ML17279A494

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WNP-2 Semiannual Effluent Rept,Jan Through June 1987. W/870818 Ltr
ML17279A494
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 06/30/1987
From: Powers C
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
GO2-87-229, NUDOCS 8708240274
Download: ML17279A494 (32)
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Text

I EGULA" 'Y INFORMATION DI~ IBUTIV SYSTEM (RIDS)

ACQRQSION NBR S708240274 DOC. DAT . NOTARIZED: NO DOCKET I FAC IL 50-397 WPPSS Nuclear Pro Jecti Unit 2I Washington Public Poee 05000397 AUTH. NAME AUTHOR AFFILIATION POWERS'. M. Washington Public Power Supply System RECIP. NAME RECIPIENT AFFILIATION

SUBJECT:

"Semiannual Effluent Rept'an-June 1987. W/S70818 I DISTRIBUTION CODE: IE4SD COPIES RECEIVED: LTR J EN SIZE:

TITLE: 50. 36a(a) (2) Semiannual Effluent Release Reports RECIPIENT COPIES REC IP IENT COP IES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 0 PD5 PD 5 5 SAMWORTHi R 1 1 INTERNAL: ACRS 1 1 *EOD/DOA 1 1 AEOD/DSP/TPAB 1 1 ARM TECH ADV 1 1 NRR/DEST/PSB 1 1 P/RPB 4 4 NR LRB 1 1 01 1 1 02 1 1 RGN2/DRSS/EPRPB 1 1 EXTERNAL: BNL TICHLERi J 1 1 LPDR 1 1 NRC PDR 1 TOTAL NUMBER OF COP IES REQUIRED: LTTR 23 ENCL 22

WNP-2 SEMI ANNUAL EFFLUENT REPORT JANUARY THROUGH JUNE 1987 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LICENSE NO. NPF-21 8708240270 870630 PDR ADOCK 05000397 R PDR

0 TABLE OF CONTENTS SECTION PAGE

1. 0 INTRODUCTION . ~ ~ 1
2. 0 LIQUID EFFLUENTS ~ ~ 2 3.0 GASEOUS EFFLUENTS 6 4.0 SOLID WASTE 17 5.0 METEOROLOGICAL DATA 24 6.0 DOSE ASSESSMENT - IMPACT ON MAN ~ ~ ~ ~ 25 7.0 REVISIONS TO THE ODCM 26

LIST OF TABL'ES TABLE TITLE PAGE 2-1 HNP"2 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES-JANUARY"JUNE 1987 3 2-2 WNP-2 LIQUID EFFLUENTS - SOURCE TERMS JANUARY-JUNE 1987 ~ ~ ~ 4 3-1 WNP"2 GASEOUS EFFLUENTS " SOURCE TERMS - MIXED MODE RELEASES " MAIN PLANT VENT JANUARY-JUNE 1987 . . . . . . . 8 3"2 WNP-2 GASEOUS EFFLUENTS - SOURCE TERMS GROUND LEVEL RELEASES TURBINE BUILDING " JANUARY"JUNE 1987 3-3 HNP-2 GASEOUS EFFLUENTS " SOURCE TERMS GROUND LEVEL RELEASES - RADWASTE BUILDING - JANUARY"JUNE 1987 13 3-4 HNP"2 GASEOUS EFFLUENTS - SUMMATION-OF ALL RELEASES .

JANUARY"JUNE 1987 15 3"5 HNP-2 GASEOUS EFFLUENTS " BATCH RELEASES JANUARY-JUNE 1987 . . . . . . . . . . . . . . . . . . . . . . 16 4-1 SCALING FACTOR FOR REQUIRED NUCLIDES 20 4"2 SCALING FACTORS FOR CONDITIONAL NUCLIDES ~ ~ ~ ~ ~ t ~ ~ ~ ~ 20 4-3 HNP"2 SOLID WASTE SHIPMENTS JANUARY-JUNE 1987 . 21

~ 0

1.0 INTRODUCTION

This report is submitted in compliance with Technical Specification 6.9.1.11. It includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from WNP-2 during the previous six months of operation with data summarized on a quarterly basi s.

