ML20207R831
| ML20207R831 | |
| Person / Time | |
|---|---|
| Site: | 07000008 |
| Issue date: | 02/02/1981 |
| From: | Buckley D, James Hammelman, Orlov G, Roland R, Wimpey F SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY |
| To: | NRC |
| Shared Package | |
| ML20207R821 | List: |
| References | |
| CON-NRC-02-80-035, CON-NRC-2-80-35 SAI81-307-WA, NUDOCS 8703180181 | |
| Download: ML20207R831 (86) | |
Text
a LJ ENVIRONMENTAL IMPACT ASSESSMENT BATTELLE MEMORIAL INSTITUTE LABORATORY COLUMBUS, OHI0 Prepared by:
Frank Wimpey George Orlov James Hammelman f^)
Raymond Roland Dennis Buckley v
Report Number: SAI81-307-WA February 2,1981 Contract No. B0A NRC-02-80-035 Task 0006 Prepared for:
U.S. Nuclear Regulatory Commission Submitted by:
Science Applications, Incorporated 1710 Goodridge Drive McLean, Virginia 22101 ATLANTA
- ANN ARBOR
- BOSTON
- CHICAGO
- CLEVELAND e DENVER
- HUNTSVILLE
- LA JOLLA LITTLE ROCK
- LOS ANGELES
- SAN FRANCISCO
- SANTA BARBARA
- TUCSON
- WASHINGTON 8703180181 870316 PDR ADOCK 07000008 C
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TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE AND NEED FOR THE PROPOSED ACTION.........
1
2.0 INTRODUCTION
AND ORGANIZATION 2
2.1 Sco'pe of. Assessment.................
2 2.2 Assessment Activities................
2 2.3 Assessment Organization...............
2 3.0 SITE AND FACILITY DESCRIPTION 3
3.1 Site Descri ptions..................
3 3.1.1 Demography..................
9 3.1.2 Climatology 9
3.1.3 Geology 13 3.1.4 Hydrology 18 3.1.5 Historical and Archaeological Sites......
21 3.1.6 Background Radiological Characteristics 24 3.2 Facility Descriptions................
24 3.2.1 The King Avenue Site.............
24 3.2.1.1 U-235 Processing Facility......
24 3.2.1.2 Bioscience Laboratories.......
25 3.2.2 The West Jefferson Site 27 4
3.2.2.1 Hot Laboratory, JN-1 27 3.2.2.2 Administrative Building, JN-2....
36 3.2.2.3 Battelle Research Reactor, JN-3...
38 3.2.2.4 Plutonium Laboratory, JN-4 38 3.2.3 Radiological Waste..............
40 3.2.4 Safety and Environmental Measures 42 3.2.4.1 Environmental Monitoring 43 3.2.4.2 Health Physics 47 3.2.4.3 Fire Detection and Control 50 3.2.4.4 Materials and Plant Protection 52 3.3 Al ternate Actions..................
53 3.3.1 License Renewal 53 53 3.3.2 No Action l
SECTION PAGE 4.0 AFFECTED ENVIRONMENT...................
54 4.1 Affected Environment of the Proposed Action.....
54 4.1.1 Historical Data 54 4.1.2 Air Quality 60 4.1.3 Historical and Archaeological Sites 60 4.1.4 Climatology 60 4.1.5-Geology 62 4.1.6 Hydrology 62 4.2 Affected Environment of the Alternatives 63 4.2.1 Current License Renewal 63 4.2.2 No Action 63 5.0 ACCIDENT ANALYSIS 64 5.1 West Jefferson Site.................
64 5.2 King Avenue Site 71 ORGANIZATIONS / PERSONS CONTACTED _..............
74 REFERENCES........................
76 APPENDIX A........................
A-1 4
1
n-e hI LIST OF FIGURES Figure Page 3.1 BMI West Jefferson Facility Location..........-
4 3.2 BMI King Avenue Facility Location............
5 3.3 BMI King Avenue Facility Plot Plan...........
6 3.4 BMI West Jefferson Facility Location..........
7 3.5 BMI Nuclear Sciences Facility Plot Plan.........
8 3.6 Neighboring Subdivision.................
12 3.7 Seismicity in Vicinity of BMI Site...........
19 3.8 Seismic Risk Map of the United States..........
20 3.9 High Water Profile,1913 Flood.............
22
-3.10 High Water Profile - Big Darby Creek, 1959 Flood....
23 3.11 U-235 Processing Area Ventilation System........
26 3.12 Hot Cell Laboratory Floor Plan.........'....
29 3.13 Plan View-Drawing of Battelle-Columbus' Hign-Energy Cell and Pool......................
32 AU
- 3. M -
Cross Section of One of the Operating Stations in the Battelle Alpha-Gamma Facility............
37 3.15 A Typical View of the Plutoniun Laboratory Glovebox and Hood........................
39 3.16 Effluent Release Points.................
44 3.17 Map of Site Boundary Air Sampling Locations and Battelle Lake and Darby Creek Water Sampling Locations.
45 3.18 Map of Grass, Foodcrop and Soil Sampling Locations...
46 5.1 Air Flow Through Plutonium Laboratory for the Explosion Accident...........
70a O
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7 l
oV LIST OF TABLES Table Page 3.1 BMI King Avenue Site Population Within 50 Miles.....
10 3.2 BMI West Jefferson Site Population Within 50 Miles...
11 3.3 Maximum Wind Speeds Expected at the Battelle Memorial Institute Site as a Function of the Probability Per Year 14 3.4 Climatological Data for Port Columbus International Airport, 1941-1970...................
15 3.5 Relative Frequency Distribution, Percent Port Columbus International Airport 1970-1974.............
16 3.6 Normals, Means and Extremes Port Columbus International Airport.........................
17 4.1 Sunnary of Total Air Releases of Radioactivity for CY 1979, 1978, 1977, West Jefferson Site..........
55
('^)
4.2 Summary of Total Water Releases of Radioactivity for CY 1979, 1978 and 1977.................
56 4.3 Summary of Atmospheric Radioactive Emissions, West Jefferson Site (CY 1977)................
57 4.4 Ohio and U.S. EPA Air Quality Standards.........
61 5.1 Inventory of Volatile Radionuclide in 2 PWR Assemblies Cladding-fuel Gap Irradiated to 44,000 MWD /MT and Cooled 60 Days................-.....
66 5.2 Amount and Concentration of Gaseous Release During Assembly Drop Accident.................
67 5.3 Estimated Doses From Airborne Releases Due to Postulated Bounding Accidents..............
68 5.4 The Amounts and Average Concentration of Radionuclides Released During a JN-1 Criticality...........
70 5.5 Estimated Doses at 400 Meters from Airborne Releases Due to Postulated Accidents (King Avenue Site).....
72 A.1 Results of Water Quality Samples Taken from Big Darby Creek Upstream and Downstream of the BCL West Jefferson Nuclear Sciences Facility................
A-4 iv
e 1.0 PURPOSE AND NEED FOR THE PROPOSED ACTION bg The action proposed is to combine the Battelle Columbus Laboratories' licenses to receive, possess, and use nuclear materials and to issue as a renewal, a single license permitting activities previously conducted under licenses no.
34-6854-5 and SNM-7.
The combined activities would be conducted under the renewed license no. SNM-7. The proposed action is needed to enable continuance of research by the Bioscience Group at the Battelle King Avenue Facility and materials performance testing and theoretical research by the Nuclear Sciences Group at the Battelle West Jefferson Facility.
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2.0 INTRODUCTION
AND ORGANIZATION LJ 2.1 SCOPE OF ASSESSMENT The general requirements for environmental impact statements (EIS), negative declarations and environmental impact appraisals (EIA) for facilities licensed under Title 10 of the Code of Federal Regulations are specified in part 51.5.
The proposed action, renewal of parts 70 and 30 licenses, is specifically addressed in 10 CFR 51.5 (b)(5).
In determining whether an EIS should or should not be prepared for such actions the NRC is guided by the Council on Environmental Quality guidelines, 40 CFR 1500.6.
An EIA is to be prepared for all negative declarations.
2.2 ASSESSMENT
ACTIVITIES To prepare this assessment a review of the licensee's license renewal application, the historical performance of the facility as described in environmental reports and many related references was performed.
Also, a study team visited _the licensee's site to inspect the site and activities being conducted under their present license. During the site visit several aspects of the license renewal application were discussed and clarified.
Discussions were also held with appropriate departments within the Ohio State Government and selected Federal Government agencies in the local area.
The data collected and the applicable federal regulations provided the basis upon which this EIA has been prepared.
O
2.3 ASSESSMENT
OaGaaIZarion The content and format of the assessment are in conformance with the provisions of 40 CFR 1502.10-1502.18, and are as follow.
Chapter 3.0 explains the proposed action and alternatives thereto that were investigated.
Chapter 4.0 provides a description of the environmental components that could be affected or could affect implementation of the proposed action.
In Chapter 5 six accidents, that are believed to be bounding accidents, are discussed and the radiological consequences estimated.
The Appendix identifies these environmental components which have been classed as non-issues and provides the reasoning leading to such classification.
O 2
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3.0 SITE AND FACILITY DESCRIPTIONS gG The action proposed is the issuance of a renewed license to Battelle Memorial Institute (BMI) to acquire, store, process, and dispose of radioactive materials.
The license would be granted under the requirements of the Code of Federal Regulations, Title 10, Parts 70 and 30.
It includes the activities of the two research groups at the Battelle Columbus Laboratories' King Avenue Facility in Columbus, Ohio, and the Nuclear Sciences Group at BMI's West Jefferson Nuclear Sciences area near West Jefferson, Ohio.
For the purposes of this assessment the amount of radioactive.naterial handled (acquired, stored, processed) at th_ BMI King Avenue Facility will be limited to:
500 curies of by-product, with a maximum of 30 curies for any given isotope, and 500 grams of uranium-235 as high enriched uranium.
The BMI West Jefferson Facility will be limited in the amount of radioactive materials handled to: 250 kilograms of uranium-235 (irradiated), 50 kilograms of plutonium (irradiated),
and 22 million curies of by-product.
Plutonium is further limited to 500 grams in process.
3.1 SITE DESCRIPTIONS The BMI King Avenue Facility is located at 39 degrees 59'N, 83 degrees 03'W in the western central portion of the city of Columbus, Ohio (Figure 3.1).
The ten-acre plot, accomodating twenty-one buildings, is bounded on the north by o()
King Avenue, Perry Street to the east, Fifth Avenue to the south and the Olentangy River to the west (Figure 3.2).
Figure 3.3 is an expanded-view of the BMI King Avenue Facility.
Buildings 6 and 7 house the Bioscience Laboratories.
Building 3 houses the uranium processing activities at the King Avenue f acility.
The West Jefferson Site is located at 39 degrees 58'N, 83 degrees 15'W, approximately 13 statute miles west of the BMI King Avenue Facility (Figure 3.1).
The West Jefferson Site consists of a 1,000 acre tract which accommodates the Engineering Area in the southeastern portion, the Experimental Ecology Area in the east central portion and the Nuclear Sciences Area in the northern portion (Figure 3.4).
The northern boundary of the Site lies approximately one mile south of Interstate Highway 70 and extends from the Georgeville-Plain City Road eastward to the Big Darby Creek.
The eastern boundary of the Site roughly parallels the valley of the Big Darby Creek southward to the Conrail tracks which constitute the southern boundary.
The Georgeville-Plain City Road defines the western boundary of the Site.
The Nuclear Sciences area, the focus of interest at the West Jefferson site, is adjacent to the Site's northern boundary.
As illustrated on Figure 3.5 ft consists of a ten-acre fenced area enclosing a guardhouse, four buildings and two other small structures on a flat bluff above Battelle Lake to the south and Big Darby Creek to the east.
The eastern edge of the bluff drops rather abruptly from an average elevation of 910 feet to 870 feet ms1, then more gradually to the 860 foot elevation of the Big Darby Creek Floodplain.
The land to the north, west, and south, to a distance of two miles, is essentially cleared farmland, O
although there is one narrt.w wooded area along the northern portion of the fence around the Nuclear Sciences Facility, and another wooded area about 1,000 feet to 3
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the northeast. To the east, within the Big Darby floodplain and along the bluffs V
to the east of the Creek, the land is heavily vegetated with deciduous trees, scrub and high grasses.
3.1.1 Demography l
The area within a two-mile radius of the BMI King Avenue Facility to the east and south can be characterized as, high-density residential.
The Ohio State University, with a student enrollment of 53,278, is adjacent to the BMI King Avenue facility on the north.
The area west of the Olentangy River consists mainly of small business and light industrial properties with scattered residential patches.
Table 3.1 shows the population within a fifty-mile radius of the King Avenue Facility.
The area immediately adjacent to the West Jefferson site has a low population density. Table 3.2 shows the population distribution, by direction and distance, within 50 miles of BMI West Jefferson.
The nearest residences to the Nuclear Sciences area are two houses located 2,500 feet to the northwest and southwest respectively.
A Girl Scout camp, Camp Ken Jockety, is located on a bluff on the east side of the Big Darby Creek at a distance of 1,500 feet. Four thousand feet to the southeast, on the eastern side of the Big Darby Creek, the Lake Darby Estates residential subdivision (Figure 3.6) is under construction.
A total of 965 single family units are planned.
A second subdivision, West Point, planned for the area east of the Lake Darby Estates and Hubbard Road, is to have 1,835 housing units by 1984.
There are 18 industries located within the ten-mile radius. Of these, there are only four that employ more than 100 people.
These are White-Westinghouse Electric Corporation, General
- Motors, Janitrol
- Aircraft, and Capital Manufacturing Company.
Each of these is located at least 8 miles from the facility.
Closest to the site are three small industries within West Jefferson that individually employ less than 60 people.
The primary agricultural activity in the area is raising field crops such as corn and soybeans. Approximately 10%
of the land area in agricultural use is devoted to pasturing beef and dairy herds.
During the last 12 years two major highways, I-70 and I-270, have been completed near the West Jefferson Site. The junction of these highways, which occurs near the eastern edge of the ten-mile perimeter around the Nuclear Sciences Area, has proven to be a popular area for industrial growth.
