ML20147D760
| ML20147D760 | |
| Person / Time | |
|---|---|
| Site: | Berkeley Research Reactor |
| Issue date: | 01/31/1988 |
| From: | KAISER ENGINEERING (FORMERLY KAISER ENGINEERS), U.S. ECOLOGY, INC. (FORMERLY NUCLEAR ENGINEERING |
| To: | |
| Shared Package | |
| ML20147D750 | List: |
| References | |
| 87-040-R, 87-40-R, NUDOCS 8801200291 | |
| Download: ML20147D760 (19) | |
Text
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ENVIRONMENTAL REPORT FOR THE TR GA MARK l
BER<ELEY RESEARCH REACTOR
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e prepared for University of Cali"ornia, Berkeley prepared by Kaiser Engineers (Ct "'.
'a) Corporation in associai on with US Ecolo.<1y, Inc.
Facility License No. R-101 Report No. 87 040 R l
Docket No. 50 224 DbCK 00 24 P
CONTENTS Page 1.
EXECUTIVE
SUMMARY
1 2.
DESCRIPTION OF DECOMMISSIONING ACTIVITIES 1
2.1 INTRODUCTION
1 2.2 ACTIVITIES REQUIRED FOR DECON 1
3.
ENVIRONMENTAL IMPLICATIONS OF DECON 2
3.1 IMPLICATIONS OF DECON 2
3.2 COMMITMENT OF RESOURCES 2
4.
HEALTH AND SAFETY IMPLICATIONS 3
4.1 OCCUPATIONAL RADIATION DOSES 3
4.2 PUBLIC RADIATION DOSES FROM ROUTINE TASKS 3
4.3 PUBLIC RADIATION DOSES FROM POSTULATED ACCIDENTS DURING DECOMMISSIONING 3
4.4 RADIATION DOSES FROM ROVIINE TRANSPORTATION 8
4.5 RADIATION DOSES FROM POSTULATED TRANSPORTATION ACCIDENTS 8
5.
DESCRIPTION OF THE STATUS OF THE FACILITY 10 5.1 GENERAL LOCALE 10 5.2 FACILITY DESCRIPTION 10 5.3 ENVIRONMENTAL CHARA'#RISTICS 10 5.3.1 Meteorology 10 5.3.2 Geology 11 5.3.3 Seismology 12 iii J
CONTENTS (Cont)
Pago 5.3.4 Hydrology 12 5.3.5 Ecosystems 12 5.3.6 Noise Standards 13 6.
STATUS OF COMPLIANCE 13 7.
ADVERSE IMPACT INFORMATION 13 8.
REFERENCES 13
\\I a
iv
e TABLES Tablo No.
Title Page 1
Calculated Occupational Radiation Ooses 4
2 Estimated Occupational Lost-Time Injuries 5
and Fatalities 3
Calculated Radiation Doses From Atmospheric 6
Releases During Routine DECON Tasks 4
Summary of Accidents and Radiation Doses to 7
the Maximum-Exposed Individual 5
Calculated Radiation Doses from Routine 9
Radioactive Waste Transport v
1.
EXECUTIVE
SUMMARY
The Berkelr, Research Reactor (BRR) is a General Atomic TRIGA Mark III reactor which is to be decommissioned in 1988. The reactor began opera-tions in 1966 and operated for 293 effective megawatt days. The decom-missioning alternative chosen is DECON with release of the DECON area so that it can be used by the Nuclear Engineering Department and by others.
This report addresses the projected occupational and public radiation doses due to DECON activities and should be considered a supplement of the BRR Safety Analysis Report.
It contains the information that is understood to be required for the decommissioning of a research reactor.
2.
DESCRIPTION OF DECOMMISSIGNING ACTIVITIES
2.1 INTRODUCTION
The BRR is located in the Nuclear Engineering Laboratories in Room 1140 of Etcheverry Hall on the University of California Berkeley campus.
The reactor is a movable core, light water cooled and reflected reactor using uranium-zirconium hydride fuel elements.
The BRR was licensed for one megawatt steady-state operation and for pulsed operation.
The reac-tor began operations in 1966 and operated fcr a total of 293 effective megawatt days.
The University plans to decommission the BRR in early 1988 and to release the DECON area, as delineated in the BRR Decommissioning Plan (DP), for unrestricted use by the Nuclear Engineering Department and by others.