2.0 LIQUID EFFLUENTS The radwaste liquid effluents were released in a batch mode only during the reporting period. Six batch releases occurred during the first calendar quarter and 27 batch releases during the second calendar quarter. The total time period for the batch releases was 58.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, with the maximum time period being-2.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> for a release, the minimum time period being 1.13 hour1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> s for a release and the average time period was 1.76 hours8.796296e-4 days <br />0.0211 hours <br />1.256614e-4 weeks <br />2.8918e-5 months <br />. The volume of dilution water considered, is the total volume of recirculating cooling tower blowdown flow for the period. The average flow rate of the Columbia River during January through June 15, 1987 was 1.1E+05 cubic feet per second.

Periodic LADTAP II computer runs were performed to verify compliance with Technical Specification limits. The calculated dose to the maximum individual due to liquid releases for the first quarter was 3.5E-04 mrem whole bog and 5.7E-04 mrem for the maximum organ. The second quarter calculated dose was 1.2E-02 mrem whole body and 2.2E-02 mrem for the maximum organ.

The liquid batch releases were recirculated prior to sampling. A repre-sentati ve sample was obtained and analyzed for each batch release. A composite of tank samples for each quarter was analyzed for strontiums and irons. The method for measurement of total radioactivity was by gamma spectroscopy, liquid scintillation and proportional counters.

All isotopes listed in Regulatory Guide 1.21, Revision 1, 1974 and our Technical Specifications are included in effluent analyses.

Additionally, any other unidentified gamma spectroscopy peak(s) is resol ved and that isotope added to the analyses. Expected pure beta emitters are included in routine analyses except for those isotopes that have been shown not to be present in significant quantities.

The percent of MPC limit is based on the total MPC fractions using those nuclides in Table 2-2 and concentrations listed in 10CFR20, Appendix B, Table 2, Column 2.

The percent of estimated total error s are listed in Table 2-1. These estimated errors are based on counting statistics, tank volume, and in obtaining a representative sample prior to discharge.

The estimated total errors were calculated by obtaining the square root of the sum of the squares of the errors of the individual contributors and multiplying by 1.96 for a 95'X confidence level.

0 c Sample Racks SW-SR-42, SW-SR-43 The Residual Heat exchanger cooling water monitoring sample racks SW-SR-42 and SW-SR-43 were removed from service to be modified to operate in a postulated accident senario, in addition to functioning as a Tech Spec leakage detection monitor. The sampling systems were moved, shielded, and had their flow instrumentation changed; sample rack SW-SR-42 was moved to 501 ft. elevation of the reactor building while sample rack SW-SR-43 just had the shield and sampling chamber moved to the opposite end of its skid on 522 ft. elevation of the reactor building. After the system was installed and declared complete, the radiometric calibration was-then performed. The total time the system was out of service for modification, exceeded the 30 day technical specification action statement. While the system was inoperative there was no danger to plant personnel, systems, or the public, as the plant was shutdown or in the refueling mode.

o 0 Table 2-1 WNP-2 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES January - June 1987 1st 2nd Est.

Unit Quarter Quarter I Total IError* 'Xl A. Fission and activation products

1. Total release (not including tritium, gases, al ha) Ci 3.8E-04 8.0E-03 l2. 2 E+011
2. Average diluted concentration durin peri od uCi/ml 1.5E-09 4. OE-08
3. Percent of MPC limit 2.6E-02 5.0E-02 B. Tri ti um
l. Total release Ci 1.2E-01 6.2E-01 I2.2 E+Oll
2. Average diluted concentration during period uCi/ml 4. 8E-07 3.1E-06
3. Percent of MPC limit 1. 6E-02 1. OE-01 C. Dissolved and entrained gases I
1. Total release Ci I(2.8E-05 l(4.0E-04 I2.2 E+Oll
2. Average diluted concentration during eriod uCi/ml I(1.1E-10 I(2. OE-09
3. Percent of MPC limit 'X I~5.5E-05 I(l.OE-03 D. Gross alpha radioactivi'ty I I I 1. Total release Ci I(3.1E-10 I(2.4E-09 l2.3 E+Ol I E. Volume of waste (prior to dil uti on) liters 3.8E+05 1.6E+06 I1.5 E+Ol I I

