ML11126A222

Radioactive Effluent Release Report for January 1 Through December 31, 2010, Enclosure 1 to BSEP 11-0045

ML11126A222
Person / Time
Site:	Brunswick
Issue date:	12/31/2010
From:	Progress Energy Carolinas
To:	Office of Nuclear Reactor Regulation
References
BSEP 11-0045
Download: ML11126A222 (43)

Text

Enclosure 1 BSEP 11-0045 Radioactive Effluent Release Report for 2010

Brunswick Steam Electric Plant Radioactive Effluent Release Report January 1 through December 31, 2010 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 3 3-36

5. Major Modification to the Radioactive Waste Treatment 37 Systems

6. Meteorological Data 38

7. Annual Dose Assessment 39-40

8. Off-Site Dose Calculation Manual (ODCM) and Process 41 Control Program (PCP) Revisions

9. Special Groundwater Protection 42 Page 1 of 42

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 (1) Calendar Quarter (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 Quarter 2 (a) _<3 mrem to total body (b) -5 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 1 Used for percent of ODCMS limit determination in Attachment 2, Table IA 2 Used for percent of ODCMS limit determination in Attachment 2, Table 2A Page 2 of 42

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.OOE-03 ptCi/ml 3 3

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

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

B. lodines 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 42

Attachment 1 Effluent and Waste Disposal Report Supplemental Information

4. Batch Releases A. Liquid (1) Number of batch releases: 3.31 E+02 (2) Total time period for batch releases: 5.3 1E+04 Minutes (3) Maximum time period for a batch release: 3.18E+02 Minutes (4) Average time period for a batch release: 1.61E+02 Minutes (5) Minimum time period for a batch release: 1.40E+01 Minutes (6) Average stream flow during periods of release of effluent into a flowing stream: 8.14E+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

5. Abnormal Releases4 A. Liquid (1) Number of releases: O.OOE+00 (2) Total activity released: O.OOE+00 Curies B. Gaseous (1) Number of releases: O.OOE+00 (2) Total activity released: O.OOE+00 Curies 4 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 42

Attachment 1 Effluent and Waste Disposal Report Supplemental Information Discussion of Carbon-14 in Gaseous Effluents Carbon-14 (C-14), with a half-life of 5730 years, is a naturally occurring isotope of carbon produced by cosmic ray interactions in the atmosphere. The concentration of C- 14 in the atmosphere was increased significantly in the 1950s and 1960s due to nuclear weapons testing.

Commercial nuclear reactors also produce C-14, but in amounts much less than those produced naturally or as a result of weapons testing. Regulatory Guide 1.21 Revision 1 (1974), to which the Brunswick Nuclear Plant (BNP) is committed, did not address C-14. However, since that time analytical methods for determining C-14 have improved and Revision 2 (2009) states that Licensees should evaluate whether C-14 is a principal radionuclide for gaseous effluents.

Improvements in fuel performance have resulted in a decrease in radioactive effluents from BNP to the point that C-14 is now considered a principal radionuclide. In Boiling Water Reactors (BWRs), such as BNP, the gaseous C-14 releases are primarily in the form of carbon dioxide.

The dose contribution of C-14 in liquid radioactive waste is minimal, therefore, evaluation of C-14 in liquid discharges is not required. BNP's Updated Final Safety Analysis Report (UFSAR) states the C-14 release rate from a BWR is approximately 9.50E+00 Ci/yr assuming 80% plant capacity factor. Since BNP has two reactors, the release rate would be 1.90E+01 Ci/yr. This value was scaled to 100% capacity factor using Effective Full Power Days (EFPD) to give a release rate of 2.1E+01 Ci/yr. Based on the 2010 Land Use Census, the critical receptor is located in the south sector at 1.6 miles with a garden. There are no meat or milk pathways within 5 miles. Regulatory Guide 1.109 methodology was used to determine the dose to this critical receptor. The bone dose for 2010 was 2.36E+00 mrem and the total body dose was 4.71E-01 mrem. The curies released are included in Attachment 2, Table 1A and the dose is included in the Annual Dose Summary, Attachment 7.

Discussion of liquid releases from the Storm Drain Collector Basin (SDCB)

During period of heavy rains, the contents of the SDCB may be released to the discharge canal in accordance with regulatory requirements to protect plant personnel and equipment. The SDCB was released directly to the discharge canal on fifteen occasions in 2010 due to heavy rains.

