ML20148F532
| ML20148F532 | |
| Person / Time | |
|---|---|
| Site: | 07001308 |
| Issue date: | 09/25/1978 |
| From: | Dawson D GENERAL ELECTRIC CO. |
| To: | Meyers S NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| DMD-226, NUDOCS 7811090065 | |
| Download: ML20148F532 (55) | |
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PROGRAMS
$ECEiVED GENERAL ELECTRIC COMPANY,175 CURTNER AVE., SAN JOSE, CALIFORNIA 95125 DlVISION
'978 SEP 29 AM 10 43 DMD-226 U.S.1:
- REG, Cw:' m.,0N g
HMSE IMIL SECTION A'
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September 25, 1978 OfficeofNuclearMaterialSafety&Safegu%~ds ar Attn: Mr. Sheldon Meyers, Director N
Division of Fuel Cycle and Material Safety U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Gentlemen:
SUB3ECT:
REV1SION B1, OPEPATING EXPERIENCE - IRRADIATED FUEL STOPAGE - MORRIS OPERATION NED0-20969B, MAY 1978 We are pleased to send you ten (10) copies of the subject revision to the operating experience report for General Electric's Morris Operation.
This revision incorporates environmental monitoring reports for 1977, as well as editoria]
changes.
Table 3-3 has been revised to incorporate offsite concentrations as well as gross releases.
Please contact our H.A. Rogers if there are questions regarding this revision.
Respectfully, l
/E M W D.M. Dawson, Manager Licensing & Transportation 408*925-6330 MC 861 qa p', p g-.a>
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- f-DMD:HAR:bn e
Enclosure
- 7. " "
3 79/ N D #
e NEDO-20969B1 Sep,tember 1978 O
Operating Experience - Irradiated Fuel Storage Morris Operation b
REVISION INDEX for Revision B1 September 1978 Incorporates errata and Appendix B-1:
Environmental Monitoring Report for 1977 Pages to be Removed New Pages to be Inserted Chapter Page Number Date Chapter Page Number Date Front 11 9/78 Matter 2
2-11, 2-12 5/78 2
2-11, 2 -12
- 9/78 3
3-3, 3-4, 5/78 3
3-3, 3-4' 9/78 3-7, 3-8, 5/78 3-7*, 3-8 9/78 3-9, 3-10, 5/78 3-9, 3-10' 9/78 3-11, 3-12 5/78 3-11, 3-12' 9/78 3-13, 3-14 5/78 3-13, 3-14*
9/78 3-17, 3-18 5/78 3-17 *, 3 -18 9/78 5
5-1, 5-2 5/78 5
5-l', 5-2 9/78 Appendix B1 B1-1 to B1-42 9/78
" Backup" page'- no change in subject matter. These pages retain previous publication number and date.
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Srptember 1978 OPERATING EXPERIENCE -IRRADIATED FUEL STORAGE MORRIS OPERATION REVISION
SUMMARY
Revision & Amendment Date Summary NEDO-20969B 5/78 Reissue and update - Replaced issue dated 8/75 NEDO-2096981 9/78 Incorporates errata and Appendix B1, environmental monitoring report for 1977 Revision Coding Key: New or changed information is indicated by vertical bars in the right hand margin opposite the new or changed information: "N" indicates new information; "E" indicates editonal changes or corrections.
Document Number Key:
Revision Prefix Senal Amendment Senes di.
NEDO-2096931 Septembar 1978 2.3.5.1 Outages There have been four times in the 6 years of experience at Morris Operation when E
the facility was not available for fuel receipt. The first instance was 13 days following the cask tipping incident in June of 1972. The second was a planned outage in August of 1976 for 10 days when the cable in the cask crane was replaced.
The third period occurred when the old fuel storage racks were being removed and new fuel storage system hardware was being installed. This occurred in October and November of 1975 (a total of 34 days). Finally, 26 days in January 1977 were used to repair minor damage to an IF-300 cask head-to-cask sealing surface.
This work was performed with the cask on the decontamination pad, blocking move-ment of other casks.
Annual outages of about two weeks per year have been scheduled so that routine maintenance items could be accomplished more expeditiously.
In addition, there have been short periods (of less than a day) when operations have been suspended for crane inspections, maintenance and repairs. Most support systems do not have an immediate or direct effect on fuel receipt and storage, and these systems
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can be nhut down for various periods of time without any adverse effect on aperaciaas. The types, typical lengths and purposes of subordinate outages are givea in Table 2-3.
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2-11
NED0-20969B May 19 78 Table 2-3
SUMMARY
OF SUBORDINATE OUTAGES Approximate App roximate Annual (Length)
Type Frequency (days)
Purpose (s)
Boile r 1
3 to 5 Inspection and tests 3
<1 Minor mairtenance Cooler Various Up to 44 Maintenance Basin response tests Minimura cooling period Filter Various Up to 65 Maintenance and Basin Response tests Ventilation 1
<1/3 Inspection and tests O
O 2-12
NEDO-20969B1 September 1978 A pneumatic quick drain system, insulation on the pipes and distribution boxes,
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and additional propane heaters have been installed to prevent a reoccurrence of cold weather problems. Cooling system pumps have been connected to the standby electrical power system.
Pending these modifications and warmer weather, the coolers remained shut down and basin water temperature was allowed to come to equilibrium. The increase from 31*C in January of 1977 to 45'C in March (averages) shown in Figure 3-1 resulted from this cooler shutdown. ~
With the onset of warmer weather, an undamaged portion of the cooler was placed in operation and the damaged section was repaired.
3.2.2.1 Heat Load E
The heat input to the basin from decay of radioactivity in the fuel has increased gradually with an increase in the amount of fuel stored. Figure 3-2 shows the approximate heat load history. The increases in 1975 and 1976 reflect the receipt of more recently discharged fuel, some out of the reactor only 122 to 150 days at the time of receipt at Morris Operation.
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3.2.2.2 Cooler Contamination E
Radioactive material from the basin water has accumulated on the inner surfaces of cooler piping, tubes, and headers. A sample of material taken from the inner surface of the cooler piping in March 1977 contained Cs-134 (15%), Cs-137 (45%),
and Co-60 (40%). Average monthly exposure rates are shown in Figure 3-3.
The rapid increase in the second half of 1977 was caused by the underwater cleaning of an insert for the IF-300 cask.
3.2.3 Cooler Operation Summary In summary, experience has shown that the fin-fan coolers will provide the cool-ing service required by water basin fuel storage, but that cold weather provisions 3-1 The scale of Figure 3-1 does not show the equilibrium period (about 47'C for "N
two weeks).
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NEDO-209693 May 1978 2400 0
g 2000 Nif!W; DRESDEN YYil' f
POINT BEACH 5
,g SAN ONOFR E o
g l
l HADDAM NECK h
P;<?:8; <
1200 S
E W
g 800 W////)
m 0
1972 1973 1974 1975 1976 1977 Figure 3-2.
History of the Heat Generated by Fuel Stored at Morris Operation 60 O
so Q AVERAGE MONTHLY EXPOSURE RATE FOR TLDS PLACED UNDER THE COOLERS 40 E
C 30 m
e a
20 10 l
l l
1 l
l l
I l
I l
l l
I 1976 1977 Figure 3-3.
History of Cooler Exposure Rates 9
3-4
NEDO-20969B May 1978 averaged about 3 x 10 and 1 x 10 pci/mt, respectively, except for periods 3-5 when the filter system was not operated (MFC for restricted areas for Cs-134 u
is 3 x 10 ; for Co-60 it is 1 x 10-3),
The history of the concentration of tritium in the basin water is shown in Figure 3-5.
This data is consistent with an annual transfer from fuel of 120 to 135 mC1. This is reduced by an effective basin water evaporative loss of 50 to 100 gal / day. Since the evaporation rate of H O is greater than that 2
of tritiated water, tritium tends to concentrate. The concentration of tritium is expected to reach equilibrium, when the losses through evaporation and tritium decay equal the transfer rate, at about 5.5 x 10 pCi/mt.
