ML20134D761

Rev 0 to Reactor Bldg Basement - History & Present Conditions, Data Rept.Related Info Encl

ML20134D761
Person / Time
Site:	Three Mile Island
Issue date:	11/30/1982
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20134D759	List: ML20134D755 ML20134D761
References
TPO-TMI-027, TPO-TMI-27, NUDOCS 8508190346
Download: ML20134D761 (190)

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TP0/TMI-027 Revision 0 November 1982 4

DATA REPORT

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EACIDR BUILDING BASEENT (EL 282'-6")

HISTORY MO PRESENT CO@ITIONS 1

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Director, Technical Planning 8

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INTRADEPARTENTAL REVIEW AND APPROVAL helacM C M Responsible Engineer Lt Manager, Data Management and Analysis Planning b s rat ve r

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SLNMARY As a result of the March 28, 1979 loss of coolant accident, the reactor building basement at THI-2 remained flooded with highly contaminated water for over two years.

The water has been a major contributor to the general area radiation on the higher elevations. Significant efforts have been expended on characterization for planning cleanup of the basement. Results of sample analyses indicated that Cs 134, Cs 137, and Sr 90 have been the predominant activities.

The SDSKPICOR systems, in series, are utilized for decontaminating the water and, to date, almost all the water has been successfully processed at an overall rate of 3.3 gpm.

The PIccessed water is being used for decontamination of the building, resulting in dilution of the basement water content s.

Current efforts eghasize sampling the sludge deposits on the floor, visually inspecting the basement area via remote controlled television, and preparing to decontaminate the casement. Preliminary results of early sludge sample analysis indicate high contents of cesium and strontium activities, with strontium mainly in solid phase. Chemically, the sludge is found to contain high concentrations of Zr, Cu, Na, B, Ti, In, and Sn. Presently, plans are being drawn to samle the sludge and conduct further visual inspection of the basement and the sludge. Sufficient understanding of the chemical and isotopic comositions, curie content, the amount of fuel present, and other characteristics of the sludge is necessary for technical planning of removal and disposal of the sludge.

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l CONTENTS PACE i

SLMMARY.

111 CONTENTS iv

1.0 INTRODUCTION

I 1.1 OEUECTIE I

1.2 BACKCROUND I

1.3 SCOPE.

1 2.0 EACTOR BUILDING BASEENT 2

3.0 FLOODING OF TE BASEMENT.

3 3.1 THE EACTOR CDCLANT SYSTEM.

3 3.2 THE CONTAIPNENT SPRAY SYSTEM 3

3.3 RIVER WATER COOLING SYSTEM.

3 4.0 BASEMENT WATER ANALYSIS.

5 5.0 WATER m0 CESSING 7

5.1 SDSK PICOR SYSTEN.

7 5.2 IMPACT OF m0 CESSING.

11 1

6.0 CURENT CONDITIONS.

13 l

I l

6.1 WATER LEWL.

13 6.2 RADI0 CHEMISTRY AND CHEMICAL CDESITION.

13 6.3 RADIOLOGICAL CHARACTERIZATION.

17 7.0 CURENT APO FUTURE TASKS, 22 7.1 REMOTE DECDNTAMINATION 22 7.2 VISUAL INSPECTION.

22 7.3 RCDT INSPECTION AND SAMPLING 24 7.4 REMOVAL OF TE WATER AND SLUDGE 24 REFEENCES.

25 l

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TABLES PACE 4-1 ISOTOPIC ANALYSES OF THE BASEENT WATER.

5 4-2 CEMICAL ANALYSIS OF TE BASEMENT WATER.

6 5-1 SDS EFFECTIVENESS IN FR0 CESSING REACTOR BUILDING SLNP WATER 7

5-2 EPICDR-II PROCESSING OF SDS EFFLUENT.

8 5-3 RB SLNP FR0 CESSING.

10 6-1 RADIOCEMICAL ANALYSIS OF BASEMENT SLUDGE 16 6-2 TMI-2 SLUDGE SAMPLE CHEMICAL CDMFOSITION 16 FIGJRES 3-1 REACTOR BUILDING WATER LEVEL 4

5-1 SCHEMTIC OF TMI-2 SLEMERGED DEMINERALIZER SYSTEM 9

6-1 REACTOR BUILDING BASEMENT WATER (BEFORE SAMPLING).

14 6-2 REACTOR BUILDING BASEENT WATER (AFTER SAMR.ING).

15 6-3 TLD TREE ANALYSIS - RCOT CUBICLE 18 6-4 TLD TREE ANALYSIS - EENEATH CORE FLOOD TANK 1A 20 6-5 TLD TREE ANALYSIS "B" D-RING.

21 7-1 REACTOR BUILDING BASEENT FLUSHING LOCATIONS 23 S

V

t SECTION

1.0 INTRODUCTION

1.1 OBJECTIVE The purpose of this report is twofold: first, to give a summary of the conditions that existed in the containment basement since March 1979; and second, to provide a brief summary of the efforts to cleanup and decontaminate the containment basement, and the results of these efforts.

1.2 BACKGROUND

On March 28, 1979, the loss of coolant accident (LOCA) at Three Mile Island's Unit 2 (TMI-2) resulted in a large amount of heavily contaminated water in the containment basement.

Investigations have concluded that this water has been a major contributor to the general area radiation in the containment building. In addition to the defueling and reactor coolant system (RCS) decontamination, the safe cleanup and removal of this water has been a major task in General Public Utilities' (GPU's) recovery effort. This is because, in addition to the obvious need to clean and dispose of the water, removal of the highly contaminated water was expected to reduce general area radiation and dose rate to personnel. Hitherto, efforts pertaining to processing of the water and characterization of the prevailing conditions have been conducted.

Documentation of these activities and of the current conditions in the containment basement are the subjects of this report.

1.3 SCOPE This report is essentially a documentation of the conditions that existed, the efforts that have been conducted, and the results achieved to date.

Conditions such as water level, the radiological properties of the water before processing, the ef forts expended on the processing and the results achieved, the current conditions and the near term planned activities will be addressed in the order presented. The report is not intended to be final or comprehensive, and it only presents relevant data and information available at the time of this report. Future developments will be included 1.n addendums or revisions to this report.

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SECTION 2.0 REACTOR BUILDING BASEENT The space between the floors on El 282'-6" and El 305' in the reactor building is referred to as the basement. The basement houses several major components. A partial list of these components is given below:

1.*

The reactor coolant drain tank (RCDT), WDL-T-3 2.*

Letdown coolers, MU-C-1A and 1B 3.*

Lower section of steam generators A and B (OTSG A and B) 4.*

Leakage coole s, WDL-C-1A and IB 5.*

Leakage transfer pugs, WL-P-9A and B 6.*

Reactor coolant drain pump (WOL-P-7) 7.

OTSG secondary side drain pum SU-P-1 8.

OTSG wet layup recirculation pmp SU-P-2 1

9.

Chemical addition tank SU-T-1 10.*

Bottom of the reactor l

11.*

Incore instrumentation 12.*

Reactor building sump peps, WDL-P-2A and 28 13.*

Tendon access gallery sump pu m, 50-P-13 A and B l

14.*

Decay heat system piping l

15.*

Radiation monitor cabinets Possible significant sources of radiation.

l The flooding of the basement entailed the immersion of the above comonents in l

highly contaminated water for over two years. Ef forts are bahg undert. ken by l

various organizations to investigate the effects of such accioent-imposed conditions on the trechanical and electrical components.

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Havirg taken ecmponents, concrete shields, and walls in the basement into l

consideration, calculations have generated the following correlation between the elevation above the basement floor and volume of the space below that l

level (Refererce 1):

El. 282'-6" - El. 286'-0" 6080 gal per in.

l El. 286'-0" - El. 289'-0" 6100 gal per in.

El. 289'-0" - El. 291'-1" 6200 ga) per in.

Along with the following known volumes, this correlation has allowed estimation of the volume of the water in the basement.

l Sump volm e 2,722 gal Drain pipes 1,274 gal Imore Instrument Chtse

~2,700 c*1 Elevot:r Pit

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SECTION 3.0 1

FLOODING OF THE BASEENT f

Before the start of processing of the water in September 1981, an estimated 640,000 gallons of ' water had been" discharged into the basement. This water is I

attributed to three major sources: reactor coolant system, containment spray l

system, and the river water cooling system.

l 3.1 THE REACTOR COOLANT SYSTEM At 15 minutes and 27 seconds into the March 28 incident, the rupture disk on the reactor coolant drain tank (RCOT) broke at a pressure of 190 psig (set point) and relieved highly radioactive water and ster into the basement.

This continued until the pressurizer block valve was secured. However, further release was repeatedly initiated when the pressurizer block valve was cycled in an effort to regulate pressure in the system. Apart from the quantity that was pumped into the auxiliary building, an estimated 265,000 gallons of water has been released into the basement sep from this sourte before SOS start @.

There has also been a continuous leak rate on the order of 0.13 gpm from the RCS for over two years.

The total quantity of water from the RCS is estimated at about 69% of the water before the SOS startup.

3.? THE CONTAINIENT SPRAY SYSTEM At about 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> and 50 minutes into the accident, the hydrogen burn resulted in a containment pressure spike of at least 26 psig, which is the set point for the actuation of the containment spray system. The spray system operated for 5 minutes and 40 seconds, dumping an estimated 17,000 gallons of water i

l into the containment, which eventually resided in the basement sump. The amount attributable to this source amounted to less than 3% of the water in the basement before the SOS start @.

Because of the adition of chemicals (NaOH) that automatically accompanies the spray solution, the sodium ion l

concentration cecame elevated.

3.3 THE RIVER WATER CDOLING SYSTEM The investigation initiated by the readily unaccountable increase of water level in tne baserent attributed the extra water to leakage fztm the river water cooling system. The leak was susoected to be from a relieving relief valve on the containment building cooling coils. Based on available data, l

back projections of water levels, and reconstruction of events asstelated with I

water inventory, it has tieen estimated that 180,000 gallons of water was released into the containment from this source before it was secured. This l

amounts to abcut 28% of the inventory before the SOS startup (Reference 2).

c'm 3-1 ill.:stretes e scWtic cf the water level rise as e function of time until the SOS starttc. The maximum deptn attained by tnt oorcant wa*.er l

was 8 ft 6 in. The rate of decrease of the water level after initiation of SOS processing of the water is addressed in Section 5.0.

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FIG. 3-1 REACTOR BUILDING WATER LEVEL Io i

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SECTION 4.0 BASEMENT WATER ANALYSIS Before the SOS processing, efforts were expended to obtain and analyze samples from the basement water. Such data were to determine contents of the water to support mass balance, decontamination, and other recovery-related activities.

In addition, because the basement water has been a major source of radiation in the building *, understanding its composition would assist in assessing the effect of removal of the water on dose levels.

l Several samples of the basement water were drawn and analyzed before t

processing began. Table 4-1 presents analysis of samples taken in August 1979, May 1981, and September 1981. The August 1979 sample was retrieved from top,. middle, and bottom depths of water. The data presented in the table, i

however, are average values for selected isotopes. For details, refer to l

Reference 4 Four samples were obtained in May 1981 from 84-3/4 in., 47-3/4 l

In., 5-3/8 in., and 0.0 in., respectively, above the basement floor. Acain, l

the data in Table 4-1 are average values for the different levels for selected j

isotopes of interest. For comparison purposes, another sample was drawn from l

the basement floor in September 1981. Results of analysis of this sample are presented in the table for selected isotopes. Details relevant to the latter two sets of data are given in Reference 5.

A close look at the results of the analysis depicts the following observation:

1 The predominant activities detected were due to Csl34, Csl37, o

and Sr90 Csl37 represented about 70% of the total measured activity. This value had increased to 85% by the later date due to decay of shorter lived isotopes.

There was no apparent significant stratification at either of the o

i points where samples had been obtained from several different l

levels.

Curie concentrations decreased with time, probably due to dilution.

o TABLE 4-1 ISOTOPIC ANALYSES OF THE BASEMENT WATER i

(selected isotopes) l l

8/79 5/81 9/81 j

(uCi/ml)

(uC1/ml)

(u C1/ml)

Csl37 176.3 142.3 137.0 Ccl34 39.9 19.15 It.)

583 2.91 5.225 4.6 H3 1.03 0.6025 0.587 l

l A stuoy concluded that a high percentage of the general area radiation on l'

El 305' was due to the contaminated water and sludge in the basement.

(Refererce 3) Radioac'!vity assoc!Pted with the basc9snt sludge is j

discussed in Section 6.2 of this report.

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r Table 4-2 illustrates the chemical composition of samples corresponding to Table 4-1.

The data in Table 4-2 are averages, as was indicated for the ones in Table 4-1.

Results of the analysis further elaborate on the observation that there was no significant stratification at the points where the samples were taken. The data also indicate high contents of boron and sodium resulting from the reactor coolant injection and the containment spray water.

TABLE 4-2 CIEMICAL ANALYSIS OF THE BASEMENT WATER (data presented only for selected chemicals) 8/79 5/81 9/81 (uif/ int)

(ugTT)

(u g/ml)

B 2116.7 2120 2300 C1 11 Cu 4.7

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f SECTION 5.0

/ PROCESSING OF THE BASEMENT WATER v

5.1 SDS/ EPIC 08 SYSTEMS

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Processing the highly contaminated water in the reactor building basement has been one of theimajor phases in the recovery effort. The system develooed for this purpose employed a. combination of the submerged demineralizer system (SDS) and a modified EPICOR system in series.

