ML20029B079

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Semiannual Effluent Release Rept 30,Jul-Dec 1990. W/910227 Ltr
ML20029B079
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 12/31/1990
From: Miller D
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9103050391
Download: ML20029B079 (16)
v • d • e


Text

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  • PillLADEl. Pill A ELECTRIC COMPANY E l'l ACll llOl'1DM AIUMIC POWI.R STNrK)N

/ R I) 1. llox 208 ThMlM' Delu, lYnns)lunia 17314 esuu sornm. tun rowin oe tunitv a ("'17) i W7ol4 D. B. Miller, Jr.

VA e Preudent February 27, 1991 Docket Nos. 50-277 .

50 278 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 S')BJECT: Semi Annual Effluent Release Report No. 30 July 1,1990 through December 31,1990 Peach Bottom Atomic Power Station Unit Nos. 2 and 3 Gentlemen:

Enclosed are two copies of the Semi-Annual EfGuent Release Report No. 29, July 1,1990 through December 31,1990 for Peach Bottom Atomic Power Station Unit Nos. 2 and 3.

This report is being submitted in compliance with 10 CFR 50.34 (a) (2) and the Technical Specifications of Operating Licenses DPR-44 and DPR 56, and to fulhil the recluicements of Regulatory Guide 10.1.

During the report period, no revisions were made to the Offsite Dose Calculation Manual (ODCM).

Sincerely, i /

h di- FIT) ,,

DBM/AAF/DPL/MJB: cme Enclosures cc: R.A. Burricelli, Public Service Electric & Gas T.M. Gerusky, Commonwealth of Pennsylvania JJ. Lyash, USNRC Senior Resident Inspector R. McLean, State of Maryland

-T.T. Martin, Administrator, Region I, USNRC ll.C. Schwemm, Atlantic Electric J. Urban, Delmarva Power INPO Records Center iCCIS4 doc r

9103050391 901231 PDR ADOCK 05000277

[*l i

R PDR

PEACH BOTTOM ATOMIC POWER STATION Unit Numbers 2 and 3 Docket Numbers 50-277 and 50-278 SEMI-ANNUAL EFFLUENT ItELEASE ItEPOllT NO. 30 JULY 1,1990 TilllOUGII DECEMBElt 31,1990 l

Submitted to The United States Nuclear Regulatory Commission Pursuant to Facility Operating 1.iccuses DPR-44 and DPR 56

Table of Contents Page No.

I. Introduction 1 II. Tables 1A. Gaseous Effluents - Summation of All Releases 2 IB. Gaseous Efuuents for Release Point - Main Stack 3 1C. Gaseous Efnuents for Release Foint U2 & U3 Roof Vents 5 2A. Liquid Effluents - Summation of All Releases 7

28. Liquid Effluents 8 UI. Classes of Solid Radioactive Waste Shipments 10 IV. Attachments A. Supplemental Information i1 Technical Concurrences: (for accuracy of information) ll Y b-Sr. Engineer RacKvaste

(

Sr. ' Chemist ICC154. doc

t SEMI ANNUAL EFFLUENT ltELEASE ItEPORT JUIN 1,1990 TilROUGli DECEMilER 31,1990 I. INTRODUCTION ,

In accordance with the Unique Reporting Requirements of Technical Specification 6.9.2h (2) applicable during the reporting period, this report summarizes the Efnuent Release Data for Peach Bottom Atomic Power Station Units 2 and 3 for the period July 1,1990 through December 31,1990. The notations E and E are used to denote positive and negative exponents to the base 10.

The release of radioactive materials during the reporting period was within the Technical Specification limits. There were no changes made to the Off Site Dose Calculation Manual (ODCM) during the reporting period.

There were no known urplanned releases of liquid radioactive material.

