GO2-92-199, WNP-2 Semiannual Radioactive Effluent Release Rept Jan Through June 1992
| ML17289A807 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 06/30/1992 |
| From: | John Baker WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GO2-92-199, NUDOCS 9208240334 | |
| Download: ML17289A807 (49) | |
Text
D ~CEI.ERATED DISTRIBUTION DEMON%'RATIONSYSTEM DOCKET 0 FACIL: 50-397 NPPSS Nuclear Pro Ject Unit 2I Mashing ton Public Pace 05000397 AUTH. NAME AUTHOR AFFILIATION BAKERI J. N.
Nashington Public Poeer Supply System REC IP. NAME RECIPIENT AFFILIATION
SUBJECT:
"NNP-2 Semiannual Radioactive Effluent Release Rept Jan through June 3.992. "
/920818 l.tr.
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TITLE: 50. 36a ( a } (2)
Semi annual Effluent Release Rep orts NOTES:
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3 REC IP IENT ID CODE/NAME PD5 PD COPIES LTTR ENCL 1
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~r-/
WASHINGTONPUBLIC POWER SUPPLY SYSTEM P.O. Bax968 ~ 3000Georje Wasblnglon Way ~ Richland, Washington 99352<968
~ (509)372-5MO August 18, 1992 G02-92-199 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.C.
20555 Gentlemen:
Subject:
WNP-2, OPERATING LICENSE NPF-21 SEMI-ANNUAL EFFLUENT REPORT JANUARY 1, 1992 - JUNE 30, 1992 In accordance with Title 10 of the Code of Federal Regulations, Part 50.36a(a)(2),
and section 6.9. 1. 11 of the WNP-2 Technical Specifications the subject report is herewith being submitted.
Should you have any questions, please contact Mr. D. J. Pisarcik,
- Manager, WNP-2 Health Physics.
Sincerely, J.
W. Baker WNP-2 Plant Manager (Hail Drop 927M)
RFH/bk Attachment CC:
JB Hartin -
NRC RV
'S Reynolds
- Winston
& Strawn RR Assa NRC DL Williams - BPA/399 NRC Site Inspector
- 901A D Sherman
- American Nuclear Insurers TS Strong WDOH RG Waldo -
EFSEC 92082403341,920b30 PDR',
ADQCK '05000397 R,'DR
~840>8
REFERENCE:
WNP-2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY THROUGH JUNE 1992 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LICENSE NO. NPF-21
TABLE OF CONTENTS SECTION
1.0 INTRODUCTION
2.0 LIQUID EFFLUENTS 3.0 GASEOUS EFFLUENTS 4.0 SOLID RADWASTE 5.0 METEOROLOGY 6.0 DOSE ASSESSMENT IMPACT ON MAN 7.0 REVISIONS TO THE ODCM
~
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~
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1
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7 22 28 29 30 8.0 REVISIONS TO THE PROCESS CONTROL PROGRAM (PCP) 31 9.0 NEW OR DELETED LOCATIONS FOR DOSE ASSESSMENTS AND/OR ENVIRONMENTAL MONITORING LOCATIONS.
32 1 0 ~ 0 MAJOR CHANGES TO RADIOACTIVE LIQUID g GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 33 (RELBASB.RPT/RAD1)
LIST OF TABLES TABLE TABLE 2-1 WNP-2 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES REPORT PERIOD:
JANUARY JUNE 1992 TABLE 2-2 WNP-2 LIQUID EFFLUENTS SOURCE TERMS REPORT PERIOD:
JANUARY JUNE 1992 TABLE 2-2A LIQUID EFFLUENT RELEASE FOR PER 292-0671 TABLE 3-1 WNP-2 GASEOUS EFFLUENTS SOURCE TERMS MIXED MODE RELEASES MAIN PLANT VENT REPORT PERIOD:
JANUARY JUNE 1992 13 TABLE 3-2 WNP-2 GASEOUS EFFLUENTS SOURCE TERMS GROUND LEVEL RELEASES TURBINE GENERATOR BUILDING REPORT PERIOD:
JANUARY JUNE 1992 15 TABLE 3-3 WNP-2 GASEOUS EFFLUENTS SOURCE TERMS GROUND LEVEL RELEASES RADWASTE BUILDING REPORT PERIOD:
JANUARY JUNE 1992 18 TABLE 3-4 WNP-2 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES REPORT PERIOD:
JANUARY JUNE 1992 20 TABLE 3-5 WNP-2 GASEOUS EFFLUENTS BATCH RELEASES REPORT PERIOD:
JANUARY JUNE 1992 21 TABLE 4-1 REQUIRED NUCLIDES 24 TABLE 4-2 CONDITIONAL NUCLIDES 24 TABLE 4-3 WNP-2 SOLID WASTE SHIPMENTS JANUARY JUNE 1992 25 (RELEASE.RPI'/RAD1)
1.0 INTRODUCTION
This report is submitted in compliance with 10CFR50.36a(a)(2) and Technical Specification 6.9.1.11. It includes a summary of the quantities of radioactive liquid and gaseous effluents and solid radwaste released from WNP-2 during the previous six months of operation.
Effluent data is summarized on a quarterly basis.
2.0 LI UID EFFLUENTS The radwaste liquid effluents were released in "batch mode" during the reporting period. Sixteen (16) liquid batch releases occurred during the first calendar quarter and 53 batch releases were performed during the second calendar quarter.
The total time period for the batch releases was 134.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, with the maximum, minimum and average time periods for a release being 2.8, 1.3, and 1.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />, respectively.
The volume of dilution water considered is assumed to be the total volume of recirculating cooling tower blowdown flow for the period.
