Text

Annual Radioactive Effluent Release Report for 2013
	ML14120A321
Person / Time
Site:	Watts Bar
Issue date:	04/30/2014
From:	Church C; Tennessee Valley Authority
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML14120A321 (261)
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{{#Wiki_filter:Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 April 30 ,2014 10 CFR 50.36a(a)(2) 10 cFR 50.4 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No. 50-390

Subject:

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT .2013 Enclosed is the subject Annual Radioactive Effluent Release Report (ARERR) for the period of January 1,2013 to December 31, 2013. This report (Enclosure 1) is being submitted as required by the respective Watts Bar Nuclear Plant WBN), Unit 1, Technical Specification 5.9.3, which specifies that the report be submitted prior to May 1't of each year. is divided into four principal sections. The first section provides the required effluent release data. Attachment 1 to Enclosure 1 documents any deviations which have occurred from Offsite Dose Calculation Manual (ODCM) requirements. Attachment 2 addresses any radioactive effluent monitoring instrumentation which was inoperable for greater than 30 days. Attachment 3 of Enclosure 1 provides a copy of Revision 23 of the ODCM. This revision was in effect as of February 12,2010, and is provided in accordance with Technical Specification 5.7.2.3. addresses requirements of the Process Control Program (PCP) which are reported in conjunction with the ARERR in accordance with Section 2.4 of the PCP.

U.S. Nuclear Regulatory Commission Page 2 April 30, 2014 There are no regulatory commitments in this letter. lf you have any questions concerning this matter, please contact Gordon Arent, Licensing Director, at (423) 365-2004. Site Vice President Watts Bar Nuclear Plant

Enclosures:

1. Annual Radioactive Effluent Release Report, 2013

2. Process Control Program Reporting Requirements cc (Enclosures):

NRC RegionalAdministrator - Region ll NRC Senior Resident lnspector - Watts Bar Nuclear Plant Unit 1 NRC Project Manager - Watts Bar Nuclear Plant Unit 1 EDMS

U.S. Nuclear Regulatory Commission Page 3 April 30, 2014 GA:TPM Enclosures bcc (w/o Enclosures): R. J, Bankes T. J. Carter S. M. Douglas D. H. Gronek A. W. Hooks G. W. Mauldin E. D. Schrull J. W. Shea J. P. Grimes M:\ln-Pro@ss Letters to NRC\RERR 2013\2013 Annual Rad Effluent Report Rev. 0.doc

Enclosure 1 Watts Bar Nuclear Plant Unit 1 Annual Radioactive Effluent Release Report - 2013 E1-1

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT

1. Regulatory Limits A. Gaseous Effluents

1. Dose rates due to radioactivity released in gaseous effluents from the site to areas at and beyond the unrestricted area boundary shall be limited to the following:

a. Noble gases: - Less than or equal to 500 mrem/year to the total body.

                                - Less than or equal to 3000 mrem/year to the skin.

b. lodine-131, iodin+133, tritium, and all radionuclides in particulate form with half-lives greater than I days:

                                - Less than or equal to 1500 mrem/year to any organ.

2. Air dose due to noble gases released in gaseous effluents to areas at and beyond the unrestricted area boundary shall be limited to the following:

a. Less than or equalto 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation during any calendar quarter.

b. Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation during any calendar year.

3. Dose to a member of the public from iodine-l31 , iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than eight days in gaseous effluents released to areas at and beyond the unrestricted area boundary shall be limited to the following:

a. Less than or equalto 7.5 mrem to any organ during any calendar quarter.

b. Less than or equal to 15 mrem to any organ during any calendar year.

B. Liquid Effluents

1. The concentration of radioactivity released in liquid effluents to unrestricted areas shall be limited to 10 times the concentrations specified in Title 10 of the Code of Federal Regulations, Part20 (Standards for Protection against Radiation), Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0 E-04 pCi/mltotal activity.

2. The dose or dose commitment to a member of the public from radioactivity in liquid effluents released to unrestricted areas shallbe limited to:

a. Less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ during any calendar quarter.

b. Less than or equalto 3 mrem to the total body and less than or equalto 10 mrem to any organ during any calendar year.

E1-2

2013 WATTS BAR NUCLEAR PTANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT

2. Effluent Concentration Limits A. Liquids The Effluent Concentration Limits (ECL) for liquids are those listed in 10 CFR 20, Appendix B, Table 2, Column 2. For dissolved and entrained gases the ECL of 2.0E-O4 pCi/ml is applied.

This ECL is based on the Xe-135 concentration in air (submersion dose) converted to an equivalent concentration in water as discussed in the lnternational Commission on Radiological Protection (ICRP), Publication 2. B. Gaseous Concentration limits for gaseous releases are met through compliance with the maximum permissible dose rates for gaseous releases as defined in plant Offsite Dose Calculation Manual(ODCM) and presented in Section 1.A.1 of this report.

3. Average Energy Watts Bar Nuclear Plant's WBN) ODCM limits the dose equivalent rates due to the release of noble gases to less than or equal to 500 mrem/year to the total body and less than or equal to 3000 mrem/year to the skin. Therefore, the average beta and gamma energies (E) for gaseous effluents as described in Regulatory Guide 1.2'1, "Measuring, Evaluation, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," are not applicable.

Measurements and Approximations of Total Radioactivity Radioactivity measurements performed in support of the WBN ODCM meet the Lower Limit of Detection requirements given in ODCM Tables 2.2-1 and2.2-2. A. Liquid Effluents Batch (Radwaste and Condensate Demineralizer tanks) Totalgamma isotopic and tritium concentrations are determined on each Radwaste batch tank prior to release. The total activity of a batch release is obtained by determining the concentration of each nuclide and then multiplying by the volume discharged to arrive at the curie activity for each nuclide. The curies of each nuclide are then summed. Composite samples are maintained and analyzed monthly for gross alpha and quarterly for iron-S5, strontium-89, and strontium-9O. During periods of no significant identified primary to secondary leakage, composite samples are not maintained for batch releases from the Condensate Demineralizer Tank releases. During periods of no significant identified primary to secondary leakage or when the Condensate Demineralizer Tanks are discharged to the Turbine Building Station Sump, the feedwater tritium concentration is used to determine the curies of tritium released ftom Condensate Demineralizer Tank. E1-3

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Continuous Releases (Turbine Building Station Sump (TBSS), Steam Generator Blowdown (SGB), and Groundwater Sump (GWS)) During periods of no significant identified primary to secondary leakage, the volume released from the TBSS and SGB is obtained. The TBSS tritium concentration is determined via weekly grab samples. The feedwater tritium concentration is used to determine the curies of tritium released from SGB. The GWS is sampled monthly and analyzed for gross gamma and tritium on a monthly basis and for Sr-89 and Sr-90 on a quarterly basis. The total activity released is obtained by determining the concentration of each nuclide and then multiplying by the volume discharged to arrive at the curie activity for each nuclide. Monitoring Wells \tt/ElN started conducting an investigation of tritium releases to the groundwater in 2003 due to identification of tritium in three of the four newly installed on-site monitoring wells associated with the December2OO2 Department of Energy tritium production program site preparation activity. This study involved pressure testing of the radwaste discharge line, evaporation calculations of the Spent Fuel Pool (SFP) and Refueling Water Storage Tank (RWST), installation and sampling of groundwater wells, inspection of drain lines, boroscopic investigation of the SFP, and Fuel Transfer Canal leak collection system channels and drains. ln addition to the six (6) Radiologocial Environmental Montioring Program (REMP) on-site groundwater monitoring wells, \IVBN also has '19 non-REMP monitoring wells to support monitoring the onsite groundwater plume for the presence or increase of radioactivity. WBN contracted with ARCADIS in 20M to perform an investigation of the impact tritium had on groundwater and to perform a site characterization, area of impact, and preliminary human health and ecological risk screening. E1-4

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Monitoring Wells (Continued) The on-site monitoring wells are sampled semi-annually for gamma and tritium. These wells continue to exhibit a downward trend. The tritium concentrations obtained in 2013 from these monitoring wells are listed below. Wells K sample was also analyzed for Sr-89, Sr-90, F+.55, and Ni-63, with no detectable results. 05t23t2013 12t20t2013 Well lD Activity pCi/L Activity pCi/L A <20L <209 B TL72 L4L2 c 223 2L8 D 348 501 E 1418 25L F 801 248 G <20L N/A H 2L9 N/A I <20L 2L5 J <20L 1045 K L74L 2754 L L758 3308 M <20L N/A o 280 263 P 268 388 a <20L <209 R 1138 1002 V N/A <208 Doses from l-131 Water lngestion Pathway The radiologicalenvironmental monitoring program (REMP) specified in Table 3.12-1 from NUREG 1 301,'Ofbite Does Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors," April 1991, requires an l-131 specific analysis for drinking water pathway samples if the annual dose from l-131 is greater than 1 mrem. To evaluate the need for implementation of this additional analysis, the drinking water pathway dose from l-131 to the maximum organ and age group was evaluated. No l-13'1 was released. Therefore, the evaluation confirmes that the drinking water pathway dose from l-131 was less than the 1 mrem limit and that the performance of the l-131 specific analysis is not required for WBN REMP drinking water samples. Quarter 1 2 3 4 Totals l-13{ Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Child/Thvroid (mrem) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Popu lation/Thyroid (m rem ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 E1-5

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT B. Gaseous Effluents Fission and Activation Gases Airborne effluent gaseous activity is continuously monitored and recorded. Weekly grab samples from the Auxiliary Building and monthly grab samples from the Service Building are taken and analyzed to determine the quantity of noble gas activity released based on the total flows for the sample period. Also, noble gas samples are collected and evaluated following startup, shutdown, or rated thermal power change exceeding 15 percent within one hour. Sampling is only required if dose equivalent l-131 concentration in the primary coolant or if the noble gas activity monitor indicates that the containment activity has increased more than a factor of three. The concentration of noble gases released through the Shield Building exhaust due to purging containment is determined by using the purge monitor response in combination with containment air samples obtained prior to purge. The quantity of activity released during the purge is determined using the duration, flowrate, and concentration of noble gases for each purge. Also, noble gas samples are collected and evaluated for ongoing containment purges following startup, shutdown, or rated thermal power change exceeding 15 percent within one hour. Sampling is only required if DEI concentration in the primary coolant or if the noble gas activity monitor shows that the containment activity has increased more than a factor of three. The quantity of noble gases released through the Shield Building exhaust due to the batch release of waste gas decay tanks is determined by sampling each tank prior to release. The total activity released is determined from the total pressure change recorded for the tank during the release. lodines and Particulates in Gaseous Releases lodine and particulate activity are continuously sampled. Weekly charcoal and particulate samples are taken from the Shield Building exhaust and auxiliary building exhausts and from the Condenser Vacuum Exhaust during periods of primary to secondary leakage. These samples are analyzed at least weekly to determine the total activity released from the plant based on the total vent flows recorded for the sampling period. Also, when a primary to secondary leak exists, particulate and charcoalsamples are taken from the Shield Building Exhausts, Auxiliary Building Exhaust, and Condenser Vacuum Exhaust once per 24 hours for 7 days following startup, shutdown, or a rated thermal power change exceeding 15 percent within one hour if dose equivalent l-131 concentration in the primary coolant or the noble gas activity monitor shows that the containment activity has increased more than a factor of three. Carbon-l4 in Gaseous Releases The Carbon-14 production and effluent source term estimates were based on EPRI methodology provided in EPRI Report 1021106, "Estimation of Carbon-l4 in Nuclear Power Plant Gaseous Effluents," dated December 2OlO.ltwas determined that 10.6 curies of Carbon-14 is generated annually at WBN. However, only 98% is considered released as gas and only the carbon dioxide form (20%) of that is used in the gaseous dose calculations. E1-6

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT

5. Batch Releases Value 1st Half 2nd Half Units A. Liquid (Radwaste only)

1. Number of releases 38 67 Each

2. Total time period of releases 4,692 10,212 Minutes 240 455 Minutes

3. Maximum time period of release 124 152 Minutes

4. Average time period of releases 5 95 Minutes

5. Minimum time period for release 51,060 36,820 CFS

6. Average dilution stream flow during release periods B. Gaseous (Batches only - containment purges, and waste gas decay tanks)

1. Number of releases 10 13 Each 15,343 6,024 Minutes

2. Total time period of releases 13,266 4,049 Minutes

3. Maximum time period for release 1,534 463 Minutes

4. Average time period for releases 5 5 Minutes

5. Minimum time period for release

6. Abnormal Releases Value Units 1st Half 2nd Half A. Liquid Number of Releases 0 0 Total Activity Released 0.00E+00 0.00E+00 Ci B. Gaseous Number of Releases Total Activity Released 0 1*

0.00E+00 2.40E-04 ci

     *Steam Generator #3 PORV release E1-7

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT ABNORMAL RELEASES Release Type: Gaseous (Steam) Release Point: Unit 1 Steam Generator#3 PORV Date(s) of Release : 0O1 1 1 12013 through 12131 12013 This evaluation is for the release to the environment that occurred from the Unit 1 Steam Generator #3 PORV. The Steam Generator #3 PORV ICS computer point alarmed intermittenly 8 to 10 times with less than 1% open. A visual inspection revealed no steam. However, it was later determined that steam was wafting around the the PORV opening but did not appear to have much pressure behind it. Review of the PORV for Steam Generator #3 postion was trended for the release period listed above and the position remained below 1%. PER 739084 documents this event. The steam generator PORV valve is scheduled to be repaired in the upcoming refueling outage. The following is data used to determine the curies and dose impacts as a result of the release: o \Mrile steam generator #3 PORV was not open continuously during this period, the evaluation assumed the release was continuous during the release period.

           . During Cycle 12, there have been no gamma emitting radionuclides identified in any Secondary Coolant samples.

o The steam generator tritium results obtained on 06/09/2013 indicated a tritium concentration of 1.77E-06 pCi/ml. This tritium concentration is assumed to have been the initial concentration with no additionaltritium introduced into the generators during the release period. All of the tritium initially present in the generator was assumed to have been released through the PORV during the date range listed above. The volume of a steam generator was taken ftom Chemistry Manual Chapter 5.01. The listed norma! water level value ol4750 ft3 was used as a conservative vatue. This calculation assumes that the total volume of steam generator 3 was released and that all the tritium present in that initial volume was released over the 3rd and 4th quarter of 2013. The calculation for the total tritium activity released is as follows: 4750tf tgenerator

2.832E+04 ml/ft3
1 generator = 1.35E+08 ml 117E-OO pCi/ml
1.35E+08 ml = 2.40E+02 pCi of H3 or 2.40E-04 Ci of H3 The activity of 1.2OE-O4 curies was added to the 3rd and 4th quarter Quarter Table 4-C and 4-D, "Curies Released in Gaseous Ground Level Releases,'and the 3rd and 4th Quarter doses in Table 6-8, 'Doses from Airborne Effluents." The additon of the 1.20E-04 curies of tritium did not have any impact on changing the dose values for the 3rd and 4th quarter of 2013.

E1-8

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT TABLE 1-A Liquid Effluents - Summation of All Releases During the period Starting: 1-Jan-2013 Ending: 30-Jun-2013 Est. Tot Type Of Effluent Units Quarter 1 Quarter 2 Error A. Fission & Activation Products

1. Total Release (Not lncluding Tritium, ci 5.53E-03 8.64E-03 25%

Gases, Alpha)

2. Average Diluted Concentration During pCi/ml 2.29E-10 4.77E-10 Period o/o * *

3. Percent Of Applicable Limit B. Tritium

1. Total Release Ci 6.59E+01 1.20E+02 18o/o

2. Average Diluted Concentration During pCi/ml 2.72E-06 6.63E-06 Period o/o *

3. Percent Of Applicable Limit C. Dissolved And Entrained Gases

1. Total Release ci 1.00E-04 4.03E-06 39%

2. Average Diluted Concentration During pCi/ml 4.13E-12 2.23E-13 Period o/o

3. Percent Of Applicable Limit 2.07E-06 1.11E-07 D. Gross Alpha Radioactivity

1. Total Release Curies 0.000E+00** 0.000E+00 N/A**

E. Total Waste Volume Released Liters 2.81E+08 2.39E+08 2o/o (Pre-Dilution) F. Volume Of Dilution Water Used Liters 2.42E+10 1 .81E+10 12% G. Radwaste Volume Released Liters 5.95E+05 8.69E+05 12o/o Zeroes in this table indicate that no radioactivity was present at detectable levels.

Applicable limits are expressed in terms of dose. See Table 7A of this report.
- N/A - Errors in measurements are not reported for these values since none were identified during the reporting period.

E1-9

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT TABLE 1-B Liquid Effluents - Summation of All Releases During the period Starting: 1-Jul-201 3 Ending: 31-Dec-2013 Est. Tot Type Of Effluent Units Quarter 3 Quarter 4 Error olo A. Fission & Activation Products

1. Total Release (Not lncluding Ci 4.78E-03 4.18E-03 25o/o Tritium, Gases, Alpha)

2. Average Diluted Concentration pCi/ml 4.1 9E-10 1 .90E-10 During Period o/o *

3. Percent Of Applicable Limit B. Tritium

1. Total Release Ci 4.1 0E+01 4.10E+02 18o/o

2. Average Diluted Concentration pCi/ml 3.60E-06 1.86E-05 During Period o/o * *

3. Percent Of Applicable Limit C. Dissolved And Entrained Gases

1. Total Release ci 0.00E+00 0.00E+00 N/A**

2. Average Diluted Concentration pCi/ml 0.00E+00 0.00E+00 During Period o/o

3. Percent Of Applicable Limit 0.00E+00 0.00E+00 D. Gross Alpha Radioactivity

1. Total Release ci 0.00E+00** 0.00E+00 N/A**

E. Total Waste Volume Released Liters 1.47E+08 1.69E+08 2o/o (Pre-Dilution) F. Volume Of Dilution Water Used Liters 1 .1 4E+1 0 2.20E+10 12o/o G. Radwaste Volume Released Liters 1.22E+06 4.06E+06 12o/o Zeroes in this table indicate that no radioactivity was present at detectable levels.

Applicable limits are expressed in terms of dose. See Table 7A of this report.
- N/A - Errors in measurements are not reported for these values since none were identified during the reporting period.

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2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT TABLE2-A Curies Released in Liquid Effluents During the period Starting: 1-Jan-2013 Ending: 31 -Mar-2013 CONTINUOUS BATCH TOTAL H-3 2.63E-01 6.56E+01 6.59E+01 FISSION & ACTIVATION PRODUCTS co-57 0.00E+00 1.48E-06 1.48E-06 co-58 0.00E+00 1 .1 3E-03 1 .1 3E-03 c0-60 0.00E+00 2.47E-04 2.47E-04 FE-55 0.00E+00 3.98E-03 3.98E-03 sB-125 0.00E+00 1.62E-04 4.97E-06 TOTALS 0.00E+00 5.53E-03 5.53E-03 DISSOLVED AND ENTRAINED GASES xE-1 33 0.00E+00 1.00E-04 1.00E-04 TOTALS 0.00E+00 0.00E+00 0.00E+00

Zeroes in this table indicate that no radioactivity was present at detectable levels.

E1-11

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT TABLE2-B Curies Released in Liquid Effiuents During the period Starting: 1-Apr-2013 Ending: 30-Jun-2013 CONTINUOUS BATCH TOTAL H-3 3.22E-01 1.20E+02 1.20E+02 FISSION & ACTIVATION PRODUCTS co-57 0.00E+00 7.44E-06 7.44E-06 co-58 0.00E+00 7.38E-04 7.38E-04 co-60 0.00E+00 1.32E-03 1.32E-03 cs-1 37 0.00E+00 1.87E-05 1.87E-05 FE-55 0.00E+OO 6.12E-03 6.12E-03 MN-54 0.00E+00 5.62E-05 5.62E-05 NB-95 0.00E+00 1.76E-06 1.76E-06 sB-125 0.00E+00 3.45E-04 3.45E-04 SR-89 0.00E+00 2.83E-05 2.83E-05 TOTALS 0.00E+OO 8.64E-03 8.64E-03 DISSOLVED AND ENTRAINED GASES xE-1 33 0.00E+00 4.03E-06 4.03E-06 TOTALS 0.00E+00 4.03E-06 4.03E-06

Zeroes in this table indicate that no radioactivity was present at detectable levels.

E1-12

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT TABLE2-C Curies Released in Liquid Effluents During the period Starting: 1-Jul-201 3 Ending: 30-Sep-201 3 CONTINUOUS BATCH TOTAL H-3 2.s6E-01 4.07E+41 4.1 3E+01 FISSION & ACTIVATION PRODUCTS co-58 0.00E+OO 3.72E-05 3.72E-05 c0-60 0.00E+00 2.95E-04 2.95E-04 CR-s1 0.00E+00 6.92E-06 6.92E-06 cs-1 37 0.00E+00 2.74E-06 2.74E-06 FE-55 0.00E+00 4.1 8E-03 4.1 8E-03 MN-54 0.00E+00 1.29E-05 1.29E-05 sB-125 0.00E+00 1.69E-04 1.69E-04 SR-89 0.00E+00 8.07E-05 8.07E-05 TOTALS 0.00E+00 4.78E-03 4.78E-03 DISSOLVED AND ENTRAINED GASES TOTALS 0.00E+00 0.00E+00 0.00E+00

Zeroes in this table indicate that no radioactivity was present at detectable levels.

E1-13

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT TABLE2-D Curies Released in Liquid Effluents During the period Starting: 1-Oct-2013 Ending: 31-Dec-2013 CONT!NUOUS BATCH TOTAL H-3 2.66E-01 4.10E+02 4.10E+02 FISSION & ACTIVATION PRODUCTS AG-1 1OM 0.00E+00 8.66E-06 8.66E-06 co-s8 0.00E+00 1.27E-05 1.27E-05 co0 0.00E+00 6.81E-04 6.81E-04 cs-137 0.00E+00 1.83E-06 1.83E-06 FE-55 0.00E+00 2.98E-03 2.98E-03 r-1 33 0.00E+00 1.98E-06 1.98E-06 MN-54 0.00E+00 2.12E-05 2.12E-05 RU-103 0.00E+00 1.58E-06 1.58E-06 sB-125 0.00E+00 4.37E-04 4.37E-04 SR-89 0.00E+00 3.28E-05 3.28E-05 TOTALS 0.00E+00 4.1 8E-03 4.18E-03 DISSOLVED AND ENTRAINED GASES TOTALS 0.00E+00 0.00E+00 0.00E+00

Zeroes in this table indicate that no radioactivity was present at detectable levels.

E1-14

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT TABLE 3-A Gaseous Effiuents - Summation of All Releases During the period Starting: 1-Jan-2013 Ending: 30-Jun-201 3 Est. Tot Type Of Effluent Units Quarter I Quarter 2 Error olo A. Fission & Activation Products

1. Total Release ci 3.03E-04 1.63E+00 22

2. Average Release Rate For Period pCi/sec 4.67E-05 2.07E-01

3. Percent Of Applicable Limit o/o

B. Radioiodines 1 . Total lodine-131 ci 0.000E+00 0.000E+00 N/A**

2. Average Release Rate For Period pCi/sec 0.000E+00 0.000E+00 o/o * *

3. Percent Of Applicable Limit C. Particulates 1 . Particulates (Half-Live*8 Days) ci 0.000E+00 5.22E-06 15

2. Average Release Rate For Period pCi/sec 0.000E+00 6.63E-13 0.000E+00 o/o *

3. Percent Of Applicable Limit

4. Gross Alpha Radioactivity ci 0.000E+00 0.000E+00 N/A**

D. Tritium

1. Total Release ci 7.1 0E+00 7.10E+00 11

2. Average Release Rate For Period pCi/sec 9.13E-01 9.02E-01 o/o

3. Percent Of Applicable Limit E. Carbon-l4

1. Total Release Ci 2.69E+00 2.65E+00 N/A

2. Average Release Rate For Period pCi/sec 3.46E-01 3.37E-01

3. Percent Of Applicable Limit o/o *

Zeroes in this table indicate that no radioactivity was present at detectable levels.
Applicable limits are expressed in terms of dose. See Table 6A of this report.
- N/A - Errors in measurements are not reported for these values since none were identified during the reporting period.

E1-15

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT TABLE 3-B Gaseous Effluents - Summation of AII Releases During the period Starting: 1-Jul-201 3 Ending: 31-Dec-2013 Est. Tot Type Of Effluent Units Quarter 3 Quarter 4 Error olo A. Fission & Activation Products

1. Total Release Ci 1.28E-01 2.01 E+00 22

2. Average Release Rate For Period pCi/sec 1.61E-02 2.53E-01 o/o * *

3. Percent Of Applicable Limit B. Radioiodines 1 . Total lodine-131 ci 0.000E+00 3.99E-08 12

2. Average Release Rate For Period pCi/sec 0.000E+00 5.02E-09 o/o *

3. Percent Of Applicable Limit C. Particulates 1 . Particulates (Half-Lives>8 Days) ci 1.26E-07 0.000E+00 15

2. Average Release Rate For Period pCi/sec 1.59E-02 0.000E+00 o/o

3. Percent Of Applicable Limit ci **N/A

4. Gross Alpha Radioactivity 0.000E+00 0.000E+00 D. Tritium

1. Total Release Ci 1.64E+01 4.38E+00 11

2. Average Release Rate For Period pCi/sec 2.07E+00 5.51E-01 o/o * *

3. Percent Of Applicable Limit E. Garbon-l4

1. Total Release ci 2.74E+00 2.74E+00 N/A

2. Average Release Rate For Period pCi/sec 3.45E-01 3.55E-01 o/o *

3. Percent Of Applicable Limit Zeroes in this table indicate that no radioactivity was present at detectable levels.

Applicable limits are expressed in terms of dose. See Table 6A of this report.
- N/A - Errors in measurements are not reported for these values since none were identified during the reporting period.

E1-16

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT TABLE 4-A Curies released in Gaseous Ground Level Releases During the period Starting: 1-Jan-2013 Ending: 31 -Mar-2013 CONTINUOUS BATCH TOTAL FISSION GASES KR-85 0.00E+00 2.12E-06 2.12E-06 xE-133 0.00E+00 8.98E-05 8.98E-05 AR41 0.00E+00 2.71E-04 2.71E-04 TOTALS 0.00E+00 3.63E-04 3.63E-04 IODINES 0.00E+00 0.00E+00 0.00E+00 PARTIGULTATES 0.00E+00 0.00E+00 0.00E+00 H-3 7.10E+00 0.00E+00 7.1 0E+00 C-l4 (Total) 2.69E+00 0.00E+00 2.69E+00 C-l 4 (COZ Form) 5.38E-01 0.00E+00 5.38E-01

Zeroes in this table indicate that no radioactivity was present at detectable levels.

E1-17

2013 WATTS BAR NUGLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT rABLE 4-B Curies released in Gaseous Ground Level Releases During the period Starting: 1 -Apr-2013 Ending: 30-Jun-201 3 CONTINUOUS BATCH TOTAL FISSION GASES KR-85 0.00E+00 3.31E-07 3.31 E-07 xE-133 0.00E+00 3.70E-02 3.70E-02 AR41 0.00E+00 1.59E+00 1.59E+00 TOTALS 0.00E+00 1.63E+00 1.63E+00 IODINES 0.00E+00 0.00E+00 0.00E+00 PARTICULATES BR-82 1.04E-06 0.00E+00 1.04E-06 co-60 4.19E-06 0.00E+00 4.1 9E-06 TOTALS 5.22E-06 0.00E+00 5.22E-06 H-3 7.1 0E+00 0.00E+00 7.10E+00 C-14 (Total) 2.65E+00 0.00E+00 2.65E+00 C-14 (CO2 Form) 5.31E-01 0.00E+00 5.31E-01

Zeroes in this table indicate that no radioactivity was present at detectable levels.

E1-18

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT I'ABLE 4-C Curies released in Gaseous Ground Level Releases During the period Starting: 1-Jul-2013 Ending: 30-Sep-201 3 CONTINUOUS BATCH TOTALS FISSION GASES KR-85 0.00E+00 4.63E-07 4.63E-07 xE-135 0.00E+00 9.68E-07 9.68E-07 xE-133 0.00E+OO 3.69E-03 3.69E-03 AR-41 0.00E+00 1.24E-01 1.24E-01 TOTALS 0.00E+00 1.28E-01 1.28E-01 IOD!NES 0.00E+00 0.00E+00 0.00E+00 PARTICULATES BR-82 1.26E-07 0.00E+00 1.26E-07 TOTALS 1.26E-07 0.00E+00 1.26E-07 H-3 1.64E+01 0.00E+00 1.64E+01 C-14 (Total) 2.74E+00 0.00E+00 2.74E+00 C-14 (CO2 Form) 5.48E-01 0.00E+00 5.48E-01

Zeroes in this table indicate that no radioactivity was present at detectable levels.

E1-19

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT TABLE 4-D Curies released in Gaseous Ground Level Releases During the period Starting: 1-Oct-2013 Ending: 31 -Dec-2013 CONTINUOUS BATCH TOTALS FISSION GASES KR-85 0.00E+00 3.31E-07 3.31 E-07 xE-133 0.00E+00 8.63E-02 8.63E-02 AR41 0.00E+00 1.93E+00 1.93E+00 TOTALS 0.00E+00 2.01 E+00 2.01E+00 IODINES t-1 31 3.99E-08 0.00E+00 3.99E-08 PARTICULATES 0.00E+00 0.00E+00 0.00E+00 H-3 4.38E+00 0.00E+00 4.38E+00 C-14 (Total) 2.74E+00 0.00E+00 2.74E+00 C-14 (CO2 Form) 5.48E-01 0.00E+00 5.48E-01

Zeroes in this table indicate that no radioactivity was present at detectable levels.

E1-20

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT TABLE 5-A solrD WASTE (RADTOACTTVE SHTPMENTS) A. Solid Waste Shipped Offisite for Burial or Disposal (not lrradiated Fuel) 12 Month Est. (Ci)

1. Tvpe of Waste Unit Period Error o/o

a. Spent resins, filters, sludges, evaporator m3 26.3 N/A bottoms, etc. Ci 250.0 +l-25o/o

b. Dry Active Waste, Compressible Waste m' 458.0 N/A Contaminated Equipment, etc. Ci 0.248 +l-25o/o

c. lrradiated Components, Control mt o.o N/A Rods, etc. ci 0.0 N/A

2. Estimate of Maior Nuclide Gomposition (bv tvpe of wastel (Percent Cutoff = 1.0 percent)

Percent ci

a. Spent resins, filter sludges, evaporator bottoffis, etc.

(nuclides determined by measurement) H-3 4.146 1.04E+01 Mn-54 3.568 8.92E+00 Fe-55 23.02 5.76E+01 Co-58 21 .13 5.28E+01 Co-60 19.44 4.86E+01 Ni-63 25.96 6.49E+01 sb-125 1.244 3.1 1 E+00

b. Dry active waste, compressible waste, contaminated equipment, etc. (nuclides determined by estimate)

Percent Mn-54 2.56 9.68E-03 Fe-55 45.76 1.73E-01 Co-58 1.42 5.37E-03 Co-60 28.11 1.06E-01 Ni-63 15.10 5.71E-02 Nb-95 1.69 6.39E-03 sb-125 1.41 5.33E-03

c. lrradiated Components None N/A N/A E1-21

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT TABLE 5-B solrD WASTE (RADIOACTIVE SHIPMENTS) Solid Waste Disposition Number of Shipments Mode of Transportation Destination 12 Motor Freight Energy Solutuins Facility - Clive, UT 5 Motor Freight Waste Control Specialist, Andrews, TX 19 Motor Freight TOXCO, Oak Ridge, TN, To Clive, UT or Chenstnut Ridge lrradiated Fuel Shipments (Disposition) Number of Shipments Tvpe Quantity Mode of Transportation Destination None N/A N/A N/A Sol id ification of Waste Was solidification performed? No If yes, solidification media: E1-22

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Radiological lmpact lntroduction Potential doses to maximum individuals and the population around WBN are calculated for each quarter as required in Section 5.2 of the Offsite Dose Calculation Manual (ODCM). Measured plant releases for the reporting period are used to estimate these doses. Dispersion of radioactive effluents in the environment is estimated using meteorological data and riverflow data measured during the period. ln this report, the doses resulting from releases are described and compared to limits established for WEIN. Dose Limits The ODCM specifies limits for the release of radioactive effluents, as well as limits for doses to the general public, from the release of radioactive effluents. These limits are set well below the Technical Specification limits which govern the concentrations of radioactivity and doses permissible in unrestricted areas. This ensures that radioactive effluent releases are As Low As Reasonably Achievable. Dose Calculations Estimated doses to the public are determined using computer models (the Gaseous Effluent Licensing Code, GELC, and the Quarterly Water Dose Assessment Code (QWATA)). These models are based on guidance provided by the NRC (in Regulatory Guides 1.109, 1.111 and 1.113) for determining the potential dose to individuals and populations living in the vicinity of the plant. The area around the plant is analyzed to determine the pathways through which the public may receive a dose. The doses calculated are a representation of the dose to a "maximum exposed individual." Some of the factors used in these calculations (such as ingestion rates) are maximum values. Many of these factors are obtained from NUREG/CR-1004. The values chosen willtend to overestimate the dose to this "maximum" person. The expected dose to actual individuals is lower. The calculated doses are presented in Tables 6A, 68, 7A, and 78, Doses From Airborne Effluents For airbome effluents, the public can be exposed to radiation from several sources: direct radiation from the radioactivity in the air, direct radiation from radioactivity deposited on the ground, inhalation of airborne radioactivity, ingestion of vegetation which contains radioactivity deposited from the atmosphere, and ingestion of milk and beef which contains radioactivity deposited ftom the atmosphere onto vegetation and subsequently eaten by milk and beef animals. Aibome Discharoe Points All releases from WBN are considered ground-level releases. The ground-level Joint Frequency Distribution (JFD) is derived from wind speeds and directions measured 10 meters above ground and from the verticaltemperature difference between 10 and 46 meters, as presented for each quarter on pages E1-33 through E1-59. E1-23

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Radiological lmpact Meteorcloaical Data Meteorologicalvariables at \trBN are measured continuously. Measurements collected include wind speed, wind direction, and temperature at heights of 10, 46, and 91 meters above the ground. Quarterly JFDs are calculated for each release point using the appropriate levels of meteorological data. A JFD provides the percentage of the time in a quarter that the wind is blowing out of a particular upwind compass sector in a particular range of wind speeds for a given stability class A through G. The wind speeds are divided into nine wind speed ranges. Calms are distributed by direction in proportion to the distribution of non-calm wind directions less than 0.7 m/s ('1.5 mph). Stability classes are determined from the vertical temperature difference between two measurement levels. Extemal Exoosurc Dose Dose estimates for maximum external air dose (gamma-air and beta-air doses) are made for points at and beyond the unrestricted area boundary as described in the WBN ODCM. The highest of these doses is then selected. Submersion Dose External doses to the skin and total body, due to submersion in a cloud of noble gases, are estimated for the nearest residence in each sector. The residence with the highest dose is then selected from all sectors. Oruan Dose Doses to organs due to releases of airborne effluents are estimated for the inhalation, ground contamination, and ingestion pathways. The ingestion pathway is further divided into four possible contributing pathways: ingestion of cow milk, ingestion of beel and ingestion of vegetables. Doses from applicable pathways are calculated for each real receptor location identified in the most recent land use survey. To determine the maximum organ dose, the doses from the pathways are summed for each receptor. For the ingestion dose, however, only those pathways that exist for each receptor are considered in the sum, i.e., milk ingestion doses are included only for locations where milk is consumed without commercial preparation and vegetable ingestion is included only for those locations where a garden is identified. Since specific data on beef animals were not available, the location of the highest beef dose for all receptors within an age group will be considered the beef dose for each receptor within that age group. For ground contiamination, the dose added to the organ dose being calculated is the total body dose calculated for that location, i.e., it is assumed that the dose to an individual organ is equal to the total body dose. Doses from airborne effluents are presented in Tables 6A and 68. E1-24

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Radiological Impact Land Use Suruey 2013 Land n Use S urv Receptor Receptor Distance GPS Coordinates Tendn Adj. Number Tvpe* Sector (m) N W Factor 1 NR N 4590 35.64356 84.79812 1.5 2 NR NNE 3750 35.63226 84.77014 1.8 3 NR NE 3399 35.62474 84.76412 2.3 4 NR ENE 3072 35.61506 84.75984 1.9 5 NR E 4388 35.60587 84.75439 1.6 6 NR ESE 4654 3s.58139 84.74604 1.8 7 NR SE 1409 35.59439 84.77861 1.5 8 NR SSE 1646 3s.58963 84.78191 1.5 I NR S 1 550 35.58879 84.79047 1.8 10 NR SSW 1832 35.58690 84.79567 1.9 11 NR SW 4141 35.581 18 84.82758 2.0 12 NR WSW 2422 35.59270 84.81403 1.7 13 NR W 2901 35.60557 84.82218 1.1 14 NR WNW 1448 35.60967 84.80387 2.5 15 NR NW 2065 35.61308 84.80929 1.5 16 NR NNW 4376 35.63792 84.81208 1.0 17 NG N 6658 35.65260 84.79348 1.0 18 NG NNE s030 35.64057 84.75969 1.6 19 NG NE 3793 35.62840 84.76258 2.2 20 NG ENE 3072 35.62769 84.74628 1.9 21 NG E 4656 35.60406 84.73881 1,6 22 NG ESE 4931 35.58282 84.74L58 1.8 23 NG SE 1409 35.59439 84.77861 1.5 24 NG SSE 1711 35.58799 84.78504 1.5 25 NG S 2349 35.57100 84.79{ { 0 2.O 26 NG SSW 5584 N/A N/A 1.8 27 NG SW 81 00 N/A N/A 1.7 28 NG WSW 3080 35.59324 84.82214 1.7 29 NG W 31 38 35.60768 84.82446 1.1 30 NG WNW 2963 35.61725 84.81780 2.2 31 NG NW 2065 35.61308 84.80929 1.5 32 NG NNW 4607 35.64017 84.8L224 1.0 33 MC ESE 6706 35.57698 84.72101 1.7 34 MC SSW 2826 35.58312 84.49693 2.0

NR: Nearest Residence, NG: Nearest Garden, MC: Milk Cow New locations and/or Terrain Adjustment Factors are represented by being bolded.

E1-25

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Radiological lmpact Doses From Liouid Effluents For liquid effluents, the public can be exposed to radiation from three sources: the ingestion of water from the Tennessee River, the ingestion of fish caught in the Tennessee River, and direct exposure from radioactive material deposited on the river shoreline sediment (recreation). The concentrations of radioactivity in the Tennessee River are estimated by a computer modelwhich uses measured hydraulic data downstream of WBN. Parameters used to determine the doses are based on guidance given by the NRC (in Regulatory Guide 1.109) for maximum ingestion rates, exposure times, etc. Wherever possible, parameters used in the dose calculation are site specific use factors determined by TVA. The models that are used to estimate doses, as wellas the parameters input to the models, are described in detail in the WBN ODCM. Liquid Release Points and River Data Radioactivity concentrations in the Tennessee River are calculated assuming that releases in liquid effluents are continuous. All routine liquid releases from \NEIN, located at Tennessee River Mile 528.5, are made through diffusers which extend into the Tennessee River. lt is assumed that releases to the river through these diffusers will initially be entrained in one-tenth of the water which flows past the plant. The QWATA code makes the assumption that this mixing condition holds true until the water is completely mixed at Tennessee River Mile 510.0. Doses are calculated for locations within a 50 mile radius downstream of the plant site. The maximum potential recreation dose is calculated for a location immediately downstream from the plant outfall. The maximum individual dose from ingestion of fish is assumed to be that calculated for the consumption of fish caught anyu'rhere between the plant and the first downstream dam (Chickamauga Dam). The maximum individual dose from drinking water is assumed to be that calculated at the nearest downstream public water supply (Dayton, TN). This could be interpreted as indicating that the maximum individual, as assumed for liquid releases from WEIN, is an individualwho obtains all of his drinking water at Dayton, TN, consumes fish caught ftom the Tennessee River between V/BN and Chickamauga Dam, and spends 500 hours per year on the shoreline just below the outfall from WBN. Dose estimates for the maximum individual due to liquid effluents for each quarter in the period are presented in Tables 7A and 78, along with the average river flows past the plant site for the periods. Pooulation Doses Population doses for highest exposed organ due to airborne effluents are calculated for an estimated 1,066,600 persons living within a S0-mile radius of the plant site. Doses from external pathways and inhalation are based on the S0-mile human population distribution. lngestion population doses are calculated assuming that each individual consumes milk, vegetables, and meat produced within the sector annulus in which he resides. Doses from externa! pathways and inhalation are based on the S0-mile human population distribution. Population doses for tota! body and the maximum exposed organ due to liquid effluents are calculated for the entire downstream Tennessee River Population. Water ingestion population doses are calculated using actual population figures for downstream public water supplies. Fish ingestion population doses are calculated assuming that all sport fish caught in the Tennessee River are consumed by the Tennessee River population. Recreation population doses are calculated using actual recreationaldata on the number of shoreline visits at downstream locations. Population dose estimates for airbome and liquid effluents are presented in Tables 6A, 68, 7A and 78. E1-26

2413 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Radiological lmpact Direct Radiation External gamma radiation levels were measured by Landauer lnLight environmental dosimeters deployed around WBN as part of the oftsite Environmental Radiological Monitoring Program. The quarterly gamma radiation levels determined from these dosimeters during this reporting period averaged 15.75 mR/quarter at onsite (at or near the site boundary) stations and 14.50 mR/quarter at offsite stations or 1.25 mR/quarter higher onsite than at ofbite stations. This difference is consistent with levels measured for preoperation and construction phases of the WBN plant site where the average radiation levels onsite were generally 2-8 mR/quarter higher than the levels ofbite. This may be attributable to natural variations in environmental radiation levels, earth moving activities onsite, the mass of concrete employed in the construction of the plants, or other undetermined influences. Fluctuations in natural background dose rates and in dosimeters readings tend to mask any small increments which may be due to plant operations. Thus, there was no identifiable increase in dose rate levels attributable to direct radiation from plant equipment and/or gaseous effluents. Dose To A Member Of The Public lnside The Unrestricted Area Boundarv As stated in the WBN ODCM, an evaluation of the dose to a member of the public inside the unrestricted area boundary is performed for a hypothetical TVA employee who works just outside the restricted area boundary for an entire work year (2000 hours). Results from onsite quarterly dosimeter measurements indicated that the highest annual dosimeter reading outside Radiological Control Areas was 130 mrem. Using this value, subtracting an annual background value of approximately 63.0 mrem/year (see previous section), and multiplying by the ratio of the occupancy times (2000/8760), the highest external dose to a member of the public inside the unrestricted area boundary would be 15.30 mrem. The doses due to radioactive effluents released to the atmosphere calculated in this report would not add a significant amount to this measured dose. This dose is below the 10 CFR 20 annual limit of 100 mrem. Total Dose To determine compliance with 40 CFR 190, annualtotal dose contributions to the maximum individualfrom

  \A/BN radioactive effluents and all other nearby uranium fuel cycle sources are considered.

The annual dose to any organ other than thyroid for the maximum individual is conservatively estimated by summing the following doses: the total body air submersion dose for each quarter, the critical organ dose any organ other than the thyroid) from airborne effluents for each quarter from ground contamination, -(for inhalation and ingestion, the total body dose from liquid effluents for each quarter, the maximum organ dose (for any organ other than the thyroid) from liquid effluents for each quarter, and any identifiable increase in direct radiation dose levels as measured by the environmental monitoring program. This dose is compared to the 40 CFR 190 limit for total body or any organ dose (other than thyroid) to determine compliance. The annualthyroid dose to the maximum individual is conservatively estimated by summing the following doses: the total body air submersion dose for each quarter, the thyroid dose from airborne effluents for each quarter, the total body dose from liquid effluents for each quarter, the thyroid dose from liquid effluents for each quarter, and any identifiable increase in direct radiation dose levels as measured by the environmental monitoring program. This dose is compared to the 40 CFR 190 limit for thyroid dose to determine compliance. Cumulative annualtotaldoses are presented in Table 8. E1-27

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT TABLE 6-A Doses from Airborne Effluents First Quarter lndividual Doses Pathway Dose Quarterly Percent of Location Limit Limit External Gamma Air 6.97E-07 mrad 5 mrad ESE/1 250 meters Beta Air 2.75E-A7 mrad 10 mrad < 1o/o ESE/1 250 meters Submersion Total Bodv 2.37E-07 mrem N/A N/A SE/1409 meters Skin 3.52E-07 mrem N/A N/A SE/1409 meters Organ Doses' (Max) Child/Bone 4.29E-01 mrem 7.5 mrem 5.72o/o SE/1409 meters Child/Thyroid 9.05E-02 mrem 7.5 mrem 1.21% SE/1409 meters Child/Total Bodv 9.05E-02 mrem 7.5 mrem 1.21o/o SE/1409 meters Population Doses Total Body Dose 1.29E-01 man-rem Maximum Organ Dose (organ) 5.83E-01 man-rem (bone) Second Quarter lndividual Doses Pathway Dose Quarterly Percent of Location Limit Limit External Gamma Air 5.61E-03 mrad 5 mrad ESE/1 250 meters Beta Air 1.99E-03 mrad 10 mrad ESE/1 250 meters Submersion Total Body 2.OTE-03 mrem N/A N/A SE/1409 meters Skin 3.03E-03 mrem N/A N/A SE/1409 meters Orqan Dosest (Max) Child/Bone 6.55E-01 mrem 7.5 mrem 8.73% SE/1409 meters Child/Thyroid 1.40E-01 mrem 7.5 mrem 1.87o/o SE/1409 meters Child/Total Bodv 1.40E-01 mrem 7.5 mrem 1.87o/o SE/1409 meters Population Doses Total Body Dose 1.91E-01 man-rem Maximum Organ Dose (organ) 8.59E-01 man-rem (bone) Population doses can be compared to the natural background dose for the entire SGmile population of about 150,000 man-rcm/year (based on 140 mrcm/yrfor natural background). rOrgan Doses include contributions from Carbon {4 as carbon dioxide E1-28

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT TABLE 6-8 Doses from Airborne Effluents Third Quarter lndividual Doses Pathway Dose Quarterly Percent of Location Limit Limit External Gamma Air 4.82E-04 mrad 5 mrad ESEl1250 meters Beta Air 1.72E-04 mrad 10 mrad ESE/1 250 meters Submersion Total Body 2.46E-04 mrem N/A N/A SE/1409 meters Skin 3.62E-04 mrem N/A N/A SE/1409 meters Organ Doses' (Max) Child/Bone 9.79E-01 mrem 7.5 mrem 13.05% SE/1409 meters Child/Thyroid 2.22E-01 mrem 7.5 mrem 2.960/o SE/1409 meters Child/Total Body 2.22E-01 mrem 7.5 mrem 2.960/o SE/1409 meters Population Doses Total Body Dose 1.92E-01 man-rem Maximum Organ Dose (organ) 7 .7 5E-01 man-rem (bone) Fourth Quarter lndividual Doses Pathway Dose Quarterly Percent of Location Limit Limit External Gamma Air 1.01E-02 mrad 5 mrad ESE/1 250 meters Beta Air 3.61E-03 mrad 10 mrad ESE/1 250 meters Submersion Total Body 4.61 E-03 mrem N/A N/A SE/1409 meters Skin 6.80E-03 mrem N/A N/A SE/1409 meters Organ Dosest Child/Bone 1.17E+00 mrem 7.5 mrem 15.60/o SE/1409 meters Child/Thyroid 2.46E-01 mrem 7.5 mrem 3.28o/o SE/1409 meters Child/Total Body 2.46E-01 mrem 7.5 mrem 3.28o/o SE/1409 meters Population Doses Total Body Dose 1.64E-01 man-rem Maximum Organ Dose (organ) 7.64E-01 man-rem (bone) Population doses can be comparcd to the natunl backgrcund dose for the entirc SGmile population of about 150,000 man-rcm/year (based on 140 mrem/yrfor naturalbackgrcund). {Organ Doses include contributions from Carbon 14 as carbon dioxide E1-29

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT TABLET-A Doses from Liquid Effluents First Quarter lndividual Doses (mrem) Age Group Organ Dose Quarterly Limit Percent of Limit chitd Total Body 1.50E-04 1.5 mrem chitd Bone 1.60E-04 5 mrem chitd Thyroid 1.50E-04 5 mrem Average Riverflow past WBN (cubic feet per second): 61,320 Population Doses Total Body Dose 9.30E-03 man-rem Maximum Organ Dose (organ) 9.30E-03 man-rem (bone) Second Quarter lndividual Doses (mreml Age Group Organ Dose Quarterly Limit Percent of Limit chitd Total Bodv 5.00E-04 1.5 mrem child Bone s.30E-4 5 mrem chitd Thyroid 4.90E-04 5 mrem Average Riverflow past WBN (cubic feet per second): 40,795 Population Doses Total Body Dose 2.60E-02 man-rem Maximum Organ Dose (organ) 2.60E -02 man-rem (Bone) Population doses can be comparcd to the natunl backgrcund dose for the entirc 1O-mile population of about 150,000 man-rcm/year (based on 140 mrcm/yrfor naturalbackgrcund). E1-30

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT TABLET-B Doses from Liquid Effluents Third Quarter lndividual Doses (mreml Aqe Group Organ Dose Quarterly Limit Percent of Limit chird Total Body 1.70E-04 1.5 mrem chitd Bone 2.00E-04 5 mrem chitd Thyroid 1.70E-04 5 mrem Average Riverflow past WBN (cubic feet per second): 37,125 Population Doses Total Body Dose 9.40E-03 man-rem Maximum Organ Dose (organ) 9.50E-03 man-rem (bone) Fourth Quarter Individual Doses (mrem) Age Group Organ Dose Quarterly Limit Percent of Limit child Total Body 1.50E-03 1.5 mrem chitd Bone 1.50E-03 5 mrem chird Thyroid 1.50E-03 5 mrem Average Riverflow past WBN (cubic feet per second): 36,51 1 Population Doses Total Body Dose 9.60E-02 man-rem Maximum Organ Dose (organ) 9.60E -02 man-rem (bone) Population doses can be compared to the natunl backgrcund dose for the entirc SGmile population of about 150,000 man-rcm/year (based on 140 mrem/yrfor natural backgrcund). E1-31

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT TABLE 8 Total Dose from Fuel Cycle First Second Third Fourth Dose Quarter Quarter Quarter Quarter Tota! Body or any Organ (except thyroid) Tota! body air 2.37E-07 2.07E-03 2.46E-04 4.61E-03 (submersion) Critical organ dose 4.29E-01 6.55E-01 9.79E-01 1.17E+00 (airborne) Total body dose 1.50E-04 5.00E-04 1.70E-04 1.50E-03 (liquid) Maximum organ 1.60E-04 5.30E-04 2.00E-04 1.50E-03 dose (liquid) Direct Radiation 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Dose Total 4.29E-01 6.58E-01 9.80E-01 1.18E+00 Gumulative Total Dose (mrem) 3.25E+00 Annual Dose Limit (mrem) 26 Percent of Limit 13.00% Thyroid Total body air 2.37E-07 2.07E-03 2.46E-04 4.61E-03 (submersion) Thyroid dose 9.05E-02 1.40E-01 2.22E-01 2.46E-01 (airborne) Total body dose 1.50E-04 5.00E-04 1.70E-04 1.50E-03 (liquid) Thyroid dose 1.50E-04 4.90E-04 1.70E-04 1.50E-03 (liquid) Total 9.08E-02 1.43E-0{ 2.23E-01 2.54E-01 Gumulative Tota! Dose (mrem) 7.1oE-Ol Annual Dose Limit (mrem) 75 Percent of Limit 9.47o/o E1-32

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION EOR STABILITY CLASS A (DELTA T<:-]-.9 C/1OO M) WATTS BAR NUCLEAR PLANT JAN l, 2013 - l"lAR 31, 201,3 WIND WIND SPEED (MPH) DIRECTION O. 6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7 .5-L2.4 12.5-18.4 18.5-24.4 ):24.5 TOTAL N 0.000 0. 000 0.000 0.047 0. 186 0. 000 0. 000 0. 000 0.000 0.233 NNE 0. 000 0. 000 0. 000 0.233 0.326 0.093 0. 000 0.000 0.000 0.652 NE 0. 000 0. 000 0. 000 0.047 0.047 o.04-7 0. 000 0.000 0.000 0. 140 ENE 0-000 0. 000 0.000 0. 047 0. 000 0. 000 0. 000 0.000 0.000 0.047 E 0. 000 0.000 0. 000 0. 000 0. 000 0.000 0. 000 0. 000 0. 000 0.000 ESE 0. 000 0.000 o. 000 0. 000 0.000 0. 000 0.000 0. 000 0. 000 0.000 SE 0. 000 0. 000 0.000 0. 000 0. 000 0. 000 0.000 0. 000 0.000 0.000 SSE 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 0. 000 s 0. 000 0. 000 0. 000 0. 000 0.047 0.233 0. 000 0.000 0.000 0.279 SSW 0. 000 o. 000 0. 000 0. 000 o.5]-2 0.279 0.000 0. 000 0. 000 0.791 SW 0. 000 0. 000 0.000 0.093 0. t_86 0.047 0.000 0. 000 0. 000 0.326 WSt^I 0. 000 0. 000 0. 000 0. 000 0.000 0.186 0. 000 0. 000 0.000 0.r,86 t,fl 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 0.000 WNW o. 000 0. 000 0.000 0. 000 0.047 0.140 0. 000 0. 000 0.000 0. l-86 NW 0. 000 0. 000 0. 000 0. 047 0.093 0.233 0.000 0. 000 0.000 0.372 NNW 0. 000 0. 000 0. 000 0. 047 0.093 0. 140 0. 000 0. 000 0.000 0.279 SUBTOTAI 0. 000 0. 000 0. 000 0.559 1.536 1.397 0. 000 0. 000 0. 000 3.492 TOTAL HOURS OE VALID STABILITY OBSERVATIONS 2T4B TOTA], HOURS OF STABILITY CI,ASS A 75 TOTAI, HOURS OT VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS A 75 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2L48 TOTAL HOURS CALM 0 METEOROLOGICAI FACILITY: WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 I4ETER LEVEL DATE PRINTEDz 2OL3/05/10 MEAN WIND SPEED : 7.14 NOTE: TOTAI,S AND SUBTOTAIS ARE OBTAINED FROM UNROUNDED NUMBERS E1-33

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT

                                      .,OINT PERCEIflIAGE FREOUENCIES OF WIND SPEED BY WIND DIRECTION TOR SIABILITY CLASS B            (-1.9< DEITA T<=-1.7 C/100   M)

WATTS BAR NUCLEAR PI"ANI

                                                          .rAN 1, 2013 -    MAR 31. 2013 WIND                                                  WIND SPEEDIMPII)

DIRECTION 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 '1.5-12.4 12.5-78.4 \4.5-24.4 >=24.5 rOTAr, N 0. 000 0. 000 a -447 0.186 0.140 0 .186 0. 000 0. 000 0.000 0.559 NNE 0. 000 0.000 0-000 0. r-40 0.093 0 .093 0.000 0. 000 0.000 0.326 NE 0. 000 0.000 0. 093 0.093 0.047 0 .000 0.000 0. 000 0.000 0. 233 ENE 0. 000 0. 000 0. 000 0.047 0.047 0 .000 0. 000 0. 000 0.000 0.093 E 0. 000 0. 000 0. 000 0.000 0.047 0 .000 0. 000 0.000 0. 000 0. 047 ESE 0. 000 0. 000 0. 000 0. 093 0.000 0 .000 0. 000 0.000 0. 000 0. 093 SE 0. 000 0. 000 0.000 0. 000 0.000 0 .000 0. 000 0. 000 0.000 0.000 ssE 0. 000 0. 000 0.000 0.000 0.000 .000 0. 000 0. 000 0. 000 0. 000 S 0. 000 0. 000 0. 000 0. 093 0. 093 .047 o. 000 0. 000 0.000 0.233 SShI 0.000 0. 000 0. 000 0.093 0.233 .140 0. 000 0. 000 0.000 0.466 SW 0.000 0. 000 0. 000 0.093 0.140 .o47 0.000 0. 000 0.000 4.279 WSW 0. 000 0. 000 0. 000 0. 000 0.047 .047 0. 000 0. 000 0. 000 0.093 r{ 0. 000 0. 000 0. 000 0. 000 0. 000 .233 0. 000 0. 000 0.000 0.233 hINW 0. 000 0. 000 0. 000 o. 000 0.093 .233 0. 000 0. 000 0.000 0.326 NW 0. 000 0. 000 0. 000 0.047 0.2-79 .279 0. 000 0. 000 0.000 0. 605 NNW 0. 000 0. 000 0.047 0. 000 o.o47 . o41 0. 000 0.000 0.000 0. 140 SI]BTOTAL 0. 000 0.000 0. r.86 0.885 1 .304 .350 0. 000 0. 000 0.000 3.724 TOTAI HOURS OE VAIID STABILITY OBSERVATIONS 2148 TOTA1 HOURS OT STABILITY CI.ASS B 80 TOTAI HOURS OT VAIID WIND DIRECTION-WIND SPEED-STABILITY CI,ASS B BO TOTAI HOURS OE VAIID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2748 TOTAI HOURS CALM o METEOROLOGICAI FACILITY: WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BETV{EEN 9.51 AI{D 45.63 METERS WIND SPEED AI{D DIRECTION MEASURED AT 9.72 I"'E,TER LEVEL DATE PRINTEDz 2OL3/A5 / L0 MEAN WIND SPEED : 6.93 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED TROM UNROUNDED NUMBERS E1-34

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JOINT PERCENTAGE EREQUENCIES OF WIND SPEED BY WIND DTRECTION TOR STABILITY CLASS C (-1.7< DELTA T(:-l-.5 C/ 100 M) WATTS BAR NUCLEAR PLANT JAII l, 20L3 - NIAR 31, 2Ot3 WIND WIND SPEED (MPH) DIRECTION 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.s-12.4 L2.5-18.4 1"8.5-24.4 ):24.5 TOTAI N 0.000 0.000 0. 093 o. 140 o -047 0. 185 0. 000 0.000 0.000 0.466 NNE 0.000 0.000 0. 000 0.093 0.L40 o.233 0. 000 0.000 0.000 0.466 NE 0.000 0.000 0.047 0. 140 0.447 0. 000 0. 000 0. 000 0. 000 0.233 ENE 0. 000 0.000 0. 000 0.093 0. 047 0. 000 0.000 0. 000 0.000 0. 140 E 0. 000 0.000 0. 000 0.000 0. 000 0.000 0. 000 0. 000 0.000 0.000 ESE 0.000 0.000 0.000 0. 047 0.000 0.000 0. 000 0. 000 0.000 0.047 SE 0.000 0.000 0. o0o 0.000 0. 000 0.000 0. 000 0.000 0.000 0.000 SSE 0.000 0.000 0. 000 0.047 0.000 0.047 0. 000 0. 000 0.000 0.093 S 0.000 0.000 0. 000 o -047 0.000 0.140 0.000 0. 000 0.000 0. 186 SSW 0.000 0.000 0.093 0.372 0.093 0.047 0. 000 0. 000 0.000 0. 60s SW 0. 000 0.000 0. 000 0. 047 0.140 0. 000 0. 000 0. 000 0.000 0. 186 wsw 0. 000 0.000 0. 000 0. 140 0.093 0.047 0. 000 0. 000 0.000 0-279 w 0. 000 0. 000 0. 000 0.o47 0. 093 0.093 0.047 0.000 0.000 0.279 hINW 0. 000 0.000 0. 000 0.000 0. 186 0. 186 0. 000 0.000 0. 000 0 .372 NW 0. 000 0.000 0. 000 0.093 0. 140 0.325 0. 000 0. 000 0.000 0.559 NNW 0.000 0.000 0.047 0.047 0.093 0. 140 0. 000 0. 000 0. 000 0 .326 SUBTOTAI 0.000 0.000 o.279 1.350 1. 11_7 1.443 0.047 0. 000 0. 000 4.236 TOTAL HOURS OF VAIID STABILITY OBSERVATIONS 2L4B TOTAL HOURS OE STABILITY CLASS C 91 TOTAL HOURS OE VATID WIND DIRECTION-WIND SPEED-STABILITY CLASS C 91 TOTAL HOURS OF VA],ID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2L4B TOTAL HOURS CALM 0 METEOROLOGICAL FACILITY: WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BETVf,EEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL DATE PRINTED: 2013/05 /1.0 WIND SPEED : 6.66 TOTALS AND SUBTOTAIS ARE OBTAINED FROM UNROUNDED NUMBERS E1-35

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JOINT PERCENTAGE FREQUENCIES OE WIND SPEED BY WIND DIRECTION STABILITY CLASS D (-1.5< DELTA T(=-0.5 C/ 100 M) WATTS BAR NUCLEAR PLANT JAN L, 2Ol3 - MAR 31, 2013 WIND WIND SPEED (MPH) DIRECTION 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7 12-4 12.5-]-B-4 18.5-24.4 ):24.5 TOTAL N 0. 000 0.047 1.2L0 2.048 L.67 6 0.93L 0. 000 0. 000 0.000 s.9L2 NNE 0. 000 0. 047 1.'7 69 2.448 1. 397 0. 605 0.233 0. 000 0.000 6.099 NE 0. 000 0.047 1.490 1.071 0. 140 0.047 0. 000 0. 000 0.000 2.793 ENE 0. 000 0.000 0.559 o.456 0. 140 0.000 0.000 0. 000 0.000 1. 164 E 0. 000 0.000 0.372 0. r-40 0.093 0.047 0. 000 0. 000 0.000 0.652 ESE 0. 000 0.000 0. 186 0.000 0.000 0. 000 0. 000 0.000 0.000 0. 186 eE 0. 000 0.000 0. 140 0.047 0.047 0.047 0. 000 0.000 0.000 4.279 SSE 0. 000 0. 186 0. 4 19 0. 186 0.000 0. 140 0. 000 0. 000 0.000 0. 931 S 0. 000 0. 140 0.885 1.07r- 0.466 0. 605 0.233 0. 000 0.000 3.399 SSW 0.000 0. 000 r-.350 1.816 1.443 0.745 0. 000 0. 000 0.000 5.354 SW 0.000 0. 186 r_.350 L.257 0.559 0.140 0. 000 0. 000 0.000 3.492 WSW 0. 000 0. 140 0. 605 0.838 0.5L2 0. 605 0. 000 0.000 0.000 2.700 w 0. 000 0. r.86 0. 698 0.652 0.745 0 .652 0.140 0. 000 0.000 3.073 WNhI 0. 000 0.140 0.652 1.304 0.885 0.885 0.047 0. 000 0.000 3. 9r.r-NW 0. 000 0. 093 0.512 0. 698 0. 931 1.723 0. 000 0. 000 0.000 3. 957 NNW 0. 000 0.000 0. 698 0. 978 2.095 1.O24 0. 000 0. 000 0.000 4.795 SUBTOTAI 0. 000 L.2L0 1"2.896 14.61_8 Lt.Lz-t 8.194 o.652 0. 000 0.000 48.696 TOTAL HOURS OF VAIID STABILITY OBSERVATIONS 2L48 TOTAI HOURS OF STABILITY CLASS D 104 5 TOTA], HOURS OF VATID WIND DIRECTION-WIND SPEED-STABILITY CI,ASS D 104 6 TOTAL HOURS OE VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2L48 TOTAL HOURS CAIM 0 METEOROLOGICAL FACILITY: WATTS BAR STABTLITY BASED ON DELTA-T BETWEEN 9.51 AND 45. 63 METERS I,{IND SPEED A}ID DIRECTION MEASURED AT 9.72 IfiTER LEVEL DATE PRINTEDz 20L3/05/10 MEAII WIND SPEED : 5.23 TOTAIS AI{D SUBTOTALS ARE OBTAINED FROM UNROUNDED NTMBERS E1-36

