Text

AX114 & AX115 Ci Loading
	ML20057B964
Person / Time
Site:	Crane
Issue date:	09/10/1993
From:	Brosey B, Lodde G; GENERAL PUBLIC UTILITIES CORP.
To:	;
Shared Package
ML20057B954	List: ML20057B953; ML20057B958; ML20057B964;
References
	4240-3233-93-01, 4240-3233-93-015-R01, 4240-3233-93-1, 4240-3233-93-15-R1, NUDOCS 9309240211
	Download: ML20057B964 (54)
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MUAU I

C:lculcti:m Shrt Subget lCalcNo.

lRev.No 1 She;1 No.

AX114 and AX115 Curie Loading l 4240-3233-93-015 l

1

! i of 67 i Ongmator Date Reviewed my Date B. Brosey 3 b%

9/8/93 G. Lodde f 4,d,,

9//o/93 1.0 PROBLEM STATEMENT The purpose of this preliminary calculation is to estimate the curie loading of the "A"

"B" Makeup Domineralizers located in the Auxiliary bldg. cubicles AX114 & AX115. Radiological survey data will be used to provide the exposure rate information necessary for this estimate.

2. 0

SUMMARY

OF 'IESULTS Based on the Radiological Controls survey data, the "A"

"B" Demineralizers contain the following total activities.

"A" DEMINERALIZER "B" DEMINERALIZER 3663 Curies

~38%

6706 Curies + -50% - -77%

Isotopic concentrations per curie are listed in attachments 2-1 & 2-2.

The following table contains the results from previous estimates of the activity contained in the TMI-2 Demineralizers (see references).

7/16/93 "A" DEMIN "B" DEMIN No. CI's No. Ci's No. Ci's No. Ci's ho. Ci's No. Ci's REPORT DATE Cs 134 Cs 137 Sr Cs-134 Cs 137 Sr-90

..........................................................................................-90.....

1 GEND-INF 013, Vol. !!, POST ACCIDENT ESTIMATES 9/86 286 3677 543 7035 2 HEDL-7285, Fuet Assessment of the TMI-2 Makeup Demin's..

10/83 3400+or-74%

3 TMI-2, TPB 85-10, rev 0, FRE ELUTION 4/22/85 1140 4365+or-12%

4 TMI-2, TFB 85-10, rev 0, POST ELUTION 4/22/85 317 813 TMI-2, TFB 85-10b, rev 1, POST ELUTION 7/10/85 380+or-20%

440+ or-20%

6 TMI 2, Division SER, 15737-2-G07-117, rev 0 11/2/88 7.3 530 100 7

THIS ESTIMATE 7/12/93 3

978 875 9

3266 168 3.O REFERENCES 3.1 Microshield Radiation Shielding Computer Code, Version 4, Grove Engineering, Inc., 15215 Shady Grove Rd.,

Rockville, MD 20850.

3.2 Lotus 1-2-3, Release 2.2, Lotus Development Corporation, 55 Cambridge Parkway, Cambridge, MA 02142.

3.3 "The Health Physics and Radiological Health Handbook", Scinta, Inc., Silver Springs, MD.,

1992.

3.4 LA-9795-MS, "NDA Measurements of the Demineralizers at TMI-2", Los Alamos National Laboratory, Los Alamos, New Mexico 87545, 8/83.

3.5 GPUNC Engineering Calculation No. 4249-3211-90-069, "MU & P Demineralizer Fuel Estimates", 11/16/90.

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(UCIOCr Cricul tion Sh: t Sublect Calc No.

Rev. No.

Sheet No. N AX114 and AX115 Curie Loading 4240-3233-93-015 1

of Onginator Date Reviewed by Date B. Brosey 3 9/8/93 G. Lodde /ffp M [

fa 3

3.0 REFERENCES

Cont'd 3.6 TMI-2 Technical Planning Bulletin, TPB-85-10, rev 0,

" Estimates of TMI-2 Letdown Demineralizer Resin Retained and Eluted Fission Products and Fuel", 4/22/85.

3.7 TMI-2 Technical Planning Bulletin, TPB-85-10b, rev 1,

" Post Elution Estimates of Cs-137 in Letdown Demineralizer Resin", 7/10/85.

3.8 TMI-2 Division Safety Evaluation Report, SER 15737-2-G07-117, "In-Place Storage of Makeup and Purification Demineralizer Resins During PDMS", 11/2/88.

3.9 HEDL-7285, " Fuel Assessment of the Three Mile Island Unit 2 Makeup Domineralizers by Compton Recoil Continuous Gamma-ray Spectrometry" U.S. Department of Energy, Hanford Engineering Development Laboratory, Richland, WA 99352, 10/83.

3.10 GEND-INF-013, "TMI-2 Purification Demineralizer Resin Study",

U.S.

Department of Energy, EG&G Idaho, Inc., Idaho Falls, Idaho 83415, 5/84.

3.11 GEND-INF-013, Vol. II, " Development of a Process...TMI-2 Makeup and Purification Demineralizers", U.S. Department of Energy, EG&G Idaho, Inc., Idaho Falls, Idaho 83415, 5/84.

3.12 GPUNC Memorandum No. 4200-88-585, " Resin Material in MU-K-1A &

B",

1/3/89.

3.13 GPUNC Technical Plan, " Makeup and Purification Deminaralizers Resin Removal", TPO/TMI-072, rev 0, 8/83.

3.14 Burns & Roe, Inc., Drawing No. 2066, rev 23, " General Arrangement Auxiliary & Fuel Handling Building Floor Plan El.

305'-0"",

W.O.

2555. 9/17/70.

3.15 3-D Visions Corporation graphing program "GRAFTOOL", Ver.

3.3, 12/16/90.

4.0 ASSUMPTIONS AND BASIC DATA 4.1 General overview of methodology.

4.1.1 In general, the two demineralizers are modeled as right circular cylinders. The activity is assumed to be at the bottom of each cylinder based on referenced data. Other locations in the cubicles are also modeled to determine the effect of differing source locations. Finally, exposure rate estimates are determined at several distances from each tank. All exposure rate information is calculated from one curie of isotopic distribution assumed to be present in the indicated demineralizer. Data in section 4.0 is preliminary in nature.

N 0016 (10-88)

-MusInnr Cciculction Shact Subject Calc No.

Rev. No.

Sheet No.

AX114 and AX115 Curie Loading 4240-3233-93-015 1

3 of ff Originator Date Reviewoo by Date G. Lodde ] d [ [

9//d/93 B. Brosey 9/8/93 4.0 ASSUMPTIONS AND BASIC DATA Cont'd 4.2 Determination of materials and densities.

4.2.1 From review of reference 3.12 and 3.13 the following data table l

was assembled using the Lotus 1-2-3 spreadsheet system (reference 3.2).

A & B DEMIN DENSITY ESTIMATE DENSITY ESTIMATE (MIN)

DENSITY EST! MATE (MID)

DENSITY ESTIMATE (MAX)

LBS g/cc g/cc g/cc LOADING ESTIMATE A

B A

B FROM REPORTED VALUES DEMIN DEMIN DEMIN DEMIN DEMIN DEMIN DEMIN DEMIN RESIN WEIGHT (lbs) 1025 1025 0.7463 0.7463 1.4927 1.4927 2.2390 2.2390 WATER WEIGHT (lbs) 193 193 0.1405 0.1405 0.2811 0.2811 0.4216 0.4216 CORE DEBRIS Fe (lbs) 95 19 0.0692 0.0138 0.1383 0.0277 0.2075 0.0415 URANIUM WEIGHT (lbs) 5 1

0.0036 0.0007 0.0073 0.0015 0.0109 0.0022 BOT. TAT. ASS. Fe (lbs) 38.4 35.4 0.0978 0.0978 0.0978 0.0978 0.0978 0.0978 OVER LOWER 6" OF TANK

==.....................................................................................

TOTALS==>

1.0575 0.9992 2.0172 1.9007 2.9768 2.8021 TANK VOLUME ~560 gallon =~74.9 cubic feet

RESIN DENSITY (g/cc)=~0.7463 INITIAL RESIN VOLUME '22 cubic feet =

622970.62 ccis PCST ELUTION VOLUME ESTIMATE ft'3>

0.2 7.1 IN CC's============> 5663.36 201049 ESTIMATED DIAMETER OF SOURCE TERM ft.====>

2.0 4.0 g.

g.

ESTIMATfD INCHES INCHES NEIGHT OF SOURCE TERM 0.764 6.780 DATA FROM TECHNICAL PLAN, TP0/TMI-072, 8/83 AND GPUNC Memorencksn 4200-88-585, 1/3/89.

4.2.2 Three postulated densities are presented for each domineralizer: a minimum value, a middle value and a maximum value. The middle value was chosen as the most likely density for the domineralizer materials. The other two densities are presented to project other possibilities and provide an error term for density variations.

The middle and maximum densities are estimated by multiplying the minimum d ncity valucs by a factor of 2 and 3 respectively.

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v 4.0 ASSUMPTIONS AND BASIC DATA Cont'd 4.2 Determination of materials and densities cont'd.

4.2.3 The minimum density values for all materials except the bottom laterals are projected by dividing the mass of the originally loaded materials listed in the reference 3.13, by the volume of the resin (22 cubic feet), listed in reference 3.13.

The effective density of the bottom laterals located in the tanks, is calculated by assuming that each lateral assembly is located in the lower 6 inches of each tank. This places the laterals in the source region making them a component of the overall density term for each tank.

4.2.4 The tanks are assumed to be composed of 0.25 inch stainless steel with a density of 7.86 g/cc.

4.2.5 The vertical exit piping near center at the bottom of eacn tank is assumed to be 3 inch schedule 40 stainless steel.

4.2.6 The horizontal run of piping in the "B" Demineralizer room is assumed to be 2 inch schedule 40 stainless steel.

4.2.7 The bottom lateral assembly is assumed to be composed of 12 pieces, 21 inches long by 3/4 inch, schedule 40 stainless steel piping with one section of 5" diameter by 6" long schedule 40 piping at the center. The total weight of this assembly is assumed to be approximately 31.1 lbs (see attachment 11-1).

l 4.3 The isotopes, and activity of the isotopes present in one curie of source materials for each demineralizer is assumed to be the same I

as that presented in reference 3.13. The activities from reference 3.13 were decayed to 7/12/93 and normalized to 1.

SOURCE TERMS FOR DEMINS (in Ci's)

ISOTOPES DEMIN "A"

DEMIN "B"

Co-60 7.97e-4 Sr-90 2.39e-1 2.51e-2 Y-90 2.39e-1 2.51e-2 Sb-125 8.91e-4 Te-125m 2.06e-4 Cs-134 7.55e-4 1.35e-3 Cs-137 2.67e-1 4.87e-1 Ba-137m 2.52e-1 4.61e-1 Ce-144 1.79e-6 Pr-144 1.79e-6 Pr-144m 2.55e-8 4.3.1 For purposes of this calculation the source term is assumed to be homogeneously distributed throughout the volume of the rour:c region.

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4.0 ASSUMPTIONS AND BASIC DATA Cont'd 4.4 Computer modeling for "A"

"B" Demineralizers.

4.4.1 From review of reference No. 3.13 and discussions with TMI-2 Engineering personnel, the following information represents the basic Microshield input data.

a) Demineralizer "A"

Basic Microshield 4 inout:

Dose point to center of cylinder (X)......... 176. 3 4 cm.

Height of cylinder (H)....................... 1.94056 cm.

Radius of cylinder (R)........................

30.48 cm.

Thickness of cylinder shell (SH'.).............

0.635 cm.

Dose point position along 7 axis (Z)............

0.0 cm.

Dose point from base of cylinder (Y)..........

68.58 cm.

Air Gap...................................... 145.225 cm.

b) Demine_r_alizer "B"

Basic Microshield 4 innut:

Dose paint to center of cylinder (X).........

270.97 cm.

Height. of cylinder (H)......................

17.2212 cm.

Radius' of cylinder (R)........................

60.96 cm.

Thickness of cylinder shell (SH1).............

0.635 cm.

Dose point position along Z axis (Z).............

0.0 cm.

Dose point from base of cylinder (Y)..........

68.58 cm.

Air Gap...................................... 209.375 cm.

