BSEP 15-0032, Radioactive Effluent Release Report for 2014

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Radioactive Effluent Release Report for 2014
ML15133A322
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 04/30/2015
From: Pope A
Duke Energy Progress
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 15-0032
Download: ML15133A322 (47)
v • d • e


Text

Brunswick Nuclear Plant P.O. Box 10429 ENERGY, Southport, NC 28461 APR 3 O2015 Serial: BSEP 15-0032 10 CFR 50.36a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket No. 50-325 and 50-324 Radioactive Effluent Release Report for 2014 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, Duke Energy Progress, Inc., is submitting the enclosed Radioactive Effluent Release Report for BSEP Unit Nos. 1 and 2. This report covers the period from January 1, 2014, through December 31, 2014.

TS 5.5.1, "Offsite Dose Calculation Manual (ODCM)," requires changes to the ODCM be submitted as part of, or concurrent with, the Radioactive Effluent Release Report. The ODCM was not revised during the report period.

No regulatory commitments are contained in this submittal. Please refer any questions regarding this submittal to Mr. Lee Grzeck, Manager - Regulatory Affairs, at (910) 457-2487.

Annette H. Pope Director - Organizational Effectiveness Brunswick Steam Electric Plant AHS/ahs

Enclosure:

Radioactive Effluent Release Report for 2014 71

U.S. Nuclear Regulatory Commission Page 2 of 2 U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Victor M. McCree, Regional Administrator 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, GA 30303-1257 U. S. Nuclear Regulatory Commission ATTN: Ms. Michelle P. Catts, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission ATTN: Mr. Andrew Hon (Electronic Copy) 11555 Rockville Pike Rockville, MD 20852-2738 Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510 Mr. W. Lee Cox, Ill, Section Chief (Electronic Copy Only)

Radiation Protection Section North Carolina Department of Health and Human Services 1645 Mail Service Center Raleigh, NC 27699-1645 lee.cox@dhhs.nc.gov

BSEP 15-0032 Enclosure Radioactive Effluent Release Report for 2014

Brunswick Steam Electric Plant Radioactive Effluent Release Report January 1 through December 31, 2014 Table of Contents Attachment Pges

1. Effluent and Waste Disposal Report Supplemental 2 - 13 Information
2. Effluent and Waste Disposal Data 14-31
3. Environmental Monitoring Program 32 - 34
4. Effluent Instrumentation 35-38
5. Major Modification to the Radioactive Waste Treatment 39 Systems
6. Meteorological Data 40
7. Annual Dose Assessment 41-42
8. Off-Site Dose Calculation Manual (ODCM) and Process 43 Control Program (PCP) Revisions
9. Special Groundwater Protection 44 Page 1 of 44

Attachment 2 Effluent and Waste Disposal Report Supplemental Information Facility: Brunswick Steam Electric Plant Licensee: Duke Energy Progress, Inc.

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

(1) Calendar Quarter (a) 5 10 mrad gamma (b) 5 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 (a) < 3 mrem to total body (b) < 10 mrem to any organ (2) Calendar Year (a) 5 6 mrem to total body (b) < 20 mrem to any organ

2. Effluent concentration limits 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 Page 2 of 44

Attachment 2 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 in 10 CFR 20.1001 - 20.2401 for radionuclides other than dissolved or entrained noble gases. The concentration shall be limited to the value given in the ODCM specifications for the following radionuclides:

(1) Tritium: limit = L.OOE-03 gCi/ml '

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

E. Tritium Analysis by liquid scintillation.

Used as applicable limits for Attachment 2, Table 2A Total error where reported represents a best effort to approximate the total of all individual and sampling errors.

Page 3 of 44

Attachment 2 Effluent and Waste Disposal Report Supplemental Information

4. Batch Releases A. Liquid Jan - Jun Jul - Dec (1) Number of batch releases: 8.80E+O I 9.90E+01 (2) Total time period for batch releases (min): 1.47E+05 3.36E+05 (3) Maximum time period for a batch release (min): 3.16E+04 4.29E+04 (4) Average time period for a batch release (min): 1.67E+03 3.39E+03 (5) Minimum time period for a batch release (min): 1.OOE+00 1.OOE+00 (6) Average stream flow during periods of release of effluent into a flowing stream (gal/min): 6.09E+05 6.88E+05 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' 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 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 44

Attachment 2 Effluent and Waste Disposal Report Supplemental Information Discussion of liquid release from the BSEP Sewage Treatment Plant In accordance with the Brunswick Steam Electric Plant (BSEP) National Pollutant Discharge Elimination System (NPDES) Permit Number NC0007064 the decant from the BSEP Sewage Treatment Plant is released to Outfall Number 004. Outfall Number 004 discharges to the discharge canal which is a designated release point. The BSEP sewage decant is sampled monthly for gamma and tritium analysis. On December 11, 2013 the monthly effluent sample contained tritium, there was no detectable gamma activity. Condition Report (CR) 651320 was generated and daily sampling was initiated for effluent accountability. Inputs to the system were sampled and it was discovered that tritiated groundwater is leaking into the Number 6 lift station.

The source of tritium is from pre-existing groundwater contamination in the general area surrounding the Number 6 lift station. Regulatory Affairs confirmed this was not reportable per NEI 07-07 groundwater reporting. Work Order 13341340 was initiated to inspect and repair the Number 6 lift station. Approximately 1.20E+06 gallons containing 1.30E-02 curies of tritium was released in 2014 to the discharge canal.

Discussion of Carbon-14 in Gaseous Effluents 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+0 1 Ci/yr. This value was scaled using Effective Full Power Days (EFPD) to give a release rate of 2.20E+01 Ci/yr. Based on the 2014 Land Use Census, the critical receptor is located in the south sector at 1.8 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 2014 was 2.03E+00 mrem and the total body dose was 4.07E-0 I mrem.

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

During periods of heavy rain, 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 eighteen occasions in 2014 due to heavy rains.

Approximately 3.39E+06 gallons containing 2.55E-01 curies of tritium were released. There was no detectable gamma radioactivity.