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JOINT PERCENTAGE FREQUENCIES OE WIND SPEED BY $IIND DIRECTION FOR STABILITY CLASS E (-0.5< DELTA T(= 1.5 C/ 100 M) WATTS BAR NUCLEAR PLANT JAN L, 2013 - MAR 31, 20L3 WIND WIND SPEED (MPH) DIRECTION 0. 6-1.4 1.5-3.4 3.5-5.4 5. 5-7.4 ):24.5 TOTAL N 0. 000 0. 093 0.3"12 0.5L2 0. l-86 0.093 0.000 0. 000 0. 000 1,.257 NNE 0. 000 0 .047 0 -3'72 0. 698 0.047 0. 000 0.047 0. 000 0. 000 L.zLo NE 0. 000 0. 000 0 .652 0.279 0. 000 0. 000 0. 000 0. 000 0.000 0. 931-ENE 0. 000 0. 047 1. 11-7 0. 140 0. 047 0. 000 0. 000 0. 000 0.000 1.350 E 0. 000 0. 000 0. 140 0. 093 0. 047 0. 000 0. 000 0. 000 0.000 0.279 ESE 0. 000 0.o47 0.047 0. 093 0. 000 0. 000 0. 000 0. 000 0.000 0. 186 SE 0. 000 0. 1"40 0. 093 0.000 0.047 0.000 0. 000 0.000 0.000 0.279 SSE 0-000 0. 093 o.279 0. 047 0.047 0.047 0. 000 0.000 0. 000 0 .5L2 S 0.000 0.186 0. 605 o.233 o .652 0.3't2 0.093 0. 000 0.000 2.L42 SShI 0. 000 o.233 1.67 6 t-.443 O. B3B 0.093 0. 000 0. 000 0. 000 4 .283 SW 0. 000 0.233 1.583 0. 698 o.326 0.093 0. 000 0. 000 0.000 2.933 wsw 0. 000 o.466 0.931 0.047 0.047 0.093 0. 000 0. 000 0.000 1.583 w 0. 000 0.419 l-.304 0. 140 0.233 0.047 0.047 0. 000 0.000 2.188 wNw 0. 000 o.372 1 . 071_ 0. 698 0.140 0.047 0. 000 0. 000 0. 000 2.328 NW 0. 000 0. r-40 0.559 0.233 0. t_86 0.140 0.000 0. 000 0. 000 L.257 NNW 0. 000 0.233 0.512 0. l_86 0.233 0.140 0. 000 0. 000 0.000 1.304 SUBTOTAI 0.000 2-747 l_1.313 5.540 3.073 1. 164 0.LB6 0.000 o.000 24.o22 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2148 TOTAI HOURS OE STABILITY CI,ASS E 516 TOTAI HOURS OF VALID WIND DIRECTION-T{IND SPEED-STABILITY CLASS E 516 TOTAI HOURS OT VALID V{IND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2L48 TOTAL HOURS CAI,M O METEOROLOGICAI FACILITY: WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.5]. AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL DATE PRINTED:. 20L3/05/LA MEAN WIND SPEED : 3.62 NOTE: TOTAI,S AND SUBTOTAIS ARE OBTAINED FROM UNROUNDED NU}4BERS E1-37

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY $IIND DIRECTION FOR STABILITY CLASS F ( l-.5< DELTA T(: 4.0 C/ 100 M) WATTS BAR NUCLEAR PLANT JAN L, 2AL3 - I,IAR 31, 2013 hIIND WIND SPEED (MPH) DIRECTION 0. 6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-t2.4 12.5-L8.4 18.5-24.4 ):24.5 TOTAL N 0. 000 0. r.40 0.093 0. 000 0.000 0. 000 0. 000 0. 000 0. 000 0.233 NNE 0. 000 0.047 0.047 0. 000 0. 000 0. 000 0. 000 0.000 0.000 0.093 NE 0. 000 0.093 0.233 0.000 0. 000 0.000 0. 000 0. 000 0.000 0.325 ENE 0.000 0.093 0.140 0. 000 0.000 0. 000 0. 000 0. 000 0.000 0.233 E 0. 000 0.140 0.047 0. 000 0. 000 0. 000 0. oo0 0.000 0.000 0. 186 ESE 0. 000 0.047 0.047 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 0. 093 SE 0. 000 0. 140 0. 047 0.000 0. 000 0. 000 0. 000 0.000 0.000 0. 186 SSE 0. 000 0. 000 0.000 0. 000 0. 000 0.000 0. 000 0. 000 0.000 0.000 s 0.000 0. 093 0. 000 0.000 0. 000 0.000 0. 000 0. 000 0. 000 0.093 SSW 0. 000 0. 093 0.233 0.047 0. 000 0.000 0. 000 0. 000 0.000 0.372 SW 0.000 0.372 0.559 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 0. 931 WSW o. 000 o.5L2 0.456 0.047 0.000 0. 000 0. 000 0. 000 0.000 L.a24 W 0. 000 0.559 0. 978 0.000 0. 000 0.000 o. 000 0. 000 0.000 1.536 WNW 0.000 O. BB5 0. 698 0.047 0. 000 o. 000 0. 000 0. 000 0.000 L.629 NW 0.000 0.326 0.186 0. 140 0. 000 0. 000 0. 000 0. 000 0.000 0.652 NNW 0. 000 0.279 0.186 0. 093 0. 000 0. 000 0. 000 0. 000 0.000 0.559 SUBTOTAT 0.000 3.818 3. 957 0.372 0. 000 0-000 0. 000 0. 000 0.000 8.L47 TOTAL HOURS OE VAIID STABILITY OBSERVATIONS 2148 TOTAL HOURS OF STABILITY CLASS F t_75 TOTAL HOURS OE VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS F ]-75 TOTAL HOURS OE VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2L48 TOTAI HOURS CALM 0 METEOROLOGICAI FACILITY: WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA.T BETWEEN 9.51 A}TD 45.53 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL DATE PRINTEDT 2OL3/05 / t0 MEAN WIND SPEED = 1.73 NOTE: TOTALS AI{D SUBTOTATS ARE OBTAINED FROM UNROUNDED NUMBERS E1-38

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JOINT PERCENTAGE EREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS G (DELTA T > 4.A C/ 100 M) WATTS BAR NUCLEAR PLANT JAN t, 2013 - MAR 31, 201"3 WIND WIND SPEED (MPH) DIRECTION 0. 6-1.4 1. 5-3.4 3.5-5. 4 5. 5-7.4 7 .5-1.2.4 L2.5-18 .4 18 .5-24 .4 ):24 .5 TOTAL N 0. 000 0.2'79 0. 093 0. 000 0. 000 0. 000 0. 000 0.000 0. 000 0 .372 NNE 0. 000 0. 000 0. 093 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 0.093 NE 0. 000 0.093 0.047 0. 000 0. 000 0.000 0. 000 0. 000 0.000 0.1_40 ENE 0. 000 0. 047 0. 093 0.000 0. 000 0. 000 0. 000 0. 000 0.000 0. 140 E 0. 000 0. 140 0.047 0. 000 0. 000 0.000 0. 000 0. 000 0.000 0. 186 ESE 0. 000 0. 093 0. 000 0. 000 0. 000 0.000 0. 000 0. 000 0.000 0. 093 SE 0.000 0.047 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 0. 047 SSE 0. 000 0.047 0. 000 0. 000 0. 000 0. 000 0.000 0. 000 0.000 0 -o47 s 0. 000 0. 093 0.047 0.000 0. 000 0. 000 0. 000 0.000 0.000 0.r-40 SSW 0. 000 0.186 0.047 0. 000 0. 000 0.000 0. 000 0. 000 0.000 0.233 SW 0. 000 0.559 o.233 0.047 0. 000 0.000 0. 000 0. 000 0. 000 0.838 wsw 0. 000 1". 1-64 0.419 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 r..583 w 0. 000 1.117 0.512 0.000 0. 000 0. 000 0. 000 0. 000 0. 000 1.629 hINW 0. 000 0.791 0 .466 0.000 0. 000 0. 000 0. 000 0. 000 0. 000 L.257 NW 0. 000 0.419 0.279 0. 000 o.000 o. 000 0. 000 0. 000 0 - 000 0. 698 NNW 0. 000 0.186 0. 000 0. 000 0.000 0.000 0. 000 0. 000 0.000 0. 185 SUBTOTAL 0. 000 5 -26L 2-374 0.047 0. 000 0.000 0.000 0. 000 0.000 7 -682 TOTAL HOURS OE VALID STABILITY OBSERVATIONS 2L48 TOTAI HOURS OF STABILITY CLASS G ]-65 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED.STABILITY CLASS G 165 TOTAI HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2148 TOTAL HOURS CALM O METEOROLOGICAL FACILITY: WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.51 AT'ID 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 I"'E.TER LEVEL DATE PRINTED.. 2OL3/05 / LO MEAN WIND SPEED : 1".35 NOTE: TOTALS A!{D SUBTOTAIS ARE OBTAINED EROM UNROUNDED NUMBERS E1-39

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION EOR STABILITY CLASS A (DELTA T(:-1 .9 C/ 100 M) WATTS BAR NUCLEAR PI,ANT APR L, 20L3 JUN 30, 2OL3 WIND hIIND SPEED (MPH) DIRECTION 0.6-1.4 1.s-3.4 3.5-5.4 5.5-7.4 7.s-Lz.4 12.s-18.4 18.5-24.4 ):24.5 TOTAI N 0. 000 0. 000 0. 000 0.046 0. 139 0.093 0. 000 0.000 0.000 0.279 NNE 0.000 0.000 0. 000 0.045 0.046 0. 093 0. 000 0. 000 0.000 0. 186 NE 0. 000 0. 000 0.000 0. 000 0. 093 0. 139 0. 000 0. 000 0.000 0.232 ENE 0. 000 0. 000 0. 000 0.000 0. 000 0.046 0.000 0. 000 0.000 0.046 E 0.000 0. 000 0. 000 0.000 0. 000 0. 000 0.000 0. 000 0 - 000 0. 000 ESE 0. 000 0. 000 0. 000 0. 000 0.000 0. 000 0. 000 0.000 0.000 0.000 SE 0. 000 0.000 0. 000 o. 000 0. 000 0.000 0. 000 0.000 0.000 0.000 SSE 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 0. 000 0.000 0.000 S 0. 000 0.000 0.046 0. 000 0.046 0.046 0.000 0. 000 0. 000 0. l-39 SSW 0. 000 0. 000 0.046 0.418 o.325 0. 604 0. 000 0. 000 0.000 1.395 SW 0. 000 0. 000 0.000 0. 093 0.325 0. 000 0. 000 0.000 0.000 0.4r-8 WSW 0.000 0.000 0.000 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 0.000 w 0. 000 0. 000 0. 000 0. 000 0.046 0. 093 0. oo0 0. 000 0. 000 0. 139 WNW 0.000 0. 000 0. 000 0. 000 0. 000 0.045 0. 000 0. 000 0.000 0.046 NW 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 0.000 NNW 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 0.000 SUBTOTAL o. 000 0.000 0. 093 0. 604 t.023 L.L62 0. 000 0.000 0.000 2.882 TOTAL HOURS OE VAI,ID STABILITY OBSERVATIONS 2L'15 TOTAI HOURS OF STABILITY CLASS A 63 TOTAI HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS A 62 TOTAL HOURS OF VAIID SIIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2L5L TOTAL HOURS CALM O METEOROLOGICAI FACILITY: WATTS BAR NUCLEAR PLAI{T STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 }IETERS WIND SPEED AI{D DIRECTION MEASURED AT 9.72 Y,ETER LEVEL DATE PRINTEDT 2Ot3/08/ 15 MEAI{ WIND SPEED : 6.74 NOTE: TOTAI,S AI,ID SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS E1-40

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JOINT PERCENTAGE TREQUENCIES OE WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS B (-1.9< DELTA T(:-1 .7 C/ 100 M) VIATTS BAR NUCLEAR PLANT APR L, 20L3 - JUN 30, 20L3 WIND WIND SPEED (MPH) DIRECTION 0. 5-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-L2.4 12.5-18.4 L8.5-24.4 ):24.5 TOTAL N 0. 000 0. 000 0. 000 0. 000 0. 139 0. 093 0. 000 0. 000 0.000 0.232 NNE 0. 000 0. 000 0. 000 0. 186 0. 000 0. 186 0. 000 0.000 0.000 0.372 NE o. 000 0. 000 0. 000 0. 139 0.045 0. 000 0. 000 0. 000 0.000 0.r-86 ENE 0. 000 0. 000 0. 000 0. t_86 0.093 0. 000 0. 000 0. 000 0.000 0 -279 E 0.000 0. 000 o. 000 0.046 0.093 0. 000 0. 000 0. 000 0.000 0. 139 ESE 0.000 0. 000 0. 000 0. 000 0.000 0. 000 0. 000 0. 000 0.000 0. 000 SE 0. 000 0. 000 0. 000 0.046 0. 000 0. 000 0.000 0.000 0.000 0.046 SSE 0-000 0. 000 0. 000 0.046 o. 000 0. 000 0.000 0.000 0.000 0.046 5 0.000 0.000 0.000 o.372 o.232 0. 093 0.000 0. 000 0. 000 0.69'7 ssw 0. 000 0. 000 0.000 o.7 44 0.465 0.046 0. 000 0. 000 0. 000 r..255 SW 0. 000 0-000 0.093 0.418 0. 139 0. 000 0. 000 0. 000 0.000 0. 651 wsw 0. 000 0. 000 0. 000 0.046 0.000 0. 000 0. 000 0. 000 0.000 0.046

   $I             0.000        0. 000       0.000        0. 000     0.045        0.000          0. 000   0. 000      0.000      0.046

[.\INW 0.000 0. 000 0. 000 0. 000 0. 139 0.045 0. 000 0. 000 0.000 0. 186 NW 0. 000 0. 000 0. 000 0.046 0.046 0. 000 0. 000 0. 000 0.000 0.093 NNW 0. 000 0. 000 0.000 0. 139 0.046 0-045 0. 000 0. 000 0,000 0.232 SUBTOTAL 0.000 0.000 0.093 2.4L7 1.488 0. 511 0.000 0. 000 0. 000 4.510 TOTAI HOURS OF VAIID STABILITY OBSERVATIONS 2175 TOTAI HOURS OF STABILITY CLASS B 99 TOTAI HOURS OF VAIID WIND DIRECTION-hIIND SPEED-STABILITY CLASS B 9'7 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2L5L TOTAI HOURS CALM O METEOROLOGICAL FACILITY: Tf,ATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 N'ETER LEVEL DATE PRINTED: 2OL3/08/L5 MEAII WIND SPEED : 5.48 NOTE: TOTAI,S AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS E1-41

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT STABILITY CLASS C (-1.7< DELTA T(:-1.5 C/ 100 M) WATTS BAR NUCLEAR PLANT APR t, 20L3 - JUN 30, 20L3 WIND WIND SPEED (MPH) DIRECTTON 0 .6-t.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-L2.4 12.5-l-8.4 L8.5-24.4 )=24.5 TOTAL N 0. 000 o. 000 o.232 0. 139 0. l-39 0.046 0. 000 0. 000 0.000 0.558 NNE 0. 000 0.000 0.046 0.232 0.046 0.186 0. 000 0. 000 0.000 0.51-1 NE 0. 000 0-000 0. 139 0.093 0. 000 0.045 0. 000 0. 000 0.000 4.279 ENE 0. 000 0. 000 0. 000 0.093 0. 139 0. 000 0. 000 0. 000 0.000 0.232 E o. 000 0. 000 0.046 0.093 0. 000 0.000 0. 000 0. 000 0.000 0. 139 ESE 0. 000 0. 000 0.046 0.046 0. 000 0. 000 0. 000 0. 000 0.000 0.093 SE 0. 000 0.046 0. 093 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 0. 139 SSE 0. 000 0.000 0.046 0.186 0. 000 0. 000 0.000 0. 000 0.000 0.232 S 0. 000 0. 000 0. 000 0. 837 o.325 0. 093 0.000 0. 000 0.000 L.255 ssw 0. 000 0. 000 0.093 o-976 0.232 o.372 0. 000 0. 000 0.000 L.674 SW 0. 000 0. 000 0.186 0. s58 0.046 0.093 0. 000 0. 000 0.000 0.883 wsw 0. 000 0.000 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 0.000 w 0. 000 0. 000 0.000 0.093 0.046 0.045 0. 000 0. 000 0.000 0.185 IiINW 0. 000 0. 000 0. 000 0.093 0. 000 0.093 0. 000 0. 000 0.000 0.186 NW 0.000 0. 000 0. 093 0.046 0.046 0.093 0. 000 0-000 0.000 0.279 NNW 0. 000 0. 000 0. 000 0.093 0.093 0. 000 0.000 0-000 0.000 0. 186 SUBTOTAI 0. 000 0.045 7.O23 3.580 1. L16 1.069 0. 000 0. 000 0.000 6.834 TOTAI HOURS OE VALID STABILITY OBSERVATIONS 2175 TOTAI HOURS OF STABILITY CLASS C L41 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS C L47 TOTAI HOURS OF VALID $IIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2151 TOTAL HOURS CALM 0 METEOROLOGICAT TACILITY: WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS II{IND SPEED AI{D DIRECTION MEASURED AT 9.72 I,fiTER LEVEL DATE PRINTED: 20L3/08/ L5 MEAN WIND SPEED : 5.17 NOTE: TOTALS A}ID SUBTOTALS ARE OBTAINED TROM UNROUNDED NUMBERS E1-42

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS D (-1.5< DELTA T(=-0.5 C/100 M) WATTS BAR NUCLEAR PLANT APR t, 2Ol3 - JUN 30, 2013 WIND WIND SPEED (MPH) DIRECTION O. 6-l-.4 1. 5-3.4 3.5-5.4 5.5-7.4 7 .5-L2.4 L2.5-18 .4 LB .5-24 .4 ):24 .5 TOTAI N 0. 000 0.046 0.744 0.511 0.511 0.232 0. 000 0.000 0. 000 2 .046 NNE 0. 000 0. 04 6 0. 604 0.837 0.372 o -279 0. 000 0.000 0. 000 2 .739 NE 0.000 0.000 0. 651 L.L62 o.232 0. 186 0.046 0. 000 0. 000 2.278 ENE 0. 000 0.000 0.5L1- o.372 o.232 0.046 0. 000 0. 000 0.000 1.t62 E 0. 000 0 - 093 0. 651 0.279 0. 000 0. 000 0. 000 0. 000 0. 000 t.023 ESE 0. 000 0.093 0. 651 0. 093 0.045 0. 000 0.000 0. 000 0.000 0.883 SE 0.000 0. 1 39 0.418 0. 186 0.046 0. 000 o. 000 0. 000 0.000 0.790 SSE 0-000 o.232 0.418 o.232 0. 139 o.2'79 0. 000 0. 000 0. 000 .302 S 0. 000 0.46s 1.488 .348 0.51-1 0.511 0.093 0.000 0. 000 .4L7 SSW 0. 000 0. r-39 2.139 .232 L.209 0-465 0. 000 0. 000 0. 000 . r,83 SW 0. 000 0.093 L.627 .930 0.232 0.000 0. 000 0. 000 0. 000 .882 wsw 0.000 0.139 0.976 .325 0. 139 0.000 0. 000 0. 000 0. 000 .581 W 0-000 0.000 0. 186 .232 0.093 0. 093 0. 000 0. 000 0. 000 .604 riNw 0. 000 0.046 0.186 .232 o .697 0.511 0.000 0-000 0. 000 .67 4 NhI 0. 000 0.000 0.279 -325 0. 325 0.790 0.000 0. 000 0.000 .720 NNW 0.000 0.000 0.232 0.651 0.790 0.2"79 0. 000 0. 000 0.000 .953 SUBTOTAI 0. 000 1. s34 71.'162 9 .949 5.579 3. 673 0. l-39 0.000 0. 000 32.636 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2]-75 TOTAI HOURS OF STABILITY CLASS D 7L2 TOTAI HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS D 702 TOTAI HOURS OF VALID 9{IND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2151 TOTAT HOURS CALM O METEOROLOGICAL TACILITY: WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AIID DIRECTION MEASURED AT 9.72 IN{EIER LEVEL DATE PRINTEDz 2OL3/08/t5 MEAN WIND SPEED : 4.45 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS E1-43

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CTASS E (-0.5< DELTA T(: L.5 C/ 100 M) WATTS BAR NUCLEAR PTANT APR t, 2013 - JUN 30, 20L3 WIND WIND SPEED (MPH) DIRECTION 0. 6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 L2.5-18.4 1.8.5-24.4 )-24.5 TOTAL N 0. 000 0.093 0.325 0.325 0.046 0. 000 0. 000 0. 000 0.000 0.790 NNE 0. 000 0. 000 0. 186 0. 000 0.046 0. 000 0. 000 0. 000 0.000 0.232 NE 0. 000 0.046 0.L86 0. 186 0.046 0. 000 0.000 0. 000 0.000 0.465 ENE 0. 000 0.093 0.418 0. 139 0.000 0. 000 0. 000 0. 000 0.000 0. 651 E 0. 000 o.232 o .697 0.093 0.000 0. 000 0. 000 0. 000 0.000 1.023 ESE 0.000 0.186 0.279 0.045 0.000 0. 000 0. 000 0.000 0.000 0.511 SE 0.000 0.093 0. 186 0. 139 0. 000 0. 000 0. 000 0. 000 0.000 0. 418 SSE 0. 000 0. 604 0.325 0.093 0.046 0. 139 0. 000 0.000 0. 000 t.2a9 S 0. 000 0.465 2.046 o.144 0.65r_ o.232 0. 000 0. 000 0.000 4. 138 SSW 0. 000 0. 604 3.8L2 2 -232 0.511 0. 000 0. 000 0. 000 0.000 7 .t59 SW 0.000 1.255 1. 395 0.4L8 0.046 0.046 0. 000 0. 000 0.000 3. 161. WSW 0. 000 0.651 1, . O23 0.046 0.093 0.045 0. 000 0.000 0.000 l-.860 W 0. 000 0.651 0.41_8 0.279 0.046 0. 000 0. 000 0. 000 0.000 1.395 WNW 0. 000 0.325 0.418 0.418 0.139 0.046 0.000 0. 000 0.000 r_.348 NW 0. 000 o.232 0.325 0. r_86 0. 139 0.046 0. 000 0. 000 0.000 0. 930 NNW 0. 000 0.093 0.372 0.418 0.372 0.046 0. 000 0. 000 0.000 1.302 SUBTOTA], 0. 000 5-625 L2.413 5.765 2.L85 0. 604 0. 000 0.000 0.000 26.592 TOTAL HOURS OF VA],ID STABILITY OBSERVATIONS 21"7 5 TOTAI HOURS OF STABILITY CLASS E 578 TOTAI HOURS OE VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS E 572 TOTAI, HOURS OE VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2L5T TOTAI HOURS CALM 0 METEOROLOGICAL FACILITY: V{ATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.51 AI{D 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 I"IETER LEVEL DATE PRINTED: 2Ol3/08/L5 MEA}T WIND SPEED : 2-96 TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NU}4BERS E1-44

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS F ( 1.5< DELTA T(: 4.0 C/ 100 M) WATTS BAR NUCLEAR PLANT APR t, 2OL3 - JUN 30, 20L3 WIND WIND SPEED (MPH) DIRECTION 0.6-l-.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-L2.4 12.5-l-8.4 ]-8.5-24.4 ):24.5 TOTAI N 0. 002 o.232 0.046 0. 000 0. 000 0. 000 0. 000 0.000 0.000 0.281 NNE 0.001 0.000 0.093 0. 000 0. 000 0. 000 0. 000 0.000 0.000 0.094 NE 0. 002 0.046 o.232 0. 000 0. 000 0.000 0. 000 0. 000 0.000 0.28]- ENE 0. 003 0.279 0. 186 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0. 4 68 E 0. 002 o.232 0.046 0. 000 0. 000 0.000 0. 000 0. 000 0.000 0.28L ESE 0. 002 0.186 0. 093 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0.281 JT. 0-000 0. 000 0.046 0. 000 o. 000 0. 000 0. 000 o. 000 0.000 0. 047 SSE 0. 003 0.279 0. 093 0.046 0.000 0. 000 0. 000 0. 000 0.000 0.42L S 0. 003 4.279 0. 186 0. 000 0.000 0. 000 0. 000 0. 000 0.000 0. 468 SSW 0.0r.0 0.558 0.883 0.046 0. 000 0. 000 0. 000 0. 000 0.000 1.498 ShI 0.013 0. 930 .o23 0. 000 0. 000 0. 000 0.000 0. 000 0.000 1.966 WSW 0.016 r..023 .348 0. 000 0. 000 0. 000 0.000 0. 000 0.000 2.387 w 0.01-4 1.534 .558 0.000 0. 000 0. 000 0. 000 0. 000 0.000 2.L06 wNw 0.0L2 1.395 .325 0. 000 0.000 0. 000 0. 000 0. 000 0. 000 1..732 NW 0. 007 0.651 . 418 0.046 0. 000 0. 000 0. 000 0.000 0.000 L.L23 NNW 0. 002 0.093 .232 0.046 0. 000 0. 000 o. 000 0. 000 0.000 0.37 4 SUBTOTA], 0. 093 7 .717 5.811 0. 186 0.000 0. 000 0. 000 0. 000 0.000 13. 808 TOTAL HOURS OF VAIID STABILITY OBSERVATIONS 2T75 TOTAL HOURS OF STABILITY CLASS F 3OO TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS F 297 TOTAI HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2T51 TOTAI, HOURS CALM 2 METEOROLOGICAI EACILITY: WATTS BAR NUCLEAR PLANT STABILTTY BASED ON DELTA-T BETWEEN 9.51 A}'ID 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 I"IETER LEVEL DATE PRINTEDT 2013/08/L5 I{EAI'I WIND SPEED : l-.50 NOTE: TOTALS AND SUBTOTAI,S ARE OBTAINED FROM UNROUNDED NUMBERS E1-45

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION STABILITY CLASS G (DELTA T > 4.O C/ ].OO M) WATTS BAR NUCLEAR PLANT APR L, 20L3 JUN 30, 2OL3 WIND WIND SPEED (MPH) DIRECTION 0. 6-1.4 1.5-3.4 3.5-5.4 s.5-7.4 ):24-5 TOTAL N 0. 000 o.279 0.000 0.000 0. 000 0. 000 0. 000 0. 000 0.000 0.279 NNE 0. 000 0. 093 0.000 0.000 0. 000 0. 000 0.000 0. 000 0.000 0.093 NE o. 000 0.093 0.000 0.000 0. 000 0. 000 0. 000 0. 000 0.000 0.093 ENE 0. 000 0.093 0. 139 0.000 0. 000 0. 000 0. 000 0.000 0.000 0.232 E 0. 000 0.139 0.000 0.000 0.000 0.000 0. 000 0. 000 0.000 0. 1_39 ESE 0. 000 0.046 0.000 0.000 0.000 0. 000 0.000 0. 000 0.000 0.046 SE 0. 000 0.139 0.000 0.000 0. 000 0. 000 0. 000 0. 000 0.000 0. 139 SSE 0.000 0. 139 0.000 0.000 0. 000 0. 000 0. 000 0.000 0.000 0. 139 S 0.000 0.139 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 0. 139 SSW 0. 000 o.697 0.093 0.000 0. 000 0. 000 0. 000 0. 000 0.000 0.790 SW 0. 000 o.7 44 o .372 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 1.116 WSW 0. 000 1. 953 0.3"72 0.000 0.000 0. 000 0. 000 0. 000 0. 000 2.325 sl 0. 000 L.67 4 0.697 0.000 0. 000 0. 000 0. 000 0. 000 0.000 2.3"7L WNW 0. 000 2.t39 0 .697 0. 000 0.000 0. 000 0.000 0. 000 0.000 2.836 N!^I 0. 000 1.059 0.455 0.000 0.000 0. 000 0.000 0. 000 0.000 1.534 NNW 0. 000 o.279 0. 186 0.000 0.000 0. 000 0. 000 0.000 0.000 0.465 SUBTOTAL 0.000 9.7L6 3.022 0.000 0. 000 0. 000 0. 000 0. 000 0.000 t2.738 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2L75 TOTAI HOURS OF STABILITY CLASS G 276 TOTAI HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CI"ASS G 214 TOTAI HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2L51 TOTAL HOURS CALM 0 METEOROLOGICAL FACILITY: WATTS BAR NIICLEAR PLANT STABILITY BASED ON DELTA.T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AI{D DIRECTION MEASURED AT 9.'72 I"IETER LEVEL DATE PRINTEDz 2013/08/ L5 MEAN WIND SPEED : t.22 TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS JOINT PERCENTAGE EREQUENCIES OF WIND SPEED BY WIND DIRECTION TOR STABILITY CLASS A (DELTA T(:-1 .9 C/ l-00 M) WATTS BAR NUCLEAR PLANT JUL I, 20L3 - SEP 30, 2AL3 WIND WIND SPEED (MPH) DIRECTION 3.5-5.4 5.5-7.4 '7

                                                                                        .5-t2 .4       12 .s-LA .4 lB .5'24  .4     )=24  .5    TOTAL N             0.000         0. 000        0. 000         0. 000      0.045            0. r.36          0. 000      0.000         0.000       0. l-82 NNE           0. 000        0. 000        0.000          0.000       0.091            0. 091           0. 000      0. 000        0.000       0. 182 NE            0. 000        0.000         0.091          0.045       0.045            0.000            0.000       0. 000        0. 000      0. 182 ENE           0.000         0. 000        0. 000         0. 000      0.091            0.045            0.000       0. 000        0.000       0. 136 E             0. 000        0.000         0.000          0.000       0.045            0. 000           0. 000      0. 000        0.000       0.045 ESE           0. 000        0. 000       0. 000         0. 000      0. 000           0. 000           0. 000      0. 000        0. 000      0. 000 SE           0. 000        0. 000       0. 000         0. 000      0. 000           0. 000           0. 000      0. 000        0.000       0.000 SSE          0. 000        0. 000       0.045          0.000       0.000            0.000            0. 000      0. 000        0.000       0.045 S            0. 000         0. 000       0.045          0. r-36     0.045            0.000            0. 000      0. 000        0.000       0.227 SSW          0. 000         0. 000       0.045          0.772       0. r_82          0. 000           0.000       0. 000        0.000       1.000 SW           0.000          0-000        0. 045         0. 136      0. 000           0. 000           0. 000      0.000         0.000       0.L82 WSW           0. 000         0. 000       0.000          0.000       0.000            0.000            0. 000      0.000         0.000       0.000 W             0.000          0. 000       0.000          0.000       0.000            0. 000           0. 000      0. 000        0.000       0.000 WNW           0. 000         0. 000       0.000          0.045       0. 000           0. 000           0. 000     0. 000        0. 000      0.04s NW           0. 000         0. 000       0.000          0.000       0. 000           0.000            0. 0oo     0. 000        0. 000      0.000 NNW          0. 000         0-000        0. 000         0.000        0. r.36         0.091            0. 000     0. 000        0.000       0.227 SUBTOTAL           0. 000         0. 000       0.273           1. 135      0.682           0. 363            0.000      0. 000        0 - 000     2.453 TOTAL HOURS OT VALTD STABILITY OBSERVATIONS                                                       22OL TOTAL HOURS OF STABILITY CLASS A                                                                     54 TOTAL HOURS OE VAIID WIND DIRECTION-WIND SPEED-STABILITY CLASS A                                     54 TOTAT HOURS OF VAIID WIND DTRECTION.WIND SPEED-STABILITY OBSERVATIONS                             2207 TOTAI HOURS CALM                                                                                       O METEOROLOGICAL    EACILITY: WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.5]" AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT          9.72 I'ETER LEVEL DATE PRINTED: 201.3/ LL/ L2 WIND SPEED   : 5.46 TOTAIS AI{D SUBTOTALS ARE OBTAINED FROM UNROUNDED           NUMBERS E1-46

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JOINT PERCENTAGE TREQUENCIES OE WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS B (-1.9< DELTA T(:-1.7 C/ 100 M) WATTS BAR NUCLEAR PLANT JUL L, 20L3 - SEP 30, 2013 WIND WIND SPEED (MPH) DIRECTION 0.6-l-.4 l-.5-3.4 3.5-5.4 5.5-7.4 7.5-L2.4 12.5-t8.4 L8.5-24.4 ):24.5 TOTAL N o. 000 o. 000 0. 000 0.091 0. 000 0. 182 0. 000 0. 000 0. 000 0.273 NNE 0. 000 0. 000 0.045 0. 135 0.09L 0 -1,82 0. 000 0. 000 0.000 0. 454 NE 0. 000 0. 000 0.045 0. 136 0.000 0. 000 0. 000 0. 000 0.000 0.L82 ENE 0. 000 0. 000 0.045 0.045 0.045 0. 000 0. 000 0. 000 0.000 0. 136 E 0. 000 0. 000 0. 000 0.045 0.000 0.000 0. 000 0. 000 0.000 0. 045 ESE 0. 000 0. 000 0.045 0.045 0. 000 0.000 0. 000 0. 000 0.000 0.091 SE 0. 000 0. 000 0.045 0. 045 0. 000 0.000 0. 000 0. 000 0. 000 0.091 SSE 0. 000 0-000 0.045 0. 045 0. 000 0. 000 0.000 0. 000 0. 000 0.091 S 0. 000 0. 000 0.091 0.409 0. 000 0. 000 0.000 0. 000 0. 000 0.500 ssw 0. 000 0. 000 0.273 0.72'7 0.091- 0. 000 0.000 0. 000 0.000 r-.090 SW 0. 000 0. 000 o.tBZ 0.454 0. 000 0. 000 0. 000 0. 000 0. 000 0. 536 WSW 0. 000 0. 000 0.045 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 0.045 w 0. 000 0. 000 0. 000 0.045 0. 000 0. 000 0. 000 0. 000 0. 000 0.04s wNw 0. 000 0. 000 0.000 0. 000 0. 091 0. 000 0. 000 0. 000 0.000 0.091-NW 0.000 0. 000 0. 000 0. 000 0. 000 0. 000 o. 000 0. 000 0.000 0.000 NNW 0. 000 0. 000 0. 000 0.045 0. 000 0. 000 0. 000 0. 000 0. 000 0.045 SI'BTOTAL 0. 000 0.000 0.863 2.272 0.318 0.363 0. 000 0. 000 0.000 3. 816 TOTAL HOURS OE VALID STABILITY OBSERVATIONS 2201, TOTAL HOURS OF STABILITY CLASS B 84 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS B 84 TOTAL HOURS OF VALID WIND DIRECTTON-hIIND SPEED-STABILITY OBSERVATIONS 2201 TOTA-L HOURS CALM 0 METEOROLOGICAT FACILITY: WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 I"ETER LEVEL DATE PRINTED.. 2OL3/IL/ L2 MEAII WIND SPEED : 4.58 NOTE: TOTAI,S AND SUBTOTA],S ARE OBTAINED EROM UNROUNDED NUMBERS E147

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT STABILITY CLASS C (-1.7< DELTA T(:-1.5 C/L00 M) V{ATTS BAR NUCLEAR PLANT JUL 1, 2013 - SEP 30, 20L3 WIND WIND SPEED (MPH) DIRECTION 0. 6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-L2.4 12.5-t8.4 L8.5-24.4 >--24.5 TOTAL N 0. 000 0. 000 0.227 0.318 0.045 0. 045 0. 000 0.000 0. 000 0. 636 NNE 0. 000 0. 000 0. 136 o .1,82 O.LB2 0.091 0. 000 0. 000 0.000 0.591 NE 0. 000 0. 000 o -782 0. 136 0.045 0.000 0. 000 0. 000 0. 000 0.363 ENE 0. 000 0. 000 0.045 0.L82 0.045 0. 000 0. 000 0. 000 0.000 a.273 E 0. 000 0. 000 0.L82 0 -L82 0. 000 0. 000 0. 000 0. 000 0. 000 0.363 ESE 0. 000 0. 000 0.045 0.091 0. 000 0. 000 0. 000 0. 000 0.000 0. 136 SE 0.000 0.000 0. 136 0. 136 0. 000 0. 000 0. 000 0. 000 0. 000 0.273 SSE 0.000 0. 000 0.136 0. 000 0. 000 0. 000 0. 000 0.000 0.000 o. 136 S 0. 000 0. oo0 0. 136 o.227 0. 000 0. 000 0. 000 0.000 0.000 0.363 SSW 0. 000 0. 000 0.409 0.772 0.091- 0. 000 0. 000 0. 000 0. 000 L.272 SW 0. 000 0. 000 0.318 0.318 0. o0o 0. 000 0. 000 0. 000 0.000 0. 636 wsw 0. 000 0. 000 0. 000 0.045 0. 000 0. 000 0. 000 0.000 0.000 0.045

   !{             0. 000      0.000       0. 000       0.091-     0.091        0. 000        0. 000       0. 000      0.000      0. 182 wNw            0. 000      0. 000      0. 000       0. 182     0. 000       0. 000        0. 000       0. 000      0.000      0. 182 NW             0. 000      0. 000      0. 000       0.045      0. 000       0.045         0.000        0. 000      0.000      0. 091 NNW            0. 000      0.000       0.091        0.782      0.045        0. 000        0. 000       0. 000      0.000      0.318 SUBTOTAI,          0. 000      0.000       2.045        3.090      0.545        0. 182        0.000        0. 000      0.000      5. 851 TOTAI  HOURS  OE  VAIID STABILITY OBSERVATIONS                                        2201 TOTAI  HOURS  OF STABILITY CLASS C                                                     1"29 TOTAI  HOURS  OF VAI,ID WIND DIRECTION.hIIND SPEED-STABILITY CLASS C                   L29 TOTA], HOURS  OF VA"LID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS              22OL TOTAI  HOURS  CAI,M                                                                       O METEOROLOGICAI EACILITY: WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BEThIEEN 9.51 AND 45.63 METERS WIND SPEED AI{D DIRECTION MEASURED AT       9.12 I'BTER LEVEL DATE PRINTED: 20L3/Ll/ L2 MEAN WIND  SPEED: 4.13 NOTE:   TOTAI,S A}TD SUBTOTAIS ARE OBTAINED TROM UNROUNDED NT]MBERS E1-48

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY !{IND DIRECTION EOR STABILITY CLASS D (-1.5< DELTA T(:-0.5 C/100 M) WATTS BAR NUCLEAR PLANT JUL 1-, 2OL3 - SEP 30, 20L3 WIND WIND SPEED (MPH) DIRECTION 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 ):24.5 TOTAL N 0. 000 0.09L 0.772 1 .353 0. 909 0.L82 0. 000 0. 000 0. 000 3.3r_7 NNE 0. 000 0.000 0.545 1 .04s 0. 909 0.500 0. 000 0. 000 0.000 2.999 NE 0. 000 0.045 0. 954 0 . 909 a.273 0. 000 0. 000 0.000 0.000 2.t81 ENE 0. 000 0.045 1.22-l 0 .954 0.000 0. 000 0. 000 0.000 0.000 2.226 E 0.000 0.000 1. r-36 0 . 318 0.000 0.000 0. 000 0. 000 0.000 1. 454 ESE 0. 000 0.136 L.227 0 .091 0. 000 0.000 0. 000 0. 000 0. 000 1.454 SE 0. 000 o.227 0.591 0 .045 0. 000 0. 000 0. 000 0. 000 0. 000 0.863 SSE 0. 000 0.409 1.363 .045 o. 000 0. 000 0.000 0.000 0.000 1.817 S 0.000 0.31-8 2.L35 .500 0.091- 0.045 0. 000 0. 000 0. 000 3.090 SSW 0. 000 o .22't 2 .635 .454 0.045 0.000 0. 000 0.000 0. 000 4 .362 SW 0. 000 0.409 l-.817 .22't 0.091 0. 000 .000 0.000 0.000 2.544 WSW 0. 000 0.091_ o.772 .221 0. 000 0.000 . 000 0. 000 0.000 1.090 W 0. 000 0.045 0.454 .273 0. 000 0. 000 .000 0. 000 0.000 0 .772 WNW 0. 000 o .227 0.454 .LBz o -227 0.045 .000 o. 000 0.000 1.136 NW 0. 000 0. 136 0.227 .273 O.LB2 0.000 .000 0.000 0.000 0.81-8 NNW 0. 000 0. 091 0. 818 .863 0.221 0. 000 .000 0. 000 0.000 1. 999 SUBTOTAI 0.000 2.499 L7.L29 .7 69 2.953 0.712 0.000 0. 000 0.000 32.t22 TOTAI HOURS OF VALID STABILITY OBSERVATIONS 22OI TOTAL HOURS OF STABILITY CI.ASS D 7O7 TOTAL HOURS OF VAIID WIND DIRECTION-WIND SPEED-STABILITY CI"ASS D 707 TOTAL HOURS OT VAIID WIND DIRECTION_WIND SPEED.STABILITY OBSERVATIONS 22AL TOTAI HOURS CALM O METEOROLOGICAI FACILITY: IIIATTS BAR NUCLEAR PI"ANT STABILITY BASED ON DELTA-T BETWEEN 9.5]. AI'ID 45.53 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 I"'ETER LEVEL DATE PRINTED : 20L3/LL/ 12 MEAN WIND SPEED : 3.35 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED TROM UNROUNDED NUMBERS E1-49

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS E (-0.5< DELTA T(= L.5 C/ 100 M) WATTS BAR NUCLEAR PLANT JUL 1., 20L3 - SEP 30, 20L3 WIND WIND SPEED (MPH) DIRECTION 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 1.5-L2.4 12 . 5-1,8 . 4 l8 .5-24 .4 ):24 .5 TOTAL N 0.003 0.22't 0.454 0. 636 o.L82 0.045 0. 000 0. 000 0.000 1. s48 NNE 0.002 0.227 0.22'7 0.318 0. 136 0. 000 o. 000 0. 000 0.000 0. 91_1 NE 0.003 0.t82 0.500 o.L82 0. 045 0. 000 0.000 0. 000 0.000 0.9L2 ENE 0.004 0. 136 0.727 0.273 0. 091 0. 000 0.000 0. 000 0.000 L.23L E 0.003 0.363 0. 363 0-045 0. 000 0. 000 0.000 0. 000 0.000 0.77 6 ESE 0.003 0.227 0.363 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0. 593 SE 0.002 0.L82 0. 363 0.000 0. 000 0. 000 0. 000 0. 000 0.000 0.548 SSE 0.006 0. s45 o.772 0. 000 0. 000 0.000 0. 000 0. 000 0. 000 L.324 S 0.016 1.318 2 .18L 0. r.36 0. 000 0.000 0. 000 0. 000 0. 000 3. 651 SSW o.o23 1.045 3. 953 0.091- 0.000 0.000 0. 000 0.000 0.000 5.111-sw 0.01_6 1.545 1. 908 0.045 0.000 0.000 0. 000 0.000 0.000 3.514 wsw 0. 015 1. 636 1. 681 0. 000 0. 000 0.000 0. 000 0. 000 0. 000 3 .332 w 0.014 1. 681 1.408 0.045 0. 000 0.000 0. 000 0.000 0. 000 3. 14 9 r{Nw 0.01 4 L-499 1.636 0.227 0. 045 0.000 0. 000 0.000 0.000 3.422 NW 0. 006 0 .772 0. 636 0. 000 0. 000 0.000 0. 000 0. 000 0. 000 1. 4 15 NNW 0.005 0.227 0.8r-8 0.772 o.227 0.091 0. 000 0. 000 0. 000 2.140 SUBTOTAL 0. 136 11.813 L7.992 2.77L 0.727 0.136 0.000 0. 000 0. 000 33.576 TOTAI HOURS OF VALID STABILTTY OBSERVATIONS 220t TOTAL HOURS OF STABILITY CLASS E "t39

                                                                                            -739 TOTAI HOURS OF VAIID !{IND DIRECTION-WIND SPEED_STABILITY CLASS E TOTAL HOURS OF VAIID WIND DIRECTION-VOIND SPEED-STABILITY OBSERVATIONS                  220L TOTAI HOURS CATM                                                                             3 METEOROLOGICAL   FACILITY: V{ATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.51 A}ID 45.63 METERS WIND SPEED AI.ID DIRECTION MEASURED AT        9.72 METER LEVEL DATE PRINTED  : 20]-3/LT/ t2 MEAN WIND SPEED   :  2.08 TOTAIS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED           NUMBERS E1-50

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JOINT PERCENTAGE TREQUENCIES OF WIND SPEED BY WIND DIRECTION EOR STABILITY CLASS F ( 1.5< DELTA T(= 4.O C/ 100 M) WATTS BAR NUCLEAR PLANT JUL L, 2OL3 - SEP 30, 201-3 WIND WIND SPEED (MPH) DIRECTION 0. 6-1. 4 1. 5-3.4 3. 5-5. 4 5. 5-7 .4 7 .5-t2.4 12. 5-18.4 L8 .5-24 .4 )=24 .5 TOTAI N 0. 003 0. l-36 0.409 0. 000 0.000 0.000 0. 000 0. 000 0.000 0. s48 NNE 0.001 0.045 0.091 0. 000 0. 000 0.000 0. 000 0. 000 0.000 0. l-37 NE 0 - 000 0.045 0.045 o. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0. 091 ENE 0. 001- 0.091 0. 091 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 0. 183 E 0.000 0. 000 0.091 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0.091 ESE 0.000 0.000 0. 000 0. 000 0.000 0. 000 0. 000 0. 000 0.000 0.000 SE 0. 00r 0 .L82 0.000 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 0. 183 SSE 0.001 0.045 0.091 0.000 0. 000 0.000 0.000 0. 000 0.000 o. 137 S 0.003 0.363 0.22-t 0.000 0. 000 0.000 o. 000 0. 000 0.000 0.594 SSW 0. 004 0.31_8 0.409 0. 000 0.000 0.000 0. 000 0. 000 0.000 0.731 SW 0. 007 0.727 0. 636 0. 000 0.000 0.000 0. 000 0. 000 0.000 1.370 wsw 0.01_l_ 1-.545 0.545 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 2.LoL w 0.019 2.590 1.045 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 3. 6s4 wNw 0.018 2.453 1.045 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 3.517 NW 0.017 L.499 t_. 681 0. 045 0. 000 0. 000 0.000 0.000 0. 000 3.243 NNW 0. 004 0. r_82 0.591 0.045 0.045 0. 000 0. 000 0. 000 0.000 0.857 SUBTOTAI 0.091 L0.223 6.997 0.091 0.045 0. 000 0. 000 o. 000 0.000 17.447 TOTAL HOURS OF VA],ID STABILITY OBSERVATIONS 220]^ TOTAL HOURS OF STABILITY CTASS F 384 TOTAI HOURS OF VAIID WIND DIRECTION-WIND SPEED-STABILITY CLASS T 384 TOTAI, HOURS OF VA],ID WIND DIRECTION-ViIND SPEED-STABILITY OBSERVATIONS 22OI TOTAI HOURS CALM 2 METEOROLOGICAI TACILITY: WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BET!{EEN 9.5]- AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 IfiTER LEVEL DATE PRINTED: 2013/LL/12 MEAN WIND SPEED : 1.45 NOTE: TOTAI,S AND SUBTOTAIS ARE OBTAINED FROM UNROUNDED NUMBERS E1-51

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS G (DELTA T > 4.0 C/ 100 M) WATTS BAR NUCLEAR PLANT JUL L, 2013 SEP 30, 20!3 WIND WIND SPEED (MPH) DIRECTION 0. 6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 ):24 -5 TOTAI N 0. 000 0. 000 0.000 0.000 0. 000 0. 000 0.000 0.000 0. 000 0. 000 NNE 0. 000 0. 000 0.000 0.000 0. 000 0. 000 0.000 0.000 0. 000 0. 000 NE 0. 000 0. 000 0.000 0.000 0. 000 0.000 0.000 0. 000 0.000 0- 000 ENE 0. 000 0. 000 0.000 0.000 0. 000 0. 000 0.000 0. 000 0.000 0.000 E 0. 000 0.000 0.000 0.000 0.000 0. 000 0.000 0.000 0.000 0.000 ESE 0. 000 0.045 0.000 0.000 0.000 0.000 0.000 0. 000 0.000 0. 045 SE 0. 000 0. 000 o.000 0.000 0.000 0.000 0. 000 0. 000 0.o0o 0-000 SSE 0. 000 0.000 0.000 0.000 0. 000 0. 000 0.000 0. 000 0.000 0.000 S 0. 000 0.045 0.000 0.000 0. 000 0.000 0. 000 0. 000 0.000 0.045 SSW 0. 000 0.000 0.091 0.000 0. 000 0.000 0.000 0. 000 0.000 0. 091 SW 0. 000 0. 182 0. 045 0.000 0. 000 0. 000 0.000 0. 000 0.000 0.227 wsw 0. 000 4.273 0. 091 0.045 0.000 0.000 0.000 0. 000 0.000 0.409 w 0.000 o -772 0.273 0.000 0. 000 0.000 0.000 0. 000 0.000 1.045 hINW 0. 000 0.727 0. 318 0. 000 0. 000 0.000 0.000 0. 000 0. 000 1.045 NhI 0. 000 0.818 0.727 0.000 0. 000 0. 000 0. 000 0. 000 0.000 1.545 NNhI 0. 000 0. 136 0. 136 0. 000 0. 000 0.000 0. 000 0. 000 0.000 0.273 SUBTOTAL 0. 000 2.999 1. 681_ 0. 045 0. 000 0.000 0.000 0. 000 0. 000 4.725 TOTAI HOURS OF VALID STABILITY OBSERVATIONS 220L TOTAL HOURS OF STABILITY CLASS G 104 TOTAL HOURS OF VALTD WIND DIRECTION-WIND SPEED-STABTLITY CLASS G 104 TOTAL HOURS OF VALID WTND DIRECTION.WIND SPEED.STABILITY OBSERVATlONS 22At TOTAL HOURS CALM o METEOROLOGICAL FACILITY: IiATTS BAR STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45. 63 METERS WIND SPEED AND DIRECTION I4EASURED AT 9.-12 I'frTER LEVEL DATE PRINTED2 2OL3/LL/L2 WIND SPEED : 1.38 TOTALS AND SUBTOTAIS ARE OBTAINED TROM UNROUNDED NUMBERS E1-52

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JOINT PERCENTAGE FREQUENCIES OE WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS A (DELTA T(:-1 .9 C/ l-00 M) WATTS BAR NUCLEAR PLANT ocr l, 2ol3 - DEC 31, 2OL3 WIND WIND SPEED (MPH) DIRECTION 0.6-1.4 1.5-3.4 3.5-5.4 5.5-'7.4 '7.5-72.4 12.5-78.4 ]-8.5-24.4 ):24.5 TOTAI N 0. 000 0. 000 0. 000 0. 136 0. 182 0.227 0. 000 0. 000 0.000 0. s45 NNE 0. 000 0.000 0. 000 0. 136 0.409 0.499 0. 000 0.000 0. 000 1".044 NE 0. 000 0. 000 0.045 0.091 0.045 0.045 0. 000 0.000 0.000 0.227 ENE 0. 000 0. 000 0.091 0.045 0.045 0.045 0. 000 0. 000 0.000 0.227 E 0. 000 0. 000 0.091 0.000 0. 000 0. 000 0. 000 0. 000 0. 000 0.091 ESE 0. 000 0. 000 0. 000 0. 000 0.000 0. 000 0. 000 0. 000 0. 000 0. 000 SE 0. 000 0.000 0.045 0.045 0. 000 0.000 0. 000 0.000 0. 000 0.091 SSE 0. 000 0. 000 0.000 0. 045 0. 000 0. 000 0. 000 0. 000 0. 000 0.045 S 0.000 0.045 0.045 0.409 0.091 0. 000 0. 000 0. 000 0. 000 .590 SSW 0. 000 0. 000 0.045 0.545 0.590 0. 000 0.000 0. 000 0. 000 .180 SW 0. 000 0. 000 0.045 0.318 0. 136 0. 000 0. 000 0. 000 0. 000 .499 WSW 0. 000 0.000 0.045 0.045 0.000 0. 000 0. 000 0. 000 0.000 .091 W 0. 000 0.000 0. 000 0. 000 0.000 0.000 0. 000 0. 000 0. 000 .000 wNw 0. 000 0. 000 0.000 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 .000 NW 0. 000 0. 000 0. 000 0. 000 0.04s 0.045 0. 000 0. 000 0. 000 .091 NNW 0. 000 0. 000 0. 000 0.091 o.227 0.045 0. 000 0.000 0. 000 .363 SUBTOTAI 0. 000 0.045 0.454 1.905 L.770 0. 908 0.000 0.000 0. 000 5.084 TOTAL HOURS OF VALTD STABILITY OBSERVATIONS 2203 TOTAL HOURS OT STABILITY CI,ASS A LL2 TOTAL HOURS OF VAIID WIND DIRECTION-WIND SPEED-STABILITY CTASS A IL2 TOTAT HOURS OF VALID 9{IND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2203 TOTAI HOURS CALM O METEOROLOGICAL EACILITY: WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 I{ETERS V{IND SPEED AND DIRECTION MEASURED AT 9 -72 I"lEfER LEVEL DATE PRINTEDz 2Ol4/02/26 MEAN WIND SPEED: 5.66 NOTE: TOTALS A}TD SUBTOTAI,S ARE OBTAINED EROM UNROUNDED NUMBERS E1-53

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JOINT PERCENTAGE EREOUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS B (-1.9< DELTA T(:-L.7 C/ 100 M) WATTS BAR NUCLEAR PLANT ocT l, 2oL3 - DEC 31, 2AL3 WIND WIND SPEED (MPH) DIRECTION 0. 6-1.4 1.5-3.4 3.5-5.4 s.5-7.4 -7

                                                                                  .5-L2.4    f 2.5-18.4    18 .5-24 .4     )=24.5     TOTAL N             0.000        0.000        0.045        0.227      0.t82           o.L82         0. 000        0. 000      0. 000     0.635 NNE           0. 000       0. 000       0.045        0.L82      0.318           0.499         0. 000        0. 000      0. 000     1.044 NE            0. 000       0.000        0.09r-        0.L82     0.045           0. 000        0. 000        0.000       0. 000     0.31"8 ENE           0. 000       0. 000       0.091         0. 091_   0.000           0. 000        0. 000        o. 000      0. 000     0. 182 E             o. 000       0. 000       0.045         0.000     0.000           0. 000        0. 000        0. 000      0. 000     0.045 ESE           0. 000       0.000        0. 000        0.091     0.000           0. 000        0. 000        0. 000      0. 000     0.091 SE            0. 000       0. 000       0. 000        0. 000    0. 000          0. 000        0. 000        0. 000      0. 000     0. 000 SSE           0. 000       0.000        0.045         0.000     0.045           0. 000        0. 000        0. 000      0. 000     0.09L S             0. 000       0. 000       0. 045        0.045     0.000           0. 000        0. 000        0. 000      0. 000     0. 091" ssw           0. 000       0.000        0. 000        0.681     0.000           0. 000        0. 000        0. 000      0. 000     0 . 681-SW            0. 000       0. 000       0. 000        0. s45    0.000           0. 000        0. 000        0. 000      0. 000       - 545 wsw           0. 000       0. o0o       0.045         0.000     0.000           0. 000        0. 000        0. 000      0. 000       .045 W             0.000        0. 000       0. 000        0.045     0.000           0. 000        0. 000        0. 000      0. 000       .045 WNW           0. 000       0. 000       0. 000        0.000     0.000           0. 000        0. 000        0. 000      0. 000       - 000 NW            0. 000       o. 000       0. 000        0.000     0.045           0.045         0. 000        0. 000      0.000        .091 NNW           0. 000       0. 000       0. 000        0. 182    0. 136          0.091         0. 000        0. 000      0.000        .409 SUBTOTAL          0.000        0. 000       0.454         2.270     0.172           0.817         0.000         0.000       0. 000     4.3t2 TOTAI HOURS OF VALID STABILITY OBSERVATIONS                                               2203 TOTAL HOURS OE STABILITY CTASS B                                                             95 TOTAI HOURS OF VAIID WIND DIRECTION_WIND SPEED-STABILITY CLASS B                             95 TOTAL HOURS OE VAIID WIND DIRECTION.WIND SPEED.STABILITY OBSERVATIONS                     2203 TOTAL HOURS CALM                                                                              0 METEOROLOGTCAL   FACILITY: WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.51 A}ID 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT         9.72 IfiTER LEVEL DATE PRINTEDi 2014/02/26 WIND SPEED  :  5.44 TOTAIS A}TD SUBTOTALS ARE OBTAINED FROM UNROUNDED      NUMBERS E1-54

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JOINT PERCENTAGE FREQUENCIES OE WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS C (-1.7< DELTA T<:_]-.5 C/].OO M) WATTS BAR NUCLEAR PI,ANT ocr t, 2073 - DEc 31, 2013 WIND WIND SPEED (MPH) DIRECTION 0.5-1.4 l_.5-3.4 3.5-5.4 5.5-7.4 7.5-L2.4 12.5-18.4 t8.5-24.4 ):24.5 TOTAL N 0.000 0. 000 0.045 0.045 0. 136 0.272 0. 000 0. 000 0.000 0.499 NNE 0. 000 0. 000 o.L82 o.272 0.227 o.t1z 0. 000 0. 000 0.000 0.862 NE 0. 000 0. 000 0. l_82 0. 136 0.045 0.000 0. 000 0. 000 0.000 0.363 ENE 0.000 0. 000 0.045 0. 136 0. 000 0. 000 0. 000 0. 000 0.000 0,182 E 0. 000 0. 000 0.091- 0. 000 0. 000 0. 000 0.000 0. 000 0.000 0. 091-ESE 0. 000 0.000 0.045 0. 000 0.000 0. 000 0. 000 0. 000 0.000 0. 045 SE 0. 000 0.000 0.045 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 0.045 SSE 0. 000 0. 000 0.045 0. l-36 0. 000 0. 000 0. 000 0. 000 0. 000 0. 182 S 0. 000 0. 000 0.045 0.272 0.091 0.045 0. 000 0. 000 0.000 0.454 SSW 0. 000 0. 000 0.091 0.68r_ 0.091 0.045 0. 000 0. 000 0.000 0. 908 st{ 0. 000 0. 000 0.09r_ 0.363 0.000 0.000 0. 000 0. 000 0.000 0.4s4 wsw 0. 000 0. 000 0. 000 0. 136 0.000 0.000 0. 000 0.000 0.000 0. 136 w 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 0. 000 0. 000 0.000 0. 000 wNw 0.000 0. 000 0.000 0. 000 0. 000 0. 136 0. 000 0. 000 0.000 0. 136 NhI 0. 000 0. 000 0. 000 0.045 0. 000 0.091 0. 000 0. 000 0.000 0. 136 NNW 0. 000 0. 000 0.045 0. 000 0.045 o.L82 0. 000 0. 000 0. 000 0 .272 SUBTOTAL 0.000 0.000 0.953 2.224 0. 535 0-953 0. 000 0.000 0.000 4.765 TOTAT HOURS OF VALID STABILITY OBSERVATIONS 2203 TOTAL HOURS OT STABILITY CLASS C 1"05 TOTAL HOURS OT'VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS C r-05 TOTAI HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2203 TOTAL HOURS CALM 0 METEOROLOGICAI FACILITY: WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.51 AI{D 45.53 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 l"frTER LEVEL DATE PRINTEDz 2OL4/02/26 MEAN WIND SPEED: 5.18 NOTE: TOTALS A}iD SUBTOTAI,S ARE OBTAINED FROM UNROUNDED NUMBERS E1-55

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT

                                     .JOINT PERCENTAGE FREQUENCIES OF IIIND SPEED BY NIND DIRECTION FOR SIASILITY CI,ASS D          (-1.5< DELTA   T<=-0.5 C,/100 M)

WATTS BAR NUCI,EAR PI,AT{T ocr 1, 2013 - DEC 31, 2013 WIND WIND SPEED(UPH) DIRECTION 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 't.5-12.4 12.5-18.4 1A.5-24.4 >=24.5 TOTAI N 0. 000 0.091 0.817 1.089 0. 999 2.L33 0.091 0. 000 0-000 5.220 NNE 0. 000 0. 091 0.908 1. 135 0. 908 7.271" 0. 000 0. 000 0-000 4.372 NE 0. 000 0. 000 0.772 0. 999 a.227 0. 000 0. 000 0. 000 0.000 t.997 ENE 0. 000 .091 0.681 0. 635 0. 000 0. 000 0. 000 0. 000 0.000 1.407 E 0. 000 .045 0.454 0. 000 0. 000 0.000 0. 000 0.000 0.000 0. 4 99 ESE 0. 000 .091 0.272 0.045 0. 000 0.000 0. 000 0.000 0.000 0.409 SE 0. 000 .L82 0. 136 0. 000 0. 000 0. 000 0. 000 0. 000 0. o0o 0.318 SSE 0. 000 .227 o.227 0.045 0. 000 0. 000 0. 000 0. 000 0.000 0.499 S 0. 000 .045 1. 180 0.499 0. 136 o.227 0.091 0. 000 0.000 2.179 SSW 0. 000 0. 000 1.498 --a-;725 0.318 o.227 0. 000 0. 000 0.000 3.768 SW 0. 000 0.045 t.770 0. 953 0.091 0.091 0. 000 0. 000 0.000 2.95L WSW 0. 000 0. 136 0. 953 0. t-36 0.045 0. o0o 0. 000 0. 000 0.000 t.27L W 0.000 0. 136 0. 635 a.L82 0. 000 0.045 0. 000 0. 000 0. 000 0. 999 WNW 0.000 0. 091 0.363 O.TB2 0.590 0.409 0. 000 0. 000 0.000 L.634 NW 0. 000 0.227 0. 635 0.227 0.454 0. 953 0. 000 0. 000 0.000 2.497 NNW 0.000 0.091 0.726 0.590 1.089 1. 634 0. 000 0. 000 0.000 4. 131 SUBTOTAI, 0. 000 1.58 9 L2.029 8.443 4.857 6. 990 0. 182 0. 000 0.000 34.090 TOTAI HOURS OF VAIID STABILITY OBSERVATIONS 2203 TOTAL HOURS OF STABILITY CLASS D 751 TOTAL HOURS OT VATID hIIND DIRECTION-WIND SPEED-STABILITY CLASS D 751 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2203 TOTA], HOURS CALM 0 METEOROLOGICAL EACILITY: WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.51 AI{D 45.63 T{ETERS WIND SPEED AND DIRECTION MEASURED AT 9.72 I"IJ'TER LEVEL DATE PRTNTED: 2OL4/02/26 MEAN WIND SPEED : 4.85 TOTALS AND SUBTOTAI,S ARE OBTAINED FROM UNROUNDED NU}AERS E1-56

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JOINT PERCENTAGE TREQUENCIES OE hIIND SPEED BY WIND DIRECTION FOR STABILITY CLASS E (-0.5< DELTA T(: 1.5 C/1OO M) WATTS BAR NUCLEAR PLANT ocr 1-, 20L3 - DEC 31, 2OL3 lrlIND WIND SPEED (l'lPH) DIRECTION 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-L2.4 L2.5-18.4 L8.5*24.4 ):24.5 TOTAL N 0.000 0.091 0.353 0.590 0. 363 0.045 0. 000 0.000 0.000 l_.453 NNE 0.000 0.091 0.318 0. 136 0.091 0.045 0. 000 0. 000 0.000 0.681-NE 0. 000 0. r_36 0.363 o.227 0. 000 0. 000 0. 000 0. 000 0. 000 4.726 ENE 0.000 0.045 0.545 o.t82 0. 000 0. 000 0. 000 0. 000 0. 000 0 .7'72 E 0. 000 0.09r. 0.091 0. 000 0.000 0. 000 0.000 0. 000 0.000 0 -182 ESE 0. 000 o.t82 0.L82 0. 000 0. 000 0. 000 0.000 0. 000 0. 000 0.363 SE 0. 000 0. t-36 0. 000 0. 000 0.000 0. 000 0.000 0. 000 0.000 0. t-36 SSE 0.000 o -227 0. 318 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 0.545 S 0. 000 0.31"8 1.089 0.272 0.091 0.454 0. 135 0. 000 0. 000 2.360 SSW 0. 000 o.772 2.224 1. 180 0.091 0.091 0. 000 0.000 0.000 4 .358 SW 0. 000 0.908 0. 999 0.409 0. 000 0. 000 0. 000 0. 000 0.000 2.3L5 WSW 0. 000 0.772 1. 135 0.091 0.000 0. 000 0. 000 0. 000 0.000 L.997 ri 0.000 0.862 0.772 0.091 0.000 0. 000 0. 000 0. 000 0.000 L.725 wNw 0.000 1.r-35 0.817 0.454 0.091 0. 000 0. 000 0. 000 0. 000 2.497 NW 0.000 0.318 0. 635 o -272 o.182 0.045 0. 000 0. 000 0.000 1.453 NNW 0.000 0.363 0.499 1. 180 0.590 o.2'72 o. 000 0. 000 0.000 2.905 SUBTOTAL 0. 000 6.446 10.350 5.084 1.498 0. 953 0. 136 0. 000 0.000 24 .467 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2203 TOTAL HOURS OE STABILITY CI,ASS E 539 TOTAI HOURS OT VALID WIND DIRECTION-WIND SPEED-STABILITY CI,ASS E 539 TOTAI HOURS OF VA],ID WIND DIRECTION-WIND SPEED.STABILITY OBSERVATIONS 2203 TOTAI HOURS CALM O METEOROLOGICAL EACILITY: WATTS BAR NUCLEAR PLANT STABILITY B.LSED ON DELTA-T BETWEEN 9.51 AI{D 45.63 METERS WIND SPEED AND DTRECTION MEASURED AT 9.-12 I"'ETER LEVEL DATE PRINTED: 2AL4/02/26 MEAN WIND SPEED : 2.96 NOTE: TOTAI,S AND SUBTOTAIS ARE OBTAINED FROM UNROUNDED NUMBERS E1-57