4.5 Review and interpretatoon of survey data.

4.5.1 Six (6) Radiological Controls Field Operations surveys and one (1) Engineering survey were reviewed to determine the true exposure rate at set locations within the "A" "B"

Demineralizer cubicles (see attachments 10-1 to 10-9). The data was analyzed and incorporated into a spreadsheet for i

manipulation purposes. The spreadsheet data table is shown below.

i i

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//7 93 4.0 ASSUMPTIONS AND BASIC DATA Cont'd 4.5 Review and interpretation of survey data cont'd.

4.5.1 Cont'd.

A & B DEMINERALIZER DATA ANALYSIS 7/16/93 SURVEY FEET RESULT FROM D

~4 FOOT ESTIMATED ESTIMATED TANK E

CALC.

POSSIBLE POS$1BLE ABOVE DISTANCE DISTANCE CENTER M

(mR/h)

TOTAL ERROR ERROR RtOM SURVEY SURVEY FLOOR IN FEET IN FEET LINE I

PER C1 Cf's IN IN NUMBER DATE NUMBER (ndt/h)

(x)

(Y)

(D)

N AT D ft ESTIMATE X FEET Y FEET

=...............s====..m===E.......................E.....s=.s=====............=============.....====E===========ss=E

Ax115 9/28/88 88J19796 125000 6.78 5.75 8.89 B

5.10 24511 0.75 0.75 Ax114* 3/13/85 NONE 90000 4.6 1.75 4.92 A

23.29 3865 0.75 0.75 Ax115 4/6/85 3N 85

'IS000 6.78 5.75 8.89 B

5.10 6863 0.75 0.75 Ax115 4/6/85 3N 85 7000 6.78 1.25 6.89 B

10.88 6432 0.75 0.75 Ax115 4/6/85 3N-85 300V1 6.78 3.25 7.52 8

8.59 3494 0.75 0.75 Ax115 6/5/85 4N 85 3700) 6.78 5.75 8.89 B

5.10 7255 0.75 0.75 Ax114* 6/5/85 2N-85 60600 4.6 2.75 5.36 A

19.94 3040 0.75 0.75 Ax115 9/28/88 NONE 42900 5.73 5.75 8.12 B

6.84 6273 0.75 0.75 Ax114* 4/24/90 90J04347 70000 5.09 2.75 5.79 A

17.14 4085 0.75 0.75 3333533B3E23338 533583B85#B33EE333323232333 33333335E33233E83E3333E2323R3333E3E2E33352253235E53E3333358333333333333335E5E2

DENOTES INTERPOLATED EXPOSURE RATE VALUES COMBINED

& AVERAGED ABSOLUTE DISTANCE DISTANCE mR/h/Cl mR/h/Ci VALUE ERROR ERROR CALC.

CALC.

LONG/

SHORT/

ERROR R004 TERM TERM mR/h/Ci mR/h/Ci CALC.

CALC.

ERROR ERROR TERMS CURIES CURIES NUMBER LONG (ft) SHORT (ft) LONG SHORT mR/h/Ci a D mR/h/Ci a D LONG SHORT

+ or -

IN "A" IN *B"

==============3E==============.e........

=E=........

................... E

......E...............................

Ax115 9.9 7.8 3.41 7.62 0.67 1.49

-33%

49%

41% N/A 24511 <NOT USED Ax114*

5.9 4.0 16.42 32.55 0.71 1.40

-29%

40%

35% 3865 N/A Ax115 9.9 7.8 3.41 7.62 0.67 1.49

-33%

49%

41% N/A 6863 Ax115 7.8 6.1 7.74 15.00 0.71 1.38

-29%

38%

33% N/A 6432 Ax115 8.5 6.5 5.85 12.51 0.68 1.46

-32%

45%

39% N/A 3494 <WOT USED Ax115 9.9 7.8 3.41 7.62 0.67 1.49

-33%

49%

41% N/A 7255 Ax114*

6.4 4.3 13.81 28.64 '

O.69 1.44

-31%

44%

37% 3040 N/A Ax115 9.2 7.1 4.57 10.23 0.67 1.50 33%

50%

41% N/A 6273 t

Ax114*

6.8 4.8 11.92 24.50 0.70 1.43

-30%

43%

37% 4085 N/A EF33RRRESSBsR333EEEsssSBSSEB33333333333333333333 333333332E3E33EEBESEEEEEEEEEEERREEEEEEEEEEEStats33333S8E35833333 AVERAGED CURIE VALUESE>

3663 6706 ESilMATED ERROR + or -

36.2% A-Demin Avg.

ESTIMATED ERROR + or -

39.3% B-Demin Avg.

)

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AX114 and AX115 Curie toading

!4240-3233-93 015 I

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dde 4.0 ASSUMPTIONS AND BASIC DATA Cont'd.

, /4, 4.5 Review and interpretation of survey data cont'd.

4.5.2 The table in section 4.5.1 presents distance estimates; calculated exposure rate estimates based on these distances, total curies present, and an estimate of error due to incorrect distance determinations. Sections 4.5.3 to 4.5.9 describes the methodology used to calculate these parameters.

4.5.3 The distance estimates were determined by review and scaling from current GPUNC drawings (see reference No. 3.14), diagrams from other references in section 3.0, and RADCON survey sheets (see attachments 10-1 to 10-9)

Since the demineralizers are at approximately the center of the cubicles, an X and Y coordinate can be used to calculate the approximate horizontal distance from a dose point to the tank vertical centerline.

4.5.4 When their location is unspecified, all exposure rate values are assumed to have been taken about 4 feet above the cubicle floor. However, the first survey listed in the table (section 4.5.1), presents a value that is at least 3 times higher than measurements taken at similar horizontal (X,Y) locations shown in other surveys. For purposes of this calculation, this value is assumed to be either in error or taken at other than 4' above the cubicle floor.

4.5.5 Several 4' radiation values presented in the table in section 4.5.1, have been interpolated from the actual survey data.

These interpolated values are marked with an asterisk.

4.5.6 The distance values in the table

("D"),

are calculated by determining the hypotenuse of a right triangle.

4.5.7 The calculated mR/h per curie values shown in the table, are determined by curve fitting the Microshield 4 calculated exposure rates for the "A"

"B" Demineralizers for several distances out from the source regions, using the sensitivity analysis option in Microshield 4. These distances use the base Microshield inputs listed in section 4.4.1 as the reference values. The functions used in the spreadsheet table seen in section 4.5.1 were determined by the curve fitting routine in the computer program "Graftool" (reference 3.15). These functions are listed below.

"A" Demineralizer Correlation Coefficient Y=133.6*0.7012*

-0.966758 "b" Demineralizer Y=149.339*0.683949"

-0.89348 WHERE: Y is the mR/h/Ci value and X is the number of horizontal foot frcm the demineralizers sertical centerline.

3 N 0016 (10 68)

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i 1J114 and AX115 Curie teacirm I4240-3233-93-015 1

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//

9[/,1 B. Brosey 4.0 ASSUMPTIONS AND BASIC DATA Cont'd 4.5 Review and interpretation of survey data cont'd.

4.5.8 total curie column in the table is calculated by dividing tne measured or interpolated exposure rate by the mR/h/Ci value determined by the method shown in section 4.5.7.

4.5.9 The estimate of the error from incorrectly determining the X & Y horizontal distances where a measurement was taken, is determined by assuming that the X and Y distance measurements could be incorrect by as much as 0.75 feet. The maximum The minimum would be ( (X '-0. 7 5 ' ) 2+ ((- ('-0. 7 5 ' ) 2)) o.5(Y ' + 0. 7 distance from the source would be X'+0.75' 2+

Y From these two distances, differing mR/h values may be estimated using the same method previously described in previous sections. The dif ferences between the mR/h estimates for correct vs incorrect distances both long and short, are averaged and converted to percentage differences and are presented as one component of the overall estimate of error for this analysis.

4.6 The following is a description of the attachments presented in this calculation.

a) Attachments 1-1 & 1-2, present and decay the isotopes extracted from reference 3.13 assumed to characterize the "A"

"B" Demineralizers, b) Attachments 2-1 to 2-2, present the decayed isotopes from attachments 1-1 & 1-2 normalized to 1.

c) Attachments 3-1 & 3-4, present the demineralizer cubicle locations with actual and estimated dimensions, d) Attachments 4-1.to 4-4, present the demineralizer tanks with estimated dimensions including associated piping.

e) Attachments 5-1 to 5-7, Microshield 4 base case output for high, middle and low density materials modeling, f) Attachments 6-1 to 6-5, Microshield 4 sensitivity analysis using middle density materials from 91.44 cm to 213.36 cm for the "A" and from 91.44 cm to 304.8 cm for "B" Demineralizer.

g) Attachment 7-1, Microshield 4 output for pipe source at base of "A" Demineralizer.

h) Attachments 8-1, Microshield 4 output for horizontal run of pipe section in the "B" Demineralizer cubicle (base case geometry).

i) Attachments 9-1 to 9-6, Graftool output from curve fitting Microshield 4 sensitivity analysis data for "A" "B"

Demineralizer for zaricus X distances.

N 0016 (10 88)

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o...

l 9/8/93 G. Lodde 9, o/ f 3 3 0 ASSUMPTIONS AND BASIC DATA Cont'd 4.6 Attachments cont'd.

j) Attachments 10-1 to 10-9. Radiological surveys that present the survey information used :o estimate the curie loading of the "A"

"B" Demineralizers.

k) Attachment 11-1, dimensions and weights of seamless and welded steel pipe, Williams and 2cmpany, inc. catalog # 23, pp D-30 & 31.

5.0 CALCULATIONS 5.1 Most of the earlier operatic ns were performed using the Lotus 1-2-3 spreadsheet system.

5.2 In section 4.2.2 three (3) possible densities were estimated for modeling purposes. In attachlents 5-1 to 5-7 the Microshield 4 output from the differing detsity computer analysis are shown.

For the "A" Demineralizer, t te calculated exposure rate for the 3 density estimates using th:t Microshield base case input is:

5 HIGH DENSITY (2.96 g/cc).,..

..................... 15.26 mR/h.

MIDDLE DENSITY (2.00 g/cc)....................... 16.73 mR/h.

LOW DENSITY (1.04) g/cc)......................... 18.22 mR/h.

For the "B" Demineralizer, tte calculated exposure rate for the 3 density estimates using the Microshield base case input is:

HIGH DENSITY ( 2. 7 8 g/ c c ).......................... 3. 619 mR/ h.

MIDDLE DENSITY (1.88 g/cc)........................ 5.107 mR/h.

LOW DENSITY (0.98) g/cc).......................... 8.496 mR/h.

Using the above listed data ald calculating the estimated error due to possible variations in density gives the following results.

"A" DEMINERALIZER (1-(15.26/16.73)) x 100% = F 8.8%

j (1-(18.22/16.73)) x 10 0 % = -

8.9%, for the "A"

DEMIN.

"B" DEMINERALIZER (1-(3.619/5.107)) x 100% = + 29.1%

(1-(8.496/5.107)) x 100% = - 16%, for the "B"

DEMIN.

N 0016 (1488)

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5.0 CALCULATIONS Cont'd 5.3 Location of the base case Microshield 4 exposure rate point relative to the demineralizers.

The diagram on attachment 4-3 shows the relative position of the base l

case Microshield 4 exposure rate points to the demineralizers and to the base pipe connections.

5.4 Placement of other source terms.

5.4.1 "A" Demineralizer.

5.4.1.1 The "A" Demineralizer source term is assumed to be a 2' diameter cylinder with a height of about 0.764 cm (section 4.2.1). If it is assumed that the majority of the source term is located in the 3" resin sluice line below the tank, the geometry for this case would then be as follows.

Assuming the vertical pipe length at base of the tank is about 9" long, then the lowest section or the elbow of this pipe is at approximately the ~306' El. The location for the highest exposure rate measurements were taken approximately 3' above the floor at the 308' El. The elevational difference is about 2'.

Assuming the horizontal distance is within a few inches of the base case horizontal distance or about 5.8 feet, the Microshield 4 output for a pipe segment containing one curie would be 17.37 mR/h (see attachment 7-1). Since the base case Microshield output for the "A" Demineralizer tank was 16.73 mR/h (section 5.2), the relative difference in activity is:

(1-(100,000 mR/h/17.37 mR/h/Ci)/

(70,000 mR/h/16.73 mR/h/Ci)) x 100% = ~38%

The possibility that all of the activity is in the this lower pipe section is remote and therefore will not be considered further.