Discussion of liquid releases from the Storm Drain Stabilization Pond (SDSP) Infiltration On August 22, 2014 water was found flowing from the Storm Drain Stabilization Facility (SDSF) outfall pipe into the intake canal when a permitted release was not in progress. The water was analyzed and found to contain tritium. Condition Report 704775 was generated and daily sampling was initiated for effluent accountability. Subsequent investigation determined the water was infiltrating through the side of the first collection box in the drainage line located near the SDSP discharge weir. The pipe was repaired by installing a fiberglass liner inside the existing outfall pipe and sealing the original pipe/liner interface. This repair was completed on March 24, 2015. Approximately 1.07E+05 gallons containing 2.75E-03 curies of tritium was released in 2014. There was no detectable gamma radioactivity.

Discussion of liquid releases from the Storm Drain Stabilization Facility (SDSF)

The SDSF collects rainwater, water from miscellaneous low volume drains on plant site, and water from the Groundwater Extraction System. Treatment consists of filtration and evaporation. When sufficient water has accumulated in the pond it is released into the intake Page 5 of 44

Attachment 2 Effluent and Waste Disposal Report Supplemental Information canal where it is drawn into the plant circulating and service water system and eventually released into the discharge canal. There were seventeen SDSF releases in 2014. Approximately 7.60E+07 gallons containing 8.43E+00 curies of tritium were released from the SDSF. There was no detectable gamma radioactivity.

Discussion of water evaporation from the Storm Drain Stabilization Pond It was calculated that 6.14E+07 gallons of tritiated water was released via evaporation from the SDSP in 2014. This yields 7.17E-01 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 2.20E-04 mrem via the inhalation pathway in 2014. 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.

Discussion of water evaporation from the Storm Drain Stabilization Facility It was calculated that 4.90E+06 gallons of tritiated water was released via evaporation from the SDSF in 2014. This yields 5.73E-01 curies of tritium released to the atmosphere as a ground release. The nearest resident to the facility is in the north northwest sector at approximately 0.5 miles. The maximum exposed individuals at that location received a calculated dose of 3.69E-04 mrem via the inhalation pathway in 2014. 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.

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. The sampling program consists of weekly sampling and analysis at eight locations. All gamma analyses performed in 2014 were less than the Lower Limit of Detection (LLD). There were 416 tritium analyses performed, which resulted in 30 positive tritium results. The average concentration each month, two high tides per day, the area of the marsh at high tide, the days in the month, and a conservative factor of 2 was used to calculated the amount of tritium released each month. In 2014, it was calculated that 5.38E+07 gallons were released to Nancy's Creek containing 1.29E-01 curies of tritium. This yielded a Total Body dose of 1.57E-03 mrem to an adult from eating fish and invertebrate (shrimp, crabs, etc.).

Discussion of Groundwater Monitoring The BSEP groundwater sampling and analysis program has grown into a significant surveillance program. Wells have been installed around the SDSP, in the Protected Area (PA), and throughout the Owner Controlled Area (OCA). Ten 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. These wells are used to evaluate groundwater movement and for remediation of the Unit 1 Condensate Storage Tank (CST) leak and the SDSP.

Page 6 of 44

Attachment 2 Effluent and Waste Disposal Report Supplemental Information Unit 1 CST Groundwater Wells - The investigation into groundwater impacts resulting from the December 2010 Unit 1 Condensate Storage Tank line leak resulted in the installation of numerous monitoring/recovery wells. Four of these wells (UICSTREM-01, U1CSTREM-07, U1CSTREM-08, and UlCSTREM-09) are installed in the Castle Hayne aquifer (greater than 70' below ground surface) to investigate and monitor potential impacts to the aquifer. Ten of these wells (U 1CSTREM-05, U 1CSTREM-02B, U ICSTREM-08, U 1CSTREM-09B, U ICSTREM-15, UICSTREM-21B, U1CSTREM-22B, U1CSTREM-27B, MW-01B, and MWPA- 1IB) are installed in the dense sand unit (45' - 70' below ground surface) to investigate and monitor impacts to this flow zone comprised of native material beneath the plant excavation backfill. At least three of these dense sand wells are planned to be used as recovery wells as part of the groundwater remediation effort. Twenty-four of these wells (U1CSTREM-02C, U1CSTREM-09C, U 1CSTEM- 10, U lCSTREM- 11, U lCSTREM- 12, U 1CSTREM- 13, U 1CSTREM- 14, U1CSTREM- 16, U1CSTREM- 18, U lCSTREM-19, U1CSTREM-2 1C, U 1CSTREM-22C, U 1CSTREM-23, U 1CSTREM-24, U 1CSTREM-25, U 1CSTREM-26, U 1CSTREM-27C, Ut CSTREM-28, U ICSTREM-29, U 1CSTREM-30, U lCSTREM-31, U 1CSTREM-32, U 1CSTREM-33, and MWPA-1 12C) are installed in the plant excavation backfill (up to 45' below ground surface) to investigate and monitor impacts to this flow zone where the leak occurred. At least fifteen of these wells are planned to be used as recovery wells as part of the groundwater remediation effort. Additional wells are planned for installation as part of the monitoring and remediation effort.

Several gamma analyses were performed and all results were less than LLD. Below are the tritium (H-3) results for the wells that are not included in the ODCM. Maps showing the locations of these wells are available upon request.