It is estimated that the industrial population has shown an increase equivalent to that of the general population in this area, i.e.,
two and one-half times the ten-mile population distribution for 1965.
Most of the growth has taken place near the outer limits of Columbus;
- however, the larger employers, e.g.,
General Motors and White-Westinghouse, have actually decreased their number of employees.
3.1.2 Climatoloqy Climatology of the sou th-central Ohio region may be described as continental-temperate. As such, the region is subject to a wide seasonal range in temperature.
Sunrners are quite warm with the mean temperature for the months 0
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of June, July, and August being 73.3 F.
Temperatures of 90 F or above are 9
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20-30 30-40 40-50 Total 83 1,205 4,202 8,700 7,216 8,502 26,724 7,615 11.143 15,914 24,936 116.157 NNE 2,225 8,882 10.041 10,061 9,073 36,911 8,315 9,702 8,687 13,102 116.999 NE 2,389 8,782 7,145 12,067 9,991 14,091 15,950 14,594 12,792 15,118 112,919 ENE 3,699 6.2%
9.335 9,041 6,378 13,580 19,159 16,745 22.731 21,900 128,864 E
3,232 4,964 5,301 4,316 7.159 19,409 16.516 16.463 24,353 22,328 134,041 ESE 2,563 3,382 5,595 14,082 12.465 63,939 15.088 17,222 19.994 12,672 167,002 SE 4,232 2,719 7,523 17,120 17.140 16,319 19,666 18,241 18,211 9,927-131,098 SSE 1,679 3.685 6,098 10,100 14,492 21,466 12,312 11.862 13,044 10,022 104,760 g5 1,346 1,797 5,940 2,969 2,229 5,673 9,019 8,323 13,122 16,497 66,915 55W 837 1,685 6,718 9,083 4.526 17,293 10,880 8,284 10,637 14,278 84,221 SW 1,400 2,167 5,119 15.565 15.129 11,062 14,925 7,001 9,529 11.322 93,219 W5W 1,288 3,018 1,561 3,094 2.723 14.483 9,903 7,661 31,354 53,895 128,980 W
1,632 3.658 3,057 898 838 2,498 8,374 11,035 32,199 41,631 105,820 WNW 1,301 3.2%
5,159 3,432 1,401 7,797 7,951 6,477 10,379 14,358 61,551 NW 1,150 2,990 5,497 5,720 7,371 6,565 9,288 7,052 9,984 13,974 69,601 NNW
%3 3,363 4,383 5,132 5.540 7,463 7,956 10,381 15,148 25,452 85,781 Total 31,141 64.886 97.172 129,896 124,957 295,273 192,917 182,196 268,018 321,412 1,707,928
-Total within 50 miles = 1,707,928
l Table 3.2 BMI West Jefferson Site Population Within 50 Miles (1980 Est.)
0-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 N
8 6
30 80 105 3,241 2,538 3,692 19,232 38,558 NNE 4
6 30 80 105 1,304 5,358 20,947 7,461 11,290 NE 2
6 30 80 105 3,310 4,405 7,734 6,631 16,466 ENE 2
6 30 80 105 18,499 109,046 11,809 8,419 11,956 E
2 6
30 80 105 18,040 342,003 42,608 10,255 53,990 ESE 2
6 30 80 105 34,158 170,123 23,960 39,354 15,115 SE O
495 30 80 105 7,240 45,405 9,298 7,591 6,259 C
SSE O
105 30 80 105 16,028 9,860 3,496 6,115 8,886 S
0 6
30 80 105 610 4,574 3,107 4,707 11,739 SSW 2
6 200 300 105 635 4,807 3,543 4,667 7,343 SW 4
6 2,000 1,800 105 1,846 5,798 2,390 6,345 16,152 WSW 2
6 150 300 105 402 7,318 7,095 19,774 184,704 W
2 6
30 80 105 728 2,074 71,132 28,610 65,312 WNW 2
6 30 80 105 561 2,547 14,966 5,636 9,794-NW 4
6 30 80 105 423 1,754 3,344 17,568 9,754 NNW 4
6 30 80 105 711 2,282 3,318 3,429 6,086 Total 40 684 2,740 3,440 1,680 107,739 719,892 232,639 205,794 473,404 Total within 50 miles = 1,748,052.
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/]
expected for abou t 15 days during these months.
The mean for the months of C
December, January, and February is 31.2 F.
The number of days per year with 0
0 0
temperatures below 32 F and below 0 F are 122 and 4, respectively. Precipitation is distributed fairly uniformly during the year although 60% falls during the spring-sumer seasons.
The annual monthly average rainfall is about 3.5 inches and the greatest recorded rainfall for any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period was 3.87 inches in July of 1947.
Changeable wind directions are characteristic of the region due to the incursion of maritime tropical air masses from the Gulf of Mexico and outbreaks of continental polar air masses from Canada. Warm air mass inversion is most common during the later spring and sumer and frequently results in frontal showers and thundershowers.
Tropical air mass thunderstorms are also comon during the sumer and are frequently accompanied by high winds.
Additionally, it is not uncommon for hot air mass thunderstorm development to be sufficiently strong to spawn tornado activity.
Cold fronts that invade the region, principally during the late fall, winter, and early spring also bring showers and thunderstorms.
During the late spring fast moving cold fronts, with large temperature discontinuities ahead of and behind the frontal surface, travel through the region and are often accompanied by thunderstorms and frequently by tornadic activity. Of the 567 tornadoes recorded within 144 miles of the BMI Facilities during the period 1950-1975, one hundred sixty-three have occurred in the month of April.
Table 3.3 sumarizes the expected windspeeds at the BMI sites as a function of probability per year.
(O The regional climatological description is generally representative of the local climatological conditions at the BMI Facilities. Data have been gathered by the National Weather Service at Port Columbus, seven miles east-northeast of the King Avenue Facility and 20 miles east-northeast of West Jefferson.
This data is shown in Tables 3.4, 3.5 and 3.6 and is considered as site specific.
A mobile meteorology station is maintained at the West Jefferson site. The data collected by the mobile station are used for long-term comparison with the Port Columbus data.
3.1.3 Geology I
The arrangement of geological strata in the BMI Facilities area consists of glacial till and outwash with formations of clay, sands, and gravel.
The sands and gravel of the outwash are found in scattered, thin, discontinuous lenses within the till which is composed of unstratified clay containing fragments of rock. The unglaciated basement formations in the West Jefferson area, at depths of from about 80 to 100 feet, consist of nearly horizontal beds of limestone, dolomite and shale several hundreds of feet thick.
Surface soils consist of patches and mixtures of: Brookston Silty Clay Loam, Crosby Silt Loam, Lewisburg Silt Loam, Celina Silt Loam and Miamian Silt Loam.
The greatest portion of the surf ace soils is represented by the Brookston-Crosby association with little more than traces representing the remaining types.
All of these soil types exhibit relatively low permeability and all grade into till clay at depths of 55 to 60 inches where the impermeability of the near-surface geology nearly precludes further percolation.
13
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Table 3.3 Maximum Wind Speeds Expected at the Battelle Memorial Institute Site As A Function of the Probability Per Year Probabilities Return periods Windspeeds in miles per hour (A)
(B)
(C) 10* per year 1 year 38 mph 48 mph 10-I 10 61 76 10-2 100 72 90 10-3 1,000 86 108
-4 10 10,000 101 126 102 mph E
10-5 100,000 113 141 171 10-6 1,000,000 125 156 237 10-7 10,000,000 297 (A) Fastest-mile speeds of straight-line winds.
(B) Gust speeds computed as 125% of ( A)
(C) Tornado wind speeds based on 1950-1975 data
O O
O Table 3.4 Climatological Data for Port Columbus International Airport, 1941-1970 feeperature. *C No. Trs.
J
[
5
{
5 f
f 5
0 ft 0
Annual Estreme meslanan 37 23 23 29 32 34 39 38 38 38 32 27 22 30.9
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nerinal agetsue 30 2.4 4.0 9.6 17.1 22.7 27.F 29.3 2A.F 25.3 19.1 10.5 3.7 16.7 hermal 30
-20
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normal sintenas 30 6.4
-5.9
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1 Days below 0*C (32*F)
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4 Precipitation sue Water (quivalent i
liighest sonthly 37 211 110 244 162 238 248 240 202 157 133 137 129 normal 30 F3 59 87 94 104 105 107 23 El 48 68 61 940 Losest sonthly 37
- 13 10 15 IF 36 32 12 15 13 3
15 12 8
Greatest in 24 hrs 29 122 55 86 60 69 F4 97 96 51 47 52 41 Days 0.25 se er more 3F 13 12 14 13 13 11 11 9
9 8
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25 sus er more Other Weather Phenoawne 8verage wind speed. aps 27 4.5 4.7 4.9 4.6 3.9 3.4 3.0 2.9 3.0 3.4 4.2 4.4
- 3. 9 Prevallint wind direction 14 55W NW 55W ImW 5
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Percent pessthis sunshine 25 37 42 44 62 SF si 63 63 62 58 39 31 52 i
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o Table 3.5 Relative Frequency Distribution, Percent Port Columbus International Airport 1970-1974 Speed (kts)
Creater Average Speed Direttfon 0-3 4-6 7-10 11-16 17-21 than 21 Total gg, N
1.0 4.2 2.8 1.2 0.1 0.1 9.3 3.7 7.1 NNE 0.7
- 1. 6 1.1 0.4 0
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- 0. 2 1.0 2.9 2.2 0.4 6.8 5.2 10.1 l
j SW 0.2 0.9 1.8 2.2 0.5 0.2 5.8 5.8 11.2 WSW 0.1 0.7 1.7 1.8 0.5 0.1 4.9 5.8 11.3 W
0.2 1.1 2.9 3.2 0.8 0.2 8.5 5.8 11.2 M
0.1 0.7 1.7 1.8 0.3 0.1 4.6 5.5 10.6 W
0.3 1.0 1.5 1.3 0.2 i
4.4 4.9 9.6 l
NW 0.4 1.6 1.6 1.2 0.1 0
4.9 4.3 8.3 1
Total 8.1 31,5 35.3 20.9 3.3 0.7 4.2 8.2
]
Total relattve frequency of calms,dtstributed above - 2.91
- = less than 0.05%
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p There have been no recorded earthquakes within 50 miles of the area of interest, V
although in 1937 a strong quake was experienced at Anna, Ohio, a little over 50 miles to the northwest of the West Jefferson Site.
The Columbus-West Jefferson areas are, however, considered to be in an aseismic region.
Figure 3.7 depicts the seismicity in the vicinity of the BMI site and Figure 3.8 is a seismic risk map of the United States. The BMI f acilities are in a Zone 1 risk area.
3.1.4 Hydrology There are two aquifers, or sources of water, in the site area.
The shallow aquifer is, of course, the dense clay till. The deep, or principal, acquifer is the limestone bedrock underlying the till.
Earlier wells in the site area ranged in depth from 10 to 40 feet, which placed them in the glacial deposits. Till is not very permeable and yields water slowly.
The effective velocity of water moving through clay under a hydraulic gradient of one percent is reported to be less than 0.004 foot per day; for water moving through silt, sand, and loess under the same gradient, the rate is about 0.0042 to 0.065 foot per day. Water movement in the till at the Battelle site is probably within the range of the former figure, since the hydraulic gradient of the water table in the area is only slightly greater than one percent.
The present wells at the Battelle facility lie below the surface of the bedrock.
The north well is 130 feet deep, the centrally located well in the Life Sciences area is 162 feet deep, and the south well is 138 feet deep.
Bedrock was encountered at approximately 103 feet below the surface in drilling these wells.
O,m A man-made hydrologic feature of the site is the artificial lake covering an area of about 25 acres that was formed by daming Silver Ditch south of, and down gradient from, the Nuclear Sciences area.
The normal surface elevation of the lake is 888 feet MSL.
The source of ground water in the site area is local precipitation.
Recharge to the shallow aquifer takes place relatively uniformly over the area. Contours of the water table, which are about 40 feet below the surface, are a subdued replica of the surface topography.
Ground water moves downslope at right angles to the contours and follows a path similar to surface runoff.
At the Nuclear Sciences area surface runoff moves downslope into the lake, thence through the controlled dam on the site into Big Darby Creek.
All ground water in the site area, and that entering on the site, is already near its place of discharge.
- Test borings carried out in 1970 for an addition to the Hot Laboratory reaffirmed the geology described above.
Only isolated pockets of water were encountered during that boring and foundation-piling excavation operations.
These pockets were readily pumped out and remained dry, which indicated that there is no interconnection of the pockets with the lake.
Flood hydrology calculation for the lake indicated a capacity of releasing water that was about three times the inflow rate measured during the January 1959 floods.
It can be concluded that the lake has not adversely affected the hydrology of the area.
O v
18
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O Big Darby Creek accounts for the principal surface water flow.
Normal flow at the Darbyville gauging station, the only continuous recording gauge on Darby v
Creek, 40.46 river miles south of the West Jefferson Facility, is 430 cubic feet per second (cfs).
Normal flow past the West Jefferson Facility is 190.5 cfs.
Reference to National Oceanic and Atmospheric Administration literaturel indicates the Probable Maximum Precipitation (PMP) for a 200 square mile area extending north of the West Jefferson Site area (the drainage area of Big Darby Creek at the Site is 240 square miles) is estimated to be as listed below.
1.
Six hour duration -- PMP of 19 inches.
2.
Twelve hour duration -- PMP of 22.5 inches.
3.
Twenty-four hour duration -- PMP of 25 inches.
4.
Forth-eight hour duration -- PMP of 28 inches.
5.
Seventy-two hour duration -- PMP of 29 inches.
Historical records of maximum floods on the Big Darby show a flood profile, during a 1913 flood, indicating high water near what is now the Nuclear Sciences Facility, at abou t the 880 elevation, i.e.,
eight feet below the level of Battelle Lake (Figure 3.9).
The profile for the January,1959 flood shows the water level at the West Jefferson Nuclear Facility (40.46 river miles north of A
the Darbyville gauging station) peaked at 876 feet (Figure 3.10).
This V
corresponds closely with the U.S.
Army Corps of Engineers 100 year flood estimate of 869 feet ms1.
