Text

Radioactive Effluent Release Report for 2013
	ML14115A408
Person / Time
Site:	Brunswick
Issue date:	04/23/2014
From:	Pope A; Duke Energy Progress
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	BSEP 14-0038
	Download: ML14115A408 (376)
	v • d • e

DUKE~

ENERGY, Brunswick Nuclear Plant P.O. Box 10429 Southport, NC 28461 APR 2 3 2014 Serial: BSEP 14-0038 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 Nos. 50-325 and 50-324 Radioactive Effluent Release Report for 2013 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, 2013, through December 31, 2013. The report is included as .

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. A copy of Revision 37 of the BSEP ODCM, current as of October 29, 2013, is included as Enclosure 2.

Changes made to the ODCM during 2013 are summarized in the 2013 Radioactive Effluent Release Report.

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.

Sin rely, Anne te H.!Pope Director - Organizational Effectiveness Brunswick Steam Electric Plant AHP/ahs

U.S. Nuclear Regulatory Commission Page 2 of 2

Enclosures:

1. Radioactive Effluent Release Report for 2013

2. Offsite Dose Calculation Manual, Revision 37 cc (with Enclosure 1 only):

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. Siva P. Lingam (Mail Stop OWFN 8G9A) (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)

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

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Brunswick Steam Electric Plant Radioactive Effluent Release Report January 1 through December 31, 2013 Table of Contents Attachment Pages

1. Effluent and Waste Disposal Report Supplemental 2- 13 Information

2. Effluent and Waste Disposal Data 14-28

3. Environmental Monitoring Program 29-31

4. Effluent Instrumentation 32-35

5. Major Modification to the Radioactive Waste Treatment 36 Systems

6. Meteorological Data 37

7. Annual Dose Assessment 38-39

8. Off-Site Dose Calculation Manual (ODCM) and Process 40 -44 Control Program (PCP) Revisions

9. Special Groundwater Protection 45 Page 1 of 45

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) < 10 mrad gamma (b) *20 mrad beta (2) Calendar Year (a) < 20 mrad gamma (b) *40 mrad beta B. Iodine-13 1, 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)

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 Page 2 of 45

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 to 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 = 1.OOE-03 ýtCi/ml 1 (2) Dissolved and entrained noble gases: limit = 2.00E-04 [tCi/ml 1

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

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

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

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

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.

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Attachment 2 Effluent and Waste Disposal Report Supplemental Information

4. Batch Releases A. Liquid Jan - Jun Jul - Dec (1) Number of batch releases: 1.34E+02 1.16E+02 (2) Total time period for batch releases (min): 1.69E+05 1.08E+05 (3) Maximum time period for a batch release (min): 4.15E+04 3.01E+04 (4) Average time period for a batch release (min): 1.26E+03 9.27E+02 (5) Minimum time period for a batch release (min): 1.1OE+01 9.OOE+00 (6) Average stream flow during periods of release of effluent into a flowing stream (gal/min): 6.12E+05 8.22E+05 B. Gaseous (1) Number of batch releases: 0.OOE+00 (2) Total time period for batch releases: 0.OOE+00 Minutes (3) Maximum time period for a batch release: 0.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 2

5. Abnormal Releases A. Liquid (1) Number of releases: 0.OOE+00 (2) Total activity released: 0.OOE+00 Curies B. Gaseous (1) Number of releases: 0.OOE+00 (2) Total activity released: 0.OOE+00 Curies 2 There were no abnormal releases that exceeded 10 CFR 20 or 10 CFR 50 limits. See pages 5-7 for a discussion of release events that occurred.

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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 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 1.43E+05 gallons containing 3.01E-03 curies of tritium was released in December to the discharge canal. 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. In addition, the volume released is accounted for under Secondary Waste Volume Released on Attachment 2, Table 2A.

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+01 Ci/yr. This value was scaled using Effective Full Power Days (EFPD) to give a release rate of 2.07E+01 Ci/yr. Based on the 2013 Land Use Census, the critical receptor is located in the south sector at 2.2 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 2013 was 1.64E+00 mrem and the total body dose was 3.28E-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 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 twenty-two occasions in 2013 due to heavy rains.

Approximately 3.06E+06 gallons containing 1.50E-01 curies of tritium were released. There was no detectable gamma radioactivity. The tritium released was included in the quarterly summary on Attachment 2, Table 2A and the dose is included in the Annual Dose Summary, . In addition, the volume released is accounted for under Secondary Waste Volume Released on Attachment 2, Table 2A.

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, however, since the third quarter of 2012 all inputs except rainwater were routed to the Storm Drain Stabilization Facility. 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. There were two SDSP releases in 2013. Approximately 7.OOE+06 gallons containing 2.95E-01 curies of tritium were released. There was no detectable gamma Page 5 of 45

Attachment 2 Effluent and Waste Disposal Report Supplemental Information radioactivity. The tritium released is included in the quarterly summary on Attachment 2, Table 2A and the dose is included in the Annual Dose Summary, Attachment 7. In addition, the volume released is accounted for under Secondary Waste Volume Released on Attachment 2, Table 2A.

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 canal where it is drawn into the plant circulating and service water system and eventually released into the discharge canal. There were sixteen SDSF releases in 2013. Approximately 7.70E+07 gallons containing 1.12E+0 1 curies of tritium were released from the SDSF. There was no detectable gamma radioactivity. The SDSF is a permitted release point. The tritium released is included in the quarterly summary on Attachment 2, Table 2A and the dose is included in the Annual Dose Summary, Attachment 7. In addition, the volume released is accounted for under Secondary Waste Volume Released on Attachment 2, Table 2A.

Discussion of water evaporation from the Storm Drain Stabilization Pond It was calculated that 6.25E+07 gallons of tritiated water was released via evaporation from the SDSP in 2013. This yields 2.01E+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 6.14E-04 mrem via the inhalation pathway in 2013. 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 water evaporation from the Storm Drain Stabilization Facility It was calculated that 4.91E+06 gallons of tritiated water was released via evaporation from the SDSF in 2013. This yields 7.30E-01 curies of tritium released to the atmosphere as a ground release. The nearest resident to the pond is in the north northwest sector at approximately 0.5 miles. The maximum exposed individuals at that location received a calculated dose of 4.71E-04 mrem via the inhalation pathway in 2013. 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 SDSF 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. The sampling program consists of weekly sampling and analysis at eight locations. All gamma analyses performed in 2013 were less than the Lower Limit of Detection (LLD). There were 416 tritium analyses performed, which resulted in 70 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 2013, it was calculated that 5.38E+07 gallons Page 6 of 45

Attachment 2 Effluent and Waste Disposal Report Supplemental Information were released to Nancy's Creek containing 1.20E-0 1 curies of tritium. This yielded a Total Body dose of 1.46E-03 mrem to an adult from eating fish and invertebrate (shrimp, crabs, etc.).

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. 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 Condensate Storage Tank (CST) leak and the SDSP.

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 (U1CSTREM-01, U1CSTREM-07, U 1CSTREM-08 3 and U1CSTREM-09) are installed in the Castle Hayne aquifer (greater than 70' below ground surface) to investigate and monitor potential impacts to the aquifer. Seven of these wells (U1CSTREM-05, U1CSTREM-02B, UICSTREM-08 4 U1CSTREM-15, U1CSTREM-21B, U1CSTREM-22B and MWPA-1 11B) 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. Fifteen of these wells (U1CSTREM-02C, U1CSTEM-10, U1CSTREM-1 1, U1CSTREM-12, U1CSTREM-13, U1CSTREM-14, U1CSTREM-16, UICSTREM-18, U1CSTREM-19, U1CSTREM-21C, U1CSTREM-22C5 , U1CSTREM-24, U1CSTREM-25, U1CSTREM-28 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 eleven 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.

3This well was converted into an intermediate (dense sand) well in November 2012.

4 This well was converted from a Castle Hayne well in November 2012 (see previous footnote.)

5This well was converted from a monitoring well to an extraction well in October 2013.

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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 (fi) in 2013 21 2013 ESS-2C 4 3 1.56E+04 3.61E+03 2.18E+04 27 ESS-3C 3 3 7.07E+02 3.77E+02 1.O1E+03 14 ESS-12C 3 0 <LLD <LLD <LLD 15 ESS-13C 4 0 <LLD <LLD <LLD 25 ESS-16 2 2 1.13E+03 8.47E+02 1.41E+03 27 ESS-17C 3 3 5.49E+03 3.38E+03 7.76E+03 26 ESS-18C 3 3 7.31E+04 5.OOE+04 8.76E+04 20 ESS-19C 2 2 1.46E+05 1.25E+05 1.68E+05 20 ESS-20C 2 2 2.16E+04 1.27E+04 3.05E+04 20 ESS-21C 4 4 2.53E+03 1.42E+03 3.85E+03 20 ESS-22C 3 3 1.50E+05 7.37E+04 2.83E+05 20 ESS-23C 2 2 1.62E+05 1.59E+05 1.66E+05 23 ESS-24C 3 3 4.18E+03 3.50E+03 5.34E+03 18 ESS-25C 4 0 < LLD < LLD < LLD 22 ESS-26C 3 3 6.49E+04 2.70E+04 9.12E+04 15 ESS-27C 2 2 1.90E+05 1.85E+05 1.95E+05 16 ESS-28C 2 2 7.04E+02 6.34E+02 7.75E+02 23 ESS-29C 2 1 8.19E+02 8.19E+02 8.19E+02 28 ESS-30C 3 3 4.06E+02 2.89E+02 5.40E+02 15 ESS-31C 10 8 3.88E+02 2.97E+02 4.60E+02 15 ESS-32C 1 0 < LLD < LLD < LLD 35 ESS-33C 1 0 < LLD < LLD < LLD 25 Page 8 of 45

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 2013 21 2013 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 3 0 < LLD < LLD < LLD 15 ESS-39C 3 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 15 ESS-45C 1 0 < LLD < LLD < LLD 21 ESS-46C 1 0 < LLD < LLD < LLD 18 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 2 1 5.30E+02 5.30E+02 5.30E+02 22 ESS-51C 2 1 8.98E+02 8.98E+02 8.98E+02 22 ESS-54C 2 1 3.29E+02 3.29E+02 3.29E+02 24 ESS-55C 1 0 < LLD < LLD < LLD 38 ESS-56C 1 0 < LLD < LLD < LLD 32 ESS-57C 1 0 < LLD < LLD < LLD 40 Page 9 of 45

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 oe H-3 H-3 Act H-3 Act H-3 Act Samples Samples in (pCi/L) (pCi/L) (pCi/L) Well (ft) in 2013 21 2013 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-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 9 3 4.75E+02 3.19E+02 6.04E+02 25 ESS-68C 1 0 < LLD < LLD < LLD 19 ESS-69C 1 0 < LLD < LLD < LLD 30 ESS-70C 1 0 < LLD < LLD < LLD 18 ESS-71C 1 0 < LLD < LLD < LLD 19 ESS-72C 9 1 8.92E+02 8.92E+02 8.92E+02 18 ESS-73C 3 0 < LLD < LLD < LLD 15 ESS-74C 1 0 < LLD < LLD < LLD 25 ESS-201C 3 3 2.23E+04 2.16E+03 3.25E+04 27 ESS-202C 3 3 8.50E+04 6.06E+04 1.17E+05 27 ESS-203C 3 3 6.89E+03 3.99E+03 1.12E+04 27 ESS-STAB 3 3 2.07E+04 1.22E+04 2.89E+04 31 ESS-NC-4A 2 2 5.30E+03 5.20E+03 5.40E+03 17 Page 10 of 45

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 Samples H-3 H-3 Act H-3 Act H-3 Act Well (ft) inmples Samples in (pCi/L) (pCi/L) (pCi/L) in2013 2013 MW-1 2 2 4.33E+02 3.85E+02 4.81E+02 24 MW-2 3 1 3.19E+02 3.19E+02 3.19E+02 24 MW-3 3 2 3.13E+02 3.1OE+02 3.17E+02 26 MWPA-100C 3 1 3.11E+02 3.11E+02 3.11E+02 30 MWPA-1O1C 3 3 4.08E+02 3.02E+02 4.97E+02 29 MWPA-102C 2 2 5.65E+02 5.56E+02 5.73E+02 30 MWPA-103C 2 1 5.23E+02 5.23E+02 5.23E+02 30 MWPA-104C 4 4 8.20E+03 6.80E+03 9.39E+03 29 MWPA-105C 3 3 9.75E+02 8.92E+02 1.13E+03 30 MWPA-106C 2 2 4.89E+02 3.87E+02 5.90E+02 29 MWPA-107C 10 9 3.05E+03 2.18E+03 4.20E+03 29 MWPA-108C 3 0 < LLD < LLD < LLD 29 MWPA-109C 2 2 8.57E+02 7.95E+02 9.20E+02 29 MWPA-1 1C 5 3 1.63E+03 8.26E+02 3.20E+03 29 MWPA- 113 C 6 5 7.81E+02 5.75E+02 1.00E+03 25 MWPA-114C 3 2 1.94E+03 1.56E+03 2.33E+03 30 MWPA-115C 6 6 1.15E+04 7.68E+03 1.51E+04 34 MWPA-116C 9 2 3.86E+02 3.15E+02 4.57E+02 30 MWPA-1 17C 9 9 7.39E+02 4.54E+02 1.22E+03 30 MWPA-118C 9 9 9.25E+02 7.20E+02 1.11E+03 30 Page 11 of 45

Attachment 2 Effluent and Waste Disposal Report Supplemental Information Intermediate Wells for Plant Site 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 2013 2013 ESS-2B 2 0 < LLD < LLD < LLD 58 ESS-3B 3 1 3.39E+02 3.39E+02 3.39E+02 52 ESS-18B 3 2 4.70E+02 4.1OE+02 5.31E+02 23 ESS-19B 2 2 3.19E+03 2.41E+03 3.96E+03 42 ESS-20B 2 0 < LLD < LLD < LLD 43 ESS-22B 3 3 1.54E+03 1.30E+03 1.73E+03 76 ESS-38B 3 0 < LLD < LLD < LLD 55 ESS-39B 3 0 < LLD < LLD < LLD 55 ESS-51B 2 0 < LLD < LLD < LLD 45 ESS-52B 2 0 < LLD < LLD < LLD 51 ESS-53B 2 0 < LLD < LLD < LLD 76 MWPA-104B 4 4 9.32E+03 7.77E+03 1.16E+04 59 MWPA-107B 4 4 5.28E+04 4.15E+04 6.97E+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 2013 2013 MWPA- 1I1B 253 242 1.85E+04 3.27E+03 3.37E+04 61 MWPA-1 12C 300 300 1.19E+05 8.63E+03 4.02E+05 34 U1CSTREM-01 6 0 0 N/A N/A N/A 80 UICSTREM-02B 6 0 0 N/A N/A N/A 80 6 Was not monitored in 2013 but will be used in the future for U1 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 2013 21 2013 U1CSTREM-02C 305 305 2.17E+05 5.68E+03 1.07E+06 45 U1CSTREM-05 7 0 0 N/A N/A N/A 60 UICSTREM-07 3 0 < LLD < LLD < LLD 80 UICSTREM-08 3 0 < LLD < LLD < LLD 80 U1CSTREM-09 4 1 5.70E+02 5.70E+02 5.70E+02 68 UICSTREM-10 7 0 0 N/A N/A N/A 45 U1CSTREM-1 1 4 1 2.78E+02 2.78E+02 2.78E+02 35 UICSTREM-12 3 3 6.60E+04 5.65E+04 7.39E+04 32 UICSTREM-13 304 304 1.96E+05 3.80E+04 1.66E+06 45 UICSTREM-14 317 317 1.54E+05 1.14E+04 1.43E+06 45 U1CSTREM-15 314 314 1.43E+05 4.53E+04 4.25E+05 59 UICSTREM-16 303 303 9.57E+05 4.78E+04 3.76E+06 41 U1CSTREM-18 305 305 5.97E+06 1.08E+06 1.O1E+07 29 UICSTREM-19 283 283 5.92E+05 6.26E+04 1.26E+06 41 UICSTREM-21B 4 4 1.52E+04 4.80E+03 2.64E+04 60 U1CSTREM-21C 4 1 3.41E+02 3.41E+02 3.41E+02 45 UICSTREM-22B 5 3 3.99E+03 2.86E+02 1.14E+04 60 UICSTREM-22C 15 15 1.96E+04 7.82E+03 5.19E+04 45 UICSTREM-24 312 312 6.29E+04 9.26E+03 3.15E+05 30 U1CSTREM-25 316 316 1.81E+05 5.04E+03 1.28E+06 45 UICSTREM-28 7 0 0 N/A N/A N/A 45 7 Was not monitored in 2013 but will be used in the future for U1 CST remediation monitoring.

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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 ID Gaseous Effluents - Mixed Mode 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 14 of 45

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

1. Total release Ci 2.84E+O1 2.02E+O1 2.02E+01 4.24E+01 2.50E+O1

2. Average release rate for period iiCi/sec 3.66E+00 2.57E+00 2.55E+00 5.33E+00 NA B. IODINES Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total Iodine - 131 release Ci 1.82E-03 4.69E-04 1.19E-03 1.28E-03 2.50E+01

2. Average release rate for period pCi/sec 2.34E-04 5.96E-05 1.50E-04 1.62E-04 NA C. PARTICULATES Estimated Total Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total release Ci 3.98E-04 2.94E-04 2.24E-04 3.74E-04 2.50E+01

2. Average release rate for period pCi/sec 5.12E-05 3.74E-05 2.82E-05 4.71E-05 NA

3. Gross Alpha Ci 2.82E-07 1.40E-07 < LLD < LLD 2.50E+01 D. TRITIUM Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total release Ci 6.10OE+0I1 5.38E+01 7.98E+01 1.16E+02 1.50E+01

2. Average release rate for period pCi/sec 7.84E+00 6.84E+00 1.00E+0 1 1.46E+O 1 NA E. CARBON-14 Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total release Ci 4.74E+00 4.18E+00 5.89E+00 5.90E+00 NA

2. Average release rate for period pCi/sec 6.1OE-07 5.32E-07 7.4 1E-07 7.42E-07 NA Page 15 of 45

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 2.35E+00 4.61E+00 7.53E-01 1.05E-01 krypton-85m Ci 9.O0E-01 2.52E-01 < LLD 1.60E-0 I krypton-87 Ci < LLD 3.94E-01 < LLD 2.48E-0 I krypton-88 Ci < LLD 6.24E-01 < LLD 4.06E-0I xenon-133 Ci 5.18E+00 2.11E-01 < LLD 7.17E-02 xenon-135m Ci 1.OE+00 < LLD 4.69E+00 1.07E+00 xenon-135 Ci 1.34E+00 1.92E+00 3.14E+00 9.09E+00 xenon-138 Ci 6.73E+00 < LLD < LLD 7.12E+00 total for period Ci 1.75E+01 8.01E+00 8.58E+00 1.83E+01

2. IODINES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 iodine-131 Ci 5.69E-04 2.53E-04 5.70E-04 5.86E-04 iodine-133 Ci 2.90E-03 1.61E-03 3.60E-03 3.39E-03 iodine-135 Ci 4.61E-03 2.OOE-03 4.87E-03 6.19E-03 total for period Ci 8.08E-03 3.86E-03 9.04E-03 1.02E-02

3. PARTICULATES Unit Quarter I Quarter 2 Quarter 3 Quarter 4 cobalt-60 Ci < LLD < LLD < LLD 1.38E-06 strontium-89 Ci 9.75E-06 4.48E-05 1.78E-05 1.48E-05 silver-110m Ci < LLD < LLD < LLD 2.82E-06 cesium-137 Ci < LLD 7.56E-07 < LLD < LLD barium- 140 Ci 6.82E-05 3.11 E-05 6.64E-05 7.52E-05 lanthanum-140 Ci 1.20E-04 4.99E-05 1.28E-04 1.34E-04 total for period Ci 1.98E-04 1.27E-04 2.12E-04 2.28E-04

4. TRITIUM Unit Quarter I Quarter 2 Quarter 3 Quarter 4 hydrogen-3 Ci 1.73E+01 1.22E+01 2.31E+O1 2.22E+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 1 Quarter 2 Quarter 3 Quarter 4 Carbon-14 Ci 1.90E+00 1.67E+00 2.35E+00 2.36E+00 Page 16 of 45

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 1 Quarter 2 Quarter 3 Quarter 4 krypton-85m Ci < LLD 9.03E-02 < LLD 1.36E-02 krypton-88 Ci < LLD < LLD 3.48E-01 < LLD xenon- 135 Ci 1.09E+01 1.21 E+O 1 1.1 3E+0 I 2.41E+01 total for period Ci 1.09E+01 1.22E+01 1.17E+01 2.4 1E+01

2. IODINES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 iodine-131 Ci 1.23E-03 2.08E-04 6.03E-04 6.79E-04 iodine-133 Ci 1.07E-02 2.34E-03 6.72E-03 7.48E-03 iodine-135 Ci 1.89E-02 1.97E-03 1.43E-02 1.79E-02 total for period Ci 3.08E-02 4.52E-03 2.16E-02 2.60E-02

3. PARTICULATES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 chromium-51 Ci < LLD < LLD 1.08E-07 < LLD cobalt-60 Ci 4.7 1E-06 1.92E-05 < LLD 2.30E-05 strontium-89 Ci < LLD < LLD < LLD 8.60E-06 barium-140 Ci 1.03E-05 < LLD < LLD 1.20E-05 lanthanum- 140 Ci < LLD < LLD < LLD 4.1OE-05 total for period Ci 1.5 1E-05 1.92E-05 1.08E-07 8.47E-05

4. TRITIUM Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 hydrogen-3 Ci 3.33E+01 3.50E+01 5.25E+01 9.08E+01

5. GROSS ALPHA Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 gross alpha Ci 2.55E-07 8.55E-08 < LLD < LLD

6. CARBON-14 Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 carbon- 14 Ci 9.49E-0 1 8.36E-01 1.18E+00 1.18E+00 Page 17 of 45

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 1 Quarter 2 Quarter 3 Quarter 4 iodine- 131 Ci 2.19E-05 8.04E-06 2.19E-05 1.90E-05 iodine- 133 Ci 1.37E-04 1.34E-04 2.20E-04 1.88E-04 total for period Ci 1.59E-04 1.42E-04 2.42E-04 2.07E-04

3. PARTICULATES Unit Quarter I Quarter 2 Quarter 3 Quarter 4 chromium-51 Ci 5.27E-05 I.OOE-05 < LLD 8.65E-06 manganese-54 Ci 4.83E-06 2.54E-07 < LLD < LLD cobalt-58 Ci 1.44E-05 9.50E-06 < LLD 2.91E-05 cobalt-60 Ci 1.11 E-04 1.27E-04 8.80E-06 2.38E-05 cesium- 137 Ci 1.99E-06 2.OOE-06 2.90E-06 < LLD total for period Ci 1.85E-04 1.48E-04 1.17E-05 6.16E-05

4. TRITIUM Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 hydrogen-3 Ci 1.04E+01 6.60E+00 4.16E+00 3.21E+00

5. GROSS ALPHA Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 gross alpha Ci 2.62E-08 5.46E-08 < LLD < LLD

6. CARBON-14 Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 carbon-14 Ci 1.90E+00 1.67E+00 2.35E+00 2.36E+00 Page 18 of 45

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 3.31E-04 6.62E-04 7.22E-04 2.06E-04 1.70E+01 (excluding tritium, gases, and alpha)

2. Average diluted concentration [iCi/ml 9.66E-13 1.68E-12 1.36E-12 4.39E-13 NA

3. Percent of 6.30E-06 5.95E-06 4.80E-06 2.25E-06 NA applicable limit B. TRITIUM (NOTE 1)

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

1. Total release Ci 5.23E+01 7.41E+01 5.66E+O 1 2.88E+01 2.30E+01

2. Average diluted 1.52E-07 1.88E-07 1.06E-07 6.14E-08 NA concentration pCi/ml

3. Percent of 1.52E-03 1.88E-03 1.06E-03 6.14E-04 NA applicable limit C. DISSOLVED AND ENTRAINED GASES (NOTE 1)

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

1. Total release Ci 8.89E-04 9.65E-04 7.52E-04 3.72E-04 1.70E+01

2. Average diluted 2.59E-12 2.45E-12 1.4 1E- 12 7.92E- 13 concentration gCi/ml NA

3. Percent of 1.30E-06 1.2313-06 7.06E-07 3.96E-07 NA applicable limit D. GROSS ALPHA RADIOACTIVITY (NOTE 1)

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

1. Total release Ci < LLD < LLD < LLD < LLD 3.20E+O1 NOTE 1: Includes radionuclides released via abnormal and/or non-routine releases Page 19 of 45

Attachment 2 Effluent and Waste Disposal Data Table 2A: Liquid Effluents - Summation of all Releases E. PRIMARY WASTE VOLUME RELEASED Estimated Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total volume liters 2.53E+06 5.21E+06 5.65E+06 2.01E+06 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 7.83E+07 1.18E+08 9.72E+07 3.72E+07 1.50E+01 G. VOLUME OF COOLING WATER DISCHARGED FROM PLANT Estimated Total Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Percent Error

1. Total volume liters 3.43E+11 3.93E+11 5.32E+11 4.70E+11 1.50E+01 Page 20 of 45

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 sodium-24 Ci < LLD 2.5 1E-05 2.30E-05 < LLD chromium-51 Ci < LLD 6.04E-06 < LLD < LLD manganese-54 Ci < LLD 1.1 5E-05 4.26E-07 < LLD cobalt-58 Ci < LLD 6.57E-05 5.70E-06 < LLD cobalt-60 Ci 6.15E-05 1.52E-04 6.65E-05 3.12E-05 zinc-65 Ci < LLD 6.37E-05 2.62E-06 2.22E-07 zinc-69m Ci < LLD 4.83E-05 < LLD < LLD yttrium-93 Ci < LLD < LLD 1.34E-06 < LLD technetium-99m Ci < LLD 8.40E-07 < LLD < LLD iodine- 131 Ci 1.77E-04 5.38E-05 1.62E-04 7.94E-05 iodine-132 Ci < LLD < LLD 2.66E-06 < LLD iodine-133 Ci 8.64E-05 1.18E-04 4.15E-04 9.30E-05 iodine-135 Ci < LLD 2.3 1E-05 3.33E-05 < LLD cesium-134 Ci < LLD 5.5 1E-06 < LLD < LLD cesium-137 Ci 5.76E-06 8.77E-05 9.67E-06 2.56E-06 total for period Ci 3.3 1E-04 6.62E-04 7.22E-04 2.06E-04

2. DISSOLVED AND ENTRAINED GASES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 krypton-85 Ci < LLD 2.75E-04 < LLD 4.54E-05 krypton-87 Ci < LLD 1.46E-06 < LLD < LLD xenon-133 Ci 1.84E-04 6.22E-05 9.62E-05 5.05E-05 xenon-135 Ci 7.05E-04 6.26E-04 6.55E-04 2.76E-04 total for period Ci 8.89E-04 9.65E-04 7.52E-04 3.72E-04 Page 21 of 45

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

1. LIQUID RELEASES 2. GASEOUS RELEASES Alpha 2.13E-08 Ar-41 1.23E-08 H-3 2.99E-06 Kr-85 3.88E-06 H-3 2.76E-07* Kr-85m 8.46E-09 Na-24 1.34E-08 Kr-87 2.64E-08 Cr-51 1.93E-07 Kr-88 2.35E-08 Mn-54 2.28E-08 Xe-133 1.66E-08 Fe-55 5.44E-07 Xe-133m 7.55E-08 Co-58 2.23E-08 Xe-135 7.42E-09 Fe-59 5.09E-08 Xe-135m 1.05E-07 Co-60 2.30E-08 Xe-137 1.40E-06 Ni-63 2.98E-07 Xe-138 2.7 1E-07 Zn-65 4.85E-08 Zn-69m 2.2 1E-08 Sr-89 2.08E-08 Sr-90 2.52E-08 Y-93 2.03E-07 Tc-99m 1.61E-08 Mo-99 1.61E-07 3. IODINES AND PARTICULATES Ag-110m 2.35E-08 1-131 2.27E-08 Alpha 1.18E-15 1-132 3.15E-08 H-3 6.83E- 1I 1-133 2.17E-08 Cr-51 3.14E-12 Cs-134 1.64E-08 Mn-54 5.84E-13 1-135 6.37E-08 Co-58 4.96E-13 Cs-137 2.34E-08 Fe-59 6.70E-13 Ce-141 3.36E-08 Co-60 4.OOE-13 Ce-144 1.34E-07 Zn-65 1.99E-12 Kr-87 5.24E-08 Sr-89 8.87E-15 Kr-88 6.50E-08 Sr-90 4.99E-15 Xe-133 4.64E-08 Nb-95 3.84E-13 Xe-133m 1.4 1E-07 Mo-99 4.95E-12 Xe-135 1.83E-08 Ag-110m 4.25E-13 Xe-135m 1.02E-07 1-131 4.08E-13 Xe-138 1.61E-07 Cs-134 5.66E-13 Cs-137 6.74E-13 Ba-140 2.211E-12 La-140 4.41 E-13 Ce-141 5.38E-13 Ce-144 2.50E-12 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, and 2B. Also included are isotopes specified in ODCMS 7.3.3 and 7.3.7.

2. Where activity for any nuclide is reported as "< LLD," that nuclide is considered not present and the LLD activity listed is not considered in the summary data.

Tritium LLD value for ground water monitoring.

Page 22 of 45

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) 1.09E+03 Total curie quantity (estimated) 1.29E+02

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

a. Spent resins, filter, sludges meter 5.43E+01 Curies 1.22E+02 1.00E+0 1 3

b. Dry active waste, compacted/non-compacted meter 1.04E+03 Curies 6.94E+00 1.00E+01 3

c. Irradiated components meters O.OOE+00 Curies O.OOE+00 N/A 3

d. Others (describe) meters 3.91 E+O 1 Lead Waste Curies 6.80E-03 1.OOE+01 Sewage Sludge

3. Estimate of major radionuclides composition

a. C-14 2.61E+00 %

Mn-54 1.43E+00 %

Fe-55 1.23E+01 %

Co-60 6.34E+01 %

Ni-63 1.24E+01 %

Cs-137 5.83E+00 %

b. Mn-54 3.33E+00 %

Fe-55 2.97E+01 %

Co-60 6.28E+01 %

Ni-63 1.13E+00 %

Cs-137 0.91E+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 23 of 45

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 1.30]E+O 1

b. Dry active waste Compacted/ Type A or GDP 2.50E+01 Non-compacted

c. Irradiated components N/A N/A

d. Others (describe) Type A or GDP 3.OOE+00 Lead Waste Sewage Sludge

5. Shipment Disposition

a. Solid Waste Number of Shipments Mode of Transportation Destination 2.20E+01 Highway Oak Ridge, TN 4.OOE+00 Rail Clive, UT 1.20E+O1 Highway Erwin, TN 3.OOE+00 Highway Richland, WA

b. Irradiated Fuel Number of Shipments Mode of Transportation Destination 0 N/A N/A Page 24 of 45

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) 1.22E+O I Total curie quantity (estimated) 3.70E+02

2. Type of Waste Estimated Total Unit Period %Error

a. Spent resins, filter, sludges meter' 1.22E+01 Curies 3.70E+02 1.00E+01

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 0.00E+00 N/A

3. Estimate of major radionuclides composition

a. Mn-54 3.83E+00 %

Fe-55 8.75E+00 %

Co-58 2.75E+00 %

Co-60 6.94E+01 %

Ni-63 8.45E+00 %

Zn-65 2.78E+00 %

Cs-137 2.11E+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.

Page 25 of 45

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 5.OOE+00

b. Dryw 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 4.OOE+00 Highway Erwin, TN 1.00E+00 Highway Andrews, TX

b. Irradiated Fuel Number of Shipments Mode of Transportation Destination 0 N/A N/A Page 26 of 45

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+O0 Curies O.OOE+O0 N/A

b. Dry active waste, compacted/non-compacted meter 3 O.OOE+O0 Curies O.OOE+00 N/A 3

c. Irradiated components meters O.OOE+O0 Curies O.OOE+O0 N/A 3

d. Others (describe) meters O.OOE+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 27 of 45

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 28 of 45

Attachment 3 Environmental Monitoring Program : Milk and Vegetable Sample Location : Land Use Census Page 29 of 45

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 30 of 45

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 2.2 miles SSW 1.2 miles 1.6 miles SW 1.1 miles 1.4 miles WSW 1.2 miles 1.2 miles W 0.9 miles 0.9 mile WNW 0.9 miles 1.0 miles NW 0.9 miles 1.0 miles NNW 0.8 miles 0.9 miles N 0.7 miles 1.0 miles Based on the 2013 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.

Page 31 of 45

Attachment 4 Effluent Instrumentation : Radioactive Liquid Effluent Monitoring Instrumentation : Radioactive Gaseous Effluent Monitoring Instrumentation : Liquid Hold-Up Tank Page 32 of 45

Attachment 4 Effluent Instrumentation Enclosure 1: Radioactive Liquid Effluent Monitoring Instrumentation There was one Radioactive Liquid Effluent Monitoring Instrument inoperable for a period of greater than 30 days during 2013.

Unit 2 entered Off-Site Dose Calculation Manual (ODCM) 7.3.1, Radioactive Liquid Effluent Monitoring Instrumentation, Condition G, on 4/22/13 due to the 2-CO-LIT- 1160, Condensate Storage Tank (CST) Level Transmitter, being declared inoperable. Required Compensatory Measure G.2 requires restoration of the channel to operable status within 30 days. As of 5/22/13 the condition had not been corrected, therefore, Condition I was entered to prepare and submit in the Radioactive Effluent Release Report the reason the channel was not restored to operable status within 30 days. Failure of the instrument was evaluated per Condition Report (CR) 604944.

Failure of the return to service of the instrument in a timely manner was evaluated per CR 606145.

Work Request (WR) 579648 and CR 604944 were initiated upon discovery of the failure of the level instrument. Alternate methods were invoked to measure CST level per OOP-31.2, Condensate and Demineralized Water Storage and Transfer System, Section 8.15 Alternate Condensate Storage Tank Level Determination. This action was performed to satisfy ODCM 7.3.1 Condition G.1 -

Estimate the tank liquid level once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months during all liquid additions and deletions to and from the tank.

WR 579648 was converted to Work Order (WO) 2232622. Troubleshooting the failure of the Level Instrument found that the level instrument tape had broken inside the tank. The Work Order replaced the level transmitter and tape, calibrated the instrument and performed post maintenance testing. The tape replacement required diving be conducted inside the tank to facilitate repairs. The diving evolution required significant coordination with ongoing Unit 2 refueling activities and was deferred due to start-up testing activities associated with High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC). These tests completed 05/09/13. Work commenced to repair the level instrumentation on 5/21/2013 and was completed on 5/26/2013.

Page 33 of 45

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 34 of 45

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 35 of 45

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 36 of 45

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 37 of 45

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 I1.46E-03

Reference pages 6-7 of Supplemental Information for a discussion of the Marsh release.

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

GI-LLI 1.30E-04 1.46E-03 1.59E-03 2.OOE+0 1 Bone 8.52E-06 0.OOE+00 8.52E-06 2.OOE+01 Liver 1.34E-04 1.46E-03 1.59E-03 2.OOE+0 1 Lung 1.08E-04 1.46E-03 1.57E-03 2.OOE+01 Total Body 1.20E-04 1.46E-03 1.58E-03 6.OOE+00 Thyroid 1.36E-04 1.46E-03 1.60E-03 2.OOE+01 Kidney 1.25E-04 1.46E-03 1.59E-03 2.00E+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 38 of 45

Attachment 7 Annual Dose Assessment Gaseous Effluents Noble Gas:

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

Gamma 2.36E-02 2.OOE+01 Beta 2.77E-02 4.00E+01 Iodine, Particulates, and Tritium:

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)( 3X 4) Total Dose (mrem) Limit (mrem)

Thyroid 7.01 E-02 3.29E-01 3.99E-01 3.OOE+01 Kidney 7.48E-03 3.29E-01 3.37E-01 3.OOE+÷0 Liver 7.45E-03 3.29E-01 3.37E-01 3.OOE+01 Total Body 7.32E-03 3.29E-01 3.36E-01 3.OOE+01 GI-LLI 7.25E-03 3.29E-0l 3.36E-01 3.OOE+01 Lung 7.25E-03 3.29E-01 3.36E-01 3.OOE+01 Bone 3.41E-04 1.64E+00 1.64E+00 3.OOE+01 (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 2.2 miles with a garden.

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

Page 39 of 45

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 37 was effective on October 29, 2013. The changes and justifications are described below:

1. List of Effective Pages: Revised to reflect all of the changes for Revision 37.

2. Table of Contents (TOC): Section 2.2 and 3.3 page numbers were updated. Section 4 title was missing "MONITORING." Section 7 listed the sections as 7.1 - 7.5 and B.7.3, in the body of the Off-Site Dose Calculation Manual (ODCM) these sections are listed as 7.1.0 - 7.5.0 and B.7.3.0, so it was corrected in the TOC. Section 7.3.0 title in the TOC included "AND" so it was deleted. The title for B.7.3.0 was missing "OFFSITE DOSE CALCULATION MANUAL SPECIFICATION (ODCM) APPLICABILITY" so it was added. Appendix A-C page numbers were updated.

3. Section 2 List of Tables was updated to include the correct page number for Table 2.2-1.

4. On page 2-3 annual average was removed from the definition of ECQ. In 10CFR20 the term is not defined as an annual average. It is listed as effluent concentration and it states that the concentration values given are equivalent to the radionuclide concentrations that if inhaled or ingested continuously over a year would produce a total effective dose equivalent of 0.05 rem.

5. Equation 2.1-3 is being changed to add parentheses to clearly delineate the order of math operation.

6. On page 2-4 there were two definitions for DFB. The definition at the bottom of the page was changed to match the definition at the top for consistency.

7. Equation 2.1-7 is being changed from CONC to Conc. This is an editorial enhancement for consistency purposes. Additionally the limit of 1 for the diluted ECL fraction is being changed to 10. This change will align this section of the ODCM with Section 7.3.3 of the Brunswick ODCM and Tech Spec 5.5.4.b. The actual calculation of a release rate based on a required dilution to ensure that diluted ECL fraction limit is satisfied is NOT being changed and as such there is no change to the methodology or practices associated with performing radioactive liquid releases. The text above Equation 2.1-7 is being revised to correct the designation of "calculated dilution factor" to "calculated diluted Effluent Concentration Limit (ECL) fraction" as the description of this equation was incorrect.

Additionally the text is being changed to limit the calculated diluted ECL fraction to 10.

8. On page 2-6 annual average was removed from the definition of ECQ. In 10CFR20 the term is not defined as an annual average. It is listed as effluent concentration and it states that the concentration values given are equivalent to the radionuclide concentrations that if inhaled or ingested continuously over a year would produce a total effective dose equivalent of 0.05 rem.

Page 40 of 45

Attachment 8 Off-Site Dose Calculation Manual (ODCM) And Process Control Program (PCP) Revisions

9. Equation 2.1-9 is being revised to change the diluted ECL fraction limit from I to 10.

Again this change will align this section of the ODCM with Section 7.3.3 of the Brunswick ODCM and Tech Spec 5.5.4.b.

10. On page 2-8 under Section 2.1.2, the last sentence was changed to state the sum of the concentration of radionuclide i in the unrestricted area due to both continuous and batch releases divided by that isotope's EC must be less than 10. This change will align this section of the ODCM with Section 7.3.3 of the Brunswick ODCM and Tech Spec 5.5.4.b.

Also, on page 2-8 under Service Water Effluent Monitor Setpoint Determination, equation 2.1-10 was removed because converting the monitor efficiency factor is not needed. The Radiation Surveillance Test (RST) already lists the efficiency in the correct units.

11. On page 2-10, Bip was missing part of the definition. The definition has been updated to match the definition in Regulatory Guide 1.109.

12. Section 2.2.2 is being revised to change the methodology for performing projected doses for liquid releases such that the projected dose can be used to evaluate the impact of a release being performed. This change will help to ensure that if a release is performed without the use of the radwaste processing system that its effect can be determined on a pre-release / proactive basis. The projected dose equation is based on projected dose equations from the Shearon Harris, HB Robinson, and the Crystal River ODCMs.

13. In Table 2.2-1, the zero values in the table were formatted to 0.OOE+00, since they were inconsistent. Some values were shown as 0.OOE 01 and 0.00E-01. Positive exponents were denoted with "+". In addition, the column of nuclides was updated with dashes.

14. Page 3-1 and 3-2: Updated the Index and List of Tables for Section 3 based on changes to the page numbering and updated Titles to match the actual title in the document.

15. Page 3-11: Corrected p.Ci/sec value for Xe- 135 to 9.97E+3 in Table 3.1.1. Included the Gale Code numbers were from NUREG-00 16 April 1976 and were scaled in accordance with NUREG-0 133 for 2923 MWt (Reference DRR 550268).

16. Page 3-18: Capitalized Stack under gaseous releases. Added "rate" to the description for Equation 3.2-3 as this refers to dose rate. Also, removed the footnote about exfiltration.

The new effluent software, OpenEMS, can handle these points separately and treats them as a ground release like the Turbine Buildings. The old software did not have this capability.

17. Page 3-19: Added "rate" to the description for Equation 3.2-4 as this refers to dose rate.

In the last paragraph there was a typographical error for the controlling location for Noble Gases, it has been updated to the ENE sector. This was identified as the correct sector in Revision 26 and is currently the controlling sector.

18. Pages 3-23 and 3-24: Section 3.2.2 is being revised to specify that the critical receptor to ensure compliance with ODCMS 7.3.7 (iodine-131, iodine-133, tritium, and all Page 41 of 45

Attachment 8 Off-Site Dose Calculation Manual (ODCM) And Process Control Program (PCP) Revisions radionuclides in particulate form with half-lives > 8 days) is a child with an inhalation pathway at the site boundary. Previously, the ODCM used a hypothetical pathway for this receptor at a non-site boundary location. If the dose rate at the hypothetical location was exceeded then the dose rate at the real limiting pathway at the site boundary would be calculated to ensure compliance. This change will eliminate the hypothetical pathway and calculate/control dose at the real site boundary location without the intermediate step.

The use of the child inhalation pathway at the site boundary is already specified in ODCM Basis 7.3.7 and NUREG-1302 Bases 3/4.11.2.1. In addition, Section 3.2.2 is also being revised to add the release points Hot Shop (Decon) Facility, Radioactive Materials Container and Storage Building (RMCSB), and Low Level Warehouse (LLW) as separate release points. Previously due to software limitations the releases from these points were included as part of releases from the Turbine Buildings. Separation of these release points does not change the quantification of activity or doses from these release points. Due to deleting the hypothetical pathway page numbers from 3-24 to the end of Section 3 shifted.

19. Page 3-25: The zeros "0" in Table 3.2-1 were formatted to 0.OE+0 to be consistent with the other values in the table.

20. Table 3.2-2, Distance to Controlling Locations as Measured from the Brunswick Plant Center (Mi), was updated to include the 2013 Land Use Census data (DRR 331769).

21. Table 3.2-5 is being revised to utilize Pi values for the child inhalation pathway only.

These values were obtained from the Ri table for this same receptor as the Pi and Ri values are identical for inhalation pathways per the ODCM Appendix C. The zero values in the table were formatted to 0.OOE+00, since they were inconsistent. Some values were previously shown as 0.OOE 01 and 0.OOE-01. In addition, the column of nuclides was updated with dashes.

22. Section 3.3.1, Noble Gases, reference to the controlling location in two places is being change from the NE sector to the ENE sector. This was identified as the correct sector in Revision 26 and is currently the controlling sector.

23. Section 3.3.2 is being revised to add the release points Hot Shop (Decon) Facility, Radioactive Materials Container and Storage Building, and Low Level Warehouse as separate release points. Previously due to software limitations the releases from these points were included as part of releases from the Turbine Buildings. Separation of these release points does not change the quantification of activity or doses from these release points.

24. Section 3.3.2.2 is being revised to change the methodology for performing projected doses for gaseous releases such that the projected dose can be used to evaluate the impact of a release being performed. This change will help to ensure that if a release is performed without the use of the waste processing system that its effect can be determined on a pre-release / proactive basis. The projected dose equation is based on projected dose equations from the Shearon Harris, HB Robinson, and the Crystal River ODCMs.

Page 42 of 45

Attachment 8 Off-Site Dose Calculation Manual (ODCM) And Process Control Program (PCP) Revisions

25. In Tables 3.3-1 through 3.3-19 the zero values in the table were formatted to 0.OOE+00, since they were inconsistent. Some values were previously shown as 0.OOE 01 and O.OOE-01. In addition, the other values in the table were formatted to show plus signs where applicable instead of a blank space before the exponent. Missing dashes were also added to the nuclide column (ex. H 3 was corrected to H-3, etc.).

26. Tables 3.3-3, 3.3-8, 3.3-9, 3.3-11, 3.3-13, and 3.3-14 are being revised to correct several dose factors which were incorrect. The methodology for the calculation of these revised dose factors is based on ODCM Appendix C.

27. Figure 4.0-1 was missing the title and the page number was incorrect. The title was updated to match the title listed in the table of contents, BSEP Sample Point Locations.

28. Section 5 Index, the title for Section 5 was missing "RADIOLOGICAL."

29. Section 6 Index, the title for Section 6 did not match the title in the main Table of Contents. The title has been updated to TOTAL DOSE (40CFR190 COMPLIANCE) and this was updated on page 6-2 as well.

30. Table 7.3.3-1, Radioactive Liquid Waste Sampling and Analysis Program, was revised to add the Storm Drain Collection Basin sample frequency, analysis frequency, analysis type, and lower limits of detection. In addition footnote (k) was added to state:

"Releasing water directly to the discharge canal through the storm drain basin overflow valves is prohibited by the National Pollutant Discharge Elimination System (NPDES) permit except where unavoidable to prevent loss of life, personnel injury, or severe property damage. Sometimes due to unanticipated inclement weather a pre-release sample is not able to be obtained, however, there is a composite sampler that samples the basin continuously and can be used for the pre-release sample."

31. ODCM Specification 7.3.5.2 is being revised to add a note detailing that performance of dose projections is only required when the liquid radwaste system is not being used to being used treat waste. Since the action to treat waste is required if a dose projection limit is exceeded, the use of the treatment system proactively eliminates the need to check if the waste system must be used. This change is consistent with the same note found for gaseous waste in ODCM Specification 7.3.11.2.

32. Table 7.3.7-1 is being revised to fix spacing issues in the names of the Radioactive Materials Container and Storage Building and Low Level Warehouse. These changes are editorial. Additionally the table is being revised to change the sampling frequency for these two points from "each batch release" to "7 days (i)" and remove the title of "Batch Release". These release points are more suited as a continuous release (with intermittent operation) as a discreet release volume is not associated with these points. Footnote (i) was also added which states, "Sample cartridges/filters shall be changed at least once per 7 days when the facility is in operation and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (or after removal from sampler)."

Page 43 of 45

Attachment 8 Off-Site Dose Calculation Manual (ODCM) And Process Control Program (PCP) Revisions

33. Table 7.3.15-2 and Table 7.3.15-3 are being revised to add lines for each column and row so the data in the tables is easier to read.

34. Appendix A is being revised to remove the x/Q, depleted x/Q, and D/Q tables at special locations for the Turbine Buildings, Reactor Buildings, and Stack. The same information can be found in the tables for standard distances located in Appendix A. As a result of this change the List of Tables have been updated under the Table of Contents and in Appendix A.

35. Appendix B page B-4 is being revised to change the controlling location from the NE sector to the ENE sector. Additionally the references to the associated tables are being changed. No table data is being changed. This is an editorial change as ENE sector is currently the controlling sector.

36. Appendix C was updated to reflect the changes made in Section 3.2.2 of the ODCM.

Since the inhalation pathway is the only pathway used for Pi, the ground plane and milk pathway Pi calculations have been removed from Appendix C.

37. Appendix G is being revised to specify the software used for performing effluent release accountability is being replaced. The new software OpenEMS performs similar functions to ensure that releases are maintained with applicable ODCM limitations.

These changes still maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I. In addition, these changes do not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

Page 44 of 45

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

Page 45 of 45

BSEP 14-0038 Enclosure 2 Offsite Dose Calculation Manual Revision 37

BRUNSWICK STEAM ELECTRIC PLANT OFF-SITE DOSE CALCULATION MANUAL (ODCM)

REVISION 37 DOCKET NOS. 50-324 50-325 CAROLINA POWER & LIGHT COMPANY Effective Date Approved By:

IINSC

LIST OF EFFECTIVE PAGES Pages Revision Pages Revision Paoes Revision i-x 37 7-iv - 7.1.1-1 25 7.3.15-14 36 xi 35 7.1.1-2 30 7.3.16-1 30 xii 37 7.1.1-3 27 7.3.16 7.4.0-2 25 1-1 34 7.1.1 7.3.0-4 25 7.4.0-3 30 2-1 35 7.3.1-1 29 7.5.0-1-B 7.3.0-10 25 2 2-4 37 7.3.1 7.3.1-3 25 B 7.3.1-1 29 2-5 25 7.3.1-4 35 B 7.3.2 B 7.3.2-2 33 2 2-7 37 7.3.1-5 26 B 7.3.3-1 35 2-8 37 7.3.1-6 25 B 7.3.4 B 7.3.6-1 25 2-9 35 7.3.1-7 35 B 7.3.7 B 7.3.8-1 30 2-10 37 7.3.2-1 29 B 7.3.9-1 31 2-11 12 35 7.3.2 7.3.2-4 25 B 7.3.10-1 25 2-13-3-3 37 7.3.2 7.3.2-6 33 B 7.3.11 B 7.3.17-1 25 3-4 35 7.3.2-7 26 A-1 -A-18 37 3 3-8 30 7.3.2-8 25 B B-3 30 3-9 25 7.3.2 7.3.2.10 33 B-4 37 3-10 30 7.3.2-11 36 B B-36 30 3-11 37 7.3.2-12 32 C-1 -C-13 37 3-12-3-13 30 7.3.3-1 25 D-1 25 3-14 25 7.3.3 7.3.3-3 35 E E-3 35 3-15-3-17 30 7.3.3 7.3.3-5 37 F-1 25 3-18-3-19 37 7.3.3-6 35 F-2 26 3 3-21 30 7.3.3-7 25 F-3 32 3-22 25 7.3.3-8 31 G-1 37 3 3-66 37 7.3.4 7.3.5-1 25 H H-2 35 4-1 2 25 7.3.5-2 37 4-3 26 7.3.6 7.3.7-1 25 4-4 32 7.3.7-2 37 4-5 30 7.3.7-3 25 4-6 34 7.3.7-4 37 4-7-4-12 35 7.3.8 7.3.8-2 25 4-13-5-1 37 7.3.9-1 31 5-2 30 7.3.9 7.3.15-5 25 5-3 35 7.3.15 7.3.15-8 35 6-1-6-2 37 7.3.15 7.3.15-10 25 6 7-ii 25 7.3.15 7.3.15-12 37 7-iii 30 7.3.15-13 25 ODCM (BSEP) ii Rev. 37

TABLE OF CONTENTS Section Title Paqe SECTION 1 INTRODUCTION INTRODUCTION .................................................................................................................. 1-1 SECTION 2 LIQUID EFFLUENTS IND EX T O S EC T IO N 2 ........................................................................................................... 2-1 2.1 COMPLIANCE WITH 10CFR PART 20 (LIQUIDS) ................................... 2-3 2.2 COMPLIANCE WITH 10CFR PART 50 (LIQUIDS) ................................. 2-12 SECTION 3 GASEOUS EFFLUENTS IND EX T O S EC T IO N 3 ........................................................................................................... 3-1 3.1 MONITOR ALARM SETPOINT DETERMINATION ................................... 3-4 3.2 COMPLIANCE WITH ODCM SPECIFICATION 7.3.7 (GASEOUS) ......... 3-17 3.3 COMPLIANCE WITH 10CFR50 (GASEOUS) .......................................... 3-30 SECTION 4 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM INDEX TO SECTION 4 ........................................................................................................... 4-1 SECTION 5 RADIOLOGICAL INTERLABORATORY COMPARISON STUDIES INDEX TO SECTION 5 ........................................................................................................... 5-1 5.1 OBJECTIVE .............................................................................................. 5-2 5.2 PROGRA M ............................................................................................... 5-2 SECTION 6 TOTAL DOSE (40CFR190) COMPLIANCE INDEX TO SECTIO N 6 ........................................................................................................... 6-1 6.1 INTRO DUCTIO N ....................................................................................... 6-2 6.2 G ENERA L................................................................................................. 6-2 6.3 CALCULATIO NS O F TOTAL BO DY DOSE .............................................. 6-3 6.4 THYRO ID DOSE ....................................................................................... 6-4 SECTION 7 OFFSITE DOSE CALCULATION MANUAL SPECIFICATIONS AND BASES INDEX TO SECTION 7 ............................................................................................................ 7-i 7.1.0 USE AND APPLICATION ................................................................... 7.1.1-1 7.2.0 NOT USED ......................................................................................... 7.2.0-1 7.3.0 OFFSITE DOSE CALCULATION MANUAL SPECIFICATION (ODCMS)

APPLICABILITY ................................................................................. 7.3.0-1 ODCM (BSEP) iii Rev. 37

TABLE OF CONTENTS Section Title Page 7.4.0 REPORTING REQUIREMENTS ......................................................... 7.4.0-1 7.5.0 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT S YS T E MS ........................................................................................... 7.5.0-1 OFFSITE DOSE CALCULATION MANUAL SPECIFICATION (ODCM)

B 7.3.0 APPLICABILITY BASES ................................................................. B 7.3.0-1 APPENDIX A METEOROLOGICAL DISPERSION FACTOR COMPUTATIONS ............. A-2 APPENDIX B CALCULATIONS OF Vi AND Bi VALUES FOR THE ELEVATED P LU ME ................................................................................................ B-1 APPENDIX C DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES AND T R ITIUM ............................................................................................. C -1 APPENDIX D LOWER LIMIT OF DETECTION (LLD) ...................................................... D-1 APPENDIX E RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION NUMBERS ............................................................. E-1 APPENDIX F LIQUID AND GASEOUS EFFLUENT SYSTEM DIAGRAMS ................. F-1 APPENDIX G ODCM SOFTWARE PACKAGE ............................................................... G-1 APPENDIX H x/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE STABILIZATION FACILITY .................................................... H-2 ODCM (BSEP) iv Rev. 37

LIST OF TABLES No. Title Page SECTION 2 2.1-1 ECs FOR SELECTED RADIONUCLIDES ............................................... 2-11 2.2-1 Ait VALUES FO R THE ADULT ................................................................. 2-14 SECTION 3 3.1-1 GALE CODE 30 MINUTE AIR EJECTOR TECHNICAL SPECIFICATIO N ................................................................. 3-11 3.1-2 GASEOUS SOURCE TERMS .................................................................. 3-15 3.1-3 DOSE FACTORS AND CONSTANTS ...................................................... 3-16 3.2-1 RELEASES FROM BRUNSWICK STEAM ELECTRIC PLANT ................ 3-25 3.2-2 DISTANCE TO CONTROLLING LOCATIONS AS MEASURED FROM THE BRUNSW ICK PLANT CENTER ....................................................... 3-26 3.2-3 DISTANCE TO SITE BOUNDARIES BASED UPON BRUNSWICK PLANT CENTER AND DIRECTION FROM THE STACK ......................... 3-27 3.2-4 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS ................... 3-28 3.2-5 Pi VALUES FOR A CHILD FOR THE BRUNSWICK STEAM E LEC T R IC P LA NT ................................................................................... 3-29 3.3-1 THRU R VALUES FOR THE BRUNSWICK STEAM ELECTRIC 3.3-19 P LA NT ..................................................................................................... 3-4 3 3.3-20 INHALATION DOSE FACTORS FOR CARBON-14 ................................. 3-64 3.3-21 INGESTION DOSE FACTORS FOR CARBON-14 ................................... 3-66 SECTION 4 4.0-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM .............. 4-4 SECTION 7 7.3.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTR UM ENTATIO N ........................................................................... 7.3.1-7 7.3.2-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTR UM ENTATIO N ........................................................................... 7.3.2-9 ODCM (BSEP) V Rev. 37

LIST OF TABLES No. Title Paae SECTION 7 (Cont'd) 7.3.3-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS P R O G RA M........................................................................................... 7.3.3-3 7.3.3-2 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM FOR POTENTIAL RELEASE PATHWAYS WHICH HAVE EXCEEDED TRIGGER LEVELS ............................................... 7.3.3-6 7.3.7-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PR O G RA M........................................................................................... 7.3.7-2 7.3.15-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ...... 7.3.15-6 7.3.15-2 LIMITS FOR THE LEVEL OF RADIOACTIVITY IN ENVIRONMENTAL SAMPLES ......................................................... 7.3.15-11 7.3.15-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE A NA LY S IS ........................................................................................ 7.3.15-12 ODCM (BSEP) vi Rev. 37 1

APPENDIX A A-1 X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE TURBINE BUILDINGS ............................................................ A-4 A-2 DEPLETED X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE TURBINE BUILDINGS ........................................ A-5 A-3 D/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE TURBINE BUILDINGS ............................................................ A-6 A-4 X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE REACTOR BUILDINGS .......................................................... A-7 A-5 DEPLETED X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE REACTOR BUILDINGS ....................................... A-8 A-6 D/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE REACTOR BUILDINGS .......................................................... A-9 A-7 X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FRO M THE STACK .............................................................................. A-10 A-8 DEPLETED X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE STACK ........................................................ A-i 1 A-9 D/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FR O M TH E STA C K .................................................................................. A -12 A-10 BRUNSWICK PLANT SITE INFORMATION TO BE USED FOR GROUND LEVEL CALCULATIONS WITH NRC "XOQDOQ" P R O G RA M ............................................................................................... A-13 A-11 BRUNSWICK PLANT SITE INFORMATION TO BE USED FOR ELEVATED RELEASE CALCULATIONS WITH NRC "XOQDOQ" P R O G RA M .............................................................................................. A-16 ODCM (BSEP) vii Rev. 37

APPENDIX B B-1 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES ENE S ITE BO UNDA R Y ..................................................................................... B-5 B-2 JOINT FREQUENCY DISTRIBUTION FOR ENE SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM E LE C T R IC P LA NT ..................................................................................... B-6 B-3 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES N SITE B O UNDA R Y .............................................................................................. B-7 B-4 JOINT FREQUENCY DISTRIBUTION FOR N SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELEC T R IC P LA NT ..................................................................................... B-8 B-5 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NNE SITE BO UNDA R Y ............................................................................................... B-9 B-6 JOINT FREQUENCY DISTRIBUTION FOR THE NNE SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC PLA NT ............................................................................... B-10 B-7 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NE SITE BO UNDA R Y ........................................................................................ B-11 B-8 JOINT FREQUENCY DISTRIBUTION FOR NE SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM E LECT R IC P LA NT ................................................................................... B-12 B-9 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES E SITE BO UND AR Y ............................................................................................. B-13 B-10 JOINT FREQUENCY DISTRIBUTION FOR E SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTR IC PLA NT ................................................................................... B-14 ODCM (BSEP) viii Rev. 37

LIST OF TABLES No. Title Page APPENDIX B (Cont'd)

B-1 1 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES ESE S ITE BO UNDA R Y .................................................................................... B-15 B-12 JOINT FREQUENCY DISTRIBUTION FOR ESE SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM E LECT R IC P LA NT ................................................................................... B-16 B-13 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SE S IT E B O UNDA R Y .................................................................................... B-17 B-14 JOINT FREQUENCY DISTRIBUTION FOR SE SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECT R IC PLA NT ................................................................................... B-18 B-15 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SSE S ITE BO UNDA R Y .................................................................................... B-19 B-16 JOINT FREQUENCY DISTRIBUTION FOR SSE SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELEC TR IC PLANT ................................................................................... B-20 B-17 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES S SITE B O UND A R Y ............................................................................................. B -2 1 B-18 JOINT FREQUENCY DISTRIBUTION FOR S SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELEC TR IC PLANT ................................................................................... B-22 B-19 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SSW S ITE BO UNDA RY .................................................................................... B-23 B-20 JOINT FREQUENCY DISTRIBUTION FOR SSW SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELEC TR IC PLANT ................................................................................... B-24 B-21 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SW SITE B O UNDA R Y............................................................................................. B-25 B-22 JOINT FREQUENCY DISTRIBUTION FOR SW SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECT R IC P LA NT ................................................................................... B-26 ODCM (BSEP) ix Rev. 37

LIST OF TABLES No. Title Page APPENDIX B (Cont'd)

B-23 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES WSW S IT E BO U N DA R Y .................................................................................... B-27 B-24 JOINT FREQUENCY DISTRIBUTION FOR WSW SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM E LECT R IC P LA N T ................................................................................... B-28 B-25 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES W SITE BO U N D AR Y ............................................................................................. B-29 B-26 JOINT FREQUENCY DISTRIBUTION FOR W SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELE C T R IC P LA NT ................................................................................... B-30 B-27 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES WNW S IT E BO U N DA R Y .................................................................................... B-31 B-28 JOINT FREQUENCY DISTRIBUTION FOR WNW SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELEC TR IC P LANT ................................................................................... B-32 B-29 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NW SITE B O U N DA R Y ............................................................................................. B-33 B-30 JOINT FREQUENCY DISTRIBUTION FOR NW SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELEC TR IC PLANT ................................................................................... B-34 B-31 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NNW SITE B O U N DA R Y ............................................................................................. B-35 B-32 JOINT FREQUENCY DISTRIBUTION FOR NNW SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECT R IC PLA NT ................................................................................... B-36 ODCM (BSEP) X Rev. 37

LIST OF TABLES No. Title Pagqe APPENDIX C C-1 PARAMETERS FOR COW AND GOAT MILK PATHWAYS ..................... C-14 C-2 PARAMETERS FOR THE MEAT PATHWAY ........................................... C-15 C-3 PARAMETERS FOR THE VEGETABLE PATHWAY ................................ C-16 APPENDIX H H-1 x/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE STABILIZATION FACILITY .................................................... H-2 ODCM (BSEP) xi Rev. 35

LIST OF FIGURES No. Title Paqe 4.0-1 BSEP Sample Point Locations ................................................................. 4-13 7.1.1-1 Site Boundary ....................................................................................... 7.1.1-5 F-1 Liquid Radwaste Effluent System ............................................................... F-2 F-2 Gaseous Radwaste Effluent System .......................................................... F-3 ODCM (BSEP) xii Rev. 37

INTRODUCTION The Off-Site Dose Calculation Manual (ODCM) provides the information and methodologies to be used by the Brunswick Steam Electric Plant (BSEP) to show compliance with 10CFR20, 10CFR50.36a, Appendix I of 10CFR50, 10CFR72, 40CFR190, and to assure compliance with ODCM Specifications (ODCMS).

The ODCM is based on "Radiological Effluent Technical Specifications for BWR's" (NUREG 0473, Draft), "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants" (NUREG 0133), and guidance from the United Stated Nuclear Regulatory Commission (NRC). Specific plant procedures for implementation of this manual are provided elsewhere.

These procedures will be utilized to assure compliance with ODCMS and Test Requirements (TRs) provided in the Radioactive Effluents Control Program.

The ODCM has been prepared as generically as possible to minimize the need for future revisions. Any changes to the ODCM will be reviewed and approved as indicated in the Administrative Control section of the BSEP Technical Specifications.

The Radioactive Effluent Release Report prepared after January 1 of each year will include an assessment of the annual radiation doses to members of the public from radioactive liquid and gaseous effluents using the methodology in the ODCM for the report period. This report will be inclusive of the requirements outlined in the BSEP Technical Specifications and ODCM Specifications.

ODCM (BSEP) 1-1 Rev. 34 1

INDEX 2.0 LIQUID EFFLUENT ..................................................................................................... 2-3 2.1 COM PLIANCE W ITH 10CFR PART 20 (LIQUIDS) ................................................ 2-3 2.1.1 Batch Releases .......................................................................................... 2-3 2.1.2 Continuous Releases ................................................................................. 2-8 2.1.3 Stabilization Pond and Stabilization Facility Releases ................................ 2-9 2.1.4 Groundwater Extraction System Releases ................................................. 2-9 2.1.5 Marsh Releases ....................................................................................... 2-10 2.2 COMPLIANCE W ITH 10CFR PART 50 (LIQUIDS) .............................................. 2-12 2.2.1 Cum ulation of Doses ................................................................................ 2-12 2.2.2 Projection of Doses .................................................................................. 2-13 ODCM (BSEP) 2-1 Rev. 35

LIST OF TABLES Table No. Title Paqe SECTION 2 2.1-1 ECs FOR SELECTED RADIONUCLIDES ................................................ 2-11 2.2-1 Ait VALUES FOR THE ADULT ................................................................. 2-15 I ODCM (BSEP) 2-2 Rev. 37

2.0 LIQUID EFFLUENT 2.1 COMPLIANCE WITH 10CFR PART 20 (LIQUIDS) 2.1.1 Batch Releases A batch release is the discharge of liquid waste of a discrete volume. Batch releases from the BSEP liquid radwaste system may occur from the waste sample tank, floor drain sample tank, detergent drain tank and the salt water tanks. The maximum release rate possible due to pump capacity is 200 GPM from all release tanks except the detergent drain tank, which has a maximum release rate of 50 GPM. All of the above liquid radwaste discharges go to the circulating water discharge canal. Circulating water leakage collected in the circulating water pits and low purity, low activity liquids are transferred to the salt water release tanks where they are recirculated, sampled, and released to the environment. For any batch release, if the radwaste monitor effluent is inoperable, then two independent samples are analyzed and must be within 15% of each other before the release is approved. The two samples may differ by more than 15% upon approval of the E&C Supervisor or equivalent. The maximum release rate is determined so that 10CFR Part 20 limits are not exceeded after dilution in the discharge canal.

The sampling and analysis frequency and the type of analysis required by the BSEP ODCM Specifications is given in Table 7.3.3-1. All applicable instrument numbers may be found in Appendix E.

1. Prerelease The radioactive content of each batch release will be determined prior to release in accordance with Table 7.3.3-1 of the BSEP ODCM Specifications. Compliance with 10CFR Part 20 will be shown in the following manner:

a. Minimum acceptable dilution factor:

DFo Z (Eq. 2.1-1)

Where:

DFo Minimum acceptable dilution factor determined from analysis of liquid effluent to be released.