Shallow Wells for Plant Site Number Number of of Positive Average Minimum Maximum Depth of Well Name of H-3 H-3 Act H-3 Act H-3 Act Samples Samples in (pCi/L) (pCi/L) (pCi/L) Well (ft) in 2014 21 2014 ESS-2C 4 4 1.61E+04 1.40E+04 1.99E+04 27 ESS-3C 2 2 1.76E+03 1.20E+03 2.31E+03 14 ESS- 12C 2 0 <LLD <LLD <LLD 15 ESS-13C 5 2 7.34E+02 2.58E+02 1.21E+03 25 ESS- 16 4 4 1.18E+03 8.17E+02 1.64E+03 27 ESS- 17C 5 5 8.38E+03 4.63E+03 1.1OE+04 26 ESS-18C 4 4 2.53E+04 4.08E+03 5.53E+04 20 ESS-19C 5 5 1.57E+05 1.20E+05 2.37E+05 20 Page 7 of 44

Attachment 2 Effluent and Waste Disposal Report Supplemental Information Shallow Wells for Plant Site Number Number of of Positive Average Minimum Maximum Depth of Well Name ol H-3 H-3 Act H-3 Act H-3 Act Samples Samples in (pCi/L) (pCi/L) (pCi/L) Well (ft) in 2014 21 2014 ESS-20C 5 5 2.12E+04 9.21E+03 3.78E+04 20 ESS-21C 2 2 1.26E+03 8.30E+02 1.69E+03 20 ESS-22C 5 4 9.1OE+04 3.44E+03 2.86E+05 20 ESS-23C 3 3 1.69E+05 1.54E+05 1.87E+05 23 ESS-24C 3 3 4.46E+03 4.08E+03 4.68E+03 18 ESS-25C 4 0 < LLD < LLD < LLD 22 ESS-26C 3 3 4.36E+04 1.24E+04 7.78E+04 15 ESS-27C 2 2 1.67E+05 1.66E+05 1.68E+05 16 ESS-28C 2 2 7.21E+02 6.97E+02 7.44E+02 23 ESS-29C 2 0 < LLD < LLD < LLD 28 ESS-30C 4 4 9.14E+02 3.63E+02 2.04E+03 15 ESS-31C 4 1 3.16E+02 3.16E+02 3.16E+02 15 ESS-38C 1 0 < LLD < LLD < LLD 15 ESS-39C 1 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-44C 1 0 < LLD < LLD < LLD 15 ESS-45C 1 0 < LLD < LLD < LLD 21 ESS-46C 1 0 < LLD < LLD < LLD 18 ESS-48C 1 0 < LLD < LLD < LLD 18 ESS-49C 1 0 < LLD < LLD < LLD 19 Page 8 of 44

Attachment 2 Effluent and Waste Disposal Report Supplemental Information Shallow Wells for Plant Site Number Number of of Positive Average Minimum Maximum Depth of Well Name ol H-3 H-3 Act H-3 Act H-3 Act in 2014 Samples in (pCi/L) (pCi/L) (pCi/L) 2014 ESS-50C 1 0 < LLD < LLD < LLD 22 ESS-51C 1 0 < LLD < LLD < LLD 22 ESS-54C 2 0 < LLD < LLD < LLD 24 ESS-55C 2 0 < LLD < LLD < LLD 38 ESS-56C 2 0 < LLD < LLD < LLD 32 ESS-58C 1 0 < LLD < LLD < LLD 18 ESS-59C 1 0 < LLD < LLD < LLD 18 ESS-60C 1 0 < LLD < LLD < LLD 19 ESS-67C 4 1 6.74E+02 6.74E+02 6.74E+02 25 ESS-68C 1 0 < LLD < LLD < LLD 19 ESS-69C 2 0 < LLD < LLD < LLD 30 ESS-70C 2 0 < LLD < LLD < LLD 18 ESS-71C 2 0 < LLD < LLD < LLD 19 ESS-72C 4 2 6.50E+02 2.99E+02 1.00E+03 18 ESS-73C 2 0 < LLD < LLD < LLD 15 ESS-74C 2 0 < LLD < LLD < LLD 25 ESS-201C 3 3 1.22E+04 6.30E+03 2.14E+04 19 ESS-202C 4 4 3.77E+04 2.14E+04 5.75E+04 19 ESS-203C 3 3 3.23E+03 2.34E+03 4.47E+03 19 ESS-STAB 3 3 1.19E+04 7.92E+03 1.70E+04 31 ESS-NC-4A 2 2 5.69E+03 5.58E+03 5.80E+03 17 MW- 1 3 3 7.1OE+02 5.05E+02 1.11E+03 24 Page 9 of 44

Attachment 2 Effluent and Waste Disposal Report Supplemental Information Shallow Wells for Plant Site Number Number of of Positive Average Minimum Maximum Depth of Well Name of H-3 H-3 Act H-3 Act H-3 Act Samples Samples in (pCi/L) (pCi/L) (pCi/L) Well (ft) in 2014 21 2014 MW-2 2 1 4.16E+02 4.16E+02 4.16E+02 24 MW-3 3 1 2.68E+02 2.68E+02 2.68E+02 26 MWPA-100C 2 0 < LLD < LLD < LLD 30 MWPA-101C 1 1 3.58E+02 3.58E+02 3.58E+02 29 MWPA-102C 2 2 4.94E+02 4.40E+02 5.47E+02 30 MWPA-103C 2 1 6.25E+02 6.25E+02 6.25E+02 30 MWPA-104C 4 4 7.24E+03 5.13E+03 1.00E+04 29 MWPA-105C 2 2 1.01E+03 7.46E+02 1.27E+03 30 MWPA-106C 3 3 7.01E+02 5.82E+02 7.65E+02 29 MWPA-107C 5 5 2.50E+03 1.61E+03 5.1OE+03 29 MWPA-108C 3 3 6.54E+02 4.62E+02 9.60E+02 29 MWPA-109C 2 2 7.98E+02 7.11E+02 8.84E+02 29 MWPA- 11OC 3 3 1.02E+03 7.53E+02 1.24E+03 29 MWPA-1 13C 4 3 8.64E+02 6.47E+02 1.08E+03 25 MWPA-114C 3 3 2.63E+03 2.OOE+03 3.53E+03 30 MWPA-1 15C 3 3 7.84E+03 6.03E+03 1.06E+04 34 MWPA-116C 4 0 < LLD < LLD < LLD 30 MWPA-I 17C 4 4 6.49E+02 5.84E+02 6.92E+02 30 MWPA- 118C 7 7 9.77E+02 6.31E+02 1.16E+03 30 Page 10 of 44

