RNP-RA/12-0040, 2011 Annual Radioactive Effluent Release Report

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2011 Annual Radioactive Effluent Release Report
ML12130A201
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 04/26/2012
From: Hightower W
Progress Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RNP-RA/12-0040
Download: ML12130A201 (41)
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Text

10 CFR 50.36a(a)(2)

TS 5.6.3

&jj. Progress Energy Serial: RNP-RA/12-0040 PR 2 6 2012 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/RENEWED LICENSE NO. DPR-23 2011 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Ladies and Gentlemen:

Attached is the Annual Radioactive Effluent Release Report for the period of January 1, 2011, through December 31, 2011, for H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2. This report is submitted in accordance withl0 CFR 50.4 as required by 10 CFR 50.36a(a)(2) and the HBRSEP, Unit No. 2, Technical Specifications Section 5.6.3.

This document contains no new Regulatory Commitments. If you have any questions on this subject, please contact me at (843) 857-1329.

Sincerely, W. Richard Hight t Supervisor - Licensing/Regulatory Programs WRH/rjr Attachment c: V. M. McCree, NRC, Region II Ms. Araceli Billoch Col6n, NRC, NRC (w/o Attachments)

NRC Resident Inspector Progress Energy Carolinas, Inc.

Robinson Nuclear Plant 3581 West Entrance Road eý Hartsville, SC 29550

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/12-0040 Page 1 of 39 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT January 1,2011 - December 31, 2011 PROGRESS ENERGY CAROLINAS H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 RENEWED OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/1 2-0040 Page 2 of 39 TABLE OF CONTENTS D escription ..................................................................................................................... Page I. EXECU TIV E SUM MA RY ........................................................................................... 4 A. D iscussion .......................................................................................................... 4 B. Significant V ariances ......................................................................................... 8 C. Regulatory Com pliance ...................................................................................... 8 II. SU PPLEM EN TA L IN FO RM A TIO N ........................................................................... 9 A. Regulatory Lim its ................................................................................................ 9 B. Measurements and Approximations of Total Radioactivity ............................. 10 C. Estim ated Total Errors ........................................................................................... 11 III. GA SEO U S EFFLU EN TS .............................................................................................. 12 A. Batch Releases ................................................................................................... 12 B. Abnorm al Releases ........................................................................................... 12 C. D ata Tables ....................................................................................................... 12 IV . LIQ U ID EFFLU EN TS ................................................................................................... 18 A. Batch Releases ................................................................................................... 18 B. A bnorm al Releases ........................................................................................... 18 C. D ata Tables ....................................................................................................... 18 V. SOLID WASTE AND IRRADIATED FUEL SHIPMENTS ....................................... 24 A. W aste Class A ................................................................................................... 24 B. W aste Class B .................................................................................................. 27 C. W aste Class C .................................................................................................. 29 V I. 40 CFR 190 D O SE CO N FO RM A NCE ......................................................................... 32 V II. M ETEO RO LO GICA L D ATA ..................................................................................... 32 A. Continuous Release D iffusion Analysis .......................................................... 32

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/12-0040 Page 3 of 39 LIST OF TABLES Table D escription ............................................................................................. Pag e Table 11-A Gaseous Effluents - Summation of All Releases .................................. 13 Table III-B Gaseous Effluents - Ground Level and Mixed Mode Releases ............ 15 Table 11-C Typical Lower Limits of Detection for Gaseous Effluents ................... 17 Table IV-A Liquid Effluents - Summation of All Releases ..................................... 19 Table IV-B Liquid Effluents - Continuous Mode and Batch Mode Releases .......... 21 Table IV-C Typical Lower Limits of Detection for Liquid Effluents ..................... 23 Table VII-A Joint Occurrence Frequencies for LOWNDDEG and LOWNDSPD -

Ground Continuous Releases ............................................................... 33

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/12-0040 Page 4 of 39

1. EXECUTIVE

SUMMARY

A. Discussion

1. Effluent Controls The H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2, Offsite Dose Calculation Manual specifies controls and dose limits pertaining to releases of radioactivity to the environment. None of these controls or dose limits were exceeded during 2011.
2. 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 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.
3. 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.

4. Noble Gas Some of the fission products released in airborne effluents are radioactive isotopes of noble gases, such as 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.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/12-0040 Page 5 of 39

5. lodines and Particulates 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.

March and April 2011, RNP's Radiological Environmental Monitoring Program identified detectable concentration of 1-131 from samples obtained from iodine cartridges at the control station #I in Florence, SC and similar locations through the region. The plant's gaseous effluent indicated similar activities of 1-131. As such, the atypical detection of 1-131 in the gaseous effluent is credibly attributed to the trans-Pacific transport of airbone releases from Dai-Ichi, Fukushima following the March 11, 2011 Tohoku earthquake and is not related to plant operations and was not accounted for in this report. (NCR-00464849)

6. Tritium Tritium, a radioactive isotope of hydrogen, is a predominate radionuclide in liquid and gaseous effluents. Tritium is produced in the reactor via a number of processes. Tritium is a weak beta particle emitter and contributes very little radiation exposure to the human body, and when tritium is inhaled, ingested, or absorbed it is dispersed throughout the body until eliminated.
7. 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 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, batch releases 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.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/12-0040 Page 6 of 39 The plant has a meteorological tower, which is linked to computers that record the meteorological data. This meteorological data and the results of the Land Use Census are used to verify the ground level dispersion factors contained in the ODCM that are used in calculating the dose to the public.

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.

8. 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.