3

) The SDS, which utilizes inorganic zeolites such as mineral chebazite and synthetic type-A zeolites, removed Csl34, Csl37, and Sr90 Thd effluent from the SDS is then' polished via EPICOR-II. A detailed account of theidesign

'i and operation of the SOS /EPICOR-II. systems is outlined in Referer,te 6.', A

, ' schematic of the combined process is shown in Figure 5-1.i Processing of the basement water began on September 23, 1981. The water was removed from the basement in batches of between 30K and 50K gallons'using a i

N surface suction pump.

This punp lost suction after the water level was reduced from B.5 feet to 6.0 inches. A small jet pump was then us'Jd to remove 4

the remaining water at a low rate of less than 5 gem.

This pumo removed virtually all the remaining water and is still being used as the water level increases.

To'date, almost all of the water in the basement has been'successfully processed at an overall rate of 3.3 gpm.

The effectiveness of the SOS and EPICOR-II in curie removal are summarized in Tables 5-l* and 5-2*.

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,t TABLE 5-1 i

SDS EFFECTIVENESS IN PROCESSING REACTOR BUILDING S0M? WATER Radionuclide Influent Effluent l

Decontaminatien,'j Removed Curies (uC1/ml)

(pC1/ml)

Factor

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I Cs-134 13.1 3.0E-4 1.3E+5 29,800 Cs-137 i 123 8.6E-4 1.4E+5 278,000 SI-90 i*

5.14 8.8E-3 5.9E+2.

11,600 Sb-125

'l.lE-2 1.lE-2 Ce-144 4E-4 4E-4 Co-60 2E-5 2E-5 TOTAL

-319,400 T.e data cre:e.~.2d herein recresent averacet; citer 0:0'essinc'aucut $10,C"C callons.

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TABLE 5-2 EPICOR-II PROCESSING OF SDS EFFLUENT Radionuclide Influent Effluent Decontamination Curies Curies (uC1/ml)

(uC1/ml)

Factor Removed Remainino Cs-134 l.0E-4 2E-7 500 0.23 4E-4 Cs-137 8.6E-4 3.2E-7 2,700 2.0 7E-4 SI-90 8.8E-3 1.7E-5 500 19.9 3.9E-2 Sb-125 1.lE-2 AE-7 27,500 24.9 9E-4 Ce-144 AE-4 9.7E-7 400 0.9 3.2E-3 Co-60 2E-5 2E-7 100 0.04 SE-4 l

Total (excluding TRITIUM) 47.97 4.5E-2 H-3 8.8E-1 8.8E-1 1

2000 l

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Part of the effluent from this combined system is being utilized for decontamination purposes. As the effort to decontaminate the containment building continues, contaminated water will accumulate in the basement.

Therefore, the SDS/EPICOR system will remain in use.

In addition, this system is being used for processing the RCS.

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During processing of the water, samples were obtained from the SDS influent before and after the prefiltering. The available data for sample points A and l

D are presented in Table 5-3.

The table shows average values for Sr and Cs contents and depicts the water level and volume at the start of the removal of the particular batch. Refer to Figure 5-1 for locations of sample points A and D.

Results of a sample analysis by ORNL, taken from sample point A, are also included. Although some variation is seen in the cesium numbers, there is no consistent treno to show any stratification; in effect, supporting the observations in Section 4.0.

The significant decrease in cesium concentration in the most recent batches is due to dilution by the processed water introduced i

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TABLE 5-3 RB SLMP R10 CESSING Volume of Basement Water In Basement Water Level Batch Isotope Point A*

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ORNL*

(X102 Gallons)

Elevation (ft 5

Sr90 3.23 5.10 6.31 291 Csl34 12.33 8.67 11.20 Csl37 106.00 tai 82.33 I.45 128.00 6

-Sr90 3.78 5.40 6.24 290.91 Csl34 11.98 10.49 136.00 Csl37 112.00 1,14 101.58I.4 128.00 7

Sr90' 3.91 5.06 5.64 290.1 Csl34 9.92 10.00 13.30 Csl37 94.60 :& 101.98 rad 129.00 8

Sr90

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4,19 5.13 5.23 289.54 Csl34 12.82 11.21 12.70 Csl37 115.40 t.u 102.84 L #128.00 '(

9 Sr 0 2.85 4.79 288.96 9

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Csl34 8.92 8.50 c

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Csl37 83.65 77.63

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@ r 288.44 10 Sr90 5.13 5.02 L 4.41 c

Csl34 12.75 11.99 13.90 Csl37 122. 50 t.i : 104.80 i.q 123.00 11 Sr90 5.30

.4.69 5.24 3.92 2b7.76 Csl34 10.7 10.81 13.00

.Cs137 135.674 m 100.39.iel19.00 Sr 0-2.66 5.50 3.50 287.19 9

14 Csl34 9.62 8.45 13.30 Csl37 93.80 L.4\\ 81.79 l <1132.00 15 Sr 0

.2.96 5.65 3.10 286.64 9

Csl34 9.33 9.31 13.90 J

Cs137 93.00 /M< 92.08144133.00 v A

16 Sr90 2.49 2.64 286.02

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Csl34 9.25 7.75

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17 Sr90 3.02 5.05 t a ; 2.49 285.81 Csl34 10.00 9.24 13.10 Cs137 100,00 #J9 94.001,n124.00 18 Sr90 4.18 5.56 2.07.

285.23 Csl34 11.66 11.68 13.40

.Cs137 113.3 i.'!.110.50 > m 128.00 19 Sr90 4.80 1.63 284.63 Cel34 U.~

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-Sr90 4.36 5.67 (

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Csl34 11.64 11.10 13.20 j

Csl37 113.30lii 106. 30 e.t e4126.00 s

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Volume of Basement Water in Basement Water Level Batch Isotope Point A*

Point 0*

ORNL*

(X101Callons)

Elevation (ft) 9 21 Sr 0 4.43 5.53 1.14 283.96 Csl34 13.00 12.42 13.60 Csl37 130.00 ' ^ ' 116.42un 131.00 22 Sr90 4.71 5.47 0.84 263.53 Csl34 13.00 12.70 14.20 Csl37 123.301 L 123.00 n s138.00 DECON WATER ADDED 25+

Sr90 5.18 0.63 283.26 Csl34 11.00 11.20 Csl37 110.00 'o 7 118.00 9

0.30 282.80 29+

Sr 0 Csl34 8.00 Csl37 87.00 33 Sr90 7.00 Csl34 9.31 Csl37 106.67

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4 34 Sr90 5.32 Csl34 6.64 Csl37 76.20 36 Sr90 2.875 5.75 0.36 282.88 Csl34 1.77 2.15 Csl37 20.60 25.25 38 Sr90 3.35 N/A Csl34 0.64 N/A Csl37 8.00 N/A

• All activities are in uci/ml.

+ Staced to tank farm only, processed in batches 33 & 34

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5.2 IMPACT OF FROCESING Cleanup and removal of over 640,000* gallons of highly contaminated water has been a significant milestone in the general recovery effort. It also had its sig71ficance in reducing the general area radiation on the higher elevations to facilitate minimizing personnel exposure because it had been one of the major sources. Lowering of water level had three possible outcomes:

1.

If there had been stratification, reduction of the water level would probably result in an increase of radiation levels. Part of this effect may also be attributed to uncovering other sources in the basement as the water is removed.

2.

If there had been no stratification and no uncovering of sources, reduction of the water level would actually result in lower radiation levels and a consistent or uniform trend would be seen.

3.

If there had been no stratification and there were other sources uncovered during the water removal, a more complicated, (i.e.,

inconsistent or at least nonuniform) trend would be observed.

Ten fixed points were designated on El 305' where radiation readings were consistently taken during the basement water removal to determine how the general radiation level changes with water level. The data obtained thus far, consistent with the previous ones, does not support any stratification hypothesis. Furthennore, although it is not unifonn, there is a general trend of reduction of the radiation level with decrease of water level. The nonuniformity of the data may be attributed to the uncovering of sources in the basement when the effective shielding of the water was removed. This su3 ports the third possibility mentioned above.

c It is noted that less than fise percent of the water subsequently left the building in vapor form as a result of containment air purges, a

SECTION 6.0 CURRENT CONDITIONS 6.1 WATER LEVEL By late May 1982, the water level in the basement had been reduced to less than four inches. The subsequent decontamination activities periodically increased the water level. To date, an estimated 105,000 gallons of processed water has been used for decontamination purposes, and has returned to the basement. The continuing decontamination effort is estimated to result in 10,000 gallons of water being collected in the basement each week for the remainder of 1982. There is also an inleakage from the RCS, but it is insignificant relative to the decontamination-induced increase in water level.

(The most recent data shows a leak rate of 0.018 gpm.)

An upper limit of 100,000 gallons has been set for the water in the basement, including the amount in the SDS/EPICOR-II systems. This limit was set based on the available tankage in the event of a need to transfer the basement water. Therefore, continued processing of the water is necessary to maintain the water level below this limit.

6.2 RADI0 CHEMISTRY AND CHENICAL COWOSITION A quick visual inspection of the renaining water on June 24, 1982 revealed a dark brown sediment on the floor. Photographs of the sump water in the vicinity of the open stairwell were taken and the relevant ones are presented in Figures 6-1 and 6-2.

The preliminary visual inspection estimates solid sediment less than one-inch thick below approximately a half-inch of clear water. Inspection personnel also indicated that there seems to be variation of these thicknesses from area to area. Figures 6-1 and 6-2 show photographs of the water before and after a scoop of the sediment was taken for analysis.

The pictures indicate the sediment to be thick enough to retain its shape.

The sample obtained was analyzed by GPU, Westinghouse Hanford Engineering Development Laboratory, and Oak Ridge National Laboratory (ORNL). Preliminary results are obtained from GPU, Westinghouse, and ORNL on isotopic analysis and from Westinghouse and ORNL on chemical conposition of the sluoge. Because of

- the method employed in sampling the sediment, the solid content and other related data are not expected to be representative of the basement sediment.

The slight variation in the results obtained by the different labs, apart from methods of analysis employed, is largely due to the way the sample was divided into three parts. However, the results give good general information, although they may not be sufficient for planning purposes. Planning activities we rant a good understanding of tcm contents 2-d aro nt of sludge.

1 limintry c!?ur:tlens ere that a Is?;e frtctic7 of

• • a cc'!d sEJiment pas 3

river mud att:iocted tc the 100,00; ga1107s of w;ter ths. leakeo.'ron tr.e river water cooling system.

Table 6-1 presents results of isotopic analysis of the basement water by Westinghouse.

The data suggests that the major curie sources were Cs 134, Cs 137, and Sr 90. Cesium was mainly in the liquid phase while strontium existed main.'y in the solid phsse. The fonner is cons} stent with pr?"Jous analysis, ano the latter is due to higher solubility of Cs relative to Sr.

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TABLE 6-1 RADI0 CHEMICAL ANALYSIS OF BASEMENT SLUOGE (ANALYSIS BY WESTINGHOUSE)*

Solids uC1/1 Filtrate Total Isotope solids uCi/o Oricinal Slurry u Ci/l y

Co60 11.4+.2 (2.98+.04)x102 (1.1+.2)x10-1 (2.98+.04)x102 Sbl25 136+1 (3.567.02)x103 (2.57.3)x101 (3.567.02)x103 Rul06 35.9+.3 (9.4+ l)x102 (2.37.4)

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~

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ND

~

(3.7+I.7)

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(4+2)x10-2 (14 7)

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ND (2078)

(1 J1.06)x105 (1.16.06)x104 Sr+Y 90 (4.9+0.2)x103 (1.29+.06)x105 1

2

• Source: Reference 8 Table 6-2 shows preliminary results on the chemical composition of the sludge. The analysis was conducted by ORNL. The data in the table show slight differences from those obtained by Westinghouse. However, both analyses indicate that the sludge contains large amounts of copper, titanium, zirconium, chlorine, sodium, indium, and tin. The large percentage of the solids (over 25%) appears to be copper.

TABLE 6-2 TMI-2 SLU0GE SAMPLE CHEMICAL COMPOSITION (ANALYSIS CONDUCTED BY ORNL)+

(ppm)

Acid Acid Element Solids Sucernate Insolubles Element Solids Sucernate Insolubles Pb 300 8

Fe 8K 0.6 1000 La 2

Mn 1K

'O.2 20 Ba 300 0.1

<5 Cr 400 3

200 Te 900 2.

70 V

3 0.8 Sb 10 5

Ti 800

<5 2000 Sn 1000

<2 70 Ca 2K 30 100 In 1.5K 1

700 K

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0.7 70.5 8

3K 3K 300 Br 10 Ce 30 2

As 30 1

Tc-99

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4 Zn 2K 30 Cu 40K 5

300 Ni 12K 0.5 200 Co 10 0.1 2

+ Source: Reference 9 -

With respect to transuranics, ORNL indicated 95.403 mg of plutonium and 64.251 mg of uranium per litre of sample. Westinghouse, on the other hand, depicted 160 mg of plutonium and 101 mg of uranium per litre of sample. The two analyses, nevertheless, show uranium to plutonium ratio within 6.5 percent of each other.

The two analyses were also in agreement with regard to the pH of the water.

ORNL indicated a pH value of 8.1 and Westinghouse reported a pH of 8.2.

Further analyses of samples taken from various points in the basement are necessary for drawing conclusions. Better methods of sampling will have to be devised to guarantee representative samples.

The soluble and suspendible contents of the water are expected to be diluted by the sig11ficant increase of water level due to the continuing decontamination effort. Therefore, the soluble or suspendible curie and chemical content per unit volume will be reduced as the SDS-decontaminatien-SDS cycle continues. This is also caused, to a limited degree, by the leak from the RCS. The Curie content of the reactor coolant is currently lower than that of the basement water. This is primarily due to the bleed and feed method of processing the RCS via the SDS and, to a smaller degree, due to leakage makeup with clean water.