The University may elect to exclude particular equipment and facilities, such as the chemical hood in Room 1140, from complete decontamination, with the provision that such equipment and facilities be released by NRC to be under the State of California Radioactive Materials License.
2.2 ACTIVITIES REQUIRED FOR DECON Fuel will be shipped off-site following a 90-day cooling period before decommissioning activities are initiated.
Removal of the fuel is described in separate documentation.
The DF outlines ninc tasks to be accomplished in the sequence shown below:
Task 1 Contractor Move-in Task 2 Initial Radiation 'urvey Task 3 Installation of Con /inement Barriers Task 4 Removal of Reactor Components and Pool Liner Task 5 Removal of Material with Potential Surface Contamination and Other Activated Materials Task 6 Cleanup and Removal of Tools and Equipment Task 7 Packaging and Shipment of Radioactive Waste Task 8 Perform Termination Radiation Survey Task 9 Demolition of Non-Activated Portion of Reactor Installation 1
Descriptions and analyses of the above tasks are covered in the BRR OP.
3.
ENVIRONMENTAL IMPLICATIONS OF DECON 3.1 IMPLICATIONS OF DECON
/ comprehensive Safety Analysis Report (SAR) was completed in February 1964. This eport addressed environmental implications of routine and accident conditions related to the reactor.
Since the fuel will have been removed prior to the start of DECON activities, tha potential for environmental impacts will be greatly reduced.
The U.S. Nuclear Regulatory Commission (NRC) in its report, h'UREG-0586, concludes the following information.
o Based on the nearly completed data base results and on NRC staff considerations, taking account of the concerns of the State and public, and of the regulatory role the NRC must provide in protecting public health and safety, the following conclusions appear evident:
The technology for decommissioning nuclear facilities is well in hand. Decommissioning at the present time can be performed safely and at a reasonable cost.
Decommissioning of nuclear facilities is not an imminent health and safety problem.
However, planning for decom-missioning as an integral activity prior to commissioning is a critical item that can impact on health and safety as well as cost.
Decommissioning uf a nuclear facility generally has a positive environmentai impact.
The major adverse environmental impact of decommissioning is the commit-ment of small amounts of land for waste burial in exchange for reuse of the facility for other nuclear or nonnuclear purposes.
3.2 COMMITMENT OF RESOURCES i
DECON activities will result in the generation of low-level radioactive waste.
This waste can be categorized as:
o Activated metal components from the reactor internals o
Activated and contaminated concrete and other structural material o
Radioactive miscellaneous waste 3
8 The estimated disposal volume of radioactive waste is 190 m (6700 ft )
as determined in the BRR DP.
2
4.
HEALTH AND SAFETY IMPLICATIONS Occupational, public, and transportation safety impacts from DECON activities are summarized in this section.
4.1 OCCUPATIONAL RADIATION DOSES Estimates of occupational radiation doses are based on the postulated radiation dose rates in various areas of Etcheverry Hall and its en-virons and on the estimated staff labor required to complete the decom-missioning work.
Summaries of radiation doses are contained in Table 1.
Also presented are estimates of worker injuries and fatalities resulting from decommissioning activities. These industrial accident estimates presented in Table 2 are based on nuclear industry experience.
4.2 PUBLIC RADIATION DOSES FROM ROUTINE TASKS The consequences of atmospheric releases of radioactivity during routine decommissioning tasks are presented in Table 3 and are based on NUREG/
CR-1756 as adjusted to Bay Area population estimates. The radiation exposure pathways considered are direct external exposure, inhalation, and ingestion of food products.
Both the first-year doses and the 50-year committed radiation dose equi-valents to total body and lungs are listed. These radiation doses are all small as compared to natural background.
The dose to the maximum-exposed individual is 1.6 x 10-30 rem which is 1.6 x 10-' percent of the average yearly background dose of 0.1 rem based on NCRP 45.
4.3 PUBLIC RADIATION DOSES FROM POSTULATED ACCIDENTS DURING DECOMMISSIONING The consequences of pcstulated decommissioning accidents that result in atmospheric releases of radioactivity are calculated in NUREG/CR-1756 and presented in Table 4 following.
In addition, the radiation dose to the maxi.;;um-exposed individual in an unrestricted area directly above the reactor in case of a premature loss of pool water is described below.
