Text

2003 Annual Radioactive Effluent Release Report
	ML041380308
Person / Time
Site:	Robinson
Issue date:	04/29/2004
From:	Baucom C; Progress Energy Carolinas
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	RNP-RA/04-0048
	Download: ML041380308 (43)
	v • d • e

10 CFR 50.36a(a)(2)

TS 5.6.3 Progress Energy Serial: RNP-RA/04-0048 APR 2 9 2004 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 2003 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Ladies and Gentlemen:

Attached is the Annual Radioactive Effluent Release Report for the period of January 1, 2003, through December 31, 2003, for 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 me.

Sincerely, C. T. Baucom Supervisor - Licensing/Regulatory Programs RAC/rac Attachment c:

Mr. L. A. Reyes, NRC, Region II Mr. C. P. Patel, NRR, NRC (w/o Attachment)

NRC Resident Inspector Progress Energy Carolinas. Inc.

Robinson Nuclear Plant 3581 West Entrance Road Hartsville, SC 29550

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 1 of 42 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT January 1, 2003 - December 31, 2003 PROGRESS ENERGY CAROLINAS 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/04-0048 Page 2 of 42 TABLE OF CONTENTS Description..................................................

Page I.

EXECUTIVE

SUMMARY

4 A.

Discussion..................................................

4 B.

Significant Variances..................................................

7 C.

Regulatory Compliance..................................................

8 II.

SUPPLEMENTAL INFORMATION.................................................

9 A.

Regulatory Limits.................................................

9 B.

Measurements and Approximations of Total Radioactivity.................................. 10 C.

Estimated Total Errors.................................................

11 Iml.

GASEOUS EFFLUENTS................................................

12 A.

Batch Releases.................................................

12 B.

Abnormal Releases.................................................

12 C.

Data Tables.................................................

12 IV.

LIQUID EFFLUENTS................................................

18 A.

Batch Releases................................................

18 B.

Abnormal Releases................................................

18 C.

Data Tables.................................................

18 V.

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS.

24 A.

Waste Class A................................................

24 B.

Waste Class B................................................

26 C.

Waste Class C................................................

28 D.

Irradiated Fuel Shipments........................................

29 VI.

40 CFR 190 DOSE CONFORMANCE........................................

30 VII.

METEOROLOGICAL DATA........................................

30 A.

Continuous Release Diffusion Analysis........................................

30 B.

Mixed Mode Batch Release Diffusion Analysis........................................

33 C.

Ground Level Batch Release Diffusion Analysis...................................

36

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 3 of 42 LIST OF TABLES Table Description........

Page Table HI-A Table HI-B Table mH-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....................................... 13 Gaseous Effluents - Ground Level and Mixed Mode Releases................. 15 Typical Lower Limits of Detection for Gaseous Effluents........................ 17 Liquid Effluents - Summation of All Releases.......................................... 19 Liquid Effluents - Continuous Mode and Batch Mode Releases............... 21 Typical Lower Limits of Detection for Liquid Effluents........................... 23 Joint Occurrence Frequencies for LOWNDDEG and LOWNDSPD -

Continuous Releases.................................................

31 Joint Occurrence Frequencies for LOWNDDEG and LOWNDSPD Mixed Mode Batch Releases.................................................

34 Joint Occurrence Frequencies for LOWNDDEG and LOWNDSPD Ground Level Batch Releases.................................................

37

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 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 Progress Energy Carolinas Inc.,

minimize health risk and environmental detriment, and ensure 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 and 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/04-0048 Page 5 of 42

4.

Iodines and Particulates There were no measurable releases of iodines during the year. Annual releases of particulates with half-lives greater than eight days were 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 particulates 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/04-0048 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 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, 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/04-0048 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, 2003 through December 31, 2003.

During the period of January 1, 2003 through December 31, 2003, the estimated maximum individual offsite dose due to radioactivity released in effluents was:

Liquid Effluents:

Total Body Dose 0.00000916 millirem Critical Organ Dose 0.00001030 millirem, GI-LLI Gaseous Effluents:

Beta Air Dose 0.00166 millirad Gamma Air Dose 0.00450 millirad Critical Organ Dose 0.08640 millirem, Total-Body B.

Significant Variances The following are explanations of significant variances in this Annual Report:

1.

The 10 CFR 50, Appendix I, doses were calculated using the Canberra (Offsite Dose Calculation Manual (ODCM) meteorology) Effluent Management System (EMS). The ODCM (EMS' 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.

2.

HBRSEP, Unit No. 2, remained in power operation for the entire 2003 year.

Continuous operation, along with continued good fuel and reactor coolant system integrity, kept gaseous and liquid effluent totals relatively low in 2003. Some of the gaseous and liquid release parameters for this reporting period are summarized below:

EMS. Effluent Management Software is 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/04-0048 Page 8 of 42 GASEOUS EFFLUENTS Units 1st Qtr 2nd Otr 3rd Otr 4th Qtr Fission & Act. Gas Ci 5.46E-02 4.63E-02 4.56E-02 7.27E-02 I-131 Ci

<LLD

<LLD Part. >8 Day Half-Lives Ci

<LLD 6.38E-07 1.49E-08 6.99E-08 Tritium Ci 1.50E+00 1.55E+00 1.71E+00 1.52E+00 LIQUID EFFLUENTS Units 1st Qtr 2nd Otr 3rd Qtr 4th Qtr Fission & Act. Products Ci 1.27E-03 1.16E-03 1.42E-03 1.39E-03 Tritium Ci 2.29E+00 3.85E+01 8.81E+00 1.16E+02 Dilution Volume Liters 2.73E+11 2.77E+1 1 2.91E+1 1 2.81E+11 Waste Volume Liters 6.75E+04 2.32E+05 2.44E+05 2.42E+05 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 2003 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. See page 40.

3.

There were no changes to the Radioactive Waste Systems (i.e., liquid, gaseous, or solid) during this reporting period. See page 40.

4.

There were no reportable instrumentation inoperability events during this reporting period. See page 40.

5.

There were no outside liquid holdup tanks that exceeded the 10 curie limit during this reporting period. See page 40.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 9 of 42

6.

There were no Waste Gas Decay Tanks that exceeded the 1.9E+04 curie limit during this reporting period. See page 40.

7.

There were no changes to the ODCM during this reporting period. See page 40.

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 yCi/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

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 10 of 42 B.

Measurements and Approximations of Total Radioactivity

1.

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.

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 exhaust 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 exhaust flow.

d)

Tritium - The activity released as tritium is based on weekly grab sample analysis and total exhaust 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)

Iodines - 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.

d)

Tritium - The activity released as tritium is based on the grab sample analysis of each batch and the batch volume.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 11 of 42

3.

Liquid Releases a)

Fission and Activation Products - The total release values (not including tritium, gases, 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 and 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.

C.

Estimated Total Errors

1.

Estimated total errors for gaseous effluents are based on uncertainties in counting equipment calibration, counting statistics, exhaust flow rates, exhaust 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/04-0048 Page 12 of 42 mII.

