ML17223B228

Corrected Table 3.9 of Semi-Annual Rept - Jan-June 1990.

ML17223B228
Person / Time
Site:	Saint Lucie
Issue date:	06/30/1990
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17223B227	List: ML17223B226 ML17223B228
References
NUDOCS 9107230350
Download: ML17223B228 (5)

Text

t FLORIDA POWER AND LIGHT CO~ST LUCIS PLANT SEMI-ANNUAL REPORT JANUARY l~1990 THROUGH JUNE 30'990 UNITS 1 AND 2, TABLE 3.9 A.Solid-Waste Shipped Off-Site for Burial or Disposal 1.Type of Waste Unit 6 Mo.Period Error 8 a.Spend resin, Process filters M3 Ci 2.458 E+1 1.059 E+2 2.0 E+1 b.Dry Compressible Waste (Note 5)M3 Ci 3.121 E+1 7.080 E+0 2.0 E+1 c.Irradiated Components M3 Ci 2.0 E+1 d.Other 1.Non-Compres-M3 sible Metal Ci (DAW)(Note 6)2.28(o E+1 8.610 E-1 2.0 E+1 2.Solidified M3 5.873 E+0 Tank Sludge Ci 3.650 E+0 2.0 E+1 2.Estimate of Ma)or Nuclid Composition (By Type of Waste)Category Nuclides a~Co 60 Co 58 Fe 55 Cs 137 Cs 134 Cr 51 Ni 63 Be 7 Mn 54 Nb 95 I 131 Zr 95 2.75 E+1 1.44 E+1 1.24 E+1 1.19 E+1 7.84 E+0 4.93 E+0 4.82 E+0 4.41 E+0 3.51 E+0 2 46 E+0 2.35 E+0 1.42 E+0 b.Fe 55 Cs 137 Co 60 Cs 134 Co 58 Ni 63 Nb 95 Sb 125 5.99 E+1 1.50 E+1 1.15 E+1 4.96 E+0 3.99 E+0 1.26 E+0 1.18 E+0 8 40 EŽl (9107230350 910716 J i'I, PDR ADOCK 05000335 R PDR Ij)

~~I 7 Page 2 A.2.Estimate of Major Nuclide Composition (By Type of Waste)(Continued)

Category Nuclides C~N/A N/A d.Co 60 Fe 55 Ni 63 Cs 137 Cs 134 Sb 125 Mn 54 4.26 E+1 3.57 E+1 9.56 E+0 6.25 E+0 1.92 E+0 1.74 E+0 9.70 E-1 3.Solid Waste Disposition Number of Shipments Mode of Transportation Sole Use Truck Destination Barnwell, S.C.B.Irradiated Fuel Shipments Number of Shipments 0 Mode of Transportation N/A Destination N/A N/A=Not Applicable FLORIDA POWER AND IIGHT COMPANY ST LUCIE PLANT SEMI-ANNUAL REPORT JANUARY lt 1990 THROUGH JUNE 30t 1990 UNITS 1 AND 2, TABLE 3-9 (CONTINUED)

Waste Class Total Volume Cubic Ft.Total Principal Caries Radionuclides (Note 1)Notes 1&2)Type of Waste (Note 3)Category Type of Reg-Guide Container 1.21 (Note 4)Solidification Agent Class A Class A 896.3 807.q 1.90E-1 8.61E-l NA NA PWR Compactible Trash (Note 5)PWR Non-Compactible Trash (Note 6)l.b.l.d.Non-specification Strong Tight Package Non-speci f ication Strong Tight Package None None Class A 215.9 1.87E-4 NA PWR Ion-Exchange Resin l.a.Non-specification Strong Tight Package None Class A Class A 205.8 207.4 6.89 3.65 Cs 137, Sr 90 Ni 63, Cs 137 PWR Compactible Trash Solidified Tank Sludge l.b.l.d NRC Certified LSA Type A NRC Certified LSA Type A None Cement Class A Class A 205.8 205.8 1.79 2.72 SR 90, Cs 137 Ni 63t Sr90 I 129 C14, PU 241 PWR Ion-Exchange Resin PWR Process Filters l.a l.a.NRC Certified LSA Type A NRC Certified LSA Type A None None Class B 120.3 81.35 Co 60, Ni 63, Sr 90, Cs 137 Sum of Nuclides~<5yr.PWR Ion-Exchange Resin l.a.NRC Certified LSA Type A None Class C 120.3 20.10 Co 60, Ni 63, Sr 90, Cs 137, C 14, I 129, Pu 241, Sum of Nuclides T4<5yr.PWR Process Fliers l.a.NRC Certified Type B None FLORIDA POWER AND LIGHT C ANY ST LUCIE PLANT SEMI-ANNUAL REPORT JANUARY 1, 1990 THROUGH JUNE 30, 1990 UNITS 1 AND 2 TABLE 3 9 (CONTINUED)

SOLID WASTE SUPPLEMENT.

Note 1: The total curie quantity and radionuclide composition of solid waste shipped from the St.Lucie plant, Units 1 and 2 are determined using a combination of qualitative and quantitative techniques.

In general, the St.Lucie Plant follows the guidelines outlined in the Low Level Waste Licensing Branch Technical Position (BTP)on Radioactive Waste Classification (5/11/83)for these determinations.

The most frequently used techniques for determining the total curie quantity in a package are the dose to curie methods and the (concentration) x (volume or mass)calculations.

Where appropriate, engineering type activation analyses may be applied.Since each of the above methodologies involves to some extent qualitative parameters, the total curie quantity is considered to be an estimate.The composition of radionuclides in the waste is determined by both on-side analyses for principal gamma emitters and periodic off-site analyses for other radionuclides.

The on-site analyses are performed either on a batch basis or on a routine basis using reasonably representative samples as appropriate for the waste type.Off-site analyses are used to establish scaling factors or other estimates for radionuclides such as 3H, 14C,.99Tc, 129I, TRU, 241Pu, 242Cm, 63Ni, 55Fe, and 90Sr.Note 2: "Principal Radionuclides" refer to those radionuclides contained in the waste in concentrations greater than.01 times the concentration of the nuclides listed in Table 1 or.Ol times the smallest concentration of the nuclides listed in Table 2 of 10 CFR 61.Note 3: "Type of Waste" is generally specified as described in NUREG 0782, Draft Environment Impact Statement on 10 CFR 61,"Licensing Requirements for Land Disposal of Radioactive Waste".Note 4: "Type of Container" refers to the transport package.Note 5: The volume and activity listed for Dry Compressible Waste represent the quantity of material that to date has been sent to the Barnwell, South Carolina burial facility.This material was shipped to a contracted vendor for volume reduction prior to final disposal at the Barnwell, South Carolina burial facility.During the reporting period, six shipments of Dry Compressible Waste (5,520 cubic feet, 1.285E+0 Curies)were made from the St.Lucie plant to the volume reduction facility.This material was shipped via"Sole Use Truck" in non-specification strong tight packages.Note 6: The volume and activity listed for non-compressible metal represent the quantity of material that during the reporting period could not be recycled by the contracted vendor and required disposal.

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