RNP-RA/02-0063, 2001 Annual Radioactive Effluent Release Report
| ML021330342 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 04/29/2002 |
| From: | Fletcher B Carolina Power & Light Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| -nr, RNP-RA/02-0063 | |
| Download: ML021330342 (43) | |
Text
TS 5.6.3 CP&L A Progress Energy Company Serial: RNP-RA/02-0063 APR 2 9 2002 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/LICENSE NO. DPR-23 2001 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Ladies and Gentlemen:
The purpose of this letter is to transmit the attached Annual Radioactive Effluent Release Report for the period of January 1, 2001, through December 31, 2001, for the H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2. This report is submitted in accordance with 10 CFR 50.36a(a)(2) and the HBRSEP, Unit No. 2, Technical Specifications, Section 5.6.3.
If you have any questions concerning this report, please contact Mr. C. T. Baucom.
Sincerely, B. L. Fletcher III Manager - Regulatory Affairs DJS/djs Attachment c:
Mr. L. A. Reyes, NRC, Region II Mr. R. Subbaratnam, NRR, NRC (w/o enclosure)
NRC Resident Inspector, HBRSEP Robinson Nuclear Plant 3581 West Entrance Road Hartsville, SC 29550
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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 1 of 42 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 1, 2001 - December 31, 2001 CAROLINA POWER & LIGHT COMPANY H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA!02-0063 Page 2 of 42 TABLE OF CONTENTS Description...............................................................................................................................
Page I.
EXECUTIVE SUM M ARY...................................................................................................
4 A. Discussion.......................................................................................................................
4 B. Significant V ariances....................................................................................................
7 C. Regulatory Com pliance...................................................................................................
9 II.
SUPPLEM ENTAL INFORM ATION..................................................................................
10 A. Regulatory Lim its............................................................................................................
10 B. M easurem ents and Approxim ations of Total Radioactivity...........................................
10 C. Estim ated Total Errors...................................................................................................
12 Iff.
GASEOUS EFFLUENTS....................................................................................................
13 A. Batch Releases.................................................................................................................
13 B. Abnorm al Releases........................................................................................................
.. 13 C. Data Tables......................................................................................................................
13 IV.
LIQUID EFFLUENTS.........................................................................................................
19 A. Batch Releases.................................................................................................................
19 B. Abnorm al Releases.........................................................................................................
19 C. D ata Tables......................................................................................................................
19 V.
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS...............................................
25 A. W aste Class A.................................................................................................................
25 B. W aste Class C.................................................................................................................
27 VI.
40 CFR 190 DOSE CONFORM AN CE...............................................................................
29 VII.
M ETEOROLOGICAL DATA..............................................................................................
29 A. Continuous Release Diffusion Analysis..........................................................................
29 B. M ixed M ode Batch Release Diffusion Analysis............................................................
32 C. Ground Level Batch Release Diffusion Analysis............................................................
35
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RAI02-0063 Page 3 of 42 LIST OF TABLES Table Description..........................................................................................................
Page Table IlI-A Table Ill-B Table Ill-C Table IV-A Table IV-B Table IV-C Table VII-A Table VII-B Table VII-C Gaseous Effluents - Summation of All Releases...................................................
Gaseous Effluents - Ground Level and Mixed Mode Releases..............................
Typical Lower Limits of Detection for Gaseous Effluents....................................
Liquid Effluents - Summation of All Releases......................................................
Liquid Effluents - Continuous Mode and Batch Mode Releases...........................
Typical Lower Limits of Detection for Liquid Effluents.......................................
Joint Occurrence Frequencies for LOWNDDEG and LOWNDSPD C ontinuous R eleases..............................................................................................
Joint Occurrence Frequencies for LOWNDDEG and LOWNDSPD M ixed M ode B atch Releases..................................................................................
Joint Occurrence Frequencies for LOWNDDEG and LOWNDSPD G round Level B atch Releases................................................................................
14 16 18 20 22 24 30 33 36
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 4 of 42 I.
EXECUTIVE
SUMMARY
A.
Discussion
- 1.
Protection Standards The main objective in the control of radiation is to ensure that any exposure is kept not only within regulatory limits, but As Low As Reasonably Achievable (ALARA). The ALARA concept applies to reducing radiation exposure both to workers at H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2 and to the general public. "Reasonably achievable" means that radiation exposure reduction is based on sound environmental practices, economic decisions, and operating practices. By practicing ALARA, HBRSEP and Carolina Power & Light (CP&L)
Company minimizes health risk and environmental detriment, and ensures that exposures are maintained well below regulatory limits.
- 2.
Sources of Radioactivity Released During normal operations of a nuclear power station, most of the fission products are retained within the fuel and fuel cladding. However, small quantities of radioactive fission and activation products are present in the reactor coolant water.
The types of radioactive material released are noble gases, iodines and particulates, and tritium.
The noble gas fission products in the reactor coolant water are released as a gas when the coolant is depressurized. These gases are collected by a system designed for collection and storage for radioactive decay prior to release to the environment.
Small releases of radioactivity in liquids may occur from equipment associated with the reactor coolant system. These liquids are collected, processed for radioactivity removal, prior to and during release.
- 3.
Noble Gas Some of the fission products released in airborne effluents are radioactive isotopes of noble gases, such as krypton, argon, and xenon. Noble gases are by nature inert and do not concentrate in humans or other organisms. Noble gases contribute to human radiation exposure as external exposure. The major isotopes released are Argon-41, Xenon-133, and Xenon-135 with half-lives of approximately two hours, five days, and nine hours, respectively. Half-life is defined as the time required for a radioactive isotope to lose 50 percent of its radioactivity by decay.
Noble gases are readily dispersed in the atmosphere.
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 5 of 42
- 4.
lodines and Particulates Annual releases of iodines, and those particulates with half-lives greater than eight days are small. Factors such as chemical reactivity and solubility in water, combined with high processing efficiencies, minimize their discharge. The main contribution of radioactive iodine to human exposure is to the thyroid gland, where the body concentrates iodine. The principal radioactive particulates are Cobalt-58 and Cobalt-60, which contribute to internal exposure of tissues such as the muscle, liver, and intestines. These particulates can also be a source of exposure if deposited on the ground.
- 5.
Tritium Tritium, a radioactive isotope of hydrogen, is the predominate radionuclide in liquid and gaseous effluents. Tritium is produced in the reactor coolant as a result of neutron interaction with deuterium (also a hydrogen isotope) and boron, both of which are present in the reactor coolant. Tritium is a weak beta particle emitter and contributes very little radiation exposure to the human body, and when tritium is inhaled or ingested it is dispersed throughout the body until eliminated.
- 6.
Processing and Monitoring Effluents are strictly controlled and monitored to ensure that radioactivity released to the environment is minimal and within regulatory limits. Effluent controls include the operation of radiation monitoring systems, in-plant and environmental sampling and analyses, quality assurance programs for both in-plant and environmental sampling and analyses, and procedures that address effluent and environmental monitoring.
The plant radiation monitoring system provides monitors that are designed to ensure that all releases are below regulatory limits. Each instrument provides indication of the amount of radioactivity present and is equipped with alarms and indicators in the control room. The alarm setpoints are set below the regulatory limits, i.e., typically at less than 50 percent of the regulatory limit, to ensure that the limits are not exceeded. If a monitor alarms, a release to the environment from a tank is automatically suspended. Additionally, releases are sampled and analyzed in the laboratory prior to discharge to the environment. The sampling and analysis done in the laboratory provides a more sensitive and precise method of determining pre-effluent composition than in-plant monitoring instruments.
The plant has a meteorological tower, which is linked to computers that record the meteorological data. The meteorological data and the release data are used to calculate dose to the public.
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 6 of 42 In addition to in-plant equipment the company maintains a Radiological Environmental Monitoring Program, which consists of devices used to sample the air and water in the environment. The samples collected from the surrounding environment are analyzed to determine the presence of radioactive material in the environment.
- 7.
Exposure Pathways Radiological exposure pathways are the methods by which people may become exposed to radioactive material. The major pathways of concern are those, which could cause the highest calculated radiation dose. The projected pathways are determined from the type and amount of radioactive material that may have been released, the environmental transport mechanism, and the use of the environment.
Environmental transport mechanisms include, but are not limited to, hydrological (i.e., water) and meteorological (i.e., weather) characteristics of the area.
Information on water flow, wind speed and direction, dietary intake of residents, recreational use of the area and location of homes and farms in the area are some of the many factors used to calculate the potential exposure to offsite personnel.
The release of radioactive gaseous effluents includes pathways such as external whole body exposure, deposition on plants and soils, and human inhalation. The release of radioactive material in liquid effluents includes pathways such as drinking water, fish consumption, and direct exposure from the lake at the shoreline and while swimming.
Even though radionuclides can reach humans by many different pathways, some radionuclides result in more exposure than others. The critical pathway is the exposure which will provide, for a specific radionuclide, the greatest exposure to a population, or a specific group of the population, called the critical group. The critical group may vary depending on the radionuclides involved, the age and diet of the group, and other cultural factors. The exposure may be received by the whole body or to a specific organ, with the organ receiving the largest fraction of the exposure called the critical organ.
