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Application to Amend Licenses NPF-9 & NPF-17,authorizing Disposal of Very Low Level Radwaste.Discussion of Proposed Disposal Method & Fee Encl
	ML20092H507
Person / Time
Site:	McGuire, Mcguire
Issue date:	06/18/1984
From:	Tucker H; DUKE POWER CO.
To:	Adensam E, Harold Denton; Office of Nuclear Reactor Regulation
References
	TAC-55306, NUDOCS 8406260142
	Download: ML20092H507 (56)
	v • d • e

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DUKE POWER GOMPANY P.O.150x 33180 CIIAMLOTTE, N.C. 28242 HAl. B. TUCKER TEI.E PIf 0NE vice Persmew, (704) 373-4331 steteAS PRODUCTION June 18, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention:

Ms. E. G. Adensam, Chief Licensing Branch no. 4 Re: McGuire Nuclear Station Docket Nos. 50-369, -370

Dear Mr. Denton:

Pursuant to 10 CFR 20 520.302, please find attached an application for the disposal of very low level radioactive waste. Duke Power Company hereby requests NRC approval of the proposed disposal method described in the attached application.

This application proposes to relocate slightly contaminated water treatment residues from the initial holdup pond of the conventional wastewater treatment system to the Landfarming Permit site which is to be covered with approximately four to six inches of uncontaminated topsoil. The landspreading site is located outside the security fence but on company owned land which is accessible from the company controlled area.

In order to prevent further build-up of low level radioactive waste in the initial holdup pond, backwashing the demineralizers can be kept to a minimum for approximately two months. Duke Power requests that the NRC review and approve this proposal expeditiously to enabic uninterrupted operation of McGuire.

Duke Power has determined that a license fee is required for this approval; therefore, please find attached a check in the amount of $150.00.

Very truly yours.

Hal B. Tucker l{f(/

WuM/php Attachment cc:

Mr. James P. O'Reilly Mr. W. T. Orders Regional Administrator NRC Resident Inspector k

U. S. Nucicar Regulatory Commission McGuire Nuclear Station 00 Region II g

101 Marietta Street, NW, Suite 2900 i

Atlanta, Georgia 30323 8406260142 840618

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MCGUIRE NUCLEAR STATION APPLICATION FOR THE APPROVAL TO DISPOSE OF VERY LOW-LEVEL RADI0 ACTIVE WASTE 1.0 Purpose Pursuant to 10CFR20, S 20.302 Duke Power Company requests NRC approval of the proposed method for the disposal of water treatment residues contaminated at very low-levels of radioactivity.

This application addresses the specific information requested in S 20.302.

2.0 Description of Waste Source Sanitary, potable, and demineralized water systems at McGuire Nuclear Station are supplied with water.that has been filtered through diatomaceous earth (DE) pressure filters.

There are two DE filters, each with a capacity of 750 gpm for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , but normal filtered water usage requires operation of one filter at 750 gpm approximately 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months per day.

The filters are backwashed as needed.

With each backwash, 0.15 cubic yards of spent DE are flushed to the conventional wastewater treat-ment system.

The condensate demineralization system, which removes impurities from the steam cycle water, consists of four mixed bed demineralizer filters that use powdered ion-exchange resin.

Under normal operation, three condensate demineralizers are operated continuously and each cell is backwashed every 10 days.

With each backwash, 0.67 cubic yards of spent resin are flushed to the conventional wastewater treatment system.

Raw water intended for condensate makeup is pretreated to remove chlorine and organic material.

Two 270 f t3 beds of organic removal type activated charcoal are used for this purpose and generate approximately 540 ft3 of spent charcoal per year.

All non-radioactive station waste streams, except sanitary waste, are routed to the conventional wastewater treatment system, which uses sedi-mentation, chemical addition, and aeration to treat the wastewater prior to discharge to the Catawba River via the National Pollutant Discharge Elimination System (NPDES) discharge point.

Primary sedimentation occurs in the initial holdup pond, a 200,000 gallon concrete basin.

Spent pow-dered resin, charcoal, and DE accumulate in this pond and must be removed periodically to maintain proper settling and retention of wastewater.

3.0 Waste Description The sludge collected from the initial holdup pond is a semi-solid mixture of powdered resins, diatomaceous earth, and associated residues.

The resins are styrene divinylbenzene polymers and contain the ions removed from the condensate.

The radioactivity concentrations of the sludge have been determined to be very low.

The radionuclides and average concentrations obtained from eight samples of these sludge were identified as follows:

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Radionuclide Average Concentration (pCi/cm3)

% Abundance Co-58 1.22 E-07 51.5 Co-60 1.15 E-07 48.5 The sample analysis reports are provided in Appendix 1.

The volume of waste being generated per year is projected to range from 8,500 to 13,500 cubic feet.

At present, McGuire has accumulated approxi-mately 10,000 cubic feet of these materials in the initial holdup pond.

j 4.0 Proposed Disposal Method r

i Because the sludge is slow to dry, it is unsuitable for landfilling, I

where the waste must be covered with soil the same day it is deposited.

It is preferable to landspread the sludge at a suitable site and in-corporate it into the soil after it has dried.

The proposed disposal procedures which already approved for use by the state under Landfarming j

permit are as follows-4.1 Transportation Procedure To remove this sludge, the pond is drained and the sludge is dredged from the bottom and transferred by dump truck to the disposal site.

l The sludge will be transported to or from.the disposal site in such way that liquid or solid spills will be kept to a minimum.

The preparation and shipment of radioactive material will be in accordance with station Health Physics procedures and station directives.

I 4.2 Disposal Procedure During and after the disposal process access to the proposed i

disposal site will be controlled.

Proper warnings will be main-tained as described in Landfarming permit.

The waste sludge (water treatment residues) will be spread on l

l the surface of the proposed disposal site over an approximate area and depth of one acre and six inches, respectively.

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The sludge will be incorporated approximately six inches into the I

soil after drying to the extent practical.

Because of water retention by the resins, there will be no inhalation hazard from diatomaceous earth particles.

A suitable year round vegetative cover will be established and i

maintained af ter the waste has been incorporated and covered with topsoil as needed, if necessary.

The workers handling the waste disposal will be properly dressed in accordance with station Health Physics procedures and station directives.

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4.3 Administration Procedure The waste volume of each batch disposed will be properly estimated and documented.

For each batch of waste generated, a composite sample from different locations will be taken for radiological analysis, and results will be documented.

The total waste volume and radioactivity inventories will be documented, and the total accumulating dose will be periodically evaluated.

The disposal rates will be limited to 500 cubic yards per year (6 inches / acre / year).

Adequate provisions will be taken to prevent wind erosion and surface runoff from conveying pollutants from the waste material application disposal area onto the adjacent property.

Upon retirement, the site will be covered with top soil, if necessary, and grassed.

5.0 Evaluation of Environmental Impact 5.1 Proposed Site Characteristics 5.1.1 Topography The proposed landspreading site is located northwest of the McGuire conventional treatment system outside the security fence but within the company controlled area.

Figure 1 indi-cates the proposed landspread site location.

The entry to the area is controlled by fencing and is only accessible from the station site.

The disposal site is at an elevation of 719.5 MSL.

Figure 2 is a USGS Topographic Map showing Duke Power property in vicinity of McGuire Nuclear Station and location of proposed land application site.

The proposed disposal site is approximately 600 ft. long and 450 ft, wide and is used for deposition of soil removed during construction activities at McGuire Nuclear Station.

McGuire FSAR Figures 2.3.2-1 through 2.3.2-3 illustrate the topography in some detail from within 1 mile to within 50 miles of the site.

There will be no im-pact on topography in this area by the proposed method of disposal.

5.1.2 Geology The ground surface residual soil consists of a variable thickness of soil underlain by partially weathered rock.

The residual soils primarily are silty sands or sandy silty clay.

The four major rock types appearing at the site are dark green meta gabbro, light gray fine to medium grained granite, black and white fine grained diorite, and black and 3

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3 white coarse grained diorite.

The fill sails are general fine sandy silts and silty sands which include clay layers of low to moderate plasticity.

For more geological information, see the McGuire FSAR, Volume 1, Section 2.5.1.

There will be no impact on geology in this area by the proposed method of disposal.

5.2 Area Characteristics 5.2.1 Meteorology Synoptic features during winter effect rather frequent alter-nation between mild and cool periods with occasional outbreaks of cold air.

Such intrusions of cold air, however, are modified in the crossing and descent of the Appalachian Moun-tains.

Summers, noted for their greater persistence in flow pattern, experience fairly constant trajectories from the south and southwest with advection of maritime tropical air.

Wintertime precipitation occurs primarily in connection with migratory low pressure systems.

Recurrence and areal distri-bution, therefore, are reasonably uniform.

Summer rains on the contrary are associated more with showers and thunder-showers of the air mass variety, occasioned by intense and uneven heating of the earth's surface.

Severe weather, although infrequent, is most likely from March-October.

During this season wind, water and hail damage can result from the thunderstorm, tornado and tropical storm (or hurricane).

There will be no impact on meteorology in this area by the proposed method of disposal.

For more meteorological infor-

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mation, see the McGuire FSAR, Volume 1, Section 2.3.

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5.2.2 Hydrology The hydrological characteristics in the site vicinity are detailed in the McGuire FSAR, Volume 1, Section 2.4.

There will be no impact on hydrology in this area by the proposed j

method of disposal.

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I 5.3 Water Usage 5.3.1 Ground Water Usage j

The plant site lies within the groundwater region known as the Charlotte area, which is' part of the Piedmont Ground-i water Province.

Groundwater in this area is derived entirely from local precipitation.

The surface materials in many locations are relatively impermeable with the result that only 10 to 15 inches of the average 43 inches of precipita-tion percolates to the water table.

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Groundwater is contained in the pores that occur in the weathered material (residual soil-saprolite) above the rela-tively unweathered rock and in the fractures in the igneous 7

and metamorphic rock.

Although generally the depth to the water table depends on climate, topography and rock type, in 1

the Charlotte area the depth depends primarily on topography and rock weathering because there is little variation in the hydrologic properties of rock types within the area.

The i

water table varies from ground surface elevation in valleys to more than 100 feet below the surface on sharply rising hills.

The groundwater level normally declines during the late spring, summer and early fall months as a result of evap-oration and transpiration by plants, and, in the fall, when rainfall is low. The groundwater level rises in the late fall and winter when the evaporation potential is reduced.

The nearest major user of groundwater for public use is in Cornelius, located approximately six miles northeast of the plant.

The nearest industrial user of surface water for human consumption is located approximately 17.8 river miles downstream of the plant.

The Charlotte Municipal Water Intake is located 11.2 river miles downstream of the plant.

For more information on ground water usage, see the McGuire FSAR, Volume 1, Section 2.4.13.

There will be no impact on ground water usage by the proposed method of disposal.

5.3.2 Surface Water Usage Subsurface water is typical of Piedmont area.

The top of the zone of saturation, or water table, follows the topography, but is deeper in the uplands and more shallow in valley bottoms.

It migrates through the pores of the weathered rock, where the feldspars have disintegrated and left inter-sticial spaces between the quartz grains.

Additional water is contained in the deeper fractures and joints below the sound rock line.