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JOINT PERCENTAGE EREQUENCIES OE WIND SPEED BY WIND DIRECTION STABILITYCLASSF (1.5< DELTA T(: 4.O C/ 100 M) WATTS BAR NUCLEAR PLANT ocr L, 20L3 - DEC 31, 2013 t,IIND WIND SPEED (MPH) DIRECTION 0. 6-1.4 1. s-3.4 3.5-5.4 5.5-7.4 N o. 000 0.045 0. 182 0.000 0.000 0. 000 0. 000 0. 000 0.000 0.227 NNE 0. 000 0.136 0.091 0.000 0.000 0-000 0. 000 0. 000 0 - 000 0.227 NE 0. 000 0.091 0. 136 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 0.22'7 ENE 0. 000 0.091 o. 182 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0 .272 E 0. 000 0.091- 0.091 0.000 0. 000 0. 000 0-000 0.000 0. 000 0. 1"82 ESE 0. 000 o.L82 0. 000 0.000 0.000 0.000 0. 000 0. 000 0.000 0. 182 SE 0. 000 0. 000 0. 000 0.000 0.000 0.000 0. 000 0. 000 0.000 0.000 SSE 0. 000 0. 000 0.091 0.000 0.000 0.000 0. 000 0. 000 0.000 0.091 s 0.000 . L82 0.091 0.000 0.000 0.000 0. 000 0. 000 0.000 0.272 ssw 0.000 .227 0.227 0.000 0.000 0. 000 0. 000 0.000 0.000 0. 454 SW 0. 000 .782 0.318 0.000 0.000 o. 000 0. 000 0. 000 0.000 0. 4 99 wsw 0. 000 .999 0.862 0.000 0.000 0. 000 0. 000 0. 000 0.000 1. 851 v{ 0. 000 .360 1.180 0.000 0.000 0. 000 0. 000 0. 000 0.000 3.541_ wNw 0. 000 .224 2.270 0.045 0. 000 0. 000 0.000 0.000 0.000 4.539 NVC 0. 000 .543 t.27L 0.045 0. 000 0. 000 0. 000 0. 000 0.000 2.860 NNW 0.000 .182 O.LBz 0.045 0.000 0. 000 0. 000 0. 000 0. 000 0.409 SUBTOTAI 0-000 8.534 7.t72 0. r.36 0. 000 0^000 0. 000 0. 000 0.000 t5.842 TOTAI, HOURS OF VAIID STABILITY OBSERVATIONS 2203 TOTAI, HOURS OF STABILITY CLASS F 349 TOTAI HOURS OF VAIID WIND DIRECTION-WIND SPEED-STABILITY CLASS F 349 TOTAI HOURS OF VAIID WIND DIRECTION-WTND SPEED-STABILITY OBSERVATIONS 2203 TOTAI HOURS CALM 0 METEOROLOGICAL FACILITY: WATTS BAR NUCLEAR PLANT STABTLITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 I"frTER LEVEL DATE PRINTEDI 2OL4/02/26 MEAN hIIND SPEED = 1.53 TOTALS A}TD SUBTOTAIS ARE OBTAINED TROM UNROUNDED NUMBERS E1-58

2013 WATTS BAR NUGLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JOINT PERCENTAGE EREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CI,ASS G (DELTA T > 4.0 C/ 1OO M) WATTS BAR NUCLEAR PLANT ocr L, 20L3 - DEC 31, 20t3 WIND WIND SPEED (MPH) DIRECTION 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 LB.5-24.4 )=24.5 TOTAI N 0. 000 0.182 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 0.t82 NNE 0. 000 0. 136 0. 000 0. 000 0. 000 0.000 0. 000 0.000 0.000 0.136 NE 0. 000 0.045 0. 000 0. 000 0. 000 0.000 0. 000 0. 000 0.000 0.045 ENE 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 0. 000 0. 000 0.000 0.000 E 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 0.000 ESE 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 0.000 SE 0. 000 0.045 0. 000 0. 000 0. 000 0.000 0. 000 0.000 0.000 0.04s SSE 0. 000 0.045 0. 000 0. 000 0. 000 0.000 0. 000 0. 000 0.000 0.045 S 0. 000 0.091 0. 000 0. 000 0. 000 0.000 0. 000 0. 000 0.000 0. 091-SSW 0. 000 0. 182 0.045 0. 000 0. 000 0. 000 0. 000 0. 000 0.000 0.227 ShI 0. 000 0. 363 0. 182 0. 000 0.000 0. 000 0. 000 0. 000 0.000 0.545 wsw 0.000 0.726 0.409 0. 000 0. 000 .000 0. 000 0. 000 0.000 1. 135 w 0. 000 1.81_6 0. 635 0. 000 0. 000 .000 0. 000 0. 000 0.000 2.45L hINW 0. 000 2.088 t.044 0. 045 0.000 .000 0. 000 0.000 0.000 3.L77 NW 0. 000 r..543 1.089 0. 000 0. 000 . 000 0. 000 0. 000 0.000 2.633 NNW 0. 000 0.545 0. 136 0.045 0. 000 .000 0. 000 0. 000 0.000 0.726 SUBTOTAI, 0. 000 7. 808 3.541 0.091 0. 000 0.000 0. 000 0. 000 0.000 r_1. 439 TOTAL HOURS OE VAIID STABILITY OBSERVATIONS 2203 TOTAI HOURS OF STABILITY CI"ASS G 252 TOTAT HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS G 252 TOTAI HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2203 TOTAI, HOURS CALM 0 METEOROLOGICAL TACILITY: WATTS BAR NUCLEAR PI"ANT STABILTTY BASED ON DELTA_T BETWEEN 9.51 AI,ID 45.63 METERS WIND SPEED AI{D DIRECTION MEASURED AT 9.72 V,E.TER LEVEL DATE PRTNTED: 2AL4/02/26 MEAII WIND SPEED : 1.33 NOTE: TOTALS A}ID SUBTOTALS ARE OBTAINED EROM UNROUNDED NUMBERS E1-59

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT ATTACHMENT 1 Deviations from ODCM Controls/Surveillance Requirements None E1-60

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT ATTACHMENT 2 Radioactive Effluent Monitoring lnstrumentation lnoperable for Greater than 30 days Essential Raw Cooling Water Effluent Monitor 0-RE-90-134 was inoperable for more than 30 days. On OBl11l2O13 at 1319 0-RE-90-134 was declared 112.1 .1 inoperable due to a sample pump mortor failure. 0-RE-90-134 was returned Control 1.1 .1 to operable status on 10/11113 at 1355. PER 767601and WO 113540074 Action B e Table 1.1-1 og/1 1tzo1" was initiated on 0-RE-90-1U to replace the sample pump on 0-RE-90-134. During the inoperable period; compensatory requirements specifted in the ltem 2. a ODCM were met for the inoperable Essential Raw Cooling Water Radiation Montior device. E1-61

2013 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT ATTACHMENT 3 Offsite Dose Calculation Manual Revision 23 (no revisions in 2013) El-62

WATTS BAR NUCLEAR PLANT OFFSITE DOSE GALCULATTON MANUAL (ODCM) Revision 23 Prepared by: Eddie Woods Date: 0112612010 Chemistry Submitted By: Darrin Hutchison Date: 0112812010 Approved By: Adam Scales Date: 0210?/2010 PORC Chairman PORC Meeting No. :4285 Plant Manager: Greg Boerschig Effective Dat e: 021 121201 0

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 2 of 195 REVISION LOG Page 1 of 1 REVISION EFFECTIVI AFFECTED NUMBER DATE PAGES DESCRIPTION OF REVISION Rev 16 08/1 9/0s 1,2, 64, 65, Revised description of liquid effluent release paths in Section 6.0 98 and Figure 6.1 to implement EDC-51879. The EDC allows for releases to be made from the Condensate Demineralizer or Steam Generator Blowdown without a minimum CTBD flow of 20,000 gpm provided the sum of the ratios of the ECLs for all release points is < 10. Rev 17 05t48/2006 1,2, 1 0, 95, Corrected typo's and discrepancies identified in the WBN/SQN 1 05, ODCM difference matrix project. Added a note to clarify the 114,1 15, calibration of 1-FlT-1 542. 117, 121 ,122, 150, 152, 154,169 Rev 18 08/18/2006 1, 2, 38, 167, Revised sample location wording in Table 2.3-1 for the fish 169, 172 exposure pathway. Added additional sample location for fish in Table 9.1 and Table 9.2. Added point 37 to sample map in Table 9.2 to reflect additional fish location. Rev 19 02t01t2007 1, 2, 4, 21 , 39, Added the Groundwater Sump (GWS) as a liquid release path and 65,1 18, 164, associated analyses and sampling frequency. Replaced all 170,193 references to Thermoluminescent Dosimeters (TLD's) with dosimeter since Western Area Radiological Laboratory vendor uses laser etched dosimeters versus TLD's. Rev 20 09107 t2007 1,2, 41 , 107- Removed the non-drinking water limit of 30,000 pCi/L tritium found 109, 112, in groundwater to be consistent with the NEI Groundwater 132,135-143 Protection Initiative Program. Updated 26lQ, D/Q, and the joint frequency distribution tables for the period from January 1986 to December 2005. Rev 21 01t22t2008 1,2, 15,67 , Clarified Action L on page 15. Revised gaseous setpoint table to be 68, 103, 104, consistent with liquid setpoint table. Added wording to allow 0-RE-169, 170, 90-1 22 setpoint to be set at a default value. Corected reference in 172, 173 gaseous setpoint table and clarified wording for 0-RE-90-1 18 setpoint. Removed dairy farm that is no longer in operation from Table 9.2. Removed an extra control location for environmental dosimeters from Table 9.3. Update Figures 9.2 and 9.3 to reflect the chanses in Table 9.2 and 9.3. Rev 22 0511112009 1,2,61 ,169, Added statement to include results from non-REMP well samples, 171 any onsite spill or leaks and their assigned doses that occurred during the reporting period in the radioactive effluent release report. Replaced Well D in the REMP with Well F. Updated Figure 9.1 to reflect location of Well F (map location #85). Rev 23 02t12t2010 1,2, 4, 43 Added Table 2.34 Detection Capabilities for Groundwater Hard-to-Detect Nuclides (LLD).

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 3 of {95 TABLE OF CONTENTS (Page 1 of2) 't.0t2.0 - coNTRoLS AND SURVEILI-ANCE REQUlREMENTS............... ........................6 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION............... ........,....,,,,,7 112,1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION............... ...,,,...,12 1t2.1.3 METEOROLOGICAL TNSTRUMENTATTON/DATA..... ...................18 'U2.2.',t.3 LtQUtD RADWASTE TREATMENT SYSTEM ............................25 112.2.2.3 DOSE - I.131, I-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM WTH HALF-LIVES 112.2.2.4 GASEOUS RADWASTE TREATMENT ................32 1/2.3 RADTOLOGICAL ENVTRONMENTAL MONITORING .......................34 II2.3.3 lNTERLABORATORY COMPARTSON PROGRAM .......................45 9.0 - RADTOLOGTCAL ENVIRONMENTAL MONTTORTNG PROGRAM (REMP)......... ........................162 11.0 SOURCE NOTES ................175 AppENDtXA - NOTATTON CONVENTlONS................. ..........................178 Lrsr or AcnoruyMs............... ..................... 183 Lrsr or Uxrs............. .........1U APPENDIX B - DEVIATIONS IN THE \A'BN ODCM CONTROLS/SURVEILLANCE REQUIREMENTS FROM THOSE GlVEN rN NUREG-1301.................. .....185 APPENDIX C - WBN ODCM REVISION PROCESS... ... 187 E1-65

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 4 of 195 TABLE OF CONTENTS (Page 2 of 2) LIST OF TABLES'FIGURES TABLES 1.1-1 . RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ............. 8 2.1-,I - MDIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION - SURVEILLANCE REQUIREMENTS...... 10 1.1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION............ 13 2.1.2. RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION. SURVEILI.ANCE REQUIREMENTS...... 16 1.1 METEOROLOGICAL MONITORING INSTRUMENTATION... 19 2.2-1 . RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM 21 2.2 RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGMM 27 2.3.1- MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM... 36 2.3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES... 41 2.3.3. DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS - 11D........... 42 2.34 - DETECTION CAPABILITIES FOR GROUNDWATER HARD-TO-NUCLIDES . LLD........... .. 43 3.1 - FREQUENCY NOTATrON............ 57 3.2. OPEMTIONAL MODES... 58 6.1 - RECEPTORS FOR LIQUID DOSE CALCUI.ATIONS...... 81 6.2 - RADIONUCLIDE DECAYAND STABLE ELEMENT TRANSFER DATA........... 82 6.3 - DOSE CALCULATION FACTORS. 85 6.4.INGESTION DOSE FACTORS... 87 6.5 - BIOACCUMUI.ATION FACTORS FOR FRESHWATER FISH....... 95 6.6 - EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND 96 7.1 .IA'BN - OFFS]TE RECEPTOR LOCATION DATA........... 135 7.2. JOINT PERCENTAGE FREQUENCIES OF WND DIRECTION AND WND SPEED FOR DIFFERENT STABILITY CLASSES 136 7.3. ADJUSTED DISPERSION FACTORS........, 143 7.4 - DOSE FACTORS FOR SUBMERSION IN NOBLE GASES........ 14 7.5 - SECTOR ELEMENTS CONSIDERED FOR POPUI.ATION DOSES... 145 7.6 - POPU!.ATION WTHIN EACH SECTOR ELEMENT. 146 7.7 - INHAI.ATION DOSE FACTORS.... 147 9.1 - REMP. MONITORING, SAMPLING, AND ANALYSIS...... 1U 9.2 - REMP - SAMPLING LOCATIONS. 168 9.3 - REMP. DOSIMETRY LOCATIONS. 169 FIGURES 3.1 - \A'BN SITE AREA MAP... 59 6.1 - LIQUID EFFLUENT RELEASE POINTS... 98 6.2 - LIQUID RADWASTE SYSTEM... 99 6.3. STEAM GENERATOR BLOWDO\AN/CONDENSATE DEMINERALIZER...... 1OO 7.1 . GASEOUS EFFLUENT RELEASE/DISCHARGE POINTS... 155 7.2 - DETAIL OF GASEOUS RELEASE/DISCHARGE POINTS... 156 7.3 - GASEOUS RADWASTE TREATMENT SYSTEM. 157 7.4. PLUME DEPLETION EFFECT FOR GROUND LEVEL RELEASES... 158 7.5 - VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME 159 7.6 - REI.ATIVE DEPOSITION FOR GROUND LEVEL RELEASES... 160 9.1 - REMP LOCATIONS WTHIN ONE MILE OF THE PLANT...... 17O 9.2. REMP LOCATIONS FROM ONE TO FIVE MILES FROM THE PLANT.. 171 9.3. REMP LOCATIONS GREATER THAN FIVE MILES FROM THE PI-ANT.. 172 E1-66

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 5 of {95 l.O INTRODUCTION The Watts Bar Nuclear Plant (WBN) Offsite Dose Calculation Manual (ODCM) is a supporting document of the WBN Technical Specifications (TS) required by WBN TS 5.7.2.3. The ODCM is divided into two major parts: Controls (Sections 1 through 5) and program description(Sections 6 through 9). References are given in each section as applicable and are further described in Section 10.0. The first part of the ODCM (Sections 1 through 5) contains:

   '1) Radioactive Effluent Controls required by Section 5.7.2.7 of the VVBN TS;

2) Radiological Environmental Monitoring Controls required by 10 CFR Part 50, Appendix l, Section lV.B;

3) Controls for Meteorclogical Monitoring lnstrumentation;

4) Descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by WBN Technical Specifications 5.9.2 and 5.9.3; and

5) Administrative Controls for the ODCM requirements.

These sections of the document have been prepared using the guidance provided in NUREG-1301 (Reference 1) and draft Nuclear Regulatory Commission Generic Letter (Reference 2). Exceptions to this guidance have been documented in Appendix B to the ODCM. The second part of the ODCM (Sections 6 through 9) contains the methodologies and parameters used to:

1) Calculate offsite doses resulting from radioactive gaseous and liquid effluents;

2) Calculate gaseous and liquid effluent monitor Alarm/Trip setpoints; and,

3) Conduct the Radiological Environmental Monitoring Program (REMP).

These methodologies and parameters were developed using the guidance in NUREG-0133 (Reference 3); Regulatory Guide 1.109 (Reference 4); Regulatory Guide 1.1'1'1 (Reference 5); Regulatory Guide 1.113 (Reference 6); Regulatory Guide 1.21 (Reference 7); and RadiologicalAssessment Branch Technical Position on Environmental Monitoring (Reference 8). \Mrere any methodology or parameter differs from the guidance provided in the above documents, it has been documented in the text and references given for the source of the information. E1-67

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 6 of 195 1.OI2,O . CONTROLS AND SURVEILLANCE REQUIREMENTS 1'2.0 APPLICABILITY CONTROLS 1.0.1 Controls shall be met during the MODES or other specified conditions in the Applicability, except as provided in Control 1.0.2. 1.0.2 Upon discovery of a failure to meet a Control, the Action(s) of the associated Conditions shall be met. lf the Control is met or is no longer applicable prior to expiration of the Action(s), completion of the Action(s) is not required unless othenrvise stated. SURVEI LI.ANCE REQU IREMENTS 2.0.1 Surveillance Requirements (SR) shall be met during MODES or other conditions in the Applicability for individual Controls, unless othenarise stated in the SR. Failure to meet the Control occurs when a surveillance is failed or when conditions occur between surveillances that would result in a failed surveillance if testing was performed. Failure to perform a surveillance within the specified frequency shall be failure to meet the Control except as provided in SR 2.0.3. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits. 2.0.2The specified frequency for each SR is met if the surveillance is performed within 1.25 times the interval specified in the frequency, as measured from the previous performance or as measured from a time a specified condition of the frequency is met. For frequencies specified as "once," the above interval extension does not apply. lf an Action requires periodic performance on a "once per..." basis, the above frequency extension applies to each performance afrer the initial performance. Exceptions to this SR control section are stated in the individual SRs. 2.0.3 lf it is discovered that a surveillance was not performed within its specified frequency, then compliance with the requirement to declare the Control not met may be delayed, from the time of discovery, up to 24 hours or up to the limit of the specified frequency, whichever is less. This delay period is permitted to allow performance of the surveillance. lf the surveillance is not performed within the delay period, the Controlmust immediately be declared not met, and the applicableAction(s) must be entered. The Action(s) begin immediately upon expiration of the delay period.

      \Nhen the surveillance is performed within the delay period and the surveillance is not met, the Control must immediately be entered. The Action(s) begin immediately upon failure to meet the surveillance.

2.0.4 Entry into a MODE or other specified condition in the Applicability of a Control shall not be made unless the Control's surveillances have been met within their specified frequency. This provision shall not prevent passage through to MODES or other specified conditions in compliance with Action(s). E1-68

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 7 of 195 1'2 CONTROLS AND SURVEILLANCE REOUIREMENTS I'2.1 INSTRUMENTATION 112.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 1.1.1 As required by WBN TS 5.7.2.7.a, the radioactive liquid effluent monitoring instrumentation channels shown in Table 1.1-1 shall be OPEMBLE with their alarm/trip setpoints set to ensure that the limits of ODCM Control '1.2.1.1 are not exceeded. The alarmftrip setpoints of these channels shall be determined in accordance with the methodology and parameters in ODCM Section 6.2. APPLICABILITY: This requirement is applicable as shown in Table 1.1-1. ACTION:

a. Wth a radioactive liquid effluent monitoring instrumentation channelalarm/trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so that it is acceptably conservative.

b. \Mth less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the action shown in Table 1.1-1. Restore the inoperable instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report, pursuant to ODCM Administrative Control 5.2, why the inoperability was not corrected within 30 days.

c. The provisions of SR 2.0.4 are not applicable. Report all deviations in the Annual Radioactive Effluent Release Report.

SURVE!LIANCE REQUIREMENTS 2.'1.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL OPERATIOML TEST operations at the frequencies shown in Table2.'l-1. E1-69

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 8 of 195 Table 1.1-l - RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUiiENTATION (Page 1 of2) MINIMUM CHANNELS ACTION APPLICABILITY INSTRUMENT OPERABLE I. RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Effluent Line (RE-90-1221 1 A QI

b. Steam Generator Blowdown Effluent Line 1 B (3)

(RE-90-120A and -1211

c. Condensate Demineralizer Regenerant 1 A (2)

    . Effluent Line (RE-90-2251

2. RADIOACTIVITY MONITORS PROVIDING ALARii BUT NOT PROVIDING AUTOMATIC TERUINATION OF RELEASE

a. Essential Raw Cooling Water Effluent 1/Discharge c (1)

Header (RE-90-1 33, -134,-1 40,-1 41\ Header

b. Turbine Building Sump Effluent Line 1 c (1)

(RE-90-2121

3. FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line 1 D (2)

(0-FrT-77-s0421

b. Steam Generator Blowdown Effluent Line 1 D (3)

(1-FrT-15421

c. Condensate Demineralizer Effluent Line 1 D (2)

(Fr-14456)

d. Diffuser Discharge Effluent Line 1 D (2)

(o-LPF-27-981 Applicabi lity Notation : (1) At all times. (2) During releases via this pathway. (3) During releases in MODES 1 ,2, 3, and 4. E1-70

WBN OFFSITE DOSE CALCUI..ATION MANUAL Revision 23 0 (oDcM) Page 9 of 195 Tabte 1.1-t RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION (Page 2 ot 2) TABLE NOTATION ACTION A -With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank(s) may be released to the environment provided that prior to initiating the release:

a. At least two independent samples of the tank's contents obtained by two technically qualified members of the facility staff are analyzed, and

b. At least two technically qualified members of the facility staff independently veriff the release rate calculations,

c. At least two technically qualified members of the facility staff independently veriff the discharge valve lineup; Othenrise, suspend release of radioactive effluents via this pathway.

ACTION B - \Mth the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for principal gamma emitters in accordance with ODCM SR 2.2.1.1.1 and2.2.1.'1.2.

a. At least once per 12 hours when the specific activity of the secondary coolant is equal to or greater than 0.01pCi/g DOSE EQUIVALENT l-131 , or

b. At least once per 24 hours when the specific activity of the secondary coolant is less than 0.01pCi/g DOSE EQUIVALENT l-131.

ACTION C - lAlith the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per'12 hours, grab samples are collected and analyzed for principal gamma emitters in accordance with ODCM SR 2.2.1.1.1 and 2.2.1..1.2 . ACTION D - \Mth the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours during actual releases. Pump curves or the change in tank level indication, if applicable, may be used to estimate flow. E1-71

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 10 of 195 Table 2.1-l - RADIOACTTVE LIQUID EFFLUENT MONITORING INSTRUMENTATION - SURVEI LLANCE REQUIREMENTS* (Page 1 of2) CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST {. RADIOACTIVIW MONITORS PROVIDING ALARM AND AUTOMATIC TERiJIINATION OF RELEASE

a. Liquid Radwaste Effluent D P R(3) 30(1 ,6)

Line (RE-90-122)

b. Steam Generator Blowdown D M R(3) 30(5)

Effluent Line (RE-90-120[and -1211

c. Condensate Demineralizer D P/M** R(3) 30(5)

Regenerant Effluent Line (RE-90-225)

2. RADIOACTTVITY TONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Essential Raw Cooling D M R(3) 3O(2)

Water Effluent Line (RE-90-1 33,-1 34,-1 40,-1 411

b. Turbine Building Sump D M R(3) 30(2)

Effluent Line (RE-90 -2121

3. FLOW RATE MEASUREMENT DEVI CES a.L quid Radwaste Effluent D(4) N/A R N/A L ne (0-FlT-77-50421

b. Steam Generator Blowdown D(4) N/A R*** N/A Effluent Line (1 -FlT -1 5421

c. Condensate Demineralizer D(4) N/A R N/A Effluent Line (Fl-1 4-456)

d. Diffuser Discharge Effluent D(4) N/A Y o Line LPF-27-98)

' See Table 3.'1 (FREQUENCY NOTATION) forthe surveillance frequency definitions.

' The source check on the condensate demineralizer radiation monitor will be performed monthly during periods of no release, and prior to each batch release during release periods (when secondary coolant activity determination (principalgamma emitters) is greaterthan 1x10 pCi/g).
- - 1-FfT-1542is a programmable device that has no calibration features. Therefore, a calibration verification satisfies the channel calibration requirement.

E1-72

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 11 of 195 Table 2.1 -i RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUIUENTATION SURVEILLANCE REQUIREMENTS (Page2ot2) TABLE NOTATION (1) The CHANNEL OPERATIONAL TEST shall demonstrate that automatic isolation of this pathway occurs if the instrument indicates measured levels above the alarm/trip setpoint. The CHANNEL OPERATIONAL TEST also demonstrates control room annunciation occurs if any of the following conditions exist:

1. lnstrument indicates measured levels above the alarm setpoint, or

2. lndication of downscale failure, or

3. lnstrumentation controls not set in operate mode, or

4. Loss of sample flow.

(2) The CHANNEL OPEMTIONAL TEST shall demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

1. lnstrument indicates measured levels above the alarm setpoint, or

2. lndication of downscale failure, or

3. lnstrumentation controls not set in operate mode.

(3) The initialCHANNEL CALIBRATION shallbe performed using one or more of the reference standards certified by the National lnstitute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that are traceable via measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBMTION, NIST traceable standards or sources that have been related to the initial calibration (transfer calibration sources) shall be used. (4) CHANNEL CHECK shall consist of veriffing indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hourc on days on which continuous, periodic or batch releases are made. (5) The CHANNEL OPERATIONAL TEST shalldemonstrate that automatic isolation of this pathway occurs if the instrument indicates measured levels above the alarm/trip setpoint. (6) The CHANNEL OPERATIONAL TEST that demonstrates control room annunciation upon a loss of sample flow shall be performed at least onoe per 92 days. E1-73

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 12 of 195 1'2 CONTROLS AND SURVEILLANCE REQUIREiiENTS 1/2.1 INSTRUMENTATION 1 12.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS 'l .1 .2 ln accordance with TAIBN TS 5.7 .2.7 .a, the radioactive gaseous effluent monitoring instrumentation channels shown in Table 1.1-2 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of ODCM Control '1.2.2.'l and Technical Specification 3.3.6 are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in ODCM Section 7.1. APPLICABILITY:As shown in Table 1.1-2. ACT]ON:

a. \Alith a radioactive gaseous effluent monitoring instrumentation channel alarmftrip setpoint less conservative than required by the above Control, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b. Wlth less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPEMBLE, take the ACTION shown in Table 1.'t-2. Restore the inoperable instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report, per ODCM Administrative Control 5.2, why the inoperability was not corrected within 30 days.

c. The provisions of SR 2.0.4 are not applicable. Report all deviations in the Annual Radioactive Effluent Release Report.

SURVEILI.ANCE REOU!REMENTS 2.1.2. Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBMTION, and CHANNEL OPEMTIONAL TEST at the frequencies shown inTable2.l-2. E1-74

WBN OFFSITE DOSE CALCUI..ATION MANUAL Revision 23 0 (oDcM) Page 13 of 195 Table 1.1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUiiENTATION Paqe 1 of 3 MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICAB!LITY ACTION {. WASTE GAS DISPOSAL SYSTEM

a. Noble Gas Activity Monitor (RE-90-1 18) 1 (e) A

b. Pressure Measuring Device 1 (ex8) J WGDT A O.PIS-77-1 15 WGDT B O-PIS-77-114 WGDT C 0-PlS-77-1 13 WGDT D O-PIS-77.100 WGDT E O-PIS.77-101 WGDT F O-PIS-77-102 WGDT G O-PIS-77-145 WGDT H 0-PlS-77-146 WGDT J O-PIS-77-147

2. CONDENSER VACUUM EXHAUST SYSTEM

a. Noble Gas Activity Monitors (RE-90-1 19) 1 (3) c

b. Deleted in Revision 5

c. Flow Rate Monitor (FE-2-256) 1 (3) B

d. lodine/Particulate Sample Line Heat Trace 1 (3) K TSOURCE NOTE 13]

3. SHIELD BUILDING EXHAUST SYSTEM

a. Noble Gas Low Ranse Activity Monitor (RE-904004) 1 QI E

b. lodine/Particulate Sampler and Sampler Flow Rate 1 (2X5) D Measurins Device (RE-90400 - Monitor ltem 028)

c. Effluent Flow Rate Measurins Device (F!-90400) 1 el B.E

d. lsokinetic Flow Control Equipment 1 (2X6) G TSOURCE NOTE 11I

e. lodine/Particulate Sample Line Heat Trace 1 (2) G TSOURCE NOTE 13I

f. Tritium flowrate measuring device 1 (1 1) M (FlQ-e0-801)

4. AUXILIARY BUILDING VENTILATION SYSTEM AND FUEL HANDLING AREA VENTILATION SYSTEM

a. Noble Gas Activity Monitor (RE-90-101 B) 1 (1) c

b. lodine/Particulate Sampler and Sampler Flow Rate 1 (1X5X7) D Measurins Device (FIS-90-1 01 C)

c. Effluent Flow Rate Measurins Device (FI-90-300/1 B) 1 (1) B,L

d. Isokinetic Flow Control Equipment 1 (10) H ISOURCE NOTE 11I

e. Tritium flowrate measuring device 1 (1 1) M (FtQ-90-800)

5. SERVICE BUILDING VENTILATION SYSTEM

a. Noble Gas Activity Monitor (RE-90-1328) 1 (1) C

b. Effluent Flow Rate Measuring System (FI-90-320118\ 1 (1) B

6. CONTAINMENT PURGE AND EXHAUST SYSTEM

a. Noble Gas Activity Monitors (RE-90-130, RE-90-131) 1 @l F

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 14 of 195 Table 1.I.2 . RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUiIENTATION (Page 2 of 3) Applicability Notation : (1) At alltimes. (2) At all times. Both Unit 'l and 2 Shield Building Exhaust System equipment must meet the minimum channel OPERABLE requirement, even for Unit I operation only. Operability of shield building noble gas activity monitor requires both flow rate and radiation inputs since the high radiation alarm is only on the effluent channel, which reads in pCi/s. (3) ln MODES 1 through 6 when CondenserVacuum Exhaust System is in operation. (4) At alltimes in MODES 1,2,3,4; during core alterations; during movement of inadiated fuel assemblies within containment. (5) Applies to charcoal and particulate filters, does not apply to detection channels. (6) Shield Building isokinetic flow control equipment may be considered operable if one primary sample pump 1,2-PMP-90.452A or 4528 and the flow controlvalve 1,2-FCV-90.452 are operable. lf automatic flow control, 1,2-FM-090-0400A, is unavailable, isokinetic flow control must be established manually (using 1,2-FC-90.452), based on flow rates determined during most recent flor rate measurement device calibration. (7) Auxiliary Building Exhaust iodine/particulate sampler may be considered operable with the isokinetic flow control equipment inoperable. (8) The pressure indicator for the WGDT being released must be operable for the tank to be released. (9) At alltimes during periods of release. (10) lsokinetic sampling on the Auxiliary Building Exhaust is required when flow rate exceeds 160,000 SCFM. (11) At all times during periods of release when inadiated TPBARs are in the Reactor or in the Spent Fuel Pool. Compensatory Actions ACTION A - \Mth the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank(s) may be released to the environment provided that prior to initiating the release:

a. At least two independent samples of the tank's contents obtrained by two technically qualified members of the facility staff are analyzed, and

b. At least two technically qualified memberc of the Facility Staff independently veriff the release rate calculations, and

c. At least two technically qualified members of the Facility Staff independently veriff the discharge valve lineup; Othenrise, suspend release of radioactive effluents via this pathway.

ACTION B - l/Vtth the number of channels OPEMBLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours during releases via this pathway. ACTION C - \A/ith the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours and these samples are analyzed for noble gases (gamma emitters) in accordance with plant procedures. Grab samples are required only during those periods when releases are being made. ACTION D - With the number of channels OPERABLE less than required by the Minimum Channels OPEMBLE requirement, effluent releases via the affected pathway may continue provided that within 4 hours after the channel has been declared inoperable, samples are continuously collected with auxiliary sampling equipment as required inTable2.2-2. Continuous sampling is required only during those periods when releases are being made. E1-76

WBN OFFSITE DOSE CALCUI-ATION MANUAL Revision 23 0 (oDcM) Page 15 of 195 Table 1.1-2 - RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (Page 3 of 3) Compensatory Actions (Continued) ACTTON E - Flow Rate Channel lnooerable - Wth an inoperable flow element on a discharge pathway where a fan is operating (Purge A, Purge B, ABGTS, or EGTS), effluent release may continue provided: (a) "Low Rng" on RE-90400 is selected instead of "Eff'; and (b) at least once per 12 hours associated instrument malfunction is verified not annunciated; and (c) a reading from "Low Rng" on RE-90-400 is obtained at least once per 24 hours during the release. Radiation Monitor lnooerable - With the "EFF'and "LOW RNG" channels inoperable, effluent releases may continue provided grab samples are taken at least once per 12 hours and these samples are analyzed for noble gases (gamma emitters) in accordance with plant procedures. Grab samples are required only during those periods when releases are being made. ACTION F - l/Vrth the number of channels OPERABLE less than required by the Minimum Channel OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway. ACTION G - Wth the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, planned ongoing effluent releases via the affected pathway may continue provided that within 4 hours after the channel has been declared inoperable, the equipment is restored to OPERABLE. ACTION H - \Aflth the required equipment inoperable, effluent releases may continue via this pathway provided the sample/s transmission factor(s) are corrected for the loss of this equipment. ACTION J - l/Vith the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases from that WGDT must be discontinued until the channelis OPEMBLE. ACTION K - With the heat trace inoperable and auxiliary sampling equipment required for iodine and particulate collection, effluent releases via the affected pathway may continue provided that steam generator activity is evaluated weekly to determine if a path exists for release of iodine or particulate activity, and any such activity being released is quantified in accordance with plant procedures. ACTION L- \Mth the required equipment INOPERABLE due to the flowrate being greaterthan 0 and less than 100,000 scfm, manually adjust sample loop 0-LPF-90-300 flowrate to 20 scfm +/- 1 scfin within 4 hours to return the channel to operable status. tn addition, if the flor rate is greater than 0 and less than 40,000 scfm, then veriff at least one Auxiliary Building or Fuel Handling exhaust fan is running. ACTION M- \Mth the required equipment inoperable, effluent releases may continue via the pathway provided that within 24 hours after the channel has been declared inoperable, samplers are replaced or tritium grab samples are taken once per 24 hours. Continuous sampling is required only during those periods when applicability note (11) is met. E1-77

WBN OFFSITE DOSE CALCUI.ATION MANUAL Revision 23 0 (oDcM) Page 16 of 195 TabIe 2.1.2. RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION . SURVEILLANCE REQUIREMENTS* (Page 1 of2) CHANNEL CHANNEL SOURCE CHANNEL OPERAT!ONAL INSTRUttilENT CHECK CHECK CAL!BRATION TEST

  . WASTE GAS DISPOSAL SYSTEM

a. Noble Gas Activity Monitor (RE-90-1 18) P P R(3) 3Q(1)

b. Pressure Measurinl g Device P N/A R N/A WGDT A O-P ls-77-1 15 WGDT B O-P ts-77-114 WGDT C O-P !s-77-1 13 WGDT D O-P rs-77-100 WGDT E O-P ts-77-101 WGDT F O-PI ts-77-102 WGDT G O-P ts-77-145 WGDT H O-P ls-77-146 WGDT J O-P ts-77-147

2. CONDENSER VACUUM EXHAUST SYSTEM

a. Noble Gas Activity Monitor (RE-90-1 19) D M R(3) 3Q(2)

b. Deleted in Revision 5

c. Effluent Flow Rate Measurino Device (FE-2-256) D N/A R N/A

d. Deleted in Revision 5

e. lodine/Particulate Sample Line Heat Trace N/A N/A N/A o TSOURCE NOTE 13I

3. SHIELD BUILDING EXHAUST SYSTETI'

a. Noble Gas Activity Monitor (RE-90400A) D M R(3) 3Q(2)

b. lodine and Particulate Sampler (RE-90-402) N/A N/A N/A N/A

c. Effluent Flow Rate Measurinq Device (FI-90-400) D N/A R o

d. Sampler Flow Rate Measuring Device D N/A R o (RE-90-400 - Monitor ltem 028)

e. lodine/Particulate Sample Line Heat Trace N/A N/A N/A o TSOURCE NOTE 13I

f. Tritium Flow Rate Measurins Device (FlQ-90-801) D N/A Y N/A O. AUXILIARY BUILDING VENTILATION AND FUEL HANDLING AREA VENTI ATION SYSTEM

a. Noble Gas Activity Monitor (RE-90-1018) D M R(3) 3Q(2)

b. lodine and Particulate Sampler (RE-90-101) N/A N/A N/A N/A

c. Effiuent Flow Rate Measuring Device D N/A R o (Fr-90-300/1 B)

d. Sampler Flow Rate Measuring Device D N/A R o (Frs-90-101c)

e. Tritium Flow Rate Measurino Device (FlQ-90-800) D N/A Y N/A

5. SERVICE BUILDING VENTILATION SYSTETU

a. Noble Gas Activity Monitor (RE-90-132) D M R(3) 3Q(2)

b. Effluent Flow Rate Measuring D N/A R o System (Fl-90-320/1B)

5. CONTAINMENT PURGE AND EXHAUST SYSTETII Noble Gas Activity Monitors *** P

                                                                                ***(3)               *

(RE-90-1 30, RE-90-1 31 )

See Table 3.1 (FREOUENCY NOTATION) for the surveillance frequency definitions.
- - See \ArBN TS 3.3.6.1, 3.3.6.7, and 3.3.6.4 for these requirements.

E1-78

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 17 of 195 T able 2.1 RADIOACTIVE GASEOUS EFFLUENT MONITOR! NG ! NSTRUMENTATION SURVE! LLANCE REQUIREMENTS-(Page2of 2) TABLE NOTATION (1) The CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists: 1.lnstrument indicates measured levels above the alarm/trip setpoint, or 2.lndication of downscale failure, or 3.lnstrumentation controls not set in operate mode. (2) The CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the folloring conditions exists: l.lnstrument indicates measured levels above the alarm setpoint, or

2. lndication of dournscale failure, or 3.lnstrumentation controls not set in operate mode.

(3) The initial CHANNEL CALTBMTION shall be performed using one or more of the reference standards certified by the National lnstitute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that are traceable via measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, NIST traceable standards or sources that have been related to the initial calibration (transfer calibration sources) shall be used. E1-79

WBN OFFSITE DOSE CALCUI.ATION MANUAL Revision 23 0 (oDcM) Page 18 of 195 1/2 CONTROLS AND SURVEILLANCE REOUIREMENTS {/2.1 INSTRUMENTATION 1I 2.1 .3 METEOROLOG ICAL I NSTRUMENTATION'DATA CONTROLS 1.1.3 The meteorologicalmonitoring instrumentation channels shown in Table 1.1-3 shallbe OPERABLE. APPLICABILITY: At all times. ACTION: With one or more required meteorological monitoring channels inoperable for more than 7 days, prepare and submit a Special Report to the NRC, pursuant to ODCM Administrative Control 5.4, within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel(s) to OPERABLE status. The provisions of SR 2.0.4 are not applicable. SURVEILI.ANCE REQUIREMENTS 2.1.3 Each of the above meteorological instrumentation channels shall be demonstrated OPEMBLE by the performance of the CHANNEL CHECK at least once per 24 hours and the CHANNEL CALIBRATION at least once per 184 days. E1-80

WBN OFFSITE DOSE CALCU1ATION MANUAL Revision 23 0 (oDcM) Page 19 of 195 Table 1.1 METEOROLOGICAL MONITORING INSTRUMENTATION Minimum lnstrument Location OPERABLE

1. WND SPEED Channe! 1 Nom nal Heiqht 10 m Channel 2 Nom nal He qht 46 m 2of3 Channel 3 Nom nal He sht 91 m

2. WND DIRECTION Channel 1 Nominal Heisht 10 m Channel 2 Nominal Heisht 46 m 2of3 Channel 3 Nominal Heiqht 91 m

3. AIR TEMPEMTURE - DELTA T Channel 1 Nom nal He sht 10 to 46 m Channel 2 Nom na! He qht 10 to 91 m 1of3 Channel 3 Nom nal He sht 46 to 91 m E1-81

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 20 of 195 {/2 CONTROLS AND SURVEILLANCE REQUIREMENTS {/2.2 RADIOACTIVE EFFLUENTS 1 12.2.1 LIQUID EFFLUENTS 1I 2.2.1.1 CONCENTRATTON CONTROLS 'l .2.1 .1ln accordance with WBN TS 5.7.2.7.b and c, the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 3.1) shall be limited to 10 times the concentration values specified in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2401tor radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2x104 pCi/ml total activity. APPLICABILIW: At all times. ACTION: With the concentration of radioactive material released in liquid effluents exceeding the above limits, immediately restore the concentration to within the above limits. The provisions of SR 2.0.4 are not applicable. Report all deviations in the Annual Radioactive Effluent Release Report. SURVEILTANCE REOUIREMENTS 2.2.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table2.2-'1. 2.2.1.1.2 The results of the radioactivity analysis shall be used in accordance with the methodology and parameters in ODCM Section 6.1 to assure that the concentrations at the point of release are maintained within the limits of Control 1.2.1.1. E1-82

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 21 of {95 Table 2.2 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM (Page 1 of3) Minimum Minimum Lower Limit of Sampling Analysis Type of Activity Detection Liquid Release Type Frequency Frequency Analysis (LLD){ (rrCi/ml} Batch Release Tanks2 P P Principal Gamma A. Radwaste System Tanks Each Each Batch Emitters3 5x10-7 Waste Condensate A, B, & C Batch Cask Decontamination !-131 1x1 0-o Chemical Drain P M Dissolved/ Monitor One Entrained Noble 1x1 0-5 Laundry and Hot Shower A&B Batch/M Gases (Gamma Emitters) B. Condensate Demineralizer P M H-3 1x1 0-5 System Tanks 6 Each Lab Waste Neutralization Batch Compositea Gross Alpha 1x1O-7 Non-Reclaimable Waste P o Sr-89, Sr-90 5x10-8 High Crud A&B Each Lab Batch Compositea Fe-55 1x10-6 Continuous Releasess D D Principal Gamma 5x10-/ C. Steam Generator Grab Each Grab Emitters3 Blowdown6 Sample Sample I-1 31 1x10-o D. Turbine Building Sumpo M M Dissolvedl Grab Entrained Noble 1x1 0-5 Sample Gases (Gamma Emitters) D M H-3 1x1 0-c Grab Lab Sample Compositea Gross Alpha 1x10-t D o Sr-89, Sr-90 5x1 0-u Grab Lab Sample Compositea Fe-55 1x1 0-o E. Groundwater Sump M M Principal Gamma 5x1 0-7 Grab Each Grab Emitters3 Sample Sample t-131 1x10-b Dissolved/ Entrained Noble 1x1 0-5 Gases (Gamma Emitters) H-3 1x10-5 o o Grab Grab Sr-89, Sr-90 5x10-8 Sample Sample

See Table 3.1 (FREQUENCY NOTATION) forthe surveillance frequency definitions.

E1-83

WBN OFFSITE DOSE CALCUIATION MANUAL Revision 23 0 (oDcM) Page 22 of 195 Table2.2-1. RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM (Page 2 of 3) TABLE NOTATION 1 Ttre ttD is defined for the purpose of these Controls as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only a 5o/o probability of falsely concluding that a blank observation represents a "real" signal. (Reference 8) For a particular measurement system (which may include radiochemical separation): 4.66sg LLD = EY 2.22E6 Y exp(-l,At) where: LLD = the "a priori" lower limit of detection (microcurie per unit mass or volume). Sg = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute). E = the counting efficiency (counts per disintegration). V = the sample size (units of mass or volume). 2.22x106 = the number of disintegrations per minute per microcurie. Y = the fractional radiochemicalyield, when applicable. I = the radioactive decay constant for the paiicular radionuclide (s-1), and Dt = the elapsed time between midpoint of sample collection and time of counting (s). The definition of Dt applies only to the calculation of the LLD. A more rigorous treatment of the buildup and decay during the sample collection and/or counting interval(s) may be applied to actual sample analysis if desired. It should be recognized that the LLD is defined as an ejflgIi@efore the fact) limit representing the capability of a measurement system and not an a oosteriori (afier the fact) limit for a particular measurement. Typicalvalues of E, V, Y, and At should be used in the calculation. 2 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 by the method described in appropriate plant proced u res to assu re representative sampl ng.i 3 The principal gamma emitters forwhich the LLD Control applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co60, ZnS, Mo-99, Cs-134, Cs-137, Ce-141. Ce:144 shallalso be measured, but with an LLD of 5x10{ pCi/ml. This list does not mean that only these nuclides are to be considered. Other gamma peaks which are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to ODCM Administrative Control 5.2, in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June '1974. 4 A hboratory composite sample is one prepared by combining representative samples from each release into one well-mixed, homogeneous sample. The volume of sample added to the composite from each release shall be proportionalto the release volume. The composite sample shall be preserved according to plant procedures as appropriate. E1-84

WBN OFFSITE DOSE CALCUI.ATION MANUAL Revision 23 0 (oDcM) Page 23 of 1 95 Table 2.2 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM (Page 3 of 3) TABLE NOTATION 5 A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.9., from a system that has an input flow during the continuous release. 6 Not applicable when most recent Secondary Coolant System activity determination (principal gamma emitters) is less than or equal to 1x10{ pCilg and either of the following conditions exist: (1) the discharge radiation monitor setpoint is less than or equalto 2 times background or (2) compensatory requirements associated with applicable inoperable monitors are met. E1-85

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 24 of 195 I/2 CONTROLS AND SURVEILLANCE REQUIREMENTS I'2.2 RADIOACTIVE EFFLUENTS 112.2.1 LIQUID EFFLUENTS 1t2.2.1.2 DOSE CONTROLS '1.2.1.2 ln accordance with WBN TS 5.7.2.7.d and e, the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents discharged from each unit to UNRESTRICTED AREAS (see Figure 3.1) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and b.During any calendar year to less than or equal to 3 mrem to the total body and to less than or equalto 10 mrem to any organ.

APPLICABILITY: At all times. ACTION: Wth the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the NRC within 30 days, pursuant to ODCM Administrative Control 5.4, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. This Special Report shall also include: (1) the results of radiological analyses of drinking water sources and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR '141, Safe Drinking Water Act, (applicable only if drinking water supply is taken from the receiving water body within three miles dornstream of the plant discharge). The provisions of SR 2.0.4 are not applicable. SURVEILI.ANCE REQUIREMENTS 2.2.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and current calendar year shall be determined in accordance with the methodology and parameters in ODCM Section 6.3 at least once per 31 days. lsouRcE NorE 5l E1-86

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 25 of 195 {/2 CONTROLS AND SURVEILLANCE REQUIREMENTS {/2.2 RADIOACTIVE EFFLUENTS 112.2.1 LIQUID EFFLUENTS 112.2.1.9 LIQUID RADWASTE TREATMENT SYSTEM CONTROLS 1.2.'1.3 ln accordance with WBN TS 5.7.2.7.f , the Liquid Radwaste Treatment System (LRTS) shall be OPERABLE and appropriate portions of the system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from each unit to UNRESTRICTED AREAS (see Figure 3.1) would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in a 31-day period. APPLICABILITY: At all times. ACTION: With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the LRTS not in operation, prepare and submit to the NRC within 30 days, pursuant to ODCM Administrative Control 5.4, a Special Report which includes the following information:

1. Explanation of why liquid waste was being discharged without treatment, identification of the inoperable equipment or subsystems, and the reason for the inoperability,

2. Action(s) taken to restore the inoperable equipment to OPEMBLE status, and

3. Summary description of action(s) taken to prevent a recurrence.

The provisions of SR 2.0.4 are not applicable. SURVEILI.ANCE REQUIREMENTS 2.2.'1.3.1 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days, in accordance with the methodology and parameters in ODCM Section 6.5 when the LRTS are not being fully utilized. [souRcE NoTE 9l 2.2.1.3.2 The installed LRTS shall be considered OPEMBLE by meeting ODCM Controls 1.2.'1.1 and 1.2.1.2. E1-87

WBN OFFSITE DOSE CALCUIATION MANUAL Revision 23 0 (oDcM) Page 26 of 195 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1'2.2 RADIOACTIVE EFFLUENTS 1I 2.2.2 GASEOUS EFFLUENTS 112.2.2.1DOSE RATE CONTROLS 1.2.2.1 ln accordance with \A/BN TS 5.7.2.7.9, the dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the UNRESTRICTED AREA BOUNDARY (see Figure 3.1) shall be limited to the following:

a. For noble gases: Less than or equal to a dose rate of 500 mrem/y to the total body and less than or equal to a dose rate of 3000 mrem/y to the skin, and b.For lodine-131, lodine-133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to a dose rate of 1500 mremff to any organ.

APPLICABILITY: At all times. ACTION: \Mth dose rate(s) exceeding the above limits, immediately restore the release rate to within the above limit(s). The provisions of SR 2.0.4 are not applicable. Report all deviations in the Annual Radioactive Effluent Release Report. SURVEILI.ANCE REQUIREMENTS 2.2.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in ODCM Section 7.2.2by obtaining representative samples and performing analyses in accordance with the sampling and anafysis program specifi ed in T able 2.2-2. lsouRcE NoTE 7I 2.2.2.L2The dose rate due to lodine-131, lodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in ODCM Section 7.2.3by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specifi ed in T able 2.2-2. lsouRcE NoTE 7,11 E1-88

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 27 of 195 Table 2.2-2-RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM* (Page 1 of3) Gaseous Release Type Minimum Analysis Type of Activity Lower Limit of Sampling Frequency Analysis Detection Frequency (LLD) (uci/m!)l A. Waste Gas P P Noble Gases' 1x1 0q Decay Tank Each Tank Each (Gamma Emitters) Grab Sample Tank H-3 (oxide) 1x1 0-6 B. Containment PE P Noble Gases' PURGE3 Each Each (Gamma Emitters) 1x1Oa PURGE Purge Grab Sample C. lncore lnstrument Each Each Noble Gases' 1x1 0a Room PURGE3 PURGEg Purge (Gamma Emitters) Grab Sample D. Requirement Deleted ru E. Auxiliary Building Exh."' M M Noble Gases' 1x1 0a F. Condenser Vacuum Exh.1 1 Grab Sample (Gamma Emitters) G. Service Buildino Exh. H. Deleted n Revision 11

l. Deleted n Revision 11 J. Deleted n Revision 11 K. Auxiliary Building Exh. ContinuousG W H-3 (oxide) 1x1 0 L. Shield Building Exh. Tritium M. Condenser Vacuum Ex1.11,12 Sample Continuouso q/ t-1 31 1x1O-12 Charcoal t-133 1x1O-10 Sample Continuous6 yy7 Principal Gamma 1x1O-1 1

Particulate Emitters2 Sample Continuouso M Gross Alpha 1x1O-11 Composite Particulate Sample o Sr-89, Sr-90 1x1O-11 'See Table 3.1 (FREQUENCY NOTATION) forthe surveillance frequency definitions. E1-89

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 28 of 195 Table2.2-2-RADIOACTIVE GASEOUS WASTE i,lONtTORlNG SAMPLING AND ANALYSIS PROGRAilI (Page 2 of 3) TABLE NOTATION t Tne ttD is defined in Note 1 otTable2.2-1. 2 The principal gamma emitters forwhich the LLD Control applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, l-131, Co-58, Co0, 2n65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-1214 in lodine and particulate releases. This list does not mean that only these nuclides are to be considered. CIher gamma peaks that are identifiable, together with the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report purcuant to ODCM Administrative Control 5.2,in the format outlined in Regulatory Guide 1 .21, Appendix B, Revision 1 , June 1974. 3 Sampling and analysis for containment purges, incore instrument room purges, and the Auxiliary Building Exhaust shall also be performed following shutdown, startup, or a thermal power change exceeding 15o/o ol RATED THERMAL POWER within a t hour period unless (a) analysis shows that the DOSE EQUIVALENT l-131 concentration in the reactor coolant has not increased more than a factor of 3 and (b) the containment noble gas activity monitor (RE-90-106 or RE-90-'112) or latest grab sample obtained as compensatory requirement associated with applicable inoperable monitor shows that the radioactivity has not increased by more than a factor of 3. 4 Debted in Revision 11 5 Deleted in Revision 11 6 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 ODCM Controls '1.2.2.1, 1.2.2.2, and 1.2.2.3. 7 Samples shall be changed at least once per 7days. Analyses shall be completed within 48 hours after changing, or after removal from sampler for those release points that had a discharge during the sampling period. Sampling shall also be performed at least once per 24 hours for at least 7 days following each shutdown, startup, or THERMAL POWER change exceeding 15o/o ol RATED THERMAL POWER within a one hour period for those release points that had a discharge during the sampling period. Analyses of samples shall be completed within 48 hours of changing. \Mten samples collected for 24 hours are analyzed, the conesponding LLDs may be increased by a factor of 10. This daily sampling and analysis requirement does not apply if: (1) analysis shows thatthe DOSE EQUIVALENT l-131 concentration in the reactor coolant has not increased by more than a factor of 3; and (2) the containment noble gas monitor aligned to lower containment (RE-90-106 or RE-90-112) or latest grab sample obtained as compensatory requirement associated with applicable inoperable monitor shows that the radioactivity has not increased by more than a factor of 3. 8 ln all MODES, the compartment(s) of the containment to be purged shall be sampled for noble gas priorto PURGING. e The incore instrument room PURGE sample shall be obtained at the shield building monitor between 5 and 20 minutes following initiation of the incore instrument room PURGE. E1-90

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 29 of 195 Tabte2.2-2-RADIOACTIVE GASEOUSWASTE MONITORING SAMPLING ANDANALYSIS PROGRAilI (Page 3 of 3) TABLE NOTATION 10 Applicable in MODES 1,2,3, and 4, the containment will be VENTED to the containment annulus and then to the auxiliary building via containment annulus fans. The lower containment noble gas monitor (RE-90-106 or -1'l2l response will be recorded daily when VENTING is occurring to monitorthe radioactivity being discharged. The Auxiliary Building Exhaust will be re-sampled when the reading on the lower containment radiation monitor (RE-90-106 or -'112) increases by 50% from the initial value. lf the lorer containment noble gas monitor (RE-90-106 or -112) is inoperable, noble gas grab samples may be used to perform this comparison. 11 Not applicable when the most recent Secondary Coolant System radioactivity determination (principal gamma emitters) is less than or equal to 1x10{ pCi/g and either of the following conditions exist: (1) the discharge radiation monitor setpoint is less than or equal to 2 times background or (2) compensatory requirements associated with applicable inoperable monitors are met. 12 Continuous tritium sample collection not applicable. E1-91

WBN OFFSITE DOSE CALCUI.ATION MANUAL Revision 23 0 (oDcM) Page 30 of 195 I'2 CONTROLS AND SURVEILLANCE REQUIREMENTS I/2.2 RADIOACTIVE EFFLUENTS 1 12.2.2 GASEOUS EFFLUENTS 112.2.2.2 DOSE - NOBLE GASES CONTROLS 1.2.2.2 !n accordance with \AIBN TS 5.7.2.7.h, the air dose due to noble gases released in gaseous effluents from each unit to areas at and beyond the UNRESTRICTED AREA BOUNDARY (see Figure 3.1) shall be limited to the following: a.During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and

b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY: At all times. ACTION: Wth the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC within 30 days, pursuant to ODCM Administrative Control 5.4, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. The provisions of SR 2.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 2.2.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in ODCM Section 7.3 at least once per 31 days. lsouRcE NoTE 5l E1-92

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 31 of 195 1'2 CONTROLS AND SURVEILLANCE REQUIREMENTS I'2.2 RADIOACTIVE EFFLUENTS 1 12.2.2 GASEOUS EFFLUENTS 112,2.2.3 DOSE - I.131,I.133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM wlTH HALF.LIVES GREATER THAN EIGHT DAYS CONTROLS 1.2.2.3 !n accordance with \NBN TS 5.7.2.7.i, the dose to a MEMBER OF THE PUBLIC from l-131, l-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas at and beyond the UNRESTRICTED AREA BOUNDARY (see Figure 3.1) shall be limited to the following: a.During any calendar quarter: Less than or equal to 7.5 mrem to any organ and,

b. During any calendar year: Less than or equal to 15 mrem to any organ.

APPLICABILITY: At all times. ACTION: l/Vith the calculated dose from the release of t-131 , l-1 33, tritium, and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC within 30 days, pursuant to ODCM Administrative Contro! 5.4, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the correc{ive actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. The provisions of SR 2.0.4 are not applicable. SURVEI L!.ANCE REQU I REMENTS 2.2.2.3 Cumulative dose contributions for the current calendar quarter and cunent calendar year for l-131 , l-1 33, tritium, and all radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in ODCM Section 7.4 at leastonce per31 days. [souRcE NoTE 5l E1-93

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 32 of ,l95 {/2 CONTROLS AND SURVEILLANCE REQUIREMENTS I/2.2 RADIOACTIVE EFFLUENTS 1 12.2.2 GASEOUS EFFLUENTS 1 12.2.2.4 GASEOUS RADWASTE TREATMENT CONTROLS 1.2.2.4 ln accordance with VVtsN TS 5.7.2.7.f , the VENTIISTION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases from each unit to areas at and beyond the UNRESTRICTED AREA BOUNDARY (See Figure 3.1) would exceed:

a. 0.2 mrad to air from gamma radiation, or

b. 0.4 mrad to air from beta radiation, or

c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

APPLICABIL!ry: At all times. ACTION: Wth the radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the NRC within 30 days, pursuant to ODCM Administrative Control 5.4, a Special Report that includes the following information:

1. ldentification of the inoperable equipment or subsystems and the reason for inoperability.

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action(s) taken to prevent a recurrence.

The provisions of SR 2.0.4 are not applicable. SURVEILHNCE REQUIREMENTS 2.2.2.4.1 Doses due to gaseous releases from each unit to areas at and beyond the UNRESTRICTED AREA BOUNDARY shall be pQected at least once per 31 days, in accordance with the methodology and parameters in ODCM Section 7.5 when theVENTII-ATION EXHAUST TREATMENT SYSTEMS and WASTE GAS HOLDUP SYSTEMS are not being fully utilized. lsouRcE NorE 9I 2.2.2.4.2 The installed VENTII-ATION EXHAUST TREATMENT SYSTEMS and WASTE GAS HOLDUP SYSTEM shallbe considered OPERABLE by meeting the requirements in ODCM Controls 1.2.2.1, 1.2.2.2, and 1.2.2.3. E1-94

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 33 of 195 I/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1t2.2.3 TOTAL DOSE CONTROLS 1.2.3 ln accordance with \IVBN TS 5.7.2.7.j, the annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and to direct radiation from uranium fuel cycle sources, shall be limited to less than or equal to 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. APPLICABILITY: At all times. ACTION: a.With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of ODCM Control 1 .2.1 .2, 'l .2.2.2, or 1 .2.2.3, calculations shall be made in accordance with ODCM Section 8.1 including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits have been exceeded. lf such is the case, prepare and submit to the NRC within 30 days, pursuant to ODCM Administrative Control 5.4, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limils. This Special Report, as defined in 10 CFR 20.2203(a)(4), shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. lt shall also describe levels of radiation and concentrations of radioactive materials involved, and the cause of the exposure levels or concentrations. lf the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190. Submiftal of the report is considered a timely request, and a variance is granted until the staff action on the request is complete. b.Wth the estimated doses exceeding the 40 CFR 190 dose limits, a separate determination must be made, in accordance with the requirements of 40 CFR 302.5, regarding the reportable quantities for radionuclide releases given in 40 CFR 302.4. Any required notifications will be made in accordance with ODCM Administrative Control 5.5.

c. The provisions of SR 2.0.4 are not applicable.

SURVEI LI.ANCE REQU I REMENTS 2.2.3.1Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with ODCM Surveillance Requirements2.2.1.2,2.2.2.2, and2.2.2.3 and in accordance with the methodology and parameters in ODCM Sections 6.3, 7.3, and7.4. 2.2.3.2Cumulative dose contributions from direct radiation from the units and from radwaste storage tanks shallbe obtained from the REMP described in ODCM Section 9.1. This requirement is applicable only under conditions set forth in the action above. E1-95

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 34 of { 95 I'2 CONTROLS AND SURVEILIANCE REQUIREMENTS I'2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 112.3.1 MONITORING PROGRAM CONTROLS 1.3.1 As required by 10 CFR Part 50, Appendix l, Section lV.B, the Radiological Environmental Monitoring Program (REMP) shallbe conducted as specified in Table 2.3-1. APPLICABILITY: At all times. ACTION:

a. \Mth the REMP not being conducted as specified in Table 2.3-1, prepare and submit to the NRG, in the Annual Radiological Environmental Operating Report described in ODCM Administrative Control 5.1, a description of the reasons for not conducting the program as required and the plan for preventing a recurrence.

b. Wth the level of radioactivity as a result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 2.3-2, when averaged over any calendar quarter, prepare and submit to the NRC within 30 days from the end of the affected quarter, pursuant to ODCM Administrative Control 5.4, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose'to a MEMBER OF THE PUBLIC is less than the calendar year limits of ODCM Controls 1.2.1.2, 1.2.2.2 and 1.2.2.3. When more than one of the radionuclides in Table 2.3-2 are detected in the sampling medium, this report shall be submitted if:

ffi*ffi*" concentrotion(il concentrotion(i+1) .

  \Mren radionuclides other than those in Table 2.3-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose* to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of ODCM Controls 1.2.1.2, 1.2.2.2, and 1.2.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological EnvironmentalOperating Report described in ODCM Administrative Control5.1.

' The methodology and parameters used to determine the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report. E1-96

WBN OFFSITE DOSE CALCUI.ATION MANUAL Revision 23 0 (oDcM) Page 35 of 195 1'2 CONTROLS AND SURVEILI-ANCE REQUIREMENTS I'2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1 12.3.1 MONITORING PROGRAM ACTION (CONTINUED):

c. With milk or fresh leaff vegetation samples unavailable from one or more of the sample locations required by Table 2.3-1, identiff specific locations for obtaining replacement samples and add them within 30 days to the REMP described in ODCM Section 9.0 (excluding short term or temporary unavailability). The specified locations from which samples were unavailable may then be deleted from the monitoring program.

Pursuant to ODCM Administrative Controls 5.2 and 5.3, submit in the next Effluent Release Report documentation for a change in the ODCM, with supporting information identiffing the cause of the unavailability of samples and justifuing the selection of the neur location(s) for obtaining samples. The provisions of SR 2.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 2.3.1 The radiological environmental monitoring samples shall be collected pursuant to Table 2.3-1 from the specific locations given in the tables and figures in ODCM Section 9.0 and shall be analyzed pursuant to the requirements of Table 2.3-1 and the detection capabilities required by Table 2.3-3. lsouRcE NorE 6l E1-97

WBN OFFSITE DOSE CALCUTATION MANUAL Revision 23 0 (oDcM) Page 36 of 195 Table 2.3 MINIMUii REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 1 of5) Exposure Pathway andror Number of Samples and Sampling and Type and Frequency of Sample Sample Locaiion"l Collection Frequency Analyses {. DIRECT RADIATION2 Forty routine monitoring Quarterly Gamma dose stations either with two or quarterly more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows: An inner ring of stations, one in each meteorological sector in the genera! area of the UNRESTRICTED AREA BOUNDARY; and An outer ring of stations, one in each meteorological sector in the 6- to 8-km range from the site; and The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in one or two areas to serve as control stations.