5.4.2 "B" Demineralizer.

5.4.2.1 The 2" diameter pipe run connected to the resin sluice outlet nozzle located in the "B" Demineralizer cubicle may also contain resin and high activity levels. This pipe run is shown in attachments 3-3 and 4-3 and is present in both cubicles. However the majority of_the activity located in the "B" Demineralizer cubicle is assumed to be located in the tank, based on the N 0016 (10-88)

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5. 0 CALCULATIONS Cont'd 5.4 Placement of other source terms cont'd 5.4.2 "B" Domineralizer cont'd.

Radiological Engineering survey data shown on attachments 10-6 to 10-8. However, if one (1) curie of activity is placed in a single pipe run located at the center of the two pipe sections running east and west (shown on attachment 4-3), the mR/h/Ci value would be approximately 20.77 mR/h/Ci (see attachment 8-1). The Microshield 4 model would be as shown below:

"B" Demineralizer 2" nine run input file Dose point to center of pipe section (X)..... 217.17 cm.

Height of cylinder (H)........................

228.6 cm.

Radius of cylinder (R)....................... 2.62509 cm.

Thickness of cylinder shell (SH1)...........

0.39116 cm.

Dose point position along Z axis (Z)..........

87.63 cm.

Dose point from base of cylinder (Y)..........

44.81 cm.

Air Gap....................................

214.15375 cm.

5.4.2.1 The pipe is 2" schedule 40 stainless steel and is located at approximately the 306' 1.5" El. The pipe starts about 9" east of the vertical centerline of the "B" Demin and runs east for about 7.5 feet. The elevational difference would be about 309'-306' 1.5" or about 2.875'. The exposure rate point is at the center of the entrance to the "B" Demin cubicle about 4'

above the floor.

5.4.2.2 Based on the two models, the relative difference between one curie of activity in the demineralizer and one curie in the pipe section is shown below.

j (1-(20.77 mR/h/Ci/5.107 mR/h/C1)) x 100% = 307%

This indicates that if the activity were predominately located in the 2" line, about 1/4 th of the calculated number of curies would be present. This is not the case since the "B" Demin retains the higher exposure rate as evidenced by the survey information. Therefore, the best estimate is that most of the activity is still retained at the "B" Demin location and not in the 2" line.

N 0016 (10-88)

~

Nust=r cricui: tion sheet i suen.m acae %

i % no

' /2-of N

{'

i sw %.

l AX114 and AX115 Curie Loading i4240-3233-93-015 I

Ongmaior Date l F+emewoo py l Date[/glt [93

3. Brosey 9/B/93 i G. Lodde 97 9,

I 5.0 CALCULATIONS Cont'd 5.5 Combination of Error Terms.

5.5.1 The combined estimate of error in this analysis includes the following:

a) The estimate of the uncertainty in the radiation measurements from the radiological surveys, due to incorrectly reported survey locations (in the X and Y directions, north-south / east-west).

b) The estimate of the uncertainty in the density of the source term materials.

c) An assumed instrumentation response error.

5.5.2 The distance error estimate ussumes that the actual exposure rate point is within -

one foot of the correct measurement location ( ( ( 9 "2+9 n2).5) = 12.7"). Since there is a similar difference in the effect of i distance error for the individual curie values presented in the table in section 4.5.1, and some uncertainty in the exact measurement locations, the absolute values of the error terms as well as the curie estimates were summed and averaged for several measurements.

The error estimate for the survey locations for the "A" Demin is:

(35% + 37% + 37%)/3 = ~ 1 36%.

The error estimate for the survey locations for the "B" Demin is:

(41% + 33% + 41% + 41%)/4 = - ! 39%.

5.5.3 From section 5.2, the uncertainty in the source term density l

is assumed to be:

-t 9% for the "A" Demineralizer and, ~+ 29% - 66% for the "B"

Demineralizer.

5.5.4 The instrumentation calibration error is assumed to be approximately t 10%.

5.5.5 The combined error estimate is approximately:

l 2

2 (36% +9g2+10% )o.5 = ~38% for the "A"

Demineralizer and, l

2 2

2 (39% +29% +10% )o.5 = - + 50%

+

2 2

2

- ( 3 9 % + 6 6 % +10 % ) 0.5 = - - 77% for the "B" Demineralizer.

N 0016 0088)

)

i

-1 j

SAMPLE

SUMMARY

SHEET NUMBER OF SAMPLES ss=>

1 7/12/93

==

=a

Today's Date SAMPLE ko.

SAMPLE No.

"A" DEMIN DATE DATE DATE DATE DATE DATE 5/15/83 7/12/93 7/12/93 7/12/93 7/12/93 7/12/93 ELAPSED (d) ELAPSED (d) ELAPSED (d) ELAPSED (d) ELAPSED (d) ELAPSED (d)

ISOTOPES I

ISOTOPES 3711 0

0 0

0 0 Decayed Totals H-3 0.00000E+00 H-3 Be-7 0.00000E+00 Be-7 C 14 0.00000E+00 C-14 Cr-51 0.00000E+00 Cr-51 Mn-54 0.00000E+00 Mn-54 Fe-55 0.00000E+00 Fe-55 co-57 0.00000E+00 Co-57 o

co-58 0.00000E+00 co-58 E

fe 59 0.00000E+00 Fe-59

)

gg Ni-59 0.00000E+00 Ni-59 m

o Co-60 1.9800E+00 5.20636E-01 Co-60 Ni*63 0.00000E+00 Ni-63 y

2n-65 0.00000E+00 2n-65 g "*

Sr-89 0.00000E+00 Sr-89 E

Sr-90 2.0000E+02 1.56355E+02

$r-90 2r-95 0.00D00E+00 2r-95 Tc-99 0.00000E+00 Tc-99 m

Ru-103 0.00000E+00 Ru 103 5

Ru-106 0.00000E+00 Ru-106 rA Ag-110m 0.00000E+00 Ag-110m T

Sb-124 0.00000E+00 Sb-124 y

{ g{

$b-125 7.4000E+00 5.82514E-01 Sb-125

.c

.m

, o Te-125m 0.00000E+00 Te-125m U3 E c5 yh j t.5 1 129 0.00000E+00 1-129 C

1 131 0.00000E+00 1-131 1-133 0.00000E+00 1-133 m

g ts-134 1.5000E+01 4.93321E-01 Cs-134 3

cn t

Cs 136 0.00000E+00 Cs-136 3

M h

ie]n Cs 137 2.2000E+02 1.74208E+02 Cs-137

,U te-139 0.00000E+00 Ce-139

[

Ba-140 0.00000E+00 Ba-140 I

ce 141 0.00000E+00 Ce-141 te-144 9.9000E+00 1.16705E-03 Ce-144 Pm-147 0.00000E+00 Pm-147 5

E u-154 0.00000E+00 Eu-154 g

y E u-155 0.00000E+00 Eu-155 U-233 0.00000E+00 U-233 l

g g

U-234 0.00000E+00 U-234 g

U 235 0.00000E+00 U-235

=

c U-236 0.00000E+00 U-236 O

E hp-237 0.00000E+00 Np-237 3

hj j

s Pu 238 0.00000E+00 Pu-238 Z

qo U-238 0.00000E+00 U-238 5 2 Pu-239 0.00000E+00 Pu 239 g

)"

Pu-240 0.00000E+00 Pu-240 y

?y U

Am 241 0.00000E+00 Am-241 Pu-241 0.00000E+00 Pu-241 cm-242 0.00000E+00 cm 242 Pu 242 0.00000E+00 Pu-242 cm-243 0.00000E+00 cm-243 Cm-244 0.00000E+00 cm-244 TOTAL==>

3.32160E+02

a 7

. -2 SAMPLE

SUMMARY

SHEET NUMBER OF SAMPLES===n 1

7/12/93

==

nuss

.....es Today's Date SAMPLE No.

SAMPLE No.

8" DEMIN OATE DATE DATE DATE DATE DATE 5/15/83 7/12/93 7/12/93 7/12/93 7/12/93 7/12/93 ELAPSED (d) ELAPSED (d) ELAPSED (d) ELAPSED (d) ELAPSED (d) ELAPSED (d)

ISOTOPES ISOTOPES 3711 0

0 0

0 0 Decayed Totals H3 0.00000E+00 H-3 Be 7 0.00000E+00 Be-7 C-14 0.00000E+00 C-14 Cr-51 0.00000E+00 Cr-51 Mn-54 0.00000E+00 Mn-54 D

fe-55 0.00000E+00 Fe 55 o

6 co-57 0.00000E+00 Co-57 Z

fN {k K

co-58 0.00000E+00 co-58 Fe-59 0.00000E+00 Fe-59 O

Ni+59 0.00000E+00 NI-59 Co-60 0.00000E+00 Co-60 j

Ni-63 0.00000E+00 Ni-63 g-Zn-65 0.00000E+00 2n-65 E

Sr 89 0.00000E+00 Sr-89 Sr-90 8.8000E+02 6.87961E+02 Sr-90 2r-95 0.00000E+00 Zr-95 3

Tc-99 0.00000E+00 Tc-99 g

Ru-103 0.00000E+00 Ru-103 4

Ru-106 0.00000E+00 Ru-106 cn Ag 110m 0.00000E+00 Ag-110m 5

m Sb-124 0.00000E+00 Sb-124 c

C EE Sb 125 0.00000E+00 Sb-125 E

6 7 la Te-125m 0.00000E+00 Te-125m

S y

$ dy l-129 0.00000E+00 1-129 1-131 0.00000E+00 1-131 I-133 0.00000E+00 1-133 3

to Cs 134 1.1300L+03 3.71635E+01 Cs-134 3

Q Cs-136 0.00000E+00 Cs-136 Q

j Cs 137 1.6900E+04 1.33823E+04 Cs-137 g

I Ch Ce-139 0.00000E+00 Ce-139 O

Ba-140 0.00000E+00 Ba-140 Ce-141 0.00000E+00 Ce-141 te-144 0.00000E+00 Ce -144 3

s Pm-147 0.00000E+00 Pm-147 g

i Eu-154 0.00000E+00 Eu-154 u

Eu-155 0.00000E+00 Eu-155 m

b U 233 0.00000E*00 U-233 km Z

U-234 0.00000E+00 U 234 E

N 0 235 0.00000E+00 U-235 v

U 236 0.00000E+00 U-236

$ cr.

Np-237 0.00000E+00 Np-237 ef Pu-238 0.00000E+00 Pu-238 C3 U 238 0.00000E+00 U-238 E

5 3

Pu-239 0.00000E+00 Pu-239 5 8 Pu 240 0.00000E+00 Pu 240

{

{"

Am 241 0.00000E+00 Am-241 9

O c'

?

