ML17304B053
| ML17304B053 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/31/1988 |
| From: | Karner D ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 161-01722-DBK, 161-1722-DBK, NUDOCS 8903090387 | |
| Download: ML17304B053 (336) | |
Text
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ACCESSION NBR:8903090387 DOC.DATE: NOTARIZED: NO DOCKET g FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530 AUTH. NAME AUTHOR AFFILIATION KARNER,D.B.
RECIP.NAME Arizona Nuclear Power i
RECIPIENT AFFILIATION EST "* "='s Project (formerly Arizona Public Serv R
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SUBJECT:
"Palo Verde Nuclea DISTRIBUTION CODE: IE4SD TITLE: 50.36a(a)(2)
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Arizona Nuclear Power Project P.O. BOX 52034 ~ PHOENIX, ARIZONA85072-2034 161-01722-DBK/GEC March 1, 1989 Docket Nos. STN 50-528/529/530 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station Pl-137 Washington, DC 20555
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2, and 3 Semiannual Radioactive Effluent Release Report File: 89-A-056-026 Pursuant to 10CFR50.36a(a)(2), and in accordance with Technical Specification 6.9.1.8,. attached please find the Semiannual Radioactive Effluent Release Report
~ ~ ~
for the Palo Verde Nuclear Generating Station Units No. 1, 2, and 3 for the six month period ending December 31, 1988.
If you have any questions, please contact Mr. A. C. Rogers at (602) 371-4041.
Very truly yours, D. B. Karner Executive Vice President DBK/GEC/vlb Attachment cc: G. W. Knighton (all w/a)
M. J. Davis T. L. Chan J. B. Martin T. J. Polich
PALO VERDE NUCLEAR GENERATING STATION UNITS 1, 2 AND 3 SEMI-ANNUALRADIOACTI'VE EFFLUENT RELEASE REPORT JULY 1, 1988 THROUGH DECEMBER 31, 1988 USNRC Dockets STN-50-528, STN-50-529 and STN-50-530 8903090387 88i23i PDR ADOCK 05000528 R PDC
PVNGS Semi-Annual Operating Report for July - December 1988 Table of Contents P~ae Introduction Bibliography Appendix A: Source Terms and Effluent and Waste Al Disposal Reports Appendix B: Meteorology Bl Appendix C: Dose Calculations C1 Appendix D: Change Pages to Palo Verde Nuclear Generating D1 Station, Units 1, 2 and 3. Semi-Annual Radioactive Effluent Release Report, January 1, 1988 through June 30, 1988 Appendix E: Revised Offsite Dose Calculation Manual (ODCM) E1 Appendix F: Changes to Offsite Dose Calculation Manual (ODCM) F1
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PVNGS Semi-Annual Operating Report for July - December 1988 List of Tables Table No. P~ae A1 PVNGS Units 1, 2 and 3 Gaseous Effluents - Average A7 Lower Limitof Detection A2 PVNGS Unit 1 1988 Gaseous Effluents - Summation of A8 AllReleases A3 PVNGS Unit 1 1988 Gaseous Effluents - Ground Level A9 Releases A4 PVNGS Unit 2 1988 Gaseous Effluents - Summation of A11 AllReleases A5 PVNGS Unit 2 1988 Gaseous Effluents - Ground Level A12 Releases A6 PVNGS Unit 3 1988 Gaseous Effluents - Summation of A14 AllReleases A7 PVNGS Unit 3 1988 Gaseous Effluents - Ground Level A15 Releases A8 Estimation Methodology of Total Percent Error A17 A9 Solid Waste Summary for July 1988 - December 1988 A18 A10 PVNGS Units 1, 2 and 3 Effluent Monitoring A24 Instrumentation Out of Service Greater than 30 Days B1 JFDs of 35-Foot Wind Versus Delta T B3 July - September 1988 B2 JFDs of 35-Foot Wind Versus Delta T B9 October - December 1988 B3 JFDs of 35-Foot Wind Versus Delta T B15 July - December 1988 B4 JFDs of 35-Foot Wind Versus Delta T B21 January - December 1988 Doses to Special Locations for January - December 1988 C2 Integrated Population Doses for January - December 1988 C5 C3 Summary of Individual Doses for January - December 1988 C7 D1 'VNGS Unit 1 1988 Revised Gaseous Effluents - Summation D3 of AllReleases
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PVNGS Semi-Annual Operating Report for July - December 1988 List of Tables Table No. ~Pa e D2 PVNGS Unit 1 1988 Revised Gaseous Effluents - Ground Level D4 Releases D3 Revised Doses to Special Locations for January - June 1988 D6 D4 Revised Summary of Individual Doses for January - June 1988 D7
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PVNGS Semi-Annual Operating Report for July - December 1988 INTRODUCTION This report summarizes meteorological data and doses from radioactive effluents for the Palo Verde Nuclear Generating Station (PVNGS) for the period July through December 1988. The data presented meet the reporting requirements of Regulatory-Guide 1.21 of the U.S. Nuclear Regulatory Commission (Revision 1, June 1974) as well as the PVNGS Radiological Environmental Technical Specifications (RETS).
The report is organized into four parts. Appendix A presents the effluent and waste disposal source term data. Appendix B presents a summary of onsite meteorological data for the report period. Appendix C presents the radiological doses from gaseous radioactive eKuents. Appendix D presents the change pages to the effluent release report for the period January through June 1988. Appendix E presents the entire revised offsite Dose Calculation Manual (ODCM). Appendix F presents changes made to the ODCM and their explanations.
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PVNGS Semi-Annual Operating Report for July- December 1988 BIBLIOGRAPHY Palo Verde Nuclear Generating Station Units 1, 2 and 3, Semi-Annual Radioactive Effluent Release Report, January 1, 1988 through June 30, 1988. USNRC Dockets STN-50-528, STN-50-529 and STN-50-530.
U.S. Nuclear Regulatory Commission, Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water- Cooled Nuclear Power Plants," Revision 1, 1974.
U.S. Nuclear Regulatory Commission, Regulatory Guide 1.23 (Safety Guide 23),
"Onsite Meteorological Programs," 1972.
U.S. Nuclear Regulatory Commission, NUREG/CR-2919, "XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations," 1982.
U,S. Nuclear Regulatory Commission, NUREG-0579, "User's Guide to GASPAR Code,", June 1980.
U.S. Nuclear Regulatory Commission, Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," Revision 1, 1977.
U.S. Nuclear Regulatory Commission, NUREG-0172, "Age-specific Radiation Dose Commitment Factors for a One- Year Chronic Intake," 1977.
U.S. Nuclear Regulatory Commission, NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," 1978.
U.S. Nuclear Regulatory Commission, NUREG-1133, "Technical Specifications, Palo Verde Nuclear Generating Station, Unit No. 1, Docket No. 50-528, Appendix 'A'o License No. NPF-41," 1985.
U.S. Nuclear Regulatory Commission, NUREG-1181, "Technical Specifications, Palo Verde Nuclear Generating Station, Unit No. 2, Docket No. 50-529, Appendix 'A'o License No. NPF-51," 1986.
U.S. Nuclear Regulatory Commission, NUREG-1287, "Technical Specifications, Palo Verde Nuclear Generating Station, Unit No. 3, Docket No. 50-530, Appendix 'A'o License No. NPF-74," 1987.
I PVNGS Semi-Annual Operating Report for July - December 1988 APPENDIX A SOURCE TERMS AND EFFLUENT AND WASTE DISPOSAL REPORTS
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PVNGS Semi-Annual Operating Report for July - December 1988 Supplemental Information 1 0 Re lator Limits 1.1 Liquid Releases
- a. PVNGS Technical S ecification 3.11.1.1 The concentration of radioactive material discharged from secondary system liquid waste to the onsite evaporation ponds shall be limited to the Lower Limitof Detectability (LLD) defined as 5 x 10-7 pCi/ml for the principal gamma emitters or l x 10-6 pCi/ml for I-131.
- b. PVNGS Technical S ecification 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to areas at and beyond. the SITE BOUNDARYshall be limited:
~ During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and
~ During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.
1.2 Gaseous Releases aO PVNGS Technical S ecification 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site shall be limited to the following:
~ For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and
~ For I-131 and I-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.
- b. PVNGS Technical S ecification 3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following:
~ During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation and, A2
I PVNGS Semi-Annual Operating Report for July - December 1988
~ During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta
'adiation.
- c. PVNGS Technical S ecification 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, Tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous efPuents released, from each reactor unit, to areas at and beyond the SITE BOUNDARYshall be limited to the following:
~ During any calendar quarter: Less than or equal to 7.5 mrems to any organ and,
~ During a'y calendar year: Less than or equal to 15 mrems to any organ.
- d. PVNGS Technical S ecification 3.11.2.4 The GASEOUS RADWASTE SYSTEM and the VENTILATION EXHAUST TREATMENTSYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases, from each reactor unit, from the site when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The VENTILATIONEXHAUSTTREATMENT SYSTEM shall be used'to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to aseous effluent releases, from each reactor unit, to areas at and eyond the SITE BOUNDARYwhen averaged over 31 days would exceed 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.
1.3 Total Dose
- a. PVNGS Technical S ecification 3.11.4 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases ofradioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.
2.0 Maximum Permissible Concentrations Air: Release Concentrations are limited to dose rate limits described in 1.2.a of this report.
3.0 'A~E The average energy (E) of the radionuclide mixture in releases of fission and activation gases is not applicable to PVNGS.
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PVNGS Semi-Annual Operating Report for July - December 1988 4.0 Measurement and A roximations of Total Radioactivit in Gaseous Effluents.
For continuous releases, sampling is in accordance with PVNGS Technical Specification Table 4.11-2 (Units 1, 2 and 3). Particulate and iodine radionuclides are sampled continuously at the three exhaust points. The particulate filters and charcoal cartridges are exchanged for analysis four times per month. Noble gas and tritium are sampled at least once per 31 days.
The hourly average Radiation Monitoring System (RMS) effluent monitor readings are used, when available, to account for increases and decreases in noble gas concentrations between noble gas grab samples. The tritium concentration is assumed constant between sampling periods.
For batch releases, sampling is also in accordance with PVNGS Technical Specification Table 4.11-2 (Units 1, 2 and 3). For containment purges, the noble gas concentration is adjusted to account for decreases or increases in concentration during the purge using RMS readings. The volume of air released during the purge is determined using the exhaust fan rated flow rate.
For Waste Gas Decay Tank releases, the volume released is corrected to standard pressure.
The Lower Limitof Detection (LLD) of a measurement system is defined in Table 4.11-2 of the PVNGS Technical Specifications (Units 1, 2 and 3). An average LLD for each radionuclide is provided in Table A1.
5.0 Batch Releases Unit 1" Unit 2* Unit 3*
'.1 Gaseous Number ofbatch releases: 52 50 Total time period for batch releases: 2188.04 1455.24 2332.72 Maximum time period for a batch release: 168.00 168.00 151.38 Average time period for a batch release: 42.08 44.10 46.65 Minimum time period for a batch release: 2.34 0.88 1.03
- Alltimes are in hours 5.2 Liquid None 6.0 Abnormal Releases None 7.0 Offsite Dose Calculation, Manual ODCM and Process Control Pro am PCP Revisions There were no revisions to the PCP. There were no major changes to the radwaste systems.
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I PVNGS Semi-Annual Operating Report for July - December 1988 The ODCM was revised and is included in Appendix E. The justification for a revision of the ODCM is presented in Appendix F.
8.0 Effluents and Solid Wastes 8.1 Gaseous Effluents The gaseous effluents for the third and fourth quarters are included in .
Tables A2 through A7. Included in these tables are summaries of the effluents and estimated total error.
8.2 Liquid Effluents There were no liquid effluents from the PVNGS site.
8.3 Solid Waste Solid waste shipments are summarized in Table A9.
9.0 Miscellaneous Information Releases made to the evaporation pond have been limited at the tank to the concentrations specified in PVNGS Technical Specification 3.11.1.1. In addition, PVNGS has imposed a limitof 3 x 10-~ pCi/ml for tritium in tanks released to the evaporation pond. This is the maximum permissible concentration for unrestricted areas for tritium in water from 10CFR20 Appendix B. The evaporation pond was monitored in accordance with PVNGS Technical Specification 3.12.1 (Units 1, 2 and 3). During this report period, the analyses showed tritium concentrations in water to be less than or equal to 1.49E-06 pCi/ml.
The results of the second quarter 1988 Strontium-89 and Strontium-90 analyses for continuous mode releases, which were not available at the time the January- June, 1988 Semi-Annual Report was written, were determined to be less than the Lower Limitof Detection.
An error was discovered in the January- June 1988 Report. The tritium total curies released for Unit 1, second quarter, continuous mode (Table A3) was 9.60E+ 01 curies versus 4.19E+ 01 as reported. Revised Tables A2, A3, C1 and C3 are included in Appendix D. The population doses for the first semi-annual period presented in Table C2 of the January- June 1988 Report were recalculated and are presented in Appendix C (Table C2).
Technical Specification 3.12.1 ACTION c. requires, in part, to identify the cause of the unavailability of samples and identify the new-location(s) for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).
On July 1, 1987, the Baisley Dairy, ODCM location 450, closed. The Lueck Dairy, (ODCM Rev. 1 location 455) ODCM Rev. 2.location 450, replaced the Baisley Dairy as the Technical Specification sample location.
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PVNGS Semi-Annual Operating Report for July - December 1988 Revised ODCM figures and tables are included as part of the ODCM Rev. 2, which is included in Appendix E of this report.
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PVNGS Semi-Annual Operating Report for July - December 1988 Table Al PVNGS UNITS 1, 2, AND 3 GASEOUS EFFLUENTS - AVERAGE LOWER LIMITOF DETECTION pCi/cc NUCLIDE CONTINUOUS BATCH KRYPTON 85 5.50E-06 5.50E-06 KRYPTON 85m 2.10E-08 2.10E-08 KRYPTON 87 4.90E-08 4.90E-08 KRYPTON 88 9.10E-08 9.10E-08 XENON 133 6.00E-08 6.00E-08 XENON 133m 1.10E-07 1.10E-07 XENON 135 2.40E-08 2.40E-08 XENON 135m 5.10E-07 5.10E-07 XENON 138 2.30E-06 2.30E-06 IODINE 131 3.70E-14 1.50E-11 IODINE 133 2.60E-14 1.00E-11 IODINE 135 9.60E-14 3.80E-11 BAIGUM140 1.10E-13 4.30E-11 CERIUM 141 3.30E-14 1.30E-11 CERIUM 144 1.40E-13 5.80E-11 CESIUM 134 1.60E-14 6.30E-12 CESIUM 137 2.40E-14 9.60E-12 COBALT 58 2.60E-14 1.00E-11 COBALT 60 3.00E-14 1.20E-11 IRON 59 3.50E-14 1.40E-11 LANTHANUM140 3.00E-14 1.20E-11 RQMGANESE 54 2.70E-14 1.10E-11 MOLYBDENUM99 2.30E-13 9.20E-11 STRONTIUM 89 5.00E-16 STRONTIUM 90 5.00E-16 TRITIUM 5.00E-07 5.00E-07 ZINC 65 5.90E-14 2.30E-11 GROSS ALPHA 6.00E-15
- Not required for batch releases.
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l PVNGS Semi-Annual Operating Report for July - December 1988 Table A2 PVNGS UNIT 1 1988 GASEOUS EFFLUENTS-SUMMATIONOF ALLRELEASES Unit Quarter Quarter Est. Total
¹3 ¹4 Error /o*
A. Fission & activation ases
- 1. Total release Ci 7.94E+02 3.99E+02 3.97E+01 2.. Average release rate for pCi/sec 9.99K+01 5.02E+Ol period
- 3. Percent of technical NA** NA**
specification limit B. Iodines
- 1. Total Iodine-131 Ci 4.30E-04 1.66E-04 2.93E+01
- 2. Average release rate for pCi/sec 5.41E-05 2.09E-05 period
- 3. Percent of technical NA** NA**
specification limit C. Particulates
- 1. Particulates with half- Ci 1.28E-05 (LLD 2.93E+01
)
lives 8 days
- 2. Average release rate for PCi/sec 1.62E-06 (LLD period
- 3. Percent of technical NA** NA**
specification limit
- 1. Total release Ci 1.51E+02 5.40E+Ol 4.22E+01
- 2. Average release rate for pCi/sec 1.90K+01 6.79E+00 period
- 3. Percent of technical NA**
specification limit
- Estimated total error methodology is presented in Table A8.
- See Table C3 for percent of technical specification limits.
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PVNGS Semi-Annual Operating Report for July - December 1988 Table A3 PVNGS UNIT 1 1988 GASEOUS EFFLUENTS-GROUND LEVELRELEASES CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter Quarter Quarter Quarter g3 44 AE3 P4
- 1. Fission ases Argon 41 Ci 8.47E-02 2.26E-01 Krypton-85 Ci <LLD <LLD 1.98E+01 2.63E+00 Kypton-85m Ci <LLD <LLD 2.81E-03 3.20E-03 Krypton-87 Ci <LLD < LLD <LLD <LLD Krypton-88 Ci <LLD <LLD <LLD <LLD Xenon-131m Ci 4.60E+00 2.40E-01 Xenon-133 Ci 2.22E+02 3.49E+02 3.78E+02 1.98E+01 Xenon-133m Ci 2.40E+00 <LLD 1.22E+00 1.31E-01 Xenon-135 Ci 6.53E+00 2.65E+01 1.04E-01 1.08E-01 Xenon-135m Ci <LLD <LLD <LLD <LLD Xenon-188 Ci 1.59E+02 <LLD <LLD <LLD Unidentified Ci Total for period Ci 3.90E+02 3.76E+02 4.04E+02 2.31E+01
- 2. Iodines Iodine-131 Ci 3.66E-04 1.30E-04 6.37E-05 3.63E-05 Iodine-133 Ci 1.89E-04 1.45E-05 4.64E-06 1.02E-05 Iodine-135 Ci <LLD <LLD 3.39E-04 3.58E-04 Total for period Ci 5.55E-04 1.45E-04 4.07E-04 4.05E-04
- 3. Particulates Antimony-124 Ci 4.98E-06 Barium-140 Ci <LLD <LLD <LLD <LLD Bromine-82 Ci 7.18E-06 1.95E-05 Cerium-141 Ci <LLD <LLD <LLD <LLD Cerium-144 Ci <LLD <LLD <LLD <LLD A9
I PVNGS Semi-Annual Operating Report for July- December 1988 Table A3 (Continued)
PVNGS UNIT 1 1988 GASEOUS EFFLUENTS-GROUND LEVELRELEASES CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter Quarter Quarter Quarter g3 44 P3 P4
- 3. Particulates (continued)
Cesium-134 Ci 2.98E-06 <LLD <LLD <LLD Cesium-137 Ci 3.99E-06 <LLD <LLD <LLD Cesium-138 Ci 3.98E-04 1.93E-03 Cobalt-58 Ci <LLD <LLD <LLD <LLD Cobalt-60 Ci'i 8.92E-07 <LLD <LLD < LLD Iron-59 <LLD <LLD <LLD <LLD Lanthanum-140 Ci <LLD <LLD <LLD <LLD Manganese-54 Ci <LLD <LLD <LLD <LLD Molybdenum-99 Ci <LLD <LLD <LLD <LLD Rubidium-88 Ci 2.82E-04 6.18E-04 Strontium-89 Ci <LLD Strontium-90 Ci <LLD Tritium Ci 6.19E+01 <LLD 8.95E+01 5.40E+01 Zinc-65 Ci <LLD <LLD <LLD <LLD Unidentified Ci Total for period Ci 6.19E+01 <LLD 8.95E+01 5.40E+01
- Not detected
- Notapplicable
- Analysisnot yet completed. Additional information willbe included in the next Semi-Annual report.
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PVNGS Semi-Annual Operating Report for July - December 1988 Table A4 PVNGS UNIT 2 1988 GASEOUS EFFLUENTS-SUMMATIONOF ALLRELEASES Unit Quarter Quarter Est. Total g3 @4 Error%*
A. Fission & activation ases
- 1. Total release Ci 4.13E+01 1.04E+02 3.97E+01
- 2. Average release rate for pCi/sec 5.20E+00 1.31E+01 peFlod
- 3. Percent of technical NA** NA*+
specification limit B. Iodines
- 1. Total Iodine-131 Ci 1.33E-04 1.77E-03 2.93E+01
- 2. Average release rate for pCi/sec 1.67E-05 2.23E-04 period
- 3. Percent of technical NA*~ NA**
specification limit C. Particulates
- 1. Particulates with half- Ci 1.54E-05 (LLD 2.93E+01
)
lives 8 days
- 2. Average release rate for pCi/sec 1.94E-06 <LLD period
- 3. Percent of technical NA**
specification limit
- 1. Total release Ci 5.33E+01 1.25E+02 4.22E+01
- 2. Average release rate for pCi/sec 6.71E+00 1.57E+01 period
- 3. Percent of technical NAQQQ NAggg specification limit
- Estimated total error methodology is pre sented in Table A8.
- See Table C3 for percent of technical spe cification limits.
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PVNGS Semi-Annual Operating Report for July - December 1988 Table A5 PVNGS UNIT 2 1988 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter Quarter Quarter Quarter g3 P4 g3 P4
- 1. Fission ases Argon 41 Ci 8.61E-02 8.16E-02 Krypton-85 Ci <LLD <LLD <LLD <LLD Kypton-85m Ci <LLD <LLD <LLD 1,97E-04 Krypton-87 Ci <LLD <LLD <LLD <LLD Krypton-88 Ci <LLD <LLD <LLD <LLD Xenon-131m Ci 1.50E-02 Xenon-138 Ci 3.69E+01 7.58E+01 2.32E+00 2.56E+Ol Xenon-133m Ci <LLD <LLD 1.30E-02 2.72E-02 Xenon-135 Ci 1.95K+00 2.51E+00 1.27E-02 4.09E-02 Xenon-135m Ci <LLD <LLD <LLD <LLD Xenon-138 Ci <LLD <LLD <LLD <LLD Unidentified Ci Total for period Ci 3.89E+01 7.83E+01 2.43E+00 2.58E+01
- 2. Iodines Iodine-131 Ci 1.21E-04 1.21E-03 1.20E-05 5.60E-04 Iodine-132 Ci 2.76E-06 Iodine-133 Ci <LLD <LLD 5.27E-06 7.37E-05 Iodine-135 Ci <LLD <LLD 5.07E-07 1.09E-05 Total for period Ci 1.21E-04 1.21E-03 1.78E-05 6.47E-04
- 3. Particu ates Antimony-124 Ci 1.54E-05 Barium-139 Ci 1.95E-06 Barium-140 Ci <LLD <LLD <LLD <LLD Bromine-82 Ci 7.20E-06 6.10E-06 Cerium-141 Ci <LLD <LLD <LLD <LLD Cerium-144 Ci <LLD <LLD <LLD <LLD A12
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PVNGS Semi-Annual Operating Report for July - December 1988 Table A5 (Continued)
PVNGS UNIT 2 1988 GASEOUS EFFLUENTS-GROUND LEVELRELEASES CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter, Quarter Quarter Quarter 43 44 g3 44
- 3. Particulates (continued)
Cesium-134 Ci <LLD <LLD <LLD <LLD Cesium-137 Ci <LLD <LLD <LLD <LLD Cesium-138 Ci 3.11E-05 Cobalt-58 Ci <LLD <LLD <LLD <LLD Cobalt-60 Ci <LLD <LLD <LLD <LLD Iron-59 Ci <LLD <LLD <LLD <LLD Lanthanum-140 Manganese-54 Molybdenum-99
'iCi Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Rubidium-88 Ci 2.37E-04 Strontium-89 Ci <LLD I Strontium-90 Tritium Ci Ci
<LLD
<LLD <LLD 5.33E+01 1.25E+02 Zinc-65 Ci <LLD <LLD <LLD <LLD Unidentified Ci Total for period Ci 1.54E-05 <LLD 5.33E+01 1.25E+02
- Not etected
- Notapplicable
- Analysisnot yet completed. Additional information willbe included in the next Semi-annual Report.
A13 I
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~,~ 'k l V 4'
~
I
~4
~
I I
PVNGS Semi-Annual Operating Report for July- December 1988 Table A6 PVNGS UNIT 3 1988 GASEOUS EFFLUENTS-SUMMATIONOF ALLRELEASES Unit Quarter Quarter Est. Total g3 44 Error%*
A. Fission & activation ases
- 1. Total release Ci 5.48E+Ol 7.33E+01 3.97E+Ol
- 2. Average release rate for pCi/sec 6.89E+00 9.22E+00 peFlod
- 3. Percent of technical NA** NA**
specification limit B. Iodines
- 1. Total Iodine-131 Ci 1.66E-05 1.05E-04 2.93E+01
- 2. Average release rate for pCi/sec 2.09E-06 1.32E-05 peFlod
- 3. Percent of technical NA*+ NA**
specification limit C. Particulates
)
lives 8 days
- 3. Percent of technical NA** NA**
specification limit
- 4. Gross Alpha Ci 2.97E-11 3.58E-11 radioactivity D. Tritium
- 1. Total release Ci 2.00E+02 1.24E+02 4.22K+01
- 2. Average release rate for pCi/sec 2.51E+01 1.55E+01 period
- 3. Percent of technical NA**
specification limit
- Estimated total error methodology is presente in Tab e A8.
- See Table C3 for percent of technical specification limits.
A14
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tT lb 4
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PVNGS Semi-Annual Operating Report for July - December 1988 Table A7 PVNGS UNIT 3 1988 GASEOUS EFFLUENTS-GROUND LEVELRELEASES CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter Quarter Quarter Quarter g3 P4 43 44
- 1. Fission ases Argon 41 Ci 9.86E-03 3.85E-01 8.79E-02 1.56E-01 Krypton-85 Ci <LLD <LLD 7.82E-05 6.59E-02 Kypton-85m Ci 4.49E-05 1.09E-01 2.38E-04 <LLD Krypton-87 Ci <LLD <LLD <LLD <LLD Krypton-88 Ci <LLD 3.08E-02 <LLD <LLD Xenon-131m Ci'i 1.12E-01 1.31E-01 Xenon-133 4.55E+01 6.37E+01 8.00E+00 6.10K+00 Xenon-133m Ci <LLD <LLD 7.29E-02 3.75E-02 Xenon-135 Ci 9.61E-01 2.57E+00 3.04E-02 1.88E-02 Xenon-135m Ci <LLD <LLD <LLD <LLD Xenon-138 Ci <LLD <LLD 1.82E-04 <LLD Unidentified Ci Total for period Ci 4.65E+01 6.68E+01 8.30E+00 6.51E+00
- 2. Iodines Iodine-131 Ci 1.64E-05 1.05E-04 1.66E-07 4.13E-07 Iodine-132 Ci 6.81E-06 Iodine-133 Ci 8.72E-06 1.19E-04 <LLD <LLD Iodine-135 Ci <LLD 1.11E-05 <LLD <LLD Total for period Ci 2.51E-05 2.42E-04 1.66E-07 4.13E-07
- 3. Particu ates
'arium-140 Ci <LLD <LLD <LLD < LLD Bromine-82 Ci 1.68E-05 2.42E-05 Cerium-141 Ci <LLD <LLD <LLD <LLD Cerium-144 Ci <LLD <LLD <LLD <LLD A15
cs I
I I
I
PVNGS Semi-Annual Operating Report for July- December 1988 Table A7 (Continued)
PVNGS UNIT 3 1988 GASEOUS EFFLUENTS-GROUND LEVELRELEASES CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter Quarter Quarter Quarter
¹3 ¹4 ¹3 ¹4
- 3. Particulates (continued)
Cesium-134 Ci <LLD <LLD <LLD <LLD Cesium-137 Ci <LLD <LLD <LLD <LLD Cesium-138 Ci 2.55E-03 ~
Cobalt-58 Ci <LLD <LLD <LLD <LLD Cobalt-60 Ci <LLD <LLD <LLD <LLD Iron-59 Ci <LLD <LLD <LLD <LLD Lanthanum-140 Ci <LLD <LLD <LLD <LLD Manganese-54 Ci <LLD <LLD <LLD <LLD Molybdenum-99 Ci <LLD <LLD <LLD <LLD Rubidium-88 Ci 2.19E-02 2.42E-05 4.25E-05 Strontium-89 Ci <LLD Strontium-90 Ci <LLD Tritium Ci 6.66E-Ol 5.54E-01 1.99E+02 1.23E+02 Zinc-65 Ci'I <LLD <LLD <LLD <LLD Unidentified Total for period Ci 6.66E-01 5.78E-01 1.99E+02 1.23E+02
- Not app ica e
- Notdetected
- Analysisnot yet completed. Additional information willbe included in the next Semi-annual Report.
A16
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PVNGS Semi-Annual Operating Report for July - December 1988 Table AS ESTIMATIONMETHODOLOGY OF TOTALPERCENT ERROR The estimated total errors is calculated as follows:
Total PementEn or = (E > + E > + E3,..., + E )
Where E> = Percent error associated with each contributing parameter.
Parameters contributing to errors in the measurement of gaseous effluents are process flow rates, sample collection, analytical counting and tank volumes.
A17
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PVNGS Semi-Annual Operating Report for July - December 1988 Table A9 SOLID WASTE
SUMMARY
FOR JULY 1988 - DECEMBER 1988 A. SOLID WASTE SHIPPED OFFSITE FOR BURIALOR DISPOSAL (not irradiated fuel)
Estimated 6-Month Total
- 1. T~fW Unit Period Error%
- a. Spent resin, filter sludges, M~ 1.96E+02 evaporator bottoms, etc. Ci 2.34E+02 +/-2.50E+01
- b. Dry compressible waste, contaminated ~ M~ 1.61E+02 equipment, etc. Ci 6.63E-01 +/-2.50E+Ol
- c. Irradiated components, fuel M~ 0.00E+00 rods, etc. Ci 0.00E+00 NA
- d. Other M~ 0.00E+00 Ci 0.00E+00 NA 2.a. Estimate of Major Nuclide Composition for Spent Resins, Filter Sludges, Evaporator Bottoms, Etc., as Determined by Measurement.
Waste Nuclide Percent Class Name Abundance Curies A 'Fe-55 58.836 A Co-60 22.953 A Sb-124 6.479 A Co-58 3.864 A Cs-137 3.065 A *Ni-63 1.554 A Cs-134 1.467 A *H-3 0.986 A Mn-54 0.649 A Nb-95 0.061 A *C-14 0.042 A Ag-110M 0.021 A Sb-125 0.017 A *Pu-241 0.001 A Ce-144 0.001 A *Tc-99 0.000 A *Pu-239/40 0.000 A Be-7 0.000
- Scaled Nuclide based on 10CFR61.55.
A18
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PVNGS Semi-Annual Operating Report for July - December 1988 Table A9 (Continued)
SOLID WASTE
SUMMARY
FOR JULY 1988 - DECEMBER 1988 Estimates of Major Nuclide Composition for Spent Resins, Filter Sludges, Evaporator Bottoms, Etc., as Determined by Measurement.
Waste Nuclide Percent Class Name Abundance Curies B Cs-137 25.275 4.16E+01 B Co-60 22.541 3.71E+Ol B *Fe-55 22.116 3.64K+01 B Cs-134 12.941 2.13E+01 B Sb-124 8.628 1.42E+ Ol B Co-58 3.718 6.12E+00 B Mn-54 2.515 4.14E+00 B *Ni-63 1.634 2.69E+00 B Ce-144 0.430 7.07E-01 B *C-14 0.112 1.85E-01 B *Sr-90 0.064 1.06E-Ol B *H-3 0.019 3.19E-02 B *Pu-241 0.005 8.11E-03 B *Tc-99 0.000 5.34E-04 B *Pu-239/40 0.000 3.27E-04
- Scaled Nuclide based on 10CFR61.55.
A19
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PVNGS Semi-Annual Operating Report for July - December 1988 Table A9 (Continued)
SOLID WASTE SUMIKARYFOR JULY 1988 - DECEMBER 1988 2.b. Estimates of Major Nuclide Composition for Dry Compressible Waste, Contaminated Equipment, Etc., as Determined by Measurement.
Waste Nuclide Percent Class Name Abundance Curies A *Fe-55 25.955 1.72E-01 A Sb-124 17.354 1.15E-01 A Cs-137 16.750 1.11E-01 A Co-60 8.511 5.64E-02 A Co-58 7.952 5.27E-02 A Cr-51 6.926 4.59E-02 A Cs-134 5.131 3.40E-02 A Nb-95 2.475 1.64E-02 A Zr-95 1.660 1.10E-02 A Ce-144 1.569 1.04E-02 A Mn-54 1.539 1.02E-02 A Fe-59 1.133 7.51E-03 A Ru-103 1.032 6.84E-03 A *C-14 0.767 5.08E-03 A Ce-141 0.549 3.64E-03 A *Ni-63 0.264 1.75E-03 A I-131 0.249 1.65E-03 A *H-3 0.183 1.21E-03 A *Tc-99 0.001 8.90E-06
- Scaled Nuclide based on 10CFR61.55.
- 3. Solid Waste Dis osition Number of Shi ments Mode of Trans ortation Destination 30 Exclusive use truck Hanford A20
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PVNGS Semi-Annual Operating Report for July - December 1988 Table A9 (Continued)
SOLID WASTE
SUMMARY
FOR JULY 1988 - DECEMBER 1988 B. IRRADIATEDFUEL SHIPMENTS Number of Shi ments Mode of Trans ortation Destination N/A N/A C. ADDITIONALINFORMATION Thirty Shipments:
88-RW-46 1- 199.4 ft~ steel liner containing evaporator bottoms solidified with Envirostone.
- 2. 88-RW-44 2 - 199.4 ft~ steel liners containing evaporator bottoms solidified with Envirostone.
88-RW-47 2 - 199.4 ft~ steel liners containing evaporator bottoms solidified with Envirostone.
4, 88-RW-48 1- 199.4 ft~ steel liner containing evaporator bottoms solidified with Envirostone.
- 5. 88-RW-49 3 - 199.4 ft~ steel liners containing dewatered resin.
- 6. 88-RW-50 1- 199.4 ft~ steel liner containing dewatered resin.
1- 199.4 ft~ steel liner containing evaporator bottoms solidified with'Envirostone.
- 7. 88-RW-51 1- 199.4 ft~ steel liner containing evaporator bottoms solidified with Envirostone.
- 8. 88-RW-52 2- 199.4 ft~ steel liners containing evaporator bottoms solidified with Envirostone..
- 9. 88-RW-53 1- 130.8 ft~ high integrity container containing dewatered resin.
- 10. 88-RW-54 1 - 49.9 ft~ high integrity container containing filters.
- 11. 88-RW-55 2- 199.4 ft~ steel liners containing evaporator bottoms solidified with Envirostone.
- 12. 88-RW-56 1 - 130.8 ft~ high integrity container containing dewatered resin.
- 13. 88-RW-57 1- 130.8 ft~ high integrity container containing dewatered resin.
A21
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PVNGS Semi-Annual Operating Report for July - December 1988 Table A9 (Continued)
SOLID WASTE
SUMMARY
FOR JULY 1988 - DECEMBER 1988
- 14. 88-RW-58 2- 199.4 ft~ steel liners containing evaporator bottoms solidified with Envirostone.