The average flow rate of the Columbia River during January through June 1992 was 1.1E+05 cubic feet per second.
Computer runs were performed to verify compliance with Offsite Dose Calculation Manual (ODCM) limits. The first quarter calculated dose for the maximum individual (adult age group) was 6.4E-03 mrem whole body and 9.1E-03 mrem for the maximum organ.
The second quarter calculated dose for the maximum individual (adult age group) was 2.5E-02 mrem whole body and 2.8E-02 mrem for the maximum organ.
The liquid batch releases were recirculated prior to sampling.
A representative sample was obtained and analyzed for each batch release.
A composite of the batch samples for each quarter was analyzed for strontium and iron.
The methods used for measuring the total radioactivity were gamma spectroscopy, liquid scintillation and proportional counting.
Table 2-1 provides a
summation of all liquid releases during this reporting period.
The percent of MPC limit in Table 2-1 is based on the total of the MPC fractions using the nuclides in Table 2-2 and the concentrations listed in 10CFR20, Appendix B, Table 2, Column 2.
Estimated total errors are listed in Table 2-1, and are propagated from individual error estimates of sample activityg sample volume, tank volume, and tank homogeneity.
The estimated total errors were calculated by obtaining the square root of the sum of the squares of the individual error contributions and multiplying by 1.96 for a 954 confidence level.
(RBLPAS8.RFf/RAD1)
There were two abnormal occurrences which were documented in the form of Problem Evaluation Requests (PER) for inclusion into this Semiannual Radioactive Effluent Release Report.
- PER, 292-0622, was issued for a liquid batch release
- sample, 1 of 24, which was found to be missing for inclusion into the monthly batch release composite.
- PER, 292-0671, was issued for a floor drain tank which was partially released to the effluent blowdown line prior to the completion of release sampling.
Refer to Table 2-2A for data content from this abnormal release.
There was no significant dose consequence to station personnel or the general public.
(RELEASE.RPT/RAD1)
TABLE 2-1 WNP-2 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES REPORT PERIOD:
JANUARY JUNE 1992 UNIT 1ST QUARTER 2ND QUARTER
- EST.
TOTAL ERROR A. FISSION AND ACTIVATION PRODUCTS TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES AND ALPHA)
AVG. DILUTED CONC.
DURING PERIOD PERCENT OF MPC LIMIT Ci uCi/ml 4.7E-03 4.9E-09 4.0E-02 6.5E-02 8.5E-08 2.4E-01 22%'.
TRITIUM TOTAL RELEASE AVG. DILUTED CONC.
DURING PERIOD PERCENT OF MPC LIMIT Ci uCi/ml 4.5E-01 4 'E-07 1.6E-02 2.6E+00 3.4E-06 1.1E-01 224 C.
DISSOLVED AND ENTRAINED GASES TOTAL RELEASE AVG. DILUTED CONC.
DURING PERIOD PERCENT OF MPC LIMIT Ci uCi/ml
<5.0E-04
<5.2E-10
<2.6E-04
<1.1E-04
<1.5E-10
<7.5E-05 224 D.
GROSS ALPHA RADIOACTIVITY TOTAL RELEASE Ci 1.5E-10 7.5E-11 234 E.
UNDILUTED EFFLUENT VOLUME VOLUME OF WATER (PRIOR LITERS TO DILUTION) 9.2E+05 3.0E+06 154 F.
DILUTION VOLUME VOLUME OF DILUTION WATER LITERS USED DURING PERIOD 9.6E+08 7.6E+08 15>o At 954 Confidence Level (RELEASE.RPT/RAD1)
TABLE 2-2 WNP-2 LIQUID EFFLUENTS SOURCE TERMS REPORT PERIOD:
JANUARY JUNE 1992 NUCLIDES RELEASED STRONTXUM-89 STRONTIUM-90 CESIUM-134 CESIUM-137 IODINE-131 UNIT Ci Ci Ci Ci Ci 1st QUARTER 6.1E-06 3.3E-06 5.1E-04 9.8E-04 5.9E-05 BATCH MODE 2nd QUARTER 9.3E-05 1.7E-05 1.4E-03 3.7E-03 9.1E-05 COBALT-58 COBALT-60 IRON-59 ZINC-65 MANGANESE-54 CHROMIUM-51 Ci Ci Ci Ci Ci Ci 8.1E-05 1.5E-03
<4.5E-05 7.7E-04 1.1E-04 3.8E-04, 1.8E-03 2.7E-02 3.3E-04 1.3E-02 1.5E-03 1.3E-02 ZIRCONIUM/NIOBIUM-95 MOLYBDENUM-99 TECHNETIUM-99m BARIUM/LANTHANUM-140 CERIUM-141 CERIUM-144 IRON-55 Ci, Ci Ci Ci Ci Ci Ci
<4.9E-05 3.6E-05
<3.5E-04
<9.1E-05
<4.1E-05
<1.5E-04 4.3E-05 3.1E-04
<7.5E-04
<5.3E-04
<1.8E-04
<7.0E-05
<2.6E-04 2.5E-03 (RBLBAS8.RPI'/RAD1)
TABLE 2-2 (Continued)
BATCH MODE NUCLIDES RELEASED OTHERS UNIT 1ST QUARTER 2ND QUARTER SODIUM-24 SILVER-110m Ci Ci 2.5E-04
<7.7E-05
<3.3E-05 2.6E-04 TOTAL FOR PERIOD ABOVE:
Ci 4.7E-03 6.5E-02 XENON-133 XENON-135 Ci Ci
<1. 4E-04
<3.6E-04
<7.1E-05
<4.2E-05 TRITIUM (HYDROGEN-3)
Ci 4.5E-01 2.6E+00 Note: Less than
(<) values are not included in the Total For Period values.