Approximately 4.12E+06 gallons containing 8.87E-02 curies of tritium were released. There was no detectable gamma radioactivity. This resulted in an estimated maximum dose to the individual of 1.35E-07 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 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 liquid releases from the Storm Drain Stabilization Pond (SDSP)

The SDSP collects rainwater and water from miscellaneous low volume drains on plant site.

Treatment consists of sedimentation, evaporation and transpiration. When sufficient water has accumulated in the pond it is released into the intake canal where it is drawn into the plant circulating and service water system and eventually released into the discharge canal. In 2010, approximately 7.01E+07 gallons containing 2.50E+00 curies of tritium were released from the SDSP to the intake canal. There was no detectable gamma radioactivity. This resulted in an estimated maximum dose to the individual of 4.06E-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 Page 5 of 42

Attachment 1 Effluent and Waste Disposal Report Supplemental Information in the quarterly summary on Attachment 2, Table 2A and the dose is included in the Annual Dose Summary, Attachment 7.

Discussion of water evaporation from the Storm Drain Stabilization Pond There was 5.72E+07 gallons of tritiated water released via evaporation from the SDSP in 2010.

This yields 2.67E+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 8.16E-04 mrem via the inhalation pathway in 2010. 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.

Discussion of liquid 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 2010 were less than the Lower Limit of Detection (LLD). There were 416 tritium analyses performed, which resulted in 149 positive tritium results. The minimum concentration detected from the 149 positive results was 2.38E-07 pCi/ml and the maximum concentration was 2.28E-05 [tCi/ml. Using the average concentration of 1.15E-06 jtCi/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 2.35E-01 curies of tritium. This yielded a Total Body dose of 2.25E-03 mrem to an adult from eating fish and 5.54E-04 mrem from eating invertebrate (shrimp, crabs, etc.) for a total dose of 2.80E-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 liquid release from Pipe Outfall On September 27, 2010 at 15:01, during a heavy rain event, a bladder plug in storm drain piping near the Storm Drain Stabilization Pond failed allowing water containing tritium to be released into the intake canal. The water was sampled at the time of discovery and contained 1.42E-06 pCi/ml of tritium. There was no detectable gamma radioactivity. Using a flow rate of 1.22 cfs, it is calculated that 6.05E+05 gallons were released containing 3.24E-03 curies of tritium in 2010. This resulted in an estimated maximum dose to the individual of 3.86E-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 Groundwater Monitoring The BSEP groundwater 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). Forty 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 Page 6 of 42

Attachment 1 Effluent and Waste Disposal Report Supplemental Information used to evaluate groundwater 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:

Shallow Wells for Plant Site Number Number of Average Minimum Maximum Depth of Well Name of Positive Pos Act Pos Act Pos Act Samples Samples in (pCi/L) (pCi/L) (pCi/L) Well (ft) in 2010 2010 ESS-3C 8 7 4.24E+02 3.42E+02 5.27E+02 14 ESS-12C 5 2 3.22E+02 2.43E+02 4.02E+02 15 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 4 1 2.96E+02 2.96E+02 2.96E+02 15 ESS-39C 4 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 42

Attachment 1 Effluent and Waste Disposal Report Supplemental Information Shallow Wells for Plant Site Number Number of Average Minimum Maximum of Positive Pos Act Pos Act Pos Act Depth of Well Name Samples Samples in (pCi/L) (pCi/L) (pCi/L) Well (ft) in 2010 2010 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 2 0 < LLD < LLD < LLD 32 ESS-57C 2 0 < LLD < LLD < LLD 30 ESS-58C 1 0 < LLD < LLD < LLD 19 ESS-59C 1 0 < LLD < LLD < LLD 18 ESS-60C 2 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 12 0 < LLD < LLD < LLD 25 ESS-68C 1 0 < LLD < LLD < LLD 19 ESS-69C 1 0 < LLD < LLD < LLD 30 Page 8 of 42