The Corps' estimate of the 100 year discharge rate is 20,900 cfm at the West Jefferson Nuclear Facility.
Calculations, performed in connection with a separate study (HUD-R05-EIS-07(d)), estimated a flow rate of 21,707 cfs at the I-70 bridge (approximately one mile north to the West Jefferson Nuclear Sciences Facility).
This estimate is in reasonable agreement with the Corps' 100-year estimate.
3.1.5 Historic and Archeological Sites In order to determine what currently recognized historical and archeological sites could possibly be affected by the operation of the BMI King Avenue and West Jefferson facilities, the 1979 National Register of Historic Places was examined.
There are 59 historic places in Franklin County aiid six in Madison County. None of these sites coincide with either BMI facility site.
1 Hydrometeorological Report No. 51, Probable Maximum Precipitation Estimates, United States East of the 105th Meridian, Louis C.
Schreiner and John T.
- Ridel, Hydrometeorological Branch, Office of Hydrology, National Weather Service.
O 21
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l Figure 3.9 High Water Profile,1913 Flood
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3.1.6 Background Radiological Characteristics O
Based on aeroradioactivity measurements of the region including the BMI b
f acilities, it is estimated tjat the natural terrestial background for area surrounding BMI is 60 mrem / year.
This number is equal to the average natural terrestrial background for the U.S.
The cosmic background for the State of Ohio is averaged to be 50 nrem/ year, compared to a U.S. average of 45 mrem / year.
The estimate for natural whole-body internal background is egnsidered to be 25 mrem / year for the U.S. with only minor regional variations.
Based on these figures, the total natural background near the BMI facilities is approximately 135 mrem / year, as compared with an average of 130 mrem / year for the U.S. as a whole.
3.2 FACILITY DESCRIPTIONS Bioscience research work at the BMI King Avenue Facility is conducted in seven small laboratories on the second and third floors of one building.
The research involves the determination of the reaction of a variety of biological specimens to specific radioactive materials. The number of people in the Bioscience group involved in handling radioactive materials is limited to approximately 30.
At the BMI West Jefferson Nuclear Sciences Facility, two major operations are involved. The first is research on the properties of irradiated materials. This work is performed in the Hot Cell Laboratory (JN-1) and involves examination and testing of irradiated reactor fuel, nuclear pressure vessel material, and fuel cladding material.
The experiments serve to collect data for the development or 7
testing of theories about material performance under irradiation conditions. The second major operation which is conducted under license at the West Jefferson site is the plutonium studies work.
This work is performed in the Plutonium Laboratory, JN-4, and will involve activities such as plutonium analysis in support of decomissioning work; decontamination tests; and plutonium package leak rate test.
These programs will support the safety of various plutonium operations in the nuclear industry. Figure 3.5 shows these two buildings in the Nuclear Sciences Facility.
3.2.1 The King Avenue Site 3.2.1.1.
U-235 Processing Facility The U-235 Processing Facility is located in Building 3 of the King Avenue Site.
Building 3 was constructed in the mid 50's.
It served until the late 60's as an exclusion area specifically designed for the processing and storing of Civil Effects Operations (LEX 59.4.23) Aeroradioactivity Surveys and Areal Geology of Parts of Ohio and Indiana (ARMS-1) May 1966.
2 " Estimates of Ionizing Radiation Doses in the United States 1960-2000,"
U.S. Environmental Protection Agency, ORP/CSD 72-1.
24
Q unirradiated enriched uranium utilized on various government and industrial R&D programs. Presently Building 3 is used for several activities, but access to the U-235 processing area is limited and entry doors to the area are alarmed.
The vault is used for the temporary storage of limited quantitites of unirradiated enriched uranium.
The area is also used for the receiving, storing, waste processing and packaging for shipment of source materials.
The major piece of processing equipment located in the area is an electric calcine furnace which is used for the reduction of scrap or waste to an oxide residue suitable for shipping to either a waste disposal site or scrap reprocessor.
The furnace consists of a closed system muffle and glove-box combination.
The exhaust system for the furnace is arranged so that room temperature air is drawn into and mixed with the hot exhaust gases within a blending box.
The semi-cooled exhaust gases are then drawn through a water scrubber system which is equipped with a re-circulating water system.
After passing through the scrubber, the washed exhaust gases flow through a bank of absolute filters and are then exhausted to the outside atmosphere through a blower and duct opening on the roof.
Figure 3.11 shows the ventilation system for the U-235 processing area.
The reduced residues and ash, after being burned and cooled, are dumped into plastic bags within the glove-box. This glove-box is an exhausted, closed system and therefore the system operating pressure is negative to the room pressure.
O This prevents any problem of contamination in the surrounding area exterior to the system.
This calcine system can be used for the reduction to oxide of limited quantities of unirradiated enriched uranium scrap.
The removal of enriched uranium ash and residues from the glove-box is accomplished by dumping the material into a hopper built into the floor of the glove-box. This hopper feeds into a pipe over which a steel can is attached.
The residue drops directly into this can which, when full, is removed and a lid applied and sealed for shipment.
The area is also the central gathering and packaging spot for low -level radioactive contaminated waste. The area also served as a receipt and shipping, sampling, and measurement area for shipments of both source materials and small quantities of unirradiated uranium which are to be, or have been, utilized on programs being performed at the BMI King Avenue site.
3.2.1.2 Bioscience Laboratories The Life Sciences Radioisotope Laboratories are designed for the preparation, utilization, and analysis of tracer quantities of radioisotopes in biological research.
Such applications of low-level radioactivity will vary from use in live animals to isolated tissues and cells and for biochemical reactions in Q
vitro.
Only levels of radioactivity will be used, which, after dilution in tee 25
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sampling for valid quantitative identification.
The work performed is primarily tracer work with small quantities of individual radionuclides.
Individual batches are normally on the order of 1 microcurie or less.
Stock quantities are normally 10 millicuries or less.
Annually the working inventory is a small number of isotopes, for example, the inventory for January 1980 consisted of a few isotopes with the maximum activity of any isotope being a few millicuries.
Thus, the 500 curie possession limit notwithstanding the accidental release of the total working inventory is inconsequential (see Section 5 for analysis of accidents).
Almost all the activity is of a wet chemistry nature using tagged compounds purchased from the supplier.
Experiments using substances of low toxicity or otherwise low hazard are performed in standard fume hoods with no filtration in the exhaust system.
Experiments utilizing substances of increased toxicity or otherwise increased hazard are handled in especially designed hoods with filtered exhaust systems.
Some substances may be handled in glove boxes.
When tagging operations are done using byproduct material (e.g., such as iodinations) they are performed in hoods which have charcoal filtration.
The particulate filters are high efficiency; hoods are designed for face velocities of 100 to 150 linear feet per minute and are periodically tested. Exhaust stacks discharge above the roof of a four-story building housing most of the laboratory facilities of this
(~5 dep artment. This places the discharge point roughly 55 feet above ground level.
L) 3.2.2 The West Jefferson Site As previously shown in Figure 3.5, there are four principal buildings at the West Jefferson Nuclear Sciences area:
JN-1, the Hot Laboratory; JN-2, the Administrative Building; JN-3, a retired Research Reactor; JN-4, the Plutonium Laboratory.
Each of these facilities is described in the following paragraphs.
3.2.2.1 Hot Laboratory, JN-1 This laboratory, containing approximately 22,000 square feet of space, is considered to be one of the most completely equipped such installations available to the nuclear comunity.
The Hot Laboratory is capable of providing research and technical assistance in the areas of:
o Power reactor fuel performance evaluations e
Pressure vessel irradiation surveillance capsule examinations and evaluations e
Postirradiation examinations of nuclear materials and components 27
e Radiation source encapsulation, and e
Physical and mechanical property studies of irradiated materials and structures.
The Hot Laboratory consists of a large high energy cell and connecting pool capable of handling complete power reactor fuel assemblies, five smaller cells, and supporting facilities.
The smaller cells are the high-level and low-level cells, the two mechanical test cells, and a segmented alpha gunma cell.
The supporting facilities include areas for cask handling, solid and liquid-waste
- disposal, contamination
- control, equipment decontamination, and other miscellaneous operations.
A floor plan of the laboratory with these operating areas is presented in Figure 3.12.
A brief description of each of these is provided in the following paragraphs.
Storage Pool and Supporting Facilities The fuel storage and transfer pool is 20 feet by 20 feet by 45 feet deep and is lined with 14-gauge, Type 304, stainless steel. All welds in the 14-gauge, Type 304, stainless steel pool liner have been dye-penetrant tested for cracks. Water leaks flow into vertical weep grooves that run the entire depth of the pool in the concrete.
The water then flows into a caison well which is analyzed at periodic intervals for radioactive materials.
O V
A tornado-proof lid is provided to cover the pool when it is unattended or when a tornado warning is announced.
A personnel bridge traverses the pool to f acilitate underwater manipulation.
The bridge has a 1-ton monorail crane and can service the entire pool area. For storage, the bridge can be moved from the pool area to an adjacent area.
Facility capability permits the handling of shipping casks weighing up to a maximum of 27,500 lbs. Operating procedures for the handling of such large casks have been established which, in the event of lifting crane failure, will preclude the possibility of the cask falling into the pool at any position other than at or near the pool center and in a vertical orientation.
i The water for the pool is processed on-site through a series of 18 ion-exchange columns. These columns have a capacity to make up to 10,000 gallons of primary l
water per day.
A 1,500-ga11on storage tank assures a continuous supply of primary water.
The pool recirculating system operates continuously to filter water and run it through 12 ion-exchange columns each having a 5 micron particulate filter in series.
The ion-exchange column contains disposable bags l
of ion-exchange resin, the filter is a disposable dry cartridge.
NOTE: The resins and filter cartridges are changed periodically in order to maintain radiation background of 2 mr/hr or less in the operating area adjacent to the walls of the ion-exchange column room (i.e., the pool mechanical room).
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q For recirculation of the pool water, there are two suction lines connected to a b
recirculation pump.
One line draws water from the bottom of the pool, the other from a six foot depth.
If no fuel, fuel rods or fuel assemblies are stored in the pool, the lower suction line is used at all times.
During weekends and at night while fuel, fuel rods or fuel assemblies are stored in the pool, the recirculation is performed by taking the water from the six feet depth.
This insures that the pool cannot be accidentally drained.
To maintain the proper pool lev el, floats are used to activate the pumps which can provide 10,000 gallons of water per day.
Should this make up be insufficient to keep ahead of any possible loss of water; a fire hose will be used to augment the makeup water supply.
The fire hose can provide a supply of 2400 gallons of water per day.
Water level alarms are incorporated in the pool control system.
Radioactivity of the pool water is monitored periodically.
The10 gaximum radioactivity leve1s, during normal operations, in the water are duci/mi beta-gama and 10-4uCi/ml alpha.
A canal connects the pool with the inside of the high-energy cell. The transfer canal is 4 feet wide and 45 feet deep.
Transfer between the pool and cell is accomplished by means of a stainless steel arm with a basket on the end.
To effect a transfer from the pool to the cell, the basket is loaded while on the bottom of the pool.
The overhead crane is then used to lift the mechanism and the basket is raised into the cell.
The entire mechanism is designed to handle 2000 lb.
The basket has a 12-1/2-inch-square opening and various size holes on the periphery so that individual rods or groups of rods can be transferred.
u The crane controls are equipped with an emergency stop button which can be activated in the event that a control button sticks.
In the unlikely event that a component of the transfer mechanism breaks, the fuel element should not f all out of the basket because its center of gravity is located far below its pivot on the transfer arm.
Should a heavy object such as a cask be dropped in the pool, there are 8 inches of crushable bricks as well as shock absorbing plates that would absorb much of the impact.
The bricks and plates are backed by 2 feet of concrete that constitutes the pool bottom.
A storage rack capable of holding LWR fuel assemblies is located in the pool.
The rack is securely anchored to prevent tipping and provides protection against l
the inadvertent movement of rods within twelve inches of a stored fuel bundle or l
fuel assembly.
The rack cannot be accidently tipped because it rests on the pool bottom and is I
securely f astened.
A length of stainless steel channel acts as a strap and runs from the storage rack to the top of the pool. The strap is then hooked over the pool lip to provide for positive fastening of the rack.
This insures tha+ the l
30
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rack cannot be accidentally tipped and in the unlikely event of an earthquake, the pool would have to collapse before the straps would release.
In that the pool construction has been shown to be earthquake resistant, to a degree, it is concluded that the storage rack is equally earthquake resistant.
In normal operations, individual rods are removed from the fuel bundles stored in the rack. To prevent bringing a single rod or an entire fuel bundle closer than twelve inches to a stored bundle, a stainless steel expanded sheet covers the top and exposed sides.
Holes in the stainless steel expanded sheet have a maximum opening of 1/4 inch.
The twelve inch distance provides for complete neutronic decoupling so that the storage rack is safe from a criticality standpoint.
High-Energy Cell A plan-view drawing of the cell and the adjacent storage and transfer pool is shown in Figure 3.1.
The cell face is constructed of a 4-foot thick Barytes concrete (205lbs/ft]).Th back wall of the cell is constructed of 6-foot thick 3
normal density (150 lbs/ft ) concrete and the ceiling of 4-foot thick normal density concrete.
There are four operating stations located on the cell f ace and one at the end of the cell.
Internal dimensions of the cell are 9 feet wide by 38 feet long by 25 feet high.
Inside the cell there are two overhead cranes. One has a 5-ton capacity and the other has a 1-ton capacity.
The cranes travel the full length of the cell and can pass each other. The ceiling of the cell has a 9 feet by 9 feet opening for insertion and removal of casks and heavy equipment.
This opening is manually plugged with three keystone-shaped concrete slabs.
Recessed in the back wall of the cell are six prefilters and six high-efficiency filters that can be changed remotely.
Each set of two filters, prefilter and HEPA filter, is exhausted by a 2,500 CFM blower. The three sets of prefilter and HEPA filters are arranged in parallel.
To f acilitate passing items into the cell, there are two 6-inch diameter
" drop-in" tubes located on the cell face.
The tubes are set at a 30-degree angle which insures that the items f all into the cell. Located in the back wall there is a " drop-out" tube which makes it possible to drop items out of the cell remotely.
