ML17300A463
| ML17300A463 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 06/30/1986 |
| From: | Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| ANPP-38052-JGH, NUDOCS 8609160032 | |
| Download: ML17300A463 (360) | |
Text
vl IDES h3ICHe~S REGULATORY INFORMATION DISTRIBUTION SYSTEM (R IDS> pvm ACCESS IQN NBR: 8609160032 DOC. DATE: 86/06/30 NOTARIZED: NQ DOCKET FAC IL: STN-50-528 Pal o Verde Nucl ear Stati one Uni t ii Ar i zona Pub 1 i 05000528 STN-50-529 Palo Verde Nuclear Station> Unit 2> Arizona Publi 05000529 AUTH. NAME AUTHOR AFFILIATION Arizona Nuclear Power Prospect (formerly Api zona Public Serv HAYNES> J. G. Arizona Nuclear Power Prospect (formerly Ari zona Public Serv RECIP. NAME RECIPIENT AFFILIATION W
MARTIN> J. B. Region 5i Office of Director Q~gg
SUBJECT:
"Palo Verde Nuclear Generating Station Units 1 8f 2p Semiannual Operating Rept'adioactive Ef f luents. Jan-June 1986. " W/860829 ltr.
DISTRIBUTION CODE: IE25D COPIES RECEIVED: LTR ENCL SIZE:
TITLE: Periodic Environ Monitoring Rept (50 DK >-Annual/Semiannual/E'f fluent/
NOTES: Standardized plant. M. Davis. NRR: iCg. 05000528 Standardized plant. M. Davis. NRR: 1Cg. 05000529 RECIPIENT COPIES RECIPIENT COP IES.
ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PNR-B PD7 L* 1 0 PNR-B PD7 PD 04 5 5 PNR-B PEICSB 3 3 INTERNAL: ACRS 1 1 AEOD AEOD/PTB 1 1 IE FILE 01 NRR BWR ADTS 1 NRR PWR-A ADTS NRR PNR-B ADTS 1 NRR/DSRO/RR*B RGN2/DRSS/EPRPB 1 1 RM/DDAMI/MIB EXTERNAL: LPDR 03 ~
1 1 NRC PDR ~
02 NOTES: 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 21
Arizona Nuclear Power Project P.o. BOX 52034 ~ PHOENIX, ARIZONA 85072-2034 August 29, 1986 ANPP-38052-JGH/PGN/98.05 Mr. John B. Hartin, Regional Administrator Office of Inspection and Enforcement Region V U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596-5368
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1 and 2 Nos. STN 50-528 (License NPF-41)
'ocket STN 50-529 (License NPF-51)
Semiannual Radioactive Effluent Release Report File: 86-A-056-026 G.l'.01.10
Dear Hr. Hartin:
Pursuant to 10 CFR 50.36(a)(2) and in accordance with Technical Specification 6.9.1.8, attached please find two copies of the Semiannual Radioactive Effluent Release Report for the Palo Verde Nuclear Generating Station Units No. 1 and 2 for the six month period ending June 30, 1986. By copy of this letter, we are also forwarding a copy of this report to the Director of Inspection and En-forcement.
Very truly yours, J. G. Haynes Vice President Nuclear Production JGH/PGN/rw Attachment cc: 0. M. De Michele E. E. Van Brunt, Jr.
J. H. Taylor (Office of IRE)
E. A. Licitra R. P. Zimmerman A. C. Gehr
I PALO VERDE NUCLEAR GENERATING STATION UNITS 1 AND 2 SEMI-ANNUAL OPERATING REPORT RAD IOACT IVE EFFLUENTS JANUARY 1, 1986 THROUGH JUNE 30, 1986 USNRC Dockets STN-50-528 and STN-50-529
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PVNGS Semi-Annual Operating Report for January June 1986 Table of Contents
~Pa e Introduction Bibliography Appendix A: Source Terms and Effluent and !4aste Al Disposal Reports Appendix B: Meteorology Bl Appendix C: Dose Calculations C1 Appendix D: Changes to Offsite Dose Calculation Manual (ODCM) DI Appendix E: Revised Offsite Dose Calculation Manual (ODCM) El
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?VNGS Semi-Annual Operating Report for January - June 1986 List of Tables Table No. Page PVNGS Unit 1 Gaseous Effluents - Minimum Detectable A6 Activity PVNGS Unit 1 Effluent and Waste Disposal Semiannual Report (1986) Gaseous Ef fluents-Summation of All Releases A7 PVNGS Unit 1 Gaseous Effluents - Ground Level Releases PVNGS Unit 1 Radiation Doses at and Beyond the Site A10 Boundary for 1986 PVNGS Unit 2 Gaseous Effluents - Lower Limit of Al 1 Detection A6 PVNGS Unit 2 Effluent and Waste Disposal Semiannual A12 Report (1986) Gaseous Effluents - Summation of All Releases A7 PVNGS Unit 2 Gaseous Effluents - Ground Level Releases A13 A8 PVNGS Unit 2 Radiation Doses at and Beyond the Site , A15 Boundary for 1986 A9 Estimation Methodology of Total Percent Error A10 Solid Waste Summary for January - June 1986 A17 Al 1 Effluent Monitoring Instrumentation Out of A19 Service Greater than 30 Days JFDs of 35-Foot Wind Versus Delta T B3 January - March 1986 B2 JFDs of 35-Foot Wind Versus Delta T B9 April - June 1986 JFDs of 35>>Foot Wind Versus Delta T B15 January - June 1986 B4 JFDs of 35-Foot Wind Versus Delta T B21 January - March 1986 Batch Releases B5 JFDs of 35-Foot Wind Versus Delta T B27 April - June 1986 Batch Releases Cl Doses to Special Locations for January-June 1986 C3
I PVNGS Semi-Annual Operating Report for January June 1986 List of Tables (Continued)
Table No. ~Pa e C2 Integrated Population Doses for January June 1986 C4 C3 Summary of Individual Doses for January - June 1986
PVNGS Semi-Annual Operating Report for January June 1986 INTRODUCTION This report summarizes meteorological data and doses from radioactive efflu-ents for the Palo Verde Nuclear Generation Station (PVNGS) for the period January through June 1986. The data presented meet the reporting require-ments of Regulatory Guide 1.21 of the U.S. Nuclear Regulatory Commission (Revision 1, June 1974).
The report is organized into four parts. Appendix A presents the effluent and waste disposal source term data. Appendix B presents a summary of on-site meteorological data for the report period. Appendix C presents the radiological doses from gaseous radioactive effluents. Appendix D presents changes made to the Offsite Dose Calculation Manual (ODCM) and their expla-nations.
Appendix E presents the entire revised ODCM.
PVNGS Semi-Annual Operating Report for January - June 1986 BI BLIOGRAPHY 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 Plant," Revision 1, 1974.
U.S. Nuclear Regulatory Commission, Regulatory Guide 1.23 (Safety Guide 23),
"Onsite Meteorological Programs," Revision 0, 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 Release 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.
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PVNGS Semi-Annual Operating R'eport for January - June 1986 APPENDIX A SOURCE TERM AND EFFLUENT AND WASTE DISPOSAL REPORTS
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PVNGS Semi-Annual Operating Report for January - June 1986 S upplemen tal In forma t ion 1.0 Regulatory Limits 1.1 Liquid Releases
- a. PVNGS Technical S ecification 3.11.1.1 The concentration of radioactive material discharged from secon-dary system liquid waste to the onsite evaporation ponds shall be limited to the Lower Limit'of Detectability (LLD) defined as 5 x 10 7 uCi/ml for the principal gamma emitters or uCi/ml for I-131.
l x 10 6
- b. PVNGS Technical S ecification 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radio-active materials in liquid effluents released, from each reactor unit, to areas at and beyond .the SITE BOUNDARY shall be limited:
o 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 o 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
- a. 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:
o 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 o 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:
o 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, I
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PVNGS Semi-Annual Operating Report for January - June 1986 o During any calendar year: Less than or equal to 10mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
- 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 ln 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 shall be limited to the following:
o During any calendar quarter: Less than or equal to 7.5 mrems to any organ and, o During any 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 TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the pro)ected 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 VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the pro)ected doses due to gaseous effluent releases, from each reactor unit, to areas at and beyond the SITE BOUNDARY when averaged over 31 days would exceed 0.3 mrem to any organ of a MEMBER OF THE PUBLICA 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 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 thy-roid, 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 The average energy (E) of the radionuclide mixture in releases of fis-.
sion and activation gases is. not applicable to PVNGS.
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PVNGS Semi-Annual Operating Report for January - June 1986 "4.0 Measurement and A roximation of Total Radioactivit in Gaseous Effluents.
For continuous releases, sampling is in accordance with PVNGS Technical Specification Table 4.11-2. Particulate and iodine radionuclides are sampled continuously at the three exhaust points. The particulate filter 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 'verage 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
'ritium concentration is assumed constant between sampling periods.
For batch releases, sampling is also in accordance with PVNGS Technical Specification Table 4.11-2 For containment purges, the noble gas concentration is ad)usted 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 MiMama Detectable Activity (MDA)'nd the Lower Limit of Detection (LLD) are the minimum . activity detectable by a measurement system for each particular sample. The MDA and LLD will include any interferences from other radionuclides and are calculated using the actual sample volume and instrument efficiency. An average MDA and LLD for each nuclide are provided in Tables Al and A5 ~
5.0 Batch Releases
- 5. 1 Gaseous Unit 1 Unit 2 Number of batch releases: 56 13 Total time period for batch releases: 176445 3985 Maximum time period for a batch release'. 10080 683 Average time period for a batch release: 3151 307 Minimum time period for a batch release'. 6 61 (All times are in minutes) 5.2 Liquid None 6.0 Abnormal Releases None A4
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PVNGS Semi-Annual Operating Report for January - June 1986 Page 2.
- 7. 0 Offsite Dose Calculation Manual (ODCM) Process Control Pro ram (PCP) and Pre lanned Alternate Sam lin Pro ram (PASP) Revisions There were no revisions to the PCP or the PASP.
The ODCM was extensively revised. The changed pages, comprising the entire ODCM, and the evaluation of this revision are provided in Appendices E and D, respectively. The changes to the Radio-logical Environmental Monitoring Program are included in these Appendices.
- 8. 0 Effluents and Solid Wastes 8.1 Gaseous Effluents The gaseous effluents for the first and second quarters are included in Tables A2, A3, A6 6 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 A10.
9.0 Miscellaneous Information Releases made to the Evaporation Pond have been limited'at the tank to the concentrations specified in Technical Specification 3.11.1.1. In addition, PVNGS has imposed a limit of 3 x 10 uCi/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 Technical Specification 3.12.1.
During this report period, the analyses showed tritium concen-trations in water to be less than 3 x 10 6 uCi/ml.
The results of the strontium 89 and strontium 90 analyses for Unit 1 for the third and fourth quarter, 1985 were less than LLD.
The gaseous effluent and dose summaries are therefore correct as reported in the July-December, 1985 Semi-Annual Report.
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PVNGS Semi-Annual Operating Report for January - June 1986 Table Al PVNGS UNIT 1 GASEOUS EF'F'LUENTS - MINIMUM DETECTABLE ACTIVITY NUCLIDE MDA (UCI/cc )
KRYPTON 85 1. 20 E-05 KRYPTON 87 1.50 E-07 KRYPTON 88 1. 30 E-07 XENON 138 8.20 E-06 XENON 133M 2.80 E-07 XENON 135M IoDINE 135 2 '0 4.10 E-06 E
IODI~E 132 2.40 E STRONTIUM 89 5.00 E STRONTIUM 90 5.00 E CEsIU~ 134 1.10 E
, CEsIUM 137 1.30 E
'EsIU~ 138 5.30 E BAR IUM 40 4.10 E LANTHANUM 140 2.20 MANGANESE 54 IRON 59 2.90 fE COBALT 58 1.20 E COBALT 60 .70 E ZINC 65 3.10 E BROMINE 82 RUBIDIUM 88 6.30 8 MOLYBDENUM 99 7.80 E -1 CERIUM 141 1.10 E CERIUM 144 4.70 E -1 HYDROGEN 3 3.30 E -07 XENON 131M ARGON 41 1 '0 3.10 E -07 E -07 BERYLLIUM 7 3 '0 E -13 ANTIMONY 124 2 '0 E -13 CEsIUM 136 5.30 E -14 ANTIMONY 122 4.90 E -14 TECHNETIUM 99M 1.90 E -14 TUNGSTEN 187 1.70 E -13 YTTRIUM 91M 6.20 E -14 GROSS ALPHA 6 '1 E -15 A6
PVNGS Semi-Annual Operating Report Table A2 for January - June 1986 PVNGS UNIT 1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1986)
GASEOUS EFFLUENTS-SUMMATION OF ALL ML1ASES UNIT QUARTER QUARTER EST ~ TOTAL
! ERROR C +
A. Fission 4 activation gases 2 42K+03 2.58EtOl 3.97E+Ol
- 2. Avera e release rate f'r eriod Ci se 3. 11E+02 3.28E+00
- 3. Percent of'echnical S ecification Limit NA%+
B. Iodines 1.. Total iodine-131 Ci 3.2~3 3.72E-O4 2.93E+Ol
- 2. Avera e release rate for eriod Ci sec 4.14E-04 4.73E-05
- 3. Percent of Technical S ecif ication Limit NA+% NA~
1 ~ Particulates with half-lives >8 da s Ci 3.01E-05 3.08E-05 2. 93E+Ol Avera e release rate for eriod Ci sec 3.87E-06 3.92E-O6 Per ent of'echnical S ecif'ication Limit NA~ NA~
d pact v t Ci <mA D. Tritium
- 1. Tota Release Ci 6.01~1 1.15E+02 4.22K+01 A e e e ase rate f'r eriod Ci sec 7.73E}00 1.46E+Ol P Te n S ec f cation Limit NA~ NA%%
- Estimated total error methodology is presented in Table A9.
- See Table A4 for percent of technical specification limits.
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T bl Table j A3 (Continued)
?VNGS Semi>>Annua 1 Opera t ing Report (C d) for January - June 1986 PVNGS UNIT 1 GASEOUS EFFLUEilTS-GROUND LEVE'ELEASES CONTINUOUS MODE BATCH MODE INuclides Released Unit Quarter " Quarter Quarter Quarter I
1st 2nd 1st 2nd
- 3. Particulates (continue ";
Lanthanum-140 Cj <M)A <M)A <M)A <M)A Cesium-137 Cj <MDA 4 62E-0 Barium-140 Ci <MDA <MD Tritium Bromine-82 Iron-59 Ci Rubidium-88 Ber ilium-7 Cj 47 Cobalt-58 Cj 1.32E-06 6 28 -06 7 Man anese-54 Antimon -124 Ci Cj
<MDA 8.65E-06 7 16 7 1 6-0
~~~g7 0-Cesium-136 Cj <MDA Cesium-138 Cj <MDA Mol bdenum-99 Cj <MDA 1 0 Antimon -122 Ci i <MDA <MDA 4 66 -05 echnetium-99m Ci <MDA <MDA 7.08E-07 <MD Tun sten-187 Ci Yttrium-91m Ci unidentified Ci I +
ental .or eric"'. > 9.97E-06 i 9 07E 1 6 0 Not applicable to PVNGS Analysis not yet completed. additional information will be included the next Semi-annual Report.
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PVNGS Semi-Annual Operating Report Table A4 for January - June 1986 PVNGS UNIT,1 Radiation Doses at and Beyond the Site Boundary for 1986*
Unit Quarter Quarter Quarter Quarter 'ear To
¹1. ¹2 ¹3 ¹4 Date
- l. a. Gamma Air mrads 2.84E-Ol 3.33E-03 2.87E-01 Dose X of T.S.
3.11 .2.2 5.68E+00 6.66E-02 2.87E+00
- b. Beta Air mrads 7.45E-01 8.27E-03 7.53E-01 Dose X of T.S.
3.11.2.2 7.45E+00 8.27E-02 3.77E+00
- 2. Maximum mrem 5.75E-Ol 4.44E-01 9.21E-01~
organ Dose Fo of T.S.
3.11.2.3 7.67E+00 5.92E+00 6.14E+00 Calculations based on parameters and methodologies of the ODCH using historical meteorology. The. beta and gamma air doses were calculated using SSW sector X/Q at the site boundary. The maximum organ dose
~ was calculated assuming a residence, garden, milk cow and meat animal using the SSW sector X/Q at site boundary and W sector D/Q at site boundary. These are the highest calculated annual average dispersion parameters for any of the three units. These doses are calculated to estimate percentage of Technical Specification limits.
The limiting organ is infant thyroid.
The limiting organ is child thyroid.
l' PVNGS Semi-Annual Operating Report for January " June 1986 Table A5 PVNGS UNIT 2 GASEOUS EFFLUENTS - LOWER LIMIT OF DETECTION NUCLIDE LLD (PCI/CC)
KRYPTON 85 6.99 E-06 KRYPTON 85M 2.72 E-08 KRYPTON 87 6.60 E-08 KRYPTON 88 8.00 E-08 XENON 138 1.26 E-06 XENON 133M 1.66 E-07 ODINE 132 2.32 E-13 ODINE 135 5.58 E-13 TRONTIUM'9 5.00 E-16 TRONT IUM 90. 5.00 E-16 CESIUM 134 CESIUM 37 7 '8 8.89 E -14 E -14 BARIUM 140 2.33 E -13 LANTHANUM 140 ~ 02 E IRON 59 .65 E COBALT 58 7.87 E -14 COBAI T 60 8.71 E -14 ZINC 65 1.45 E -13 BROMI NE 82 8.38 E -14 CERIUM 141 7.96 E -14
. CERIU~ 144 4.00 E -13 HYDROGEN 3 BERYLLIUM 7 3 '7 2.75 E -07 E -13 RUTHENIUM 103 2 '1 E -14 GROSS ALPHA 1.03 E -14 XENON 135M 4.02 E -07 ARGON 41 3.73 E -08
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P~GS Semi-Annual Operating Report for January - June 1986 Table A6 PVNGS UNIT AND WASTE DISPOSAL SEMIANNUAL REPORT 2'FFLUENT (1986)
GASEOUS EFFLUENTS-SUMMATION OF AU RELEASES I! !
UNIT QUARTER j QUARTER I . 2
)
I EST ~ TOTAL ERROR A. Fission & activation gases Ci NA 9.04E+00 5.88E+01 l
- 2. Avera e release rate for eriod Ci se NA 1.15E+00
- 3. Percent of Technical S ecification Limit NA NA%+
B. Iodines 1 . Total iodine-131 Ci NA 1.47E-05 5.23E+Ol
- 2. Avera e release rate for eriod Ci sec NA 1.87E-06
- 3. Percent of'echnical S ecification Limit NA NA~
C. Particulates Ci NA 1;49E-06 5.23E+01 2 Avera e release rate for eriod Ci sec NA 1.90E-07 Pe t f Techn a S ecification Limit NA NA+%
ado t'v t Ci NA D. Tritium 1 Tota Re ease Ci NA 1.39E-03 4.22E+01 A e e e rate for eriod Ci sec NA 1. 77E-04 T a S ec f cation Limit NA NA+%
- Estimated total error methodology is presented in Table A9 .
- See Table AS for percent of technical specification limits.
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Table A7 PVNGS Semi-Annual Operating Report fo r January - J~e 1986 PVNGS UNIT 2 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE Nuclides Released Unit Qu rter Quar er Quarter t Qujger
- 1. Fission gases Kr ton-85 Ci NA+ <LLD <LLD Kr ton-85m Ci NA <LLD 1.10E-03 Kr ton-87 Ci NA <LLD NA Kr ton-88 Ci <LLD Xenon-133 Ci 5. 8E+00 NA 1.36E+00 Xenon-135 Ci 1.54E-02 Xenon-135m Ci <LLD NA <LLD I Xenon-138 Ci NA 7.45E-02 Ar on 41 . Ci NA 2.55E-02 Xenon 133m Ci NA 9.35E-03 unidentified Ci Total for eriod Ci NA 7. 55E+00 1. 49E430
- 2. Iodines Iodine-131 Ci NA NA 1. 23E-06 Iodine-132 Ci <LLD NA <LLD Iodine-133 Ci 4 E-7 1.01E-06 Iodine-135 Ci <LLD NA <LLD Total for eriod Ci 1.39E-05 iVA 2.24E-06
- 3. Particulates Strontium-89 Ci NA iVA Strontium-90 Ci NA Cesium-134 Ci <LLD NA <LLD A13
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PVNGS Semi-Annual Operating Report for January - June 1986 Table A7 (Continued)
PVNGS UNIT 2 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter Quarter Quarter Quarter 1st 2nd 1st 2nd
- 3. Particulates (continued)
Cesium-137 NA <LLD Barium-140 Ci NA <LLD <LLD Ci NA <LLD NA 1.39E-03 NA 1.28E06 NA <LLD Ruthenium- 03 NA -07 NA <LLD Ci NA NA 2.00E-06 Co alt-60 Ci NA <LLD NA 3.89E-08 Lanthanum-140 Ci NA <ELD NA <LLD unidentified Ci Total for eriod NA 1.45E-O 1.39E-03 PVNGS Unit 2 achieved initial criticality on April 18, 1986.
Not applicable to PVNGS.
Analysis not yet completed. Additional information will be included in the next Semi-annual Report.
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PVNGS Semi-Annual Operating Report for January - June 1986 Table AS PVNGS UNIT 2 Radiation Doses at and Beycnd the Site Boundary for 1986*
Unit Quarter Quarter Quarter Quarter Year To
¹1 ¹2 ¹3 ¹4 Date
- 1. a. Gamma Air mrads NA 1.99E-03 1.99E-03 Dose X of T.S. NA 3.98E-02 1.99E-02 3.11.2.2
- b. Beta Air mrads NA 3.53E-03 3.53E-03 Dose 7o of T.S. NA 3.53E-02 1.77E-02 3.11.2.2
- 2. Maximum mrem NA 2.21E-03 2.21E-03~~
Organ Dose X of T.S. NA 2.95E-02 1.47E-02 3.11.2.3
+ Calculations based on parameters and methodologies of the ODCM using historical meteorology. The beta and gamma air doses were calculated using the SSW sector X/Q at the site boundary. The maximum organ dose was calculated assuming a residence, garden, milk cow and meat animal using the SSW sector X/Q at site boundary and W sector D/Q at site boundary. These are the highest calculated annual average dispersion parameters for any of the three units. These doses are calcu-lated to estimate percentage of Technical Specification limits.
~ The limiting organ is infant thyroid.
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PVNGS Semi-Annual Operating Report for January June 1986 Table A9 Estimation Methodology of Total Percent Error The estimated total error is calculated as follows:
2 2 2 2 1/2 Total Percent Error (E1 + E2 + E3,..., + E n)
Where E n
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.
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PVNGS Semi-Annual. Operating Report for January June 1986 Table A10 Solid Waste Summary for January-June 1986 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)
- 1. Type of Waste Es timated 6-Month Total Unit Period Error X
- a. Spent resins, filter sludges, M3 4. 1 1E+01 evaporator bottoms; etc Ci 2. 46E+00* 2. 50E+01
- b. Dry compressible waste, contaminated M3 O.OOE+00 equipment, etc Ci O.OOE+00 'NA
- c. Irradiated components, control M3 0.00E+00 rods, etc Ci 0 'OE+00
- d. Other (describe) M3 O.OOE+00 Ci O.OOE+00 NA
- 2. Estimate of Major Nuclide Composition for Spent Resins, Filter Sludges, Evaporator Bottoms, etc., as Determined by Measurement Tritium 4 ~ 72E+01 Antimony 124 2.22E+01 Cobalt 58 1.19E+01 Cesium 137 7.00E+00 Cobalt 60 3.30E+00 Manganese 54 2.30E+00
- Iron 55 1.90E+00 Iodine 131 1.70E+00
- +Nickel 63 1 '0E+00 Iron 59 6.00E-01
- 3. Solid Waste Disposition Number of Shi ments Mode of Trans ortation Destination 5 Overland (Truck) Hanford Reservation Richland, Washington (U.S. Ecology)
- As determined by measurement; see A.2 for scaled nuclides.
- Isotopic concentration derived using scaling factors in accordance with 10 CFR 61.55.
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PVNGS Semi-Annual Operating Report for January June 1986 Table A10 (Continued)
Solid Waste Summary for January - June 1986 B. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shi ments Mode of Trans ortation Destination NA NA C. ADDITIONAL INFORMATION
- 1. Six (6) 182 fthm Steel Liners shipped.
o 4 liners were evaporator bottoms solidified in cement.
o 2 liners were dewatered resin with no solidification media used.
- 2. Seven (7) - 29.3 ft3 Disposable Demineralizers which were dewatered and not solidified.
- 3. Types of containers:
Thirteen (13) - DOT Strong Tight Containers - LSA A18
l l
PVNGS Semi-Annual Operating Report for January June 1986
'Bable A11 Effluent i&nitoring Instrumentation Out of Service Greater Than 30 Days Ins trumen t Inoperability Inoperability Cause Explanation Date H,/0, 1/'86 to Engineering Evalua- Vendor delay in providing-Analyzer Present tion Requests (EER) drawings ~ DCP delay; to Unit 1 dispositioned to be issued to construction perform rewiring and by 11/86.
circuitry changes per vendor instruc-tions. Design Change Packages (DCP) being prepared to install condensate pots on gas stripper and holdup tank sample lines and analyzer drain line to prevent gas leakage to rad>>
waste building floor drains.
H2/02 4/86 to Require completion of DCP status explanation Analyzer Present pre-operational test. same as Unit 1, above.
Unit 2 DCP status same as Preoperational test Unit 1 Hp/+ ana- completion has prerequis-lyzer, above. ites which can not be fulfilled pending comple-tion of higher priority work items.
RU-14 3/ 144 2/20/86 Power supply and Unanticipated delays in Unit 1 to detector failure. troubleshooting and 4/4/86 obtaining parts.
RU-141/142 5/26/86 Erroneous alarms and Installation of a modi fi-Unit 1 'to indication. cation to stabilize 7/3/86 readings.
RU-143/.144 5/27/86 Erroneous alarms and Installation of a modifi-Unit 1 to indication. cation to stabilize 7/2/86 readings A19
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PVNGS Semi-Annual Operating Report for January - June 1986 APPENDIX 3 METEOROLOGY
I I
PVNGS Semi-Annual Operating Report for January June 1986 JOINT FREQUENCY DISTRIBUTION TABLES The tables presented in this section are results obtained from processing the hourly meteorological data collected at the Palo Verde Nuclear Generating Station for the period January-June 1986. 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, semi-annual and 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). JFDs are also presented for the batch releases for both the first and second quarters.
B2
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I
PVNGS Semi-Annual Operating Report for January - June 1986 Table 81 JFDs of 35&oot Wind Versus Delta T January . i'larch 1986 B3
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2VNGS Semi-Annual. Operating Report for January - June l986 PYNCS JFO: 35FT VINO YS DELTA T (200'$ ') FOR OTRI L986 SITE IDENTIFIER: PYNCS DATA PERIOD EIAHINED: 1/ 1/86 3/31/86 FIRST OUARTER STA41LITY CLASS A STARILITY SASED ON: DELTA T SETVEEN 200 ~ 0 VINO HEASURED ATt 35 ' FEET ANO 35 ' fEET ltlNO THRESHOLD ATt 0 7$ HPH JOINT FREOUEXCY OLSTR18UTLON Of VINO SPEED ANO DIRECTION LN HOURS AT 3S F 00 FEET 0 00 0 00 oooo SPEED LHPH) 8 NNE NE ENE E E5E SE SSE S SSV SV VSVO V VNM NV NNV TOTAL 0 00 0 00 0 0 000 0 0 0 0 0 CAUI 0 0 ~ 76 1050 0 0 0 . 0 0 0 0 0 0 0 1051 2 50 0 0 0 0 0 0 0 0 0 0 2051 3 50 0 0 0 0 0 0 0 0 0 0 3 F 51 4050 0 0 0 0 0 0 0 0 0 0 4~$1 5 F 50 0 0 0 0 0 0 0 0 0 0
$ +SL 6.50 0 0 0 0 0 0 0 0 0 ~ 0 4~ 510 8 $0 0 0 0 8.51 LL.SO 0 0 .0 0 ~ 0 0 1 0 0 0 0 0 0 1 0 7 LI 51016 ~ 50 0 0 0 0 0 0 0 0 9 I< ~ $ 1 20.50 0 2 0 0 0 0 0 0 0 5
>20 F 50 0 0 0 0 0 0 0 00 0 0 0 0 0 0 0 0 0 0 0 TOTAL 0 0 0 0 LO 2 0 0 0 6 0 1 4 0 1 0 22 STA41LITY CLA55 4 STASILITT 4ASED ONt DELTA T SETMEEN 200 ~ 0 ANO 35 ~ 0 FEET ltlND HEASURED AT. 35 0 f EET
'ItlND THRESHOLD AT: 0 '5 HPH JOINT FREOUENCY OISTRLSUTION OF VINO SPEED ANO DIRECTION IN HOURS AT 3$ .00 FEET SPEED
{HPH) 8 NNE XE ENE E E58 SE SSE 5 ~ SSlt SV VSV V MNV NV NNV TOTAL eoe ooe 00 0 e 0 00 CAUI 0 ~ 76 ISO 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.510 2.50 2
3 'l
'1 4 ~ Slo 5 F 50 4050
'0 6,50 0
0 0
Oi 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 '
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 5 F 51
'1 0 0 I 0 2 0 0 0 0 0 0 0 0 3 4 8 F 50 4 ~ Sl LIOSO I 0 $ 4 I 1 0 2 0 0 0 0 19 11.$ 1 14.50 I I 10 I 0 0 3 I 0 I 3 I 0~ 26 L4.$ 1 20.50 0 3 0 0 I 0 0 0 2 0 0 0 8 0 0 L 0 0 0 0 3 0 0 0 0 0 4
>20 F 50 0 0 0 0 0 0 0000 00 00000 00000000 000000 0 0 0 0 0 0 0 0 00000 00000000 0 000000000000 0 00000 00 00000 00000 0 000 TOTAL L 3 2 2 20 5 3 2 3 6 4 2 3 3 1 0 58 B4
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I
PIGS Semi-Annual. Operating Report for January - June l.986 PYNCS JFOI 3SFT VINO YS DELTA T (200'5') FOR CTRL 1986 SITE LOENTIFIERI PYNCS OA'TA PERIOD EIAHLNEOI I/ I/86 3/31/86 FIRST OUARTER STAOILITT CLASS C STASILITY SASED ONI DELTA T SETVEEN 200 ~ 0 ANO 3$ ~ 0 FEET VINO HEASUREO AT: 35 ~ 0 FEET VINO THRESHOLD ATI 0 ~ 7$ HPH JOINT FREOUENCY DISTRISUTION OF VINO StEED AND DIRECTION IN HOURS AT 3S.OO FEET ooo ooo oo oo o oo SPEED (NPH) N NNE NE EXE K KSE oo o SE SSK SSV SV VSV V 'VNV NV NNV TOTAL.
