton / cay capacity, 2,160 gm/ ton uranium processed. The calculated release rat of 0.05 gm/sec assumes an ambient air concentration aj Station 18 of 0.5 ugm/m ; if the ambient air concentration is only 0.1 ugm/m then _ the calculated release rate would be 0.01 gm/sec, corre:ponding to 864 gm/ day or, further assuming the 2 ton / day production rate, 432 gm/ ton uranium. It should be noted that in 1974 (reference 1) the estimated release rate for fluorides was 0.0112 gm/sec. The staff considers the calculated values of 0.01 or 0.05 gm/sec for the ENC plant is not unreasonable. Thus, the staff concludes that the concentration of fluorides in vegetation measured as part of the ENC environment surveillance program is inconsistent with the ENC data on fluoride releases per ton uranium processed. The staff estimates that the fluoride releases are from a few hundred to a few thousand grams per ton uranium. 39
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- - . . .- e e
Table 3.14 Micrograms Fluoride Per Gram Vegetation Station Number Date 1A 1B 5 11 12 08/71 10.5 14.4 29.5 17.5 10.5 09/71 6.5 -- -- -- 6.0 10/71 21.0 14.5 -- -- 10.5 12/71 -- 22.8 20.0 16.8 30.0 01/72 -- 27.5 -- -- 27.6 02/72 -- 10.2 -- -- 11.9 03/72 -- 22.1 5.1 6.8 14.0 04/72 -- 29.6 -- -- 16.2 05/72 -- 20.8 -- -- 27.3 06/72 -- 15.4 19.5 16.4 12.7 07/72 -- 50.0 -- -- 57.4 08/72 -- 20.4 -- -- 20.9 09/72 -- 13.5 13.5 14.3 14.7 10/72 -- 29.2 -- -- 46.0 11/72 -- 14.0 -- -- 21.0 12/72 -- 27.6 33.3 41.2 47.5 04/73 -- 13.0 12.7 8.6 19.1 05/73 -- 38.5 -- -- 16.0 06/73 -- -- -- -- 13.9 07/73 -- 12.1 17.3 7.9 11.4 08/73 -- 26.5 -- -- 16.0 09/73 -- 53.1 -- -- 20.8 10/73 -- 32.1 45.1 46.1 30.3 03/74 -- 3.0 2.0 5.0 2.0 05/74 0.7 0.3 -- -- 0.3 06/74 3.0 7.0 -- -- 2.0 07/74 10.5 7.5 2.5 2.5 10.8 08/74 4.0 4.0 -- -- 4.0 09/74 4.8 6.8 -- -- 4.4 10/74 7.2 5.8 3.2 5.6 7.2 11/74 1.0 1.0 -- -- 1.0 12/74 5.2 6.0 -- -- -- 05/75 4.0 2.3 -- -- 1.0 06/75 9.2 3.2 -- -- 21.0 07/75 3.8 2.0 -- -- -- 08/75 16.0 2.5 0.6 1.9 3.9 09/75 8.3 4.4 -- -- 3.8 10/75 11.0 0.6 -- -- 1.5 11/75 6.6 2.4 7.0 6.8 4.0 l 12/75 29.3 14.0 -- -- 23.0 - 41
. . l . Table 3.14(Cont'd) Micrograms Fluoride Per Gram Vegetation Station Number Date 1A 1B 5 11 12 03/76 20.6 9.6 10.8 24.4 8.8 04/76 13.8 5.3 -- -- 8.5 05/76 4.6 4.1 -- -- 7.8 06/76 64.6 37.7 -- -- 48.9 07/76 62.0 38.9 37.4 24.4 11.6 08/76 9.0 8.4 -- -- 2.1 09/76 20.8 49.0 -- -- 24.6 10/76 3.8 3.8 2.2 8.8 2.2 11/76 26.0 18.0 -- -- -- 12/76 35.0 22.0 -- -- 19.0 03/77 75.9 40.0 45.8 37.6 29.7 04/77 43.2 39.7 -- -- 53.6 05/77 101.2 108.9 -- -- 21.5 06/77 12.5 1.3 11.9 36.7 35.3 07/77 35.9 27.2 -- -- -- 08/77 -- -- -- -- 26.7 09/77 34.4 21.5 23.8 23.4 27.8 10/77 36.2 33.9 72.6 -- 13.8 11/77 8.0 5.0 -- -- 25.6 12/77 74.0 16.0 22.7 33.3 15.9 ~ 03/78 17.9 4.7 38.5 52.5 20.6 04/78 46.7 33.3 -- -- 34.0 05/78 57.6 19.8 -- -- -- 06/78 151.4 565.8 85.0 189.9 191.4 07/78 477.1 282.6 -- -- 215.9 03/78 8.0 73.1 -- -- 21.5 09/78 14.3 4.7 13.9 1.6 8.1 10/78 6.3 3.2 -- -- 15.4 11/78 26.2 13.5 -- -- 5.3 42
