ML101241051

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Enclosure 1, BSEP 10-0060, Radioactive Effluent Release Report for 2009
ML101241051
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 12/31/2009
From:
Progress Energy Carolinas
To:
Office of Nuclear Reactor Regulation
References
BSEP 10-0060
Download: ML101241051 (42)
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Text

Enclosure 1 BSEP 10-0060 Radioactive Effluent Release Report for 2009

Brunswick Steam Electric Plant Radioactive Effluent Release Report January 1 through December 31, 2009 Table of Contents Attachment Pages

1. Effluent and Waste Disposal Report Supplemental 2- 14 Information
2. Effluent and Waste Disposal Data 15 -29
3. Environmental Monitoring Program 30-32
4. Effluent Instrumentation 33-36
5. Major Modification to the Radioactive Waste Treatment 37 Systems
6. Meteorological Data 38
7. Annual Dose Assessment 39
8. Off-Site Dose Calculation Manual (ODCM) and Process 40 Control Program (PCP) Revisions Page 1 of 40

Attachment 1 Effluent and Waste Disposal Report Supplemental Information Facility: Brunswick Steam Electric Plant Licensee: Carolina Power & Light Company, now doing business as Progress Energy Carolinas, Inc.

1. Regulatory Limits A. Fission and activation gases (ODCM 7.3.8)

(1) Calendar Quarterl (a) < 10 mrad gamma (b) < 20 mrad beta (2) Calendar Year (a) < 20 mrad gamma (b) < 40 mrad beta B. Iodine- 131, iodine-133, tritium, and particulates with half-lives greater than eight days (ODCMS 7.3.9)

(1) Calendar Quarter' (a) < 15 mrem to any organ (2) Calendar Year (a) < 30 mrem to any organ C. Liquid Effluents (ODCMS 7.3.4)

(1) Calendar Quarter2 (a) < 3 mrem to total body (b) < 10 mrem to any organ (2) Calendar Year (a) < 6 mrem to total body (b) *20 mrem to any organ

2. Maximum permissible concentration and dose rates which determine maximum instantaneous release rates.

A. Fission and activation gases (ODCMS 7.3.7.a)

(1) < 500 mrem/year to total body (2) < 3000 mrem/year to the skin B. Iodine- 131, iodine- 133, tritium, and particulates with half-lives greater than eight days (ODCMS 7.3.7.b)

(1) < 1500 mrem/year to any organ NOTE: Dose calculations are determined in accordance with the ODCM

'Used for percent of ODCMS limit determination in Attachment 2, Table 1A 2Used for percent of ODCMS limit determination in Attachment 2, Table 2A Page 2 of 40

Attachment 1 Effluent and Waste Disposal Report Supplemental Information C. Liquid effluents (ODCMS 7.3.3)

The concentration of radioactive material released in liquid effluents to unrestricted areas after dilution in the discharge canal shall be limited to 10 times the concentrations specified in Appendix B, Table 2, Column 2 to 10 CFR 20.1001 - 20.2401 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to the value given in the ODCM specifications.

(1) Tritium: limit = 1.00E-03 lICi/ml '

(2) Dissolved and entrained noble gases: limit = 2.OOE-04 [tCi/ml 3

3. Measurements and Approximations of Total Radioactivity A. Fission and activation gases Analyses for specific radionuclides in representative grab samples by gamma spectroscopy.

B. Iodines Analysis for specific radionuclides collected on charcoal cartridges by gamma spectroscopy.

C. Particulates Analysis for specific radionuclides collected on filter papers by gamma spectroscopy.

D. Liquid Effluents Analysis for specific radionuclides of individual releases by gamma spectroscopy.

3 Used as applicable limits for Attachment 2, Table 2A Nuclear counting statistics are reported utilizing 1-sigma error. Total error where reported represents a best effort to approximate the total of all individual and sampling errors.

Page 3 of 40

Attachment 1 Effluent and Waste Disposal Report Supplemental Information

4. Batch Releases A. Liquid (1) Number of batch releases: 2.62E+02 (2) Total time period for batch releases: 3.61E+04 Minutes (3) Maximum time period for a batch release: 2.37E+02 Minutes (4) Average time period for a batch release: 1.38E+02 Minutes (5) Minimum time period for a batch release: 1.30E+01 Minutes (6) Average stream flow during periods of release of effluent into a flowing stream: 8.05E+05 Gallons per Minute B. Gaseous (1) Number of batch releases: O.OOE+00 (2) Total time period for batch releases: O.OOE+00 Minutes (3) Maximum time period for a batch release: O.OOE+00 Minutes (4) Average time period for a batch release: O.OOE+00 Minutes (5) Minimum time period for a batch release: O.OOE+00 Minutes 4
5. Abnormal Releases A. Liquid (1) Number of releases: 0.OOE+00 (2) Total activity released: 0.OOE+00 Curies B. Gaseous (1) Number of releases: 0.OOE+00 (2) Total activity released: 0.OOE+00 Curies There were no abnormal releases that exceeded 10 CFR 20'or 10 CFR 50 limits. See pages 5-6 for a discussion of release events that occurred.

Page 4 of 40

Attachment 1 Effluent and Waste Disposal Report Supplemental Information Tritium levels in excess of Nuclear Energy Institute (NEI) voluntary reporting criteria were confirmed to be present in onsite shallow groundwater wells on June 13, 2007. The NRC was notified, reference Event Number 43420. Immediate corrective actions were taken to perform additional sampling of areas surrounding the Storm Drain Stabilization Pond (SDSP) and to reconfigure the Turbine Building HVAC airwash system. The reconfiguration of the turbine building airwash system was done to eliminate the designed pathway of tritiated water to the Storm Drain Collection Basin (SDCB) and the SDSP. Additional corrective actions included installing monitoring wells at various locations to determine groundwater flow and checking for the presence of tritium in surrounding groundwater. There has been no indication that tritium has migrated offsite to drinking water supplies. The SDSP is also contributing to the offsite dose via the airborne pathway due to evaporation. Increased sampling of the SDSP has been instituted and monthly calculations of the airborne release are being performed. In addition, tritium has been found in the onsite tidally influenced marsh area near the SDSP. These release points are discussed in more detail below and include the associated dose to the public.