Pu-241 0.00000E+00 Pu-241 tm-242 0.00000E+00 cm-242 Pu-242 0.00000E+00 Pu-242 cm-243 0.00000E+00 cm-243 cm 244 0.00000E+00 cm-244 TOTALa=>

1.41075E+04

q

= -1 NORMALIZATION WORKSHEET (1 Cl)

CALCULATED

=

==

7/12/93 EXPOSURE RATE PER Ci==>

mR/h ACTUAL===>

mR/h

==

UN!TS IN>C1

=

==

Today's 0 ate I.0. NtHBER OR NAMES >"A" DEMIN, AX114 ADJUSTED NRC REPORTABLE INPUT UNIT PERCENT (%)

ACTIVITY ADJUSTED WITHOUT If > 1% of Sr-90/cs-137 ISOTOPE ACTIVITY of Total PER CUR 1E ACTIVITY (mCl) DAUGHTERS (mCl)

TOTAL ISOTOPES RATIO

==================================================================================================================**************

1 H-3 0.00000-0.00E+00 ***

ERR ERR ERR H3

ERR

2 C-14 0.00000 0.00E+00 ***

ERR ERR ERR C 14 **************

3 Cr-51 0.00000 0.00E+00 ***

ERR ERR ERR Cr-51 4

Mn-54 0.00000 0.00E+00 ***

ERR ERR ERR Mn-54 5

Fe-55 0.00000 0.00E*00 ***

ERR ERR ERR Fe-55 6

Co-58 0.00000 0.00E+00 *"

ERR ERR ERR Co-58 7

Co-60 5.21E-01 ***

0.07967 7.97E 04 *"

ERR ERR ERR Co-60 8

Ni-63 0.00000 0.00E+00 "*

ERR ERR ERR.Ni-63 9

2n-65 0.00000 0.00E+00 ***

ERR ERR ERR Zn-65 10 Sr-89 0.00000 0.00E+00 *"

ERR ERR ERR Sr-89 3

11

$r-90 1.56E+02 "*

23.92754 2.39E-01 *"

ERR ERR ERR Sr-90

\\g 12 Y-90 1.56E+02 ***

23.92754 2.39E-01 ***

ERR

============================= Y-90 0

13 Te-99 0.00000 0.00E+00 "*

ERR ERR ERR Tc-99 f

14 Ru-106 0.00000 0.00E+00 "*

ERR ERR ERR Ru-106

g j

15 Rh-106 0.00000 0.00E+00 ***

ERR

============================= Rh-106 O

i 16 Ag-110m 0.00000 0.00E+00 "*

ERR ERR ERR Ag-110m t

17 Ag-110 0.00000 0.00E+00 "*

ERR

=============== ========="=== A g - 110 I

18 Sb-125 5.23E-01

0.08914 8.91E-04 * "

ERR ERR ERR Sb-125 g "* (

19 Te-125m 1.35E 01 *"

0.02059 2.06E-04 ERR ERR ERR Te-125m E

T 20 I-129 0.00000 0.00E+00 ***

ERR ERR ERR I-129 21 Cs 134 4.93E 01

0.07549 7.55E 04

ERR ERR ERR Cs-134 22 Cs-137 1.74E+02 "*

26.65964 2.67E-01 ***

ERR ERR ERR Cs-137 23 Ba-137m 1.65E+02 *"

25.22002 2.52E-01 "*

ERR

=======================*===== Ba-137m g

24 Ce-141

~

0.00000 0.00E+00 *"

ERR ERR ERR Ce-141 4

4 25 Ce-144 1.17E-03 * "

0.00018 1.79E-06

ERR ERR ERR Ce 144 m

4 26 Pr-144m 1.67E-05

0.00000 2.55E-08 ***

ERR

===========*=== ===== ="=== ** = Pr-144m $

c, 27 Np-237 0.00000 0.00E+00

ERR ERR ERR Np-237

.O C EE 28 Pa-233 0.00000 0.00E+00 *"

ERR

=============== ***=========== Pa 233 j g}

f 29 Pu-238 0.00000 0.00E+00

ERR ERR ERR Pu-238 3 =

3

- 30 Pu 239 0.00000 0.00E+00 *"

ERR ERR ERR Pu-239 h OU $'

31 Pu-241 0.00000 0.00E+00

ERR ERR ERR Pu-241 32 Am-241 0.00000 0.00E+00 *"

ERR ERR ERR Am-241

.5 i

m 33 cm-243 0.00000 0.00E+00 *"

ERR ERR ERR Cm-243 3

.E 34 U 235 0.00000 0.00E+00 "*

ERR ERR ERR U-235 35 U-238 0.00000 0.00E+00

ERR ERR ERR U-238 y

a e i

36 Pu-240-0,00000 0.00E+00 *"

ERR ERR ERR Pu-240 37 U-234 0.00000 0.00E+00 ***

ERR ERR ERR U 234 38 Pm-147 0.00000 0.00E+00

ERR ERR ERR Pm-147 39 Eu-154 0.00000 0.00E+00 "*

ERR ERR ERR E u-154

{

40 Eu-155 0.00000 0.00E+00

ERR ERR ERR Eu-155 g

41 U-236 0.00000 0.00E+00 *"

ERR ERR ERR U 236.

v L

42 Pr-144 1.17E-03 "*

0.00018 1.79E 06 *"

[RR

============================= Pr-144 m

M 43 Cm-242 0.00000 0.00E+00 *"

ERR ERR ERR Cm-242 b

C 44 cm-244 0.00000 0.00E+00 *"

ERR ERR ERR Cm-244 E

E 45 0.00000 0.00E+00 ***

ERR ERR ERR O

m

======m=====m=====mm=======memm======mmem===============m=mm======m==me====mm-,g 7

TOTALS =n6.5345E*02 Cl 100.00 1.00000 Ci ERR mci ERR mci n-S re m I

sE R

s

?-

m

,o

)

l i

.c.~

~ - -

a

. -2 NORMALIZATION WORKSHEET (1 Cl)

CALCULATED

=

========== "

7/12/93 EXPOSURE RATE PER Ci==>

mR/h ACTUAL===>

mR/h

==

UNITS !N>Ci

=

==

Today's 0 ate 1.D. NUMBER OR NAMES >"B' DEMIN, Ax115 ADJUSTED NRC REPORTABLE INPUT UNIT PERCENT (%)

ACTIVITY ADJUSTED WITHOUT If > 1% of Sr-90/Cs-137 ISOTOPE ACT1VITT of Total PER CURIE ACTIVITY (mCl) DAUGHTERS (mCl)

TOTAL ISOTOPES RATIO

=============..===========.============================================...==========================..============********=*****

1 H-3 0.00000 0.00E+00 ***

ERR ERR ERR H-3 ERR

2 C-14 0.00000 0.00E+00 ***

ERR ERR ERR C-14 3

Cr-51 0.00000 0.00E+00 ***

ERR ERR ERR Cr-51 4

Mn-54 0.00000 0.00E+00 ***

ERR ERR ERR Mn-54 5 Fe 55 0.0D000 0.00E+00 ***

ERR ERR ERR Fe-55 6

Co-58 0.00000 0.00E+00 ***

ERR ERR ERR Co*58 7

Co-60 0.00000 0.00E+00 ***

ERR ERR ERR Co-60 8

Ni-63 0.00000 0.00E+00 ***

ERR ERR ERR Ni-63

' 9 9

2n-65 0.00000 0.00E+00 ***

ERR ERR ERR 2n-65 10 Sr-89 0.00000 0.00E+00 *"

ERR ERR ERR Sr-89 3

h 11

$r-90 6.88E+02 '"

2.50577 2.51E-02

ERR ERR ERR Sr-90 y

fN %

12 Y-90 6.88E+02

2.50577 2.51E-02 *"

ERR

============================= Y-90 13 Tc-99 0.00000 0.00E+00 ***

ERR ERR ERR Tc 99 14 Ru-106 0.00000 0.00E+00 ***

ERR ERR ERR Ru-106 o

15 th-106 0.00000 0.00E+00 *"

ERR

===============.============= Rh-106 16 Ag-110m 0.00000 0.00E+00 ***

ERR ERR ERR Ag-110m a

17 Ag-110 0.00000 0.00E+00 ***

ERR

===

==========s=== Ag-110 18 Sb-125 0.00000 0.00E+00 ***

ERR ERR ERR Sb-125 19 Te-125m 0.00000 0.00E+00 ***

ERR ERR ERR Te-125m u,

20 1 129 0.00000 0.00E+00 "*

ERR ERR ERR I-129 h

h 21 Cs-134 3.72E+01 *"

0.13536 1.35E-03 "*

ERR ERR ERR Cs-134 E

22 Cs 137 1.34E+04 *"

48.74260 4.87E-01 *"

ERR ERR ERR Cs-137 A

C EO 23 Ba-137m 1.27E+04 ***

46.11050 4.61E-01 *"

ERR

========================.=== Ba-137m 24 Ce-141 0.00000 0.00E+00

ERR ERR ERR Ce-141 h g2 3

25 te-144 0.00000 0.00E+00 "*

ERR ERR ERR Ce-144 sE g O* ';,*.

26 Pr-144m 0.00000 0.00E+00

ERR

============================= Pr-144m O

27 Np-237 0.00000 0.00E+00

ERR ERR ERR Np-237 5

28 Pa 233 0.00000 0.00E+00 ***

ERR

=============.=============== Pa-233 3

29 Pu-238 0.00000 0.00E+00

ERR ERR ERR Pu-238

.9 30 Pu-239 0.00000 0.00E+00 *"

ERR ERR ERR Pu-239 iR 31 Pu-241 0.00000 0.00E+00 '"

ERR ERR ERR Pu-241 32 Am-241 0.00000 0.00E+00 *"

ERR ERR ERR Am-241 33 cm 243 0.00000 0.00E+00 "*

ERR ERR ERR Cm-243 5

34 U-235 0.00000 0.00E+00

ERR ERR ERR U-235 35 U-238 0.00000 0.00E+00 "*

ERR ERR ERR U-238 3

p 36 Pu-240 0.00000 0.00E+00

ERR ERR ERR Pu-240 y

9 37 U-234 0.00000 0.00E+00

ERR ERR ERR U-234 I=

b U

38 Pm-147 0.00000 0.00E+00 *"

ERR ERR ERR Pm-147 39 Eu-154 0.00000 0.00E+00

ERR ERR ERR Eu-154 40 Eu-155 0.00000 0.00E+00 '"

ERR ERR ERR Eu-155 0

3 41 U-236 0.00000 0.00E+00

ERR ERR ERR U-236 3

42 Pr-144 0.00000 0.00E+00 "*

ERR

============================= Pr-144 E

5 D

43 cm-242 0.00000 0.00E+00

ERR ERR ERR Cm-242 e

aE 45 0.00000 0.00E+00 '"

ERR ERR ERR O"3fE 44 cm-244 0.00000 0.00E +00 *"

ERR ERR ERR Cm-244 1

65

..======.===...============.= ~=================== ~===== ~===== ~.. -====..= -======= ~.===.... - =.== ~

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. -2 Nuclear caiculation sheet

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Aw.Na SW Na Loading 4240-3233-93-015 1

IO Of B osey 9/8/93 doe M g

[f]

I 4

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Nuclear Calculation Sheet 4_

l se AX114 and AX115 Curie mN.

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i -4 ENuclear Calculation Sheet semei AX114 and AX115 Curle M No.

Rev. No.

SheetNo.

Loading 4240-3233-93-015 1

30 of bI y

Onenator Date Rowoomed by Date B. Brosey 9/8/93 G. Lodde

/jf 9, 4 93 4

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=

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3/8-in. HEAD

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MAKE.UP AND PURIFICATION DEMINERAll2ERS TOP CONNECTtONS

PROCESS INLET EVENT e RESIN ADDITION O$

e ACCESS COVER 1/48n. WALL m

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S

$ A u"

PROCESS OUTLET

RESIN StulCE Y

C 6 7 3j S it a

v U) zo l'[,'

cv

. i d TOP LATERALS j*#

os C

12 TOTAL 5

,9 4N

164n. LONG E

3/44n. *,30488 3

m e 21 HOLES. 3/1S in. PER LATERAL

]

(

=

SOTTOM LATERALS g e*n

C a 12 TOTAL o

+ 20-in. LONO

+ 3/4-in. *,304 SS

+ 21 HOLES. 3/1Ha, PER LATERAL h

a 100 MESH WIRE SCREEN 111/2 in.

d j

2 TANK VOLUME j

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PROCESS OUTLET REllN StulCE 2

a3 n =e Dimensions of demineralizer vessel.

g g

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' Attachment 5-1 2

Micro $hield Batch Run Log m

{

Batch Run Started on Wedrwsday, Septereer 8.1993 at 1:02 p.m.

Six cases initially in the queue.

j CASE FILE CEOM START TIME ELAPSED sWt/hr w/ BUILDUP SENS. CYCLE

_j

............... m...

4 h

1 AHIGMDEM 7

1:02 p.m.

0:26:06 1.526e+001 (n/a) 2 ALOWDMIN 7

1:28 p.m.

0:25:06 1.822e+001 (n/a) 3 AMIDDMIN 7

1:54 p.m.

0:25:52 1.673e+001 REFERENCE 4

AMIDDMIN 7

1:54 p.m.

0:51:11 4.767e+001 1 of 5 I

i 5

AMIDDMIN 7

1:54 p.m.

1:16:21 3.178e+001 2 of 5 I

g 6

AMIDDMIN 7

1:54 p.m.

1:41:30 2.185e+001 3 of 5 A

o i

7 AMIDDMIN 7

1:54 p.m.

2:06:42 1.561e+001 4 of 5 j

8 t)tIDDMIN 7

1:54 p.m.