C = Concentration of radionuclide i in the batch to be released, pCi/ml EC = Effluent concentration limit of radionuclide i from Appendix B, Table 2, Column 2 of 10CFR20, pCi/ml ODCM (BSEP) 2-3 Rev. 37

DFB (10) (DF.) (Eq. 2.1-2)

Where:

DFB Conservative dilution factor used by BSEP to calculate maximum release rate prior to release in order to assure compliance with 10CFR Part 20 10 A factor of 10 less than 10CFR Part 20 limits as specified in Appendix B, Table 2, Column 2. This factor represents one layer of conservatism for all releases at BSEP DFo Minimum acceptable dilution factor per Equation 2.1-1

b. Maximum release rate:

MRR = (n -1XRPFcw)+ (p -1XRPFsw) 2(DFB) (Eq 2.1-3)

Where:

MRR = Maximum release rate of the batch to be released, GPM n = Number of operating circulating water pumps p = Number of operating service water pumps RPFcw = Minimum rated pump flow of each circulating water pump

= 1.357 E5 GPM RPFsw = Rated pump flow of each service water pump

= 8E3GPM 2 = Engineering factor to prevent spurious alarms caused by deviations in the mixtures of radionuclides which affect the monitor response DFB = Conservative dilution factor used by BSEP to calculate maximum release rate prior to release in order to assure compliance with 10CFR Part 20 ODCM (BSEP) 2-4 Rev. 37

c. Monitor Alarm/Trip Setpoint:

Monitor alarm/trip setpoints are determined to ensure that the concentration of radionuclides in the liquid effluent released from the site to unrestricted areas does not exceed the limits specified in 10CFR Part 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. An effluent concentration (EC) of 2 E-4 jiCi/ml has been established for noble gases dissolved or entrained in liquid effluents, based on the assumption that Xenon-135 is the controlling radionuclide.

(NUREG 0133)

SP CT(Em){(n- 1XRPFcw)+ (p - 1XRPFsw)] +Bkg (Eq. 2.1-4)

RR Where:

SP = Monitor alarm/trip setpoint, cps Em = The monitor efficiency for the mixture of radionuclides in the liquid effluent prior to dilution, cps/g.Ci/ml CT 3 E-7 ýtCi/ml; engineering factor to ensure that the final concentration for the mixture of radionuclides will be less than 10CFR Part 20 limits at unrestricted areas n = Number of operating circulating water pumps p = Number of operating service water pumps RPFcw = 1.357 E5 GPM RPFsw = 8 E3GPM RR = 200 GPM; maximum design release rate Bkg = Background count rate due to internal contamination and the radiation levels in the area in which the monitor is installed when the detector sample chamber is filled with an uncontaminated fluid, cps SP 3 E -7(EmX(n - 1X1.357 E5)+ (p - 1X8.0 E3)] + Bkg (Eq. 2.1-5) 200 ODCM (BSEP) 2-5 Rev. 25

d. Calculated concentration at unrestricted area:

= (Ci) (MRR)

Conc (n -1) (RPFcw) + (p - 1) (RPF.*) (Eq. 2.1-6)

Where:

Conci = Calculated concentration of radionuclide i at the unrestricted area, g*Ci/ml Ci = Concentration of radionuclide i in the batch to be released, PiCi/mI MRR = Maximum release rate of the batch to be released (see Equation 2.1-3),

GPM n = Number of operating circulating water pumps P = Number of operating service water pumps RPFcw = 1.357 E5 GPM RPFsw = 8E3GPM

e. 10CFR Part 20 Prerelease Compliance Check:

Before initiating the batch release, one final check for compliance with 1 OCR Part 20 will be performed. If the calculated diluted Effluent Concentration Limit (ECL) fraction at the unrestricted area is less than or equal to 10, then 10CFR Part 20 limits have been met. The following equation must be true:

Y2i(Conci/Eci) - 10 (Eq. 2.1-7)

Where:

Conci = Concentration of radionuclide i at the unrestricted area per Equation 2.1-6,

ýLCi/ml ECi = Effluent concentration limit of radionuclide i from Appendix B, Table 2, Column 2 of 10CFR20, pCi/ml.

ODCM (BSEP) 2-6 Rev. 37

2. Postrelease The actual concentration of each radionuclide following release from a batch tank will be calculated to show final compliance with 10CFR Part 20 as follows:

a. Actual concentration at unrestricted area:

= (CN).(Ve) (Eq. 2.1-8)

Concik Vd, Where:

The actual concentration of radionuclide i at the unrestricted area during ConCik release k, ptCi/ml Ci = Concentration of radionuclide i in the batch released, gCi/ml Veff = Actual volume of liquid effluent released, gal Vdil = Actual volume of dilution water during release k, gal

= [n (RPFcw) + P (RPFsw)] (tk)

Where:

n = Number of operating circulating water pumps P = Number of operating service water pumps RPFcw = 1.357 E5 GPM RPFsw = 8E3GPM tk = Total release time, min

b. 10CFR Part 20 Postrelease Compliance Check:

To show final compliance with 10CFR Part 20, the following relationship must hold:

Ei (Concik/EC1 ) < 10 (Eq. 2.1-9)

Where:

ConCik The actual concentration of radionuclide i during release k (from Equation 2.1-8), jiCi/ml EC1 Annual average effluent concentration limit of radionuclide i from Appendix B, Table 2, Column 2 of 10CFR20, DCi/ml.

ODCM (BSEP) 2-7 Rev. 37

2.1.2 Continuous Releases A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of a system that has an input flow during the continuous release. The Groundwater Extraction System is considered a continuous release. The potential for a continuous release exists in the service water system. Weekly tests are performed on the service water system during system operation as specified in Table 7.3.3-1 of the BSEP ODCM Specifications. For continuous releases, the concentration of various radionuclides in the unrestricted area would be calculated using Equation 2.1-8 with C, being the concentration of radionuclide i in the continuous release stream. To show compliance with 10CFR Part 20, the sum of the concentration of radionuclide i in the unrestricted area due to both continuous and batch releases divided by that isotope's EC must be less than 10.

1. Service Water Effluent Monitor Setpoint Determination This procedure determines the monitor alarm setpoints that indicate the abnormal presence of radionuclides in the service water liquid effluents released from the site to unrestricted areas. This procedure is applicable to any service water effluent monitor.

a. Determine the monitor efficiency factor, EF, in jiCi/mi

, from the appropriate RST cps

b. Determine the monitor trigger level setpoint, TLS, in cps TLS TL/EF + Bkg (Eq. 2.1-10)

Where:

TL The alarm trigger level (jiCi/ml) as per ODCM TR 7.3.3.2

= 5.0 x 10-6 tCi/ml Bkg = Monitor background, (cps)

ODCM (BSEP) 2-8 Rev. 37

2.1.3 Stabilization Pond and Stabilization Facility Releases Prerelease and post-release compliance checks similar to those of Section 2.1.1 are to be performed for releases from the Stabilization Pond and Stabilization Facility. Prerelease calculations will be based on a gamma isotopic and a tritium analysis prior to release. Post-release calculations will be based on a composite sample that is collected in proportion to flow during the release period. Analyses will be performed on the composite sample after the release is complete in accordance with Table 7.3.3-1.

Dilution flow will be estimated from the minimum number of circulating water and service water pumps that were in use during the release period.

Typical release times are on the order of days. (Note: Calculated doses as in Section 2.2 will be compiled along with those resulting from normal radwaste discharges.)

2.1.4 Groundwater Extraction System Releases Prerelease and post release compliance checks similar to those of Section 2.1.1 are to be performed for releases from the Groundwater Extraction System. Prerelease calculations will be based on gamma isotopic and a tritium analysis prior to release. Post-release calculations will be based on a composite sample that is collected in proportion to flow during the release period. Analyses will be performed on the composite sample in accordance with Table 7.3.3-1. Dilution flow will be estimated from the minimum number of circulating water and service water pumps that were in use during the release period. (Note: Calculated doses as in Section 2.2 will be compiled along with those resulting from normal radwaste discharges.)

ODCM (BSEP) 2-9 Rev. 35 1'

2.1.5 Marsh Releases Marsh releases from the area around the outside area of the Stabilization Pond are an ongoing release. The release from the marsh areas to Nancy's Creek are sampled in accordance with Table 4.0-1. Curies released and associated doses will be determined and included in the Annual Radioactive Release Report. Doses will be calculated by the following methodology from Regulatory Guide 1.109:

Rapj =1100 ap-'P QB,,, Daipj Where:

Raj is total annual dose to organ j of individuals of age group a from all of the nuclides i in pathway p, in mrem/year; 1100 is the factor to convert from (Ci/yr)/(ft 3/sec) to pCi/liter; Uap is a usage factor that specifies the exposure time or intake rate for an individual of age group a associated with pathway p, in kg/yr; MP is the mixing ratio (reciprocal of the dilution factor) at the point of exposure (or the point of withdrawal of harvest of aquatic foods), dimensionless; F = is the flowrate of the liquid effluent in ft 3/sec; Q* = is the release rate of nuclide i, in Ci/yr; Bip = is the equilibrium bioaccumulation factor for nuclide i in pathway p, expressed as the ratio of the concentration in biota (in pCi/kg) to the radionuclide concentration in water (in pCi/liter), in liters/kg; A, = is the radioactive decay constant of nuclide i, in hr 1 ;

tp = is the average transit time required for nuclides to reach the point of exposure. For internal dose, tp is the total time elapsed between release of the nuclide and ingestion, in hours.

Daip] = is the dose factor, specific to a specific age group a, radionuclide i, pathway p, and organ j, which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem/pCi.

Historically, only tritium has been identified in the marsh areas, therefore only tritium will be routinely used in dose calculations unless other nuclides are identified. Due to tidal fluctuations in the marsh area the annual dose will be determined on two releases per day for the year using average activity for the year.

ODCM (BSEP) 2-10 Rev. 37

TABLE 2.1-1 ECs FOR SELECTED RADIONUCLIDES Radionuclide ECi (aCi/ml)

H-3 1 E-3 Na-24 5 E-5 Cr-51 5 E-4 Mn-54 3 E-5 Co-58 2 E-5 Fe-59 1 E-5 Co-60 3 E-6 Cu-64 2 E-4 Zn-65 5 E-6 Zn-69m 6 E-5 Sr-89 8 E-6 Sr-90 5 E-7 Sr-91 2 E-5 Zr-95 2 E-5 Mo-99 2 E-5 1-131 1 E-6 1-132 1 E-4 1-133 7 E-6 Cs-134 9 E-7 1-134 4 E-4 1-135 3 E-5 Cs-137 1 E-6 La-141 5 E-5 Np-239 2 E-5 Am-241 2 E-8 Noble Gases 2 E-4 ODCM (BSEP) 2-11 Rev. 35 1

2.2 COMPLIANCE WITH 10CFR PART 50 (LIQUIDS) 2.2.1 Cumulation of Doses ODCM TR 7.3.4.1 requires that the cumulative dose contributions from liquid effluents be determined at least once per 31 days, and a cumulative summation of these total body and any organ doses should be maintained for each calendar quarter. The cumulative dose contributions will consider the dose contributions from the maximum exposed individual's consumption of fish and invertebrates. At BSEP the adult is considered as the maximum exposed individual. The dose or dose commitment limits based on 10CFR Part 50, Appendix I, are defined in ODCM Specification 7.3.4 a and b. The dose contribution for all releases for the quarter will be calculated using the following equation:

DT Z[=i 4k C,,k Fk] (Eq. 2.2-1)

Where:

D = The cumulative dose commitment to the total body or any organ t, from the liquid effluents releases, mrem tk = The length of time of release k over which Cik and Fk are averaged for each liquid release, hours Cik = The concentration of radionuclide i in the undiluted liquid effluent during release k from any liquid release, jiCi/ml Fk The near-field average dilution factor for Cik during any liquid effluent release. It is defined as the ratio of the volume of undiluted liquid waste released to the product of the dilution volume from the site discharge to unrestricted receiving water times 1. (1 is the site-specific applicable factor for the mixing effect of the BSEP discharge structure as defined in NUREG 0133.)

= Ve. (See Equation 2.1-8).

Vdii AiT The ingestion dose commitment factor to the total body or any organ T for each identified gamma and beta emitter i (as presented in Table 2.2-1).

Values are for an adult, mrem-ml per hr-jiCi

= 1.14 E5 (5 Bli + 21 BFi) DCFi, ODCM (BSEP) 2-12 Rev. 35 1

Where:

1.4E5 =, r6Pc!r103

ýtCi) mlI'< lyr L ) 8760 hr) 5 = Maximum adult invertebrate consumption rate from Table E-5 of Regulatory Guide 1.109, Rev. 1, kg/yr BlI = Bioaccumulation factor for radionuclide i in invertebrates from Table A-1 of Regulatory Guide 1.109, Rev. 1, pCi/kg per pCi/L 21 = Maximum adult fish consumption rate from Table E-5 of Regulatory Guide 1.109, Rev. 1, kg/yr BFi = Bioaccumulation factor for radionuclide i in fish from Table A-1 of Regulatory Guide 1.109, Rev. 1, pCi/kg per pCi/L DCFi = Dose conversion factor for radionuclide i for adults for a particular organ c from Table E-11 of Regulatory Guide 1.109, Rev. 1, and BSEP File:

B10-10530, Letter to J. W. Davis, "Dose Factors for Hf-181 and Sn-113,"

May 24, 1988, and NUREG CR4653 for Am-241, mrem/pCi.

2.2.2 Proiection of Doses Dose projections for this section are required at least once per 31 days in ODCM TR 7.3.5.2.

The projection of doses for liquid effluents can be accomplished by using Equation 2.2-2. Where possible, credit for expected operational evolutions (i.e., major planned liquid releases, etc.), can be taken in the dose projections. This may be accomplished by using the source-term data from similar historical operating experiences where practical and adding the dose as additional anticipated dose.

D, ,xRL 3l1 +JD, (Eq. 2.2-2)

Where:

31 day projected dose by organ 'in mrem; D. = Current cumulative monthly dose of organ T up to the end of the release under evaluation, in mrem; Te= Time elapsed in month up to the end of the release under evaluation, in days; 31= Number of days dose is projected; and Da, = Additional anticipated dose by organ " in mrem ODCM (BSEP) 2-13 Rev. 37

TABLE 2.2-1 Ait VALUES FOR THE ADULT (MREM/HR PER MICRO-CI/ML)

Note: Nuclides not listed in this table are assigned a value of zero.

Nuclide Bone Liver T.Body Thyroid Kidney LunA GI-LLI H-3 0.OOE+00 2.82E-01 2.82E-01 2.82E-01 2.82E-01 2.82E-01 2.82E-01 C-14 1.45E+04 2.90E+03 2.90E+03 2.90E+03 2.90E+03 2.90E+03 2.90E+03 NA-24 4.57E-01 4.57E-01 4.57E-01 4.57E-01 4.57E-01 4.57E-01 4.57E-01 P-32 1.67E+07 1.04E+06 6.45E+05 O.OOE+00 0.OOE+00 O.OOE+00 1.89E+06 CR-51 0.OOE+00 0.O0E+00 5.58E+00 3.34E+00 1.23E+00 7.40E+00 1.40E+03 MN-54 O.OOE+00 7.06E+03 1.35E+03 0.OOE+00 2.1OE+03 0.OOE+00 2.16E+04 MN-56 0.OOE+00 1.78E+02 3.15E+01 0.OOE+00 2.26E+02 0.OOE+00 5.67E+03 FE-55 5.11 E+04 3.53E+04 8.23E+03 0.OOE+00 0.OOE+00 1.97E+04 2.03E+04 FE-59 8.06E+04 1.90E+05 7.27E+04 O.OOE+00 O.OOE+00 5.30E+04 6.32E+05 CO-57 O.OOE+00 1.42E+02 2.36E+02 0.OOE+00 0.OOE+00 0.OOE+00 3.59E+03 CO-58 0.OOE+00 6.03E+02 1.35E+03 O.OOE+00 0.OOE+00 0.OOE+00 1.22E+04 CO-60 0.OOE+00 1.73E+03 3.82E+03 0.OOE+00 0.OOE+00 O.OOE+00 3.25E+04 NI-63 4.96E+04 3.44E+03 1.67E+03 0.OOE+00 O.OOE+00 0.OOE+00 7.18E+02 NI-65 2.02E+02 2.62E+01 1.20E+01 0.OOE+00 0.OOE+00 0.OOE+00 6.65E+02 CU-64 O.OOE+00 2.14E+02 1.01 E+02 0.OOE+00 5.40E+02 O.OOE+00 1.83E+04 ZN-65 1.61E+05 5.13E+05 2.32E+05 O.OOE+00 3.43E+05 0.OOE+00 3.23E+05 ZN-69 3.43E+02 6.56E+02 4.56E+01 0.OOE+00 4.26E+02 O.OOE+00 9.85E+01 BR-83 O.OOE+00 0.OOE+00 7.25E-02 O.OOE+00 O.OOE+00 0.OOE+00 1.04E-01 BR-84 0.00E+00 O.OOE+00 9.39E-02 0.OOE+00 0.OOE+00 0.OOE+00 7.37E-07 BR-85 O.OOE+00 0.OOE+00 3.86E-03 0.OOE+00 0.OOE+00 0.OOE+00 1.80E-18 RB-86 0.OOE+00 6.24E+02 2.91E+02 O.OOE+00 0.OOE+00 O.OOE+00 1.23E+02 RB-88 0.OOE+00 1.79E+00 9.49E-01 O.OOE+00 0.OOE+00 0.OOE+00 2.47E-1 1 RB-89 0.OOE+00 1.19E+00 8.34E-01 0.OOE+00 O.OOE+00 0.OOE+00 6.89E-14 SR-89 4.99E+03 0.OOE+00 1.43E+02 0.OOE+00 O.OOE+00 0.OOE+00 8.OOE+02 SR-90 1.23E+05 O.OOE+00 3.01 E+04 0.OOE+00 O.OOE+00 O.OOE+00 3.55E+03 SR-91 9.18E+01 O.OOE+00 3.71 E+00 0.OOE+00 O.OOE+00 0.OOE+00 4.37E+02 SR-92 3.48E+01 O.OOE+00 1.51 E+00 O.OOE+00 0.OOE+00 0.OOE+00 6.90E+02 Y-90 6.06E+00 0.OOE+00 1.63E-01 0.OOE+00 0.OOE+00 0.OOE+00 6.42E+04 Y-91M 5.73E-02 0.OOE+00 2.22E-03 0.OOE+00 O.OOE+00 O.OOE+00 1.68E-01 Y-91 8.88E+01 O.OOE+00 2.37E+00 0.OOE+00 0.OOE+00 0.OOE+00 4.89E+04 Y-92 5.32E-01 0.O0E+00 1.56E-02 O.OOE+00 0.OOE+00 0.OOE+00 9.32E+03 Y-93 1.69E+00 0.OOE+00 4.66E-02 O.OOE+00 0.OOE+00 O.OOE+00 5.35E+04 ODCM (BSEP) 2-14 Rev. 37

TABLE 2.2-1 (Cont'd)

Nuclide Bone Liver T.Body Thyroid Kidney lunQ GI-LLI ZR-95 1.59E+01 5.11E+00 3.46E+00 O.OOE+00 8.02E+00 0.OOE+00 1.62E+04 ZR-97 8.81E-01 1.78E-01 8.13E-02 0.OOE+00 2.68E-01 0.OOE+00 5.51E+04 NB-95 4.47E+02 2.49E+02 1.34E+02 0.OOE+00 2.46E+02 0.OOE+00 1.51E+06 MO-99 0.OOE+00 1.28E+02 2.43E+01 0.OOE+00 2.89E+02 0.OOE+00 2.96E+02 TC-99M 1.30E-02 3.66E-02 4.66E-01 O.OOE+00 5.56E-01 1.79E-02 2.17E+01 TC-101 1.33E-02 1.92E-02 1.88E-01 0.OOE+00 3.46E-01 9.81E-03 5.77E-14 RU-103 1.07E+02 O.OOE+00 4.60E+01 0.OOE+00 4.07E+02 0.OOE+00 1.25E+04 RU-105 8.89E+00 O.OOE+00 3.51E+00 O.OOE+00 1.15E+02 O.OOE+00 5.44E+03 RU-106 1.59E+03 O.OOE+00 2.01E+02 O.OOE+00 3.06E+03 O.OOE+00 1.03E+05 AG-11OM 1.56E+03 1.45E+03 8.60E+02 O.OOE+00 2.85E+03 O.OOE+00 5.91E+05 SN-113 2.18E+03 8.43E+01 2.05E+03 2.96E+01 6.16E+01 O.OOE+00 3.80E+04 TE-125M 2.17E+02 7.86E+01 2.91E+01 6.52E+01 8.82E+02 O.OOE+00 8.66E+02 TE-127M 5.48E+02 1.96E+02 6.68E+01 1.40E+02 2.23E+03 O.OOE+00 1.84E+03 TE-127 8.90E+00 3.20E+00 1.93E+00 6.60E+00 3.63E+01 O.OOE+00 7.03E+02 TE-129M 9.31 E+02 3.47E+02 1.47E+02 3.20E+02 3.89E+03 O.OOE+00 4.69E+03 TE-129 2.54E+00 9.55E-01 6.19E-01 1.95E+00 1.07E+01 O.OOE+00 1.92E+00 TE-131M 1.40E+02 6.85E+01 5.71E+01 1.08E+02 6.94E+02 O.OOE+00 6.80E+03 TE-131 1.59E+00 6.66E-01 5.03E-01 1.31E+00 6.99E+00 O.OOE+00 2.26E-01 TE-132 2.04E+02 1.32E+02 1.24E+02 1.46E+02 1.27E+03 O.OOE+00 6.24E+03 1-130 3.96E+01 1.17E+02 4.61E+01 9.91E+03 1.82E+02 O.OOE+00 1.01 E+02 1-131 2.18E+02 3.12E+02 1.79E+02 1.02E+05 5.35E+02 O.OOE+00 8.23E+01 1-132 1.06E+01 2.85E+01 9.96E+00 9.96E+02 4.54E+01 O.OOE+00 5.35E+00 1-133 7.45E+01 1.30E+02 3.95E+01 1.90E+04 2.26E+02 O.OOE+00 1.16E+02 1-134 5.56E+00 1.51E+01 5.40E+00 2.62E+02 2.40E+01 O.OOE+00 1.32E-02 1-135 2.32E+01 6.08E+01 2.24E+01 4.01 E+03 9.75E+01 O.OOE+00 6.87E+01 CS-134 6.84E+03 1.63E+04 1.33E+04 0.OOE+00 5.27E+03 1.75E+03 2.85E+02 CS-136 7.16E+02 2.83E+03 2.04E+03 0.OOE+00 1.57E+03 2.16E+02 3.21E+02 CS-1 37 8.77E+03 1.20E+04 7.85E+03 O.OOE+00 4.07E+03 1.35E+03 2.32E+02 CS-138 6.07E+00 1.20E+01 5.94E+00 0.OOE+00 8.81E+00 8.70E-01 5.12E-05 BA-139 7.85E+00 5.59E-03 2.30E-01 O.OOE+00 5.23E-03 3.17E-03 1.39E+01 BA-140 1.64E+03 2.06E+00 1.08E+02 0.OOE+00 7.02E-01 1.18E+00 3.38E+03 BA-141 3.81E+00 2.88E-03 1.29E-01 O.OOE+00 2.68E-03 1.63E-03 1.80E-09 BA-142 1.72E+00 1.77E-03 1.08E-01 O.OOE+00 1.50E-03 1.OOE-03 2.43E-18 LA-140 1.57E+00 7.94E-01 2.10E-01 O.OOE+00 0.OOE+00 O.OOE+00 5.83E+04 ODCM (BSEP) 2-15 Rev. 37

TABLE 2.2-1 (Cont'd)

Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI LA-142 8.06E-02 3.67E-02 9.13E-03 O.OOE+00 O.OOE+00 O.OOE+00 2.68E+02 CE-141 3.43E+00 2.32E+00 2.63E-01 O.OOE+00 1.0BE+00 O.OOE+00 8.86E+03 CE-143 6.04E-01 4.46E+02 4.94E-02 O.OOE+00 1.97E-01 O.OOE+00 1.67E+04 CE-144 1.79E+02 7.47E+01 9.59E+00 O.OOE+00 4.43E+01 O.OOE+00 6.04E+04 PR-143 5.79E+00 2.32E+00 2.87E-01 O.OOE+00 1.34E+00 O.OOE+00 2.54E+04 PR-144 1.90E-02 7.87E-03 9.64E-04 O.OOE+00 4.44E-03 O.OOE+00 2.73E-09 ND-147 3.96E+00 4.58E+00 2.74E-01 O.OOE+00 2.68E+00 O.OOE+00 2.20E+04 HF-181 1.72E+02 9.66E-01 1.94E+01 6.14E-01 8.08E-01 O.OOE+00 1.27E+04 W-187 9.16E+00 7.66E+00 2.68E+00 O.OOE+00 O.OOE+00 O.OOE+00 2.51E+03 NP-239 3.53E-02 3.47E-03 1.91 E-03 O.OOE+00 1.08E-02 O.OOE+00 7.11E+02 AM-241 4.76E+05 4.44E+05 3.41 E+04 O.OOE+00 2.56E+05 O.OOE+00 4.67E+04 F-18 6.66E+00 O.OOE+00 7.38E-01 O.OOE+00 O.OOE+00 O.OOE+00 1.97E-01 SB-124 2.76E+02 5.22E+00 1.09E+02 6.70E-01 O.OOE+00 2.15E+02 7.84E+03 ODCM (BSEP) 2-16 Rev. 37

INDEX 3.0 GASEOUS EFFLUENTS ............................................................................................. 3-4 3.1 MONITOR ALARM SETPOINT DETERMINATION ................................................ 3-4 3.1.1 Setpoint Based on Conservative Radionuclide Mix (Ground and Mixed Mode Releases) .......................................................... 3-4 3.1.2 Setpoint Based on Conservative Radionuclide Mix (Long-Term Elevated Release .............................................................................. 3-7 3.1.3 Condenser Air Ejector Monitor Alarm Setpoint ......................................... 3-10 3.1.4 Condenser Off-Gas Treatment System (AOG) Monitor Alarm Setpoint D eterm ination ............................................................................. 3-13 3.2 COMPLIANCE WITH ODCM SPECIFICATION 7.3.7 (GASEOUS) ...................... 3-17 3.2.1 Noble G ases ............................................................................................ 3-17 3.2.2 1-131, 1-133, Particulates, and Tritium ....................................................... 3-23 3.3 COMPLIANCE WITH 10CFR50 (GASEOUS) ...................................................... 3-30 3.3.1 Noble G ases ............................................................................................ 3-30 3.3.2 1-131, 1-133, Particulates, and Tritium ....................................................... 3-35 ODCM (BSEP) 3-1 Rev. 37

LIST OF TABLES Table No. Title Page SECTION 3 3.1-1 GALE CODE 30 MINUTE AIR EJECTOR TECHNICAL SPECIFICATION 3-11 I 3.1-2 GASEO US SOURCE TERMS .................................................................. 3-15 3.1-3 DOSE FACTORS AND CONSTANTS ...................................................... 3-16 3.2-1 RELEASES FROM BRUNSWICK STEAM ELECTRIC PLANT ................ 3-25 3.2-2 DISTANCE TO CONTROLLING LOCATIONS AS MEASURED FROM THE BRUNSW ICK PLANT CENTER ....................................................... 3-26 3.2-3 DISTANCE TO SITE BOUNDARIES BASED UPON BRUNSWICK PLANT CENTER AND DIRECTION FROM THE STACK ......................... 3-27 3.2-4 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS ................... 3-28 3.2-5 Pi VALUES FOR A CHILD FOR THE BRUNSWICK STEAM E LE C T R IC P LA NT ................................................................................... 3-29 3.3-1 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT - GROUND.. 3-43 3.3-2 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -

VEG ETABLE/AD ULT ............................................................................... 3-44 3.3-3 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -

VEG ETA BLE/TEEN ................................................................................. 3-45 3.3-4 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -

VEG ETA BLE/C HILD ................................................................................ 3-46 3.3-5 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -

MEAT/A D ULT .......................................................................................... 3-47 3.3-6 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -

MEA T/T E E N............................................................................................. 3-48 3.3-7 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -

MEA T/C HILD ........................................................................................... 3-49 3.3-8 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT - COW MILK/A D ULT ............................................................................................ 3-50 ODCM (BSEP) 3-2 Rev. 37

LIST OF TABLES Table No. Title Paqe 3.3-9 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT - COW MILK/T E E N .............................................................................................. 3-5 1 3.3-10 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT - COW MILK/C HILD ............................................................................................. 3-52 3.3-11 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT - COW MILK/IN FA NT ........................................................................................... 3-53 3.3-12 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT - GOAT MILK/A D ULT ............................................................................................ 3-54 3.3-13 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT - GOAT MILK /T E E N .............................................................................................. 3-55 3.3-14 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT - GOAT MILK/C HILD ............................................................................................. 3-56 3.3-15 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT - GOAT MILK/INFA NT ........................................................................................... 3-57 3.3-16 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -

INHA LATIO N/A D ULT ............................................................................... 3-58 3.3-17 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -

INHA LAT IO N/TEEN ................................................................................. 3-59 3.3-18 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -

INHA LATIO N/C HILD ................................................................................ 3-60 3.3-19 R VALUES FOR BRUNSWICK STEAM ELECTRIC PLANT -

INHA LAT IO N/IN FA NT .............................................................................. 3-61 3.3-20 INHALATION DOSE FACTORS FOR CARBON-14 ................................. 3-64 3.3-21 INGESTION DOSE FACTORS FOR CARBON-14 ................................... 3-66 ODCM (BSEP) 3-3 Rev. 37

3.0 GASEOUS EFFLUENTS 3.1 MONITOR ALARM SETPOINT DETERMINATION This procedure determines the monitor alarm setpoint that indicates if the dose rate in the unrestricted areas due to noble gas radionuclides in the gaseous effluent released from the site to areas at and beyond the site boundary exceeds 500 mrem/year to the whole body or exceeds 3000 mrem/year to the skin.

(NUREG-01 33) 3.1.1 Setpoint Based on Conservative Radionuclide Mix (Ground and Mixed Mode Releases)

The following method applies to gaseous releases via the Units 1 and 2 Turbine Building Vents and via the Units 1 and 2 Reactor Building Vents when determining the high alarm setpoint for the Turbine Building Vent Gas Monitors and Reactor Building Vent Gas Monitors.

1. Determine the "mix" (noble gas radionuclide composition) of the gaseous effluent (the "mix" can be determined from actual data or by using GALE code results of Table 3.1-2):*

a. Determine the gaseous source terms that are representative of the "mix" of the gaseous effluent. Gaseous source terms are the noble gas activities in the effluent.

Gaseous source terms can be obtained from:

- Table 3.1-2; Turbine Building Vent Release

- Table 3.1-2; Reactor Building Vent Release

- Actual release data

b. Determine Si (the fraction of the total noble gas radioactivity in the gaseous effluent comprised by noble gas radionuclide i) for each individual noble gas radionuclide in the gaseous effluent.

Si Ai (3.1-1)

Ei Ai Ai The radioactivity of noble gas radionuclide i in gaseous effluent from Table 3.1-2, Turbine Building Vent Release; Table 3.1-2, Reactor Building Vent Release; or from analysis of gaseous effluent.

Ifactual plant data is used, the dose constants need to be confirmed.

ODCM (BSEP) 3-4 Rev. 35

2. Determine Qt (the maximum acceptable total release rate of all noble gas radionuclides in the gaseous effluent, jiCi/sec) based upon the whole body exposure limit.

Qt (X/Q) 500 Y-,i(Ki Si) (3.1-2)

(X/Q~t= The highest calculated annual average relative concentration of effluents released via the Turbine Building Vent for any area at or beyond the site boundary for all sectors (sec/m 3) from Table A-i, Appendix A 3

= 1.5 E-5 sec/m X-IQT = The highest calculated annual average relative concentration of effluents released via the Reactor Building Vent for any area at or beyond the site boundary for all sectors (sec/m 3) from Table A-7, Appendix A 3

= 2.5 E-6 sec/im NOTE: Use the :X/Q that applies to the monitor for which the alarm setpoint is being calculated.

I= The total whole body dose factor due to gamma emissions from noble gas radionuclide i (mrem/yearliCi/l 3) from Table 3.1-3.

3. Determine Qt based upon the skin exposure limit.

Qt = ~~(*/Q) Y-,[(i3000+ 1.1iM,)S,](.13 (3.1-3)

Li + 1.1Mi = The total skin dose factor due to emissions from noble gas radionuclide i (mrem/year/gCi/m 3) from Table 3.1-3.

NOTE: The Turbine Building radiation monitors are designed to input the monitor high alarm setpoint in V.Ci/sec or g.Ci/cc. The monitor setpoint in jiCi/sec can be obtained by multiplying the lowest Qt value (obtained from Sections 3.1.1.2 and 3.1.1.3) by the Tm value found in Section 3.1.1.5.b. The gCi/cc setpoint can be obtained by dividing the jaCi/sec setpoint by the design flow rate in cc/sec. The equations for calculating the setpoint in cpm are included for completeness and may be used if desired.

ODCM (BSEP) 3-5 Rev. 301

4. Determine Ct (the maximum acceptable total radioactivity concentration of all noble gas radionuclides in the gaseous effluent, [iCi/sec/cfm).

Ct Q_ (3.1-4) f NOTE: Use the lower of the Qt values obtained in Sections 3.1.1.2 and 3.1.1.3.

f = The maximum acceptable effluent flow rate at the point of release (cfm) based on design flow rates

= 15,500 cfm (Turbine Building Vent- Recirculation Mode)

= 95,000 cfm (Turbine Building Vent - Once Thru Mode)

= 172,800 cfm (Reactor Building Vent)

5. Determine the monitor high alarm setpoint above background:

a. Determine CR (the calculated monitor count rate above background attributed to the noble gas radionuclides, net cpm).

CR Ct (3.1-5)

Em Em The detection efficiency of the monitor for the "mix" of noble gas radionuclides in the gaseous effluent (p.Ci/sec/cfm-cpm) from E&RC files

b. Determine HSP (the monitor high alarm setpoint with background, cpm).

HSP = TmCR + Bkg (3.1-6)

Tm = Fraction of the radioactivity from the site that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded during simultaneous releases from several pathways. Typical values for Tm are shown below.

= 0.10 for the Unit 1 Turbine Building Vent Gas Monitor

= 0.10 for the Unit 2 Turbine Building Vent Gas Monitor

= 0.20 for the Unit 1 Reactor Building Vent Gas Monitor

= 0.20 for the Unit 2 Reactor Building Vent Gas Monitor NOTE: Tm is defined such that Z Tm <1.

I ODCM (BSEP) 3-6 Rev. 30 1

Bkg = The background count rate (cpm) due to internal contamination and the radiation levels in the area in which the monitor is installed when the detector sample chamber is filled with uncontaminated air

c. The monitor high alarm setpoint including background (cpm) shall be set at or below the HSP value determined above.

3.1.2 Setpoint Based on Conservative Radionuclide Mix (Long-Term Elevated Release The following method applies to gaseous releases via the stack when determining the high-high alarm setpoint for the Stack Monitor during continuous release via the stack.

1. Determine the "mix" (noble gas radionuclide composition) of the gaseous effluent (the "mix" can be determined from actual data or by using GALE code results of Table 3.1-2):*

a. Determine the gaseous source terms that are representative of the "mix" of the gaseous effluent. Gaseous source terms are the noble gases radionuclide activity concentrations in the effluent.

Gaseous source teams can be obtained from:

- Table 3.1-2; Stack Release

- Actual Release Data

b. Determine Si (the fraction of the total radioactivity in the gaseous effluent comprised by noble gas radionuclide i) for each individual noble gas radionuclide in the gaseous effluent.

Si = Ai (3.1-7)

Ii Ai Ai = The radioactivity of noble gas radionuclide i in gaseous effluent from Table 3.1-2, Stack Release, or from analysis of gaseous effluent.

2. Determine Qt (the maximum acceptable total release rate of all noble gas radionuclides in the gaseous effluent, jiCi/sec) based upon the whole body exposure limit.

Ifactual plant data is used, the dose constants need to be confirmed.

ODCM (BSEP) 3-7 Rev. 30

Q =

- 500 (3.1-8)

VI = The constant for noble gas radionuclide i accounting for the gamma radiation from the elevated finite plume (mrem/year/jiCi/sec) from Table 3.1-3

3. Determine Qt based upon the skin exposure limit.

3000 Qt 300 (3.1-9)

Q_[(L, (x/Q)s + 1.1 B)S, Lj(X, Q+ 1.1 B, The total skin dose constant for long term releases (greater than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year) due to emissions from noble gas radionuclide i (mrem/year/jlCi/sec) from Table 3.1-3).

NOTE: The stack radiation monitor is designed to input the monitor high-high alarm setpoint in ýiCi/sec or p.Ci/cc. The monitor setpoint in jiCi/sec can be obtained by multiplying the lowest Qt value (obtained from Sections 3.1.2.2 and 3.1.2.3 by the Tm value found in Section 3.1.2.5.b. The pCi/cc setpoint can be obtained by dividing the VtCi/sec setpoint by the design flow rate in cc/sec. The equations for calculating the setpoint in cps are included for completeness and may be used if desired.

4. Determine Ct (the total maximum acceptable radioactivity concentration of noble gas radionuclides in the gaseous effluent, ACi/sec/cfm).

Ct = Q (3.1-10) f NOTE: Use the lowest of the Qt values obtained in Sections 3.1.2.2 and 3.1.2.3.

f = The maximum acceptable effluent flow rate at the point of release (cfm) based on design flow rates 86,000 cfm (stack)

ODCM (BSEP) 3-8 Rev. 30 1

5. Determine the monitor high-high alarm setpoint above background:

a. Determine the CR (the calculated monitor count rate above background attributed to the noble gas radionuclides, net cpm).

CR C- (3.1-11)

Em Em The detection efficiency of the monitor for the "mix" of noble gas radionuclides in the gaseous effluent (p.Ci/sec/cfmocpm) from E&RC files

b. Determine HHSP (the monitor high-high alarm setpoint with background, cpm).

HHSP = TmCR + Bkg (3.1-12)

Tm = Fraction of the radioactivity from the site that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded during simultaneous releases from several pathways

= 0.40 for the Stack Monitor Bkg = The background count rate (cpm) due to internal contamination and the radiation levels in the area in which the monitor is installed when the detector sample chamber is filled with uncontaminated air

c. The monitor high-high alarm setpoint including background (cpm) shall be set at or below the HHSP value determined above.

ODCM (BSEP) 3-9 Rev. 25

3.1.3 Condenser Air Eiector Monitor Alarm SetDoint This procedure determines the alarm setpoint for the Condenser Air Ejector Monitor that will provide reasonable assurance that the total body exposure to an individual at the exclusion area boundary will not exceed a small fraction of the limits of 10CFR100 in the event of an inadvertent release via the condenser air ejector.

1. The following method applies to gaseous releases via the Units 1 and 2 condenser air ejectors when determining the maximum allowable alarm setpoint for the Condenser Off-gas Radiation Monitors, Reference Table 3.1-1.

a. Determine Q, the allowable release rate (ýLCi/sec) at the air ejector for the noble gas radionuclides.

Technical Specification 3.7.5 limits the gross radioactivity rate of noble gases measured at the main condenser air ejector to less than or equal to 243,600 giCi/sec (after 30 minutes' decay). Assume that the noble gas concentrations at the air ejector (t = 0) are representative of the GALE code. Since the holdup time between the air ejector and the stack (down the 30-minute holdup line) can vary due to operational conditions, the mix of the noble gases at the stack should be determined based on the actual decay time not to exceed 30 minutes. This mix can then be applied to the 243,600 jiCi/sec limit and then back-calculated to determine the allowable release rate at the air ejector, Q. As an example, assume that the holdup time is 30 minutes. The mix of the noble gases after 30 minutes' decay (t = 30 minutes) can be determined by the following table.

ODCM (BSEP) 3-10 Rev. 30 1

TABLE 3.1-1 GALE CODE 30 MINUTE AIR EJECTOR TECHNICAL SPECIFICATION Decayed Release Fraction (for 3400 MWt) (for 2923 MWt)

Kr-83m 1.1E-3 9.46E-4 1.52E+3 8.3E-1 1.26E+3 2.85E-2 Kr-85m 1.9E-3 1.63E-3 2.63E+3 9.2E-1 2.43E+3 5.50E-2 Kr-85 6.OE-6 5.16E-6 8.31E+0 1.OE+0 8.31E+0 1.88E-4 Kr-87 6.6E-3 5.67E-3 9.14E+3 7.6E-1 6.96E+3 1.57E-1 Kr-88 6.6E-3 5.67E-3 9.14E+3 8.8E-1 8.08E+3 1.82E-1 Kr-89 4.1E-2 3.52E-2 5.68E+4 1.4E-3 7.89E+1 1.78E-3 Kr-90 9.OE-2 7.74E-2 1.25E+5 1.7E-17 2.11E-12 4.76E-17 Xe-131m 4.7E-6 4.04E-6 6.51E+0 1.OE+0 6.50E+0 1.47E-4 Xe-133m 9.0E-5 7.74E-5 1.25E+2 9.9E-1 1.24E+2 2.80E-3 Xe-133 2.6E-3 2.24E-3 3.60E+3 1.OE+0 3.59E+3 8.11E-2 Xe-135m 8.4E-3 7.22E-3 1.16E+4 2.6E-1 2.99E+3 6.75E-2 Xe-135 7.2E-3 6.19E-3 9.97E+3 9.6E-1 9.60E+3 2.17E-1 I Xe-1 37 4.7E-2 4.04E-2 6.54E+4 4.4E-3 2.90E+2 6.54E-3 Xe-138 2.8E-2 2.41E-2 3.88E+4 2.3E-1 8.87E+3 2.01E-1 TOTAL 4.43E+4 1.OOE+0 Applying this mix to 243,600 jICi/sec (after 30 minutes' delay) and back calculating to t = 0 will yield the allowable gCi/sec per noble gases at the air ejectors. The Gale Code numbers were obtained from NUREG-0016 April 1976 and were scaled in accordance with NUREG-0133 for 2923 MWt.

I

Steam Flow = (12.782 E6 lbs/hr)( 0.1260 gm/secJ = 1.61E + 6 gm/sec IBE)31 e.3 ODCM~~lb/h ODCM (BSEP) 3-11 Rev. 37

TABLE 3.1-1 (Continued)

GALE CODE 30 MINUTE AIR EJECTOR TECHNICAL SPECIFICATION Release Rate Limits Nuclide Fraction of Mix Tech Spec ext Tech Spec t = 30 min (jiCi/sec) t = 30 min (jiCi/sec) t = 30 min t=0 Kr-83m 2.85E-2 6.95E+3 8.3E-1 8.38E+3 Kr-85m 5.50E-2 1.34E+4 9.2E-1 1.45E+4 Kr-85 1.88E-4 4.57E+1 1.OE+0 4.57E+1 Kr-87 1.57E-1 3.83E+4 7.6E-1 5.03E+4 Kr-88 1.82E-1 4.44E+4 8.8E-1 5.03E+4 Kr-89 1.78E-3 4.34E+2 1.4E-3 3.12E+5 Kr-90 4.76E-17 1.16E-11 1.7E-17 6.85E+5 Xe-131m 1.47E-4 3.58E+1 1.OE+0 3.58E+1 Xe-133m 2.80E-3 6.81E+2 9.9E-1 6.85E+2 Xe-133 8.11E-2 1.97E+4 1.OE+0 1.98E+4 Xe-135m 6.75E-2 1.64E+4 2.6E-1 6.40E+4 Xe-135 2.17E-1 5.28E+4 9.6E-1 5.48E+4 Xe-137 6.54E-3 1.59E+3 4.4E-3 3.58E+5 Xe-138 2.OOE-1 4.88E+4 2.3E-1 2.13E+5 TOTALS 1.OOE+0 2.44E+5 1.83E+6 Therefore:

Q 1.83E+6 jLCi/sec (for 30 minutes' holdup)

b. Determine Cm (the total radioactivity concentration of noble gases) in the condenser air ejector gas (piCi/sec/cfm).

Cm = Q/f (3.1-13)

Q = The allowable release rate (giCi/sec) at the air ejector for noble gases f = The main condenser air inleakage rate plus the radiolytic gas flow rate (cfm)

ODCM (BSEP) 3-12 Rev. 30 1

c. Determine the monitor high-high alarm setpoint above background.

(1) Determine MR (the calculated monitor response attributed to the noble gas radionuclides, mR/hr).

MR = Cm (3.1-14)

Em Em = The detection efficiency of the monitor for the "mix" of noble gas radionuclides in the gaseous stream [([tCi/sec)/(mR/hr.cfm)] from E&RC files (2) The monitor high-high alarm setpoint (mR/hr) should be set at or below the MR value determined above.

3.1.4 Condenser Off-Gas Treatment System (AOG) Monitor Alarm Setpoint Determination This method determines the monitor alarm setpoint that includes sufficient noble gas activity to cause an alarm at the stack effluent noble gas monitor.

1. Determine Qt (the maximum acceptable total release rate of all noble gas radionuclides in the gaseous effluent, jtCi/sec) based upon the whole body exposure (see Equation 3.1-8) and skin exposure (see Equation 3.1-9).

NOTE: Use the lowest of the Qt values obtained.

2. Determine Qs (the site adjusted maximum release rate, j.Ci/sec, for effluent releases via the stack).

Qs = Qt x Tm (3.1-15)

Tm = Fraction of radioactivity from the site that may be released via the stack to ensure that the site boundary limit is not exceeded during simultaneous releases from several pathways. The typical value used for Tm is shown below

= 0.4 for the stack monitor ODCM (BSEP) 3-13 Rev. 30 1

3. Determine HSP (high alarm setpoint in giCi/cc).

HSP = Qs - f (3.1-16) f = Maximum design flow rate of the AOG System

= 70,800 cc/sec (150 cfm)

4. The monitor high alarm setpoint shall be set at or below the HSP value determined above.

ODCM (BSEP) 3-14 Rev. 25

TABLE 3.1-2 GASEOUS SOURCE TERMS **

(Ci/year/unit)

Turbine Bldg Vent Reactor Bldg Vent Stack Radionuclide Ai (Ci/yr) Si Ai (Ci/yr) Si Ai (Ci/yr) Si Kr-83m * * - 3.7E+4 2.84E-2 Kr-85m 6.8E+1 1.95E-2 6.OEO 1.72E-2 7.2E+4 5.46E-2 Kr-85 * * - 2.4E+2 1.86E-4 Kr-87 1.9E+2 5.45E-2 6.OEO 1.72E-2 2.05E+5 1.56E-1 Kr-88 2.3E+2 6.59E-2 6.OEO 1.72E-2 2.4E+5 1.82E-1 Kr-89 * * - 3.5E+3 2.64E-3 Xe-1 31m * * - 1.9E+2 1.46E-4 Xe-133m * * - 3.6E+3 2.78E-3 Xe-133 2.8E+2 8.03E-2 1.32E+2 3.78E-1 1.1E+5 8.24E-2 Xe-135m 6.5E+2 1.86E-1 9.2E+1 2.64E-1 8.8E+4 6.72E-2 Xe-135 6.3E+2 1.81E-1 6.8E+1 1.95E-1 2.8E+5 2.16E-1 Xe-137 * * - 1.1E+4 8.09E-3 Xe-138 1.44E+3 4.13E-1 1.4E+1 4.01E-2 2.6E+5 2.OOE-1 Ar-41

2.5E+1 7.16E-2

TOTAL 3.49E+3 3.49E+2 1.31E+6

< 1.0E+1

- Source terms are based upon GALE code and not actual releases.

ODCM (BSEP) 3-15 Rev. 30 1

TABLE 3.1-3 I

DOSE FACTORS AND CONSTANTS Radio Total Whole Body Total Skin Total Body Dose Total Skin Dose Nuclide Dose Factor Dose Factor Constant For Constant for (Ki) (Li + 1.1 Mj) Long-Term Long-Term (mrem/yrlj.Ci/m 3) (mrem/yr/jiCi/m 3) Releases Releases (Vi) (L1(x/Q)s + 1.1 Bi)

(mrem/yrlgCi/sec) (mrem/yr/l*Ci/sec)

Kr-83m 7.56E-2 2.12E+1 2.70E-09 8.21E-07 Kr-85m 1.17E+3 2.81E+3 1.14E-04 2.33E-04 Kr-85 1.61E+1 1.36E+3 1.69E-06 4.57E-05 Kr-87 5.92E+3 1.65E+4 5.12E-04 1.16E-03 Kr-88 1.47E+4 1.91 E+4 1.35E-03 2.30E-03 Kr-89 1.66E+4 2.91 E+4 7.59E-04 1.58E-03 Xe-131m 9.15E+1 6.48E+2 2.78E-05 6.41E-05 Xe-133m 2.51E+2 1.35E+3 2.12E-05 7.04E-05 Xe-1 33 2.94E+2 6.94E+2 2.22E-05 4.85E-05 Xe-135m 3.12E+3 4.41E+3 2.62E-04 4.59E-04 Xe-135 1.81E+3 3.97E+3 1.82E-04 3.61E-04 Xe-137 1.42E+3 1.39E+4 6.42E-05 4.97E-04 Xe-138 8.83E+3 1.43E+4 8.09E-04 1.46E-03 Ar-41 8.84E+3 1.29E+4 9.71 E-04 1.69E-03 ODCM (BSEP) 3-16 Rev. 30 1

3.2 COMPLIANCE WITH ODCM SPECIFICATION 7.3.7 (GASEOUS) 3.2.1 Noble Gases The gaseous effluent monitors' setpoints are utilized to show compliance with ODCM Specification (ODCMS) 7.3.7 for noble gases. However, because they are based upon a conservative mix of radionuclides, the possibility exists that the setpoints could be exceeded and yet ODCMS 7.3.7 limits may not be exceeded. Therefore, the following methodology has been provided in the event that ifthe alarm/trip setpoints are exceeded, a determination may be made as to whether the actual releases have exceeded ODCMS 7.3.7.

The dose rate in unrestricted areas resulting from noble gas effluents is limited to 500 mrem/year to the total body and 3000 mrem/year to the skin.

Based upon NUREG 0133, the following are used to show compliance with ODCMS 7.3.7.

vi Qi, + Ki (X/Q), Qi,

[Vi 1 _*500 mrem/yr (3.2-1) i { [Li~X/QX +1.1BQ] + (L +1.IM)(T/Q) Q }_*3000 mrem/yr (3.2-2) where:

K

= The total body dose factor due to gamma3 emissions for noble gas radionuclide i, mrem/year per jiCi/m Li = The skin dose factor due 3 to beta emissions for noble gas radionuclide i, mrem/year per ýiCi/m M* = The air dose factor due 3 to gamma emissions for noble gas radionuclide i, mrad/year per ViCi/m VI = The constant for each identified noble gas radionuclide i accounting for the gamma radiation from the elevated finite plume mrem/year per jLCi/sec Bi = The constant for long-term releases (greater than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year) for each identified noble gas radionuclide i accounting for the gamma radiation from the elevated finite plume in mrad/year per jiCi/sec ODCM (BSEP) 3-17 Rev. 30 1

1.1 = The ratio of the tissue to air absorption coefficients over the energy range of the photon of interest, mrem/mrad Q =s The release rate of noble gas radionuclide i in gaseous effluents from free-standing stack, jiCi/sec Qiý The release rate of noble gas radionuclide i in gaseous effluents from all vent releases, 1iCi/sec At the Brunswick Steam Electric Plant (BSEP), gaseous releases may occur from:

1. The Turbine Building vent*

2. The Reactor Building vent

3. The Stack Releases from the Turbine Building are ground level. The sources of these releases are steam leakage through valve stems, pump seals, and flanged connections. Releases from the Reactor Building are considered mixed mode in nature, and the source is also leakage through valve stems, pump seals, and flanged connections. Releases from the stack are considered elevated. Their sources are the main condenser's steam jet air ejectors, Radwaste Building and AOG Building ventilation system exhausts, mechanical vacuum pump exhausts during startup, and gland seal off-gases.

Noble gas releases may occur from all three points. To show compliance with ODCMS 7.3.7, Expressions 3.2-1 and 3.2-2 are now in terms of the actual release points for BSEP.

For the total body dose rate:

Vi Q, + Zi K,[(TJQ)r Qx, + (T/Q), Q1 ,, 1*500 mrem/yr YQ, (3.2-3)

ODCM (BSEP) 3-18 Rev. 37

For the skin dose rate:

E. [Li (x/Q). + 1.1B1]Qi + X,[Li + 1. iM,] [(X/Q),t Q,, + x./Q Qj. ]-* 3000 mrem/yr (3.2-4)

Where:

Release rate of radionuclide i from the stack, .Ci/sec Release rate of radionuclide i from the two Reactor Buildings, ViCi/sec Release rate of radionuclide i from the two Turbine Buildings, giCi/sec Annual average relative concentration for releases from the stack, sec/ m3 (X/Q)rb Annual average relative concentration for releases from the Reactor 3

Buildings, sec/m (x/Q). Annual average relative concentration for releases from the Turbine 3

Buildings, sec/ m All other terms remain the same as those defined previously.

The determination of controlling location for implementation of ODCMS 7.3.7 for noble gases is a function of the radionuclide mix, the isotopic release rate, and the meteorology.

The incorporation of these variables into Expressions 3.2-3 and 3.2-4 result in the following expressions for the controlling locations for the BSEP. This location is 0.7 miles, the ENE site boundary.

ODCM (BSEP) 3-19 Rev. 37

For the total body:

-_ZKi (1.9 +6.0 x 10-6 Qijb ) *500 mrem/yr (3.2-5) 1Vi1Qi. + X 10-6 Qi,-#

For the skin:

(3.2-6)

" i (3.2 x 10-8 Li+ 1.1Bi)Qi +

SI(Li +1.1Mi (1.9 x 10-6 Qi,, + 6.0 x 10- 6 Qi, 1 3000 mrem/yr The radionuclide mix was based upon source terms calculated using the NRC GALE code. They are presented in Table 3.2-1 as a function of release point. It should be noted, however, that the releases in Table 3.2-1 do not reflect the actual BSEP release data to date. The releases to date have been substantially less. This table was used as a calculational tool to determine the controlling location.

The X/Q values utilized in the equations for implementation of 10CFR20 are based upon the maximum long-term annual average (X/Q) in the unrestricted area. Table 3.2-2 presents the distances from the Reactor and Turbine Buildings to the nearest unrestricted area for each of the 16 sectors as well as to the nearest residence, vegetable garden, cow, goat, and beef animal. Table 3.2-3 presents the distances and directions from the stack to the same site boundaries of Table 3.2-2. Note that only distance has changed in relation to Table 3.2-2.

Long-term annual (X/Q) values for the stack, Reactor Building, and Turbine Building release points from BSEP to the special locations in Table 3.2-2 are presented in Appendix A. A description of the derivation is also provided in this appendix. X/Q values at the limiting site boundary for releases from the Turbine Building, Reactor Building, and stack were obtained from Tables A-i, A-7, and A-1 3, respectively, of the appendix.

To determine the controlling location for implementation of 10CFR20, the two or three highest site boundary x/Q values for each release point were utilized in conjunction with the radionuclide mix and release rate for each release point. Since mixed mode and elevated releases occur from BSEP, their maximum X/Q value may not decrease with distance; i.e., the site boundary may not have the highest X/Q values.

ODCM (BSEP) 3-20 Rev. 30 1

Therefore, long-term annual average X/Q values were calculated at the midpoint of the 10 standard distances as given in Table A-4 of Appendix A.

The highest two or three x/Q values for each release point at a distance greater than the site boundary were used in conjunction with the radionuclide mix to determine the controlling location. A particular combination of release point mix and meteorology dominates in the determination of the controlling location. For BSEP, it is the stack, and the dominant factor in determining a control location becomes the Vi values.

The controlling location is at the ENE at the site boundary due to its higher Vi values.

Values for Ki, Li, and Mi, which were used in the determination of the controlling locations and which are to be used by BSEP in Expressions 3.2-5 and 3.2-6 to show compliance with ODCMS 7.3.7, are presented in Table 3.2-4. These values originate from NUREG 0472, Revision 0, and were taken from Table B-1 of the NRC Regulatory Guide 1.109, Revision 1.

The values have been multiplied by 106 to convert picocuries 1 to microcuries 1 for use in Expressions 3.2-5 and 3.2-6.

Values for Vi and Bi for the finite plume model can be expressed as shown in Equations 3.2-7 and 3.2-8. They were calculated at the site boundary of each of the 16 sectors using the NRC code RABFIN. Values for Vi and Bi for each of the 16 sectors are presented in Appendix B.

Bi j Ek f ALA El (3.2-7) rd Ill I The results of numerical integration over the plume spatial distribution of the airborne activity as defined by the meteorological condition of wind speed (H) and atmospheric stability class "K"for a particular wind direction K A numerical constant representing unit conversions 260 mrad (radians)(m 3)(transformation) x 16 sectors X sec(Mev)(Ci) 27c radians 10 Ci 3.15x107 sec PCi yr 2.1 x 104 mrad (M3) (transformation) / year (Mev) (pLCi)

ODCM (BSEP) 3-21 Rev. 30 1

rd = The distance from the release point to the receptor location, meters

= The mean wind speed assigned to the jth wind speed class, meters/sec f = The joint frequency of occurrence of the jth wind speed class and the kth stability class (dimensionless)

Al = The number of photons of energy corresponding to the Ith energy group emitted per transformation of the ith radionuclide, number/transformation E = The energy assigned to the Ith energy group, MeV la = The energy absorption coefficient in air for photon energy Ei, meters 1 The Vi factor is computed with conversion from air dose to tissue depth dose, thus; Vi = 1.1K/rd yy, y, fik Ai la Ell e-P TT. (3.2-8)

Where:

ILT = The tissue energy absorption coefficient for photons of energy El, cm 2/gm Td = The tissue density thickness taken to represent the total body dose (5 gm/cm 2) 1.1 = The ratio of the tissue to air absorption coefficients over the energy range of photons of interest, mrem/mrad ODCM (BSEP) 3-22 Rev. 25

3.2.2 1-131, 1-133, Particulates, and Tritium*

The dose rate in unrestricted areas resulting from the release of radioiodines and particulates with half-lives greater than 8 days is limited to 1500 mrem/year to any organ. Based upon NUREG 0133, the following is used to show compliance with ODCMS 7.3.7.

[~IQs~,+(~I~rQ,6

~,P + z/),b (011b + +! *1500 rnrem/yr (3.2-9)

Where:

Pi Dose parameter for radioiodines and particulates with half-lives greater than 8 days based upon the organ 3 and the age group (child) at the site boundary, mrem/year per jiCi/m

= .The release rate of radionuclide i in gaseous effluents from free standing stack, jiCi/sec Qi = Release of radionuclide i from the two Reactor Buildings, jiCi/sec

= Release of radionuclide i from the two Turbine Buildings, jLCi/sec Q'DC = Release of radionuclide ifrom the Hot Shop (Decon) Facility, LCi/sec

= Release of radionuclide i from the Radioactive Materials Container and Storage Building (RMCSB), [tCi/sec Q,,. = Release of radionuclide ifrom the Low Level Warehouse (LLW), lICi/sec (Z/Q)rb = Annual average relative 3

concentrations for releases from the Reactor Buildings, sec/im (X/Q),b = Annual average relative concentrations for releases from the Turbine Buildings, and3 other ground level releases such as Decon, RMCSB and LLW, sec/m 3

X/Q)=, Annual average relative concentrations for releases from the stack, sec/m

For ODCM calculations performed to comply with ODCM TRs 7.3.7.2 and 7.3.9.1, the 1-133 values used are determined by actual analysis.

ODCM (BSEP) 3-23 Rev. 37

Radioiodines, particulates, and tritium are primarily released from the Stack, Reactor Buildings, and Turbine Buildings at BSEP. Radioiodines and particulates may also be released from other sources such as the Hot Shop (Decon) Facility, the Radioactive Materials Container and Storage Building (RMCSB), and the Low Level Warehouse (LLW). Effluent doses from Decon, RMCSB, LLW, and any building exfiltration are quantified using ground level meteorology.

To show compliance with ODCMS 7.3.7, Expression 3.2-9 is evaluated at the limiting site boundary. The limiting site boundary location is 0.7 miles NE.

In the determination of the controlling site boundary location, the highest two or three site boundary XIQ values for each release point were utilized in conjunction with the radionuclide mix and the release rate for each release point. At BSEP, the release rate which dominates comes from the stack.

The higher value for x/Q for the NE sector at the site boundary make it the dominant meteorological sector and the control location.

Values for Pi were calculated for a child for various radionuclides for the inhalation pathway using the methodology of NUREG 0133. The Pi values are presented in Table 3.2-5. Appendix C presents the methodology which was utilized in calculating Pi values.

Annual average x/Q values at the standard distances for the Stack, Reactor Building, Turbine Building and other effluent release points can be obtained from Appendix A. A description of the derivation of the x/Q values is provided in Appendix A.

ODCM (BSEP) 3-24 Rev. 37 1

TABLE 3.2-1 RELEASES FROM BRUNSWICK STEAM ELECTRIC PLANT *

(Ci/yr per unit)

Isotope Turbine Building Reactor Building Stack (Ground Level) (Mixed Mode) (Elevated)

Kr-83m O.OE+O O.OE+O 3.7E+4 Kr-85m 6.8E+1 6.OE+O 7.2E+4 Kr-85 O.OE+O O.OE+O 2.4E+2 Kr-87 1.9E+2 6.OE+O 2.05E+5 Kr-88 2.3E+2 6.OE+0 2.4E+5 Kr-89 O.OE+O O.OE+O 3.5E+3 Xe-131m O.OE+O O.OE+O 1.9E+2 Xe-133m O.OE+O O.OE+O 3.6E+3 Xe-133 2.8E+2 1.3E+2 1.1E+5 Xe-135m 6.5E+2 9.2E+1 8.8E+4 Xe-135 6.3E+2 6.8E+1 2.8E+5 Xe-137 0.0E+0 O.OE+O 1.1E+4 Xe-138 1.4E+3 1.4E+1 2.6E+5 Ar-41 O.OE+O 2.5E+1 O.OE+O 1-131 1.9E-2 3.4E-1 5.1E+O 1-133 7.6E-2 1.4E+O 2.0E+1 Cr-51 1.3E-4 6.OE-4 9.OE-3 Mn-54 6.OE-6 6.OE-3 3.6E-2 Fe-59 5.OE-6 8.OE-4 1.5E-2 Co-58 6.OE-6 1.2E-3 4.5E-3 Co-60 2.OE-5 2.OE-2 9.OE-2 Zn-65 2.OE-6 4.OE-3 1.OE-3 Sr-89 6.OE-5 1.8E-4 5.OE-4 Sr-90 2.OE-7 1.OE-5 3.OE-4 Zr-95 1.OE-6 8.OE-4 5.OE-5 Sb-124 3.OE-6 4.OE-4 5.OE-5 Cs-134 3.OE-6 8.OE-3 4.5E-3 Cs-136 5.OE-7 6.OE-4 4.5E-4 Cs-137 6.OE-6 1.1E-2 9.OE-3 Ba-140 1.1E-4 8.OE-4 1.OE-4 Ce-141 6.OE-6 2.OE-4 2.6E-3 C-14 O.OE+O O.OE+O 9.5E+O H-3 O.OE+O 3.6E+1 O.OE+O

Calculations based upon GALE code and not actual releases.

ODCM (BSEP) 3-25 Rev. 37 1

TABLE 3.2-2 DISTANCE TO CONTROLLING LOCATIONS AS MEASURED FROM THE BRUNSWICK PLANT CENTER (Mi)

Sector Site Milk Cow Milk Goat Meat Nearest Nearest i Boundary ________ Animal: Resident Garden NNE 0.7 - - 0.8 0.9 NE 0.7 4.75* - -

ENE 0.7 - -

E 0.7 - -

ESE 0.7 - - 1.4 SE 0.7 - -

SSE 0.7 - - 2.1 S 0.8 - - 1.1 2.2 SSW 0.8 - - 1.2 1.6 SW 0.7 - - 1.1 1.4 WSW 0.7 - - 1.2 1.2 W 0.7 - - 0.9 0.9 WNW 0.6 - - 0.9 1.0 NW 0.6 - - 0.9 1.0 NNW 0.6 - - 0.8 0.9 N 0.7 - 0.7 1.0

A "hypothetical" cow milk pathway is located at this point in accordance with 5.3.1 of NUREG 0133.

ODCM (BSEP) 3-26 Rev. 37 1

TABLE 3.2-3 DISTANCE TO SITE BOUNDARIES BASED UPON BRUNSWICK PLANT CENTER AND DIRECTIONS FROM THE STACK Based on Center of Brunswick Plant From Stack to Site Boundaries of Table 3.2-2 Direction Site Boundary: Direction Distance (Mi)

...Distance (Mi)

NNE 0.7 NNE 0.7 NE 0.7 NE 0.7 ENE 0.7 ENE 0.7 E 0.7 E 0.6 ESE 0.7 ESE 0.6 SE 0.7 SE 0.6 SSE 0.7 SSE 0.6 S 0.8 S 0.6 SSW 0.8 SSW 0.7 SW 0.7 SW 0.7 WSW 0.7 WSW 0.7 W 0.7 W 0.8 WNW 0.6 WNW 0.7 NW 0.6 NW 0.7 NNW 0.6 NNW 0.7 N 0.7 N 0.8 ODCM (BSEP) 3-27 Rev. 37 1

TABLE 3.2-4 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS*

Radionuclide Total Body Skin Gamma Air Beta Air Dose Factor Dose Factor Dose Factor Dose Factor K. Li Mi Ni (mrem/yr per (mrem/yr per (mrad/yr per (mrad/yr per

ýLCi/m3) gCi/m3) gCi/m3) g.Ci/m3)

Kr-83m 7.56E-02** --- 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61 E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01 E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03

The listed dose factors are for radionuclides that may be detected in gaseous effluents.