Attachment 2 Effluent and Waste Disposal Report Supplemental Information Intermediate Wells for Plant Site Number Number of Positive Average Minimum Maximum Depth Well Name of H-3 H-3 Act H-3 Act H-3 Act of Well in 2014 Samples in (pCi/L) (pCi/L) (pCi/L) (ft) 2014 ESS-2B 1 0 < LLD < LLD < LLD 58 ESS-3B 2 0 < LLD < LLD < LLD 52 ESS-18B 4 3 4.36E+02 3.87E+02 5.11E+02 23 ESS-19B 4 4 4.91E+03 3.81E+03 5.89E+03 42 ESS-20B 4 0 < LLD < LLD < LLD 43 ESS-22B 5 5 1.61E+03 1.30E+03 1.84E+03 76 ESS-38B 1 0 < LLD < LLD < LLD 55 ESS-39B 1 0 < LLD < LLD < LLD 55 ESS-51B 2 0 < LLD < LLD < LLD 45 ESS-52B 2 0 < LLD < LLD < LLD 51 ESS-53B 3 0 < LLD < LLD < LLD 76 MWPA-104B 4 4 1.OOE+04 8.65E+03 1.1OE+04 59 MWPA-107B 5 5 3.64E+04 3.3 1E+04 4.09E+04 60 Unit 1 CST Groundwater Wells Number Number of Positive Average Minimum Maximum Depth Well Name of H-3 H-3 Act H-3 Act H-3 Act of Well Samples Samples in (pCi/L) (pCi/L) (pCi/L) (ft) in 2014 2014 MWPA-1I1B 261 256 1.01E+04 3.16E+03 2.46E+05 61 MWPA-I 12C 259 247 3.67E+04 8.87E+03 1.76E+05 33 UICSTREM-01' 0 0 N/A N/A N/A 85 UICSTREM-02B 1 0 < LLD < LLD < LLD 68 Was not monitored in 2014 but will be used in the future for UI CST remediation monitoring.

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Attachment 2 Effluent and Waste Disposal Report Supplemental Information Unit 1 CST Groundwater Wells Number Number of Positive Average Minimum Maximum Depth Well Name of H-3 H-3 Act H-3 Act H-3 Act of Well Samples Samples in (pCi/L) (pCi/L) (pCi/L) (ft) in 2014 2014 UICSTREM-02C 258 258 6.42E+04 3.02E+03 2.40E+06 45 UICSTREM-05 5 0 < LLD < LLD < LLD 65 U ICSTREM-07 2 0 < LLD < LLD < LLD 85 U1CSTREM-08 16 4 3.22E+03 2.97E+03 3.46E+03 68 UICSTREM-09 4 0 < LLD < LLD < LLD 85 U1CSTREM-09B 4 2 3.33E+03 3.01E+03 3.65E+03 68 UICSTREM-09C 4 1 3.16E+03 3.16E+03 3.16E+03 45 U1CSTREM-10 3 0 < LLD < LLD < LLD 45 UICSTREM-11 4 0 < LLD < LLD < LLD 40 UICSTREM-12 3 1 2.43E+04 2.43E+04 2.43E+04 34 U1CSTREM-13 264 264 1.68E+05 4.13E+03 5.99E+05 44 UICSTREM-14 264 264 8.81E+04 5.68E+03 6.31E+05 44 UICSTREM-15 265 265 4.66E+04 1.52E+04 1.43E+05 59 UICSTREM-16 266 266 1.37E+05 4.07E+04 2.71E+05 40 UICSTREM-18 264 264 2.14E+06 1.76E+04 4.63E+06 29 U1CSTREM-19 263 263 1.25E+05 6.76E+03 3.74E+06 40 UICSTREM-21B 15 11 1.41E+04 3.OOE+03 1.14E+05 69 U1CSTREM-21C 4 3 4.07E+03 3.83E+03 4.23E+03 45 UICSTREM-22B 3 0 < LLD < LLD < LLD 69 UICSTREM-22C 246 185 7.46E+03 2.95E+03 2.42E+05 45 U1CSTREM-23 222 221 1.78E+04 3.41E+03 2.07E+05 45 U1CSTREM-24 254 253 3.29E+04 1.36E+04 5.1OE+04 29 UICSTREM-25 264 264 4.63E+04 3.05E+03 7.78E+05 45 Page 12 of 44

Attachment 2 Effluent and Waste Disposal Report Supplemental Information Unit 1 CST Groundwater Wells Number Number of Positive Average Minimum Maximum Depth Well Name of H-3 H-3 Act H-3 Act H-3 Act of Well in 2014 Samples in (pCi/L) (pCi/L) (pCi/L) (ft) 2014 U1CSTREM-26 14 6 2.46E+04 3.95E+03 1.14E+05 45 UICSTREM-27B 5 1 4.40E+03 4.40E+03 4.40E+03 68 U1CSTREM-27C 5 1 3.85E+03 3.85E+03 3.85E+03 45 UICSTREM-28 2 0 < LLD < LLD < LLD 45 U1CSTREM-29 198 198 8.16E+04 3.18E+03 2.34E+05 45 U1CSTREM-30 200 166 1.42E+04 2.73E+03 1.11 E+06 45 UICSTREM-31 165 73 9.44E+03 2.91E+03 1.81E+05 46 U1CSTREM-32 5 0 < LLD < LLD < LLD 45 U1CSTREM-33 217 216 1.50E+04 5.76E+03 1.46E+05 45 MW-lB 17 13 2.82E+04 3.21E+03 4.64E+04 45 Page 13 of 44

Attachment 2 Effluent and Waste Disposal Data Table IA Gaseous Effluents - Summation of all Releases Table lB Gaseous Effluents - Elevated Releases Table IC Gaseous Effluents - Ground Level Releases Table ID Gaseous Effluents - Mixed Mode Releases Table 2A Liquid Effluents - Summation of all Releases (Discharge Canal)

Liquid Effluents - Summation of all Releases (Marsh Area)

Table 2B Liquid Effluents - Batch Mode Table 2C Liquid Effluents - Continuous 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 14 of 44