F. Volume of dilution water I I used durin eriod liters 2.5E+08 2.0E+08 l1.5 E+Ol I

  • At 95% confidence level

Table 2-2 WNP-2 LIQUID EFFLUENTS - SOURCE TERMS January - June 1986 BATCM MODE Nuclides Released

'st 2nd Unit Quarter Quarter Strontium-89 Ci 1.2 E-04 4.0 E-05 Strontium-90 Ci 7. 5 E-06 I ~ 9. 0 E-06 Cesium-134 Ci ~ 7.2 E-06 ~ 1.5 E-04 Cesium-1 37- Ci I" 5.9 E-06 l~ 1.2 E-04 Iodine-131 Ci I~ 6.3 E-06 I~ 1.0 E-04 Cobalt-58 Ci l~ 1.5 E-05 3.2 E-04 Cobalt-60 Ci I~ 1.7 E-05 8.2 E-04 Iron-59 Ci ~ 1.2 E-05 l~ 1.6 E-04 Zinc-65 Ci 8.1 E-05 5.3 E-03 Man anese-54 Ci l~ 8.5 E-06 1.4 E-04 Chromium-51 Ci 1.5 E-04 1.4 E-03 Zirconium-Niobium-95 Ci I< 1.2 E-05 l~ 1.4 E-04 Mol bdenum-99 Ci l~ 5.6 E-05 I~ 9.2 E-04 Technetium-99m Ci l~ 6.0 E-06 l~ 6.6 E-05 Barium-1anthanum-140 Ci I< 2.0 E-05 l~ 3.7 E-04 Cerium-141 Ci I 7. 9 E-06 I 1. 2 E-04

TASLE 2-2 (Continued)

Others Cerium-144 Ci ~ 3.0 E-05 l 5.1 E-04 Iron-55 Ci 2.4 E-05 2.9 E-05 Total for Period (Above) I Ci 3.8 E-04 8.0 E-03 Xenon-133 Ci l~ 2.0 E-05 l~ 3.2 E-04 Xenon-135 Ci l~ 7.6 E-06 l~ 8.2 E-05 Tritium l ci 1.2 E-01 6.2 E-01 NOTE: Less than (~) values are not included in the Total For Period values.

3.0 GASEOUS EFFLUENTS The gaseous radwaste effluents from WNP-2 were released in a continuous mode. There are three (3) release points at WNP-2:

1. Main Plant Yent - mixed mode release
2. Turbine Building - ground level release
3. Radwaste Building - ground level release The gaseous source terms from each release point are listed in Tables 3-1 to 3-3. Table 3-4 provides a summation of the total activity released, the average release rate, the percent of Technical Specification limit, gross alpha radioactivity and the estimated total error associated with the measurements of radioactivity in the gaseous effluents.

Radioactivity measurements for gaseous effluent releases are performed for fission and activation gases by collecting the samples on charcoal traps and analyzing them using gamma spectroscopy. Tritium is sampled by freeze trapping and analyzed by liquid scintillation counting. Par ticu-lates and iodines are sampled using charcoal cartridges and particulate filters and analyzed using gamma spectroscopy.

The "Percent of Technical Specification Limit" calculations were based on exposure at specified locations. Air dose due to noble gases was deter-mined at the site boundary with the quarterly limit of 5 mrads for gamma being the more restrictive for each time per iod. The gamma air dose fr om noble gases for the first quarter was 1.2E-Ol mrads and 5.8E-02'mrad for the second quarter. Iodines, particulates and tritium calculations were determined at Taylor Flats, located 4.2 miles southeast. A limit of 7.5 mrems per quarter to any organ was used in these calculations. The maxi-mum organ dose to a "Member of the Public" was 1.2E-02 mrem for the first quarter and 7.2E-03 mrem for the second quarter.

To verify compliance with Technical Specification limits, calculations were performed for each month's releases using the GASPAR computer program and parameters as outlined in the ODCM. Doses were determined at two special locations.

1. The Site Boundary at 1.2 miles from the plant and for the sector with the maximum X/g value.
2. Taylor Flats - at 4.2 miles SE.

There were no abnormal releases of gaseous effluent during the first and second quarter s of 1987. Sampling and monitoring of the gaseous effluents were performed in accordance with Technical Specifications and Plant Procedures.

e Total error estimates are based on grab samples, gamma spectrometry, analyzer detectors, and beta scintillation readings. The overriding uncertainty in all cases is the measurement of the effluent and sample volumes. The estimated error was determined to be 36% at the 95%

conf i dence level .

