BSEP 08-0059, Transmittal of Annual Radioactive Effluent Release Report for 2007

Transmittal of Annual Radioactive Effluent Release Report for 2007

ML081270270
Person / Time
Site:	Brunswick
Issue date:	04/29/2008
From:	Ivey R Carolina Power & Light Co, Progress Energy Carolinas, Progress Energy Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 08-0059
Download: ML081270270 (46)

Text

Progress Energy lCER-50.36a O

'APR-2 92008 SERIAL: BSEP 08-0059 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Docket Nos. 50-325 and 50-324/License Nos. DPR-71 and DPR-62 Radioactive Effluent Release Report for 2007 Ladies and Gentlemen:

In accordance with 10 CFR 50.36a and Technical Specification (TS) 5.6.3 for the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2, Carolina Power &

Light Company, now doing business as Progress Energy Carolinas, Inc., is submitting the enclosed Radioactive Effluent Release Report for BSEP Unit Nos. 1 and 2. This report covers the period from January 1, 2007, through December 31, 2007.

TS 5.5.1, "Offsite Dose Calculation Manual (ODCM)," requires changes to theODCM be submitted as part of, or concurrent with, the Radioactive Effluent Release Report; There, were no revisions of the ODCM in 2007.

No regulatory commitments are contained in this submittal. Please refer'any questions regarding this submittal to Mr. Gene Atkinson, Supervisor - Licensing/Regulatory Programs (Acting), at (910) 457-2056.

Sincerely, Randy C. Ivey Manager - Support Services Brunswick Steam Electric Plant MAT/mat

Enclosure:

Radioactive Effluent Release Report for 2007 Progress Energy Carolinas, Inc.

Brunswick Nuclear Plant PO Box 10429 Southport, NC 28461  : I ,c

Document Control Desk BSEP 08-0059 / Page 2 cc (with enclosure):

U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Victor M. McCree, Regional Administrator (Acting)

Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission ATTN: Mr. Joseph D. Austin, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)

ATTN: Mrs. Farideh E. Saba (Mail Stop OWFN 8G9A) 11555 Rockville Pike Rockville, MD 20852-2738 Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510

Enclosure BSEP 08-0059 Radioactive Effluent Release Report for 2007

Brunswick Steam Electric Plant Radioactive Effluent Release Report January 1, through December 31, 2007 Table of Contents Attachment Pages

1. Effluent and Waste Disposal Report Supplemental 2 - 17 Information

2. Effluent and Waste Disposal Data 18 - 32

3. Environmental Monitoring Program 33 - 35

4. Effluent Instrumentation 36-39

5. Major Modification to the Radioactive Waste Treatment 40 Systems

6. Meteorological Data 41

7. Annual Dose Assessment 42

8. Off-Site Dose Calculation Manual (ODCM) and Process 43 Control Program (PCP) Revisions Page 1 of 43

Attachment I 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 (Off-Site Dose Calculation Manual Specification (ODCMS) 7.3.8)

(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 1 (a) < 15 mrem to any organ (2) Calendar Year (a) < 30 mrem to any organ C. Liquid Effluents (ODCMS 7.3.4) 2 (1) Calendar Quarter (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 NOTE: Dose calculations are determined in accordance with the ODCM 1Used 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 43

Attachment I Effluent and Waste Disposal Report Supplemental Information 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 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 ltCi/ml 3 (2) Dissolved and entrained noble gases: limit = 2.OOE-04 pCi/ml 3

3. Measurements and Approximations of Total Radioactivity A. Fission and activation gases (1) Analyses for specific radionuclides in representative grab samples by gamma spectroscopy.

B. lodines (1) Analysis for specific radionuclides collected on charcoal cartridges by gamma spectroscopy.

C. Particulates (1) Analysis for specific radionuclides collected on filter papers by gamma spectroscopy.

D. Liquid Effluents (1) 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.

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Attachment I Effluent and Waste Disposal Report Supplemental Information

4. Batch Releases A. Liquid (1) Number of batch releases: 1.39E+02 (2) Total time period for batch releases: 2.06E+04 Minutes (3) Maximum time period for a batch release: 2.60E+02 Minutes (4) Average time period for a batch release: 1.48E+02 Minutes (5) Minimum time period for a batch release: 1.20E+01 Minutes (6) Average stream flow during periods of release of effluent into a flowing stream: 7.75E+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 Releases 4 A. Liquid (1) Number of releases: O.OOE+00 (2) Total activity released: O.OOE+00 Curies B. Gaseous (1) Number of releases: 0.00E+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 page 5 for a discussion of release events that occurred.

