ML20056H039

1993-1 Semiannual Effluent Rept

ML20056H039
Person / Time
Site:	Oyster Creek
Issue date:	06/30/1993
From:	J. J. Barton GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C321-93-2238, NUDOCS 9309080118
Download: ML20056H039 (32)

Text

o

.+

... - V GPU Nuclear Corporation  !

.,4 h Q gf Post Office Box 388 Route 9 South Forked River, New Jersey 08731-0386 609 971-4000 -

Wnter's Direct Dial Number: I C321-93-2238 l August 27, 1993  ;

U.S. Nuclear Regulatory Commission ,

Att: Document Control Desk Washington, D.C. 20555 ,

r

Subject:

Oyster Creek Nuclear Generating Station ,

Docket No. 50-219 >

Effluent Release Report Attached is a copy of the Oyster Creek Effluent Release Report for the period covering January,1993 through June,1993. This submittal is made in accordance with 10 CFR .50.36a(a)(2) and our Operating License and Technical Specifications.

If you should have any questions or require furtl'er information, please contact Brenda DeMerchant, OC Licensing Engineer at (609) 971-4642.

Very truly yours,

\ '

L_ad%m '

$(JohnJ.Barton Vice President & Director Oyster Creek j

)

'l JJB/BDEM:jc i Attachment cc: Administrator, Region 1 Senior NRC Resident Inspector Chief, Bureau of Nuclear Engineering N.J. Dept. of Environmental Protection & Energy CN 411 Trenton, New Jersey 08623 01 9309080118.930630 eon ^ Dock osooo259 R PDR fs b

GPU Nuclear Cvp3 ration s a subscary of General Pubhc Utd.t<es Corporation

//I/ l  !

i , . t

, EXECUTIVE SUMNIARY.1993-1 SEMI-ANNUAL RELidSE REPORT l The Semiannual Efiluent Release Repon is submitted to the United States Nuclear Regulatory Conunission (NRC) every six months in accordance with the Oyster Creek Nuclear  ;

Generating Station (OCNGS) Technical Specifications (Tech Specs). It Sununarizes the  !

radioactive paseous and liquid effluents released and solid radioactive wastes shipped from  !

OCNGS.

Attached Tables show that doses based on quantities of radioactive material released were all

{

less than I % of the limits allowed by the OCNGS Tech Specs. Limi:s for the release of  ;

radioactive effluents at OCNGS are based upon offsite exposure to members of the general  !

public. These limits were compared to dose projections calculated using the methodology in  ;

the Offsite Dose Calculation Manual (ODCM). There were no liquid releases from OCNGS  ;

during the period. Solid waste shipments were similar to those of nuclear plants of i comparable type. age and size. Concrete was used for solidification material during the reponing period. The report summarizes the fact that all effluents released were within  !

fedemi regulatory requirements of the OCNGS Technical Specifications. [

i Included is a description of changes made to the Offsite Dose Calcula. ion Manual (ODCM) .

and the Process Control Plan (PCP) during the reponing period. Effluent monitoring  :

instruments that were inoperative as per Technical Specification 3.15 for the reporting period i are also discussed.  ;

' (

J r

4 k AM NGR I t

+

l 1 e i

)

i k

Maxina.sa Of f aite Dose Due to RadionucL tdes in Ef fluents Jan June 1993 r

Tech. Spec. 3.6.J.1 3.6.J.1 3.6.L.1 3.6.L.1 3.6.K 1 3.6.M.1 3.6.K.1 Liquid Dose Air Dose (Cas) Whole (Thyroid) ,

WB Organ Beta Canna Body Organ skin arem mrem arem mrem mrem mrem erem ,

Jan-June Total 0. 00E + 00 0.00E+00 ' 39E-4 9.82E-4 4.42E-4 1.45E-2 6.61E-4  ;

lech. Spec. Limit 3 10 20 10 500 15 3000 8

Fraction of Limit 0.00E+00 0.00E+00 1.7E-5 9.82E 5 8.84E-7 9.67E-4 2.2E-7 i

t b

i i

i 1

Oyster Cntk Nuclear Station 1 1993-1 Semi Annual Effluent Report I i

i Otanges to the Offsite Dose Calculation Manual No changes were made to the ODCM during this time period. I Changes to the Process Control Pla_t! l No changes were made to the PCP during this time period.

