Text

Revision B4, Operating Experience Rept - Irradiated Fuel Storage at Morris Operation,Jan 1972 - Dec 1979
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Issue date:	09/30/1980
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NEDO-20969B4 Saptemb3r 1980 Operating Experience Report Irradiated Fuel Storage at Morris Operation REVISION INDEX for Revision B4 September 1980 Incorporates changes and Appendix 33, environmental monitoring report for 1979.

Pages to be Removed New Pages to be Inserted Chapter Page Number Date Chapter Page Number Date Cover Cover Title Page Title Page 11 11 9/80 iii 1/79 iii 9/80 iv 4/79 iv 9/80 v/vi 1/79 v

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NEDO-209698 CLASSI Operating Experience Report IRRADIATED FUEL STORAGE at MORRIS

-OPERATION January 1972 to December 1979 K. J. Eger SPENT FUEL SERVICES OPERATION NUCLEAR FUEL ANO S RVIC S 08V1310N

ENERAL E LECT 91C COMPANY GEN ER AL $ ELECTRIC

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NEDO-20969B4 September 1980 3

NOTICE AND DISCLALM

'i Thia repor: :xa prepared by General Mectric Ccmpany for i:a use and for use by the U.S. Nuclear Ecgulatcry Ccmission (NRC) in relation to the Morris Cperaticn fuel storage facility. General Electric ass:ctes no responsibility fcr liability or damge which may re_sult frcm any other use of the infomation disclosed in this repor:.

The infomaticn ecntained in chia report is believed to be an accu-rate and : rue representa:icn of the facts kncun, ch: ined, or provided

o General Electric at :he :i.~e chia repor: uas prepared. General Elec:ric Ccepany and the indiv~~ dual ecntributors to chia repor: mke no e press or i.mlied xrranty of ace:a'acy, ccnpleteneas, or usefut-neas of the infomation ocntained in this report with respect to any change of fact cr lau se: fcrth therein, whether mierial or other-uice; and General Electric Cct pany makes no ucrranty or representation, e: press or implied, vi:h respect to the accuracy, ccepteteness, or usefulness of the infomaticn ecntained in this repor, other than for i:a use and fcr use by the SEC in reta ~~cn to the Morris Operation, or

ha: the use of any infczn: ~;cn diactosed in this report my at infringe priva ety ctmed r~'ghts including patent rights.

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l FUEL STORAGE BASIN AREAS AT MORRIS OPERATION: V!EW ACROSS THE TWO FUEL STORAGE BASaNS AT MCRRIS OPERATICN. WITH THE CASK RECEIVING AREA IN THE BACKGRCUNO $L:GHTED AREA). IRRADIATED FUEL lN THE FOREGRCUND IS STCAED IN STAIN-i LESS STEEL BASKET ASSEMBUES. WHICH ARE LOCKED INTO A SUP ACRT GRID CN THE F'.CCR OF THE BASIN. WATER OEPTH tS ASCUT 14 FEET TO THE TCPS CF THE FUEL 9 UNCLES. WITH A TOTAL CEPTH CF ABOUT 28 FEFT P00R BRIGINAl.

NEDO-30969B4 September 1980 3,

OPERATING EXPEHIENCE-IRRADIATED FUEL STORAGE MORRIS OPERATION REVISION

SUMMARY

Revision & Amendment Date Summary NEDO 20969B SU8 Reissue and update - Replaced issue dated 8n5 NEDO 20969B1 9n8 incorporates errata and Appendix B1, environmental monitoring report for 1977 NEDO-2096982 1/79 Update to incorporate 1978 data NEDO 2096983 4/79 incorporates Appendix B2, environmental monitoring report for 1978 NEDO-2096984 9/80 Incorporates changes and Appendix B3, environmental monitoring feport for 1979 l

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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 infor-mation: "E" indicates editorial changes or corrections.

Document Number Key:

NED0 2096981 i

Revision Revision Prefix Ceial Series Amendment

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NEDO-20969B4 September 1980 TABLE OF CONTENTS E3%S 1.

INTRODUCTION AND SLMfARY 1-1

1.1 Purpose and Scope

1-1 1.2 The Morris Operation 1-1 1.3 Summary of Operations 1-2 2.

IRRADIATED FUEL RECEIPT AND STORAGE 2-1 2.1 Principal Facilities and Activities 2-1 2.2 Irradiated Fuel Receipt 2-1 2.3 Storage Facilities 2-6 3.

SUPPORT SYSTEMS 3-1 3.1 Principal Facilities and Activities 3-1 3.2 Basin Water Cooling System 3-1 3.3 Basin Water Cleanup System 3-5 3.4 Ventilation System 3-12 3.5 Waste Water Management 3-15 3.6 Solid Waste Management 3-20 4.

RADIOLOGICAL SAFETY 4-1 4.1 Routine Activities Involving Exposures 4-1 4.2 Current Sources 4-1 4.3 External Exposures 4-2 4.4 Internal Exposure 4-3

,.5 "As Low as Reasonably Achievable" 4-5 4

5.

ENVIRONMENTAL LTACT 5-1 5.1 Introduction 5-1 5.2 Morris Operation Effluents and Containment 5-1 5.3 Environmental Monitoring 5-2 x

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NEDO-2096984 S:ptember 1980 4

TABLE OF CONTENTS (Continued)

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Page APPENDICES A.

ENVIRONMENTAL MONITORING REPORT-1974 A-1 B.

ENVIRONMENTAL MONITORING REPORT-1976 B-1 B-1. ENVIRONMENTAL MONITORING REPORT-1977 B1-1 h

l B-2. ENVIRONMENTAL MONITORING REPORT-1978 B2-1 B-3. ENVIRONMENTAL MONITORING REPORT-1979 B3-1 s.

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I NEDO-20969B4 September 1980 LIST OF TABLES Table Title h

2-1 Fuel Receipts From January 1972 2-2 2-2 Summary of Cask Coolant Activity 2-6 2-3 Suzanary of Subordinate Outages 2-12 3-1 Ionic Impurities in Basin Water 3-11 3-2 Average Concentrations of Radioactivity in Air in Work Areas at Morris Operation 3-12 3-3 Summary of Releases of Radioactivity at Morris Operation via the Main Stack 3-13 3-4 History of LAW Vault Usage 3-16 3-5 Hiscory of LAW Vault Centents 3-17 3-6 History of Cladding Vault Radioactive Material Concentration 3-18 3-7 History of Cladding Vault Usage 3-13 3-8 Recent Vault Leak Detection Experience 3-19 3-9 Shipment of Solid (Dry) Radioactive Waste From Morris Operation 3 4-1 Personnel Exposures at Morris Operation by Job Category 4-4 4-2 Summary of Annual Whole Body Counting Results for.% rris Operation Personnel 4-4 4-3 Results of Specific Exposure Reduction Activities 4-6 i

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NEDO-2096984 September 1980 LIST OF ILLUSTRATIONS Figure Title Page 2-1 IF-300 Irradiated Fuel Shipping dask 2-3 2-2 History of Fuel Receipts at Morris Operation 2-4 2-3 History of the Basin Expansion Cate Leak Rate 2-8 2-4 Morris Fuel Storage System 2-10 3-1 History of Basin Water Temperature at Morris Operation 3-2 3-2 History of the Heat Generated by Fuel Stored at Morris Operation 3-4 3-3 History of Cooler Exposure Rates 3-4 3-4 History of Morris Operation Basin Water Activity 3-6 3-5 Tritiun Activity 3-8 3-6 Chemical Contaminants on the Morris Fuel Storage Basin Waeer 3-10 4-1 Work and Exposure Experience at Morris Operation 4-3 4

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NEDO-20969B4 September 1980 1.

INTRODUCTION AND

SUMMARY

1.1 PURPOSE AND SCOPE General Electric Company owns and operates the Morris Operation, a facility near !beris, Illinois, for the storage of irradiated nuclear fuel from light water reactors. The Morris Operation is a functional component of General Electric's Nuclear Fuels and Services Division (NFSD), with headquarters at San Jose, California.

This report contains a discussion of operating experience at Morris Operation for the period between January 1972 and the date shown on the cover and title page of this issue. This report will normally be revised annually by issuing E

replacement or new pages to incorporate operating experiences from the preceding year.

1.2 THE MORRIS OPERATION The fuel storage facility at Morris Operation includes water-filled basins equipped with cranes, a water cleanup system, waste management systems, and other provisions required to receive irradiated fuel and store it under water for an interim period, until final disposition.1-1 The fuel storage facility is designed to protect the integrity of the fuel rods under all operating conditions and during seismic or meteorological events.

Special provisions can be made for storage of damaged or leaking fuel. Security measures are in effect to protect stored fuel as required by Federal regulations.

l Detailed descriptions of the facility and fuel storage operations are contained in General Electric publication NEDO-21326C, Consolidated Safety Analysis l

Report for Morris Cperation. ~A I

l-1 Statement by the President of the United States on Nuclear Power Policy, Ap ril, 19 77.

1-2 Also, NEDO-21326, revisions A through A4, which are consolidated by

!ED0-21326C.