o o o o oooo oo ooo oo oo o o oo oooo o o o 0 '6CALH I ~ 51o I
Ze50 50 0 0 '0 0 0 0 0 0 0 0 0 0
0 0 0 0 0 0 0 0 0 2 ~ 51 3~$0 0 0 0 0 0 0 0 0 0 0 5
6~
'l 3 ~ Sl l.$ 1o Slo8 8 ~ $1 4 ~ 50 S ~
F 50
~
50 50 LI~ $ 0 0
0 0
I 0
0 0
0 l
6 I 0 2
0 0
0 I
I 0 ~
0 I
I 3
0 I
0 I
0 0
0 0
. 0 0
0 0
12 13 26 4
0 0 4 0 0 0 Zl Ll~ Slo14 ~ $ 0 0 I 2' 0 0 0 0 0 Ll 14 ~ $ 1 20 ~ 50 0 0 0 0 0 0 0
>20 ~ 50 0 0 0 0 0 0 0 0 0 0 0
'eo o o o o TOTAL 2 3 8 20 12 2 $ 2 9 6 9 ll l 0 0 94 STASILLTT CLASS 0 STAOILITY CASED ONI DELTA T SETVEEN 200.0 ANO 35eO FEET HIND HEASUREO AT 3$ ~ 0 FEET VINO THRESHOLD ATS Oe76 NtH JOINT FREOUENCY OIS'TRISUTION OF VINO SPEED ANO DIRECTION LN HOURS AT 3$ F 00 FEET SPEED (NPH) N RNE NE ENK E ESE SE 55E 5 SSV SV VSV V oo o ooo oo o o ooooo ooooo oo oooe VNV NV NNV TOTAL oo ooo o oo o o oo CAIN 0 '6 I ~ 51 le50 Z ~ 50 2 2 I 2 0 3 0 I 0 I 0 0 I 16 I
8 9. 14 9 5 4 5 I I 9'2 2 ~ Sl 3 'lo ISO l.50 11 6
6 7
14 1$
13 10 10 10 12 10 12 17 ll 3
5 '"
I 8
2 5
I 131 5
Sl
'1 ST 50 F 50 2
I
$ 4 5 l2 7 7'
l 7 13 2
5 0 I '
2 0
0 I
3 0
101 48 5 6 6 I 4 I 0 I I 39 6.51 Ce50 8 ~ Sl 11.50 11.$ 1 14.50 14 ~ $ 1 20.$ 0 4
0 0
2 3
2 9
5 I
6 9
7 13 Ll 0
2 0
0 0 2
0 4
3 2
2 2
2 I
3 0
S 4
.0 0
I 0
I 0
'550 26 520 F 50 0
0 0
0 Z
0 2
0 0
0 0
0 I
0 0
0 3
0 I
0 0
0 2
0 0
0 0
0 Il0 o o o o oo eo oo oooooo oooooo oo ooo oooo oooo TOTAL Il 29 33 4570 49 42 o
23 42 42 oo 46 o o 30 ooo 14 1513 12 560 B5
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I I
PVNGS Semi-Annual Operating Report for January - June l986 PTNCS JFO$ 35FT VINO VS DELTA T (200' 3$ ') FOR Ol'Rl 1986 SITE IOENTIFIERI PVHCS DATA PERIOD EIAHINEOI I/ I/86 3/31/86 FIRST OUARTER STAOLLITT CLASS E STASILLTY EASED ONI DELTA T RETVEEN 200oO ANO LSD 0 FEET VINO NEASURED AT: 35 ' FEET VINO THRESHOLD ATI 0 7$ HPH JOINT FREOUENCT DISTRLOUTION OF VIND SPEED AND DIRECTION IN HOURS AT 35 F 00 FEET oo ee o o o o SPEED (HPH) N NNE XE ENE E ESK SE SSE 5 SSV SV VSV V VNV NV NNV TOTAL eeoc o ooeoooooeoeo CALH
'6$ loSO l. I 2
0 I
2 'l
~
3 Sl lo50
~
1 '0 3 '0 2
3 3
5 I
2 6
4 3
I 8
5 2 5
I 0
2 0
5 2
2 I
3 0
0 I
3 I
I 5
I 0
LS 5~
$1 31 4 ~ $1 5 ~ $0 Z 4 3 2 0 3 I 33 5 ~ 51 6 ~ Sl 6oSO doSO I I I l2 I 3 2 I 0 I tl 8 ~ Slel1 ~ $ 0 2 4 8 2 3 5 I 48 I
lloSL 14 $ 1 ll ~
20.50 SO 0
I 0
0 I t
0 0
6 0
2 3
5 2
3 I
3$
19
>20 F 50 2
0 2
0 0 0 0 I 0 0 9 0 0 0 0 0 0 0 1 e oooo o o o e o TOTAL 20 23 26 22 29 28 18 12 18 23 19 12 17 20 14 16 319 STAR ILITT CLASS STAOILLTT EASED ONI DELTA T OETVEEN 200.0 AND 35.0 FEET
'VINO HEASURKO AT$ 3S ~ 0 FEET VINO THRESHOLD AT ~ 0 ~ 7S HPN JOINT FRKOUENCY OIS'TRIRUTION OF VINO SPEED ANO DIRECTION IN NOURS AT 35.00 FKET e o e o o oe eoo eo ooe oe o o o SPEED (HPH) oooo N NNE o ooooo NE o oo o ENE oo E
eo KSK eo
'E o
5SE e oooooo 5
o 5SV SV o oo VSV oo V VNV NV NNV TOTAL CALH 0 '6 I ~ $ 1 ISO I ~ SO 4 2 2 I 0 0 I 0 I 1
14 2,51 13 13 7 5 8 I 0 0 3 73 F 50 16 9 7 5 3 2 2 3 5 7$
3 Sl ISO Ll 16 7 I 0 '
0 I 2 54 4 F 51 5.50 $ 8 5 2 2 I 2 I 39 5 ~ Sle 6 ~ SO Z 2 I I 2 0 I 6 ~ Sl 3 26 OoSO 3 2 2 0 0 .6 I 27 8 ~ $1 lloSO I 0 I I ll 51~
0 0
0 0 0
0 0
0
.I 0
8 I
>20 e
'0o ooooo 0
0 0
0 o oo 0
0 o
0 0
0 0
oeo oooo 0
0 ooooeo 0
0 o oo o eo o oooeoo 0
0 ooo o 0
0 e
0 0
o e o TOTAL 5$ $2 33 17 17 'L6 Ll 8 5 3 9 17 LS 14 Zt 23 318 B6
l l'
PVNGS Sead.-Annual Operating Report for January - June 1986 PYNCS JFDI 35FT VINO YS DELTA T (200'3$') FOR 4TRI 1966 SITE IOENTIFIKR: PYNCS DATA PERIOD ELAN)NEO) I/ I/86 3/il/86
~ ~~ FIRST 4UARTKR STABILITY CLASS 8 STABILITT SASED ON: DELTA T BETVEEN 240.0 ANO 3$ ~ 0 FEET VINO HEASURED AT: 3$ .0 FEET IIINO THRESNOLD AT'e7$ HPH JOINT FREOUENCT DISTRIBUTION OF HIND SPEED AND DIRECTION IN HOURS AT 3$ .00 FEET o o e o o e o oo e o o e o r oo oo ooo e o r o SPEED IHPN) 8 NNK NK ENK K ESE SK $ 5E 5 SSV SV VSV V VII NV XNV TOTAL e e o oo ooo r o oo o eo oee o o o e ee e eee o oo error r o e CAUI 3 0 el 6 I ZOIC~ $0 C 5 3 0 I I 0 2 0 0 3 5 3 35 I ~ Sl 250 42 33 19 2 3 5 5 8 19 18 178 Zosl 3.50 $7 62 26 2 0 3 4 I 2 7 14 38 228 ieSL 4.SO 48 57 23 0 0 0 I I 0 3 2$ 111 4oSI 5 ~ 50 21 29 I I 6 82
'l 9 0 0 2 0 0 5 5~ $1 Co $ 0 11 10 5 0 0 0 0 I ' 0
'04 0 ' 0 3 34 6 8 ~ 50 14 9 6 0 0 0 0 ~ 0 0 3 34 8 ~ Sl LL.SO 5 0 0 0 0 0 0 0 11 ll ~
L4esl Slo14 SO 50 I
0 5
2 0
0 I
0 0' 0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 4
0
>20e50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 e e oe er r
'IOTAL 24S 213 92 22 10 3 6 10 8 9 8 13 10 22 48 99 7$ 1 STABLLITT CLASS ALL STABILITY SASEO ON: DELTA T SETVEEN 200eO ANO 3S ~ 0 FEET ItIND HEASUREO AT: 35 ~ 0 FEET VINO TNRESHOLD AT: Oe75 HPH JOINT FREOIIENCY DLSTRISUTION OF VINO SPEED ANO DIRECTION IN HOURS AT 35 F 00 FEET SPEED (HPH) N NNE NE ENK E ESE SE SSE S SSV SV VSV V VNV NV NHV TOTAL eo e e eeeeeeee e eee eee eee ee e e oooo o oo r oo o CAUI 4
I
'651 I 2 SO 54 13 66 12 55 35 8
26 3
23 3
21 1$
1 2 10 4
14 0
15 3
II 2 4 36 8
32 81 397
~
Z.slo 3.50 3 ~ Sl 4 50 7$
60 86 82 47 i8 il 22 23 1$
1$
14 18 14 L5 7
17 IS
.24 11 9
L3 19 21 9
14 13 2
1$
14 7
22 9
48 31 45$
361 4+SI S.SO Z9 41 21 12 13 14 8 8 Li 12 9 6 4 10 LO 214 5~ Sle 6.SO 17 14 14 9 8 I 136 5.$ 1 ISO 8 ~ Sl 11,$ 0 23 6
20 6
1819 11 7
9 8
27 28 11 24 24 7
7 0
5 2
5 3
16 13 9
10 ll 6
9 10 5
1 9 16 8
5 I
5 5
5 6
205 1$ 4 Ilesl 14 ~ SO 2 20 I 0 0 I 5 5 5 15 .1 2 18 14esl ZO.SO 2 2 0 2 10 0 0 I I 0 10 2 I 2 0 0 33 PZO,SO 0 0 0 0 0 0 0 0 0 0 0 error0 r 4 0 0 I oo oo ooo oooo oo oooo oooo ooeooo oooo oorooooo ooo oo oo ooe oe e o r TOTAL 296 322 1$ '9 136 175 127 15 55 52 104 9$ $3 14 18 99 150 ZI SZ B7
l g
I I
PVNGS Semi-Annual Operating Report for January " June 1986 (200'35')
PVHCS JFDI 3SFT VINO SITE IOEHTIFIER: PYHCS DATA PERIOD EXANLHEOI '/
YS DELTA T 1/86 3/3'L/86 FOR OTRL 1986 FIRST OUARTER STAOILITT bASED OH: DELTA T bETVEEH 200+0 AHO 35.0 FEET HEASUREO AT: 35.0 FEET 'LHO VINO THRESHOLD AT: 0 F 75 HPH TOTAL HUNOER OF 08$ ERVATIONSI 2160 TOTAL HUHOER OF VALID OSSERVATIOHSI 21S2 TOTAL NURSER OF HISSIHC OOSKRVATIOHS: 8 PERCENT DATA RECOVERT FOR THIS PERLOOI 99+6 5 NEAN VLHD SPEED FOR THIS PERIOOI 4 ~ 8 HPH TOTAL NUNOER OF OSSKRYATIOHS VITH OACNUP DATA: 0 PKRCENTACE OCCURRENCE OF STASII.ITT CLASSKS C D. E F 8 I ~ 02 2 '0 4 '7 26 F 02 14.82 14.78 36 '9 OISTRlbUTLOH OF VINO DIRECTION YS STAOILITT N HHE NE ENE E ESE SE SSK 5 SSV V VNV NV HNV CALN 0 0 0 0 10 2 0 0 0 I 0 0 1 0 0 1 3 2 20 S 3 2 3 2 3 3 I 0 0 I 2 3 8 20 12 2 5 2 9 6 9 11 4 0 0 0 14 29 33 6$ 70 69 42 23 42 42 46 30 14 LS 13 12 I 20 23 26 22 29 28 18 12 18 23 19 12 LT 20 14 16 2
$5 205
$2 213 33 92 17 22 17.
10 8
3 5
6 10, 3
8 16 9
11 8
17 13
'LS 10 14 22 48'9 2'2 23 1 3
TOTAL 296 322 189 L36 176 127 76 55 82 104 98 83 74 78 99 150 7
PVNGS Semi-Annual Operating Report for January - June 1986 Table B2 JFDs of 35&oot Wind Versus Delta T April June 1986 B9
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PVNGS Semi-Annual Operating Report for January - June 1986 PTNCS JFDE 35FT VINO TS DELTA T (200'3$') FOR OTRZ 1946 SITE IOENTIFIERE PYNCS DATA PERIOD EIAHINEO5 6/ I/86 4/30/86 SECOND OUARTER STA41LITT CLASS A STAblLITT 4ASED ONE DELTA T bKTVEEN ZOO ~ 0 ANO 15 ~ 0 FEET VINO HEASUREO AT: 3$ .0 FEET
'IIINO THRESHOLD ATE 0 '5 HPN JOINT FREOUENCT DISTRISUTION OF IIIND SPEED ANO DIRECTION IN HOURS AT 35.00 FEET SPEED (HPH) N NNE NK KNE E ESE 5E SSE 5 SSV SV VSV V VNV NV NNV, TOTAL'ALN 0
0 '4~ I ~ 50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1$ 1-2 ~ 50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 ~ SI~ 3 ~ 50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 ~ $1 6 ~ $0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6 ~ SI S ~ $ 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 I 0 I 5~ Sl- 6 ~ SO 0 0 0 0 0 0 0 0 0 I 0 I 0 0 0 0 2 6 ~ $ 1- 8 ~ 50 0 0 0 0 0 0 2 2 7 12 14 2 0 2 I 0 42 8~ Sl-ll. $ 0 0 0 3 0 5' I I 1 27 $1 Zl 0 0 123 II . 51-14 o 50 0 0 I 0 2 0 0 0 3 9 25 4 12 6 6 I 69 Id F 51-20 F 50 I
~K 520.50 0
0 0
0 0 0
0 0
0 0
0 0
0 0
0 0
0 rr 10 0
23 6
TlV 0
1 6
I 6
I fV 0
0 0
0 m 9 STASILITT CLASS 8 STAblLITT SASEO ONE DELTA T 4ETVEEN ZOO.O AND 1$ ~ 0 AT) 1$ .0 FEET FEEl'INO HEASUREO VINO THRE5HOLO ATE Oe7$ NPII JOINT FREOUENCT OISTRISU'TION OF HIND SPEED ANO DIRECTION IN HOURS AT 35 ~ OD FEET SPEED (HPH) N NNE NE ENE K ESK SK SSE S SSV SV VSV V ItNV NV NNV TOTAL 0%
CALH 0 I
'050 0 0 0 0
'.76
~ 0 0 0 0 - 0 0 0 0 0 0 0 I ~ $1 2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 ~ Sl 3. SO 0 0 0 0 0 0 0 D 0 0 0 0 0 0 0 3 ~ Sl 4 SO 0 0 0 0 0 0 0 0 0 0 0 0 0 I 2 6 F 51 I I I I I I 6 'l 5 F 51 8 ~ Sl 5 F 50 F 50 8,SO 11.$ 0 0
0 0
0 0
0 0
0 I
0 0
I 0
I I
I 0
6 0
I 0
8 I
4 14 11 6
15 12 0
'I 2
5 0
I 2
0 0
I 0
1 0
19 28 4$
61 II SIAIA 50 2 1 1
~
16ISI 20 '0 0 0 0 0 2 0 0 0 0 9 0 I I 0 17
~R 0 0 0 0 0 0 0 0 0 5 0 2 0 I 9
>ZD.SO 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 B10
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I
PVNGS Semi-Annual Operating Report for January - June 1986 PYNCS JFOs 3SFT VINO YS DELTA T (200'5') FOR OTR2 1986
$ !TE LOENTIFIER: PYNCS DATA PERIOD EIAHINEDg l/ I/86 6/30/86 SECOND OUARTER STAR ILITT CLASS C STAKILITT SASED ON: DELTA T SETVEEN 200 ~ 0 ANO 3$ .0 FEET VINO NEASURED AT: 35eO FKET VINO TNRESHOLD AT? 0 ~ 75 HPH JOINT FREOUENCT OISTRICUTION Of VINO SPEED ANO DIRECTION IN HOURS AT 3$ ~ 00 FEET SPEED (HPH) N NNE NE ENE E ESE SE SSE 5 5SV SV VSV V VNV NV NNV TOTAL CALH 0 0 F 76~ I ~ 50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 I ~ 51~ 2,50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 ~ SI~ 3 ~ 50 0 I 0 0 0 0 0 I 0 0 0 0 0 0 0 2 3 ~ SI~ 4 ~ 50 0 0 0 0 3 2 2 0 4 3 I I 0 0 0 16 4.51 S.SO 2 I I 0 I LS 10 9 9 5 I I I "
0 60 5 ~ 51 6 ~ 50 0 0 0 I 2 6~ 8 11 8 4 0 S 2 1 I 52 F 51 8 F 50 0 I 0 I 3. I 0 5 9 LL 7 I 1 0 44 l.
8 ~ $ 1 L SO 0 0 0 0 I 3 0 0 I 2 9 5 I 0 25 LL ~ $ 1 14.SO L4+SL 20 ISO 0
0 0
0 0
0 0
0 2
0 1
0 0
0 0
0 0
0 I
I l3 4 0
0 0
2 0
2 0
0 13 7
>20.50 TUTKL 0 0 0 0 0 ZK'K' 0 0 0 0 0 2 ZZ 0 0 0 2 STADILITT CLASS 0
~ Sl'ACILITT CASED ON: DELTA T SETVEEN 200 ~ 0 ANO 3$ .0 fEET VINO HEASURED AT: 35 V!NO TNRESHOLD ATL 0+75 NPH
' FEET JOINT FREOUENCT OISTRIKUTION OF VINO SPEED ANO DIRECTION IN HOURS AT 3$ ,00 FEET SPEED (HPH) N NNE NE ENE K ESE SE SSE 5 SSV SV VSV V VNV NV NNV TOTAL 0
CALH 0 Oo76 L.SO 0 I 0 0 I 0 0 I 0 0 0 0 3 I ~ 51 I I I 2
3 'l
'1 3ISO 4.SI 2 ~ 50
'0 ISO 0
I 2
I I
2 0
5 0
I 0
I 3
I 8
6 I
7 9
2 2
5 10 7
0 8
7 I
10 6,
I 5
7 2
0 0 I
0 15 55 67 5 ~ Sl do $ 0 0 I 2 I 2 0 2 5 4 5 0 ~
34 6 ~ 51 ~ ISO 0 0 I 0 I ll8 ~ Sl ll ~
14.50 50 I I 0
0 3
I 2
2 I 3
0 I 0 2
4 18 6 0 0
34
~ SL lieSL 20e50 0 0 0 0 I 0 0 0 0 I 16 0 31 0 2 0 0 0 0 0 0 0 14 0 28
>20.50 0 0 0 I I I
~)T)ir 1 0 0 Z)r 0 0 ZK 2
ZV
I l
I
pVNGS Semi-Annual Operating Report for January - -June l986 PTNCS JFO: 3SFT VINO VS DELTA 'I (200'e35') FOR OTR2 1986 SITE 10'EHTIFIER. PYMCS DATA PERIOD EZAHINKO'/ I/86 e 6/30/86 SECOND OUARTER STASILITT CLASS E STASILITT CASED ON: DELTA T SETVEEN 200 ' ANO 35 ~ 0 FEET VINO HEASURED AT: 35 ' FEET VINO THRESHOLD ATc 0 ~ 1$ NPH JOIN'I FREDUENCT DISTRISUTION OF VINO SPEED ANO DIRECTION IN HOURS AT 35.00 FEET 5PEED
{HPH) N NNE NE ENE K ESE SE SSK 5 SSV SV VSV V VNV NV NNV TOTAL oe o oooo eeo CAUI 0 Ool6 I ~ Slo I ~ 50 t 50 I
0 0
3 t 0 3
0 0
0 I
0 I
0 0
0 I
0 2
0 0
0 3
0 3
0 0
3 22 2 ~ 51o 3 ~ 50 0 I I I 2 0 I I I 3 I 26 3 ~ Sl F 50 2 3 6 0 0 2 2 0 I 5 2 0 I 30 4oSI S ~ 50 2 I I 0 t 0 2 3 5 3 I 0 0 23 5 '1 6SI 6 50 850 I
I 0
0 0
I 0
2 I
I I
I I
I 2
2 e
1$
5 5 18 5
14 4
6 0
3 0
I 26 TO SoSI 11 ~ 50 11 ~ $ 1 14 ~ 50 3
I 0
I 0
0 0 3 3
t I 0
2 2
22 20 3$
32 25 12 3
I 2
I I 105 78 14.51 20.50 I 0 0 0 2 0 0 0 2 5 2 0 16
~CK >20.50 IT, 0 0 7
0
?T 0 0 0 0 0 IY 0
nK 0 0 EIr 0 0 0 0.
STAOILITT CLASS F STASILITT SA5ED ON> DELTA T SETVEEN 200.0 ANO 35.0 FEET RIND HEASURED AT: 3S 0 FEET VINO THRESHOLD AT: Oo7$ NPH JOINT FREOUENCT DISTRISUTION OF VINO $ PEEO ANO OIRKCTION 'IN HOURS AT 35 ~ 00 FEET 5PEEO
{HPH) N NNE NE ENE E ESE SE 5SE 5 SSV SV V5V V VNV NV NNV TOTAI.
CAUI 0 0.26- 1.$ 0 0 2 0 0 I I 0 0 0 0 0 0 0 0 4
'1 '0 0
ICOSI 2 io$ 0 6 0 0 0 1 I
0 0 4
0 0 2 I 2 2 5 tl 60 2
3 ~ 51o 4 4 ~ 51 5
'0
'0 5
3 I I
3 2
0 0
2 I
0 0 I
3 0
I 2
1 0
'2 I 9 6
3 6
3 8 3 t3 5
3 1
39 30 5o51 6.SO 0 I 0 0 0 0 2 ' 34 6.51 Se 8.50 Sl" I l. 50 1
0 0 I 0
0 I
0 0
0 I
I 2
0 0
0 2
0 1
ll 1$
33 23 6 6 18 10 13 3
6 1
2 1
96 51 11 ~ $ 1 14.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 14 e Sl 20. 50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 h Tr B12
5 I
PVNGS Semi-Annual Operating Report for January - June 1986 PYNCS JFDt lSFT VINO YS OELZA T (200e 3$ ') FOR Ol'R2 1984 SITE LOENTIFLERt PYNCS DATA PERIOD EIAHLNEOt 4/ I/86 6/30/bd SECOND OUARTER STASILITT CLASS C STASLLITY SASED ONt DELTA T SEZVEEN 200 ~ 0 ANO 3$ ~ 0 FEET VIND NEASURED ATt 3S ~ 0 FEET VINO TNRESNOLO ATt 0 F 75 HPH JOINT FREOIIENCZ DISTRlbUTIOII OF VINO SPEED ANO DIRECTION LN NOIIRS AT 35 F 00 FEET SPEED (NPN) N NNE NET ENE E ESE $5 SSE 5 $ 5M SM MSV V VNM NV XNM TOTAL CALH I 0 ~ 76e I ~ $ 0 I 2 0 0 0 0 0 I 0 0 0 I 0 0 1 1 7 I ~ $ 1 2 ~ 50 10 0 I 3 0 0 0 2 I 10 44 2 '1 le $ 1 3.50 4e50 5
22 33 28 24 7
9 12 5
7 0
3 0
2 0
0 I
I 2 2 l2 I 0
3 2
1 2
7 3
1 2
6 27 119 107 4 ~ 51e 5 ~ 50 20 15 4 2 I 0 0 0 0 0 3 1 3 1 0 4 56 S ~ Sl- 6eSO 4 5 I I 0 0 0 0 0 0 I 2 I 0 3 0 18 4.$ 1 8.$ 0 6 6 3 0 I 0 0 I I I 3 I 0 1 0 I ?5 8 ~ $ 1 11 ~ 50 0 0 0 0 0 0 0 0 2 0 0 0 0 0 0 6 11 ~ $1 ~ 14,50 0 0 0 I 0 0 0 0 0 0 0 0 0 0 0 0 1
- 14. $ 1-20. SO 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0
>20.$ 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 K ET 5'ZAbILITY CLASS ALL STAblLITT SASED Okt DELTA T CETMEEN 200 ~ 0 ANO ~ 3$ ~ 0 FEET ItlNO HEASURED ATt lb ~ 0 F EET VINO TIIRESHOLD ATt 0 ~ 75 NPH JOIIII'REOUENCZ OISTRlbUZLON OF VINO SPEED ANO DIRECTION IN IIOURS AT 35.00 FEET SPEED (NPH) N NNE NE ENE 5 ESE SE SSE 5 SSII SM VSV V 'MNV NM NNV TOTAL CALH I 0 ~ 76~ I~ $ 0 2 5 2 0 2 I 0 2 0 0 0 I 0 0 I 1 17 Ie51 2 ~ Sl Z.SO leSO 9
28 1$
37 19 10 1$
I 5 I 18 I
12 4
ll 6 5 Il 16 10 32 102 262 3~
4 'ISl- 4 '0 5 F 50 40 lb 30 19 17 Zl 11 LO 4
10 4
10 14 4
8 14 27 14 21 18 24 14 14 19 21 Zb 14 13 1$
14 9
10 4
6 8
5 15 4
261 233 Se51 ISO 6 6 7 11 23 Zl 23 26 23 16 8 6 5 194 6eble Se50 7 10 5 8 b 10 . Ll 12 28 48 94 53 27 15 10 8 376 8.$ 1 II.SO 6 I 12 I 8 83 148 73 21 16 7 5 401 11.$ 1 L4.$ 0 'L I I 3 'LO 3 0 0 31 85 32 14 11 9 209 14 F 51 lb.50 I 2 I 0 5 0 0 0 0 13 50 10 6 10 2 104
%20.50 0 I et m0 1 R
1 0 0 0 0 7 1 E)f 0 1 nTT
I PVNGS Seed.-Annual Operating Report for .January - June 1986 PVHCS JFOI 3SFT NLNO VS DELTA T (200'$ ') FOR OTR2 1986 SITE IOEHTIFLER: PVNCS DATA PERIOD EXAHINEOI 4/ 1/86 6/30/86 SECOND CUARTER STASILITY 4ASED ON: DELTA T 4ETMEEN 200.0 AHO 35.0 FEET VINO HEASURED AT: 35 ' FEET VINO THRESHOLD AT: 0 '5 HPH TOTAL NUH4ER OF 04$ ERVATIOHSR 2144
'TOTAL HUHbER OF VALID OSSERVATIONSI 2177 TOTAL NUH4ER OF HISSING OSSERVATLONS: 7 PERCENT DATA RECOVERT FOR THIS PERIOOI 99 ~ 7 5 NEAR MIND SPEED FOR THIS PERIOD: 7.4 HPH TOTAL NUH4ER OF ObSERVATIONS 'MITH dACKUP DATA: 0 PERCENTACE OCCURRENCE OF STASILLTY CLASSES E F 13 '2 8 ~ 31 10.1$ 16 58 Lb+33 15.66 17.64 DISTRLSUTLOH OF VINO DIRECTION YS STASLLITT N NNE NE ENE E ESE SE SSE 5 SSM SU USM K UNU N'N NNM CALH 0 0 5 0 7 2 3 3 13 59 119 31 22 19 6 I I 1 1 2 6 7 8 9 1$ 34 50 19 8 8 3 6 2 3 1 2 ~ 12 16 2$ 27 31 31 29 22 5 7 7 1 5 10 Lt 10 28 Zl 29 31 26 29 $2 3$ 12 10 15 3 12 17, 9 1$
15 9
8 4
9 6
2 6
ll9 12 8
72 36 106 82 68 47 26 42 17 20 12 17 6
16 91 91 4L 16 5 3 5 7 10 8 12 14 7 17 $2 TOTAL LZS 132 44 42 76 64 77 9$ 115 271 476 237 129 88 77 Bl4
l I
PVNGS Semi-Annual Operating Report for January - June 1986 Table B3 JFDs of 35Woot Wind Versus Delta T January June 1986
I rl PVNGS Seali-Annual Operating Report for January - June 1986 PYNCS JFO: 35FT VINO YS DELTA T (200'~3$ ') FOR JANUART JUNE 1986 SITE IDENTIFIER: PYNCS DATA PERIOD EZAHINEDl 'L/ I/86 6/30/86 FIRST SEHIANNUAL ~~~
STASILITT CLASS A STASILLTY SASEO ON) DELTA T SETVEEN t00 ~ 0 AND 35.0 fEET VINO HEASURED AT: 3$ ~ 0 FEET VINO THRESHOLD ATl 0 '$ HPH JOINT fREDUENCT OISTRISUTION OF VINO SPEED ANO DIRECTION IN HOURS AT 35 ~ 00 FEET 5FEED
{HPH) N NNE NE ENE E ESE 5E 5SE 5 55V Slt VSV V VNV NV NNV TOTAL CALH 0 '6~ I 50 ~ 0 0 0 0 0 0 0 0 0 0 0
0 I ~ SL~ te$ 0 0 0 0 0 0 0 0 0 0 0 0 2 ~ Sl 3+$ 0 0 0 0 0 0 0 0 0 0 0 0 3 ~ SL~ F 50 4 'L~ 5 5 ~ SL~ do50
'0 ~
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 I
0 0
0 1
6.51 8 ~ $ 0 0 0 0 I 0 I ~ 0
'20 . 0 0 2 0 I 2 12 14 2 0 'L 0 43 8 ~ Sl 11 ~ 50 I 14 'l 11 ~ $ 1-14 ~ 50 20o50
~20 ISO 0
0 0
0 e oo o e ooo 0
0 0
o 0
0 27 10 10 0
$1 26 26 6
21 6
0 I
6 15 4
I 4
6 4
Io I
0 0
0 I
0 0
130 78 49 9
o o 0 em oo o TOTAL 0 0 5 0 17 4 3 3 13 40 123 31 26 'L9 7 1 312 STAS ILLTY CLA55 8 STASILITY SASED ON: OEI.TA T SETVEEN 200+0 ANO 35+0 FEET
'VINO NEA5URED ATl 3$ ~ 0 FEET VINO THRESHOLD AT: 0 ~ 7$ HPH JOINI' REOIIENCT OLSTRLSUTION OF ltlNO SPEED AND DIRECTION IN HOURS AT 3$ ~ 00 FEET SPEED (HPH) N NNE NE ENE E $ 5E SE 55E $ 5$ V Slt VSV V ltNlt NV NNV TO'TAL 0 0 0 o eo CALH 0.76 0 1.50 0 0 0 0 0 0 0 0 0 .0 0 0 1.$ 1 2.$ 0 0 0 0 0 0 0 0 0 0 0 0 0 2.51 3.50 0 0 ~ 0 0 0 0 0 0 0 0 0 0 4 'I~' '0 3 ~ SL
$ .$ 1 4~ $0 5 '0 0 I
0 0
0 L
0 I
0 I
0 4
0 I
0 0 I
0 0 0
2 19 0 0 0 2 0 3 4 5 6 6 0 31 6 ~$1 8~$0 I 2 I 6 I 8 ~ Sl LI ~ $ 0 Ll~ SL~L4 ~ 50 0 I I ll5 LO I 0 10 I
I 17 14 1$
L3. 2 84 6$
14 'L 20.$ 0 i20+50 0
0 0
0 0
0 0
0 I
0 0
0 0
0 0 0 0
0 9
8 1
0 25 13 0 0 0 0 0 0 0 0 0 TOTAL t 4 3 4 26 12 ll 11 2'L 38 $4 Zl ll ll 4 6 239 B16
I I
PVNGS Semi-Annual Operating Report for January - June 1986 PTNCS JFD: 35FT VINO TS DELTA T (200'S') FOR JANUART JUNE 1986 SITE IOEHTIFIER: PYNSS DATA PERIOD EIAHINEDc I/ I/86 6/30/86 FIRST SENIANNUAL STASILITT CLASS C STASILITT SASKD ONs DELTA T SETVEEN 200.0 ANO 35.0 FEFT MIND HEASURED AT: 35+0 FEET VINO THRESHOLD ATS 0 ~ 75 HPH JOIN'7 FREOUENCT OISTRISUTION OF VINO SPEED ANO DIRECTION IN HOURS AT 35 F 00 FEET 5PEEO (HPH) N NNE NE ENE E ESE SE SSE 5 $ 5V SV VSV V VNV NV NNM TOTAL CALN 0 0 ~ 76 I ~ 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 ~ Sl 3 ~ 50 0 0 I 0 0 0 0 0 0 2 3 ~ Sle 4 ~ 50 2 0 3 I I 20 4eSI 5 ~ Sl 5 ~ 50 6 ~ 50 6
10 17 8
ll 12 10 9
10 5
6 0 3 I
0 I
3 .