2:31:56 1.153e+001 5 of 5 g

g-9 BMIGMDEM 7

4:26 p.m.

0:17:06 3.619e+000 (n/a) 10 BLOWEMI 7

4:43 p.m.

0:16:54 8.496e+000 (n/s) e l

11 BMIDDEMI 7

5:00 p.m.

0:17:01 5.107e+000 (n/s) l l

0 Batch run completed on Wednesday, Septentaer 8,1993 et 5:17 p.m.

TOTAL EXECUTION TIME: 4:15:22 A

" EE j

m u

as a

m

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.i

(,

Microshield 4.00 - Serial 84.00-00247 j

CPU Page

1 File Reft i\\

DOS file: ALOWDMIN.MS4 Cater

/

l[}

)

i Rm Date: July 27,1993 By:

Run Time: 11:07 a.m. Tuesday Checked:

I Duration: 0:25:06

'M Case

Title:

MAKEUP DEMIN AX114 & AX115 i

CEOMETRY 7 - Cylinder Volme - $1de Shields centimeters feet and inches Dose point coordinate X:

176.34 5.0 9.4 Dose point coordinate Y:

68.58 2.0 3.0 i

Dose point coordinate Z:

0.0 0.0

.0 Cylinder height:

1.94056 0.0

.8

. o Cylinder radius:

30.48 1.0

.0 E

Shield 1:

0.635 0.0

.3 g

Air Gap:

145.225 4.0 9.2 Y j, Source volme: 5663.79 cm*3

.200015 cu ft.

345.625 cu in.

E:

1 MATERI AL DENSITIES (g/cm'3) f~

Material Source Shield 1 Transition Air Gap Immersion Shield Cylinder Shield Shield Air 0.00122 0.00122 0.00122 Carbon 0.7463 i

fron 0.1485 7.86 0

Urani m 0.0036

?

j Water 0.1405 g

i eS as BUILDUP Method: Buildup factor Tables j$ l3 The (naterial reference is Shield 1 l

y

.h OU i!

INTECRAfl0N PARAMETERS

.t m

Quadrature Order CM Radial 22 8

D

'I Circumferential 22 Axial (alung Z) 22 j*

SOURCE NUCLIDES Nuclide curies nC1/cm*3 Nuclide curies gCl/cm*3 Ba 137m 2.5200e 001 4.4493e 001 Ce-144 1.7900e-006 3.1604e-004 3

Co-60 7.9700e-004 1.4072e-001 Cs-134 7.5500e-004 1.3330e-001 6.

Cs 137 2.6700e-001 4.7142e+001 Pr-144 1.7900e-006 3.1604e 004 3

Pr-144m 2.5500e-008 4.5023e-006 Sb-125 8.9100e-004 1.5732e-001 Sr-90 2.3900e-001 4.2198e+001 Te-125m 2.0600e-004 3.6371e-002 N

,1 Y-90 2.3900e-001 4.2198e+001 g

O k

E 9

========================= RESULTS=========================

5 cn I

Energy Activity Energy fluence Rate Exposure Rate in Air N

, f.

(Mev) (photons /sec )

(MeV/sq cm/sec)

(mR/hr)

E

-v No Buildup With Buildup No Buildup With Buildup g

<O 3 0.1 1.076e+005 1.756e-003 2.975e 003 2.686e-006 4.552e-006 a

0.15 8.989e+004 6.280e-003 1.212e-002 1.034e-005 1.995e-005 B 8 0.2 2.502e+006 3.236e-001 6.507e 001 5.711e-004 1.148e-003

{"

0.3 1.474e+005 3.688e-002 7.199e 002 6.995e-005 1.366e-004 g "-

0.4 1.032e+007 3.898e+000 7.198e+000 7.595e-003 1.403e-002 O

0.5 3.821e+006 1.958e+000' 3.417e+000 3.843e-003 6.708e-003 0.6 8.436e+009 5.514e+003 9.161e+003 1.076e+001 1.788e+001 0.8 2.630e+007 2.506e+001 3.857e+001 4.767e-002 7.336e 002 1.0 3.027e+007 3.846e+001 5.60Be+001 7.088e-002 1.034e-001 1.5 3.034e+007 6.414e+001 8.563e+001 1.079e-001 1.441e 001 2.0 5.126e+002 1.535e-003 1.955e-003. 2.373e-006 3.023e-006 TOTAL:

8.539e+009 5.64Be+003 9.353e+003 1.100e+001 1.E22e+001 l-l-

=.,

l. -3 f

Microshield 4.00 - Serial A4.00-00247 CPU Page-3.1 File Reft

. l\\,

DOS File: AMIDDMlW.MS4 Date:,_t g / g Run Date: July 27, 1993 Sy: At R e

l Run Times 11:33 a.m. Tuesday Checked: 1 tk%\\

Duration: 0:25:50 W 7\\

i Case

Title:

MAKEUP DEMIN Ax114 & Ax115 l

GEOMETRY 7 - Cylinder Volme - Side Shields centimeters feet and inches Dose point coordinate x:

176.34 5.0 9.4 K.

' Dose point coordinate T:

68.58 2.0 3.0 y

Dose point coordinate 2 0.0 0.0

.0 i

Cylinder height:

1.94056 0.0

.8 p.3 Cylinder radius:

30.48 1.0

.0 s

Shield is 0.635 0.0

.3 Air cap:

145.225 4.0 9.2 7 j Source Volune: 5663.79 cm*3

.200015 cu ft.

345.625 cu in.

.m MATERIAL DENSITIES (0/cm*3) 3 Material Source Shield 1 Transition Air Cap Immersion Shield cylinder Shield Shield Air 0.00122 0.00122 0.00122 i

Carbon 1.4927 I

Iron 0.2176 7.86 m

Uranlun 0.0073 5

l Water 0.2811

,J, cn r

BUILDUP g

C A@

Method: Buildup Factor Tables

.C

- m o

l.

The material referenceds Shield 1 (O EE h

INTEGRATION PARAMETERS 3

Quadrature Order

,5 m

Radial 22

3 cn Ciremferential 22

,o 3

Axial (along 23 22 es

.N O

f*

S0JRCE NUCLIDES l

Nuclide curies uCi/cm'3 Nuclide curies uCi/cm*3 Ba 137m 2.5200e-001 4.4493e+001 Ce-144 1.7900e-006 3.1604e-004 as co 60 7.9700e-004 1.4072e-001 Cs 134 7.5500e-004 1.'L330e-001 I

Cs-137 2.6700e 001 4.7142e+001 Pr-144 1.7900e-006 3.'. 604e-004 m

Pr 144m 2.5500e 008 4.5023e 006 Sb-125 8.9100e-004 1.5732e-001 Sr 90 2.3900e-001 4.2198e+001 Te-125m 2.0600e-004 3.6371e-002 T-90 2.3900e-001 4.2198e+001 b

===============s===

RESULTS===============================

mme c

Ener9y Activity Energy Fluence Rate Exposure Rate In Air Q

E (MeV)

(photons /sec )

(MeV/sq cm/sec).

. (mR/hr) g

$q No Buildup With Buildup No Buildup With Buildup eoe A

0.1 1.076e+005 1.267e-003 2.196e-003 1.93Be 006 3.359e-006

-E. E, 3

0.15 8.989e+004 4.673e-003 9.486e-003 7.6%e 006 1.562e 005

~ o g

0.2 2.502e+006 2.479e-001 5.369e-001 4.376e-004. 9.476e-004 a as 1:

0.3 1.474e+005 2.924e-002 6.274e-002 5.546e-005 1.190e-004 0.4 1.032e+007 3.159e+000 6.444e+000 6.156e-003 1.256e-002 6*

i 0.5 3.821e+006 1.613e+000 3.106e+000 3.166e-003 6.097e-003 l

, 0.6 8.436e+009 4.602e+003 8.405e+003 8.983e+000' 1.641e+001 C.8 2,630e+007 2.134e+001 3.578e+001 4.058e-002 6.806e-002 1.0 3.027e+007 3.323e+001 5.234e+001 6.125e-002 9.648e-002 1.5 3.034e+007 5.684e+001 8.079e+001 9.563e-002 1.359e-001 2.0 5.126e+002 1.382e-003 1.858e-003 2.137e-006 2.874e-006 701AL:

B.539e+009

4. 719e+ 003 S. 581.e+ 003 9.191e+000 1.673e+001 l:

_5

- Attachment 5-4

-l

+

Microshield 4.00 - Serial #4.00-00247 CPU Page

1 File Ref:

.n DOS File: AHIGHDEM.MS4 Date:

h Run Date: July 27, 1993 By:

Run Times 10:42 a.m. luesday Checked:

'l th' m\\6%

Duration: 0:26:07

'M Case

Title:

MAKEUP DEMIN AX114 & AX115 GEOMETRY 7 Cylinder Volume - Side Shields centimeters feet and ir;ches Dose point coordinate X:

176.34 5.0 9.4' Dose point coordinate Y:

68.58 2.0 -

3.0 N

Dose point coordinate 2:

0.0 0.0

.0

/

cylinder height:

1.94056 0.0

.8 9

i Cylinder radius:

30.48 1.0

.0 Shield 1:

0.635 0.0

.3 y

s Air caps 145.225 4.0 9.2 2

3

'Y i s.

Source Volume 5663.79 cm*3

.200015 cu f t.

345.625 cu in.

o j

g.

?

MATERIAL DENSITIES (g/cm*3) 2.-

Material source Shield 1 Transition Air Cap Inunersion j

Shield Cylinder Shield Shield Air 0.00122 0.00122 0.00122 Carbon 2.239 fron 0.2868 7.86 Urantun 0.0109 m

j Water 0.4216 5

'h i

cA BUILDUP cu Method: Buildup factor Tables g

Q g]

i The material reference is shield 1

.c

. rn o

U)

E c$

h INTEGRATION PARAMETERS a

Quadrature Order

. ;lll Radial 22 e

n circunf erential 22 m

Axist (along 2) 22 O

g 25

.N O

E*

')

SOURCE NUCL10ES O

Nuclide curies uti/cm'3 Nuclide curies' uti/cm'3 Ba-137m 2.5200e-001 4.4493e+001 Ce-144 1.7900e-006 3.1604e-004 co-60 7.9700e-004 1.4072e-001 Cs-134 7.5500e-004 1.3330e-001 j

e Cs 137 2.6700e 001 4.7142e+001 Pr-144 1.7900e-006 3.1604e-004 Pr-144m 2.5500e-008 4.5023e-006

$b-125 8.9100e-004 1.5732e-001 5

j Sr-90 2.3900e-001 4.2198e+001 Te-125m 2.0600e 004 3.6371e 002

.]

Y-90 2.3900e-001 4.2198e+001' e

&m O

i e-a

/9

............................... mU, T, Energy Activity Energy Fluence Rate Exposure Rate In Air 3-l (MeV)

(photons /sec )

(Nev/sq cm/sec)

(mR/hr) g

l l

No Buildup With Buildup No Buildup With Buildup

-r -

g 0.1 1.076e+005 9.647e 004 1.694e-003 1.476e-006 2.591e 006 0.15 8.989e+004 3.629e-003 7.609e-003 5.975e-006' - 1.253e-005-E y%

Z w

o o

0.2 2.50?e+006 1.964e-001 4.472e-001 3.467e-004 7.893e-004 o

E 5 0.3 1.474e+005 2.376e-002 5.456e-002 4.506e-005 1.035e-004

-E E

0.4 1.032e+007 2.611e+000 5.736e+000 ~5.088e-003 1.118e-002' 0.5 3.821e+006 1.351e+000 2.805e+000 2.652e-003' 5.506e-003 j

f c5 0.6 0.436e+009 3.896e+003 7.665e+003~ 7.605e+000 1.496e+001 0.8 2.630e+007 1.837e+001 3.305e+001' 3.493e 002 6.286e-002 1.0 3.027e+007 2.897e+001 4.871e+001 5.340e-002 8.978e-002 1.5 3.034e+007 5.067e+001

'7.603e+001 8.525e-002 1.279e-001 2.0 5.126e+002 1.249e-003 1.761e-003 1.932e-006 2.724e-006 TOTAL:

8.539e+009 3.998e+003 7.832e+003 7.787e+000 1.526e+001

{c..