Even though radionuclides can reach humans by many different pathways, some radionuclides result in more exposure than others. The critical pathway is the one that, for a specific radionuclide, will result in 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, and usage factors.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/12-0040 Page 7 of 39

9. Plant Operation With the exception of September 26, 2011 thru September 29, 2011 HBRSEP, Unit No. 2, operated continuously.
10. 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, 2011 through December 31, 2011. 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 Otr Fission & Act. Gas Ci 5.48E-02 7.06E-02 6.92E-02 1.05E-01 1-131 Ci ND1 ND 1.58E-07 9.97E-07 Part. >8 Day Half-Lives Ci ND 8.36E-08 ND ND Tritium Ci 1.36E+00 2.31E+00 1.76E+00 9.80E-01 LIQUID EFFLUENTS Units 1st Otr 2nd Otr 3rd Ot. 4th Otr Fission & Act. Products Ci 3.67E-04 1.47E-03 8.91E-04 1.99E-04 Tritium Ci 6.14E+00 1.59E+01 6.77E+01 3.34E+02 Dilution Volume Liters 2.80E+1 1 2.73E+11 2.89E+ 11 2.87E+1 1 Waste Volume Liters 9.66E+04 2.1OE+05 3.51E+05 9.03E+05 During the period of January 1, 2011 through December 31, 2011, the estimated maximum individual offsite dose due to radioactivity released in effluents was:

Liquid Effluents:

  • Total Body Dose 0.0000385 millirem
  • Critical Organ Dose 0.0000392 millirem, Liver Note - an additional 0.163 mrem to a child was estimated based on the evaporation of tritium from Lake Robinson. This is based on Lake Robinson 2011 environmental sample results, 2011 meteorology and represents the dose from the buildup in the lake. This conservatively bounds the dose due to 2011 tritium effluents.

I ND, No Detectable Activity

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/12-0040 Page 8 of 39 Gaseous Effluents:

" Beta Air Dose 0.00150 millirad

" Gamma Air Dose 0.00303 millirad

" Critical Organ Dose 0.08830 millirem, Thyroid Note - Carbon-14 releases resulted in 0.122 mrem to the total body and 0.610 mrem to the bone of a child, which is not included in the above doses. It is estimated that 8.95 curies of Carbon-14 were released during 2011.

B. Significant Variances

1. No variances in historical data of significance were identified during this period.

C. Regulatory Compliance

1. The 10 CFR 50, Appendix I, doses were calculated using the Canberra Effluent Management System (EMS'). The 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. 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 2011, 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 36.
3. There were no changes to the Radioactive Waste Systems (i.e., liquid, gaseous, or solid) during this reporting period. See page 36.
4. There were no reportable instrumentation inoperability events during this reporting period. See page 37.
5. There were no outside liquid holdup tanks that exceeded the 10 curie limit during this reporting period. See page 37.
6. There were no Waste Gas Decay Tanks that exceeded the 1.9E+04 curie limit during this reporting period. See page 37.
7. There were no instances of missed compensatory samples during this reporting period. See page 37.
8. There was one revision to the ODCM during this reporting period. See page 36.

EMS, Effluent Management System Software is a product of Canberra Nuclear Industries used for determining dose from radioactive effluent releases.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/12-0040 Page 9 of 39

9. There were no dose calculations performed or special reports made as a result of any spills or leaks during this period. See page 37.
10. There were no events associated with a failure to meet an ODCM specified sampling frequency. See page 37.
11. 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 pCi/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/12-0040 Page 10 of 39 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.

e) Carbon 14 - The activity released is determine by using NUREG-0017 (GALE Code) Section 2.2.25 and corrected for Effective Full Power Days (EFPD) for 2011.

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.

e) Carbon 14 - The activity released is determine by using NUREG-0017 (GALE Code) Section 2.2.25 and corrected for Effective Full Power Days (EFPD) for 2011.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/12-0040 Page 11 of 39

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 - The activity released as tritium is based on the grab sample analysis of each batch and the batch volume. For continuous releases, the activity released as tritium is based on analysis of a weekly composite sample. For continuous releases without a composite sampler, the tritium activity is based on analysis of daily grab samples or a composite of grab samples.

c) Alpha - The measured alpha concentration in a monthly composite sample is used to calculate the total release and average diluted concentration during each period.

d) 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/12-0040 Page 12 of 39 III. GASEOUS EFFLUENTS A. Batch Releases Jan-June 2011 July - Dec 2011 Number of batch releases 58 66 Total time period for batch releases 2.97E+04 min 1.96E+04 min Maximum time period for a batch release 9.68E+03 min 6.90E+02 min Average time period for a batch release 5.12E+02 min 2.97E+02 min Minimum time period for a batch release 3.OOE+01 min 6.OOE+00 min B. Abnormal Releases Jan - June 2011 July - Dec 2011 Number of releases 0 0 Total activity released 0.OOE+00 Ci 0.OOE+00 Ci C. Data Tables The following tables provide the details of gaseous releases:

Table 111-A Summation of All Releases Table III-B Ground Level and Mixed Mode Releases Table III-C Typical Lower Limits of Detection for Gaseous Effluents

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/12-0040 Page 13 of 39 TABLE III-A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT - 2011 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total UI t I 1 2 1 Error % I A. Fission and Activation Gases