In addition to the reactor site, WNP-2 has a permanent laundry facility located approximately 0.75 miles from the site. Its ventilation system contains HEPA filters on the discharge and is continuously monitored for particulates and radioiodines. Also at this location is a backup chemistry lab within the EOF. The radiochemical hood containing HEPA filters is monitored for radioactive releases when in operation. Gamma spectrometry indicated no isotopes present other than those attributable to natural background.

iO Table 3-1 MNP-2 GASEOUS EFFLUENTS SOURCE TERMS - MIXED MODE RELEASES MAIN PLANT YENT January - June 1987 CONTINUOUS MODE st nd Nuclides Released Unit Quarter Quarter

1. Fission gases Krypton-85 Ci [( 2.9 E+01 l~ 3.4 E+01 Kr pton-85m Ci 2.7 E-01 3.5 E-02 Krypton-87 Ci 4.0 E-01 6.0 E-01 Kry ton-88 Ci 4.9 E-Ol 6.6 E-01 Xenon-133 Ci 6.7 E-01 7.0 E-01 Xenon-133m Ci 1.5 E+00 1.4 E+00 Xenon-135 Ci 1.8 E-01 3.5 E-01 I

Xenon-135m Ci j~ 6.9 E+00 7.8 E-02 Xenon-138 Ci 1.9 E+00 1.5 E+Ol Ar on-41 Ci l~ 3.2 E-01 4.5 E-03 Total for eriod Ci 5.4 E+00 1.9 E+01

2. Iodines Iodine-131 Ci 2.0 E-04 1.0 E-04 Iodine-133 Ci 9.6 E-04 2.3 E-04 Iodine-135 Ci I< 4.2 E-05 I~ 4.7 E-05 Total for period Ci I 1.2 E-03 3.3 E-04

Table 3-1 (Continued)

3. Particulates
  • Strontium-89 Ci 7.8 E-06 1.9 E-07
  • Strontium-90 Ci l~ 5.1 E-10 2.7 E-07 Cesium-134 Ci I+ 9.3 E-05 I< 1.4 E-04 Cesium-137 Ci 2.7 E-05 l~ 1.1 E-04 Barium-lanthanum-140 Ci l~ 2.7 E-04 I

~ 3.6 E-04 Molybdenum-99 Ci I~ 1.3 E-03 2.9 E-04 Cerium-141 Ci l~ 7.3 E-05 l~ 8.5 E-05 Cerium-144 Ci I< 3.3 E-04 )< 3.6 E-04 Cobalt-58 Ci 3.0 E-04 2.8 E-04 Cobal t-60 Ci. 3.3 E-04 1.2 E-03 Iron-59 Ci I~ 1.5 E-04 I~ 2.3 E-04 Man anese-54 Ci 5.9 E-05 2.8 E-04 Zinc-65 Ci 1.2 E-03 2.7 E-03 Others Chromium-51 Ci 4.8 E-04 1.4 E-04 Zirconium-95 Ci I~ 1.5 E-04 7.3 E-04 Cesium-138 Ci I~ 9.4 E-06 3.9 E-04 Technetium - 99m Ci 4. 9 E-03 I ~1.1 E-05 Sodium - 24 Ci 9.0 E-04 c1.2 E-05 Total for eriod -

Ci 8.2 E-03 6.0 E-03

Table 3-1 (Continue I

l4. Tritium Ci 9.9 E-02 2.1 E-01 Total bui1 din rel ease Ci 5.5 E+00 1.9 E+01

  • The strontium analysis for LLD levels was modified between the first and second quarter reports. A newer, more conservative calculation is being used for estimating MDA in the analytical scheme.

NOTE: Less than (~) values are not included in the Total For Period values.