The water table is not stationary, but fluctuates continually as a reflection seasonal precipitation.

Shallow dug wells are supplied from surface deposits or from the upper decomposed parts of the bedrock.

Many drilled wells of moderate depth are supplied from joints in the crystalline rocks.

Figure 3 indicates the locations of existing drinking wells in the vicinity of McGuire Nuclear Station.

For more information on surface water usage, see McGuire FSAR, Volume 1, Section 2.4.13.

There will be no impact on surface water usage by the proposed method of disposal.

j 5.4 Nearby Facilities Military and transportation facilities are nearly non existent and only a few industrial facilities are located in the vicinity of McGuire.

The few facilities that do exist have no effect on the j

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McGuire Nuclear Station nor will McGuire Nuclear Station have any effect on the nearby facilities.

For more information, see the McGuire FSAR, Volume 1, Section 2.2.

There will be no impact on nearby facilities by the proposed method of disposal.

5.5 Radiological Impact he annual dose rate to the total body for a person continuously (ccupying the area is estimated to be 0.5 mrem /yr at the center and 0.25 mrem /yr at the boundary of the disposal site.

After one year the total dose at the center will be 0.3 mrem /yr.

For a worker spending 2000 hr/yr in the area, the estimated whole body dose would be 0.1 mrem /yr.

Actual doses to any member of the public are antici-pated to be much lower due to infrequent occupancy.

Detail calcu-lations of annual dose rate estimation are included in Appendix 2.

6.0 Radiation Protection The operational procedure to minimize the risk of unexpected or hazardous exposures will follow the guidelines provided by System Health Physics Manual and station directivet on radiation exposure control and radio-active material control.

All radioactive-waste release and disposal operations will be performed under the technical guidance and review of the Station Health Physicist.

7.0 Evaluation of Overall Benefit This sludge (10,000 ft3), if packaged and disposed of as radioactive waste, will cost approximately $750,000 without solidification, and will cost more than 1.14 million dollars if solidification is required depend-ing on radioactive waste packaging and waste form requirements.

The ac-tual burial space will be more than 12,000 ft3 in licensed radioactive waste burial site.

Considering the generation rate of this type of waste (8,500 to 13,500 f t3 per year), the total cost saving could range from

$620,000 to 1.5 million dollars per year and save burial site space of 10,000 to 15,000 cubic feet per year.

The annual dose rate for both the public and workers is much less than 1 mrem /yr assuming that they continu-ously occupy the proposed disposal site.

Appendix:

(1) Water Treatment Residue Sample Analysis Results (2) Annual Dose Rate Estimations 6

Figure 1.

Layout of McGuire Nuclear Station Conventional Wastewater Treatment System, Showing Location of Proposed Land Application Site 7

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APPENDIX 1 Water Treatment Residue Sample Analysis Results 13

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CCUIRE DATE: 30-MAY-84 17:03:28

FWHM(1332) 2.639 3 RESET TIME (LIVE) :

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SENSITIVITY:

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JETECTOR: C GELI 1669

LIBRARY:NUCL. MASTER

ALIB DATE

21-MAY-84 18:18:42

ENERGY TOLERANCE:

1.500KV (EV/CHNL:

0.5000634

HALF LIFE RATIO:

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ENERGY WINDOW 24.97 TO 2025.51 PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC */. ERR FIT 1

0 107.48 23.

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4.63 214.98 206 17 3.91E-02 68.9 2

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1.49 2346.81 2332 20 1.66E-02 33.8 10 0 1332.C4 18.

4 2.42 2663.96 2655 16 3.00E-02 28.3 PEAK SEARCH COMPLETED (REV 11)

1UCLIDE LINE ACTIVITY REPORT PAGE 1

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0.000E O

608.19 39.

15.

2.90 4.470E-01 4.047E -6 9.011E -7 ACTIVATION PRODUCT 1 SIGMA IUCLIDE SBHR ENERGY AREA BKGND

/. AB N

%EFF UCI / UNIT ERROR 20-58 AP G10.75 27.

40.

99.50*

3.352E-01 1.035E -7 3.989E -8 863.94 0.

O.

0.70 0.000E-01 0.000E O

0.000E O

1674.73 0.

O.

0.50 0.000E-01 0.000E O

0.000E O

20-60 AP 1173.21 10.

1.

99.90 2.500E-01 5.129E -8 1.735E -8 1332.46 18.

4.

100.00*

2.252E-01 1.025E -7 2.914E -8 P-239 AP 99.55 0.

O.

15.00 0.000E-01 0.000E O

0.000E 0

103.76 0.

O.

24.00 0.000E-01 0.000E O

0.000E O

106.13 23.

119.

22.70*

9.927E-01 1.359E -7 9.365E -8 117.00 0.

O.

11.30 0.000E-01 0.000E O

0.000E O

277.60 0.

O.

14.10 0.000E-01 0.000E O

0.000E O

ISSION PRODUCT 1 SIGMA 9UCL1DE SBHR ENERGY AREA BKGND

%ABN Y.EFF UCI / UNIT ERROR 3A-143 FP 423.81 6.

41.

2.50*

6.112E-01 4.721E -7 7.926E -7 537.32 0.

O.

20.00 0.000E-01 0.000E O

0.000E O

4ATURAL PRODUCT 1 SIGMA 9UCLIDE SBHR ENERGY AREA BKGND

%ABN

%EFF UCI / UNIT ERROR 7B-214 NP 295.17 45.

88.

19.20 7.875E-01 2.247E -6 7.408E -7 351.90 45.

63.

37.10*

7.010E-01 1.312E -6 3.801E -7 3I-214 NP 609.32 39.

15.

46.10 4.470E-01 2.646E -6 5.614E -7 1120.28 0.

O.

15.00*

0.000E-01 0.000E O

0.000E O

1764.51 0.

O.

15.90 0.000E-01 0.000E O

0.000E O

.p caJCLICE [DENTIFICAT(CN

-3 Y 3 tim tMEV S/S9>

.ONKNOWN,LINE REPORT PAGE 2

S SN!

PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC ". ERR

%EFF 2. 2L-188. 9 2 0.--

163 6._S'4 T76.-38---363--26--3. ??E-93-32rG-1. i 1 C OC k

-8 3 1171.54 18.

1.

1.49 2342.65 2332 20 2.92E-02 25.4 2.50E-01 Gig i

LINES NOT MEETING

SUMMARY

CRITERIA

^

5 4 RR NUCLIDE ENERGY HLFE DECAY UCI / UNIT ABNDIFF FAILED 1 NP-239 106.13 2.36D 1.014E O

1.359E -7 26.06%

ABN j

5 BA-140 423.81 12.79D 1.003E O

4.721E -7' 11.11%

ABN i

6 XE-135 608.19 9.08H 1.091E O

4.247E -6 3.12%

ABN 6 BI-214 609.32 19.90M 1.081E 1

2.646E -6 59.87%

ABN i

r I

i t

4' i

b

-l 1

It f

r i

L i

4 1 '

s f'

h t-4 i

I

}

ii i

1 A,

[

e s

.4

)

.---m.-.-

_, _ _ ~,. _ _, _, _

._,._._.,-(_,_____.-,___,___...._,_,m.m-_.- _, _.,.. _ _ _.. _,,....., _, -,.. _ -.. -. _ - -, _.. _. - -

w-

[lVCLIDE IDEr4TIFICATION SYSTEM ( REVS 5 / t)0)

PAGE 3

c1p I i

~

!3UMMARY.0F NUCLIDE ACTIVITY

\\ v

(,,

rOTAL LINES.IN SPECTRUM

'10.'

.INdS NOT LISTED IN' LIBRARY 2

(DENTIFIED-IN

SUMMARY

REPORT

, 5; 50,.00%

t }

4CTIVATION PRODUCT 1

1-SIGMA s

!JUCLIDE SBHR HLIFE

DECAY, UCI / UNIT ERROR

% ERR

'20-58' AP 70.80D 1.000 q 1.035E -7 3.989E -8 38.55 20-60 AP 5.27Y.

.1.000 ~ 1.028E -7 2.914E -8 28.34

.)

i e

ii e y

NATURAL PRODUCT SBHR'/

1-SIGMA HLIFE DECAY UCI / UNIT ERROR

/. ERR 10CLIDE 3DB-214 NP 26.80M 2.155 1.312E -6 3.801E -7 28.97

\\

.i 3

l 1

i r A

s e

8 t

w b

t i

/

1

A, N

b',

4 y

l ; (_.y ?,

f i

?

9 L

i t

?.

l

..j.

t U

p

(:

i

~

m b

o

} l1' i

I i

L

~

<**oooo*o*oo*oooo 30-MAY-84 17:09:14

- - - - oc* coco ***o occ.*ooooooooooooooooooooooooooooooooooooooooooo*oooooooooooo*o AC IHP'SCUDGE C6 WILSON 3 AMPLE'DATE:

30-MAY-84 16:00:00 3 AMPLE IDENTIFICATION:

84-10971 Suqle.1Y 1 TYPE OF SAMPLE:

C/ SLUDGE I

3 AMPLE QUANTITY:

3500.000 UNITS:

ML 3 AMPLE GEOMETRY:

MARINELLI IFFICIENCY FILE NAME:

DEFF.D3500M,,

.****ooo*******************************************************

4CQUIRE DATE: 30-MAY-84 16:59:03

FWHM(1332) 2.103 3 RESET TIME (LIVE):

600. SEC

SENSITIVITY:

3.900 ILAPSED REAL TIME:

600. SEC

SHAPE PARAMETER : 15.0 %

ELAPSED LIVE TIME:

600. SEC

NBR ITERATIONS:

10.

+t************************************************************

OETECTOR: D-GEM 23-P-67WB

LIBRARY:NUCL. MASTER 2ALIB DATE:

25-MAY-84 17:33:58

ENERGY TOLERANCE:

1.500KV (EV/CHNL:

0.4997780

HALF LIFE RATIO:

8.00

.JFFSET:

0.3698110 KEV

ABUNDANCE LIMIT:

80.00Y.

2.

COEFF. :

-1.322E-08 KEV /C**2

ooooooo*******************************************************

4 DEAD TIME =

0.00 %

REVIEWED BY:

+*********************************************************

ENERGY WINDOW 25.36 TO 2024.25 PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC /. ERR F'. T 1

0 240.27 43.

86.

3.86 480.01 470 18 7.08E-02 34.4 2

0 295.60 56.

56.

1.74 590.74 585 32 9.39E-02 23.0 3

0 351.81 66.

28.

1.32 703.20 696 14 1.10E-01 16.7 4

0 511.05 20.

14.

2.02 1021.84 1017 18 3.30E-02 34.6 l

5 0

609.29 78.

7.

1.85 1218.41 1210 26 1.30E-01 12s2 l

6 0

810.82 8.

39.

0.73 1621.69 1613 26 1.33E-02 ****

I 7

0 1173.21 16.

7.

1.45 2346.88 2340 13 2.67E-02 33.7 l

8 0 1332.93 12.

O.

1.10 2666.50 2661 13 2.00E-02 28.9 9

0 1461.11 16.

O.