Efnuent Monhors Out of Service Greater than 30 Days

[

During the first half of 1993 three instnaments were out of service for longer than 30 days:  !

The Overbcani Discharge Monitor was declared inoperable December 7.1992, and  !

was returned to service March 3,1993. No overboard discharges occurred during the period from December through March when the instniment was out of service.

The Service Water Rad. Monitor was returned to service Febniaiy 16,1993. Daily discharge samples were collected as required while the monitos was out of service i The AOG vent monitor was out of service from November,1992 due to sample tubing .;

leakage. It was returned to service May 21,1993.  :

?

i 3

i j

i e

6 j

q R ADLNGR/13 - i h

I 4

OYSTER CREEK NUCLEAR GENERATING ST,tTION j LIQUID EFFLUENT RELEASES i FIRST AND SECOND QUARTERS 1993 j

t s

Oyster Creek Nuclear Generating Station (OCNGS) policy is to strive for zero liquid  ;

discharge of radioactive material.

i As a result, there were no liquid continuous or batch releases fann OCNGS in the first lialf l of 1993.

l l

s 4

4 k

Q 6

I i'

I l

i 1

i R AITENGkt!2 6 i

i

' +

Effluent and Waste Disposal Supplemental Information f'ACILITY: Oyster Creek Nuclear Generating Station 1

LICENSEE: Owner - Jersey Central Power and Light Company Operator - GPU Nuclear Corporation

)

1.) Regulatory Limits  ;

a.) Fission and Activation Gases

-i Technical Specification 3.6.E.1 '

t The gross radioactivity in noble gases discharged from the main condenser air ejector shall not acced a 0.21/E Ci/sec after the holdup line ,where E is the average gamma encry (Afev per atomic transfonnation). i Technical Specification 3.6_K.1 The dose equivalent rate outside of the EXCLUSION AREA due to radioactive i

noble gas in gaseous effluent shall not exceed 500 mrem / year to the total body or 3000 mrem / year to the skin. ]'

Technical Specification 3.6.L1 '

The air dose outside of the EXCLU3 ION AREA due to noble gas released in gaseous effluent shallnot exceed:

\

5 mrad / calendar quarter due to ganuna radiation, 10 nuad/ calendar quarter due to beta radiation, .{

10 mrad /calendaryear due to ganuna radiation, or 20 mrad /calendaryear due to beta radiation Technical Specification 3.6X1 -,

1

• The annual dose to a AfEAfBER OF THE PUBLIC due to radiation and .\

radioactive materialin effluents from the OCNGS outside of the EXCLUSION AREA shall not exceed 75 miem to his thyroid or 25 macm to his total body or to l

?

, any other organ.

)

l

. m  !

l i

I

b. lodines and Particulates '

. l Technical Specification 3.6.K.2 t 1

77tc dose equivalent rate outside of the EXCLUSION AREA due to if-3,1131, t..

133, and to radioactive materialin paniculates having half-lives of S days or more in l gaseous efpuents shall not exceed 1500 nuem/ year to any body organ a hen the dose t rate due to 11-3, Sr-89, Sr-90, and alpha-emitting radionuclides is averaged over no l.

more than 3 months and the dose rate due to other radionuclides is averaged over no l

more than 31 days.

l t

Technical Specification 3.6.M.1

' 77te dose to a MEMBER OF Tile PUBLICfrom iodine-131, iodine 133, andfrom radionuclides in partiadate fann having half-lives of 8 days or more in gaseous  ;

cffluents, outside of the EXCLUSION AREA shall not exceed 7.5 mrem to any t body organ per calendar quarter or 15 mrem to any body organ per calendaryear.

c. Liquid Effluents i

, Technical Specification 3.6.1.1 i

The concentration of radioactive material, other than noble gases, in liquid efpuent t.

in the discharge canal at the Route 9 bridge shall not exceed the concentrations specified in 10 CFR Part 20, Appendix B, Table 11, Colunm 2.

t Technical Specification 3.6.I.2  !