This tube is normally bagged with plastic to prevent the spread of contamination.
31
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,, bq The principal examination of spent, light-water power reactor fuel assemblies.
The cell was designed to provide:
o Hot cell space recoirements for BWR and PWR fuel assembly exatnination with rehu'isite beta-gamma shielding, o
Alpha containment for, future mixed-oxide fuels.
e Neutron shielding for recycle fuels, e
Inert atmosphere for future LMFBR component requirements.
Since it involves a significant cost and is not required at the present state of 5
power reactor technology,'the inert atmosphere containment is not provided for at present..The design of the cell permits operation with an inert atmosphere if the need arises.
Aost of the destructive examination performed in the High-Energy Cell is the sectioning of fuel rods and components. The selected sections are transferred to other cells within the laboratory for detailed chemical, metallurgical, and r hysical properties studies.
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LT A minimum number of access ports have been provided for the insertion of utility cables and tubes, and the mounting.of special equipment.
All permanent p@etrations for items such as electrical conduit are installed in a " lazy-S"
-- mtaner to insure against leakage of collimated radiation.
To that end other penetrations have been designed with a " stepped plug".
, Entrance to the cell is : gained by moving the 18-ton solid steel door in the cask
, /.T wash-down area with<the 50-ton capacity overhead crane. Leakage of cell air into surro6nding occupied-spaces is prevented by maintaining a 0.5 inch water gauge
,j
' pressur2 differential between the cell and the operating galleries.
When a cell
. e,ntry is to be made, it is, of course, a planned event. Personnel are dressed in coveralls, a disposable paper suit, and a full face mask.
The individuals are
~,provided with the necessary radiation-detection instruments and monitoring devices.
Viewing windows in the hot cell are constructed from a combination of lead-glass, and oil so that the windows are equivalent to the concrete wall with respect to gamma and neutron attenuation. For remote manipulation each operating station is ecuipped with a pair of manually operated manipulators.
/
An entire fuel anembly or individual fuel rods can be stored in the cell by placing them in a storage pit located in the floor of the cell (Figure 3.11).
C 33
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The pit is 17.4 feet deep with a 4.0-foot-diameter hole in the center and six bq 8.0-inch-diameter holes around the outside.
High-Level and Low-Level Cells The High-Level Cell (HLC) has interior dimensions of 18 feet long, 8 feet wide, and 12 feet high and is designed to provide sufficient shielding for 10 million curies of a 1.0 Mev gama emitter.
Another cell, designated the Low-Level Cell (LLC), is 20 feet long, 8 feet wide, and 12 feet high.
It is designed to provide sufficient shielding for 10 thousand curies of a 1.0 Mev gama emitter.
The HLC and LLC are adjoining and have a comon operating and access area. Material can be transferred directly between the HLC and LLC by means of a port.
Access to the High-Level, Low-Level, and Mechanical Test Cells is through hydraulic or mechanically operated shielding door located at the rear of each cell.
Contamination levels of the floor and walls in the access area are controlled.
Radiation background levels are in the range of 10 to 100 mr/hr.
This area has a special floor and wall coating to aid in decontamination.
Atmospheric pressure within the cells is maintained at a lower level than that of adjoining noncontaminated or suspect areas. This prevents the spread of airborne contamination from the cells into adjoining areas.
Entry of personnel into the cells is a preplanned and controlled event requiring procedures as described in the operations section of this application. Access is normally made through the adjoining decontamination locker room.
Under special circumstances, personnel may also enter the hot area from the High-Level Cell operating area or through doors on the back loading dock.
Personnel access to the cell interiors is possible only through the heavy shielding doors at the rear of each cell.
Located within the contaminated zone are three other laboratory support areas.
These are the dry storage area, the contamination equipment storage room, and the liquid waste evaporator.
Storage for irradiated fuel specimens and other radioactive material is provided by 74 steel tubes that are imbedded vertically into the floor of the southeast corner of the area.
The upper end of each tube is flush with the floor.
Shielding is provided by the high density concrete into which the tubes are imbedded.
Opposite the dry storage area is a large enclosed room with an overhead balcony that provides storage space for contaminated reusuable equipment.
When practicable, equipment stored in this room is individually bagged in a plastic sheet to reduce the air contamination.
Access to this room is through a 34
i rm mechanically operated shielding door.
The walls and floor of this room are i
V coated with a special material to f acilitate decontamination.
A small room adjacent to the dry storage area contains facilities for slow evaporation processing of liquid wastes.
Past experience hgs shown that the level of ac uCi/ml beta-gama and 1-4x10 givity in the liquid waste is of the order 2-7x10-uCi/ml alpha. The evaporation unit consists of two 55-gallon drums, each containing a thermostatically controlled electrical imersion heater.
In operation, liquid waste (primarily low-level contaminated waste water) which is collected in the 5,000-gallon holdup tank and the holdup sump is pumped into the evaporator drums by a manually switched pump. The heaters maintain the liquid at 0
a temperature of approximately 190 F.
The evaporated water mixes with the air of the evaporator room and is exhausted from the building through the filtered exhaust system.
When radiation levels within the evaporator drums reach about 20 to 50 mr/hr, as determined by a portable radiation survey meter, the remaining liquid is solidified with concrete and the drum is shipped to a licensed site for burial.
The liquid is never boiled nor are the drums allowed to approach dryness.
Mechanical Test Cell Adjacent and to the east of the low-level cell is a Mechanical Test cell that is qb used primarily in studies to determine the mechanical properties cf irradiated material specimens.
The cell provides adequate shielding for relatively low-level radiation sources. Therefore significant quantities of irradiated fuel are generally not handled in this cell.
The cell operating face is an ' 8-inch-thick steel wall containing five (5) lead-glass shielding windows.
Each window consists of two 4-inch-thick leaded glass panes. The cell is served by four manually operated remote manipulators.
Access to the cell is through an electrically operated sliding steel door.
A transfer tube connects the Mechanical Test Cell and the Low-Level Cell.
Alpha-Gama Cells Tne alpha-gama cell consists of ten operating stations located in the basement under the back shipping dock and is served by a separate operating and access area.
The cell is designed to provide shielding for the handling of irradiated-fuel metallography specimens.
Each box has provisions for bagging equipment or materials in or out of the box, and glove ports are available in each box for repair of equipment, etc.
Repairs can be made or equipment can be bagged into or out of the boxes in the operating area but containment of the box is not broken without first moving the box to the hot area above the grade.
O 35
O The cell and operating area are framed in a room 70 feet long by 17 feet wide by b
11 feet high.
The walls of this room are construgted of 12 inches of reinforced regular, concrete (density approximately 147 lb/ft ).
The ceiling of the room is constructed of 8 inches of reinforced, regular concrete.
In addition, 3 inches of steel plate and 8 inches of cast-concrete beams have been added to the ceiling directly over the cell to provide further shielding for the operating area.
A cross section through cae alpha-gama cell work station is depicted in Figure 3.14.
The cell face consists of 6-3/4 inches of lead faced on both sides with 1-inch steel plate. This wall is designed so that the radiation level from 2,000 curies of 1-Mev gama radiation is reduced to about 2 mr/hr at the outside face of the cell.
A limited number of access ports have been provided for the insertion of utility cables and tubes, and the mounting of special equipment.
Each of the ten viewing windows is constructed of one 5-inch-and one 3
6-inch-thick block of lead glass (density of 6.2 g/cm ).
Since the window shielding does not match the wall, it is necessary to install an additional thickness of glass if the cell is to be operated at its maximum capacity.
Each operating position is equipped with either one or two manually operated manipulators. Tne slave end is protected and sealed by a boot from which the arm may be extracted without breaking containment of the box.
Entrance to each box is accomplished by rolling the individual sections of the cell shielding wall away from the cell f ace to expose the attached containment box. During this operation, necessary precautions against external contaminat!an and radiation exposure are taken. Additional cleaning and/or repair of equipment v
is accomplished either through a series of glove ports located on the containment box or by taking the sealed box to the hot area above grade.
No radioactive material is exposed outside the boxes in the area of the alpha-gamma cell.
An 8-inch diameter vertical transfer tube leads from the cell to the floor of the area above.
This tube is used for the transfer of materials to and from the cell.
Anything removed from the alpha-gama cell is adequately contained to insure control of contamination.
3.2.2.2 Administrative Building, JN-2 This building was designed and constructed for use as a critical assembly laboratory.
It was used for critical experiments from 1957 through 1963.
Since the cessation of critical experiments, the facility has been used for several nuclear related projects including direct conversion concepts, irradiation experiment assembly, and special nuclear materials handling.
The operating license was terminated in 1970.
Offices and small laboratories are used by nuclear supporting services staff including Section Administration, Health Physics Services, Nuclear Materials Accountability, Quality Assurance, and Instrument Maintenance. These activities are the major building activities at this time.
The building also currently 36
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.y.,y Os Figure 3.14 Cross Section of One of the Operating Stations in the Battelle Alpha-Gamma Facility 37
3 houses the vault, used for storage of special nuclear materials, and a nuclear (V
instrumentation laboratory.
3.2.2.3 Battelle Research Reactor, JN-3 The Battelle Research Reactor began operations October 29, 1956, but those operations were terminated on December 31, 1974, and dismantling initiated. The dismantling was completed without incident during 1975 and the license changed to a possession only status.
Storage of waste awaiting shipment for burial is the only licensed activity conducted in JN-3 at this time.
3.2.2.4 Plutonium Laboratory, JN-4 The BMI Plutonium Facility was built in 1960 to house activities in plutonium research and processing. With time, the capabilities required to stay abreast of the increased interest in plutonium research expanded to a point that necessitated expansion of this facility.
In 1964, an addition to the original facility was built to provide the capability of a high teniperature gas pressure autoclave and a high temperature vacuum hot press that permitted extensive study of both the bonding characteristics of plutonium with other materials and the production of nigh density plutonium fuel forms.
As research necessitated more space for property study and powder processing equipment, a second addition was added to the facility in 1967 which more than doubled the area of the facilii.y.
(3 With this addition, the capabilities of the laboratory rapidly expanded to V
include analytical chemical determinations, Pu-238 fabrication processing, high temperature property
- studies, improved machining and powder processing capabilities, and mechanical testing.
Over the years of operation the management of the laboratory has directed the efforts of this facility in research and development to advance the state-of-the-art of plutonium technology for both industry and government.
Future activities in the laboratory will involve work such as plutonium analysis in support of environmental characterizations, plutonium decontamination experiments and plutonium shipping container leak experiments.
These experiments are conducted in gloveboxes and hoods in a single room. These gloveboxes and hoods are of standard design and involve ventilation systems specifically designed according to NRC Regulatory Guide 3.12.
A typical glovebox and hood during the construction phase is shown in Figure 3.15.
Air for the laboratory is introduced from the atmosphere and passed through an electrostatic filter and a preconditioner where the temperature is raised or lowered to 55 F.
During the suniner, this preconditioned air is passed over 0
cooling coils to further lower the temperature before it enters the laboratory.
During the winter or heating season, the air is passed over heating elements 38
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i r3 located in the ceiling light fixtures before it enters the lab. The air in the V
lab is changed a minimum of 13 times per hour and flows from around the ceiling light fixtures to the floor.
Each exhaust system is equipped with a prefilter, a high-efficiency fire-resistant
- filter, a
pressure-regulating
- damper, a
pressure-indicating manometer, and a Pitot tube.
Thus, the volume of air being i
exhausted at any location can be adjusted and maintained.
A much smaller amount of air is exhausted from the laboratory through open-front hoods and air-atmosphere glove boxes.
To insure against a loss of laboratory exhaust in the event of power failure, all blowers are wired into an emergency power supply.
In order to control any accidental release of contamination in the laboratory, the entire building has been pressure regulated to prevent the spread of particulate matter from one room to another or to the surrounding atmosphere.
The hallways and hot-change rooms are maintained at a pressure greater than that of any of the laboratory rooms, and the building itself, with the exception of the office area, is maintained at a negative pressure to the outside atmosphere.
Waste water from laboratory sinks and floor drains, where the possibility for radioactive contamination exists, is routed to and collected in two 6,000-gallon fiber glass storage tanks.
The tanks are equipped with indicating devices that alarm, visual and audible, when the tanks are near full. To dispose of the water collected in the tanks one et two disposal methods is taken.
To determine the method the contents of a tank is throughly mixed and then sampled.
The sample r
and a control standard are analyzed for gross alpha and beta-gamma activity. The
(~3 results of the analyses are documented.
If the concentrations and activity are
/
above the applicable standards in 10 CFR 20 then the contents are disposed of by solidification and land burial at a licensed waste site. Otherwise the disposal of the water is arranged for through commercial means.
The drains from the cold change room and the office area of JN-4 are connected to the sanitary drain to the on-site septic tank and filter bed for treatment before release.
3.2.3 Radiological Waste The processing of liquid waste from the operations at the West Jefferson site was discussed above.
In sumary, contaminated liquids from the JN-1 Hot Cell are collected and concentrated using an evaporator.
(See the discussion of the High-and Low-Level cells above.) Liquids from JN-4, the plutonium laboratory, sinks and floor drains are collected in two 6,000 gallon tanks.
Liquid in these tanks is sampled and either disposed of by a comercial contractor if the activity is acceptable for unrestricted release, or the liquid is solidified and then the solid waste disposed of by a licensed disposal contractor.
Therefore liquids which could potentially contain radioactive materials from these facilities are contained thus preventing the accidental release of radioactive materials to the sanitary sewer system. Highly contaminated liquids 40
are mixed (remotely if required) with a solidifying agent and disposed of (v]
separately rather than being permitted to mix with large volumes of mildly contaminated liquids in the holdup tanks.
Liquid wastes from the King Avenue site include solutions from the biosciences area and, possibly, waste water in the U-235 processing area.
All liquid waste from the biosciences laboratories are solidified for disposal.
Laboratory procedures insure that no solution is discharged to the sewer systems without approval of the Radiological Safety Committee.
Solid radiological wastes from operations at the King Avenue site are collected, compacted if necessary, and packaged for shipment to a licensed disposal site.
