Text

FH109/FH300 Ci Estimate
	ML20057B958
Person / Time
Site:	Crane
Issue date:	08/27/1993
From:	Brosey B, Lodde G; GENERAL PUBLIC UTILITIES CORP.
To:	;
Shared Package
ML20057B954	List: ML20057B953; ML20057B958; ML20057B964;
References
	4240-3233-93-02, 4240-3233-93-020-R00, 4240-3233-93-2, 4240-3233-93-20-R, NUDOCS 9309240205
	Download: ML20057B958 (35)
	v • d • e

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

t AdalNuclear Calculation Sheet l $yesect I Cat No.

1 Rev. No. I Sheet ND W

l FH109/FH300 Curie Estirrate 4240-3233-93-020 0

1 of Ongmator i Date l Revewea Dy Date B. Brosey 3. 3 ; g l8/27/93 lG. Lodde

[/f 7 3

l 1.0 PROBLEM STATEMENT The purpose of this calculation is to estimate the curie loading of the TMI-2 Fuel Pool "A" located in the Fuel Handling Building at the 347' El.

Radiological Controls survey data will be used to provide the exposure rate information necessary for this estimate.

2.0

SUMMARY

OF RESULTS 1

(

Based on the Radiological Controls survey data and isotopic concentrations determined to be present in smear data, the Fuel Pool "A"

I area contains an upper bound of approx'mately 135 Ci 22 Ci's of activity. A previous estimate from reference 3.7 (from 9/21/89),

reported that about 59 Ci of activity were present in the FHB "A"

Fuel Pool. The previous preliminary estimate did not include all the isotopes present in the mixture and was subject to a larger sampling error.

1

3.0 REFERENCES

3.1 Microshield Radiation f aielding Computer Code, Version 4, Grove Engineering, Inc.,

15.15 Shady Grove Rd.,

Rockville, MD 20850.

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

l 3.3 "The Health Physics and Radiological Health Handbook", Scinta, j

Inc., Silver Springs, MD.,

1992.

3.4 Burns & Roe, Inc., Drawing No. 2068, rev 23, " General Arrangement Auxiliary & Fuel Handling Building Floor Plan El.

347'-6",

W.O.

2655, 9/17/70.

3.5 NES, Drawing No. 83E0950, rev 2,

" Spent Fuel Pool Canister Storage Rack Arrangement", Danbury, Connecticut, 11/84.

3.6 GPUNC Engineering Calculation No. 4800-4420-89-095, rev.

O, "G.M.

Measurements of Fuel Debris (FTS)", 9/21/89.

3.7 GPUNC Memorandum No. 4800-89-127, " Fuel Debris in Defueling Canal and Fuel Pool "A"", 10/16/89.

3.8 GPUNC Engineering Calculation No. 4240-3233-93-001, rev.

O, "TMI-2 Waste Stream Analysis", 1/11/93.

3.9 NES, Drawing No. 83E0943, rev 3,

" Top Plate", Danbury, Connecticut, 10/84.

3.10 NES, Drawing No. 83E0919, rev 4,

" Fuel Canister Storage Rack 7 x 9",

Danbury, Connecticut, 10/84.

9309240205 930915 PDR ADOCK 05000320

1'

> tuclear Calculation Sheet-i' j Subsect l Calc No.

I Rev. No.

$heet No.

l FH109/FH300 Curie Estimate I

4240-3233-93-020 l

0 of l

oregsrtator Date Reviewed Dy Date B. Br0Sey 3 3d G'. Lodde,fjf 8/27/93 27 3_

4.0 ASSUMPTIONS AND BASIC DATA 4.? General overview and description of methodology.

4 4.1.1 In general, the Fuel Pool "A" area is modeled in sections.

l In section one, the activity is assumed to be at the bottom of the Fuel Pool in the region of the north canister i

handling / dewatering platforms. A three (3) inch deep water

+

shield is assumed to cover the-activity in this region at the time of the Radiological Controls survey.

4.1.2 The south region or section two of the fuel pool, contains the fuel canister racks. The source term is assumed to occupy only i

the area of the fuel racks and is homogeneously distributed in i

the rack volume. This is a conservative assumption since a.

portion of the source is actually distributed around the rack i

space as a surface deposition with little shielding. However, it is assumed that a significant portion of the source i

materials are present within the fuel racks as fuel debris.

4.2 Determination of materials and densities.

4.2.1 From review of reference 3.9 and 3.10 the following data table was assembled using the Lotus 1-2-3 spreadsheet system (reference 3.2). These values are used to estimate the effective density of the fuel rack region.

s INPUT DENSITY VALUES FOR FUEL POOL

A

ASSUMED COMPOSIT10N=============>

0.0%

LEAD BY WEIGHT 100.0%

IRON l

DIMENSICNS OF INTERNALS TO BE SUBTRACTED (ft)

LENGTH==>

0 WIDTH===>

0 NEIGHT=>

0 VOLUME OF INTERNALS TO BE SUBTRACTED (ce's)>

D.00E+00 DIMENSIONS OF SOURCE REGION IN FUEL POOL An (ft)

LENGTH==>

44.40625 WIDTH===>

14.12$

HEICHT=>

13.1979 VOLUME OF SOURCE REGION (cc's)=============>

2.34E+08 SOURCE REGION IN FUEL POOL A MINUS REGION TO BE SUBTRACTED.

EFFECTIVE SOURCE VOLUME (ce's)=>

2.34E+08 FUEL POOL MATERIALS MATERIALS WEIGHT OF WEIGHT OF DENSITY OF DENSITY OF **

APPROA! MATE WEICHT LEAD

!RON LEAD 1RON MATERIALS WE!CHT (tbs) (gms)

(gms)

(gms) g/cc g/cc

............................................................................... e COMPOSITION 1 31696 37057306 0

37057306 0.000000 0.153085 **

COMPOSITION 2 0

0 0

0 0.000000 0.000000 **

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

l l

7 N 0016 (10-88) j

7 r

Fid4 Nuclear Calculation Sheet i suoiect i Cai: No.

I Rev. No.

l Sheet No.

4 i

l FH109/FH300 Curie Estimate 4240-3233-93-020 0

l.9 of 2 l

? onginator i Date Revewed by i Date l B. BroSey l 8/27/93 G. Lodde k l hM9y 4.0 ASSUMPTIONS AND BASIC DATA Cont'd 4.2 Determination of materials and densities cont'd.

4.2.2 The Fuel Racks are assumed to be composed of steel with a weight of approximately 17,380 lbs per 7 x 9 section. There are four sections in the pool (reference 3.5 & 3.10).

4.2.3 The steel top plate sections are assumed to weigh approximately 3044 lbs per section. There are four sections (reference 3.9).

l 4.3 The isotopes, and activity of the isotopes present in one curie of source materials were determined from smear radiochemistry analysis and from the use of the Lotus 1-2-3 spreadsheet from reference 3.8.

Iso *T 7s normally found at TMI-2 were scaled in assuming a

" D.

.eling" waste stream (attachrent 1-1 to 1-6).

4.4 The following table presents the smear numbers and decayed results for ten (10) smears taken from the Fuel Pool and assayed by GPUNC.

Smear results are decayed to 8/24/93.

FH109 SMEAR DATA FILE NAME: SFP A.WK1

)

100A1'S DATES >B/24/93 I

ISOTOPES and ACTIVITY'S (OUTPUT VALUES)

WASTE CLASS SMEAR SMEAR SAMPLE uti's per 100 cm'2 Based on ALPHA AREA LOCATICN

!.D.

NUMBER OATE Cs-137 Sr-90 Cs-134 Sb-125 Co-60 Eu-154 ** Sr/Cs Sr/Cs ACTIVITY

.......................==============*::========.............................................+===........................

1 FHB FH109 9206003 8 6/3/92 " 8.14E-03 1.77E-02 1.78E-05 0.00E+00 1.21E-04 0.00E+00 "

2.17 CEFUELING 2.162E-04 2 FNB FH109 9206002 7 6/3/92 " 4.68E-03 1.14E-02 0.00E+00 0.00E+00 6.12E-05 0.00E+00 "

2.43 DEFUELING 2.207E-04 3 FHB Fh109 9205016 NONE 5/28/92 " 3.14E-03 6.62E-03 0.00E+00 9.97E-05 3.92E-05 0.00E+00 "

2.11 DEFUELING 1.279E-04 4 FHB FH109 9205015 NONE 5/28/92 ** 5.10E-03 1.24E-02 2.39E-05 0.00E+00 8.36E-05 0.00E+00 **

2.43 DEFUELING 1.658E-04 5 FHD TH109 NONE 12 7/25/92 " 2,45E-03 5.76E-03 0.00E+00 0.00E+00 3.34E-05 0.00E+00 "

?.35 CEFUELING NOT DONE 6 (NB FH100 NONE 10 7/25/92 *

8.57E -04 2.11E-03 0.00E+00 0.00E +00 1.18E-05 0.00E+00 **

2.47 CEFUELING NOT DONE 7 FHB FH109 NokE 11 7/25/92 " 3.82E-03 1.14E 02 0.00E+00 0.00E+00 8.ESE-05 0.00E+00 "

2.98 CEFUELING NOT DONE 8 FHB FH109 NONE 14 7/25/92 ** 4.15E-04 9.44E-04 0.00E*00 0.00E+00 9.46E-06 0.00E+00 **

2.28 DEFUELING NOT DONE 9 FHB FH109 3960-6 9

7/25/92 " 6.07E-04 3.73E-03 0.00E+00 0.CCE+00 0.00E+00 0.00E+00 "

6.15 DEFUELING NOT DONE 10 FHB FH109 NONE 13 7/25/92 " 1.1L E-03 2.53E-03 0.00E+00 0.00E+00 2.00E-05 0.00E+00 **

2.30 CEFUELING NOT DONE 3 3 33 32 2E*22 E3E R 2 5 2 3 3 2 3.. 22t s 2 E 2 2 E ST E F.E E.%.12 E ST R E S S S3 3 3 3CE E E E S 3

E E.t2 ESSES 2EEE E ES E EEE r3 3 8 2 EES* 3 22 3333. 3..t.23.

2 33 2 33 3 AVERACESa=> 3.03 E-03 7.45E-03 4.17E-06 9.97E-06 4.6SE-05 0.00E+00 2.7663 1.827E-04 4.5 Computer modeling for Fuel Pool "A".

4.5.1 From review of the references the following information represents the basic Microshield 4 input files.

a) Section 1, Basic Micrashield 4 input:

Dose point to center of rectangular area (X).. 30.48 cm.

Height of rectangular area (H)...............

720.09 cm.

Rectangular area width (W)...................

387.35 cm.

Thickness of shield 1 (SH1)....................

7.62 cm.

Dose point position along Z axis ( 2 )...... 19 3. 67 4 9 5 cm.

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

360.045 cm.

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

22.86 cm.

N 0016 (1CL68)

5 c

MW Nuclear Calculation Sheet i suo, ci

! cane No i sev. No I sneet No l

FH109/FH300 Curie Estimate i

4240-1233-93-020 0

!Y of h I

ongmator Date Reviewed Date B. Brosey 8/27/93 C. Locae

/fff 7 kJ _

4.0 ASSUMPTIONS AND BASIC DATA Cont'_dd 4.5 Computer modeling for Fuel Pool "A"

cont'd.

4.5.1 Cont'd.

b) Section 2.

Basic Microshi ?ld 4 input:

Dose point to center rectangle (X)........ 1264.3104 cm.

Height of rectangle (H)...................

1353.5025 cm.

Rectangular vol. width (W)...................

430.53 cm.

Rectangular vol. length ( L)............... 4 0 2. 2 719 9 cm.

Thickness of shield 1 ( S H 1 ).................... 7. 6 2 cm.

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

215.265 cm.

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

676.75125 cm.

Air Gap.................................... 854.41841 cm.