2. AIRBORNE Radioiodine Samples from five locations: Continuous sampler Radioiodine canister:

and Three samples from close to operation with I-131 analysis weekly Particulates the three unrestricted area sample collection boundary locations in weekly, or more Particulate sampler: different sectors of the frequently if required Gross beta highest calculated annual by dust loading. radioactivity analysis average ground-level D/Q ; following fi lter change4 One sample from the vicinity and gamma isotopic of a community having the analysisc of composite highest calculated annual (by location quarterly) average ground level D/Q; and One sample from a control location, as for example 15-30 km distant and in the least prevalent wind direction3 E1-98

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 37 of 195 Table 2.3-l - MtNliiUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 2 of 5) Exposure Pathway and/or Number of Samples gnd Sampling and Type and Frequency of Sample Sample Locations' Collection Frequency Analyses

3. WATERBORNE Surfaceo One sample upstream. Composite sample Gamma isotopic One sample downstream. over a 1-month analysiss monthly; period.T composite for tritium analvsis quarterly.

Ground Samples from one or two At least once per 92 Gamma isotopic5 and sources _only if likely to be days tritium analysis affecteds quarterly. Drinking One sample of each of one to Composite sample Gross beta and three of the nearest water over a one month gamma is_otopic supplies that could be period.T analyseso monthly. affected by the dischargee Composite for tritium analvsis quarterly. Shoreline One Sample from Semiannually Gamma isotopict Sediment downstream area with analysis semiannually existing or potential recreational value Holding Samples from at least three Annually Gamma isotopic Pond locations in the Yard Holding analysiss annually Sediment Pond

4. INGESTION MiIK Samples from milking Semimonthly when Gamma isotopic5 and animals in three locations animals are on l-131 analysis semi-within 5 km distance having pasture; monthly at monthly when animals the highest dose potential. lf other times. are on pasture; there are none, then one monthly at other times.

additional sample from milking animals in each of one to three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem/yr1o One sample from milking animals at a control location 15-30 km distant and in the least prevalent wind direction.3 E1-99

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 38 of 195 Table 2.3-l MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAii (Page 3 of 5) Exposure Pathway andlor Number of Samples and Sampling and Type and Frequency of Sample Sampte Locailonsl Gollection Frequency Analyses INGESTION (continued) Fish One sample of commercially Sample in season, Gamma isotopic important species and one or semiannually if analysiss on edible sample of recreational ly they are not portions. important species in vicinity seasonal of plant discharge area and the Chickamagua Reservoir. One sample of same species in areas not influenced by plant discharge. Food One sample of each principal At time of harvestl l Gamma lsotopic Products class of food products from analysiss on edible any area within 10 miles of portion. the plant that is irrigated by water in which liquid plant wastes have been discharged. Samples of three different kinds of available broad leaf vegetation grown nearest each of two different offsite Iocations of highest predicted annual average ground-level D/Q if milk sampling is not performed as outlined in 4.a. above. One sample of each of the similar broad leaf vegetation grown 15-30 km distant in the Ieast prevalent wind direction if milk sampling is not performed as outlined in 4.a. above.3 E1-100

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 39 of 1 95 Table 2.3-l - MlNliiUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 4 of 5) TABLE NOTATION 1 Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, shall be provided for each and every sample location in Table 2.3-'l in a table(s) and figure(s) in ODCM Section 9.0. Refer to NUREG-1301 , "Offsite Dose Calculation Manual Guidance: Standard Effluent Controls for Pressurized Water Reactors, Generic Letter 89-01, Supplement 1," April 1991. 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. lf specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete conective 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 pursuant to ODCM Administrative Control 5.1. lt 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. ln these instances suitable specific 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 given in ODCM Section 9.0. Pursuant to ODCM Administrative Controls 5.2 and 5.3, submit in the next Annual Radioactive Effluent Release Report documentation for a change in ODCM Section 9.0, including a revised figure(s) and table reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples for that pathway and justifoing the selection of the new location(s) for obtaining samples. 2 Removed in Revision 19. 3 The purpose of this sample is to obtain background information. lf 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. a Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hourc or more after sampling to allow for radon and thoron daughter decay. lf gross beta activity in air particulate samples is greater than 10 times that of control samples, gamma isotopic analysis shall be performed on the individual samples. 5 Gamma isotopic analysis means the identification and quantification of gammacmitting radionuclides that may be attributable to the effluents from the \AIBN plant. 6 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. E1-101

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 40 of 195 Table 2.3-l- MlNlilUM REQUIRED RADIOLOGICAL ENVIRONMENTAL iIONITORING PROGRAM (Page 5 of 5) TABLE NOTATION 7 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. ln this program composite sample aliquots shall be collected at time intervals that are very short (e.9., hourly) relative to the compositing period (e.9., monthly) in order to assure obtaining a representative sample. The composite sample shall be preserved according to plant procedures as appropriate. 8 Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination. Groundwater flow in the area of WBN has been shown to be toward Chickamauga Reservoir (Reference 9). There are no sources tapped for drinking or irrigation purposes between the plant and the reservoir. Therefore, sampling of the medium is not required. 9 The surface water control shall be considered a control for the drinking water samples. 10 The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in ODCM Section 7.4. 11 lf harvest occurs more than once a year, sampling shall be performed during each discrete harvest. lf harvest occurs continuously, sampling shall be monthly. Aftention shall be paid to including samples oftuberous and rootfood products. E1-102

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 41 of 195 Table2.3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS lN ENVIRONMENTAL SAMPLES Airborne Food Water Particulate or Fish Products Analysis (pCi/L)3 gases (pGi/Kg, wet)a Milk (pCi/L)3 (pCi/Kg, wetla (pCi/m3t5 H-3 20,0001 N/A N/A N/A N/A Mn-54 1,000 N/A 30,000 N/A N/A Fe-59 400 N/A 10,000 N/A N/A Co-58 1,000 N/A 30,000 N/A N/A Co-60 300 N/A 10,000 N/A N/A Zn-65 300 N/A 20,000 N/A N/A Zr-Nb-95 400 N/A N/A N/A N/A t-1 31 22 0.9 N/A 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2.000 Ba-La-140 200 N/A N/A 300 N/A 1 Footnote 1 deleted in Revision 20. 2 For drinking water samples. lf no drinking water pathway exists, value of 20 pCi/L may be used. 3 ttuttipty the values in this column by 10-e to convert to units of pCi/ml. + ttultiply the values in this column by 10-e to convert to units of pCi/g (wet). 5 Muftipty the values in this column by 1g-12 to convert to units of pCi/cc. E1-103

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 42 of 195 TAbtE 23A. DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ITTITYSIST,2. LOWER LIMITS OF DETECTIO]l (t-l-O)s (Page 1 of2) Airborne Particulate Food Water or Gases Fish (pc!/Kg, MiIK Products Sediment Analysis (pCi/L)o (pCi/m)8 wet)7 (pci/L)6 (pCi/Kg, wet)7 (pGi/Kg, dry)7 oross beta 4 0.01 N/A N/A N/A N/A H-3 20004 N/A N/A N/A N/A N/A Mn-54 15 N/A 130 N/A N/A N/A Fe-59 30 N/A 260 N/A N/A N/A Co-58, 60 15 N/A 130 N/A N/A N/A Zn-65 30 N/A 260 N/A N/A N/A Zr-95 30 N/A N/A N/A N/A N/A Nb-95 15 N/A N/A N/A N/A N/A l-131 15 0.07 N/A 1 60 N/A Cs-1 34 15 0.05 130 15 60 150 Cs-1 37 18 0.06 150 18 80 180 Ba-140 60 N/A N/A 60 N/A N/A La-140 15 N/A N/A 15 N/A N/A TABLE NOTATION 1 This list does not mean that only these nuclides are to be considered. Other nuclides that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Administrative Control 5.1. 2 Required detection capabilities for DOSIMETERs used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13. 3 The ttD is defined, for the purpose of these specifications, as the smallest concentration of r:adioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only a 5o/o probabili$ of falsely concluding that a blank observation represents a "real" signal. (Reference 8) For a particular measurement system (which may include radiochemical separation): 4.66 s6 LLD = EY 2.22 v e{+li)

       \Mrere:

LLD = the "a priori" lower limit of detection (pCi per unit mass or volume) s6 = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute) E = the counting efficiency (counts per disintegration) V = the sample size (units of mass or volume) 2.22 = the number of disintegrations per minute per picocurie E1- 104

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcttt) Page 43 of 195 TAbIE 2.33. DETECTION CAPABILTTIES FOR ENVIRONMENTAL SAMPLE ANALYSIST'2. LOWER Ltulrs oF DETEcflott (t-t-o)s (Page2ot2) Y = the fractional radiochemical yield, when applicable l = the radioactive decay constant for the particular radionuclide (sJ) Dt = the elapsed time between midpoint of environmental sample collection and time of counting (s). Typicalvalues of E, V, Y, and Dt should be used in the calculation. It should be recognized that the LLD is defined as an UIigIi(before the fact) limit representing the capability of a measurement system and not an a oosteriori (after the fact) limit for a particular measurement. Analysis will be performed in such a mannerthat the stated LLDs will 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. ln such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to ODCM Administrative Control 5.2. a lf no drinking water pathway exists, a value of 3,000 pCi/L may be used. s lf no drinking water pathway exists, a value of 15 pCi/L may be used. 6 Muftiply the values in this column by 1g-e to convert to units of pCi/ml. z tvtuttiply the values in this column by 1g-e to convert to units of pCi/g(wet). 8 tvtuttipty the values in this column by 10-12 to convert to units of pCi/cc. Tabte 2.34 - DETECTION CAPABILITIES FOR GROUNDWATER HARD-TO-DETECT NUCLIDES - LOWER LrMrrS OF DETECTION (LLD) ANALYSIS WATER (pCi/L)' Fe-55 200 Ni-63 30 Sr-89 1 Sr-90 5 Gross Alpha 4 1 Muftiply the values in this column by 10-e to convert to units of pCi/ml. E1-105

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 4 of 195 I/2 CONTROLS AND SURVEILLANCE REQUIREMENTS I /2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 112.3.2 LAND USE GENSUS CONTROLS 1.3.2 A Land Use Census shall be conducted and shall identiff within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectgrs of the nearest milk animal, the nearest residence, and the nearest garden* of greater than 50 m2 (SOO tP) producing fresh leafo vegetation.

       ' Broad leaf vegetation sampling of at least three difbrent kinds of vegetation may be perficrmed at the UNRESTRICTED AREA BOUNDARY in each of two difbrent direction seclors with the highest predicted D/Qs in lieu of the garden oensus. Controls for broad leaf vegetation sampling in Table 2.*1 Parl4.c., shall be followed, including analysis of control samples.

APPLICABILITY: At all times. ACTION:

a. \Mth a Land Use Survey identiffing a location(s) that yields a calculated dose or dose commitment greater than the values cunently being calculated in Control 2.2.2.3, pursuant to ODCM Administrative Controls 5.1 and 5.2, identiff the new location(s) in the next Annual Radioactive Effluent Release Report.

b. \Mrth a Land Use Census identiffing a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20o/o greater than at a location from which samples are currently being obtained in accordance with the requirements of ODCM Control 1.3.1, add the new location(s) within 30 days to the radiological environmental monitoring program given in ODCM Section 9.0, if samples are available. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted.

Pursuant to ODCM Administrative Controls 5.2 and 5.3, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM reflecting the new location(s) with the information supporting the change in sampling locations.

c. The provisions of SR 2.0.4 are not applicable.

SURVEILI.ANCE REQUIREMENTS 2.3.2 The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-todoor survey, mail survey, telephone survey, aerial survey, or by consulting local agricultural authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to ODCM Administrative Control 5.1. E1-106

WBN OFFSITE DOSE CALGUI..ATION MANUAL Revision 23 0 (oDcM) Page 45 of 1 95 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS I /2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1 12.9.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS 1.3.3 Analyses shall be performed on all radioactive materials, supplied as part of an lnterlaboratory Comparison Program which has been approved by the NRC, that correspond to samples required by Table 2.3-1. APPLICABILITY: At all times. ACTION: With analyses not being performed as required above, report the conective actions being taken to prevent a recurence to the NRC in the Annual Radiological Environmental Operating Report pursuant to ODCM Administrative Control 5. 1. The provisions of SR 2.0.4 are not applicable. SURVEILI.ANCE REQUIREMENTS 2.3.3 The lnterlaboratory Comparison Program shallbe described in ODCM Section 9.0. A summary of the results obtained as a part of the above required lnterlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to ODCM Administrative Control 5. 1. E1- 107

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 46 of 195 BASES FOR SECTIONS 1.0 AND 2.A CONTROLS AND SURVEILLANCE REQUIREMENTS NOTE The BASES contained in succeeding pages summarize the reasons for the Controls in Sections 1.0 and 2.0, but are not part of these Controls. E1-108

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 47 of 195 BASES FOR SECTTONS 1.0 AND 2.0 - CONTROLS AND SURVEILISNCE REQUIREMENTS I'2.1 INSTRUiIENTATION 1 12.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING I NSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual and potential releases of liquid effluents. The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in ODCM Section 6.2 to ensure that the alarm/trip will occur prior to exceeding ten times the concentration limits of 10 CFR 20. The OPERABILIW and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR 50. 1 12.1 .2 RADIOACTTVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual and potential releases of gaseous effluents. The radiation monitor alarm/trip setpoints for each release point are based on the radioactive noble gases in gaseous effluents. lt is not considered practicalto apply the instantaneous alarm/trip setpoints to integrating radiation monitors sensitive to radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases. The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in ODCM Sec{ion 7.1 to ensure that the alarm/trip will occur prior to exceeding the dose rate limits of ODCM Control 1.2.2.1. The OPEMBILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR 50. 1 12.1.3 METEOROLOGICAL INSTRUMENTATION/DATA The OPERABTLIW of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Programs," February 1972, ANSUANS-3.1'l-2O00, "Standard for Determining Meteorological lnformation at Nuclear Power Sites," 2000, Regulatory Guide 1.97, "lnstrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident," May 1983, and Supplement 1 to NUREG-0737, "Requirements for Emergency Response Capability (Generic Letter 82-33)," December 1982. The intervalforthe sensorcalibration portion of the CHANNEL CALIBRATION is based on the length of time a sensor has been in service (i.e., non-service or "shelf'time, not to exceed six months, is not included). NUREG-0452, "standard Technical Specifications for Westinghouse Pressurized Water Reactors," contained meteorological monitoring instrumentation requirements. As part of the Technical Specification lmprovement Program, these requirements have been split out of the Standard Technical Specifications. Therefore, the meteorological monitoring Control has been included in the ODCM. E1-109

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 48 of 195 1/2.2 RADIOACTIVE EFFLUENTS 112.2.1 LIQUID EFFLUENTS 1 t2.2.1.1 CONCENTRATTON This Control is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than 10 times the concentration values specified in Appendix B, Table 2, Column 2lo 10 CFR 20.'t00'l-20.2402. lt provides operationalflexibility for releasing liquid effluents in concentrations to follow the Section ll.A and ll.C design objectives of Appendix I to 10 CFR 50. This limitation provides reasonable assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section ll.A design objectMes of Appendix l, 10 CFR 50, to a MEMBER OF THE PUBLIC, and (2) restrictions authorized by 10 CFR 20.1301(e). The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its concentration in air (submersion) was converted to an equivalent concentration in water. This specification does not affect the requirement to comply with the annual limitations of 10 CFR 20.1301(a). This Control applies to the release of radioactive materials in liquid effluents from all reactors at the site. The required detection capabilities for mdioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed description of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 , Cunie, 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-21 5 (June 1 975). 112.2.1.2 DOSE This Control is provided to implement the requirements of Sections ll.A, lll.A, and lV.A of Appendix l, 10 CFR 50. The Control implements the guides set forth in Section ll.A of Appendix l. Compliance with this Control will be considered to demonstrate compliance with the 0.'1 rem limit of 1 0 CFR 20.1 301 (aXl ) per 56 FR23374. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section lV.A of Appendix I to assure that the releases of radioactive materials in liquid effluents to UNRESTRICTED AREAS will be kept "as low as reasonable achievable." Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculation methodology and parameters in the ODCM implement the requirements in Section lll.A of Appendix ! 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 section for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1 .109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50 Appendix 1," Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of lmplementing Appendix 1," April 1977. This Control applies to the release of radioactive materials in liquid efiluents from each unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.9., flow to each of the radioactive producing units sharing the Radwaste Treatment System. E1-1 10

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 49 of 195 For determining conformance to controls, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total release per site. For those nuclides whose activities are determined from composite samples (as noted in Table 2.2-1),lhe concentrations for the previous composite period will be assumed as the concentration for the next period to perform the calculations in ODCM Sections 6.'1 and 6.3. 112.2.1.3 LIQUID RADWASTE TREATMENT SYSTEM The OPEMBILITY of the LRTS ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The Control that the appropriate portions of this system be used when specified provides assurance that the releases of radioac{ive materials in liquid effluents will be kept "as low as reasonably achievable." This requirement implements the requirements of 10 CFR 50.36a, General Design Criteria 60 of AppendixA to 10 CFR 50 and the design objective given in Section ll.D of Appendix I to 10 CFR 50. The specified limits governing the use of appropriate portions of the liquid radwaste system were specified as a suitable fraction of the dose design objectives set forth in Section ll.A of Appendix l, 10 CFR 50, for liquid effluents. This Control applies to the release of radioactive materials in liquid effluents from each unit at the site. When shared LRTS are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.9., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases be allocated equally to each of the radioactive producing units sharing the LRTS. For determining conformance to controls, these allocations from shared LRTS are to be added to the releases specifically attributed to each unit to obtain the total release per site. 1 12.2.2 GASEOUS EFFLUENTS 112.2.2.1DOSE RATE This Control 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 in excess of the design objectives of Appendix I to 10 CFR 50. This Control is provided to ensure that gaseous effluents from all units on the site will be appropriately controlled. lt provides operational flexibility for releasing gaseous effluents to satisfy the Section ll.A and ll.C design object!1e3_o{Appendix I tq_-1O_QFR 50. For MEMBERS OF THE PUBLIC who may at times be within the CONTROLLED or RESTRICTED AREAS, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compelsate for the reduced atmospheric dispersion relative to that forthe UNRESTRICTED AREA BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits rgstqct, a! all_times, the correspolqlng_gqtln4g_{td beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the UNRESTRICTED AREA BOUNDARY to <500 mrem/y to the total body or to <3000 mrem/y to the skin. These limits also restrict, at alltimes, the corresponding thyroid dose rate above background to a child via the inhalation pathway to <1500 mrem/y. This Control does not affect the requirement to comply with the annual limitations of 10 CFR 20.1301(a). This requirement applies to the release of radioactive material in gaseous effluents from all reactors at the site. The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed description of the LLD, and other detection limits can be found in HASL Procedures Manual, fl{S!;QQQ, Cunie, 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-21 5 (June 1 975). For those nuclides whose activities are determined from composite samples (as noted in Table 1.2-1), the concentrations for the previous composite period will be assumed as the concentration for the next period to perform the calculations in ODCM Sections 7.2. E 1- 111

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 50 of 195 112.2.2.2 DOSE - NOBLE GASES This Control is provided to implement the requirements of Sections ll.B, lll.A and lV.A of Appendix l, 10 CFR 50. The requirement implements the guides set forth in Section l.B of Appendix l. Compliance with this control will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR 20.1301(a)(1) per 56 FR23374. The ACTIONS to be taken provide the required operating flexibility and at the same time implement the guides set forth in Section lV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as reasonably achievable." The surveillance implements the requirements in Section !!l.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 dose calculation methodology and parameters established in ODCM Section 7.3for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1 .1 09, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispercion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reaclors," Revision 1, July 1977. 'lhe equations provided for determining the air doses at and beyond the UNRESTRICTED AREA BOUNDARY are based upon the historical average atmospheric cond itions. This Control applies to the release of gaseous effluents from each reactor at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.9., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases be allocated equally to each of the radioactive producing units sharing the Radwaste Treatment System. For determining conformance to requirements, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total release per site. 112.2.2.3 DOSE.IODINE.{3I,IODINE.{33, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORi' WITH HALF.LIVES GREATERTHAN EIGHT DAYS This Control is provided to implement the requirements of Sections ll.C, lll.A and lV.A of Appendix l, 10 CFR 50. The Control implements the guides set forth in Section ll.C of Appendix l. Compliance with this controlwill be considered to demonstrate compliance wilh the 0.1 rem limit of 10 CFR 20.1301(a)(1) per 56 FR23374. The ACTION to be taken provides the required operating flexibili$ and at the same time implements the guides set forth in Section lV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as reasonably achievable." ODCM Section 7.4 calculational methods specified in the Surveillance Requirement implement the requirements in Section lll.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 appropriately modeled pathways is unlikely to be substantially underestimated. ODCM Section 7.4 calculational methodology and parameters for calculating the doses due to the aclual release rates of the subject materials are consistent with the methodologies provided in NUREG/CR-I004, 'A StatisticalAnalysis of Selected Parameters for Predicting Food Chain Transport and lnternal Dose of Radionuclides," October 1979 and Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1 , October 1977 and Regulatory Guide 1 .1 1 1 , "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 controls for l-131, l-133, tritium and particulate radionuclides with half-lives greater than eight days are dependent upon the existing radionuclide pathways to man in the areas at and beyond the UNRESTRICTED AREA BOUNDARY. The pathways that were examined in the development of the calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leaf, vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and beef producing animals graze with consumption of the milk and beef by man, and (4) deposition on the ground with subsequent exposure of man. E1-112

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 51 of 195 For those nuclides whose activities are determined from composite samples, the concentrations for the previous composite period will be assumed as the concentration for the next period to perform the calculations in ODCM Section 7.4. 112.2.2.4 GASEOUS RADWASTE TREATMENT SYSTEM The OPERABILIW of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The Control that the appropriate portions of these systems be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This requirement implements the requirements of 10 CFR 50.36a, General Design Criteria 60 of AppendixA to 10 CFR 50, and the design objectives given in Section ll.D of Appendix I to 10 CFR 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Section ll.B and ll.C of Appendix l, 10 CFR 50, for gaseous effluents. This Control applies to the release of radioactive materials in gaseous effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.9., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases be allocated equally to each of the radioactive producing units sharing the Radwaste Treatment System. For determining conformance to Controls, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total release per site. 1t2.2.3 TOTAL DOSE This Control is provided to meet the dose limitations of 40 CFR 190 that have been incorporated into 10 CFR 20.1301(d). The Control requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrem to the total body or any other organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. 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 190 if the individual reactors remain within twice the dose design objectives of Appendix I and if direct radiation doses from the units and from outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR 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 fuelcycle souroes 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. lf 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 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR20.2203(a)(4), is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR 20, as addressed in ODCM Contrcls 1.2.1.'l and 1.2.2.1. 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. Demonstration of compliance with the timits of 40 CFR 190 or with the design objectives of Appendix I to 10 CFR 50 will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR 20.130'1. The requirements for evaluating compliance with 40 CFR 302 are added to ensure compliance with these limits. The regulation states that federally permitted releases do not have to determine compliance with the reportable quantities unless the permitted release allowance is exceeded. E1-1 13

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 52 of 195 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1 12.3.1 ITiONITORING PROGRAM The Radiological Environmental Monitoring Program required by this Control provides representative 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 the plant operation. This monitoring program implements Section lV.B.2 of Appendix !to 10 CFR 50 and thereby supplements the Radiological Effluent Monitoring Program by veriffing that the measurable concentration of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979. The initially specified monitoring program will be effective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on operationalexperience. The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 2.3-3 are considered optimum for routine environmental measurements in industrial laboratories. lt should be recognized that the LLD is defined as an g pflggj (before the fact) limit representing the capability of a measurement system and not as g oosteriori (after the fact) limit for a particular measurement. Detailed description of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300, Cunie, 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 RadioanalyticalCounting Techniques,"Atlantic Richfield Hanford Company ReportARH-SA-215 (June 197s). 112.3.2 LAND USE CENSUS This Control is provided to ensure that changes in the use of areas at and beyond the UNRESTRICTED AREA BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of that census. The best information from the door-todoor survey, mail survey, telephone survey, aerial survey, or by consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section lV.B.3 of Appendix I to 10 CFR 50. Restricting the census to gardens of greater than 50 m2 provides assurancb that significant exposure pathwiys via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to provide the quantity (26 kg/y) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used, 1) that 20o/o ol the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2kglm2. E1- 114

WBN OFFSITE DOSE CALCUTATION MANUAL Revision 23 0 (oDcM) Page 53 of 195 1 12.3.3 INTERLABORATORY COMPARISON The Controlfor participation in an approved lnterlaboratory 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 assuranoe program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section lV.B.2 of Appendix lto 10 CFR 50. E1-1 15

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 54 of I 95 3.0 DEFINITIONS The defined terms in this section appear in capitalized type in the text and are applicable throughout these Controls and Bases. 3.1 ACTTON ACTION shall be that part of a Control that prescribes remedial measures required under designated conditions. 3.2 CHANNEL GALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel such that it responds within the necessary range and accuracy to known values of input. The CFIANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm, interlock, display, and/or trip functions. Calibration of instrument channels with resistance temperature detector or thermocouple sensors shall consist of an in place cross calibration of the remaining adjustable devices in the channel. \Alhenever a sensing element is replaced, the next required in place cross calibration consists of comparing the other sensing elements with the recently installed sensing element. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping channel calibrations or total channel steps such that the entire channel is calibrated. 3.3 CHANNEL CHECK A CHANNEL CHECK shallbe the qualitative assessment, by observation, of channelbehavior 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. 3.4 CHANNEL OPERATIONAL TEST A CHANNEL OPERATIONAL TEST shall be the injection of a simulated signal or actual signal into the channel as close to the sensor as practicable to veriff OPERABILIW of alarm, interlock, and/or trip functions. The CHANNEL OPERATIONAL TEST shall include adjustments, as necessary, of the required alarm, interlock, and/or trip setpoints such that the setpoints are within the required range and accuracy. 3.5 CONTROLLED AREA A CONTROLLED AREA, as defined in 10 CFR 20, is the area outside the RESTRICTED AREA but inside the 10 CFR 20 defined UNRESTRICTED AREA BOUNDARY, access to which can be limited by the licensee for any reason (see Figure 3.1). 3.6 DOSE EQUIVALENT I.{31 DOSE EQUIVALENT l-131 shall be that concentration of l-131 (pCi/g) that alone would produce the same thyroid dose as the quantity and isotopic mixture of l-131 , l-1 32, l-133, l-134, and l-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table E-7 ot NRC Regulatory Guide 1.109, Revision 1, October 1977. E1-1 16

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 55 of 1 95 3.0 DEFINITIONS 3.7 FREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 3.1. 3.8 MEiTBER(S) OF THE PUBLIC MEMBER(S) OF THE PUBLIC, as defined in 10 CFR 20, is any individual except when that individual is receiving an occupational dose. 3.9 itoDE A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 3.2 with fuel in the reactor vessel and reactor vessel head closure bolt tensioning. 3.IO OPERABLE - OPERABILIW A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILIW when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, normalor emergency electrical po\ rer, cooling and sealwater, lubrication and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified function(s) are also capable of performing their related support function(s). 3.II PURGE. PURGING PURGE or PURGING shall be any 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 puriff the confinement. 3.I2 RATED THERMAL POWER RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3459 MWt. 3.13 REPORTABLE EVENT A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10 CFR 50. 3.14 RESTRICTED AREA The RESTRICTED AREA, as defined in 10 CFR 20, is that area, access to which is limited by the licensee for the purposes of protecting individuals against undue risks from exposure to radiation and radioactive materials. RESTRICTED AREA does not include areas used as residential quarterc, but sepaete rooms in a residential building may be set apart as a RESTRICTED AREA (see Figure 3.1). E1-117

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 56 of 195 3.0 DEFINITIONS 3.I5 SITE BOUNDARY The site boundary is defined in 10 CFR 20 as that line beyond which the land or proper$ is not owned, leased, or othenarise controlled by the licensee (see Figure 3.1). 3.16 SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source or other channel sensor internal test circuits. 3.1 7 UNRESTRICTED AREA/U NRESTRICTED AREA BOU NDARY An UNRESTRICTED AREA, as defined in 10 CFR 20, shall be any area, access to which is not controlled by the licensee for the purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes 3.{8 VENTILATION EXHAUST TREATMENT SYSTEM A VENTILATION EXHAUST TREATMENT SYSTEM is any 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 VENTIIATION EXHAUST TREATMENT SYSTEM components. 3.19 VENTING 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 during VENTING. Vent, used in system names, does not imply a VENTING process. 3.20 WASTE GAS HOLDUP SYSTEM A WASTE GAS HOLDUP SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System offgases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. E1-1 18

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 57 of 195 Table 3.1 - FREQUENGY NOTATION NOTATION FREQUENCY S At least once per 12 hours. D At least once per 24 hours. W At least once per 7 days. M At least once per 31 days. o At Ieast once per 92 days. SA At least once per 184 days. 3Q At least once per 276 days. Y At least once per 365 days. R At least once per 18 months. N/A Not applicable. P Completed prior to each release.

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 58 of 195 Table 3.2 - OPERATIONAL MODES REACT!VITY CONDITION, % RATED THERMAL AVERAGE COOLANT MODE K.r POWER- TEMPERATURE

1. Power Operation > 0.99 > 5o/o N/A

2. Startup > 0.99 3 5o/o N/A

3. Hot Standby < 0.99 N/A > 350"F

4. Hot Shutdown** < 0.99 N/A 350"F)To.,..>200"F

5. Cold Shutdown** < 0.99 N/A < 200"F

6. Refuelinq*** N/A N/A N/A

Excluding decay heat.
- All reactor vessel head closure bolts fully tensioned.
  - One or more reactor vessel head closure bolts less than fully tensioned.

E1-120

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 59 of 1 95 Figure 3.1 - WBN SITE AREA MAP UNRESTRICTED AREA BOUNDARY RESTHICTED AREA BOUNDARY E1-121

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 60 of {95 4.0 - (NOT USED) 5.0 ADMINISTRATIVE CONTROLS 5.1 ANNUAL RADIOLOGICAL ENVIRONiIENTAL OPERATING REPORT As required by WBN TS 5.9.2, Routine Annual Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submifted prior to May 15 of each year. The annual radiologicalenvironmentaloperating reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, with operational controls, and with previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by ODCM Control1.3.2. The annual radiologicalenvironmentaloperating reports shall include summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. ln the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. The reports shall also include the following: a summary description of the radiological environmental monitoring program; at least two legible maps (one map shall cover stations near the UNRESTRICTED AREA BOUNDARY, a second shall include the more distant stations) covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; and the results of licensee participation in the lnterlaboratory Comparison Program and the corrective actions being taken if the specified program is not being performed as required by ODCM Control 1.3.1;discussion of all deviations from the sampling schedule of Table 2.3-1; reasons for not conducting the radiological environmental monitoring program as required by ODCM Control 1.3.1 and discussions of environmental sample measurements that exceed the reporting levels of Table 2.3-2 but are not the result of plant effluents, pursuant to action b. of ODCM Control 1.3.1; and discussion of all analyses in which the LLD required by Table 2.3-3 was not achievable. 5.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT As required by \NBN TS 5.9.3, a Radioactive Effluent Release Report covering the operation of the unit during the previous year shall be submitted prior to May 1 of each year. The period of the first report shall begin with the date of initial criticality. The Annual Radioactive Effluent Release Report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the units as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof, as applicable. Additional requirements for reporting solid waste are specified in the Process Control Proglam. The radioactive effluent release reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period. E1-122

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 6{ of 195 The radioactive effluent release reports shall include any changes made during the reporting period to the Process Control Program, and to the ODCM pursuant to ODCM Administrative Control 5.3, as well as any major changes to Liquid, Gaseous, or Solid Radwaste Treatment Systems, pursuant to IAIBN Technical Specifications. lt shall also include a listing of new location for dose calculations and/or environmental monitoring identified by the Land Use Census pursuant to ODCM Control 1.3.2. The radioactive effluent release reports shall also include the following: an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not conected within the time specified in ODCM Controls 1.1.1 or 1.1.2, respectively. The radioactive effluent release report shall include an annual summary of hourly meteorological data collected over the previous 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. ln lieu of submission with the radioactive effluent release report, this summary of required meteorological data may be retained on site in a file that shall be provided to NRC upon request. This same report shall include an assessment of the radiation doses due to radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the UNRESTRICTED AREA BOUNDARY during the report period. All assumptions used in making these assessments (i.e., specific activity, exposure time, and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with Sections 6.6 and 7.7. [SOURCE NOTE 8] The radioactive effluent release report shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuelcycle sources, including doses from primary effluents and direct radiation, for the previous calendar year to show conformance with 40 CFR 190, in accordance with ODCM Section 8.1. The radioactive effluent release report shall include results from any groundwater samples obtained during the reporting period that are not described in the ODCM. The radioactive effluent release report shall include any onsite radioactive spills or leaks, and their assigned doses that occurred during the reporting period. E1-123

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 62 of 195 5.3 OFFSITE DOSE CALCUI.ATION MANUAL CHANGES As required by WBN TS 5.7.2.3, changes to the ODCM:

1. Shall be documented and records of reviews performed shall be retained . This documentation shallcontain:

a. Sufficient information to support the change together with the appropriate analyses or evaluations justiffing the change(s) and

b. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302,40 CFR 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

2. Shall become effective after review and acceptance by the PORC and the approval of the Plant Manager.

3. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report forthe period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month/year) the change was implemented.

Changes to the ODCM shall be performed in accordance with the requirements of Appendix C. 5.4 SPECIAL REPORTS SpecialReports shallbe submitted in accordancewith 10 CFR Part SO.4.[SOURCE NOTE 161 5.5 40 CFR 302 REPORTING Any releases of radioactivity exceeding both the 40 CFR 190 dose limits and 40 CFR 302.4 reportable quantities, shall be reported immediately to the National Response Center in accordance with the requirements given in 40 CFR 302.6. E1-124

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 63 of 1 95 5,6 CHANGES TO RADWASTE TREATMENT SYSTEM Licensee-initiated major changes to the Radwaste Treatment Systems (liquid and gaseous) shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Plant Operations Review Committee (PORC). The discussion of each change shall contain:

1. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;

2. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;

3. A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems;

4. An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from those previously evaluated in the Final Safety Analysis Report;

5. An evaluation of the change, which shows that the expected maximum exposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the Final Safety Analysis Report;

6. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents, to the actual releases for the period prior to when the changes are to be made;

7. An estimate of the exposure to plant operating personnel as a result of the change;

8. Documentation of the fact that the change was reviewed and found acceptable by the PORC.

E1- 125

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 64 of 195 6.0. LIQUID EFFLUENTS !NTRODUCTION Radioactive liquid effluents from WBN enter the UNRESTRICTED AREA through the diffusers into the Tennessee River. There are four plant systems from which radioactive effluents are released. These are the Liquid Radwaste Treatment System (LRTS), the Condensate Demineralizer System, the Turbine Building Sump (TBS), and the Units 1 and 2 Steam Generator Blowdown (SGBD). Figure 6.1 provides an outline of these liquid release paths with associated radiation monitors. The LRTS, the Condensate Demineralizer System and the SGBDs flor into the Cooling Tower Blowdown (CTBD) for dilution. Each of these release paths is also monitored by a radiation monitor. These monitors perform two main functions: to identify any unexpected radioactivity releases, and to ensure that the concentration limits of ODCM Control '1.2.1.'l are not exceeded. Each monitor has an alarm/trip setpoint which will alarm if the monitor's setpoint is exceeded. Alarm and trip functions are not provided by separate devices, therefore the alarmftrip setpoint is a single calculated value. The monitors on the Radwaste, Condensate Demineralizer, and SGBD systems will alarm and isolate any release which exceeds the alarm/trip setpoint. The TBS radiation monitor will alarm if the setpoint is exceeded, but this monitor does not have an isolation function. Releases are made as either a batch or continuous release. Releases from Radwaste Tanks (see Figure 6.2) and the Condensate Demineralizer tanks (see Figure 6.3) are made as batch releases. The TBS and SGBD are continuous releases when flow exists. For batch releases, any tank to be released is sampled for radioactivity, as described in ODCM Section 6.1.1. The tank contents are analyzed to determine the maximum allowable release flow rates to ensure compliance with the concentration limits of ODCM Control 1.2.1.1as described in ODCM Section 6.1.2. The sampling results are also used to determine a setpoint for the associated radiation monitor for the release in accordance with ODCM Section 6.2.3. For continuous releases, the pathways are sampled for radioactivity periodically, as described in ODCM Section 6.1.1. The samples are analyzed to ensure compliance with the concentration limits of ODCM Control 1.2.'1.1, as described in ODCM Section 6.1.2. The sampling results are also used to determine a setpoint for the associated radiation monitor for the release in accordance with ODCM Section 6.2.3. Dose calculations are performed for each sampling period, or release, as applicable, to determine compliance with ODCM Control 1.2.1.2 as detailed in ODCM Sections 6.3 and 6.4. Once per month, the projected dose is calculated, as outlined in Section 6.5, to determine compliance with ODCM Control 1.2.1.3. The calculationalmethodologies are based on the guidance provided in NUREG 0133 and Regulatory Guide 1.109. The quantities of each radionuclide identified and released are input into a more rigorous calculation methodology, described in ODCM Section 6.6, to determine the individual and population doses to be reported to the NRC in the Annual Radioactive Effluent Release Report. These dose methodologies are based on the guidance provided in Regulatory Guide 1.109. E1- 126

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 65 of { 95 RELEASE POINTS Liquid Radwaste Treatment System The LRTS processes liquid from the Reactor Building and Auxiliary BuiHing Floor Drains, the CVCS Holdup Tanks, the Laundry/Hot Shower, the Waste Condensate Tanks and Chemical Drain Tanks. Figure 6.2 provides a schematic of the Liquid Radwaste System, showing the flow pathways and flow rates. The LRTS has individual release points for each of the tanks. The routine release points for liquid radwaste are the Monitor Tank and the Cask Decontamination Collector Tank (CDCT). The Monitor Tank has a capacity of 20,000 gal and can be released at a maximum design flow rate of 150 gpm. The CDCT has a capacity of 15,000 gal and can be released at a maximum design flow rate of '100 gpm. The Monitor Tank and CDCT discharge to the Cooling Tower Blowdown line as a batch release and are monitored by radiation monitor 0-RE-90-122. There is a flow interlock on the CTBD which suspends the release if the flow is less than 20,000 gpm. Condensate Demineralizer System The Condensate Demineralizer System liquid wastes are released from the High Crud Tanks (HCT-A and -B), the Neutralization Tank, and the Non-Reclaimable Waste Tank (NRWT). Figure 6.3 provides a schematic of the Condensate Demineralizer System, showing the flow pathways and flow rates. The HCTs have a capacity of 20,000 gal and a maximum design discharge flow rate of 150 gpm. The Neutralization Tank has a capacity of 20,000 gal and a maximum design discharge flow rate of 100 gpm. The NRWT has a capacity of 11,000 gal and a maximum design discharge flow rate of 30 gpm. Each of these tanks is defined as a release point for the system. \Mren tank contents are required to be permitted for radioactivity, the Condensate Demineralizer System waste is released to the CTBD line and is monitored by radiation monitor 0-RE-90-225. There is a flow interlock on the CTBD which suspends the release if the flout is less than 20,000 gpm. The low flow interlock may be bypassed and releases made from the Condensate Demineralizer System with less than 20,000 gpm CTBD flow provided the sum of the ratios of the ECLs for all release points is < 10. Turbine Building Sump The TBS normally releases to the Low Volume Waste Treatment Pond, but can be released to either the Metal Waste Cleaning Ponds or the 35 acre Yard Holding Pond. The TBS has a capacity of 57,783 gal and a design discharge release rate of 2,000 gpm per pump. The TBS is monitored by radiation monitor 0-RE-90-212. Steam Generator Blowdown The SGBD is processed in the Steam Generator Blowdown Flash Tanks or SGBD Heat Exchangers. Figure 6.3 provides a schematic of the SGBD System, showing the flow pathways and flow rates. The SGBD discharge has a maximum design flow rate of 65.5 gpm per steam generator when discharging to the Cooling Tower Blowdown. SGBD is recycled or is released to the CTBD line and monitored by radiation monitors 1,2-RE-90-120A and 1,2-RE-90-121. There is a flow interlock on the CTBD which suspends the release if the flow is less than 20,000 gpm. The low flow interlock may be bypassed and releases made from the Steam Generator Blowdown System with less than 20,000 gpm CTBD flow provided the sum of the ratios of the ECLs for all release points is < 10. Groundwater Sump The Groundwater Sump (GWS) normally releases to the 35 acre Yard Holding Pond via the storm drains. The GWS has a design discharge release rate of 300 gpm per pump. The GWS is not monitored by a radiation monitor^ E1- 127

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 66 of 195 6.I LIQUID RELEASES 6.1.1 Pre-Release Analysis Radwaste and Condensate Demineralizer tanks will be mixed for a period of time (specified in plant procedures) prior to sampling to ensure that a representative sample is obtained. Recirculation times to ensure adequate mixing will be established by testing. Periodically, checks will be made to ensure a representative mixing of tank contents. Prior to any batch release, a grab sample will be taken and analyzed in accordance with Table 2.2-1. Releases from the steam generator blowdown and turbine building sump are considered continuous. For continuous releases, daily grab or composile samples will be taken on days when releases are being made and analyzed in accordance with Table 2.2-1. Composite samples are maintained during periods of radioactive discharge from all pathways (as required by Table 2.2-1) to determine the concentration of certain nuclides (H-3, Fe-55, Sr-89, Sr-90, and gross alpha). For those nuclides whose activities are determined from composite samples, the concentrations for the previous composite period can be assumed as the concentration for the next period to perform the calculations in Sections 6.3 and 6.5. The actual measured concentrations will be used for the dose calculations described in Section 6.6. A maximum allowable waste flow rate, which will ensure compliance with ODCM Control 1.2.1.1, will be determined using Equations 6.1 and 6.2. Setpoints for the release are determined as described in Section 6.2. Dose calculations are performed in accordance with Section 6.3 6.1.2 Effluent Concentration Limits (ECL)um of the Ratios To determine release parameters to ensure compliance with ODCM Control 1 .2.1 .1 , a sum of the ratios calculation is performed. The sum of the ratios (R) for each release point will be calculated by the following relationship. R=r ci (6.1) T ECLl where: R = the sum of the ratios for the release point. ECL; = the ECL of radionuclide i, pCi/ml, from 10 CFR 20, Appendix B, Table 2, Column 2. C1 = concentration of radionuclide i, pCi/ml. The sum of the ECL ratios must be < '10 following dilution due to the releases from any or all of the release points described above. The ECL ratios for releases from the Turbine Building Sump will be < 10 at the sump. E1-128

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 67 of I 95 The following relationship is used to ensure that this criterion is met: Rres

tRt + fzRz + fsRs + f+R+ < I o.o (6.2)

F where: Rres = sum of the ECL ratios of the turbine building sump as determined by equation 6.1. fr,z,g,t = effluent flow rate for radwaste, condensate demineralizer system and the steam generator blowdowns, respectively, gPm. Rt,z,s+ = sum of ECL ratios for radwaste, condensate demineralizer system and the steam generator blowdowns, respectively, as determined by equation 6.1. p = dilution flow rate for CTBD. The minimum assumed flow of 20,000 gpm will be used for radwaste pre-release calculations. 6.1 .3 Post-Release Analysis A post-release evaluation will be done using actual release data to ensure that the limits specified in ODCM Control 1.2.1.1were not exceeded. A composite list of concentrations (Ci), by nuclide, will be used with the actual waste flow (f) and dilution (F) flow rates (or volumes) during the release. The data will be evaluated to demonstrate compliance with the limits in ODCM Control 1.2.1.1. [SOURCE NOTE 101 6.2 TNSTRUMENT SETPOINTS Liquid effluent monitor setpoints are determined to ensure that the concentration of radioactive material released at any time frcm the site to UNRESTRICTED AREAS does not exceed ten times the ECL limits referenced in ODCM Gontrol 1.2.1.1 and to identiff any unplanned releases. The liquid effluent radiation monitors and their setpoint information are outlined below: Pathway Monitor Default Setpoint Setpoint ODCM Limit Section ERCW 0-RE-90-133 Section 6.2.1 N/A 6.2.1 0-RE-90-1 34 0-RE-90-140 0-RE-90-141 Radwaste 0-RE-90-122 Section 6.2.2 S 6.2.2 Condensate 0-RE-90-225 Section 6.2.2 sr", 6.2.2 Demineralizer TBS 0-RE-90-212 Section 6.2.2 S 6.2.2 SGBD 1-RE-90-1204 Section 6.2.2 Sr", 6.2.2 2-RE-90-1204 1-RE-90-121 2-RE-90-121 E1-129

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 68 of 195 6.2.1 Process Discharge Point Monitor Setpoints (0-RE-90-133,-134,-140,-1411 The setpoints for the ERCW monitors (RE-90-1 33, -1U,-140,-141) must ensure that the concentration of radioactive materials released at any time from the site do not exceed the limits given in ODCM Control 1 .2.1.1 . Since this effluent stream will not routinely contain radioactivity, the setpoints for these monitors will be set at two times background to ensure that any radioactivity is identified. Site procedures will document and controlthis value. 6.2.2 Release Point Monitor Setpoints (0-RE0-{22;0-RE-90-225; 0-RE-90-212; {,2-RE-90-120A,-1211 The radiation monitor for batch release points, the Liquid Radwaste System and the Condensate Demineralizer System, monitors the undiluted waste stream as it comes out of a tank. The purpose of the monitor setpoints for these batch releases is to identiff any gamma-emifting release that is larger than expected and would have the potentialto exceed the limits after dilution. Setpoints are calculated as described by equations 6.3, 6.4, and 6.5 and may be set at a default value. Site procedures will document and controlthis value. The continuous release points, the Steam Generator Blowdowns, and the Turbine Building Sump, will not be releasing gamma-emitting radioactivity unless there is or has been a primary to secondary leak. lf this is the case, the continuous release points are monitored to identiff any gamma-emitting release that is larger than expected and would have the potential to exceed the ODCM Control 1.2.1.1 concentration limits after dilution. The monitor setpoints are calculated using Equations 6.3, 6.4, and 6.5 when this is the case. When these release points are being treated in this manner, a single release is defined as all effluent released through this point on a continuous bases for a period of time (usually one week). During periods when there is no identified primary to secondary leak, these monitors are set to < 2 times background. Site procedures will document and control these setpoint values. For each release from a release point, two setpoints are calculated: one based on the monitor response to the contents of the effluent stream (as described below in Equation 6.4); and another based on the predicted response of the monitor to the activi$ in the release stream if it were large enough to exceed ten times the 10 CFR 20 limits after dilution (as described below in Equation 6.5). A comparison is made between these two calculated setpoints and the lower of the two is used for the release. lf default setpoints are used then a comparison is made between the two calculated setpoints and the default setpoint as described below to choose the appropriate setpoint for the monitor during the release (after the release, the monitor is normally retumed to the defauh setpoint). 1 . lf Sen ( Sa"r"utt < Sr", Reported = Soeraun

2. lf Sen ( Sr", ( Soetault Reported = Sen

3. lf Sen ) Sr", Reported = Sr",

6.2.2.1 Expected Response An expected response (ER) is calculated for the monitor for each release: ER = BKG + y(Ei Ci ) (6.3) I where: BKG = monitor background, cpm. The monitor's background is controlled at an appropriate limit to ensure adequate sensitivig in accordance with site procedures. E; = monitor efficiency for nuclide i, cpm per pCi/ml. This term may also be referred to as a response or calibration factor. C; = tank concentration of nuclide i, pCi/ml. E1-130

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 69 of 195 6.2.2.2 Expected Response Setpoint An expected response setpoint Sgp is calculated for the monitor for each release: sr :XZ E,C, + X BKG (6.4) i where: X = administrative factors designed to account for expected variations in monitor response and background (as defined in plant procedures). The ranges of values are: 0< X < 2.0. 6.2.2.3 Calculated Maximum Monitor Setpoint A second setpoint is calculated for the release based on the predicted response of the monitor to the gamma-emitting activity in the release stream if it were large enough to exceed ODCM Control 1.2.'l..1 limits after dilution. This setpoint ensures that the release will be stopped if it exceeds this limit. The maximum calculated setpoint calculation must satisff the following relationship from NUREG-0133: sf <C m where: C = the effluent concentration limit from 10 CFR 20 Appendix B, Table 2, Column 2, in pCi/ml, represented by a value of 't. s = the setpoint, in pCi/ml, of the monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release. The setpoint, which is proportional to the volumetric flow of the effluent line and inversely proportional to the volumetric flow of the dilution stream, represents a value which, if exceeded, would result in release concentrations exceeding the limits of ODCM Control 1.2.1.1when the effluent enters the Tennessee River. f = the flow rate of the waste stream, gpm. F = the dilution flow rate, gpm. To determine the setpoint in cpm, lf no dilution is available, then s < C. Since C in the above equation represents the concentration equalto the limit, the setpoint s can be replaced by: s=c.D* where c" = the actualeffluent concentration, pCi/ml. Dreq = the required dilution factor. E1-131

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 70 of 195 The required dilution can be defined as: -R D,.q = i6TF where: R = the sum of the ratios for gamma-emitting radionuclides, as determined by equation 6.1. 10 = a value which implements the concentration limits of ODCM Control '1.2.'1.1. SF = a safety factor. The range of values for SF is: 0 < SF < 1. Substituting c" Dr"q into the above equation for s, substituting 1 for C, and solving for c": l0 SF tF + f) -"o-< ---------------: fR This value represents the amount that the expected response setpoint would be adjusted upward to account for the downstream dilution. For WBN, a portion of the total dilution flow is allocated to each release point using an allocation factor (AF). To determine the maximum calculated monitor setpoint, Sr"r, in cpm for a release point, the following equation is used: o sF(f + (ot ,0) I ox- l(en-BKG) +BKG (6.5) T R

where: AF = fraction of dilution flow allocated to this release point. For the TBS, AF = 0. The fractions for the remaining 4 release points are normally defined as the ratio of the allocated CTBD flow forthat release point to the total CTBD flow. The CTBD flow allocation fractions for these release points are routinely: Radwaste 0.6 Condensate dem i neral izer 0.2 Steam Generator Blowdown (U1) 0.1 Steam Generator Blowdown (U2) 0.1 These allocation factors may be adjusted for a particular release if it is known that there are no releases being made through other release points into the CTBD. For example, if there are no releases being made through the Condensate Demineralizer or either SGBD, the AF for the Radwaste System may be set equalto one. ER = expected monitor response, cpm, as calculated in Equation 6.3. BKG = background, cpm. E1-132

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 71 of 195 6.3 CUiiUt.ATtVE LIQUID EFFLUENT DOSE CALCULATIONS Doses due to liquid effluents are calculated for each release for the following age groups: adult (17 years and older), teen (11-17 years), child (1-11 years), infant (0-1 years) (Reference 4); and the following organs: bone, liver, totalbody, thyroid, skin, kidney, lung, and Gltract. Using the methodology presented in NUREG-0133, Section 4.3, doses due to liquid effluents are calculated for the ingestion of drinking water and freshwater fish consumption. Due to the amount of recreation along the Tennessee River, a dose for shoreline recreation is also calculated. This recreation dose is calculated by deriving a dose factor for use in the dose equation for the recreation pathway using equations A-4 and A in Regulatory Guide 1.109. Dose factors for these three pathways are calculated as described in Section 6.7. For pathways with no age or organ specific dose factors (i.e., shoreline recreation), the total body dose will be added to the intemal organ doses for all age groups. The consumption of freshwater invertebrates and consumption of food crops inigated with Tennessee River water are not considered significant pathways for the area surrounding V\/BN (References 9 and 10), so they are not considered in the dose calculations. The maximum individual dose from drinking water is assumed to be that calculated at the location immediately dornstream from the diffuser. The maximum individual dose from fish ingestion is assumed to be that calculated for the consumption of fish caught anywhere between the plant and the 100% mixing point downstream (Table 6.1). The maximum potential recreation dose is calculated for a location immediately dornstream of the plant outfall. The general equation for the dose to an organ j is: Dj --zAurciD (6.6) where: Aij- = the total dose factor to the total body or any organ j for nuclide i, mrem/h per pCi/ml. The total dose factor is the sum of the dose factors forwater ingestion, fish ingestion, and shoreline recreation, as defined in Section 6.7. T = the length of time period over which the concentrations and the flovvs are averaged, h. G; = the average concentration of radionuclide i, in undiluted liquid effluent during the time period T from any liquid release, pCi/ml. D = the near field average dilution factor for C; during any effluent release. D is calculated by the following equation:

     = Ol0,fx ,,

RF (6.7) where: f = maximum undiluted liquid waste flow during the release, cfs. For TBS releases, this term is the waste flow into the pond. 0.10 = mixing fraction of effluent in river, defined as the fraction of the riverflow which is available for dilution of the release (Reference 1 1). RF = default riverflow, cfs. For each release, this value is set to 25,657 cfs (the average quarterly riverflow recorded from the period 1985-94). From the four age groups considered, the maximum organ dose is determined by comparing all organ doses for all age groups. The age group with the highest single organ dose is selected as the critical age group. The total body and maximum organ doses for the critical age group are used in the calculation of the cumulative doses described in Section 6.3.1. E1-133

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 72 of I 95 6.3.1 Cumulative Doses Cumulative quarterly and annual sums of all doses are determined for each release to compare to the limits given in ODCM Control 1.2.1.2. These quarterly and annual sums will be the sum of the doses for each release which occurred in that quarter or year. These doses will be used in the comparison to the limits. 6.3.2 Comparison to Limits The cumulative calendar quarter and calendar year doses are compared to the limits in ODCM Control 1.2.1.2 at least once per 31 days to determine compliance. 6.4 LIQUID WASTE TREATMENT SYSTEM The LRTS described in the \NBN FSAR shall be maintained and operated to keep releases ALARA. A flow diagram for the LRTS is given in Figure 6.2. 6.5 DOSE PROJECTIONS ln accordance with ODCM Surveillance Requirements2.2.1.3.'l and2.2.1.3.2, dose projections will be performed at least once per 31 days using the equation below: (6.8) where. D= the 31-day dose projection, mrem. a= the cumulative dose for the quarter, mrem. b= the projected dose for this release, mrem. c= any anticipated additional dose in the next month from other sources, mrem. d= current number of days into the quarter up to the time of the release under consideration. E1- 134

WBN OFFSITE DOSE CALCULATpN MANUAL Revision 23 0 (oDcM) Page 73 of 195 6.6 DOSE CALCUTATIONS FOR REPORTING A complete dose analysis utilizing the total estimated liquid releases for each calendar quarter will be performed and reported as required in ODCM Administrative Control 5.2. Methodology forthis analysis is based on the methodology presented in Regulatory Guide '1.109 and is described in this section. The releases are assumed, for this calculation, to be continuous over the 90 day period. The near-field dilution factor, Dpp, usd for the quarterly calculations is: I DNr = (for receptors upstream of Tennessee River Mile 510.0) (6.e) 0., *, and DNr =+ (for receptors downstream of Tennessee River Mile 51 0.0) (6.10) where: RF = the avemge actual riverflow for the location at which the dose is being determined, cfs. 0.1 0 = the fraction of the riverflow available for dilution in the near field, dimensionless (Reference 11 ). Note: TRM 510.0 is the point at which the effluent is considered to be fully mixed with the riverflow (Reference 11). E1-135

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 74 of 195 6.6.1 tlUater lngestion Water ingestion doses are calculated for each water supply identified within a 50 mile radius downstream of \AIBN (Table 6.1). The water ingestion dose equation is based on Regulatory Guide 1 .1 09, Equation 1 :

,  =l( (*"r"')Eqi      Awoi exd-r,1t6)

For \NBN, the dilution factor (Mo/F) is replaced by the near field dilution factor (Dpp) described by Equations 6.9 and 6.10, and the usage factor (Uap) and dose conversion factors (Aw"i) are incorporated into the dose factor (as described in Section 6.7.1). The resulting equation for the water ingestion dose, Di, in mrem, to organ j is: Dj = l06 (9.80E-09) 0.25 t Awoi ei DNr exd-8.64Eo4tita) (6.1 1) where: 106 = conversion factor, pCi/Ci. 9.80E-09 = conversion factor, cfs per ml/h. 0.25 = fraction of the yearly water consumption in one quarter, dimensionless. Awri = dose factor for water ingestion for age group a, nuclide i, mrem/h per pCi/ml, as calculated in Section 6.7.1. Qi = quantlty of nuclide i released during the quarter, Ci. Drur = dilution factor, as described above, cts-1. li = radiological decay constant of nuclide i, s-1 Gable 6.2). t6 = decay time for water ingestion, equal to the travel time from the plant to the water supply plus one day to account for the time of processing at the water supply (per Regulatory Guide 1.109), d. 8.64E+04 = conversion factor, s/d. 6.6.2 Fish lngestion Fish ingestion doses are calculated for each identified reach within a 50 mile radius downstream of WBN (Table 6.1 ). The fish ingestion dose equation is based on Regulatory Guide 1 . 1 09, Equation 2: o=t. ['"'"t-] Eqi BiAroiiexd-l;t6) I F )T" For \AIBN, the dilution factor (My'F) is replaced by the near field dilution fac{or (Dpp) described by Equations 6.9 and 6.10, and the usage factor (U"j, bioaccumulation factor (B), and dose conversion factors (Ar";) are incorporated into the dose factcjr (as described in Section 6.7.2). The resulting equation forlhe fish ingestion dose D;, in mrem, to organ j is: Dj = l06 (9.80E-09) o.25IAro,i ei DNr exp(-8.64Eo4 rito) (6.12) where: 106 = conversion factor, pCi/Ci. 9.80E-09 = conversion factor, cfs per ml/h. 0.25 = fraction of the yearly fish consumption eaten in one quarter, dimensionless. AraU = dose factor for fish ingestion for nuclide i, age group a, organ j, mrem/h per pCi/ml, as calculated in Section 6.7.2. Qi = quantrty of nuclide i released during the quarter, Ci. Drur = dilution factor, as described above, cft-1. t; = radiological decay constant of nuclide i, s-1 Gable 6.2). E1-136

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 75 of 1 95 h = decay time for fish ingestion, equal to the travel time from the plant to the center of the reach plus one day to account for transit through the food chain and food preparation time (per Regulatory Guide 1.109), d. 8.64E+04 = conversion factor, s/d. 6.6.3 Shoreline Recreation Recreation doses are calculated for each identified reach within a 50 mile radius dornstream of WBN (Table 6.1). lt is assumed that the maximum exposed individual spends 500 hours per year on the shoreline at a location immediately downstream from the diffusers. This is a more conservative usage factor than that provided in Regulatory Guide 1.109. lt assumes that an individual visits the shoreline for an average of 10 hours per week for 50 weeks per year. The shoreline recreation dose equation is based on Regulatory Guide 1.109, Equation 3: For I/VBN, the dilution factor My'F is replaced by the near field dilution factor (Dpp) described by Equations 6.9 and 6.10, and the usage factor (Uap), shoreline width factor (SWF), radioactive halfJife (Ti), dose conversion factor (Anai;) and the second exponentialterm are incorporated into the dose factor (as described in Section 6.7.3). The resulting equation for the shoreline recreation dose D;, in mrem, to organ j is: (6.13) where: 106 = conversion factor, pCi/Ci. 9.80E-09 = conversion factor, cfs per ml/h. tt = recreation factor, used to account for the fact that the same amount of time will not be spent at a recreation site during each quarter (Reference 25). Recreation factors used are: 1st quarter - 0.1 2nd quarter - 0.3 3rd quarter - 0.4 4th quarter - 0.2. Anarj = dose factor for shoreline recreation for nuclide i, age group a, organ j, mrem/h per pCi/ml, as calculated in Section 6.7.3. gi = quantrty of nuclide i released during the quarter, Ci. Drur

  "'        = dilution factor, as described above, cfs-l 11           = radiological decay constant of nuclide i, s-l fiable 6.2).

td = decay time for recreation, equal to the travel time from the plant to the center of the reach, d. 8.64E+04 = conversion factor, s/d. E1- 137

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 76 of {95 6.6.4 Total Maximum lndividual Dose The total maximum individual quarterly total body dose for each age group a , D(tb)a, is obtained using the following equation: D(tb)a = Dyy + Dp + Dp (6.14) where: Dyy = the highest total body water ingestion dose for age group a from among all the public water supplies Dr = the highest total body fish ingestion dose for age group a from among allthe reaches Dn = the total body maximum shoreline recreation dose. The total maximum individual quarterly organ dose for each age group a and each organ j, D(org)s1, is obtained using the following equation: D(org)q; = Dw + Dr + Dn (6.15) where: Dw = the highest water ingestion dose for age group a and organ j from among all the public water supplies Dr = the highest fish ingestion dose for age group a and organ j from among allthe reaches DR = the maximum shoreline recreation dose for organ j. The total body dose is used for all organs except skin. The doses reported are the highest total body dose (selected from all age groups) and the highest maximum organ dose (selected from all remaining organs and all age groups). E1-138

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 77 of 195 6.6.5 Population Doses For determining population doses to the SO-mile population around the plant, an average dose is calculated for each age group and each pathway and then multiplied by the population and the fraction of the population in each age group. The population dose is determined using equation D-1 from Regulatory Guide 1.109: For I/VBN, the average individual doses (D1ma) are determined by obtaining the ratio of the average consumption rate to the maximum consuniption rate and multiplying this by the maximum individual dose. For water ingestion, the general equation used for calculating the population doses, POPWTR, in person-rem for a given Public Water Supply (PWS) is: (6.16) where: POPWTRi = water ingestion population dose to organ j, person-rem. fPa = fraction of population in each age group a (from NUREG CR-1004, table 3.39). Adult = 0.665 Child = 0.168 lnfant = 0.015 Teen = 0.153 POP, = population at PWS m. The 3 PWSs and their populations are listed in Table 6.1. ATMWa = ratio of average to maximum water ingestion rates for each age group a. The values for maximum water ingestion rates are given as U*" in Table 6.3. Average water ingestion rates, in Uy, (from Reference 4, Table E4) are: Adult = 370 Child = 260 lnfant = 260 Teen = 260 TV\IDOS66 = total individual water ingestion dose to organ j at PWS m, to the age group a (calculated as described in Section 6.6.1), mrem. 1O-3 = conversion factor for rem/mrem. For population doses resulting from fish ingestion the calculation assumes that all fish caught within a 50-mile radius downstream of WBN are consumed by local population. The total fish harvest is calculated by multiplying the average fish harvest for the Tennessee River (HVST) by the size of the river reach under consideration (APR). These terms replace POP,. The general equation for calculating population doses, POPF, in person-rem from fish ingestion of all fish caught within a 50-mile radius downstream is: (6.17) where: POPFj = totalfish ingestion population dose to organ j, person-rem. HVSI = fish harvest for the Tennessee River, 3.04 lbs/acre/y edible weight (Reference 12). APR = size of reach, acres (Table 6.1). TFDOS.4 = total fish ingestion dose to organ j for reach r, for the age group a, (calculated as described in Section 6.6.2), mrem. fPa = fraction of population in each age group a, as given above. FISHa = amount of fish ingested by each age group a, kg/y. Average fish ingestion rates, kg/y (Reference 4, Table E-4) are: Adult = 6.9 Child =2.2 Teen = 5.2 lnfant = 0.0 E1-139

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 78 of 195 453.6 = conversion factor, g/lb. to-3 = conversion factor, iem/mrem. 1O-3 = conversion factor, kg/g. For shoreline recreation, the total recreation dose is determined by multiplying the average dose rate (TSHDOS) to an individual by the number of visits to that river reach (SHVIS) and the length of the avemge visit (HRSVIS). The general equation used for calculating the population doses, POPR, in person-rem is: popRi = jrsnoos, sHvrsr HRSVrsr