1 1CCi.Rdoe l

1

EFFLUENT & WASTE DISPOSAL SEMI- ANNUAL REPORT (7/1/90 - 12/31/90)

Table 1 A Page 1 of 1 Gascous Effluents - Summation of All Releases Quarter Quarter l Est. Error

_ _ _ . _ .__._ U ni t s . t_ 3_ _4_j_ Tot _al 96_

L.A. Fission & activation gasses . . - . .

..,--__i

1. Total release Ci 5.27 E3_ __2 JOS E..i 54.0 EO j

{

2. Average release rate for period LpCi/stec _6.70E2 , _ 2.61 E2 _ ._

! I

3. Gamma Air Dose . _M__ill_ ira d 3.06 E - 2_....__6.9._7 E - 2 _ . _ _ . . _

Percent of Technical Specification ci _._ 3.06E- 1 . 6.97 E- 1__ _ _y

4. Beta Air Dose ._

Millitud 4.40E ;_24.8.18 E_- . 2 , _ _ _

Percent of Technical Specification _j_ 9F _j_2.20E - 1j _4J2E- 1 j___j B lodines . .

1. Totat iodine - 131 _ L_ Ci ,,_ g .37 6 E - 3 4.00 E - 3._ 61.0 E0._
2. Average release rate for period _p_Ci/sec_ _M O E - .4 _ _ 5.09 E - 4 , .
3. Critical Organ dose ,

_ ),lill_ ire.m_,. 145E- 2 ,_ 4.5S E - 2,_

Percent of Technical Specification I 9e I 1.63E- 1 3.05 E - ! , _ _ _ _

C. Particulates ~

' ~ ~

~TParticulates 4iih~hiili hves greater tisiR '- - ~ ~~i-~-~~

days (includes Alpha and Strontium 89 -901 Ci 1.86 E- 3. _1.0S E- 3_! 61.0 EO

2. Average release rate for period pCi/sec 2.37 E-4 1.37E-4 l
3. Gross Alpha Radioactivity ___._Ci_ _ 5.88 E- 5__2.31 E- 5 [ _

D. Tritium r

1. Total release T 5 ; .T_4_._.i_ _li.E._i ...i __. _ 94.0 8.29E0 E.0

_q l 2. Average release rate forperiod [_pCi!sec [_121E0E 1.06E0 j 2

EFFLUENT & WASTE DISPOSAL SEht!- ANNU AL REPORT (7/1/90 - 12/31NO)

Table IB Page 1 of 2 Oascous Effluents For Release Point - Main Stack Continuous hiode ! Batch.hiode_ _

Quarter Quarter Quarter -

rier Nuclides Released l Units ,

3 4_ __3_ __4_.

l 1. Fission gasses

[ Krypton _- 85ht Ci 2.46E2 4.44 El _ 0.00 EO _ _ 0.00 E0 ,

__ Krypton - 87 Ci 1.36E2 8.16El 0.00 EO _ 0.00 Ijo . __

Krypton - SS Ci 1.64 E2 9.09El 0.00_E0_ _0 00 EO .

Xenon - 133 Ci 4.18E3 1.11 E3 0.00 EO 0.00 E0 t

._ Xenon - 135 Ci 1.04 E2 3.03E2

_ 0 00 E0_0.00_E0 J Xenon - 135h! Ci 5.13El 7.92 El Olk) EO 0.00 E0 }

Xenon - 138 Ci 7.55E0 3.8SE1 0.00 EO 0.00 EO I

[_ Xenon - 133ht Ci 5.0SE1 0 00E0 0.00 EO 0.00 E0 i Xenon - 131hi Ci 4.92El 3.30El 0.00 EO 0.00 EO Unidentificd Ci 0.00E0 _

0.00E0 ODO EO 0.00 EO Total for Period Ci 4.99E3 1.78E3 0110 E0 LO.00 E0 l

L 2.lodines lodine - 131 Ci 4.12 E-3 8.43E-4 0.00 EO 0.00 E0 lodine - 133 Ci 1.88 E-3 5.88 E-4 0.00 EO 0.00 EO I lodine - 135 3.14 E-3 0.00E0 Ci _ 0.00 EO 0.00 EO Total for Period ___