GASEOUS EFFLUENTS A.

Batch Releases Jan - June 2003 July - Dec 2003 Number of batch releases 5.90E+01 5.60E+01 Total time period for batch releases 2.69E+04 min 2.30E+04 min Maximum time period for a batch release 1.97E+03 min 1.85E+03 min Average time period for a batch release 4.55E+02 min 4.1 IE+02 min Minimum time period for a batch release 4.20E+01 min 2.OOE+00 min B.

Abnormal Releases Jan - June 2003 July - Dec 2003 Number of releases 0.OOE+00 0.OOE+00 l

Total activity released 0.OOE+00 Ci 0.OOE+00 Ci C.

Data Tables The following tables provide the details of gaseous releases:

Table EH-A Table HI-B Table m-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/04-0048 Page 13 of 42 TABLE m-A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT - 2003 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter o

A.

Fission and Activation Gases

1. Total release Ci 5.46E-02 4.63E-02 3.63E+01

2. Average release rate for period ltCi/sec 7.02E-03 5.89E-03 J B.

Iodines I. Total Iodi ne-131 Ci J

<LLD J

<LLD J1.74E+01

2. Average release rate for period j jiCi/sec l

<LLD l

<LLD J C.

Particulates

1. Particulates with half-lives >8 days Ci

<LLD 6.38E-07 1.05E+01

2. Average release rate for period iLCi/sec

<LLD 8.1 E-08

3. Gross alpha radioactivity Ci

<LLD

<LLD D.

Tritium

1. Total release l

Ci 1.50E+00 l 1.55E+00 2.31E+01 LI

2. Average release rate for period

[LCi/sec 1.93E-01 1.97E-01 E.

Percent of 10 CFR 50, Appendix I

1. Quarterly limit Gamma air 2.54E-02 2.17E-02 Beta air 4.5 1E-03 3.85E-03 Organ: Total Body 2.75E-01 2.84E-01

2. Annual limit Gamma air 1.27E-02*

2.36E-02*

Beta air 2.26E-03*

4.18E-03*

Organ: Total Body 1.38E-01*

2.80E-01*

Cumulative total for the year-to-date using the methodology in the ODCM.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 14 of 42 TABLE IE-A (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT - 2003 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter J Quarter Est. Total A.

Fission and Activation Gases

1. Total release l

Ci J 4.56E-02 J 7.27E-02 J 3.63E+01

2. Average release rate for period l lCi/sec l 5.74E-03 l

9.14E-03 J B.

Iodines

1. Total Iodine-131 Ci

<LLD

<LLD 1.74E+01

2. Average release rate for period pCi/sec

<LLD

<LLD C.

Particulates

1. Particulates with half-lives >8 days Ci 1.49E-08 6.99E-08 1.05E+01

2. Average release rate for period

[LCi/sec 1.87E-09 8.79E-09

3. Gross alpha radioactivity Ci J

<LLD

]

D.

Tritium

1. Total release l

Ci J 1.71E+00 1.52E+00 l 2.31E+01 II

2. Average release rate for period

[Ci/sec 2.16E-01 1.91E-01

U

.J E.

Percent of 10 CFR 50, Appendix I

1. Quarterly limit Gamma air 2.14E-02 2.16E-02 Beta air 3.79E-03 4.48E-03 Organ: Total Body 3.14E-01 2.78E-01

2. Annual limit Gamma air 3.42E-02*

4.50E-02 Beta air 6.05E-03*

8.31E-03*

Organ: Total Body 4.37E-01*

5.76E-01 I

Cumulative total for the year-to-date using the methodology in the ODCM.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 15 of 42 TABLE Ill-B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT - 2003 GASEOUS EFFLUENTS - GROUND LEVEL AND MIXED MODE RELEASES Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 I Quarter 2

1.

Fission Gases Ar-41 Ci

<LLD

<LLD 5.33E-02 4.56E-02 Xe-133 Ci 1.09E-03

<LLD 1.38E-04 7.09E-04 Xe-135 Ci

<LLD

<LLD 3.53E-05

<LLD Total for Period Ci 1.09E-03

<LLD 5.35E-02 4.63E-02

2.

Iodines' I-131 Ci

<LLD

<LLD I-133 Ci

<LLD

<LLD Total for Period Ci

<LLD

3.

Particulates_

Co-57 Ci

<LLD

<LLD 1.17E-08 Co-60 Ci

<LLD

<LLD 6.26E-07 Br-82 Ci

<LLD

<LLD 2.24E-07

<LLD Total for Period Ci

<LLD

<LLD 2.24E-07 6.38E-07

'Mixed mode continuous accountability includes mixed mode batch accountability (excludes tritium).

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 16 of 42 TABLE 1-B (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT - 2003 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 4.48E-02 4.42E-02 Xe-133 f

Ci

<LLD 2.82E-02 8.25E-04 2.09E-04 Total for Period Ci

<LLD 2.82E-02 4.56E-02 4.44E-02

2.

lodines_

_-131 Ci

<LLD

- <LLD I-133 Ci

<LLD

<LLD ITotal forPeriod J

Ci

<LLD J

<LLD

<LLD J

<LLD

3.

Particulates' I

Br-82 Ci

<LLD

<LLD 2.70E-08

<LLD Co-60 Ci

<LLD

< LLD 1.49E-08 l 6.99E-08 Total for Period Ci

<LLD J

<LLD 4.19E-08 6.99E-08

'Mixed mode continuous accountability includes mixed mode batch accountability (excludes tritium).

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 17 of 42 TABLE mH-C TYPICAL LOWER LIMITS OF DETECTION FOR GASEOUS EFFLUENTS Nuclide LLD (gCilcc)

H-3 1.52E-07 Ar-41 6.43E-08 Mn-54 2.38E-14 Co-58 3.01E-14 Fe-59 4.78E-14 Co-60 2.78E-14 Zn-65 7.42E-14 Br-82 4.37E-13 Kr-85 5.14E-06 Kr-85m 1.73E-08 Kr-87 4.78E-08 Kr-88 5.85E-08 Sr-89 3.52E-15 Sr-90 1.44E-15 Mo-99 6.55E-13 1-131 1.72E-14 Xe-131m 7.66E-07 1-133 1.04E-12 Xe-133 7.OOE-08 Xe-133m

1. lOE-07 Cs-134 2.09E-14 1-135 3.41E-08 Xe-135 1.26E-08 Xe-135m

1. 19E-07 Cs-137 2.71E-14 Xe-138 1.22E-06 Ba-140 1.09E-13 La-140 6.40E-14 Ce-141 3.99E-14 Ce-144 1.88E-13 Gross Alpha 2.62E-15

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 18 of 42 IV.

LIQUID EFFLUENTS A.

Batch Releases Jan - June 2003 July - Dec 2003 Number of batch releases 1.00E+01 1.7E+01 Total time period for batch releases 2.06E+03 min 3.14E+03 min Maximum time period for a batch release 3.20E+02 min 2.40E+02 min Average time period for a batch release 2.06E+02 min 1.84E+02 min Minimum time period for a batch release 1.28E+02 min 3.40E+01 min Average stream flow during release periods 5.58E+05 gpm 5.70E+05 gpm B.