1. otal release Ci 5.48E-02 7.06E-02 3.24E+01
2. Average release rate for period IiCi/sec 7.04E-03 8.99E-03 B. lodines
1. Total Iodine-131 Ci ND 3 ND 3 6.21E+0 I
2. Average release rate for period [XCi/sec ND 3 ND3 C. Particulates
1. Particulates with half-lives >8 days Ci ND 8.36E-08 5.80E+01
2. Average release rate for period [iCi/sec ND 1.06E-08
3. Gross alpha radioactivity Ci ND ND D. Tritium
1. Total release Ci 1.36E+00 2.31E+00 5.25E+01I
2. Average release rate for period *ICi/sec 1.74E-0I 2.94E-01 E. Carbon- 14
1. Total release' Ci 2.24E+00 2.24E+00
2. Average release rate for period ýICi/sec 2.84E-01 2.84E-01 F. Percent of 10 CFR 50, Appendix I I. Quarterly limit Gamma air  % 1.54E-02 1.50E-02 Beta air  % 3.27E-03 3.62E-03 Organ: Thyroid 2  % 2.49E-01 4.24E-01
2. Cumulative Annual limit*

Gamma air  % 7.71E-03 1.52E-02 Beta air  % 1.64E-03 3.45E-03 Organ: Thyroid 2  % 1.24E-01 3.36E-01

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

'The estimated releases of Carbon-14 are not based on measurements of effluents, but on the methodology of NUGEG-0017 adjusted for EFPD. The calculated annual release is divided equally among the four calendar 2quarters.

The maximum organ dose (determined to be the thyroid from measured effluents) does not include Carbon-14 child bone dose of 0.153 mrem per quarter. Total Body dose from Carbon-14 releases is 0.0304 mrem per quarter.

3 lodines were detected in effluent sample during March and April while at the same time period the Environmental Samples reveal the similar concentrations due to Dai-Ichi, Fukushima and are not reported.

(NCR-00464849)

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/12-0040 Page 14 of 39 TABLE 11-A (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT - 2011 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Quarter Quarter Est. Total Unt3 4 Error %

B. lodines

1. Total Iodine-131 Ci 1.58E-07 9.97E-07 6.21E+O1
2. Average release rate for period [Ci/sec 1.99E-08 1.26E-07 C. Particulates
1. Particulates with half-lives >8 days Ci ND ND 5.80E+01
2. Average release rate for period pLCi/sec ND ND
3. Gross alpha radioactivity Ci ND ND D. Tritium
1. Total release Ci 1.76E+00 9.80E-01 5.25E+01 11 2. Average release rate for period ICi/sec 2.2 1E-01 1.23E-01 E. Carbon- 14
1. Total release' Ci 2.24E+00 2.24E+00
2. Average release rate for period pCi/sec 2.84E-01 2.84E-01 F. Percent of 10 CFR 50, Appendix I I. Quarterly limit Gamma air  % 1.36E-02 1.67E-02 Beta air  % 3.41E-03 4.70E-03 Organ: Thyroid 2  % 3.22E-01 1.82E-01
2. Cumulative Annual limit*

Gamma air  % 2.20E-02 3.03E-02 Beta air  % 5.15E-03 7.50E-02 Organ: Thyroid 2  % 4.97E-01 5.88E-01

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

'The estimated releases of Carbon-14 are not based on measurements of effluents, but on the methodology of NUREG-0017 adjusted for EFPD. The calculated annual release is divided equally among the four calendar 2The quarters maximum organ dose (determined to be the thyroid from measured effluents) does not include Carbon-14 bone dose of 0.153 mrem per quarter. Total Body dose from Carbon-14 releases is 0.0304 mrem per quarter.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/12-0040 Page 15 of 39 TABLE II-B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT - 2011 GASEOUS EFFLUENTS - GROUND LEVEL AND MIXED MODE RELEASES Continuous Mode Batch Mode

[Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2

1. Fission Gases Ar-41 Ci ND ND 3.15E-02 2.99E-02 Kr-85 Ci ND ND ND 5.65E-04 Xe-133 Ci ND 2.70E-02 2.33E-02 1.32E-02 Xe-135 Ci ND ND 1.95E-05 ND Total for Period Ci ND 2.70E-02 5.48E-02 4.37E-02
2. Iodines' 1-131. Ci ND ND ND ND 1-133 Ci ND ND ND ND Total for Period Ci ND ND ND ND
3. Particulates1

/ Co-60 Ci ND ND ND 8.36E-08 Total for Period Ci ND ND ND 8.36E-08

4. Carbon- 14 C-14 Ci 1.38E+00 1.38E+00 8.59E-01 8.59E-01 Total for Period Ci 1.38E+00 1.38E+00 8.59E-01 8.59E-01 Mixed mode continuous accountability includes mixed mode batch accountability (excludes tritium).

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/12-0040 Page 16 of 39 TABLE Ill-B (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT - 2011 GASEOUS EFFLUENTS - GROUND LEVEL AND MIXED MODE RELEASES Continuous Mode Batch Mode Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 1 Quarter 4

1. Fission Gases Ar-41 Ci ND ND 2.69E-02 3.22E-02 Kr-85 Ci ND ND 3.15E-04 4.1OE-04 Kr-85m Ci ND ND ND 1.17E-05 Xe-131m Ci ND ND ND 6.42E-04 Xe-133 Ci 3.15E-02 1.63E-02 1.06E-02 5.38E-02 Xe-133m Ci ND ND ND 4.96E-04 Xe-135 Ci ND ND 2.01E-06 7.97E-04 Total for Period Ci 3.15E-02 1.63E-02 3.78E-02 8.84E-02
2. lodines1 1-131 Ci 1.58E-07 9.97E-07 ND ND 1-133 Ci ND 2.75E-06 ND ND Total for Period Ci 1.58E-07 3.75E-06 ND ND
3. Particulates' Total for Period Ci ND ND ND ND
4. Carbon-14 C-14 Ci 1.38E+00 1.38E+00 8.59E-01 8.59E-01 Total for Period Ci 1.38E+00 1.38E+00 8.59E-01 8.59E-01