3.3.2 Chemical Cleanup In early 1972 a substantial quantity of sodium nitrate (NANO ) was introa ced 3
into the basin water. This material had been used as antifreeze in several casks and contaminated the basin water to the extent of at least 250 parts per million. This reduced the effectiveness of the resin ion-exchanger in control of chloride and radiocesium. No special efforts were made to remove the NANO 3 other than one period of increased filter change frequency in late 1972. This resulted in a brief acceleration of the reduction in NANO 3 concentration (Figure 3-6).
The chloride concentration remained relatively constant through the entire period when NANO 3 was present at concentrations greater than 10 parts per million. The routine use of the filter system resulted in gradual removal of the sodium nitrate. In March of 1976 the frequency of filter change was accelerated - on one occasion, six changes were made in two days. As the sodium nitrate approached five parts per million, the chloride concentration began to drop rapidly. By the end of April 1976, chloride, sodium, and nitrate were all below analytical detection limits (0.02 ppm C1, 0.2 ppm Na, and 0.2 ppm NO ),
3 where they have remained.
3 "' Referred to as Project 1.
Because of anticipated fuel mix (as of March, 1978) the capacity will probably be about 700 TcU.
3-4 A proprietary product of the Norton Co.
3-5 Cs-134 is used as a basis, since this is more restrictive than the MPC for Cs-137.
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3-7
NED0-20969 B1 September 1978 l
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22 50 gal / day 2.6 100 ga/ day 2.4 g
lE 2.2 a
g E
2.0 1
3 u
o n
1.6 h
~
1.4 a
t; 1.2 O
2 1.0 02 0.6 0.4 0.2 0
1972 1973 1974 1975 1976 1977 Figure 3-5.
Tritium Activity O
3-8
NEDO-20969B1 September 1978 In October 1975 when the sodium concentration was about five parts per million, a twelve liter sample of basin water was evaporated to a solid which was analyzed for 71 elements by spark source mass spectrography (SSMS) and for nitrate tetraborate, chloride, and sulfate by wet chemical methods. The elements at or above concentration levels of 0.01 parts per million in the original basin water are listed in Table 3-1 (uranium is also included).3-6 3.3.3 Ionic cleanup The removal of ionic impurities by ion exchange is predictable. At ionic con-centrations in water above a few parts per million, the resins can be loaded to saturation, and the amount removed is governed by the chemical capacity of the resin. At lower concentrations the distribution coefficient for the species in question governs the equilibrium loading of the resin.
For cation exchange the distribution coefficient for cobalt and cesium were 0
5
~
found to bu about 10 and 10 mE/g respectively.
Once the concentrations of impurities were reduced, application of this resin allowed the content of f
radiocobalt in the basin to be held below 0.5 curies. However, the resin was less effective in removing cesium, so an effort was made to find a more efficient method.
3.3.3.1 Zeolon Application Zeolon-100 was first tested in February 1974 and later it was used experimentally in the basin filter system (through 1974-1975).
It came into routine use in January 1976 and was found to have a high specific affinity for cesium.
In addition, the distribution coefficient for use in high purity water was found to be the unusually large value of 10 mt/g. Tests have shown that only 3-6 Currently, with reduction of the total ionic content to a demineralized water level (conductivity one micromho per centimeter) concentrations of metallic elements are probably even lower than listed in Table 3-1.
3-7 The ratio of concentration of adsorbed ion in the resin to ionic concentration in the water is expressed:
E gm ion /gm resin gm ion /m2 water O
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3-9
NEDO-20969B May 1978 9
A A
A A
A A
A A
A t
O O
O A
~
O O
O A
O A
O A
O O
A A
10 O
O O
- s g
O O
O O
O O
O O
o O
0 1.0 6
d NITRATE O CHLORIDE O sooivu O
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A O
O l
l l
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0.1 1972 1973 1974 1975 1976 Figure 3-6.
Chemical Contaminants in the Morris Fuel h
Storage Basin Water, 1972-1977 3-10
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NEDO-20969B1 September 1978 Table 3-1 IONIC IMPURITIES IN BASIN WATER lE (October 1975)
Element PPW Method Li 0.02 SS}S*
Mg 0.d1 SSFS A1 0.01 SSMS C1 0.8 SSFS K
0.08 SSMS U
0.008 SSMS NO3 7.9 Wet Chem.
B0 2.7 Wet Chem.
47 C1 1.6**
Wet Chem.
SO 0.05 Wet Chem.
4
- Spark Source Mass Spectrography
- Limit of detection
>O 2 kilograms of Zeolon-100 are needed to partition the radiocesium in the basin so that 88% is captured by cae e;: changer and only 12% remains in the water. For example, the application of 2 kilograms of Zeolon-100 to the basin filter three times in succession would reduce an daitial basin inventory of 1000 curies to less than 2.
In this case, as with any true ion-exchanger which is not pushed to capacity, the limiting rate of removal is determined by the rate of approach to equilibrium. Since the turn-over rate of the basin water is 45 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br />, the j
time to reach equilibrium is several days.3-8 i
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3-8 Details of these studies are contained in the following paper:
L. L. Denio, D. E. Knowlton, E. E. Voiland; Control of Nuclear Fuel Storage Basin Vater Quality by use of Poudered Ion Exchange Recin and Zeolites; ASFE 77-JPGC-NE-15 (June,1977).
b) v 3-11 1
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NEDO-20969B May 1978 3.4 VENTILATION SYSTEM O
Air quality in the Morris Operation fuel storage areas (main building) and environs is controlled through the building ventilation system, the sand filter, and the stack.
3.4.1 Work Area Air Concentrations Table 3-2 gives the concentrations of particulate radioactive materials in air within the building and the exhaust air. Without exception these concentrations have been much less than the applicable MPC values.
Table 3-2 AVZRAGE CONCENTRATIONS OF RADI0 ACTIVITY IN AIR IN WORK AREAS AT MORRIS OPERATION - 1976/1977 Gross Alpha Activity Gross Beta Activity x 10~
pC1/mi x 10~
pC1/mt Location 1976 1977 1976 1977 Decontamination Area 0.06 2.6 3
Upper 0.01 0.23 3
Lower 0.05 15.0 Basin 0.11 0.03 2.2 4.0 Canyon 0.04 0.03 7.9 4.3 Laboratory 0.08 0.04 0.27 0.24 Outside Air 0.19 0.10 0.49 0.46 i
-10 Notes:
1.
U natural basis MPCA = 1 x 10 uCi/mt 2.
Cs-134 basis MPC = 1 x 10~
uC1/mi A
3.
Singic monitor replaced by two in 1977 O
3-12
September 1978 i
An increase in concentrations in the basin exhaust plenum occurra.d during the 3-9 fourth quarter of 1976, attributed to work in a greenhouse on the decon pad.
Ventilation air from the greenhouse was exhausted directly into the plenum.
Concentrations of airborne radioactivity in many portions of the process build-ing, as typified by values in the Laboratory, are lower than those in the out-side air. This is the result of filtration of the air as it is drawn into the building. Concentrations of radioactivity in the building exhaust, downstream of the sand filter have been lower than the applicable MPC values, without taking credit for atmospheric dilution. The amount of radioactive materials, in Curies, release.J to the environment by way of the stack during each of the past three yr.ars is shown on Table 3-3.