10

Table 3-2 MNP-2 GASEOUS EFFLUENTS SOURCE TERMS GROUND LEVEL RELEASES TURBINE BUILDING January - June 1987 CONTINUOUS MODE st nd Nuclides Released Unit Quarter Quarter

l. Fission gases Kry ton-85 Ci l~ 2.9 E+02 I ~ 2.8 E+02 Kry ton-85m Ci l~ 3.4 E-Ol Ic 3.3 E-Ol Krypton-87 Ci 1.9 E+00 6.8 E-01 Kry ton-88 Ci 2.2 E+00 1.2 E+00 Xenon-133 Ci 2.0 E+00 1.2 E+00 Xenon-133m Ci 5.6 E+00 3.0 E+00 Xenon-135 Ci 1.0 Ei00 7.0 E-01 Xenon-135m Ci 4.2 E+00 ~ 8.9 E-01 Xenon-138 Ci 1.5 E+01 9.1 E+00 Total for eriod Ci I 3.2 E+Ol 1.6 E+01
2. Iodines Iodine-131 Ci 5.3 E-05 7.4 E-05 Iodine-133 Ci 3.6 E-04 l~ 1.9 E-04 Iodine-135 Ci l~ 1 ~ 2 E-04 I ~ 1.1 E-04 Total for eriod Ci I 4.1 E-04 I 7.4 E-05 I

0 Table 3-2 (Continued)

3. Particulates Strontium-89 Ci 1.1 E-04 I~ 3.0 E-06 Strontium-90 Ci l~1.6 E-09 I~ 2.1 E-06 Cesium-134 Ci fc 2 1 E 04 (~1 0 E 04 Cesium-137 Ci I< 1.1 E-04 I ~ 9.1 E-05 Barium-1 anthanum-1 40 Ci I~ 4.4 E-04 I 2.9 E-04 Mol bdenum-99 Ci l~ 1.1 E-03 ~ 1.0 E-03 Cer ium-1 41 Ci I 1. 2 E-04 ~1.0 E-04 Cerium-144 Ci l~ 4.9 E-04 ~ 3.6 E-04 Cobalt-58 Ci I~ 1.1 E-04 I 1.0 E-04 Cobal t-60 Ci l~ 1.8 E-04 I~1.7 E-04 Iron-59 Ci I>> 2.4 E-04 l~ 2.1 E-04 Man anese-54 Ci I~ 1.0 E-04 I>> 9.9 E-05 Zinc-65 Ci 9.3 E-05 1.6 E-04 Others Chromium-51 Ci l~ 1.2 E-03 3.1 E-04 Zirconium-95 Ci )~1.8 E-04 I~1.6 E-04 Cesium - 138 Ci l~ 3.1 E-04 2.2 E-03 Technetium - 99 1.8 E-05 l~ 1.9 E -05l Total for eriod Ci 2.2 E-04 2.7 E-03 I I l4. Tritium Ci 1.2 E+00 3.3 E-01 I Total buil din release Ci l 3.3 E+Ol I 1.6 E+01 NOTE: Less than (~) values are not included in the Total For Period values.

Table 3-3 WNP-2 GASEOUS EFFLUENTS SOURCE TERMS GROUND LEVEL RELEASES RADMASTE BUILDING January - June 1987 CONTINUOUS MODE st nd I Nuclides Released Unit Quarter Quarter

1. Fission gases Kry ton-85 Ci l~ 3.6 E+01 I 3.9 E+Ol Kry ton-85m Ci l~ 1 ~ 1 E-01 lc 1 ~ 1 E-01 Krypton-87 Ci 4.6 E-01 3.8 E-01 Kr ton-88 Ci 5.9 E-01 1.3 E+00 Xenon-133 Ci 7.1 E-01 5.0 E-Ol Xenon-133m Ci 2.0 E+00 2.8 E+00 Xenon-135 Ci 3.5 E-01 3.8 E-01 Xenon-135m Ci 3.8 E-01 8.1 E-Ol Xenon-138 Ci 2.3 E+00 1.4 E+00 Total for eriod Ci 6.8 E+00 7.6 E+00
2. Iodines Iodine-131 Ci 2.3 E-05 t~ 2.1 E-05 Iodine-133 Ci 9.6 E-05 2.0 E-05 Iodine-135 C) l~ 1 ~ 9 E-05 I~ 2.1 E-05 Total for period Ci 1.2 E-04 2.0 E-05 13