Table 3.15 Summary of Fluoride Content of Environmental Vegetation Samples Sample Fluoride Content (ppm) No. of Conditions Station Year M Low Mean Exceeding Standard 1-A 1976 65 4 21 1977 101 8 36 1978 477 6 26 1979 89 67 81 1980 90 37 73 1-B 1976 49 4 14 1977 109 1 27 1978 566 3 20 1979 47 40 44 1980 72 10 37 5 1976 37 2 11 1977 73 12 24 1978 85 14 39 1979 133 41 87 1980 34 20 29 11 1976 24 9 24 - 1977 39 23 35 1978 190 2 53 1979 50 44 47 1980 61 9 20 12 1976 49 2 10 1977 54 14 27 1978 216 <1 21 1979 78 31 58 1980 60 2 36 13 1980 29 17 21 43
3.3.3 Solid Wastes. Containers of contaminated solid waste from the plant are gamma-scanned prior to being released for burial. The sensitivity of the j procedure for uranium measurement is roughly 1 gm af U-235 per container. Containers having very low uranium content are shipped to a licensed low-level waste burial site while containers having larger concentrations are stored on-site for possible further processing. 3.3.4 Conclusions and Recommendations, Environmental Monitoring Programs Rad iological . The environmental monitoring programs for radiological effluents is adequate. The release- of radiological effluents via process ventilation system, process cooling water and sanitary waste systems are adequately monitored. The radiological monitoring systems provide sufficient and timely enough information that the licensee can assure conformance with the appropriate regulations. The groundwater monitoring system at the ENC site he, consistently had uranium concentrations of less than 0.1 ppm. The only recommendations concerning the radiological environmental monitoring programs concern the test well monitoring program. First, it is required that the samples from the test wells be monitored for uranium, gross alpha, and gross beta activity. Analysis for uranium should be at least quarterly, and the analyses for alpha and beta monthly. If the gross beta activity in any of the well water exceeds 50 pCi/1, the licensee shall conduct isotopic analysis to verify the significant individual beta emitting nuclides. Non-Radiolooical. With the exception of groundwater and fluoride air monitoring systems, it is the staff's conclusion that the non-radiological environmental program is adequate. The fluoride air monitoring system consisting of samples collected on sodium carbonate-treated filter paper and determining a f actor to relate particulate to
~ gaseous fluoride is not equivalent to the EPA recommended impinger method nor the sodium carbonate tube method required by Washington State. Therefore, the staff requires that ENC modify this stack monitoring method for measuring total fluoride releases. The method should be acceptable to EPA or the State.