- 7.56E-02 = 7.56 x 10-2 ODCM (BSEP) 3-28 Rev. 37 I

TABLE 3.2-5 Pi VALUES FOR A CHILD FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Inhalation AGE GROUP = Child Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 1.12E+03 1.12E+03 0.OOE+00 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 P-32 9.86E+04 4.21E+04 2.60E+06 1.14E+05 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 CR-51 1.54E+02 1.08E+03 0.OOE+00 0.OOE+00 2.43E+01 8.53E+01 1.70E+04 0.OOE+00 MN-54 9.50E+03 2.29E+04 O.OOE+00 4.29E+04 1.OOE+04 O.OOE+00 1.57E+06 0.OOE+00 FE-59 1.67E+04 7.06E+04 2.07E+04 3.34E+04 O.OOE+00 0.OOE+00 1.27E+06 O.OOE+00 CO-58 3.16E+03 3.43E+04 0.OOE+00 1.77E+03 0.OOE+00 O.OOE+00 1.1OE+06 O.OOE+00 CO-60 2.26E+04 9.61E+04 0.OOE+00 1.31E+04 O.OOE+00 0.OOE+00 7.06E+06 0.OOE+00 ZN-65 7.02E+04 1.63E+04 4.25E+04 1.13E+05 7.13E+04 0.OOE+00 9.94E+05 0.OOE+00 RB-86 1.14E+05 7.98E+03 0.OOE+00 1.98E+05 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 SR-89 1.72E+04 1.67E+05 5.99E+05 0.OOE+00 O.OOE+00 0.OOE+00 2.15E+06 O.OOE+00 SR-90 6.43E+06 3.43E+05 1.01 E+08 0.OOE+00 0.OOE+00 O.OOE+00 1.47E+07 0.OOE+00 Y-91 2.43E+04 1.84E+05 9.13E+05 0.OOE+00 0.OOE+00 0.OOE+00 2.62E+06 O.OOE+00 ZR-95 3.69E+04 6.1OE+04 1.90E+05 4.17E+04 5.95E+04 0.OOE+00 2.23E+06 0.OOE+00 NB-95 6.54E+03 3.69E+04 2.35E+04 9.16E+03 8.61E+03 0.OOE+00 6.13E+05 O.OOE+00 RU-103 1.07E+03 4.47E+04 2.79E+03 0.OOE+00 7.02E+03 0.OOE+00 6.61E+05 0.OOE+00 RU-106 1.69E+04 4.29E+05 1.36E+05 0.OOE+00 1.84E+05 0.OOE+00 1.43E+07 0.OOE+00 AG-110M 9.13E+03 1.OOE+05 1.68E+04 1.14E+04 2.12E+04 0.OOE+00 5.47E+06 0.OOE+00 SN-113 9.84E+03 7.45E+03 9.01E+03 2.91E+02 2.03E+02 1.19E+02 3.40E+05 0.OOE+00 TE-127M 3.01E+03 7.13E+04 2.48E+04 8.53E+03 6.35E+04 6.06E+03 1.48E+06 0.OOE+00 TE-129M 3.04E+03 1.81E+05 1.92E+04 6.84E+03 5.02E+04 6.32E+03 1.76E+06 0.OOE+00 1-131 2.72E+04 2.84E+03 4.80E+04 4.80E+04 7.87E+04 1.62E+07 O.OOE+00 0.OOE+00 1-132 1.87E+03 3.20E+03 2.11E+03 4.06E+03 6.24E+03 1.93E+05 O.OOE+00 0.OOE+00 1-133 7.68E+03 5.47E+03 1.66E+04 2.03E+04 3.37E+04 3.84E+06 0.OOE+00 0.OOE+00 1-135 4.14E+03 4.43E+03 4.91E+03 8.72E+03 1.34E+04 7.91E+05 0.OOE+00 0.OOE+00 CS-134 2.24E+05 3.84E+03 6.50E+05 1.01E+06 3.30E+05 0.OOE+00 1.21E+05 0.OOE+00 CS-136 1.16E+05 4.17E+03 6.50E+04 1.71E+05 9.53E+04 0.OOE+00 1.45E+04 0.OOE+00 CS-137 1.28E+05 3.61E+03 9.05E+05 8.24E+05 2.82E+05 0.OOE+00 1.04E+05 0.OOE+00 BA-140 4.32E+03 1.02E+05 7.39E+04 6.47E+01 2.11E+01 0.OOE+00 1.74E+06 0.OOE+00 CE-141 2.89E+03 5.65E+04 3.92E+04 1.95E+04 8.53E+03 0.OOE+00 5.43E+05 0.OOE+00 CE-144 3.61E+05 3.88E+05 6.76E+06 2.11E+06 1.17E+06 0.OOE+00 1.19E+07 O.OOE+00 HF-181 8.50E+03 5.31E+04 8.44E+04 3.28E+02 2.64E+02 2.76E+02 7.95E+05 0.OOE+00 AM-241 4.59E+08 1.75E+05 1.10E+10 6.81E+09 2.82E+09 O.OOE+00 7.47E+08 0.00E+00

Units are mrem/yr per liCi/m 3 for the inhalation pathway.

ODCM (BSEP) 3-29 Rev. 37 I

3.3 COMPLIANCE WITH 10CFR50 (GASEOUS) 3.3.1 Noble Gases

1. Cumulation of Doses Section ll.B.1 of Appendix I of 10CFR50 limits the releases of gaseous effluents from each reactor such that the estimated annual gamma air dose is limited to 10 millirad and the beta air dose is limited to 20 millirad.

Based upon NUREG 0133, the air dose in the unrestricted area due to noble gases released in gaseous effluents can be determined by the following expressions:

During any calendar quarter, for gamma radiation:

(3.3-1) 3.17 X 10-8y, f{M [(X/Q)v, Qj, + (X/q)v, qjý ]+,,+bq,}5 mrad During any calendar quarter, for beta radiation:

3.17 x 10-' XiNi [ (x/Q)v Qai + (X/q), qi, + (x/Q)s Qi, + (X/q)s qi, ]< 10 mrad (3.3-2)

During any calendar year, for gamma radiation:

(3.3-3) 3.17 x 10-8yi {M1 I(X/Q)v Qiv + (x/q)v qi, ]+Bi Qi +biq2' }<10 mrad During any calendar year, for beta radiation:

3.17 x 10-8 y iN ['(X/Q) Qi, + (X/q)* qi1 + (X/Q). Qi, + (X/q)s qi, ]< 20 mrad (3.3-4)

Where:

M = The air dose factor due to gamma emissions 3

for each identified noble gas radionuclide i, mrad/year per ýiCi/m N, = The air dose factor due to beta emissions 3

for each identified noble gas radionuclide i, mrad/year per pCi/m (x/Q)v = The annual average relative concentration for areas at or beyond the unrestricted area3 boundary for long-term vent releases (greater than 500 hrs/year), sec/m ODCM (BSEP) 3-30 Rev. 37 1

(x/q)v = The relative concentration for areas at or beyond the unrestricted area boundary for short-term 3 vent releases (equal to or less than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year), sec/m (X/Q)s = The annual average relative concentration for areas at or beyond the unrestricted area boundary for long-term, 3 free-standing stack releases (greater than 500 hours/year), sec/m (x/q) = The relative concentration for areas at or beyond the unrestricted area boundary for short-term,3 free-standing stack releases (equal to or less than 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months year), sec/m qi = The average release of noble gas radionuclide i in gaseous effluents for short-term stack releases (equal to or less than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year), lICi qi = The average release of noble gas radionuclide i in gaseous effluents for short-term vent releases (equal to or less than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year), jiCi Qi = The average release of noble gas radionuclide i in gaseous effluents for long-term, free-standing stack releases (greater than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year), jICi ai = The average release of noble gas radionuclide i in gaseous effluents for long-term vent releases (greater than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year), l.Ci Bi = The constant for long-term releases (greater than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year) for each identified noble gas radionuclide i accounting for the gamma radiation from the elevated finite plume, mrad/year per gCi/sec bi = The constant for short-term releases (equal to or less than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year) for each identified noble gas radionuclide i accounting for the gamma radiation from the elevated finite plume, mrad/year per jiCi/sec 3.17 x 10-8 = The inverse of the number of seconds in a year For BSEP all releases are considered long-term. The incorporation of the stack, Reactor Building, and Turbine Building release points into Expressions 3.3-1 through 3.3-4 results in the following expressions for two units to show compliance with 10CFR50.

ODCM (BSEP) 3-31 Rev. 37 1

During any calendar quarter or year:

Gamma radiation:

{

3.17 x 10-8 i Mi [ (X/Q)rb (Qi, + Qird2 ) + (X*Q)tb (Qi., + Qij 2) ]+ BiQi, }

_<10 mrad per quarter or 20 mrad per year (3.3-5)

Beta radiation:

3.17 x 1O- 8Z1 Ni [ (X/Q)rb (Qi,,, + Qi,,, ) + (X/Q)tb (Qi11 + Qib2) + (./Q)sQ ]

<_20 mrad per quarter or 40 mrad per year (3.3-6)

Where:

(X/Q)b = Annual average relative concentration for releases from the FReactor 3

Building, sec/m (X/Q)tb = Annual average3 relative concentration for releases from the -Furbine Building, sec/im 3

concentration for releases from the sstack, sec/m (x/Q)S = Annual average relative Qirl,Qi2 = Release of radionuclide i from Reactor Buildings 1 and 2, res pectively, j.Ci QilQi.2 = Release of radionuclide i from Turbine Buildings 1 and 2, res pectively, liCi Qi = Release of radionuclide i from the stack, jiCi At BSEP, the limiting location for noble gases is 0.7 miles ENE.

Substitution of the appropriate X/Q values into Expressions 3.3-5 and 3.3-6 results in the following:

ODCM (BSEP) 3-32 Rev. 37 1

During any calendar quarter or year:

Gamma radiation:

3.17 x10- 8 Y-i JMi [1.9 x10-6 (Qi,,+Qi 1 2)+6.0 x10- 6 (Qi,, + Q.o )J+ BQ i

_ 10 mrad per quarter or 20 mrad per year (3.3-7)

Beta radiation:

3.17 x 10- 8 ZiNi [1.9 x 10- 6 (Q' 11,+Qi'2)+6.0 X 10-6 (Qi ,+Qi2 )+3.2 x10- 8 Qi,]

20 mrad per quarter or 40 mrad per year (3.3-8)

The determination of the controlling locations for implementation of 10CFR50 is a function of parameters such as radionuclide mix, isotopic release, and meteorology.

The incorporation of these parameters into Expressions 3.3-1 through 3.3-4 resulted in the expressions for the controlling locations as presented in Expressions 3.3-7 and 3.3-8. The radionuclide mix was based upon source terms calculated using the NRC GALE Code and is presented in Table 3.2-1 as a function of release point.

The two or three highest site boundary (X/Q) values for each release point were utilized in conjunction with the radionuclide mix and release for each release point to determine the controlling site boundary location. Since mixed mode and elevated releases occur from BSEP and their maximum X/Q values may not decrease with distance (i.e., the site boundary may not have the highest X/Q values); X/Q values were calculated at the midpoint of 10 standard distance intervals out to a distance of 5 miles. The two or three highest X/Q values were considered in conjunction with the radionuclide mix and releases to determine the controlling location.

In the determination of the controlling location, annual average X/Q values are utilized. These values are presented in tables in Appendix A. '/Q values at the limiting site boundary location for releases from the Turbine Buildings, Reactor Buildings, and stack were obtained from Tables A-i, A-7, and A-1 3, respectively, of Appendix A. A description of the derivation of X/Q values is also presented in Appendix A.

ODCM (BSEP) 3-33 Rev. 37 1

A particular combination of release point mix and meteorology dominates in the determination of the controlling location. For BSEP the controlling release point is the stack. The dominate factor in determining a control location becomes the Bi values. The ENE sector at the site boundary is the control location because of its higher Bi values.

Values for Mi and Ni, which were used in the determination of the controlling location and which are to be used by BSEP in Expressions 3.3-7 and 3.3-8 to show compliance with 10CFR50 were presented in Table 3.2-4. These values originate from NUREG 0472, Revision 0, and were taken from Table B-1 of NRC Regulatory Guide 1.109, Revision 1. The values have been multiplied by 106 to convert from picocuries to microcuries.

The following relationship should hold for BSEP to show compliance with ODCM Specification 7.3.8.

For the calendar quarter:

Dy*!_ 10mrad (3.3-9)

Df3 _ 20mrad (3.3-10)

For the calendar year:

Dy*< 20mrad (3.3-11)

DI3 < 40mrad (3.3-12)

Where:

Dy = The air dose from gamma radiation, mrad DP3 = The air dose from beta radiation, mrad The quarterly limits given above represent one-half the annual design objective of Section ll.B.1 of Appendix I of 10CFR50. If any of the limits of Expressions 3.3-9 through 3.3-12 are exceeded, a special report pursuant to Section IV.A of Appendix I of 10CFR50 must be filed with the NRC.

ODCM (BSE P) 3-34 Rev. 37

3.3.2 1-131, 1-133, Particulates, and Tritium*

1. Cumulation of DosesSection II.C of Appendix I of 10CFR50 limits the release of radioiodines and radioactive material in particulate form from each reactor such that estimated dose or dose commitment to an individual in an unrestricted area from all pathways of exposure is not in excess of 15 mrem to any organ.

Based upon NUREG 0133, the dose to an organ of an individual from radioiodines and particulates, with half-lives greater than 8 days in gaseous effluents released to unrestricted areas, can be determined by the following expression:

During any calendar quarter or year:

3.17 x 10-8 Y, Ri (WsQi +wsqi, + WQv, + wvqi) (3.3-13)

< 7.5 mrem per quarter or 15 mrem per calendar year Where:

Q = Release of radionuclide i for long-term, free-standing stack releases (greater than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year), jiCi QiV Release of radionuclide i for long-term vent releases (greater than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year), ýLCi qi = Release of radionuclide i for short-term, free-standing stack releases (equal to or less than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year), jLCi qiv Release of radionuclide i for short-term vent releases (equal to or less than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year), 1iCi W. Dispersion parameter for estimating dose to an individual at the controlling location for long-term, free-standing stack releases (greater than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year)

= sec/m 3 for the inhalation pathway and tritium

= meters 2 for the food and ground plane pathway

For ODCM calculations performed to comply with ODCM TRs 7.3.7.2 and 7.3.9.1, the 1-133 values used are determined by actual analysis.

ODCM (BSEP) 3-35 Rev. 37 1

WV The dispersion parameter for estimating the dose to an individual at the controlling location for long-term vent releases (greater than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year)

= sec/m 3 for the inhalation pathway and tritium

= meters 2 for the food and ground plane pathway W = Dispersion parameter for estimating the dose to an individual at the controlling location for short-term stack releases (equal to or less than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year)

= sec/m 3 for the inhalation pathway and tritium

= meters 2 for the food and ground plane pathway wV = The dispersion parameter for estimating the dose to an individual at the controlling location for short-term vent releases (equal to or less than 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year) sec/m 3 for the inhalation pathway and tritium

= meters-2 for the food and ground plane pathway 3.17 x 108 = The inverse of the number of seconds in a year Ri = The dose factor for each identified radionuclide i of3 the organ of interest, 2

mrem/yr per liCi/sec per m- or mrem/yr per jLCi/m Radioiodines, particulates, and tritium are primarily released from the Stack, Reactor Buildings, and Turbine Buildings at BSEP. Radioiodines and particulates, may also be released from other sources such as the Hot Shop (Decon) Facility, the Radioactive Materials Container and Storage Building (RMCSB), and the Low Level Warehouse (LLW). Effluent doses from Decon, RMCSB, LLW and any building exfiltration are quantified using ground level meteorology. At BSEP all releases are considered long-term in duration. Therefore, incorporating the various release points into Expression 3.3-13 results in the following expression to show compliance with 10CFR50 for a particular organ:

,RM

+Q i,,w) (3.3-14))

3.17 x 1 0- 8T iR i[W r js.+ Wrb (Q , +Q i r,) + W tb (Q i,+Q i., +Q ,. +Q

_ 15.0 mrem per quarter or 30 mrem per year ODCM (BSEP) 3-36 Rev. 37 1

Where:

ws Dispersion parameter for releases from the stack Dispersion parameter for releases from the Reactor Building Wtb Dispersion parameter for releases from the Turbine Building Release of radionuclide i from the stack, liCi 2

Release of radionuclide i from Reactor Buildings 1 and 2, respectively, jiCi Q,b., Qi,b = Release of radionuclide i from Turbine Buildings 1 and 2, respectively, [iCi QR 'Q QiS = Release of radionuclide i from the Hot Shop (Decon) Facility, jtCi

= Release of radionuclide i from the Radioactive Materials Container and Storage Building (RMCSB), .tCi QlLLW

= Release of radionuclide i from the Low Level Warehouse (LLW), jlCi In determining the dose at a particular location, W (as in Section 3.2.2) is a function of the pathway. For the food and ground plane pathway, W is in terms of D/Q. If the inhalation pathway is considered, W is in terms of x/Q.

Incorporation of the various pathways into Expression 3.3-14 results in the following:

3.17 x lO-ZY

{(Rl + RA,, + R,,. + RIB ) [(D/Q),Q, + (D/Q )rb (Q,,6 + Q,1, ) + (D/Q),lb(Q,,,, + Q,. + QDC + QRm* + QILLW )J +

R,, [(z/Q)' QR + (IQ)r)b (Q',I + Q',b ) + (XIQ),b (QRH + QI,,b + QDC + QRM + QLLW )]V

15 mrem (perquarter)or 30 mrem (peryear)

(3.3-15)

Where:

Ri = Dose factor for an organ for radionuclide i for the ground plane exposure pathway, mrem/yr per 1iCi/sec per M-2 RiM = Dose factor for an organ for radionuclide i for either the cow milk or goat milk pathway, mrem/yr per jiCi/sec per m' Riv = Dose factor for an organ for radionuclide i for the vegetable pathway, mrem/yr per jiCi/sec per M-2 Ri = Dose factor for an organ for radionuclide i for the meat pathway. mrem/yr per jiCi/sec per M2 Ri, = Dose factor for an organ for radionuclide i for the inhalation pathway, 3

mrem/yr per giCi/m ODCM (BSEP) 3-37 Rev. 37 1

(D/Q), = Annual average deposition for releases from the Reactor Buildings,m-2 (D/Q),b = Annual average deposition for releases from the Turbine Buildings, and 2

other ground level releases such as Decon, RMCSB, and LLW, m (D/Q)., Annual average deposition for releases from the stack, m-2 As discussed in Section 3.2.2, for tritium the parameter W for the food pathway is based upon ,/Q. The ground plane pathway is not appropriate for tritium. Therefore, the left-hand portion of Expression 3.3-15 may be modified for tritium as:

For tritium:

3.17x 10-8 (RT +RTr +RTrn + RT) (

DT

[XQ), QT, + (X/Q)rb(QT,,, + QT,,, ) + (%/Q)tb (QT,b, + QTOb)]

Where:

DT = Dose resulting from tritium, mrem RT, = Dose factor for an organ for tritium for the milk pathway, mrem/yr per 3

ýiCi/m RTV = Dose factor for an organ for tritium for the vegetable pathway, mrem/yr per 3

giCi/m RTB = Dose factor for an organ for tritium for the beef pathway, mrem/yr per 3

giCi/m RT, Dose factor for an organ for tritium for the inhalation pathway, mrem/yr per 3

giCi/m

= Release of tritium from the stack, giCi QT.. QT,,,,

= Release of tritium from Reactor Buildings 1 and 2, respectively, jICi QT., 'QT,, = Release of tritium from Turbine Buildings 1 and 2, respectively, iLCi ODCM (BSEP) 3-38 Rev. 37 1

To show compliance with 10CFR50, Expression 3.3-15 is evaluated at the controlling pathway location. At BSEP the controlling location is a milk cow 4.75 miles in the NE sector. Expression 3.3-15 becomes:

3.17 x 10-8~i t(RIG + RIM)[2.9 x 10-+°Qis + 7.0 x 1O-1°(Qirb1 + Qirb2) +

7.2 x 10-1 0 (Qitbl + Qitb2 + QiDc + QiRM + QiLLW)] + Ri 1[2.4 X 10- 8 %Q +

1.9 X 10-7(Qirbi + Qirb2) + 3.2 x 10-7(Qitbl + Qitb2 + QiDc + QiRM + QiLLW)]}

<15 mrem/quarter or 30 mrem/year (3.3-17)

For tritium, Equation 3.3-16 reduces to:

D, =3.17x10-8 (RTi +RT,)[2.4x 10-QT, +1.9x10- 7 (QT'I +Q,, )+3.2x10-7 (QT, +QT.ý)]

(3.3-18)

Airborne Tritium Releases from the Stabilization Pond and Stabilization Facility Airborne releases of tritium from the Storm Drain Stabilization Pond (SDSP) and Storm Drain Stabilization Facility (SDSF) by evaporation are routinely calculated and dose rates determined based on the following equation:

QT] (3.2-19)

DT = (RTJ +/-RT.)kX/

Where:

DT = Dose rate from the SDSP or SDSF tritium airborne release, mrem/year 3 RT = Dose parameter for tritium for the inhalation pathway, mrem/year per PCi/m 3

RV = Dose parameter for tritium for the ingestion pathway, mrem/year per pCi/m X/ Q = Annual average relative concentrations for releases from the SDSP or SDSF to the nearest resident.

QT = Release rate of tritium from the SDSP or SDSF, pCi/sec.

Note: The nearest resident from the center of the SDSP is typically to the NW at approximately 0.3 miles. The nearest resident from the center of the SDSF is typically to the NNW at approximately 0.5 miles.

ODCM (BSEP) 3-39 Rev. 37 1

The determination of a controlling location for implementation of 10CFR50 for radioiodines and particulates is a function of:

a. Radionuclide mix and isotopic release

b. Meteorology

c. Exposure pathway

d. Receptor's age The incorporation of these parameters into Expression 3.3-14 results in the respective equations at the controlling location.

In the determination of the controlling location, the radionuclide mix of radioiodines and particulates was based upon the source terms calculated using the GALE code. This mix was presented in Table 3.2-1 as a function of release point.

In the determination of the controlling location, all of the exposure pathways, as presented in Table 3.2-2, were evaluated. These include cow milk, goat milk, beef and vegetable ingestion, and inhalation ground plane exposure. An infant was assumed to be present at all milk pathway locations. A child was assumed to be present at all vegetable garden and beef animal locations. The ground plane and inhalation pathways were considered present everywhere a residence was present.

For the determination of the controlling location, the highest D/Q values for each release point and release mode for the vegetable garden, cow milk, and goat milk pathways were selected. At BSEP, no cow milk or goat milk pathways are present. In accordance with NUREG 0133, dose to a "hypothetical" cow milk pathway located 4.75 miles NE was evaluated against existing vegetable garden pathways. The thyroid dose was calculated at each of these locations using the radionuclide mix and releases of Table 3.2-1. Based upon these calculations, it was determined that the controlling receptor pathway is the "hypothetical" cow milk-infant pathway in the NE sector, at 4.75 miles.

ODCM (BSEP) 3-40 Rev. 37 1

Tables 3.3-1 through 3.3-19 present Ri values for the total body, GI tract, bone, liver, kidney, thyroid, and lung organs for the ground plane, inhalation, cow milk, goat milk, and vegetable and meat ingestion pathways for the infant, child, teen, and adult age groups as appropriate to the pathways. These values were calculated using the methodology described in NUREG 0133 using a grazing period of eight months. A discussion of their calculation is presented in Appendix C.

In the determination of the controlling location annual average D/Q and x/Q values are utilized. D/Q values at the limiting real pathway locations for releases from the Turbine Buildings, Reactor Buildings, and the stack were obtained from Tables A-3, A-9, and A-15, respectively, of Appendix A.

X/Q values at the same location for these same release points were obtained from Tables A-i, A-7, and A-1 3 of Appendix A. A description of the derivation of the various X/Q and D/Q values is presented in Appendix A.

Long-term D/Q values for the stack, Reactor Buildings, and Turbine Buildings are provided for the midpoints of the following distances:

0.0-0.5 mi. 0.5-1.0 mi. 1.0-1.5 mi. 1.5-2.0 mi.

2.0-2.5 mi. 2.5-3.0 mi. 3.0-3.5 mi. 3.5-4.0 mi.

14.0-4.5 mi. 4.5-5.0 mi.

These values appear in tables in Appendix A. These tables may be utilized if an additional special location arises which is different from one presented in the special locations of Appendix A.

The following relationships should hold for BSEP to show compliance with BSEP ODCM Specification 7.3.9.

For the calendar quarter:

Dt < 15 mrem (3.3-19)

For the calendar year:

Dr < 30 mrem (3.3-20)

Where:

DT = The dose to any organ - from radioiodines and particulates, mrem ODCM (BSEP) 3-41 Rev. 37 1

The quarterly limits given above represent one-half the annual design objective of Section II.C of Appendix I of 10CFR50. If any of the limits of Expressions 3.3-19 or 3.3-20 are exceeded, a special report pursuant to Section IV.A of Appendix I of 10CFR50 must be filed with the NRC.

2. Projection of Doses Dose projections for this section are required at least once per 31 days in ODCM TR 7.3.11.2.

The doses will be projected using the equation below. Where possible, credit for expected operational evolutions (i.e., outages, etc.) should be taken in the dose projections. This may be accomplished by using the source term data from similar historical operating experiences where practical and adding the dose as additional anticipated dose.

Dpt = x 31 + Dar Where:

Dp = 31 day projected dose by organ r, in mrem; Dr = Current cumulative monthly dose of organ T up to the end of the release under evaluation, in mrem T = time elapsed in month up to the end of the release under evaluation, in days; 31 = number of days dose is projected; and Dar = additional anticipated dose by organ T in mrem.

ODCM (BSEP) 3-42 Rev. 37 1

TABLE 3.3-1 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Ground Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin CR-51 4.66E+06 4.66E+06 4.66E+06 4.66E+06 4.66E+06 4.66E+06 4.66E+06 5.51 E+06 MN-54 1.34E+09 1.34E+09 1.34E+09 1.34E+09 1.34E+09 1.34E+09 1.34E+09 1.57E+09 FE-59 2.75E+08 2.75E+08 2.75E+08 2.75E+08 2.75E+08 2.75E+08 2.75E+08 3.23E+08 CO-58 3.79E+08 3.79E+08 3.79E+08 3.79E+08 3.79E+08 3.79E+08 3.79E+08 4.44E+09 CO-60 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.52E+10 ZN-65 7.49E+08 7.49E+08 7.49E+08 7.49E+08 7.49E+08 7.49E+08 7.49E+08 8.61 E+08 RB-86 8.99E+06 8.99E+06 8.99E+06 8.99E+06 8.99E+06 8.99E+06 8.99E+06 1.03E+07 SR-89 2.23E+04 2.23E+04 2.23E+04 2.23E+04 2.23E+04 2.23E+04 2.23E+04 2.58E+04 Y-91 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.22E+06 ZR-95 2.49E+08 2.49E+08 2.49E+08 2.49E+08 2.49E+08 2.49E+08 2.49E+08 2.89E+08 NB-95 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.60E+08 RU-103 1.09E+08 1.09E+08 1.09E+08 1.09E+08 1.09E+08 1.09E+08 1.09E+08 1.27E+08 RU-106 4.19E+08 4.19E+08 4.19E+08 4.19E+08 4.19E+08 4.19E+08 4.19E+08 5.03E+08 AG-11OM 3.48E+09 3.48E+09 3.48E+09 3.48E+09 3.48E+09 3.48E+09 3.48E+09 4.06E+09 SN-113 1.44E+07 6.28E+06 1.22E+07 6.21E+06 1.OOE+07 1.33E+07 8.14E+06 4.09E+07 TE-127M 9.15E+04 9.15E+04 9.15E+04 9.15E+04 9.15E+04 9.15E+04 9.15E+04 1.08E+05 TE-129M 2.OOE+07 2.OOE+07 2.OOE+07 2.OOE+07 2.OOE+07 2.OOE+07 2.OOE+07 2.34E+07 1-131 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 2.09E+07 1-132 1.24E+06 1.24E+06 1.24E+06 1.24E+06 1.24E+06 1.24E+06 1.24E+06 1.46E+06 1-133 2.47E+06 2.47E+06 2.47E+06 2.47E+06 2.47E+06 2.47E+06 2.47E+06 3.OOE+06 1-135 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.99E+06 CS-134 6.82E+09 6.82E+09 6.82E+09 6.82E+09 6.82E+09 6.82E+09 6.82E+09 7.96E+09 CS-136 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.69E+08 CS-137 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.20E+10 BA-140 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.34E+07 CE-141 1.36E+07 1.36E+07 1.36E+07 1.36E+07 1.36E+07 1.36E+07 1.36E+07 1.53E+07 CE-144 6.95E+07 6.95E+07 6.95E+07 6.95E+07 6.95E+07 6.95E+07 6.95E+07 8.03E+07 HF-181 1.97E+08 1.63E+08 2.30E+08 1.70E+08 1.76E+08 2.33E+08 1.82E+08 2.82E+08 AM-241 5.16E+08 5.16E+08 5.16E+08 5.16E+08 5.16E+08 5.16E+08 5.16E+08 7.45E+08 3

R Values in units of mrem/yr per p.Ci/m for inhalation and tritium, and in units of m2-mrem/yr per pCi/sec for all others.

ODCM (BSEP) 3-43 Rev. 37

TABLE 3.3-2 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Vegetable AGE GROUP = Adult Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 2.28E+03 2.28E+03 0.OOE+00 2.28E+03 2.28E+03 2.28E+03 2.28E+03 2.28E+03 P-32 5.91E+07 1.72E+08 1.53E+09 9.51E+07 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CR-51 4.60E+04 1.16E+07 O.OOE+00 O.OOE+00 1.01E+04 2.75E+04 6.1OE+04 O.OOE+00 MN-54 5.83E+07 9.36E+08 O.OOE+00 3.05E+08 9.09E+07 0.OOE+00 O.OOE+00 0.OOE+00 FE-59 1.12E+08 9.75E+08 1.24E+08 2.93E+08 O.OOE+00 0.OOE+00 8.17E+07 0.OOE+00 CO-58 6.71E+07 6.07E+08 O.OOE+00 2.99E+07 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 CO-60 3.67E+08 3.12E+09 O.OOE+00 1.66E+08 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 ZN-65 5.77E+08 8.04E+08 4.01 E+08 1.28E+09 8.54E+08 O.OOE+00 0.OOE+00 0.OOE+00 RB-86 1.03E+08 4.36E+07 O.OOE+00 2.21E+08 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 SR-89 2.87E+08 1.60E+09 1.00E+10 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 SR-90 1.64E+11 1.93E+10 6.70E+11 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Y-91 1.34E+05 2.76E+09 5.01 E+06 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 ZR-95 2.51E+05 1.17E+09 1.16E+06 3.71E+05 5.82E+05 0.OOE+00 O.OOE+00 0.OOE+00 NB-95 4.19E+04 4.73E+08 1.40E+05 7.79E+04 7.70E+04 0.OOE+00 0.OOE+00 0.OOE+00 RU-103 2.04E+06 5.53E+08 4.74E+06 0.OOE+00 1.81E+07 0.OOE+00 0.OOE+00 0.OOE+00 RU-106 2.46E+07 1.26E+10 1.94E+08 0.OOE+00 3.75E+08 0.OOE+00 0.OOE+00 O.OOE+00 AG-11iM 6.23E+06 4.28E+09 1.13E+07 1.05E+07 2.06E+07 0.OOE+00 0.OOE+00 O.OOE+00 SN-113 1.36E+07 2.53E+08 1.44E+07 5.60E+05 4.09E+05 1.96E+05 0.OOE+00 O.OOE+00 TE-127M 6.12E+07 1.68E+09 5.02E+08 1.80E+08 2.04E+09 1.28E+08 0.OOE+00 O.OOE+00 TE-129M 4.71E+07 1.50E+09 2.98E+08 1.11E+08 1.24E+09 1.02E+08 0.OOE+00 0.OOE+00 1-131 6.61E+07 3.04E+07 8.07E+07 1.15E+08 1.98E+08 3.78E+10 O.OOE+00 O.OOE+00 1-132 5.21E+01 2.80E+01 5.57E+01 1.49E+02 2.37E+02 5.21E+03 O.OOE+00 0.OOE+00 1-133 1.12E+06 3.30E+06 2.11E+06 3.67E+06 6.40E+06 5.39E+08 0.OOE+00 0.OOE+00 1-135 3.91E+04 1.20E+05 4.05E+04 1.06E+05 1.70E+05 7.OOE+06 0.OOE+00 0.OOE+00 CS-134 8.83E+09 1.89E+08 4.54E+09 1.08E+10 3.49E+09 0.OOE+00 1.16E+09 O.OOE+00 CS-136 1.19E+08 1.88E+07 4.19E+07 1.66E+08 9.21E+07 0.OOE+00 1.26E+07 0.OOE+00 CS-137 5.94E+09 1.76E+08 6.63E+09 9.07E+09 3.08E+09 O.OOE+00 1.02E+09 0.OOE+00 BA-140 8.40E+06 2.64E+08 1.28E+08 1.61E+05 5.47E+04 0.OOE+00 9.22E+04 0.OOE+00 CE-141 1.48E+04 4.99E+08 1.93E+05 1.31E+05 6.07E+04 0.OOE+00 O.OOE+00 0.OOE+00 CE-144 1.69E+06 1.06E+10 3.15E+07 1.32E+07 7.80E+06 O.OOE+00 0.OOE+00 0.OOE+00 HF-181 1.08E+06 7.06E+08 9.51E+06 5.36E+04 4.48E+04 3.41E+04 O.OOE+00 O.OOE+00 AM-241 4.12E+09 5.65E+09 5.75E+10 5.37E+10 3.10E+10 0.OOE+00 0.OOE+00 0.OOE+00

R Values in units of mrem/yr per pCi/m 3 for inhalation and tritium, and in units of mZ-mrem/yr per i.Ci/sec for all others.

ODCM (BSEP) 3-44 Rev. 37 I

TABLE 3.3-3 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Vegetable AGE GROUP = Teen Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 2.61E+03 2.61E+03 O.OOE+00 2.61E+03 2.61E+03 2.61E+03 2.61E+03 2.61E+03 P-32 6.80E+07 1.47E+08 1.75E+09 1.09E+08 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CR-51 6.11E+04 1.03E+07 O.OOE+00 O.OOE+00 1.34E+04 3.39E+04 8.72E+04 O.OOE+00 MN-54 8.79E+07 9.09E+08 O.OOE+00 4.43E+08 1.32E+08 O.OOE+00 O.OOE+00 O.OOE+00 FE-59 1.60E+08 9.78E+08 1.77E+08 4.14E+08 O.OOE+00 O.OOE+00 1.30E+08 O.OOE+00 CO-58 9.79E+07 5.85E+08 O.OOE+00 4.25E+07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CO-60 5.57E+08 3.22E+09 O.OOE+00 2.47E+08 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 ZN-65 8.68E+08 7.88E+08 5.36E+08 1.86E+09 1.19E+09 O.OOE+00 O.OOE+00 O.OOE+00 RB-86 1.30E+08 4.09E+07 O.OOE+00 2.76E+08 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-89 4.36E+08 1.81E+09 1.52E+10 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-90 2.05E+11 2.33E+10 8.32E+11 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-91 2.06E+05 3.15E+09 7.68E+06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 ZR-95 3.68E+05 1.23E+09 1.69E+06 5.35E+05 7.86E+05 O.OOE+00 O.OOE+00 O.OOE+00 NB-95 5.77E+04 4.48E+08 1.89E+05 1.05E+05 1.02E+05 O.OOE+00 O.OOE+00 O.OOE+00 RU-103 2.90E+06 5.66E+08 6.78E+06 O.OOE+00 2.39E+07 O.OOE+00 O.OOE+00 O.OOE+00 RU-106 3.93E+07 1.50E+10 3.12E+08 O.OOE+00 6.02E+08 O.OOE+00 O.OOE+00 O.OOE+00 AG-11iM 9.39E+06 4.34E+09 1.63E+07 1.54E+07 2.95E+07 O.OOE+00 O.OOE+00 O.OOE+00 SN-113 2.02E+07 2.29E+08 1.91E+07 8.03E+05 5.65E+05 2.63E+05 O.OOE+00 O.OOE+00 TE-127M 9.44E+07 1.98E+09 7.93E+08 2.81E+08 3.22E+09 1.89E+08 O.OOE+00 O.OOE+00 TE-129M 6.79E+07 1.61E+09 4.29E+08 1.59E+08 1.77E+09 1.38E+08 O.OOE+00 O.OOE+00 1-131 5.77E+07 2.13E+07 7.68E+07 1.07E+08 1.85E+08 3.14E+10 O.OOE+00 O.OOE+00 1-132 4.72E+01 5.72E+01 5.02E+01 1.31E+02 2.07E+02 4.43E+03 O.OOE+00 O.OOE+00 1-133 1.01E+06 2.51E+06 1.96E+06 3.32E+06 5.83E+06 4.64E+08 O.OOE+00 O.OOE+00 1-135 3.49E+04 1.04E+05 3.66E+04 9.42E+04 1.49E+05 6.06E+06 O.OOE+00 O.OOE+00 CS-134 7.54E+09 2.02E+08 6.90E+09 1.62E+10 5.16E+09 O.OOE+00 1.97E+09 O.OOE+00 CS-136 1.13E+08 1.35E+07 4.28E+07 1.68E+08 9.16E+07 O.OOE+00 1.44E+07 O.OOE+00 CS-137 4.90E+09 2.OOE+08 1.06E+10 1.41E+10 4.78E+09 O.OOE+00 1.86E+09 O.OOE+00 BA-140 8.88E+06 2.12E+08 1.38E+08 1.69E+05 5.72E+04 O.OOE+00 1.14E+05 O.OOE+00 CE-141 2.12E+04 5.29E+08 2.77E+05 1.85E+05 8.70E+04 O.OOE+00 O.OOE+00 O.OOE+00 CE-144 2.71E+06 1.27E+10 5.04E+07 2.09E+07 1.25E+07 O.OOE+00 O.OOE+00 O.OOE+00 HF-181 1.54E+06 6.90E+08 1.38E+07 7.58E+04 6.32E+04 4.63E+04 O.OOE+00 O.OOE+00 AM-241 4.97E+09 6.80E+09 6.89E+10 6.50E+10 3.72E+10 O.OOE+00 O.OOE+00 0.00E+OO 3

R Values in units of mrem/yr per piCi/m for inhalation and tritium, and in units of m2-mrem/yr per piCi/sec for all others. I ODCM (BSEP) 3-45 Rev. 37 I

TABLE 3.3-4 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Vegetable AGE GROUP = Child Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 4.04E+03 4.04E+03 O.OOE+00 4.04E+03 4.04E+03 4.04E+03 4.04E+03 4.04E+03 P-32 1.42E+08 1.01E+08 3.67E+09 1.72E+08 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CR-51 1.16E+05 6.15E+06 O.OOE+00 O.OOE+00 1.76E+04 6.44E+04 1.18E+05 O.OOE+00 MN-54 1.73E+08 5.44E+08 O.OOE+00 6.49E+08 1.82E+08 O.OOE+00 O.OOE+00 O.OOE+00 FE-59 3.17E+08 6.62E+08 3.93E+08 6.36E+08 O.OOE+00 O.OOE+00 1.84E+08 O.OOE+00 CO-58 1.92E+08 3.66E+08 O.OOE+00 6.27E+07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CO-60 1.11E+09 2.08E+09 O.OOE+00 3.76E+08 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 ZN-65 1.70E+09 4.81E+08 1.03E+09 2.74E+09 1.73E+09 O.OOE+00 O.OOE+00 O.OOE+00 RB-86 2.81 E+08 2.94E+07 O.OOE+00 4.56E+08 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-89 1.03E+09 1.40E+09 3.62E+10 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-90 3.49E+11 1.86E+10 1.38E+12 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-91 4.89E+05 2.44E+09 1.83E+07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 ZR-95 7.44E+05 8.71 E+08 3.80E+06 8.35E+05 1.20E+06 O.OOE+00 O.OOE+00 O.OOE+00 NB-95 1.12E+05 2.91E+08 4.04E+05 1.57E+05 1.48E+05 O.OOE+00 O.OOE+00 O.OOE+00 RU-103 5.86E+06 3.94E+08 1.52E+07 O.OOE+00 3.84E+07 O.OOE+00 O.OOE+00 O.OOE+00 RU-106 9.38E+07 1.17E+10 7.52E+08 O.OOE+00 1.02E+09 O.OOE+00 O.OOE+00 O.OOE+00 AG-110M 1.87E+07 2.78E+09 3.46E+07 2.34E+07 4.35E+07 O.OOE+00 O.OOE+00 O.OOE+00 SN-113 3.98E+07 1.46E+08 3.64E+07 1.18E+06 8.09E+05 4.82E+05 O.OOE+00 O.OOE+00 TE-127M 2.26E+08 1.54E+09 1.90E+09 5.12E+08 5.42E+09 4.55E+08 O.OOE+00 O.OOE+00 TE-129M 1.55E+08 1.22E+09 9.98E+08 2.79E+08 2.93E+09 3.22E+08 O.OOE+00 O.OOE+00 1-131 8.16E+07 1.23E+07 1.43E+08 1.44E+08 2.36E+08 4.75E+10 O.OOE+00 O.OOE+00 1-132 7.53E+01 1.93E+02 8.91E+01 1.64E+02 2.51E+02 7.60E+03 O.OOE+00 O.OOE+00 1-133 1.67E+06 1.78E+06 3.57E+06 4.42E+06 7.36E+06 8.21E+08 O.OOE+00 O.OOE+00 1-135 5.54E+04 8.92E+04 6.50E+04 1.17E+05 1.79E+05 1.04E+07 O.OOE+00 O.OOE+00 CS-134 5.40E+09 1.38E+08 1.56E+10 2.56E+10 7.93E+09 O.OOE+00 2.84E+09 O.OOE+00 CS-136 1.43E+08 7.77E+06 8.04E+07 2.21E+08 1.18E+08 O.OOE+00 1.76E+07 O.OOE+00 CS-137 3.52E+09 1.50E+08 2.49E+10 2.39E+10 7.78E+09 O.OOE+00 2.80E+09 O.OOE+00 BA-140 1.61E+07 1.40E+08 2.76E+08 2.42E+05 7.87E+04 O.OOE+00 1.44E+05 O.OOE+00 CE-141 4.75E+04 3.99E+08 6.42E+05 3.20E+05 1.40E+05 O.OOE+00 O.OOE+00 O.OOE+00 CE-144 6.49E+06 9.94E+09 1.22E+08 3.81E+07 2.11E+07 O.OOE+00 O.OOE+00 O.OOE+00 HF-181 3.15E+06 3.17E+08 3.13E+07 1.22E+05 9.78E+04 1.03E+05 O.OOE+00 O.OOE+00 AM-241 7.12E+09 5.34E+09 9.50E+10 8.17E+10 4.35E+10 O.OOE+00 O.OOE+00 O.OOE+00 3

R Values in units of mrem/yr per gCi/m for inhalation and tritium, and in units of mZ-mrem/yr per giCi/sec for all others.

ODCM (BSEP) 3-46 Rev. 37

TABLE 3.3-5 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Meat AGE GROUP = Adult Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 3.27E+02 3.27E+02 O.OOE+00 3.27E+02 3.27E+02 3.27E+02 3.27E+02 3.27E+02 P-32 1.18E+08 3.43E+08 3.05E+09 1.89E+08 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CR-51 4.27E+03 1.08E+06 O.OOE+01 O.OOE+00 9.42E+02 2.56E+03 5.67E+03 O.OOE+00 MN-54 1.06E+06 1.71E+07 O.OOE+00 5.57E+06 1.66E+06 O.OOE+00 O.OOE+00 O.OOE+00 FE-59 1.43E+08 1.25E+09 1.59E+08 3.74E+08 O.OOE+00 O.OOE+00 1.04E+08 O.OOE+00 CO-58 2.43E+07 2.20E+08 O.OOE+00 1.08E+07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CO-60 1.03E+08 8.76E+08 O.OOE+00 4.66E+07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 ZN-65 3.58E+08 4.98E+08 2.49E+08 7.91E+08 5.29E+08 O.OOE+00 O.OOE+00 O.OOE+00 RB-86 1.42E+08 6.OOE+07 O.OOE+00 3.04E+08 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-89 5.23E+06 2.92E+07 1.82E+08 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-90 2.02E+09 2.38E+08 8.22E+09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-91 1.80E+04 3.71 E+08 6.75E+05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 ZR-95 2.43E+05 1.14E+09 1.12E+06 3.59E+05 5.64E+05 O.OOE+00 O.OOE+00 O.OOE+00 NB-95 4.12E+05 4.65E+09 1.38E+06 7.66E+05 7.58E+05 O.OOE+00 O.OOE+00 O.OOE+00 RU-103 2.72E+07 7.38E+09 6.32E+07 O.OOE+00 2.41E+08 O.OOE+00 O.OOE+00 O.OOE+00 RU-106 2.19E+08 1.12E+11 1.73E+09 O.OOE+00 3.35E+09 O.OOE+00 O.OOE+00 O.OOE+00 AG-110M 2.34E+06 1.61E+09 4.27E+06 3.95E+06 7.76E+06 O.OOE+00 O.OOE+00 O.OOE+00 SN-113 2.80E+07 5.19E+08 2.97E+07 1.15E+06 8.40E+05 4.03E+05 O.OOE+00 O.OOE+00 TE-127M 1.OOE+08 2.76E+09 8.22E+08 2.94E+08 3.34E+09 2.1OE+08 O.OOE+00 O.OOE+00 TE-129M 1.17E+08 3.73E+09 7.40E+08 2.76E+08 3.09E+09 2.54E+08 O.OOE+00 O.OOE+00 1-131 5.77E+06 2.66E+06 7.04E+06 1.01E+07 1.73E+07 3.30E+09 O.OOE+00 O.OOE+O0 1-133 1.51E-01 4.46E-01 2.85E-01 4.96E-01 8.66E-01 7.29E+01 O.OOE+00 O.OOE+00 1-135 6.07E-17 1.86E-16 6.28E-17 1.64E-16 2.64E-16 1.08E-14 O.OOE+00 O.OOE+00 CS-134 7.81E+08 1.67E+07 4.01E+08 9.55E+08 3.09E+08 O.OOE+00 1.03E+08 O.OOE+00 CS-136 2.14E+07 3.33E+06 7.53E+06 2.97E+07 1.65E+07 O.OOE+00 2.27E+06 O.OOE+00 CS-137 4.99E+08 1.47E+07 5.57E+08 7.61E+08 2.58E+08 O.OOE+00 8.59E+07 O.OOE+00 BA-140 1.20E+06 3.77E+07 1.83E+07 2.30E+04 7.82E+03 O.OOE+00 1.32E+04 O.OOE+00 CE-141 6.46E+02 2.18E+07 8.42E+03 5.69E+03 2.65E+03 O.OOE+00 O.OOE+00 O.OOE+00 CE-144 4.70E+04 2.96E+08 8.75E+05 3.66E+05 2.17E+05 O.OOE+00 O.OOE+00 O.OOE+00 HF-181 1.52E+06 9.97E+08 1.34E+07 7.57E+04 6.33E+04 4.81E+04 O.OOE+00 O.OOE+00 AM-241 1.80E+07 2.47E+07 2.52E+08 2.35E+08 1.36E+08 O.OOE+00 O.OOE+00 0.00E+:0

R Values in units of mrem/yr per piCi/m 3 for inhalation and tritium, and in units of m -mrem/yr per pCi/sec for all others.

ODCM (BSEP) 3-47 Rev. 37 1

TABLE 3.3-6 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Meat AGE GROUP = Teen Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 1.95E+02 1.95E+02 O.OOE+00 1.95E+02 1.95E+02 1.95E+02 1.95E+02 1.95E+02 P-32 9.98E+07 2.16E+08 2.58E+09 1.60E+08 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CR-51 3.42E+03 5.75E+05 O.OOE+00 O.OOE+00 7.49E+02 1.90E+03 4.88E+03 O.OOE+00 MN-54 8.43E+05 8.72E+06 O.OOE+00 4.25E+06 1.27E+06 O.OOE+00 O.OOE+00 0.00E+00 FE-59 1.15E+08 7.02E+08 1.27E+08 2.97E+08 0.00E+00 O.OOE+00 9.36E+07 O.OOE+00 CO-58 1.93E+07 1.15E+08 0.00E+00 8.36E+06 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 CO-60 8.15E+07 4.71E+08 0.00E+00 3.62E+07 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 ZN-65 2.83E+08 2.57E+08 1.75E+08 6.07E+08 3.89E+08 O.OOE+00 O.OOE+00 O.OOE+00 RB-86 1.19E+08 3.76E+07 0.00E+00 2.54E+08 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-89 4.40E+06 1.83E+07 1.54E+08 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 SR-90 1.31 E+09 1.49E+08 5.32E+09 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 Y-91 1.52E+04 2.33E+08 5.68E+05 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 ZR-95 1.95E+05 6.53E+08 8.97E+05 2.83E+05 4.16E+05 O.OOE+00 O.OOE+00 0.00E+00 NB-95 3.29E+05 2.55E+09 1.08E+06 5.97E+05 5.79E+05 0.00E+00 O.OOE+00 O.OOE+00 RU-103 2.20E+07 4.30E+09 5.15E+07 O.OOE+00 1.82E+08 O.OOE+00 O.OOE+00 0.00E+00 RU-106 1.84E+08 7.OOE+10 1.46E+09 O.OOE+00 2.81E+09 O.OOE+00 0.00E+00 0.00E+00 AG-11OM 1.86E+06 8.59E+08 3.23E+06 3.06E+06 5.83E+06 0.00E+00 0.00E+00 0.00E+00 SN-113 2.22E+07 2.51E+08 2.09E+07 8.80E+05 6.19E+05 2.89E+05 0.00E+00 0.00E+00 TE-127M 8.25E+07 1.73E+09 6.94E+08 2.46E+08 2.81E+09 1.65E+08 O.OOE+00 O.OOE+00 TE-129M 9.81E+07 2.33E+09 6.20E+08 2.30E+08 2.59E+09 2.OOE+08 O.OOE+00 0.00E+00 1-131 4.40E+06 1.62E+06 5.85E+06 8.20E+06 1.41E+07 2.39E+09 O.OOE+00 O.OOE+00 1-133 1.23E-01 3.06E-01 2.39E-01 4.05E-01 7.1OE-01 5.65E+01 0.00E+00 0.00E+00 1-135 4.88E-17 1.46E-16 5.11E-17 1.32E-16 2.08E-16 8.46E-15 0.00E+00 O.OOE+00 CS-134 3.48E+08 9.34E+06 3.19E+08 7.51E+08 2.39E+08 O.OOE+00 9.11E+07 0.00E+00 CS-136 1.55E+07 1.86E+06 5.87E+06 2.31E+07 1.26E+07 O.OOE+00 1.98E+06 O.OOE+00 CS-137 2.14E+08 8.75E+06 4.62E+08 6.15E+08 2.09E+08 O.OOE+00 8.13E+07 O.OOE+00 BA-140 9.76E+05 2.34E+07 1.51E+07 1.86E+04 6.29E+03 O.OOE+00 1.25E+04 0.00E+00 CE-141 5.42E+02 1.35E+07 7.07E+03 4.72E+03 2.22E+03 0.00E+00 O.OOE+00 0.00E+00 CE-144 3.96E+04 1.85E+08 7.37E+05 3.05E+05 1.82E+05 O.OOE+00 O.OOE+00 O.OOE+00 HF-181 1.23E+06 5.50E+08 1.1OE+07 6.05E+04 5.04E+04 3.69E+04 0.00E+00 O.OOE+00 AM-241 1.13E+07 1.55E+07 1.57E+08 1.48E+08 8.49E+07 O.OOE+00 O.OOE+00 0.00E+00 3

R Values in units of mrem/yr per piCi/m for inhalation and tritium, and in units of m2-mrem/yr per pCi/sec for all others.

ODCM (BSEP) 3-48 Rev. 37

TABLE 3.3-7 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Meat AGE GROUP = Child Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 2.36E+02 2.36E+02 O.OOE+00 2.36E+02 2.36E+02 2.36E+02 2.36E+02 2.36E+02 P-32 1.87E+08 1.34E+08 4.86E+09 2.27E+08 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CR-51 5.33E+03 2.83E+05 O.OOE+00 O.OOE+00 8.09E+02 2.96E+03 5.40E+03 O.OOE+00 MN-54 1.30E+06 4.08E+06 O.OOE+00 4.86E+06 1.36E+06 O.OOE+00 O.OOE+00 O.OOE+00 FE-59 1.82E+08 3.80E+08 2.25E+08 3.65E+08 O.OOE+00 O.OOE+00 1.06E+08 O.OOE+00 CO-58 2.99E+07 5.70E+07 O.OOE+00 9.76E+06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CO-60 1.27E+08 2.38E+08 O.OOE+00 4.30E+07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 ZN-65 4.35E+08 1.23E+08 2.62E+08 6.99E+08 4.40E+08 O.OOE+00 O.OOE+00 O.OOE+00 RB-86 2.21 E+08 2.32E+07 O.OOE+00 3.60E+08 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-89 8.31E+06 1.13E+07 2.91E+08 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-90 1.74E+09 9.26E+07 6.87E+09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-91 2.87E+04 1.43E+081 1.07E+06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 ZR-95 3.12E+05 3.65E+08 1.59E+06 3.50E+05 5.01E+05 O.OOE+00 O.OOE+00 O.OOE+00 NB-95 5.17E+05 1.34E+09 1.86E+06 7.23E+05 6.80E+05 O.OOE+00 O.OOE+00 O.OOE+00 RU-103 3.58E+07 2.41E+09 9.31E+07 O.OOE+00 2.34E+08 O.OOE+00 O.OOE+00 O.OOE+00 RU-106 3.43E+08 4.27E+10 2.75E+09 O.OOE+00 3.71E+09 O.OOE+00 O.OOE+00 O.OOE+00 AG-110M 2.89E+06 4.30E+08 5.36E+06 3.62E+06 6.74E+06 O.OOE+00 O.OOE+00 O.OOE+00 SN-113 3.43E+07 1.25E+08 3.14E+07 1.01E+06 6.97E+05 4.15E+05 O.OOE+00 O.OOE+00 TE-127M 1.55E+08 1.06E+09 1.31E+09 3.52E+08 3.73E+09 3.13E+08 O.OOE+00 O.OOE+00 TE-129M 1.81E+08 1.42E+09 1.17E+09 3.26E+08 3.43E+09 3.77E+08 O.OOE+00 O.OOE+00 1-131 6.20E+06 9.72E+05 1.09E+07 1.09E+07 1.79E+07 3.61E+09 O.OOE+00 O.OOE+00 1-133 2.07E-01 2.21E-01 4.43E-01 5.48E-01 9.13E-01 1.02E+02 O.OOE+00 O.OOE+00 1-135 7.87E-17 1.27E-16 9.25E-17 1.66E-16 2.55E-16 1.47E-14 O.OOE+00 O.OOE+00 CS-134 1.95E+08 4.93E+06 5.63E+08 9.23E+08 2.86E+08 O.OOE+00 1.03E+08 O.OOE+00 CS-136 1.80E+07 9.78E+05 1.01E+07 2.78E+07 1.48E+07 O.OOE+00 2.21E+06 O.OOE+00 CS-137 1.20E+08 5.1OE+06 8.51E+08 8.15E+08 2.65E+08 O.OOE+00 9.55E+07 O.OOE+00 BA-140 1.63E+06 1.42E+07 2.80E+07 2.45E+04 7.97E+03 O.OOE+00 1.46E+04 O.OOE+00 CE-141 9.86E+02 8.28E+06 1.33E+04 6.64E+03 2.91E+03 O.OOE+00 O.OOE+00 O.OOE+00 CE-144 7.42E+04 1.14E+08 1.39E+06 4.36E+05 2.41E+05 O.OOE+00 O.OOE+00 O.OOE+00 HF-181 2.02E+06 3.31E+08 2.01E+07 7.79E+04 6.26E+04 6.56E+04 O.OOE+00 O.OOE+00 AM-241 1.27E+07 9.49E+06 I1.69E+08 1.45E+08 7.74E+07 O.OOE+00 O.OOE+00 O.OOE+00

R Values in units of mrem/yr per pCi/m 3 for inhalation and tritium, and in units of m2-mrem/yr per j.Ci/sec for all others.

ODCM (BSEP) 3-49 Rev. 37

TABLE 3.3-8 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Cow Milk AGE GROUP = Adult Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 7.69E+02 7.69E+02 0.OOE+00 7.69E+02 7.69E+02 7.69E+02 7.69E+02 7.69E+02 P-32 4.32E+08 1.26E+09 1.12E+10 6.95E+08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CR-51 1.73E+04 4.36E+06 0.OOE+00 0.00E+00 3.82E+03 1.04E+04 2.30E+04 0.00E+00 MN-54 9.76E+05 1.57E+07 0.OOE+00 5.11E+06 1.52E+06 0.00E+00 0.00E+00 0.00E+00 FE-59 1.60E+07 1.39E+08 1.77E+07 4.17E+07 0.00E+00 0.00E+00 1.17E+07 0.OOE+00 CO-58 6.28E+06 5.68E+07 0.OOE+00 2.80E+06 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CO-60 2.24E+07 1.91E+08 0.OOE+00 1.02E+07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 ZN-65 1.38E+09 1.92E+09 9.59E+08 3.05E+09 2.04E+09 0.OOE+00 0.OOE+00 0.OOE+00 RB-86 7.54E+08 3.19E+08 0.OOE+00 1.62E+09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 SR-89 2.50E+07 1.40E+08 8.70E+08 O.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 SR-90 7.59E+09 8.94E+08 3.09E+10 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 Y-91 1.37E+02 2.81E+06 5.11E+03 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 ZR-95 1.22E+02 5.71E+05 5.62E 02 1.80E 02 2.83E 02 0.OOE+00 0.OOE+00 0.00E+00 NB-95 1.48E+04 1.67E+08 4.95E+04 2.75E+04 2.72E+04 0.OOE+00 0.OOE+00 0.OOE+00 RU-103 2.63E+02 7.14E+04 6.11E+02 0.OOE+00 2.33E+03 0.OOE+00 0.OOE+00 0.00E+00 RU-106 1.60E+03 8.17E+05 1.26E+04 0.OOE+00 2.44E+04 0.OOE+00 0.OOE+00 0.OOE+00 AG-110M 2.04E+07 1.40E+10 3.71E+07 3.44E+07 6.76E+07 0.OOE+00 0.OOE+00 O.OOE+00 SN-1 13 1.32E+06 2.44E+07 1.40E+06 5.41 E+04 3.96E+04 1.90E+04 0.OOE+00 0.OOE+00 TE-127M 4.11E+06 1.13E+08 3.37E+07 1.21E+07 1.37E+08 8.62E+06 0.OOE+00 0.OOE+00 TE-129M 6.19E+06 1.97E+08 3.91E+07 1.46E+07 1.63E+08 1.34E+07 0.OOE+00 0.OOE+00 1-131 1.59E+08 7.32E+07 1.94E+08 2.77E+08 4.76E+08 9.09E+10 0.OOE+00 0.OOE+00 1-132 1.03E-01 5.51E-02 1.10E-01 2.93E-01 4.67E-01 1.03E+01 0.OOE+00 0.OOE+00 1-133 1.40E+06 4.13E+06 2.64E+06 4.59E+06 8.01E+06 6.75E+08 0.OOE+00 0.OOE+00 1-135 9.03E+03 2.76E+04 9.34E+03 2.45E+04 3.92E+04 1.61E+06 0.OOE+00 0.OOE+00 CS-134 6.71E+09 1.44E+08 3.45E+09 8.22E+09 2.66E+09 0.OOE+00 8.82E+08 O.OOE+00 CS-136 4.73E+08 7.46E+07 1.66E+08 6.57E+08 3.65E+08 0.OOE+00 5.01E+07 0.OOE+00 CS-137 4.22E+09 1.25E+08 4.71E+09 6.44E+09 2.19E+09 0.OOE+00 7.27E+08 0.OOE+00 BA-140 1.12E+06 3.53E+07 1.71E+07 2.15E+04 7.32E+03 0.OOE+00 1.23E+04 0.OOE+00 CE-141 2.23E+02 7.52E+06 2.91E+03 1.97E+03 9.14E+02 0.OOE+00 0.OOE+00 0.OOE+00 CE-144 1.15E+04 7.26E+07 2.15E+05 8.97E+04 5.32E+04 0.OOE+00 0.OOE+00 0.OOE+00 HF-181 6.68E+02 4.39E+05 5.91E+03 3.33E+01 2.79E+01 2.12E+01 0.OOE+00 0.OOE+00 AM-241 1.27E+06 1.74E+06 1.77E+07 1.66E+07 9.56E+06 0.OOE+00 0.OOE+00 0.OOE+00

R Values in units of mrem/yr per gCi/m3 for inhalation and tritium, and in units of m2-mrem/yr per gCi/sec for all others.

ODCM (BSEP) 3-50 Rev. 37 I

TABLE 3.3-9 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Cow Milk AGE GROUP = Teen Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 1.00E+03 1.OOE+03 O.OOE+00 1.OOE+03 1.OOE+03 1.OOE+03 1.OOE+03 1.OOE+03 P-32 8.OOE+08 1.73E+09 2.06E+10 1.28E+09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CR-51 3.02E+04 5.08E+06 O.OOE+00 O.OOE+00 6.63E+03 1.68E+04 4.32E+04 O.OOE+00 MN-54 1.69E+06 1.75E+07 O.OOE+00 8.52E+06 2.54E+06 O.OOE+00 O.OOE+00 O.OOE+00 FE-59 2.79E+07 1.71E+08 3.10E+07 7.23E+07 O.OOE+00 O.OOE+00 2.28E+07 O.OOE+00 CO-58 1.09E+07 6.50E+07 O.OOE+00 4.72E+06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CO-60 3.88E+07 2.25E+08 O.OOE+00 1.72E+07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 ZN-65 2.38E+09 2.16E+09 1.47E+09 5.11E+09 3.27E+09 O.OOE+00 O.OOE+00 O.OOE+00 RB-86 1.39E+09 4.37E+08 O.OOE+00 2.95E+09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-89 4.59E+07 1.91E+08 1.60E+09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-90 1.08E+10 1.23E+09 4.37E+10 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-91 2.52E+02 3.85E+06 9.40E+03 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 ZR-95 2.13E+02 7.14E+05 9.83E+02 3.10E+02 4.56E+02 O.OOE+00 O.OOE+00 O.OOE+00 NB-95 2.58E+04 2.OOE+08 8.45E+04 4.68E+04 4.54E+04 O.OOE+00 O.OOE+00 O.OOE+00 RU-103 4.65E+02 9.08E+04 1.09E+03 O.OOE+00 3.83E+03 O.OOE+00 O.OOE+00 O.OOE+00 RU-106 2.93E+03 1.11E+06 2.32E+04 O.OOE+00 4.48E+04 O.OOE+00 O.OOE+00 O.OOE+00 AG-110M 3.53E+07 1.63E+10 6.14E+07 5.81E+07 1.11E+08 O.OOE+00 O.OOE+00 O.OOE+00 SN-113 2.28E+06 2.58E+07 2.15E+06 9.06E+04 6.37E+04 2.97E+04 O.OOE+04 O.OOE+00 TE-127M 7.39E+06 1.55E+08 6.22E+07 2.21E+07 2.52E+08 1.48E+07 O.OOE+00 O.OOE+00 TE-129M 1.13E+07 2.69E+08 7.15E+07 2.65E+07 2.99E+08 2.31E+07 O.OOE+00 O.OOE+00 1-131 2.65E+08 9.75E+07 3.52E+08 4.93E+08 8.48E+08 1.44E+11 O.OOE+00 O.OOE+00 1-132 1.83E-01 2.22E-01 1.94E-01 5.09E-01 8.02E-01 1.71E+01 O.OOE+00 O.OOE+00 1-133 2.49E+06 6.19E+06 4.82E+06 8.18E+06 1.43E+07 1.14E+09 O.OOE+00 O.OOE+00 1-135 1.58E+04 4.74E+04 1.66E+04 4.27E+04 6.75E+04 2.75E+06 O.OOE+00 O.OOE+00 CS-134 6.54E+09 1.75E+08 5.99E+09 1.41E+10 4.48E+09 O.OOE+00 1.71E+09 O.OOE+00 CS-136 7.48E+08 8.97E+07 2.83E+08 1.11E+09 6.07E+08 O.OOE+00 9.56E+07 O.OOE+00 CS-137 3.96E+09 1.62E+08 8.54E+09 1.14E+10 3.87E+09 O.OOE+00 1.50E+09 O.OOE+00 BA-140 1.99E+06 4.77E+07 3.09E+07 3.79E+04 1.28E+04 O.OOE+00 2.55E+04 O.OOE+00 CE-141 4.09E+02 1.02E+07 5.35E+03 3.56E+03 1.68E+03 O.OOE+00 O.OOE+00 O.OOE+00 CE-144 2.12E+04 9.93E+07 3.95E+05 1.63E+05 9.76E+04 O.OOE+00 O.OOE+00 O.OOE+00 HF-181 1.18E+03 5.28E+05 1.06E+04 5.81E+01 4.84E+01 3.55E+01 O.OOE+00 0.00E+00 AM-241 1.74E+06 2.38E+06 2.42E+07 2.28E+07 1.31E+07 O.OOE+00 O.OOE+00 0.00E+00 3

R Values in units of mrem/yr per LCi/rm for inhalation and tritium, and in units of m 2-mrem/yr per PCi/sec for all others.

