ML17285A721

Revised Pages to Semiannual Effluent Rept for Jan-June 1988, Reflecting Changes in Scaling Factor Data

ML17285A721
Person / Time
Site:	Columbia
Issue date:	06/30/1988
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17285A720	List: ML17285A719 ML17285A721 ML17285A722
References
NUDOCS 8909190082
Download: ML17285A721 (8)

Text

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4.0. ID W A total volume of 9828.5 ft3 (278.25 m3) of solid waste was transported in 23 shipments during the January through June, 1988 reporting period. The total activity of the waste shipped was 197.-2V-C1; 196 Ci contained in dewatered spent resins, , i in Dry Active Haste (DAH), and 7.59 E-2 Ci in other (absorbed liqh ds).

Dewatered resins accounted for 4468.5 ft3 (126.5 m3) of the radioactive wastes shipped during the reporting period. The burial containers were ES-190 and ES-142 liners provided by NUPAC Services, Inc. The total activity of the resins shipped during the reporting period was 196 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, and NUPAC 14-210H, NUPAC 10-142, or LN-14-170 casks as appropriate.

The counting error associated with the total activity has been found to be less than 1.0% at one standard deviation in previous effluent reports and to decrease with increasing activity. The statistical counting error is assumed to be 1% 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 the 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 5%. The best estimate of the total error in the activity of spent resin shipped was assumed to be less than or equal

8. 'r to A

20%.

'v H s e D W total of 5330 ft3 (150.4 m3) of DAH was shipped in 58 Container Products Corporation, 8-25 steel boxes. The total activity of the DAII shipped was +P'Ci. The values for the activities shipped were determined by us>ng dose rate-to-curie conversion factors. The conversion factors were based on nuclide distribution taken from analysis of contamination found in each of the major DAW production areas. The nuclide distribution i s 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 20% since DAH would be subjected to similar error contributions as the spent resins.

pppsppp82 appppp PDR AGOCK 05000397 R 16 PDC

A total of f 30 t3 (0. 85 m3) of absorbed liquids was shipped during the reporting period. The total activity of the shipped absorbed liquid was 7.59E-2 Ci. The liquid consisted of sump sludges absorbed in Aqueset and Aqueset II in 55 gallon Type 7A drums in order to meet burial ground requirements. The drums were 17C, 17H and 17E/H designation but, were shipped only as strong tight containers (STCs) per DOT requirements.

The values for the activities shipped were determined by using dose-rate-to-curie conversion factors and were based on sample analysis of the liquid at time of absorption. As with DAN, the total error is assumed to be less than or equal to 20% due to the likelihood of similar contributing errors to those associated with resins.

4.1 ali r eh oo Scaling factors are based on outside laboratory (SAIC) analysis of hard-to-measure nuclides. The process of updating scaling factors has been 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 performed 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.

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.

TRU nuclides would be 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.

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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 referrenced EPRI Report will be used for scaling factors. The values obtained in the referenced EPRI report were 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.

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 r ro The Process Control Program (PCP) used to control solidification at WNP-2 will be provided by the vendor waste processor, Pacific Nuclear Inc. in accordance with Contract C-20452, and wi 11 be subjected 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 Con-tainers (HIC's) could be used for the transport of wastes requiring stabilization'ther portions of the radwaste program are controlled by the WNP-2 procedures PPM 1.12.1, "Radwaste Management Program",

PPM 1.12.2, "Radwaste Process Control Program", and 1.12.3, "Contract (Vendor) Waste Processing". The only significant change was in transportation contractor from Pacific Nuclear to LN Technologies.

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SCALING FACTORS b 4 RWCU CFD EDR/FDR EDR/FDR POWDER POWDER POWDER BEAD fK85 iKG9 4.55E-l 4. 55E-1 3.56E-l 3. 10E-1 4.0E-5+

H-3/Rx Coolant C-14/Co-60 kkk "~ 4.55E-1 1.69E-5 6.2E-4++++ 1. 18E-3 5.81E-2 8.81E-5 1.3E-2+

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

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

Tb 4- - i G os'f4~

Ni-63/Co-60 7.73E-3 1 ~ 3E-2 4.53E-2 6 '6E-2 1.5E-2+++ 1.2EO+

Fe-55/Co-60 2.37E-1 5. 16E-1 6.03E-1 1.9E-2 4 ~ 10E-1 1. 5EO+

Sr-90/Cs-137 2.6E-3+ 1.19E-4 3.88E-2 2.92E-3 1 ~ 11E-3 2.67E-5 3. 3E-1+

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-241/Pu-239 1.1E2+ 8.8E1+ 9.6E1+ 9.6E1+ 9.6El+ 9.1E1+ 1.2E2+