1.60 2923.00 2918 16 2.67E-02 25.0 PEAK SEARCH COMPLETED (REV 11) l

uCLIDE IDtiu f 6 4 4. - v. i o r a

.:.1 s e.. iM

UCLIDE LINE ACTIVITY REPORT PAGE 1

602 gn FISSION GAS 1 SIGMA

.UCLIDE SBHR ENERGY AREA BKGND

%ABN

%EFF UCI / UNIT ERROR E-135 FG 249.79 0.

O.

89.90*

0.000E-01 0.000E O

0.000E O

608.19 78.

7.

2.90 5.680E-01 6.615E -6 8.088E -7

CTIVATION PRODUCT 1 SIGMA UCLIDE SBHR ENERGY AREA BKGND

%ABN

%EFF UCI / UNIT ERROR lO-58 AP 810.75 8.

39.

99.50*

4.445E-01 2.329E -8 2.700E -8 863.94 0.

O.

0.70 0.000E-01 0.000E O

0.000E O

1674.73 0.

O.

0.50 0.000E-01 0.000E O

0.000E O

'0-60 AP 1173.21 16.

7.

99.90 3.402E-01 6.058E -8 2.039E -8 1332.46 12.

C.

100.00*

3.039E-01 5.082E -8 1.467E -8 iALOGEN FISSION PRODUCT i

i SIGMA

!UCLIDE SBHR ENERGY AREA BKGND

/.ABN

/.EFF UCI / UNIT ERROR

-132 HFP 505.90 0.

O.

5.00 0.000E-01 0.000E O

0.000E O

522.65 0.

O.

16.10 0.000E-01 0.000E O

0.000E O

630.22 0.

O.

13.70 0.000E-01 0.000E O

0.000E O

667.69 0.

O.

98.70 0.000E-01 0.000E O

0.000E O

671.60 0.

O.

5.20 0.000E-01 0.000E O

0.000E O

772.60 0.

O.

76.20*

0.000E-01 0.000E O

0.000E O

812.20 8.

39.

5.60 4.445E-01 5.706E -7 6.614E -7 954.55 O.

O.

18.10 0.000E-01 0.000E O

0.000E O

1398.57 0.

O.

7.10 0.000E-01 0.000E O

0.000E O

ATURAL PRODUCT 1 SIGMA UCLIDE SBHR ENERGY AREA BKGND

%ABN

%EFF UCI / UNIT ERROR

-43 NP 1460.81 16.

O.

10.70*

2.934E-01 6.791E ~7 1.698E -7 B-214 NP 295.17 56.

56.

19.20 1.001E 00 1.971E -6 4.541E -7 351.90 66.

28.

37.10*

8.746E-01 1.36aE -6 2.290E -7 I-214 NP 609.32 78.

7.

46.10 5.680E-01 3.553E ~6 4.344E -7 1120.28 0.

O.

15.00*

0.000E-01 0.000E O

0.000E O

1764.51 0.

O.

15.90 0.0005-01 0.000E O

0.000E O

l l

t i

educt. I DE IDiita r II Ica r ICr4 G v G riiM

( PE.V 5/u0)

M(g pf)

UNHNOWN*LINE REPORT PAGE 2

PK'IT E[JERGY AREA EKGND,FWHM CHANNEL LEFT PW CTS /SEC % ERR

/ EF F 1

0' 240.27 43.

86.

3.86 480.01 470 18 7.08E-02 34.4 1.13E 007&O 4

0 511.05 20.

14.

2.02 1021.84 1017 18 3.30E-02 34.6 6.53E-012mN

_INES NOT MEETING

SUMMARY

CRITERIA PK NUCLIDE ENERGY HLFE DECAY UCI / UNIT ABNDIFF FAILED 5 XE-135 608.19 9.08H 1.085E O

6.615E -6 3.12%

ABN 5 BI-214 609.32 19.90M 9.262E O

3.553E -6 59.87%

ABN

.6 I-132 812.20' 2.30H 1.379E O

5.706E -7 2.28/.

ABN

' 40CLICE A DENTIFICA TION SydTEM thdV 5/ cm

SUMMARY

,OF NUCLIDE ACTIVITY PAGE 3

TOTAL LINES IN SPECTRUM 9

,qjpoph811 2-

_INES NOT LISTED IN LIBRARY 2

I

[DENTIFIED IN

SUMMARY

REPORT 6

66.67%

ACTIVATION PRODUCT 1-SIGMA 1UCLIDE SBHR HLIFE DECAY UCI / UNIT ERROR

% ERR 20-56 RP 70.80D

1. 00io ~2r-329E -S P 7mmF -8 115.S3 U.P.

30-60 AP 5.27Y 1.000 5.082E -8 1.467E -8 28.87 1ATURAL PRODUCT 1-SIGMA 1UCLIDE SBHR HLIFE DECAY UCI / UNIT ERROR

% ERR

(-40 NP *********Y 1.000 6.791E -7 1.698E -7 25.00 39-214 NP 26.80M 2.051 1.368E -6 2.290E -7 16.74

ouple # 2

- - - - +***************+++++++++++**+++++++++++**++++4**++++4*

-+********+******

20-MAY-84 17:06:12

+++***+++++++++4*

n***+#+++++**++***++*++++++****+++*++++*+++++*+++++++++++*+++

'C IHP SLUDGE #7 WILSON 1 AMPLE DATE:

30-MAY-84 16:00:00

AMPLE IDENTIFICATION:

84-10972 "YPE OF SAMPLE:

C/ SLUDGE

AMPLE QUANTITY:

3500.000 UNITS:

ML iAMPLE GEOMETRY:

MARINELLI IFFICIENCY FILE NAME:

AEFF.A3500M,,

>**oco***********************************************+#**+#4+*

1COUIRE DATE: 30-MAY-84 16:56:01

FWHM(1332) 2.176 3 RESET TIME (LIVE):

600. SEC

SENSITIVITY:

4.000 ILAPSED REAL TIME:

601. SEC

SHAPE PARAMETER : 15.0 %

ILAPSED LIVE TIME:

600. SEC

NBR ITERATIONS:

10.

eococoo*******************************************************

DETECTOR: A GELI 1729

LIBRARY:NUCL. MASTER CALIB DATE:

24-MAY-84 18:03:36

ENERGY TOLERANCE:

1.500KV MEV/CHNL:

0.5005288

HALF LIFE RATIO:

8.00 OFFSETS

-0.1135935 KEV

ABUNDANCE LIMIT:

80.00%

-1.962E-07 KEV /C**2.*

0.

COEFF. :

V***.*#*******************************************************

% DEAD TIME =

O.17 %

ftEVIEWED BY:

/

c ENERGY WINDOW 49.94 TO 2038.78 PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC %E33 F r~

1 0

185.53 21.

63.

1.15 370.94 365 11 3.56E-02 57.0 2

6 238.39 28.

23.

1.36 476.59 471 29 4.5??-02 T'. 9 2. 99E en 3

6 241.40 29.

20.

1.24 482.62 471 29 4.923-22 22.5 4

0 295.16 36.

36.

1.14 590.06 5SA le 5.3EE-02 13, 5

0 352.16 69.

17.

1.65 703.99 694 33

1.. :,I-M

. +. -

6 0

582.61 12.

18.

3.83 1164.75 1159 13 1.soI-:1 23 2 7

0 609.63 42.

8.

1.99 1218.78 1214 II I.i i-?1 8

0 811.41 7.

30.

0.90 1622.36 1615 2C 1.* 22 21 a 9

0 1461.40 9.

3.

0.66 2923.29 2913 13 1.?OE-02 12.2 PEAK SEARCH COMPLETED (REV 11)

p eA3

'J C"_ I D E IDENTIFICAi!ON SYSTEM (REV 5/80) d-.. DE L;i4E AC~IVITY REPORT PAGE 1

(1Y5 ION ?.k ;

1 SIGMA NUCLIDE SBHR ENERGY AREA BKGND

%ABN

/.EFF UCI / UNIT ERROR

'E-135 FG 249.79 0.

O.

89.90*

0.000E-01 0.000E O

0.000E O

608.19 42.

8.

2.90 4.533E-01 4.422E -6 7.974E -7 RCTIVATION PRODUCT 1 SIGMA MUCLIDE SBHR ENERGY AREA BKGND

%ABN

/.EFF UCI / UNIT ERROR 20-58 AP 810.75 7.

30.

99.50*

3.535E-01 2.416E -8 2.987E -8 863.94 0.

O.

0.70 0.000E-01 0.000E O

0.000E O

1674.73 0.

O.

0.50 0.000E-01 0.000E O

0.000E O

HALOGEN FISSION PRODUCT 1 SIGMA NUCLIDE SDHR ENERGY AREA BKGND

%ABN

%EF'F UCI / UNIT ERROR I-132 HFP 505.90 0.

O.

5.00 0.000E-01 0.000E O

0.000E O

522.65 O.

O.

16.10 0.000E-01 0.000E O

0.000E O

630.22 0.

O.

13.70 0.000E-01 0.000E O

0.000E O

667.69 0.

O.

98.70 0.000E-01 0.000E O

0.000E O

671.60 0.

O.

5.20 0.000E-01 0.000E O

0.000E O

772.60 0.

O.

76.20*

0.000E-01 0.000E O

0.000E O

812.20 7.

30.

5.60 3.535E-01 5.829E -7 7.208E -7 954.55 O.

O.

18.10 0.000E-01 0.000E O

0.000E O

1398.57 0.

O.

7.10 0.000E-01 0.000E O

0.000E O

NATURAL PRODUCT 1 SIGMA NUCLIDE*SBHR ENERGY AREA BKGND

%ABN

%EFF UCI / UNIT ERROR K-40 NP 1460.81 9.

3.

10.70*

2.196E-01 5.181E -7 2.188E -7 PB-214 NP 295.17 36.

36.

19.20 7.762E-01 1.498E -6 4.336E -7 351.90 69.

17.

37.10*

6.874E-01 1'.671E -6 2.457E -7 BI-214 NP 609.32 42.

8.

46.10 4.533E-01 2.146E -6 3.869E -7 1120.28 0.

O.

15.00*

0.000E-01 0.000E O

0.000E O

1764.51 8.

O.

15.90 0.000E-01 0.000E O

0.000E O

e

+m

-w w.-.

o

$d CNb MUCLIDE IDEtJTIFICATIDi> SYETEM 'REV S/80)

JNKNOWN LINE REPORT PAGE 2

PK E.NEr>2r A REr, n;st,'E F t. 'HM CHANNEL LEFT PW CTS /SEC % ERR MErr

'~

l' C

1 e5. L 21.

62.

1,15 370 W ~365 11-~ 3. 56E-02 57. 0 1.01E CC 2

6 22 ';. I'-

S E..

E2.

1.36.

47E_EQ A71 PA 4. 59E-02 20.34.-63E-A ~

3 6

2,;. 4 P, 25.

26.

1.24 482.62 471 28 4.85E-02 28.5 8.57E-C15c'.

E.

B 582.61 12.

16.

3.83 1164.75 11"o is h-94EJP Mo ? 4._20E-C ' (v.