The concentration of nobic gases dissolved or entrained in liquid efpuent in the discharge canal at the Route 9 bridge shall not exceed 2X10-4 microcuries/ milliliter.

TechnicalSpecipcation 3.6.1.2  !

The dose to a MEMBER OF Tile PUBLIC due to radioactive materialin liquid i efpuents hqond the outside of the EXCLUSION AREA shall not acced:

I.5 nucm to the total body during any calendar quwter.

l 5 mrcm to any body organ during any calendar quaner, 3 nuem to the total body during any calendar year, or i

10 nuem to any body organ during any calendar year.

I i

2.) Maximum Pennissibic Concentrations (MPC) i i

a. Fission and Activation Gases:

Appendix B, Table II, Column 2 of 10 CFR 20

b. Iodines and Particulates:

Appendix B, Table II, Column 2 of 10 CFR 20 1

c. Liquid Effluents: .:

Appendix B, Table II, Column 2 of 10 CFR 20, except for dissolved or entrained noble gases where the lirait is 2 x 10-4 uCi/ml 3.) Measurements and Approximation of Total Radioactivity i

a. Fission and Activation Gases: '

1. Stack De continuous recording of gross activity and the incorporation of isotopic  !

data obtained from a weekly grab sample analyzed using gamma spectroscopy. .

2. Augmented Offgas (AOG) Vent '

i De continuous recording of gross activity and the incorporation of isotopic i data obtained from a weekly grab sample analyzed using gamma  !

spectroscopy.

i

3. Turbine Building Stack and Feedpump Room Vent n

The continuous recording of gross activity and the incorporation of isotopic - >

data obtained from a monthly grab sample analyzed tising gamma spectroscopy. i

b. Iodines I l

1. Stack i

?

Filters are changed twice weekly and analyzed using g:nnma spectroscopy.

2. AOG Vent Filters are changed twice weekly and analyzed using gamma spectroscopy. -!

i t

.i

.c, _ , , _ _ , . - - . , . , . . . , -~ , - - . , _.

., u

P

?

h- .. .  !

3. Turbine Building Stack and Feedpump Room Vent i Filters are changed twice weekly and analyzed using ganuna spectroscopy.

c. Particulates .

1. Stack . i

.t Filters are changed twice weekly and analyzed using a low background' beta -

counter and gamma spectroscopy.

l l

2. AOG Vent  :

Filters are changed twice weekly and analyzed using gamma spectroscopy. '

l

3. Turbine Building Stack and Feedpump Room Vent  ;

Filters are changed twice weekly and analyzed using gamma spectroscopy.

i

d. Liquid Effluents Analysis per batch release using gamma spectrometry with a germanium detector, a low background beta counter, and a liquid scintillation counter. '

i I

i s'

lI s

i l

I i

t 4

. - - . , . , ,. . - , , , - , , . - - - ,n. -

n,. ,---

.- OYSTER CREEK NUCLEAR GENERATING STATION GASEOUS EFFLUENT ELEVATED RELEASES First Quarter 1993 d

FISSION GASES QUANTITY (ci )

KR85M 1.98E+00

, KR87 8.07E+00 XE133 7.36E+00 XE135 1.16E+01 Total Fission Gases Released: 2.90E+01 ci Gamma EBar: 0.342-Mev Average Rate of Release: 3.77E+00 uCi/sec IODINES QUANTITY (ci )

I131 5.87E-03 I132 2.87E-02 1133 6.06E-02 I135 1.06E-01 Total Iodines Released: 2.01E-01 ci Average Rate of Release: 2.61E-02 uCi/sec PARTICULATES QUANTITY (ci )

CRS1 9.90E-05

. MN54 1.24E-05 CO60 2.05E-04 SR89 1.01E-04 SR90 4.65E-06 Y91M 5.02E-02 TC99M 5.01E-04 TE132 4.61E-04 CS137 4.54E-05 CS138 7.81E+00 BA139 2.47E-01 BA140 1.32E-04 LA140 1.43E-04 CE144 2.15E-05 GROSSA 3.78E-06 Total Particulates Released: 8.11E+00 ci Average Rate of Release: 1.05E+00 uCi/sec RADIONUCLIDE QUANTITY-(ci )

H3 3.31E-01 Avg. Rate of Release for H3: 4.31E-02 uCi/sec Quantity of noble gases derived from gross activity.