1-1

NEDO-2096984 September 1980 1.3

SUMMARY

OF OPERATIONS

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Since 1972, more than 1000 bundles of irradiated fuel from BWR and PWR power plants have been received and stored at the Morris Operation facility. E f fe c-tive control of radioactive material in the basin water and other factors, such as water temperature, cask contamination, and airborne radioactivity, as well as safe and efficient methods of cask and fuel handling, have been demonstrated.

There has been no appreciable fuel leakage as determined by measurement of radioactivity in the basin water. Fuel shipments by truck and rail have been ecmpleted safely and ef ficiently. These years of operations have resulted in no significant environmental 1::ipact.

Experience in storage of irradiated nuclear fuel from light water reactors, both in the United States and abroad, has demonstrated that this is a technically unconplicated and passive operation. There are no forces involved in fuel stor-age at !beris Operation with the potential for causing an energy release large enough to disperse the fuel in a form that could be carried, in any biologically significant quantity, to an off-site location to pose a threat to public health

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1-3 Boiling Water Reactor (BWR) and Pressurized Water Reactor (FWR), are the two principal for=s of Light Water Reactors (LWR).

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IRRADIATED FUEL RECEIPT AND STORACE 2.1 PRINCIPAL FACILITIES AND ACTIVITIES Fuel receipt and storage operations constitute the principal activities at Morris Operation. The facilities directly involved in fuel receipt and stor-age are the concrete, stainless-steel-lined basins; cranes and lifting equip-stainless-steel fuel storage baskets and mounting grid, and the fuel ment; shipping casks. Activities include cask receipt, with associated monitoring and flushing operations; cask unloading, and; movement of fuel baskets to storage positions.

2.2 IRRADIATED FUEL RECEIPT The first fuel for storage at Morris Operation was received in January 1972.

Fuel has been received every year since then, with the largest quantity (512 fuel bundics) received in 1976. The first shipments were made in IF-100 and IF-200 shipping casks from Connecticut Yankee and San Onofre nuclear power plants.

Beginning in 1975, the NFS-4 casks were used to ship fuel from Point Beach and San Onofre. The IF-300 casks (Figure 2-1) were used during 1975-1977 to ship fuel from Dresden reactors to Morris Operation. Although over only a short distance (about 2 miles), this activity provided valuable experience in handling these large casks.

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2.2.1 Fuel In Storage Figure _2-2 shows the accumulation of irradiated fuel in storage according to lE i

fuel origin. The illustration is based on a weight per fuel bundle of about 0.4 TeU and 0.2 TeU for FWR and BWR fuel respectively.2-1 Fuel received through the cutoff date for this report is listed in Table 2-1.

v 2-1 TeU: Metric ton of uranium as contained in fuel rods; equal to one megagram (Mg).

2-1

NEDO-2096934 Septenber 1980 Table 2-1 3 '

FUEI. RECEIPTS FROM JANUARY 1972 5i Reactor Origin Asse:nblies TeU Spaces #

PWR Haddan Neck 80 33 20 Point Beach 109 42 27-1/4 San Onofre 254 90 63-2/4 443 165 110-3/4 Bia Dresden 753 145 83-6/9 Lacrosse

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g/9 761 146 84-5/9 TOTAL ##

1204 311 195+

NOTES

" Space" - ene basket, either FWR or BWR. Fraction (2/4, etc.)

indicates partial basket loads (2 out of 4, etc.).

1. raction of basin capacity occupied 12/31/79 = 47.3::

El FAvailable spaces, including parking = 415 Nl

Temporary storage; to be returned.

2.2.2 Cask Excerience Since 1972, casks have been received, unloaded, and reshipped safely and effi-ciently. During this period only a few events occurred ir.<olving casks that required reporting to the USNRC. These events included a cask tipping incident in 1972, sinor damage'to a cask sealins surface in 1976, and the receipt of casks with cavity inner valves open in 1977. Casks have been received with minor snearable contraination on the surface, but this was not caused by leakage of the cask contents, and health and safety standards were not exceeded.

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IF-300 Irradiated Fuel Shipping Cask: lising different inserts, spacers, baskets and closure heads, the cask can accommodate 7 PWR or 18 BWR fuel bundles. Demineralized water or air may be used as internal heat transfer media. The cask is alanst 13 ft long, 6ft in diameter (overall),

and weighs about 53 tons empty and 64 tons with fuel.

Licensed by USNRC, the cask will with-stand accident conditions, dissipate decay he.it and present negligible radiation at the cask surface.

It is a multi-modal cask, usually shipped in a special, skidmounted enclosure on a 100-ton rail car with self-contair.ed cooling air system and ot her erluipment.

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History of Fuel Receipts at Morris Operation

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NEDO-20969B4 September 1980 2.3.1 Liner Leakage Water collected in the basin leak detection sump is Toutinely sampled and analyzed to determine basf a leakage rate versus intrusion water from sur-rounding rock strata. The liner leak rate has been less than one liter per day. The remaining water flow has come from the surrounding rocks (intrusion water) rather than from the basin.

2.3.2 Expansion Gate Leakage A small leak in the expansion gate was discovered in late 1971. A sump was constructed in the bottom of the gate opening to collect the water, which is jetted to the low activity waste (LAW) vault. In 1975 a level indicator and recorder were installed to record the leak rate. Rates vary from nearly 50 1/ day to less than 1 1/ day (see Figure 2-3).

The leakage appears to be influenced by both basin water temperature and ambient temperature.

2.3.3 Cranes and Lifting Equipment Experience with the three principal cranes (125 ton radio-controlled cask handling crane; 5 ton fuel handling crane; and 7-1/2 ten basin crane) has been very good. Routine saintenance programs for this machinery are in effect, including scheduled inspections. Several types of yokes are available to meet lifting requirements for casks now in use, as well as the necessary grapples for movement.of baskets and fuel bundles. No deficiencies of safety significance have been found in this equipment.

2.3.4 Fuel Storage System The fuel storage system utilizes uniformly spaced baskets (26-inch square baskets on 27-inch centers), consisting primarily of vertical sections of l

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NEDo-20069B4 September 1980 3.

SUPPOKr SYSTEMS 3.1 PRINCIPAL EQUIPMENT AND ACTIVITIES The support systems include the basin water cooling system, basin water cleanup system, the ventilation system, and waste management systems.

Experience with these systems is discussed in this section. Conventional plant systems, such as the on-site water system and electrical system, are not discussed; experi-ence with these systems has not disclosed any operational characteristics or problens peculiar to nuclear fuel storage.

3.2 3ASIN '4ATER COOLING SYSTEM The basin water cooling system includes a ptmping system to circulate basin water through one or more of three sections of finned-tube heat exchangers cooled by fan driven ambient air. The coolers are mounted outside of, 2nd adjacent to the southwest vall of the Basin 2 area.

Since censtruction, the coolers have been modified by the addition of heaters, an enclosure, and a pneumatic blow-down system, and one section has been refitted with stainless steel components.

3.2.1 System Modification The basin water cooling system was first used in 1973 but was shut down almost immediately because of contamination of basin water by corrosion products (rust particles, etc.) from carbon steel components of the system. An intensive filter compaign returned the basin water to its normal clarity in a few days. The coolers were not operated again until May 1976, after one cooler section of three tube bundles and related piping had been replaced with stainless steel componente.

During thi~s period, basin water was cooled by evaporation, and conduction through the basin walls. The temperature of the basin water followed seasonal ambient temperature variations (Figure 3-1).

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ilistory of Basin Water Temperature at Morris Operation When the modified cooler was placed in operation in May 1976, there was a sharp reduction in water temperature. Since then the. coolers have been run continuously except for maintenance and repairs, operational tests, and periods during summer days when the ambient air temperature is the same as or higher than basin water temperature. During hot summer weather, the cooler is normally run at night when cooling is.aore ef ficient and turned of f during the day to conserve energy.

3.2.2 Cooler Freezeup In January 1977 a single cooler section was being used, when electricc1 power to the plant failed during bitter cold weather with high winds (wind Ehill factor - 67'F). Water in the cooler froze and caused a leak at a tube-header junction. Af ter the cooler thawed (about 50 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months later), the system was shut down and drained. A small amount of gravel under the coolers became slightly contaminated by basin water that leaked from the cooler and was recoved and d

disposed of as low level waste.

3-2

NEDO-20969B4 S:ptembcr 1980 A pneumatic quick drain system, insulation on the pipes and distribution boxes, 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

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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 The heat input to the basin from decay of radioactivity in the fuel increased gradually with an increase in the a=ount of fuel stored, and decreased as a function of time in storage.

Figure 3-2 shows the approximate heat load history.

N The increases in 1975, 1976, and 1977 reflect the receipt of more recently discharged fuel,'some out of the reactor only 128 days at the time of receipt at Morris Operation.

3.2.2.2 Coolet Contamination Radioactive material from the basin water accumulates on the inner surf aces of cooler ;iping, tubes, and headers. A sample of material taken from the inner surf ace of the cooler piping in March 1977 contained Cs-134 (15%), Cs-137 (45%),

and Co-60 (40%). Average monthly exposure ratec are shown in Figure 3-3.