ODCM (BSEP) 3-51 Rev. 37 I

TABLE 3.3-10 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Cow Milk AGE GROUP = Child Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 1.58E+03 1.58E+03 O.OOE+00 1.58E+03 1.58E+03 1.58E+03 1.58E+03 1.58E+03 P-32 1.96E+09 1.41E+09 5.09E+10 2.38E+09 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 CR-51 6.17E+04 3.27E+06 O.OOE+00 O.OOE+00 9.36E+03 3.42E+04 6.25E+04 O.OOE+00 MN-54 3.39E+06 1.07E+07 O.OOE+00 1.27E+07 3.57E+06 O.OOE+00 O.OOE+00 O.OOE+00 FE-59 5.79E+07 1.21E+08 7.18E+07 1.16E+08 O.OOE+00 O.OOE+00 3.37E+07 O.OOE+00 CO-58 2.21 E+07 4.20E+07 O.OOE+00 7.21E+06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CO-60 7.90E+07 1.48E+08 O.OOE+00 2.68E+07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 ZN-65 4.79E+09 1.35E+09 2.89E+09 7.70E+09 4.85E+09 0.OOE+00 O.OOE+00 O.OOE+00 RB-86 3.36E+09 3.52E+08 0.OOE+00 5.47E+09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-89 1.13E+08 1.54E+08 3.97E+09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-90 1.87E+10 9.95E+08 7.38E+10 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-91 6.21 E+02 3.09E+06 2.32E+04 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 ZR-95 4.47E+02 5.23E+05 2.28E+03 5.02E+02 7.18E+02 O.OOE+00 O.OOE+00 O.OOE+00 NB-95 5.31E+04 1.37E+08 1.91E+05 7.42E+04 6.98E+04 O.OOE+00 O.OOE+00 O.OOE+00 RU-103 9.88E+02 6.65E+04 2.57E+03 O.OOE+00 6.47E+03 O.OOE+00 0.OOE+00 O.OOE+00 RU-106 7.14E+03 8.90E+05 5.72E+04 O.OOE+00 7.72E+04 O.OOE+00 O.OOE+00 0.OOE+00 AG-110M 7.19E+07 1.07E+10 1.33E+08 9.OOE+07 1.68E+08 O.OOE+00 0.OOE+00 O.OOE+00 SN-113 4.61E+06 1.69E+07 4.22E+08 4.13E+07 4.37E+08 3.66E+07 0.OOE+00 0.OOE+00 TE-127M 1.82E+07 1.24E+08 1.53E+08 4.13E+07 4.37E+08 3.66E+07 O.OOE+00 0.OOE+00 TE-129M 2.74E+07 2.15E+08 1.76E+08 4.92E+07 5.18E+08 5.68E+07 O.OOE+00 O.OOE+00 1-131 4.88E+08 7.64E+07 8.54E+08 8.59E+08 1.41E÷09 2.84E+11 O.OOE+00 O.OOE+00 1-132 3.89E-01 9.95E-01 4.60E-01 8.45E-01 1.29E+00 3.92E+01 O.OOE+00 O.OOE+00 1-133 5.48E+06 5.84E+06 1.17E+07 1.45E+07 2.41E+07 2.69E+09 O.OOE+00 O.OOE+00 1-135 3.35E+04 5.39E+04 3.93E+04 7.07E+04 1.08E+05 6.26E+06 O.OOE+00 O.OOE+00 CS-134 4.78E+09 1.22E+08 1.38E+10 2.27E+10 7.03E+09 O.OOE+00 2.52E+09 O.OOE+00 CS-136 1.14E+09 6.17E+07 6.39E+08 1.76E+09 9.36E+08 O.OOE+00 1.40E+08 O.OOE+00 CS-137 2.91E+09 1.23E+08 2.06E+10 1.97E+10 6.42E+09 O.OOE+00 2.31E+09 O.OOE+00 BA-140 4.36E+06 3.78E+07 7.47E+07 6.54E+04 2.13E+04 O.OOE+00 3.90E+04 O.OOE+00 CE-141 9.73E+02 8.17E+06 1.31E+04 6.55E+03 2.87E+03 O.OOE+00 O.OOE+00 O.OOE+00 CE-144 5.20E+04 7.96E+07 9.74E+05 3.05E+05 1.69E+05 0.OOE+00 O.OOE+00 O.OOE+00 HF-181 2.53E+03 4.16E+05 2.51E+04 9.79E+01 7.86E+01 8.24E+01 O.OOE+00 O.OOE+00 AM-241 2.55E+06 1.91E+06 3.40E+07 2.92E+07 1.56E+07 O.OOE+00 O.OOE+00 O.OOE+00

R Values in units of mrem/yr per pCi/m3 for inhalation and tritium, and in units of m2-mrem/yr per iCi/sec for all others.

ODCM (BSEP) 3-52 Rev. 37 I

TABLE 3.3-11 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Cow Milk AGE GROUP = Infant Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 2.40E+03 2.40E+03 O.OOE+00 2.40E+03 2.40E+03 2.40E+03 2.40E+03 2.40E+03 P-32 4.06E+09 1.42E+09 1.05E+11 6.17E+09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CR-51 9.77E+04 2.85E+06 O.OOE+00 O.OOE+00 1.39E+04 6.38E+04 1.24E+05 O.OOE+00 MN-54 5.37E+06 8.71 E+06 O.OOE+00 2.37E+07 5.25E+06 O.OOE+00 O.OOE+00 O.OOE+00 FE-59 9.23E+07 1.12E+08 1.34E+08 2.34E+08 O.OOE+00 O.OOE+00 6.92E+07 O.OOE+00 CO-58 3.60E+07 3.59E+07 O.OOE+00 1.44E+07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CO-60 1.29E+08 1.30E+08 O.OOE+00 5.47E+07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 ZN-65 6.14E+09 1.12E+10 3.88E+09 1.33E+10 6.45E+09 O.OOE+00 O.OOE+00 O.OOE+00 RB-86 6.86E+09 3.55E+08 O.OOE+00 1.39E+10 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-89 2.17E+08 1.55E+08 7.55E+09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-90 2.05E+10 1.OOE+09 8.04E+10 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-91 1.16E+03 3.12E+06 4.36E+04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 ZR-95 7.01E+02 4.92E+05 4.05E+03 9.88E+02 1.06E+03 O.OOE+00 O.OOE+00 O.OOE+00 NB-95 8.48E+04 1.24E+08 3.56E+05 1.47E+05 1.05E+05 O.OOE+00 O.OOE+00 O.OOE+00 RU-103 1.74E+03 6.33E+04 5.21E+03 O.OOE+00 1.08E+04 O.OOE+00 O.OOE+00 O.OOE+00 RU-106 1.47E+04 8.95E+05 1.18E+05 O.OOE+00 1.39E+05 O.OOE+00 O.OOE+00 O.OOE+00 AG-110M 1.19E+08 9.32E+09 2.46E+08 1.80E+08 2.57E+08 O.OOE+00 O.OOE+00 O.OOE+00 SN-113 6.66E+06 1.37E+07 6.46E+06 2.45E+05 1.32E+05 9.34E+04 O.OOE+00 O.OOE+00 TE-127M 3.75E+07 1.25E+08 3.10E+08 1.03E+08 7.64E+08 8.96E+07 O.OOE+00 O.OOE+00 TE-129M 5.57E+07 2.16E+08 3.62E+08 1.24E+08 9.05E+08 1.39E+08 O.OOE+00 O.OOE+00 1-131 9.23E+08 7.49E+07 1.78E+09 2.1OE+09 2.45E+09 6.90E+11 O.OOE+00 O.OOE+00 1-132 6.90E-01 1.57E+00 9.55E-01 1.94E+00 2.16E+00 9.09E+01 O.OOE+00 O.OOE+00 1-133 1.05E+07 6.09E+06 2.47E+07 3.60E+07 4.23E+07 6.55E+09 O.OOE+00 O.OOE+00 1-135 5.93E+04 5.83E+04 8.17E+04 1.63E+05 1.81E+05 1.46E+07 O.OOE+00 O.OOE+00 CS-134 4.19E+09 1.13E+08 2.23E+10 4.15E+10 1.07E+10 O.OOE+00 4.38E+09 O.OOE+00 CS-136 1.37E+09 5.58E+07 1.25E+09 3.67E+09 1.46E+09 O.OOE+00 2.99E+08 O.OOE+00 CS-137 2.72E+09 1.20E+08 3.28E+10 3.84E+10 1.03E+10 O.OOE+00 4.18E+09 O.OOE+00 BA-140 7.91E+06 3.77E+07 1.54E+08 1.54E+05 3.65E+04 O.OOE+00 9.43E+04 O.OOE+00 CE-141 1.87E+03 8.23E+06 2.60E+04 1.59E+04 4.90E+03 O.OOE+00 O.OOE+00 O.OOE+00 CE-144 7.82E+04 8.01E+07 1.40E+06 5.71E+05 2.31E+05 O.OOE+00 O.OOE+00 O.OOE+00 HF-181 4.23E+03 3.94E+05 4.78E+04 2.26E+02 1.32E+02 1.91E+02 O.OOE+00 O.OOE+00 AM-241 2.72E+06 1.92E+06 3.65E+07 3.17E+07 1.64E+07 O.OOE+00 O.OOE+00 O.OOE+00

R Values in units of mrem/yr per iACi/m 3 for inhalation and tritium, and in units of m2-mrem/yr per iQCi/sec for all others.

ODCM (BSEP) 3-53 Rev. 37

TABLE 3.3-12 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Goat Milk AGE GROUP = Adult Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 1.57E+03 1.57E+03 O.OOE+00 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 P-32 5.19E+08 1.51E+09 1.34E+10 8.34E+08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CR-51 2.08E+03 5.23E+05 O.OOE+00 0.OOE+00 4.58E+02 1.24E+03 2.76E+03 0.OOE+00 MN-54 1.17E+05 1.88E+06 0.OOE+00 6.14E+05 1.83E+05 O.OOE+00 0.OOE+00 0.OOE+00 FE-59 2.08E+05 1.81E+06 2.31E+05 5.42E+05 0.OOE+00 0.OOE+00 1.51E+05 0.OOE+00 CO-58 7.54E+05 6.82E+06 O.OOE+00 3.36E+05 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 CO-60 2.69E+06 2.29E+07 O.OOE+00 1.22E+06 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 ZN-65 1.65E+08 2.31E+08 1.15E+08 3.66E+08 2.45E+08 0.OOE+00 0.OOE+00 0.OOE+00 RB-86 9.05E+07 3.83E+07 0.OOE+00 1.94E+08 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 SR-89 5.24E+07 2.93E+08 1.83E+09 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 SR-90 1.59E+10 1.88E+09 6.49E+10 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 Y-91 1.64E+01 3.37E+05 6.13E 02 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 ZR-95 1.46E+01 6.85E+04 6.74E+01 2.16E+01 3.39E+01 0.OOE+00 0.OOE+00 O.OOE+00 NB-95 1.78E+03 2.01E+07 5.94E+03 3.31E+03 3.27E+03 0.OOE+00 0.OOE+00 0.OOE+00 RU-103 3.16E+01 8.56E+03 7.33E+01 0.OOE+00 2.80E+02 O.OOE+00 O.OOE+00 O.OOE+00 RU-106 1.92E+02 9.81E+04 1.52E+03 0.OOE+00 2.93E+03 0.OOE+00 O.OOE+00 0.OOE+00 AG-110M 2.45E+06 1.68E+09 4.46E+06 4.12E+06 8.11E+06 O.OOE+00 0.OOE+00 0.OOE+00 SN-113 1.32E+05 2.44E+06 1.40E+05 5.41E+03 3.96E+03 1.90E+03 O.OOE+00 0.OOE+00 TE-127M 4.93E+05 1.36E+07 4.05E+06 1.45E+06 1.64E+07 1.03E+06 0.OOE+00 O.OOE+00 TE-129M 7.43E+05 2.36E+07 4.69E+06 1.75E+06 1.96E+07 1.61E+06 0.OOE+00 0.OOE+00 1-131 1.91E+08 8.78E+07 2.33E+08 3.33E+08 5.71E+08 1.09E+11 O.OOE+00 O.OOE+00 1-132 1.23E-01 6.61E-02 1.32E-01 3.52E-01 5.61E-01 1.23E+01 0.OOE+00 0.OOE+00 1-133 1.68E+06 4.95E+06 3.17E+06 5.51E+06 9.61E+06 8.10E+08 O.OOE+00 O.OOE+00 1-135 1.08E+04 3.32E+04 1.12E+04 2.94E+04 4.71E+04 1.94E+06 0.OOE+00 O.OOE+00 CS-134 2.01E+10 4.31E+08 1.03E+10 2.46E+10 7.97E+09 0.OOE+00 2.65E+09 0.OOE+00 CS-136 1.42E+09 2.24E+08 4.99E+08 1.97E+09 1.10E+09 O.OOE+00 1.50E+08 O.OOE+00 CS-137 1.27E+10 3.74E+08 1.41E+10 1.93E+10 6.56E+09 0.OOE+00 2.18E+09 0.OOE+00 BA-140 1.35E+05 4.23E+06 2.06E+06 2.58E+03 8.78E+02 0.OOE+00 1.48E+03 0.OOE+00 CE-141 2.68E+01 9.03E+05 3.49E+02 2.36E+02 1.10E+02 0.OOE+00 0.OOE+00 O.OOE+00 CE-144 1.38E+03 8.71E+06 2.58E+04 1.08E+04 6.39E+03 O.OOE+00 O.OOE+00 0.OOE+00 HF-181 8.02E+01 5.26E+04 7.09E+02 3.99E+00 3.34E+00 2.54E+00 O.OOE+00 0.OOE+00 AM-241 1.52E+05 2.09E+05 2.12E+06 1.99E+06 1.15E+06 O.OOE+00 O.OOE+00 0.OOE+00

R Values in units of mrem/yr per pCi/m3 for inhalation and tritium, and in units of m2-mrem/yr per pCi/sec for all others.

ODCM (BSEP) 3-54 Rev. 37 I

TABLE 3.3-13 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Goat Milk AGE GROUP = Teen Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 2.04E+03 2.04E+03 0.OOE+00 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2.04E+03 P-32 9.60E+08 2.08E+09 2.48E+10 1.53E+09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CR-51 3.63E+03 6.1OE+05 0.00E+00 0.OOE+00 7.95E+02 2.02E+03 5.18E+03 0.OOE+00 MN-54 2.03E+05 2.1OE+06 O.00E+00 1.02E+06 3.05E+05 0.OOE+00 0.OOE+00 0.OOE+00 FE-59 3.63E+05 2.22E+06 4.03E+05 9.40E+05 0.OOE+00 0.OOE+00 2.96E+05 0.OOE+00 CO-58 1.30E+06 7.80E+06 0.OOE+00 5.66E+05 O.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 CO-60 4.66E+06 2.69E+07 0.OOE+00 2.07E+06 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 ZN-65 2.86E+08 2.60E+08 1.77E+08 6.13E+08 3.93E+08 0.00E+00 0.OOE+00 0.00E+00 RB-86 1.66E+08 5.24E+07 O.OOE+00 3.54E+08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 SR-89 9.65E+07 4.01 E+08 3.37E+09 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 SR-90 2.27E+10 2.58E+09 9.18E+10 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Y-91 3.02E+01 4.62E+05 1.13E+03 O.00E+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 ZR-95 2.56E+01 8.59E+04 1.18E+02 3.72E+01 5.47E+01 0.OOE+00 O.OOE+00 0.00E+00 NB-95 3.09E+03 2.40E+07 1.01 E+04 5.62E+03 5.45E+03 0.OOE+00 0.OOE+00 0.OOE+00 RU-103 5.58E+01 1.09E+04 1.30E+02 0.OOE+00 4.60E+02 0.00E+00 0.00E+00 0.OOE+00 RU-106 3.51E+02 1.34E+05 2.79E+03 O.OOE+00 5.38E+03 0.OOE+00 O.OOE+00 0.00E+00 AG-110M 4.24E+06 1.96E+09 7.37E+06 6.97E+06 1.33E+07 0.OOE+00 0.00E+00 0.OOE+00 SN-113 2.28E+05 2.58E+06 2.15E+05 9.06E+03 6.37E+03 2.97E+03 0.OOE+00 0.OOE+00 TE-127M 8.87E+05 1.86E+07 7.46E+06 2.65E+06 3.02E+07 1.77E+06 0.OOE+00 0.OOE+00 TE-129M 1.36E+06 3.22E+07 8.58E+06 3.19E+06 3.59E+07 2.77E+06 0.OOE+00 O.OOE+00 1-131 3.18E+08 1.17E+08 4.22E+08 5.91E+08 1.02E+09 1.73E+11 0.OOE+00 0.OOE+00 1-132 2.19E-01 2.66E-01 2.33E-01 6.11E-01 9.62E-01 2.06E+01 0.OOE+00 0.OOE+00 1-133 2.99E+06 7.43E+06 5.79E+06 9.81E+06 1.72E+07 1.37E+09 0.OOE+00 O.OOE+00 1-135 1.90E+04 5.63E+04 1.99E+04 5.13E+04 8.1OE+04 3.30E+06 0.OOE+00 O.OOE+00 CS-134 1.96E+10 5.26E+08 1.80E+10 4.23E+10 1.34E+10 O.OOE+00 5.13E+09 0.OOE+00 CS-136 2.25E+09 2.71E+08 8.50E+08 3.34E+09 1.82E+09 0.OOE+00 2.87E+08 0.OOE+00 CS-137 1.19E+10 4.85E+08 2.56E+10 3.41E+10 1.16E+10 0.OOE+00 4.51E+09 0.OOE+00 BA-140 2.39E+05 5.72E+06 3.71E+06 4.55E+03 1.54E+03 0.OOE+00 3.06E+03 0.OOE+00 CE-141 4.91E+01 1.22E+06 6.40E+02 4.27E+02 2.01E+02 0.OOE+00 0.OOE+00 0.OOE+00 CE-144 2.55E+03 1.19E+07 4.74E+04 1.96E+04 1.17E+04 O.OOE+00 0.OOE+00 O.OOE+00 HF-181 1.41E+02 6.34E+04 1.27E+03 6.97E+00 5.81E+00 4.26E+00 0.OOE+00 O.OOE+00 AM-241 2.09E+05 2.86E+05 2.90E+06 2.74E+06 1.57E+06 0.OOE+00 0.OOE+00 O.OOE+00

R Values in units of mrem/yr per pCi/m 3 for inhalation and tritium, and in units of m2-mrem/yr per pCi/sec for all others.

ODCM (BSEP) 3-55 Rev. 37

TABLE 3.3-14 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Goat Milk AGE GROUP = Child Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 3.23E+03 3.23E+03 0.OOE+00 3.23E+03 3.23E+03 3.23E+03 3.23E+03 3.23E+03 P-32 2.35E+09 1.69E+09 6.11E+10 2.86E+09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CR-51 7.40E+03 3.93E+05 O.OOE+00 0.OOE+00 1.12E+03 4.11E+03 7.50E+03 0.OOE+00 MN-54 4.07E+05 1.28E+06 0.OOE+00 1.53E+06 4.29E+05 0.OOE+00 0.OOE+00 O.OOE+00 FE-59 7.52E+05 1.57E+06 9.34E+05 1.51 E+06 O.OOE+00 0.OOE+00 4.38E+05 0.OOE+00 CO-58 2.65E+06 5.05E+06 0.OOE+00 8.65E+05 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 CO-60 9.48E+06 1.78E+07 0.OOE+00 3.21E+06 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 ZN-65 5.74E+08 1.62E+08 3.47E+08 9.24E+08 5.82E+08 0.OOE+00 0.OOE+00 0.OOE+00 RB-86 4.04E+08 4.22E+07 0.OOE+00 6.57E+08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 SR-89 2.38E+08 3.23E+08 8.34E+09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 SR-90 3.93E+10 2.09E+09 1.55E+11 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Y-91 7.45E+01 3.71E+05 2.79E+03 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 ZR-95 5.36E+01 6.28E+04 2.74E+02 6.02E+01 8.62E+01 0.OOE+00 O.OOE+00 O.OOE+00 NB-95 6.37E+03 1.65E+07 2.29E+04 8.91E+03 8.37E+03 O.OOE+00 0.OOE+00 0.OOE+00 RU-103 1.19E+02 7.98E+03 3.09E+02 0.OOE+00 7.77E+02 0.OOE+00 0.OOE+00 O.OOE+00 RU-1 06 8.56E+02 1.07E+05 6.86E+03 0.OOE+00 9.27E+03 0.OOE+00 0.OOE+00 O.OOE+00 AG-110M 8.63E+06 1.28E+09 1.60E+07 1.08E+07 2.01E+07 0.OOE+00 0.OOE+00 0.OOE+00 SN-113 4.61E+05 1.69E+06 4.22E+05 1.36E+04 9.38E+03 5.59E+03 O.OOE+00 O.OOE+00 TE-127M 2.18E+06 1.49E+07 1.84E+07 4.95E+06 5.24E+07 4.40E+06 0.OOE+00 0.OOE+00 TE-129M 3.28E+06 2.58E+07 2.12E+07 5.91E+06 6.21E+07 6.82E+06 0.OOE+00 0.OOE+00 1-131 5.85E+08 9.17E+07 1.02E+09 1.03E+09 1.69E+09 3.41E+11 0.OOE+00 0.OOE+00 1-132 4.67E-01 1.19E+00 5.52E-01 1.01E+00 1.55E+00 4.71E+01 0.OOE+00 0.OOE+00 1-133 6.58E+06 7.OOE+06 1.41E+07 1.74E+07 2.90E+07 3.23E+09 0.OOE+00 0.OOE+00 1-135 4.01E+04 6.47E+04 4.72E+04 8.49E+04 1.30E+05 7.52E+06 0.OOE+O0 0.OOE+00 CS-134 1.43E+10 3.67E+08 4.14E+10 6.80E+10 2.11E+10 0.OOE+00 7.56E+09 0.OOE+00 CS-136 3.41E+09 1.85E+08 1.92E+09 5.27E+09 2.81E+09 0.OOE+00 4.19E+08 0.OOE+00 CS-137 8.72E+09 3.70E+08 6.17E+10 5.91E+10 1.93E+10 O.OOE+00 6.93E+09 0.OOE+00 BA-140 5.23E+05 4.55E+06 8.96E+06 7.85E+03 2.56E+03 0.OOE+00 4.68E+03 0.OOE+00 CE-141 1.17E+02 9.81E+05 1.53E+03 7.36E+02 3.45E+02 O.OOE+00 0.OOE+00 0.OOE+00 CE-144 6.24E+03 9.55E+06 1.17E+05 3.66E+04 2.03E+04 O.OOE+00 0.OOE+00 0.OOE+00 HF-181 3.04E+02 4.99E+04 3.02E+03 1.17E+01 9.43E+00 9.89E+00 O.OOE+00 O.OOE+00 AM-241 3.06E+05 2.29E+05 4.08E+06 3.50E+06 1.87E+06 0.OOE+00 0.OOE+00 0.OOE+00 3

R Values in units of mrem/yr per gCi/m for inhalation and tritium, and in units of m -mrem/yr per pCi/sec for all others.

ODCM (BSEP) 3-56 Rev. 37 I

TABLE 3.3-15 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Goat Milk AGE GROUP = Infant Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 4.90E+03 4.90E+03 O.OOE+00 4.90E+03 4.90E+03 4.90E+03 4.90E+03 4.90E+03 P-32 4.88E+09 1.70E+09 1.26E+1 1 7.40E+09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CR-51 1.17E+04 3.42E+05 O.OOE+00 O.OOE+00 1.67E+03 7.65E+03 1.49E+04 O.OOE+00 MN-54 6.45E+05 1.04E+06 O.OOE+00 2.84E+06 6.30E+05 O.OOE+00 O.OOE+00 O.OOE+00 FE-59 1.20E+06 1.45E+06 1.74E+06 3.04E+06 O.OOE+00 O.OOE+00 9.OOE+05 O.OOE+00 CO-58 4.31E+06 4.31E+06 O.OOE+00 1.73E+06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CO-60 1.55E+07 1.56E+07 O.OOE+00 6.56E+06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 ZN-65 7.36E+08 1.35E+09 4.66E+08 1.60E+09 7.74E+08 O.OOE+00 O.OOE+00 O.OOE+00 RB-86 8.23E+08 4.26E+07 O.OOE+00 1.67E+09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-89 4.55E+08 3.26E+08 1.59E+10 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-90 4.30E+10 2.11E+09 1.69E+11 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-91 1.39E+02 3.75E+05 5.23E+03 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 ZR-95 8.41E+01 5.90E+04 4.85E+02 1.19E+02 1.28E+02 O.OOE+00 O.OOE+00 O.OOE+00 NB-95 1.02E+04 1.48E+07 4.27E+04 1.76E+04 1.26E+04 O.OOE+00 O.OOE+00 O.OOE+00 RU-103 2.09E+02 7.60E+03 6.25E+02 O.OOE+00 1.30E+03 O.OOE+00 O.OOE+00 O.OOE+00 RU-106 1.77E+03 1.07E+05 1.41E+04 O.OOE+00 1.67E+04 O.OOE+00 O.OOE+00 O.OOE+00 AG-11OM 1.43E+07 1.12E+09 2.95E+07 2.16E+07 3.08E+07 O.OOE+00 O.OOE+00 O.OOE+00 SN-113 6.66E+05 1.37E+06 6.46E+05 2.45E+04 1.32E+04 9.34E+03 O.OOE+00 O.OOE+00 TE-127M 4.51E+06 1.50E+07 3.72E+07 1.23E+07 9.16E+07 1.08E+07 O.OOE+00 O.OOE+00 TE-129M 6.69E+06 2.59E+07 4.34E+07 1.49E+07 1.09E+08 1.67E+07 O.OOE+00 O.OOE+00 1-131 1.11E+09 8.99E+07 2.14E+09 2.52E+09 2.94E+09 8.28E+11 O.OOE+00 O.OOE+00 1-132 8.28E-01 1.88E+00 1.15E+00 2.33E+00 2.59E+00 1.09E+02 O.OOE+00 O.OOE+00 1-133 1.27E+07 7.31E+06 2.97E+07 4.32E+07 5.08E+07 7.86E+09 O.OOE+00 O.OOE+00 1-135 7.11E+04 7.06E+04 9.81E+04 1.95E+05 2.17E+05 1.75E+07 O.OOE+00 O.OOE+00 CS-134 1.26E+10 3.38E+08 6.68E+10 1.25E+11 3.21E+10 O.OOE+00 1.31E+10 O.OOE+00 CS-136 4.11E+09 1.67E+08 3.75E+09 1.10E+10 4.39E+09 O.OOE+00 8.98E+08 O.OOE+00 CS-137 8.17E+09 3.61E+08 9.85E+10 1.15E+11 3.10E+10 O.OOE+00 1.25E+10 O.OOE+00 BA-140 9.50E+05 4.53E+06 1.84E+07 1.84E+04 4.38E+03 O.OOE+00 1.13E+04 O.OOE+00 CE-141 2.24E+02 9.85E+05 3.13E+03 1.91E+03 5.88E+02 O.OOE+00 O.OOE+00 O.OOE+00 CE-144 9.39E+03 9.61E+06 1.67E+05 6.86E+04 2.77E+04 O.OOE+00 O.OOE+00 O.OOE+00 HF-181 5.08E+02 4.72E+04 5.74E+03 2.71E+01 1.58E+01 2.30E+01 O.OOE+00 O.OOE+00 AM-241 3.26E+05 2.30E+05 4.38E+06 3.80E+06 1.97E+06 O.OOE+00 O.OOE+00 O.OOE+00 3

R Values in units of mrem/yr per giCi/m for inhalation and tritium, and in units of m2-mrem/yr per giCi/sec for all others.

ODCM (BSEP) 3-57 Rev. 37

TABLE 3.3-16 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Inhalation AGE GROUP = Adult Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 1.26E+03 1.26E+03 0.OOE+00 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 P-32 5.OOE+04 8.63E+04 1.32E+06 7.70E+04 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CR-51 9.99E+01 3.32E+03 O.OOE+00 0.OOE+00 2.28E+01 5.94E+01 1.44E+04 O.OOE+00 MN-54 6.29E+03 7.72E+04 0.OOE+00 3.95E+04 9.83E+03 O.OOE+00 1.40E+06 0.OOE+00 FE-59 1.05E+04 1.88E+05 1.17E+04 2.77E+04 O.OOE+00 0.OOE+00 1.01E+06 0.OOE+00 CO-58 2.07E+03 1.06E+05 0.OOE+00 1.58E+03 0.OOE+00 O.OOE+00 9.27E+05 0.OOE+00 CO-60 1.48E+04 2.84E+05 O.OOE+00 1.15E+04 0.OOE+00 O.OOE+00 5.96E+06 0.OOE+00 ZN-65 4.65E+04 5.34E+04 3.24E+04 1.03E+05 6.89E+04 0.OOE+00 8.63E+05 O.OOE+00 RB-86 5.89E+04 1.66E+04 0.OOE+00 1.35E+05 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-89 8.71E+03 3.49E+05 3.04E+05 0.OOE+00 0.OOE+00 0.OOE+00 1.40E+06 0.OOE+00 SR-90 6.09E+06 7.21E+05 9.91E+07 0.OOE+00 0.OOE+00 O.OOE+00 9.59E+06 0.OOE+00 Y-91 1.24E+04 3.84E+05 4.62E+05 O.OOE+00 0.OOE+00 0.OOE+00 1.70E+06 0.OOE+00 ZR-95 2.32E+04 1.50E+05 1.07E+05 3.44E+04 5.41E+04 O.OOE+00 1.77E+06 O.OOE+00 NB-95 4.20E+03 1.04E+05 1.41 E+04 7.80E+03 7.72E+03 O.OOE+00 5.04E+05 0.OOE+00 RU-103 6.57E+02 1.1OE+05 1.53E+03 0.OOE+00 5.82E+03 0.OOE+00 5.04E+05 0.OOE+00 RU-106 8.71E+03 9.11E+05 6.90E+04 O.OOE+00 1.33E+05 O.OOE+00 9.35E+06 0.OOE+00 AG-11iM 5.94E+03 3.02E+05 1.08E+04 9.99E+03 1.97E+04 O.OOE+00 4.63E+06 0.OOE+00 SN-113 6.48E+03 2.48E+04 6.87E+03 2.66E+02 1.97E+02 9.33E+01 2.99E+05 0.OOE+00 TE-127M 1.57E+03 1.49E+05 1.26E+04 5.76E+03 4.57E+04 3.28E+03 9.59E+05 0.OOE+00 TE-129M 1.58E+03 3.83E+05 9.75E+03 4.67E+03 3.65E+04 3.44E+03 1.16E+06 0.OOE+00 1-131 2.05E+04 6.27E+03 2.52E+04 3.57E+04 6.12E+04 1.19E+07 0.OOE+00 0.OOE+00 1-132 1.16E+03 4.06E 02 1.16E+03 3.25E+03 5.18E+03 1.14E+05 0.OOE+00 0.OOE+00 1-133 4.51E+03 8.87E+03 8.63E+03 1.48E+04 2.58E+04 2.15E+06 0.OOE+00 0.OOE+00 1-135 2.56E+03 5.24E+03 2.68E+03 6.97E+03 1.11E+04 4.47E+05 O.OOE+00 O.OOE+00 CS-134 7.27E+05 1.04E+04 3.72E+05 8.47E+05 2.87E+05 O.OOE+00 9.75E+04 0.OOE+00 CS-136 1.1OE+05 1.17E+04 3.90E+04 1.46E+05 8.55E+04 0.OOE+00 1.20E+04 O.OOE+00 CS-137 4.27E+05 8.39E+03 4.78E+05 6.20E+05 2.22E+05 0.OOE+00 7.51E+04 O.OOE+00 BA-140 2.56E+03 2.18E+05 3.90E+04 4.90E+01 1.67E+01 O.OOE+00 1.27E+06 0.00E+00 CE-141 1.53E+03 1.20E+05 1.99E+04 1.35E+04 6.25E+03 O.OOE+00 3.61E+05 0.OOE+00 CE-144 1.84E+05 8.15E+05 3.43E+06 1.43E+06 8.47E+05 0.OOE+00 7.76E+06 0.OOE+00 HF-181 5.16E+03 1.29E+05 4.56E+04 2.57E+02 2.15E+02 1.63E+02 5.99E+05 0.OOE+00 AM-241 5.37E+08 3.68E+05 1.34E+10 9.04E+09 4.03E+09 O.OOE+00 4.85E+08 O.OOE+00

R Values in units of mrem/yr per pCi/m 3 for inhalation and tritium, and in units of mZ-mrem/yr per pCi/sec for all others.

ODCM (BSEP) 3-58 Rev. 37 1

TABLE 3.3-17 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Inhalation AGE GROUP = Teen Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 1.27E+03 1.27E+03 O.OOE+00 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 P-32 7.15E+04 9.27E+04 1.89E+06 1.09E+05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CR-51 1.35E+02 3.OOE+03 O.OOE+00 O.OOE+00 3.07E+01 7.49E+01 2.09E+04 O.OOE+00 MN-54 8.39E+03 6.67E+04 O.OOE+00 5.10E+04 1.27E+04 O.OOE+00 1.98E+06 O.OOE+00 FE-59 1.43E+04 1.78E+05 1.59E+04 3.69E+04 O.OOE+00 O.OOE+00 1.53E+06 O.OOE+00 CO-58 2.77E+03 9.51E+04 O.OOE+00 2.07E+03 O.OOE+00 O.OOE+00 1.34E+06 O.OOE+00 CO-60 1.98E+04 2.59E+05 O.OOE+00 1.51E+04 O.OOE+00 O.OOE+00 8.71E+06 O.OOE+00 ZN-65 6.23E+04 4.66E+04 3.85E+04 1.33E+05 8.63E+04 O.OOE+00 1.24E+06 O.OOE+00 RB-86 8.39E+04 1.77E+04 O.OOE+00 1.90E+05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-89 1.25E+04 3.71E+05 4.34E+05 O.OOE+00 O.OOE+00 O.OOE+00 2.41E+06 O.OOE+00 SR-90 6.67E+06 7.64E+05 1.08E+08 O.OOE+00 O.OOE+00 O.OOE+00 1.65E+07 O.OOE+00 Y-91 1.77E+04 4.08E+05 6.60E+05 O.OOE+00 O.OOE+00 O.OOE+00 2.93E+06 O.OOE+00 ZR-95 3.15E+04 1.49E+05 1.45E+05 4.58E+04 6.73E+04 O.OOE+00 2.68E+06 O.OOE+00 NB-95 5.66E+03 9.67E+04 1.85E+04 1.03E+04 9.99E+03 O.OOE+00 7.50E+05 O.OOE+00 RU-103 8.95E+02 1.09E+05 2.1OE+03 O.OOE+00 7.42E+03 O.OOE+00 7.82E+05 O.OOE+00 RU-106 1.24E+04 9.59E+05 9.83E+04 O.OOE+00 1.90E+05 O.OOE+00 1.61E+07 O.OOE+00 AG-11iM 7.98E+03 2.72E+05 1.38E+04 1.31E+04 2.50E+04 O.OOE+00 6.74E+06 O.OOE+00 SN-113 8.69E+03 2.03E+04 8.19E+03 3.45E+02 2.46E+02 1.13E+02 4.27E+05 O.OOE+00 TE-127M 2.18E+03 1.59E+05 1.80E+04 8.15E+03 6.53E+04 4.38E+03 1.65E+06 O.OOE+00 TE-129M 2.24E+03 4.04E+05 1.39E+04 6.57E+03 5.18E+04 4.57E+03 1.97E+06 O.OOE+00 1-131 2.64E+04 6.48E+03 3.54E+04 4.90E+04 8.39E+04 1.46E+07 O.OOE+00 O.OOE+00 1-132 1.57E+03 1.27E+03 1.59E+03 4.37E+03 6.91E+03 1.51E+05 O.OOE+00 O.OOE+00 1-133 6.21E+03 1.03E+04 1.21E+04 2.05E+04 3.59E+04 2.92E+06 O.OOE+00 O.OOE+00 1-135 3.48E+03 6.94E+03 3.69E+03 9.43E+03 1.49E+04 6.20E+05 O.OOE+00 O.OOE+00 CS-134 5.48E+05 9.75E+03 5.02E+05 1.13E+06 3.75E+05 O.OOE+00 1.46E+05 O.OOE+00 CS-136 1.37E+05 1.09E+04 5.14E+04 1.93E+05 1.1OE+05 O.OOE+00 1.77E+04 O.OOE+00 CS-137 3.11E+05 8.48E+03 6.69E+05 8.47E+05 3.04E+05 O.OOE+00 1.21E+05 O.OOE+00 BA-140 3.51E+03 2.28E+05 5.46E+04 6.69E+01 2.28E+01 O.OOE+00 2.03E+06 O.OOE+00 CE-141 2.16E+03 1.26E+05 2.84E+04 1.89E+04 8.87E+03 O.OOE+00 6.13E+05 O.OOE+00 CE-144 2.62E+05 8.63E+05 4.88E+06 2.02E+06 1.21E+06 O.OOE+00 1.33E+07 O.OOE+00 HF-181 7.05E+03 1.21E+05 6.32E+04 3.48E+02 2.90E+02 2.12E+02 9.39E+05 O.OOE+00 AM-241 5.68E+08 3.90E+05 1.42E+10 9.60E+09 4.26E+09 O.OOE+00 8.40E+08 O.OOE+00

R Values in units of mrem/yr per giCi/m3 for inhalation and tritium, and in units of m -mrem/yr per iiCi/sec for all others.

ODCM (BSEP) 3-59 Rev. 37 I

TABLE 3.3-18 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Inhalation AGE GROUP = Child Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 1.12E+03 1.12E+03 O.OOE+00 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 P-32 9.86E+04 4.21E+04 2.60E+06 1.14E+05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CR-51 1.54E+02 1.08E+03 O.OOE+00 O.OOE+00 2.43E+01 8.53E+01 1.70E+04 O.OOE+00 MN-54 9.50E+03 2.29E+04 O.OOE+00 4.29E+04 1.OOE+04 O.OOE+00 1.57E+06 O.OOE+00 FE-59 1.67E+04 7.06E+04 2.07E+04 3.34E+04 O.OOE+00 O.OOE+00 1.27E+06 O.OOE+00 CO-58 3.16E+03 3.43E+04 O.OOE+00 1.77E+03 O.OOE+00 O.OOE+00 1.1OE+06 O.OOE+00 CO-60 2.26E+04 9.61E+04 O.OOE+00 1.31E+04 O.OOE+00 O.OOE+00 7.06E+06 O.OOE+00 ZN-65 7.02E+04 1.63E+04 4.25E+04 1.13E+05 7.13E+04 O.OOE+00 9.94E+05 O.OOE+00 RB-86 1.14E+05 7.98E+03 O.OOE+00 1.98E+05 O.OE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-89 1.72E+04 1.67E+05 5.99E+05 O.OOE+00 O.OOE+00 O.OOE+00 2.15E+06 O.OOE+00 SR-90 6.43E+06 3.43E+05 1.01E+08 O.OOE+00 O.OOE+00 O.OOE+00 1.47E+07 O.OOE+00 Y-91 2.43E+04 1.84E+05 9.13E+05 O.OOE+00 O.OOE+00 O.OOE+00 2.62E+06 O.OOE+00 ZR-95 3.69E+04 6.1OE+04 1.90E+05 4.17E+04 5.95E+04 O.OOE+00 2.23E+06 O.OOE+00 NB-95 6.54E+03 3.69E+04 2.35E+04 9.16E+03 8.61E+03 O.OOE+00 6.13E+05 O.OOE+00 RU-103 1.07E+03 4.47E+04 2.79E+03 O.OOE+00 7.02E+03 O.OOE+00 6.61E+05 O.OOE+00 RU-106 1.69E+04 4.29E+05 1.36E+05 O.OOE+00 1.84E+05 O.OOE+00 1.43E+07 O.OOE+00 AG-110M 9.13E+03 1.OOE+05 1.68E+04 1.14E+04 2.12E+04 O.OOE+00 5.47E+06 O.OOE+00 SN-113 9.84E+03 7.45E+03 9.01E+03 2.91E+02 2.03E+02 1.19E+02 3.40E+05 O.OOE+00 TE-127M 3.01E+03 7.13E+04 2.48E+04 8.53E+03 6.35E+04 6.06E+03 1.48E+06 O.OOE+00 TE-129M 3.04E+03 1.81E+05 1.92E+04 6.84E+03 5.02E+04 6.32E+03 1.76E+06 O.OOE+00 1-131 2.72E+04 2.84E+03 4.80E+04 4.80E+04 7.87E+04 1.62E+07 O.OOE+00 O.OOE+00 1-132 1.87E+03 3.20E+03 2.11E+03 4.06E+03 6.24E+03 1.93E+05 O.OOE+00 O.OOE+00 1-133 7.68E+03 5.47E+03 1.66E+04 2.03E+04 3.37E+04 3.84E+06 O.OOE+00 O.OOE+00 1-135 4.14E+03 4.43E+03 4.91E+03 8.72E+03 1.34E+04 7.91E+05 O.OOE+00 O.OOE+00 CS-134 2.24E+05 3.84E+03 6.50E+05 1.01E+06 3.30E+05 O.OOE+00 1.21E+05 O.OOE+00 CS-136 1.16E+05 4.17E+03 6.50E+04 1.71E+05 9.53E+04 O.OOE+00 1.45E+04 O.OOE+00 CS-137 1.28E+05 3.61E+03 9.05E+05 8.24E+05 2.82E+05 O.OOE+00 1.04E+05 O.OOE+00 BA-140 4.32E+03 1.02E+05 7.39E+04 6.47E+01 2.11E+01 O.OOE+00 1.74E+06 O.OOE+00 CE-141 2.89E+03 5.65E+04 3.92E+04 1.95E+04 8.53E+03 O.OOE+00 5.43E+05 O.OOE+00 CE-144 3.61E+05 3.88E+05 6.76E+06 2.11E+06 1.17E+06 O.OOE+00 1.19E+07 O.OOE+00 HF-181 8.50E+03 5.31E+04 8.44E+04 3.28E+02 2.64E+02 2.76E+02 7.95E+05 O.OOE+00 AM-241 4.59E+08 1.75E+05 1.10E+10 6.81E+09 2.82E+09 O.OOE+00 7.47E+08 O.OOE+00

R Values in units of mrem/yr per jiCi/m 3 for inhalation and tritium, and in units of mZ-mrem/yr per giCi/sec for all others.

ODCM (BSEP) 3-60 Rev. 37 I

TABLE 3.3-19 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT*

PATHWAY = Inhalation AGE GROUP = Infant Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 6.46E+02 6.46E+02 0.OOE+00 6.46E+02 6.46E+02 6.46E+02 6.46E+02 6.46E+02 P-32 7.73E+04 1.61E+04 2.03E+06 1.12E+05 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CR-51 8.93E+01 3.56E+02 0.OOE+00 0.OOE+00 1.32E+01 5.75E+01 1.28E+04 0.OOE+00 MN-54 4.98E+03 7.05E+03 0.OOE+00 2.53E+04 4.98E+03 0.OOE+00 9.98E+05 0.OOE+00 FE-59 9.46E+03 2.47E+04 1.35E+04 2.35E+04 0.OOE+00 O.OOE+00 1.01 E+06 0.OOE+00 CO-58 1.82E+03 1.11E+04 0.OOE+00 1.22E+03 O.OOE+00 O.OOE+00 7.76E+05 0.OOE+00 CO-60 1.18E+04 3.19E+04 0.OOE+00 8.01E+03 O.OOE+00 0.OOE+00 4.50E+06 O.OOE+00 ZN-65 3.1OE+04 5.13E+04 1.93E+04 6.25E+04 3.24E+04 0.OOE+00 6.46E+05 0.OOE+00 RB-86 8.81E+04 3.03E+03 0.OOE+00 1.90E+05 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 SR-89 1.14E+04 6.39E+04 3.97E+05 0.OOE+00 0.OOE+00 0.OOE+00 2.03E+06 0.OOE+00 SR-90 2.59E+06 1.31E+05 4.08E+07 0.OOE+00 0.OOE+00 0.OOE+00 1.12E+07 0.OOE+00 Y-91 1.57E+04 7.02E+04 5.87E+05 0.OOE+00 0.OOE+00 0.OOE+00 2.45E+06 0.OOE+00 ZR-95 2.03E+04 2.17E+04 1.15E+05 2.78E+04 3.1OE+04 0.OOE+00 1.75E+06 0.OOE+00 NB-95 3.77E+03 1.27E+04 1.57E+04 6.42E+03 4.71E+03 0.OOE+00 4.78E+05 0.OOE+00 RU-103 6.78E+02 1.61E+04 2.01E+03 0.OOE+00 4.24E+03 O.OOE+00 5.51E+05 0.OOE+00 RU-106 1.09E+04 1.64E+05 8.67E+04 0.OOE+00 1.06E+05 0.OOE+00 1.15E+07 0.OOE+00 AG-110M 4.99E+03 3.30E+04 9.97E+03 7.21E+03 1.09E+04 0.OOE+00 3.66E+06 0.OOE+00 SN-113 4.89E+03 2.29E+03 4.68E+03 1.74E+02 9.94E+01 6.73E+01 2.30E+05 O.OOE+00 TE-127M 2.07E+03 2.73E+04 1.66E+04 6.89E+03 3.75E+04 4.86E+03 1.31E+06 0.OOE+00 TE-129M 2.22E+03 6.89E+04 1.41E+04 6.08E+03 3.17E+04 5.47E+03 1.68E+06 O.OOE+00 1-131 1.96E+04 1.06E+03 3.79E+04 4.43E+04 5.17E+04 1.48E+07 0.OOE+00 O.OOE+00 1-132 1.26E+03 1.90E+03 1.69E+03 3.54E+03 3.94E+03 1.69E+05 0.OOE+00 0.OOE+00 1-133 5.59E+03 2.15E+03 1.32E+04 1.92E+04 2.24E+04 3.55E+06 0.OOE+00 0.OOE+00 1-135 2.77E+03 1.83E+03 3.86E+03 7.59E+03 8.46E+03 6.95E+05 O.OOE+00 O.OOE+00 CS-134 7.44E+04 1.33E+03 3.96E+05 7.02E+05 1.90E+05 O.OOE+00 7.95E+04 0.OOE+00 CS-136 5.28E+04 1.43E+03 4.82E+04 1.34E+05 5.63E+04 0.OOE+00 1.17E+04 0.OOE+00 CS-137 4.54E+04 1.33E+03 5.48E+05 6.11E+05 1.72E+05 O.OOE+00 7.12E+04 O.OOE+00 BA-140 2.89E+03 3.83E+04 5.59E+04 5.59E+01 1.34E+01 O.OOE+00 1.59E+06 0.OOE+00 CE-141 1.99E+03 2.15E+04 2.77E+04 1.66E+04 5.24E+03 0.OOE+00 5.16E+05 0.OOE+00 CE-144 1.76E+05 1.48E+05 3.19E+06 1.21E+06 5.37E+05 O.OOE+00 9.83E+06 0.OOE+00 HF-181 5.05E+03 1.90E+04 5.65E+04 2.66E+02 1.59E+02 2.26E+02 6.73E+05 0.OOE+00 AM-241 1.83E+08 6.69E+04 4.41E+09 2.73E+09 1.11E+09 0.OOE+00 5.68E+08 0.OOE+00

R Values in units of mrem/yr per jiCi/m3 for inhalation and tritium, and in units of m2-mrem/yr per jiCi/sec for all others.

ODCM (BSEP) 3-61 Rev. 37 1

3.3.3 Carbon-14 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 Steam Electric Plant (BSEP) 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 BSEP to the point that C-14 is now considered a principal radionuclide. In Boiling Water Reactors (BWRs), such as BSEP, 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.

The C-14 curies released may be determined by any of the following methodologies:

a. Use BSEP's Updated Final Safety Analysis Report (UFSAR) C-14 release rate of 9.5 Ci/yr per unit assuming 80% plant capacity factor (292 Effective Full Power Days (EFPD)) and scale it using actual EFPD for each unit. The curies per year will be allotted based on ODCM allocation fractions of 0.40 for the Stack, 0.20 for each Reactor Building, and 0.10 for each Turbine Building and attributed to each quarter for reporting in the Annual Radioactive Effluent Release Report.

b. Use of historical values (with power up-rate adjustment) as indicated in NUREG/CR-4245 (1985).

c. Use of actual sample data obtained during the reporting period.

d. Use of Electric Power Research Institute's, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents" methodology.

The Annual Land Use Census will be used to determine the critical receptor. Typically, there are no meat or milk pathways within 5 miles of BSEP, therefore, unless other pathways are identified, the reported dose to the individual will be determined from inhalation and vegetable consumption. Regulatory Guide 1.109 Revision 1 methodology will be used to determine the dose. The dose rate and subsequent dose to an individual from C-14 intake depends on the specific activity of the food from each source and the amount of the ingested C-14 which is retained over the period under consideration. Atmospheric Carbon Dioxide (C02) is incorporated in cellular material by the photosynthetic action of plants. Plants and grasses equilibrate with the C-14 C02 of the air. The portion of the curies released that is determined to be carbon dioxide is 90%. This value is based on conservative historical values from NUREG/CR-4245 (1985). The growing season may be utilized and can be derived from the North Carolina Cooperative Extension Service, current data available indicates that average growing season is 238 days. BSEP gaseous releases are continuous and no credit is taken for releases in non-daylight hours where photosynthetic action of plants is minimal or non-existent.

Carbon-14 releases are typically tabulated at the end of the yearly reporting period and included in the Annual Radioactive Effluent Release Report, however, special circumstances as determined by E&C Management may require that C-14 releases be assessed on a more frequent basis. Once the C-14 dose is determined it is included in the Annual Radioactive Effluent Release Report.

ODCM (BSEP) 3-62 Rev. 37 1

1. Annual Dose from Inhalation of Carbon-14 in Air

a. The annual average airborne concentration of C-14 may be determined as follows:

Xc = (3.17 x 104) (Qc) - (3.3-21)

Where:

xc is the annual average concentration of C-14 in air, pCi/m 3 ;

3.17 x 104 is the number of pCi/Ci divided by the number of sec/year; Qc is the release rate of C-14 to the atmosphere, in Ci/yr; and For Reactor and Turbine Buildings using methodology a. listed under Section 3.3.3 to determine the C-14 curies released:

CiEFPD Oc= (C for applicable release point ED for applicable dt] Unit For Stack using methodology a. listed under Section 3.3.3 to determine the C-14 curies released:

xis J(292 Qc = (Ci) (EFPD of Unit I and Unit2

~yr days+ 292 days the annual average atmosphere dispersion factor, in sec/n 3 .

b. The annual dose associated with inhalation of 0-14 may be determined as follows:

Dc =[(BR)a](Xc)(DFAo a) (3.3-22) ja j Where:

Dc Ja is the C-14 annual dose to organ j of an individual in age group a, in mrem/yr; (BR)a is the breathing rate of the receptor of age group a, in m3/yr, reference ODCM Section C.2.1 for these values; X, is the annual average concentration of C-14 in air, in pCi/m 3 .

DFAcja is the C-14 inhalation dose factor for organj, and age group a, in mrem/pCi, reference Table 3.3-20 for values.

ODCM (BSEP) 3-63 Rev. 37 1

Table 3.3-20 Inhalation Dose Factors for Carbon-14 (DFA)

(mrem pCi)

Age Group Bone Liver T.Body Thyroid Kidney Lung GI-LLI Adult 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Teenager 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Child 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Infant 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Note: These values are from Regulatory Guide 1.109 Revision 1 Tables E-7 through E-10.

2. Concentration of Airborne Carbon-14 in Vegetation

a. The annual concentration of Carbon-14 in vegetation may be determined as follows:

C,1 =(3.17x10 7)(p)(Qc)(X)'.J (3.3-23)

Where:

C 4 is the concentration of Carbon-14 in vegetation in pCi/kg; Qc is the annual release rate of Carbon-14, in Ci/yr; p is the fractional equilibrium ratio, dimensionless (0.9 based off conservative historical values from NUREG/CR-4245 (1985));

3 factor, in sec/m ;

(-- is the annual average atmosphere dispersion 0.11 is the fraction of total plant mass that is natural carbon, dimensionless, from RG 1.109 Revision 1 Appendix C; 3

0.16 is equal to the concentration of natural carbon in the atmosphere in g/m from RG 1.109 Revision 1 Appendix C; and 3.17 x 107 is equal to (1.0 x 1012 pCi/Ci)(1.0 x 3 glkg) / (3.15 x10' yr

3. Concentration of Airborne Carbon-14 in Milk

a. The concentration of Carbon-14 in milk is dependent on the amount and contamination level of the feed consumed by the animal. The C-14 concentration in milk may be determined as follows:

Cm4=(F)(C)(Q)14 F(3.3-24)

Where:

ODCM (BSEP) 3-64 Rev. 37 1

is the C-14 concentration in milk, in pCi/liter; Fm is the average fraction of the animal's daily intake of C-14, which appears in each liter of milk, in days/liter. Cow = 0.012 days/liter from Table E-1 of RG 1.109 Revision 1 and Goat = 0.10 days/liter from Table E-2 of RG 1.109 Revision 1; 14 is the concentration of C-14 in the animal's feed, in pCi/kg; QF is the amount of feed consumed by the animal per day, in kg/day, see ODCM Table C-1.

4. Concentration of Airborne Carbon-14 in Meat

a. The concentration of Carbon-14 in meat is dependent on the amount and contamination level of the feed consumed by the animal. The C-14 concentration in meat may be determined as follows:

14 =(Ff)(CIl)(QF) (3.3-25)

Where:

CF4 is the concentration of C-14 in animal flesh, in pCi/kg; Ff is the fraction of the animal's daily intake of C-14, which appears in each kilogram of flesh, in days/kg. Value for C-14 is 0.031 days/kg from Table E-1 in RG 1.109 Revision 1; 14 is the concentration of C-14 in the animal's feed, in pCi/kg; QF is the amount of feed consumed by the animal per day, in kg/day, see ODCM Table C-1.

5. Annual Dose from Atmospherically Released Carbon-14 in Foods

a. The annual dose associated with the ingestion of Carbon-14 in food may be determined as follows:

= [U

[ v m m F L v]

D =DFIjafgC4 +Ua C14 Ua C14 +Ua f1 C 1 4 (3.3-26)

Where:

D DJa is the annual dose to organ j of an individual in age group a from dietary intake of atmospherically released C-14, in mrem/yr; DFI4a is the dose conversion factor for the ingestion of C-14 for organ j, and age group a, in mrem/pCi, reference Table 3.3-21; ODCM (BSEP) 3-65 Rev. 37 1

Ua the ingestion rate of produce (non-leafy vegetables, fruit, and grains) for individuals in age group a, in kg/yr, see ODCM Table C-3; Um the ingestion rate of milk for individuals in age group a, in liters/year, see ODCM Table C-1 (Uap);

a the ingestion rate of meat for individuals in age group a, in kg/yr, see ODCM Table C-2 (Uap);

a Lthe ingestion rate of leafy vegetables for individuals in age group a

a, in kg/yr, see ODCM Table C-3; fg is the fraction of produce ingested grown in garden of interest, 0.76 from Table E-15 of RG 1.109; is the fraction of leafy vegetables grown in the garden of interest, 1.0 from Table E-15 of RG 1.109; C 4' is the concentration of C-14 in vegetation, in pCi/kg; 14 C14 is the concentration of C-14 in milk, in pCi/liter; C14 is the concentration of C-14 in animal flesh, in pCi/kg.

Table 3.3-21 Ingestion Dose Factors for Carbon-14 (DFI)

(mrem/pCi)

Age Group Bone Liver T.Body Thyroid Kidney Lung GI-LLI Adult 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Teenager 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 Child 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 Infant 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Note: These values are from Regulatory Guide 1.109 Revision 1 Tables E-11 through E-14.

ODCM (BSEP) 3-66 Rev. 37 1

INDEX 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ............................... 4-3 ODCM (BSEP) 4-1 Rev. 25

LIST OF TABLES Table No. Title Paqe SECTION 4 4.0-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM .............. 4-4 ODCM (BSEP) 4-2 Rev. 25

4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Table 4.0-1 contains the sample point description, sampling and collection frequency analysis, and analysis frequency for various exposure pathways in the vicinity of the BSEP for the radiological monitoring program. Figure 4.0-1 shows the location of various sample points. Figure F-2, Gaseous Radwaste Effluent System, denotes the various release pathways.

ODCM (BSEP) 4-3 Rev. 26 1

TABLE 4.0-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM*

Exposure Pathway Sample Sample Point Description, ,Approximate Distance, Sampling and ..'Analysis Analysis (a) and/or Sample ID No. and Direction. Collection Frequency Fre'quency

1. DIRECT 1 1.1 miles E Q Q Gamma Dose RADIATION 2 0.9 miles ESE Q Q Gamma Dose 3 0.9 miles SE Q Q Gamma Dose 4 1.1 miles SSE Q Q Gamma Dose 5 1.6 miles S Q Q Gamma Dose 6 1.6 miles SSW Q Q Gamma Dose 7 1.1 miles SW Q Q Gamma Dose 8 1.2 miles W Q Q Gamma Dose 9 1.8 miles WNW Q Q Gamma Dose 10 0.8 miles NW Q Q Gamma Dose 11 0.9 miles NNW Q Q Gamma Dose 12 1.1 miles N Q Q Gamma Dose 13 1.2 miles NNE Q Q Gamma Dose 14 0.5 miles NE Q Q Gamma Dose 15 0.9 miles ENE Q Q Gamma Dose 16 1.0 miles WSW Q Q Gamma Dose 17 1.4 miles ESE Q Q Gamma Dose

Refer to Figure 4.0-1 and Figure F-2.

ODCM (BSEP) 4-4 Rev. 32 1

TABLE 4.0-1 (Cont'd)

Exposure Pathway Sample Sample Point Description, Approximate Distance, Sampling and Analysis Analysis (a) and/or Sample ID No. and Direction Collection Frequency Frequency

1. DIRECT 18 1.7 miles Q Q Gamma Dose RADIATION (Cont'd) 77 5.4 miles S Q Q Gamma Dose 75 4.7 miles S Q Q Gamma Dose 76 4.8 miles SSW Q Q Gamma Dose 22 5.3 miles SW Q Q Gamma Dose 23 4.6 miles WSW Q Q Gamma Dose 24 3.0 miles W Q Q Gamma Dose 25 8.6 miles WNW Q Q Gamma Dose 26 5.9 miles NW Q Q Gamma Dose 27 5.1 miles NNW Q Q Gamma Dose 79 9.5 miles N Q Q Gamma Dose 78 9.9 miles NNE Q Q Gamma Dose 30 2.0 miles NE Q Q Gamma Dose 31 2.5 miles ENE Q Q Gamma Dose 32 5.8 miles ENE Q Q Gamma Dose 33 4.1 miles E Q Q Gamma Dose 34 5.4 miles E Q Q Gamma Dose 81 9.9 miles WNW (c) Q Q Gamma Dose ODCM (BSEP) 4-5 Rev. 30 1

TABLE 4.0-1 (Cont'd)

Exposure Pathway Sample Sample Point Description, Approximate Distance, Sampling and Analysis Analysis (a) and/or Sample ID No. and Direction Collection Frequency Frequency

1. DIRECT 36 8.9 miles NE Q Q Gamma Dose RADIATION (Cont'd) 37 5.5 miles NW Q Q Gamma Dose 38 11.0 miles W Q Q Gamma Dose 39 5.3 miles SW Q Q Gamma Dose 40 6.9 miles WSW Q Q Gamma Dose 20 2.1 miles S Q Q Gamma Dose 21 2.9 miles SSW Q Q Gamma Dose 28 4.2 miles NW Q Q Gamma Dose 29 2.6 miles SSW Q Q Gamma Dose 35 7.3 miles SSE Q Q Gamma Dose 82 0.17 miles NNE Q Q Gamma Dose 83 0.27 miles NE Q Q Gamma Dose 84 0.27 miles NE Q Q Gamma Dose 85 0.09 miles ENE Q Q Gamma Dose ODCM (BSEP) 4-6 Rev. 34 1

TABLE 4.0-1 (Cont'd)

Exposure Pathway Sample Sample Point Description, Approximate Distance, Sampling and Analysis Analysis (a) and/or Sample ID No. and Direction Collection Frequency Frequency

2. AIRBORNE 200 1.0 miles WSW - Visitors Center .ontinuous sampler W Radioiodine Radioiodine and peration with Canister 1-131 Particulate Sample collected analysis ieekly or as r4 equired by dust W Particulate

,ading, whichever sampler more frequent 201 0.5 miles NE - Bio. Lab Road - Projected Gross beta Maximum Annual Concentration (PMAC) radioactivity analysis following filter change (b) 202 1.0 miles S - Substation, Construction Rd. Q Gamma isotopic analysis of composite by location 203 2.0 miles SSW - Southport Substation 204 22.4 miles NNE - Sutton Plant - (Historical Control) 205 0.6 miles SSE - Spoil Pond 206 11.3 miles NW - Brunswick County Complex -

Control(c)

ODCM (BSEP) 4-7 Rev. 35 1

TABLE 4.0-1 (Cont'd)

Exposure Pathway Sample Sample Point Description, Approximate Sampling and Analysis Analysis (a) and/or Sample ID No. Distance, and Direction Collection Frequency Frequency

3. WATERBORNE 400 0.6 miles NE - Intake Canal - Control (c) Composite sample Monthly Gamma (d) Collection-M Isotopic

a. Surface 401 4.9 miles SSW - Discharge Canal at OD Q Tritium Pumps 495 Nancy's Creek - WP-52 Grab Sample, Weekly Tritium 496 Nancy's Creek - WP-53 eekly,Monthly Gamma 497 Nancy's Creek - WP-55 Isotopic f'g 498 Nancy's Creek - WP-57 499 Cape Fear River (c)- WP-61 Grab Sample, Weekly Tritium 494 Nancy's Creek Marsh Area -WP-106 Weekly Gamma Isotopic from composite 604 Nancy's Creek Marsh Area - WP-92 of WP-106 and WP-92 ODCM (BSEP) 4-8 Rev. 35 1

TABLE 4.0-1 (Cont'd)

Exposure Pathway Sample Sample Point Description, Approximate Sampling and Analysis Analysis (a) and/or Sample ID No. Distance, and Direction Collection Frequency Frequency

3. WATERBORNE 605 Nancy's Creek Marsh Area-WP-72 Grab Sample, Weekly Tritium 60 Nancycs Weekly Gamma Isotopic

a. Surface (Continued) from composite 606 Nancy's Creek Marsh Area - WP-74 of WP-72, WP-74, and WP-76 607 Nancy's Creek Marsh Area - WP-76 608 Nancy's Creek Marsh Area - WP-82 Grab Sample, Weekly Tritium Weekly Gamma Isotopic from composite 609 Nancy's Creek Marsh Areao- WP-84 f WP-82, WP-84, and WP-88 610 Nancy's Creek Marsh Area -WP-88 ODCM (BSEP) 4-9 Rev. 35 1

TABLE 4.0-1 (Cont'd)

Exposure Pathway Sample Sample Point Description, Approximate Distance, Sampling and Analysis Analysis (a) and/or Sample ID No. and Direction Collection Frequency Frequency

b. Sediment 500 5.0 miles SSW - Discharge - Beach near OD Semiannual Semiannual Gamma Pumps Isotopic M 501 Nancy's Creek, Adjacent to WP-55, Near Storm Annual Annual Gamma Drain Stabilization Pond Isotopic h

c. Groundwater 404 Monitoring Well ESS-1B, 0.16 miles SW Grab Sample, Q Tritium Quarterly, 407 Monitoring Well ESS-13B, 0.06 miles ENE Semiannual Semiannual Gamma 409 Monitoring Well ESS-17A, 0.65 miles NE Isotopicf 410 Monitoring Well ESS-17B, 0.65 miles NE 418 Monitoring Well ESS-21B, Near Storm Drain Stabilization Pond Monitoring Well ESS-24A, Near Storm Drain 423 Stabilization Pond Monitoring Well ESS-24B, Near Storm Drain 424 Stabilization Pond Monitoring Well ESS-25B, Near Storm Drain 426 Stabilization Pond Monitoring Well ESS-27A, Near Storm Drain 429 Stabilization Pond 612 Monitoring Well ESS MWPA-1 18B, Near Intake Canal and Plant Stack ODCM (BSEP) 4-10 Rev. 35 1

TABLE 4.0-1 (Cont'd)

Exposure Pathway Sample Sample Point Description, Approximate Distance, Sampling and Analysis Analysis (a) and/or Sample ID No. and Direction Collection Frequency Frequency

4. INGESTION 600 To be identified as available With animals on Semi- Gamma

a. Milk pasture - monthly isotopic and semi-monthly 1-131 601 t other times - analyses monthly (animals on pasture) 602 Monthly Gamma isotopic and 603 1-131 analysis (other times)

b. Fish and 700-702 5.5 mile SSW - Atlantic Ocean (e)at Discharge When in Season - Semiannual Gamma Invertebrates (shrimp) Semiannual isotopic on edible portions 703-705 Not Specified - Atlantic Ocean (c)(e) 706-708 Nancy's Creek (e) nnual nnual Gamma isotopic on edible portions ODCM (BSEP) 4-11 Rev. 35 1

TABLE 4.0-1 (Cont'd)

Exposure Pathway Sample Sample Point Description, Approximate Distance, Sampling and: Analysis Analysis .(a) and/or Sample ID No* and Direction Collection Frequency

..Frequency

c. Broadleaf Vegetation 800 0.7 miles NE - Intake Canal When available - Monthly Gamma Monthly Isotopic 801 0.8 miles SW - Discharge Canal Monthly 1-131 802 10.1 miles - Control - Location not Specified (c) 803 0.6 miles SSE - Spoil Pond 804 0.7 miles S - Leonard Street plant exit adjacent to RR tracks (a) The LLD for each analysis is specified in Table 7.3.15-3, with the exception of the Nancy's Creek Marsh Area principal gamma isotopic and 1-131. The LLD for the Nancy's Creek Marsh Area gamma isotopic is 5 x 107 pCi/ml for Principal Gamma Emitters and 1 x 10-6 pCi/ml for 1-131.

(b) Particulate samples will be analyzed for gross beta radiation 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more following filter change. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic shall be performed on the individual samples.

(c) Control Station - These stations are presumed to be outside the influence of plant effluents.

(d) Composite samples shall be collected by collecting an aliquot at intervals not exceeding 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

(e) A sample of one free swimmer, one bottom feeder, and one shellfish (shrimp) will be collected if available. A control sample of each species collected will be obtained if available.

(f) Gamma isotopic scan means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

(g) The weekly samples are to be composited for monthly gamma isotopic analyses. If plant activity is detected, Sr-89, 90 and Fe-55 analysis are to be performed.

(h) If plant activity is detected, Sr-89, 90 and Fe-55 analysis are to be performed and frequency will be increased to Semi-Annual.

ODCM (BSEP) 4-12 Rev. 35

FIGURE 4.0-1 BSEP Sample Point Locations

,I, h Pinelevel ODCM (BSEP) 4-13 Rev. 37

INDEX 5.0 RADIOLOGICAL INTERLABORATORY COMPARISON STUDIES ............................. 5-2 5.1 OBJECTIVE ........................................................................................................... 5-2 5.2 PROGRAM ............................................................................................................ 5-2 5.2.1 Environmental Sample Analyses Comparison Program .............................. 5-2 5.2.2 Effluent Release Analyses Program ........................................................... 5-2 5.2.3 Abnormal Results ....................................................................................... 5-2 ODCM (BSEP) 5-1 Rev. 37

5.0 RADIOLOGICAL INTERLABORATORY COMPARISON STUDIES 5.1 OBJECTIVE The objective of this program is to evaluate the total laboratory analysis process by comparing results with results obtained by a separate laboratory or laboratories for an equivalent sample.

5.2 PROGRAM 5.2.1 Environmental Sample Analyses Comparison Program Environmental samples from the BSEP environs will be analyzed by the Harris Energy & Environmental Center or by a qualified contracting laboratory. These laboratories will participate at least annually in a interlaboratory comparison study.

The results of the laboratories' performances in the study will be provided to BSEP E&RC and will be included in the Annual Radiological Environmental Operating Report. The results will be provided to the NRC upon request.

5.2.2 Effluent Release Analyses Program BSEP E&RC will perform sample analyses for gamma-emitting radionuclides in effluent releases. The E&RC radiochemistry laboratory will participate annually in a corporate interlaboratory comparison study or equivalent study. The results of these studies will be provided to the NRC upon request.

