ML17285A722

Revised Pages to Semiannual Effluent Rept for Jul-Dec 1988, Reflecting Changes to Scaling Factor Data

ML17285A722
Person / Time
Site:	Columbia
Issue date:	12/31/1988
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17285A720	List: ML17285A719 ML17285A721 ML17285A722
References
NUDOCS 8909190083
Download: ML17285A722 (7)

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4.0 A total volume of 6786.3 ft3 (192.2 m3) of solid waste was transported in 23 shipments during the July t/rough December 1988gI6 '2S reporting period. The total activity of the (waste sh pped was 8+~ Ci; 813 Ci contained in dewatered spent resins and ~4-Ci in Dry Active Haste (DAH). 8't5' A.

Dewatered resins accounted for 4196.3 ft3 (118.8 m3) of the radioactive wastes shipped during the reporting period. The burial containers were ES-190, ES-142, EA-142 and PL-142 liners provided by NUPAC Services, Inc. The total activity of the resins shipped during the reporting period was 813 Ci. The principle nuclides and their percent contribution to the total activity are listed in Table 4-3. The solid wastes were shipped to the U.S. Ecology, Hanford burial site using flat bed trailers, shielded van and LN-142, NUPAC 10-142, LN 14-170, or U.S.Ecology 14D-2.0 casks as appropriate.

The counting error associated with the total activity has been found to be less than 1.0'L at one standard deviation in previous effluent reports and to decrease with increasing activity. The statistical counting error is assumed to be 11. for the purpose of this error evaluation.

Other parameters considered in estimating the total error of the activity shipped included the error in measuring the absolute volume, the weight of'he waste in the liners, the representative-ness of the sample taken, the homogeneity of the nuclide distribu-tion within a batch or liner and the geometry error in the gamma spectroscopy analysis. The gamma spectroscopy calibration error was approximately 5L. The best estimate of the total error in the activity of spent resin shipped was assumed to be less than or equal to 20'4.

B. v H A total of 2590 ft3 (73.3 m3) of DAH was shipped in 28 Container Products Corpora i , B-25 steel boxes. The total activity of the DAH shipped was . i. The values for the activities shipped were determined by using dose rate-to-curie conversion factors. The con-version factors were based on a nuclide distribution taken from analysis of contamination found in each of the major DAH production areas. The nuclide distribution is updated monthly. Short lived nuclides were eliminated based on decay of the DAH prior to shipment.

A meaningful counting error cannot be generated for the DAH, however, the total error may be assumed to be less than or equal to 201. since DAH would be subjected to similar error contributions as the spent resins.

890'9 g 9008'DR ADOCK 05000397 PDC 16

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4.1 1 in Scaling factors are based on outside laboratory (SAIC) analysis of hard-to-measure nuclides. The process of updating scaling factors is being initiated. For those waste streams where the scaling or the scaled nuclide concentration is not sufficient to provide a viable scaling factor, the final EPRI Report "Updated Scaling Factors in Low Level Radwaste", NP-5077, March 1987 has been used as a basis for the determination of a scaling factor.

Sampling of individual waste streams was performed with analysis provided by an outside lab. The H-3 concentration was measured per gram of waste material. This value was compared to the Reactor Coolant System H-3 concentration. The scaling factor is derived from the ratio of the H-3 concentration in the waste stream to RCS H-3 concentration.

- 4 T-Sampling of the individual waste stream was performed with analysis by off-site lab to determine isotopic concentration. Ratios were developed between the scaled nuclide to the scaling nuclide concen-tration determined by analysis. In those cases where the scaling nuclide is not available in large enough quantities to develop reliable (viable) scaling factors, the recommendations made in section 7 of the referenced EPRI report for the plant in the initial stages of operation are used.'RU nuclides were scaled to Ce-144, as recommended by the AIF report "Methodolgies for Classification of Low Level Radioactive Haste from Nuclear Power Plants". These nuclides are not considered to be present if the scaled values are less than: 1 nCi/g for TRU, 35 nCi/g for Pu-241 or 200 nCi/g for Cf-242. TRU nuclides will be reported if the scaling nuclide (Ce-144) is reliably detected and Cs-137 is also present.

Sampling of individual waste streams has been performed with analysis by an outside laboratory. Cs-137 and Sr-90 concentrations were measured in each waste stream except waste oil. The ratio of Cs-137 to Sr-90 has been determined and is used as the scaling factor for Sr-90 from Cs-137. For waste oil, the values from the referenced EPRI Report wi 11 be used for scaling factors. Co-60 and Ni-63 concentrations were measured in each of the sampled waste streams.

The ratio of Co-60 to Ni-63 has been determined and is used as the scaling factor for Ni-63 from Co-60.

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Table 4-1 lists those scaling factors by waste stream for those nuclides that are required to be reported. Table 4-2 lists those scaling factors for the conditional nuclides that are reported only when the scaling nuclide is found to be present.

4.2 r P The Process Control Program (PCP) used to control solidification at HNP-2 wi 11 be provided by the vendor waste processor, Pacific Nuclear Inc. in accordance with Contract C-20452, and will be sub)ected to POC review prior to any solidification of radwaste. Two Pacific Nuclear generic solidification PCP's, TP-04, "Portable Solidifica-tion System", and TP-05, "Radwaste Solidification System", are currently under NRC review. As an alternative, approved High Integrity Containers (HIC's) could be used for the transport of wastes requiring stabilization. Other portions of the radwaste program are controlled by the HNP-2 procedures PPH 1.12.1, "Radwaste Management Program", PPH 1.12.2, "Radwaste Process Control Program",

and 1.12.3, "Contract (Vendor) Haste Processing". There were no significant changes during the reporting period.