4.6 Review and interpretation of survey data.

4.6.1 Two (2) Radiological Controls Field Operations surveys were reviewed to determine the average exposure rate at set locations within the FHB Fuel Pool "A" area. Copies of these surveys are shown as attachments 2-1 and 2-2.

The average value for the sur v e;' locations were determined by spreadsheet analysis (see attachments 3-1 and 3-2).

4.6.2 The estimate of the error from incorrectly determining the vertical distance from a source tt 9,

is determined by assuming a1 six inch error in the radiation measurement reported for section one and that 1 two foot errors could have occurred in section two measurement locations.

4.7 A one curie source term is used to estimate the exposure rate at the same locations reported on the Radiological Controls survey sheets.

The calculated output is then compared to the actual measured values.

The actual measurement data is converted into the number of curies present in the measurement location. Activities as of 8/24/93.

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

a) Attachments 1-1 to 1-6, present and scale in the isotopes extracted from section 4.4 and assumed to characterize the "A" Fuel Pool.

b) Attachments 2-1 &

2-2, present the two Radiological Controls surveys for section 1 and 2 respectively, of the "A" Fuel Pool, c) Attachments 3-1 & 3-2, present the Statistical Determination Worksheet for section 1 and 2 respectively, of the "A" Fuel Pool.

The average exposure rates for both regions are computed on these attachments.

N 0016 (1048)

e 1 9' Nuclear Calculation Sheet lSubmet l Cale No.

Rev.No.

Sneet No l

j FH109/FH300 Curie Estimate I

4240-3233-93-020 0

5 Of

~l l

I orepnetor Date Reviewed oy Date

}

B. Brosey 8/27/93 G'. Lodde

[Jf d

7/27 9%

l 4.0 ASSUMPTIONS AND BASIC DATA Cont'd L

\\

4.8 Continued.

l d) Attachments 4-1 & 4-2, present the Microshield 4 output data for a 1 curie "Defueling" mixture of activity for section 1 (De-watering Station), of the "A" Fuel Pool.

i e) Attachments 5-1 & 5-2, present the Microshield 4 output data for i

a 1 curie "Defueling" mixture of activity for section 2 (Fuel Rack Area), of the "A" Fuel Pool.

f) Attachments 6-1, Lotus 1-2-3 " Normalization Worksheet", used to compare and estimate from the 1 curie Microshield 4 output to the number of curies present (suggested by actual exposure rate from i

survey data). This attachment presents the estimated number of.

i curies in section 1 of the "A" Fuel Pool.

g) Attachments 7-1, Lotus 1-2-3 " Normalization Worksheet", used to compare and estimate from the 1 curie Microshield 4 output to the number of curies present (suggested by actual exposure rate from

-j survey data). This attachment presents the estimated number of curies in section 2 of the "A" Fuel Pool.

h) Attachments 8-1 to 8-6, are diagrams and sections of drawings for i

the Fuel Pool storage racks as well as general layouts for the Fuel Pool area.

1 i) Attachments 9-1 to 9-7,'are Microshield 4 output. data for error estimates for this calculation including a graphical presentation.

5.0 CALCULATIONS 5.1 Most of the earlier operations were performed using the Lotus.1-2-3 I

spreadsheet system or Microshield 4.

l 5.2 Estimation of error terms.

5.2.1 The combined estimate of error in this analysis includes the l

following:

l a) The estimate of the uncertainty in the radiation measurements from the radiological surveys, due to-incorrectly reported survey locations (in the vertical plane).

b) An assumed instrumentation response error of.

20%.

l 5.2.2 The distance error estimate assumes that the actual. exposure rate point is within -

2 feet of the correct measurement L

location for the Fuel Rack section, and -i 6 inches for the De-watering Station location. To estimate this effect the

~]

N 0016 00-88).

c

> Nuc!aar Calculation Sheet i sud,eer lCakNo.

) Rw. No.

' Snest No.

I

[

FH109/FH300 Curie Estimate l

4240-3233-93-020 l

Ongmator 0

b of.

l Date B. Brosey 3.3 Reviewoo by yr Date i8/27/93 '

G. Lodde-h.

7.[27/93 5.0 CALCULATIONS Cont'd

+

5.2 Estimation of error terms cont'd.

5.2.2 Cont'd.

but with these distance effects includedMicroshield 4 s 5

I to 9-7). The results are shown below:

(see attachments 9-3..;

De-watering Station Exposure rate error term for -6 inch location is 1-(10.23/10.99) x 100% = -6.9% and about -4% on the

+6 inch side of the one foot measurement. The graph shown on

-}

attachment 9-7 shows the exposure rate variation from an area j source for the model presented herein. The one foot calculation appears to be about the highest value for this problem.

Therefore, 6 inches closer or farther away produce a small reduction in the calculated exposure rate and a resulting increase in the~ curie estimate. Assume 1 5% for this' err(

term.

l 5.2.3 The error _ term for the Fuel Rack section'is' computed in the same manner as above. The Microshield' output foot variation in distance produces the following error for a i 2 l

1-(1.088e-1/9.761e-2) l x.100% = +11.5%, for -2. feet and 1-(8.795e-2/9.761e-2) x 100% = -10%, for +2 feet. Assume 10% for this error term.

{'

t 5.2.4 Combination of error terms.

Combined error term for De-watering station is:

(( 20%)2+ (15%)2)o.5

~1 21%.

=

Combined error term for Fuel Rack area is:

( (120 %) 2+ (110 % ) 2) o.5 22%.

=-

Combined section error estimate is:

(21%/100%) x 49.29 Ci = 1 10.4 Ci., De-watering Station.

(22%/100%) x 86.057 Ci =-1 18.9 Ci., Fuel Racks area.

Total estimate of error is:

( (i 10. 4 Ci) 2+ (

18.9 Ci)2)0.5 =

21.6 Ci's i

i i

N 001E (104B)

_ _. _ _. --l

)

j

-1 SAMPLE RESULTS AND VOLUME ACTIVITIES SCALED FROM WEICHTED ORICEN2 VALUES Page 1 of 6

.. sau..s======. a.s==essrss=.sse.....==.... :

3..

.s................ss.........smasse.m===.=

" ALPHA DATE"n 1/1/93 700AY'S DATES >

8/24/93 Use EPRI

==s.=====.........=s3

.....=========== SCALED VALUES ?**===========

SAMPLE NAME.=> OEFUELING WALTE IN FH109 1=fES, 2.N0=>

1

..............= = = =. m e s s e s = =.a.. =. s = = s s s = =..= s u. s.a. e = =.....s = = s ens.s s s.s== = =s s===s a s s========

Unitsn uti's 0 Days Detween analysis date and "TODAY'S DATE".

s==.

nsssassesess.ss==.=..

Analysis Oaten 8/24/93

-235 Days between analysis date and = ALPHA DATE=.

A pq.)y a

Analysis Date Activity (uCl)

Normalized

============.s

ISDTOPES HALF LIFE (d) Activity (uci) at " ALPHA DATE"

% of Total to 1 Input Values Reviewed by:

1 H-3 4.485E+03 0.00E+00 0.00%

0.00E+00 2

C-14 2.093E+06 0.00E+00 0.00%

0.00E+00 3

Cr-51 2.770E+01 0.00E+00 0.00%

0.00E+00=========================

4 mn-54 3.127E+02 0.00E+00 0.00%

0.00E+00 Input values checked by:

5 Fe-55 9.862E+02 9.73E-05 0.45%

4.47E-03 6

Co-58 7.080E+01 0.00E+00 0.00%

0.00E+00 k

D 7

Co-60 1.925E+03 4.68E-05 5.09E-05 0.23%

2.34E-03 8

Ni-63 3.656E+04 4.64E-04 2.14%

2.14E-02 g

9 In 65 2.444E+02 0.00E+00 0.00%

0.00E+00 10 Sr-89 5.055E+01 0.00E+00 0.00%

0.00E+00 o

g g

11 Sr-90 1.045E+04 7.45E-03 7.57E-03 34.79%

3.48E 01 z

12 Y-90

2. 671 E + 00 """"* ""*

7.57E-03 34.79%

3.48E-01

}M eg 13 Tc-99 7.780E+07 0.00E+00 0.00%

0.00E+00 14 Ru-106 3.682E+02 0,00E+00 0.00%

0.00E+00 15 Rh-106 3.463E-04 ***************

0.00E+00 0.00%

0.00E+00 16 Ag 110m 2.49BE+02 0.00E+00 0.00%

0.00E+00 a

17 Ag-110

2. 844E - 04 """""""*

0.00E+00 0 00%

0.00E+00 5

18 Sb-125 1.012E+03 9.97E-06 1.17E -05 0.05%

5.3BE-04 19 Te-125m 5.800E+01 ***************

2.71E-06 0.01%

1.24E-04 20 1-129 5.734E+09 0.00E+00 0.00%

0.00E+00 o

21 Cs 134 7.531E+02 4.17E - 06 5.18E*06 0.02%

2.38E-04 o

22 Cs-137 1.102E+04 3.03E-03 3.0BE-03 14.14%

1.41E-01 A

h 23 Ba 137m

1. 772E - 03 * "" *" *"""

2.91E-03 13.37%

1.34E-01 i

24 Ce-141 3.250E+01 0.00E+00 0.00%

0.00E+09 Q

25 Le-144 2.843E+02 0.00E+00 0.00%

0,00'+00 N

26 Pr-144

1. 2 00E - 02 * * * * " * * """

0.00E+00 0.00%

0.00E+00 0

+

c r 27 Pr-144m

5. 000E - 03 ""*"""""

0.00E+00 0.00%

0.00E+00 E

6O IE 28 pm-147 9.582E+02 0.00E+00 0.00%

0.00E+00

,.j f" 2 "

29 Eu-154 3.214E+03 0.00E+00 0.00%

0.00E+00 3

yd 30 Eu-155 1.812E+03 0.00E+00 0.00%

0.00E+00 31 Pa 233 2.700E*01 0.00E+00 0.00%

0.00E+00 c3 32 U-234 8.930E+07 0.00E+00 0.00%

0.00E+00 3

Q 33 U-235 2.571E+11 0.00E+00 0.00%

0.00E+00

.M Q

34 U-236

1. 24 7E + 09 0.00E+00 0.00%

0.00E+00 M

e eu O

$S 35 Ap-237 7.816E+08 0.00E+00 0.00%

0.00E+00 36 U 238 1.632E+12 0.00E+00 0.00%

0.00E+00 e

37 Pu-238 3.205E+04 0.00E+00 0.00%

0.00E+00 38 Pu-739 8.814E+06 0.00E+00 0.00%

0.00E+00

.5 g

39 Pu 240 2.388E+06 0.00E+00 0.00%

0.00E+00 g

v 40 Pu-241 5.260E+03 0.00E+00 0.00%

0.00E+00

'd 41 Am-241 1.579E+05 0.00E+00 0.00%

0.00E+00 0

42 Cm242 1.632E+02 0.00E+00 0.00%

0.00E+00 E

43 Cm 243 1.041E+04 0.00E+00 0.00%

0.00E+00 5

A 44 Cm 244 6.615E+03 0.00E+00 0.00%

0.00E+00 o

.. _................................ _...... _. _........................... _.......................... 3 g

TOTALS uti's>

1.05E-02 2.18E-02 100.00%

1.00E+00 g

g g

S o

x

_' -se cc T

g i

e l

~ -2

]

9524.695 uti Alpha /Ci (debris)

IS010FE USED FOR SCALING=====>

NA SAMPLE NAME=>0EFUELING WASTE IN FH109 as of 1/1/93 " ALPHA DATE" RESULTS (Scaled Alpha)s======> CAN'T SCALEl Page 2 of 6 i

Alpha %==>

0.776621%

1.827E-04 uCI (Samte or Scaled Alpha Results)

TODAY'S DATE> 8/24/93

... =..............==.. = s============rs...===.....====.==........