5.2.3 Abnormal Results Progress Energy laboratory or vendor laboratory results shall be compared to the criteria established in the NRC Inspection Manual (Procedure 84750) for Radioactive Waste Treatment, Effluent, and Environmental Monitoring.

The referenced criteria is as follows:

a. Divide each standard result by its associated uncertainty to obtain resolution (the uncertainty is defined as the relative standard deviation, or sigma, of the standard result as calculated from counting statistics).

ODCM (BSEP) 5-2 Rev. 30 1

b. Divide each laboratory result by the corresponding standard result to obtain the ratio (laboratory result/standard).

c. The laboratory measurement is in agreement if the value of the ratio falls within the limits shown below for the corresponding resolution:

Resolution Ratio

<4 0.4-2.5 4-7 0.5 - 2.0 8-15 0.6- 1.66 16- 50 0.75- 1.33 51 - 200 0.80- 1.25

> 200 0.85- 1.18 If the Progress Energy laboratory or vendor laboratory results lie outside the ratio criteria, an evaluation will be performed to identify any recommended remedial actions to reduce anomalous errors.

Complete documentation of the evaluation will be available to BSEP and will be provided to the NRC upon request.

ODCM (BSEP) 5-3 Rev. 35

INDEX 6.0 TOTAL DOSE (40CFR190 CO MPLIANCE) .................................................................. 6-2 I 6.1 INTRO DUCTIO N .................................................................................................... 6-2 6.1 G ENERAL .............................................................................................................. 6-2 6.3 CALCULATIO NS O F TOTAL BODY DOSE ............................................................ 6-3 6.3.1 Direct Radiation ........................................................................................... 6-3 6.3.2 Inhalation Dose ........................................................................................... 6-3 6.3.3 Ingestion Pathway ....................................................................................... 6-3 6.3.4 Other Uranium Fuel Cycle Sources ............................................................. 6-3 6.4 THYRO ID DOSE .................................................................................................... 6-4 ODCM (BSEP) 6-1 Rev. 37

6.0 TOTAL DOSE (40CFR190 COMPLIANCE)

6.1 INTRODUCTION

Compliance with 40CFR190 as prescribed by ODCM Specification 7.3.14 is to be demonstrated only when one or more of ODCM Specifications 7.3.4.a, 7.3.4.b, 7.3.8.a, 7.3.8.b, 7.3.9.a, 7.3.9.b is exceeded by a factor of 2. Once this occurs, the Company has 30 days to submit this report.

6.2 GENERAL To perform the calculations to evaluate conformance with 40CFR190, an effort is made to develop doses that are realistic by removing assumptions that lead to overestimates of dose to a MEMBER OF THE PUBLIC (i.e., calculations for compliance with 1 OCR50, Appendix I). To accomplish this, the following calculational rules are used:

6.2.1 Doses to a MEMBER OF THE PUBLIC via the liquid release pathway are considered to be <1 mrem/yr. (Ref: NUREG 0543).

6.2.2 Doses to a MEMBER OF THE PUBLIC due to a milk pathway will be evaluated only as can be shown to exist. Otherwise, doses via this pathway will be estimated as <1 mrem/yr.

6.2.3 Environmental sampling data which demonstrates that no pathway exists may be used to delete a pathway to man from a calculation.

6.2.4 To sum numbers represented as "less than" (<), use the value of the largest number in the group.

(i.e., <5 + <1 + <1 + <3 = 5) 6.2.5 When doses via direct radiation are added to doses via inhalation pathway, they will be calculated for the same distance in the same sector.

6.2.6 The calculational locations for a MEMBER OF THE PUBLIC will only be at residences or places of employment.

NOTE: Additional assumptions may be used to provide situation-specific parameters, provided they are documented along with their concomitant bases.

ODCM (BSEP) 6-2 Rev. 37

6.3 CALCULATIONS OF TOTAL BODY DOSE Estimates will be made for each of the following exposure pathways to the same location by age class. Only those age classes known to exist at a location are considered.

6.3.1 Direct Radiation The component of dose to a MEMBER OF THE PUBLIC due to direct radiation will be determined by:

1. Determining the direct radiation dose at the plant boundary in each sector, DB,0.

2. Extrapolating that dose to the calculational location as follows:

DB,, (1.49 E + 6)

DuO (X2, 0)

DL, = dose at calculational location in sector 0 1.49E + 6 = square of mean distance to the site boundary (1220 m).

XL, 0 = distance to calculational locations in sector 0 in meters.

6.3.2 Inhalation Dose The inhalation dose will be determined at the calculational locations for each age class at risk according to the methods outlined in Section 3.3 of this manual.

6.3.3 Ingestion Pathway The dose via the ingestion pathway will be calculated at the consumer locations for the consumers at risk. If no milk pathway exists in a sector, the dose via this pathway will be treated as <1 mrem/yr.

6.3.4 Other Uranium Fuel Cycle Sources The dose from other fuel cycle sources will be treated as <1 mrem/yr.

ODCM (BSEP) 6-3 Rev. 25

6.4 THYROID DOSE The dose to the thyroid will be calculated for each sector as the sum of inhalation dose and milk ingestion dose (if existing). The calculational methods will be those identified in Section 3.3 of this manual.

6.4.1 Dose projections can incorporate planned plant operations such as power reduction or outages for the projected period.

ODCM (BSEP) 6-4 Rev. 25

SECTION 7.0 RADIOACTIVE EFFLUENTS CONTROLS PROGRAM CONTAINING OFFSITE DOSE CALCULATION MANUAL SPECIFICATIONS (ODCMS) AND BASES FOR BRUNSWICK STEAM ELECTRIC PLANT UNITS 1 AND 2 Brunswick Units 1 and 2 7-0 Rev. 25

INDEX 7.1.0 USE AND APPLICATION ...................................................................................... 7.1.1-1 7.1.1 Definitions ............................................................................................ 7.1.1-1 7.1.2 Logical Connectors ............................................................................... 7.1.2-1 7.1.3 Completion Times ................................................................................ 7.1.3-1 7.1.4 Frequency ............................................................................................ 7.1.4-1 7.2.0 Not used ................................................................................................................ 7.2.0-1 7.3 OFFSITE DOSE CALCULATION MANUAL SPECIFICATIONS 7.3.0 Offsite Dose Calculation Manual Specification (ODCMS) Applicability. 7.3.0-1 7.3.0 Test Requirement (TR) Applicability ..................................................... 7.3.0-3 7.3.1 Radioactive Liquid Effluent Monitoring Instrumentation ........................ 7.3.1-1 7.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation .................... 7.3.2-1 7.3.3 Concentration- Liquid Effluents ........................................................... 7.3.3-1 7.3.4 Dose--Liquid Effluents ......................................................................... 7.3.4-1 7.3.5 Liquid Radwaste Treatment System ..................................................... 7.3.5-1 7.3.6 Liquid Holdup Tanks ............................................................................. 7.3.6-1 7.3.7 Dose Rate--Gaseous Effluents ............................................................ 7.3.7-1 7.3.8 Dose- Noble Gases ............................................................................. 7.3.8-1 7.3.9 Dose--4-131, 1-133, Tritium, and Radionuclides in Particulate Form ..... 7.3.9-1 7.3.10 Gaseous Radwaste Treatment System .............................................. 7.3.10-1 7.3.11 Ventilation Exhaust Treatment System ............................................... 7.3.11-1 7.3.12 Explosive Gas Mixture ........................................................................ 7.3.12-1 7.3.13 Drywell Venting or Purging ................................................................. 7.3.13-1 7.3.14 Total Dose (40 CFR Part 190) ............................................................ 7.3.14-1 7.3.15 Radiological Environmental Monitoring Program ................................ 7.3.15-1 7.3.16 Land Use Census ............................................................................... 7.3.16-1 7.3.17 Interlaboratory Comparison Program .................................................. 7.3.17-1 7.4.0 REPORTING REQUIREMENTS ............................................................................ 7.4.0-1 7.4.1 Annual Radiological Environmental Operating Report .......................... 7.4.0-1 7.4.2 Radioactive Effluent Release Report .................................................... 7.4.0-1 7.5.0 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS ........... 7.5.0-1 BASES B 7.3.0 Offsite Dose Calculation Manual Specification (ODCMS)

Applicability ....................................................................................... B 7.3.0-1 (continued)

Brunswick Units 1 and 2 7-i Rev. 25

INDEX (continued)

B 7.3.0 Test Requirement (TR) Applicability .................................................. B 7.3.0-6 B 7.3.1 Radioactive Liquid Effluent Monitoring Instrumentation ..................... B 7.3.1-1 B 7.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation ................. B 7.3.2-1 B 7.3.3 Concentration- Liquid Effluents ........................................................ B 7.3.3-1 B 7.3.4 Dose- Liquid Effluents ...................................................................... B 7.3.4-1 B 7.3.5 Liquid Radwaste Treatment System .................................................. B 7.3.5-1 B 7.3.6 Liquid Holdup Tanks .......................................................................... B 7.3.6-1 B 7.3.7 Dose Rate--Gaseous Effluents ......................................................... B 7.3.7-1 B 7.3.8 Dose Rate- Noble Gases ................................................................. B 7.3.8-1 B 7.3.9 Dose-I-131, 1-133, Tritium, and Radionuclides in Particulate F o rm .................................................................................................. B 7 .3 .9-1 B 7.3.10 Gaseous Radwaste Treatment System ........................................... B 7.3.10-1 B 7.3.11 Ventilation Exhaust Treatment System ............................................ B 7.3.11-1 B 7.3.12 Explosive Gas Mixture ..................................................................... B 7.3.12-1 B 7.3.13 Drywell Venting or Purging .............................................................. B 7.3.13-1 B 7.3.14 Total Dose (40 CFR Part 190) ......................................................... B 7.3.14-1 B 7.3.15 Radiological Environmental Monitoring Program ............................. B 7.3.15-1 B 7.3.16 Land Use Census ............................................................................ B 7.3.16-1 B 7.3.17 Interlaboratory Comparison Program ............................................... B 7.3.17-1 Brunswick Units 1 and 2 7-ii Rev. 25

LIST OF TABLES Table 7.3.1-1 Radioactive Liquid Effluent Monitoring Instrumentation ........................ 7.3.1-7 Table 7.3.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation .................... 7.3.2-9 Table 7.3.3-1 Radioactive Liquid Waste Sampling and Analysis Program .................. 7.3.3-3 Table 7.3.3-2 Radioactive Liquid Waste Sampling and Analysis Program for Potential Release Pathways Which Have Exceeded Trigger Levels .................... 7.3.3-6 Table 7.3.7-1 Radioactive Gaseous Waste Sampling and Analysis Program ............. 7.3.7-2 Table 7.3.15-1 Radiological Environmental Monitoring Program ................................ 7.3.15-6 Table 7.3.15-2 Limits for the Level of Radioactivity in Environmental Samples ........ 7.3.15-11 Table 7.3.15-3 Detection Capabilities for Environmental Sample Analysis ............... 7.3.15-12 Brunswick Units 1 and 2 7-iii Rev. 30

LIST OF FIGURES Figure 7.1.1-1 SITE BOUNDARY ................................................................................ 7.1.1-5 Brunswick Units 1 and 2 7-iv Rev. 25

Definitions 7.1.1 7.1.0 USE AND APPLICATION ODCMS 7.1.1 Definitions NOTE The defined terms of this section appear in capitalized type and are applicable throughout these Offsite Dose Calculation Manual Specifications and Bases.

Term Definition CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, display, and trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is calibrated.

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

CHANNEL FUNCTIONAL A CHANNEL FUNCTIONAL TEST shall be the injection of a TEST simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY, including required alarm, interlock, display, and trip functions, and channel failure trips. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is tested.

(continued)

Brunswick Units 1 and 2 7.1.1-1 Rev. 25

Definitions 7.1.1 ODCMS 7.1.1 Definitions (continued)

GASEOUS RADWASTE A GASEOUS RADWASTE TREATMENT SYSTEM is any TREATMENT SYSTEM system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

LIQUID RADWASTE A LIQUID RADWASTE TREATMENT SYSTEM is any TREATMENT SYSTEM system designed and installed to collect, treat and process radioactive liquid waste streams for reuse or for controlled discharge from the restricted area in compliance with established regulatory requirements.

MEMBER(S) OF MEMBER(S) OF THE PUBLIC shall mean any individual(s)

THE PUBLIC except when that individual is receiving occupational dose.

MODE A MODE shall be as required by Technical Specifications.

OPERABLE-OPERABILITY A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

PURGE-PURGING PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the containment.

(continued)

Brunswick Units 1 and 2 7.1.1-2 Rev. 30 1

Definitions 7.1.1 ODCMS 7.1.1 Definitions (continued)

RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to the (RTP) reactor coolant of 2923 MWt.

SITE BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased nor otherwise controlled by the licensee, as defined by Figure 7.1.1-1. For the purpose of effluent release calculations, the boundary for atmospheric releases is the SITE BOUNDARY and the boundary for liquid releases is the SITE BOUNDARY prior to dilution in the Atlantic Ocean.

SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to radiation.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

UNRESTRICTED AREA An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purpose of protection of individuals from exposure to radiation and radioactive materials or any area within the SITE BOUNDARY used for residential quarters or industrial, commercial, institutional or recreational purposes.

VENTILATION EXHAUST A VENTILATION EXHAUST TREATMENT SYSTEM is any TREATMENT SYSTEM system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents.

Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

(continued)

Brunswick Units 1 and 2 7.1.1-3 Rev. 27 1

Definitions 7.1.1 ODCMS 7.1.1 Definitions (continued)

VENT-VENTING VENT or VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required. Vent, used in system names, does not imply a VENTING process.

Brunswick Units 1 and 2 7.1.1-4 Rev. 25

Definitions 7.1.1 Ir- 7 PROPERTY BOUNDARY SITE AREA BOUNDARY EXCLUSION AREA BOUNDARY Figure 7.1.1-1 (page 1 of 1)

SITE BOUNDARY Brunswick Units 1 and 2 7.1.1-5 Rev. 25

Logical Connectors 7.1.2 7.1.0 USE AND APPLICATION ODCMS 7.1.2 Logical Connectors PURPOSE The purpose of this section is to explain the meaning of logical connectors.

Logical connectors are used in Offsite Dose Calculation Manual Specifications (ODCMS) to discriminate between, and yet connect, discrete Conditions, Required Compensatory Measures, Completion Times, Tests, and Frequencies. The only logical connectors that appear in ODCMS are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings.

BACKGROUND Several levels of logic may be used to state Required Compensatory Measures. These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Compensatory Measure. The first level of logic is identified by the first digit of the number assigned to a Required Compensatory Measure and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Compensatory Measure). The successive levels of logic are identified by additional digits of the Required Compensatory Measure number and by successive indentions of the logical connectors.

When logical connectors are used to state a Condition, Completion Time, Test, or Frequency, only the first level of logic is used, and the logical connector is left justified with the statement of the Condition, Completion Time, Test, or Frequency.

EXAMPLES The following examples illustrate the use of logical connectors.

(continued)

Brunswick Units 1 and 2 7.1.2-1 Rev. 25

Logical Connectors 7.1.2 ODCMS 7.1.2 Logical Connectors (continued)

EXAMPLES EXAMPLE 7.1.2-1 (continued)

COMPENSATORY MEASURES CONDITION REQUIRED COMPLETION COMPENSATORY TIME MEASURE A. ODCMS not A.1 Verify...

met. AND A.2 Restore...

In this example the logical connector AND is used to indicate that when in Condition A, both Required Compensatory Measures A.1 and A.2 must be completed.

(continued)

Brunswick Units 1 and 2 7.1.2-2 Rev. 25

Logical Connectors 7.1.2 ODCMS 7.1.2 Logical Connectors (continued)

EXAMPLES EXAMPLE 7.1.2-2 (continued)

COMPENSATORY MEASURES CONDITION REQUIRED COMPLETION COMPENSATORY TIME MEASURE A. ODCMS not A.1 Trip...

met. OR A.2.1 Verify...

AND A.2.2.1 Reduce...

OR A.2.2.2 Perform...

OR A.3 Align...

This example represents a more complicated use of logical connectors.

Required Compensatory Measures A.1, A.2, and A.3 are alternative choices, only one of which must be performed as indicated by the use of the logical connector OR and the left justified placement. Any one of these three Compensatory Measures may be chosen. If A.2 is chosen, then both A.2.1 and A.2.2 must be performed as indicated by the logical connector AND. Required Compensatory Measure A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical connector OR indicates that A.2.2.1 and A.2.2.2 are alternative choices, only one of which must be performed.

Brunswick Units 1 and 2 7.1.2-3 Rev. 25

Completion Times 7.1.3 7.1.0 USE AND APPLICATION ODCMS 7.1.3 Completion Times PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.

BACKGROUND Offsite Dose Calculation Manual Specifications (ODCMS) specify minimum requirements for unit systems or variables. The COMPENSATORY MEASURES associated with an ODCMS state Conditions that typically describe the ways in which the requirements of the ODCMS can fail to be met. Specified with each stated Condition are Required Compensatory Measure(s) and Completion Times(s).

DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Compensatory Measure. It is referenced to the time of discovery of a situation (e.g., inoperable equipment or variable not within limits) that requires entering a COMPENSATORY MEASURES Condition unless otherwise specified, providing the unit is in a MODE or specified condition stated in the Applicability of the ODCMS. Required Compensatory Measures must be completed prior to the expiration of the specified Completion Time. A COMPENSATORY MEASURES Condition remains in effect and the Required Compensatory Measures apply until the Condition no longer exists or the unit is not within the ODCMS Applicability.

If situations are discovered that require entry into more than one Condition at a time within a single ODCMS (multiple Conditions), the Required Compensatory Measures for each Condition must be performed within the associated Completion Time. When in multiple Conditions, separate Completion Times are tracked for each Condition starting from the time of discovery of the situation that required entry into the Condition.

Once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition unless specifically stated. The Required Compensatory Measures of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition.

(continued)

Brunswick Units 1 and 2 7.1.3-1 Rev. 25

Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)

DESCRIPTION However, when a subsequent division, subsystem, component, (continued) or variable expressed in the Condition is discovered to be inoperable or not within limits, the Completion Time(s) may be extended. To apply this Completion Time extension, two criteria must first be met. The subsequent inoperability:

a. Must exist concurrent with the first inoperability; and

b. Must remain inoperable or not within limits after the first inoperability is resolved.

The total Completion Time allowed for completing a Required Compensatory Measure to address the subsequent inoperability shall be limited to the more restrictive of either:

a. The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; or

b. The stated Completion Time as measured from discovery of the subsequent inoperability.

The above Completion Time extension does not apply to those ODCMS that have exceptions that allow completely separate re-entry into the Condition (for each division, subsystem, component or variable expressed in the Condition) and separate tracking of Completion Times based on this re-entry. These exceptions are stated in individual ODCMS.

The above Completion Time extension does not apply to a Completion Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e., "once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ," where the Completion Time is referenced from a previous completion of the Required Compensatory Measures versus the time of Condition entry) or as a time modified by the phrase "from discovery. . ." Example 7.1.3-3 illustrates one use of this type of Completion Time. The 10 day Completion Time specified for Condition A and B in Example 7.1.3-3 may not be extended.

(continued)

Brunswick Units 1 and 2 7.1.3-2 Rev. 25

Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)

EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.

EXAMPLE 7.1.3-1 COMPENSATORY MEASURES CONDITION REQUIRED COMPLETION COMPENSATORY TIME MEASURE B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Compensatory AND Measure and associated B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Completion Time not met.

Condition B has two Required Compensatory Measures. Each Required Compensatory Measure has its own separate Completion Time. Each Completion Time is referenced to the time that Condition B is entered.

The Required Compensatory Measures of Condition B are to be in MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND in MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . A total of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is allowed for reaching MODE 3 and a total of 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (not 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ) is allowed for reaching MODE 4 from the time that Condition B was entered. If MODE 3 is reached within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , the time allowed for reaching MODE 4 is the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months because the total time allowed for reaching MODE 4 is 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

If Condition B is entered while in MODE 3, the time allowed for reaching MODE 4 is the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

{*nnfini ipri)

Brunswick Units 1 and 2 7.1.3-3 Rev. 25

Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)

EXAMPLES EXAMPLE 7.1.3-2 (continued)

COMPENSATORY MEASURES CONDITION REQUIRED COMPLETION COMPENSATORY TIME MEASURE A. One pump A.1 Restore pump to 7 days inoperable. OPERABLE status.

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Compensatory AND Measure and associated B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Completion Time not met.

When a pump is declared inoperable, Condition A is entered. If the pump is not restored to OPERABLE status within 7 days, Condition B is also entered and the Completion Time clocks for Required Compensatory Measures B.1 and B.2 start. If the inoperable pump is restored to OPERABLE status after Condition B is entered, Condition A and B are exited, and therefore, the Required Compensatory Measures of Condition B may be terminated.

(continued)

Brunswick Units 1 and 2 7.1.3-4 Rev. 25

Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)

EXAMPLES EXAMPLE 7.1.3-3 (continued)

COMPENSATORY MEASURES CONDITION REQUIRED COMPLETION COMPENSATORY TIME MEASURE A. One Function X A.1 Restore 7 days subsystem Function X inoperable, subsystem to OPERABLE 10 days from status. discovery of failure to meet the ODCMS B. One Function Y B.1 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months subsystem Function Y inoperable, subsystem to OPERABLE 10 days from status. discovery of failure to meet the ODCMS C. One Function X C.1 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months subsystem Function X inoperable, subsystem to OPERABLE status.

One Function Y OR subsystem 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. C.2 Restore Function Y subsystem to OPERABLE status.

(continued)

Brunswick Units 1 and 2 7.1.3-5 Rev. 25

Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)

EXAMPLES EXAMPLE 7.1.3-3 (continued)

(continued)

When one Function X subsystem and one Function Y subsystem are inoperable, Condition A and Condition B are concurrently applicable. The Completion Times for Condition A and Condition B are tracked separately for each subsystem, starting from the time each subsystem was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second subsystem was declared inoperable (i.e., the time the situation described in Condition C was discovered).

If Required Compensatory Measure C.2 is completed within the specified Completion Time, Conditions B and C are exited. If the Completion Time for Required Compensatory Measure A.1 has not expired, operation may continue in accordance with Condition A. The remaining Completion Time in Condition A is measured from the time the affected subsystem was declared inoperable (i.e., initial entry into Condition A).

The Completion Times of Conditions A and B are modified by a logical connector, with a separate 10 day Completion Time measured from the time it was discovered the ODCMS was not met. In this example, without the separate Completion Time, it would be possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the ODCMS. The separate Completion Time modified by the phrase "from discovery of failure to meet the ODCMS" is designed to prevent indefinite continued operation while not meeting the ODCMS. This Completion Time allows for an exception to the normal "time zero" for beginning the Completion Time "clock". In this instance, the Completion Time "time zero" is specified as commencing at the time the ODCMS was initially not met, instead of at the time the associated Condition was entered.

(continued)

Brunswick Units 1 and 2 7.1.3-6 Rev. 25

Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)

EXAMPLES EXAMPLE 7.1.3-4 (continued)

COMPENSATORY MEASURES CONDITION REQUIRED COMPLETION COMPENSATORY TIME MEASURE A. One or more A.1 Restore valve(s) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves to OPERABLE inoperable, status.

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Compensatory AND Measure and associated B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Completion Time not met.

A single Completion Time is used for any number of valves inoperable at the same time. The Completion Time associated with Condition A is based on the initial entry into Condition A and is not tracked on a per valve basis. Declaring subsequent valves inoperable, while Condition A is still in effect, does not trigger the tracking of separate Completion Times.

Once one of the valves has been restored to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first valve was declared inoperable. The Completion Time may be extended if the valve restored to OPERABLE status was the first inoperable valve. The Condition A Completion Time may be extended for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months provided this does not result in any subsequent valve being inoperable for > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Ifthe Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (plus the extension) expires while one or more valves are still inoperable, Condition B is entered.

(rnnnfini ipri)

Brunswick Units 1 and 2 7.1.3-7 Rev. 25

Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)

EXAMPLES EXAMPLE 7.1.3-5 (continued)

COMPENSATORY MEASURES NOTE Separate Condition entry is allowed for each inoperable valve.

CONDITION REQUIRED COMPLETION COMPENSATORY TIME MEASURE A. One or more A.1 Restore valve to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves OPERABLE inoperable, status.

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Compensatory AND Measure and associated B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Completion Time not met.

The Note above the COMPENSATORY MEASURES Table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the COMPENSATORY MEASURES Table.

The Note allows Condition A to be entered separately for each inoperable valve, and Completion Times tracked on a per valve basis. When a valve is declared inoperable, Condition A is entered and its Completion Time starts. If subsequent valves are declared inoperable, Condition A is entered for each valve and separate Completion Times start and are tracked for each valve.

(continued)

Brunswick Units 1 and 2 7.1.3-8 Rev. 25

Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)

EXAMPLES EXAMPLE 7.1.3-5 (continued)

(continued)

If the Completion Time associated with a valve in Condition A expires, Condition B is entered for that valve. If the Completion Times associated with subsequent valves in Condition A expire, Condition B is entered separately for each valve and separate Completion Times start and are tracked for each valve. If a valve that caused entry into Condition B is restored to OPERABLE status, Condition B is exited for that valve.

Since the Note in this example allows multiple Condition entry and tracking of separate Completion Times, Completion Time extensions do not apply.

EXAMPLE 7.1.3-6 COMPENSATORY MEASURES CONDITION REQUIRED COMPLETION COMPENSATORY TIME MEASURE A. One channel A.1 Perform Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable. TR 7.3.x.x.

OR A.2 Reduce 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months THERMAL POWER to

50% RTP.

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Compensatory Measure and associated Completion Time not met.

(continued)

Brunswick Units 1 and 2 7.1.3-9 Rev. 25

Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)

EXAMPLES EXAMPLE 7.1.3-6 (continued)

(continued)

Entry into Condition A offers a choice between Required Compensatory Measure A.1 or A.2. Required Compensatory Measure A.1 has a "once per' Completion Time, which qualifies for the 25% extension, per TR 7.3.0.2, to each performance after the initial performance. The initial 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval of Required Compensatory Measure A.1 begins when Condition A is entered and the initial performance of Required Compensatory Measure A.1 must be completed within the first 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval. If Required Compensatory Measure A.1 is followed and the Required Compensatory Measure is not met within the Completion Time (plus the extension allowed by TR 7.3.0.2), Condition B is entered. If Required Compensatory Measure A.2 is followed and the Completion Time of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months is not met, Condition B is entered.

If after entry into Condition B, Required Compensatory Measure A.1 or A.2 is met, Condition B is exited and operation may then continue in Condition A.

(continued)

Brunswick Units 1 and 2 7.1.3-10 Rev. 25

Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)

EXAMPLES EXAMPLE 7.1.3-7 (continued)

COMPENSATORY MEASURES CONDITION REQUIRED COMPLETION COMPENSATORY TIME MEASURE A. One subsystem A.1 Verify affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable, subsystem AND isolated.

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months subsystem to OPERABLE status.

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Compensatory AND Measure and associated B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Completion Time not met.

Required Compensatory Measure A.1 has two Completion Times. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time begins at the time the Condition is entered and each "Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter" interval begins upon performance of Required Compensatory Measure A.1.

If after Condition A is entered, Required Compensatory Measure A.1 is not met within either the initial 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or any subsequent 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval from the previous performance (plus the extension allowed by TR 7.3.0.2), Condition B is entered. The Completion Time clock for Condition A does not stop after Condition B is entered, but continues (continued)

Brunswick Units 1 and 2 7.1.3-11 Rev. 25

Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)

EXAMPLES EXAMPLE 7.1.3-7 (continued)

(continued) from the time Condition A was initially entered. If Required Compensatory Measure A.1 is met after Condition B is entered, Condition B is exited and operation may continue in accordance with Condition A, provided the Completion Time for Required Compensatory Measure A.2 has not expired.

IMMEDIATE When "Immediately" is used as a Completion Time, the Required COMPLETION TIME Compensatory Measure should be pursued without delay and in a controlled manner.

Brunswick Units 1 and 2 7.1.3-12 Rev. 25

Frequency 7.1.4 7.1.0 USE AND APPLICATION ODCMS 7.1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.

DESCRIPTION Each Test Requirement (TR) of the Offsite Dose Calculation Manual has a specified Frequency in which the Test must be met in order to meet the associated Offsite Dose Calculation Manual Specification (ODCMS). An understanding of the correct application of the specified Frequency is necessary for compliance with the TR.

The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 7.3.0, Test Requirement (TR)

Applicability. The "specified Frequency" consists of the requirements of the Frequency column of each TR, as well as certain Notes in the Test column that modify performance requirements.

Sometimes special situations dictate when the requirements of a Test are to be met. They are "otherwise stated" conditions allowed by TR 7.3.0.1.

They may be stated as clarifying Notes in the Test, as part of the Test, or both. Example 7.1.4-4 discusses these special situations.

Situations where a Test could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated ODCMS is within its Applicability, represent potential TR 7.3.0.4 conflicts. To avoid these conflicts, the TR (i.e., the Test or the Frequency) is stated such that it is only "required" when it can be and should be performed. With a TR satisfied, TR 7.3.0.4 imposes no restriction.

The use of "met or "performed" in these instances conveys specific meanings. A Test is "met" only when the acceptance criteria are satisfied. Known failure of the requirements of a Test, even without a Test specifically being "performed," constitutes a Test not "met."

"Performance" refers only to the requirement to specifically determine the (continued)

Brunswick Units 1 and 2 7.1.4-1 Rev. 25

Frequency 7.1.4 ODCMS 7.1.4 Frequency (continued)

DESCRIPTION ability to meet the acceptance criteria. TR 7.3.0.4 restrictions would not (continued) apply if both the following conditions are satisfied:

a. The Test is not required to be performed; and

b. The Test is not required to be met or, even if required to be met, is not known to be failed.

EXAMPLES The following examples illustrate the various ways that Frequencies are specified. In these examples, the Applicability of the ODCMS (ODCMS not shown) is MODES 1, 2, and 3.

EXAMPLE 7.1.4-1 TEST REQUIREMENTS TEST FREQUENCY Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Example 7.1.4-1 contains the type of TR most often encountered in the ODCMS. The Frequency specifies an interval (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) during which the associated Test must be performed at least one time. Performance of the Test initiates the subsequent interval. Although the Frequency is stated as 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an extension of the time interval to 1.25 times the interval specified in the Frequency is allowed by TR 7.3.0.2 for operational flexibility. The measurement of this interval continues at all times, even when the TR is not required to be met per TR 7.3.0.1 (such as when the equipment is inoperable, a variable is outside specified limits, or the unit is outside the Applicability of the ODCMS). If the interval specified by TR 7.3.0.2 is exceeded while the unit is in a MODE or other specified condition in the Applicability of the ODCMS, and the performance of the Test is not otherwise modified (refer to Examples 7.1.4-3 and 7.1.4-4), then TR 7.3.0.3 becomes applicable.

(continued)

Brunswick Units 1 and 2 7.1.4-2 Rev. 25

Frequency 7.1.4 ODCMS 7.1.4 Frequency (continued)

EXAMPLES EXAMPLE 7.1.4-1 (continued)

(continued)

If the interval as specified by TR 7.3.0.2 is exceeded while the unit is not in a MODE or other specified condition in the Applicability of the ODCMS for which performance of the TR is required, the Test must be performed within the Frequency requirements of TR 7.3.0.2 prior to entry into the MODE or other specified condition. Failure to do so would result in a violation of TR 7.3.0.4.

EXAMPLE 7.1.4-2 TEST REQUIREMENTS TEST FREQUENCY Verify flow is within limits. Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after

Ž 25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Example 7.1.4-2 has two Frequencies. The first is a one time performance Frequency, and the second is of the type shown in Example 7.1.4-1. The logical connector "AND" indicates that both Frequency requirements must be met. Each time reactor power is increased from a power level < 25% RTP toŽ_ 25% RTP, the Test must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The use of "once" indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by "AND").

This type of Frequency does not qualify for the extension allowed by TR 7.3.0.2.

(continued)

Brunswick Units 1 and 2 7.1.4-3 Rev. 25

Frequency 7.1.4 ODCMS 7.1.4 Frequency (continued)

EXAMPLES EXAMPLE 7.1.4-2 (continued)

(continued)

"Thereafter" indicates future performances must be established per TR 7.3.0.2, but only after a specified condition is first met (i.e., the "once" performance in this example). If reactor power decreases to < 25% RTP, the measurement of both intervals stops. New intervals start upon reactor power reaching 25% RTP.

EXAMPLE 7.1.4-3 TEST REQUIREMENTS TEST FREQUENCY NOTE

,Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after

,> 25% RTP.

L------------------------------------- 7 days Perform channel adjustment.

The interval continues whether or not the unit operation is < 25% RTP between performances.

As the Note modifies the required performance of the Test, it is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is < 25% RTP, this Note allows 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after power reaches > 25% RTP to perform the Test. The Test is still considered to be within the "specified Frequency." Therefore, ifthe Test were not performed within the 7 day interval (plus the extension allowed by TR 7.3.0.2), but operation was < 25% RTP, it would not constitute a failure of the TR or failure to meet the ODCMS. Also, no violation of TR 7.3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not exceed 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with power _> 25% RTP.

(continued)

Brunswick Units 1 and 2 7.1.4-4 Rev. 25

Frequency 7.1.4 ODCMS 7.1.4 Frequency (continued)

EXAMPLES EXAMPLE 7.1.4-3 (continued)

(continued)

Once the unit reaches 25% RTP, 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months would be allowed for completing the Test. If the Test were not performed within this 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months interval, there would then be a failure to perform a Test within the specified Frequency, and the provisions of TR 7.3.0.3 would apply.

EXAMPLE 7.1.4-4 TEST REQUIREMENTS TEST FREQUENCY r ---------------------------------------

NOTE

Only required to be met in MODE 1.

Verify leakage rates are within limits. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Example 7.1.4-4 specifies that the requirements of this Test do not have to be met until the unit is in MODE 1. The interval measurement for the Frequency of this Test continues at all times, as described in Example 7.1.4-1. However, the Note constitutes an "otherwise stated" exception to the Applicability of this Test. Therefore, if the Test were not performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (plus the extension allowed by TR 7.3.0.2) interval, but the unit was not in MODE 1, there would be no failure of the TR nor failure to meet the ODCMS. Therefore, no violation of TR 7.3.0.4 occurs when changing MODES, even with the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency exceeded, provided the MODE change was not made into MODE 1. Prior to entering MODE 1 (assuming again that the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency were not met), TR 7.3.0.4 would require satisfying the TR.

Brunswick Units 1 and 2 7.1.4-5 Rev. 25

7.2.0 Not used.

Brunswick Units 1 and 2 7.2.0-1 Rev. 25

ODCMS Applicability 7.3.0 7.3.0 OFFSITE DOSE CALCULATION MANUAL SPECIFICATION (ODCMS)

APPLICABILITY ODCMS 7.3.0.1 ODCMSs shall be met during the MODES or other specified conditions in the Applicability, except as provided in ODCMS 7.3.0.2.

ODCMS 7.3.0.2 Upon discovery of a failure to meet an ODCMS, the required Compensatory Measures of the associated Conditions shall be met, except as provided in ODCMS 7.3.0.5.

If the ODCMS is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Compensatory measure(s) is not required, unless otherwise stated.

ODCMS 7.3.0.3 Not used.

ODCMS 7.3.0.4 When an ODCMS is not met, entry into a MODE or other specified condition in the Applicability shall not be made except when the associated COMPENSATORY MEASURES to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time. This ODCMS shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with COMPENSATORY MEASURES, or that are part of a shutdown of the unit.

Exceptions to this ODCMS are stated in the individual ODCMSs. These exceptions allow entry into MODES or other specified conditions in the Applicability when the associated COMPENSATORY MEASURES to be entered allow unit operation in the MODE or other specified condition in the Applicability only for a limited period of time.

ODCMS 7.3.0.5 Equipment removed from service or declared inoperable to comply with COMPENSATORY MEASURES may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to ODCMS 7.3.0.2 for the system returned to service under administrative control to perform the required testing.

(continued)

Brunswick Units 1 and 2 7.3.0-1 Rev. 25

ODCMS Applicability 7.3.0 7.3.0 ODCMS APPLICABILITY (continued)

ODCMS 7.3.0.6 ODCMSs and associated COMPENSATORY MEASURES shall apply to both units except as follows:

a. Whenever the ODCMS refers to systems or components which are not shared by both units, the ODCMS and associated Applicability and COMPENSATORY MEASURES shall apply to each unit individually (e.g., in the event of an inoperability in a non-shared system, the appropriate COMPENSATORY MEASURES will apply only to the unit with the inoperable system);

b. Whenever the ODCMS only applies to one unit, this will be identified in the Applicability of the ODCMS; and

c. Whenever certain portions of the ODCMS, Applicability, or COMPENSATORY MEASURES contain operating parameters, setpoints, etc., which are different for each unit, this will be identified in parentheses, notes, or the body of the requirement.

Brunswick Units 1 and 2 7.3.0-2 Rev. 25

TR Applicability 7.3.0 7.3.0 TEST REQUIREMENT (TR) APPLICABILITY TR 7.3.0.1 TRs shall be met during the MODES or other specified conditions in the Applicability for individual ODCMSs, unless otherwise stated in the TR.

Failure to meet a Test whether such failure is experienced during the performance of the Test or between performances of the Test, shall be failure to meet the ODCMS. Failure to perform a Test within the specified Frequency shall be failure to meet the TRMS except as provided in TR 7.3.0.3. Tests do not have to be performed on inoperable equipment or variables outside specified limits.

TR 7.3.0.2 The specified Frequency for each TR is met ifthe Test is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.

For Frequencies specified as "once," the above interval extension does not apply. If a Completion Time requires periodic performance on a "once per ..." basis, the above Frequency extension applies to each performance after the initial performance.

Exceptions to this ODCMS are stated in the individual ODCMSs.

TR 7.3.0.3 If it is discovered that a Test was not performed within its specified Frequency, then compliance with the requirement to declare the ODCMS not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is less. This delay period is permitted to allow performance of the Test.

If the Test is not performed within the delay period, the ODCMS must immediately be declared not met, and the applicable Condition(s) must be entered.

When the Test is performed within the delay period and the Test is not met, the ODCMS must immediately be declared not met, and the applicable Condition(s) must be entered.

(continued)

Brunswick Units 1 and 2 7.3.0-3 Rev. 25

TR Applicability 7.3.0 7.3.0 TR APPLICABILITY (continued)

TR 7.3.0.4 Entry into a MODE or other specified condition in the Applicability of an ODCMS shall not be made unless the ODCMS's Tests have been met within their specified Frequency. This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with COMPENSATORY MEASURES or that are part of a shutdown of the unit.

TR 7.3.0.5 TRs shall apply to both units (e.g., a single Test performed at the specified Frequency will satisfy the TR for both units) except as follows:

a. Whenever the ODCMS refers to systems or components which are not shared by both units, the associated TR shall apply to each unit individually (e.g., individual tests must be performed on each of the two units' non-shared systems or components; a single Test on a non-shared system of one unit performed at the specified Frequency will not satisfy the TR for the non-shared system of the other unit);

b. Whenever a TR only applies to one unit, this will be identified by a note to the TR; and

c. Whenever certain portions of the TRs, contain test parameters, acceptance criteria, or frequencies which are different for each unit, this will be identified in parentheses, notes, or the body of the requirement.

Brunswick Units 1 and 2 7.3.0-4 Rev. 25

Radioactive Liquid Effluent Monitoring Instrumentation 7.3.1 7.3.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ODCMS 7.3.1 The radioactive liquid effluent monitoring instrumentation channels in Table 7.3.1-1 shall be OPERABLE.

NOTE The annunciator function may be removed from operation for performance of troubleshooting for up to 30 minutes provided the associated function maintains monitoring capability APPLICABILITY: In accordance with Table 7.3.1-1.

COMPENSATORY MEASURES r-------------------------------------------------------------------

NOTE Separate Condition entry is allowed for each required channel.

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. One or more radioactive A.1 Enter the Condition Immediately liquid effluent monitoring referenced in instrumentation channels Table 7.3.1-1 for the inoperable, channel.

B. As required by Required B.1 Perform TR 7.3.3.1 on two Prior to release Compensatory Measure A.1 independent samples of through the liquid and referenced in the batch to be released. radwaste effluent Table 7.3.1-1. AND line B.2 Verify the associated release rate calculations Pror to lease and the discharge valve through the liquid lineup using two qualified line members of the technical staff.

AND B.3 Restore the channel to 30 days OPERABLE status.

(continued)

Brunswick Units 1 and 2 7.3.1-1 Rev. 29 1

Radioactive Liquid Effluent Monitoring Instrumentation 7.3.1 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME C. As required by Required C.1 Estimate the flow rate Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Compensatory Measure A.1 through the associated during releases and referenced in pathway using pump through the Table 7.3.1-1. performance curves or associated line tank level indicators.

AND C.2 Restore the channel to 30 days OPERABLE status.

D. As required by Required D.1 Collect and analyze a grab Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Compensatory Measure A. 1 sample for gross and referenced in radioactivity (beta or Table 7.3.1-1. gamma) of the associated effluent. The LLD shall be

_<1.0 E-7 pICi/gm.

AND 30 days D.2 Restore the channel to OPERABLE status.

E. As required by Required E.1 Collect and analyze a grab Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Compensatory Measure A.1 sample for principal and referenced in gamma emitters per Table 7.3.1-1. Table 7.3.3-1.

AND 30 days E.2 Restore the channel to OPERABLE status.

(continued)

Brunswick Units 1 and 2 7.3.1-2 Rev. 25

Radioactive Liquid Effluent Monitoring Instrumentation 7.3.1 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME F. As required by F.1 Estimate the flow rate through the Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Required associated pathway using the Compensatory V-notch weir or another acceptable Measure A.1 and method.

referenced in Table 7.3.1-1.

F.2 Restore the channel to OPERABLE 30 days status.

G. As required by G.1 Estimate the tank liquid level. Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Required during all liquid Compensatory additions and Measure A.1 and deletions to and from referenced in the tank Table 7.3.1-1.

AND G.2 Restore the channel to OPERABLE 30 days status.

H. Required H.1 Suspend effluent releases via the Immediately Compensatory associated pathway.

Measure B.1, B.2, AND C.1, D.1, E.1, F.1, or G.1 and H.2 associated Completion Time NOTE not met. :_:Only applicable for Function 6.

Suspend liquid additions to the Immediately Condensate Storage Tank.

(continued)

Brunswick Units 1 and 2 7.3.1-3 Rev. 25

Radioactive Liquid Effluent Monitoring Instrumentation 7.3.1 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME Required Compensatory 1.1 Prepare and submit, in the Upon submittal of Measure B.3, C.2, D.2, E.2, Radioactive Effluent current calendar F.2, G.2, or J.2 and Release Report, the year Radioactive associated Completion Time reason the channel was Effluent Release not met. not restored to Report OPERABLE status within 30 days.

J. As required by Required J.1 Estimate the flow rate Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Compensatory Measure A. 1 through the associated and referenced in Table pathway using the 7.3.1-1. Parshall flume or another acceptable method.

AND J.2 Restore the channel to 30 days OPERABLE status.

TEST REQUIREMENTS NOTE Refer to Table 7.3.1-1 to determine which TRs apply for each Radioactive Liquid Effluent Monitoring Instrumentation Function.

TEST FREQUENCY TR 7.3.1.1 NOTE For Function 6, only required to be met during liquid additions to the tank.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Perform CHANNEL CHECK.

TR 7.3.1.2 NOTE Only required to be met during continuous, periodic, or batch releases.

bh-r--------------------

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Verify indication of flow.

(continued)

Brunswick Units 1 and 2 7.3.1-4 Rev. 35

Radioactive Liquid Effluent Monitoring Instrumentation 7.3.1 TEST REQUIREMENTS (continued)

TEST FREQUENCY TR 7.3.1.3 Perform SOURCE CHECK. 31 days TR 7.3.1.4 Perform CHANNEL FUNCTIONAL TEST, including 92 days demonstration of automatic isolation of the pathway and control room annunciation in response to any of the following:

a. Alarm/trip setpoint exceeded.

b. Circuit failure.

c. Downscale failure.

d. Instrument controls not set in "operate" mode.

TR 7.3.1.5 Perform CHANNEL FUNCTIONAL TEST. 92 days TR 7.3.1.6 Perform CHANNEL FUNCTIONAL TEST, including 92 days demonstration of control room annunciation in response to any of the following:

a. Alarm/trip setpoint exceeded.

b. Circuit failure.

c. Downscale failure.

d. Instrument controls not set in "operate" mode.

(continued)

Brunswick Units 1 and 2 7.3.1-5 Rev. 26

Radioactive Liquid Effluent Monitoring Instrumentation 7.3.1 TEST REQUIREMENTS (continued)

TEST FREQUENCY TR 7.3.1.7 NOTE For Functions 1 and 3, previously established calibration procedures or sources that have been related to the initial CHANNEL CALIBRATION shall be used. 24 months Perform CHANNEL CALIBRATION.

Brunswick Units 1 and 2 7.3.1-6 Rev. 25

Radioactive Liquid Effluent Monitoring Instrumentation 7.3.1 Table 7.3.1-1 (page 1 of 1)

Radioactive Liquid Effluent Monitoring Instrumentation FUNCTION (a) APPLICABLE REQUIRED CONDITIONS TEST ALARM/

MODES OR CHANNELS REFERENCED REQUIREMENTS TRIP OTHER PER FROM REQUIRED SETPOINT SPECIFIED FUNCTION COMPENSATORY VALUE CONDITIONS MEASURES A.1

1. Liquid Radwaste Radioactivity At all times 1 B TR 7.3.1.1 (c)

Effluent Monitor (b) TR 7.3.1.3 TR 7.3.1.4 TR 7.3.1.7

2. Liquid Radwaste Effluent Flow At all times 1 C TR 7.3.1.2 NA Measurement Device TR 7.3.1.5 TR 7.3.1.7

3. Main Service Water System At all times 1 D TR 7.3.1.1 (c)

Effluent Radioactivity Monitor TR 7.3.1.3 TR 7.3.1.6 TR 7.3.1.7

4. Stabilization Pond Effluent (d) 1 E TR 7.3.1.1 NA (e)

Composite Sampler TR 7.3.1.5 TR 7.3.1.7

5. Stabilization Pond Effluent (d) 1 F TR 7.3.1.1 NA Flow Measurement Device TR 7.3.1.5 TR 7.3.1.7

6. Condensate Storage Tank At all times 1 G TR 7.3.1.1 NA Level Indicating Device TR 7.3.1.5 TR 7.3.1.7

7. Groundwater Extraction (d) 1 E TR 7.3.1.1 NA Effluent Composite Sampler TR 7.3.1.5 TR 7.3.1.7

8. Groundwater Extraction (d) 1 J TR 7.3.1.1 NA Effluent Flow Measurement TR 7.3.1.5 Device TR 7.3.1.7

9. Stabilization Facility Effluent (d) 1 E TR 7.3.1.1 NA (h)

Composite Sampler TR 7.3.1.5 TR 7.3.1.7

10. Stabilization Facility Effluent (d) 1 J TR 7.3.1.1 NA Flow Measurement Device TR 7.3.1.5 TR 7.3.1.7 (a) Specific instrumentation identification numbers are provided in Appendix E.

(b) Provides alarm and automatic termination of release.

(c) Alarm/trip setpoints shall be determined in accordance with ODCM methodology and set to ensure the limits of ODCMS 7.3.3, "Concentration-Liquid Effluents," are not exceeded.

(d) At all times other than when the line is valved out and locked.

(e) Flow Totalizer 2-DST-FQIS-5026 provides a trip signal to the composite sampler that will initiate sampling.

(0 1(2) CO-LIT-1160 provides local level indication and also provides a signal to 1(2) CO-LI-1160A and 1(2) CO-LI-1160B.

(g) Flow Measurement Device O-GWE-FIT-1 directly triggers the composite sampler.

(h) Flow Measurement Device 0-SDSF-FIT-2 directly triggers the composite sampler.

Brunswick Units 1 and 2 7.3.1-7 Rev. 35

Radioactive Gaseous Effluent Monitoring Instrumentation 7.3.2 7.3.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ODCMS 7.3.2 The radioactive gaseous effluent monitoring instrumentation channels in Table 7.3.2-1 shall be OPERABLE.

NOTE The annunciator function may be removed from operation for performance of troubleshooting for up to 30 minutes provided the associated function maintains monitoring capability. If removing the annunciator for the 1/2-CAC-AT-1264 refer to ODCM Bases 7.3.2.

APPLICABILITY: In accordance with Table 7.3.2-1.

COMPENSATORY MEASURES r-----------------------------------------------------

NOTE Separate Condition entry is allowed for each required channel.

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. One or more radioactive A.1 Enter the Condition Immediately gaseous effluent monitoring referenced in instrumentation channels Table 7.3.2-1 for the inoperable, channel.

B. As required by Required B.1 Take a grab sample at the Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Compensatory Measure A.1 associated sample and referenced in location.

Table 7.3.2-1. AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after B.2 Analyze the grab sample completion of required by Required Required Compensatory Compensatory Measure B.1 for gross Measure B.1 noble gas activity.

AND 30 days B.3 Restore the channel to OPERABLE status.

(continued)

Brunswick Units 1 and 2 7.3.2-1 Rev. 29 1

Radioactive Gaseous Effluent Monitoring Instrumentation 7.3.2 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME C. As required by Required C.1.1 Initiate actions to establish Immediately Compensatory Measure A.1 auxiliary sampling and referenced in equipment to continuously Table 7.3.2-1. collect samples from the associated effluent release pathway as required by Table 7.3.7-1.

OR C.1.2 NOTE Only applicable for ODCM

test requirements, sample analysis, or system purging. Reference ODCMS 7.3.0.5 for post maintenance test 45 minutes requirements.

Initiate continuous sample collection from associated release pathway as required by Table 7.3.7-1 with auxiliary sampling equipment.

30 days AND C.2 Restore the channel to OPERABLE status.

(continued)

Brunswick Units 1 and 2 7.3.2-2 Rev. 25

COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME D. As required by Required D.1 Estimate the flow rate Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Compensatory Measure A.1 through the associated and referenced in pathway.

Table 7.3.2-1. AND D.2 Restore the channel to 30 days OPERABLE status.

E. Required Compensatory E.1 Suspend effluent releases Immediately Measure B.1, B.2, C.1.1, via the associated C.1.2, and D.1 and pathway.

associated Completion Time not met.

(continued)

Brunswick Units 1 and 2 7.3.2-3 Rev. 25

Radioactive Gaseous Effluent Monitoring Instrumentation 7.3.2 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME F. As required by Required NOTE Compensatory Measure A.1 :Required Compensatory and referenced in ,Measures F.1 and F.2 are only Table 7.3.2-1. :applicable iftwo channels are

inoperable in the operating

recombiner train.

F. 1 Take a grab sample from the operating recombiner Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months train.

AND F.2 Analyze the grab sample 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after required by Required completion of Compensatory Required Measure F.1. Compensatory AND Measure F.1 F.3 Verify proper functioning of the operating In accordance with recombiner train by approved monitoring recombiner procedures temperature.

AND F.4 Restore the channel(s) to 30 days OPERABLE status.

G. Required Compensatory G.1 Suspend operation of the Immediately Measure F.1, F.2, or F.3 and associated recombiner associated Completion Time train.

not met.

(continued)

Brunswick Units 1 and 2 7.3.2-4 Rev. 25

Radioactive Gaseous Effluent Monitoring Instrumentation 7.3.2 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME H. Required Compensatory H.1 Prepare and submit in the Upon submittal of Measure B.3, C.2, D.2, Radioactive Effluent current calendar or F.4 and associated Release Report, the year Radioactive Completion Time not met. reason the channel was Effluent Release not restored to Report OPERABLE status within 30 days.

1. As required by Required 1.1 Verify GASEOUS Immediately Compensatory Measure A.1 RADWASTE and referenced in TREATMENT SYSTEM is Table 7.3.2-1. not bypassed.

AND Immediately 1.2 Verify the main stack effluent noble gas monitor is OPERABLE.

AND 1.3 ---- NOTE----------

If the SJAE grab sample cannot be obtained at the normal sample point the sample can be obtained at the inlet to the Gaseous Radwaste Treatment System and the results decay corrected back to Once within normal location to verify 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months the activity level at the AND SJAE. Every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter Take a grab sample and analyze to verify that the 30 days noble gas gross gamma activity rate is < 243,600 pCi/second AND 1.4 Restore the channel to OPERABLE status.

(continued)

Brunswick Units 1 and 2 7.3.2-5 Rev. 33 I

Radioactive Gaseous Effluent Monitoring Instrumentation 7.3.2 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME J. Required Compensatory J.1 Be in MODE 2. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Measure and associated AND AND Completion Time of Condition I not met. J.2 Prepare and submit in the Upon submittal of Radioactive Effluent current calendar Release Report, the year Radioactive reason the channel was Effluent Release not restored to Report OPERABLE status within 30 days.

I K. As required by Required K.1 Suspend effluent releases Immediately Compensatory Measure A.1 via the associated and referenced in pathway.

Table 7.3.2-1.

TEST REQUIREMENTS NOTE Refer to Table 7.3.2-1 to determine which TRs apply for each Radioactive Gaseous Effluent Monitoring Instrumentation Function.

TEST FREQUENCY TR 7.3.2.1 Perform CHANNEL CHECK. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months TR 7.3.2.2 Perform CHANNEL CHECK. .7 days TR 7.3.2.3 Perform SOURCE CHECK. 31 days TR 7.3.2.4 Perform CHANNEL FUNCTIONAL TEST. 31 days (continued)

I Brunswick Units 1 and 2 7.3.2-6 Rev. 33

Radioactive Gaseous Effluent Monitoring Instrumentation 7.3.2 TEST REQUIREMENTS (continued)

TEST FREQUENCY TR 7.3.2.5 Perform CHANNEL FUNCTIONAL TEST, including 92 days demonstration of control room annunciation in response to any of the following:

a. Alarm/trip setpoint exceeded.

b. Downscale failure.

c. Instrument controls not set in "operate" mode.

TR 7.3.2.6 Perform CHANNEL FUNCTIONAL TEST. 92 days TR 7.3.2.7 Perform CHANNEL FUNCTIONAL TEST; including 92 days demonstration of control room annunciation in response to any of the following:

a. Alarm/trip setpoint exceeded.

b. Downscale failure.

TR 7.3.2.8 Perform CHANNEL FUNCTIONAL TEST including 92 days control room annunciation in response to any of the following:

a. Alarm/trip setpoint exceeded.

b. Circuit failure.

c. Downscale failure. I

d. Instrument controls not set in "operate" mode.

(continued)

Brunswick Units 1 and 2 7.3.2-7 Rev. 26 1

Radioactive Gaseous Effluent Monitoring Instrumentation 7.3.2 TEST REQUIREMENTS (continued)

TEST FREQUENCY TR 7.3.2.9 Perform CHANNEL CALIBRATION. The CHANNEL 92 days CALIBRATION shall include the use of standard gas samples containing a nominal:

a. Two volume percent hydrogen, balance nitrogen; and

b. Four volume percent hydrogen, balance nitrogen.

TR 7.3.2.10 NOTE For Functions 1.a, 2.a, 3.a, 4, and 6, previously established calibration procedures or sources that have been related to the initial CHANNEL CALIBRATION shall be used. 24 months Perform CHANNEL CALIBRATION.

Brunswick Units 1 and 2 7.3.2-8 Rev. 25

Radioactive Gaseous Effluent Monitoring Instrumentation 7.3.2 Table 7.3.2-1 (page 1 of 4)

Radioactive Gaseous Effluent Monitoring Instrumentation FUNCTION (a) APPLICABLE REQUIRED CONDITIONS TEST ALARM]

MODES OR CHANNELS REFERENCED REQUIREMENTS TRIP OTHER PER FROM REQUIRED SETPOINT SPECIFIED FUNCTION COMPENSATORY VALUE CONDITIONS MEASURES A.1 Main Stack Monitoring System

a. Noble Gas Activity At all times 1 B TR 7.3.2.1 (b)

Monitor TR 7.3.2.3 TR 7.3.2.5 TR 7.3.2.10

b. Iodine Sampler At all times 1 C TR 7.3.2.2 NA Cartridge

c. Particulate Sampler At all times 1 C TR 7.3.2.2 NA Filter

d. System Effluent Flow At all times 1 D TR 7.3.2.1 NA Rate Measurement TR 7.3.2.6 Device TR 7.3.2.10

e. Low Range Sampler At all times 1 D TR 7.3.2.1 (c)

Flow Rate TR 7.3.2.6 Measurement Device TR 7.3.2.10

f. Mid/High Range (m) 1 D TR 7.3.2.6 N/A Sampler Flow Rate TR 7.3.2.10 Measurement Device

2. Reactor Building Ventilation Monitoring System

a. Noble Gas Activity At all times 1 B TR 7.3.2.1 (b)

Monitor TR 7.3.2.3 TR 7.3.2.7 TR 7.3.2.10

b. Iodine Sampler At all times 1 C TR 7.3.2.2 NA Cartridge

c. Particulate Sampler At all times 1 C TR 7.3.2.2 NA Filter

d. System Effluent Flow At all times 1 D TR 7.3.2.1 NA Rate Measurement TR 7.3.2.6 Device TR 7.3.2.10 (continued)

(a) Specific instrumentation identification numbers are provided in Appendix E.

(b) Alarm/trip setpoints shall be determined in accordance with ODCM methodology and set to ensure the limits of ODCMS 7.3.7, "Dose Rate-Gaseous Effluents," are not exceeded.

(c) Alarm/trip setpoints shall be determined in accordance with associated design specification(s) and set to ensure the limits of ODCMS 7.3.7, "Dose Rate-Gaseous Effluents," are not exceeded.

(m) During Mid/High Range System operation Brunswick Units 1 and 2 7.3.2-9 Rev. 33

Radioactive Gaseous Effluent Monitoring Instrumentation 7.3.2 Table 7.3.2-1 (page 2 of 4)

Radioactive Gaseous Effluent Monitoring Instrumentation FUNCTION (") APPLICABLE REQUIRED CONDITIONS TEST ALARM/TRIP MODES OR CHANNELS REFERENCED REQUIREMENTS SETPOINT OTHER PER FROM REQUIRED VALUE SPECIFIED FUNCTION COMPENSATORY CONDITIONS MEASURES A.1

2. Reactor Building Ventilation Monitoring System (continued)

e. Sampler Flow Rate At all times 1 D TR 7.3.2.1 (c)

Measurement Device TR 7.3.2.6 TR 7.3.2.10

3. Turbine Building Ventilation Monitoring System

a. Noble Gas Activity At all times 1 B TR 7.3.2.1 (b)

Monitor TR 7.3.2.3 TR 7.3.2.5 TR 7.3.2.10

b. Iodine Sampler At all times 1 C TR 7.3.2.2 NA Cartridge

c. Particulate Sampler At all times 1 C TR 7.3.2.2 NA Filter

d. System Effluent Flow At all times 1 D TR 7.3.2.1 NA Rate Measurement TR 7.3.2.6 Device TR 7.3.2.10

e. Low Range Sampler At all times I D TR 7.3.2.1 (c)

Flow Rate TR 7.3.2.6 Measurement Device TR 7.3.2.10

f. Mid/High Range (m) 1 D TR 7.3.2.6 NA Sampler Flow Rate TR 7.3.2.10 Measurement Device

4. Main Condenser Off-Gas (e) 1 B TR 7.3.2.1 (b)

Treatment System Noble TR 7.3.2.3 Gas Activity Monitor (d) TR 7.3.2.6 (Downstream of AOG TR 7.3.2.10 Treatment System)

(continued)

(a) Specific instrumentation identification numbers are provided in Appendix E.

(b) Alarm/trip setpoints shall be determined in accordance with ODCM methodology and set to ensure the limits of ODCMS 7.3.7, "Dose Rate-Gaseous Effluents," are not exceeded.

(c) Alarm/trip setpoints shall be determined in accordance with associated design specification(s) and set to ensure the limits of ODCMS 7.3.7, "Dose Rate-Gaseous Effluents," are not exceeded.

(d) Provides alarm.

(e) During Main Condenser Off-Gas Treatment System operation (m) During Mid/High Range System operation Brunswick Units 1 and 2 7.3.2-10 Rev. 33 1

Radioactive Gaseous Effluent Monitoring Instrumentation 7.3.2 Table 7.3.2-1 (page 3 of 4)

Radioactive Gaseous Effluent Monitoring Instrumentation FUNCTION ( APPLICABLE REQUIRED CONDITIONS TEST ALARM/

MODES OR CHANNELS REFERENCED REQUIREMENTS TRIP OTHER PER FROM REQUIRED SETPOINT SPECIFIED FUNCTION COMPENSATORY VALUE CONDITIONS MEASURES A.1

5. Main Condenser Off-Gas Treatment System Explosive Gas Monitoring System

a. Recombiner Train A (I) 2 F TR 7.3.2.1 (c)

TR 7.3.2.4 TR 7.3.2.9

b. Recombiner Train B (I) 2 F TR 7.3.2.1 (c)

TR 7.3.2.4 TR 7.3.2.9

6. Main Condenser Air Ejector (f) 1 I TR 7.3.2.1 (b)

Noble Gas Radioactivity TR 7.3.2.3 Monitor (k) (Prior to input to TR 7.3.2.8 Treatment System) TR 7.3.2.10

7. Hot Shop Ventilation Monitoring System

a. Iodine Sampler (j) 1 K TR 7.3.2.2 NA Cartridge

b. Particulate Sampler (j) 1 K TR 7.3.2.2 NA Filter

c. Sampler Flow Rate (j) K TR 7.3.2.1 NA Measurement Device TR 7.3.2.2 (continued)

(a) Specific instrumentation identification numbers are provided in Appendix E.

(b) Alarm/trip setpoints shall be determined in accordance with ODCM methodology and set to ensure the limits of ODCMS 7.3.7, "Dose Rate--Gaseous Effluents," are not exceeded.

(c) Alarm/trip setpoints shall be determined in accordance with associated design specification(s) and set to ensure the limits of ODCMS 7.3.7, "Dose Rate--Gaseous Effluents," are not exceeded.

(f) During operation of the main condenser air ejector (j) During operation of the Hot Shop Ventilation System (k) Provides Hi and Hi Hi alarm I (I) During associated recombiner train operation Brunswick Units 1 and 2 7.3.2-11 Rev. 36 1

Radioactive Gaseous Effluent Monitoring Instrumentation 7.3.2 Table 7.3.2-1 (page 4 of 4)

Radioactive Gaseous Effluent Monitoring Instrumentation FUNCTION ( APPLICABLE REQUIRED CONDITIONS TEST ALARM/

MODES OR CHANNELS REFERENCED REQUIREMENTS TRIP OTHER PER FROM REQUIRED SETPOINT SPECIFIED FUNCTION COMPENSATORY VALUE CONDITIONS MEASURES A.1

8. Radioactive Materials Container and Storage Building Decontamination Facility

a. Iodine Sampler (g) 1 K TR 7.3.2.1 NA Cartridge

b. Particulate Sampler (g) 1 K TR 7.3.2.1 NA 0 Filter

c. Sampler Flow Rate (g) 1 K TR 7.3.2.1 NA Measurement Device

9. Low Level Warehouse

a. Particulate Sampler Filter (h) 1 K TR 7.3.2.2 NA )

(a) Specific instrumentation identification numbers are provided in Appendix E.

(g) During operation of the Radioactive Materials Container and Storage Building Decontamination Facility.

(h) During operation of the Low Level Warehouse ventilation system.

(i) Local alarm.

Brunswick Units 1 and 2 7.3.2-12 Rev. 32 1

Concentration - Liquid Effluents 7.3.3 7.3.3 CONCENTRATION-LIQUID EFFLUENTS ODCMS 7.3.3 The concentration of radioactive material released to UNRESTRICTED AREAS after dilution in the discharge canal shall be limited to:

a. 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; and

b. 2 x 10-4jiCi/ml total activity concentration for all dissolved or entrained noble gases.

APPLICABILITY: At all times.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Concentration of radioactive A.1 Initiate action to restore Immediately material released to concentration to within UNRESTRICTED AREAS limits.

not within limits.

TEST REQUIREMENTS TEST FREQUENCY TR 7.3.3.1 Verify the concentration of radioactive material In accordance with released to UNRESTRICTED AREAS is within limits. Table 7.3.3-1 (continued)

Brunswick Units 1 and 2 7.3.3-1 Rev. 25

Concentration - Liquid Effluents 7.3.3 TEST REQUIREMENTS (continued)

TEST FREQUENCY TR 7.3.3.2 NOTE Only required to be performed if service water samples analyzed in accordance with Table 7.3.3-1 indicate concentrations of any gamma-emitting radionuclides greater than the trigger level of 5 x 106LCi/ml.