Solid waste from the West Jefferson site is from many sources. Examples of solid waste are the HEPA filters and disposal cartridge water filters, the spent ion-exchange resins, disposable clothing or other supplies consumed and contaminated in the laboratories, and gloves from the glove boxes.
Glove boxes and hoods from the plutonium laboratory that are to be discarded or replaced, and cannot be decontaminated to.non-TRU levels (i.e.,10 nCi/gm) will be disposed of at a DOE waste disposal site.
Other glove boxes will be disposed of at a licensed disposal site. The transportation of solid waste to commercial disposal sites is performed in accordance with 49 CFR and 10 CFR.
g Any releases of gaseous wastes to the environment are carefully controlled and (V
dispersed to ensure that concentrations are as low as practicable within recomended standards.
Radionuclides in particulate form are removed from exhaust stack effluents by the use of high-efficiency particulate air (HEPA) filters. The air effluents are filtered first at the points of operations, i.e.,
gloveboxes, hoods, test cells, and finally at the stack release point by one or two banks of HEPA filters in series.
Radioactive gases present in fuel pins under examination at the Hot Cell Facility are drawn off for subsequent disposal with solid wastes.
The residual gases trapped in the fuel matrix or otherwise released is monitored continously by effluent monitors.
Constant air monitors are located throughout the laboratory.
They monitor the environmental air for alpha, beta, and gama-emitting particulate matter.
These air monitors, upon detection of radiation exceeding a preset level, will activate the alarm bell.
The hot laboratory has two separate exhaust stack systems.
One for JN-1A; one for JN-1B.
There are two significant differences in the two systems. First, the JN-1A system consists of five individual stacks; the JN-1B system uses only one large stack.
The other difference in the two systems is that the JN-1B system contains a large I-131 charcoal trap.
41 1
- l 4
1 For the JN-1A stacks a single AM-2 constant air monitor is used. This instrument O-nas three channels; one monitors for alpha particulate, one for beta-gamma particulate, and one for. effluent.
Any of the three channels will activate the alarm and shut off the exhaust f an for the high level, low level, and alpha-gama i
(basement) cells.
For the JN-1B stack.' there are four separate CAMS, alpha particulate, beta-gamma i
- particulate, gaseous effluent and Iodine-131.
Any of the four instruments will i
activate. the alarm, shut down all exhaust fans for the HEC and close the butterfly valves so no more air can be drawn from the cell.
In the event that -
the I-131 monitor activates the alarm,. two additional operations take place: an exhaust fan is started and a diversion damper opens causing any exhaust air to e
flow through the charcoal trap.
i f
Although the two stack monitoring and control systems operate _ independently, they function on a similar basis.
The alarm set point of each instrument is set at a level based upon regulatory values of MPC in 10 CFR 20 for various radiation species in unrestricted areas.
Alpha particulate monitors are set on the basis of the MPC for Pu-239, beta-gama particulate monitors, on the. basis of the MPC for Sr-90.
Effluent monitors are set on the basis of the MPC for Kr-85m and the i.
I-131 monitor is set on the basis for that isotope.
I
' For each monitor, if the concentration in the stacks equals or exceeds the
- O ana14ca8ie MeC ievel thea aa aiarm and corre5Pondin9 action is taken.
under this
_ procedure the activity in unrestricted areas will remain less then the values in 10 CFR 20.
A Ventilation in the plutonium facility is provided by a system of eight exhaust f ans and eight air supply f ans that are designed and operated in a manner to both maintain-a negative pressure atmosphere in the laboratory and provide adequate 4
j air exchange.
The outside make-up air is drawn into the f acility and filtered to remove airborne particulate matter and then conditioned to regulate temperature.
1 Air movement in the laboratory is provided in a downdraft manner with the exhaust i
pickup located at the floor level. The air exhaust is made up of 9-inch diameter i
duct that empties into large volume plenums to which twelve 24" x 12" absolute L
filters are sealed.
Each exhaust stack from the facility is equipped with alarmed ~ continuous alpha monitoring to detect the release of any radioactive l
matter.
l 3.2.4 Safety and Environmental Measures i
The primary responsibility for the safety of all operations conducted at BMI l
- rests with the section managers under whose supervision the operations are conducted.
The section managers are responsible for safety, as for all other things, to the Laboratory Director through their respective Department Managers.
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Q The Safety Office shares the responsibility for safe operations throughout BMI.
V In all operations the Safety Office performs the functions of consulting, surveillance, and education.
It has the authority, through the office of the Laboratory Director, to order the cessation or modification of experiments which it believes to be unsafe.
The Radiation Safety Comittee (RSC) shares with the Safety Office additional responsibility for the safe conduct of experiments involving radiological safety.
The primary RSC function is to review experiments planned by the research staff.
The RSC has the responsibility and au thority, through the office of the Laboratory Director, to interdict the operation of a facility or an experiment believed to be potentially unsafe to personnel, property or the environment.
3.2.4.1 Environmental Monitoring The impact of operations on the health and safety of the public is evaluated i
routinely by an environmental monitoring program which has been in existence since 1955.
The basic objective of the environmental monitoring program is to evaluate the effectiveness of the waste management program in maintaining the concentrations of radioactive and non-radioactive wastes so that effluent levels are maintained as low as reasonably achievable and well within applicable q
standards.
All effluents involving polluting materials are contained within the V
operating facilities to the extent possible and are disposed of as packaged wastes by authorized services.
A sanitary sewerage system, which is operated in accordance with State of Ohio regulations under NPDES permit no. N404-CD, handles all sanitary sewerage generated on the West Jefferson Site.
The liquids are first treated in a 7,000-gallon septic tank and then re'. eased to a 2,300-sq-foot sand and gravel filter bed. From the filter bed the effluent goes to a chlorinating system prior to release to Big Darby Creek.
Figure 3.16 shows the location of the gaseous and liquid effluent release points for the West Jefferson site.
Each of the release points is monitored as part of the environmental monitoring program.
Additional air and water sampling locations are indicated on Figure 3.17.
The soil, foodcrop, and grass sampling locations are shown on Figure 3.18.
In addition to the monitoring locations shown on Figures 3.16, 3.17, and 3.18, there are several air sampling stations within the perimeter fence as well as numerous environmental TLD stations along the perimeter fence.
Results of the monitoring program are summarized and reported annually.
Liquid effluent from operations at the King Avenue site are monitored for gross alpha and beta activity.
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A SCAll ifIi Figure 3.17 Map of Site Boundary Air Sampling Locations and Battelle Lake and Darby Creek Water Sampling Locations
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3.2.4.2 Health Physics r&
The Health Physics department is vitally concerned with safety measures.
Its activities at the BMI sites includes the following:
e Maintenance of current files of Codes of Federal Regulations, USNRC l Rules and Regulations, Title 10, Chapter I,
AEC Regulatory Guides, AEC Manual Chapters dealing with health and safety, Reports of the NCRP, ICRP, and ICRU, applicable ANSI Standards, miscellaneous AEC and other publications concerning health and safety, e
Monitoring and sampling programs for evaluating releases of radioactivity in liquids, particulates, or gases to the environment.
e Effectuation and management of personnel dosimetry programs employing film as the primary dosimeter with pocket chambers and TLD units as exposure control devices, and maintenance of personnel dosimetry permanent records as required by regulations.
4 e
Routine personnel bioassay sampling and analysis programs for radioactive nuclides.
e Individual personnel breathing zone air sampling programs.
e Monitoring and sampling programs for evaluating airborne radioactive nuclides in work areas.
e Radiation and surfaces monitoring programs in work areas, e
Training and fitting programs for respiratory protective devices for routine or emergency use.
e 00P-testing program for HEPA final filters.
i e
Radiological consulting and advising for routine, special, and emergency situations.
e Surveying and evaluat_ ion of equipment and procedures with respect to compliance with rules, standards, and regulations.
For the years 1978 and 1979 the annual average personnel exposure in the plutonium laboratory was less than 0.2 rem /per person.
The maximum exposure in the plutonium laboratory was 0.2 rem for these years. The annual average for the same years in the hot cell was 1.5 rem; the maximum exposure was between 4 and 5 rem for 1978 and 2 to 3 rem for 1979; and the minimum exposure being less than 0.1 rem.
47
Plutonium Laboratory Routine beta-gama radiation probe surveys - are performed on a weekly basis at various glovebox _. locations throughout the laboratory.
Survey data are recorded on External Radiation Survey Form, HPS-RS-68. Personnel monitors are provided at exit points from the laboratory areas and buildings.
All. persons who enter laboratory areas - are instructed to monitor themselves before leaving the laboratory. The laboratory area exit monitors are alpha hand and foot type and movable hand-held types.
Approximately 200 surface smears of floor areas, gloveboxes, gloves, laboratory equipment and desks are taken routinely __ on a weekly basis throughout the laboratory. Survey data are recorded on Smear Survey Report Form,- HPS-51-73.
All' laboratory areas where the existence of airborne radioactive materials is a distinct possibility _ are continuously monitored with alpha-type continuous air monitors (CAMS).
All of the CAMS are equipped with audible alarms.
All personnel wear " lapel" air samplers while working in the laboratory.
Filters associated with routine operations are removed and _ analyzed daily prior to starting work for the day as an aid in assessing the ' percent of the weekly permissible concentration.
O An Alarm System has been installed on the Stack Monitors SC-1, SC-2, SC-3, and l
SC-4. When any monitor reaches the alarm point, pulsing sonalerts are actuated I
throughout the laboratory _and the office area.
In the count-rate-meter of each CAM, there is a' meter relay.
When the meter pointer contacts the set point, a relay located in the Mechanical Equipment Room is actuated which sounds the Bell Alarm System in the laboratory and the office l
areas.
~ An additional part of the safety measures for the plutonium laboratory is the general procedure for handling fissile materials.
The major points of these procedures are:
o All shipment containers of fissile materials received at the lab must be opened in the down-draft room with the proper health physics supervision, o
Fissile material or contaminated items transferred through the lab must be contained in vessels with uncontaminated surfaces.
O 48
(-)
o The opening of transfer containers of fissile material must v
be performed in gloveboxes, o
Plastic pouches containing fissile material should be placed in protective vessels prior to being transported through the lab.
o The storage of fissile material within gloveboxes must be in sealed containers.
Hot Cell Laboratory Radiation levels and various automatic operations within the laboratory are constantly monitored by a system of detectors and sensors.
Any abnormality or deviation from normal conditions is indicated by a designated alarm.
Specific radiation conditions within the laboratory which are alarmed are:
o Criticality Conditions o
Airborne Radiation-Emitting Particulate Matter o
Exhaust Stack Effluent o
Poolside Gama Background q
o Water Hold-Up Tank Gama Background L
1 o
Background Level at the HEC Air Intake Duct.
Of the several alarm alerts, two are laboratory wide and require immediate evacuation of the building by all personnel. These are the criticality alarm and a constant air monitor alarm.
Other alarm indicators are generally audible or visible only in the vicinity of the problem.
They usually require investigation and corrective action but not evacuation of the building.
Within the hot cell laboratory
- itself, three specific areas are continuously monitored for gama-radiation background.
These are: the area above the storage and transfer pool, the 5,000 gallon waste water hold-up tank, and the HEC air-inlet duct.
Each meter has an alarm set-point which is set at a predetermined level.
The alarm level is determined in accord with the background level of the particular area being monitored.
Each monitor has a separately functioning alarm which consists of a locally audible sonalert tone and a panel-mounted indicator light.
The response to the alarm is to investigate its cause and initiate corrective action as required.
The primary purpose for monitoring the gama radiation background in each of these areas differ.
In the case of the pool, the radiation background indicates j]
the sufficiency of shielding provided by the water.
Should the level of the pool 49
q water drop or if radioactive material is raised so high in the pool that b
sufficient shielding is not provided, the alarm would indicate the presence of a high radiation level.
In the event of a low water level, independent water level sensors will automatically actuate the make-up water pump and add water to the p ool.
The hold-up tank monitor gives an indication of the degree of contamination being generated in laboratory waste water.
The radiation level at the air-inlet duct produces a background in the cell operating areas.
Monitoring the level at the single duct location provides qualitative monitoring of several laboratory operating areas.
Three display panels indicate key operational and radiaticn conditions throughout the laboratory.
One panel is a Honeywall control and display panel located in the HEC operating area. Another is a f an indicator panel located on the exterior west wall of the HLC.
Tne third is an indicator panel located inside the main personnel entrance door. Abnormal conditions are indicated by panel lights and, locally, audible alarms.
3.2.4.3 Fire Detection and Control n
Fire protection is important for the safe operation of the facilities.
In addition to its own fire fighting capabilities the West Jefferson Nuclear Sciences Facility has an assistance agreement with the West Jefferson Village Fire Department. They maintain close liaison and hold periodic meetings between the Facility Staff and Fire Department personnel to conduct planning and provide Fire Department personnel familiarization with the Facility.
Plutonium Laboratory For the plutonium laboratory the f acility design and operations addresses both fire detection and subsequent fire control.
The fire detection system consists of six major components:
o The fire detectors are Fenwal 130-degree rate of rise-fixed temperature detectors, o
The local alarm boxes are a combination of a detector and an alarm system that are provided for each glovebox and each room.
Each local alarm box has its own power supply (emergency power) and its own alarm readout and is provided with a set of normally closed contacts for the main alarm system.
1 OV 50
1
~q o'
A main' relay box is provided that transmits signals from the D:
local alarm boxes to the building fire alarms, and the alarm panel. ' This relay box is wired to each local' alarm box.
o The building alarms for fire are intermittent bells or. gongs (ding----ding----ding----)
that are activated by current 1
supplied' by the main relay box. The bells are located one to
-a. room with one located outside the south end of the building.
o The alarm panel. mentioned at the-beginning of this section provides readout for the entire fire alarm system. All local alarm boxes are represented by red neon pilot -lights located realistically on a lab schematic diagram.
o Glovebox fire alarms are indicated by 1/2-inch - diameter red lights and the room fire alarms are indicated by 1-inch diameter amber lights.
For fire suppression, the laboratory has the use of both fire extinguishers and-hoses. The specific extinguishers are CO2 (15 lb), Haylon 1211 (8 lb), and water (2-1/2 gal) extinguishers.