m==......====ss==============.............===..========

i SAMPLE WE!CHTED Per Ci Scated SUM OF REAL SAMPLE SAMPLE WEICK1ED lsotopes Fractions Alpha Adjusted Alpha Remainders COLUMNS RESULTS ORIGEN2 tot tams Isotopes ORIGEN2 per Cf Fraction Emitters (D) Using Pu-239 (E) D'& E (uci)

(uti)

RESULTS (uC1)

N/F ORICEN2 Ac 227*

1.610E-10 1.610E-10 3.088E-18 3 088E-12 3.088E-12 1 Ac-227 Ag-108 6.530E-09 1.253E-16 1.253E-10 1.253E-10 1 Ag-108 Ag-108m 7.020E-08 1.347E-15 1.347E-09 1.347E-09 1 Ag 108m Ag-109m 9.000E-09 1.726E-16 1.726E-10 1.726E-10 1 Ag-109m Ar '10 1.800E-11 3.453E-19 3.453E 13 3.453E-13 1 Ag-110 Ag-im 1.360E-09 2.609E-17 2.609E-11 0.000E+00 2.609E-11 1 Ag-110m A:

,41*

1.650E-03 1.650E-03 3.165E-11 3.165E-05 0.000E+00 3.165E-05 1 Am-241 a#242 2.160E-07 4.143E-15 4.143E-09 4.143E-09 1 Am-242 Am-242m*

2.170E-07 2.170E-07 4.162E-15 4.162E-09 4.162E-09 1 An-242m Am-243*

8.490E-08 8.490E-08 1.629E-15 1.629E 09 1.629E-09 1 Am-243 Be-137m 8.400E-02 1.611E-09 1.611E-03 2.909E-03 2.909E-03 1.8054493 Be-137m 8e-10 1.930E-11 3.702E 19 3.702E-13 3.702E 13 1

Be-10 Bi 211*

1.590E-10 1.590E-10 3.050E-18 3.050E-12 3.050E-12 1 81-211-B4-212*

1.600E 08 1.600E-08 3.069E-16 3.069E-10 3.069E-10 1 91-212 81-214 3.090E-11 5.927E-19 5.927E-13 5.927E-13 i 81-214 i

C-14 1.030E-05 1.976E-13 1,976E-07 0.000E+00 1.976E-07 1

C-14 Ca-41 1.030E-09 1.976E-17 1.976E-11 1.976E-11 1

Ca-41 Cd-109 9.000E-09 1.726E-16 1.726E-10 1.726E-10 1 Cd-109 Cd-113m 9.160E-05 1.757E-12 1.757E-06 1.757E-06 1 Cd-113m Ce-144 6.800E-05 1.304E-12 1.304E-06 0.000E+00 1.304E-06 1 Ce-144 Ct-36 6.850E-08 1.314E-15 1.314E-09 1.314E-09 1

Cl-36 cm-242*

1.790E-07 1.790E-07 3.434E-15 3.434E-09 0.000E+00 3.434E 09 1 cm-242 Cm-243*

1.800E-08 1.800E-08 3.453E-16 3.453E-10 0.000E+00 3.453E-10 1 Cm-243 cm-244*

4.290E-07 4.290E-07 8.229E-15 8.229E 09 0.000E+00 8.229E-09 1 Cm-244 Co-60 1.640E-03 3.146E-11 3.146E-05 5.093E-05 5.093E-05 1.6190171 Co-60 Cs 134 2.690E-04 5.160E-12 5.160E-06 5.177E 06 5.177E 06 1.0032408 Cs-134 Cs-135 2.050E-06 3.932E-14 3.932E-08 3.932E-08 1 Cs-135 t

8.880E-02 1.703E-09 1.703E-03 3.075E-03 3.075E-03 1.8053461 Cs-137 i

[

1.680E 05 3.223E-13 3.223E-07 3.223E-07 1 Eu-152

.f

' 1.950E-03 3.740E-11 3.740E-05 0.000E+00 3.740E-05 1 Eu-155 1.290E-03 2.474E 11 2.474E 05 0.000E+00 2.474E-05 1 Eu-154 g

E 1.780E-C3 3.414E-11 3.414E-05 9.728E-05 9.728E-05 2.8491064 Fe-55 i

[ j

' 1.530E 10 2.935E-18 2.935E 12 2.935E-12 1 Gd-153

)

2.600E-03 4.987E-11 4.987E 05 0.000E+00 4.987E-05 1

H-3 J,

3.300E-10 6.330E-18 6.330E-12 6.330E-12 1 Ho-166m g

j 4.150E-08 7.960E-16 7.960E-10 0.000E+00 7.960E-10 1

1-129 2.420E-07 4.642E-15 4.642E-09 0.000E+00 4.642E 09 1

Mn-54 o

1.580E-07 3.031E-15 3.031E-09 3.031E-09 1

Mo-93 Y

- 5.510E-06 1.057E-13 1.057E 07 1.057E-07 1 Nb-93m B.27DE-06 1.586E-13 1.586E-07 1.586E-07 1

Nb-94

{

3.110E-05 5.966E-13 5.966E 07 5.966E-07 1

Ni-59 s4 3.510E-03

6. 733E-11 6.733E 05 4.645E-04 4.645E-04 6.8989505 Ni-63 M g$

6.980E-07 6.980E-07 1.339E-14 1.339E-08 0.000E+00 1.339E-08 1 Np-237 j*

g 1.030E-09 1.976E-17 1.976E 11 1.976E-11 1 Np-238 e

8.490E-08 1.619E 15 1.629E-09 1.629E-09 1 Np-239 -

j 7.980E-10 7.980E-10 1.531E-17 1.531E-11 1.531E-11 1 Pa-231 S

E 6.980E-07 1.339E-14 1.339E-08 0.000E+00 1.339E-08 1 Pa-233 0

j$

2.760E-08 5.294E-16 5.294E-10 5.294E-10 1 Pa-234 1.720E-05 3.299E-13 3.299E 07 3.299E-07 1 Pa-234m i

1.590E-10 3.050E-18 3.050E-12 3.050E-12 1 Pb-211 3

1.600E-08 3.069E-16 3.069E-10 3.069E-10 1 Pb-212 s

3.090E-11 5.927E-19 5.927E-13 5.927E-13 1 Pb-214 i

{

2.110E-07 4.047E 15 4.047E-09 4.047E-09 1 Pd-107 h

ig 5.150E-07 9.879E-15 9.879E-09 9.879E-09 1 Pm-146 3

fJ 8

5.190E-02 9.955E-10 9.955E-04 0.000E+00 9.955E 04 i Pm-147 3

f h 1.020E-08 1.020E-OS 1.957E-16 1.957E-10 1.957E-10 i Po-212 "3

g; L

3.090E-11 3.090E-11

5. 927E - 19 5.927E-13 5.927E-13 1 Po-214

[

5 j

1.590E-10 1.590E-10 3.050E-18 3.050E-12 3.050E-12 1 Po-215

I A 1.600E-C8 1.600E-C8 3.069E-16 3.069E-10 3.069E-10 1 Po-216 g

9 3.090E-11 3.090E-11 5.727E-19 5.927F 13 5.927E-13 1 Po-218 y

JJj 6.800E-05 1.304E 12 1.304E-06 0.000E+00 1.304E-06 1 Pr-144

- -3 I

Pr-144m

9. 730E -07 1.866E-14 1.866E-08 0.000E+00 1.866E-08 1 Pr-144m Pu-236*

6.400E 09 6.400E-09 1.228E-16 1.228E-10 1.22SE-10 1 Pu-236 Pu-238*

4. 750E -04 4.750E-04 9.111E-12 9.111E-06 0.000E+00 9.111E-06 1 Pu-238 Pu-239*

5.770E 03 5.770E-03 1.107E-10 1.107E-04 0.000E+00 1.107E-04 1 Pu-239 Pu-240*

1.530E-03 1.530E-03 2.935E-11 2.935E-05 0.000E+00 2.935E-05 1 Pu-240 Pu-241 5.300E 02 1.017E-09 1.017E 03 0.000E+00 1.017E-03 1 Pu-241 Pu-242*

9.970E-08 9.970E-08 1.912E-15 1.912E-09 1.912E-09 1 Pu-242 Fu-244*

1.310E-10 1.310E-10 2.513E-18 2.513E-12 2.513E 12 1 Pu-244 aa-223*

1.590E-10 1.590E-10 3.050E 18 3.050E-12 3.050E-12 1 Ra-223 Ra-224*

1.600E-08 1.600E 08 LC69E-16 3.069E-10 3.069E-10 1 Ra-224 Ra-226*

3.100E-11 3.100E-11 5.946E-19 5.946E-13 5.946E-13 1 Ra-226 Rb-87 1.310E-10 2.513E-18 2.513E-12 2.513E-12 i

Rb-87 Rn 106 1.020E-04 1.957E-12 1.957E-06 0.000E+00 1.957E-06 1 Rh-106 En-219*

1.590E-10 1.590E-10 3.050E-18 3.050E-12 3.050E-12 1 Rn-219 R n-220*

1.6000-08 1.600E-08 3.069E-16 3.069E-10 3.069E-10 1 Rn-220 en 222*

3.090E-11 3.090E-11 5.927E - 19 5.927E-13 5.927E-13 1 Rn-222 Ru-106 1.020E-04 1.957E - 12 1.957E-06 0.000E+00 1.957E-06 1 Ru-106 Sb-125 8.890E 04 1.705E-11 1.70$E-05 1.171E-05 1.171E-05 0.6867714 Sb-125 Sb-126 4.470E 07 8.574E-15 8.574E-09 8.574E-09 1 Sb-126 Sb-126m 3.200E-06 6.138E-14 6.13BE-08 6.138E-08 1 Sb-126m Se-79 2.180E-06 4.182E-14 4.182E-08 4.182E-08 1

Se-79 Sm-147 4.900E-11 9.399E-19 9.399E-13 9.399E-13 1 Sm-147 Sm-151 6.290E-03 1.207E-10 1.207E-04 1.217E-04 1 Sm-151 Sn-119m 1.720E-07 3.299E-15 3.299E-09 3.299E-09 1 Sn-119m Sn-126 3.200E-06 6.138E-14 6.138E-OS 6.138E-08 1 Sn-126 Sr-90 3.460E-01 6.637E - 09 6.637E-03 7.567E-03 7.567E-03 1.1401536 Sr-90 Tc 99 7.350E-05 1.410E-12 1.410E-06 0.000E+00 1.410E 06 i

Tc-99 Te-125m 2.050E-04 3.932E-12 3.932E 06 2.705E-06 2.705E-06 0.6879741 Te-125m Th-227*

1.580E-10 1.580E-10 3.031E-18 3.031E-12 3.031E-12 1 Th-227 Th-228*

1.600E-08 1.600E-CB 3.069E-16 3.069E-10 3.069E-10 1 Th-228 Th-230*

1.010E-08 1.010E-08 1.937E-16 1.937E-10 1.937E-10 1 Th-230 Th 231 2.550E-06 4.891E-14 4.891E-08 4.891E-08 1 Th-231 Th 234 1.720E 05 3.299E-13 3.299E-07 3.299E-07 1 Th-234 ft-207 1.590E-10 3.050E-18 3.050E-12 3.050E-12 1 ft 207 Tt-208 5.740E-09 1.101E-16 1.101E-10 1.101E-10 1 ft-208 U-232*

1.600E-08 1.600E-08 3.069E-16 3.069E-10 3.069E-10 1

U-232 U 233*

1.960E-10 1.960E 10 3.760E 18 3.760E-12 3.760E-12 1

U-233 U-234*

7.840E-05 7.840E 05 1.504E-12 1.504E-06 0.000E+00 1.504E 06 1

U-234 U-235*

3.170E-06 3.170E - 06 6.081E 14 6.081E-08 0.000E+00 6.081E 08 1

U-235 U-236*

2.080E-06 2.080!-06 3.990E-14 3.990E-08 0.000E+00 3.990E-08 1

U-236 U 23S*

1.480E-05 1.4EE 05 2.839E-13 2.839E-07 0.000E+00 2.839E-07 1

U-238 Y-90 3.460E 01 6.637E-09 6.637E-03 7.567E-03 7.567E-03 1.1401536 Y-90 2n-65 1.0BCE-09 2.072E 17 2.072E-11 0.000E+00 2.072E-11 1

2n-65 2r-93 1.130E-05 2.168E-13 2.16BE-07 2.168E-07 1

Zr-93

...........e======e=======sz=============,,========2============r.===========..rs.............===============================

TOTAL==>

1.00 9.52SE 03

1. 827E - 10 1.900E-08 1.919E-02 2.175E-02 2.419E-02 TOCAY'S CATE=========>

S/24/93 SAMPLE AAVE==> DEFUELI G WASTE W FH109 Pa9e 3 of 6 Im.HNuclear Calculation Sheet l Subteet l Cale No.

l Rev, No_ j Sheet No i

i FH109/FH300 Curie Estimate i

4240-3233-93-020 i

0 I h of I

Ongmator Date Renewed by Date

h. f [/hv k/r/p3 B. Brosey VM.