' +

(6.18) 10" 8760et where: POPR; ' = total recreation population dose for all reaches to organ j, person-rem. rf = fraction of yearly recreation which occurs in that quarter, as given in Section 6.6.3. TSHDOS4 = total shoreline dose rate for organ j, in reach r, mrem/h. SHVIST = shoreline visits per year at each reach r, (Table 6.1). HRSVIST = length of average shoreline recreation visit at reach r, 5 hours. 10r = conversion factor, mrem/rem. 8760 = conversion factor, h/y. E1-140

WBN OFFSITE DOSE CALCUIATION MANUAL Revision 23 0 (oDcM) Page 79 of 195 6.7 LIQUID DOSE FACTOR EQUATIONS The general form of the liquid dose factor equation from NUREG-0133 is: A,i = ko u6B[ + r,rq) oq [*. where: ko = conversion factors. Uw = water consumption rate, Uy. Dw = dilution factor from the near field area within one4uarter mile of the release point to the potable water intake for water consumption, dimensionless. Up = fish consumption rate, kg/y. BF; = bioaccumulation factor for nuclide i in freshwater fish, pCi/kg per pCi/L. U; = invertebrate consumption rate, kg/y. DF; = ingestion dose conversion factor, mrem/pCi. Since the value of the term U; is negligible, VVBN will not be considering the dose from invertebrate ingestion and that portion of the equation is dropped. ln addition, a term is added to account for recreation. The near-field dilution factor is assigned a value of 1 in the water ingestion portion of the equation and is not used for WBN due to the use of riverflow as the dilution factor in the dose calculation. The resulting general dose factor equation is: A',i = ko (u* +ur eq) or' +r, UR cs DFGI where: ko.t = conversion factors. Up = recreation usage factor, h/y. C; = accumulation factor for buiidup of activity in sediment, p}itmz per pCi/L. DFG; = dose factor for standing on contaminated ground, mrem/h per pCi/m2. The equations for each of the individual pathway dose factors are presented in the following sections. 6.7.1 Water lngestion Dose Factor - AwaU (mrem/h per pCi/ml) to6to3 DFs;; Awoii=-ffi

^                       Uvyq (6.1e) where:

DFaii = ingestion dose conversion factor for nuclide i, age a, organ j, mrem/pCi, (Table 6.4). Uwa = water consumption rate for age group a, Uy, (Table 6.3). 106 = convercion factor, pCi/pCi. 103 = conversion factor, mUL. 8760 = conversion factor, h/y. E1-141

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 80 of 195 6.7.2 Fish lngestion Dose Factor - Ara[ (mrem/h per pCi/ml) lo5lo3 DF6;1U16 ft

^rou =-EZ6- (6.20) where: DFaii = ingestion dose conversion factor for nuclide i, age a, organ j, mrem/pCi, (Table 6.4). Ufa = fish consumption rate for age group a, kg/y, Oable 6.3). Bi = bioaccumulation factor for nuclide i, pCi/kg per pCi/L, (Table 6.5). 106 = conversion factor, pCi/pCi. 103 = conversion factor, mUL. 8760 = conversion factor, h/y. 6.7.3 Shoreline Recreation Dose Factor - Anal (mrem/h per pCi/ml). Equation A in Regulatory Guide 1 .1 09 provides a methodology for calculating the dose due to shoreline recreation along a water body: Dose = k Kc u swF r, oroo

                  ?c,*          [r-exd-l,to) ]

Since the terms C;yy and T are part of the dose equation (Equation 6.6), the equation for the dose factor becomes: (6.21) Anoi = f, exp(-}, to) I { } where: DFGI = dose conversion factor for standing on contaminated ground for nuclide i and organ i (total body and skin), mrem/h per pCi/m', (Table 6.6). l& = transfer coefficient from water to shoreline sediment, Ukg-h, (Table 6.3). M = mass density of sediment, kg/m2, (Table 6.3). SWF = shoreline width factor, dimensionless, (Table 6.3). 103 = convercion factor, mUL. 106 = conversion factor, pci/pCi. 3600 = conversion factor, s/h. li = decay constant for nuclide i, s-t, 6able 6.2;. t6 = time shoreline is exposed to the concentration of the water, s, (Table 6.3). Up = recreation usage factor, 500 h/y. 8760 = conversion factor, h/y. E1- 142

WBN OFFSITE DOSE CALGULATION MANUAL Revision 23 0 (oDcM) Page 81 of 195 Table 6.1 - RECEPTORS FOR LIQUID DOSE CALCULATIONS Tennessee River Reaches Within 50 Mile Radius Downstream of WBN Beginning Ending Sizel Recreationz Name TRM TRM (acres) visits/y Chickamauga Lake (from \A/BN to 528 51 03 4799 85,200 100o/o mixing point) Chickamauga Lake (from 100o/o mixing 51 03 484 22101 914,000 point to Sequoyah Nuclear Plant) Chickamauga Lake (from Sequoyah 484 471 9889 5,226,700 Nuclear Plant to Chickamauga Dam) Nickajack Lake (from Chickamauga 471 460 1 799 200,000 Dam to WBN S0-mile radius) TRM - Tennessee River Mile. 1 Reference 13. 2 Reference 14. 3 100o/o Mixing Point (Reference 1 1). Public Water Supplies Within 50 Mile Radius Downstream of WBN Name TRM 1990 Population Dayton, TN 504 13,500 Soddy-Daisy/Falling 487 10,000 Water Utility District East Side Utility, TN 473 35,000 Chattanooga, TN 465 167,500 NOTE: Tennessee river mile locations are rounded to the nearest mile for dose calculation purposes. E1-143

WBN OFFSITE DOSE CALCUTATION MANUAL Revision 23 0 (oDcM) Page 82 of {95 Table 6.2 . RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA (Page 1 of 3) Half-Life I Bi, Fmi Fmi F6 Nuclide (minutes) (s-{) (cow) (goat) (beef) H-3 6.46E+06 1.79E-09 4.80E+00 1.00E-02 1.70E-01 1.20E-02 c-14 3.01 E+09 3.84E-12 5.50E+00 1.20E.02 1.00E-01 3.1 0E-02 Na-24 9.00E+02 1.28E-05 5.20E-02 4.00E-02 4.00E-02 3.00E-02 P-32 2.06E+04 5.61 E-07 1.10E+00 2.50E-02 2.50E-01 4.60E-02 Cr-51 3.99E+04 2.90E-07 2.50E-04 2.20E-03 2.20E-03 2.40E-03 Mn-54 4.50E+05 2.57E-08 2.90E-02 2.s0E-04 2.50E-04 8.00E-04 Mn-56 1.55E+02 7.45E-05 2.90E-02 2.50E-04 2.50E-04 8.00E-04 Fe-55 1.42E+06 8.13E-09 6.60E-04 1.20E-03 1.30E-04 1.20E-02 Fe-59 6.43E+04 1.80E-07 6.60E-04 1.20E-03 1.30E-04 1.20E-02 Co-57 3.90E+05 2.96E-08 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Co-58 1 .02E+05 1 .1 3E-07 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Co-60 2.77E+06 4.17E-09 9.40E-03 1.00E-03 1.00E-03 1.30E-02 NL63 5.27E+07 2.19E-10 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Ni-65 1.51E+02 7.65E-05 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Cu-64 7.62E+02 1.52E-05 1.20E-01 1.40E-02 1.30E-02 9.70E-04 Zn-65 3.52E+05 3.28E-08 4.00E-01 3.90E-02 3.90E-02 3.00E-02 Zn-69m 8.26E+02 1.40E-05 4.00E-01 3.90E-02 3.90E-02 3.00E-02 Zn-69 5.56E+01 2.08E-04 4.00E-01 3.90E-02 3.90E-02 3.00E-02 Br-82 2.12E+03 5.45E-06 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Br-83 1.43E+02 8.08E-05 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Br-84 3.1 8E+01 3.63E-04 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Br-85 2.87E+00 4.02E-03 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Rb-86 2.69E+0+ 4.29E-07 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Rb-88 1.78E+01 6.49E-04 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Rb-89 1.54E+01 7.50E-04 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Sr-89 7.28E+04 1.59E-07 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-90 1.50E+07 7.70E-10 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-91 5.70E+02 2.03E-05 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-92 1.63E+02 7.09E-05 1.74E-02 1.40E-03 1.40E-02 6.00E-04 Y-90 3.85E+03 3.00E-06 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-91m 4.97E+01 2.32E-04 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-91 8.43E+04 1.37E-07 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-92 2.12E+02 5.45E-05 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-93 6.06E+02 1.91E-05 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Zr-95 9.22E+04 1.25E-07 1.70E-04 5.00E-06 5.00E-06 3.40E-02 Zr-97 1.01 E+03 1.14E-05 1.70E-04 5.00E-06 5.00E-06 3.40E-02 Nb-95 5.05E+04 2.29E-07 9.40E-03 2.s0E-03 2.50E-03 2.80E-01 Nb-97 7.21 E+01 1.60E-04 9.40E-03 2.50E-03 2.50E-03 2.80E-01 Mo-99 3.96E+03 2.92E-06 1.20E-01 7.50E-03 7.50E-03 1.10E-03 Tc-99m 3.61 E+02 3.20E-05 2.50E-01 2.50E-02 2.50E-02 4.00E-01 Tc-1 01 1.42E+01 8.13E-04 2.50E-01 2.s0E-02 2.50E-02 4.00E-01 Ru-103 5.67E+04 2.04E-07 5.00E-02 1.00E-06 1.00E-06 4.00E-01 E1- 144

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 83 of I 95 Table 6.2 - RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA (Page 2 of 3) Half-Life I Br Fmi Fmt Fn Nuclide (minutes) (s{) (cow) (goat) (bee0 Ru-105 2.66E+02 4.34E-05 5.00E-02 1.00E-06 1.00E46 4.00E-01 Ru-106 5.30E+05 2.18E-08 5.00E-02 1.00E-06 1.00E-06 4.00E-01 Ag-1 10m 3.60E+05 3.21E-08 1.50E-01 5.00E-02 5.00E-02 1.70E-02 sb-124 8.67E+04 '1.33E-07 N/A 1.50E-03 1.50E-03 N/A sb-125 1.46E+06 7.91E-09 N/A 1.50E-03 1.50E-03 N/A Te-1 25m 8.35E+04 1.38E-07 1.30E+00 1.00E-03 1.00E-03 7.7OE-O2 Te-1 27m 1.57E+05 7.36E-08 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-127 5.61E+02 2.06E-05 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-129m 4.ilE+04 2.39E-07 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-129 6.96E+01 1.66E-04 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-1 31m 1.80E+03 6.42E-06 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-1 31 2.50E+01 4.62E-04' 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-132 4.69E+03 2.46E-06 1.30E+00 1.00E-03 1.00E-03 7.7OE-02 t-130 7.42E+02 1.56E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03 t-131 1.16E+04 9.96E-07 2.00E-02 1.20E-02 4.30E-01 2.90E-03 t-132 1.38E+02 8.37E-05 2.00E-02 '1.20E-02 4.30E-01 2.90E-03 t-133 1.25E+03 9.24E-06 2.00E-02 1.20E-02 4.30E-01 2.90E-03 t-134 5.26E+01 2.20E-0/. 2.00E-02 1-20E-02 4.30E-01 2.90E-03 t-135 3.97E+02 2.91E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03 Cs-1 34 1.08E+06 1.06E-08 '1.00E-02 8.00E-03 3.00E-01 1.50E-02 Cs-1 36 1.90E+04 6.08E-07 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Cs-1 37 1.59E+07 7.26E-10 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Cs-1 38 3.22E+01 3.59E-04 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Ba-1 39 8.31E+01 1.39E-04 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-140 1.&4E+O4 6.28E-07 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-141 1.83E+0'l 6.31E-04 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-142 1.07E+01 1.08E-03 5.00E-03 4.00E-04 4.00E-04 3.20E-03 La-140 2.41E+03 4.79E-06 2.50E-03 5.00E-06 5.00E-06 2.00E-04 La-142 9.34E+01 '1.21E-U 2.50E-03 5.00E-06 5.00E-06 2.00E-04 Ce-141 4.68E+04 2.47E-07 2,50E-03 1.00E-04 1.00E-04 1.20E-03 Ce-143 1.98E+03 5.83E-06 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Ce-144 4.09E+0s 2.82E-08 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Pr-143 1.95E+04 5.92E-07 2.50E-03 5.00E-06 5.00E-06 4.70E-03 Pr-144 1.73E+01 6.68E-04 2.50E-03 5.00E-06 5.00E-06 4.70E-03 Nd-147 1.58E+04 7.3'lE-07 2.40E-03 5.00E-06 5.00E-06 3.30E-03 w-187 1.43E+03 8.08E-06 1.80E-02 5.00E-04 5.00E-04 1.30E-03 Np-239 3.39E+03 3.41E-06 2.50E-03 5.00E-06 5.00E-06 2.0OE U Ar41 1.10E+02 1.05E-04 N/A N/A N/A N/A Kr-83m 1.10E+02 1.05E-04 N/A N/A N/A N/A Kr-85m 2.69E+02 4.29E-05 N/A N/A N/A N/A Kr-85 5.64E+06 2.05E-09 N/A N/A N/A N/A Kr-87 7.63E+01 1.51E-04 Il/A N/A N/A N/A E1-145

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 84 of ,l95 Table 6.2. RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA (Page 3 of 3) Half-Life I Biu tr rml Fmi Fri Nuclide (minutes) (s'1) (cow) (goat) (beef) Kr-88 1.70E+02 6.79E-05 N/A N/A N/A N/A Kr-89 3.16E+00 3.66E-03 N/A N/A N/A N/A Kr-90 5.39E-01 2.14E-02 N/A N/A N/A N/A Xe-1 31m 1.70E+04 6.79E-07 N/A N/A N/A N/A Xe-1 33m 3.1 5E+03 3.67E-06 N/A N/A N/A N/A Xe-1 33 7.55E+03 1.53E-06 N/A N/A N/A N/A Xe-1 35m 1.54E+01 7.50E-04 N/A N/A N/A N/A Xe-1 35 5.47E+02 2.11E-05 N/A N/A N/A N/A Xe-137 3.83E+00 3.02E-03 N/A N/A N/A N/A Xe-1 38 1 .41E+01 8.19E-04 N/A N/A N/A N/A

References:

All nuclides half-lives from: Reference 15. Transfer factors for Sb- isotopes: Reference 16 Table 2-7. Cow-milk transfer factors for l, Sr, and Cs nuclides are from Reference 21 , Table 3.17 . Goat-milk transfer factors for I nuclides are from Reference 21 , Table 3.17 . Beef transferfactors for Fe, Cu, Mo, and Cs nuclides are from Reference 21, Table 3.18. All other nuclides transfer factors are from Reference 4, Tables E-1 and E-2. E1-146

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 85 of I 95 Table 6.3 - DOSE CALCULATION FACTORS (Page 1 ot 2) Factor Value Units Reference BR" (infant) 1400 m3/y Reference 20 BR" (chiH) 5500 m3/y Reference 20 BR, (teen) 8000 m3/v Reference 20 BR" (adult) 81 00 m3/y Reference 20 fs 1 Conservatively assumes all stored vegetables are grown locallv. fr 1 Reference 4 (Table E-1 5)

f. 1 see Note f" 0 see Note H I g/m3 TVA Value Kc 0.072 L/kq-h Reference 4 (Section 2.C.)

M 40 kslmz Reference 4 (Section 2.C.) P 240 kslmz Reference 4 (Table E-1 5) Qr (cow) 64 ks/dav Reference 21 (Sect. 3.4) Qr (goat) 08 kg/day Reference 21 (Sect. 3.4) r 0.47 Reference 21 (Sect. 3.2) tr, 4.73E+08 (15 y) S Reference 4 fiable E-15) tcn 7.78E+06 (90 d) s Reference 10. Section 1 1 .3.9.1 tr:sf 1.56E+07 (180 d) S Reference 10, Section 1 1 .3.9.1 t 5.18E+06 (60 d) S Reference 4 fiable E-1 5) Reference 4 fiable E-1 5) Lo 2.59E+06 (30 d) S Lst 7.78E+06 (90 d) S Reference 4 ffable E-1 5) tr- 8.64E+04 fi d) S Reference 10, Section 1 1 .3.9.1 tn" 8.64E+04 fi d) S Reference 21 , Table 3.40 ts 1.12E+06(13 d) S Reference 21 , Table 3.40 t=, 2.38E+07e75 dl S Reference 10. Section 1 1 .3.9.1 U,- (infant) 0 ks/v Reference 4 (Table E-5) U,- (child) 41 ks/y Reference 4 ffable E-5) U,- (teen) 65 ks/y Reference 4 (Table E-5) U,- (adult) 110 ks/y Reference 4 (Table E-5) Note: Calculations for release permits use the conservative value given in the table for these parameters. The calculations performed for reporting purposes (as described in Section 7.7) use actual grazing percentages identified in the land use census. E1- 147

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 86 of 195 Table 6.3 - DOSE CALCUTATION FACTORS (Page 2 ot 2) Factor Value Units Reference Ur. (infant) 330 Uy Reference 4 (Table E-5) U,^ (child) 330 UY Reference 4 ffable E-5) Ur. (teen) 400 Uy Reference 4 (Table E-5) U,^ (adult) 310 Uv Reference 4 ffable E-5) Ur"(infant) 0 kq/v Reference 4 ffable E-5) Ur"(child) 6.9 kq/v Reference 4 ffable E-5) Ur"(teen) 16 ks/v Reference 4 ffable E-5) Ur"(adult) 21 kq/v Reference 4 ffable E-5) Un , (infant) 0 kq/v Reference 4 ffable E-5) Urr , (child) 26 ks/v Reference 4 ffable E-5) Un (teen) 42 ks/y Reference 4 (Table E-5) Un (adult) 64 kq/y Reference 4 ffable E-5) Us, (infant) 0 kq/y Reference 4 ffable E-5) U.q, (child) s20 ko/v Reference 4 ffable E-5) Us, (teen) 630 kq/y Reference 4 ffable E-5) Us, (adult) 520 kq/y Reference 4 ffable E-5) Uw"(infant) 330 Llv Reference 4 ffable E-5) Uw"(child) 510 UY Reference 4 ffable E-5) Uw"(teen) 510 Uv Reference 4 ffable E-5) Uw"(adult) 730 LIY Reference 4 ffable E-5) SWF 0.2 none Reference 4 ffable A-2) Yr 1.85 kslmZ Reference 21 ffable 3.4) Y"t 1.18 kolmz Reference 21 ffable 3.3) Ycf 0.64 kslmZ Reference 21 ffable 3.3) Yw 0.57 kglmz Reference 21 (Table 3.4) (value selected is for non-leaff veqetables) Iry (iodines) 7.718-07 st Reference 21 (Table 3.10) n5.4 d half-life) lw (particulates) 5.21E-07 sr Reference 21 (Table 3.10) (10.4 d half-life) E1- 148

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 87 of 195 Table 6.4 - INGESTION DOSE FACTORS - DFari (mrem/pCi ingested) (Page 1 of 8) ADULT Nuclide bone liver total body thyroid kidney lung GI-LLI H-3 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 c-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 s.68E-07 5.68E-07 5.68E-07 Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 0.00E+00 0.00E+00 0.00E+00 2.17E-05 Cr-51 0.00E+00 0.00E+00 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 Mn-54 0.00E+00 4.57E-06 8.72E-07 0.00E+00 1.36E-06 0.00E+00 1.40E-05 Mn-56 0.00E+00 1.15E-07 2.04E-08 0.00E+00 1.46E-07 0.00E+00 3.67E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 0.00E+00 0.00E+00 1.06E-06 1.09E-06 Fe-59 4.34E-06 1.02E-05 3.91 E-06 0.00E+00 0.00E+00 2.85E-06 3.40E-05 Co-57 0.00E+00 1.75E-07 2S1E-07 0.00E+00 0.00E+00 0.00E+00 4.44E-06 Co-58 0.00E+00 7.45E-07 1.67E-06 0.00E+00 0.00E+00 0.00E+00 1 .51E-05 Co-60 0.00E+00 2.14E-06 4.72E-06 0.00E+00 0.00E+00 0.00E+00 4.02E-05 Ni-63 1.30E-04 9.01E-06 4.36E-06 0.00E+00 0.00E+00 0.00E+OO 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 0.00E+00 0.00E+00 0.00E+00 1.74E-06 Cu-64 0.00E+00 8.33E-08 3.91E-08 0.00E+00 2.10E-07 0.00E+OO 7.1 0E-06 Zn-65 4.84E-06 1.54E-05 6.96E-06 0.00E+00 1.03E-05 0.00E+00 9.70E-06 Zn9 1.03E-08 1.97E-08 1.37E-09 0.00E+00 1.28E-08 0.00E+00 2.96E-09 Zn9m 1.70E-07 4.08E-07 3.73E-08 0.00E+00 2.47E-07 0.00E+00 2.49E-05 Br-82 0.00E+00 0.00E+00 2.26E-06 0.00E+00 0.00E+00 0.00E+00 2.59E-06 Br-83 0.00E+00 0.00E+00 4.02E-08 0.00E+00 0.00E+00 0.00E+00 5.79E-08 Br-84 0.00E+00 0.00E+00 5.21E-08 0.00E+00 0.00E+00 0.00E+00 4.09E-13 Br-85 0.00E+00 0.00E+00 2.14E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.11E-05 9.83E-06 0.00E+00 0.00E+00 0.00E+00 4.16E-06 Rb-88 0.00E+00 6.05E-08 3.21E-08 0.00E+00 0.00E+00 0.00E+00 8.36E-19 Rb-89 0.00E+00 4.01E-08 2.82E-08 0.00E+00 0.00E+00 0.00E+00 2.33E-21 Sr-89 3.08E-04 0.00E+00 8.84E-06 0.00E+00 0.00E+00 0.00E+00 4.94E-05 Sr-90 7.58E-03 0.00E+00 1.86E-03 0.00E+00 0.00E+00 0.00E+00 2.19E-04 Sr-91 5.67E-06 0.00E+00 2.29E-07 0.00E+00 0.00E+00 0.00E+00 2.70E-05 Sr-92 2.15E-06 0.00E+00 9.30E-08 0.00E+00 0.00E+00 0.00E+00 4.26E-05 Y-90 9.62E-09 0.00E+00 2.58E-10 0.00E+00 0.00E+00 0.00E+00 1.02E-04 Y-91m 9.09E-1 1 0.00E+00 3.52E-12 0.00E+00 0.00E+00 0.00E+00 2.67E-10 Y-91 1.41E-07 0.00E+00 3.77E-09 0.00E+00 0.00E+00 0.00E+00 7.76E-05 Y-92 8.45E-1 0 0.00E+00 2.47E-11 0.00E+00 0.00E+00 0.00E+00 1.48E-05 Y-93 2.68E-09 0.00E+00 7.40E-11 0.00E+00 0.00E+00 0.00E+00 8.50E-05 Zr-95 3.04E-08 9.75E-09 6.60E-09 0.00E+00 1.53E-08 0.00E+00 3.09E-05 Zr-97 1 .68E-09 3.39E-10 1.55E-1 0 0.00E+00 5.12E-10 0.00E+00 1.05E-04 Nb-95 6.22E-09 3.46E-09 1.86E-09 0.00E+00 3.42E-09 0.00E+00 2.1 0E-05 Nb-97 5.22E-11 1.32E-11 4.82E-12 0.00E+00 1.54E-11 0.00E+00 4.87E-08 Mo-99 0.00E+00 4.31 E-06 8.20E-07 0.00E+00 9.76E-06 0.00E+00 9.99E-06 Tc-99m 2.47E-10 6.98E-10 8.89E-09 0.00E+00 1.06E-08 3.42E-10 4.13E-07 Tc-1 01 2.54E-10 3.66E-10 3.59E-09 0.00E+00 6.59E-09 1.87E-10 1.10E-21 Ru-103 1.85E-07 0.00E+00 7.97E-08 0.00E+00 7.06E-07 0.00E+00 2.16E-05 Ru-105 1.54E-08 0.00E+00 6.08E-09 0.00E+00 1.99E-07 0.00E+00 9.42E-06 Ru-106 2.75E-06 0.00E+00 3.48E-07 0.00E+00 5.31E-06 0.00E+00 1.788-04 E1- 149

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 88 of 195 Table 6.4 - INGESTION DOSE FACTORS - DFaU (mrem/pCi ingested) (Page2 of 8) ADULT Nuclide bone liver tota! body thyroid kidney lung GI-LLI Ag-1 10m 1.60E-07 1.48E-07 8.79E-08 0.00E+00 2.91E-07 0.00E+00 6.04E-05 sb-124 2.80E-06 5.29E-08 1.11E-06 6.79E-09 0.00E-00 2.18E-06 7.95E-05 sb-125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 0.00E-00 1.38E-06 1.97E-05 Te-1 25m 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 0.00E+00 1.07E-05 Te-1 27m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 0.00E+00 2.27E-05 Te-127 .10E-07 3.95E-08 2.38E-08 8.15E-08 1 4.48E-07 0.00E+00 8.68E-06 Te-129m .15E-05 4.29E-06 .82E-06 3.95E-06 1 1 4.80E-05 0.00E+00 5.79E-05 Te-129 3.14E-08 .1 8E-08 7.65E-09 2.41E-08 1 1.32E-07 0.00E+00 2.37E-08 Te-1 31m 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 0.00E+00 8.40E-05 Te-1 31 1.97E-08 8.23E-09 6.22E-09 .62E-08 1 8.63E-08 0.00E+00 2.79E-09 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 0.00E+00 7.71E-05 I-130 7 .56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 0.00E+00 1.92E-06 r-131 4.16E-06 5.95E-06 3.41E-06 .95E-03 1 1.02E-05 0.00E+00 1.57E-06 t-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 0.00E+00 1.02E-07 t-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 0.00E+00 2.228-06 l-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0.00E+00 2.51 E-10 r-1 35 4.43E-07 .16E-06 4.28E-07 7.65E-05 1 1 .86E-06 0.00E+00 1 .31E-06 Cs-1 34 6.22E-05 1.48E-04 1.21E-04 0.00E+00 4.79E-05 1.59E-05 2.59E-06 Cs-1 36 6.51 E-06 2.57E-05 1.85E-05 0.00E+00 1.43E-05 1.96E-06 2.92E-06 Cs-1 37 7.97E-05 .09E-04 7 .14E-05 0.00E+00 1 3.70E-05 1.23E-05 2.11E-06 Cs-1 38 5.52E-08 .09E-07 5.40E-08 0.00E+00 1 8.01E-08 7.91E-09 4.65E-13 Ba-1 39 9.70E-08 6.91 E-1 1 2.84E-09 0.00E+00 6.46E-1 1 3.92E-1 1 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 0.00E+00 8.67E-09 1 .46E-08 4.1 8E-05 Ba-141 4.71E-08 3.56E-1 1 1.59E-09 0.00E+00 3.31E-11 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-11 .34E-09 0.00E+00 1 1.8sE-1 1 1.24E-11 3.00E-26 La-140 2.50E-09 1.26E-09 3.33E-1 0 0.00E+00 0.00E+00 0.00E+00 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-11 0.00E+00 0.00E+00 0.00E+00 4.25E-A7 Ce-141 9.36E-09 6.33E-09 7.18E-10 0.00E+00 2.94E-09 0.00E+00 2.42E-05 Ce-143 .65E-09 1.22E-06 .35E-10 0.00E+00 1 1 5.37E-10 0.00E+00 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-08 0.00E+00 1.21E-07 0.00E+00 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 0.00E+00 2.13E-09 0.00E+00 4.03E-05 Pr-144 3.01E-1 1 1.25E-11 1.53E-12 0.00E+00 7 .05E-12 0.00E+00 4.33E-18 Nd-147 6.29E-09 7 .27E-09 4.35E-10 0.00E+00 4.25E-09 0.00E+00 3.49E-05 W-1 87 1.03E-07 8.61E-08 3.01E-08 0.00E+00 0.00E+00 0.00E+00 2.82E-05 Np-239 .1 9E-09 .17E-10 6.45E-1 1 0.00E+00 1 1 3.65E-10 0.00E+00 2.40E-05

References:

Dose Factors for Co-57, Zn69m, Br-82, Nb-97, Sb-124, Sb-125 are from Refercnce 17,Table 4. All others are from Reference 4, Table E-11. NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. This assumes that tritium will act similarly in all organs (Reference 24). E1-150

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 89 of 195 Table 6.4 - INGESTION DOSE FACTORS - DFaU (mrem/pCi ingested) (Page 3 of 8) TEEN Nuclide bone liver total body thyroid kidney lung GI.LLI H-3 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 c-14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.768-04 1.71E-05 1.07E-05 0.00E+00 0.00E+00 0.00E+00 2.32E-05 Cr-51 0.00E+00 0.00E+00 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 Mn-54 0.00E+00 5.90E-06 1 .17E-06 0.00E+00 1 .76E-06 0.00E+OO 1.21E-05 Mn-56 0.00E+00 1.58E-07 2.81E-08 0.00E+00 2.00E-07 0.00E+00 1.04E-05 Fe-55 3.78E-06 2.68E-06 6.25E-07 0.00E+00 0.00E+00 1.70E-06 1 .16E-06 Fe-59 5.87E-06 1.37E-05 5.29E-06 0.00E+00 0.00E+00 4.32E-06 3.24E-05 Co-57 0.00E+00 2.38E-07 3.99E-07 0.00E+00 0.00E+00 0.00E+00 4.44E-06 Co-58 0.00E+00 9.72E-07 2.248-06 0.00E+00 0.00E+00 0.00E+00 1.34E-05 Co-60 0.00E+00 2.81E-06 6.33E-06 0.00E+00 0.00E+00 0.00E+00 3.66E-05 Ni-63 1.77E-04 1.25E-0s 6.00E-06 0.00E+00 0.00E+00 0.00E+00 1.99E-06 Ni-65 7.498-07 9.57E-08 4.36E-08 0.00E+00 0.00E+00 0.00E+OO 5.19E-06 Cu-64 0.00E+00 .15E-07 1 5.41E-08 0.00E+00 2.91E-07 0.00E+00 8.92E-06 Zn-65 5.76E-06 2.00E-05 9.33E-06 0.00E+00 1.28E-05 0.00E+00 8.47E-06 Zn-69 1.47E-08 2.80E-08 1.96E-09 0.00E+00 1.83E-08 0.00E+00 5.16E-08 Zn-69m 2.40E-07 5.66E-07 5.19E-08 0.00E+00 3.44E-07 0.00E+00 3.11E-05 Br-82 0.00E+00 0.00E+00 3.04E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 5.74E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 7.22E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+OO Br-85 0.00E+00 0.00E+00 3.05E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.98E-05 1.40E-05 0.00E+00 0.00E+00 0.00E+00 4.41 E-06 Rb-88 0.00E+00 8.52E-08 4.54E-08 0.00E+00 0.00E+00 0.00E+00 7.30E-1 5 Rb-89 0.00E+00 5.50E-08 3.89E-08 0.00E+00 0.00E+00 0.00E+00 8.43E-17 Sr-89 4.40E-04 0.00E+00 1.26E-05 0.00E+00 0.00E+00 0.00E+00 5.24E-05 Sr-90 8.30E-03 0.00E+00 2.05E-03 0.00E+00 0.00E+00 0.00E+00 2.33E-04 Sr-91 8.07E-06 0.00E+00 3.21E-07 0.00E+00 0.00E+00 0.00E+00 3.66E-05 Sr-92 3.05E-06 0.00E+OO 1.30E-07 0.00E+00 0.00E+00 0.00E+00 7.77E-05 Y-90 1.37E-08 0.00E+00 3.69E-10 0.00E+00 0.00E+00 0.00E+00 1 .1 3E-04 Y-91m 1.29E-1 0 0.00E+00 4.93E-12 0.00E+00 0.00E+00 0.00E+OO 6.09E-09 Y-91 2.01E-07 0.00E+00 5.39E-09 0.00E+00 0.00E+00 0.00E+00 8.24E-05 Y-92 1.21E-09 0.00E+OO 3.50E-1 1 0.00E+00 0.00E+00 0.00E+00 3.32E-05 Y-93 3.83E-09 0.00E+00 1.05E-1 0 0.00E+00 0.00E+00 0.00E+OO 1.17E-04 Zr-95 4.12E-08 1.30E-08 8.94E-09 0.00E+00 1.91E-08 0.00E+00 3.00E-05 Zr-97 2.37E-09 4.69E-1 0 2.16E-10 0.00E+00 7 .11E-10 0.00E+00 1.278-04 Nb-95 8.22E-09 4.56E-09 2.51 E-09 0.00E+00 4.42E-09 0.00E+00 1.95E-05 Nb-97 7 .37E-11 1.83E-1 1 6.68E-12 0.00E+00 2.14E-11 0.00E+00 4.37E-07 Mo-99 0.00E+00 6.03E-06 1.15E-06 0.00E+00 1 .38E-05 0.00E+00 1.08E-05 Tc-99m 3.32E-1 0 9.26E-1 0 1.20E-08 0.00E+00 1.38E-08 5.14E-10 6.08E-07 Tc-1 01 3.60E-1 0 5.12E-10 5.03E-09 0.00E+00 9.26E-09 3.12E-10 8.75E-17 Ru-103 2.55E-07 0.00E+00 1.09E-07 0.00E+00 8.99E-07 0.00E+00 2.1 3E-05 Ru-105 2.1 8E-08 0.00E+00 8.46E-09 0.00E+00 2.75E-07 0.00E+00 1.76E-05 Ru-106 3.92E-06 0.00E+00 4.94E-07 0.00E+00 7.56E-06 0.00E+00 1.88E-04 E1-151

WBN OFFSITE DOSE CALCUTATION MANUAL Revision 23 0 (oDcM) Page 90 of 195 Table 6.4 - INGESTION DOSE FACTORS - DFa1 (mrem/pCi ingested) (Page 4 of 8) TEEN Nuclide bone liver totalbody thyroid kidney lung Gl-LLl Ag-110m 2.05E-07 1.94E-07 1.18E-07 0.00E+00 3.70E-07 0.00E+00 5.45E-05 sb-124 3.87E-06 7.13E-08 1.51E-06 8.78E49 0.00E-00 3.38E-06 7.80E-05 Sb-125 2.48E-06 2.71E-08 5.80E-07 2.37E-09 0.00E+OO 2.18E-06 1.93E-05 Te-125m 3.83E-06 1.38E-06 5.12E-07 1.07E-06 0.00E+00 0.00E+00 1.13E-05 Te-127m 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 0.00E+00 2.41E45 Te-127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 0.00E+00 1.22E-Os Te-129m 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 0.00E+00 6.12E-05 Te-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 0.00E+00 2.45E-07 Te-131m 2.4r'.E-06 1.17E-06 9.76E-07 1.76E-06'1.22E-05 0.00E+00 9.39E-05 Te-131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 0.00E+00 2.29E-09 Te-132 3.49E-06 2.21E-6 2.08E-06 2.33E-06 2.12E-05 0.00E+OO 7.00E-05 l-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 0.00E+00 2.29E-06 I-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 0.00E+00 1.62E-06 l-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 0.00E+00 3.18E-07 l-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 0.00E+00 2.58E-06 l-134 1.46E47 3.87E-07 1.39E-07 6.45E-06 6.10E-07 0.00E+00 5.10E-09 l-135 6.10E{7 1.57E-06 5.82E-07 1.01E44 2.48E-06 0.00E+00 1.74E-06 Cs-134 8.37E-05 1.97E-04 9.14E-05 0.00E+00 6.26E-05 2.39E-05 2.45E-06 Cs-136 8.59E-06 3.38E-05 2.27E-05 0.00E+00 1.84E-05 2.90E-06 2.72E-06 Cs-137 1.'l2E-04 1.49E-04 5.19E-05 0.00E+00 5.07E-05 1.97E-05 2.12E-06 Cs-138 7.76E-08 1.49E-07 7.45E-08 0.00E+00 1.10E-07 1.28E-08 6.76E-11 Ba-139 1.39E-07 9.78E-11 4.05E-09 0.00E+00 9.22E-11 6.74E-'l'l 1.24E-06 Ba-140 2.84E-05 3.48E-08 1.83E-06 0.00E+00 1.18E-08 2.34E-08 4.38E-05 Ba-141 6.71E-08 5.01E-11 2.24E-09 0.00E+00 4.65E-11 3.43E-11 1.43E-13 Ba-142 2.99E-08 2.99E-11 1.84E-09 0.00E+00 2.53E-11 1.99E-11 9.18E-20 La-140 3.48E-09 '1.71E-09 4.55E-10 0.00E+00 0.00E+00 0.00E+00 9.82E-05 La-142 1.79E-10 7.95E-11 1.98E-11 0.00E+00 0.00E+00 0.00E+00 2.42E-Oo Ce-141 1.33E-08 8.88E-09 1.02E-09 0.00E+00 4.18E-09 0.00E+00 2.54E45 Ce-143 2.35E-09 1.71E-06 1.91E-10 0.00E+00 7.67E-10 0.00E+00 5.14E-05 Ce-144 6.96E-07 2.88E-07 3.74E-08 0.00E+00 1.72E-07 0.00E+00 1.75E-04 Pr-143 1.31E-08 5.23E-09 6.52E-10 0.00E+00 3.04E-09 0.00E+00 4.31E-05 Pr-144 4.30E-1 'l 1.76E-11 2.18E-12 0.00E+00 1 .01E-11 0.00E+00 4.74E-'14 Nd-147 9.38E-09 1.02E-08 6.11E-10 0.00E+00 5.99E-09 0.00E+00 3.68E-05 W-187 1.46E-O7 1.19E-07 4.17E-08 0.00E+00 0.00E+00 0.00E+00 3.22E-05 Np-239 1.76E-09 1.66E-10 9.22E-1'l 0.00E+00 5.21E-10 0.00E+00 2.67E-05

References:

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124, Sb-125 are from Reference 9, Table 4. All others are from Reference 4, Table E-12. NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. This assumes that tritium will act similarly in all organs (Reference 24). E1-152

WBN OFFSITE DOSE CALCUI.ATION MANUAL Revision 23 0 (oDcM) Page 91 of 195 Table 6.4 - INGESTION DOSE FACTORS - DFari (mrem/pCi ingested) (Page 5 of 8) CHILD Nuclide bone liver total body thyroid kidney lung GI-LLI H-3 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 c-14 1.21E-05 2.42E-06 2.428-06 2.42E-06 2.42E-06 2.428-06 2.42E-06 Na-24 5.80E-06 5.80E-06 5.80E-06 s.80E-06 5.80E-06 5.80E-06 s.80E-06 P-32 8.25E-04 3.86E-05 3.18E-05 0.00E+00 0.00E+00 0.00E+00 2.28E-05 Cr-51 0.00E+00 0.00E+00 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 Mn-54 0.00E+00 1.07E-05 2.85E-06 0.00E+00 3.00E-06 0.00E+OO 8.98E-06 Mn-56 0.00E+00 3.34E-07 7.54E-08 0.00E+00 4.04E-07 0.00E+00 4.84E-05 Fe-55 1 .15E-05 6.1 0E-06 1.89E-06 0.00E+00 0.00E+00 3.45E-06 1 .1 3E-06 Fe-59 1.65E-05 2.67E-05 1.33E-05 0.00E+00 0.00E+00 7.74E-06 2.78E-05 Co-57 0.00E+00 4.93E-07 9.98E-07 0.00E+00 0.00E+00 0.00E+00 4.04E-06 Co-58 0.00E+00 1.80E-06 5.51E-06 0.00E+00 0.00E+00 0.00E+00 1.05E-05 Co0 0.00E+00 5.29E-06 1.56E-05 0.00E+00 0.00E+00 0.00E+00 2.93E-05 Ni-63 5.38E-04 2.88E-05 1.83E-05 0.00E+00 0.00E+00 0.00E+00 1.94E-06 Ni-65 2.22E-06 2.09E-07 1.22E-07 0.00E+00 0.00E+00 0.00E+OO 2.56E-05 Cu-64 0.00E+00 2.45E-07 1.48E-07 0.00E+00 5.92E-07 0.00E+00 1 .1 5E-05 Zn-65 1.37E-05 3.65E-05 2.27E-05 0.00E+00 2.30E-05 0.00E+00 6.41E-06 Zn4,9 4.38E-08 6.33E-08 5.85E-09 0.00E+00 3.84E-08 0.00E+00 3.99E-06 Zn-69m 7.10E-07 1.21E-06 1.43E-07 0.00E+00 7.03E-07 0.00E+00 3.94E-05 Br-82 0.00E+00 0.00E+00 7.55E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 1.71E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 1.98E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 9.12E-09 0.00E+00 0.00E+00 0.00E+OO 0.00E+00 Rb-86 0.00E+00 6.70E-05 4.12E-05 0.00E+00 0.00E+00 0.00E+00 4.31E-06 Rb-88 0.00E+00 1.90E-07 1.32E-07 0.00E+00 0.00E+00 0.00E+00 9.32E-09 Rb-89 0.00E+00 1.17E-07 1.04E-07 0.00E+00 0.00E+00 0.00E+00 1.02E-09 Sr-89 1.32E-03 0.00E+00 3,77E-05 0.00E+00 0.00E+00 0.00E+00 5.1 1E-05 Sr-90 1.70E-02 0.00E+00 4.31E-03 0.00E+00 0.00E+00 0.00E+00 2.29E-04 Sr-91 2.40E-05 0.00E+OO 9.06E-07 0.00E+00 0.00E+00 0.00E+00 5.30E-05 Sr-92 9.03E-06 0.00E+00 3.62E-07 0.00E+00 0.00E+00 0.00E+00 1.71E-04 Y-90 4.11E-08 0.00E+00 1 .10E-09 0.00E+00 0.00E+00 0.00E+00 1.17E-04 Y-91 m 3.82E-10 0.00E+00 1.39E-1 1 0.00E+00 0.00E+00 0.00E+00 7.48E-07 Y-91 6.02E-07 0.00E+00 1.61E-08 0.00E+00 0.00E+00 0.00E+00 8.02E-05 Y-92 3.60E-09 0.00E+00 1.03E-10 0.00E+00 0.00E+00 0.00E+00 1.04E-04 Y-93 1.14E-08 0.00E+00 3.13E-10 0.00E+00 0.00E+00 0.00E+00 1.70E-04 Zr-95 1 .16E-07 2.55E-08 2.27E-08 0.00E+00 3.65E-08 0.00E+00 2.66E-05 Zr-97 6.99E-09 1 .01E-09 5.96E-1 0 0.00E+00 1.45E-09 0.00E+00 1.53E-04 Nb-95 2.25E-08 8.76E-09 6.26E-09 0.00E+00 8.23E-09 0.00E+00 1.62E-05 Nb-97 2.17E-10 3.92E-1 1 1.83E-1 1 0.00E+00 4.35E-1 1 0.00E+00 1.21E-05 Mo-99 0.00E+00 1.33E-05 3.29E-06 0.00E+00 2.84E-05 0.00E+OO 1 .10E-05 Tc-99m 9.23E-1 0 1.81E-09 3.00E-08 0.00E+00 2.63E-08 9.19E-10 1.03E-06 Tc-1 01 1.07E-09 112E-09 1.42E-08 0.00E+00 1 .91E-08 5.92E-1 0 3.56E-09 Ru-103 7.31E-07 0.00E+00 2.81E-07 0.00E+00 1.84E-06 0.00E+00 1.89E-05 Ru-105 6.45E;08 0.00E+00 2.34E-08 0.00E+00 5.67E-07 0.00E+00 4.21 E-05 Ru-106 1 .17E-05 0.00E+00 1.46E-06 0.00E+00 1.58E-05 0.00E+00 1.828-04 E1-153

WBN OFFSITE DOSE CALCUI.ATION MANUAL Revision 23 0 (oDcM) Page 92 of {95 Table 6.4 - INGESTION DOSE FACTORS - DFa1 (mrem/pCi ingested) (Page 6 of 8) CHILD Nuclide bone liver totalbody thyroid kidney lung GI-LLI Ag-110m 5.39E-07 3.64E-07 2.91E-07 0.00E+00 6.78E-07 0.00E+00 4.33E-05 Sb-124 '1.11E-05 '1.44E-07 3.89E-06 2.45E48 0.00E+00 6.16E-06 6.94E-05 Sb-125 7.16E-06 5.52E-08 1.50E-06 6.63E-09 0.00E+00 3.99E-06 1.71E-05 Te-125m 1.14E-05 3.09E-06 1.52E-06 3.20E-06 0.00E+00 0.00E+00 1.10E-05 T*127m 2.89E-05 7.78E-06 3.43E-06 6.91E-06 824E-05 0.00E+00 2.34E-05 T+127 4.71E-07 1.27E-07 '1.01E-07 3.26E-07 1.34E-06 0.00E+00 1.84E-05 Te-129m 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 0.00E+00 5.94E-05 Te-129 1.34.E-O7 3.74E-08 3.18E-08 9.56E-08 3.92E-07 0.00E+00 8.34E-06 Te-131m 7.20E46 2.49E-06 2.65E-06 5.12E-06 2A1E-05 0.00E+00 1.01E-04 Te-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 0.00E+00 4.36E-07 Te-132 1.01E-05 4.47E-06 5.40E-06 6,51E-06 4.'t5E-05 0.00E+00 4.50E-05 l-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 0.00E+00 2.76E-06 f-131 1.72E45 1.73E-05 9.83E-06 5.72E43 2.84E-05 0.00E+00 1.54E-06 l-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0.00E+00 1.73E-06 f-133 5.92E-06 7.32E-06 2.77E-06 1.36E43 1.228-05 0.00E+00 2.95E-06 l-1U 4.19E-07 7.78E-07 3.58E47 1.79E-05 1.19E-06 0.00E+00 5.16E-07 l-135 1.75E-06 3.15E-06 1.49E-06 2.79E44 4.83E-06 0.00E+00 2.40E-06 Cs-134 23/E-04 3.84E-04 8.10E-05 0.00E+00 1.19E-04 4.27E-05 2.07E-06 Cs-135 2.35E-05 6.46E-05 4.18E-05 0.00E+00 3.44E-05 5.13E-06 2.27E-06 Cs-137 3.27E-U 3.13E-04 4.62E-05 0.00E+00 1.02E-U 3.67E-05 1.96E-06 Cs-138 2.28E-07 3.17E-07 2.01E-07 0.00E+00 2.23E-07 2.40E-08 1.46E-07 Ba-139 4.14E47 2.21E-10 1.20E-08 0.00E+00 1.93E-10 1.30E-10 2.39E-05 Ba-140 8.31E-05 7.28E-08 4.85E-06 0.00E+00 2.37E-08 4.34E-08 4.21E-Os Ba-141 2.00E-07 '1.128-10 6.51E-09 0.00E+00 9.69E-11 6.58E-10 1.14E-O7 Ba-142 8.74E-08 6.29E-11 4.88E-09 0.00E+00 5.09E-1'1 3.70E-11 1.14E-09 La-140 1.01E-08 3.53E-09 1.19E-09 0.00E+00 0.00E+00 0.00E+00 9.84E-05 La-142 5.24E-10 1.67E-10 5.23E-11 0.00E+00 0.00E+00 0.00E+00 3.31E-05 Ce-'141 3.97E-08 1.98E-08 2.94E-09 0.00E+00 8.68E-09 0.00E+00 2.47E-05 Ce-143 6.99E-09 3.79E-06 5.49E-10 0.00E+00 1.59E-09 0.00E+00 5.55E-05 Ce-144 2.08E-06 6.52E-07 1.'l1E-07 0.00E+00 3.61E-07 0.00E+00 1.70E-U Pr-143 3.93E-08 1.18E-08 1.95E-09 0.00E+00 6.39E-09 0.00E+00 4.24E-05 Pr-144 1.29E-10 3.99E-11 6.49E-12 0.00E+00 2.11E-'11 0.00E+00 8.59E-08 Nd-147 2.79E-08 2.26E-08 1.75E-09 0.00E+00 1.24E-08 0.00E+00 3.58E-05 W-187 4.29E-07 2.54E47 1.14E-07 0.00E+00 0.00E+00 0.00E+00 3.57E-05 Np-239 5.25E-09 3.77E-10 2.65E-10 0.00E+00 1.09E-09 0.00E+00 2.79E-Os

References:

Dose Factors for Co-57, Zn9m, Br-82, Nb-97, Sb-124, Sb-125 are from Reference 17,Table 4. All others are from Reference 4, Table E-13. NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. This assumes that tritium will act similarly in all organs (Reference 24). E1-154

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 93 of 1 95 Table 6.4 - INGESTION DOSE FACTORS - DFaU (mrem/pCi ingested) (Page7 of 8) INFANT Nuclide bone liver total body thyroid kidney lung GI.LLI H-3 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 c-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Na-24 1.01E-05 1.01E-05 1 .01 E-05 1 .01 E-05 1 .01E-05 1.01 E-05 1.01 E-05 P-32 1.70E-03 1.00E-04 6.59E-05 0.00E+00 0.00E+00 0.00E+00 2.30E-05 Cr-51 0.00E+00 0.00E+00 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 Mn-54 0.00E+00 1.99E-05 4.51E-06 0.00E+00 4.41E-06 0.00E+00 7 .31 E-06 Mn-56 0.00E+00 8.'l8E-07 1.41E-07 0.00E+00 7.03E-07 0.00E+00 7.43E-05 Fe-55 1.39E-05 8.98E-06 2.40E-06 0.00E+00 0.00E+00 4.39E-06 1 .14E-06 Fe-59 3.08E-05 5.38E-05 2.12E-05 0.00E+00 0.00E+00 1.59E-05 2.57E-05 Co-57 0.00E+00 .15E-06 1 1.87E-06 0.00E+00 0.00E+00 0.00E+00 3.92E-06 Co-58 0.00E+00 3.60E-06 8.98E-06 0.00E+00 0.00E+00 0.00E+00 8.97E-06 Co-60 0.00E+00 1.08E-05 2.55E-05 0.00E+00 0.00E+00 0.00E+00 2.57E-05 Ni-63 6.34E-04 3.92E-05 2.20E-05 0.00E+00 0.00E+00 0.00E+00 1.95E-06 Ni-65 4.70E-06 5.32E-07 2.42E-07 0.00E+00 0.00E+00 0.00E+00 4.05E-05 Cu64 0.00E+00 6.09E-07 2.82E-07 0.00E+00 1.03E-06 0.00E+00 1.25E-05 Zn-65 1.84E-05 6.31E-05 2.91E-05 0.00E+00 3.06E-05 0.00E+00 s.33E-05 Zn-69 9.33E-08 1.68E-07 1.25E-08 0.00E+00 6.98E-08 0.00E+00 1.37E-05 Zn-69m 1.50E-06 3.06E-06 2.79E-07 0.00E+00 1.24E-06 0.00E+00 4.24E-05 Br-82 0.00E+00 0.00E+00 1.27E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 3.63E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 3.82E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 1.94E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+OO Rb-86 0.00E+00 1.70E-04 8.40E-05 0.00E+00 0.00E+00 0.00E+00 4.35E-06 Rb-88 0.00E+00 4.98E-07 2.73E-07 0.00E+00 0.00E+00 0.00E+00 4.85E-07 Rb-89 0.00E+00 2.86E-07 1.97E-07 0.00E+00 0.00E+00 0.00E+00 9.74E-08 Sr-89 2.51E-03 0.00E+00 7.20E-05 0.00E+00 0.00E+00 0.00E+00 5.16E-05 Sr-90 1.85E-02 0.00E+00 4.71E-03 0.00E+00 0.00E+00 0.00E+00 2.31E-04 Sr-91 5.00E-05 0.00E+00 1.81E-06 0.00E+00 0.00E+00 0.00E+00 5.92E-05 Sr-92 1.92E-05 0.00E+00 7.13E-07 0.00E+00 0.00E+00 0.00E+00 2.07E-04 Y-90 8.69E-08 0.00E+00 2.33E-09 0.00E+00 0.00E+00 0.00E+00 1.20E-04 Y-91 m 8.10E-10 0.00E+00 2.76E-11 0.00E+00 0.00E+00 0.00E+OO 2.70E-06 Y-91 1 .13E-06 0.00E+00 3.01 E-08 0.00E+00 0.00E+00 0.00E+00 8.10E-05 Y-92 7.65E-09 0.00E+00 2.15E-10 0.00E+00 0.00E+00 0.00E+00 1.468-04 Y-93 2.43E-08 0.00E+00 6.62E-10 0.00E+00 0.00E+00 0.00E+00 1.92E-04 Zr-95 2.06E-07 5.02E-08 3.56E-08 0.00E+00 5.41E-08 0.00E+00 2.50E-05 Zr-97 1.48E-08 2.54E-09 1.16E-09 0.00E+00 2.56E-09 0.00E+00 1.62E-04 Nb-95 4.20E-08 1.73E-08 1.00E-08 0.00E+00 1.24E-08 0.00E+00 1.46E-05 Nb-97 4.59E-10 9.79E-1 1 3.53E-1 1 0.00E+00 7.65E-1 1 0.00E+00 3.09E-05 Mo-99 0.00E+00 3.40E-05 6.63E-06 0.00E+00 5.08E-05 0.00E+00 1.12E-05 Tc-99m 1.92E-09 3.96E-09 5.10E-08 0.00E+00 4.26E-08 2.07E-09 1 .1 5E-06 Tc-101 2.27E-09 2.86E-09 2.83E-08 0.00E+00 3.40E-08 1.56E-09 4.86E-07 Ru-103 1.48E-06 0.00E+00 4.95E-07 0.00E+00 3.08E-06 0.00E+00 1.80E-05 Ru-105 1.36E-07 0.00E+00 4.58E-08 0.00E+00 1.00E-06 0.00E+00 5.41 E-05 Ru-106 2.41 E-05 0.00E+00 3.01E-06 0.00E+00 2.85E-05 0.00E+00 1.83E-04 E1-155

WBN OFFSITE DOSE CALCUI..ATION MANUAL Revision 23 0 (oDcM) Page 94 of 195 Table 6.4 - INGESTION DOSE FACTORS - DFal (mrem/pCi ingested) (Page 8 of 8)

                                                     !NFANT Nuclide bone                liver totalbody thyroid kidney lung                         GI-LLI Ag-110m 9.96E-07 7.27E-07 4.81E-07 0.00E+00 1.04E-06 0.00E+00 3.77E-05 Sb-124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 0.00E+00 1.34E-05 6.60E-05 Sb-125 1.23E-05 1.19E-07 2.53E-06 1.54E-08 0.00E+00 7.72E-M 1.64E-05 Te-125m 2.33E-05 7.79E-06 3.15E-06 7.84E-06 0.00E+00 0.00E+00 1.11E-05 Te-127m 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.4E-04 0.00E+00 2.36E-05 Te:127 1.00E-06 3.35E-07 215E-07 8.14E-07 2.4E-06 0.00E+00 2.10E-05 Te-129m 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 0.00E+00 5.97E-05 Te-129 2.84.E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 0.00E+00 2.27E-05 Te-131m 1.52E-05 6.12E-06 5.05E-06 1.24E45 4.21E-05 0.00E+00 1.03E-04 Te-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 0.00E+00 7.11E-06 Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 0.00E+00 3.81E-05 I-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 0.00E+00 2.83E-06 l-131 3.sgE-0s 4.23E-05 1.86E-05 1.39E-02 4.94E-05 0.00E+00 1.51E-06 t-132 1.66E-06 3.37E-06 1.20E-06 1.58E-M 3.76E-06 0.00E+00 2.73E-06 f-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 0.00E+00 3.08E-06 l-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 0.00E+00 1.84E-06 l-135 3.64E-06 7.24E-06. 2.64E-06 6.49E-04 8.07E-06 0.00E+00 2.62E-06 Cs-134 3.77E-04 7.03E-04 7.10E-05 0.00E+00 '1.81E-04 7.42E-05 1.91E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 0.00E+00 5.38E-05 1.10E-05 2.05E-06 Cs-137 5.22E-04 6.11E-04 4.33E-05 0.00E+00 1.64E-04 6.64E-05 1.91E-06 Cs-138 4.81E-07 7.82E-07 3.79E-07 0.00E+00 3.90E-07 6.09E-08 1.25E-06 Ba-'!39 8.81E-07 5.84E-10 2.55E-08 0.00E+00 3.51E-10 3.54E-10 5.58E-05 Ba:140 1.71E-U 1.71E-07 8.81E-06 0.00E+00 4.06E-08 1.05E-07 4.20E-05 Ba-141 4.25E47 2.91E-10 1.34E-08 0.00E+00 1.75E-10 1.77E-'10 5.19E-06 Ba-142 'l.84.E-07 1.53E-10 9.06E-09 0.00E+00 8.81E-11 9.26E-'l'l 7.59E-07 La-140 2.1'lE-08 8.32E-09 2.14E-09 0.00E+00 0.00E+00 0.00E+00 9.77E-05 La-142 1.10E-09 4.04E-10 9.67E-11 0.00E+00 0.00E+00 0.00E+00 6.86E-05 Ce-141 7.87E-08 4.80E-08 5.65E-09 0.00E+00 1.48E-08 0.00E+00 2.48E-05 Ce-143 1.48E-08 9.82E-06 1.12E-09 0.00E+00 2.86E-09 0.00E+00 5.73E-05 Ce-1M 2.98E-06 1.22E-06 1.67E-07 0.00E+00 4.93E-07 0.00E+00 1.7'lE-O4 Pr-143 8.13E-08 3.04E-08 4.03E-09 0.00E+00 1.13E-08 0.00E+00 4.29E-05 Pr-'144 2.74E-10 1.06E-10 1.38E-11 0.00E+00 3.84E-11 0.00E+00 4.93E-06 Nd-147 5.53E-08 5.68E-08 3.48E-09 0.00E+00 2.19E-08 0.00E+00 3.60E-05 W-187 9.03E-07 6.28E-07 2.17E-07 0.00E+00 0.00E+00 0.00E+00 3.69E-05 Np-239 1.11E-08 9.93E-10 5.61E-10 0.00E+00 1.98E-09 0.00E+00 2.87E-05

References:

Dose Factors for Co-57, Zn69m, Br-82, Nb-97, Sb-124, Sb-125 are from Reference 17,Table 4. All others are from Reference 4, Table E-14. NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. This assumes that tritium will act similarly in all organs (Reference 24). E1-156

WBN OFFSITE DOSE CALCUI..ATION MANUAL Revision 23 0 (oDcM) Page 95 of 195 Table 6.5 - BIOACCUMULATION FACTORS (Br) FOR FRESHWATER FISH Nuclide Bi Nuclide Bi H-3 9.0E-01 Tc-99m 1.5E+01 c-14 4.6E+09 Tc-101 1.5E+01 Na-24 1.0E+02 Ru-1 03 1.0E+01 P-32 1.0E+05 Ru-105 1.0E+0t Cr-51 2.0E+42 Ru-1 06 1.0E+01 Mn-54 4.0E+02 Ag-1 10m 2.3E+00 Mn-56 4.0E+02 sb-124 1.0E+00 Fe-55 1.0E+02 sb-125 1.0E+00 Fe-59 1.0E+02 Sn-125 3.0E+03 Co-57 5.0E+01 Te-125m 4.0E+02 Co-58 5.0E+01 Te-1 27m 4.0E+02 Co-60 5.0E+01 Te-127 4.0E+02 Ni-63 1.0E+02 Te-129m 4.0E+02 Ni-65 1.0E+02 Te-129 4.0E+02 Cu-64 5.0E+01 Te-131m 4.0E+02 Zn4,5 2.0E+03 Te-1 31 4.0E+02 Zn-69 2.0E+03 Te-132 4.0E+02 Zn-69m 2.0E+03 t-1 30 4.0E+0t Br-82 4.2E+02 I-1 31 4.0E+01 Br-83 4.2E+02 l-132 4.0E+01 Br-84 4.2E+02 t-1 33 4.0E+01 Br-85 4.2E+02 t-134 4.0E+01 Rb-86 2.0E+03 t-1 35 4.0E+01 Rb-88 2.0E+03 Cs-1 34 1.9E+03 Rb-89 2.0E+03 Cs-1 36 1.9E+03 Sr-89 5.6E+01 Cs-137 1.9E+03 Sr-90 5.6E+01 Cs-138 1.9E+03 Sr-91 5.6E+01 Ba-1 39 4.0E+00 Sr-92 5.6E+0t Ba-140 4.0E+00 Y-90 2.5E+01 Ba-141 4.0E+00 Y-91 m 2.5E+01 Ba-142 4.0E+00 Y-91 2.5E+01 La-140 2.5E+01 Y-92 2.5E+01 La-142 2.5E+0t Y-93 2.5E+01 Ce-141 1.0E+00 Zr-95 3.3E+00 Ce-143 1.0E+00 Zr-97 3.3E+00 Ce-144 1.0E+00 Nb-95 3.0E+04 Pr-143 2.5E+01 Nb-97 3.0E+04 Pr-144 2.5E+01 Mo-99 1.0E+01 Nd-147 2.5E+01 w-187 1.2E+03 Np-239 1.0E+0t

References:

Bioaccumulation fac{ors for Ag, Sb, and Sn - nuclides are from Reference 16. Bioaccumulation factors for l-, Cs-, and Sr- nuclides are from Reference 21,Table 3.2.4. All other nuclides' bioaccumulation factors are from Reference 4, Table A-1. E1- 157

WBN OFFSITE DOSE CALCUIATION MANUAL Revision 23 0 (oDcM) Page 96 of 195 Table 6.6 - EXTERNAL DOSE FACTORS FORSTANDING ON CONTAMINATED GROUND - DFU (mrem/h per pCi/m2) (Page 1 of 2) Nuclide Total Body Skin H-3 0.0 0.0 c-14 0.0 0.0 Na-24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-57 1.77E-09 2.21 E-09 Co-58 7.00E-09 8.20E-09 Co0 1.70E-08 2.00E-08 Ni-63 0.0 0.0 Ni-65 3.70E-09 4.30E-09 Cu4 1.50E-09 1.70E-09 Zn5 4.00E-09 4.60E-09 Zn9 0.0 0.0 Zn-69m 5.50E-09 6.59E-09 Br-82 3.18E-08 3.90E-08 Br-83 6.40E-1 1 9.30E-1 1 Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 Rb-86 6.30E-1 0 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-1 3 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91m 3.80E-09 4.40E-09 Y-91 2.40E-11 2.708-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Nb-97 8.1 1E-09 1.00E-08 Mo-99 1.90E-09 2.20E-09 Tc-99m 9.60E-10 1 .1 0E-09 Tc-101 2.70E-09 3.00E-09 Ru-1 03 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 E1-158

WBN OFFSITE DOSE CALCUI.ATION MANUAL Revision 23 0 (oDcM) Page 97 of 195 Table 6.6 - EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND - DF1J (mrem/h per pCi/m2) Page2ot2) Nuclide Total Body Skin Ru-106 1.s0E-09 1.80E-09 Ag-1 10m 1.80E-08 2.10E-08 sb-124 2.17E-08 2.57E-08 sb-125 5.48E-09 6.80E-09 Te-1 25m 3.50E-1 1 4.80E-1 1 Te-1 27m 1.10E-12 1.30E-12 Te-127 1 .00E-1 1 1 .10E-1 1 Te-129m 7.70E-10 9.00E-10 Te-129 7.10E-10 8.40E-1 0 Te-131m 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.00E-09 t-1 30 1.40E-08 1.70E-08 t-1 31 2.80E-09 3.40E-09 t-132 1.70E-08 2.00E-08 r-1 33 3.70E-09 4.s0E-09 t-134 1.60E-08 1.90E-08 t-1 35 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-1 39 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 s.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-1 0 2.30E-1 0 Nd-147 1.00E-09 1.20E-09 w-1 87 3.10E-09 3.60E-09 Np-239 9.50E-10 1 .1 0E-09

References:

Dose Factors for Co-57, Zn69m, Br-82, Nb-97, Sb-124 and Sb-125 are from Reference 18. All others are from Reference 4, Table E. E1-159

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 98 of 195 Figure 6.1 - LIQUID EFFLUENT RELEASE POINTS Condensate Demineralizer 0-RE-90-225 System Stearn Generator 1-RE 1204.121 Blowdown Unit 1 Steam Generator 2-RE-90-120AJ21 Blowdorn Unit 2 0-RE-90-133,140 Liquid &RE-90-13/-,141 0-RE-90-122 Radwaste System D I L U T I o N F Coolinq Tourer Blowdown L o W E1-160