Ci 9.14 E-3 i 1.43E- 3 0.00 E0_ i_0.00 EO 3.Particulates Strontium - 89 Ci 8.04 E-4 4.45 E-4

[ " i50U0[I550 EO

[ Strontium - 90 Ci _2.1 l E-6 1.00E-6 0.0G EO L 0.00 E0 Strontium - 91 _

Ci 8.00 E-4 4.4SE-4 0.00 E0 l 0.00EOj Cesium - 134 Ci 0.00E0 0.00E0 0.00 EO I 0.00 E0 l 1

Cesium - 137 Ci 6.20E-5 1.35 E- 5 0.00 EO 0.00 EO j Cesium - 138 Ci 3.25E-2 3.53E-2 0.00 EO 0.00 EO Barium - 139 Ci 8.53E -3 4.92 E- 3 0.00 EO 0.00 E0 Barium - 140 Ci 8.66E-4 0.00 EO 0.00 EO

, 1.07E-3 [

Lanthanum - 140 Ci 5.12E-4 2.91 E-4 0.00 EO 0.00 EO Cobalt - 57 Ci 0.00E0 0.00E0 0.00 EO 0 00 E0 Cobalt - 58 Ci DD0E0 _7.00E-7 f 0.00 E01[ 0.00 E 3

EITLUb.NT & WASTE DISPOSAL SEhti- ANNUAL REPORT (7/lf>0 - 12/31/90)

Table 1B Page 2 of 2 Gascous Effluents For Release Point - hiain Stuck Continuous hiode Batch hiode )

Quarter Quarter Quarter Quarter '

Nuclides Released Units 3 4 3 4 Cobalt - 60 Ci 0.00 EO 0.00E0 0.00 EO 0.00 EO Zine - 65 Ci 0.00 EO 0.00E0 0.00 EO 0.00 EO Yttriun - 91hi Ci 3.63E- 3 2.76 E-3 0.00 EO 0.00 E0 lodine - 133 Ci OfK)E0 0.00E0 0.00 EO 0.00 E0 Copper - 64 Ci 0.00E0 0.00E0 0.00 EO 0.00 EO Rubidium - 83 Ci 4.02E-3 0.00 EO 0.00 E_0 0.00 E0_l Rubidium - 89 . . _

Ci 3.87 E-4 0.00 EO _0.00_E0 . _,0.00 EO j Total for Period Ci 5.21 E-2 4.52E-2 . 0.00 EO 0.00 E0 l 4

- EFFLUENT & WASTE DISPOSAL SEMI- ANNUAL REPORT (7/lNO - 12/31N0)

Table 1C Page 1 of 2 Gascous Effluents For Release Point - Unit 2 & Unit 3 Roof Vents Continuous Mode ._ __11atch Mode _.

7 Quarter Quarter Quarter Quarter Nuclides Released Units 1 2 1 2

1. Fission gasses Krypton - 85M Ci 0.00 EO 4.50E0 0.00 EO 0.00 E0 Krypton - 87 Ci 0.00 EO 0.00EO, 0.00 EO 0.00 E0 k,'rypton - 88 Ci 0.00 EO 0.00E0 0.00 EO 0.00 EO Xenon - 133 Ci 9.97El 4.36El 0.00 EO 0.00 EO Xenon - 135 Ci 8.24El 9.43El 0.00 EO 0.00 EO Xenon - 135M Ci 1.96El 0.00E0 0.00 EO O 00 EO Xenon - 138 Ci 0.00EO 0.00E0 0.00 EO 0.00 E0 ,

Unidentified Ci 8.12 El 1.23E2 0.00 EO 0.00 EO Total for Period Ci 2.83E2 2.65E2 0.00 EO 0.00 E0