! The staff's assessment of the groundwater monitoring led to the following conclusions. First, the shutdown and corrective action limits for the quality of the groundwater are set too high. Based upon historical data these limits would not have been exceeded even if the chemical waste had been pumped directly into the groundwater. Secondly, the knowledge of groundwater flow in the immediate area of the ENC site is not well known. ENC staff now believes thatat the lagoon site the groundwater ficw is generally eastward but under the lagoons they believe the flow is northward. And lastly, the test wells are not located vin an arrangement that allows the tracking of a contaminated plume. The overall groundwater monitoring program is considered marginally adequate. This qualified approval of the groundwater monitoring program can be raised to adequate' when the following recommendations are included. 44
[ Recommendations:
- 1) The between and below liners leak detectior system be incorporated as part of the groundwater monitoring systems.
- 2) Action levels for the between and below liners leak detection system be prepared.
- 3) The licensee be required to notify NRC promptly whenever the investigate action level for the between or belcw liner leak detection system is exceeded. Furthermore, whenever the investigate action level is exceeded the licensee should prepare an initial assessment and describe the actions planned to correct the leakage. This assessment should be provided t NRC within 3 months and thereafter, while remaining the investigative range, stauld be documented and provided to NRC on a semiannua' basis.
- 4) The licensee should establish a system of test wells to monitor the contaminated groundwater plume.
3.4 ALTERNATIVE ACTION 3.4.1 No Action No action, in the context of this Environmental Assessment. would mean the denial of the application for license renewal (the proposed action). This alternative, if I implemented, would result in plant shutdown. To put this alternative into perspective, the ENC plant has been in operation since 1971 with insignificant environmental impact. If the alternative were implemented then the plant would be decommissioned. During deconunissioning more solid waste would be gene ated. A possible local environmental advantage might be attributable to denia', of application for renewal, that is, a source of fluoride and uranium would be removed. However, as stated above, the release of fluoride and all radioactivity is controlled, monitored, and is a fraction of the applicable regulatory requirements. The disJvantages to this alternative are several. For example, it would result
- in less American competition for the manufacture of low-enriched LWR fuels. ENC l would have to find other means to meet the conditions of its fuel supply contracts with various companies. There would be local economic disruption in the Tri-Cities area, ENC duld reduce employment, the local government would j experience some reduction in its tax base. This alternative would also mean that
! an egensive facility designed for approximately a 30-year useful life would be abandoned or converted to some other use. l 45 t
l l 4.0 AFFECTED ENVIRONMENT 4.1 AFFECTED ENVIRONMENT OF THE PROPOSED ACTION 4.1.1 Air Quality The ENC fuel fabrication site is located in an area where the quality of the ambient air meets the National Primar/ and Secondary Ambient Air Quality Standards, except for particulates. High concentrations of airborne dust, which originate primarily from agricultural activities, are characteristic of most of southeastern Washington State. Consequently, the Tri-Cities area is classified as a Priority I region with respect to suspended particulates. For the remaining air pollutants, Priority III is applicable, which places the region in general conformance with the national ambient air quality standards. The normal operation of the Exxon fuel fabrication plant results in the release of very small amounts of airborne radioactivity. In terms of concentration, the 1976, a 4x10y977,, 6x10 and g 1978 annuagaverage 5.5x10- exhaust air All uCi/ml respectively. concentrations of uranium were of these oncentrations have remained well below the 10 CFR 20 limits for U-234 of 4x10-1 uCi/ml. The radiological consequences of normal gaseous releases are calculated in Section 5.1. The normal operation of the ENC nuclear fuel plant also results in the release of fluorides. The fluoride monitoring data were <11scussed in Section 3. Using the staff's estimate of the grams fluoride released per second the average concegtration of fluoride in the ambient air is estimated to be less than 0.5 ugm/m . This concentration, assuming that the average for the months of April through October is the same or less than the annual average 6 stimate, is in compliance with Washingtor. State requirements. 