The rapid increase in the second half of 1977 was caused by the underwater cleaning l

of an insert for the IF-300 cask. Chemical cleaning techniques introduced in 1978 provided improved control of cooler exposure rates.

l 3.2.3 Ccoler Operation Summary In summary, experien ( has shown that the fin-fan coolers will provide the cool-ing servic,. required by water basin fuel storage, but that cold weather provi' ions 3-1 The scale of Figure 3-1 does not show the equilibrium period (about 47'C for two weeks).

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History of the Heat Generar.ed by vuel S:ored at Morris Operation

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NEDO-20969B4 September 1980 and corrosion-resistant construction are necessary. Contamination buildup in the cooler system was sharply reduced beginning in mid-1978 using new chemical E

decontamination techniques.

p 3.3 BASIN WATER CLEANUP SYSTEM The basin water cleanup system is a precoated filter-demineralizer system with associated pumps, valving and controls. The filter is located in a shielded room to protect operating personnel from accumulated radioactive material.

3.3.1 Operational Historv From the beginning of fuel storage operatiens in 1972, soluble radionuclides, principally radiocesium and radiocobalt, - were found to transfer to the basin water (Figure 3-4).

The concentration of these chemicals has been controlled by a mixture of anion and cation exchs,nge resins used in conjunction with a cellulose fiber filter aid. The filter system removes both particulate and ionic chemical materials.

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The decision to increase the storage capacity of the basins to about 750 TeU stimulated an investigation of the transfer mechanism for radiochemicals from fuel to water, and of improved methods of removing these chemicals from the basin water. Sharp changes in basin radioactive inventory during June -

l December 1975 reflect tests conducted during this investigation, including periods when the inventory was deliberately allowed to increase as a part of the test program.

Based on the results of these tests, the filter charge was altered in early 3-4 l

1976 to include Zeolon-100

, an inorganic ion exchange medium with high specificity and affinity for cesium. As a result, the removal rate of radio-l cesium was improved. The concentrations of radiocesium and radiocobalt have 1

3-2 From 1972 through 1975, radiocobalt constituted only a few percent of the I

total radioactive material in basin water. Radiocesium was the predominant T

constituent.

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l 3-3 Referred to as Project 1.

Because of anticipated fuel mix (as of March, 1978) the capacity will probably be about 700 TeU.

3-4 A proprietary product of the Norton Co.

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NEDO-20969B4 September 1980 averaged about 3 x 10- and 1 x 10 ' pei/mi, respectively, except for periods 3-5 when the filter system was not operated (MPC for restricted areas for Cs-134 y

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 quantity is reduced by an effective basin water evaporative loss lE of 50 to 100 gal / day. The concentration of tritium is expected to reach equilibrium, when the losses through evaporation and tritium decay equal

-0 the transfer rate, at about 5.5 x 10 pCi/mi.

3.3.2 Chemical Cleanup In early 1972 a substantial quantity of sodium nitrate (NANO ) was introduced 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 i

drop rapidly. By the end of April 1976, chloride, sodium, and nitrate were all below analytical detection limits (0.02 ppe C1, 0.2 ppm Na, and 0.2 ppm NO ).

3 where they have remained.

i t

l 3-5 Cs-134 is used as a basis, since it is more restrictive than the MFC lE for Cs-137.

3-7 l

NEDO-20969B6 i

September 1980 5

2J 50 get/dey 2A 9

100 gal /osy

]

2,4 2,2 q

2,0 T,

22 e

1,8

>D 1,4 e

2 y

1.2 i.0 Ey 02 OA

=

0,4 02

' I I !

0 1972 1973 1974 1975 1976 1977 1978 1979 1980 N'I Figure 3-5.

Tritium Activity 5

\\

J 3-8 i

l

NEDO-20969B4 September 1980 Table 3-1

^

IONIC IMPURITIES IN BASIN W.UER (October 1975)

Element PPti Method Li 0.02 SS36*

~

Mg 0.01 SSMS Al 0.01 SS)6 Cl 0.8 SSMS K

0.08 SSMS U

0.008 SSMS NO3

7. 9 Wet Chem.

30 2.7 Wet Chem.

47 C1

1. 6 *

Wet Chen.

SO 0.05 Wet Chem.

4

Spark Source Mass Spectrography

- Limit of detection 2 kilograms of Zeolon-100 are needed to partition the radiocesium in the basin so that 88% is captured by the exchanger 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 initial basin inventory of 1000 curies to j

less than 2.

In this case, as with any true ion-exchanger which is not pushed l

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 0.0125 hours 7.440476e-5 weeks 1.71225e-5 months , the time to reach equilibrium is several days. ~

3-8 Details of these studies are contained in the following paper:

L. L. Denio, D. E. Knowlten, E. E. Voiland; Control of Actect hel Storcge Scain Vcter Celity by use of Ecedered Icn Exchange Resin and Zeolites; ASME 77-JPGC-NE-15 (June, 1977).

3-11

NEDO-20969B4 September 1980 N

3.4 VENTILATION SYSTEM 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 in the exhaust air. Without exception, these concentrations have been much less than the applicable MPC values.

Table 3-2 AVERAGE CONCENTRATIONS OF RADI0 ACTIVE MATERIAL IN AIR IN WORK AREAS AI N

MORRIS OPERATION

-l' (x 10 pCi/ni) l Decontamination G oss a A#**

J ad Outside 3

l Gross S' Upper Lower Basin Canyon Laboratory Air 1976 2

0.06 Note 3 0.11 0.04 0.08 0.19 8

2.6 Note 3 2.2 7.9 0.27 0.49 1977 2

0.01 0.05 0.03 0.03 0.04 0.10 3

0.23 15.0 4.00 4.3 0.24 0.46 1978 a

0.03 0.10 0.04 0.03 0.04 0.06 8

0.99 25.0 3.1 3.9 0.28 0.42 1979 a

0.07 0.15 0.08 0.05 0.07 0.08 8

2.9 14.9 0.75 20.8 0.32 0.39 Notes:

1.

U natural MPCA = 1 x 10-10 uCi/mi 2.

Cs-134 MPCA = 1 x 10-8 yeifag 3.

Single monitec in decontamination area until 1977.

4.

Related to use of evaporator. Canyon area not considered as

,)

a work area - no routine activity.

3-12

NEDO-20969B4 Sept:=b;r 1980 An increase in concentrations in the basin exhaust plenum occurred during the fourth quarter of 1976 and was attributed to work in a temporary greenhouse erected to control contamination while cutting up hardware from the original E

fuel storage system en the decon pad.

Ventilation air from the greenhouse was exhausted directly into the plenum. The 1979 increase in the canycn was caused by LX4 evaporator operation with the cell cover recoved.

Concentrations of airborne radioactivity in many portions of the building, as typified by values in the Laboratory, are lower than those in the outside air.

This is the result of filtration of the air as it is drawn into the building.

Concentrations of radioactive material in the building exhaust air, dcwnstreas E

of the sand filter, have been lower than the applicable VPC values. The amount of radioactive naterials released to the environ =ent by way of the stack is shown on Table 3-3.

Table 3-3 SC" MARY OF RELEASES OF RADICACTIVE FATERIAL AT MCRRIS CPERA!!CN N

VIA THE MAIS STACK l

l

.I Gross Alpha Activity Gross Beta Activity l

Highest Highest Amount Off-Site Ascunt Off-Site pCi Concentration *1 uCi Concentration *2 i

Half Year aCi/ n1 uCi/ 21 l

2nd Half 1974**

78 6.6 x 10-19 115 9.6 x 10-19

-20

-19 1st Half 1975 16 3.8 x 10 51 1.2 x 10 I

-20

-19 l

2nd Half 1975 10 3.2 x 10 33 1.0 x 10

-20

'O Ist Half 1976 7

2.7 x 10 18 6.

x 10

-20

-19 2nd Half 1976 11 4.5 x 10 23 1.2 x 10 8.5 x 10_20

-20 ist Half 1977 4

2.3 x 10 15 19

-20 2nd Half 1977 6

3.1 x 10 119 6.1 x 10

-0

-20 15 6.7 x 10 1st Half 1978 3

1.3 x 10~

52 3.0 x 10~

2nd Half 1978 20 1.2 x 10

-0

~19 ist Half 1979 4

1.7 x 10 30 1.3 x 10

-40

-19 2nd Half 1979 5

3.2 x 10 28 1.8 x 10 NOTES:

Calculated average over the period indicated

- Data not tabulated prior to July 1974

- - To obtain average concentration in WC1/=1 divide by 1.93 x 10 '

1 ml (total flow in 6 mo.)

g = 5 x 10-12 uCi/21 1.

U natural MPC 2.

Co-60 MPCA = 3 x 10-10 aci/=1 i_

3-13

NEDO-2d969B4 September 1980 3.4.2 The Sand Filter The sand filter has operated effectively in removing radioactive particulates from the main building exhaust air. Two incidents occurred *that reduced air 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 top layer of sand was raked to return it to its original consistency, and the vent:lation 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.)

's J

In 1973 another increase in sand filter pressure drop was observed, this time 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-l l

up work. The screens were cleaned, and a second set of screens, more readily accessible than the first, was placed upstream.