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Attachment 1 Effluent and Waste Disposal Report Supplemental Information Summary Water is routinely discharged from the plant storm drainage system to the Storm Drain Stabilization Pond (SDSP). This system is intended to provide for mitigation and control of release of storm water and plant drainage water to the environment. In addition to storm water, this water also includes potentially radioactive contaminated liquids, including tritium that originated primarily from the Turbine Building. The Turbine Building Heating Ventilation and Air Conditioning (TB HVAC) System employs an air recirculation system to ventilate the building. Prior to the exhaust air being drawn into the supply fans, the air passes through the TB HVAC cooling system that consists of two spray coolers (airwashes) to control building temperatures. The chilled water receives heat and contaminants (including tritium) through mechanical scrubbing from the incoming air and is recycled through the cooling system. The total air environment consists of approximately 90% of the air volume being re-circulated with approximately 10% of the air volume being exhausted from the building. This constant recycling results in buildup of radioactive contaminants in the cooling water. Water that overflows from the spray coolers containing tritium was discharged to the Storm Drain Collection Basin (SDCB). The water that is collected into the SDCB gets pumped to the SDSP for retention prior to release from the site to meet National Pollution Discharge Elmination System (NPDES) requirements. Water from the SDSP is ultimately released to the intake canal through a controlled discharge process.

On May 7, 2007 water samples obtained from two electrical manholes located in the vicinity of the meteorological tower, approximately 50 yards from the west side of the SDSP, were analyzed and found to contain detectable concentrations of tritium. Investigation of the source led to the detection of tritium in surface water at several locations around the perimeter of the SDSP.

These locations are all on company property. As a result of ongoing investigations to determine the source and potential migration path of the tritium, an increased environmental sampling program was initiated. On June 13, 2007, tritium levels in excess of Nuclear Energy Institute (NEI) voluntary reporting criteria were confirmed to be present in new onsite shallow groundwater wells. The NRC was notified on 6/13/07 (Event Number 43420). Immediate corrective actions were taken to perform additional sampling of areas surrounding the stabilization pond 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 and the storm drain stabilization pond. Additional corrective actions included installation of additional monitoring wells at various locations to determine groundwater flow and checking for the presence of tritium in the surrounding groundwater. There has been no indication that tritium has migrated offsite to drinking water supplies.

Further investigations indicated that the pond was contributing to 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.

Additional investigations indicate the presence of tritium in the onsite tidally influenced marsh area near the pond. Release impacts from the tidally influenced marsh are calculated based on Page 5 of 43

Attachment 1 Effluent and Waste Disposal Report Supplemental Information falling tides from the marsh areas to Nancy's Creek. Fish and invertebrate sampling and analysis for tritium was performed twice in Nancy's Creek in 2007. Routine fish and invertebrate sampling has also been initiated. The results indicated that tritium concentrations for fish and invertebrates in Nancy's Creek was <LLD.

Discussion of releases from the Storm Drain Collection Basin Due to heavy rain events, the Storm Drain Collection Basin (SDCB) was released directly to the discharge canal on two occasions in 2007. The SDCB is a permitted release point during periods of inclement weather to protect plant personnel and equipment. Approximately 4.63E+05 gallons containing 4.50E-02 curies of tritium were released. There was no detectable gamma radioactivity. This resulted in an estimated maximum dose to the individual of 6.47E-08 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 summaries on Attachment 2, Table 2A.

Discussion of releases from the Storm Drain Stabilization Pond Approximately 7.97E+06 gallons containing 1.80E+01 curies of tritium were released from the Storm Drain Stabilization Pond (SDSP) to the intake canal during this reporting period. There was no detectable gamma radioactivity. This resulted in an estimated maximum dose to the individual of 2.70E-05 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 summaries on Attachment 2, Table 2A. The SDSP is a permitted release point.

Discussion of releases from water evaporation from the Storm Drain Stabilization Pond There was 5.43E+06 ft3 of tritiated water released via evaporation from the Storm Drain Stabilization Pond for 2007. This yields 73.9 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 2.1 IE-02 millirem via the inhalation pathway. Only inhalation dose was determined because these exposed individuals do not have a garden and also do not have any milk or meat animals at this location. The dose from this release is not included in Attachment 7, Annual Dose Assessment.

The total curies released are not included in Attachment 2, Table IA. The curies, volume released, and dose were not included because those releases are not part of the pathway for designed releases from the plant.

Discussion of releases from the Marsh to Nancy's Creek On June 28, 2007 tritium activity at a concentration of 3.56E-06 pCi/mI was detected at Waypoint 74. This location is on company owned property in the marsh approximately 100 yards from Nancy's Creek (which is offsite). This location (marsh land) is under the influence of high and low tides which releases to Nancy's Creek offsite. This constituted a release point for evaluation (curies released, volume, offsite dose impact, etc). From the point of discovery the sampling program was expanded to weekly sampling and analysis at seven locations.