Abnormal Releases Jan - June 2003 July - Dec 2003 Number of releases O.OOE+00 J

O.OOE+00 Total activity released O.OOE+00 Ci l

O.OOE+00 Ci C.

Data Tables The following tables provide the details of liquid releases:

Table IV-A Table IV-B Table IV-C Summation of All Releases Continuous Mode and Batch Mode Releases Typical Lower Limits of Detection for Liquid Effluents

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 19 of 42 TABLE IV-A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT - 2003 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES

_ x _ _ _ _ _ _

I nt IQuarter 1Quarter 1Est. Total

_____t 1

l 2

Error %

A.

Fission and Activation Products

1. Total release (not including tritium, gases, alpha)

Ci 1.27E-03 1.16E-03 1.07E+01 D

2. Average diluted concentration during period i+/-Ci/ml 4.64E-12 4.18E-12 B.

Tritium

1. Total release Ci 2.29E+00 3.85E+01 9.20E+00

2. Average diluted concentration during period liCi/ml 8.37E-09 1.39E-07 C.

Dissolved and entrained gases

1. Total release Ci

<LLD 6.47E-05 9.60E+00

2.

Average diluted concentration during period

,uCi/ml

<LLD 2.33E-13

3. Percent of applicable limit NA 1.17E-07 D.

Gross alpha radioactivity

1. Total release Ci

<LLD

<LLD 1.83E+Q1 E.

Volume of waste released prior to Liters 6.75E+04 2.32E+05 dilution__

F.

Volume of dilution water used during i

period Liters 2.73E+1 1 2.77E+1 I G.

Percent of 10 CFR 50, Appendix I

1. Quarterly Limit Organ: GI-LLI 4.27E-06 4.77E-05 Total body 5.13E-06 1.51E-04

2. Annual Limit Organ: GI-LLI 2.14E-06*

2.60E-05*

Total body 2.57E-06 7.82E-05*

Cumulative total for the year-to-date using the methodology in the ODCM.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 20 of 42 TABLE IV-A (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT - 2003 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Que Q

Est.Total

%l I3ni Qare Qu4e Error % Jj A.

Fission and Activation Products

1. Total release (not including 1.42E-03 1.39E-03 tritium, gases, alpha)

Ci 1.07E+o1

2. Average diluted concentration 4.89E-12 4.95E-12 2 during period 11Ci/ml B.

Tritium

1. Total release Ci 8.81E+00 1.16E+02 9.20E+00

2. Average diluted concentration 3___

____ ___ _I7 during period

[uCi/mI 3.03E-08 4.14E-07 C.

Dissolved and entrained gases

1. Total release Ci

<LLD 1.34E-05 9.60E+00

2. Average diluted concentration

<LLD 4.75E-14 during period yCi/ml

3. Percent of applicable limit NA 2.38E-08 D.

Gross alpha radioactivity

1. Total release Ci

<LLD

<LLD 1.83E+01 E.

Volume of waste released prior to 1 Liters 12.441+05 2.42+05 d ilu tio n Liter I.4

+ 52 4 E 0 F.

Volumeofdilutionwaterusedduring 1 r

1 1 I F.

period Liters 2.91E+11 2.81E+11 G.

Percent of 10 CFR 50, Appendix I

1. Quarterly Limit Organ: GI-LLI 3.76E-05 NA Organ: Liver NA 1.19E-04 Total body 6.69E-05 3.87E-04

2. Annual Limit Organ: GI-LLI 4.45E-05 1.03E-04 Total body 1.12E-04 3.05E-04*

Cumulative total for the year-to-date using the methodology in the ODCM.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 21 of 42 TABLE IV-B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT - 2003 LIQUID EFFLUENTS - CONTINUOUS MODE AND BATCH MODE RELEASES Continuous Mode Batch Mode eNuclides Released Unit Quarter Quarter Quarter Quarter NuldsRlae nt12 1

2 l H-3 l

Ci

<LLD

<LLD l_2.29E+00 __3.85E+01 Fe-55 Ci

<LLD

<LLD 5.23E-06 1.43E-05 Co-58 Ci

<LLD

<LLD 7.8 1E-05 6.99E-05 Co-60 Ci

<LLD

<LLD 7.52E-04 6.91E-04 Te-123m Ci

<LLD

<LLD 5.57E-06 Sb-124 Ci

<LLD

<LLD 3.38E-05

<LLD Sb-125 Ci

<LLD

<LLD 3.98E-04 3.73E-04 Cs-134 Ci

<LLD

<LLD Cs-137 Ci

<LLD

<LLD 5.64E-06 Total for Period Ci

<LLD

<LLD 1.27E-03 1.16E-03 I

Xe-133 Ci J

<LLD

<LLD 6.47E-05 Total for Period Ci

<LLD

<LU)

<LLD l

6.47E-05

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 22 of 42 TABLE IV-B (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT - 2003 LIQUID EFFLUENTS - CONTINUOUS MODE AND BATCH MODE RELEASES Continuous Mode Batch Mode l Nuclides Released Unit Quarter Quarter Quarter } Quarter H-3 Ci

< LLD

<LLD 8.80E+00 1.16E+02 Mn-54 Ci

<LLD

<LLD 1.46E-05

<LLD Fe-55 Ci

<LLD

<LLD 6.53E-05 1.38E-04 Co-57 Ci

<LLD

<LLD 2.70E-06

<LLD Co-58 Ci

<LLD

<LLD 6.52E-05 3.23E-06 Co-60 Ci

<LLD

<LLD 1.08E-03 8.96E-04 Zr-95 Ci

<LLD

<LLD 6.73E-06

<LLD Nb-95 Ci

<LLD

<LLD 1.70E-05

<LLD Ag-I 10mi Ci

<LLD

<LLD 4.51E-06

<LLD Sn-113 Ci

<LLD

<LLD 3.52E-06

<LLD Sb-125 Ci

<LLD

<LLD 1.44E-04 3.41 E-04 Cs-137 Ci

<LLD

<LLD 1.63E-05 1.31E-05 Total for Period Ci

<LLD

<LLD 1.42E-03 1.39E-03 l Xe-133 Ci

<LLD

<lLD

<LLD l

1.33E-05 Total for Period Ci l<LLD ldD

<LLD I 1.33E-05 JI

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 23 of 42 TABLE IV-C TYPICAL LOWER LIMITS OF DETECTION FOR LIQUID EFFLUENTS Nuclide LLD (uCifml)

H-3 3.75E-06 Cr-51 3.45E-07 Mn-54 3.36E-08 Fe-55 3.35E-08 Co-57 4.69E-08 Co-58 4.13E-08 Fe-59 6.08E-08 Co-60 3.66E-08 Zn-65 9.91E-08 Sr-89 3.14E-08 Sr-90 1.56E-08 Nb-95 4.47E-08 Zr-95 4.24E-08 Mo-99 3.47E-07 Tc-99m 5.08E-08 Ag-lOnm 2.86E-08 Sn-113 4.76E-08 Sb-122 6.38E-08 Te-123m 3.73E-08 Sb-124 1.30E-07 Sb-125 1.28E-07 Xe-127 7.63E-07 1-131 5.14E-08 Xe-131 m 1.93E-06 Te-132 4.14E-08 Xe-133 2.35E-07 Xe-133m 4.54E-07 Cs-134 3.14E-08 Xe-135 2.02E-07 Cs-137 4.01E-08 Ba-140 1.35E-07 La-140 6.67E-08 Ce-141 6.88E-08 Ce-144 3.55E-07 Gross Alpha 8.30E-08

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 24 of 42 V.