(RELEASE.RPT/RAD1)
TABLE 2-2A LIQUID EFFLUENT RELEASE FOR PER 292-0671 NUCLIDES RELEASED STRONTIUM-89 STRONTIUM-90 COBALT-58 COBALT-60 ZINC-65 MANGANESE-54 IRON-55 JUNE 92 Ci 1.9E-06 Ci 3.5E-07 Ci 2.1E-05 Ci 6.7E-04 Ci 1.9E-04 Ci 3.9E-05 Ci 5.1E-05 TRITIUM (HYDROGEN-3)
Ci 4.3E-01 TOTAL Ci 4.3E-01 TOTAL DISCHARGED COOLING TOWER BLOWDOWN FLOWRATE DISCHARGED TIME (Liters)
(Liters/min)
(Hours) 6.0E+04 5.9E+03 2 ~ 1 TOTAL FISSION AND ACTIVATION PRODUCTS:
Total Release (Ci)
Diluted Concentration (uCi/ml)
Percent of MPC Limit 9.4E-04 1.3E-06 3.5E+00 TRITIUM:
Total Release Diluted Concentration Percent of MPC Limit (Ci)
(uCi/ml) 4.3E-01 5.8E-04 1.9E+01 CALCULATED DOSE (Adult Age Group)
Whole Body Organ (mrem)
,(mrem) 6.8E-05 1.3E-04 (RELEASE.RFf/RAD1)
3.0 GASEOUS EFFLUENTS The gaseous radwaste effluents from WNP-2 were released from three (3) release points:
1.
Main Plant Vent 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, 3-2, and 3-3. Table 3-4 provides a summation of the total activity released, the average release rate, the percent of ODCM 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. Particulates and iodines are sampled using particulate filters and charcoal cartridges.
Both are analyzed using gamma spectroscopy.
Total error estimates are propagated from individual error estimates of sample volume, sample activity and effluent flow rate measurements.
The overriding uncertainty in all cases is in the measurement of the effluent and sample volumes.
The estimated error was determined to be 364 at the 954 confidence level.
The percent of ODCM limit for fission and activation gases (air dose) was determined for locations 1 through 8 and was based on quarterly limits of ten (10) millirads for beta and five (5) millirads for gamma.
Locations 1 through 8 were used to determine the most restrictive value to be used in Table 3-4, Section A.3.
The percent of ODCM limit calculations for iodines, particulates with half-lives greater, than eight (8) days and tritium are based on the quarterly limit of '7.5 mrem to any organ.
Locations 4
through 8 were used to determine the most restrictive value to be used in Table 3-4 for each quarter.
Calculations were performed for releases using the NRC GASPAR II computer program and parameters as outlined in the ODCM.
Quarterly doses were determined at the following locations:
(RELEASB.RFf/RADAR)
Location 1:
Site Boundary; 1.2 miles (ground and inhalation pathways)
QUANTITY 1ST QUARTER 2ND QUARTER BETA AIR DOSE PERCENT OF ODCM LIMIT mrad 5.7E-02 5.7E-01 8.5E-04 8.5E-03 GAMMA AIR DOSE PERCENT OF ODCM LIMIT mrad 3.9E-02 7.8E-01 6.4E-04 1.3E-02 HIGHEST ORGAN DOSE PERCENT OF ODCM LIMIT mrem 5.8E-02 7.7E-01 1.6E-02 2.1E-01 Location 2:
Beyond Site Boundary; 3.9 and 3.3 miles ESE, respectively (ground and inhalation pathways) at the location having the highest X/Q values for mixed mode releases.
QUANTITY UNIT 1ST QUARTER 2ND QUARTER BETA AIR DOSE PERCENT OF ODCM LIMIT mrad 7.9E-03 7.9E-02 7.5E-05 7.5E-04 GAMMA AIR DOSE PERCENT OF ODCM LIMIT mrad 5.4E-03 1.1E-01 7.3E-05 1.5E-03 HIGHEST ORGAN DOSE PERCENT OF ODCM LIMIT mrem 9.0E-03 1.2E-01 2.5E-03 3.3E-02 (RELEASE.RFf/RAD1)
Location 3:
Beyond Site Boundary; 3 miles ESE for the first and second quarters, respectively (ground and inhalation pathways) at the location having the highest X/Q values for ground level release mode.
