ML17278A930

Revs to Tables 2-1,3-4 & 4-2 of Wpps 2 Semiannual Effluent Rept,Jan-June 1985.

ML17278A930
Person / Time
Site:	Columbia
Issue date:	06/30/1985
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17278A927	List: ML17278A926 ML17278A928 ML17278A930
References
NUDOCS 8607220312
Download: ML17278A930 (4)

Text

Table 2-1 WNP-2 LI(}UID EFFLUENTS - SUMMATION OF ALL RELEASES January - July 1985 1st 2nd Est.

Unit quarter quarter Total lError, Xl A. Fission and activation products

1. Total release (not including tritium, ases, al ha) Ci 1.0E-03 2.8E-03 2.2 E+11

2. Average diluted concentration durin eriod uCi/ml 9.5E-10 1.0E-08

- 3. Percent of MPC limit 5.0E-02 6.7E-02 B. Tritium I

l. Total release Ci 1.5E-01 9.2E-Ol 2.2 E+ll

2. Average diluted concentration durin eriod uCi/ml 1.5E-07 3.7E-06

3. Percent of MPC limit 4.9E-03 1.5E-01 C. Gross alpha radioactivity(1) l l I 1. Total release l Ci I 4.3E-05 I 8.0E-07 I 1.7 E+1 I I

D. Volume of waste (prior to I dilution) liters 1.2E+05 8.6E+05 1.5 E+1(

I E. Volume of dilution water I used durin eriod liters 1.0E+09 2.7E+08 1.5 E+lf (1)Below MDA values.

Sb07220312 Sb0707 PDR ADOCK 05000397 PDR

Table 3-4 f

WNP-2 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES January - June 1985 I

1st 2nd lEst. Totall Unit l}uarter uarter I Error %* I A. Fission 8 activation gases I

Total release Ci 4.4 E+01 3.0 E+01 3.6 E+1 I verage release rate for eriod uCi/sec 5.7 E+00 3.8 E+00 Percent o ech.

S ec. limit 7.4 E-04 5.6 E-03 B. Iodines ota io ine I (131, 133) Ci 1.3 E-02 6.8 E-03 3.6 E+1 I

2. Average release rate for eriod uCi/sec 9.4 E-04 8.6 E-04

3. Percent o ech.

S ec. limit 4.7 E-04 1.3 E-04 C. Particulates

1. Particulates with I half-lives 8 da sl Ci 2.0 E-02 3.2 E-02 3.6 E+1 verage release rate for eriod uCi/sec 2.7 E-03 4.1 E-03

3. Percent of ech.

S ec. limit 1.3 E-03 2.1 E-03

4. ross alpha radioactivit Ci 3.1 E-04 2.7 E-04 D. Tri ti um I

1. Total .eleases Ci 6.6 E-Ol 2.7 E-0', 3.6 E+i I

2. Average release rate for eriod uCi/sec 8.6 E-02 3.4 E-02 ercent o ec .

S ec. limit~ 1.0 E-05 7.3 E-06

• At 95% confidence level

~ Based on offsite exposure to the maximum organ. age group, the child.

4. 0 SOLID WASTE 0

A total volume of 2.19E+02 m3 (7.74E+03 ft3) of solid waste was trans-ported in 25 shipments during the reporting period. The total activity of the solid waste shipped was 1.95E+02 Ci; 195.24 Ci consisting of Dewatered Spent Resins and 2.73 E-02 Ci as Dry Active Waste (DAW).

A. Dewatered Spent Resin 1 ~ 38 E+02 m3 (4.86 E+03 ft3) of dewatered spent resin were shipped during the reporting period. The shipping containers were CNS 14-195 liners (burial volume - 195 ft3, actual volume-180 ft3) from Chemical Nuclear. The total activity shipped during the reporting period was 195 Ci. The principle nuclides and their percentage contribution to the total activity is listed in Table 4-1. The solid wastes were shipped to the U.S. Ecology burial site in Richland, Washington using flat bed trailers.

The counting error associated with the total activity of the six principle nuclides (about 99.5X of the total activity shipped) is 0.6% at one standard deviation. Since the remaining nuclides represents such a small portion of the total activity shipped, their error contribution was neglected.

Other parameters considered in estimating the total error of the activity shipped included the error in measuring the absolute volume, the weight of the waste in the liners, the representativeness of the sample taken, the homogeneity of the nuclide distribution within a batch or liner and the geometry error in the gamma spectroscopy analysis. The NDG600 NBS calibration error was approximately 5%.

The hest estimate of the total error in the activity of spent resin shipped was assumed to be less than or equal to 20%.

B. A total of 8.16 E+01 m3 (2.88 E+03 ft3) of dry active waste (DAW) was shipped in 32 Container Product Corporation B-25 steel boxes. The values for the activities shipped were determined by using dose rate-to-curie conversion factors. The conversion factors were based on a nuclide distribution taken from reactor coolant sample analyses which are representative for the time period in which the waste was generated. Short lived nuclides were eliminated based on decay of the DAW prior to shipment. A meaningful counting error cannot be generated for the DAW, however, the total error may be assumed to be less than or equal to 20% since DAW would be subjected to similar error contributions as the spent resins.

TABLE 4-2 page 2 of 2

3. Solid Haste Disposition Number of Shipments trode of Transportation Destination 25 Flat bed trailer (4) US Ecology 14-195H Cask {4) Richland, WA 21-300 Cask (17)

B. IRRADIATED FUEL SHIPh1ENTS (Disposition)

Number of Shipments Node of Transportation Destination None