I j

3.4.2.2 Filter Efficiency El Efforts have been made to determine the particulate removal efficiency of 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-ment the efficiency was found to be 98.9% for Co-60 and 99.8% for Cs-137 and I

Cs-134.

i s

3-14 l

y

=

+9--

--.e o

e. -,

-.,m

s NEDO-20969B4 September 1980 3.5 WASTE WATER MANAGEEIT There are three categories of waste water at Morris Operations; water contaminated with radioactive materials, industrial waste water, and sanitary wastes. Each of these categories is discussed in the following paragraphs.

3.5.1 Radioactive Wasta Water The accumulation of contaminated water at Morris Operation began in 1972 with the first receipt of irradiated fuel and the initiation of cold startup tests of MFRP using natural uranium. The LAW vault was filled to near capacity in October 1973. About 300,000 gallons were transferred to the cladding vault to give additional latitude in the use of the LAW vault, and boiloff of the LAW solution was begun. No liquid radioactive waste has been shipped or otherwise moved from the site.3~9 3.5.1.1 LAW Dewatering In the initial boil-off campaign, water in the LAW vault was reduced fron 454,000 gallons to 169,000 gallons over a 4-monta period. Most of the water in the cladding vault was then transferred back to che LAW vault and boiled off.

Since the conclusion of this campaign, contaminat:ed water has been collected con-tinuously from fuel storage activities and periodically boiled off (usually in the autumn). Two-to-three months of boiloff have accommodated the buildup of LAW vault liquid for an entire year. The accumulation and bo11down of radio-active waste water since the end of the first campaign is shown in Table 3-4.

l r

Contaminated water in the LAW vault has increased as new material accumulated each year from fuel receiving and storage, and concentrations have increased as a result of the boildown campaigns. A quantitative assessment of the actual contents of the vault is complicated by the existetce of a slurry at the bottom l

of the vault and the resultant heterogeneity. Besi: estimates of the l

3-9

~

Refer to NEDC-21326, Chapter 5, for information regarding sources of low activity waste collected in the LAW and cladding vaults.

i I

3-15 l

FEDO-20969B4 September 1980 Table 3-4 3

Nl HISTORY OF LAW VAULT USAGE LAW Vault Activity Date Net Change (Gallons)

Accumulation to 10-5-73

+589,000 Transfer to Cladding to 10-17-73

-135,000 Evaporation and Accumulation to 2-18-75

-285,000 Jet from Cladding Vault, normal to 5-20-75

+76,000 Evaporation and Accumulation Pump from Cladding Vault to 6-4-75

+166,000 Evaporate to 10-25-75

-229,000 Accumulate to 9-1-76

+171,000 Evaporate to 11-6-76

-183,000 Accumulate to 10-13-77

+167,000 Evaporate to 12-15-77

-105,000 Accumulate to 6-9-78

+64,000 Pump from Cladding Vault to 6-11-78

+50,000 Accumulate to 9-24-78

+43,000 i

Evaporate to 11-5-78

-139,000 Accumulate te 5-19-79

+70,000 Evaporate to 6-8-79

-78,000 Accumulate to 7-6-79

+9,000 Evaporate to 8-10-79

-60,000 Accumulate to 12-31-79

+23,000 Balance on 12-31-79 215,000 concentrations of radioactive material in the vault at various times are given in Table 3-5.

Boildown campaigns have been largely uneventful. However, in the initial campaign (January 1975), a steam shutdown coincident with an over-filled condition in the boiler allowed some contaminated water to enter the utility steam system and an estimated 50 microcuries of beta emitting isotopes I

were released to the process sewer. This release was not detectable at the site boundary.

The most frequent maintenance item has been the failure of pumps in the LAW vault.

The caustic nature of the solution has resulted in seal failures, and

~'

2 the pumps have occasionally had to be replaced.

3-16 p

y3_.

n,,

U NEDO-2096934 Sspterbar 1980 Table 3-5 HISTORY OF LAW VAULT CONTENTS lN Volume of Approximate Approximate Vault Contents Gross 3 Concentrations

Density

Date (Gallons) uC1/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.C60 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 6-4-78 297,000 0.33 1.079 6-11-78 347,000 0.25 1.089 9-24-78 390,000 0.15 1.008 11-5-78 251,000 0.40 1.105 5-13-79 326,000 0.41 1.095 6-9-79 245,000 0.47 1.118 7-1-79 249,000 0.42 1.109 8-12-79 198,000 0.57 1.148 12-30-79 221,000 0.55**

1.143

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.

- The major contributing isotopes were the following:

Cs-137 0.41 uCi/mi Cs-134 0.053 uCi/mi Co-60 0.089 pCi/mi

~

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 have averaged only about 7,000 gallons per year. Cladding vault use is summarized in Table 3-7.

3-17

NEDO-20969B4 Sspter.bar 1980 Table 3-6 Nl HISTORY OF CLADDING VAULT RADI0 ACTIVE MATERIAL CONCENTRATION-Date Gross S (aci/mi)

-3 July 1973 0.004 x 10

~3 November 1973 0.97 x 10

-3 January 1975 5.1 x 10

-3 November 1975 5.3 x 10

~

November 1977 4 x 10

-3 November 1978 1.5 x 10

-3 Julv 1979 2.4 x 10

Estimated frem the then current LAW Vault Activity.

Table 3-7 HISTORY OF CLADDING VAULT USAGE gg Cladding Vault Net Change Event Date (Gallons)

-s

)

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 Jst-out to LAW vault to 5-20-75

- 23,000 Pump-out to LAW Vault to 6-4-75

- 156,000 l

Accumulation to 6-9-78

+ 31,000 l

Pump-out to LAW Vault to 6-11-78

- 50,000 l

Accumulation to 12-31-79

+

5,000 on 12-31-79 19.000 3.5.1.3 Radioactive Waste Summary During the operation of the vaults, there have been few problems. The accumu-lation 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 j

uncertain. Best values of leakage as determined by modified isotope dilution techniques are given in Table 3-8.

1 1

3-18

~

NEDO-20969B4 Sapte:bsr 1980 Table 3-8 RECENT VAULT LEAK DETECTION EXPERIENCE N

Number of Calculated Leak Rate

Cladding Vault Date Determinations LAW Vault (1/ day)

(1/ day) 1979 7

<0.1

<0.1 1978 6

1.6

.<0.1 1977 4

0.4 0.2 1976 8

2.4

<0.1

Determined by a =cdified isotopic dilution analysis 3.5.2 Industrial Waste Water Operation of the process sewer began in 1971, when the process waste water consisted of well water with traces of boiler chemicals. The application for renewal of the State permit was denied in May 1974 because the process sewer discharges, in ce=bination with those of the sanitary sewer, did not conply with lever levels required by new State of Illinois regulations. Discharges con-tinued pending system modifications, which were completed in Septe=ber 1976.

The process sewer line was then diverted through the sanitary lagoons to a holding pond so that its effluents no longer leave the site. Monitoring of this water on a regular basis has shown no detectable radioactive material.3-10 The evaporation pond has operated under a State permit since its first use in May 1971. There has been no significant buildup of water since then, and most of the bottom remained dry. A leak in the pond via an old farm drain tile was discovered in November of 1977 and plugged in December. The release of chemi-I cals, mainly nitrates, was monitored through sampling at the retention basin at the Corps of Engineers Pump Station where this and other water was collected for discharge to the Kankakee River. No significant concentrations were ever l

found, indicating that any losses from the pond were substantially diluted by l

l l

-6 3-10 There have been three instances of concentrations up to 6 x 10 pCi/mi reported, but these measurements are suspected to be cross contamination in laboratory processes. The unrestricted area MPC, is 9 x 10-6 uC1/mi lE (Cs-134).

l 1

1 3-19 i

~

NEDO-20969B4 Ssptembtr 1980 the time they reached the pump station. The evaporation pond supports a T

variety of wildlife.

/

3.5.3 Sanitarv Waste Water The two sanitary lagoons were first operated in 1968 under a State permit.

Modificatio'ns to the system were made ending in September 1976 in order to bring the system into compliance with new rules and definitions which became effective in July of 1974. Now the sanitary waste from the lagoons is collected in a holding pond to be used for irrigation of adjacent GE-owned farmland.

Monitoring of the effluent from the lagoons has shown no detectable radio-

-1 active material.

3.6 SOLID WASTE MANAGEMEh"r Table 3-9 summarizes the production and shipment of solid radioactive waste.

All of the material listed was sent through Nuclear Enginee' ring to Sheffield, Illinois for burial. The large number of shipments and volume shipped in 1976 consisted largely of contaminated hardware replaced during the Project I

')

modification of the plant. Solid nonradioactive waste is collected and disposed of through conventional commercial waste disposal channels.

l l

~0 3-11 There have been five instances of concentrations of up to 2 x 10 uCi/mi being reported but these reports are suspected to be cross contamination in laboratory processes. The unrestricted area MPC is 9 x 10-6 pCi/mt

'])

El (Cs-134).