- OYSTER CREEK NUCLEAR GENERATING STATION [

GASEOUS EFFLUENT GROUND-LEVEL RELEASES First Quarter 1993

[

I

• i FISSION GASES QUANTITY f (ci )  ;

XE133 1.44E-02 4

XE135 3.74E-03 .

i Total Fission Gases Released: 1.81E-02 ci Average Rate of Release: 2.35E-03 uCi/sec .

IODINES QUANTITY (ci ) l 1131 1.70E-07 I133 1.04E-05  ;

Total Iodines Released: 1.05E-05 ci Average Rate of Release: 1.37E-06 uCi/sec  ;

i PARTICULATES QUANTITY (ci ) l SR89 2.53E-06 l 1

Total Particulates Released: 2.53E-06 ci .

Average Rate of Release: 3.29E-07 uCi/sec RADIONUCLIDE QUANTITY i

, (ci )

H3 0.00E+00

\  ;

Avg. Rate of Release for H3: 0.00E+00 uCi/sec j i

• l Quantity of noble gases derived from gr oss activity.  !

1 i

i E

l l

1 I

,...a. _ _ . -

. OYSTER CREEK ITUCLEAR GENERATING STATION GASEOUS EFFLUENT ELEVATED RELEASES Second Quarter 1993 FISSION GASES QUANTITY  :

(ci ) )

KR85M 2.08E+00 l KR87 1.02E+01 j XE135M 9.61E+00  ;

, XE135 1.46E+01 l Total Fission Gases Relcased: 3.65E+01 ci j Gamma EBar: 0.443 Mev .

Average Rate of Release: 4.69E+00 uCi/sec j

, i IODINES QUANTITY  ;

(ci ) ,

I131 1.84E-03 i I133 6.31E-03 i Total Iodines Released: 8.15E-03 ci -

Average Rate of Release: 1.05E-03 uCi/sec i PARTICULATES QUANTITY f (ci )  !

NA24 3.82E-05 CR51 9.80E-05 >

CO60 5.84E-05 l RB89 3.44E-02  ;

SR89 3.90E-04 >

Y91M 2.43E-02 l TC99M 2.64E-03 TE132 7.21E-06 CS138 7.66E-01  ;

BA139 2.61E-01  !

BA140 5.08E-05 i GROSSA 5.91E-07  !

Total Particulates Released: 1.09E+00 ci  !

Average Rate of Release: 1.40E-01 uCi/sec l RADIGNUCLIDE QUANTITY (ci )

H3 1.37E+00 e

, Avg. Rate of Release for H3: 1.76E-01 uCi/sec i

Quantity of noble gases derived from gross activity. .l

. l e

1 1 ]

t

. OYSTER CREEK NUCLEAR GENERATING STATION GASEOUS EFFLUENT GROUND-LEVEL RELEASES i Second Quarter 1993 FISSION GASES QUANTITY i (ci )

Total Fission GaseF Released: 0.00R+00 ci l Average Rate of Release: 0.00E+00 uCi/sec j IODINES QUANTITY  ;

(ci )

• I131 3.00E-06 ,

I133 1.18E-05 Total Iodines Released: 1.48E-05 ci Average Rate of Release: 1.90E-06 uCi/sec PARTICULATES QUANTITY (ci ) l CRS1 4.17E-07  :

MN54 3.97E-07 SR89 1.05E-05 i CS138 4.51E-03 BA139 4.74E-04 -l GROSSA 2.74E-06 Total Particulates Released: 4.99E-03 ci Average Rate of Release: 6.42E-04 uCi/sec j i

RADIONUCLIDE QUANTITY i i

(ci )

H3 0.00E+00 l

Avg. Rate of Release for H3: 0.00E+00 uCi/sec I l

l Quantity of noble gases derived from gross activity.