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Report Time Period: January 1, 2003, through December 31, 2003 A.

SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (not irradiated fuel)

Waste Class A

i.

Type of Waste Unit Period Est. Total J Solid.

Cont.

Form BNo ojTotal Error (%)

1 Agent 1 Type Ship.

a)

Spent resins, filter sludges, MNA N/A N/A N/A N/A N/A evaporator bottoms, etc.

Ci b)

Dry compressible waste, m3 1.53E+02 1.OOE+00 contaminated equipment, etc.

Ci 7.23E-01 2.07E+01 None STP Normal 2

c)

Irradiated components, control m

N/A N/A N/A N/A N/AN/A rods, etc.

Ci d)

Other: Containment vessel sludge m3 9.54E+01 I2.07E+01 None STP Normal 1

STP = Strong Tight Package HIC = High Integrity Container

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 25 of 42

2.

Estimate of major nuclide composition (by type of waste)

Ci

a.

N/A N/A N/A

b.

H-3 7.101E-01 5.11IE-03 C-14 8.24E+00 5.96E-02 Cr-51 9.20E-01 6.63E-03 Mn-54 4.40E-01 3.18E-03 Fe-55 2.16E+01 1.56E-0 I Co-58 1.41E+01 1.02E-01 Co-60 1.92E+01 1.39E-01 Ni-63 1.11E+01 8.OOE-02 Nb-95 1.68E+01 1.21E-01 Zr-95 4.84E+00 3.50E-02 Ag-110m.

5.00E-01 3.59E-03 Sb-125 4.60E-01 3.29E-03 Others*

1.10E+00 7.49E-03

c.

NA NA NA

d.

H-3 2.80E-01 2.70E-03 C-14 8.30E-01 7.91E-03 Mn-54 2.60E-01 2.52E-03 Fe-55 6.30E+00 6.03E-02 Co-58 4.00E-02 3.95E-04 Co-60 6.73E+0 1 6.45E-01 Ni-63 1.90E+01 1.82E-01 Zr-95 2.00E-02 2.34E-04 Sb-125 3.96E+00 3.80E-02 Cs-137 1.61E+00 1.54E-02 Ce-144 3.40E-01 3.28E-03 Pu-241 6.00E-02 5.63E-04 Others**

1.28E-02 1.22E-04

3.

Solid Waste Disposition Number of Shipments:

Mode of Transportation:

Destination:

3 Exclusive Use - Highway Race LLC, Duratek, Alaron Corp

Others include: Co-57, Fe-59, Sr-89, Sr-90, Tc-99, Cd-109, Sn-I 13, Te-123m, Sb-124,1-129, Cs-137, Ce-144, Pu-238, Pu-239, Pu-241, Am-241, Cm-242, Cm-243.

- Others include: Nb-95, Tc-99,1-129, Pu-238, Pu-239, Am-241, Cm-243.

Total Curie Quantity and Principle Radionuclides were determined by estimate.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 26 of 42 V.

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Report Time Period: January 1, 2003, through December 31, 2003 B.

SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (not irradiated fuel)

Waste Class B

Tyeo at nt Period Est. Total Solid.

Cont.

I Formn Shp

. TypeofWaste lUnit Total Error (%)

Agent Type l___Shi_

l a)

Spent resins, filter sludges, m3 N/A N/A N/A N/A N/A N/A evaporator bottoms, etc.

Ci b)

Dry compressible waste, m

N/A N/A N/A N/A N/A N/A contaminated equipment, etc.

Ci c)

Irradiated components, control m

N/3/

/

rods, etc.

Ci NIA N/A NIA NIA NIA N/A d)

Other:

m3 N/A N/A N/A N/A N/A N/A

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 27 of 42

2.

Estimate of major nuclide composition (by type of waste)

3.

Solid Waste Disposition Number of Shipments:

N/A Mode of Transportation:

N/A Destination:

N/A l[

[

=

a.

N/A

b.

N/A

c.

N/A

d.

N/A lN/A lN/A lN/A lN/A Ci Izz/A.

i j1

]1

]

1

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 28 of 42 V.

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Report Time Period: January 1, 2003, through December 31, 2003 C.

SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (not irradiated fuel)

Waste Class C

T of Wate Unit Period IEst. Total Solid. ICont. J For INo.

ypeo ase l

i Total l

Error(%)

Agent Type orm l Ship.

a)

Spent resins, filter sludges, m3 3.85E+00 1.00E+00 evaporator bottoms, etc.

Ci 6.71 E+00 2.07E+01 None HIC Normal I

b)

Dry compressible waste, m/3 contaminated equipment, etc.

Ci NIA NIA NIA N/A N/A NIA c)

Irradiated components, control m/3 rods, etc.

Ci NIA NIA NIA NIA N/A NIA d)

Other:

m3 N/A N/A N/A N/A N/A N/A HIC = High Integrity Container

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 29 of 42

2.

Estimate of major nuclide composition (by type of waste)

3.

Solid Waste Disposition Number of Shipments:

Mode of Transportation:

Destination:

I Exclusive Use - Highway Barnwell Ci

a.

C-14 8.16E+00 5.47E-01 Mn-54 6.90E-01 4.65E-02 Fe-55 3.25E+O1 2.18E+00 Co-58 2.42E+00 1.62E-01 Co-60 3.73E+01 2.50E+00 Ni-63 1.27E+01 8.54E-01 Nb-95 8.50E-01 5.70E-02 Zr-95 1.21E+00 8.12E-02 Cd-109 4.60E-01 3.09E-02 Ag-110mi 1.13E+00 7.59E-02 Sn-113 2.OOE-01 1.32E-02 Sb-125 1.46E+00 9.81E-02

Others 8.69E-01 5.82E-02

b.

N/A N/A N/A

c.

N/A N/A N/A

d.

N/A N/A N/A

Others include: H-3, Cr-51, Co-57, Fe-59, Ni-59, Zn-65, Sr-89, Sr-90, Tc-99, Te-123m, Sb-124, I-129, Cs-134, Cs-137, Ce-144, Pu-238, Pu-239, Pu-241, Am-241, Cm-242, Cm-243, Am-243.

Total Curie Quantity and Principle Radionuclides were determined by estimate.