Am-241/Pu-239 9. 1E-1+ 9. OE-1+ 6.6E-1+ 6.6E-1+ 6.6E-1+ 1.7EO+ 4.7E-l+

Cm-242/Pu-239 9. 5E-1+ 1.0EO+ 9.7E-1+ 9.7E-1+ 9.7E-l+ 5.7E-1+ 3.1E-1+

Cm-244/Pu-239 7.2E-l+ 8.3E-l+ 7.6E-1+ 7. 6E-1+ 7.6E-1+ 7.8E-l+ 2.9E-l+

+ 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 th'e H-3 concentration in RWCU equal to Reactor Coolant concen-tration. The resin mix used in RWCU and CFD are the same. The reactor coolant and conden-sate H-3 concentration are approximately the same. The Scaling Factor for CFD is 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-2 uCi/gm. This comparison would yield a Scaling Factor of 1.14E-l. The above mentioned EPRI Report reconmends 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 to report from SAIC showed the C-14 concentration in CFD of 1. 12E-2 uCi/gm which compares the Co-60 concentration of 1.08E-2 uCi/gm. This comparison would yield a Scaling Factor of 1.02EO. The above mentioned EPRI report recommends a Scaling Factor of 6.2E-4. It is felt that there was cross contamination of the sample at the lab resulting in high concen-tration of C-14. The reconmended EPRI number will be used.

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Table 4-3 HNP-2 SOLID HASTE SHIPMENTS January dune 1988 A. SOLID HASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL

1. Type of Haste Haste Stream Unit 6-month Est. Total r o (~~O

a. Spent resins, filter sludges, m3 126.5 ev lll 1 1

b. Dry active waste, contaminated 150. 9 ui

~rc. Irradiated components, control m3 No n

Ship-

d. Other, (absorbed aqueous liquid) 0.85

2. Estimate of major nuclide composition (by type of waste):

a. Dewatered Spent Resins Null 1 7n- 4. 'I.07E~

.17 1

~l~r- 1 1.5 1 4 .1 E

.01 2.4 4. 4 2.

,4

• Indi cates scaled nuclide 20

b. Dry Active Hastes (DAH)

<>'~Ml

4. -1 A/5 -I f-f.

H-3* ~ 2 o D 2

~Nb- 5 l. E-2 10 -1 6 4.4 -3

c. Irradiated Components None

d. Other Absorbed Liquids O

0

.47 E-2 2 2n- 1. E-2 3 n- 4. E-5.2 E-4 E-5

3. Sol i d Haste Di sposi tion

~D~in~igg 23 Flat bed trailer (6) US Ecology 14-210H Cask (5) Ri'chland, WA 10-142 Cask (1)14-170 Cask (11)

B. IRRADIATED FUEL SHIPMENTS (Di sposition)

None

• Indicates scaled nuclide 21

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Internal Distribution: ail Drop:

TE Chapman - 1020 RG Graybeal - 927S FD quinn w/o 1020 RA Chitwood - 1020 CR Hexum - 981G S Regev 1020 LF Coleman - 927S DE Larson 1020 VE Schockley - 927S KD Cowan 988U GV Oldfield 1020 GC Sorensen - 280 AI Davis - 927S AL Oxsen 1023 CHP/Ib 927M AG Hosier - 956B PL2/lb 9568 GH Godfrey 1023 Docket File - 9568 MNP-2 Files 964Y Ops Files - 1216 927S Ops File---1316.2 - 927S G02-88-177 August 10, 1988 Docket No. 50-397 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Hail Station Pl-137 Ilashington, D.C. 20555 Gentlemen:

Subject:

NUCLEAR PLANT NO. 2 SEMI-ANNUAL EFFLUENT REPORT JANUARY 1, 1988 JUNE 30, 1988 In accordance with Title 10 of the Code of Federal Regulations, Part 50.36a (a)

(2), the subject report is herewith being submitted.

Should you have any questions, please contact Hr. R. G. Graybeal', Manager, INP-2 Health Physics Chemistry.

Very truly yours, C. M. Powers WNP-2 Plant Manager TEC/bk cc: JB Hartin - NRC RV RB Samworth - NRC DL Williams - BPA/399 NRC Site Inspector 901A C Eschels - EFSEC D Sherman - Amer. Nuclear Insurers RR Strong - DSHS Author: TE Cha man For Signature of: CH Powers Section:

For Approval of: A H e D L rgb l Approved:

Date:

WP 387 R2