The exposures to the general public in the area surrounding HBRSEP, Unit No. 2 are calculated for gaseous and liquid releases. The exposure due to radioactive material released in gaseous effluents is calculated using factors such as the amount of radioactive material released, the concentration beyond the site boundary, weather conditions at the time of release, locations of exposure pathways, and usage factors. The exposures calculated due to radioactive materials released in liquid effluents are calculated using factors such as the total volume of liquid, the total volume of dilution water, field irrigation, and usage factors.
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 7 of 42
- 8.
Results The Radioactive Effluent Release Report is a detailed listing of the radioactivity released from the HBRSEP, Unit No. 2 during the period from January 1, 2001, through December 31, 2001.
During the period of January 1, 2001, through December 31, 2001, the estimated maximum individual offsite dose due to radioactivity released in effluents was:
Liquid Effluents:
0 Total Body Dose 0.000704 millirem 0
Critical Organ Dose 0.000831 millirem, gi-lli1 Gaseous Effluents:
0 Beta Air Dose 0.00236 millirad 0
Gamma Air Dose 0.00494 millirad 0
Critical Organ Dose 0.15700 millirem, lung B.
Significant Variances The following are explanations of significant variances in this Annual Report:
- 1. The 10 CFR 50, Appendix I, doses were calculated from the last posted release for the period indicated using the Canberra (Offsite Dose Calculation Manual (ODCM) meteorology) Effluent Management System (EMS). The ODCM (EMS2 Software) provides day-by-day dose estimates that are conservative because all releases are assigned to the limiting receptor, using the continuous ground level dispersion factors calculated from 1978 meteorology.
1 gi-li, gastrointestinal-lower level intestine 2 EMS, Effluent Management Software, A product of Canberra Nuclear Industries used for determining curies and dose released from routine radioactive effluent releases
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 8 of 42
- 2. HBRSEP Unit No. 2 was removed from service on April 7, 2001 for a refueling outage. Power operations was resumed on May 12, 2001 and continued through the end of the year.
Continued good fuel and reactor coolant system integrity kept gaseous and liquid effluent totals relatively low in 2001. Some of the gaseous and liquid release parameters for this reporting period are summarized below:
GASEOUS EFFLUENTS Units 1st Otr 2nd Otr 3rd Otr 4th Qt Fission & Act. Gas Ci 4.53E-02 1.19E-01 9.76E-02 1.16E-01 1-131 Ci
<LLD 8.66E-07
<LLD
<LLD Part. >8 Day Half-Lives Ci 2.53E-06 5.59E-06 5.94E-08 6.89E-08 Tritium Ci 1.46E+00 4.44E+00 2.09E+00 3.42E+00
- 3. Virtually all parameters associated with liquid effluents were stable for the year except for the differences caused by the refueling outage in the second quarter. Also, the pond release in the fourth quarter made the liquid waste volume unusually high.
Some of the liquid release parameters for this reporting period are shown below:
LIQUID EFFLUENTS Units 1st Otr 2nd Otr 3rd Otr 4th tr Fission & Act. Products Ci 6.95E-03 5.67E-02 5.98E-03 1.42E-04 Tritium Ci 1.55E+02 6.21E+01 5.51E+01 6.41E+01 Dilution Volume Liters 2.77E+11 2.10E+ll 2.91E+11 2.78E+11 Waste Volume Liters 6.54E+05 8.26E+06 3.37E+05 5.22E+07
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 9 of 42 C.
Regulatory Compliance
- 1.
When projected on a day-by-day basis utilizing conservative meteorological conditions, the dose commitment from gaseous and liquid effluents is a small fraction of the 10 CFR 50, Appendix I limits. The direct radiation assessment to the most likely exposed member of the public is reported in the Annual Radiological Environmental Operating Report. During 2001 the results of the direct radiation assessment demonstrated no measurable effect above background for plant operations.
- 2.
There were no changes to the waste solidification Process Control Program (PCP) during this reporting period.
- 3.
There were no changes to the Radioactive Waste Systems (i.e., liquid, gaseous, or solid) during this reporting period.
- 4.
There were no reportable instrumentation inoperability events during this reporting period.
- 5.
There were no outside liquid holdup tanks that exceeded the 10 curie limit during this reporting period.
- 6.
There were no Waste Gas Decay Tanks that exceeded the 1.9E+04 curie limit during this reporting period.
- 7.
There was a revision to the ODCM during this reporting period. See page 39.
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 10 of 42 II.
SUPPLEMENTAL INFORMATION A.
Regulatory Limits
- 1.
Fission and Activation Gases:
10 CFR 20 Limits (Instantaneous Release Rate)
Total Body Dose <500 mrem/yr Skin Dose <3000 mrem/yr 10 CFR 50, Appendix I For Calendar Quarter Gamma Dose <5 mrad Beta Dose <10 mrad For Calendar Year Gamma Dose <10 mrad Beta Dose <20 mrad
- 2.
Iodine - 131 and 133, Tritium, and Particulates >8 day half-lives:
10 CFR 20 Limits (Instantaneous Release Rate)
Dose from Inhalation (only) to a child to any organ <1500 mrem/yr 10 CFR 50, Appendix I (Organ Doses)
For Calendar Quarter <7.5 mrem For Calendar Year < 15 mrem
- 3.
Liquids:
Concentrations are specified in 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.OOE-04 4Ci/ml total activity.
10 CFR 50, Appendix I For Calendar Quarter Total Body Dose <1.5 mrem Any Organ Dose <5 mrem For Calendar Year Total Body Dose <3 mrem Any Organ Dose <10 mrem B.
Measurements and Approximations of Total Radioactivity I1.
Continuous Gaseous Releases
- a.
Fission and Activation Gases - The total activity released is determined from the net count rate of the gaseous monitor, its calibration factor, and the total exhaust flow. The activity of radioactive gas is determined by the fraction of that radioactive gas in the isotopic analysis for that period.
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 11 of 42
- b.
lodines - The activity released as Iodine-131, 133, and 135 is based on isotopic analysis of the charcoal cartridge and particulate filter and the total vent flow.
- c.
Particulates - The activity released via particulates with half-lives greater than eight days is determined by isotopic analysis of particulate filters and the total vent flow.
- d.
Tritium - The activity released as tritium is based on weekly grab sample analysis and total vent flow.
- 2.
Batch Gaseous Releases
- a.
Fission and Activation Gases - The activity released is based on the volume released and the activity of the individual nuclides obtained from an isotopic analysis of the grab sample taken prior to the release.
- b.
lodines - The iodines from mixed mode batch releases are included in the iodine determination from the mixed mode continuous Reactor Auxiliary Building release.
- c.
Particulates - The particulates from mixed mode batch releases are included in the particulate determination from the mixed mode continuous Reactor Auxiliary Building release. Ground level batch particulates are reported in the batch mode accountability.
- d.
Tritium - The activity released as tritium is based on the grab sample analysis of each batch and the batch volume.
- 3.
Liquid Releases
- a.
Fission and Activation Products - The total release values (not including tritium, strontium, Iron-55, and alpha) are comprised of the sum of the individual radionuclide activities in each release to the discharge canal for the respective quarter. These values represent the activity known to be present in the liquid radwaste effluent.
- b.
Tritium & Alpha - The measured tritium and alpha concentrations in a monthly composite sample are used to calculate the total release and average diluted concentration during each period.
- c.
Strontium-89, 90, and Iron The total release values are measured quarterly from composite samples.
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 12 of 42 C.
Estimated Total Errors
- 1.
Estimated total errors for gaseous effluents are based on uncertainties in counting equipment calibration, counting statistics, vent flow rates, vent sample flow rates, non-steady release rates, chemical yield factors, and sample losses for such items as charcoal cartridges.
- 2.
Estimated total errors for liquid effluents are based on uncertainties in counting equipment calibration, counting statistics, non-steady release flow rate, sampling and mixing losses, and volume determinations.
- 3.
Estimated total errors for solid waste are based on uncertainties in equipment calibration, dose rate measurements, geometry, and volume determinations.
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 13 of 42 III.