Attachment 1 Effluent and Waste Disposal Report Supplemental Information Shallow Wells for Plant Site Number Number of Average Minimum Maximum Depth of Well Name of Positive Pos Act Pos Act Pos Act Samples Samples in (pCi/L) (pCi/L) (pCi/L) Well (ft) in 2010 2010 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 12 0 < LLD < LLD < LLD 15 ESS-74C 1 0 < LLD < LLD < LLD 20 ESS-STAB 8 8 3.15E+04 2.11E+04 4.14E+04 31 ESS-MW-l 5 0 < LLD < LLD < LLD 24 MWPA-100C 10 5 3.76E+02 2.77E+02 4.60E+02 30 MWPA-101C 9 7 6.79E+02 4.52E+02 8.21E+02 30 MWPA-102C 9 9 3.09E+03 2.15E+03 4.72E+03 30 MWPA-103C 10 10 < LLD < LLD < LLD 30 MWPA-104C 12 12 1.80E+04 1.03E+04 2.55E+04 29 MWPA-105C 9 8 2.24E+03 1.33E+03 5.12E+03 30 MWPA-106C 9 7 4.92E+02 3.47E+02 6.29E+02 29 MWPA-107C 12 12 3.67E+03 3.13E+03 4.15E+03 29 MWPA-108C 10 4 3.54E+02 2.86E+02 4.22E+02 29 MWPA-109C 9 1 4.37E+02 4.37E+02 4.37E+02 29 MWPA-11OC 12 7 3.89E+02 2.50E+02 4.99E+02 29 MWPA-111C 16 16 2.05E+04 1.11E+04 2.80E+04 30 MWPA-112C 22 22 1.17E+06 6.24E+03 4.23E+06 34 MWPA-113C 12 3 3.13E+02 2.69+02 3.82E+02 25 Page 9 of 42

Attachment 1 Effluent and Waste Disposal Report Supplemental Information Shallow Wells for Plant Site Number Number of Well Name of Positive pos Act Pos Act Pos Act Depth of Samples Samples in (pCi/L) (pCi/L) (pCi/L) Well (ft) in 2010 2010 MWPA- 114C 12 9 1.05E+03 5.58E+02 1.95E+03 30 MWPA-115C 17 17 1.73E+04 9.76E+03 2.50E+04 34 MWPA-116C 12 1 2.41E+02 2.41E+02 2.41E+02 30 MWPA-117C 16 11 8.42E+02 4.90E+02 1.39E+03 30 MWPA- 118C 10 4 6.17E+02 4.02E+02 7.75E+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 2010 Samples in (pCi/L) (pCi/L) (pCi/L) Well (ft) 2010 ESS-38B 4 0 < LLD < LLD < LLD 55 ESS-39B 4 1 3.20E+02 3.20E+02 3.20E+02 55 ESS-51B 4 0 < LLD < LLD < LLD 45 ESS-52B 4 0 < LLD < LLD < LLD 51 ESS-53B 5 0 < LLD < LLD < LLD 76 MWPA- 12 12 2.27E+04 1.86E+04 2.89E+04 59 104B MWPA- 11 11 5.3 8E+04 4.43E+04 6.06E+04 60 107B MWPA- 11 8 2.16E+03 1.32E+03 4.OOE+03 59 lllB MWPA- 10 0 < LLD < LLD < LLD 60 118B Page 10 of 42

Attachment 1 Effluent and Waste Disposal Report Supplemental Information Overview of Plant Site, SDSP, and Nancy's Creek Protected Area Wells Page 11 of 42

Attachment 1 Effluent and Waste Disposal Report Supplemental Information Area One Wells Near Caswell Beach Area 2 Wells Near Intracoastal Waterway Page 12 of 42

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 42

Attachment 1 Effluent and Waste Disposal Report Supplemental Information Area 8 and Area 11 Wells in OCA Well ESS-36C Area 9 Wells in OCA Page 14 of 42

Attachment 2 Effluent and Waste Disposal Data Table 1A Gaseous Effluents - Summation of all Releases Table 1B 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 42

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 1.17E+02 1.02E+02 1.19E+02 1.11E+02 4.50E+01

2. Average release rate for period ptCi/sec 1.50E+01 1.30E+01 1.50E+01 1.40E+O1 NA

3. Percent of ODCM limit %5.8 1E-02 5.7 1E-02 5.50E-02 5.15E-02 NA B. IODINES Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total Iodine - 131 release Ci 6.26E-03 1.02E-02 1.33E-02 9.10E-03 3.50E+01

2. Average release rate for period iCi/sec 8.06E-04 1.30E-03 1.68E-03 1.14E-03 NA C. PARTICULATES Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total release Ci 1.60E-03 7.32E-04 2.14E-03 1.12E-03 3.50E+01