QUANTITY UNIT 1ST QUARTER 2ND QUARTER BETA AIR DOSE PERCENT OF ODCM LIMIT mrad
- 1. 3E-02
- 1. 3E-01 7.7E-05 7.7E-04 GAMMA AIR DOSE PERCENT OF ODCM LIMIT mrad 9.9E-03 2.0E-01 7.1E-05 1.4E-03 HIGHEST ORGAN DOSE PERCENT OF ODCM LIMIT mrem 1.1E-02 1.5E-01 2.8E-03 3.7E-02 Location 4:
4.5 miles ESE (ground, vegetables and inhalation pathways)
QUANTITY UNIT 1ST QUARTER 2ND QUARTER BETA AIR DOSE PERCENT OF ODCM LIMIT mrad 5.9E-03 5.9E-02 3.9E-05 3.9E-04 GAMMA AIR DOSE PERCENT OF ODCM LIMIT mrad 4.0E-03 8.0E-02 3 'E-05 6.6E-04 HIGHEST ORGAN DOSE PERCENT OF ODCM LIMIT mrem 1.4E-02 1.9E-01 5.0E-03 6.7E-02 (RELEASE.RFf/RAD1)
IYE
Location 5:
6.4 miles SE (ground,
- meat, cow milk and inhalation pathways)
QUANTITY UNIT 1ST QUARTER 2ND QUARTER BETA AIR DOSE PERCENT OF ODCM LIMIT mrad 2.6E-03 2.6E-02 4.4E-05 4.4E-04 GAMMA AIR DOSE PERCENT OF ODCM LIMIT mrad 1.8E-03 3 'E-02 3.8E-05 7.6E-04 HIGHEST ORGAN DOSE PERCENT OF ODCM LIMIT mrem 6.0E-03 8.0E-02 9.1E-03 1.2E-01 Location 6:
4.1 miles ESE (ground, vegetables and inhalation pathways)
QUANTITY BETA AIR DOSE PERCENT OF ODCM LIMIT mrad 1ST QUARTER 8.2E-03 8.2E-02 2ND QUARTER 5.2E-05 5.2E-04 GAMMA AIR DOSE PERCENT OF ODCM LIMIT mrad 5.7E-03 1.1E-01 5.2E-05 1.0E-03 HIGHEST ORGAN DOSE PERCENT OF ODCM LIMIT mrem'.8E-02 2.4E-01 6.0E-03 8.0E-02 (RELBASB.RFZ/RAD1) 10
Location 7:
4.3 miles NE (ground and inhalation pathways)
QUANTITY UNIT 1ST QUARTER 2ND QUARTER BETA AIR DOSE PERCENT OF ODCM LIMIT mrad 1.6E-03 1.6E-02 3.5E-05 3.5E-04 GAMMA AIR DOSE PERCENT OF ODCM LIMIT mrad 1.1E-03 2.2E-02 2.8E-05 5.6E-04 HIGHEST ORGAN DOSE PERCENT OF ODCM LIMIT mrem 1.8E-03 2.4E-02 8.0E-04 1.1E-02 Location 8:
4.1 miles ENE; (ground, vegetables and inhalation pathways)
QUANTITY UNIT 1ST QUARTER 2ND QUARTER BETA AIR DOSE PERCENT OF ODCM LIMIT mrad 3.1E-03 3.1E-02 3.6E-05 3.6E-04 GAMMA AIR DOSE PERCENT OF ODCM LIMIT mrad 2.0E-03 4.0E-02 3 'E-05 6.6E-04 HIGHEST ORGAN DOSE PERCENT OF ODCM LIMIT mrem 6.9E-03 9.2E-02 3.2E-03 4.3E-02 (RELEASE.RFf/RAD1)
1 Zn addition to the reactor facility, WNP-2 has a permanent laundry facility located approximately 0.75 miles from the reactor building.
Its ventilation system contains HEPA filters on the discharge and is continuously monitored for particulates.
Also, the backup chemistry laboratory within the Emergency Operations Facility (EOF) is located adjacent to the laundry facility. The radiochemical hood within the backup chemistry lab contains HEPA filters and is monitored for radioactive releases when in operation.
Gamma spectrometry indicated no radioactive material present other than that attributable to natural background.
There were no abnormal releases of gaseous effluent during the first and second quarters of 1992.
(RELBASB.RPT/RAD1) 12
TABLE 3-1 WNP-2 GASEOUS EFFLUENTS SOURCE TERMS MIXED MODE RELEASES MAIN PLANT VENT REPORT PERIOD:
JANUARY JUNE 1992 CONTINUOUS MODE 1.
FISSION/ACTIVATION GASES NUCLIDES RELEASED UNIT 1ST QUARTER 2ND QUARTER KRYPTON-85 KRYPTON-85m KRYPTON-87 KRYPTON-88 XENON-133 XENON-133m XENON-135 XENON-135m XENON-138 OTHERS XENON-137 ARGON-41 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci
<1. 3E-01
<2.8E+01
<5.3E-01
<8.6E-01 1.8E+00
<2.1E+00 7.3E+00 3.6E+00 3.0E+00 7.2E-01 8.2E-02
<1.7E-01
<8.7E+00
<4.4E-01
<5.2E-01 1.3E-01
<1.1E+00 1.5E-01 4.7E-01 1.3E+00
<6.4E+00 9.0E-02 TOTAL FOR PERIOD ABOVE:
Ci 1.7E+01 2.1E+00 2.
IODINES NUCLIDES RELEASED UNIT 1ST QUARTER 2ND QUARTER IODINE-131 IODINE-132 IODINE-133 IODINE-134 IODINE-135 Ci Ci Ci Ci Ci 8.'3E-04 2.6E-04 2.3E-03
<1.4E-03
<7.0E-04 9.0E-04
<2.2E-04 2.2E-03
<1.4E-03
<7.0E-04 TOTAL FOR PERIOD ABOVE:
Ci 3.4E-03
- 3. 1E-03 (RBLPASE.RPf/RAD1) 13
1
't
3.