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

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/12-0040 Page 17 of 39 TABLE III-C TYPICAL LOWER LIMITS OF DETECTION FOR GASEOUS EFFLUENTS Nuclide LLD (gCi/cc)

H-3 6.85E-09 Ar-41 2.54E-08 Mn-54 9.55E-15 Co-58 5.70E-14 Fe-59 6.OOE-14 Co-60 1.41E-14 Zn-65 6.47E-14 Br-82 1.93E-13 Kr-85 2.60E-06 Kr-85m 1.75E-08 Kr-87 4.60E-08 Kr-88 4.52E-08 Sr-89 1.92E-15 Sr-90 8.25E-16 Mo-99 7.40E- 13 1-131 5.30E-14 Xe-131m 7.03E-07 1-133 1.20E-12 Xe-133 4.45E-08 Xe-133m 1.29E-07 Cs-134 3.91E-14 1-135 2.21E-09 Xe-135 1.72E-08 Xe-135m 6.63E-08 Cs-137 2.42E-14 Xe-138 2.07E-07 Ba-140 1.67E-13 La-140 5.62E-14 Ce-141 6.23E-14 Ce- 144 2.28E- 13 Gross Alpha 3.44E- 15

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/12-0040 Page 18 of 39 IV. LIQUID EFFLUENTS A. Batch Releases Jan -June 2011 July - Dec 2011 Number of batch releases 10 44 Total time period for batch releases 2.04E+03 min 9.56E+03 min Maximum time period for a batch release 2.36E+02 min 3.07E+02 min Average time period for a batch release 2.04E+02 min 2.17E+02 min Minimum time period for a batch release 1.13E+02 min 7.00E+01 min Average stream flow during release periods 3.75E+05 gpm 3.96E+05 gpm B. Abnormal Releases Jan - June 2011 July - Dec 2011 Number of releases 0 0 Total activity released O.00E+00 Ci 0.OOE+00 Ci C. Data Tables The following tables provide the details of liquid releases:

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

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/12-0040 Page 19 of 39 TABLE IV-A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT - 2011 LIOUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 1 1 2 Error % I A. Fission and Activation Products B. Tritium

1. Total release Ci 6.14E+00 1.59E+01 3.03E+01
2. Average diluted concentration during LCi/ml 2.19E-08 5.84E-08 period _Ci/ml 2.19E-08 5.84E-08 C. Dissolved and entrained gases
1. Total release Ci 2.57E-06 7.49E-06 4.72E+0 I
2. Average diluted concentration during VCi/ml 9.18E-15 2.75E-14 period
3. Percent of applicable limit  % 4.59E-09 1.38E-08 D. Gross alpha radioactivity
1. Total release Ci ND ND 1.83E+01 E. Volume of waste released prior to Liters 9.66E+04 2.10E+05 dilution I F. Volume of dilution water used during Liters 2.80E+ 2.73E+1 period i G. Percent of 10 CFR 50, Appendix I
1. Quarterly Limit Organ: GI-LLI, Liver'  % 3.22E-06 4.63E-05 Total body  % 7.08E-06 1.25E-04
2. Cumulative Annual Limit*

Organ: Liver, GI-LLI  % 1.61E-06 2.42E-05 Total body  % 3.53E-06 6.58E-05 GI-LLI, gastrointestinal-lower

  • Cumulative large intestine total for the year-to-date using the received the highest methodology in the dose ODCM.for Quarter 1 & Liver for Quarter 2.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/12-0040 Page 20 of 39 TABLE IV-A (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT - 2011 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 1 1 Quaer tUnit Quarter Est. Total B. Tritium

1. Total release Ci 6.77E+01 3.34E+02 3.03E+01
2. Average diluted concentration during [.Ci/ml 2.34E-07 1.1 6E-06 period C. Dissolved and entrained gases
1. Total release Ci 7.71E-04 5.21E-02 4.72E+0 I
2. Average diluted concentration 2.67E-12 1.81E-10 n1Ci/mi during period ___i/ml 2.67E-12 1.81E-10
3. Percent of applicable limit  % 2.39E-07 4.23E-06 D. Gross alpha radioactivity
1. Total release Ci ND 5.55E-05 1.83E+01 E. Volume of waste released prior to Liters 3.51E+05 9.03E+05 dilution F. Volume of dilution water used during Liters 2.89E+11 2.87E+1l period G. Percent of 10 CFR 50, Appendix I
1. Quarterly Limit Organ: Liver, GI-LLI1  % 1.13E-04 6.23E-04 Total body  % 3.64E-04 2.07E-03
2. Cumulative Annual Limit*

Organ:, GI-LLI  % 8.06E-05 3.92E-04 Total body  % 2.48E-04 1.28E-03 1Liver received the highest dose for Quarter 3 & 4.

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

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RAJ12-0040 Page 21 of 39 TABLE IV-B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT - 2011 LIQUID EFFLUENTS - CONTINUOUS MODE AND BATCH MODE RELEASES Continuous Mode Batch Mode Nuclides Released Uni Quarter Quarter Quarter Quarter

.H-3 Ci [ ND ND 6.13E+00 1.59E+01 Fe-55 Ci ND ND 8.78E-05 7.13E-05 Mn-54 Ci ND ND ND 1.58E-05 Co-57 Ci ND ND 1.02E-06 ND Co-58 Ci ND ND 4.25E-05 5.74E-05 Co-60 Ci ND ND 1.79E-04 1.22E-03 Nb-95 Ci ND ND ND 4.53E-06 Ag-1Orn Ci ND ND ND 5.39E-06 Sb-125 Ci ND ND 5.61E-05 6.OOE-05 Cs- 134 Ci ND ND ND 9.68E-06 Cs-137 Ci ND ND ND 2.51E-05 Total for Period Ci ND ND 3.67E-04 1.47E-03 Xe-133 Ci ND ND 2.57E-06 7.49E-06 Total for Period Ci ND ND 2.57E-06 7.49E-06