Discussion of releases from the Storm Drain Collector Basin Due to heavy rain events and maintenance, the SDCB was released directly to the discharge canal on twelve occasions in 2009. The SDCB is a permitted release point during periods of inclement weather to protect plant personnel and equipment. Approximately 1.80E+06 gallons containing 5.71E-02 curies of tritium and 8.79E-05 curies of Co-60 were released. This resulted in an estimated maximum organ dose to the individual's GI-Tract of 1.50E-05 mrem and a Total Body dose of 1.83E-06 mrem. The volume released was not included in the average diluted concentration determination or in the volume of waste released on Attachment 2, Table 2A. The tritium and Co-60 released was included in the quarterly summary on Attachment 2, Table 2A and the dose is included in the Annual Dose Summary, Attachment 7.

Discussion of releases from the Storm Drain Stabilization Pond Approximately 5.26E+07 gallons containing 4.25E+00 curies of tritium were released from the SDSP to the intake canal during this reporting period. This resulted in an estimated maximum dose to the individual of 7.37E-06 mrem. The SDSP is a permitted release point. The volume released was not included in the average diluted concentration determination or in the volume of waste released on Attachment 2, Table 2A. The tritium released is included in the quarterly summary on Attachment 2, Table 2A and the dose is included in the Annual Dose Summary, .

Discussion of water evaporation from the Storm Drain Stabilization Pond There was 4.54E+07 gallons of tritiated water released via evaporation from the SDSP in 2009.

This yields 3.89E+00 curies of tritium released to the atmosphere as a ground release. The nearest resident to the pond is in the northwest sector at approximately 0.3 miles. The maximum exposed individuals at that location received a calculated dose of 1.19E-03 mrem via the inhalation pathway in 2009. Only inhalation dose was determined because the exposed individuals do not have a garden and also do not have any milk or meat animals at this location.

The curies of tritium released from the SDSP evaporation are included in Attachment 2, Table IA. The dose is included in the Annual Dose Summary, Attachment 7.

Page 5 of 40

Attachment 1 Effluent and Waste Disposal Report Supplemental Information Discussion of releases from the Marsh to Nancy's Creek Samples are routinely analyzed from the marsh areas that drain into Nancy's Creek during falling tides. The marsh areas are all on company owned property. The marsh land is under the influence of high and low tides and releases to Nancy's Creek, which is offsite. This constitutes a release point for evaluation (curies released, volume, offsite dose impact, etc). The sampling program consists of weekly sampling and analysis at eight locations.

All gamma analyses performed in 2009 were less than the Lower Limit of Detection (LLD).

There were 416 tritium analyses performed, which resulted in 157 positive tritium results. The minimum concentration detected from the 157 positive results was 2.33E-07 [tCi/ml and the maximum concentration was 4.24E-05 ptCi/ml. Using the average concentration of 1.49E-06 ptCi/ml, two high tides per day, the area of the marsh at high tide, 365 days, and a conservative factor of 2, it is calculated that 5.37E+07 gallons were released to Nancy's Creek containing 3.02E-01 curies of tritium. This yielded a Total Body dose of 2.90E-03 mrem to an adult from eating fish and 7.13E-04 mrem from eating invertebrate (shrimp, crabs, etc.) for a total dose of 3.61E-03 mrem. The curies released are included in Attachment 2, Table 2A and the dose is included in the Annual Dose Summary, Attachment 7.

Discussion of release from Pipe Outfall at Well ESS-24 Water was found leaking from a pipe near Well ESS-24 into the intake canal on December 29, 2008. The pipe was grouted and the release was secured on February 18, 2009. Samples were obtained for tritium analysis and the maximum tritium activity was 3.67E-05 pCi/ml. Using the maximum flow rate of 1,500 ml/min, it is calculated that 2.80E+04 gallons were released containing 3.89E-03 curies of tritium in 2009. This resulted in an estimated maximum dose to the individual of 5.83E-09 mrem. The curies released are included in Attachment 2, Table 2A and the dose is included in the Annual Dose Summary, Attachment 7.

Discussion of Ground Water Monitoring The BSEP ground water sampling and analysis program has grown into a significant surveillance program over the past few years. Wells have been installed around the SDSP, in the Protected Area (PA), and throughout the Owner Controlled Area (OCA). By the end of 2009 the ground water program included approximately 117 monitoring wells. Forty of these wells are listed in the ODCM and are addressed in the Radiological Environmental Monitoring Report (REMP).

The monitoring wells that are not covered in the ODCM will be discussed below. These wells consist of shallow and intermediate wells in different locations around the OCA and PA and are used to evaluate ground water movement. Several gamma analyses were performed and all results were less than LLD. Below are the tritium results and maps showing the well location for the wells that are not included in the ODCM:

Page 6 of 40

Attachment 1 Effluent and Waste Disposal Report Supplemental Information Shallow Wells for Plant Site Number Number of Average Minimum Maximum Depth of of Positive Pos Act Pos Act Pos Act Well Name Samples Samples in (pCi/L) (pCi/L) (pCi/L) Well (ft) in 2009 2009 ESS-3C 12 11 8.52E+02 3.34E+02 1.70E+03 14 ESS-5C 1 0 < LLD < LLD < LLD 17 ESS-2D 1 0 < LLD < LLD < LLD 15 ESS-12C 9 5 3.27E+02 2.44E+02 4.28E+02 15 ESS-14 1 0 < LLD < LLD < LLD 22 ESS-15C 1 0 < LLD < LLD < LLD 15 ESS-32C 1 0 < LLD < LLD < LLD 35 ESS-33C 1 0 < LLD < LLD < LLD 25 ESS-34C 1 0 < LLD < LLD < LLD 22 ESS-35C 1 0 < LLD < LLD < LLD 20 ESS-36C 1 0 < LLD < LLD < LLD 22 ESS-37C 1 0 < LLD < LLD < LLD 30 ESS-38C 7 1 5.17E+02 5.17E+02 5.17E+02 15 ESS-39C 7 0 < LLD < LLD < LLD 20 ESS-40C 1 0 < LLD < LLD < LLD 30 ESS-41C 1 0 < LLD < LLD < LLD 27 ESS-42C 1 0 < LLD < LLD < LLD 30 ESS-43C 1 0 < LLD < LLD < LLD 17 ESS-44C 1 0 < LLD < LLD < LLD 14 ESS-45C 1 0 < LLD < LLD < LLD 21 ESS-46C 1 0 < LLD < LLD < LLD 18 Page 7 of 40

