ML20100H060
| ML20100H060 | |
| Person / Time | |
|---|---|
| Site: | 07000398 |
| Issue date: | 03/31/1985 |
| From: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| References | |
| NUREG-1130, NUDOCS 8504080548 | |
| Download: ML20100H060 (45) | |
Text
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l Environmental Assessment for renewal and consolidation of Materials License Nos. SNM-362, SMB-405, 08-00566-05, 08-00566-10, and 08-00566-12 4
' Docket No.~ 70-398 U.S. Department of Commerce
- National Bureau of Standards i.
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U.S. Nuclear Regulatory i Commission I
Offico of Nuclear Material Safety and Safeguards i
March 1985 kB RfC g'
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l NOTICE '
Availability of Reference Materials Cited in NRC Publications Most documents cited in NRC publications will be available from one of the following sources:
1.1 The NRC Public Document Room,1717 H Street, N.W.
. Washington, DC 20666
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i 2. The NRC/GPO Sales Program, U.S. Nuclear Regulatory Commission,
. Washington, DC 20555
- 3. - The National Technical Information Service, Springfield, VA 22161 Although the listing that follows represents the majority of documents cited in NRC publications,
. it is not intended to be exhaustive.
Referenced documents'available for inspection and copying for a fee from the NRC Public Docu-
- ment Room include NRC correspondence and internal NRC memoranda; NRC Office of taspection and Enforcement bulletins, circulars, information notices, irispection and investigation notices; Licensee Eyant Reports; vendor reports and correspondence; Commission papers; and applicant and licensee documents and correspondence.
Tha following documents in the NUREG series are available for purchase from the NRC/GPO Sales Program: formal NRC staff and contractor reports, NRC-sponsored conference proceedings, and NRC booklets and brochures. Also available are Regulatory Guides, NRC regulations in the Code of Federal Regulations, and Nucteer Regulatory Commission issuances.
Documents available from the National Technical Information Service include NUREG series reports and technical reports prepared by other federal agencias and reports prepared by the Atomic-
- i Energy Commission, forerunner agency to the Nuclear Regulatory Commission.
Documents available from public and special technical libraries Include all open literature items,
.. such as books, joumal and periodical articles, and transactions. Federal Register notices, federal and state legislation, and congressional reports can usually be obtained from these libraries.
Documents such as t% eses, dissertations, foreign reports and translations, and non-NRC conference proceedings are available for purchase from the organization sponsoring the publication cited.
~
Single copies of NRC draft reports are available free, to the extent of supply, upon written request
- to the Division of Technical Information and Document Control, U.S. Nuclear Regulatory Com-mission, Washington, DC 20555.
Copies of industry codes and standards used in a substantive manner in the NRC regulatory process H
~
are maintained at the NRC Library, 7920 Norfolk Avenue, Bethesda, Maryland, and are available l there for reference use by the public. Codes and standards are usually copyrighted and may be purchased from the originating organization or, if they are American National Standards, from the American National Standards institute,1430 Broadway, New York, NY 10018.
i GPO Printed copy price: $3.75~
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NUREG-1130 Environmental Assessment for renewal and consolidation of Materials License Nos. SNM-362, SMB-405, 08-00566-05, 08-00566-10, and 08-00566-12 Docket No.70-398 U.S. Department of Commerce National Bureau of Standards U.S. Nuclear Regulatory Commission Office of Nuclear Material Safety and Safeguards I Aarch 1985
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CONTENTS Pag.e LIST OF FIGURES............................
vi LIST OF TABLES...........
vii ABBREVIATIONS AND ACRONYMS.......................
viii LIST OF FACTORS FOR CONVERSION OF ENGLISH TO INTERNATIONAL SYSTEM 0F UNITS...............................
ix 1.
PURPOSE AND NEED FOR ACTION 1-1 1.1 Introduction.........................
1-1 1.2 Summary of Proposed Action..................
1-1 1.3 Need for Action.......................
1-2 1.4 Scoping Process.......................
1-3 REFERENCES FOR SECTION 1......................
1-3 2.
ALTERNATIVES INCLUDING THE PROPOSED ACTION.............
2-1 2.1 Alternative of No License Consolidation and Renewal......
2-1 2.2 The Alternative of License Renewal..............
2-1 2.2.1 Description of the Current Operation..........
2-1 2.2.1.1 General Discussion of Site..........
2-1 2.2.1.2 Building 221, Physics Building........
2-1 2.2.1.3 Building 222, Chemistry Building.......
2-4 2.2.1.4 Building 235, Reactor Building........
2-5 2.2.1.5 Building 245, Radiation Physics........
2-5 2.2.1.6 General. Description of Operations.......
2-6 2.2.2 Waste Confinement and Effluent Controls........
2-7 2.2.2.1 Cadioactive Gaseous Emissions.........
2-7 2.2.2.2 Radioactive Particulate Emissions.......
2-7 2.2.2.3 Liquid Effluents...............
2-8 2.2.2.4 Solid Wastes.................
2-9 2.2.2.5 Direct Radiation...............
2-9 2.3 Pecommissioning........................
2-9 2.4 Safeguards..........................
2-10 2.5 Staff Evaluation of the Proposed Action and Alternatives...
2-11 l
REFERENCES FOR SECTION 2.~
2-11 l
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CONTENTS (Continued)
.Page 3.
-THE AFFECTED ENVIT.ONMENT.....................
3-1 3.1 Site Description.......................
3-1 3.2 Climatology and Meteorology.................
3-1 7
3.2.1' Climatology......................
3-1 3.2.2 Winds, Tornadoes, and Storms.............
3-3 3.2.3 Meteorology.......................
3-3 3.2.4 Air Quality......................
3-3 3.3 Demography and Socioeconomics................
3-3
- 3. 4 Land Use...........................
3-6 3.4.1 Site Land Use.....................
3-6 3.4.2 Adjacent Area..;...................
3-6 3.4.3 Historic Signii'icance.................
3-6 Floodplains and Wetlands...............
3-6 3.4.4 3.5 Geology and Seismicity....................
3-6 l
3.5.1 Geology........................
3-6 3.5.2 Seismicity......................
3-8 3.6 Hydrology..........................
3-8 3.6.1 Surface. Water.....................
3-8 3.6.2 Groundwater..,...................
3-8 3.7 Biota............................
3-11 3.7.1 Terrestrial......................
3-11 3.7.2 Aquatic........................
3-11 3.7.3 Endangered Species..................
3-11 3.8 Radiological Characteristics (Background)...........
3-11 REFERENCES FOR SECTION 3........................
3-11 a
4.
ENVIRONMENTAL CONSEQUENCES OF PROPOSED LICENSE RENEWAL......
4-3 4.1 Monitoring Programs'and Mitigatory Measures.........
4-1 4.1.1 Effluent Monitoring..................
4-1 4.1.2 _ Environmental Monitoring...............
4-1 4.1.3-External, Background Monitoring............
4-1 4
4.1.4 Monitoring Results..................
4-3 4
e iv i
CONTENTS (Continued)
.PaM 4-3 4.2 Direct Effects and Their Significance............
4-3 4.2.1-Air Quality......................
4-3 4.2.2 Land Use........................
4-3 4.2.3 Water Use.......................
4-4 4.2.4 Ecological.......................
4-4 4.2.5 Radiological Impacts.................
4-4 4.2.5.1 Direct Radiation................
4.2.5.2 Maximum Individual Doses from 4-4 Accidental Releases.............
4-6
'4.2.5.3 Population Doses from Accidental Releases..
4 4-6 4.3 Indirect Effects and Their Significance...........
3 4-6 4.3.1 Socioeconomic Effects.................
4-7 i
4.3.2 Potential Effects of Accidents..........
4.3.3 Possible Conflicts Between the Proposed Action and the Objectives of Federal, Regional, State, 4-7 and Local Plans and Policies.............
,l 4.3.4 Effects on Urban Quality,-Historical and 4-7 Cultural Resources, and Society...:.........
4-7 REFERENCES FOR SECTION 4.....................
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LIST OF FIGURES P_ age 2.1 Map of the National Bureau of Standards site and surrounding area, showing the principal roadways leading to the site and surface drainage streams.....................
2-2 2.2 ; Location of buildings on the Nationa'l Bureau of Standards site in which radiological materials are stored or used........
2-3 4-3.1 Regional site map.........................
3-2 1
- 3.,2 Annual wind rose showing wind direction frequency (%) for 16 radial directions.......................
3-4 i
3.3 Location of the National Bureau of Standards site in relation to adjacent urban areas.......................
3-7 3.4 Seismic risk map of the United States...............
3-9 3.5 Preliminary map of horizontal acceleration (expressed as percent of gravity) in rock with 90% probability of not being exceeded in 50 years............................
3-10 4.1 Location of radiological monitoring site and the principal buildings ~in which radioactive materials are stored or used....