3

- -5 Micro $hield 4.00 - Serial 84.00-00247 GPU Page

1 File Reft it DOS Files BLOWEMI.MS4 Date:

W h

Run Date! Septanber 8,1993 By:

I Run Time: 5:00 p.m. Wednesday Checked: \\ E Duration: 0:16:54 "W

Case

Title:

MAKEUP DEMIN Ax114 & Ax115 GEOMETRY 7 - Cylinder volune - Side Shields centimeters feet and inches Dose point coordinate x:

270.97 8.0 10.7 Dose point coordinate Y:

68.58 2.0 3.0 q,

Dose point coordinate 2 0.0 0.0

.0 Cylinder height:

17.2212 0.0 6.8 15 s

cylinder radius:

60.96 2.0

.0 I

Shield 1:

0.635 0.0

.3

]

=

s-Air Gaps 209.375 6.0 10.4 aN 5 Source volune: 201050. cm*3 7.1 cu ft.

12268.8 cu in.

g k

MATERIAL DENSITIES (g/cm*3)

Material source Shield 1. Transition Air Gap Immersion Shield Cylinder Shield Shield Air 0.00122 0.00122 0.00122 Carbon 0.7463 o

g 3

Iron 0.0931 7.86 Urantun 0.0007 t,

Water 0.1405 g

g g=

2 m

n

(/) I c5

.3 BUILDUP jN C:

Method: Buildup Factor Tables

.9 The material reference is Source 55

- - - - "*" CAUT I ON "*****"*

u Q

This buildup reference material is a mixed material with a high atomic 3

number element (91). Buildup Factors less than and somewhat greater

'. O

.g jT N

than 113 kev may be incorrect.

...........e............u...Pl ase understand your resultsi INTEGRATION PARAMETERS' I

Quadrature order 8

Radial 22

{

Circumferential 22

@f Axial (along 2) 22

]

h SOURCE NUCLIDES Nuclide curies

Cl/cm*3 Nuclide curies gCi/cm'3 g

Ba 137m 4.6100e-001 2.2930e+000 Cs 134 1.3500e-003 6.7148e 003 Cs 137 4.8700e-001 2.4223e+000 Sr-90 2.5100e-002' 1.2484e-001 E

"E D

Y-90 2.5100e 002 1.2484e-001 3

j@

fG d

d e'

= = = = = = = = = = = = = = = = = " = = = = = = " = = RESdt,TS=============================

Energy Activity Energy Fluence Rate Exposure Rate In Air (Nev) (photons /sec )

(MeV/sq cm/sec)

(ndt/hr)

No Buildup. With Buildup No Buildup With Buildup 0.3 1.768e+004' 5.282e-004-2.415e-003 1.002e-006 4.582e-006 0.5 7.293e+005 5.063e-002 1.693e-001' 9.937e-005 3.323e-004 0.6 1.541e+010 1.434e+003 4.334e+003 - 2.799e+000 8.459e+000 0.8 4.702e+007 6.925e+000 1.802e+001 1.317e-002 3.428e-002 E

1.0 1.399e006 2.937e-001 6.892e-001 5.413e-004 1.270e-003 1.5 1.510e 006 6.021e-001 1.192e+000 1.013e-003 2.006e-003 TOTAL:

1.546e+010 1.442e+003 4.354e+003 2.814e+000 8.496e+000

'I T1 3.

O J -6

.')

i MicroShield 4.00 - Serial #4.D0-00247

- l i

GPU Page-

1 File Reft Eb.

1l I

)

DOS File: BMIDDEMI.MS4 Dater RLet Cates. Septenezer 8,1993 By:

a i

Run Time: 5:17 p.m. Wednesday Checked: 1 V7o\\

j Duration: 0:17:02

~\\

- l Case

Title:

MAKEUP DEMIN AX114 & AX115 h

l GEOMETRY 7 Cylinder Volume - Side Shields I

centimeters feet and inches g

i Dose point coordinate X:

270.97 8.0 10.7 O

f4) j Dose point coordinate Y:

68.58 2.0 3.0 Dose point coordinate 2:

0.0 0.0

.0 Cylinder height:

17.2212 0.0 6.8 Cylinder radius:

60.96 2.0

.0 I

Shield is 0.635 0.0

.3 j~

Air Gap:

209.375 6.0 10.4 i

\\g Source Volume 201050, em 3 7.1 cu ft.

12268.8 cu in.

MATERIAL DENS! TIES (g/ca'3) k Material Source Shield 1 Transition Air cap immersion m

Shield' Cylinder Shield Shield 5

p i

Air 0.00122 0.00122 0.00122 e

m E u, Carbon 1.4927 j g]

]

Iron 0.107 7.86

$ $ or0 si Uraniun 0.0015 Water 0.2811 g;

23 m

BUILDUP M

.Q Methods Buildup Factor Tables y

eR 5m The material' reference is Source

...******* CAUTION **********

This buildtp reference material is a mixed material with a high atomic

(

jI number element (91). Buildup Factors less than and somewhat greater -

than 113 kev may be incorrect. Please understand your resultsi 3

E=i I

INTEGRATION PARAMETERS S

3 Quadrature Order g

.n Radial 22

=

0 circunf erential 22 O

Q Axial (along 2) 22 3

m 2

--e SOURCE NUCLIDES h

Nuclide curies

Cl/cm*3 Nuclide curies gCf/cm*3 g 5, Ba 137m 4.6100e-001 2.2930e+000 Cs 134 1.3500e-003 6.714Be 003 a

6m Co-137 4.8700e-001 2.4223e+000 Sr-90 2.5100e-002 1.2484e-001 Y-90 2.5100e-002 1.2484e 001

=============...=======.= RESULTS=====*===================

Energy Activity Energy Fluence Rate Exposure Rate In Air (MeV)

(photons /nc /

(MeV/sq cm/sec)

(mR/hr)

No Buildup With Bulldup No Bulloup With Buildup.

0.3 1.768e+004 2.907e-004 1.414e-003-5.514e-007 2.682e-006 0.5 7.293e 005 2.822e-002 1.009e-001 5.539e-005 1.981e-004 0.6 1.541e+010- 8.042e+002 2.605e+003 1.570e+000 5.084e+000 -

0.8 4.702e+007 3.930e+000- 1.100e+001 7.475e-003 2.092e-002 1.0 1.399e+006 1.686e 001 4.264e-001 3.107e-004-7.860e-004 1.5 -

1.518e+006 3.546e-001 7.602e-001 5.967e-004 1.279e-003 TOTAL:

1.546e+03 8.087e+002 '2.617e+003 1.578e+000 5.107e+000

)

.y 7

.a -7 MicroShield 4.00 - 'Seriet #4.00-00247 CPU Page-

1 File Reft Or DOS File: BHIGHDEM.MS4 Date: At /ge i

Y Rui Date Septanber 8,1993 By:

Rd q7 Rm Time 4:43 p.m. Wednesday Checked: l ' R.\\

Duration: 0:17:06 3

-Case Titte: MAKEUP DEMIN AX114 & AX115 GECMETRY 7 - Cylinder Volme - Side Shields 9

centimeters-feet and inches Dose point coordinate X:

270.97 8.0 10.7

\\.

g

^

Dose point coordinate Y 68.55 2.0 3.0 -

g Dose point coordinate 2:

0.0 0.0

.0 g g, Cylinder height:

17.2212 0.0 6.8 Cylinder radius:

60.96 2.0

.0 l

Shield 1 0.635 0.0

.3 I

j Air Gap:

209.375 6.0 10.4

~

Source Volume: 201050. cm*3' 7.1 cu ft.

12268.8 cu in, f

m MATERIAL DENSITIES (g/cm*3) g Material Source Shield 1 Transition Air Cap Irsnersion

,4 shield Cylinder Shield Shield m

j Air 0.00122 0.00122 0.00122 m

carbon 2.239 C '0 Iron 0.1208 7,86 7

3 l

E Uraniun 0.0022 '

O

_g 8@

i Water 0.4216 O

d 3

e BUILDUP 3

i m

Method: Buildup factor Tables M

m

.j The nwterial reference is Source y

5 *co

- - - - CAUTION **********

t This buildup reference material is a mixed materlat with a high atomic en number element (91). Buttdup Factors less than and somewhat greater

~S g

than 113 kev may be incorrect Please understand your resultst o

INTEGRATION PARAMETERS 3.

Quadrature Order g

3 h-Radial 22 g

m Circunf erential 22 0

==

Asist (along Z) 22

=

t 1

SOURCE NUCLIDES a

Nuclide curies

Cf/cm'3 Nuctice curies

Ci/cm"3

% l2 Be 137m 4.6100e 001 2.2930e+000 Cs 134 1.3500e-003 6.714Be-003 O.h" l

Cs 137 4.8700e-001 2.4223e+000 Sr-90 2.5100e-002 1.2484e-001 Od 4

Y 90 -

2.5100e-002 1.2484e-001 i

========================= RESULTS=========================

Energy Activity Energy Fluence Rate Exposure Rate In Air (MeV)

( $ ctons/sec )

(MeV/sq cm/sec)

(sit /hr)

No Buildup With Buildup No Buildup With Buildup 0.3 1.768e+004 2.003e-004 9.941e-004 3.800e 007 1.886e-006 0.5 7.293e+005 1.952e-002 7.133e-002 3.832e-005 1.400e-004 0.6 1.541e+010 5.575e+002 1.846e+003 1.088e+000 3.603e+000 0.8 4.702e+007 2.735e+000 7.831e+000 5.202e-003 1.490e-002 1.0 1.399e+006 1.177e 001 3.050e-001 2.170e-004 5.623e-004 1.5 1.518e+006 2.498e-001 5.496e-001 4.203e-004 9.247e-004 TOTAL:

1.546e+010 5.606e+002 1.855e+003 1.094e+000 3.619e+000

n-

. -1 Micro $hield Batch Rm Log Batch Run Started on WeMenday, Septecher 8,1993 at 1:02 p.m.

Six cases initially in the queue.

CASE FILE GEDM START TIME ELAPSED mR/hr w/ BUILDUP SENS. CYCLE h

1 AHICHDEM 7

1:02 p.m.

0:26:06 i.526e+001 (n/a) 2 ALOWDMIN 7

1:28 p.m.

0:25:06 1.822e+001 (n/s) 3 AMIDDMIN 7

1:54 p.m.

0:25:52 1.673e+001 REFERENCE j

\\

4 AMIDDMIN 7

1:54 p.m.

0:51:11 4.767e+001 1 of 5 r) ffry j 5

AMIDDMIN 7

1:54 p.m.

1:16:21 3.178e+001 2 of 5 6

AMIDDMIN 7

1:54 p.m.

1:41:30 2.185e+001 3 of 5 7

AMIDDMIN 7

1:54 p.m.

2:06:42 1.561e+001 4 of 5 8

AMIDDMIN 7

1:54 p.m.

2:31:56 1.153e+001 5 of 5 I

9 BMICHDEM 7

4:26 p.m.

0:17:06 3.619e+000 (n/a) j~

i 10 BLOWDEMI 7

4:43 p.m.

0:16:54 8.496e+000 (n/a) i 11 BMIDDEMI 7

5:00 p.m.

0:17:01 5.107e+000 (n/a)

Batch run completed on Wechesday, September 8,1993 at 5:17 p.m.

A cn TOTAL EXECUTION TIME: 4.15:22 A

~

l U)

E tb

'O

@ $5 Ld Page

2 m

DOS File: BMIDDEMI.MS4 3

i Rm Date Septenber 9,1993

3 Run Time: 9:17 a.m. Thursday S

R Titte : MAKEUP DEMIN AX114 & AX115 y

j*

SEN5ITIVITY RESULIS for: X (cm)

Case Sensitivity Energy Fluence Rate Exposure Rate in Air g'

NL. saber Variable (MeV/sq cm/sec)

(mR/hr)

Value No Buildup With Buildup No Buildup With Buildup e

i 1

304.8 6.057e+002 1.969e+003 1.182e+000 3.843e+000 3

a i

2 251.46 9.714e+002 3.136e+003 1.896e+000 6.121e+000 e

3 198.12 1.737e+003 5.587e+003 3.390e+000 1.090e+001 1.