Attachment 1 Effluent and Waste Disposal Report Supplemental Information Shallow Wells for Plant Site Number Numbrof Number Positiveof Average Minimum Maximum Depth of Well Name ofms Smpoesite Pos Act Pos Act Pos Act Well (fi)

Samples Samples in (pCi/L) (pCi/L) (pCi/L) in 2009 2009 ESS-47C 1 0 < LLD < LLD < LLD 20 ESS-48C 1 0 < LLD < LLD < LLD 18 ESS-49C 1 0 < LLD < LLD < LLD 19 ESS-50C 1 0 < LLD < LLD < LLD 22 ESS-51C 2 0 < LLD < LLD < LLD 22 ESS-54C 1 0 < LLD < LLD < LLD 24 ESS-55C 1 0 < LLD < LLD < LLD 38 ESS-56C 1 0 < LLD < LLD < LLD 32 ESS-57C 1 0 < LLD < LLD < LLD 30 ESS-58C 1 0 < LLD < LLD < LLD 19 ESS-59C 1 0 < LLD < LLD < LLD 18 ESS-60C 1 0 < LLD < LLD < LLD 19 ESS-61C 1 0 < LLD < LLD < LLD 28 ESS-62C 1 0 < LLD < LLD < LLD 20 ESS-63C 1 0 < LLD < LLD < LLD 29 ESS-64C 1 0 < LLD. < LLD < LLD 21 ESS-65C 1 0 < LLD < LLD < LLD 15 ESS-66C 1 0 < LLD < LLD < LLD 20 ESS-67C 13 6 3.97E+02 2.68E+02 4.90E+02 25 ESS-68C 1 0 < LLD < LLD < LLD 19 ESS-69C 1 0 < LLD < LLD < LLD 30 Page 8 of 40

Attachment 1 Effluent and Waste Disposal Report Supplemental Information Shallow Wells for Plant Site Number Number of Nube Numbtiero Average Minimum Maximum Depth of Well Name of SvplagnPos Positive Act Pos Act Pos Act Well (ft)

Samples Samples in (pCi/L) (pCi/L) (pCi/L) in 2009 2009 ESS-70C 1 0 < LLD < LLD < LLD 19 ESS-71C 1 0 < LLD < LLD < LLD 19 ESS-72C 1 0 < LLD .< LLD < LLD 18 ESS-73C 13 1 2.62E+02 2.62E+02 2.62E+02 15 ESS-74C 1 0 < LLD < LLD < LLD 20 ESS-STAB 12 12 4.91E+04 3.38E+04 6.58E+04 31 ESS-MW-1 9 7 3.96E+02 2.48E+02 6.78E+02 24 MWPA-100C 5 3 3.56E+02 2.54E+02 4.44E+02 30 MWPA-101C 5 5 1.34E+03 6.36E+02 3.41E+03 30 MWPA-102C 5 5 4.94E+03 3.49E+03 9.29E+03 30 MWPA-103C 5 0 < LLD < LLD < LLD 30 MWPA-104C 5 5 2.54E+04 1.11E+04 3.45E+04 29 MWPA-105C 5 5 3.62E+03 2.41E+03 4.82E+03 30 MWPA-106C 5 4 5.33E+02 3.68E+02 6.80E+02 29 MWPA-107C 6 6 3.18E+03 1.31E+03 4.62E+03 29 MWPA-108C 5 4 3.53E+02 2.54E+02 4.72E+02 29 MWPA-109C 5 2 4.35E+02 2.87E+02 5.84E+02 29 MWPA- 11OC 5 4 4.04E+02 3.OOE+02 5.69E+02 29 MWPA-111C 5 5 2.73E+04 2.42E+04 3.08E+04 30 MWPA- 112C 5 5 1.00E+04 8.19E+03 1.21E+04 34 MWPA-113C 5 1 4.05E+02 4.05E+02 4.05E+02 25 Page 9 of 40

Attachment 1 Effluent and Waste Disposal Report Supplemental Information Shallow Wells for Plant Site Number Number of Average Minimum Maximum Well Name of Positive Pos Act Pos Act Pos Act Depth of Samples Samples in (pCi/L) (pCi/L) (pCi/L) Well (ft) in 2009 2009 MWPA-114C 5 4 5.12E+02 2.92E+02 6.60E+02 30 MWPA-115C 5 5 2.74E+04 2.49E+04 3.13E+04 34 MWPA-116C 5 5 < LLD < LLD < LLD 30 MWPA- 117C 6 5 1.37E+03 1.05E+03 1.59E+03 30 MWPA-118C 5 1 3.83E+02 3.83E+02 3.83E+02 30 Intermediate Wells for Plant Site Number of Number of Average Minimum Maximum Depth of Well Name Samples in Positive Pos Act Pos Act Pos Act 2009 Samples in (pCi/L) (pCi/L) (pCi/L) Well (ft) 2009 ESS-38B 7 0 < LLD < LLD < LLD 55 ESS-39B 7 2 5.35E+02 4.90E+02 5.79E+02 55 ESS-51B 2 0 < LLD < LLD < LLD 45 ESS-52B 2 0 < LLD < LLD < LLD 51 ESS-53B 2 0 < LLD < LLD < LLD 76 MWPA- 5 5 2.74E+04 2.55E+04 3.09E+04 59 104B MWPA-MWPA- 5 5 2.91E+03 2.38E+03 3.19E+03 59 lllB MWPA- 5 5 5.13E+04 3.72E+04 6.30E+/-04 60 107B MWPA- 5 0 < LLD < LLD < LLD 60 118B Page 10 of 40