4-2 1
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l LIST OF-TABLES P_ajte 1.1' Current radioactive materials licenses for National Bureau of Standards...........................
1-2 2.1 Facilities for nuclear materials at the National Bureau of Standards, Gaithersburg, Maryland.................
2-4
- 2. 2 Potential release point characteristics..............
2-7 2.3 Limits and rules for radiological materials at the NBS Alpha Chemi s try Labo rato ry.......................
2-8 2.4 Discharges of liquids from holdup tanks to the municipal sanitary sewer system.......................
2-9 3.1 Incremental 1980 population data for 8-km (5-mile) radial segments and for the total 80-km (50-mile) radius in each of 16 directions from the National Bureau of Standards site............
3-5 4.1 Maximum individual doses from an accidental release of 100 mci o f a s Kr..............................
4-5 4
4.2 Maximum individual doses from an accidental release of 1 pCi of 2ssPu...................... :
4-5 4.3 Population doses from accidents involving asKr and 239Pu.....
4-6 t
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ABBREVIATIONS AND ACRONYMS ALARA As Low As Reasonably Achievable
-AQCR Air Quality Control Region CEQ Council on Environmental Quality CFR Code of Federal Regulations EA Environmental Assessment EIA Environmental Impact Assessment EIS Environmental Impact Statement i
EPA U.S. Environmental Protection Agency FR Federal Pegister HEPA High Efficiency Pa'rticulate Absolute MPC Maximum Permissible Concentration MSL Mean Sea Level N8S National Bureau of Standards NEPA National Environmental Policy Act NRC U.S. Nuclear Regulatory Commission ORNL Oak Ridge National Laboratory SNM Special Nuclear Materials TLD Thermoluminescent Dosimeter viii 4
n
LIST OF FACTORS FOR CONVERSION OF ENGLISH TO l'
INTERNATIONAL SYSTEM OF UNITS (SI)
The following table gives the factors used im this document for the conversion of conventional English units to the equivalent International System of Units (SI) now being adopted worldwide or conventional metric units.
TheconversionfactgrshavebeenobtainedfromtheASTMpublicationStandard' for Metric Practice and are used to four-digit accuracy, since most of the values in this document are not known to any more exactness.
After conversion, j
the SI values have been rounded to reflect an accuracy sufficient for the requirements of this document. Most of the values will be presented in SI units with the equivalent English unit following within parentheses.
Conversion of English to SI Units To Convert From To Multiply By acre
. hectare (ha) 0.4047 feet (ft) meters (m) 0.3048 l
cubic feet (ft )
cubic meters (m )
0.02832 8
8 8
gallon (gal) cubic meters (m )
0.003785 gallon (gal) liters (L) 3.79 gal / min-liters /s (L/s) 0.06309 inch (in.)
centimeters (cm) 2.54 '
inch (in.)
meter (m) 0.0254 mile (statute) kilometer (km) 2 1.609 2
1 square mile (mile )
square kilometer (km ) 2.590 pound (1b) kilograms (kg)-
0.4536 4
a l
American Society for Testing and Materials, Standard E-380, Standard for i
Metric Practice, February 1980.
l ix
t 1.
PURPOSE AND NEED FOR ACTION 1.1 Introduction.
By letter dated November 15, 1983,1 the National Bureau of Standards (NBS) of
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the U.S. Department of Commerce submitted an' application for renewal and consolidation.of five nuclear materials licenses covering operations at the
-NBS site at Gaithersburg, Maryland (Sect. 1.2).
The applicant submitted supporting environmental-information on February 29,_1984.2 The staff of the U.S. Nuclear Regulatory Commission (NRC) and its contractor, Oak Ridge National i
Laboratory (ORNL), visited the site for observations and discussions with the applicant on April 26, 81984, and a response to the staff's questions was submitted in June 1984.
i.
To evaluate the licensee's proposed action, NRC,'with the technical assistance of ORNL, prepared this environmental asse'ssment (EA) pursuant to Council of Environmental Quality (CEQ) regulations (40 CFR Parts 1500-1508) and NRC regula-tions.(10 CFR Part 51), which require an environmental assessment,(EA) imple-menting requirements of the National Environmental Policy Act (NEPA) of 1969 i
(PL 91-190).
Paragraph 1508.9 of the CEQ regulations defines " environmental assessment" as follows:
1-1.
An environmental. assessment is a concise public document, for which a federal agency is responsible,-that serves to briefly provide sufficient evidence and analysis for determining 4
i whether to prepare an environmental impact statement (EIS) or'a finding of no significant impact,
)
aid an agency's compliance with the act when no EIS is necessary, and facilitate preparation of an EIS when one is necessary.
2.
An environmental assessment shall include brief discussions of the need for the proposal, of alternatives as required by Sect. 102(2)(E) of NEPA, of the environmental impacts of the proposed action and alternatives, and a listing of agencies and persons consulted.
1.2 -Summary of Proposed Action l
- The proposed action for which this EA-is prepared is the renewal and consolida-tion of five nuclear materials licenses-(Table 1.1) for radiological activities at the N8S site. These licenses cover most uses of radioactive material at i
NBS except that controlled by the license for operation of the NBS reactor.'
The reactor license is not associated with and will not be 'affected by the currently proposed licensing action.
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L Table 1.1 Current radioactive materials licenses L
for National Bureau of Standards j
l Previous License number renewal date Expiration date
-07/12/79 07/31/84 SM-405 09/29/78 09/30/83 08-00566-05' 12/20/77 12/31/82 08-00566-10:
06/22/81 05/31/86 08-00566-12; 08/28/78 08/31/83 Radiological activities are conducted principally in 4 of the 29 buildings at the 233-ha (576-acre) NBS site, and include the following:
1.
irradiation of materials and. equipment; 2.
'research on the chemistry of radioactive materials; 3.
calibration of instruments for. measurement of radioactivity; 4.
preparation of calibrated, contained (sealed) sources of low-level radio-activity, and the distribution of these sources to licensed customers; j
i 5.
determination of emission rates and dose rates from sealed sources; 6.
determination of the responses of radioactivity monitors to radiaticn beams; and 7.
miscellaneous research and development projects (e'.g., conducting assays and preparing radioactive samples during participation in various environ-mental and medical test programs).
Radioactive materials or. sources are (1) maintained long term, (2) distributed to outside customers, and (3) received for. characterization or use prior to l
reshipment or redistribution. Maintained sources are usually kept in sealed containers and range from the very small activities of most sources to several tens of kilocuries of irradiator units.
Some unsealed materials are maintained for historical purposes or for feedstock for sample preparation. Materials that are distributed include radioactive counting samples, standard reference materials of well-characterized elemental and isotopic content, and samples for medical testing.
Materials-received by NBS are usually from customers who:
want the emissions and dose rates.of the materials characterized against-standard reference sources.
1.3 Need for Action Activities under the nuclear materials licenses at NBS serve a wide variety of federal, state, commercial, and research needs, both nationwide and inter-l national..For example, nuclear power plants use sources and instrument:;
1-2 i
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j calibrated at NBS.. Industrial users of radioactive materials depend on certi-fications by the NBS, and the establishment of international standards involves interaction with the N8S.
The licensing action addressed in this document is the consolidation and renewal of five nuclear materials licenses.
Consolidation of the licenses is needed to increase the efficiency of the applicant's preparation of license applications and the NRC staff's reviews of these applications.
The current system,.with staggered expiration dates of licenses, requires that license reviews occur at several different times. This results-in unnecessary duplica-tion of effort over the complete cycle of renewals for all licenses.
Consoli-dation can eliminate this redundancy in the licensing procedures for NBS.
- 1. 4 Scopin'a Process
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The NBS facilities at the Gaithersburg site have been in operation since the 1960s. Documentation of. the lack of impacts of N85 operations has been obtained from the applicant and is based on material control and accountability and on monitoring required by various state and federal permitting agencies.
The principal possible impacts of operation are associated with routine and acci-dental releases.of radioactive gases and particulates to the atmosphere.
Waste liquids are stored temporarily and sampled before release to sanitary 1
l sewers leading to local sewage treatment facilities.
Solid wastes are deposited at approved commercial landfill sites.
Because'of the controls applied to routine releases, the low level of radioactivity of most materials used, and i
tile small amounts of radioactive materials handled, potential impacts of l
routine operation and accidents are insignificant.
The proposed consolidation of licenses does not involve an increased level of operations with radioactive materials, and no increase in environmental impacts is expected.
Because of the lack of potential impacts of the current operations (Sect. 4), the staff I
did not find it necessary to provide a formal public. scoping process to adequately determine the scope of impacts of the proposed ' action.
I REFERENCES FOR SECTION 1 L
1 National Bureau of Standards, Materials License Document (Application'for Renewal and Consolidation of License. Numbers 08-00566-05, 08-00566-10, 08-00566-11G, 08-00566-012, 08-0566-13E, SMB-405, and SNM-362; Docket.
i
- Nos. 30-3918, 30-6894, 30-3919, 30-97%, 30-1167, 40-4348, and 70-398),
i Ncvember 1983.