2. Average release rate for period [tCi/sec 2.06E-04 9.31E-05 2.69E-04 1.41E-04 NA

3. Gross Alpha Ci 1.24E- 11 2.73E-11 O.OOE+00 O.OOE+00 3.50E+01 D. TRITIUM Estimated Total Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total release Ci 4.46E+0O1 3.61E+O1 4.90E+01 6.76E+O1 3.OOE+01

2. Average release rate for period liCi/sec 5.73E+00 4.59E+00 6.16E+00 8.51E+00 NA Page 16 of 42

Attachment 2 Effluent and Waste Disposal Data Table 1A: Gaseous Effluents - Summation of all Releases E. IODINE- 131. IODINE- 13 3. TRITIUM AND PARTICULATES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4

1. Total release Ci 4.46E+O1 3.62E+O1 4.91E+01 6.77E+O1

2. Average release rate for period jtCi/sec 5.74E+00 4.60E+00 6.18E+00 8.52E+00

3. Percent of ODCM limit %4.16E-01 6.47E-0 1 8.35E-01 5.79E-0 I D. CARBON- 14 Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total release Ci 4.51E+00 4.82E+00 5.94E+00 5.90E+00 3.OOE+01

2. Average release rate for period tCi/sec 5.80E-01 6.13E-01 7.47E-0 1 7.43E-01 NA Page 17 of 42

Attachment 2 Effluent and Waste Disposal Data Table 1B: Gaseous Effluents - Elevated Releases Continuous Release Nuclides Released

1. FISSION GASES Unit Quarter I Quarter 2 Quarter 3 Quarter 4 krypton-85m Ci < LLD < LLD < LLD 1.86E-01 krypton-87 Ci < LLD 1.22E+00 1.92E+00 2.93E-01 krypton-88 Ci < LLD < LLD 3.97E-01 3.09E-01 xenon-133 Ci < LLD 1.06E+00 4.53E+00 3.76E+00 xenon-135 Ci 9.25E+00 9.OOE+00 9.75E+00 1.05E+01 xenon-135m Ci 2.96E+01 2.50E+01 2.47E+O1 3.08E+01 xenon-138 Ci 6.95E+O1 5.56E+01 7.07E+O1 5.83E+01 total for period Ci 1.08E+02 9.19E+O1 1.12E+02 1.04E+02

2. GASEOUS IODINES Unit Quarter I Quarter 2 Quarter 3 Quarter 4 iodine-131 Ci 4.59E-03 7.96E-03 1.07E-02 7.16E-03 iodine-132 Ci 3.OOE-02 7.59E-02 1.28E-01 8.27E-02 iodine-133 Ci 3.64E-02 7.85E-02 1.15E-01 7.40E-02 iodine-134 Ci 6.04E-02 1.62E-01 2.89E-01 1.67E-01 iodine-135 Ci 6.03E-02 1.36E-01 2.1OE-01 1.38E-01 total for period Ci 1.92E-01 4.60E-01 7.52E-01 4.69E-01

3. PARTICULATES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 chromium-51 Ci 2.29E-05 <LLD < LLD < LLD manganese-54 Ci 6.26E-07 2.07E-06 < LLD < LLD cobalt-58 Ci 7.89E-06 2.18E-06 < LLD < LLD cobalt-60 Ci 5.40E-05 1.01E-05 1.16E-05 4.50E-06 zinc-65 Ci 4.12E-06 1.99E-06 < LLD < LLD strontium-89 Ci 8.30E-05 3.70E-05 1.92E-04 8.96E-05 strontium-90 Ci 1.24E-06 2.13E-07 3.56E-06 8.78E-07 cesium-137 Ci 4.11E-06 < LLD < LLD 4.65E-06 barium-140 Ci 1.77E-04 2.18E-05 4.89E-04 3.17E-04 lanthanum-140 Ci 3.15E-04 3.07E-05 8.76E-04 5.49E-04 total for period Ci 6.70E-04 1.06E-04 1.57E-03 9.65E-04

4. TRITIUM Unit Quarter I Quarter 2 Quarter 3 Quarter 4 hydrogen-3 Ci 1.19E+O1 1.31E+01 2.28E+01 2.58E+O1 Page 18 of 42

Attachment 2 Effluent and Waste Disposal Data Table IC: Gaseous Effluents - Ground Level Releases Continuous Release Nuclides Released