Attachment 1 Effluent and Waste Disposal Report Supplemental Information Overview of Plant Site, SDSP, and Nancy's Creek Protected Area Wells Page 11 of 40

Attachment 1 Effluent and Waste Disposal Report Supplemental Information Area One Wells Near Caswell Beach Area 2 Wells Near Intracoastal Waterway Page 12 of 40

Attachment 1 Effluent and Waste Disposal Report Supplemental Information Area 3 and Area 4 Near Plant Area 5, Area 6, and Area 10 Wells in OCA Page 13 of 40

Attachment 1 Effluent and Waste Disposal Report Supplemental Information Area 8 and Area 11 Wells in OCA

- wnII fSS-wK Area 9 Wells in OCA Page 14 of 40

Attachment 2 Effluent and Waste Disposal Data Table 1A Gaseous Effluents - Summation of all Releases Table lB Gaseous Effluents - Elevated Releases Table 1C Gaseous Effluents - Ground Level Releases Table 2A Liquid Effluents - Summation of all Releases Table 2B Liquid Effluents - Batch Mode Lower Limits of Detection Table 3A Solid Waste and Irradiated Fuel Shipments - Waste Class A Table 3B Solid Waste and Irradiated Fuel Shipments - Waste Class B Table 3C Solid Waste and Irradiated Fuel Shipments - Waste Class C Page 15 of 40

Attachment 2 Effluent and Waste Disposal Data Table 1A: Gaseous Effluents - Summation of all Releases A. FISSION AND ACTIVATION GASES Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total release Ci 2.98E+02 1.35E+02 1.39E+02 1.25E+02 4.50E+01
2. Average release rate for period liCi/sec 3.83E+01 1.71E+01 1.75E+01 1.57E+01 NA
3. Percent of ODCM limit %6.07E-01 1.39E-01 1.11E-01 6.77E-02 NA B. IODINES Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error
1. Total Iodine - 131 release Ci 1.72E-02 5.16E-03 1.23E-02 8.15E-03 3.50E+O1
2. Average release rate for period tCi/sec 2.2 1E-03 6.57E-04 1.55E-03 1.03E-03 NA C. PARTICULATES Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error
1. Total release Ci 4.09E-03 1.88E-03 1.92E-03 1.34E-03 3.50E+01
2. Average release rate for period jtCi/sec 5.26E-04 2.39E-04 2.42E-04 1.69E-04 NA
3. Gross Alpha Ci < LLD 2.41E-08 < LLD 1.41E-07 3.50E+01 D. TRITIUM Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error
1. Total release Ci 7.32E+01 5.47E+O1 5.22E+01 5.70E+O1 3.OOE+01
2. Average release rate for period itCi/sec 9.42E+00 6.96E+00 6.57E+00 7.17E+00 NA Page 16 of 40

Attachment 2 Effluent and Waste Disposal Data Table 1A: Gaseous Effluents - Summation of all Releases E. IODINE-131, IODINE-133, TRITIUM AND PARTICULATES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4

1. Total release Ci 7.33E+O1 5.48E+01 5.24E+O1 5.71E+01
2. Average release rate for period jtCi/sec 9.43E+00 6.97E+00 6.59E+00 7.18E+00
3. Percent of ODCM limit  % 1.21E+00 3.11E-01 6.89E-01 4.93E-01 Page 17 of 40

Attachment 2 Effluent and Waste Disposal Data Table IB: Gaseous Effluents - Elevated Releases Continuous Release Nuclides Released

1. FISSION GASES Unit Quarter I Quarter 2 Quarter 3 Quarter 4 argon-41 Ci < LLD 4.83E-02 < LLD < LLD krypton-85m Ci 7.32E-01 1.64E+00 < LLD < LLD krypton-87 Ci 4.72E+00 2.39E+00 < LLD < LLD krypton-88 Ci < LLD 4.14E+00 < LLD <LLD xenon-133 Ci 1.35E+01 2.55E+00 < LLD < LLD xenon-133m Ci < LLD < LLD < LLD < LLD xenon-135 Ci 1.44E+O1 3.3 1E+O1 9.58E+00 9.73E+00 xenon-135m Ci 5.57E+01 1.87E+01 3.59E+01 3.49E+O1 xenon-137 Ci 3.08E+01 4.84E-01 1.O1E+01 < LLD xenon-138 Ci 1.30E+02 5.88E+01 7.62E+O1 6.91E+O1 total for period Ci 2.50E+02 1.22E+02 1.32E+02 1.14E+02
2. GASEOUS IODINES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 iodine-131 Ci 1.08E-02 4.29E-03 1.09E-02 6.65E-03 iodine-132 Ci 5.23E-02 3.17E-02 1.07E-01 5.03E-02 iodine-133 Ci 7.87E-02 3.78E-02 1.09E-01 5.85E-02 iodine-134 Ci 1.17E-01 6.13E-02 2.58E-01 1.01E-01 iodine-135 Ci, 1.20E-01 6.04E-02 1.89E-01 9.48E-02 total for period Ci 3.79E-0I 1.95E-01 6.73E-01 3.11E-01
3. PARTICULATES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 chromium-51 Ci < LLD < LLD < LLD < LLD.