2.
National Bureau of Standards, Environmental Information in Support of the Application for U.S. NRC Msterials License Consolidation, Docket No.
i L70-398, Feb. 29, 1984.
3.
National Bureau of Stanlards, " Response to NRC Site Visit Questions,"
l
' Docket No. 70.398, June 30,.1984.
l
- 4. -
U.S. Nuclear Regulatory Commission, Final Environmental Statement Related J.
- to License Renewal and Power Increase for the National Bureau of Standards Reactor, Docket No. 50-184, August 1982.
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t 2.
ALTERNATIVES INCLUDING THE PROPOSED ACTION 2.1 Alternative of No License Consolidation and Renewal This alternative includes two options:
(1) nonrenewal, and (2) renewal without consolidation.
The option of nonrenewal precludes the continuation of the respective licensed operations by the NBS.
A denial of the license renewals would occur only if issues of adverse public health and safety impacts could 4
not be resoJved or mitigated.
However, as discussed in Sects. 2 and 4, the environmental impacts associated with the current license renewal action are small and acceptable, and denial of license renewal would result in little benefit to the environment.
Renewal of the licenses without consolidation would maintain the status quo.
i Nonconsolidation would result in the need for more frequent NRC reviews of NBS operations than if licenses were consolidated.
Because of the lack of potential impacts of the NBS radiological operations, frequent NRC reviews will not 4
provide significantly greater benefits in the form of higher standards of 1
j control of materials and associated operations.
- 2. 2 The Alternative of License Renewal j
2.2.1 Description of the Current Operation I
2.2.1.1 General Discussion of Site The National Bureau of Standards (NBS) site is a 233-ha (576-acre) tract of land in upper Montgomery County, Maryland, about 1.6 km (1 mile) southwest of Gaithersburg. The site is bounded on the east by Interstate 270 and Muddy 4
Branch Road and on the north and west by Maryland Route 124 (Fig. 2.1).
Principal operations covered by the nuclear materials licenses are summarized
.in Sect. 1.2 and are conducted in 4 of the 29 buildings on the site (Fig. 2.2) as described in Table 2.1.
The 29 buildings include an 11-story administration i
building, 7 general purpose laboratories with similar floor plans,-11 buildings designed for specific purposes,~and several buildings providing support services i
for NBS operations.1 A nuclear research reactor is also loc &ted on the site, and its operation and environmental impact is addressed by NRC under a separate j
license action.2 Although the operation of the research reactor is not discus-sed in this document, the impact of its operation is included in the effluent and environmental effects monitoring (Sect. 4.1) at the site.
2.2.1.2 Building 221, Physics Building The' portion of this building involved with radioactive material consists of a laboratory complex housing six mass spectrometers with two hoods, and has services including gas, air, vacuum, and electricity.
The complex is the size of seven individual laboratory modules (one module is about 7.3 m long, 3 m wide, and 3.4 m high). Two of the spectrometers are usually reserved for radiological work using filaments with a maximum deposition of one microgram 2-1
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RADIATION
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PHYSICS CHEMISTRY
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O 500 1000 1500 FEET 150 300 450 METERS Og Fig. 2.2 Location of buildings on the National Bureau of Standards site in which radiological materials are stored or used 2-3
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Table 2.1.
Facilities for nuclear materials at the National Bureau of' Standards, Gaithersburg, Maryland Building number and name 221 222 Physics building.
Chemistry building 235 245 Reactor building Radiation physics building One~ mass spectrometry -Vault-type storage Radiochemistry.
Source receiving and
_ laboratory complex-room-(room B118) rooms (36 rooms,-
storage (3 rooms, (rooms A30,-B25, B119 through B131-8133) and B33)
B154)
Alpha chemistry.
i laboratory (room Waste handling Sealed source calibra-A344)
_ facility tion (5 rooms, B141-J B145) j Several general Sealed source opera-i purpose tions (52 rooms, B05-laboratories d-25,B013-B043)
Radiochemistry rooms (28 rooms, B44-B53, i
B146-8157, Cll, C13, c15,E103,E105,E106)
Water-well irradiator
-(room F101)-
Dry irradiators (several specially designed or approved rooms)
I of activity, e.g., about 30'nCi of Pu-239.
Hoods associated with all licensed f
activities-in all buildings have both roughing and high efficiency _ particulate i
absolute (HEPA). filters, and a ventilation rate of 30 lin m/ min.
f 2.2.1.3 Building 222 Chemistry Building:
4 Room B118 in this building is used for the storage of contained radioactivt.-
materials. The room is smaller than individual module size and has a single entrance with a' double-hung vault-type door._ Services include electricity, l
fire and intrusion sensors, and air exchange ducts.
Room A344 isLan alpha chemistry laboratory containing one vertical-door hood, two horizontal-door hoods, and four glove boxes.
The room is used for normal i
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j 2-4
i 4
4 chemistry operations with high-toxicity alpha-active radionuclides in quan-tities-no more'than 1 mci or.0.01 g, whichever is less. eThe glove boxes
. exhaust through^ absolute' filters into the hood duct. -The room is the size of one module.'- Services include water, electricity, air, gas, and vacuuni.
l
. Tracer and'1abeling operations and other processes using similar very small quantities of activities and nuclides are conducted in other laboratories in this building.
2.2.1.4 Building 235, Reactor Building 1
Building 235 contains about 36 rooms of various-sizes used for radiochemistry
-activities'.
Each laboratory has standard laboratory services and at least one hood.. The hoods vent into the-exhaust stack of the reactor, which-is also
~
located in this building but not covered by this proposed licensing action.
i 2.'2.1.5 ~ Building 245,. Radiation Physics Various rooms and laboratory complexes serve a variety of purpoises iri this building.
Receiving, storage,- and calibration Nuclear-source materials are recIived, stored, and calibrated in one complex of adjacent rooms and laboratories (B131-B133, B141-8145).
Room B133 is the radioisotope receiving laboratory and-is a special purpose radiochemistry facility.' Room B141 has a manganese sulfate bath facility used for neutron source calibration.. Transfers of sources are accomplished-with remote handling tools, nominally about 1 to 4 m long, to minimize exposure of personnel to radioactivity.
Sealed-source operations i-Sealed-source operations are performed in two complexes of rooms and labora-tories, one (805-B25) in the basement. level of.the building and.the other
(
(8013-8043) in the subbasement level. A water-well irradiator in room F101, an extension of.the first floor level, is also used.
Sealed-source operations primarily involve. sample irradiation using either gamma or neutron sources.
~
Gamma irradiation is performed with the one water-well irradiator:and with several dry-irradiators.
The water-well. irradiator consists Jof a nominal 11 kCi of cobalt-60:in a sunken water' pool about~2.8 m in diameter and 3.4 m deep.
The irradiator is. maintained in a fixed location and provides-for wet, self-contained storage and irradiation conditions.
Each dry irradiator consists of sealed sources totaling 250 Ci or more and is maintained in a.
- fixed location in a: dry container constructed.of solid materials.
These dry sources are shielded at all: times when not in use.
Human access tc these sources is effectively eliminated by the design of the storage facility and the interlocks with'.the operation control system.
Walls.of: concrete at least'
~ O.6 m (2 ft) thick separate the irradiator rooms-from the control room and-
. other occupied areas.
Both wet and dry irradiators and their facilities are provided with appropriate monitors,Lautomatic interlocks on the irradiation room access. doors,.and postings and warnings according to potential radiation-
-level intensity categories ~as.specified in 10 CFR-Pt. 20.-
Neutron operations 2-5
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include calibration of neutron sources and production of neutrons by particle E
accelerators.
Various isotopic neutron sources, including Pu-Be, Am-Be, Ra-Be, E
and Cf-252, are located at NBS.
Some belong to NBS whereas others are received from customers for calibration in the manganese sulfate bath facility. Neutron sources are stored in concrete wells or water tanks in several areas and can i
be temporarily stored in the calibration bath.
Several accelerators located in Building 245 are occasionally operated with targets of both stable and radioactive nuclides to study the properties of the particular nuclide in use or to produce radionuclides.
Tritium in up to curie activities is used for neu_ tron production by the accelerators.
2 Radiochemistry W
Radiochemistry is conducted primarily in two complexes, one (rooms B146-B157) on the first floor and the other (rooms B44-B50) in the basement level.
Rooms y
E105 and E106 are also devoted to radiochemistry.
The laboratories have the customary facilities and are also equipped with hoods or glove boxes.
=
2.2.1.6 General Description of Operations r
Although a wide variety of miscellaneous research and development projects are conducted with nuclear materials at NBS, radiochemistry and source calibration are the principal activities.
All operations conducted at NBS are batch type with finite end points or goals to be achieved.
Although some of these opera-tions are repeated at regular intervals, none involve continuous, ongoing activities.