Table 3-3
SUMMARY
OF RELEASES OF RADIOACTIVITY AT MORRIS OPERATION VIA THE MAIN STACK N
Gross Alpha Activity Oross Beta Activity Amount Highest Amount Highest pCi Off-Site pCi Off-Site Concentra-Concentra-tional tion 2 Half Year UCi/cm3 uC1/cm3 2nd Half 1974**
78 6.6 x 10 19 115 9 6 x 10-19 1st Half 1975 16 3.8 x 10-20 51 1.2 x 10-19 2nd Half 1975 10 3 2 x 10-20 33 1.0 x 10-19 1st Half 1976 7
2.7 x 10-20 18 6.8 x 10-20 2nd Half 1976 11 4.5 x 10-20 28 1.2 x 10-19 1st Half 1977 4
2 3 x 10-20 15 8.5 x 10-20 2nd Half 1977 6
3 1 x 10-20 119 6.1 x 10-19 r
i Notes:
- Averaged over the period indicated
- Data not tabulated prior to July 1974 1.
U natural basis MPCA = 5 x 10-12 pci/cm3
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2.
Co-60 basis MPCA = 3 x 10-10 PCi/cm3 N
3-9 A temporary enclosure erected to control contamination while cutting up I
hardware from the original fuel storage system.
O 3-13
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NED0-20969B May 1978 3.4.2 The Sand Filter j
The sand filter has operated effectively in removing radioactive particulates from the main building exhaust air.
Two incidents occurred that reduced air j
flow capacity.
3.4.2.1 Sand Filter Problems In May 1972 a plugged ventilation line between the fluorine building and the sand filter, and an increase in the pressure drop across the sand filter prompted a sand filter inspection.
The top surface of the sand was found to be caked with electrolyte from the fluorine building. The tcp layer of sand was raked to return it to its original consistency, and the ventilation line from the fluorine building was routed directly to the air via a 35-ft stack.
In addition, monitoring of the sand filter at various depths was begun.
(Since then the fluorine generating equipment and hydrogen fluoride have been removed from the site.)
In 1973 another increase in sand filter pressure drop was observed, this time g
in the bottom of the filter. Inspection via an air-tunnel entry uncovered a partial clogging of the inlet screens. This was attributed to process start-up work. The screens were cleaned, and a second set of screens, more readily accessible than the first, was placed upstream.
3.4.2.2 Filter Efficiency Twice, efforts were made to determine the particulate removal efficiency for the sand filter. The first time the downstream activity was so low it could not be determined, and the second time, the downstream activity was near the threshold for detection.
Based on the values determined in the second assess-the efficiency was found to be 99.9% for Co-60 and 99.8% for Cs-137 and ment Cs-134.
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3-14
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NEDO-20969B May 1978 Table 3-5 O
HISTORY OF LAW VAULT CONTENTS Volume of Approximate Approximate Vault Contents Cross S Concentrations
- Density
- Date (Gallons) uCi/mi g/cm3 3-6-74 367,000 0.014 2-18-75 169,000 0.039 6-5-75 411,000 0.033 1.060 11-16-75 187,000 0.13 1.141 8-15-76 343,000 0.11 1.000 12-12-76 206,000 0.27 1.204 2-20-77 224,000 0.21 1.122 10-9-77 338,000 0.18 1.080 12-31-77 238,000 0.36**
1.125
- The density and concentration of the solution in the LAW vault vary with depth. These values should not be used to compute the total solids or activity in the vault.
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- The major contributing isotopes were the following:
Co-58 0.0074 pC1/mi Co-60 0.028 pCi/mi Cs-134 0.065 uC1/mt Cs-137 0.28 pCi/mt i
3.5.1.2 Cladding Vault By comparison to the LAW vault, the cladding vault has been little used.
Table 3-6 shows the activity in the cladding vault over about the same period as Table 3-5 for the LAW vault. Because of little use, the increase in con-centrations and activities in the cladding vault have been much smaller. New accumulations since the initial retransfer of water back to the LAW vault 1
have averaged only about 7,000 gallons per year.
Presently, the cladding vault contains only about 50,000 gallons of waste water.
Cladding vault use 1s summarized in Table 3-7.
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3-17
. 1
NEDO-20969B1 September 1978 Table 3-6 HISTORY OF CLADDING VAULT RADIOACTIVE MATERIAL CONCENTRATION Date Gross 6 (uCi/mf.)
July 1973 0.004 x 10'
-3 November 1973 0.97 x 10
-3 January 1975 5.1 x 10 November 1975 5.3 x 10~
November 1977 4 x 10~
- Estimated from the then current LAW Vault Activity.
Table 3-7 HISTORY OF CLADDING VAULT USAGE Cladding Vault Net Change Event Date (Gallons)
Accumulation to 10-5-73
+ 49,000 Transfer from LAW Vault to 10-17-73
+ 146,000 Accumulation to 2-18-75
+ 17,000 Partial Jet-out to LAW Vault to 5-20-75
- 23,000 Pump-out to LAW Vault to 6-4-75
- 156,000 Accumulation to 12-31-77
+ 17,000 on 12-31-77 50,000 3.5.1.3 Radioactive Waste Summary During the 6 years of operation of the vaults there have been few problems.
The accumulation of water in the leak detection system (which is collected and returned as radioactive waste water) has been so small that measurements of it are uncertain.
Best values of leakage as determined by modified isotope dilution E
techniques are given in Table 3-8.
O 3-18
NEDO-20969B May 1978 p
5.
ENVIRONMENTAL IMPACT v
5.1 INTRODUCTION
Six years of receiving and storing irradiated nuclear fuel at the Morris Operation have not caused any measurable impact on the environment. Experi-ence during this time indicates that fuel storage and associated fuel handling and waste treatment offers very little potential for any significant environ-mental impact.
5.2 MORRIS OPERATION EFFLUENTS AND CONTAINMENT Two types of solid wastes result from fuel storage operations: Ordinary non-radioactive trash and solid waste contaminated with low-level radioactive material. Trash disposal is through an authorized disposal company. The contaminated waste is packaged in accordance with NRC and DOT regulations and shipped to a NRC-licensed waste disposal facility.
The low-level radioactive liquid waste is maintained in the LAW vault and, if needed, the cladding vault. None is released to the environment.
Nonradioactive liquid waste consists of:
(1) waste from regenerating the water demineralizer units which is routed to the evaporation pond (none released beyond the site boundary), (2) sanitary waste which is routed to the sanitary lagoons and (3) condensate blowdown water from the utility boiler, blowdown i
waste from the air compressor cooling tower, and intrusion water from the LAW j
vault which are also routed to the evaporation pond.
No liquid wastes are j
discharged from the site.
A holding pond has been added to the sanitary waste system. Effluent from the holding pond can be chlorinated, and applied to land in the GE tract in an j
irrigation program.
0 5-1
NEDO-20969B1 Septembsr 1978 The only waste effluents from Morris Operation consist of the following:
a.
Exhaust from the utility boiler which is combustion gases from a maximum rated 25,000 lb/hr natural gas fired steam boiler, b.
Exhaust from the auxiliary diesel generator which is combustion gases from a rated 815 hp diesel engine, normally operated only on an inter-mittent basis (%1 hr/wk).
c.
Ventilation air and vapor from the main process building, via the sand filter and stack.
As indicated in the discussion of the ventilation system, the building off-gas contains virtually no radioactive material. Doses calculated from measured releases of radioactive material are less than one billionth of the average dose from background radiation. ~
5.3 ENVIRONMENTAL MONITORING O
Environmental radiation monitoring near the 11 orris site has been done by Commonwealth Edison since 1958.
In late 1967 General Electric joined with them to expand the program to fit the combined needs of the two facilities.
By June 1973, all the samples were being taken and analyzed that would have been required if fuel reprocessing were to start up.
The Dresden environmental reports are a matter of public record.
The reports for 1974 and 1976 are presented in Appendix A and B (for comparison). ~
~
The results of the monitoring program have not identified any radioactive materials off-site or any increase in off-site dose rates resulting from fuel storage (or the previous process testing) at !! orris Operation.