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/12-0040 Page 22 of 39 TABLE IV-B (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT - 2011 IJOUJID FEFFLUENTS - CONTINIJOI~JS MODE AND BATCH MODE RELEASES LIQUID EFFLUENTS - CONTINUOUS MODE AND BATCHMODE RELEASES Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter H-3 Ci ND ND 6.77E+01 3.33E+02 Fe-55 Ci ND ND 3.47E-04 8.18E-05 Mn-54 Ci ND ND 1.50E-06 3.14E-07 Co-57 Ci ND ND 1.06E-06 ND Co-58 Ci ND ND 1.69E-05 4.68E-07 Co-60 Ci ND ND 4.67E-04 5.47E-05 Sb-125 Ci ND ND 5.17E-05 5.97E-05 Te- 132 Ci ND ND 1.15E-06 ND Cs-137 Ci ND ND 4.34E-06 7.05E-07 Ce-141 Ci ND ND ND 2.08E-07 Total for Period Ci ND ND 8.91E-04 1.98E-04 Xe-127 Ci ND ND ND 1.50E-07 Xe-131m Ci ND ND ND 3.90E-04 Xe-133 Ci ND ND 7.71E-04 5.13E-02 Xe- 133m Ci ND ND ND 3.67E-04 Xe-135 Ci ND ND ND 1.77E-05 Total for Period Ci ND ND 7.7 1E-04 5.2 1E-02 Gross Alpha Ci ND ND ND 5.55E_05

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/ 12-0040 Page 23 of 39 TABLE IV-C TYPICAL LOWER LIMITS OF DFTFCTION FOR LIOI JID EFFI I JENTS Nuclide LLD (jCi/ml)

H-3 4.19E-06 Cr-51 1.25E-07 Mn-54 1.84E-08 Fe-55 8.64E-08 Co-57 2.29E-08 Co-58 2.84E-08 Fe-59 2.88E-08 Co-60 2.48E-08 Zn-65 3.24E-08 Sr-89 3.70E-08 Sr-90 1.36E-08 Nb-95 1.21E-08 Zr-95 2.16E-08 Mo-99 1.61E-07 Tc-99m 2.06E-08 Ag- I1I0m 1.87E-08 Sn- 113 2.46E-08 Sb- 122 2.72E-08 Te-123m 2.02E-08 Sb-124 1.44E-08 Sb-125 5.20E-08 Xe-127 1.45E-08 1-131 1.67E-08 Xe-131m 1.05E-06 Te-132 1.77E-08 Xe-133 7.07E-08 Xe-133m 1.90E-07 Cs- 134 2.04E-08 Xe- 135 2.67E-08 Cs- 137 1.26E-08 Ba-140 7.30E-08 La-140 2.30E-08 Ce-I141 3.71E-08 Ce- 144 1.49E-07 Gross Alpha 8.74E-08

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RAIl 1-0027 Page 24 of 39 V. SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Report Time Period: January 1, 2011, through December 31, 2011 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (not irradiated fuel)

Waste Class A Waste Activity Estimated No.

1. Type of Waste Volume (M 3) (Ci) Error (%) Ship.
a. Spent resins, filter sludge, evaporator 6.81E+00 5.41E+00 2.OOE+01 2 bottoms, etc.
b. Dry compressible waste, contaminated 5.59E+01 1.04E-01 2.OOE+0l 1 equipment, etc.
c. Irradiated components, control rods, etc. N/A N/A N/A N/A
d. Other: Oil 2.28E+00 3.62E-06 2.OOE+01 1
1) shipped with Dry Compressible Waste

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/l 1-0027 Page 25 of 39

2. Estimate of major nuclide composition (by type of waste)

Re~in!~

Radionuclide  % Ci Ni-63 7.66E+01 4.14E+00 Fe-55 6.49E+00 3.51E-01 Co-60 6.39E+00 3.45E-01 Cs-137 4.15E+00 2.24E-01 Cs-134 2.96E+00 1.60E-OI C- 14 1.14E+00 6.14E-02 Sb-125 7.OOE-01 3.78E-02 Sr-90 4.73E-01 2.56E-02 Ni-59 4.64E-01 2.51 E-02 Mn-54 3.45E-01 1.87E-02 Co-58 1.43E-01 7.73E-03 H-3 7.92E-02 4.28E-03 Others

  • 8.85E-02 4.79E-03 Dry Compressible Waste Radionuclide  % Ci Fe-55 5.29E+01 5.50E-02 Co-60 1.33E+01 1.39E-02 Ni-63 1.14E+01 1.18E-02 Co-58 8.59E+00 8.93E-03 Cr-51 2.41E+00 2.51E-03 Cs-137 2.OOE+00 2.08E-03 Ce-144 1.94E+00 2.02E-03 Nb-95 1.80E+00 1.87E-03 H-3 1.72E+00 1.79E-03 Zr-95 1.52E+00 1.58E-03 Fe-59 8.55E-01 8.89E-04 Ag-I lOm 6.20E-01 6.45E-04 Others ** 9.60E-01 1.04E-01 Oil Radionuclide  % Ci Cs-137 7.89E+01 2.86E-06 Co-60 1.88E+01 6.82E-07 Ce- 144 2.25E+00 8.14E-08
  • Others include Co-57, Pu-241, Ce-144, Tc-99, Cm-243, Cm-242, Pu-238, Am-241, & Pu-239.
    • Others include Sb-125, Mn-54, C-14, Sr-90, Co-57, Cs134, Sn-i 13, Zn-65, Cm-242, Cm-243, Pu-238, Am-241, Pu-239, &

Sn-117m.