I d

4 144.75 3.607e+003 1.166e+004 7.039e+000 2.276e+001 (5

3 M j

5 91.44 8.406e+003 2.835e+004 1.640e+001 5.534e+001 (g

i rj

.n g

s gg U.e,he oi.,ia, M_,o, Ene,,y Crou. Re.u, t.,o, m C..e..

z e

$E a

E so l

l l

l t

i l

l l

t l

r

E.--

+ -2 Microshield 4.00 - Seria! #4.00-00247 CPU Page 1

File Ref:

/k _

DOS File: AMIDOMIN.MS4 Date:

G Y'

Run Date: July 27, 1993 By: 71 Run Time: 3:45 p.m. Tuesday Checked: \\ F ob Duration: 2:57:58

" In Case

Title:

MAKEUP DEMIN AX114 & Ax115 GEOMETRY 7 Cylinder Volune - Side Shields centimeters feet and inches Dose point coordinate x:

176.34 5.0 9.4 Dose point coordinate Y:

68.58 2.0 3.0 Dose point coordinate Z:

0.0 0.0

.0 Cylinder heignt:

1.94056 0.0

.8 k

Cylinder radius:

30.48 1.0

.0 h

Shield 1:

0.635 0.0

.3 Air cap:

145.225 4.0 9.2 3

g s

f jh Source volune: 5663.79 cm'3

.200015 cu ft.

345.625 cu in.

MATERIAL DENSITIES (g/cm 3) o Material Source Shield 1 Transition Air Gap Inunersion

M j

Shield Cylinder Shield Shield j

Air 0.00122 0.00122 0.00122 Carbon 1.4927 Iron 0.2176 7.86 Uraniun 0.0073 g k Water 0.2811 5

BUILDUP A

+*

a, Method: Buildup Factor Tables h

gg m

The material reference is Shield 1

,cl:

m o

U) z cs h

INTEGRATION PARAMETERS Quadrature Order Radial 22

.5 Q

{

Circunf erential 22 3

Axial (along 2) 22

.9 W

2 G

2N O

\\

SOURCE NUCLIDES Nuclide curies

Cl/cm'3 wuctide curies gCl/cm 3 Ba-137m 2.5200e-001 4.4493e+001 Ce 144 1.7900e-006 ? 1/34e-004 co-60 7.9700e-004 1.4072e 001 Cs 134 7.5500e-004 1.3330e 001 3

Cs 137 2.67006-001 4.7142e+001 Pr-144 1.7900e-006 3.1604e-004 h

I Pr-144m 2.5500e-008 4.5023e 006 Sb-125 8.9100e-004 1.5732e-001 v

Sr-90 2.3900e-001 4.2198e+001 Te-125m 2.0600e-004 3.6371e-002 m

C Y-90 2.3900e 001 4.219Be+ 001 km C

N 5

W u

==== RESULTS FOR SENSITIVITY REFERENCE CASE (X = 176.34)====

==

c Energy Activity Energy Fluence Rate Exposure Rate In Air Q

E (MeV)

(pho ons/sec )

(MeV/sq cm/sec)

(mR/hr) g ZE No Buildup With Buildup No Buildup With Buildup Qg g

0.1 1.076e+005 1.267e-003 2.196e-003 1.938e-006 3.359e-006 4.>

a 0.15 8.989e+004 4.673e-003 9.486e-003 7.696e-006 1.562e-005 Q

g8 0.2 2.502e+006 2.479e-001 5.369e-001 4.376e-004 9.476e-004 d

E g"

E m

0.3 1.474e+005 2.924e-002 6.274e-002 5.546e-005 1.190e-004 7

{

g 0.4 1.032e+007 3.159e+000 6.444e+000 6.156e-003 1.256e-002 L

0.5 3.821e+ 006 1.613e+000 3.106e+000 3.166e-003 6.097e-003 0.6 8.436e+009 4.602e+003 8.405e+003 8.983e+000 1.641e+001 0.8 2.630e+007 2.134e+001 3.578e+001 4.058e-002 6.806e-002 1.0 3.027e+007 3.323e+001 5.234e+001 6.125e-002 9.648e-002 1.5 3.034e+007 5.684e+001 S.079e+001 9.:53e-002 1.359e-001 2.0 5.126e+002 1.382e-003 1.858e-003 2.137e-006 2.874e-006 TOTAL:

8.519e+009

4. 719e+ 003 S.584e+003 9.191e+000 1.673e+001

=,~.

. -3 Page 2 2 DOS File: AMIDOMIN.MS4 Run Date: July 27,1993 Run Time: 3:45 p.m. Tuesday iltle : MAKEUP DEMIN AX114 & AX115 SENSITIVITY RESULTS For: X (cm)

Case Sensitivity Energy fluence Rate Exposure Rate in Air Ntsuber Variable (MeV/sq cm/sec)

(mR/hr)

Value No Buildup With Buildup No Buildup With Buildup 1

91.44 1.382e+004 2.447e+004 2.692e+001 4.767e+001 2

121.92 9.231e+003 1.631e+004 1.798e+001 3.178e+001 3

152.4 6.260e+003 1.122e+004 1.219e+001 2.185e+001 4

182.88 4.384e+003 8.011e+003 8.539e+000 1.561e+001 5

213.36 3.173e+003 5.920e+003 6.179e+000 1.153e+001 Use the Display Menu For Energy Group Results For All Cases, w

'o A

3 l~

=?

A a.

G3 0 E$

I m I o f/) Ed j" 5 85i 5 O

3 m

0 i&

]

a, I3 o

b, h)

E G

e E

U

?

ll3 E

3$

i a

l i =e l

i

'I G=

4 -4 Microshield 4.00 - Serial #4.00-00247 Page

1 File Ref:

I DOS File: BMIDDEMI.MS4 Date:

Rm Date: September 8, 1993 By:

l'

\\.

Run Time: 5:17 p.m. Wednesday checked: 'Mr\\

Duration: 0:17:02 D,

Case

Title:

MAKEUP DEMIN Ax114 & Ax115

,3 k

GEOMETRY 7 - Cylinder Volune - Side Shields fg jQN centimetera feet and inches Dose point coordinate x:

270.97 8.0 10.7 u) o Dose point coordinate Y:

68.58 2.0 3.0 Dose point coordinate Z:

0.0 0.0

.0 Cylinder height:

17.2212 0.0 6.8 Cyltrder radius:

60.96 2.0

.0 g-Shield 1:

0.635 G.0

.3 g

Air Cap:

209.375 6.0 10.4 Source volune 201050. cm'3 7.1 cu ft.

12268.8 cu in.

m MATERIAL DENSITIES (g/cm*3) o Material Source Shield 1 Transition Air Cap Innersion 8

Snfeld cylinder Shield shield i

Air 0.00122 0.00122 0.00122 e

carbon 1.4927

.G

, a3

)

Iron 0.107 7.86 9

N at Urantun 0.0015

.C 67 IE Water 0.2811 (A

zo O *E j(. a 2

g K

O BUILDUP

=

4 )

Method: Buildup Factor Tables g

The material reference is Source U

rn

.......*** CAuT10W **********

3 R

This buildup reference material is a mixed material with a high atomic N

e as number element (91). Buildup Factors less than and somewhat greater O

than 113 kev may be incorrect. Please understand your results!

cn INTEGRATION PARAMETERS

.5 i

Quadrature Order t

i Radial 22 3

i circumferential 22 J

Axial (along 2) 22 as Ims E

3 SOURCE NUCLIDES N

Nuclide curies gCl/cm 3 Nuclide curies acl/cm 3 g

m Ba-137m 4.6100e-001 2.2930e+000 Cs-134 1.3500e-003 6./148e-003 maan Cs-137 4.8700e-001 2.4223e+000 Sr 90 2.5100e-002 1.2484e-001 g-Q

~

y-90 2.5100e-002 1.2484e-001 gz e

..............===.........====.RESULTS===============================

m Energy Activity Energy Fluence Rate Exnosure Rate In Air

r go (MeV)

(photons /sec )

(MeV/sq cm/sec)

(udt/hr)

).

3m No Buildup With Buildup No Buildup With Buildup 5x Ja 0.3 1.768e+004 2.907e-004 1.414e-003 5.514e-007 2.682e-006 6 cd 0.5 7.293e+005' 2.822e-002 1.009e-001 5.539e-005 1.981e-004 0.6 -

1.541e+010 8.042e+002 2.605e+003 1.570e+000 5.084e+000 0.8 4.702e+037 3.930e+000 1.100e+001 7.475e-003 2.092e-002 1.0 1.399e+006 1.686e-001 4.264e-001 3.107e-004 7.860e-004 1.5 1.518e+006 3.546e-001 7.602e-001 5.967e-004 1.279e-003 TOTAL:

1.546e+010 8.087e+002 2.617e+003 1.578e+000 5.107e+000

.ig..s_

i h

l -5 Page

2 DOS Files BMIDDEMI.MS4 Run Date: Septemer 9, 1993 RLn Time: 9:17 a.m. Thursday Title : MAKEUP DEMIN AX114 & AX115 SENSITIVITY RESULTS For: X (cm)

Case Sensitivity Energy Fluence Rate Exposure Rate In Air NLater Variable (MeV/sq cm/sec)

(nR/hr)

Value No Buildup With Buildte No Buildup With Buildup 1

304.8 6.057e+002 1.969e+003 1.182e+000 3.843e+000 l

2 251.46 9.714e+002 3.136e+003 1.896e+000 6.121e+000 3

198.12 1.737e+003 5.587e+003 3.390e+000 1.090e+001 4

144.78 3.607e+003 1.166e+004 7.039e+000 2.276e+001 g

i 5

91.44 8.406e+003 2.835e+004 1.640e+001 5.534e+001 g

IV, Use the Display Menu For Energy Group Results for All Cases.

,g 2

}b s

i' l-O e

t.

y g

g if j.S va

@ 80 AJ

~

-5

_m N

O r;

8 a

W h

' N 3

3, f:

3z e

s

.=

A

.E a

l i

)

i

-I

)

1 4

~

i g

+ -1 MicrcShield 4.00 - Serial #4.00 00247 GPU Page

1 File Reft i De M o D.

DOS File: ADPIPE2.MS4 Date:

1/

P Run Date: July 27,1993 By:

Run Times 2:44 p.m. Tuesday Checked:

V1 o U Ouratlon: 0:25:43 7i i

1 Case

Title:

PIPE AT BASE OF A DEMIN CEOMETRY 7 - Cylinder Vol m e - Side Shields centimeters feet and inches Dose point coordinate x:

176.784 5.0 9.6 h

Dose point coordinate Y:

60.96 2.0

.0 Dose point coordinate 2:

0.0 0.0

.0 Cylinder height:

22.86 0.0 9.0

- o cylinder radius:

3.89636 0.0 1.5 E

N Shield 1:

0.54864 0.0

.2

{M t

gh j.

Air cap:

172.339 5.0 7.9 Source Volme: 1090.3 cm'3 3.85034e-2 cu ft.

66.5339 cu in.