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 99 of 195 Figure 6.2 - LIQUID RADWASTE SYSTEM CVCS Fo gpm Monitor Tank 18,000 gal Reactor Building and Radwaste Auxiliary Building Floor Cleanup Cask Decon Drains, CVCS Holdup Tanks System Collector Tank 100 gp 15,000 gal Waste Condensate 2O gpm Tank x 3 1 500 gal Chemical Drain Tank 600 gal Laundry and Hot Shower Tanks x 2 600 gal each I I I I 0-RE-go-122 I I

/,

Cooling Tower Blowdown E1-161

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page {00 of {95 Figure 6.3 - STEAM GENERATOR BLOWDOWNTCONDENSATE DEMINERALIZER I I I I I.I TDtt I' ItI I TI I I II I I. I --- - E -I I I - - -l t I I I I I t ffimGrn*Sr Eqffit t.ltt I or2 r (r r r !r r r r r rr rl ln tI r r r sr rr r rD

                      --              -                                                  -      -                              -J
                   -----IIIfIeIIflI'rrrr Gsil;rfrhriurhrffi l(cr gGhm0rlrraor tUX )lrtEdrqrnr SGEDhmSncr*r Emdorr                                                          CoofrgTowElffinn E1-162

WBN OFFSITE DOSE CALCULATpN MANUAL Revision 23 0 (oDcM) Page 10,l of 195 7.0. GASEOUS EFFLUENTS INTRODUCTION There are six discharge points for gaseous radioactive effluents from \AIBN. These discharge points are: Unit '1 CondenserVacuum Exhaust (CVE), Unit 2 CVE, Service Building Exhaust, Auxiliary Building Exhaust, Unit 1 Shield Building Exhaust, and Unit 2 Shield Building Exhaust. Detailed descriptions are provided belor, and Figure 7.1 provides an outline of these airbome discharge points with associated radiation monitors. None of these discharge points meets the criteria of Regulatory Guide 1.111 lor elevated releases; therefore, all releases are considered to be groundJevel. Various plant systems contribute activity to the CVE, the Service Building Exhaust and the Auxiliary Building Exhaust, but these sources are not treated as individual release points. There are two gas systems associated with each Shield Building Exhaust the Waste Gas Decay Tank (WGDT) System and the Containment Purge System which includes the lncore lnstrument Room Purge The discharge points and the two associated gas systems are each monitored by noble gas radiation monitors. These monitors perform two main functions: to identifo any unexpected radioactivity releases, and to ensure that the dose rate limits of ODCM Control '1.2.2.'l are met. Each monitor has an alarmftrip setpoint which causes the monitor to alarm if the monito/s setpoint is exceeded. The monitors do not have sepaete alarm and trip setpoints; they have one setpoint which performs both functions. The noble gas radiation monitors for Containment Purge and the WGDT release points initiate an isolation function if the alarm/trip setpoint is exceeded. The radiation monitor alarm/trip setpoints for each release point and discharge point are based on the radioactive noble gases in the gaseous effluent. lt is not considered practical to apply instantaneous alarm/trip setpoints for integrating radiation monitors sensitive to radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases. Releases are continuous, except for releases from the WGDT or Containment Purge Systems which are made as batch releases. For batch releases, the WGDT or Containment to be released is grab sampled for radioactivity in accordance with Table 2.2-2. The samples are analyzed to determine the maximum allowable release florv rate to ensurc compliance with the dose rate limits of ODCM Control 1.2.2.1as described in ODCM Section 7.2. The sampling results are also used to determine a setpoint for the associated noble gas radiation monitor for the release. The setpoints are determined in accordance with ODCM Section 7.1. Dose calculations are performed for each release, as outlined in ODCM Sections 7.3 and 7.4,1o determine compliance with ODCM Controls 1.2.2.2 and 1.2.2.3. For continuous releases, the pathways are sampled for edioactivity periodically, as required by Table2.2-2. The samples are analyzed to ensure compliance with the dose and dose rate limits of ODCM Control 1.2.2.1, 1.2.2.2, and 1.2.2.3, as described in ODCM Sections 7.1 and7.2. The sampling results are also used to determine a setpoint for the associated noble gas radiation monitor for the release. The setpoints are determined in accordance with ODCM Section 7.1. Dose calculations are performed for each sampling period, as outlined in ODCM Sections 7.3 and 7.4, to determine compliance with ODCM Controls 1.2.2.2 and 1.2.2.3. Once per month, the pQected dose is calculated, as outlined in ODCM Section 7.5, to determine compliance with ODCM Control 1.2.2.4. E1-163

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 102 of 195 All dose calculations performed to determine compliance with ODCM Controls 1.2.2.2,1.2.2.3 and 1.2.2.4 are detailed in ODCM Sections 7.3 and 7.4. The calculational methodologies are based on the guidance provided in NUREG-O133 and Regulatory Guide 1.109. Because allreleases are ground level, semi-infinite cloud models are used in the dose calculations. The quantities of each radionuclide identified and released are input into a more rigorous calculation methodology, described in ODCM Section 7 -7, to determine the individual and population doses to be reported to the NRC in the Annual Radioactive Effluent Release Report. These dose calculation methodologies are based on the guidance provided in Regulatory Guide 1.109. RELEASE'DISCHARG E POINTS DESCRIPTION There are six discharge points at \AIBN that are monitored for airbome radioactive effluents. These are: a CVE for each unit, a Service Building Exhaust, an Auxiliary Building Exhaust and a Shield Building Exhaust for each unit. Each of these discharge points may have one or more release points associated with it as described below. Figure 7.1 provides a simplified outline of the airborne effluent release and discharge points with associated radiation monitor identifications. Figure 7.2 provides a more detailed description of the release and discharge points, with flow rates, radiation monitors, and associated inputs. Condenser Vacuum Exhaust The CVEs are located in the turbine building. They exhaust at a maximum design flow rate of 45 cfm per pump. These discharge points are monitored by radiation monitors 1,2-RE-90-119 for normal operation. Service Buildino Exhaust Areas in the Service Building in which work is conducted which may produce radioactive effluents all exhaust to the Service Building Exhaust. This discharge point exhausts at a maximum design flow rate of approximately 10,000 cfm and is monitored by radiation monitor 0-RE-90-1328. Auxiliarv Buildino Exhaust The Auxiliary Building exhausts at a maximum total design flow of 228,000 cfm (2 ot 4 ventilation fans and 1 fuel handling fan). This discharge point exhaust is monitored by radiation monitor 0-RE-90-101B. The annulus vacuum priming fans (2 fans at 1000 cfm each) exhaust to the auxiliary building fuel handling exhaust header. Shield Buildino Exhaust There is one Shield Building Exhaust for each unit. These discharge points are monitored by radiation monitors 1,2-RE-90.4004. There are nine Waste Gas Decay Tanks (WGDTS) that discharge into the waste gas headerwhich is released into the Unit 1 Shield Building Vent (see Figure 7.3). The Train AAuxiliary Building Gas Treatment System (ABGTS) is operated during a WGDT release. Each WGDT has a design capacity of 600 ft3 and a maximum design release rate of 100 cfrn ISOURCE NOTE 17]. The WGDT retease point is monitored by radiation monitor 0-RE-90-118. E1-164

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 103 of 195 The Auxiliary Building Gas Treatment System (ABGTS) draws from the Auxiliary Building Secondary Containment Enclosure and exhausts to the Shield Building Exhaust. Any aclivity released from the Auxiliary Building through the ABGTS is accounted for as a part of the Auxiliary Building Exhaust releases, and will not be tracked separately. An Auxiliary Building lsolation signal starts the ABGTS. The Emergency Gas Treatment System is used to draw a vacuum in the annulus and exhaust to the Shield Building Exhaust under emergency conditions, and could do so during normal operation. Both the Containment Purge and the lncore lnstrument Room Purge from each unit tie into the Shield Building Exhaust. The Containment Purge release point exhausts at a maximum of 28,000 cfm and is monitored by radiation monitors 1,2-RE-90-130 and 1,2-RE-90-131. lf the lncore lnstrument Room Purge is operating exclusively, it exhausts at 800 cfnr, and is monitored by the Containment Purge Monitors given above. The common header exhausts to the Shield Building Exhaust. 7.I GASEOUS EFFLUENT MONITOR INSTRUMENT SETPOINTS Airborne effluent noble gas monitor setpoints are determined to ensure that the dose rate at the UNRESTRICTED AREA BOUNDARY does not exceed the dose rate limits given in ODCM Control 1.2.2.'l and to identify unexpected releases. ODCM Control 1.1.2 establishes operability requirements for these monitors. Allocation factors (AF) are used in the setpoint calculation to allocate a fraction of the total body dose rate limit to each discharge point. These allocation factors may be changed as required to support plant operational needs, but shall not exceed a sum of one. Therefore, a particular monitor reaching the calculated maximum setpoint as described below does not necessarily mean that the dose rate limit at the UNRESTRICTED AREA BOUNDARY is being exceeded; the alarm indicates that the specific release/discharge point is contributing a greater fraction of the dose rate limit than was allocated to the associated monitor and will require further evaluation. The gaseous effluent radiation monitors and their setpoint information are outlined below: Pathway Monitor Default Setpoint Setpoint Release Limit Setpoint Containment 1-RE-90-1 30 Purge 2-RE-90-130 SectionT.l .1.3 (1) Section 7 .1 .2 1-RE-90-131 2-RE-90-131 WGDT 0-RE-90-1 18 Section 7 .1 .1 .2 S Section 7.1 .2 Shield 1-RE-90400A Building 2-RE-90-4004 SectionT.l .1 .3 sr", Section 7.1 .2 Exhaust Auxiliary Building 0-RE-90-1018 Section 7 .1 .1 .3 sr., Section 7 .1 .2 Exhaust Service Building 0-RE-90-132B SectionT.l .1.3 sr", Section 7 .1 .2 Exhaust 1-RE-90-1 19 CVE 2-RE-90-1 19 SectionT.l .1 .4 S Section 7.1 .2 (1) Sr* or Tech Spec value from setpoint and scaling document, whichever is smaller. E1-165

WBN OFFSITE DOSE CALCU1ATION MANUAL Revision 23 0 (oDcM) Page 1O4 of 195 7.1.1 Default Monitor Setpoints 7.1.1.'l Section Deleted 7.1.1.2Waste Gas Decay Tank Efrluent Monitor (0-RE-90-118) During periods of release, the methodology in Section 7 .1 .2 will be used to determine the monitor setpoint and may be set at a default value. Site procedures will document and controlthis value. 7.1.1.3 Shield Building Exhaust (1,2-RE-90400A), Auxiliary Building Exhaust(0-RE-90-10,lB), Containment Purge Effluent Monitors (1,2-RE-90-{30,-l3l), and Seruice Building Exhaust (0-RE-90-r32B) These discharge point effluent monitors are set to ensure compliance with ODCM Control 1.2.2.1. The default setpoints are determined by calculating the maximum calculated setpoint described by Equation 7.3 using Xe-133 monitor efficiencies, design flow rates, and setting the ratio Dft;*/DR equal to 1.0. The default setpoints for the shield building monitors are calculated in units of pCils. The default setpoints will be defined in plant procedures. 7 .1.1.4 Condenser Vacuum Exhaust Vent (,l ,2-RE-90-i 19) This discharge point effluent monitor is set to ensure compliance with ODCM Control '1.2.2.1 and to identiff the presence of primary to secondary leakage of radioactivity. The default setpoint is determined in one of two ways: by calculating the maximum calculated setpoint as described in Section 7.1.1.3, and then taking a percentage of this value as the setpoint; or by defining the setpoint as two times the normal background. The default setpoint will be defined in plant instructions. Once a primary to secondary leak is identified, the setpoint on this monitor may be incrementally adjusted upward as defined in plant procedures to enable it to be used to identifl any further increases in the leak rate. 7.1.2 Release Permit Monitor Setpoint Determination For each release, two setpoints are calculated for the monitor: one based on the expected response of the monitor to the radioactivity in the effluent stream (described in Sections 7 .1 .2.1and 7 .1 .2.2) which allows for the identification of any release of radioactivity above the expected amount; and a calculated maximum setpoint which corresponds to the most restrictive dose rate limit given in ODCM Control 1.2.2.1 (described in Section 7.1.2.3) which ensures that the release will be stopped if it exceeds the dose rate limits afrer dilution. A comparison is then made (as described in Section 7.1.2.4) between these two calculated setpoints and the default setpoints (described in Section 7.1.1) to determine which is used for the release. E1-166

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 105 of 195 7.1.2.1 Expected Monitor Response The expected monitor response, ER, is determined using the following equation: ER= BKG +IN, C, (7.1) where: ' BKG= monitor background, cpm. E; = efficiency factor for the monitor for nuclide i, cpm per pCi/cc. This term may also be refened to as a response or calibration factor. C; = measured concentration of nuclide i, pCi/cc. 7.1.2.2 Expected Response Setpoint An expected response setpoint Sgp is calculated for the monitor for each release: Sr -x1r,C,+x BKG (7.2) where: X = administrative factors designed to account for expected variations in monitor response and background (as defined in plant procedures). The ranges of values are: 1< X <2.O. lsouRcE NoTE 151 7 .1.2.3 Calculated iiaximum Setpoint The calculated maximum setpoint, Sr",. in cpm, corresponding to the dose rate limit is determined using the following equation: MU= {o. s-o u". r.[& + BKG LDR'@n-r"cil] (7 3) I 'JJ where: AF = dose rate allocation factor for the release point, dimensionless. The sum of all dose rate allocation factors must be < 1. The dose rate allocation factors for release points are defined in approved plant procedures. VCF = Vacuum conection factor applied to noble gas monitors whose detector operates at a negative pressure. This factor will be defined in plant procedures for applicable monitors and will have a range of: 0 < VCF < 1.0. ISOURCE NOTE 2] SF = safeU factor for the monitor, dimensionless. Safe$ factors will be < 1. Safety factors for each monitor are defined in approved plant procedures. DRri.= the dose rate limit, mrem/y.

       = 500 mrem/y to the total body for noble gases,
       = 3000 mrem/y to the skin for noble gases, and DR = the calculated dose rate for the release, mrem/y.
       = DRrg for total body (as described in Section 7.2.'l),
       = DRs for skin (as described in Section 7.2.2), and ER = expected monitor response (as calculated in Equation 7.1), cpm.

BKG = the monitor background, cpm. E1- 167

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 106 of 195 7 .1.2.4 Setooint Determination When release permits are generated, the expected response and maximum calculated setpoints are determined as described in Equations 7 .2 and 7 .3. A comparison is made between these two calculated setpoints and the default setpoint as described below to choose the appropriate setpoint for the monitor during the release (after the release, the monitor is normally retumed to the default setpoint).

1. lF Sen ( So"r"rtt ( Sr"* RepOfted = Soeraun

2. lF SER ( Sro < So"arn RePorted = S.*

3. lF Saearlt < Sen < Sr", Reported = Sgp

                                                     = Sd"r"rrt (for Containment Purge monitors)

4. IF Sen 2 Sr", Reported = Sr",

E1-168

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 107 of 195 7.2 GASEOUS EFFLUENTS. DOSE RATES Dose rates are calculated for total body and skin due to submersion within a cloud of noble gases using a semi-infinite cloud model as described in NUREG-O133. The dose rates are compared to their respective limits and are used in the determination of setpoints for noble gas radiation monitors. 7.2.1Total Body Dose Rate The calculated total body dose rate must meet the condition (from NUREG-O133 Section 5.2.1): 500 mrem / y

?  [ro,,+DFB, {(*),o,"}]   =

Since there are no elevated release points at IA/BN, the elevated release terms in the equation (V1 and Qc) are not used. Substituting the flow (0 multiplied by the concentration (C) for the release rate (Q) in the above equation, the dose rate to the total body, DR1g in mrem/y, is calculated using the following equation: DRrr=*f I Ci DFBl (7.4) where: x/Q = tenain adjusted relative concentration, s/m3. Relative air concentrations are calculated for the unrestricted area boundary in each of the 16 sectors as described in Section 7.9.2 using the historical meteorological data for the period 1 986-2005 given in Table 7 .2. For dose rate calculations, the highest value from the 16 unrestricted area boundary locations is used. The values for each of the sixteen sectors are given in Table 7.3 (maximum values are highlighted on the table). f = flowrate of effluent stream, cc/s. Ci = concentration of noble gas nuclide i in effluent stream, pCi/cc. DFB; = total body dose factor due to gamma radiation for noble gas nuclide i, mrem/y per pCi/m3 (Table 7.4). The total body dose rate is calculated for each release. lt is compared to the limit of 500 mrem/y and is also used in the determination of the radiation monitor setpoint as described in Section 7.1.2. E1-169

WBN OFFSITE DOSE CALCUI.ATION MANUAL Revision 23 0 (oDcM) Page 108 of 195 7.2.2 Skin Dose Rate The calculated skin dose rate must meet the condition (from NUREG-O133 Section 5.2.1): (,'"), +r.r ai)o,,].[ors, +r.r DF,1f 3ooo mrem/y

? {[(,"                                        [(t),o,,] =

Since there are no elevated release points at VVBN, the stack terms in the equation, DFS;, (x/Q)s, B;, lnd Qis, ?re not used. Substituting the flow (f) multiplied by the concentration (C) for the release rate (Q) in the above equation, the dose rate to the skin, DRg in mrem/y, is calculated using the following equation:

                      +l.l I                                                                           (7.5)

DRs = t t ?.,(rt, oF.yi) where: /Q = tenain adjusted relative concentration, si/m3. Relative air concentrations are calculated for the unrestricted area boundary in each of the 16 sectors as described in Section 7.9.2 using the historical meteorological data for the period 1986-2005 given in Table7.2. For dose rate calculations, the highest value from the 16 unrestricted area boundary locations is used. The values for each of the sixteen sectors are given in Table 7.3 (maximum values are highlighted on the table). f = flowrate of effluent stream, ccy's. C; = concentration of noble gas nuclide i in effluent stream, pCi/cc. DFsi = skin dose factor due to beta radiation for noble gas nuclide i, mrem/y per pCi/m3 (Table 7.4). 1.1'l = the average ratio of tissue to air energy absorption coefficients, mrem/mrad. DFgi = dose conversion factor for external gamma for noble gas nuclide i, mradr! per pCi/m3 (Table 7.a). The skin dose rate is calculated for each release. lt is compared to the limit of 3000 mrem/y and is also used in the determination of the radiation monitor setpoint as described in Section 7.1 .2. E1-170

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 109 of 195 7 .2.3 l-131 , l-133, Tritium and A!! Radionuclides in Particulate Form with Half-Lives of Greater Than 8 Days - Organ Dose Rate Organ dose rates due to l-131, l-133, tritium and all radionuclides in particulate form with half-lives of greater than 8 days, D$ in mrem/y, are calculated for all age groups (adult, teen, child, and infant) and all organs (bone, liver, total body, thyroid, kidney, lung, and Gl Tract). The calculated organ dose rate must meet the condition (from NUREG-0133 Section 5.2.1): I B(W'o,

w,ar) < I 5oo mrem / v Since there are no elevated release points at WBN, the elevated release terms (W. and Q.) are not used.

Substituting the flow (0 multiplied by the concentration (C) for the release rate (Q) in the above equation, and inserting the appropriate dispersion factor (1/Q or D/Q) for each pathway considered, the organ dose rate, DRl in mrem/y, is calculated using the following equation: DRj - r{.,*(*,, *Rcrr).p.,[*Rri +$(n.r, .*.,))) (7.6) where: f = flowrate of effluent stream, ccy's. Cr = concentration of tritium in effluent stream, pCi/cc. XIO = tenain adjusted relative concentration, si/m3. Relative air concentrations are calculated for the unrestricted area boundary in each of the 16 sectors as described in Section 7.9.2 using the historical meteorological data for the period 1 986-2005 given in Table 7 .2. For dose rate calculations, the highest value from the 16 unrestricted area boundary locations is used. The values for each of the sixteen sectors are given in Table 7.3 (maximum values are highlighted on the table).

       = (1/Q) for the inhalation and tritium ingestion pathways, Rr      = inhalation dose factor for tritium, mrem/y per pCi/m3. Dose factor is calculated as described in Section 7.8.13.

Rcrp = Grass-cow-milk dose factor for tritium, mrem/y per pCi/m3. Dose factor is calculated as described in Section 7.8.7. C; = concentration of nuclide i in effluent stream, pCi/cc. Rri = inhalation dose factor for each identified nuclide i, mrem/y per pCi/m3. Dose factors are calculated as described in Section 7.8.13. D/Q = terrain adjusted relative deposition, 1/m2. Relative deposition is calculated for the unrestricted area boundary in each of the 16 sectors as described in Section 7.9.3 using the historical meteorological data for the period 1986-2005 given in Table7.2. For dose rate calculations, the highest value from the 16 unrestricted area boundary locations is used. The values for each of the sixteen sectors are given in Table 7.3 (maximum values are highlighted on the table). Rcpi = Grass-cow-milk dose factor for each identified nuclide i, m2-mrem/y per pCi/s. Dose factors are calculated as described in Section 7.8.1. Rq = ground plane dose factor for each identified nuclide i, m2-mrem/y per pCi/s. Dose factors are calculated as described in Section 7.8.14. The maximum organ dose rate is selected from among the dose rates calculated for all the organs and all age groups. lt is compared to the limit of 1500 mrem/y. E 1- 171

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 110 of 195 7.3 DOSE. NOBLE GASES Doses are calculated for gamma and beta air doses due to exposure to a semi-infinite cloud of noble gases. These doses will be calculated at the unrestricted area boundary location with the highest tenain adjusted annual-average 1glQ based on 1974-1993 meteorologicaldata (Table 7.2). This location is chosen from the UNRESTRICTED AREA BOUNDARY locations listed in Table 7.1. Dispersion factors are calculated using the methodology described in Section 7.9.2. No credit is taken for radioactive decay. 7.3.1 Gamma Dose to Air NUREG-0133 Section 5.3.1 provides the following equation for the calculation of the gamma air dose from noble gases: D=k E [*(*),n,, *(;) o,,]*[a1e5 +b,q*] Because there are no elevated release points, the terms subscripted s in the equation are not used. Since all releases are considered to be longterm, the terms using lower case variables are not used. Since WBN will be calculating a dose for each release made, the total release (Q) in the above equation is replaced by the release rate (Q) multiplied by the length of the release (I). The gamma air dose, Ds in mrad, is calculated for each release using the following equation:

    =l.eE-06 t                                                                                     (7.7)
                 ? Qi D,,                    DFrT where:

1.9E{6= conversion factor, y/min. XIA = highest terrain adjusted unrestricted area boundary annual-average relative concentration, s/m3 (from Table 7.3). Qi = release rate for nuclide i, pCi/s. DFgi = dose conversion factor for external gamma for nuclide i (Table 7.4), mradly per pCi/m3. T = duration of release, min. The gamma air dose calculated by this method will be used in the cumulative dose calculations discussed in Section 7.3.3. E1- 172

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 111 of 195 7.l.2Beta Dose to Air NUREG-0133 Section 5.3.1 provides the following equation for the calculation of the beta air dose from noble gases:

, =,. ,{*,[*)un,, * (*)"o"]. ((*),n* . (,"t),',))

Because there are no elevated release points, the terms subscripted s in the equation are not used. Since all releases are considered to be long-term, the terms using lower case variables are not used. Since WBN will be calculating a dose for each release made, the total release (Q) in the above equation is replaced by the release rate (Q) multiplied by the length of the release (T). The beta air dose, Ds in mrad, is calculated for each release using the following equation: Dp=1.9E-06 (7.8)

               * ? Qi DFp, T where:

1 .9E-06= conversion factor, y/min. xlQ = highest tenrain adjusted unrestricted area boundary annual-average relative concentration, ym3 (from Tabte 7.3). Qi = release rate for nuclide i, pCi/s. DFoi = dose conversion factor for external beta for nuclide i, mrad/y per pCi/m3 (from Table 7.4). T = duration of release, min. The beta air dose calculated by this method will be used in the cumulative dose calculations discussed in Section 7.3.3. 7.3.3 Cumulative Doee - Noble Gas Quarterly and annual sums of all doses are calculated for each release as described below to compare to the limits listed in ODCM Control 1.2.2.2. For noble gases, cumulative doses are calculated for gamma and beta air doses. Doses due to each release are summed with the doses for all previous releases in the cunent quarter or year to obtain cumulative quarterly and annual doses. 7.3.4 Comparison to Limits The cumulative calendar quarter and calendar year doses are compared to their respective limits in accordance with S u rvei lance Req u rement 2.2.2.2. to determ ine compl iance. I i E1- 173

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 112 of 195 7.4 DOSE DUE TO I.I3I, I.{33, TRITTUM AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF.LIVES OF GREATERTHAN 8 DAYS 7.4.1 Organ Dose Calculation Organ doses due to l-131, l-133, tritium and all radionuclides in particulate form with halfJives of greater than 8 days are calculated for each release for the critical receptor. The critical receptor is defined as the unrestricted area boundary in the sector with the highest annual average terrain adjusted 2glQ. The annual average ;g/Q and D/Q are calculated using the methodology in Sections 7.9.2 and 7.9.3 using the historical 1986-2005 meteorological data (Table 7.2). A conservative assumption is used to select the dispersion factors for the critical receptor. The highest calculated 1glQ and D/Q values are chosen from Table 7.1 values after being multiplied by the applicable tenain adjustment factors (from Table 7.3), and may not be for the same compass sector. Pathways considered to exist at this location are inhalation, ground plane exposure, grass-cow-milk ingestion, grass-cow-beef ingestion and fresh leafo and stored vegetable ingestion. All age groups are considered (adult, teen, child and infant). Dose factors for these age groups and pathways are calculated as described in Section 7.8. For the ground exposure pathway, which has no age or organ specific dose factors, the total body dose will be added to the internal organ doses for all age groups. No credit is taken for radioactive decay. NUREG-OI33 Section 5.3.1 provides the following equation for the calculation of the organ dose from radioiodines, radioactive materials in particulate form with half-lives greater than 8 days: O=

R,(w.Q. + w,qi, + W"Qi, + wvqiv)

Because there are no elevated release points, the terms subscripted s in the equation are not used. Since all releases are considered to be long-term, the terms using lower case variables are not used. Since WBN will be calculating a dose for each release made, the total release (Q) in the above equation is replaced by the release rate (a) times the length of the release (T). The general equation for the calculation of organ dose is: Di = 3.17E-08 T I I Rr,(Wa,) (7.e) where: 3.17E-08 = conversion factor, y/s T = duration of release, s. Rpi = dose factor for pathway P for each identified nuclide i, m2-mrem/y per pCi/s for ground plane, grass-milk animal-milk, grass-cow-beet and vegetation pathways, and mrem/y per pCi/m3 for inhalation and tritium ingestion pathways. Equations for calculating these dose factors are given in Section 7.8. Wp = dispersion factorforthe location and pathway P (from Table 7.3),

            = tenain  adjusted  1/Q for the inhalation and tritium ingestion pathways,
            = tenain adjusted D/Q for the food and ground plane pathways, Q;          = release rate for radionuclide i, pCi/s.

E1-174

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 113 of 195 From the four age groups considered, the maximum is determined by comparing all organ doses for all age groups. The age group with the highest single organ dose is selected as the critical age group. The organ doses for the critical age group will be used in the cumulative doses discussed in Section 7.4.2. 7.4.2 Gumulative Oryan Doses Quarterly and annual sums of all doses are calculated for each release as described below to compare to the limits listed in ODCM Control 1.2.2.3. For maximum organ dose, cumulative quarterly and annual doses are maintained for each of the eight organs considered. The cumulative dose is obtained by summing the doses for each organ of the critical age group (as calculated in Section 7.4.1) as determined for each release with the organ doses for all previous releases in the quarter or year to obtain the cumulative quarterly and annual doses. Thus, the cumulative organ doses will be conservative values, consisting of doses belonging to various age groups depending on the mix of radionuclides. The highest of these cumulative organ doses is used for the comparison to the limits described in ODCM Control 1.2.2.3. 7.4.3 Comparison to Limits The cumulative calendar quarter and calendar year doses are compared to their respective limits in accordance with ODCM Surveillance Requiremenl2.2.2.3 to determine compliance. 7.5 DOSE PROJECTIONS !n accordance with ODCM Surveillance Requirement2.2.2.4.'1, dose projections will be performed. This will be done for the gamma dose, the beta dose and the maximum organ dose. (7.1 0) where: D = the 31day dose projection, mrem. a = the cumulative dose for the quarter, mrem. b = the projected dose forthis release (as calculated in Sections 7.4.1,7.4.2and7.4.3), mrem. c = any anticipated additional dose in the next month from other souroes, mrem. d = cunent number of days into the quarter up to the time of the release under consideration. The 31day projected dose will be compared to the limits given in ODCM Control '1.2.2.4 in accordance with S urvei lance Req uirement 2.2.2.4. 1 to determine compliance. I 7.6 GASEOUS RADWASTE TREATMENT SYSTEM DESCRIPTION The GASEOUS RADWASTE TREATMENT SYSTEM (GRTS) described in the \AIBN FSAR shall be maintained and operated to keep releases AI-ARA. A simplified flow diagram for the GRTS is given in Figure 7.3. E1-175

WBN OFFSITE DOSE CALCUTATION MANUAL Revision 23 0 (oDcM) Page 114 of 195 7.7 DOSE CALCULATIONS FOR REPORTING A complete dose analysis utilizing the total estimated gaseous releases for each calendar quarter will be performed and reported as required in ODCM Administrative Control5.2. All realpathways and receptor locations identified by the most recent land use survey are considered. ln addition, actual meteorological data representative of a ground level release for each conesponding calendar quarter will be used. For iodine releases, it is assumed that half the iodine released is in organic form. Oqanic iodine causes a dose only by inhalation. For cow-milk and beef ingestion doses, the fraction of the time the animals are on stored feed (identified in the survey) is used in the calculation. 7.7.1 Noble Gas - Gamma and Beta Air Dose Regulatory Guide 1.109 Equation B-5 provides the following equation for the calculation of gamma and beta air doses from noble gas releases: P=! r,- Pq orD$i) Ol'l) where: cim = concentration of nuclide i at location m, pCi/m3. Air concentrations are calculated as described by Equation 7.33. DFgi = dose conversion factor for external gamma for nuclide i, mrad/y per pCi/m3 Clable 7.4). DFq = dose conversion factor for external beta for nuclide i, mradr! per pCi/m3 (Table 7.4). 7.7.2 Noble Gas - Air Submersion Dose Regulatory Guide 1.109 Equation B-8 provides the following equation for the calculation of the total body submersion dose from noble gas releases: D = sF II x;- DFE Q.12) where: SF = shielding factor. This factor is conservatively set equal to 1.0. cim = concentration of nuclide i at location m, pCi/m3. Air concentrations are calculated as described by Equation 7.33. DFB; = total body dose conversion factor due to submersion in a semi-infinite cloud of noble gases for nuclide i, mrem/y per pCi/m3 (Table 7.4). Regulatory Guide 1.109 Equation B-9 provides the following equation for the calculation of the skin submersion dose from noble gas releases: rt +l DF$ D= ll.l I SF ! 296 DFn f 2(i. (7.13) Li)i where: 1.11 = the average ratio of tissue to air energy absorption coefficients, mrem/mrad. SF = shielding factor. This factor is conservatively set equal to 1.0. cim = concentration of nuclide i at location m, pCi/m3. Air concentrations are calculated as described by Equation 7.33. DFoi = dose conversion factor for external gamma for nuclide i, mrad/y per pCi/m3 (Table 7.4). DFS; = skin dose conversion factor due to submersion in a semi-infinite cloud of noble gases for nuclide i, mrem/y per pCi/m3 (Table 7.4). E1- 176

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 115 of 195 7.7.3 Radioiodine, Particulate, and Tritium - Maximum Organ Dose Regulatory Guide 1 .109 Equations C-12, -1 3, and -14 provides the following equation for the calculation of doses from the release of iodine and particulate radionuclides: D = Sr Ii CrRo, (for ground contamination) D = BRoZ r, Rr, (for inhalation) D :Znr,(u *yrc * +(J *c,^ +(J ,oc r, +(J ,Frc ,,) (for ingestion) These three equations are combined into one equation for this presentation by dropping the subscripts on the dose factors, and substituting the appropriate dispersion factor (D/Q or /Q) multiplied by the total release (Q) for the concentration terms (C) as follows: D = BR,)t Q,R,, + s rlfi Q,Ro,

I R* t Q,(u
f r
u * + (J,o + u, f ,)

The shielding factor (Se) is conservatively set equal to 1.0, therefore, that term drops out of the equation. The vegetable fractions (f), ingestion rates (U) and breathing rate (BR) are included in the calculation of the dose factors, given in ODCM Sections 7.8.1 through 7.8.14, therefore, they may also be dropped from this equation. The equation then becomes: D =>6Q, R,, *T6a, R, *16Q, n" Since the calculation of tritium concentration in vegetation is based on air concentration rather than ground deposition (Equation C-9 in Regulatory Guide 1.109), a separate term is added to the equation to account for the tritium ingestion dose pathways. ln addition, a tenain adjustment factor (TAF) is added. Therefore the equation for calculating the organ dose, D1 in mrem, is: D j -3.17 ,)1^*s, .\l@)e*4 *@-)ger)R", +e)@AF)^,]r,} Ql4)

            "-*      {G.X,                                  ^,,

where: 3.17E-08 = conversion factor, y/s. D/Q = Relative deposition for location under consideration, m-2. Relative deposition is calculated as described in Equation 7.35. Rpr = ingestion dose factor for pathway P for tritium, m2-mrem/y per pCi/s. lngestion pathways available for consideration are the same as those listed above for Rp1. Equations for calculating ingestion dose factors for tritium are given in Sections 7.8.7 through7.8.12. Qr = adjusted release rate for tritium for location under consideration, pCi/s. The initial release rate is adjusted to account for decay between the release point and the location, depending on the frequency of wind speeds applicable to that sector. Hence, the adjusted release rate is equalto the actual release rate decayed for an average traveltime during the period. e, - e,ifu exp[^,i) (7.15) where: Q, = initial average release rate for tritium over the period, pCi/s. fk = joint relative frequency of occurrence of winds in windspeed class k blowing toward this exposure point, expressed as a fraction. li = radiological decay constant for nuclide i, s-1. x = downwind distance, m. ur = midpoint value of wind speed class interval k, m/s. E1- 177

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 116 of 195 Rpi = ingestion dose factor for pathway P for each identified nuclide i (except tritium), m2-mrem/y per pCils. lngestion pathways available for consideration include: pasture grass-milk animal-milk ingestion - R6p (see Section 7.8.1). stored feed-milk animal-milk ingestion - R6s (see Section 7.8.21. pasture grass-beef ingestion - Ryp (see Section 7.8.3). stored feed-beef ingestion - Rys (see Section 7.8.4). fresh leafo vegetable ingestion - Ryp (see Section 7.8.5). stored vegetable ingestion - Rys (see Section 7.8.6). Rci = Dose factor for standing on contaminated ground, m2-mrem/y per pCi/s. The equation for calculating the ground plane dose factor is given in Section 7.8.14. xlQ = Relative concentration for location under consideration, s/m3. Relative concentrations are calculated as described by Equation 7.34. Rri = lnhalation dose factor, mrem/y per pCi/m3. The equation for calculating the inhalation dose factor is given in Section 7.8.13. Qi = adjusted release rate for nuclide ifor location under consideration, pCi/s. Calculated in the same manner as Q1 above. The highest organ dose for a real receptor is determined by summing the dose contribution from all identified pathways for each receptor including ground contamination, inhalation, vegetable ingestion (for identified garden locations), cow and/or goat milk ingestion (if a cow or goat is identified for the location), beef ingestion (the beef ingestion dose for the location of highest beef dose for all receptors will be considered the beef dose for all receptors). 7.7.4Population Doses The population dose is determined using Equation D-1 from Regulatory Guide 1.109: D-kuPOPm I Do,i FPro m I For determining population doses to the SO-mile population around the plant, each compass sector is broken dovvn into elements. These elements are defined in Table 7.5. Dispersion factors are calculated for the midpoint of each sector element (see Table 7.5). For each of these sector elements, an average dose is calculated, and then multiplied by the population in that sector element. The average dose is determined by multiplying the maximum individual dose for the sector by the ratio of the average to the maximum usage rates. For population doses resulting from ingestion, it is conservatively assumed that all food eaten by the average individual is grown within the sector element. The general equation used for calculating the population dose in a given sector element is: Doseooo = 0.001 tRATlop PoPm FPo DosEp P where: 0.001 = conversion from mrem to rem. MTIOp = ratio of average to maximum dose for pathway P. Maximum ingestion rates are given in Table 6.3. (Average ingestion rates are obtained from Reference 4, Table E-4.)

          = 0.5 for submersion and ground exposure pathways, a shielding/occupancy factor.
          = 1.0 for the inhalation pathway.
          = 0.515, 0.515, 0.5, and 0.355 for milk, for infant, child, teen and adult, respectively. (lt is assumed that the ratio of average to maximum infant milk ingestion rates is the same as that for child.)
          = 1.0, 0.90, 0.91, 0.86 for beef ingestion, for infant, child, teen and adult, respectively.
          = 1.0, 0.38, 0.38, 0.37 for vegetable ingestion, for infant, child, teen and adult, respectively. (lt is assumed that the average individual eats no fresh leaff vegetables, only stored vegetables.)

POPm = the population of the sector element m, persons (Table 7.6). FP" = fraction of the population belonging to each age group. E1- 178

WBN OFFSITE DOSE CALCUI.ATION MANUAL Revision 23 0 (oDcM) Page 117 of 195

         = 0.015, 0.168, 0.153, 0.665 for infant, child, teen and adult, respectively (fractions taken from Reference 21, Table 3.39).

DOSEp = the dose for pathway P to the maximum individual at the location under consideration, mrem (as described in Sections 7 .7 .1 ,7 .7 .2, and 7 .7 .3). For ingestion pathways, this dose is multiplied by an average decay conection to account for decay as the food is moved through the food distribution cycle. This average decay correction, ADC, is defined as follows: For milk and vegetables: ADC - exd-rito) (7.17) For beef: exd-l"itd) l,itcb ADC _ (7.1 8) I - exd-rit.o) where: li= decay constant for nuclide i, s-l. td = distribution time for food product under consideration (values from Reference 4, Table D-1)

              = 1.21E+06 s (14 d) for vegetables.
              = 3.46E+05 s (4 d) for milk.
              = 7d for beef to = time to consume a whole beef, as described in Section 7.8.3.

For beef ingestion, the additional factors in the calculation of ADC negate the integration of the dose term over the period during which a whole beef is consumed, for the calculation of population dose. ln other words, this assumes that the maximum individualfreezes and eats a whole beel while the average individual buys smaller portions at a time. Population doses are summed over all sector elements to obtain a total population dose for the SO-mile population. 7.7.5 Reporting of Doses The calculated quarterly doses and calculated population doses described in Section 7.7 are reported in the Annual Radioactive Effluent Release Report as required by ODCM Administrative Control 5.2. E1- 179

WBN OFFSITE DOSE CALGUI.ATION MANUAL Revision 23 0 (oDcM) Page 118 of 195 7.7.6 Dose to a MEMBER OF THE PUBLIC Inside the CONTROLLED or RESTRICTED AREA The Basis for ODCM Control 1.2.2.1 states that for MEMBERS OF THE PUBLIC who may at times be within the CONTROLLED or RESTRICTED AREA, the occupancy factor of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric dispersion factor above that for the unrestricted area boundary. This basis also states that examples of calculations for such MEMBERS OF THE PUBLIC will be given in the ODCM. Calculations are presented in Section 12.4 of the WBN UFSAR which estimate the annual doses at the boundary of the restricted area (WBN UFSAR Table '12.4-2). The total dose rate is the sum of the adult whole body inhalation dose rate, the gamma dose rate from the plume and ground contamination, and the gamma dose rate from outdoor storage tanks. As indicated in the UFSAR, the highest total dose rate at the boundary of the restricted area is 105 mrem/y, based on a continuous 2000 h/y occupancy. Use of a more realistic occupancy, reflective of the transient traffic expected for this location, would result in a much lower dose estimate. lt is, therefore, considered highly unlikely that a member of the public would receive greater than 100 mrem/y at or beyond the restricted area boundary. ln addition to this calculation, the dose to these MEMBERS OF THE PUBLIC (obtained from dosimeters deployed at the Restricted Area Boundary and from estimates of the dose from gaseous effluents) will be reviewed on an annual basis to ensure that the actual exposure to any individuals is less than 100 mrem/y for these locations. The results of this review will be included in the Annual Radiological Effluent Report pursuant to ODCM Administrative Control 5.2. E1-180

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 119 of 195 7.8 GASEOUS RELEASES. DOSE FACTORS 7.8.1 Pasturc Grass4odGoat-Milk lngestion Dose Factorc - Rcpl (m2-mrem/y per pCi/s) The general dose equation stated in Regulatory Guide 1.109 for calculating the annual dose from consuming foods containing atmospherically released radionuclides (Equation C-13) is: Dose(D) = Dose Conversion Facto(DFL)*Usage Rate(U)*Radionuclide Concentration in Media(C) Forthe milk pathway, Regulatory Guide 1.109 Equations C-5 and C-10 are inserted into the above equation to yield the following: Sincethe dose equation in Sections 7.4and 7.7.3 (Equations 7.9 and7.14) contain the variable di (equal to the product of the release rate (a) and the deposition factor (D/Q)), the factors remaining in the above equation are defined as the dose factor. For pasture grass, the variable t6 is defined as zero in Regulatory Guide 1 .1 09, therefore that exponential term drops out of the equation. The resulting dose factor equation is: Rcri - I06 DFL;q; Uop (7.1 e) where: 106 = conversion factor, pCi/pCi. DFL;.i = ingestion dose conversion factor for nuclide i, age group a, organ j, mrem/pCi (Table 6.4). Uao = milk ingestion rate for age group a, Uy. Fri = transfer factor for nuclide i from animal's feed to milk, d/L(Table 6.2). Qt = animal's consumption rate, kg/d. li = decay constant for nuclide i, s{ fiable 6.2). t61 = transport time from milking to receptor, s. fo = fraction of time animal spends on pasture, dimensionless. r = fraction of activity retained on pasture grass, dimensionless. 16 = the efiective decay constant, due to radioactive decay and weathering, s-1.

        = li+ hv.

lyy = weathering decay constant for leaf and plant surfaces, s-1. tep = time pasture is exposed to deposition, s. V; = agricuttural productivity by unit area of pasture grass, kg/m2. Bi, = transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil). Oable 6.2) t5 = time period over which accumulation on the ground is evaluated, s. P = effective surface density of soil, kg/m2. NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3. E1-181

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 120 of 195 7.8.2 Stored FeedodGoat-Milk lngstion Dose Factors - Rcst (m2-mrem/y per pCi/s) The general dose equation stated in Regulatory Guide 1.109 for calculating the annual dose from consuming foods containing atmospherically released radionuclides (Equation C-13) is: Dose(D) = Dose Conversion Factor(DFL)*Usage Rate(U)*Radionuclide Concentration in Media(C) For the milk pathway, Regulatory Guide 1.109 Equations C-5 and C-10 are inserted into the above equation to yield the following: D = DFL Uop F, e6 exd-r"r1,,,,) .,{tffiJ

ei'[r -

                                                                 ",d-]'ro)l]
                                                                             "U"r.l Since the dose equation in Sections 7.4 and 7.7.3 (Equations 7.9 and7.14) contain the variable d; (equal to the product of the release rate (Q) and the deposition factor (D/Q)), the factors remaining in the above equation are defined as the dose factor. For stored feed, it is assumed that the milk animals will be eating the feed continuously from the time of harvest, therefore the decay term for the consumption of stored feed used is not that given in Reg. Guide 1.'109 for the end of the period between harvest and consumption, but is instead an integrated decay over the period (Reference 10). The resulting dose factor is:

Rcsi=106DFL6;U6pF,1e1exp(-r,,*)r,{fifft*I}{rydl.tf '-'q-^'t'niJ (7.20) where: 106 = conversion factor, pCi/pCi. DFLH = ingestion dose conversion factor for nuclide i, age group a, organ j, mrem/pCi (Table 6.4). Uap = milk ingestion rate for age group a, Uy. Fmi = transfer factor for nuclide i from animal's feed to milk, d/L (Table 6.2). Qt = animal's consumption rate, kg/d. fr = fraction of time animal spends on stored feed, dimensionless. li = decay constant for nuclide i, s-1 Oable 6.2). t6 = transport time from milking to receptor, s. tcst = time between harvest of stored feed and consumption by animal, s. r = fraction of activity retained on pasture grass, dimensionless. ls = the effective decay constant, due to radioactive decay and weathering, s-1

         = l; + lyy.

lry = weathering decay constant for leaf and plant surfaces, s-1. te = time stored feed is exposed to deposition, s. Ysr = agricultural productivity by unit area of stored feed, kg/m2. Bi, = transfer factor f,or nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per pCiftg (dry soil). (Iable 6.2) t6 = time period over which accumulation on the ground is evaluated, s. P = effective surface density of soil, kglm2. NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3. E1-182

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDGM) Page 121 of 195 7.8.3 Pasture Grass-Beef lngestion Dose Factorc - Rmpt (m2-mrem/y per pCi/s) The general dose equation stated in Regulatory Guide 1.109 for calculating the annual dose from consuming foods containing atmospherically released radionuclides (Equation C-13) is: Dose(D) = Dose Conversion Facto(DFL)'Usage Rate(U)*Radionuclide Concentration in Media(C) For the beef pathway, Regulatory Guide 1.109 Equations C-5 and C-12 are inserted into the above equation to yield the following: si, - exp(-?'to)J] D - DFL Uop Ft Qr exp(-},t,) d, * [r

                                                                           "^o,-r,tn)

{ry Since the dose equation in Sections 7.4 and 7.7.3 (Equations 7.9 and7.14) contain the variable di (equal to the product of the release rate (Q) and the deposition factor (D/Q)), the factors remaining in the above equation are defined as the dose factor. ln addition, a factor is added to account for the decay during the time the beef is being consumed. This term assumes that the individual slaughters and eats the animal over a period of time (t"s) (Reference 10). For pasture grass, the variable t6 is defined as zero in Regulatory Guide 1 .109, therefore that exponential term drops out of the equation. The resulting dose factor is: RM,i =106 DFLid u"- Fn o, ,.0(-1,,t.)t s* [ - exp (- l, itb xl (7.21) {W} {W- PIt where: 106 = conversion factor, pCi/pCi. DFL;4 = ingestion dose conversion factor for nuclide i, age group a, organ j, mrem/pCi (Table 6.4). U", = beef ingestion rate for age group a,kgly. F6 = transfer factor for nuclide i from cow's feed to beef, d/kg (Table 6.2). Qt = cow's consumption rate, kg/d. li = decay constant for nuclide i, s-1 Gable 6.2). tco = time for receptor to consume a whole beef, s. ts = transport time from slaughter to consumer, s. fo = fraction of time cow spends on pasture, dimensionless. i = fraction of activity retained on pasture grass, dimensionless. lE = the effective decay constant, due to radioactive decay and weathering, s-1, equalto l;+1y,1 lw = weathering decay constant for leaf and plant surfaces, s-1. tep = time pasture is exposed to deposition, s. V; = agricultural productivity by unit area of pasture grass, kg/m2. Bi, = transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil). (Table 6.2) t6 = time over which accumulation on the ground is evaluated, s. P = effective surface density of soil, kglm2' NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3. E1-183

WBN OFFSITE DOSE CALCUI.ATION MANUAL Revision 23 0 (oDcM) Page 122 of 195 7.8.4 Stored Feed-Beef lngestion Dose Factorc - Rusr (m2-mrem/y per pCi/s) The general dose equation stated in Regulatory Guide 1.109 for calculating the annual dose from consuming foods containing.atmospherically released radionuclides (Equation C-13) is: Dose(D) = Dose Conversion Facto(DFL)*Usage Rate(U)*Radionuclide Concentration in Media(C) For the beef pathway, Regulatory Guide 1 .1 09 Equations C-5 and C-12 are inserted into the above equation to yield the following: B,[1 _ exp( _aru) DFL U", F, QF exp( -1t,) d, . 1l exp(-zth) P)" { Since the dose equation in Sections 7.4 and 7.7.3 (Equations 7.9 and7.14) contain the variable d; (equal to the product of the release rate (Q) and the deposition factor (D/a)), the factors remaining in the above equation are defined as the dose factor. ln addition, factors are added to account for the decay during the time the animals are consuming the stored feed (to1) and during the time period of over which the beef is being consumed (Lr) (Reference 10). The resulting dose factor is: Rr,rsi = rdDF,,"-*n{ry}.*,,*l t{ff* }{.W.ryrx, } (t 22) where: 106 = conversion factor, pCi/pCi. DFL6; = ingestion dose conversion factor for nuclide i, age group a, organ j, mrem/pCi (Table 6.4). Uam = beef ingestion rate for age group a,kgly. Fg = transfer f;actor for nuclide i from co#s feed to beet d/kg (Table 6.2). Qr = corir's consumption rate, kg/d. t; = decay constant for nuclide i, s-1 fiable 6.2). tco = time for receptor to consume a whole beef, s. ts = transport time from slaughter to consumer, s. fs = fraction of time cow spends on stored feed, dimensionless. tcst = time between harvest of stored feed and consumption by cow, s. r = fraction of activity retained on pasture grass, dimensionless. te = time stored feed is exposed to deposition, s. Yst = agricultural productivity by unit area of stored feed, kg/m2.

!g         = the effective decay constant, due to radioactive decay and weatheriog, s-1,
           =  li+lw.

lu/ = weathering decay constant for leaf and plant surfaces, s-l. Bi, = transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil). (Table 6.2) tp = time overwhich accumulation on the ground is evaluated, s. P = effective surface density of soil, kglm2. Factors defined above which do not reference a table for their numerical values are given in Table 6.3. E1- 184

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 123 of 195 7.8.5 Fresh Leafy Vegetable lngestion Dose Factorc - Ryp; (m2-mrem/y per pCi/s) The general dose equation stated in Regulatory Guide 1.109 for calculating the annual dose from consuming foods containing atmospherically released radionuclides (Equation C-13) is: Dose(D) = Dose Conversion Facto(DFL)'Usage Rate(U)'Radionuclide Concentration in Media(C) For the vegetable pathway, Regulatory Guide 1.109 Equation C-5 is inserted into the above equation to yield the following:

                        - el{-r'et")l   si"[1- exd-tt)l]

D = DFL uFLo q {r [r

v^F'\ ^'nc/

I t"^, Pi' J "ro(-rt".) Since the dose equation in Sections 7.4 and 7.7.3 (Equations 7.9 andT .14) contain the variable d; (equal to the product of the release rate (Q) and the deposition factor (D/Q)), the factors remaining in the above equation are defined as the dose factor. Thus, the dose factor is: RVE - I 06DFL;qiexp(-r,tn.) Urro t ry} (7.23) {ry. where: 106 = conversion factor, pC/pCi. DFL;.; = ingestion dose conversion factor for nuclide i, age group a, organ j, mrem/pCi (Table 6.4). [ = decay constant for nuclide i, s-l Gable 6.2). thc = average time between harvest of vegetables and their consumption and/or storage, s. UFLa = consumption rate of fresh leaff vegetables by the receptor in age group a, kg/y. f1 = fraction of fresh leafy vegetables grown locally, dimensionless. r = fraction of deposited activity retained on vegetrables, dimensionless. lg = the effective decay constant, due to radioactive decay and weathering, s-1.

          =li+lw lw = decay constant for removal of activity on leaf and plant surfaces by weathering, s-1.

te = exposure time in garden for fresh leaff and/or stored vegetables, s. Yr = agricultural yield for fresh leafy vegetables, kglm2. Biu = transfer fiactor for nuclide i from soil to vegetables, pCi/kg (wet weight of vegetation) per pCiftg (dry soil). (Table 6.2) ts = time period over which accumulation on the ground is evaluated, s. P = effective surface density of soil, kglm2. NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3. E1-185

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 124 of {95 7.8.6 Stored Vegetable lngestion Dose Factors - Rvsr m2-mrem/y per pCi/s) The general dose equation stated in Regulatory Guide 1.109 for calculating the annual dose from consuming foods containing atmospherically released radionuclides (Equation C-13) is: Dose(D) = Dose Conversion Facto(DFL)*Usage Rate(U)*Radionuclide Concentration in Media(C) For the vegetable pathway, Regulatory Guide 1 .1 09 Equation C-5 is inserted into the above equation to yield the following: D -DFL UFL. d, . B, [ - exp(- lt r)l ho") { P,L )r.0, Since the dose equation in Sections 7.4 and 7.7.3 (Equations 7.9 and7.14) contain the variable d; (equal to the product of the release rate (Q) and the deposition factor (D/Q)), the factors remaining in the above equation are defined as the dose factor. One additional decay term is added to account for the decay during the period of time after harvest during which the food is consumed (tsr); this term assumes that the stored vegetables are eaten throughout the storage period (Reference 10). Thus, the dose factor is: RVS, = 1 ee DFL6; exd-r rn") Uso,. . Uf-"lg(-^"nf (7.24) where: flL,,-.4pl}itffiJ 106 = conversion factor, pCi/pCi. DF\6; = ingestion dose conversion factor for nuclide i, age group a, organ j, mrem/pCi (Table 6.4). I; = decay constant for nuclide i, s-1 Gable 6.2). tn" = average time between harvest of vegetables and their consumption and/or storage, s. Ust = consumption rate of stored vegetables by the receptor in age group a, kgfi. fs = fraction of stored vegetables grown locally, dimensionless. tw = time between storage of vegetables and their consumption, s. r = fraction of deposited activity retained on vegetables, dimensionless. lg = the effective decay constant, due to radioactive decay and weathering, s-1.

           =li+lw l\^,'       = decay constant for removal of activity on leaf and plant surfaces by weathering, s-1 te          = exposure time in garden for fresh leaff and/or stored vegetables, s.

Yw = agricultural yield for stored vegetables, kg/m2. Bv = transfer factor for nuclide i from soil to vegetables, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil). (Table 6.2) tg = time period over which accumulation on the ground is evaluated, s. P = effective surface density of soil, kglm2. NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3. E1-186

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 125 of 195 7.8.7 Tritium-Pasture Grass4odGoattlilk Dose Factor - Rcpr (mrem/y per pCi/m3) The general dose equation stated in Regulatory Guide 1.109 for calculating the annual dose from consuming foods containing atmospherically released radionuclides (Equation C-13) is: Dose(D) = Dose Conversion Factor(DFL)*Usage Rate(U)*Radionuclide Concentration in Media(C) For the milk pathway, Regulatory Guide 1.109 Equations C-9 and C-10 are inserted into the above equation to yield the following: D -DFL Uu, F- Q, exp(- ht^)Q, 61,,'(f)] Since the dose equation in Sections 7.4 and 7.7.3 (Equations 7.9 and7.'14) contain the variables for the release rate (Q) and the dispersion factor (1/Q), the factors remaining in the above equation are defined as the dose factor. The resulting dose factor equation is: tlr (f RCTP -lo' lou DFLr"j F-r Q, Uu, r' expc t, tr. ) (7.25)

                                                       )]',

where: 103 = conversion factor, g/kg. 106 = conversion factor, pCi/pCi. DFL14 = ingestion dose conversion factor for tritium for age group a, organ j, mrem/pCi (Table 6.4). Fmr ' = transfer factor for tritium from animal's feed to milk, d/L (Table 6.2). Qt = animal's consumption rate, kg/d. Uap = milk ingestion rate for age group a, Uy. 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. H = absolute humidi$ of the atmosphere, g/m3. f, = fraction of time animal spends on pasture, dimensionless. li = decay constant for tritium, s-t 6able 6.2). t6s = transport time from milking to receptor, s. E1-187

WBN OFFSITE DOSE CALCUIATION MANUAL Revision 23 0 (oDcM) Page 126 of 195 7.8.8 Tritiumtored FeedodGoat-Milk Dose Factor - Rcsr (mremfi per pCi/m3) The general dose equation stated in Regulatory Guide 1.109 for calculating the annual dose from consuming foods containing atmospherically released radionuclides (Equation C-13) is: Dose(D) = Dose Conversion Facto(DFL)*Usage Rate(U).Radionuclide Concentration in Media(C) For the milk pathway, Regulatory Guide 1.109 Equations C-9 and C-10 are inserted into the above equation to yield the following: D -DFL U"o F- Q, exp(- ht*)Q, (7.26) tl,,'[T)] Since the dose equation in Sections 7.4 and 7.7.3 (Equations 7.9 and7.14) contain the variables for the release rate (Q) and the dispersion factor (1/Q), the factors remaining in the above equation are defined as the dose factor. ln addition, a factor is added to account for the decay during the time the animals are consuming the stored feed (Reference 10). The resulting dose factor is: R.r. -lo' lou DFLruj Ffr Q, U,, r'(f)]', exp(- t,t ) [r-'xpI h, t rrf x} tlr { 7rt csf where: 103 = conversion factor, gftg. 106 = conversion factor, pCi/pCi. DFL16; = ingestion dose conversion factor for H-3 for age group a, organ j, mrem/pCi (Table 6.4). F6 = transfer factor for H-3 from cow's feed to beef, d/kg (Table 6.2). Qr = cow's consumption rate, kg/d. U", = beef ingestion rate for age group a, kg/y. 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. H = absolute humidig of the atmosphere, g/m3. fr = fraction of time cow spends on stored feed, dimensionless. [ = decay constant for tritium, s-t Gable 6.2). ts = transport time from slaughter to consumer, s. Gf = time to consume stored feed, s. NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3. E1-188

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 127 of 195 7.8.9 Tritium-Pasture Grass-Beef Dose Factor - Rmpr (mrem/y per pCi/m3) The general dose equation stated in Regulatory Guide 1.109 for calculating the annual dose from consuming foods containing atmospherically released radionuclides Equation C-13) is: Dose(D) = Dose Conversion Facto(DFl)'Usage Rate(U)*Radionuclide Concentration in Media(C) For the beef pathway, Regulatory Guide 1 .1 09 Equations C-9 and C-10 are inserted into the above equation to yield the following: D -DFL Uu, Fr Q, expft ht,)Q, 61,,'[f)] Since the dose equation in Sections 7.4 and 7.7.3 (Equations 7.9 and7.14) contain the variables for the release rate (Q) and the dispersion factor (X/Q), the factors remaining in the above equation are defined as the dose factor. Two decay terms are added to the equation to account for the decay during the time the pasture is exposed to the activity in the air, and the decay during the time the beef is being consumed (Reference 10). The resulting dose factor is: (7.27) wr =1031 06 DFLrq, F,, e, u

                              -            r,       u, l{@){[-=*rdr.

[r "(T)] "-l-R

where: 103 = conversion factor, g/kg. 106 = conversion f;actor, pCilpCi. DFL16; = ingestion dose conversion factor for H-3 for age grou! al organ j, mrem/pCi (Table 6.4). Fs = transfer factor for H-3 from cow's feed to beef, d/kg (Table 6.2). Qr = cow's consumption rate, kg/d. U", = beef ingestion rate for age group a, kg/y. 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. H = absolute humidity of the atmosphere, g/m3. f, = fraction of time cow spends on pasture, dimensionless. li = decay constant for tritium, s-1 Gable 6.2). ts = transport time from slaughter to consumer, s. t o = time pasture is exposed to deposition, s. tb = time for receptor to consume a whole beef, s. E1-189

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 128 of 195 7.8.10 Tritiumtored Feed-Beef Dose Factor - Rmsr (mremfi per pCi/m3) The general dose equation stated in Regulatory Guide 1 .1 09 for calculating the annual dose from consuming foods containing atmospherically released radionuclides (Equation C-13) is: Dose(D) = Dose Conversion Facto(DFL)'Usage Rate(U)'Radionuclide Concentration in Media(C) For the beef pathway, Regulatory Guide 1 .1 09 Equations C-9 and C-1 0 are inserted into the above equation to yield the following: D -DFL U,,, F, Q, ht,)Q, exp(- tl"'(T)] Since the dose equation in Sections 7.4 and 7.7.3 (Equations 7.9 and7.14) contain the variables forthe release rate (Q) and the dispersion factor (1/Q), the factors remaining in the above equation are defined as the dose factor. Two decay terms are added to the equation to account for the decay during the time the pasture is exposed to the activity in the air, and the decay during the time the beef is being consumed (Reference 10). The resulting dose factor is: R,rasr=103106DFLTdFoQ,U-[,"(H)]'"-or-u,l{ff}{ryd}rz.zal where: 103 = conversion factor, g/kg. 106 = conversion factor, pCi/rrCi. DFL14 = ingestion dose conversion factor for H-3 for age group a, organ j, mrem/pCi (Table 6.4). Fs = transfer factor for H-3 from cow's feed to beef, d/kg (Table 6.2). Qt = co r's consumption rate, kg/d. U", = beef ingestion rate for age group a,kgly. 0.75 = the fraction of totalfeed that is water. 0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water. H = absolute humidity of the atmosphere, g/m3. G = fraction of time cow spends on stored feed, dimensionless. [ = decay constant for tritium, s-l (Table 6.2). ts = transport time from slaughter to consumer, s. tcst = time to consume stored feed, s. tcb = time for receptor to consume a whole beef, s. NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3. E1-190

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 129 of 195 7.8.11Tritium-Fresh Leafy Vegetable Dose Factor - Rvrr (mrem/y per pCi/m3) The general dose equation stated in Regulatory Guide 1 .1 09 for calculating the annual dose from consuming foods containing atmospherically released radionuclides (Equation C-13) is: Dose(D) = Dose Conversion Facto(DFL)*Usage Rate(U).Radionuclide Concentration in Media(C) For the vegetable pathway, Regulatory Guide 1.109 Equation C-9 is inserted into the above equation to yield the following: D -DFL U,p exp(- htn") Q, bI,,,(f)] Since the dose equation in Sections 7.4 and 7.7.3 (Equations 7.9 and7.14) contain the variables for the release rate (Q) and the dispersion factor (X/Q), the factors remaining in the above equation are defined as the dose f;actor. The resulting dose factor is: Rrr, = lo3 106 DFLruj u.," rL exp{- (7.2e) [o.rr(T)] ^,to") where: 103 = conversion factor, g/kg. 106 = convercion factor, pCi/pCi. DFL13i = ingestion dose conversion factor for tritium for age group a, organ j, mrem/pCi (Table 6.4). 0.75 = the fraction of totalvegetation that is water. 0.5 = the ratio of the specific activity of the vegetables water to the atmospheric water. H = absolute humidity of the atmosphere, g/m3. Uru = consumption rate of fresh leaff vegetables by the receptor in age group a, kg/y. fs = frac{ion of fresh leaff vegetables grown locally, dimensionless. 11 = decay constant for tritium, s-1 Gable 6.2). tnc = time between harvest of vegetables and their consumption and/or storage, s. NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3. E1-191

WBN OFFSITE DOSE CALCUI.ATION MANUAL Revision 23 0 (oDcM) Page {30 of 195 7.8.12 Tritiumtored Vegetable Dose Factor - Rvsr (mrem/y per pCi/m3; The general dose equation stated in Regulatory Guide 1.109 for calculating the annual dose from consuming foods containing atmospherically released radionuclides (Equation C-13) is: Dose(D) = Dose Conversion Factor(DFL)*Usage Rate(U).Radionuclide Concentration in Media(C) For the vegetable pathway, Regulatory Guide 1.109 Equation C-9 is inserted into the above equation to yield the following: D -DFL Uun exp(- Atn")Q", tl,,'(f)] Since the dose equation in Sections 7.4 and 7.7.3 (Equations 7.9 and7.14l contain the variables for the release rate (Q) and the dispersion factor (1/Q), the factors remaining in the above equation are defined as the dose factor. An additional decay term is added to account for the decay during the time the vegetables are stored (this term assumes that the vegetables are being eaten during the storage period) (Reference 10). The resulting dose factor is: Rrr, - lo3 106 DFL,raj u,"t-{ [t - e*p(- Arl- I t,tn") (7.30) [0,'(f)] tr t* )*oC where: 103 = conversion factor, g/kg. 106 = conversion factor, pCi/pCi. DFLlsi = ingestion dose conversion factor for tritium for age group a, organ j, mrem/pCi (Table 6.4). 0.75 = the fraction of total vegetation that is water. 0.5 = the ratio of the specific activity of the vegetation water to the atmospheric water. H = absolute humidity of the atmosphere, g/m3. Us" = consumption rate of stored vegetables by the receptor in age group a, kg/y. fs = fraction of stored vegetables grown locally, dimensionless. li = decay constant fortritium, s-t gable 5.2). tsv = time between harvest of stored vegetables and their consumption and/or storage, s. tnc = time between harvest of vegetables and their storage, s. E1- 192

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 131 of 195 7.8.l3lnhalation Dose Factors - R;l (mrem/y per pCi/m3) The inhalation dose factors are calculated using the equation provided in NUREG-O1 33, Section 5.3.1 .1 . Rri = I 06 DFAioi BRo (7.31) where: 106 = conversion factor, pCi/pCi. DFAiai = inhalation dose conversion factor for nuclide i, age group a and organ j, mrem/pCi (Table 7.7). BR" ' = breathing rate for age group a, m3ly (Table 6.3). 7.8.14 Ground PIane Dose Factors - R61 1m2-mrem/y per pCi/s) The ground plane dose factors are calculated using the equation provided in NUREG-0133, Section 5.3.1.2. The shielding factor in that equation is conservatively assumed to be 1.0. u Ro, - lo BTIIDFG i +[t -.*p(- 1,r, ) ] (7.32) where: tO6 = conversion factor, pCi/pCi. 8760 = conversion factor, h/y. DFG;1 = dose conversion factorfor standing on contaminated ground for nuclide i and organ j (total body

       ' and skin), mrem/h per pCi/m2 (Table 6.6).

li = decay constant of nuclide ;, 3-1 fiable 6.2). tp = time period over which the ground accumulation is evaluated, s (Table 6.3). E1-193

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 132 of 195 7.9 DISPERSION METHODOLOGY Dispersion factors are calculated for radioactive effluent releases using hourly average meteorological data consisting of wind speed and direction measurements at 10m and temperature measurements at 10m and 46m. A sector-average dispersion equation consistent with Regulatory Guide 1.111 is used. The dispersion model considers plume depletion (using information from Figure 7.41, and building wake effects. Tenain effects on dispersion are considered as described in Section 7.9.4. Hourly average meteorological data are expressed as a joint-frequency distribution of wind speed, wind direction, and atmospheric stability. The joint-frequency distribution which represents the historical meteorological data for the period January 1986 to December 2005 is given in Table7.2. The wind speed classes that are used are as follows: Number RanEe (mls Midpoint (m/s) 1 <0.3 0.13 2 0.3-0.6 0.45 3 0.7-1 .5 1.10 4 1.6-2.4 1.99 5 2.5-3.3 2.88 6 3.4-5.5 4.45 7 5.6-8.2 6.91 8 8.3-t0.9 9.59 I >10.9 10.95 The stability classes that will be used are the standard Pasquill A through G classifications. The stability classes 1-7 will conespond to A=1, B=2, ..., G=7. 7.9.1 Air Concentration - X Air concentrations of nuclides at downwind locations are calculated using the folloring equation:

,,=i     L,Effii "^p(-i,,-,J                                                                              s33) where:

fn = joint relative frequency of occunence of winds in windspeed class k, stability class l, blowing toward this exposure point, expressed as a fraction. Qi = average annual release rate of radionuclide i, pCi/s. p = fraction of radionuclide remaining in plume (Figure 7.4). TAF = site specific terrain adjustment factor (from Table 7.3). Calculated as described in Section 7.9.4. Sz = vertical dispersion coefficient for stability class lwhich includes a building wake adjustment,

l" *;c"

           't/"'       '

or = .fi , o1 whichever is smaller. where: s2t is the vertical dispersion coefficient for stability class I (m) (Figure 7.5), c is a building shape factor (c=0.5) (Reference 5), a is the minimum building cross-sectional area (1630 m2) (Reference 23). U1 = midpoint value of wind speed class interval k, m/s. E1- 194

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 133 of {95 x = downwind distance, m. n = numberof sectors, 16. li = radioactive decay coefficient of radionuclide i, s-l 2pxln = sector width at point of interest, m. 7.9.2 Relative Concentration - TgrQ Relative concentrations of nuclides at downwind locations are calculated using the following equation: r-33 E t*'rot-a= 3, i-, {; iffil (T.U) where: ftr = joint relative frequency of occunence of winds in windspeed class k, stability class l, blowing toward this exposure point, expressed as a fraction. TAF = site specific terrain adjustment factor (from Table 7.3). Calculated as described in Section 7.9.4. Sz = vertical dispersion coefficient for stability class I which includes a building wake adjustment,

          ={"'+-

Lc" or = $ oo, whichever is smaller. where: s,; is the vertical dispersion coefficient for stabili$ class I (m) (Figure 7.5), c is a building shape factor (c=0.5) (Reference 5), a is the minimum building cross-sectionalarea (1630 m1(Reference 23). u1 = midpoint value of wind speed class interval k, m/s. x = downwind distance, m. n = numberof sectors, 16. 2pxln = sector width at point of interest, m. 7.9.3 Relative Deposition - D/Q Relative deposition of nuclides at downwind locations is calculated using the following equation: [, dr H D 9 7 TAF o I I (7.35)

-=    k=l   l=l whe rel' frr        = joint relative frequency of occunence of winds in windspeed class k and stability class l,     bloring toward this exposure point, expressed as a fraction.

dr = relative deposition rate, rn-1 (from Figure 7.6). TAF = site specific tenain adjustment factor (from Table 7.3). Calculated as described in Section 7.9.4. x = downwind distance, m. n

   ,n
          = numberof sectors, 16.