3-20

U NEDO-20969B4 S1ptsmbsr 1980 Table 3-9 SHIPMENT OF SOLID (DRY) RADIOACTIVE WASTE N

FROM MORRIS OPERATION Number of Volume Approximate Activity Year Shipments (Cubic Feet)

(Curies) 1972 3

1,300 0.,06 1973 5

2,700 0.18 1974 6

3,700 2.4 1975 2

1,100 4.2 1976 20*

14,200 3.4 1977 3

2,500 1.5 1978**

3 1,900 3.1 1979 2

1.300 1.1 Total 44 28,700 15.9 Average Per Shipment 650 0.4 Per Year 5.45 3,600 2.0 0.00055 Per Cubic Foot

Largely contaminated hardware replaced during Project I modification.

- 1978 data corrected (Revision B4).

i f

3-21/3-22 y

1-e 7 -,

m-m r

.wr-e.e w

~

NEDO-20969B2 January 1979 4.

RADIOLOGICAL SAFETY 4.1 ROUTINE ACTIVITIES INVOLVING EXPOSURES Employees at Morris Operation receive radiation exposure as a result of their duties. Certain routine activities have a higher potential for personnel exposure than others due to the nature of the work, its location, or its dura-tion. The potential for the higher exposures exists in working with, or in the immediate vicinity of:

a.

Fuel shipping casks -

Activities include monitoring, degri=ing, venting, flushing, head loosening, draining, head tightening, and decontamination; b.

Basin filter and associated piping -

Activities include solution =akeup, naintenance, housekeeping, and filter rework; c.

Basin water -

Activities include all jobs in the fuel storage basin enclosure.

Until the surcer of 1975 the most significant radiation area was the area above the basin, because of radioactive contaminants in the water. There were a few locally higher level areas such as near casks during unloading, near the cask flush line, and near the decontamination (decon) pad sump. However, since 1975, radiation exposure rates from the basin water have been reduced, the cask flush line has been shielded, and other improvements in radiation reduction have been made.

4.2 CURRENT SOURCES The primary sources of exposure at the time of writing were contaminated piping and contaminated surfaces on the decen pad. Most of this contamination 4-1

?v v

~

m w

y eam

NEDO-20969B4 September 1980 is fixed and is difficult to remove, with Co-60 the most common isotope.

However, Co-58 activity has been greater during times when 120 to 150 day old fuel is received. Cesium-134 and -137 are also invariably present in significant quantities.

The threa commonly used areas where exposure rates are currently the highest are the decon pad, the basin pump room, and areas near the basin coolers. Of these three, the occupancy rate of the decon pad is highest, so that area has the highest potential for personnel exposure.

4.3 EXTERNAL EXPOSURES Three approaches were selected to study the personnel exposure experience at Morris. Operation; determination of exposures by year, exposures by job title, and exposures from cask handling operations by cask type and operation.

Figure 4-1 shows the history of annual exposures at Morris Operation superimposed on a bar graph which gives the amount of fuel handled for each year. The increase j

of 1976 over 1975 in tons of fuel received per man-rem exposure is due to the use of the IF-300 cask.

(3.6 tons of fuel per cask versus 0.4 tons per NAC-1 or NFS-4 casks). However, this benefit is partially offset, in comparison to 1972, because recent fuel shipments have been accompanied by more crud, ano fuel burn-ups have been higher.

Table 4-1 gives the breakdown of exposures by job category. Since Operations personnel unload and decontaminate casks, their exposures are highest.

Maintenance personnel as a group receive the next highest percentage of the total site exposure, but when exposure is figured on a per man basis Safety personnel exposures are higher than maintenance personnel. Safety personnel survey the casks in and out and survey the radiation dose rates and levels of contamination throughout the facility. Contractor personnel may exceed exposures for other personnel; see notes on Table 4-1.

s 4-2 w

w ee-.g y

n

&v-,.

e e.

g e-

-y-pu

g-

NEDO-20969B4 September 1980 120 80,

2 w

C TONS PER MAN-REM

~

51"

~

1972 33 1973 1.2

[

1974 0A

=

~

9 5

1977 2.1 I*

d 1978 0.2 30 y i

go 1979 < 0,1 I

5 E

se

/

m!

i S

10 i

20 t

~

0 o

z i

0 0

1972 1973 1974 1975 1976 1977 1978 1979

(

Figure 4-1.

Work and Exposure Experience at Morris Operation N

4.4 INTERNAL EXPOSURE Results of whole body counting performed annually for Morris Operation person-nel parallel the fuel receiving experience. Body burdens of 1 to 2 percent of the Maximum Permissible Body Burden (see footnote, Table 4-2) were seen mostly in Operations personnel, and primarily in 1972, 1975 and 1976 when fuel receiv-ing was most intense. Table 4-2 summarizes this data, l

m-e-4-3

. -3

--,wv

NEDO-20969B4 Septemb2r 1980 Table 4-1

~

3 Nl PERSONNEL EXPOSURES AT MORRIS OPERATION BY JOB CATEGORY Total Exposure

~~

(Persor.-Rem)

{#'"

Job Category Persons ( )

1976 1977 1978 1979 Total Operations 19 21.6 30.9 21.4 12.4 64 Maintenance 9

2.9 6.7 7.2 3.5 15 Safety 4

3.5 4.C 3.3 1.7 9

Others 27 1.3 2.1 0.8 0.7 4

I)

Contractors

'79 = 59 3.2 2.2 0.5 4.6 8

Totals 32.5 45.9 33.2 22.9 100 Notes:

1.

Numbers are typical for past 4 years, except contractor personnel where number for most recent year is specified.

2.

Of 59 contractors in 1979, 20 had measurable exposure.

Contractors worked on IF-300 shipping cask insert modification program.

Table 4-2 Nl

SUMMARY

OF ANNUAL WHOLE BODY COUNTING RESULTS FOR

^

MORRIS OPERATION PERSONNEL Average Body Burden Number of Persons as Percentage Metric Tons Having Detectable of the Applicable of Fuel Month and Year Isotopes MPBB**

Received

December 1972 27 0.9 46 November 1973 6

l December 1974 6

January 1976 21 1.0 35 January 1977 26 1.5 116 I

November 1977 21 1.3 95 November 1978 25 1.3 7

November 1979 20 0.4 1

See Figure 2-2; fuel received since preceding count.

- Applicable body burdens in order of importance:

Co-60 = 1.1 pCi Cs-137 = 30 uCi Cs-134 = 20 aci

[)

4-4

NEDO-20969B2 January 1979 4.5 "AS LOW AS REASONABLY ACHIEVABLE" It is the policy of General Electric Morris Operation to minimize personnel This policy is in full accord with the regulatory principle, "as exposures.

low as reasonably achievable" (ALARA). Factors which bear on,the attainment of this end are the facility design, its use, and the critical review of operational results.

Keeping exposures ALARA is achieved through personnel training, operating experience reviews, administrative controls, and engineered facility mainte-nance and modification.

Personnel are trained and retrained in safety, and in the conduct of their particular job. In addition, specific training is provided prior to the use of any specialized equipment, i.e., cranes. Periodic work unit safety meetings and facility wide meetings are held as needed to complement these training Administrative controls require that both work and safety considera-programs.

tions must be defined beforehand, so that the most effective way for doing the work and the proper deployment of protective clothing and equipment can be determined.

4.5.1 Review Practices A primary method for achieving ALARA is through the critical review of operating l

experience. Reviews result in identification of the cause of any unnecessary or economically preventable exposures, and identify action to eliminate them.

Success in this approach has been seen in the reduction in exposure from basin water contaminants and the reduction in decon pad exposure rates through shield-ing of the cask flush line. In addition, a reduction in exposure rates on the decon scaffolding during unbolting of the IF-300 cask head has been achieved through the construction and use of a temporary shield. Table 4-3 gives a summary of the activities to achieve and maintain exposures ALARA and the con-ditions which resulted. An estimate of man-Rem saved is also included.

l 4-5

NEDO-20969Bt S1ptembsr 1980 Table 4-3 3

N RESULTS OF SPECIFIC EXPOSURE REDUCTION ACTIVITIES Estimated Avoidance of Exposure (Person-Rem)

Activity Reduction 1977*

1978,g 1979e b

Replacement and Shield-95% of Line Exposure Rate 1.0 1.9 1.2 ing of the Cask Flush Line 25% of Area Exposure Rate Basin Water Cleanup 97% of Activity 3.0 1.8 1.0 Fabrication of Shield-647. of Exposure Rate 1.5 ing Band for the IF-300 Cesium Flush of 100% Cesium Activity 1.2 0.4 Coolerse 27% of Exposure Rate Coolers Freeze-Thaw 40% of Exposure Race 0.6 0.6 Flushc Use of Torque Wrenches 70% of Time 2.7 2.4 2.4f for removing / replacing

/

IF-300 Cask Head Cooler Decontamination 86% of Exposure Rate 4.4 5.9 BWR Cask Insert 99% of Exposure Rate d

Cleaning 0.8 Cesium Flush of 65% of Exposure Rate ers 10.0 11.5 11.3 "1977 exposures are estimated to have been decreased by 18% through these exposure reduction activities.

1978 exposures are estimated to have been decreased by 26% through these exposure reduction activities.

Parts of tests and investigations referewced in Section 3.2.3.

dCleaning permitted b'asket (insert) modification, otherwise modification impossible. Result - reduced exposure in transit and receiving locations.