l

k e

l' Solid Waste Shipped Offsite for Disposal

, During Period From 01/01/93 to 06/30/93 Report Date 8/19/93 3

WASTE STREAM: FILTERS AND DRY ACTIVE WASTE ,

i WASTE VOLUME CURIES  % ERROR (Ci)

CLASS SHIPPED ,

3 3 Ft M i A 170.8 4.83 8.20 25%

B 0 0 0 25%

C 0 0 0 25%

All 170.8 4.83 8.20 25%

b i

1 2611.WAC/5 ,

P 4

9 t

I Estimates of Major Nuclides by Waste Class and Stream with 1% Cutoff 8/19/93 .

I WASTE STREAM: FILTERS AND DRY ACTIVE WASTE ,

(Packaged in HIC) i Waste Nuclide Percent Class Name Abundance Curies A Fe-55 49.02% 4.02 E0  :

Co-60 34.63% 2.84 E0 +

Cs-137 9.67% 7.93 E-1 Mn-54 2.48% 2.03 E-1 Cs-134 1.89% 1.55 E-1  :

Cr-51 1.18% 9.66 E-2  !

Ni-63 0.36% 2.95 E-2 C-14 0 7.30 E-4 i Ni-59 0 2.43 E-3 l Tc-99 0 LLD(6.09E-5 uCi/CC)

I-129 0 LLD(1.89E-4 uCi/CC)

Pu-241 0 7.31 E-3 Cm-242 0 3.3 E-5 ,

H-3 0 4.28 E-4 1 Sr-90 0 6.17 E-3  :

i 5

i

~

l t

i 2611.WAC/6 9

9  !

. l 1

i Solid Waste Shipped Offsite for Disposal During Period 31/01/93 to 06/30/93 ,

Report Date 8/19/93 l I

WASTE STREAM: DRY ACTIVE WASTE SENT TO BURIAL GROUND l

}

Waste Volume Curies  % Error (Ci) l Class Shipped  :

Ft 3 M 3

A 360.2 10.2 3.07 25% l B 0 0 0 25%

f C 0 0 0 25%  ;

I All 360.2 10.2 3.07 25% i l

I

, l l

4 i l

?

o 2611.WAC/9 4

.- i

I

. l i- Estimates of Major Nuclides by Waste Class and Stream  !

with 1% Cutoff j s  ;

8/19/93 l WASTE STREAM: DRY ACTIVE WASTE SENT TO BURIAL GROUND ]

Waste Nuclide Percent  !

Class Name Abundance Curies  !

A Fe-55 52.257% 1.60 E+0 Co-60 32.229% 9.88 E-1 t Cs-137 7.209% 2.21 E-1 i Mn-54 3.582% 1.10 E-1 -;

Cr-51 2.205% 6.76 E-2  ;

Zn-65 1.484% 4.55 E-2  !

Cs-134 1.034% 3.17 E-2 Cm-242 0 0  ;

Pu-241 0 0 I-129 0 0  ;

Tc-99 0 0 .

Sr-90 0 0  !

C-14 0 0 l H-3 0 0 .

Nb-94 0 0 -i Ni-63 0 0  !

Ni-59 0 0  !

l

't I

l l

)

I 2611.WAC/10

• l I

i e

^

Solid Waste Shipped Offsite for Disposal i During Period from 01/1/93 to 06/30/93 l Report Date 8/19/93 P

l l

I WASTE STREAM: DRY ACTIVE WASTE SENT TO A REPROCESSOR WASTE VOLUME CURIES  % ERROR (Ci) l CLASS SHIPPED Ft 3 M 3

t A 15,582 440.97 2.776  : 25%  !

B 0 0 0 -

25%

C 0 0 0 25%  !

All 15,582 440.97 2.776 25% l l

l Note: This material was sent to a Reprocessor for further Volume Reduction prior to !

burial.