NBS maintains radioactive sources on the site, prepares sources for distribution to customers, and receives from customers sources to be characterized (calibrated) and returned.
i Radiochemistry a
Chemistry operations include preparation of unsealed samples of radioactive materials for distribution to customers, preparation of samples for assay c
F purposes, and many different types of research and development projects con-ducted in cooperation with private and government institutions.
Preparation of I
samples is typically accomplished by depositing known activities on a substrate y
and then using a fixing technique such as heat treatment or electrolysis.
1 Most projects involve materials of low-level radioactivity.
The unsealed feedstock of the radioactive material kept in the process laboratory may have E
ten times the radioactivity of the samples actually prepared.
Source and instrument calibrations NBS receives from customers low-level radioactive sources for characterization.
E These sources are assayed and calibrated using measurement techniques based on standard sources maintained by NBS.
Similarly, inaccurate or noncalibrated instruments for measuring radioactivity are calibrated by exposing them to radiation fields of known strength and are then returned to the custoner.
An example of these activities is the research and development of particle and photon dosimetry, including the interlaboratory testing and calibration of neutron personnel dosimeters.
2-6
2.2.2 Waste Confinement and Effluent Controls This section considers the controls employed at NBS to limit the releases of hazardous and radioactive materials to the ambient environment external to the facilities.
Releases of radioactive materials may occur during three types of activities:
(1) the use of noble gases for production of standard samples, (2) operations involving high-toxicity, alpha-emitting nuclides, and (3) the discharge of low L
activity liquids from waste retention tanks.
Releases of nonradioactive gases and particulates at NBS are so small that they are of no environmental concern.
Concentrations of organics, hydrocarbons, and heavy metals in the releases are very low and cannot be measured.3 The release points for any gaseous releases 4
j are indicated in Table 2.2.
Potential release point characteristics Table 2.2 Distance (m) to nearest Release point Height above ground Boundary Resident 4
Building 221 Four stories (20 m) 600 760
?
Building 222 Four stories (20 m) 600 1000 9
Building 235 30-meter stack 400 670 i
Building 245 Two stories (10 m) 560 670 4j t
i"-
2.2.2.1 Radioactive Gaseous Emissions i
d No radioactive gases are routinely released, although small releases may occur i
during the batch-type operations characteristic of NBS activities.
These 7
gases are noble gases infrequently used in Building 245 for standard sample
-Q production. Quality control procedures are followed to minimize releases of these gases.
The quantity of noble gas produced during any batch-type activicy is so small that, even if the entire amount were released to the atmosphere, Q
the potential impacts would be inconsequential (Sect. 4.2.5).
h 2.2.2.2 Radioactive Particulate Emissions Particulate emissions to the atmosphere are controlled by the use of hoods N
with roughing and HEPA filters.4 All chemical operations requiring special precautions are conducted in hoods, or in glove boxes that vent into.the E
hoods. During operation, the hoods maintain a ventilation velocity at the hood I
opening of 30 m/ min. Alpha chemistry activities, which may result in the
?
release of radioactive particulates, are controlled as'shown in Table 2.3.
The E
HEPA filters are tested upon installation and annually thereafter for air fi leaks that would allow excessive particulates to be' emitted.
Other tests of F
hoods and glove boxes are conducted to ensure occLpational health and safety.
.[
Work requiring HEPA filters is not permitted if air leakage through the filter is demonstrated or if filter loading is four times the loading of freshly ci installed filters.1 e-N 2-7
+$a_
Table 2.3 Limits and rules for radiological materials at the NBS Alpha Chemistry Laboratory Type of operation Limit, lesser of Conditions s&
Simple storage 100 mci or 10 g In closed containers y[F Simple wet chemistry 10 mci or 1 g Within hoods (e.g., aliquot preparation) i[
Normal chemistry 1 mci or 0.1 g In HEPA-filtered hoods t
(e.g., analysis)
[
Complex wet chemistry 0.1 mci or 0.01 g in HEPA-filtered hoods F
(e.g., complex apparatus)
=
Simple dry operations 0.1 mci or 0.01 g In HEPA-filtered hoods
[
Dry and dusty 0.01 mci or 0.001 g In glove boxes 5
operations (e.g.,
grinding) i J
2.2.2.3 Liquid Effluents 1
?
All radiological liquid wastes at NBS are assayed for radioactivity and then either released to the sanitary sewer for treatment at the public sewage plant or are collected'for special handling.
No liquid wastes are released to surface waters or groundwaters.4 All radiochemistry laboratories in Building 235 and most of them in Building 245 drain directly to holding tanks.
Building 235 has one 19,000-L tank and Building 245 has two such tanks. When full or near full, the contents of these tanks are assayed and, if the activity concentration is low enough, the contents are dumped into the sanitary sewer.
To date, all tank contents have been of such low activity that small fractions of maximum permissible levels have been achieved.
In Building 235 almost all liquids, including air condi-tioning condensate, drain to the tank, and dumps of the tank are necessary about twice each month 3 (Table 2.4).
Usually only one dump in several years is necessary for the tanks in Building 245.
In other laboratories in Building 245 and in Buildings 221 and 222, liquid wastes expected to have significant concentrations of radioactivity are collec-ted in polyethylene bottles or equivalent containers.
These bottles, with appropriate information regarding their contents, are transferred to the radioactive waste handling facility in Building 235.
The liquids are either solidified for disposal as solid radioactive waste or are routed to the 19,000-L liquid waste tank.2 2-8
2
=T-7
-?
E
?
Table 2.4 Discharges of liquids from holdup tanks
=
to the municipal sanitary sewer system h
+
Radioactivity Source Volume Year (building)
(L)
(Ci of tritium)
(Ci, beta gamma)
-s 1981 234 362,000 0.735 0.00039 O
245 8,500
(<10 5)
(<0.5 Bq) f 1982 235 397,000 0.849 0.06
-i
^
245 0
0 0
1983 235 447,000 3.349 0.14 245 0
0 0
w 5
c 2.2.2.4 Solid Wastes
[
z Solid wat,i.es produced in association with radiological operations at NBS i
include paper, glassware, process residues spent particulate filters, radio-active sealed sources, and other solids.1,5 All solid wastes are collected n
I; by NBS for offsite disposal.
I Nonradioactive wastes collected during radiological operations are combined 2
with other nonradioactive, nonhazardous trash from other NBS operations and i
are deposited at a local municipal waste disposal facility.
q i
Radioactive wastes are collected in polyethylene bags or equivalent containers at the workplace and transported to the radioactive waste facility in Building 235, which is equipped with a compactor.
Radioactive sealed sources and other 4
high-activity materials are treated separately from low-level wastes.
Radio-
)
active wastes are usually compacted and packaged in 208 m3 (55 gal) metal i
a drums for offsite burial at a licensed disposal facility. The compactor
/
facility includes a filtered ventilation system to minimize releases of radio-J active particulates to the atirosphere.
Exhaust air from the compactor is a
sampled regularly to detect releases.
The annual volume of solid waste, 5
including both compacted wastes and wastes that could not be' compacted, has ji (283 fts), and has had an activity of less than 1 Ci.8 E
been less than 8 m3 a
2.2.2.5 Direct Radiation r
'r k
Direct radiation from Buildings 221, 222, and 235 is of no potential signifi-the californium-252 facility.I produces more radiation, which emanates from cance.
Building 245, however The possible effects of this radiation are s
j discussed in Sect. 4.2.5.1.
g
)
2.3 Decommissioning
[
y Whenever activities related to nuclear materials licenses at the NBS site c
f cease, the affected buildings and facilities will be decontaminated and h,
o I
2-9 i
I i
- 1 3
p
?
f released to unrestricted use.
A significant level of work activity at this site is not under auspices of NRC licenses.
This site would continue to be used by the applicant, and the decontaminated areas of the affeqted buildings
[
would be used for activities not requiring an NRC license.
5 i
Decontamination of the affected areas for continued use without radioactive material should be accomplished using the following major guidelines:
i 1.
All areas are to be cleaned to levels established for unrestricted use.
2.
Current radiological limits and decontamination technology are to be used.
3.
All process and ancillary equipment in controlled areas is to be cleaned 8-to the extent practicable, packaged, and transported to a licensed disposal 5
facility for burial.
4.
Any contaminated underground piping is to be removed, cleaned to the extent practicable, packaged, and transported to a licensed disposal facility for burial.
The ground surrounding such piping is also to be surveyed and removed for disposal if contaminated beyond established limits.
o k
If NBS ever decides to terminate all activities at the site, a decommissioning plan for future action or final decommissioning report of past action will be submitted to allow NRC to determine the effectiveness of the decommissioning g%.f m
activities.
gd
=
2.4 Safeguards
[
r Current safeguards are set forth in 10 CFR Parts 70 and 73.