4.1.2 Water Quality Both ground and surface water in tne area of the Exxon Nuclear Company site is of good quality, both biologically and chemically, and is classed as grade A by Washington State. Operation of the ENC does release small amounts of liquid radioactive effluents to the surf ace water (Columbia River) via the public sewage system. Results of samples of the water arriving at the sewage plant from ENC were shown in Table 3.11 as yearly averages of element ions, in parts per million, except with plutoniu which has been counted in pCi/ liter. The plutonium conc is 1.35x10- uCi/ml that is well below the 10 CFR 20 limits of 1x10 gntrationuCi/ml per liter. 46
, . <? . 4.1.3 Terrestrial Quality The fluoride accumulation in vegetation was discussed in Section 3. The data indicated that on occasions concentrations of fluorides have exceeded 40 carts per million and that during the summer of 1978 exceeded 60 parts per millio : for three consecutive months. Data presented in the previous section also <nowed that during 1979 at four sampling stations, the average fluoride concer.tration exceeded 40 ppm for the 12-month period. At the sampling locations no forage was being grown. Based upon the atmospheric dilution factors at distances in excess of two miles from the ENC site, where forage would have been growing, it is concluded that the Washington State fluoride concentration limits for forage would not have been exceeded at locations where forage was being grown. 4.2 AFFECTED ENVIRONMENT OF ALTERNATIVES 4.2.1 No Action. i.e.. Denial of any License Renewal Implementation of this alternative would obviate any further release of radioactive materials to the environment, provided the plant decommissioning and decontamination were effected without incident. There would be no further expenditure of energy nor use of natural resources. The primary impact would be socioeconomic. The ENC employees would suffer loss of employment, ENC would be out of business and the City of Richland note a reduction in tax base. 47
, . l .
5.0 ENVIRONMENTAL CONSETIDICES Two types of impact were considered: radiological and non-radiological. In the radiological assessment, u-snium was considered the material of mahr concern. The non-radiolo.)ical assessment focused on the potential impacts caused by the direct releases of fluoriden For both types of assessment, impacts caused by routine plant operations and possible accidents were analyzed. The radiological assessment was accomplished by comparing calculated results from plant operatior, information with established requirements stipulated in Title 40, Code of Federal Regulations, Part 190 (40 CFR 190). This code limits the individual dose for routine plant operation to 25 mrem / year to the whole b dy, 75 mrem / year to the thyroid, and 25 mrem / year to any other organ. The significant pathways considered in the assessment include air immersion, inhalation, food ingestion, and direct exposuN to soil and water bodies. The major activity involved in the assessment was to estimate the human exposure dosage by using models which were developed gt Oak Ridge National Laboratory, and incorporated in the computer code AIRD05 II . These models include atmospheric dispersion models and environmental exposure models which follow the requirements of United States Nuclear Regulatory Commission Regulatory Guide 1.109,
" Calculation of annual doses to man from routine releases of reactor effluents for the purpose of evaluating compliance with 10 CFR Part 50, Appendix I," and Regulatory Guide 1.111, " Methods for estimating atmospheric transport and dispersion of gaseous effluents in routine release from light-water-cooled-reactors."
In the assessment of the impacts resulting from the release of fluoride, the guidelines for fluoride prepared by the State of Washington were used. TheStatg of Washington regulation limits the emission of fjuoride to an average 3.7 ug/m for any 12-hour period; an average of 2.9 ug/m for any 24-hour peryod; an 3 for 30
. average of 1.7 ug/m for any for the period Ma consecutive year. The OCGIH days; gnd 0.5 ug/m}forconsecutive days; an aver fluoride at the industrial workplace.