- 15. 88-RW-59 1- 130.8 ft~ high integrity container containing dewatered resin.
- 16. 88-RW-60 11 - 107.5 ft~ boxes containing dry compressible waste.
- 17. 88-RW-61 1 - 130.8 ft~ high integrity container containing dewatered resin.
- 18. 88-RW-62 2 - 206.1 ft~ steel liners containing sump water.
- 19. 88-RW-63 2 - 199.4 ft~ steel liners containing evaporator bottoms solidified with Envirostone.
- 20. 88-RW-64 1- 130.8 ft~ high integrity container containing dewatered resin.
- 21. 88-RW-65 7 - 107.5 ft~ boxes containing dry compressible waste.
6 - 54.3 ft~ boxes containing dry compressible waste.
- 22. 88-RW-66 84- 7.5 ft~ drums containing dry compressible waste.
- 23. 88-RW-67 2- 199.4 ft~ steel liners containing evaporator bottoms solidified with Envirostone.
- 24. 88-RW-68 This shipment number was never used.
- 25. 88-RW-69 1- 206.1 ft~ steel liner containing sump water.
1 - 199.4 ft~ steel liner containing dry'compressible waste.
- 26. 88-RW-70 12 - 107.5 ft~ boxes containing dry compressible waste.
- 27. 88-RW-71 12 - 107.5 ft~ boxes containing dry compressible waste.
- 28. 88-RW-72 1- 49.9 ft~ high integrity container containing dewatered resin.
- 29. 88-RW-73 2 - 170.2 ft~ steel liners containing dewatered resin.
1 - 199.4 ft~'steel liner containing dewatered resin.
- 30. 88-RW-74 1- 170.2 ft~ steel liner containing dewatered resin.
1- 206.1 ft~ steel liner containing solidified evaporator bottoms.
- 31. 88-RW-75 1- 130.8 ft~ high integrity container containing dewatered resin.
A22
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g
PVNGS Semi-Annual Operating Report for July - December 1988 Table A9 (Continued)
SOLID WASTE
SUMMARY
FOR JULY 1988 - DECEMBER 1988 D. Changes to processes and/or equipment.
D.1 No changes were made to the Solid Radwaste Process Control Program.
D.2 No major changes were made to installed plant equipment.
D.3 No major changes were made to installed plant equipment. Therefore, predicted release or quantity of solid waste generated, remain unchanged as addressed in the UFSAR.
D.4 No major changes were made to installed plant equipment. Therefore, predicted exposures to the public and'general population, remain unchanged as addressed in the UFSAR.
A23
l PVNGS Semi-Annual Operating Report for July - December 1988 Table AIO PVNGS UNITS 1, 2 and 3 EFFLUENT MONITORINGINSTRUMENTATIONOUT OF SERVICE GREATER THAN 30 DAYS Instrument Ino erabilit Dates Ino erabilit Cause E~lti None N/A N/A N/A A24
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PVNGS Semi-Annual Operating Report for July - December 1988 APPENDIX B METEOROLOGY
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PVNGS Semi-Annual Operating Report for July - December 1988 JOINT FREQUENCY DISTRIBUTIONTABLES The tables presented in this section are results obtained from processing the hourly meteorological data collected at the Palo Verde Nuclear Generating Station for 1988.
The joint frequency distribution (JFD) tables represent the frequency, in terms of the number of observations, that a particular wind speed, wind direction, and stability category occurred simultaneously. On a quarterly and semi-annual basis, the JFDs were produced for 35-foot wind speed and wind direction by atmospheric stability class corresponding to the seven Pasquill stability categories, and for wind speed and wind direction for all stability classes combined. Atmospheric stability was classified per Regulatory Guide 1.23, using the 200-foot to 35-foot temperature difference (delta T).
In accordance with NUREG-0133, the batch releases for the third and fourth quarters for 1988 were considered as "long term", since for each quarter, the sum of the batch release periods for each unit exceeded 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br />. Consequently, the JFDs for the batch releases for both quarters are the same as for the continuous releases.
B2
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FVNGS Semi-Annual Operating Report for July - December 1988 Table Bl JFDs of 35-Foot Wind Versus Delta T July - September 1988
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II
PVNGS Semi-Annual Operating Report for July - December 1988 PVNGS JFDs 35FT WIND Vs DELTA T (200'-35') FOR 3RO QTRBB SITE IOENI'IFIERs PVNGS DATA PERIOD EXAMINEDs 7/ I/88 - 9/30/88
~ ~ 3RD QUARTCR 1988 ~+~
STABILITY CLASS A STABILITY BASED ONs DELTA T BETWEFN 200.0 ANO 35.0 FEET WIND ISCASUREO ATs 35 ' FEET WIND THRESHOLD AT ~ 0.75 IlPH JOINT FREQUENCY DISTRIBUl'ION OF WINO SPEED ANO DIRECTION IN HOURS AT 35.00 FEET 0
(MPH) N NNE Ne ENe e ese se sse S SSW SW WSW W WNW NW NNW TOTAL ALM 0.76- 1.50. 0 0 0 1.51- 2.50 0 0 0 2.51- 3.50 0 0 0 3.51 4.50 0 0 0 4.51 5,50 0 0 0 5.51- B.SO 0 0 I 8.51 8.50 4 4 15 8.51 11,50 25 17 63 11.51 14,50 5 2 13 14.51-20.50 3 I 14
>20.50 0 0 3
'IAI. 0 I I I I 7 15 7 4 I 0 0 109 STABILITY CLASS 8 STABILITY BASED ON) DELTA T BETWEEN 200.0 AND 35.0 FEET WINO MEASURED ATs 35.0 FEET WINO THRCSHOLD ATs 0.75 MPH JOINT FREQUENCY OISTRIBUI'ION OF WINO SPEED ANO DIRECTION IN HOURS AT 35.oo Feei PEED (MPH) N NNE Ne ENE E cse se sse s ssw sw wsw w wNw Nw NNw TQTAL ALM 0.78 1.50 0 0 0 0 0 0 0 0 0 1.51 2.50 0 0 0 0 0 0 0 0 0 2.51 3.50 0 0 0 0 0 0 0 0 0 3.51- 4.50 0 0 0 0 0 0 0 2 4.5 I- 5.50 0 0 I 0 I 0 o 6 5.51- 8.50 0. 0 I 3 0 0 0 0 10 6.51- 8.50 2 5 11 IB 13 10 0 0 82 8.51 11.50 2 10 6 20 13 5 I 0 83 I '1.51 14,50 2 3 2 7 I 0 0 0 16 14.51 20.50 4 5 0 I 0 0 0 0 10
>20.50 0 0 I 0 0 0 0 0 I TOTAL I 3 10 23 7 ' 5 12 22 47 28 I 5 2 0 190 B4
f 1,
5 lI (j
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PVNGS Semi-Annual Operating Report for July - December 1988 PVNGS JFOs 35FT WIND VS DELTA T (200'-35') FOR 3RO 0'IRBS SITE IOENTIFIERs PVNGS DATA PERIOD EXAMINEDs 7/ 1/88 9/30/88
~~4 3RO OUARTER 1988 ~~~
STABILITY CLASS C STABILITY BASED OHs DELTA T BETWEEN 200.0 AND 35.0 PRET WINO MEASURED ATs 35 0 FEET WIND THRESHOLD ATs 0.75 MPH JOINT FREOUENCY OISTRIBUl'ION OF WINO SPEED ANO DIRECTION IN HOURS AT 3S,OO FRET SPEED (MPH) H NNE NE ENE R RSE SR SSE 5 SSW SW WSW W WNW NW NNW TOTAL CALss 0.76 1.50 0 0 0 0 ~ 0 0 0 0 1.51- 2.50 0 0 0 0 0 0 0 0 2.51- 3.50 0 0 0 0 0 0 0 2 3.51 4.50 1 1 2 0 0 0 0 8 4.51 5.50 5 10 12 5 6 1 0 50 S.Sl- 6.50 10 14 8 3 0 1 52 8.51- 8.50 7 'l l 18 8 4 2 87 8 51 'll 50 0 1 2 8 5 1 1 29
'11.51 14.50 0 0 0 4 2 0 0 9 14.51 20.50 0 0 2 1 0 0 1 13 i20.50 0 0 0 0 0 0 0 1 TOTAL 2 1 5 11 4 11 1 4 44 2 5 2 4 2 1 STABILITY CLASS D STABILITY BASED ONs OPLTA T BETWEEN 200.0 AND 35.0 PERT WINO MEASURED ATs 35.0 PERT WINO THRESHOLD AT) 0 75 MPH JOINT FREOUEHCY DISTRIBUTION OP WINO SPEED AND DIRECTION IH HOURS AT 35.00 PERT PEF.D (MPH) H NNE HE ENR E ESK SK SSR S SSW SW WSW W WNW NW NNW TOTAL CALss
' 0 0.76 1.50 0 0 0 0 0 0 2 1.51- 2.50 1 0 0 1 1 0 0 18 2.Sl- 3.50 2 1 8 5 7 1 4 51 3.51- 4.50 1 3 19 12 11 7 3 83 4.51 5.50 5 2 17 18 18 7 3 91 5.51 8.50 3 3 10 14 15 3 5 70 651 8 50 1 1 7 ll 21 8 5 79 8.51 11.50 7 3 3 5 18 17 2 73 11.51 14.50 6 5 1 1 11 4 0 35 14.51-20.50 7 2 2 4 7 1 0 32
>20.50 1 3 0 2 0 0 0 8 TOTAL 14 21 18 34 23 2 1 2 5 71 1 5 48 22 18 13 16 538 B5
I 5
5
PVNGS Semi-Annual Operating Report for July - December 1988 PVNGS JFOs 35FT WIND VS DELTA T (200'-35') FOR 3RD OTRBB SITEs IDENTIFIERs PVNGS DATA PERIOD EXAMINEDs 7/ 1/88 9/30/88
~ ~~ 3RD OUARTKR 1988 ~~~
STABILITY CLASS 8 STABILITY BASED ONs DELTA T BETWEEN 200,0 AND 35.0 FEET WINO MEASURED ATs 35.0 FEET WINO THRESHOLD ATs 0,75 MPH JOINT FREOUENCY DISTRIBUTION OF WINO SPEED AND DIRECTION IN HOURS AT 35.00 FEET (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAl ALII 0 0.76-1,51 2.51-3.51-1.50 2,50 3.50 4.50 2,
2 1
1 0
2 1
'2 0
1 1
2 0
3 4
0 2
8 ll 0
3 8
10 0
4 3
10 4
41 54 65 4.51 5.50 6 3 2 3 12 3 3 51 5.51- 6.50 0 1 2 4 7 7 2 48 6.51- 8.50 7 5 2 13 26 15 2 100 8,51 11.50 5 7 6 15 38 22 1 119 11.51 14.50 0 4 8 2 14 3 0 39 14.51 20.50 0 3 1 5 1 2 1 18
>20.50 0 0 0 0 0 0 0 1 701'Al. 0 24 24 28 s, 24 22 16 9 2 . 1 115 1 4 2 1 26 538 STABILITY CLASS F STABILITY BASED ONs DELTA T BETWEEN 200.0 AND 35.0 FEET WINO ISEASURED ATs 35.0 FEET WINO THRESHOLD ATs 0.75 MPH JOINT FREOUENCY DISTRIBUTION OF WIND SPEED ANO DIRECTION IN HOURS AT 35.00 lsEE1'PEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL ALM ' 0 0.76 1.50 0 1 0 7 1.51 2.50 2 4 27 2.51- 3.50 7 4 1 1 3 7 ll9 55 3.Sl- 4.50 12 4 8 3" 55 4.51 5 50 4 5 3 3 36 5.51 8.50 0 8 4 4 0 27 8.51 8.50 1 21 6 0 0 50 8.51 11.50 0 10 1 0 0 30 1'1.51 14.50 0 0 0 0 0 3 14.51 20.50 0 0 0 0 0 0
>20.50 0 0 0 0 0 0 TOTAL 29 1 17 14 7 2 4 10 21 53 26 14 20 25 27 90 B6
~
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PVNGS Semi-Annual Operating Report for July -. December 1988 PVNGS JFOc 35FT WlND VS DELTA T (200'5') POR 3RO OTRBB SlTE IDENTIFIERs PVNGS OAl'A PERIOD EXAM!MEDI 7/ I/88 9/30/88
~~~ 3RD QUARTER 1988 ~~~
STABILITY CLASS G STABILITY BASED OH> DELTA T BETWEEH 200.0 AND 35.0 FEET WIND MEASUAKD ATI 35.0 FMT WIND THRESHOLD AT< 0 '75 MPH JOINT FAEGUENCY DISTRIBUTION OP WINO SPMD ANO DIRECTION IN HOURS AT 35.00 FEET PEED (MPH) N NNE HE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL ALM 0 0.76 1.50 0 0" 0 2 3 1.51- 2.50 11 2 8 3 35 2.51- 3.50 15 5 11 15 68 3.51 4,50 35 10 9 15 89 4.51- 5.50 21 7 6 6 47 5.51 6.50 9 II 0 3 29 6.51 8.50 2 7 0 2 IB 8.51 11.50 0 3 0 0 9 11.51-14.50 0 0 0 0 0 14.51 20.50 0 0 0 0 0
>20.50 0 0 0 0 0 I AL 3 45 I 5 I I 4 10 10 17 7 32 46 296 STABILITY CLASS ALL STABILITY4BASEO ON< DELTA T BETWEEN 200.0 ANO 35.0 FEET WINO MFASURED ATi 3S.O FEET WIND THRFSHOLO ATI 0,75 MPH JOINT FAEGUENCY DISTRIBUTION OP WIND SPEED AND OIAECTlON IN HOURS AT 35.00 FMT PMD (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL ALM 0 0.78 1.50 2 I I 0 0 0 0 0 2 0 2 0 2 3 2 18 I.SI 2.50 21 7 5 3 I 3 I 5 4 I 8 8 14 9 19 '12 119 2,51- 3,50 29 13 7 7 4 9 8 2 II ~ 12 18 13 19 17 28 33 230 3,51 4,50 56 19 16 5 5 8 5 9 24 24 27 24 20 8 17 37 302 4,51 5.50 31 20 14 9 6 5 8 14 30 35 40 21 8 15 12 13 281 5.51 8.50 16 19 6 11 7 10 3 13 23 38 42 18 9 14 2 8 237 6.51- 8.50 9 19 17 13 15 19 19 9 26 53 109 52 27 9 4 9 409
- 8. 51 11. 50 3 7 20 21 35 18 5 7 16 38 115 75 18 5 3 2 386 11.51 14.50 2 *2 I 13 20 8 I 0 2 9 41 12 0 4 I 'I 115 14.51 20.50 0 3 I 21 18 I I 2 6 13 13 4 0 2 0 2 85
>20.50 0 0 0 I 4 0 I 0 2 4 0 0 0 0 0 0 12 TOTAL I 8 105 113 75 52 I 144 227 411 229 115 85 89 119 2192 B7
IE lf II Il
PVNGS Semi-Annual Operating Report for July - December 1988 PVNGS JFDs 35PT WIND VS DELTA T (200'5') FOR 3RD QTRBB SITE IOENTIFIERs PVNGS DATA PERIOD EXAMINEDs 7/ 1/88 - 9/30/88
's ~ 's 3RD QUARTER 1988 ~ '
~
STABILITY BASED ONs DELTA T BETWEEN 200.0 AND 35 ~ 0 FEET WINO MEASURED ATs 35.0 FEET WIND THRESHOLD ATs 0,75 MPH TOTAL NUMBER OF OBSERVATIDNSs 2208 TOTAL NUMBER OF VAI.IO OBSERVATIONSs 2192 TOTAL NUMBER OF MISSING OBSERVATIONSs 16 PERCENT DATA RECOVERY FOR THIS PERIODs 99.3 %
MEAN WINO SPEED FOR THIS PERIODs 6.9 MPH TOTAL NUMBER OF OBSERVATIONS WITH BACKUP OATAs PERCENTAGE OCCURRENCE OF STABILITY CLASSES A 8 C 0 E F G 4.97 8.67 10.54 24.54 24.54 13.23 13.50 DISTRIBUTION OF WIND DIRECTION VS STABII.ITY N NNE NE ENE E ESE SE SSE S SSW SW WSW NW NNW CALM A 0 1 0 3 10 3 1 1 7 15 37 24 8 'I 0 0 0 8 0 1 3 10 23 7 9 5 12 22 47 28 18 5 2 0 0 C 2 1 5 11 24 7 11 15 29 43 44 22 8 5 2 4 0 0
E F
G TOTAL 14 30 29 93 168
'8 21 24 45 111 18 24 17 21 88 'I 34 28 14 5
05 23 24 7
2 113 32 22 2
2 75 12 18 52 3
0 28 9
4 81 1
65 20 10 1
144 71 5'I 21 227 4
105 115 53 10 4'll 48 71 28 10 229 22 34
'14 17 115 18 29 20 7
85 13 15 25 32 89 18 28 27 46 119 0
0 0
0 0
B8
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PVNGS Semi-Annual Operating Report for July - December 1988 Table B2 JFDs of 35-Foot Wind Versus Delta T October - December 1988 B9
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PVNGS Semi-Annual Operating Report for July - December 1988 PVNGS JFO> 35FT WINO Vs DELTA T (200'5') FOR 4TH OIR88 SITE IDENTIPIERI PVNGS DATA PERIOD EXAMINEDs 10/ 1/88 - 12/31/88
~ '
~ 4TH OUARTER 1988 ~~~
STAOILITY CLASS A STAOILITY 8ASKO ONi OCLTA T OCTWCCN 200,0 ANO 36.0 FCET WINO MCASURCD ATi 35.0 FEET WINO THRESHOLD AT> 0.75 MPH JOINT FREQUENCY OISTRIOUTION OP WINO SPEED ANO DIRECTION IN HOURS AT 35 F 00 FEET PCCO (MPH) N NNE NE ENE C ESE SE SSE 5 SSW SW WSW W WNW NW NNW TOTAL CALM 0.78- 1.50 0 0 0 0 0 0 0 0 0 1.51 2.50 0 0 0 0 0 0 0 0 0 2.51 3.50 0 0 0 0 0 0 0 0 0
'0 3.51- 4 0 0 0 0 0 ' 0 0 0 4.51- 5.50 0 0 0 0 0 0 0 0 0 5.51 6.50 0 0 0 0 0 0 0 0 0 6,51 8.50 0 0 0 0 0 0 0 0'
0, 1 1 S.S1 11.50 1 0 0 0 1 0 1 0 11.51 14.50 0 0 0 2 2 0 2 14.51-20.50 0 0 0 0 1 2 0 0 0
>20.50 0 0 0 0 0 0 0 0 0 AL 1 5 21 STAOILITY CLASS 8 STAOILITY OASED ON< DELTA T SKTWCKN 200.0 ANO 35.0 PEST WINO MEASURED ATI 3$ .0 FEET WINO THRESHOLD ATI 0,7S MPH JOINT FREQUENCY DISTRIBUTION OP WINO SPKKO AND DIRECTION IN HOURS AT 3S.OO FEET P D (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL ALM 0 0.78- 1.50 1.S1- 2.50 0
0 0
0 0,
0 0
0 0
0 2.51 3.50 0 0 1 0 1 3,51- 4.50 0 0 2 1 6 4.51 5.50 0 0 0 1 5 5.51 6.50 0 0 3 1 15 6.51 8.50 0 0 12 5 34 8.51 11.50 0 0 ~ 3 4 24 11.51 14,50 0 0 0 3 7 14.51 20.50 0 0 1 0 3 P20.50 0 0 0 0 0 I TAL 0 0 10 2 15 1 2 4 9 3 4 3 1 0 95 B10
I Il ig tl
~
I
PVNGS Semi-Annual Operating Report for July - December 1988 PVHGS JFOs 35FT WIND VS DELTA T (200'S') FOR 4TH QTRBB SiTE IDEHTIFIERs PVNGS DATA PERIOD EXAMINEDs 10/ 1/88 - 12/31/88
~ ~ '
4TH QUARTER 1988 ~' '
STABILITY CLASS C STABILITY SASEO OHs DELTA T BETWEEN 200.0 ANO 35.0 FEET WIND ISEASURKD AT< 35 ~ 0 FEET WINO THRESHOLD ATs'.75 MPH JOIHI'REQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IH HOURS AT 35.00 FEET P 0 (lSPH) H HNK NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM O. 76 1,50 0 0 0
'1.51 2.50 0 0 0 2.51- 3.50 0 1 13 3.51 4.50 1 0 22 4.Sl 5.50 4 0 33 5'.Sl- 8.'50 13 0 48 8.51- 8.50 4 0 42 S.S1 11.50 1 3 24 11.51 14.50 0 0 9 14.5'I 20.50 0 0 9
>20.50 0 0 2 TOTAL 1 1 1 4 7 4 4 2 2 STABILITY CLASS 0 STABILITY BASED ONs DELTA T BETWEEN 200.0 ANO 3S.O FEET WIND MEASURED ATs 35.0 FEET WIND THRESHOLD ATs 0.75 lSPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED ANO DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) H NNE NE EHE E ESE SE > SSE S SSW SW WSW W WNW NW HNW TOI'AL ALM 0 0.78- 1.50 0 0 0 0 0 1.51- 2.50 3 2 7 1 35 2.51- 3.50 3 9 12 10 90 3.51- 4.50 3 ll ll5 3 62 4.51- 5.50 3 13 '2 45 5.51- 8.50 1 2 1 0 34 6.51 8.50 1 8 9 3 44 8,5'I 11.50 8 3 8 3 42 11.51 14,50 9 3 4 1 27
- 14. 5 20. 50
'1 10 1 1 1 22
>20.50 3 0 0 0 8 TOTAL 10 11 3 31 4 19 11 14 3 50 56 24 26 23 1'I 1 407
.tg J+
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8 1
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I II II
PVNGS Semi-Annual Operating Report for July - December 1988 PVNGS JFOc 35PT WIND Vs DELTA T (200'-35') FOR 4TH QTR88 SITE IDENTIPIERs PVNGS DA'IA PERIOD EXAllINEOs 10/ 1/88 12/31/88
~~ ~ 4TH QUARTER 1988 ~ ~ '
STABILITY CLASS E S'TABILITY BASED ON< DELTA T BETWMN 200.0 AND 35.0 PKET WINO MEASURED ATs 35.0 PMT WINO THRESHOLD ATs 0.75 NPH JOINT PREQUENCY DISTRIBUTION OF WINO SPMO AND OlRECTION IN HOURS AT 35.00 FEET PMD (MPH) N NNE Ne KNE 5 Ese se sse s ssw sw wsw w www Nw NNw T0TAL ALM 0 0.76" 1.50 0 0 0 0 0 1 2 1.S1 2,50 0 2 1 3 2 3 30 2.51 3.50 1 1 1 1 5 4 49 3.51 4.50 ~
1 0 1 1 8 4 39 4.51- F 50 1 0 1 2 4 5 31 5.51- 8.50 1 0 1 0 8 9 33 6.51 8.50 ~ 0 2 2 0 4 10 35 8.51 11,50 3 4 1 1 4 7 50 11 51 14,50 9 2 1 0 1 1 34 14.51-20 50F 4 0 2 0 0 0 23
>20.50 5 0 0 0 0 0 6 I AL 1 1 32 1 8 11 3 44 21 2 332 STABILITY CLASS F STABILITY BASED ONs DELTA T BETWEEN 200.0 AND 3S.O FMT WIND MEASURED ATI 35,0 PFET WINO THRESHOLD ATs 0 75 llPH JOINT PREQUKNCY OISTRIBUTlON OP WINO'SPMD ANO DIRECTION IN HOURS AT 3$ ,00 PMT PMD (MPH) N NNK Ne eNe e ese se sse s ssw sw wsw w wNw Nw NNw TOTAL ALN 0.76- 1.50 0 1 0 0 1 0 0 0 4 1.S1 2,50 2 0 ,0 1 0 3 11 8 34 2.51 3.50 1 1 1 2 5 6 9 12 65 3.51 4.50 1 0 1 3 7 4 7 9 56 4.51 S.SO 0 2 7 10 3 9 53 5.51 8.50 0' 1 0
1 3 ~ 6 1 0 1 34 8.51 8.50 1 0 0 10 9 2 3 2 43
- 8. 51-1 1. 50 0 0 1 1 2 1 0 12 11,51 14.50 1 0 0 0 0 0 1 0 7 14.51-20.50 0 0 0 0 0 0 0 0 1
>20.50 0 0 0 0 0 0 0 0 0 I TAL 30 25 14 10 3 1 4 5 22 37 27 23 34 2 40 309 B12
PVNGS Semi-Annual Operating Report for July - December 1988 PVNGS JFDs 35FT WIND Vs DRI.TA T (200'5') FOR 4TH OTR88 SITE IOKNTLPIRAs PVNGS DATA PFRIOD EXAMLNRDs 10/ I/88 12/31/88
~ ~4 4TH OUARTER 1988 ~F4 STABILITY CLASS 0 S'TASILITY BASED ONs OFLTA T BETWEEN 200.0 ANO 35.0 FRET WINO MEASURED AT> 35.0 PERT WINO THRESHOLD ATs 0.75 MPH JOINT PAEQUENCY Olsl'RISUI'IOH OP WINO SPEED ANO DIRECTION IH HOURS AT 35,00 PMT (MPH) H NNE Ne RNR E Ese Se Sse S Ssw SW WSW W WHW NW NNW TOTAL ALM 0 0.78- 1.50 0 0 0 I 0 I 0 I 4 1.51- 2.50 13 6 I 3 12 15 19 19 97 2.51- 3.50 3.51 4.50 46 77 19 30 12 5
ll3 13 3
19 8
34 27 69 72 247 238 4 51 51 24 8 2 2 3 12 29 140 8.50 5.50'.51-28 19 3 I 0 I I 13 67 B.SI 8.50 13 12 I 0 0 0 I 4 32 8.51 11.50 6 3 I 0 0 0 0 0 10 11.51 14.50 0 0 0 0 0 0 0 0 0 14.51 20.50 0 0 0 0 0 0 0 0 0 F20.50 0 0 0 0 0 0 0 0 0 T AL 4 ll I 17 I 2 11 21 20 30 47 94 207 835 STABILITY CLASS ALL STASILITY BASED ONs DELTA T SETWKEN 200.0 ANO 35.0 PMT WINO IIEASUAED ATs 35.0 FRET WINO THRESHOLD ATI 0,75 MPH JOINT FREQUENCY DISTRIBUTION OP WIND SPMO AND DIRECTION IN HOURS AT 35,00 FeeT PEKO (IIPH) N NNR Ne ENK R ese se sse s ssw sw wsw w www Nw NNw TOTAL CALM 0 0.78" 1.50 0 0 I I 0 I 0 0 3 0 0 I I I 10 I 51 2 50 18 11 8 2 8 I 9 8 13 10 21 31 28 28 198 2.51 3.51-3.50 4.50 60 88 27 43 22 22 15 12 9
7 5
2 ll9 20 28 33 28 28 12 36 20 43 19 50 39 94 86 465 423 4.51- 5.50 68 38 18 7 8 3 11 26 25 27 4 12 20 42 307 5.51- 8.50 36 24 6 233 6.51- 8.50 '7 29 22 23 19 10 20 3
13 20 5
9 22 22 23 37 13 7
7 7
7 12 5
15 8 234 8.51 11.50 11,5'I 14.50 8 9 15 18 17 25 13 3 14 20 11 ll4 12 4 4
I 166 0 0 9 12 9 0 8 9 2 8 0 91 14.51 20.50 0 0 7 22 16 0 2 4 I 3 3 2 0 0 62
>20.50 0 0 0 I 9 0 0 0 0 0 2 2 0 0 14
'TOTAL 291 177 140 120 111 59 35 43 78, 148 192 112 115 144 161 275 2201
I 5
a j1 I
I I
I I
PVNGS Semi-Annual Operating Report for July - December 1988 PVNGS JFOs 35FT WINO VS DELTA T (200'-35') FOR 4TH QTRBB SITE IOENTIFIERs PVNGS DATA PERIOD EXAMINEDs 10/ 1/88 12/31/88
~+~ 4TH QUARTER 1988 ~ 's ~
STABII.ITY BASED ONs DELTA T BETWEEN 200.0 ANO 35.0 FEET WINO MEASURED ATs 35.0 FEET WINO THRESHOLD ATs 0.75 MPH TOTAL NUMBER OP OBSERVATIONSs 2208 TOTAL NUMBER OP VALID OBSERVATIONSs 2201 TOTAL NUISBER OF MISSING OBSERVATIONSs 7 PERCENT DATA RECOVERY FOR THIS PERIODs 99.7 5 MEAN WINO SPEED FOR THIS PERIODs 5.7 MPH TOTAL NUMBER OP OBSERVATIONS WITH BACKUP OATAs 0 PERCENTAGE OCCURRENCE OF STABILITY CLASSES A 8 C 0 E F G
- 0. 95 4.32 9.18 18.49 15,08 14,04 37.94 DISTRIBUTION OF WINO DIRECTION VS STABILITY N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW CALM A 0 1 3 2 1 2 0 0 4
1 5 2 2 2 0 0 0, 0 0
8 0 0 10 22 15 10 8 8 9 3 4 3 'I 0 C
D 5
10 8
11 20 30 20 31 18 42 16 19 2
8 ll 9, 14 23 33 18 50 23 58 15 24 26 4 7 23 4
11 4
18 0
0 E 12 19 32 18 25 8 11 11 8 38 44 21 28 30 23 8 0 F 30 25 14 10 8 3 1 4 5 22 37 27 23 34 28 40 0 G 234 113 31 17 4 2 1 2 11 21 20 30 47 94 207 0 TOTAI 291 177 140 120 111 59 35 43 78 148 192 1 'I 2 1
'1 5 144 181 275, 0 B14
4 n
l L
PVNGS Semi-Annual Operating Report for July - December 1988 Table B3 JFDs of 35-Foot Wind Versus Delta T July - December 1988 B15
I I
I l
PVNGS Semi-Annual Operating Report for July - December 1988 PVNGS JFOs 35FT WIND VS DELTA T (200'-35') FOR OTRS384 OF 1988 SITE'OENl'IFIERs PVNGS DATA 'PERIOD EXAMINEDs 7/ 1/88 - 12/31/88
~+~ 3RD 4 4TH QTRS 1988 ~ 4>