This. point is further emphasized by the significant decrease in the sodium content of the water since the decontamination began. The only source of sodium in the water had been the NaOH storage tank that released the solution into the building via the containment spray system and the RCS.

6.3 RADIOLOGICAL CHARACTERIZATION Several efforts have been expended to radiologically characterize the reactor building basement. Strings of TLDs in series have been suspended between El 305 and El 282'-6" at different locations. Access for the TLD trees was attained U1 rough available penetrations and manholes. Representative data of TLD tree analysis are presented herein. The data are from TLDs suspended in the RCDT cubicle, beneath the "A" core flood tank, and in the "B" D-ring. In the first two cases, attempts were made to give directionality for the data obtained. For details, see Reference 7.

Preliminary interpretations of the data are presented below.

6.3.1 RCDT Oubicle

.The data from analysis of the TLDs suspended in the RCDT cubicle from El 305' via penetration R-37 is presented in Figure 6-3.

There were four TLDs at five feet intervals along the string. The "A"s in the figure indicate readings from TLDs facing to;ard the tank and the "E"s represent data from TLDs faciN the "A" D-ring well. A close 1:e': at the c..h: i;] geste the followiro obserystions:

1 A significant increase of both beta and gamma levels is seen closer o

to the basement floor.

FIG 6-3

"- s aw e*w a =% pum TLD TREE ANALYSIS i

6.zi4 o.eos 6.7 s 3 o.sss RC DRAIN TK. CUBICLE 2

9.744 5.G42 9.857 6.941 3

20.zo 31.4 0 28.80 647.30 4

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o wall and the RCDT outer surface.

The readings suggest high level of contamination on both surfaces. This may be attributed to the imersion of the RCDT and the wall in 8.5 feet of contaminated water for over two years.

Contaminated water in the tank is estimated to contribute o

sicfificantly to the gama readings obtained.

6.3.2 Beneath CF-T-1A The data obtained from analysis of TLDs suspended beneath CF-T-1A into the basement via penetration 220 are shown in Figure 6-4.

There were four TLD systems attached to the string, each with a TLD facing toward the wall and one facing away from it. The "A"s indicated data from TLDs facing the east wall of the refueling canal; the "B"s indicate data from TLDs facing away from the wall. The following are preliminary observations:

Both beta and gama readings are higher closer to the floor. A o

significant increase is seen below the highest water level attained in the basement.

o The TLDs at the end of the string show relatively high readings.

This could be from particles retained in the radiation monitor cabinet (IC-R-1092) due to the filtration effect as the water level decreased or a pool formed on top of the cabinet during reduction of water level that has subsequently dried to via evaporation.

6.3.3 Inside the "B" D-riro The data obtained from analysis of the TLDs suspended in the "B" D-ring along the walls are shown in Figure 6-5.

Nine TLDs were attached to each of the five 85 ft long strings. The relative positions of the strings in the "B" D-ring are shown in the figure. A close look at the data suggests the following:

o The readings cle'ser to the floor are significantly lower than those presented in Figures 6-3 and 6-4.

A possible explanation is the low pressuIe warm water decontamination of the D-ring walls. This is suroected to have resulted in washing the sludge into the incore instrumentation chase, which is one foot lower than the 282'-6" floor elevation, thereby eliminating contribution from the msjer source in the base snt.

o There seems to Le high bets sources at *.he tcp of +.ne D-nr*;

above the reactor coolant pumps RC-P-2A and 28.

o Lower sections of OTSG-8 and suction lines of the ptsnps appear to be hitt gama sources.

o The upper secticq of PC-P-28 appears to be a high gama source.

9

"'i -

TLD TREE ANALYSIS

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SECTION 7.0 a

CURENT AND FUTURE TASKS i

The following are tasks that are currently underway or in the planning stage for near-term inplementation:

Remote decontamination of El 282'-6" i

o o

Visual inspection of the basement o

RCDT inspection and sampling Removal of the remaining water and sludge.

o 7.1 REMOTE DECDNTAMINATION OF EL 282'-6" Currently, efforts are underway to decontaminate the walls in the reactor building basement Areas of planned decontamination are shown in Figure 7-1.

To date, Area 1 has been completed and Area 2 is in progress.

i 1

Decontamination is being performed by lowering a troll ball assembly

• at l

i ircrements of five feet beginning at El 300' and flushing the walls for j

specified periods of time. Access to the basement is achieved through the j

seismic gap.

There are plans in progress to estimate the effectiveness of the i

4

' decontamination. Pre-and post-decontamination data are being generated using i

TLD strings at specified locations. The data obtained will enable evaluation of the effectiveness of methods of decontamination in use.. They will also provide more comprehensive data for the radiation levels in the basement.

s i

7.2 VISUAL INSPECTION

' Efforts have been initiated to visually inspect the basement area using a Ismote. control color television camera. Available tapes from the first effort show the upper elevations of the basement at two different locations. The j

water and lower elevations are visible only in one area due to lack of li@ ting.' The first looks indicate the following o

There is very minimal corrosion visible in the area.

2 There seem to be some reflective insulation pieces missing from o

pipirg.

Peinted carbon steel ccmponents appear to be in ? cud shape.

i e

o Tie general area is clean.

I i

Plans are in progress to improve the lighting system and inspect the basement, l

' including the sludge on the floor at several locations.

}

• Itus is essentially a suspended spinning sphere that sprays water throup l

holes on the surface at about 2500 psi.

i

)-

F G. 7 u REACTOR BLDG. BASEMENT Fl.USHING LOCATIONS I

ggtEMIC 4AP SEl&MIC SAP 2

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+

j 7.3 RCDT INSPECTION AND SAMPLING l

The RCOT had been one of the major participants in the LOCA. The condition j

and contents of this tank are not sufficiently clear at this time. Efforts are underway to visually inspect the tank and the cubicle via a remote controlled TV camera.

There are also preliminary plans to sample the tank and the basement water. These activities are to support planning of cleanup of both.the basement and the RCDT. The first look into the cubicle indicated that pipes and conponents are intact. There also seems to be minimal sign of

+

corrosion and some deposits of baron crystals on pipes. The view angle of the l

first attempt was limited. Further efforts are required for a more l

comprehensive visual inspection.

7.4 REMOVAL OF THE REMAINING WATER AND SLLOGE Major considerations are now b?ing given to the mmoval of the water and sludge in the basement. This is important because the basement water and i

sludge is considend to be a major contributor to the radiation levels on the w per levels. A good understanding of the contents of the basement water is i

necessary to devise a method for mmoval and clean @.

Plans are underway currently to sample the sludge at different points to get a more apresentative evaluation of its contents.

i I

l l

E EFEENCES 1.

General Public Utilities, May 5,1982 Reactor Building Water Level Measurements, Interoffice Memorandum from R. H. Greenwood to L. P. King.

2.

General Public Utilities, September 10, 1981, Reactor Building Floodin0 Followino TMI-2 Accident, Interoffice Memorandum from R. H. Greenwooo to D. K. CronebeIger.

3.

General Public Utilities, October 12, 1982, Radioloalcal Source Terms and Field Calculations for the Unit II Reactor Buildino, Interof fice Memorandum from H. K. Peterson to C. A. Shorts.

4.

Letter from W. D. Shults of Oak Ridge National Laboratory to J. A. Daniel of GPU Service Corporation, September 14, 1979.

5.

U. S. Department of Energy, August 1982, " Containment Sunp Radionuclide Distribution Studies", Draft GEND-IW-011, Vol. II.

6.

K. J. Hofstetter, C. G. Hitz, T. D. Lookabil, S. J. Eichfield, " Submerged Demineralizer System Design, Operation, and Results", General Public Utilities Nuclear Corporation,1982.

7.

EG&G, Characterization of the THI-2 Reactor Building Basement, attacMent to letter from H. M. Barton to K. Pastor, September 1,1982.

8.

Analysis of TMI Containment Building Sump Sludge, AttacMent to letter from J. J. McCown of Westinghouse Hanford to H. M. Burton of EG&G Idaho Inc., September 10, 1982.

9.

Oak Ridge National Laboratory, October 27, 1982, Preliminary TMI Sludge Results, Intra-Laboratory Correspondance from J. A. Carter to D. O.

Campbell.

e-juClear Memorandum December 6, 1984 SDS BATCH REPORTS Date Sut;ect 4410-84-M-0698 TMI-2 Licensing From Manager, TMI-2 Licensing Locat.on J. J. Byrne To Deputy Program Director W. D. Travers u

Attached for your information are Submerged Demineralizer System (SDS)

Batch Reports 106 and 107 which represent processing of water from the Makeup and Purification Demineralizer elution project and the Reactor Building Sump, respectively.

If you have any questions, please contact me.

/

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J. J. By ne Extension 8461 JJB/JCP Attachment cc: Site Dperations Director, S. Levin - w/o attachment CARIRS - THI i:

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I inter Office Memorandum

'uly 21, 1983 J

Date 4410-83-M-0634 Gar Sutuect SDS BATCH REPORT To L.

H.

Barrett locat on TMI-2 Licensing j

Attached, for your information, is the batch report for SDS Batch S-057 representing the processing of Reactor Building decon water.

l j

If you have any question, please call me.

J.

. Byrne Manager, TMI-2 Licensing JJB/grs

.t Attachment i

CC:

E.

H. Gischel w/o attachment

.l J.

E. Larson 1

T.

D.

Lookabill b

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PATCH #

sesq l

DATE 1/s-it / s3 l

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f SDS FEESSl% PATCH DATA 1

f i

PROCESSINGS@iMRY(0140 3

u.)

SYSTE

()

RADIONUC'IDE AVEPAGE INFLUENT AVERAGE EFFLUENT l

Sinotalui 90 '

i9 s.mio 5 I

CEs:ui 134

i. n u o '

i came

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g/4

4. u s 9 6'5aio

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!0NEXCPA"GE' DEPOSITION

.AA AB

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Inter-Office Memorandum Jote June 23, 1983 E Nuclear 4410-83-M-0562 s~.,

sos mxH.

Vo L. H. Barrett t ocat on TMI-2 Licensing

/Ettached find SD3 Batch Report S-055 representing the processiig of Reactor Building decon water.

Picase feel free to call no if you have any questions.

/

/J.

.B Panager, IMI-2 Licensing JJB/JEP l

Attac h.mt CC:

J. J. Barton w/o attach:mnt E. H. Gischel J. E. Larson 6

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SUMMARY

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- ' DATE/ TIME -

GALLONS A

C D

E-F..... G 11 e.

Cesium 137 n

3.4 sal s).-

..ite -

.O(4) b/3

- 05'*/ **S'*5

' * ' 5/.., s

- 2..

2.9

.ts Sr=90.

M1)

_ a t..)

Gross By

.s(-th

,M!O

.s7 Cesium 137

3. 3 35 v.+ 0 at:0

.i.i(:~d

'Sr'90 6+

a +55/'5 *9 8587W s.

,a i.1

.24

-239) j f(..q Cross'Sy a'1 i A( 2)

_MP S)

Cesium 137 s

32l-s) i.S t4) i Al >)

6/5

/*'517

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.Alb)

."3t(q Sr 90

$ 5'23 i.s '

17 Gross By

_ 10*4

. i's al-t) 4 Cesium 137

~

6 os**

AA-

' ^ l' '}

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" Y m.

o,

,.S i.8 53

?sb)

_3&.)

Gross By 35 24 2)

_ bel >)

- Cesium 137--

csajMs a.s 2.5

. i.B(- a) 8.,u) h(i ')

3 cob

.. Sr.90 I

'3*tt' s.9 I

67 5.'l 9

_n..(

)

'- Gross Sy

.35 21l-1)

JkO

~

Cesium:137 ony4y.

3gs a.3 aS

>.t0 6). m)

_t;H)

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. ~ l

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~

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sal 3) 15( J 39 13.k4 3 M->)

~,

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~

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s

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+4L ld(*)

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)'

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~

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1

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W

r --

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SDS PROCESSING SAMPLE

SUMMARY

~,

BATCil 5055

~

DATE/ TIME:

GA5.LONS A

C D

E F

G Cesium 137

2. i a.i s.u.q '

M2 i.q-s) 5 "S'3/565%

Sr 90-i.w i.s

.e3 i..s t..)

p(.)

Gross Sy 45 4abq

_1( 3)

Cesium 137 6

Ls_

s. 5 JJ!-t. )

sa(5)

.uts "

os*7/**5

%3bs/5"64 u

Sr 90 2.5 a.1-

'6 tabs)

Ai6 s)

Gross By 44 4104

_ t,.M-s )

Cesium 137 yit eso3ds3g 6'519 cn%

u

. 2 3_

6.7 t-t) 11(-s)

.st.d Sr 90 i.9 5.4

.es 1.5 t- )

.#A s)

Gross Sy

.5 4 ibt)

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Cesium 137

.,w_

o.5 7ak) i4Q M(-)

%4 w'@ous is Sr 90 a

i.7 s7 m

.M2)

.15( i)

- Gross Sy 51 41(-t)

L@ *)

Cesium 137 bg oso,j 3,o4g

_aa_

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i.%

A.1 s.1

.55

. a.!(- > )

Gross Sy.

9 5.4Q

_M P s )

Cesium 137 Sr 90 Gross Sy Cesium 137'

]{

Sr 90

~

Gross SY e

O

c Inter-Office Memorandum sate May 4, 1983 Gar 4410-83-M-0418 Subiect SDS Batch Report To L. H. Barrett Location TMI-2 Licensing Attac8dd for your information are batch reports for SDS Batches S-046, S-047, and S-048 representing the processing of Reactor Building decon water.