1 Table 3-3 (Continued)

3. Particulates Strontium-89 Ci 6.8 E-07 j>>3.7 E-07 Strontium-90 Ci 4 5.4 E-09 l~ 2.6 E-07 Cesium-134 Ci c 1.9 E-05 l~ 1.9 E-05 Cesium-137 Ci I~ 1.5 E-05 l~ 1.7 E-05 Barium-Lanthanum-140 Ci I+ 4.9 E-05 l~ 5.6 E-05 Mol bdenum-99 Ci l~ 1.7 E-04 l~ 1.8 E-04 Cerium-141 Ci l~ 1.7 E-05 l~1.8 E-05 Cerium-144 Ci I~6.6 E-05 I~7.4 E-05 Cobalt-58 Ci l~1.6 E-05 I~1.8 E-05 Cobal t-60 Ci I< 2.4 E-05 I 2.7 E-05 Iron-59 Ci I< 3.8 E-05 l~ 4.4 E-05 Man anese-54 Ci l~ 1 ~ 9 E-05 l ~1.8 E-05 Zinc-65 Ci l~ 3.9 E-05 4.8 E-05 Others Chronium-51 Ci I

~ 1.1 E-04 I < 1. 2 E-04 Zirconium-95 Ci I~ 2.7 E-05 1~2.9 E-05 Total for eriod Ci 6.8 E-07 4.8 E-05 I

l4. Tritium Ci 1.2 E-01 1.2 E-01 I I Total buil din release Ci 6.9 E+00 7.7 E+00 I NOTE: Less than (~) values are not included in the Total For Period values.

14

Table 3-4 MNP-2 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES January - June 1987 1st 2nd lEst. Total Uni t Quarter Quarter I Er ror  %*

A. Fission 8 activation gases I

1. Total release Ci 4.4 E+Ol 4.3 E+01 3.6 E+Oll
2. Average re ease rate for eriod uCi/sec 5.7 E+00 5.5 E+00 ercen o ec .

S ec. limit 2.4 E+00 1.2 E+00 B. Iodines ota io ine (131, 133) Ci 1.7 E-03 4.2 E-04 3. 6 E+01 I

2. Average release rate for eriod uCi/sec 2.2 E-04 5.3 E-05 ercent o ec .

S ec. limit 1.6 E-01 9.6 E-02 C. Particulates Par ticu ates wit

'alf-lives 8 da s Ci 8.4 E-03 8.7 E-03 3.6 E+Oll I

2. Average re ease rate for eriod uCi/sec 1.1 E-03 1.1 E-03 ercen o ec .

S ec. limit 1.6 E-01 9.6 E-02 ross a pa radioacti vit Ci 1.7 E-03 1.3 E-03 D. Tr itium I

1. Total releases Ci 1.4 E+00 6.6 E-Ol 3.6 E+Oll verage re ease rate for eriod uCi/sec 1.8 E-01 8.4 E-02 ercent o ec .

S ec. limit 1.6 E-01 9.6 E-02

  • At 95% confidence 'level

Table 3-5

~

WNP-2 GASEOUS EFFLUENTS, BATCH RELEASES January - June 1987 ota ax 1 lllulll 1 n1lllulll ean T e Number Time (hrs) Time (hrs) Time (hrs) Time (hrs)

Purge 10 127. 5 31. 5 2. 25 12. 8 Vent 69.8 4.25 0.5 1.55 NOTE: Batch releases were performed through the Main Plant Vent - mixed mode release.

16

P 8r e 4.0 SOLID WASTE A total volume of 7276 ft3 (206.0 m3) of solid waste was transported in 19 shipments during the January 1 through June 30, 1987 reporting period. The total activity of the waste. shipped was 660.641 Ci; 658.305 Ci contained in dewatered spent resins and 2.336 Ci in Dry Active Waste (DAW).

A. Dewatered S ent Resin Dewatered resins accounted for 2956 ft3 (83.7 m3) of the radio-active wastes shipped during the reporting period. The burial containers were LSA-190 and ES-142 liners provided by NUPAC Services, Inc. The total activity of the resins shipped during the reporting period was 658.305 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, NUPAC 14-210H, or NUPAC 10-142 casks as appropriate.

The counting error associated with the total activity has been found to be less than 1.0X 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-within a batch or liner and the geometry error in the gamma 'ion 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 to. 20%.