4 2611,WAC/11 j l

l

l 1

Estimates of Major Nuclides by Waste Class and Stream l with 1% Cutoff 8/19/93 WASTE STREAM: DRY ACTIVE WASTE SERT TO A REPROCESSOR l

Waste Nuclide Percent I

_ Class Name Abundance Curies A Fe-55 51.30% 1.42 E0 Co-60 31.70% 8.80 E-1 i Cs-137 7.07% 1.963E-1 ,

Mn-54 3.53% 9.8 E-2 Cr-51 2.17% 6.024E-2 '

Zn-65 1.46% 4.053E-2 Cs-134 1.02% 2.832E-2

.! Ni-63 0.36% 9.99 E-3  :

Sr-90 0.06% 1.67 E-3  !

j. Pu-241 0.06% 1.67 E-3 ,

Ni-59 0.02% 5.55 E-4  ;

H-3 0 LLD(1.40E-3 uti/CC)

C-14 0 LLD(1.40E-4 uCi/CC) l Tc-99 0 LLD(1.73E-4 uCi/CC) ,

I-129 0 LLD(2.60E-4 uti/CC) 1 a

s 2611.WAC/12

,,e-- - - - ,.

Solid Waste Shipped Offsite for Disposal During Period 01/01/93 to 06/30/93 Report Date 8/19/93 WASTE STREAM: RESINS. FILTERS SLUDGE Waste Volume Curies  % Error (C1)

Class Shipped

'3 Ft 3 A 2717.0 77.46 2.52 E+2 25%

B 873 b 24.72 4.60 E+2 25%

C 0 0 0 25%

All 3610.5 102.18 7.12 E+2 25%

2611.WC/1 6

.%, e- - -.a. -. 4 ,a. .a 4

l i

Estimates of Major Nuclides by Waste Class and Stream with 1% Cutoff t

t 8/19/93  :

WASTE STREAM: RESINS. FILTERS SLUDGE i

l Waste Nuclide Percent Class Name Abundance Curies ,

A Co-60 44.04% 1.11 E+2 Fe-55 41.30% 1.04 E+2 Cs-137 5.91% 1.49 E+1 Mn-54 3.17% 8.00 EO Co-58 1.71% 4.3 E0 ,

Cr-51 1.46% 3.68 E0 i Cs-134 0.95% 2.4 EO '

Zn-65 0.45% 1.13 E0 i Ni-63 0.433% 1.09 E0 i Sr-90 0.10% 2.3 E-1

• C-14 0.11% 2.71 E-1 Pu-241 0.05% 1.26 E-1 i Hi-59 J.02% 5.61 E-2  :

3 H-3 0.001% 3.61 E-3 i Cm-242 0 5.65 E-4 Tc-99 0 LLD(1.73 E-4 uti/CC) .

1-1c9 0 LLD(2.6 E-4 uti/CC) ,

B I

i i un.waen {

l i

l

I i

Estimates of Major Nuclides by Waste Class and Stream with 1% Cutoff j 8/19/93 WASTE STREAM: RESINS. FILTERS SLUDGE r

i t

r Waste Nuclide Percent  !

i Class Name Abundance Curies l B Co-60 50.86% 2.37 E+2 Fe-55 24.03% 1.12 E+2 l Mn-54 10.06% 4.69 E+1  ;

Cr-51 4.06% 1.89 E+1 i Cs-137 3.88% 1.81 E+1 l Co-58 2.53% 1.18 E+1 l Zn-65 1.92% 8.97 EO Cs-134 1.54% 7.16 EO .

Ni-63 0.37% 1.73 E0 l Sr-90 0.07% 3.35 E-1 C-14 0.06% 2.66 E-1 )

Pu-241 0-.02% 9.08 E-2 Ni-59 0.006% 2.98 E-2 H-3 0 1.1 E-3  ;

Cm-242 0 5.95 E-4  ;

Tc-99 0 LLD(1.73E-4 uCi/CC) }

I-129 0 LLD(2.6E-4 uCi/CC)  ;

[

I I

2611.WAC/3

\

1 Estimates of Major Nuclides by Waste Class and Stream l with 1% Cutoff '

1 8/19/93  :

l WASTE STREAM: RESINS. FILTERS SLUDGE i Waste Nuclide Percent Class Name Abundance Curies All Co-60 48.47% 3.48 E+2 l Fe-55 30.08% 2.16 E+2  !