PARTICULATES NUCLIDES RELEASED TABLE 3-1 (Continued)
UNIT 1ST QUARTER 2ND QUARTER STRONTIUM-89 STRONTIUM-90 CESIUM-134 CESIUM-137 BARIUM/LANTHANUM-140 MOLYBDENUM-99 CERIUM-141 CERIUM-144 COBALT-58 COBALT-60 IRON-59 MANGANESE-54 ZINC-65 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 2.1E-05 2.4E-06 7.0E-05
<1.3E-04 1.0E-02
<7.3E-04
<7.6E-05
<2.1E-04
<1.0E-04
<2.4E-04
<3.8E-04
<1.3E-04
<2.6E-04 1.2E-04 8.1E-06 8.9E-05 1.6E-04 1.4E-04
<9.3E-04
<1.4E-04
<5.2E-04
<1.0E-04 1.6E-03
<3.5E-04
<1.3E-04 1.5E-04 TOTAL FOR PERIOD ABOVE:
Ci 1.0E-02 2.3E-03 OTHER PARTICULATES WITH T 1/2 8
DAYS NUCLIDES RELEASED UNIT 1ST QUARTER 2ND QUARTER STRONTIUM-91 CESIUM-138 BARIUM-139 Ci Ci Ci 4.8E-05 1.1E-02 3.6E-02 1.1E-05 2.6E-03 4.9E-03 TOTAL (T 1/2 <8 DAYS):
Ci 4.7E-02 7.5E-03 4.
TRITIUM NUCLIDES RELEASED TRITIUM (HYDROGEN-3)
UNIT Ci 1ST QUARTER 8.0E-01 2ND QUARTER 1.5E+00 TOTAL BUILDING RELEASE:
Ci 1.7E+01 3.6E+00 Note:,Less than
(<) values and particulates with T 1/2 8 days are not included in Total Building Release values.
(RELEASE.RF1'/RADI) 14
TABLE 3-2 WNP-2 GASEOUS EFFLUENTS SOURCE TERMS GROUND LEVEL RELEASES TURBINE GENERATOR BUILDING REPORT PERIOD:
JANUARY JUNE 1992 CONTINUOUS MODE 1.
FISSION/ACTIVATION GASES NUCLIDES RELEASED UNIT 1ST QUARTER 2ND QUARTER KRYPTON-85 KRYPTON-85m KRYPTON-87 KRYPTON-88 XENON-133 XENON-133m XENON-135 XENON-135m XENON-138 OTHERS NONE Ci Ci Ci Ci Ci Ci Ci Ci Ci
<3.8E-01
<8.5E+01
<8.3E-01
<9.2E-01 1.2E+Ol
<3.8E+00 2.7E+01 3.8E+00 3.1E+00
<5.1E-01
<9.2E+01
<7.7E-01
<7 'E-01
<5.1E-01
<3.1E+00 2.1E-01 2.8E-01 6.8E-01 TOTAL FOR PERIOD ABOVE:
Ci 4.6E+01 1.2E+00 2.
IODINES NUCLIDES RELEASED IODINE-131 IODINE-132 IODINE-133 IODINE-134 IODINE-135 UNIT Ci Ci Ci Ci Ci 1ST QUARTER 1.4E-03 6.9E-03 1.2E-02 7.5E-04 2 'E-02 2ND QUARTER 1.1E-03
<2.4E-04 1.9E-03
<6 'E-04 2.3E-02 TOTAL FOR PERIOD ABOVE:
Ci 4.1E-02 2.6E-02 (RELEASE.RP1'IRAD 1) 15
3.
PARTICULATES TABLE 3-2 (continued)
NUCLIDES RELEASED UNIT 1ST QUARTER 2ND QUARTER STRONTIUM-89 STRONTIUM-90 CESIUM-134 CESIUM-137 BARIUM/LANTHANUM-140 MOLYBDENUM-99 CERIUM-141 CERIUM-144 COBALT-58 COBALT-60 IRON-59 MANGANESE-54 ZINC-65 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 6.0E-04
<3.5E-06
<2.4E-04
<3.2E-04 1.2E-02
<2.3E-03
<2.7E-04
<6.6E-04
<2.9E-04
<3.5E-04
<6.8E-04
<2.4E-04
<5.2E-04 1.1E-03
<2.7E-06
<1.8E-04
<2.5E-04 1.1E-03
<1.8E-03
<2.1E-04
<5.1E-04
<2.2E-04
<2.7E-04
<5.2E-04
<1.8E-04
<4.0E-04 TOTAL FOR PERIOD ABOVE:
Ci 1.3E-02 2.2E-03 OTHER PARTICULATES WITH T 1/2 8
DAYS NUCLIDES RELEASED UNIT 1ST QUARTER 2ND QUARTER RUBIDIUM-89 STRONTIUM-91 STRONTIUM-92 CESIUM-138 BARIUM-139 Ci Ci Ci Ci Ci 9.,4E-04 1.4E-03 1.4E-02 1.8E+00 7.5E-01 2.5E-04 1.5E-04
<2.8E-04 2.2E-01 1.9E-01 TOTAL (T 1/2 <8 DAYS):
Ci 2.6E+00 4.1E-01 (RBLEASB.RP1'/RAD1) 16
4.
TRITIUM TABLE 3-2 (continued)
NUCLIDES RELEASED TRITIUM (HYDROGEN-3)
UNITS Ci 1ST QUARTER 5.6E+00 2ND QUARTER 5.4E-01 TOTAL BUILDING RELEASE Ci 5.2E+01 1.7E+00 Note: Less than
(<) values and particulates with T 1/2
< 8 days are not included in the Total Building Release values.
(RBLBASB.RPI'/RAD1) 17
I
)
I II 1
TABLE 3-3 WNP-2 GASEOUS EFFLUENTS SOURCE TERMS GROUND LEVEL RELEASES RADWASTE BUILDING REPORT PERIOD JANUARY JUNE 1992 CONTINUOUS MODE 1.