GASEOUS EFFLUENTS A. Batch Releases Jan - June 2001 July - Dec 2001 Number of batch releases 5.40E+01 6.30E+01 Total time period for batch releases 4.05E+04 min 9.78E+04 min Maximum time period for a batch release 1.39E+04 min 7.63E+04 min Average time period for a batch release 7.50E+02 min 1.55E+03 min Minimum time period for a batch release 2.OOE+00 min 8.OOE+00 min B. Abnormal Releases Jan - June 2001 July - Dec 2001 Number of releases 0.OOE+00 0.OOE+00 Total activity released 0.OOE+00 Ci 0.00E+00 Ci C. Data Tables The following tables provide the details of gaseous releases:
Table I11-A Table Il1-B Table III-C Summation of all Releases Ground Level and Mixed Mode Releases Typical Lower Limits of Detection for Gaseous Effluents
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 14 of 42 TABLE nII-A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 11 2
1Error % I A. Fission and Activation Gases
- 1. Total release Ci 4.53E-02 1.19E-01 3.63E+01
- 2. Average release rate for period
[ICi/sec 5.83E-03 1.52E-02 B. lodines
- 1. Total Iodine-131 Ci
<LLD 8.66E-07 1.74E+01
- 2. Average release rate for period
- Ci/sec
<LLUD 1.lOE-07 C. Particulates
- 1. Particulates with half-lives >8 days Ci 2.53E-06 5.59E-06 1.05E+01
- 2. Average release rate for period
ýLCi/sec 3.25E-07 7.1 1E-07
- 3. Gross alpha radioactivity Ci
<LLD
<LLD D. Tritium
- 1. Total release Ci 1.46E+00 4.44E+00 2.31E+01
- 2. Average release rate for period I.tCi/sec 1.88E-01 5.65E-01 E. Percent of 10 CFR 50, Appendix I
- 1. Quarterly limit Gamma air 1.43E-02 2.30E-02 Beta air 2.90E-03 5.85E-03 Organ: Total Body 2.71E-01 Organ: Liver 8.17E-01
- 2. Annual limit Gamma air 7.13E-03*
1.86E-02*
Beta air 1.45E-03*
4.38E-03*
Organ: Total Body 1.35E-01*
Organ: Liver 5.44E-01 *
- Cumulative total for the year-to-date using the methodology in the ODCM.
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 15 of 42 TABLE IIl-A (Continued)
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 3
1 4
1Error %
A. Fission and Activation Gases
- 1. Total release Ci 9.76E-02 1.16E-01 3.63E+01
- 2. Average release rate for period
[tCi/sec 1.23E-02 1.46E-02 B. lodines
- 1. Total Iodine-131 Ci
<LLD
<LLD 1.74E+01
- 2. Average release rate for period ftCi/sec
<LLD
<LLD C. Particulates
- 1. Particulates with half-lives >8 days Ci 5.94E-08 6.89E-08 1.05E+01
- 2. Average release rate for period
[tCi/sec 7.47E-09 8.67E-09
- 3. Gross alpha radioactivity Ci
<LLD
<LLD D. Tritium
- 1. Total release Ci 2.09E+00 3.42E+00 2.31E+01
- 2. Average release rate for period PCi/sec 2.63E-01 4.31E-01 E. Percent of 10 CFR 50, Appendix I
- 1. Quarterly limit Gamma air 1.27E-02 4.88E-02 Beta air 5.72E-03 9.16E-03 Organ: Total Body 3.83E-01 6.28E-01
- 2. Annual limit Gamma air 2.50E-02*
4.94E-02*
Beta air 7.24E-03*
1.18E-02*
Organ: Lung 7.35E-01*
1.05E+00*
- Cumulative total for the year-to-date using the methodology in the ODCM.
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 16 of 42 TABLE I1-B ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 GASEOUS EFFLUENTS - GROUND LEVEL AND MIXED MODE RELEASES Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 1 Quarter I
Quarter 2
- 1. Fission Gases Ar-41 Ci
<LLD
<LLD 2.92E-02 4.53E-02 Kr-85m Ci
<LLD
<LLD
<LLD 3.24E-06 Xe-131m Ci
<LLD
<LLD 1.34E-04 4.90E-04 Xe-133 Ci
<LLD 1.05E-02 1.55E-02 6.12E-02 Xe-133m Ci
<LLD
<LLD 1.05E-04 1.OOE-03 Xe-135 Ci
<LLD
<LLD 3.50E-05 9.23E-04 Total for Period Ci
<LLD 1.05E-02 4.53E-02 1.09E-01
- 2. lodines'
- 3. Particulates' Co-58 Ci
<LLD 9.33E-07
<LLD 1.59E-06 Co-60 Ci
<LID
<L)LD 2.53E-06 2.77E-07 Br-82 Ci
<LLD 3.42E-06
<LLD
<LLD Sb-122 Ci
<LLD 1.75E-07
<LLD
<LLD Te-123m Ci
<LILD 1.93E-08
<LLD 2.01E-08 Cs-137 Ci
<LLD
<LLD
<LID 2.76E-06 Total for Period Ci
<LLD 4.54E-06 2.53E-06 4.64E-06
'Mixed mode continuous accountability includes mixed mode batch accountability (excludes tritium).
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 17 of 42 TABLE EII-B (Continued)
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 GASEOUS EFFLUENTS - GROUND LEVEL AND MIXED MODE RELEASES Continuous Mode Batch Mode Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4
- 1. Fission Gases Ar-41 Ci
<LLD
<LLD 2.63E-02 1.OOE-01 Kr-85 Ci
<LLD
<LLD 6.91E-02
<LLD Kr-85m Ci
<LLD
<LLD
<LLD 3.94E-04 Kr-87 Ci
<LLD
<LLD
<LLD 9.18E-04 Xe-131m Ci
<LLD
<LLD
<LLD 4.48E-05 Xe-133 Ci
<LLD
<LLD 2.10E-03 9.06E-03 Xe-133m Ci
<LLD
<LID
<LLD 4.06E-05 Xe-135 Ci
<LLD
<LLD 6.70E-06 3.33E-03 Xe-135m Ci
<LLD
<LLD
<LLD 2.17E-03 Total for Period Ci
<LLD
<LLD 9.75E-02 1.16E-01
- 2. Iodines 1
- 3. Particulates' Co-58 Ci 5.94E-08
<LLD
<LLD
<LLD Br-82 Ci
<LLD
<LLD 2.92E-07
<LLD Cs-137 Ci
<LLD 6.89E-08
<LLD
<LLD Total for Period Ci 5.94E-08 6.89E-08 2.92E-07
<LLD
'Mixed mode continuous accountability includes mixed mode batch accountability (excludes tritium).
GASEOUS EFFLUENTS - GROUND LEVEL AND MIXED
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 18 of 42 TABLE II-C TYPICAL LOWER LIMITS OF DETECTION FOR GASEOUS EFFLUENTS Nuclide LLD (pCi/cc)
H-3 1.OOE-06 Ar-41 6.80E-09 Mn-54 1.OOE-11 Co-58 1.OOE-1I Fe-59 1.OOE-1I Co-60 1.OOE-1I Zn-65 1.OOE-11 Br-82 1.21E-13 Kr-85 5.98E-06 Kr-85m 1.66E-08 Kr-87 1.OOE-04 Kr-88 1.OOE-04 Sr-89 1.OOE-11 Sr-90 1.OOE-11 Mo-99 1.OOE-11 Sb-122 2.63E-14 Te-123m 7.92E-15 1-131 1.OOE-12 Xe-131 m 4.66E-07 1-133 1.OOE-10 Xe-133 1.OOE-04 Xe-133m 1.OOE-04 Cs-134 1.OOE-11 1-135 3.86E-10 Xe-135 1.OOE-04 Xe-135m 4.38E-07 Cs-137 1.OOE-11 Xe-138 1.OOE-04 Ba-140 2.08E-14 La-140 9.40E-14 Ce-141 1.OOE-11 Ce-144 1.OOE-1 1 Gross Alpha 1.OOE-I1
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 19 of 42 IV. LIQUID EFFLUENTS A. Batch Releases Jan - June 2001 July - Dec 2001 Number of batch releases 8.1OE+01 1.70E+01 Total time period for batch releases 1.70E+04 min 3.29E+03 min Maximum time period for a batch release 8.08E+02 min 2.60E+02 min Average time period for a batch release
- 2. 1OE+02 min 1.94E+02 min Minimum time period for a batch release 2.OOE+00 min 1.05E+02 min Average stream flow during release periods 4.94E+05 gpm 5.67E+05 gpm B. Abnormal Releases Jan - June 2001 July - Dec 2001 Number of releases 0.OOE+00 0.OOE+00 Total activity released 0.OOE+00 Ci 0.00E+00 Ci C. Data Tables The following tables provide the details of gaseous releases:
Table TV-A Table IV-B Table IV-C Summation of all Releases Continuous and Batch Mode Releases Typical Lower Limits of Detection for Liquid Effluents
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 20 of 42 TABLE IV-A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 1
2 Error %
A. Fission and Activation Products
- 1. Total release (not including tritium, gases, alpha)
Ci 6.95E-03 5.67E-02 1.07E+01
- 2. Average diluted concentration during period JLiCi/ml 2.51E-11 2.70E-10 B. Tritium
- 1. Total release Ci 1.55E+02 6.21E+01 9.20E+00
- 2. Average diluted concentration during period l.Ci/ml 5.59E-07 2.96E-07 C. Dissolved and entrained gases
- 1. Total release Ci 1.40E-02 2.37E-03 9.60E+00
- 2. Average diluted concentration during period l.Ci/ml 5.50E-11 1.13E-11
- 3. Percent of applicable limit 2.75E-05 5.65E-06 D. Gross alpha radioactivity
- 1. Total release Ci
<LLD
<LLD 1.83E+01 E. Volume of waste released prior to dilution Liters 6.54E+05 I 8.26E+06 I
F. Volume of dilution water used during period Liters 2.77E+11 2.10E+11 G. Percent of 10CFR50, Appendix I
- 1. Quarterly Limit Organ: Liver 4.94E-04 NA Organ: GI-LLI NA 5.44E-03 Total body 1.45E-03 6.37E-03
- 2. Annual Limit Organ: Liver 2.47E-04*
NA Organ: GI-LLI NA 2.94E-03*
Total body 7.23E-04*
3.91E-03"
- Cumulative total for the year-to-date using the methodology in the ODCM.