E i

MATERIAL DENSITIES (g/cm*3)

Material Source Shield 1 Transition Air Cap Imersion Shield cylinder Shield Shield Air 0.00122 0.00122 0.00122 Carbon 1.4927 m

Iron 0.2176 7.86 Uranium 0.0073 T

Water 0.2811 Q

N m

i BUILDUP O

h j @7 3

Method: Buildup Factor Tables The material reference is shield 1 y

C t.s O ew O

INTEGRATION PARAMETERS Q

Quadrature Order Radial 22 3

Ciremf erent f el 22 M

^*

y j5 Axial (along 2) 22 SOURCE NUCLIDES Nuclide curies

Ci/cm*3 Nuclide curies Aci/cm*3 Ba-137m 2.5200e-001 2.3113e+002 Ce.144 1.7900e-006 1.6418e-003 m

(O co-60 7.9700e-004 7.3099e-001 Cs-134 7.5500e-004 6.9247e-001' L

Ca*137 2.6700e-001 2.4489e+002 Pr 144 1.7900e-006 1.6418e-003 3

pr 144m 2.5500e 008 2.338Be-005

$b 125 8.9100e-004 8.1721e-001 q

g d

Sr-90 2.3900e-001 2.1921e+002 Te 125m 2.0600e-004 1.8894e-001 T-90 2.3900e-001 2.1921e+002 S'

<O 9

u

$ en

============================ RESULTS===========================*

Energy Activity Energy fluence Rate E."posure Rate In Air N

,3

}

(MeV)

(photons /sec )

(MeV/sq cm/sec)

(mR/hr) 3

-v Wo Buildup With Buildup No Buildup With Buildup g

N$

h 0.1 1.076e+005 1.573e-003 2.672e-003 2.406e-006 4.088e-006

<W g *g 0.15 8.989e+004 5.112e-003 1.019e-002 8.419e-006 1.679e-005 5-0.2 2.502e+006 2.635e-001 5.624e-001 4.651e-004 9.927e-004 E.

e 0.3 1.474e+005 3.060e-002 6.513e-002 5.804e-005 1.236e-004

{

[d 0.4

. 1.032e+007 3.292e+000 6.685e+000 6.415e-003 1.303e-002 m

0.5 3.821e+006 1.678e+000 3.224e+000 3.294e-003 6.328e 003-0.6 8.436e+009 4.784e+003 8.728e+003 9.338e+000 1.704e+001 0.8 2.630e+007 2.217e+001 3.720e+001 4.216e-002 7.075e-002 1.0 3.027e+007 3.452e+001 5.445e+001 6.363e-002 1.004e-001 1.5 3.034e+007 5.909e+001 8.413e+UO1 9.942e-002 1.416e-001 2.0 5.126e+002 1.438e-003 1.937e-003 2.224e-006 2.996e-006 TOTAL:

8.539e+009 4.90$e+003 8.915e+003 9.554e+000

1. 737e+001

~

i e-

+

S*:

! -1 l

i Microshield 4.00 - Serial #4.00 00247

(

GPU h,

Page

1 File Ref:

M d i

DOS File: 821NLINE.MS4 Date; p

t Rm Date: Septenber 9,1993 By:

ai 1

Rm Time: 9:45 a.m. Thursday Checked: I Duration: 0:11:33 Case Titte: PIPE AT BASE OF 8 DEMIN A

CEOMETRY 7 - Cylinder Volme - Side Shields j

9 centimeters feet and inches l

Dose point coordinate M:

217.17 7.0 1.5 Dose point coordinate Y:

44.81 1.0 5.6 Dose point coordinate 2:

87.63 2.0 10.5 g

Cylinder height:

228.6 7.0 6.0 I

Cytinder radius 2.62509 0.0 1.0 y%

shield 1:

0.39116 0.0

.2 g t)

]

Air Gaps 214.15375 7.0

.3 P

Source Volm e 4948.97 cm 3

.174771 cu f t.

302.004 cu in.

Ik-MATERIAL DEhSITIES (g/cm*3)

Meterial Source Shield 1 Transition Air cap Shield Cylinder Shield Air 0.00122 0.00122 5

in carbon 1.4927 A

Iron 0.0277 7.86 uranim 0.0015 I

2 Water 0.2811 j

M I :,g, j

sn &f 3

}

BUILDUP h

E a5 Method: Buildup Factor Tables 3

The material reference is Source 3

1 3

m i

- - - - CAUTION **********

I This build m reference material is a mixed material with a high atomic o

j*R ruter element (91).~ 8uildup Factors less than and somewhat greater than 113 key may be incorrect.

Pleas

.......... e understand your results!

p r

INTEGRATION PARAMETERS g

7 Quadrature Order '

Radial 20 Ciremferential 20 b

I Axist (along 2) 20 15 0

=

SOURCE NUCLIDES O

h i

Nuclide curies

CI/cm*3 Nuctide curies gC1/cm*3 E

e Ba-137m 4.6100e-001 9.3151e+001 Ce 144 0.0000e+000 0.0000e+000 E

D i

Co-60 0.0000e+000 0.0000e+000 Cs-134 1.3500e-003 2.7278e-001 gg Cs 137 4.8700e-001 9.8404e+001 Pr-144 0.0000e+000 0.0000e+000 0 ]g Pr-144m - 0.0000e+000 0.0000e+000 Sb 125 0.0000e+000 0.0000e+000 g

3..

Sr-90 2.5100e-002 5.0718e+000 Te 125m 0.0000e+000 0.0000e+000

=

6 co Y-90 2.5100e-002 5.0718e+000 I

= = = = = = = = = = = = = = = = = * " * = = = = = = = = = RESULTS==============================

Energy Activity Energy Fluence Rate Exposure Rate in Air i

(MeV)

(photons /sec )-

(MeV/sq cm/sec)

(mR/hr)

No Bulldup With Build @ - No suitdup With Buildup 0.3

.1.768e+004 2.820e-003 6.725e-003-5.349e-006 1.276e-005 0.5 7.293e+005 2.297e-001 4.260e-001 4.510e-004 8.363e-004 0.6 1.541e+010 6.141e+003 1.059e+004 1.199e+001 2.068e+001 0.8 4.702e+007 2.702e+001 4.203e+001 5.139e-002 7.995e-002 1.0 1.399e+006 1.063e+000 1.557e+000- 1.960e-003 2.870e-003 1.5 1.518e+006 1.900e+000 2.517e+000 3.197e-003 4.236e-003 TOTAL:

1.546e+010 6.171e+003 1.064e*004 1.204e+001 2.077e+001 W'

w w

-+e-r--

y

.c

.r-Attachment.9-1 "A" DEMIN EXPOSURE RATE PER CURIE 50 45.

40

.x 35

.x' N-

,_o

.\\

N

~

d-R 30 cc

'N' E

25 N'

A4

" ' ~

'N

\\

.O 3

20

]R i; j

15

-q j~

N

):

10 (i

)

m 3

3.5 4

4.5 5

5.5 6

6.5 7

NUMBER OF FEET FROM "A" DEMIN CENTERLINE 5

5.e is

\\

9

.c

,o VJ $$,{

_E$$ d S-

~s m,

Ni j *i R

o 3

'5 u

i m

l h

S U

e' t

3 M

=

~2 b

ame

<c a m.

1 y ~ '?

I e"

$A

~s

-- ~.

..n

-.~2.-

..a.s.

l

.a u.

3 3.-

Att8chment 9-2 I\\Exponen't'let regression

\\correlstfon statistics:

_-\\ correlation coefficent = -0.966758

\\mean of x's 5

'1

\\mean of y = 25.688

\\ standard deviation of x = 1.41421

)

\\ standard deviation of y = 12.9388 i

' \\verience of x = 2

\\ variance o' y = 167.413-

\\covariance of x and y = -17.69 l\\D2ta format Curve

l Wertable format Non-parametric i

.\\Anguter units: Radians i

\\x=3,7,100,0 i

\\y=133.6

0.7012*x 100 2 3 46.061' 3.0404 45.4051 j

3.08081 44.7585-g

'3.12121 44.1212 1

3.16162 43.4929 -

- o E

3.20202 42.8736 g

I 3.24242 42.2631

)h {

6 3.23283 41.6613 j

O 3.32323 41.0681 3.36364 40.4833 E-

.3.40404 39.9068 j

3.44444 39.3385 i

3.48485 38.7784 3.52525 38.2262 3.56566 37.6819 0

3.60606 37.1453 o

3.64646 36.6164 g

3.68687 36.095 g

A 3.72727 35.581 e

O Ag 3.76768 35.0743

.E

- ?

o

?

O 3.80808 34.5749 -

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S 10-E6-EEZE-Ob2t' Sutpeol ou =.e ou w ow ni.a a una stixv pue etIxv m laatis uonelnoteo JeegonN RAD:0 LOGICAL SVo.VEY Survey Information Instrument Data Air Samole File Code Number: AX115-3rl-5T

Contamination Survey Radiation Survey

hQ Time 5mearable Contamination

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Streey Infermation Irstrument Data

Air SaTole File Cod) Number: AX115 - //4 -87

Contailnation Survey Radiaticn Surrey

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Survey Information Instrument 'Jata Air Samole

File Code Number: Ay114 -cJp-Y -

Contamination Survey

- Radiation Survey

ITItN Time Smearable Contariination

Location 3MOv th b or :I nsk, Inst

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SubjeQ4AKE-UP AND PURIFICATION DEMINERALIZERf MU-K-183 Date:

October 21, 1988 AND CUBICLE RADIATION SURVEY N

1345a From: B. M. Trachim Location:TMI-2 Radiological Engineer 9240-88-4745 To:

J. E. Tarpinian i

K Manager, Radiologicci Engineering. TMI-2 b

,O On 9-28-88 a robotic radiation survey of the "B" Make-up and Purification Eo e

Demineralizer arri cubicle was perforised using Loute 4 7 e radiation jh g

i o

l instrument used on the robot was a SAM-II #323 remote readout with a tungsten shielded 180* probe. A response curve was developed to convert I

K cpm to R/HR on 9-21-88 at the Radiological Controls Instrument Shop j

)

using a CSl37 source #310. The only problem encountered was the i

response curve was only plotted out to 800 R/HR.

The highest survey point in the Make-Up Demin cubicle was 947.5 R/MR; this y

was calculated by extrapolating the response curve (attached).

The A

response curve becomes somewhat linear over 500 R/HR.

4 After the "A" Make-up and Purification Demin cubicle is surveyed the E

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3 j

instrument will be returned to the Radiological Controls Instrument Shop M

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to measure the respnse beyond 1K R/HR using the same CS 37 #310 source j $0 1

m i

as used in the previous response measur,ements.

m 1

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This survey was performed to provide radiological information associated S with the resin content in the "B" Make-up and Purification Demineralizer. 3 2

3g By our procedures, these results cannot constitute an official documented.O a

radiological controls survey.

g.A.Yi 5

h B. M. Trachim g

{

Radiological Engineer g

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Attachment.

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G. A. Kuehn - Site Operations Director g

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D. W. Turner - Radiological Controls Director, TMI-2 y

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- 0-7 I<1w1 Nuclear Calculation Sheet l Sub*ct AX114 and AX115 Curie cae m 6 Rn a sw w Loadin9 4240-3233-93-015 1

6 l of b ;'

1

Ongmaior Date Renewoo Dy Date 3 'S 9/8/93

c. Lodde hp P M /p g B. Brosey v

i LOCATIONS OF SURVEY POINTS CPM R/HR

1. Inside MU-K-18 Cubicle Doorway probe face horizontal up 117.2 K 4.1

2. Inside HU-K-1B Cubicle Doorway probe face verticle forward 439.3 K 18.6

3. Inside MU-K-1B Cubicle 3' Level probe face verticle forward 791.7 K 42.9

4. Probe contact with Discharge Line Valve probe f ace verticle forward 901.0 K 54.7

5. Probe contact with Discharge Line Reducer probe face verticle forward 1.780.5 K 278.8 i

6. Probe contact with Tank Conicle Bottom Weld probe f ace verticle forward 2.392.0 K 775.7

7. Probe contact 3" above Tank Conicle Bottom Weld probe face verticle forward 2.547.7 K 947.5

8. Probe contact 8" above Tank Conicle Bottom Weld probe face verticle forward 2.331.9 K 709.5 t

9. Probe contact 2' above Tank Conicle Bottom Weld probe f ace verticle forward 1.929.8 K 351.1

10. Probe contact 2'6" above Tank Conicle Bottom Weld

_ probe f ace verticle forward 1.736.1 K 257.3

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Location MAKE-UP DEMIN location 83 Corm nts Inst /A Inst Inst 76an.*t Inst % CD 2A Activity

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ML l NON Calculation Sheet tNDat M114 and M115 Curie I""

Loacina i4240-3233-93-015 1

S Y Of 6I I Ongmator i Date i Aemewed by

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ML20057B964

Text

SUMMARY

3.0 REFERENCES

=...............s====..m===E.......................E.....s=.s=====............=============.....====E===========ss=E

SUMMARY

==

=a

=

SUMMARY

==

=

==

==

=

==

=

========== "

==

=

==

===

Title:

========================= RESULTS=========================

Title:

===============s===

Title:

Title:

= = = = = = = = = = = = = = = = = " = = = = = = " = = RESdt,TS=============================

Title:

=

=============...=======.= RESULTS=====*===================

========================= RESULTS=========================

Title:

==== RESULTS FOR SENSITIVITY REFERENCE CASE (X = 176.34)====

==

Title:

Title:

============================ RESULTS===========================*

= = = = = = = = = = = = = = = = = * " * = = = = = = = = = RESULTS==============================

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