8/27/93 G. Lodde m p

.~

1 l

r j

il 1

1 -4 NOTE: An "*" next to an isotope.name indicates an alpha emitter.

{

RADENG Scaled Values Based on Co-60 & Sb-125 ISOTOPES (uti)

(uct) ' RATIO (1)/(2) l EPRI (1)' 'ORICEN2 (2)

-Fe-55 9.73E-05 3.41E 05 2.8491064248 Ni-63 4.64E-04 6.73E-05 6.8989505015 SAMPLE NAME.>DEFUELING WASTE IN FH109 TODAY'S DATE>B/24/93 WASTE WASTE

.Sr/Cs BASED ON BASED ON k

RATIO ALPHA Sr/Cs ALPHA 2.4607416 0.776621%- DEFUELING DEFUELING Page 4 of ?

n E

b Db iA

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6 0

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f 68 1

i

4 -5 SAMPLE RESULTS AND RESULTING votuME ACTIVITIES SCALED EPRI VALUES?> YES Pa9e 5 of 6 3 sssssssssssssssssa:Essessss===ss=====3 ssssssssssssssssssssssss======ss===ses===esessssssssssss====ss===Ressa.

TODAY'S CATES > 8/24/93 volume of small container=====>

0.00 gal

====3ssassessssssssss===sssa asssssssssss==sessssssssssssssssss=== essas SAMPLE NAMEss> DEFUELING WASTE IN FH109 0.00 ml 3 ssessassasasssssssssssssssssssssssssssss==ssesesssss===sss=3:ss3ssessasss=essnes===s ss===ses== sass.

Units =>

uti's size to:

0.00 gal

==ssasssss==sssassassessmas:

" ALPHA DATE"==31/1/93 235 Days have elapsed since

ALPHA DATE".

.ssssssssnesas:s=Essssssssssssssss==== ssasssssssss====sseses3===33 ssmassesssssssssssssssesesssassessssssssssesassssssss.

Activity (uCi) Activity (uCl)

Normalized Rad Eng ISOTOPES HALF-LIFE (d) aALPHA CATE" 10 CAY'S DATE

% of Total to 1 Rad Eng Activities 1

M-3 4.485E+03 4.99E-05 4.81E-05 0.20%

2.04E-03 Isotopes utt's 2

C-14 2.093E+06 1.98E-07 1.98E-07 0.00%

B.40E-06 es=ses=ss==sssssssss=ses.

3 Cr-51 2.770E+01 0.00E+00 0.00E+00 0.00%

0.00E+00 Am-241 3.25E-05 4

Mn-54 3.127E+02 4.64E-09 2.76E-09 0.00%

1.17E-07 Ba-137m 2.87E-03 l

5 Fe 55 9.862E+02

9. 73E - 05 8.25E-05 0.35%

3.51E-03 Ce-144 7.36E-07 l

6 Co-58 7.080E+01 0.00E+00 0.00E+00 0.00%

0.00E+00 Co-60 4.68E-05 i

7 Co 60 1.925E+03 5.09E-05 4.68E-05 0.20%

1.99E-03 Cs-134 4.17E-06 8

Ni-63 3.656E + 04 4.64E-04 4.62E-04 1.97%

1.97E-02 Cs-137 3.03E-03 9

Zn-65 2.444E+02 2.07E-11 1.06E-11 0.00%

4.52E-10 Eu-154 2.35E-05 to Sr-89 5.055E+01 0.00E+00 0.00E+00 0.00%

0.00E+00 Fu-155 3.42E-05 11 Sr-90 1.045E+04 7.57E-03 7.45E-03 31.67%

3.17E-01 1-129 7.96E-10 12 Y-90

2. 6 71 E + 00 """" *"""

7.45E-03 31.67%

3.17E-01 Pm-147 8.40E-04 13 Tc 99 7.780E+07 1.41E-06 1.41E-06 0.01%

5.99E-05 Pr-144 7.36E-07 14 Ru-106 3.682E+02 1.96E-06 1.26E 06 0.01%

5.34E-05 Pu-238 9.07E-06 l

15 Rh-106 3.463E 04 * " *""""*"

1.26E-06 0.01%

5.34E-05 Pu 239 1.11E-04 1/ t A2-110m 2.498E+02 2.61E-11 1.36E-11 0.00%

5.78E-10 Pu-241 9.86E-04 37 Ag.110

2. 844E -04 "* *""""*"

1.81E 13 0.00%

7.69E-12 Rh-106 1.26E-06 18 sb-125 1.012E+03 1.17E-05 9.97E-06 0.04%

4.24E-04 Ru-106 1.26E-06 19 Te-125m

5. 800E + 01 * *""""* ""

2.30E-06 0.01%

9.79E-05 Sb-125 9.97E-06 l

20 1-129 5.734E+09 7.96E-10 7.96E-10 0.00%

3.38E-08 Tc-99 1.41E-06 i

21 Cs-134 7.531E+C2 5.18E-06 4.17E-06 0.02%

1.77E-04 Te-125m 2.30E-06 l

22 Cs-137 1.102E+04 3.0EE-03 3.03E-03 12.88%

1.29E-01 Y-90 7.45E-03 23 Ba 137m

1. 772E - 03 " *"""" * *"

2.87E-03 12.18%

1.22E 01 Fe-55 8.25E-05

)

24 Ce-141 3.250E+01 0.00E+00 0.00E+00 0.00%

0.00E+00 Ni-63 4.62E-04 25 Ce-144 2.843E+02 1.30E-06 7.36E-07 0.00%

3.13E-05 Sr-90 7.45E-03 26 Pr-144 1.200E-02 ***************

7.36E-07 0.00%

3.13E-05 U-234 1.50E-06 27 Pr-144m

5. 000E - 03 * "" *""" * "

1.05E-08 0.00%

4.47E 07 U 235 6.08E-08 28 Pm-147 9.582E+02 9.96E-04 8.40E-04 3.57%

3.57E - 02 0-238 I 64E-07 29 Eu-154 3.214E+03 2.47E-05 2.35E-05 0.10%

1.00E-03 Pu-240 4.93E-05 30 Eu 155 1.812E+03 3.74E 05 3.42E-05 0.15%

1.45E-03 31 Pa 233 2.700E+01 1.34E-08 1.34E-08 0.00%

5.69E-07 l

32 U 234 8.930E+07 1.5DE-06 1.50E-06 0.01%

6.39E-05 l

33 U-235 2.571E+11 6.08E-08 6.08E-08 0.00%

2.58E-06 l

34 U-236 1.247E+09 3.99E-08 3.99E-CB 0.00%

1.70E-06 35 Ap-237 7.816E+0B 1.34E-08 1.34E-08 0.00%

5.69E-07 36 U-238 1.632E+12 2.84E-07 2.84E 07 0.00%

1.21E-05 37 Pu-238 3.205E+04 9.11E-06 9.07E 06 0.04%

3.85E 04 38 Pu-239 8.814E+06 1.11E 04 1.11E-04 0.47%

4.70E-03 39 Pu 240 2.38CE+06 2.93E-05 2.93E-05 0.12%

1.2SE-03 40 Pu 241 5.260E+03 1.02E-03 9.86E-04 4.19%

4.19E-02 41 Am-241 1.579E+05 3.16E-05 3.25E-05 0.14%

1.3BE-03 42 cm-242 1.632E+02 3.43E-09 3.42E-09 0.00%

1.46E-07 43 cm-243 1.041E+04 3.45E 10 3.40E-10 0.00%

1.44E-08 44 cm-244 6.615E+03 8.23E-09 8.03E-09 0.00%

3.41E-07 essssssass====sesssss=5=sessssssssssssssssssss3 sssssssssssssssssnests===sesasss==sassassssssssssssssssmessasses TOTALS uti's>

1.36E-02 2.35E-02 100.00%

1.00E+00 lWINuclear Calculation Sheet i Subrect I Calc No

! Rey,No.

t Sneet NC FH109/FH300 Curie Estimate 4200-3233-93-020 0-

//

cf i

I Ongmator

! Date i Reviewed Dy a.

/)

! Date q

B. isrosey v U" ),

iS/27/93 G. L0cce j )Jf f h / d

! 9/J'//B 1

l

~

,e l

.c a

l

- -6 700AY'S DATE==>8/24/93 SAMPLE NAME.. DEFUELING UASTE IN FH109 i

RADENG VALUES?>YES Total Activity Total Activity NRC Activities (in uti's)

(in millicuries) " REPORTABLE" ISOTOPES uCi's Small Container LARGE Container (> 1% of TOTAL) Page 6 of 6

.................s

. -.... n..........................................................

a 1

H3 4.81E 05 0.00E+00 0.00E+00 2

C 14 1.98E-07 0.00E+00 0.00E+00 3

Cr-51 0.00E+00 0.00E+00 0.00E+00 4

Mn-54 2.76E 09 0.00E+00 0.00E+00 5

Fe-55 8.25E 05 0.00E+00 0.00E+00 6

Co-58 0.00E+00 0.00E+00 0.00E+00 l

7 Co-60 4.68E 05 0.00E+00 0.00E+00

{

8 Ni-63 4.62E-04 0.00E+00 0.00E+00 REPORTABLEll

,i 9

Zn-65 1.06E-11

-0.00E+00 0.00E+00 b

l k

10 Sr 89 0.00E+00 0.00E+00 0.00E+00 11 Sr 90 7.45E 03 0.00E+00 0.00E+00 REPORTABLEll 12 Y-90 7.45E 03 0.00E+00 0.00E+00 * ** * * * =

O o-13 Tc 99 1.41E 06 0.00E+00 0.00E+00 14 Ru-106 1.26E-06 0.00E+00 0.00E+00 I

s 15 Rh-106 1.26E-06 0.00E+00 0.00E+00 ***************

16 Ag-110m 1.36E 11 0.00E+00 0.00E+00

.I 17 Ag 110 1.81E-13 0.00E+00 -

0.00E+00 * ***"***

j 18 Sb-125 9.97E-06 0.00E+00 0.00E+00 gO

~

19 Te-125m 2.30E 06 0.00E+00 0.00E+00 a;

20 1-129 7.96E-10 0.00E+00 0.00E+00-Jl 21 Cs-134 4.17E-06 0.00E+00 0.00E+00 22 Cs-137 3.03E-03 0.00E+00 0.00E+00 REPORTABLEll

'O

~

I 23 sa-137m 2.87E-03 0.00E+00

0. 00E +00 **"* ***"*

O 24 Ce-141 0.00E+00 0.00E+00 0.00E+00 Q

25 Ce-144 7.36E-07 0.00E+00 0.00E+00

.A

'26 Pr-144 7.36E-07 0.00E+00

0. 00E+00 **""""***

m 27 Pr 144m 1.05E-08 0.00E+00

0. 00E +00 "** """""

W

~m o

28 Pm-147 8.40E-04 0.00E+00 0.00E+00 REPORTABLEff

, d E

'I 29 Eu-154 2.35E-05 0.00E+00 0.00E+00 gg) {Z O

I 30 Eu-155 3.42E-05 0.00E+00 0.00E+00

.9

h O

d 31 Pa-233 1.34E-08 0.00E+00

0. 00E+00 "**""**""

32 U-234 1.50E 06 0.00E+00 0.00E+00 3

33 U 235 6.08E-08 0.00E+00 0.00E*00 3

-i 34 U 236 3.99E-08 0.00E+00 0.00E+00

~3 35 Np 237 1.34E 08 0.00E+00 0.00E+00 M

R

[

2Q 36 U 238 2.84E-07 0.00E+00 0.00E+00 Sm 37 Pu 238 9.07E 06 0.00E+00 0.00E+00 38 Pu-239 1.11E-04' O.00E+00 0.00E+00 0

39 Pu-240 2.93E 05 0.00E+00 0.00E+00 40 Pu-241 9.86E 04 0.00E+00 0.00E+00 REPORTABLE!!

41 Am-241 3.2SE-05 0.00E+00 0.00E+00 42 Cm-242 3.42E-09 0.00E+00 0.00E+00 i

'43 cm-243 3.40E-10 0.00E+00 0.00E+00 44 cm-244 8.03E-09 0.00E+00 0.00E+00 g

g m.(

v TOTALS men 2.35E-02 0.00E+00 0.00E+00 mci o

g 9

O IU s'

3

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m 1

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i Nuclear Calculation Sheet Sutymt Calc No, Rev.No.