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 3.40E+O1 2.26E+01 5.46E+O 1 2.90E+O 1 2.50E+O 1
2. Average release rate for period gCi/sec 4.37E+00 2.88E+00 6.87E+00 3.65E+00 NA B. IODINES Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error
1. Total Iodine - 131 release Ci 1.09E-03 1.45E-03 1.87E-03 1.38E-03 2.50E+01
2. Average release rate for period gCi/sec 1.40E-04 1.84E-04 2.3513-04 1.74E-04 NA C. PARTICULATES Estimated Total Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Percent Error
1. Total release Ci 3.07E-04 2.92E-04 3.37E-04 3.02E-04 2.50E+O1
2. Average release rate for period gCi/sec 3.95E-05 3.72E-05 4.24E-05 3.8 1E-05 NA
3. Gross Alpha Ci 2.60E-08 2.07E-09 < LLD < LLD 2.50E+O 1 D. TRITIUM Estimated Total Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Percent Error
1. Total release Ci 1.22E+02 8.48E+01 1.95E+02 1.66E+02 1.50E+01
2. Average release rate for period gCi/sec 1.57E+01 1.08E+O1 2.45E+O I 2.08E+O1 NA E. CARBON-14 Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error
1. Total release Ci 4.66E+00 5.40E+00 6.OOE+00 5.99E+00 NA
2. Average release rate for period gCi/sec 5.99E-01 6.87E-01 7.55E-01 7.54E-0 1 NA Page 15 of 44

Attachment 2 Effluent and Waste Disposal Data Table IB: Gaseous Effluents - Elevated Releases Continuous Release Nuclides Released I. FISSION AND ACTIVATION GASES Unit Quarter I Quarter 2 Quarter 3 Quarter 4 argon-41 Ci < LLD 2.54E+00 < LLD < LLD xenon-135m Ci < LLD < LLD 3.66E+00 1.45E+00 xenon-135 Ci 7.54E+00 5.87E+00 1.12E+01 1.41E+01 xenon-138 Ci 4.74E-01 3.24E-01 2.19E+01 <LLD total for period Ci 8.02E+00 8.74E+00 3.67E+01 1.55E+01

2. IODINES Unit Quarter I Quarter 2 Quarter 3 Quarter 4 iodine-131 Ci 5.16E-04 7.52E-04 9.51E-04 6.71E-04 iodine-133 Ci 3.04E-03 5.95E-03 8.49E-03 5.54E-03 iodine- 135 Ci 5.27E-03 1.04E-02 1.50E-02 9.73E-03 total for period Ci 8.82E-03 1.7 IE-02 2.44E-02 1.59E-02
3. PARTICULATES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 cobalt-60 Ci 1.6 1E-06 < LLD < LLD < LLD strontium-89 Ci 1.08E-05 2.57E-05 2.50E-05 2.57E-05 strontium-90 Ci < LLD < LLD 6.87E-08 4.68E-09 silver-i I10m Ci < LLD < LLD 5.83E-06 4.99E-07 barium- 140 Ci 2.39E-05 8.89E-05 1.01E-04 8.8 1E-05 lanthanum- 140 Ci 3.60E-05 1.31E-04 1.69E-04 1.57E-04 total for period Ci 7.23E-05 2.46E-04 3.01E-04 2.7 1E-04
4. TRITIUM Unit Quarter I Quarter 2 Quarter 3 Quarter 4 hydrogen-3 Ci 1.55E+01 2.08E+01 5.65E+01 4.18E+01
5. GROSS ALPHA Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 gross alpha Ci < LLD < LLD < LLD < LLD
6. CARBON-14 Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Carbon- 14 Ci 1.86E+00 2. 16E+00 2.40E+00 2.40E+00 Page 16 of 44

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

1. FISSION AND ACTIVATION GASES Unit Quarter I Quarter 2 Quarter 3 Quarter 4 xenon-133 Ci < LLD < LLD 6.46E-02 < LLD xenon-135 Ci 2.60E+O1 1.39E+01 1.78E+01 4.58E+00 xenon-138 Ci < LLD < LLD < LLD 8.89E+00 total for period Ci 2.60E+O I 1.39E+01 1.79E+01 1.35E+01
2. IODINES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 iodine- 131 Ci 5.65E-04 6.77E-04 8.66E-04 6.83E-04 iodine-133 Ci 6.33E-03 7.98E-03 1.09E-02 7.69E-03 iodine-135 Ci 1.24E-02 1.72E-02 2.47E-02 1.79E-02 total for period Ci 1.93E-02 2.59E-02 3.64E-02 2.63E-02
3. PARTICULATES Unit Quarter I Quarter 2 Quarter 3 Quarter 4 cobalt-57 Ci < LLD < LLD < LLD 1.4 1E-06 cobalt-60 Ci 3.33E-06 2.72E-07 < LLD < LLD strontium-89 Ci 6.16E-07 5.95E-06 1.25E-05 1. 14E-05 total for period Ci 3.95E-06 6.23E-06 1.25E-05 1.28E-05
4. TRITIUM Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 hydrogen-3 Ci 1.02E+02 5.77E+01 1.29E+02 1.16E+02
5. GROSS ALPHA Unit Quarter I Quarter 2 Quarter 3 Quarter 4 gross alpha Ci 2.60E-08 2.07E-09 < LLD < LLD
6. CARBON-14 Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 carbon- 14 Ci 9.32E-01 1.08E+00 1.20E+00 1.20E+00 Page 17 of 44

Attachment 2 Effluent and Waste Disposal Data Table ID: Gaseous Effluents - Mixed Mode Releases Continuous Release Nuclides Released