The extinguishers are located throughout the lab and office areas.
The classification and use charts are posted by each container.
All containers are checked by a local inspection company semiannually, and monthly visual checks are made by lab personnel.
.O Four fire' hoses are locate'd in the laboratory area (none in the office area) with varying lengths, according to the area they must cover.
All. are 1-inch high-pressure rubber hoses on reels equipped with fog nozzles and a wall-mounted valve. These hose lines are not alarmed but are inspected at regular intervals.
Hot Cell Laboratory The HEC smoke detection' system monitors the air (a) flowing into the High Energy Cell lthrough the air in-take duct and (b) flowing from the service area into the HEC operating area.
If either of these detectors senses smoke, an alarm is activated.
The alarm consists of a repeating gong audible throughout the operating area.
In addition, a red light indicating which detector has been activated lights on the Honeywell control panel and the panel buzzer sounds.
The High Energy Cell has an in-cell automatic sprinkler system for fighting in-cell fires. The control panel for this system is located in the HEC operating area.
It has two alarms:
(1) A flashing sign with legend " Low Pressure In-Cell Fire Monitor".
This indicates that the water pressure or the air pressure in the sprinkler system is below a safe level.
O 51 1
p (2) An Electronic Wailer which sounds in the event of an in-cell V
fire.
3.2.4.4 Materials and Plant Protection Physical Protection and Material Accounting Current safeguards are set forth in 10 CFR Parts 70 and 73. The regulations in Part 70 provide for material accounting and control requirements with respect to f acility organization, material control arrangements, accountability measurements, statistical controls, inventory methods, shipping and receiving procedures, material storage practices, records and reports, and management control.
The Comission's current regulations in 10 CFR Part 73 provide requirements for the physical security and protection of fixed sites and transportation involving strategic quantities of nuclear materials.
Physical security requirments for i
protecting fixed sites include the establishment and training of a security organization (including armed guard s), provision for physical barriers, and establishment of response plans.
The Comission's regulations in 10 CFR Parts 70 and 73, describ'ed briefly above, are applied in the review of individual license and permit applications. License pJ 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 f acility involved.
The Battelle Columbus site is an existing licensed activity, and while experience and continuing study may indicate areas where revisions in the Comission's regulations applicable to the Battelle site should be made, the Comission has determined that for the kind of installation under review the safeguards framework of existing and proposed regulations discussed in its statements of November 14, 1975 and January 27, 1977 is adequate to enable the Comission to carry out its responsibilities to protect the public health and safety and the comon defense and security.
The licensee has material control and accounting plans and physical security plans that meet the current requirements of 10 CFR Parts 70 and 73.
It is concluded that the applicant's safeguards-related activities have insignificant environmental impact.
- Reference 40 CFR 53056 and 40 CFR 5150.
i O
52
o 3.3 ALTERNATE ACTIONS V
3.3.1 License Renewal An alternative to the proposed action would be the renewal of the license for the King Avenue and West Jefferson Nuclear Facilities while maintaining the limits specified by the current license for the possession and processing of radioactive materials.
Possible advantages of this alternative could be: (1) Simplification of the license renewal process; (2)
Obviation of the general public's possible opposition to change in operations it has come to accept; and (3) No change in the statistical probability of an accidental release.
The disadvantage of this alternative is that it could limit the scope of services which could be otherwise provided by the BMI Facilities and which may be needed by the nuclear conrnunity as the state-of-the-art expands and new uses for radioactive materials are found.
3.3.2 No Action-O V
This alternative would be manifested by the NRC denial of license renewal as petitioned for by BMI, i.e., no action would bring an end to the testing and research on radioactive materials at the BMI.
The denial of license renewal would result in either (1) "mothballing" the BMI facilities (which would involve some kind of license) or (2) decommissioning and decontamination of the facilities so that no license would be required.*
- It should be noted that at some time the facilities currently in use will be retired from use, decontaminated and decommissioned in accordance with NRC guide-lines. BMI has made provisions for underwriting the cost of the decommissioning O
activities with revenue generated from the use of the facilities.
53
/7 4.0 AFFECTED ENVIRONMENT V
This section of this Environmental Assessment discusses those environmental components which will or could be affected by the proposed action.
It will also discuss environmental components which will not be affected by operations but could themselves affect operations and thereby the environment.
For example:
geological, hydrological and meteorological components would be affected by neither the proposed license renewal nor subsequent operations.
Certain geological and/or meteorologic phenomena could, however, affect operations (implicit in license renewal) such that environmental hazards could conceivably result.
These kinds of environmental components will be addressed in following subsections.
4.1 AFFECTED ENVIRONMENT OF THE PROPOSED ACTION 4.1.1 Historical Data Radionuclide releases to the environment from Battelle's West Jefferson Nuclear Sciences and King Avenue Sites are sumarized in Tables 4.1 and 4.2 for CY 1979, 1978 and 1977.
Nonradioactive effluents in water discharged from the West Jefferson Site were also monitored.
The highest average concentration at the site boundary for any identified radionuclide emitted was less than a few hundredth of the respective RCG value. No significant uptake of radionuclides by grass or food crops in the vicinity of the West Jefferson Site was observed.
The amount of radioactivity discharged to the atmosphere from the King Avenue Facility is not known due to the cessation of atmospheric monitoring in June of 1975.
Monitoring was stopped at this time due to the sharp cutback in uranium operations at the f acility.
Prior to the cutbacks the total annual radioactivity in atmospheric emissions was 0.32 uCi.
The U.S.
Department of Energy, Energy Research and Development Radiation Concentration Guide (RCG) specifies the maximum acceptable radiation emission for radioactive materials.
Table 4.3 is a sumary of atmospheric radioactive emissions from the West Jefferson Nuclear Sciences Facility including percentage of RCG value during the years 1977, 1978 and 1979.
The BMI Environmental Reports for calendar years 1977, 1978 and 1979 on Radiological and Nonradiological Parameters list the gama emitting radionuclides identified in the building JN-1 (Hot Cell) stack emissions along with concentrations and percentage of RCG values. The largest fraction of the maximum permissible exposure for atmospheric releases from the West Jefferson Site was found to occur to the skin (1977),
kidney (1978), and lung (1977) at the site boundary and, in all cases, was 0.003%
or less of the limits recomended by ICRP.
The average concentration of mixed alpha and beta activity releasd in liquid discharges from the King Avenue Site was less than 2.5% of the RCG value.
54
Table 4.1
SUMMARY
OF TOTAL AIR RELEASES OF RADI0 ACTIVITY FOR CY 1979, 1978, 1977 West Jefferson Site s- '
Activity (uti) 1979 1978 1977 Gross Alpha 0.12 0.03 1.84 Gross Beta 2.18 0.76 7.38 Plutonium-239 0.34 1.14 0.60 Cobalt-60.
2.50 26.77 139.29 Cobalt-57 0.11 2.13 0.04 Thallium-208 1.09 2.71 Cesium-137 0.09 4.41 1.3 Lead-210 0.04 0.30 Cesium-134 0.03 0.25 0.13 Lead-212 0.41 0.88 Lead-214 0.26 0.52 Tantalum-182 0.04 Cesium-136 0.38 Cadmium-109 0.57 Krypton-85m 0.04 0.02 Bismuth-214 1.63 37.59 Cerium-144 0.73 0.07 Antimony-125 0.55 9.64 34.89 Terbium-160 0.10 0.10 0.32 Krypton-85 812810.00 1859.70 5.24 Rhodium-101 0.03 r~
Cerium-139 0.02 i _)/
Actinium-228 0.76 0.20 s
0.006 Barium-133-1.70 Xenon-138 0.21 0.04 Cerium-141 0.03 0.48 Barium-140 0.13 Americium-241' O.05 Samarium-145 0.23 0.16 Manganese-54 0.11 Iodine-129 0.013 0.19 Uranium-235 0.02 Europium-155 0.19 0.45 Europium-154 0.01 Thorium-234 0.03 Dysprosium-159 0.04 1.91 0.02 Chromium-51 0.13 0.06 Tin-113 0.61 0.22 Zirconium-95 0.04 Niobium-95 0.004 Iridium-192 0.15 Iodine-131 0.14 Ruthenium-97 0.27 Antimony-124 29.41 Lanthanum-140 0.29 Xenon-113m 0.09 Zinc-65 1.05 0.42
('d'N Mercury-203 C.65 Rodium-103m 1.02 Ruthenium-103 0.12 Bismuth-207 55
Table 4.2 d
SUPMARY OF TOTAL WATER RELEASES OF RADI0 ACTIVITY FOR CY 1979, 1978 AND 1977 West Jefferson Site Activity (uCi) 1979 1978 1977 Gross Alpha 82.68 0.03 0.007 Gross Beta 20M0 0.14 0.38 Iodine-129 2.23 OT048 07003 Cesium-137 158.84 0.17 0.22 Strontium-90 81.88 0.073 0.096 Plutonium-238 0.03 0.0006 0.0002 Plutonium-239 0.03 0.0004 0.0002 Radium-226 4.13 0.002 0.009 Radium-228 2.23 0.001 0.04 0.06 Cobal t-60 21.78 0.02 Cobal t-58 0.11 Chromium-51.
0.009 Rutnenium-103 2
27/
o.295 0.sc 7 King Avenue Site Gross Alpha 477.8 211.2 409.2 Gross Beta 798.6 686.4 171.6 0
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59
(3 4.1.2 Air Quality V
Air quality standards, both national and for the State of Ohio, are enumerated in Table 4.4.
The ambient air quality at the BMI King Avenue Facility can be characterized by data recorded at the Ohio EPA (0 EPA) air quality monitoring stations located at 1313 Chesapeake Avenue and at 1016 Grandview Avenue in Columbus, Ohio, approximately one mile west and one and one half miles southw@t of the BMI King Avenue Facility, respectively.
These data (Ohio EPA, Ohio Air Quality 1978) indicate that standards for total suspended solids and photochemical oxidants are exceeded.
Other pollutants: sulfur dioxide, carbon monoxide, and nitrogen oxides are present in measurable amounts but do not exceed standards.
For the West Jefferson Site, data from the nearest OEPA ambient air monitoring.
station (New Rome: six miles east of the West Jefferson site) does not 'ndicate.
any exceeding of either State or National Ambient Air Quality Standards at that s ite. The more rural location of the Nuclear Sciences Facility and the f act that this location is basically upwind of any significant metropolitan / industrial area makes it reasonable to assume the air quality there is at least as good as at New -
Rome.
As most of the area surrounding the Nuclear Sciences Facility is a agricultural, the one possible ambient air pollutant could be fugitive dust generated by farming activities.
Historically,
- however, particulate' concentrations have not been a problem in f arming areas of central Ohio.
4.1.3 Historical and Archaeological Sites Since no additional off-site construction is expected at BMI, no effects on historic sites are expected due to construction.
The release of radionuclides from the BMI facilities during both normal operations and possible accidental releases would have no detrimental effect on nearby historic sites. The release of any nonradiological effluents to the environment is also expected to be of such a low level as to be of no significant consequence.
The operation of the BMI Columbus Laboratories under the proposed NRC license is expected to have no adverse or detrimental effects on historic and archaeological sites or natural landmarks.
4.1.4 Climatology The proposed licensing renewal and subsequent permitted operations at the BMI Facilities will not affect regional nor local climatological / meterological conditions as no significant production of thermal, gaseous, or solid pollutants will result.
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4 5
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's
US s
pu li, o Q LEA _NT tellATIf4t DFSTRICTi es 2 s e ansinnen,,
Mary Serenderz f
- k \\
Seepended Annual met te be esceeded
+N.
3 # 60 75 60 Particulates pese (C) 7 "s 3
24-hour po'. to be enceeded more
. 150 260 150 3
esmeentration then once per year Setter A*wel met to be enceeded 60 (.02)**
00 (.01)
Stestde Meen (A) s
!&-heer mot to be onceeded more 260 f.IO) 365
.14).
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.e-. ate.t..a st a e.,er,*er s
3-hour
.e-eeneentratten
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1.100 (.50)
Cerben S-hour seen (A) met sie be esceeded more thes to* (9.0) 10* (9.0) 10* (9.0)
Itenentde concentratten 1 eight beer persed par year l-hour seen (A) pet to be esceeded more 40* (35.0) 408 (35.0) concentration then once per year Ch w
Photochesteel 1-heer even (A)
Det *e be escoeded 189 (0.06)
IfO (.09) 160 (.00) coldsste concentratten 4-hour seen (A) pet to be enreeded more then I 79 (0.04) j eencentratten eeneecettee 4-hour period per year 4
24-hour seen (A)
Not to be enceeded more then 1 40 (0.02) ge.
concentratten,
doy per year pen-mothese 3-hour seen (A) pet to be enceeded between 176 (0.19) 160 (.74) 160 (.24) p drocarbene eencontratten 6 AM end 9 Ase y
24-hour mese (A) pet to be esceeded more then 1 318(5.50) concentration day per year pttregen Annual seen (A) pot to be escoeded 100 (.05) 100 (.05) 100 (.05)
Dioelde Lead Quarterly seen (A) feet to be escoeded
==
3.5 (A) Artthmette (C) Geneetrie
- Only etenderd espreseed in ellIleveme per eiAle meter Frieery St enderd - For treteet ten of Public neelth
- Tetwee in po'enthenee__ere egelvelent eelwee in perte per etilgen.
SerenJary Sean.leed - Far Frasertgan of Fut.lle tielfare v
,1 1
t%
4.1.5 Geology Q
The proposed relicensing of the BMI Facilities, and their subsequent operation, will have no affect on the geology of the area.
The only other concern then, becomes the possible affects of the geology on the operating facilities.
The affecting geologic activity would be seismic. The BMI f acilities are in a Zone 1 risk area.
4.1.6 Hydrology The proposed action will not affect, adversely or otherwise, the hydrology in the West Jefferson site area.
A minute, man-made addition to the Big Darby annual flow results from the Facility's sanitary sewage plant.
The annual addition amounts to an estimated 0.000485% of the Big Darby annual flow.