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 21 of 42 TABLE IV-A (Continued)
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 TIOTTID PFFITTPNTS
- SuMMATION Unit OF ATJ. RF, TASES Quarter 3
Quarter 4
A. Fission and Activation Products
- 1. Total release (not including tritium, gases, alpha)
Ci 5.98E-03 1.42E-04 1.07E+01
- 2. Average diluted concentration during period
[iCi/mi 2.05E-11 5.11E-13 B. Tritium
- 1. Total release Ci 5.5 1E+01 6.41E+01 9.20E+00
- 2. Average diluted concentration during period 4Ci/ml 1.89E-07 2.3 1E-07 C. Dissolved and entrained gases
- 1. Total release Ci 8.33E-05 4.32E-06 9.60E+00
- 2. Average diluted concentration during period 4Ci/ml 2.86E-13 1.56E-14
- 3. Percent of applicable limit I 1.43E-07 7.80E-09 D. Gross alpha radioactivity
- 1. Total release Ci
<LLD
<LLD 1.83E+01 E. Volume of waste released prior to dilution Liters I 3.37E+05 5.22E+07 F. Volume of dilution water used during period Liters 2.91E+11 2.78E+11 G. Percent of 10CFR50, Appendix I
- 1. Quarterly Limit Organ: Liver 2.97E-03 9.40E-03 Total body 8.44E-03 3.07E-02
- 2. Annual Limit Organ: GI-LLI 3.88E-03*
8.31E-03*
Total body 8.14E-03*
2.35E-02*
- Cumulative total for the year-to-date using the methodology in the ODCM.
Est. Total Error %
LIQTTM EFFLUENTS - SUQIATIONOF AL R LEASES
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 22 of 42 TABLE IV-B ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 LIQUID EFFLUENTS - CONTINUOUS MODE AND BATCH MODE RELEASES H-3 Ci
<LLD
<LLD 1.55E+02 6.21E+01 Cr-51 Ci
<LLD
<LLD
<LLD 4.45E-03 Mn-54 Ci
<LLD
<LLD 2.69E-05 6.13E-06 Fe-55 Ci
<LLD
<LLD 1.19E-04 8.96E-04 Co-57 Ci
<LLD
<LLD 2.59E-05 6.68E-05 Co-58 Ci
<LLD 1.15E-03 2.67E-04 2.13E-02 Fe-59 Ci
<LLD
<LLD
<LLD 2.21E-05 Co-60 Ci
<LLD
<LLD 5.74E-03 5.69E-03 Ag-110m Ci
<LLD
<LLD 3.85E-04 2.33E-04 Sn-i 17m Ci
<LLD
<LLD
<LLD 2.72E-04 Sb-122 Ci
<LLD
<LLD
<LLD 1.15E-03 Te-123m Ci
<LLD
<LLD 4.1OE-05 2.50E-03 Sb-124 Ci
<LLD
<LLD 3.05E-05 1.33E-02 Sb-125 Ci
<LLD
<LLD 2.60E-04 5.58E-03 Cs-137 Ci
<LLD
<LLD 5.68E-05 4.52E-06 Ce-141 Ci
<LILD
<LLD
<LLD 5.23E-06 Total for Period Ci
<LLD
<LLD
<LLD
<LILD 1.07E-04 Xe-131m Ci
<LLD
<LLD 4.11E-05
<LLD Xe-133 Ci
<LLD
<LLD 1.39E-02 2.26E-03 Xe-133m Ci
<LLD
<LLD 8.48E-05
<LLD Total for Period Ci
<LLD
<LLD 1.40E-02 2.37E-03
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 23 of 42 TABLE IV-B (Continued)
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 LIQUHD EFFLUENTS - CONTINUOUS MODE AND BATCH MODE RELEASES Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 3
4 3
4 H-3 Ci 3.24E-05 1.42E+00 5.5 1 E+O 1 6.27E+01I Fe-55 Ci
<LLD
<LLD 6.02E-04 5.04E-05 Co-58 Ci
<LLD
<LLD 2.61E-04 5.34E-06 Co-60 Ci
<LLD
<LLD 2.76E-04 4.26E-06 Te-123m Ci
<LLD
<LLD 6.43E-05 8.41E-06 Sb-124 Ci
<LLD
<LLD 3.06E-03 2.18E-05 Sb-125 Ci
<LLD
<LLD 1.70E-03 4.90E-05 Cs-137 Ci
<LLD
<LLD 1.72E-05 2.47E-06 Total for Period Ci
<LLD
<LLD 5.97E-03 1.42E-04 Xe-133 Ci
<LLD
<LLD 8.33E-05 4.32E-06 Total for Period Ci
<LLD
<LLD 8.33E-05 4.32E-06
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 24 of 42 TABLE IV-C TYPICAL LOWER LIMITS OF DETECTION FOR LIQUID EFFLUENTS Nuclide LLD (uCi/ml)
H-3 1.OOE-05 Cr-51 1.59E-07 Mn-54 5.OOE-07 Fe-55 1.OOE-06 Co-57 2.24E-08 Co-58 5.OOE-07 Fe-59 5.OOE-07 Co-60 5.OOE-07 Zn-65 5.OOE-07 Kr-85 1.OOE-05 Sr-89 5.OOE-08 Sr-90 5.OOE-08 Nb-95 2.21E-08 Zr-95 5.55E-08 Mo-99 5.OOE-07 Tc-99m 3.69E-08 Ag-110m 2.86E-08 Sn-117m 5.62E-07 Sb-122 2.79E-08 Te-123m 2.22E-08 Sb-124 7.34E-08 Sb-125 6.30E-08 1-131 1.OOE-06 Xe-131 m 1.OOE-05 Xe-133 1.OOE-05 Xe-133m 1.OOE-05 Cs-134 5.OOE-07 Xe-135 1.OOE-05 Cs-137 5.OOE-07 Ba-140 4.21E-08 La-140 5.13E-08 Ce-141 5.OOE-07 Ce-144 5.OOE-07 Gross Alpha 1.OOE-07
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 25 of 42 V.
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Report Time Period January 1, 2001, Through December 31, 2001 A.
SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (not irradiated fuel)
Waste Class A
- 1. Type of Waste Unit Period Est. Total Solid.
Cont.
Form No.
Total Error (%)
Agent Type Ship.
- a. Spent resins, filter sludges, evaporator m3 NA NA NA NA NA NA bottoms, etc.
Ci
- b. Dry compressible waste, contaminated m3 3.98E+02 1.OOE+00 None STP Compacted and 6
equipment, etc.
Ci 5.17E-01 2.31E+01 Incinerable
- c. Irradiated components, control rods, m3 NA NA NA NA NA NA etc.
Ci
- d. Other: Wax stripper sludge, mixed m3 NA NA NA NA NA NA waste shipment of freon still bottoms, Ci part washer sludge.
STP = Strong Tight Package
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 26 of 42
- 2.
Estimate of major nuclide composition (by type of waste)
- 3. Solid Waste Disposition Number of Shipments:
6 Mode of Transportation: Exclusive use Destination:
GTS Duratek, Envirocare Ci
- a.
NA NA NA
- b.
Nb-95 3.05E+01 1.58E-01 Zr-95 2.18E+01 1.13E-01 Co-58 1.54E+01 7.94E-02 Fe-55 1.31E+01 6.78E-02 Ni-63 6.55E+00 3.39E-02 Co-60 4.8 1E+00 2.49E-02 Cr-51 3.25E+00 1.68E-02 Sb-124 1.25E+00 6.49E-03 Sn-113 7.25E-01 3.75E-03 Mn-54 5.51E-01 2.85E-03 C-14 4.41E-01 2.28E-03 H-3 4.08E-01 2.11E-03 Pu-241 3.15E-01 1.63E-03
- Others 8.41E-01 4.35E-03
- c.
NA NA NA
Total Curie Quantity and Principle Radionuclides were determined by Estimate.
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 27 of 42 V.
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Report Time Period January 1, 2001, Through December 31, 2001 B.
SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (not irradiated fuel)
Waste Class C
- 1. Type of Waste Unit Period Est. Total Solid.
Cont.
Form No.
Total Error (%)
Agent Type Ship.
- a. Spent resins, filter sludges, evaporator m3 1.54E+01 1.OOE+00 None DOT 7A Dewatered bead 4
bottoms, etc.
Ci 6.27E+01 2.3 1E+O1 Type A resin, dewatered STP filters
- b. Dry compressible waste, contaminated m3 NA NA NA NA NA NA equipment, etc.
Ci
- c. Irradiated components, control rods, m3 NA NA NA NA NA NA etc.