FISSION/ACTIVATION GASES NUCLIDES RELEASED KRYPTON-85 KRYPTON-85m KRYPTON-87 KRYPTON-88 XENON-133 XENON-133m XENON-135 XENON-135m XENON-138 OTHERS NONE UNIT Ci Ci Ci Ci Ci Ci Ci Ci Ci 1ST QUARTER
<3.2E+01
<1.1E-01
<1.3E+00
<3.2E+00 3.6E+00
<6.3E+00 3.8E+00 8.3E+00 1.9E-01 2ND QUARTER
<3.9E+01
<1.4E-01
<4.2E-01
<5.3E-01 1.1E+00
<7.3E-01 8.2E-01
- 1. 2E+00
- 1. 8E-01 TOTAL FOR PERIOD ABOVE:
Ci 1.6E+01 3.3E+00 2.
IODINES NUCLIDES RELEASED UNIT 1ST QUARTER 2ND QUARTER IODINE-131 IODINE-132 IODINE-133 IODINE-134 Ci Ci Ci Ci 1.2E-04 7 'E-05 3.1E-04 3.3E-05 5 'E-05 2 'E-05 8.0E-05
<3.9E-04 IODINE-135 Ci '
2.5E-05 3.1E-05 TOTAL FOR PERIOD ABOVE:
Ci 5.7E-04 1.9E-04 (RELEASE.RFf/RADAR) 18
3.
PARTICULATES TABLE 3-3 (Continued)
NUCLIDES RELEASED STRONTIUM-89 STRONTIUM-90 CESIUM-134 CESIUM-137 BARIUM/LANTHANUM-140 MOLYBDENUM-99 CERIUM-141 CERIUM-144 COBALT-58 COBALT-60 IRON-59 MANGANESE-54 ZINC-65 UNIT Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 1ST QUARTER 2.8E-05
<4.7E-06
<4.9E-05
<5.5E-05
<1.3E-04
<5.2E-04
<4.5E-05
<1.7E-04
<4.2E-05
<7.7E-05
<1.5E-04
<4.3E-05
<1.0E-04 2ND QUARTER 2.4E-05
<3.7E-06
<3.1E-05
<3.2E-05
<9.0E-05
<3.6E-04
<2.7E-05
<9.0E-05
<2.6E-05
<5.1E-05
<8 'E-05
<2.5E-05
<6.4E-05 TOTAL FOR PERIOD ABOVE:
Ci 2.8E-05 2.4E-05 OTHER PARTICULATES, WITH T 1/2 8
DAYS NUCLIDES RELEASED NONE UNIT
'1ST QUARTER 2ND QUARTER Ci TOTAL (T 1/2
<8 DAYS):
Ci NA NA 4.
TRITIUM NUCLIDES RELEASED UNITS 1ST QUARTER 2ND QUARTER TRITIUM (HYDROGEN-3)
Ci
- 4. OE-02 2.6E-01 TOTAL BUILDING RELEASE:
Ci
- 1. 6E+Ol 3.6E+00 Note: Less than
(<) values are not included in the Total Building Release value.
(RBLEASB.RPI'/RAD1) 19
I 4 j l'
TABLE 3-4 WNP-2 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES REPORT PERIOD:
JANUARY JUNE 1992 UNITS 1ST QUARTER 2ND QUARTER
- EST.
TOTAL ERROR A.
FISSION AND ACTIVATION GASES 1.
TOTAL RELEASE 2.
AVG. RELEASE RATE FOR PERIOD 3.
PERCENT OF ODCM LIMIT Ci uCi/sec
- 7. 8E+01
- 1. OE+01 7.8E-01 6.6E+00 8.4E-01 1.3E-02 36%
B.
IODINES 1.
TOTAL IODINE RELEASE 2.
AVG. RELEASE RATE FOR PERIOD 3.
PERCENT OF ODCM LIMIT Ci uCi/sec 4.5E-02 5.7E-03 2.4E-01 2.9E-02 3.7E-03 1.2E-01 364 C.
PARTICULATES 1.
TOTAL PARTICULATE RELEASE 2.
AVG. RELEASE RATE FOR PERIOD 3.
PERCENT OF ODCM LIMIT 4.
GROSS ALPHA ACTIVITY Ci uCi/sec Ci 2.3E-02 2.9E-03 2.4E-01 8.3E-04 4.5E-03 5.7E-04 1.2E-01 6.6E-04 364 D.
TRITIUM 1.
TOTAL TRITIUM RELEASE 2.
AVG. RELEASE RATE FOR PERIOD 3.
PERCENT OF ODCM LIMIT Ci uCi/sec 6.4E+00
- 8. 2E-01 2.4E-01 2.3E+00 2.9E-01 1.2E-01 36%
- At 95'onfidence level (RELEASE.RPf/RADI) 20
TABLE 3-5 WNP-2 GASEOUS EFFLUENTS BATCH RELEASES REPORT PERIOD:
JANUARY JUNE 1992 TYPE NUMBER TOTAL TIME (hr)
MAXIMUM MINIMUM TIME TIME (hr)
(hr)
MEAN TIME (hr)
PURGE
- 17. 3 7.3 3.1 5.8 VENT 30 32.5 3.1 0.5 1.1 (RBLBASB.RPT/RAD1) 21
4.0 SOLID RADWASTE A total volume of 6194.6 ft (175.3 m ) of solid waste was transported in 27 shipments during the January through June 1992 reporting period.
The reported volumes are the disposal volumes of the containers shipped for burial.
The total activity of the waste shipped was 470 Ci; 469.4 Ci was contained in dewatered spent resins, 0.325 Ci was contained in DAW and 0.235 Ci was contained in solidified liquids.
A.
Dewatered S ent Resin Dewatered resins accounted for 3194.6 ft (90.4 m ) of the radioactive wastes shipped during the reporting period.