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Attachment 1 Effluent and Waste Disposal Report Supplemental Information From the point of discovery all gamma analysis were <LLD. There were 181 tritium analyses with 45 positive results. The minimum concentration detected was 2.67E-07 pCi/ml. The maximum concentration was 1.66E-05 pCi/ml. Using the average concentration of 1.44E-06 pCi/ml, two high tides per day, the area of the marsh at high tide, and 186 days (from June 28 thru December 31,2007), it is calculated that 2.69E07 gallons were released to Nancy's Creek containing 5.45E+01 curies of tritium. This yielded a Total Body dose of 7.15 E-04 mrem to an adult from eating fish and 1.76E-04 mrem from eating invertebrate (shrimp, crabs, etc.) for a total dose of 8.91E-04 mrem.

However, for purposes of estimating the total release for the calendar year 2007 a linear extrapolation was performed to account for releases during the entire year. This is done because it is generally realized that the releases were most likely occurring prior to the point of discovery.

An accounting of data in this manner utilizes assumptions that the data was the same from January 1, 2007 to point of discovery. Since the point of discovery was June 28, 2007 (day 179 of the year) the resulting computations were applied to the known data. Utilizing these assumptions it is estimated that 1.07E+02 curies of tritium and approximately 5.27E07 gallons were released to Nancy's Creek. This yielded a Total Body dose of 1.40E-03 mrem to an adult from eating fish and 3.45E-04 mrem from eating invertebrate (shrimp, crabs, etc.) for a total dose of 1.75E-03 mrem.

The curies and volume released are not included in Attachment 2, Table 2A. The calculated dose is not included in the Annual Dose Summary, Attachment 7. The curies, volume released, and dose were not included because those releases are not part of the pathway for designed releases from the plant.

Discussion of Ground Water Monitoring Based on the aforementioned event, in June of 2007 the site ground water sampling and analysis surveillance program expanded. By the end of 2007 the ground water program included approximately 42 wells. During this time period there were 214 tritium analyses with 105 positive results. Several gamma analysis and hard to identify analysis (Sr-90, Sr-89, & Fe-55) were performed and all these results were less than the Lower Limit of Detection (<LLD). Due to the positive results of tritium analysis two Open House Meetings (June 19, 2007 and August 21, 2007) were held to inform the general public that on site wells had detectable tritium radioactivity.

The sampling program consists of shallow, intermediate, and deep wells in different locations around the Storm Drain Stabilization Pond and various plant site locations to evaluate ground water movement. Shallow wells are being sampled around Nancy's Creek to evaluate potential ground water movement towards offsite.

The major source of tritium to the Storm Drain Stabilization Pond, the turbine building airwash system, has been rerouted to Radwaste to be released to the designed discharged point of release (discharge canal which discharges into the ocean).

The following are the tritium results and maps showing each well location.

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Attachment I Effluent and Waste Disposal Report Supplemental Information Shallow Wells for Plant Site Number Number Well of of Average Minimum Maximum Depth Name Samples Positive Pos Act Pos Act Pos Act of Well Samples (pCi/L) (pCi/L) (pCi/L) (ft)

Iin 2007 in 2007 (ft)

ESS-2C 3 3 1.82E+06 1.74E+06 1.89E+06 23.0 ESS-3C 4 4 4.34E+02 3.11E+02 6.21E+02 14.3 ESS-13C 3 0 < LLD < LLD < LLD 24.8 ESS-16 3 3 4.38E+04 2.83E+04 5.40E+04 25.4 MW-2 3 1 4.70E+02 4.70E+02 4.70E+02 24.7 MW-3 2 0 < LLD < LLD < LLD 24.7 Intermediate Wells for Plant Site Number Number Well of of Average Minimum Maximum Depth We of Positive Pos Act Pos Act Pos Act Well Samples (pCi/L) (pCiIL) (pCi/L) (ft) in 2007 in 2007 ESS-IB 3 0 < LLD < LLD < LLD 59.2 ESS-2B 3 1 4.70E+02 4.70E+02 4.70E+02 54.8 ESS-3B 4 4 1.10E+03 4.53E+02 1.56E+03 52.4 ESS-13B 3 0 < LLD < LLD < LLD 56.5

• LLD for groundwater monitoring is 259 pCi/L.