Sheet No FH109/FH300 Curie Estimate 4240-3233-93-020 0

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N/A

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SURVEY DATEsss>

8/26/92 SURVEY NUMBER =ss>

92J07218 LOCATION OR AREAS===>Fh300 A TODAY'S DATE SUR VE Y C AT E === >

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CPU Page 1

File Ref:

A DOS File: FP-B.MS4 Date: _/

J.

Run Date August 25, 1993 By:

N'.

t Run Time: 11:23 a.m. Wednesday Checked:

l W %\\ l

.{

Ouration: 0:03:04 m

Case

Title:

DEWATERING STATION AREA 0F FUEL POOL A i

CEOMETRY 4 - Vertical Rectangular Area centimeters feet and inches

[

Dose point coordinate x:

30.48 1.0

.0 g

Dose point coordinate Y:

360.045 11.0 9.7 4) l Dose point coordinate 2:

193.67495 6.0

'4.2 Rectangular area height:

720.09 23.0 7.5 s

Rectangular area width:

387.35 12.0 8.5 O

g Shield 1:

7.62 0.0 3.0 g

Air Cap:

22.86 0.0 9.0 3

s a

Source Area: 278927. sq cm 300.234 sq ft.

43233.8 sq in.

N.

MATERIAL DENSITIES (g/cm'3)

C3 Materist Shield 1 Air Oap Stab Air 0.00122 Water 1.0 a

o BUILOUP Method: Buildup Factor Tables T

The material reference is Shield 1 Mm n? NS INTEGRATION PARAMETERS g

c3 t2 i

(f) N'Z 3

Quadrature Order 2 Direction 30 y <r Y Direction 30 g d g,

SOURCE NUCL10ES

~

I m

Nuclide curies gCi/cmf Nuclide curie 5

Ci/Cma 3

Ch Ag-110 7.6900e-012 2.7570e-011 As-110m 5.7800e-010 2.0722e 009 M

R Am 241 1.3800e-003 4.9475e-003 Ba-137m 1.2200e-001 4.3739e-001 8

2N C 14 8.4000e 006 3.0115e 005-Ce 141 0.0000e+000 0.0000e+000 O

a5 Ce-144 3.1300e 005 1.1222e 004 cm-242 1.4600e-007 5.2343e 007 cm-243 1.4400e-008 5.1626e-008 cm-244 3.4100e 007 1.2225e-006 3

Co 58 0s0000e+000~ 0.0000e+000 co-60 1.9900e-003 7.1345e-003 g

Cr-51 0.0000e+000 0.0000e+000 Cs-134 1.7700e 004 6.3457e 004 Cs 137 1.2900e 001 4.6249e-001 Eu 154 1.0000e-003 3.5852e-003

[a Eu-155 1.4500e-003 5.1985e 003 Fe 55 3.5100e 003 1.2584e-002 w

H-3 2.0400e-003 7.3137e-003 l-129 3.3800e 008 1.2118e-007

/

c, Mn-54 1.1700e 007 4.1946e 007 N1-63 1.9700e-002 7.0628e-002 I

Wp-237 5.690ce-007 2.0400e-006 Pa-233 5.6900e 007 2.0400e-006 be Ii k

Pm 147 3.5700e-002 1.2799e-001 Pr-144 3.1300e 005 1.1222e-004 g.

U Pr-144m 4.4700e 007 1.6026e-006 Pu-238 3.8500e-004 1.3803e-003 m

cs Pu-239 4.7000e-003 1.6850e 002 Pu-240 1.2500e-003 4.4815e-003 g

R

)

Pu-241 4.1900e-002 1.5022e 001 Rh-106 5.3400e 005 1.9145e-004

=c Ru 106 5.3400e-005 1.9145e 004 Sb-125 4.2400e-004 1.5201e 003 Sr-89 0.0000e+000. 0.0000e+000 Sr-90 3.1700e-001 1.1365e+000 E

Q L

Tc 99 5.9900e-005~.2.1475e-004 ie-125m 9.7900e-005 3.5099e-004 g

ce U 234 6.3900e-005 2.2909e-004 u-235 2.5800e-006 9.2497e-006

-- E B *$

u-236 1.7000e 006 6.0948e-006

.u-238 1.2100e-005 4.3381e-005 5-Y 90 3.1700e-001 1.1365e+000 2n 65 4.5200e-010 1.6205e-000 g

3-i 3

i

7

. -2 Page 2

DOS File: FP 9.MS4 Ruri Date: August 25, 1993 Run t ime: 11:23 a.m. weanesday Title %.,. DEWATERikG STATION ARE A 0F FUEL POOL A

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

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

(photons /sec )

(MeV/sq cm/sec)

(mR/hr)

NO Buildup With Buildup No Buildup With Buildup 0.1 2.624e+007 6.400e-001 8.650e+000 9.792e-004 1.323e-002 0.15 1.795e+005 8.244e-003 8.013e-002 1.358e-005 1.319e-004 0.2 3.777e+006 2.719e 001 2.070e+000 4.798e-004 3.653e-003 0.3 7.837e+004 1.070e 002 5.504e 002 2.029e-005 1.044e-004 0.4 5.177e+006 1.116e+000 4.581e+000 2.174e-003 8.926e-003 0.5 2.207e+006 6.764e-001 2.361e+000 1.328e-003 4.635e-003 0.6 4.079e+009 1.666e+003 5.161e+003 3.252e+000 1.007e+001 0.8 2.061e+007 1.321e+001 3.443e+001 2.513e-002 6.548e-002 b

1.0 8.524e+007 7.733e+001 1.798e+002 1.426e-001 3.314e-001

y 1.5 B.828e+007 1.492e+002 2.886e+002 2.510e-001 4.855e-001 o

2.0 8.964e+003 2.329e-002 4.057e-002 3.602e-005 6.273e-005 z

1Q3 TOTAL:

4.310e+009 1.90se+003 5.6eze+003 3.675e+000 1.099e+001 p

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1 File Ref:

. fi DOS File: FUELPARA.MS4 Dates ~ / )

Run Dates August 25, 1993 By:

7 Run Times 1:13 p.m. Wednesday.

Checked:

' (4' A -

j Duration: 0:24:42 N

i Case

Title:

FUEL POOL A FUEL RACK AREA CEOMETRY 11 - Rectangular Volune centimeters feet and inches'

-I

[q Dose point coordinate x:

1264.3104 41.0 5.8 Dose point coordinate V:

676.75125

.22.0 2.4 Dose point coordinate 2:

215.265 7.0

.8 41 Rectangular volume width :

430.53 14.0 1.5 Rectangular volune length:

402.27199' 13.0 2.4

.3 Rectangular volune height:

1353.5025 44.0 4.9 y

Shield 1:

7.62 0.0 3.0 g6 Air Gap:

854.41841 28.0

.4 gN g Source volume: 2.34413e+8 cm*3 8278.23 cu ft.

1.43048e+7 cu in.

6 MATERIAL DENSITIES (g/cm*3)

?

Material Source Shield 1 Air Gap E

Shield Stab Air 0.00122 i

Iron 0.15809 o

')

Water 1.0 cn j.

BUILDUP d

Method: Buildup Factor Tables M

$. A u, The material reference is Source e

c eC S 1E INTEGRAfl0N PARAMETERS N

N [ ".

2 #

l Quadrature Order g

O E C X Direction 22 O

Y Direction 22 l

Z Direction 22 ~

J3

_80 l'

ll3 Q

l U

SOURCE NUCLlDES 3

,Q Nuclide curies

Cl/cm*3 Nuclide curies gCl/Cm'3 O

liii %

Ag-110 7.6900e 012 3.2805e-014 Ag-110m 5.7800e-010 2.4657e 012 O CD Am-241 1.3800e-003'5.8870e-006 Ba-137m 1.2200e-001 S.2045e 004 as C-14 8.4000e 006 3.5834e-008 Ce-141 0.0000e+000 0.0000e+000 ce-144 3.1300e-005 1.3352e-007 cm-242 1.4600e-007 6.2283e-010 E

Cm-243 1.4400e-008 6.1430e-011 cm 244 3.4100e-007 1.4547e-009 L

Co-58 0.0000e+000 0.0000e+000 co-60 1.9900e-003 8.4893e-006

.d Cr-51 0.0000e+000 0.0000e+000 Cs-134 1.7700e-004 7.550Be-007~

3

-g Cs 137 -

1.2900e 001 5.5031e-004 Eu 154 1.0000e-003 4.2660e-006 Eu-155-1.4500e-003 6.1857e-006 Fe-55 3.5100e-003 1.4974e-005 5-g' l

H-3 2.0400e-003 :8.7026e-006 1-129 3.3800e-008 1.4419e-010 d

Mn-54 1.1700e 007 4.9912e-010 Ni-63 1.9700e-002 8.4040e-005 N

o Np-237 5.6900e-007 2.4273e-009 Pa-233 5.6900e-007 2.42736-009 o

Pm-147 3.5700e-002 1.5230e-004 Pr-144 3.1300e-005 't.3352e-007 anse 2

Pr 144m 4.4700e-007 1.9069e-009 -

Pu-238 3.8500e-004 1.6424e 006 O

ta-

- Pu-239 4.7000e-003 2.0050e-005 Pu-240-1.2500e-003 5.3325e-006 g

Pu-241 4.1900e-002 1.7874e 004 Rh-106 5.3400e-005 2.2780e-007 o

A Ru-106 5.3400e-005. 2.2780e-007

.Sb-125 4.2400e-004 1.8088e-006 E

.s Sr-89 0.fl000e+000 0.0000e+000. Sr 90 3.1700e-001' 1.3523e-003 o

g Tc-99 5.9900e-005 2.5553e-007 Te 125m 9.7900e 005 4.1764e-007 ym U-234 6.3900e-005 2.7260e-007

~U-235 2.5800e-006 1.1006e-008 g.