D.

IRRADIATED FUEL SHIPMENTS Number of Shipments:

4 Mode of Transportation:

Exclusive Use - Rail Destination:

Shearon Harris Nuclear Power Plant

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 30 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 continuous releases, for the period January 1, 2003, through December 31, 2003.

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 (11 meter) sensor elevation.

Pertinent information available from the tables is as follows:

1.

Stability Percent occurrence Pasquill Stability categories based on lower level (11 meter) wind distribution:

A B

C D

E F

l G

8.39 6.12 7.42 37.38 22.19 8.57 9.93

2.

Wind Speed 11 Meter Average Speed (mph) 4.24 Percent Calm 8.85 Percent Less than 3.5 mph 47.34

3.

Wind Direction 11 Meter Prevailing S

Percent Occurrence 12.73

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 31 of 42 TAnlr1VII.A TJNT OCCU !iWRRrNrrFrRrOUiENCripq RRilVNffnl ANnL twNnlPnrT)CONvNIuJ 1RF1AqS~

Atmospheric Stability Class A Max (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 Total Max (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 Total N

0.00 0.05 0.38 0.12 0.01 0.00 0.00 0.56 NNZ 0.00 0.06 0.26 0.01 0.00 0.00 0.00 0.33 NE 0.00 0.15 0.18 0.00 0.00 0.00 0.00 0.33 ENE 0.00 0.14 0.20 0.00 0.00 0.00 0.00 0.34 E

0.00 0.14 0.15 0.00 0.00 0.00 0.00 0.30 ESE 0.00 0.23 0.13 0.00 0.00 0.00 0.00 0.36 SE 0.00 0.17 0.19 0.00 0.00 0.00 0.00 0.36 SSE 0.00 0.09 0.43 0.07 0.00 0.00 0.00 0.59 S

SSW SW 0.00 0.00 0.00 0.07 0.05 0.11 0.27 0.52 0.89 0.15 0.18 0.24 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.50 0.76 1.23 WSW 0.00 0.08 0.69 0.06 0.00 0.00 0.00 0.83 W

0.00 0.08 0.58 0.05 0.00 0.00 0.00 0.71 WNW 0.00 0.02 0.39 0.08 0.00 0.00 0.00 0.50 NW 0.00 0.04 0.17 0.19 0.01 0.00 0.00 0.40 NNW 0.00 0.00 0.12 0.13 0.05 0.00 0.00 0.30 Total 0.00 1.48 5.55 1.28 0.08 0.00 0.00 8.39 Total 0.01 1.22 3.70 1.14 0.05 0.01 0.00 6.12 Atmospheric Stability Class B N

0.00 0.06 0.41 0.20 0.00 0.00 0.00 0.68 NNE 0.00 0.02 0.21 0.02 0.00 0.00 0.00 0.26 NE 0.00 0.09 0.07 0.00 0.00 0.00 0.00 0.17 ENE 0.00 0.05 0.06 0.00 0.00 0.00 0.00 0.11 E

0.00 0.09 0.04 0.00 0.00 0.00 0.00 0.13 ESE 0.00 0.01 0.06 0.00 0.00 0.00 0.00 0.07 SE 0.00 0.09 0.06 0.00 0.00 0.00 0.00 0.16 SSE 0.00 0.09 0.28 0.08 0.00 0.00 0.00 0.46 S

0.00 0.05 0.17 0.06 0.00 0.00 0.00 0.27 SSW 0.00 0.05 0.55 0.15 0.00 0.00 0.00 0.75 SW 0.00 0.12 0.75 0.18 0.00 0.00 0.00 1.04 WSW 0.00 0.21 0.40 0.00 0.00 0.00 0.00 0.62 W

0.00 0.19 0.17 0.00 0.00 0.00 0.00 0.36 WNW 0.00 0.01 0.15 0.06 0.00 0.00 0.00 0.23 NW 0.00 0.04 0.17 0.23 0.02 0.00 0.00 0.45 NNW 0.00 0.04 0.15 0.15 0.02 0.01 0.00 0.38 Atmospheric Stability Class C Max (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 Total N

0.00 0.05 0.41 0.25 0.00 0.00 0.00 0.71 NNE 0.00 0.05 0.31 0.05 0.00 0.00 0.00 0.40 NE 0.00 0.12 0.21 0.00 0.00 0.00 0.00 0.33 ENE 0.00 0.19 0.24 0.00 0.00 0.00 0.00 0.43 E

0.00 0.11 0.01 0.00 0.00 0.00 0.00 0.12 ESE 0.00 0.17 0.01 0.00 0.00 0.00 0.00 0.18 SE 0.00 0.18 0.14 0.00 0.00 0.00 0.00 0.32 SSE 0.00 0.05 0.40 0.11 0.00 0.00 0.00 0.56 S

SSW 0.00 0.00 0.05 0.08 0.41 0.77 0.23 0.28 0.01 0.00 0.00 0.00 0.00 0.00 0.70 1.14 SW 0.00 0.08 0.69 0.06 0.00 0.00 0.00 0.83 WSW 0.00 0.13 0.21 0.01 0.00 0.00 0.00 0.36 W

0.00 0.12 0.13 0.00 0.00 0.00 0.00 0.25 WNW 0.00 0.05 0.12 0.04 0.00 0.00 0.00 0.20 NW 0.00 0.04 0.30 0.15 0.05 0.00 0.00 0.53 NNW 0.00 0.04 0.19 0.11 0.04 0.00 0.00 0.37 Total 0.00 1.48 4.56 1.28 0.09 0.00 0.00 7.42 Atmospheric Stability Class D Max (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 Total N

0.02 0.62 3.35 1.14 0.05 0.00 0.00 5.18 NNE 0.04 0.96 3.34 0.33 0.00 0.00 0.00 4.67 NE 0.05 1.23 1.26 0.00 0.00 0.00 0.00 2.54 ENE 0.05 1.28 1.01 0.00 0.00 0.00 0.00 2.34 E

0.03 0.71 0.37 0.00 0.00 0.00 0.00 1.11 ESE 0.03 0.75 0.09 0.00 0.00 0.00 0.00 0.87 SE 0.03 0.77 0.17 0.00 0.00 0.00 0.00 0.97 SSE 0.04 1.03 1.77 0.23 0.01 0.00 0.00 3.07 S

0.03 0.68 2.67 0.92 0.11 0.00 0.00 4.40 SSW 0.05 1.16 1.77 0.17 0.01 0.00 0.00 3.15 SW 0.04 1.00 1.01 0.05 0.00 0.00 0.00 2.09 WSW 0.03 0.82 0.39 0.06 0.00 0.00 0.00 1.30 W

0.02 0.63 0.25 0.00 0.00 0.00 0.00 0.90 WNW 0.02 0.47 0.37 0.09 0.00 0.00 0.00 0.96 NW 0.01 0.36 0.68 0.32 0.05 0.00 0.00 1.41 NNW 0.01 0.27 0.95 0.84 0.36 0.00 0.00 2.43 Total 0.51 12.73 19.42 4.15 0.58 0.00 0.00 37.38