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Attachment I Effluent and Waste Disposal Report Supplemental Information Shallow Wells for Storm Drain Stabilization Pond Number Number Depth of of Average Minimum Maximum of Well Name of Positive Pos Act Pos Act Pos Act Well inmples Samples (pCi/L) (pCi/L) (pCi/L) (ft) in 2007 in 2007 ESS-17C 6 6 4.28E+03 3.29E+03 5.10E+03 26.0 ESS-18C 6 6 6.55E+05 5.07E+05 7.50E+05 20.0 ESS-19C 8 8 4.33E+05 3.55E+05 5.35E+05 20.0 ESS-20C 7 7 1.56E+04 1.25E+04 1.76E+04 20.0 ESS-21C 6 5 5.51E+02 3.78E+02 7.40E+02 20.0 ESS-22C 6 6 5.89E+05 2.94E+05 7.88E+05 20.0 ESS-23C 6 6 2.11E+05 1.91E+05 2.39E+05 23.0 ESS-24C 6 6 3.51E+03 3.06E+03 4.23E+03 18.0 ESS-25C 6 0 < LLD < LLD < LLD 22.0 ESS-26C 6 6 6.3 1E+05 5.62E+05 6.89E+05 15.0 ESS-27C 6 6 2.62E+05 2.35E+05 3.02E+05 15.5 ESS-28C 6 2 3.17E+02 3.06E+02 3.28E+02 23.0 ESS-30C 3 3 1.78E+04 2.41E+03 4.82E+04 15.0 ESS-31C 3 3 3.19E+03 1.56E+03 4.87E+03 15.0 ESS-STAB 6 6 6.33E+05 5.31E+05 6.86E+05 31.0 Intermediate Wells for Storm Drain Stabilization Pond Number Number Depth of of Average Minimum Maximum of Well Name of Positive Pos Act SamplesWell Pos Act Pos Act Samples (pCi/L) (pCi/L) (pCi/L) (ft) in 2007 in 2007 (ft)

ESS-17B 7 2 4.71E+02 3.1OE+02 6.33E+02 53.0 ESS-18B 6 0 < LLD < LLD < LLD 63.0 ESS-19B 8 8 4.18E+03 2.85E+03 7.20E+03 42.0 ESS-20B 6 0 < LLD < LLD < LLD 43.0 ESS-21B 6 0 S LLD < LLD < LLD 67.0 ESS-22B 6 1 4.22E+02 4.22E+02 4.22E+02 76.0 ESS-24B 6 1 8.50E+02 8.50E+02 8.50E+02 53.0 ESS-25B 4 0 . LLD - LLD I LLD 43.0

• LLD for groundwater monitoring is 259 pCi/L.

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Attachment 1 Effluent and Waste Disposal Report Supplemental Information Deep Wells for Storm Drain Stabilization Pond Number Number Well of of Average Minimum Maximum Depth Positive Pos Act Pos Act Pos Act of Well in 2007 Samples (pCi/L) (pCi/L) (pCi/L) (ft) in 2007 ESS-17A 4 0 < LLD <LLD < LLD 150.0 ESS-24A 5 0 < LLD < LLD < LLD 140.0 ESS-27A 6 0 < LLD < LLD <LLD 150.0 Shallow Wells for Nancy's Creek Number Number of Of Average Minimum Maximum Depth of Well Name ofs Positive Pos Act Pos Act Pos Act Well (ft)

Samples Samples (pCi/L) (pCi/L) (pCi/L) in 2007 2007 ESS-GLB-1 5 0 < LLD < LLD < LLD 8.0 ESS-NC-1 6 0 <5 LLD 5 LLD < LLD 7.5 ESS-NC-2 6 0 < LLD < LLD < LLD 8.0 ESS-NC-3 5 0 5 LLD < LLD < LLD 8.0 ESS-NC-4 5 1 3.14E+02 3.14E+02 3.14E+02 8.0 ESS-NC-5 5 0 < LLD < LLD < LLD 8.0

• LLD for groundwater monitoring is 259 pCi/L.

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Attachment 1 Effluent and Waste Disposal Report Supplemental Information Overview of Plant Site, SDSP, and Nancy's Creek Page 11 of 43

Attachment 1 Effluent and Waste Disposal Report Supplemental Information Shallow Wells for Plant Site Page 12 of 43

Attachment 1 Effluent and Waste Disposal Report Supplemental Information Intermediate/Shallow Wells for Plant Site Page 13 of 43

Attachment 1 Effluent and Waste Disposal Report Supplemental Information Shallow Wells for Storm Drain Stabilization Pond IIVZIL4ý11v=

Page 14 of 43

Attachment 1 Effluent and Waste Disposal Report Supplemental Information Intermediate Wells for Storm Drain Stabilization Pond MUMMY:!