Please call if you have any questions.

/lJ. lJ. dyrne 0_

Manager, TMI-2 Licensing JJB/JEP Attachment CC:

J. J. Barton w/o attachment J. E. Larson

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Inter-Office Memorandum e

March 3, 1983 4410-83-M-0207 U

Gar Suciect SDS BATCH REPORT To L. H. Barrett

~

Location TMI-2 Licensing Attache'd for your information is the SDS Batch Report for batch S-045 representing the processing of Reactor Building Decon Water.

If you have any questions, please call me.

. B rne Manager, TM1-2 Licensing JJB/JEP Attachment CC:

E. H. Gischel w/o attachment J. E. Larson T. D. Lookabill R. P. Warren e

TE E !?

y

(

6 s a ese

EATCH#

sov:

DATE a/ m-zz / 8:

GAU_CNS esW SDS PP.0CESSl% BATCH DATA P,0.0CESSItG STEARY (ut/ML1 S_YSE A'ERAGE EFFLUErfE I

AVERAGE INFLUENT BADIONUCLIDE

9. o s u o'"

3.o n 2cits co-5 STRONTitn90 c..<,s n o '.

4.6 os uo"5 CESim 134,.

O.115 CESILM 137 Il lb 154 -

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1.164 (d)

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_4127d*3 TOTALCURIES-EsER STTRRY STAcEn:

8 05 %

-RBWATEa I49 's t03 TOTAL

~

2' 53 A SL-T ICTAL CURIES DEPOSITED

(

CE353' B134 55 6 WATEE

.cest<u l~.TA CLC.IE5 DEFCEiTE i L'5-+0."?'

i sT A_

~ M B?S II-k *. ; C W' W.'. DMS C

1 i

i

• n 7O OO 7 --

? 7 t~

m&+

y<! a..

1. %. --

.. v r

.e

.23 r

~=

=

Jf E! d M

• l d; N i  ! c' M Ji di

.i j

l j

l l

I o

l l

1 i

7>c.

O?

-7 v

v.> a o-f

.,.. 2

c. s 2

v. ;

.l e t 3 ri t T

s' vi M

,d d: 61 el di o; ualMa Ci

• i 01 dl A

m T

T T

7 oe a e a co

% T 7

N

.j J S

".l f m

e4

=

n J

o,*

ji f, =

n W

-l 4 0

~

I, T.I f*

e-7 d.

e r r ni e e

a w

e m

8 o

=5 ds$

m a

4I D N"l l

4 7

dV 9,

t ml }

8 u (

M e

g7q m f i

4 f

0 2: =

O.

-0 E-Mm <

31 CI4 Oo

=.:

m gl I

i a

< vs

.I et

.9 g

el g 1

8 9 M1 e

m 7

~

@l O

T M

o O

C 3

A e

C o

e N

r o

3 c_

g 0,

d Q

~~'

H o

O Y

o d

Q Q

Q e

o o

n 0

a-O o

(

Q e*

A d

O O

d 4

r.

o w

n o

f(

~

~

n

~

~

~

~

M.

.M.e

>=

M M

M M

M p

M

. ' = *

-+

>=

w w

p c

ci c

cz2 a

c c

2 8

5 5

8 5

G o m 3 o m 3 O a 3 o a O n 3 o fa

=.3 4

O VI w O ul

-* O in

+ O W

.' 3 3 O w

~4 O

M O

M O

f4 O

M Q

M O

• 3 Q

^

• O M

~t O

sn

'-4 O

'A 0

he u

"J L

6 "J

h h

3 L

u o 4 u a

6 s.e Q

4 La U

"A O

O C4

• J O 03 O O C/3 O U f/3 O Q A O U

• A U

-~.....;..... _,,.,,

e

Q [i MTCH #. 7so + i MTE 24 > /6 : - vitre s CAURIS 49343 SDS PPDCESSE MTCH MTA

. 9a/

PROCESSING SLM%RY (ul/ML)

SYSTD1 RADIONUCLIDE A

AVERAGE INFLUENT AVERAGE EFFLUENT

-3 STRONTitri 90 3.423 9.+it = to CESitti 134 A m5 = 1O"'

3.M3 x to"'

CESitri 137 9.9o t 2 ie s.,46 3.2ee te-5 ION EXUANCE DEPOSITION lA 2.3 2_C

__D llNER#

D acete b t c o t z.

Dtce u

"/A THIS PATCH C%LLONS 49343 49343-49343 ESitti t%7.M 5 2.co9 s.is s f-s)

OtE llF4 @

1stsis iss.us 2 s.tu TAL LURIES 4o75.s 2 A 5i5.ii7

%.s 5 t

/

CtEULATIVE (THROUGH -

(

ABOVELINERS)

ONS 14566B e47183 9Mzo

-~

Silti 4as.%t 2.m t 4.,2M9)

TRONT(tfi90 iws. iss 2*s.ws s s.s%,

OTAL W RIES to 464.65 4,= 2.os t 57.is e WATER SLM%RY STAGED:

.RBWATER 763607 0TAL I % Sci 9 OTAL CtRIES DEPOSITED 14'60.e44 Partss=n:

g WA75p -

iso 439 JOTA,

iv ili7 5 10TA UF.IES DEPOSITE'.

6,tA si.5 Cc.

a:. ret.

1 *.M 9 '

t..,2 wA>.

bec.m h *.'s s.a

~

f h_

SDS PROCESSI-

'JtPLE SUFRIARY BATCil 504%

liatc/ Time Ga1Lons A

B C

D E

F G

11

r. - t..m i 11 33 s 2.

n/st/** 150 0 g

3.9 r....-g3 s '. : ii,..r 1 17 S.t T

y>f a its5 2 sw.

2 2.

.,., n e

a :,..., py a '.. ; i i i, I i/

T.h T.5

.u,-

'l*/*3

• * =

4 r92o 2I 21 ny

..., i..,,, i u s.1 5.3t 9) 4.sl.5) 2.st: 0 W.tes aas?

naos s.s o.19 tq-3)

.g( )

.:,.i.,

,:,.... n 24 i.9 a.s s ag(2)

....i,.. in 85

%<)

4.M:5)

>g.5)

/'8/43 lett 11950 3.1 0.88 4.5( 3}

_T.M-M)

.s o c,

p4_

i. i o.u ita) c..- i.,m iu e5

.t>( 3) 4.4-5) 2.i(->)

'It /s) es4o w9ea ts_

i. e o.u.

Ag.3)

i.,

2 o.ts 1.43) i.s(-2) c,... i i.,, in s.:

4_.s(-3).

1 1 5 (. 5 ) A1(-5)

,I'*/*5 esto 4 B167.

3.3 2.s o.53 4.1(-2)

.:,., n sy 23 3.1 o.19 e.is

m s

, =. ~.

.y Inter office Memorandum cata August 30, 1932 l' O1Nuolear m0-n-m Sue;ect SDS Batch Report To L. P. King Location TMI-2 Sit e Ops.

Attached please find a batch report for SDS Batch S-033 representing the processing of Reactor Building sump water staged in batches S025 and S029.

If you have any questions on this information, please contact me.

72PWW pg E.

H. Gischel Plant Engineering Director TMI-2

~

EHG:TDL:hh Attachment cc:

J. J.

Chwastyk W. T. Conaway J. C. Devine C. G. Hitz K. J. Hofstetter J. E. Larson (2)

T. D. Lookabill (2)

R. J. McGoey S.

B. Presgrove (2)

T. E. Rekart B.

G. Smith H. K. Peterson e

f

3.Tci ='

xu

';,TE af. - - a 3.

ES ??CESSii6 'sTOi ~J'.TA PPDESSING SLM%RY (ut/ML)

SYSTEM RADIONUCLTDE A

AVEDAGE INFLUCNT AVERAGE EFFLUENT

'STRONTim 90 7

a.4 n n a

• CESIlli]34 -

9.3 6 i s1o'8 2.3 5 a so

• 3.c't mi o'3 CESIlfi 137

,v,/q toro. 6(. 7 ION EXO %NGE E POSITIOV D

M a_C

__D l.INER#

D' bloonB

'bloolfo Tsts B Tcs 6ALLONS

'3177 +

31774-3'217 4 ESIlli nuts 4 tw A.%7 i. +19 ONTilfi T w.151 2.ees

.64.54 4 OTAL LURIES 2s b44.e n 4.< c4 v12.e -

OMJLATIVE (THROUGH ABOVE LINERS) i ONS M1436

S1'I +3 41115 SIlli tus4.ces nii.ow 21.553 TRONilt.fi %

s +c1.w i 2co..t r

.too e s OTALCURIES 3osu.en 44n3 444.Az2 WATER Siff%RY STAGED:

% WATER

(,422.12.

. 0TAL s595279 OTALCURIESDEPOSITED n'96.+oI

• 4 SEE BA h 4 % 006 PROCESSED

• r

$ WATER

(*3(=7 40 0TAL t114es3 OTALCURIESDEPOSITED 47i836.54 144SS2 R c.s e u re rt.

1s1" *'s

,/

u s ua.e m, _

.g i

SDS PROCESSING S/

• E

SUMMARY

BATCil s'o:53 DATE/ TIME GALLONS A

C D

E F

b 11 alum 137 iso 8M 4_ab) 1(-3) 90 62o a757 i.7

.1[-3) i.b hl-9 ces By

• 11 201 2.VI 1 AM-i) asium 137

a. M 12L-3) 34 's) is o 90 A

oB32 9 114-1A 1.it*)

2.1 i A l-t) oaa By isi 1.a5 2.s t i.co cium 137 lah) 3dL4) 2B_L->)

iso 90

%t 075B lb8CL 1.3 lit-i) 1b 2C-t) rO3G By

8 4 M

8

cium 137 la6)

' 6t9

.3a(,-3) i=

90 B/z.3 obi 3 a.4cB6

7. 2.

I i3 3 M-t) c e By i4t WI 2bB

.1d5 cium 137

.Lut-2) 33t-2) 4,51,9 )

ico

- 90 TV24 0815 3 t164

,. z.

i.3 i. 2.

s.1(- t )

-oaa By 16L M

2.6 J,.2 6 cium 137 90

'oco By eium 137 90 ose By

e Inter-Office Memorandum

[

Nove:nber 19, 1982 e

4410-82-M-0283 U

ear Suciect Beu"G REPORTS To L. H. Barrett Location IMI-2 Licensing Attached for yotr inforration is a batch report for SDS Batch S-038 representing the processing of decon water from the Reactor Building Strp, and batch reports for EPICOR II Batches 146,147,148, and 149 dich includes a processing sinrary of SDS effluent water originating in SDS Batch S-038.

If you have any questions, please contact rne.

hhh~

/

J. 'J. Byrne

(

Panager, TMI-2 Licensing JJB/JEP AttacS. ent CC:

E. H. Gischel w/o attachtnent B. K. Kanga J. E. Larson 3

T. D. Inokabill a

g

--U R

N,C o.a

'y no em 3

is f;*

h N,9 w

z A.

i

e Wnvi9 M Inter Office Memorandum Date November 17, 1982 mm a 4240-82-889 E

gg Sueject SDS Batch Report To -

L. P. King, Site Ops. Director Location TMI-2 Bldg. 222

, Attached please find a batch report for SDS Batch S-038 representing the processing of decon water from the Reactor

,' Building Sump.

If you have any questio.ns on this information, please contact me.

fo$ E.

H.

Gischel Plant Engineering Director TMI-2

{

EHG:TDL:hh Attachment cc:

J. J. Byrne (2)

J. J. Chwastyk W. T. Conaway J. C. DeVine C. G. Hitz K. J. Hofstetter C. M. Hrbac J. E. Larson T. D. Lookabill (2)

R. J. McGoey S.

B. Presgrove B.

G. Smith H. K. Peterson ummu

e MT01#

seas MTE it /i-i+/ sz SDS PP.0ESSlf6 MT0i MTA s

PRO ISSit6 S&TRRY (ut/ML)

SYSTEM RADIONUCLIDE e

AVERAGE INCLUENT AVERAGE EFLUENT SfaamtM 90 3.B33 a. sho-*

CES!!N 1%

9.5 x \\0

A.c44 io-5 Il 463 M49 x iD'

.CESitM 1T/

-Aminat:tS.o ION ENCME DEPOSITION M

M a_C

_D LINER #

W U.

Dum.1 h37 TsrsBATcs GAu ONS 44i,7 44i tv 44i17 ESILM u*u+1 7.ne(.0 4.6,r.(.5) w.m m +s-a.*ow( )

ONTJ,lN @

AL LURIES Sse s.5-B 1w.7 51 6.ssBC-*)

l' OEU' ATIVE (T)EOUGH '

(

ABOVE LINERS)

.S i9swes 984w 44irr SllN am.n1 9.e.,st-)

4 v,t(.3)

TRONT 9 de.94 44.55 2.ao W-il OTAL IES but w+

9 c.m+

6.<, s s (..)