Total Curie Quantity and Principle Radionuclides were determined by estimate.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/1 1-0027 Page 26 of 39

3. Irradiated Fuel Shipments Number of Shipments: 0 Mode of Transportation N/A Destination N/A
4. Solid Waste Number of Shipments: 3 Mode of Transportation Highway - Exclusive Use Destination Barnwell Disposal Facility, Duratek Services, Inc.(Bear Creek)

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/1 1-0027 Page 27 of 39 V. SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Report Time Period: January 1,2011, through December 31, 2011 B. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (not irradiated fuel)

Waste Class B Waste Activity Estimated No.

1. Type of Waste Volume (Mi) (Ci) Error (%) Ship.
a. Spent resins, filter sludge, evaporator N/A N/A N/A N/A bottoms, etc.
b. Dry compressible waste, contaminated N/A N/A N/A N/A equipment, etc.
c. Irradiated components, control rods, etc. N/A N/A N/A N/A
d. Other: N/A N/A N/A N/A N/A

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/1 1-0027 Page 28 of 39

2. Estimate of major nuclide composition (by type of waste)

% Ci II Resins N/A T N/A N/A

3. Irradiated fuel shipments Number of Shipments: 0 Mode of Transportation N/A Destination N/A
4. Solid Waste Number of Shipments: 0 Mode of Transportation Exclusive Use Destination Bamwell Disposal Facility No Class B Shipments were made in 2011.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/1 1-0027 Page 29 of 39 V. SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Report Time Period: January 1, 2011, through December 31, 2011 C. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (not irradiated fuel)

Waste Class C Waste Activity Estimated No.

1. Type of Waste Volume (M3) (Ci) Error (%) Ship.
a. Spent resins, filter sludge, evaporator 1.02E+01 2.11 E+02 2.OOE+01 3 bottoms, etc.
b. Dry compressible waste, contaminated N/A N/A N/A N/A equipment, etc.
c. Irradiated components, control rods, etc. N/A N/A N/A N/A
d. Other N/A N/A N/A N/A

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/1 1-0027 Page 30 of 39

2. Estimate of major nuclide composition (by type of waste)

Resins & Filters Radionuclide  % Ci Ni-63 5.71E+01 1.21E+02 Cs-137 1.32E+01 2.78E+01 Cs- 134 1.04E+01 2.20E+01 Fe-55 9.01E+00 1.90E+01 Co-60 5.92E+00 1.25E+01 C- 14 1.23E+00 2.60E+00 Sr-90 1.07E+00 2.27E+00 Mn-54 7.79E-0I 1.65E+00 Sb-125 4.59E-01 9.70E-01 Co-58 4.36E-01 9.22E-01 H-3 1.64E-01 3.46E-01 Ce- 144 6.44E-02 1.36E-01 Others* 1.58E-01 3.34E-01

  • Others include Co-57, Zr-95, Nb-95, Pu-241, Sn-i 13, Ni-59, Ag-i 10m, Zn-65, Tc-99, Cm-242, Pu-238, Cm-243, Fe-59, Cr-51, Pu-239, Am-241, Sr-89, Ru-103, Sn-117m Total Curie Quantity and Principle Radionuclides were determined by estimate.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/1 1-0027 Page 31 of 39

2. Estimate of major nuclide composition (by type of waste)

N/A

3. Irradiated Fuel Shipments Number of Shipments: 0 Mode of Transportation N/A Destination N/A
4. Solid Waste Number of Shipments: 0 Mode of Transportation N/A Destination N/A

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/1 1-0027 Page 32 of 39 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 Installations indicate 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 release, for the period January 1, 2011, through December 31, 2011.

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 G 4.86 6.59 8.01 42.54 20.80 9.21 7.99

2. Wind Speed 11 Meter Average Speed (mph) 4.89 Percent Calm 3.79 Percent Less than 3.5 mph 35.19 (excludes calm)
3. Wind Direction 11 Meter Prevailing S Percent Occurrence 10.4

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/1 1-0027 Page 33 of 39 TABLE VII-A JOINT OCCURRENCE FREQUENCIES FOR LOWNDDEG AND LOWNDSPD - GROUND CONTINUOUS RELEASES JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS A UMAX (M/S) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 0.36 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 1.56 0.000 0.011 0.000 0.000 0.011 0.011 0.011 0.011 0.011 0.000 0.000 0.011 0.000 0.011 0.000 0.000 0.092 3.35 0.023 .0.034 0.103 0.126 0.103 0.183 0.206 0.115 0.160 0.298 0.562 0.481 0.218 0.046 0.046 0.011 2.717 5.59 0.011 0.000 0.000 0.000 0.000 0.023 0.011 0.023 0.252 0.436 0.378 0.252 0.126 0.138 0.160 0.023 1.834 8.27 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.034 0.046 0.034 0.034 0.011 0.034 0.011 0.000 0.206 10.95 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.011 0.000 0.000 0.000 0.000 0.000 0.000 0.011 15.65 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 0.03 0.05 0.10 0.13 0.11 0.22 0.23 0.15 0.46 0.79 0.97 0.78 0.36 0.23 0.22 0.03 4.86%