2pxl = sector width at point of interest, m. E1-195

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 134 of 195 7.9.4 Terrain Adjustment Factor - TAF As discussed in Reference 5, the straight-line dispersion model does not account for spatial and temporal variations in the airflow expected from the southwest-northeast aligned river valley. Such variations are considered by application of site-specific tenain adjustment factors, TAF. These factors were developed through the comparison of variable trajectory model results with straight-line model results for onsite meteorological data for 1978 (Reference 1 9). The ratio of the variable trajectory model dispersion f;actors to the straight-line model dispersion factors is defined as the TAF. The dispersion factors used in the dose rate and dose calculations described in Sections 7 .2.2, 7 .2.3,7 .3.1 , 7.3.2, and7.4.'l are calculated using the meteorological data from the 1986 to 2005 period (in Table 7.2). 1/Q and D/Q values are calculated for each of the 16 UNRESTRICTED AREA BOUNDARY sector locations (Table 7.1). These are multiplied by the TAF associated with each of these sectors (see Table 7.3). The highest of these dispersion values are chosen for the dose or dose rate calculations. The dispersion factors used in the dose calculations described in Section 7.7 are calculated using the actual meteorological data for the period. 1/Q or D/Q values are calculated using Equations 7.34 and 7.35 for the unrestricted area boundary locations identified in Table 7.'l,lor the 16 nearest resident locations, and all garden and milk animal locations identified in the annual land use census described in Section 9.3. The TAF values associated with these dispersion factors is the ratio of the dispersion factor calculated by the variable trajectory model to that calculated by the straight-line model for each of these locations using the 1978 meteorological data. These values will be calculated for all locations identified by the land use census and then used to modiff the 1/Q and D/Q values determined with the actual meteorological data. Any TAF values of less than 1.0 will be defined as 1.0. E1-196

WBN OFFSITE DOSE CALCUI.ATION MANUAL Revision 23 0 (oDcM) Page 135 of 195 Table 7.1 - WBN - OFFSITE RECEPTOR LOCATION DATA Sector DISTANCE

D/Q*

Receptor x/Q from plant (m) (s/m3) $lm2l Unrestricted Area Boundary N 1 550 3.01E-06 4.78E-09 Unrestricted Area Boundary NNE 1 980 3.53E-06 6.83E-09 Unrestricted Area Boundary NE 1 580 5.00E-06 5.24E-09 U nrestricted Area Boundary ENE 1370 7.24E-06 5.16E-09 Unrestricted Area Boundary E 1280 8.56E-06 6.04E-09 Unrestricted Area Boundary ESE 1250 7.94E-06 6.44E-09 Unrestricted Area Boundary SE 1250 7.40E-06 6.33E-09 Unrestricted Area Boundary SSE 1250 4.03E-06 5.47E-09 U nrestricted Area Boundary S 1340 2.81 E-06 6.16E-09 Unrestricted Area Boundary SSW 1 550 2.07E-06 5.25E-09 Unrestricted Area Boundary SW 1 670 2.12E-06 3.50E-09 Unrestricted Area Boundary WSW 1 430 3.04E-06 3.54E-09 Un restricted Area Boundary W 1460 1.76E-06 1.73E-09 Unrestricted Area Boundary \^/NW 1400 9.96E-08 9.52E-10 Un restricted Area Boundary NW 1400 1.21E-06 1.25E-09 Unrestricted Area Boundary NNW 1460 1.68E-06 1.93E-09 Liquid Discharse N/A N/A NOTE: For quarterly airborne dose calculations, doses will also be calculated for all locations identified in the most recent land use census, and for any additional points deemed necessary. 'These 1/Q and D/Q values must be multiplied by the sector specific Terrain Adjustment Factor (from Table 7.3) priorto selecting the critical UNRESTRICTED AREA BOUNDARY location to be used in dose calculations. E1- 197

WBN OFFSITE DOSE CALCUI-ATION MANUAL Revision 23 0 (oDcM) Page {36 of 195 Table7.2 - JOINT PERCENTAGE FREQUENCIES OF WND DIRECTION AND WND SPEED FOR DIFFERENT STABILITY CLASSES (Page 1 of7) STABILITY CTASS A (DELTA T<:-1 .9 C/ 100 M) Watts Ba. Nuclea! Plant JAN 1, 1986 - DEC 31, 2005 WIND WIND SPEED(I,IPH) DIRECTIoN cAlM 0.6-1.,1 1.5-3.4 3.5-5.4 5.5-?.4 7.5-72.4 f2.5-18.4 1A.5-24.4 >=24.5 TOTAI N 0.000 0. 001 0.01"1 0. 052 0 .079 0.095 0. 005 0. 000 0.000 0.244 NNE 0. 000 0.001 0.o2L 0.084 0 .L24 0. 181 0.007 0. 000 0.000 0.41_8 NE 0. 000 0.000 0. 034 0. 100 0 .080 0.094 0.000 0.000 o. 000 0.308 ENE 0. 000 0.000 0.039 0.076 0 .045 0.017 0. 000 0-o0o 0.000 0.175 E 0. 000 0. 000 0. 037 0.040 0 .010 0. 004 0. 000 0.000 0.000 0.092 ESE 0. 000 0. 000 0. 0t_7 0. 023 .o02 0.001 0. 000 0.000 0.000 0 .o42 SE o. 000 0. 001 0.026 o.o27 .005 0. 004 0. 000 0. 000 0. 000 0.064 SSE 0. 000 0. 000 0.049 0. 063 .015 0.011 0. 001 0. 000 0.000 0. 140 S 0. 000 0.002 o. 070 0. 180 .L42 o -72). 0. 020 0.001 0.000 0.535 ssw 0. 000 0. 000 0. 063 0.371 .594 0.700 0.049 0.001_ 0-000 L.778 SW 0. 000 0. 000 0.029 0.146 .148 0. 065 o. 002 0.000 0.000 0.390 wsw 0. 000 0. 000 0. 007 0. 020 .018 0.040 0. 005 0.000 0.000 0.091 W 0.000 o. 000 0. 006 0. 007 .029 0.059 0. 007 0.000 0.000 0. 108 WNW 0. 000 0. 000 0. 004 0. 01"0 . 011 0.064 0. 005 0. 000 0.000 0.093 NW 0. 000 0. 000 0. 004 0. 007 .019 0. 052 0. 005 0. 000 0.000 0.087 NNW 0. 000 0. 000 0.009 0.02t .038 0.081 0.012 0.000 0.000 0. r.61 SUBTOTAL O. OO]. 0. 005 0 .426 1.226 .359 1.589 0. 1l_9 0.001 0.000 4 .725 TOTAL HOURS OF VAIID STABILITY OBSERVATIONS 170639 TOTAI HOURS OE STABILITY CLASS A 8030 TOTAI HOURS OF VAIID WIND DIRECTION-WIND SPEED-STABILITY CLASS A 7945 TOTAI HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS ].68144 TOTAI HOURS CAIM 1 METEOROLOGICAL EACILITY: Watts BaT Nuclear Plant STABILITY BASED ON DELTA-T BETWEEN 9.51 A}TD 45. 63 METERS WIND SPEED A}ID DIRECTION MEASURED AT 9.'72 I',ETER LEVEL MEAN WIND SPEED : 6.72 NOTE: TOTALS A}ID SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS E1-198

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 137 of 195 Tabte7.2 - JOINT PERCENTAGE FREQUENCIES OF wlND DIRECTION AND WND SPEED FOR DIFFERENT STABILIW CLASSES (Page2 ot7) STABILIIY CLASS B (-1.9< DELTA T<=-1.? c/100 M) Watts Bar Nuclear Plant JAN L, 1986 - DEC 31, 2OO5 WIND WIND SPEED (MPH) DIRECTION cArM 0.6-1.4 1.s-3.4 3.5-5.4 5.5-7.4 7.5-L2.4 L2.5-L8.4 L8.5-24.4 ):24.5 TOTAI N 0. 000 0. 000 o.027 0.o92 0.084 0. 109 0. 005 0. 000 0.000 0.318 NNE 0.000 0. o0t- 0.039 0. 155 o.L47 0.2L2 0.009 0. 000 0. 000 0.563 NE 0.000 0. 000 0.081 o.L47 0.090 0.077 0.001 0. 000 0.000 0.396 ENE 0.000 0. 001 0.058 0.096 0.043 0.01_0 0. 000 0. 000 0.000 0.208 E 0.000 0. 001_ 0.045 0. 052 0. 004 0. 002 0. 000 0. 000 0.000 0.105 ESE 0. 000 0. 002 o.026 0.o22 0. 000 0. 000 0. 000 0. 000 0. 000 0.051 SE 0. 000 0. 000 0.039 0. 032 0. 005 0. 002 0.001 0. 000 0.000 0.078 SSE 0. 000 0. 000 0. 057 o. 035 0. 008 0.004 0. 000 0. 000 0.000 0. 104 S 0.000 0. 001 0. 077 0.148 0. 075 0.039 0.014 0.001 0.000 0.354 SSW 0.000 0.001 0.082 0.322 o.266 0. 199 0. 020 0.000 0.000 0.890 SW 0.000 0. 000 0. 035 0.169 0.054 0.014 0.001, 0. 000 0.000 0.275 rIsw 0. 000 0. 000 0. 007 0. 037 0.015 o.ozL 0.001 0. 000 0.000 0. 081 s{ 0. 000 0. 000 0.006 0.0L1 0.025 0.040 0.009 0. 000 0.000 0. 09r. WNW 0. 000 0. 001 0. 005 0. 0t-4 0. 031 0.079 0. 007 0. 000 0. 000 0. 137 NW 0. 000 0. 000 0. 007 0.015 0. 033 0.071 0. 008 0.000 0.000 0. 135 NNW 0.000 0. 000 0.011 0. 034 0.040 0.079 0. 008 0.000 0. 000 0. 173 SUBTOTAL O. OOO 0. 007 0. 606 1. 383 0 .923 0.958 0.083 0. 00r. 0.000 3. 960 TOTAI HOURS OF VALID STABILITY OBSERVATIONS 170639 TOTAL HOURS OF STABILITY CI"ASS B 6'722 TOTAL HOURS OF VAIID WIND DIRECTION-WIND SPEED-STABILITY CI,ASS B 5659 TOTAI HOURS OE VAIID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS ]-68]-44 TOTAI HOURS CALM O METEOROLOGICAL FACILITY: Watts Bar Nuclear Plant STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 I"frTER LEVEL MEAN hIIND SPEED = 5.98 NOTE: TOTALS A}ID SUBTOTAIS ARE OBTAINED EROM UNROUNDED NUMBERS E1-199

WBN OFFSITE DOSE CALCUI.ATION MANUAL Revision 23 0 (oDcM) Page 138 of 195 Table 7.2 - JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES (Page 3 of7) STABILITY CLASS C (-1.7< DELTA T(:-1.5 C/100 M) Watts Bar Nuclear Plant JAti L, 1986 - DEC 31, 2005 WIND WIND SPEED (MPH) DIRECTION CALM 0.5-1.4 1,.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 L2.5-L8.4 1.8.5-24.4 ):24.5 TOTAL N 0. 000 0. 001 0 .060 0. 141 o.t25 0.151 0. 007 0.000 0.000 0.485 NNE 0. 000 0.001_ 0 . 111 0.224 0.209 0.260 0. 013 0.000 0.000 0.817 NE 0. 000 0. 003 0 .139 0.221, 0. L17 0.070 0. o0l_ 0. 000 0.000 0.552 ENE 0. 000 0. 001 0 . 113 0.L27 0.030 0. 00s 0.001 0.000 0.000 a.277 E 0. 000 0. 005 0 .080 0.049 0. 005 0. 002 0. 000 0.000 0.000 0. 140 ESE 0. 000 0. 003 0 .054 0.028 0.002 0.001 0.000 0.000 0. 000 0. 088 SE o. 000 0.002 . 071 0. 033 o.002 0. 00r, 0. 000 0.000 0.000 0. 109 SSE 0. 000 0. 002 .080 0. 064 0. 009 0. 004 0. 002 0. 000 0.000 0. 161 S 0. 000 0. 001 .L28 0.230 0. 085 0.048 0.008 0.001 0.000 0.503 SSW 0. 000 0. 001 .L52 o-423 0.256 0.t77 . 019 0. 000 0. 000 L.o28 SW 0. 000 0. 001 .080 o -225 0. 070 0.011 .001 0. 000 0. 000 0.387 wsw 0.000 0. 001- .423 0.049 0.026 0-015 .001 0. 000 0. 000 0. 117 w 0. 000 0.001 .016 0.027 0.039 0 .042 .004 0. 000 0. 000 0. 130 wNw 0.000 0. 000 . 013 0. 030 0.049 0. 111 .010 0. 000 0.000 0.2L4 NW 0. 000 0. 000 .o20 0.036 0.043 0.096 . 011 0. 000 0. 000 0 .206 NNW 0. 000 0. 000 .o32 0.059 0.064 0.098 . 011 0. 000 0.000 0.264 SUBTOTAI O. OOO 0. 023 .t71 1. 968 t .130 1.093 0.089 0.001 0.000 5.476 TOTAI HOURS OF VAIID STABILITY OBSERVATIONS 170639 TOTAL I{OURS OT STABILITY CI,ASS C 9309 TOTAL HOURS OT VAL]D WIND DIRECTION-WIND SPEED-STABILITY CTASS C 9207 TOTAI HOURS OF VAIID WIND DIRECTION-WIND SPEED_STABILITY OBSERVATIONS ]-68]-44 TOTAI HOURS CALM O METEOROLOGICAI FACILITY: Watts Bar Nuclear Plant STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AI{D DIRECTION MEASURED AT 9.72 I,BTER LEVEL MEAN If,IND SPEED : 5.57 NOTE: TOTA],S AND SUBTOTAIS ARE OBTAINED FROM UNROUNDED NUMBERS E1-200

WBN OFFSITE DOSE CALGUI.ATION MANUAL Revision 23 0 (oDcM) Page 139 of {95 Table7.2 - JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WlND SPEED FOR DIFFERENT STABILIW CLASSES (Page 4 of7) STABILITY CLASS D (-1.5< DELTA T<=-0.5 C,/100 M) Watts Bar Nuclear Plant JAII L, 1986 - DEC 31, 2005 WIND WIND SPEED (MPH) DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-L8.4 L8.5-24.4 )=24 -5 TOTAL N 0.006 0. 050 0.656 0.996 1.063 1.203 0. 034 0. 000 0.000 4.007 NNE 0.005 0. 052 0 .697 r.241 L.206 1,.l-82 0.072 0. 002 0.000 4.458 NE 0.007 0.064 0.796 1. 060 0 .4't7 0.203 0. 005 o. 000 0.000 2.6L2 ENE 0.008 0. 095 0.840 0.479 0. 1r_5 0. 038 0. 002 0. 000 0. 000 L.577 E 0.005 0.L26 0.478 0. 137 0.o22 0. 005 0.000 0. 000 0. 000 0.77 4 ESE 0.003 0.081 4.275 0. 057 0. 006 0. 004 0. 000 0. 000 0.000 0.426 sE 0.004 0.090 0.369 0.076 0.022 0.01_4 0.001 0.001_ 0. 000 0. s75 ssE 0.006 0. 133 0.566 0.160 0. 035 0. 034 0.014 0. 000 0.000 0. 949 s 0.011 o .1,7 4 1. 104 0. 699 o -296 o.25L 0.076 0. 004 0.000 2.6L5 ssw 0.015 0. 145 r_. 610 1.795 0 .927 0.815 0.076 0. 002 0.000 5.386 s[{ 0. 010 o.L67 1.060 0.790 0.202 0. 097 0.004 0. 000 0.000 2.329 [{s[lr 0.006 0. 109 0. 558 0 -289 0.L23 0.088 o. 004 0. 000 0.000 L.1-77 hr 0. 005 o.L2t 0.406 0.293 0.258 0.256 0. 008 0. 000 0. 000 L.347 htNw 0. 004 0.095 0.353 0.394 0.491 0.520 0.021 0. 000 0.000 1.879 NW 0.004 0.071 0.353 0.403 0.532 0. 608 0.046 0. 001- 0.000 2.0L7 NNW 0.004 0.042 0.445 0.556 0. 631 0,795 0. 034 0. 000 0. 000 2.5L7 SUBTOTAL 0.104 1. 515 10.566 9.436 6.405 6.113 0.395 0.010 0.000 34.645 TOTAL HOURS OT VAIID STABILITY OBSERVATIONS 170639 TOTAL HOURS OF STABILITY CI,ASS D 58946 TOTAI HOURS OT VAIID WIND DIRECTION-hIIND SPEED-STABILITY CLASS D 58253 TOTAL HOURS OF VALID WIND DIRECTION-$IIND SPEED.STABILITY OBSERVATIONS 168144 TOTAL HOURS CALM 175 I{ETEOROLOGICEL TACILTTY: WAttS BAr Nuclear PIant STABILITY BASED ON DELTA_T BETWEEN 9.51- AND 45. 63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 N,ETER LEVEL MEAI-I WIND SPEED : 4.96 NOTE: TOTALS A}ID SUBTOTAIS ARE OBTAINED FROM I,NROUNDED NUMBERS E1-201

WBN OFFSITE DOSE CALCUTATION MANUAL Revision 23 0 (oDcM) Page 140 of 195 Table 7.2 - JOINT PERCENTAGE FREQUENCIES OF WND DIRECTION AND WND SPEED FOR DIFFERENT STABI LITY CLASSES (Page 5 of7) STABILITY CLASS E (-0.5< DELTA T(: 1.5 C/ 100 M) Watts Bar Nuclear Plant JAN L, 1986 - DEC 3l-, 2005 I,{IND WIND SPEED (MPH) DIRECTION 0.6-1".4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 L2.5-18.4 L8.5-24.4 ):24.5 TOTAL N 0. 032 0. 155 0.484 o-623 0.300 o.062 0. 002 0. 000 0.000 1. 659 NNE a.029 0.L42 0.431 0.322 0.171 0.047 0.003 0. 000 0 - 000 1. 144 NE 0.039 0. 169 0. 606 0.366 0. 068 0.012 0.003 0. 000 0. 000 7.264 ENE 0. 053 o.240 0.813 0. 196 0.01_5 0.004 0. 001- 0. 000 0. 000 1.32t E 0.029 0.27-t 0. 310 0.040 0 . 01r. 0. 003 0. 000 0. 000 0.000 0. 671 ESE 0.0r_4 0. 157 0. 118 0.024 0.006 0. 004 o. 001- 0. 000 0.000 0.333 SE 0.018 0.203 0.149 0.048 0.025 0.017 o. 002 0. 000 0.000 0.462 SSE 0. 032 0.324 0.321 0.083 0.051 0. 039 o. 007 0.000 0.000 0.856 S 0.0't7 0.519 L.OL2 0.415 0.197 0. 193 0 . 041, 0.001 0.000 2.454 SSW o.L23 0. 504 1.864 1.178 0.645 0.516 0.051 0. 000 0.000 4.98r. sw 0-101 0.731- L.29L 0.307 0 .1.2L 0.462 0. 002 0. 000 0.000 2.6L6

     !\Isv{         0.072         0.735      0.711           0.L47      0. 087         0. 037        0.001    0. 000   0.000    L.792 hI             0.064         0. 698     0.591           0. 194     0. 083         0. 034        0-000    0.000    0.000    7.564 IIINW          0.059         0. 645     0.537           o.263      0. 099         0. 037        0.001-   0.000    0.000    1.642 NW             0.048         0.461      0. s07          0.2-t9     0. 108         0. 047        0. 002   0.001    0.000    1.453 NNhI           0. 035        0.255      0.457           0.375      o.247          o.o92         0.005    0. 000   0.000    1.465 suBToTAt      0.827         6.326    r.0.201           4.862      2.234          L.206         0.121,   0. 002   0. 000  25 .777 TOTAI HOURS OF VAJ,ID STABILITY OBSERVATIONS                                            t_70639 TOTAL HOURS OF STABILITY CI,ASS E                                                         44130 TOTAL HOURS OF VA],ID WIND DIRECTION-WIND SPEED.STABILITY CLASS            E              43343 TOTAL HOURS OF VAIID WIND DIRECTION-IIIIND SPEED-STABTLITY OBSERVATIONS 168144 TOTAI HOURS CAI,M                                                                          1390 METEOROLOGICAI FACILITY: ttlatts Bar Nuclear Plant STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT         9.'12 I"'ETER LEVEL MEAN WIND SPEED    :   3.03 NOTE:  TOTAI,S AI.ID SUBTOTALS ARE OBTAINED FROM UNROUNDED NI,MBERS E1-202

WBN OFFSITE DOSE CALCU1ATION MANUAL Revision 23 0 (oDcM) Page 141 of 195 Table 7.2 - JOINT PERCENTAGE FREQUENCIES OF WIND DIREGTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES (Page 6 of7) STABILITY CI"ASS F ( 1.5< DELTA T(: 4.A C/ 100 M) Watts Bar Nuclear Plant JAI'I l, 1986 - DEC 31, 2005 WIND WIND SPEED (MPH) DIRECTTON CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 L2.5-L8.4 L8.5-24.4 ):24.5 TOTAI N 0.045 4.268 0 . 181_ 0. 018 0.001 0.001 0. 000 0. 000 0.000 0.515 NNE 0. 038 0. t-99 o.L72 0.016 0. 002 0.001 0. 000 0.000 0.000 0.429 NE 0. 050 0.218 0.266 0.029 0. 002 0. 000 0. 000 0. 000 0.000 0.565 ENE 0-064 0.275 0.348 0.032 0. 002 0. 001 0. 000 0. 000 0. 000 0.72L E 0. 033 0 . L9"7 0.L23 0. 005 0. 001_ 0. 000 0. 000 0. 000 0. 000 0. 358 ESE 0. 015 O.L2L 0.02-7 0. 000 0-000 0. 000 0. 000 0.000 0. 000 0. 163 SE 0.016 0. l_19 0. 036 0. 004 0.001 0.001- 0. 000 0. 000 0. 000 0.L76 SSE 0. 025 o.L77 0. 066 0. 0r-0 0.001 0. 002 0.001 0. 000 0.000 0.282 S 0. 055 0.313 36 .o32 0.004 0. 002 0. 000 0. 000 0.000 0.643 SSW 0. 103 0.459 47 .156 0.020 0. 004 0. 000 0.000 0.000 L.290 sw 0. 136 0. 698 27 .040 0. 006 0.001 0. 000 0. 000 0. 000 1".507 wsw 0. 167 0. 994 39 .023 0. 002 0.001 0. 000 0. 000 0.000 L.827 hI 0. 183 L.268 22 .02L 0.003 0.001 0. 000 0. 000 0.000 1.999 hINW 0.17'7 t.279 47 .029 0.001 0.001 0. 000 0. 000 0.000 L. 933 NW 0. 171 1. 198 72 .034 0.002 0.001 0. 000 0. 000 0.000 1.878 NNW 0. 080 0.525 54 .036 0. 002 0.001 0. 000 0. 000 0.000 0.897 SUBTOTAL 1.360 8.307 4.963 0.486 0.049 0.016 0.001 0-000 0 . 000 15 . l_81 TOTAI HOURS OF VAIID STABILITY OBSERVATIONS 170639 TOTA], HOURS OE STABILITY CI,A"SS E 26048 TOTAT HOURS OE VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS F 25526 TOTAI HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 168144 TOTAI HOURS CAI,M 2286 METEOROLOGICAI FACILITY: Watts Bar Nuclear Plant STABILITY BASED ON DELTA-T BETWEEN 9.51 AT'ID 45.53 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 I"IF,TER LEVEL MEAII WIND SPEED : 1,.42 NOTE: TOTAI,S AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS E1-203

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 142 of 195 Table7.2 - JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILIW CLASSES (Page 7 of7) STABILITY CLASS G (DELTA T > 4.0 C/ 100 M) Watts Bar Nuclear Plant JAN r, 1986 - DEC 31, 2005 hIIND rilIND SPEED (MPH) DIRECTTON 0. 6-1 .4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-t2.4 L2.5-78.4 L8.5-24.4 ):24.5 N 0. 035 0.221 0.065 0.001_ 0. 000 o-000 0. 000 0.000 0.000 0.323 NNE 0. 034 0. 199 0. 077 0.001 0. 000 0. 000 0. 000 0.000 0. 000 0.31-0 NE 0.048 0.271 o.t23 0. 002 0. 000 0.000 0. 000 0. 000 0.000 0.444 ENE 0.059 0.300 0. 188 0.004 0. 001_ 0. 000 0. 000 0.000 0.000 0.551 E 0. 032 o.202 o.058 o. 002 0.000 0. 000 0. 000 0.000 0. 000 0 .294 ESE 0.015 0. 116 0.018 0. 000 0. 000 0. 000 0.000 0.000 0.000 0. 151 SE 0.021 0. 145 0. 023 0. 000 0.000 0. 000 0. 000 0.000 0.000 0. 1 89 SSE 0. 02s o. 173 0. 032 0.001 0.000 0. 000 0. 000 0.000 0.000 0.237 S 0. 035 o -246 0-051 0. 002 0. 000 0. 000 0. 000 0.000 0.000 0.335 SSW 0. 050 0.357 o.L23 0. 005 0.001 0. o0o 0. 000 0.000 0. 000 0.556 SW 0.096 0.559 o.222 0. 002 0. 000 0.000 0.000 0. 000 0.000 0.889 WSW 0.762 0. 916 0.4r-0 0. 007 0. 000 0.000 0.000 0. 000 0.000 1.495 W 0.169 1. 036 0.351 o.oo2 0. 000 0. 000 0. 000 0. 000 0.000 1.559 WNW 0. 1"30 0. 825 0.240 0. 004 0.000 0. 000 0.000 0. 000 0.000 L.200 NW 0.L27 0.751 0.292 0. 002 0.000 0. 000 0. 000 0. 000 0.000 1. 173 NNW 0. 058 0.356 4.]-20 0. 002 0.000 0. 000 0.000 0. 000 0.000 0.536 SUBTOTAL 1. ].09 6. 695 2.394 0.037 0.001 0. 000 0. 000 0. 000 0.000 t0.236 TOTAL HOURS OF VAIID STABILITY OBSERVATIONS r.70 639 TOTAL HOURS OF STABILITY CLASS G 17 454 TOTAL HOURS OE VAIID WIND DIRECTION.WIND SPEED-STABILITY CLASS G T72LL TOTAI HOURS OF VAIID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS L68L44 TOTAI, HOURS CATM r_8 64 METEOROLOGICAL EACILITY: Watts Bar Nuclear Plant STABILITY BASED ON DELTA-T BETV{EEN 9.51 AND 45.63 METERS WIND SPEED AITD DIRECTION MEASURED AT 9.72 I,'tr'IER LEVEL MEAN WfND SPEED : 1.L4 NOTE: TOTA],S A}TD SUBTOTALS ARE OBTAINED FROM UNROi,NDED NI.,MBERS E1-204

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 143 of 195 Table 7.3 - ADJUSTED DISPERSION FACTORS Sector TAF* 1/afiNF) Dro(rAF) (stmr) (lmll N 1.7 5.12E-06 8.13E-09 NNE 1.8 6.35E-06 1.23E-08 NE 2.1 1.05E-05 1 .10E-08 ENE 1.7 1.23E-05 8.77E-09 E 1.6 1.37E-05 9.66E-09 ESE 1.8 1.43E-05 1 .16E-08 SE 1.5 1.11E-05 9.49E-09 SSE 1.5 6.04E-06 8.21E-09 S 1.9 5.33E-06 1.17E-08 SSW 2.0 4.14E-06 1.05E-08 SW 2.1 4.46E-06 7.34E-09 WSW 1.8 5.47E-06 6.37E-09 W 1.2 2.11E-06 2.07E-09 WNW 2.5 2.49E-06 2.38E-09 NW 1.7 2.05E-06 2.13E-09 NNW 1.6 2.68E-06 3.08E-09

The Site Specific Tenain Adjustment Factor fiAF) is equalto the ratio of the variable trajectory;6/Q the straight-line 1/Q. See ODCM Section 7 .9.4lor a full explanation.

E1-205

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 14 of 195 Table 7.4 - DOSE FAGTORS FOR SUBMERSION IN NOBLE GASES Submercion dose Air dose mrem/y per uCi/m3 mrad/v per uCi/m3 DFni DF-si DF.'i DFr'i 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 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.1 7E+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-1 31m 9.1 5E+01 4.76E+02 1.56E+02 1.11E+03 Xe-1 33m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-1 33 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-1 35m 3.1 2E+03 7.11E+02 3.36E+03 7.39E+02 Xe-1 35 1.81 E+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-1 38 8.83E+03 4.1 3E+03 9.21E+03 4.75E+03 Ar41 8.84E+03 2.69E+03 9.30E+03 3.28E+03

Reference:

Regulatory Guide 1 .109, Table B-1 . E1-206

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 145 of 195 Table 7.5 - SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES Range of Sector Element Midpoint of Sector Element (mi) (mi) Unrestricted Area Boundary - 1 0.8 1-2 1.5 2-3 2.5 3-4 3.5 4-5 4.5 5 - 10 7.5 10-20 15 20-30 25 30-40 35 40-50 45

I WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 146 of 195 Table 7.6 - POPULATION WITHIN EAGH SECTOR ELEMENT Distance from Site (miles) 0-1 1-2 2-3 34 4-5 5-10 10-20 2040 3040 40-50 N 0 111 32 47 13s 893 2071 2166 3453 4040 NNE 0 25 25 76 43 796 8591 19187 9342 1194 NE 0 0 130 208 130 861 3381 19210 30623 54111 ENE 0 2555378 252 2445 9497 38457 1 36395 E 0 275338 482 9716 8837 1 0649 17404 ESE 0 244758 591 4514 12085 3420 300 SE 0 0163529 505 7835 081 8 1 1 3969 3756 SSE 12 2332724 714 4018 8056 3899 6362 S 0 54 14 24 257 1 368 1141 34699 40812 11522 SSW 0 3471932 739 5653 17523 25829 1 17868 SW 0 0520 51 9 6490 9411 68565 1 25338 wsw 0 10 40 38 30 1281 10369 2091 7134 6571 W 2 5 19 59 65 837 965 5337 2839 2035 wNw 5 30 10 140 121 244 1461 2925 3440 1 7598 NW 0 1 0 111 113 387 2279 314 7266 7004 9802 NNW 0 0628798 2081 874 18279 4784 2983 Total 19 308 540 1028 1525 14442 79838 187387 264219 517279 Total 1 066s85 1990 Population data from Reference 10 E1-208

WBN OFFSITE DOSE CALCULATpN MANUAL Revision 23 0 (oDcM) Page 147 of 195 Table 7.7 - INHALATION DOSE FACTORS - DFi"o (mrem/pCi inhaled) (Page 1 of 8) ADULT Nuclide bone liver total body thyroid kidney lung GI.LLI H-3 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 c-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Na-24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P-32 1.65E-04 9.64E-06 6.26E-06 0.00E+00 0.00E+00 0.00E+00 1.08E-05 Cr-S1 0.00E+00 0.00E+00 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 0.00E+00 4.95E-06 7.87E-07 0.00E+00 1.23E-06 1.75E-04 9.67E-06 Mn-56 0.00E+00 1.55E-10 2.29E-11 0.00E+00 1 .63E-10 1 .18E-06 2.53E-06 Fe-55 3.07E-06 2.12E-06 4.93E-07 0.00E+00 0.00E+00 9.01E-06 7.54E-07 Fe-59 1.47E-06 3.47E-06 1.32E-06 0.00E+00 0.00E+00 1.27E-04 2.35E-05 Co-57 0.00E+00 8.65E-08 8.39E-08 0.00E+00 0.00E+00 4.62E-05 3.93E-06 Co-58 0.00E+00 1.98E-07 2.59E-07 0.00E+00 0.00E+00 1 .16E-04 1.33E-05 Co-60 0.00E+00 1.44E-06 1.85E-06 0.00E+00 0.00E+00 7.46E-04 3.56E-05 Ni-63 5.40E-05 3.93E-06 1.81E-06 0.00E+00 0.00E+00 2.23E-05 1.67E-06 Ni-65 1.92E-10 2.62E-11 1.14E-11 0.00E+00 0.00E+00 7.00E-07 1.54E-06 Cu64 0.00E+00 1.83E-10 7.69E-1 1 0.00E+00 5.78E-10 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-05 5.82E-06 0.00E+00 8.62E-06 1.08E-04 6.68E-06 Zn-69 4.23E-12 8.14E-12 5.65E-1 3 0.00E+00 5.27E-12 1 .15E-07 2.04E-09 Zn-69m 1.02E-09 2.45E-09 2.24E-10 0.00E+00 1.48E-09 2.38E-06 1 .71E-05 Br-82 0.00E+00 0.00E+00 1.69E-06 0.00E+00 0.00E+00 0.00E+00 1.30E-06 Br-83 0.00E+00 0.00E+00 3.01 E-08 0.00E+00 0.00E+00 0.00E+00 2.90E-08 Br-84 0.00E+00 0.00E+00 3.91 E-08 0.00E+00 0.00E+00 0.00E+00 2.05E-1 3 Br-85 0.00E+00 0.00E+00 1.60E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.69E-05 7.37E-06 0.00E+00 0.00E+00 0.00E+00 2.08E-06 Rb-88 0.00E+00 4.84E-08 2.41E-08 0.00E+00 0.00E+00 0.00E+00 4.18E-1 I Rb-89 0.00E+00 3.20E-08 2.12E-08 0.00E+00 0.00E+00 0.00E+00 1.16E-21 Sr-89 3.80E-05 0.00E+00 1.09E-06 0.00E+00 0.00E+00 1.75E-04 4.37E-05 Sr-90 1.24E-02 0.00E+00 7.62E-04 0.00E+00 0.00E+00 1.20E-03 9.02E-05 Sr-91 7.748-09 0.00E+00 3.13E-10 0.00E+00 0.00E+00 4.56E-06 2.39E-05 Sr-92 8.43E-1 0 0.00E+00 3.64E-1 1 0.00E+00 0.00E+00 2.06E-06 5.38E-06 Y-90 2.61E-07 0.00E+00 7.01E-09 0.00E+00 0.00E+00 2.12E-05 6.32E-05 Y-91m 3.26E-1 1 0.00E+00 1.27E-12 0.00E+00 0.00E+00 2.40E-07 1 .66E-10 Y-91 5.78E-05 0.00E+00 1.55E-06 0.00E+00 0.00E+00 2.13E-04 4.81 E-05 Y-92 1.29E-09 0.00E+00 3.77E-11 0.00E+00 0.00E+00 1.96E-06 9.19E-06 Y-93 1 .18E-08 0.00E+00 3.26E-10 0.00E+00 0.00E+00 6.06E-06 5.27E-05 Zr-95 1.34E-05 4.30E-06 2.91E-06 0.00E+00 6.77E-06 2.21 E-04 1.88E-05 Zr-97 1.21E-08 2.45E-09 1 .13E-09 0.00E+00 3.71E-09 9.84E-06 6.54E-05 Nb-95 1.76E-06 9.77E-07 5.26E-07 0.00E+00 9.67E-07 6.31 E-05 1.30E-05 Nb-97 2.78E-11 7.03E-12 2.56E-12 0.00E+00 8.18E-12 3.00E-07 3.02E-08 Mo-99 0.00E+00 1.51E-08 2.87E-09 0.00E+00 3.64E-08 1.14E-05 3.1 0E-05 Tc-99m 1.29E-13 3.64E-13 4.63E-12 0.00E+00 5.52E-12 9.55E-08 5.20E-07 Tc-101 5.22E-15 7.52E-15 7 .38E-14 0.00E+00 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91E-07 0.00E+00 8.23E-08 0.00E+00 7.298-07 6.31E-05 1.38E-05 Ru-105 9.88E-1 1 0.00E+00 3.89E-1 1 0.00E+00 1.27E-10 1.37E-06 6.02E-06 Ru-106 8.64E-06 0.00E+00 1.09E-06 0.00E+00 1.67E-05 1 .17E-03 1.14E-04 E1-209

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 148 of {95 Table7.7 - INHALATION DOSE FACTORS - DF6o (mrem/pCi inhaled) (Page 2 of 8) ADULT Nuclide bone liver totalbody thyroid kidney lung Gl-LLl Ag-110m 1.35E-06 1.25E-06 7.43E-07 0.00E+00 2.46E-06 5.79E-04 3.78E-05 Sb-124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 0.00E+00 3.10E-04 5.08E-05 Sb-125 6.67E-06 7.44E-08 1.58E-06 6.75E-09 0.00E+00 2.18E-04 1.26E-05 Sn-125 1.16E-06 3.12E-08 7.03E-08 2.59E-08 0.00E+00 7.37E-05 6.81E-05 Te-125m 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127m 1.58E-06 7.21E-07 '1.96E-07 4.11E-07 5.72E-6 '1.20E-04 1.87E-05 Te-127 1.75E-10 8.03E-11 3.87E-'l'l 1.32E-'10 6.37E-'10 8.14E-O7 7.17E-6 Te-129m 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-U 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.UE-11 2.42E-07 1.96E-08 Te-131m 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 Te-131 1.39E-12 7.44E-'13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 '1.82E-07 3.60E-05 6.37E-05 l-130 5.72E47 1.68E-06 6.60E-07 1.42E-04 2.61E-06 0.00E+00 9.61E-07 l-131 3.15E-06 4A7E-06 2.56E-06 1.49E-03 7.66E-06 0.00E+00 7.85E-07 l-132 '1.45E-07 4.07E-07 '1.45E-07 1.43E-05 6.48E-07 0.00E+00 5.08E-08 l-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 0.00E+00 1.11E-06 f-134 8.05E-08 2.16E-O7 7.69E-08 3.73E-06 3.448-07 0.00E+00 1.26E-10 l-135 3.35E-07 8,73E-07 3.21E-07 5.60E-05 1.39E-06 0.00E+00 6.56E-07 Cs-134 4.66E-05 1.06E-04 9.10E-05 0.00E+00 3.59E-05 1.22E-05 1.30E-06 Cs-136 4.88E-06 1.83E-05 1.38E-05 0.00E+00 1.07E-05 1.50E-06 1.46E-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 0.00E+00 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-08 7.76E-08 4.05E-08 0.00E+00 6.00E-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 0.00E+00 7.78E-14 4.70E-07 1.'l2E-07 Ba-140 4.88E-06 6.13E-09 3.21E-07 0.00E+00 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 0.00E+00 8.75E-15 2A2E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 0.00E+00 2.86E-15 1A9E-07 1.96E-26 La-'140 4.30E-08 2.17E-08 5.73E-09 0.00E+00 0.00E+00 1.70E-05 5.73E-05 La-142 8.54E-11 3.88E-11 9.65E-12 0.00E+00 0.00E+00 7.91E-O7 2.6/,E-07 Ce-141 2.49E-06 1.69E-06 1.91E-07 0.00E+00 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-08 '1.72E48 1.91E-09 0.00E+00 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-U 2.30E-05 0.00E+00 1.06E-04 9.72E-O4 1.O2E-U Pr-143 1.17E-06 4.69E-07 5.80E-08 0.00E+00 2.70E-07 3.51E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91E-13 0.00E+00 8.81E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E.o7 4.56E-08 0.00E+00 4.45E-07 2.76E-05 2.16E-05 W-187 1.06E-09 8.85E-10 3.10E-10 0.00E+00 0.00E+00 3.63E-06 1.94E-05 Np-239 2.87E-08 2.82E49 1.55E-09 0.00E+00 8.75E-09 4.70E-06 1.49E-05

Reference:

Dose Factors for Co-57, Zn9m, Br-82, Nb-97, Sb-124, Sb-125, Sn-125 are from Reference 17, Table 8. Allotherc from: Regulatory Guide 1.109, Table E-7. NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. This assumes that tritium will act similarly in all organs (Reference 24). E1-210

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 149 of 195 Table 7.7 - INHALATION DOSE FACTORS - DFi"o (mrem/pCi inhaled) (Page 3 of 8) TEEN Nuclide bone liver total body thyroid kidney lung GI.LLI H-3 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 c-14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Na-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.728-06 P-32 2.36E-04 1.37E-05 8.95E-06 0.00E+OO 0.00E+00 0.00E+00 1 .16E-05 Cr-S1 0.00E+00 0.00E+00 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 Mn-54 0.00E+00 6.39E-06 1.05E-06 0.00E+00 1.59E-06 2.48E-04 8.35E-06 Mn-56 0.00E+00 212E-10 3.15E-1 1 0.00E+00 2.24E-10 1.90E-06 7.1 8E-06 Fe-55 4.18E-06 2.98E-06 6.93E-07 0.00E+00 0.00E+00 1.55E-05 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 0.00E+00 0.00E+00 1.91 E-04 2.23E-05 Co-57 0.00E+00 1 .18E-07 1 .15E-07 0.00E+00 0.00E+00 7.33E-05 3.93E-06 Co-58 0.00E+00 2.59E-07 3.47E-07 0.00E+00 0.00E+00 1.68E-04 1 .1 9E-05 Co-60 0.00E+00 1.89E-06 2.48E-06 0.00E+00 0.00E+00 1.09E-03 3.24E-05 Ni-63 7.25E-05 5.43E-06 2.47E-06 0.00E+00 0.00E+00 3.84E-05 1.77E-06 Ni-65 2.73E-10 3.66E-1 1 1.59E-1 1 0.00E+00 0.00E+00 1 .17E-06 4.59E-06 Cu-64 0.00E+OO 2.54E-10 1 .06E-10 0.00E+00 8.01E-10 1.39E-06 7.68E-06 Zn-65 4.82E-06 1.67E-05 7.80E-06 0.00E+00 1.08E-05 1.55E-04 s.83E-06 Zn-69 6.04E-12 1.15E-1 1 8.07E-13 0.00E+OO 7 .53E-12 1.98E-07 3.56E-08 Zn-69m 1.44E-09 3.39E-09 3.11E-10 0.00E+00 2.06E-09 3.92E-06 2.14E-05 Br-82 0.00E+00 0.00E+00 2.28E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+OO Br-83 0.00E+00 0.00E+00 4.30E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 5.41E-08 0.00E+OO 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 2.29E-09 0.00E+00 0.00E+OO 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.38E-05 1.05E-05 0.00E+00 0.00E+00 0.00E+00 2.21 E-06 Rb-88 0.00E+00 6.82E-08 3.40E-08 0.00E+00 0.00E+00 0.00E+00 3.65E-1 5 Rb-89 0.00E+00 4.40E-08 2.91 E-08 0.00E+OO 0.00E+00 0.00E+00 4.22E-17 Sr-89 5.43E-05 0.00E+00 1.56E-06 0.00E+00 0.00E+00 3.02E-04 4.64E-05 Sr-90 1.35E-02 0.00E+00 8.35E-04 0.00E+00 0.00E+00 2.06E-03 9.56E-05 Sr-91 1 .10E-08 0.00E+00 4.39E-10 0.00E+00 0.00E+00 7.59E-06 3.24E-05 Sr-92 1.19E-09 0.00E+00 5.08E-1 1 0.00E+00 0.00E+00 3.43E-06 1.49E-05 Y-90 3.73E-07 0.00E+00 1.00E-08 0.00E+00 0.00E+00 3.66E-os 6.99E-05 Y-91m 4.63E-1 1 0.00E+00 1.77E-12 0.00E+00 0.00E+00 4.00E-07 3.77E-09 Y-91 8.26E-05 0.00E+00 2.21E-06 0.00E+00 0.00E+00 3.67E-04 5.1 1 E-05 Y-92 1.84E-09 0.00E+00 5.36E-1 1 0.00E+00 0.00E+00 3.35E-06 2.06E-05 Y-93 1.69E-08 0.00E+00 4.65E-10 0.00E+00 0.00E+00 1.04E-05 7.24E-05 Zr-95 1.82E-0s 5.73E-06 3.94E-06 0.00E+00 8.42E-06 3.36E-04 1.86E-05 Zr-97 1.72E-08 3.40E-09 1 .57E-09 0.00E+00 5.1 5E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 0.00E+00 1.25E-06 9.39E-05 1.21E-05 Nb-97 3.92E-11 9.72E-12 3.55E-12 0.00E+00 1.14E-11 4.91E-07 2.71E-07 Mo-99 0.00E+00 2.11E-08 4.03E-09 0.00E+OO 5.14E-08 1.92E-05 3.36E-05 Tc-99m 1.73E-13 4.83E-13 6.24E-12 0.00E+00 7.20E-12 1.44E-07 7.66E-07 Tc-1 01 7.40E-15 1.05E-14 1 .03E-13 0.00E+00 1.90E-13 8.34E-08 1.09E-16 Ru-103 2.63E-07 0.00E+00 1.12E-07 0.00E+00 9.29E-07 9.79E-05 1.36E-05 Ru-105 1.40E-1 0 0.00E+00 5.42E-11 0.00E+00 1 .76E-10 2.27E-06 1 .1 3E-05 Ru-106 1.23E-05 0.00E+00 1.55E-06 0.00E+00 2.38E-05 2.01E-03 1.20E-04 E1-211

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 150 of 195 Table 7.7 - INHALATION DOSE FACTORS - DF6o (mrem/pCi inhaled) (Page 4 of 8) TEEN Nuclide bone liver total body thyroid kidney Iung Gl-LLl Ag-110m 1.73E-06 1.44E-06 9.99E-07 0.00E+00 3.13E-06 8.4r',E-04 3.41E-05 Sb-124 5.38E-06 9.92E-08 2.10E-06 1.22E48 0.00E+00 4.81E-04 4.98E-05 Sb-125 9.23E-06 1.01E-07 2.15E-06 8.80E-09 0.00E+00 3.42E-04 1.24E-Os Sn-125 1.66E-06 4.42E-08 9.99E-08 3.45E-08 0.00E+00 1.26E-04 7.29E-O5 Te-125m 6.10E-07 2.80E-07 8.34E-08 '1.75E-07 0.00E+00 6.70E-05 9.38E-06 Te-127m 2.25E-OO 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-U 1.99E-05 Te-127 2.51E-10 1.14E-10 5.52E-1'l '1.77E-10 9.10E-'10 1.40E-06 1.01E-05 Te-129m 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-1'l 4.12E-07 2.O2E-07 Te-13'1m 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-OS 7.76E-05 Te-131 1.97E-'12 1.0/,E-12 6.30E-13 1.55E-'12 7.72E-12 2.92E-07 1.89E-09 Te-132 4.50E-08 3.63E-08 2.74E-Og 3.07E-08 2.44E-07 5.61E-05 5.79E-05 l-130 7.80E-07 2.24E-6 8.96E-07 1.86E-04 3.44E-06 0.00E+00 1.14E-06 !-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 0.00E+00 8.11E-07 t-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 0.00E+00 1.59E-07 l-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 0.00E+00 1.29E-06 l-'134 1.1'lE-07 2S0E-07 1.05E-07 4.%E46 4.58E-07 0.00E+00 2.55E-09 l-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 0.00E+00 8.69E-07 Cs-134 6.28E-05 1.41E-o4. 6.86E-05 0.00E+00 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 0.00E+00 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 0.00E+00 3.80E-05 1.51E-05 1.06E-06 Cs-138 5.82E-08 1.07E-07 5.58E-08 0.00E+00 8.28E-08 9.84E-09 3.38E-11 Ba-'l39 '1.67E-10 1.18E-13 4.87E-12 0.00E+00 1.11E-'13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 0.00E+00 2.85E-09 2.ilE-04 2.86E-05 Ba-'141 '1.78E-11 1.32E-14 5.93E-13 0.00E+00 1.23E-14 4.'l1E-07 9.33E-14 Ba-'142 4.62E-12 4.63E-15 2.UE-13 0.00E+00 3.92E'15 2.39E-07 5.99E-20 La-140 5.99E-08 2.95E-08 7.82E-09 0.00E+00 0.00E+00 2.68E-05 6.09E-05 Laj42 1.20E-10 5.31E-1 1 '1.32E-1'l 0.00E+00 0.00E+00 '1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E46 2.7'lE-07 0.00E+00 1.11E-06 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-Og 0.00E+00 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.11E-04 2.53E-04 3.28E-05 0.00E+00 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 0.00E+00 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 0.00E+00 1.26E-12 2.19E-O7 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.4'1E-08 0.00E+00 6.28E-07 4.65E-05 2.28E-05 W-187 1.50E-09 1.22E-09 4.29E-10 0.00E+00 0.00E+00 5.92E-06 2.21E-05 Np-239 4.23E-08 3.99E-09 2.21E-09 0.00E+00 1.25E-08 8.11E-06 1.65E-05

References:

Dose Factors for Co-57, Zn9m, Br-82, Nb-97, Sb-124, Sb-125, Sn-'l25 are from Reference 17, Table 8. Allothers from: Regulatory Guide 1.109, Table E-8. NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. This assumes that tritium will act similarly in all organs (Reference 24). E1-212

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page {5,l of 195 Table 7.7 - INHALATION DOSE FACTORS - DFi"o (mrem/pCi inhaled) (Page 5 of 8) CHILD Nuclide bone liver total body thyroid kidney lung GI.LL! H-3 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 c-14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 2.67E-05 0.00E+00 0.00E+00 0.00E+00 1 .14E-05 Cr-51 0.00E+00 0.00E+00 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 0.00E+00 1.16E-05 2.57E-06 0.00E+00 2.71E-06 4.26E-04 6.19E-06 Mn-56 0.00E+00 4.48E-10 8.43E-1 1 0.00E+00 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.10E-06 0.00E+00 0.00E+00 3.00E-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51E-06 0.00E+00 0.00E+00 3.43E-04 1 .91E-05 Co-57 0.00E+OO 2.4E-07 2.88E-07 0.00E+00 0.00E+00 1.37E-04 3.58E-06 Co-58 0.00E+00 4.79E-07 8.55E-07 0.00E+00 0.00E+00 2.99E-04 9.29E-06 Co-60 0.00E+00 3.55E-06 6.12E-06 0.00E+00 0.00E+00 1.91 E-03 2.60E-05 Ni-63 2.22E-04 1.25E-05 7.56E-06 0.00E+00 0.00E+00 7.43E-05 1.71E-06 Ni-65 8.08E-1 0 7.99E-1 1 4.448-11 0.00E+00 0.00E+00 2.21 E-06 2.27E-05 Cu-64 0.00E+00 5.39E-10 2.90E-10 0.00E+00 1 .63E-09 2.59E-06 9.92E-06 Zn-65 1 .15E-05 3.06E-05 1.90E-05 0.00E+00 1.93E-05 2.69E-04 4.41 E-06 Zn-69 1.81E-1 1 2.61E-1 1 2.418-12 0.00E+00 1.58E-1 1 3.84E-07 2.75E-06 Zn-69m 4.26E-09 7.28E-09 8.59E-1 0 0.00E+00 4.22E-09 7.36E-06 2.71E-05 Br-82 0.00E+00 0.00E+00 5.66E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 1.28E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 1.48E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+OO Br-85 0.00E+00 0.00E+00 6.84E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 5.36E-05 3.09E-05 0.00E+00 0.00E+00 0.00E+00 2.16E-06 Rb-88 0.00E+00 1.52E-07 9.90E-08 0.00E+00 0.00E+00 0.00E+00 4.66E-09 Rb-89 0.00E+00 9.33E-08 7.83E-08 0.00E+00 0.00E+00 0.00E+00 5.1 1 E-10 Sr-89 1.62E-04 0.00E+00 4.66E-06 0.00E+00 0.00E+00 5.83E-04 4.52E-05 Sr-90 2.73E-02 0.00E+00 1.74E-03 0.00E+00 0.00E+00 3.99E-03 9.28E-05 Sr-91 3.28E-08 0.00E+00 1.24E-09 0.00E+00 0.00E+00 1.44E-05 4.70E-05 Sr-92 3.54E-09 0.00E+00 1.42E-10 0.00E+00 0.00E+00 6.49E-06 6.55E-05 Y-90 1.11E-06 0.00E+00 2.99E-08 0.00E+00 0.00E+00 7.07E-05 7.24E-05 Y-91m 1.37E-1 0 0.00E+00 4.98E-12 0.00E+00 0.00E+00 7.60E-07 4.64E-07 Y-91 2.47E-04 0.00E+00 6.59E-06 0.00E+00 0.00E+00 7.10E-04 4.97E-05 Y-92 5.50E-09 0.00E+00 1.57E-10 0.00E+00 0.00E+00 6.46E-06 6.46E-05 Y-93 5.04E-08 0.00E+00 1.38E-09 0.00E+00 0.00E+00 2.01E-05 1.05E-04 Zr-95 5.13E-05 1 .13E-05 1 .00E-05 0.00E+00 1.61E-05 6.03E-04 1.65E-05 Zr-97 5.07E-08 7.34E-09 4.32E-09 0.00E+00 1.05E-08 3.06E-05 9.49E-05 Nb-95 6.35E-06 2.48E-06 1.77E-06 0.00E+00 2.33E-06 1.66E-04 1.00E-05 Nb-97 1.16E-10 2.08E-11 9.74E-12 0.00E+00 2.31E-11 9.23E-07 7.52E-06 Mo-99 0.00E+00 4.66E-08 1 .15E-08 0.00E+00 1 .06E-07 3.66E-0s 3.42E-05 Tc-99m 4.81E-1 3 9.41E-13 1.56E-1 1 0.00E+00 1.37E-11 2.57E-07 1.30E-06 Tc-1 01 2.19E-14 2.30E-14 2.91E-13 0.00E+00 3.92E-13 1.58E-07 4.41 E-09 Ru-103 7.55E-07 0.00E+00 2.90E-07 0.00E+00 1.90E-06 1.79E-04 1.21E-05 Ru-105 4.13E-1 0 0.00E+00 1 .50E-10 0.00E+00 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.68E-05 0.00E+00 4.57E-06 0.00E+00 4.97E-05 3.87E-03 1 .16E-04 E1-213

WBN OFFSITE DOSE CALCUI-.ATION MANUAL Revision 23 0 (oDcM) Page 152 of 195 Table 7.7 - INHALATION DOSE FACTORS - DF6o (mrem/pCi inhaled) (Page 6 of 8) CHILD Nuclide bone liver totalbody thyroid kidney lung Gl-LLl Ag-110m 4.56E-06 3.08E-06 2.47E-06 0.00E+00 5.74E-06 1.48E-03 2.71E-O5 Sb-124 1.55E-05 2.0OE-07 5.41E-06 3.41E-08 0.00E+00 8.76E-M 4.43E-05 Sb-125 2.66E-05 2.05E-07 5.59E-06 2.46E-08 0.00E+00 6.27E-U 1.09E-05 Sn-125 4.95E-06 9.94E-08 2.95E-07 1.03E-07 0.00E+00 2.43E-U 7.17E-05 Te-125m 1.82E-06 6.29E-07 2.47E-07 5.20E-07 0.00E+00 '1.29E-04 9.13E-06 Te-127m 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-0s Te-129m 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 Te-129 2.64.E-1'l 9.45E-'12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 Te-131m 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-0/- 3.72E-Os l-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 0.00E+00 1.38E-06 !-131 1.30E-05 1.30E-05 7.37E-06 4.39E43 2.13E-05 0.00E+00 7.68E-07 l-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 0.00E+00 8.65E-07 l-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 0.00E+00 1.48E-06 l-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 0.00E+00 2.58E-07 l-135 1.33E-06 2.36E-06 1.12E-06 214E-04 3.62E-06 0.00E+00 1.20E-06 Cs-134 1.76E-04 2.74E-A4 6.07E-05 0.00E+00 8.93E-05 3.27E-OS 1.04E-06 Cs-136 1.76E-05 4.62E-05 3.14E-05 0.00E+00 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 0.00E+OO 7.63E-05 2.81E-05 9.78E-07 Cs-138 1.71E-07 2.27E-07 1.50E-07 0.00E+00 1.68E-07 1.84E-08 7.29E-08 Ba-139 4.98E-10 2.66E-13 1.45E-11 0.00E+00 2.33E-13 1.56E-06 1.56E-05 Ba-140 2.00E-05 1.75E-08 1.17E-06 0.00E+00 5.71E-09 4.7'lE-04 2.75E-05 Ba-141 5.29E-11 2.95E-14 1.72E-'12 0.00E+00 2.56E-14 7.89E-07 7.44E-Og Ba-142 1.35E-11 9.73E-15 7.ilEj3 0.00E+00 7.87E-15 4.4E-07 7.41E-10 La-140 1.74E-07 6.08E-08 2.ME-08 0.00E+00 0.00E+00 4.94E-05 6.10E-05 La-142 3.50E-10 1.11E-10 3.49E-11 0.00E+00 0.00E+00 2.35E-06 2.05E-05 Ce-141 1.06E-05 5.28E-06 7.83E-07 0.00E+00 2.31E-06 1.47E-U 1.53E-05 Ce-143 9.89E-08 5.37E-08 7.77E-09 0.00E+00 2.26E-08 3.12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 0.00E+00 3.17E-U 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 0.00E+00 8.11E-07'1.17E-04 2.63E-05 Pr-144 '1.61E-11 4.99E-12 8.10E-13 0.00E+00 2.6/,E-12 4.23E-07 5.32E-08 Nd-147 2.92E-06 2.36E-06'1.84E-07 0.00E+00 1.30E-06 8.87E-05 2.22E-05 W-187 4.41E-09 2.61E-09 1.17E-09 0.00E+00 0.00E+00 1.11E-05 2.46E-05 Np-239 '1.26E-07 9.04E-09 6.35E-09 0.00E+00 2.63E-08 1.57E-05 1.73E-05

Reference:

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124, Sb-125, Sn-125 are from Reference 17, Table 8. Allothers from: Regulatory Guide 1.109, Table E-9. NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. This assumes that tritium will act similarly in all organs (Reference 24). E1-214