WATER SlH%RY STACED:

BBWATER 7ises r i'n '5%O OTAL 0TAL CURIES DEPOSITED ek 272s.6 Process =D:

~T 'b i o %

% Rt,s 10TAL d. '2 e 3 ICTA CtF.*E; TEDOS*F

"' ' 3 c 5 7 a e c. F.i 'l gg om

@W5 c.::.r. m c X to:.rt c

SDS PROCESSINC SAMPLE

SUMMARY

BATCH 1s038 Date/ Time Callons A

B C

D E

F C

11 Cesium 137 B.3 B.'1 1%[2.

44 %

9 000 3.6 3.6 Sr 90 Cross SY an.S 20 Cesium 137 1.r 77 Sr 90

"/4 I'OO 2%~18 a.9 M

Cross SY tB it Cesium 137 34-3_4_-

'4 0800 41681 q4 c,. L Sr 90 Cross SY

$v_

64_,

C:sium 137 I4-4.bl L) 2.L(W) 3tt(-Q b

I O

g7 0b 3,g o3 3,43) 2_gg)

Sr 90 3dm t.li O.524 0.4 $t Cross SY lt 3.V3) 3.4b5) 16(5)

Cesium 137 0

3.6

't A (-a) 7 (W)

Lif4 Sr 90 16 0.56 o.i3 935 Cross SY b

3il-*)

l-5) in t 503)

Cesium 137

/ti l'l+$

AB536 4

o.L't i.it.3)

Jgt.,)

Sr 90 o.O 23.

a4_1_

p,gg Cross Sy i3 s.il-0 43-5) 4.R s )

Cesium 137 Sr 90 e5 A3236 3.7

o. 'i 6 4AS) a_ib)

'D A7 0.t.B O.0 9.i s Cross 6Y 6

0

e gEt 09 El

4 -/ / -l [Yf Inter Office Memorandum Cate September 8, 1982 4240-82-689 Sucie:t SDS Batch Report To L. P. King 1.ocation TMI-2 Site Ops.

Attached please find a batch report for SDS Batch

.S-034 representing the completion of the processing of Reactor Building sump water staged in batches S-025 and S-029, and SDS Batch S-035 representing the processing of water in RCBT 'C' (originally processed as RCS, but left over during feed and bleed due to chemical addition).

If you have any questions on this information, please contact me.

p/ 1. H. Gischel f

I.

Plant Engineering Director TMI-2 g

EHG:TDL: hh i

Attachment cc:

J. J. Chwastyk W. T. Conaway J. C. DeVine C. G. Hitz j

K. J. Hofstetter 1

I J. E. Larson (2) t T. D. Lookabill (2)

/

f/

R. J. McGoey

)

/

S. B. Presgrove (2)

T. E. Rekart I

.B. G. Smith

/

H. K. Peterson

Q Q

MTG #

soM MTE G'/1,no h2 GAU.MS isq45 SDS PPDESSING MTG MTA PR0rRSING SINARY (ut/ML)

SYSTEM AVERAGE EFFLUENT A

AVERAGE INFI1JENT RADIONLrtIDE S

7. m sci 6.32 STaoNTilN 90 2.14'10 bb4 CESilN 1 %

1BWO

%1 CESIlN'lIl N[A ION EXCME DEPOSITION a_A

.a3 a_C

._D

~

>20o12 LINER #

T560s 4

)2o0%

Twis BATcs 5S9+5 is445 is44s 9A4sf.2)

Cw.LONS 1.9 I 571o.452 SILM t.4.7 54 4.159 1 TRONillN @

3 c+. tit 3.105 OTAL ujRIES JtW 9.9&i

_niid l,-

_ MUTIVE (T)RoVGH-c O

ABOVELINERS) s tieno se44s 3it%3 q A*W)

ONS ten

• AS7

~2(A3 245 % ;

' 4.1s9 _

SIlN TRONTilN @

mi.wi 3 to il7 G7c5_

OTAL QJRIES 14nct 196 WATER SlWARY STAGED:

f t

Mill 2.

f.3 WATER 4198779 0TAL 5%4c7W 10TALCURIESDEPOSITED 4 v.E eAba sees Pmssen:

unis 83 WATER t14 7oU i 0T/,'

< 8 EMCw l0TA CLF.IES [EFOSF 2M 952 in uwr.

abIW A15 M.5 Coc.nC.i h r O

- ~.

SDS PROCESSING SAMPLE

SUMMARY

BATCH 3034-DATE/ TIME GALLONS A

C D

E F

G H

5 t-3)

Jill-1) 47 2sk2)

C2sium 137 Sr 90 UB 0B36 40 Mo b1 1 l_

S s(-t) 142) wo 31_

14.-4) 9.34.)

Gross Sy 9o -

AT4)

_43.4) 34-3)

C:sium 137 16 LM GBc4 6

L3

.13(-2)

Wa)

Sr 90 slo 16 t.ab t 06 Gross Sy Cesium 137

_hi_

ikt) 4A(-1) 13% 3)

Sr 90 29

@S

\\oSO4 w _

3,t 6,g4) 449)

$30 2.i}

t.lfs a.og Gross By bl 3x4)

_ tat-s) 23(a)~

Ceaium 137 VL'l IS45 0

41 3.Qa) 7.t(4) yga)

Sr 90 111 84

}.16 Gross By

• 2-41

_ut4)

.13(.>)

_?_d(-s)

Cesium 137 4"

l694I 35 f.9(4) 4M4)

_g{,-3)

^

Sr 90 66.4 l+5 Mp)

U R-i)

Gross By Cesium 137 Sr 90 Gross Sy Cesium 137 Sr 90, Gross By 9

%., /

MTG #

sou MTE BIso-st/ 6z. _

25s+

CnLONS SDS PROESSING MTG MTA

(

PR0rRSING Siff%RY (ut/ML)

SYSTE AVERAGE EFFUEt(T A

AVERAGE INFU BIT _

RAD 10NucM DE 43C-4 G,3 STRONTIm 90 SI-5)

G M-N CESIW 1%

S. 2.(- 4) 2.9 23 CESIW 37 Gy %gh)

IONEXOWGEDEPOSITIm

?_A 33 3_C

_J)

"D2co42.

31oc7.6 LINER #

ytect4-IHISEATCH sw sss asbt J 5 set)

Cwu.ONS 5.57.(-9

_ s..+ i (..J 34tbE_

Sim is.ite _

e6 3 5_

iT W @

li 6L i16-OTAL IES la'*.nt CtMP3TIVE (Tl410VGH ABOVELINERS) 1251ce ii<nsa J156w L i.ss ( _i)

JS 2ews.71s

_ 16.c is _

s. s3_

SIW

_ e e..1

_ane: s ;

s ie.* e s TR0fl71W %

424ssn

_ 6ii.bo OTAL LURIES WAI B Slff'%RY STAGED:

M11'2-BBWATER i t%%3

'IOTAL 0. RIES DEPOSITED E t-t M 7.

• M v _

sn sus s% doo 6

- OTAL PRrEssEn:

esssas

_iG. WAm tie.4% 2 JOTA;_ CLRIES [EPOSITC 1 Yc!'% w0 10TA 244951 kOS 4 tCf Mm M te.

encer..e _

l

SDS PROCESSING SAMPLE

SUMMARY

BATCH sc36 DATE/ TIME GALIDNS A

C D

E F

G 11 2.9 2.7 Cecium 137-NO 1 9

50 99 8.3 Sr 90 Grcas By 11L4) l?lla)

L31 d C:sium 137 i.t

,44) 13(4) 3 m

h Sr 90 us

<.s.it-.)

4(-i)

Gross Sy C:sium 137 Sr 90 Gross Sy C'sium 137 Sr 90 Gross Sy Cesium 137 Sr 90 Gross Sy l

C:sium 137 Sr 90 Gross Sy Cesium 137 Sr 90 '

Gross Sy

%-H-C 58 h nn an Inter Office Memorandum Date March 19, 1982

[

Subject SDS Batch Report TM1 U-2 Plant Engineering Location 4240-82-241 Acting Director, Site Operations

4. ;

Attached please find batch reports fo'r SDS Batch S-022 6 023. Batch No. S-022 represents the processing of the 16th and last batch of Reactor Building sump water, Batch No. S-023 represents the processint; of miscellaneous water from RCBT "B".

If you have any questions on this information, please call me.

'E. IT. G1schel

~.

Plant Engineering Director TMI-2 TDL/n3Dh ec:

J. J. Chwastyk W. T. Conaway J. C. DeVine C. G. Eitz K. J. Hofstetter T. D. Lookabill (2)

R. J. McGoey S. B. Presgrove (2)

-J.- E.-La rson-(2)

T. E. Rekart B. G. Smith s

I t

Ao000641

(

MTG #

son.

MIE 2/2s - %/s1 SDS PPOESSING MTG MTA

(

PR0rFRSING SlM%RY (ui/ML)

SYSTD1 RADIONucLIDE

,d AVERAGE INFiljENT AVERAGE EFFLUENT 4.15 5.67 (- O STRONTitM 90 CESILN 1M 11 7 5 %'ll-0 CESILN137 t ni c.cse 12 3 5d t-*)

ION EX0%NGE DEPOSITION 2_A AB 3_C a_p (cAf6)

[lNER # '

t'coib w eei9 Tseet i ps.cos,9 Tais h TCH S

M N4 3bi44 nW9 ni49 SIlN tw.1a,in4 271A43 i.%N) 2.4 t 4 f.t)

OtG 2 52.w +1 les.3n 40.hi I.u.4 OTAL IES 3 toes.se,

ioits.w r.i ti. ew 44n CttiULATIVE (TWOUGH

> ABOVE LINERS)

OfG wi.es7 siq 64+

zioasq no+46 S!tN 5% c.m aq +.9 tA s t..)

1.s 42 (.t)

TRONT isew.515 A r.r59 65., el

's.own OTAL IES m +it.5%

1851.8 41 671.

6.U2 POSTFILTER MTCHSTART 24 M/hr MTCHEND DO N/W MXIMLM

32. E /W.

WATERSLMRRY STAGED:

$ MTER Ipoo 5%

' 0TAL BD & 45 OTAL CURIES DEPOSITED dole. 6 r i r Sc6 adnd s-006 PRTESSED:

@ MTER wo34(e J.0TAL 85et%

10TA'. CLF.!ES DENSITO 44% 59. s c7

O SDS PROCEastNG SAMPLE

SUMMARY

BATCil 5071 iDate/ Time Gallons A

B C

D E

F G

II ce,tum il7 i.s

i. <

[

' sr 9n Af t~l i118 tigt1 4.%t) gg(-t) c,nnn 63

.~y conium 337 s.4 e.L sr 90 2/1*

o'+6 242.s3 s.s:(-t) 3.%t)

• /

g cennn 6) ccetum 137 1.ai i.1 Y18 otto 31%b 7.ir (-t) 1k(-1)

Sr 9n cronn FY

~

~ ~

cc i tiin 11, 110 2.5( i) 4 3(-5) 5.9(-i M(-v) sr 90

%s 20 i +-

i990 5

2.9 2.il-il i.it-a) 1.il s) co nna -

2io 5.1 i,*i 83 9W(-')

cen t iim 137 i10 7.i(-s). i.S(-3) 4.*(-4) 1r.a(-y)

Sr on 1

0148 ii6tl

_g_

2,g 3.1(.i) i.B(4) 5(-3) cion,' OY 2 0 13 2.1 1.4 f.*/

re, i i.. ia7 iso a

sa(s) ra(w) 5(-<) -

%+ osos so i,9 4.s 2.s i.t(--)

iat-s) 5(-3) c

~

. sr 9n cinnn rY no

_u i.s i.t i.i cenium i37 iso 4.s 2.st-3) it-s) i.L(-a) sr 9n-5 sb&b 3ggog g

_A 33(,,)

2.is(-t)

[2(-5) g

~

connn 6Y iR i4.4.

2.41 1.18 l.b!

a w-q

..I, l'

s.

_..1i

. i e

i i

f r i 6

- ~-

9 i,

. 1 i ;i l

P1 {

.I i

i iii

!i,

) f i

i 4 l

t l

'!t i 'i f

f j

• 6

.i

{

~~.~* f' N

l I

{

l t

i 6

1 i

t I

r g'

~

l 6

6 O

k i

i g,

l-3., r e

/

i

..L_

... h. 4..

f I

.g[

?

' Mi,

.& J...$_..

' Y.

g

' }

.i 1

p l

-y-H j -

i

g..._.

1 j)_.. ?

I

...... 1_

....y._

(..

._ 4Q f

i.

-Cp _..-_.g l

h T4

..rt...a r!-

R

...p b.

.I..

g

.. -.., -_.e_

j

+

.s --

-1 i

i 1

. j

.l..

h H.-

4..

I '

}.2.

.. H,..,

1.

i i.

-.i,

-t-

+

i l, -

i t-

!.,t.

I j

2

.._._. pp_.

-l-i i

A

~e i

R j

e

_t a

s i

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Fe elNuclear g

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Location TMI-2 Licensing To 4

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Attach'ed for your information is SDS Batch Report S-021.

The cover

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i.;

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J. J. Barton wo/a J. J. Byrne

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Inter-Office Memorandum I

i March 9, 1982 SubjGct SDS Batch Report TMI U-2 Plant Engineering j

Location 4240-82-193 To L. P. King Acting Director, Site Operations Att, ached please find batch report for SDS Batch S-021.

Batch No. S-021 represents the processing of the 15th batch of Reactor Building su=p water.

However, SDS is still performing exceptionally well, If you have any questions on this information, please call ce.

/

/

E. H. Gischel

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Plant Engineering Director TMI-2 TDL/tn cc:

J. J. Chwastyk

'n'. T. Conaway J. C. DeVine C. G. Hitz K. J. Hofstetter T. D. Lookabill (2)

R. J. McGoey S. B. Presgrove (2)

J. E. Larson (2)

T. E. Rekart B. G. S=ith j

1 AooOOM E J

SDS PROCESSING SAMPLE

SUMMARY

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B C

D E

F G

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Attached please find batch report for SDS Batch S-020.