manganese-54 Ci < LLD < LLD < LLD < LLD cobalt-58 Ci < LLD 3.03E-06 < LLD < LLD cobalt-60 Ci 7.50E-06 2.60E-05 4.40E-06 3.49E-06 zinc-65 Ci < LLD < LLD < LLD < LLD strontium-89 Ci 7.23E-05 1.89E-04 2.65E-05 1.47E-04 strontium-90 Ci 4.40E-07 1.12E-06 3.85E-07 7.OOE-07 niobium-95 Ci < LLD < LLD < LLD < LLD cesium-134 Ci < LLD < LLD < LLD < LLD cesium-137 Ci < LLD 1.56E-06 < LLD < LLD barium-140 Ci 5.39E-04 4.59E-04 6.54E-04 3.56E-04 lanthanum-140 Ci 9.29E-04 8.19E-04 1.20E-03 6.19E-04 total for period Ci 1.55E-03 1.50E-03 1.88E-03 1.13E-03

4. TRITIUM Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 hydrogen-3 Ci 1.95E+01 1.81E+01 2.56E+01 2.05E+01 Page 18 of 40

Attachment 2 Effluent and Wastet Disposal Data Table 1C: Gaseous Effluents - Ground Level Releases Continuous Release Nuclides Released

1. FISSION GASES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 krypton-85m Ci < LLD < LLD < LLD < LLD krypton-87 Ci < LLD < LLD < LLD < LLD krypton-88 Ci < LLD < LLD < LLD < LLD xenon- 133 Ci 3.57E+00 6.71E+00 5.72E-01 5.48E-01 xenon- 135 Ci 5.52E+00 3.02E-01 3.24E+00 1.1 OE+0 1 xenon- 135 m Ci 1.24E+01 < LLD < LLD < LLD xenon- 137 Ci < LLD < LLD < LLD < LLD xenon- 138 Ci 2.59E+01 6.01E+00 3.79E+00 < LLD total for period Ci 4.75E+01 1.30E+01 7.60E+00 1.15E+01
2. GASEOUS IODINES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 iodine- 13 1 Ci 6.39E-03 8.7 1E-04 1.45E-03 1.50E-03 iodine- 132 Ci 2.08E-02 8.90E-03 1.74E-02 1.94E-02 iodine- 133 Ci 2.50E-02 8.18E-03 1.43E-02 1.50E-02 iodine-134 Ci 4.38E-02 1.07E-02 4.37E-02 4.52E-02 iodine-135 Ci 3.70E-02 9.43E-03 2.86E-02 2.53E-02 total for period Ci 1.33E-01 3.81 E-02 1.05E-01 1.06E-01
3. PARTICULATES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 chromium-51 Ci 2.70E-05 1.57E-05 5.44E-06 1.72E-05 manganese-54 Ci 2.57E-06 5.28E-06 < LLD < LLD cobalt-58 Ci 1.38E-05 6.06E-06 8.19E-06 3.84E-05 cobalt-60 Ci *,1.68E-04 1.26E-04 1.82E-05 4.29E-05 zinc-65 Ci 2.96E-06 < LLD < LLD < LLD strontium-89 Ci 2.98E-04 7.66E-05 5.40E-06 7.91E-05 strontium-90 Ci 1.51E-06 4.98E-07 < LLD 6.47E-07 cesium- 134 Ci < LLD < LLD < LLD < LLD cesium-137 Ci 1.60E-07 1.48E-06 < LLD < LLD barium-140 Ci 6.90E-04 6.11E-05 < LLD 1.38E-05 lanthanum- 140 Ci 1.34E-03 8.50E-05 < LLD 2.49E-05 cerium-141 Ci 1.59E-09 < LLD < LLD < LLD total for period Ci 2.54E-03 3.78E-04 3.72E-05 2.17E-04
4. TRITIUM Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 hydrogen-3 Ci 5.28E+01 3.50E+01 2.57E+01 3.61E+01 Page 19 of 40

Attachment 2 Effluent and Waste Disposal Data Table 2A: Liquid Effluents - Summation of all Releases A. FISSION AND ACTIVATION PRODUCTS (NOTE 1)

Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total release Ci 8.24E-04 7.20E-03 2.79E-03 8.14E-04 4.OOE+01 (excluding tritium, gases, and alpha)
2. Average diluted concentration [LCi/ml 6.50E-11 2.OOE-10 7.88E-1 1 3.16E-11 NA (NOTE 2)
3. Percent of 4.93E-03 1.60E-02 5.20E-03 2.59E-03 applicable limit NA B. TRITIUM (NOTE 1)

Estimated Total Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total release Ci 5.62E+01 6.67E+O1 4.05E+O 1 4.74E+01 4.50E+01
2. Average diluted concentration 4.43E-06 1.85E-06 1.14E-06 1.84E-06 lICi/ml NA (NOTE 2)
3. Percent of applicable limit 4.43E-01 1.85E-01 1.14E-01 1.84E-01 NA C. DISSOLVED AND ENTRAINED GASES (NOTE 1)

Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total release Ci 1.05E-02 1.21E-02 6.16E-03 1.29E-02 4.OOE+01
2. Average diluted concentration 8.29E-10 3.3 6E-O10 .74E-10 5.OOE-1O NA

.tCi/ml (NOTE 2)

3. Percent of applicable limit 4.15E-04 1.68E-04 8.70E-05 2.50E-04 NA D. GROSS ALPHA RADIOACTIVITY Estimated Total Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Percent Error
1. Total release Ci < LLD < LLD < LLD < LLD 4.OOE+01 NOTE 1: Includes radionuclides released via abnormal and/or non-routine releases NOTE 2: Does not include rainwater (i.e. Storm Drain Collector Basin and/or Storm Drain Stabilization Pond)

Page 20 of 40

Attachment 2 Effluent and Waste Disposal Data Table 2A: Liquid Effluents - Summation of all Releases E. VOLUME OF WASTE RELEASED (NOTE 2)

Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total volume liters 2.7 1E+06 5.38E+06 4.64E+06 3.4 1E+06 1.50E+01 F. VOLUME OF DILUTION WATER Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error I. 1.50E+01 Total volume liters 1.27E+10 3.61E+10 3.54E+10 2.58E+10 (used during release for average diluted concentration)