Page 15 of 43

Attachment 1 Effluent and Waste Disposal Report Supplemental Information Deep Wells for Storm Drain Stabilization Pond Page 16 of 43

Attachment I Effluent and Waste Disposal Report Supplemental Information Shallow Wells for Nancy's Creek Page 17 of 43

Attachment 2 Effluent and Waste Disposal Data Table IA 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 18 of 43

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

1. Total release Ci 5.34E+02 3.01E+02 3.18E+02 3.3 4E+02 4.50E+01

2. Average release rate for period ItCi/sec 6.87E+01 3.83E+01 4.OOE+01 4.20E+01 NA

3. Percent of ODCMS limit 1.14E-01 5.89E-02 7.52E-02 7.70E-02 NA B. IODINES Estimated Total Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total Iodine - 131 release Ci 3.95E-02 1.63E-02 9.96E-03 1.06E-02 3.50E+Of

2. Average release rate for period jtCi/sec 5.07E-03 2.08E-03 1.25E-03 1.33E-03 NA C. PARTICULATES Estimated Total Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total release Ci 1.19E-02 3.48E-03 4.61E-03 3.69E-03 3.50E+01

2. Average release rate for period liCi/sec 1.53E-03 4.43E-04 5.80E-04 4.64E-4 NA

3. Gross Alpha Ci O.OOE+00 5.91E-08 O.OOE+00 O.OOE+00 3.50E+01 D. TRITIUM Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total release Ci 5.78E+01 6.5 1E+O1 6.72E+01 6.59E+01 3.OOE+01

2. Average release rate for period ltCi/sec 7.43E+00 8.28E+00 8.46E+00 8.29E+00 NA Page 19 of 43

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

1. Total release Ci 5.8 1E+O1 6.53E+01 6.73E+01 6.60E+01

2. Average release rate for period pCi/sec 7.47E+00 8.30E+00 8.47E+00 8.30E+00

3. Percent of ODCMS limit  % 1.77E+00 5.85E-01 3.54E-01 3.77E-01 Page 20 of 43

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

1. FISSION GASES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 krypton-85m Ci 4.74E+00 3.14E-01 5.69E-02 < LLD krypton-87 Ci 1.21E+01 6.23E+00 7.01E+00 6.59E+00 krypton-88 Ci 7.21E+00 7.13E-01 4.82E-01 < LLD xenon-133 Ci 1.23E+01 4.07E+00 3.29E+00 7.1OE+00 xenon-135 Ci 2.55E+01 1.43E+01 1.96E+01 3.02E+01 xenon-135m Ci 6.26E+01 4.42E+01 5.92E+01 5.83E+01 xenon-137 Ci 2.11E+02 1.30E+02 8.91E+01 9.23E+01 xenon-138 Ci 1.56E+02 '8.64E+01 1.24E+02 1.26E+02 total for period Ci 4.91E+02 2.87E+02 3.03E+02 3.2 1E+02

2. GASEOUS IODINES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 iodine-131 Ci 3.OOE-02 1.60E-02 9.43E-03 1.01E-02 iodine-132 Ci 1.40E-01 1.06E-01 5.03E-02 4.87E-02 iodine- 133 Ci 2.21E-01 1.56E-01 7.66E-02 8.05E-02 iodine-134 Ci 4.36E-01 3.35E-01 1.32E-01 1.03E-01 iodine-135 Ci 3.52E-01 2.66E-01 1.22E-01 1.24E-01 total for period Ci 1.18E+00 8.79E-01 3.90E-01 3.66E-01

3. PARTICULATES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 manganese-54 Ci < LLD < LLD < LLD < LLD cobalt-58 Ci < LLD < LLD < LLD < LLD cobalt-60 Ci 1.40E-05 9.37E-06 < LLD < LLD zinc-65 Ci < LLD < LLD < LLD < LLD strontium-89 Ci 1.35E-03 4.80E-04 3.90E-04 5.06E-04 strontium-90 Ci 1.88E-05 6.26E-06 2.48E-06 2.82E-06 ruthenium-106 Ci < LLD 1.61E-04 < LLD < LLD cesium-134 Ci < LLD < LLD 1.55E-06 < LLD cesium-137 Ci 2.08E-06 < LLD 2.70E-06 2.22E-06 barium- 140 Ci 3.53E-03 9.95E-04 1.54E-03 .1.12E-03 lanthanum-140 Ci 6.37E-03 1.67E-03 2.59E-03 2.02E-03 total for period Ci 1.13E-02 3.32E-03 4.53E-03 3.65E-03