1. FISSION GASES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 xenon-133 Ci 7.92E-01 9.55E-01 < LLD < LLD xenon-133m Ci < LLD 2.94E-0 1 7.34E-01 < LLD xenon-135 Ci 6.92E+00 9.18E+00 5.98E+00 6.06E+00 xenon-135m Ci 5.58E-01 < LLD 6.28E-01 8.76E-01 total for period Ci 8.27E+00 1.04E+01 7.34E+00 6.93E+00

2. GASEOUS IODINES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 iodine-131 Ci 1.67E-03 2.23E-03 2.69E-03 1.94E-03 iodine- 132 Ci 2.18E-02 3.50E-02 5.18E-02 3.27E-02 iodine-133 Ci 1.60E-02 2.45E-02 3.09E-02 2.18E-02 iodine- 134 Ci 3.04E-02 8.5 1E-02 1.07E-0 1 5.47E-02 iodine- 135 Ci 3.45E-02 5.32E-02 6.92E-02 4.50E-02 total for period Ci 1.04E-01 2.OOE-01 2.62E-01 1.56E-01

3. PARTICULATES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 chromium-51 Ci 5.08E-04 5.62E-05 2.44E-05 < LLD manganese-54 Ci 1.63E-05 4.59E-06 < LLD < LLD cobalt-58 Ci 7.25E-05 5.76E-05 1.45E-05 < LLD cobalt-60 Ci 1.53E-04 2.12E-04 7.49E-05 2.33E-05 zinc-65 Ci 4.01E-06 < LLD < LLD < LLD strontium-89 Ci 8.21E-05 6.98E-05 7.25E-05 4.44E-05 strontium-90 Ci 9.21E-07 4.27E-07 1.36E-06 < LLD barium- 140 Ci 4.07E-05 7.32E-05 2.20E-04 2.32E-05 lanthanum- 140 Ci 5.50E-05 1.52E-04 1.57E-04 6.12E-05 total for period Ci 9.32E-04 6.26E-04 5.64E-04 1.52E-04

4. TRITIUM Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 hydrogen-3 Ci 3.27E+01 2.29E+01 2.62E+01 4.18E+01 Page 19 of 42

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 1.17E-03 1.18E-03 1.67E-03 3.48E-04 4.OOE+01 (excluding tritium, gases, and alpha)

2. Average diluted concentration VCi/ml 3.23E-11 2.61E-11 3.26E-11 1.13E-11 NA (NOTE 2)

3. Percent of 4.90E-03 4.43E-03 4.OOE-03 4.07E-03 applicable limit NA B. TRITIUM (NOTE 1)

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

1. Total release Ci 7.14E+O1 7.36E+01 7.30E+01 8.28E+01 4.50E+01

2. Average diluted 1.97E-06 1.62E-06 1.43E-06 2.69E-06 concentration PCi/ml NA (NOTE 2)

3. Percent of 1.97E-01 1.62E-01 1.43E-01 2.69E-0 1 applicable limit 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 3.15E-02 2.74E-02 2.66E-02 2.63E-02 4.OOE+O1

2. Average diluted concentration 8.67E-10 6.02E-10 5.19E-10 8.53E-10 ptCi/ml NA (NOTE 2)

3. Percent of 4.33E-04 3.01E-04 2.60E-04 4.27E-04 applicable limit NA D. GROSS ALPHA RADIOACTIVITY Estimated Total Unit Quarter 1 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 42

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 5.75E+06 6.89E+06 7.13E+06 4.45E+06 1.50E+01 F. VOLUME OF DILUTION WATER Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error I1. 1.50E+01 Total volume liters 3.63E+10 4.54E+10 5.12E+10 3.08E+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 3.68E+l1 4.51E+l 1 5.24E+1 1 4.70E+1 1 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)

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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 1.25E-05 < LLD < LLD manganese-54 Ci 5.83E-06 2.13E-05 < LLD < LLD cobalt-58 Ci 2.11E-05 7.64E-06 2.4 1E-06 < LLD cobalt-60 Ci 4.94E-04 4.54E-04 6.55E-04 1.15E-04 arsenic-76 Ci 7.62E-06 < LLD < LLD < LLD yitrium-91m Ci 2.68E-06 < LLD < LLD < LLD yitrium-92 Ci 4.04E-05 < LLD < LLD < LLD iodine- 131 Ci 1.84E-04 1.87E-04 2.64E-04 1.17E-04 iodine-133 Ci 2.36E-04 3.50E-04 6.41E-04 1.09E-04 iodine-135 Ci < LLD < LLD 2.08E-05 < LLD cesium-134 Ci 5.85E-06 7.OOE-06 < LLD < LLD cesium-137 Ci 1.74E-04 1.45E-04 8.42E-05 7.25E-06 total for period Ci 1.17E-03 1.18E-03 1.67E-03 3.48E-04