5.1 EFFECTS OF OPERATIONS During routine plant operations, releases that could affect humans and the environment radiologically include gaseous and liquid effluents and solid wastes containing uranium radionuclides. The impacts caused by radiological air effluents were assessed by estimating the maximum dose to the nearest resident of the plant, using available information on routine operational releases, and the AIRDOS II computer code for air releases. The maximum annual release of uranium is 112.8 uCi that occurred in 1978 (see Section 3.3.2) . This value was used as the source term for an annual release. Table 5.1 presents calculated radiological dose equivalent that would be received by an adult residing in the residence nearest the fuel fabrication building assuming the 1978 uranium effluent data. The nearest resident is located about 48 l 1 -. - -
Table 5.1 Dose Canmitments Based tipon Normal Operating Gaseous - Radiological Releases i l Organ Dose Total Body Kidney Bone GI Tract Lung Population Dose (50 mile) l units perspn rem /yr 9.5 x 10'" 3.1 x 10 5 1.3 x 10- 9.5 x 10 ' 9.5 x 10 2 Nearest Resident g; units rem /yr 1.2 x 10 7 4.0 x 10 7 1.6 x 10 6 1.2 x 10 7 1.2 x 10 5 3 Site Bound'ary i 1.8 mile to Southeast i units rem /yr 1.9 x 10 7 6.3 x 10 7 2.5 x 10 6 1.9 x 10 7 1.9 x 10 5 l 1 O
2-1/4 miles (about 3600 meters) to the southeast of the plant site. The pathways considered in the dose calculation include direct irradiation, direct inhalation, inhalation from resuspension and ingestion of vegetation, meat, etc. The term " dose" referred to in this assessment is actually a 50-year dose commitment.* The critical organ considered in this assessment is the lungs of the nearest resident that is estimated to receive an annual dose of 0.012 mrem. The critical individual would be an infant (0-1 yr age) in the inhalation pathway and the lung dose would be increased by a f actor of 1.8 compared to adults. The estimated annual dose for such an infant is calculated to be 0.022 mrem. The dose to this critical individual is 0.09% of the 25 mrem limit specified in 10 CFR 190. Doses to the thyroid were not estimated as no radioactive iodine is present in the normal releases of the ENC plant. Doses due to liquid pathways were not calculated. However, the NRC staff 10 had previously calculated an estimated dose (assuming a sourc year) fgom the liquid pathways to be approximately 1.4x10 mremg(total-body) term of 3.54 and mci per 2.2x10- mrem (bone). Thus, it is concluded that the maximum individual dose at the nearest residence to a critical individual is well below the recommended limits, and therefore adverse impacts to humans and the surrounding environment are not expected. The annualtodose calculated to the gntire be 9.5x10- population person- within rem to the a 50-mile who'e radius body and of tpeperson-rem 9.5x10- plant was to the lung, without consideration of the dose tnat *ay result from resuspension of the uranium deposited. For comparison, natural background radiation in the area near the ENC plant results in an annual whole body dose of about 135 mrem (reference 2). The annual dose that would be received from natural causes by the population of 250,220 living within a 50-mile radius of the plant would be 33,780 person-rem. Another source that could affect the environment is the leaching of radiological waste water from holding ponds to the water table. Even though the ponds are iined with impermeable materials, various failures of the liners have resulted in some seepage of lagoon contents into the sofl and non-radiological contaminants have been detected in the groundwaters. Less than 0.1 ppm of uranium, the limits of detectability for the analysis being used to monitor the groundwater, has been detected in the groundwater. It is concluded that the non-radiological, as well as the uranium, contamination of the soils under the lagocas poses no immediate impact to the environment Decause there is only a remote probability of the water entering the environment. This is concluded based upon (1) the nearest well used for drinking water is over 2 miles from the lagoons in a direction opposite the direction of groundwater flow; and (2) by the time the contaminated groundwater
*A 50-year dose conunitment is the total dose to the reference organ from a one-year chronic intake of radionuclides which will accrue during the remaining lifetime (50 years) of an individual.