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SCALING FACTORS bl 4-1 RWCU CFD EDR/FDR EDR/FDR POWDER POWDER POWDER BEAD EMH BESLH KSIH H-3/Rx Coolant 4.55E-l 4.55E-1 4. 55E-1 3.56E-l 3. 10E-1 4.0E-5+

C-14/Co-60 kN& 1.69E-S 6.ZE-4~ 1. 18E-3 5.81E-Z 8.81E-S 1.3E-Z+

Tc-99/Cs-137 4.6E-4+ 1.94E-6 9.3E-5+ 9.3E-S+ 9.3E-S+ 9.3E-S+ 4.2E-S+

I-129/Cs-137 4.6E-4+ 2.23E-5 3.9E-5+ 3.9E-S+ 3.9E-5+ 3.9E-5+ 6.3E-S+

b 4-g.ops-'2 Ni-63/Co-60 Fe-55/Co-60 Sr-90/Cs-137 RÃ 2.6E-3+

7.73E-3 2.37E-l

1. 19E-4 1.3E-2 5.16E-1 3.88E-2 4.53E-Z 6.03E-1 2.92E-3 6.36E-Z 1.9E-2

l. 11E-3

1. 5E-2+++

4. 10E-1 2.67E-5 1.2EO+

1.5EO+

3.3E-l+

Pu-239/Ce-144 4.5E-3+ 9.1E-3+ 9.7E-3+ 9.7E-3+ 9.7E-3+ 8.7E-4+ 1.1E-2+

Pu-238/Pu-239 1.5EO+ 1.3EO+ 1.7EO+ 1. 7EO+ 1.7EO+ 1.7EO+ 1. 6EO+

Pu-Z41/Pu-239 1.1E2+ 8 BEl+

~ 9.6El+ 9. 6E1+ 9.6El+ 9.6E1+ 1.2E2+

Am-Z41/Pu-239 9.1E-1+ 9.0E-1+ 6.6E-l+ 6. 6E-1+ 6.6E-1+ 1.7EO+ 4.7E-l+

Cm-242/Pu-239 9. SE-1+ 1.0EO+ 9.7E-1+ 9.7E-1+ 9.7E-1+ 5.7E-1+ 3.1E-l+

Cm-244/Pu-239 7. 2E-1+ 8.3E-1+ 7.6E-1+ 7.6E-l+ 7.6E-l+ 7.8E-1+ 2. 9E-1+

+ Scaling or scaled nuclide not present in enough concentration to make determination of scaling factor. In these cases the scaling factor obtained from the "Updated Scaling Factors in Low-Level Radwaste" EPRI NP-5077 Final Harch 1987.

~ The report from SAIC, showed the H-3 concentration in RWCU equal to Reactor Coolant concentra-tion. The resin mix used in RWCU and CFD are the same. The reactor coolant and condensate H-3 concentration are approximately the same. The Scaling Factor for CFD is a 4.55E-l which is more representative of H-3 retention on the two resin streams.

+++ The report from SAIC showed the Ni-63 concentration of sludges at 4.03E-3 uCi/gm which compares to the Co-60 concentration of 3.52E-Z uCi/gm. This comparison would yield a Scaling Factor of 1.14E-1 ~ The above mentioned EPRI Report reconxnends a Scaling Factor of 1.5E-2. Because of the long period of time between the generation of the waste and the counting of the sample (approximately 1 year) the EPRI Number is considered more accurate.

++++ The report from SAIC showed the C-14 concentration in CFD of l. 12E-2 uCi/gm which compares to the Co-60 concentration of 1.08E-Z uCi/gm. This comparison would yield a Scaling Factor of 1.02EO.

The above mentioned EPRI report recoamends a Scaling Factor of 6.2E-4. It is felt that there was cross contamination of the sample at the lab resulting in high concentration of C-14. The recomnended EPRI number will be used.

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Table 4-3 WNP-2 SOLID WASTE SHIPMENTS July December 1988 A. SOLID HASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL

1. Type of Haste Haste Stream Unit 6-month Est. Total P ri r

a. Spent resins, filter sludges, m3 118.8 r 1

b. Dry active waste, contaminated 73.34 i

c. Irradiated components, control m3

d. Other, (absorbed aqueous liquid) No

2. Estimate of ma]or nuclide composition (by type of waste):

a. Dewatered Spent Resins N 1 1 4. 2 2 17. 1.4 2 4 F

• 4.4

.01 n- 4

• Indicates scaled nuclide 20

b. Dry Active Wastes (DAW)

F

~ 1

> 'y.s. 8-I 8~K

c. Irradiated Components None

d. Other - Absorbed Liquids Hone

3. Solid Waste Disposition 23 14D-2.0 Cask (ll)

Flat bed trailer (4) US Ecology 10-142 Cask (2) Richland, WA 14-170 Cask (3)

LH-142 Cask (2)

Shielded Van <1)

B. IRRADIATED FUEL SHIPMENTS <Disposition)

None

• Indicates scaled nuclide 21

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