U-236 1.7000e-006 7.2521e-009 U-238 1.2100e-005 5.1618e-008 5"

l Y-00 3.1700e-001 1.3523e-003 In-65 4.5200e-010 1.9282e-012 l,

I-l l

l

-n

. - =

II l

=

) -2 I

i l

Page

2' DOS File: FUELPARA.MS4 Run Date August 25, 1993 Run ifme 1:13 p.m. Wednesday fitte : FUEL POOL A FUEL RACK AREA I

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

1 Energy Activity Energy Fluence Rate Exposure Rate In Air j

(Mev) (photons /sec ). (MeV/sq cm/sec)

(ndt/hr)

No Buildup With Buildup No Buildup With Buildup 0.1 2.624e+007 2.038e-003 3.450e-003 3.118e-006 5.278e-006 0.15 1.795e+005 4.546e-005 1.040e-004 7.486e-008 1.713e-007 0.2 3.777e+006 - 1.869e-003 5.127e-003 3.299e-006 9.048e-006 0.3 7.837e+004 8.757e-005 2.678e-004 1.661e-007 5.080e-007 l:

0.4 5.177e+006 ' 9.871e-003 3.009e-002 1.923e-005 5.863e-005

/3 l

0.5 2.207e+006 6.290e-003 1.843e-002 1.235e-005 3.618e 005 l

0.6 4.079e+009 1.607e+001 4.484e+001 3.136e-002 8.752e-002 7) l-0.8 2.061e+007 1.345e-001 3.424e-001 2.559e 004 6.512e-004 1.0 8.524e+007 8.200e-001-1.928e+000 1.512e-003. 3.554e-003

.M 1.5 8.828e+007 1.691e+000 3.436e+000 2.845e-003 5.781e-003 2

2.0 8.964e+003 2.729e-004 5.081e-004 4.220e-007 7.857e-007 0m,w TOTAL:

4.310e+009 1,873e+001 5.060e+001 3.601e-002 9.761e-002 0

3 i

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NORMALIZATION WORKSHEET (1 Cl)

CALCULATED

==

8/25/93 EXPOSURE RATE PER Ct==>

1.10E+01 mR/h ACTUAL===>

5.42E+02 mR/h

==

UNITS IN>Ci

- - - ===*88=

====

TDday's Date 1.0. NUMBER OR KAMES >DEFUELING WASTE IN FUEL POOL "A" AT DEWATERING STATION A0 JUSTED NRC REPORTABLE INPUT UNIT PERCENT (%) ACTIVITY A0 JUSTED WITHOUT If > 1% of Sr-90/Cs-137 ISOTOPE ACTIVITY of Total PER CUR!E ACTIVITY (mCl)

DAUGHTERS (mCl)

TOTAL ISOTOPES RATIO

===================u==============n=========n=========n=================================================*************

1 H-3 2.04E-03 *"

0.20379 2.04E-03 * "

1.00E+02 1.00E+02 H-3 2.457

2 C-14 8.40E-06 ***

0.00084 8.39E-06 ***

4.14E 01 4.14E-01 C-14 3

Cr-51 0.00000 0.00E+00 ***

0.00E+00 0.00E+00 Cr-51 4

Mn-54 1.17E-07 * "

0.00001 1.17E-07 * "

5.76E-03 5.76E-03 Mn-54 5

Fe-55 3.51E-03 *"

0.35064 3.51E-03 ***

1.73E+02 1.73E+02 Fe-55 6

Co-58 0.00000 0.00E+00 *"

0.00E+00 0.00E+00 Co-58 7

Co-60 1.99E -03 *"

0.19880 1.99E 03 "*

9.80E+01 9.80E+01 Co-60 8 Wi 63 1.97E-02 '"

1.96798 1.97E 02 '"

9.70E+02 9.70E+02 REPORTABLEl Ni-63 9

Zn-65 4.52E-10 "

0.00000 4.52E-10 ***

2.23E-05 2.23E-05 2n-65 fh h %

10 Sr-89 0.00000 0.00E+00 "*

0.00E+00 0.00E+00 Sr-89 11 Sr-90 3.17E-01 *"

31.66757 3.17E 01 "*

1.56E+04 1.56E+04 REPORTABLEI Sr-90 M

N 12 Y-90 3.17E-01 *"

31.66757 3.17E- 01 "*

1.56E+04

========================== Y-90 N

13 Tc-99 5.99E-05 *"

0.00598 5.98E-05 *"

2.95E+00 2.95E+00 Tc-99 6

\\f(:

14 Ru-106 5.34E-05 *"

0.00533 5.33E-05 "*

2.63E+00 2.63E+00 Ru-106 N

2 h

{

15 Rh-106 5.34E-05 "*

0.00533 5.33E-05 *"

2.63E+00

= = = = = = = = = = ============ R h - 106 16 Ag-110m 5.78E-10 *"

0.00000 5.77E -10 "*

2.85E-05 2.85E-05 Ag-110m o

O 17 Ag-110 7.69E-12 "*

0.00000 7.68E-12 "*

3.79E-07

= = = = = = = = = = =

============== Ag-110 18 Sb-125 4.24E -04 "*

0.04236 4.24E-04 ***

2.09E+01 2.09E+01 Sb-125 y

i 19 Te-125m 9.79E -05 *"

0.00978 9.78E-05 "*

4.82E+00 4.82E+00 Te-125m o

j 20 1-129 3.38E-08 *"

0.00000 3.38E-08 *"

1.66E-03 1.66E-03 1-129 E

j 21 Cs-134 1.77E -04 "*

0.01768 1.77E -04 *"

8.72E+00 8.72E+00 Cs-134 22 Cs-137 1.29E -01 *"

12.88680 1.29E-01 **

6.35E+03 6.35E+03 REPORTABLEI Cs-137 23 Ba-137m 1.22E- 01 "*

12.18752 1.22E-01 *"

6.01E+03

=========== = ===== = = = = = B a - 137m 8

{

24 Ce-141 0.00000 0.00E+00 * "

0.00E+00 0.00E+00 Ce-141

?

g%

25 Ce-144 3.13E-05 "*

0.00313 3.13E-05 *"

1.54E+00 1.54E+00 Ce-144 Q

26 Pr-144m 4.47E-07 ***

0.00004 4.47E-07 * "

2.20E-02

= = = = = = = = = = = = = === = = = = = = P r-144m em 27 Np-237 5.69E - 07 *"

0.00006 5.68E-07 "*

2.80E-02 2.80E-02 Np-237 m

28 Pa-233 5.69E-07 *"

0.00006 5.68E- 07 "*

2.80E-02

============= === = ==== = = = = = P a-233 0

x o j

d 29 Pu-238 3.85E-04 *"

0.03846 3.85E- 04 "*

1.90E+01 1.90E+01 Pu-238

{g33 30 Pu-239 4.70E -03 *"

0.46952 4.70E-03 *"

2.31E+02 2.31E+02 Pu-239 y) yZ 31 Pu-241 4.19E 02 *"

4.18571 4.19E-02 *"

2.06E+03 2.06E+03 REPORTABLEI Pu-241 2"

g C

O c0 32 Am-241 1.38E-03 ***

0.13786 1.38E 03 "*

6.80E+01 6.80E+01 Am-241 o

33 Cm-243 1.44E-08 ***

0.00000 1.44E-OS ***

7.09E-04 7.09E-04 cm-243 34 U-235 2.58E-06 *"

0.00026 2.58E 06 *"

1.27E-01 1.27E-01 U 235

.3 35 U-238 1.21E -05 "*

0.00121 1.21E-05 "*

5.96E-01 5.96E-01 U-238 23 36 Pu-240 1.25E-03 *"

0.12487 1.25E-03 *"

6.15E+01 6.15E+01 Pu-240 M

D h

{Q 37 U 234 6.3?E-05 "*

0.00638 6.38E 05 *"

3.15E+00 3.15E+00 U-234 38 Pm-147 3.57E-02 "*

3.56635 3.57E-02 "*

1.76E+03 1.76E+03 REPORTABLE! Pm-147 O

W~

39 Eu-154 1.00E -03 *"

0.09990 9.99E-04 "*

4.92E+01 4.92E+01 Eu-154 0

40 Eu-155 1.45E- 03 *"

0.14485 1.45E-03 *"

7.14E+01 7.14E+01 Eu-155 e

41 U-236 1.70E-06 "*

0.00017 1.70E-06 ***

8.37E-02 8.37E-02 U-236 3

42 Pr-144 3.13E-05 *"

0.00313 3.13E-05 * "

1.54E+00

= = = = = = = = = = = = = =============== Pr-144 N

43 Cm-242 1.46E-07 *"

0.00001 1.46E-07 ***

7.19E-03 7.19E-03 Cm-242 44 cm-244 3.41E-07 "*

0.00003 3.41E-07 ***

1.68E-02 1.68E-02 cm-244

.3 45 0.00000 0.00E+00 "*

0.00E+00 0.00E+00 6

5 /$

_=====_========-===--=--=-======m=mo=======_m=om==========m==========_m===_=_===-===g u

TOTALS==>1.0010E+00 Cl 100.00 1.00000 Ci 49290.264 mci 27669.755 mci g

g e

O c

3 A

0 x

Z e

3 e a=

t.,

c

+'

. -1 1

l NORMALIZATION WORKSHEET (1 Cl)

CALCULATED

=

==

8/25/93 EXPOSURE RATE PER Ci==>

9.76E-02 mR/h ACTUAL===>

8.40E+00 mR/h

==

UNITS IN>Ci

- =========

==

Today's Date I.D. NUMBER OR NAMES >DEFUELING WASTE IN FUEL POOL "A= AT FUEL RACK AREA ADJUSTED WRC REPORTABLE INPUT UNIT PERCENT (%)

ACTIVITY ADJUSTED WITHOUT If > 1% of Sr-90/Cs-137 ISOTOPE ACTIVITY of Total PER CURIE ACTIVITY (mCl) DAUGHTERS (mC1)

TOTAL ISOTOPES RATIO

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

1 H3 2.04E-03 * "

0.20379 2.04E -03 *"

1.75E+02 1.75E+02 H-3 2.457

2 C 14 8.40E-06 *"

0.00084 8.39E-06 "*

7.22E-01 7.22E-01 C-14 3

Cr-51 0.00000 0.00E+00 ***

0.00E+00 0.00E+00 Cr-51 4

Mn-54 1.17E-07 *"

0.00001 1.17E-07 ***

1.01E-02 1.01E-02 Mn-54

(

5 Fe-55 3.51E-03 ***

0.35064 3.51E-03 ***

3.02E+02 3.02E+02 Fe-55 t'

6 Co-58 0.00000 0.00E+00 '"

0.00E+00 0.00E+00 Co-58 7

Co-60 1.99E-03 *"

0.19880 1.99E-03 *"

1.71E+02 1.71E+02 Co-60

, '5 8 Ni 63 1.97E 02 "*

1.96793 1.97E-02 *"

1.69E+03 1.69E+03 REPORTABLEl Ni-63 g

9 2n-65 4.52E-10 '"

0.00000 4.52E -10 *"

3.89E-05 3.89E-05 In-65 g

10 Sr-89 0.00000 0.00E+00 *"

0.00E+00 0.00E+00 Sr-89 3

11 Sr-90 3.17E 01 ~

31.66757 3.17E-01 *"

2.73E+04 2.73E+04 REPORTABLEt Sr-90 12 Y 90 3.17E-01 *"

31.66757 3.17E-01 '"

2.73E+04

============================= Y-90 6

13 Tc-99 5.99E-05 "*

0.00598 5.98E-05 "*

5.15E+00 5.15E+00 Tc-99 Z

e 14 R u-106 5.34E-05 ***

0.00533 5.33E-05 ***

4.59E+00 4.59E+00 Ru-106 e"

15 Rh-106 5.34E-05 ***

0.00533 5.33E-05 *"

4.59E+00

========"r

= = = ==== ===== = R h - 106 16 Ag-110m 5.7BE-10 ***

0.00000 5.77E-10 *"

4.97E-05 4.97E-03 Ag-110m g

17 A g-11u' 7.69E-12 "*

0.00000 7.68E -12 *"

6.61E-07

= = = = = = = = = = = =

============== Ag-110 o

N 18 Sb-125 4.24E-04 ***

0.04236 4.24E-04

3.65E+01 3.65E+01 Sb-125

@ k 19 Te-125m 9.79E-05 *"