SINES NOT MEETING

SUMMARY

CRITERIA PK NUCLIDE ENERGY HLFE DECAY UCI / UNIT ABNDIFF FAILED 7 XE-135 608.19 9.08H 1.081E O

4.422E -6 3.12%

ABN 7 BI-214 609.32 19.90M 8.335E O

2.146E -6 59.87%

ABN 8 I-132 812.20 2.30H 1.359E O

5.829E -7 2.28%

ABN t

LYS

~

JCLIDE IDENTIFICATION SYSTEM (REV 5/80)

PAGE 3

lJMMARY OF NUCLIDE ACTIVITY jJTAL LINES IN SPECTRUM 9

INES NOT LISTED IN LIBRARY 4

l0ENTIFIED IN

SUMMARY

CC.

?T 4

44.44%

CTIVATION PRODUCT 1-SIGMA lUCLIDE SBHR HLIFE DECAY UCI / UNIT ERROR

-' E R R C-58 AP 70'.edD 1.000 2.4T5E -8 r?87FB~' 12W ib

~

ATURAL PRODUCT 1-SIGMA LUCLIDE SBHR HLIFE DECAY UCI / UNIT ERROR

% ERR

. NP *********Y 1.000 5.181E -7 2.188E -7 42.23

8B-214 NP 26.80M 1.982 1.671E -6 2.457E -7 14.71 I

c.

i l-i

{

l l

l I

~.e n.cw><,cn wwa,n.<a&>>,w,x,sx,wa,,,,,e,,,,,,,,,,,,,e+,,,,,,n soo,cccacococonoco 30-MAY-84 16:58:42

- - - - o**********

hooosi*oooooo*oooooo*ooooooooooooo*oooo**oooooo***ooo**o*******

4C IHP SLUDGE #8 cS%Mf2 N Y

'3 AMPLE DATE:

30-MAY-84 16:00:00 l3 AMPLE IDENTIFICATION:

84-10973 TYPE OF SAMPLE:

C/ SLUDGE

.3 AMPLE QUANTITY:

3500.000 UNITS:

ML 3 AMPLE GEOMETRY,:

MARINELLI EFFICIENCY FILE NAME:

CEFF.C3500M,,

>*no*no*******************************************************

ACQUIRE DATE: 30-MAY-84 16:45:08

FWHM(1332) 2.639 3 RESET TIME (LIVE):

600. SEC

SENSITIVITY:

3.500 ILAPSED REAL TIME:

600. SEC

SHAPE PARAMETER : 15.0 %

ILAPSED LIVE TIME:

600. SEC

NBR ITERATIONS:

10.

FoWoooo*******************************************************

'3ETECTOR: C GELI 1669

LIBRARY:NUCL. MASTER 2ALIB DATE:

21-MAY-84 18:18:42

ENERGY TOLERANCE:

1.500KV (EV/CHNL:

0.5000634

HALF LIFE RATIO:

8.00

.JFFSET:

-0.0307648 KEV

ABUNDANCE LIMIT:

80.00%

~2.

COEFF. :

1.719E-08 KEV /C**2

too*co********************************************************

'4 DEAD TIME =

0.00 %

REVIEWED BY.

...=.00o....

.#.W.*..*.*.

ENERGY WINDOW 24.97 TO 2025.51 PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR FIT 1

0 295.47 13.

173.

1.67 590.91 581 46 2.23E-02 ****

2 0

352.11 64.

44.

1.94 704.17 695 22 1.07E-01 19.3 3

0 443.90 17.

9.

14.94 887.72 874 35 2.87E-02 34.2 4

0 511.05 12.

38.

3.26 1022.00 1016 15 2.06E-02 75.8 5

3 605.14 21.

12.

2.53 1210.13 1204 37 3.42E-02 32.4 5.61E-01 6

3 609.43 41.

10.

2.43 1218.71 1204 37 6.76E-02 19.2 7

0 1173.20 28.

20.

3.80 2345.98 2334 27 4.60E-02 29.9 8

0 1332.26 34.

4.

3.18 2663.99 2657 16 5.68E-02 19.0 PEAK SEARCH COMPLETED (REV 11)

.sa.,ic;wn

.... e i c..:.r i s.sc -

a,a, 9UC, LID,E,LINE ACT.IVITY REPORT PAGE 1

,a&* 6N

ISSION GAS 1 SIGMA 1UCLIDE SBHR ENERGY AREA BKGND

/.ABN

%EFF UCI / UNIT ERROR

! XE-135 FG 249.79 0.

O.

89.90*

0.000E-01 0.000E O

0.000E O

608.19 41.

10.

2.90 4.467E-01 4.297E -6 8.237E -7 i

4CTIVATION PRODUCT 1 SIGMA

.NUCLIDE SBHR ENERGY AREA BKGND

%ABN

%EFF UCI / UNIT ERROR

CO-60 AP 1173.21 28.

20.

99.90 2.500E-01 1.422E -7 4.252E -8 1332.46 34 4.

100.00*

2.252E-01 1.948E -7 3.708E -8 i

LISSION PRODUCT

~

1 SIGMA

NUCLIDE SBHR ENERGY AREA BKGND

%ABN

%EFF UCI / UNIT ERROR

'CS-134 FP 563.23 0.

O.

8.40 0.000E-01 0.000E O

0.000E O

569.32 0.

O.

15.40 0.000E-01 0.000E O

0.00mE O

604.70 21.

12.

97.60 4.494E-01 6.025E -8 1.955'I -8 795.85 0.

O.

85.40*

0.000E-01 0.000E O

0.000E O

801.93 0.

O.

8.70 0.000E-01 0.000E O

0.000E O

~ NATURAL PRODUCT 1 SIGMA

-NUCLIDE SBHR ENERGY AREA BKGND

%ABN

%EFF UCI / UNIT ERROR QB-214 NP 295.17 13.

173.

19.20 7.896E-01 4.149E -7 5.861E -7 351.90 64.

44.

37.10*

7.005E-01 1.156E -6 2.226E -7

-BI-214 NP 609.32 41.

10.

46.10 4.467E-01 1.446E -6 2.773E -7 1120.28 0.

O.

.5.00*

0.000E-01 0.000E O

0.000E O

1764.51 0.

O.

15.90 0.000E-01 0.000E O

0.000E O

I

tuCLIDE IDENTIFICATION SYSTEA ( eid V 5/30) d

/td'"g e dk N UNKN'OWN LINE REPORT PAGE 2

PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR

%EFF 53 2. B-7E-02-34.2-5.87E-01 EI,[

o w

,*a..,.

17.

9.

14.94 887.72 e/*

4 -0 511.05 19-28.

-3r26---1022 r04-101 C 15-2.06E-02 75 A 5 1 W-a1, - 'INES NOT MEETING

SUMMARY

CRITERIA OK NUCLIDE ENERGY HLFE DECAY UCI / UNIT ABNDIFF FAILED 5 CS-134 604.70 2.06Y 1.000E 0 6.025E -8 45.29% ABN 6 XE-135 608.19 9.08H 1.066E O 4.297E -6 3.12% ABN 6 BI-214 609.32 19.90M 5.704E O 1.446E -6 59.87% ABN .i 1 1^ [. 1 I i 1 i l l l- ['.

,,UCLiLd IDEiJ T IF I CAT I CN S'( S TEM.HEV 5 / 2 0.' /Rd/#p d' 77 h! 3UMMARY CF NUCLIDE ACTIVITY PAGE 3 TOTAL LINES IN~ SPECTRUM 8 -INES NOT LISTED IN LIBRARY 2 IDENTIFIED IN

SUMMARY

REPORT 4 50.00% ACTIVATION PRODUCT 1-SIGMA JUCLIDE SBHR HLIFE DECAY UCI / UNIT ERROR % ERR 20-60 AP 5.27Y 1.000 1.948E -7 3.708E -8 19.03 4ATURAL PRODUCT 1-SIGMA MUCLIDE SBHR HLIFE DECAY UCI / UNIT ERROR % ERR 3D-214 NP 26.80M 1.754 1.156E -6 2.225E -7 19.26 O J i i 4 e

(- f. S )$f , ggf / ~ ^^- 4 + o c o o o m *

m
m * * * * * * * + w -. ~ 4 * + u + + % m+.. +,,,-. ~ + + ~ + e 4 * +

oo*o************* 30-MAY-84 10:22:55 -+-+----*+++++ ' s o o n * +

u + + + + * + + * * + + + + + + -- + n > + - - v + m e. - +, r +. - + - +-- ~. ~ --

AC I HD SLUDGE I 3 AMPLE DATE: 30-MAY-84 _C:CC:00 3 AMPLE IDENTIFICATION: 24-19952 TYPE OF SAMPLE: C/ SLUDGE 3 AMPLE QUANTITY: 3500.000 UNITS: ML -3 AMPLE GEOMETRY: MARI IFFICIENCY FILE NAME: CEFF.C3500M,, +oooo*o*********************************+*****,++***++*+,,*+** ACQUIRE DATE: 30-MAY-84 10:22:43

FWHM(1332) 2.639

PRESET TIME (LIVE):

600. SEC

SENSITIVITY:

3.500 ELAPSED REAL TIME: 601. SEC

SHAPE PARAMETER : 15.0 %

ELAPSED LIVE TIME: 600. SEC

NBR ITERATIONS:

10. noc*ooo******************************************************* , DETECTOR: C GELI 1669

LIBRARY:NUCL. MASTER CALIB DATE:

21-MAY-84 18:18:42

ENERGY TOLERANCE:

1.500KV KEV /CHNL: 0.5000634

HALF LIFE RATIO:

8.00 OFFSET: -0.0307648 KEV

ABUNDANCE LIMIT:

80.00% Q. COEFF. : 1.719E-08 KEV /C**2

ncocooc*******************************************************

i DEAD TIME = 0.17 %

REVIEWED BY:

,4 ( Soooooo*********************************++********++*****+4+** ENERGY WINDOW 24.97 TO 2025.51 PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR FIT 1 0 104.01 17. 264. 7.79 208.06 194 24 2.83E-02 **** 2 0 136.33 18. 52. 1.35 272.68 268 8 2.98E-02 61.8 3 0 186.62 27. 84. 1.57 373.26 365 16 4.46E-02 52.1 4 0 226.00 6, 142. 0.75 45E.00 446 21 9.23E-03 **** 5 0 295.36 46. 67. 1.15 590.70 580 19 7.67E-02 29.1 6 0 251.97 83. 38. 2.13 703.09 696 19 1.38E-01 15.2 7 0 462.04 5. 17. 0.67 924.00 917 17 8.33E-03 ***+ 8 0 477.05 3. 62. 0.29 95a.00 9*3 19 4.32E-03 ***+ 9 0 480.55 3. 13,

3. 70 961.00 961 9 4.35E-03 ++++

10 0 513.55 3. 23. 0.56 1027.00 1023 10 4.54E-03 **** 11 0 536.56 3. 24 0.46 1073.00 '.061 16 5.SSE-03 **** 12 0 609.28 65. 48. 2.30 1213.41 1210 19 1.08E-01 19.6 13 0 911.64 7. 5.

0. 5a 1823.00 1815 11 1.08E-02 64.4 14 0 1460.03 15.