Mn-54 7.65% 5.49 E+1 l 3.3 E+1 Cs-137 4.60%

Cr-51 3.15% 2.26 E+1 l Co-58 2.24% 1.61 E+1 i Zn-65 1.41% 1.01 E+1 Cs-134 1.33% 9.56 EO  !

Ni-63 0.39% 2.82 EO  !

Sr-90 0.08% 5.65 E-1 C-14 0.075% 5.37 E-1 Pu-241 0.03% 2.17 E-1 Ni-59 0.012% 8.59 E-2 H-3 0.0007% 4.71 E-3  ;

Cm-242 0.0002% 1.16 E-3 $

Tc-99 0 LLD(1.73E-4 uti/CC)

I-129 0 LLD(2.6E-4 uCi/CC) i F

3 9

I f

2611.WAC/4 l

4:  ;

'l l

Solid Waste Shipped Offsite for Disposal l During Period From.01/1/93 to 05/30/93 Report Date 8/19/93 i l

l 1

l WASTE STREAM: IRRADIATED COMPONENTS i WASTE VOLUME CURIES SHIPPED  % ERROR (Ci)

CLASS i 3 3 Ft M ,

i A 118.4 3.35 8.34 25%  :

B 0 0 0.00 E+00 25%

l C 0 0 0.00 E+00 25%

All 118.4 3.35 8.34 25% ,

1 i

)

l l

2611.WAC/7 ,

i

.1 l

• i

)

. 1 1

i i

l Estimates.of Major Nuclides by Waste Class and Stream .

with 1% Cutoff

8/19/93 l 4

WASTE STREAM: IRRADIATED COMPONENTS l I

Waste Nuclide Percent  ;

Class Name Abundance Curies  !

l A Fe-55 38.9 3.24  ;

Co-60 32.3 2.69 Cr-51 24.5 2.04 {

Ni-63 4.3 .358 ,

C-14 0 2.92 E-4  ;

Ni-59 0 2.64 E-3  :

Tc-99 0 1.19 E-8 I-129 N.P. N.P. l

~

Pu-241 0 1.85 E-3 Cm-242 0 2.94 E-7  !

H-3 N.P. N.P. j Sr-90 0 3.07 E-5 -

Cs-137 0 2.37 E-3  !

Nb-94 0 7.85 E-7  !

I i

4 t

i

(

i 2611.WAC/8 3

i

. I

+  :

l Solid Waste Shipped Offsite for Disposal i During Period from 01/1/93 to 06/30/93 l Report Date 8/19/93 i I

1 WASTE STREAM: CONTAMINATED METAL SENT TO REPR00E550R l

)

WASTE VOLUME CURIES  % ERROR (Ci) .I CLASS SHIPPED a Ft 3 M 3

i A 1,917 54.25 3.45 E-1 25%

B 0 0 0 25%

C 0 0 0 25%

)

All 1,917 54.25 3.45 E-1 25%

Note: This material was sent to a Reprocessor for further Volume Reduction prior to -

burial.

i l

l 4

2611.WAC/13

e e

Estimates of Major Nuclides by Waste Class and Stream with 1% Cutoff 8/19/93-WASTE STREAM: CONTAMINATED METAL SENT TO REPROCESSOR Waste Nuclide Percent

";lais Hamg Abundance Curies A Fe-55 51.30% 1.77 E-1 Co-60 31.70% 1.09 E-1 Cs-137 7.07% 2.44 E-2 Mn-54 3.53% 1.22 E-2 Cr-51 2.17% 7.49 E-3 Zn-65 1.46% 5.04 E-3 Cs-134 1.02% 3.52 E-3

Ni-63 0.36% 1.24 E-3 Sr-90 0.06% 2.07 E-4 C-14 0 LLD(1.40E-4 uCi/CC)

Pu-241 0.06% 2.07 E-4 Ni-59 0.02% 6.9 E-5 H-3 0 LLD(1.40E-3 uCi/CC)

Cm-242 0 0 Tc-99 0 LLD(1.73E-4 uC1/CC)