0.00978 9.7BE-05

8.42E+00 S.42E+00 Te-125m 4

20 1 129 3.38E-08 "*

0.00000 3.38E-08 "*

2.91E-03 2.91E-03 1-129 o$

e 21 Cs 134

1. 77E -04

0.01768 1.77E-04

1.52E+01 1.52E+01 Cs-134 m

m" 22 Cs-137 1.29E-01

12.88680 1.29E-01

1.11E+04 1.11E+04 REPORTABLEI Cs-137 h

7 E:

23 Ba 137m 1.22E-01 "*

12.18752 1.22E-01 ~

1.05E+04

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

0.00E+00 0.00E+00 Ce-141

.C O 71 o

25 Ce-144 3.13E-05

0.00313 3.13E-05 "*

2.69E+00 2.69E+00 Ce-144 Z N f.

f 5

26 Pr-144m 4.47E-07

0.00004 4.47E-07

3.84E-02

=============== === <======= P r-144m C

27 hp-237 5.69E-07 *"

0.00006 5.68E-07

4.89E-02 4.89E-02 Np-237

.9 28 Pa-233 5.69E-07 "*

0.00006 5.68E-07 *"

4.89E-02

= = = = = = = = = = ====== mum Pa-233 5

29 Pu 238 3.85E 04 ***

0.03846 3.85E-04

3.31E+01 3.31E+01 Pu-238 3

r 30 Pu-239 4.70E-03

0.46952

4. 70E -03 "*

4.04E+02 4.04E+02 Pu-239 0

5 31 Pu-241 4.19E -02 "*

4.18571 4.19E-02

3.60E+03 3.60E+03 REPORTABLEI Pu-241 lh

.[

32 Am-241 1.3BE- 03 "*

0.13786 1.38E-03

1.19E+02 1.19E+02 Am-241 O

j; 33 cm-243 1.44E -08 "*

0.00000 1.44E-OS

1.24E-03 1.24E-03 Cm-243 g

34 U 235 2.58E-06 ***

0.00026 2.5BE 06 ***

2.22E-01 2.22E-01 U 235

+>

35 U 238 1.21E-05 "*

0.00121 1.21E-05

1.04E+00 1.04E+00 U-238 E

36 Pu-240 1.25E-03 ***

0.12487 1.25E-03

1.07E+02 1.07E+02 Pu 240 C

37 U-234 6.39E-05 "*

0.00638 6.38E-05 *"

5.49E+00 5.49E+00 U-234 0

38 Pm-147 3.57E-02 ~

3.56635 3.57E 02 "*

3.07E+03 3.07E+03 REPORTABLEt Pm-147 o

39 E u-154 1.00E-03

0.09990 9.99E-04

8.60E+01 8.60E+01 Eu-154 E

40 E u-155 1.45E 03 ***

0.14485 1.45E-03 *"

1.25E+02 1.25E+02 Eu-155 b

j 41 U 236 1.70E -06 "*

0.00017 1.70E-06

1.46E-01 1.46E-01 U-236 E

g

= = = = = = = = = = = = = = ======= ====== P r-144 h 42 Pr-144 3.13E 05 ***

0.00313 3.13E-05

2.69E+00 o

43 Cm-242 1.46E-07

0.00001 1.46E -07 *"

1.26E-02 1.26E-02 Cm-242 E

44 Cm-244 3.41E-07

0.00003 3.41E-07 ***

2.93E-02 2.93E-02 Cm-244 D

45 0.00000 0.00E+00

0.00E+00 0.00E+00 E

o 3

g

====_=============== m - -======= m======= m=== m======_========================== _===== _=== _=====_