Furthermore, 5-1 Background radiation:
naturally occurring radiation from the earth and from outer space which amounts to about 140 mrem / year, and man-made radiation not associated with nuclear power, e.g., watch dials, television and medical x-rays which amount to s60 mrem / year on the average. Natural background can E ""
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5-2 * ""ts for subsequent years will be added by revisions as Appendix B-1, B-2, etc N
Repor 5-2
NEDO-20969B1 September 1978 O
APPENDIX B-1 RADIOACTIVE WASTE AND ENVIRONMENTAL MONITORING January - December 1977 0
A O
B1-1/B1-2
NEDO-20969B1 Septetnber 1978
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O GENERAL ELECTRIC COMPANY MORRIS OPERATION RADI0 ACTIVE WASTE AND ENVIRONMENTAL MONITORING JANUARY THROUGH JUNE 1977 O
B1-3/B1-4
)
NEDO-20969B1 September 1978 TABLE OF CONTENTS PAGE Introduction...................................................
1 Summary........................................................
2 Effluents to the Atmosphere....................................
2 Table A GE-MO Releases to the Atmosphere.................
3 Table B Maximum Off-Site Relative Concentration (X/Q)-
GE-M0 Main Chimney...............................
4 Environmental Monitoring Results...............................
5 Table C Site Monitoring Results..........................
6 Table D Plutonium in Air Particulate Filter Composites... 8 Table E I.
Gross Beta in Air Particulates..............
9 O
II.
Gross Alpha in Air Particulates.............
10 Table F Quarterly Fluoride Analysis of Fallout Strip Samples.........................................
11 Table G Miscellaneous Tritium Analyses...................
12 Table H Gross Alpha and Gross Beta in Surface Water Samples..........................................
13 Table I Gross Beta and HTO in Well Water Samples.........
13 Table J Nitrates in Surface and Well Water Samples....... 14 Table K Fluoride in Vegetation Samples...................
15 Table L Radionuclides in Precipitation Samples...........
16 O
B1-5/B1-6
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NEDO-20969B1 September 1978 Introduction The General Electric Morris Operation (GE-MO) is located approximately twelve miles southwest of Joliet, Illinois, immediately south of and adjacent to the Dresden Nuclear Power Station.
The facility is used to store spent nuclear fuel, and is designed to contain all radioactive liquids and essentially all of the airborne particulate radioactivity in its effluents. Traces of gaseous radionuclides, mainly Kr-85, and tritium may be released to the atmosphere.
The facility may also re-lease small amounts of hydrogen fluoride.
Releases to the atmosphere via the 91 meter stack are estimated by analyses of continuously col-lected composites samples of particulate matter (filter) and of fluorides (scrubbed condensate). The monthly average atmospheric dispersion factor (X/Q) is calculated using on-site meteorological data for the period.
The gamma radiation doses from GE-MO releases and Dresden plus GE-MO combined are calculated based on isotopic analyses of ef-fluents and meteorological data for the period.
Environmental monitoring is conducted around GE-MO to measure changes in fluoride concentrations and radiation or radioactivity levels that may be attributable to plant operations.
If significant changes in environ concentrations are measured, these changes are correlated with effluent release data to estimate any GE-MO contributions.
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B1-7
NEDO-20969B1 September 1978 Summary O
GE-MO was used only for storage during the reporting period.
No significant amounts of radioactive materials were released in gaseous or liquid effluents.
Effluents to the Atmosphere Released to the atmosphere are summarized in Table A.
Atmospheric dilution factors measured for the period are given in Table B.
No measurable Kr-85 was released during the period.
A total of 2.2 kg of hydrogen fluoride was released during the six-month period.
O O
31-3
NEDO-20969B1 September 1978 O
TABLE A GE-MO RELEASES TO THE ATMOSFHERE
' January through June 1977 HF(a) uCi bbnth Kg Gross Alpha Gross Beta January 0.2 0.6 3.7 February 0.4 0.6 2.0 March 1.0 0.5 1.5 April 0.6 0.8 2.2 May 1.0 1.6 June 0.8 3.0 Six-month Total 2.2 4.3 14.0 (a) Anhydrous HF and Fluorine generating equipment were removed from site in March and April. Monitoring subsequently discontinued.
O v
B1-9
NEDO-20969B1 September 1978 O
TABLE B Maximum Of f-si te Relative Concentrations (sec/m3)
GEMO Main Chimney (times 10~8)977 January-June 1 Sector 6 month Month Average January February March April May June N
52 6.2 5.4 4.8 52 6.9 27 NNE 54 6.6 5.4 5.6 33 6.8 4.8 NE 7.8 10.6 8.8 4.7 4.6 8.6 6.9 ENE 6.5 4.7 6.4 53 7.6 8.9 6.2 E
8.8 19 2 11.2 9.2 3.3 4.7 6.1 ESE 17 6.1 2.6 1.8 3.8 6.3 4.7 g
SE 1.7 2.7 2.8 1.9 1.2 0.4 2.I SSE 1.8 1.9 5.6 19 1.7 0.0 7.8 5
1.1 1.0 13 0.6 0.9 05 3.2 SSW 1.6 1.1 09 0.0 31 2.0 2.8 SW 1.7 0.9 0.6 0.6 2.4 35 23 WSW 1.8 1.0 0.2 0.5 2.5 39 2.5 V
23 0.7 0.4 1.2 31 5.7 2.8 WNW 34 0.9 0.2 4.9 4.5 52 4.6 Nw 5.4 0.4 0.8 92 7.9 6.1 8.3 NNW 5.6 1.8 3.0 8.7 6.7 6.6 7.1 O
31-10
NEDO-20969B1 September 1978 j
ENVIRONMENTAL MONITORING RESULTS The GE-MO environmental monitoring program is conducted in conjunction with a more extensive program for the Dresden Nuclear Power Station.
Results from the combined CE-M0/Dresden environmental monitoring pro-gram important to GE-MO are summarized in Tables C, through L.
The semiannual report for Dresden may be used to obtain additional infor-mation.
The purpose of the GE-MO environmental monitoring program is to verify the adequacy of stack effluent monitoring and to help answer questions concerning possible environmental impact of releases.
l l
Tritium concentrations were raeasured in water from:
1.
Pond approximately 800 meters west of the GE-MO stack.
2.
Corps of Engineers pump basin approximately 2400 meters O
southeast of the GE-M0 stack.
3.
Illinois River at Morris.
4.
Thorsen well.
5.
Grass from approximately 300 meters cast-northeast of the stack.
6.
Soil from the same location as grass.
7.
On-Site Well GE-MO.
These results are summarized in Tables C and G.
The results of the tritium analysis on an adult rabbit indigenous to the GE-M0 site are given in Table G.
First and second quarter analyser, of fluoride strips are recorded in Table F.
None of these analyses indlentes any measureable environmental impact from GE-MO cffluents.
l 0
B1-11
TABLE C SITE MONITORING RESULTS January through June 1977 UNITS JANUARY FEBRUARY MARC 11 APRIL MAY JUNE Grass Fluoride (D-40) ug/g NR NR NR NR 2.2 2.1 Davidson's Milk I-131 pC1/1
<4
<4
<4
<0.5
<0.5
<0.5 Sr-90 pCi/l 311 4!2 3
1 211 111 11 1 Cs-134 pCi/l
<5
<5
<5
<5
<5
<5 Cs-137 pCi/l
<5
<5
<5
<5
<5
<5 Mather Farm Milk 1-131 pC1/1
<4
<4
<4
<0.5
<0.5
<0.5 mvM
, Tritium Analyses
{aw y Water from Pond West
[
of CE-MO (n-35) nCi/1 NR NR 0.3 2 0.1 NR NR 0.3 ! 0.1 @
~
ww 85 D-33 Corps of Eng. Pump Basin nCi/l (a) 0.3 1 0.1 NR
<0.2 NR NR IL River at 11wy 47 nCi/l Quarterly Composite 0.2 0.1 Quarterly Composite
<0.2 Thersen Well nCi/l 0.5 1 0.1 NR NR 0.7 1 0.1 NR NR On-Site Well (CE-MO) nCi/1 NR NR
<0.2 NR NR
<0.2 Grasn Near GE-M0(D-39) nCi/l NR NR (a)
NR NR 1.2 1 0.4 Moisture Content of Soil at 10-15 cm (D-39) nCi/1 NR NR 0.5 1 0.1 NR NR 0.7 1 0.4 NR = Not Required
~
(a) Sample lost in processing.