2. DISSOLVED AND ENTRAINED GASES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 krypton-85 Ci < LLD < LLD 2.45E-04 < LLD xenon-133 Ci 6.94E-03 4.70E-03 4.65E-03 4.88E-03 xenon-133m Ci 1.92E-04 < LLD < LLD < LLD xenon-135 Ci 2.43E-02 2.27E-02 2.17E-02 2.14E-02 xenon-135m Ci 1.46E-05 2.97E-06 < LLD < LLD total for period Ci 3.15E-02 2.74E-02 2.66E-02 2.63E-02 Page 22 of 42

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

1. LIQUID RELEASES 2. GASEOUS RELEASES Alpha 1.92E-08 Kr-85 2.67E-06 H-3 2.53E-06 Kr-85m 8.57E-09 H-3 2.33E-07* Kr-87 2.28E-08 Cr-51 1.72E-07 Kr-88 3.27E-08 Mn-54 1.14E-08 Xe-133 2.09E-08 Fe-55 1.33E-07 Xe-133m 5.62E-08 Co-58 2.05E-08 Xe-135 8.07E-09 Fe-59 3.90E-08 Xe-135m 8.79E-08 Co-60 2.63E-08 Xe-137 1.20E-06 Zn-65 4.69E-08 Xe-138 2.70E-07 As-76 3.72E-08 Sr-89 2.03E-08 Sr-90 1.35E-08 Y-91m 2.96E-08 Y-92 1.16E-07 Mo-99 1.41E-07 1-131 1.99E-08 1-135 8.OOE-08 Cs-134 1.46E-08 3. IODINES AND PARTICULATES Cs-137 2.12E-08 Alpha 1.O1E-15 Ce- 141 2.38E-08 H-3 8.71E-11 Ce- 144 9.93E-07 Cr-51 2.99E-12 Mn-54 2.36E-13 Kr-85 5.14E-06 Co-58 4.01E-13 Kr-87 3.90E-08 Fe-59 5.38E-13 Kr-88 5.40E-08 Co-60 3.56E-13 Xe-133 3.72E-08 Zn-65 1.04E-12 Xe-133m 1.54E-07 Sr-89 2.04E-15 Xe-135 1.71E-08 Sr-90 1.06E-15 Xe-135m 6.OOE-08 Mo-99 3.11E-12 Xe-138 2.07E-07 1-131 4.17E-13 Cs-134 4.58E-13 Cs-137 5.93E-13 Ce-141 5.07E-13 Ce-144 1.96E-12 NOTES:

1. The above values represent typical "a priori" LLDs for isotopes where values of "< LLD" are indicated in Tables 1A, IB, 1C, 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.

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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) 9.16E+02 Total curie quantity (estimated) 9.68E+01

2. Type of Waste Estimated Total Unit Period %Error

a. Spent resins, filter, sludges meter3 5.25E+01 Curies 9.52E+O1 1.00E+01

b. Dry active waste, compacted/non-compacted meter 3 8.64E+02 Curies 1.60E+00- 1.00E+01

c. Irradiated components meters3 O.OOE+00 Curies 0.00E+00 N/A

d. Others (describe) meters3 O.OOE+00 Curies O.OOE+00 N/A

3. Estimate of major radionuclides composition

a. Fe-55 1.88E+01%

Co-60 5.32E+01%

Ni-63 1.98E+01%

Cs-137 5.04E+00%

b. Fe-55 1.89E+01  %

Co-60 6.21E+01  %

Ni-63 5.38E+00  %

Cs-137 1.27E+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.