Historical and current data, and the location of the West Jefferson Nuclear Sciences Facility at 910 feet msl, indicate the Facility's high immunity to flooding. However, the possibility that the principal hydrological feature, Big Darby Creek, might affect the West Jefferson Nuclear Sciences Area is considered.
p Using the PMP estimates given in section 3.1.4 above simplified calculations v
(without benefit of detailed data on the topography and drainage system of the drainage area) were conducted to approximate stream loading.
The PMP of 19 inches in a six hour period was the worst case with a calculated loading rate of 497,283 cfs.
(No attempt was made to relate loading the flow capacity.)
An investigation of stream flow capacity, done previously,1 calculated (using the Manwing equation with a slope of 0.1% and a n value of 0.04) a flow capacity of 329,000 cfs for the Big Darby at the 900 foot elevation adjacent to the West Jefferson Nuclear Sciences Facility.
It should be noted that calculations using the National Weather Service PMP rates will be extremely conservative in view of the fact that the maximum recorded precipitation in the area, for any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, was 4.8 inches.
1 Nuclear Regulatory Comission Memorandum to Chief, Nuclear Fuel Reprocessing and Recycle Branch, Division of Fuel Cycle and Material Safety from Chief, Hydrology-Meteorology Branch, Division of Site Safety and Environmental Analysis, June 27, 1978.
62 I
O 4.2 AFFECTED ENVIRONMENT OF THE ALTERNATIVES U
4.2.1 Current License Renewal Renewal of the license with the same stipulations that are contained in the current license would, under normal operating conditions, have no more effects on environmental components than have past facilities' operations, and these have been negligible.
4.2.2 No Action The alternative could cause decommissioning of the West Jefferson Nuclear Sciences Facility and/or placing it in a caretaker status.
Decomissioning, disassembly, decontamination and disposal of equipment could conceivably result in increased risk of accidental. release of radioactive contaminants during the process. Placing the f acility in a caretaker status would result in a dimunition of monitoring and maintenance activities and present the possibility of undetected release of residual radioactivity due to component deterioration.
OV 63 i
5.0 ACCIDENT ANALYSIS Several accidents which are considered to be bounding cases from a consequence standpoint were postulated and analyzed for the West Jefferson Nuclear Sciences Center and Biosciences Laboratory. The purpose of this analysis was to estimate environmental consequences resulting from operating accidents at the sites. The accidents included at the West Jefferson Site were e
Fuel assembly drop in the JN-1 high energy cell e
Criticality in the JN-1 high enengy cell e
Explosion in a JN-4 glovebox e
Fire and for the Biosciences Laboratory e
Release of radioactive iodine e
Release of radioactive carbon dioxide O
C e
Release of radioactive carbon powders.
- Other accidents were also postulated but upon initial examination they involved smaller releases of material than the above accidents and therefore were not developed further.
Among the accidents which were considered but which had smaller or no releases were cask drop in JN-1, waste handling accident, fire in the operating areas and fire in JN-1 cells.
In all cases, the three major accidents identified above were judged to be bounding in terms of releases and consequences.
This environmental appraisal only looked at offsite effects. Each of these three bounding accidents are briefly discussed in the following paragraphs.
5.1 WEST JEFFERSON SITE Fuel Assembly Drop This accident is of interest because it represents an opportunity for the volatile components in spent reactor fuel to be released over a short term and dispersed by the building ventilation.
In general, this accident could occur in or out of the storage pool.
A more pessimistic case of the assembly drop accident occuring in the high-energy cell is considered in this situation where no fission product adsorption by water is involved.
64
p It is assumed that two fuel assemblies are involved in the accident, one dropping V
on top of the other.
It is further assumed that all of the fuel pins are ruptured so that volatile gases can be released. The inventory of volatile gases is obtained by conservatively assuming that the two assemblies are from a pressurized water reactor (PWR), have been irradiated to 44,000 MWD /MT and have been cooled 60 days.
With these assumptions, the inventory of the volatile radionuclides in the cladding-fuel gap are calculated and the results presented in Table 5.1.
The gases are assumed to be released over a very short time such that all of the activity is in the high energy cell atmosphere. 3 This atmgsphere is changed out at the rate of 1.7 minutes per change (8,550 ft /5,000 ft / min).
Assuming complete mixing within the cell, 95% of the activity will have been released within five minutes.
Automatic activation of an iodine absorption system is assumed to work at its rated efficiency of 99.9%.
On the above basis Table 5.2 presents the " average" concentration of radionuclides products assumed to be released during the accident.
Table 5.3 lists the calculated doses at the site boundary and at the nearest residence (2500 feet to the SW) resulting from the release of activity given in Table 5.2.
Criticality O
Criticality, like other accidents could occur in a variety of places.
While its probability of occuring does appear to be very small it has been addressed as an accident in the Nuclear Sciences Facilities.
It is conceivable that a
criticality could occur in two buildings at the West Jefferson Site. The first of these is in the plutonium laboratory, JN-4 and would involve the release of volatile fission products to the atmosphere. The second would involve spent fuel assemblies in the JN-1 pool or High Energy Cell.
This second criticality scenario is considered to be the worst case because of the higher initial inventory of volatile fission products before the criticality.
An array of 4 PWR assemblies each with 44,000 MWD /MT exposure and cooled sixty days are assumed to be moderated and reflected by water spray from the High Energy Cell fire sprinklers.
The volatile isotopes which are initially present in the assemblies and induced by ghe criticality are presented in Table 5.3.
It 1
is assumed that a total of 7 x 10 fissions occur in the fuel.
As with the assembly drop accident, it is assumed that all of the elements rupture due to pressurization caused by the rapid energy release.
Also it is again assumed that 30% of the volatile radionuclides are released because they exist in the gap between the fuel and tge cladding.
The iodine isotopes are reduced in concentration by a factor of 10 due to the absorption by the charcoal filter beds. The materia is assumed to be released within 5 minutes in a volume of air equal to 25,000 ft 65
I f
o 1
. Table 5.1 Inventory of Volatile Radionuclide in 2 PWR Assemblies Cladding-fuel Gap'
. Irradiated to 44,000 MWD /MT and Cooled 6'O Days 3
i n
Radionuclide Curies
% of Total Inventory v
H-3 273 30 Kr 3950 30 I-129 1.62 x 10~4
.30 i
i 1-131 19.3 30 1
i Xe-131m 212.7 30 f
.Xe-133 212.7 30 4
i
!O I
l 1
I l
L l
b.
I i
l l
(:)
I 1
66
0:
Table 5.2.. Amount and Concentration of Gaseous Release 'During Assembly Drop Accident 3
Radionuclides Curies Release to Stack Average Concentration (Ci/ft )
H-3 273 1.1 x 10-2 Kr-85 3950 1.6 x 10-1
-7 I-129 1.62 x 10 6.5 x 10-12 I-131' 1.93 x 10-2 7.7 x 10-7 Xe-131m 212.7 8.5 x 10-3 Xe-133 212.7 8.5 x 10-3 0
O 67
O.
O IO:
Table 5.3 Estimated Doses (REM) From Airborne Releases Due To Postulated Bounding Accidents Assembly Drop in Criticality in Explosion / Fire Organ High Energy Cell High Energy Cell in Glovebox-Fenceline Nearest Res.
Fenceline Nearest Res.
Fenceline Nearest Res.
Total Body 1.5E-1 6.8E-3 6.3E O 2.8E-1 8.0E-4 3.5E-5 Kidneys 1.4E-1 6.3E-3 5.0E O 2.2E-1 3.6E-3 1.6E-4 Liver 1.4E-1 6.1E-3 5.4E O 2.4E-1 3.8E-3 1.7E-4 Bone 1.7E-1 7.0E-3 7.2E O 3.2E-1 3.3E-2 1.5E-3 Thyroid 2.3E-1 1.0E-2 2.0E+1 9.0E-1 G.I. Tract 1.4E-1 6.0E-3 6.4E O 2.8E-1 5.9E-7 2.6E-8 Lungs 1.5E-3 6.4E-5
n
~
p _ Table 5.4 presents the amounts and concentrations of each of the isotopes mleased during the spent fuel criticality.
x Explosion An explosion in the plutonium hot lab was considered as an accident for the release of material to the environment. An apparent worst case scenario involves the explosion in a glovebox containing plutonium.
The explosion could possibly come from the solvent that might be used in plutonium analysis or possible material cleaning.
It was assumed that an explosion occurred in a glovebox containing 500 grams of plutonium.
Of the 500 grams of plutonium it was assumed that because a glovebox is about 50%
windows and gloves 50% was dispersed in the room outside the glovebox and 50% was retained in the glovebox. The portion which entered the room is assumed to pass through three stages' of HEPA filters with an efficiency of 99.8% for-the third.
Of the material which remains in the glovebox, it is assumed that 10% passes a failed HEPA filter in the glovebox and then to two stages of HEPA filters each with an efficiency of 99.95%. The amount of material released through each route as well as the air flow rates are presented in Figure 5.1.
Assuming perfect mixing in the room, over 99% of the material is removed within q
15 ginutes)
Over this time period, the average concentration is 1.25 x 10- gPu/ft.
Table 5.3 lists the calculated doses at the site boundary and at the nearest residence resulting from the release of 6.38x10-6 grams of plutonium.
v Assuming a reduced mixing effect would result in lower releases due to the increased settling of material within the room.
Fire
~
A fire accident in the plutonium laboratory was also examined in order to determine the consequences from this type of accident.
Because of the limited combustable' loading of plutonium handling in the JN-4 gloveboxes it it not likely that any fire will burn for very long or that filters will fail.
For this analysis however it was assumed that there was a 15 minute fire and that the first filter failed. The two remaining HEPA filters are considered to remain operational.
The amoynt of plutonium 'which enters the ventilation system is assumed to be 33 mg/m, the maximum air loading according to General Electric calculations.
Two HEPA filters with an efficiency of 99.95% wi concentration of plutonium released to the atmosphere to 8.25 x 10-]1 reduce t g
grams /m.
Table 5.3 lists the calculated doses at the sjte boundary and at the nearest residence resulting from the release of 8.25x10- grams of plutonium.
O i
69
)
.:0 ras e 5.4 The Amounts and Average Concentration of Radionuclides Released During a JN-1 Criticality 3
Radionuclides Amount Released (Ci)
Average Concentration (Ci/ft )
1-129 3.3 x 10-5
-1.3 x 10~9
.I-131 3.9 1.5 x 10~4 I-132 1.7 x 10 6.6 x 10-7 2
I-133 5.7 x 10-2
- 2.3 x 10-6 I-134 1.0 4.0 x 10-5 I-135 2.4 x 10~1 9.4 x 10-6 Kr-83m 1.5 x 10 5.9 x 10-4 1
Kr-85 7.9 x 10 3.2 x 10~1 3
-Kr-85m 7.2 x 10 2.9 x 10-3 1
Kr-87 4.3 x 10 1.7 x 10-2 2
Kr-88 3.1 x 10 1.2 x 10-2 2
O Xe-131m 4.3 x 10 1.7 x 10-2 2
Xe-133 5.5 x 10 2.2 x 10-2 2
Xe-133m 1.0 4.1 x 10-5 Xe-135 2.7 x 10 1.1 x 10-3 1
Xe-135m 6.6 x 10 2.6 x 10-3 1
Xe-138 1.9 x 10 7.6 x 10-2 3
]
O 1
70
?
v._.,, -,, _,,, <.,. -, -
.-,,,,,-.----.__.,-,.,._.~.-_.m,..-,.__-._,,.-.,,,,_.,..._.._-,,c-_.-,..,__,-
O O
O 2 Stages of HEPA
[
1]l
+ To stack, 3400 cfm Inlet Flow Pu release 6.25 x 10-0 from hood 1
3400 cfm l
k]
1.25 x 10-7 from room 6.38 x 10-6 total t
i 1
4 l
f 10g Pu I
GLOVEB0X y
e 250g Pu 4
l i
PLUT0NIUM LAB HEPA Filter i
I Figure 5.1 Air Flow Through Plutonium Laboratory for 1
the Explosioii Accident I
i
5.2 KING AVENUE SITE A likely accident that might occur is the spill of a liquid solution containing between one microcurie to one millicurie of a radionuclide. The volume of liquid would be in the range of few milliliters.
The spill would in most instances contaminate only a small area and be contained and cleaned up in a short period of time.
An offsite release would occur only if the radionuclide is in a volatile chemical state, a comon example being tritiated water.
In this case a fraction of the spilled liquid would evaporate and the radionuclide would escape via the exhaust hoods into the atmosphere. The magnitude of the offsite release
[
would depend on the volatility of the radionuclide and on how quickly the spill
\\
is contained. Assuming a volatilized fraction of 5% and a total sample activity of 100 microcuries, the offsite release would be 5 microcuries.
The resulting exhaust plume would be extremely diluted due to the release mechanism.
The assumption of a constant evaporation rate from the time of the spill to the time of containment, perhaps 3 minu tes, combined with the diffusion of the radionuclide throughout the room (assuming the spill did not occur inside a fume hood), would suggest a source term for the release at the exhaust stack of less than one microcurie per minute over a period of approximately five minutes.
A one-time release of this magnitude and duration would have no significant effect on the offsite environment.
Three severe accidents are postulated based on the release of the entire
,o inventory of a given isotope.
The three examples involve the release of a gas, a U
volatile iodine compound, and a powder. Although the handling of such quantities of radionuclides in these chemical and physical forms is not expected in the course of expected normal operation of the laboratory, their possession and hand ling is not excluded by the proposed license.
The consequences are sumarized in Table 5.5.
Radioactive Gas Release, Unfiltered The first severe accident is postulagd to be the release of 30 curies of a 0, into the laboratory building or the radioactive gas, such as tritium or C 2
exhaust hoods.
Both gases would pass through any HEPA or charcoal filter and be released into the atmosphere.
Assuming the initial release from the gas bottle is instantaneous, the source term at the exhaust stack would range from a puff of short duration (less than one minute) for a release in a fume hood to a substantial-release of a smaller rate for a longer duration (perhaps five to ten minu tes).
This type of release can not be readily contained.