Etcheverry Hall is sited on a slope which allows unrestricted access above Room 1140. The nearest dose point is 32 ft above the reactor core with 25 in. of ordinary concrete shielding supplied by the roof struc-tures. The SAR addresses a loss-of-pool water accideat and the dose to an individual above the core.
Since the dose rate from the irradiated fuel greatly exceeds the dose rate from the core structure and since the fuel is to be removed prior to DECON, the dose to a member of the public in case of a loss-of-pool water is greatly reduced.
3
Table 1 Calculated Occupational Radiation Doses Range (b)
Total (a)
Exposure Dose Rate Total (c)
Task / Activity Man hour Man hours Mrem, hour Man rem 1.
Contractor Move-in 412 84 0.2 0.017 2.
Initial Radiation Survey 144 84 0.2-10 0.19 3.
Installation of Confinement Barriers 472 354 0.1-0.2 0.068 4.
Removal of Reactor Components and 808 606 2-4 1.6 Pool Liner 5.
Removal of Material with Potential Surface Contamination and Other
' tivated Equipment 2372 1779 2
3.56 6.
Cleanup and Removal of Tools and Equipment 1140 855 0.1-2 1.2 7.
Packaging and Shipment of Radioactive Waste 384 288 2
0.58 8.
Perform Termination Radiation Survey 360 280 0.02 0.004 UCB Decommissioning Staff 640 480 0.5-1.0 0.36 GRAND TOTAL 6732 4810 7.7(c) a) Based on tasks man-hour estimates BRR OP.
b) Based on survey data BRR and NUREG/CR-1756.
c) Rounded to 2 digits.
I l
4
Tabic 2 Estimated Occupational Lost. Time Injuries and Fatalitics(a)
Frequency (Accidents /10' man hours)(b,c)
Lost Time Lost Time Category of Effort injuries Fatalities Man. hours injuries Fatalities Heavy Construction (d) 10.0 4.2x10-2 5.2x10 3
5.2x10-2 2.2x10-'
3 2.6x10-2 1.4x10-'
Light Construction 5.4 3.0x10-2 4.8x10 Operational Support 2.1 2.3x10-2 1.7x10' 3.6x10-2 3.9x10-'
2.7x10' l.1x10-1 7.5x10-'
(a) NUREG/CR 1756. Table 12.2-12.
(b) Estimates of man-hours, injuries, and fatalities are rounded to two significant figures.
(c) Lost-time injuries and fatality frequencies are from Operation Accidents and Radiation Exposure Experitocas Within the U.S., AEC 1943-1970, WASH-1192, 1977.
(d) Heavy construction involves demolition tasks such as removal of piping, equipment, and concrete.
5
Table 3 Calculated Radiation Dosec From Atmospgric Releases During Routino DECON Tasks Fif ty Year Committed First Year Dose Dose Equivalent (rem)
(rem)
Total Body Lungs Total Body Lungs Maximum-Exposed Individual 1.6x10-3' 4.8x10-18 3.0x10-1' 1.3x10-8 General Population (b) 1.3x10-'
6.1x10-'
2.6x10-'
1.8x10-'
(a) NUREG/CR-1756 (Based on Tables 12.3-1 and 12.3-2.)
(b) Doses are calculated tc a total population of 4.5 million paople residing within a 50-mile (80 km) radius.
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Table 4 Summary of Accidents and Radiation Doses to the Maximum-Exposed Individual (a) 50-Year Committed Dose Frequency of First. Year Dose (rem)
Equivalent (rem)
Accident Occurrence (D)
Total Body Lungs Total Body Lungs Oxyacetylene Explosion Medium 4.4x10-5 1.2x10-3 6.3x10-5 1.6x10-'
HEPA Filter Failure Low 8.4x10-'
2.4x10-7 1.2x10-*
3.1x10-'
Severe Transportativn i
Accident Low 1.3x10-'
4.1x10-'
1.3x10-6 8.3x10-'
i c'. ~xplosion Low 7.6x10-$
3.9x10-*
7.7x10-8 4.2x10-*
Vacuum filter-Bag I.upture Medium 1.5x10-'
4.3x10-*
2.2x10-'
5.6x10-a y
Minor Transportation Accident Low 3.2x10-'
1.0x10-5 3.2x10-*
2.1x10-5 Accidental Cutting of Activated Al in Air High 2.4x10-8*
6.9x10-'
3.5x10-8*
9.1x10-'
Loss-of-Pool Water Low 4.0x10-8 NA NA NA Contaminated Sweeping Compound Fire Medium 1.0x10-'2 5.3x10-i2 1.0x10- 2 2 5.7x10-i2 Combustible Waste fire High 4.8x 10- 8 '
1.5x10-*
4.i
'0-
3.2x10-(a) NUREG/CR 1756 (Based on Table 12.3-5)
(b) The frequency of occurrence considers not only the probability of the accident but also the probability of an atmospheric release of the calculated magnitude.