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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 1.00E+01

b. Dry active waste Compacted/ Type A or GDP 2.30E+01 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 2.OOE+01 Highway Oak Ridge, TN 3.OOE+00 Rail Clive, UT 1.00E+01 Highway Erwin. TN

b. Irradiated Fuel Number of Shipments Mode of Transportation Destination 0 N/A N/A Page 25 of 42

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) 7.70E+00 Total curie quantity (estimated) 2.01E+02

2. Type of Waste Estimated Total Unit Period %Error

a. Spent resins, filter, sludges meter3 7.70E+00 Curies 2.01E+02 1.00E+01

b. Dry active waste, compacted/non-compacted meter 3 0.OOE+00 Curies 0.OOE+00 N/A

c. Irradiated components meters3 O.OOE+00 Curies 0.OOE+00 N/A

d. Others (describe) meters 3 0.OOE+00 Curies 0.OOE+00 N/A

3. Estimate of major radionuclides composition

a. Mn-54 3.87E+00 %

Fe-55 5.61E+00 %

Co-58 4.90E+00 %

Co-60 7.11E+01%

Ni-63 4.94E+00 %

Zn-65 5.45E+00 %

Cs-137 2.40E+00 %

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.

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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 3.00 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 3.00E+00 Highway Erwin, TN

b. Irradiated Fuel Number of Shipments Mode of Transportation Destination 0 N/A N/A Page 27 of 42

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+00 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 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 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 or spent fuel was shipped offsite for storage or disposal during the reporting period.

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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 42

Attachment 3 Environmental Monitoring Program : Milk and Vegetable Sample Location : Land Use Census Page 30 of 42

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.

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Attachment 3 Environmental Monitoring Program Enclosure 2: Land Use Census The 2010 Land Use Census did not identify any locations that are reportable in the Radioactive Effluent Release Report for 2010.

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 1.6 miles SSW 1.2 miles 1.7 miles SW 1.1 miles 1.6 miles WSW 1.2 miles 1.2 miles W 0.9 miles 1.0 mile WNW 0.9 miles None NW 0.9 miles 1.0 miles NNW 0.8 miles 0.9 miles N 0.7 miles 0.9 miles Page 32 of 42

Attachment 4 Effluent Instrumentation : Radioactive Liquid Effluent Monitoring Instrumentation : Radioactive Gaseous Effluent Monitoring Instrumentation : Liquid Hold-Up Tank Page 33 of 42

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.

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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.

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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.

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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). The following change was made during this reporting period:

The installation of the Unit 2 Salt Water Release Tank (SWRT) was completed under Engineering Change 70824. This change was submitted under Licensing Document Change Request 1OFSAR-014. This change will revise Section 11.2.2, Table 9-24, and Table 11-4 of the UFSAR.

Portions of the Unit 2 system were installed during the Unit 1 SWRT installation including the SWRT and piping from the condenser pit to enable pump out to the Unit 1 SWRT. This EC completed the installation and includes various upgrades based on Unit 1 operating experience.

The following work activities were required to complete the Unit 2 SWR system:

" Installation of SWRT pump, filters, piping and supports.

• Installation of local instrument control panel, wiring and associated instruments.

• Installation of tank level indicator at the Radwaste control panel.

• Installation of electrical power feeds from local 480 and 120VAC distribution systems to the SWRT pump and instrument control panel.

" Completion of the SWRT grating. Most of the grating was in place but modifications were required to mount various components including the pump, filters and piping.

" Completion of the tank inlet and outlet piping. The tank has two inlets: one for condenser pit pumpout and one for spray cooler basin drains. Tank outlet piping was tied-in with the Unit 1 tank outlet piping which goes to Radwaste.

The following design upgrades were included for the Unit 2 SWR system:

" Epoxy lining for the SWRT interior to protect the concrete, improve the ability to clean the tank wall, and reduce maintenance.

" Upgraded tank level instrumentation including installation of a stilling well and local indicator for improved performance.

" Upgraded filters to reduce maintenance dose rate exposure. The new horizontal filters are single cartridge design compared to nearly sixty cartridges on the existing units. The existing filter housing design has long since been discontinued due to poor sealing performance.

" Filter isolation valves that are operable from the outside the high rad area on top of the tank to reduce maintenance dose rate exposure.

" The system will not include the control valve on the tank inlet which closes automatically when the tank is 80% full. This change is due to the addition of a second inlet pipe to the SWRTs under interfacing EC 70821 for the spray cooler basin overflow drains. SWRT isolation will be accomplished by closing both inlet valves manually per revised procedures.

" Modified DPI instrument valve configuration to facilitate in-place calibration of instruments.

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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.