Ci
- d. Other: Wax stripper sludge, mixed m3 NA NA NA NA NA NA waste shipment of freon still bottoms, Ci part washer sludge.
STP = Strong Tight Package
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 28 of 42
- 2.
Estimate of major nuclide composition (by type of waste)
Ci
- a.
Co-60 3.24E+O1 2.03E+01 Ni-63 2.79E+01 1.75E+01 Fe-55 2.62E+01 1.64E+01 Sb-125 3.92E+00 2.46E+00 Mn-54 1.93E+00 1.21E+00 Cs-137 1.90E+00 1.19E+00 Cd-109 1.71E+00 1.07E+00 C-14 1.47E+00 9.21E-01 Co-58 5.65E-01 3.54E-01 Ag-110m 5.01E-01 3.14E-01 Sb-124 3.43E-01 2.15E-01 Cs-134 2.20E-01 1.38E-01
- Others 1.01E+00 6.34E-01
- b.
NA NA NA
- c.
NA NA NA
- d.
NA NA NA Others include: H-3, Cr-51, Cm-242, Am-243, Cm-243.
- 3. Solid Waste Disposition Number of Shipments:
4 Mode of Transportation: Exclusive use Destination:
Barnwell Co-57, Ni-59, Sr-89, Sr-90, Nb-95, Zr-95, Sn-113, Te-123m, Ce-144, Pu-238, Pu-239, Am-241, Pu-241, Total Curie Quantity and Principle Radionuclides were determined by Estimate.
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 29 of 42 VI.
40 CFR 190 DOSE CONFORMANCE The direct radiation assessment to the most likely exposed member of the public is reported in the Annual Radiological Environmental Operating Report.
The results of the assessment demonstrate no measurable affect above background from plant operations. Since no 10 CFR 50, Appendix I, limits have been exceeded and the evaluation of the Independent Spent Fuel Storage Installation indicates only a small fraction of the total dose to the environs, this demonstrates conformance with 40 CFR 190, "Environmental Radiation Protection Standards for Nuclear Power Operation."
VII.
METEOROLOGICAL DATA A.
Continuous Release Diffusion Analysis Table VII-A presents the number and frequency of wind direction occurrences by wind speed class as recorded at the onsite meteorological system during the period January 1, 2001, through December 31, 2001.
The frequencies are presented as a percent of total occurrences for each stability class as well as a summary for all classes for the lower (10 meter) sensor elevation.
Pertinent information available from the tables is as follows:
- 1.
Stability Percent occurrence Pasquill Stability categories based on lower level (10m) wind distribution:
A B
C D
E F
G 2.9 5.0 6.5 39.3 28.3 8.6 9.4
- 2.
Wind Speed 10 Meter Average Speed (mph) 4.22 Percent Calm 11.97 Percent Less than 3.5 mph 48.00
- 3.
Wind Direction 10 Meter Prevailing S
Percent Occurrence 11.90
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 30 of 42 TABLE VII-A JOINT OCCURRENCE FREQUENCIES FOR LOWNDDEG AND LOWNDSPD - CONTINUOUS RELEASES JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION NNE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 NE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 ENE 0.000 0.000 0.149 0.000 0.000 0.000 0.000 0.15 E
0.000 0.000 0.138 0.011 0.000 0.000 0.000 0.15 ESE 0.000 0.000 0.057 0.011 0.000 0.000 0.000 0.07 SE 0.000 0.011 0.218 0.000 0.000 0.000 0.000 0.23 SSE 0.000 0.000 0.046 0.034 0.000 0.000 0.000 0.08 S
0.000 0.000 0.057 0.138 0.000 0.000 0.000 0.19 SSW 0.000 0.000 0.195 0.195 0.000 0.000 0.000 0.39 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION NNE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 NE 0.000 0.000 0.034 0.000 0.000 0.000 0.000 0.03 ENE 0.000 0.000 0.298 0.011 0.000 0.000 0.000 0.31 E
0.000 0.023 0.608 0.034 0.000 0.000 0.000 0.66 ESE 0.000 0.057 0.332 0.023 0.000 0.000 0.000 0.41 SE 0.000 0.034 0.321 0.080 0.000 0.000 0.000 0.44 SSE 0.000 0.000 0.241 0.023 0.000 0.000 0.000 0.26 S
0.000 0.000 0.160 0.046 0.000 0.000 0.000 0.21 SSW 0.000 0.000 0.355 0.344 0.000 0.000 0.000 0.70 ATMOSPHERIC STABILITY CLASS A SW 0.000 0.000 0.241 0.218 0.000 0.000 0.000 0.46 WSW 0.000 0.000 0.218 0.138 0.000 0.000 0.000 0.36 W
0.000 0.000 0.298 0.092 0.000 0.000 0.000 0.39 WNW 0.000 0.000 0.092 0.080 0.023 0.000 0.000 0.19 NW 0.000 0.000 0.000 0.046 0.126 0.000 0.000 0.17 ATMOSPHERIC STABILITY CLASS B SW 0.000 0.000 0.493 0.206 0.000 0.000 0.000 0.70 WSW 0.000 0.011 0.481 0.149 0.000 0.000 0.000 0.64 W
0.000 0.000 0.241 0.046 0.000 0.000 0.000 0.29 WNW 0.000 0.000 0.092 0.057 0.011 0.000 0.000 0.16 NW 0.000 0.000 0.011 0.069 0.023 0.011 0.000 0.11 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION NNE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 NE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 ENE 0.000 0.011 0.447 0.034 0.000 0.000 0.000 0.49 E
0.000 0.138 0.573 0.023 0.000 0.000 0.000 0.73 ESE 0.000 0.160 0.275 0.034 0.000 0.000 0.000 0.47 SE 0.000 0.149 0.458 0.023 0.000 0.000 0.000 0.63 SSE 0.000 0.023 0.367 0.034 0.000 0.000 0.000 0.42 S
0.000 0.023 0.390 0.115 0.000 0.000 0.000 0.53 SSW 0.000 0.023 0.630 0.160 0.000 0.000 0.000 0.81 ATMOSPHERIC STABILITY CLASS C SW 0.000 0.092 0.470 0.138 0.000 0.000 0.000 0.70 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION WSW 0.000 0.080 0.504 0.023 0.000 0.000 0.000 0.61 W
0.000 0.080 0.355 0.046 0.000 0.000 0.000 0.48 WNW 0.000 0.000 0.149 0.069 0.000 0.000 0.000 0.22 NW 0.000 0.000 0.057 0.229 0.046 0.011 0.000 0.34 UMAX (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL NNW TOTAL 0.000 0.332 0.011 12.918 0.172 20.426 0.275 5.112 0.057 0.436 0.046 0.103 0.000 0.000 0.56 39.33 UMAX (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N
0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 UMAX (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N
0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 NNW 0.000 0.000 0.000 0.000 0.023 0.000 0.000 0.02 TOTAL 0.000 0.011 1.708 0.963 0.172 0.000 0.000 2.85 UMAX (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N
0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 NNW 0.000 0.000 0.000 0.000 0.000 0.023 0.000 0.02 TOTAL 0.000 0.126 3.668 1.089 0.034 0.034 0.000 4.95 N
0.001 0.023 0.011 0.011 0.000 0.000 0.000 0.05 NNE 0.000 0.011 0.034 0.000 0.000 0.000 0.000 0.05 NNW 0.000 0.000 0.000 0.023 0.000 0.000 0.000 0.02 NE 0.003 0.138 0.172 0.011 0.000 0.000 0.000 0.32 TOTAL 0.000 0.779
- 4. 677 0.951 0.046 0.011 0.000 6.46 ENE 0.040 1.559 3.038 0.401 0.011 0.000 0.000 5.05 E
0.048 1.880 2.063 0.344 0.000 0.000 0.000 4.34 ESE 0.041 1.582 1.375 0.355 0.000 0.000 0.000 3.35 SE 0.040 1.570 1.364 0.149 0.000 0.000 0.000 3.12 ATMOSPHERIC STABILITY CLASS D SSE 0.030 1.169 2.866 0.344 0.000 0.000 0.000 4.41 S
0.022 0.860 2.338 0.699 0.034 0.000 0.000 3.95 SSW 0.029 1-100 2.189 0.550 0.000 0.000 0.000 3.87 SW 0.030 1.158 1.410 0.516 0.000 0.000 0.000 3.11 WSW 0.021 0.802 0.928 0.332 0.011 0.000 0.000 2.10 W
0.017 0.676 0.906 0.195 0.023 0.000 0.000 1.82 WNW 0.007 0.264 0.871 0.183 0.023 0.000 0.000 1.35 NW 0.003 0.115 0.688 0.745 0.275 0.057 0.000 1.88
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 31 of 42 TABLE VII-A JOINT OCCURRENCE FREQUENCIES FOR LOWNDDEG AND LOWNDSPD - CONTINUOUS RELEASES JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS E UMAX (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL NNW TOTAL 0.028 2.741 0.149 14.626 1.055 9.181 0.642 1.685 0.023 0.092 0.011 0.011 0.000 0.000 1.91 28.34 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION NNE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 NE 0.016 0.023 0.000 0.000 0.000 0.000 0.000 0.04 ENE 0.031 0.046 0.000 0.000 0.000 0.000 0.000 0.08 E
0.039 0.057 0.000 0.000 0.000 0.000 0.000 0.10 ESE 0.031 0.046 0.000 0.000 0.000 0.000 0.000 0.08 SE 0.047 0.069 0.000 0.000 0.000 0.000 0.000 0.12 SSE 0.384 0.562 0.023 0.000 0.000 0.000 0.000 0.97 S
0.557 0.814 0.034 0.000 0.000 0.000 0.000 1.41 SSW 0.424 0.619 0.011 0.000 0.000 0.000 0.000 1.05 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION NNE 0.000 0.000 0,000 0,000 0.000 0.000 0.000 0.00 NE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 ENE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 E
0.044 0.023 0.000 0.000 0.000 0.000 0.000 0.07 ESE 0.022 0.011 0.000 0.000 0.000 0.000 0.000 0.03 SE 0.044 0.023 0.000 0.000 0.000 0.000 0.000 0.07 SSE 0.581 0.309 0.000 0.000 0.000 0.000 0.000 0.89 S
0.409 0.218 0.000 0.000 0.000 0.000 0.000 0.63 SSW 0.323 0.172 0.000 0.000 0.000 0.000 0.000 0.50 ATMOSPHERIC STABILITY CLASS F SW 0.314 0.458 0.011 0.000 0.000 0.000 0.000 0.78 WSW 0.298 0.436 0.011 0.000 0.000 0.000 0.000 0.75 W
0.228 0.332 0.011 0.000 0.000 0.000 0.000 0.57 WNW 0.204 0.298 0.023 0.000 0.000 0.000 0.000 0.52 NW 0.322 0.470 0.436 0.011 0.000 0.000 0.000 1.24 ATMOSPHERIC STABILITY CLASS G SW 0.258 0.138 0.000 0.000 0.000 0.000 0.000 0.40 WSW 0.323 0.172 0.000 0.000 0.000 0.000 0.000 0.50 W
0.172 0.092 0.000 0.000 0.000 0.000 0.000 0.26 WNW 0.539 0.287 0.011 0.000 0.000 0.000 0.000 0.84 NW 2.346 1.249 0.172 0.000 0.000 0.000 0.000 3.77 TOTAL HOURS CONSIDERED ARE 8724.