G. VOLUME OF COOLING WATER DISCHARGED FROM PLANT Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total volume liters 3.38E+1l 4.54E+11 5.10E+1I 4.70E+11 1.50E+01 NOTE 1: Includes radionuclides released via abnormal and/or non-routine releases NOTE 2: Does not include rainwater (i.e. Storm Drain Collection Basin and/or Storm Drain Stabilization Pond)

Page 21 of 40

Attachment 2 Effluent and Waste Disposal Data Table 2B: Liquid Effluents - Batch Mode Nuclides Released

1. FISSION AND ACTIVATION PRODUCTS Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 chromium-51 Ci < LLD < LLD < LLD < LLD manganese-54 Ci 1.54E-05 3.16E-04 5.35E-05 4.76E-06 iron-55 Ci < LLD < LLD < LLD < LLD cobalt-58 Ci < LLD 2.41E-04 1.19E-05 < LLD iron-59 Ci < LLD < LLD < LLD < LLD cobalt-60 Ci 3.54E-04 6. 1OE-03 2.1OE-03 4.50E-04 zinc-65 Ci 1.48E-06 2. 1OE-04 4.85E-05 < LLD strontium-89 Ci < LLD < LLD < LLD < LLD strontium-90 Ci < LLD < LLD < LLD < LLD niobium-95 Ci < LLD < LLD < LLD < LLD zirconium-95 Ci < LLD < LLD < LLD < LLD molybdenum-99 Ci < LLD < LLD < LLD < LLD iodine- 131 Ci 3.3 1E-04 7.20E-05 1.76E-04 1.36E-04 iodine-133 Ci 3.53E-05 1.54E-04 3.94E-04 1.4 1E-04 iodine- 135 Ci < LLD < LLD < LLD 3.22E-06 cesium-134 Ci 7.OOE-06 6.56E-06 1.72E-07 3.22E-06 cesium-137 Ci 8.07E-05 1.05E-04 1.15E-05 7.61E-05 barium-140 Ci < LLD < LLD < LLD < LLD lanthanum-140 Ci < LLD < LLD < LLD < LLD cerium- 141 Ci < LLD < LLD < LLD < LLD cerium- 144 Ci < LLD < LLD <LLD < LLD total for period Ci 8.24E&04 7.20E-03 2.79E-03 8.14E-04
2. DISSOLVED AND ENTRAINED GASES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 xenon-133 Ci 1.94E-03 2.08E-03 1.13E-03 2.27E-03 xenon-135 Ci 8.57E-03 1.OOE-02 5.04E-03 1.06E-02 xenon-135m Ci < LLD < LLD <LLD < LLD total for period Ci 1.05E-02 1.2 1E-02 6.16E-03 1.29E-02 Page 22 of 40

Attachment 2 Effluent and Waste Disposal Data Lower Limits of Detection Units: pCi/ml

1. LIQUID RELEASES 2. GASEOUS RELEASES Alpha 2.02E-08 Ar-41 8.26E-09 H-3 2.68E-06 Kr-85m 5.69E-09 H-3 2.43E-07* Kr'-87 2.13E-08 Mn-54 1.65E-08 Kr-88 2.74E-08 Fe-55 1.13E-07 Xe-133 1.78E-08 Co-58 1.35E-08 Xe-133m 4.87E-08 Fe-59 5.10E-08 Xe-135 7.13E-09 Co-60 2.71E-08 Xe-135m 1.05E-07 Zn-65 4.OOE-08 Xe-137 7.44E-07 Sr-89 1.51E-08 Xe 138 2.20E-07 Sr-90 1.17E-08 Mo-99 1.57E-07 1-131 1.30E-08 1-135 6.52E-08 3. IODINES AND PARTICULA TES Cs-134 2.35E-08 Alpha 1.07E-15 Cs-137 1.76E-08 H-3 9.13E-11 Ce-141 2.48E-08 Cr-51 9.74E-13 Ce-144 9.42E-08 Mn-54 5.70E-13 Co-58 6.41E-13 Kr-85 4.74E-06 Fe-59 1.69E-12 Kr-87 3.63E-08 Co-60 2.78E-13 Kr-88. 4.49E-08 Zn-65. 2.98E-12 Xe-133 3.79E-08 Sr-89 2.89E-15 Xe-133m 1.23E-07 Sr-90 8.48E-16 Xe-135 1.49E-08 Mo-99 7.6 1E-12 Xe-135m 6.3 1E-08 1-131 7.21E-13 Xe-138 1.91E-07 Cs-134 8.50E-13 Cs-137 9.60E-13 Ce-141 9.92E-13 Ce-144 4.53E-12 NOTES:
1. The above values represent typical "a priori" LLDs for isotopes where values of "< LLD" are indicated in Tables IA, IB, IC, 2A, and 2B. Also included are isotopes specified in ODCMS 7.3.3 and 7.3.7.
2. Where activity for any nuclide is reported as "< LLD," that nuclide is considered not present and the LLD activity listed is not considered in the summary data.
  • Tritium LLD value for ground water monitoring.

Page 23 of 40

Attachment 2 Effluent and Waste Disposal Data Table 3A: Solid Waste and Irradiated Fuel Shipments - Waste Class A Waste Class A

1. Total volume shipped (cubic meters) 1.21E+03 Total curie quantity (estimated) 6.03E+01
2. Type of Waste Estimated Total Unit Period %Error 3
a. Spent resins, filter, sludges meter 4.81 E+O 1 Curies 5.71E+O1 1.00E+01 3
b. Dry active waste, compacted/non-compacted meter 1.16E+03 Curies 3.22E+00 1.00E+01 3
c. Irradiated components meters O.OOE+00 Curies O.OOE+00 N/A 3
d. Others (describe) meters O.OOE+00 Curies O.OOE+00 N/A
3. Estimate of major radionuclides composition
a. H-3 1.1OE+00 %

Fe-55 2.20E+01 %

Co-60 5.20E+01 %

Ni-63 1.50E+01 %

Cs-134 1.40E+00%

Cs-137 7.80E+00 %

b. Fe-55 1.90E+01 %

Co-60 6.20E+01 %

Ni-63 5.50E+00 %

Cs-137 1.30E+01 %

c. N/A
d. N/A NOTE:

Solid Radioactive Waste listed above was shipped for processing to various waste processing services or directly shipped to a licensed disposal facility.