1979 exposures are estimated to have been decreased by 33% through these l

reduction activities.

fUse of torque wrenches for IF-300 head removal at other facilities provides exposure avoidance in addition to that shown here.

)

SData corrected for cooler decontamination in 1979.

l l

4-6 l

[

r

NEDO-20969B's September 1980 APPENDIX B-3 ENVIRONMENTAL SAMPLING AND ANALYSIS FOR DRESDEN NUCLEAR POWER STATION INCLUDING GENERAL ELECTRIC'S MORRIS OPERATION BY EBERLINE INSTRUMENT CORPORATION MIDWEST FACILITY i

HQIE.

In 1979 a separate environmental report for Morris Operation was not prepared; instead, a combined report for DNPS and Morris Operation is used.

W B3-1/B3-2 l'

NEDO-2096B4 Ssptemb:r 1980 ENVIRON > ENTAL SAXPLING AND ANALYSIS FOR DRESDEN NUCLEAR PO's'ER STATION DECEMBER 1979 s

SUBMITTED BY EBERLINE INSTROE:IT CORPORATION Midwest Facility

[ddMM 01/19/80 Date:

Approved:

Chandrasekarank E. S., Mgr.

B3-3/B3-4

NEDO-20969B4 September 1980 The attached table lists results of radiochemical analyses on the special samples collected weekly from two locations in the Dresden cooling lake.

These samples are not part of the regular environmental radiological monitoring program and the results are not included in the regular reports. We will, however, collect, analyze, and report the results on a monthly basis until further notice.

J cc:

B. B. Stephenson, Dresden J. Golden, Ceco C. Schwarz, EIC/Sfe i

I l

l

/

B3-5

DRESDEN Radioactivity in Water Samples from Dresden Cooling Lake (Weekly Collections)

Dresden Road County Line Road Dresden Road County Line Road Crossinn Crossing Crosning Crossing pCi/1/

pC1/1/

pCi/1/

pC1/1/

Collection pCi/l nuclide pCi/l nuclide Collection pCi/l nuclide pCi/l nuclide Date Cross 8_

y Emitters Cross 8 y Emitters Date Cross 6 y Emitturs Gross 8 y Emitters 01/06/79

<5

<10

<5

<10 07/07/79 4!2

<10 52

<10 01/14/79 411

<10 (a)

(a) 07/14/79

<5

<10 412

<10 01/21/79 4!2 (10 612

<10 07/20/79 312

<10

<5

<10 01/28/79 423

<10

<5

' <10 07/28/79

<5

<10

<5

<10 02/04/79 312

<10 512

<10 08/04/79

<5

<10 412

<10 i

02/11/79 512

<10 411

<10 08/10/79 3!2

<10

<5

<10 02/18/79 522

<10 1723

<10 08/19/79 1513

<10

<5

<10 i

02/25/79

<5

<10 422

<10 08/25/79 411

<10 5!1

<10 y N 03/03/79

<5

<10 312

<10 09/03/79

<5

<10 1713

<10

%$f w

Y 03/10/79 1012

<10 522

<10 09/08/79 513

<10 323

<10 03/17/79

<5

<10

<5

<10 09/15/79 312

<10 413

<10 78 03/24/79 412

<10

<5

<10 09/22/79 14t2

<10 1412

<10 03/31/79 312

<10

<5

<10 09/30/79

<5

<10

<5

<10 04/07/79 1012

<10 42

<10 10/06/79 1023

<10 422

<10 8"

04/14/79 813

<10 11 3

<10 10/13/79 413

<10

<5

<10 04/21/79 723

<10 813

<10 10/20/79 513

<10 322

<10 04/29/79 412

<10 1312

<10 10/27/79 412

<10 523

<10 05/05/79

<5

<10 1013

<10 11/04/79 6!2

<10

<5

<10 11/10/79 412 (10 523 (10 05/12/79 412

<10

<5

<10 11/17/79 612

<10 822

<10 05/19/79 6!2

<10 522

<10 11/24/79 412

<10 422

<10 05/26/79

<5

<10

<5

<10 12/01/79 412 (10 512

<10 06/03/79 1012

<10

<5

<10 12/08/79 3!2

<10 412

<10 l

06/09/79 612

<10 622

<10 12/15/79 812

<10 712

<10 06/16/79 522

<10

<5

<10 12/22/79 612

<10 06/23/79 5!2

<10

<10 12/29/79 812

<10 513 (10 06/29/79 422

<10 323

<10 (a) Not availal>1e due to severe weather conditions.

N.b s,

J

NEDO-20969B4 September 1980 Introduction During the month indicated on the cover of this report, environmental sampling at, and in the vicinity of, the power station was performed.

on a weekly basis. This report lists the results of analyses available as of the closing day of the month for samples collected in the program.

Blank spaces following dates indicate that work on this sample was not completed in time for inclusion in the monthly report.

Discussion df Results and Summary Results of analyses available unless noted below do not indicate the presence of discernable amounts of radioactivity due to station operations in the environmental media sampled.

Deviations from Scheduled Sampling and Corrective Actions Taken All samples were collected within the scheduled periods unless other-wise noted in the Listing of Missed Samples.

0 B3-7

.e,

-r9

NEDO-20969B4 Scptemb:r 1980 DRESDEN

~,

LISTING OF MISSED SAMPLES Expected Co11cetion Sample Tyne Location Date Reason AP D-01,02,06 01/13/79 Snow conditione.

SW D-29,30 January Drifting and closed 1

roads.

AP D-02 02/11/79 Malfunctioning pump.

CW D-19 07/14/79 Sampling apparatus out of order.

CW D-18 07/28,08/04/79 Sampling' apparatus needs repairs.

M D-25 08/10 Dorin sold his cows.

Station replaced ASAP.

O G

e 4

t O

+

6 9

.O b

e

/

e

.y B3-8

.gy+--

y y

.,,----w n

1,.

I DRESDEN AIRBORNE 10 DINE-131* and GROSS DerA in AIR PARTICUUCE FILTERS (Weekly Co11cetionu)

Gross Beta 10-2 pCi/m3 Collins Bennitt Pheasant D-01 ONS 1 D-02 ONS 2 D-03 ONS 3 D-018' Rd.

D-OS**

Farm D-06" Trail 4

Week Volume Gross Volume Gross Volume Gross Volume Gross Volume Gross Volume Gross 3

3 3

3 Ending (m )

Beta (m )

Beta 01/06/79 290 411 290 611 295 611 290 711 285 8!1 290 511 01/13/79 (a)

(a) 325 711 325 811 300 611 (a) 01/21/79 620 611

,620 611

'301 911 290 211 285 912 605 711 01/28/79 290 611 290 511 290 7!1 290 311 285 611 290 411 02/04/79 285 711 265 811 285 9!1 285 511 285 911 250 1111 02/11/79 280 611 (a) 285 8!1 285 511 285 911 285 811 02/18/79 280 411 285 311 285 611 280 421 285 721 230 611 02/25/79 290 411 290 7 11 290 311 290.

711 290 8!1 290 111 p.,

i 03/03/79 245 211 240 111 245 6!1 245 311 240 421 245 311 3m gf P',

03/10/79 285 411 285 2!1 285 4!1 290 3!1 285 411 285 411 1

03/17/79 290 621 290 311 290 611 285 311 290 511 285 611 gg 03/24/79 285 511 285 311 285 511 285 31 290 511 85 812 "g

03/31/79 285 511 285 311 280 711 285 311 280 611 35 (6

gg 04/07/79 285(b) 611 285(b) 311 285 611 285 411 285

<1 215

<1 8*

04/14/79 285 611 285 321 280 511 285 3!!

285 61'1 150

<1 04/21/79 285 411 285 311 285 611 285 311 285 511 285 41 04/29/79 330 511 330 111 330 41 330 211 330 411 325 321 05/05/79 245 Sil 245 311 245 711 245 111 240 411 245 711 05/12/79 280 311 280 311 275 411 280 211 280 311 275 511 05/19/79 285 411 290 411 290 511' 290 lil 290' 411 290 621 05/26/79 290 311 290 511 285 41 290 41 290 311 285 411 06/03/79 325 lil 290 611 325 611 325 611 325 511 310 611 06/09/79 245 5!1 280 6!1 245 621 240 611 245 5!1 240 511 06/16/79 285 511 285 711 280 611 285 511 285 411 270 611 06/23/79 285 411 285 411 285 4 11 285 411 285 411 285 711 06/29/79 245 511 335 911 245 6 11 245 Sil 245 511 245 511 e

4 (a) See Introduction Page.

(b) Mean volumes - temporary pumps.

3

Iodine Cartridges are sampled alternate weeks. Concentrations'are <0.10 pCi/m unless 6therwise noted.

- Stations shared by Dresden and G.E.

4 DRESDEU AIRBORNE IODINE-131* and GROSS BETA in AIR PARTICULATE FILTERS (Weekly Collections)

Gross Heta 10-2 pCi/n3 Collins Bennitt Pheasant D-01 ONS 1 D-02 ONS 2 D-03 ONS 3 D-Oh*"

Rd.