The regulations in UE E
Part 70 provide for material accounting and control (MC&A) requirements for
[
special nuclear material (SNM) with respect to facility organization, material control arrangements, accountability measurements, statistical controls, y
inventory methods, shipping and receiving procedures, material storage practices, E
records and reports, and management control.
For licensees authorized to l
possess and use a maximum of one effective kilogram of SNM, the basic MC&A requirements include specific records and reports, and an annual physical F
I inventory of the SNM.
A detailed MC&A plan is not required when possession and
[
use is limited to one effective kilogram.
NRC's current regulations in 10 CFR Part 73 provide requirements for the physical security and protection of fixed sites and for nuclear material in transit.
Physical protection requirements for SNM of low strategic significance (including low-enriched uranium) include provisions for establishing controlled access areas, monitoring these areas to detect unauthorized penetration, providing a response capability for unauthorized penetrations and activities, and establishing procedures for response to theft and threats of theft.
NRC's regulations in 10 CFR Parts 70 and 73, described briefly above, are applied in the reviews of individual license applications.
Appropriate license condi-tions are then developed and imposed which (1) require the licensee to follow the NRC approved safeguards plans, (2) may allow for site-specific alternatives to safeguards requirements, and (3) may augment the approved plan to assure the licensee's capability to meet the intent of the regulations.
2-10
The licensee has an approved physical security plan which meets the current requirements for any SNM possessed at the site.
It is concluded, therefore, that the safeguards-related environmental impact of the proposed action is insignificant.
2.5 Staff Evaluation of the Proposed Action and Alternatives The staff has concluded that denial of license renewal would provide very little in the way of environmental benefits.
The staff believes that the NBS operations, methods of waste confinement, and effluent controls meet all applicable state and federal standards, and that the monitoring program for waste releases and environmental impacts is adequate to detect adverse effects of plant operation.
The staff recommends that the licenses be renewed.
REFERENCES FOR SECTION 2 1.
National Bureau of Standards, Materials License Document (Application for Renewal and Consolidation of License Numbers 08-00566-05, 08-00566-10, 08-00566-11G, 08-00566-012, 08-0566-13E, SMB-405, and SNM-362; Docket Nos.
30-3918, 30-6894, 30-3919, 30-9796, 30-1167, 40-4348, and 70-398), November 1983.
2.
National Bureau of Standards, Environmental Information in Support of the Application for U.S. NRC Materials License Consolidation, Docket No.70-398, Feb. 29, 1984.
3.
National Bureau of Standards, " Response to NRC Site Visit Questions,"
Docket No.70-398, June 30, 1984.
2-11
i p
=
I Mi
[
A i
h f
3.
THE AFFECTED ENVIRONMENT
[
3.1 Site Description
?
The NBS facilities are located on a 233-ha (576-acre) tract of upland Maryland Piedmont (Fig. 3.1) in upper Montgomery County, Maryland, approximately 1.6 km i
4 (1 mile) southwest of Gaithersburg. The site is bounded by Clopper Road to k
the north, Muddy Branch Road and Washington National Pike (I-270) to the east, R
Maryland Route 124 to the west, and private lands in the watershed of Muddy a
Branch to the south and southwest (Fig. 2.1).
Major radiological activities 5
subject to NRC licenses occur in only 4 of the 29 buildings on the site. The
?
site lies on level to gently sloping uplands separating the watersheds of
?
Muddy Branch to the south and Long Draught Branch of Seneca Creek to the
(
I north.
Both streams flow west to the Potomac River.
The site vicinity has
/
a combination of residential, commercial, and rural land uses.
The nearest population centers are Rockville, 8 km (5 miles) southeast of the site, and
=
Gaithersburg. The site is approximately 32 km (20 miles) northwest of the i
center of the District of Columbia.
Elevations on the site rance from 111 to f
142 m (365 to 465 ft) above mean sea level (MSL).
3.2 Climatology and Meteorology
(
3.2.1 Climatology a
s 1
The climate of the region in which NBS is located is continental, modified y
somewhat by the Appalachian Mountains to the west and the Atlantic Ocean to a
T the east.
Spring and fall weather changes rapidly because of a rapid succes-sion of warm and cold fronts that generally move from west to east.
Prevailing a
winds are from the northwest quadrant from October through June and from the e
southwest quadrant from July through September. Mean wind speeds at the
?
surface range from 14 to 16 km/h (9 to 10 mph) in summer and increase to 16 to
@y 19 km/h (10 to 12 mph) in winter and early spring.
Winds from the east gener-i 4
ally bring rain, while tho:e from the west are usually associated with dry, fair weather.1 The r.ean annual temperature in the area is about 13 C, ranging
,2 from about 0 C in January to about 25 C in July.
Extreme temperatures of 1
-26 C and 41 C have been reported in the area.
Annual precipitation is about 3
F 102 cm (40 in.) and is well distributed throughout the year. The lowest monthly precipitation usually occurs in February and October [about 6.3 cm (2.5 in.)];
w)
July and August are usually the wettest months [between 10.2 and 11.4 cm (4.0 L=
and 4.5 in.) of precipitation]. A maximum monthly precipitation of 46 cm (18 in.) was reported at Dulles International Airport in June 1972.
The maximum
=
4 24-h rainfall of 30 cm (12 in.) was also reported at Dulles in June 1972 during the passage of Hurricane Agnes.
Annual snowfall at the NBS site is about 51 cm (20 in.), with the maximum monthly snowfall [13 to 18 cm (5 to 7 in.)] expected in February. The maximum ona-month snowfall in the area was p!E reported to be 90 cm (35 in.) in February 1899; the maximum 24-h snowfall was reported to be 63 cm (25 in.) in January 1922.
>cj N
3-1
ES4101 G "' ' "
cb N
canuxNTOwN cAiTuenseuno e
."^11"n !! ^" *
'/
nocxvtLLE k
,v AR LINGTON -
e 6
ALEXANDalA m es Fig. 3.1 Regional site map l
3-2
3.'2. 2 Winds, Tornadoes, and Storms Storms originating to the south and moving into Maryland often bring strong easterly to northeasterly winds, thunderstorms, and heavy rains.
About 40 thunderstorms can be expected at the NBS site each year, most frequently from May through August. Hail sometimes accompanies severe thunderstorms, with July being the month of peak activity.
Hail with diameter 1.9 cm (0.75 in.)
or larger occurs about once each year.
During the period 1955-1967, 28 tornadoes were reported in a 2 latitude-longitude square containing the site. The computed recurrence interval for a tornado at the NBS site is about 2000 years, which is comparable to that calculated using reports of tornadoes for the period 1950-1976.
July is the month with the highest frequency of tornadoes.
In the period 1871-1978, about 20 tropical cyclones, storms, and hurricanes passed within 160 km (100 miles) of the NBS site.
The " fastest mile" wind speed reported at Washington National Airport was 122 km/h (76 mph) and was associated with the passage of Hurricane Hazel in October 1954.
3.2.3 Meteorology The average wind speed in the area is about 13 km/h (8 mph).
Figure 3.2 gives representative wind rose data for the NBS site.
Winds from the northwest quadrant (west-northwest, northwest, and north northwest) occur about 30% of the time, and winds from the south and south-southwest occur about 20% of the time.
Some meteorological measurements have beun made at the NBS site. Wind speed and direction are currently measured at the top of a small tower located on the southwest corner of the roof of Building 235, about 4.6 m (15 ft) above the top of the building.
Comparison of wind data at the NBS site with data collected at Washington National Airport shows reasonable agreement.
There appear to be no unusual atmospheric dispersion characteristics at the NBS site.
3.2.4 Air Quality The NBS site is located in the National Capitol Interstate Air Quality Control
>egion (AQCR).
In this region, concentrations of particulates and 502 are better than national primary standards.
3.3 Demography and Socioeconomics The 1980 population for the surrounding area [80 km (50 miles)] is shown in Table 3.1.
The data are divided into 16 sectors of 22.5 each, with the center of vne first sector due north. The popult. tion is shown as a function of distance fru the NBS reactor.
The NBS site is shown in relation to the surrounding urban area in Fig. 3.3.
Households within the 8-km (5-mile) radius of the site include many federal employees and support or contracted staff for the numarous federal agencies in the Washington, D.C., metropolitan area.
The daytime population of the NBS site is about 3000 persons, all of whom are under the control of NBS. The NBS 3-3 L
an
ES-6096 N
N 15%
15%
m e
m 10 10 5
5 i
i AVERAGE WIND DIRECTION WIND DIRECTION FREQUENCIES FREQUENCIES DURING PRECIPITATION I
i 15 10 15%
WIND D!RECTION FREQUENCIES DURING NIGHT INVERSIONS Fig. 3.2 Annual wind rose showing wind direction frequency (%) for 16 radial directions 3-4
h
+
Table 3.1.