B. Dry Active Waste (DAW)

A total of 4320 ft (122.3 m ) of DAW was shipped in 48 Container Products Corporation, B-25 steel boxes. The total activity of the DAW shipped was 2.336 Ci. 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.

17

e Li dd C. ~Ab b There were no absorbed liquids shipped during the reporting period.

4.1 Scalin Factor Nethodolo y Scaling factors are based on outside laboratory (TNA/Norcal) analysis of hard-to-measure nuclides. 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 "Radionuclide Correlations in Low Level Radwaste", HP-4037, June 1985 has been used as a basis for the determination of a scaling factor.

H-3 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.

C-14, Tc-99, I-129 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 concentration 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, Sr-90, Ni-63 TRU nuclides would be scaled to Ce-144. As recommended by the AIF report "Methodolgies for Classification of Low Level Radioactive Waste 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.

18

~ 0 Sampling of individual waste streams has been performed with analysis by an outside labortory. Cs-137 and Sr-90 were not available in sufficient concentrations to allow development of reliable 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 repor ted. Table 4-2 lists those scaling factors for the conditional nuclides that are reported only when the scaling nuclide is found to be present.

19

Table 4-1 Scalin Factors for Re uired Nuclides DAW RMCU CFD EDR/FDR EDR/FDR OIL Powder Resin Powder Resin Powder Resin Bead Resin Co-60/C-14 5.9 E-4 1.7 E-4 1.0 E-4 + 1.0 E-4 + 1.0 E-4 1.0 E-4 +

Cs-137/Tc-99 3.0 E-5 3.0 E-5 + 3.0 E-5 + 3.0 E-5 + 3.0 E-5 + 3.0 E-5 +

Cs-137/I-129 2.0 E-5 + 2.0 E-5 + 2.0 E-5 + 2.0 E-5 + 2.0 E-5 + 2.0 E-5 +

Rx Coolant/H-3 4.4 E-1 1.75 E-1 ++ 1.75 E-1 1.0 E-1 2.25 E-1 4.0 E-5 +++

Table 4-2 Scalin Factors for Conditional Nuclides DAM RMCU CFD EDR/FDR EDR/FDR OIL Powder Resin Powder Rs Powder Resin Bead Resin Co-60/Ni-63 6.5 E-2 9.0 E-3 4.0 E-2 1.8 E-1 1.7 E-2 2.0 E-2 +

Ce-144/Pu-238 8.0 E-3+ 8.0 E-3 + 8.0 E-3 + 8.0 E-3+ 8.0 E-3 + 8.0 E-3 +

Ce-144/Pu-239 5.0 E-3 + 5.0 E-3+ 5.0 E-3 + 5.0 E-3 + 5.0 E-3 + 5.0 E-3 +

Ce-144/Pu-241 5.5 E-1 + 5.5 E-1 + 5.5 E-1 + 5.5 E-1 + 5.5 E-1 + 5.5 E-1 +

Ce-144/Am-241 3.0 E-3 + 3.0 E-3 + 3.0 E-3 + 3.0 E-3 + 3.0 E-3 + 3.0 E-3 +

Ce-144/Cm-242 Ce-144/Cm-244 1.5 3.5 E-2 +

E-3+

1.5 3.5 E-2 +

E-3 +

1.5 3.5 E-2 E-3

+

+

1.5 3.5 E-2 +

E-3 +

1.5 3.5 E-2 +

E-3 +

1.5 3.5

~-~ +

E-3 +

~

Cs-137/Sr-90 6.0 E-3 + 6.0 E-3 + 6.0 E-3 + 6.0 E-3 + 6.0 E-3 + 6.0 E-3 +

+ Scaling Nuclide not present in enough concentration to make determination of scaling factor. In these cases the scaling factor obtained from the final EPRI Report "Radionuclide Correlations in Low Level Radwaste" (NP-.4037, June 1985), will continue to be used as the WNP-2 scaling factors.

++ The report from 1NA/Norcal, showed a concentration of H-3 in RWCU resin of 2.35 times the Rx Coolant H-3 concentration. The resin mix used in RWCU and CFD is the same and the reactor coolant and condensate H-3 concentration are approximately the same. The scaling factor for CFD powdered resins is 1.75 E-1 which is more representative of H-3 retention on the dried powdered resins.