0 I
I 72 65 6~ $1 8 ~ SO 5 0 7 9 14 8 2 I 70 8 ~$1 lloSI 11 ~ SO 14 ~ SO 4,
I '
0 0 0 0 I 6 13 4
4 5
0 2
2 0
49 24 I4ISI 20,$ 0 0 0 I 0 I 3 0 I 2 11
>20.50 0 0 0 0 0 0 0 0 0 2 o o e oo oo o o e oo TOTAL 3 5 4 10 32 28 27 3Z 33 40 3S 31 16 ll 7 I 315 STAR I LITT CLASS D STASILITT SASED ONS DELTA T SETVEEN 200 ~ 0 ANO 3$ on FKET VINO HEASURED ATP 35.0 FKET VINO THRESHOLD AT. 0 ~ 7S NPH JOINT FREOUENCT OISTRISUTIDN OF MIND SPEED AHO DIRECTION IN HOURS AT 3$ .00 FEET oo oo o o eoo oo o o o o oo ooooo o o o oooo o SPEED (HPH) N NNE NE ENE ' ESE SK 55K 5 5$ V SV VSV 'V eo VNV NV NNV TOTAL o o o ooooo o oooo ooo ooo o ee oeoeo ooo ooo ooooo o o oo o CALN 0.76 ISO I I 0 2 0 3 2 2 0 I I I 1.51 2 '1 Z.SO F 50 8
I 12 10 9 8 1$
10 21 15 17 ll 17 5
16 6
ld 22 5
13 5
0 4
12 I
6 0
2 2
0 9
4 5
2 19 107 IS6 3 ~ Sl 4 ~ 50 2 8 7 18 16 19 14 I 4.SI 5.$ lo 5~ $0 6 ~ 50 2
3 2
2 4
6 6
6 7
8 7
6 ll ZO 4
8 5
17 13 8 6 19 ll 12 7
7 ~ I 0
2 I
0 0
3 3
0 I
168 92 73 6.$ 1o 8 ~ SO '2 4 2 12 8 14 I 8 ~ 51 lls51 11,$ 0 14.SO I
0 I
0 3 6 I
ll8 12 0
5 0
0 2
2 0
2 0 5 10 21 18 10 10 8
6 6
4 7
7 2
I 0
I 0
84 89
%7 I4ISlo20+50 0 2 0 2 5 0 0 0 I 0 17 7 0 2 0 39
>20o$ 0 0 oooo I 0 0 I 0 0 0 0 2 I 0 0 0 0 I 5 e eeeeeeee e eeeoeoeoe eee oeeeeoee e ee oooo ooe oee eo TOTAL 19 39 45 75 98 90 71 $4 68 71 IZS dd 26 ZS 28 15 921 B17
I
?VNGS Semi-An'nual Operating Report for January - June 1986 PYNCS JFD: 3$ FT VINO YS DELTA T (200'$ ') FOR JANUARY JUNE 1986 SITE IDENTIFIER) PYNCS DATA PERIOD EXAHINED: I/ I/46 6/30/86 o~~ FIRST SEHIANNUAL ~~~
STASILLTY CLASS E STASILITT SASED ONL OKLTA T SETVEEII 200.0 ANO 3$ .0 FEET
'MLNO NEASURED AT) 3S.O FEET VINO 'THRESHOLD ATL 0 ~ 7$ HPH JOINT FREOUENCY OLSTRISUTION.OF MIND SPEED ANO OLRKCTION LN HOURS AT 3S.OO fEET SPEED (HPH) N NNE NK ENE E ESE SK SSE 5 SSV SV MSV 'M MNV NV NNV TOTAL CALH 2 0 ~ 74 I 50
~ 2 0 0 I I 0 I 0 18 I ~ $1 250 5 4 d 3 I 2 8 4 76 2 ~ 51o 3 ~ 50 3 3 2 6 d 4 3 77 3 ~ Sl 4 ~ 50 d 4 3 8 3 0 3 61 4 ~ $1 5~$0 2 6 7 d 3 I I 56 5 ~ Slo 6 ~ SO deSL 8 ~ SO 2
3 5 ~
19 7 8 20 5
16 I I 47 118 8 ~ Sl 11.50 11.$ 1 14 ~ $ 0 ll3 2 2
28 20 37 34 t1 8
11 5 2
140 97 13 2 2 3 L4.51 20 F 50 0 0 2 6 4 0 0 I 25
>20 F 50 0 0 0 0 0 0 0 ,1 1 eo o ooo o o o o o TOTAL 32 32 41 30 43 37 20 23 30 9S LZS . 80 43 31 26 "
tt 118 5TAblLITT CLASS F STAblLLTT SASEO ON: DELTA T 4ETVEEN 200 ~ 0 ANO 3$ .0 fEET MIND HEA5VRED AT: 35.0 FEET VIND THRESHOLD ATL 0 '5 llPH JOINT f REDUENCT OISTRlbUTION OF MIND SPKKO ANO DIRECTION IN HOURS AT 3$ ~ 00 FEET SPEED LHPH) H NNE NE KNK E E55 5E 5SE 5 5SV SM VSV V MNV NV NNV TOTAL o oo oo o o CALH 1 0 ~ 16 1.50 4 4 L I 0 0 0 I 0 18 I rdl 2.50 17 17 7 1510 0 0 2 0 7 94 4 'l'1 2 ~ 51 3r$ 1
$ .$ 1 3 ~ 50 4.SO S.SO 6.50 21 14 9
L7 9
2 10 1
2 5
0 2
I 2
I, 5
2 4
2 4
6 6
Li 7
6 4
8 9
11 12 5
135 93 69 60 4 ISO $ 3 2 0 0 17 3$ 19 1$ 123 8.$ 1 11.50 11 ~ 51 14.$ 0 I
0 0 I I 0
0 0
0 0
I 0
1$
0 24 0
ll0 0 65 I
LdoSL 20.50 0 0 0 0 0 0 0 0 0 0 0
>20r50 0 0 0 0 0 0 0 0 0 0 r oooo o oo oooooo oo o roooo roo error ooo or TOTAL 1'I 10 o
42 21 21 Ld 11 12 o
17 o
52 93 ooo oo 64 o
$7 34 39 39 '59 B18
I I
I
PVNGS Semi-Annual Operating Report, for January - June 1986 PYNCS JFO! 3SFT VIHD YS DELTA 7 (200'5') FOR JANUARY JUNE 1986 SITE IDENTIFIERt PYHOS DATA PERIOD EIAHINEOI I/ I/86 6/30/86
~I~ FIR5T SEHIAXNUAL ~ oe STASILITT CLASS 6 STASILITT SASEO ONt DELTA T SETVEEN '100 ~ 0 AND SS ~ 0 FEET VINO HEASURED ATI 15
'ltlNO THRESHOLD AYI 0 '5' FEET HPH JOINT FREOUENCY DI5TRlbltTION OF VINO SPEED AND DIRECTION IN HOURS AT 3$ .00 FEET 5PEED (NPH) 8 NNE NE ENE E '5E SE SSE 5 SSV Qt VSV V VHV NV NNV TOTAL CALII 0 ~ Td>> I ~ 50 7 8 3 2 0 I I 2 0 0 3 7 43 le51o toSO 47 40 29 8 3 5 3 8 6 6 9 ZI 28 222 2 ~ $ 1 le $ 0 79 90 SS 12 2 3 5 5 6 10 20 65 347 3 ~$1 do 50 sl 81 35 9 3 0 I 3 2 7 4 9 37 Z78 4 Sle 5 ~ 50 lb. '138
'l 41 44 15 4 2 0 0 0 0 2 6 5 5 ~ Sl 6 ~ SO 15 1$ 6 2 0 0 0 I . 0 3 I 0 3 3 $2 6 ISO 20 15 9 0 I 0 0 I I 2 0 I 0 59 8 ~ 51 lle$ 0 I 0 17
'l 5 9 0 0 D 0 0 0 2 0 0 0 11.$ 1 14a50 I 2 I 1 0 0 0 0 0 0 D 0 0 0 5 14 20o50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0
>20.50 0 0 0 0 0 /o 0 0 0 0 0 0 0 0 0 0 o o oo oo ooe oooo oo o oooo oo o o e e oe eoe o oo o o o o TOTAL 29d, l04 133 lb 1$ d 10 15 15 19 16 2$ t4 29 65 ISI 1165 STADILITT CLASS ALL STASILITY VINO SASEO ON: DELTA T NEA5IIRED AT: lS 0 FEET SETVEEN 200 ' ANO 35 ' FEET
'HIND THRESHDLD ATI 0 ~ 7$ IIPH JOINT FREOUENCT 01$ 'TRISUTION OF VINO SPEED AND DIRKCTION IN HOURS AT lb.00 FEET oo 4 SPEED (HFH) N NNK NE ENK E ESK SE SSE $ 5$ V SV VSV V VNV NV NHV TOTAI.
ooo o o o ooo oooo oo CALH 8 I SO
'l IT 0 76 1$ 10 4 5 4 4 0 3 5 2 4 9 5 98 I $1 2 $0 75 70 54 29 24 25 20 11 15 19 13 1$ 20 IO 47 42 499 2 ISO 3 ~ Sle 4 F 50 106 100 I tl 112
. 64 59 41 32 38 2$
25 tb 26
'tb 33 tl 29 31 ib ZS 22 40 32 2$
28 16 Z4 13 38 17 80 52 747 622
$ .50 ld lb IS 447 4 F 51 5 ~ 51 6 ~ SI 6 ~ 50 8.SO
~
59 23 60 20 io 32 1$
23 12 27 19 tO 35 ZD 18 34 3$
18 18 29 27 lb 37 30 3l 31 31 84 352962
'106 19 13 22 34 10 23 9 11 11 10 13 330 581 8 ~ $ 1 11.$ 0 11 ~ 5le14 ~ $0 10 3
12 5
10 5
9 6
40 io 33 4
I 0
6 0
ll6 95 36 159 91 83 37 io 30 32 18 12 12 11 555 287 14 ~ SI 20 ~ $ 0 2 15 0 0 I I 13 db 12 7 12 4 t 137
>20 ~ 50 o e o 0 1 0 o
0 I o o 0
oo 0
ooooo 0 0 2 7 I I 0 2 18 e o TOTAL 42 ~ 4$ 4 t73 178 tSZ 191 153 1$ 0 197 l75 S74 320 t03 ld6 17d 235 4329 B19
I I
I
PVNGS Semi-Annual Operating Report for January - June 1986 PVNOS JFO: 35FT MIND VS DELTA T (200'5') FOR JANUARY JUNE 1986 SITE IDENTIFIER: PVNOS DATA PERIOD EXAXINED: I/ I/86 6/30/86 FIRST SEHIANNUAL i~~
STABILITT BASED OH: DELTA T BETMEEN 200+0 AND 3S.O FEET MIND HEASURED AT: 3$ .0 FEET MIND THRESHOLD AT: 0 ~ 75 NPH TOTAI. NUHSER OF OBSERVATIONS: 4344 TOTAL NUNBER Of VALID.OBSERVATIONS: 4329 TOTAL NUMBER OF HISSIHB OBSERVATIONSe 1$
PERCENT DATA RECOVERY FOR TIIIS PER100$ 99 ~ 7 S HEAR MIHO SPEED fOR THIS PERIOD) 6.1 HPH TOTAL NUXBER OF OBSERVATIONS MITH SACYUP DATA: O PERCENTAEE OCCURRENCE OF STABILITT CLASSES 8 C 0 E F 6 7.21 $ .52 . 7.28 2lo28 Ido$ 9 ~ ISI22 26.91 OISTRlbUTION OF MIND DIRECTION YS STABILITT H NHE NE ENE E ESE SE SSE 5 SSM SM MSM M MNM NM NHM CALX 17 4 3 13 60 123 31, 26 19 7 I 0 0
2 0 5 0 26 32 12 28 Il3 27 11 32 21 33 38 40 Si 35 21 31 11 16 11 11 4
7 6
I 0
0 S 4 10 39 45 75 98 90 71 $4 68 71 128 68 26 2$ 28 15 I 19 32 72 32 70 il 42 30 21 43 21 37 14 20 ll
'23 12 30 17 95 52 125 93 80 64 43 57 37 34 26 39 22 39 2
I 296 304 133 38 15 6 10 IS 15 19 16 25 24 29 65 151 4 TOTAL 424 454 273 178 2$ 2 191 1$ 3 150 197 37S $ 74 320 203 166 176 235 8 B20
I I
1 I
PVNGS Semi-Annual Operating Report for January June 1986 Table B4 JFDs of 35&oot Wind Versus Delta T January torch 1986 Batch Releases B21
I PVNGS Semi-Annual Operating Report for January - June l986 PYNCS JFO: 35FT VINO YS DELTA t (200'o3$ ') FOR OTRI 1986 SAtCH RELEASES SITE IDEHTIFIERl PYNOS DATA PERIOD EZAHIHEOl I/ I/66 - 3/31/66 F IRST OUARTER STASILITT CLASS A STARILITT SASED ON: DELTA 7 A'tl SETMEEN 200 ' ANO 3' FEET VIND HEASURED 3$ .0 FEET VINO THRESHOLD At: 0.75 NPH JDINt FREOUENCY OISTRISUTION OF VINO SPEED AND DIRECTION IN HOURS AT 3$ .00 FEKT oo SPEED IHPH) ~
N NNE NE ENE E ESE $E SSE 5 SSM SV VSM V VNV NV NHV TOTAL oo o CAUI 0 76'I ~ 50 0 0 0 1.51 Z. 50 0 0 0 2 ~ Slo 3.SO 0 0 0 4
5
'l-3.51 4.50
'1 $ .$ 0 F 50 0
0 0
0 0
0 0
0 0
6.'Sl- b'.SO 0 0 0 6 Sl 11. 50 0 0
- 11. 51 14. 50 1 0
- 14. 51 lb. 50 2 0 0~
>20,50 0 0 0 o
TOTAL 0 0 0 0 10 I 0 0 0 I 4 0 4 21 0 1 0 STAb!LITY CLASS b STAOILITY SASED ON: DELTA T SETVEEN 200 MIND MEASURED Atl 3$ .0 FEET
' ANO 35 ~ 0 FEET VINO 'THRESHOLD Atl 0 ~ TS HPH JOINT FREDUEHCT OISTRIRU'tlON OF VINO SPEED ANO DIRECTION IN HOURS AT 35 F 00 FEET ooo o SPEED (HPH) N NNE NK KNK E ESE SK SSK 5 SSM SV VSV M MNV NV HHV tOTAL ooo ooo ~ o o CALH 0 '6 losl ISO 0 0 0 0 0 0 0 0 0
0 3
4
'l'l-2 ~ Sl Z.SO ISO 4esb ISO 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 .
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
SeSI ISO 0 0 I 0 0 0 0 0 6.51- 6.50 I I 5 2 I 3
R.SI 11 ~ 50 O 0 0 19 11.51 14.SO 0 0 10 0 I I 0 22 Isesl lb.50 0 0 3 I 0 0 0 0 7
>20.$ 0 0 0 I 0 0 0 0 0 0 0 0 0 0 0 0 ooooo oo ooooo oo o o o ~
TOTAL I I I 2 20 5 3 2 3 4 4 2 3 3 I 0 55 B22
I I
I I
I I
?VNGS Semi-Annual Operating Report for January - June 1986 PVNSS 3FO: 35FT VIND VS DELTA T I'200'5') FOR OTRI 1986 OATCN RELEASES SiTE IDENTIFIER: PVNCS DATA PERIOD KIAHINEO: I/ I/86 3/31/86 FIRST OUARTER STARILITT CLASS C STAblLITT bASED ONs DELTA T SETVEEN 200 ~ 0 ANO 3$ ~ 0 FKK'I VINO HEASUREO AT: 35.0 FEET VINO THRESHOLD AT: 0+75 NPH JOINT FREOUENCY OISTRISUTION OF VINO SPEED AND DIRECTION IN HOURS AT 3$ ~ 00 FEET SPEED IHPH) N NNE NE KNE E ESE SE SSE 5 SSV SV VSV V VNV Nv NNV TOTAL CALN 0 0 F 76~ I ~ 50 0 0 0 0 0 0 0 I ~ Sli 2,SO 0 0 0 .0 0 0 0 0
2 ~ SI>> 3 ~ 50 0 0 0 0 0 0 3~ SI~ 4~ 50 I 0 0 I I 0 4 4eSI>>
S ~ SI~
5~ $0 6~ $0 0
4 t
0 I
1 0
I 0
I 0
0 8
13
- 6. 51 8. $ 0 5 0 0 I 0 0 Zl doSI 11.50 0 0 3 I 0 20 11.51 14 ~ 50 t 0 0 2 0 8 14.$ 1 20.50 0 0 0 0 0 4 PZO.SO 0 0 0 0 0 0 0 see o eo o o o o o e o TOTAL 0 0 I 7 19 11 2 S 2 9 4 8 7 3 0 0 78 STAOILITT CLASS 0 STAOILITT SASEO Ovs DELTA T SKTVEKN 20O.O ANO 35.0 FEET VINO HEASUREO AT: 3$ .0 FEET VIND THRKSHOLO ATE 0.7$ HPH 30INT FREOUENCT OIS'IRISUTION OF VIND SPEED AND DIRECTION IN HOURS AT 35 F 00 FEET SPKEO (HPH) N NNE NE ENE E ESK SK SSE 5 SSV SV VSV V VNV NV NNV TOTAL er o e o a s eo pa CALH 0 ~ 76 IISI 2.50 I ~ 50 0 I 0 0 I ll0 2
3 4
'l'I~
'I
'1 3 '0
~ ISD
$ .50
'0 11 6
5 2
2 2
4 I
4 7
5 9
2 3
6
~ 3 4
6 0
50 69 60 24 5 6 5 ~ 0 2 I 2 Zl 6eSI 8.50 0 0 I 2 2D 8/$ 1 11. So I 0 2 23 ll ~
14+$
51 14.50 ZO.SO 0 0 0
0 I
4 0
1 17 d
1 0 3
>20 ISO 0 0 0 0 0 0 OO 0 0 OOOO OO 0 0 o o o oo oooo o oeoeooo oar o e e oo TOTAL 4 11 13 41 40 36 24 11 26 26 24 17 8 8 6 8 303 B23
t I
I I
I I
I
PUNGS Semi-Annual Operating Report for January - June l986 PYNCS JFOt 3SFT VINO YS DELTA f (200'5') FOR OfRI 19d6 SATCH RELKASES SITE IDENTIF IERt PYNSS DATA PERIOD EIAHINEOL I/ '1/66 3/31/66
~~ ~ FIRST OUARTER STASILITY CLASS E STASLLITY SASEO ONt DELTA T SETVEEN 200mb ANO 3$ eO FEET VINO HEASUREO ATt 3' FEET VINO THRESHOLD Aft' '$ HPN JOINT FREOUENCT OISTRISUTION OF VINO SPEED AHO DIRECTION IN HOURS AT 3S ~ 00 FEET SPEED (NPH) N NNE NE ENE E ESK SE SSE S SSV SV VSV V VNV NV NHV TOTAL o o CALH I 0 ~ 76o I ~ 50 2 0 I 0 0 0 I 0 L.Slo Zo50 2 0 I I 0 21 2.$ lo 3 ~ $ 0 2 2 2 0 I 0 23 14 SL 4 $0 0 3 0 0 2 0 0 4 ~ Sl S. 50 I I 2 I I 2 I 20 5 ~ Slo 6e$ 0 I I I I 0 0 . I 14 6.5Lo 6 F 50 Lr I 6 2 3 I 31
- b. 51 11. 50 0 0 1 I' 6 I 3 3 23 11.51 I ~ .50 0 0 0 0 0 I 7
- 14. 51 o20. SO 0 0 0 I 0 0 3 520.50 0 0 0 0 0 0 0 0 0 o o o o o TOTAL 10 12 1$ 9 16 13 LO 10 '10 16 6 7 6 'LO 6 2 165 STAOILITY CLASS F STAOILLTT SASEO ONt OKLTA 'f SETVEEN 200 ' ANO 35 ' FEET VINO HEASURED AT: 35 VINO THRESNOLD ATt Oo15 NPtl
' FEET JblttT FREOUFNCT OISTRISUTION OF VINO SPEED AIIO DIRECTION IN HOURS AT 3$ ~ 00 FEET SPEED (HPH) N NNE NE ENK E KSK 5'E SSE 5 $ $ ll SV VSV 'V VNV NV NNV TOTAL oo o CALH 0 0 ~ 76 I ~ SO I 0 0 I 0 0 7 I ~ SL 2 50 0 ~ 0 1 ~ 2 1 3 40 2.51 3. 50 2 0 3 2 I 2 2 35 F 51 F 50 0 0 2 I 0 3 4 35 4 ~ SL $ .$ 0 0 0 0 0 0 3 1 ZZ SoSL 6o50 I 2 0 I I I 0 12 6.51 6~ $0 0 0 2 I I 0 '1 19 6~ $1 LI.SO 0 0 0 0 0 0 2 ll Sl )4oSO L4oSI 20 F 50 0 0 0 0
0 0
0 0 0 0 0 0 0 0 0 0 0
>20 ~ 50 0 0 0 0 o 0 0 0 0 o o oo oo ooo o ooooo o oo o o ooo o o oo ooo oooo oo o ooooo oooo oo oooo o oo oo o TOTAL 26 21 20 10 10 4 4 3 1 6 0 II 7 6 10 II 11Z B24
I I
I
pVNQS $ emi-Annual Operating Repor~
for January - June 1986 PYNOS JFO: 35FT VINO YS DELTA 7 {200'35') FOR OTRL 1986 bATCH RELEASES SITE IDENTIFIER: PYNOS DATA PERIOD EIAHINEDt 1/ I/86 r 3/ll/86 woo FIRST OUARTER eee STASILITY CLASS 8 STASLLIT'I SAS'ED ON) DELTA T SETMEEN 200 ~ 0 ANO 35 ~ 0 FEET VINO HEASURED AT: 35 0 f EET VINO THRESHOLD AT'o7$ HPH JOINI'REOUENCT DISTRISUTION Of MIND SPEED ANO DIRECTION IN NOURS AT 3S ~ 00 FEET SPEED LHPN) N NNE NE ENE E ESE SE SSE $ SSV SV VSV V VNV NV NNI TOTAL CALM I 1.$ 0 I I I 22 0 76 lrSlr t.50 2 ~ $1 3~ $0 25 32 22 42 12 20 3
0 2
I I
0 5
2 2
3 I
3 6
9 18 ill 137 3 ~ Sle 4 50 ZS 15 2 0 I 2 2 18 102 4 ~ Slo S ~ 50 16 16 5 0 0 0 I 56 5 ~ Sl 6 ~ SO 9 6 0 I ' 0 0 . 0 24 6 ~ 5 le 8 ~ 50 10 6 5 0 0 0 0 3 26 8 ~ 51 LYSO I 0 0, 0 0 0 0 0 5 0
11 ~ 51 14 ~ 50 0 0 0 0 0 0 0 0 0 LirSL 20+$ 0 0 0 0 0 0 0 0 0 0 0
>20,50 0 0 0 0 0 0 0 0 0 0 r e o r TOTAL 122 133 62 Lb 7 I 4 8 4 b 6 10 7 9 29 54 484 STASILITT CLASS ALI.
STASILITT SASEO ONI OEL'IA T SETVEEN 200 ~ 0 AKO 35 0 fEET VINO HEASUREO ATt 35 ~ 0 EET VINO THRESHOLD ATi 0.75 NPN f
JOINT FREOUEHCY OISTRIbUTION OF MIND SPEED AND DIRECTION IN HOURS AT 35 00 FEET SPEED (HPH) N NNE NE ENE E ESE 5E SSE $ SSV SM VSV V VNV NV NNV TOTAL CALH 2
'6r I ~ 50 t I I 48 0
I ~ 51r 2,50 toslr ISO 37 41 7
li 7
$3 lb 31 16 2'L li 12 2
13 8
5 8
9 6
2 6
10 10 13 0
5 7
7 11 7
3 7
4 20 8
2 16 20 222 264 3 ~ slo 4 ~ 50 ir Sl S. 50 32 20 46 24 2$ lt 11 6 9 7
5 8
10 5 ll 8 7
2 3 5 t5 215 130 Sosl 6o50 6 ~ Slo 8 SO ll 14 8
11 7
lt 14 6
23 6
9 8
9 Ll 7
6 4 7
ll 9
8 6 3
1 2
3 I
8 2
I 6
2 87 137 8.51 LLoSO 11 ~ Slr L4 ~ 50 I
0 9
0 I 7
'L 22 16 llI 0 0
2 0 1 13 5
7 2
6 5 12 6 12 2
5 2
0 0
101,,
48 14 ~ 51r20. $ 0 0 0 0
0
. 2 7 0 0 I I 0 10 2 I 0 0 0 24 itbo$ 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 o rr rrrrr rrr rrr rr rr rrr r o orrr TOTAL 163 184 lit 88 122 71 47 39 5t 7Z 58 55 44 39 55 7S 127S S25
I I
I I
PVNGS Semi-Annual Operating Report for January - June 1986 PVNCS JFO: 35FT 'MIND YS DELTA T (200'5') FOR OTRI 1986 bATCH RELEASES SITE IDENTIFIER: PVNES DATA PERIOD EXAHINED: I/ I/86 3/31/86 FIRST OUARTER STAOILITT OASED OH: DELTA T SETMEEN 200.0 AHO 35.0 FEET MIHO HEASUREO AT: 35 MIND THRESHOLD AT: 0 '5' TOTAL NUHSER OF,OSSERYATIOHSt FEET HPH 1285 TOTAL NUHDER OF VALID ObSERVATIONS: 1278 TOTAL NUHBER OF HISSIHC ObSERVATIONS: 7 PERCENT DATA RECOVERY FOR THIS PERIOD: 99.5 S NEAR MIND SPEED FOR THIS PERIOD: 5.0 HPH TOTAL NUHOER OF OSSERVATIONS MITH bACKUP DATA: 0 PERCENTAEE OCCURRENCE OF STADILITY CLASSES E F I. 64 4.30 6.10 23. 71 lb.91 13 '6 37.87 DISTRISUTION OF MIND DIRECTION YS STADILITY H NNE NE ENE f. ESE SE SSE 5 SSM SM MSM M MNM NM NNM CALH 0 0 0 0 10 I 0 0 0 I 0 0 1 0 0 I I I 2 20 5 3 2 4 2 3 I 0 0 0 0 I 19 11 2 5 8 0 4
10 11 12 13 15 7
41 9
40 16 36 13 24 10 ll 10 26 10 26 16 9 4 8
17 7
3 8
10 0
6 8
0 8
2 0
1 26 27 20 10 10 4 3 7 8 8 11 6 10 11 0 122 133 62 19 7 ~
I 4 8 4 8 6 10 9 29 54 1 TOTAL 163 184 112 88 122 71 47 39 52 72 58 55 44 39 55 75 2 a26
I I
I I
I I
I I
PVNGS Sesqui-Annual Operating Report for January - June 1986 Table B5 JFDs of 35&oot Wind Versus Delta. T April June 1986 Batch Releases.
B27
I l
I I
PVNGS Semi-AnnuaL Opera(:ing Report, for January - June 1986 PTNCS JFO: 3SFT VIND TS DELTA 7 (200'35') FOR OTR2 1946 4ATCH RELEASE SITE IDENTIFIER: PYN6$
DATA PERIOD EIAHINEOc 4/ I/46 - 6/30/46 SECOND OUARTER STAblLITT CLASS A STASILITY bASKO ONI DELTA T bETVEEN 200 ~ 0 ANO 3S.O FKET VINO HEASURED ATI 3S ~ 0 FEET VINO THRESHOLD AT< 0075 NPH JOINT FREOUENCT OISTRISUTION OF VINO SPEED AND DIRECTION IN HOURS AT 35 00 FEET e 0 0 000 0 0 000 0 0 0 0 00 SPEED (HPH) N NNE NE ENE E ESE SE SSE 5 SSV SV VSV' VNV NV NNV TOTAL 00 00 0 r 0 00 Iosl CALH 0 ~ 76 I~ $0 0 0 0 0 0 0 0 0 0 0,'0 0 0
0 2051 2 50 3050 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 '00 0 3'.Sl- 4'.So O 0 0 0 0 0 0 0 0 0 0 0 4051 5 ~ So 0 0 0 0 0 0 0 0 0 I 0 1 5 ~ 51 650 0 0 0 0 o 0 0 0 0 0 0 0 6 ~ 51 $0 I 6 0 16 b.'5 I-I4I.'SO
~ 0 O
0 0'
0 I 1 10 16 2
12 0
5 2
4 1
0 0 57 Iles( limbo 0 0 1 5 13 3 12 5 4 1 45 Iiosl 20 ~ So 0 0 0 5 15 0 2 4 0 0 27
>20 F 50 0 o 0 0 0 4 0 1 1 0 0 6 0 0 0 0 e 0 0 TOTAL 0 0 $ 0 4 0 I 2 3 23 $4 17 20 16 6 1 1$ 2 STAb ILITT CLASS b STAdILITT 4ASED ONI DELTA T 4ETVEEN 200 ~ 0 ANO 35 ~ 0 FEET VINO HEASURKD ATI 3S 0 FEET VINO THRESHOLD ATI OI7$ HPH JOINT FRKOUENCT DISTRISUTION OF VINO SPEED AND DIRECTION IN HOURS AT 3S ~ 00 FEET SPEED (HPH) NNK NE ENK E KSE SE SSE S SSV SV VSV V VNV NV NHV TOTAL 00 0 0 00 000 0 0 00 000 0 ooroo 000 0 00 000 000 >>0 00 0 0 0 0 0 0 r 00 00 00 CALH 0 0 ~ 760 I I~ $ 1 2051 2 '050
~
3 F 50 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
D 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 3 '10 F 50 0 0 0 0 0 0 0 0 0 0 I 2 4 $1 5 ~ So I I 0 0 1 0 I 0 0 0 0 7 SSI 650 0 0 0 0 I 0 0 I 0 0 1 14 6 $ 104 50
~ ~ 0 0 0 I I 3 0 1 2 1 0 lb 51 lloSD I
'll4 ~
~ 51 14.$ 0 0
0 0
0 0
0 0
0 0
I 0
0 0
0 0 2
1 1 0 3 26 14.'SIOKO.'SO 0 0 0 O O O O 0 0 0 1 4
>20 F 50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 00 0 00 0 000 0000 0 000 0 00 00 0 0 00 oooo oo 00 00 0 0 or 0 0 r TOTAL I I 0 I 4 3 I 3 9 13 2511 6 $ 3 6 92 S28
l R
I' 1
l
PVNGS Sead.-Annual Operae1ng Report for January - June 1986 PYNOS JFOt 35FT VINO YS DELTA T (200'e35') FOR O'TR2 1986 SATCH RELEASK SITE IOENTIF IERt PYNES DATA PERIOD EIAHINEO'/ I/86 6/30/86 5ECONO 4UARTER STASILITY CLASS C STAR)LITT SASED ONs OEL'lA T SKTVEEN 200.0 ANO 35.0 FEET VIXD MEASURED ATs 3' FEET
'MIND THRK$ HOLO ATY 0 7$ NPH JOINT FREOUKNCY DISTR'ISUTIOH OF HIND SPEED AND DIRECTION IX HOURS AT 3$ 00 FEET SPEED (HPH) NNE NE ENE E ESK 5E 55K 5 SSV SV VSV V VNV NV NNV TOTAl.
o o' CALM 0 Oe76 le50 0 0 0 0 0 0 0 0 0 0 0 le51 2.50 0 0 0 0 0 0 0 0 0 0 0
'1e 3 ~ $0 0 0 0 0 0 0 0 0 0 0 0 2
3 '1 4 '0
'0 I I 0 2 0 0 0 0 0 0 5 4eSI 5
6 'l
'1 5 6 '0 8 'o I
2 I
5 3
0 2,
5 6
3 5
I 0
I 2
I 0
2 I
I 0
0 o
I 0
0 25 24 22 8~ Sl Ile50 Oe 0 I I I I 0 0 2 0 7 11.$ 1 14.50 0 0 0 I 4 2 0 I 0 0 8 14.51 20 F 50 0 0 0 0 2 0 0 I 2 0 5
>20 ~ 50 o o o o oo oo 0
oo oo 0
ooo 0 0 0 I 0 0 eo 0 0 1 TOTAL 0 2 0 1 5 7 9 10 12 18 11. 8 3 5 5 I 97 STAOILITT CLASS 0 STASILITT SA5ED VINO MEASURED OM; DELTA T SETVEEN 200 ' AMD 35 ~ 0 FEET AT 35 ~ 0 FEET VINO THRESHOLD ATs 0.7$ HPH JOINT FREOUENCZ OISTRISUTION OF VIND SPEED AND DIRECTION IH HOURS AT 3'0 FEET SPEED (HPH) 8 NNE NE ENK E ESK 5E SSE 5 SSV SV VSV 8 VNV NV NNV TOTAL oooo ooo ooo e CALH 0 0 F 76 I.SO 0 0 0 0 0 0 0 0 0 0 0 2 I ~ Sle 2 ~ So 0 0 I 0 I I 0 0 I 0 0 9 2eSI 3.50 2 I 5 5 2 2 I I 0 I 35 3.51 4.50 0 2 5 9 4 I 0 0 0 38 4e$ 1 SeSO 1, D I 3 4 2 I 3 0 I 2 0 22
$ .$ 1 6 'le OeSI 11.50 6.50 8 F 50 I
0 0
I I
1 0
I 0
2 2
0 0,
4 I
2 I
0 2
I I
11 0
3 3
0 I
2 2
2 I
0 0
0 19 17 25 11.$ 1 14.50 0 0 0 0 0 0 0 12 I 2 2 0 21 14 F 51 20.50 0 0 0 0 0 0 0 0 I 0 13 ee
?20 '0 ee e o o o ooo 0
oe oo 0
0 0 0 0 ooooooooeeooo oeooooo o oooeo ooooo oo 0
o 0
ooeooooo 6
0 oo oo o 0
o 0
o 0 I ooo 3
o TOTAL $ 7 8 6 15 12 21 19 12 14 38 18 9 8 I0 2 204
I I
PVNGS Semi-Annual Operating Report for January - June l986
~ YNCS JFO: 3SFT MIND YS DELTA T SITE IDENTIFIER: PYN6$
(200'$ ') FOR OTR2 1986 bATCH RELEASE DATA PERIOD EIAHIHEDg 4/ I/86 6/30/bd SECOND OUARTER STAOILITT CLASS STADILITY bASED ONi DELTA T
'VINO HEASUREO ATt 3$ .0 FEET EETVKEN 200 ' AND 3$ ~ 0 FEET VINO THRESHOLD AT> 0 ~ 75 HPH JOINT FREOUENCT DISTRIOUTION OF VINO SPEED ANO DIRECTION IN HOURS AT 3S ~ 00 FEET o o o o SPEED
{HPH) N NNE NE ENE E ESE SK 5SK 5 SSV SV VSV lf . VNt HM XNt TOTAL e e oo oe e o oo el e CALH 0 Oo76 io50 0 0 0' 0 0 0 0 0 0 2 I ~ Sle 2 50 0 0 0 0 2 0 0 I 2 0 15 2 ~ Slo 3 ~ SO 0 I 0 0 0 I 2 I 3 0 10 3 ~ Sl 4.50 2 0 0 I 2 I 0 2 0 I 15 io$ 1e S.SO 2 I I 3 I 5 ~$1 doSI 6.50 8 F 50 I
I 0
0 2
0
. 3 2
4 3 0 O
I O
0 0
0 I
li 13 36 8 ~ Sl 11.$ 0 11 ~ $ 1 14.$ 0 3
I 3' 0 0
9 10 22 18 9
li 8
10 2
I 3
5 0
3 2
0 0
0 '4 6O 14 ~ Sl 20.SO I 2 0 0 5 3 2 0 0 'I 'I 4
>20.$ 0 0 0 0 0 0 0 0 0 0 0 0
' oee e e oooo e e e TOTAL 11 5 11 4 7 4 0 4 3 30 64 41 11 13 10 3 223 STADILITT CLASS F STADILITY RASED ONt OKLTA T MIND NEASURED AT: 35 ' FEET EKTVEEN 200 ' ANO 3$ ~ 0 FEET
'VINO 'INRE5HOLO AT: Oo7$ HPH JOINT FREOUENCT 015'TRlbUTION OF ViNO SPEED AND DIRECTION IN HOURS AT 3$ .00 FEET e oooo o oo roooo oo o oooooo oo o o oooo oo o o oo SPEED (HPH) N NNE NE ENK K ESE SE SSE 5 SSM , SV VSV lt VNV NV NHM TOTAL oo o oo ooo o ooo ooreoo ooo oooo erooooo oo o oooo CALH 0 ~ 76 I So 0
~ 0 0 0 0 0 0 0 0 0 0 0 0 2 I~ $1 2.SO 0 I 0 0 0 0 I 0 2 4 0 16 2 ~ Sl 3 ~ So I F 51 4.50 3 2 3 I 2 4 2 I I 34 0 0 0 0 0 0 3 2 2 0 0 16 4.$ 1 5~ $0 0 0 0 0 I 2 tI I 2 2 0 0 16 5 ~$1 6 ~ So 6 ~ Sle 8 ~ 50 0
0 0 0 I I I 2 2 2 0 I 12 0 2 0 0 4 21 3 7 $ 1 4 $2 8 ~ $ 1 11 ~ $ 0 I 11 ~ 51 el ~ So
)4 ~ Slotoe i $0 0
0 0 0
0 0
0 0,
0 3
0 0 7 6 0 0 1
0 0
0
'I 0
23 0
0 0 0 0 0 0 0 ~
0 0 0 0 0 0 RED.SO 0 0 0 0 0 0 0 0 ooo oeo o oooo oooooo 0 0 0 0 0 o o oo oo ~ oooo ooo o oooooo rere o oooo oooooeooooooo ooo o ~ e TOTAL 10 14 4 3 2 3 4 4 4 14 37 17 22 16 6 7 171 B30
1' PVNGS Semi-Annual Operating Report for January - June 1986 PTNCS JFO: 1$ FT VINO TS DELTA T {200'S') FOR OTRZ 19d4 SATCH RELEASE SITE IDENTIFIER: PVNCS DATA PKRIOO KIAHtINKO: 4I Ildb bl30ldb SECOND OUARTER STASILITT CLASS C STASILITY SASEO ONt DELTA 7 SETVEEN 200 ~ 0 ANO 1$ ~ 0 FEET ltlNO MEASURED ltINO THRESHOLD AT AT'5'$ 0 0 FEET HPH JOINT FREOUENCT DISTRISUTION OF 'MIND SPEED AND OIRECTIDN I'N HOUR'3 AT 35 ~ OD FEET SPEED
{NPH) N NNE NE ENE E ESE SE 55E 5 SSM SV MSV V VNV NV NNlt TOTAL CAUI 0 Oetb I~ $ 0 0 2 0 0 0 0 0 I 0 5 le51e 2,50 6 10 0 I I a 2 4 33 2 ~ Sl 3 ~ $ 0 3 ~ Sl 4 ~ 50 16, 19 22 16 7 Z 3 I
1 2 4 4
10 5
79 65 10 0 2 4.SI 5 ~ 50 8 11 I 1 0 . a I 29 I '12 5~
6 'ls Sl 8 ~ 51 4 ~ 50 8.50 11.$ 0 2
3 0 1 0
0 0
l.