1. FISSION AND ACTIVATION GASES Unit Quarter I Quarter 2 Quarter 3 Quarter 4 total for period Ci < LLD < LLD < LLD < LLD
2. GASEOUS IODINES Unit Quarter I Quarter 2 Quarter 3 Quarter 4 iodine- 13 1 Ci 6.86E-06 1.96E-05 5.27E-05 2.53E-05 iodine-133 Ci 1. 11E-04 2.12E-04 3.24E-04 2.9 1E-04 total for period Ci 1.18E-04 2.32E-04 3.77E-04 3.17E-04
3. PARTICULATES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 chromium-51 Ci 1.04E-04 1.90E-05 < LLD < LLD manganese-54 Ci 2.49E-06 3.49E-07 < LLD < LLD cobalt-58 Ci 1.1 OE-05 3.50E-07 1.29E-06 < LLD cobalt-60 Ci 8.24E-05 2.09E-05 2.23E-05 1.83E-05 zinc-65 Ci 1.29E-05 < LLD < LLD < LLD strontium-89 Ci < LLD < LLD 2.36E-07 1.68E-08 cesium- 137 Ci 1.75E-06 < LLD <LLD < LLD total for period Ci 2.14E-04 4.06E-05 2.38E-05 1.83E-05
4. TRITIUM Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 hydrogen-3 Ci 4.70E+00 6.32E+00 9.18E+00 7.59E+00
5. GROSS ALPHA Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 gross alpha Ci < LLD < LLD < LLD < LLD
6. CARBON-14 Unit Quarter I Quarter 2 Quarter 3 Quarter 4 carbon-14 Ci 1.86E+00 2.16E+00 2.40E+00 2.40E+00 Page 18 of 44

Attachment 2 Effluent and Waste Disposal Data Table 2A: Liquid Effluents - Summation of all Releases (Discharge Canal)

A. FISSION AND ACTIVATION PRODUCTS (NOTE 1)

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

1. Total release Ci 4.91E-03 5.26E-04 6.57E-04 1.28E-04 i.70E+01 (excluding tritium, gases, and alpha)
2. Average diluted concentration gCi/ml 1.44E- I1 1.12E- 12 1.25E- 12 2.73E- 13 NA
3. Percent of applicable limit 3.03E-05 5.06E-06 4.73E-06 1. 11E-06 NA B. TRITIUM (NOTE 1)

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

1. Total release Ci 5.08E+O1 1.51E+O1 5.14E+OI 1.33E+01 2.30E+OI
2. Average diluted concentration 1.49E-07 3.22E-08 9.80E-08 2.84E-08 liCi/ml NA
3. Percent of applicable limit 1.49E-03 3.22E-04 9.80E-04 2.84E-04 NA C. DISSOLVED AND ENTRAINED GASES (NOTE 1)

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

1. Total release Ci 2.34E-04 7.34E-05 2.33E-04 2.77E-05 1.70E+01
2. Average diluted concentration 6.87E- 13 1.56E- 13 4.43E- 13 5.90E-14

.tCi/ml NA

3. Percent of applicable limit 3.44E-07 7.82E-08 2.22E-07 2.95E-08 NA D. GROSS ALPHA RADIOACTIVITY (NOTE 1)

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

1. Total release Ci < LLD < LLD < LLD < LLD 3.20E+O 1 NOTE 1: Includes releases from Radwaste, SDCB. SDSP, SDSP Infiltration, SDSF. and BSEP Effluent.

Page 19 of 44

Attachment 2 Effluent and Waste Disposal Data Table 2A: Liquid Effluents - Summation of all Releases (Discharge Canal)

E. PRIMARY WASTE VOLUME RELEASED (NOTE 2)

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

1. Total volume liters 2.79E+06 2.42E+06 4.40E+06 8.73E+05 1.50E+01 F. SECONDARY WASTE VOLUME RELEASED (NOTE 3)

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

1. Total volume liters 9.60E+07 5.88E+07 8.79E+07 6.29E+07 1.50E+01 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 3.41E+1I 4.70E+11 5.25E+11 4.70E+11 1.50E+01 NOTE 2: This is the volume released from Radwaste.

NOTE 3: This is the volume released from the SDCB, SDSP. SDSP Infiltration, SDSF. and BSEP Effluent Page 20 of 44

Attachment 2 Effluent and Waste Disposal Data Table 2A: Liquid Effluents - Summation of all Releases (Marsh Area)

A. FISSION AND ACTIVATION PRODUCTS Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total release Ci < LLD < LLD < LLD < LLD 1.70E+OI (excluding tritium, gases, and alpha)
2. Average diluted NA NA NA NA concentration gCi/ml NA
3. Percent of applicable limit NA NA NA NA NA B. TRITIUM Estimated Total Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Percent Error
1. Total release Ci 2.45E-02 2.07E-02 4.86E-02 3.55E-02 2.30E+01
2. Average dilutedZý .4.8S.

concentration gCi/ml )E-07 4.07E-07 9.47E-07 6.93E-07 NA

3. Percent of applicable limit %4"8 )E-03 4.07E-03 9.47E-03 6.93E-03 NA C. DISSOLVED AND ENTRAINED GASES Estimated Total Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Percent Error
1. Total release Ci < LLD < LLD < LLD < LLD 1.70E+OI
2. Average diluted concentration gCi/ml NA NA NA NA NA
3. Percent of applicable limit  % NA NA NA NA 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 3.20E+OI Page 21 of 44

Attachment 2 Effluent and Waste Disposal Data Table 2A: Liquid Effluents - Summation of all Releases (Marsh Area)

E. PRIMARY WASTE VOLUME RELEASED Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total volume liters NA NA NA NA 1.50E+01 F. SECONDARY WASTE VOLUME RELEASED Estimated Total Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Percent Error
1. Total volume liters 5.02E+07 5.07E+07 .5.13E+07 5.13E+07 1.50E+01 G. DILUTION WATER VOLUME DURING PERIOD Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error
1. Total volume liters 5.02E+07 5.07E+07 5.13E+07 5.13E+07 1.50E+01 Page 22 of 44