4. TRITIUM Unit Quarter I Quarter 2 Quarter 3 Quarter 4 hydrogen-3 Ci 1.86E+01 3.40E+O1 3.70E+01 3.11E+01 Page 21 of 43

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

1. FISSION GASES Unit Quarter I Quarter 2 Quarter 3 Quarter 4 krypton-85m Ci 1.811E-02 < LLD " LLD < LLD krypton-87 Ci < LLD < LLD < LLD < LLD krypton-88 Ci < LLD < LLD < LLD < LLD xenon-133 Ci 1.57E+01 3.03E-01 2.69E-01 < LLD xenon- 135 Ci 8.87E+00 5.65E+00 7.1 OE+00 6.62E+00 xenon- 135m Ci 1.82E+01 8.72E+00 7.63E+00 6.37E+00 xenon-137 Ci < LLD < LLD < LLD < LLD xenon-138 Ci 1.67E-01 1.54E-01 < LLD < LLD total for period Ci 4.30E+01 1.48E+01 1.50E+01 1.30E+01

2. GASEOUS IODINES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 iodine-131 Ci 9.47E-03 3.55E-04 5.28E-04 5.30E-04 iodine-132 Ci 1.07E-02 3.88E-03 4.84E-03 6.42E-03 iodine-133 Ci 1.31E-02 3.26E-03 4.92E-03 5.23E-03 iodine-134 Ci 3.94E-02 7.08E-03 1.33E-02 1.i 1E-02 iodine-135 Ci 2.24E-02 7.26E-03 8.45E-03 1.05E-02 total for period Ci 9.50E-02 2.18E-02 3.20E-02 3.37E-02

3. PARTICULATES Unit Quarter I Quarter 2 Quarter 3 Quarter 4 chromium-51 Ci 3.49E-05 2.89E-05 < LLD < LLD manganese-54 Ci 2.71E-06 1.32E-06 < LLD < LLD cobalt-58 Ci 6.17E-06 4.84E-06 < LLD < LLD cobalt-60 Ci 1.24E-04 9.29E-05 2.43E-05 3.41E-05 zinc-65 Ci < LLD < LLD < LLD < LLD strontium-89 Ci 3.1IE-05 5.38E-06 5.47E-05 5.91E-06 strontium-90 Ci 7.98E-07 < LLD 5.12E-07 2.43E-07 cesium-134 Ci < LLD < LLD < LLD < LLD cesium-137 Ci 4.67E-06 < LLD < LLD < LLD barium- 140 Ci 1.32E-04 1.22E-05 < LLD < LLD lanthanum-140 Ci 2.78E-04 1.81E-05 < LLD < LLD cerium-141 Ci 6.20E-06 1.68E-07 < LLD < LLD total for period Ci 6.21E-04 1.64E-04 7.95E-05 4.03E-05

4. TRITIUM Unit Quarter I Quarter 2 Quarter 3 Quarter 4 hydrogen-3 Ci 3.92E+01 3.11E+01 3.02E+01 3.49E+01 Page 22 of 43

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

i. Total release Ci 1.32E-03 1.49E-03 1.89E-03 1.18E-03 4.OOE+01 (excluding tritium, gases, and alpha)

2. Average diluted concentration ACi/ml 1.17E-10 1.02E-10 1.08E-10 6.95E- 11 NA (NOTE 2)

3. Percent of 7.23E-03 6.37E-03 5.30E-03 4.26E-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 9.06E+01 7.80E+01 3.98E+01 5.45E+01 4.50E+01

2. Average diluted concentration 8.02E-06 5.36E-06 2.27E-06 3.20E-06 ACi/ml NA (NOTE 2)

3. Percent of applicable limit 8.02E-01 5.36E-01 2.27E-01 3.20E-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 3.31E-02 2.9 1E-02 1.84E-02 2.66E-02 4.00E+01

2. Average diluted concentration 2.93E-09 2.OOE-09 1.05E-09 1.56E-09 pCi/ml NA (NOTE 2)

3. Percent of applicable limit 1.46E-03 I.OOE-03 5.25E-04 7.80E-04 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 Collection Basin and/or Storm Drain Stabilization Pond)

Page 23 of 43

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 I Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total volume liters 2.32E+06 2.50E+06 2.33E+06 2.29E+06 1.50E+01 F. VOLUME OF DILUTION WATER Estimated Total Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total volume liters 1.13E+I0 1.46E+10 1.75E+10 1.70E+10 1.50E+01 (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 3.43E+ 1I 4.47E+ 11 5.02E+ 11 4.62E+I I 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 I Quarter 2 Quarter 3 Quarter 4 manganese-54 Ci < LLD 7.2 IE-05 2.64E-06 < LLD iron-55 Ci 5.26E-04 3.85E-04 < LLD < LLD cobalt-58 Ci < LLD 6.83E-05 1.95E-06 < LLD cobalt-60 Ci 7.37E-04 7.44E-04 3.19E-04 1.80E-04 strontium-89 Ci < LLD < LLD < LLD < LLD strontium-90 Ci < LLD < LLD < LLD < LLD iodine-131 Ci < LLD < LLD 7.81E-04 5.94E-04 iodine-133 Ci 3.35E-05 1.39E-05 7.04E-04 3.98E-04 iodine-135 Ci < LLD < LLD 1.36E-05 < LLD cesium-134 Ci 8.18E-07 3.OOE-05 5.14E-06 1.97E-06 cesium-137 Ci 2.34E-05 1.79E-04 5.86E-05 1.04E-05 barium-140 Ci < LLD < LLD < LLD < LLD lanthanum-140 Ci < LLD < LLD < LLD < LLD cerium-144 Ci < LLD < LLD <LLD < LLD total for period Ci 1.32E-03 1.49E-03 1.89E-03 1.18E-03