The burial containers were ES-190, EL-142 and EA-142 liners provided by NUPAC Services, Inc. The total activity of the resins shipped during the reporting period was 469.4 Ci. The principal 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 NUPAC 10-142 or NUPAC 14-210 casks.
The counting error associated with the total activity has consistently been found to be less than 3.0% at one standard deviation for previous reporting periods.
The statisti'cal counting error is assumed to be 3.04 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 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 gamma spectroscopy calibration error is approximately 54.
The best estimate of the total error in the activity of spent resin shipped is assumed to be less than or equal to 254.
B.
Dr Active Waste DAW A total of 2775 ft'78.5 m') of DAW was shipped in Container Products Corporation B-25 boxes or NUPAC Services ES-190 encapsulation liners.
The total activity of the DAW shipped was 0.325 Ci.
The value of the activity shipped was determined by using computerized dose rate-to-Curie conversion factors.
The conversion factors were based on a nuclide distribution taken from analysis of contamination found in the major DAW production areas.
This distribution is updated annually in conjunction with offsite analyses of hard-to-measure nuclides.
A meaningful counting error cannot be generated for DAW; however, the total error may be assumed to be less than or equal to 254, since DAW would be subjected to similar error contributions as spent resin.
/%LEASE.RFf/RADAR) 22
C.
Other Waste A total of 225 ft (6.4 m ) of aqueous liquid was solidified using an approved solidification agent (Aquaset) and was shipped for bur'ial in Type A, 17H or 17C drums.
The total activity was 0.235 Ci.
The activity was determined by using computerized dose rate-to-Curie conversion factors.
The isotopic distribution for this waste was a composite consisting of DAW scaling factors for C-14, Tc-99, I-129 and Fe-55, plus 'an in-house measured Tritium (H-3) and gamma isotopic distribution for reactor coolant (decayed 30 days).
The distribution will be updated annually in conjunction with offsite analyses of hard-to-measure nuclides.
This distribution is subject to the same error components as resins and DAW. Therefore, the total error may be assumed to be less than or equal to 25%.
4.1 Scalin Factor Methodolo Scaling factors are based on outside laboratory (SCIENTECH Inc.
formerly SAIC) analysis of hard-to-measure nuclides.
Scaling factors are updated on an annual basis or when triggered by an order of magnitude change in corrosion to fission product ratios (Co-60/Cs-137) in the resin waste streams, as compared to the previous offsite analysis.
C-14 Ni-63 Fe-55 The ratio of each of these nuclides to Co-60 is determined after outside laboratory analysis of each waste stream.
The resulting scaling factors are applied to the measured Co-60 concentration for a particular batch or container of radwaste to arrive at the C-14, Ni-63 and Fe-55 concentrations.
H-3 Tc-99 I-129 Sr-90 The ratio of each of these nuclides to Cs-137 is determined after outside laboratory analysis of each waste stream.
The resulting scaling factors are applied to the measured Cs-137 concentration for a particular batch or container of radwaste to arrive at the H-3, Tc-99, I-129 and Sr-90 concentrations.
Transuranics The ratio of hard to measure TRU nuclides to Ce-144 is determined after outside laboratory analysis of each waste stream, as recommended by the AIF report, "Methodologies for Classification of Low Level Radioactive Waste for Nuclear Power Plants."
These nuclides will be reported if Ce-144 is detected and TRU nuclides have been detected by outside laboratory analyses.
TRU nuclides include Pu-239, Pu-238, Pu-241, Am-241, Cm-242 and Cm-244.
Outside laboratory LLDs must be at least 1 nCi/g for TRU, 35 nCi/g for PU-241 and 200 nCi/g for Cf-242.
(RELBAS8.RFI'/RAD1) 23
f I
t E
RATIO SCALING FACTORS TABLE 4-1 RE UIRED NUCLIDES RWCU CFD EDF/FDR EDR/FDR POWDER POWDER POWDERED BEAD DAW RESIN RESIN RESIN RESIN H-3/
CS-137 1.97E+00*
1.88E-06*
6.34E-02*
1.07E-04*
1.27E-02*
C-14/
CO-60 2.25E-03*
8.63E-06 1.32E+00 2.61E-04 3.20E-03 Tc-99/
Cs-137 I-129/
Cs-137 3.11E-01*
4.02E-01*
1.37E-06*
8.76E-03*
9.82E-06*
1.44E-05*
1.24E-02*
8.04E-06*
2.97E-03*
2.41E-03*
Scaling factor based on LLD value.
TABLE 4-2 CONDITIONAL NUCLIDES RATIO DAW RWCU POWDER RESIN CFD EDF/FDR EDR/FDR POWDER POWDERED BEAD RESIN RESIN RESIN Ni-63/Co-60 Fe-55/Co-60 Sr-90/Cs-137 NOTE 1 2.36E-01 NOTE 1
- 5. 12E-03 9.83E-02 1.30E-02 3.32E-02 1.84E-01 2.23E-01 2.46E-01 1.92E-01 2.81E-03 NOTE 1 NOTE 1 4.84E-02 Pu-239,240
/Ce-144 Pu-238/Ce-144 Pu-241/Ce-144 NOTE 1
NOTE 1
NOTE 1
9.65E-02 4.70E-02 5.50E+00 NOTE 1 NOTE 1 NOTE 1 2.60E-03
- 7. 03E-03 2.14E-01 NOTE 1 NOTE 1 NOTE 1 Am-241/Ce-144 Cm-242/Ce-144 Cm-243,244/
Ce-144 NOTE 1
NOTE 1 NOTE 1
8.29E-03 9.25E-03 1.13E-02 2.56E-04 NOTE 1 7.80E-03 2.75E-02 4.08E-04 NOTE 1 NOTE 1 NOTE 1 NOTE 1 NOTE 1:
Isotope not identified by offsite laboratory analysis.