STABILITY CLASS A STABILITY BASED ONs DELTA 7 BETWEEN 200.0 AND 35.0 FEET WIND MEASURED ATs 35.0 FEET WIND THRESHOLD ATs 0.75 MPH JOINT FREGUENCY OISTRIBUI'ION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 PEET PEED (MPH) N NNE NE ENE E ESE SE SSE SSW SW WSW W WNW NW NNW TOTAL ALM 0.78 1.50 0 0 0 0 1.51 2.50 0 0 0 0 2.51 3.50 0 0 0 0 3.51- 4.50 0 0 0 0 4.51- 5.50 0 0 0 0 5.51 8.50 0 0 0 3 8.51 8.50 4 5 0 19 8.5'1-11.50 25 18
' 87 11.51 14.50 7 2 2 20 14.51 20.50 3 1 0 18
>20.50 0 0 0 3 TOTAL 11 5 1 1 1 0 0 1 0 STABILITY CLASS 8
>STABILITY BASED ONs DELTA T BETWEEN 200.0 ANO 35.0 FEET WIND MEASURED ATs 35.0 FEET WIND THRESHOLD ATs 0,75 MPH JOINT FREOUKNCY DISTRIBUTION OP WINO SPEED AND OIRFCTION IN HOURS AT 35.00 FEET ~
SPEED (MPH) N NNE NE ENE E ESE SK SSE 5 SSW SW WSW W WNW NW NNW TOTAL ALM 0 0.78 1 50~ 0 0 0 0 0 0 0 0 0 0 1,51 2,50 0 0 0 0 0 0 0 0 0 0 2.51" 3.50 1 0 0 0 0 0 0 0 0 1 3.51 4.50 2 1 0 0 0 0 0 1 0 8 4.5'I- 5.50 0 1 0 0 1 1 3 0 0 11 5.51- 8.50 3 6.51 8,50 8.51 11.50 14 5
10 14 1 2 12 3
ll42 2 12 9
18 22 8 s 0 13 ll0 0 0
25 118 14 8 0 87 11.51 14.50 2 8 0 0 2 8 1 0 0 23 14.51-20.50 5 5 0 1 1 1 0 0 0 13
>20.50 0 0 0 0 1 0 0 0 0 1 TOTAL 0 1 13 32 38 17 9 1 2 5 1 20 0 285 B16
PVNGS Semi-Annual Operating Report for July - December 1988 PVHGS JFDs 35PT WIND VS DELTA T (200'5') POR QTRS384 OP 1988 SITE IOKNTIFIERs PVNGS DATA PERIOD EXAlllNEDs 7/ I/88 - 12/31/88
~ ~ 3RD 8 4TH QTRS 1988 +~~
STABILITY CLASS C STABILITY BASED ONs DELTA T BETWMH 200.0 AND 3S.O PMT WIND MEASURED ATs 35 ' FEET WINO THRESHOLD ATs 0 75 IIPH JOINT FREQUENCY DISTRIBUTION OP WINO SPMD ANO DIRECTION IN HOURS AT 3S.OO FMT D
(HPH) N NNE NE ENE E ESE SE SSE 5 SSW SW WSW W WNW NW NNW TOTAL ALS4 0.78- '1.50 0 0 0 0 0 0 0 0 0 0 1.51 2.50 0 0 0 0 0 0 0 0 0 0 2.5'I- 3.50 I I I I 0 0 I I 3 15 3.51- 4.50 I I 0 I 2 4 3 0 I 30 4.51 5.50 I 2 3 6 14 17 10 11 2 83 5.51 8.50 23 22 5 I 100 B.'Sl- 8.'SO 7
5 ll0 5 9 ~
2 8 11 ~ 12 11 25 9 I 109
- 8. 51-11. 50 4 13 2 I 2 4 I 'I 7 0 53 11,5'I 14.50 I 5 3 0 0 0 5 3 0 18 14.51 20.50 10 7 0 0 0 2 I I 0 22
>20.50 I 2 0 0 0 0 0 0 0 3 TOTAL 7 9 25 31 4 2 19 24 52 I 7 37 - I 12 6 8 433 STABILITY CLASS 0 STABIL'ITY BASED ONs DELTA T BETWEEN 200.0 AND 3S.O PMT WINO IIEASURED AT 1 3S. 0 F MT WIND THRESHOLD ATs 0.75 HPH JOINT FREQUENCY DISTRIBUTION OP WINO SPEED AND DIRECTION IH HOURS AT 35.00 FEET PEP.D (HPH) N NNE HE ENE E ESE SK SSE S SSW SW WSW W WNW NW NNW TOTAL ALH
- 0.78 1.50 0 0 0 0 0 0 0 0 0 0 I 0 ~ 2
'1.51 2.50 I 2 3 2 5 3 8 I 5 3 '5 2 5I 2.51- 3.50 10 5 4 5 IS 14 19 11 II 9 2 10 141
- 3. 51- 4. 50 10 4 8 5 24 23 22 10 8 2 7 5 145 4.51 5.50 2 7 5 3 22 29 21 9 3 10 4 3 136 S.'Sl- B'.SO 11 S 4 5 16 16 16 3 7 6 I 3 104 6.5'I 8.50 8 4 2 lo 10 17 30 11 6 2 2 6 123 8 Sl 11 50 5 12 9 15 3 8 22 20 5 5 2 - I 115 11.51 14.50 0 11 14 8 I 4 15 5 0 2 0 I 62 14.51 20.50 3 13 12 0 2 5 8 2 I I 0 I 54
>20.50 0 I 8 0 0 2 0 0 2 I O O TOTAL 24 3 4 65 5 51 23 40 98 I I I I 72 48 41 24 45 B17
I I
PVNGS Semi-Annual Operating Report for July - December 1988 PVNGS JPDI 35FT WIND VS DELTA T (200'5') fOR QTRS384 OF 1988 SITE IDENTIFIER I PVHGS DATA PERIOD EXAMINKDI 7/ 1/88 12/31/88
~ '
~ 3RD 8 4TH QTRS 1988 ~ '
+
STABILITY CLASS E STABILITY BASED ONI DELTA T BETWEEN 200.0 AND 35,0 FEKT WIND MEASURED ATI 35 0 FEET WIND THRESHOLD ATI 0 7S MPH JOINT FREQUKNCY DISTRIBUTION OP WINO SPEED ANO DIRECTION IN HOURS AT 35.00 PEST SPEED (MPH) N HNE NE ENE E ESE SE SSE 5 SSW SW WSW W WNW NW NNW TOTAL ALM 0 0.76- 1.50 0 0 2 1 0 0 0 1 o e
'1.51 2 50 F 5 2 1 2 5 5 11 8 5 6 71 2.51- 3.50 2 3 2 8 10 8 10 13 14 7 103 3,51 4,50 5 2 2 12 15 11 13 5 6 12 '104 4.51 5.50 e 3 3 7 17 8 2 5 3 3 82 5.51- $ .50 2 2 3 12 le 10 e 5 3 2 81 8.51 8.50 12 5 2 17 38 19 8 6 0 2 135 8,$ 1 11.50 13 10 9 19 43 25 e 9 3 'I 169
'11.51 14 ~ 50 5 9 17 3 15 3 2 5 3 0 73 14.51 20.50 5 10 5 5 1 3 2 2 0 I 39
>20.50 0 0 5 0 0 0 0 1 0 0 7 7 TAL 42 43 56 4 49 27 2 7 15 5 8 4 0 STABILITY CLASS F
" Sl'ABII.ITY BASED ONI DELTA T BETWEEN 200.0 AND 35.0 FEET WINO MEASURED *TI SS.O FEET WIND THRESHOLD ATI 0.75 MPH JOINT FREQUENCY DISTRIBUI'ION OF WINO SPEED ANO DIRECTION IN HOURS AT 35.00 PEST PKEO (MPH) H HNE NE ENE E ESE SE SSE 5 SSW SW WSW W WNW NW NNW TOTAL ALM 0.78 1.50 1 0 1 0 1 2 0 1 2 0 11 1.SI- 2.50 5 3 1 1 1 4 3 13 10 10 81 2.51- 3.50 ls 2 '2 5 9 9 13 18 16 23 120 3.51 4.51-4.50 5.50 17 13 ll98 0 1
7 4
ll 1'2 10 13 9
4 10 e
5 4
IS 12 111 89 s.sl- e.so 4 0 6 14 5 3 4 9 61 8.51-8.51 11.50 8.50 4 ll 0 15 30 8 5 3 5 1
2 93 0 1 0 5 12 2 0 0 1 1 42 11.51 14.50 0 0 0 0 0 0 0 1 1 0 10 14.51 20.50 0 0 0 0 0 0 0 0 0 0 1
>20.50 0 0 0 0 0 0 0 0 0 0 0 TOTAL 59 43 31 24 1 15 43 90 53 37 54 53 7 59 B18
1
~
II
% 4
~
~
~
~
~
~
1 1
I I
PVNGS Semi-Annual Operating Report for July - December 1988 PVNGS JFOs '35FT WIND VS DELTA 7 (200'5" ) FOR QTRS364 OF 1988 SITE I OEHl'IF IER s PVNGS DATA PERIOD EXAMINEOs 7/ 1/88 - 12/31/88
~+~ 3AD d 4TH QTAS 1988 ~ ~~
STABILITY CLASS G 5'TABILITY BASED ONs DELTA T BETWEEN 200,0 ANO 35,0 FEET WINO ISEASUAED ATs 35 ' FEET WINO THRESHOLD ATs 0 76 MPH JOIHT FREQUENCY DISTRIBUTION OP WINO SPEED ANO OIAECTION IH HOURS AT 35,00 PEST SPE 0 (1SPH) N NNE NE ENE E FSE SE SSE S SSW SW WSW W WNW NW NNW TOTAl ALM 0.78 1.50 0 0 0 1 0 1 0 0 2 0 3 7 1.51- 2.50 24 8 2 0 1 5 8 18 I IS 25 22 132 2.51 3,50 81 24 15 9 3 12 12 20 21 45 84 315 3.51- 4.50 11'2 40 12 8 1 4 5 9 9 36 87 327 4.51- 5.50 72 31 10 3 0 4 4 2 4 18 35 187 5.51- 8.50 37 30 5 0 1 2 1 0 2 1 18 98 S.S1 8,50 15 19 2 2 0 3 0 0 0 1 6 ~
48 8.51 11.50 8 8 8 1 0 0 0 0 0 0 0 19 1 'I 51 14. 50 0 0 0 0 0 0 0 0 0 0 0 0 14.51-20.50 0 0 0 0 0 0 0 0 0 0 0
>20.50 0 0 0 0 0 0 0 0 0 0 0 0 T TAI 327 15 2 2 3 15 1 0 47 54 1 253 1131 STABILITY CLASS ALL STASILITY BASED OHs DELTA T BETWEEN 200.0 AND 35.0 PEET WINO MFASURKD ATs 3S.O FEET WIND THRESHOLD ATi 0 75 MPH JOINT FREQUENCY DISTRIBUTION OP WIND SPEED AHO DIRECTION IN HOURS AT 35.00 FEET PEED (MPH) N NNE NE ENE E ESE SE SSK S SSW SW WSW W WNW NW NNW TOTAL ALSS
- 0. 78 1. 50 1 2 2 2 0 1 1 0 0 2 3 2 0 3 4 3 28 1.51 2.50 39 'IS 11 5 7 4 5 7 13 9 19 IS 35 40 45 40 315
" 80 78 127 895 2.51 3.50 89 40 29 22 13 14 12 10 22 32 51 41 55 3.51- 4.50 33 50 55 38 40 27 56 123 725
~
4.51 5.50 144 97 62 58 38 30 17 16 12
'12 8
8 ll88 18 17 41 IS 1 65 48 12 27 32 55 23 588 470 5.51 8.50 52 48 29 21 10 15 19 47 58 65 24 18 21 14 6.51- 8.50 28 41 38 33 28 39 27 18 35 75 146 65 34 18 9 17 843
- 8. 51- I I . 50 9 18 35 39 52 29 12 12 19 52 135 86 29 17 7 3 552 11 51 14 50 2 2 10 25 45 15 3 1 2 15 50 14 4 12 5 1 206 14.51-20.50 0 3 8 43 32 1 1 4 8 17 14 7 3 4 0 2 147
>20.50 0 0 0 2 13 0 1 0 2 4 0 0 2 2 0 0 26 TOTAL 459 288 22 225 224 134 87 104 2 2 37S 60 341 230 229 250 94 4 B19
I
~t
~
~
I
~
~
II l
PVNGS Semi-Annual Operating Report for July - December 1988
'PVNGS JFD) 35FT WIND VS DELTA T (200'-35') FOR QTRS384 OF 1988 SITE IDENTIFIER) PVNGS DATA PERIOD EXAMINED) 7/ 1/88 12/31/88
~+~ 3RD S 4TH QTRS 1988 ~~~
STABILITY BASED ON( DELTA 7 BETWEEN 200.0 AND 35 0 FEET WIND MEASURED AT) 35.0 FEET WIND THRESHOLD AT) 0 F 75 MPH TOTAL NUMBER OF OBSERVATIONS) 4418 TOTAL NUMBER OF VALID OBSERVATIONS) 4393 TOTAL NUMBER OF MISSING OBSERVATIONS) 23 PERCENT DATA RECOVERY FOR THIS PERIOD) 99.5 5 MEAN WINO SPEED FOR THIS PERIOD) 8.3 MPH TOTAL NUMBER OF OBSERVATIONS WITH BACKUP DATA) 0 PERCENTAGE OCCURRENCE OF STABILITY CLASSES A 8 C 0 E F G 2.96 8.49 9.88 21.51 19.80 13.64 25.75 DISTRIBUTION OF WINO DIRECTION VS STABILITY N NNE NE ENE E ESE SE SSK S SSW SW WSW W WNW NW NNW CALM A 0 2 3 5 Il 5 I 8 20 39 28 8 0 0 0 8 0 1 13 25 32 38 42 17 ll 1 9
24
'18 52 28 58 87 31 37 20 10 8
1 3
6 0
8 0
0 C 7 9 31 23 19 81 12 D 24 32 48 65 65 51 23 40 98 121 161 72 48 41 24 32 0 E 42 43 58 48 49 30 27 20 28 87 159 92 60 59 38 34 0 F 59 43 31 24 13 5 4 8 15 43 90 53 37 54 53 67 0 G 327 158 52 22 6 3 2 2 3 15 31 30 47 54 126 253 0 TOTAL 459 288 228 225 224 134 87 104 222 375 803 341 230 229 250 394 0 B20
I I
l
PVNGS Semi-Annual Operating Report for July - December 1988 Table B4 JFDs of 35-Foot Wind Versus Delta T January - December 1988 B21
I
'IWel+
l I
PVNGS Semi-Annual Operating Report for July - December 1988 PVNGS JFOs 35FT WIND VS DELTA T (200'5') FOR 1988 ANNUAL PERIOD SITE IDENTIFIERs PVNGS DATA PERIOD EXAMINEDs 1/ 1/88 12/31/88
~ ~ '
ANNUAL ~+~
STABILITY CLASS A S'fABILITY BASED ON( DELTA T BETWEEN 200.0 ANO 35,0 FEET WINO SSEASUREO AT) 35.0 FKET WINO THRESHOLD ATs 0,75 MPH JOINT FREQUKNCY OISTRIBUl'ION OF WIND SPEED ANO DIRECTION IN HOURS AT 35,00 FEET SPEED (MPH) N NNK NE ENK E ESE SE SSE S SSW SW WSW W WNW NSS NNW TOTAL ALM 0.76 1.50 0 0 0 0 0 0 0 0 1.51- 2.50 0 . 0 0 0 0 ~ 0 0 0 2.51 3.50 0 0 0 0 0 0 0 0 3.51- 4.50 0 0 0 0 0 0 0 0 4.51- 5.50 0 0 0 0 0 0 0 0 S.'Sl- 6'.SO 0 1 0 0 0 0 0 3 6.51- 8.50 0 1 2 8 6 1 0 23 8.51 11.50 2 8 '15 39 21 2 0 109 11.51 14.50 0 2 17 28 7 4 5 73 14.51 20.50 4 8 18 26 2 14 5 82
>20.50 0 0 2 4 2 0 1 15 TOTAL 4 1 14 5 1 3 3 1 1 7 11 STABILITY CLASS 8
'TABILITYBASED ONs DELTA T BETWEEN 200.0 AND 3S.O FEET WIND MEASURKD ATs 35,0 1'EKT WIND THRESHOLD AT ~ 0.75 ISPH JOIN'f FREQUENCY DISTRIBUTION OF WINO SPEED AND DIRECTION IN HOURS AT 35,00 FEET PEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL ALII 0
- 0. 76 1.50 0 0 0 ,0 0 0 0 0 0 0 1.51 2.50 0 0 0 0 0 0 0 0 0 0 2.51- 3.50 1 0 ~
0 0 0 0 0 0 0 2 3.5'I- 4.50 2 1 0 0 0 0 0 1 0 8 4.51 5.50 1 1 0 2 4 1 3 0 0 19 5.51 6.50 3 1 5 8 3 10 1 0 1 48 8.5'I- 8.50 16 18 18 18 27 31 17 14 1 181 8.51 11.50 5 20 8 7 27 40 21 12 0 158 11.51 14.50 3 9 0 4 8 11 5 0 0 50 14.51-20 50 F 5 8 0 1 8 6 0 3 33
>20.50 0 0 0 0 1 1 0 1 0 3 fofAL 1 1 56 29 1 10 40 74 1 0 48 28 15 1 5 502 B22
/p C
~ 'l l 4
I l
PVNGS Semi-Annual Operating Report for July - December 1988 PVNGS JFOa 35FT WINO Vs DELTA T (2000 3$ ') FOR 1988 ANNUAL PERIOD SITE IOENTIFIERs PVNGS DATA PKRIOD EXAMINEOa 'I/ I/88 12/31/88
~ '
~ ANNUAL ~+~
STABILITY CLASS C STABILITY BASKD ONs DKI TA T BETWEEN 200.0 ANO 35.0 FEET WINO MEASURED ATa 35.0 FEET WINO THRKSHOLD ATa 0 75 ISPH F
JOINT FREQUENCY DISTRIBUTION OF WINO SPEED ANO DIRECTION IN HOURS AT 35.00 FEET 0
(MPH) N NNE NE ENE E KSE SE SSE 5 SSW SW WSW W WNW NW NNW TOTAL ALM 0.78 1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51- 2.50 0 I 0 0 0 0 0 0 0 0 0 0 0 I 2.$ 1- 3.50 I I I I 'I I 0 I I I I 3 18 3.51 4.50 3 I 3 0 3 7 5 8 6 I 2 '
I 48 4.51 5.50 10 4 4 7 9 5 23 22 18 12 3 2 4 130 S.SI- 6.50 9 10 6 8 4 17 33 34 22 17 2 3 I 177 8,51- 8.50 8 10 19 15 10 9 23 27 47 20 10 4 2 210 8.51-11.50 4 8 14 7 I 2 5 7 28 15 5 2 2 100 11.51-14.50 0 3 9 3 0 0 I 3 12 7 0 I 0 42 14.51 20.50 0 12 II 0 0 0 0 3 8 I 4 I I 42
>20.50 0 I 2 0 0 0 0 I 0 0 0 0 0 4 10 AL 15 19 33 4 9 41 41 I 10 '140 74 7 I I 14 770 STABILITY CLASS 0 STABILITY BASED ONs DELTA T BETWEEN 200.0 ANO 35.0 FEET WINO MEASURED ATs 35,0 PEKT WINO THRESHOLD ATa 0.75 IIPH JOINT FREOUENCY DISTRIBUTION OF WINO SPEED ANO DIRECTION IN HOURS AT 3S F 00 FEET PE 0 (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL ALM I 0.78 1.50 0 I 0 0 I 0 I 0 0 0 0 0 0 0 2 0 5 1.51- 2.50 3 4 . 8 5 8 5 9 8 7 7 13 7 9 4 8 8 107 2.51- 3.50 12 20 19 17 20 18 15 19 37 40 32 20 22 13 14 23 339 3,51 4,50 13 14 18 17 15 15 10 22 50 44 43 23 12 7 18 18 335 4.51- 5.50 9 11 12 26 14 12 13 15 49 61 42 20 8 14 9 11 326 5.51 8.50 6 14 20 9 13 8 2 10 30 25 37 14 12 9 5 8 220 8.51 8.50 7 II 14 9 12 13 7 8 18 28 49 21 12 8 5 10 224 8.5'l-l'1.50 5 4 8 21 18 19 4 0 4 16 36 35 11 7 4 2 194 11.51 14.50 2 2 I 15 29 11 0 I 4 9 24 12 3 '/ 2 4 126 14.51 20.50 I 3 4 15 18 0 2 2 5 13 23 7 6 10 I 4 114
>20.50 0 0 0 I 7 0 0 0 2 3 0 I 2 3 0 0 19 OTAL 58 4 104 I I 9 3 3 04 244 299 160 7 64 2 2010 B23
I I
II '~
I l
'l
PVNGS Semi-Annual Operating Report for July - December 1988 PVNGS JFOa 35FT WIND VS DELTA T (200'5') FOR 1988 ANNUAL PERIOD SITE IDENTIFIERa PVNGS DATA PERIOD CXASiINEOa 1/ 1/88 12/31/88
~~1 ANNUAL ~~~
STABILITY CLASS 6 STABILITY BASED ONa DELTA T BETWEEN 200.0 AND 35.0 PEST WIND MEASURED ATs 35,0 FEET WINO THRESHOLD AT a 0,7S MPH JOINT FREOUENCY DISTRIBUTION OF WINO SPCCD ANO DIRECTION IN HOURS AT 35.00 FEET PEE (MPH) N NNC NE ENC E CSC SE SSE $ SSW SW WSW W WNW NW NNW TOTAL ALii 1 0.78- 1.50 0 0 0 0 0 8 0 2 0 2 15
- 1. 51 2. 60 2.$ 1- 3.50 12 20 1
20 1
8 7,
'10 1
3 8
2 2
4 3
1 2
7 8
3 13 12 1
8 13 8 19 12 14 24 10 26 1
9 17 114 194 3.51 4.50 18 10 9 3 4 8 3 6 19 20 18 19 9 '10 14 188 4.51- 5.50 14 9 7 4 5 3 5 12 18 28 17 8 8 7 8 154 5.51- 8.50 8 9 7 3 4 3 2 5 22 31 22 12 6 7 S 149 6.S1- 8.50 11 7 17 11 3 5 9 9 38 51 30 13 9 2 6 229 B.Sl 11.50 0 8 18 14 11 10 9 7 36 70 60 '21 15 9 6 298 11,5'I 14,50 2 2 7 10 21 7 1 12 12 39 7 8 14 9 2 155
- 14. 51-20,50 2 1 5 10 7 1 2 8 13 10 8 3 17 4 2 89 F20.50 0 0 1 0 5 0 0 2 0 0 0 0 1 0 2 12 I AL 1 7 4 4 42 7 4 74 1 26 1 115 11 74 157 STABILITY CLASS P STABILITY BASED ONa DELTA 7 BETWEEN 200 0 ANO 35,0 FEET WINO MEASURED AT> 35.0 FEET WIND THRESHOLD ATs 0.7S MPH JOINT FREOUENCY DISTRIBUTION OF WINO SPEED AND DIRECTION IN HOURS AT 35.00 FEET PE 0 (MPH) N NNC NE ENC E CSK SC SSE S SSW SW WSW W WNW NW NNW TOTAL ALM 0.76- 1.50 2 0 1 0 0 2 2 0 1 3 0 15 1.51- 2.50 12 7 7 3 2 2 '13 6 20 18 14 114 2.51- 3.50 23 10 8 4 14 19 20 19 24 26 30 210 3.51- 4.50 31 23 8 10 12 22 16 15 22 19 37 225 4.51-5.51-5.50 24 13 5 2 ll 23 22 7 16 7 27 189 6.50 13 9 7 4 11 24 12 11 13 13 11 133 6.5'1- 8.50 9 13 8 2 29 51 25 23 13 15 17 212 8.51 11,50 4 8 10 4 13 30 12 6 2 5 10 118 11.51 14,50 0 4 5 0 1 '2 0 0 1 5 1 24 14.51 20,50 0 0 0 0 0 0 0 0 0 0 0 1 P20.50 0 0 0 0 0 0 0 0 0 0 0 0 I TAL >>8 85 53 7 18 S>>0 13 29 93 175 122 87 112>> 1 147 B24
l PVNGS Semi-Annual Operating Report for July - December 1988 PVHGS JFOs 35PT WIHO VS DELTA T (200'5') POR 1988 ANNUAL PERIOD SITE IDENTIFIERs PVNGS DATA PERIOD EXAMINEDs I/ I/88 - 12/31/88 4'NNUAL ATE STABII.ITY CLASS G STABILITY BASED ONs DELTA 7 BETWMH 200.0 ANO 35.0 FEET WINO MEASURKD AT ~ 35.0 PEKT WINO THRESHOLD ATs 0,75 MPH JOINT FREOUEHCY DISTRIBUTION OP WIND SPEKD ANO DIRECTION IH HOURS AT 35.00 FEET P D (MPH) H NHE Ne KNE E ESE Se SSE S SSW SW WSW W WNW NW NNW TOTAL AIJl I 0.76- 1.50 I 2 0 2 0 I I 0 3 5 2 6 24 2.50 '.51 48 25 14 3 2 6 12 11 22 23 41 48 287 2.SI 3.SO I S2 74 31 18 10 12 17 22 29 35 80 '149 847 3.$ 1 4.50 209 I 13 30 11 2 6 12 10 15 26 55 150 646 4,51 5,50 130 101 24 8 0 5 9 8 6 5 29 64 392 5.51- 8.50 7$ 84 14 0 0 I 5 3 I 4 3 3S 209
$ .51- 8.50 39 38 11 2 0 3 4 0 0 0 5 18 120 8.51 11.50 11 21 7 2 0 0 6 0 0 0 0 4 51 11.5'I '14.50 I 8 0 0 0 0 0 0 0 0 0 0 9 14.$ 20.50 1 0 0 0 0 0 0 0 0 0 0 0 0 0
>20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 AL 44 I I 4 IS 14 9 6 14 34 66 $2 76 98 21$ 474 2366 STABILITY CLASS ALL
'TASILITY BASED ONI DELTA T BETWMH 200.0 ANO 35.0 FMT WINO MEASURED ATs 35.0 FEET WIHO THRESHOLD ATs 0.75 MPH JOINT FREGUENCY DISTRIBUTION OF WINO SPEED AND DIRECTION IN HOURS AT 35.00 FEET PEED (MPH) NNe He ENE e ese se sse s ssw sw wsw w WNW Nw NNw TQTAL AIJI 3 0.76- 1.50 4 4 2 3 I 2 2 0 I 7 4 2 5 6 8 8 59 1.51- 2.50 7$ 42 38 14 13 14 17 12 21 18 33 39 58 61 75 77 603 2.51 3.50 207 126 87 46 38 33 28 28 54 79 81 76 83 97 147 222 1408 3.51 4.50 272 163 89 38 28 23 17 38 74 87 103 66 64 66 102 218 1428 4.5'I 5.50 179 13S 60 48 27 24 30 31 88 '121 121 80 32 45 56 114 1190 5.51- 8.50 107 108 60 30 26 24 13 32 82 96 129 69 38 36 31 80 939 6.51- 8.50 72 75 62 53 54 53 35 27 68 152 239 119 72 36 28 54 1199 8,51 11,50 21 43 52 59 74 48 18 17 33 114 247 164 64 30 22 24 10'26 11.5'I 14,50 14.51-20 50
>20 F 50 TOTAL 94B 5
4 0
22 721 0,
4 13 431 9
I 35 47 373 2
71 50 14 394 21 241 I
0 5
2 166 I
I 9 2
4 0
23 IS 466 7
48 51 780 7
116 73 1151 5
38 17 673 3
13 15 448 6
31 45 457 4
24 9
0 502 807 12 15 3
479 361 53 748 B25
I I
t'V" ~
Ijj Ij I
'VNGS Semi-Annual Operating Report for July - December 1988 PVNGS JFD> 35FT WIND VS 'DELTA T (200'-38') 'fOR 1988 ANNUAL PERIOD SITE IDENTIFIER( PVNGS DATA PERIOD EXAMINEDI 1/ 1/88 12/31/88
~ ~ '
ANNUAL '
~+
STABILITY BASED ON< DELTA T BETWEEN 200.0 AND 35.0 FEET WINO MEASURED AT> 35.0 FFET WIND THRESHOLD AT< 0.75 MPH TOTAl. NUMBER OF OBSERVATIONSa 8784 TOTAL NUMBER OF VALID OBSERVATIONS> 8748 TOTAL NUMBER Of MISSING OBSERVATIONSI 36 PERCENT DATA RECOVERY FOR THIS PERIODS 99.6 %
MEAN WINO SPEED FOR THIS PERIOD( 8.4 MPH TOTAL NUMBER OF OBSERVATIONS WITH BACKUP DATAI 0 PERCENTAGE OCCURRENCE OF STABII.ITY CLASSES A 8 C D E F G 3.49 5.74 8.80 22.98 18.02 13.93 27.05 DISTRIBUTION OF WIND DIRECTION VS STABILITY N NNE NE ENE E ESE SE SSE 5 SSW SW WSW W WNW NW NNW CALM A 0 3 4 6 18 5 3 2 14 52 103 38 18 21 7 11 8 3 13 19 36 58 29 16 10 40 74 100 48 28 15 10 5 C 15 19 33 49 69 41 28 41 91 103 140 74 27 18 10 14 0 58 84 104 135 153 99 83 83 204 244 299 160 97 80 84 82 6 88 71 87 84 84 42 37 34 74 180 268 179 115 115 85 74 F 118 85 53 37 18 11 10 13 29 93 175 122 87 1'12 111 147 G 688 448 131 48 18 14 9 8 14 34 88 52 76 98 215 474 TOTAL 948 721 431 373 394 241 188 189 488 780 1151 673 448 457 502 807 B26
I PVNGS Semi-Annual Operating Report for July - December 1988 APPENDIX C DOSE CALCULATIONS
I
%%'l4 "
P I
b'
PVNGS Semi-Annual Operating Report for July - December 1988
, GASEOUS EFFLUENT* DOSE CALCULATION Doses to the maximum individual and the surrounding population resulting from the release of radioactive material in gaseous effluents from the Palo Verde Nuclear Generating Station were calculated using the GASPAR computer program. Gaseous effluents were released from Units 1, 2 and 3 during the year 1988. The radionuclides considered in the dose calculations were Tritium, Iodine-131, Iodine-132, Iodine-133, Iodine-135, all noble gases, and particulates having a half-life eater than eight days and for which dose factors are contained in NUREG-0172.
trontium-89 and Strontium-90 were considered for the third quarter only since the fourth quarter results were not available. Locations selected for individual dose calculations included for each sector, the site boundary, and within five miles, if present, the nearest residence, the nearest garden, and the nearest milk animal.
GASPAR implements the radiological dose models of Regulatory Guide 1.109 to determine the radiation exposure to man from four principal atmospheric exposure pathways: plume, ground deposition, inhalation, and ingestion. The ingestion pathways considered were cow milk, goat milk, meat, and vegetables. Doses to the maximum individual and the population were calculated as a function of age group and pathway for significant body organs. Assumptions and data sources used for input to the GASPAR code are described on page C8.
Table C1 presents the doses for the first two quarters and the first semi-annual period of 1988 for the highest exposed location on the site boundary, the maximum individual in the general public and the Visitor Center. The site boundary and residence locations for which data are presented represent the highest annual doses.
An occupancy factor of 1.0 (implying continuous occupancy over the entire year) was considered for the Visitor Center and the exposure pathways considered to calculate its doses were plume, ground deposition, and. inhalation.
Table C2 presents the population doses for the year 1988. Table C3 summarizes the individual doses and compares the result to PVNGS Technical Specification limits.
Based on results obtained by placing TLDs on the site boundary in each sector, the net annual dose from direct-radiation, plume and ground deposition from all three units was determined to be zero.
- There were no liquid effluents associated with the operation of this facility C2
t
'1 I l.