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

1. FISSION AND ACTIVATION PRODUCTS (NOTE 1)

Unit Quarter I Quarter 2 Quarter 3 Quarter 4 manganese-54 Ci 5.07E-05 4.44E-06 < LLD < LLD cobalt-58 Ci 1.39E-04 < LLD < LLD < LLD cobalt-60 Ci 2.69E-03 2.60E-04 3.81E-05 2.588E-05 nickel-63 Ci 1.03E-03 < LLD < LLD < LLD zinc-65 Ci 3.58E-06 < LLD < LLD " LLD antimony-124 Ci < LLD 1.29E-06 < LLD < LLD antimony-125 Ci 8.95E-04 1.38E-05 < LLD < LLD iodine-131 Ci 3.13E-05 8.05E-05 1.69E-04 3.48E-05 iodine- 133 Ci 7.94E-06 1.13E-04 4.47E-04 3.93E-05 iodine- 135 Ci < LLD < LLD < LLD 2.6 1E-05 cesium- 134 Ci 1.00E-05 < LLD < LLD < LLD cesium-137 Ci 4.26E-05 5.34E-05 2.38E-06 2.30E-06 cesium-138 Ci 9.25E-06 < LLD < LLD < LLD tungsten- 18 7 Ci 5.05E-06 < LLD < LLD < LLD total for period Ci 4.9 1E-03 5.26E-04 6.57E-04 1.28E-04

2. DISSOLVED AND ENTRAINED GASES (NOTE 1)

Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 krypton-88 Ci 4.82E-07 < LLD < LLD < LLD xenon-133 Ci 2.15E-05 8.7 1E-06 1.40E-05 4.5 1E-06 xenon-135 Ci 2.12E-04 6.47E-05 2.19E-04 2.32E-05 total for period Ci 2.34E-04 7.34E-05 2.33E-04 2.77E-05

3. TRITIUM (NOTE 1)

Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 hydrogen-3 Ci 5.08E+01 1.51E+01 5.14E+01 1.33E+01

4. GROSS ALPHA (NOTE 1)

Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 gross alpha Ci < LLD < LLD < LLD < LLD NOTE 1: Includes releases from Radwaste, SDCB. SDSP, SDSP Infiltration, and SDSF.

Page 23 of 44

Attachment 2 Effluent and Waste Disposal Data Table 2C: Liquid Effluents - Continuous Mode Nuclides Released

1. FISSION AND ACTIVATION PRODUCTS (NOTE 1)

Unit Quarter I Quarter 2 Quarter 3 Quarter 4 total for period Ci < LLD < LLD < LLD < LLD

2. DISSOLVED AND ENTRAINED GASES (NOTE 1)

Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 total for period Ci < LLD < LLD < LLD < LLD

3. TRITIUM (NOTE 1)

Unit Quarter I Quarter 2 Quarter 3 Quarter 4 hydrogen-3 Ci 2.45E-02 2.07E-02 5.76E-02 3.95E-02

4. GROSS ALPHA (NOTE 1)

Unit Quarter I Quarter 2 Quarter 3 Quarter 4 gross alpha Ci < LLD < LLD < LLD < LLD NOTE 1: Includes releases from BSEP Effluent and Marsh Area.

Page 24 of 44

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

1. LIQUID RELEASES 2. GASEOUS RELEASES Alpha 2.29E-08 Ar-41 1.17E-08 H-3 2.86E-06 Kr-85 2.59E-06 H-3 2.74E-07* Kr-85m 7.98E-09 Cr-51 1.49E-07 Kr-87 2.60E-08 Mn-54 1.62E-08 Kr-88 2.62E-08 Fe-55 5.25E-07 Xe- 133 2.11E-08 Co-58 1.59E-08 Xe-133m 6.56E-08 Fe-59 1.82E-08 Xe- 135 8.12E-09 Co-60 1.71 E-08 Xe-135m 9.64E-08 Ni-63 2.38E-07 Xe- 137 1.38E-06 Zn-65 2.90E-08 Xe- 138 2.63E-07 Zn-69m 1.95E-08 Sr-89 1.49E-08 3. IODINES AND PARTICULATES Sr-90 1.56E-08 Alpha 1.211E-15 Nb-95 1.69E-08 H-3 3.43E- 1I Zr-95 3.57E-08 Cr-51 2.70E- 12 Mo-99 1.15E-07 Mn-54 5.07E- 13 Tc-99m 1.53E-08 Co-57 2.93E- 13 Ag- 110m 2.42E-08 Co-58 6.09E- 13 Sb- 124 2.17E-08 Fe-59 1.02E- 12 1-131 2.34E-08 Co-60 3.98E- 13 1-133 1.71E-08 Zn-65 6.62E- 13 Cs- 134 2.09E-08 Sr-89 8.53E-15 1-135 7.OOE-08 Sr-90 3.51 E- 15 Cs- 137 2.21E-08 Nb-95 3.32E- 13 Cs-138 4.63E-08 Mo-99 3.95E- 12 Ba- 140 8.60E-08 Ag-I 10m 5.22E- 13 La-140 3.33E-08 1-131 3.79E-13 Ce- 141 2.58E-08 1-133 1.14E- 12 Ce- 144 1.30E-07 Cs- 134 4.65E-13 W-187 7.53E-08 1-135 7.25E- 12 Kr-87 4.78E-08 Cs- 137 4.12E- 13 Kr-88 6.33E-08 Ba-140 1.17E- 12 Xe- 133 5.65E-08 La- 140 5.64E- 13 Xe- 133m 1.33E-07 Ce- 141 4.56E- 13 Xe- 135 1.47E-08 Ce- 144 2.25E- 12 Xe-135m 8.87E-08 Xe-138 1.84E-07 NOTES:
1. The above values represent typical "a priori" LLDs for isotopes where values of "< LLD" are indicated in Tables IA. IB, IC. ID, 2A, 2B, and 2C. 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 25 of 44

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) 1.83E+03 Total curie quantity (estimated) 3.64E+O 1
2. Type of Waste Estimated Total Unit Period %Error 3
a. Spent resins, filter, sludges meter 4.81 E+O 1 Curies 3.33E+O0 1.OOE+O1 3
b. Dry active waste, compacted/non-compacted meter 1.78E+03 Curies 3.06E+00 1.00E+0 I 3
c. Irradiated components meters O.OOE+00 Curies O.OOE+00 N/A 3
d. Others (describe) meters 8.50E+00 Oily water/water Curies 1.22E-02 1.00E+01
3. Estimate of maior radionuclides composition
a. C-14 2.99E+00  %