The frequency of occurrence is listed as "high" if the occurrence of a release of similar magnitude is >10-2 per year,'as "medium" if between 10-2 and 10-5, as "low" if >10-5
In the case of loss-of-pool-water prior to dismantlement and shipment of the core structure, the calculated dose rate outside, directly above the core, is 0.2 mrad /h six months after the reactor has been shut down.
This dose rate i; 10 percent of the permissible level of radiation in unrestricted areas cited in 10 CFR 20.105 for non-continuous exposure.
If one assumes that shielding or area control would be secured within two hours, the maximum dose to an individual would be 0.4 mrad which is approximately 0.4 percent of the yearly dose from natural background.
4.4 RADIATION DOSES FROM ROUTINE TRANSPORTATION Transportation of radioactive materials results in external radiation doses to the transportation workers and to the public along the trcns-portation route. Table 5 adapted from NUREG/CR-1759 gives the calcu-lated radiation doses from routine radioactive waste shipments.
4.5 RADIATION DOSES FROM POSTULATED TRANSPORTATION ACCIDENTS Transportation accidents have a wide range of severities. Most acci-dents occur at low vehicle speeds and have relatively minor consequences.
In general, as speed increases, accident severity also increases.
How-ever, accident severity is not a function of vehicle speed only.
Other l
factors such as the type of accident, the kind of equipment involved, and the location of the accident can have an important bearing on acci-dent severity.
Furthermore, damage to a package in a transportation accident is not directly related to accident severity.
In a series of accidents of the same severity, or in a single accident involving a number of packages, damage to packages may vary from none to extensive.
In relatively minor accidents, serious damage to packages can occur from impacts on sharp objects or from being struck by other cargo.
Conversely, even in very severe accidents, damage to packages may be minimal.
The re!ioactive materials that are transported in Type B packages (the highi / activated reactor core internals) are in solid, noncombustible forms that are not likely to become airborne in an accident.
Therefore, no accident analysis of Type B packages is considered.
Instead, NUREG/
CR-1756 analyzes two more realistic accidents involvir.g combustible radioactive wastes in Type A peckages.
Both, however, are judged to have a low frequency of occurrence. The calculated radiation doses to the lungs of the maximum-exposed individual resulting from these acci-dents are shown in Table 4 The severe transportation accident is assumed to involve rupture and fire in 40 waste containers (55-gal equivalent).
The total atmospheric releases are calculated to be:
5.2 x 10-' C1.
The calculated 50-year committed dose equivalent to the lungs of the maximum-exposed individual is 8.3 x 10" rem. For a minor accident, only one package is assumed to rupture and burn.
In that case, 1.3 x 10-' Ci are released.
The result-ing 50-year committed dose equivalents to the lungs are calculated to be 2.1 x 10-5 8
Table 5 Calculated Radiation Doses from Routino Radioactive Waste Transport (a)
Radiation Doso Total Population Alternative / Group (Man rom) '
Shipments ( <
Doso por Ggup per Shipm t
Number of (Man rom)
Truck Drivers 8.0 x 10-2 11 8.8 x 10-1 G_arage Men 4.0 x 10-8 11 4.4 x 10-2 Total Worker Oose 9.2 x 10-1 Onlookers 6.0 x 10-8 11 6.6 :, 10-General Public 2.2 x 10-8 11 2.4 x 10-2 Total Public Dose 9.0 x 10-2 (a) Based on NUREG/CR 1756 Table 12.4-1 and one-way tript, to Beatty, Nevada, cf 960 km (600 miles).
(b) Based on the waste disposal requirements discussed in the Decommissioning Plan.
(c) All doses are rounded to two significant figures.