0 0
0 1
0 0
0 0
I 0
3 0
0 0
0 0
11 4
- 11. 51 I b. $ 0 0 0 0 0 0 0 0 0 0 I Iie Sl lb. 50 0 0 0 0 0 0 0 0 0 0
>20 F 50 0 0 0 a 0 0 0 0 0 0 e r o eos oo e o o oe o oo ooo oo eo or o o TOTAL $2 48 32 ll 4 I t 3 5 4 2 8 S 4 14 22 239 STAOILITT CLASS ALL STAOILITT bASED ON: OEI.TA T SKTMKEN 200.0 AND 3$ ~ 0 FEET MIND MEASURED VINO THRESHOLD AT'S ~ 0 FEET AT Oe7$ HPH JOINT FREOUENCT DISTRISUTION OF VINO SPEED AND DIRECTION IN HOURS AT 3$ .00 FEET SPEED (HPH) N NNE NK ENE E ESE SE $ 5E 5 Edit SM VSM V MNV NV NNV TOTAI.
r o oeo o oo sores oo o ooo sore o sores oo sore eoo roose o oo rosser ooo os error o r CAUI 0 0.76e I SO 0 5 2 0 0 0 0 t 0 0 0 1 0 0 . 1 0 11 I. 51s
- 2. 51 2.50 3 $0 6
20 13 26 18 2 9
I 10 2 0 I 2 3 I 1 8 8
6 12 '58 73 i.'1Slr 9 7 6 10 7 9 5 4 8 6 3 4.50 24 20 14 5 4 4 10 7 $ 8 7 6 5 5 7 141 Sebo ,' 16 14 4 I 5 9 10 '12 10 6 3 1 113 Seblo F 50
- 6. 51 deba 4 5
8 1
I 2
4 4
4 2
4 5 lt5 11 11 la 27 4$
9 11 20 15 5 5 14 5
9 3
5 9$
182 be Slr 11 ~ 5D 4 4 1 I 7 2 I 2 2 31 45 19 17 14 4 4 202 11 ~ Sle 1450 I I I 2 I 0 0 I 16 53 21 14 9 7 1 130
- 14. $ 1 ta $ 0 I 2 , 1 0 2 0 0 0 0 5 10 8 4 5 2 63
>20 .50 e o e 0
r e I 0 sore ee oosooeesss 0
eee I 0 0 0 0 0 4 I I I 0 1 Ia TOTAL 79 99 40 tb il 30 38 47 48 120 231 120 76 67 $4 42 1178 B31
l 1
I t
I
PVNGS Semi-Annual Operating Report for January June 1986 PYNOS UFO: 35FT VINO YS OEL'lA T (200'5') FOR OTR2 1986 SATCN RELEASE SITE IOEHTIFIER: PYNOS DATA PERIOD EXAHIHED: 4/ I/86 6/30/86 SKCONO OUARTER STASILITT SASEO ON: DELTA I SKTVEEH 200.0 ANO 35.0 FEET HIND HEASURED ATc 35.0 FEET
'VINO THRESHOLD AT: 0.75 HPN TOTAL NUHSER OF ObSKRYATIONS: 1183 TOTAL NUHSER OF YALIO OSSERYATIOHS: 1178 TOTAL NUHbER OF HISSIHQ ObSERVATIONS: S PERCENT DATA RECOYERY FOR THIS PERIOD: 9' S HEAN VINO SPEED FOR THIS PERIOD: 7.4 HPH TOTAL NUHSER OF OSSERYATIONS 'VITH SACNUP DATA: 0 I
PERCENTAOE OCCURRENCK OF STAblLIT'I CLASSES C 0 E F
- 12. 90 7>>bl 8>>23 17.32 lb.93 lb.S2 lb.29 OISTRISUTIOH OF VINO DIRECTION YS STAOILITT N NNE NE ENE E ESE SE SSK S SSV SV VSV V VNV NV NNV CALH 0 23 54 17 20 16 6 I 0
1 0
0 I
2 0
0 5 0 I
I 4
4 5
3 7
1 1
9 2
3 10 3
9 12 13 18 25 11 ll8 6 3
5 5
3 5
6 I
$ IS 12 19 12 14 38 18 9 8 10 2 11 10 7
5 16 ll8 6 7
2 4
3 21 0
4 6 3 30 16 64 37 41 17 11 22 13 16 10 6
3 7
52 68 32 ll 4 I 3 S 6 2 8 5 4 14 22 TOTAL 79 99 60 26 41 30 38 47 48 120 231 120 76 67 54 42 0 B32
1 I
I I
PVNGS Semi-Annual Operating Report for J anuary - J une 1986 APPENDIX C DOSE CALCULATIONS
PVNGS Semi-Annual Operating Report for January June 1986 GASEOUS EFFLUE~ 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 Unit 1 during the first quarter** and from Units 1 and 2 during the second quarter. The radionuc-lides considered in the dose calculations were Tritium, Iodine-131, Iodine-133, all noble gasses, and particulates having a half-life greater than eight days and for which dose factors are contained in NUREG-0172.
Three locations were selected for individual dose calculations: the site boundary, the nearest residence and the nearest garden. 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 indivi'dual and the population are 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 C6.
Table Cl presents the doses on a quarterly and semi-annual basis for the site boundary, and the maximum individual in the general public. The loca-tions for which data are presented represent the highest annual doses. It should be noted that locations are the same as those reported in the July-December 1985 report based on the results of the December 1985 land use census.
Table C2 presents the po'pulation 4oses for the first two quarters, and the first semi-annual period of 1986. Table C-3 summarizes the individual doses and compares the result to PVNGS Technical Specification'imits.
- There were no liquid effluents associated with the operation of this facility
- Unit 2 was not operational during the first quarter of 1986.
C2
PVNGS Semi-Annua1 Operating Report for January - June 1986 TABLE Cl DOSES TO SPECIAL LOCATION FOR JANUARY-JUHE 1986 SITE BOUHOARY 1.40 miles SSN from UNIT 1 and 1.14 miles SSN from UNIT 2 BETA GAMHA AIR DOSES(HRAD) 1ST QUARTER 1.20E+00 4. 49E-Ol 2HD QUARTER 7.73E-03 3.43E-03 1ST SEHI-ANNUAL 1. 21E+00 4.52E-01 T. BODY SKIN MAXIHUH INDIVIDUAL(MREH) 1ST QUARTER 2.67E-01 7.38E-01 2NO QUARTER 2. 11E-03 5.72E-03 1ST SEMI-ANNUAL 2.69E-01 7.44E-01 MAXIHUM INDIVIDUAL IN GEHERAL PUBLIC LOCATED AT A RESIDENCE 4.60 miles S from UNIT 1 and 4.50 miles 5 from UNIT 2 (HREH) T.BODY GI- TRACT BONE LIVER KIDNEY THYROID LUHG SKIN 1ST QUARTER ADULT 1.04E-01 1.04E-01 9.12E-02 1.04E-01 1.04E-01 1.10E-01 1.04E-01 2.69E-01 TEEH 1. 04E-01 1.04E-01 9. 12E-02 1.04E-01 1.04E-01 1.11E-01 1.04E-Ol 2. 69E-01 CHILD 1.02E-01 1.02E-01 9.12E-02 1.02E-01 1.02E-01 1.10E-Ol 1.02E-OI 2. 67E-01 INFANT 9.76E-02 9.76E-02 9. 12E-02 9.76E-02 9.76E-02 1.05E-01 9.76E-02 2.63E"01 2NO QUARTER ADULT 9.50E-03 9.50E-03 6.25E-04 9.50E-03'.50E-03 9.75E-03 9. 51E-03 1. 06E-02 TEEN 9.57E-03 9.57E-03 6.25E-04 9.57E-03 9.57E-03 9.88E-03 9 '7E-03 1.07E-02 CHILD 8. 53E-03 8.53E-03 6.26E-04 8.53E-03 8.53E-03 8.88E-03 8.53E-03 9.64E-03 IHFAHT 5.17E-03 5.17E-03 6.25E-04 5.17E-03 5.17E-03 5.'49E-03 5. 17E-03 6. 28E-03 1ST SEHI-ANNUAL ADULT 1. 13E-01 1.13E-01 9.18E-02 1. 13E-01 1.13E-01 1.19E-Ol 1. 13E-01 2.79E-01 TEEH 1.13E-01 1.13E-01 9.18E-02 1.13E-01 1. 13E-01 1.21E-01 1.13E-01 2.79E>>01 CHILD 1.11E-01 1.11E-01 9.19E-02 1.11E-01 1.11E-01 1.19E-01 1.11E-01 2. 77E-01 INFANT 1. 03E" 01 1. 03E-01 9.18E-02 1.03E-01 1.03E-01 1.10E-Ol 1.03E-01 2.69E-01 C3
I l
l
PVNGS Semf-Annual Operating Report for January - June 1986 TABLE C2 IHTEDRATED POPULATION DOSES FOR JANUARYrJUHE 1986 HANREH JAHUART HARCH 1986 PATHMAY T,BODY 6I TRACT BOHE LIVER KIDHET THYROID LUH6 SKIN reeeeeeaefeeee + + e+ eeooooaoo+sssooeoooo+o + a f +
PLUHE 4.39E Ol ( 4.39E Ol ( 4.39Eo01 ( 4.39E Ol ( 4.39E 01 ( 4.39Ee01- ( 4.39E Ol ( 1.55K+00
(
seeeeeeee+oeeeeeeeeef oeeeeeeeae+eeees eeefeeeeeeee efeeeeeeeeee+e f +
6ROUHD ( 7.06E 06 ( 7.06E 06 ( 7.06E 06 ( 7.06K 06 ( 7.06E 06 ( 7.06E 06 ( 7.06E 06 (
8.40Ee06 seeeeeooofeeeeoeooeefeeeeeeooeofeeeeeeeeeefeeeeeeoeeefoaooaeoeoefeeeeeeaeeefeeeeeeeeee+eeeeeee f
( 1.03E Ol ( lo03E-OI ( 9.59E 05 ( 1.03E Ol ( lr04E 01 ( 1.43E IHHAL 01 ( 1.03E Ol ( 1.03E Ol (
oo eoeoos+seeeeeeeoe+e oeo eoeofoo eeeeeeeeef esses eee fe + e+ e e ere+
VESET I 5.17E Ol ( 5.17E Ol ( 1.89Ee04 ( 5.17E 01 ( 5.17K Ol ( 5.91Ee01 ( 5.17Ee01 ( 5.17Ee01 of o o o o f f e f e f e ee a+esses e eef COM HILK ( 3.83E 02 ( 3.83Ee02 ( 1.78Ee05 ( 3.84E 02 ( 3o84E 02 ( 4.52Ee02 ( 3.83Ee02 3.83E 02 seeeeeeef <<f f e sf oeeeeee
(
a+easer aee +
HEAT 1.69Ee02 ( 1 ~ 69E 02 ( 4.01E 08 ( 1.69E 02 ( 1.69E 02 ( 1.69Ea02 ( 1 ~ 69E 02 ( 1.69Ee02 re f
(
o oooooofooeoo eoesfoeoooooooo+oooososo a+as o oar+ oooooeroa+ooeooos oe+
TOTAL 1.11E+00 ( 1.11K+00 ( 4.39Ee01 ( 1.11E+00 ( 1.11E+00 ( 1.23E+00 ( 1.11E+00 ( 2;23E+00 ee esses+ (
oo o feeoeeeeoeefeeee e eoefoaoeooeoa f o f + +
os+soars o + er err+a + o o + f + +
AVERASE PERSON 6.18E 07 6.18E 07 2.44E 07 6rIBE 07 SrIBE 07 6.85E 07 6 ~ 18E 07 1.24E 06 (REH) re assessors\
APRIL JUNK 1986 PATHMAY eeeeaeeaef e T.BODY
+
6l oo TRACT a+a BOHE
+
LIVER f KIDNET
+
THYROID LUN6, SKIN+ +
PLUHE 7.02E 03 ( 7.0RE 03 ( 7.02E 03 ( 7.0RE 03 ( 7.02E 03 ( 7.02E 03 ( 7:02E 03 ( 2.48K 02
(
esoeeefoeeeeeeeeefeeoaaoeo f e ease e f eraser feooaeeaerofeoe f 6ROUHD (
1.96Ke05 ( 1 ~ 96E 05 ( 1.96Ee05 ( 1.96Ee05 ( 1.96Ee05 ( 1 ~ 96Ea05 ( 1.96E 05 ( 2.29Ee05 o oars+ooossseseofoseeossooefseesooooar+assessorsefossososeso+oooooooooo+oooooooooo+rooooooo +
IHHAL, I 1.92E 01 I 1.92E 01 I 1.39E 05 I 1.92E 01 I 1.92E 01 I 1.97K 01 I 1.92E 01 I 1.92Eo01 eeoeoeeeef eeoeeeeeeef eeeeeeeaaef aero'lars sf eeoeeeeeee eeeeeeeeee f f esses ea f esses serf ee I VK6KT ( 5.33E 01 ( 5.33Ee01 ( 4.36EeOS ( 5 ~ 33Ee01 ( 5.33E 01 ( 5.42Ee01 (
5.33Ee01 ( 5.33Ee01 e e ee eefeeeeeeoeee+eeaeeeoaaefa eee eaa fe e e ea sf assess seafare esse e+e es eeee+eaeeeee +
COM HILK ( 7.60K 02 ( 7.60E 02 ( 9.8$ E 06 ( 7.60E 02 ( 7.60E 02 ( 7.76E 02 ( 7.60Ee02 7.60E 02 eeeeeeeeaf esses f f eroeooooee f eo ooeooof ooe sears (
+ore eoooooO HEAT 1.99E 02 1.99K 02 2.06E 07 ( 1.99E 02 ( 1.99E 02 ( 1.99Ee02 ( 1.99E 02 ( 1.99Ee02 rseoaeeerf ( ooeeeoeeeef ( eeeereeoeo f( o f sfoooroooooof reassess +reassess oO TOTAL ( 8.28E 01 ( 8.28E 01 ( 7 ~ 10E 03 ( 8.28E 01 ( 8.28E 01 ( 8.43Eo01 ( 8.28E Ol ( 8.45Ee01 e eeeeeeefeeeeeaeeeefeeeoeoooeof e f e ee ef erases eooooooos+osooooooeo+eeoooooooe+oooooeooeo+oooooooooe+oooeoooeao+oaoosooooo+oooooooooo+oooooooeoo+
asses fears f AVERA6E PERSON 4.61E 07 4.61E 07 3.95Ee09 4oSIE-07 4.61E 07 4.69Ee07 4 ~ SIEe07 4.70Ee07 (REH)
+ oo + r + f oar+
JANUARY JUNK 1986 PATHMAT T.BODY 6l TRACT BONE LIVER KIDNEY THTROID LUX6 SKIN oeeooaoeo+eoeeooeooo+ oooeeeeee+eeeeeeeeee fassesseeee+eeeeeeeeeo+eeooeoeeee+ erasers e+
PLUHE' 4.46Ke01 ( 4;46Ee01 ( 4;46Ee01 4:46Ee01 4.46E-'Ol 4.46E-'Ol 4.46E-OI 1.58E+00 eases ass f oese eeeaeof eeoeeeoaee fear ) J
(
f(
f(
ef 6ROUNO ( 2.67E 05 ( 2.67E 05 ( 2.67E 05 2.67E 05 2.67E 05 2.67Ee05 2.67K 05 3.13Eo05 a o of J ) ) $ f ef INHAL ( 2.95Ke01 ( 2.95Ee01 ( 1.10Ee04 ( 2.95Ee01 ( 2.95Ee01 3.40Ee01 2.95Ke01 2.95Ee01 eeaoooeaofeooeeeoeoefooooaeoooofoooeo o eafoeaoeooeaefeooeoooao
(
f(
f
(
eof
( 2 '2E 04 ( I OSE+00 ( I ~ 05K+00
( IrOSE+00 ( I 05E+00 f I f I VE6ET 13K+00 OSE+00 1 OSE+00 ee o refers ooe oaf soars f o e f assessors+esses eo
( (
f
(
ore+
COM HILK ( 1.14Ee01 ( 1 ~ 14Ke01 ( 2.77Ee05 ( 1.14Ee01 ( 1.14E Ol 1.23Ee01 1.14E 01 1.14E Ol f
oea eeee oeaeeo feeeaeaeeee faeeeeeeeee feeeeeeoaee feeaaeeeeee feeeeeeeee sf eaeeeeeeeef esse e f
( (
HEAT ( 3.68Ee02 ( 3.68Ee02 ( 2.45Ee07 3.68E 02 ( 3.68E 02 ( 3.68Ee02 3.68Ee02 ( 3.68Ee02 ease oeeefaeeaooeo (
efeeeeeeaeeefeeaaaeaeee+eeeaeaeeeefeeee f f + o o+
TOTAL ( 1.94K+00 ( 1.94E+00 ( 4.46Ee01 ( 1.94E+00 ( 1.94K+00 ( 2.08E+00 1.94E+00 ( 3.07E+00 o ooooooofoooooosoeefoeooeooosofooooooeoeof ooosoooofeooooooooofsos ooo o +era eeeeeef f oooo oar+ ooaooooeo+ooooooooos+eoeeoree o+ oooaoos s+ soarer o + o o + e oeo o+
AVERA6K PERSON 1.08E 06 1.08Ee06 2.48Ee07 1.08Ee06 IeOBE-06 1.16Ee06 1.08Ee06 1.71Ee06 (REH) re\error'o reer eeraoeeaee eeaeesoere ee eeeeeee ea eee C4
I PVNGS Semi-Annual Operating Report for January - June 1986 Table C3 Summary of Individual Doses for January-June 1986 Quarter Quarter Year to Unit 81 82 Date Gamma Air Dose mrad 4 '9E-01 3.43E-03 4.52E-01 T ~ ST F 11.2.2 Limit mrad 5.00E+00 5.00E+00 1.00E+01
% T.S. Limit 0/ 8.98E+00 6.86E-02 4.52E+00 Beta Air Dose mrad 1.20E+00 7. 7 3E-03 1.21E+00 T.S. 3.11.2.2 Limit mrad 1.00E+01 1.00E+01 2.00E+01
% T.S. Limit 1.20E+01 7 . 73E-02 6.05E+00 Maximum Organ Dose mrem 1.11E-01* 9.88E-03* 1. 21E-01*
T.S. 3.11.2.3 Limit mrem 7.50E+00 7.50E+00 1. 50E+01
% T.ST Limit 1.48E+00 1.32E-01 8.07E-01
+These control location doses are imparted via three principal atmospheric pathways: plume, ground exposure, and inhalation; unlike the hypothetical site boundary location doses presented in tables A4 and A8 of Appendix A, which are based on the ODCM, and also include an ingestion contribution. The highest organ dose (neglecting skin) is to the teenager's thyroid resulting from exposure in the South Sector, 4.6 miles and 4.5 miles from Units 1 and 2, respectively. Technical Specification 3.11.4 has higher limits than Technical Specification 3.11.2.3 and there-fore the percent of limits are more conservative based on Technical Specification 3.11.2.3 than on Technical Speci-fication 3.11.4.
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PVNGS Semi-Annual Operating Report for January June 1986 DOSE CALCULATlON MODELS 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:
o 0 to 5 mile land use census conducted in December 1985. The fol.low-ing changes in land use were identified between August 1984 and December 1985; deletion of all milk animals within 5 miles, deletion of gardens at several residences, changes in location of nearest residence in several sectors.
o 0'o 5 mile population distribution based on the land use census conducted June-August, 1984 o 5 to 50 mile population distribution from PVNGS ER-OL Figure 2.1-6.
o The population distribution of metropolitan Phoenix greater than 50 miles from PVNGS, based on the 1980 census results, were conserva-tively included in the 40 to 50 mile sectors.
o Absolute humidity of 6.0 g/m3 from PVNGS ER-OL Table 2.3-34.
o The fraction of the year that vegetables are grown (0. 67) from PVNGS ER-OL Section 2.1.3.4.
o The fraction of daily feed derived from pasture and length of graz-ing season for milk animals (0.35 and 0.75) from PVNGS ER-OL Section
- 2. 1. 3.4.
o The fraction of daily feed derived from pasture and length of graz-ing season for meat animals (0.05 and 0.25) from PVNGS ER-OL Section
- 2. l. 3.4.
Other values used for input to GASPAR are default values from Regulatory Guide 1.109 Revision 1.
C6
l PVNGS Semi-Annual Operating Report for January - June 1986 APPENDIX D CHANGES TO OFFSITE DOSE CALCULATION HANUAL (ODCM)
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PVNGS Semi-Annual Operating Report for January - June 1986 EVALUATION OP CHANGES TO THE PVNGS OPPSITE DOSE CALCULATION MANUAL The Offsite Dose Calculat1on . Manual (ODCM) for the Palo Verde Nuclear Generating Station (PVNGS) was revised in September, 1985. This revision to the ODCM (Revision 1) was necessary in order to adapt it for from oae written for multi-unit operation a single unit operation (Revision 0) to one wr1tten (Revision 1). Revision 1 became effective with respect to Unit 1 on Ja~~ra 1 1986, and is identical to the ODCM Revision 1 which was submitted on the Unde License Docket.
Licenseeinit1ated changes to the ODCM must be made in accordance with PVNGS Technical Specification 6.14.2. This report contains sufficieatly 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.
Many changes made in the ODCM were editorial in nature aad were made for ease of reading for the user (e.g., paragraphs were recorded, etc.). Where the changes were purely editor1al 1n nature and did not affect technical conteat or interpretation, they are not discussed in this document. The number of strictly editorial changes was 'so large that only the salieat ones are discussed herein.
The ma)or technical changes made in, the rev1sion are.
Adaptiag the single unit ODCM (for PVNGS Unit 1), for use by the multi~it site (PVNGS Units 1, 2, and 3) and apportioning the site limits 1n Rev1s1oa .0 to the specific unit 11mits in Revision l.
2~ Inclusion of the nuisance release pathway, which includes the evaporation pond.
3e Recalculation of the meteorological dispers1on parameters (X/g and D/g) based on 9 years of data.
4, Recalculation of Ri values to more closely conform to NURE~133.
- 5. Change in dose assessment methodology from using the overly conservative critical location (Revision 0) to using the realistic controlliag location (Revision 1). The critical location was the nearest resident that would receive the highest dose, and a garden and milk animal were assumed to be there. The controlliag location is the actual resident that would receive the highest dose when the real location of milk animals and gardens is considered. Each reactor unit has a controlling location based on 9 years of meteorologic data and the current Land Use Census.
6915A/2148A
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PVNGS Semi-Annual Operating Report for January - June 1986
- 6. Change in dose projection methods. Revision 1 allows the doses from anticipated. operational events (e.g., shutdown). to be included in the 31 'ay projection required by Technical Specification
. 3.11.2.4.
Revision 1 of the ODCM represents a refinement of the overly conservative Revision O. Revision 1 decreases the conservatism of the dose calculation methodologies of the ODCM but increases greatly their accuracy and reliability. Revision 1 was designed to accommodate three operating units without compromising their effectiveness with extremely over conservative dose assessments while simultaneously protecting the public by using the most accurate and realistic data available.
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, etc.).
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PVNGS Semi-Annual Operating Report for January - June 1986
- 1. 0 INTRODUCTION Change 1.1:
Revision 0 states:
1.2.1 Iodine 131 iodine 133 Tritium and Radionuclides in Particulate Form with Half-Lives Greater than Ei ht Da s In this model, a critical location is identified for assessing the maximum exposure to an individual for the various pathways and to critical organs Revision 1 states:
1 ~ 2.1 Iodine 131 . iodine 133 Tritium and Radionuclides in Particulate Form with Half-Lives Greater than Ei ht Da s In this model, a controlling location is identified for assessing the maximum exposure to a MEMBER OF THE PUBLIC for the various pathways and to critical organs.
Explanation 1.1:
Revision 1 uses the controlling location methodology to determine the maximum exposure to an individual offsite. The controlling location is defined as the location of the member of the public who receives the highest dose (Appendix A to Revision 1, ODCM) The controlling location reflects the actual exposure pathways around PVNGS and is based on the annual land use census and a nine year meteorologic data base.
This change in dose evaluation methodology results in a more accurate
'ssessment of doses delivered offsite from PVNGS operations.
Change 1.2:
Vaxious editorial changes appear in Section 1.2.2 of Revision 1 of the ODCH.
Change 1.3:
Revision 0 states:
The ODCM will be maintained at the station for use as a document of acceptable methodologies and calculations to be used in implementing the Technical Specification. Changes in the calculational methods or parameters will be incorporated into the ODCM in order to assure that the ODCM represents the present methodology.
1-1
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PVNGS Semi-Annual Operating Report for January - June 1986 Revision 1 states:
The ODCM 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 ODQf in accordance with Technical Specification 6.14.
Explanation 1.3:
Revision 1 specifies the method in which changes will be made to the OD(H.
Change 1.4 Revision 0 does not discuss nuisance pathways.
Revision 1 states:
Nuisance Pathwa s This section addresses the potential release pathways which should not contribute more than 10K 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. The doses from these nuisance pathways will periodically be evaluated to ensure that they do not contribute more than 10K of the doses evaluated in this manual'f any nuisance pathway exceeds this limit then the "ODQf methodology for calculation of doses will be applied to each applicable release pathway.
Table l-l NUISANCE PATHWAYS Evaporation Pond Cooling Towers Laundry Building Exhaust Unmonitored Secondary System Steam Vents/Reliefs Turbine Building Ventilation Unmonitored Tank Atmospheric Vents Explanation 1.4 The nuisance pathway section was inserted to provide PVNGS with flexibility in the application of the ODCM dose calculations. The evaporation pond as a nuisance pathway because it is anticipated to contribute is'ncluded neglibile dose during each unit's life and is the receiving body of water for any liquid discharges of process liquids beyond the protected area of each unite 1-2
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PVNGS Semi-Annual Operating Report for January - June l986 Change 1.5 Revision 0 includes Table 1-1, "Annual Radiological Effluent Objectives'nd Standards".
Revision 1 deletes this table.
Explanation 1.5 A tabulation of Technical Specification requirements, although relevant, is not needed in the ODCM.
1-3
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PVNGS Send.-Annual Operating Report for January - June 1986 2.0 GASEOUS EFFLUENT MONITOR SETPOINT Change 2.1:
Revision 0 states:
Setpoints are conservatively established for each efflueat monitor so that the iastantaneous dose rates corresponding to 10 CFR 20 annual dose limits in unrestricted areas w111 aot be exceeded. Conservatism is to be incorporated into the determination of each setpoint to account for: !
All exposure pathways of significaace at the critical receptor locatioas; Dose contributions to critical receptors from multiple release points; and Dose coatributions from major radioisotopes expected to be present in gaseous effluents.
The general methodology for establishing gaseous efflueat monitor setpo1nts as based upon a site release rate limit 1a uC1/sec derived from site specific meteorological dispersioa conditioas, radioisotopic distributioa, aad whole body and skin dose factors. A fraction of the site release rate limit (the administrative value) is then allotted to each release point aad its monitor setpoint (uCi/cc) 1s derived usiag actual or design maximum flow rates.
Revision 1 states:
The general methodology for establ1shing low range gaseous effluent monitor setpoints is based upon a site release rate limit in uC1/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 exceediag Technical Specification 3.11.2.1. 80K of Technical Specification 3.11.2 1 limits is considered to be the site release rate limit. 3he site release rate limit vill be allocated amoag the liceased un1ts'elease points. The unit release rate limit vill then be utilized for the determiaation of gaseous moa1tor 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 desiga flov rates. ~
Explanation 2.1 Revision 1 of the ODCM accommodates the multi~nit PVNGS site. This introductory text states the method of determining effluent monitor setpo1nts by successive allocatioa of the site release rate limit to each unit, and allocation of each un1ts'elease rate limit to each effluent monitor.
2-1
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PVNGS Semi-Annual Operating Report for January - June 1986 Change 2.2-Revision 0 states:
For the purpose of implementation of Technical Specification 3.3.3.9, the alarm setpoint level for effluent noble gas monitors shall be established to ensure that the noble gas releases do aot exceed the total body dose r'ate of 500 mrem/yr and 3000 mrem/yr skin dose (Technical Specification 3.11.2.1) ~
Revision 1 states:
For the purpose of implementation of Technical Specificatioa 3 '.3.9, 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).
Explanation 2.2:
Revision 1 clarifies that the purpose of the monitor setpoints is aot to ensure that the release does not exceed a limit but rather to ensure that personnel are alerted by the alarm when releases approach the limit.
Change 2.3:
Revision 0 states:
Zaitially, the equivalent dose factors will be evaluated frequeatly (at least quarterly) to assure that the best information on isotopic distribution is being used for the dose effective value. The frequency of evaluation may change in the future when historical data show that quarterly evaluations are unnecessary.
Revision 1 states:
The equivalent dose factors will be evaluated periodically to assure that the best information on isotopic distribution is,being used for the dose equivalent value.
Explanation 2.3:
Revision 1 does not specify the remvaluation frequency for the isotopic distribution being used for the dose equivalent value. The isotopic distribution will be re~valuated as necessary, taking into account operational evolutions of the plant.
2-2
I PVNGS Semi-Annual Operating Report for January - June 1986 Change 2.4:
Revision 0 does not address Unit Release Rate Limits (QUNyT).
Revision 1 presents a method to allocate the Site Release Rate Limit (QS1TE) to determine the release rate limit for each operating unit. The Unit Release Rate Limit (QUNZT) will be calculated as follows:
Unit Release Rate Limits ( yT) 1 l
Typically, QSlTE will be divided equally amoag 'perating units. If operational history dictates a larger fraction of the QSZTE be assigned to a specific uait then a weighted average of each unit's contribution to the QSZTE vill be utilized to determine the QUN1 ZT (fUNZT) (QS1TE) (2-S) where:
I QUNZT unit release rate limit in u Ci/sec.
fUNXT the fraction ( Kl) of aoble gas historically released from a specific operating unit to the total of all noble gas released from the site.
QSZTE the site release rate limit, in u Ci/sec determined ia Section 2-2 of this manual.
Explanation 2.4:
This chaage accommodates the multi~nit site and provides a means to allocate the site release rate limit to each operating unit.
Change 2.5:
Revision 0 states:
To comply vith Technical Specification 3.3.3.9, the alarm/trip setpoints can now be established using the Site Release Rate Limit to ensure that aoble gas releases do not exceed the dose rate limits.
Revision 1 states:
To comply with Techaical Specificatioa 3 3.3.9, the alarm/trip setpoints can now be established using the unit release rate limit (QUNZT) to ensure that the noble gas releases do not exceed the dose rate limits.
Explanation 2.5:
This change is a result of instituting the Unit Release Rate Limit explained in Change 2.4. All monitor setpoint determinations in Revisioa 1 are based oa the Unit Release Rate Limit (QUNlT) ~
2-3
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PVNGS Semi-Annual Operating Report for January -. June 1986 Change 2 ~ 6:
Revision 1 states:
Monitor setpoints will also be adjusted in accordance with Station Manual Procedures to account for monitormpecific characteristics.
Explanation 2.6:
This change was introduced to allow PVNGS operational flexibility in monitor adjustments. As stated, these adjustments will be made in accordance to Station Manual Procedures. This change is an addition and appears at the end of the second paragraph of Section 2.4 Change 2.7:
Revision 1 states that the flow rate used for monitor RU-12 setpoint determination should be expressed in cfm at STP.
Explanation 2.7:
This change was introduced to allow for the pressure correction to be made in determining this setpoint for RU-12., RU-12 monitors releases from pressurized tanks. This pressure correction is specified in the applicable Station Manual procedures.
2-4
I PVNGS Semi-Annual Operating Report for January - June 1986 3' GASEOUS EFFLUENT DOSE RATE Change 3.1:
Revisioa 0 states:
The dose rate in unrestricted areas due to radioactive materials released in gaseous efflueats may be averaged over a 24+our period aad shall be determined by the following equation for whole body dose:
1 Revision 1 states:
The dose rate in unrestricted areas shall be determined using the following equations.
Explanatioa 3.1:
Revision 1 does not specify the averagiag period for gaseous effluent release dose rate.
Change 3.2 Revision 0 contains the followiag equatioas to calculate the dose rate from noble gases:
Whole body dose rate wb i~ i) (>>~)SB (3-1)
Skin dose rate'S
'i<(Li +1 ~) (>>a)SB (Qi)] (3-2)
Where the value that will change is:
X/Qg B 6.49 x 10~ sec/m3, the highest calculated anaual average dis persion parameter for any sector at the site boundary from Table 3 20 Revision 1 uses the following equations to calculate the dose rate from noble gases:
For whole body dose rate:
(X/A)SBW (~i)~
For skin dose rate:
DSK Q[(Li + lo1Mi) (X/g)SBW (~i) ] (3-2) 3-1
(
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PVNGS Semi-Annual Operating. Report for January - June 1986 Where the value that has changed is:
(X/Q) SBW ~ 8.9lxl0 , the highest calculated annual average dispersion parameter, in sec/m3, for any of the three units, from Table 3-2.
Explanation 3.2:
The ma)or change in the equations for calculating the dose rate from noble gases is the meteorological dispersion parameter. 2xis dispersion parameter is the highest annual averaged X/Q for any of the three units at the site boundary with the radial grid sectors centered on each unit. The X/Q values are calculated using desert sigmas and are based on 9 years of data.
This change in treatment of the X/Q values allows each unit to be handled as a discrete release point to accommodate the multi~nit site. It should be noted that due to the differing orientation of each unit, the site boundary locations described in Tables 3-2, Sheet 1 through Sheet 3, are not the same physical location for each unit (e.g., the west site boundary location for Unit 1 may not be the same physical location as the west site boundary location for Unit 3 or Urd.t 2)'. This is the result of using the radial sectors centered on each .of the units The X/Q and D/Q values used in Revision 0 are based on 5 years of data. The 9 year annual averaged meteorological dispersion parameters appearing in Revision 1 give a more accurate dose assessment for individuals in the offsite environs of PVNGS and a more accurate dose rate assessment in unrestricted areas.