+++ Oil is processed at MNP-2 by filtration and dewatering. This process removes the water from -oil.

The report from TMA/Norcal was less than 4.0 E-5 for H-3. The 4.0 E-5 factor was chosen and should be conservative in determining H-3 concentrations in oil.

Table 4-3 WNP-2 SOLID WASTE SHIPMENTS January - June 1987 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL

1. Type of Waste Waste Stream Unit 6-month lEst. Totall Period Error, %
a. Spent resins, filter sludges, m3 83. 7 evaporator bottoms, etc. Ci 658.305 20
b. Dry active waste, contaminated m3 122.3 e ui ., etc. Ci 2.336 20
c. Irradiated components, control m3 No Ship-rods, etc. Ci ment
d. Other, (absorbed aqueous liquid) m3 No Ship-Ci ment
2. Estimate of major nuclide composition (by type of waste):

'a ~ Dewatered Spent Resins uc de 0"

0-0-

  • Indicates scaled nuclide 21

'g Table 4-3 (Continu

b. Dry Active Wastes (DAW) uc 1 e n-2 Cr-1 20. 6 .4825 0" 6 0-5 Mn-54 4.71 0.1099 6 Nb-95 2. 7 4.822E-2 Ni -6 8 H-3* 0.501 1.171E-2
c. Irradiated Components - None
d. Other - Absorbed Liquids (None)
3. Solid Waste Disposition Number of Shi ments Mode of Trans ortation Destination 19 Flat bed trailer (5) US Ecology 14-210H Cask (13) Richland, WA 10-142 Cask (1)
8. IRRADIATED FVEL SHIPMENTS (Di sposition)

None

  • Indicates scaled nuclide 22

4.2 Process Control Pro ram 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 will be subjected to POC review prior to any solidification of radwaste.

Two Pacific Nuclear generic solidification PCP's, TP-O4, "Portable Solidification 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 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". No significant changes have occurred in these procedures during this reporting period.

23

( oe

5. 0 METEOROLOGY The meteorological data for the first half of calendar year 1987 will be included in the Semi-Annual Effluent Report due 60 days. after January 1, 1988 and will include data covering the full calendar year 1987.

24

~ 0 6.0 DOSE ASSESSMENT - IMPACT ON MAN The dose impact on man for the calendar year 1982 will be included in the Semi-Annual Effluent Report due 60 days after January 1, 1988.

~- '7 O'EVISIONS

~ 4l TO THE ODCM During this semi-annual reporting period, no revisions were made to the offsite Dose Calculation Manual (ODCM).

26

Washington Public Power Supply System 3000 George Washington Way P.O. Box 968 Richiand, Washington 99352-0968 (509)372-5000 August 18, 1987 G02-87-229 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Contr ol Desk Washington, D.C. 20555 Gentlemen:

Subject:

NUCLEAR PLANT NO. 2 SEMI-ANNUAL EFFLUENT REPORT JANUARY 1, 1987 TO JUNE 30, 1987 (ATIACHED)

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 Mr. R. G. Graybeal, Manager, WNP-2 Health Physics/Chemistry.

Very truly yours, C. M. Powers WNP-2 Plant Manager bk Attachment cc: RB Samworth - NRC C Eschels - EFSEC D Jaquish- DOE JB Martin NRC RV (2)

D Sherman Amer. Nuclear Insurers TR Strong - DSHS NRC Site Inspector

Washington Public Power Supply System 3000 George Washington Way P.O. Box 968 Richland, Washington 99352-0968 (509)372-5000 August 18, 1987 G02-87"229 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:

Subject:

NUCLEAR PLANT NO. 2 SEMI-ANNUAL EFFLUENT REPORT JANUARY 1, 1987 TO JUNE 30, 1987 (ATTACHED)

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 Mr. R. G. Graybeal, Manager, WNP-2 Health Physics/Chemistry.

Very truly yours, 47$ (4~

C. M. Powers WNP-2 Plant Manager bk Attachment cc: RB Samworth - NRC C Eschels - EFSEC D Jaquish- DOE JB Martin - NRC RV (2)=

D Sherman - Amer. Nuclear Insurers TR Strong - DSHS NRC Site Inspector

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