9
- 5. DESCRIPTION OF THE STATUS OF THE FACILITY 5.1 GENERAL LOCALE l
The BRR is located on the University of California Berkeley campus in l
Alameda County, Califorrla.
The San Francisco Bay Area has a projected l
population of 4.5 million.
The reactcr site is approximately 2-1/2 miles l
east of the San Francisco Bay Interstate Highway 80, and the Southern Pacific Railroad.
The nearest major airport, Metropolitan Oakland International Airport, is approximately 11 miles south of the site.
5.2 FACILITY DESCRIPTION The BRR is in Etcheverry Hall in Room 1140, which is a high bay room, containing the reactor at the east end and various research and teaching facilities distributed throughout the remainder of the room. Additional rooms are located on the north side and on the west side.
The room is below grade, and the east wall is a retaining wall.
There is a parking lot and a patio on the roof above Room 1140.
Room 1140 is equipped with an independent ventilation exhaust system using HEPA filters.
There is also an emergency ventilation system.
Room 1140 and the rest of Etcheverry Hall is of reinforced concrete construction.
In addition to the existing ventilation system, a HEPA-filtered, negative pressure containment barrier surrounding the reactor will be in place during DECON activities.
5.3 ENVIRONMENTAL CHARACTERISTICS 5.3.1 Meteorology o
Predominant Wind Direction The most probable wind directions are west and southwest.
This is to be expected, since the normal westerly winds from the Pacific Ocean have a turning component created by the East Bay and Berkeley hills. The southwest winds are predominant in all quarters with the exception of the fourth-quarter wind rose. The daytime wind roses indicate an even higher proba-bility of winds from the west and southwest. Only in the case of the first-and fourth-quarter nighttime wind roses do the north to east components become predominant.
Surface wind conditions are summarized in Appendix A of the BRR Safety Analysis Report.
The 500-meter wind roses show a low probability of winds above 25 mph, whereas the surface wind roses indicate a very small probability of sustained wind above 22 mph.
o Temperature The temperatures expected in Berkeley are characterized by a rather narrow trargin of variations compared with other regions of the United States.
The mean daily maximum temperature is 10
71*F for September, with the mean daily minimum of 42*F in January. The highest recorded temperatures was 106*F for i
September, and the lowest recorded temperatures was 25'F for January.
The mean daily annual temperature is 56.7'F.
The mean daily maximum and the mean daily minimum vary at most
+ 15'F from this annual mean, o
Precipitation The precipitation data for the Berkeley region shows a rela-tively short rainy season.
The average mean precipitation of approximately 24 in, comes in the months of October through April. The summer months of May through September are charac-terized by very small average rainfall averages. The maximum mean precipitation of 4.9 in, was recorded in the month of January, with the minimum of 0.02 in, reported for July, o
Inversion Conditions The San Francisco Bay Area, in general, has a relatively high probability for the existence of inversion conditions.
The high, overall probability of inversion conditions existing in the San Francisco Bay Area agrees with the relatively high probability of wind velocities below 10 mph.
This over-all probability vsries from 27% to 59%, depending on the elevation and the time of day.
o Unusual Weather Conditions The most unusual weather phenomenon in the San Francisco Bay Area is the frequency of ocean fogs during the summer months.
The major significance of the high frequency of fog during the summer months is that stable, poor diffusion conditions will often be present.
This is correlated with the high frequency of inversion conditions existing during these same summer months.
Tornadoes rarely occur in California, and none has ever been reported in the San Francisco area. Destructive winds seldom occur and are not generally an engineering problem.
In general, the meterological conditions are similar to those parameters used in NUREG/CR-1756.
5.3.2 Geology The site of Etcheverry Hall lies near the foot of the Berkeley hills.
The surface soils consist of stiff silty clay mixed with ;and and rock fragments to depths varying from 10 to 20 ft below the surface.
These cover soils are derived from the bedrock present, and are considered to be fairly inert to normal chemical or physical destruction.
Below the surface soil, dense fractured sandstone is found to a depth of about 45 ft below the surface.
This is underlaid by dense decomposed shale and fractured sandstone.
11
5.3.3 Seismology The Hayward fault runs within approximately 30 m (100 ft) of the reactor site. The last significant event on this nearby Hayward fault occured in 1868. Recent studies indicate that the probability cf an earthquake on that f ault again is approximately 0.03% per year.