O O
O
l O
O O
i TABLE C (cont'd)
SITE MONITORING RESULTS l
I January through June 1977 UNITS JANUARY - MARCH APRIL - JUNE SIX-MONTH TOTAL Gamma Exp. calculated GE-MO Contribution Bennitt D-09 mR/ Week 0
0 0
Joliet D-03 0
0 0
4 Clay Prod.
D-15 0
0 0
Coose lake Vilinge D-44 0-0' 0
i Pheasant Trail D-45 0
0 0
i Collins Road D-46 0
0 0
ta SY no e
3?
=
cr w 7
to o C Camma Exposure, All Sources
+t g 9e Measured 15ennit t D-09 1.1 0.5 1.9 1 0.3 3.0 05 i
Joliet D-03 1.1 ! 0.2 1.1 0.1 2.2 i
Clay Prod.
D-15 1.1 ! 0.2 1.0 ! 0.1 2.1 i
Coose Lake Village D-44 1.2 0.1 1.2 1 0.1 2.4 j
Phcasant Trail D-45 1.2 1 0.2 1.1 0.2 2.' 3 Collins Road D-46 1.2 2 0.3 1.7 1 0.3 2.9 i
i i
I i
l
\\
4 i
i 5
1
,%y
-,,-w
~
NEDO-20969B1 September 1978 TABLE D PLUT0NIUM IN AIR PARTICULN.E FILTER COMPOSITES g
January through June 1977 Stations Composited:
Bennitt Clay Products On-Site i Pheasant Trail Collins Road Joliet Morris Coal City Funooka Goose Lake Village Month of Composite 10-4 pCi/m3 January
<0.03 February
<0.02 March
<0.04 April
<0.04 May
<0.02 lll June
<0.07 l
B O
Data reported ac "<" are at the 99% confidence icvel. All other data are at the 95% confidence icvel, all based on counting errors.
B1-14 l
l
I O-b O
l e
TABLE E-I.
MONTHLY AVERAGE GROSS BETA CONCENTRATIONS IN AIR PARTICULATES 4
Collection JANUARY FEBRUARY MARCH APRIL MAY JUNE Site (10-2 pCi/m s (10 2 pCi/m )
(10-2 pCi/m )
(10-2 pCi/m )
(10-2 pCi/m )
'(10-2 pCi/m )
3 3
3 3
3 3
Indicator Stations i
l, D-09 Bennitt 8
2 711
.8 2
26 1 4 53 1 7 45 7
D-15 Clay Products 712 5
1 812 22 1 4 49 6
41 6
i D-18 On-Site 3 7
1 5
1 9
2 22 ! 4 4816 40 1 6 D-45 Pher. dant Trail 812 711 8
2 25 4
51 1 7 37 ! 5 D-46 Collins Road 712 6t1 8
1 22 ! 4 51 ! 6 41 6 pg 3 E' i
a?
~
,y TE g
Background Stations "g
U$
D-03 Joliet 5!2 611 10 1 2 26 1 4 55 1 7 4517 gH 1
D-06 Morris 711 711 9
1 24 1'4
, 5112 45 ! 7 D-08 Coal City 7!2 7
1 10 ! 2 27 4
49 i 6 40 ! 6 D-14 Minooka 812 7
1 812 19 3
5217 4417 D-44 Goose Lake Village 812 611 7
1 25 1 4 5217 43 ! 6 O
e t
r i
j e
- .-6
._y 5
.w.
p g
n
-y-e g
'm y 4 c
~
.ar.we-rM---:-M wws
TABLE E-II.
CROSS ALPIIA IN AIR PARTICULATES Collection JANUARY FEBRUARY MARCil APRIL MAY JUNE Site (10-3 pC1/m )
(10-3 pC1/m )_
(10-3 pCi/m )
(10-3 pCi/m )
(10-3 pCi/m )
(10-3 pCi/m )_
3 3
3 3
3 3
Indicator Stations D-09 Bennitt
<5
<5
<5 1!1
< 5
<5 D-15 Clay Prooucts
<5
<5
<5 221
< 5
<5 D-18 On-Site 3
<5
<5
<5 2
1
< 5
<5 D-45 Pheasant Trail
<5
<5
<5 111
< 5
<5 D-46 Collins Road
<5
<5
<5 2
1
< 5
<5-Ez
% Ei Background Stations l,4 m
48 5
D-03 Joliet
<5
<5
<5 2
1
< 5
<5 yg D- 06 Morris
<5
<'5
<5 2
1
< 5
<5 gm D-08 Coal City
<5
<5
<5 211
< 5
<5 m
D-14 Minooka
<5
<5
<5 211
< 5
<5 D-44 Goose Lake
<5
<5
<5 1 1 1-
< 5
<5 Village O
4 O
O O
NEDO-20969B1 September 1978 IABLE F O
ANALYSES OF FLUORIDE ABSORBENT STRIPS pgF"/dm / day (average) 2 LOCATION First Quarter Second Quarter D-02 Elwood
.41 1.05 0.7 0.2 D-03 Joliet Brandon Road 1.90'
.20 3.1 1 0.6 D-04 Wilmington
.15
.02 0.6 1 0.1 D-06 Morris
.14
.02 0.6 1 0.1 D-07 Lisbon
.17 1.02 0.3 1 0.1 D-08 Coal City
.19 !.02 0.5 1 0.2 D-11 Channahon.
.22 2.02 0.7 0.4 D-16 On-Site.1
.14
.02 0.3 0.1 D-17 On-Site 2
.08
.01 0.3 1 0.1 D-18 On-Site 3
. 09
.01 0.3 1 0.1 0.4 1 0.1 D-40 300 Meters E. of MFRP Plant.93 1.09 D-40 West of MFRP Plcnt at Site Boundary
.32
.03 2.0 2 0.5 D-40 On-Site
.89 t.09 1.1 0.2 O
O B1-17 r
.-,r,
.-v
NEDO-2096931 Septembsr 1978 TABLE G MISCELLANEOUS ANALYSES D-40 RABBIT - CEMO AREA Collection Blood Tritium Thyroid I-131 Muscle Cs-137 Bone Sr-90 Date pC1/ml pCi/ animal pCi/gm pCi/gm 04/23/77 22 : 2 (a)
(a)
(a)
D-39 TRITIUM IN SOIL MOISTURE (Simulator Area)
Collection Tritium Concentration Date pCi/ml soil moisture 03/05/77
.52 :.11 06/12/77
.73 1.35 D-39 TRITIUM IN GRASS Collection pC1/ml Date (loose Water) 03/05/77 Insufficient water for analysis lll 06/12/77 1.2 2 0.4 D-3$
POND WEST OF MFRP Collection Tritium Date pCi/l 03/05/77 250 2 100 06/04/77 300 t 100 D-33 GOOSE LAKE, CORP. OF ENGINEERS PUMPING STATION Collection pCi/l Date Gross Beta Tritium 01/08/77 Insufficient sample for analysis 02/05/77 4 : 2 280 : 90 04/02/77 4: 2
<200 (a) Insufficient sample for analysis.
B1-18
~
NED0-20969B1 Saptember 1978 TABLE H
./~'i
(-)
GROSS ALPHA AND GROSS BETA IN SURFACE WATER SAMPLES Collection Collection Gross a Cross B Site Date fpC1/1)
(pC1/1)
Sanitary Lagoon 01/08/77
<2.0 18 3
(D-54) 02/05/77
<1.1 10 1 4 03/05/77
<0.6 7
2 04/02/77
<1.0 3!2 05/14/77
<0.7 9
2 06/04/77
<0.7
'13 2 3 Evaporation Pond 01/01/77 (a)
(a)
(D-55) 02/05/77 (a)
(a) 03/12/77
<1.0 8
2 04/02/77
<1.0 11 ! 2 05/14/77
<0.7 612 06/04/77 111 10 ! 2 TABLE I GROSS BETA AND TRITIUM IN WELL WATER SAMPLES Collection Collection pCi/1 Site Date Gross B Tritium D-38 MFRP Well 03./05/77 13 ! 2
<200 06/04/77 25 3
<200 Data reported as "<" are at the 99% confidence level. All other data are at the 95% confidence level, all based on counting errors.