PVNGS Semi-Annual Operating Report for July - December 1988 TABLE Cl DOSES TO SPECIAL LOCATIONS FOR JANUARY-DECEMBER 1988 SITE BOUNDARY 1.40 MILES SSW FROM UNIT I, 1.14 MILES SSW FROM UNIT 2 ANO 1.10 MILES SSW FROM UNIT 3 BETA GAMMA AIR DOSES(MRAD) 1ST QUARTER I.OSE+00 3.73E-OI 2ND QUARTER 1. 13E-O I 5.05E-02 1ST SEMI-ANNUAL I . 17E+00 4.23E-OI 3RD QUARTER 7.65E-02 5.38E-02 4TH QUARTER 1. 16E-01 4.58E-02 2ND SEMI-ANNUAL 1.92E-01 9.95E-02 ANNUAL 1.36E+00 5.236-01 T. BODY SKIN MAXIMUM INDIVIDUAL(MREM) 1ST QUARTER 2.20E-01 6.28E-01 2ND QUARTER 3. I OE-02 8. 16E-02 1ST SEMI-ANNUAL 2. 5 I E-01 7. IOE-01 3RO QUARTER 3.44E-02 7.64E-02 4TH QUARTER 2.76E-02 7.60E-02 2NO SEMI-ANNUAL 6.20E-02 1.52E-OI ANNUAL 3. 13E-01 8.62E-OI MAXIMUM INDIVIDUAL IN GENERAL PUBLIC LOCATED AT A RESIDENCE 4.60 MILES S FROM UNIT I, 4.50 MILES 5 FROM UNIT 2 AND 4. 23 MILES 5 FROM UNIT 3 (MREM) T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN 1ST QUARTER ADULT I . OSE-O I I . 05E-01 9. 168-02 1. 06E-01 1.06E-OI 1.68E-OI 1.05E-O I 2. 76E-01 TEEN 1.06E-OI 1.06E-01 9. 17E-02 1 . 06E-01 1.06E-OI 1.82E-OI '1.06E-OI 2 ~ 76E-01 CHILD 1.04E-OI I . 04E-O I 9. I BE-02 1.04E-OI 1.04E"01 1.89E-OI 1.04E-OI 2.74E-OI INFANT 9.87E-02 9.86E"02 9. 17E-02 9.88E-02 9.89E-02 '1.76E-OI 9.87E-02 2.69E-OI 2ND QUARTER ADULT 4. 12E-02 4. 12E-02 1.35E-02 4. 12E-02 4. 12E-02 4 '0E-02 4. 13E-02 6.45E-02 TEEN 4. 14E-02 4. 14E-02 1.35E 02 4. 14E-02 4. 14E-02 4.48E-02 4. 16E-02 6.47E-02 CHILD 3.81E-02 3. 8 I E-02 1.358-02 3.8'IE-02 3.81E-02 4.20E-02 3.83E-02 6. 14E-02 INFANT 2.77E-02 2.77E-02 1.35E-02 2.77E-02 2.77E-02 3. 12E-02 2.78E-02 5. IOE-02 I ST SEMI-ANNUAL ADULT I . 47E-01 I . 47E-01 1.05E-OI 1.47E-01 1.47E-OI 2. 12E-01 1.47E-OI 3.40E-O I TEEN 1.47E-OI 1.47E-O I 'I
. OSE-O I I . 476-01 1.47E-OI 2.278-01 I . 47E" 01 ~
~ 1.42E-OI I.OSE-OI 1. 42E-01 I . 42E-01 2. 31E-01 1.42E-OI 3.36E-OI INFANT 1.26E-O I 1.26E-OI 1.05E-OI 1.27E-OI I . 27E-O I 2.08E-OI 1.26E-OI 3.20E-OI 3RD QUARTER ADULT 4.45E-02 4.45E-02 1. I OE-02 4.45E-02 4.45E-02 4.50E-02 4.45E-02 6.53E-02 TEEN 4.48E-02 4.48E-02 1. IOE-02 4.48E-02 4.48E-02 . 4.54E-02 4.485-02 6.56E-02 CHILD 4.09E-02 4.09E-02 I ~ I 0E-02 4.09E-02 4.09E-02 4.15E-02 4.09E-02 6. 17E-02 INFANT 2.82E-02 2.82E-02 1 ~ I 0E-02 2.82E-02 2.825-02 2.875-02 2.82E-02 4.89E-02 4TH QUARTER ADULT 7.35E-02 7.35E-02 2.06E-02 7.35E-02 7.35E-02 7.66E-02 7.35E-02 1. IOE-01 TEEN 7.40E-02 7.39E-02 2.065-02 7.40E-02 7.40E-02 7.76E-02 7.39E-02 1. IOE-01 CHILD 6.77E-02 6.77E"02 2.06E-02 6.77E-02 6.77E-02 7. I BE-02 6.77E-02 1.04E-OI INFANT 4.77E-02 4.778-02 2.065-02 4.77E-02 4.77E-02 5. 14E-02 4.77E-02 8.40E-02 2ND SEMI-ANNUAL ADULT 1. I BE-01 I . I BE-O'I 3. I SE-02 I . I BE-01 1. IBE-01 I . 22E-01 1. I BE-01 1.75E-OI TEEN 1. 19E-O I I . 19E-01 3. I SE-02 I . 19E-01 'I . 19E-0'I I . 23E-01 1. 19E-0 I 1.76E-OI CHILD I . 096-01 I . 09E-01 3. 15E-02 1.09E-OI 'I
. 09E-01 I . 13E-01 '1.09E-OI 1.66E-O'I INFANT 7.58E-02 7.58E-02 3. I SE 02 7.59E-02 7.596-02 8. 016-02 7.58E-02 1.33E-O'I ANNUAL ADULT 2.65E-OI 2.65E-OI I . 37E-O I 2.65E-OI 2.65E-OI 3. 33E-01 2. 65E-01 5. 16E-01 TEEN 2.66E-OI 2.66E-OI 1.37E 01 2.66E-OI 2.66E-01 3.50E-01 ~ 2.66E-OI 5. 16E-01 CHILD 2. 51E-01 2. 51E-O I 1.37E-OI 2. 51E-01 2.51E-OI 3.44E-OI 2.51E-OI 5. 0 I E-O I INFANT 2.02E-OI 2. 025-01 1.37E-01 2.02E-OI 2.02E-OI 2.88E-01 2.02E-OI 4.53E-OI C3
i PVNGS Semi-Annual Operating Report for July - December 1988 TABLE C1 (CONTINUED)
VISITOR'S CENTER LOCATED ONSITE 0.45 MILES WNW FROM UNIT I, 0.42 MILES NW FROM UNIT2 AND 0.58 MILES NW FROM UNIT 3 (MREM) T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN IST QUARTER ADULT 3.40E-02 3 '0E-02 2.986-02 3.40E-02 3.4 IE-02 5.546-02 3.40E-02 8.82E-02 TEEN 3.40E-02 3.40E-02 2.98E-02 3.41E 02 3.42E-02 6.046-02 3.41E-02 8.836-02 CHILD 3.36E-02 3 '5E-02 2.98E-02 3.36E-02 3.36E-02 6. 28E-02 3.36E-02 8.78E-02 INFANT 3. 19E-02 3. 19E-02 2.98E-02 3 '0E-02 3.20E-02 5.86E-02 3. 19E-02 8.61E-02 2ND QUARTER ADULT 3.26E-02 3.26E-02 I . 20E-02 3.26E-02 3.26E-02 3.48E-02 3.27E-02 5 ~ 17E-02 TEEN 3.28E-02 3.28E-02 1.20E-02 3.28E-02 3.28E-02 3.546-02 3.29E-02 5. 19E-02 CHI LD 3.04E-02 3.04E-02 1.206-02 3.04E-02 3.046-02 3.336-02 3.05E-02 4.94E-02 INFANT 2.26E-02 2.25E-02 1.20E-02 2.266-02 2.26E-02 2.52E-02 2.26E-02 4. 16E-02 I ST SEMI-ANNUAL ADULT 6.666-02 6.66E-02 4. 17E-02 6.676-02 6.67E-02 9.03E-02 6.67E-02 1.40E-O I TEEN 6.68E-02 6.68E-02 4. 17E-02 6.69E-02 6.696-02 9.58E-02 6.70E-02 1. 40E.-O I CHILD 6.39E-02 6.39E-02 4. 18E-02 6.40E-02 6.40E-02 9.61E-02 6.416-02 1. 37E-01 INFANT 5.45E-02 5.446-02 4. 17E-02 5.45E-02 5.456-02 8.38E-02 5.46E-02 1. 28E-01 3RD QUARTER ADULT 6.33E-02 6.33E-02 4.36E-02 6.33E-02 6.33E-02 6.37E-02 6.33E-02 1.09E-OI TEEN 6.35E-02 6.35E-02 4.36E-02 6.35E-02 6.35E 02 6.40E-02 6.35E-02 1.09E-DI CHILD 6. 12E-02 6. 12E-02 4.36E-02 6. 12E-02 6. 12E-02 6. 17E-02 6. 12E-02 1.076-01 INFANT 5 '7E-02 5.376-02 4.36E-02 5.37E-02 5.37E-02 5.42E-02 5.37E-02 9. 91E-02 4TH QUARTER ADULT 2.06E-02 2.06E-02 6.06E-03 2.06E-02 2.06E-02 2. 16E-02 2.06E-02 3. 12E-02 TEEN 2.07E-02 2.07E-02 6.06E-03 2 '7E-02 2 '7E-02 2.20E-02 2.07E-02 3. 13E-02 CHILD 1.90E-02 1.90E-02 6.06E-03 1.90E-02 1.90E-02 2 '4E-02 1.90E-02 2.96E-02 INFANT 1.35E-02 1.35E-02 6 '6E-03 1.356-02 1.35E-02 1.48E-02 1.35E-02 2. 4 I E-02 2ND SEMI-ANNUAL
~ ADULT 8.39E-02 8.39E-02 4.97E-02 8.39E-02 8.39E-02 8.53E-02 8.39E-02 1.40E-O I TEEN 8.41E-02 8.4IE-02 4.976-02 8 ~ 42E-02 8.42E-02 8.59E-02 8.41E"02 I . 40E-01 CHILD 8.02E-02 8.02E-02 4.97E-02 8.02E-02 8.02E-02 8 '1E-02 8.02E-02 1,36E-O I INFANT 6.72E-02 6.72E-02 4.97E-02 6.72E-02 6.72E-02 6.90E-02 6.72E-02 I . 23E-01 ANNUAL ADULT I . 51E-01 I ~ 516-01 9. 14E-02 1.51E-01 1 ~ 516-01 I . 76E-01 1.51E-O'I 2.80E-01 TEEN I . 51E-01 I . 51E-01 9. 146-02 I . 51E-01 I ~ 516-01 I . 82E-01 I . 51E-01 2.80E-OI CHILD I . 44E-01 1. 44E-O I 9. 156-02 1. 446-01 1.44E"01 1. 78E-01 1. 44E-01 2.73E-OI INFANT I ~ 22E-01 I ~ 22E-01 9. 14E-02 1.22E-OI I . 22E-01 1.536-01 I . 22E-01 2.51E-OI C4
7" 7' 5
S
PVNGS Semi-Annual Operating Report for July - December 1988 TABLE C2 INTEGRATED POPULATION DOSES FOR JANUARY DECEMBER 1988 PERSONREM JANUARY 1
- JUNE 30 1988 PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+ +
PLUME I 6. 348-01 I B. 348-01 I 6 ~ 34E 01 I 6 ~ 34E-01 I 8 ~ 34E-01 6. 348-01 6.34E-01 2 '9E+00 I
+ + + + +
GROUND I 1.64E 03 I 1.64E-03 I 1.64E-03 I 1 ~ 648-03 I 1.648-03 1.64E-03 1.64E-03 1.92E-03 I INHAL I 7.33E-01 I 7.32E-01 I 1.37E 03 I 7.348-01 I 7.355-01 1.27E+00 7.34E-01 7. 32E-01
+ + + + +
VEGET I 2.2 IE+00 I 2.21E+00 I 3 ~ 25E 03 I 2.21E+00 I 2 ~ 22E+00 3.26E+00 2.21E+00 2. 218+00
+ + +
COW MILK I 3.03E-01 I 3.03E-01 I 4 '58-04 I 3.03E-O'I I 3 '3E-O'I 4. 13E-01 3.03E-01 3.038-01
+ + +
MEAT I 9.34E 02 I 9 '4E 02 I 7 '4E 06 I 9 '4E 02 I 9.34E 02 9.36E-02 9.34E-02 9.34E-02
~TOTAL' I 3 '8E+00 I 3 '8E+00 I 6 '1E-OI I 3 '8E+00 I 3 '8E+00 5.67E+00 3.98E+00 5.638+00
+ +
+'ULY (a)
PER CAPITA 2.21E"06 2.21E-06 3.57E-07 2.218-06 2.21E-06 3. 16E-06 2. 21E-06 3.13E"06 DOSE (REM)
+ + +
1'- SEPTEMBER 30 1988 PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+ + + + + + +
PLUME I 1 42E 01 I 1 ~ 42E O'I I 1 ~ 42E 01 I
'I ~ 42E 01 I 1 ~ 42E 01 1. 42E-01 I ~ 42E-01 5. 28E-01 GROUND I 2.77E-05 I 2.77E-05 I 2.778-05 I 2 77E 05 I 2.77E 05 2.77E-OS 2.77E"05 3.23E-05
+ +
INHAL I 7. 30E-01 I 7. 308-01 I 2. 27E-05 I 7-30E 01 I 7 ~ 30E 01 7.388-01 7.30E-01 7. 308-01
+ +
VEGET I 1.73E+00 I 1.73E+00 I 6.13E"05 I 1 ~ 73E+00 I 1 ~ 73E+00 1.75E+00 1.73E+00 1.73E+00
+ + + + +
COW MILK I 3.03E-01 I 3.038-0'1 I 1.24E-05 I 3.03E-01 I 3.03E"01 3.05E-OI 3.03E-01 3.03E-01 MEAT I 7 '3E 02 I 7 '3E 02 I 2.80E-07 I'.03E"02 I 7.038-02 7.03E-02 7.03E-02 7.03E-02
+ + + + +
~TOTAL' I 2 '8E+00 I 2 '88+00 I 1 ~ 42E-01 I 2 ~ 98E+00 I 2 ~ 98E+00 3.DOE+00 2.98E+00 3.37E+00
+
(a)
PER CAPITA 1.66E-06 1 ~ 66E-06 7. 91E-08 1. 66E-06 1. 66E-06 1. 67E-06 1.66E-06 1.888-06 DOSE (REM)
I OCTOBER 1
- DECEMBER Ql 1988 PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+ + + + + + +
PLUME I 2. 05E-01 I 2.05E-01 I 2 ~ 05E-01 I 2.05E-01 I 2.05E 01 2.05E-01 2. OSE-01 7.05E-OI
+ + +
GROUND I 3 '6E 06 I 3.56E-06 I
+
3.56E-06 I
+
3 '68 08 I
+
3 '6E 06 3.56E-06 3.56E-OB 4.32E-OB INHAL I 9.47E-01 I 9.47E-O'I I 1.12E-04 I 9 ~ 47E-01 I 9. 47E-01 9.94E-01 9. 46E-01 9. 46E-01
+ + + +
VEGET I 2 ~ 98E+00 I 2 ~ 98E+00 I I ~ 29E 04 I 2 '8E+00 I 2 '8E+00 3.03E+00 2.98E+00 2.98E+00
+ + + + +
COW MILK I 3.95E-01 I 3.95E-01 I 1.65E-05 I 3 '5E 01 I 3.958-01 4.01E-01 3.95E-01 3.95E-O'I
+ + + +
MEAT I 1.49E-01 I I ~ 49E 01 I 2 ~ 49E 08 I 1.49E-O'I I 1.498-01 I . 49E-01 1.49E-01 1 . 49E-O'I
+ + + + +
+TOTALS I 4 ~ 67E+00 I 4 ~ 67E+00 I 2 ~ 05E-01 I 4.678+00 I 4 '7E+00 4.78E+00 4.67E+00 5. 17E+00
+
(a)
PER CAPITA, 2.60E-06 2.60E-06 1. 14E-07 2.60E-06 2.60E-06 2.668-08 2.60E-06 2.88E-06 DOSE (REM)
+ + + +
a Personrem divided by 50-mi le population of 1,796,000 C5
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PVNGS Semi-Annual Operating Report for July - December 1988 TABLE C2 (CONTINUED)
PERSONREM JULY 1
- DECEMBER 3) 1988 PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+ + + +
PLUME I 3 '78-01 3.478-01 I 3.478-01 I 3.478-01 I 3 ~ 478-01 I 3 ~ 47E-01 I 3 ~ 478-01 I ) . 23Ev 00 I
+ + + + + +
GROUND I 3. 12E-05 I 3. 12E-05 I 3. 12E-05 I 3.12E-05 I 3.125-05 I 3.12E-05 I 3. 12E-05 I 3. 67E-05 I INHAL I 1 . 688+00 1.68E+00 I 1.35E-04 I 1.68E+00 I 1 ~ 68E+00 I 1 ~ 73E+00 I 1 ~ 68E+00 I 1.68E+00 I
+ + + + + + + + +
VEGET I 4. 71E+00 I 4.7)5+00 I 1. 90E-04 t 4. 7)E+00 i 4. 7)E+00 i 4. 78E+00 I 4. 7) E+00 i 4. 7)E+00
+ + + + + + +
COW MILK ) 6.988-01 I 6. 98E-01 I 2.88E-05 I 6.98E-OI I 6.98E-01 I 7.07E-01 I 6.98E-OI I 6.98E-O) I
+ + + + + + + +
MEAT f 2. 19E-01 / 2. 19E-01 f 3. 05E-07 f 2. 19E-01 / 2. 19E-01 f 2. )BE-01 / 2. ) 9E-01 f 2. 19E-01
+ + + + + + +
+TOTAL' I 7 ~ 65E+00 I 7 ~ 658+00 I 3 ~ 48E 01 I 7 ~ 65E+00 I 7 '5E+00 I 7.78E+00 I 7.65E+00 I 8-54E+00 I
+ + + + +
+
~ (a)
PER CAPITA 4.26E-OB 4.268-06 1.948-07 4.26E"06 4.26E-OB 4.33E-06 4.26E-06 4.76E-06 DOSE (REM)
JANUARY 1
- DECEMBER 31 1988 PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+ + + + + + + + +
PLUME I 9.81E-O) I 9. 81E-01 I 9. 81E-01 I 9.818-01 I 9.81E-01 I 9.818-01 I 9.8)E-01 i 3.52E+00
+ + + + +
GROUND I 1. 67E-03 I 1.678-03 I 'I
~ 67E-03 ( 1 ~ 678-03 / ).87E-03 / 1.67E-03 I 1.678-03 / 1.96E-03
+ + + + + + + + +
INHAL I 2.4'IE+00 I 2 ~ 4)E+00 I 1 ~ 5)E 03 I 2 ~ 41E+00 I 2 ~ 42E+00 I 3 ~ OOE+00 I 2 ~ 41E+00 I 2.41E+00 I
+ + + + + + +
VEGET I 6 ~ 92E+00 I 6.92E+00 I 3.44E-03 6 ~ 92E+00 I 6 ~ 93E+00 I 8 ~ 04E+00 I 6 '2E+00 I 6 '2E+00 I
+ + + + + + +
COW MILK i 'l. DOE+00 1 ~ DOE+00 I 4 ~ 54E 04 I 1.DOE+00 I 1 ~ DOE+00 I ) . 12E+00 I 1 ~ OOE+00 I ).DOE+00 I
+ + + + + +
MEAT I 3. 12E-01 I 3.12E-01 I 7.85E-06 I 3. 2E-01
'I I 3. 25-01
'I I 3. 13E-0) I 3. 12E-01 I 3. 12E-01 I
+ + + + + +
~ TOTAL~ I 1. 16E+01 1. 16E+01 I 9. 89E-01 I 1 ~ 165+01 I 1 ~ 16E+01 I 1 ~ 35E+01 I 1 . I BE+01 I 1 ~ 42E+01 I
+ + + + + + +
'T + + + +
(a)
PER CAPITA 6.46E-06 6.46E-06 5.51E-07 6.46E-OB 6.46E-OB 7.52E-06 6.465-06 7.9)E-06 DOSE (REM)
+
a Personrem d)v)ded by 50-mi le population o)',796,000 C6
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PVNGS Semi-Annual Operating Report for July - December 1988 Table C3 SUMlKARYOF INDIVIDUALDOSES FOR JANUARY- DECEMBER 1988*
Unit Quarter Quarter
¹1 ¹2 Gamma Air Dose mrad 3.73E-01 5.05E-02 T.S. 3.11.2.2 Limit mrad 5.00E+00 5.00E+00
% T.S. Limit 7.46E+00 1.01E+00 Beta AirDose mrad 1.05E+00 1.13E-01 T.S. 3.11.2.2 Limit mrad 1.00E+01 1.00E+01
% T.S. Limit 1.05E+01 1.13E+00 Maximum Organ Dose (neglecting skin) mrem 1.82E-01** 4.48E-02~*
T.S. 3.11.2.3 Limit mrem 7.50E+00 7.50E+00
% T.S. Limit 2.43E+00 5.97E-01 Unit Quarter Quarter Total for
¹3 ¹4 1988 Gamma AirDose mrad 5.38E-02 4.58E-02 5.23E-01 T.S. 3.11.2.2 Limit mrad 5.00E+00 5.00E+00 1.00E+01
% T.S. Limit 1.08E+00 9.16E-01 5.23E+ 00 Beta AirDose mrad 7.65E-02 1.16E-01 1.36E+00 T.S. 3.11.2.2 Limit mrad 1.00E+ 01 1.00E+01 2.00E+ 01
% T.S. Limit 7.65E-01 1.16E+00 6.80E+00 Maximum Organ Dose (neglecting skin) mrem 4.54E-02** 7.76E-02** 3.50E-01 T.S. 3.11.2.3 Limit mrem 7.50E+ 00 7.50E+00 1.50E+ 01
% T.S. Limit 6.05E-01 1.03E+ 00 2.33E+00
- From Table l.
- These control location doses are imparted via three principal atmospheric pathways: plume, ground exposure and inhalation. The highest organ dose is to the teenager's thyroid resulting from exposure in the South Sector at 4.60, 4.50 and 4.23 miles from Units 1, 2, and 3, respectively. Technical Specification 3.11.4 has higher limits than Technical Specification 3.11.2.3 and therefore the percent of limits are more conservative based on Technical Specification 3.11.2.3 than on Technical Specification 3.11.4.
C7
I PVNGS Semi-Annual Operating Report for July - December 1988 DOSE CALCULATIONMODELS The GASPAR computer code was used to evaluate the radiological consequences of the routine release of gaseous effluents. GASPAR implements the dose calculational methodologies of Regulatory Guide 1.109, Revision 1.
Source terms for each quarter are combined with station-specific demographic data and each quarter's atmospheric diffusion estimates for gaseous dose calculations.
Atmospheric diffusion estimates are generated by the XOQDOQ computer code using onsite meteorological data as input. Doses for the semi-annual period are the summation of the quarterly doses. Additional input to GASPAR includes the following site-specific data:
0 to 5 mile land use census conducted in December 1988. The following changes in land use were identified between December 1987 and December 1988: addition of three gardens, the first located in the east-northeast sector at 2.7 miles from Unit 2, the second in the north sector at 1.7 miles from Unit 2 and the third in the northeast sector at 5.0 miles from Unit 2; deletion of a residence in the south sector at 2.8 miles from Unit 2 and one in the south-southeast sector at 4.5 miles from Unit 2.
0 to 5 mile population distribution based on the land use census conducted June-August, 1984.
~ 5 to 50 mile population distribution from PVNGS ER-OL Figure 2.1-6.
~ The population distribution of metropolitan Phoenix greater than 50 miles from PVNGS, based on the 1980 census results, was conservatively included in the 40 to 50 mile sectors.
~ Absolute humidity of 6.0 g/m~ from PVNGS ER-OL Table 2.3-34.
~ The fraction of the year that vegetables are grown (0.667) from PVNGS
.ER-OL Section 2.1.3.4.
~ The fraction of daily feed derived from pasture while on pasture and length of grazing season for milk animals beyond 5 miles (0.35 and 0.75) from PVNGS ER-OL Section 2.1.3.4.
~ The only milk animal (goats) located within 5 miles from PVNGS was fed fiftypercent on stored feed and the other fiftypercent on pasture grass during 1988, based on the land use census conducted in December 1988.
~ The fraction of daily feed derived from pasture while on pasture and length of grazing season for meat animals (0.05 and 0.25) from PVNGS ER-OL Section 2.1.3.4.
Other values used for input to GASPAR are default values from Regulatory Guide 1.109, Revision 1.
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PVNGS Semi-Annual Operating Report for July - December 1988 APPENDIX D CHANGE PAGES TO PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2 AND 3. SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT, JANUARY 1, 1988 THROUGH JUNE 30, 1988
~
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PVNGS Semi-Annual Operating Report for July - December 1988 This Appendix contains the revised portions of the first semi-annual effluent release report For 1988 that were affected by a change in the release amount of tritium from Unit 1 during the second quarter. Tables D1 and D2 reflect the corrected release amount and correspond to Tables A2 and A3, respectively of the first semi-annual report for 1988. Tables D3 and D4 present the corrected doses and correspond to Tables C1 and C3, respectively of the first semi-annual report for 1988. The corrected population doses for the first semi-annual period are presented in Table C2 in Appendix C of this report.
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,, PVNGS Semi-Annual Operating Report for July - December 1988 Table Dl PVNGS UNIT 1 1988 REVISED GASEOUS EFFLUENTS-SUMMATIONOF ALLRELEASES 0
Unit Quarter Quarter Est. Total Error%*
'2
@1 A. Fission & activation ases
- 1. Total release Ci 2.72E+Ol 6.16E+02 3.97E+01
- 2. Average release rate for pCi/sec 3.46E+00 7.84E+01 period
- 3. Percent of technical NA*~ NA**
specification limit B. Iodines
- 1. Total Iodine-131 Ci 1.33E-04 8.29E-04 2.93E+01
- 2. Average release rate for pCi/sec 1.69E-05 1.05E-04 period
- 3. Percent of technical NA**
specification limit C. Particulates
- 1. Particulates with half- Ci 1.75E-04 7.03E-05 2.93E+Ol
)
lives 8 days
- 2. Average release rate for pCi/sec 2.23E-05 8.94E-06 period
- 3. Percent of technical NA**
specification limit
- 1. Total release Ci 5.43E+00 2.13E+02 4.22E+Ol
- 2. Average release rate for pCi/sec 6.91E-01 2.71E+Ol period
- 3. Percent of technical NA** NA**
specification limit
- Estimated total error methodology is presented in Table A8.
- See Table C3 for percent of technical specification limits.
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PVNGS Semi-Annual Operating Report for July - December 1988 Table D2 PVNGS UNIT 1 1988 REVISED GASEOUS EFFLUENTS-GROUND LEVELRELEASES CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter Quarter Quarter Quarter 81 g2 Pl g2
- 1. Fission ases Argon 41 Ci 3.88E-02 2.13E-Ol Krypton-85 Ci <LLD <LLD 8.52E-02 3.30E+00 Krypton-85m Ci <LLD 3.59E-01 1.03E-02 5.02E-02 Krypton-87 Ci <LLD <LLD < LLD 7.21E-04 Krypton-88 Ci <LLD <LLD 7.20E-03 2.77E-02 Xenon-131m Ci 2.15E+00 Xenon-133 Ci 2.28K+00 2.54E+02 1.81E+Ol 3.25E+02 Xenon-133m Ci <LLD <LLD 2.74E-01 2.19E+00 Xenon-135 Ci 6.17E+00 2.78E+01 2.47E-01 1.24E+00 Xenon-135m Ci <LLD <LLD <LLD <LLD Xenon-138 Ci < LLD <LLD <LI D <LLD Unidentified Ci Total for period Ci 8.45E+00 2.82E+02 1.88E+01 3.34E+02
- 2. Iodines Iodine-131 Ci 1.29E-04 7.73E-04 3.67E-06 5.57E-05 Iodine-133 Ci 2.68E-04 7.82E-06 2.02E-06 1.07E-05 Iodine-135 Ci <LLD <LLD .
<LLD <LLD Total for period Ci 3.97E-04 7.81E-04 5.69E-06 6.64E-05
- 3. Particulates Antimony-124 Ci 5.83E-06 1.37E-06 1.19E-05 Barium-140 Ci <LLD 5.31E-06 2.32E-07 <LLD Bromine-82 Ci 3.15E-06 2.18E-05 Cerium-141 Ci <LLD <LLD <LLD <LLD Cerium-144 Ci 8.50E-06 <LLD <LLD <LLD D4
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PVNGS Semi-Annual Operating Report for July- December 1988 Table D2 (Continued)
PVNGS UNIT 1 1988 REVISED GASEOUS EFFLUENTS-GROUND LEVELRELEASES CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter Quarter Quarter Quarter
¹1 ¹2 ¹1 ¹2
- 3. Particulates (continued)
Cesium-134 Ci <LLD 1.57E-05 4.37E-06 2.00E-09 Cesium-137 Ci <LLD 3.13E-05 6.92E-06 1.28E-07 Cobalt-58 Ci 3.32E-05 4.77E-06 8.32E-06 1.28E-08 Cobalt-60 Ci 4.19E-05 4.60E-06 4.01E-05 1.41E-08 Iron-59 Ci 2.01E-06 <LLD <LLD 2.51E-08 Lanthanum-140 Ci <LLD <LLD <LLD <LLD Manganese-54 Ci 3.33E-06 6.64E-07 3.65E-06 <LLD Molybdenum-99 Ci <LLD <LLD <LLD <LLD Niobium-95 Ci 3.46E-06 3.87E-06 Rubidium-88 Ci 1.32E-04 3.18E-03 Ruthenium-103 Ci 1.15E-06 Strontium-89 Ci <LLD <LLD Strontium-90 Ci <LLD <LLD Tin-117m Ci 5.61E-07 6.65E-07 Tritium Ci <LLD 9.60E+Ol 5.43E+00 1.17E+02 Zinc-65 Ci <LLD <LLD <LLD <LLD Zirconium-95 Ci 1.82E-06 Unidentified Ci Total for period Ci 9.99E-05 9.60K+01 5.43E+00 1.17E+02
- Not detected
- Notapplicable D5
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PVNGS Semi-Annual Operating Report for July - December 1988 TABLE 03 REVISED DOSES TO SPECIAL LOCATIONS FOR JANUARY-JUNE 1988 SITE BOUNDARY I 40 MILES
~ SSW FROM UNIT I e 1. 14 MILES SSW FROM UNIT 2 AND 1. 10 MILES SSW FROM UNIT 3 BETA GAMMA AIR DOSES(MRAD)
IST QUARTER 1.05E+00 3.736-01 2ND QUARTER I . 13E-01 5.05E-02 IST SEMI-ANNUAL I . 176+00 4.236-01 T. BODY SKIN MAXIMUM INDIVIDUAL(MREM)
IST QUARTER 2.20E-01 6 ~ 286-01
~
2ND QUARTER 3. I OE-02 8. 16E-02 IST SEMI-ANNUAL 2 ~ 51E-01 7. IOE-01 MAXIMUM INDIVIDUAL IN GENERAL PUBLIC LOCATED AT A RESIDENCE 2.96 MILES S FROM UNIT I, 2.80 MILES S FROM UNIT 2 AND 2.64 MILES S FROM UNIT 3 (MREM) T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN IST QUARTER ADULT 1.59E-01 I . 59E-01 1. 386-01 I . 59E-01 I . 59E-01 2.54E-01 1.59E-O'I 4. 15E-01 TEEN I.59E-01 I . 59E-01 1. 38E-01 I . 59E-01 I . 60E-01 2.766-01 I . 59E-O I 4. 15E-01 CHILD 1.57E-OI 1.56E-01 I . 396-01 I . 57E-01 I . 576-01 2.87E-OI I . 576-01 4. 13E-01 INFANT 1.49E-O'I 1.49E-OI 1.38E-OI I .49E-01 1.49E-01 2.68E-01 I . 49E-01 4.05E-O I 2ND QUARTER ADULT 6.05E-02 6.06E-02 2.03E-02 6.05E-02 6.06E-02 6.48E-02 6.07E-02 9.49E-02 TEEN 6.07E-02 6.07E-02 2.03E-02 6.07E-02 8.07E-02 8.60E-02 6. IOE-02 9.51E-02 CHILD 5. 61E-02 5.61E-02 2.04E-02 5.61E-02 5.61E-02 6. 19E-02, 5. 63E-02 9.05E-02 INFANT 4.09E-02 4.09E-02 2.03E-02 4.09E-02 4.09E-02 4.626-02 4. IIE-02 7.53E-02 IST SEMI-ANNUAL 4 ADULT 2. 19E-01 2. 19E-01 I . 596-01 2.20E 01 2.20E-OI 3. 19E-01 2. 20E-01 S. IOE-01 TEEN 2 '0E-01 2.20E-OI 1.59E-O I 2.20E-OI 2.20E-OI 3.42E-OI 2.20E-O'I 5. I OE-01 CHILD 2. 13E-01 2. 13E-01 I . 59E-O I 2. 'I3E-O'I 2. 13E-01 3.49E-OI 2. 13E-0 I 5.036-01 INFANT 1.90E-OI I . 90E-O I I . 596-01 1.90E-OI I . 90E-01 3. 14E-01 1. 90E-01 4.80E-01 D6
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PVNGS Semi-Annual Operating Report for July - December 1988 Table D4 REVISED SUhQrIARY OF INDIVIDUALDOSES FOR JANUARY- JUNE 1988*
Unit Quarter Quarter Year to
¹1 ¹2 Date Gamma AirDose IIll'ad 3.73E-01 5.05E-02 4.23E-Ol T.S. 3.11.2.2 Limit IIli'ad 5.00E+00 5.00E+00 1.00E+01
% T.S. Limit 7.46E+00 1.01E+00 4.23E+00 Beta AirDose InI'ad 1.05E+00 1.13E-01 1.17E+00 T.S. 3.11.2.2 Limit Ini'ad 1.00E+01 1.00E+01 2.00E+01
% T.S. Limit 1.05E+01 1.13E+00 5.85E+00 Maximum Organ Dose (neglecting skin) mrem 2.87E-OI** 6.19E-02** 3.49E-Ol**
T.S. 3.11.2.3 Limit mrem 7.50E+00 7.50E+00 1.50K+01
% T.S. Limit 3.83E+00 8.25E-01 2.33E+00
- From Table D3.
- These control location doses are imparted via threeprincipal atmospheric pathways: plume, ground exposure and inhalation. The highest organ dose is to the child's thyroid resulting from exposure in the South Sector at 2.96, 2.80 and 2.64 miles from Units 1, 2, and 3, respectively. Technical Specification 3.11.4 has higher limits than Technical Specification 3.11;2.3 and therefore the percent of limits are more conservative based on Technical Specification 3.11.2.3 than on Technical Specification 3.11.4.
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PVNGS Semi-Annual Operating Report for July - December 1988 APPENDIX E REVISED OFFSITE DOSE CALCULATIONhQQVUAL (ODCM)
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CONTROLLED BY USER OFFSITE DOSE CALCULATION MANUAL PALO VERDE NUCLEAR GENERATING STATION UNITS I, 2 AND 3 Originator phvL C LNoh Date ~lo 2o 9--
Tech. Revi ewer Kcvw gurgg~ l~//fat Date ~lZ-Zz-8 Mgr. Radiation Protection & Cheiiiistry Date ~zt Effective Date Ot -ol-89 ta ~~ a q - p,4 t ra CQ Pg 38228,3823E/0409E
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OFFSITE DOSE CALCULATION MANUAL PALO VERDE NUCLEAR GENERATING STATION UNITS 1 2 AND 3 TABLE OF CONTENTS SECTION TITLE PAGE
1.0 INTRODUCTION
1-1 1.1 Liquid Effluent Pathways l-l 1.2 Gaseous Effluent Pathways 1-3 1.3 Nuisance Pathways 1'-4 2.0 GASEOUS EFFLUENT MONITOR SETPOINTS 2-1 2.1 Equivalent Dose Factor Determination 2-2 2.2 Site Release Rate Limit 2-3 2.3 Unit Release Rate Limits 2-5 2.4 Setpoint Determination 2-6 2.5 Monitor Calibration 2-8 3.0 GASEOUS EFFLUENT DOSE RATE 3-1 3.1 Noble Gases 3-1 3.2 Radionuclides Other Than Noble Gases 3-3 4.0 DOSE DUE TO GASEOUS EFFLUENT 4-1 4.1 Noble Gases 4-1 4.2 Iodine-131, Iodine-133, Tritium, and All 4-3 Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days 4.3 Dose Projection 4-6 5.0 TOTAL DOSE AND DOSE TO PUBLIC ONSITE 5-1 5.1 Technical Specification 3.11.4 5-1 5.2 Dose to Public Onsite 5-4 6.0 RADIOLOGICAL ENVIRONMENTAL PROGRAM 6-1 6.1 Radiological Environmental Monitoring Program 6-1 6.2 Land Use Census 6-2 6.3 Interlaboratory Comparison Program 6-4 APPENDIX A DETERMINATION OF CONTROLLING LOCATION A-I Rev. 2
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OFFSITE DOSE CALCULATION MANUAL PALO VERDE NUCLEAR GENERATING STATION UNITS 1 2 AND 3 List of Tab1es TABLE ~TITL PAGE NUISANCE PATHWAYS 1-5 3-1 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS 3-2 PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES-AT THE SITE BOUNDARY (3 SHEETS) 3-5 3-3 P) VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION 3-8 4-1 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY GROUND 4-10 4-2 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY VEGET, AGE GROUP = ADULT 4-11 4-3 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY VEGET, AGE GROUP = TEEN 4-12 4-4 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY VEGET, AGE GROUP = CHILD 4-13 4-5 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY = MEAT, AGE GROUP = ADULT 4-14 4-6 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY = MEAT, AGE GROUP = TEEN 4-15 4-7 R VALUES fOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY MEAT, AGE GROUP = CHILD ' 4-16 4-8 VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY = COW MILK, AGE GROUP = ADULT 4-17 4-9 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY = COW MILK, AGE GROUP = TEEN 4-18 4-10 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY COW MILK, AGE GROUP = CHILD 4-19 Rev. 2
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OFFSITE DOSE CALCULATION MANUAL PALO VERDE NUCLEAR GENERATING STATION UNITS 1 2 AND 3 List of Tab1es (Continued)
TABLE TITLE PAGE 4-11 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY = COW MILK, AGE GROUP = INFANT 4-20 4-12 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY = INHAL, AGE GROUP = ADULT 4-21 4-13 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY = INHAL, AGE GROUP = TEEN 4-22 4-14 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY = INHAL, AGE GROUP = CHILD 4-23 4-15 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY = INHAL, AGE GROUP = INFANT 4-24 4-16 PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS (3 SHEETS) 4-25 6-1 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS (4 SHEETS) 6-5 A-I EXPOSURE PATHWAY LOCATIONS (3 SHEETS) A-2
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OFFSITE DOSE CALCULATION MANUAL PALO VERDE NUCLEAR GENERATING STATION UNITS 1 2 AND 3 List of Fi ures FIGURE TITLE PAGE 2-1 Calibration Curve for PVNGS Effluent Monitors RU-141, RU-143, and RU-145. Response to Noble Gas. 2-9 2-2 Calibration Curve for PVNGS Monitor RU-12.
Response to Noble Gas.
6-1 Radiological Environmental Monitoring Program Sample Sites, 0 to 5 miles 6-9 6-2 Radiological Environmental Monitoring Program Sample Sites, beyond 5 miles 6-10
-1 v-Rev. 2
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1.0 INTRODUCTION
The purpose of the Offsite Dose Calculation Manual (ODCM) is to provide the parameters and methodology to be used in calculating offsite doses and effluent monitor setpoints at the Palo Verde Nuclear Generating Station (PVNGS) for Unit I, Unit 2, and Unit 3.
Included are methods for determining air dose from beta and gamma radiation, and organ dose at the controlling location.due to plant effluents, to assure compliance with the dose limitations in the Technical Specifications. Methods are included for performing dose projections to assure compliance with the gaseous treatment system operability sections of the Technical Specifications. This manual, in addition to Regulatory Guide 1.109, includes the methods used for determining quarterly individual doses for inclusion in Semiannual Radioactive Effluent Release Reports.
- 1. 1 Li uid Effluent Pathwa s Dose calculation methodology for liquid effluents is not included in this manual because of the desert location of the plant and the hydrology of the area. PVNGS is located in the drainage basin of the Centennial Wash, which flows southeasterly into the Gila River. Surface water flows near the site area are intermittent and of short duration because the flows are caused by storm runoff, usually occurring in August and September and from December to April. Surface water bodies, such as ponds, lakes, and marshes, are not present in the area offsite because of the arid climate, the geological character of surficial materials, and the high potential evaporation rate.
The groundwater in the site area consists of an extensive regional aquifer'nd a local perched-water zone. The regional aquifer extends to over 400 square miles. The primary recharge source to the regional aquifer is underflow from the Upper Hassayampa Valley to the north. The general flow direction is Rev. 2
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north to south. Infiltration of precipitation, surface runoff, and return flow from irrigation constitute a small portion o' the total recharge of the aquifer. Discharge of the aquifer occurs as underflow to Arlington Valley to the south and pumpage from irrigation wells (the major use of groundwater in the area).
Contaminated water, if accidentally spilled during plant operation, may seep through the ground surface. For this postulated occurrence, the contaminated water will infiltrate downward through the unsaturated soil and reach the perched water table about 40 feet below the land surface. It will then disperse into the perched groundwater. Further downward movement of water from the base of the perched water zone is restricted due to the presence of the Palo Verde Clay layer about 200 feet below the ground surface. Two aquifer systems have been analyzed for the possible effect of a contaminated water spill: the perched water zone and the underlying regional aquifer. The impact of such postulated accidental seepages on the groundwater system, and in particular on the existing wells located in the 5-mile zone around the site area has been calculated and analyzed in Section 2.4. 13:3 of the PVNGS FSAR. It is shown that the resultant concentrations of the refueling water tank source-term radionuclides are well below the MPC values listed in 10 CFR 20, Appendix B, Table II. Therefore, no methods for calculating doses due.to the liquid have been included.
If geological conditions, surface, or groundwater sources change in the future, or if plant operating conditions become such that the likelihood of a liquid effluent pathway increases, then dose calculation methodology for this pathway will be added to this manual.
