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 JANUARY ST LUCIS PLANT SEMI-ANNUAL REPORT l~ 1990 THROUGH JUNE CO~

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, M3 2.458 E+1 Process filters Ci 1.059 E+2 2.0 E+1

b. Dry Compressible M3 3.121 E+1 Waste (Note 5) Ci 7.080 E+0 2.0 E+1

c. Irradiated M3 Components Ci 2.0 E+1

d. Other

1. Non-Compres- M3 2.28(o E+1 2.0 E+1 sible Metal Ci 8.610 E-1 (DAW) (Note 6)

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 2.75 E+1 Co 58 1.44 E+1 Fe 55 1.24 E+1 Cs 137 1.19 E+1 Cs 134 7.84 E+0 Cr 51 4.93 E+0 Ni 63 4.82 E+0 Be 7 4.41 E+0 Mn 54 3.51 E+0 Nb 95 2 46 E+0 I 131 2.35 E+0 Zr 95 1.42 E+0

b. Fe 55 5.99 E+1 Cs 137 1.50 E+1 Co 60 1.15 E+1 Cs 134 4.96 E+0 Co 58 3.99 E+0 Ni 63 1.26 E+0 Nb 95 1.18 E+0 Sb 125 8 40 E'l 9107230350 910716 J i PDR ADOCK 05000335 'I,

( R PDR Ij)

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7 A.

2. Estimate of Major Nuclide Composition (By Type of Waste)

(Continued)

Category Nuclides C~ N/A N/A

d. Co 60 4.26 E+1 Fe 55 3.57 E+1 Ni 63 9.56 E+0 Cs 137 6.25 E+0 Cs 134 1.92 E+0 Sb 125 1.74 E+0 Mn 54 9.70 E-1

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination Sole Use Truck Barnwell, S. C.

B. Irradiated Fuel Shipments Number of Shipments Mode of Transportation Destination 0 N/A 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)

Total Total Principal Type of Category Type of Waste Volume Caries Radionuclides Waste Reg-Guide Container Solidification Class Cubic Ft. (Note 1) Notes 1 & 2) (Note 3) 1.21 (Note 4) Agent Class A 896.3 1.90E-1 NA PWR l.b. Non-specification None Compactible Strong Tight Trash (Note 5) Package Class A 807.q 8.61E-l NA PWR l.d. Non-speci fication None Non-Compactible Strong Tight Trash (Note 6) Package Class A 215.9 1.87E-4 NA PWR l.a. Non-specification None Ion-Exchange Strong Tight Resin Package Class A 205.8 6.89 Cs 137, Sr 90 PWR l.b. NRC Certified None Compactible LSA Trash Type A Class A 207.4 3.65 Ni 63, Cs 137 Solidified Tank l.d NRC Certified Cement Sludge LSA Type A Class A 205.8 1.79 SR 90, Cs 137 PWR l.a NRC Certified None Ion-Exchange LSA Resin Type A Class A 205.8 2.72 Ni 63t Sr90 PWR l.a. NRC Certified None I 129 C14, Process Filters LSA PU 241 Type A Class B 120.3 81.35 Co 60, Ni 63, PWR l.a. NRC Certified None Sr 90, Cs 137 Ion-Exchange LSA Sum of Nuclides Resin Type A

~<5yr.

Class C 120.3 20.10 Co 60, Ni 63, PWR l.a. NRC Certified None Sr 90, Cs 137, Process Fliers Type B C 14, I 129, Pu 241, Sum of Nuclides T4<5yr.

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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