I)
(a) Sample not available due to excavation interference with pond.
V B1-19
NEDO-2096931 September 1978 TABLE J NITRATES IN SURFACE WATER AND WELL WATER SAMPLES Nitrates Collection (as nitrogen)
Collection Site Date ppm Goose Lake Corporation 01/08/77
<1 of Engineering (D-33) 02/05/77
<1 03/05/77 9
04/02/77
<1 05/14/77 18 06/04/77
<1 6" Law Well (D-56) 01/08/77
<1 02/05/77 55 03/05/77 16 04/02/77
<1 05/14/77
<1 g
06/04/77 22 W
G.E. Surface Water (D-57) 12/31/76 9
02/05/77 9
03/05/77 11 04/02/77 158 05/07/77 480 06/04/77 18 O
B1-20 l
1
NEDO-20969B1 September 1978 TABLE K FLUORIDE IN VEGETATION SAMPLES Collection Collection ug/g Site Date Annuals (l)
Perennials (2)
Evergreens On-Site GE-M0 01/08/77
- 330 (pg/g)
(Area 1) 05/28/77 1.7 6.1 4.9' 06/12/77 3.1 1.8 4.5 Dresden Locks -
01/08/77
- 290 (ug/g)
Northwest 05/28/77 2.2 2.4 2.7 (Area 2) 06/12/77 1.6 2.0 1.6 West Boundary 01/08/77
- 300 (vg/g)
(Acca 3) 05/28/77 2.0 1.6 1.3 06/12/77 0.9 2.2 1.4 East E:
.tary 01/08/77
- 170.(pg/g)
(Area 4) 05/28/77 3.1 8.9 2.2 06/12/77 2.9 3.1 2.7 (1) Grass (2) Deciduous leaves Combined sample of grass and evergreens.
Believed to be contaminated in the Laboratory.
B1-21
.~
NEDO-20969B1 September 1978 TABLE L RADIONUCL1DE CONCENTRATIONS IN PRECIP1TATION January - June 1977 Collection Collection Gross Eeta Gross Beta H-3 as Water Site Date (pCi/1)
(pCi/m )
(pCi/1) 2 On-Site 2 Jan.
39 1 4 517 1 53
<360 (a)
(D-17)
Feb.
53 1 6 420 1 50 260 t 90 lbr.
87 1 9 2800 300+
520 t 110 Apr.
7117 2800 2300+
380 t 80 May 290 130 1600 1200+
< 500(a)
June 7217 2100 2200+
370 1 100 Davidson Farm Jan.
40 : 6 318 48
<360 (a)
(D-30)
Feb.
4525 480 2 50 250 ! 90 Mar.
49 2 5 2600 1300+
780 ! 110 Apr.
96 110 3400 1300+
550 2 90 May 200 220 1100 1100+
< 200 June 65 ! 7 2900 2300+
270 1 100 Brandon Lock Jan.
40 1 7 318 ! 56
<360 (a) llh (D-32)
Feb.
6316 500 2 50 210 1 130 Mar.
100 110 2700 2300+
460 2 110 Apr.
300 130 5500 1600&
430 : 90 May 180 220 960 2100 530 1 350(a)
Jure 100 110 2900 1300+
260 1 100 lbther Far Jan.
21 1 5 167 1 40
<360 (a)
(D-53)
Feb.
48 1 6 380 1 50
<200 Mar.
50 5
1900 2200+
610 : 110 Apr.
310 130 4900 2500+
440 : 90 May 100 110 540 2 50 230 100 Junc 6817 2000 2200+
260 1 100
+ Unusual reading Data reported as "<" are at the 99% confidence level.
All other data are at tbc 95*4 confidence j evel, all based on counting errors.
(a) Insufficient sample for more sensitive analysis.
Samples were direct counted.
31-22 l
j
NEDO-20969B1 September 1978 O
GENERAL ELEC.TRIC COMPANY MORRIS OPERATION RADIOACTIVE WASTE AND ENVIRONMENTAL MONITORING JULY THROUGH DECEMBER 1977 O
O B1-23/B1-24
NEDO-20969B1 September 1978 TABLE OF CONTENTS PAGE Introduction...................................................
1 Summary........................................................
2 Effluents to the Atmosphere....................................
2 Tablo A G E-M0 Re l e a s e s t o' t h e A t mo s phe r e.................
2 Table B Maximum Off-Site Relative Concentration (X/Q)*
CE-MO Main Chimney...............................
3 Environmental Monitoring Results...............................
4 Tabic C Site Monitoring Results..........................
5 Table D Plutonium in Air Particulate Filter Composites...
7 Table E 1.
Cross Beta in Air Particulates..............
8 II.
Gross Alpha in Air Particulates.............
9 Table F Quarterly Fluoride Analysis of Fallout Strip Samples..........................................
10 Table C Mincellaneous Tritium Analyses...................
11 Table il Gross Alpha and Cross Beta in Surface Water Samp1cs..........................................
12 Table I Cross Beta and itTO in Well Water Samples.........
12 Table J Nitrates in Surface and Well Water Samples.......
13 Table K Fluoride in Vegetation Samp1cs...................
14 Tobic L Radionuclides in Precipitation Sampics...........
15 BI-25/B1-26 y
e.-.w s-w w
,wy,.
~
yvpt w-ey-+
y y--
eyr gy y, - -.g 9--.-y-
--re v
-=yre w
w-yy w
,v.
,-r-ce-'
NEDO-20969B1 September 1978 Introduction The General Electric Morris Operation (GE-MO) is located approxinately twelve miles southwest of Joliet, Illinois, immediately south of and adjacent to the Dresden Nuclear Power Station.
The facility is used to store spent nuclear fuel, and is designed to contain all radioactive liquids and essentially all of the airborne particulate radioactivity in its effluents.
Traces of gaseous radionuclides, mainly Kr-85, and tritium may be released to the atmosphere.
Releases to the atmosphere i
via the 91 meter stack are estimated by analyses of continuously col-Iceted composite samples of particulate matter (filter). The monthly average atmospheric dispersion factor (X/Q) is calculated using on-site meteorological data for the period. The gamma radiation doses from GE-MO releases and Dresden plus GE-M0 combined are calculated based on iso-topic analyses of effluenta and meteorological data for the period.
Environmental monitoring is conducted around GE-M0 to measure changes in radiation or radioactivity levels that may be attributable to plant ope ra tions.
If significant changes in environ concentrations are measured, these changes are correlated with effluent release data to estimate any GE-MO contributions.
O O
B1-27
NEDO-20969B1 September 1978 Summary CE-MO was used only for storage during the reporting period.
No significant amounts of radioactive materials were released in gaseous or liquid effluents.
Effluents to the Atmosphere Released to the atmosphere are summarized in Table A.
Atmospheric dilution factors measured for the period are given in Table B.
No measurable Kr-85 was released during the period.