C. '. 71 3919.47 2910 19 2.50E-02 25.3 PEAK SEARCH' COMPLETED (REV 11)

g/e W f-NUCLIDE IDENTIFICATION SYSTEM (REV 5/80) NUCLIDE LINE ACTIVITY REPORT PAGE 1 c:5SION GAS 1 SIGMA NUCLIDE SBHP ENERGY AREA BKGND %ABN %EFF UCI / UNIT ERROR MR-85 FG 513.99 3. 23. 0.40* 5.168E-01 1.697E -6 4.301E -6 XE-135 FG 249.79 0. 9. 89.90* 0.000E-01 0.000E O 0.000E O 608.19 65. 48. 2.90 4.468E-01 6.647E -6 1.300E -6

CTIVATION PRODUCT 1 SIGMA NUCLIDE SBHR ENERGY AREA BKGND

'/.ABN %EFF UCI / UNIT ERROR W-187 AP 479.53 3. 13. 23.40* 5.467E-01 2.662E -8 5.548E -8 685.81 0. O. 29.20 0.000E-01 0.000E O 0.000E O NP-239 AP 99.55 0. O. 15.00 0.000E-01 0.000E O 0.000E O 103.76 17. 264. 24.00 9.665E-01 9.486E -8 1.303E -7 106.13 0. O. 22.70* 0.000E-01 0.000E O 0.000E O 117.00 0. O. 11.30 0.000E-01 0.000E O 0.000E O 277.60 0. O. 14.10 0.000E-01 0.000E O 0.000E O FISSION PRODUCT 1 SIGMA NUCLIDE SBHR ENERGY AREA BKGND %ABN %EFF UCI / UNIT ERROR CS-138 FP 408.98 0. O. 4.70 0.000E-01 0.000E O 0.000E O 462.79 5. 17. 30.70 5.659E-01 6.715E -8 8.387E -8 871.80 0. O. 5.10 0.000E-01 0.000E O 0.000E O 1009.78 0. O. 29.80 .0.000E-01 0.000E O 0.000E O 1435.86 0. O. 76.30* 0.000E-01 0.000E O 0.000E O -3A-140 FP 423.81 0. O. 2.50* 0.000E-01 0.000E O 0.000E O 537.32 3. 24. 20.00 4.980E-01 4.406E -8 9.275E -8 l1ATURAL PRODUCT 1 SIGMA 9UCLIDE SBHR ENERGY AREA BKGND %ABN %EFF UCI / UNIT ERROR t-40 NP 1460.81 15. O. 10.70* 2.085E-01 8.653E -7 2.234E -7 3D-214 NP 295.17 46. 67. 19.20 7.898E-01 7.975E -7 2.319E -7 351.90 83. 38. 37.10* 7.007E-01 8.393E -7 1.275E -7

3I-214 NP 609.32 65.

48. 46.10 4.468E-01 1.055E -6 2.063E -7 1120.28 0. O. 15.00* 0.000E-01 0.000E O 0.000E O 1764.51 O. O. 15.90 0.000E-01 0.000E O 0.000E O l l l l I

ptHfe $ ~ 1UCLIDE IDENTIFICATION SYSTEM (REV 5/80) 'JNKNOWN LINE REPORT PAGE 2 CK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR %EFF 2 0 136.us 18.

52.. ' 1. 3 272.68 268 8 2.98E-02 61.S 1.15hs00 3

0 (86.62 27. 8 4.' 1.57 373.26 365 16 4.4s% 03 02 52.1 1'. 1 2 E ' 0 0 4 0 '226.00 6. L4'2. 0.75 452.00 446 21 9.23E- +++w 9.46E-01 C 8 477.05 3. ' 62. 0.29 4.00 943/ 19 4.32E-03 ++++;5.50E-01 13 0 911.64 6. 0.54 182w 00 1818 11 1.08E-02 64.4 2.96E-01, '_INES NOT MEETING

SUMMARY

CRITERI A PK NUCLIDE ENERGY HLFE DECAY UCI / UNIT ABNDIFF FAILED 1 NP-239 103.76 2.36D 1.006E O 9.486E -8 27.55% ABN 7 CS-138 462.79 32.20M 1.813E O 6.715E -8 20.94% ABN 9 W-187 479.53 23.90H 1.013E O 2.662E -8 44.49% ABN 12 XE-135 608.19 9.08H 1.036E O 6.647E -6 3.12% ABN 12 BI-214 609.32 19.90M 2.613E O 1.055E -6 59.87% ABN f t l l l l L

pfe 4f NUCLIDE IDENTIFICATION SYSTEM (REV 5/80)

SUMMARY

OF NUCLIDE ACTIVITY PAGE 3 TOTAL LINES IN SPECTRUM 14 LINES NOT LISTED IN LIBRARY 5 IDENTIFIED IN

SUMMARY

REPORT 5 35.71/. ) FISSION GAS 1-SIGMA NUCLIDE SBHR HLIFE DECAY UCI / UNIT ERROR % ERR K3 05 m: 10._Z2Y 4r000

1. E'37E =6 4.201E -5 25M2 N O FISSION PRODUCT 1-SIGMA NUCLIDE SBHR HLIFE DECAY UCI / UNIT ERROR

% ERR BA-140 FP 12.79D 1.000

- KEY LINE NOT PRESENT**

NATURAL PRODUCT 1-SIGMA NUCLIDE SBHR HLIFE DECAY UCI / UNIT ERROR % ERR K-43 NP *********Y 1.000 8.653E -7 2.234E -7 25.82 PB-214 NP 26.80M 1.364 8.393E -7 1.275E -7 15.19 m a si si e i

,a t u u ' EL 0 4 ~ 1' X 9SO conoco******************************************************** coo +cc*********** 30-MAY-84 10:49:03 o**oco******************************************************** 'JC I HP SLUDGE II 3 AMPLE DATE: 30-MAY-84 10:00:00 '"MPLE IDENTIFICATION: 84-10953 TYPE OF SAMPLE: C/ SLUDGE 3 AMPLE QUANTITY: 3500.000 UNITS: ML 3 AMPLE GEOMETRY: MARI EFFICIENCY FILE NAME: DEFF.D3500M,, 4*++********************************************************* ACQUIRE DATE: 30-MAY-84 10:38:53

FWHM(1332) 2.103 PRESET TIME (LIVE):

600. SEC

SENSITIVITY:

3.900 3 LAPSED REAL TIME: 600. SEC

SHAPE PARAMETER : 15.0 %

ELAPSED LIVE TIME: 600. SEC

NBR ITERATIONS:

10. OGGGQC******************************************************** 'JETECTOR: D-GEM 23-P-67WB

LIBRARY:NUCL. MASTER 2ALIB DATE:

25-MAY-84 17:33:58

ENERGY TOLERANCE:

1.500KV 'EV/CHNL: 0.4997780

HALF LIFE RATIO:

8.00 3FFSET: 0.3698110 KEV

ABUNDANCE LIMIT:

80.00% L COEFF. : -1.322E-08 KEV /C**2 * + &*Q*O********************************************************* DEAD TIME = 0.00 %

REVIEWED BY:

.....om...........*....#..*....*..#.*.......#.....W...W.**.**. ENERGY WINDOW 25.36 TO 2024.25 PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR FIT 1 0 77.06 31. 304. 0.82 153.46 149 19 5.20E-02 81.0 2 0 185.97 22. 378. 1.00 371.37 368 36 3.70E-02 **** 3 7 238.46 32. 28. 1.24 476.41 468 20 5.34E-02 29.4 1.21E 00 4 7 241.97 25. 20. 1.16 483.42 468 20 4.25E-02 31.7 5 0 295.20 43. 35. 1.27 589.92 586 10 7.11E-02 24.9 6 0 352.09 79. 29. 1.37 703.77 700 13 1.31E-01 14.9 7 5 477.81 36. O. 2.08 955.33 947 37 5.93E-02 16.8 2.08E 00 8 5 486.95 18. O. 2.39 973.62 947 37 3.02E-02 23.5 9 0 511.62 40. 18. 2.44 1022.97 1018 14 6.65E-02 21.7 10 0 582.22 15. 16. 0.53 1164.26 1158 16 2.49E-02 45.9 11 0 609.00 36. 44, 2.04 1217.85 1209 22 6.06E-C2 30.7 12 0 657.91 7. 30. 1.31 1315.72 1311 20 1.24E-02 *+++ 13 G 810.80 54. 10. 1.78 1621.54 1613 20 8.92E-02 16.0 14 0 1120.06 14. O. 1.83 2240.50 2233 17 2.33E-02 26.7 15 0 1173.30 24, 4. 1.08 2347.04 2339 15 4.06E-02 23.2 16 0 1332.74 29. O. 2.14 2666.10 2659 14 4.83E-02 13.6 17 0 1461.08 16. 15. 1.12 2922.95 2916 20 2.72E-02 A1.7 18 0 1764.77 17. 3. 1.94 3530.69 3526 14 2.79E-02 29.1 PEAK SEARCH COMPLETED (REV 11)

4 den E 9f I f l l lUCLIDE IDENTIFICATION SYSTEM (REV 5/80)

UCLIDE LINE ACTIVITY REPORT PAGE 1

] i

ISSION GAS 1 SIGMA

~ 'UCLIDE SBHR ENERGY AREA BKGND %ABN %EFF UCI / UNIT ERROR ,E-135 FG 249.79 0. 3. 89.90* 0.000E-01 0.000E O 0.000E O 608.19 36. 44. 2.90 5.682E-01 3.002E -6 9.210E -7 ICTIVATION PRODUCT 1 SIGMA

1UCLIDE SBHR ENERGY AREA BKGND

%ABN %EFF UCI / UNIT ERROR

D-58 AP 810.75 54.

10. 99.50* 4.445E-01 1.557E -7 2.496E -8 863.94 0. O. 0.70 0.000E-01 0.000E O 0.000E O 1674.73 0. O. 0.50 0.000E-01 0.000E O 0.000E O

O-63 AP 1173.21 24.

4. 99.90 3.402E-01 9.220E -8 2.137E -8 1332.46 29. O. 100.00* 3.039E-01 1.228E -7 2.281E -8 7G-110M AP 446.79 0. O. 3.70 0.000E-01 0.000E O 0.000E O G57.75 7. 30. 94.70 5.341E-01 1.896E -8 2.090E -8 706.67 0. O. 16.40 0.000E-01 0.000E O 0.000E O 744.26 0. O. 4.70 0.000E-01 0.000E O 0.000E O 763.93 0. O. 22.40 0.000E-01 0.000E O 0.000E O 937.48 0. O. 34.40* 0.000E-01 0.000E O 0.000E O 1384.27 0. O. 24.70 0.000E-01 0.000E O 0.000E O 1475.76 0. O. 4.00 0.000E-01 0.000E O 0.000E O 1505.00 0. O. 13.30 0.000E-01 0.000E O 0.000E O 1562.27 0. O. 1.20 0.000E-01 0.000E O 0.000E O 1ALOGEN FISSION PRODUCT 1 SIGMA JUCLIDE SBHR ENERGY AREA BKGND %ABN "EFF UCI / UNIT ERROR (-132 HFP 505.90 0. O. 5.00 0.000E-01 0.000E O 0.000E O 522.65 0. O. 15.10 0.Ct0E-01 0.000E O 0.000E O 630.22 0. O. 13.70 0.000E-01 0.000E O 0.000E O 667.69 0. O. 98.70 0.000E-01 0.000E O 0.000E O 671.60 0, 0,

5. E0 0.000E-01 0.000E O

0.000E O 772.60 0. O. 76.10+ 0.00GE-01 0.000E O 0.000E O '+.+A52-01 3.a48E -6 5.526E -7 812.20 54. '0.