I-129 0 LLD(2.60E-4 uCi/CC) 3 2611.WAC/14

e

'4 Solid Waste Shipped Offsite for Disposal During Period From 01/1/93 to 06/30/93 Report Date 8/19/93 WASTE STREAM: SUM OF ALL CATEGORIES I WASTE VOLUME CURIES  % ERROR (Ci)

CLASS SHIPPED 3

Ft 3 M A 20885.4 ~591.06 275 25%

B 873.5 24.72 460 25%

C 0 0 0 25%

All 21758.9 615.78 735 25%

2611.WAC/15 ,

e l i

l b

Estimates of Major Nuclides by Waste Class and Stream '

with 1% Cutoff 8/19/93  ;

WASTE STREAM: SUM OF ALL CATEGORIES Waste Nuclide Percent Class Name Abundance Curies A Co-60 43.32% 119 E0 Fe-55 41.5 % 114 E0 i Cs-137 5.86% 16.1 E0 Mn-54 3.06% 8.42 E0  :

Cr-El 2.17% 5.95 EO '

Co-58 1.57% 4.3 EO Cs-134 0.95% 2.62 E0 ,

Ni-63 0.54% 1.49 E0  ;

Sr-90 0.087% 2.38 E-1 C-14 0.1% 2.72 E-1 Pu-241 0.05% 1.37 E-1 Ni-59 0.02% 6.18 E-2 H-3 0 4.04 E-3 Cm-242 0 5.98 E-4 '

Tc-99 0 LLD(1.73E-4) ,

1-129 0 LLD(2.6 E-4 uti/CC)  :

Nb-94 0 7.85 E-7 1 I

1 l

l l

l l

2611.WAC/16

e 0

Estimates of Major Nuclides by Waste Class and Stream with 1% Cutoff 8/19/93 WASTE STREAM: SUM OF ALL CATEGORIES Waste Nuclide Percent Class Name Abun_ dance Curies B Co-60 50.86% 2.37 E+2 Fe-55 24.03% 1.12 E+2 Mn-54 10.06% 4.69 E+1 Cr-51 4.06% 1.89 E+1 Cs-137 3.88% 1.81 E+1 Co-58 2.53% 1.18 E+1 Zn-65 1.92% 8.97 E0 Cs-134 1.54% 7.16 E0 Ni-63 0.37% 1.73 E-7 Sr-90 0.07% 3.35 E-7 C-14 0.06% 2.66 E-1 Pu-241 0.02% 9.08 E-2 Ni-59 0.006% 2.98 E-2 H-3 0 1.1 E-3 Cm-242 'O 5.95 E-4 Tc-99 0 LLD(1.73E-4 uCi/CC) 1-129 0 LLD(2.6 E-4 uCi/CC)

Nb-94 0 0 2611.WAC/17

e

. + , .

Estimates of Major Nuclides by Waste Class and Stream  ;

with 1% Cutoff 8/19/93 WASTE STREAM: SUM OF ALL CATEGORIES  ;

Waste Nuclide Percent .

Cla11 Name Abundance Curies -

All Co-60 48.37% 356 Fe-55 30.70% 226 i Cs-137 4.65% 34.2 Mn-54 7.52% 55.32 Cr-51 3.38% 24.85 09-58 2.19% 16.1 l Zn-65 1.22% 8.97 Cs-134 1.33% 9.78 '

Ni-63 0.44% 3.22 Sr-90 0.08% .0573 .

C-14 0.07% .0538 Pu-241 0.03% .228 i Ni-59 0.01% 0.0916 H-3 0.01% 0.0967 i Cm-242 0 0.0012 Tc-99 0 LLD(1.75E-4 uCi/CC) l I-129 0 LLD(2.6 E-4 uCi/CC)

Nb-94 0 7.85 E-7 L

7611.WAC/18

o l e-

.. . . ~ ,

1 l

i l

l SOLID WASTE DISPOSITION

SUMMARY

NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 24 Truck Barnwell, SC 9 Truck Oak Ridge, TN 3 Truck Wampum, PA 0 Truck Richland, WA 0 Truck Beatty, NV 9

2611.WAC/19

,