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 32 of 42 Atmospheric Stability Class E Max (MIS)

N NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Total 0.34 0.04 0.05 0.06 0.05 0.02 0.02 0.03 0.10 0.23 0.29 0.16 0.11 0.06 0.06 0.06 0.04 1.37 1.56 0.34 0.43 0.50 0.41 0.15 0.14 0.24 0.88 2.03 2.51 1.43 0.94 0.56 0.51 0.51 0.37 11.94 3.35 0.40 0.04 0.01 0.04 0.05 0.04 0.02 0.69 1.58 1.11 0.91 0.25 0.11 0.44 1.01 0.97 7.65 5.59 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.11 0.08 0.06 0.01 0.00 0.05 0.20 0.59 1.13 8.27 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.04 0.05 0.09 11.18 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 24.59 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Total 0.80 0.51 0.57 0.50 0.22 0.19 0.29 1.68 3.95 4.00 2.57 1.30 0.73 1.05 1.81 2.02 22.19 Atmospheric Stability Class F Max (MIS)

N NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Total 0.34 0.04 0.05 0.01 0.00 0.00 0.00 0.01 0.17 0.33 0.34 0.26 0.14 0.11 0.09 0.13 0.13 1.81 1.56 0.11 0.13 0.04 0.01 0.01 0.01 0.02 0.49 0.97 1.01 0.77 0.41 0.31 0.26 0.38 0.38 5.31 3.35 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.04 0.19 0.24 0.09 0.02 0.00 0.04 0.36 0.44 1.42 5.59 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.02 0.02 8.27 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 11.18 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 24.59 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Total 0.16 0.18 0.05 0.02 0.02 0.02 0.03 0.69 1.49 1.59 1.13 0.58 0.41 0.39 0.86 0.97 8.57 Atmospheric Stability Class a Max (M/S)

N NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Total 0.34 0.18 0.10 0.03 0.00 0.00 0.04 0.08 0.45 0.76 0.36 0.36 0.41 0.23 0.30 0.89 0.96 5.14 1.56 0.15 0.08 0.02 0.00 0.00 0.04 0.07 0.38 0.64 0.31 0.31 0.34 0.19 0.25 0.75 0.81 4.34 3.35 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.01 0.01 0.00 0.00 0.00 0.00 0.11 0.31 0.45 5.59 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 8.27 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 11.18 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 24.59 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Total 0.34 0.18 0.05 0.00 0.00 0.08 0.16 0.84 1.41 0.68 0.67 0.75 0.41 0.54 1.74 2.07 9.93 Overall Wind Direction Frequency Total hours considered are 8440.

Wind measured at 11.0 meters.

Wind Direction N

NNE NE ENE E

ESE SE S5E 8

SSW SW WSW W

WNW NW NNW Total Frequency 8.41 6.53 4.03 3.73 1.89 1.76 2.27 7.89 12.73 12.06 9.57 5.74 3.78 3.86 7.21 8.53 100.00

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 33 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, 2003, through December 31, 2003.

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 (11 meter) sensor elevation.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 34 of 42 TABLE VTIIB JOINT OCCURRENCE FREOUENCIES FOR ILOWND)DEG AND LOWNDSPD - MIXED MODE BATCH RELEASFS Atmospheric Stability Class A Max (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 Total Max (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 Total N

0.00 0.27 0.27 0.00 0.00 0.00 0.00 0.53 0.00 0.00 0.00 0.40 0.00 0.00 0.00 0.00 0.40 NE 0.00 0.13 0.00 0.00 0.00 0.00 0.00 0.13 ENE 0.00 0.00 0.13 0.00 0.00 0.00 0.00 0.13 0

0.00 0.00 0.66 0.00 0.00 0.00 0.00

0. 66 ESE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 SE SSE S

SSW SW 0.00 0.00 0.00 0.00 0.00 0.13 0.00 0.13 0.13 0.13 0.13 0.53 0.13 0.27 0.80 0.00 0.27 0.27 0.00 0.40 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.27 0.80 0.53 0.40 1.33 WSW 0.00 0.13 0.27 0.00 0.00 0.00 0.00 0.40 WSW 0.00 0.00 0.40 0.00 0.00 0.00 0.00 0.40 W

0. 00 0.13 0.27 0.00 0.00 0.00 0.00 0.40 W

0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 WNW 0.00 0.00 0.53 0.00 0.00 0.00 0.00 0.53 WNW 0.00 0.13 0.27 0.00 0.00 0.00 0.00 0.40 NW 0.00 0.00 0.00 0.13 0.00 0.00 0.00 0.13 NW 0.00 0.00 0.00 0.13 0.00 0.00 0.00 0.13 NNW 0.00 0.00 0.27 0.13 0.00 0.00 0.00 0.40 NNW 0.00 0.00 0.00 0.13 0.00 0.13 0.00 0.27 Total 0.00 1.19 4.64 1.19 0.00 0.00 0.00 7.03 Total 0.00 0.53 3.45 0.40 0.00 0.13 0.00 4.51 Atmospheric Stability Class B N

0.00 0.00 0.00 0.00 0.00 0.00 0.00

0. 00 NNE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 NE 0.00 0.00 0.27 0.00 0.00 0.00 0.00 0.27 ENE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 E

0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ESE 0.00 0.00 0.27 0.00 0.00 0.00 0.00 0.27 SE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 SSE 0.00 0.27 0.40 0.13 0.00 0.00 0.00 0.80 S

0.00 0.00 0.00 0.00 0.00 0.00 0.00

0. 00 SSW 0.00 0.00 0.93 0.00 0.00 0.00 0.00 0.93 SW 0.00 0.13 0.93 0.00 0.00 0.00 0.00 1.06 Atmospheric Stability Class C Max (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 Total Max (HIS) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 Total N

0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 NNE 0.00 0.13 0.13 0.00 0.00 0.00 0.00 0.27 NE 0.00 0.13 0.53 0.00 0.00 0.00 0.00 0.66 ENE 0.00 0.00 0.40 0.00 0.00 0.00 0.00 0.40 E

0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ESE 0.00 0.00 0.13 0.00 0.00 0.00 0.00 0.13 SE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 SSE 0.00 0.00 0.40 0.27 0.00 0.00 0.00 0.66 S

SSW 0.00 0.00 0.00 0.00 0.13 0.53 0.27 0.13 0.00 0.00 0.00 0.00 0.00 0.00 0.40 0.66 SW 0.00 0.00 0.27 0.00 0.00 0.00 0.00 0.27 WSW 0.00 0.13 0.27 0.13 0.00 0.00 0.00 0.53 W

0.00 0.13 0.53 0.00 0.00 0.00 0.00 0.66 WNW 0.00 0.00 0.13 0.00 0.00 0.00 0.00

0. 13 NW 0.00 0.00 0.27 0.00 0.00 0.00 0.00 0.27 NNW 0.00 0.00 0.13 0.13 0.27 0.00 0.00 0.53 Total 0.00 0.53-3.85 0.93 0.27 0.00 0.00 5.57 Total 0.56 10.35 20.03 3.58 1.33