D-05'8 Farm D-06 Tra il Weck Volume Gross Volume Gross Volume Gross Volume Gross Volume Gross Volume Gross 3

3 3

3 Ending (m )

Beta (m )

Beta (n )

Beta (m )

Beta 07/07/79-325 911 245 821 325 7il 325 621 325 621 320 721 I

07/14/79 285

-911 330- 1511 285 911 285 8 11 285 721 255 911 07/20/79 245 411 245 711 245 711 245 311 245 421 245 421 07/28/79 335 511 320 5!1 335 511 335 421 330 421 335 421 08/04/79 280 321 255 511 280 511 280 511 280-321 255 521 08/10/79 245 31 240 611 250 611 250 621 250 421 230 621 08/19/79 365 321 365 321 365 121 365 311 365 221 365 221 08/25/79 250 121 250 411 250 411 250.

311 250 3!1 250-521 Ez w

09/03/79 370 321 375 31 375 421 370 411 365 321 375 5!!

%Q Y

09/08/79 200 121 195 421 200 421 200 411 205 5!!

200 211 0e 5

09/15/79 285 511 290 411 290 411 290 411 290 411 290 411 iM i

09/22/79' 280 211 280 411 280 521 280 511 280 411 280 711 j

09/30/79 320 311 325 611 320 511 320 6t1 320 621 320 711 C$

10/06/79 250 211 245 411

?50 411 250 521 250 411 250 411 E; -

10/14/79 325 221 290 721 325 211 325 211 325 121 320 321 10/20/79 245 611 250 1211 245 611 245 511 245 111 245 521 10/27/79 290 321 285 61 285 321 290 221 290 311 285 221 11/04/79 320 611 325 911 325 321 325 321 325 31 325 311 11/10/79 250 611 255 1522 250 621 250 5!1 250 911 250 4:1 11/17/79 280 711 275 711 280 611 280 511 280 911 280 621 11/24/79 290 611 295 721 295 611 290 621 100 821 290 621 12/01/79 285 411 285 411 285 311 285 411 285 511 285 411 3

12/08/79 290 311 280 221 290 421 290 321 290 211 285 421 12/15/79 285 311 275 311 285

' 421 285 411 270 311~

285 421 12/22/79 280 511 280 511 280 421 280 611 280 611 280 511 12/29/79 280 321 280 211 280 3il 280 221 280 211 285 321 I

i 3

Iodine Cartridges are sampled alternate weeks. Concentrations are <0.10 pCi/m uhless 6therwise noted.

- Stations shared by Dresden and G.E.

\\>

\\.'

~

NEDO-20969B4 S:ptembsr 1980 i

DRESDEN IODINE-131 in MID:

Collection pCi/1 at time of collee, tion Date D-2h Davidson Farm D-25 Dorin Farm U-26 Mather Farm (c) corbin Faca ORAZING SEASON MAY through OCTOBER (Weekly Collections) 05/05/79

<0.5

<0.5 05/12/79

<0 5

<0.5

.<0.5 05/19/79

<0.5

<0.5 05/26/79

<0.5

<0.5 06/03/79

<0.5

<0.5 06/09/79

<0.5

<0.5 06/16/79

<0.5

<0.5 06/23/79

<0.5

<0.5 06/29/79

<0.5

<0 5

<0.5 I

07/07/79.

<0.5

<0.5 07/14/79

<0.5

<0.5 07/20/79

<0.9(a)

(0.5

<0.7 (4) 07/28/79

<0.5

<0.5 i

08/04/79

<0.6(a)

<0.8(a)

..<0.5 08/10/79

<0.5 (b)

<0.5

'<0.5 03/19/79

<0.5 08/25/79

<0.5

<0.5 09/03/79

<0.5

<0.5 09/08/79

<0.5

<0.5 09/15/79

<0.5

<0.5 09/22/79

<0.5

<0,5

<0.5 09/29/79

<0.5 (b)

<0.5 10/06/79

<0.5

<0.5 10/14/79

<0.5

<0.5 10/20/79

<0.5

<0.5 10/27/79

<0.5

<0.5 I

l 1

NON-GRAZING SEASON - NOVEMBER through APRIL (Monthly Collections)

]

01/06/79

<5

<5 j

02/04/79

<5

<5 03/03/79

<5

<5 04/07/79

<5

<5 11/04/79

<5

<5 12/01,08/79

<5

-1 (c) New farm, Corbin, replaces Dorin as of 08/25/79. Code number remains same.

(b) See Listing of Fussing Samples page.

~(a) Lower sensitivity due to low chemical yield.

B3-11 y

2-F

-g*e-

,..3m.-+

-.-y

,c-.i..

g

-+-e---y

-..y--9

..y'e e

v.-

---,-w

DRESDDI CROSS DETA in C00 lit:C WATER SAMPLES (Weekly Collections) l pCi/1 pCi/1

===.

Background===

Indicator

Background

Indicator

+

Station Stations Station Stations INLET DISCHARGE DISCHARGE INLET DISCllARGE DISCilARGE Collection CANAL CANAL CANAL Collection CANAL CANAL CANAL Date D-18 D-19-1 D-20-2/3 Date D-18 D-19-1 D-20-2/3 01/06/79 2215 1013 511 07/07/79

<5 1023

<5 01/14/79 512 1112 722 07/14/79 4t2 (a)

<5 4

01/21/79 512 422 512 07/20/79 3!2 513 2t2 l

01/28/79

<5 312

<5 07/28/79 (a)

<5

<5 02/04/79 413

<5 1413 08/04/79 (a)

' 9!3 422 02/11/79 422 3i2 422 08/13/79 522 322 622 m

02/18/79 422 4!2 312 08/21,25/79

<S

<5

<5 3N i

l3 02/25/79 52 312 512 08/28,09/01/79

<5

.<5

<5 "8

hh h

03/03/79

<5

<5 413 09/05/79

<5

<5 422 03/10/79 10!2

<5 612 09/15/79 313 413

<5 38 03/17/79 612

'813

<5 09/22/79 813 713

<5 g o 03/24/79 612 812 612 09/30/79 412 723 513

$ j' 03/31/79 512 722 Ar2 10/06/79

<5

<5 o

04/07/79 5415 4014 2823 10/13/79 513

<5 512 04/14/79 11!3 1013 813 10/20/79

<5 1013 1123 04/21/79

<5 1513 1513 10/27/79 822 411 412

~

04/29/79 722 1013 72 11/04/79 812 612 512 11/10/79 412 622 322 05/05/79 713 1613 1013 11/17/79 723 522

<5 05/12/79 412 813 612 11/24/79 322 612 412 05/19/79 612 612

<5 12/01/79 312 713 312 05/26/79

<5

<5 12/08/79 412 42 312 06/02/79

<5

<5 12/15/79

<5

<5 1013 j

06/09/79

<5 5!2

<5 12/22/79 512-612 512 06/16/79 3!3 713

<5 12/29/79 522 312 622 06/23/79 322 813 512 06/30/79

<5 322

<5 i

t (a) See Listin5 of Missed Samples Page.

\\

'2 4

_r

NEDO-20969B4 Scptenbsr 1980 DRESDEN s

RADI0 ACTIVITY IN SURFACE WATER SA!FLES (Monthly Collections) oCi/1 Collection Sanitary Lagoon D-29*

Evaroration Pond D-30*

Date Gross a Gross 8 Gross a Gross 8 January (a)

February (2/25) 817 1024 211 2024 March (3/10)

<1 1216

<1 17:6 April (5/05)

<2 7 13

<2 522 May (6/03)

<2 512

<2

<5 June (6/23) 121 6:3

<2 4 13 July (7/20) 221 1023

<0.5 6t3 August (8/04)

<3 St2

<3 612 September 9/15)

<3 723

<3 523 October (10/06) 1:1 622

<1 522 November (11/17) 322 1023

<4 622 December (12/22) 211 1313

<2 612 RADIONUCLIDES IN SURFACE WATER (Monthly Composites of Weekly Collections)

D-21 Illinois River at EJ5E RR Bridge Collection Gamma Emitters Date pCi/1 January

<10 February

<10 March

<10 April

<10 May

<10 June

'<10 July

<10 August

<10 September

<10 October

<10 November (10 December

<10 (a) See Listing of Missed Sa=ples.

G.E. Station B3-13 a

-m

,e-y9-.--

NEDO-20969B4 Ssptemb2r 1980 DRESDEN RADIOACTIVITY IN WELL WATER SAMPLES

)

(Quarterly Collections) pCi/1 Co11cetion D-23*

Worsen Well D-32**

L.A.W. Well Period Cross S Tritium Gross B Tritium 1st Qtr.

<5 3302120 512 2602140 2nd Qtr.

1023 200 100 63 (200 3rd Qtr.

4 12 240 110 1022 2501100 4th Qtr.

512 5002140 922 190290 RADI0 ACTIVITY IN SURFACE WATER SAMPLES (Quarterly Collections)

.)

-D-22*

D-31*

D-33*

' Morris Water Works Goose Lake Corp. of Eng.

Fond West of FERP Collection pCi/1 Period Gross S Tritium

' Gross B Tritium Gross S Tritium ist Qtr.

52

<200 12 2 1902120 8!2 1901110 2nd Qtr.

5 13 6402120 523 3202130 52 120!100 3rd Qtr.

7!3 2202120 43 3502120

. <5 160 110 4th Qtr.