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1.2 Gaseous Effluent Pathwa s All gaseous effluents are treated as ground level releases and are considered to be "long-term" as discussed in NUREG-0133, Section 3.3, page 8. This includes the containment purge and gaseous decay tank releases as well as the normal ventilation system and condenser vacuum exhaust releases. All releases are either greater than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> in duration or are made at random,'ot depending upon atmospheric conditions or time of day. The releases are lumped together and calculated as an entity. The historical annual average X/g is therefore used throughout this manual for all gaseous effluent set-point and dose calculations. Airborne releases are further subdivided into two subclasses:
1.2.1 Iodine - 131 Iodine .- 133 Tritium and Radionucl ides in Particulate Form with Half-lives Greater than Ei ht
~Da s In this model, a controlling location is i'dentified for assessing the maximum exposure to a MEMBER OF THE PUBLIC for the various pathways and to critical organs. Infant exposure occurs through inhalation and any actual milk pathway. Child, teenager and adult exposure derives from inhalation, consumed vegetation pathways, and any actual milk and meat pathways. Dose to each of the seven organs listed in Regulatory Guide 1. 109 (bone, liver, total body, thyroid, kidney, lung and GI-LLI) are computed from individual nuclide contributions in each sector. The largest of the organ doses in any sector is compared to 10 CFR 50, Appendix I design objectives.
This dose calculation is performed monthly for all age groups. The release rates of these nuclides will be converted to instantaneous dose rates for comparison to the limits of 10 CFR 20.
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1.2.2 Noble Gases The air dose from both the beta 'and gamma radiation component of the noble gases will be assessed and compared to the 10 CFR 50, Appendix I design objectives. The noble gas release rate will be converted to instantaneous dose rates for comparison to the limits of 10 CFR 20.
This manual discusses the methodology to be used in determining effluent monitor alarm/trip setpoints to be used to assure compliance with the instantaneous release rate limits of Technical Specification 3.11.2.1. Hethods are described for determining the annual cumulative dose to a HEHBER OF THE PUBLIC, from gaseous effluents and direct radiation for critical organs, to assure compliance with Technical Specification 3.11.4.
'he Radiological Environmental Honitoring Program is described in this manual; also included is the Annual Land Use Census Survey.
The ODCH will be maintained for use as a document of acceptable methodologies and calculations to be used in implementing the Technical Specifications. Changes will be incorporated 'into the ODCH in accordance with Technical Specification 6.14.
1.3 Nuisance Pathwa s This section addresses the potential release pathways which should not contribute more than 10% of the doses evaluated in this manual. Table 1-1 lists examples of potential release pathways. The doses from these nuisance pathways will periodically be evaluated to ensure that they do not contribute more than 10% of the doses evaluated in this manual. If any nuisance pathway exceeds this limit then the ODCH methodology for calculation of doses will be applied to each applicable release pathway.
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TABLE 1-1 NUISANCE PATHWAYS (EXAMPLES)
Evaporation Pond Cooling Towers Laundry/Decon Building Exhaust Unmonitored Secondary System Steam Vents/Reliefs Turbine Building Ventilation Exhaust Unmonitored Tank Atmospheric Vents Dry Active Ilaste Processing and Storage (DAllPS) Building Respirator Cleaning Facility Secondary Side Decontamination Equipment 1-5 Rev. 2
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2.0 GASEOUS EFFLUENT MONITOR SETPOINTS Technical S ecification 3.3.3.8 - The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-12 [of the Technical Specifications] shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3. 11.2. 1 are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.
The general methodology for establishing low range gaseous effluent monitor setpoints is based upon a site release rate limit in uCi/sec derived from site specific meteorological dispersion conditions, radioisotopic distribution, and whole body and skin dose factors.
The high alarm of the low range monitors will alarm/trip when the release rate from an individual vent will result in exceeding Technical Specification 3.11.2.1; 80% of Technical Specification 3.11.2.1 limits is considered to be the site release rate limit.
The site release rate limit will be allocated among the licensed units'elease points. The unit release rate limit will then be utilized for the determination of gaseous effluent monitor setpoints. A fraction of the unit release rate limit is then allotted to each release point and its monitor alert setpoint (uCi/cc) is derived using actual or fan design flow rates.
Administrative values are used to reduce each setpoint to account for the potential activity in other releases. These administrative values shall be reviewed based on actual release data.
For the purpose of implementation of Technical Specification 3.3.3.8, the alarm setpoint levels for low range effluent noble gas monitors are established to ensure that personnel are alerted when the noble gas releases approach the total body dose rate of 500 mrem/yr and 3000 mrem/yr skin dose (Technical Specification,
- 3. 11.2. 1). The equations in Section 3.0 of this manual provide the methodology for calculating the gaseous effluent dose rate.
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g The evaluation of doses due to releases of radioactive material can be simplified by the use of equivalent dose factors as defined in Section 2.1.
The equivalent dose factors will be evaluated periodically to assure'hat the best information on isotopic distribution is being used for the dose equivalent value.
- 2. 1 E uivalent Dose Factor Determination The equivalent whole body dose factor is calculated as follows:
g E) [(K( ) (f) ) I (2-1)
Wher e:
K, the equivalent whole body dose factor weighted by historical r adionuclide distribution in releases.
the whole body dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrem/yr per uCi/m~ from Table 3-1.
the fraction of noble gas radionuclide i in the total noble gas radionuclide mix.
The equivalent skin dose factor is calculated as follows:
(L+l e 1M)pq Z> [(L< + I o 1M> ) (f> )] (2-2) 2-2 Rev. 2
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Where:
(L+i.iM)., = the equivalent skin dose factor due to beta and gamma emissions from all noble gases released, weighted by the historical radionuclide distribution in releases.
Lz the skin dose factor due to the beta emissions for each identified noble gas radionuclide i, in mrem/yr per uCi/m'rom Tab 1 e 3-1.
the air dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrad/yr per uCi/m~ from Table 3-1.
the fraction of noble gas radionuclide i in the total noble gas radionuclide mix.
2.2 Site Release Rate Limit (Q>>TE)
The release rates corresponding to 808 of the whole body
((}>>) and skin (Q<<) dose rate limits are calculated using the equivalent dose factors defined in Section 2.1.
The site release rate limit (Q,zTE) is the lower of Q>>
or Q,, thus assuring that the more restrictive dose rate limit will not be exceeded.
The Q,zTE is established as follows:
QszTE, WB . ('we) o.s (2-3)
Keq X Q $ Q'M 2-3 Rev. 2
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Where:
~SITE,MB the site release rate, in uCi/sec, that would deliver a dose rate 80% of the whole body dose rate 1 imi t, D>> .
D>> whole body dose rate limit of 500 mrem/yr.
equivalent ..whole body dose. factor, in mrem/yr per uCi/IIP weighted by the historical radionuclide distribution.
(</~)SBM= 8.91X10-6, the highest calculated annual average disper sion parameter, in sec/IIP, at the Site Boundary for any of the 3 units, from Table 3-2.
0.8 administrative factor to provide conservatism to compensate for any unexpected vari ability in the radionuclide mix and to ensure that Site Boundary dose rate limits will not be exceeded.
SK 0.8 SITE~SK (1+1 e 1H)~q (X/g)ssM (2-4)
Where:
~SITE,SK the site release rate limit, in uCi/sec, that would deliver a dose rate 80% of the skin dose rate limit, DsK .
DSK skin dose rate limit of 3000 mrem/yr.
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(L+1.1H),q ", equivalent skin dose factor, in mrem/yr per uCi/oP, weighted by the radionuclide distribution.
(X /~)seu 8.91X10-6, the highest calculated annual average dispersion parameter, in sec/ms, at the Site Boundary for any of the three units, from Table 3-2.
0.8 administrative factor to provide conservatism to compensate for any unexpected variability in the radionuclide mix and to ensure that Site Boundary dose rate limits will not be exceeded.
After determination of the gsI'TE whole body and skin dose rates (equations 2-3 and 2-4, respectively), the most conservative result will be used as gsITE the site release rate limit.
2.3 Unit Release Rate Limits HIT/
Typically 9<< TE will be divided equally among operating units. If operational history dictates a larger fraction of the g$ ITf be assigned to a specific unit then a weighted average of each unit's contribution to the g<< TE will be utilized to determine the HUH >> .
~UHI T (fUHI T ) (~S I TE ) (2-5) where:
HUH >> = unit release rate limit, in uCi/sec.
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fvwzv the fraction (< 1) of noble gas historically released from a specific operating unit to the total of al noble gas released from the site.
1 g,zzE = the site release rate limit, in uCi/sec determined in section 2.2 of this manual.
2.4 Set oint Determination To comply with Technical Specification 3.3.3.8, the alarm/trip setpoints can now be established using the unit release rate limit (g>>~) to ensure that the noble gas releases do not exceed the dose rate limits.
To allow for multiple sources of releases from different or common release points, the effluent monitor setpoint includes an administrative factor which allocates a percentage of the unit release rate limit to each of the release sources. Monitor setpoints will also be adjusted in accordance with Station Manual Procedures to account for monitor-specific characteristics.
2.4.1 Monitors RU-141 RU-143 and RU-145 The alarm/trip setpoint for Monitors RU-141, RU-143, and RU-145 is calculated as follows:
Monitor Setpoint UNIT a (uCi/cc) <
Where:
Monitor Setpoint = the setpoint for the effluent monitor, in uCi/cc, which provides a safe margin of assurance that the allowable dose rate limits will not be exceeded.
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Quvzv unit release rate limit, in uCi/sec, as determined in Section 2.3.
Flow Rate the flow rate, in cfm, from flow rate monitors or the fan design flow rate for the release source under consideration.
471.9 conversion factor, cubic centimeter/second per cubic feet/minute.
fraction of (}>>~ allocated for a specific release point. The sum of these administrative values will be less than or equal to one.
2.4.2 Monitor RU-12 The alarm/trip setpoint for Monitor RU-12, the Waste Gas Decay Tank Monitor, is calculated as follows:
Monitor Setpoint (uCi/cc) < UNIT a 0.9 - H PF 471.9 (2-7)
F ow Rate 47 .9 where:
Monitor Setpoint = the setpoint for the monitor, in uCi/cc at STP, which provides a safe margin of assurance that the allowable dose rate limits will not be exceeded.
OUNIT unit release rate limit, in uCi/sec, as determined in Section 2.3.
Flow Rate flow rate, in cfm at STP at which the tank 'will be released.
PF the current process flow of the plant vent in CFM.
the current plant vent monitor concentration in uCi/cc.
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fraction of pug,y allocated for a specific release point. This administrative value should be equal to or less than the administrative value used for the Plant Vent.
0.9 an administrative value to account for potential increases in activity from other contributors to the same release point.
471.9 conversion factor, cubic centimeter/second per cubic feet/minute.
If there is no release associat'ed with this monitor, the monitor setpoint should be established as close as practical to background to prevent spurious alarms, and yet assure an alarm should an inadvertent release occur.
2.5 Monitor Calibration The calibration factor for each monitor is entered into the Radiation Monitoring System Database and may change whenever the monitor is calibrated. Calibration is performed in accordance with Station Manual Procedures. The calibration factor may vary with detector age and equipment changes.
The typical calibration conversion factor for the Plant Vent Airborne Monitor (RU-143), .Condenser Evacuation Monitor (RU-141), and Fuel Building Vent Exhaust (RU-145) is based on the detector energy response curve (Figure 2-1) and the FSAR .
source term.
The typical calibration conversion factor for the Waste Gas Decay Tank Monitor (RU-12) is based on the detector energy response curve (Figure 2-2) and the FSAR source term decayed for forty five (45) days.
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10 re 2 E
V 0
E Q 10 1
0 ~
c S
S 4 S I 7 ~ ~ ~ S 10 Maximum Beta Energy (MeV)
FIGURE 2-1 CALIBRATION CURVE FOR PVNGS EFFLUENT MONITORS RU-141, RU-143, AND RU-145. RESPONSE TO NOBLE GAS
Reference:
Kaman Instrumentation Corporation Calibration Report K-82-50-U(R) 2-9 Rev. 2
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O IO5 CL E
C1, IO4 1O-'oo MAXIMUMBETA ENERGY, MeV FIGURE 2-2 CALIBRATION CURVE FOR PVNGS MONITOR RU-12.
RESPONSE to NOBLE GAS
Reference:
Kaman Instrumentation Corporation Calibration Report K-83-30-U(R) 2-10 Rev. 2
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3.0 GASEOUS EFFLUENT DOSE RATE Technical S ecification 3. 11.2. - The dose rate due to radioactive 1
materials released in gaseous effluents from the site (see
'[Technical Specification] Figures 5. 1-1 and 5. 1-3) shall be limited to the following:
- a. For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and
- b. For I-131 and I-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.
3.1 Noble Gases Noble gas activity monitor setpoints are established at release rates which permit some margin for corrective action to be taken before exceeding offsite dose rates corresponding to the 10 CFR 20 annual dose limits as described in Section 2.0. The methods for sampling and analysis of continuous and batch effluent releases are given in the Station Manual Procedures. The dose rate in unrestricted areas shall be determined using the following equations.
For whole body dose rate:
DMe Z [(<<) (X/Q)ssu (Q.)3 For skin dose rate:
DsK =
gi [(Li + l.';) (X/Q)SBN (Qi ) ~ (3-2) 3-1 Rev. 2
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Where:
the whole body dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrem/yr per uCi/m~ from Table 3-1.
Qg the release rate of radionuclide i, in uCi/sec.
8.9lx10-6, the highest calculated annual average dispersion parameter, in sec/m~, for any of the three units, from Table 3-2.
owe the annual whole body dose rate (mrem/yr.).
the skin dose factor due to the beta emissions for each identified noble gas radionuclide i, in mrem/yr per uCi/oP from Table 3-1.
the air dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrad/yr per uCi/P from -Table 3-1 (conversion constant of l. 1 converts air dose-mrad to skin dose-mrem).
Dsx the annual skin dose rate (mrem/yr).
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3.2 Radionuclides Other Than Noble Gases The methods for sampling and analysis of continuous and batch releases for I-131, I-133, tritium and radionuclides in particulate form with half-lives greater than 8 days, are given in the applicable plant procedures. Additional monthly and quarterly analyses shall be performed in accordance with Table
- 4. 11-2 of the PVNGS Technical Specifications. The total organ dose rate in unrestricted areas shall be determined by the following equation:
00 E) H t)@/Q)seu (Ql)3 (3-3)
Where:
p) the dose factor, in mrem/yr per uCi/m~, for radionuclide I
i, for the child inhalation pathway, from Table 3-3.
( /Q)ssu 8.9lx10-6, the highest calculated annual average dispersion parameter, in sec/m~, at the Site Boundary, for any of the three units, Qg the release rate of radionuclide i, in uCi/sec Do the total organ dose rate (mrem/yr).
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TABLE 3-1 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS<'~
Whole Body Gamma Air Beta Air Dose Factor Skin Dose Factor Dose Factor Dose Factor K; L; H) N, Radionuclide (mrem/yr per uCi/m~) (mrem/yr per uCi/m~) (mrad/yr per uCi/m~ ) (mrad/yr per uCi/m~)
Kr-83m 7.56E-02 1.93E<01 2.88Ew02 Kr-85m 1.17E<03 1.46E+03 1.23E%03 1.97003 Kr-85 1.61001 1.34E+03 1.72Ew01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E103 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E404 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1,63E+04 7.83E+03 Xe-131m 9. 15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2. 51E+02 9.94E+02 3.27Ew02 1.48E403 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7. 11E+02 3.36E+03 7.39902 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-.138 8.83E+03 4.13E+03 9. 21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30Et03 3.28E+03
< >>The listed dose factors are for noble gases that may be detected in gaseous effluents.
7 56E 02 = 7.56 x 10 ~.
Reference:
Regulatory Guide 1.109, Table B-l.
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TABLE 3-2 (Sheet 1 of 3)
PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE SITE BOUNDARY CENTERED ON UNIT 1 DISTANCE x/Q D/Q DIRECTION ~METERS ~SEC rrP+ +m- ~g N 1037 4.93 E-06<~> 9.24 E-09 NNE 1057 4.14 E-06 1.19 E-08 NE 2206 2.84 E-06 6.84 E-09 ENE 1967 2.51 E-06 4.43 E-09 E 1927 2.56 E-06 3.24 E-09 ESE 1967 2.61 E-06 2.46 E-09 SE, 2049 3.56 E-06 2.36 E-09 SSE 2730 3.80 E-06 1.58 E-09 S 3006 5.07 E-06 1.78 E-09 SSW 2258 6.52 E-06 3.20 E-09 SW 1487 7.47 E-06 5.65 E-09 WSW 1251 4.52 E-06 5.93 E-09 W 1225 4.73 E-06 9.49 E-09 WNW 1244 3.76 E-06 6.76 E-09 NW 1254 3.43 E-06 5.87 E-09 NNW 1069 3.70 E-06 7.26 E-09 (s) 4 93 E 06 4.93 X 10 6
Reference:
Distances are from the PVNGS ER-OL, Table 2.3-33. Dispersion and Deposition parameters are from a September, 1985, calculation by NUS Corporation based on 9 years of meteorological data; NUS Corporation letter NUS-ANPP-1386, dated October 4, 1985.
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TABLE 3-2 (Sheet 2 of 3)
PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE SITE BOUNDARY CENTERED ON UNIT 2 DISTANCE X/Q D/Q DIRECTION ~METERS ~SEC nPQ. ~m- ~g N 1318 3.85 E-06 6.17 E-09 NNE 1342 3.18 E-06 7.93 E-09 NE 2545 2.42 E-06 5.34 E-09 ENE 2206 2.22 E-06 3.64 E-09 E 2163 2.27 E-06 2.66 E-09 ESE 2067 2.32 E-.06 2.11 E-09 SE 2101 3.47 E-06 2.26 E-09 SSE 3026 3.43 E-06 1.32 E-09 S 2699 5.16 E-06 1.97 E-09 SSW 1836 7.90 E-06 4.56 E-09 SW 1208 7.72 E-06 6.88 E-09 WSW 1014 5.55 E-06 8.44 E-09 W 993 5.86 E-06 1.34 E-08 WNW 1010 4.67 E-06 9.60 E-09 NW 1191 3.62 E-06 6.40 E-09 NNW 1342 2.85 E-06 4.87 E-09
Reference:
Distances are from the PVNGS ER-OL, Table 2.3-33. Dispersion and Deposition parameters are from a September, 1985, calculation by NUS Corporation based on 9 years of meteorological data; NUS Corporation letter NUS-ANPP-1386, dated October 4, 1985.
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TABLE 3-2 (Sheet 3 of 3)
PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE SITE BOUNDARY CENTERED ON UNIT 3 DISTANCE X /Q D/Q DIRECTION ~METERS ~SEC rrP+ +m ag N 1661 3.54 E-06'.86 4.86 E-09 NNE 1693 E-06 6.23 E-09 NE 2756 2.21 E-06 4.65 E-09 ENE 2337 2.08 E-06 3.30 E-09 E 2290 2.14 E-06 2.41 E-09 ESE 2023 2.37 E-06 2.10 E-09 SE 2256 3.24 E-06 2.00 E-09 SSE 2786 3.72 E-06 1.52 E-09 S 2346 5.90 E-06 2.51 E-09 SSW 1607 8.91 E-06 5.73 E-09 SW 1057 8.68 E-06 8,61 E-09 WSW 889 5.34 E-06 8.83 E-09 871 6.72 E-06 1.67 E-08 WNW 885 5.37 E-06 1.19 E-08 NW 1045 4.17 E-06 7.98 E-09 NNW 1561 2.93 E-06 4.58 E-09
Reference:
Distances are from the PVNGS ER-OL, Table 2.3-33. Dispersion and Deposition parameters are from a September, 1985, calculation by NUS Corporation based on 9 years of meteorological data; NUS Corporation letter NUS-ANPP-1386, dated October 4, 1985.
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TABLE 3-3 P,'alues for the Palo Verde Nuclear Generating Station Inhalation Pathway <'>
~Isoto e H 3 1.12E+03
Cr 51 1.70E+04 Hn 54 1.57E+06 Fe 59 1.27E+06 Co 58 1.10E+06 Co 60 7.06E+06 Zn 65 9.94E+05 Sr 89 2.15E+06 Sr 90 1.01E+08 Zr 95 2.23E+06 Sb 124 3.24E+06 I 131 1.62E+07 I 133 3.84E+06 Cs 134 1.01E+06 Cs 137 8.24E+05 Ba 140 1.74E+06 Ce 141 5.43E+05 Ce 144 1.19E+07
<>> Child receptor
1.12E+03 - 1.12 x 10~
References:
NUREG-0133, Section 5.2.1.1 (Calculation of P; (inhalation))
Regulatory Guide 1.109, Table E-5, Table E-9.
NUS Corporation letter NUS-ANPP-1385, dated 9/26/85.
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4.0 DOSE DUE TO GASEOUS EFFLUENT
- 4. 1 Noble Gases Technical S ecification 3. 11.2.2 - The air dose due to noble gases released in gaseous effluents, from each reactor unit to areas at and beyond the SITE BOUNDARY (see [Technical Specification] Figures 5. 1-1 and 5. 1-3) shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation and,
- b. During any calendar .year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
The air dose in unrestricted areas beyond the site boundary due to noble gases released in gaseous effluents from each unit during any specified time period shall be determined by the following equations:
For gamma radiation:
D Y
= (3. 17 x 10-8 ) E> [(Mt ) (X/Q)se (Q (4-1)
For beta radiation:
D 8 - (3. 17 x 10 ) Z,
[(N,) (X/Q)(Q,)] (4-2)
Where:
the air dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrad/yr per uCi/m> from Table 3-1.
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N; the air dose factor due to beta emissions for each identified noble gas radionuclide i, in mrad/yr per uCi/ttP from Table 3-1.
<u'Q)see the highest calculated annual average dispersion parameter, in sec/ttP, at the site boundary for the particular unit, from Table 3-2.
7.47X10-6 from Unit 1
- 7.90X10-6 from Unit 2
= 8.91X10-6 from Unit 3 Dy the total gamma air dose, for the particular unit, in mrad, due to noble gases released in gaseous effluents for a specified time period at the SITE BOUNDARY.
D g the total beta air dose, for the particular unit, in mrad, due to noble gases released in gaseous effluents for a specified time period at the SITE BOUNDARY.
the integrated release, from the particular unit, in uCi, of each identified noble gas radionuclide i, in gaseous effluents for a specified time period.
3.17 x 10-e the inverse of seconds in a year (yr/sec).
The cumulative gamma air dose and beta air dose for a quarterly or annual evaluation shall be based on the calculated dose contribution from each specified time period occurring during the reporting time period.
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4.2 Iodine - 131 Iodine-133, Tritium and All Radionuclides in Particulate Form With Half-Lives Greater Than 8 Da s Technical S ecification 3. 11.2.3 - The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see [Technical Specification] Figures 5.1-1 and 5.1-3) shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ and,
- b. During any calendar year: Less than or equal to 15 mrems to any organ.
The organ dose to an individual from I-131, I-133, tritium, all radionuclides in particulate form, with half-lives 'nd greater than eight days, in gaseous effluents released to unrestricted areas from each reactor unit is calculated using the following expressions:
D, (3.17 x 10-~) gz [ gk (Rzk Wk) (Qz)]
Where:
D, the total accumulated organ dose from gaseous for a particular unit, to a MEMBER OF.
'ffluents THE PUBLIC, in mrem, at the SITE BOUNDARY or at the controlling location.
the quantity of radionuclide i, in uCi, released in gaseous effluents from a particular unit.
4-3 Rev. 2
I Il
the- dose factor for each identified radionuclide i, for pathway k (for the inhalation pathway in mrem/yr per uCi/oP and for the food and ground plane pathways in ma - mrem/yr per uCi/sec) at the controlling location. The R<'s for each age group are given in Tables 4-1 through 4-15.
3.17X10-a = the inverse of seconds per year (yr/sec).
Wg the highest annual average dispersion or deposition parameter for the particular unit, used for estimating the dose at the site boundary or to a MEMBER OF THE PUBLIC at the controlling location for the particular unit.
( X/g) , in sec/m~ for the inhalation pathway and for all tritium calculations, for organ dose at the site boundary, from Table 3-2.
= 7.47X10-~ from Unit 1
- 7.90X10-~ from Unit 2
= 8.91X10 ~ from Unit 3
( X/g)~, in sec/m~ for the inhalation pathway and for all tritium calculations, for organ dose at the controlling location, from Table 4-16.
= 2. 92X10- ~ from Un i t 1
= 2.19X10- ~ from Unit 2
= 2. 31X10- ~ from Unit 3 4-4 Rev. 2
l J
Il 1
II
( D/9),>>, in m-~, for- the food and ground plane pathways, for organ dose at the site boundary, from Table 3-2.
1.19X10-a from Unit 1 1.34X10-a from Unit 2 1.67X10-a from Unit 3
( D/g)<<, in m-a, for the food and ground plane pathways, for organ dose at the controlling location, from Table 4-16.
= 3.25XIO ~ from Unit 1
= 3.88XIO-~o from Unit 2
= 4.21X10 'o from Unit 3 Residences, vegetable gardens and meat and milk animals located within 5 miles of the site will be identified during the annual land use census. The controlling pathway and location will be identified .and will be used for all MEMBER OF THE PUBLIC dose evaluations.
The R; values were calculated in accordance with the methodologies in NUREG-0133 and generated using the GASPAR code. The following site specific information was used to calculate R;:
Value fraction of year milk animals and beef animals are on pasture, f 0.75 fraction of the feed that is pasture grass while the milk and beef animals are on pasture, f, 0.35 4-5 Rev. 2
il I
4A I
l
fraction of year vegetables are grown, f~ approximation 0. 667,.
the annual absolute humidity (g/m~), H 6 These site specific values are from the PVNGS Environmental Report, Section 2 and Appendix 5-B.
4.3 Technical S ecification 3. 11.2.4 - The GASEOUS RADWASTE SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases, from each reactor unit, from the site (see [Technical Specification] Figures 5. 1-1 and 5. 1-3) when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see
{Technical Specification] Figures 5. 1-1 and 5. 1-3) when averaged over 31 days would exceed 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.
Where possible, consideration for expected operational evolutions (i.e., outages, etc.) should be taken in the dose projections.
4.3.1 Noble Gas Dose Pro'ection For the purpose of satisfying requirements of Technical Specification'.11.2.4, the air dose at the site boundary due to noble gases released in gaseous effluents from a particular unit is projected at least once per 31 days.
4-6 Rev. 2
l l
The air dose, in mrads for the current quarter is determined using the methodology described in Section 4.1 of this manual. This information is used to determine an air dose projection for the next 31 days using the following equations:
For gamma radiation:
y qtr/Tqtr) 31 day> = (D 31 + CDy (4 4)
For beta radiation:
31 day g =
(Dg qtr/Tqtr) 31 + CDg where:
Dy qtr = the total gamma air dose due to noble gases released in gaseous effluents for the current quarter, in mrads, at the site boundary.
D8 qtr = the total beta air dose due to noble gases released in gaseous effluents for the current quarter, in mrads, at the site boundary.
Tqtr = the time period, in days, over which Dy qtr and D g qtr were integrated.
31 the number of days over which the dose projections are made.
],
I I
31 dayy = the 31 day projected gamma air dose due to noble gases released in gaseous effluents, in mrads, at the site boundary.
31 day8 the 31 day projected beta air dose due to noble gases released in gaseous effluents, in mrads, at the site boundary.
CDy any current or projected gamma air dose, in mrads, due to noble gases released in gaseous effluents, which could have a significant impact on 31 day y CDg any current or projected beta air dose, in mrads, due to noble gases released in gaseous effluents, which could have a significant impact on 31 dayg .
Or an Dose Pro ection For the purpose of satisfying requirements of Technical Specification 3.11.2.4 for a particular unit, the organ dose, in mrem, for the current quarter is determined using the methodology described in Section 4.2 of this manual. This information is used to determine an organ dose projection for the next 31 days using the following equation:
3lday, = (D, qtr/Tqtr)31 + CD, (4-6) 4-8 Rev. 2
a l
I l
l
where:
D, qtr the total organ dose from a particular unit due to I-131, I-133, tritium, and all radionuclides in particulate form with half-lives greater than eight days, released in gaseous effluents for the current quarter, in mrem.
Tqtr the time period, in days, over which D,qtr was integrated.
31 the number of days over which the dose projections are made.
31 day, = the 31 day projected organ dose, in mrem, from a particular unit.
CD any current or projected organ dose for a particular unit, in mrem, which could have a significant impact on 31 day,.
4-9 Rev. 2
I
<J I
l l
I
TABLE 4-1 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION<'7 PAINUAY ~ GROUND NUCLI DE T. BODY Gl- TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
-+---
Ih 54 Cr 51
+
)
1.38Et09 4.65Et06 lie jt 1.38Et09 4.65ft06
+
)
1.38Et09 4.65f+06 t
t) 1.38Et09 4,65Et06
- l. 1.38Et09 4.65Et06
) 1.38Et09 4.65E+06
+
)
1 38E 09 4.65E+06
)
1 5.49E+06 62E 09
+
)
t) )
+ +
)
t) t
) ) )
+ t) )
Fe 59 2.72Et08 2.72Et08 2.72E+08 2.72Et08 2.72Et08 2.72E+08 ) 2.72Et08 3.20Et08
+
)
-- -- -+) -- - - -t) ) ) )
t- - -- +)
)
Co 58 3.79f+08 3.79E+08 3.79E+08 3.79E+08 3.79E+08 3.79E+08 3.79E+08 4.44E+08 t-
) )
+
)
+
I ) )
+
)
-t--- - +
)
Co 60 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2. 15E+10 2.52Et10
) )
+ t) ) ) )
-t-- - -- -t - - - t
) )
Zn 65 7.44E+08 7.44Et08 7.44Et08 7.44E+08 7.44Et08 7.44E+08 ) 7.44Et08 8.56Et08
)
+
) )
+
) ) )
-+)
Sr &9 )
2.16E+04 ) 2.16E+04 ) 2.16Et04 ) 2.16E+04 ) 2 16Et04 ) 2 16E 04 ) 2.16E 04 ) 2 ~ 50E+04 1 Zr 95 2.45Et08 2.45Et08 2.45E+08 2.45Et08 2.45Et08 2.45E+08 2,45E+08 2.84Et08 t
) )
+
)
-t-
) ) )
+ - - - -t--
) )
+
)
Sb124 5.98E+08 5.98E+08 5.98E+08 5.98E+08~) 5.98Et08 5.98Et08 5.98Et08 6.91E+08
)
+- --- -t) --- +
) ) ) ) ) )
I 131 1.72E+07 1.72E+07 1.72f+07 ) 1.72E+07 1.72Et07 1.72Et07 1.72E+07 2.09E+07 t
) )
-+) - - - -+- t) ) )
+
)
+
I 133 .) 2.45E+06 2.45Et06 ) 2.45E+D6 ) 2.45Et06 2.45Et06 ) 2.45E+06 2.45E+06 2.98Et06
+
)
t t +-
) )
) f Cs134 )
6.82E+09 )
6.82E+09 )
6.82f+09 )
6.82E+09 )
6.82Et09 )
6.82Et09 )
6.82E+09 )
7.96Et09
+ +
Csl37 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.20E+10 f--
) ) ) ) ) )
4
)
t) )
Ba140 2.05Et07 2.05Et07 )
2.05E+07 ) 2.05Et07 ) 2.05E+07 ) 2.05Et07 ) 2.05E+07 ) 2.34Et07 )
)
t)
Cel41 1.36E+07 1.36E+07 1.36E+07 1.36Et07 1.36Et07 1.36Et07 1.36E+07 1.54Et07
)
t)
) )
t) t
)
+
)
+
)
t)
Ce144 6.95Et07 )
6.95Et07 6.95Et07 )
6.95Et07 6,95Et07 6.95E+07 6.95Et07 8.03Et07
) )
+
)
- -- t) ) ) )
(a) R values are in units of m2-mrem/yr peY uCi/sec.
(b) 1.38E+09 = 1.38 X 109.
Reference:
NUREG-0133; NUS Corporation letter NUS-ANPP-1385, dated 9/26/85.
TABLE 4-2 R VALUES FOR THE PALO.VERDE. NUCLEAR GENERATING STATION<o>
PATINAY > VEGET AGE GROUP = ADULT UUCLIDE T.BODY GI-TRACT BODE LIVER KIDUEY THYROID LUUG SKIII
t--------wit- t + + +
H 3 4.34E OP( 4.34E 03 i O.OQE-OI i 4.34E 03 i 4.34E 03 i 4.34E 03 / 4.34E 03 4.34E 03 i ti t + t t J IIo 54 5.65Et07 9.07Et08 O.QOE-OI i 2.96Et08 / B.BIEt07 / O.OOE-OI i O.OOE-OI O.OOE-OI ti i t
J t t )
Cr 51 i 3.99Et04 (
I.OQEt07 (
O.OOE-OI O.OOE-OI ) 8.79Et03 ) 2.3&Et04 )
5.29Et04 J O.OOE-OI i J
+ -+-
Fe 59 1.02Et08 i 8.91Et08 / 1. 14Et08 / 2.67Et08 /
O.OOE-OI i O.OOE-OI i 7.47E+07 i O.OOE-QI
/
+ + - -- -t --- -- -t- --- - - +--
Co 58 6.3&E+07 5.77E+08 O.OOE-DI / 2.85E+07 i O.OOE-QI O.OOE-OI O.OOE-OI O.OOE-OI t/ t/ /
+ + +-
( (
+
(
+ -----+(
Co 60 3.51E+08 i 2.99E+09 i O.OOE-QI i 1.59Et08 O.OOE-OI i O.OOE-OI O.OOE-QI O.OOE-QI i )
-+) -- -- -+) -- --+ J Zn 65 / 4.31Et08 i 6.01Et08 )
3.DOE+08 i 9.54E+08 )
6.3&E+08-j O.OOE-QI f O.QOE-QI )
0 ~ OOE-01
+ + + + + +
Sr 89 2.60Et08 1.45E+09 9.06E+09 O.OOE-QI / O.OOE-OI ) O.OOE-OI O.OOE-QI O.OOE-OI f f ) )
+
Sr 90 i 1.41E+ll J 1.66E+10 j 5.76E+11 i O.OOE-OI )
O.OOE-OI
)
O.OOE-OI J O.OQE-OI ) O.OOE-OI
+ +
Zr 95 2.35E+05 I.IOEt09 i I.OBE+06 f 3.47E+05 5.45E+05 O.OOE-OI i Q.QOE-01 Q.OOE-QI
[
+
)
+- -- --- +- ) )
+
Sb124 3.7&Et07 i 2.71E+09 9.53E+07 1.&OE+06 ) Q.OOE-OI 2.31E+05 7.42E+07 O.OQE-OI
[
t- -- -- t --- ---ti --- ---+-
J )
+
) )
I 131 )
4.49E+07 )
2.07E+07 )
5.47Et07 i 7.83Et07 )
1.34Et08 )
2.57E+10 )
O.OOE-QI )
O.OOE-OI i
+ + +
I 133 7.35E+05 i 2.17Et06 1.39E+06 2.41E+06 4.21Et06 3.54Et08 i Q.OOE-OI 0.00E-OI
)
t +
)
t) )
+
)
+
)
-+)
Csl34 &.62Et09 1.85Et08 i 4.43E+09 1.05E+10 j 3.41Et09 i O.OOE-OI 1.13E+09 O.OOE-OI
)
+
)
+
)
t +
) )
+
Cs 137 5.42Et09 1.60Et08 6.05E+09 8.2&Et09 )
2.&IE+09 j O.QQE-OI 9.34Et08 O.OQE-01
)
t) )
+
) ) ) )
+
Ba140 6.17Et06 i 1.94EtOS i 9.42Et07 i I.IBEt05 4.03Et04 )
O.QQE-OI 6.7&E+04 i O.QOE-DI )
t) + +
) )
+
Ce 141 1.33Et04 i 4.47Et08 i 1.73Et05 1.17Et05 5.43Et04 i 0:OOE-Dl i O.OOE-OI i O.OQE-OI i
)
t- )
t)
+--
Ce144 1.67Et06 i 1.05E+10 j 3. IIEt07 1.30Et07 ) 7.72Et06 i Q.OOE-OI ) O.OQE-OI i O.OOE-OI
) /
-+ --- t-- -- t.