Incrementa l 1980 population data for 8-km (5-mile) radial segments and for the total 80-km (50-mile) radius in each of 16 directions from the National Bureau of Standards site Population distribution at distances given in miles Direction 0-5 5-10 10-15 15-?n 20-25 25-30 30-35 35-40 40-45 45-50 0-50 N
18,800 2,200 3,792 5,335 2,760 5,329 7,534 8,382 6,882 19,122 80,136 NME 12,800 2,700 3,073 6,614 6,067 8,973 25,750 10,053 7,731 40,164 123,925 NE 6,500 2,700 3,591 6,461 12,949 26,842 36,140 23,070 5,361 11.189 134,803 ENE 10,200 10,000 6,446 23,656 35,457 148,454 568,076 355,856 16,507 32,196 1,246,850 g3 E
6,400 8,500 7,023 38,877 45,896 36,887 141,963 83,700 19,191 0
388,437 La ESE 6,900 46,500 64,979 62,927 41,988 38,466 10,230 32,275 24,481 0
328,746 SE 16,400 44,400 176,441 356,955 239,098 70,506 17,604 6,674 7,092 9,176 944,346 SSE 8,200 20,600 103,775 261,538 287,029 96,620 20 fs44 17,008 9,166 9,807 834,567 S
3,100 25,700 43,020 166,658 158,452 42,871 60,467 18,906 16,758 5,359 540,291 S0W 2,400 1,800 15,754 35,344 25,760
,34,691 12,072 3,183 2,818 8,749 142,571 s-f 1,900 1,700 17,325 7,081 6,899 6,574 5,890 7,243 6,704 4.555 65,871 WCW 1,500 1,100 3,132 2,053 2,011 2,794 4,384 2,512 1,763 2,673 03,922 W
1,900 1,000 1,452 8,178 5,529 6,510 3,526 2,840 3,632 12,543 47,110 WNW 2,500 1,400 1,462 1,674 3,467 6,226 8,597 14.04%
A,725 25 937 73,493 NW 5,600 2,200 1,552 3,079 7,755 7,037 6,315 9.2k7 16,n35 19,985 100,955 NNW 4,600 2,700 2,587 5,741 31,230 7,752 7,725 7,624 10,603 23,158 103,720 Total 109,700 175,200 455,404 992,171 912,347 546,532 937,097 582,670 244,549 244,073 5,179,743
' staff. contributes only a small share to the dynamics of the local economy and minor changes in NBS operation as a result of possible adverse action of the NRC staff would have an insignificant impact on the local economy.
3.4 ' Land Use r
3.4.1 Site Land Use The plot plan of the 233-ha (576 acre) NBS site is shown in Fig. 2.2, and the i
site boundaries and the general location of facilities are as described in i
Sect. 3.1.'.About half of the site is vacant and is maintained in mowed grass.
i.
Two large ponds on the site (Fig. 2.1), which lie in the upper end of the 1
Mud @ Branch watershed,'are not used for activities associated with the pro-posed action. Of the 29 buildings on the site, major activities with nuclear L
materials will be conducted in only 4 buildings-221 (physics), 222 (chemistry),
j 235 (reactor), and 245 (radiation physics)-as identified in Fig. 2.2.
The reactor building contains the N8S research reactor, which is licensed sepa-rately by NRC (Sect. 1.2).
i-3.4.2 Ad.facent Area
)
Ihe N8S site vicinity has a mix of light industry, commercial, residential, i
and rural land uses. The eastern site boundary, I-270, is a major commuter highway for Washington,'D.C. The area on the opposite side of I-270 has seen rapid commercial and residential growth during the last decade.
The area east j
and west of the site is currently undergoing rapid residential growth, including multifamily development. Much of the area immediately south of the N8S property is owned by the National Geographic Society and is contrc11ed as a wildlife preserve, thus assuring its natural state for some time into the future.
3.4.3 Historic Significance The National Register of Historic Places 2 lists many historic sites in 1-Montgomery County.
None is located in the immediate vicinity of the site; the P
closest is in Rockville. No natural landmarks are located in Montgomery County,
[
according to the National Register of Natural Landmarks (48 FR (Mar. 1, 1983)].
1
'3.4.4 Floodplains and Wetlands No permanent streams and no floodplains are. located on or in'the immediate vicinity of the NBS site.
The only wetlands located on the site are two large
}
manmade ponds lying in the upper reaches of the Muddy Branch watershed. These ponds support a variety of aquatic fauna but are not associated with nuclear materials operations.
Several other manmade ponds also occur in the Muddy j
Branch watershed (Fig. 2.1).
.3.5= Geolony and Seismicity 3.5.1 Geolony l
.The site lies within a part of the Piedmont physiographic province, which is underlain by gneiss and schist of the Wissahickon Formation of Precambrian to early Cambrian age (600 to 550 million years before the present).
The schist, l
3-6
-. -.- - ---.~ - -
-~O
i l
ES4095
((
GERMANTOWN AND VICINITY GAITHERS8URG VICINITY I
>GAITHERSBURG I
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1 DARNESTOWN AND VICINITY ROCKVILLE TRAVILAH AND VICINITY i
l
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l t
f Fig. 3.3 Location of the National Bureau of Standards site in relation to adjacent urban areas 3-7
1 i
. which is derived from greatly compressed' sedimentary strata, is believed to be several thousand feet thick at the site.
-i Borings at the site indicate that the upper surface of relatively sound rock 1
ranges from 11 to 23 m (35 to.74 ft) below ground surface.
Above this sound rock is badly weathered rock and then various grades of saprolite, ranging from a fine silty sand with weathered rock fragments to silty clay in the 1.5 to 3.0 m (5 to 10 ft) below the surface top soil.
3.5.2 Seismicity.
1 The applicant presented a geological history of the different structures.in the region and correlated these structures with trends of local seismicity.
The-level of seismicity was found to be more uniform in the Southern Appalachian
}
fold belt, but nowhere is it defined well enough to indicate individually
~
aqtive structures.
Figure 3.4 shows that the site is in a region of minor seismic risk, but near a region of moderate seismic risk that correlates well with the observed seismic activity in an east-west belt in Central Virginia.a 4
The largest event identified occurred near Richmond, Virginia, in 1875 and was i
a modified Mercalli intensity VII event.4 A probabilistic acceleration map (Fig. 3.5) indicates that the horizontal acceleration at the NBS site, with a 90% probability of not being exceeded in i
50 years, is about 0.04 gravities. This is consistent with an earlier communi-cation from the U.S. Coast and Geodetic Survey,5 which indicates that the maximum potential earthquake for the area would result in a maximum ground acceleration of 0.07 g at the N85 site.
On the basis of the historic seismicity I
record and the tectonic framework of the region, it is highly unlikely that an earthquake of-high magnitude will affect the site.
3.6 Hydrology I
3.6.1 Surface Water There are no permanent streams on the NBS site, which lies on uplands between the watersheds of Muddy Branch and Long Draught Branch (Fig. 2.1).
During intense rainstorms, some' surface water may run off to Muddy Branch to the south and Long Draught Branch to the west and north, and to the Potomac River.
Two i
large ponds on the site lie in the upper reaches of a tributary of Muddy i
Branch (Fig. 2.1).
Drains located at parking lots and in the large expanses I
of lawns around the facilities ' direct much of the site's surface runoff to storm sewers, which empty into the Washington Suburban Sanitary Commission i
sewage system, and then into the Potomac River.
1 3.6.2 Groundwater j
The source of the groundwater at N85 is local precipitation, which averages j
about 102 cm (40 in.) per year (Sect. 3.2.1).
A zone of saturation or water.
table is maintained in the subsoils by rainwater that neither runs off directly nor evaporates. Generally, the water table is a subdued replica of the topo-graphy of the land surface, and the hydraulic gradients result in the movement of groundwater to the streams.
The rate of groundwater movement varies; in the subsoil or saprolite zone, the rate may be 3 to 30 cm/d (1 to 12 in./d), while i
3-8 i
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M 1 '.
.,,i\\.~',p 2
s.
3
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M 1 !).O., h
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4 -. " }...
- NBS s
SITE 2
s' b.
3 2
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s Q'
3 n,g DAMAGE Q 0 NONE O
O C"3 1 MINOF M 2 MODERATE M 3 MAJOR Fig. 3.4 Seismic risk map of the United States 3-9
ES-6100 4
9 9
g 1
1
, g!
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T;
-NBS
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,;Kl SITE
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4
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to A
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Fig. 3.5 Preliminary map of horizontal acceleration (expressed as percentofgravity)inrockwith90%probabilityofnotbeing exceeded in 50 years 3-10
khe'ratein'theunderlyingrock=ismuchslower.
Probably all groundwater at
- the site flows.toward either Muddy Branch or Long Draught Branch.
i
.I i
~The major use of groundwater within a 1.6-km (1 mile) radius of the site is for domestic and farm purposes.
Five currently inactive wells, located southwest
~
of the center of Gaithersburg, are public-supply wells owned by the Washington Suburban Sanitary Commission; these wells formerly supplied the town with 4
water.