Change 3.3:
Revision 0 contains the following equation to calculate the organ dose rate from radionuclides other than noble gases:
D ~i[(Pi) ( X/Q)SB(Qj) 1 (3-3) where the value that will change is:
( X/Q)SB 6.49 x LO~ sec/m3, the highest calculated annual average dispersion parameter for any sector at the site boundary from Table 3-2.
Revision 1 uses the following equation to calculate the organ dose rate from radionuclides other than noble gases:
Do ~i[(Pi)( X/Q)SBW (Qi)] (3-3) where the value that has changed is:
( X/Q)SBW 8.9lxLO~, the highest calculated
. annual average dispersion parameter, in sec/m , at the Site Boundary, for any of the three units.
Explanation 3.3 See Explanation 3.2 3-2
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PVNGS Semi-Annual Operating Report Eor January - June l,986 Change 3.4:
Revision 0, Table 3-2, "Palo Verde Nuclear Generating Station Unit 1 Dispersion Parameters for Long Term Releases at the Site Boundary", contains X/Q and D/Q values for Unit 1.
Revision 1, Table 3-2, contains 3 sheets with X/Q and D/Q values at the Site Boundary for distances and directions from the 3 units. Unit 1 values of X/Q and D/Q have been changed.
Explanation 3.4:
The Site Boundary X/Q and D/Q values have been recalculated based on the availability of 9 years of data from the PVNGS Meteorological Tower. Desert sigmas were used in the calculation. The X/Q and D/Q values used in Revision 0 are based on 5 years of data. The 9 year annual averaged meteorological dispersion parameters appearing in Table 3-2'f Revision 1 give a more accurate dose assessment for individuals in the offsite environs of PVNGS and a more accurate dose rate assessment in unrestricted areas.
The addition of Site Boundary X/Q values for Unit 2 and Unit 3 enables selection of the highest calculated annual average X/Q value for any of the three units for the gaseous effluent dose rate calculations of Section 3.0 of the ODCM. 'Ihe addition of Site Boundary X/Q and D/Q values. for Unit 2 and Unit 3 enables calculation of Unit 2- and Unit 3- specific doses in Section 4.0 of the ODQf.
Change 3.5:
Table 3-3, "Pi Values for the Palo Verde Nuclear Generating Station", contains the following changes in the isotopic listing of the values:
ODQf ODQf Rev. 0 Rev. 1 H-3 H-3 Cr 51 Mn-54 Mn-54 Pe-59 Pe-59 Co-58 Co-58 Co&0 Co&0 Zn-65 Sr-89 Sr-89 Sr 90 Sr 90 Zr 95 Sb-124 I-130 I-131 I-131 I-132 I-133 I-133 3-3
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PVNGS Semi-Annual Operating January - June 1986 Report'or ODCM ODCM Rev. 0 Rev. 1 I-134 I-135 Cs-134 Cs-134 Cs-137 Cs-137 Sa-140 Ce-141 Ce-144 Explanation 3.5:
The revised list of isotopes closely reflects the isotopes which can be expected in gaseous effluents from PVNGS 'nd which are described in PVNGS Technical Specifications.
3-4
I PVNGS Semi-AnnuaL Operating Report for January,- June 1986 4.0 DOSE DUE TO GASEOUS EFFIUENT Change 4.1:
Revision 0 titles Section 4.0 "Dose Due to Gaseous Effluent (AIR)". Revision 1 changes the title to "Dose Due to Gaseous Effluent".
Explanation 4'1:
Change is editorial.
Change 4.2:
Revision gaseous 0 states effluents that "the air from the site dose . " due to noble shall be determined
=-
gases released in by the following equation". Revision 1 states that the air dose is calculated based on the effluent from each unit during any specified time period (emphasis added).
Explanation 4.2:
This change emphasizes that these dose limits are app1ied to each reactor unit and that the dose calculations (equations 4-1 and 4-2) will be calculated for each unit.
Change 4.3:
Equations 4-1 and 4-2 (gamma and beta air dose, respectively) have changed as follows:
Revision 0 states:
D~
- ~ (3.17 x 10~) ~i [(Mi) (X/Q)SB(Qi)]
and by the following equation for beta radiation during any specified time period:
DS (3.17 x 10 8) Ei [(Ni) (X/Q)SB(Q Revision 1 states:
For gamma radiation:
Dg (3.17 x 10 8) ~i [(Mi) (X/Q)SBu(Qi)]
u For beta radiation:
D gu (3.17 x 10 8) Ei [(Ni) (X/Q)SBu(Qi) ] (4-2)
The definition of the variables which changed are listed below.
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PVNGS Semi-Annual Operating Report for January - June 1986 Revision 0 states:
(X/Q)Sg 5.49 x 10 6 sec/m3, the highest calculated annual average relative concentration for any sector at the site boundary (sec/m ) from Table 3-2.
Revision 1 states:
(X/Q)SP the highest calculated. annual average dispersion parameter, in sec/m , 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 Explanation 4.3a:
This change was made to accommodate the multi~nit site. The X/Q from Revision 0 was centered on Unit 1 and based on 5 year data; the three X/Q's used in Revision 1 are centered on each unit and based on 9 year data.
Change 4.3b:
Revision 0 states:
the integrated release of each identified. noble gas radionuclide, i, in gaseous effluents for a specified time period in uCi.
Revision 1 states:
Qi the integrated release, from the particular unit, in u Ci, of each identified noble gas radionuclide i,, in gaseous effluents for a specified time period.
Explanation 4.3b:
This change accommodates the multimnit site and clarifies that the release from the particular unit is to be used to calculate the highest dose delivered by the unit at the site boundary.
Change 4.4:
Revision 0 states:
A discussion of the method used to calculate the individual dose from gaseous effluents is given in Appendix A. Also, Appendix A includes sample calculations for determining gamma and beta air doses from noble gas radionuclides released from the PVNGS.
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PUNGS Semi-Annual Operating Report for January - June 1986 Revision 1 deletes the sample calculations from Appendix A.
Change 4.5:
Revision 0 states:
The dose to an individual from I-131, I-133, tritium, and all radionuclides in particulate form, with half-lives greater than eight days, in gaseous effluents released to unrestricted areas is calculated using the following expressions:
Revision 1 states:
The organ dose to an individual from I-131, I-133, tritium, and all radionuclides in particulate form, with half-lives greater than eight days,. in gaseous effluents released to unrestricted areas from each reactor unit is calculated using the following expressions:
Explanation 4.5:
These changes clarify that:
1 organ doses are to be calculated and
- 2. the doses are to be calculated on a per unit basis.
Change 4.6:
Change in equation 4-3.
Revision 0 states:
o e (3.17 x 10"8) E i [ E g (Rig ~e)(qi)] (4 3)
Revision 1 states:
Dou (3.17 x 10 8) E i[ E g(RiIt Wk) (qi)~
Where the variables that change in equation 4-3 are defined as:
in Revision 0:
Doe the total pro)ected dose from gaseous effluents to an individual, in mrem, at the nearest residence in Sector 8 .
in Revision 1:
Dou the total accumulated organ dose from gaseous effluents f'r a particular unit, to a MEMBER OF THE PUBLIC, in mrem, at the SITE BOUNDARY or at the controlling location.
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PVNGS Semi-Annual Operating Report for January - June 1986 Explanation 4.6a:
The revised wording clarifies the meaning of the dose calculated, Dou, and emphasizes that the doses are calculated baaed on the effluents from a particular unit. 'Ihe doses are calculated for a MEMBER OF THE PUBLIC at the site boundary or the controlling location. The controlliag location is the location where an iadividual will receive the, highest dose. Further discussioa of the controlling locatioa and its selection is found in Appendix A to Revisioa 1 of the PVNGS ODCH.
Other variables that change in equation 4-3 are ia Revision 0:
Qi the amount of radioiodines, radioactive materials in particulate form, aad radionuclides other than noble gases with half-lives greater than eight days, 1, released in gaseous effluents, in UC1 ~
ia Revision 1:
the quantity of radionuclide 1, in uC1, released in gaseous efflueats from a part1cular unit.
Explanation 4.6b:
The revised wording is an editorial simplification which emphasizes that the source term, Qi, 1s that from the particular unit of interest.
Meteorological dispersion variables that chaage ia equatioa 4-3 are as follows:
Rev1sion 0 states:
the highest annual average d1spersion parameter for any sector, used for estimating the dose to an individual at the maximally exposed, closest residence ia Sector 8 and for pathway k.
X/Q for the inhalatioa pathway, includ1ng tritium, in sec/m3.
The highest X/Q for the nearest residence to PVNGS is 3.92x106 sec/m3, given in Table 4-16 and occurs in the N sector. (For the s1te boundary, use the X/Q for the N sector from Table 3-2.)
Wk8 D/Q for the food and grouad plane pathways, in m 2. 'Ihe h1ghest D/Q for the nearest residence to PVNGS is 3.87x109/m2 as given in Table 4-16 and occurs in the NE sector. (For the site bouadary, use the D/Q for the NE sector from Table 3-2) ~
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PVNGS Semi-Annual Operating Report for January - June 1986 Revision 1 states:
the highest anaual average dispersion or deposition parameter for the particular uait, used for estimating the dose at the site boundary or to a MEMBER OP THE PUBLXC at the controlliag location for the part1cular uait.
( X/Q)SBU>> in sec/m for the inhalation pathway and for all trit1um calculations, for organ dose at the site boundary, from Table 3-2.
7.47x106 from Unit 1 7.90x106 from Unit 2 8.91x10~ from Unit 3
( X/Q)RU, in sec/m for the iahalation pathway and for all tritium calculations, for organ dose at the contro111ng location, from Table 4-16.
2.92x10~ from Unit 1 2.19x10 6 from Uait 2 2.31x106'from Unit 3
( D/Q)SBU, in m , for the food and ground plane pathways, for organ dose at the site bouadary, from Table 3-2.
1.19x10 8 from Unit 1 1.34x108 from Unit 2 1.67x10+ from Uait 3
( D/Q)Ru, in m 2, for the food aad ground plane pathways, for organ dose at the controlliag location, from Table 4-16.
3.25x109 from Unit 1 3.88x10 10 from Unit 2 4.21x10 10 from Unit 3 Explanation 4.6c:
The change 1n dispersion variables is as a result of a more complete data set (9 years vs. 5 years) and as a result of change in methodology for dose calculat1ons. Revision 1 uses the actual locations identified in the annual land use ceasus for dose calculation. This methodology presents a more accurate and realistic model of poss1ble radiation exposure pathways in the:>> offsite enviroas of PVNGS.
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PVNGS Semi-Annual Operating Report for January -'une 1986 Change 4.7:
Revision 0 states:
In order to provide a conservative estimate of the doses, each of the nearest residences is assumed to have a milk animal, a meat animal, and a vegetable garden. They provide the maximally exposed individual with 100X .of. his dietary intake.
Revision 1 states:
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.
Explanation 4.7:
The revised ODCM (Rev. 1) provides a more realistic and therefore more accurate methodology for dose calculations at the nearest resident, garden, and milk animal The Revision 0 methodology was extremely conservative and assumed that a milk animal, meat animal, and vegetable garden existed at the nearest residence. Such is not an accurate representation of the desert around the PVNGS. The Revision 1 methodology uses the actual locations identified during the annual land use census for mQ.ch and meat animals, vegetable gardens, and residences. The controlling location for a given unit is that location which will result in the highest dose from that unit through realistic and existing exposure pathways. The use of the .controlling location-is a more realistic and therefore more accurat'e method to assess the dose delivered to a member of the public from PVNGS operations.
Change 4.8 4.3 DOSE PROJECTION Revision 0 contains no introductory statement.
Revision 1 states:
Where possible, consideration for expected operational evolutions (i.e.,
outages, etc.) should be taken in the dose progections.
Explanation 4.8:
This change in the text of this section introduces the change in methodology for calculating dose progections in equations 4A and 4-5. Revision 0 does not contain a provision to include planned occurrences in the dose projection.
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PVNGS Semi-Annual Operating Report for January - June 1986 Change 4.9:
Revision 0 states:
"3he air dose in unrestricted areas beyond the site boundary due to noble gases released in gaseous effluents from the site shall be pro)ected by the following equation for gamma radiation at least once per 31 days:
Revision 1 states:
Noble Gas Dose Pro ection Por the purpose of satisfying requirements of Technical Specification 3.11.2.4, 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.
Explanation 4.9:
Mitorial changes in text and added emphasis of the per unit basis of the dose pro)ection.
Change 4.10:
The method for pro)ecting doses has changed in Revision 1 of the ODCM.
In Revision 0 the dose was pro)ected using equations 4-1 and 4-2 for beta and gamma air dose calculation as follows:
Revision 0:
y(3 17x10) i [(Mi)(X/Q)S>(pi)]
Dg (3 17 x 10 ) i [(Ni) (X/g)Sp (gi)]
where:
gi ~ the integrated release of each identified noble gas radionuclide, i, in gaseous effluents during the previous month in uCi and the other values in these equations have been previously explained.
Revision 0 further states that "The pro)ected gamma air dose and beta air dose for each month shall be calculated using the previous month's release of each identified noble gas radionuclide."
I In Revision 1 of the ODCM the dose is projected for the next 31 days based on a 31 day pro)ection of the average daily air dose for the current quarter plus the anticipated dose from operational evolutions (i.e., outages, etc.).
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'i PVNGS Semi-Annual Operating Report for January - 'June 1986 Revision 1 calculates the projection using the following equations:
Por gamma radiation:
31 day> (D> qtr/Tqtr) 31 + CD (4-4)
Por beta radiation:
31 dayS (DS qtr/Tqtr) 31 + CD) where:
D> qtr the total gamma air dose due to noble gases released in gaseous effluents for the current quarter, in mrads, at the site boundary.
DS 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 D> qtr and D> qtr were integrated.
31 the number of days over which the dose projections are made.
31 day> the 31 day projected gamma air dose due to noble gases released in gaseous effluents, in mrads, at the site boundary.
31 day< the 31 day projected beta air dose due to noble gases released in gaseous effluents, in mrads, at the site boundary.
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>
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 dayS Explanation 4.10:
This change allows the consideration of planned operational occurrences to be included in the dose projection.
Change 4.11 Organ Dose projection:
Similarily, in Revision 0 the dose from I-131, I-133, tritium and all radionuclides in particulate form other than noble gases was projected using the equation 4-3 which appears in Change 4.6.
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PVNGS Semi-Annual Operating Report for January - June 1986 where:
gi the integrated release of radionuclide, i, released in gaseous effluents, in uCi, during the previous month.
Revision 1 prospects organ doses by calculating a 31 day pro)ection of the average daily organ dose for the current quarter plus the anticipated dose from operational evolutions (i.e., outages, etc.) Revision 1 calculates the progectioas using the following equation:
31 day o (Do qtr/Tqtr)31 + CDo (4-6) where:
Do qtr the total organ dose from a particular unit due to I-131, I-133, tritium, aad all radioauclides 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 Doqtr was integrated.
31 ~ the number of days over which the dose projections are made.
31 dayo the 31 day projected organ dose, in mrem, from a particular unit.
CDo any curreat or pro)ected organ dose for a particular unit in mrem, which could have a sigaificant impact on 31 dayo.
Explanation 4.11:
This change allows the consideration of planned operational occurrences to be iacluded in the dose projection.
Change 4.12:
Tables 4-1 through 4-15, "R Values for the Palo Verde Nuclear Generatiag Station" are revised in Revision 1 of the ODCM.
The R values ia these tables have changed because of the changes ia both the biological buildup time and environmental transport time used to calculate these values. Revisioa 1 of the ODCM contains R values which more closely comply with NUREG-0133.
Change 4.13:
Certain nuclides have been'dded in Revision 1. Iodine-130, Iodine-132, Iodine-134 and Iodine-135 have beea deleted. The revised nuclide listing reflects nuclides which can be expected to occur and which are described in Technical Specification 3.11.2.3.
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PVNGS Semi-Annual Operating Report for January - June 1986 Change 4.14:
Revision 0, Table 4-16, "Palo Verde Nuclear Generating S tati on Unit 1 Dispersion Parameters for long-term releases at the Nearest residences",
contains X/Q and D/Q values for Unit l.
Revision 1, Table 4-16, contains 3 sheets with X/Q and D/Q values at the nearest pathway locations for distances and directions from the 3 units.
Values are t'abulated for residences, gardens and milch animal locations. Unit 1 values of I/Q and D/Q have been changed. Some Unit 1 distances have been changed. Dispersion and deposition values are tabulated for all 16 direction sectors. Distances are tabulated in another Table.
Explanation 4.14 Pathway location X/Q and D/Q values have been calculated on 9 years of meteorology data versus 5 years, as in Explanation 3.4. The tabulation of X/Q and D/Q values for Units 2 and 3 enables calculation of Unit 2- and Unit 3-specific doses in Section 4.2 of the ODCM IKstances from pathway locations to the three units are as determined in the latest (as of submission of ODCM for Unit 2 licensure) Land Use Census, and have been moved to Table A-1 in order to make space in Table 4-16 for garden and milk dispersion and deposition values The location within the ODCM of the distance values is footnoted in Table 4-16. Distance values are given, in Table A-1 for the nearest residence, garden and milch animal in each of 16 sectors for each unit.
The provision of X/Q and D/Q values for garden and milk pathway locations enables determination of controlling location for each unit, and enables a more accurate and realistic calculation of dose in Section 4.2 of Rev. 1 of the ODCM.
All 16 22-1/2 degree compass sectors are presented in Table 4-16. Where the Land Use Census identified a lack of residences, gardens or milch animals for a sector and within 5 miles of a particular unit, these pathway locations were assigned at 5 miles for that particular sector of that particular unit, except that the nearest garden and cow south of Unit 1 are located at 5.2 miles and 5.1 miles respectively and are calculated at these distances. This is location 12 from the 1984 Land Use Census. Location 12 is not the controlling location for Unit 1;. see discussion of change A.l. Location 12 is the controlling location for Units 2 and 3, but its residence, garden and cow are less than or equal to 5 miles distance from Units 2 and 3; see Table A-l, Sheets 2 and 3, of the ODCM, Rev. 1.
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PVNGS Semi-Annual Operating Report for January - June 1986 5 0 TOTAL DOSE Change 5.1 Revision 0 contains no introductory statement Revision 1 states:
"Since all other uranium fuel cycle sources are greater than 20 miles away, only the PVNGS site needs to be considered.
The total dose to any MEMBER OP 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 F 11.2.3.
Explanation 5.1!
This change provides a narrative explanation of the purpose and scope of calculations used to evaluate the total dose delivered to a member of the public from the operation of the three PVNGS units.
The format of Section 5.0 of Revision 1 of the ODCM has changed to accommodate the change in this section's scope. Revision 1 includes not only a submection pertaining to "Doses from Releases" (Section 5.1.1) but also "Dose Due to Direct Radiation (Section 5.1.2) and "Dose to Public Onsite" (Section 5.2).
Change 5.2:
The equation used to calculate the total whole body and skin dose (equations 5-1 and 5-2 has changed as follows:
Revision 0 states:
D b (3.17 x 10 8) ~ i [(Ki) (X/Q) e (Qi)] (5-1) or:
Dsk (3.17 x 10 8) ~ i [(Li + 1.~)(X/Q)e (Qi)] (5-2) 5-1
~
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PVNGS Semi-Annual Operating Report for January - June 1986 where the variables that will change are:
Qi sm The release of radionuclide, i, in uCi for a specified time period.
(x/Q) e 3.92x108 sec/m3, the highest calculated annual average relative concentration for the nearest residence of any sector from Table 4-16.
Db the annual whole body dose ia mrem/yr due to gamma emissioas.
Dsk
~ the annual skin dose in mrem/yr.
Revision 1 states:
(3.17 x 10 ) i [(Ki) (X/Q)RU (Qi)] (5-1) where the variables that have changed are:
The integrated release of radionuclide i, in uCi for the previous calendar year.
(X/Q)RU The highest calculated annual average dispersion parameter, in sec/m3, for a particular uanit, at the controlling location, from Table 4-16, or concurrent meteorological data if available.
2.92x106 from Unit 1 2s19x106 from Unit 2 2.31x106 from Unit 3 The annual whole body dose in mrem to a MEMBER OP THE PUBLIC at the controlling location due to noble gases released in gaseous effluents.
Explanation 5.2:
The changes to the equation for calculating total whole body dose in Revision 1 were made to accommodate the multi~t site aad to consistently use the controlling location methodology. The controlling location selection methodology is explained in Appendix A of the OD(Z, Rev. 1, and in Explanations 4.7 and Ael of this report.
It should be noted that the ODCM, Rev. 1 does not contain a method to calculate the total skin dose from noble gases. The PVNGS Technical Specification 3.11.4, which requires the calculation of total dose, assures PVNGS compliance with 40CPR190. This regulation specifies dose limits to the whole body, thyroid aad any other organ from uranium fuel cycle operatioas within 8 km. of PVNGS.
However "organ", as defined in 40CPR190.02.i, "means any human organ exclusive od the dermis, the ~eidenais, or the cornea" ~ (emphasis added). Therefore PVNGS does not calculate the dose to the skin for compliance to this Technical Specification.
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PVNGS Semi-Annual Operating Report for January - June 1986 The exponent given on the (X/Q)8 value defined for equatioas (5-1) and 5-2) of Revision 0 was a typographical error.
0 Change 5.3:
The equation used to calculate the total dose to the critical organ of an individual (equation 4-3, Rev. 0) has. changed as follows:
Revision 0 states:
Doe (3.17x10 g) Zi[ Ek (Rik Wkg)(Qi)] (4-3) where the variables that will change are:
Doe the total pro5ected dose from gaseous effluents to an individual, ia mrem, at the nearest residence in Sector 8.
the integrated release of radionuclide i, released in gaseous effluents in uCi for a specified time period.
Wk the"highest annual average dispersion parameter for any sector, used for estimating the dose to an individual at the maximally exposed closest residence in Sector 8 and for pathway k.
WK8 I/Q for the inhalation pathway, in sec/m 3 . The highest I/Q for the nearest resideace, 3.92x10~ sec/m3, is given in Table 4-16.
Wke 3.92 x 10~ sec/m , I/Q for the dose contribution for tritium in all pathways.
D/Q for the food and ground plane pathways, in m 2.
The highest D/Q for the nearest residence occurs in sector NE, and is givea in Table 4-16 as 3.87 x 10 9/m2 Revision 1 states:
Do (3'17xl0~) i[ k (Rik Wk )(Qi)] (4-3)-
Where the variables that have changed are:
Do the total annual organ dose from gaseous effluents to a MEMBER OF THE PUBLIC, in mrem, at the coatrolling location.
Qi the integrated release of radionuclide i, in uCi, for the previous calendar year.
WK 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.
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PVNGS Semi-AnnuaL Operating Report far January - June 1986
( X/Q)RU, in sec/m3 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.
2.92x106 from Unit 1 2.19x10 6 from Unit 2 2.31x10 6 from Unit 3 (D/Q)RU, in m 2, for the food and ground plane pathways, for organ dose at the coatrolling location, from Table 4-16 or concurrent meteorological data if available.
3.25x10 9 from Uait 1 3.88x10 10 from Unit 2 4.21x10 10 from Unit 3 Explanation 5 3 The changes to the equat1on for calculating total organ dose in Revis1oa 1 were made to accommodate the multimnit site and to consistently use the controlling location methodology. The controlling location selection methodology is explained in Appendix A of the ODCM, Rev. 1, and in Explanations 4.7 and A.l of this report.
Change 5.4 Dose Due to Direct Radiation Revisioa 0 states:
The d1rect radiation from the site should be determined from the environmental monitoring program's direct radiation (TLD) monitors (compr1sed of a network of TLDs). Since all other uranium fuel cycle sources are greater thea 20 miles away, only the PVNGS s1te need be considered as a uran1um fuel cycle source for meetiag the EPA regulations.
Revisioa 1 states:
The component of dose to a MEMBER OP THE PUBLIC due to direct radiat1on will be evaluated by first determining the direct radiat1on dose at the site boundary in each sector, and then extrapolating the site boundary dose to the controlling locat1on by the inverse square law of distance.
Explanation 5 '
Revis1on 1 more explicitly states the method to be used ia evaluating doses to members of the public from direct radiation.
Change 5.5 Dose to Public Onsite
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PVNGS Semi-Annual Operating Report for January - June 1986 Revision' 0 states:
Technical Specification 6 '.1.8 For the purpose of evaluating the dose to MEMBERS OF THE PUBLIC due to their activit1es within the SITZ BOUNDARY the preceding calculations w111 be used. These activities have been determined to be limited to the vicinity of the Visitor Center located neer the SITZ BOUNDARY west of Unit 1. An assumption was made that no MEMBER OF THE PUBLIC would spend more than eight hours per year at this location which is 0.1X of the annual occupancy of a MEMBER OF THE PUBLIC at the SITE BOUNDARY The most restr1ctive X/Q value vill be used for this calculation.
Revision 1 states:
For the purpose of evaluating the dose to MEMBERS OF THE PUBLIC due to the1r activities within the SITE BOUNDARY the following methodology will be used. Mesc activities have been determined to be limited to the vicinity of the V1sitor Center located 1nside the SITE BOUNDARY west of Unit 1. An assumption was made that no MEMBER OF THE PUBLIC would spend more than eight hours per year at this location.
X/Q, determined for the Visitor Center, will be used for this assessment.
Equations 5-1 and 4-3 in Sections 5.1.1 and 5.1.2 should be used for this assessment. Qi should be the integrated release of radionuclide 1, 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 Qi)."
Explanation 5.5 Rev1sion 1 contains several changes from Revision O. They are included below.
aO Revision 1 specifies the exact equations and def1nit1ons to be used.
- b. Revision 1 identifies the fact that the Visitors Center is located within the site boundary.
Co Revision 1 states that the source term for this dose calculation is based on the annual release rate of radionuc11des integrated over 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
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PVNGS Semi-Annual Operating Report for January - June 1986 6 0 OPERABILITY OF E UIPMENT Revision 0 of the ODCM contains schematic drawings of the liquid, gaseous and solid radiological waste management systems (Figures 6-1 through 6-3). 'these drawings are reduced copies of those in the PVNGS FSAR.
Revision 1 of the ODCM contains a simplified flow diagram of the liquid radiate management systems with no change being made in the essential information presented (Figure &-1).
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l PVNGS Semi-Annual Operating Report for January - June 1986
- 7. 0 RADIOLOGICAL ENVIRONMENTAL PROGRAM Minor editorial changes have been made in this section. Revision 1 contains no additional information or new commitments. Table 7-1, "Radiological Environmental Monitoring Sample Collection Locations", in Revision 1 contains several changes from Revision O. The major change is the addition of two sampling locations for citrus and vegetation (sample locations 61 and 62). The other change is the relocation of the REMP laboratory offsite to Buckeye, Arizona-(20 miles east of PVNGS), and the consequent change in locating the control TLD (845). Minor changes have occurred in this table to more closely reflect sample locations currently in use (i.e., names of sample locations have changed to reflect current ownership, more explicit sample location descriptions have been used, and sample location distances to PVNGS have been corrected).
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PVNGS Semi-Annual Operating Report for January - June 1986 APPENDIX A Change A.l.
Revision 0 contained sample calculations.
Revision 1 de1etes the sample calculations, and adds a discussion of determination of controlling location and Table A-1 (sheets 1, 2 and 3, for Units 1, 2 and 3). Table A-1 gives locations of the nearest residence, garden and milch animal in each of the 16 compass sectors for each of the 3 units Explanation A.l Table A-1 gives results of the 1984 Land Use Census, which is the most current one prior to submission of the ODCM for Unit 2 licensure.
The discussion of determination of controlling 1'ocation summarizes work performed by a consultant to identify the'ontrolling location for each Unit.
Further explanation of this work follows.
ANPP supplied consultant with a map and tables (based on the 1984 annual land use census) identifying all the residences within a S~ile radius of the Palo Verde Plant. The residences that had vegetable gardens and milch animals (cows or goats) were identified by ANPP on the map and tables.
The atmospheric dispersion parameters in the form of X/Q and D/Q data based on the annual average meteorology for the 9 year period of record were calculated by consultant, using the XOQDOQ computer code in accordance with NRC
.Regulatory Guide 1.111, Rev. 1 assuming a ground release.
three sets of fiftieth percentile X/Qs and D/Qs for the thxee units were calculated for the closest residence, vegetable garden and milch animal within each sector. Por each unit the highest values of meteorological parameters (undecayed/undepleted X/Q and D/Q) were identified for the gardens and milch animals, and the highest X/Q was identified for the residences. The reason for considering the highest X/Q for the gardens and milch animals is because tritium is a significant contributor to dose. Bate reason for considering the highest X/Q for the residences is because inhalation is the major dose pathway.
Of all the residences, the one at location number 13 had the highest X/Q for releases from units 1, 2 and 3 and was therefore identified as a possible controlling location. Of all the gardens, the ones at location numbers 2 and 3 had comparatively the highest X/Q and D/Q and were therefore identified as possible controlling locations. The D/Q for location S is slightly highex (by 1X) than for location 3 while the X/Q for location 5 was 40% lower than location 3. Location 5 was therefore not identified as a possible controlling location. Since there is only one cow at location 12 and one goat at location 9, within the fivemile xadius, they were identified as possible controlling locations.
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PVNGS Semi-Annual Operating Report for January - June 1986 Thus by scanning the X/Q-D/Q table, five possible controlling locations were identified:
- 1. Vegetable garden at location 2 in the North direction at 1.56, 1.70 and 1.88 miles from Units 1,' and 3, respectively.
2~ Vegetable garden at location 3 in the North direction at 1.41 miles from unit one, and in the North Northeast direction at 1.50 and 1.75 miles from Units 2 and 3, respectively.
- 3. Milk Animal Goat at location 9 in the East Southeast direction at 4.59 and 4.75 miles from Units 1 and 2, respectively and in the East direction at 4.45 miles from Unit 3.
- 4. Milk Animal - Cow - at location 12 in the South direction at 5.13, 5.0 and 4.78 miles from Units 1, 2 and 3, respectively.
- 5. Residence at location 13 in the South Southwest direction at 3.45, 3.25 and 3.13 miles from Units 1, 2 and 3, respectively.
Selection of two gardens as possible controlling locations is because of the directional variance of location 3 resulting from centering the directional grid on the three units. The North directional sector in general, has a higher X/Q than the North Northeast directional sector causing location 2 to have a higher X/Q than location 3 when the directional grid is centered on units 2 and 3, even though garden 2 is more distant than garden 3 and is in the same general direction from the reactor buildings. However, when the directional grid is centered on Unit. 1, both locations 2 and 3 lie in the North sector and location 3 results in a higher X/Q.
To determine, which of the five critical receptor locations identified earlier is the controlling location, GASPAR computer code was run for releases from each unit, using the 9~ear meteorological parameters calculated by XOQDOQ computer code.
The annual source term used was from PVNGS ERAL Table 3.5-12. However, noble gases and carbon-14 were omitted since they are excluded from ODCM Equation (4-3) analyses. Dose pathways were determined for each of the five possible controlling locations. For locations 2 and 3 (vegetable garden at a residence) the pathways were ground exposure, vegetable ingestion and inhalation For location 9 (goat and vegetable garden at a residence) and location 12 (cow and vegetable garden at residence) the pathways were ground exposure, vegetable ingestion, milk ingestion and inhalation. For location 13 (residence) the pathways were ground exposure and inhalation.
By inspection of the computer outputs, in comparing location number 9 (goat and vegetable garden at a residence) to location number 12 (cow and vegetable garden at a residence), location number 9 was re)ected since its milk pathway doses were lower due to a lower X/Q and D/Q. Location number 13 (residence) was also re)ected since its inhalation pathway dose was found to be lower than.
the vegetable ingestion pathway dose at location number 12.
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PVNGS Semi-Annual Operating Report for January - June 1986 Cumulative doses for all applicable pathways to the maximum organ (thyroid) for location numbers 2, 3 and 12 were compared. Location number 3 resulted in the highest cumulative organ dose for releases from unit one. Location number 12 resulted in the highest cumulative organ dose for releases from units 2 and 3 Therefore it was concluded, that location 3 (vegetable garden at a residence) was the controlling location for releases from unit 1, and location 12 (cow and vegetable garden at a residence) was the controlling location for releases from both Units 2 and 3.
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APPENDIX E REVISED OFFSITE DOSE CALCULATION MANUAL (ODCM)
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OFFSITE DOSE CALCULATION MANUAL PALO 'VERDE NUCLEAR GENKtATING STATION UNITS 1, 2 AND 3 Dept. Head:
Date:
PRB Chairman:
Date:
Plant Manager:
Date:
Date Effective: Oi ..i ~- fV 0311M; 6064A/0015K CONTROLLED BY USER I
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CONTROLLED BY USER OFFSITE DOSE CALCULATION MANUAL PALO VERDE NUCLEAR GENERATING STATION'NITS 1 2 AND 3 TABLE OF CONTENTS SECTION TITLE PAGE
1.0 INTRODUCTION
l>>l 1.1 Liquid Effluents 1-1 1.2 Gaseous Effluents 1-3 1.3 Nuisance Pathways 1W 2.0 GASEOUS EFFIUENT 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 2W 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 4.0 4-1 y DOSE DUE TO GASEOUS EFFLUENT 4.1 Noble Gases 4-1 4.2 Iodine-&1, Iodine-333, 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 S-l 5.1 Technical Specification 3.11.4 5-1 5.2 Dose to Public Onsite 5-4 6.0 OPERABILITY OF EQUIPMENT 6-3.