In accordance with Verify concentration of radioactive material released to Table 7.3.3-2 for UNRESTRICTED AREAS is within limits. liquid wastes exceeding the trigger level Brunswick Units 1 and 2 7.3.3-2 Rev. 35

Concentration - Liquid Effluents 7.3.3 Table 7.3.3-1 (page 1 of 3)

Radioactive Liquid Waste Sampling and Analysi Program LIQUID RELEASE SAMPLE SAMPLE ANALYSIS SAMPLE SAMPLE LOWER TYPE FREQUENCY FREQUENCY ANALYSIS LIMIT OF TYPE DETECTION (LLD) (0)(e) 1 Sample Tanks, Prior to release of Prior to release of each Principal Gamma 5 x 10-7(b) PCi/mI Detergent Drain each batch batch Emitters (a)

Tank, and Salt Water 1-131 1 x 10-6pCi/ml Release Tanks (Batch Release), (h)

Prior to release of one 31 days Dissolved and 1 x 10l5pCi/ml batch once per entrained gases AND 31 days (Gamma Emitters)

Circulating Water Pit Prior to release of 31 days Gross Alpha 1 x 10,7ýLCi/ml each batch Composite(c) H-3 1 x 10%.Ci/ml Prior to release of 92 days Sr-89, Sr-90 5 x 10'p.Ci/ml each batch Composite(c) Fe-55 1 x 10-6PCi/mI

2. Stabilization Pond Prior to each release Prior to each release Principal Gamma 5 x 10.1 ( )1 I.Ci/mI Emitters (g)

H-3 1 x 10s pCi/mI AND AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during periods of release M periods of release M After completion of After completion of Sr-89, Sr-90 5x 10.a pCi/ml each release (' each release (i) Fe-55 1x 1067 pCi/mI Gross Alpha 1x 10. pCi/mI Principal Gamma 5x 10.7 pCi/ml Emitters (g)

H-3 1 x 10"1 pCi/ml

3. Service Water (d) 7 days during system 7 days during system Principal Gamma 5 x 10.7 pCi/ml"b)

(Potential operation operation Emitters (g)

Continuous Release)

4. Groundwater Prior to each releasea) Grab Sample Principal Gamma 5 x 10.7 pCi/ml Extraction System 7 day Composite(c) Emitters(g)

(Continuous 1-131 1 x 106 pCi/mI Release) AND H-3 1 x 10.f pCi/ml 7 days during system operation(c)0D 31 day Composite(c) Gross Alpha 1 x 10.7 pCi/ml 92 day Sr-89, Sr-90 5 x 10.8 pCi/mI Composite(c) Fe-55 1 x 10e pCi/mI

5. Stabilization Facility Prior to each release Pnor to each release Principal Gamma 5 x 10-7 (b) pCi/ml Emitters W H-3 1 x 10.5 pCi/mI AND AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during periods of release(O periods of release(O After completion of After completion of Sr-89, Sr-90 5 x 10.8 pCi/mI 1

each release(i) each release( ) Fe-55 1 x 10e pCi/mI Gross Alpha 1 x 107 pCi/ml Principal Gamma 5 x i0. pCi/ml Emitters (1)

H-3 1 x 10.5 pCi/mI Brunswick Units 1 and 2 7.3.3-3 Rev. 35

Concentration - Liquid Effluents 7.3.3 Table 7.3.3-1 (page 2 of 3)

Radioactive Liquid Waste Sampling and Analysis Program LIQUID RELEASE SAMPLE SAMPLE ANALYSIS SAMPLE SAMPLE LOWER TYPE FREQUENCY FREQUENCY ANALYSIS LIMIT OF TYPE DETECTION (LLD) (a)(e)

6. Storm Drain Prior to each release(k) Prior to each release(k) Principal Gamma 5 x 107 (b)p*Ci/ml Collection Basin Emitters (g)

H-3 1 x 10 5 pCi/mI AND AND During each release During each release Sr-89, Sr-90 5x 10-8 pCi/ml Fe-55 1x 108 pCi/ml Gross Alpha 1x 107 pCi/ml Principal Gamma 5x 1077 pCi/ml Emitters (g)

H-3 1 x 10"5 pCi/ml (a) The detectability limits for activity analyses are based on technical feasibility limits and on the potential significance in the environment of the quantities released. For some nuclides, lower detection limits may be readily achievable; and when nuclides are measured below the stated limits, they should also be reported.

(b) When operational limitations preclude specific gamma radionuclide analysis of each batch, gross radioactivity measurements shall be made to estimate the quantity and concentrations of radioactive material released in the batch; and a weekly sample composited from proportional aliquots from each batch released during the week shall be analyzed for principal gamma-emitting radionuclides.

(c) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.

(d) The service water liquid release type represent potential release pathways and not an actual release pathway. Test of this pathway is intended to alert the plant to a potential problem; analysis for principal gamma emitters should be sufficient to meet this intent. If analysis for principal gamma emitters indicates a problem (i.e., exceeds the trigger level of 5x106 ýiCi/ml), then complete sampling and analyses shall be performed as per Table 7.3.3-2.

(e) The lower limit of detectability (LLD) is the smallest concentration of a radioactive material in an unknown sample that will be detected with a 95% probability with a 5%

probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

LLD = 4.66 Ob t

E. V.2.22 x 106 *Y.e-0-ie)

Where:

LLD is the "a priori" lower limit of detection as defined above (as microcuries per unit mass or volume)

-*b (N/tb)y"

= standard deviation of background (cpm)

Brunswick Units 1 and 2 7.3.3-4 Rev. 37

Concentration - Liquid Effluents 7.3.3 Table 7.3.3-1 (page 3 of 3)

Radioactive Liquid Waste Sampling and Analysis Program Radioactive Liquid Waste Sampling and Analysis Program N = background count rate (cpm) tb = time background counted for (min)

E = counting efficiency, as counts per disintegration V = volume or mass of sample 2.22 x 106 = conversion factor (dpm/microcurie)

Y = fractional radiochemical yield Xi radioactive decay constant of ith nuclide (sec1 )

te = elapsed time between sample collection and counting (sec)

Typical values of E, V, Y, and te should be used in the calculation. It should be recognized that the LLD is defined as an "a prio" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement.

(f) The stabilization pond and stabilization facility are typically released over a several-day period. The pond and facility are to be sampled and analyzed prior to commencing a release. When composite sampling instrumentation is OPERABLE, daily grab sampling of the stabilization pond or stabilization facility effluent will not be required during release and the composite sample will be analyzed at the end of the release.

(g) The principal gamma emitters for which the LLD specifications apply exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report.

(h) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated and then thoroughly mixed to assure representative sampling.

(i) Sr-89, Sr-90, Fe-55 and Gross Alpha analyses are to be performed on the composite sample at the end of the release period.

(j) These requirements only apply if the Groundwater Extraction (GWE) System is being released directly to the intake canal. During periods when the GWE System is directed to the Stabilization Pond or Stabilization Facility sampling of the GWE System is not required.

(k) Releasing water directly to the discharge canal through the storm drain basin overflow valves is prohibited by the National Pollutant Discharge Elimination System (NPDES) permit except where unavoidable to prevent loss of life, personnel injury, or severe property damage. Sometimes due to unanticipated inclement weather a pre-release sample is not able to be obtained, however, there is a composite sampler that samples the basin continuously and can be used for the pre-release sample.

Brunswick Units 1 and 2 7.3.3-5 Rev. 37

Concentration - Liquid Effluents 7.3.3 Table 7.3.3-2 (page 1 of 3)

Radioactive Liquid Waste Sampling and Analysis Program for Potential Release Pathways Which Have Exceeded Trigger Levels LIQUID RELEASE SAMPLE SAMPLE ANALYSIS SAMPLE SAMPLE LOWER TYPE FREQUENCY FREQUENCY ANALYSIS LIMIT OF TYPE DETECTION (LLD) OX))

1 Service Water 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (d) 7 days Principal Gamma 5 x 10.' 0(b)iCi/ml (Continuous Composite(.) Emitters M" Release) (g) 1-131 1 x 10laCi/ml 31 days 31 days Dissolved and 1 x 105iCi/ml Grab Sample entrained gases (Gamma Emitters) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (d) 31 days Gross Alpha 1 x 107pCi/ml Composite(')

H-3 1 x 10 .Ci/ml 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (d) 92 days Sr-89, Sr-90 5 x 10 .iCi/ml Composite(')

Fe-55 1 x 10 pCi/ml Brunswick Units 1 and 2 7.3.3-6 Rev. 35

Concentration - Liquid Effluents 7.3.3 Table 7.3.3-2 (page 2 of 3)

Radioactive Liquid Waste Sampling and Analysis Program for Potential Release Pathways Which Have Exceeded Trigger Levels (a) The detectability limits for activity analyses are based on technical feasibility limits and on the potential significance in the environment of the quantities released. For some nuclides, lower detection limits may be readily achievable; and when nuclides are measured below the stated limits, they should also be reported.

(b) When operational limitations preclude specific gamma radionuclide analysis of each batch, gross radioactivity measurements shall be made to estimate the quantity and concentrations of radioactive material released in the batch; and a weekly sample composited from proportional aliquots from each batch released during the week shall be analyzed for principal gamma-emitting radionuclides.

(c) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.

(d) Until such time as continuous proportional composite samplers are installed on the service water discharge line, daily grab sampling of the service water effluent will be required for use in making up the composite.

(e) The lower limit of detectability (LLD) is the smallest concentration of a radioactive material in an unknown sample that will be detected with a 95% probability with a 5%

probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

LLD = 4.66 ab E- V-2.22 x 106 -Y-e-< te)

Where:

LLD is the "a priori" lower limit of detection as defined above (as microcuries per unit mass or volume) ab - (N/tb)'A

= standard deviation of background (cpm)

N = background count rate (cpm)

Brunswick Units 1 and 2 7.3.3-7 Rev. 25 1

Concentration - Liquid Effluents 7.3.3 Table 7.3.3-2 (page 3 of 3)

Radioactive Liquid Waste Sampling and Analysis Program for Potential Release Pathways Which Have Exceeded Trigger Levels tb = time background counted for (min)

E = counting efficiency, as counts per disintegration V = volume or mass of sample 2.22 x 106 = conversion factor (dpm/microcurie)

Y = fractional radiochemical yield X= radioactive decay constant of ith nuclide (set")

te = elapsed time between sample collection and counting (sec)

Typical values of E, V, Y, and te should be used in the calculation. It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement.

(f) The principal gamma emitters for which the LLD specifications apply exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report.

(g) A continuous release is the discharge of liquid waste of a nondiscrete volume, e.g., from a volume or a system that has an input flow during the continuous release.

Brunswick Units 1 and 2 7.3.3-8 Rev. 31 1

Dose-Liquid Effluents 7.3.4 7.3.4 DOSE-LIQUID EFFLUENTS ODCMS 7.3.4 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS shall be limited to:

a. < 3 mrem to the total body and < 10 mrem to any organ during any calendar quarter; and

b. < 6 mrem to the total body and < 20 mrem to any organ during any calendar year.

APPLICABILITY: At all times.

COMPENSATORY MEASURES NOTE Enter applicable Conditions and Required Compensatory Measures of ODCMS 7.3.14, "Total Dose (40 CFR 190)," when liquid effluent dose results in exceeding an annual total dose limit.

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. A.1 Submit a Special Report to 30 days r----------- the NRC that identifies NOTE causes for exceeding Required Compensatory limits, corrective actions Measure A.1 shall be taken to reduce releases, completed if this Condition is and corrective actions to Lentered. assure that subsequent Calculated dose from the releases will be in release of radioactive compliance with the materials in liquid effluents required limits.

to UNRESTRICTED AREAS not within limits.

Brunswick Units 1 and 2 7.3.4-1 Rev. 25

Dose-Liquid Effluents 7.3.4 TEST REQUIREMENTS TEST FREQUENCY TR 7.3.4.1 Verify the cumulative dose contributions from liquid 31 days effluents for the current calendar quarter and current calendar year are within limits in accordance with the methodology and parameters in the ODCM.

Brunswick Units 1 and 2 7.3.4-2 Rev. 25

Liquid Radwaste Treatment System 7.3.5 7.3.5 LIQUID RADWASTE TREATMENT SYSTEM ODCMS 7.3.5 The Liquid Radwaste Treatment System shall be used to reduce radioactive materials in liquid wastes prior to their discharge.

APPLICABILITY: During release of liquid radioactive water when the projected doses due to the liquid effluent, from the site to UNRESTRICTED AREAS, would exceed 0.12 mrem to the total body or 0.4 mrem to any organ in a 31 day period.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. A.1 Submit a Special Report to 30 days

......................... the NRC that includes NOTE explanation of why liquid Required Compensatory radwaste was being Measure A.1 shall be discharged without completed if this Condition is treatment, identification of entered. any required inoperable Liquid waste being equipment or subsystem discharged and the reasons the for the treatment without h inoperability, corrective actions taken to restore the required inoperable equipment to OPERABLE status, and a summary description of the corrective actions taken to prevent recurrence.

Brunswick Units 1 and 2 7.3.5-1 Rev. 25

Liquid Radwaste Treatment System 7.3.5 TEST REQUIREMENTS TEST FREQUENCY TR 7.3.5.1 Verify required valve alignments to ensure Liquid Prior to release of Radwaste Treatment System is in use to reduce liquid effluents radioactive materials in liquid waste.

31 days NOTE Only required to be performed when the Liquid Radwaste Treatment System is not in use when performing Liquid Radwaste Releases.

L--------------------------------------------------------

TR 7.3.5.2 Determine the projected doses due to liquid releases from the site to UNRESTRICTED AREAS in accordance with the methodology and parameters in the ODCM.

Brunswick Units 1 and 2 7.3.5-2 Rev. 37

Liquid Holdup Tanks 7.3.6 7.3.6 LIQUID HOLDUP TANKS ODCMS 7.3.6 The quantity of radioactive material, excluding tritium and dissolved or entrained gases, suspended in solution in the condensate storage tank, auxiliary surge tank and outdoor temporary tank shall be maintained within limits.

APPLICABILITY: At all times.

COMPENSATORY MEASURES NOTE Separate Condition entry is allowed for each tank.

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Quantity of radioactive A.1 Suspend addition of Immediately material in one or more of radioactive materials to the specified liquid holdup the associated tank.

tanks not within limit. AND A.2 Restore quantity of 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months radioactive material in the tank to within limit.

AND Upon submittal of A.3 Prepare and submit in the the current Radioactive Effluent calendar year Release Report, a Radioactive description of the events Effluent Release leading to the Report non-compliance.

Brunswick Units 1 and 2 7.3.6-1 Rev. 25

Liquid Holdup Tanks 7.3.6 TEST REQUIREMENTS TEST FREQUENCY TR 7.3.6.1 NOTE Only required to be performed when radioactive

, materials are being added to the tank.

7 days Verify the quantity of radioactive material, excluding tritium and dissolved or entrained gases, in the condensate storage tank is _<10 Ci by analyzing a representative sample of the tank's contents.

TR 7.3.6.2 NOTE Only required to be performed when radioactive materials are being added to the tank.

7 days Verify the quantity of radioactive material, excluding tritium and dissolved or entrained gases, in the auxiliary surge tank is _<10 Ci by calculation using dose measurement(s) of the tank area.

TR 7.3.6.3 NOTE Only required to be performed when radioactive materials are being added to the tank.

7 days Verify the quantity of radioactive material, excluding tritium and dissolved or entrained gases, in the outdoor temporary tank is < 10 Ci by analyzing a representative sample of the tank's contents.

Brunswick Units 1 and 2 7.3.6-2 Rev. 25

Dose Rate-Gaseous Effluents 7.3.7 7.3.7 DOSE RATE-GASEOUS EFFLUENTS ODCMS 7.3.7 The dose rate at and beyond the SITE BOUNDARY due to radioactive materials released in gaseous effluents from the site shall be limited to the following:

a. For nobles gases, _<500 mrem per year to the total body and

< 3000 mrem per year to the skin; and

b. For iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days, < 1500 mrem per year to any organ.

APPLICABILITY: At all times.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Dose rate from the release A.1 Initiate action to restore Immediately of radioactive materials in dose rate to within limits.

gaseous effluents from the site at or beyond the SITE BOUNDARY not within limits.

TEST REQUIREMENTS TEST FREQUENCY TR 7.3.7.1 Verify the dose rate due to noble gases in gaseous In accordance with effluents is within limits in accordance with the ODCM methodology and parameters in the ODCM.

TR 7.3.7.2 Verify dose rate due to iodine-131, iodine-1 33, tritium, In accordance with and all radionuclides in particulate form with half lives Table 7.3.7-1

> 8 days in gaseous effluents is within limits in accordance with the methodology and parameters in the ODCM.

Brunswick Units 1 and 2 7.3.7-1 Rev. 25

Dose Rate-Gaseous Effluents 7.3.7 Table 7.3.7-1 (page 1 of 3)

Radioactive Gaseous Waste Sampling and Analysis Program GASEOUS RELEASE SAMPLE SAMPLE ANALYSIS SAMPLE ANALYSIS SAMPLE LOWER TYPE FREQUENCY FREQUENCY TYPE LIMIT OF DETECTION (LLD) (a)

1. Drywell Purge Prior to each purge Prior to each Principal Gamma 1 x 10-4 pCi/ml Grab Sample purge Emitters (b)

2. Environmental Release 31 days 31 days Principal Gamma 1 x 10-4 pCi/ml Points Grab Sample Emitters(b) (c)

a. Continuous Release: H-3 (d) 1 x 10-6 j+/-Ci/ml Main Stack Reactor Building Continuous (e) 7 days (f) (g) 1-131 1 x 10-12 j.Ci/ml Vents Charcoal Sample Turbine Building Vents Continuous (e) 7 days M (g) Principal Gamma 1 x 10-11 laCi/ml Hot Shop (h) Particulate Emitters (b) (1-131, Sample others)

Building Vents Continuous (e) 31 days Gross Alpha 1 x 10-11 .Ci/ml Composite Particulate Sample Continuous (e) 92 days Sr-89, Sr-90 1 x 10-11 l.Ci/ml Composite Particulate Sample Continuous (e) Noble Gas Noble Gases, 1 x 10-6 A.Ci/ml Monitor Gross Beta or Gamma

b. Radioactive During RMCSB (e) 7 days (i) 1-131 1 x 10-12 jiCi/ml Materials operation only Charcoal Sample Container and Storage Building During facility (e) 7 days (i) Principle Gamma 1 x 10-11 jiCi/ml Decontamination operation Particulate Emitters(b) (1-131, Facility (RMCSB) Sample others)

Low Level During facility (e) 31 days Gross Alpha 1 x 10-111 .Ci/ml Warehouse operation Composite Facility (LLW) Particulate Sample During facility (e) 92 days Sr-89, Sr-90 I x 10-11 p.Ci/ml operation Composite Particulate Sample Brunswick Units 1 and 2 7.3.7-2 Rev. 37 1

Dose Rate-Gaseous Effluents 7.3.7 Table 7.3.7-1 (page 2 of 3)

Radioactive Gaseous Waste Sampling and Analysis Program (a) The lower limit of detectability (LLD) is the smallest concentration of a radioactive material in an unknown sample that will be detected with a 95% probability with a 5%

probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

LLD = 4.66 - b E. V- 2.22 x 106 *Y-e-(a'")

Where:

LLD is the "a priori" lower limit of detection as defined above (as microcuries per unit mass or volume) b= (N/tb)/

= standard deviation of background (cpm)

N = background count rate (cpm) tb = time background counted for (min)

E = counting efficiency, as counts per disintegration V = volume or mass of sample 2.22 x 106 = conversion factor (dpm/microcurie)

Y = fractional radiochemical yield

.= radioactive decay constant of ith nuclide (sec-1 )

te = elapsed time between sample collection and counting (sec)

Typical values of E, V, Y, and te should be used in the calculation. It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement.

Brunswick Units 1 and 2 7.3.7-3 Rev. 25

Dose Rate--Gaseous Effluents 7.3.7 Table 7.3.7-1 (page 3 of 3)

Radioactive Gaseous Waste Sampling and Analysis Program (b) The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-1 38 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report.

(c) With a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one hour, or following shutdown or start-up, sampling and analyses shall also be performed unless (1) analysis shows that the Dose Equivalent 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the applicable noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.

(d) If during refueling, the tritium concentration in the spent fuel pool water exceeds 2 x 1044Ci/ml, tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area whenever spent fuel is in the spent fuel pool. Spent fuel pool water will be sampled at least once per 7 days during refueling.

(e) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with ODCMS 7.3.7, 7.3.8, and 7.3.9.

(f) Sample cartridges/filters shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (or after removal from sampler).

(g) Sampling shall be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, start-up, or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if (1) analysis shows that the Dose Equivalent 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the applicable noble gas monitor shows that effluent activity has not increased more than a factor of 3. This footnote does not apply to the Hot Shop environmental release point.

(h) Monthly grab samples to be analyzed for principal gamma emitters and tritium are not applicable for the Hot Shop environmental release point. In addition, the Hot Shop release point does not have a noble gas monitor and, therefore, the noble gas activity analysis requirements of Table 7.3.7-1 are not applicable.

(i) Sample cartridges/filters shall be changed at least once per 7 days when the facility is in operation and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (or after removal from sampler).

Brunswick Units 1 and 2 7.3.7-4 Rev. 37 1

Dose-Noble Gases 7.3.8 7.3.8 DOSE-NOBLE GASES ODCMS 7.3.8 The air dose at and beyond the SITE BOUNDARY due to noble gases in gaseous effluents from the site shall be limited to the following:

a. < 10 mrads gamma radiation and _< 20 mrads beta radiation during any calendar quarter; and

b. < 20 mrads gamma radiation and _<40 mrads beta radiation during any calendar year.

APPLICA131LITY: At all times.

COMPENSATORY MEASURES NOTE Enter applicable Conditions and Required Compensatory Measures of ODCMS 7.3.14, "Total Dose (40 CFR 190)," when gaseous effluent (noble gases) dose results in exceeding an annual total dose limit.

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. A. 1 Submit a Special Report to 30 days

Ithe NRC that identifies NOTE causes for exceeding the Required Compensatory limits, corrective actions Measure A.1 shall be taken to reduce releases, completed if this Condition is and corrective actions to Lentered. assure that subsequent Calculated air dose from releases are within limits.

radioactive noble gases in gaseous effluents at or beyond the SITE BOUNDARY not within limits.

Brunswick Units 1 and 2 7.3.8-1 Rev. 25

Dose-Noble Gases 7.3.8 TEST REQUIREMENTS TEST FREQUENCY TR 7.3.8.1 Verify the cumulative dose contributions from noble 31 days gases in gaseous effluents for the current calendar quarter and current calendar year are within limits in accordance with the methodology and parameters in the ODCM.

Brunswick Units 1 and 2 7.3.8-2 Rev. 25

Dose-]-131, 1-133, Tritium, and Radionuclides in Particulate Form 7.3.9 7.3.9 DOSE-I-131, 1-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM ODCMS 7.3.9 The dose to a MEMBER OF THE PUBLIC at and beyond the SITE BOUNDARY from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days, in gaseous effluents released from the site shall be limited to the following:

a. < 15 mrems to any organ during any calendar quarter;

b. _ 30 mrems to any organ during any calendar year; and APPLICABILITY: At all times.

COMPENSATORY MEASURES NOTE Enter applicable Conditions and Required Compensatory Measures of ODCMS 7.3.14, "Total Dose (40 CFR 190)," when gaseous effluent (1-131, 1-133, tritium, radionuclides in particulate form) dose results in exceeding an annual total dose limit.

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. A.1 Submit a Special Report to 30 days

Ithe NRC that identifies NOTE causes for exceeding the Required Compensatory limits, corrective actions Measure A.1 shall be taken to reduce releases, completed if this Condition is and corrective actions to entered.

L'entered, -- assure subsequent Calculated dose from the releases are within limits.

release of iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives > 8 days, in gaseous effluents at or beyond the SITE BOUNDARY not within limits.

Brunswick Units 1 and 2 7.3.9-1 Rev. 31

Dose--4-131, 1-133, Tritium, and Radionuclides in Particulate Form 7.3.9 TEST REQUIREMENTS TEST FREQUENCY TR 7.3.9.1 Verify the cumulative dose contributions from 31 days iodine-131, iodine-133, tritium, and radionuclides in particulate form with half lives > 8 days, in gaseous effluents for the current calendar quarter and current calendar year are within limits in accordance with the methodology and parameters in the ODCM.

Brunswick Units 1 and 2 7.3.9-2 Rev. 25

GASEOUS RADWASTE TREATMENT SYSTEM 7.3.10 7.3.10 GASEOUS RADWASTE TREATMENT SYSTEM ODCMS 7.3.10 The GASEOUS RADWASTE TREATMENT SYSTEM shall be in operation.

APPLICABILITY: Whenever the Main Condenser Air Ejector (evacuation) System is in operation.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. GASEOUS RADWASTE A.1 Place GASEOUS 7 days TREATMENT SYSTEM not RADWASTE in operation. TREATMENT SYSTEM in operation.

B. B.1 Submit a Special Report to 30 days the NRC that identifies the NOTE required inoperable Required Compensatory equipment and the Measure B. 1 shall be reasons for the completed if this Condition is inoperability, corrective entered. actions taken to restore Required Compensatory the required inoperable measure and associated equipment to OPERABLE Completion Time not met. status, and a summary description of the corrective actions taken to prevent recurrence.

TEST REQUIREMENTS TEST FREQUENCY TR 7.3.10.1 Verify GASEOUS RADWASTE TREATMENT 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SYSTEM in operation by checking the readings of the relevant instruments.

Brunswick Units 1 and 2 7.3.10-1 Rev. 25

VENTILATION EXHAUST TREATMENT SYSTEM 7.3.11 7.3.11 VENTILATION EXHAUST TREATMENT SYSTEM ODCMS 7.3.11 The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge.

APPLICABILITY: During release of gaseous radioactive wastes when the projected doses due to gaseous effluent, from the site to areas at or beyond the SITE BOUNDARY, when averaged over 31 days, would exceed 0.6 mrem to any organ in a 31 day period.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. A.1 Submit a Special Report to 30 days the NRC that identifies the NOTE inoperable equipment or Required Compensatory subsystems and the Measure A. 1 shall be reason for inoperability, completed if this Condition is the corrective actions entered. taken to restore the Gaseous waste being inoperable equipment to discharged without OPERABLE status, and a treatment. summary description of the corrective actions taken to prevent recurrence.

TEST REQUIREMENTS TEST FREQUENCY TR 7.3.11.1 Verify required valve alignment to ensure Prior to release of VENTILATION EXHAUST TREATMENT SYSTEM is gaseous effluents in use to reduce radioactive materials in gaseous waste.

(continued)

Brunswick Units 1 and 2 7.3.11-1 Rev. 25

VENTILATION EXHAUST TREATMENT SYSTEM 7.3.11 TEST REQUIREMENTS (continued)

TEST FREQUENCY TR 7.3.11.2 NOTE Only required to be performed when the VENTILATION EXHAUST TREATMENT SYSTEM is

'not in use.

31 days Determine the projected doses due to gaseous releases from the site to areas at or beyond the SITE BOUNDARY in accordance with the methodology and parameters in the ODCM.

Brunswick Units 1 and 2 7.3.11-2 Rev. 25

Explosive Gas Mixture 7.3.12 7.3.12 EXPLOSIVE GAS MIXTURE ODCMS 7.3.12 The concentration of hydrogen in the Main Condenser Offgas Treatment System shall be < 4% by volume.

APPLICABILITY: When the Main Condenser Air Ejector System is in operation.

COMPENSATORY MEASURES NOTE ODCMS 7.3.0.4 is not applicable.

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Hydrogen concentration in A.1 Restore hydrogen 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months the Main Condenser Offgas concentration to within Treatment System > 4% by limit.

volume.

TEST REQUIREMENTS TEST FREQUENCY TR 7.3.12.1 Verify the concentration of hydrogen in the Main Continuously Condenser Offgas Treatment System is < 4% by volume by monitoring waste gases with the required hydrogen monitors of ODCMS 7.3.2, "Radioactive Gaseous Effluent Monitoring Instrumentation."

Brunswick Units 1 and 2 7.3.12-1 Rev. 25

Drywell VENTING or PURGING 7.3.13 7.3.13 DRYWELL VENTING OR PURGING ODCMS 7.3.13 The drywell shall be purged to the environment at a rate in conformance with ODCMS 7.3.7, "Dose Rate-Gaseous Effluents."

APPLICABILITY: When the drywell is being vented or purged.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Requirements of ODCMS A.1 Suspend VENTING and Immediately not met. PURGING of the drywell.

TEST REQUIREMENTS TEST FREQUENCY TR 7.3.13.1 Perform a sample analysis in accordance with Prior to each Table 7.3.7-1. drywell PURGE Brunswick Units 1 and 2 7.3.13-1 Rev. 25

Total Dose (40 CFR Part 190) 7.3.14 7.3.14 TOTAL DOSE (40 CFR PART 190)

ODCMS 7.3.14 The dose or dose commitment to any MEMBER OF THE PUBLIC over the calendar year due to releases of radioactivity and radiation from uranium fuel cycle sources shall be limited to:

a. _<25 mrems to the total body or any organ (except the thyroid);

and

b. < 75 mrem to the thyroid.

APPLICABILITY: At all times.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. A.1

- -- NOTE NOTE Required Compensatory Estimates of radiation exposure

Measures A.1 and A.2 shall from uranium fuel cycle sources be completed ifthis shall include the effects of all Condition is entered. effluent pathways and direct radiation, including releases Calculated dose for uranium covered by this Special Report.

fuel cycle sources to any 30 days MEMBER OF THE PUBLIC Submit a Special Report to not within limits. the NRC that includes corrective actions taken to prevent recurrence, the schedule for achieving conformance with required limits, an analysis that estimates the radiation exposure to a MEMBER OF THE PUBLIC from uranium fuel cycle sources for the calendar year, descriptions of the levels of radiation and concentrations of radioactive material (continued) involved, and the cause of the exposure levels or concentrations.

AND Brunswick Units 1 and 2 7.3.14-1 Rev. 25

Total Dose (40 CFR Part 190) 7.3.14 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. (continued) A.2 NOTES

1. Only applicable if the release:

condition resulting in violation of 40 CFR 190 has not been corrected.

2. Special Report submitted is considered a timely request and a variance is granted until NRC action on the 30 days request is complete.

Submit a request for a variance in accordance with 40 CFR 190 in the Special Report to the NRC.

TEST REQUIREMENTS TEST FREQUENCY TR 7.3.14.1 Determine cumulative dose contributions from liquid In accordance with and gaseous effluents in accordance with TR 7.3.4.1, ODCM TR 7.3.8.1 and TR 7.3.9.1, and the methodology and parameters in the ODCM.

(continued)

Brunswick Units 1 and 2 7.3.14-2 Rev. 25

Total Dose (40 CFR Part 190) 7.3.14 TEST REQUIREMENTS (continued)

TEST FREQUENCY TR 7.3.14.2 NOTE Only required to be performed when calculated doses from the release of radioactive materials in liquid or gaseous effluents exceed twice the limits of ODCMSs 7.3.4.a, 7.3.4.b, 7.3.8.a, 7.3.8.b, 7.3.9.a., or 7.3.9.b. In accordance with ODCM Determine cumulative dose contributions from direct radiation from the reactor units and from radwaste storage tanks in accordance with methodology and parameters in the ODCM.

Brunswick Units 1 and 2 7.3.14-3 Rev. 25

Radiological Environmental Monitoring Program 7.3.15 7.3.15 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ODCMS 7.3.15 The Radiological Monitoring Program shall be as follows:

a. Radiological environmental monitoring samples shall be collected at locations and analyzed as specified in Table 7.3.15-1.

b. Each sample location specified in Table 7.3.15-1 shall contain required milk or leafy vegetable samples

c. The level of radioactivity as the result of plant effluents for each radionuclide in each environmental sampling medium at a required location shall be less than the limits specified in Table 7.3.15-2, when averaged over the calendar quarter;

d. The total level of radioactivity as the result of plant effluents in each environmental sampling medium at a required location shall be less than the limit specified in Table 7.3.15-2, when averaged over the calendar quarter; and

e. The potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides other than those in Table 7.3.15-2 in each environmental sampling medium at a required location shall be less than the calendar year limits of ODCMS 7.3.4, ODCMS 7.3.8, and ODCMS 7.3.9.

APPLICABILITY: At all times.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. A.1 Prepare and submit, in the Upon submittal of

Annual Radiological current calendar NOTE Environmental Operating year Annual Required Compensatory Report, a description for Radiological Measure A. 1 shall be not conducting the Environmental completed if this Condition is Radiological Operating Report Lentered. Environmental Monitoring One or more samples not sampling and analysis collected or analyzed as requirements as required specified in Table 7.3.15-1. and the corrective actions to prevent recurrence.

(continued)

Brunswick Units 1 and 2 7.3.15-1 Rev. 25

Radiological Environmental Monitoring Program 7.3.15 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME B. B.1 Identify locations for 30 days obtaining replacement NOTES samples and replace, in

1. Separate Condition entry the Radiological is allowed for each Environmental Monitoring sample location. Program, the location(s) from which samples are

2. Required Compensatory unavailable with the new Measure B.2 shall be location(s).

completed if this Upon submittal of Condition is entered. AND current calendar year Radioactive One or more sample locatios requred B.2 byRadioactive Prepare and Effluent submit, in the Effluent Release Rpr locations required by Release Report, the cause Report Table 7.3.15-1 with required of the unavailability of milk or fresh leafy vegetable samples, the new samples unavailable, locations for obtaining replacement samples, and the revised figure(s) and table for the ODCM reflecting the new locations.

(continued)

Brunswick Units 1 and 2 7.3.15-2 Rev. 25

Radiological Environmental Monitoring Program 7.3.15 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME C. C.1 Submit a Special Report to 30 days the NRC which includes NOTES the cause(s) for exceeding

1. Separate Condition entry the limit(s) and the is allowed for each corrective actions to sample location. reduce radioactive effluents so that the

2. Required Compensatory potential annual dose to a Measure C.1 shall be MEMBER OF THE completed ifthis PUBLIC is less than the Condition is entered. calendar year reporting One or more sample limits of ODCMS 7.3.4, locations with the level of ODCMS 7.3.8, and radioactivity for one or more ODCMS 7.3.9.

radionuclides as the result of plant effluents in an environmental sampling medium not within the limits of Table 7.3.15-2 when averaged over the calendar quarter.

OR One or more sample locations with the total level of radioactivity as a result of plant effluents in an environmental sampling medium not within the limits of Table 7.3.15-2 when averaged over the calendar quarter.

(continued)

Brunswick Units 1 and 2 7.3.15-3 Rev. 25

Radiological Environmental Monitoring Program 7.3.15 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME D. D.1 NOTES NOTE Only required ifthe radionuclides'

1. Separate Condition entry are the result of plant effluents.

is allowed for each sample location. 30 days Submit a Special Report to

2. Required Compensatory the NRC which includes Measures D.1 and D.2 the methodology and shall be completed ifthis parameters used for Condition is entered. estimating the potential annual dose, the cause(s)

One or more sample for exceeding the limit(s) locations with the potential and the corrective actions annual dose to a MEMBER to reduce radioactive OF THE PUBLIC from all effluents so that the radionuclides other than potential annual dose to a those in Table 7.3.15-2 not MEMBER OF THE within limits. PUBLIC is less than the calendar year limits of ODCMS 7.3.4, ODCMS 7.3.8, and ODCMS 7.3.9.

AND D.2 NOTE Upon submittal of the current Only required ifthe radionuclides are not the result of plant calendar year effluents. Annual Radiological Describe the condition in Environmental the Annual Radiological Operating Report Environmental Operating Report.

Brunswick Units 1 and 2 7.3.15-4 Rev. 25

Radiological Environmental Monitoring Program 7.3.15 TEST REQUIREMENTS TEST FREQUENCY TR 7.3.15.1 Verify radiological environmental monitoring samples In accordance with collected at the locations given in the table and Table 7.3.15-1 figure(s) in the ODCM and analyzed as specified in Table 7.3.15-1 are within limits. Detection capabilities for the analyses are specified in Table 7.3.15-3.

Brunswick Units 1 and 2 7.3.15-5 Rev. 25

Radiological Environmental Monitoring Program 7.3.15 Table 7.3.15-1 (page 1 of 5)

Radiological Environmental Monitoring Program EXPOSURE PATHWAY NUMBER OF SAMPLES AND SAMPLING AND TYPE AND AND/OR SAMPLE SAMPLE LOCATIONS(') COLLECTION FREQUENCY FREQUENCY OF ANALYSIS

1. Direct Radiation(b) Forty-nine locations, either with two or 92 days Gamma dose:

more dosimeters or with one or more 92 days instruments for measuring and recording dose rate continuously to be placed as follows:

An inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDARY as is reasonably accessible and practical.

An outer ring of stations, one in each of the meteorological sectors at distances of 8 km or greater from the site as is reasonably accessible and practical.

The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and one or two areas to serve as control stations.

2. Airborne- Samples from the following locations: Continuous sampler operation 1-131 analysis of Radioiodine and Sample collection: 7 days or radioiodine canisters:

Particulate Three samples from different as required by dust loading, 7 days sectors as close to the SITE whichever is more frequent.

BOUNDARY as is reasonably AND accessible, one of which being at the highest calculated Gross beta radioactivity annual average ground level analysis of particulate D/Q. sampler: following filter change(d)

One sample from the vicinity of a nearby community. AND One sample from a control Gamma isotopic location, as for example analysis(') of composite greater than 15 km distant and (by location): 92 days in a less prevalent wind direction(c).

(continued)

Brunswick Units 1 and 2 7.3.15-6 Rev. 35

Radiological Environmental Monitoring Program 7.3.15 Table 7.3.15-1 (page 2 of 5)

Radiological Environmental Monitoring Program EXPOSURE PATHWAY NUMBER OF SAMPLES AND SAMPLING AND TYPE AND AND/OR SAMPLE SAMPLE LOCATIONS(a) COLLECTION FREQUENCY OF FREQUENCY ANALYSIS

3. Waterbome

a. Surfaceef) Two locations: Composite(s) Gamma isotopic One sample upstream. sample collection: 31 days analysis(.): 31 days One sample downstream.

AND Tritium analysis: 92 days Four locations from Nancy's Creek Grab Samples Tritium Weekly 7 Days Composite samples for monthly gamma isotopic analysis, if gamma activity detected from plant, Sr- 89, Sr-90, Fe-55 analysis required.

Eight locations from Nancy's Creek Grab Samples Tritium Weekly Marsh Areas 7 Days Composite samples for weekly gamma isotopic analysis, if gamma activity detected from plant, Sr- 89, Sr-90, Fe-55 analysis required.

b. Sediment from One sample from downstream 184 days Gamma isotopic Shoreline area with existing or potential analysis(e): 184 days recreational value.

One sample from Nancy's 365 days Gamma isotopic (,

Creek Area analysis 365 days

c. Groundwater One sample from 10 184 days Gamma isotopic (e):

Monitoring wells: 184 days 92 days Tritium: 92 days

4. Ingestion Samples from the following four With animals on pasture: Gamma isotopic(e) and locations: 14 days 1-131 analyses: 14 days

a. Milk One sample from milking when animals are on animals in each of three At other times: 31 days pasture locations within 8 km of the site having the highest dose AND potential (when available).Y" Gamma isotopic(') and One sample from milking 1-131 analyses: 31 days animals at a control location at other times greater than 15 km distance from the site and in a less prevalent wind direction.

(continued)

Brunswick Units 1 and 2 7.3.15-7 Rev. 35

Radiological Environmental Monitoring Program 7.3.15 Table 7.3.15-1 (page 3 of 5)

Radiological Environmental Monitoring Program EXPOSURE PATHWAY NUMBER OF SAMPLES AND SAMPLING AND TYPE AND AND/OR SAMPLE SAMPLE LOCATIONS(a) COLLECTION FREQUENCY OF FREQUENCY ANALYSIS

4. (continued)

b. Fish and Samples from the following When in season: 184 days Gamma isotopic Invertebrates locations: analysis(e) on edible portion: 184 days One sample of each of three recreationally important species in vicinity of plant discharge area (one free swimming species, one bottom feeding species, and one shellfish species).

One sample of each similarly edible species from an area not influenced by plant discharge to serve as control samples.

One sample of each of 365 days Gamma isotopic three recreationally analysis(e) on edible important species in portion: 365 days Nancy's Creek (one free swimming species, one bottom feeding species, and one shellfish species.)

c. Broadleaf Samples from the following three When available: 31 days Gamma isotopic(e) and Vegetation locations: 1-131 analyses: 31 days when available Samples of broadleaf vegetation grown in two sectors of historically high D/Q values at the SITE BOUNDARY if milk sampling is not performed.

One sample of similar broadleaf vegetation grown at a distance of greater than 15 km from the site in a less prevalent wind direction if milk sampling is not performed.

Brunswick Units 1 and 2 7.3.15-8 Rev. 35

Radiological Environmental Monitoring Program 7.3.15 Table 7.3.15-1 (page 4 of 5)

Radiological Environmental Monitoring Program (a) Specific parameters of distance and direction sector from the site, and additional description where pertinent, shall be provided for each and every sample location in Table 7.3.15-1 in a table and figure(s) in the ODCM. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment, and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. Identify the cause of the unavailability of samples for that pathway and identify the new location(s) for obtaining replacement samples in the next Radioactive Effluent Release Report and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

(b) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation.

The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.

(c) The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted.

(d) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

(e) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

Brunswick Units 1 and 2 7.3.15-9 Rev. 25

Radiological Environmental Monitoring Program 7.3.15 Table 7.3.15-1 (page 5 of 5)

Radiological Environmental Monitoring Program (f) The "upstream" sample shall be taken at a distance beyond significant influence of the discharge. The "downstream" sample shall be taken in an area beyond but near the mixing zone. "Upstream" samples in an estuary must be taken far enough upstream to be beyond the plant influence. Salt water shall be sampled only when the receiving water is utilized for recreational activities.

(g) A composite sample is one in which the quantity (aliquot) of liquid sampled is proportional to the quantity of flowing liquid and in which the method of sampling employed results in a specimen that is representative of the liquid flow. Composite samples shall be collected with equipment that is capable of collecting an aliquot at time intervals that are short (e.g., once per 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ) relative to compositing period (e.g.,

monthly) in order to assure obtaining a representative sample.

(h) When less than three (3) milking animal locations are available for testing within an 8-km distance, sampling of broadleaf vegetation shall be performed as indicated in Table 7.3.15-1, 4.c, in lieu of milk sampling.

Brunswick Units 1 and 2 7.3.15-10 Rev. 25

Radiological Environmental Monitoring Program 7.3.15 Table 7.3.15-2 (page 1 of 1)

Limits for the Level of Radioactivity in Environmental Samples (

ANALYSIS WATER AIRBORNE FISH MILK BROADLEAF (pCi/I) PARTICULATE (pCi/kg, wet) (pCi/I) VEGETATION AND GASES (pCi/kg)

(pCi/m 3 )

H-3 30,000 Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 (a) The Limits are for samples that have only one radionuclide detected. When a sample contains more than one radionuclide, the total level of radioactivity limit is concentration(I) + concentration(2) + . < 1.0.

limit (1) limit (2)

Brunswick Units 1 and 2 7.3.15-11 Rev. 37

Radiological Environmental Monitoring Program 7.3.15 Table 7.3.15-3 (page 1 of 3)

Detection Capabilities for Environmental Sample Analysis 0)

Lower Limit of detection (LLD) ()

ANALYSIS WATER AIRBORNE FISH MILK BROADLEAF SEDIMENT (pCi/I) PARTICULATE (pCi/Kg, wet) (pCi/I) VEGETATION (pCi/kg, dry)

OR GASES (pCi/m 3) (pCi/kg, wet)

Gross Beta 4 0.01 H-3 3,000 Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-Nb-95 15 1-131 10) 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 Brunswick Units 1 and 2 7.3.15-12 Rev. 37

Radiological Environmental Monitoring Program 7.3.15 Table 7.3.15-3 (page 2 of 3)

Detection Capabilities for Environmental Sample Analysis (a) This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall be analyzed and reported in the Annual Radiological Environmental Operating Report.

(b) The LLD is defined for purposes of the specifications, as the smallest concentration of radioactive material in an unknown sample that will be detected with 95% probability with a 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

LLD = 4"66 ( kt E-V. 2.22.Y.e .-(Y )

Where:

LLD is the "a priori" lower limit of detection as defined above, as picocuries per unit mass or volume.

Cb = (N/tb)/2

= standard deviation of background (cpm)

N = background count rate (cpm) tb = time background counted for (min)

E = counting efficiency, as counts per disintegration V = volume or mass of sample 2.22 = conversion factor (dpm/pCi)

Y = fractional radiochemical yield k = radioactive decay constant of ith nuclide (sec1 )

te = elapsed time between sampling collection and counting (sec)

Brunswick Units 1 and 2 7.3.15-13 Rev. 25

Radiological Environmental Monitoring Program 7.3.15 Table 7.3.15-3 (page 3 of 3)

Detection Capabilities for Environmental Sample Analysis Typical values of E, V, Y, and te should be used in the calculation. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs shall be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.

(c) LLD for drinking water samples. If no drinking water pathway exists, a value of 15 pCi/L may be used.

Brunswick Units 1 and 2 7.3.15-14 Rev. 36 1

Land Use Census 7.3.16 7.3.16 LAND USE CENSUS ODCMS 7.3.16 A land use census shall be conducted and:

a. Shall identify the location of the nearest milk animal, residence, and garden of greater than 50m 2 (500 ft2) producing broadleaf vegetation in each of the 16 meteorological sectors within a distance of 8 km (5 miles);

b. Shall identify (for elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977) the location of all milk animals and all gardens of greater than 50m 2 producing broadleaf vegetation in each of the 16 meteorological sectors within a distance of 5 km (3 miles);

c. The calculated dose and dose commitment at each identified location shall be less than the most recent values calculated by TR 7.3.9.1; and

d. The calculated dose and dose commitment at each identified location, via the same exposure pathways, shall be < 120% of the actual dose and dose commitment from the current sample location identified in Table 7.3.15-1, excluding the central station location.

NOTE In lieu of the garden census of ODCMS 7.3.16.a, broadleaf vegetable sampling of at least 3 different kinds of vegetation may be performed at the SITE BOUNDARY in each of 2 different direction sectors with the highest D/Qs. Specifications for broadleaf vegetation sampling of Table 7.3.15-1 (item 4.c) shall be followed, including analysis of control

samples.

APPLICABILITY: At all times.

OBrunswick Units 1 and 2 7.3.16-1 Rev. 30 1

Land Use Census 7.3.16 COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. A.1 Prepare and submit, in the Upon submittal of Annual Radiological current calendar NOTE Environmental Operating year Annual Required Compensatory Report, a description for Radiological Measure A.1 shall be not conducting the land Environmental completed ifthis Condition is comeed. iuse census and the Operating Report entered._ corrective actions to Land use census not prevent recurrence.

conducted.

OR All required locations not identified.

B. B.1 Identify new location(s) in Upon submittal of the Radioactive Effluent the current NOTE Release Report. calendar year Required Compensatory Radioactive Measure B.1 shall be Effluent Release completed if this Condition is Report entered.

One or more identified locations with the calculated dose or dose commitment greater than the values calculated by TR 7.3.9.1.

(continued)

Brunswick Units 1 and 2 7.3.16-2 Rev. 25

Land Use Census 7.3.16 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME C. C. 1 Add the new location to 30 days the Radiological S

NOTE Environmental Monitoring Required Compensatory Program.

Measure C.1 shall be completed if this Condition is AND After October 31 of entered. IC.2 Delete the sampling the year in which

Cloc ti vthe sm lo t land use census One or more identified location having the lowest was conducted locations with the calculated commitment, via the same dose or dose commitment, cosure pathe sam via the same exposure exposure pathway, from pathway, > 120% of the the Radiological actual dose or dose Monitoring program.

commitment from currnt the AND intheocaton dentfie Upon submittal of current current location identified in C.3 Identify the new location(s) calendar year Table 7.3.15-1. in the Radioactive Effluent Radioactive Release Report, and the Effluent Release revised figure(s) and table Report for the ODCM reflecting the new location.

Brunswick Units 1 and 2 7.3.16-3 Rev. 25

Land Use Census 7.3.16 TEST REQUIREMENTS TEST FREQUENCY TR 7.3.16.1 Conduct a land use census during the growing season 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities; identify all required locations, and verify the calculated dose and dose commitments at each identified location is within limits.

Brunswick Units 1 and 2 7.3.16-4 Rev. 25

Interlaboratory Comparison Program 7.3.17 7.3.17 INTERLABORATORY COMPARISON PROGRAM ODCMS 7.3.17 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program approved by the NRC.

APPLICABILITY: At all times.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. A.1 Prepare and submit, in the Upon submittal of E---------- Annual Radiological current calendar NOTE Environmental Operating year Annual Required Compensatory Report, corrective actions Radiological Measure A.1 shall be to prevent recurrence. Environmental completed if this Condition is Operating Report entered.

Requirements of ODCMS 7.3.17 not met.

TEST REQUIREMENTS TEST FREQUENCY TR 7.3.17.1 Perform the analyses required by the Interlaboratory In accordance with Comparison Program. the ODCM Brunswick Units 1 and 2 7.3.17-1 Rev. 25

Reporting Requirements 7.4.0 7.4.0 REPORTING REQUIREMENTS ODCMS 7.4.1 Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report shall be submitted in accordance with the requirements of Technical Specification 5.6.2. In addition to the requirements of Technical Specification 5.6.2, the Annual Radiological Environmental Operating Report shall include:

a. Summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with pre-operational studies, with operational controls (as appropriate), and with previous environmental surveillance reports, and an assessment of the observed impact of the plant operation on the environment;

b. Results of the land use census required by ODCMS 7.3.16;

c. A summary description of the radiological environmental monitoring program;

d. At least two legible maps of all sampling locations keyed to a table giving distances and directions from the centerline of one reactor (one map shall cover stations near the SITE BOUNDARY and the second map shall include more distant stations);

e. Results of the Interlaboratory Comparison Program required by ODCMS 7.3.17;

f. Discussion of all deviations from the sampling schedule of Table 7.3.15-1; and

g. Discussion of all analyses in which the LLD required by Table 7.3.15-3 was not achievable.

ODCMS 7.4.2 Radioactive Effluent Release Report The Radioactive Effluent Release Report shall be submitted in accordance with the requirements of Technical Specification 5.6.3. In addition to the requirements of Technical Specification 5.6.3, the Radioactive Effluent Release Report shall include:

(continued)

Brunswick Units 1 and 2 7.4.0-1 Rev. 25

Reporting Requirements 7.4.0 7.4.0 REPORTING REQUIREMENTS (continued)

ODCMS 7.4.2 Radioactive Effluent Release Report (continued)

a. A summary of the quantities of radioactive liquid and gaseous effluents and solid waste released for the facility as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactivity Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis similar to the format of Appendix B thereof.

b. Information specified below for each class of solid waste (as defined by 10 CFR Part 61, when implemented) shipped offsite during the report period:

1. Container volume;

2. Total curie quantity (specify whether determined by measurement or estimate);

3. Principal radionuclides (specify whether determined by measurement or estimate);

4. Source of waste and processing employed (e.g.,

dewatered spent resin, compacted dry waste, evaporator bottoms);

5. Type of container (e.g., LSA, Type A, Type B, Large Quantity); and

6. Solidification agent or absorbent (e.g., cement, urea formaldehyde).

c. A list and description of unplanned releases from the site to the UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

d. Any changes made during the reporting period to the Process Control Program (PCP) or the Offsite Dose Calculation Manual (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to ODCMS 7.3.16.

(continued)

Brunswick Units 1 and 2 7.4.0-2 Rev. 25

Reporting Requirements 7.4.0 7.4.0 REPORTING REQUIREMENTS (continued)

ODCMS 7.4.2 Radioactive Effluent Release Report (continued)

e. An annual summary of hourly meteorological data collected over the previous calendar year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. In lieu of submission of this summary of required meteorological data with the Radioactive Effluent Release Report, the summary of required meteorological data may be retained in a file that shall be provided to the NRC upon request.

f. An assessment of radiation doses due to radioactive liquid and gaseous effluents released from the station during the previous calendar year.

g. The Radioactive Effluent Release Report shall include results from any groundwater samples obtained in accordance with the Radiological Environmental Monitoring Program during the reporting period that are not described in the ODCM.

h. The Radioactive Effluent Release Report shall include any assigned doses that were performed as a result of a spill or leak from the site that occurred during the reporting period.

The Radioactive Effluent Release Report shall include a summary of any on-site spills and leaks that occurred during the reporting period that were communicated to offsite agencies.

Brunswick Units 1 and 2 7.4.0-3 Rev. 30 1

Major Changes to Radioactive Waste Treatment Systems 7.5.0 7.5.0 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS ODCMS 7.5.1 Licensee initiated 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 annual UFSAR update. The discussion of each change shall contain:

a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR Part 50.59;

b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;

c. A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems;

d. An evaluation of the change that shows the predicted release of radioactive materials in the liquid and gaseous effluents and quantity of solid waste differ from those previously predicted in the license application and amendments thereto;

e. An evaluation of the change that shows the expected maximum exposure to an individual in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto;

f. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid wastes, to the actual releases for the period prior to when the changes are to be made;

g. An estimate of the exposure to plant operating personnel as a result of the change; and

h. Documentation of the fact that the change was reviewed and found acceptable by the PNSC.

ODCMS 7.5.2 The change shall become effective upon review and acceptance by the PNSC.

Brunswick Units 1 and 2 7.5.0-1 Rev. 25

ODCMS Applicability B 7.3.0 B 7.3.0 OFFSITE DOSE CALCULATION MANUAL SPECIFICATION (ODCMS)

APPLICABILITY BASES ODCMSs ODCMS 7.3.0.1 through ODCMS 7.3.0.6 establish the general requirements applicable to all Specifications and apply at all times, unless otherwise stated.

ODCMS 7.3.0.1 ODCMS 7.3.0.1 establishes the Applicability statement within each individual ODCMS as the requirement for when the ODCMS is required to be met (i.e., when the unit is in the MODES or other specified conditions of the Applicability statement of each ODCMS).

ODCMS 7.3.0.2 ODCMS 7.3.0.2 establishes that upon discovery of a failure to meet an ODCMS, the associated COMPENSATORY MEASURES shall be met.

The Completion Time of each Required Compensatory Measure for a COMPENSATORY MEASURES Condition is applicable from the point in time that a COMPENSATORY MEASURES Condition is entered. The Required Compensatory Measures establish those remedial measures that must be taken within specified Completion Times when the requirements of an ODCMS are not met. This ODCMS establishes that:

a. Completion of the Required Compensatory Measures within the specified Completion Times constitutes compliance with an ODCMS; and

b. Completion of the Required Compensatory Measures is not required when an ODCMS is met within the specified Completion Time, unless otherwise specified.

There are two basic types of Required Compensatory Measures. The first type of Required Compensatory Measure specifies a time limit in which the ODCMS must be met. This time limit is the Completion Time to restore an inoperable system or component to OPERABLE status or to restore variables to within specified limits. If this type of Required Compensatory Measure is not completed within the specified Completion Time, a shutdown may be required to place the unit in a MODE or condition in which the ODCMS is not applicable. (Whether stated as a Required Compensatory Measure or not, correction of the entered (continued)

Brunswick Units 1 and 2 B 7.3.0-1 Rev. 25

ODCMS Applicability B 7.3.0 BASES ODCMS 7.3.0.2 Condition is a compensatory measure that may always be considered (continued) upon entering COMPENSATORY MEASURES.) The second type of Required Compensatory Measure specifies the remedial measures that permit continued operation of the unit that is not further restricted by the Completion Time. In this case, compliance with the Required Compensatory Measures provides an acceptable level of safety for continued operation.

Completing the Required Compensatory Measures is not required when an ODCMS is met or is no longer applicable, unless otherwise stated in the individual ODCMSs.

The nature of some Required Compensatory Measures of some Conditions necessitates that, once the Condition is entered, the Required Compensatory Measures must be completed even though the associated Condition no longer exists. The individual ODCMS's COMPENSATORY MEASURES specify the Required Compensatory Measures where this is the case.

The Completion Times of the Required Compensatory Measures are also applicable when a system or component is removed from service intentionally. The reasons for intentionally relying on the COMPENSATORY MEASURES include, but are not limited to, performance of Tests, preventive maintenance, corrective maintenance, or investigation of operational problems. Entering COMPENSATORY MEASURES for these reasons must be done in a manner that does not compromise safety. Intentional entry into COMPENSATORY MEASURES should not be made for operational convenience.

Alternatives that would not result in redundant equipment being inoperable should be used instead. Doing so limits the time both subsystems/ divisions of a safety function are inoperable. Individual ODCMSs may specify a time limit for performing a TR when equipment is removed from service or bypassed for testing. In this case, the Completion Times of the Required Compensatory Measures are applicable when this time limit expires, ifthe equipment remains removed from service or bypassed.

When a change in MODE or other specified condition is required to comply with Required Compensatory Measures, the unit may enter a MODE or other specified condition in which another ODCMS becomes applicable. In this case, the Completion Times of the associated (continued)

Brunswick Units I and 2 B 7.3.0-2 Rev. 25

ODCMS Applicability B 7.3.0 BASES ODCMS 7.3.0.2 Required Compensatory Measures would apply from the point in time (continued) that the new ODCMS becomes applicable and the COMPENSATORY MEASURES Condition(s) are entered.

ODCMS 7.3.0.3 Not used.

ODCMS 7.3.0.4 ODCMS 7.3.0.4 establishes limitations on changes in MODES or other specified conditions in the Applicability when an ODCMS is not met. It precludes placing the unit in a MODE or other specified condition stated in that Applicability (e.g., Applicability desired to be entered) when the following exist:

a. Unit conditions are such that the requirements of the ODCMS would not be met in the Applicability desired to be entered; and

b. Continued noncompliance with the ODCMS requirements, if the Applicability were entered, would result in the unit being required to exit the Applicability desired to be entered to comply with the Required Compensatory Measures.

Compliance with Required Compensatory Measures that permit continued operation of the unit for an unlimited period of time in a MODE or other specified condition provides an acceptable level of safety for continued operation. This is without regard to the status of the unit before or after the MODE change. Therefore, in such cases, entry into a MODE or other specified condition in the Applicability may be made in accordance with the provisions of the Required Compensatory Measures.

The provisions of this Specification should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before unit startup.

The provisions of ODCMS 7.3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with COMPENSATORY MEASURES. In addition, the provisions of ODCMS 7.3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown.

(continued)

Brunswick Units 1 and 2 B 7.3.0-3 Rev. 25

ODCMS Applicability B 7.3.0 BASES ODCMS 7.3.0.4 Exceptions to ODCMS 7.3.0.4 are stated in the individual Tests.

(continued) Exceptions may apply to all the COMPENSATORY MEASURES or to a specific Required Compensatory Measure of an ODCMS.

Tests do not have to be performed on the associated inoperable equipment (or on variables outside the specified limits), as permitted by TR 7.3.0.1. Therefore, changing MODES or other specified conditions while in a COMPENSATORY MEASURES Condition, either in compliance with ODCMS 7.3.0.4 or where an exception to ODCMS 7.3.0.4 is stated, is not a violation of TR 7.3.0.1 or TR 7.3.0.4 for those Tests that do not have to be performed due to the associated inoperable equipment. However, TRs must be met to ensure OPERABILITY prior to declaring the associated equipment OPERABLE (or variable within limits) and restoring compliance with the affected ODCMS.

ODCMS 7.3.0.5 ODCMS 7.3.0.5 establishes the allowance for restoring equipment to service under administrative controls when it has been removed from service or declared inoperable to comply with COMPENSATORY MEASURES. The sole purpose of this ODCMS is to provide an exception to ODCMS 7.3.0.2 (e.g., to not comply with the applicable Required Compensatory Measure(s)) to allow the performance of TRs to demonstrate:

a. The OPERABILITY of the equipment being returned to service; or

b. The OPERABILITY of other equipment.

The administrative controls ensure the time the equipment is returned to service in conflict with the requirements of the COMPENSATORY MEASURES is limited to the time absolutely necessary to perform the allowed TRs. This ODCMS does not provide time to perform any other preventive or corrective maintenance.

An example of demonstrating the OPERABILITY of the equipment being returned to service is taking an inoperable channel or trip system out of the tripped condition after it has been tripped to comply with Required Compensatory Measures since it must be untripped to perform the TRs.

(continued)

Brunswick Units 1 and 2 B 7.3.0-4 Rev. 25

ODCMS Applicability B 7.3.0 BASES ODCMS 7.3.0.5 An example of demonstrating the OPERABILITY of other equipment is (continued) taking an inoperable channel or trip system out of the tripped condition to prevent the trip function from occurring during the performance of a TR on another channel in the other trip system. A similar example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to permit the logic to function and indicate the appropriate response during the performance of a TR on another channel in the same trip system.

ODCMS 7.3.0.6 ODCM 7.3.0.6 delineates the applicability of each ODCMS and associated COMPENSATORY MEASURE to Brunswick Unit 1 and Brunswick Unit 2 operations.

Brunswick Units 1 and 2 B 7.3.0-5 Rev. 25

TR Applicability B 7.3.0 B 7.3.0 TEST REQUIREMENT (TR) APPLICABILITY BASES TRs TR 7.3.0.1 through TR 7.3.0.5 establish the general requirements applicable to all ODCMSs and apply at all times, unless otherwise stated.

TR 7.3.0.1 TR 7.3.0.1 establishes the requirement that TRs must be met during the MODES or other specified conditions in the Applicability for which the requirements of the ODCMS apply, unless otherwise specified in the individual TRs. This ODCMS is to ensure that Tests are performed to verify the OPERABILITY of systems and components, and that variables are within specified limits. Failure to meet a Test within the specified Frequency, in accordance with TR 7.3.0.2, constitutes a failure to meet an ODCMS.

Systems and components are assumed to be OPERABLE when the associated TRs have been met. Nothing in this ODCMS, however, is to be construed as implying that systems or components are OPERABLE when:

a. The systems or components are known to be inoperable, although still meeting the TRs; or

b. The requirements of the Test(s) are known to be not met between required Test performances.

Tests do not have to be performed when the unit is in a MODE or other specified condition for which the requirements of the associated ODCMS are not applicable, unless otherwise specified.

Tests, including Tests invoked by Required Compensatory Measures, do not have to be performed on inoperable equipment because the COMPENSATORY MEASURES define the remedial measures that apply. Tests have to be met and performed in accordance with TR 7.3.0.2, prior to returning equipment to OPERABLE status.

Upon completion of maintenance, appropriate post maintenance testing is required to declare equipment OPERABLE. This includes ensuring applicable Tests are not failed and their most recent performance is in accordance with TR 7.3.0.2. Post maintenance testing may not be possible in the current MODE or other specified conditions in the (continued)

Brunswick Units 1 and 2 B 7.3.0-6 Rev. 25

TR Applicability B 7.3.0 BASES TR 7.3.0.1 Applicability due to the necessary unit parameters not having been (continued) established. In these situations, the equipment may be considered OPERABLE provided testing has been satisfactorily completed to the extent possible and the equipment is not otherwise believed to be incapable of performing its function. This will allow operation to proceed to a MODE or other specified condition where other necessary post maintenance tests can be completed.

TR 7.3.0.2 TR 7.3.0.2 establishes the requirements for meeting the specified Frequency for Tests and any Required Compensatory Measure with a Completion Time that requires the periodic performance of the Required Compensatory Measure on a "once per..." interval.

TR 7.3.0.2 permits a 25% extension of the interval specified in the Frequency. This extension facilitates Test scheduling and considers plant operating conditions that may not be suitable for conducting the Test (e.g., transient conditions or other ongoing Test or maintenance activities).

The 25% extension does not significantly degrade the reliability that results from performing the Test at its specified Frequency. This is based on the recognition that the most probable result of any particular Test being performed is the verification of conformance with the TRs.

As stated in TR 7.3.0.2, the 25% extension also does not apply to the initial portion of a periodic Completion Time that requires performance on a "once per..." basis. The 25% extension applies to each performance after the initial performance. The initial performance of the Required Compensatory Measure, whether it is a particular Test or some other remedial action, is considered a single compensatory measure with a single Completion Time. One reason for not allowing the 25% extension to this Completion Time is that such a compensatory measure may verify that no loss of function has occurred by checking the status of redundant or diverse components or accomplishes the function of the inoperable equipment in an alternative manner.

(continued)

Brunswick Units 1 and 2 B 7.3.0-7 Rev. 25

TR Applicability B 7.3.0 BASES TR 7.3.0.2 The provisions of TR 7.3.0.2 are not intended to be used repeatedly (continued) merely as an operational convenience to extend Test intervals (other than those consistent with refueling intervals) or periodic Completion Time intervals beyond those specified.

TR 7.3.0.3 TR 7.3.0.3 establishes the flexibility to defer declaring affected equipment inoperable or an affected variable outside the specified limits when a Test has not been completed within the specified Frequency. A delay period of up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is less, applies from the point in time that it is discovered that the Test has not been performed in accordance with TR 7.3.0.2, and not at the time that the specified Frequency was not met.

This delay period provides adequate time to complete Tests that have been missed. This delay period permits the completion of a Test before complying with Required Compensatory Measures or other remedial measures that might preclude completion of the Test.

The basis for this delay period includes consideration of unit conditions, adequate planning, availability of personnel, the time required to perform the Test, the safety significance of the delay in completing the required Test, and the recognition that the most probable result of any particular Test being performed is the verification of conformance with the requirements.

When a Test with a Frequency based not on time intervals, but upon specified unit conditions or operational situations, is discovered not to have been performed when specified, TR 7.3.0.3 allows the full delay period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to perform the Test.

TR 7.3.0.3 also provides a time limit for completion of Tests that become applicable as a consequence of MODE changes imposed by Required Compensatory Measures.

(continued)

Brunswick Units 1 and 2 B 7.3.0-8 Rev. 25

TR Applicability B 7.3.0 BASES TR 7.3.0.3 Failure to comply with specified Frequencies for TRs is expected to be (continued) an infrequent occurrence. Use of the delay period established by TR 7.3.0.3 is a flexibility which is not intended to be used as an operational convenience to extend Test intervals.

If a Test is not completed within the allowed delay period, then the equipment is considered inoperable or the variable is considered outside the specified limits and the Completion Times of the Required Compensatory Measures for the applicable ODCMS Conditions begin immediately upon expiration of the delay period. If a Test is failed within the delay period, then the equipment is inoperable, or the variable is outside the specified limits and the Completion Times of the Required Compensatory Measures for the applicable ODCMS Conditions begin immediately upon the failure of the Test.

Completion of the Test within the delay period allowed by this ODCMS, or within the Completion Time of the COMPENSATORY MEASURES, restores compliance with TR 7.3.0.1.

TR 7.3.0.4 TR 7.3.0.4 establishes the requirement that all applicable TRs must be met before entry into a MODE or other specified condition in the Applicability. This ODCMS ensures that system and component OPERABILITY requirements and variable limits are met before entry into MODES or other specified conditions in the Applicability for which these systems and components ensure safe operation of the unit.

However, in certain circumstances failing to meet a TR will not result in TR 7.3.0.4 restricting a MODE change or other specified condition change. When a system, subsystem, division, component, device, or variable is inoperable or outside its specified limits, the associated TR(s) are not required to be performed, per TR 7.3.0.1, which states that Tests do not have to be performed on inoperable equipment. When equipment is inoperable, TR 7.3.0.4 does not apply to the associated TR(s) since the requirement for the TR(s) to be performed is removed. Therefore, failing to perform the Test(s) within the specified Frequency does not result in a (continued)

Brunswick Units 1 and 2 B 7.3.0-9 Rev. 25

TR Applicability B 7.3.0 BASES TR 7.3.0.4 TR 7.3.0.4 restriction to changing MODES or other specified conditions of (continued) the Applicability. However, since the ODCMS is not met in this instance, ODCMS 7.3.0.4 will govern any restrictions that may (or may not) apply to MODE or other specified condition changes.

The provisions of TR 7.3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with COMPENSATORY MEASURES. In addition, the provisions of TR 7.3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown.