2. DISSOLVED AND ENTRAINED GASES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 krypton-85 Ci 5.57E-04 < LLD < LLD < LLD xenon-133 Ci 5.19E-03 4.63E-03 3.177E-03 4.19E-03 xenon-133m Ci < LLD 3.50E-05 <LLD < LLD xenon-135 Ci 2.73E-02 2.44E-02 1.52E-02 2.24E-02 xenon-135m Ci 4.41E-05 2.28E-05 <LLD 4.66E-06 total for period Ci 3.3 1E-02 2.91E-02 1.84E-02 2.66E-02 Page 25 of 43

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

1. LIQUID RELEASES 2. GASEOUS RELEASES Alpha 3.69E-08 Kr-85m 6.68E-09 H-3 2.58E-06 Kr-87 1.55E-08 Cr-51 1.48E-07 Kr-88 1.50E-08 Mn-54 2.33E-08 Xe- 133 1.40E-08 Fe-55 1.3 IE-07 Xe-133m 5.84E-08 Co-58 2.77E-08 Xe- 135 2.52E-09 Fe-59 3.96E-08 Xe-135m 2.12E-08 Co-60 2.65E-08 Xe- 137 6.70E-07 Zn-65 3.87E-08 Xe-138 4.14E-08 Sr-89 2.99E-08 Sr-90 1.33E-08 Mo-99 1.39E-07 3. IODINES AND PARTICULATES 1-131 1.82E-08 1-133 1.44E-08 Alpha 1.94E-15 1-135 6.57E-08 H-3 4.62E- 11 Cs-134 3.13E-08 Mn-54 7.64E- 13 Cs-137 2.50E-08 Co-58 9.63E-13 Ba-140 5.07E-08 Fe-59 2.08E-12 La- 140 4.28E-08 Co-60 1.18E-12 Ce-141 2.38E-08 Zn-65 1.86E-12 Ce- 144 1.06E-07 Sr-89 2.33E-15 Kr-85 5.40E-06 Sr-90 1.IE-15 Kr-87 4.35E-08 Mo-99 3.37E-12 Kr-88 7.32E-08 Ru- 106 6.42E- 12 Xe-133 4.27E-08 1-131 5.36E-13 Xe-133m 1.47E-07 Cs-134 9.55E-13 Xe-135 1.40E-08 Cs-137 8.47E-13 Xe-135m 6.78E-08 Ba-140 2.44E-12 Xe-138 1.90E-07 La-140 9.83E-13 Ce- 141 8.32E-13 Ce- 144 4.49E-12 NOTES:

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

Page 26 of 43

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) 9.08E+02 Total curie quantity (estimated) 5.35E+01

2. Type of Waste Estimated Total Unit Period %Error 3

a. Spent resins, filter, sludges meter 3.86E+01 Curies 5.24E+01 1.00E+01 3

b. Dry active waste, compacted/non-compacted meter 8.70E+02 Curies 1.16E+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 maior radionuclides composition

a. H-3 6.53E+00  %

Mn-54 1.65E+00  %

Fe-55 2.16E+01  %

Co-60 5.27E+01  %

Ni-63 1.09E+01  %

Zn-65 1.23E+00  %

Cs-134 1.15E+00  %

Cs- 137 3.38E+00  %

Ce- 144 1.44E+00  %

b. Mn-54 6.03E+00  %

Fe-55 2.04E+01  %

Co-60 6.87E+01  %

Ni-63 4.47E+00  %

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 27 of 43

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 GP 9.OE +00

b. Dry active waste Compacted/ Type A or GP 1.9E+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 5.OE+00 Highway Oak Ridge, TN 5.OE+00 Highway Erwin, TN 3.OE+00 Highway Richland, WA 9.OE+00 Rail Clive, UT 1.OE+00 Highway Clive, UT 5.OE+00 Highway Ashford, AL

b. Irradiated Fuel Number of Shipments Mode of Transportation Destination 0 N/A N/A Page 28 of 43

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) 1.77E+00 Total curie quantity (estimated) 1.89E+02

2. Type of Waste Estimated Total Unit Period %Error 3

a. Spent resins, filter, sludges meter 1.77E+00 Curies 1.89E+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 major radionuclides composition

a. Cr-51 1. 13E+00  %

Mn-54 2.83E+00  %

Fe-55 2.63E+01  %

Co-58 3.85E+00  %

Co-60 5.43E+01  %

Ni-63 0.77E+00  %

Zn-65 5.95E+00  %

Cs-134 1.55E+00  %

Cs-137 1.75E+00  %

b. N/A

c. N/A

d. N/A NOTE:

Solid Radioactive Waste was shipped either directly for disposal or to a waste processor for processing and then transported for disposal by the processor.