WIND MEASURED AT 11.0 METERS.
OVERALL WIND DIRECTION FREQUENCY WIND DIRECTION:
N NNE NE ENE E
WNW NW NNW TOTAL FREQUENCY:
0.1 0.1 0.7 7.9 7.1 5.1 5.4 9.5 11.9 11.6 8.9 6.7 5.2 4.7 10.2 4.9 100.0 N
0.005 0.023 0.011 0.000 0.000 0.000 0.000 0.04 NNE 0.005 0.023 0.023 0.011 0.000 0.000 0.000 0.06 NE 0.034 0.183 0.080 0.000 0.000 0.000 0.000 0.30 ENE 0.209 1.112 0.493 0.000 0.000 0.000 0.000 1.81 E
0.123 0.653 0.206 0.023 0.000 0.000 0.000 1.01 ESE 0.076 0.401 0.172 0.000 0.000 0.000 0.000 0.65 SE 0.101 0.539 0.126 0.034 0.000 0.000 0.000 0.80 SSE 0.260 1.387 0.802 0.034 0.000 0.000 0.000 2.48 S
- 0. 536 2.866 1.387 0.183 0.000 0.000 0.000 4.97 SSW 0.431 2.304 1.456 0.126 0.000 0.000 0.000 4.32 SW 0.330 1.765 0.585 0.046 0.000 0.000 0.000 2.73 WSW 0.214 1.146 0.390 0.046 0.000 0.000 0.000 1.80 W
0.157 0.837 0.367 0.057 0.000 0.000 0.000 1.42 WNW 0.123 0.653 0.493 0.115 0.023 0.000 0.000 1.41 N
0.024 0.034 0.000 0.000 0.000 0.000 0.000 0.06 NW 0.110 0.585 1.536 0.367 0.046 0.000 0.000 2.64 UMAX (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL UMAX (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N
0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 NNW 0.141 0.206 0.493 0.023 0.000 0.000 0.000 0.86 TOTAL 3.060 4.470 1.055 0.034 0.000 0.000 0.000 8.62 NNW 0.775 0.413 0.321 0.000 0.000 0.000 0,000 1.51 TOTAL 5.835 3.106
- 0. 504 0.000 0.000 0.000 0.000 9.45
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 32 of 42 VII.
METEOROLOGICAL DATA B.
Mixed Mode Batch Release Diffusion Analysis Table VII-B presents the number and frequency of wind direction occurrences by wind speed class as recorded at the onsite meteorological system during mixed mode batch releases for the period January 1, 2001, through December 31, 2001.
The frequencies are presented as a percent of total occurrences for each stability class as well as a summary for all classes for the lower (10 meter) sensor elevation.
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 33 of 42 TABLE VII-B JOINT OCCURRENCE FREQUENCIES FOR LOWNDDEG AND LOWNDSPD - MIXED MODE BATCH RELEASES JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION NNE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 NE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 ENE 0.000 0.000 0.144 0.000 0.000 0.000 0.000 0.14 E
0.000 0.144 0.289 0.000 0.000 0.000 0.000 0.43 ESE 0.000 0.000 0.144 0.000 0.000 0.000 0.000 0.14 SE 0.000 0.000 0.144 0.000 0.000 0.000 0.000 0.14 SSE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 S
0.000 0.000 0.144 0.000 0.000 0.000 0.000 0.14 SSW 0.000 0.000 0.433 0.433 0.000 0.000 0.000 0.87 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION NNE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 NE 0.000 0.000 0.144 0.000 0.000 0.000 0.000 0.14 ENE 0.000 0.000 0.144 0.000 0.000 0.000 0.000 0.14 E
0.000 0.000 0.289 0.000 0.000 0.000 0.000 0.29 ESE 0.000 0.144 0.289 0.000 0.000 0.000 0.000 0.43 SE 0.000 0.000 0.144 0.000 0.000 0.000 0.000 0.14 SSE 0.000 0.000 0.289 0.000 0.000 0.000 0.000 0.29 S
0.000 0.000 0.144 0.144 0.000 0.000 0.000 0.29 SSW 0.000 0.000 0.289 0.289 0.000 0.000 0.000 0.58 ATMOSPHERIC STABILITY CLASS A SW 0.000 0.000 0.289 0.000 0.000 0.000 0.000 0.29 WSW 0.000 0.000 0.000 0.578 0.000 0.000 0.000 0.58 W
0.000 0.000 0.289 0.000 0.000 0.000 0.000 0.29 WNW 0.000 0.000 0.866 0.433 0.000 0.000 0.000 1.30 NW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 ATMOSPHERIC STABILITY CLASS B SW 0.000 0.000 0.289 0.000 0.000 0.000 0.000 0.29 WSW 0.000 0.000 0.433 0.000 0.000 0.000 0.000 0.43 W
0.000 0.000 0.289 0.000 0.000 0.000 0.000 0.29 WNW 0.000 0.000 0.289 0.000 0.000 0.000 0.000 0.29 NW 0.000 0.000 0.000 0.000 0.144 0.000 0.000 0.14 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION NNE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 NE 0.000 0.000 0.144 0.000 0.000 0.000 0.000 0.14 ENE 0.000 0.000 0.433 0.000 0.000 0.000 0.000 0.43 E
0.000 0.000 0.289 0.000 0.000 0.000 0.000 0.29 ESE 0.000 0.289 0.000 0.000 0.000 0.000 0.000 0.29 SE 0.000 0.144 0.578 0.000 0.000 0.000 0.000 0.72 SSE 0.000 0.000 0.433 0.000 0.000 0.000 0.000 0.43 S
0.000 0.000 0.144 0.000 0.000 0.000 0.000 0.14 ATMOSPHERIC STABILITY CLASS C SSW 0.000 0.000 0.578 0.144 0.000 0.000 0.000 0.72 SW 0.000 0.000 0.433 0.289 0.000 0.000 0.000 0.72 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION WSW 0.000 0.000 0.289 0.000 0.000 0.000 0.000 0.29 W
0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 WNW 0.000 0.000 0.144 0.000 0.000 0.000 0.000 0.14 NW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 UMAX (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL NNW TOTAL 0.000 0.390 0.000 10.684 0.000 13.716 0.144 4.043 0.000 0.289 0.000 0.000 0.000 0.000 0.14 29.12 UMAX (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N
0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 UMAX (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N
0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 NNW 0.000 0.000 0.000 0.000 0.144 0.000 0.000 0.14 TOTAL 0.000 0.144 2.743 1.444 0.144 0.000 0.000 4.48 UMAX (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N
0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 NNW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 TOTAL 0.000 0.144 3.032 0.433 0.144 0.000 0.000 3.75 N
0.000 0.144 0.144 0.000 0.000 0.000 0.000 0.29 NNE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 NNW 0.000 0.000 0.000 0.144 0.000 0.000 0.000 0.14 NE 0.000
- 0. 144 0.000 0.000 0.000 0.000 0.000 0.14 TOTAL 0.000 0.433 3.465 0.578 0.000 0.000 0.000 4.48 ENE 0.058 1.444 0.866 0.000 0.000 0.000 0.000 2.37 E
0.043 1.155 1.299 0.144 0.000 0.000 0.000 2.64 ESE 0.058 1.444 0.866 0.866 0.000 0.000 0.000 3.23 SE 0.043 1.155 0.722 0.433 0.000 0.000 0.000 2.35 ATMOSPHERIC STABILITY CLASS D SSE 0.058 1.588 2.166 0.578 0.000 0.000 0.000 4.39 S
0.029 0.722 2.310 0.5'/8 0.144 0.000 0.000 3.78 SSW 0.014 0.433 1.444 0.144 0.000 0.000 0.000 2.04 SW 0.029 0.722 1.444 0.433 0.000 0.000 0.000 2.63 WSW 0.058 1.588 1.011 0.000 0.144 0.000 0.000 2.80 W
0.000 0.144 0.433 0.144 0.000 0.000 0.000 0.72 WNW 0.000 0.000 0.722 0.000 0.000 0.000 0.000 0.72 NW 0.000 0.000 0.289 0.578 0.000 0.000 0.000 0.87
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 34 of 42 TABLE VII-B JOINT OCCURRENCE FREQUENCIES FOR LOWNDDEG AND LOWNDSPD - MIXED MODE BATCH RELEASES JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS E UMAX (M/S)
N NNE NE ENE E
WNW NW NNW TOTAL 0.34 0.000 0.000 0.072 0.347 0.303 0.000 0.101 0.375 0.996 0.751 0.476 0.476 0.347 0.202 0.173 0.000 4.620 1.56 0.000 0.000 0.289 1.444 1.299 0.000 0.433 1.588 4.187 3.176 2.021 2.021 1.444 0.866 0.722 0.000 19.492 3.35 0.000 0.000 0.000 0.289 0.000 0.000 0.289 0.578 0.866 0.578 0.578 0.578 0.578 0.289 1.588 1.011 7.219 5.59 0.000 0.000 0.000 0.000 0.000 0.000 0.144 0.289 0.000 0.000 0.000 0.000 0.144 0.289 0.433 0.578 1.877 8.27 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 11.18 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 24.59 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 TOTAL 0.00 0.00 0.36 2.08 1.60 0.00 0.97 2.83 6.05 4.50 3.08 3.08 2.51 1.65 2.92 1.59 33.21 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS F UMAX (M/S)
N NNE NE ENE E