(a) R values are in units of mrem/yr per uCi/m3 for tritium, and in units of
.m2-mrem/yr per uCi/sec for all others.
(b) 4.34E+03 = 4.34 X 103 .
J 1
I l
II
TABLE 4-3 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION<e>
PAIIQAY = VEGET AGE GROUP R TEEN'UG LIDE T. BODY GI-TRACT BONE LIVER KIDHEY THYROID . LUNG SKIN
t--------VEt- + + + + -+ - - ---+
H 3 5.08EtOJ f 5.08Et03 O.OOE-01 5.08E+03 5.08E+03 5.08Et03 5.08E+03 5.08Et03
) ) ) )
t ----
)
t--------
) )
l.
)
+ + +
Hn 54 I 8.72Et07 I 9.02Et08 O.OOE-Ol I 4.40Et08 I 1.31E+08 I O.OOE-01 I O.OOE-01 I O.OOE-01 I Cr 51 5.58Et04 9.37Et06 O.OOE-OI O.OOE-01 1.22E+04 3.10E+04 7.96E+04 O.OOE-01
) )
+
) )
+
) )
+
)
t
) )
Fe 59 )
1.52Et08 )
9.28Et08 1 68E+08 )
3'92E+08 )
0'OOE 01 )
0 OOE 01 )
1'24E+08 )
0'OOE 01 I
+ +
Co 58 )
9.60Et07 )
5.74Et08 )
D.OOE-Ol )
4.17E+07 I D.ODE-01 )
O.OOE-01 I O.OOE-01 I O.OOE-01 I
+
Co 60 5.44Et08 3. 14Et09 O.OOE-OI 2.41E+08 O.OOE-OI O.OOE-OI O.OOE-01 O.OOE-Ol
t
) ) ) ) )
+
) ) )
Zn 65 6.64E+DB 6.03Et08 4.10E+08 1.42E+09 9.11E+08 O.OOE-01 O.OOE-01 O.OOE-01
) ) )
t-
) )
+ +
)
-- - -t
)
--- t--
)
-+)
Sr 89 4.09Et08 1.70Et09 1.43E+10 I O.OOE-01 I O.OOE-01 O.OOE-Ol ) 0 ~ OOE-01 )
O.OOE-DI
)
f )
t) I Sr 90 1.80E+11 2.05E+10 i.7.29EI12 i O.OOE-Ol [ O.ODE-Dl O.OOE-Ol O.OOE.Ol i O.OOE.Ol
) )
+- - --- t [ i t
Zr 95 I 3 56E+05 1'9E+09 1'64E+06 )
5 IBE+05 ) 7.60E+05 O.OOE-Ol O.OOE-OI O.OOE-OI
+
)
+---
)
+
) ) )
Sb124 5.73Et07 I 2.96E+09 I 1.47E+08 2.70E+06 O.OOE-01 3.33E+05 1.28E+08 O.OOE-01
)
+- --t) ----t) )
I 131 3.97E+07 1.46E+07 5.28Et07 7 .40E+07 ) 1.27Et08 2. 16E+10 O.OOE-Ol I O.OOE-01 I
)
--+) )
-t I )
I 133 )
6.66Et05 )
1.65Et06 )
1.29Et06 I 2.18E+06 I 3.83E+06 )
3.05E+08 )
O.OOE-OI )
O.OOE-DI
+ + +
Cs134 7.52Et09 2.02Et08 6.89Et09 1.62E+10 5.15Et09 O.OOE-01 1.97Et09 O.OOE-01
)
t)
+
) )
+ -+) ) )
t)
Cs137 4.56E+09 1.86Et08 9.84E+09 1.31E+10 4.46E+09 O.OOE-OI ) 1.73Et09 )
O.OOE-01
+
)
t
) )
-+- ) ) )
+ +
Ba 140 6.87Et06 1.65Et08 1.07Et08 )
1.31Et05 ) 4.43E+04 O.OOE-DI 8.79Et04 O.OOE-Ol t) )
t)
-+
) ) )
-+
Ce141 2.00Et04 I 4.97Et08 I 2.60E+05 1.74Et05 8.18Et04 O.OOE-01 I O.OOE-01 I O.OOE-01
)
t) )
I I Cel44 2.74Et06 1.28E+10 5.11E+07 2.11E+07 1.26E+07 O.OOE-01 O.OOE-OI I O.OOE-OI I j )
+
)
+
)
t
) ) )
(a) R values are in units of mrem/yr per uCi/m3 for tritium, and in units of m2-mrem/yr per uCi/sec for all others.
(b) 5.08E+03 = 5.08 X 103 .
TABLE 4-4 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION(s PATIMAY VEGET AGE GROUP ~ CHILD HUCLIDE T.OODY GI-TRACT 80WE LI VER KIDHEY THYROID LUHG SKIN
+ %6~ + + + -t - ---- t H 3 7.91Et03 'f 7.91Et03 O.OOE-OI 7.91Et03 7.91E+03 7.91E+03 7.91Et03 7.91Et03
)
t
) ) ) )
l.
) ) )
t +
Hn 54 1.73Et08 5.44Et08 O.OOE-OI 6 48E+08 1 82E+08 0 OOE Ol I O.OOE Ol I 0 OOE 01 I I I
! f f Cr 51 I 1.08E+05 )
5.73Et06 )
O.OOE-OI )
0 ~ OOE 01 I I 64E 04 ) 6 OOE 04 )
I 09E 05 I 0 ~ OOE Ol'
-+-
Fe 59 3.04Et08 6.36Et08 3.78E+08 6.11Et08 O.OOE-OI O.OOE-OI 1.77Et08 O.OOE-OI t- ) ) )
t
)
-t) ' )
t l.
) )
+ +
Co 58 1.90E+08 I 3.63E+08 O.OOE-OI 6.22E+07 I O.OOE-OI I O.OOE-OI )
O.OOE-OI I O.OOE-OI f f Co 60 1.09Et09 2.05E+09 O.OOE-01 3.70E+08 O.OOE-OI O.OOE-01 O.OOE-01 I O.OOE-01 I
) )
t) ) )
t
) )
ln 65 )
1.31Et09 )
3.70Et08 )
7.92E+08 )
2.11E+09 )
1.33E+09 )
O.OOE-OI )
O.OOE-OI )
O.OOE-OI
-+ + -+ +
Sr 89 9.80Et08 1.33E+09 3.43Etl0 O.OOE-OI O.OOE-OI O.OOE-OI O.OOE-OI O.OOE-OI
)
+ t
) ) )
+
) )
-t) t
)
)
Sr 90 3.08E+ll 1.64E+10 1.22E+12 O.OOE-OI O.OOE-OI O.OOE-OI O.OOE-OI O.OOE-OI
)
+ t
)
+
) ) ) )
+
) )
Lr 95 7.27Et05 8.52Et08 3.72E+06 8.17E+05 1.17Et06 O.OOE-01 O.OOE-DI O.OOE-OI
) )
+
) ) )
---+- - -- - t---
)
---t) t
) )
Sb124 1.19Et08 I 2.12Et09 I 3.38E+08 4.39Et06 I O.OOE-OI I 7.47Et05 I 1.88Et08 I O.OOE-OI f )
I 131 )
5.67Et07 )
8.89Et06 )
+
9.92E+07 t
)
9 9 0 I " +
t)
-3 E+10 t) 0 I )
I 133 1.10Et06 1.17Et06 2.35Et06 2'90Et06 4'84E+06 )
5 39Et08 0'OOE Ol ) 0'OOE Ol t) ) )
+- ) )
+- )
+ +
Csl34 5.42Et09 1.39Et08 1.57E+10 ') 2.57EtIO 7 ~ 96Et09 ) 0.00E-01 2.86Et09 0 OOE 01 I
)
+-- ) ) )
+- --------t----------t----------t
) )
Csl37 3.31Et09 1.40Et08 2.34E+10 2.24E+10 7.30E+09 O.OOE-OI 2.63E+09 ) O.OOE-OI
+
)
t)
+
)
+
)
+
)
+
)
t) i 8a140 1.28Et07 1.11Et08 2.20E+08 1.93Et05 6,27E+04 O.OOE-OI 1.15Et05 O.OOE-OI
) )
t ) )
t) t) t-
)
-- - )
Cel41 ) 4.54Et04 I 3.82E+08 tI 6.14Et05 l. 3.06E+05 I 1.34E+05 I O.OOE-OI O.OOE-OI
+
I O.OOE-OI
t----------t
-+)
Ce144
+
)
6.61Et06 )
1.DIE+10 I 1.24Et08 l. 3.89Et07 I 2.15Et07 I O.OOE-OI t)
O.OOE-OI I O.OOE-OI )
(a) R values are in units of mrem/yr per uCi/m3 for tritium, and in units of m2 -mrem/yr per uCi/sec for all others.
(b) 7.91E+03 = 7.91 X 103 .
l I
I l
~
I
TABLE 4-5 R VAIUES FOR THE PALO VEROE NUCLEAR GENERATING STATION<
PAlhMAY ~ HEAT AGE GROUP ADULT NUCLIDE T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
t------ -yg +--- t + +
H 3 )
6.55Et02 6.55Et02 )
O.OOE-Ol )
6.55Et02 )
6.55E+02 )
6.55EtOZ )
6.55E+02 )
6.55Et02 )
+ + + + +
Mn 54 8.29Et05 1.33Et07 O.OOE-OI 4.34E+06 1.29Et06 O.OOE-01 O.OOE-01 O.OOE-OI
)
+ t
)
t) +
) ) )
+ t
)
+
)
Cr 51 2.04Et03 )
5.12E+05 )
O.OOE-DI O.OOE-01 4.48E+02 1.2ZEt03 2.70E+03 O.OOE-01 )
(
+ t) t) ) )
t) +
Fe 59 7.78Et07 6.77Et08 8.64E+07 2.03E+08 O.OOE-01 O.OOE-01 5.67Et07 O.OOE-Ol )
-+) t ) )
t
)
+ t) +
) ) )
+
Co 58 (
1.51E+07 )
1.37E+08 (
O.OOE-OI ( 6.74E+06 ( O.OOE-DI ( O.OOE-DI ( O.OOE-01 O.OOE-01
} }
Co 60 )
8.49E+07 )
7.23E 08 )
O.OOE-OI )
3.85E 07 )
O.OOE-01 )
O.OOE-01 )
O.OOE-01 )
O.OOE-01 )
r En 65 2.36Et08 3.29Et08 )
1.64E+08 5.23E+08 3.50E+08 O.OOE-OI O.OOE-DI O.OOE-01
(
+
)
+
)
t) )
+ t
)
- t)
+
(
Sr 89 )
2.91E+06 )
1.63E+07 (
1.02Et08 ( O.OOE-OI )
O.OOE-01 ( O.OOE-OI ( O.OOE-01 ( O.OOE-DI )
+
Sr 90 )
1.58Et09 )
1.86Et08 )
6.45E+09 )
D.OOE-01 )
O.ODE-01 )
O.OOE-Ol ( O.ODE-Ol )
O.ODE-01 )
+ + + +
Zr 95 1.46Et05 6.85Et08 6.74E+05 2.16E+05 3.39E+05 O.OOE-01.) O.OOE-01 O.OOE-DI
-t) ---- - )
+-
( )
+
)
--t) t (
+
)
2.78E+06 1.99E+08 7.01Et06 1.32E+05 ( O.OOE-01 ( 1.70E+04 ( 5.45f+06 Sb124
} ) ) )
f----------t---------- O.OOE-01 ( (
I 131 2.31E+06 1.06E+06 2.81E+06 4.03Et06 ) 6.90Et06 1.32E+09 0.00E-OI 0.00E-DI
} } } } )
-t--- - - t -- - - t
( (
I 133 5. 14E-02 )
1.52E-01 )
9.69E-02 (
1.69E-DI ( 2.94E-Ol ( 2.48Et01 ( O.OOE-OI ( O.OOE-OI
}
C5134 6.39Et08 1.37Et07 )
3.28Et08 )
7.81Et08 ( 2.53E+08 ( O.OOE-Ol ( 8.39E+07 ( O.OOE.01 (
} } +
Csl37 4,05Et08 1,20E+07 4,52Et08 6.18Et08 2,10Et08 O.OOE-01 6.98Et07 O.OOE-OI
+
) )
t) )
--t-)
t) t-
) (
Ba140 4.97E+05 1.56E+07 7.59E+06 9.54Et03 ( 3.24Et03 ) O.ODE-OI ( 5.46E+03 ) O.OOE-01
)
t-
) ( )
t t )
Ce141 )
3 23E'02 I 1 09E'07 )
4 21E'03 )
2.85E'03 )
1 32Et03 ( 0'OOE 01 ( 0 ODE Ol )
0 ~ OOE"01 (
Ce144 )
3.67E+04 )
2.31E+08 (
6.84E+05 )
2.86Et05 )
~
1.70E+05 )
O.ODE-Ol (
O.OOE-OI )
O.OOE-Ol )
+ + + + +
(a) R values are in units of mrem/yr per uCi/m3 for tritium, and in units of m2-mrem/yr per uCi/sec for all others.
(b) 6.55E+02 = 6.55 X 102.
l I
I
TABLE 4-6 R VALUES FOR THE PALO, VERDE NUCLEAR GENERATING STATION<a PAIIMAY = HEAT AGE GROUP TEEN UUCLIDE T.BODY Gl-TRACT BORE LIYER KIDUEY THYROID LUIIG SKIN
t--------opt + + t +
II 3 3.9IEt02 f 3.91Et02 O.OOE-OI )
3.91E+02 3.91Et02 3.91Et02 3.91Et02 3.91Et02 )
)
+
) )
t
)
t) t
)
Hn 54 6.57Et05 )
6.79Et06 f O.OOE-OI 3.31E+06 f 9.88E~OS f O.OOE-DI f O.OOE-DI )
O.OOE-OI
)
+ + +- )
+ )
Cr 51 )
1.63Et03 )
2.74E+05 )
O.OOE-DI )
O.OOE-OI f 3.57Et02 f 9.04E 02 )
2.32E+03 f O.OOE-OI )
Fe 59 6.22E+07 3.DIE+08 6.91E+07 1.61E+08 O.OOE-OI O.OOE-OI S.OBE+07 O.OOE-OI
) )
tf )
+ +
)
- -- -- -t -- ----
)
-+) ---------t---- -
)
- +
Co 58 ) 1.20E+07 ) 7. 16E+07 )
O.OOE-OI ) S. 19E+06 ) O.OOE-OI f O.OOE-OI ) O.OOE-OI ) O.OOE-01 )
Co 60 6.72E+07 3.89E+08 O.OOE-OI 2.99Et07 O.OOE-OI O.OOE-OI O.OOE-DI O.OOE-DI f
)
+
) f )
tf t) t
) )
Zn 65 1.87E+08 1.70Et08 1.15E+08 4.DIE+08 2.57Et08 O.OOE-OI f O.OOE-DI O.OOE-OI
) f t
) )
t ) )
+
)
+
)
Sr 89 2.4SE+06 1.02Et07 8.57E+07 O.OOE-OI O.OOE-OI O.OOE-DI O.OOE-01 O.OOE-01
-t) - -- t-
)
- - -- t- )
- -- --+-
)
t ) ) ) ) )
Sr 90 1.03E+09 1.17E+08 4.17E+09 O.OOE-OI ) O.OOE-OI f O.OOE-OI O.OOE-OI f O.OOE-OI f
+
f f
+ t
) f r +
)
Zr 95 1.1?E+05 )
3.93E+08 )
5.40E+05 1.?DE+05 2.ME+OS O.OOE-01 O.OOE-Ol O.OOE-OI 0 t) - - -- t- t-
)
t) f
+
)
t)
+
)
Sb124 2.23Et06 1.15E+08 5.72E+06 1.05E+05 O.OOE-OI f 1.30E+04 5.00Et06 O.OOE-OI f t) )
t) )
+
)
t tf f
+
I 131 )
1.76E+06 f 6.48E+05 )
2.34Et06 f 3.27E+06 )
5.64E+06 )
9.56EtO& )
O.OOE-OI )
O.OOE-01 )
+ --+ t +
tl
'E-2) 04E-'
t
.I'-2)13E-t +
I ~ "'
+
I E'l
+
I
. E-ol
+
I E-l I Cs134 2.85E+08 7.64Et06 2.61E+08 6.14E+08 f 1.95Et08 l 0.00E-OI l 7.45E+07 D.OOE.OI f f f ) )
i Cs137 1.74E+08 f 7.11Et06 3.75E+08 f 4.99Et08 )
1.70Et08 )
0.00E-01 6.60Et07 O.OOE-01 )
)
tf + +
)
t
)
+
Ba140 )
4.04Et05 )
9.68Et06 6.28Et06 7.69Et03 2.61E+03 0.00E-OI 5.1?E+03 f 0.00E-OI t +
) ) )
t) )
t" t +
Ce141 2.71Et02 6.75E+06 3.53Et03 2.36Ei03 ),1.11Et03 O.OOE-DI 0 OOE-01 O.OOE-01 t--
f
- - f t- -- - - )
t- f t
) ) ~
t) )
Ce144 3.10EtD4 1.45Et08 5.76Et05 2.38Et05 1.42Et05 f O.OOE-OI O.OOE-OI O.OOE-OI
) ) )
--tf ) )
+
)
tf (a) R values are in units of mrem/yr per uCi/m3 for tritium, and in units of m2-mrem/yr per uCi/sec for all others.
(b) 3.9lE+02 = 3.9l X 102.
~
a gi
TABLE 4-7 R VALUES FOR THE PALO iVERDE NUCLEAR GENERATING STATION(e)
PAlIQAY = HEAT AGE GROUP ~
NUCLIDE H 3
+
I CHILD T. BODY f
Gl-TRACT 4.72Et02$ 4.72Et02
+
+
tI DONE O.OOE-OI
'II YER 4.72E+02
+
tI KIDNEY 4.72Et02 t
I THYROID 4.72Et02 LUNG 4.72Et02
+
I SKIN 4.72E+02 I Hn 54 I 1.01Et06 I 3.18Et06 I 0.00E-OI I 3.79E+06 I 1.06Et06 0.00E-OI O.OOE-OI O.OOE-OI
+-- I Cr 51 2.54E+03 1.35Et05 O.OOE-OI I O.OOE-OI I 3.85E+02 1.41Et03 2.57E+03 O.OOE-OI tI I I
-+- I
+
I Fe 59 9.87E+07 2.06Et08 1.22E+08 1.98E+08 I 5 '4E+07 I O.OOE-OI I I I I I O.OOE-Ol I O.OOE-OI
+ +
Co 58 1.86Et07 I 3,54Et07 I 0.00E-01 I 6.07Et06 O.OOE-OI 0.00E-OI O.OOE-01 O.OOE-01 I
t- t---- -----+- I
+
I Co 60 I 1.05E+08 1.96Et08 I O.OOE-OI I 3.54Et07 O.OOE-OI I O.OOE-OI O.OOE-OI'.OOE-01 I
--t- I 1 j I 2.87E+08 I 8.11Et07 I 1.73E+08 I 4.62E+08 Zn 65 2.91E+08 i Q.OOE-01 O.OOE-01 O.OOE-OI
t- -+- I
+- I
+---
I Sr 89 4.63E+06 6.28E+06 1.62E+08 O.OOE-OI O.OOE-OI I O.OOE-OI 0.OOE-OI Sr 90 I
t 1.37Et09 I I 7.26E+07 I 5.39E+09 I I l O.OOE-OI J I I
t----------f-O.OOE-OI I I O.OOE-01 e- -
I O.OOE-OI O.OOE-01 O.OOE-01 l
Zr 95 1.88E+05 I 2.2OEt08 I 9.59E+05 I 2.11E+05 I 3.0?Et05 O.OOE-01 O.OOE-OI O.OOE-OI I ti t t I
- l. 1 tI Sb124 3.63E+06 6.47Et07 1.04E+07 1.34E+05 I O.OOE-01 2.28Et04 5.74E+06 O.OOE-01
-+(
+---I I I
+ +
I I I I 131 I 2.48Et06 I 3.88Et05 I 4.34E+06 I 4.36E+06 I 7.16E+06 1.44E+09 O.OOE-OI O.OOE-01 'I e +
I I t---
J I 133 I 7.05E-02 I 7.50E-02 I 1.51E-01 I 1.86E-OI I 3.10E-Ol I 3.46E+Ol O.OOE-OI O.OOE-01 1
Csl34 I 1 59E'08 I 4 '7E'06 4.60E+08 7.55E+08 2.34Et08 I O.OOE-01 8.40E+07 O.OOE-01 9.77Et07 4. 14Et06 I
6.91E+08 I I l
Cs137 I I I 6.62Et08 2. 16Et08 0.00E-01 7.76Et07 O.OOE-01 I I i
DaI40 I 6.76Et05 I 5.87Et06' 1. 16E+07 I 1.01Et04 I 3.30Et03 0.00E-OI 6.05E+03 O.OOE-OI t I I Ce141 I 4.93Et02 I 4.14Et06 I 6.66E+03 I 3.32E+03 I 1.46Et03 I O.OOE-OI O.OOE-OI I O.OOE-OI I Ce144 I 5.80Et04 tI 8.88Et07 I 1.09E+06 I 3.41E+05 I 1.89E+05 I O.OOE-OI
- l. O.OOE-OI I O.OOE-OI I (a) R values are in units of mrem/yr per uCi/m3 for tritium, and in units of m2-mrem/yr per uCi/sec for all others.
(b) 4.72E+02 = 4.72 X 102.
TABLE 4-8 R VALUES fOR THE PALO )VERDE NUCLEAR GENERATING STATION<'>
PATIMAY - CD)1 HILK AGE GROUP R ADULT
. NUCLIDE T. BODY GI -TRACT BONE LI VER KIDNEY THYROID LUNG SKIN
t---------gt + t + + -+- ------+
i 1.54Et02 3 'f 1.54Et03 O.OOE-OI i 1.54Et03 i 1.54Et03 i 1.54Et03 H
t- i
--+ i 1.54E+03 i 1.54Et03
+ t +
)
Hn 54 i 7.60Et05 i 1.22E+07 J O.OOE-Ol ( 3.98Et06 i 1.18E+06 i O.OOE-OI ) O.OOE-OI i O.OOE-OI Cr 51 8.26E+03 2.USE+06 i O.OOE-OI O.OOE-OI 1.82E+03 4.94Et03 1.10E+04 ti / / i
+-
( / / O.OOE-OI i
+ +
Fe 59 i 8.71Et06 7.57E+07 9.67E+06 i 2.27E+07 i O.OOE-OI O.OOE-OI 6.35E+06 O.OOE-DI i
(
t(
+- ------+- )
+
J )
+
'T Co 58
/ 3.90Et06 / 3.53Et07 O.OOE-OI / 1.74E+06
/ O.OOE-OI O.OOE-OI O.OOE-OI O.OOE-OI
+ -+ i
+ ---t----------t- J
-t--
J
+
J
)
Co 60 1.85Et07 1.58E+08 O.OOE-.OI i 8.39E+06 i O.OOE-OI O.OOE-OI O.OOE-OI i O.OOE-OI t-i i
+ ----t J ) (
- -----t----------4)
Zn 65 / 9. IIEt08 i 1.27E+09 6.33E+08 i 2.02E+09 i 1.35E+09 i O.OOE-OI O.OOE-OI / O.OOE-OI
+ --+) ---+ +
/
+--
Sr 89 i 1.40E+07 i 7.84E+07 / 4.89Et08 i O.OOE-OI J O.OOE-OI i O.OOE-Ol / O.OOE-DI i O.OOE-OI S) 90 5.95E+09 7.DIE+08 2.43E+10 0.00E-OI i O.DOE-01 i D.OOE-DI i 0.00E-DI i D.OOE-OI t-i ) ) i
+ ---t----------t- ----- --+-- i Zr 95 7.37E 01 3.45E 05 3.39E+02 1.09E+02 i 1.7)Et02 O.OOE-01 i O.OOE-OI O.OOE-OI'I
) ) I i t (
f----------+----------t
)
Sb124 i 3.61E+06 ) 2.59Et08 ) 9. IIE+06 ( 1.72E+05 i O.OOE-OI i 2.21E+04 i 7.09Et06 0.00E.-DI i
)
I 131 J 6.36E+07 i 2.93Et07 J 7 .76Et07 ) 1. IIE+08 i 1.90E+08 j 3.64E+10 J O.OOE-OI i O.OOE-Oli/
I 133 i 5.39Et05 i 1.59Et06 i 1.02E+06 1.77E+06 i 3.08Et06 2.60Et08 0.00E-OI O.OOE-OI
)
+ ------ -------
t t --------t
) ) )
Cs134 5.49Et09 1, IBE+08 i 2.82E+09 6,72Et09 2. 17Et09 i O.OOE-OI 7.21Et08 O.OOE-01 ti )
+
i
+ ti +
i
t -- --+
(
Cs 137 3.43Et09 1.01Et08 3.83E+09 5.23E+09 i 1.78E+09 i O.OOE-OI / 5.91Et08 ti ----- --t ------- -t
) ) i
---e- -------t--------t------ i O.OOE-DI i Ba140 i 4.65Et05 i 1.46Et07 )
7.10E+06 i 8.92E+03 i 3.03Et03 O.OOE-OI i 5.11Et03 O.OOE-OI i
+ + + t
( )
+
CeI41 i 6.68Et02 (
2.25Et07 / 8.71Et03 / 5.89E+03 i 2.74Et03 i O.OOE-DI i O.OOE-OI i O.OOE-OI Ce144 5.41Et04 3.40E+08 1.01Et06 i 4.2IEt05,i.'2 50Et05 i O.OOE-OI i O.OOE-OI / O.OOE-01 i ti
~
) (
t---- -----t----------4 (a) R values are in units of mrem/yr per uCi/m3 for tritium, and in units of m2-mrem/yr per uCi/sec for all others.
(b) 1.54E+03 = 1.54 X 103 .
I j
I I
TABLE 4-9 R VALUES FOR THE PALO VEROE NUCLEAR GENERATING STATION(a)
PAIN'JAY ~ CN HILK AGE GROUP ~ TEEN NUCLIDE T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+--- ggf--- ---- t ---- - --+ t -+
H 3 )
2.00E 09 2.00Et03 O.OOE-01 2.00Et03 )
2.DOE+03 )
2.00Et03 )
2.DOE+03 2.00Et03 t) ) )
+
)
)
lh 54 1.32Et06 I 1.36E+07 I O.OOE-01 6.63Et06 I 1.9&E+06 I O.OOE-01 O.OOE-OI
~ I O.OOE-'01 t
) )
-+- }
Cr 51 1.44Et04 2.42Et06 O.OOE-OI O.OOE-OI I 3.16E+03 8.DIE+03 2.06Et04 O.OOE-OI
} t) )
+----
)
--- e I I ~
--t I
Fe 59 1.52Et07 9.31Et07 1.69E+07 3.94EtD7 O.OOE-OI O.OOE-OI 1.24E+07 O.OOE-OI I t
) ) )
t) )
t
) ) )
}.
+
Co 58 6.75E+06 4.04Et07 ) 0 OOE-Ol 2 93E+06 I O.OOE-DI I O.OOE-01 O.OOE-OI I O.OOE-OI t
) )
-+)
Co 60 3.20E+07 1.85E+0& I O.OOE-01 1.42Et07 I O.OOE-01 I O.OOE-Ol O.OOE-Dl O.OOE-01 I I
+----------t--
) I
} I Z" 65 1 58E 09 ) 1 43E 09 9'E+08 3 3&E D9 2 16E+09 0 OOE Ol O.OOE-OI O.OOE-OI
)
+ +
1 )
t
) )
+
)
t - -- - t'
)
Sr 89 2.5&Et07 1.07E+08 9.DIE+08 O.DOE-DI O.OOE-OI O.OOE-DI O.OOE-OI O.OOE-OI I I ) ) I I I
-t----------
I Sr 90 8.46E+09 9.62E+08 3.43E+10 O.OOE-OI O.OOE-OI O.OOE-DI O.OOE-OI O.OOE-OI
) ) ) )
t
) ) ) )
Zr 95 Sbl24
+
I
)
1.29Et02 6.34Et06
+
)
I 4.32Et05 3.27E+08
+
)
I 5.93E+02 )
1.87E+02 1.62E+07 I 2.99E+05 t
)
I 2.75E+02 O.OOE-Ol
)
)
O.OOE-OI 3.6&Et04
+----
)
}.
O.OOE-OI t--+
)
Q.OOE-01 1.42E+07 I O.OOE-Ol
)
I 131 )
1.06Et08 )
3.90Et07 t) -'-
1.41E+08 )
---+-
1.97E+08
+
)
3.39E+08 5.75E+10 )
O.OOE-OI )
O.OOE-OI .I I 133 9 ~ 60Et05 2.3&Et06 I 86E+06 15Et06 5 52E+06 4 ~ 40E+08 O.OOE-OI O.OOE-OI t
) ) I
-t- 3
) ) ) )
Cs134 5.35E+09 1.43Et08 4.90E+09 1.15E+10 3.66E+09 O.OOE-OI )
1.40E+09 O.OOE-OI
-t-
) )
t) ) ) )
+
) )
Cs137 3.22E 09 1.31Eto& 6.94E 09 9.23Et09 3.14E+09 O.OOE-Ol 1.22Et09 O.OOE-OI
)
-+- ) )
t) )
} } -- e---
)
t Bal40 8.26Et05 1.98E+07 1.28E+07 1.57Et04 5.33Et03 O.OOE-01 1.06Et04 O.OOE-OI t i- --
) )
+-
) ) ) ) )
t) t
..}
+ +
Cel41 I 1.23Et03 I 3.05E+07 )
1.60Et04 1.07Et04 I 5.02Et03 I O.OOE-OI O.OOE-OI O.OOE-OI t )
} }
Ce144 9.96Et04 4.66E+08 1.85E+06 7.67Et05 4.58E+05 O.OOE-DI O.OOE-DI O.OOE-OI I
)
+ -t---
) ) ) )
} }
(a) R values are in units of mrem/yr per uCi/m3 for tritium, and in units of m2-mrem/yr per uCi/sec for all others.
(b) 2.00E+03 = 2.00 X 103 .
I I
I i
I i
I I
I
~
I
~
I
~
e I I I I e I I I
' I ~ ~
~ ~
I I o I
~
I I I I o I '
I 'e I
II I
H I
5 l
(
I
TABLE 4-11 R VALUES FOR THE PALq.VERDE NUCLEAR GENERATING STATION<e>
PATIMAY ~ CON HILK AGE GROUP % INFANT NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
t------ + + --+
H 3 i 4.80E+03 f 4.80Et03 i O.OOE-OI i 4.80E+03 i 4.80Et03 i 4.80E+03 i 4.80E+03 / 4.80Et03
+- -----+- ---+i Hn 54 4. I BEt06 i 6. 78E+06 0. OOE-01 1.85E+07 4.09E+06 O.OOE-OI O.OOE-OI O.OOE-OI
} } } } } } } }
Cr 51 4.66Et04 / 1.36E+06 i O.OOE-OI 0. OOE-01 6. 64E+03 3. 04E+04 5. 92Et04 0. OOE-Ol
} + } } } }
Fe 59 5.03E+07 6.09E+07 7.30E+07 1.28E+08 i O.OOE-OI 3.77E+07 i
t i i O.OOE-OI O.OOE-OI J J t ----t --------+-------
) )
+
Co 58 2.23Et07 i 2.23E+07 O.OOE-OI 8.96Et06 O.OOE-OI i O.OOE-OI i O.OOE-DI i O.OOE-OI
} J )
Co 60 i 1.06E+08 ) 1.07E+08 ) O.OOE-OI i 4.51E+07 i O.OOE-OI i O.OOE-OI i O.OOE-OI i O.OOE-OI Zn 65 4.05Et09 7.42E+09 2.56E+09 i 8.79Et09 4.26E+09 i O.OOE-OI i O.OOE-OI i O.OOE-OI
(
+ -------+-i ) )
-+-----
Sr 89 )
1.22EtDB i 8.71E+07 4.24Et09 0.OOE-OI O.OOE-01 i O.OOE-OI O.OOE-OI i O.OOE-OI
+---
)
} ) J Sr 90 i 1.60E+10 i 7.87E+08 i 6.30E+10 O.OOE-OI O.OOE-OI O.OOE-OI O.OOE-OI O.OOE-OI t ) I
} } }
Zr 95 4.23Et02 i 2.97E+05 i 2.45E+03 5.97E+02 i 6.43Et02 O.OOE-OI i O.OOE-OI O.OOE-OI i,
)
t- +
i )
t- i
+
Sb124 i 2.30Et07 i 2.29Et08 7.41Et07 1.09E+06 i O.OOE-OI i 1.97Et05 i 4.64E+07 i O.OOE-OI i
} }
I 131 i 3.69Et08 i 3.DOE+07 7.13Et08 i 8.40E+08 i 9.81Et08 2.76E+ll i O.OOE-OI O.OOE-OI
---+ J i J I,
+
I 133 4.06Et06 2.35E+06 9.52Et06 1.39E+07 1.63E+07 i 2.52E+09 O.OOE-OI i O.OOE-OI J
+-
) )
} } i Cs 134 3.43Et09 9.23E+07 1.82E+10 3.40E+10 8.74Et09 O.OOE-OI 3.58E+09 O.OOE-OI J J
} } } } } } .}
. Cs137 2.21Et09 i 9.76Et07 i 2.67E+10 3.12E+10 i 8~
38Et09 i O.OOE-OI i 3.39E+09 O.OOE-OI J
t t) I
+
I Bal40 3.28E+06 1.56E+07 6.37Et07 6.37E+04 i 1.51Et04 i O.OOE-OI i 3.91E+04 i O.OOE-OI
-t----------+-
) J t) +
)
+--
Ce141 i 5.60E+03 / 2.46E+07 i 7.80E+04 / 4.76E+04 1.47Et04 O.OOE-OI O.OOE-OI O.OOE-OI i
+ } } }
Cel44 3.67Et05 i 3.76E+08 i 6.54E+06 2.68Et06 i I.OBEt06 i O.OOE-DI D.OOE-OI i O.OOE-OI
} -+- } } t +
(a) R values are in units of mrem/yr per uCi/m3 for tritium, and in units of m2-mrem/yr per uCi/sec for all others.