' 0.00 0.00 35.84 Atmospheric Stability Class D N

0.03 0.53 2.52 0.13 0.00 0.00 0.00 3.21 NNM 0.08 1.59 5.04 0.13 0.00 0.00 0.00 6.84 NE 0.01 0.27 0.53 0.00 0.00 0.00 0.00 0.81 ENE 0.05 1.06 0.53 0.00 0.00 0.00 0.00 1.64 E

0.01 0.13 0.27 0.00 0.00 0.00 0.00 0.41 ESE 0.03 0.40 0.13 0.00 0.00 0.00 0.00 0.56 SE 0.04 0.66 0.00 0.00 0.00 0.00 0.00 0.70 SSE 0.08 1.59 3.58 0.93 0.00 0.00 0.00 6.18 S

0.05 0.93 3.18 1.19 0.00 0.00 0.00 5.36 SSW 0.05 0.93 1.86 0.13 0.00 0.00 0.00 2.97 SW 0.03 0.40 1.06 0.00 0.00 0.00 0.00 1.49 WSW 0.03 0.53 0.13 0.00 0.00 0.00 0.00 0.69 W

0.01 0.27 0.00 0.00 0.00 0.00 0.00 0.28 WNW 0.00 0.00 0.27 0.00 0.00 0.00 0.00 0.27 NW 0.04 0.80 0.40 0.00 0.00 0.00 0.00 1.23 NNW 0.01 0.27 0.53 1.06 1.33 0.00 0.00 3.20

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 35 of 42 Atmospheric Stability Class E Max (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 Total N

0.03 0.13 0.40 0.00 0.00 0.00 0.00 0.56 NNE 0.03 0.13 0.13 0.00 0.00 0.00 0.00 0.29 NE 0.09 0.53 0.00 0.00 0.00 0.00 0.00 0.62 ZNZ 0.05 0.27 0.00 0.00 0.00 0.00 0.00 0.32 E

0.07 0.40 0.13 0.00 0.00 0.00 0.00 0.60 ESE 0.03 0.13 0.00 0.00 0.00 0.00 0.00 0.16 SE 0.05 0.27 0.13 0.00 0.00 0.00 0.00 0.45 SSE 0.24 1.33 1.86 0.13 0.00 0.00 0.00 3.55 S

0.42 2.39 3.05 0.00 0.00 0.00 0.00 5.86 SSW 0.40 2.25 2.52 0.13 0.00 0.00 0.00 5.31 SW WSW W

WNW NW NNW Total 0.25 1.46 1.72 0.13 0.00 0.00 0.00 3.57 0.09 0.53 0.00 0.00 0.00 0.00 0.00 0.62 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.03 0.13 1.19 0.00 0.00 0.00 0.00 1.35 0.07 0.40 0.93 0.13 0.00 0.00 0.00 1.53 0.05 0.27 0.93 0.80 0.00 0.00 0.00 2.04 1.90 10.61 13.00 1.33 0.00 0.00 0.00 26.83 Atmospheric Stability Class F Max (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 Total N

0.00 0.00 0.13 0.00 0.00 0.00 0.00 0.13 NNE 0.05 0.13 0.00 0.00 0.00 0.00 0.00 0.19 N0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 O.00 ZNZ 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 E

0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ESE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 SE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 SSE 0.15 0.40 0.00 0.00 0.00 0.00 0.00 0.54 S

0.24 0.66 0.40 0.00 0.00 0.00 0.00 1.30 SSW 0.57 1.59 0.53 0.00 0.00 0.00 0.00 2.69 SW 0.33 0.93 0.00 0.00 0.00 0.00 0.00 1.26 SW 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 WSW 0.15 0.40 0.00 0.00 0.00 0.00 0.00 0.54 WSW 0.36 0.27 0.00 0.00 0.00 0.00 0.00 0.62 W

0.05 0.13 0.00 0.00 0.00 0.00 0.00 0.19 W

0.36 0.27 0.00 0.00 0.00 0.00 0.00 0.62 WNW 0.05 0.13 0.13 0.00 0.00 0.00 0.00 0.32 WNW 0.17 0.13 0.00 0.00 0.00 0.00 0.00 0.31 NW 0.15 0.40 0.13 0.00 0.00 0.00 0.00 0.68 NW 1.42 1.06 0.00 0.00 0.00 0.00 0.00 2.48 NNW 0.15 0.40 0.27 0.13 0.00 0.00 0.00 0.94 NNW 1.42 1.06 0.27 0.00 0.00 0.00 0.00 2.75 Total 1.88 5.17 1.59 0.13 0.00 0.00 0.00 8.78 Total 6.39 4.78 0.27.

0.00 0.00 0.00 0.00 11.43 Atmospheric Stability Class G Max (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 Total N

0.36 0.27 0.00 0.00 0.00 0.00 0.00 0.62 NNE 0.36 0.27 0.00 0.00 0.00 0.00 0.00 0.62 NE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ENZ 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 E

0.00 0.00 0.00 0.00 0.00 0.00 0.00

0. 00 ESE 0.17 0.13 0.00 0.00 0.00 0.00 0.00 0.31 SE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 SSE 0.36 0.27 0.00 0.00 0.00 0.00 0.00 0.62 S

SSW 1.06 0.36 0.80 0.27 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1.86 0.62 Overall Wind Direction Frequency Total hours considered are 754.

Wind measured at 11.0 meters.

Wind Direction Frequency N

NNE NE ENE E

5.05 8.61 2.49 2.49 1.67 ESE SE 1.42 1.42 SSE 13.16 S

15.31 SSW 13.58 SW WSW 8.97 3.81 W

WNW 2.15 3.30 NW 6.45 NNW Total 10.12 100.00

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 36 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, 2003, through December 31, 2003.

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 (11 meter) sensor elevation.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 37 of 42 TABLE VII-C JOINT OCCMRRENCE FROIIENCIFS FOR LOWNDDEG AND) LOWNDSPD - GROUIND lEVEl. BATCH RELEASES Atmospheric Stability Max (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 Total N

0.00 0.79 0.00 0.00 0.00 0.00 0.00 0.79 NNM 0.00 0.79 0.00 0.00 0.00 0.00 0.00 0.79 NE 0.00 0.79 0.00 0.00 0.00 0.00 0.00 0.79 ENE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 E

0.00 0.00 0.00 0.00 0.00 0.00 0.00

0. 00 ESE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 SE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 SSE 0.00 0.00 0.00 0.00-0.00 0.00 0.00 0.00 S

0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Class A SSW 0.00 0.00 2.38 0.00 0.00 0.00 0.00 2.38 Class B SSW 0.00 0.00 3.17 0.00 0.00 0.00 0.00 3.17 SW 0.00 0.00 1.59 0.00 0.00 0.00 0.00 1.59 SW 0.08 0.79 5.56 0.00 0.00 0.00 0.00 6.43 WSW 0.00 0.00 1.59 0.00 0.00 0.00 0.00 1.59 WSW 0.16 1.59 3.97 0.00 0.00 0.00 0.00 5.71 W