Page 29 of 43

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 2.00 E+00

b. Dry active waste J

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 2.00E+00 Highway Erwin, TN

b. Irradiated Fuel Number of Shipments Mode of Transportation Destination 0 N/A N/A Page 30 of 43

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) 6.65E+00 Total curie quantity (estimated) 4.72E+04

2. Type of Waste Estimated Total Unit Period %Error 3

a. Spent resins, filter, sludges meter 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 6.65E+00 Curies 4.72E+04 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. Mn-54 3.43E+00  %

Fe-55 5.71E+01  %

Co-60 2.86E+01  %

Ni-63 3.77E+00  %

Hf- 181 1.46E+00  %

Ta- 182 4.62E+00  %

d. N/A NOTE:

Solid Radioactive Waste was shipped either directly for disposal or to a waste processor for processing and then transported for disposal by the processor.

Page 31 of 43

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 Type B 3.OOE+00

d. Others (describe) N/A N/A

5. Shipment Disposition

a. Solid Waste Number of Shipments Mode of Transportation Destination 3.OOE+00 Highway ý" Barnwell, SC

b. Irradiated Fuel Number of Shipments Mode of Transportation Destination 7.OOE+00 Rail New Hill, NC Page 32 of 43

Attachment 3 Environmental Monitoring Program : Milk and Vegetable Sample Location : Land Use Census Page 33 of 43

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 34 of 43

Attachment 3 Environmental Monitoring Program Enclosure 2: Land Use Census The 2007 Land Use Census did not identify any locations that are reportable in the Radioactive Effluent Release Report for 2007.

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 None NE None None ENE None None E None None ESE 1.4 miles None SE None None SSE 2.1 miles None S 1.1 miles 1.7 miles SSW 1.2 miles 1.9 miles SW 1.1 miles 2.5 miles WSW 1.2 miles 1.2 miles W 0.9 miles 1.0 miles WNW 0.9 miles None NW 0.9 miles 4.9 miles NNW 0.8 miles 0.9 miles N 0.8 miles 1.0 miles Page 35 of 43

Attachment 4 Effluent Instrumentation : Radioactive Liquid Effluent Monitoring Instrumentation : Radioactive Gaseous Effluent Monitoring Instrumentation : Liquid Hold-Up Tank Page 36 of 43

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.

Page 38 of 43

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 39 of 43

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 50.7 1(e). No changes have been made during this reporting period.

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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 Summary Liquid Effluents (1)

Critical Age: Adult Controlling location for liquid releases: SW sector at 0.1 miles (mrem) Limit: (mrem)

GI-LLI 9.66E-04 2.OOE+01 Bone 3.25E-04 2.OOE+01 Liver 7.07E-04 2.OOE+01 Lung 5.68E-04 2.OOE+01 Total Body 5.58E-04 6.00E+00 Thyroid 1.27E-03 2.00E+01 Kidney 4.60E-04 2.OOE+01 Gaseous Effluents (1)

Noble Gas: Critical Age: Infant Controlling location: NE sector at 0.7 mile (mrad) Limit: (mrad)

Gamma 3.25E-02 2.00E+01 Beta 1.32E-02 4.OOE+01 Iodine, Particulates, and Tritium: Critical Age: Infant Controlling location: NE sector at 4.75 mile Assuming a cow milk pathway (mrem) Limit: (mrem)

Thyroid 4.62E-01 3.OOE+01 Kidney 3.45E-03 3.OOE+01 Liver 3.21E-03 3.OOE+01 Total Body 2.37E-03 3.00E+01 Skin 1.75E-03 3.OOE+OI GILLI 1.81E-03 3.00E+01 Lung 1.75E-03 3.OOE+01 Bone 1.50E-03 3.OOE+01 (1)Reference - dose determined using site specific ODCM software Page 42 of 43

Attachment 8 Off-Site Dose Calculation Manual, (ODCM) And Process Control Program (PCP) Revisions There were no revisions to the ODCM and no revisions to the PCP during the report period.

Page 43 of 43