5. 10 954.55 9.

J. 12.10 C."002-01 0.000E O 0.000E O ~ ~ ?, '0'Z'E-01 0.000E O 0.000E O 1398.57 0. J. ISSION PRODUCT 1 SIGMA 1UCLIDE SBHR ENERGY AREA SKGND "G 3 M " E. UCI / UNIT ERROR 13-97 FP 657.92 7. 30. 90.34+ 5.2-12-0; i.732E -8 3.067E -8 NATURAL PRODUCT 1 SIGMA 'NUCLIDE SBHR ENERGY AREA BKGND %ABN %EF: UCI / UNIT ERROR <-40 NP 1460.81 16, 15. 10.70s 2.5342-01 d._;19E -7 2.888E -7 09-214 NP 295.17 43. 35. 19.10 1.00EE 00 8.351E -7 2.203E -7 351.90 79. 29. 37,10* 3.

il-01 9.706E -7 1.443E -7 r

m. 2 gdyl ' E Y b -luCLIDE IDENTIFICATION SYSTEM (REV 5/80) ,iUCLIDE LINE ACTIVITY REPORT PAGE 2 'iATURAL PRODUCT 1 SIGMA 4 .'1UCLIDE SBHR ENERGY AREA BKGND %ABN %EFF UCI / UNIT ERROR l3I-214 NP 609.32 36. 44. 46.10 5.682E-01 8.193E -7 2.514E -7 i-1120.28 14. O. 15.00* 3.510E-01 1.570E -6 4.196E -7 1764.51 17. 3. 15.90 2.454E-01 2.529E -6 7.368E t t l l [ 1 i i a + i I + 4 I l i o I r i t f t I i i I i i r t l t I +

SW GY b NUCLIDE IDENTIFICATION SYSTEM (REV 5/80) .JNKNOWN LINE REPORT PAGE 3 -PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR

/.E F F

-1 0 7-7. 0 6 - 31. -304. - -0. 82 -F5-3740 140 13 C. 20E 81. 0 0. 00E-01 p F 0 - 185.-97 22r- --G78. -1. 00 -- 37-1. -36 8-36 3. 70E-02 **** 1.31E 00 #8 -3 030.40 32. CO. 1_24 4 7 A. 4.1 ': 60 CO-5734E 29. 4 1.13E 00 NF 4 7 241.97 25. 20. 1.16 483.42 468 20 4.25E-02 31.7 1.12E 00fBU 7 5 47-7r84-36 ---0.-2. 08 -- 955. 33__9_47_ 37- -5r93E-02 T6 8-6. 89E-01W F 8 5 486.95 18. O. 2.39 973.62 947 37 3.02E-02 23.5 6.79E-019dl 9 0 5i1.62 40. 18. 2.44 1022.97 1018 14 6.65E-02 21.7 6.53E-01/l* 1m ? --582722-- 15.- 1& C. 53-1.164. 26---1158-16-- 2. 49E 45. 9 5. 89E-01 NF l LINES NOT MEETING

SUMMARY

CRITERIA PK NUCLIDE ENERGY HLFE DECAY UCI / UNIT ABNDIFF FAILED 11 XE-135 608.19 9.08H 1.057E O 3.002E -6 3.12% ABN 12 AG-110M 657.75 250.80D 1.000E O 1.896E -8 43.14% ABN 13 I-132 812.20 2.30H 1.246E O 3.448E -6 2.28% ABN i l i l r 0 -_-.,,-,,,.-n, .----,a

m A E4b NUCLIDE IDENTIFICATION SYSTEM (REV 5/80) 3UMMARY OF NUCLIDE ACTIVITY PAGE 4

TOTAL LINES IN SPECTRUM 18

.INES NOT LISTED IN LIBRARY a IDENTIFIED IN

SUMMARY

REPORT 10 55.56/. ACTIVATION PRCDUCT 1-SIGMA ~1UCLIDE SBHR HLIFE DECAY UCI / UNIT ERROR % ERR 30-58 AP 70.80D 1.000 1.557E -7 2.496E -8 16.02 00-60 AP 5.27Y 1.000 1.228E -7 2.281E -8 18.57 ISSION PRODUCT 1-SIGMA NUCLIDE SBHR HLIFE DECAY UCI / UNIT ERROR % ERR Jm-w / F? 72 imM 1 ?mi 2.7CCE -o 3.007E -8 110;24 NP ?JATURAL PRODUCT 1-SIGMA NUCLIDE SBHR HLIFE DECAY UCI / UNIT ERROR % ERR -40 NP *********Y 1.000 6.919E -7 2.888E -7 41.74 3B-214 NP 26.80M 1.635 9.706E -7 1.443E -7 14.87 3I-214 NP 19.90M 1.938 1.570E -6 4.'196E -7 26.73 I j t i l

- - - +*****+******

30-MAY-84 17:22: 42 o*s++*++++**+*+*+**++++sr+++++r*+++n++++++*+++**++++++e*++++* p gyg (L 1# )I WC IHP SLUDGE 03 WILSON q SAMPL8E DATE: 30-MAY-84 16:00:00 SAMPLE IDENTIFICATION: 84-10352 TYPE OF SAMPLE: C/SLUD3E . SAMPLE QUANTITY: 3500.00: UNITE: ML SAMPLE GEOMETRY: MARINE _L: EFFICIENCY FILE NAME: DEFC.D2500% oo0ce****************++++++++-++++++++++-+++++++**+++++******* c > ACQUIRE DATE: 30-MAY-84 17.2;Di FW# ;.201) 2.103 + PRESET TIME (LIVE): v2C EE: 4 EENE: IU~~ 3.900 ELAPSED REAL TIME: 60c. EE; & ErARE 0;RCMETER : 15.0 % ELAPSED LIVE TIME:

.. EET

+ NBE ITEPrTIONS: 10. 4 0c*o************+++++++++-++++++++++++++++++++++++************ 5 lETECTOR: D-GEM 23-P-67WB

LIBRARY:NUCL. MASTER SALIB DATE:

25-MAY-04 17:30:58 + ENEROY TOLERANCE: 1.500KV MEV/CHNL: 0.49977LO + HALF LIFE RATIO: 8.00 5FFSET: 0.3698110 KEV + ABUNDANCE LIMIT: 80.00% 2% COEFF. : -1.322E-08 KEV /C**2 + 00000a*****++***++++++++++++*+++++r+*++++++++*+************+*+ 0 DEAD TIME = 0.00 /.

REVIEWED BY:

ocooooo******************************************** ENERGY WINDOW 25.36 TO 2024.25 PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR FIT 1 0 92.06 17. 92. 1.51 183.47 180 9 2.76E-02 85.6 2 0 186.25 34. 156. 0.92 371.92 365 24 5.59E-02 55.4 3 0 234.26 7. 58. 0.59 468.00 463 10 1.20E-02 **** 4 4 238.82 25. 24. 1.18 477.12 473 21 4.12E-02 34.3 3.30E 00 5 4 242.06 35. 29. 1.38 483.60 473 21 5.83E-02 27.5 6 0 294.98 98. 14. 1.74 589.50 582 14 1.63E-01 11.5 7 0 352.35 100. 30. 1.61 704.29 699 24 1.67E-01 12.6 8 0 386.47 30. 13. 8.06 772.57 761 26 5.00E-02 24.9 9 0 582.84 19. 5.

1. 4G 1165.50 1159 18 3.21E-02 27.6 l 10 0

609.54 94. O. 1.88 1218.91 1212 20 1.57E-01 10.3 11 0 810.66 36. 14. 2.21 1621.38 1611 28 6.00E-02 22.2 l 12 0 835.11 7. 7. 0.76 1670.29 1666 9 1.24E-02 61.5 l 13 0 1120.81 5. 11. 0.57 2242.00 2236 11 8.48E-03 **** 114 0 1173.75 11. 24. 3.22 2347.96 2340 19 1.90E-02 67.3 i 15 0 1461.33 26. 3. 1.76 2923.45 2918 14 4.31E-02 22.2 16 0 1764s75 9. O. 0.62 3530.67 3527 10 1.50E-02 33.3 PEAK SEARCH COMDLETED (REV 11) em i t L

o4UCLIDE IDENTIFICATION SYSTEM (HEV 5/80)

ygg g }/

MUCLIDE.LINE ACTIVITY REPORT PAGE 1 ( 4 ~ ISSI.ON GAS 1 SIGMA ' UCLIDE SBHR ENERGY AREA BKGND %ABN %EFF UCI / UNIT ERROR

R-88 FG 165.98 0.

O. 3.10 0.000E-01 0.000E O 0.000E O 196.32 0. O. 26.30* 0.000E-01 0.000E O 0.000E O 362.23 0. O. 2.30 0.000E-01 0.000E O 0.000E O 834.83 7. 7. 13.10 4.329E-01 2.316E -7 1.423E -7 1518.39 0. O. 2.20 0.000E-01 0.000E O 0.000E O 1529.77 0. O. 11.10 0.000E-01 0.000E O 0.000E O 2029.84 0. O. 4.60 0.000E-01 0.000E O 0.000E O 2035.41 0. O. 3.80 0.000E-01 0.000E O 0.000E O (E-133M FG 233.18 7. 58. 10.30* 1.143E 00 8.037E -8 1.230E -7 (E-135 FG 249.79 0. O. 89.90* 0.000E-01 0.000E O 1.000E O 608.19 94. O. 2.90 5.678E-01 8.109E -6 a.364E -7 4CTIVATION PRODUCT 1 SIGMA NUCLIDE SBHR ENERGY AREA BKGND /.ABN /.EFF UCI / UNIT ERROR AN-54 AP 834.83 7. 7. 100.00* 4.329E-01 2.213E -8 1.361E -8 CO-58 AP 810.75 36. 14. 99.50* 4.445E-01 1.048E -7 2.329E -8 863.94 0. O. 0.70 0.000E-01 0.000E O 0.000E O 1674.73 0. O. 0.50 0.000E-01 0.000E O 0.000E O CO-60 AP 1173.21 11. 24. 99.90 3.401E-01 4.316E -8 2.907E -8 1332.46 0. O. 100.00* 0.000E-01 0.000E O 0.000E O NATURAL PRODUCT 1 SIGMA NUCLIDE SBHR ENERGY AREA BKGND %ABN %EFF UCI / UNIT ERROR <-40 NP 1460.81 26. 3. 10.70* 2.833E-01 1.098E -6 2.433E -7 PB-214 NP 295.17 98. 14. 19.20 1.003E 00 4.838E -6 5.5S2E -7 351.90 100. 30. 37.10* 8.736E-01 2.945E -6 3.722E -7 '3I-214 NP 609.32 94. O. 46.10 5.678E-01 6.847E -6 7.062E -7 1120.28 5. 11. 15.00* 3.509E-01 1.844E -6 1.886E -6 1764.51 9. O. 15.90 2.454E-01 4.397E -6 1.466E -6 r l

Nb N b PR PAGE 2 M PK-IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC /. ERR %EFF 1 -92. 17. - - - 92 r- -1.- 51---- 183.- 47 13 0 9 2.76E-02 35 E 1 06E_-GO-p 2 e ts6.25 24-1-56.-C.--92 3 7-1. 9 2 - 3 6

24 5.59E-02 55.4 1.31E 00f)dr 9 --4-23&r82

~ ~ 25. "dU~f.18 477.12-472. 2 1_. 4. 1 2 E - 0 2 _.3 4. 3 1.13E 00 5 ~ 4 242.06 35, 29. 1.38 A83. 30 473 21 5.83E-02 27.5 1.12E00W 8 0-386.47-30. 13.