TABLE A CE-MO RELEASES TO THE ATMOSPHERE July through December 1977 uCi Month Gross Alpha Cross Beta July 0.8 3.0 August 1.4 3.5 September 0.8 3.1 October 2.0 4.8 November 0.9 2.6 December 0.5 2.8 Six-month Total 6.4 19.8 O
B1-28
_------____---_--_---__-___---__-_____--_-__-__--__a
NEDO-20969B1 September 1978 O
TABLE B Maximum Off-Site Relative Concentrations (sec/m3)
GEMO Main Chimney July-December 1977 (times 10-8)
Sector 6 month Month
~
Averag July August September October November December N
6.4 6.6 7.7 5.6 73 51 5.6 NNE 74 9.4 93 4.0 77 4.2 9.6 NE 6.7 14.8 92 4.2 2.7 52 4.2 ENE 8.1 12.6 7.6 7.4 4.4 69 98 E
7.4 52 79 6.7 53 9.9 22.6 ESE 2.6 0.8 25 2.6 2.4 2.6 6.9 SE 1.6 0.8 2.6 30 1.8 1.4 25 SSE 1.5 0.7 2.2 1.3 2.8 1.7 4.5 5
2.0 1.4 2.0 33 3.2 2.1 4.4 SSW 1.4 1.6 1.5 1.4 13 2.6 03 SW 1.9 1.7 1.1 34 1.2 6.0 1.2 vsw 1.7 1.0 09 4.3 2.1 13 1.3 v
2.7 0.8 30 4.6 4.3 09 4.4 WNW 37 6.0 3.4 36 3.4 3.6 2.2 Nw 4.4 3.9 3.9 4.6 2.9 5.8 57 NNW 6.4 52 39 93 4.3 8.7 8.5 8
B1-29
NEDO-20969B1 September 1978 O
ENVIRONMENTAL MONITORING RESULTS The GE-MO environmental monitoring progra: is conducted in conjunction with a more extensive program for the Dresden Nuclear Power Station.
Results from the combined CE-M0/Dresden environmental monitoring pro-gram important to GE-MO are su=carized in Tables C, through L.
The semiannual report for Dresden may be used to obtain additional infor-mation.
The purpose of the GE-MO environ = ental monitoring program is to verify the adequacy of stack effluent monitoring and to help answer questions concerning possible environmental impact of releases.
Tritium concentrations were measured in water from:
1.
Pond approximately 800 meters west of the GE-MO stach.
2.
Corps of Engineers pump basin approximately 2400 meters southeast of the GE-MO stack.
3.
Illinois River at Morris.
4.
Thorsen well.
5.
Grass from approximately 300 meters east-northeast of the stack.
6.
Soil from the same location as grass.
7.
On-Site Well CE-MO.
l l
Ihese results are summarized in Tables C and C.
The results of the tritium analysis on an adult rabbit indigenous to the CE-M0 site are given in Table G.
Third and fourth quarter analyses of fluoride strips are recorded in Table T.
None of these analyses indicates any ceasureable environmental impact from GE-50 effluents.
l l
llk B1-30 l
l l
l
O O
O TABLE C SITE MONITORING RESULTS July through December 1977 UNITS JULY AUGUST SEPTEMBER OCTOBER NOVDIBER DECDIRER Graes 1'luoride (D-40) pgF~/dm / day NR NR 1.3 ! 0.33 NR
. NR 0.57 0.33 2
D.tvidson's Milk I-131 pCi/1
<0.5
<0.5
<0.5 21.0 2.2 0.76 ! 0.32
<0.5
.ir-90 pCi/1
<2 (a) 2!2 2
1 NR NR C.4-134 pCi/1
<5
<5
<5
<5 NR NR Cs-137 pCi/1
<5 (a)
<5
<5 NR NR Mather Farn Milk cn 1-131 pC1/1
<0.5
<0.5
<0.5 10.5 1 1.2
<0.5
<0.5
~g8 w
a Tritium Analyses gg Uater from Pond West
- ne Hh of GE-MO (D-35) nCi/1 NR NR 0.3 0.1 NR NR NR 5"
D-33 Corps of Eng. Pump ta.In nCi/l NR
<200 NR 0.210.1 NR NR IL River at ilwy 47 nCi/l NR NR 0.210.1 NR NR NR Thorsen Well nCi/1 0.4 0.2 NR NR 0.310.1 NR NR Cn-Site Well (GE-MO) nCi/1 NR NR
<0.2 NR NR NR Grac,s Near GE-M0 (D-39) nci/ml 1.5 ! 0.4 5.1 ! 0.9 1.5 1 0.5 1.4 ! 0.5 NR NR 1
Moisture Content of Soil it 10-15 cm (D-39) nCi/ml NR UR 0.7 1 0.4 NR NR NR (a) Sample lost in processing.
NR = not required i
TABLE C cont'd SITE MONITORING RESULTS July throur,h December 1977 UNITS JULY - SEPTE!!BER OCTOBER - DECEMBER S X-MONTH TOTAL C.rra Exp. calculated GE-MO Centribution enni.tt D-09 mR 0
0 0
Jeliet D-03 mR 0
0 0
Clay Prod.
D-15 mR 0
0 0
Geoce Lake Village D-l.4 mR 0
0 0
.':n anant Trail D-45 mR 0
0 0
Ce i li u r: Road D-46 mR 0
0 0
<n4M no ho4 m
Ca: ma D:posure, All Sources ao M :ured
'a t smit t D-09 mR 16.9 1 2.6 26.0 1 2.6 42.9 1 3.7 e
Jeliet D-03 mR 14.3 1 1.3 23.4 ! 2.6 37.7 1 2.9 55 Clny Prod.
D-15 mR 14.3 1 1.3 23.413.9 37.7 1 4.1 5"
t;ou u-Lake Villa;,e D-44 nR 15.6 1 2.6 23.4 1 3.9 39.0 1 4.7 Pi."a na a t trail D-45 mR 13.0 2 3.9 24.7 1 2.6 37.7 1 4.7 t.ollins Road D-46 mR 16.9 1 2.6 27.3 2 3.9 44.2 ! 4.7 9
O O
e
NEDO-20969B1 September 1978 d(~N TABLE D PLUTONILDI IN AIR PARITUCLATE FILTER COMPOSITES July through October 1977 Stations Composited:
Bennitt Clay Products On-Site 3 Pheasant Trail Collins Road Joliet Morris Coal City Minooka Coose Lake Village Month of Composite lo_4 pCi/m3 July 40 14
()
August
<0.05 September 0.06 0.06 October 0.03!0.01 O
me,. m a me..<- m m tae m ccmae-1~c1.
^u ets - dete m et t he 9 ~)," ConfidenCC l eVL I,
.".11 bn 3 Od On COMCt In',( UrrOrS.
B1-33
TABLE E-l MONTil',Y AVERACE CROSS BETA CONCENTRATIONS IN AIR PARTICULATES Collection JULY AUCUST SEPTEMBER OCTOBER NOVEMBER DECEMBER-Site (10-2 pCL/m )
(10-2 pCL/m )
(10-2 pCi/m )
(10-2 pCL/m )
(10-2 pCi/m ),
(10-2 pCi/n )
3 3
3 3
3 3
Indicator Stations 1909 Bennitt 27 1 4 27 ! 4 14 1 2 39 1 22 1012 1112 D-15 Clay Products 31 1 5 2324 13 1 3 39 1 6 NR 13 1 2 D-18 on-Site 3 37 1 5 2814 14 1 2 42 1 6 14 ! 2 1012 D-45 Pheasant Trail 42 1 6 24-1 4 2014 (a) 912 91'l D-46 Collins Road 27 1 5 24 1 4 13 2-39 1 6 13 2 2
.8 g.L 7
Background Stations IS D-03 Joliet 31 1 5 30 1 4 16 1 3
. 40 1 6 1512 NR as U
~
2925 21 2 3 12 i 2 39 ! 5 17 1 3 Nlt D-06 Morris 1913 21 2 3 1312 34 1 5 17 1 3 NR D-08 Coal City 2915 2314 812 27 1 4 19 1 3 NR D-14 Minooka 29 1 5 2314 2313 53 1 6 18 ! 3 NR D-44 Goose 1.ake Village (a) Sample not available; power out at site.