1623 660290 812 180180 J

Station shared by Dresden and C.E.

- G.E. Station.

B3-14 f ts--

-w-y p-,__,-,-

NEDO-20969B4 Ssptemb:r 1980 DRESDEN RADIONUCLIDES IN FISH SAMPLES (Semiannaul Collections)

D-28 Dresden Pool of Illinois River Collection Gamma Emitters Date Species pCi/g wet 05/26/79 Carp

<0.1 (Above discharge)06/79 Unknown

<0.1 (Below discharge)06/79 Unknown

<0.1 (Upstream)08/29/79 Drum

<0.1 Redhorse

<0.1 Mooneye

<0.1 Gizzard Shad

<0.1 Carp

<0.1 Goldfish

<0.1 Carpsuckers

<0.1 (Downstream)08/29/79 Shorthead Redhorse

<0.1 Channel catfish

<0.1 Alewives

<0.1 Mooneye

<0.1 Carp

<0.1 Longnose Gar

<0.1 Carpsuckers

<0.1 Drum

<0.1 C.zzard Shad

<0.1 I

l RADIONUCLIDES IN SEDIMENT SAhTLES (Annual Collection)

D-27 Dresden Lock and Dam Collection pCi/g vet Date Cs-137 Other y 06/03/79 0.6!0.1

<0.2, Co-60=0.220.1 07/20/79 0.810.2

<0.2 33-15

DRESDEN GAMMA RADIATION Average mR/Qtr. Using *thermoluminescent Dosimeters Date Annealed:

12/11/78 03/12/79 06/11/79 09/28/79 Date Read:

03/21/79 06/18/79 10/09/79 12/17/79 (a) Read 03/22/79 Location 1st Quarter 2nd Quarter 3rd Quarter hth Quarter On-Site' Indicator Stations D-01 On-Site 1 14.311.3 14.3 3.9 12.611.3 16.913.9 D-02 On-Site 2 13.012.6 12.4!1.3 13.011.3 16.922.6 D-03 On-Site 3 13.0 1.3.

11.711.3 11.214.2 16.913.9

D-04 Collins Road (a)13. 011.3

'13.013.9

.13.011.3 16.912.6 Average 13.311.6 12.9 2.6 12.5!2.0 16.913.3 m0$

E Off-Site Indicator Stations y8 l

h

D-05 Bennitt Farm 13.011.3 14.3!2.6 14.312.6 18.223.9 j

D-06 Pheasant Trail (a)12. 012.'O 9.210.9 10.511.4 14.311.-3 ob i

D-07 Clay Products 12.221.4 12.712.3 11.113.0 16.912.6

$S f

D-08 Prairie Park (a)11. 212.1 12.514.6 10.411.2 16.913.9 yE 12.111.7 12.2!2.6 11.612.1 16.8!2.9 j

Average Background Stations 8D-09 Coal City 10.7!2.2 9.811.3 8.221.4' 14.311.3 l

D-10 Goose Lake Village (a)11. 7 tl. 2 12.7!2.2 12.112.3 16.912.6

D-11 Morris 11.211.2 10.8tl.0 10.5 1.4 14.3!1.3 I

D-12 Lisbon 11.321.4 13.0!2.6 9.811.0 15.612.6

D-13 Minooka 11.3 1.2 10.822.7 9.8!2.1 14.311.3

D-lh Channahon 11.3 1.6 12.113.6 10.521.0 15.611.3

D-15 Joliet Brandon Rd.

12.221.2 12.712.9 10.922.3 16.911.3 D-16 Elwood 12.111.6 14.312.6 10.4!1.0 15.611.3 D-17 Wilmington 12.211.4 13.022.6 10.511.2 14.311.3 I

Average 11.611.4 12.122.4 10.321.5 15.311.6 l

Stations shared by Dresden and G.E.

~

O w

1

NEDO-20969B4 S2ptemb:r 1980

'OUALITY CONTROL ANALYSES SU>D!ARY DECEMBER 1979 iite tables below sum =arize results of samples run for process quality control purposes during the subject conth. Tnese ' listings are in add-ition to such measurements as detector backgrounds, check source values, radiometric-gravimetric comparisons, system calibrations, etc. Detailed listings of each measurement are maintained at the laboratory and are available for inspection if required.

BLANK SAMPLES Nuclide Number of Kumber of enalyses exceeding Analyzed _

Determinations the LLD for that analysis Gross Beta 17 0

^

Gross Alpha 14 0

Iodine-131 24 0

Strontium-89 1

0 Strontium-90 1

0 Gam =a Emitters 5

0 Tritium H-3 4

0 SPLIT SAMPLES Nuclide Number of' No. agreeing No. agreeing No.". differing Analyzed Det'ns within 2a uithin 3s by >3a l

Gross Beta 6

6 0

0 Gross Alpha 1

1 0

0 l

Iodine-131 1

1 0

O l

Strontium-89 7

7 0

0 l

Strontium-90 7

7 0

0 Camma Emitters 3

3 0

0 Tritium H-3 6

6 0

0 Calcium-45 1

1 0

0 SPIKED SAMPLES Nuclide No. of Within 2a Within 30 differing from l

Analyzed Det'ns of known of known known by > 3o Gross Beta 13 13 0

0 Strontium-90 6

6 0

0 Tritium H-3 2

2 0

0 Gamma Emitters 5

5 0

0 l

w l

l B3-17 l

l

NEDO-20969B4 September 1980

~

T EPA INTERCOMPARISO! RESULTS l

1979 1

Control M',fF Sar.ple Agency Limits Measured Type Analysis value (3o,n=1) 2a error Units Air Filter Gross a 5

15 311 pCi/ filter Air Filter Cross 8 18 15 20t2 pCi/ filter Air Filter Sr-90 6

4.5 722 pCi/ filter Air Filter Cs-137 6

15

~921 pCi/ filter Water Gross a 6

15 712 pCi/1 Water Gross a 10 15 3311 pCi/1 Water Gross 8 16 15 1.42 pCi/1 Water Cross 8 16 15 3323 pC1/1 Uater H-3 1280 993 12M 300 pC1/1 Uater H-3 2270 1047 2303!200 pCi/1 i

Water Sr-89 14 15 321 pCi/1 Water Sr-90 6

4.5 511 pCi/1

~,

I i

4 B3-18 y

ew-+-

g 9+=e- - -s-r

---em-p

,y

.,y-.

e-y

-e o

gag-

~,-

---c.s er w-w c

NEDO-20969B4 September 1980 USDOE QUAI.I'IY ASSESSMENT PROCitAM i

-w 1979 Sample Measured Type Nuclide Known ila error Units Air Co-57 0.116 E+03 0.131:0.013 ' 03 pCi/ filter

%.C v

Air Sr-90 0.135 E+02 0.155:0.025 E+02 pCi/ filter cg Air Ru-106 0.174 E+03 0.167 0.020 E+03 pCi/ filter Air Sb-125 0.749 E43 0.823:0.082 E+03 pCi/ filter

- ;.1)

Air Cs-134 0.985 E+02

'0.947:0.095 E+02 pCi/ filter

' 3

' ~ ' '

Air Ca-45 0.134 E+03 0.230:0.023 E+03 pC1/ filter

. p.,

Soil K-40 0.216 E+02 0.235:0.024 E+02 pCi/g Ji Soil St-90 0.200 E+00 0.200:0.080 E+00 pCi/g Soil Cs-137 0.240 E+00 0.26620.027 E+00 pCi/g CO 43 Tissue K-40 0.840 E+01 0.900:0.090 E+01 pCi/g Tissue St-90 0.440 E-02

<0.200 E+00 pCi/g Tissue Cs-137 0.230 E-01 0.120 0.030 E-01 pCi/g Vegetation K-40 0.225 E+03 0.220 0.022 E+03 pCi/g VeZetation Sr-90 0.573 E+01 0.593:0.059 E+01 pCi/g Vegetation Cs-137 0.256 E+00 0.23020.030 E+00 pCi/g t!ater H-3 0.124 E+02 0.130:0.013 E+02 pCi/ml Water Na-22 0.843 E+00 0.907:0.091 E+00 pCi/mi teater Mn-54 0.737 E+00 0.800:0.096 E+00 pCi/n1 llater Co-60 0.871 E+00 0.97020.097 E+00 pCi/mi Water Cs-137

-0.980 E+00 0.11710.012 E+01 pCi/ml l

l I

i l

1 B3-19 i

I

II

l

f#M\\ChC)'

DRESDEN Collection'Sched'ule '

Quarter:

i i

n i.I lJ l

'4 2

.For samples scheduled for collection at intervals of cnc month or-greater,I"Date.' Scheduled" indicates the NOTE:

Samples should be obtained as close to that date.no'possible, and in any

target' date for obtaining the sampic(s).

event, before the nex't scheduled target, collection._ Dates of unsuccessful sampling attempts are to,be noted on the I

l veckly sampic collection data' sheet.:

l

.l 8

nonth:

OCToot2,

.lJoVEH 8ER.

T>ECEreER-

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NOTES Scheduled Date:

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Text

SUMMARY

1.1 Purpose and Scope

SUMMARY

SUMMARY

SUMMARY

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