Page 24 of 40

Attachment 2 Effluent and Waste Disposal Data Table 3A: Solid Waste and Irradiated Fuel Shipments - Waste Class A

4. Cross reference table, waste stream, form, and container type Stream Form Container Type No. of shipments Type A/Type B
a. Resin Dewatered Type A or GDP 1.10 E+01
b. Dry active waste Compacted/ Type A or GDP 2.60E+O1 Non-compacted
c. Irradiated components N/A N/A
d. Others (describe) N/A N/A
5. Shipment Disposition
a. Solid Waste Number of Shipments Mode of Transportation Destination 1.60E+01 Highway Oak Ridge, TN 1.00E+00 Highway Richland, WA 1.1 OE+0 1 Rail Clive, UT 6.OOE+00 Highway Ashford, Al 3.OOE+00 Highway Erwin, TN f
b. Irradiated Fuel Number of Shipments Mode of Transportation Destination 0 N/A N/A Page 25 of 40

Attachment 2 Effluent and Waste Disposal Data Table 3B: Solid Waste and Irradiated Fuel Shipments - Waste Class B Waste Class B

1. Total volume shipped (cubic meters) 2.27E+00 Total curie quantity (estimated) 2.30E+02
2. Type of Waste Estimated Total Unit Period %Error
a. Spent resins, filter, sludges meter 3 2.27E+00 Curies 2.30E+02 1.00E+01 3
b. Dry active waste, compacted/non-compacted meter O.OOE+00 Curies O.OOE+00 N/A 3
c. Irradiated components meters O.OOE+00 Curies O.OOE+00 N/A 3
d. Others (describe) meters O.OOE+00 Curies O.OOE+00 N/A
3. Estimate of maior radionuclides comnosition
a. Mn-54 2.80E+00 %

Fe-55 2.30E+01 %

Co-58 2.40E+00 %

Co-60 6.20E+01 %

Ni-63 9.40E-01 %

Zn-65 6.80E+00 %

Cs-137 7.10E-01 %

b. N/A
c. N/A
d. N/A NOTE:

Solid Radioactive Waste was shipped to a waste processor for processing and then transported for storage pending future disposal by the processor.

Page 26 of 40

Attachment 2 Effluent and Waste Disposal Data Table 3B: Solid Waste and Irradiated Fuel Shipments - Waste Class B

4. Cross reference table, waste stream, form, and container type Stream Form Container Type No. of shipments Type A/Type B
a. Resin & Filters Dewatered Type B 1.00 E+00
b. Dry active waste Compacted/ N/A N/A Non-compacted
c. Irradiated components N/A N/A
d. Others (describe) N/A N/A
5. Shipment Disposition
  • a. Solid Waste Number of Shipments Mode of Transportation Destination 1.00E+00 Highway Erwin, TN
b. Irradiated Fuel Number of Shipments Mode of Transportation Destination 0 N/A N/A Page 27 of 40

Attachment 2 Effluent and Waste Disposal Data Table 3C: Solid Waste and Irradiated Fuel Shipments'- Waste Class C Waste Class C

1. Total volume shipped (cubic meters) O.OOE+O0 Total curie quantity (estimated) O.OOE+00
2. Type of Waste Estimated Total Unit Period %Error
a. Spent resins, filter, sludges meter 3 O.OOE+00 Curies O.OOE+00 N/A
b. Dry active waste, compacted/non-compacted meter3 O.OOE+00 Curies O.OOE+00 N/A 3
c. Irradiated components meters O.OOE+00 Curies O.OOE+00 1.00E+01 3
d. Others (describe) meters O.OOE+00 Curies O.OOE+00 N/A
3. Estimate of major radionuclides composition
a. N/A
b. N/A
c. N/A
d. N/A NOTE:

No Waste Class C material orspent fuel was shipped offsite for storage or disposal during the reporting period.

Page 28 of 40

Attachment 2 Effluent and Waste Disposal Data Table 3C: Solid Waste and Irradiated Fuel Shipments - Waste Class C

4. Cross reference table, waste stream, form, and container type Stream Form Container Type No. of shipments Type A/Type B
a. Resin & Filters Dewatered N/A N/A
b. Dry active waste Compacted/ N/A N/A Non-compacted
c. Irradiated components N/A N/A
d. Others (describe) N/A N/A
5. Shipment Disposition
a. Solid Waste Number of Shipments Mode of Transportation Destination O.OOE+00 N/A N/A
b. Irradiated Fuel Number of Shipments Mode of Transportation Destination O.OOE+00 N/A N/A Page 29 of 40

Attachment 3 Environmental Monitoring Program : Milk and Vegetable Sample Location : Land Use Census Page 30 of 40

Attachment 3 Environmental Monitoring Program Enclosure 1: Milk and Vegetable Sample Location No milk animals are located in the area evaluated by the last Land Use Census, therefore, no milk sampling locations were available during this time period.

Page 31 of 40

Attachment 3 Environmental Monitoring Program Enclosure 2: Land Use Census The 2009 Land Use Census did not identify any locations that are reportable in the Radioactive Effluent Release Report for 2009.

The following is a summary of the nearest resident and garden locations identified within five miles of the plant for each of the 16 meteorological sectors. No milk animals were found within five miles of the plant.

Direction Residence Garden NNE 0.8 miles 0.9 miles NE None None ENE None None E None None ESE 1.4 miles 1.4 miles SE None None SSE 2.1 miles None S 1.1 miles 2.0 miles SSW 1.2 miles 2.0 miles SW 1.1 miles 1.6 miles WSW 1.2 miles 1.2 miles W 0.9 miles 0.9 mile WNW 0.9 miles None NW 0.9 miles 1.0 miles NNW 0.8 miles 0.9 miles N 0.7 miles None Page 32 of 40

Attachment 4 Effluent Instrumentation : Radioactive Liquid Effluent Monitoring Instrumentation : Radioactive Gaseous Effluent Monitoring Instrumentation : Liquid Hold-Up Tank Page 33 of 40

Attachment 4 Effluent Instrumentation Enclosure 1: Radioactive Liquid Effluent Monitoring Instrumentation No Radioactive Liquid Effluent Monitoring Instruments were inoperable for a period of greater than 30 days.