Iodine Release A second severe accident is the release of 30 curies of I-131 in a volatile organic compound. With the basic assumption that the initial release is within a (7
fume hood, the source term at the exhaust stack depends on whether or not a V
71
-(5
. yf Table 5.5' Estimated Doses at 400 Meters From Airborne Releases Due to Postulated Accidents (King Avenue Site) 1 t
Dose (rem) 1 Organ Case 1(2)
Case 2 Case 3 Total Body 9.7E-03 9.7E-06 1.4E-03 Kidneys 9.7E-03 9.7E-06 1.4E-03 Liver 9.7E-03 9.7E-06 1.3E-03 l
l Bone 5.2E-02 5.2E-05 1.8E-03 i
L Thyroid 9.7E-03 9.7E-06 3.5E-02 G. I. Tract 9.7E-03 9.7E-03 1.1E-03 Lungs 9.7E-03 9.7E-06 1.4E-03 l
l t
(1)
Dose includes exposure to plume and ground during plume passage and 50-year dose commitments resulting from inhalation of l
activity during plume passage.
(2) Cases:
l l
1 - Release of 30 Ci of C-14 as gas l
2 - Release of 0.03 Ci of C-14 as powder l
l 3 - Release of 0.03 Ci of I-131 l
O 72 I --
charcoal filter is employed, and if so, the extent to which the filter has been preloaded with other organics.
Assuming the filter is unloaded, the efficiency s
of adsorbtion is approximately 99.9%.
In this case the release would be only 30 millicuries of radiciodine.
In the case of a fully loaded filter, the filter efficiency approaches zero, and thus the magnitude of the release approaches 30 curies.
In the case where no charcoal filter is used, the entire 30 curies will be released.
Release of a_ Radioactive Powder The third severe accident is the di finely-divided powder.
The example in this case is 30 curies of Cgersion of in the form of carbon powder.
If the material is spilled in an airtight glovebox, the spill is contained.
If the material is accidently dispersed in an operating fume hood, a sizeable fraction of it is carried into the exhaust stream.
If a HEPA filter is used, assuming an efficiency of greater than 99.9% for particles with the size distribution of the carbon powder, then less than 30 millicuries will escape into the atmosphere.
If no filter is used in the exhaust stream, then no barrier exists for the escape of the radionuclide carbon dust into the atmosphere, and, as a worst-case, 30 curies might be released.
It is quite likely, however, if the exhaust stream velocity is relatively low and if the ducting includes sharp bends, that a fraction of the carbon dust may settle and remain trapped in the duct work.
This trapping would be further aided by the reduction in air flow velocity caused by shutting down the exhaust system.
O 73
i i
ORGANIZATIONS / PERSONS CONTACTED Battelle Columbus Laboratories M.A.
Eischen R.G.
Evans W.J.
Madia R.A.
Mayer M.
Musick V.J.
Pasupathi R.E.
Snyder D.A.
Tolle H.L.
Toy G.E.
Kirsch D.G.
Freas Ohio Department of Agriculture Mr. Kirby, Environmental Science Division Ohio Department of Economic and Comunity Development Ms.
N.
Trobes, Office of Research Ohio Department of Natural Resources Mr. Wayne Channel, Division of Water Mr. Dennis Chase, Division of Wildlife Ohio Environmental Protection Agency O
74
3 Mr. Dave Chenault, Office of Planning Coordinator Mr. Rod Melhop, Chief of Surveillance Mr. Al Walters, Division of Air Ohio State University Division of Records U.S.
Army Corps of Engineers, Westerville, Ohio U.S.
Army Corps of Engineers, Huntington, West Virginia Mr.
Ira Belcher, Division of Flood Plain Management U.S.
National Weather Service, Port Columbus, Ohio Mr.
Lou Ramey, Chief U.S.
National Weather Service, Silver Spring, Maryland O
Mr. John Miller, Office of Hydrology l
l O
75 l
A REFERENCES U
Louis C.
Schreiner and John T.
Riedel, Hydrometeorological Branch, Office of Hydrology, National Weather Service, Probable Maximum Precipitation Estimates, United States East of the 105th Meridian,1978.
World Meteorological Organization, Manual of Estimation of Probable Maximum Precipitation, 1973.
Ohio Environmental Protection
- Agency, B_ig Darby intensive Survey 1979, unpublished draft.
Ohio Department of Economic and Community Planning, 1978 Ohio Population Estimates and Profit in Ohio, Economic Data Series, 1980.
U.S.
Department of Housing and Urban Development, Federal Insurance Administration, Flood Hazard Boundry Map, Panels 390773 004A and 390167 0004A, 1978.
U.S.
Department of Housing and Urban Development, Expansion of the Lake Darby Area Known as West Point, Draft Environmental Impact Slatement, HUD-R05-EIS-M7(5T~BW O
Onio Env4ronmentei erotect4on A encx, Weter cuei4ty Stenderds, Chenter 3745-1 of 9
the Administrative Code, 1978.
Ohio Department of Natural Resources, Endangered and_ Wild Animals in Ohio, Division of Wildlife Publication 316, 1979.
U.S.
Department of the Interior, Endangered and Threatened Wildlife and Plants, Federal Register 42:36419-36431, 1977.
Mid-Ohio Regional Planning Commission, Ohio Historical Society's Present Inventory of Historic Places, 1975.
The President's Council on Environmental Quality, Environmental Quality-1979, the tenth annual report, 1979.
Code of Federal Regulations, 40 CFR 1500-1508, 40 CFR 250.2-250.4, 40 CFR 123 and 125.
TERA Corporation, Draft Seismic Risk Analysis for Battelle Memor_ial_ Institute Nuclear Research FacTlity West Jefferson, Ohio, 1T78.
T.
Theodore Fujitu, Review of Severe Weather Meteorology at Battelle Memorial Institute Columbus, Ohio, 1977.
R.G.
Evans, Environmental Report for Calender Year 1977_ on Radiological _ and Nonradiological Parameters, BattelleEumbus Laboratories,1978.
76
,q R.G.
Evans and J.C.
Woodward, Environmental Report for Calender Year 1978 on-U Radiological and Nonradiological Parameters, Batte1 T Columbus Laboratories 1979.
R.G.
Evans and J.C.
Heinline, Environmental Report for Calender Year 1979 on Radiological and Nonradiological Parameters, Battelle Columbus Laboratories, 1980.
L.G.
Hulman, Assistance in Hydrologic Aspects - Analysis of Effects of Natural Phenomena on Existing 7Tutonium Fabrication Facilities ~ Batte1TE.
1978:
~
-~
~
Memorandum.
Ohio Environmental Protection Agency, Office of Air Pollution Control, Ohio Air Quality 1978, 1979.
O O
77
T p
Appendix A V
Environmental issues are classed as
- key, significant, and minor.
Key environmental issues are those which could stop the proposed action. Significant issues are those which will not stop the proposed action but require thorough investigation and possible plan / procedure modification in order to be obviated or mitigated to an acceptable impact level.
Minor issues are those which are very short-term and/or can be obviated or mitigated by use of standard engineering, construction and operating practices.
Those environmental components which will not be subject to any adverse impact are addressed below.
Justification for classification of the listed environmental components as "non-issues" is provided regarding each.
Archaeological. Historical and Cultural Resources The BMI has not and does not pre-antly impact any of the above resources.
The action proposed does not contain nrovisions for construction or areal expansion, therefore status quo will be maintained.
Land Features - Land Use There will be no impact on land features or use due to the absence of provision q
for any construction or areal expansion of the BMI f acilities.
v Natural Resources Natural resources will not be significantly affected due to the proposed license renewal. Subsequent operation will continue to tap one natural resource; water.
The small amounts of water usage by the Biosciences group at the King Avenue Facility would be a virtually undetectable fraction of the city water supply.
Water use at the West Jefferson Nuclear Sciences Facility annually averages 21.5 gallons per minute taken from an aquifer with a 450 gallon per minute yield capacity.
No adverse affects to the agt.ifer, penetrated by a number of industrial and municipal wells, have been ne'ed in the past and no adverse affects in the future are anticipated from continued use by the West Jefferson Facility.
Socioeconomics The proposed action, to relicense and continue operation of the Bioscience and Nuclear Sciences activities, would have no significant socioeconomic affects.
Continuance of operation will not involve change in employment levels, therefore, none of the existing socioeconomic components, e.g.,
public services, medical f acilities, schools, housing, utilities, transportation / traffic, and commercial services will be impacted either more or less than is currently the case.
i A-1
r; 3
1 Species and Ecosystems There is a wide variety of terrestrial, avian, and aquatic life in the Scioto River watershed.
Due to the urban character of the King Avenue Facility very little habitat is available for wildlife and, therefore, supports only limited numbers of small mamals, e.g., squirrels and those other rodents which tend to live in proximity to man and are classed as pests.
Avian life is somewhat more plentiful but still limited to such birds as pigeons, starlings, sparrows, swallows, wrens and a few others, none of which are considered endangered or threatened.
The proposed action will have no additional incremental effect on these species.
Wildlife habitat within a five mile radius of the West Jefferson Nuclear Sciences Facility is still rather sparce, as a result of farming practices, principally limited to fencerows, woodlots and the wooded area along the Big Darby and Little Darby Creeks. The Indiana bat is the only mamal occurring in the area which is listed as endangered or threatened.
It is listed on both the State and Federal lists as is the rarely seen American peregrine falcon.
The sharp-shinned hawk and the upland sandpiper which occur in the area are on the State list only.
Their survival is not impacted by actions at the BMI West Jefferson site.
Currently, Big Darby Creek has one of the most unique and diverse benthic and fish comunities in Ohio and is being considered by the Ohio Department of Natural Resources for possible. designation as a scenic river.
The stream is populated by a large number of fish, insect larvae and mollusks that are indicators of good water quality. Some of these organisms are larvae and nymphs of mayflies, damselflies, stoneflies, freshwater naiads, various darter and s
shiners, crappie, bass, and sunfish. There are seven species of fish which have been found in Big Darby Creek, downstream of the West Jefferson Site, that are officially declared endangered in Ohio.
These are the Northern brook lamprey, Scioto
- madtom, Eastern sand
- darter, river redhorse, slenderhead
- darter, Tippecanoe darter, and spotted darter.
The Scioto madtom, which is also on the Federal endangered species list, has its sole distribution in the Big Darby Creek.
In addition to the fish, there are four species of mollusk which have been found in Big Darby that are considered endangered in Ohio.
These are Simpsonatas (= Simpsoniconcha) ambigua, Quadrula cylindrica, Pleurobema clava, and Villose babalis.
Results of measurements
- taken over past years of operation indicate that radionuclide releases to the environment from BMI King Avenue and West Jefferson Facilities has been at levels which amount to an extremly small percentage of the Radiation Concentration Guide (RCG) values and/or far below background levels; nonradiological discharges have been within NPDES permit levels.
In light of these historical data, and the fact that no physical plant expansion is planned, it is not anticipated that continued operation of these f acilities under normal conditions would create any adverse effects to species and ecosystems.
- Environmental Reports for Calendar Years 1979, 1978 and 1977 on Radiological and Nonradiological Parameters, Battelle Columbus Laboratories.
O A-2
n Water Quality V
Big Darby Creek has good quality water as indicted by its aquatic inhabitants (Ref. Species and Ecosystems), the BMI annual environmental reports, and by the results of a study of the stream conducted by the Ohio Environmental Protection Agency during the sumer and fall of 1979.
The water samples taken during the study show the water quality indicators are equal to and/or better than state standards for all but three parameters.
The high iron content, i.e., greater than 1,000 micrograms per liter (mg/1), which appeared in samples from 19 of the 20 sampling sites along the course of the stream from river mile 79.2 to river 3.4 (north of the Darbyville gauging station) is unexplained. Likewise the high content of cadmium at three sampling sites (river miles 79.2, 54.0, and 3.4) and the high lead content at the same three sampling sites, plus the 66.1 river mile sampling site has not yet been accounted for.
The study and analysis are still in progress and the final report has not been published.
In order to determine the effects of past operation of the West Jefferson Nuclear Sciences Facility on Big Darby water quality, the data from two sampling sites has been reviewed.
The sites selected were; one north of the facility at river mile 41.8 (the facility is at river mile 40.46) and one downstream at river mile 36.4.
The data, presented in Table 4.1, show no significant contributions from the Nuclear Sciences Facility to the stream water quality. Small improvements in water quality downstream of the facility occurred in the cases of seven of the 18 quality parameters.
Seven other parameters showed no change.
The increase in B005 is insignificant in both amount and importance (importance due to the q
analysis protocol) and the iron content is in question along the entire reach of V
the stream.
The increase of total Kjeldahl Nitrogen (TKN) in the stream between the two sampling sites, while insignificant is indicative of the presence of sanitary treatment facilities along the five mile distance separating the sampling sites.
To the south of the Nuclear Sciences location there are three other known sanitary treatment facilities serving: the BMI Ecological Sciences complex, BMI Engineering complex, and the Lake Darby Estates.
It would be difficult, with the available data, to determine the percentage of the increase in TKN (organic nitrogen) that could be attributed to the Nuclear Sciences area.
In the future, that unknown percentage should be decreased or eliminated due to operation of an entirely new treatment facility at the Nuclear Sciences complex, commenced at the beginning of this year.
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Table A.1 r
I,,'l Results of Water Quality Samples Taken From V
Big Darby Creek Upstream and Downstream of the BCL West Jefferson Nuclear Sciences Facility River Mile River Mile River Mile 41.8 40.67(BCL) 36.4 parameter Unit 8.03 PH SU 8.05 9.7 D0 mg/l 9.55 4.1 B00 mg/l 2.8 5
Missing f
JSS mg/l 31.0 1.3 i
l TKN mg/l 0.85
<0.05 NH3-N mg/l
<0.05 3.9 NO3-N mg/l 4.05 q
L>
0.4 Total P mg/l 0.13 0.10 MBAS mg/l 0.19 8.4 000 mg/l 14.8 3.25 368 Hardness mg/l Total Cd mg/l
<5
<5
<30 Total Cr mg/l
<30
<30 Total Cu mg/l
<30 g
<30 Total Zn mg/l
<30
<100 Total Ni mg/l
<100 1770*
Total Fe mg/l 1195*
10.0 Total Pb mg/l 11.5
<0.5 Total Hg mg/l
<0.5
- Abnormal, unexplained high value; exceeds State water quality standards.
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