Batch No. S-020 represents the processing of the 14th batch of Reactor Building su=p water.

However, SDS is still performing exceptionally well.

If you have any questions on this information, please call me.

[t8 E. H. Gischel

[

Plant Engineering Director N

TMI-2 TDL/tn cc:

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R. J. McGoey S. B. Presgrove (2)

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D2.e February 17, 1982 14 U 0 G a r Subject SDS Batch Report TMI U-2 Plant Engineering p

Location 4240-82-114 Acting Director, Site Operations s.;

Attached please find batch report for SDS Batch S-019.

Bat'ch No. S-019 represents the processing of the 13th batch of Reactor Building su=p water.

However, SDS is still performing exceptionally well.

If you have any questions on this information, please call me.

(

Plant Engineering Director E. H. Gischel q

TMI-2 TDL/tn J. J. Chwastyk cc:

W. T. Conaway J. C. DeVine C. G. Hitz K. J. Hofstetter T. D. Lookabill (2)

R. J. McCoey S. B. Presgrove (2)

.J. E. Larson.

T. E. Rekart B. G. Smith aooooe4r r

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's a - g-Q 3 3 c-Inter-Office Memorandum i

February 11, 1982 l

Subbet SDS Batch Report TMI U-2 Plant Engineering Location 4240-82-105 To L. P. King Acting Director, Site Operations Att'dched please find batch report for SDS Batch S-018.

Bate,h No. S-018 represents the processing of the 12th batch of Reactor Building sump water.

However, SDS is still perfoming exceptionally well. If you have any questions on this information, please call me.

,x/

a E.'H'.

Gischel

[

Plant Engineering Director TMI-2 g

TDL/tn ec:

J. J. Chwastyk W. T. Conaway J. C. DeVine C. G. Hitz K. J. Hofstetter T. D. Lookabill (2)

R. J. McGoey i

S. B. Presgrove (2)

J. E. Larson T. E. Rekart E. G. Smith Ao00064f

MT01 #

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AVERAGE INFLUENT AVERAGE EFFLUEtE.

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~. fEb E:n %- 14-O\\% Inter-Office Memorandum k. February 3, 1982 Subj:ict SDS Batch Report TMI U-2 Plant Engineering ~ ~ To L. P. King Acting Director, Site Operations Athached please find batch report for SDS Batch S-017. Batch No. S-017 represents the processing of the lith batch of Reactor Building sunp water. However, SDS is still performing exceptionally well. If you have any questions on this infomation, please call ne. " E. B. Gischel Plant. Engineering Director TMI-2 ( a$ TDL/tn cc: J. J. Chwastyk

• '. T. Conaway J. C. DeVine R. E. Hahn C. G. Hitz K. J. Hofstetter T. D. Lookabill (2)

R. J. McGoey S. B. Presgrove (2) J. E. Lsrson (2) T. E. Rekart i 4 Accoo W

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= : la f) /);-cC;f6 ( Inter-Office Memorandum \\ Date January 14. 1982 N Subj:ct SDS Batch Report TMI U-2 Plant Engineering Location 4240-82-027 To L. P. King Acting Director, Site Operations Atta'ched please find Batch Report for SDS Batch S.-016. Batch No. S-016 represents the processing of the 10th Batch of Reactor Building sump water. However, SDS is still perfoming exceptionally well. If you have any questions on this infomation, please call me. ,m E. H. Gischel [ Plant Engineering Director ~ TMI-2 OQf TDL/tn cc: J. J. Chwastyk W. T. Conaway J. C. DeVine R. E. Hahn C. G. Hitz K. J. Hofstetter T. D. Lookabill (2) R. J. McGoey S. B. Presgrove (2) J. E. Larson (2) T. E. Rekart O A000064f

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SUMMARY

BATCH Soib Date/ Time Callons A B C D E F G 11 a -C2cium 137 t.1 i 'I'" O'lO i0000 131(4) 9.8(-a) A, Sr 90 Cr:sa SY 1.o6(4) 8.97(-e) ..4 Cerium 137 ,, t s,t g Sr 90 4. 07 t9 Mtst. i.i1(-.) 5.Vi(-t) ~ ~ Crass SY Cesium 137 Sr 90 Cross SY Craium 137 99 s.4(*) 13 8) 't/4H) 5.%- i) '/4 'totB Sr 90 2B93 ,gs i, gg,.,) g,tg. ) i.g (.gj Crcss 8Y tit 5.3t t.12 t.51 t.94 75 .A5(-.) 99H) 23[-*) hM-y C231um 137 .j U 3 11 9(4) _Lild Ml'O Sr 90 Cress SY too 53 2 t.l 1b /q A r.4( ) L.M1) t(-1) 1.E) I Cecium 137* Sr 90 2, i.i t.il-8) M-1) 5.h) Crcss gy tBo (o.St 131 161 5 59 Cseium 137 34 r.* (. ) 3 Al-3) M(-1) 2it(-i) 4 %to g3g.. ,,,K-i) 8.! t.t (-.) M(-2) tal 8) Sr 90 Crcss 6Y J 47_ 1 t.% 1.71 4.45 1 e

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M B-M-C C%3 E '..S 1 } ', [2 Inter-Office Memorandum k Dats January 7, 1982 Subjtet SDS Batch Reports TMI U-2 Plant Engineering Location 4240-82-003 p Acting Director, Site Operations v. Attached please find Batch Reports for SDS Batches S-014 and S-015. Batches No's S-014 & S-015 repres.ent the processing of the 8th a'nd 9th Batches of Reactor Building sump water. However, SDS is still performing exceptionally well. If you have any questions on this information, please call me. ,, / " E.'n.~Gischel [ Plant Engineering Director TMI-2 TDL/tn cc: J. J. Chwastyk W. T. Conaway J. C. DeVine R. E. Hahn C. G. Hitz K. J. Hofstetter T. D. Lookabill (2) R. J. McGeey E. B. Presgrove (2) J. E. Larson (2) T. E. Rekart l l I ( Aooyawt r

BATG # Sois DATE 'W-d si SDS PROCESS % BATG IATA PROCESSifG StM %RY (ul/ML) SYSTEM RADIONUCLIDE AVERAGE INFLUENT AVERAGE EFFLUENT STRONTlui T R.4 5 7 8 h 9 510-3 CESIU41% BA5 "8*' CESiU4137 S t., su f " ' *io Im EXC#lGE IHOSITIm B B AC B (cu s) 1.lNER# 'D ' es 3 'D ioo"L6 nimig dion,L_ Prev =.y P<w.%o 9esw.% TH1SEATCH 16 l em 6 (%LLONS 4%% "b 9 4 4 % 99 4 % 99 ESIU4 Hw44.571 7.% = o S m u e lu z. = iv'- ONTlui 90 3a c.c. se.<> s.,a 4 - o-a i.w. me-i OTAL LURIES 2 Biob 5't 41.' b i.u r 4 4n uo-' CLNU'),TIVE (THROUGH N. ABOVE LINERS) ONS Nobt. iT1we wet r2 usw 2 S!U4 w*se. m icu a n o mio ' w246 TRONTlui 90 ww.es 4 4e.e 3 3.4 % i-sw me-' 1 M i.c3i 12.tv ia7 4.m ~ e-' OTAL UE!ES d POST FILTER PATcHSTART d6 */hr BATCHEND 35 ~/wr bltg4 '35 =[hr WATER SlH%RY STAGED: .$ WATER 3377 B b OTAL ses664 "0TALCURIESDEPOSITED

• 6 56. Tis w sec wcTV- -
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% WATER MBit i IOTA r,s s zi IDTA ORIES DEPOSIT ~_; A 4 + +-~. 2 51

SDS PROCESSING SAMPLE

SUMMARY

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1 ' ~' ^ Cross SY~ ~ Crsinia 137 1L 4 'r(-t). s.st-5) 35(H) yt. ) ( Sr 90 'Vte 0835 800+ 2A 1.5 M. .akt) .5ga) 4E-s) Cross SY. sao _ga 15_2 gg _ f,3 Cssium 137 9'l _2.bl.-Q 9M*) 9.s(W) 8._9 (-.) a3 is Sr 90 ,,,g3 3 gg,) g) g( 3) . igg,) Cross SY 162. 3 e4 M ).22 3.o'I Cesium 137 1'l 3.*(-5) 8 3I'h 8.d(-3) is(- <) ds- 0B20 dliB3 - ~ ' a.: a il-i) 9 i t-9 _c_A(. ) IM s) ~ Sr 90 4 ISO 35_ a.2 a.5 aa Cross 6Y Cesium 137 _3_h_ ~ B(,-3) 5.1(4) 44s) .11_(- s) i 'Yn chil 4cen; i.L A.st ) J &t) J.3( z) ,3_102) Sr 90 Cross 6Y [ 69.2 Jw 2.1 A ce _!j j l- ,+ s

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BATG # soi s DATE '2ha / si-W /.z GALLONS 4s2.m SDS PROESSl4 BATG DATA s PROISSINGSTi%RY(ul/ML) SYSTEM RADIONUCLIDE AVERAGE INFLUEtR AVERAGE EFFLUEtU STR0tmU4 90 2.%2 7.we tid ~8 CESilti }3!4 4.308 8.569 m io CESitr4137 a t o,, s.s is - io " Im EXCkMGE IEPOSITimB M a_C 9 (un s) LINER # t'ot'3 M oe' b he'b ~> toos$ THIS EATCH GALLONS 43249 And 4ndi mb9 ESILFi io05 h&4 4.5t7 2.5w (-s) 3.7s9 (-2) LTRONTitri@ 1e2 ti ' Sc 5 4.7 *7 4. 49 (-i) CURIES 3 e%.+41 3e9.sia 9.s+1 ..e, i f i CtfiULATIVE (THROUGH ' ABOVE LINERS) "' ONS 384t41 i'56tA '3 ? 4 t 41 17 % 8 SILT 4 nsa.n3 __s.si_ 2,5c5(-i) 7.%s t-s) TR0fallr4 90 9 a.a.4 i,0.sss n.,s s Jg) u.s is t.. OTAL LURIES s47so. 91t w.71+ it.9 2 POST FILTER MTCHSTART D me/hr MTCH EtO 2 6-r/br. hitg4 3hclhr. WATER S&T%RY STAGE: % WATER 380b+7 0TAL 64675i IOTAL CLRIES DEPOSITED 132.655 n se.t. Oc% S A-t C*4 6006 W TESS_D: $ WATE:, 37i 55 0 ICT;c t> l 9 ? 9 6 10T;_ CU:.!EE DEPOSITC 2M'io 51 i i

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en u:s 3\\- e- 075 'h. Inter-Office Memorandum l Data December 11, 1981 gg{ Subj;ct SDS Batch Reports To L. P. Kin 8 L cation TMI U-2 Plant Engineering 4240-81-0457 At'tached please find Batch Report for SDS Batch S-012. Batch.#S-012 represents the processing of RCBT 'B' which . consisted of normal RCS letdown, RCBT decon.& flush, ini-tial SDS effluent, etc. It should be noted that near 30% Strontium breakthrough was reached on the lA liner, and Cesium 137 breakthrough on the same liner was less than 0.1%. Strontium breakthrough on the 1B liner was 10%. However, SDS is still performing exceptionally well. If you have any questions on this information, please call me. d \\ "E. H. Gischel Plant Engineering Director TMI-2 TDL/nlm cc: J. J. Chwastyk W. T. Conaway j R. E. Hahn .\\ C. G. Hitz G K. J. Hofstetter j T. D. Lookabill (( R. J. McGoey S. B. Presgrove i! p J. E. Larson (2) (/ L[> T. E. Rekart J. C. DeVine jj / J A0000 Mt

MTCH # so i2 MTE

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• CESIU4 k,'.o463 toca, 6S.72 S.5 xie-3

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u. N e-M-C 3 \\h Inter-Office Memorandum '.ie Dece=ber 4, 1981 -(UClear D Subject SDS BATCH REPORTS To L. P. King Location TMI U-2 Plant Engineering 4240-81-0428 Attached please find Batch Report for SDS Batch S-Oll. ~ Batch #S-Oll represents the seventh RB Sump Water proces-sed through SDS. It should be noted that near 30% Strontium breakthrough was reached on the 2A liner, and Cesium 137 breakthrough on the same l'iner was less than 0.17.. Strontium breakthrough on the 2B liner was 27.. However, SDS is still performing exceptionally well. Effluent Cesium levels are still nearly a factor of ten (10) lower than expected, however, strontium 90 effluent concentrations have been a little higher than originally anticipated. { If you have any questions on this information, please call me. E. H. Gischel Plant Engineering Director TMI-2 90[ TDL/nlm cc: J. J. Chwastyk W. T. Conaway 4 R. E. Hahn C. G. Hitz K. J. Hofstetter T. D. Lookabill R. J. McGoey S. B. Presgrove J. E. Larson (2) T. E. Rekart J. C. DeVine A0000 M!