Joint FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS B UMAX (M/S) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 0.36 0.000 0.001 0.001 0.001 0.001 0.003 0.004 0.002 0.003 0.002 0.003 0.002 0.000 0.000 0.001 0.001 0.023 1.56 0.000 0.023 0.011 0.023 0.023 0.057 0.092 0.034 0.057 0.046 0.069 0.046 0.000 0.000 0.011 0.011 0.504 3.35 0.195 0.195 0.287 0.252 0.298 0.287 0.275 0.287 0.229 0.447 0.539 0.413 0.298 0.092 0.057 0.011 4.161 5.59 0.126 0.034 0.011 0.000 0.000 0.000 0.011 0.011 0.183 0.287 0.287 0.183 0.103 0.160 0.126 0.126 1.651 8.27 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.023 0.034 0.046 0.023 0.011 0.057 0.046 0.000 0.241 10.95 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.011 0.000 0.000 0.000 0.000 0.000 0.000 0.011 15.65 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 0.32 0.25 0.31 0.28 0.32 0.35 0.38 0.33 0.50 0.83 0.94 0.67 0.41 0.31 0.24 0.15 6.59%

JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS C UMAX (M/S) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 0.36 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 1.56 0.034 0.057 0.115 0.172 0.115 0.160 0.057 0.034 0.069 0.046 0.115 0.057 0.034 0.011 0.023 0.011 1.112 3.35 0.619 0.504 0.504 0.355 0.218 0.264 0.344 0.252 0.172 0.367 0.390 0.229 0.229 0.183 0.115 0.092 4.838 5.59 0.218 0.092 0.069 0.034 0.011 0.000 0.046 0.057 0.160 0.195 0.275 0.160 0.092 0,195 0.092 0.160 1.857 8.27 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.011 0.034 0.069 0.011 0.046 0.000 0.011 0.023 0.000 0.206 10.95 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 15.65 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 0.87 0.65 0.69 0.56 0.34 0.42 0.45 0.36 0.44 0.68 0.79 0.49 0.36 0.40 0.25 0.26 8.01%

JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS D UMAX (MIS) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 0.36 0.011 0.022 0.023 0.023 0.021 0.019 0.014 0.014 0.014 0.015 0.013 0.012 0.010 0.008 0.005 0.006 0.229 1.56 0.413 0.837 0.906 0.906 0.814 0.722 0.539 0.550 0.539 0.573 0.516 0.459 0.378 0.310 0.195 0.229 8.885 3.35 2.614 4.127 1.937 1.525 0.848 0.527 0.883 2.625 1.995 1.949 1.674 0.997 0.653 0.493 0.447 0.688 23.983 5.59 1.410 1.066 0.092 0.023 0.023 0.023 0.252 0.642 1.433 0.848 0.539 0.539 0.241 0.287 0.183 0.631 8.231 8.27 0.092 0.011 0.000 0.000 0.000 0.000 0.057 0.195 0.287 0.160 0.057 0.057 0.000 0.023 0.103 0.138 1.181 10.95 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.011 0.023 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.034 15.65 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 4.54 6.06 2.96 2.48 1.71 1.29 1.74 4.04 4.29 3.55 2.80 2.06 1.28 1.12 0.93 1.69 42.54%

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/I 1-0027 Page 34 of 39 TABLE VII-A (Continued) JOINT OCCURRENCE FREQUENCIES FOR LOWNDDEG AND LOWNDSPD - GROUND CONTINUOUS RELEASES JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS E UMAX (M/S) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 0.36 0.015 0.028 0.018 0.012 0.008 0.007 0.018 0.047 0.063 0.080 0.062 0.049 0.030 0.026 0.019 0.022 0.504 1.56 0.298 0.539 0.344 0.241 0.160 0.126 0.355 0.906 1.227 1.548 1.204 0.940 0.573 0.493 0.367 0.424 9.744 3.35 0.436 0.160 0.160 0.023 0.080 0.034 0.034 1.089 1.525 1.250 0.963 0.516 0.642 0.470 0.562 1.422 9.366 5.59 0.011 0.000 0.000 0.000 0.000 0.000 0.000 0.069 0.275 0.103 0.103 0.046 0.069 0.011 0.057 0.413 1.158 8.27 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.011 0.000 0.000 0.000 0.000 0.000 0.000 0.011 0.023 10.95 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 15.65 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 0.76 0.73 0.52 0.28 0.25 0.17 0.41 2.11 3.10 2.98 2.33 1.55 1.31 1.00 1.00 2.29 20.80%

JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS F UMAX (M/S) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 0.36 0.055 0.026 0.009 0.005 0.000 0.002 0.024 0.109 0.115 0.095 0.098 0.088 0.067 0.044 0.078 0.102 0.917 1.56 0.344 0.160 0.057 0.034 0.000 0.011 0.149 0.688 0.722 0.596 0.619 0.550 0.424 0.275 0.493 0.642 5.766 3.35 0.069 0.000 0.011 0.000 0.000 0.000 0.011 0.115 0.069 0.183 0.310 0.092 0.069 0.103 0.344 1.101 2.476 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 0.011 0.011 0.023 0.046 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 10.95 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 15.65 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 0.47 0.19 0.08 0.04 0.00 0.01 0.18 0.91 0.91 0.87 1.03 0.73 0.56 0.43 0.93 1.87 9.21%

JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS G UMAX (M/S) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 0.36 0.092 0.005 0.000 0.005 0.009 0.014 0.046 0.207 0.216 0.170 0.156 0.179 0.129 0.170 0.353 0.372 2.121 1.56 0.229 0.011 0.000 0.011 0.023 0.034 0.115 0.516 0.539 0.424 0.390 0.447 0.321 0.424 0.883 0.929 5.296 3.35 0.023 0.000 0.000 0.000 0.000 0.000 0.000 0.011 0.000 0.000 0.000 0.046 0.023 0.000 0.183 0.287 0.573 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 10.95 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 15.65 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 0.34 0.02 0.00 0.02 0.03 0.05 0.16 0.73 0.75 0.59 0.55 0.67 0.47 0.59 1.42 1.59 7.99%