0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 W

0.08 0.79 0.79 0.00 0.00 0.00 0.00 1.67 WNW 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 WNW 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 NW 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 NW 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 NNW 0.00 0.00 0.79 0.00 0.00 0.00 0.00 0.79 NNW 0.08 0.79 0.00 0.00 0.00 0.00 0.00 0.87 Total 0.00 2.38 6.35 0.00 0.00 0.00 0.00 8.73 Total 0.95 9.52 17.46 0.00 0.00 0.00 0.00 27.94 Atmospheric Stability Max (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 Total N

0.16 1.59 2.38 0.00 0.00 0.00 0.00 4.13 N00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 NE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ENE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 K

0.08 0.79 0.00 0.00 0.00 0.00 0.00 0.87 ESE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 SE 0.08 0.79 0.00 0.00 0.00 0.00 0.00 0.87 SSE 0.16 1.59 1.59 0.00 0.00 0.00 0.00 3.33 S

0.08 0.79 0.00 0.00 0.00 0.00 0.00 0.87 Atmospheric Stability Max (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 Total Max (M/S) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 Total N

0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 N

0.00 0.79 0.79 0.00 0.00 0.00 0.00 1.59 NNZ 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Nkm 0.00 0.00 2.38 0.00 0.00 0.00 0.00 2.38 NE 0.00 0.00 0.79 0.00 0.00 0.00 0.00 0.79 NE 0.16 4.76 1.59 0.00 0.00 0.00 0.00 6.51 ENE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 EN!

0.08 0.00 0.79 0.00 0.00 0.00 0.00 0.87 0

0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 E

0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ESE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 I

ESE 0.00 0.79 0.00 0.00 0.00 0.00 0.00 0.79 SE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 SSE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 S

0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Class C SSW 0.00 0.79 0.79 0.00 0.00 0.00 0.00 1.59 SW 0.00

0. 00 1.59 0.00 0.00 0.00 0.00 1.59 SW 0.00 0.79 1.59 0.00 0.00 0.00 0.00 2.38 WSW 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 WSW 0.08 3.17 0.00 0.00 0.00 0.00 0.00 3.25 W

0.00 0.79 0.00 0.00 0.00 0.00 0.00 0.79 W

0.08 2.38 0.00 0.00 0.00 0.00 0.00 2.46 WNW 0.00 0.00 0.79 0.00 0.00 0.00 0.00 0.79 WNW 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 NW 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 NW 0.08 3.17 0.00 0.00 0.00 0.00 0.00 3.25 NNW 0.00 0.79 0.00 0.00 0.00 0.00 0.00 0.79 NNW 0.00 0.79 0.00 0.00 0.00 0.00 0.00 0.79 Total 0.00 2.38 3.97 0.00 0.00 0.00 0.00 6.35 Total 0.71 23.02 8.73 0.79 0.00 0.00 0.00 33.25 Ltmospheric Stability Class D SE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 SSE 0.00 0.79 1.59 0.00 0.00 0.00 0.00 2.38 S

0.08 1.59 0.00 0.79 0.00 0.00 0.00 2.46 SSW 0.16 3.97 0.00 0.00 0.00 0.00 0.00 4.13

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 38 of 42 Max (MIS) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 Total Max (MIS) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 Total Max (MIS) 0.34 1.56 3.35 5.59 8.27 11.18 24.59 Total N

0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 N

0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 NNE NE 0.08 0.00 0.79 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.87 0.00 NNE NE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 NNE NE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ENE E

0.08 0.08 0.79 0.79 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.87 0.87 ENE E

0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ENE E

0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Atmospheric Stability Class Z ESE SE SSE S

SSW 0.00 0.00 0.00 0.00 0.24 0.00 0.00 0.00 0.00 1.59 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1.83 Atmospheric Stability Class F ESE SE SSE S

SSW 0.00 0.00 0.00 0.24 0.40 0.00 0.00 0.00 0.79 1.59 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1.03 1.98 Atmospheric Stability Class 0 ESE SE SSE S

SSW 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 SW 0.08 0.79 0.00 0.00 0.00 0.00 0.00 0.87 SW 0.40 1.59 0.00 0.00 0.00 0.00 0.00 1.98 SW 1.59 2.38 0.00 0.00 0.00 0.00 0.00 3.97 WSW 0.08 0.79 0.00 0.00 0.00 0.00 0.00 0.87 WSW 0.24 0.79 0.00 0.00 0.00 0.00 0.00 1.03 WSW 1.03 1.59 0.00 0.00 0.00 0.00 0.00 2.62 W

WNW 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 W

WNW 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 NW 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 NW 0.40 1.59 0.79 0.00 0.00 0.00 0.00 2.78 NW 0.56 0.79 0.00 0.00 0.00 0.00 0.00 1.35 NNW 0.00 0.00 0.79 0.00 0.00 0.00 0.00 0.79 NNW 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 NNW 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Total 0.63 5.56 0.79 0.00 0.00 0.00 0.00 6.98 Total 1.67 6.35 0.79 0.00 0.00 0.00 0.00 8.81 Total 3.17 4.76 0.00 0.00 0.00 0.00 0.00 7.94 Overall Wind Direction Frequency Total hours considered are 126.

Wind measured at 11.0 meters Wind Direction N

NNE NE Frequency 6.51 4.05 8.10 ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Total 1.75 1.75 0.79 0.87 5.71 4.37 15.08 18.81 15.08 4.92 0.79 7.38 4.05 100.00

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 39 of 42 CHANGES TO ODCM, PCP, AND RADIOACTIVE WASTE SYSTEMS TABLE OF CONTENTS Description..

Pane I.

Changes to the Offsite Dose Calculation Manual (ODCM).40 II.

Changes to the Radioactive Waste Systems.40 III.

Changes to the Process Control Program (PCP).40 IV.

Changes to the Land Use Census.40 V.

Instrument Inoperability.40 VI.

Liquid Holdup Tank Curie Limit.40 VII.

Waste Gas Decay Tank Curie Limit.40

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 40 of 42 I.

CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)

There were no changes to the ODCM during this reporting period.

II.

CHANGES TO THE RADIOACTIVE WASTE SYSTEMS There were no changes to the Radioactive Waste Systems during this reporting period.

mII.

CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)

There were no changes to the Process Control Program during this reporting period.

IV.

CHANGES TO THE LAND USE CENSUS The Land Use Census is performed every 24 months and was last performed in 2002. The next Land Use Census will be performed in 2004.

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.

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.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 41 of 42 CORRECTIONS TO PREVIOUS REPORTS TABLE OF CONTENTS Description Page I.

DISCUSSION.42

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0048 Page 42 of 42 I.

DISCUSSION There are no corrections to previous reports.

RNP-RA/04-0048, 2003 Annual Radioactive Effluent Release Report

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