~ 2.lodines lodine - 131 Ci 2.25 E- 3 _ 3.16 E- 3 0.0050]_ 0.00 E0 ,

lodine - 133 _

Ci 7.94 E-3 1.40E-3 _ 0.00E0j 0.00 E0 l

lodine - 135 Ci 0.00E0 0.00 EO 0.00 E0 0.00 EO _

Total for Period Ci 1.02 E-2 4.56E-3 0.00 EO 0.00 EO 3.Particulates Strontium - 89 Ci 1.03E-4 1.28E-4 0.00 E0 0.00 E0 Strontium - 90 Ci 1.98E-5 __ 2.20E- 5 - 0.00 EO 0.00 E0 Strontium - 91 Ci 0.00E0 0.00 EO 0.00 EO 0.00 E0 Cesium - 134 Ci 0.00 EO 0.00 EO 0.00 EO 0.00 E0 Cesium - 137 Ci 0.00 EO 0.00 EO 0.00 EO 0.00 E0 Cesicm - 138 Ci 1.89E-2 1.27 E-2 0.00 EO 0.00 E0 Barium - 139 - Ci 1.77 E-3 1.26E-3 0.00 EO 0.00 EO Barium - 140 Ci _ 0.00 EO 0.00E0 0.00 EO 020 E0 Lanthanum - 140 Ci 0.00 E0 OB0E0 0.00 EO 0.00 E0 Cobalt - 57 Ci 0.00 E0_ 0.00E0 0.00 EO 0.00 E0 Cobalt - 58 Ci 0.00 EO 0.00EO 0.00 EO 0.00 E0 Cobalt - 60 Ci 0.00 EO ODOE0 0.00 E0 L 0.00 EO 5

EFFLUENT & WASTE DISPOSAL SEMI- ANNU AL REPORT (7/1S0 - 12/31/90)

Table IC Page 2 of 2 onscous Effluents For Release Point - Unit 2 & Unit 3 Roof Vents Continuous Mode flatch Modc__

Ouarter Quarter Quarter Quarter Nuclides Released _ Units 1 2 1 2 Zine - 65 Ci 0.00 EO 0.00 EO 0.00 EO 0.00 EO Yttrium - 91M Ci 4.87 E-4 1.46E-4 0.00 EO 0.00 E0 g Iodine - 133 Ci 7.99E- 5 8.76E-5 0.00 EO 0.00 E0 l 1

Copper - 64 Ci 0.00E0 0.00E0 0.00 EO 0.00 E0 l Rubidium - 88 _

Ci 4.77E-3 2.64 E-3 0.00 EO 0.00 E0 Rubidium - 89 Ci 7.85 E-4 0.00E0 0.00 EO 0.00 EO Technetium - 99M Ci 3.53 E-5 2.89 E-5 0.00 EO 0.00 ri  !

Molybdenum - 99 Ci 2.25E-5 2.40E-5 0.00 EO 0.00 EO Tellurium - 132 Ci 6.70E-6 0.00E0 0.00 EO 0.00 E0 l l

Total for Period Ci 2.70c -2 1.70E- 2 0.00 E0 l 0.00 E0 6

5 EFFLUENT & WASTE DISPOSAL SEMI- ANNUAL REPORT (7/ ISO - 12/31N0) -

' TaMc 2A _ Page l of t Liquid Effluents - Summation of All Releases Quarter Quarter Est. Error' Units 3 4 Total %

A. Fission & acthution gasses

- - ' ~ "

1. T6iiiTTET6iiiE~(not includI5'g Tililum, passes, alp}al Ci 2.27 E- 3 7.81 E-4 32.0 E0
2. Average diluted concentration during period pCi/ml 4.07E- 11 1.18 E- 10 _  ;
3. Body Dose Millirem 4.82 E-4 1.91 E-4 Percent _of Technical Specification  % _1.61 E -2 6.37E-3
4. Maximally Exposed Organ Dose Millitem 8.66E- 4 4.76E-4 _