(b) 4.80E+03 = 4.80 X 103.
I t
I I
I I
~
L I ~
I I
TABLE 4-12 R VALUES FOR THE PALO -VEROE NUCLEAR GENERATING STATION<e>
PATIMAY ~ INHAL AGE GROUP < ADULT NUCLIDE T.BODY Gl-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
t--------ret- t----- + ----+
H 3 i I'26E 0~3 I'26E 03 (
0 OOE 01 I I'26E 03 I'26E 03 (
I 26E 03 i 1'26E 03 i 1'26E 03 i
+ + +
J t + t Hn 54 ) 6.29Et03 i 7.72Et04 / O.OOE-OI i 3.95Et04 i 9.83E+03 i O.OOE-OI ) 1.40E+06 i O.OOE-01 Cr 51 (
9.99E+01 / 3.32Et03 J O.OOE-OI (
O.OOE-01 i 2.28E+01 i 5.94E+01 )
1.44E+04 )
O.OOE-OI J
+
Fe 59 1.05Et04 1.88Et05 i 1.17E+04 i 2.77E+04 i O.OOE-OI O.OOE-OI 1.DIE+06 O.OOE-OI i ti t/ + t +
) (
+ +
)
t Co 58 2.07E+03 1.06E+05 i O.OOE-OI 1.58E+03 O.OOE-OI i O.OOE-OI i 9.27E+05 i O.OOE-OI
+
/ /
t- +
) /
+
Co 60 1.48Et04 i 2.84E+05 )
O.OOE-01 i 1.15E+04 i O.OOE-DI i O.OOE-01 i 5.96E+06 i O.OOE-OI i tJ
+ +
Zn 65 4.65Et04 5.34Et04 i 3.24E+04 i 1.03E+05 i 6.89E+04 i O.OOE-01 8.63E+05 i O.OOE-OI t---------
i i
+------ - +--- ------t------- --t- - -----t )
t-<< ~ti Sr 89 i 8.71E+03 i 3.49Et05 i 3.04E+05 i O.OOE-OI i O.OOE-01 i O.OOE-DI i 1.40E+06 i O.OOE-OI i Sr 90 6.09Et06 7.21Et05 i 9.91E+07 O.OOE-OI i O.OOE-01 i O.OOE-OI i 9.59E+06 i O.OOE-OI i ti +
) )
+
Zr 95 2.32E+04 1.50E+05 1.07E+05 3.44E+04 i 5.4)Et04 O.OOE-OI i 1.77E+06 i O.OOE-OI i
+
/ ) (
--t/ +
i
+
Sbl24 1.24Et04 i 4.06E+05 3.12E+04 i 5 ~ BBE+02 i O.OOE-OI i 7.54E+01 i 2.48E+06 i O.OOE-OI
/ (
t- +
/
I 131 2.05E+04 i 6.27E+03 i 2.52E+04 3.57E+04 6. 12E+04 1. 19E+07 O.OOE-OI O.OOE-OI i
+
/ )
ti / ) )
I 133 4.51Et03 i 8.87Et03 i 8.63E+03 ) 1.48Et04 i 2.58E+04 i 2.15E+06 O.OOE-01 O.OOE-OI
+
)
+------ ---------+- + t )
ti +
Cs134 i 7 27E 05 i 1 04E 04 i 3 72Et05 i 8 47E 05 I 2 ~ 87E 05 i 0.00E 01-) 9 75Et04 O.OOE 01 /
+ ---+-- + -t----------4 J
Cs137 i 4.27E+05 i 8.39Et03 i 4.78Et05 )
6.20E+05 [ 2.22Et05 i O.OOE-OI i 7.51Et04 ) O.OOE-OI i Ba140 2.56Et03 2. IBEt05 i 3.90E+04 i 4.90Et01 i 1.67E+Ol O.OOE-OI i 1.27E+06 i O.OOE-OI /
ti +
i
+
)
+
Cel41 i 1.53E+03 )
1.20Et05 i 1.99Et04 i 1.35Et04 ) 6.25E+03 i O.OOE-OI ) 3.61E+05 O.OOE-DI /
+- J Cel44 i 1.84E+05 i 8.15Et05 i 3.43E+06 i 1.43Et06.I'8.47Et05 i O.OOE-OI i 7.76Et06 i O.OOE-OI
>>--t----------f----------t----------t- ------t----------t----------t (a) R values are in units of mrem/yr per uCi/m3 .
(b) 1.26E+03 = 1.26 X 103 .
a TABLE 4-13 R VALUES FOR THE PALOI-:VERDE NUCLEAR GENERATING STATIONS PAIIMAY ~ IHHAL AGE GROUP = TEER HUCLIDE T.BODY GI-TRACT BORE LIVER KI DHEY THYROID LUHG SKI H
- -------t -------rGEE- + + +- + -+
H 3 1.27ft03 'f 1.27Et03 O.OOE-DI 1.27Et03 1.27Et03 1.27Et03 1.27E+03 1.27E+03 t) t- t ) ) )
t- ) )
l.
) )
+ + +
Ih 54 8.39Et03 6.67Et04 O.OOE-01 5. IOE 4 04 1. 27E+04 0. OOE-01 1. 98E+06 0. OOE-01 i ) )
) ) ) )
-t Cr 51 1.35Et02 3.00Et03 O.OOE-01 O.OOE-01 3.07E+01 7.49E+Ol 2.09f+04 O.OOE-01
+
)
t
)
- -- )
+
) ) ) ) )
Fe 59 1.43Et04 1.78E+05 1.59Et04 3.69Et04 O.OOE-01 O.OOE-OI 1.53ft06 ) O.OOE-01
+
)
t
)
t
)
+
) )
t
)
-- )
- +- - --+--- )
Co 58 2.77EtD3 9.51Et04 O.OOE-OI 2.07Et03 O.OOE-DI 0 OOE-Ol ) 1.34ft06 ) O.OOE-DI
~
) ) )
t) +
) )
Co 60 1.98Et04 2.59Et05 O.OOE-Dl 1.51Et04 O.OOE-Ol O.OOE-01 8.71E+06 O.OOE-OI t ) )
-t
)
t) t) ) ) ) )
In 65 6.23E+04 4.66Et04 3.85Et04 1.33Et05 8.63E+04 O.OOE-01 1.24E+06 O.OOE-Ol t ) )
+
)
+ +
)
+
) ) )
t
)
- -- -+)
Sr 89 ) 1.25Et04 ) 3.71Et05 4.34Et05 O.OOE-01 ) O.OOE-01 )
0.00f-01 ) 2.41E+06 ) O.OOE-01 )
Sr 90 lr 95
)
6.67Et06 3.15E+04
)
+
7.64E+05 1.49E+05
)
)
+
1.08Et08 1.45E+05
- l. O.ODE-Ol [ O.QDE-01 [ O.ODE-01 i 1.666+07 4.58E+04 6.73E+04
+
0.00f-01 )
2.68E+06 i
O.QOE-Ol O.OOE-OI
) )
) )
-+) )
t +
Sb124 1.68E+04 3.98E+05 4 '0E+04 )
7.92E+02 ) O.OOE-OI ) 9.75E+01 ) 3.84E+06 )
O.OOE-OI
)
) +
I 131 2.64Et04 6.48Et03 3.54Et04 4.90E+04 8.39E+04 1.46E+07 O.OOE-OI O.OOE-OI t) )
+
) ) ) )
-- -e---------
) )
I 133 )
6.21Et03 )
~ 1.03E+04 )
1.21Et04 )
2.05Et04 3.59E+04 2.92E+06 O.OOE-OI )
O.OOE-DI Csl34 )
5.48Et05 )
9.75Et03 )
5.02E+05 )
- 1. 13E+06 )
3.75E+05 )
O.OOE-01 )
1.46E+05 )
0.00E-01
+ + + +
Cs137 )
3.11Et05 )
8.47E+03 )
6.69Et05 )
8.47Et05 )
3.04E+05 )
O.OOE-OI )
1.21E+05 )
O.OOE-OI J
Ba140 3.51E+03 2.28E+05 5.46E+04 6.69E+01 2.28E+01 O.OOE-OI 2.03Et06 O.OOE-OI
+
)
+
)
- -- -+
) ) )
t) )
t)
-t Ce141 2.16Et03 1 .26Et05 2.84Et04 1,89Et04 8.87Et03 O.OOE-OI 6.13ft05 O.OOE-01
)
t) )
1
) ) )
J i Ce 144 )
- 2. 62Et05 )
- 8. 63Et05 )
- 4. BBEt06 )
- 2. 02E t06 )
- 1. 21E t06 )
- 0. DOE -01 )
- 1. 33Et07 )
- 0. OOE-01
+
(a) R values are in units of mrem/yr per uCi/m3 .
(b) 1.27E+03 = 1.27 X 103 .
I A
l 1
l l
I
TABLE 4-14 R VALUES FOR THE PALO-'VERDE NUCI.EAR GENERATING STATION<'I PATttMAY ~ IttlNL AGE GROUP = CHILD llUCLIDE T. BODY Gl-TRACT BOtlE LI VER KIDttEY THYROID LUtlG SKIN
- - -+ ----<sP + + +
H ~ I'12Et03 I I 12Et03 I 0 OOE 01 I I'12Et03 I'12E+03 I'12E+03 I'12E+03 I 12E+03
+-(
+
(
+ +
( (
+ t
) (
+
Hn 54 (
9.50E+03 (
2.29E+04 (
O.OOE-OI (
4.29E+04 ( 1.00Et04 (
O.OOE-OI ( 1.57Et06 ( O.OOE-OI (
Cr 51 1.54E+02 (
I.OBEtD3 )
O.OOE-QI (
O.OOE-OI ( 2.43E+Dl ( &.53E+Ol ( 1.70E+04 i O.OQE-OI (
-+)
Fe 59 1.67E+04 7.06Et04 2.07E+04 3.34Et04 O.OOE-OI O.OOE-OI 1.27E+06 O.OOE-OI
+
)
t) t-- -- -- t-
) )
- -- --t-
)
- -----+) - ----- )
+ - -- -+) )
Co 58 ( 3.16E+03 1 3 43E+04 ) 0 ~ OOE 01 ) I 77E 03 ( 0 ~ OOE 01 ( 0 OOE 01 ( I IOE 06 i 0 OOE 01 i Co 60 2.26Et04 9.61E+P4 O.OOE-QI 1.31E+04 O.OOE-OI O.OOE-OI 7.06E+06 O.OOE-OI t(
t(
t
(
t) t +-- - - t-( ) ( ( (
Zn 65 7.02Et04 1.63Et04 4.25Et04 1.13E+05 7.13E+04 (
O.OOE-OI 9.94E+05 (
O.OOE-OI t( )
+
)
+
)
t(
+
)
+ +
(
+
Sr 89 1.72E+04 1.67E+05 5.99Et05 ( O.QOE-OI Q.OQE-OI O.OOE-OI 2.15E+06 ( O.OQE-OI
)
t-
) )
+ t) ) )
Sr 90 6.43Et06 3.43E+05 1.DIE+08 O.OOE-OI O.OQE-OI O.OOE-DI 1.47E+D7 O.OQE-OI t( ) ) ) (
+
)
-t
) ( )
+
Zr 95 3.69E+04 6.10E+04 1.90E+05 4.17E+04 5.95Et04 O.OOE-OI 2.23Et06 )
O.OOE-OI t(
t
( (
+ t) t(
t
( (
t )
Sb124 )
2.DOE+04 (
1.64Et05 ( 5.73E+04 ( 7.39Et02 (
O.OOE-OI (
1.26E+02 (
3.24Et06 (
O.OQE-QI I 131 2.72E+04 2.84Et03 4.&DE+04 4.&OE+04 7.87Et04 1.62E+07 O.OOE-OI O.QOE-OI t(
-+(
)
+ - -- t) (
-+( - - -- +-- ( (
t I 133 7.68E 03 5.47E+03 1.66E+04 2.03E+04 3.37E+04 ) 3.84Et06 ) O.OOE-DI O.OQE-OI
+
)
-+ )
+
)
+
)
- --- -+ )
+ t )
t )
Cs134 2.24E+05 3.84EtD3 6,50Et05 1,01Et06 3.30E+05 0.00E-OI 1.2IE+05 O.OOE-OI
)
+
)
+
) )
-t) - - - -+-)
- t ( )
-t CsI37 1.2&E+05 3.61E+03 9.05Et05 8.24Et05 2.82Et05 O.OOE-OI 1.04E+05 0.00E-OI
-t- )
-t-)
t) ( ( (
+
( (
f Be140 4.32Et03 (
1.02Et05 (
7.39E+04 6.47E+01 (
2.11E+01 (
O.OOE-OI 1.74E+06 O.OOE-QI
+
) (
t( (
Ce141 2.89Et03 5.65Et04 3.92Et04 1.95E+04 &.53Et03 0;OOE-01 ) 5.43Et05 O.QQE-QI i (
t)
- - - t-
)
-- -t) i- - --t- (
- - -- t- f f Cel44 )
3.61E+05 )
3.88E+05 )
6.76E+06 )
2.11Et06 )
1.17Et06 (
Q.OQE-OI )
1.19E+07 )
O.OOE-OI
+- )
(a) R values are in units of mrem/yr per uCi/m3 .
(b) 1.12E+03 = 1.12 X 10>.
I I
1 I
I
TABLE 4-15 R VALUES FOR THE PALO,-.VERDE NUCLEAR GENERATING STATION<'I PA1IMAY
- IttllAL AGE GROUP = IHFAHT HUCLIDE T.BODY GI-TRACT BOHE LIVER KIDHEY THYROID LUNG SKItt
t--------q,t------ t + + +
H 3 6.46ft02 'f 6.46E+02 O.OOE-OI 6.46Et02 6.46ftO) 6.46Et02 i 6.46E+02 i 6.46E+02 i
+
1
+
1
+
1
+
1
--t 1
+
Hn 54 4.98Et03 7.05f+03 O.OOE-OI i 2.53Et04 i 4.98E+03 O.OOE-OI i 9.98E+05 i
+----- --t-- i O.OOE-OI 1 1
+- 1
+- ------+ ---------t----------t Cr 51 8.93E+01 [ 3.56E+02 i O.OOE-OI O.OOE-DI 1.32E+01 5.75Et01 1.28E+04 O.OOE-OI
+
1 t 1
+- / 1 i 1
+ +
Fe 59 9.46E+03 2.47E+04 i 1.35E+04 i 2.35E+04 O.OOE-OI O.OOE-OI 1.DIE+06 O.OOE-OI 1
+- --- -t-1
-- ----+-- 1 t
1
--- t J
t- -----
i
+
Co 58 1 1.82E+03 i 1.11E+04 i O.OOE-DI i 1.22Et03 i O.OOE-DI 1 O.OOE-OI i 7.76E+05 f O.OOE-OI Co 60 1.18E+04 3.19E+04 O.OOE-DI 8.DIE+03 0.00E-OI 0.00E-DI i 4.50E+06 i'0.00E-DI i
t 1
i 1
+
/ 1 i Zn 65 3.10E+04 5.13E+04 1.93Et04 6.25E+04 3.24E+04 O.OOE-OI 6.46E+05 i O.OOE-OI ti t 1
t 1
t 1
--e----------t----------t----------t----------t 1 i 1 Sr 89 i 1. 14E+04 6.39E+04 3.97Et05 O.OOE-OI O.DOE-DI i D.OOE-DI 2.03E+06 i 0.00E-DI 1 1 1
--t----------t-1 1
t----------4 1 Sr 9P i 2.59E+06 i 1.31E+05 4 '8E+07 O.OOE-OI i 0.00E-OI 0 '0E-01 1. 12Et07 O.OOE-OI 1 i
--t- 1 1 J 1 Zr 95 2.03Et04 2 '7Et04 1. 15E+05 i 2.78Et04 i 3. IOE+04 O.OOE-OI i 1.75Et06 0 ~ OOE-01
t--
1
--+---
1 i
+ +
J 1 /
+
Sb124 1.20Et04 5.90Et04 3.79Et04 5 ~ 55E+02 O.OOE-OI i 1.00Et02 2.64E+06 i O.OOE-OI
) ) J 1 1 1 I 131 1.96E+04 1.06E+03 3.79E+04 4.43E+04 5. 17E+04 1.48Et07 O.OOE-DI / O.OOE-DI i 1
-- -----t----------+----------t-
) 1 i 1 i 1 I 133 5.59E+03 2. 15Et03 1.32Et04 1.92E+04 2.24E+04 i 3.55Et06 i O.OOE-DI i O.OOE-OI
) ) ) j 1 Cs134 1 7 44E 04 1 I 33E 03 i 3 96E 05 I 7 02E 05 i I 90E 05 i 0 OOE Ol i 7 '5E 04 i O.OOE 01 i
+
Cs137 4.54E+04 1.33f+03 5.48E+05 6.11E+05 / 1.72Et05 i O.OOE-OI 7.12Et04 O.OOE-DI i 1 i J
f----------f-- i 1 J BaI40 2.89E+03 3.83E+04 i 5.59Et04 5.59Et01 I i 1,34E+01 O.OOE-DI 59E+06 i O.OOE-OI
+------
~
i
-t- ti 1 1 J Ce141 1 1.99Et03 i 2.15E+04 i 2.77Et04 1.66E+04 5.24E+03 O.OOE-DI i 5.16E+05 O.OOE-OI 1 1 1 t 1 1 Ce144 i 1.76E+05 j 1.48E+05 3.19Et06 1.2Ift06,)-'5.37ft05 O.OOE-OI i 9.83E+06 i 0 ~ OOE-Ol J
t 1 i 1 (a) R values are in units of mrem/yr per uCi/m3.
(b) 6.46E+02 = 6.46 X 10z
I I
'I I
TABLE 4-16 (Sheet 1 of 3)
PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERN RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 1 RESIDENCE(c) GARDEN(c) MILK(c)
DIRECTION X/Q D/Q X/Q D/Q x /Q D/Q (Sec/m~ ) (m a) (Sec/m~) (m ~) (Sec/m~ ) (m- ~ )
N 2.92E-06<b 3.25E-09 2.92E-06 3.25E-09 7 03E 07(a 3 48E 10< a)
NNE 1.81E-06 2.88E-09 4.70E-07(a 4.04E-10<>> 4 70E 07(a 4 04F 10(a NE 1.95E-06 3.85E-09 1.76E-06 =
3.29E-09 5 77E 07(a 6.5IE-IO<<)
ENE 1.03E-06 1.08E-09 1.03E-06 1.08E-09 3.86E-07<') 2 86E 10(a E 9.39E-07 6.68E-10 3 71E 07(a 1 87E 10(a 3.71E-07<') 1 87E 10(a ESE 6.37E-07 2.84E-10 4.12E-07 1.60E-10 4.12E-07 1. 60E-10 SE 8.83E-07 2.61E-10 8.83E-07 2.61E-10 5 84E 07(a 1. 52E-10< ')
SSE 1.27E-06 2.61E-10 I 09E 06(a 2.15E-IO<>> 1.09E-06<>> 2 15E 10(a S 2.58E-06 4.85E-10 2.09E-06" 3.59E-10 2. 13E-06 3.71E-10 SSW 3.26E-06 8. 26E-10 2.28E-06<') 4 53E 10(a 2.28E-06(') 4 53E 10(a SW 2.80E-06 9. 10E-10 1.58E-06(a) 3. 56E-10(a) 1'.58E-06(a) 3.56E-10(a)
WSW 1.95E-06 1.09E-09 8.55E-07(a) 3. 18E-10(a) 8.55E-07 a) 3.18E-10(a W 7 54E 07(s 4.44E IO(a) 7.54E-07<') 4. 44E-10< ') 7.54E-07<') 4 44E 10(a WNW 6 03E 07< s 3 25E IO(a 6 03E 07(a 3 25E 10(a 6.03E-07(8) 3 25E 10(a NW 8.24E-07 5.25E-10 7.55E-07 4.61E-10 6 02E 07(a 3 27E 10(a)
NNW 1.46E-06 1.47E-09 5 20E 07(a 3 04E 10(a 5 20E 07(a) 3 04E 10(a 5-mile value used since there is no pathway located within the sector up to five miles.
2.92E-06 = 2.92 x 10 6 Locations of these residences, gardens and milk animals are given in Table A-l, sheet 1.
Controlling locations are discussed in Appendix A.
References:
1984 Land Use Census (letter ANPt3-21221-JRti/LEB).
NUS Corporation letters NUS-ANPP-1385 and NUS-ANPP-1386.
I I
I I
I I
I I
I
TABLE 4-16 (Sheet 2 of 3)
PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAHETERS FOR LONG TERN RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON. UNIT 2 RESIDENCE(c) GARDEN(c) HILK(c)
DIRECTION X/Q D/Q X/Q D/Q X/Q D/Q (Sec/m~) (m a) (Sec/m>) (m a) (Sec/oP ) (m- ~ )
N 2.73E-06<bi 2.92E-09 2.39E-06 2.35E-09 7 03f 07< a 3 48E 10<a NNf 2.20E-06 3.87E-09 2.20E-06 3.87E-09 4.70E-07<a 4.04E-10<>>
NE 1.85E-06 3.55E-09 1.57E-06 2.78E-09 77E 07<a 6. 51E-10<>>
ENE 1.03E-06 1.08E-09 1.03E-06 1.08E-09 3 86E 07<a 2.86E-10<>>
E 8.80E-07 6 ~ 06E-10 3.71E-07<>> 1 87E 10<a 3 71E 07<a 1.87f-lo<>>
ESE 6.25E-07 2.76E-10 3.96E-07 1.51E-10 3.96E-07 1.51E-10 SE 9.06E-07 2.72E-10 . 9.06E-07 2.72E-10 5 84E 07<a 1 52E 10<a SSE 1.34E-06 2.81E-10 1.09E-06<>> 2.15E-10<>> 1 09E 06<a 2 15E 10<e S 2.63E-06 5.01E-10 2.19E-06' 3.88E-10 2.19E-06 3.88E-10 SSW 3.48E-06 9.19E-10 28E 06< a 4.53E-10<>> 2.28f-06<>> 4.53E-10<>>
SW 2.93E-06 9.75E-10 1.58E-06(a) 3.56f-10(a) 1.58E-06(a) 3. 56E-10(a)
WSW 2.01E-06 1.16E-09 8.55E-07(a) 3.18E-10(a) 8.55E-07(a) 3.18E-10(a)
W 7.54E-07< >> 4.44E-10< >> 7.54E-07<>> 4 44E 10<a 7.54E-07<>> 4 44E 10<a
'NW 6.03E-07< >> 3.25f-10< >> 6 03E 07<a 3.25E-10<>> 6.03E-07<>> 3.25E-10<>>
NW 7.84E-07 4.88E-10 7.84E-07 4.88E-10 6.02E-07<>> 3 27E 10<a NNW 1.46E-06 1.47E-09 5.20E-07 3.04E-10 5 20E 07<>> 3 04E 10< a 5-mile value used since there is no pathway located within the sector up to five miles.
2.73E-06 = 2.73 x 10-s Locations of these residences, gardens and milk animals are given in Table A-l, sheet 2.
Controlling locations are discussed in Appendix A.
References:
1984 Land Use Census (letter ANPH-21221-JRH/LEB).
NUS Corporation letters NUS-ANPP-1385 and NUS-ANPP-1386.
l I
TABLE 4-16 (Sheet 3 of 3)
PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAHETERS FOR LONG TERN RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 3 RES IDENCE(c) GARDEN(c) HILK(c)
DIRECTION .
X/Q D/Q X/Q D/Q x/Q D/Q (Sec/m~ ) (m- ~ ) (Sec/m>) . (m-a) (Sec/m~) (m ~),
2.58E-06<~> 2.47E-09 2.42E-06 2.22E-09 7 03E 07<a 3 48E 10<a NNE 1.85E-06 2.97E-09 1.85E-06 2.97E-09 4.70E-07<a 4 04E 10< a NE 1.66E-06 3.00E-09 1.48E-06 2.54E-09 5 77E 07<>> 6. 51E-10<>>
ENE 8.75E-07 8.86E-10 8.75E-07 8.86E-10 3 86E 07< a 2. 86E-10<>>
E 8.90E-07 6.17E-10 4.06E-07 2.15E-10 4.25E-07 2.31E-10 ESE 6.37E-07 2.84E-10 5.80E-07 2.46E-10 3.73E-07<>> I 37E 10<a SE 5 84E 07< a 1.52E-10<>> 5 84E 07< a 1 52E 10<a 5 84E 07<a 1 52E 10<a SSE 1.36E-06 2.88E-10 1 09E 06<a 2 15E 10<a 1.09E-06<>> 2 15E 10< a S 2.65E-06 5.25E-10 4.06E-10 2.31E-06 4.21E-10 2.25E-06'.28E-06<>>
SSW 3.64E-06 9.82E-10 4 53E 10<a 2. 28E-06<>> 4 53E 10< a SW 3.19E-06 1.11E-09 1.58E-06(a) 3.56E-10(a) 1.58E-06(a) 3.56E-10(a)
WSW 2. 12E-06 1.26E-09 8.55E-07(a) 3.18E-10(a) 8.55E-07(a) 3.18E-10(a)
W 7 54E 07<a 4.44E-10<>> 7 54E 07<>> 4 44E 10<a 7.54E-10<>> 4.44E 10<>>
WNW 6 03E 07< a 3.25E-10< >> 6.03E-07<>> 3 25E 10<a 6.03E-07<>> 3 25E 10<a NW 6.83E-07 4.05E-10 6.82E-07 4.05E-10 6 02E 07<a 3 27E 10<a NNW 1.34E-06 1.26E-09 5.16E-07 3.01E-10 5.20E-07<>> 3 04E 10<a 5-mile value used since there is no pathway located within the sector up to five miles.
2.58E-06 = 2.58 x.lO-s Locations of these residences, gardens and milk animals are given in Table A-l, sheet.,3.
Controlling locations are discussed in Appendix A.
References:
1984 Land Use Census (letter ANPH-21221-JRH/LEB).
NUS Corporation letters NUS-ANPP-1385 and NUS-ANPP-1386.
5.0 TOTAL'OSE AND DOSE TO PUBLIC ONSITE 5.1 Technical S ecification 3. 11.4 - The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.
Since all other uranium fuel cycle sources are greater than 20 miles away, only the PVNGS site need be considered.
The total dose to any HEHBER OF THE PUBLIC will be determined based on a sum of the doses from all three units'eleases and doses from direct radiation from PVNGS.
This dose evaluation is done annually and submitted with the Semiannual Radioactive Effluent Release Report for July through December to assure compliance with 40CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation. This dose evaluation will also be performed whenever calculated doses associated with effluent releases exceed twice the limits of any one of the Technical Specifications 3.11.2.2 or 3.11.2.3.
5.1.1 Doses from Releases The annual whole body dose accumulated by a MEMBER OF THE PUBLIC for the noble gases released in gaseous effluents is determined by using the following equation:
Dl4 B (3 17
~ " 10 ) El HKl ) ( /0)gU (0; )1 5-1 Rev. 2
l Where:
K) the whole body dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrem/yr per uCi/m~ from Table 3-1.
the integrated release of radionuclide i, in uCi for the previous calendar year.
(VQ)Ru the highest calculated annual average dispersion parameter, in sec/oP, for a particular unit, at the controlling location, from Table 4-16, or concurrent meteorological data if available.
2.92xIO-~ from Unit 1 2.19x10-~ from Unit 2 2.31xl0-~ from Unit 3 DwB the annual whole body dose in mrem to a MEMBER OF THE PUBLIC at the controlling location due to noble gases released in gaseous effluents.
The annual dose to any organ accumulated by a MEMBER OF THE PUBLIC for iodine-131, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days released in gaseous effluents is determined by using the following equation:
o0 (3.17 x 10-8) z, [ ~(R;kWk )(9;)) (4-3)
Where:
o0 the total annual organ dose from gaseous effluents to a MEMBER OF THE PUBLIC, in mrem, at the controlling location.
5-2 Rev. 2
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the integrated release of radionuclide i, in uCi, for the previous calendar year.
the dose factor for each identified radionuclide i, for pathway k (for the inhalation pathway in mrem/yr per uCi/m~ and for the food and ground plane pathways in m~ -mrem/yr per uCi/sec) at the controlling location. The R;'s for each age group are given in Tables 4-1 through 4-15.
the highest annual average dispersion or deposition parameter for the particular unit, used for estimating the total annual organ dose to a MEMBER OF THE PUBLIC at the controlling location for the particular unit.
(X/9)<<, in sec/oP for the inhalation pathway .and for all tritium calculations, for organ dose at the controlling location, from Table 4-16 or concurrent meteorological data if available.
= 2.92xlO-~ from Unit 1
= 2.19xlO-~ from Unit 2
= 2.3lx10-~ from Unit 3 (D/g) <<, in m- ~, for the food and ground plane pathways, for organ dose at the controlling location, from Table 4-16 or concurrent meteorological data if available.
- 3.25xlO-~ from Unit 1 3.88xlO.~o from Unit 2
= 4.2lxIO-~o from Unit 3 5-3 Rev. 2
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5.1.2 Dose Due to Direct Radiation The component of dose to a MEMBER OF THE PUBLIC due to direct radiation will be evaluated by first determining the direct radiation dose at the site boundary in each sector, and then extrapolating the site boundary dose to the controlling location by the inverse square law of distance; 5.2 Dose to Public Onsite Technical S ecification 6.9. 1.8 - For the purpose of evaluating the dose to MEMBERS OF THE PUBLIC due to their activities'within the SITE BOUNDARY the following methodology will be used. These activities have been determined to be limited to the vicinity of the Visitor Center located inside the SITE BOUNDARY west of Unit l. An assumption was made that no MEMBER OF THE PUBLIC would spend more than eight hours per year at this location.
A X /0, determined for the Visitor Center, will be used for this assessment.
Equations 5-1 and 4-3 i'n Sections 5.1.1 and 5.1.2 s'hould be used for this assessment. g< should be the integrated release of radionuclide i, in uCi, for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (determined from the yearly 9,).
5-4 Rev. 2
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6.0 RADIOLOGICAL ENVIRONMENTAL PROGRAM 6.1 Radiolo ical Environmental Monitorina Pro ram Technical S ecification 3. 12. 1 - The radiological environmental monitoring program shall be conducted as specified in Table 3. 12-1 [of the Technical Specifications] .
Samples shall be collected as specified in Table 3.12-1 [of the Technical Specifications] and from the specific locations given in Table 6-1 and Figures 6-1 and 6-2 of the ODCM, and shall be analyzed pursuant to the requirements of Table 3 .12-1
[of the Technical Specifications], and the detection capabilities required by Table 4. 12-1 [of the Technical Specifications] .
The results of the radiological environmental monitoring program are intended to supplement the results of the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected based on the effluent measurements and modeling of the environmental exposure pathways. Thus, the specified environmental monitoring program provides measurements of radi ation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures to individuals resulting from station operation.
If the analysis .of an environmental sampling medium at a specified location exceeds the reporting level of Table 3.12-2
[of the technical specifications] when averaged over any calendar quarter, an investigation shall be conducted. If the radioactivity is determined to be the result of plant effluents a Special Report is submitted to the NRC, within 30 days, which identifies the cause(s) for exceeding the limit(s) and corrective actions to be taken. If the radioactivity is determined not to be the result of plant effluents, the condition is reported and described in the Annual Radiological Environmental Operating Report.
6-1 Rev. 2
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The initial radiological environmental monitoring program will be conducted. for the first three years of commercial operation of Unit 1. With the radiological environmental monitoring program not being conducted as specified in Table 3.12-1, [of the Technical Specifications] prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
6.2 Land Use Census Technical S ecification 3.12.2 - A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden* of greater than 50 m~ (500 ft') producing broad leaf vegetation.
A land use census is conducted in accordance with Technical Specification 3. 12.2. When a land use census identifies a.
location(s) which yields a calculated dose or dose commitment greater than the values calculated in Technical Specification 4.11.2.3, identify the new location(s) in the next Semiannual Radioactive Effluent Release Report.
- Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of.
the garden census. Specifications for broad leaf vegetation sampling in Table 3. 12-1 shall be followed, including analysis of control samples.
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When a land use census 'identifies a location(s) which yields a
.calculated dose or dose commitment (via the same exposure pathway) 20~ greater than at a location from which samples are currently bei'ng obtained, the new location(s) is added to the Radiological Environmental Monitoring Program within 30 days.
An equivalent sampling location(s), excluding the control location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from the Radiological Environmental Monitoring Program after October 31 of the year in which this land use census was conducted.
New sampling location(s) are identified in the next Semiannual Radioactive Effluent Report along with revised ODCM figure(s) and table(s) which reflect the new location(s).
A land use census is conducted during the growing season at least once per 12 months by a door-to-door or aerial survey, by consulting local agricultural authorities, or by any combination of these methods. The results of the land use census are reported in the Annual Radiological Environmental Operating Report.
6-3 Rev. 2
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6.3 Interlaborator Com arison Pro ram Technical S ecification 3 . 12.3 - Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission that correspond to samples required by [Technical Specification] Table 3.12-1.
PVNGS laboratories or contract laboratories which perform analyses for the Radiological Environmental Monitoring Program (REMP) participate in the Environmental Protection Agency's (EPA's)
Environmental Radioactivity Laboratory Intercomparisons Studies (crosscheck) Program. The participation includes all of the determinations (sample medium-radionuclide combinations) that are offered by the EPA and that are also included in the monitoring program.
The sample handling, preparation and analysis procedures approved for use on routine REMP samples, at the time the crosscheck samples are received from the EPA, are used to implement the program. The results of the crosscheck sample analyses are reviewed, at minimum on an annual basis, to ensure that the control limits established by the EPA are not exceeded.
If deviation from these specified limits is identified an investigation is made to determine the reason for the deviation and corrective actions are taken as necessary. The results of all analyses made under this program are included in the Annual Radiological Environmental Operating Report.
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TABLE 6-1 (Sheet 1 of 4)
RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS SAMPLE SAMPLE LOCATION SITE TYPE NOTATION(4) DESIGNATION<'> LOCATION DESCRIPTION TLD E30 APS Goodyear Office Air E30 Air East of RR Tracks TLD ENE24 Scott-Libby School, Perryville Rd. & Thomas Rd.
TLD E21 Liberty School, 19800 W. Hwy. 85 TLD E16 APS Buckeye Office, 615 N. 4th St, Buckeye Air E16 Same as TLD TLD ESE11 Palo Verde Rd. (291st Ave.) & Old Hwy. 80 TLD SP SSE31 APS Gila Bend Substation, Service Rd. West Of Town, Off I-8 6 Air <b~ Control SSE31 Same as TLD 7 TLD,<b~ SP SE7 Old U.S. 85 and Arlington School Road 7A Air SE8 Arlington School, 16351 S. Arlington School Rd.