Mn-54 1.82E+00  %

Fe-55 1.71E+01  %

Co-60 6.29E+01  %

Ni-63 1.04E+01  %

Cs- 137 2.06E+00  %

b. Mn-54 3.68E+00  %

Fe-55 2.98E+01  %

Co-60 6.03E+01  %

Ni-63 1.15E+00  %

Cs- 137 0.88E+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 26 of 44

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/filters Dewatered Type A or GDP 1.50 E+O l
b. Dry active waste Compacted/ Type A or GDP 4.OOE+O I Non-compacted C. Irradiated components N/A N/A
d. Others (describe) Type A or GDP 2.OOE+00 Oily water/water
5. Shipment Disposition
a. Solid Waste Number of Shipments Mode of Transportation Destination 5.50E+O I Highway Oak Ridge, TN 2.OOE+00 Highway Wampum, PA
b. Irradiated Fuel Number of Shipments Mode of Transportation Destination 0 N/A N/A Page 27 of 44

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) O.OOE+00 Total curie quantity (estimated) O.OOE+00
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 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. N/A
b. N/A
c. N/A
d. N/A NOTE:

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

Page 28 of 44

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 A/Type B 0.00 E+00
b. Dryd active waste Comvacted/ 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 0.00E+00 N/A N/A
b. Irradiated Fuel Number of Shipments Mode of Transportation Destination 0.OOE+00 N/A N/A Page 29 of 44

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 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 O.OOE+00 Curies O.OOE+00 N/A 3
d. Others (describe) meters 0.00E+00 Curies O.OOE+00 N/A
3. Estimate of maior 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.

Page 30 of 44

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 31 of 44

Attachment 3 Environmental Monitoring Program : Milk and Vegetable Sample Location : Land Use Census Page 32 of 44

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 33 of 44

Attachment 3 Environmental Monitoring Program Enclosure 2: Land Use Census 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 None SE None None SSE 2.1 miles None S 1.1 miles 1.8 miles SSW 1.2 miles 1.9 miles SW 1.1 miles 1.4 miles WSW 1.2 miles 1.3 miles W 0.9 miles 1.1 mile WNW 0.9 miles 1.0 miles NW 0.9 miles 4.9 miles NNW 0.8 miles 0.9 miles N 0.7 miles 1.0 miles Based on the 2014 Land Use evaluation the ODCM controlling location of 4.75 miles in the North-East sector using a hypothetical cow milk-infant pathway may not be the most conservative.

Brunswick has continued to report in this location due to NRC Task Interface Agreement 2009-04.

Unit 2 Once Through Ventilation and Carbon-14 dose reporting are the main drivers for the location change. Condition Report 682424 has been generated to determine the most appropriate reporting location and to update the Environmental Monitoring Program to support this change. An industry expert is currently reviewing the data to recommend any necessary changes.

Page 34 of 44

Attachment 4 Effluent Instrumentation : Radioactive Liquid Effluent Monitoring Instrumentation : Radioactive Gaseous Effluent Monitoring Instrumentation : Liquid Hold-Up Tank Page 35 of 44

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 36 of 44

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 37 of 44

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 38 of 44

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). There were no major modifications to the Radioactive Waste Treatment System during the reporting period.

Page 39 of 44

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 40 of 44

Attachment 7 Annual Dose Assessment Liquid Effluents Critical Age: Adult Controlling Location for Routine ODCM Liquid Releases: SW sector at 0.1 miles Supplemental Marsh"')

Dose*

mrem 1.57E-03

  • Reference page 6 of Supplemental Information for a discussion of the Marsh release.

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

GI-LLI 1.29E-04 1.57E-03 1.70E-03 2.OOE+0 1 Bone 3.02E-05 O.OOE+00 3.02E-05 2.OOE+01 Liver 7.40E-05 1.57E-03 1.64E-03 2.OOE+O1 Lung 6.67E-05 1.57E-03 1.64E-03 2.OOE+O1 Total Body 7.58E-05 1.57E-03 1.65E-03 6.OOE+00 Thyroid 8.89E-05 1.57E-03 1.66E-03 2.OOE+O I Kidney 6.79E-05 1.57E-03 1.64E-03 2.OOE+01

  • 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 41 of 44

Attachment 7 Annual Dose Assessment Gaseous Effluents Noble Gas:

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

Gamma 3.97E-02 2.OOE+O1 Beta 3.74E-02 4.OOE+01 Iodine, Particulates, and Tritium:

Supplemental SDSP 2 SDSF Carbon- 14 (All Carbon-14 D2Evaporation Evaporation( 3 ) except Bone Dose* and Skin) (4) (Bone) (4) mrem 2.20E-04 3.69E-04 4.07E-0I 2.03E+00

  • Reference page 5-6 of Supplemental Information Critical Age: Infant Controlling Location for Routine ODCM Dose: NE sector at 4.75 mile, assuming a cow milk pathway Routine ODCM Dose Supplemental Dose (mrem) (mrem)*(2)( 3)(4) Total Dose (mrem) Limit (mrem)

Thyroid 8.54E-02 4.08E-0 I 4.93E-0 1 3.OOE+0 I Kidney 1.36E-02 4.08E-01 4.22E-01 3.OOE+01 Liver 1.36E-02 4.08E-0I 4.22E-01 3.OOE+01 Total Body 1.35E-02 4.08E-01 4.22E-01 3.OOE+01 GI-LLI 1.34E-02 4.08E-01 4.2 1E-01 3.OOE+01 Lung 1.34E-02 4.08E-01 4.21E-01 3.OOE+01 Bone 2.85E-04 2.03E+00 2.03E+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 SDSF evaporation is the NNW sector at approximately 0.5 miles assuming inhalation pathway only, since no garden is present. The critical age is a teen. Reference page 6 of supplemental information.

(4)The controlling location for the Carbon-14 supplemental dose is the south sector at 1.8 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.

The ODCM was not revised during the report period.

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Attachment 9Protection Special Groundwater "9 No special reports were made as a result of any radioactive spills or leaks.

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