TOTAL HOURS IN YEAR: 8760 TOTAL HOURS MISSING: 37 TOTAL HOURS CONSIDERED: 8723 TOTAL CALM HOURS: 331

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/12-0040 Page 35 of 39 ADDENDUM 1 CHANGES TO ODCM, PCP, AND RADIOACTIVE WASTE SYSTEMS TABLE OF CONTENTS D escrip tion ............................................................................................................................................. P ag e I. Changes to the Offsite Dose Calculation Manual (ODCM) ...................................................... 36 II. Changes to the Radioactive Waste Systems ............................................................................. 36 ii1. Changes to the Process Control Program (PCP) ...................................................................... 36 IV. Changes to the Land Use Census .............................................................................................. 36 V. Instrum ent Inoperability ........................................................................................................... 37 VI. Liquid Holdup Tank Curie Limit .............................................................................................. 37 VII. Waste Gas Decay Tank Curie Limit ......................................................................................... 37 VIII. Missed Compensatory Samples ................................................................................................ 37 IX. Special Ground Water Protection Requirements ...................................................................... 37 X. M issed O D CM Sam ples ............................................................................................................ 37

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/12-0040 Page 36 of 39 I. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)

There was one revision to the ODCM during this reporting period. Summaries of the revision are shown below. A complete copy of the updated ODCM is being submitted in a separate letter.

ODCM, Revision 33 Description of Changes

1) Page 2-4, Section 2.1.2 was revised to add guidance for the use of Cs-134 as a default radionuclide when no gamma emitting nuclides are present.
2) Page 2-27, Table 2.6-1, item 4.d was revised to delete minimum channel operable (MCO) requirements for outside temporary tanks.
3) Page 2-30 was revised by deleting Note 2 from Table 2.6-1 which defines an outside temporary tank.
4) Pages 3-102 through 3-107, Section 3.16 has been added detailing the methodology for the calculation of gaseous dose from C- 14.

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

III. 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 currently performed every 12 months and was last performed in 2011.

The results of the 2011 Land Use Census and average meteorological data for the last 10 years identified no changes that required an ODCM change. The next Land Use Census will be performed in 2012.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/12-0040 Page 37 of 39 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.

VIII. MISSED COMPENSATORY SAMPLES There were no instances of missed compensatory samples during this reporting period.

IX. SPECIAL GROUND WATER PROTECTION REQUIREMENTS There were no dose calculations performed or special reports made as a result of any spills or leaks during this period.

Additional groundwater monitoring wells were sampled and analyzed during 2011 as part of the NEI Groundwater Protection Initiative. There were a total of seventeen wells monitored, fifteen of which are described in the ODCM and will be addressed in the Annual Radiological Environmental Operating Report. For the two wells not in the ODCM program, no plant related gamma activity was detected. Low level tritium activity was found in the wells. The following are the tritium results from the two additional wells:

Groundwater Tritium - 2011 pCi/L Well ID 1st Quarter 2 nd Quarter 3 rd Quarter 4t Quarter PDW-05 345 320 396 395 TS-07B 294 263 463 372 X. MISSED ODCM SAMPLES There were no failures to meet the ODCM specified sample frequencies or analyses during this reporting period.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/12-0040 Page 38 of 39 ADDENDUM 2 CORRECTIONS TO PREVIOUS REPORTS TABLE OF CONTENTS Description Page I. D IS CU S S ION ........................................................................................................................ 39

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/12-0040 Page 39 of 39

1. DISCUSSION There is one correction to the previous 2010 report letter 11-0027, dated April 26, 2011. Page 20 of 40, which contained the continued Table IV -A ,EFFLUENT AND WASTE DISPOSAL Annual Report -2009 should be 2010. A copy of the corrected page is attached.

United States Nuclear regulatory Commission Attaclhnent to Serial: RNP-RA/1 1-0027 Page 20 of 40 TABLE IV-A (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT - 2010 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES t Quarter Qi Quarter Est. Total Unit3 4 1Error %

A. Fission and Activation Products

i. Total release (not including tritium, gases, alpha)
2. Average diluted concentration during period B. Tritium I. Total release Ci 7.83E+00 8.31E+01 9.20E+00
2. Average diluted concentration during C/l 3 period i 3.07E-08 3.15E-07 C. Dissolved and entrained gases
1. Total release Ci 1.22E-04 2.23E-03 9.60E+00
2. Average diluted concentration [Ci/ml 4.78E-13 8.46E-12 during period t i 4 1 .
3. Percent of applicable limit  % 2.39E-07 4.23E-06 D. Gross alpha radioactivity I. Total release Ci ND ND 1.83E+01 E. Volume of waste released prior to dilution Liters 5.73E+05 5.68E+05 F. Volume of dilution water used during Liters 2.55E+1 I 2.64E+1 I period G. Percent of 10 CFR 50, Appendix I
1. Quarterly Limit Organ: Liver, GI-LLIl  % 5.23E-05 4.59E-04 Total body  % 1.49E-04 1.48E-03
2. Annual Limit*

Organ:, GI-LLI  % 1.44E-03 1.66E-03 Total body  % 3.01E-03 3.75E-03 Liver for Quarter 3 & GI-LLI, gastrointestinal-lower large intestine for Quarter 4 Cumulative total for the year-to-date using the methodology in the ODCM.

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