Currently, water is piped to N85 and Gaithersburg from the surface waters of Sanitary Commission reservoirs.
3.7 Biota.
l 3.7.1' Terrestrial l
s Natural plant communities on the N8S site are lacking, as the site consists of l
1 extensive lawns with widely scattered plantings of trees and shrubs.
Such l
habitats support relatively low wildlife pop 41ations and relatively few wildlife j
species. - Robins, house finches, and house s; arrows are common.
The two large ponds on the site (Fig. 2.1) may provide habitat for migratory and resident waterfowl species.
3.7.2 Aquatic l
The only permanent aquatic habitats on the site are two large ponds lying in I
the upper reaches of a tributary of Muddy Branch (Fig. 2.1).
These may support several species of reptiles (e.g., frogs and turtles) and fish.
3.7.3 Endangered Species I
Aquatic or terrestrial species listed as endangered by the U.S. Department of the Interior'(50 CFR Parts 17.11 and 17.12) are unlikely to occur at the site.
Bald eagles and peregrine falcons may occur rarely as visitors in-the area, but no habitat in'the area is.important to their continued existence.
l 3.8 Radiological Characteristics (Background) f The total-body dose rate for the population in the vicinity of the N85 site is approximately 113 millires/ year.8 This dose rate includes 40 millires/ year i
from cosmic rays, 55 millires/ year from terrestial sources,'and 18 millires/
year.from internal emitters.
REFERENCES FOR SECTION 3 1.-
National Oceanic and Atmospheric Administration, Climates of the States, Vol. 1, Dale Research Company, Detroit, 1978.
[
2.
U.S. Department of the Interior, " National Register of Historic Places:
Annual Listing of Historic Places," Fed. Regist. 44(26),7415-7649 (Feb. 6, 1979); 45(54), 17446-17519 (Mar. 18, 1980); 46(22), 10622-10679 i
(Feb.3,1981);47(22),4932-4969(Feb.2,1982);48(41),86268679 (Mar. 1, 1983).-
3-11 i
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3.
Hadley, J. B and J. F. Devine, "Seismotectonic Map of the Eastern United States," United States Geological Survey, 1974.
4.
Bollinger, G. A., and M. G. Hopper, " Virginia's Two Largest Earthquakes-December 22, 1875, and May 31, 1897," Seismological Society of America Bulletin 61: 1033-39 (1971).
5.
Tison, Director of U.S. Coast and Geodetic Survey, letter with enclosures to Price, Director of Regulations, USAEC, Feb. 8,1967.
6.
D. T. Oakley, Natural Radiation Exposure in the United States, ORP/SID 72-1, U.S. Environmental Protection Agency, June 1972.
3-12
4.
ENVIR0hMENTAL CONSEQUENCES OF PROPOSED LICENSE RENEWAL 4.1 Monitoring Programs and Mitigatory Measures The environmental monitoring program at NBS includes sampling and analysis activities to detect changes in environmental radioactivity levels that could result from operation of the facility.1 There is no monitoring program for release or environmental accumulation of adverse nonradioactive material.
4.1.1 Effluent Monitoring The applicant collects samples from liquid waste tanks at the Reactor Building and at the Radiation Physics Building and analyzes them for radioactivity prior to releasing the liquid waste to the municipal sewer systems.
Little or no radioactivity above background has ever been detected in these liquid wastes.
The applicant does not monitor for radioactivity in the gaseous waste streams from the building vents.
Because of the large number of vents and the low quantity of gaseous radioactivity that might be discharged, the concentrations would probably be much lower than the sensitivity of available detectors.
Potentially contaminated solid wastes, including glassware, cloth and paper wipes, packaging material, and laboratory filters, are packaged for offsite disposal at a licensed facility.
These wastes are examined for unusual radio-activity to ensure that important source material is not accidentally discarded.
4.1.2 Environmental Monitoring Soil samples from four designated areas on the NBS site are collected periodi-cally, except during the growing season, when grass samples are collected from five areas (Fig. 4.1).
The soil and grass samples are analyzed for radio-activity by gamma spectroscopy.
Water samples are collected periodically from five surface streams and one residential well in the vicinity of the NBS facility (Fig. 4.1).
These samples are analyzed for gross gamma activity by gamma spectroscopy and for tritium activity by liquid scintillation counting.
4.1.3 External, Background Monitoring The ambient-background radiation level at the NBS site is measured by about 50 thermoluminescent dosimeters (TLDs) placed around the site perimeter fence and on NBS buildings.
Control monitors are kept at locations 5 to 32 km (3 to 20 miles) from NBS.
The minimum detectable level for this monitoring is 4 milli-rems or less per TLD.
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D RADIAtl0N PHYSICS,8LDO 24S E N85 RtACTOR,8LDO 23S O GRASS SAMPLING LOCATION A SOIL SAMPLING LOCATION WATER SAMPLING LOCATIONS G SURFACE WAf tR O WELL WATER Fig. 4.1 Location of radiclogical monitoring site and the principal buildings in wnich raoicactive materials are stored or used 4-2 t.
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. 4.' 1'. 4 Monitorina Results The environmental monitoring program at NBS began in 1963 with the collection l
of water samples.
Soil and grass sampling was initiated in 1965 and background
^
radiation measurements were initiated in 1966.
According to the applicant,1 no significant changes in activity levels have been observed since the start of l
the monitoring program.
Minor fluctuations in levels were observed over time, j
but.the variations.could not be correlated with any N8S operation.1 For the years 1981-1983, analysis of. composite surface water samples indicated i
no more than 0.018 pCi/ml of tritium, which is only 7% of.the 0.25 pCi/m1 average concentration in drinking water in selected cities of the United States.2 For the composite soil and grass samples, the analysis indicates no more than 0.8 pCi/g of asSr, 0.31 pCi/g of 80Sr, and 0.9 pCi/g of sa7Cs.
These concentra-I 1
tions are within the range of values for residual atmospheric fallout in U.S.
cities,2 indicating that N85 has not measurably added to the radioactivity on j
the site.
j f
4.2 Direct Effects And Their Significance t
4.2.1 Air Quality i
Nationalambientairqualitystandardsand/orgulhelineshavebeenpromulgated to limit the impacts of sulfur dioxide, nitrogen oxides, carbon monoxide, particulates, and hydrocarbons on air quality.
Releases of.these substances from operations associated with the proposed action are either nonexistent or j
so small (Sect. 2.2.2) that there is no concern that they would violate the l
standards.
Releases of non-regulated substances such as various organics are f
{
also very small and have no potential for significant impact on air quality.
No measurable changes in air quality should occur on or off the N85 site.
Radiological impacts on air quality are discussed in Sect. 4.2.5.
4.2.2 Land Use s
l No land use impacts have occurred as a result of N85 operations associated with the proposed action.
No additional buildings, major additions to existing l
buildings, or changes in operations are planned for activities with nuclear materials.. Therefore, no new impacts on land use, soils, or vegetation are expected.
Emissions to the air are very minor and will have no impact'on soils or vegetation important to landscaping, residential horticulture, agriculture, or other land uses in the local area.
No historic sites, floodplains, or wetlands will be affected.
4.2.3 Water Use i
Water for N85 operations is obtained from the treated Montgomery County (water supply. Total daily water use for all N85 operations is 1.3 million L 343,460 gal). Water use associated with the proposed action is a very small fraction of.this amount. No equipment associated with the proposed action requires water for cooling.
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- 4.2.4 Because no new facilities are planned as part of this licensing action, there will be no construction-related impacts on terrestrial or aquatic ecosystems.
Gaseous and particulate _ emissions from the facilities are inconsequential and will have no effect on vegetation or animals. All liquid effluents are routed i
to the sanitary sewer system and therefore will have no effect on surface 2
^
waters and aquatic ecology at the NBS site.
The site is well landscaped and areas not occupied by the facilities are well covered with vegetation so that sediment-laden surface runoff from rainstorms is minimal.
No endangered species resides or occurs regularly in the area, and none is affected by NBS operations.
4.2.5, Radiological Impacts Ggneral purpose laboratory facilities are contained in Buildings 222 and 245,
)
and radiochemical work is done in both buildings.
In addition, Building 245 contains several irradiators and some isotopic neutron sources.
There-are no routine releases of radionuclides from these facilities; however, for radio -
nuclide operations, roughing and HEPA filtration is available for discharges Lthat could result from accidental releases.
4.2.5.1 Direct Radiation There is some direct radiation from the assCf facility in Building 245.
According to the applicant, direct radiation at the site boundary is about.
l 0.004 milliress/h. That boundary separates NBS from undeveloped land, and the nearest resident (667 m distance) is shielded from line-of-sight by at least 50 m of earth. The sky shine contribution is about 0.0005 milliress/h.