9. OS 772.57 76i 26 5.00E-02.24 9-8r17E-01 U.t 9

0 582.84 19. 5.

1. M 11.55.50 t139 1e 3.21E-02 27.6 5.88E-0146M

.INES NOT MEETING

SUMMARY

CRITERIA - PK NUCLIDE ENERGY HLFE DECAY UCI / UNIT ABNDIFF FAILED 10:XE-135 608.19 9.08H 1.104E O 8.109E -6 3.12% ABN 12 KR-88 834.83 2.84H 1.371E O 2.316E -7 19.70% ABN 14'CO-60 1173.21 5.27Y 1.000E O 4.316E -8 49.97% ABN t i I l l i l !~ r i

'muMMARY OF NUCLIDE ACTIVITY PAGE 3p td 6$) c irOTAL lit 1ES IN SPECTRUM 16 _INES NOT LISTED IN LIBRARY 6 IDENT.IFIED IN

SUMMARY

REPORT 9 56.25%

ISSION GAS

~ 1-SIGMA

1UCLIDE SBHR HLIFE DECAY UCI / UNIT ERROR

% ERR

(E-- 133M FG

- __2.1SD--1v 007 -8763<t -8 1.230E -7 133. G2 M 1CTIVATION PRODUCT 1-SIGMA 1UCLIDE SBHR HLIFE DECAY UCI / UNIT ERROR % ERR ~

1N-54 AP did.beu i.G00 C.213C

-0

1. 3&1 C O

61. 48 N - -

10-58 AP 70.80D 1.000 1.048E -7 2.329E -8 22.22 1ATURAL PRODUCT 1-SIGMA l1UCLIDE SBHR HLIFE DECAY UCI / UNIT ERROR % ERR

<-43 NP *********Y 1.000 1.098E -6 2.433E -7 22.17 l

'JB-214 NP 26.80M 2.386 2.945E -6 3.722E -7 12.64 1 21^ N" 19.??"

2. 22 ';

1.044C -6 1.OOCE -E 1 C't%.2_,4 N. k-f l i I l 4 r 6 i l0 l 'l ,--m---,--,c--.-,vm,

cosoconocoscoco** 30-MAY-84 17:30:08

- - - - o***o***

+ccaccococooooooooooooooooooco*c*oo*ooooooooooooo**ooooooo*o*o & @k 4C IHP, SLUDGE 04 WILSON r 3 AMPLE DATE: 30-MAY-84 16:00:00 3 AMPLE IDENTIFICATION: 84-10969 TYPE OF SAMPLE: C/ SLUDGE IAMPLE QUANTITY: 3500.000 UNITS: ML ,3 AMPLE GEOMETRY: MARINELLI IFFICIENCY FILE NAME: CEFF.C3500M,, to****o******+************************************************ + 1CGUIRE DATE: 30-MAY-84 17:19:58

FWHM(1332) 2.639 3 RESET TIME (LIVE):

600. SEC

SENSITIVITY:

3.500 ELAPSED REAL TIME: 600. SEC

SHAPE PARAMETER : 15. 0 Y.

ILAPSED LIVE TIME: 600. SEC

NBR ITERATIONS:

10. DETECTOR: C GELI 1669

LIBRARY:NUCL. MASTER 2ALID DATE:

21-MAY-84 18:18:42

ENERGY TOLERANCE:

1.500KV (EV/CHNL: 0.5000634

HALF LIFE RATIO:

8.00 3FFSET: -0.0307648 KEV

ABUNDANCE LIMIT:

80.00/. 3. COEFF. : 1.719E-08 KEV /C**2 * -f*Qo**o******************************************************* 4 DEAD TIME =

0. 00 */.

REVIEWED BY:

+ococoo**************************************** ENERGY WINDOW 24.97 TO 2025.51 PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC Y. ERR FIT 1 0 117.49 7. 135. 0.49 235.00 229 15 1.20E-02 **** 2 3 230.48 26. 37, 2.21 460.95 456 32 4.38E-02 38.1 2.49E 00 3 3 240.35 50. 30. 2.73 480.69 456 32 8.35E-02 21.0 4 0 295.74 61. 48. 1.89 591.45 579 24 1.01E-01 20.6 5 0 351.98 74. 22. 2.09 703.91 698 18 1.23E-01 14.8 6 0 392.03 4. 36. 0.40 784.00 776 16 6.38E-03 **** 7 0 609.33 52. 35. 1.53 1218.51 1207 28 8.72E-02 21.1 8 0 810.93 33. 15. 3.03 1621.63 1612 20 5.42E-02 24.3 PEAK SEARCH COMPLETED (REV 11)

UCLIDE IDENTIFICATION SYSTEM (REV 5/80) UCt. ICE t.INE ACTIVITY REPORT PAGE I 8AM N sd3LON GAS 1 SIGMA UCLICE SEHR ENERGY AREA EKGND %ABN %EFF UCI / UNIT ERROR E-t T5 FG x19. 79 0. O. 89.90* 0.000E-01 0.000E O 0.000E O 608.19 52. 35. 2.90 4.468E-01 5.788E -6 1.224E -6 CTIVATICN PFCDUCT 1 SIGMA UCLIDE SBHR ENERGY AREA BKGND %ABN %EFF UCI / UNIT ERROR 0-S8 AP 810.75 33. 15. 99.50* 3.350E-01 1.257E -7 3.055E -8 863.94 0. O. 0.70 0.000E-01 0.000E O 0.000E O 1674.73 0. O. 0.50 0.000E-01 0.000E O 0.000E O iP-239 AP 99.55 O. O. 15.00 0.000E-01 0.000E O 0.000E O 103.76 0. O. 24.00 0.000E-01 0.000E O 0.000E O 106.13 0. O. 22.70* 0.000E-01 0.000E O 0.000E O 117.00 7. 135. 11.30 1.060E 00 7.869E -8 1.820E -7 ,277.60 0. O. 14.10 0.000E 0.000E O 0.000E O }4ALOGEN FISSION PRODUCT 1 SIGMA JUCLIDE SBHR ENERGY AREA BKGND /.ABN %EFF UCI / UNIT ERROR tI-132 HFP 505.90 0. O. 5.00 0.000E-0I 0.000E O 0.000E O 522.65: 0. O. 16.10 0.000E-01 0.000E O 0.000E O 630.22 0. O. 13.70 0.000E-01 0.000E O 0.000E O 667.69 0. O. 98.70 0.000E-01 0.000E O 0.000E O 671.60 0. O. 5.20 0.000E-01 0.000E O 0.000E O 772.60 0. O. 76.20* 0.000E-01 0.000E O 0.000E O 812.20 33. 15. 5.60 3.350E-01 3.419E -6 8.311E -7 954.55 0. O. 18.10 0.000E-01 0.000E O 0.000E O 1398.57 0. O. 7'. 1 0 0.000E-01 0.000E O 0.000E O ATURAL DRODUCT 1 SIGMA

UCLIDE SBHR ENERGY AREA BKGND

%ABN %EFF UCI / UNIT ERROR G-214 NP 295.17 61. 48. 19.20 7.891E-01 4.636E -6 9.549E -7 351.90 74. 22. 37.10* 7.007E-01 3.280E -6 4.844E -7 31-214 NP 609.32 52. 35. 46.10 4.468E-01 6.272E -6 1.326E -6 1120.28 0. O. 15.00* 0.000E-61. 0.000E O 0.000E O 17G4.51 0. O. 15.90 0.000E-01 0.000E O 0.000E O '[ e 4 9 l 9

. ~.. _ ~ _ NUCLIDE IDENTIFICATION. SYSTEM (REV 5/80) d.//Y !JNKNOWN.LINE REPORT PAGE 2 PK'IT ENERGY-AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR %EFF 2' ~3 280.48 26. -37. 2.21 460.95 456 32 4.38E-02 38.1 9.30E-017 d 3-3 240.35 50. 30. 2.73 480.69 456 32 '8. 35E-02 21. 0 9. 00E-01 negj 4.m0'~ 392.03 -,... 3 6... - - A 7AF-03_n**_6 52E-91 L: ,1, 4. O.40 784.00 776 1A } i. 1/; 3, l = M14ES -NOT MEETING

SUMMARY

CRITERI A l

y-J$

PK-NUCLIDE ENERGY NLFE DECAY UCI / UNIT ABNDIFF FAILED 1 NP-239 117.00 2.36D 1.017E O 7.869E -8 12.97% ABN 7-XE-135 605.'19 !9.08H 1.114E O 5.788E -6 3.'12% ABN i 7 BI-214-60'3.'32 19,90M~ 1. 9 1 9 Ei. 1 6.272E -6 59.87% ABN 8 I-132 812.20 g"2.30Hl 1.532E O 3.419E -6 2.28% ABN i (, 4 t [ / ie f i. b s- .t / 5. e i ! 1 7 , s + r >:, b o, d p* j. F t- \\ A 4 I i t',. j [ ,. ~ ,.}' l I \\., .t - e, lp5 t k 3' j. b i + s' ), i 11 .p 7 / "Y ^ sa t e,! ,e.. ~,,- . - - - -. ~. ~. - - - - -

SUMMARY

OF NUCLIDE ACTIVITY PAGE 3 a puye # P TOT'AL L$NES IN SDECTRUM 8 LINES NOT LISTED IN LIBRARY 3 IDENTIFIED IN

SUMMARY

REPORT 3 37.50% ACTIVATION PRODUCT 1-SIGMA NUCLTDE SBHR HLIFE DECAY UCI / UNIT ERROR % ERR CO-58 AP 70.80D 1.000 1.257E -7 3.055E -8 24.31 NATURAL PRODUCT 1-SIGMA NUCLIDE SBHR HLIFE DECAY UCI / UNIT ERROR /. ERR PB-214 NP 26.80M 2.594 3.280E -6 4.844E -7 14.77

YecYG llcb e }}.' AJ MLH Gs f MINIMUM DETECTABLE ACTIVITY REPORT (REV 10/80) PEAK WIDTH = 2.18 FWHM. CONFIDENCE LEVEL = 4.66. ft)FC /. i MINIMUM ~NUCLIDE BKG ENERGY UCI / UNIT 4R-41 3. 1293.64 6.3413E-08 KR-85 8. 513.99 8.1855E-06

KR-85M 25.

151.18 4.4932E-08 ~KR-87 12. 402.58 1.1609E-07 KR-88 30. 196.32 1.6315E-07 XE-131M 28. 163.93 1.5226E-06 .XE-133 36. 81.00 2.2771E-07

XE-132M 26.