7.0 RADIOLOGICAL ENVIRONMENTAL PROGRAM 7-1 7.1 Radiological Environmental Monitoring Program 7-1 7.2 Land Use Census 7-2 7.3 Interlaboratory Comparison Program 7-3 APPENDIX A DETERMINATION OF CONTROLLING LOCATION A-1 i
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CONTROLLED BY USER OFFSITE DOSE CALCULATION MANUAL PALO VERDE NUCLEAR GENERATING STATION UNITS 1 2 AND 3 List of Tab1es TITIZ 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 Pi 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 4-3 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY ~ VEGET, AGE GROUP ~ TEEN 4-4 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY ~ VEGET, AGE GROUP ~ CHILD 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 4-7 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY ~ MEAT, AGE GROUP ~ CHILD 4-16 4-8 R 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
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I CONTROLLED BY USER OFFSITE DOSE CALCULATION MANUAL PALO VERDE NUCLEAR GENERATING STATION UNITS 1 2 AND 3 List of Tables (Continued)
TITIZ PAGE R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY ~ COW MILK, AGE GROUP INFANT 4-20 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY INHAL, AGE GROUP ~ ADULT 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 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 7-1 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS (4 SHEETS) 7-4 7-2 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS (2 SHEETS) 7-8 7~3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 7-10 A-1 EXPOSURE PATHWAY LOCATIONS (3 SHEETS) A-2 CONTROLLED BY USER 09nol85
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CONTROLLED BY USER OFFSITE DOSE CALCULATION MANUAL PALO VERDE NUCLEAR GENERATING STATION UNITS 1 2 AND 3 List of Fi ures FIGURE IIIIE PAGE 2-1 Calibration Curve for PVNGS Effluent Monitors RU-141, RU-143, and RU-145. Response t'o Noble Gas. 2-9 2-2 Initial Calibration Curve for PVNGS Monitor RU-12. Response to Kr-85 Gas. 2-10 6-1 Process Flow Diagram Liquid Radwaste System (Sheet 1 of 2) 6-2 6-1 Process Flow Diagram Liquid Radwaste System (Sheet 2 of 2) 6-3 6-2 Basic Flow Diagram Gaseous Radwaste System 6-3 Basic Flow Diagram Solid Radwaste System 6-5 7-1 Radiological Environmental Monitoring Program Sample Sites, 0 to 5 miles 7~2 Radiological Environmental Monitoring Program Sample Sites, beyond 5 miles
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CONTROLLED BY USER
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 1, 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,'n addi'tion 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 Effluents 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'asin 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.
Th'e groundwater in the site area consists of an extensive regional aquifer and 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 CONTROLLED BY USER
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CONTROLLED BY USER north to south. Infiltration of precipitation, surface runoff, and return flow from irrigation constitute a small portion of 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 beche such that the likelihood of a liquid effluent pathway increases, then dose calculation methodology for this pathway will be added to this manual.
1-2 Rev. 1 CONTROLLED BY USER
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CONTROLLED BY USER 1.2 Gaseous Effluents 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, not depending upon atmospheric conditions or time of day. 3he releases are lumped together and calculated as an entity. The historical annual average X/Q is therefore used throughout this manual for all gaseous effluent set~oint and dose calcuLations. Airborne releases are further subdivided into two subclasses:
1.2.1 Iodine - 131 Iodine - 133 Tritium and Radionuclides in Particulate Form with Half-lives Greater than Eight
~Da s In this model, a controlling location is identified 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.
1-3 CONTROLLED BY USERo~griog85
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CGNTRGLLED BY USER 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 3.11.2.3.. Methods are described for determining the annual cumulative dose to a MEMBER OF THE PUBLIC, from gaseous effluents and direct radiation for critical organs, to assure compliance with Technical Specification 3.11.4..
The Radiological Environmental Monitoring Program is described in this manual; also included is the Annual Land Use Census Survey.
The ODCM 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 ODCM 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 lOX 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. The doses from these nuisance pathways will periodically be evaluated to ensure that they do not contribute more than 10K of the doses evaluated in this manual. If any nuisance pathway exceeds this limit then the ODCM methodology for calculation of doses will be applied to each applicable release pathway.
1"4 CQQTRQLLED.BY USEl@rio<8~ ,~ ~ )>> .<> lASOWIAI
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CONTROLLED BY USER T+LE 1-1 NUISANCE PATHWAYS Evaporation Pond Cooling Towers Laundry Building Exhaust Unmonitored Secondary System Steam Vents/Reliefs Turbine Building Ventilation Exhaust Unmonitored Tank Atmospheric Vents 1 5 CONTROLLED BY USER "'"'"
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CGNTRGLLED BY USER 2 0 GASEOUS EFFLUENT MONITOR SETPOINTS Technical S ecification 3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 [of the Technical Specifications] shall be OPERABLZ 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 pCi/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. 80K 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 xelease.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 (pCi/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 3.3.3.9, 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.
2-1 CGNTRGLLED BY USER"'""'
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CONTROLLED BY USER The evaluation of doses due to releases of radioactive material can be simp1ified by the use of equivalent dose factors as defined in Section 2.1.
The equivalent dose factors will be evaluated periodically to assure that the best information on isotopic distribution is being used for the dose equivalent value.
2.1 uivalent Dose Factor Determination The equivalent whole body dose factor is calculated as follows:
K, - Z [(K )(f )] (2-1)
Where:
K the equivalent whole body dose factor weighted eq by historical radionuclide distribution in releases.
Ki the whole body dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrem/yr perp Cilm3 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:
(Z,+l.m)eq - Z ((L +1.M )(f )] (2-2) 2-2 CONTROLLEO BY USER""'"'
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(L+l.m)eq the equivalent skin dose factor due to beta and gamma emissions from all noble gases released, weighted by the historical radionuclide distribution in releases.
Li the skin dose factor due to the beta emissions for each identified noble gas radionuclide i, in mrem/yr per 0 Ci/m3 from Table 3-1.
the air dose factor due to gamma emissions for each identified noble'gas radionuclide i, 3
in mrad/yr per PCi/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 SITE )
The release rates corresponding to 80X of the whole body (QW ) and, skin (QSK) dose rate limits are calculated using the equivalent dose factors defined in Section 2.1.
The site release rate limit (Q is the lower of QWB SITE )
or QSK, thus assuring that the more restrictive dose rate limit will not be exceeded.
The QSITE is established as follows:
(D )
QSITE, MB VB (0.8) (2-3)
X QSBW 2-3 CONTROLLED BY USERo9>>oi85
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CONTROLLED BY USER Where:
QSITE, WB the site release rate, in uCi/sec, that would deliver a dose rate 80X of the whole body dose rate limit, DWB.
WB whole body dose rate limit of 500 mrem/yr.
K eq equivalent whole body dose factor, in mrem/yr per pCi/m3 weighted by the historical radionuclide distribution.
-6 (X/Q)SBW 8~ 91X10, the highest calculated annual average dispersion parameter, in sec/m 3 , 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 variability in the radionuclide mix and to ensure that Site Boundary dose xate limits will not be exceeded.
D Q ( SK) (0.8)
SITE>SK L+lolH eq X Q (2-4 )
Whex'e:
QSITE,SK the site release rate limit, in p Ci/sec, that would deliver a dose rate 80X of the skin dose rate limit, DSK.
SK skin dose rate limit of 3000 mrem/yr.
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CGNTRGLLED BY USER (I,+l.ZZ) eq equivalent skin dose factor, in mxem/yr per 3
p Ci/m , weighted by the radionuclide distribution.
-6 (X /Q) 8.9lXl0, the highest calculated annual average dispersion parameter, in sec/m 3 ,,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 Q SITE whole body and skin dose ratees ose ra (equations 2-3 and 2W, resp'ectively), the most conservative result will be used as QSITE, the site release rate limit.
2.3 Unit Release Rate Limits ( IT- )
Typically QSITE will be divided equally among operating units. If operational history dictates a larger fraction of the QSITE be ass1gned to a specific unit then a weighted average of each unit's contribution to the Q SITE will be utilized to determine the Q UNIT'UNIT QSITE (2-S)
UNIT where:
unit release x'ate limit, 1n p Ci/sec.
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CGNTRGLLED BY USER UNXT the fraction ( < 1) of noble gas historically released from a specific operating unit to'he total of all noble gas released from the site.
the site release rate limit, in p Ci/sec determined in section 2-2 of this manual.
2.4 Set oint Determination To compLy with Technical Specification 3.3.3.9, the alarm/trip setpoints can now be established using the unit release rate limit (Q~>T) 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 I 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 monito~pecific characteristics.
2.4.1 Monitors RU-l.41 RU-143 and RU-145 The alarm/trip setpoint for Monitors RU-141, RU-143, and RU-145 is calculated as follows:
cfm )
( UNIT)(2.12a10 ~cc aec)(a) (2-6)
Monitor Setpoint (pCi/cc) <
(Flow Rate)
%here.
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.
2-6 CGNTRGLLED BY USER"'"',',
e I each 0 "A 4'%4J4~44e)aeJkeee
l CONTROLLED BY USER UNIT unit release rate limit, in P Ci/sec, as determined in Section 2.3.
Plow Rate the flow rate, in cfm, from flow rate monitors or the fan design flow rate for the release M source under consideration..
1 2.12XLO conversion factor, cubic feet/minute per cubic centimeter/second.
fraction of QUNIT 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 Paste Gas Decay Tank Monitor, is calculated as follows:
-3 cfm )
Monitor Setpoint (uCi/cc) < f( Q UNIT) (2.12xl0 cc/sec) (0.9)(a)J (2-7)
(Flow Rate) where:
Monitor Setpoint the setpoint for the monitor, in pCi/cc at STP, which provides a safe margin of assuzance that the allowable dose rate limits vill not be exceeded.
QUNIT unit release rate limit, in WCi/sec, as determined in Section 2.3.
Plow Rate flov rate, in cfm at STP at which the tank will be released.
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CONTROLLED BY USER fraction of ~UNIT s-Llocated 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.'3 2.12XLO ~ conversion factor, cubic feet/minute per cubic centimeterlsecond.
If there is no release associated 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 M.rborne 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 Paste Gas Decay Tank Monitor (RU-12) is based on Kr-85 calibration as indicated on Figure 2-2.
2-8 CONTROLLED BY USER9riai8~
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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&2-50-U(R) 2H CONTRGLLED BY USER
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10 10 10 Kr-85: 1.22(10 } cpa 10" per pCi/cc 6
CJ ca 10 A
10 10 10 10 10 10 10 ACTIVITY CONCENTRATION ( uCi/cc)
FIGURE 2-2 INITIAL CALIBRATION CURVE FOR PVNGS HONITOR RU-12 RESPONSE to Kr-85 GAS Reference. Kaman Instrumentation Corporation Calibration Report K-83-30-U(R) 2-lo CONTROLLED BY USER
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CONTROLLED BY USER 3.0 GASEOUS EPFLUENT DOSE RATE Technical S ecification 3.11.2.1 The dose rate due to radioactive 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. Por 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.
Por whole body dose rate:
%a i f(Ki) (X/Q)Sag (Qi)l (3-1)
Por skin dose rate:
DSK i ~(Li + 1 lMi) (X/Q)SBg (Qi)l (3-2) 3-1 CONTROLLED BY USERR.. ~
09/20/85
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CONTROLLED BY USER Where:
Ki the whole body dose factor due to gamma emissions for each identified noble gas
, radionuclide i, in mrem/yr per u Ci/m3 from
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Table 3-1.
the release rate of radionucli.de i, in p Ci/sec.
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~ SBW 8.91x10 , the highest calculated annual average dispersion parameter, in sec/m 3 , for any of the three units, from Table 3-2.
WB 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 3
mrem/yr per 0 Ci/m from Table 3-1.
the air dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrad/yr per tL Ci/m3 from Table 3-1 (conversion constant of 1.1 converts air dose-mrad to skin dose~rem).
SK the annual skin dose rate (mrem/yr).
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CONTROLLED BY USER 3.2 Radionuclides Other Than Noble Cases The methods for sampl1ng and analys1s of continuous and batch releases for I-131, Z-l33, tritium and radionuclides in particulate form w1th half-lives greater than 8 days, are given in the applicable plant procedures. Additional monthly and quarterly analyses shall be performed 1n 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:
Do 1 f (Pi) (X/q)SBW (q 1 ) ] (3-3)
Where:
3 the dose factor, in mrem/yr per WC1/m, for x'adionuclide 1, for the child inhalation pathway, fxom Table 3-3.
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(+~)SBW 8.9lxl0, the highest calculated annual average dispersion "parameter, in sec/m 3 , at the Site Boundary, for any of the three units, the release rate of radionuclide 1, in pCi/sec D
0 the total organ dose rate (mremlyr) ~
3-3 CO NTROLLED BY USER9na<85
I 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 Ki Li Mi Ni Radionuclide (mrem/yr per PCi/m3) (mrem/yr per PCi/m3) (mrad/yr per 4Ci/m ) (mrad/yr per PC )
Kr-83m 7.56E-02(b) 1.93E+01 2.88E+02 Kr-85m 1.17E&3 1.46E&3 1.23E&3 1.97E&3 Kr-85 l. 61E+01 1.34E&3 l. 72E&1 l. 95E&3 Kr&7 5.92E&3 9.73E+03 6.17E&3 1.03E&4 Kr-88 1.47E&4 2.37E+03 1.52E+04 2.93E&3 Kr-89 . 1.66E&4 1.01E+04 1.73K&4 1.06E&4 Kr-90 l. 56E&4 7.29E+03 l. 63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E&3 Xe-133m 2. 51E&2 9.94E+02 3. 27E&2 1.48E+03 Xe-133 . 2.94')2 3.06E+02 3.53E&2 1.05E&3 Xe-135m 3.12E&3 7.11E+02 3.36E&3 7.39E&2 Xe-135 l. 81E&3 1.86E+03 1.92E+03 2.46E&3 Xe-137 1.42E&3 1.22E+04 1. 51E+03 1.27E&4 Xe-138 8.83')3 4.13E+03 9.21E&3 4.75E&3 Ar-41 8. 84E&3 2.69E+03 9.30E&3 3.28E+03 a The listed dose factors are for noble gases that may be detected in gaseous effluents.
'cl m (b)7.56E-02 ~ 7.56 x 10-2.
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Reference:
Regulatory Guide 1.109, Table B-l.
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CONTROLLED BY USER TABLE 3-2 (Sheet 1 of 3}
PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERN RELEASES AT THE SITE BOUNDARY CENTERED ON UNIT 1 DISTANCE 9/Q DIRECTION (DIETERS} <sEc/m3) (m ~)
N 1037 4.93 E&6(a} 9.24 E9 NNE 3.057 4.14 E-06 1.19 E&8 NE 2206 2 84 E&6 6.84 E&9 ENE 1967 2.51 E&6 4.43 E-09 E 1927 2,56 E&6 3.24 E&9 ESE 1967 2.61 E&6 2 46 E&9 SE 2049 3.56 E&6 2 36 E&9 SSE 2730 3.80 E&6 1.58 E-09 S 3006 5.07 E&6 1.78 E&9 SSW 2258 6 52 E&6 3.20 EW9 SW 1487 7.47 E&6 5.65 E&9 WSW 1251 4.52 E&6 5.93 EW9 W 1225 4.73 E-06 9.49 E&9 WNW 1244 3.76 E&6 6.76 E-09 NW 1254 3.43 E&6 5.87 E&9 NNW 1069 3.70 E-06 7.26 EW9 (a} 4,93 EW6 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.
3-5 CONTROLLED BY USER
~ W ~ V* 0 ) 'h H 414 NA1144y~
l I
I
~
I II
CONTROLLED BY USER 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/m3) Ca 2)
N 1318 3.85 Z&6 6 17 E&9 NNE 1342 3.18 E&6 7 93 E&9 NE 2545 2.42 E&6 5.34 E&9 ZNE 2206 2.22 E&6 3.64 E-09 E 2163 2.27 E&6 2 66 E&9 ESE 2067 2.32 E&6 2 11 E&9 SE 2101 3.47 Z-06 2 26 E&9 SSE 3026 3.43 E&6 1 32 E&9 S 2699 5 16 E&6 1.97 EM9 SSW 1836 7 90 E-06 4.56 E&9 SW 1208 7 72 E&6 6 88 EW9 WSW 1014 5.55 E&6 8.44 E-09 W 993 5.86 E&6 1 34 Z&8 WNW 1010 4.67 E&6 9.60 E-09 NW 1191 3.62 E-06 6.40 E-09 NNW 1342 2.85 E&6 4.87 E9
Reference:
Distances are from the PVNGS ZR-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.
3-6 Rev. 1 09/20/85 CONTROLLED BY USER
l Il
~
CGNTRGLLED BY USER TABLE 3-2 (Sheet 3 of 3)
PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PXUQKTERS FOR LONG TERM RELEASES
'AT THE SITE BOUNDARY CENTERED ON UNIT 3 DISTANCE X/Q D/Q
, DIRECTION (NETERS) (SEC/m3) (m 2>
N 1661 3.54 E&6 4<<86 E-09 NNE 1693 2.86 E&6 6 23 E&9 NE 2756 2.21 E&6 4 65 E&9 ENE 2337 2.08 E&6 3 30 EW9 E 2290 2.14 E&6 2 41 E&9 ESE 2023 2.37 E&6 2 10 E&9 SE 2256 3.24 E&6 2 00 E&9 SSE 2786 3 72 E&6 1 52 E&9 2346 5.90 E&6 2.51 E&9 SSW 1607 8.91 E&6 5.73 E&9 SW 1057 8.68 E&6 8 61 E&9 WSW 889 5.34 E&6 8 ~ 83 E&9 W 871 6 ~ 72 E&6 1 67 E&8 WNW 885 5.37 E&6 1.19 E&8 NW 1045 4.17 E&6 7.98 E&9 NNW 1561 2.93 E&6 4.58 E&9
Reference:
Distances are from the PVNGS ER-OL, Table 2.3-33. Dispersion and Deposition parameters are from a September, 198S, calculation by NUS Corporation based on 9 years of meteorological data; NUS Corporation letter NUS-ANPP-3386, dated October 4, 1985.
3-7 4
Rev. 1 09/20/85 CGNTRGLLED BY USER 4 ~
N ~ ~ v"" wl%t aea~~k I
l l
l t
~
1
CONTROLLED BY USER TABLE 3-3 Pi Values for the Palo Verde Nuclear Generating Station Inhalation pathway (a>
~Xsoto e (mrem/ r/MCi/m3)
H 3 1.12E&3(b)
Cr 51 1.70E+04 54 1.57E&6 Fe 59 1.27E+06 Co 58 1 10E<6 Co 60 7.06E+06 Zn 65 9.94E&5 Sr 89 2.15E+06 Sr 90 1. OiE&8 Zr 95 2. 23E+06 Sb 124 3.24E&6 I 131 1 62E+07 I 133 3.84E&6 Cs 134 1.01E+Q6 Cs 137 8.24E&5 Ba 140 1. 74E+06 Ce 141 5.43E+05 Ce 144 1.19E+07 (a) Child receptor (b) 1.12E&3 ~ 1.12 x 103
References:
NUREG&133, Section 5.2.1.1 (Calculation of Pi (inhalation))
Regulatory Guide 1.1Q9, Table E-5, Table E-9.
NUS Corporation letter NUS-ANPP-1385, dated 9/26/85.
3-8 CONTROLLED BY USER
I I
CONTROLLED BY USER 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 SlTE 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:
Por gamma radiation:
D V u (3 1>> 10 ) i [(Mi) ( X'Q)SBu(Qi)] (4-1)
Por beta radiation:
D Where.
Bu (3.17 x 10 8) E i [(Ni) ( VQ)SBu(Qi)l (4-2)
M i the air dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrad/yr per u Ci/m3 from Table 3-1.
CONTROLLED BY USER9<20<s5
I l
l
CGNTRGLLED BY USER N
i the air dose factor due to beta emissions for each identified noble gas radionuclide i, in mrad/yr per u Ci/m3 from Table 3-1.
h /Q)SBu the highest calculated annual average dispersion parameter, in sec/m 3 , at the site boundary for the particular unit, from Table 3-2.
~ 7.47X10 from Unit 1
~ 7.90X10 from Unit 2
~ 8.91X10 from Unit 3 D
Yu 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.
Dg 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 pCi, of each identified noble gas radionuclide i, in gaseous effluents for a specified time period.
3.1? K 10 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.
4-2 CGNTRGLLED BY USER,";",',
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I
CGNTRGLLED BY USER 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 SITZ BOUNDARY (see [Technical SpecificationJ 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, and all radionuclides in particulate form, with half-lives greater than eight days, in gaseous effluents released to unrestricted areas from each reactor unit is calculated using the following expressions:
Dou (3.17 x 10 8) q f E k (Rig Wk) (gi)l Where.
D the total accumulated organ dose from gaseous effluents for a particular unit, to a MEMBER OF THE PUBLIC, in mrem, at the SITE BOUNDARY or at the controlling location.
the quantity of radionuclide i, inw Ci, released in gaseous effluents from a particular unit.
4~3 CGNTRGLLED BY USE/;,";,',
I CQNTRQLLED BY USER ik the dose factor for each identified radionuc$ ide i, for pathway k (for the inhalation pathway'n mrem/yr per u Ci/m3 and for the food and ground plane pathways in m 2 - mrem/yr per 0 Ci/sec) at the controlling location. The Rik's for each age group are given in Tables 4-1 through 4-15.
3.17XLO ~ the inverse of seconds per year (yr/sec).
Wk 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/Q) >BU, in sec/m 3 for the inhalation pathway and for all tritium calculations, for organ dose at the site boundary, from Table,3-2.
~ 7.47X10 -6 from Unit 1 7.90X10 from Unit 2 8.91X10 from Unit 3 3
( X/Q)RU, 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 -6 from Unit 1
~ 2.19X10 from Unit 2
-6.'from 2.31X10 Unit 3 4-4 CQNTRQLLED BY USER"9i;,g
I CGNTRGLLED BY USER
( D/g) , in m , for the food and ground plane pathways, for organ dose at the site.
boundary, from Table 3-2.
1.19X10 from Unit 1
-8 1.34X10 from Unit 2
-8 1.67X10 from Unit 3
( D/Q)RU, in m , for the food and ground plane pathways, for organ dose at the controlling location, from Table 4-16.
~ 3.25X10 from Unit 1
~ 3.88X10 -10 from Unit 2
~ 4.21X10 -10 from Unit 3 Residences, vegetable gar'dens and meat and milch 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 wi11 be used for all HEMBER 0p THE PUBLIC dose evaluations.
The Ri values were calculated in accordance with the Ri-'alue methodologies in NUREG-0133 and generated using the GASPAR code. The following site specific information was used to calculate fraction of year milch animals and beef animals are on pasture, fP 0.75 fraction of daily intake of milch animals and beef animals derived from pasture while on pasture, fs 0.35 4-5 CGNTRGLLED BY USER
CONTROLLED BY USER fraction of year vegetables aze grown, fl approximation 0.667 absolute humidity (g/m 3 ) over the growing season, H These site specific values are from the PVNGS Environmental Report, Section 2 and Appendix 5-B.
4.3 Dose Pro ection 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 I 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 zadi'ation 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 pzojected 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 Projection For the purpose of satisfying requirements of Technical Specification 3.11.2.4, the air dose at the site boundary due to noble gases released in gaseous effluents from a particular unit is projected at least once pez 31 days.
4-6 CONTROLLED BY USER
l CONTROLLED BY USER 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:
31 day y (D y qtrlTqtr) 31 + CD y (4-4)
For beta radiation:
31 day >
(D <
qtr/Tqtr) 31 + CD (4-S) where:
D y qtr ~ the total gamma air dose due to noble gases released in gaseous effluents for the current quarter, in mrads, at the site boundary.
D g 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 p qtr-and Dg qtr were integrated.
31 the number of days over which the dose projections are made.
4-7 CONTROLLED BY USEP9~j20/ss
CGNTRGLLEID BY USER 31 dayy the 31 day projected gamma air dose due to noble gases released in gaseous effluents, in mrads, at the site boundary.
.31 dayg ~ the 31 day projected beta air dose due to noble gases released in gaseous effluents, in mrads, at the site boundary.
CD y 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 CD g 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 day g 4.3.2 Or an Dose Pro ection For the purpose of satisfying requirements of Technical Specification 3.11.2.4 for a particular
'nit, 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:
31day (D qtr/Tqtr)31 + CD (4-6) 4-8 Rev. 1 CONTROLLED BY USER""'"'
I I
CGNTRGLLED BY USER where:
D 0
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
0 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 0
any current or projected organ dose for a particular unit, in mrem, which could have a significant impact on 31 day 0 .
4-9 CGNTRGLLED BY USER"'""'
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TABLE 4-1 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION(
PAT t tUAY . GROUttQ ttUCLIDE T. BODY GI-TRACT DOttE LIVER KIDttEY TIIYROID LUNG SKIN t t A o ttn S4 )
1.38E009 1.3QE609 ( 1.3QE609 )
1.3QEt09 1.3QEt09 ( 1.3QEt09 ( 1.38Et09 ( 1.62Et09 )
O Cr 51 Fe 59 t(
4.65Et06 2.72Et08
)
4.65EI06 2.72Et08
(
4.CSE606 2.72Et08
(
4.65Et06 2,72Et08
(
4.65E606 2.72Et08 t) 4.65Et06 2.72Et08
( 4.65Et06 2.72Et08
( 5.49Et06 3.20E+08
(
~
-t) t) ) )
t) ) )
Ce 58 3.79Et08 ) 3.79Et08 ) 3.79E608 ) 3.79Et08 ) 3.79Et08 3.79Et08 3.79Et08 4.44Et08
)
-t - --- -t- - - -t- ) (
Co 60 2. ISE+10 2. 15E+10 2. ISE610 2. 15E+10 2.15Et10 2.15Etl0 2.15E+10 2.52Et10 t) ) ) (
t) )
O; I
Zn 65 Sr 89
(
)
7.44E608 2.16Et04 t(
(
7.44Et08 2.16Et04 )
7.44E608 2.16Et04
(
(
7.44Et08 2.16E604
)
7.44E608
- 2. 16Et04 f
)
7.44E608 ) 7.44Et08
- 2. 16Et04
)
2,16Et04
)
(
8.56Et08 2.50Et04 Ir 95 2.45Et08 2.45Et08 2.45Et08 2.45EtOB 2.45E+08 2.45Et08 2.45Et08 2.84Et08
-t ) ) ) ) ) ) ) (
Sb124 (
5.98Et08 )
5.98Et08 ( 5.98Et08 ( 5.98Et08 5.98Et08 ) 5.98E608 )
5.98Et08 ) 6.91Et08 (
I 131 1.72Et07 1.72Et07 1.12E 07 1.12Et01 1.12Et01 1.12Et07 1.72Et07 2.09Et07 QO +
) )
f( )
.t) t) ) )
3 333 [ 2.455<06 i 2.452<06,[ 2.452i06 i 2.452+06 2.4SEt06 ) 2.45Et06 ( 2.45Et06 ( 2.98Et06 (
t I Cs134 )
6.82E+09 t) 6.82Et09 (
6.82E609 t-6.82Et09
(
6.82Et09 ( 6.82Et09 (
6.82Et09 ( 7.96Et09 )
-f----------t Csl37 1,03E+10 1.03E+10 ) 1.03E+10 1.03E+10 ) 1.03E+10 ) 1.03E+10 1.03E+10 ) 1.20Etl0 CA
( )
I( )
Bel40 2.05E607 ( 2.05E607 ) 2.05E607 )
2.05Et07 ( 2.05Et07 2.05Et07 2.05Et07 2.34Et07 f f
~ Ce141 Cel44 (
1,36Et01 6.95Et07 t-(
)
1.36Et07 6.95Et07 f
(
(
1.36Et07 6.95Et07 f
(
t) 1,36Et01
-t-(
1.36Et01 6.95E Ol ).6.95Et07 t
f
(
)
1.36E607 6.95EtQl f
)
(
)
1.36Et07 6.95E+07
(
t) 1,54Et07 8.03E 07
)
t)
(a) R values are in units of m -mrem/yr per >Ci/sec.
(b) 1.38E+09 = 1.38 X 109.
Reference:
NUREG-0133; NUS Corporation letter NUS-ANPP-1385, dated 9/26/85.
I l
M M n
R VALUES POR THE PALO VERDE NUCLEAR GENERATINQ STATION(a)
PATIMAY ~ VEGET AGE GROUP ~
UUCLIDE '. ADULT BODY Gl-TRACT BORE
+
LIVER KIDNEY t
THYROID LUIIG SK]II 0 3 [ 4.34E F 09'l 4.34E/03 O.OOE-OI I 4.34Et03 4.34Et03 4.34Et03 4.34Et03 4.34EtD3 l
A
(
(
t( l lln 54 5.65Et07 9.Q7EtQB D.OOE-OI I 2.96ft08 B.BIEt07 }. O.OOE-OI I 0 ~ OOE-Ol O.OOE-01 o
I I I
} }
Cr 01 3.999r04 3.00Er03 O.OOE-DI Q.OOE-QI I 8.79EE03 2.38Et04 5.29Et04 O.QOE-OI l f l } }
~
I
}
Fe 59 (
1.02Et08 (
8.91Et08 (
- 1. 14Et08 (
2.67E+08 (
O.OOE-DI ( O.OOE-DI I 7.47Et07 (
0-OOE-01 Co 58 (
6,38Et07 (
5.77Et08 (
O.OQE-OI I 2.85Et07 O.OOE-OI O.OQE-DI I O.OQE.OI I O.QOf-01
-f RJ Co 60 3.5IE 08 I 2 '9E 09 I O.OOE-DI 1.59Et08 O.OOE-OI O.OQE-OI Q.QOE-DI O.OQE-DI
} . l i ln 65 4.3lft08 6.01Et08 ( 3.DOE+08 9.54E+08 6,38Et08 O.OOE-DI O.OOE-DI O.OOE-OI
}
I Sr 89 2.60Et08 1.45Et09 ( 9.06Et09 D.QOE-OI O.OOE-DI 0 ~ OQE-01 O.OOE-DI O.OOE-OI I } } }
M ~ Sr 90 1.41Etll (
1.6GEt10 (
5.76E+ll (
O.OOE-OI O.OOE-OI O.OOE-OI O.OOE-DI O.QOE-DI lr 95 Sb124
}
(
2.35Et05 3.7GEt07
(
- 1. IOEt09 2.71Et09
( I.OBEt06 9.53Et07
- l. 3.47Et05 1.80E+06 5.45Et05 O.OOE-OI O.OOE-DI 2.31Et05 O.OOE-QI 7.42Et07 O.OOE-OI O.OQE-DI Q3 }
( ( (
I 131 I 4.49E+07 2.07Et07 I 5.47Et07 (
7.83Et07 (
1.34Et08 (
2.57ftlO O.OOE-DI I O.OOE-DI I 133 (
7.35Et05 (
2.17Et06 (
1.39Et06 (
2.41Et06 (
4.21Et06 ( 3.54Et08 (
O.OOE-OI ( O.OOE-DI tA Cs134
}
8.62Et09
}
1.85ftQB
}
4.43ftQ9 (
1.05E+10 I 3.41Et09 (
O.OOE-OI
}
- 1. 13Et09 (
O.OOE-OI (
m Cs137 t(
5.42Et09
}
I 60Et08 6.05E+09 ( 8 ~ 28Et09 I 2.81Et09 ( O.OOE-OI 9.34Et08 (
O,OOE-DI o5 Ba 140 6.17Et06 1.94Et08 9.42Et07 1.18Et05 4 ~ 03EE04 O.OQE-OI }',78Et04 O.OQE-OI
(
-t-(
t(
-tI -f------
I EO tO N~
o Cel41
}
(
1.33Et04 (
4.47Et08 1.05E+10
( 1.73EE05 3.11Et07
-t-(
1.17E+05 1.30E+07
(
5.43Et04 7.72EE06
( O.OOE-OI l.O.OOE-OI (
O.OOE-OI
-t----------f Ce 144 I 1.67EE06 ( (
D.QQE-OI O.OOE"01 I O.OQE-OI (
Ln t t( (
(a) R values are in units of mrem/yr per PCi/m3 for tritium, and in units of m2-mrem/yr per PCi/sec for all others.
(b) 4.34E+03 4.34 X 10
I I
I
TABLE 4-3 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION(+)
PATI4lAY ~ VEGET AGE GROUP ~ TEEN NUCLIDE T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+- - ----ort-N 3 )
S.DBEtOi [ 5.08Et03 ) O.OOE-OI )
5.08Et03 )
S.OBEt03 )
S.OBEt03 )
5.08E+03 )
5.0BEt03 4
Nn 54 ) 8.72Et07 ) 9.02Et08 O.OOE-OI 4.40Et08 ) 1.31Et08 O.OOE-OI O.QOE-OI O.ODE-OI
} } } } } } }
Ce 51 5.58Et04 9.37Et06 D.OOE.Ol O.OOE-QI 1.22Et04 3. IQEt04 7.96E+04 O.OOE-QI
)
-t
) ) ) )
}
Fe 59 )
1.52Et08 )
9.28Et08 )
1.68Et08 3.92Et08 O.OOE-01 O.DOE-01 1.24Et08 O.OOE-QI t } t }
Co 58 9.60Et07 5.74Et08 O.OOE-OI }'.17Et07 Q.OQE-OI O.OOE-01 O.OOE-OI O.QOE-OI t)
) ) ) )
} -t)
Co 60 )
5.44Et08 ) 3. 14Et09 O.OOE-DI 2.41Et08 ) O.OOE-OI O.OOE-QI O.OOE-QI O.OOE-QI
}
En 65 )
6.64Et08 )
6.03EtDB 4.10Et08 1.42Et09 )
9.11Et08 O.QOE-OI O.OOE.OI ) O.OOE-QI
+
St 89 ) 4.09Et08 ) 1.70Et09 1.43Etl0 O.OOE-01 ) O.ODE-01 O.DOE-OI O.OOE-OI O.OOE-OI Sr 90 )
I.BDEtll Z.OSE+10 7.29Etll O.OOE-OI O.OOE-OI O.OOE-Ol O.OOE-OI ) O.OOE-Ol
)
t)
Er 95 )
3.56Et05 ) 1.19Et09 1.64Et06 5.18EtOS ) 7.60Et05 O.OOE-01 O.OOE-OI O.OOE-DI t
)
5.73Et07 ) 2.96Et09 ) 1.47Et08 2.70Et06 ) O.OOE-OI 3.33Et05 1.2BEtQB O.OQE-QI I 131 3.97Et07 1.4GEt07 5.2BEt07 7.40Et07 ) 1.27Et08 2.16E+10 O.ODE-OI O.OOE-OI )
}
I 133 6.G6Et05 ). 1.6SEt06 1.29Et06 2,18Et06 )
3.83Et06 3.0SEt08 O.OOE-QI O.OOE-OI O.OOE-01'bl24 Cs134 7.52Et09 )
Z.Q2Et08 6.89Et09 1.62Et10 )
5.15Et09 O.OOE-01 1.97Et09 Csl37 4.56Et09 )
I.BGEt08 ) 9.84Et09 1,31Etl0 )
4.46Et09 O.OOE-01 1.73Et09 O.ODE-01 88140 6.87Et06 )
1.65Et08 )
1.07Et08 1.31Et05 )
4,43Et04 O,OOE-OI 8.79Et04 I O.OOE.OI ).