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Attachment 7 Annual Dose Assessment Liquid Effluents Critical Age: Adult 1

Controlling location for liquid releases: SW sector at 0. 1 miles( )

Supplemental SDSP SDCB Marsh(1 ) Pipe Total Dose*

mrem 4.06E-06 1.35E-07 2.80E-03 3.86E-09 2.80E-03

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

GI-LLI 7.85E-04 2.80E-03 3.59E-03 2.OOE+01 Bone 2.55E-05 0.OOE+00 2.55E-05 2.OOE+01 Liver 5.15E-04 2.80E-03 3.32E-03 2.OOE+01 Lung 4.65E-04 2.80E-03 3.27E-03 2.OOE+01 Total Body 5.22E-04 2.80E-03 3.33E-03 6.OOE+00 Thyroid 9.92E-04 2.80E-03 3.80E-03 2.00E+01 Kidney 4.76E-04 2.80E-03 3.28E-03 2.OOE+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.

Page 39 of 42

Attachment 7 Annual Dose Assessment Gaseous Effluents Noble Gas:

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

Gamma 2.22E-02 2.OOE+01 Beta 1.50E-02 4.OOE+01 Iodine, Particulates, and Tritium:

Supplemental SDSP Carbon-14 (All Carbon- 14 Dose* Evaporation except Bone (Bone) and Skin) mrem 8.16E-04 4.71E-01 2.36E+00

• Reference page 5-6 of Supplemental Information Critical Age: Infant Controlling location: NE sector at 4.75 mile, assuming a cow milk pathway<2 ) (3)

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

(mrem) (mrem)

Thyroid 3.71E-01 4.72E-0 1 8.43E-01 3.OOE+0 1 Kidney 5.36E-03 4.72E-01 4.77E-01 3.OOE+01 Liver 5.16E-03 4.72E-01 4.77E-01 3.OOE+01 Total Body 4.45E-03 4.72E-01 4.76E-01 3.OOE+01 Skin 4.OOE-03 8.16E-04 4.82E-03 3.OOE+01 GI-LLI 4.02E-03 4.72E-01 4.76E-01 3.OOE+01 Lung 3.96E-03 4.72E-01 4.76E-01 3.OOE+01 Bone 1.38E-03 2.36E+00 2.36E+00 3.OOE+O1 (2) 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 6 of supplemental information.

(3)The controlling location for the Carbon-14 supplemental dose is the south sector at 1.6 miles with a garden.

The critical age is a child. Reference page 5 of supplemental information.

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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 34 was effective on July 13, 2010. The ODCM Revision 34 changes are as follows:

1. On Page 1-1, included a reference to 10CFR72, Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste. Reference Engineering Change 67583.

2. On page 4-6, updated Table 4.0-1, Radiological Environmental Monitoring Program, 1.

Direct Radiation to include information about TLDs: 82, 83, 84, and 85. Reference Engineering Change 67583.

3. On page 4-14, updated Figure 4.0-1 to include the location of TLDs 82, 83, 84, and 85.

Reference Engineering Change 67583.

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Attachment 9 Special Groundwater Protection On December 9, 2010, water was found leaking from electrical junction box WL2 into the Diesel Generator Building basement. The tritium levels of the water were determined to be in excess of the Nuclear Energy Institute (NEI) voluntary reporting criteria (i.e., 30,000 pCi/L for onsite groundwater, as specified in the Offsite Dose Calculation Manual). Further investigation determined the source of the tritiated water to be an underground portion of the Unit 1 Hotwell Makeup line, l-CO-32-12-C-2, from the Unit 1 Condensate Storage Tank (CST). The Unit 1 Hotwell Make-up line was isolated and Engineering Changes 79448 and 79450 were implemented to provide Unit 1 Hotwell Makeup from the Unit 2 CST. The leak was inside the plant protected area, well inside the site's property boundary. There is no indication that tritium migrated into drinking water sources or off plant property. The leakage did not impacted plant reliability or the operability of any safety-related equipment. Corrective actions were taken to capture the inleakage of water into the diesel generator building and route it through normal permitted discharge paths. Additional water samples were obtained from site monitoring wells until the leak was isolated. The Brunswick plant has had an extensive groundwater protection monitoring program in place since 2007. This environmental sampling program consists of more than 100 monitoring wells which are routinely sampled. The following agencies were notified of this incident: City of Southport, Brunswick County, State Officials, NEI, INPO, ANI, and the NRC Resident Inspector. Reference Nuclear Condition Report 437478 for further details on this leak.

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