- Percent of Technical Spgification  % . J66E-3 4.76E-3 B. Tritium

l. Total release Ci 8.37E0 ' l.75E0 l9.0 E0
2. Average diluted concentirtion duringperiod pCi/ml 3 1.50 E-7 2.62 E- 7 ,

C. Dissolved and entrained gasses

1. Total release Ci 2.98 E-2 2.26 E-3 42.0 EO

_ 2. Average diluted concentration duringeriod pCi/mi 5.34 E- 10 3.3S E- 10 _ _ _

D. Gross alpha radioactidly _ _ , _ , _

l. Total release Ci 9.61 E-5 8.76 E-6 39.0 E0
2. Average diluted concentration during_ period pCi/ml 1.72 E- 12 1.31 E- 12 E. Volume of waste released (prior to dilution) liters 3.3SE6 5.03E5 32.0 E0 F. Volume of dilution water used during period liters 5.58E10 6.68E9 30.0 E0 l

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- EFFLUENT & WASTE DISPOSAL SEMI- ANNUAL REPORT (7/180 - 12/3190)

Table 2B Page 1 of 2 Liquid Effluents Continuous Mode llatch Mode _

Ouarter Quarter Quarter Quarter Nuclides Released Units 3 4 3 4 Stront!um - 89 Ci 0.00 EO 0.00 EO 6.40E- 5 2.10E- 5 Strontium - 90 Ci 0.00 EO 0.00 EO _2.87 E - 5 7.40E-6 Alpha Ci 0.00 EO 0.00 EO 9.61 E- 5 8.76E- 5 Tritium Cl 0.00 EO 0.00 EO 8.37E0 1.75E0 Phosphorus - 32 Ci 0.00 EO 0.00 E0 2.31 E-4 1.30E - 4

__ 1ron Ci 0.00 EO 0.00 EO 6.27 E-4 6.28 E- 5

- Xenon - 131M Ci 0.00 EO 0.00 EO 0.00EO 0.00EO Xenon - 133 Ci 0.00 EO 0.00 E0 1.82 E-2 1.18E-3 Xenon - 133M Ci 0.00 EO 0.00 EO 6.84 E-4 0.00E0 Xenon - 135 Ci 0.00 EO 0.00 E0 1.09E-2 1.07 E- 3 Krypton - 85M Ci 0.00 EO 0.00 EO 0.00EO 0.00EO

. Krypton - 87 Ci 0.00 E0 0.00 EO 0.00E0 OfX)E0 Krypton - 88 Ci 0.00 EO 0.00 EO 0.00E0 0.00E0 Xenon - 135M Ci 0.00 EO 0.00 E0 2.76 E- 5 0.00E0 Manganese - 54 Ci 0.00 EO 0.00 EO 0.00E0 2.77 E- 5 Cesium - 134 Ci 0.00 EO 0.00 E0 1.09 E-5 1.53 E -6 Cesium - 137 Ci 0.00 EO 0.00 E0 2.02 E-4 4.26E-5 j Cesium - 138 Ci 0.00 EO 0.00 EO 0.00E0 0.00E0 i Zine - 65 Ci 0.00 EO 0.00 EO 0.00E0 7.21 E-5

' Sodium - 24 Ci 0.00 EO 0.00 EO 0.00E0 0.00E0 Cobalt - 58 Ci -0.00 EO ' 0.00 E0 : 9.61 E-6 2.14 E- 5

. Cobalt - 60' Ci 0.00 EO 0.00 E0 S.02 E- 5 7.83E-5 lodine - 131 Ci 0.00 EO 0.00 EO 0.00E0 1.77 E-4 Iodine - 133 Ci 0.00 EO 0.00 EO 0.00E0 0.00E0 Molybdenum Ci 0.00 EO - 0.00 EO 0.00E0 0.00E0