Since i
operation of the 858Cf facility is intermittent, the total-body dose to the-nearest +esident or nearest line-of-sight boundary is estimated to be less than 0.1 milliress/ year, j
4.2.5.2 Maximum Individual Doses from Accidental Releases Two radiochemical operations can be considered as representative of potential releases of radioactivity to the environment.
Noble gases are occasionally used in Building 245 for standard production of. source capsules, and occasional alpha chemistry is done.
Both of these are batch processes and occur-infrequently.
Atmospheric dilution factors were calculated by the staff for the boundary distance (560 m) and the nearest resident distance (667 m).
Using methodology given in NUREG/CR-2260,8 releases were assumed to be at Class D (neutral) weather, and into a wind speed of 3 m/ ground level, in s.8
' Dose conversion factors were taken from Kocher* for external doses and from Dunning, et al.,5 for internal doses.
For the noble gas case -a process using 1 Ci esKr might be considered.
It is assumed that a 105 loss occurs during a 1-h operation. All of this loss is 1
released into the exhaust system and into the atmosphere.
This would lead to estimated concentrations in air of.1.3 x 10 ' pC1/mL at the boundary and 8.8 10 30 pCi/mL at the nearest residence.
Estimated doses to the total-bo@ and J4,4 j
-L- -. -
selected organs of exposed individuals at the boundary and at the nearest residence are given in Table 4.1.
Table 4.1 Maximum individual-doses from an accidental release of 100 sci of askr Dose to individual (millires)a Organ Boundary.
Nearest resident J
Total body 1.6 x 10.s 1.1 x 10.s j
. Skin 2.2 x 10 s 1.5 x 10.s
. Red marrow 1.5 x 10.s 1.0 x 10.s 1
i
'Endostial cells 1.7 x 10 8 1.2 x 10.s Lungs 1.5 x 10.s 1.0 x 10.s I
Liver 1.4 x 10.s 9.5 x 10.s i
Kidney 1.4 x 10 s 9.5 x 10 s aExposure is for a 1-h period of submersion in a radioactive plume.
I For the al ha chemistry case, it is assumed that a 1-h operation involving 1 mci of 8 'Pu is conducted in a hood.
It is further assumed that 10% of this amount escapes into the hood and that 1% is released into the environ-ment through the butiding/mL at the boundary and 9 x 10 15 i
exhaust.
This 1 pci release gives a concentration in air of 1.3 x 10 14 pCi pCi/mL at the i
7 nearest residence.
Estimated doses to an individual at the boundary and at 4l the nearest residence are given in Table 4.2 for the inhalation pathway of j
exposure.
External doses from submersion in the radioactive plume would be less than 10 12 millires.
i Table 4.2 Maximum individual doses from an accidental release of 1 pCi of sePu Dose to individual (millires)*
Organ Boundary Nearest resident Total body 1.3 x 10 8 9.1 x 10 4 Red marrow 5.9 x 10 8 4.1 x 10.s Endostfal cells-8.5 x 10 8 5.6 x 10 8 Lungs 1.1 x 10 8 8.3 x 10 8 Liver 1.5 x 10 8 1.0 x 10 8 Kidney 2.0 x 10.s 1.4 x 10 8 aExposure is for a 1-h period of. inhalation (air intake is a
0.93 m ) and represents a 50 year dose commitment.
r f
4-5
l Maximum individual doses associated with either the asKr or 88'Pu release are h
orders of magnitude below limits set for routine releases for uranium fuel-cycle facilities.
For example the total-body doses from asKr (1.6 x 10 8 millires) and assPu (1.3 x 10 5 millires) are 6.4 x 10.s and 5.2 x 10 8%
i respectively, of the 25 millires/ year total-body dose limit given in 40 CFR Pt. 190.
Moreover, the doses range from one-thousandth to one-millionth of a percent of the annual natural background radiation received by an individual (Sect. 3.8).
4.2.5.3 Population Doses from Accidental Releases Since complete site meteorological data were not available, an estimate of radiation doses to the surrounding population within 16 km (10 miles) was made as follows.
It was conservatively assumed that the population exposed i
to airborne radioactivities resides at a distance of 4000 m (2.5 miles) from the release point and that they are evenly distributed about the perimeter.
The activity concentrations in air at 4000 m are 2.8 x 10 22 pCi/mL for asgp and 2.8 10 17 pCi/mL for 88'Pu.
For the 284,900 persons within the 16-km l
l radius, the' population doses are given in Table 4.3.
The conservatively j
calculated doses for either the s*Kr or 2asPu release are all much smaller i
than 1 person-rem.
This may be compared to an annual background radiation dose l
of about 3.2 104 person-rem (total body) for this population.
l l
Table 4.3 Population doses from accidents involving i
asKr and assPu l
j Dose from asgr Dose from assPu" a
l (person-res)
(person-rem)
{
Total Body 9.5 x 10 7 8.0 x 10 4
)
Skin 1.4 x 10.s 1.3 x 10 8 j
Red Marrow 9.1 x 10 7 3.6 x 10 8 Endostial cells 1.0 x 10 8 5.0 x 10 2 4
Lungs 8.9 x 10 7 7.3 x 10.s i
Liver 8.3 x 10 7 9.5 x 10 8 j
Kidney 8.6 x 10 7 1.2 x 10 8
- Collective dose to 284,900 persons living within 16 km (10 miles) of the facility assuming this population resides 4 km (2.5 miles) from the site, 4.3 Indirect Effects and Their Significance 4.3.1 Socioeconomic Effects Because employment at the N85 facility is only about 1% of the population l
. within 16 km (10 miles) and is less than-0.2% of the population within 32 km (20 miles), operations at the site have an insignific. ant effect on the local econosty.' Therefore, neither license renewal or discontinuance of operations with SNM would have a measurable socioeconomic impact.
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4-6
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4.3.2 Potential Effects of Accidents i
i The NBS operations authorized by the SNM licenses involve small guantities of j
nonradioactive chemicals that would result in insignificant offsite impacts if accidentally released.
l As discussed in Sect. 4.2.5, the effects of potential accidental releases of p
radioactive materials, which could only occur infrequently because of the U
infrequent operations involved, would result in radiation exposures that are orders of magnitude below applicable Environmental Protection Agency (EPA) standards (40 CFR Pt. 190) for an individual and virtually immeasurable for C
the regional population.
1 The administrative controls established by the applicant, as described in the application documents,6 include (1) review committees for every process invol-ving SNM, (2) limitations on the quantity of SNM permitted in a laboratory for c
a processing operation, (3) responsibility assigned to one person for any SNM removed from storage, and (4) a strict materials accountability program admin-j istered by an independent health physics department.
The administrative controls J
are believed adequate to ensure that accidental releases of SNM from the batch
)
processing at the NBS site do not exceed the conservative values used in the j
assessment in Sect. 4.2.5.
.I 4.3.3 Possible Conflicts Between the Proposed Action and the Objectives of Federal, Regional, State, and Local Plans and Policies At this time, the staff is not aware of any conflict between the proposed action and the objectives of federal, regional, state (Maryland), or local plans, policies, or controls for the action proposed as long as the proper f
agencies are contacted, the proper applications are submitted, and proper 1
monitoring and mitigatory measures, if necessary, are taken to protect the j
environment and public health and safety.
1 4.3.4 Effects on Urban Quality, Historical and Cultural Resources, and Society The environmental effects of the proposed license renewal action as discussed above are considered to be insignificant. The facility has not affected histor-ical or cultural resources.
The short-term social effects during operation are immeasurable.
REFERENCES FOR SECTION 4 4
1.
National Bureau of Standards, Environmental Information in Support i
of the Application for U.S. NRC Materials License Consolidation, Docket No.70-398, Feb. 29, 1984.
2.
U.S. Environmental Protection Agency, Radiological Quality of the Environment, EPA-520/1-76-010, 1976.
3.
U.S. Nuclear Regulatory Commission, Technical Basis for Regulatory Guide 1.145, Atmospheric Dispersion Models for Potential Accident 1
Consequence Assessments at Nuclear Power Plants, NUREG/CR-2260,
)
October 1981.
5 e
4-7 5
. 4.
D. C. Kocher, Dose-rate Conversion Factors for External Exposure to Photons and Electrons, NUREG/CR-1918, August 1981.
5.
D. E. Dunning, G. G. Killough, S. R. Bernard, J. C. Pleasant, and P. J. Walsh, Estimates of Internal Dose Equivalent to 22 Target 4
Organs for Radionuclides Occurring in Routine Releases from Nuclear Fuel Cycle Facilities, Vol. III, NUREG/CR-0150, November 1981.
6.
National Bureau of Standards, Materials License Document (Application for Renewal and Consolidation of License Numbers 08-00566-05, 08-00566-10, 08-005ES-11G, 08-00566-012, 08-0566-13E, SMB-405, and SNM-362; Docket Nos. 30-3918, 30-6894, 30-3919, 30-9796, 30-1167, 40-4348, and 70-398), November 1983.
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