8 TLD<b~ OR SSE5 Corner of 363rd Ave. & Southern Pacific Pipeline Rd.
9 TLD OR S5 Corner of 371st Ave. & Southern Pacific Pipeline Rd.
10 TLD~b> OR SE5 Corner of 355th Ave. & Elliot Rd.
11 TLD OR ESE5 Corner of 339th Ave. & Dobbins Rd.
12 TLD~b~ OR E5 Corner of 339th Ave. & Buckeye-Salome Rd.
13 TLD<bi IR Nl N Site Boundary 14 TLD~bi IR NNE2 NNE Site Boundary 14A Air NNE2 Buckeye-Salome Rd. & 371st Ave.
15 TLD~b~ IR NE2 NE Site Boundary 15 Air ~bi NE2 Same as TLD 16 TLD<b~ IR ENE2 ENE Site Boundary 17 TLD~b IR E2 E Site Boundary
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T E 6-1 (Sheet 2 of 4)
SAMPLE SAMPLE LOCATION SITE TYPE NOTATION<4i DESIGNATION ~'> LOCATION DESCRIPTION'7A Air E4 351st Ave., 1 mi. S of Buckeye Salome Rd.
18 TLO<b IR ESE2 ESE Site Boundary 19 TLD~b IR SE2 SE Site Boundary 20 TLD<b IR SSE2 SSE Site Boundary 21 TLD~bi IR S3 S Site Boundary 21 Air <bi S3 Same as TLD 22 TLD<bi IR SSH3 SSW Site Boundary 23 TLD<b OR H5 2 miles N. of Elliot Rd., 3 miles W. of Wintersburg Rd.
24 TLO<b OR SW4 Elliot Rd. at Desert Farms 25 TLD~bi OR HSH5 Elliot Rd. at Cattle Guard cn 26 TLD<bi OR SSH5 Shepard Farm, 13202 S. 383rd Ave.
27 TLD IR SW2 SH Site Boundary 28 TLD~b> IR WSH1 WSH Site Boundary 29 TLD~bi. IR W1 W Site Boundary 29 Air Hl Same as TLD 30 TLD~b IR WNW1 WNW Site Boundary 31 TLD<bi IR NW2 NW Site Boundary 32 TLD<b IR NNH1 NNH Site Boundary 33 TLO OR NH4 Buckeye Rd., I/2 mile Hest of 395th Ave.
34 TLD<bi OR NNH5 Corner of 395th & Van Buren Rd.
35 TLD<bi SP NNH9 Tonopah, Palo Verde Inn Fire Station, 40901 W. Osborn Rd.
35 Air NNH9 Same I
as TLD 36 TLD OR N5 Corner of Hintersburg Rd. & Van Buren Rd.
37 TLD~b> OR NNE5 Corner of 363rd Ave. & Van Buren Rd.
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TABLE 6-1 (Sheet 3 of 4)
SAMPLE SAMPLE LOCATION SITE TYPE NOTATION<~> DESIGNATION ~>> LOCATION DESCRIPTION 38 TLD< OR NE5 Corner of 355th Ave. 5 Buckeye Rd.
39 TLD<>> OR ENE5 343rd Ave.,:.1/2 mi. South of Lower Buckeye Rd.
40 SP N3 Wintersburg, End of Transmission Rd.
TLD'ir<>>
40 N3 Same as TLD 41 TLD~ >> SP HNH20 Harquahala Valley School, Van Buren St., 1 mi H. of Steve Martori Dr.
42 TLD~>> SP Ruth Fisher School, Indian School Rd. 8 Wintersburg Rd.
43 TLD~>> SP N45 Vulture Peak Sch., Wickenburg, 1 mi S. of US 60 44 TLD<>> ENE35 APS El Mirage Office, 12313 W. Grand Ave.
44 Air ~>> Control ENE35 Same as TLD 45 TLD~ >> Control E20 REMP Lab. (Lead PIG), 615 N. 4th St, Buckeye 46 Hater<>> WD NNW9 McArthur's Farm, 41701 W. Indian School Rd.
46 TLD ENE30 Litchfield Park Sch, 13825 W. Indian School Rd.
47 Vegetation<>> ENE3 Adams Residence, Buckeye-Salome Rd.
47 TLD E35 Littleton School, 115th Ave. 5 Hwy 85 48 Hater< >>
Milk~>> WD SSH5 Shepard Farms, 13202 S. 383rd Ave.
48 TLD E24 Perryville, Jackrabbit Trail, S. of Circle K 49 Hater~ >> WD ESE4 Glover Residence, 9199 S. 351st Ave.
49 TLD ENE11 Hopeville, Palo Verde Rd, 1/2 mi S. of I-10 50 E28 Lueck Dairy, Jackrabbit Trail 5 Elliot Rd.
50 TLD WNH5 Olinski Road, 2 mi. S. of Buckeye-Salome Rd.
51 Milk> E15 Schroeder Farm, Miller Rd. 8 Broadway Rd.
53 Milk~b >
E26 Kerr Dairy, Dean Rd. 8 Buckeye Rd.
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LE 6-1 (Sheet 4 of 4)
SAMPLE SAMPLE LOCATION SITE TYPE NOTAT ION << ~
DES IGNATION << 'OCATION DESCRIPTION 54 Milk E27 Smart Dairy, Airport Rd. 8 Dobbins Rd.
55 Water SW3 GaVette Residence, 39326 W. Elliot Rd.
56 Milk<~~ Control E75 Hamstra Dairy 82, Mcgueen Rd. 8 Ryan Rd.
57 Hater< >> WG Onsite Well 27ddc 58 Water<>> WG Onsite Well 34abb 59 Surface Hater<>> WS Onsite PVNGS Evaporation Pond 81 60 Surface Water<>> WS Onsite PVNGS Reservoir 6l Citrus Control E80 Cooley Farms, Inc. (Higley, Arizona),
643 S. Sierra 62 Vegetation<>> Control ENE75 J.A. Hood Co,, N. Alma School Rd.
63 Surface Water<>> WS Onsite PVNGS Evaporation Pond f2 (a) Location Designation based on Sector and Zone Nomenclature from Table J-l, NUREG-0654. Distances are from the centerline of Unit 2 containment.
(b) These samples fulfill the requirements of the PVNGS Technical Specifications.
(c) Refer to Figures 6-1 and 6-2 for relative locations of Sample sites.
(d) IR - Inner Ring OR - Outer Ring SP - School or Population Center HS - Waterborne Surface WG - Waterborne Ground WD - Waterborne Drinking
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~Ifonitoring Program Samole Sites 0 to 5 miles Figure 6-1 6-9 Rev. 2
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APPENDIX A DETERMINATION OF CONTROLLING LOCATION The controlling location is the location of the MEMBER OF THE PUBLIC who receives the highest doses.
The determination of a controlling location for implementation of 10CFR50 for radioiodines and particulates is known to be a function of:
(I) Isotopic release rates (2) Meteorology (3) Exposure pathway (4) Receptor's age The incorporation of these parameters into Equation 4-3 results in the respective equations at the controlling location. The isotopic release rates are based upon the source terms calculated using the PVNGS Environmental Report, Operating License Stage, fable 3.5-12, without carbon.
All of the locations and exposure pathways, identified in the 1984 Land Use Census, have been evaluated. These include cow milk ingestion, goat milk ingestion, vegetable ingestion, inhalation, and ground plane exposure. An infant is assumed to be pr esent at all milk pathway locations . A child is assumed to be present at all vegetable garden locations. The ground plane exposure pathway is only .considered to be present where an infant is not present. Naturally, inhalation is present everywhere an individual is present.
For the determination of the controlling locations, the highest ~/g and 0/g values', based on the 9 year meteorological data base, for the vegetable garden, cow milk, and goat milk pathways, are selected for each unit. The receptor organ doses have been calculated at each of these locations. Based upon these calculations, it is determined that the controlling receptor pathway is a function of unit location. For Unit I, the controlling receptor is a garden-child pathway; for releases from Unit 2 and Unit 3 the controlling receptor is a cow milk-infant pathway. These determinations are based upon Table 4-16 which, in turn, is based upon the 1984 Land Use Census. Locations of the nearest residences, gardens and milk animals, as determined in the 1984 Land Use Census, are given in Table A-l.
A-I Rev. 2
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TABLE A-1 (Sheet 1 of 3)
EXPOSURE PATHWAY LOCATIONS NEAREST TO PVNGS UNIT 1 Nearest Nearest Location Nearest L'ocation Milk Location Residence Designator Garden Designator .. Animal Designator Animal Sector Distance (b) Distance (b) Distance (b) Type Desi nator a Miles a Miles a Miles a N 1.4 3 1.4 (c)
NNE 1.8 20 (c) (c)
NE 1.9 4 2.1 (c)
ENE 2.7 6 2.7 (c)
E 2.8 9 (c) (c)
ESE 3.7 8 4.6 9 4.6 Goat SE 4.1 10 4.1 10 (c)
SSE 4.7 11 (c) (c)
S 4.6 19 5.2 12 5.1 12 Cow SSW 3.5 13 c) (c)
SW 2.9 14 c) (c)
WSW 2.6 '15 (c) (c)
W (c) (c) (c)
WNW (c) (c) (c)
NW 3.8 21 4.1 16 (c)
NNW 2.0 17 (c) (c)
(a) Sector designators and distances derive from the 1984 Land Use Census (letter ANPH-21221-JRH/LEB), and are specific to the subject PVNGS unit.
(b) Location designators, and animal types at locations indicated, are from the 1984 Land Use Census (letter ANPH-21221- JRM/LEB) .
(c) Postulated to be at 5 mile distance since the 1984 Land Use Census identified no pathway (residence, garden or milk animal as appropriate) within the sector and within 5 miles.
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TABLE A-1 (Sheet 2 of 3)
EXPOSURE PATHWAY LOCATIONS NEAREST TO PVNGS UNIT 2 Nearest Nearest Location Nearest Location Hilk Location Residence Designator Garden Designator . Animal Designator Animal Sector Distance (b) Distance (b) Distance (b) Type Desi nator a Hiles a Hiles a Hiles a N 1.5 1 1.7 (c)
NNE 1.5 3 1.5 (c).
NE 2.0 2.3 (c)
ENE 2.7 6 2.7 (c)
E 3.0 7 (c) (c)
ESE 3.7 8 4.7 9 4.7 Goat SE 4.0 10 4.0 10 (c)
SSE 4.5 11 (c) (c)
S 4.5 19 5.0 12 5.0 12 Cow SSW 3.2 13 (c) (c)
SW 2.7 14 (c (c)
WSW 2.5 15 (c) (c)
W (c) (c) c)
WNW (c) (c) (c)
NW 4.0 16 4.0 16 (c)
NNW 2.0 17 5.0 18 (c)
(a) Sector designators and distances derive from the 1984 Land Use Census (letter ANPH-21221-JRH/LEB), and are specific to the subject PVNGS unit.
(b) Location designators, and animal types at locations indicated, are from the 1984 Land Use Census (letter ANPH-21221- JRH/LEB) .
(c) Postulated to be at 5 mile distance since the 1984 Land Use Census identified no pathway (residence, garden or milk animal as appropriate) within the sector and within 5 miles.
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TABLE A-1 (Sheet 3 of 3)
EXPOSURE PATHWAY LOCATIONS NEAREST TO PVNGS UNIT 3 Nearest Nearest Location Nearest Location Hilk Location Residence Designator Garden Designator Animal Designator Animal Sector Distance (b) Distanc'e (b) Distance (b) Type Desi nator a Hiles a Hiles a Hiles a N 1.8 1.9 2 (c)
NNE 1.7 1.7 3 (c)
NE 2.2 2.4 5 (c)
ENE 2.9 2.9 6 (c) .
E 3.0 4.6 9 4.5 Goat ESE 3.7 4.0 10 (c)
SE (c) (c) (c)
SSE 4.4 11 (c) (c)
S 4.2 19 4.9 12 4.8 12 Cow SSW 3.1 13 (c) (c)
SW 2.5 14 (c) (c)
WSW 2.4 15 (c) (c)
W (c) (c) c)
WNW (c) (c) (c)
NW 4.3 16 4.3 16 (c)
NNW 2.2 17 5.0 18 (c)
(a) Sector designators and distances derive from the 1984 Land Use Census (letter ANPH-21221-JRH/LEB), and are specific to the subject PANGS unit.
(b) Location designators, and animal types at locations indicated, are from the 1984 Land Use Census (letter ANPH-21221- JRH/LEB) .
(c) Postulated to be at 5 mile distance since the 1984 Land Use Census identified no pathway (residence, garden or milk animal as appropriate) within the sector and within 5 miles.
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PVNGS Semi-Annual Operating Report for July - December 1988 APPENDIX F CHANGES TO OFFSITE DOSE CALCULATIONhQMUAL(ODCM)
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NUCL~<R ADMINISTRATIVEAND TECHNICAL MANUAL
'g'~lIEW Revision AND CONTROL OF THE 75AC-9RP18 0 OFFSITE DOSE CALCULATION MANUAL Appendix A Page 1 of 1 R" 1ISION REQUEST ."ORM
- ~a ORIGINATOR: F'AVL L EZT: /086 Descr'pt'on and Just'="'cat'on of Revision:
Licensee initiated changes to the ODCM must be made in accordance with PVNGS Technical Specification 6.14.2. This report contains sufficiently detailed information to support the rationale for the changes to the ODCM and hereby determines that the changes will not reduce the accuracy or reliability of dose calculations or set point determinations.
The major technical changes made in the revision are:
- 1. Use of a new ODCM review and approval process.
- 2. Additional potential nuisance release pathways.
- 3. Revised calibration curve for the Waste Gas Decay Tank. Monitor.
- 4. Revised setpoint calculation for the Waste Gas Decay Tank Monitor.
5 ~ Deletion of Section 6.0, "Operability of Equipment."
- 6. With reference to the Land Use Census, replacement of the concept of increase in D/Q with increase in dose.
A detailed discussion of the changes appears in this report. The evaluations are organized by Section of the ODCM (i.e., change 1.1 is the first change in ODCM Section 1, change 5'.7 is the seventh change in ODCM Section 5, etcee zero is used to designate changes which occur in the document prior to Section 1).
Pa e 1 of 20 Aoproved By: Date:D Ch mis try S tandards Supe visor Use addit'onal pages as reaui ed.
~Cover Pa ac Change 0.1:
Revision 1 has signatures of (a) department head, (b) the Plant Review Board Chairman and (c) the Plant Manager.
Revision 2 will bear signatures of (a) originator, (b) technical reviewer and (c) the Manager, Radiation Protection and Chemistry, (d) PRG Chairman.
Explanation 0.1:
The review and control of revisions to the ODCM are now subject to the requirements of an Administrative Control procedure in the PVNGS Station Manual, in order to provide a formal and documented means of complying with PVNGS'echnical Specification 6.5.2v9 in lieu of the previous review process.
TABLE OF CONTENTS:
Section 1.1 "Liquid Effluents" was changed to "Liquid Effluent Pathways" Section 1.2 "Gaseous Effluents" was changed to "Gaseous Effluent Pathways" Explanation 0.2:
Editorial Change 0.3:
Section 6.0, "Operability of Equipment", was deleted, and Section 7.0, "Radiological Environmental Program", its page numbers, table numbers and figure numbers were redesignated for new section 6.0, "Radiological Environmental Program."
Explanation 0.3:
Section 6.0 of Rev. 1 of the ODCM consisted simply of flow diagrams of the radioactive waste systems. These are deleted as not required and of no apparent value in the ODCM.
Section 7.0 of Rev. 1 is renumbered to Section 6.0 of Rev. 2, to conform.'
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Change 0.4:
Figure 2-2 (Rev. 1) has title: "Initial Calibration Curve for PVNGS Monitor RU-12. Response to Kr-85 Gas."
Explanation 0.4:
Figure 2-2 and its title have been revised to reflect the same units on the X and Y axis as Figure 2-1.
Change 0.5:
Tables 6-2 and 6-3 were deleted.
Explanation 0.5:
These tables are copies of tables in the Technical Specification, Section 6 was revised to reference the Technical Specification Tables.
INTRODUCTIONt Change 1.1:
Rev. 1 heading for Section 1.1 reads: "Liquid,Effluents".
Rev. 2 heading for Section 1.1 reads: '"Liquid Effluent Pathways".
Explanation 1.1: .
Editorial change only.
Change 1.2:
Rev. 1 heading for Section 1' reads; "Gaseous Effluents".
Rev. 2 heading for Section 1.2 reads: "Gaseous Effluent Pathways".
Explanation 1.2:
Editorial change only.
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Change 1.3:
Rev. 1 states:
"1.3 Nuisance Pathwa s This section addresses the potential release pathways which should not contribute more than 10Z of the doses evaluated in this manual.
Table 1-1 identifies these potential release pathways which would occur primarily due to operation with primary to secondary leakage.---".
Rev. 2 states:
"1.3 Nuisance Pathwa s This section addresses the potential release pathways which should not contribute more than 10X of the doses evaluated'in this manual.
Table 1-1 lists examples of potential release pathways.---".
Table 1-1 is now characterized as listing examples of pathways, rather than identifying all potential pathways, due to an intent to not mislead the reader to accept the listing as exhaustive for all time. New pathways for potential release have been added to PVNGS since Rev. 1 was issued, and it is recognized that this process can continue. The reference to primary to secondary leakage has been deleted due to recognition of potential release pathways not associated with primary to secondary leakage, Table 1-1:
Change 1.4:
Rev. 1 lists Laundry Building Exhaust Rev. 2 lists Laundry/Decontamination Building Exhaust Explanation 1.4:
This potential pathway is 'better-characterized as the Laundry/Decontamination Building Exhaust,
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Change 1.5:
Rev. 2 adds:
"Dry Active Waste Processing and Storage (DAWPS) Building Respirator Cleaning Facility Secondary Side decontamination equipment."
Explanation 1.5:
These items have been added to PVNGS and are recognized to be potential release pathways.
2.0 GASEOUS EFFLUENT MONITOR SETPOINTS$
Change 2.1:
All Rev. 1 references to Technical Specification 3.3.3.9 have been changed to Technical Specification 3.3.3.8 in Rev. 2.
Explanation 2.1:
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The cited Technical Specification has been renumbered in the Operating l Licenses Change 2.2:
for the 3 units.
All Rev. 1 references to Technical Specification Table 3.3-13 have been changed to Table 3.3-12 in Rev. 2.
Explanation 2 ':
The cited Table has been renumbered in the Operating Licenses for the 3 units.
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2.4.1 Monitors Ru-141 Ru-143 and Ru-145 Change 2.3:
Rev. 1 states:
"The alarm/trip setpoint for Monitors Ru-141, Ru-143, and Ru-145 is calculated as follows:
'~h (Flow Rate)
CFM where:
Monitor Setpoint ~ the setpoint for the effluent monitor, in PCi/cc, which provides a safe margin of assurance that the allowable dose rate limits will not be exceeded.
~UNIT ~ unit release rate limit, in pCi/sec, as determined in Section 2.3.
Flow Rate = the flow rate, in cfm, from flow rate monitors or the fan design flow rate for the release source under consideration.
2.12x10 ~ conversion factor, cubic feet/minute per cubic centimeter/second.
fraction of Qggzy allocated for a specific release point. The sum of these administrative values will be less than or equal to one."
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Rev. 2 states:
"The alarm/trip setpoint for Monitors Ru-141, Ru-143, and Ru-145 is calculated as follows:
(2-6)
(471.9)(Flow Rate) where:
Monitor Setpoint = the setpoint for the effluent monitor, in PCi/cc, which provides a safe margin of assurance that the allowable dose rate limits will not be exceeded.
<UNIT = unit release rate limit, in pCi/sec, as determined in Section 2.3.
Flow Rate = the flow rate, in cfm, from flow rate monitors or the fan design flow rate for the release source under consideration.
471.9 conversion factor, cubic centimeter/second per cubic feet/minute.
= fraction of QuNzy allocated for a specific release point. The sum of these administrative values will be less than or equal to one."
Explanation 2.3:
The Rev. 2 conversion factor oX 471.9 is the reciprocal of the Rev. 1 conversion factor of 2.12E-3.
2.4. 2 Monitor RU-12!
Change 2.4:
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Rev. 1 states:
"The alarm/trip setpoint for Monitor RU-12, the Waste Gas Decay Tank Monitor, is calculated as follows:
CFM (Flow Rate) where:
Monitor Setpoint the setpoint for the monitor, in )JCi/cc at STP, which provides a safe margin of assurance that the allowable dose rate limits will not be exceeded.
qUNIT unit release rate limit, in LzCi/sec, as determined in Section 2.3.
Flow Rate ~ flow rate, in cfm at STP at which the tank will be released.
fraction of Qgszz allocated for a specific release point. This administrative value should be equal to or less than the administrative value used for the Plant Vent.
0.9 ~ an administrative value to account for potential increases in activity from other contributors to the same release point.
2.12 X 10 conversion factor, cubic feet/minute per cubic centimeter/second."
Rev. 2 states'The alarm/trip setpoint for Monitor RU-12, the Waste Gas Decay Tank Monitor, is calculated as follows:
Monitor Setpoint (LzCi/cc) < QqUNIT) a 0.9 - (H PF (471.9)
(Flow Rate) (.471.9) where:
Monitor Setpoint ~ the setpoint for the monitor, in LICi/cc at STP, which provides a safe margin of assurance that the allowable dose rate limits will not be exceeded.
qUNIT = unit release rate limit, in LzCi/sec, as determined in Section 2.3.
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Flow Rate flow rate, in cfm at STP at which the tank will be released.
PF ~ the current process flow of the plan vent in CFM.
~ the current plant vent monitor concentration in llCi/cc.
fraction of QUAN>> allocated for a specific release point. This administrative value should be equal to or less than the administrative value used for the Plant Vent.
0 ' an administrative value to account for potential increases in activity from other contributors to the same release point.
471.9 conversion factor, cubic centimeter/second per cubic feet/minute."
Explanation 2.4:
Waste Gas Decay Tank (WGDT) discharges are to the atmosphere via the Plant Vent. Equation (2-7) of Rev. 1 does not account for the existing release via the Plant Vent -- for sources other than WGDT -- in the determination of a setpoint for the WGDT monitor when developing a release permit for a planned WGDT discharge. Any existing release is indeed accounted for in the setpoint procedure, and Equation (2-7) of Rev. 2 reflects this. The change in conservative. Variables H and PF, added to Equation (2-7) of Rev. 2 provide the parameters needed to account for existing release via the Plant Vent.
The Rev. 2 conversion factor of 471.9 is the reciprocal of the Rev. 1 conversion factor of 2.12X10 ~", the reciprocal, Rev. 2, value is mathematically required by the form of the equation.
2.5 Monitor Calibrationi Change 2.5:
The third paragraph in Rev. 1 reads:
"The typical calibration conversion factor for the Waste Gas Decay Tank Monitor (RU-12) is based on Kr-85 calibration as indicated on Figure 2-2."
The third paragraph in Rev.. 2 reads:
"The typical calibration conversion factor for the Waste Gas Decay Tank Monitor (RU-12) is based on the detector energy response curve (Figure 2-2) and the FSAR source term decayed for forty five (45) days."
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Explanation 2.5:
Same as explanation 0.3.
~Fi ace 2 2s-Change 2.6:
Figure 2-2 and its title have been revised to reflect the same units on the X and Y axis as Figure 2-1. A different curve is presented.
Explanation 2.6:
,Same as explanation 0.4.
4.2 Iodine - 131 Eodine - 133 Tritium and All Radionuclides in Particulate Form With Half-Lives Greater Than 8 Da s Technical S ecification 3.11.2.3:
Change 4.1:
Rev. 1 states:
"The R< values were calculated in accordance with the methodologies in NUREG-0133 and generated using the GASPAR code. The following site specific information was used to calculate R<..
Value fraction of year milch animals and beef animals are on pasture, f P 0.75 fraction of daily intake of milch animals and beef animals derived from pasture while on pasture, f, 0.35 fraction of year vegetables are grown, f> approximation 0.667 absolute humidity (g/m>) over the growing season, H These site specific values are from the PVNGS Environmental Report, Section 2 and Appendix 5-B."
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"The R< values weie calculated in accordance with the methodologies in NUREG-0133 and generated using the GASPAR code. The following site specific information was used to calculate R<..
Value fraction of year milk animals and beef animals are on pasture, f 0.75 fraction of the feed that is pasture grass while the milk and beef animals are on pasture, f, 0.35 fraction of year vegetables are grown, f> approximation 0.667 the annual absolute humidity (g/m~), H These site specific values are from. the PVNGS Environmental Report, Section 2 and Appendix 5-B."
Explanation 4.1:
The term "Milch" while technically correct tended to confuse some readers. The term "Milk" has been substituted in this revision to avoid this problem in the future. In addition, the ER-OL lists 2 values for H over the growing season (4 and 6). To avoid confusion the annual value of 6 will be used. The definition of H reflects this change.
6.0 OPERABILITY OF E UIPMENT:
Change 6.1:
Section 6 ' is deleted from Rev. 2.
Explanation 6.1:
Same as explanation 0.2.
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7.0 RADIOLOGICAL ENVIRONMENTAL PROGRAM (Rev. 1 title)
Change 6.2:
All page numbers, section numbers, table"numbers and figure numbers have been changed to reflect the renumbering of Section 7.0 in Rev. 1 to Section 6.0 in Rev. 2.
Explanation 6.2:
Consistency with change 6.1.
6.1 Radiolo ical Environmental Monitorin Pro ram. Technical S ecification 3 '2.1s Change 6.3:
Rev. 1 states:
"Samples shall be collected as specified in Table 3.12-1 [of the Technical Specifications] and from the specific locations given in the table and figure(s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 3.12-1, and the detection capabilities required by Table 4.12-1 [of the Technical Specifications].
Environmental samples are collected at locations shown in Figures 7-1 and 7-2 and described in Table 7-1. Analytical techniques used ensure that the detection capabilities in Table 7-2 are achieved. Environmental samples are collected and analyzed according to Table 7-3."
Rev. 2 states:
Samples shall be collected as specified in Table 3.12-1 [of the Technical Specifications] and from the specific locations given in Table 6-1 and Figures 6-1 and 6-2 (of the ODCM), and shall be analyzed pursuant to the requirements of Table 3.12-1, [of the Technical Specifications) and the detection capabilities required by Table 4.12-1 [of the Technical Specifications].
Explanation 6.3:
The sampling and analysis requirements are controlled by the Technical Specifications, not the ODCM. Only the table and figures of the specific locations are required in the ODCM.
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Change 6.4:
.Add paragraph:
"If the analysis of an environmental sampling medium at a specified location exceeds the reporting level of Table 3.12-2 [of the technical specifications) when averaged over any calendar quarter, an investigation shall be conducted. If the radioactivity is determined to be the result of plant effluents a Special Report is submitted to the NRC, within 30 days, which identifies the cause(s) for exceeding the limit(s) and corrective actions to be taken. If the radioactivity is determined not to be the Lesult of plant effluents, the condition is reported and described in the Annual Radiological Environmental Operating Report."
.Explanation 6.4 This is additional program information describing the activities which would be conducted for the contingency mentioned; this is derived from Action Statement 3.12.lb of the PVNGS Technical Specifications.
Change 6.5 Rev. 1 states:
"Following this period, program changes may be proposed based on operational experience. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment, and other legitimate reasons.
If specimens are unobtainable due to sampling equipment malfunction, an effort is made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule are documented in the annual report."
Rev. 2 states:
"With the radiological environmental monitoring program not being conducted as specified in Table 3.12-1-, (of the Technical Specifications]
prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence."
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Explanation 6.5:
This change clearly states the Technical Specification Action Statement.
6.2 LAND USE CENSUS'hange 6.6:
Rev. 2 adds the footnote of PVNGS Technical Specification 3.12.2: "*Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 3.12-1 shall be followed, including analysis of control samples."
Explanation 6.6:
Editorial change; previous quotation of the Technical Specification was less complete.
Change 6.7:
Rev. 1 states:
"A land use census is conducted in accordance with Technical Specification 3.12.2. When a land use census identifies a location(s) which yields a calculated dose or dose commitment greater than the values calculated from current sample locations, appropriate changes in the sample locations are made."
Rev. 2 states:
"A land use census is conducted in accordance with Technical Specification 3.12.2. When a land use census identifies a location(s) which yields a calculated dose or dose commitment greater than the values calculated in Technical Specifications 4.11.2.3, identify the new location(s) in the next Semiannual Radioactive Effluent Release Report."
Explanation 6.7:
This is additional program information describing the activities which would be conducted for the contingency mentioned; this is derived from Action Statement 3.12.2a of the PVNGS Technical Specifications.
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Change 6.8:
Rev. 1 states:
"If a land use census identifies a location(s) with a higher average annual disposition rate (D/Q) than a current indicator location, the following applies:
- 1. If the D/Q is at least 20l greater than a previously high D/Q, one of the existing sample locations may be replaced after and evaluation with a new one within 30 days. The evaluation is based on past history of the location, availability of sample, milk production history, and other environmental conditions.
Z. If the D/Q is not ZOX greater than the previously highest D/Q, distance and D/Q are considered in deciding whether to replace one of the existing sample locations.
within 30 days."
If applicable, replacement is made Rev. 2 states:
"When a land use census identifies a location(s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20X greater than at a location from which samples are currently being obtained, the new location(s) is added to the Radiological Environmental Monitoring Program within 30 days.
An equivalent sampling location(s), excluding the control location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from the Radiological Environmental Monitoring Program after October 31 of the year in which this land use census was conducted.
New sampling location(s) are identified in the next Semiannual Radioactive Effluent Report along with revised ODCM figure(s) and table(s) which reflect the new location(s)."
Explanation 6.8:
This is additional program information describing the activities which would be conducted for the contingency mentioned; this is derived from Action Statement 3.12 'b of the PVNGS Technical Specification. In addition, the action specified is based on an increase of ZOZ or greater of the calculated dose or dose commitment-rather than an increase in the D/Q as in Revision 1. This methodology more closely implements the referenced Technical Specification.
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Change 6.9:
Rev. 1 states:
"A land use census is conducted at least one per calendar year by a door-to-door or aerial survey, by consulting local agricultural authorities, or by any combination of these methods."
Rev. 2 states:
"A land use census is conducted during the growing season at least once per 12 months by a door-to-door or aerial survey, by consulting local agricultural authorities, or by any combination of these methods. The results of the land use census are reported in the Annual Radiological Environmental Operating Report."
Explanation 6.9:
This change clarifies that the census is conducted during the growing season, and that results are reported.
6.3 INTERLABORATORY COMPARISON PROGRAM:
Change 6.10 Rev. 1 states:
"The results of analyses of these crosscheck samples are included in the annual report."
Rev. 2 states:
"The results of all analyses made under this program are included in the Annual Radiological Environmental Operating Report."
Explanation 6.10:
Editorial change: The statement was combined with material added; see change 6.11, following.
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Change 6.11:
Rev. 2 has additional text:
'The sample handling, preparation and analysis procedures approved for use on routine REMP.samples, at the time the crosscheck samples are received from the EPA, are used to implement the program. The results of the crosscheck sample analyses are reviewed, at minimum on an annual basis, tn ensure that the control limits established by the EPA are not exceeded.
If deviation from these specified limits is identified an investigation is mad~ to determine the reason for the deviation and corrective actions are taken as necessary. The results of all analyses made under this program are included in the Annual Radiological Environmental Operating Report."
Explanation 6.11:
Paragraph one above identifies the specific review areas and schedule that will be performed with regard to the EPA crosscheck sample analysis results as recommended by Reg Guide 4.15, Section 6 '.2.
Paragraphs one and two above identify the "Methodology and Parameters (acceptance criteria or actions based on non-acceptance)" as required by section 4.12.3 of PVNGS Technical Specification.
Table 6-ls Change 6.12:
Changes occurred at the sample sites listed, for the following reasons:
Sample Site Change Reason Add: Air, East of RR Tracks TLD and Air not together Add: Perryville Rd & Thomas Rd Specify address E25 to E21, Distance wrong in Rev. 1, Add: 19800 W. Hwy. 85 Specify address E20 to E16 Distance wrong in Rev. 1, Add: 615 N. 4th St. Buckeye Specify address ESE 15 to ESE 11 Distance wrong in Rev. 1, Add: (291st Ave) & Old Hwy 80 Specify address 17
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Explanation 6.12 (cont'd):
Sampl'e Site Change Reason SSE 35 to SSE 31 Distance wrong in Rev. 1, Add: Service Rd W. of Town, off I-8 Specify address 7A Add: 16351 S. Arlington School Rd Specify address 10 Ward Rd to Elliot Rd New Rd. Name 14A NNE 3 to NNE 2 Distance wrong in Rev. 1 23 Ward Rd to Elliot Rd New Road Name 24 26 Add: 13202 S. 383rd Ave Specify Address 33 NNW 5 to NNW 4 New location SE corner of 395th and Buckeye Rd.
34 Belmont Rd to 395th Rd. Marked 395th Add: 40901 W. Osburn Rd Specify Address 38 Yuma Rd to Buckeye Rd New Road Name 40 TLD Add: End of Transmission Rd Specify address 41 Add: Van Buren St., 1 mi W. of Specify address Steve Martori Dr.
Add: Indian School Rd. & Specify address Wintersburg Rd.
43 Add: 1 mi. S. of US 60 Specify address 44 TLD Add: 12313 W. Grand Ave. Specify address Add: 615 N. 4th St, Buckeye Specify address 46 Water Add: 41701 W. Indian School Rd. Specify address TLD ENE 30 Litchfield Pk Sch.,
13825 W. Indian School Rd. New TLD Si.te 18
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Explanation 6.12 (cont'd):
Sample Site Change Reason 46 Water Add: 41701 W. Indian School Rd. Specify address 47 Vegetation NE3 to ENE3 Direction wrong in Rev. 1 47 Vegetation Add: Buckeye-Salome Rd. Specify-Address TLD E35 Littleton School, 115th Ave & Hwy 85 New TLD site 48 Water(b) SSW 5 Shepard Farms, 13202 S. 383rd Ave New Water Site 48 TLD E24 Perryville, Jackrabbit Trail, S. of Circle K New TLD Site 49 Wedgeworth to Glover, Adds 9199 S 351st Ave. New Property Owner 49 TLD ENE11 Hopeville, Palo Verde Rd.
1/2 mi. S. of I-10 New TLD Site 50 E 28 Leuck Dairy, Jackrabbit Trail New Site Number
& Elliot Rd (Baisley Dairy gone) 50 TLD WNW5 Olinski Rd 2 mi. S. of Buckeye-Salome Rd. New TLD Site 52 Cambron to Schroeder New Resident 54 Skousen to Smart New Resident 55 Water SW3 Gavette Residence, 39326 W. Elliot Rd New Water Site Add: fl There are 2 Evap Ponds 61 Add: 643 S. Sierra Specify Address 62 AJM Farms to J.A. Wood Co. New Name of Site 63 Surface Water(b) PVNGS Evap Pond S2 New Location 19
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Pi urea 6-1 and 6-2s Change 6. 13:
A column "NOTATlON" was added to Table 6-1. This clarifies the locations stated in Technical Specifications Table 3.12-1.
Change 6.14:
Sample locations are updated.
Explanation 6. 14:
Changes required for consistency with change 6.12.
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Change A.l:
Rev. 1 uses "milch animal".
Rev. 2 uses "milk animal".
Explanation A.l:
Editorial; delete German and use English consistently, 20
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