BATG # sani t DATE "As-3*/s. SDS PP0 CESSING BAT Q DATA PROCESSING SlWARY (ul/ML) SYSTEM RADIONUCLIDE h AVERAGE INFLUENT AVERAGE EFFLUENT ~3 STRONTIU4 9 4 69 4-9. n 2. m.t o CESilti1M 10 B1 i 7 i B's *

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.G 3 0 l;u T1 - H-C(c R Inter-Offico Memorandum l' ' oa November 24, 1981 tuclear Subj;ct SDS BATCH REPORTS To L. P. King Location TMI U-2 Plant Engineering 4240-81-0405 Attached please find Batch Report for SDS Batch S-010. Batch #S-010 represents the sixth RB Sump Water proces- , sed through SDS. It should be noted that near 107. Stront,ium breakthrough was reached on the 2A liner, and Cesium 137 breakthrough on the same liner was less than .017.. Strontium breakthrough on the 2B liner was 47.. However, SDS is still performing exceptionally well. Effluent Cesium levels are still nearly a factor of ten (10) lower than expected, however, strontium 90 effluent concentrations have been a little higher than originally anticipated. g If you have any questions on this information, please call ( me. s. E. 'd. Gischel Plant Engineering Director TMI-2 TDL/nlm cc: J. J. Chwastyk W. T. Conaway R. E. Hahn (2) C. G. Hitz K. J. Hofstetter T. D. Lookabill R. J. McGoey S. B. Presgrove J. E. Larson (2) T. E. Rekart wusw

BATCH # seeio DATE "/,2-i</si SDS PPOCESSM BAT 01IATA 3 PROCESSINGStWARY(Ul/ML) SYSTEM RADION'JCLIDE 4 . AVERAGE INCLUENT AVERAGE EFFLUENT STRONTim 90 s.its s.,,s-io-3 CESim 33t.; u.% s .. ow. o-s CESIm 137 io4 5 9 '65 'io s S!&.S ION EXdWE DEPOSITION M M a_C .a.D (ca' a') LINER # b.cc i i

1. icoi3 4 tec 2b Dieesw W

• * 'I

' " * ** * ) Tms h 6ALLONS 4 + t'3 M l'3 + + 1' S 4+1'S ESIU4 aisse.% a ws9 e.ou 6 ...e. e i. ) OrnJ.m 90 i s,.s.n. ..$ s .$4, 2 at i) OTAL WRIES 4 tie 7 e bb its.bb 4 is7 4.s t 4 bi ) CLNULATIVE (THROUGH ~ ABOVELINERS) ONS i%%% 252115 M 2ib .15171s ESIU4 aish 2% 2 sh7 i.%4 ')

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TRONT m 90 i ns.s t i ,.4u .. w 2.oca OTAL IES

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• • '*ib 0TALCURIESDEPOSITED
• 5 M.k i1 wm temmeos o=

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• 5 '

SD3 PROCESSING SAMPLE

SUMMARY

BATCH $ con o D. ate / Time Callons A 1 C D E F G 11 Cesium 137 4.M-*) +(-s) 1 Sr 90

• • /.e 2oSb eaoo s. R-i)

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M.' 7 i!.i ,f SI-H -CQ y3 Inter Office Memorandum i \\ Dste November 16, 1981 MNuclear Subpet SDS BATCH REPORTS To L. P. King Location TMI U-2 Plant Engineering 4240-81-0378 Att' ached please find Batch Report for SDS Batch S-009.

• Batch #S-009 represents the fifth RB Sump Water proces-sed through SDS, in addition, approximately 7,000 gal.

of waste from RCBT 'A' was included in this batch. It should be noted that near 1007. Strontium breakthrough was reached on the 2A liner, and Cesium 137 breakthrough on the same liner reached 407.. However, SDS is still performing exceptionally well. Effluent Cesium levels are still nearly a factor of ten (10) lower than expected, however, strontium 90 effluent concen-trations have been a little higher than originally antici-( vated. N. If you have any questions on this information, please call me. E. H. Gischel 3S Plant Engineering Director TMI-2 TDL/nlm cc: J. J. Chwastyk W. T. Conaway C. P. Deltete(2) C. G. Hitz K. J. Hofstetter T. D. Lookabill R. J. McGoey S. B. Presgrove J. E. Larson (2) T. E. Rekart noww

BATCH # s-o o<i MI[ /A -4 / 6. SDS PROCESSE BATCH IRTA PROCESSINGS&PARY(ui/ML) -RADIONUCLIDE [ , AVERAGE IfFLUENT AVERAGE EFFLUEPE -3 STRONTim 90 2 x 4, 7.wu io CESIlti17A B.6 T 5*io ~5 7 * ' ' " - l o" CESItri 137 .t 52t.t 6 6 .n 10NEXCMNGEDEPOSITIi 2_A 2_E _2_C al) (a, a) LINER # "Discit Dioo " 'Dioci$ Dicotw Tsis PATcs 6ALLONS

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L MTG # 5o05 MTE 9/23-2 5 / si CKLONS i 55 5 cl SDS PROISSING MTG MTA .(' ) PROESSING Slit %RY (ut/MD .sunn RADIONtJCLIDE [ . AVERAGE INFLUCNT AVERAGE EFFLUENT STRONTitri 90 3.u3 i 5 o o ~ CESitiq1% 8.bb1 8.0i7xto CESilti 137 8z.s33 8 3 l 5t o" g g7 '- Wt frC Im EXOWE EPOSITIm 9 9 2__C O LINER # Tico n "Di oil teois b ootb THIS M TCH GAL!.ONS iSSS*i ius; 15559 e5559 ESilti Sits.35i 2 *3 = so* 2%=io ' 2 4 % =io-S n,.tw s w io-i iss uo-' 2.is io- ONTJtr490 AL djRIES tocALm7 81 7.sev=so-' 4.7 h st o- ' CU'03TIVE ( OUGH - ABOVE LINER ' ONS isoBo liese 2iose zioso -3 3.cis io-5 ESilti sin.s ee - 2 %7 eo-L n w =io TRONTilr4 90 iso.is - s.us mo-i. %, o-. s =,o-t OTAL LURIES iciit.793 t Lei 3.ki9 io ' 7st3=io

• POST FILTER BATcHSTART O ~b/

PATCHEtO S "' / k< blMLri 3 M kr WAER S! WARY STAGCD: R3 WnER 4 oo s IOTAL 47 5c49 NuS TOTALCuIESDEPOSITED h7.53 4 h 3:EES 3: P3 WCEF 15559 NTA, s t-E C i i twel 1075 M.IE2 lEPCEITC-GCV ' " ' ' '

SDS PROCESSING SAMPLE

SUMMARY

BATCil soo5 l Date/ Time Callons A B C D E F C si C:sium 137 6.5(-e) 1.5(-1) Sr 90 9lA2 1135 1000 Cross SY as3 6b3 C:sium 137 .1A(-1) 4.d(-* ) 9/22 23 % soooo Sr 90 Cross SY alb 2o4 Cesium 137 b 3('0 13Ih Sr 90 9/23 oe25 fvoos 6% I45 Cross SY id{- 4 ) Cesium 137 1 Sr 90 4/23 hoo I17 2-1-i!-

• I

# 1 Gross SY Cesium 137 90_ l.1(4) (..B( 'd) 1.3( *) 1(d ) .s(-4) Sr 90 9/2.4 005S 8986 3 ri 4.t(2) s.7 (-1) s.5(-z) AbI 3.4 % _2M L'l .J - 5 Cross SY 4.1(-9) d-4) c..e l-*) 51(e) ico .Cssium 137 Lb-s.2(-2) 24(-0 ..s (-2) , n3(-a ) ill4-06'43_ 3MO Sr 90 2_5[,_ 2 57 88

s. b b

/ h3 Cross Sy 85 9.5( '*) M( te) M( d) L.,( s) C sium 137 Sr 90 Y2A lbib 632'2,' 2.9 a.1(-t) g-1) s. s (-a) _f f(- ) J10 2.8 g 2b J7 Cross 6Y I-4 L 'V s

SDS PROCESSING SAMPLE

SUMMARY

BATCH 5 oo 5 Date/ Time Callons A B C D E F G l Cesium 137 e'l i(-Q 92(9) c.4(-9) s:i0 d 'f/25 oc % %%I g i.9(-t) 2 2(-Q p(s) . 2( * ) Sr 90 Gross SY J V 2. 3.3 e.7 4 f.i t 23L l Cesium 137 15 .. V(- 5) i t-9)

• s (-J) 614( :i)~

t I i Sr 90 'l/25 0B45 it' h o AB s.' (-2)

• N-z) 2}/-a),r:i( 0 Cross SY g

,,2.66 2.c1 2 56 [?L ~ Cesium 137 61 8 =(-O g -s) s.f(- s) M (- >) Sr 90 4/25 e41 o l'544!O .7 i:st-a) g[-a) g[-4) ..,(..)- Cross SY 89'I J7 .s e 9 - --a.c w J.. c. n. l l Cesium 137 9/s.$ W 65559 ue s A ms e5 - cu a. oc a A rtit_ Sr 90 4 l Cross SY Cesium 137 Sr 90 Cross SY Cesium 137 Sr 90 Cross Sy ~ Cesium 137 . Sr 90 Cross SY [ p 9 \\6

.g.pe-6.W f ~ ~- u... i ($ i I F-i I i 4' l l - 'H H i" 9 i ? i i f I f l _.. t-e t .i i i I i i - } - l-t j-., i i. i-t-i i i i A i i i t [ i i i i i e i F' i. i i C --i 6 I i i O i..i i _C i i i i 4 , i 4 h i i i. i. vs .. j. _ i t t g -h-l' l s l' e.a i .6 i. a i i . i. g.. i _e 4 l4 i. e i. i i . i ..i e j .i . i i l I i i i g[ i-i i n . i ! i !e< i

• /

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f_, MT0i# S oo 6 l I MTE 91u-io/* lei SDS PROCESS 1t6 MT04 MTA PROCESSlfG SUt%RY (ulhat) RADIONJCLIDE M AVERAGE INFLUENT AVERAGE EFFLUENT STRONTitr4 90 ~ 3.7s4 t. tes s iti' _ . CESitti 3 10.4B9 2.151sso " CESitti 1y., n o1.5'8 6.597 *to" ION EK0WE DEPOSITION 1A 2B EC 1.D LINER # Stooq 310011. " Tiboi3 'Diooit THIS EATCH C%LLONS 45511 Assii 4sain 4ssit Sitti $4tst2% e ntue-' a w u o i.iw v io-'- TRONTilE % 7o=#.w s st.i % s.3e s = c-' 8.srtus-i OTAL LURIES 3'13o.wse -n.628 tasi i.6 M / O FULATIVE (THROUGH N ABOVELINERS) ~ ' OtiS W.M i b4M i e6M i 66 e i Silfi 2%2c.nt 9..e iv 2 a.tc9..e2-i.4 3 cue-2. TR0tR Lf4 90 ent%s it.zst 6.vn -e-i sin ue-. IOTAL IES 47 t*417 i 2+.629

i. sis t.,n POST'FI E R PATCHSTART b<

BATCHEf0 8~ I k - lhari b fk< f WATER SUT%RY STAGED: _RB WATER b's ss'2. OTAL m 5 Es 6 au ws "0TALCURIESDEPOSITED 538. i bs SD'EES 3: _Id WATE. 60 70 f 10TAL, 2i % s ?. (-<.u.e e 3 i ! TA._ UJ'*EE L'EPOI:TE-5 e s e. '. P - ~:

SDS PROCESSING SAMPLE

SUMMARY

BATCil 5-cob Date/ Time Callons A B C D E F G 11 Cesium 137 84 _ l.5 Sr 90 % osos io.o 2A 3.t Cross SY 191 279 ~ Cesium 13,7 2.4(-s) 1(-a) Sr 90 9/n 1:3o toooo s.9 2A i Gross SY aso l'46 Cesium 137

• t.B(-e )

15(-0 Sr 90 I4 1853 2 5 c.= 2.s

2. 8 Gross SY EB 297 Cesium 137 9I~'I EM-' )

Ill

• N IT **

T.T 3 Sr 90 Cross BY Abb 153 2 I l Cesium 137 77t(-*) '1 * (.- 0 Sr 90 d7 1 % 4954'I 4't 35 Cross BY 2'15 152. 'I O l SI~N 'l-9 '? 8(?) kil 8) Cesium 137 Sr 90 18 Octb 11 % 39 t.M-t) n.t(-2) > it.a} i.i(-4) L s6 4 t. Cross sy 29, 3 56 .sm Cesium 137 fit iO) 7 (-'d) 33{ 'd) ' ! '*8 ) I USI 3 i.,(-t) i. il-1) s p (.3) g - t{ - 4 ) Sr 90 16 06 f ] Cross 6Y J_2J 375 J78 J; t8' .n 9 0 0 o Oq.- y,

) ) ) ) ) ) ) ) ) ) ) ) g u M (" i d ) . e ) 2 9. A. _ L ( L ( d ( A { D K l. l y 6 t i j a a. a 3 t da , o t ( 4 9a a 9 ! 4 9 l s, ) ) u 9_ 4

i. $

d L- } s )b )4 ) ) ) ) s ) ) ) 2 9 ) ) . d s )a t s - 5 z - b 6_. 9_ I I ( t l l ( g t l ( ( a t n,,, 2

• g y G

4 1 } - 3 2 u. } L a_. p2

h. 1 A k.