TOTALS==>1.0010E+00 Ci 100.00 1.00000 Ci 86056.756 mci 48309.122 mci

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ELE VATION VIEW
( FUEL HANDLING BUILDING )
t FUEL CANISTF9 STORAGE RACKS O!lld 1
-- --I---
.V 7
E e
' -1
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MicrcShield 4.00 - Serial #4.00-00247 i
CPU Page
1 File Reft h
005 file: FUELPARA.MS4 Dates if Rtn Date: August 26, 1993 By:
(N M l Rur. Times 2:05 p.m. Thursday Checked:
4 Duration: 0:24:45
'N Case
Title:
FUEL POOL A FUEL RACK AREA GEOMETRY 11 - Rectangular Volune centimeters feet and inches j
cose point coordinate x:
1203.3504 39.0 5.8 i
Dose point coordinate Y:
676.75125 22.0 2.4 t
cose point coordinate 2:
215.265 7.0
.7 Rectangular volume width :
430.53 14.0 1.5 Rectangular volume length:
402.27199 13.0 2.4 g.
Rectangular volune height:
1353.5025 44.0 4.9 fn Shield 1:
7.62 0.0 3.0 g
Air caps
' 793.45841 26.0
.4 o
Source Volune: 2.34413e+8 cm*3 8278.23 cu ft.
1.43048e+7 cu in, j
l 6
i s
MATERIAL DENSITIES (g/cm*3) b
[
Material Source Shield 1 Air Cap Shield Slab 6
t Air 0.00122 z
?
Iron 0.15809 gC Water 1.0 m
f BUILDUP o
Method: Buildup f actor Tables y
j The material reference is Source 9
]NTEGRAT!OM PARAMETERS J
I "h
7 A$
Quadrature Order N
+
X Direction 22 Y Ofrection 22
.c o
"o 2 Direction 22 f/) NN
.3 2 #
.i g
O O
SOURCE NUCL10ES 4
Nuclide curies ECl/cm*3 Nuclide curies
Cl/cm*3 h
Ag-110 7.6900e-012 3.2805e-014' An-110m 5.7800e-010 2.4657e-012 3
m Am-241 1.3800e-003 5.8870e-006 - Ba-137m 1.2200e-001 5.2045e-004 O
R C-14 8.4000e-006 3.5834e-008 Ce-141.
0.0000e+000 0.0000e+000 h
Ce-144 3.1300e-005 1.3352e-007 Cm-242 1.4600e-007 6.2283e-010 2N
$m s
Cm 243 1.4400e-008 6.1430e-011 cm-244 3.4100e-007 1.4547e-009 Co-58 0.0000e+000 0.0000e+000 Co-60 1.9900e-003 8.4893e-006 i
e Cr-51 0.0000e+000 0.0000e+000 Cs-134 1.7700e-004 7.5508e-007
+d Cs-137 1.2900e-001 5.5031e-004 Eu-154 1.0000e-003 4.2660e 006 Eu-155 1.4500e-003 6.1857e 006 Fe 55 3.5100e-003 1.4974e-005 1
H-3 2.0400e-003 8.7r46e-006 1-129 3.3800e-008 1.4419e-010 m
u Mn-54 1.1700e-007 4.9912e-010 Ni-63 1.9700e-002 8.4040e-005 W
Np-237 5.6900e-007 2.4273e-009 Pa-233 5.6900e-007 2.4273e-009 as Pm-147 3.5700e-002-1.5230e-004 Pr-144 3.1300e-005 1.3352e-007 T.
Pr 144m 4.4700e-007 1.9069e-009 Pu-238
-3.8500e-004 1.6424e 006 b'
3 Pu-239 4.7000e-003 2.0050e-005 Pu-240 1.2500e-003 5.3325e-006
i Pu-241 4.1900e-002 1.7874e-004 Rh 106 5.3400e-005 2.2780e-007 g
^
Ru-106 5.3400e-005 2.2780e-007 Sb-125 4.2400e-004 1.8088e-006 me m
Sr-89 0.0000e+000 0.0000e+000 Sr-90 3.1700e-001 1,3523e-003 Q
C Tc-99 5.9900e-005 2.5553e-007 Te-125m 9.7900e-005. 4.1764e-007 N
U-234 6.3900e-005 2.7260e-007 U 235 2.5800e-006 1.1006e-008 x
U 236 1.7000e-006 7.2521e 009 U-238 1.2100e-005 5.1618e-008 g'
O Y-90 3.1700e-001 1.3523e-003 Zn-65 4.5200e-010 1.9282e-012 C
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{
DOS Files FUELPARA.HS4 Run Date: August 26, 1993 Run Times 2:05 p.m. Thursday l
Title : FUEL POOL A FUEL RACC AREA l
............===========...... RESULTS===============================
l Energy Activity Energy Fluence Rate Exposure Rate in Air l
(Mev) (photons /sec )
(MeV/sq cm/sec)
(ndt/hr)
Wo Buildup With Bui(dup No Buildup With Buildup 0.1 2.624e+007 2.279e-003 3.858e 003 3.486e-006 5.902e-006-0.15 1.795e+005 5.081e 005 1.162e-004 8.367e-008 1.914e 007 O.2 3.777e+006 2.089e-003 5.726e 003 3.686e-006 1.011e-005 i
l 0.3 7.837e+004 9.780e-005 2.958e-004 1.855e-007 5.669e-007 -
l.
0.4 5.177e+006 1.102e 002 3.357e-002 2.147e-005 6.540e-005 O.5 2.207e+006 7.021e-003 2.055e-002 1.378e-005 4.035e-005 0.6 4.079e+009 1.793e+001 4.999e+001 s.500e-002 9.758e-002 N'
0.8 2.061e+007 1.501e-001 3.816e-001 2.855e-004 7.258e 004
.o 1.0 8.524e+007 9.147e-001 2.149e+000 1.686e-003 3.961e 003 E O 1.5 8.828e+007 1.886e+000 3.828e+000 3.172e-003 6.440e-003 IgD g, 2.0
. 8.964e+003 3.042e-004 5.659e-004 4.704e-007 8.751e-007
-f TOTt.L:
4.310e+009 2.090e+001 5.641e+001 4.018e-002 1.088e-001 2
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1 File Reft A
DOS File: FUELPARA.MS4 Date: _f I
}
Run Date: August 26, 1993 By:
l A _
Rm Time: 2:38 p.m. Thursday Checked:
1 W\\*
Duration: 0:24:45 95 Case title: FUEL POOL A FUEL RACK AREA CEONETRY 11 - Rectangular volume l
centimeters feet and inches Dose point coordinate x:
1325.2704 43.0 5.8 o
Dose point coordinate Y:
676.75125 22.0 2.4 E
I N
Dose point coordinate 2:
215.265 7.0
.7 i
gZ D j.
l Rectangular volune width :
430.53 14.0 1.5 Rectangular volume length:
402.27199 13.0 2.4 Rectangular volune height:
1353.5025 44.0 4.9 3
Shield 1:
7.62 0.0 3.0 g
Air Cap:
915.37841 30.0
.4
,. o i
i Source volune 2.34413e+8 cm*3 8278.23 cu ft.
1.43048e+7 cu in.
k MATERI AL DENS 111ES (g/cm"3)
O Material Source Shield 1 Air Gap o
1 Shield Stab d
Air 0.00122 Ch Iron 0.15809 A
i Water 1.0 C
7 A$
BUILDUP d
Methods Buildup Factor Tables
[$
The material reference is source g
y
=
INTEGRATION PARAMETERS E
g Quadrature Order 3
cn X Direction 22
.9 R
Y Direction 22 15 e eu 1
2 Direction 22 O
8g
]
3 SOURCE NUCL10ES e
Nuclide curies
Cl/cm*3 Nuclide curies
/LCi/Cm 3 b
j Ag-110 7.6900e-012 3.2805e-014 Ag-110m 5.7800e-010 2.4657e-012 Am-241 1.3800e-003 5.8870e-006 Ba 137m 1.2200e-001 5.2045e-004.
w i
-1 C 14 8.4000e-006 3.5834e-008 Ce-141 0.0000e+000 0.0000e+000 as Ce-144.
3.1300e-005 1.335?e-007 cm-242 1.4600e-007 6.2283e-010 l
Cm-243 1.4400e-005 6.1430e-011 Cm-244 3.4100e-007 1.4547e-009 h,
5 g
h.
i co 58 0.0000e+000 0.0000e+000 co-60 1.9900e-003 8.4893e-006 u
l Cr 51 0.0000e+000 0.0000e+000 Cs-134 1.7700e-004 7.5508e-007 m
o l
Cs-137 1.2900e-001 5.5031e-004 Eu-154 1.0000e-003 4.2660e-006 W
M Eu-155 1.4500e-003 6.1857e-006 Fe 55 3.5100e-003 1.4974e-005 "O l t
=
H-3 2.0400e-003 d.7026e-006 1-129 3.3800e-008 1.4419e-010 Mn-54 1.1700e-007 4.9912e-010 Ni-63 1.9700e-002 8.4040e-005 E.
-Q g
Np-237 5.6900e-007 2.4273e-009 Pa-233 5.6900e-007 2.4273e-009 as Pm.147 3.5700e-002 1.5230e-004 Pr 144 3.1300e-005 1.3352e-007 5
g Pr 144m 4.4700e-007 1.9069e-009 Pu-238 3.8500e-004 1.6424e-006-s-
Pu-239 4.7000e-003 2.0050e-005 Pu-240 1.2500e-003 5.3325e-006 E
1-Pu-241 4.1900e-002 1.7874e-004 Rh 106 5.3400e-005 2.2780e-007 g
O" Ru-106 5.3400e 005 2.2780e-007 Sb-125 4.2400e-004 1.8088e-006 co Sr-89 0.0000e+000 C.0000e+000 Sr-90 3.1700e-001 1.3523e-003 Tc-99 5.9900e-005 2.5553e-007 Te-125m-9.7900e-005 4.1764e-007 U-234 6.3900e-005 2.7260e-007 U-235 2.5800e-006 1.1006e 008 U 216 1.7000e-006 7.2521e-009 U-238 1.2100e-005 5.1618e-005 Y-90 3.1700e 001 1.3523e-003 2n-65 4.5200e-010 1.9282e-012 l
1 i
I 1
i
. -4 1
'i Page
2 i
DOS Files FUELPARA.MS4 Run Date August 26, 1993 i
Run Times 2:38 p.m. Thursday Title FUEL POOL A FUEL RACK AREA
...........................==== RESULTS===============================
Energy Activity Energy Fluence Rate Exposure Rate In Air I
(Mev)
(stotons/sec )
. (MeV/sq cm/sec)
(mR/hr)
No Buildup With Buildup 'No Buildup With Buildup 0.1 2.624e+007 1.829e-003 3.097e-003 2.798e-006 4.738e-006 ~
0.15 1.795e+005 4.082e-005 9.344e-005 6.722e-008 1.539e-007-0.2 3.777e+006 '1.679e-003 4.609e-003 2.964e-006 8.135e-006
-i 0.3 7.837e+004 7.872e-005 2.410e-004 1.493e 007 4.:31e-007 0.4 5.177e+006 8.877e-003. 2.709e-002 1.730e-005 5.279e-005 O.5 2.207e+006 5.658e 003 1.660e-002 1.111e-005 3.259e 005 h'
O.6 4.079e+009 1.446e+001 4.040e+001 2.822e-002 7.885e-002 s
0.8 2.061e+007 1.211e-001 3.086e-001 2.303e-004 5.869e-004 o
g 1.0 8.524e+007 7.383e-001 1.738e+000 1.361e-003 3.204e-003 z
1.5 8.828e+007 1.523e+000 3.099e+000 2.563e-003 5.213e-003 1
2.0 8.964e+003 2.459e-004 4.583e-004 - 3.803e-007 7.087e-007 g
j-TOTAL:
4.310e+009 1.686e+001 4.559e+001 3.240e 002 8.795e-002 I
h t
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003 Files FP-B.MS4 Rm Date: August 26, 1993 Run Times 3:35 p.m. Thursday
[
Title : DEWATERING STATION AREA 0F FUEL POOL A l
==== RESULTS FOR SENSITIV1TT REFERENCE CASE (X = 30.48)=====
}
Energy Activity Energy Fluence Rate Exposure Rate in Air 4
(MeV)
(photons /sec )
(MeV/sq cm/sec)
(pA/hr) 6 No Buildup With Buildup No Buildup With Buildup.
+
0.1 2.624e+007 6.400e 001 8.650e+000 9.792e-004 1.323e-002 0.15 1.795e+005 8.244e 003 8.013e-002 1.358e-005 1.319e-004
' i 0.2 3.777e+006 2.719e-001 2.070e+000 4.798e-004 3.653e 003 0.3 7.837e+004 1.070e-002 5.504e-002 2.029e 005 1.044e-004 0.4 5.177e+006 1.116e+000 4.581e+000 2.174e-003 - 8.926e-003 0.5 2.207e+006 6.764e 001 2.361e+000 1.328e 003 4.635e-003 6
N 0.6 4.079e+009 1.666e+003-5.161e+003 3.252e+000 1.007e+001
)b i
0.8 2.061e+007 1.321e+001 3.443e+001 2.513e-002 6.548e-002 2
1.0 8.524e+007 7.733e+001 1.798e+002 1.426e-001 3.314e-001 2D S
1.5 8.828e+007 1.492e+002 2.886e+D02 2.510e-001 4.855e-001 2.0 8.964e+003 2.329e-002 4.057e-002 3.602e-005 6.273e-005 i
E TOTAL:
4.310e+009 1.908e+003-5.682e+003 3.675e+000 1.099e+001 gO c
SENSITIVITY RESULTS For: X (cm)
Case Sensitivity Energy Fluence Rate Exposure Rate In Air o
4 N&r Variable (MeV/sq cm/sec)
(mR/hr) y Value No Buildup With Buildup No Buildup With Buildup e
1 15.24 1.593e+003 5.289e+003 3.065e+000 1.023e+001 m"
2 23.70667 1.860e+003 5.666e+003 3.582e+000 1.096e+001 e
3 32.17333 1.912e+003 5.670e+003 3.683e+000 1.096e+001 Q
r 4
40.64 1.910e+003 5.555e+003 3.679e+000 1.074e+001
~%
N I
5 49.10667 1.890e+003 5.385e+003 3.640e+000 1.042e+001 sp 6
57.57333 1.859e+003 5.185e+003 3.582e+000 1.003e+001
.c o
V 4
7 66.04 1.822e+003 4.968e+003 3.511e+000 9.610e+000
(/) $"
3 I
m 8
74.50667 1.779e+003 4.745e+003 3.429e+000' 9.179e+000 s **
l g
9 82.97333
1. 733e+003 4.522e+003 3.339e+000 8.749e+000 0
i 0
10 91.44 1.683e+003 4.304e+003 3.244e+000 8.326e+000 j
S Use the Olsplay Menu For Energy Group Results For All Cases.
]
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Microshield 4.00 - Serial #4.00 00247 CPU Page
1 File Ref:
JL/M-l DOS File FP 8.MS4 Date:
Run Date: August 26, 1993 By:
\\ \\snW Run Time: 3:35 p.m. Thursday Checked: NWV Duration: 0:28:02 5
"'\\
e Case
Title:
DEWATERING STAT:0N AREA Of FUEL POOL A GEOMETRY 4 - Vertical Rectangular Area centimeters feet and inches i
Dose point coordinate X 30.48 1.0
.0 l
Dose point coordinate Y 360.045 11.0 9.7
'M i
Dose point coordinate 2:
193.67495-6.0 4.2 Rectangular area height:
720.09 23.0 7.5 l
Rectangular area width:
387.35 12.0 8.5
.5 shield 1:
7.62 0.0 3.0 g
7 Air Cap:
22.86 0.0 9.0
,b l
Source Area: 278927. sq cm 300.234 sq ft.
43233.8 sq in, a
i MATERIAL DENSITIES (g/cm*3) 2
- \\
6 i
,o e
Material Shield 1 Air Gap g
slab E
Air 0.00122 Water
-1.0 O
o BUILDUP a
j Method: Buildup factor Tables c"n j
The material reference is shield 1
),
i N
e m
a Ue INTEGRATION PARAMETERS S
i Quadrature Order
.C 6O 3
2 Direction 30
. U3 2 N J
1 Y Direction 30 g
T.:
1 SOURCE NUCL! DES EB]
Wuclide curies
Ci/cm8 Nuclide curies
Cl/cma m
Ag 110 7.6900e-012 2.7570e 011 An-110m 5.7800e-010 2.0722e 009 o
-T Am-241 1.3800e-003 4.9475e-003 Ba-137m 1.2200e-001 4.3739e 001 3
-,y C-14 8.4000e-006 3.0115e-005 Ce 141 0.0000e+000 0.0000e+000 Q
5 Ce-144 3.1300e-005 1.1222e-004 Cm-242 1.4600e-007 5.2343e 007 Cm-243 1.4400e-008 5.1626e 008 Cm-244 3.4100e-007 1.2225e 006 cu co 58 0.0000e+000 0.0000e+000 co 60 1.9900e-003 7.1345e 003 Cr-51 0.0000e+000 0.0000e+000 Cs 134 1.7700e-004 6.3457e-004 E
Cs-137 1.2900e-001 4.6249e-001 Eu-154 1.0000e-003 3.5852e 003 3
1 Eu-155
~1.4500e-003 5.1985e-003 fe-55 3.5100e-003 1.2584e 002 j
H3 2.0400e-003 7.3137e-003 1-129 3.3800e-008 1.2118e-007 Mn-54 1.1700e-007 4.1946e 007 Ni-63 1.9700e-002 7.0628e-002 Wp 237 5.6900e-007 2.0400e-006 Pa-233 5.6900e 007 2.0400e-006 s-b-
3 Pm-147 3.5700e-002 1.2799e-001 Pr-144 3.1300e 005 1.1222e 004 Pr-144m 4.4700e-007 1.6026e-006 Pu 238 3.8500e-004 1.3803e-003
.E Pu-239 4.7000e-003 1.6850e-002 Pu-240 1.2500e-003 4.4815e-003 g^
.O Pu-241 4.1900e-002 '1.5022e-001.
Rh-106 5.3400e-005 1.9145e 004 amma O
Ru 106 5.3400e-005 1.9145e-004 Sb-125 4.2400e-004 1.5201e-003 Q
C I
g A
(
Sr-89 0.0000e+000 0.0000e+000 Lr-90 3.1700e-001 1.1365e+000 Te 99 5.9900e-005 2.1475e 004 Te 125m 9.7900e-005 3.5099e-004 o
I U 234 6.3900e-005 2.2909e-004 U-235 2.5800e-006 9.2497e-006 E
E
')
U-236 1.7000e-006 6.094Be 006 U 238 1.2100e-005 4.3381e-005 A
g g Y-90 3.1700e-001 1.1365e+000 2n-65 4.5200e-010 1.6205e-009 m
ic- 'OA
EXPOSURE RATE FROM AREA SOURCE t.
FH109 FUEL POOL-1 Curie Source m
w 11.2
_ y 6
(Ns
lo 4 11
~
jrn ju 10.8 k
I s
10.6 io
/
\\
-~
5 Y
10.4 k
10.2 i
,\\
9 %
10 g
2 x
N 9.8 N
l,-
o lg.s m s 9.6 Q--
g j" 5
s
\\
~"
0 u) 9.4 N
2
\\
k 9.2 e
m
.O g
O 82 9
\\
3
\\
8.8 k
a l
8.6 as
\\
b 5
d g ; /n 84 n
8.2 3
3 (g 10 30 50 70 90 g
2 S
b g
NUMBER OF CENTIMETERS FROM SURFACE 5,@
a=
p f
6" vs
. kI 9

ML20057B958

Contents

Text

SUMMARY

3.0 REFERENCES

A

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Title:

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

Title:

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

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Title:

==== RESULTS FOR SENSITIV1TT REFERENCE CASE (X = 30.48)=====

Title:

Navigation menu

ML20057B958

Text

SUMMARY

3.0 REFERENCES

A

============.s

Title:

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

Title:

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

==

==

==

*==*==

= = = = = = = = = = =

=

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= = = = = = = = = = = =

= b === = = = = = = =

Title:

==== RESULTS FOR SENSITIV1TT REFERENCE CASE (X = 30.48)=====

Title:

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

====