ML17278A930
| ML17278A930 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 06/30/1985 |
| From: | WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | |
| Shared Package | |
| ML17278A927 | List: |
| References | |
| NUDOCS 8607220312 | |
| Download: ML17278A930 (4) | |
Text
Table 2-1 WNP-2 LI(}UID EFFLUENTS - SUMMATION OF ALL RELEASES January - July 1985 A.
Fission and activation products Unit 1st quarter 2nd Est.
quarter Total lError, Xl 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
- 3.
Percent of MPC limit B.
Tritium uCi/ml 9.5E-10 5.0E-02 1.0E-08 6.7E-02 l.
Total release 2.
Average diluted concentration durin eriod 3.
Percent of MPC limit C.
Gross alpha radioactivity(1)
Ci uCi/ml 1.5E-01 9.2E-Ol 1.5E-07 3.7E-06 4.9E-03 1.5E-01 I
2.2 E+ll l
I 1.
Total release l
l Ci I 4.3E-05 I 8.0E-07 I 1.7 E+1 I
D.
Volume of waste (prior to dilution)
I I
liters 1.2E+05 8.6E+05 1.5 E+1(
E.
Volume of dilution water used durin eriod (1)Below MDA values.
I I
liters 1.0E+09 2.7E+08 1.5 E+lf Sb07220312 Sb0707 PDR PDR ADOCK 05000397
Table 3-4 f
WNP-2 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES
, January - June 1985 Unit A.
Fission 8 activation gases 1st l}uarter I
2nd lEst. Totall uarter I Error %*
I Total release verage release rate for eriod Percent o
ech.
S ec. limit B.
Iodines ota io ine (131, 133) 2.
Average release rate for eriod 3.
Percent o
ech.
S ec. limit C.
Particulates Ci uCi/sec Ci uCi/sec 4.4 E+01 5.7 E+00 7.4 E-04 1.3 E-02 9.4 E-04 4.7 E-04 3.0 E+01 3.8 E+00 5.6 E-03 6.8 E-03 8.6 E-04 1.3 E-04 I
3.6 E+1 I
I 3.6 E+1 I
1.
Particulates with half-lives 8 da sl Ci 2.0 E-02 3.2 E-02 I
3.6 E+1 verage release rate for eriod 3.
Percent of ech.
S ec. limit 4.
ross alpha radioactivit D.
Triti um uCi/sec Ci 2.7 E-03 4.1 E-03 1.3 E-03 2.1 E-03 3.1 E-04 2.7 E-04 1.
Total.eleases 2.
Average release rate for eriod ercent o
ec S ec. limit~
Ci 6.6 E-Ol uCi/sec 8.6 E-02 1.0 E-05 2.7 E-0',
3.4 E-02 7.3 E-06 I
3.6 E+i I
- 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.
B.
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%.
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 3.
Solid Haste Disposition page 2 of 2 Number of Shipments 25 trode of Transportation Flat bed trailer (4) 14-195H Cask
{4)21-300 Cask (17)
Destination US Ecology
- Richland, WA B.
IRRADIATED FUEL SHIPh1ENTS (Disposition)
Number of Shipments None Node of Transportation Destination