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• s W

)t s s ) 1 3 1 1 9 u @6 N ( [- E F g 9 t l ( ( ( ( l l s 3 9 1 v 1 q o 3t 1 s - 1M L 1 7 3 9 J 2 7 J 3 8 3 2 1 t i ) ) ) ) ) ) ) ) ) 5 1 L f ) i ) ) L 4 ) a ) a 3 4 p 2 2 5 W (t ~5 U t'- l 3 4-G ( ( ( a W 3 5 J ( ( E 9-3 3 t ( f i. 1 ( t 1 n s J 2 'l 2 9 3 2 9 2 l 1 \\ 2 4 a o 8 0 0 t I 5 8 f 0 b oB 4 6 2 0 A' 0 g4 1 5 0 i 5 0 3 1, 4 I 4 Y D 3 A' 4 2 1 1 t 2 9 3 2 1 R 1 L I AM M U S EL b P C M oc AS S G o. l N i I C S T B S A E B k C O R P S D A S s (. n 9 q s 9 1 3 0 o } 0 M o ) 1 9 T) l a 3 9 l M 1 t y 5 a t 1 g C / D ~ 3 9 5 M O m e 0 5 4 B m 0 0 M 0' i T O i / 0 e 0 o 9 4 1 3 t e 9 / / a t 9' L S N - 9 D / 7 7 7 7 7 7 7 y 3 } 3 3 3 3 3 1 Y l Y 1 Y 1 Y 1 Y 1 y 1 Y S S S S S S S m m m m m m m u 0 s u 0 s u 0 s u 0 s u 0 s u 0 s u 0 s i 9 s i 9 s i 9 s i9 s i 9 s i 9 s i 9 s s o s o s o s o s o s o s o e r r e r r e r r e r r e r r e r r e r r C S C C S G C S C C S C C S C C S C C S C i e e I y. ll! f

SDS PROCESSING SAMPLE

SUMMARY

s l BATCH SOO(o i Date/ Time Callons A B C D E F .G 11 Cesium 137 'l2 T.7(W) 7.(w) 39(4) y g.,) ' II 0o69 11055 t.1 JSt) j{.a} 9g.5) - y.) Sr 90 Cross SY g 2.8'4 2.ts t 1 9 -( 3 w k, j Cesium 13 lio 94t(w) ,.s t ) -g (.y) , g ( T_ Sr 90 194'I3 45 b.7t-t) 4il-t) ,g(2) !.g(.) Cross SY 24:,9 3.'i l MJ jm i Cesium 137 9b l.il-5) 9g-*) L. L(W) o.(..) tc/8 t i.9 o -~ 24"I40 Lt(-z) g[.t) _gg [.t) }gQ Sr 90 Cross SY 24o 40 37 3 z.. d 22 / Cesium 137 loo I.il 'd 9.14 4 L4( *) 's il 4) 3 33 N 2%'l# l Lt 1.4,( 1) t l(-0 g3(;t) ',8 M 0 Sr 90 t Gross SY ggo '/ 3 3.G 13 j Cesium 137 9 'i iM) 74.(4) 1[M 'f h l * ) Sr 90 / ~2. 06%3 3)l3'L +l 9.ll-t) 9.1(-d 32(-2) h(- a ) Cross SY 264 _3_d9 13 3 99 -3_ t; Ul-4) 7.4-1) L 'it-9') 9.*;l.') Cesium 137 10 0 Sr 90 /t Ib3o 329oi. 3.9 it-i) JM-t) g-t) i3 (.) Cross Sy M1 3.e L 3.c9 2. t'g a (, Cesium 137 95 i.. (-i) g{.,) g(w) 3(..) II 0001 3516% 3.9 i.tl-i) s.4-a) .i_(- t) 'tHs) Sr 90 Cross SY ~ M9 V.s 9 J_]) .2 Ts 3

• e-9 4

e ,4* D e t.- s ; y,

SDS PROCESSING SAMPLE

SUMMARY

BATCil GOob Date/ Time Callons A B C D E F G 11 sao J e(-8) ' U-) (* 3 (-) o sg s) Cerium 137 3'145l 4J al-s) fdf.-3) 8 8(-2) 3..t1-3) Sr 90 W3 ce n _ Crecs SY 2R

1. 48 3d._

13 3 '3 Cesium 137

• 2:

I ' yo 13f-5) 11(*) J 3( 's) _J.) l- *.) I ist1

1. 2 a t-s) h3fs) s.2 (- t )

y., P s ) ih 55 Mas 9 Sr 90 Crecs SY 3_9A 4.s 3 3 22. 3.3 3,j I C22ium 137 w/4 too !df-3) 1r.2 (- 4) 4.. l(-as ) y g...)

• • 3 41'C19

.11 2.H4) _2_3,{.2) 3(-1) ng (-4 ) Sr 90 Crrs 8Y _AS$ 4*'18 3X3 3 s't .FS Cotium 137 tof4 osgo Sr 90 6Ah nab 45'S t i Cr es SY I C2mium 137 g Sr 90 Crsss SY Cesium 137 Sr 90 Cr:ss Sy Cacium 137 Sr 90 Cr:ss 6Y

~ . + gne e. 6 ~ t e m. 1 l"*i -.i,--,, 44 e. y .t . $.o p, .u ,. e i L* l . s t t ( (, *-- I i - i. i.., i i e i i i n. e t .. i s.. l i. e I I i ,1- ,i i _~_~..._... 4 e i i + i r i n e i 4 1 , L.

• • .I

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SDS PROCESSING SAMPLE

SUMMARY

BATCil

• Aco~1 Date/ Time Callons A

B C D E F G 11 C oium 137

• t 8 (-s) 9.8(-e)
• " ' ' * ~ ' '*-^- -

~ Sr 90 80/4 it"50 sooo e.s(.s) s.6(-.) ~ Crcss SY 2Vo 2 59 C:cium 137 5.q(..)

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1. 1(.s) s.s r.5) af./(-v)

.,(- 4 ) Sr 90

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4.u( a)

e..s(.a) s.u-a)

Crcss SY ha 3.1 2.5 1 2$ C:sium 137 95 ,a.(-3) s.1(-5) s.s(-3) _. (-J ) 2 ( 4) Sr 90 . */st oct8 65069 y s.q (-a) ,.2(-a) g-a) 3 Cross SY ASB V.1 3.GG 3.y? Mb --- ,_.,{;s) gh) C:sium 137 A 2.i( 5) 3 (-3) t Sr 90 5 5b5 2. 3 6.s(-a) s(-a) 9.,g.3)

y. 3[.3)

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MTCH # s-oo B DATE ie/ zs - > i / s. l GAIENS s us, SDS PROISSING BATG DATA I 1 PROESSING SLIT %RY (ut/rit) SYSTEh. RADIONUCLIDE. A . AVERAGE INFLUEf6 (~/,tj AVERAGE EFFLUENT STRONTItn 90

4. 89 e.,os io-S CESilN 3

"2' so.u ix io'5 'ot S42 s.sss to" CESIlN 137 -0 ISc) + / IONEXCHANGEDEPOSITION 2_A a_B 2C 2._D (,m a) llNER# 3 50052. 'Dico I I 'Dioo G tiooth Tsis PATcs GALLONS wm uwm o n, u y n, ESitM ite95. 54 is.W6 i. ass t o- ' 2.e93 nio " ONTilM 90 6ei.sss i o..su m2 io. 4 OTAL LURIES w7seN 22 i.w9 w,si..e. 9.ese n io-. CaiULATIVE(THROUGH ABOVELINERS) GALLONS mes% wwwos . 6e,w iweig SilM

• • e4 45.5 %

ii.ses 7.57 8 = ia $.,esmio ' TRONT LN 90.

32. 256 iii.is 2.c34

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CTA'.

33iC i' IDTA 05. EI DEPOI*T M M ~$ ' 5 ' )

SDS PROCESSINC SAMPLE

SUMMARY

BATCil 50ob Date/ Time Callons A B C D' E F C 61 Casium 137 h(-s) g-.) S "A "A Sr 90

• • /.g 1Mo

.eco d65 tem \\,sweae m h 6* CD C: slum 137 g-e) 5.4 (-.) nas p.%4 %.3 "A "A - Sr 90

• • /iq II*05 asaoo Cross SY 3os 259 Cesium 137 4.7(-i) 1Ai)

Sr 90 '*/to 05 % 494c1 "/A "A Cross SY ' loo ill Cesium 137 m aciL-s) 33[- e) a.s t s) 3 tt. ) Sr 90 '*/3 3 o9co im LL s.9(..) as) mii) g(g) Cross SY 178 M J.R J.bl 2.pt C:sium 137 95 4.2(-1') 605) Mi-9) 9 )[- s) 'Y

• tS b sigh
• i 8 51(-s) 201)

_i(-z) 3 '}(. 3) Sr 90 Cross gy 220 4 bs

3. te J.D5 45 Casium 137 iso A11-a)

M-v) 1.i(-1) $sg.f Sr 90

• % chiG socq3 g.)

...(.g) g.3) gg) Cross Sy J1'I _fde M1 J_. 85 .9 l l l Casium 137 A i.Q-.) nt-9) y;i(m) L-v) Sr 90 'U.

• cac 44n4 n

i g t) 4,) i q.4) Cross 6Y 309 .1h3 J 185 J 77 J 3' + O j ' e#

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g h\\d V \\ - SN \\ Inter-Office Memorandum ( 3 ate December 16, 1981 Subj;ct ORNL Analyses of SDS Samples To Distribution LocatiertTMI U-2 Plant Engineering 4240-81-0465 Attached are the results of the analyses'of SDS samples sent to ORNL taken during batch S-0010 processing. Table 1, gives the ORNL results for the gamma emitting nuclides and Sr concentrations. Our on-site results on parallel sa=ples are indicated in parentheses. Table 2, gives the results of U, Pu, Solids,and B analyses. These analyses are not routinely performed on site. E. H. Gischel f Plant Engineering Director TMI-2 N KJH/nla cc: J. J. Barton L. P. King J. C. DeVine J. E. Larson K. L. Harner

• C. G. Hitz K. J. Hofstetter 3

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) TABLE 1 Activity, uCi/ml ~~ ~~' THI/ CPU Sample #' 90-Sr* 134-Cs* 137-Cs* 106-Ru 125-Sb 144-ce 54 - t i.. hp i:.. PT-A-92108 5.02 13.9 123 <0.4 <0.2 <0.3 (12.3) (110) PT-C-92109 5.05 13.4 120 <0.4 <0.2 <0.3 (12.7) (111) INF-D-92220 4.90 .14.1 124 <0.4 <0.2 <0.3 (6.2) (13.2) (131) 2A-E-92221 0.30 6.1 E-4 5.4 E-3 2.5 E-4 1.1 E-2 <2 E-4 (.44) (6.5 E-4) (6.2 E-3) (<1.2 E-4) (1.3 E-2) (<5.6 E-4) 2B-F-92222 1.06 E-2 1.6 E-4 1.4 E-3 3.5 E-4 1.1 E-2 1.4 E-4 (1.7 E-2) (1.8 E-4) (1.7 E-3) (2.8 E-4) (1.3 E-2) (<4.8 E-4) 2C-C-92223 4.2 E-3 9.5 E-5 8.2 E-4 <2.E-4 1.1 E-2 1.1 E-4 (1.1 E-2) (1.0 E-4) (9.6 E-4) (3.9 E-4) (1.3 E-2) (2.8 E-4) CAT-II-92224 3.6 E-3 8.6 E-5 7.8 E-4 2.3 E-4 1.1 E-2 1.2 E-4 2. t, 1:-1, 1,4 L S (6.1 E-3) (1.4 E-4) (9.9 E-4) (2.6 E-4) (1.4 E-2) (<4.5 E-4) (. 2. 2 [,; CTio Precision is stS%. w 4 &,/

D ( "~'.'\\ TABLE 2 Concentration, w;/mi 1ttI/Gril Sampic I Pu U Total Solids Solids Suspended. B PT-A-92108 1.1 E-7 4.7 E-3 13.9 E3 <10 2.04 E3 rT-c-92109 1.1 E-7 3.9 E-3 14.0 E3 <10 2.03'E3 IliF-D-92220 1.2 E-7 5.7 E-3 15.3 E3 <10 1.99 E3 2A-E-92221 2.4 E-7 3.8 E-3' 13.0 E3 <10 1.99 E3 28-F-92222 2.2 E-7 3.8 E-3 11.8 E3 <10 '2 00 E3 2C-C-92223 1.6 E-7 2.7 E-3 13.1 E3 <10 1.95 E3 CAT-II-92224 1.2 E-7 3.6 E-3 .12.8 E3 <10 '1.92 E3 / / O e G 9 d, e

R8 SUNP ACTIVITY Page 1 {4 ',!h ~ v.: 1 \\ i TRANSFER NO. BATCH NO. DA GALLONS REMOVED uCi/ml Cs137 s r h 1 S005 9/23/81 14,004 82.3 2 S006 9/27/81 49,547 101.6 3 S007 10/10/81 50,091 102.0 4 S008 10/23/81 49,497 102.8 ,. t 5 S009 11/02/81 36,676 77.6 6 S010 11/12/81 49,497 104.8 ( 7 S011 11/22/81 44,099 100.4 8 S014 12/21/81 44,369 81.8 9 S015 12/29/81 42,867 92.1 10 S016 1/06/82 19,232 76.5 11 S017 1/23/82 43,670 94.0 12 S018 1/31/82 43,385 110.5 13 - S019 2/07/82 19,216 115.0 14 S020 2/11/82 31,346 106.3 15 S021 2/21/82 31,150 116.4 17 S025

i. O1C/"2 Y[*/22.36,960 1ic.o 106.7

- '[#[ 16 S022 2/28/82 31,948 123.0 ' 18 S029 8/19/82 4,718 M. 106.7 fM i c 19 5036 9/27/82 30,031 u.7 25. J f 20 S038 11/01/82 41,681

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21 SO41 12/31/82 47,920

8. 7 22 SO45 2/16/83 41,519 8.4 23 SO46 3/04/83 53,425

6. 6 24 SO47 4/13/83 30,384 3.7

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/[ O 25 5055 6/03/83 63,081 2.2 [ p'g 26 S059 7/08/83 29,093 27 SO96 7/03/84 7,897 9.34 gj /p 28 SO98 7/12/84 27,080

8. 4E 29 S107 11/08/84 41,275

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