= lodine - 135 Ci 0.00 EO 0.00 EO ' 0.00E0 0.00E0 Barium - 140 Ci 0.00 EO 0.00 EO 0.00E0 0.00E0 Neptunium'- 239 Ci 0.00 E0 0.00 EO 0.00E0 0.00E0 Chromium - 51 Ci 0.00 EO 0.00 EO 8.27 E-4 9.51 E- 5

-8

EFFLUENT & WASTE DISPOSAL SEMI- ANNUAL REPORT (7/INO - 12/31N0)

Table 2B Page 2 of 2 Liquid Effluents Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nuclides Released Units 3 4 3 4 Yttrium - 91M Ci 0.00 EO 0.00 EO 0.00E0_ 0.00 E0 Strontium - 91 Ci 0.00 EO 0.00 EO 0.00E0 0.00 EO Antimony - 122 Ci 0.00 EO 0.00 EO 0.00E0 0.00 E0 Tellurium - 132 Ci 0.00 EO ' O.00 EO 0.00 EO _ 0.00 EO

- Niobium - 95 Ci 0.00 EO 0.00 E0 1.78E- 5 1.97 E-5 Lanthanum - 140 Ci 0.00 EO 0.00 EO 4.18 E- 5 0.00E0_

Cadmium - 109 Ci 0.00 EO 0.00 EO 0.01EO 0.00E0 Cesium - 136 Ci 0.00 EO 0.00 EO 0.00E0 _, 0.00E0 Antimony _- 124 Ci 0.00 EO _ 0.00 EO 0.00E0 0.00E0 iron - 59 Ci 0.00 EO 0.60 EO 0.00EO 0.00EO Tellurium - 129M Ci 0.00 EO 0.00 EO 0.00E0 0.00E0 Tellurium - 131M Ci 0.00 EO 0.00 EO 0.00E0 0.00E0 Zinconium - 95 Ci 0.00 EO 0.00 EO 0.00E0 0.00E0 ,

' Cerium - 141 Ci 0.00 EO 0.00 EO 0.00E0 0.00E0 Silver - 110M Ci 0.00 EO 0.00 E0 1.31 E-4 2.98 E- 5 Total for Period (above) Ci 0.00 EO 0.00 EO 8.40218E0 1.75304 E0 1

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. . .. ~~.

a ATTACllMENT A SUPPLEMENTAL INFORMATION Pacility: Peach Bottom Units 2 & 3 Licenses: DPR 44 DPR 56

1. Regulatory Limits (Technical Specif1 cation Limits)

A. Noble Oases; 1 1500 mrem /Yr total body - " instantaneous" limits 13000 mrem /Yr skin Tech. Spec. 3.8.C. I.a 2 110 mrad - air gamma - quarterly air dose limits 120 mrad - air beta Tech. Spec. 3.8.C.2.a 3 120 mrad - air gamma -

yearly air dose limits s 40 mrad - air beta Tech. Spec. 3.8.C.2.b B. Indines. Tritium: Particulates with Half Life > 8 days:

1 11500 mrem /Yr - any organ - " instantaneous" limits (inhalation path) Tech. Spec. 3.8.C.1.b

2. A 15 mrem any organ - quarterly dose limits Tech. Spec. 3.8.C.3.a

- 3 130 mrem - any organ -

yearly dose limits Tech. Spee. 3.8.C.3.b C Liauld Effluents:

1. Concentration i 10 CFR 20, - " instantaneous" limits Appendix B, Table II, Col. 2 Tech Spec. 3.8.B.1

'2 13.0 mrem - total body - quarterly dose limits 1 10 mrem any organ Tech Spec. 3.8.B.2.a -

3. 16.0 mrem - total body -

yearly dose limits 5 20 mrem - any organ Tech. Spec. 3.8.B.2.b ICC1.Rdoc ,

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11

5 ATI'ACllMENT A SUPPLEMENTAL, INFORM ATION

2. Maximum Permissible Concentrations:

MPCs are not used to calculate permissible release rates and concentrations for gaseous releases.