(RBLEASB.RFf/RAD1) 24
TABLE 4-3 WNP-2 SOLID WASTE SHIPMENTS JANUARY JUNE 1992 A.
SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL 1.
Type of Waste a ~
Waste Stream Spent resins, filter sludges, evaporator bottoms, etc.
Unit m'i 6-month Period 90 '
469.4 Est. Total Error 4 25 b.
Dry active waste, contaminated equip., etc.
m Ci 78.5 0.325 25 c ~
Irradiated components, control
- rods, etc.
m'i No Shipment d.
- Other, (absorbed aqueous liquid) m Ci 6.4 0.235 25 (RELEASE.RFF/RAD1) 25
2 ~
Estimate of major nuclide composition (by type of waste):
a.
Dewatered Spent Resins **
Nuclide Zn-65 Co-60 Cr-51 Cs-137 Cs-134 Fe-55*
Co-58 Sr-89 Mn-54 Ni-63*
Ce-144 Ba/La-140 37.3 28.5 7.6 4.9 4.2 4.0 2 '
2.4 2.1 1.5 1.5 1.2 Ci 175 134 35.5 23 '
19.8 18.8 12.7 11.4 9.84 7.23 6'7 5.49
- Xndicates scaled nuclide
- Nuclides contributing 1 percent (4) of total are not listed.
b.
Dry Active Waste (DAW) **
Nuclide Co-60 Fe-55*
Zn-65 Sb-125 Mn-54 72.6 17.1
'.8 2.3 1.2 Ci 0.236 0.056 0.022 0.008 0.004
- Indicates scaled nuclide
- Nuclides contributing 1 percent (4) of total are not listed.
(RELEASE.RPT/RAD1)
C ~
d.
Irradiated Components None Other Waste Solidified Liquids **
Nuclide Co-60 Zn-65 Cr-51 H-3 Fe-55*
Co-58 Mn-54 33.0 23.5 16.3 13.5 7.9 2 '
1.3 Ci 0.078 0.055 0.038 0.032 0.018 0.007 0.003
- Indicates Scaled Nuclide
- Nuclides contributing
< 1 percent (4) of total are not listed.
3 ~
Solid Waste Disposition Number of Shi ments Mode of Trans ortation Destination 27 10-142 Cask (9)14-210 Cask (12)
Flatbed (6)
US Ecology Richland,WA (RELEASE.RPT/RADAR) 27
5.0 METEOROLOGY The meteorological data for the first half of calendar year 1992 will be included the Semiannual Radioactive Effluent Release Report due 60 days after January 1,
- 1993, and will include data covering the full calendar year 1992.
A planned outage of the main meteorological tower occurred during the 2nd Quarter 1992 driven by the WNP-2 computer outage.
(RBLBASB.RFf/RADI) 28
6.0 DOSE ASSESSMENT IMPACT ON MAN The dose impact on man for the Calendar Year 1992 will be included in Semiannual Radioactive Effluent Release Report due 60 days after January 1,
1993.
(RELEASE.RFf/RAD1) 29
7.0 REVISIONS TO THE ODCM During this reporting period there were no amendments to the Offsite Dose Calculation Manual (ODCM) reviewed and accepted by the Plant Operations Committee (POC) and approved by the Plant Manager.
(RBLBASB.RFf/RAD1) 30
~ 0$
C
)
8.0 REVISIONS TO THE PROCESS CONTROL PROGRAM PCP There have been no significant changes to the Process Control Program (PCP) during the reporting period.
The PCP implementing procedure (PPM 1.12.2) was revised to provide clarity effective 01/20/92.
(RBLEASB.RFf/RAD1) 31
9.0 NEW OR DELETED LOCATIONS FOR DOSE ASSESSMENTS AND OR ENVIRONMENTAL MONITORING LOCATIONS 9.1 Locations where GASPAR II dose calculations were performed for the first and second quarters of 1992:
9.1.1 4.5 miles east southeast (ESE) for the highest organ dose using ground, vegetation and inhalation pathways.
9.1.2 6.4 miles southeast (SE) for the highest organ dose using ground,
- meat, cow milk, and inhalation pathways.
9.1.3 4.1 miles east southeast (ESE) for the highest organ dose using ground, vegetable and inhalation pathways.
9.1.4 4.3 miles northeast (NE) for the highest organ dose using ground and inhalation pathways.
9.1.5 4.1 miles east northeast (ENE) for the highest organ dose using ground, vegetable and inhalation pathways.
9.2 Environmental monitoring locations which have been added during this reporting period are as follows.
- 9. 2. 1 Station 59,
- 9. 6 miles SE, milk sampling was re-established at this location.
9.2.2 Station ST 101/
0'3 miles ENE, storm drain; this location will be sampled for water, sediment, soil and vegetation.
9.2.3 Station ST 102, 0.36 miles SE, sanitary waste treatment facility; this location will be sampled for water and sediment.
9.2.4 Station ST 118, 0.27 miles S, protected storage area; this location will be sampled for soil.
9.3 Station 61, 6.5 miles SE, was discontinued as a TLD and cherry sampling location during this reporting period at the owner's request.
(RELEASB.RFf/RADAR) 32
10.0 MAJOR CHANGES TO RADIOACTIVE LI UID GASEOUS AND SOLID WASTE TREATMENT SYSTEMS No major changes were made to the radioactive waste systems (liquid, gaseous, or solid) during this reporting period.
gtBLBASB.RPf/RAD1) 33