233.18 3.4457E-07 XE-135 15. 249.79 3.3131E-08

XE-135M 7.

526.56 4.2859E-08 XE-138 22. 258.31 2.1275E-06 !I-131 6. 364.48 2.7005E-08 .I-132 3. 772.60 5.0139E-08 'I-133 6. 529.89 3.4402E-08

I-134 9.

595.36 7.6382E-07 'I-135 1. 1260.41 9.4345E-08 SR-91 4. 749.80 1.4739E-07 SR-92 3. 1383.94 6.5105E-08 NA-24 2. 1368.53 3.8291E-08 CR-51 16. 320.08 3.3365E-07 MN-54 7. 834.83 4.6067E-08 MN-56 0. 1810.72 0.0000E-01 CO-57 41. 122.06 4.9839E-08 CC-63 10. 1332.46 7.9905E-08 NI-65 O. 1481.84 0.0000E-01 FE-59 5. 1099.22 8.6529E-08 ZN-65 - 5. 1115.52 9.7329E-08 'ZN-69M 12. 438.63 3.9175E-08 9B-86 2. 1076.63 3.4591E-07 .RB-88 5. 898.03 3.6758E-07 lRB-89 0. 1031.88 0.0000E-01 lZR-95_ 5. 756.74 6.4824E-08 lZR-97 14. 355.39 1.4886E-06 !Y-91M 4. 557.57 6.0745E-08 J/-92 5. 934.50 3.7712E-07 lY-93 23. 266.87 5.5427E-07 lNB-95 6. 765.83 3.9491E-08 lNB-97 8. 657.92 7.2635E-08

MO-99 4.

777.88 7.1785E-07 l TC-99M 25. 140.51 3.7738E-08 MU-103 8. 497.08 3.6955E-08 (RU-106 3. 1050.10 2.4329E-06 l10-108M 8. 614.37 4.1640E-08 AG-110M 5. 937.48 1.2520E-07 lCD-115 9. 492.14 3.3358E-07 l93-122 6. 563.93 4.3660E-08 'SB-124 1. 1691.02 6.3281E-08 3D-125 12. 427.90 1.1733E-07 05-134 S. 795.85 5.5222E-08 1 lCG-136 4. 1048.07 5.2840E-08 -<n,

r f/ f. /$. { PAGE 2 .)EAK WIDTH = 2.18 FWHM. CONFIDENCE LEVEL = 4.66. MINIMUM iUCLIDE BKG ENERGY UCI / UNIT i;S-137 7. 661.65 4.3880E-08 '3-138 1. 1435.86 1.2114E-07 JA-139 2. 1420.50 2.0962E-05 .%- 140 4. 423.81 7.9498E-07 1E-141 35. 145.44 7.2453E-08 ':E-143 26. 293.26

9. 2375E -08

'E-144 28. 133.53 3.0182E-07 .A-140 1. 1596.49 3.1308E-08 J-187 8. 479.53 1.3653E-07 3R-84 1. 881.60 1.6471E-07 - JP-239 28. 106.13 1.8851E-07 IN-115M 20. 336.24 9.5423E-08 TE-131M ' 1. 852.21

8. 6'd10E-08 3I-214 12.

1120.28 4.2904E-06 3R-82 2. 554.32 2.5094E-08 1 I b t' t' d 4 j .,.,-_.._-.._-....m,..

APPENDIX 2 Annual Dose Rate Estimations 14

e APPENDIX 2 ANNUAL DOSE RATE ESTIMATIONS Waste

Description:

McGuire Water Treatment Residues M Average Co-58 Concentration = 1.2E-7 c Average Co-60 Concentration = 1.2E-7 i Total Volume of Waste

400 yard 3 s 1.08E4 ft3 + 3.06E3 cm3 thickness of the source
6 in. = 15.24 cm (assume homogeneous with soil) covering of soil
4 in. = 10.16 cm surface area of source
2E7 cm2 circle of radius = 2528 cm
83 ft.

or square of side = 4481 cm s 147 ft. Source may be approximated by an infinite slab Assumethatsoilmaybeapproximatedbyordinaryconcrete(p=2.35h) -_ K(E) ES 2 A V g [E (big) - E (b34)] I 2 2 2 i=1 Esi D = dose rate (mrem /yr) K(E) = energy flux to dose rate conversion factor (rem - cm2 sec) y 9y E = energy of source photon (Mev/y) S = source strength of volume source of photon with energy E (cm3 sec) y A,og = Taylor-form buildup factor coefficients l 4 p linear attenuation coefficient of source material (cm 1) = s p i * (1 + "i)ps s i = 1 p x) = total optical thickness of the shield b j b3=bi + p t = total optical thickness of the source + shield s p) = linear attenuation coefficient of the j S shield (cm ~ 2) 1

X) = thickness of j S shield (cm) bni = (1 + a )b j n Co-58 E = 0.511 Mev J pCi dis y y S = 1.2E-7 cm3

3.7E4 sec pCi 0.3 dis = 1.332E-3 cm3 - sec y

rem - cm2 - sec K(0.511) = 2.33E-6 hr - Mev A1 = 38.225 A2 = 1-At = -37.225 a1 = -0.14824 2 = -0.10579 a p = 0.204 cm1 s 1 p i = 0.174 cm s 1 p 2 = 0.184 cm s b = px = 0.204 cm 1

10.16 cm = 2.07 i

bit = 1.76 b12 = 1.85 j b =b + p,t = 2.07 + 0.204

15.24 = 5.18 3

i b33 = 4.41 bs2 = 4.63 E (b31) = E (1.76) = 5.23E-2 2 2 E (b31) = E (4.41) = 2.00E-3 2 2 E (bit) - E (b33) = 5.03E-2 2 2 E (b12) = E (1.85) = 4.58E-2 2 2 E (bs2) = E (4.63) = 1.53E-3 i 2 2 E (bt2) - E (bs2) = 4.43E-2 2 2 g = 2.33E-6

0.51
1.332E-3 g38.225
5.03E-2 37.225
4.43E-2]

2 0.174 0.184 2 1

I rem mrem 6 = 1.65E-9 hr = 1.45E-2 yr Co-58 E = 0.810 Mev rem - cm2 - sec K(0.810) = 2.10E-6 hr - Mev pCi dis y y S = 1.2E-7 cm3

3.7E4 sec pCi 0.99 dis = 4.40E-3 cm3 - sec i

y 1 i A = 30.34 1 = -29.34 A2 = 1-A3 ai = -0.10116 a2 = -0.05163 p = 0.165 cm~1 s p i = 0.148 cm-1 s ~1 p 2 = 0.156 cm s -1

10.16 cm = 1.68 i

bi = px = 0.165 cm 2 b = 1.51 it J b12 = 1.59 i l b =bi + p t = 1.68 + 0.165

15.24 = 4.19 3

s bat = 3.77 i b32 = 3.97 { E (b11) = 7.31E-2 2 E (bat) = 4.05E-3 2 E (bti) - E (b31) = 6.91E-2 2 2 E (b12) = 6.38E-2 2 + E (b32) = 3.20E-3 2 E (b12) - E (ba2) = 6.06E-2 2 2 i g = 2.106E-6

0.81
4.40E-3 E.148 6.91E-2 29.34
6.06E-2]

30.34 0 0.156 2 I 1 rem mrem 6 = 1.04E-8 hr = 9.11E-2 yr J i 3

t [ mrem Total Co-58 6 = 1.06E-1 yr -In2*365.25 mrem 1 yr.-decay total Co-58 6 = 0.160*e 70.78 = 2.97 E-3 yr Co-60 E = 1.173 Mev i rem - cm2 - sec K(E) = 1.90E-6 hr - Mev i pCi dis y y S = 1.2E-7 cm3

3.7E4 sec pCi 1 dis = 4.44E-3 cm3 - sec y

A1 = 24.246 i A2 = 1-At = -23.246 l ai = -0.0672 I j - a2 = -0.0139 i p = 0.138 cm 1 s ~1 p i = 0.129 cm s J -1 p 2 = 0.136 cm s ~ 1

10.16 cm = 1.40 bi = px = 0.138 cm bgi = 1.31 1

b z = 1.38 i i l - 1

15.24 cm = 3.50 b =bi + p t = 1.40 + 0.138 cm 3

s t i bat = 3.26 P ba2 = 3.45 l r L (b21) = 9.64E-2 [ A E (bas) = 7.38E-3 j 2 E (bti) - E (bas) = 8.90E-2 i 2 2 E (b 2) = 8.39E-2 2 E (ba2) = 5.80E-3 2 E (bi2) - E (ba2) = 7.81E-2 2 2 i da D = 1. 90E-6

1.173
4. 44E-3 E24.246, 8.90E-2 23.246, 7.81E-2]

2 0.129 0.136 i 4 4 1

t o h 1 t rem mrem 6 = 1.67E-8 hr = 1.47E-1 yr i Co-60 E = 1.332 Mev rem - cm2 - sec K(E) = 1.83E-6 hr - Mev pCi dis y y S = 1.2E-7 cm3

3.7E4 sec pCi 1 dis = 4.44E-3 cm3 - sec y

A1 = 23.059 A2 = 1-At = -22.059 og = -0.0625 a2 = -0.0095 0.130 cm1 = p 3 p 1 = 0.122 cm-1 s p 2 = 0.129 cm-1 s ~1

10.16 cm = 1.32 bi = px = 0.130 cm b

= 1.24 it b12 = 1.31 i bi + p t = 1.32 + 0.130 cm-1

15.24 cm = 3.30 l

b = 3 s b31 = 3.09 t ba2 = 3.27 E (b11) = 1.11E-1 2 E (b31) = 9.42E-3 2 E (bit) - E (bat) = 1.02E-1 2 2 E (bt2) = 9.64E-2 2 E (ba2) = 7.38E-3 2 E (bt2) - E (ba2) = 8.90E-2 2 2 g = 1.83E-6

1.332
4.44E-3 E_23.059 a 0.102 0.12922.059
0.089]

2 0.122 rem mrem 6 = 2.20E-8 hr = 1.93E-1 yr 5 L ~. -

^

o mram Total Co-60 D = 3.4E-1 yr -In2

1 mrem 1 yr. decay total Co-60 6 = 0.34
e 5.26

= 2.98E-1 yr mrem Total 6 = 4.46E-1 yr 6

r s e

== Conclusions:== For dose rate at the ground level center, the source may be approximated by an infinite slab. The waste is spread 6" (15.24 cm) thick with a 4" (10.16 cm) soil covering. Neglecting decay during the year: 1) For continuous exposure: Total Dose Rate (center)

0.5 mrem /yr Total Dose Rate (boundary)
0.25 mrem /yr 2)

After one year the total dose rate at the center will be 0.3 mrem /yr. 3) For 2000 hr/yr continuous exposure: Total Dose Rate s 0.1 mrem /yr 7}}

v t e Letter Sequence Request
TAC:55306, (Open)
Initiation Request, Request Acceptance... Administration Questions Answers Results Approval... Other: ML20100A811
MONTHYEAR1984-06-18 [Table View]

ML20092H507

Text

Dear Mr. Denton:

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Description:

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