Cel41 2.00Et04 4.97Et08 2.60Et05 ) 1.74Et05 ) B.IBEt04 O.OOE-OI O.OOE-QI O.ODE-OI
} }
Ce144 2.74Et06 )
1 ~ 28Et10 ) S. 11Et07 )
- 2. IIEt07 ) 1.26Et07 I O.OOE-OI O.OOE-OI O.OOE-OI I
} } }
(a) R values are in units of mrem/yr per li Ci/m3 for tritium, and in units of m2-mrem/yr per It Ci/sec for all others.
(b) 5.08E&3 5.08 X 10 .
I I
I I
~ ~ ~
)
I I I I I I I I I I I I I I I, I I s I II I I I; I '
~
I ~
I I ' I I I I I:
I I I I ~
e I I (
I I ~
I
~ ~
I
fl I
I
TABLE 4-5 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION(a)
PATlQAY ~ HEAT AGE GROUP ~ AOULT HUCLIDE T.800Y GI-TRACT 80HE LIVER KIOHEY THYROIO LUHG SKIN t
H 3 )
6.55ftok 6.55Et02 O.OOE-OI 6.55Et02 6.55Et02 i 6.55Et02 6.55Et02 6.55Et02
)
-t) t) t
)
Hn 54 i 8.29Et05 1.33Et07 O.OOE-OI
)
4.34E006 )
1.29ft06 )
0.00E-OI )
0.00E-OI O.OOE-OI f
Cr 51 2.04Et03 5.12Et05 O.OOE-OI O.OOE-OI 4.48Et02 1.22Et03 2.70Et03 0.00E-ol
)
t} ) ) )
l Fe 59 7.78Et07 6.77Etao 8.64Et07 2.03Etaa O.OQE-OI O.OOE-OI I 5.67Et07 O.aaf-al
(
t( ( ) ) I t ti Co 58 J
1,51Et07
)
1.37Ctao f
O.aaf-al ) 6.74Et06 O.oof-al L J.O.aaf-al
} O.OOE-OI / O.OOE-OI Co 60 ) 8.49Et07 )
7.23Et08 t O.OOE-OI f 3.85Et07 0.00E-ol ) 0.0OE-ol 0.00f-ol If 0.00E-OI I
} }
Zn 65 2.36Et08 3.29Et08 I ~ 64Etaa 5.23Et08 3.50ft08 O.OOE-OI ) O.OOE-OI [ O.OOE-OI
) [ ( ) (
-f----- -- -t Sr 89 ) 2.91Et06 ) 1.63Et07 ) 1.02Et08 ) O.OOE-OI O.OOE-OI ) O.OOE-OI O.OOE-OI
~ I O.OOE-OI
~ 1 Sr 90 1.58Et09 1.86Et08 6.45Et09 O.OOE-OI [ O.OOE-OI [ O.oof-ol ( O,OOE-OI ) Q.OOE-OI [
/ ) (
t--
(
Zr 95 )
1.46Et05 )
6.85Et08 / 6.74Et05 )
2,16Et05 )
3.39Et05 )
0.00E-OI )
O.OOE-OI )
0.00E-OI t Sbl24 I 2.78Et06 I 1.99E 08 l 7.0IEt06 ! 1.32Et05 } O.OOE-OI l 1.70Et04 1 5.45ft06 / 0.00E-OI 1 I 131 2.31Et06 )
1.06Et06 )
2.8IEt06 ) 4.03Et06 ) 6.90Et06 / 1.32Et09 ) O.OOE-OI ) O.OOE-OI )
f 133 I 5.14E-02 ) 1.52E-OI ) 9.69E-02 / 1.69E-OI I 2.94E-OI / 2.48E Ol / O.OOE-OI I O.OOE-OI /
C 134 6.39Et08 [ 1.37E 07 3.28Et08 ) 7.81E 08 ) 2.53E 08 [ O.OOE-OI ) 8.39Et07 ) O.aaf-al
) J f
24137 f 4.05Es08 f 2.202s07 f 4.522s00 [ 0.18Es00 ] 2.1DEs00 D.DDE.D1 6.98EsD7 D.DDE.01 t } } } }
oa140 f 4.97Et05 f 1.56EtO7 f 7.59Et06 f 9.54Et03 )
3.24E.03 )
O.OOE-OI )
5.46Eta3 )
O.aaE-al f.
+
Ce141 )
3.23Et02 )
1.09Et07 J 4.21Et03 )
2.85Et03 )
1.32ft03 / O.OOE-OI / O.OOE-OI / O.OOE-OI f t
Ce144 )
3.67Et04 )
2.31E008 f 6.84ft05 )
2.86Et05 f 1,70Et05 )
O.OOE-OI )
O.OOE-OI f O.OOE-OI )
+
(a) R values are in units of mrem/yr per pLCi/m3 for tritium, and in units of m2-mrem/yr per pCi/sec for all others.
(b) 6.55E+02 6.55 X 10 .
I I
4-6 R VALUES FOR THE PALO VERllp NUCLEAR OENERATZNO STATION(a).
PAlltMAY ~ HEAT AGE GROUP ~ Tfftt tlUCI.IDE T.BODY Gl-TRACT BORE LIVER KIDtlEY TttYROID LUttG SKItt
+ 1g e$ +
H 3 )
3.91fi02 f 3.9IE~02 )
O.OOE-OI I 3 9IEt02 ) 3.9Ift02 )
3.9IE~02 )
3.9IE<02 )
3.91ft02 )
le 54 Cr 51 f
6.57fi05 6.79fttI6
)
2.74E>05
) O.OOE-OI
- l. 3 ~ 3IE+06 )
-4 9.88ft05 ) O.OOE-OI ) O.OOE-OI ) O.OOE-OI )
1.63E>03 ) D.DOE-OI O.OOE-OI I) 3.57E>02
~ I) 9.04E402
~
)I 2.32E>03 ) O.OOE-OI )
I I Fe 59 )
6.22E~07 )
3.81fi08 )
6.9Ifi07 )
1.6IEEOB ) O.OOE-DI )
O.OOE-OI )
5.08ft07 )
O,OOE-OI I Co 58 Co 60
) 1.20fi07 6.72fi07
) 7.16fi07 3.89ft08
)
)
O.OOE-OI O,OOE-OI
- l. 5.19fi06 2.99fi07
) O.OOE-OI O.OOE-Ol
) O.ODE-DI O.OOE-Ol
) O.OOE-OI O.OOE-Ol
) O.OOE-OI )
O.OOE.Ol
) ) f f t I t t En 65 1.87fi08 1.70E>08 1.15ft08 4.070t00 2.57ft08 ) O.ODE-DI ) O.OOE-OI O.OOE-DI
) )
t I f-- ---- )
f Sr 89 2.45E>06 ) 1.02EE07 ) 8.57E<07 )
O.OOE-DI O.OOE-OI ) O.OOE-OI ) O.OOE-OI ) O.OOE-DI I e $ o Sr 90 )
1.03E>09 ) I.I7ftDB ) 4.17E409 )
O.OOE-OI ) O.OOE-OI ) O.OOE-DI ) O.OOE-DI )
O.OOE-OI )
Ir 95 )
I.lif>05 ) 3.93ft08 )
5.40ft05 )
1.70ftOS )
2.50ft05 )
O.OOE-OI
)
O.OOE-OI ) O.OOE-OI Sb124 ) 2 '3E~06 I I 15E 08 ) 5 '2E 06 ) l.OSE 05 O.OOE-OI ) 1.30E<04 ) 5.00fi06 ) O.OOE-OI
)
I 131 )
1.76E406 )
6.48fi05 )
2.34ft06 ) 3.27fi06 5.64E<06 )
9.56E<08 )
O.OOE-OI O.OOE-OI I I 133 ) 4. 19E-02 )
1.04E-OI ) 8. IIE-02 )
1.38E-DI 2.41E-DI )
1.92E401 )
O.OOE-OI O.OOE-OI )
Csl34 2.85ft08 7.64fi06 ) 2.6IE~08 ) 6.14ft08 1.95E+08 ) O.OOE-DI ) 7.45E<07 O.OOE-OI )
) )
f )
Csl37 )
1.74E<08 ) 7.IIE~06 ) 3,75ft08 [ 4.99ft08 1.70E+08 ) O.ODE-DI 6.60fi07 ) O.OOE-QI )
}
80140 )
4.04E<05 )
9.68E>06 (
6.28E<06 )
7,69ft03 )
2,61ft03 O.OOE.OI 5.17fi03 O.OOE-OI )
E-46141 i 2.71E<402 i 6.76Et406 [ 3.'36<03 2.36E 03 1. I IE 403 O.OOE-DI O.OOE-OI 0.00f-01 ti I )
CD144 ) 3.IOE~04 ) I.45EEOB ( 5.76fi05 ) 2.38E 405 1.42E 05 O.OOE-DI O.OOE-OI ) O.OOE-OI f I l (a) R values are in units of mrem/yr per ttCi/m for tritium, and in units of m2-mrem/yr per IiCi!aec for all others.
(b) 3.91E+02 ~ 3.91 X 102,
I I
I I
I
TABLE 4-7 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION~
PAIHMAY ~ HEAT AGE GROUP % CHILO NUCLIOE T. BOOY GI-TRACT BONE LIVER KIONEY THYROID LUNG SKIN
t--- ----tet----------t t- - - t H 3 ) 4.72EtOPQ 4.72Et02 ) O.OOE-OI ) 4.72Et02
- -----t--------t--- ------t----------t- )
4.72Et02 l. 4.72Et02 I 4.72Et02 4.72Et02 Hn 54 Cr 51
) 1.01Et06 2.54Et03
( 3. 18Et06 1.35Et05
) O.OOE-OI O.OOE-01
( 3.79Et06 O.OOE-Ol I 1.06Et06 3.85Et02
- l. O.OOE-01 1.41Et03
( O.OOE-OI 2.57Et03
}
O.OOE-OI O.OOE-OI
}
) ) ) ) )
l } }
Fe 59 )
9.87Et07 )
2.06Et08 )
1.2ZEt08 )
1.98Et08 )
O.OOE-Ol O.OOE-OL 5.74Et07 O.OOE-Ol t
Co 58 1.86Et07 3.54Et07 ( 0.00E-OI ( 6.07Et06 ( O.OOE-Ol O.OOE-OI O.OOE-OI I O.OOE-01 I
} }
Co 60 1.05Et08 1.96Et08 ) O.OOE-OI I 3.54Et07 ),O.OOE-OI O.OOE-OI O.OOE-OI I O.OOE-OI I
} }
Ln 65 2.87Et08 8.11Et07 1.73Et08 4.62Et08 2.91Et08 Q.OOE-OI O.OOE-01 O.OOE-OI
)
t) -t) t) ) (
Sr 89 4.63Et06 6.28Et06 ) 1.62Et08 O.OOE-OI O.OOE-Ol O.OOE-Ol O.OOE-01 I O.OOE-01 I
} } } } }
Sr 90 I I J7Et09 7.26Et07 (
5,39Et09 )
O.OOE-OI ) O.OOE-Ol ) O.OOE-OI O.OOE-OI ( O.OOE-OI
} }
Er 95 )
1.88Et05 )
2.20Et08 )
9.59Et05 )
2.11Et05 )
3.02Et05 O.OOE-01 O.OOE-OI O.OOE-OI Sbl24 3.63Et06 6.47Et07 ( 1.04Et07 1.34Et05 O.OOE-Ol 2.28Et04 5.74Et06 O.OOE-OI
} }
) )
4 t) 3.88Et05 4.36Et06 7.16Et06 1.44Et09 )'0.00E-OI I 131 2.48Et06 t) )
4.34EtOG )
1.86E-OI t-
)
3.10E-Ol
) )
O.OOE-OI )
I 133 7.05E-OZ 7.50E-02 1.51E-OI ( ( 3.46Et01 O.OOE-QI O,OOE-OI
} } t( ( ( (
Cs 134 1.59Et08 4.07Et06 4.60Et08 ) 7.55Et08 ( 2.34Et08 )
O.OOE-OI ) 8.40Et07 ( 0.00E-OI
} } }
Cs137 9.77Et07 4.14Et06 6.91Et08 ) 6.62Et08 ( 2.16Et08 ( O.OOE-01 I 7.76Et07 O.OOE-OI (
} } } f Bz 140 )
6.76Et05 5.87Et06 1.16Et07 ( I.OIEt04 ) 3.30Et03 )
O.QOE-OI ) 6.05Et03 ( O.OOE-Ol )
t t( }
C0141 4.93Et02 4.14EtOG 6.66Et03 (
3.32Et03 ( 1.46Et03 ) O.OOE-OI I 0 ~ OOE Ol ( 0 ~ OOE Ol
} } }
Ce144 )
5.80Et04 8.88Et07 1.09Et06 ) 3.4IE<05 ) 1.89Et05 )
O.OOE-OI I 0 OOE 01 I O.OOE 01 I I ) I (a) R values are in units of mrem/yr per liCi/m for tritium, and in units of m2-mrem/yr per I'Gl/sec for all others.
(b) 4.72EK2 = 4.72 X 102.
I I
I I
I I
I
TABLE 4-8 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATIOII~a~
PATINAY < CN tIILK AGE GRallp ~ ADULT NUCLIDE T. BODY GI-TRACT BallE LIYER KIDNEY THYROID LIIG SKIN
---t---------(t---- +- - -+
II 3 1.54E 09 f 1.54E 03 I O.QQE.OI )
1.54E+03 I 54Et03
~ I 54Et03 (
~ I ~ 54Et03 1.54Et03
( ( )
t -t ) (
lh 54 7.6QEtas 1.22Et07 O.QOE-QI 3.98Et06
. 1.18Et06
. O.aaf-al O.OQE-OI ) O.OOE-OI )
) ) )
l l ) )
Cr 51 ) 8.26Et03 2 ~ OBEt06 ) 0 ~ OOE-01 O.OOE-DI 1.82Et03 4.94Et03 1. IOEt04 O.OOE-OI
)
f (
Fe 59 8.71Et06 7.57Et07 I 9.67Et06 2.27Et07 ) O.OOE-OI O.OOE-DI 6.35Et06 O.OOE-OI (
) ) )
+
Co 58 3,90Et06 3.53Et07 0.00E-OI 1.74Et06 O.OOE-OI
. O.OOE-OI O.OOE-OI I O.OOE-OI I
) ) )
l 60 I.bsft07 1.58Et08 O.QOE-DI 8.39Et06 O.QOE-OI O.OOE-OI .
l O.OOE-OI Co I O.OOE-OI
)
)
) )
5 t---------
) I Zn 65 9.11Et08 5.222409 [ 6.335<00 [ 2.025<09 I . 35Et09 ) 0 . OQE-Ol I O.OOE-OI I O.QOE-OI I
) (
l Sr 89 ) 1.4OEt07 7.84FtD7 4.89Et08 ) O.OOE-DI 0. OOE-Ol ( 0 . OOE-OI O.OOE-OI O.OOE-OI
) J J 1 1 )
Sr 90 ( 5.95Et09 (
7.01Et08 2.43E+10 I 0.00E-DI 0 . OOE-Ol ) Q.QOE-OI a.aaE-al Q.aOE-QI I f } ) }
Lr 95 7.37Etal 3.555i05 3.395t02 1.092~02 I . 71E 002 0 . OOE-01 O.OQE-OI O.OOE-OI
)
J l ~
l (
l J )
Sb124 3.6IEt06 2.59Et08 9.11Et06
. 1.72Etas 0 ~ OQE-OI 2.21Et04 7.09Et06 O.OOE-OI
)
I l ) ) ) ) ) )
I 131 6.36Et07 2.93EtD7 7 . 76Et07 I.IIEt08 I 90E908 ) 3 64E+10 0 ~ QQE-01 D.OOE-OI
-t- l )
~ ~ ~ ) )
) ) (
f 5.39E as I.s9Eta6 1.02Et06 I 1.77Et06 3.08Et06 ( 2.6QE+08 0.00E-DI O.QOE-DI
) ) ( (
tI t) )
Cs I34 )
5.49Et09 ( 1. IBEt08 (
2.82Et09 )
6 ~ 72ft09 )
2.17Et09 ) 0~
OQE-Ol
)
7.21Et08 I O.OQE-OI CSI37 3.43Et09 I.alfta8 3.83Et09 5.23Et09 ) 1.78E009 ) 0.00f-al 5.91Et08 O.OOE-DI
) )
I
)
t- -t----------t- ) f )
BeI40 (
4.65Etas 1.46Et07 ( 7. IQEt06 I 8.92Et03 (
3.03E903 Q.QQf-al )
5.11Et03 )
D.QQE-OI )
Cel41 6.68E902 2.25Et07 8.71Et03
. 5.89Et03 2.74E903 O.OQE-OI 0 ~ OOE-01 O.OOE-OI
-t---
) )
l ) ) ) ) )
Cel44 I 5.4IEt04 ( 3.40Et08 I.QIEt06 4.21Et05 2.50E605 O.QQE-OI O.QQE-OI O.OOE-OI
-t--- - ----t- f I t
)
} f )
(a) R values are in units of mrem/yr per I Ci/m3 for tritium, and in units of m2-mrem/yr per ItCi/sec for all others.
(b) 1.54E&3 1.54 X 103.
I I,
l' g
l I
TABLE 4-9 R VALUES FOR THE PALO VERDE NUCLEAR GENERATlNG STATION(
PATNAY ~ Cml gllK AGE GROUP ~ TEE tl UUCLIDE .T. BODY GI-TRACT BODE LIVER KI OBEY THYROID LWG SKIII
t--------vCt- t e w 3 (
2.0oft09 j 2.0oEt03 ( D.ooE-DI )
2.ooEt03 )
2.00Et03 ( 2.00Eto3 I 2.ooEt03 (
2.0oEto3 )
Hn 54 ( 1.32Et06 ( 1.36E+07 ( O.DOE-OI I 6.63Et06 I 1.98Et06 I O.OOE-OI I O.OOE-OI I O.OOE-DI Cr 51 (
1.44Et04 (
2.42Et06 (
O.OOE-OI ( O.OOE-OI ( 3. 16ft03 ( B.OIEt03 I 2.06Et04 I D.oof-ol I Fe 59 1.52Et07 9.31Et07 (
1.69Et07 (
3.94Et07 (
O.OOE-OI ( O.OOE-OI 1.24E+07 O,OOE-OI I t) (
( (
Co 58 6.75Et06 4,04ft07 O.OOE-DI 2.93Et06 D.OOE-01 0.00E-DI I 0.00E-DI I O.oof-ol I
)
t-(
- t( ( ( I Co 60 3.20Et07 ( 1.85Et08 (
O.OOE-OI ( 1.42Et07 O,OOE-OI O.OOE-OI O.OOE-DI O.OOE-OI
(
} } } } }
Zo 65 1.58Et09 1.43Et09 9.73Etoo 3.38Et09 2.16Et09 O.OOE-OI O.OOE-OI D.OOE-OI (
(
-t
( ) ( ) ( ( )
Sr 89 ( 2.58Et07 (
1.07Et08 ( 9.0IEt08 I O.OOE-OI ( D.oof-ol ( O.OOE-OI ( O.OOE-OI I O.OOE-OI I Br 90 8.4CEt09 9.62Et08 3.43E 10 O.OOE-DI O.OOE-OI O.OOE-DI O.OOE-OI ( O.OOE-OI
( ( ( ( ( (
t )
t f(
7r 95 1.29Et02 4 ~ 32Et05 ) 5.93Et02 1.87EtD2 2.75Et02 O.OOE-DI O.OOE-OI O.oof-ol
) (
t -t-
)
t) t- ) )
t)
Sbl24 I 6.34Et06 I 3.27Et08 (
1,62Et07 I 2.99Et05 ( O.OOE-DI (
3.68Et04 (
1.42ft07 (
O.OOE-OI (
I 131 )
1.06Et08 )
3.90Et07 ( 1.41Et08 I 1.97Et08 ( 3.39Et08 ( 5.75Etlo O.DOE-OI )
D.OOE-DI I t
I 133 9.60Et05 2.38Et06 I 1.86Et06 3.15Et06 5.52Et06 4.40Et08 0.00E-DI D.ODE-DI t( I ( ( (
f( t
(
+
Cs]34 Cs137
(
5.35Et09 3.22Et09
(
1.43Et08 1.31Et08
(
I 4.90E+09 6.94Et09 t----t
(
(
1.15E+10 9.23Et09
)
I 3.66Et09 3.14Et09
)
(
D.OOE-DI O.OOE-OI
)
(
1.40Et09 1.22Et09
)
0.00E-QI 0.00E-01
)
)
J 1 BaI40 (
8.2GEt05 )
1.98Et07 )
1.2BEt07 ) 1.57Et04 ( 5.33Et03 O.OOE-OI ( 1.06Et04 )
O,OOE-DI I.
t r Ce141 1.23Et03 3.05Et07 (I 1.60fto4
~
I 1.07Et04 I 5 02Et03 I O.OOE-OI I O.OOE-OI
~ 0.00E-D1
} I 1 Cel44 (
9.96ft04 (
4.66Etoo ( 1.85Et06 (
7.67Et05 I 4.58ft05 I O.OOE-OI (
O.OOE-OI O.OOE-OI
} }
(a) R values are in units of mrem/yr per It Ci/m3 for tritium, and in units of m2-mrem/yr per Ij Ci/sec for all others.
(b) 2.00E403 2.00 X 103.
I I
a
~
I
TABLE 4-10 R VALUES FOR THE PALO VERM NUCLEAR GENERATING STATION~
PAUfAAY ~ CDM BILK AGE GROUP ~ CIIILD IIUCLIDE .T. BODY GI-YRACY BORE LIVER KIDHEY THYROID LUNG SKIN
t--------vgt----------t- t --+-
8 3 )
317E'O~ I317E03) O'ODEDI ) 317E03) 3'E 3 (317E03) 3'17E03) 317E03) t t IQ 54 (
2.64Et06 (
8.33Et06 (
D,DOE-OI )
9.92Et06 ) 2.78Et06 )
0.00E-DI ( D.DDE-OI ( D,DOE-OI [
Cr 51 2.94Et04 1.56Et06 O.OOE-OI O.OOE-OI 4.46Et03 1.63Et04 2.98Et04 O.OOE-OI t) ) ) )
t-
) ) ) )
Fe 59 3.15Et07 6 ~ 59E+07 ) 3.91Et07 6.33E+07 O.ODE-DI ) O.OOE-OI ) 1.84E+07 O.OOE-OI
) )
t- ) ) ) (
Co 58 1.37Et07 2.61Et07 O.DDE-OI 4.48Et06 O.OOE-OI ( O.OOE-DI O.OOE-OI ( O.OOE-OI (
J J t
) (
t (
t- (
Co 60 )
6.51Et07 )
1.22Et08 )
O.OOE-OI ) 2.21Et07 (
O.OOE-OI ) O.OOE-DI ) O.OOE-DI ( O.OOE-OI Zn 65 )
3.16Et09 ) 8.93Et08 ( 1.91Et09 ) 5.08Et09 ( 3.20Et09 ( O.DOE-OI ) O.ODE-DI ( O.DOE-OI )
Sr 89 ) 6.37Et07 ) 8.63Et07 ) 2.23E+09 ) O.DDE-OI ) O.ODE-DI ) O.OOE-OI ( O.ODE-DI ) O.OOE-OI )
Sr 90 )
1.47E+10 (
7.80Et08 ( 5.79E+10 (.0.00E-DI ) O.DOE-DI ( O.ODE-DI ) 0.00E-OI ( D.OOE-OI )
Zr 95 2.70Et02 3.16Et05 1.38Et03 3.03Et02 4.34Et02 O.OOE-DI O.OOE-OI ) O.OOE-DI (
) ) ( ) ( (
t)
Sbl24 1.35Et07 ( 2.40Et08 ( 3.84Et07 ) 4.99Et05 ( O.ODE-OI ) 8.48Et04 ) 2.13Et07 ) O.OOE-OI )
)
I 131 1.95Et08 3.06EtD7 ) 3.42Et08 ) 3,44Et08 ) 5.64Et08 ) 1.14E+ll ( O.OOE-OI )
O.OOE-DI
} )
I 133 (
2.11Et06 (
2.25Et06 )
4.5IEt06 (
5.58Et06 (
9.29Et06 ) 1.04Et09 )
D.DDE-DI (
D.DDE-OI CsI34 3.91Et09 I.DDEt08 1.13E+10 1.85Et10 5.75Et09 O.OOE-OI 2.06E+09 D.DOE-'Ol
( ) )
t-) ( )
-t) ) (
C 137 2'36E 09 I'DDE 08 1'67E 0 I I'60E 10 5'21E 09 0'OOE Ol ( I'BBE'09 ) 0'DDE 01 (
)
t) - )
1 -- --t ) )
Bal40 )
1.81Et06 )
1.57Et07 )
3.09Et07 2.71Et04 )
8.82Et03 )
O.OOE-DI )
1.62Et04 O.OOE-OI
) ( (
t t Cel41 (
2.91Et03 ( 2,45Et07 ) 3.93Et04 (
1.96Et04 (
8.60Et03 ( O.OOE-OI [ O,DDE-DI ( O.OOE-OI (
Ce144 (
2.44E 05 3.73E 08 4.57E 06 1.43E 06 )
7-93E 05 )
O.ODE-OI ) O.OOE-OI O.ODE-OI
) ) ) ) )
(a) R values are in units of mrem/yr per It Ci/m3 for tritium, and in units of m2-mrem/yr per Ij Ci/sec for all others.
(b) 3.17E+O3 " 3,17 X 103.
I I
I I
I
TABLE 4-11 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION~a)
PATI5IAY > COW IIILK AGE GROUP ~ IIIFAIIT UUCLIDf . T. BODY GI-TRAC'I Botif LI VfR KIOIIEY TIIYRQID LUIIG SKIN
-vgt- + e e +
B 3 4.80ft0$ f 4.80Et03 O.OOE-OI 4.80Et03 4.80Et03 4.80Et03 4.80Et03 4.80Et03
)
t-- ) ) ) ) ) )
-+)
IIn 54 4.18Et06 6.78Et06 I O.QOE-01 I 1.85Et07 4.09Et06 O.OQE-OI I O.OOE-OI I O.OQE-OI
) I
} I
}- ----- f-----
Cr 51 4.66Et04 1.36Et06 I O.OOE-OI I 0.00E-01 6,64Et03 ) 3.04Et04 I 5.92Et04 I O,OOE-OI I
} } }
Fa 59 )
5.03Et07 6.09Etol )
1.30Etol I 1.2BEtoB O.OQE-ol O.OOE-OI 3.77Et07 O.OOE-01
)
t) ) ) )
Co 58 2.23Et07 2.23Etol I Q.QOE-OI I 8.96Et06 O.OOE-OI I O.OOE-OI I O.OOE-ol I O.OOE-ol I tI I
} -t--- - ----t Co 60 )
1.06Etoo I 1.07Et08 I O,oof-ol I 4,51Et07 O.OQE-QI I O.OOE-OI I O.QOE-OI I Q.OQE-OI I In 65 )
4.05Et09 I 7.42Et09 I 2.56Et09 I 8.79Et09 }. 4.26Et09 I O.OOE-OI I O.OOE-OI I O.OOE-OI 5r 89 1.22Et08 8.71Et07 I 4.24Et09 I Q.QOE-01 I O.QOE-OI O.OOE-DI I O.OOE-OI I O.OOE-OI
)
tI I 5r 90 I 1.60E+10 I 7.87Et08 )
6.30Etlo I O.OOE-QI I Q.OOE-OI O.OOE-OI I O.OOE.OI ) O.OOE-DI I Zr 95 4.23Et02 )
2.91Et05 )
2.45Et03 )
5.97ft02 6.43Et02 O.OQE-OI )
O.OOE-Ol O.OOE-OI )
t)
) )
5bl24 I 2.30Etol I 2.29Et08 I 7.41Et07 I 1.09ft06 I O.OQE-ol 1.91E 05 4.64Et07 ) O.OQE-OI I
}
I 131 )
3.69Et08 )
3.00Etol )
7.13Et08 )
8.40Et08 9.81Et08 2,76Etll O.OQE-QI I Q.OOE-QI I I 133 4.06Et06 2.35Et06 9.52Et06 1.39Etol 1.63Etol 2.52Et09 O.OOE-QI I O.OOE-QI
)
-t----------t--
) ) )
Csl34 I 3.43Et09 I 9.23Et07 ) 1.82ftlo ) 3.40E+10 I 8,74Et09 O.OQE-QI 3.58f+09 I O.OOE-OI
} }
Cs137 I 2.21Et09 )
9.76Etol ) 2.67Etlo )
3.12Etlo )
8.3BFt09 O.OOE-ol ) 3.39ft09 O.OQE-OI Ba 140 3.28E 06 1.56Etol 6.37E Ol 6.31Et04 1.51Et04 Q.OOE-OI 3.91Et04 O.oof-ol
) ) ) )
t t---
)
- - - f
)
} } }
Co141 5.60E 03 2.4GEtol 7..80E 04 4.76E 04 ) 1.41Et04 I O,OQE-OI O.OOE-ol 0 ~ OOE-Ol
) )
t-
) )
-t----------t- )
L 1 CQI44 3.67ft05 3.76Et08 6.54Et06 2.6BEt06 I I.OBEt06 ) O.OOE-OI 0;OOE-Ol
}
)
}
) )
t------- }
(a) R values are in units of mrem/yr per It Ci/m3 for tritium, and in units of m2-mrem/yr per lj Ci/sec for all others.
(b) 4.80E+03 4.80 X 10 .
'I
I I
t I
TABLE 4-12 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION~a)
PATIMAY < IHUAL AGE GROUP ~ ADULT NUCLIDE T.BODY Gl-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
--- ---f--------tE.f--------- f + + - +
3 )
1.26ff00 I 1.26ff03 (
0.00E-DI )
1.26ff03 )
1.26ff03 (
1.26ff03 )
1.26fi03 ) 1.26Ef03 )
ltd 54 6.29E003 ( 7.72ff04 O.OOE-OI 3.95ff04 9.83ff03 O.OOE-D1 1.40E+06 O.OOE-OI
( ( ( ( (
)
(
-t
(
Cr 51 ( 9.99EEQI ) 3,32fi03 ( O.OQE-OI f O.OOE-Ol ( 2.28ff01 ( 5.94ff01 1.44E+04 (
O.OOE-OI (
I Fe 59 1.05fi04 1.88fi05 )
1.17ff04 2.77Ef04 )
O.OOE-OI O.OOE-QI 1.01Ef06 0.00E-QI f( (
t t-
)
Co 58 (
2.07fi03 (
1.06ff05 ) O.ODE-OI ) 1.58ff03 ( 0.00f-01 ) O.OOE-OI 9.27fi05 ) O.OOE-OI J
Co 60 1.48E<04 )
2.84E005 (
O.OOE-QI I.ISEf04 )
Q.QOf-QI )
Q.QOE-OI 5.96ff06 (
O.OOE-QI f) )
~
Zn 65 4.65E004 5.34ff04 3.24E+04 1.03ff05 6.89ff04 O.OOE-OI 8.63E405 I O.OOE-QI
( ( ) ( ) ( )
-f------ ---f I
Sr 89 8.71ff03 3.49ff05 3.04ff05 ( O.OOE-OI ( 0.00f-01 ) O.ODE-Ol 1,40ff06 ( 0.00E-OI I I I I Er 90 6.09E506 7.275r05 9.945r07 O.OOE-01 [ 0.005-01 t O.OOE-Ol 9.59fi06 (
O.OOE-QI (
I I I J I Zr 95 2.32ff04 1,50fi05 1507Ei05 3.44fi04 5.4IEf04 O.OOE-QI 1.77E+06 O.OOE-QI
) ) ) ) ( )
-t----------f)
(
94124 [ 4.245r04 [ 4.065r05 / 3.725r04 5.005r02 O.OOE-Ol / 7.545r04 2.48ff06 O.DOE-QI )
f 7 I (
I 131 ( 2.05E<04 ) 6.27ff03 (
2.52ff04 ( 3.57ff04 )
6.12ff04 ) 1.19E<07 O.OOE-QI I O.OOE-QI I I
I 133 ) 4.51Ef03 )
8.87ff03 ) 8.63fi03 1.48Ef04 2.58ff04 2.15ff06 O.OOE-OI I O.OOE-OI
)
t) ) )
Csl34 ) 7.27ff05 ( 1.04E>04 ) 3.72fi05 ( 8.47ff05 ) 2.87ff05 (
O.OOE-OI 9.75ff04 ( O.OOE-OI I
Csl37 ( 4.27fi05 ) 8.39fi03 4 ~ 78E'05 6 20E'05 2-22E 05 I 0 OOE 01 7.51ff04 O.OOE-OI
) ( )
I f--
(
De140 2.56E503 ) 2,18ff05 3,90ff04 ( 4.90ff01 1.67fwDI O,OOE-OI 1.27ff06 Q.OQE-OI
) )
t) ) ( )
Cel41 ) 1.53E<03 ) 1.20E<05 ( 1.99ff04 ( 1.35ff04 ) 6.25f<03 ( O.OOE-01 3.61fi05 (
O.OOE-OI (
)
Cel44 ( 1.84E>05 8.15ff05 3.43fi06 1.43ff06 8.47ff05 O.QDE-QI 7.76E506 O.OOE-QI
f----------f- ( )
-f-
) )
} I )
(a) R values are in units of mremlyr per Ij Ci/m3.
(b) 1.26E&3 1.26 X 103.