The precise requirements for performance of TRs are specified such that exceptions to TR 7.3.0.4 are not necessary. The specific time frames and conditions necessary for meeting the TRs are specified in the Frequency, in the Test, or both. This allows performance of Tests when the prerequisite condition(s) specified in a Test procedure require entry into the MODE or other specified condition in the Applicability of the associated ODCMS prior to the performance or completion of a Test. A Test that could not be performed until after entering the ODCMS Applicability would have its Frequency specified such that it is not "due" until the specific conditions needed are met. Alternately, the Test may be stated in the form of a Note as not required (to be met or performed) until a particular event, condition, or time has been reached. Further discussion of the specific formats of TRs' annotation is found in ODCMS Section 7.1.4, Frequency.

TR 7.3.0.5 TR 7.3.0.5 delineates the applicability of the test activities to Brunswick Unit 1 and Brunswick Unit 2 operations.

Brunswick Units 1 and 2 B 7.3. 0-10 Rev. 25

Radioactive Liquid Effluent Monitoring Instrumentation B 7.3.1 B 7.3.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION BASES The radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. The purpose of tank level indicating devices is to assure the detection and control of leaks that, if not controlled, could potentially result in the transport of radioactive materials to UNRESTRICTED AREAS.

The initial CHANNEL CALIBRATION for the Table 7.3.1-1, Functions 1 and 3, instruments was performed using National Bureau of Standards traceable sources which verified that each detector would operate properly over its intended energy range and measurement range. For instruments which were operational prior to this specification being implemented, previously established calibration procedures may be substituted for the initial requirement. Subsequent to CHANNEL CALIBRATIONS will be performed using sources that have been related to the initial calibration in order to ensure that each detector is still operational, but the sources need not span the full ranges used in the initial CHANNEL CALIBRATION.

The ODCMS are modified by a Note to indicate that the annunciator function may be removed from operation for performance of troubleshooting for up to 30 minutes provided the associated function maintains monitoring capability. Upon completion of troubleshooting, or expiration of the 30 minute allowance, the annunciator must be returned to operation or the applicable condition entered and required Compensatory Measures taken. Appropriate compensatory actions should be determined an implemented during the loss of annunciator function. This note is based on the availability of the associated monitor and appropriate compensatory actions to identify changes in the liquid effluent for the monitored location. The monitor availability and compensatory actions ensure that the 30 minute trouble shooting allowance does not significantly reduce the probability of identifying the changing radiological conditions to allow appropriate response.

Brunswick Units 1 and 2 B 7.3. 1-1 Rev. 29 1

Radioactive Gaseous Effluent Monitoring Instrumentation B 7.3.2 B 7.3.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION BASES The radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60 and 64 of Appendix A to 10 CFR Part 50.

The main condenser air ejector monitoring instrumentation, the main condenser offgas treatment system monitor, and the explosive gas monitoring instrumentation shown in Table 7.3.2-1 are not considered effluent monitoring instrumentation in the same sense as the other instrumentation listed in the table. Therefore, their alarm/trip setpoints are not necessarily set to ensure that the limits of ODCMS 7.3.7 are not exceeded.

The main condenser air ejector monitoring instrumentation channels 1(2)-D12-RM-K601A and 1(2)-D1 2-RM-K601 B are provided to monitor and control gross radioactivity removed from the main condenser. The alarm/trip setpoints for the main condenser air ejector monitors are set to ensure that the limits of Technical Specification 3.7.5 are not exceeded. The alarms alert the operator that an abnormal condition exists. Operability of the Hi and Hi Hi alarms are required for satisfying the main condenser air ejector monitoring instrumentation channel function. The trip function associated with the monitors, initiates when any combination of HI-HI, downscale, or INOP is received on both monitors. The trip function associated with the monitors initiates the off-gas timer which, after 15 minutes, initiates closure of 1(2)-AOG-HCV-102 and the Loop Seal Reservoir Drain Valve. Operability of the 1(2)-AOG-HCV-102 and Loop Seal Reservoir Drain Valve are not required for operability of the main condenser air ejector monitoring instrumentation.

The alarm/trip setpoint for this monitor shall be calculated in accordance with NRC approved methods to provide reasonable assurance that the potential total body accident dose will not exceed a fraction of the limits specified in 10 CFR Part 100.

This specification also includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the offgas treatment system (hydrogen monitors).

The initial CHANNEL CALIBRATION for the Table 7.3.2-1, Functions 1.a, 2.a, 3.a, 4 and 6, instruments was performed using National Bureau of Standards traceable sources which verified that each detector would operate properly over its intended energy range and measurement range. For instruments which were operational prior to this specification being implemented, previously established calibration procedures may be substituted for the initial requirement. Subsequent CHANNEL CALIBRATIONS will be performed using sources that have been related to the initial calibration in order to ensure that each detector is still operational, but the sources need not span the full ranges used in the initial CHANNEL CALIBRATION.

(continued)

Brunswick Units 1 and 2 B 7.3.2-1 Rev. 33

Radioactive Gaseous Effluent Monitoring Instrumentation B 7.3.2 BASES Regulatory Guide 1.21 requires continuous sampling of iodine and particulate in gaseous effluents and subsequent analysis at least weekly. However, a short downtime period of the sample devices is necessary to accomplish applicable ODCM test requirements, sample analysis, or system purging. This time will be accounted for in sample volume calculations. As such, 45 minutes is provided to initiate the auxiliary sampling system or restore the normal sampling devices to OPERABLE status.

Reference ODCMS 7.3.0.5 and B 7.3.0.5 for the performance of post maintenance testing.

Upon identification of a loss of radioactive gaseous effluent monitoring instrumentation, steps shall be taken immediately to install auxiliary sampling. If this cannot be accomplished, releases via the associated effluent pathway shall be secured. Any monitor downtime will be accounted for in sample volume calculations.

The ODCMS are modified by a note to indicate that the annunciator function may be removed from operation for performance of trouble shooting for up to 30 minutes provided the associated function maintains monitoring capability. Upon completion of the troubleshooting, or expiration of the 30 minute allowance, the annunciator must be returned to operation or the applicable condition entered and Required Compensatory Measures taken. Appropriate compensatory actions should be determined and implemented during the loss of annunciator function. Since the 1/2-CAC-AT-1264 alarm is used as an EAL entry condition, removal of the 1/2-CAC-AT-1264 annunciator for 30 minutes for troubleshooting is prohibited when there are any fuel handling activities on the refuel floor or activities where there is the potential to cause a decrease in spent fuel pool water level. This Note is based on the availability of the associated monitor and appropriate compensatory actions to identify changes in the gaseous effluent for the monitored location. The monitor availability and compensatory actions ensure that the 30 minute troubleshooting allowance does not significantly reduce the probability of identifying the hanging radiological conditions to allow appropriate response.

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Concentration-Liquid Effluents B 7.3.3 B 7.3.3 CONCENTRATION-LIQUID EFFLUENTS BASES This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS after dilution in the discharge canal will be less than or equal to 10 times the concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2401 for radionuclides other than dissolved and entrained noble gases. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will not result in exposures within (1) the Section II.A design objectives of Appendix 1,10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR Part 20.1302(b)(2)(i) to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP), Publication 2.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the Lower Limits of Detection (LLDs). Detailed discussion of the LLD and other detection limits can be found in HASL Procedures Manuals, HASL-300 (revised annually),

Currie, L. A. "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

Note that for batch releases, recirculation of at least two tank volumes shall be considered adequate for thorough mixing.

The service water liquid release represents a potential release pathway and not an actual release pathway. Test of this pathway is intended to alert the plant to a potential problem; analysis for principal gamma emitters is sufficient to meet this intent. If analysis for principal gamma emitters indicates a problem (i.e., exceeds the trigger level of 5x10-6 jCi/ml), then complete sampling and analyses shall be performed as per Table 7.3.3-2. The trigger level of 5x1 0-6 jiCi/ml was chosen as being sufficient to provide reasonable assurance of accountability of all nuclides released based upon lower limits of detection and expected concentrations.

Brunswick Units 1 and 2 B 7.3.3-1 Rev. 35

Dose-Liquid Effluents B 7.3.4 B 7.3.4 DOSE-LIQUID EFFLUENTS BASES This specification is provided to implement the requirements of Sections II.A, Ill.A, and IV.A of Appendix I, 10 CFR Part 50. ODCMS 7.3.4 implements the guides set forth in Section II.A of Appendix I. The COMPENSATORY MEASURES provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I of 10 CFR Part 50 to assure that releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I,"April 1977.

The dose or dose commitment to a MEMBER OF THE PUBLIC is based on the 10 CFR Part 50, Appendix I, guideline of:

a. 1.5 mrem to the total body and 5.0 mrem to any organ during any calendar quarter, and

b. 3 mrem to the total body and 10 mrem to any organ during any calendar year, from radioactive material in liquid effluents from each reactor unit to UNRESTRICTED AREAS.

This specification is written for a two unit site.

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Liquid Radwaste Treatment System B 7.3.5 B 7.3.5 LIQUID RADWASTE TREATMENT SYSTEM BASES The requirement that appropriate portions of this system be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criteria 60 of Appendix A to 10 CFR Part 50 and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction of the dose design objectives set forth in Section IL.A of Appendix 1,10 CFR Part 50, for liquid effluents.

Mechanical filtration as per system design is considered to be an appropriate component of the Liquid Radwaste Treatment System.

The requirements of 0.12 mrem total body or 0.4 mrem to any organ in a 31-day period is based on two reactor units having a shared Liquid Radwaste Treatment System.

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Liquid Holdup Tanks B 7.3.6 B 7.3.6 LIQUID HOLDUP TANKS BASES The tanks listed in this specification include all those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System.

Since the condensate storage tanks have continuous influent and effluent, stratification should not occur. Samples taken from the operating condensate transfer pump(s) vent or drain shall be deemed representative of this system.

Appropriate alternatives to the COMPENSATORY MEASURES and TEST REQUIREMENTS are acceptable ifthey provide reasonable assurance that in the event of an uncontrolled release of the tank's content, the resulting concentrations would be less than 10 times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2401 at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

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Dose Rate-Gaseous Effluents B 7.3.7 B 7.3.7 DOSE RATE-GASEOUS EFFLUENTS BASES This specification provides reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a Member of the Public in an Unrestricted Area, either at or beyond the Site Boundary in excess of the design objectives of Appendix I to 10 CFR part 50. This specification is provided to ensure that gaseous effluents from all units on the site will be appropriately controlled. It provides operational flexibility for releasing gaseous effluents to satisfy the Section IL.A and II.C design objectives of Appendix I to 10 CFR part 50.

For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/year to the total body or to less than or equal to 3000 mrems/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/year. This specification does not affect the requirements to comply with the annual limitations of 10 CFR 20.1301.

This specification applies to the release of gaseous effluents from all reactors at the site.

With regard to footnotes (c) and (g) of Table 7.3.7-1:

1. The sampling is only required following transients when the primary coolant DEI and the applicable noble gas monitor increase by a factor of 3.

2. To determine whether the Dose Equivalent 1-131 concentration in the primary coolant has increased by more than a factor of 3, the iodine-I131 analysis performed after the transient will be compared to the most recent routine analysis for Dose Equivalent 1-131 concentration performed before the transient.

3. To determine whether the effluent noble gas monitor has increased by more than a factor of 3, the activity indicated on the monitor's chart recorder after the transient will be compared to the activity indicated on the recorder just before the transient occurred.

4. The intent of footnote (c) is to determine the impact of the transient on the isotopic mix release for the applicable effluent pathway.

5. Sampling described in footnote (g) shall be performed on the applicable effluent pathways. For example, a Unit 1 transient could potentially result in sampling the Stack, Unit 1 Reactor Vent, and the Unit 1 Turbine Building Vent. Each of these pathways should be included in the evaluation. Actual sampling will only be performed on the path or pathways that meet the factor of 3 increase criteria.

6. The intent of the sampling is to evaluate the impact on particulate and iodine releases during the transient. The sampling can be exited when both entry conditions (DEI and noble gas monitor) have returned to steady-state levels below a factor of 3 change or after 7 days, whichever condition comes first.

The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the Lower Limits of Detection (LLDs). Detailed discussion of the LLD and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually),

Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

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Dose Rate--Noble Gases B 7.3.8 B 7.3.8 DOSE -NOBLE GASES BASES This specification is provided to implement the requirements of Sections 1l.B, IllI.A, and IV.A of Appendix I, 10 CFR Part 50. ODCMS 7.3.8 implements the guides set forth in Section II.B of Appendix I. The COMPENSATORY MEASURES provide the required operating flexibility and, at the same time, implement the guides set forth in Section IV.A of Appendix I, to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The TEST REQUIREMENTS implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents will be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY will be based upon the historical annual average atmospheric conditions. NUREG-01 33 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111. The limits of this specification are twice the 10 CFR 50 Appendix I per reactor guidelines because they are written for a two unit site.

Brunswick Units 1 and 2 B 7.3.8-1 Rev. 30 1

Dose - Iodine-131, Iodine-133, Tritium, and Radionuclides in Particulate Form B 7.3.9 B 7.3.9 DOSE - IODINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM BASES This specification is provided to implement the requirements of Section II.C, Ill.A, and IV.A of Appendix I, 10 CFR Part 50. ODCMS 7.3.9 implements the guides set forth in Section II.C of Appendix I. The COMPENSATORY MEASURES provide the required operating flexibility and, at the same time, implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the TEST REQUIREMENTS implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guide 1.109, "Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specification for iodine-131, iodine-1 33, tritium, and radioactive material in particulate form with half-lives greater than 8 days are dependent on the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY. The pathways which are examined in the development of these calculations are: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze, with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man. The limits of this specification are twice the 10 CFR 50 Appendix I per reactor guidelines because they are written for a two unit site.

Brunswick Units 1 and 2 B 7.3.9-1 Rev. 31

GASEOUS RADWASTE TREATMENT SYSTEM B 7.3.10 B 7.3.10 GASEOUS RADWASTE TREATMENT SYSTEM BASES This requirement provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section 11.D of Appendix I to 10 CFR Part

50. The GASEOUS RADWASTE TREATMENT SYSTEM refers to the 30-minute offgas holdup line, stack filter house filtration, and the Augmented Off-Gas-Treatment System.

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VENTILATION EXHAUST TREATMENT SYSTEM B 7.3.11 B 7.3.11 VENTILATION EXHAUST TREATMENT SYSTEM BASES This requirement provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections 11.B and II.C of Appendix 1,10 CFR Part 50, for gaseous effluents. At the Brunswick Steam Electric Plant, the only VENTILATION EXHAUST TREATMENT SYSTEMS shall be those installed for the Turbine Buildings' ventilation.

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Explosive Gas Mixture B 7.3.12 B 7.3.12 EXPLOSIVE GAS MIXTURE BASES This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas treatment system is maintained below the flammability limits of hydrogen. Maintaining the concentration of hydrogen below the flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

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Drywell VENTING or PURGING B 7.3.13 B 7.3.13 DRYWELL VENTING or PURGING BASES This specification provides reasonable assurance that releases from drywell VENTING or PURGING operations will not exceed the annual dose limits of 10 CFR Part 20 for UNRESTRICTED AREAS.

Brunswick Units 1 and 2 B 7.3.13-1 Rev. 25

Total Dose (40 CFR Part 190)

B 7.3.14 B 7.3.14 TOTAL DOSE (40 CFR PART 190)

BASES This specification is provided to meet the dose limitations of 40 CFR Part 190 that have now been incorporated into 10 CFR Part 20 by 46 FR 18525. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 ifthe individual reactors remain within the reporting requirement level. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected) in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203(a)(4) is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in ODCMSs 7.3.3 through 7.3.14. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

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Radiological Environmental Monitoring Program B 7.3.15 B 7.3.15 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM BASES The radiological environmental monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from station operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials are not higher than expected on the basis of effluent measurements and the modeling of the environmental exposure pathways.

The required detection capabilities for environmental sample analyses are tabulated in terms of the Lower Limits of Detection (LLDs). The LLDs required by Table 7.3.15-3 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement.

Detailed discussion of the LLD and other detection limits can be found in HASL Procedure Manual, HASL-300 (revised annually), Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination Application to Radiochemistry" Anal. Chem 40, 586-93 (1968), and Hartwell, L. K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

Groundwater is not monitored by this specification because plant liquid effluents are not tapped as a source for drinking or irrigation purposes.

In the absence of the availability of leafy vegetables intended for human consumption, sampling of indigenous broadleaf vegetation may be performed since the objective of sampling broadleaf vegetation (i.e., to approximate fallout from plant operation) is satisfied in either case.

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Land Use Census B 7.3.16 B 7.3.16 LAND USE CENSUS BASES This specification is provided to ensure that changes in the use of the area at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made, if required, as a result of the census. The best information from door-to-door surveys, aerial surveys, or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.

Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine the minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing2 broadleaf vegetation (i.e., similar to lettuce and cabbage; and (2) a vegetation yield of 2 kg/m Brunswick Units 1 and 2 B 7.3.16-1 Rev. 25

Interlaboratory Comparison Program B 7.3.17 B 7.3.17 INTERLABORATORY COMPARISON PROGRAM BASES The requirement for participation in the Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

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LIST OF TABLES Table No. Title Paqe APPENDIX A A-1 X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE TURBINE BUILDING S ....................................................................... A-4 A-2 DEPLETED X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE TURBINE BUILDINGS ........................................ A-5 A-3 D/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE TURBINE BUILDING S ....................................................................... A-6 A-4 X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE REACTO R BUILDINGS ...................................................................... A-7 A-5 DEPLETED X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE REACTOR BUILDINGS ....................................... A-8 A-6 D/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE REACTO R BUILDINGS ...................................................................... A-9 A-7 X/Q VALUES AT.THE STANDARD DISTANCES FOR RELEASES FROM T HE STA C K ........................................................................................ A -10 A-8 DEPLETED X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE STACK ........................................................ A-11 A-9 D/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM T HE ST A C K ............................................................................................. A-12 A-10 BRUNSWICK PLANT SITE INFORMATION TO BE USED FOR GROUND LEVEL CALCULATIONS WITH NRC "XOQDOQ" PROGRAM ................. A-13 A-11 BRUNSWICK PLANT SITE INFORMATION TO BE USED FOR ELEVATED RELEASE CALCULATIONS WITH NRC "XOQDOQ" PROGRAM ........... A-16 ODCM (BSEP) A-1 Rev. 37

APPENDIX A METEOROLOGICAL DISPERSION FACTOR COMPUTATIONS Carolina Power & Light Company (CP&L) engaged the services of Dames and Moore to assess the transport and dispersion of the effluent in the atmosphere as outlined in Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, NUREG 0133 (USNRC, 1978). The methodology for this assessment was based on guidelines presented in Regulatory Guide (RG) 1.111, Revision 1 (USNRC, 1977). The results of the assessment were to provide the relative depositions flux and relative concentrations (undepleted and depleted) based on numerical models acceptable for use in Appendix I evaluations.

Regulatory Guide 1.111 presented three acceptable diffusion models for use in estimating deposition flux and concentrations. These are (1) particle-in-cell model (a variable trajectory model based on the gradient-transport theory), (2) puff-advection model (a variable trajectory model based on the statistical approach to diffusion), and (3) the constant mean wind direction model referred to here as the straight-line trajectory Gaussian diffusion model (the most widely used model based on a statistical approach). It was resolved that for operational efficiency, the straight line described in XOQDOQ Pro-gram for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations (Draft), NUREG 0324 (USNRC, September 1977) would be used for generating the required analyses of Appendix I. To provide a more realistic accounting of the variability of wind around the plant site, terrain/ recirculation correction factors (TCF) were to be determined from a combined puff-advection/straight-line scheme for a one-year meteorological data base.

In 2005, Murray and Trettel utilized a five-year record of meteorological data from the on-site meteorological program at the Brunswick Steam Electric Plant. This data consisted of all collected parameters at both the 10-meter and 103-meter tower levels for the years 2000 through 2004.

Tables A-1 through A-3 Relative undepleted concentration, relative depleted concentration, and relative deposition flux estimates for ground-level release for standard distances.

Tables A-4 through A-6 Relative undepleted concentration, relative depleted concentration, and relative deposition flux estimates for mixed-mode release for standard distances.

ODCM (BSEP) A-2 Rev. 37 1

Tables A-7 through A-9 Relative undepleted concentration, relative depleted concentration, and relative deposition flux estimates for elevated release for standard distances.

Operation Computations The NRC "XOQDOQ" Program (Revision 1) was obtained and installed on the CP&L computer system. For routine meteorological dispersion evaluations, the "XOQDOQ" Program will be run with the appropriate physical plant data, appropriate meteorological information for the standard distances, and special locations of interest without a terrain/recirculation factor. The input to "XOQDOQ" for ground-level releases are presented in Table A-10 and for elevated releases in Table A-1 1. The resulting computations will have applied the TCFs to produce a final atmospheric diffusion estimate for the site.

In general, it is concluded that the straight-line model is as reasonable a projection of concentrations as the puff-advection model. By inclusion of the terrain correction factors developed by a combination of the puff-advection/straight-line scheme with the results of the XOQDOQ Program, ready evaluation of on-site meteorological data may be made.

Reference Chandler, Martin W. and George Hoopes, Revised Radiological Effluent Technical Specifications: Gaseous Effluent Dilution Factors, Prepared for Carolina Power & Light Company, Brunswick Facility, Dames and Moore, January 18, 1979.

ODCM (BSEP) A-3 Rev. 37 1

TABLE A-1 x/Q Values at the Standard Distances for Releases from the Turbine Buildings Progress Energy - Brunswick Release Type: Annual Release Mode: Ground Level Variable: Relative Concentration (Sec./Cubic Meter)

Calculation Points: Standard Model: Straight Line Gaussian Diffusion Period: 2000-2004 Number of Observations: 43598 Base Distance in Miles Aftd Design 0.25 0.50 0.75 1.00 1.25 1.50 1.75 2.00 2.50 3.00 3.50 4.00 4.50 4.75 Sect Dist Mi NNE 0. 1.0E-05 3.2E-06 1.7E-06 1.1E-06 7.9E-07 6.OE-07 4.9E-07 4.1E-07 3.0E-07 2.3E-07 1.9E-07 1.6E-07 1.3E-07 1.2E-07 NE 0. 2.6E-05 8.2E-06 4.3E-06 2.8E-06 2.OE-06 1.5E-06 1.2E-06 1.OE-06 7.6E-07 6.0E-07 4.8E-07 4.0E-07 3.4E-07 3.2E-07 ENE 0. 4.OE-05 1.2E-05 6.0E-06 3.9E-06 2.8E-06 2.2E-06 1.8E-06 1.5E-06 1.1E-06 9.0E-07 7.4E-07 6.2E-07 5.3E-07 5.0E-07 E 0. 4.1E-05 1.2E-05 6.0E-06 3.9E-06 2.8E-06 2.1E-06 1.8E-06 1.5E-06 1.1E-06 9.0E-07 7.4E-07 6.2E-07 5.4E-07 5.OE-07 ESE 0. 4.3E-05 1.3E-05 6.3E-06 4.OE-06 2.9E-06 2.2E-06 1.8E-06 1.6E-06 1.2E-06 9.4E-07 7.7E-07 6.5E-07 5.7E-07 5.3E-07 SE 0. 6.1E-05 1.8E-05 8.9E-06 5.7E-06 4.1E-06 3.1E-06 2.6E-06 2.2E-06 1.7E-06 1.3E-06 1.1E-06 9.2E-07 8.OE-07 7.5E-07 SSE 0. 1.2E-04 3.1E-05 1.5E-05 9.6E-06 6.9E-06 5.2E-06 4.3E-06 3.7E-06 2.8E-06 2.2E-06 1.9E-06 1.6E-06 1.4E-06 1.3E-07 S 0. 6.3E-05 1.9E-05 9.4E-06 6.1E-06 4.4E-06 3.4E-06 2.8E-06 2.4E-06 1.8E-06 1.4E-06 1.2E-06 9.7E-07 8.4E-07 7.8E-07 SSW 0. 2.8E-05 8.6E-06 4.4E-06 2.9E-06 2.1E-06 1.6E-06 1.3E-06 1.1E-06 8.1E-07 6.4E-07 5.2E-07 4.4E-07 3.8E-07 3.5E-07 SW 0. 1.7E-05 5.4E-06 2.8E-06 1.8E-06 1.3E-06 1.OE-06 8.2E-07 6.8E-07 5.1E-07 4.OE-07 3.2E-07 2.7E-07 2.3E-07 2.2E-07 WSW 0. 1.1E-05 3.5E-06 1.9E-06 1.2E-06 8.9E-07 6.9E-07 5.5E-07 4.6E-07 3.4E-07 2.6E-07 2.1E-07 1.8E-07 1.5E-07 1.4E-07 W 0. 7.9E-06 2.5E-06 1.3E-06 8.8E-07 6.4E-07 4.9E-07 3.9E-07 3.3E-07 2.4E-07 1.9E-07 1.5E-07 1.2E-07 1.1E-07 9.8E-08 WNW 0. 7.4E-06 2.3E-06 1.2E-06 8.OE-07 5.8E-07 4.5E-07 3.6E-07 3.OE-07 2.2E-07 1.7E-07 1.4E-07 1.2E-07 9.9E-08 9.2E-08 NW 0. 7.6E-06 2.4E-06 1.3E-06 8.3E-07 6.OE-07 4.6E-07 3.7E-07 3.1E-07 2.3E-07 1.8E-07 1.4E-07 1.2E-07 1.OE-07 9.4E-08 NNW 0. 1.OE-05 3.2E-06 1.7E-06 1.1E-06 8.1E-07 6.2E-07 5.OE-07 4.2E-07 3.1E-07 2.4E-07 2.OE-07 1.6E-07 1.4E-07 1.3E-07 N 0. 8.6E-06 2.7E-06 1.5E-06 9.7E-07 7.1E-07 5.4E-07 4.4E-07 3.7E-07 2.7E-07 2.1E-07 1.7E-07 1.4E-07 1.2E-07 1.1E-07 ODCM (BSEP) A-4 Rev. 37

TABLE A-2 Depleted x'Q Values at the Standard Distances for Releases from the Turbine Buildings Progress Energy - Brunswick Release Type: Annual Release Mode: Ground Level Variable: Relative Concentration (Sec./Cubic Meter)

Calculation Points: Standard Model: Straight Line Gaussian Diffusion Period: 2000 - 2004 Number of Observations: 43598 Base Distance in Miles Aftd Design 0.25 0.50 0.75 1.00 1.25 1.50 1.75 2.00 2.50 3.00 3.50 4.00 4.50 4.75 Sect Dist Mi NNE 0. 9.6E-06 2.9E-06 1.5E-06 9.5E-07 6.7E-07 5.1E-07 4.OE-07 3.3E-07 2.4E-07 1.8E-07 1.4E-07 1.2E-07 9.9E-08 9.1E-08 NE 0. 2.4E-05 7.5E-06 3.8E-06 2.4E-06 1.7E-06 1.3E-06 1.OE-06 8.5E-07 6.1 E-07 4.7E-07 3.7E-07 3.OE-07 2.5E-07 2.3E-07 ENE 0. 3.8E-05 1.1E-05 5.3E-06 3.4E-06 2.4E-06 1.8E-06 1.5E-06 1.2E-06 9.OE-07 7.OE-07 5.6E-07 4.6E-07 3.9E-07 3.6E-07 E 0. 3.9E-05 1.1 E-05 5.3E-06 3.4E-06 2.4E-06 1.8E-06 1.4E-06 1.2E-06 8.9E-07 6.9E-07 5.6E-07 4.6E-07 3.9E-07 3.6E-07 ESE 0. 4.1E-05 1.2E-05 5.6E-06 3.5E-06 2.5E-06 1.9E-06 1.5E-06 1.3E-06 9.3E-07 7.3E-07 5.9E-07 4.9E-07 4.1E-07 3.8E-07 SE 0. 5.8E-05 1.6E-05 7.9E-06 4.9E-06 3.5E-06 2.6E-06 2.1E-06 1.8E-06 1.3E-06 1.OE-06 8.2E-07 6.9E-07 5.8E-07 5.4E-07 SSE 0. 1.OE-04 2.8E-05 1.3E-05 8.3E-06 5.8E-06 4.4E-06 3.6E-06 3.OE-06 2.2E-06 1.7E-06 1.4E-06 1.2E-06 9.9E-07 9.2E-07 S 0. 6.OE-05 1.7E-05 8.3E-06 5.3E-06 3.8E-06 2.9E-06 2.3E-06 1.9E-06 1.4E-06 1.1E-06 8.8E-07 7.3E-07 6.1E-07 5.7E-07 SSW 0. 2.7E-05 7.9E-06 3.9E-06 2.5E-06 1.8E-06 1.3E-06 1.1E-06 8.9E-07 6.5E-07 5.OE-07 4.OE-07 3.3E-07 2.8E-07 2.5E-07 SW 0. 1.6E-05 4.9E-06 2.5E-06 1.6E-06 1.1E-06 8.5E-07 6.8E-07 5.6E-07 4.OE-07 3.OE-07 2.5E-07 2.OE-07 1.7E-07 1.6E-07 WSW 0. 1.1E-05 3.2E-06 1.7E-06 1.1E-06 7.6E-07 5.8E-07 4.6E-07 3.8E-07 2.7E-07 2.1E-07 1.6E-07 1.3E-07 1.1E-07 1.0E-07 W 0. 7.4E-06 2.3E-06 1.2E-06 7.6E-07 5.4E-07 4.1E-07 3.3E-07 2.7E-07 1.9E-07 1.4E-07 1.1E-07 9.4E-08 7.8E-08 7.2E-08 WNW 0. 7.OE-06 2.1E-06 1.1E-06 7.OE-07 5.OE-07 3.8E-07 3.OE-07 2.5E-07 1.8E-07 1.3E-07 1.1E-07 8.7E-08 7.3E-08 6.7E-08 NW 0. 7.1E-06 2.2E-06 1.1E-06 7.2E-07 5.2E-07 3.9E-07 3.1E-07 2.5E-07 1.8E-07 1.4E-07 1.1E-07 8.9E-08 7.5E-08 6.9E-08 NNW 0. 9.6E-06 2.9E-06 1.5E-06 9.7E-07 6.9E-07 5.2E-07 4.2E-07 3.4E-07 2.5E-07 1.9E-07 1.5E-07 1.2E-07 1.OE-07 9.5E-08 N 0. 8.1E-06 2.5E-06 1.3E-06 8.4E-07 6.OE-07 4.6E-07 3.6E-07 3.OE-07 2.1E-07 1.6E-07 1.3E-07 1.1E-07 8.8E-08 8.1E-08 ODCM (BSEP) A-5 Rev. 37

TABLE A-3 D/Q Values at the Standard Distances for Releases from the Turbine Buildings Progress Energy - Brunswick Release Type: Annual Release Mode: Ground Level Variable: Relative Deposition (Meter**-2)

Calculation Points: Standard Model: Straight Line Gaussian Diffusion Period: 2000-2004 Number of Observations: 43598 Base Distance in Miles Afid Design 0.25 0.50 0.75 1.00 1.25 1.50 1.75 2.00 2.50 3.00 3.50 4.00 4.50 4.75 Sect Dist Mi NNE 0. 4.1E-08 1.4E-08 7.2E-09 4.4E-09 3.OE-09 2.2E-09 1.7E-09 1.3E-09 9.OE-10 6.5E-10 5.0E-10 3.9E-10 3.2E-10 2.9E-10 NE 0. 1.OE-07 3.5E-08 1.8E-08 1.1E-08 7.5E-09 5.5E-09 4.2E-09 3.3E-09 2.3E-09 1.6E-09 1.2E-09 9.8E-10 7.9E-10 7.2E-10 ENE 0. 4.4E-08 1.5E-08 7.6E-09 4.7E-09 3.2E-09 2.3E-09 1.8E-09 1.4E-09 9.6E-10 6.9E-10 5.3E-10 4.1E-10 3.4E-10 3.OE-10 E 0. 2.5E-08 8.3E-09 4.3E-09 2.6E-09 1.8E-09 1.3E-09 1.0E-09 7.9E-10 5.4E-10 3.9E-10 3.OE-10 2.3E-10 1.9E-10 1.7E-10 ESE 0. 2.6E-08 8.7E-09 4.5E-09 2.8E-09 1.9E-09 1.4E-09 1.0E-09 8.3E-10 5.6E-10 4.1E-10 3.1E-10 2.4.E-10 2.0E-10 1.8E-10 SE 0. 3.6E-08 1.2E-08 6.3E-09 3.9E-09 2.6E-09 1.9E-09 1.5E-09 1.2E-09 7.9E-10 5.7E-10 4.3E-10 3.4E-10 2.8E-10 2.5E-10 SSE 0. 5.OE-08 1.7E-08 8.6E-09 5.3E-09 3.6E-09 2.6E-09 2.OE-09 1.6E-09 1.1E-09 7.8E-10 5.9E-10 4.7E-10 3.8E-10 3.4E-10 S 0. 5.3E-08 1.8E-08 9.2E-09 5.6E-09 3.8E-09 2.8E-09 2.1E-09 1.7E-09 1.1E-09 8.3E-10 6.3E-10 5.OE-10 4.OE-10 3.7E-10 SSW 0. 4.3E-08 1.5E-08 7.5E-09 4.6E-09 3.1E-09 2.3E-09 1.8E-09 1.4E-09 9.4E-10 6.8E-10 5.2E-10 4.1E-10 3.3E-10 3.OE-10 SW 0. 4.1E-08 1.4E-08 7.1E-09 4.4E-09 3.OE-09 2.2E-09 1.7E-09 1.3E-09 8.9E-10 6.5E-10 4.9E-10 3.9E-10 3.1E-10 2.8E-10 WSW 0. 2.9E-08 9.8E-09 5.1E-09 3.1E-09 2.1E-09 1.5E-09 1.2E-09 9.4E-10 6.3E-10 4.6E-10 3.5E-10 2.8E-10 2.2E-10 2.OE-10 W 0. 1.8E-08 6.2E-09 3.2E-09 2.OE-09 1.3E-09 9.7E-10 7.4E-10 5.9E-10 4.OE-10 2.9E-10 2.2E-10 1.7E-10 1.4E-10 1.3E-10 WNW 0. 1.5E-08 4.9E-09 2.5E-09 1.6E-09 1.1E-09 7.7E-10 5.9E-10 4.7E-10 3.2E-10 2.3E-10 1.7E-10 1.4E-10 1.1E-10 1.iE-10 NW 0. 1.6E-08 5.2E-09 2.7E-09 1.7E-09 1.1E-09 8.2E-10 6.3E-10 5.OE-10 3.4E-10 2.4E-10 1.9E-10 1.5E-10 1.2E-10 1.1E-10 NNW 0. 1.7E-08 5.9E-09 3.OE-09 1.9E-09 1.3E-09 9.2E-10 7.OE-10 5.6E-10 3.8E-10 2.7E-10 2.1E-10 1.6E-10 1.3E-10 1.2E-10 N 0. 2.3E-08 7.7E-09 3.9E-09 2.4E-09 1.7E-09 1.2E-09 9.2E-10 7.3E-10 4.9E-10 3.6E-10 2.7E-10 2.1E-10 1.7E-10 I1.6E-10 ODCM (BSEP) A-6 Rev. 37

TABLE A-4 X/Q Values at the Standard Distances for Releases from the Reactor Buildings Progress Energy - Brunswick Release Type: Annual Release Mode: Mixed Mode Variable: Relative Concentration (Sec./Cubic Meter)

Calculation Points: Standard Model: Straight Line Gaussian Diffusion Period: 2000-2004 Number of Observations: 43598 Base Distance in Miles Aftd Design 0.25 0.50 0.75 1.00 1.25 1.50 1.75 2.00 2.50 3.00 3.50 4.00 4.50 4.75 Sect Dist Mi NNE 0. 4.9E-06 1.7E-06 9.0E-07 6.0E-07 4.4E-07 3.4E-07 2.8E-07 2.3E-07 1.7E-07 1.4E-07 1.1E-07 9.3E-08 8.OE-08 7.5E-08 NE 0. 1.3E-05 4.3E-06 2.3E-06 1.6E-06 1.1E-06 8.8E-07 7.1E-07 6.0E-07 4.5E-07 3.5E-07 2.9E-07 2.4E-07 2.1E-07 1.9E-07 ENE 0. 1.1E-05 3.5E-06 1.9E-06 1.3E-06 9.6E-07 7.6E-07 6.4E-07 5.5E-07 4.3E-07 3.5E-07 3.OE-07 2.6E-07 2.3E-07 2.2E-07 E 0. 7.8E-06 2.5E-06 1.3E-06 9.OE-07 6.8E-07 5.5E-07 4.5E-07 4.OE-07 3.2E-07 2.7E-07 2.3E-07 2.0E-07 1.8E-07 1.7E-07 ESE 0. 7.8E-06 2.5E-06 1.3E-06 8.8E-07 6.6E-07 5.3E-07 4.4E-07 3.9E-07 3.1E-07 2.6E-07 2.2E-07 1.9E-07 1.7E-07 1.7E-07 SE 0. 1.1E-05 3.4E-06 1.8E-06 1.2E-06 8.9E-07 7.1 E-07 6.OE-07 5.2E-07 4.2E-07 3.5E-07 3.OE-07 2.7E-07 2.4E-07 2.3E-07 SSE 0. 1.6E-05 4.8E-06 2.5E-06 1.6E-06 1.2E-06 9.8E-07 8.3E-07 7.2E-07 5.9E-07 5.OE-07 4.3E-07 3.9E-07 3.5E-07 3.4E-07 S 0. 1.4E-05 4.6E-06 2.5E-06 1.7E-06 1.3E-06 I.0E-06 8.6E-07 7.4E-07 5.9E-07 4.9E-07 4.2E-07 3.6E-07 3.2E-07 3.1E-07 SSW 0. 8.9E-06 3.OE-06 1.6E-06 1.1E-06 8.2E-07 6.5E-07 5.3E-07 4.5E-07 3.5E-07 2.8E-07 2.4E-07 2.OE-07 1.8E-07 1.7E-07 SW 0. 6.7E-06 2.3E-06 1.2E-06 8.3E-07 6.1E-07 4.8E-07 3.9E-07 3.3E-07 2.5E-07 2.OE-07 1.7E-07 1.4E-07 1.2E-07 1.2E-07 WSW 0. 5.2E-06 1.7E-06 9.8E-07 6.5E-07 4.8E-07 3.8E-07 3.1 E-07 2.7E-07 2.OE-07 1.6E-07 1.3E-07 1.1E-07 9.7E-08 9.1E-08 W 0. 3.6E-06 1.2E-06 6.7E-07 4.6E-07 3.5E-07 2.7E-07 2.3E-07 1.9E-07 1.5E-07 1.2E-07 9.6E-08 8.1E-08 7.OE-08 6.6E-08 WNW 0. 3.1 E-06 1.OE-06 5.8E-07 3.9E-07 2.9E-07 2.3E-07 1.9E-07 1.6E-07 1.2E-07 1.OE-07 8.2E-08 7.OE-08 6.1E-08 5.7E-08 NW 0. 3.4E-06 1.1E-06 6.3E-07 4.3E-07 3.2E-07 2.5E-07 2.1E-07 1.8E-07 1.3E-07 1.1E-07 8.8E-08 7.5E-08 6.4E-08 6.OE-08 NNW 0. 4.1 E-06 1.4E-06 7.8E-07 5.3E-07 4.OE-07 3.2E-07 2.6E-07 2.3E-07 1.7E-07 1.4E-07 1.2E-07 9.8E-08 8.5E-08 8.OE-08 N 0. 4.2E-06 1.4E-06 7.9E-07 5.4E-07 4.OE-07 3.2E-07 2.6E-07 2.2E-07 1.7E-07 1.4E-07 1.1E-07 9.5E-08 8.2E-08 7.7E-08 ODCM (BSEP) A-7 Rev. 37

TABLE A-5 Depleted x/Q Values at the Standard Distances for Releases from the Reactor Buildings Progress Energy - Brunswick Release Type: Annual Release Mode: Mixed Mode Variable: Relative Depleted Concentration (Sec./Cubic Meter)

Calculation Points: Standard Model: Straight Line Gaussian Diffusion Period: 2000-2004 Number of Observations: 43598 Base Distance in Miles Aftd Design 0.25 0.50 0.75 1.00 1.25 1.50 1.75 2.00 2.50 3.00 3.50 4.00 4.50 4.75 Sect Dist Mi NNE 0. 4.6E-06 1.5E-06 8.1E-07 5.3E-07 3.8E-07 2.9E-07 2.3E-07 1.9E-07 1.4E-07 1.1E-07 9.OE-08 7.5E-08 6.4E-08 6.OE-08 NE 0. 1.2E-05 3.9E-06 2.1E-06 1.4E-06 9.8E-07 7.6E-07 6.1E-07 5.OE-07 3.7E-07 2.9E-07 2.3E-07 1.9E-07 1.7E-07 1.5E-07 ENE 0. 1.OE-05 3.2E-06 1.7E-06 1.1E-06 8.3E-07 6.6E-07 5.5E-07 4.7E-07 3.6E-07 3.OE-07 2.5E-07 2.2E-07 1.9E-07 1.8E-07 E 0. 7.4E-06 2.2E-06 1.2E-06 7.9E-07 5.9E-07 4.7E-07 4.OE-07 3.5E-07 2.7E-07 2.3E-07 1.9E-07 1.7E-07 1.5E-07 1.4E-07 ESE 0. 7.4E-06 2.2E-06 1.2E-06 7.7E-07 5.8E-07 4.6E-07 3.8E-07 3.3E-07 2.6E-07 2.2E-07 1.8E-07 1.6E-07 1.4E-07 1.4E-07 SE 0. 1.OE-05 3.1E-06 1.6E-06 1.OE-06 7.7E-07 6.1E-07 5.1E-07 4.4E-07 3.5E-07 2.9E-07 2.5E-07 2.2E-07 2.OE-07 1.9E-07 SSE 0. 1.5E-05 4.4E-06 2.2E-06 1.4E-06 1.1E-06 8.4E-07 7.1E-07 6.2E-07 5.OE-07 4.2E-07 3.7E-07 3.3E-07 3.OE-07 2.8E-07 S 0. 1.4E-05 4.2E-06 2.2E-06 1.5E-06 1.1E-06 8.8E-07 7.4E-07 6.3E-07 5.OE-07 4.1E-07 3.5E-07 3.OE-07 2.7E-07 2.6E-07 SSW 0. 8.4E-06 2.7E-06 1.5E-06 9.6E-07 7.1E-07 5.6E-07 4.6E-07 3.9E-07 2.9E-07 2.3E-07 1.9E-07 1.7E-07 1.4E-07 1.4E-07 SW 0. 6.4E-06 2.1E-06 1.1E-06 7.3E-07 5.3E-07 4.1E-07 3.4E-07 2.8E-07 2.1E-07 1.7E-07 1.4E-07 1.2E-07 1.OE-07 9.3E-08 WSW 0. 4.9E-06 1.6E-06 8.5E-07 5.7E-07 4.2E-07 3.3E-07 2.7E-07 2.3E-07 1.7E-07 1.3E-07 1.1 E-07 9.2E-08 7.9E-08 7.4E-08 W 0. 3.4E-06 1.1E-06 6.OE-07 4.1E-07 3.OE-07 2.4E-07 1.9E-07 1.6E-07 1.2E-07 9.8E-08 8.OE-08 6.7E-08 5.8E-08 5.4E-08 WNW 0. 2.9E-06 9.5E-06 5.2E-07 3.5E-07 2.6E-07 2.OE-07 1.7E-07 1.4E-07 1.1E-07 8.3E-08 6.9E-08 5.8E-08 5.OE-08 4.6E-08 NW 0. 3.2E-06 1.OE-06 5.6E-07 3.8E-07 2.8E-07 2.2E-07 1.8E-07 1.5E-07 1.1E-07 8.9E-08 7.3E-08 6.1E-08 5.3E-08 4.9E-08 NNW 0. 3.9E-06 1.2E-06 6.9E-07 4.7E-07 3.5E-07 2.8E-07 2.3E-07 1.9E-07 1.5E-07 1.2E-07 9.6E-08 8.1E-08 7.OE-08 6.5E-08 N 0. 4.OE-06 1.3E-06 7.1E-07 4.7E-07 3.5E-07 2.8E-07 2.3E-07 1.9E-07 1.4E-07 1.1E-07 9.2E-08 7.8E-08 6.7E-08 6.2E-08 ODCM (BSEP) A-8 Rev. 37

TABLE A-6 D/Q Values at the Standard Distances for Releases from the Reactor Buildings Progress Energy- Brunswick Release Type: Annual Release Mode: Mixed Mode Variable: Relative Deposition (Meter**-2)

Calculation Points: Standard Model: Straight Line Gaussian Diffusion Period: 2000-2004 Number of Observations: 43598 Base Distance in Miles Aftd Design 0.25 0.50 0.75 1.00 1.25 1.50 1.75 2.00 2.50 3.00 3.50 4.00 4.50 4.75 Sect Dist Mi NNE 0. 4.OE-08 1.4E-08 7.OE-09 4.3E-09 2.9E-09 2.1E-09 1.6E-09 1.3E-09 8.8E-10 6.4E-10 4.8E-10 3.8E-10 3.1E-10 2.8E-10 NE 0. 1.OE-07 3.4E-08 1.7E-08 1.1E-08 7.3E-09 5.3E-09 4.1E-09 3.2E-09 2.2E-09 1.6E-09 1.2E-09 9.5E-10 7.7E-10 7.OE-10 ENE 0. 3.8E-08 1.3E-08 6.5E-09 4.OE-09 2.8E-09 2.OE-09 1.5E-09 1.2E-09 8.2E-10 6.OE-10 4.5E-10 3.6E-10 2.9E-10 2.6E-10 E 0. 1.8E-08 6.1E-09 3.1E-09 1.9E-09 1.3E-09 9.6E-09 7.4E-10 5.9E-10 4.OE-10 2.9E-10 2.2E-10 1.7E-10 1.4E-10 1.3E-10 ESE 0. 1.9E-08 6.5E-09 3.3E-09 2.OE-09 1.4E-09 I.OE-09 7.8E-10 6.2E-10 4.2E-10 3.OE-10 2.3E-10 1.8E-10 1.5E-10 1.3E-10 SE 0. 2.7E-08 9.OE-09 4.7E-09 2.9E-09 2.OE-09 1.4E-09 1.1E-09 8.7E-10 5.9E-10 4.2E-10 3.2E-10 2.5E-10 2.1E-10 1.9E-10 SSE 0. 3.3E-08 1.1E-08 5.8E-09 3.6E-09 2.5E-09 1.8E-09 1.4E-09 1.1E-09 7.3E-10 5.3E-10 4.OE-10 3.2E-10 2.6E-10 2.3E-10 S 0. 4.3E-08 1.4E-08 7.4E-09 4.6E-09 3.1E-09 2.3E-09 1.7E-09 1.4E-09 9.3E-10 6.8E-10 5.1E-10 4.OE-10 3.3E-10 3.OE-10 SSW 0. 3.9E-08 1.3E-08 6.8E-09 4.2E-09 2.8E-09 2.1E-09 1.6E-09 1.3E-09 8.5E-10 6.2E-10 4.7E-10 3.7E-10 3.OE-10 2.7E-10 SW 0. 3.8E-08 1.3E-08 6.7E-09 4.1E-09 2.8E-09 2.1E-09 1.6E-09 1.2E-09 8.4E-10 6.1E-10 4.6E-10 3.7E-10 3.OE-10 2.7E-10 WSW 0. 2.7E-08 9.3E-09 4.8E-09 2.9E-09 2.OE-09 1.5E-09 1.1E-09 8.9E-10 6.OE-10 4.3E-10 3.3E-10 2.6E-10 2.1E-10 1.9E-10 W 0. 1.7E-08 5.7E-09 3.OE-09 1.8E-09 1.2E-09 9.1E-10 6.9E-10 5.5E-10 3.7E-10 2.7E-10 2.OE-10 1.6E-10 1.3E-10 1.2E-10 WNW 0. 1.3E-08 4.5E-09 2.3E-09 1.4E-09 9.7E-10 7.1E-10 5.4E-10 4.3E-10 2.9E-10 2.1E-10 1.6E-10 1.3E-10 1.0E-10 9.3E-11 NW 0. I.4E-08 4.8E-09 2.5E-09 1.5E-09 1.OE-09 7.6E-10 5.8E-10 4.6E-10 3.1E-10 2.3E-10 1.7E-10 1.4E-10 1.1E-10 1.0E-10 NNW 0. 1.6E-08 5.3E-09 2.7E-09 1.7E-09 1.1E-09 8.3E-10 6.4E-10 5.1E-10 3.4E-10 2.5E-10 1.9E-10 1.5E-10 1.2E-10 1.1E-10 N 0. 2.1E-08 7.2E-09 3.7E-09 2.3E-09 1.6E-09 1.1E-09 8.7E-10 6.9E-10 4.7E-10 3.4E-10 2.6E-10 2.OE-10 1.6E-10 1.5E-10 ODCM (BSEP) A-9 Rev. 37

TABLE A-7

,/Q Values at the Standard Distances for Releases from the Stack Progress Energy - Brunswick Release Type: Annual Release Mode: Elevated Variable: Relative Concentration (Sec./Cubic Meter)

Calculation Points: Standard Model: Straight Line Gaussian Diffusion Period: 2000-2004 Number of Observations: 42768 Base Distance in Miles Aftd Design 0.25 0.50 0.75 1.00 1.25 1.50 1.75 2.00 2.50 3.00 3.50 4.00 4.50 4.75 Sect Dist Mi NNE 0. 1.1E-08 1.7E-08 1.9E-08 2.1E-08 2.3E-08 2.3E-08 2.3E-08 2.3E-08 2.1E-08 1.9E-08 1.7E-08 1.6E-08 1.4E-08 1.4E-08 NE 0. 4.1E-08 4.7E-08 4.6E-08 4.7E-08 4.8E-08 4.7E-08 4.6E-08 4.4E-08 3.9E-08 3.5E-08 3.1E-08 2.8E-08 2.5E-08 2.4E-08 ENE 0. 2.3E-08 2.9E-08 3.2E-08 3.7E-08 4.OE-08 4.2E-08 4.3E-08 4.2E-08 4.0E-08 3.6E-08 3.3E-08 3.OE-08 2.7E-08 2.6E-08 E 0. 3.0E-09 5.7E-09 8.4E-09 1.1 E-08 1.3E-08 1.4E-08 1.5E-08 1.5E-08 1.5E-08 1.5E-08 1.4E-08 1.3E-08 1.2E-08 1.2E-08 ESE 0. 5.4E-09 8.OE-09 9.3E-09 1.OE-08 1.1E-08 1.1E-08 1.1E-08 1.1E-08 1.OE-08 9.7E-09 9.OE-09 8.3E-09 7.7E-09 7.4E-09 SE 0. 8.9E-09 9.8E-09 1.OE-08 1.1E-08 1.1E-08 1.2E-08 1.2E-08 1.2E-08 1.1E-08 1.OE-08 9.3E-09 8.6E-09 7.9E-09 7.6E-09 SSE 0. 1.7E-08 1.6E-08 1.5E-08 1.6E-08 1.6E-08 1.6E-08 1.6E-08 1.5E-08 1.4E-08 1.2E-08 1.1 E-08 1.0E-08 9.2E-09 8.8E-09 S 0. 1.4E-08 1.4E-08 1.6E-08 1.8E-08 2.OE-08 2.1E-08 2.1E-08 2.OE-08 1.9E-08 1.7E-08 1.5E-08 1.4E-08 1.2E-08 1.2E-08 SSW 0. 8.2E-09 1.1 E-08 1.5E-08 2.OE-08 2.4E-08 2.5E-08 2.6E-08 2.6E-08 2.4E-08 2.2E-08 2.OE-08 1.8E-08 1.6E-08 1.5E-08 SW 0. 6.5E-09 1.2E-08 1.6E-08 2.OE-08 2.3E-08 2.4E-08 2.5E-08 2.4E-08 2.3E-08 2.OE-08 1.8E-08 1.7E-08 1.5E-08 1.4E-08 WSW 0. 2.2E-08 2.4E-08 2.4E-08 2.5E-08 2.5E-08 2.5E-08 2.5E-08 2.4E-08 2.2E-08 2.OE-08 1.8E-08 1.6E-08 1.4E-08 1.4E-08 W 0. 2.2E-08 2.2E-08 1.9E-08 1.7E-08 1.7E-08 1.7E-08 1.6E-08 1.5E-08 1.4E-08 1.3E-08 1.2E-08 1.1E-08 9.8E-09 9.4E-09 WNW 0. 1.4E-08 1.6E-08 1.4E-08 1.3E-08 1.2E-08 1.2E-08 1.1E-08 1.1E-08 1.0E-08 9.2E-09 8.4E-09 7.7E-09 7.1E-09 6.8E-09 NW 0. 1.4E-08 1.5E-08 1.4E-08 1.3E-08 1.2E-08 1.2E-08 1.1E-08 1.1E-08 1.OE-08 9.1E-09 8.3E-09 7.5E-09 6.9E-09 6.6E-09 NNW 0. 1.2E-08 1.1E-08 1.OE-08 1.OE-08 1.OE-08 1.1E-08 1.1E-08 1.OE-08 9.9E-09 9.2E-09 8.5E-09 7.8E-09 7.2E-09 6.9E-09 N 0. 7.7E-09 8.9E-09 9.8E-09 1.1E-08 1.2E-08 1.2E-08 1.2E-08 1.2E-08 1.2E-08 1.1 E-08 1.OE-08 9.6E-09 8.9E-09 8.6E-09 ODCM (BSEP) A-1 0 Rev. 37

TABLE A-8 Depleted X/Q Values at the Standard Distances for Releases from the Stack Progress Energy - Brunswick Release Type: Annual Release Mode: Elevated Variable: Relative Depleted Concentration (Sec./Cubic Meter)

Calculation Points: Standard Model: Straight Line Gaussian Diffusion Period: 2000-2004 Number of Observations: 42768 Base Distance in Miles Aftd Design 0.25 0.50 0.75 1.00 1.25 1.50 1.75 2.00 2.50 3.00 3.50 4.00 4.50 4.75 Sect Dist Mi NNE 0. 1.1E-08 1.7E-08 1.9E-08 2.1E-08 2.2E-08 2.3E-08 2.3E-08 2.2E-08 2.OE-08 1.8E-08 1.7E-08 1.5E-08 1.4E-08 1.3E-08 NE 0. 4.1E-08 4.7E-08 4.5E-08 4.6E-08 4.6E-08 4.6E-08 4.4E-08 4.2E-08 3.8E-08 3.3E-08 2.9E-08 2.6E-08 2.3E-08 2.2E-08 ENE 0. 2.3E-08 2.8E-08 3.1E-08 3.6E-08 4.OE-08 4.2E-08 4.2E-08 4.1E-08 3.8E-08 3.5E-08 3.2E-08 2.9E-08 2.6E-08 2.5E-08 E 0. 3.0E-09 5.6E-09 8.3E-09 1.1E-08 1.2E-08 1.4E-08 1.4E-08 1.5E-08 1.5E-08 1.4E-08 1.3E-08 1.2E-08 1.1E-08 1.1E-08 ESE 0. 5.8E-09 7.9E-09 9.1E-09 9.8E-09 1.OE-08 1.1E-08 1.1E-08 1.1E-08 1.OE-08 9.4E-09 8.7E-09 8.OE-09 7.5E-09 7.1E-09 SE 0. 8.9E-09 9.7E-09 9.8E-09 1.OE-08 1.1E-08 1.1E-08 1.1E-08 1.1E-08 1.1E-08 9.8E-09 9.OE-09 8.2E-09 7.5E-09 7.2E-09 SSE 0. 1.7E-08 1.6E-08 1.5E-08 1.5E-08 1.6E-08 1.6E-08 1.5E-08 1.5E-08 1.3E-08 1.2E-08 1.1E-08 9.6E-09 8.7E-09 8.3E-09 S 0. 1.4E-08 1.4E-08 1.6E-08 1.8E-08 2.OE-08 2.OE-08 2.OE-08 2.OE-08 1.8E-08 1.6E-08 1.5E-08 1.3E-08 1.2E-08 1.1E-08 SSW 0. 8.2E-09 1.1E-08 1.5E-08 2.OE-08 2.3E-08 2.5E-08 2.5E-08 2.5E-08 2.3E-08 2.1E-08 1.9E-08 1.7E-08 1.5E-08 1.4E-08 SW 0. 6.5E-09 1.2E-08 1.6E-08 2.OE-08 2.3E-08 2.4E-08 2.4E-08 2.4E-08 2.2E-08 2.OE-08 1.8E-08 1.6E-08 1.4E-08 1.4E-08 WSW 0. 2.2E-08 2.4E-08 2.3E-08 2.4E-08 2.5E-08 2.5E-08 2.4E-08 2.3E-08 2.1E-08 1.9E-08 1.7E-08 1.5E-08 1.4E-08 1.3E-08 W 0. 2.2E-08 2.2E-08 1.9E-08 1.7E-08 1.6E-08 1.6E-08 1.5E-08 1.5E-08 1.4E-08 1.2E-08 1.1E-08 1.OE-08 9.3E-09 8.9E-09 WNW 0. 1.4E-08 1.5E-08 1.4E-08 1.3E-08 1.2E-08 1.2E-08 1.1E-08 1.1E-08 9.7E-09 8.8E-09 8.OE-09 7.3E-09 6.7E-09 6.4E-09 NW 0. 1.4E-08 1.5E-08 1.3E-08 1.2E-08 1.2E-08 1.1E-08 1.1E-08 1.OE-08 9.6E-09 8.7E-09 7.9E-09 7.1E-09 6.5E-09 6.2E-09 NNW 0. 1.2E-08 1.1E-08 1.0E-08 1.0E-08 1.iE-08 1.0E-08 1.0E-08 I1.E-08 9.5E-09 8.8E-09 8.1E-09 7.4E-09 6.8E-09 6.6E-09 N 0. 7.5E-09 8.8E-09 9.6E-09 1.E-08 liE-0B 1.2E-08 1.2E-08 1.2E-08 1.2E-08 1.1E-08 1.E-08 9.2E-09 8.5E-09 8.2E-09 ODCM (BSEP) A-1 1 Rev. 37

TABLE A-9 D/Q Values at the Standard Distances for Releases from the Stack Progress Energy - Brunswick Release Type: Annual Release Mode: Elevated Variable: Relative Deposition (Meter**-2)

Calculation Points: Standard Model: Straight Line Gaussian Diffusion Period: 2000-2004 Number of Observations: 42768 Base Distance in Miles Aftd Design 0.25 0.50 0.75 1.00 1.25 1.50 1.75 2.00 2.50 3.00 3.50 4.00 4.50 4.75 Sect Dist Mi NNE 0. 1.6E-09 1.3E-09 1.OE-09 8.4E-10 6.7E-10 5.5E-10 4.5E-10 4.0E-10 3.1E-10 2.4E-10 2.OE-10 1.6E-10 1.3E-10 1.2E-10 NE 0. 4.5E-09 3.5E-09 2.7E-09 2.2E-09 1.7E-10 1.3E-09 1.1E-09 9.6E-10 7.3E-10 5.7E-10 4.6E-10 3.8E-10 3.1E-10 2.9E-10 ENE 0. 2.7E-09 2.1E-09 1.8E-09 1.5E-09 1.2E-10 1.0E-09 8.4E-10 7.4E-10 5.7E-10 4.5E-10 3.7E-10 3.OE-10 2.5E-10 2.3E-10 E 0. 5.1E-10 4.2E-10 3.7E-10 3.4E-10 2.8E-10 2.3E-10 2.OE-10 1.8E-10 1.4E-10 1.IE-10 8.9E-11 7.3E-11 6.1E-11 5.6E-11 ESE 0. 7.2E-10 5.6E-10 4.4E-10 3.6E-10 2.8E-10 2.3E-10 1.9E-10 1.7E-10 1.3E-10 1.0E-10 8.1E-11 6.6E-11 5.5E-11 5.1E-11 SE 0. 9.2E-10 7.1E-10 5.5E-10 4.6E-10 3.5E-10 2.8E-10 2.3E-10 2.OE-10 1.5E-10 1.2E-10 9.7E-11 7.9E-11 6.6E-11 6.1E-11 SSE 0. 1.4E-09 1.1E-09 8.OE-10 6.4E-10 4.9E-10 3.9E-10 3.2E-10 2.8E-10 2.1E-10 1.7E-10 1.3E-10 1.1E-10 9.1E-11 8.3E-11 S 0. 1.3E-09 1.0E-09 8.5E-10 7.3E-10 5.9E-10 4.9E-10 4.1E-10 3.6E-10 2.8E-10 2.2E-10 1.8E-10 1.5E-10 1.2E-10 1.1E-10 SSW 0. 9.3E-10 8.2E-10 7.9E-10 7.7E-10 6.6E-10 5.6E-10 4.9E-10 4.4E-10 3.4E-10 2.8E-10 2.2E-10 1.8E-10 1.5E-10 1.4E-10 SW 0. i.1E-09 9.5E-10 8.5E-10 7.9E-10 6.6E-10 5.6E-10 4.8E-10 4.2E-10 3.3E-10 2.7E-10 2.2E-10 1.8E-10 1.5E-10 1.3E-10 WSW 0. 2.1E-09 1.6E-09 1.3E-09 1.OE-09 8.OE-10 6.4E-10 5.3E-10 4.7E-10 3.5E-10 2.8E-10 2.2E-10 1.8E-10 1.5E-10 1.4E-10 W 0. 1.6E-09 1.2E-09 8.9E-10 6.8E-10 5.1E-10 4.OE-10 3.2E-10 2.8E-10 2.1E-10 1.6E-10 1.3E-10 i.1E-10 8.9E-11 8.1E-11 WNW 0. 1.1E-09 8.2E-10 5.9E-10 4.4E-10 3.3E-10 2.5E-10 2.OE-10 1.7E-10 1.3E-10 1.iE-10 8.OE-11 6.6E-11 5.5E-11 5.OE-11 NW 0. 1.0E-09 7.8E-10 5.6E-10 4.3E-10 2.2E-10 2.5E-10 2.OE-10 1.7E-10 1.3E-10 1.OE-10 8.OE-11 6.5E-11 5.4E-11 5.0E-11 NNW 0. 8.2E-10 6.2E-10 4.6E-10 3.6E-10 2.8E-10 2.2E-10 1.7E-10 1.5E-10 1.2E-10 9.OE-11 7.3E-11 6.OE-11 5.OE-11 4.5E-11 N 0. 7.7E-10 6.OE-10 4.7E-10 3.9E-10 3.1E-10 2.4E-10 2.OE-10 1.8E-10 1.4E-10 i.iE-10 8.8E-11 7.2E-1I 6.OE-11 5.5E-11 ODCM (BSEP) A-12 Rev. 37

TABLE A-10 Brunswick Plant Site Information To Be Used for Ground Level Calculations with NRC "XOQDOQ" Program Card Columns Description Value to be Used in Type XOQDOQ 1 1 Print input data 1 38 Calculate annual X/Qs for points of interest 1 39 Calculate annual X/Q averages for site radial segments 1 41 Print out set distance x/Qs and D/Qs 1 55 Calculate annual D/Q averages for the set radial segments 1 56 Allow depleted X/Qs (if Decays (1), (2), or (3) are negative) 1 58 Calculate annual D/Qs for points of interest 1 2 1-80 Title card N/A 3 1-5 Number of wind velocity categories 7 6-10 Number of stability categories 7 11-15 Number of distances within terrain data for each sector 1 16-20 Total number of hours in joint wind frequency distribution

21-25 Increment in % for which plotted results are to be printed 5 26-30 Number of titles of receptor types 31-35 Number of release exit locations 1 4 1-5 Height of the measured wind 11 6-20 Half-life (days) used in the X/Q calculations 101.00 2.26 8.00

Appropriate data to be supplied.

ODCM (BSEP) A-13 Rev.37

TABLE A-10 (Cont'd)

Card Columns Description Value to be Used in Type XOQDOQ 5 N/A N/A 6 1-80 Joint wind frequency distribution

7 1-5 Wind velocity units correction 200.00 6-75 Maximum wind speed in each wind class (m/sec) 0.75 3.50 7.50 12.50 18.50 25.00 26.00 8 1-80 Distance in meters at which terrain heights are given All are 100 9 1-80 Terrain heights (in meters, above plant grade) correspond to distances in All are 0 Card Type 8 10 1-25 Number of receptor locations for a particular receptor type Site Boundary 16 Dairy 1 Meat 8 Residence 14 Garden 12 11 1-16 Title of receptor type for receptor locations Site Boundary Dairy Meat Residence

Appropriate data to be supplied.

ODCM (BSEP) A-14 Rev. 37

TABLE A-10 (Cont'd)

Card Columns Description Value to be Used in Type XOQDOQ 1-16 Cont'd Title of receptor type for receptor locations (Cont'd) Garden 12 1-80 Receptor direction and distance (See Table 1) 13 1-80 Title for release point whose characteristics are described on Card

Type 14 14 1-5 Vent average velocity (m/sec) 1.0 6-10 Vent inside diameter (m) 1.0 11-15 Height of vent release point (m) 0.000 16-20 Height of the vent's building (m) 56.9 2

21-25 Minimum cross-sectional area for the vent's building (M ) 2120.0 26-30 Wind height used for vent elevated release 11.0 31-35 Vent heat emission rate (cal/sec) 0.0 15 1 Identification for release point A 2-5 Intermittent releases 0 6-10 Number of intermittent releases per year for this release point 0 11-15 Average number of hours per intermittent release 0

Appropriate data to be supplied.

ODCM (BSEP) A-1 5 Rev. 37

TABLE A-11 Brunswick Plant Site Information To Be Used for Elevated Release Calculations with NRC "XOQDOQ" Program Card Columns Description Value to Be Used in Type XOQDOQ 1 1 Print input data 1 4 Release to be elevated 100% of the time 1 38 Calculate annual X/Qs for points of interest 1 39 Calculate annual X/Q averages for site radial segments 1 41 Print out set distance X/Qs and D/Qs 1 55 Calculate annual D/Q averages for the set radial segments 1 56 Allow depleted x/Qs (if Decays (1), (2), or (3) are negative) 1 58 Calculate annual D/Qs for points of interest 1 2 1-80 Title card N/A 3 1-5 Number of wind velocity categories 7 6-10 Number of stability categories 7 11-15 Number of distances within terrain data for each sector 1 16-20 Total number of hours in joint wind frequency distribution

21-25 Increment in % for which plotted results are to be printed 5 26-30 Number of titles of receptor types 5 31-35 Number of release exit locations 1 4 1-5 Height of the measured wind 104 6-20 Half-life (days) used in the X/Q calculations 101.00 1_ 1 2.26

Appropriate data to be supplied.