50 t
plume reaches the Columbia River there will have been considerable dilution of the contaminants and additional dilution would be provided by the river. 5.2 ACCIDENTS AND EFFECTS Postulated accidents that have the potential for resulting in release of radioactive materials from the ENC plant were analyzed when special Nuclear Materials License SNM-1227 was issued to the licensee. Additional accident analyses have been performed ta support license amendments to permit various plant modifications made since the plant began operation. The analyses performed have addressed those accidents that are considered to occur with the same frequency as with normal industrial plant operations. Analyses have also been performed to assess the consequences of severe accidents that are expected to occur rarely, if at all, if the consequences of the accidents could endanger the health and safety of the public. The accident analyses have been reviewed and it has been concluded that the analyses were performed in a rigorous manner and that the accident spectrum analyzed addre'ised the infrequent, severe accidents that could conceivably endanger the publ;c. However, as was noted, the assumptions on the criticality accident analysis did not conform to the current NRC regulatory guidance. Consequently, a criticality accident analysis was performed. Also, the analysis of accidental release of a large quantity of UF6 was also performed. 5.2.1 Analysis of Large'UF 6 Release The most severe radiological accident which can be costulated that could be initiated by an event typical of industrial operations would result from the release of the material contained in a uranium hexafluoride cylinder outsida a building or when the ventilation system filters were inoperative at the time of
- the accident. UF6 is a solid at room temperature. If a cylinder were to fail, I the UF6 wou!d vaporize gradually. The consequences of an accidental release of UF6 from a cylinder were calculated using the following assumptions.
FACTOR VALUE USED. Nearest Industrial Site: Distance 2000 m Direction EtoENg Atmospheric Dilution 2.2x10- sec/m3 Factor Nearest Residence: Distance 3600 m l Oirection SE l Atmospheric Dilution 3.9x10-5 sec/m 3 l Factor l 51 l i i _
gUF Released: Weight 540 Kg Time 15 minutes Uranium Released: Weigat 365 Kg Forms soluble, uranium compound Class D Particle Size 1 um Building, Wake 1 Factor Breathing Rate 3.47x10~4 m3 /sec
- Release is assumed to occur at ground level.
The calculated doses to an individual at the nearest industrial site and at the nearest residence are given in Table 5.2. For an individual at approximately 2000 meters from the cylinder storage area at the time of the accidental release, the total body dose is calculated to be 0.11 rem and the dose to the bone is calculated to be 1.7 rem. The maximum fluoride concentration at the neagest site boundary corresponding to this UF3 accident is estimated to b 1.5 mg/m . This concentration is 60% of the OCGIH recomended limit of 2.5 mg/m 5.2.2 Criticality Report The accident analyses of a fuel manufacturing plant required under 10 CFR 70 must include the discussion of the effects of a postulated criticality accident. However, the possibility of such an accident at a low-enrichment uranium f acility is remote. Historically, no accident of this kind has ever occurred in a low-enrichment fuel fabrication facility. Achievement of criticality with low-enriched uranium requires carefully controlled conditions and is not likely to happen accidentally. In addition, at the ENC plant. programs of design, review, procedural control, engineered safeguards, and audits are implemented routinely to prevent a criticality accident of this kind The postulated criticality accident has the following characteristics (Regulatory Guide 3.34): o The accident results in 1019 fissions produced in a series of pulses within a supercritical liquid system. o The accident releases only the volatile fission products produced by the above number of fissions. At this time radioactive decay begins. 52
i ! i Table 5.2 Estimated Doses (REM) From Postulated Accidents i j Large UF6 Release Accidental Criticality ! Organ Nearest , Nedrest Nearest Nearest I Industrial Resident
.ndustrial Resident Site Site Total Body 1.1E-1 6.4E-2 9.2E-3 3.7E-3 I
i Kidneys 4.ZE-1 2.5E-1 -- -- Bone 1.7E-0 1.1E-0 2.8E-2 1.5E-2 G.I. Tract 1.1E-1 6.4E-2 8.1E-1 1.5E-2 Thyroid -- -- 4.5E-0 1.7E-0 i Lungs 3.3E-2 2.1E-2 1.7E-1 5.3E-2 i f i { i l l l l l l l e 53 t
In the event of a c. icality accident, an individual would receive exposure from internal as well as extern 11 sources of radiation. The doses to the ine.iv' dual resulting from direct exposure to prompt neutron and gamma rad i atir.n , fcom submersion in a cloud containing beta and gama emitting fission proaucts and from inhalation of the fission products in the cloud have been calculated using the following assumptions: FACT _0R_ VALUE USED Building Area 100,000 ft 2 Approximately Building Wake Fuctor 1.0 at 500 meters Weather Stability F Stability Factor Wind Velocity 1 meter /sec X/Q at 0<t<8 hr
- 1.0x10-4 sec/m 3 X/Q at t>8 hr* 2.1x10-3 sec/m 3 .-
Building Confinement 30 air changes /hr
*Thesevaluesareforthenearestrgsidence,valgesforthe 3 nearest industrial site are 2.2x10- and 3.8x10- sec/m respectively.