NR=Not required i
f 9
9 e
O O
O
~
TABLE E-Il CROSS ALPHA IN AIR PARTICULATES Co11cetion JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Site (10-3 pCi/m )
(10-3 pCi/m )
(10-3 pCi/m )
(10-3 pCi/m )
(10-3 pCi/m )
(10-3 pCi/m )
3 3
3 3
3 3
Indicator Stations D-09 Bennitt
<5
<5
<5
<5
<5 NR D-15 Clay Products
<5
<5
<5
<5 NR NR D-18 On-Site 3
<5
<5
<5
<S
<5 NR D-45 Pheasant Trail
<5
<5
<5
<5
<5 NR D-46 Collins Road
<5
<5
<5
<5
<5 NR.
Ez 3E Bac.eground Stations gg>
w ow i
bl 0-03 Joliet
<5
<5
<5
<5
<5 NR
$ 6$
D-06 Morris
<5
<5
<5
<5
<5 NR r4 D-03 Coal City
<5
<5
<5
<5
<5 NR 230$
D-14 Mineoka
<5
<5
<5
<5
<5 NR 1944 Gocac I;ake
<5
<S
<5
<5
<5 NR Village 1
NR = not required
io NEDO-20969B1 Septembzr 1978 TABLE F ANALYSES OF FLUORIDE ABSORBENT STRIPS ugF /dm2/ day Location Third Quarter Fourth Quarter D-02 Elwood 0.6110.06 0.3820.05 D-03 Joliet Brandon Road 1.2 20.5 1.10!0.36 D-04 Wilmington 0.51:0.05 0.23:0.02 D-06 Morris 0.4120.04 0.27!O.03 D-07 Lisbon 0.45 0.19 0.2020.02 D-08 Cosi City 0.7320.22 0.2620.03 D-11 Channahon 0.55 0.06 0.30 0.03 D-16 On-Site 1 0.19!0.02 0.1310.01 D-17 On-Site 2 0.4310.04 0.1110.01 D-18 On-Site 3 0.1520.04 0.4220.04 D-40 300 Meters E. of MFRP Plant 0.90 L'.09 0.7320.07 D-40 West of MFRP Plant at Site 2.0 10.3 0.90!0.09 Boundary D-40 On-Site 1.0 !0.6 0.09:0.01 0
I O
B1-36 i
I i
NEDO-20969B1 Septembsr 1978 TABLE G O
MISCELLANEOUS ANALYSES D-42 RABBIT - GEMO AREA Collection Blood Tritium Thyroid 1-131 Muscle Cs-137 Bone Sr-90 Date pCi/nd pCi/ animal pCi/gm pCi/gm 10/21/77 0.8 0.7 16 ! 5
<0.1 0.3 ! 0.1 D-39 TRITIUM IN SOIL MOISTURE (Simulator Area)
Collection Tritium Concentration Date pCi/ml soil moisture 09/03/77 0.7 ! 0.4 D-39 TRITIUM IN GRASS Co11cetion pCi/ml Date (loose Water) 07/09/77 1.5 2 0.4 08/06/77 5.1 0.9 09/03/77 1.5 0.5 10/02/77 1.4 ! 0,5 D-35 POND WEST OF MFRP Collection Tritium Date pCi/1 09/03/77 330 120 D-33 C00SE LAKE. CORP. OF ENGINEERS PUMPING STATION Collection pCi/1 Date Gross Beta Tritium 07/23/77
<5
<200 10/02/77 8!2 200 ! 100 O
B1-37
SEDO-2096931 Septenber 1979 TABLE H GROSS ALPRA AND CEOSS EETA IS Si;RFACE ilATER SAMPLES Collec:1on Collec: ion Cross a Grcss 3 Site Date (pC1/1)
(pCi/1)
Sanitary Lagoon 07/09/77
<1,0 13 : 2
(:>-54) 08/06/77
<1.0 13 : 2 09/03/77
<1.0 11 : 2 10/02/77
<5 11 : 4 11/05/77 (6
12 : 4 12/03/77
<2 10 : 2 Evaporation Pond 07/09/77
<0.7 S: 2 (p-33) 05/06/77 2: 1 S: 2, 09/03/77
<1.0 6: 2 10/02/77
<3 13 : 4 11/05/77 (5
10 : 4 12/03/77 3
2 12 : 2 h
TABLE 1 G 'OSS SETA AND TRIT!D IN 1 ELL GATER S.O.PLES Collection Collection pCi/1 Si:e Date Cross S Trities D-38 09/03/77 19 : 2
<203 c i g o t t e,.
- "C are., : t!. 99L confidtnce leve:.
A1 c:5:
ar 0 '. :'a SE' t e n f !? : ? It'V01, 2,11 '?ted On C,
c r r,. r r,
31-35
c NEDO-20969B1 September 1978
' => -
TABLE J C:)
NITRATES IN SURFACE WATER 'AND WELL UATER SAMPLES Nitrates Collection (as nitrogen)
Collection Site Date ppm Coose Lake Corporation 07/23/77 4
of Engineering (D-33) 08/06/77
<1 09/10/77 9
6" Law Ucil (D-56) 07/09/77
<1 08/06/77
<1 09/03/77
<1 10/02/77
<1 C.E. Surface Water (D-57) 07/09/77 13 08/06/77 18 09/03/77 123 10/02/77 42 O
B1-39
e w
.=M.a J
A S--
+--3
-+4=-J J
4 4
-4
---we, sit:
-.. +
September 1978
- TABLE K, i
e:
FLUORIDE IN VEGETATION SAMPLES c
h Collection
' Collection ug/g Site Date Annuals (l)
Perennials (2)
Evergreens.
On-Site GE-MO 07/09/77 221 221 1!1 (Area 1) 08/12/77 4
1 321 321 09/03/77 221 2
1 1
1 10/02/77 4
1 121 121 Dresden Locks - 07/09/77 2
1 2!1 221 Northwest 08/12/77 421 321 321 (Area 2) 09/03/77 121 221 2
1.
10/02/77 621 1!1 111 Uest Eoundary 07/09/77 321 1: 1 321 (Arca 3) 08/12/77 311 2: 1 221 1
09/03/77 121 321 1: 1 i
10/02/77 5: 1 221 1!1 East Ecundary 07/09/77 221 111 121 (Area 4) 08/12/77 211 221 3: 1 09/03/77 221 12 : 1 2: 1 10/02/77 10 2 1 121 221 l
I (1) cr w g
(2)
D::ciduoan 1 caves B1-40 l
_ _,,. __ _ _ _._ _ _ _ l
NEDO-20969B1 September 1978 TABLE L RADIONUCLIDE CONCENTRATIONS IN PRECIPITATION July - Decceber 1977 Collection Colle~ction Cross Beta Cross Beta H-3 as Water Site Date (pCi/1)
(pCi/m )
(pC1/1).
2 1
On-Site 2 July 200 ! 20 5300 t 500 400 ! 120 (D-17)
Aug.
26 1 3 5300 500 320 1.
30 j
Sept.
68 1 7 9000 900 350 1 100
(
PRECIPITATION PROGRAM DISCONTINUED l
i I
Davidson Farm July 130' 2 13 3400 1 300 280 100 (D-30)
Aug.
19 2 2 3900 400 220 ! 50 Sept.
47 5
7500 1 800 360 100 l
l PRECIPITATION PROGRAM DISCONTINUED Erandon Lock July 230 1 23 6100 600 290 100 (D-32)
Aug.
16 1 2 3400 400 130 ! 50
/~'i Sept.
37 4
6000 600 200 100 V
PRECIPITATION PROGRAM DISCONTINUED Mather Farm July 83 ! 8 2200 200 180 1 100 (D-53)
Aug.
40 1 4 4200 400 130 1 50 Sept.
60 t 6 7900 ! 800 220 100 PRECIPITATION PROGRAM DISCONTINUED A
N.
Data reported as "<" are at the 99% confidene.c 1 cycl.
All other data are at the 95% confidence levci, all haned on counting, errors.
B1-41/B1-42