I t
l l
k
TABLE It-13 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION(+)
PATIMAY ~ INHAL AGE GROUt' TEEN NUCLIDE T.BODY Gl-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
t--------re t + t H 3 1.27fto) f 1.27Et03 ( O.OOE-OI ) 1.27Et03 1.27Et03 1.27Et03 1.27ft03 1.27Et03
)
- -----t----------f----------t- ) (
t) )
fh 54 ( 8.39Et03 6.67Et04 ( O.OOE-OI ( 5.10Eta4 1.27Et04 O.OOE-OI 1.98Et06 O.OOE-OI
~
- I(
(
l (
f)
Cr 51 1.35E+02 3.00ft03 ( D.OOE-OI D.DOE-DI 3.07Etol 7.49Etal 2 '9E 04 0 OOE 01
t----------t----------f----------t-
) ) )
1
(
f(
tI f(
Fe 59 )
1.43Et04 )
1.78Et05 )
1.59ft04 3.69Et04 O.OOE-OI O.OOE-OI )
1.53Et06 )
O.OOE-DI Co 58 ( 2.77Et03 )
9.5lf f04 ( O.OOE-OI 2.07Et03 O.OOE-OI O.OOE-OI ( 1.34ft06 ( o.aaf-al (
Ca 60 ( 1.98Et04 2.59Et05 ( O.OOE-OI 1.51Et04 O.OOE-DI O.OOE-OI ( 8.71E+06 (
O.OOE-DI )
) 1 )
En 65 ) 6.23Et04 4.66E+04 3,85Et04 1.33Etas 8.63Et04 O.OOE-DI ) 1.24E+06 O.OOE-OI t )
Sr 89 1.25Et04 3.71Et05 4.34Et05 O.OOE-OI O.OOE-OI O.OOE-DI ( 2.41E+06 O.OOE-OI e
(
f ) f Sr 90 ( 6.67Et06 7.64Et05 1.08Et08 o:aof-ol a.aaE-al 0.00E-DI 1.655+07 }'.005.07
$ J Er 95 3.15Et04 )
1.49Et05 1.45Et05 4.58Et04 6.73Et04 O.OOE-DI ( 2.68Et06 ( D.OOE-DI (
)
f Sb124 1.68Et04 3.98Et05 4.30Et04 7.92Et02 O.OOE-DI 9.75Et07 3.045406 O.OOE.01
( (
) l J f f I 131 2.64Et04 )
6.48Et03 )
3.54E+04 )
4.90ft04 ( 8.39Et04 7.466<07 D.OOE-01 O.OOE-01 /
f f I 133 )
6.21Et03 1.03ft04 1.21Et04 )
2.05Eta4 ( 3.59Et04 2.92Et06 O.OOE-DI O.OOE-DI )
t) )
1 Cs134 5.48Et05 9.75Et03 5.02Et05 1. 13Et06 3.75Et05 O.OOE-DI 1.46Et05 O.OOE-OI
)
t) -- - -t) ) )
Cs137 3. IIEt05 )
8.47Et03 )
6.69EODS )
8.47Et05 (
3.04Et05 ( O.OOE-DI ( 1.21Et05 )
O.OOE-OI')
t( ~j Ba140 3.51Et03 )
2.28Et05 5.46Et04 )
6.69ftDI 2.28Etol )
O.OOE-OI )
2.03Et06 )
O.OOE-OI )
t) ) )
Cel41 2. 16Et03 )
1.26EtaS ( 2.84Et04 1.89Et04 ( 8.87Et03 (
O.OOE-OI (
6.13Et05 (
O.OOE-OI (
Ce144 )
2.62Et05 )
8.63Et05 (
4.88Et06 )
2,02Et06 ( 1.21Et06 )
O.OOE-OI ( 1.33Et07 (
O.OOE-OI (a) R values are in uairs of mrem/yr per It Ci/m3.
(b) 1.27E+03 ~ 1.27 X 103.
II I
i
(
I
TABLE 4-14 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION(+)
PATNAY ~ IHHAL AGE GROUP ~ CHILD HUCLIDE T. BODY Gl-TRACT BORE LIVER KIDNEY THYROID LUHG SKIN
t--------(gt -- ----- t t
- 1. 12ft03 f 1. 12ft03 1.12ft03 1.12Et03 1.12Et03 1.12Et03 1.12Eto3 A
H 3 O.OOE-OI J J J J ) J
-- ---t-
) J Hn 54 9.50Et03 2.29Et04 O.OOE-OI 4.29Et04
- I.OOEt04
~ O.OOE-OI ) 1.57Et06 O.OOE-OI )
})
J J J
} } }
Cr 51 1.54Et02 I.OBEt03 J O.DOE-01 O.DOE-Ol 2.43Etol J 8.53Etol
~
I 1.70Et04
~ O.OOE-OI J
} } }
J J Fe 59 J 1.67ft04 J 7.06Et04 J 2.07Et04 3.34Et04 J O.OOE-OI )
O.OOE-OI ) 1.27Et06 )
O.OOE-OI )
Co 58 3. 16f+03 3.43Et04 J O.OOE-OI 1.77E+03 O.OOE-OI O.OOE-QI ) 1.10E+06 J O.OOE.OI
} } }
J J J jQ Co 60 J 2,26Et04 J 9.6lft04 ) O.OOE-OI 1.31Et04 O.OOE-OI J D.ODE-DI ) 7.06Et06 ) O.OOE-OI J
} }
Zn 65 J 7.02Et04 )
1.63Et04 )
4.25Et04 )
1.13ft05 7. 13Et04 O.OOE-OI 9.94Et05 J O.OOE-OI J m
Sr 89 1.72Et04 ) 1.67ft05 ) 5.99Et05 O.OOE-OI O.QQE-OI ) O.OOE-OI 2.15Et06 ) O.OOE-OI )
m } } } }
Sr 90 6.43Et06 3.43Et05 )
1.01Et08 O.oof-ol O.OOE-OI O.OOE-OI 1.47E+07 O.OOE-OI J t) )
J J
}
Zr 95 )
3.69Et04 J
- 6. IOEt04 )
1.90E+05 )
4.17Et04 5.95Et04 O.OOE-OI 2.23Et06 )
O,OOE-DI )
+
Q3 Sbl24 J 2.00Et04 }. 1.64Et05 ) 5.73Et04
}
7 .39Et02 4.80Et04
}
0.00E-OI
}
1.26Et02 7.87Et04 IJ 1.62ft07
) 3.24Et06 )
O.OOE-OI )
I 131 2.72Et04 2.84Et03 4,80Et04 O.OOE-OI O.OOE-OI J
l ) ) )
I 133 7.68Et03 5.47Et03 1.66Et04 2.03Et04 3.37E+04 3.84Et06 O.OOE-OI O.OOE-OI
) ) ) ) ) )
f----------t-------"---t
) )
t'ai Cs134 2.24E t05 3.84Et03 )
6.5OEtO5 )
I.OIE.06 3.30E 05 ) O.OOE-OI )
1.2lft05 )
O.OOE-OI )
t J
tJ ETl Csl37 1.28Et05 3. 61Et03 9. 05Et05 8, 24Et05 2.82Et05 O.OOE-OI 1.04Et05 O.OOE-OI
)
} -t)
- -- -- -t-
)
} tJ J J Bnl40 4.32Et03 1.02Et05 7.39Et04 6.47Et01 I 2.11Etol O.OOE-OI 1.74Et06 O.OOE-OI ED +
Q t-J J ) ) ) ) J )
Ce141 2.89Eto3 5.65Et04 3.92Et04 1.95Et04 8.53E+03 O.OOE-OI 5.43Et05 O.ODE-OI
~ ~
J
}
) J
}
) J ) J Ce144 3.61Et05 3.88Et05 i 6.76Et06 i 2. IIEt06 1.17Et06 J 0.00E-DI 1.19Et07 0.00E-OI CO ln J
tJ
} } } }
(a) R values are in units of mrem/yr per IjCi/m .
(b) 1.12E&3 1.12 X 103.
I I
TABLE 4-15 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION(a)
PAl)NAY > IHllAL AGE GROUP ~ lNFAHT HUCLlDE T.BODY Gl-TRACT BONE LI VER KIDNEY THYROlD LUNG SKlH
vgt---- t t H 3 )
6.4&E+04l $ 6.46Et02 ) O.OOE-OI 6.46E+02 )
6.46Et02 6.46E+02 6.4&Et02 6.46Et02
+ t) t
) )
Hn 54 4.98Et03 7.05Et03 O.OOE-DI 2.53Et04 4.98Et03 0.00f-01 9.98Et05 O.OOE-OI l'
) ) ) ) ) ) )
f Cr 51 0.93sisl 3.565402 i 0.00E-ol O.OOE-O1 i 1.322ial i 5.256~03 i 3.206+04 O.OOE-O1 f i l t ~ i Fe 59 9.46Et03 2.47Et04 1.35Et04 2.35Et04 O.OOE-DI O.OOE-OI I.DIE+06 O.OOE-OI
)
---t------ ---t-
) ) ) )
t ) ) )
Co 58 i 1.82E 03 ) l. Ilf 04 ) O.OOE-OI 1.22Et03
~ - )I ~
O.OOE-OI ~
I) O.OOE-OI ) 7.76Et05 ) O.OOE-OI Ca 60 1.10E504 3.396<04 i O.OOE-al B.OLEt03 O.OOE-OI O.OOE-OI 4.50Et06 O.OOE-DI
[ ) l ) ) ) )
t)
Zn 65 ) 3. 10Et04 )
- 5. 13Et04 1.93Et04 ) 6.25Et04 ) 3.24Et04 ) 0.00f-DI ) 6,46Et05 ) O.ODE-DI )
t)
Sr 89 )
1.14Et04 6.39Et04 ) 3.97Et05 )
0.00E-OI ) O.OOE-OI ) O.OOE-DI ) 2.03Et06 ) O.OOE-DI )
t)
Sr 90 2,59Et06 1.31Et05 ) 4.08E007 O.OOE-OI O.OOE-OI O.OOE-OI 1.12Et07 O.ODE-OI
)
t) )
) I f f Lr 95 2.03Et04 )
2.17Et04 1.15Et05 )
2.78Et04 )
3.10Et04 O.OOE-DI )
1.75Et06 )
O.OOE-DI )
) )
t t Sbl 24 3.206+04 E.sasi04 i 3.19Ei04 i 5.555i02 / 0.00E-O! I.OOEt02 2.64E+06 ) O.DOE-OI f f )
1 131 1.96Et04 ) 1.06Et03 )
3,79Et04 ) 4.43Et04 ) 5.17Et04 1.48Et07 ) O.OOE-OI ) O.OOE-OI )
t)
I 133 Csl34
- l. 5.59Et03 7.44ft04
) 2. 15Et03 1.33Et03
) 1.32Et04 3.9&Et05
)
)
1.92Et04 7.02Et05
)
)
2.24Et04 1.90Et05 )
3.55E+06 O.OOE-OI
)
)
O.OOE-OI 7.95Et04
)
)
O.OOE-OI O.OOE-OI )
)
1 f Csl37 4.54Et04 ) 1.33Et03 )
5.48Et05 ) 6.11Et05 ) 1.72E 05 ) O.OOE-DI ) 7.12Et04 ) O.OOE-OI,)
Da140 )
2.89Et03 )
3.83E 04 )
5.59E 04 )
5.59E Ol )
1.34E 01 )
O.OOE-OI
)
1.59E 06 )
O.OOE-OI ).
CeI41 1.99Et03 ) 2.15Et04 ) 2.77Et04 ) 1.66Et04 ) 5.24ft03 )
O.OOE-OI )
5.16Et05 ) O.OOE-OI )
Cel44 )
1.76Et05 )
1.48Et05 )
3.19Et06 )
1.21Et0& )
5.31Et05 )
O.OOE-OI )
9.83Et06 )
O.OOE-DI (a) R values are in units of mremlyr per n Ci/m3.
(b) 6.46E+02 " 6.46 X 10~.
I I
k
TABLE 4-16 (Sheet 1 of 3)
PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PAT)lWAY LOCATIONS CENTERED ON UNIT 1 RESIDENCE(c) GARDEN(c) MILK(c)
DIRECTION X /Q D/9 x/q D/g x/q D/Q (Sec/m3) (m ~) (Sec/m ) (m ) (Sec/m3) (m ~)
N 2.92E-06(b) 3.25E-09 2.92E-06 3.25E9 7.03E-07(a) 3.48E-10(a)
NNE 1.81E&6 2.88E-09 4.70E-07(a) 4.04E-10<<) 4.70E-07(a) 4.04E-10(a)
NE 1.95E&6 3.85E-09 1.76E6 3.29E&9 5.77E-07(a) 6.51E-10(a)
ENE 1.03E&6 1.08E-09 1.03E-06 1.08E-09 3.86E-Q7(a) 2.86E-10(a)
E 9.39E&7 6.68E-10 3.71E-07(a) 1.87E-10(a) 3.71E-07(a) 1.87E-10(a)
ESE 6.37E-07 2.84E-10 4.12E-07 1.60E-10 4.12E7 1.60E-10 SE 8.83E&7 2.61E-10 8.83E-07 2.61E-10 5,84E-07(a) 1.52E-10(a)
SSE 1.27E&6 2.61E-10 1.09E-06(a) 2.15E-10(a) 1.09E-06(a) 2.15E-lQ(a)
I S 2. 58E6 4. 85E-1 0 2.09E-06 3.59E-10 2.13E6 3.71E-10 SSW 3.26E-06 8.26E-10 2.28E&6(a) 4.53E-10(a) 2.28E&6(a) 4.53E-10(a)
SW 2.80E&6 9.10E-10 1.58E-06(a) 3.56E-10(a) 1.58E-06(a) 3.56E-10(a)
WSW 1.95E&6 1.09E-09 8.55E&7 a 3.18E-10 a 8.55E&7 a 3.18E-10(aj W 7.54E-07<<) 4.44E-10(a) 7.54E-07 a 4.44E-10 a 7 54E&7 a 4.44E-10<<~
WNtf 6.03E-07(a) 3.25E-10(a) 6.03E-07(a) 3.25E-10(a) 6.03E-07(a) 3.25E-10(a)
NW 8.24E-07 5.25E-lQ 7.55E-07 4.61E-10 6.02E-07(a) 3.27E-10(a)
NNW 1.46E&6 1.47E-09 5.20E-07(a) 3.04E-10(a) 5.20E-07(a) 3.04E-lo(a) 5-mile value used since there is no pathway located within the sector up to five miles.
(b) 2.92E-06 ~ 2.92 x 1Q-6 O
M gQ Locations of these residences, gardens and milch animals are given in Table A-l, sheet l.
lO ~ Controlling locations are discussed in Appendix A.
mW CO
References:
1984 Land Use Census (letter ANPH-21221-JRH/LEB).
NUS Corporation letters NUS-ANPP-1385 and NUS-ANPP-1386.
I I
I 1
~
I l
Il
TABLE 4-16 (Sheet 2 of 3)
PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 2 RESIDENCE(c) GARDEN(c) MILK(c)
DIRECTION x/Q D/Q x/q D/Q x/q D/9 (Sec/m3) (m ) (Sec/m3) (m ") (Sec/m3) (m ~)
N 2.73E-06(b) 2.92E-09 2.39E&6 2.35E&9 7.03E-O7(a) 3 48E-10(a)
NNE 2.20E-06 3.87E-09 2.20E&6 3.87E-09 4.70E-07(a) 4.04E-10(a)
NE 1.85E-Q6 3.55E-09 1.57K&6 2.78E-09 5.77E-07(a) 6.51E-10(a)
ENE 1.03E-06 1.08E-09 1.03E&6 1.08E&9 3.86E"07(a) 2;86E-10(a)
E 8.80E-07 6.06E-10 3.71E-O7(a) 1.87E-1Q(a) 3.71E-Q7(a) 1.87E-10(a)
ESE 6.25E-07 2.76E-10 3.96E-07 1.51E-10 3.96E&7 1. 51E-10 SE 9.06E-07 2.72E-10 9.06E&7 2 '2E-10 5.84E-Q7(a) 1.52E-10(a)
SSE 1.34E&6 2.81E-10 1.09E-06(a) 2.15E-10(a) 1.09E&6(a) 2.15E-10(a)
S 2. 63E&6 5.01E-10 2. 19E-'06 3.88E-10 2.19E-06 3.88E-10 SSW 3.48E-06 9.19E-10 2.28E-06(a) 4.53E-10(a) 2.28E-06(a) 4.53E-10(a)
SW 2.93E&6 9.75E-10 1.58E-06(a) 3.56E-1Q(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&7 a . 3.18E-10(a)
W 7.54E-07<<) 4.44E-10<<) 7.54E-07 a 4.44E-10 a 7 54E 07 a 4.44E-10<a>
WNW 6.03E-07(a) 3.25E-10(>> 6.03E-07(a) 3.25E-10(a) 6.03E-07(a) ~ 3.25E-10(a)
NW 7.84E-07 4.88E-10 7.84E-07 4.88E-10 6.02E-07(a) 3.27E-10<<)
NNW 1.46E6 1.47E-09 5.20E-07 3.04E-10 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.
2.73E-06 ~ 2.73 x 10 6 Locations of these residences, gardens and milch animals are given in Table A-lp sheet 2.
Controlling locations are discussed in Appendix A.
References:
1984 Land Use Census (letter ANPM-21221-JRM/LEB).
NUS Corporation letters NUS-ANPP-1385 and NUS-ANPP-1386.
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TABLE 4-16 (Sheet 3 of 3)
PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 3 RESIDENCE(c) GARDEN(c) MILK(c)
DIRECTION x/q D/g x/q D/g X/q D/Q (Sec/m3) (m ~) (Sec/m3) (m-~) (Sec/m3) (m )
N 2.58E-06(b) 2.47E-09 2.42E-06 2.22E&9 7.03E-07(a) 3.48E-10 <<)
NNE 1.85E-06 2.97E-09 1.85E&6 2.97E-09 ~
4.70E&7(a) 4.04E-10(a)
NE 1.66E&6 3.00E-09 1.48' 2.54K&9 5.77E-07(a) 6.51E-10(a)
ENE 8.75E-07 8.86E-10 8.75E&7 8.86E-10 3.86E&7(a) 2.86E-10(a)
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&7(a) 1.37E-10(a)
SE 5.84E-07<<) 1.52E-10(a) 5.84E-07(a) 1.52E-10<<) 5.84E-07(a) 1.52E-10(a)
SSE 1.36E&6 2.88E-10 1.09E-06(a) 2.15E-10<<) 1.09E&6( ) 2.15E-10( )
S 2.65E-06 5.25E-10 2. 25E&6 4.06E-10 2.31E-06 4.21E-10 SSW 3.64E&6 9.82E-10 2.28E-06(a) 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 W 7.54E-07<<) 4:44E-10(a) 7.54E-07 a 4.44E-10 a 7.54E-10 a 4.44E-10 a WNW 6.03E-07(a) 3.25E-10(a) 6.03E-07<<) 3.25E-10(a) 6.03E-07<<) 3.25E-10(a)
NW 6.83E&7 4.05E-10 6.82E-07 4.05E-10 6.02E-O7(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 10 Locations of these residences, gardens and milch animals are given in Table A-l, sheet 3.
Controlling locations are discussed in Appendix A.
References.'984 Land Use Census (letter ANPM-21221-JRM/LEB).
NUS Corporation letters NUS-ANPP-l385 and NUS-ANPP-1386,
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CGNTRGLLED BY USER 5.0 TOTAL DOSE 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 MEMBER 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:
OgB (3. 7 x 10 ) i [(Ki) (X/g)RU (qi)]
5-1 Rev.. 1 CQNTRQLLED BY USER
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CGNTRGLLED BY USER Where:
Ki the whole body dose factor due .to gamma emissions for each identified noble gas radionuclide i, in mremlyr peru Cifm3 from Table 3-1.
the integrated release of radionuclide i, in'i for the previous calendar year.
<<~)RU the highest calculated annual average dispersion parameter, in seclm 3 , for a particular unit, at the controlling location, from Table 4-1.6; or
, concurrent meteorological data'if available..
~ 2.92x10 -6 from Unit 1
~ 2.19x10 from Unit 2 2.31xlO from Unit 3 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:
Do (3.17 x 10 ) E i [ Ek(RikWk )(Qi)] (4-3)
,Where:
D 0
the total annual organ dose from gaseous effluents to a MEMBER OF THE PUBLIC, in mrem, at the controlling location.
CONTROLLED BY USER"o'i'".i-
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CQNTRQLLED BY USER the integrated release of radionuclide i, in PCi, for the previous calendar year.
the dose factor for each identified radionuclide for pathway k (for the inhalation pathway in 3
mrem/yr per ~Ci/m and for the food and ground plane pathways in m 2 -mrem/yr per MCi/sec) at the controlling location. 3he Rik '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 OP THE PUBLIC at the controlling location for the particular unit.
3
( X/Q)RU, in sec/m 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.
~ 2.92xl0 from Unit 1
~ 2.19x10 from Unit 2
~ 2.31x10 from Unit 3
-2 (D/Q)RU, 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.
-9 3.25x10 from Unit 1
~ 3.88xl0 -10 from Unit 2
-10 4.21x10 from Unit 3 l:QNTRQLLED BY USERo9i2ois~
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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 1. An assumption was made that no MEMBER OF THE PUBLIC would spend more than eight hours per year at this location.
X/Q, determined for the Visitor Center, will be used for this assessment.
Equations 5-1 and 4-3 in Sections 5.1.1 and 5.1.2 should be used for this assessment. Qi should be the integrated release of radionuclide i, in 0 Ci, 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 Q ).
5-4 Rev. 1 l."QNTRQLLED BY USER""""
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6.0 OPERABILITY OF E UIPMENT The flow diagrams defining the treatment paths and the components of the liquid, gaseous, and solid radioactive waste .systems are shown in Figures 6-1 through 6-3, respectively.
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- 7. 0 RADIOLOGICAL ENVIRONMENTAL PROGRAM 7.1 Radiolo ical Environmental Monitoring 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'n 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 7-3. 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. 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 radiation 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. The initial radiological environmental monitoring program will be conducted for the first three years of commercial operation of Unit l. Following this period, program changes may be proposed based on operational experience. Deviations are 7-1 CGNTRGLLED BY USER
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CGNTRGLLED BY USER 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. 7.2 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 2 (500 ft2 ) 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 from current sample locations, appropriate changes in the sample locations are made. Xf a land use census identifies a location(s) with a higher average annual deposition rate (D/Q) than a current indicator location, the following applies:
- l. If the D/Q is at least 20X greater than a previously high D/Q, one of the existing sample locations may be replaced after an evaluation with a new one within 30 days. The.
7-2 CGNTRGLLED BY USER
CGNTRGLLED BY USER, evaluation is based on past history of the location, availability of sample, milk production history, aad other environmental conditions.
- 2. If the D/Q is aot 20X greater than the previously highest D/Q, distance and D/Q are considered in deciding whether to replace one of the existing sample locations. If applicable,I replacement is made withia 30 days.
A land use ceasus is coaducted at least once per calendar year by a door-toMoor or aerial survey, by consulting local agricultural authorities, or by any combination of these methods. 7.3 Interlaborator Com arison Pro ram Technical S ecificatioa 3.12.3 - Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that has beea approved by the Commission that correspond to samples required by [Technical Specification] Table 3.12-1. PVNGS laboratories or coatract laboratories which perform analyses for the Radiological Environmental Monitoring Program participate in the Environmental Protection Agency's (EPA's) Environmental Radioactivity Laboratory Intercomparisons Studies (Crosscheck) Program. This participation includes all of the determinations (sample medium-radionuclide combination) that are offered by EPA and that also are included in the monitoring program. The results of analyses of these crosscheck samples are included in the annual report. 7-3 CGNTRGLLED BY USER
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TABLE 7-1 (Sheet 1 of 4) RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS SAr1PLE SAMPLE LOCATION SITE TYPE DESIGNATION(a) LOCATION DESCRIPTION TLD, Air E30 APS Goodyear Office TLD ENE24 Scott-Libby School TLD E25 Liberty School TLD, Air E20 APS -Buckeye Of fice TLD ESE15 Palo Verde, AZ TLD, Air (Control)(b) SSE35 APS Gila Bend Substation Tro() SE7 Old U.S. 85 and Arlington School Road 7A Air Arlington School 8 TLD SSE5 Corner of 363rd Ave. & Southern Pacific Pipeline Rd.. 9 Tro( ) S5 Corner of 371st Ave. & Southern Pacific Pipeline Rd. 10 TLD SE5 Corner of 355th Ave. & Ward Rd. TLD ESE5 Corner of 339th Ave. & Dobbins Rd. 12 TLO(" E5 Corner of 339th Ave. & Buckeye-Salome Rd. 13 TLD Nl N Site Boundary 14 TLD NNE2 NNE Site Boundary 14A Ai'" Buckeye-Salome Rd. & 371st Ave. 15 TLD P Air NE2 NE Site Boundary 16 TLD ENE2 ENE Site Boundary 17 Tr.o(b) E Site Boundary
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TABLE 7-1 (Sheet 2 of 4) SAMPLE SAMPLE LOCATION SITE TYPE DESIGNATION '(a) LOCATION DESCRIPTION 17A Air E4 351st Ave., 1 mi. S of Buckeye Salome Rd. 18 TLD(b) ESE2 ESE Site Boundary 19 TLD SE2 SE Site Boundary 20 ...(b) SSE2 SSE Site Boundary 21 TLD , Air S3 S Site Boundary 22 TLD(b) SSM3 SSM Site Boundary 23 -D(b) M5 2 miles N. of Ward Rd., 3 miles W. of Wintersburg Rd. 24 SM4 Ward Rd. at Desert Farms 25 TLD(b) MSW5 Ward Rd. at Cattle Guard 26 TLD(b) SSW5 Shepard Farm TLD SW2 SW Site Boundary 28 TLD(b) WSM1 WSW Site Boundary 29 TLD(b) Ai (b) W Site Boundary 30 TLD(b) MNW Site Boundary 31 TLD(b) NW Site Boundary 32 TLD(b) NNM Site Boundary 33 TLD Yuma Rd., 1/2 mile W of Belmont Rd. 34 TLD NNW5 Corner of Belmont Rd. & Van Buren Rd. 35 TLD , Air Tonopah, Palo Verde Inn Pire Station 36 TLD N5 Corner of Mintersburg Rd. & Van Buren Rd. XLD NNE5 Corner of 363rd Ave. & Van Buren Rd.
l TABLE 7-1 (Sheet 3 of 4) SAMPLE SAMPLE LOCATION SITE . TYPE DESIGNATION ( LOCATION DESCRIPTION 38 TLD NE5 Corner of 355th Ave. & Yuma Rd. 39 L,(b) ENE5 343rd Ave., 1/2 mi. South of Lower Buckeye Rd. 40 TLD , Air N3 Mintersburg, AZ 41 TLD (b) WNW20 Harquahala Valley School 42 TLD") N8 Ruth Fisher School 43 TLD N45 Vulture Peak School (Mickenburg, AZ) 44 TLD $ Air ENE35 APS El Mirage Office (Sun City, AZ)) 45 TLD (b) (Control). E20 REMP Lab. (Buckeye, AZ) (Lead PIG) 46 Water (b) (Control) NNW9 McArthur's Farm (Tonopah, AZ)) 47 Vegetation (b) NE3 Adams Residence 48 Water SW5 Desert Farms 49 Water (b) ESE4 Medgeworth Residence, 351st Ave. & Dobbins 50 Milk NE7 Baisley Dairy, 331st Ave. & Van Buren Rd. 51 Milk( Vegetation Ell Butler Dairy, Palo Verde Rd. & Southern Ave. 52 Vegetation (b) E15 Cambron Farm, Hiller Rd. & Broadway Rd. 53 Hilk E26 Kerr Dairy, Dean & Buckeye Rds. 54 Hilk E27 Skousen Dairy, Airport & Dobbins Rd. 55 Hilk E28 Lueck Dairy, Jackrabbit & Hazen Rds. 56 Milk(b). (Control) E75 Hamstra Dairy !I2, Mcgueen & Ryan Rds. 57 Water (b) Onsite Moll 27ddc 58 Mater (b) Onsite Well 34abb
TABLE 7-1 (Sheet 4 of 4) SAMPLE SAMPLE LOCATION SITE TYPE DESIGNATION ( LOCATION DESCRIPTION 59 Surface Water (b) Onsite PVNGS Evaporation Pond 60 Surface Water (b) Onsite PVNGS Reservoir 61 Citrus (Control) EBO Cooley Farms, Inc. (Higley, Arizona) 62 Vegetation(b) E60 AJM Farms, Inc., Chandler Industrial Park (Control) (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 fulfillthe requirements of the PVNGS Technical Specifications. (c) Refer to Figures 7-1 and 7-2 for relative locations of Sample sites.
I TABLE 7-2 (Sheet 1 of 2) DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS Lower Limit of Detection (LLD)(a) Airborne Particulate Water or Gas Milk Food Products Analysis (pCi/1,) (pCi/m3) (pCi/1) (pCi/kg, wet) Gross Beta 1 x 10 2 H-3 2000(>> Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 I-131 7 K 10-2 60 Cs-134 15 5 x 10-2 15 60 Cs-137 18 6xl02 18 80 Ba-140 60 60 La-140 15 15
l TABLE 7-2 (Sheet 2 of 2) a The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95X probability and with 5X probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radiochemical separation'.66S LLD 2.22 EVY exp -AAt Where: LLD is the 'a priori" lower
~e limit of detection as defined above (asas ppCi per er un t unit mass or volume),
Sb is the standard deviation of the backgound counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), 2.22 is the number of disintegrations per minute per picocurie, E is the counting efficiency (as counts per transformation), U is the sample size (in units of mass or volume), Y is the fractional radiochemical yield (when applicable), his the radioactive decay constant for the particuar radionuclide, and A t is the elapsed time between sample collection (or end of the sample collection period) and time of counting. In calculating the LLD for a radionuclide determined by gamma-ray gamma-r spectrometry, t t , the h background should include the contributions of other radionuclides normally present in the samples (e.g., potassium-40 milk samples). Typical values for E, V, Y, and should be used in the calculations. Zt should be recognized that the ILD is defined as a priori (before tha fact) limit representing the capability of a measurement system and not as a osteriari (after the fact) limit for a particular measurement, i ( )LLD for drinking water.
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TABLE 7-3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM PVNGS Exposure Pathway Sampling and Type and Frequency and/or Sample Collection Frequency of Analysis Sampling Locations Airborne radioiodine Continuous sampling Gross beta weekly; Six locations as and particulates coll'ected weekly I-131 weekly; gamma listed in Table 7-1. spectrum monthly; Control locations are 6 composite of filters and 44 (alternate). Direct radiation TL dosimeters at Gamma dose 'quarterly Forty locations as location changed listed in Table 7-1. quarterly Control locations are 43 and 44. Waterborne: Surface Monthly Composite of Gamma spectrum monthly; On-site reservoir and weekly grab sample tritium quarterly evaporation pond (sample locations 59 and 60). Ground quarterly grab Tritium and gamma On-site well Nos. 34abb and sample spectrums quarterly 27ddc (sample locations 57 and 58). Drinking (Well) Composite or grab Gross beta and gamma Locations 46, 48 & 49. sample one-month spectrums monthly; Control location is 46. period tritium quarterly OQ Ingestion: Semimonthly for Gamraa spectrum and Locations 50, 51, 53 and MQ Milk animals on radioiodine semi- 56. Control location is CQ pasture, other- monthly or monthly 56. Ca wise monthly Ln Food Products Once per harvest Gamraa spectrum and Locations 47, 52 and 62. radioiodine per saraple
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CONTROLLED BY USER APPENDIX A DETERMINATION OF CONTROLLING LOCATION The coatrolling 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 kaown to be a function of (1) Isotopic release rates (2) Meteorology (3) Exposure pathway (4) Receptor's age The iacorporation of these parameters into Equation 4-3 results ia the respective equations at the controlling location. The isotopic release rates are based upon the source terms calculated using the PVNGS Environmeatal Report, Operating License Stage, Table 3.5-12, without carbon. All of the locations and exposure pathways, identified in the 1984 Laad Use Census, have been evaluated. These include cow milk ingestion, goat milk ingestion, vegetable ingestion, inhalation, and ground plane exposure. An iafant is assumed to be present 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 preseat everywhere an individual is preseat. For the determination of the controlling locations, the highest X/Q and D/Q 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 upoa these calculations, it is determined that the coatrolling receptor pathway is a function of unit location. For Unit 1, the controlling receptor is a gardea-child pathway; for releases from Unit 2 and Uait 3 the controlling receptor is a cow milk-infaat pathway. These determinations are based upon Table 4-16 which, in turn, is based upon the 1984 Laad Use Census. Locations o the nearest residences, gardens aad milch animals, as determined in the 1984 Land Use Census, are given in Table A-l. A-1 CONTROLLED BY USERo>>>>i>>
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TABLE A-1 (Sheet 1 of 3) EXPOSURE PATHWAY LOCATIONS NEAREST TO PVNGS UNIT 1 Nearest Nearest Location Nearest Location Milch Location Residence Designator Garden Designator Animal Designator Animal Sector Distance (b) Distance (b) Distance (b) Type Desi ator(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 SSM 3.5 13 (c) (c) SW 2.9 14 (c) (c) WSM 2.6 15 (c) (c) (c) (c) (c) WNW (c) (c) (c) NM 3.8 21 4.1 16 (c) NNM 2.0 17 (c) (c) (a) Sector designators and distances derive from the 1984 Land Use Census (letter ANPM-21221-JRMILEB), and are specific to the subject PVNGS unit. o8 (b) Location designators, and animal types at locations indicated, are from the 1984 Land Use Census (letter ANPM-21221-JRM/LEB) ~ Ni O CX7 (c) Postulated to be at 5 mile distance since the 1984 Land Use Census identified no pathway (residence, Vs garden or milch animal as appropriate) within the sector and within 5 miles.
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TABLE A-1 (Sheet f 2 o 3) EXPOSURE PATHWAY LOCATIONS NEAREST TO PVNGS UNIT 2 Nearest Nearest Location Neares t Location Milch 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 1.5 1 1.7 2 (c) NNE l.'5 3 1.5 3 -(c) NE 2.0 2.3 5 (c) (c)
'c)
ENE 2.7 6 2.7 6 E 3.0 7 (c) (c) ESE 3.7 8 4.7 9 4.7 Goat SE 4,0 10 4.0 10 SSE S 4.5 4.5 ll 19 (c) 5.0 12 (c) 5.0 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 ANPM-21221-JRM/LEB), and are specific to the subject PUNGS unit. M (b) Location designators, and animal types at. locations indicated, are from the 1984 Land Use Census (letter ANPM-21221-JRM/LEB). (c) Postulated to be at 5 mile distance since the 1984 Land Use Census identified no pathway (residence, garden or milch 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 Milch Location Designator 'esidence Garden Designator Animal Designator Animal Sector Distance (b) Distance (b) Distance (b) Type Desi nator(a) Miles(a) Miles(a) Miles(a) N 1.8 1.9 2 (c) A 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 S 4 4.2 ll 19 (c) 4.9 12 (c) 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) C (a) Sector designators and distances derive from the 1984 Land Use Census (letter ANPM-21221-JRM/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 ANPM-21221-JRM/LEB) ~ (c) Postulated to be at 5 mile distance since the 1984 Land Use Census identified no pathway (residence, garden or milch animal as appropriate) within the sector and within 5 miles.
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