The MPCs specified in 10 CFR 20, Appendix B Table II, Co;umn 2, for identified nuclides are used to calculate permissible celease rates and concentrations for liquid release per Peach Bottom Technical Speciticatien 3.8.B.1,

3. Average Energy:

Not Applicable

4. Measurements and Approximations of Total Radioactivity:

A. Fission and Activation Gases:

The method used is the Nuclear Data 6700 Counting System

- Oas Marinelli -

B. lodine:

The method used is the Nuclear Data 6700 Counting System

- Charcoal Cartridge -

C. Particulates:

The method used is the Nuclear Data 6700 Counting System

- Air Particulate Sample, (47 mm filter) -

D; Liquid Effluents:

' The method used is the Nuclear Data 6700 Counting System and the Radwaste Liquid Discharge Pre-Release Method with a liter marinelli.

1CC154 doc 12 l

A1TACilMENT A SUPPL >EMENTAL INI'ORM ATION

5. llatch Releases:

A. Idquit OTR 3 QIlu Number of batch releases: 50 12 Total time for batch releases (minutes): 12103 1886 Maximum time period for batch release (minutes): 380 355 Average time period for batch release (minutes): 242 157 Minimum time period for batch release (minutes): 15 30 Dilution now (liters): 5.58E 10 6.68e9

11. Onseous:

Not Applicable

6. Abnormal Releases:

A. Liquid.

None

13. Gaseous:

None ICC154. doe 13

c EFFLUENT & WASTE DISPOSAL SEh11- ANNUAL REPORT (7/1N0 - 12/3190)

PEACil DOTTOM UNITS 2 & 3 JULY 1,1990 TO DECEMBER 31,19!)0 CLASSES OF SOLID RADIOACTIVE WASTE SHIPMisNTS individual Total i Total # of Waste Description Volume Volume Total Principal  !

Shipments (source of waste) Containerffype_(cubic It.) _(cobic f_t.)_ Curie . Radionuclides __

Class A 56 Ocwatered Resin HIC / Type A Cask 202.1 11317.6 L70E+05 Cs - 137,1 - 131, l Co-60,70 -65, La-140 4 1 DAW hietal Drum / 7.5 600.0 3.09E-01 Co-60, Cs- 137 Type A Cask Ru - 106, Co - 57, Sb- 125  ;

l 52 DAW hietal Drum /STC variable (*) 2229.7 8.59E + 00 Co -60, Fe - 55, Zn - 65, l j Cs -137, Cs-lM  ;

i 10 DAW Metal DrumETC variable (") 211.6 9.83 E-02 Co -60, Os - 137,  !

Fe - 55. Zn - 65, Cs - l M I

1 Filters HIC /fype A Cask 170.8 170,8 2.83 E + 00 Co-60, Zn - 65, Fe - 55 l t I;'s - J 34, Cs - 137 i Class D I

'2 Dewatered Resin 1 HIC /fype A Cask 202.1 404.2 2 24E + 01 l Cs - 137, Co -60 ,

Cs - 134, Zc-65, Ni-63 2 Dewatered Resin HIC / Type B Cask 132.4 264.S 7.46 E + 02 Cr - 5 ! , Co - 60, Zn - 65, i Co-58. Fe - 5 5  !

Class C 1 @rradiated Metal Steel Liner / 57.4 ' 57.4 2.39E + 03 s Co-60. Fe - 55, Ni-63, I Type B Cask ' C - 14, TC - 99  !

l ~~

Totals ,

125 15256.1 L73E+05 i NOTES:

- Indicates actual total PECo radwaste shipped from Otradrex,after volume reduction,to the burial site.

"- Indicates actual total PECo radwaste shipped from SEG, after volume reduction, to the burial sitc.

10 i

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