The results of the calculations indicate that an individual at the n i residence would be expected to receive a dose to the whole body of 3.7x10 garest rem, and a dose to the thyroid of 1.7 rem. An individual at the nearest industrial l site would be expected to receive a whole body dose of 9.2x10-3 rem and a thyroid dose of 4.45 rem. These doses are below the lh9 ts of 1 rem to the whole body and 5 rem to the thyroid as specified in the EPA's Protective Action Guides. l 54 i
6.0 MATERIALS AND PLANT PROTECTION e 6.1 PHYSICAL PROTECTION AND MATERIAL ACCOUNTING Current safeguards are set forth in 10 CFR Parts 70 and 73. The regulatior.s in Part 70 provide for material accounting and control requirements with respect to facility organization, material control arrangements, account- , ability measurements, statistical controls, inventory methods, shipping and receiving procedures, material storage practices, records and reports, and management control. The Commission's current regulations in 10 CFR Part 73 provide requircments for the physical security and protection of fixed sites and for nuclear material in transit. Physical security requirements for protecting highly strategic types and quantities of material, including 2 kilograms or more of plutonium, include the establishment and training of a security organiza-tion (including armed guards), provision for physical barriers, and estab-lishment of response and safeguards contingency plans. Physical protection requirements for special nuclear mat tal of moderate and low strategic significance (including low enriched anium) include provision for estab-lishment of controlled access areas, monitoring these areas to detect unauthorized penetration, and communications capabilities to notify offsite response forces of the need for assistance. Tne Commission's regulations in 10 CFR Parts 70 and 73, described briefly above, are applied in the reviews of individual license applications. Liense conditions then are developed and imposed which translate the regulations into specific requirements and limitations that are tailored to fit the particular type of plant or facility involved. The licensee has an approved material control and accounting plan and an approved physical security plan which meet the current requirements for the low enriched uranium which would be possessed at the site. Amendments to this security plan would have to be submitted and approved prior to the licensee's bringing onto the site large quantities of plutonium which the licensee may possess in the future. These amendments would also have to be in conformance with the current requirements of 10 CFR Parts 70 and 73. It 's concicded, therefore, that the safeguards-related environmental impact of the proposed action is insignificant. t< 55 i
. o . .
1 APPEND:XA Plots prep; red by ENC staff of the concentratiens of nitrate in the test wells are presented on pages A.2 through A.14. Plots of the sulfate con-centrations are presented on pages A.15 through A.27. t 1 A.1
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1lGURE 7N : Average Monthly NO3 + NH3 (as N) Concentrations (PPM) In
?
co Test Well No. 7 . Note: "X" signifies concentration below " Alert Level". m _ _ . . .
9
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J13f 'funt " ^ ".i u t i n n 71 n 72 .'nn@73 n hf n75 n 76 n/7 n 7s n7> e FIGURE O N : Average Monthly fl03 + NII3 (as N) Concentrations (PPM) In
Test Well flo. J_,.
.- - a .a 4, .,i ri~- cancont ra t ion below " Alert f.evel".
~
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- Test 14 ell flo. 9 .
~
o flo te. "X" signifies concentration below " Alert Level".
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