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 153 of 195 Table 7.7 - INHALATION DOSE FACTORS - Dfi"o (mrem/pCi inhaled) (Page 7 of 8) INFANT Nuclide bone liver total body thyroid kidney !ung GI.LLI H-3 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 c-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Na-24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P-32 1.45E-03 8.03E+05 5.53E-05 0.00E+OO 0.00E+00 0.00E+00 1 .1 5E-05 Cr-S1 0.00E+00 0.00E+00 6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 Mn-54 0.00E+00 1.81E-05 3.56E-06 0.00E+00 3.56E-06 7.14E-04 5.04E-06 Mn-56 0.00E+00 1.10E-09 1 .58E-10 0.00E+00 7.86E-10 8.95E-06 5.12E-05 Fe-55 1.41E-05 8.39E-06 2.38E-06 0.00E+00 0.00E+00 6.21 E-05 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 0.00E+00 0.00E+00 7.25E-04 1.77E-05 Co-57 0.00E+00 4.65E-07 4.58E-07 0.00E+00 0.00E+00 2.71E-04 3.47E-06 Co-58 0.00E+00 8.71E-07 1.30E-06 0.00E+00 0.00E+00 5.55E-04 7.95E-06 Co-60 0.00E+00 5.73E-06 8.41E-06 0.00E+00 0.00E+00 3.22E-03 2.28E-05 Ni-63 2.42E-04 1.46E-05 8.29E-06 0.00E+00 0.00E+00 1.49E-04 1.73E-06 Ni-65 1.71E-09 2.03E-10 8.79E-1 1 0.00E+00 0.00E+00 5.80E-06 3.58E-05 Cu64 0.00E+OO 1.34E-09 5.53E-10 0.00E+00 2.84E-09 6.64E-06 1.07E-05 Zn-65 1.38E-05 4.47E-05 2.228-05 0.00E+00 2.32E-05 4.62E-04 3.67E-05 Zn-69 3.85E-1 1 6.91E-1 1 5.13E-12 0.00E+00 2.87E-11 1.05E-06 9.44E-06 Zn-69m 8.98E-09 1.84E-08 1.67E-09 0.00E+00 7.45E-09 1.91 E-05 2.92E-05 Br-82 0.00E+00 0.00E+00 9.49E-06 0.00E+00 0.00E+OO 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 2.72E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 2.86E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 1.46E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.36E-04 6.30E-05 0.00E+00 0.00E+00 0.00E+00 2.17E-06 Rb-88 0.00E+00 3.98E-07 2.05E-07 0.00E+00 0.00E+00 0.00E+00 2.42E-07 Rb-89 0.00E+00 2.29E-07 1.47E-07 0.00E+00 0.00E+OO 0.00E+00 4.87E-08 Sr-89 2.84E-04 0.00E+00 8.15E-06 0.00E+00 0.00E+00 1.45E-03 4.57E-45 Sr-90 2.92E-02 0.00E+00 1.85E-03 0.00E+00 0.00E+00 8.03E-03 9.36E-05 Sr-91 6.83E-08 0.00E+00 2.47E-09 0.00E+00 0.00E+00 3.76E-05 5.24E-05 Sr-92 7.50E-09 0.00E+00 2.79E-10 0.00E+00 0.00E+00 1.70E-05 1.00E-04 Y-90 2.35E-06 0.00E+00 6.30E-08 0.00E+00 0.00E+00 1.92E-04 7.43E-05 Y-91 m 2.91 E-10 0.00E+00 9.90E-12 0.00E+00 0.00E+00 1.99E-06 1.68E-06 Y-91 4.20E-04 0.00E+00 1.12E-05 0.00E+00 0.00E+00 1.75E-03 s.02E-05 Y-92 1.17E-08 0.00E+00 3.29E-1 0 0.00E+00 0.00E+00 1.75E-05 9.04E-05 Y-93 1.07E-07 0.00E+OO 2.91E-09 0.00E+00 0.00E+00 5.46E-05 1 .19E-04 Zr-95 8.24E-05 1.99E-05 1.45E-05 0.00E+00 2.22E-05 1.25E-03 1.55E-05 Zr-97 1.07E-07 1 .83E-08 8.36E-09 0.00E+00 1.85E-08 7.88E-05 1.00E-04 Nb-95 1.12E-05 4.59E-06 2.70E-06 0.00E+00 3.37E-06 3.42E-04 9.05E-06 Nb-97 2.44E-10 5.21E-11 1.88E-1 1 0.00E+00 4.07E-11 2.37E-06 1.92E-05 Mo-99 0.00E+00 1.18E-07 2.31E-08 0.00E+00 1.89E-07 9.63E-05 3.48E-05 Tc-99m 9.98E-1 3 2.06E-12 2.66E-1 1 0.00E+00 2.22E-11 5.79E-07 1.45E-06 Tc-101 4.65E-14 5.88E-14 5.80E-13 0.00E+00 6.99E-1 3 4.17E-07 6.03E-07 Ru-103 1.44E-06 0.00E+00 4.85E-07 0.00E+00 3.03E-06 3.94E-04 1 .1 5E-05 Ru-105 8.74E-10 0.00E+00 2.93E-1 0 0.00E+00 6.42E-10 1 .12E-05 3.46E-05 Ru-106 6.20E-05 0.00E+00 7.77E-06 0.00E+00 7.61E-05 8.26E-03 1.17E-04 E1-215

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page lil of 195 Table 7.7 - INHALATION DOSE FACTORS - Dt"o (mrem/pCi inhaled) (page I of 8) INFANT Nuclide bone liver total body thyroid kidney lung GI-LLI Ag-1 10m 7.13E-06 5.16E-06 3.57E-06 0.00E+00 7.80E-06 2.62E-03 2.36E-05 sb-124 2.71E-05 3.97E-07 8.56E-06 7.18E-08 0.00E+00 1.89E-03 4.22E-05 sb-125 3.69E-05 3.41E-07 7.78E-06 4.45E-08 0.00E+00 1.17E-03 1 .05E-05 Sn-125 1.01 E-05 2.51E-07 6.00E-07 2.47E-07 0.00E+00 6.43E-04 7.26E-05 Te-1 25m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 0.00E+00 3.19E-04 9.22E-06 Te-1 27m 1 .19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81E-10 3.49E-10 1 .32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129m 1.01 E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E-1 1 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-131m 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 Te-1 31 1.248-11 5,87E-12 3.57E-12 1.13E-1 1 2.85E-11 1.47E-06 5.87E-06 Te-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 I-1 30 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 0.00E+00 1.42E-06 t-1 31 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 0.00E+00 7.56E-07 ,-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 0.00E+00 1.36E-06 r-1 33 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 0.00E+00 1.54E-06 t-134 6.58E-07 1.34E-06 4.7sE-07 3.18E-05 1 .49E-06 0.00E+00 9.21E-07 I-1 35 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 0.00E+00 1 .31E-06 Cs-1 34 2.83E-04 5.02E-04 5.32E-05 0.00E+00 1.36E-04 5.69E-05 9.53E-07 Cs-1 36 3.45E-05 9.61E-05 3.78E-05 0.00E+00 4.03E-05 8.40E-06 1.02E-06 Cs-1 37 3.92E-04 4.37E-04 3.25E-05 0.00E+00 1.23E-04 5.09E-05 9.53E-07 Cs-1 38 3.61 E-07 s.58E-07 2.84E-07 0.00E+00 2.93E-07 4.67E-08 6.26E-07 Ba-1 39 1.06E-09 7.03E-13 3.07E-1 1 0.00E+00 4.23E-13 4.25E-06 3.64E-05 Ba-140 4.00E-05 4.00E-08 2.07E-06 0.00E+00 9.59E-09 1.14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-14 3.55E-12 0.00E+00 4.64E-14 2.12E-06 3.39E-06 Ba-142 2.UE-11 2.36E-14 1.40E-12 0.00E+00 1.36E-14 1.11E-06 4.95E-07 La-140 3.61 E-07 1.43E-07 3.68E-08 0.00E+00 0.00E+00 1.20E-04 6.06E-05 La-142 7.36E-1 0 2.69E-1 0 6.46E-1 1 0.00E+00 0.00E+00 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.19E-05 1.42E-06 0.00E+00 3.75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-08 0.00E+00 4.03E-08 8.30E-05 3.55E-0s Ce-144 2.28E-03 8.65E-04 1.26E-04 0.00E+00 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.00E-05 3.74E-06 4.99E-07 0.00E+00 1.41E-06 3.09E-04 2.66E-05 Pr-144 3.42E-11 1.32E-11 1.72E-12 0.00E+00 4.80E-12 1 .15E-06 3.06E-06 Nd-147 5.67E-06 5.81 E-06 3.57E-07 0.00E+00 2.25E-06 2.30E-04 2.23E-05 w-1 87 9.26E-09 6.44E-09 2.23E-09 0.00E+00 0.00E+00 2.83E-05 2.54E-05 Np-239 2.65E-07 2.37E-08 1.34E-08 0.00E+00 4.73E-08 4.25E-05 1.78E-05

Reference:

Dose Fac-tors for Co-57, Zn9m, Br-82, Nb-97, Sb-124, Sb-125, Sn-125 are from Reference 17, Table 8. Allothers from: Regulatory Guide 1.109, Table E-10. NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. This assumes that tritium will ac,t similarly in all organs (Reference 24). E1-216

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 155 of 195 Figure 7.1 - GASEOUS EFFLUENT RELEASE/DISCHARGE POINTS 1 ,2-RE-90-119 o-RE-go-l01 B 0-RE-90-1328 Condenser Service Auxiliary Vacuurn Building Building Exhaust Vent Vent (one per (common) (common) unit) 1,2-RE-90-400A Waste Gas Decay 0-RE-90-11E Tanks (e) Containment Purge 1 ,2-RE-9O-130,-1 31 System (one per unit) Shield Building Vent (one per unit) E1-217

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 156 of 195 Figure 7.2 - DETAIL OF GASEOUS RELEASE/DISCHARGE POINTS

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WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 157 of 195 Figure 7.3 - GASEOUS RADWASTE TREATMENT SYSTEM CVCS Volume Control Tank Unit 1 CVCS Volume Control Tank Unit 2 Reactor Drain Collector Tank Unit I Waste Gas Compressor Package x 2 Reactor Drain Collector Tank Unit 2

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Waste Gas Waste Gas Decay Tank Decay Tank (providlng (isolated cover gas) x7) 0-RE-90-119 E1-219

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 158 of 195 Figure 7.4 - PLUME DEPLETION EFFECT FOR GROUND LEVEL RELEASES (AllStabili$ Classes) ry t-k

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WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 159 of 195 Figure 7.5 -VERTICAL STANDARD DEVIATION OF MATERIAL lN A PLUME 1 000 I I I Jr I L r I T -{ I I ,l I -L ,/ 1 /

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WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 160 of 195 Figure 7.6 - RELATM DEPOSITION FOR GROUND LEVEL RELEASES (AIl Stability Classes) 1E-03

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WBN OFFSITE DOSE CALCUI..ATION MANUAL Revision 23 0 (oDcM) Page 161 of 195 8.0 - TOTAL DOSE 8.1 TOTAL MAXMUM INDIVIDUAL DOSES To determine compliance with 40 CFR 190 as required in ODCM Surveillance Requirement2.2.3.1 and 2.2.3.2, the dose contributions to the maximum individual from \AIBN radioactive effluents and all other nearby uranium fuel cycle sources will be considered. The annual dose to the maximum individualwill be conservatively estimated by using the following equation: 4 p = S.D(airtb)

           \      + D(airorg) + D(liqtb) + D(liqorg) + D(direct)                                       (8.1)

Q=1 where: q = calendar quarter D(airtb) = the total body air submersion dose (as calculated in Section 7.7) D(airorg)= the critical organ dose from gaseous effluents (as calculated in Section 7.7), D(liqtb) = the total body dose from liquid effluents (as calculated in Section 6.6.4), D(liqorg) = the critical organ dose from liquid effluents (as calculated in Section 6.6.4), D(direct) = the direct radiation dose measured by the environmental monitoring program. The dose calculated is compared to the total body/organ limit of 25 mrem. lf the dose is greater than 25 mrem, then the dose to each individual organ will be evaluated separately for comparison to the limits. E1-223

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 162 of 195 9.0 - RADTOLOGTCAL ENVTRONMENTAL MONTTORING PROGRAM (REMP) 9.1 iIONITORING PROGRAM DESCRIPTION The REMP shall be conducted in accordance with the requirements of ODCM Control 1.3.1. The monitoring program described in Tables 9.1, 9.2, and 9.3, and in Figures 9.1,9.2 and 9.3 shallbe conducted. The program consists of 3 major sections corresponding to the atmospheric pathway, the tenestrial pathway, and the waterborne pathway. ln the atmospheric monitoring program, samples of air particulates and atmospheric radioiodines are collected from established stations. The stations are identified as Local Monitor (LM) stations, located at or near the unrestricted area boundary; Perimeter Monitor (PM) stations, located typically 3-10 miles from the site; and Remote Monitor (RM) stations, located greater than 10 miles from the site. The remote monitors are considered as background or control stations. The terrestrial monitoring program includes the collection of milk, soil, and food crops. ln addition, direct gamma radiation levels will be measured in the vicinity of the plant. The waterborne monitoring program consists of the collection of samples of surf;ace and ground water, drinking water, sediment, and fish. Samples are collected both dornstream and upstream from the plant site. The basic description of the REMP is included in Tables 9.1 and 9.2. Table 9.3 describes the locations of the direct gamma radiation detectors (dosimeter). Figures 9.1,9.2, and 9.3 show the locations of the stations within one mib of the site, between one and five miles from the site, and greater than 5 miles from the site, respectively. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, sample unavailability, or malfunction of sampling equipment. lf the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period. Deviations from the required program will be reported in the Annual Radiological Environmental Operating Report in accordance with the provisions of ODCM Control 1.3.1.a and Administrative Control 5.1. Changes made in the program resulting from unavailability of samples will be reported in accordance with ODCM Control1.3.1.c. 9.2 DETECTION CAPABILITIES Analyticaltechniques shall be such that the detection capabilities listed in Table 2.3-3 are achieved. 9.3 LAND USE CENSUS A land use survey shall be conducted in accordance with the requirements given in ODCM Control 1.3.2. The results of the survey shall be reported in the Annual Radiological Environmental Operating Report. Changes made in the REMP as a result of the Land Use Census will be reported in accordance with the provisions of ODCM Control 1.3.2.b. E1-224

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 163 of 195 9.4 INTERLABORATORY COMPARISON PROGRAM Analyses shall be performed on radioactive materials supplied as part of an lnterlaboratory Comparison Program which has been approved by the NRC. A summary of the results obtained in the intercomparison shall be included in the Annual Radiological Environmental Operating Report (or the EPA program code designation may be provided). lf analyses are not performed as required corrective actions taken to prevent a recurence shall be reported in the Annual Radiological Environmental Operating Report. 9.5 DATA REVIEWAND REPORTING Results of this program shall be reported in accordance with ODCM Administrative Control 5.1, Annual Radiological Environmental Monitoring Report. Analyticalresults exceeding the reporting levels outlined in ODCM Table 2.3-2 will be reported in accordance with the requirements of ODCM Control 1.3.1.b. As noted in V\IBN FSAR Section 11.6, routine releases from V\IBN will result in environmental concentrations well below the detection limits for environmental media, making correlations between calculated effluent release data and environmental measurements impractical. Only if radioactive releases from the site result in statistically measurable increases in environmental levels can dose correlations be made. E1-225

WBN OFFSITE DOSE CALCUIATION MANUAL Revision 23 0 (oDcM) Page 164 of 195 Table 9.1 - REMP - MONITORING, SAMPLING, AND ANALYSIS (Page 1 of 5) Exposure Sarnple Locations'r Sampling and Type and Frequency of Pathway Collection Frequency Analysis and/or Sample

1. DIRECT RADIATION 2 or more dosimeters Once per 92 days Gamma dose at least placed at locations (in once per 92 days different sectors) at or near the unrestricted area boundary in each of the 16 sectors.

2 or more dosimeters placed at stations located approximately 5 miles from the plant in each of the 16 sectors 2 or more dosimeters in at least 8 additional locations of special interest, including at least 2 control stations. E1-226

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 165 of 195 Table 9.{ - REMP - MONITORING, SAMPLING, AND ANALYSIS (Page 2 of 5) Exposure Sample Locationsl Sampling and Type and Frequency of Pathway Collection Frequency Analysis and/or Sample

2. AIRBORNE Particulates 4 samples from locations Continuous sampler Particulate samples:

and (in different sectors) at or operation with Analyze for gross beta Radioiodines near the unrestricted area sample collection radioactivity > 24 hours boundary once per 7 days following filter change. (LM-1 ,2,3,and 4) (more frequently if Perform gamma required by dust isotopic analysis on 4 samples from loading) each sample if gross communities beta > 10 times that of approximately 6-1 0 miles control sample. distance from the plant. (PM-2,3,4,and 5) Composite at least once per 31 days (by 2 samples from control location) for gamma locations greater than 10 scan. miles from the plant (RM-2 and 3) Rad ioiod ine cartridge:

                                                                    !-131 at least once per 7 davs Atmospheric    4 samples from locations        Continuous sampler    Analyze each sample Moisture       (in different sectors) at or    operation with        for H-3 near the site boundary          sample collection (LM-1 ,2,3,and 4)               biweekly 2 samples from communities approximately 4-10 miles distance from the plant.

(PM-2,5,) l sample from control location greater than 10 miles from the plant (RM-3) Soil Samples from same Once per year Gamma scan, Sr-89, Iocation as air particulates. Sr-90 once per year E1-227

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 166 of 195 Table 9.1 - REMP - MONITORING, SAMPLING, AND ANALYSIS (Page 3 of 5) Exposure Sample Locationsl Sampling and Type and Frequency of Pathway Collection Frequency Analysis and/or Sample

3. WATERBORNE Surface TRM 529.3 Collected by Gamma scan and H-3 TRM 523.1 automatic sequential- analysis of each TRM 517.9 type samplerz with sample composite samples collected at least once per 31 days Ground 5 sampling locations from Collected by Gross beta, gamma ground water monitoring automatic sequential- scan, and H-3 analysis wells adjacent to plant type sampler with of each sample composite samples 1 sampling location from collected at least groundwater source once per 31 days uporadient from the plant Drinking l sample at the first Collected by Gross beta, gamma potable surface water automatic sequential scan, and H-3 analysis supply downstream from type sampler2 with of each sample the plant (TRM 503.8) composite sample collected at least 1 sample at the next once per 31 days downstream potable surface water supplier (greater than 10 miles downstream) (TRM 473.0) 1 sample at control location3 ffRM 529.3)

Shoreline TRM 513, TRM 530.2 At least once per 184 Gamma scan of each davs sample. Pond One sample from at least Annually Gamma scan of each Sediment three locations in Yard sample. Holdinq Pond. E1-228

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 167 of ,l95 Table 9.1 - REMP - MONITORING, SAMPLING, AND ANALYSIS (Page 4 of 5) Exposure Sample Locationsl Sampling and Type and Frequency of Pathway Collection Frequency Analysis andlor Sample 4.INGESTION Milk 1 sample from milk At least once per 15 Gamma isotopic and producing animals in each days l-131 analysis of each of 1-3 areas indicated by sample. Sr-89, Sr-90 the cow census where once per quarter doses are calculated to be highest. lf samples are not available from a milk anima! Iocation, doses to that area may be estimated by projecting the doses from concentrations detected in milk from other sectors or samples of vegetation may be taken monthly where milk is produced but is not available. At least 1 sample from a control location Fish One sample of At least once per 184 Gamma scan on edible commercial ly mportant i days. portion. species and one sample of recreationally important species. One sample of each species from downstream of Watts Bar Nuclear Plant, Ch ickamauga reservoi r, and Watts Bar reservoir. Food 1 sample each of principal At least once per 365 Gamma scan on edible Products food products grown at days at the time of portion. private gardens and/or harvest. The types of farms in the vicinity of the foods available will plant. vary. Following is a list of typical foods which may be available: Cabbage and/or Lettuce Corn Green Beans Potatoes Tomatoes E1-229

WBN OFFSITE DOSE CALCULATpN MANUAL Revision 23 0 (oDcM) Page 168 of 195 Table 9.1 - REMP - MONITORING, SAMPLING, AND ANALYSIS (Page 5 of 5) Exposure Sample Locationsl Sampling and Type and Frequency of Pathway Collection Frequency Analysis and/or Sample Vegetationa Samples from farms At least once per 31 l-131 and gamma scan producing milk but not days at least once per 31 providino a milk sample davs. 1 Sample locations are listed in Tables 9.2 and 9.3 and shown on Figures 9.1, 9.2 and 9.3. 2 Samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours. 3 The surface water sample collected at TRM 529.3 is considered a control for the raw drinking water sample. 4 Vegetation sampling is applicable only for farms that meet the criteria for milk sampling and when milk sampling cannot be performed. Other Notes: LM = LocalMonitor PM = Perimeter Monitor RM = Remote Monitor TRM = Tennessee River Mile E1-230

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 169 of 195 Table 9.2 - REMP - SAMPLING LOCATIONS Map Stationa Sector Approximate lndicator (l) Samples-Location Distance or Gollectedb Number (mi) Gontrol(C) 2 PM-2 NW 7.0 AP, CF, S, AM 3 PM-3 NNE 10.4 ! AP. CF. S 4 PM4 NE/ENEC 7.6 AP. CF. S 5 PM-5 S 8.0 I AP, CF, S, AM 6 RM.2 SW 15.0 c AP, CF, S 7 RM-3 NNW 15.0 C AP, CF, S, AM I LM-1 SSW 0.5 I AP, CF, S, AM 9 LM-2 NNE 0.4 I AP, CF, S, AM 10 LM.3 NNE 1.9 AP, CF, S, AM 11 LM-4 SE 0.9 AP, CF, S, AM 12 Farm L SSW 1.3 lq M,W 15 Farm K ENE 11.6 c M 18 Well #1 S 0.6 W 20 Farm N ESE 4.1 M 22 Farm EH SSW 24.0 c M 23 Well#5 N 0.5 c W 25 TRM s17.9 g.ge SW 26 TRM 523.1 4.7e SW 27 TRM 529.3 1.5e C SW. PWI 31 TRM 473.0 (C.F. lndustries) 54.9e PW 32 TRM 513.0 14.8e I SS 33 TRM 530.2 2.4e c SS 35 TRM 503.8 (Davton) 24.Oe PW 37 TRM 522.8-527 .8 (Downstream of F WBNP) 38 TRM 471-530 (Chickamausa Lake) F 39 TRM 530602 (Watts Bar Lake) c F 81 Yard Pond SSE/S/SSW Onsite I PS 82 Well A SSE 0.6 I W 83 Wel! B SSE 0.5 I W 84 Well C ESE 0.3 I W 85 Well F SE 0.3 I W See Figures 9.1, 9.2, and 9.3 bSamplecodes:AP=Airparticulatefilter; CF=Charcoal Filter; F=Fish; S=Soil; AM=atmosphericmoisturc,M=Milk; PW= Public Water; SS = Shoreline Sediment; SW = Surface Water; \ ,! \ /bll Water, PS= Pond Sediment c Station located on boundary betriveen these seclors d A control for r rell water e Distance fiom plant discharge CIRM 527.8) f The surface water sample fom TRM 529.3 is also considered a control for raw Public Water samples. E1-231

WBN OFFSITE DOSE CALCULATIoN MANUAL Revision 23 0 (oDcM) Page 170 of 195 Table 9.3 - REMP - DOSIMETRY LOCATIONS Map Station Sector Approx. On/ Map Station Sector Approx. On/ Location Dist. Offsitea Location Dist. Offsitea (mi) Number (mi) Number 2 NW-3 NW 7.0 off 55 SSE-14 SSE 0.6 On 3 NNE-3 NNE 10.4 off 56 SSE-2 SSE 5.8 off 4 ENE.3 ENE 7.6 off 57 s-1 S 0.7 On 5 s-3 S 7.8 off 58 s-2 S 4.8 off 6 SW-3 SW 15.0 off 59 SSW-1 SSW 0.8 On 7 NNW-4 NNW 15.0 off 60 SSW-3 SSW 5.0 ofr 10 NNE-14 NNE 1.9 On 62 SW-1 SW 0.8 On 11 SE-1A SE 0.9 On 63 SW-2 SW 5.3 off 12 SSW-2 SSW 1.3 On 64 WSW.1 WSW 0.9 On 14 w-2 W 4.8 off 65 WSW-2 WSW 3.9 off 40 N-1 N 1.2 On 66 w-1 W 0.9 On 41 N-2 N 4.7 off 67 WNW-1 WNW 0.9 On 42 NNE-1 NNE 1.2 On 68 WNW-2 \ANW 4.9 off 43 NNE.2 NNE 4.1 off 69 NW-1 NW 1.1 On 44 NE-1 NE 0.9 On 70 NW-2 NW 4.7 off 45 NE-2 NE 2.9 off 71 NNW-1 NNW 1.0 On 46 NE-3 NE 6.1 off 72 NNW-2 NNW 4.5 off 47 ENE-1 ENE 0.7 On 73 NNW.3 NNW 7.0 off 48 ENE-2 ENE 5.8 off 74 ENE-2A ENE 3.5 off 49 E-1 E 1.3 On 75 SE-2A SE 3.1 off 50 E-2 E 5.0 ofr 76 S.2A S 2.0 off 51 ESE.1 ESE 1.2 On 77 W-2A W 3.2 off 52 ESE-2 ESE 4.4 off 78 NW.2A NW 3.0 off 54 SE-2 SE 5.3 off 79 SSE.1 SE 0.5 On a Dosimeters designated onsite (On are those located two miles or less from the

                                       )                                         plant. Dosimeters designated offsite (Off) are those located more than two miles from the plant.

E1-232

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 171 of 195 Figure 9.1 - REMP LOCATIONS WITHIN ONE MILE OF THE PLANT 303.75 56.25 WNW ENE 281.25 78.75 W 258.7 5 w WATTS BAR NUGLEAR PLANT E 101 .25 WSW ESE 236.25 123.7 5 SE 146.25 168.75 Scale E1-233

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 172 of 195 Figure 9.2 - REMP LOCATIONS FROil ONE TO FIVE itlLES FROM THE PI-ANT 30ers ffir- ,\ i8r.*fi n

   *-                    ilArr8 Bln lrrcurn pr-*rr, I I         t --;b4t 2Sa7S ffiT esat6 I1016 Se.f E1-234

WBN OFFSITE DOSE CALCU1ATION MANUAL Revision 23 0 (oDcM) Page 173 of 195 Figure 9.3 - REMP LOCATIONS GREATERTHAN FIVE MILES FROM THE PLANT t*f,.rs t 1,26 tffi

                                           --.}"'

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WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 174 of 195 1O.O REFERENCES

1. NUREG-1301, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors," Generic Letter 89-01, Supplement No. 1. April 1991.

2. Draft NRC Generic Letter, "Guidance for Modification of Technical Specifications to Reflect (a)

Revisions to 10 CFR Part 20, 'Standards for Protection Against Radiation'and 10 CFR 50.36a,

   'Technical Specifications on Effluents from Nuclear Power Reactors', (b) Related Current Industry lnitiatives and (c) Miscellaneous Related Editorial Clarifi cations."

3. NUREG-0l33, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," September 1978.

4. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents forthe Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October 1977.

5. Regulatory Guide 1.1 11, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.

6. Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of lmplementing 10 CFR Part 50 Appendix 1," Revision 1, April 1977.

7. Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Reactors," Revision 1, June 1974.

8. Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979.

9. V\IBN Final Environmental Statement, WBNP Units 1,2,3, Chattanooga, TN, November 9, 1972.

10. WBN Final Safety Analysis Report.

11. TVA Memorandum, E. E. Driverto R. B. Maxwell, 'Watts Bar Nuclear Plant Dispersion," December 3, 1984.

12. TVA Memorandum, Edwin M. Scott to Betsy Eiford-Lee, "Fish Harvest Estimates for the Revision of the QWATA Computer Code," December 15, 1987.

13. TVA Memorandum, D. L. Stone to B. Eiford-Lee, "Surface area Computations for the Revision of the QWATA Code," April 26, 1988.

14. TVA Memorandum, R. A. Marker, "Revision to QWATA Computer Code," January 6, 1988.

15. DOE-TlC-11026, "Radioactive Decay Data Tables - A Handbook of Decay Data for Application to Radiation Dosimetry and Radiological Assessment," D. C. Kocher, 1981.

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WBN OFFSITE DOSE CALCUIATION MANUAL Revision 23 0 (oDcM) Page 175 of 195

16. ORNL 4992, 'Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment," March 1 976,.

17. NUREG-0172,"A1e Specific Radiation Dose Commitment Factors for a One Year Chronic lntake,"

November 1977.

18. Dose-Rate Conversion Factors for Extemal Exoosure to Photon and Electron Radiation from Radionuclides Occuninq in Routine Releases from Nuclear Fuel Cvcle Facilities. D. C. Kocher, Health Physics Volume 38, April 1980.

19. TVA Memorandum, John P. Blacloruellto M. L. Millinor, "Development of Atmospheric Dispersion Adjustment Factors forApplication in the Watts Bar Nuclear Plant Ofbite Dose Calculation Manual,"

November 16,1990.

20. lntemationalCommission on Radiological Protection Publication 23, "Report of the Task Group on Reference Man," 1975.

21. NUREG/CR-1004, 'A Statistical Analysis of Selected Parameters for Predicting Food Chain Transport and lntemal Dose of Radionuclides," October 1979.

22. 'Tennessee Valley Authodty Effluent Management System (48-8434) Technical Reference Manual,"

Canberra Nuclear - Nuclear Data Systems Division, January 1994.

23. TVA Memorandum, M. S. Robinson to Radiological Hygiene Branch Files, "Cross-SectionalAreas of Nuclear Reactor Buildings," November 2,'1977 .

24. Sequoyah Nuclear Plant Offsite Dose Calculation Manual.

25. TVA Quarterly Water Dose Assessment Computer Code Documentation, Revision 2.0, November 1989

26. TVA Memorandum, M. C. Brickey to M. E. Greeno, 'Watts Bar Nuclear Plant Oftsite Dose Calculation Manual - Changes Required - Revised agreements based on meeting between Nuclear Engineering and Chemistry on March 9, 1994," March '17,'1994 27.-lVA Memorandum, Ed Steinhauser and Stan Nelson to Mike Greeno, "Offsite Dose Calculation Manual for Systems 14 and 15," February 10, 1994

28. TVA Memorandum, M. C. Brickey to Mike Greeno, 'ODCM Change Request," March 3, 1995

29. NDP-00-0344, Revision 1, "lmplementation and Utilization of Tritium Producing Bumable Absorber Rods (TPBARS) in Watts Bar Unit 1.'

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WBN OFFSITE DOSE CALGUTATION MANUAL Revision 23 0 (oDcM) Page 176 of 195 11.0 SOURCE NOTES SOURCE Source NOTE Document Summarv 1 NCO850192001 TVA response as described in NRC evaluation SER No. 5, Section 1 1 .7, paragraph 4. 2 NRC IE Bulletin 8249 Adjust noble gas monitor setpoints based on chamber sQN LER 50-327t92019 pressure. 3 Source Note deleted and calibration interval changed to 18 months per NE SSD 1-F-90400A,8,C,D,452 and 2-F-90-400C ,452. NCO920030880 Specifications will ensure compliance with 10 CFR 50.34a (ALARA) and to ensure that concentrations of radioactive effluents released to unrestricted areas are within the limits specified in 10 CFR 20.106 (20.1301). The reporting requirements of 50.36a (aX2) will also be included in these specifications. NCO920042424 To ensure compliance with Radiological Effluent Tech Specs, cumulative dose calculations wil! be performed once per month. NCO920042422 ODCM shall contain Radiological Environmental Monitoring Program sampling and analysis frequencies. NCO920042500 Dose Calculations will be performed monthly to ensure that the dose rate in unrestricted areas due to gaseous effluents from the reactor at the site will be limited to the prescribed values. NCO920042501 A complete analysis utilizing the total estimated liquid release for each calendar quarter will be performed and reported as required by Technical Specifications. NCO920042502 Dose projections will be performed in accordance with Tech n ical Specifications. 10 NCO920042423 Post-release analysis will be done using actual release data to ensure that limits were not exceeded. This data and setpoints will be recorded in auditable records by plant personnel. 11 WBPER960319 Operability requirements for Kuz isokinetic sampling panels will be added to the ODCM. E1-238

WBN OFFSITE DOSE CALCUI.ATION MANUAL Revision 23 0 (oDcM) Page 177 of 195 SOURCE Source NOTE Document Summary 13 WBPER97O486 Added operability requirements for heat trace on NCO970059002 iodine/particulate sample lines for Condenser Vacuum NCO970059004 Exhaust and Shield Building Exhausts. 15 WBPER970492 Changed allowable monitor tolerance factor to 2.0 for gaseous monitor setpoint calculations. 16 WBPERg71422 Changed submittal requirements to correspond to CFR requirements. 17 WBPER970332 Changed maximum design release flow rate for WGDT from 55 cfm to 100 cfm to reflect current design output. E1-239

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 178 of 195 APPENDIXA - NOTATION CONVENTIONS (Page 1 of7) Symbo! Key This symbol key provides a cross-reference between the symbols used in the Watts Bar ODCM and those symbols used in the Regulatory Guidance documents for the ODCM (References 1 , 2, 3,4, and 5). The Watts Bar symbol is given, along with a definition of the term; then the reference document is given for that term, along with the corresponding symbol used in that reference. Some terms may be subscripted in the WBN ODCM text and in the regulatory document. For simplification, no subscripts are included in this symbol key. The use of subscripts is standard throughout the WBN ODCM as follows: subscript a: age group subscript i: radionuclide (T is used to denote tritium) subscript j: organ subscript k: windspeed category subscript l: Pasquill stability class subscript m: Public Water Supply or population element subscript P: dose pathway subscript r: river reach WBN ODGM Source Svmbol Definition Source Reference Symbol a Minimum building cross-sectional area R.G . 1.111 (p. 1 1) D12 A Liquid dose factor NUREG-O133 (p. 15) A a Cumulative dose for a quarter N/A ADC Average decay correction N/A AF Allocation Fraction N/A APR Size of river reach N/A Ap Dose factor for fish ingestion NUREG-O1 33 (p. 15) Ap Dose factor for shoreline recreation N/A ATMW Ratio of average to maximum ingestion N/A rates BKG Background N/A B Bioaccu mu lation factor NUREG-0133 (p. 16) BF b Projected dose for a release N/A Biv Transfer factor for nuclide i from soil to R.G. 1.10e (p. 3) Biv vegetation BR Breathing rate NUREG-0133 (p. 25) BR c Air concentration R.G . 1.10e (p. 25) c c Any anticipated additional dose in the N/A next month from other sources c Concentration NUREG-0133 (p. 15) c x/Q Relative co ncentration R.G . 1.10e (p. 5) xlQ E1-240

WBN OFFSITE DOSE CALCUI.ATION MANUAL Revision 23 0 (oDcM) Page 179 of 195 APPENDIX A . NOTATION CONVENTIONS (Page 2 of 7) bol K WBN oDclul Source Svmbol Definition Source Reference Svmbol d Number of days in the current quarter prior N/A to the time of a release D Dose NUREG-0133 (p. 15) D D*r Near-field dilution NUREG-0133 (p. 15) F D/Q Relative deposition R.G . 1.109 (p. 24\ d DFB Dose Conversion Factor for total body R.G . 1.10e (p. 6) DFB submersion DFr, Dose Conversion Factor for beta air dose R.G . 1.10e (p. 5) DFr, DFG Dose conversion factor for standing on NUREG-O133 (p. 26) DFG contaminated ground DFo Dose conversion factor for gamma air dose R.G. 1 .10e (p. 5) DF., DF lngestion dose conversion factor NUREG-0133 (p. 16, 33) DF, DFL DFA Inhalation Dose Conversion Factor NUREG-O1 33 (p. 25) DFA DFS Dose conversion factor for skin R.G . 1.10e (p. 6) DFS submersion dose DR Dose rate N/A dr Relative deposition rate R.G . 1.111 (p. 12) dr E Efficiency NUREG-1301 (p. 40) E ECL Effiuent Concentration Limit N/A ER Expected Monitor Response N/A F Dilution flow NUREG-O133 Addendum A F t Waste flow NUREG-O1 33 Addendum A f Fg Transfer factor from cow's feed to beef R.G. 1.10e (p.28) F1 fo Fraction of stored vegetables grown locally R.G. 1.10e (p.7) fd FISH Average amount of fish ingested N/A fm Joint relative frequency of occurrence of R.G . 1.111 (p. e) n/N winds in windspeed class k and stability class I f1 Fraction of fresh leafy vegetables grown R.G. 1.10e (p.7) Fg locally Fm Transfer factor from animal's feed to milk R.G. 1 .10e (p. 27) Fm fP Fraction of population in an age group R.G . 1.10e (p. 30) f fD Fraction of time animal spends on pasture R.G . 1.10e (p. 28) fD E1-241

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 180 of {95 APPENDIX A . NOTATION CONVENTIONS (Page 3 of 7) S mbo WBN ODCM Source Svmbol Definition Source Reference Symbol fs Fraction of time animal spends on R.G . 1.10e (p. 28) fs stored feed H Absolute humidity of the atmosphere R.G . 1.10e (p. 27) H HRSVIS Length of shoreline recreation visit N/A HVST Fish harvest for the Tennessee River N/A Kc Transfer coefficient from water to R.G . 1.10e (p. 14) Kc shoreline sediment

      ?'"    Radioactive decay constant                  N/A l"E      Effective decay constant                    R.G . 1.10e (p. 4)           l,p LLD       Lower Limit of detection                    NUREG-1301 (p. 40)          LLD
    \,r,     Weathering decay constant                   R.G . 1.10e (p. a)           \,r, M       Mass density of sediment                    R.G . 1.10e  (p. 14)          M n      Number of compass sectors                   N/A P      Effective surface density of soil           R.G . 1.10e (p. 3)             P p      Fraction of radionuclide remaining in        R.G. 1.111 (p. 12)            p plume POP       Population                                   R.G . 1.10e (p. 30)           P POPF       Population dose due to fish ingestion        R.G. 1.10e (p. 30)          pP POPR       Total recreation population dose             R.G . 1.10e (p. 30)         pP POPWTR       Population dose due to water ingestion       R.G . 1.10e (p. 30)         pP o       Release rate                                 NUREG-0133 (p. 22)           o q      Total release in a period                    NUREG-0133 (p. 2e)            q Qr      Milk animal's consumption rate               R.G . 1.10e (p. 3)           Qg r     Fraction of activity retained on pasture     R.G . 1.10e (p. 3)            r grass.

Rp Gaseous Dose Factor for Pathway P NUREG-O133 (p. 26) P R1 Inhalation dose factor NUREG-O133 (p. 26) P R6 Ground plane dose factor NUREG-0133 (p. 26) P Rcp Pasture g rass-milk animal-milk NUREG-O133 (p. 26) P ingestion Rcs Stored feed-milk animal-milk ingestion NUREG-O133 (p. 26) P Rnrtp Pastu re g rass-beef i ngestion NUREG-O133 (p. 26) P Rnas Stored feed-beef ingestion NUREG-O133 (p. 26) P Rvp Fresh leafy vegetable ingestion NUREG-O133 (p. 26) P E1-242

WBN OFFSITE DOSE CALCUI.ATION MANUAL Revision 23 0 (oDcM) Page 181 of 195 APPENDIX A . NOTATION CONVENTIONS (Page 4 ot 7) bol Ke WBN oDctul Source Symbo! Definition Source Reference Symbol Rvs Stored vegetable ingestion NUREG-0133 (p. 26) P R Sum of the ratios N/A RATIO Ratio of average to maximum dose N/A REQFRA Fraction of yearly recreation which N/A occurs in a quarter rf Recreation factor N/A RF River flow N/A S6 Standard deviation NUREG-1301 (p. 40) S6 SF Safety factor N/A SHVIS Shoreline visits per year N/A smax Setpoint corresponding to the ODCM N/A Limit zz Vertical dispersion coefficient R.G.1.111 (p. 11) zz 67 Vertical dispersion coefficient R.G . 1.111 (p. 11) sz T Duration of release NUREG-0133 (p. 15) At At Elapsed time between midpoint of NUREG-1301 (p. 40) At sample collection and counting time TAF Terrain adjustment factor N/A tg Time period over which accumulation R.G . 1.109 (p. 14,26) tb, t on the ground is evaluated tcb Time for receptor to consume a whole N/A beef t6 Distribution time for water, fish, milk, R.G . 1.10e (p. 4) tp beef, or vegetables tcsf Time between harvest of stored feed R.G . 1.10e F. a) t6 and consumption by animal te Exposure time in garden for fresh leafy R.G . 1.10e (p. 4) te and/or stored vegetables teo Time pasture is exposed to deposition R.G . 1.10e (p. 4) te tesf Time stored feed is exposed to R.G . 1.10e (p. 4) te deposition TFDOS lndividual fish ingestion dose R.G. 1.10e (p. 30) D tfm Transport time from milking to receptor N/A tfm thc Average time between harvest of R.G . 1.10e (p. 4) t6 vegetables and their consumption and/or storage E1-243

WBN OFFSITE DOSE GALCULATION MANUAL Revision 23 0 (oDcM) Page 182 of 195 APPENDIX A . NOTATION CONVENTIONS (Page 5 of 7) Symbol Key WBN ODCM Source Symbo! Definition Source Reference Symbo! ts Transport time from slaughter to R.G . 1.10e (p. 28) ts consumer TSHDOS Total shoreline dose rate R.G . 1.10e (p. 30) D tsv Time period over which stored N/A vegetables are consumed TWDOS Total individual water dose R.G . 1.10e (p. 30) D u Wind speed R.G. 1.111 (p. e) u Ur Fish consumption rate NUREG-0133 (p. 16) Up Urt Consumption rate of fresh leafy vegetables R.G . 1.10e (p. 7) gL um Meat ingestion rate R.G . 1.10e (p. 7) gF UD Milk ingestion rate R.G. 1.10e (p.7) UD Up Recreation usage factor R.G. 1.10e (p. 14) U Ug Consumption rate of stored vegetables R.G. 1.10e (p.7) gV by the receptor UW Water consumption rate NUREG-O133 (p. 16) Uvv V Sample size NUREG-1301 (p. 40) V W Dispersion factor NUREG-0133 (p. 22) W SWF Shoreline width factor R.G . 1.10e (p. 14) W x Downwind distance R.G . 1.111 (p. 1 1) x Y Radiochemical yield NUREG-1301 (p. 40) Y Y1 Agricultural yield for fresh leafy R.G . 1.10e (p. a) YV vegetables Yp Agricultural productivity by unit area of R.G . 1.10e (p. 4) YV pasture grass Ysf Agricultural productivity by unit area of R.G. 1.10e (p.4) YV stored feed Y=, Agricultural yield for stored vegetables R.G. 1.10e (p.4) YV E1-244

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 183 of 195 APPENDIX A . NOTATION CONVENTIONS (Page 6 of 7) List of Acronyms ABGTS - Auxiliary Building Gas Treatment System ALARA - As Low As Reasonably Achievable CDCT - Cask Decontamination Collector Tank CFR - Code of Federal Regulations CTBD - Cooling Tower Blowdorn CVCS - ChemicalVolume Control System CVE - CondenserVacuum Exhaust EPA - Environmental Protection Agency ERCW- EssentialRaw Cooling Water ESF - Engineered Safety Feature Fl - Flow Indicator FSAR - Final Safety Analysis Report GRTS - Gaseous Radwaste Treatment System GWS- Groundwater Sump HCT - High Crud Tanks HEPA - High Efficiency Particulate Air LLD - Lower Limit of Detection LM - LocalMonitor LPF - Loop Flow LRTS - Liquid Radwaste Treatment System NIST - National lnstitute of Standards and Technology NRC - Nuclear Regulatory Commission NRWT - Non-Reclaimable Waste Tank ODCM - Offsite Dose Calculation Manual PM - Perimeter Monitor PWS - Public Water Supply REMP - Radiological Environmental Monitoring Program RE - Radiation Element RM - Remote Monitor SGBD - Steam Generator Blowdown SQN - Sequoyah Nuclear Plant SR - Surveillance Requirement SSP - Site Standard Practice TBS - Turbine Building Sump TRM - Tennessee River Mile TS - Technical Specifications WBN - Watts Bar Nuclear Plant WGDT -Waste Gas Decay Tank E1-245

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 184 of 195 APPENDIX A . NOTATION CONVENTIONS (Page 7 of7) List of Units The following units are used consistently throughout the WBN ODCM. The table is included to provide the reader with the unit corresponding to each abbreviation used. cc cubic centimeters cfs cubic feet per second ci Curie cpm counts per minute d day g qram gpm qallons per minute h hour kq kiloqram L liter tb DOund m meters uci microcurie m mile mn minute ml mill liter mrad mill rad mrem mill rem pci Drcocune S second v vear Other Notes: Equations in the text of the WBN ODCM are numbered by section, i.e., equations in Section 6.0 are numbered as 6.1, 6.2, etc. Only final equations are numbered; any equations which are reproduced from Regulatory Guides or NUREGS and used to derive a WBN specific equation are not numbered. E1-246

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 185 of 195 APPENDIX B - Deviations in the WBN ODCM Controls/Surveillance Requirements from Those Given in NUREG-1301 (Page 1 of4)

1. Controls 1.0.1 and 1.0.2 and Surveillance Requiremenls2.0.l-2.0.4 have been replaced by the most recent WBN LCOs 3.0.1 and 3.0.2 and SRs 3.0.1-3.0.4. This has been done to ensure consistency between the WBN TS and the V\IBN ODCM.

2. Control 112.1.'l NUREG-1301 does not list the applicability for liquid monitoring instrumentation.

Applicability for V\IBN liquid effluent instrumentation is defined in Table 1.1-1 to match the requirements provided in the ACTION statements associated with the table. Table 2.1 Channel calibration for the Diffuser Discharge Flow lndicator is changed to yearly due to requirements in the NPDES permit. This is more conservative than required by NUREG-1301. Table2.1 The Channel Operational Test Frequency for items 3.a (Radwaste Flow), 3.b (Steam Generator Blowdown Flow), and 3.c (Condensate Demineralizer Flow) are N/A. These items do not have an associated alarm, interlock, and/or trip setpoint, therefore a Channel Operational Test cannot be performed for these items. Table2.'l Footnote 1 is deleted from ltems 1.b (Steam Generator Blowdown Radiation) and 1.c (Condensate Demineralizer radiation). ltem 1.b and 1.c generate an automatic isolation on level above the alarmftrip setpoint, not instrument malfunction. Table2.1-'l - The circuit failure test associated with the channel operational test (COT) has been deleted. By definition a COT verifies the channel can process an input signal and actuate output devices and that there are no circuit failures that impact the required functions. The notes in Tables 2.1-2 which supplement the COT definition require tests to veriff operation of specific features that alert the operator of a malfunction. These include downscale failure (loss of counts), controls not in operate mode (switch mispositioned), and loss of sample flow. Circuit failure could be caused by any number of subcomponent failures. There is not a specific circuit that is monitoring for each of those subcomponent failures.

3. Control 112.1 .2 - Table 1 . 1 -2 limits operability for WGDT release instrumentation to periods of release.

Table 1.1 lncludes operability requirements for heat trace on iodine/particulate sample lines for Condenser Vacuum Exhaust and Shield Building Exhaust. Tables 1.1-2 and2.'l-2 require that both Unit 1 and 2 Shield Building Exhaust monitors must meet operability requirements to operate either unit. This is because releases through the ABGTS may exit from either unit's Shield Building Vent. Table 1.1 Wording is added to clariff the Shield Building Vent monitor noble gas channel operability requirements. This monitor has the capability to read in units of pCi/cc or pCi/s. The usual channel will read in pCi/s, but this wording allows the monitor to be switched to read in pCi/cc if the flow channel becomes inoperable to eliminate the need for compensatory samples. Table'1.1 The Applicability for ltems 2.a, c , and d (Condenser Vacuum Exhaust (CVE) radiation monitors and flow instruments) is MODES '1,2, 3, and 4 and during MODES 5 and 6 with CVE System in operation. The radiation monitoring instrumentation does not have to be operable if the Exhaust system is not in operation. Table 1 .1 ltems 3.f and 4.e were added as part of the changes associated with operating with a TPBAR core. Table2.1 lncludes surveillance requirements for heat trace on iodine/particulate sample lines for Condenser Vacuum Exhaust and Shield Building Exhaust. Table2.1 The channel operational test frequency for 3.b (Shield Building Exhaust lodine and Particulate Sampler), and 4.b (Auxiliary Building Exhaust lodine and Particulate Sampler) of Table 2.1-2 are N/A. These items have no associated alarm, interlock, and/or trip setpoint, therefore a Channel Operational Test cannot be performed. E1-247

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page I 86 of I 95 APPENDIX B - Deviations in the WBN ODCM Gontrols/Surueillance Requiremenouor,rr"l:"r"o?l;eninNUREG-I301 Table2.1 The channel check requirements for all iodine and particulate samplers are N/A. The channel check requirement is intended to demonstrate that the sampler is operable. An indication of flow through the sampler verifies its operability. The daily channel check for the sampler flor(s) and the weekly sampler filter changeout required by the sampling and analysis program inTable2.2-2 provide this indication of operability, therefore a channel check requirement in this Table is redundant. Table2.l The circuit failure test associated with the channel operationaltest (COT) has been deleted. By definition a COT verifies the channel can process an input signal and actuate output devices and that there are no circuit failures that impact the required functions. The notes in Tables 2.1-2 which supplement the COT definition require tests to veriff operation of specific features that alert the operator of a malfunction. These include downscale failure (loss of counts), controls not in operate mode (switch mispositioned), and loss of sample flow. Circuit failure could be caused by any number of subcomponent failures. There is not a specific circuit that is monitoring for each of those subcom ponent failures.

4. Control 112.1.3 is added to place the meteorological monitoring requirements in the ODCM.

5. Control 112.2.1.1 - Table 2.2-1, the requirements for sampling of continuous liquid release pathways OBS and SGBD) are for daily grab samples rather than a continuous sampler. This is consistent with the requirements for SQN for the same points. The definition of a composite liquid effluent sample is somewhat different than that given in NUREG-1301 0 /tsN will be creating the composite in the lab from the grab samples, the NUREG is referring to a composite sample from a continuous sampler).

The analyses for these daily grab samples are daily, rather than weekly. Each sample will be analyzed, rather than compositing the samples for the week. Table2.2-'l - Footnote 6 is added to require that the continuous liquid release points be sampled only if primary to secondary leakage is identified, and either the monitor must be set to two times background OR compensatory samples are being collected. This is consistent with requirements in the SQN effluent control program. The activity determination is clarified to state that principal gamma emitters will be used for the determination.

6. Control 112.2.2.1:

Table2.2-2 is reformatted from the NUREG version to place more of the requirements in the table itself, and eliminate some of the footnotes. This allows easier implementation of the sampling requirements in plant procedures.

a. Table 2.2-2 rquires sampling of containment purge and vent following shutdown, startup, or a thermal power change exceeding 'l5o/o ol RATED THERMAL POWER within a t hour period. This is consistent with the NUREG, but VVtsN goes further to state that this does not need to be done if analysis shows that the DEI has not increased by a factor of 3 or more, AND if the lower containment noble gas monitor does not show an increase of a factor of 3 or more. This is consistent with the requirements in the SQN effluent control program.

b. Table 2.2-2,Footnote 8 details applicability and timing requirements for sampling of the containment for purges. This note is consistent with one in the SQN ODCM, except that MODE requirements and times are different.

c. Table 2.2-2,Foolnote 8 details applicability and timing requirements for sampling for incore instrument room purges. This note is consistent with one in the SQN ODCM, except that MODE requirements and times are different.

c. Table 2.2-2, Footnote 10 details applicability requirements for sampling of the containment for venting.

This note is consistent with one in the SQN ODCM, but details are different. E1-248

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 187 of 195 APPENDIX B - Deviations in the WBN ODGM Gontrols/Suryeillance Requirements from Those Given in NUREG-I301 (Page 3 of 4)

d. Table 2.2-2,the Shield Building Exhaust is excluded from the monthly requirement for grab sampling to analyze for noble gas and tritium, since all releases through this point will have been quantified previously.

e. Table 2.2-2, Footnote 11 excludes the Condenser Vacuum Exhaust from the requirements for sampling until a primary to secondary leak is identified. The activity determination is clarified to state that principal gamma emitters will be used for the determination.

f. Table 2.2-2,lhe table limits the principal gamma emitters for grab samples to the noble gas nuclides to clariff that particulate releases are quantified frcm filter analyses.

g. Table 2.2 Footnotes 3 and 7 allow compensatory grab samples to be used to determine if activity levels have increased during periods of radiation monitor inoperability.

h. Table 2.2 Requirements for continuous tritium sampling were added for the Auxiliary Building Exhaust and Shield Building Exhaust to quantiff releases during the irradiation and storage of TPBARs. Since tritium samples will be collected continuously footnotes 4 and 5, which required tritium grab samples, were removed. The use of continuous tritium samplers provides a more accurate account of the tritium released than grab samples.

i. Footnotes 8 and 10 clarifies that only the containment compartment to be released needs to be sampled. This will eliminate unnecessary sampling.

j. Table 2.2-2-Prior to release each Waste Gas Decay Tank will require tritium analysis as part as the changes associated with operating with a TPBAR core.

7. Control '112.3.1:

a. Table 2.3 the drinking water control sample location is defined in footnote 9 to be the upstream surface water sample.

b. Requirements for drinking water sample analysis differ from the NUREG. Due to the large downstream distance of the first public water supply (> 10 miles) and the volume of dilution water available, doses due to water ingestion will be very low under normal circumstances. This situation applies at both SQN and BFN and is reflected in their Environmental Monitoring Programs.

c. Text is added to Table 2.3-1 footnote 8 to state that the hydraulic gradient of the groundwater at the VVtsN site is such that the groundwater will move from the site toward the river, therefore groundwater sampling is not required.

d. Table 2.3-1 footnote 3 is added to clariff identification of control samples for iodine and particulate airborne monitoring.

e. Table 2.3-1, The invertebrate sampling requirements have been relocated to the waterborne section of the Table to more accurately reflect the purpose of these samples. There is negligible ingestion of invertebrates from the Tennessee River.

8. BASES 112.1.3 - Bases for the meteorological monitoring instrumentation Control are in the ODCM.

9. BASES 112.2.'1.1 - An additional reference is given for further LLD discussion (ARH-SA-215, June 1975). Allocation of activity between the reactor units for dose calculation purposes is discussed in more detail.

10. BASES 112.2.1.2 - Text is added to explain that the dose for composited nuclides will be calculated using the values from the previous compositing period.

1 1. BASES 112.2.1.4 Allocation of activity between the reactor units for dose calculation purposes is discussed in more detail. E1-249

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 188 of 195 APPENDIX B - Deviations in the WBN ODCM Controls/Surveillance Requirements from Those Given in NUREG-i301 (Page 4 of4)

12. BASES 112.2.2.1An additional reference is given for further LLD discussion (ARH-SA-215, June 1975). Allocation of activity between the reactor units for dose calculation purposes is discussed in more detail.

13. BASES 112.2.2.2 and 112.2.2.4 Allocation of activity between the reactor units for dose calculation purposes is discussed in more detail.

14. BASES 112.3.1An additional reference is given for further LLD discussion (ARH-SA-215, June 1975).

15. The definitions of Member of the Public and Restricted area are not consistent with those given in NUREG-1301. This is due to the revision to 10 CFR 20 implemented by WA on 111194. The definitions are consistent with that regulation. Similar changes are made to the BASES sections to clariff the wording where these definitions are used. Figure 3.1 shows the locations of these boundaries and areas. A calculation is given in Section 7.7.61or a member of the public inside the Site Boundary demonstrating that the location of the unrestricted area boundary on the opposite side of the Tennessee River meets the intent of the regulation.

16. The Source Check definition is changed to refleci changes made in the definition for SQN (revision 271. The nar definition will allow the use of internal test circuits in lieu of a radioactive source (some monitors use an LED light source to provide the check signal to the photomultiplier tube).

17. The Operational Modes Table (Table 3.2) is consistent with the WBN TS.

E1-250

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 189 of 195 APPENDIX C . WBN ODCM REVISION PROCESS (Page 1 of7) This Appendix establishes the minimum requirements for preparation, review, and approval of the Watts Bar Nuclear Plant Offsite Dose Calculation Manual. This Appendix also implements the requirements of ODCM Section 5.3 and WBN TS 5.7.2.3. 1 .0 Reviewer Responsibilities 1.1 Affected Organization Review (AOR) The identification of affected organizations is the responsibility of the Sponsor and applies to all revisions of the ODCM. The affected organizations shall ensure that their reviewers have adequate understanding of the requirements and intent of the ODCM and access to pertinent background information. The AO reviews the draft for impact on the organization and adequate interface - not technical content. 1.2 lndependent Qualified Review (lQR) An independent qualified review is the process of independent technical review by Qualified Reviewers of activities potentially affecting nuclear safety. The IQR shall NOT be the person who prepared the ODCM revision. An IQR is performed by an individual designated by responsible department level managers to perform an independent technical review of activities potentially affecting nuclear safety. The IQR must be qualified to perform the 10 CFR 50.59 review. 1.3 Cross Disciplinary Review (CDR) The need for a CDR is determined by the lQR. CDR is a technical review by disciplines other than those responsible for the document reparation. The CDR is responsible for only the technical aspects of the areas specified by the lQR and any portions of the document that support or justify those areas. Persons performing CDR do not have to be IQR qualified. 1.4 Plant Operations Review Committee (PORC) Review The PORC reviews and recommends final approval of the ODCM. 1.5 Approval Authority The Plant Managerwill approve all revisions to the ODCM as required by Technical Specifications. Signaturc authority shall not be delegated to a lower level manager. E1-251

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 190 of 195 APPENDIX G . WBN ODCM REVISION PROGESS (Page 2of 7) 2.0 Processing ODCM Revisions 2.1 Requestor (lf other than the Sponsor) ldentiff the need for an ODCM improvement. Prepare a justification for the ODCM revision. Aftach a marked-up copy of the existing ODCM. Fonrard the requested ODCM revision to the sponsoring organization. 2.2ODC,M Sponsor Evaluate requested changes and determine if necessary. lf the requested change is not necessary, retum the request to the requestor with explanation why the change is not needed. lncorporate all changes in a draft revision on BSL. ldentiff the organizations to perform AOR and complete the top portion of Attachment A for each organization. Distribute Attachment A to each Affected Organization and request completion of the review prior to expected PORC review date. Obtain appropriate reviews of the ODCM revision in BSL. 2.3 Reviews 2.3.1 tQR Review the ODCM using all questions on Attachment B as a guideline and fonrad comments to the Sponsor. ldentiff discipline or organization to perform CDR, if needed. E1-252

WBN OFFSITE DOSE CALCUIATION MANUAL Revision 23 0 (oDcM) Page 191 of 195 APPENDIX C - WBN ODCM REVISION PROCESS (Page 3 of 7) 2.3.2 Affected Organization Reviewer Review the proposed changes on BSL and provide comments to the ODCM Sponsor. Review the ODCM for impact on assigned organization, identiff procedures/documents which require revision to implement the ODCM revision on the Aftachment A, and return the Attachment A to the ODCM Sponsor. 2.4 Sponsor Resolve comments and obtain reviewe/s concurence in BSL. Escalate any unresolved comments to appropriate management. Ensure ODCM has been reviewed by sponsor and lQR in accordance with Attachment B. Ensure allAffected Organizations have reviewed the ODCM change and have identified the affected procedures on Attachment A. Ensure all lQR, and CDR review requirements have been met. Assign an Effective Date typically 60 calendar days fonrvard UNLESS there is reasonable justification for making it effective earlier, such as plant operating conditions, test schedules, commitment or corrective action deadlines, or implementation of upper-tier requirements, or lack of affected procedures identified on Attachment A. 2.5 PORC Review changes and Attachment B. Document recommendation for approval in BSL. 2.6 Plant tlanager Approve the ODCM revision in BSL. 3.7 ODCM Sponsor Record the ODCM approval date and implementation date on each completed Attachment A provided by the affected organizations. Return the Attachment A to each affected organization. 3.8 Affected Organization Revise procedures identified on the Attachment A and assign an effective date which matches that of the ODCM revision. Complete the Attachment A and return to the ODCM Sponsor. E1-253

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 192 of 195 APPENDIX C. WBN ODCM REVISION PROCESS (Page 4ol7) 3.9 ODCM Sponsor Ensure allAffected Organizations have completed and returned Attachment A prior to the effective date of the ODCM. Fonrard the approved ODCM change to Management Services at least three working days before the implementation date. The completed Attachments A and B are QA records, and are handled in accordance with the Document Control and Records Management Program. Fonrard a completed copy of each revision to Licensing to be filed and fonrvarded to the NRC in the Annual Radiological Effluent Release Report. 3.10 Management Services lssue the ODCM and implementing procedures on the effective date of the ODCM revision. E1-254

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 193 of 195 APPENDIX C.WBN ODCM REVISION PROCESS (Page 5 of 7) Aftachment A ODCM Affected Organization Reviedlmplementation Proposed ODCM Revision No. Expected PORC Review Date: Expected Effective Date: AffectedOrganization: t] Operations I RADCON tI Chemistry I Maintenance t] Technical Support I Scheduling I] Engineering I Licensing tI Other The following procedures,/documents will require revision to implement this ODCM change: PROCEDURE/DOCUMENT PROCEDURE/DOCUMENT ODCM Approval Date: ODCM Effective Date: The required procedure/document revisions to support this ODCM revision have been completed and have an implementation date which matches that given above for the ODCM revision. Affected Organization Date E1-255

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page { 94 of 1 95 APPENDIX C - WBN ODCM REVISION PROCESS (Page 6 of 7) Attachment B ODCttl Review Checklist All questions of this checklist are considered by the ODCM preparer and reviewed by the lndependent Qualified Reviewer (lQR). Only the revised portion of the ODCM should be evaluated. Chanoes to Section(s) 1.0-5.0 YES NO N/A

1. Does the revision meet the intent of the guidance provided in NUREG-1301 for radiological effluent and environmental monitoring controls/s u rvei lance req u i rements?

I

2. Do definitions in Section 3.0 match those provided in the WBN TS, NUREG-1301 . or other NRC quidan ce?

3. Do Administrative Controls in Section 5.0 match those provided in WBN TS, NUREG-1301 , or other NRC guidance?

4. Does the ODCM fulfill the requirements of TVA, Federal or State Laws, WBN FSAR, and any other referenced requirements documents?

5. Does the numbering of the Control and its accompanying Surveillance Req u i rement correspond?

6. Are instrumenUequipment numbers and units of measure an exact match with those on the equipment?

7. Does nomenclature accurately describe the equipment and correspond to label identifiers?

8. Are referenced documents applicable, valid, and listed in the reference section?

9. Does this change maintain the level of radioactive effluent control required by 10 CFR Part 20.1302,40 CFR Part 190, 10 CFR Part 50.36a, and Appendix I to 10 CFR Part 50? Provide justification for answer:

Preparer Date I IQR Date E1-256

WBN OFFSITE DOSE CALCULATION MANUAL Revision 23 0 (oDcM) Page 195 of {95 APPENDIX C . WBN ODCM REVISION PROCESS (Page 7 of 7) Attachment B ODCM Review Checklist (continued) Chanqes to Section(s) 6.0-1 1.0 YES NO N/A

10. Are there methodologies given in Sections 6.0 through 9.0 which imolement the applicable ODCM Controls?

11. Are references to ODCM Controls and Surveillance Requirements accurate and correct?

12. Are changes to setpoint calculation methodologies consistent with the quidance provided in NUREG-O133?

13. Are changes to liquid effluent concentration compliance methodologies consistent with the guidance provided in NUREG-01 33 and 10 CFR Part 20?

14. Are changes to gaseous effluent dose rate calculation/compliance methodologies consistent with the guidance provided in NUREG-O1 33 and/or Requlatorv Guide 1.109?

15. Are changes to dose or dose projection calculation/compliance methodologies consistent with the guidance provided in NUREG-0133 and/or Requlatorv Guide 1 .109?

16. Are instrumenUequipment numbers and units of measure an exact match with those on the equipment?

17. Are referenced documents applicable, valid, and listed in the references?

18. Are ODCM Sections numbered consistently and consecutively?

19. Are references to other ODCM Sections correct?

20. Are references to ODCM Tables and Fiqures accurate and correct?

21 . Are any new acronyms defined in Appendix A?

22. Are equations numbered consecutively?

23. Does dimensional analysis yield the correct units for equations?

24. Are terms used in equations defined after the equation (and in Appendix A) and the proper units given for that term?

25. Do units on equation terms which reference tables match the units used for that term in the Table?

26. Are references qiven for table and other values correct and accurate?

27. Do data values given match those in the reference?

28. Do text descriptions of release/discharge points in Sections 6.0 and 7.0 correspond with the Figures referenced in those sections?

29. The change does not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations? Provide justification for answer:

I Preparer Date IQR Date E1-257

Enclosure 2 Watts Bar Nuclear Plant Unit 1 Process Control Program Reporti ng Req u irements Section 2.4.D.2 and Section2.4.E of the Process Control Program (PCP) address the reporting requirements applicable to the PCP. Section 2.4.D.2 requires that revisions to the PCP, which occurred during the reporting period of the Annual Radioactive Effluent Release Report (ARERR), be fonrvarded to NRC with the ARERR. The current revision level of the PCP is Revision 3, which became effective on August 20,2012. Revision 3 of the PCP only converted the procedure to .docx format and made no changes to the content of the PCP. Section 2.4.E of the PCP requires that major changes to the radiological waste treatment systems be reported in conjunction with the ARERR. For this reporting period, no major changes to the radiological waste treatment systems were made. E2-1}}

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