WNW NW NNW TOTAL 0.34 0.101 0.000 0.000 0.000 0.000 0.101 0.101 0.722 1.343 0.520 0.303 0.303 0.202 0.000 0.202 0.419 4.317 1.56 0.144 0.000 0.000 0.000 0.000 0.144 0.144 1.011 1.877 0.722 0.433 0.433 0.289 0.000 0.289 0.578 6.064 3.35 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.144 1.155 0.722 2.021 5.59 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.144 0.144 8.27 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 11.18 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 24.59 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 TOTAL 0.25 0.00 0.00 0.00 0.00 0.25 0.25 1.73 3.22 1.24 0.74 0.74 0.49 0.14 1.65 1.86 12.55 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS G UMAX (M/S)
N NNE NE ENE E
WNW NW NNW TOTAL 0.34 0.000 0.000 0.000 0.000 0.000 0.000 0.260 1.040 0.000 1.040 0.780 0.260 0.260 0.520 2.339 1.299 7.797 1.56 0.000 0.000 0.000 0.000 0.000 0.000 0.144 0.578 0.000 0.578 0.433 0.144 0.144 0.289 1.299 0.722 4.332 3.35 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.144 0.144 0.289 5.59 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 8.27 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 11.18 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 24.59 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 TOTAL 0.00 0.00 0.00 0.00 0.00 0.00 0.40 1.62 0.00 1.62 1.21 0.40 0.40 0.81 3.78 2.17 12.42 TOTAL HOURS CONSIDERED ARE 693.
WIND MEASURED AT 11.0 METERS.
OVERALL WIND DIRECTION FREQUENCY WIND DIRECTION:
N NNE NE ENE E
WNW NW NNW TOTAL FREQUENCY:
0.5 0.0 0.8 5.2 5.3 4.3 5.0 11.3 13.6 11.6 9.0 8.3 4.7 5.1 9.4 6.0 100.0
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 35 of 42 VII.
METEOROLOGICAL DATA C.
Ground Level Batch Release Diffusion Analysis Table VII-C presents the number and frequency of wind direction occurrences by wind speed class as recorded at the onsite meteorological system during ground level batch releases for the period January 1, 2001, through December 31, 2001.
The frequencies are presented as a percent of total occurrences for each stability class as well as a summary for all classes for the lower (10 meter) sensor elevation.
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 36 of 42 TABLE VII-C JOINT OCCURRENCE FREQUENCIES FOR LOWNDDEG AND LOWNDSPD - GROUND LEVEL BATCH RELEASES JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION NNE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 NE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 ENE 0.000 0.000 0.294 0.000 0.000 0.000 0.000 0.29 E
0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 ESE 0.000 0.000 0.059 0.000 0.000 0.000 0.000 0.06 SE 0.000 0.059 0.118 0.000 0.000 0.000 0.000 0.18 SSE 0.000 0.000 0.059 0.000 0.000 0.000 0.000 0.06 S
0.000 0.000 0.177 0.235 0.000 0.000 0.000 0.41 SSW 0.000 0.000 0.059 0.235 0.000 0.000 0.000 0.29 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION UMAX (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL UMAX (MIS) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N
0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 N
0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 ENE 0.000 0.000 0.177 0.000 0.000 0.000 0.000 0.18 E
0.000 0.000 0.177 0.000 0.000 0.000 0.000 0.18 ESE 0.000 0.000 0.353 0.000 0.000 0.000 0.000 0.35 SE 0.000 0.059 0.177 0.000 0.000 0.000 0.000 0.24 SSE 0.000 0.000 0.118 0.000 0.000 0.000 0.000 0.12 S
0.000 0.000 0.294 0.059 0.000 0.000 0.000 0.35 SSW 0.000 0.000 0.294 0.353 0.000 0.000 0.000 0.65 ATMOSPHERIC STABILITY CLASS A SW 0.000 0.000 0.294 0.294 0.000 0.000 0.000 0.59 WSW 0.000 0.000 0.177 0.177 0.000 0.000 0.000 0.35 W
0.000 0.000 0.235 0.059 0.000 0.000 0.000 0.29 WNW 0.000 0.000 0.177 0.118 0.000 0.000 0.000 0.29 NW 0.000 0.000 0.000 0.059 0.000 0.000 0.000 0.06 ATMOSPHERIC STABILITY CLASS B SW 0.000 0.000 0.589 0.530 0.000 0.000 0.000 1.12 WSW 0.000 0.000 0.294 0.059 0.000 0.000 0.000 0.35 W
0.000 0.000 0.412 0.000 0.000 0.000 0.000 0.41 WNW 0.000 0.000 0.118 0.000 0.000 0.000 0.000 0.12 NW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION NNE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 NE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 ENE 0.000 0.000 0.471 0.000 0.000 0.000 0.000 0.47 E
0.000 0.118 0.648 0.000 0.000 0.000 0.000 0.77 ESE 0.000 0.177 0.235 0.000 0.000 0.000 0.000 0.41 SE 0.000 0.059 0.530 0.059 0.000 0.000 0.000 0.65 SSE 0.000 0.000 0.412 0.000 0.000 0.000 0.000 0.41 S
0.000 0.000 0.648 0.412 0.000 0.000 0.000 1.06 ATMOSPHERIC STABILITY CLASS C SSW 0.000 0.059 1.060 0.177 0.000 0.000 0.000 1.30 SW 0.000 0.000 0.706 0.294 0.000 0.000 0.000 1.00 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION WSW 0.000 0.000 0.294 0.059 0.000 0.000 0.000 0.35 W
0.000 0 059 0.177 0.000 0.000 0.000 0.000 0.24 WNW 0.000 0.000 0.118 0.059 0.000 0.000 0.000 0.18 NW 0.000 0 000 0.000 0.589 0.000 0.000 0.000 0.59 UMAX (MIS) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL NNW TOTAL 0.000 0.171 0.000 10.832 0.177 20.898 0.353 6.122 0.000 0.177 0.000 0.000 0.000 0.000 0.53 38.20 NNE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 NE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 NNW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 TOTAL 0.000 0.059 1.648 1.177 0.000 0.000 0.000 2.88 UMAX (MIS) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 TOTAL N
0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 NNW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 TOTAL 0.000 0.059 3.002 1.001 0.000 0.000 0.000 4.06 N
0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 NNE 0.000 0.059 0.000 0.000 0.000 0.000 0.000 0.06 NNW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 NE 0.000 0.118 0.059 0.000 0.000 0.000 0.000 0.18 TOTAL 0.000 0 471 5.298 1.648 0.000 0.000 0.000 7.42 ENE 0.018 1.177 1.825 0.000 0.000 0.000 0.000 3.02 E
0.029 1.648 1.825 0.118 0.000 0.000 0.000 3.62 ESE 0.035 2.002 2.060 0.412 0.000 0.000 0.000 4.51 SE 0.029 1.884 1.884 0.177 0.000 0.000 0.000 3.97 ATMOSPHERIC STABILITY CLASS D SSE 0.012 0.648 3.414 0.765 0.000 0.000 0.000 4.84 S
0.006 0.412 2.531 1.884 0.177 0.000 0.000 5.01 SSW 0.006 0.530 2.472 0.942 0.000 0.000 0.000 3.95 SW 0.018 1.060 1.472 0.589 0.000 0.000 0.000 3.14 WSW 0.012 0.765 1.060 0.235 0.000 0.000 0.000 2.07 W
0.006 0.294 1.001 0.059 0.000 0.000 0.000 1.36 WNW 0.000 0.118 0.706 0.000 0.000 0.000 0.000 0.82 NW 0.000 0.118 0.412 0.589 0.000 0.000 0.000 1.12
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 37 of 42 TABLE VII-C JOINT OCCURRENCE FREQUENCIES FOR LOWNDDEG AND LOWNDSPD - GROUND LEVEL BATCH RELEASES JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS E UMAX (M/S)
N NNE NE ENE E
WNW NW NNW TOTAL 0.34 0.000 0.000 0.047 0.130 0.100 0.029 0.041 0.253 0.277 0.165 0.153 0.106 0.100 0.029 0.024 0.006 1.460 1.56 0.000 0.000 0.353 1.001 0.765 0.235 0.294 1.943 2.119 1.236 1.177 0.824 0.765 0.235 0.177 0.059 11.185 3.35 0.000 0.000 0.000 0.059 0.059 0.294 0.118 1.295 1.648 0.883 0.235 0.412 0.353 0.353 1.177 0.706 7.594 5.59 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.059 0.177 0.000 0.000 0.000 0.059 0.059 0.059 0.059 0.471 8.27 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 11.18 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 24.59 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 TOTAL 0.00 0.00 0.40 1.19 0.92 0.56 0.45 3.55 4.22 2.28 1.57 1.34 1.28 0.68 1.44 0.83 20.71 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS F UMAX (MIS)
N NNE NE ENE E