Therefore, the probability of a significant earthquake occuring during the one to two year decommissioning period is very small.
in the event an earthquake does occur, the only significant hazards would be the normal hazards of falling objects since the spent fuel, which is the major source of radioactivity, will have been removed prior to the start of the decommissioning activities.
5.3.4 Hydrology Surface drainage and underground drainage in the area of the reaccor site is down Strawberry Creek and into the Bay.
This creek has a small flow rate which is dependent on how much rain has fallen in the past month. Strawberry Creek is exposed during its run across the campus but is mainly covered or flows in culverts when it goes through Berkeley on its way to the Bay.
The water table will probably be above the reactor floor level on the east side of the building since the floor is about 50 ft below the grade level.
All the water which will drain from under the building will go into the sub-surface drainage pipe which eventually flows into Strawberry Creek.
The public water supply comes from rivers in the Sierras by way of aqueducts across the Sacramento Valley to stor-age reservoirs in the East Bay hills. There are no reservoirs below the elevation of the reactor.,ite, and the nearest reservoir is over 1/2 mi aaay to the north.
5.3.5 Ecosystems o
Wildlife in general, the University site supports habitats and asso-ciated wildlife that are typical of disturbed portions of the Berkeley-0akland hills.
Approximately 79 species of birds, 20 mammal species, and 19 reptile and amphibian species can be expected to occur on or near this area.
I No rare, threatened, endangered, or special status species are knonn or expected to occur in this area, o
Vegetation During the 19th and early 20th century, the University site was grazing land.
Cattle were managed at the site through the 1950s, and the predominant land cover was native and intro-duced grasses and shrubs.
l 12
1 The vegetation within the site can generally be classified into the following seven major types:
Baccharis brushland Coastal sagebrush scrub Oak-bay woodland Introduced annual grassland / disturbed /ruderal Introduced Eucalyptus plantation Introduced Monterey pine plantations Landscape plantings about roads and buildings 5.3.6 Noise Standards There are no applicable State of California or Federal Noise Standards that would apply to the decommissioning other than personnel exposure.
The City of Berkeley, in December 1982, passed a notarized ordinance which applies, among other items, to continually operating equipment such as mechanical equipment.
For example, the City of Berkeley ordi-nance which applies to R-1 and R-2 residential districts allows 55 dBA daytime sound levels (7:00 a.m. to 10:00 p.m.) and 45 dBA nighttime sound levels (10:00 p.m. to 7:00 a.m.) incident upon the property receiving the sound. These sound levels are not to be exceeded for more than 30 noise level measurement is appropriate as minutes in any hour; thus Lg a base for comparison with the steady-state noise generated by operation of mechanical equipment.
6.
STATUS OF COMPLIANCE The regulatory frame ork and applicable regulations, regulatory guide-lines, standards, and informed guidelines are specified in the BRR OP.
Engineering controls and implementation of the occupational and Radia-tion Protection Program will ensure compliance with applicable environ-mental quality standards during DECON activities.
7.
ADVERSE IMPACT INFORMATION DECON activities as implemented at the BRR should have minor adverse impact. Theses include an occupational dose burden which is well within regulatory guidelines, a modest cost compared to commissioning and operational cost, and the irreversible commitment of a small amount of land at a commercial low-level radioactive waste burial facility.
8.
REFERENCES NRC Oraft "Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities," NUREG-0586, 1981.
National Council on Radiation Protection and Measurements.
"Natural Background Radiation in the United States," NCRP 45, 1975.
G.J. Konzek, et al.
"Technology, Safety and Cost of Decommissioning Reference Nuclear Research and Test Reactors," NUREG/CR-1756 and addenda, 1982.
13
University of California, Berkeley, "Safety Analysis Report for the University of California Berkeley Research Reactor," February 1964.
Lawrence Berkeley Laboratory "Site Development Plan Final Environmental Impact Report," August 1987.
Lawrence Berkeley Laboratory, "Site Development Plan Draft Environmental Impact Report," December 1986.
University of California, Berkeley, "Emergency Response Plan for the University of California TRIGA Mark III Berkeley Research Reactor,"
License No. R-101, Docket No. 50-224, October 1982, revised August 1984.
University of California, Berkeley.
"Berkeley Research Reactor Decom-missioning Plan," 1987.
PREPARERS Paula Trinoskey Harry Isakarf l
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