ODCM (BSEP) A-16 Rev. 37

TABLE A-11 (Cont'd)

Card Columns Description Value to Be Used in Type XOQDOQ 6-20 Half-life (days) used in the x/Q calculations (Cont'd) 8.00 (Cont'd) 5 N/A N/A 6 1-80 Joint wind frequency distribution

7 1-5 Wind velocity units correction 200.00 6-75 Maximum wind speed in each wind class (m/sec) 0.75 3.50 7.50 12.50 18.50 25.00 26.00 8 1-80 Distance in meters at which terrain heights are given All are 100 9 1-80 Terrain heights (in meters, above plant grade) correspond to distances in All are 0 Card Type 8 10 1-25 Number of receptor locations for a particular receptor type Site Boundary 16 Dairy 1 Meat 8 Residence 14 Garden 12

Appropriate data to be supplied.

ODCM (BSEP) A-17 Rev. 37

TABLE A-1 1 (Cont'd)

Card Columns Description Value to Be Used in Type XOQDOQ 11 1-16 Title of receptor type for receptor locations Site Boundary Dairy Meat Residence Garden 12 1-80 Receptor direction and distance (See Table 1) 13 1-80 Title for release point whose characteristics are described on Card Type

14 14 1-5 Vent average velocity (m/sec) 4.66 6-10 Vent inside diameter (m) 3.58 11-15 Height of vent release point (m) 100.9 16-20 Height of the vent's building (m) 0.0 21-25 Minimum cross-sectional area for the vent's building (M2) 0.00 26-30 Wind height used for vent elevated release 104.0 31-35 Vent heat emission rate (cal/sec) 0.0 15 1 Identification for release point A 2-5 Intermittent releases 0 6-10 Number of intermittent releases per year for this release point 0 11-15 Average number of hours per intermittent release 0

Appropriate data to be supplied.

ODCM (BSEP) A-18 Rev. 37

LIST OF TABLES Table No. Title Paqe APPENDIX B B-1 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES ENE SITE BO UND A R Y ............................................................................................... B-5 B-2 JOINT FREQUENCY DISTRIBUTION FOR ENE SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC PLANT ... B-6 B-3 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES N SITE B O UND AR Y............................................................................................... B -7 B-4 JOINT FREQUENCY DISTRIBUTION FOR N SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC PLANT ............... B-8 B-5 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NNE SITE BO UND AR Y ............................................................................................... B-9 B-6 JOINT FREQUENCY DISTRIBUTION FOR NNE SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC P LA NT ................................................................................................ B -10 B-7 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NE SITE BO UNDA R Y ........................................................................................ B-11 B-8 JOINT FREQUENCY DISTRIBUTION FOR NE SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC P LA NT ..................................................................................................... B -12 B-9 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES E SITE B O UND A R Y............................................................................................. B -13 B-10 JOINT FREQUENCY DISTRIBUTION FOR E SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC PLANT ............. B-14 B-11 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES ESE SITE B O UNDA RY ............................................................................................. B-15 B-1 2 JOINT FREQUENCY DISTRIBUTION FOR ESE SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC P LA NT ..................................................................................................... B-16 ODCM (BSEP) B-1 Rev. 30

LIST OF TABLES (Cont'd)

Table No. Title Paqe APPENDIX B (continued)

B-13 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SE SITE B O UNDA R Y ............................................................................................. B-17 B-14 JOINT FREQUENCY DISTRIBUTION FOR SE SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC PLANT ............. B-18 B-15 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SSE SITE B O UND AR Y ............................................................................................. B-19 B-16 JOINT FREQUENCY DISTRIBUTION FOR SSE SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC P LANT ..................................................................................................... B-2 0 B-17 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES S SITE BO UND AR Y ............................................................................................. B-2 1 B-18 JOINT FREQUENCY DISTRIBUTION FOR S SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC PLANT ............. B-22 B-19 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SSW SITE B O UND A R Y............................................................................................. B-23 B-20 JOINT FREQUENCY DISTRIBUTION FOR SSW SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC P LA NT ..................................................................................................... B-24 B-21 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SW SITE B O UND AR Y ............................................................................................. B-25 B-22 JOINT FREQUENCY DISTRIBUTION FOR SW SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC P LA NT ..................................................................................................... B-26 B-23 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES WSW SITE B O UND A R Y............................................................................................. B-27 B-24 JOINT FREQUENCY DISTRIBUTION FOR WSW SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC P LANT ..................................................................................................... B-28 ODCM (BSEP) B-2 Rev. 30

LIST OF TABLES (Cont'd)

Table No. Title Page APPENDIX B (continued)

B-25 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES W SITE B O UND AR Y............................................................................................. B-29 B-26 JOINT FREQUENCY DISTRIBUTION FOR W SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC PLANT ............. B-30 B-27 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES WNW SITE B O UND A RY ............................................................................................. B-31 B-28 JOINT FREQUENCY DISTRIBUTION FOR WNW SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC P LA NT ..................................................................................................... B-32 B-29 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NW SITE BO UNDA R Y ............................................................................................. B -33 B-30 JOINT FREQUENCY DISTRIBUTION FOR NW SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC P LA NT ..................................................................................................... B -34 B-31 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NNW SITE B O UNDA R Y ............................................................................................. B -35 B-32 JOINT FREQUENCY DISTRIBUTION FOR NNW SECTOR (%) PERIOD 1-1-00 THROUGH 12-31-04, BRUNSWICK STEAM ELECTRIC P LA NT ..................................................................................................... B -36 ODCM (BSEP) B-3 Rev. 30

APPENDIX B Calculation of Vi and Bi Values for the Elevated Plume Values of Vi and Bi were calculated for the elevated plume release from the Brunswick stack using the NRC computer program RABFIN. This program was used to determine the controlling location based upon the releases of Table 3.2-1. In addition it was used to develop the Vi and Bi values for the various noble gas radionuclides at the site boundary at each of the 16 sectors.

Table B-1 presents the Vi and B1 values for the ENE sector which is the controlling location for noble gases for showing compliance with 10CFR20 and 10CFR50. Table B-2 presents the joint frequency distribution for the ENE sector. Tables B-3 through B-32 present the Vi and Bi values and the joint frequency distribution for the remaining sectors. The inputs which were utilized in the RABFIN code are presented below.

1. Height of Stack - 100.9 (m)

2. Stack Diameter - 3.6 (m)

3. Exit Velocity - 5.0 m/sec

4. Wind Height - 104.6 (m)

ODCM (BSEP) B-4 Rev. 37

TABLE B-1 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES ENE SITE BOUNDARY*

Noble Gas Radionuclides Vi Total Body Bi Gamma Air mrem/yr (mrad/yr jICi/sec) ljtCi/ sec)

Kr-83m 2.70E-09 7.46E-07 Kr-85m 1.14E-04 1.69E-04 Kr-85 1.69E-06 2.56E-06 Kr-87 5.12E-04 7.71E-04 Kr-88 1.35E-03 2.02E-03 Kr-89 7.59E-04 1.14E-03 Xe-1 31 m 2.78E-05 4.44E-05 Xe-133m 2.12E-05 3.51E-05 Xe-1 33 2.22E-05 3.52E-05 Xe-1 35m 2.62E-04 3.97E-04 Xe-135 1.82E-04 2.74E-04 Xe-1 37 6.42E-05 9.70E-05 Xe-138 8.09E-04 1.21E-03 Xe-139 1.89E-05 2.83E-05 Ar-41 9.71E-04 1.46E-03

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-5 Rev. 30 I

TABLE B-2 JOINT FREQUENCY DISTRIBUTION FOR ENE SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT F - MAXIMUM WIND SPEED (m/sec)

Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.39 0.00 0.00 0.01 0.10 0.21 0.06 0.01 2 0.55 0.00 0.00 0.02 0.13 0.32 0.08 0.00 3 0.95 0.00 0.00 0.05 0.33 0.44 0.12 0.01 4 5.71 0.00 0.06 0.45 1.58 2.33 1.06 0.22 5 3.69 0.00 0.02 0.24 1.17' 1.58 0.58 0.09 6 0.96 0.00 0.03 0.19 0.39 0.28 0.06 0.00 7 0.77 0.01 0.06 0.22 0.32 0.16 0.00 0.00 Total 13.02 0.02 0.16 1.18 4.01 5.32 1.98 0.34 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 6.16 6.16 Harmonic 0.00 4.85 4.85 ODCM (BSEP) B-6 Rev. 30 1

TABLE B-3 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES N SITE BOUNDARY*

Noble Gas Radionuclides C

Vi Total Body mrem/yr')

ICi/sec)

Bi Gamma Air (mrad/yr"

,QCi/ sec)

Kr-83m 9.02E-10 2.46E-07 Kr-85m 4.25E-05 6.29E-05 Kr-85 6.50E-07 9.85E-07 Kr-87 1.91 E-04 2.88E-04 Kr-88 5.24E-04 7.86E-04 Kr-89 2.49E-04 3.74E-04 Xe-131m 1.03E-05 1.64E-05 Xe-133m 7.88E-06 1.30E-05 Xe-133 8.13E-06 1.28E-05 Xe-135m 9.13E-05 1.39E-04 Xe-135 6.88E-05 1.03E-04 Xe-137 2.01E-05 3.03E-05 Xe-1 38 2.98E-04 4.47E-04 Xe-1 39 5.74E-06 8.62E-06 Ar-41 3.67E-04 5.50E-04

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-7 Rev. 30 1

TABLE B-4 JOINT FREQUENCY DISTRIBUTION FOR N SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec)

Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.11 0.00 0.00 0.01 0.06 0.04 0.00 0.00 2 0.12 0.00 0.00 0.01 0.08 0.02 0.00 0.00 3 0.31 0.00 0.00 0.05 0.17 0.06 0.02 0.00 4 1.27 0.00 0.04 0.23 0.44 0.31 0.16 0.08 5 1.52 0.00 0.02 0.11 0.42 0.49 0.33 0.14 6 0.48 0.00 0.03 0.09 0.17 0.12 0.04 0.02 7 0.43 0.00 0.04 0.16 0.16 0.06 0.01 0.00 Total 4.23 0.02 0.14 0.66 1.50 1.09 0.57 0.25 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 5.78 5.78 Harmonic 0.00 3.87 3.87 ODCM (BSEP) B-8 Rev. 30 1

TABLE B-5 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NNE SITE BOUNDARY*

Noble Gas Vi Total Body Bi Gamma Air Radionuclides (mrem/yr (mrad/yr

(,tCi/sec) 1 iCi/ sec)

Kr-83m 1.55E-09 4.62E-07 Kr-85m 6.42E-05 9.54E-05 Kr-85 9.59E-07 1.45E-06 Kr-87 2.88E-04 4.34E-04 Kr-88 7.66E-04 1.15E-03 Kr-89 4.14E-04 6.22E-04 Xe-131m 1.58E-05 2.52E-05 Xe-133m 1.20E-05 2.OOE-05 Xe-133 1.26E-05 2.OOE-05 Xe-135m 1.45E-04 2.20E-04 Xe-135 1.03E-04 1.55E-04 Xe-137 3.47E-05 5.25E-05 Xe-138 4.54E-04 6.81E-04 Xe-139 1.05E-05 1.58E-05 Ar-41 5.48E-04 8.22E-04

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-9 Rev. 30 I

TABLE B-6 JOINT FREQUENCY DISTRIBUTION FOR NNE SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec)

Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.17 0.00 0.00 0.00 0.06 0.09 0.01 0.00 2 0.33 0.00 0.00 0.00 0.13 0.16 0.03 0.00 3 0.62 0.00 0.00 0.02 0.27 0.23 0.08 0.01 4 2.93 0.00 0.04 0.25 0.86 1.04 0.58 0.15 5 1.86 0.00 0.02 0.18 0.48 0.52 0.41 0.24 6 0.62 0.00 0.02 0.11 0.22 0.20 0.06 0.00 7 0.57 0.00 0.04 0.16 0.22 0.13 0.02 0.00 Total 7.11 0.01 0.13 0.74 2.24 2.38 1.19 0.41 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground Velocity 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity __ I AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 6.29 6.29 Harmonic 0.00 4.62 4.62 ODCM (BSEP) B-10 Rev. 30 1

TABLE B-7 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NE SITE BOUNDARY*

Noble Gas Vi Total Body Bi Gamma Air Radionuclides rmrem/yr mrad/yr

(, tCi/sec) (,pLCi/ sec)

Kr-83m 3.11E-09 1.10E-06 Kr-85m 1.07E-04 1.59E-04 Kr-85 1.55E-06 2.35E-06 Kr-87 4.73E-04 7.11E-04 Kr-88 1.23E-03 1.84E-03 Kr-89 7.51E-04 1.13E-03 Xe-131m 2.69E-05 4.35E-05 Xe-133m 2.05E-05 3.46E-05 Xe-133 2.19E-05 3.51E-05 Xe-135m 2.48E-04 3.77E-04 Xe-135 1.70E-04 2.55E-04 Xe-137 6.53E-05 9.87E-05 Xe-138 7.49E-04 1.12E-03 Xe-1 39 2.22E-05 3.33E-05 Ar-41 8.91E-04 1.34E-03

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-11 Rev. 30 I

TABLE B-8 JOINT FREQUENCY DISTRIBUTION FOR NE SECTOR (%)

PERIOD 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec)

Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.02 0.00 0.00 0.00 0.01 0.00 0.01 2 0.21 0.00 0.00 0.00 0.05 0.10 0.06 3 1.13 0.00 0.00 0.03 0.28 0.50 0.32 4 7.30 0.01 0.15 0.63 2.50 2.51 1.50 5 5.15 0.03 0.09 0.30 1.21 1.99 1.53 6 1.04 0.01 0.06 0.32 0.33 0.24 0.08 7 0.41 0.01 0.12 0.10 0.13 0.03 0.02 Total 15.26 0.06 0.42 1.38 4.51 5.37 3.52 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.23 0.70 1.24 1.93 2.71 3.48 Velocity Elevated 0.74 2.21 3.93 6.14 8.59 11.05 Velocity AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 7.81 7.81 Harmonic 0.00 6.63 6.63 ODCM (BSEP) B-12 Rev. 30 1

TABLE B-9 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES E SITE BOUNDARY*

Noble Gas Vj Total Body Bi Gamma Air Radionuclides (mrem/yr' (mrad/yr" PyCi/ sec ) jiCiI sec)

Kr-83m 1.05E-09 2.15E-07 Kr-85m 5.81 E-05 8.63E-05 Kr-85 9.08E-07 1.38E-06 Kr-87 2.66E-04 4.OOE-04 Kr-88 7.39E-04 1.11E-03 Kr-89 3.12E-04 4.69E-04 Xe-131m 1.39E-05 2.19E-05 Xe-133m 1.06E-05 1.73E-05 Xe-133 1.08E-05 1.69E-05 Xe-135m 1.23E-04 1.86E-04 Xe-135 9.52E-05 1.43E-04 Xe-1 37 2.40E-05 3.62E-05 Xe-138 4.13E-04 6.19E-04 Xe-139 5.31E-06 7.98E-06 Ar-41 5.12E-04 7.69E-04

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-13 Rev. 30 I

TABLE B-10 JOINT FREQUENCY DISTRIBUTION FOR E SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT I MAXIMUM WIND SPEED (m/sec) I Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.04 0.00 0.00 0.01 0.02 0.01 0.00 0.00 2 0.06 0.00 0.00 0.02 0.03 0.01 0.00 0.00 3 0.26 0.00 0.01 0.12 0.10 0.03 0.00 0.00 4 1.50 0.00 0.06 0.39 0.68 0.31 0.04 0.01 5 1.67 0.00 0.04 0.28 0.96 0.39 0.00 0.00 6 0.72 0.00 0.03 0.16 0.35 0.16 0.00 0.00 7 0.67 0.01 0.07 0.25 0.24 0.10 0.00 0.00 Total 4.91 0.02 0.21 1.23 2.38 1.01 0.05 0.01 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity MAXIMUM WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 4.31 4.31 Harmonic 0.00 3.15 3.15 ODCM (BSEP) B-14 Rev. 30

TABLE B-11 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES ESE SITE BOUNDARY*

Noble Gas Vi Total Body Bi Gamma Air Radionuclides (mrem/yr 1 rmrad/yr I, iCi/sec) jLiCi/ sec)

Kr-83m 8.29E-10 2.29E-07 Kr-85m 3.88E-05 5.76E-05 Kr-85 5.93E-07 8.99E-07 Kr-87 1.76E-04 2.65E-04 Kr-88 4.77E-04 7.17E-04 Kr-89 2.42E-04 3.64E-04 Xe-131m 9.43E-06 1.50E-05 Xe-133m 7.20E-06 1.19E-05 Xe-133 7.43E-06 1.17E-05 Xe-135m 8.55E-05 1.30E-04 Xe-1 35 6.29E-05 9.46E-05 Xe-1 37 2.OOE-05 3.02E-05 Xe-1 38 2.75E-04 4.12E-04 Xe-139 6.19E-06 9.30E-06 Ar-41 3.37E-04 5.05E-04

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-15 Rev. 30 I

TABLE B-12 JOINT FREQUENCY DISTRIBUTION FOR ESE SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (misec)

Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.09 0.00 0.00 0.01 0.03 0.03 0.02 0.00 2 0.14 0.00 0.00 0.01 0.05 0.05 0.02 0.00 3 0.29 0.00 0.01 0.06 0.12 0.08 0.02 0.00 4 1.15 0.00 0.06 0.13 0.30 0.41 0.19 0.05 5 1.23 0.00 0.01 0.13 0.24 0.50 0.34 0.01 6 0.70 0.00 0.02 0.05 0.16 0.24 0.21 0.02 7 0.69 0.00 0.04 0.09 0.16 0.23 0.14 0.03 Total 4.28 0.01 0.14 0.48 1.05 1.54 0.95 0.11 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 6.27 6.27 Harmonic 0.00 4.29 4.29 ODCM (BSEP) B-16 Rev. 30

TABLE B-13 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SE SITE BOUNDARY*

Noble Gas Vi Total Body Bi Gamma Air Radionuclides (mrem/yr (mrad/yr (gCi/ sec) piCiI 1 sec)

Kr-83m 8.52E-10 2.44E-07 Kr-85m 3.84E-05 5.70E-05 Kr-85 5.86E-07 8.88E-07 Kr-87 1.73E-04 2.61 E-04 Kr-88 4.71 E-04 7.07E-04 Kr-89 2.41 E-04 3.62E-04 Xe-131m 9.38E-06 1.49E-05 Xe-133m 7.17E-06 1.18E-05 Xe-133 7.42E-06 1.17E-05 Xe-135m 8.42E-05 1.28E-04 Xe-135 6.23E-05 9.36E-05 Xe-137 2.OOE-05 3.02E-05 Xe-1 38 2.70E-04 4.06E-04 Xe-1 39 6.45E-06 9.68E-06 Ar-41 3.32E-04 4.98E-04

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-17 Rev. 30 1

TABLE B-14 JOINT FREQUENCY DISTRIBUTION FOR SE SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT I MAXIMUM WIND SPEED (m/sec)

Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.17 0.00 0.00 0.01 0.03 0.06 0.04 0.02 2 0.20 0.00 0.00 0.02 0.04 0.06 0.06 0.01 3 0.29 0.00 0.00 0.04 0.08 0.09 0.06 0.01 4 1.34 0.00 0.06 0.17 0.34 0.44 0.25 0.07 5 1.13 0.00 0.02 0.04 0.20 0.44 0.41 0.01 6 0.62 0.00 0.04 0.06 0.15 0.19 0.15 0.02 7 0.60 0.00 0.02 0.06 0.17 0.24 0.09 0.02 Total 4.33 0.02 0.15 0.42 1.02 1.51 1.07 0.16 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity I AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 6.49 6.49 Harmonic 0.00 4.38 4.38 ODCM (BSEP) B-1 8 Rev. 30

TABLE B-15 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SSE SITE BOUNDARY*

Noble Gas Radionuclides Vi Total Body mrem/yr ]

(l,* ,e) rmrad/yr Bi Gamma Air

(,pCi/ sec )

Kr-83m 1.15E-09 3.88E-07 Kr-85m 4.49E-05 6.67E-05 Kr-85 6.69E-07 1.01 E-06 Kr-87 2.01 E-04 3.02E-04 Kr-88 5.35E-04 8.04E-04 Kr-89 2.86E-04 4.30E-04 Xe-131m 1.11E-05 1.79E-05 Xe-133m 8.49E-06 1.42E-05 Xe-133 8.92E-06 1.42E-05 Xe-135m 1.OOE-04 1.52E-04 Xe-135 7.20E-05 1.08E-04 Xe-137 2.39E-05 3.61E-05 Xe-138 3.16E-04 4.75E-04 Xe-139 7.36E-06 1.1OE-05 Ar-41 3.82E-04 5.74E-04

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-19 Rev. 30 I

TABLE B-16 JOINT FREQUENCY DISTRIBUTION FOR SSE SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT I MAXIMUM WIND SPEED (m/sec) I Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.28 0.00 0.00 0.02 0.09 0.13 0.04 0.00 2 0.27 0.00 0.00 0.02 0.10 0.09 0.04 0.01 3 0.43 0.00 0.00 0.11 0.17 0.10 0.05 0.00 4 1.74 0.00 0.05 0.22 0.53 0.57 0.29 0.08 5 0.98 0.00 0.01 0.05 0.20 0.36 0.34 0.02 6 0.70 0.00 0.02 0.08 0.08 0.26 0.27 0.00 7 0.66 0.00 0.03 0.10 0.15 0.22 0.14 0.02 Total 5.06 0.01 0.11 0.59 1.32 1.72 1.18 0.13 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity I Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 6.31 6.31 Harmonic 0.00 4.58 4.58 ODCM (BSEP) B-20 Rev. 30

TABLE B-17 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES S SITE BOUNDARY*

Noble Gas Vi Total Body Bi Gamma Air Radionuclides mrem/yr mrad/yr

(, Ci/sec) , gCi/ sec)

Kr-83m 1.31 E-09 3.79E-07 Kr-85m 5.42E-05 8.06E-05 Kr-85 8.09E-07 1.22E-06 Kr-87 2.44E-04 3.68E-04 Kr-88 6.46E-04 9.70E-04 Kr-89 3.57E-04 5.37E-04 Xe-131m 1.33E-05 2.13E-05 Xe-133m 1.01E-05 1.69E-05 Xe-133 1.06E-05 1.69E-05 Xe-135m 1.23E-04 1.87E-04 Xe-135 8.71E-05 1.31E-04 Xe-137 3.01E-05 4.55E-05 Xe-138 3.85E-04 5.79E-04 Xe-139 9.15E-06 1.37E-05 Ar-41 4.64E-04 6.96E-04

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-21 Rev. 30 I

TABLE B-18 JOINT FREQUENCY DISTRIBUTION FOR S SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT I MAXIMUM WIND SPEED (m/sec)

Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.24 0.00 0.00 0.03 0.08 0.08 0.05 0.01 2 0.24 0.00 0.00 0.02 0.09 0.10 0.03 0.01 3 0.42 0.00 0.01 0.09 0.14 0.14 0.05 0.00 4 2.81 0.00 0.06 0.25 0.69 1.07 0.69 0.06 5 1.21 0.00 0.01 0.07 0.30 0.56 0.26 0.00 6 0.62 0.00 0.01 0.05 0.12 0.29 0.14 0.00 7 0.72 0.00 0.03 0.11 0.23 0.26 0.08 0.01 Total 6.27 0.01 0.12 0.61 1.64 2.50 1.30 0.09 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 6.28 6.28 Harmonic 0.00 4.75 4.75 ODCM (BSEP) B-22 Rev. 30 1

TABLE B-19 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SSW SITE BOUNDARY*

Noble Gas Vi Total Body Bi Gamma Air Radionuclides mrem/yr mrad/yr

(, gCi/sec ) (luCi/ sec)

Kr-83m 1.45E-09 3.36E-07 Kr-85m 6.52E-05 9.96E-05 Kr-85 9.75E-07 1.48E-06 Kr-87 2.95E-04 4.45E-04 Kr-88 7.77E-04 1.17E-03 Kr-89 4.48E-04 6.73E-04 Xe-131m 1.58E-05 2.52E-05 Xe-133m 1.20E-05 1.99E-05 Xe-133 1.26E-05 1.99E-05 Xe-135m 1.51E-04 2.30E-04 Xe-135 1.05E-04 1.58E-04 Xe-137 3.81E-05 5.76E-05 Xe-1 38 4.66E-04 7.OOE-04 Xe-139 1.16E-05 1.74E-05 Ar-41 5.61 E-04 8.41 E-04

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-23 Rev. 30 I

TABLE B-20 JOINT FREQUENCY DISTRIBUTION FOR SSW SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT I MAXIMUM WIND SPEED (mlsec) 1 Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.12 0.00 0.00 0.02 0.04 0.06 0.00 0.00 2 0.19 0.00 0.00 0.02 0.08 0.07 0.02 0.00 3 0.33 0.00 0.00 0.05 0.14 0.10 0.04 0.00 4 4.02 0.00 0.05 0.24 0.88 2.03 0.78 0.03 5 1.53 0.00 0.02 0.06 0.29 0.90 0.26 0.00 6 0.81 0.00 0.01 0.06 0.17 0.34 0.23 0.00 7 0.82 0.00 0.03 0.12 0.24 0.31 0.13 0.00 Total 7.84 0.01 0.12 0.56 1.83 3.81 1.46 0.04 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 6.37 6.37 Harmonic 0.00 5.01 5.01 ODCM (BSEP) B-24 Rev. 30

TABLE B-21 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SW SITE BOUNDARY*

Noble Gas Vi Total Body Bi Gamma Air Radionuclides rmrem/yr " (mrad/yr (l~tCi/sec) j.+/-CiI sec)

Kr-83m 1.45E-09 3.61 E-07 Kr-85m 6.40E-05 9.51 E-05 Kr-85 9.58E-07 1.45E-06 Kr-87 2.89E-04 4.36E-04 Kr-88 7.63E-04 1.15E-03 Kr-89 4.38E-04 6.57E-04 Xe-131m 1.56E-05 2.48E-05 Xe-133m 1.19E-05 1.96E-05 Xe-133 1.24E-05 1.96E-05 Xe-135m 1.48E-04 2.24E-04 Xe-135 1.03E-04 1.55E-04 Xe-1 37 3.73E-05 5.63E-05 Xe-138 4.56E-04 6.85E-04 Xe-139 1.13E-05 1.69E-05 Ar-41 5.49E-04 8.24E-04

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-25 Rev. 30 I

TABLE B-22 JOINT FREQUENCY DISTRIBUTION FOR SW SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec)

Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.10 0.00 0.00 0.00 0.02 0.04 0.03 0.00 2 0.21 0.00 0.00 0.01 0.06 0.11 0.02 0.00 3 0.48 0.00 0.00 0.04 0.14 0.22 0.08 0.00 4 3.69 0.00 0.05 0.23 0.77 1.83 0.69 0.10 5 1.55 0.00 0.01 0.08 0.36 0.94 0.16 0.00 6 0.68 0.00 0.02 0.04 0.15 0.36 0.10 0.00 7 0.90 0.01 0.05 0.08 0.30 0.38 0.07 0.00 Total 7.60 0.01 0.13 0.50 1.80 3.89 1.17 0.10 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 6.34 6.34 Harmonic 0.00 4.96 4.96 ODCM (BSEP) B-26 Rev. 30

TABLE B-23 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES WSW SITE BOUNDARY*

Noble Gas Vi Total Body Bi Gamma Air Radionuclides mrem/yr mrad/yr

(,p.Ci/sec) (, tCi/ sec)

Kr-83m 1.75E-09 5.79E-07 Kr-85m 6.69E-05 9.93E-05 Kr-85 9.93E-07 1.50E-06 Kr-87 2.98E-04 4.49E-04 Kr-88 7.92E-04 1.19E-03 Kr-89 4.32E-04 6.50E-04 Xe-131m 1.66E-05 2.67E-05 Xe-133m 1.27E-05 2.12E-05 Xe-133 1.33E-05 2.13E-05 Xe-135m 1.51 E-04 2.29E-04 Xe-135 1.07E-04 1.61 E-04 Xe-137 3.64E-05 5.51E-05 Xe-1 38 4.70E-04 7.06E-04 Xe-139 1.05E-05 1.58E-05 Ar-41 5.67E-04 8.51 E-04

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-27 Rev. 30 1

TABLE B-24 JOINT FREQUENCY DISTRIBUTION FOR WSW SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT F- MAXIMUM WIND SPEED (m/sec)

Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.37 0.00 0.00 0.01 0.12 0.20 0.04 0.00 2 0.45 0.00 0.00 0.02 0.15 0.24 0.05 0.00 3 0.68 0.00 0.01 0.08 0.25 0.28 0.07 0.00 4 3.10 0.00 0.06 0.26 0.69 1.32 0.68 0.10 5 1.51 0.00 0.01 0.10 0.44 0.84 0.11 0.00 6 0.56 0.00 0.03 0.09 0.23 0.20 0.01 0.00 7 0.74 0.00 0.04 0.13 0.34 0.21 0.01 0.00 Total 7.41 0.01 0.14 0.67 2.21 3.29 0.98 0.11 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 6.02 6.02 Harmonic 0.00 4.61 4.61 ODCM (BSEP) B-28 Rev. 30

TABLE B-25 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES W SITE BOUNDARY*

Noble Gas Vi Total Body Bi Gamma Air Radionuclides (mrem/yr (mrad/yr /

, *Ci/sec) (, Ci/ sec )

Kr-83m 1.34E-09 4.89E-07 Kr-85m 5.04E-05 7.49E-05 Kr-85 7.56E-07 1.15E-06 Kr-87 2.24E-04 3.37E-04 Kr-88 6.07E-04 9.11E-04 Kr-89 2.93E-04 4.41 E-04 Xe-131m 1.26E-05 2.03E-05 Xe-133m 9.63E-06 1.61 E-05 Xe-133 1.01E-05 1.61E-05 Xe-1 35m 1.09E-04 1.65E-04 Xe-135 8.11E-05 1.22E-04 Xe-1 37 2.38E-05 3.60E-05 Xe-1 38 3.52E-04 5.28E-04 Xe-1 39 5.78E-06 8.68E-06 Ar-41 4.28E-04 6.42E-04

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-29 Rev. 30 I

TABLE B-26 JOINT FREQUENCY DISTRIBUTION FOR W SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec) I Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.31 0.00 0.00 0.04 0.19 0.08 0.01 0.00 2 0.40 0.00 0.00 0.02 0.26 0.11 0.00 0.00 3 0.44 0.00 0.00 0.06 0.25 0.13 0.00 0.00 4 1.50 0.00 0.04 0.26 0.54 0.49 0.16 0.01 5 1.14 0.00 0.03 0.11 0.44 0.47 0.08 0.01 6 0.47 0.00 0.03 0.11 0.25 0.06 0.00 0.00 7 0.53 0.00 0.02 0.11 0.30 0.09 0.00 0.00 Total 4.79 0.01 0.14 0.71 2.22 1.43 0.25 0.02 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 5.02 5.02 Harmonic 0.00 3.80 3.80 ODCM (BSEP) B-30 Rev. 30 1

TABLE B-27 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES WNW SITE BOUNDARY*

Noble Gas Vi Total Body Bi Gamma Air Radionuclides

mrem/yr I*Ci/sec ) mrad/yr Vima/yrec Kr-83m 1.01 E-09 3.71 E-07 Kr-85m 3.96E-05 5.89E-05 Kr-85 6.01E-07 9.11E-07 Kr-87 1.76E-04 2.65E-04 Kr-88 4.86E-04 7.29E-04 Kr-89 2.10E-04 3.15E-04 Xe-131m 9.88E-06 1.59E-05 Xe-133m 7.57E-06 1.26E-05 Xe-1 33 7.89E-06 1.26E-05 Xe-135m 8.24E-05 1.25E-04 Xe-135 6.41E-05 9.63E-05 Xe-137 1.63E-05 2.47E-05 Xe-138 2.75E-04 4.12E-04 Xe-139 3.71E-06 5.57E-06 Ar-41 3.38E-04 5.07E-04

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-31 Rev. 30 1

TABLE B-28 JOINT FREQUENCY DISTRIBUTION FOR WNW SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT I MAXIMUM WIND SPEED (m/sec) I Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.21 0.00 0.00 0.02 0.13 0.05 0.00 0.00 2 0.25 0.00 0.00 0.04 0.18 0.02 0.00 0.00 3 0.32 0.00 0.01 0.11 0.18 0.02 0.00 0.00 4 0.85 0.00 0.03 0.25 0.34 0.20 0.04 0.00 5 0.88 0.00 0.02 0.14 0.32 0.33 0.06 0.01 6 0.39 0.00 0.03 0.10 0.19 0.06 0.00 0.00 7 0.43 0.00 0.04 0.14 0.21 0.03 0.00 0.00 Total 3.33 0.01 0.13 0.81 1.55 0.71 0.11 0.01 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 4.49 4.49 Harmonic 0.00 3.29 3.29 ODCM (BSEP) B-32 Rev. 30

TABLE B-29 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NW SITE BOUNDARY*

Noble Gas Vi Total Body Bi Gamma Air Radionuclides _mrem/yr mrad/yr

,mrCi/secr nyCi/sec)

Kr-83m 9.83E-10' 3.64E-07 Kr-85m 3.83E-05 5.69E-05 Kr-85 5.83E-07 8.83E-07 Kr-87 1.70E-04 2.55E-04 Kr-88 4.72E-04 7.08E-04 Kr-89 1.95E-04 2.93E-04 Xe-131m 9.58E-06 1.54E-05 Xe-133m 7.34E-06 1.23E-05 Xe-133 7.64E-06 1.22E-05 Xe-135m 7.85E-05 1.19E-04 Xe-135 6.21E-05 9.33E-05 Xe-137 1.50E-05 2.27E-05 Xe-1 38 2.64E-04 3.97E-04 Xe-1 39 3.48E-06 5.23E-06 Ar-41 3.26E-04 4.90E-04

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-33 Rev. 30 I

TABLE B-30 JOINT FREQUENCY DISTRIBUTION FOR NW SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT F- MAXIMUM WIND SPEED (m/sec)

Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.19 0.00 0.00 0.04 0.14 0.01 0.00 0.00 2 0.25 0.00 0.00 0.05 0.18 0.02 0.00 0.00 3 0.30 0.00 0.00 0.13 0.13 0.04 0.00 0.00 4 0.88 0.00 0.02 0.36 0.29 0.14 0.05 0.02 5 0.72 0.00 0.02 0.12 0.29 0.18 0.08 0.03 6 0.31 0.00 0.03 0.09 0.09 0.09 0.01 0.00 7 0.43 0.01 0.05 0.15 0.18 0.05 0.00 0.00 Total 3.09 0.01 0.12 0.94 1.30 0.52 0.14 0.05 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity I I AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 4.42 4.42 Harmonic 0.00 3.13 3.13 ODCM (BSEP) B-34 Rev. 30 1

TABLE B-31 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NNW SITE BOUNDARY*

Noble Gas Radionuclides Vi Total Body Bi Gamma Air imrem/yr" smrad/yr s mr sec ) (I.0/sr Kr-83m 8.53E-10 2.74E-07 Kr-85m 3.71 E-05 5.52E-05 Kr-85 5.69E-07 8.62E-07 Kr-87 1.67E-04 2.51 E-04 Kr-88 4.61 E-04 6.92E-04 Kr-89 1.97E-04 2.96E-04 Xe-131m 9.13E-06 1.46E-05 Xe-133m 6.99E-06 1.16E-05 Xe-133 7.23E-06 1.14E-05 Xe-135m 7.75E-05 1.18E-04 Xe-1 35 6.03E-05 9.06E-05 Xe-137 1.53E-05 2.31E-05 Xe-1 38 2.59E-04 3.89E-04 Xe-1 39 3.77E-06 5.66E-06 Ar-41 3.20E-04 4.80E-04

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-35 Rev. 30 I

TABLE B-32 JOINT FREQUENCY DISTRIBUTION FOR NNW SECTOR (%)

PERIOD 1-1-00 THROUGH 12-31-04 BRUNSWICK STEAM ELECTRIC PLANT I MAXIMUM WIND SPEED (m/sec) I Stability Total 0.36 1.56 3.35 5.59 8.27 10.95 15.65 1 0.17 0.00 0.00 0.04 0.12 0.01 0.00 0.00 2 0.16 0.00 0.00 0.03 0.11 0.02 0.00 0.00 3 0.25 0.00 0.00 0.10 0.12 0.02 0.00 0.00 4 0.91 0.00 0.03 0.29 0.36 0.16 0.05 0.01 5 0.94 0.00 0.02 0.12 0.34 0.22 0.14 0.09 6 0.42 0.00 0.03 0.12 0.16 0.05 0.04 0.02 7 0.36 0.00 0.03 0.16 0.13 0.03 0.00 0.00 Total 3.21 0.01 0.12 0.86 1.34 0.52 0.23 0.12 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.06 0.30 0.76 1.39 2.15 2.98 4.12 Velocity Elevated 0.18 0.95 2.42 4.40 6.83 9.47 13.10 Velocity AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 4.80 4.80 Harmonic 0.00 3.28 3.28 ODCM (BSEP) B-36 Rev. 30

LIST OF TABLES Table No. Title Page APPENDIX C C-1 PARAMETERS FOR COW AND GOAT MILK PATHWAYS ................. C-11 C-2 PARAMETERS FOR THE MEAT PATHWAY ........................................... C-12 C-3 PARAMETERS FOR VEGETABLE PATHWAY ........................................ C-13 ODCM (BSEP) C-1 Rev. 37

APPENDIX C DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES AND TRITIUM This appendix contains the methodology which was used to calculate the dose parameters for radioiodines, particulates, and tritium to show compliance with 10CFR 20 and Appendix I of 10CFR50 for gaseous effluents. These dose parameters Pi and Ri were calculated using the methodology outlined in NUREG 0133, Regulatory Guide 1.109 Revision 1, and letter to J. W.

Davis, "Dose Factors for Hf-181 and SN-113", BSEP File: B10-10530, May 24, 1988 and NUREG CR4653 for Am-241. The following sections provide the specific methodology which was utilized in calculating the Pi and R, values for the inhalation pathway.

C.1 CALCULATION OF Pi The parameter Pi contained in the radioiodine and particulate portion of Section 3.2, includes pathway transport parameters of the ith radionuclide, the receptor's usage of the pathway media and the dosimetry of the exposure. Pathway usage rates and the internal dosimetry are functions of the receptors age. The following section provides the methodology which was used in calculating the Pi values for inclusion into this ODCM.

C.1.1 Inhalation Pathway R = K' (BR) DFA1 (C.1-1) where:

P, dose parameter for radionuclide i for the inhalation pathway, mrem/yr per 3

jiCi/m K' = a constant of unit conversion

= 106 pCi/[LCi BR = the breathing rate of the receptor age group, m3/yr DFAI = the organ inhalation dose factor for the receptor age group for radionuclide i, mrem/pCi. The total body is considered as an organ in the selection of DFAi.

ODCM (BSEP) C-2 Rev. 37

C.2 CALCULATION OF Ri The Radioiodine and Particulate ODCM Specification 7.3.9 is applicable to the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposure occurs. The inhalation and ground plane exposure pathways shall be considered to exist at all locations. The grass-goat-milk, the grass-cow-milk, grass-cow-meat, and vegetation pathways are considered based on their existence at the various locations. Ri values have been calculated for the adult, teen, child, and infant age groups for the ground plane, cow milk, goat milk, vegetable and beef ingestion pathways. The methodology which was utilized to calculate these values is presented below.

C.2.1 Inhalation Pathway Ri = K' (BR)a (DFAi)a (C.2-1) where:

R = Dose factor for each identified radionuclide i of the organ of interest, 3

mrem/yr per jiCi/m K' = A constant of unit conversion

= 106 pCi/g*Ci (BR)a = Breathing rate of the receptor of age group a, m3/yr (DFAi), = Organ inhalation dose factor for radionuclide i for the receptor of age group a, mrem/pCi ODCM (BSEP) C-3 Rev. 37 1

The breathing rates (BR)a for the various age groups are tabulated below, as given in Table E-5 of the Regulatory Guide 1.109, Revision 1.

Age Group (a) Breathing Rate (m3/yr)

Infant 1400 Child 3700 Teen 8000 Adult 8000 Inhalation dose factors (DFAj), for the various age groups are given in Tables E-7 through E-10 of Regulatory Guide 1.109, Revision 1, BSEP File:

B10-10530, Letter to J. W. Davis "Dose Factors for Hf-181 and Sn-113,"

May 24,1988, and NUREG CR4653 for AM-241.

C.2.2 Ground Plane Pathway Ro = Ii K'K"(SF) DFGj (1-e-'")/I*. (C.2-2) where:

RI = Dose factor for the ground plane pathway for each identified radionuclide i for the organ of interest, mrem/yr per pCi/sec per M-2 K' = A constant of unit conversion

= 106 pCi/laCi K" = A constant of unit conversion

= 8760 hr/year

, = The radiological decay constant for radionuclide i, sec1 t = The exposure time, sec

= 4.73 x 108 sec (15 years)

DFG = The ground 2

plane dose conversion factor for radionuclide i; mrem/hr per pCi/m ODCM (BSEP) C-4 Rev. 37 1

SF = The shielding factor (dimensionless)

= Factor to account for fractional deposition of radionuclide i For radionuclides other than iodine, the factor Ii is equal to one. For radioiodines, the value of li may vary. However, a value of 1.0 was used in calculating the R values in Table 3.3-2.

A shielding factor of 0.7 is suggested in Table E-15 of Regulatory Guide 1.109 Revision 1. A tabulation of DFG, values is presented in Table E-6 of Regulatory Guide 1.109, Revision 1.

C.2.3 Grass-Cow or Goat Milk Pathway RiM =1IK'QFUapFm(DFLI)a e-- t' SF.r(

ffs-

- e-XE, )

)+ ]k Bv(1- e-Xtb )rl-

+ (1-fpf) )[

eXEtie

) Bgiv(1 - e-ktb Pxi I

e-t (C.2-3) where:

Rim = Dose factor for the cow milk or goat milk pathway, for each identified radionuclide i for the organ of interest, mrem/yr per giCi/sec per m2 K' = A constant of unit conversion 106 pCi/gCi QF = The cow's or goat's feed consumption rate. kg/day (wet weight)

Uap = The receptor's milk consumption rate for age group a, liters/yr 2

Yp = The agricultural productivity by unit area of pasture feed grass, kg/m 2

YS = The agricultural productivity by unit area of stored feed, kg/m Fm The stable element transfer coefficients, pCi/liter per pCi/day ODCM (BSEP) C-5 Rev. 37 1

r = Fraction of deposited activity retained on cow's feed grass (DFLi)a The organ ingestion dose factor for radionuclide i for the receptor in age group a, mrem/pCi Ei = Xi + XW j = The radiological decay constant for radionuclide i, sec1 k = The decay constant for removal of activity on leaf and plant surfaces by weathering sec'

= 5.73x10-7 sec1 (corresponding to a 14 day half-life) tf = The transport time from feed to cow or goat to milk, to receptor, sec th = The transport time from harvest to cow or goat consumption, sec tb = Period of time that soil is exposed to gaseous effluents, sec Biv = Concentration factor for uptake of radionuclide i from the soil by the edible parts of crops, pCi/Kg (wet weight) per pCi/Kg (dry soil) 2 P = Effective surface density for soil, Kg (dry soil)/m fp = Fraction of the year that the cow or goat is on pasture f = Fraction of the cow feed that is pasture grass while the cow is on pasture te = Period of pasture grass and crop exposure during the growing season, sec

= Factor to account for fractional deposition of radionuclide i For radionuclides other than iodine, the factor li is equal to one. For radioiodines, the value of Ii may vary. However, a value of 1.0 was used in calculating the R values Tables 3.3-9 through 3.3-16.

Milk cattle and goats are considered to be fed from two potential sources, pasture grass and stored feeds. Following the development in Regulatory Guide 1.109, Revision 1, the value of f, was considered unity in lieu of site-specific information. The value of fp was 0.667 based upon an 8-month grazing period.

ODCM (BSEP) C-6 Rev. 37 1

Table C-1 contains the appropriate parameter values and their source in Regulatory Guide 1.109, Revision 1.

The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the Ri is based on X/Q:

RTM K'K"FmQFUap(DFLi)a 0.75(0.5)] (C.2-4) where:

RTM = Dose factor for the cow or goat milk pathway for tritium for the organ of 3

interest, mrem/yr per jiCi/m K' = A constant unit of conversion, 106 pCi/ýiCi K'" = A constant unit of conversion

= 10 3gm/kg 3

H = Absolute humidity of the atmosphere, gm/m 0.75 = The fraction of total feed that is water 0.5 = The ratio of the specific activity of the feed grass water to the atmospheric water Other parameters and values as defined previously. A value for H of 8 grams/meter 3, was used in lieu of site-specific information.

C.2.4 Grass-Cow-Meat Pathway The integrated concentration in meat follows in a similar manner to the development for the milk pathway, therefore:

RB =IiK'QFU.aFf (DFLI)a e-*

Fr( -e*E.

Biv1- -*1b -fpf,) ) BF( --- .

lLYpX-E,

{fpfr( -e- )4+ Bv(1-ek t Pxj,,kb + (1- f r(1 - e-"t)e Pk,,

t ib th

)le (C.2-5) where:

R = Dose factor for the meat ingestion pathway for radionuclide i for any organ of interest, mrem/yr per jiCi/sec per M-2 ODCM (BSEP) C-7 Rev. 37 1

Ff = The stable element transfer coefficients, pCi/Kg per pCi/day Uap = The receptor's meat consumption rate for age group a, kg/yr t = The transport time from slaughter to consumption, sec th = The transport time from harvest to animal consumption, sec te = Period of pasture grass and crop exposure during the growing season, sec Ii = Factor to account for fractional deposition of radionuclide i For radionuclides other than iodine, the factor Ii is equal to one. For radioiodines, the value of I may vary. However, a value of 1.0 was used in calculating the R values in Tables 3.3-6 through 3.3-8.

All other terms remain the same as defined in Equation C.2-3. Table C-2 contains the values which were used in calculating Ri for the meat pathway.

The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, R, is based on X/Q.

RTB= J K'K-FfQFUab(DFLi)a[0.75( 0.5)](C.2-6) where:

RTB = Dose factor for the meat ingestion pathway for tritium for any organ of 3

interest, mrem/yr per jiCi/m All other terms are as defined in Equation C.2-4 and C.2-5, above.

C.2.5 Vegetation Pathway The integrated concentration in vegetation consumed by man follows the expression developed in the derivation of the milk factor. Man is considered to consume two types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption, therefore:

ODCM (BSEP) C-8 Rev. 37

Riv =IiK'(DFLi)a

) B iv(1 - tLtb)

Bjv(1 - e - +U afgee ith r(1 - e-'e E t e-)

?A W - yLYEP

- )'i',) itb L YVXE + P)Li (C.2-7) where:

Riv = Dose factor for vegetable pathway for radio nuclide i for the organ of interest mrem/yr per liCi/sec per m -2 K' = a constant of unit conversion

= 106 pCi/jiCi UL = The consumption rate of fresh leafy vegetation by the receptor age group a, kg/yr Us = The consumption rate of stored vegetation by the receptor in age group a, kg/yr fg = The fraction of the annual intake of stored vegetation grown locally fL = The fraction of annual intake of fresh, leafy vegetables grown locally tL = The average time between harvest of leafy vegetation and its consumption, sec th The average time between harvest of stored vegetation and its consumption, sec 2

Yv = The vegetation area density, kg/M te = Period of leafy vegetable exposure during growing season, sec Ii = Factor to account for fractional deposition of radionuclide i For radionuclides other than iodine, the factor li is equal to one. For radioiodines, the value of li may vary. However, a value of 1.0 was used in Tables 3.3-3 through 3.3-5.

All other factors were defined above.

ODCM (BSEP) C-9 Rev. 37 1

Table C-3 presents the appropriate parameter values and their source in Regulatory Guide 1.109, Revision 1.

In lieu of site-specific data default values for fL and fg, 1.0 and 0.76, respectively, were used in the calculation of Ri. These values were obtained from Table E-15 of Regulatory Guide 1.109, Revision 1.

The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, the Ri is bases on X/Q:

RTv K'K- [UL fL + Us fg](DFLi )a 0.075 05] (C.2-8) where:

R TV Dose factor for the cow or goat milk pathway for tritium for the organ of 3

interest, mrem/yr per giCi/m All other terms remain the same as those in Equations C.2-4 and C.2-7.

ODCM (BSEP) C-10 Rev. 37

TABLE C-1 PARAMETERS FOR COW AND GOAT MILK PATHWAYS Parameter Value Reference (Re-q. Guide 1.109, Rev. 1)

QF (kg/dlay) 50 (cow) Table E-3 6 (goat) Table E-3 Y, (kg/n n2) 0.7 Table E-15 tf (secornds) 1.73 x 105 (2 days) Table E-15 r 1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15 (DFLi)a (mrem/pCi) Each radionuclide Tables E-1 1 to E-14*

Frm (pCi/ 1 per pCi/day) Each stable element Table E-1 (cow)*

Table E-2 (goat)**

tb (seco nds) 4.73 x 108 (15 yr) Table E-15 Y. (kg/n 12) 2.0 Table E-15 Yp (kg/n 12) 0.7 Table E-15 th (seco nds) 7.78 x 106 (90 days) Table E-15 Uap (literrs/yr) 330 infant Table E-5 330 child Table E-5 400 teen Table E-5 310 adult Table E-5 te (secornds)

.... i 2.59 x 106 (pasture) Table E-15 5.18 x 106 (stored feed)

Bi, pCi/Kg (wet weight) Each stable element Table E-1 per pCi/Kg (dry soil) 2 P Kg (dry soil)/m 240 Table E-15

Reference 1, BSEP File: B130-10530, Letter to J. W. Davis "Dose Factors for Hf-1 81 and Sn-1 13," May 24, 1988, and NUREG CR4653 for AM-241.

- Where goat data was not available, cow value Fm was assumed.

ODCM (BSEP) C-11 Rev. 37

TABLE C-2 PARAMETERS FOR THE MEAT PATHWAY Reference Parameter Value (Reg. Guide 1.109, Rev. 1)

Table E-15 r 1.0 (radioiodines) 0.2 (particulates) Table E-15 Ff (pCi/Kg per pCi/day) Each stable element Table E-1

Uap (Kg/yr) 0 infant Table E-5 41 child Table E-5 65 teen Table E-5 110 adult Table E-5 (DFLi)a (mrem/pCi) Each radionuclide Tables E-11 to E-14 Yp (kg/M 2) 0.7 Table E-15 Y, (kg/M 2) 2.0 Table E-15 tb (seconds) 4.73 x 108 (15 yr) Table E-15 t, (seconds) 1.73 x 106 (20 days) Table E-15 th (seconds) 7.78 x 106 (90 days) Table E-15 te (seconds) 2.59 x 106 (pasture) Table E-15 5.18 x 106 (stored feed)

QF (kg/day) 50 Table E-3 Bi, pCi/Kg (wet weight) Each stable element Table E-1*

per pCi/Kg (dry soil) 2 P kg (dry soil)/m 240 Table E-15

Reference 1, BSEP File: B10-10530, Letter to J. W. Davis "Dose Factors for Hf-181 and Sn-1 13," May 24, 1988, and NUREG CR4653 for AM-241.

ODCM (BSEP) C-12 Rev. 37

TABLE C-3 PARAMETERS FOR THE VEGETABLE PATHWAY Reference Parameter Value (Re-q. Guide 1.109, Rev. 1)

Table E-1 r (dimensionless) 1.0 (radioiodines) 0.2 (particulates) Table E-1 (DFLi). (mrem/Ci) Each radionuclide Tables E-11 to E-14*

ua (kg/yr) -Infant 0 Table E-5

-Child 26 Table E-5

-Teen 42 Table E-5

-Adult 64 Table E-5 Us (kg/yr) -Infant 0 Table E-5

-Child 520 Table E-5

-Teen 630 Table E-5

-Adult 520 Table E-5 tL (seconds) 8.6 x 104 (1 day) Table E-15 th (seconds) 5.18 x 106 (60 days) Table E-15 Yv (kg/m 2) 2.0 Table E-15 te (seconds) 5.18 x 106 (60 days) Table E-15 tb (seconds) 4.73 x 108 (15 yr) Table E-15 P (Kg[dry soil]/m 2) 240 Table E-15 Bj, (pCi/Kg[wet weight] Each stable element Table E-1*

per pCi/kg [dry soil])

Reference 1, BSEP File: B130-10530, Letter to J. W. Davis "Dose Factors for Hf-1 81 and Sn-1i13," May 24, 1988, and NUREG CR4653 for AM-241.

ODCM (BSEP) C-1 3 Rev. 37 1

APPENDIX D LOWER LIMIT OF DETECTION (LLD)

The following discussion of LLD is taken from NUREG-0473, Rev. 2, February 1, 1980. It represents the bases for LLD footnotes (e) in Table 7.3.3-1, (e) in Table 7.3.3-2, (a) in Table 7.3.7-1, and (b) in Table 7.3.15-3 of the BSEP ODCM Specifications. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95 percent probability with 5 percent probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

LLD -466sb E.V-2.22x 106. Y-exp(-AAt)

LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),

sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

E is the counting efficiency (as counts per transformation),

V is the sample size (in units of mass or volume),

2.22 x 106 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

X is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting (for plants effluents, not environmental samples).

The value of sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. Typical values of E, V, Y, and At shall be used in the calculation.

ODCM (BSEP) D-1 Rev. 25

APPENDIX E RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION NUMBERS Liquid Effluent Monitoring Instruments A. Liquid Radwaste Radioactivity Monitor 2-D12-RM-K604 B. Liquid Radwaste Effluent Flow Measurement 2-G16-FIT-N057 Device C. Main Service Water Effluent Radioactivity 1(2)-D1 2-RM-K605 Monitor D. Stabilization Pond Effluent Composite Sampler 2-DST-XE-5027 E. Stabilization Pond Effluent Flow Measurement 2-DST-FIT-5026 Device F. Condensate Storage Tank Level Indicating 1(2)-CO-LIT-I 160 Device G. Groundwater Extraction Effluent Composite 0-GWE-COMP-SAMPLER-Sampler 1 H. Groundwater Extraction Effluent Flow 0-GWE-FIT-1 Measurement Device I. Stabilization Facility Effluent Composite 0-SDSF-COMP-SAMPLER-Sampler 2 J. Stabilization Facility Effluent Flow Measurement 0-SDSF-FIT-2 Device II. Gaseous Effluent Monitoring Instruments

1. Main Stack Monitoring System 2-D12-RM-23S

a. Noble Gas Activity Monitor (2-D12-RE-4982)

b. Iodine Sampler Cartridge IRSH35 Prefilters A or B

c. Particulate Sampler Filter IRSH35 Prefilters A or B

d. System Effluent Flow Rate 2-VA-FIQ-5902-1 OR -2 Measurement Device

e. Low Range Sampler Flow Rate 2-D12-FE-4597 Measurement Device

f. Mid/High Range Sampler Flow Rate 2-D12-FE-4596 Measurement Device ODCM (BSEP) E-1 Rev. 35 1

APPENDIX E (Cont'd)

RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION NUMBERS (Cont' d)

2. Reactor Building Ventilation Monitoring System

a. Noble Gas Activity Monitor 1 (2)-CAC-AQ H-1264-3

b. Iodine Sampler Cartridge 1 (2)-CAC-AQ H-1264-2 (collection cartridge only)

c. Particulate Sampler Filter 1(2)-CAC-AQH-1264-1 (collection filter only)

d. System Effluent Flow Rate 1(2)-VA-FIQ-3356 Measurement Device

e. Sampler Flow Rate Measurement 1(2)-CAC-FI-1264 Device

3. Turbine Building Ventilation Monitoring System

a. Noble Gas Activity Monitor 1(2)-DI2-RM-23 (1(2)-D12-RE-4563)

b. Iodine Sampler Cartridge 1(2)-IRTB32 (Recirculation Mode) Prefilters A or B Iodine Sampler Cartridge for Once 2-D12-OTV-FLT-03(04)

Through Ventilation (Unit 2 only)

c. Particulate Sampler Filter 1(2)-IRTB32 (Recirculation Mode) Prefilters A or B Particulate Sampler Filter Once Through 2-D12-OTV-FLT-03(04)

Ventilation (Unit 2 only)

d. System Effluent Flow Rate Measurement 1(2)-VA-FIQ-3358 Device (Recirculation Mode)

System Effluent Flow Rate Measurement 2-VA-FIQ-7554 Device for Once Through Ventilation (Unit 2 only)

e. Low Range Sampler Flow Rate 1(2)-D12-FE-4542 Measurement Device Sampler Flow Rate Measurement Device for Once Through Ventilation 2-D1 2-FE-7559 (Unit 2 only)

f. Mid/High Range Sampler Flow Rate 1(2)-D12-FE-4543 Measurement Device ODCM (BSEP) E-2 Rev. 35 1

APPENDIX E (Cont'd)

RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION NUMBERS (Cont'd)

4. Main Condenser Off-Gas Treatment System (AOG) Monitor

a. Noble Gas Activity Monitor 1(2)-AOG-RM-103

5. Main Condenser Off-Gas Treatment System Explosive Gas Monitoring System

a. Recombiner Train A

1. First Hydrogen Monitor 1(2)-OG-AIT-4284 -

Stream 1

2. Second Hydrogen Monitor 1(2)-OG-AIT-4324 -

Stream 2

b. Recombiner Train B

1. First Hydrogen Monitor 1(2)-OG-AIT-4324 -

Stream 1

2. Second Hydrogen Monitor 1(2)-OG-AIT-4284 -

Stream 2

6. Main Condenser Air Ejector Radioactivity Monitor

a. Noble Gas Activity Monitor 1 (2)-D12-RM-K601A l(2)-D12-RM-K601B

7. Hot Shop Ventilation Monitoring System

a. Iodine Sampler Cartridge

b. Particulate Sampler Filter

c. Sampler Flow Rate Measurement 2-D12-FI-6094 Device

8. Radioactive Materials Container and Storage Building Decontamination Facility

a. Iodine Sampler Cartridge

b. Particulate Sampler Filter

c. Sampler Flow Rate Measurement Device ODCM (BSEP) E-3 Rev. 35 1

APPENDIX F LIQUID AND GASEOUS EFFLUENT SYSTEM DIAGRAMS ODCM (BSEP) F-1 Rev. 25

FIGURE F-1 Liquid Radwaste Effluent System RADIATION MONITORING BLOCK STATION VALVE LIQUID I* -- - 1' _RADWASTE\

/TO MEET 42 SEC ICFT LIMITS)

/

POTENTIAL LIQUID RELEASE PATHWAYS

" MAIN SERVICE WATER DISCHARGE LINES HAVE CONTINUOUS RADIOACTIVITY MONITORS.

" THE STABILIZATION POND EFFLUENT TO THE INTAKE CANAL HAS A PROPORTIONAL COMPOSITE SAMPLER FUELCASK AND A FLOW MEASURING DEVICE.

THE REACTOR BUILDING COMPONENT COOLING WATER (SERVICE WATER)

LINE HAS CONTINUOUS RADIOACTIVITY MONITORS.

LOW PURITY I HIGH ACTIVITY LIQUID WASTES NOTES

" SOLID RADWASTE SYSTEM - NOT USED LIQUID PROCESS . HIGH INTEGRITY MEDIA CONTAINER so STORAGEIBURIAL ODCM (BSEP) F-2 Rev. 26

FIGURE F-2 Gaseous Radwaste Effluent System GASEOUS RADWASTE TO MEET 10CFR2O AND IOCFR50 EFFLUENT LIMITS CONDENSER AIR EJECTION RAD MONITOR IL 30 CONDENSER AIR EJECTION RAD MONITOR 02 MONITORS CONDENSER 1H2MONITORS AIR EJECTION RAD MONITOR SJ E RECOMSINER A ICNOENSER I . H2 MONITORS -- F I I l I LSJAE JRECOMBINER.. l,* B *..I %

181 I RA*NB I __. _____ 30MIN DELIAYLINE CONDENSER AIR EJECTION RAD MONITOR SECONDARY CONTAINMENT ISOLATION RAD MONITOR UNIT I T INEOBEUILDING VENTILATION MON[I NOTATIONS

OTHER PATHWAYS MONITORED FOR RELEASE

- BUILDING EXFILTRATION

- CIRC WATER PIPING VENTILATION ENTILATION EXHAUS FILTER SYSTEM SYSTEM THE HCV-102 VALVEAUTOMATICALLY GASEOUS ISOLATES 15 MIN AFTER HIGH READING RADWASTE ON THE CORESPONDING CONDENSER AO IODINE CARTRIDGE AND - TO MEET AIR EJECTOR RAD MONITOR VENTILAT ONE FILTER SYSTEM PARTICULATE FILTER T EACH VENTILATION MONITORING VETLION EXA 9UJ ITRY i'iý PRIUAEFLE SAMPLER 10CFR50 AND SYSTEM CONTAINS:

EFFLUENT LIMITS ) -NOBLE GAS ACTIVITY MONITOR IR °°c °"F IODINE CARTRIDGE AND - IODINE SAMPLER CARTRIDGE

- PARTICULATE SAMPLER FILTER

- SYSTEM FLOW MONITOR VENTILATION EXHAUST HEPA FILTER SYSTEM PARTICULATE FILTER - SAMPLER FLOW MONITOR MONITOR SLOW 4EVELWAREHOUSE 1 HEPA FILTER SYEI PARTICULATE FILTER VENTILATION EXHAUST MONITO SECONDARY CONTAINMENT ISOLATION RAD MONITOR VENTILTIONREXACOUSTLDING I LYTM UNIT 2 TURIE BUIA VENTILATION MONITORING VENTILATION EXHAUST FILTER SYSTEMSYSTEM ONCE THROUGHVENTILATION EXHAUST(OPTIONAL)

ODCM (BSEP) F-3 Rev. 32 1

APPENDIX G ODCM SOFTWARE PACKAGE In order to minimize calculational errors and to facilitate the use of the ODCM, BSEP utilizes a Canberra developed software package called OpenEMS. All applicable calculations listed in the ODCM have been included in this software.

During periods when the OpenEMS software is not available, the following alternate method may be used to assess dose or dose rates to the public from liquid or gaseous effluents:

Dt = (Dh x Ct)/Ch where: Dt = the unknown dose/dose rate for the time period Dh = the known dose/dose rate from historical data Ct = the total curies released for the time period Ch = the total curies used to calculate the known dose/dose rate When the OpenEMS software becomes available again, all doses to the public will be reassessed using the software package.

ODCM (BSEP) G-1 Rev.37 I

LIST OF TABLES Table No. Title Paqe APPENDIX H H-1 x/Q Values at the Standard Distances for Releases from the Stabilization Facility .................................................................................... H-2 ODCM (BSEP) H-1 Rev. 35

TABLE H-1 x/Q Values at the Standard Distances for Releases from the Stabilization Facility Progress Energy - Brunswick Release Type: Annual Release Mode: Ground Level Variable: Relative Concentration Sec./Cubic Meter)

Calculated Points: Standard Model: Straight Line Gaussian Diffusion Period: 2006-2010 Number of Observations: 43738 Base Distance in Miles Sector 0.25 0.50 0.75 1.00 1.50 2.00 2.50 3.00 3.50 4.00 4.50 NNE 5.78E-05 1.69E-05 8.21 E-06 3.92E-06 1.48E-06 7.79E-07 4.86E-07 3.36E-07 2.48E-07 1.93E-07 1.55E-07 NE 1.10E-04 3.20E-05 1.56E-05 7.46E-06 2.80E-06 1.47E-06 9.12E-07 6.28E-07 4.64E-07 3.59E-07 2.88E-07 ENE 2.04E-04 5.97E-05 2.91 E-05 1.39E-05 5.26E-06 2.77E-06 1.73E-06 1.20E-06 8.86E-07 6.88E-07 5.54E-07 E 2.36E-04 6.88E-05 3.33E-05 1.60E-05 6.08E-06 3.23E-06 2.03E-06 1.41 E-06 1.05E-06 8.20E-07 6.63E-07 ESE 2.77E-04 8.04E-05 3.87E-05 1.86E-05 7.10E-06 3.78E-06 2.38E-06 1.66E-06 1.24E-06 9.70E-07 7.85E-07 SE 3.47E-04 1.01E-04 4.85E-05 2.32E-05 8.88E-06 4.73E-06 2.98E-06 2.08E-06 1.55E-06 1.21E-06 9.84E-07 SSE 6.69E-04 1.94E-04 9.29E-05 4.46E-05 1.71E-05 9.13E-06 5.77E-06 4.03E-06 3.01 E-06 2.36E-06 1.91 E-06 S 6.39E-04 1.85E-04 8.91 E-05 4.27E-05 1.64E-05 8.73E-06 5.51 E-06 3.85E-06 2.87E-06 2.25E-06 1.82E-06 SSW 2.38E-04 6.95E-05 3.38E-05 1.62E-05 6.14E-06 3.25E-06 2.04E-06 1.41E-06 1.05E-06 8.18E-07 6.60E-07 SW 8.73E-05 2.55E-05 1.24E-05 5.94E-06 2.24E-06 1.18E-06 7.34E-07 5.06E-07 3.74E-07 2.90E-07 2.33E-07 WSW 5.67E-05 1.65E-05 8.08E-06 3.85E-06 1.44E-06 7.54E-07 4.67E-07 3.21 E-07 2.36E-07 1.82E-07 1.46E-07 W 5.40E-05 1.58E-05 7.70E-06 3.67E-06 1.38E-06 7.22E-07 4.49E-07 3.09E-07 2.28E-07 1.77E-07 1.42E-07 WNW 4.83E-05 1.41 E-05 6.88E-06 3.28E-06 1.23E-06 6.47E-07 4.03E-07 2.78E-07 2.05E-07 1.59E-07 1.28E-07 NW 4.80E-05 1.40E-05 6.85E-06 3.27E-06 1.23E-06 6.45E-07 4.01 E-07 2.76E-07 2.04E-07 1.58E-07 1.27E-07 NNW 5.48E-05 1.60E-05 7.82E-06 3.73E-06 1.41 E-06 7.40E-07 4.61E-07 3.19E-07 2.36E-07 1.83E-07 1.47E-07 N 6.23E-05 1.82E-05 8.91 E-06 4.26E-06 1.61 E-06 8.47E-07 5.29E-07 3.65E-07 2.70E-07 2.10E-07 1.69E-07 ODCM (BSEP) H-2 Rev. 35

BSEP 14-0038, Radioactive Effluent Release Report for 2013

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BSEP 14-0038, Radioactive Effluent Release Report for 2013

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