WNW NW NNW TOTAL 0.34 0.053 0.000 0.000 0.024 0.000 0.024 0.100 0.330 0.406 0.383 0.230 0.283 0.077 0.130 0.177 0.024 2.237 1.56 0.118 0.000 0.000 0.059 0.000 0.059 0.235 0.765 0.942 0.883 0.530 0.648 0.177 0.294 0.412 0.059 5.180 3.35 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.118 0.118 0.000 0.000 0.000 0.000 0.000 0.706 0.883 1.825 5.59 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.059 0.059 8.27 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 11.18 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 24.59 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 TOTAL 0.17 0.00 0.00 0.08 0.00 0.08 0.34 1.21 1.47 1.27 0.76 0.93 0.25 0.42 1.30 1.02 9.30 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS G UMAX (MIS)
N NNE NE ENE E
WNW NW NNW TOTAL 0.34 0.000 0.000 0.000 0.000 0.071 0.000 0.071 1.372 0.942 0.506 0.147 0.436 0.218 0.795 2.961 1.372 8.889 1.56 0.000 0.000 0.000 0.000 0.059 0.000 0.059 1.119 0.765 0.412 0.118 0.353 0.177 0.648 2.414 1.119 7.241 3.35 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.059 0.235 1.001 1.295 5.59 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 8.27 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 11.18 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 24.59 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 TOTAL 0.00 0.00 0.00 0.00 0.13 0.00 0.13 2.49 1.71 0.92 0.26 0.79 0.39 1.50 5.61 3.49 17.43 TOTAL HOURS CONSIDERED ARE 1699.
WIND MEASURED AT 11.0 METERS.
OVERALL WIND DIRECTION FREQUENCY WIND DIRECTION:
N NNE NE ENE E
WNW NW NNW TOTAL FREQUENCY:
0.2 0.1 0.6 5.2 5.6 6.0 6.0 12.7 14.2 10.7 8.4 6.2 4.2 4.0 10.1 5.9 100.0
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 38 of 42 CHANGES TO ODCM, PCP, AND RADIOACTIVE WASTE SYSTEMS TABLE OF CONTENTS Description Page I.
Changes to the Offsite Dose Calculation Manual................................................................
39 II.
Changes to the Radioactive Waste Systems.........................................................................
39 MlI.
Changes to the Process Control Program..............................................................................
39 IV.
Changes to the Land Use Census.........................................................................................
39 V.
Instrum ent Inoperability.......................................................................................................
39 VI.
Liquid Holdup Tank Curie Limit.........................................................................................
39 VII.
Waste Gas Decay Tank Curie Limit.....................................................................................
40 V III.
U nanticipated R elease..........................................................................................................
40
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 39 of 42
- 1.
CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)
There was a change to the ODCM during this reporting period. A summary of the change is shown below. A complete copy of the updated ODCM is being forwarded under separate letter.
ODCM REVISION 19 DESCRIPTION OF CHANGE The ODCM was revised to correct typographical errors and make format enhancements as well as to make several programmatic changes. The programmatic changes are listed below:
- 1. Section 9.0 has been changed to remove the requirements for using LADTAP and GASPAR computer codes for assessing integrated population dose and dose to each pathway. Instead, the Effluent Management System software will be used to evaluate the dose to the maximum exposed member of the public due to liquid and gaseous radioactive releases.
- 2. Section 2.0 has been changed, for simplicity and conservatism, to use the 10 CFR 20 limits for liquid releases. HBRSEP is allowed to make liquid discharges at a rate equal to ten times the values listed in 10 CFR 20.
- 3. R-37 has been added to Table 2.6-1 to require compensatory measures when the monitor is rendered inoperable.
- 4. R-22 and R-23 have been added to Tables 3.10-1 and 3.11-1 to specify compensatory measures for monitor inoperability and to specify required monitor surveillances.
- 5. Section 4.4 has been revised to require the Land Use Census to be performed once per 24 months instead of once per 12 months.
- 6. ESR 00-0001 removed the radiation measurement channels of R-23. Therefore, Section 3.0 has been changed to delete the methodology for R-23 setpoint calculations.
- 7. Section 10.0, Radioactive Releases - Monthly Summation, has been deleted. This section was mistakenly included when RETS was implemented.
II.
CHANGES TO THE RADIOACTIVE WASTE SYSTEMS There were no changes to the Radioactive Waste System during this reporting period.
III.
CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)
There was no change to the PCP during this reporting period.
IV.
CHANGES TO THE LAND USE CENSUS There were no changes to the environmental sampling program as a result of the Land Use Census performed in 2001.
V.
INSTRUMENT INOPERABILITY There were no reportable instrumentation inoperability events during this reporting period.
VI.
LIQUID HOLDUP TANK CURIE LIMIT There were no outside liquid holdup tanks that exceeded the ten curie limit during this reporting period.
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 40 of 42 VII.
WASTE GAS DECAY TANK CURIE LIMIT There were no waste gas decay tanks with a curie content that exceeded the 1.90E+04 curie limit during this reporting period.
VIII.
UNANTICIPATED RELEASE While analyzing monthly liquid release composites on December 4, 2001, it was discovered that the West Settling Pond effluent sample contained tritium. This release point normally contains no detectable activity. Subsequent investigation revealed a leaking valve on top of a primary system demineralizer to be the source of the tritium. This valve is used to load new resin into the demineralizer and is accessed from an emergency diesel generator muffler deck outside of the Reactor Auxiliary Building. When this primary system demineralizer is in use, the effected valve becomes a primary system boundary with any leakage going to the storm drain system, which in turn goes to the West Settling Pond.
This occurrence was entered into the station's Corrective Action Program via Action Request 52254. A temporary plug has been installed in the drain of the demineralizer valve access trench and an inspection frequency established to prevent release reoccurrence until the drain is permanently rerouted.
Accountability was performed on the liquid portion of the release by using the weekly sample results from the West Settling Pond effluent composite sampler, and readings from the pond discharge flow integrator. This accountability concluded that a release of 1.2495E+07 gallons of pond discharge containing a total of 1.415 curies of tritium occurred during the months of November and December 2001. No gamma activity was detectable at the pond effluent.
The 1.415 curies of tritium released by the pond discharge corresponded to a release of 2.43E+06 milliliters of reactor coolant. This information was used to generate a ground-level gaseous release permit for the gaseous activity contained in that volume of reactor coolant.
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0063 Page 41 of 42 SUPPLEMENTS TO PREVIOUS REPORTS TABLE OF CONTENTS Description Pane I.
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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RAI02-0063 Page 42 of 42 I.
DISCUSSION There are no corrections to previous reports.