Page 34 of 40

Attachment 4 Effluent Instrumentation Enclosure 2: Radioactive Gaseous Effluent Monitoring Instrumentation No Radioactive Gaseous Effluent Monitoring Instruments were inoperable for a period of greater than 30 days.

Page 35 of 40

Attachment 4 Effluent Instrumentation Enclosure 3: Liquid Hold-Up Tank No Liquid Hold-Up Tank exceeded the 10-Curie limit of ODCMS 7.3.6 during this reporting period.

Page 36 of 40

Attachment 5 Major Modification To The Radioactive Waste Treatment Systems In accordance with ODCMS 7.5.1, major changes to the liquid, gaseous, and solid Radioactive Waste Treatment Systems shall be reported to the NRC as part of the Radioactive Effluent Release Report or as part of the Updated Final Safety Analysis Report (UFSAR) update. Any major modifications to the radioactive waste treatment systems will be submitted with the UFSAR in accordance with 10 CFR 50.71(e). No changes have been made during this reporting period.

Page 37 of 40

Attachment 6 Meteorological Data Per Technical Specification 5.6.3 and ODCMS 7.4.2, the annual summary of meteorological data collected over the calendar year has been retained in a file and is available for NRC review upon request.

Page 38 of 40.

Attachment 7 Annual Dose Assessment Liquid Effluents Critical Age: Adult Controlling location for liquid releases: SW sector at 0.1 miles(')

Supplemental SDSP Marsh(') Pipe Total Dose*

mrem 7.37E-06 3.61E-03 5.83E-09 3.62E-03

  • Reference page 5-6 of Supplemental Information Routine ODCM Supplemental Dose SDCB Total Dose Limit Dose (mrem) (mrem) Supplemental (mrem) (mrem)

Dose (mrem)

GI-LLI 2.37E-03 3.62E-03 1.50E-05 6.OOE-03 2.00E+01 Bone 2.31E-04 0.00E+00 0.00E+00 2.31E-04 2.00E+01 Liver 1.16E-03 3.62E-03 8.75E-07 4.78E-03 2.OOE+01 Lung 3.55E-04 3.62E-03 8.32E-08 3.97E-03 2.00E+01 Total Body 8.61E-04 3.62E-03 1.83E-06 4.48E-03 6.OOE+00 Thyroid 9.17E-04 3.62E-03 8.32E-08 4.54E-03 2.00E+01 Kidney 8.24E-04 3.62E-03 8.32E-08 4.44E-03 2.00E+01 Gaseous Effluents Noble Gas:

Critical Age: Infant Controlling location: ENE sector at 0.7 mile Routine ODCM Dose (mrad) Limit (mrad)

Gamma 9.24E-02 2.OOE+01 Beta 4.74E-02 4.OOE+01 Iodine, Particulates, and Tritium:

Critical Age: Infant Controlling location: NE sector at 4.75 mile, assuming a cow milk pathway(2)

Routine ODCM Dose Supplemental Dose (mrem) (mrem)r 2 ) Total Dose (mrem) Limit (mrem)

Thyroid 4.04E-01 1.19E-03 4.05E-01 3.00E+01 Kidney 6.24E-03 1.19E-03 7.43E-03 3.00E+01 Liver 6.02E-03 1.19E-03 7.21E-03 3.OOE+01 Total Body 5.27E-03 1.19E-03 6.46E-03 3.OOE+0 1 Skin 4.76E-03 1.19E-03 5.95E-03 3.OOE+01 GI-LLI 4.80E-03 1.19E-03 5.99E-03 3.00E+01 Lung 4.75E-03 1.19E-03 5.94E-03 3.00E+01 Bone 1.42E-03 O.OOE+00 1.42E-03 3.00E+01 (1) Dose from the Marsh was calculated based on guidance from Regulatory Guide 1.109 assuming a fish and invertebrate ingestion pathway for an adult.

(2) Gaseous effluent supplemental dose is from the SDSP evaporation. The controlling location for the SDSP evaporation is the NW sector at approximately 0.3 miles assuming inhalation pathway only, since no garden is present. The critical age is a teen. Reference page 5 of supplemental information.

Page 39 of 40

Attachment 8 Off-Site Dose Calculation Manual (ODCM) And Process Control Program (PCP) Revisions The PCP was not revised during the report period.

ODCM Revision 33 was effective on December 18,2009. The ODCM Revision 33 changes are as follows:

1. Revised Condition I of ODCM 7.3.2 to extend the completion time for Function 6 of Table 7.3.2-1 (Main Condenser Air Ejector Noble Gas Radioactivity Monitor) from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 30 days. Additionally, the requirement to perform a compensatory grab sample during the 30 day completion time was added.
2. Table 7.3.2-1, Pages 1-2, under Main Stack Monitoring System and Turbine Building Ventilation Monitoring System Function f. Mid/High Range Sampler Flow Rate Measurement Device, Test Requirement 7.3.2.6, perform Channel Functional Test every 92 days was added.
3. The following typographical errors in the first sentence of the third paragraph of B 7.3.2-1 were corrected:

1(2)-D 12-K60 1A changed to 1(2)-D 12-RM-K60 1A 1(2)-D 12-K601 B changed to 1(2)-D 12-RM-K601 B

4. A typographical error in the last paragraph of B 7.3.2-2 was corrected. 1/2-CAC-AT-264 was corrected to 1/2-CAC-AT-1264.

Page 40 of 40

Enclosure 2 BSEP 10-0060 Offsite Dose Calculation Manual Revision 33

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